ML20082U000

Proposed Tech Specs for Afrri,Changing Safety Analyses Where Required & Replacing Pages

ML20082U000
Person / Time
Site:	Armed Forces Radiobiology Research Institute
Issue date:	09/10/1991
From:	DEFENSE, DEPT. OF, DEFENSE NUCLEAR AGENCY
To:
Shared Package
ML20082T998	List: ML20082T996 ML20082U000
References
NUDOCS 9109190232
Download: ML20082U000 (16)

Text

,. ,.

. I TECllNICAL SI'ECIFICATIONS FOlt Till:

AFititi itEACTolt FACILITY [

1,1 CENSE NO.1184 -

DOCK 171' #50170 f TAllLE OF CONTENTS  !

l'31t l 1.0 DEFINITIONS 3 1.1 ALAllA I

- 1.2 Channel Calibration i 1.8 Channel Check 1 1.4 Channel Test i 1.5 Cold Critical .

I 1.0 Core Grid Position 1 l.7 I?xperiment I i' 1.8 Esperinnental Facilities  !

l.9 Fual Element 2 1.10 Innrumented Element 2 1.11 Lirniting SeJety System Setting 2 .

1.12 hicasured Value 2 1.13 hicasuring Channel 2 1.14 On Call 2 1.15 Operable 2 1.16 l'ulse hiode 3 1.17 llenetor Operation 3 1.18 lleactor Safety Systems 3 1.19 llenctor Secured 8 1.20 lleactor Shutdown 3 1.21 lleportable Occurrence 3 1.22 Safety Channel 4 1.23 Safety Lim!t 4 1.24 Shutdown hiargin 4 1.25 Standard Control llod 4l 1.26 Steady State blode 4 1.27 Transient Itod 4 2.0 SAFETY 1.lhilTS AND LlhtlTING SAFETY SYSTEh! SETTINGS 5 2.1 Safety Limit Fuel Element Temperature 5 2.2 Limiting Safety System Setting for Fuel Temperaturc &

3.0 LlhllTING CONDITIONS FOlt Ol'EltATIONS 7 i 3.1 Iteactor Core Parameters 7-3.1.1 Steady State Operation 7 3.1.2 l'ulse blode Operation 7 3.1.3 lleactivity Limitations 8 j 3.1.4 Scram -Time 8 i

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c. Iteattor l'ool

d. Core Experiment Tube .

e, l'ottable lleam Tubes

f. l'neumatic Transfer System

g. Incore 1,ocations 1.9 Furl, FIFMENT A fuel element is a single TitlG A fu;l tod, or the fuel portion of a fuel follower control rod. {

l.10 lESTitUMENTFI) El FMFS2 An instrumented e ent is a special fuel element in which sheathed chroinal/mlute' or equivalent thermos slam are embedded in the fuel.

1.11 IIMITING S AFETf SYSTrM SI'TTING 1,imiting 66.e.y ?;stetu settings are settings for automatic protective devices related to those variables having sigtiificant safety functions.

1.12 MI' ASUltl:D V Al.UE A rneasured salue is the magnitude of a variable an it appears on the output of a measuring channel.

L18 MI:AStilllNG Cll ANN!!L A measuring channel is that combination of sensor, interconnecting cables or lines, amp;ifiers, and output device that are connected for the purpoac of measuring the value of a variable.

1.14 ON C Al,1, A person is considered on call if

a. The individual has been specifically designated and the opera'or knows of the designation; b, The individual keeps the operator posted as to his/her whereabouts and telephone number; and

c. The individual is capable of qctting to the reactor facility within 30 minutes under normal circumstances.

I f> Ol' Ell A DI E A system channel, device, or component shall be considered operable when it in capable of performing its intended function (s) in a normal manner.

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e 30 1 INilTINC. CONI)lTIONS FOlt OPI'It ATIONS 31 jlEAUTOlt COltO l'A11 AMl'TEllji 3.1.1 STP ADY STATl? OPEll ATION Areticability This specification applies to the maximuin reactor power attained during steady state operation.

Obiective To manure that the reactor safety limit (fuel temperature) is not exceeded, and to provide for a set point for the high flux limiting safety systems, so that automatic protective action will prevent the safety limit froin being reached during steady state operations.

Specifications The reactor steady state power level shall not exceed 1.1 megaw atts. The normal steady state operating power limit of the reactor should be 1.0 megawatt. For l purposes of testing and calibration, the reactor snay be operated at power levels not to exceed 1.1 megawatts during the testing period.

IM Thermal and hydraulic calculations and operational experience indicate that TitlG A fuel may I c safely operated up to power levels af at least 1.5 inegawatts with natural convective cooling.

3.1.2 PUI,SE MODE OPEll ATION Apr licabilit y This specification applies to the maximum thermal energy produced in the reactor as a result of a prompt critical insertion of reactivity, Qbiective The objective in to assure that the fuel temperature safety liinit will not be exceeded.

Specific ation The maxi mum step insertion of reactivity shall be 2.8% Ak/k ($4 00) in the pulse mode.

1%

11aned upon the Fuchs-Nordheim mathematical model (cited by C.11 Clifford et al. in the April 1901 G A lleport #2119, 'Model of the AFitill TillG A Itenctor"), an insertion of 2 8% Ak/k results in a maximum average fuel temperature of less than 550'C, thereby staying within the limiting safety settings that protect the safety limit 4 The 50'C margin to the Limiting Safety 7

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. . Syotem Setting and the 450'C margin to the safety limit amply ollow for ,

uncertainties due to extrapolation of measured data, accuracy of meuured data, and location of instrumented fuel elements in the core. l 3.1.3 IWACTIVITY LIMITATIONS 1 Aeolicability These specifications apply to the reactivity condition of the reactor and the reactivity worths cf control rods and experiments. They apply for all modes of l operation.

Obicetive -

The objective is to guarantee that the reactor can be shut down at all tiuce and that the fuel temperature safety limit will not be exceeded.

Specifications ,

a. The reactor shall not be operated with the maximum available excess reactivity abose cold critical with or without all experiments in place '

greater than $5.00 (3.5% Ak/k).

b. The minimum shutdown margin provided by the remaining control rods  ;

with the most reactive control rod fully withdrawn or removed shall be

$0.50 (0.35% Ak/k) for any condition of op ration. l

}. lid!

a. The limit on available excess reactivity establishes the maximum power if all control elements are removed,

b. The shutdown margin assures that the reactor can be shut down from any operating condition even if the highest worth control rod rensins in the fully withdrawn position or is completely removed.

3.1.4 SCR AM TIME ,

Aeolicability The specification applies to the time required to fully insert any control rod to a full down. position from a full up position.

Oblective The objective is to achieve rapid shutdown of the reactor to prevent fuel I

damage, Srweifiention The time from scram initiation to the full insertion of any control rod from a full up positio; shall be less than I second.

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. Fr ecific ation Functional checks shall be made annually, but not to exceed 15 months, to insure the following:

a, With *he lead shield doors open, neither exposure room plug door can be [

electrically opened.

b. The core dolly cannot be mosed into position 2 with the lead shield doors closed.

c. The warning horn shall sound in the exposure room before opening the lead shield door, which allows the core to move to that exposure room unless ,

cleared by two licensed operators.

IM I These functional checks will verify operation of the interlock system. Experience  !

at AFititi indicates that this is adequate to insure operability, 4.2.5 ItEACTOlt FUFL ELEMENTS Ai+1ic abilit v -

This specification applies to t u surveillance requirements for the fuel elements. i i

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The objective in to verify the interrity of the fuel element cladding.

Epecificatione All the fuel elements present in the reactor core, to include fuel follower control . I rods, shall be inspected for damage or deterioration, and measured for length and bow at intervals separated by not more than 500 pulses of insertion greater than 82.00 or annually (not to execed 15 months), whichever occur first. Puel elements in long term storage need not be measured until returned to core; however, fuel elements routinely moved to temporary storage shall be meuured every 500 pulses of insertion greater than $2,00 or annually (not to exceed 15 rnonths)i whichever occurs first.

Mid!

- The frequency of inspection and measurement is based on the parameters most likely to affect the fuel cladding of a pulse remetor, and the utilisation of fuel l clements whose characteristics are well known4 i The limit of transverse bend has been shown to result in no difficulty in disassembling the core. Analysis of a woret case scenario in which two adjacent fuel elements suffer sufficiently. severe transverse bends to result in the touching of.the fuel elements has shown that no damage to the fuel elements will result '

via a hot spot or any'other known mechanism, t

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'4.3 [f00L ANT SYSTI:MS A eolicabilit y This specification applies to the surveillance requirements for menitoring the pool water and the water conditioning system.

Obintive The objective is to usure the integrity of the water purification system, thus maintaining the purity of the reactor pool water, eliminating ponible radiation huards from activated impurities in the water system, and limiting the potential corrosion of fuel cladding and other components in the primary water system. j Specificatiens i

m. The pool water temperature, u meuured near the input to the water purification system, shall be measured daily, whenever operations are planned.

b. . The conductivity of the water at the output of the purification system shall be meputed weekly, whenever operations are planned.

ULN1  !

liased on experience, observation at these inteivals provides acceptable surveillance of l .

limits that assure that fuel clad corrosion and neutron activation of dissolved materials will not occur.

4.4 VENTIf ATION SYSTEM A nelicabilit y This specification applies to the facility sentilation system isolation.

ObitLO%.1 The objective is to assure the proper operation of the ventilation system in controlling the releue of radioactive material into the unrestricted environment.

Specification The operating mechanism of the positive sealing dampers in the reutor room ventilation

- system shall be verified to be operable and visually inspected at leut monthly (interval ,

not to exceed six weeks). l Egig i Experience accumulated over years of operation has demonstrated that the tests of the ventilation system on a monthly buis are sufficient to usure proper operation of the  !

system and control of the releue of radioactive material.

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5.0 DESIGN FEATUllES 5.1 El,TE AND FACl'ITY DI Scittl' Tion fnlirebility This specification applies to the building that houses the reactor.

Obiective The objective is to restrict the amount of radioactivity released into the environment.

Snecificationa

m. The remetor building, se a structurally independent building in the AritRI complex, shall have its own ventilation system branch. The etnuent from the reactor ventilation system shall enhaust through absolute filters to a stack having a minimurn eleution that is 18 feet above the roof level of the highest building in the AFRRI complea,

b. The reactor room shall contain a minimum free volurne of 22,mo cuble feet.

c. The ventilating system air ducts to the reactor room shall be equipped with positive sei. ling dampers that are activated by fail safe controls, which will automatically close off ventilation to the reactor room upon a signal from the reactor root, air particulate monitor,

d. The teactor room shall be designed to restrict air leakage when the positive sealing dampers are closed.

Duis The facility is designed so that the ventilation system will normally maintain a negative piessure with respect to the atmosphere, so that there will be no uncontrolled leakage to the environment. The free air volume Wthin the reactor building is confined when there is an emerttency shutdown of the ventilation system. Iluilding construction and gaskets around doorways help restrict leakage of air into or out of the r-actor room. The stack

• height insures an adequate dilution of effli ents well above ground level. The separate ventilation system branch insures a dedicated air flow system for reactor effluents.

5.2 REACTOR CORE AND FULL

$ 2.1 HEACTOR FUFL Aonlinbility These specifiewtions apply to the fuel tiements, to include fu"1 fcilower control rods, used in the reactor core.

Obicetive The objectives are to (1) assure that the Invl elements are designed and fabricated na such a manner as to permit their use with a high degree of reliability with respect to their physicel and nucimr characteristics, and (2) anure that the fuel elemen.ts used in the core are substantially those anstped in the Safety Analysis lleport.

Spe< ific at inn s The iadividual nonirradisted standard TitlG A fuel elements shall have the following characteristics:

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a. Uranium content: Maximum of 9.0 weight percent enriched to less than 20% uranium 235. In the fuel follower, the maximum uranium content will be 12.0 weight percent enriched to less than 20?[ uranium-235.

b.

Ilydrogen-to-airconium atom ratio (in1.0 theand ): Nominal 1.7 11 atoms to Zril'7.

1.0 Zr atoms with a range between I

c. Cladding: 304 stainless steel, nominal 0.020 inch thick,

d. An> burnable poison ured for the specific purpose of compensating for fuel burnup or long term reactivity adjustments shall be an integral part of the manufactured fuel elements.

Ih.d1 A maximum uranium content of 9 weight percent in a standard TitlG A eleinent is greater than the design vahte of 8.5 weight percent, and encompasses the mar.' mum probable variation in individual elements. Such an increase in loading would result in an increase in power density of less than 64. An increase in local power density of 6% in an individual fuel element reduces the safety margin by 10?t, at most. The hydrogen to-rirconium ratio of 1.7 will produce a maximum prenure within the cladding well below the rupture strength of the cladding.

The local power density of a 12 0 weight percent fuel follower is 21% greater than an 8.5 weight percent standard TitlG A fuel element in the D Iting. The volume of fuel in a fuel followed rod is 56% of the volume of a standard TillG A fuel element. Therefore, the actual power produced in the fuel followed rod is 33% less than the power produced in a standard TillG A fuel element in the D ring.

5.2.2  !!EACTOlt COllC Annlie nbilit y These specificatione apply to the configuration of fuel and in core experiments.

Obiective The objective is to restrict the arrangement of fuel elements and experiments so as to provide anurance that caressive pt.wcr densities will not be produced.

St.ecific at ions a, The reactor core shall consist of standard TitlG A reactor fuel elements in a close packed array and a minimum of two therrnocouple instrumented TitlG A reactor fuel elements,

b. There shall be four single core positions occupied by the three standard control rods and transient rod, a neutron start-up source with holder, and positions for ponible in-core experirnents.

c. The core shall be cooled by nature.1 convection water flow. ,

d. In core experiments shall nat be placed in adjacent fuel positions of the ll-ring and/or C-ring.

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e. Fuel elements indicating an elongation greater than 0.100 inch, a lateral bending greater than 0.062F inch, or significant visible damage l shall be considered damaged, and thall not be used in the reactor core.

Endt Standard TillG A cores have been in use for years, and their safe operational characteristics are well documented thperiente with TillG A reactoes has shown that fuel element bowing that could result in touching has occurred without deleterious effects. The elongation limit has been specified to (a) assure that the cladding material will not be subjected to stresses that could cause a loss of integrity in the fuel containment, and (b) assure adequate coolant flow.

6.7.3 QQNTHOL 110D8 A t,t, lie abilit y These specifications apply to the control rods used in the reactor core.

Objective The objective is to anure that the control rods are designed to permit their use with a high degree of reliability with respect to their ph) leal and nuclear I characteristics.

Specifiestions  ;

a. The standard control rods shall have scram capability, aad shall contain borated graphite, D4C powder, or baron and its compounds in solid form as a poison in aluminum or stainless-steel cladding. These rode may have an aluminum, air, or fuel follower. - If fuel followed, the fuel region will .

conform to the Specifications of 6.2.1.

The transient control rod shall have scram capability, and shall contain b.

borated graphite,11 C powder, or boron and its compounds in solid form as a poison in alumindm _or stainless-steel cladding. This rod may incorporate r an aluminum, poison, or air follower.

EA?$l The poison requirements for the control rods are satisfied by using neutron- ,

absorbing borated graphite,11 C powder, or boron and its compounds. These materials must be contained iA a suitable cladding material, such as aluminum or stainless steel, to insure mechanical stability during movement and to isolate the poison from the pool water environment. Scram capabilities are provided by the l rapid insertion of the control rods, which is the primary operational safety feature of the reactor. The transient control rod is designed for use in a pulsing-TRIG A reactor.

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6.3 SPIX'I Al, NUCl EAlt M ATI'ltl Al, STOll AGE ,

A t+t> lie abilit y This specification applies to the storage of remetor fuel at times when it is not in the [

ttattor tote. ,

Oblective The oliective is to assure tha. stored fuel will not become critical and will not renth an ,

unsafe temperature.

St etification i All fuel elements not in the reactor core shall be stored and handled in accordance with applicable regulations. Irradiated fuel elements and fueled devices shall be stored in an array that will permit sufficient natural convective cooling by water or air, so that the fuel element or fueled device temperature will not enceed design values. Storage shall I.e such that- groups of stored fuel elements will remain suberitical under all conditions of moderation.

UE!!!

The limits impe=ed by this specification are conservative and assure safe storage and l L

handling. Experience shows that alisiroximately 67 fuel elements are required, of the design used at Al'itill, in a closely packed array to achieve critkality. Calculations show that in the event of a full storage ruk failure with all 12 elements falling in the most reactive nucleonic configuration, the mass would be less than that required for criticality.

Therefore, under normal storage conditions, criticality cannot be reached.

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en 'A13tlNISTil ATi\T CONTitOlS 6.l OftG ANil ATION,,

e 1.1 STitOCTUltE The orgatiisation of Iersonnel for the management and os.eration of the Al'Ilitt reactor facility is show n in l'igure 1. Organisation changes may occur, based on Institute requirements, and they will lie depicted en internal doturnents. lloweser, no changes may t,e made in the Operation, Safety, and 1:niergency Control Chain kn which the llenctor l'acility Director has direct responsibility to the l Director, Al71till, Dtic(tof,AlhRl

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Reacwr Orerauous StafI' Figure 1. Orgartteattom of Personnel for Management and Operation of the AFRR1 Reacter Facility.

Amy reertor staff memtier has seeens to the Director for mattere of eefety 29

.. 0.1.2 ItESI'ONS!!111,lTY The Director, AFiliti, shall have license responsibility for the reactor facility. The Iteactor l'acility Director (ItFD) shall be responsible for administration and operation of the Iteactor l'acility and for determination of applicability of proceduies, experiment authorisations, maintenance, and operations. The itFD may designate an individual who meets the requirements of Section 0.1.3.1.a to oischarge the Ill'D's iesponsibilities in the itFD's absence. During brief absences (periode len than four hours) of the lleactor facility Director and his designee, the lleactor Operations Supervisor shall discharge these responsibilities.

6.1.3 STAFFING s 0.1.3.1 hlection of Percennel

a. llenctor l'acility Director l At the time of appointment to this position, the lleactor f acility Director shall have 6 or more years of nuclear experience. Iligher education in a v.cientific or nuclear engineering field may fulfill up to 4 years of experience on a one-for.one basis. The Facility Director must have held a tMNitC Senior Iteactor Operator license on the Afilitt reactor for at least 1 year before appointment to this position.

b. Itcactor Operations Supervisor (llOS)

At the time of appointment to this position, the itOS shall have 3 I years nuclear experience. I!igher education in a science or nuclear engineering field may fulfill up to 2 years of experience on a one for one bnels. The MOS shall hold a USNitC Senior lleactor Operator license on the AFititt reactor. In addition, the 1105 shall have 1 year of experience as a USNitC licensed Senior lleactor Operator at AFiliti or at a similar facility before the appointment to this position.

c. Ileactor Operators / Senior lleactor Operators At the time of appointment to this position, an individual shall have a high school diploma or equivalent, and shall poness the appropriate USMtO licenac.

d. Additional staff as required for support and training. At the time of appointment to the reactor staff, an individual shall ponen a high school diploma or equivalent.

6.1.3.2 Qatatinns

a. Minirnum staff when the reactor is not secured shall include:

1. A licensed Senior lleactor Operator (SitO) on call but not necenarily on site

2. Itadirition control technician on call

3. At least one licensed iteactor Operator (110) or Senior llenctor Oper6 tor (Silo) present in the control room 4, Another person within the AFiliti complex who it at.le w carry out written emergency procedures, instructions at the operator, or to summon help in case the operator becows incapacitated.

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b. Maintenance activities that could affect the reactivity of the reactor shall be accomplished under the supervision of an SitO.

c. A list of the names and telephone numbers of the following personnel shall be readily available to the operator on duty: i i

1. Management personnel (llenctor Facility Director, AFillt! Dirutor)

2. Radiatien safety personnel (llcad, Safety and llealth Department) l

3. Other operations personnel (Itenctor StalT, itOS) 6.1.4 Til AININC OF PEltSONNil A training and retraining program will be maintained, to insure adequate levels of profielency in persons involved in the reactor and reactor operations.

0.2 ItEVIEW / ND AUDIT Tilt itEACTOR AND ft ADIATION FACIIlTY SAFETY COMMITT !:E OtitFsci 6.2.1 - COMPOSITION AND QUAI,lFICATIONS I 6.2,1.1 Composition

a. Itegular HitFSC Members (l'ermanent Members)

(1) The following shall be members of the IlltFSC:

(a) Chairman, Safety and llealth Department, AFHit! l (b) - Reactor Faellity Director, AFRitt (2) The following shall be appointed to the IlitFSC by the Director, AFl!RI:

(a) Chairman as appointed by the AFitit! Directorate.

(b) One to three non AFititi mernbers who are knowledgeable in fields related to_ reactor safety. At least one shall be a lteactor Operations Specialist, or a llealth I'hysics Specialist.

b. Special ititFSC Members (Temporary Members)

(1) Other knowledgeable persons to serve as alternates in item a(2)(b) above as appointed by the Afill4 Director.

(2) Voting 3d }g members, invited by the Director of AFititi, to assist in review of a particular problem,

c. Nonvoting members as invited by the chairman, ItitFSC.

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6.2.1.2 Qualifications The minimum qualifications for a person on the IlllFSC shall be 6 years of profenional exnerience in the discipline or specific field represented. A baccalaureate degree may fulfill 4 years of experience.

6.2.2 FUNCT!ON AND AUTilOlllTY I

6.2.2.1 Function

- The Iteactor and itadiation Facility Safety Committee is directly responsible to the Director, AFilltt. The committee shall review all radiological health and safety matters concerning the reactor and its associated equipment, the structural reactor facility, and those items listed in Section 6.2.4.

0.2.2.2 Authority The IlilFSC shall report to the Director, AFiliti, and shall advise the Itcactor Facility Director in those areas of responsibility specified in Section 6.2.4.  !

6.2.3 Cll AitTFil AND ItULES >

6.2.3.1 Alternatee ,

Alternate members may be appoir.ted in writing. by the IlltFSC Chairman to serve on a temporary basis. No more than two alternates shall participate on a voting basis in ititFSC activities at any one time.

6.2.3.2 Meetine Freauency The IlitFSC or a subcommittee thereof shall meet at least four times a  !

. calender year. The full ItllFSC shall meet at least semi annually, l

. 6.2.3.3 Quorum A quorum of the IlllFSC for review shall consist of the Chairman or designated alternate) and two other members (or alternate members)(, one which must be a non AFitill member A majority of those present shall be regular members.

6.2.3.4 V otinr R glg, Each regular IIIIFSC member shr.l! have one vote. Each special appointed member shall have one vote. The ma.iority is 51% or more of the regular and special members present and voting.

6.2.3.5 Minutes Minutes of the previous meeting shall be available to regular members at least I week before a regular scheduled meeting.

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f. Any other aves of Facility operations considered appropriate by the ItitFSC l or the Director /AFiliti.

g. Ileactor Facility Al,All A Program. This program may be a section of the )

total AFititi prograin. l 0.8 PilOCEDUlli:S 0.3.1 Written instrnetions for certain activities shall be approved by the Itenctor Facility Director and reviewed by the llenctor and Itadiation Facility Safety Committee (ItitFSC). The procedures shall be adequate to assure safe operation of the reactor, but shall not preclude the vse of Independent judgment and action as deemed neccesary. These activilles are as follows:

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s. Conduct of inf adiatione and everiments that could affect the operation and taitty ed Ilie teattnr.

b. lle:.ctor etaff.ttnining program.

c. Surveillance, testing, and calibration of instruments, components, and systems involving nuclear safety,

d. l'ersonnel radiation protection consistent with 10 CFR 20.

e. Implementation of required plans such us the Security Plan and I:mergency i Plan.

f. Iteactor core loading and unloading.

5 Checkout startup, standard operations, and securing facility. l l

0.3.2 A!; hough substantive changes to the above procedures shall be made only with approval by the Reactor Facility Director, temps tary changes to ebe prmedures that do not change their original intent may be made by the ItOS All such temporary changes shall be documented and subsequent!y reviewed and approved by the Iteactor Facility Director, 6.4 ItEVIEW AND APPROVAL OF EXPEltlMENTS 0.4.t Ildore issuance of a reactor authorisation, new experiments shall be reviewed for radiological safety and approved by the followingt

a. - Reactor Facility Director

b. Safety a d llealth Depar;, ment

c. Reactor and Radiation Facility Safety Committee (RitFSC) 6.4.2 Prior to its performance, an experimen'. , hall be included under one of the following' types of authorisations;

a. Sveelal lleactnt- Autherbatinn for new experiments or experiments nos jncluded in 't floutine Reacter Authorisation. These experiments shall be performed under the direct supervinion of the Iteactor Facilhy Director or designee.

b. Routine Reactor Aathoritatinn, fo expenments safely girformed at least onct. These experimen'.s inay be performed at the discretion of the Reactor Fe.edity Director and coordinated with the Safety and llcalth. Dqartment l when appropriate. These authoritahons do not require additional RitFSC . ,

icVleW.

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c lleactor.l'arameters Authorisation for routine measurements o' reactor parameters, routine core measurements, instrumentation and calibration chocks, maintenance, operator trainirg, tours, testing to verify reactor outputs, and other reactor testing procedures. This shall constitute a single authorisation. These operations may be peeformed under the authorisation of the Ileactor Facility Director or the lleactor Operatians Supervisor.

6.4.3 Substantive (reactivity worth more than 180.25) changes to previously approved ex;criments shall be made only after review by the IlitFSC and after approval (in writing) by the lleactor Facility Director or designated alternate. hiinor changes that do not significantly alter the experiment (reactivity worth of less then 180.25) may Ie approved by the 1108, Approved experiments shall be l carried out in accordance with established procedures.

0.5 llEQUlitFD ACTIONS c.5.1 ACTIONS TO 11E TAKEN IN CASE OF SAFETY l'hllT VIOLATION

a. The reactor thall be shut down immediately, and reactor operation shall not be resumed without authoritation by the NitC.

- b. The safety limit violation shall be reported to the Director of Nito llegion .

1, 0Tice of Inspection and Enforcement (or designate); the Dircoor, AFillth and the ItitFSC not later than the next workin day.

c. A Safety Limit Violation Iteport shall be prepared. This report shsil be  !

reviewed by the IlltFSC, and shall describe 11) applicable circumstances l )

- preceding the violation, (2) effects of the viMation on faellity components, structures, or systems, and (3) corrective action taken to prevent or reduce the probability of recurrence.

4. The Cafety Limit Violation Iteport shall be submitted to the NitC; the l Director, AFititt; and the ItitFSC within 14 days of the violation.

0.5.2 IWPOllTAllLE OPCUltilENCES 4

lleportable occurrences as defined in 1.21 (including causes, actual or probable consequences, corrective actions, and mnsures to prevent recurrence) shall be 7

seported to the NitC. Supplemental repoits may be required to fully describe the final resolution of the occurrence. y i

n. I'rompt Notifkation With Written Followuo. The types of events listed below shall be reported as soon as possible by telephone and confirmed by 1

i i

35 l

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