ML20099D379

Forwards Rev 2 to Tech Specs for Manhattan College Zero Power Reactor,Requested During 840918-19 Site Visit.Response to NRC Final Questions Submitted on 841026.Commitments from Site Visit Complete

ML20099D379
Person / Time
Site:	05000199
Issue date:	11/15/1984
From:	Kane R MANHATTAN COLLEGE, RIVERDALE, NY
To:	Chu A Office of Nuclear Reactor Regulation
References
NUDOCS 8411200351
Download: ML20099D379 (68)

Text

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MANHATTAN COLLEGE PARKWAY Man haMan . RIVERDALE NEW YORK 10471 - '

' MECHANICAL ENGINEERING DEPARTMENT

, (212) 92tNH46 . ,.

'e r  %> *^ ~ *

, November 154 1984

-- Ms. Angela' Chu, Projeet-Manager 7 U. S. Nuclear Regulatory Commission

) Standardization and Special Projects. Branch Division of Licensing-Washington, : D. C. 20555-Subjeet: ' Manhattan College . ..

Zero Power Reactor (MCZPR)

Docket 50-199 Technical Specifications

Dear Ms. - Chu:

' Attached find a' copy of our latest revision of the l Technical Specifications for the MCZPR. This was requested during your site visit of September 18 and 19,1984 with an agreed due date of November 15, 1984. Our response to the NRC Final Questions was mailed to you on' October 26,;1984 The revised Technical Speci-fications and our response to the NRC' Final Questions represent the .

completion of our commitments resulting from the site visit. We hope these will enable you to complete your review.

If you have any questionson the Technical Specifications,-

~

please contact our Chief Reactor Supervis.or, Dr. Jih-Perng Hu.

(212)-920-0147 or the writer (212)920-0145 Very truly yours, bh Dr. Ronald S. Kane Reactor Administrator RSK/w-enc fyM,MV

. 7 g jgg f4 /d0 PETER M. BROWN Notary Public, State of New York No.4502374 Qualified in Westchester County Commission Expires March 30,1985 D , O P- t -

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s 16.0 . TECHNIC AL SPECIFIC ATIONS -

FOR- THE -

. MANHATTAN COLLEGE'ZERO POWER REACTOlU

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1 Dr. .Jih-Perng Hu :

Bro. Gabriel Kane, FSC '

Dr. - Ronald S. Kane i- ,

i Revision 2

!? Novembe r 15, 1984 u

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T 9 Revision' Record

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-: Revision No.' - 1 Comment '

d' 0 - Submitted to U. S. N.-R. 'CT- on J August .26; .1983 'as 'part of the.

Safety -Analysis Report forithe :

MCZPR 1- ' Complete revision submitted on -

Januarp 12, 1984

'2 . Complete revision submhted 'on

~- Novemb e r 15,'1984' e.

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Contents , Page No.

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Revision Record - -

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~ Table ~of Contents 16-3

- .1.' 0 ? iDEFINITIONS ' ' 4

'16 8

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2. 0 > rSAFETY LIMITS AND LIMITING ' -

SAFETY SYSTEM SETTINGS ' '

16 10

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LIMITING CONDITIONS.FOR OPERATION

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3. 0 '

- 4. 0 -  : SURVEILLANCE REQUIREMENTS - 16 25 ,

7

- 5. 0 =-DESIGN FE AT RES I16 35

' 6. 0 : ADMINISTRATIVE CONTROLS 116-53' Table l3 - 1, Safety System - 13' Figure 5-1, Cutaway of MCZPR Facility -- :16-36 F Figure 5-2,': Plan of First Floor of MCZPR 16-37,

' Figure'5-3,' Plan of Second Floor of MCZPR 16-38 Figure 5-4,- Grid Plate Stand (Plan View)16-424

'; Figure 5-5, Grid Plate Stand (Section View) 16-43 I Figure 5-6, ' Grid Plate - 16-44 Figure 5-7, Lucite Holddown Rod 16 45'

+

Figure. 5-8, Fuel Element 16 47-

~ Figure 5-9, Control Rod Assembly 16 49

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Figure 5-10, Rod Drive Mechanism 16-50 Figure 6-1, Table of Organization 16-54.

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1. 0 ' DEFINITIONS The terms Safety Limit,' Limiting Safety System Setting, and Limiting Condition for Operation are as defined in paragraph 50. 36 cf 10 CFR Part 50.

- channe1 - A channel is the combination of sensor, line , amplifier and output devices which are connected for the purpose of measuring the value of a parameter.

channel test - A channel test is the introduction of a signal into the channel for verification that it is operable.

channel calibration - A channel calibration i~s an adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter which the channel measures. Calibration shall encompass the entire channel, including equipment actuation, ala'rm,' or trip and shall be deemed to include a channel test.

channel check - A channel check is a qualitative verification of acceptable performance by observation of channel behavior. This verification, where possible, shallinclude comparison of the channel with other independent channels or systems measuring the same variable.

control rod - Plates fabricated with neutron absorbing material used to establish neutron flux changes and to compensate for routine reactivity losses.

This includes safety-type and regulating rods, core - The portion of the reactor volume which includes the fuel elements, the source, and the control rods.

delayed neutron fraction - When converting between absolute - and dollar-value reactivity units, a beta of 0.00645 is used.

d_ rop time - The elapsed time between reaching the complete removal setpoint and the full insertion of a safety-type rod. (It must be less than

1. 0 second).

excess reactivity - Excess reactivity is that amount of reactivity that would exist if all control rods (control, regulating) were moved to the maximum reactive condition from the point where the reactor is exactly critical (K ff

= 1).

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, 5 experiment- /An'y objectdother' than a' fuel Element.or handling tool,L

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? which is. inserted.into thelvolume formed by projectingithefgrid; plate -

g  ; vertically to th$ tank pool w'ater surface is to be regarde'd asf an5 ' -

j t experiment.in th'e core.$

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(meas'ured v' alue '-? The' me'asuredivalue is;the valueiof a parameter as it - ~ '

i e appears on the output of a'channeli m ,

. movable experiment / An' e'xperiment1where it is intended that the entire

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experiment may be moved in or. near.:the core or into"a'nd out'of thei .]

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ireacto r ; pool .wate r. <

~P f operable .-[ Operable means a' component'or system is capable of. performing .

~ ~ ~ its-intended function.- t operiting _

JOperating means 'a component or system is' performing its -

-intended function.- -

. reactivity limits - [The reastivity' limit"slare those limits iniposed on

reactor core excess reactivity. For the MCZPR the reactivity limits'are

0. 44% 3 A k/k'(O. 68 $ ).at 110. 60F.

reactivity worth of an experiment - The reactivity worth of an experiment:

'is the maximum absolute value of the reactivity change that would occur .

as a result of intended or anticipated changes or credible malfunctions that alter experiment position or configuration. [

reacto'r operating - The reactor is operating whenever it is not secured or shutdown.

reactor operator - (RO) - An individual who is licensed to manipulate

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the controls of a reactor.

. reactor safety systems - Reactor safety systems are those systems, including their associated input channels, which are designed to initiate automatic reactor protection or to provide information for initiation of manual p . protective ~ action, i

h _ reactor-secured - A reactor is secured when: -

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1)- . It contains insufficient fissile material or moderator present in the reactor, adjacent experiments;or control rods, to attain criticality ,

4 , under optimum available conditions of moderation and reflection, or s -

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m ill 5 combination of all of the. followingi

'a)f- All neutron absorbing control rods are fully inserted and othern .

m.'  ! safety devices xare in shutdo'wn position,U as required by the.

1 technical specifications,- andi E

b)j The' console key switchlis~ in the off position and the' key is:removedi L from the lock,' and :

c) j No ' work is:in_ progres's involving core fuel, core ; structure, installed ,

control rods,.~ or control rod devices unle'ss they are physica11yi-

- :decoupled from theicontrol. rods, and; d) ;NoLexperimentsiare in.ar near the-reactor.

reactsr shutdown - The reactor is shut'down if it is -suberitical by.at least'

one dollar in the reference core condition and the: reactivity worth of all experiments is accounted. for.

reference core condition - The condition of the core when the pool water .

temperature is between 60 F and 80 F.

regulating rod' -

A low-worth control rod used primarily to maintain an

' intendel power level.: Its position may be varied by operator action.

research -reactor - A research reactor-is defined as a device designed to

-support a self-sustaining neutron chain reaction for research, development, .

educational, training, or laboratory . purposes, and.which may have provisions for.the production of radioisotopes.

reverse trip - The electronic setting within the console instrumentation which will initiate a reverse system which will drive in an electromagnet when certain specified limits are exceeded.

l safety-type rod - A rod that can be rapidly inserted by cutting off the

- holding current in its electromagnetic clutch. This applies to both control crods.

. scram time - The time for the control rods (shim, regulating) acting under

!. - the force of gravity to' change.the reactor from a critical to a suberitical condition. This will be equal to or less than the drop time.

' scram trg - The electronic setting within the console instrumentation ~ which I will activate scram circuits.when certain specified limits are exceeded.

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_ senior re ctor opsratoi-.-(SRO)l ..?An~ individual who is licensed to direct

the activities of ajReactor= Operator _.(RO) and to manipulate'the controls .

'.Jof a reactor . , ,

._ s (shall, "should and may' The wordL"shall" is used to' d'enote a, req'uirement :

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> the word "should" to deno't e a' recommendation: and' ths .wo rd .niay" to _

Lden6te'; permission,: neither a requirement nor a recommendation.

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. shutdown margin - Shutdown margin shall mean the minimum shutdown'- -

. reactivity necessary to provide l confidence.that the' reactor can be' made 'suberitical-by mean's of th'e control and safety s~ ystems. starting from any permiesible

) operating condition although the most reactive rod is in'its most reactive

. position,- and that the reactor will remain:subcriticallwithout further.

ope'rator action.

' unscheduled shutdown - An unscheduled shutdown is defined as any unplanned '

shutdown of the reactor caused by. actuation of the reactor safety. system,'.

. operator error, equipment malfunction,: or a manual shutdown in response :

to' conditions which could adversely affect' safe operation,' not including _ shut-- -

downs which occur'~during te' sting or, check-out operations.

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Safety Limits

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f The,. . + aManhattan C' ol'lege:Zero : Power ~ Reactor (MCZPR)fshall r

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f n6t ' operate' at a ' steady power level in exc'ess of 0.1' watt. clNo otherl . , :-

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.S afetyLLimits need be specified:since convective cooling is'not

, '? x:: 1 required forl this power level.' This' power level isjsufficient to -

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satisfy .the' 'educationailland. training purposes. of .thei MC ZPR. :

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Limiting Safety. System Settings (LSSS)

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<  : 2. 2.1 J Applicability 7 This -specification applies to the:setpoints of safety channels.

2. 2. Z ? Objective

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, - To assure that automatic trip; action is initiated and that the

-. operator is. warned to.take protective action'to prevent a-

. safety limit from being exceeded. >

" 2. 2. 3 Specifications The limiting safety system settings are the following:

. A. The maximum steady state power level trip setpoints shall .

not exceed O.1. watt.

B. sWhen performing the _high flux t.ests, the transient power level

, trip setpoints, shall not exceed C.18 watt.

2. 2. 4 B'ase s -

The trip setpoints provide' adequate margins for the limits of operation. Both trip setpoints, ~A and B,; initiate automatic scrams.

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( ?3)0f MLIMITING CONDITIONS FON OPERATION:

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23.11' - Reactor. Core Parameters' < ;. ?

-4 f 361/1f Applicabilitp t

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These' specifications ~ apply toi the pa'rameters which: .

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,t describe the reactivity; condition'of the core.'

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3.1. 2 LObjective' s '

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- To ensure that theireactorlcanno_t achieve; promptf

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criticality and that it can beisafely shut'down under anyIcondition.

3. I'. 3 : Specifications ~ v l 4 1The: reactor shall not be made critical unless the following coriditions exist: _

JA. LThe total core excess. reactivity with or without the movable experimencs of section 3.' 8. 3 shall not exceed O. 44% Ak/k

,(0 68$ ). -

? :B. The minimum shutdown rnargin provided by control rods in-

. the reference core condition shall not be-les's than

. L 0.'90% Ak /k (1. 40 $).

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' The'1ower limit of water resistivity based.on the requirements

C.

for' the corrosion protection system'shall be set at 0.1 Megaohm-cm.

g There shall be.no upper limit for the water resistivity.

[ D. An'y change in the fuelloading pattern and experimental ,

- apparatus shall be' a'pproved by the Reactor Operations

!: Committee.-

3.1. 4 Bases i Specification A is based upon the experimentally determined value for excess reactivity 0. 44% Ak/k (0.68$) at a reactor pool l water temperature of 110. 6 F.

Specification B is. based upon the negative wortn or the-regulating . rod: that is, the control rod with the smaller negative worth.

Specification C provides the minimum resistivity of water in L

the reactor tank.- If the water resistivity is less than this - l

t. level of 0.1 Megaohm-cm, the resin bed in the deionizer is

(~ re place d.' The resistivity of the water has little or no b' earing ' i

. on the corrosive effects experienced or possible other than

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. to offer some guarantee that catalyzing anions are excluded from the system. In the absence.of.the other: protective-Lmechanisms that are in place,--corrosion will occur reg'ardless

.s- of the resistivity of the water.= The ' supplemental protective device selected for use is a dynamic cathodic ~ protection

. system operating at 10 volts and an expected current density

. of.25 to 50.milliamps. . The~ 1ower. limit of 0.1 Megaohm-cm t

, has been selected to allow this system to provide an electron saturated barrier. layer'over the entire internal surface of the tank thus preventing the development of any galvanic cells as a result of discrete areas becoming anodic.

1 Specification'.D limits the changes in core configuration to

-those: approved by the committee charged with review and-approval. of experiments.

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safety-relat ed in~strumentation. - ,

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1 3. 2.' 21 Objective s L n

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.~,  ; To specify thel lowest acceptable 1evel of performance or the .

n minimmn. number of acc'eptable _ comp'onents for the reactor -

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3 safety system and safety-related. instrumentation.

13. 2. 3 ' Specifications : <

The. reactor shall'not be made criiical.un1'ess the following -

conditions exist:

The reactor safety system shall be' operable'lin -

7 A. -- -

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accordance _with Table 3-1. _ ,

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'B. There shall be two safety-type control rods: -

A regulating rod with a negative worth of'O. 90%. Ak/k (1. 40$)

f - and a shim rod with a negative worth'of 2;50% Ak/k (3;88$). '

C. The drop time for either safety rod should not exceed 1. 0 l: '

second: measurements of rod drop times 'shall be made '

once per semester.

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i D. The reactivity insertion rate for a single rod shall not exceed G 0, 10 % Ak /k ( .-154$) per second.

3.~ 2. 4 ~ Base a Specification A provides assurance that the reactor safety system i which may be needed to shut down the reactor is operable. Each p - feature of the system is described in Table 3-1.

Specification B provides assurance that the reactor can be js - operated safely at the critical state because these negative l worths make it possible to shutdown the reactor rapidly. -

I Specification C provides assurance that both reactor safety ,

rods can be fully inserted into the core to decrease the power level within 1. 0 ~ second,

[

r Specification D assures a safe rate of power change during startup and during power ascensions.. '

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Table 13 -1 Safety Syste_m.:

' The1following. circuits 1 shall be~ functioning whenever fuel is in the reactor. ~

L and power is available to' the. control drives.

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Scram Circuits +

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( A ' scram ~ system shall be provided that willT eause interruption of.

-the' magnet current to the electromagnets supporting the control

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f rodsL whenever a' scram trip i's' exceeded. . Power to thef magnets-

'shall be available when t.he ." reactor on" switch is on and there are no-scram trip signals. A' scram trip shall be provided for each of-the conditions below,' with'the trip.' setting as specified.- -

a;

High' neutronLfluxi- Count' Rate Channel electronic trip-set

. for 180% or less-of Full Power (Full po'wer shall be equal ,

to 0.11 watt). .

b'.' High neutron flux - Linear Channel electronic trip set for 180% or less of' Full Power.

High gamns activity - high' level signal from either of the

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.c. ~

two' Gamma. Channels electronically set for 10mR/hr.or 1ess.

d.- Manual scram - operates upon actuation of the manual-scram button on the ' console. .

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e. Low water level - operates when the tank water level drops one foot below the tank full position. Tank full position is

- defined as seven feet above the bottom of the reactor vessel.

f. Reactor key switch off -' operates when the " REACTOR ON" ,

switch is turned to the off position,

g. Power failure - operates whenever the power supply to the console or to the nuclear instrumentction fails.

2 Reverse Circuits ,

A reverse system shall be provided that will cause both control rod drives to drive the control rods into the reactor whenever a reverse trip is exceeded. The reverse action shall override any rod selection made by an operator _ and shall persist as' long as a reverse trip is-exceeded. Reverse trips shall be provided for each condition as '

below with the trip setting as specified:

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ACour?Ra'thChanns1' revers $ trip shall occur?for-any of ) 2

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t the followin[ conditions:-- ,

$(l')). iCount liate recoider off,

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$a;Y. s , (2): ' = Count : Rate recorder down' scale-- sha11' occur 'when the c -

[ 'm. recorder indicat'es less' than 2 counts per second; i h1 '

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, f(3)?  ; Count _ Rate recorder up scale;-fshall occur when ths _ .

t recorder indicates greater than' 50,~000 counts.'perX , *

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tb. ~ i Linear Channel reverse trip shall obcur for any of thel .

cfo11owing conditions: 7

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(1)' l Linear recorder off. ,

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• Linear recorder down scale ~ - shall'o'ccur whsn the -

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(2) ,

<line'ar recorder is-less than 5% of fullis cale.

. (3) ' Linear recorder up scale ;shall. occur.when the ilinear recorder is greatier than 95% of full-scale;

c. Gamma Channel re' verse trip Shall occur for any of the

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following 'c'onditions: -

' (1) ' Gamma recorde r' off.

(2) Gamma recorder dow'n scale - shall occur when the~

recorder indicates less than~ 0. 2 mR/hr.

(It should be noted that the minimum reading on the -

. . recorder is 0.1 mR/hr :while the minimum reading on the instruments on the' Gamma' Channels for' Area t Radiation Monitoring is . 01 mR/hr ). ,

(3)' Gamma recorder up scale.- shall occur when the recorder ~ indicates greater than 95 mR/hr.

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d. Any scram' condition shall cause the control rod drives.to drive in the electromagnets.

[ e. . Manual run-in-trip shall occur upon actuation of the "Run-In" switch on the control console.  ;

~3 Bypass in Safety Systems i-The only bypasses in the scram or reverse circuits shall be those' described below. The bypasses shall be key l operated switches

' -located on the console, t.

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Table 3-1 Safety System '(continued)

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- a.1 ' A bypass to eliminate a-reverse as-a. consequence of th'e

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. gamma' recorder being down' scale may be. utilized '

.during startup until the gamma recorder reads on. scale.

- b'. A bypa'ss' to eliminate-a- reverse as a consequence of;

. the linear recorder being.,down' scale ~may be: utilized;

'in the. initial fuel loading while conducting experiments-to determine suberitical multiplication'.- -

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' systems are required other than the; pool'of water _

maintained in the; reactor tank. (The total heat capacity.l-f' -

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4 ,. - , b ~ m e K w - ,- o n. . - Eme rgency ' Powe r~ ~ '  ; 3. 6Y- ' L >;,:. f ' ~ No emergency;; power is- supplied to'the MCZPR. ;.In the . ~ '  ; event of power. failure while the reactorfis operating', a ,

scram trip 'shall occur.

~ , , s ~. ~ 9 h h f 3 = . S-4 r h V S - u 16-19

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'. f- V ~ T x -g < TQ ;n. . . y :j .y . , y < y j #' 7 i .-.A 4 x, - q ^ ~ j@ @g . ~ ' ' ~ ' plW i Qf , 1 4-N j3l73 l RaidiationL Monitoring! Systems : ~ $ - g , , i~$ - ~ 2. .. ^ " ' " y . . J 3. 7.;1l ; Applicabilitp ~ ~ l These~ specifications apply to the. radiation monitoring. fsystems f and to-the- timits on thel radiatio'n detection level ~ ' - of each channel. - 13T7. 2 Objectiveh ' .To specify the' minimum number of acceptable 1 components or

the lowest acceptable level of.' performance for. the radiation-

- monitoring ;' systems.' -

3.' 7. 3 Specifications '

' A. . Two radiation, monitoring channels shall.be'provided to measure gamma intensity. -These channels--shall also be used . . ' , to monitor, reactor _ operation and' shall be use'd in the reactor- ~ safety system as described 1n Table,3'-1, t Each' channel ~ consists of a Gamma Detector arid Gamma Indicator. Unit. - A common strip chart recorder shall_be provided with a ; -selector switch for recording the output of either channel. ~ . . i B. !Each Gamma-Detector shall be a sealed unit containing ^ a Geiger-Mueller tube, transistorized count rate' amplifier'. and check source. The output from the Detector'shall be .; logarithmic with respect to the radiation level. - The check t source shall be exposed to the. Detector by a solenoid which - is actuated by a pushbutton on the control console. , C. One of the Detectors (Gamma 1) shall be located on the react'or platform directly over the core area while the other Detector (Gamma 2) shall be mounted on the. side ' of the reactor' tank. l D. The Gamma Indicator shall contain the power supply 3 for the' system, the alarm reset check source control, ' and the output connector for the Detector. Also contained i ~- on the front of the Indicator is a logarithmic meter relay' ' for indication and alarm of the gamma level. The alarm - shall be set to give audible annunciation whenever the o radiation level exceeds 6mR/hr for Gamma 1 and  ! 10 mR/hr for Gamma 2 i t E. The range of both detectors shall be from .01 to 100mR/hr. ~ The system shall be designed so that if the radiation intensity is greater than 100mR/hr. the detector shall  ; indicate full scale, , 16-20 1 e , y- .-. ,.e. .~n ry y.r-~, w ,r w - + - - * * .m--v- e ev-. v--e-++ .- --e -- -* * -++ *vv-* f g., ., - . . ~ \ m  ; -- - 4 > ?pl ; ~ Q ^ .] /- 3. 7. 4 : Bases Specification A provides the functions and components of two radiation monitoring channels and provides assurance - that these two channels can also be used as . safety-related channels. Specification B provides the composition of each detector. and provides' assurance that' each detector' can function well by.using the check source. ~ Specification .C provides assurance that radiation in both ~ radial and axial directions can be' detected. Specification D provides assuranc'e that the; safety; alarm system will be activated when radiation exceeds the allowable limit. Specification E provides the range and design configuration. of the monitoring system. 16-21 gy -- ~ n c; _ L 1> -> ' 7 g s g, ps f

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~ " > > . ,', g. , ^ w .. A  ! 3. 8 ' iExperimebs , ' ~ A f Ln ;l%; , - - ' !These' specifications apply to the l experiments installedL  ; ~

y. ,

^ -^ _.in the reactor. -- , , 7 .

3. 8. 2 4 Objective

~ ~ ~ . . To prevent' damage to the reactor.and release of radioactive! , material in the event _of experiment failure,7 and to ' avoid s ' - . exceeding any safety. limit.- 3,8. 3- Specifications? ' Limitations lon experiments and material irradiations ini the, reactor shall meet the following conditionsi A.;  ; No experiment shall be installed in the reactor,in such a location that any part of the apparatus will touch or in anyl, way interfere with the action 'of thel control rods. ~ B.- ;No experirnent shall'be installe'd in' the- reactor thdt can shadow the nuclear instruments, thereby giving erroneous: or unreliable information to the reactor operator.- C. -No experiment which has explosive properties shall bei irradiated.- D. ~ Experiments containing materials whose' release to the' water could result in a violent chemical reaction (e. g. = , . Sodium) or would result in chemical or corrosive attack to the reactor components (e, g. Mercury) shall not be irradiated. E. Experiments containing materials whose release ~ could result in overexposure of personnel to gaseous or' particulate. radioactivity shall not be irradiated. F. Each experiment, other.than laboratory exercises defined in Item G shall receive the specific approval of the Reactor Operations Committee. In addition, all operations leading I to the production of more than one millicurie of any radioisotope; outside of fuel elements shall receive the approval,of the Reactor Operations Committee. G. Laboratory exercises - The following laboratory _. exercises, while not requiring the presence of a Reactor ) Supervisor, require the presence of a Reactor Operator. Laboratory exercises involving use of experiments-(other- , than experiments used in the following exercises) shall be 16-22 l u p% n, - my 7 e S.L . .

n. J. Mf a w <. A:

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$ p ,. &. ~ ;( ~. % A.% 7 +. ... , - .7% ', g . 3 q- ~~ ~' ~ %  ; cpnducted 'inJhe presence. 'of a Reactor. Supervisor.

,- . . w; .i - ; ,

1. L Startup,and. Ope ration of Manhattan College

. Ze ro' Poy(e r . Re acto r: LApproach t'o Criticality - . 2; - Critical h?.ys Determination

3. ~ Reactor. Period:and Reactivity 4

4.s L Void'Coeff'ide nt' Me asureme nt b y 5.  : Flux Disttibution '~ in the Manhattan College- , ,,, Ze.ro Power iteactgir I.7 .6., pgermination of Buckling; . 7a (Measurement of Diffusion Length and Age; . l(,8, 7 I, Temperature Coefficient of' Reactivity . 9 9. y,Gimma Ray Energy Spectrum in thejVicinity ' i: *

• j _7 of the Reactor Coit '

-H. A ni imum~of'seven a16m'inum covered'in'dium foils with a ~ , icomb%d negative reactivity ofi-1.113 X i10 .4 Ak/k may be; ~ used WA .labot stoj+y exercise (Flux Distribution in the MCZPR); 4 7,^ v[df 4)t.b~inegativeLwD,$h)of -10.~ 4 X 10-4 A k/k may'also' / w; - )a,be 'used in .a-laboratory exercise (Void Coefficient Measurement). ? . f., f' I .- - A record of each material irradiation shall be included in

• 'the reactor log'. The record shall include at least the'

• following data: 3

' ^ Material irradiated . ~ ' Position in core v Reactor Power / Irradiation time, time in, time out ^ Dose rate on contact at time of removal - ^ /, Supyrvisor's signature 3.8.4 Bases Specifications A, B, C, D,1,E F, and I are based on require-i e ments stated in the Standard for The Development of Technical: / Specifications for l,esearch Reactors, ANSI / ANS -15.1 - 1982. .' Specification G list'sI all been performed with the,the 'MCZPRlaboratory for teachingexercises and training that have purposes. There at'e no lis61 ting conditions for these exercises except item 5 - Flux Distribution.in the MC7,PR. With regard to SpecificatiIn H, for the laboratory exercise - 'a involving the'irradhtion of the seven indium foils, the reactor . is alwaJys scrammyIEeTore these foils are removed. Also,- / g in the laboratory exercise for determination of the void coeffiTient, both bontrol rods are fully inserted before the rod is fully removed.7 , I 16 -2 3 .<? # r . r -+ . , - . r. , ; . , _ _. i .N , ._ , , , , . _ , , , , , _ _ . _ _ , _ _ , , . , , . , %,, L...ht 4 7 *.c n ie -- s t 4 .i m.. j n , o ,w- - M ~ ,_ ': 7 (. i gl1 g' - . m. - , , > .c)_

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r i "' w' _g 77= _ ' ^ Q;f"' - ', ,W: - - ~ ~ ..L. ', [ -J l [ - + 3 .3 e . . ,; . c L _ = f4.'0I SURVEILINNCE REQUIREMENTS 2 i s Surveillance tests,iexcept those 'specifically. required fori l safety when the reac' tor isl shutdown,f may be~ deferred during- , -. 7$e- . reactor shutdown: however;- theylmust be: complete'd prior:to - rea'ctor starthp. ~

• 1

, 9 t - 7

421.  : Reactor Core Parameters -

~ y . No'significant core configuration or: control rod changes.: " have' occurredLsince the initial excess reactivity tests of 1966.' ~ Any.significant changes:must=be_ approved by the .Re. actor'- Operations Committee (ROC) prior to'thel change.< ~The' ' Reactor Operations Committee' meets semi-annually.- f.. f' 3 16-25 u.. QyRQ2f < j7 m g .

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1. 4 .2 Q }, fReactorEContrdi and Safety Sysl tem? ' * - '

~ - ~ gi . W i4.:2; 19; Applicability 7 ' e e _ JThese specifications l apply to the; surveillance activitiesi ~ t y Virequired for the reactor control and safety sps' tem.- 2=, > J4.' 2. 210bje ctive { - ~ ~ _ e 'i(To^specifyShe frequen^ f cy and type' of; testing'oricalibration'to j . , . -lassure[that the' reactor control and safet Lspstem conforms.E -ito the ' specification' ofisection 3 of these Specifications. t = 14, 2. 3 M Specifications - , A' ^ Y 1It is assumeid' that the > worth of the. control rods remains ~;; j unchanged. ;Ho. wever, the relative worths' of the' control rods M' L , -;shall be checked, annually.by comparing;the criticality positions

of the control rods with the criticalitp positions of. previous _

years.

LB. The rod withdrawal speedsishall be. measured at least twice: ~ La year, and shall be such that the maximum speed is:no. greater - than 12 inches per minute in the MCZPR.

C. The operability of the_ control rods and driving mechanism shall be tested daily when the reactor is operating.

. ;. D. An operability test, including trip. action of each. safety channel ? listed'in Table 3-l that' provides a scram function shall be ' completed prior to each reactor startup following-a period when the reactor has been secured for more 'tha~n 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or p .at least week 1y during_ continuous op_erating periods, - E. - A calibration of the channels listed in Table-3-1 shall be performed at least annually and whenever any maintenance on a channel which may affect i ts_ performance is completed. 4.2.4 Bases Specification A provides assurance that relative worths of the control rods will be checked annually. The rod withdrawal and insertion time measurement intervals - required in' specification B verify the limits in specification 3.2. 3 ~D and are appropriate to detect abnormal performance. . Specification C verifies the operability requirements in 7 , specification 3. 2. 3 C during'each day of operation. ,? 16 -26 w L. ,. ' - . - ( n,- ~ g ; 1 ,+ ; - a f' _ _, g[@g'f.4.j s ; IS - '( d .. ,-o q..- ~ ~ . ! '. i , i 1 & l.3, ' , + , j fs y i ' 'O p,;_ v-- , lIn's pe,cificatio'n1D eas.h channel capable of generating-a scrarn' ~ _ signal is test'ed during the prs-critic'al procedure,'(prior to '; , . startup,<so that the fconditions of specification 3.Z'.3 A j.'are - s . satisfied. * ' Specification E requires' calibration of safety and safety-~- related channels'at an' interval which is1 appropriate?and1 . (justified by prior experience ~ at.this facility; J '/ 'fs + h., [ 4 f h i- ~ J) . 9 i. _ 16 -2 7 4 k, - ['-

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' ~ - - -p .d,,,e - [t c. 4; ,- ~ 4 r ~ '.. , ' : . iAi , ,'.~ , , _ jb 1 qi- , E* - , hy 1 ~ O < l Coolant. Systems ,

4. 3

, ' :There is no: coolant' or. coolant sys' tern in this' facility s . "other than the. pool watbr.; : Water in the-MCZPR iost:

due;to' evaporation (is replenished wit'h New; York City. '

' water. - The water' from the city system is pas' sed ' afdemineralizer, -an eleciricallyg ~

through]:a}; filter,-

^ ' controlled check valve, and-a short flexible hose over the ~ top of the reactor tank. .The check . valve insures no.back -flow:of water from the reactor. in ' case 'of-press.ure los.s

in the water supply; system.~ The flexible hose is removed:

~ from the reactor tank when the hose'is not in use. , The water level in thef reactor pool is maintained atiabout - seven feet from the tank bottom and is checked every- ,

day that the ; reactor is operated.

i s i i a 16-28 ^ I a j s - - La _ pg -- j!: j (- gj,;

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/4.' 4 : Confinement or Containment .

The re is no confinement or containment system.

~ 16-29 ^

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; ,

i ' , , >d ( 4.#5. IhApplicability ? , ~ y'^ , , iThis specificatior. applies to[the surveillan~ce. activities - 2" ' ' required for/ the ; reactor ventilation'systemi ~ ' .- ~ , , . , , i4i 5. 2 l 'Objeetive t , ~ '..Tojspecify.theifrequency; add type of testing'to ' assure tliatL ' - lthelventilation system conforms to-the ' specifications!of. t seetion 3. 5 of these Specifications. i !4.' 5. 3f Specidication ; ',_' \The blower and switch Sf ventilation system shall undergo ~ 1 M  ; testing for normal operation at leastlonce per year. ,

4' 5[4 m Bases -

,;This -specification requires that the blo'wer and ' switch of : ' ventilation system be teste.d to verify that'they can' be - ' operated when needed.' The testing interval is ' adequate to ~ . verify operability, based on~ experience at this facility.: L 4 4 g *, h t i i 16-30 . c .l 3 i 1 L~ _.- . n; 4 ?mv a. n. +. p'. y. .. rn- , - - . , ~ , =As-- -w ; ny ' . r % . =2 o y; -! ys dy/ , >mm ne

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4. 7 Radiation Monitoring System 4,7.-1 Applicability These specifications apply to the surveillance activities required for the radiation monitoring system.

4.7.2 Objective To specify the frequency and type of testing to assure that the radiation monitoring system conforms to the specification of section 3.7 of these Specifications. 4.7.3 Specifications These. surveillance activities are required for safety. A. A calibration of the two radiation monitoring channels shall be performed at least annually and whenever any maintenance on a channel which may affect its performance is completed. This calibration shall be performed by comparing the readings of these instruments with those on a portable beta-gamma survey meter. The latter shall be calibrated annually by a recognized diagnostic laboratory.

B. An operability test, including source checks, of the radiation monitoring channels shall be performed at least quarterly (and recorded in the reactor checkout sheets).

C. Readings of the radiation levels of all instruments shall be recorded hourly during operation with the reactor being critical. D. The environmental film badge and smear surveys in and around the reactor enclosure shall be performed at least twice a year. E. An ALARA program shall be established and monitored by a Radiation Safety Officer (RSO). 4.7.4 Bases Based on experience at this facility and the average usage pattern of the reactor, specifications A-E are adequate to verify that the operations conform to the specifications of

3. 7. 3. The usage pattern will be subject to review by the Reactor Operations Committee.

16-32 ' I klAk n . 1 .f . n .~. 4 . , ' 5" RA I ~ " ll- [(', , ^ > t , f f7f.^ , k ~ g G- , 71 , f; . , , 3 gw w ;r - - -t _ m .- ,4-ti' < w 7s. sy; s - , ~ [ ~ . e 1 .i 54.81  : Expe riments 'b a. Ti , :3 ? g: J.42 8.15 Applicability' : ~ The se specifications ? apply to' the: surveillance activities -- -

required for experiments installed in'.the reactor.

4 (4. 8. 2fObjec'tive : _ 4 , sTo'specify the frequency-and t pe lof[ testing to assure thatl , 7 :the experiments conform to the. specifications 'of section ' ( 3. 8 of these Specifications. ~ ~ ~

4. 8. 3' : Specifications '

-A. The identification ~and location ~of all installed experiments shall; ~ be ~ recorded priorito each re' actor startup; E B.? cOther specificfsurveillance activities:shall be established during. the review and approvat~ process specified in section 6.~ 0.- , ?4. 8.'41 Bases - . Specification A requires that the reactor operator verify that- - the installed experiments are approved. .. Specification B. recognizes.that detailed surveillance require-- rnents will vary among experiments, and that the Rsactor . .O perations Committee specifies the appropriate type and . frequency of surveillance. ~ .s [ ~16-33 m ) n . , _ .~ - . . ' nm . " = 26::  :.s .' -" ~ 'y-W. 49.~ > %v ^ ;" e 3, ..-,':.\ .; 3*, ';W , 4;, Cz" .,.5 . ~ , _ lc ,m qq- e. ^n? ^f.'% ~Mi.;': < ;x w ~ ~^ W- .: p. s 1 ,--:- r' - ..gsn '7 t p. n. .r-y." . ( '3 ,. m -'a -4 ,,. ' , t m3" e, y M: ::n .i ' g ','u-s -t so - - p , sy- e " , /+. ' . ,.4;r ' p? q e-'? pf -. .-. . , .Q:-

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25. 1: JSitefand Facility De'scriptioni. _ _

H [- The Manhattan College;Zero Power Reactor'(MCZPR) is- ' located in theilico Engineering Building of; Manhattan College ; ~ C - x ~ ~ !at 3825 Corlear.%enuel Bronx,X New York.' _ m . . i .- ' "l ' s. D - The[ laboratory / room where the reactoriisilocated is) ~ fconsi.dered a' restrict'ed area'asfdefined in; paragraph ' q ~ . 20. 3(a),114hof 10= CFR 20. j + + ~ . . . ,  ? - 7 , 1 The principal activitie's carried on wi, thin the) site are those! . .

related to the ~edu'cational program of M,anhattan College. ;The.

reactor may be. utilized in'this program for-instructional use -- ^ ^ - and may be.Tused infiaboratory exercise's1for teaching;and training AV _ purposes. ' ' , a - The Leo Englneeringl Building of Manhattan lC.ollege.;is a four Estory,.; brick building providing space for Engineering and , - Science Laboratories. The building provides classrooms,7 _ computer l facilities,c and laboratories for 'an estimated 1800 ~ ~

students' at any one time, t as well as ' office ~ space for the Dean * .

a e of the' School o_f Engineering. . chairmen,: and faculty members using the building. The laboratory housing the' Manhattan College = ZPR is completely 1-

1. -separated from the remainder ~of the. Reactor Laboratory as ~

g -shown in figure 5-1. Security locked doors provide ~ the only-access to the Reactor; Laboratory. ~ M - l . The MCZPR laboratory has the following penetrations: a e

a. Electrical conduits '

[ b. Air circulation system [ c. D >or (secured with locks and a security system)

d. ~ Window (sealed with plywood)

The MCZPR is located in the laboratory as shown in figures 5-.2 and 5-3. The. reactor tank rests on a concrete slab in the first ,

floor.and extends upward through the second floor. The first floor room housing the reactor has' concrete walls extending from the floor to the ceiling on three sides and a metal partition ~ l, from the retainer wall to the ceiling on the' fourth side. ' The ' , p. p .- !) 4 i 35 , r s w . , , a-r, , -c., e-  % 4 +. m w,-r.,#w, 3-- ,- -, . ,-e<. -.,v, .-w.., n.,, 4 e .. m.e-,.,2re,- hy ---w-wy-.~e. i WATER / MODERATED 'SUB CRITICAL REACTOR GRAPHITE MODERATED SUB CRITIC /)L - REACTOR / s. i / h M >  ; I CONSO j~ 7

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M I w pyt f J ' .l.o N >  !! 'y . / [Y REACTOR ib VESSEL / i;. T. % ^ '~ ) ... }, - Q-/p/ / - / ,5 COUNTING N ROOM i BRIEFING RCOM Figure 5-1, Cutaway of MCZPR Facility 16-36 , JPLAN ( ON' FIRST FLOOR OF LEO ENGINEERING ' BUILDING . ) f u. M rAn. A rr f mpAL af u.W ' r_g - -. - ~}, l;  : L- J U w ~l I -

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' ~ ' ' + qy  ; , . . + o M' - ;g ' , _i g p- , ^ !7 n ' only access' to th5 renctor from~the' first floo'r is through) - -i

a mital' door which penetrates lthe metal partition' as' shown : ,

~ ^ y in figure $5-2MThe metal' door?is kept; locked _at'all' times ['%h[e' ~ 'when there is fuel lin the reactor. : The only unlocked access , ~ - " ^ l' , ;to the~ first floor of the -MCZPR room when fuel is in the ,p ~ ~ reactor is from the cecond floor _ through:a trapidoor in the. , ll ^ l ' -( f- y reactor' platform and ~down a vertical steel' ladder adjacent' ~ 1 4 , to the reactor tank ~ as 'shown in figure 5-3. - , < + f.j

The reactor platform is located on'the second floor. above the tank whenever fuel is located in the reactor. The platform is surrounded by a link fence to prevent personnel from-

~ ~ ^ 7 inadvertently approaching th'e open areas in the platform? ? . S 1 'In addition'to the concrete walls extending from, floor _to _ , -ceiling on three. sides 'of the first floorJroom' housing the ; reactor,:a concrete be rm has been con'structed on the fourth - side sufficiently high to contain all the' water in th'e reactor , , tank.. ' The window to the~ MCZPR Laboratory ha.s. a window guard thatn . has been' sealed _ to prevent unauthorized entry into'the~ room.: The. door into the facility.is locked whenever, a reactor; . . operator is not in attendance in the room. During times when an operator is not in attendance 'in the ~ MCZPR Laboratory, the MCZ5R Laboratory is under electronic surveillance. The reactor vessel consists of a cylindrical aluminum tank-eight feet high and ten feet in diameter. The tank wall is one - ~ The only tank wall penetration is a ~ quarter of an inch thick. 3/4 inch ' diameter. aluminum coupling located near the tank bottom with a'3/4 inch diameter short ni_pple and a 3/4 inch' aluminum gate valve. The inlet'to the demineralizer is connected to this gate ' valve. The outlet of the demineralizer feeds into a pipe which rises vertically and forms a gooseneck loop over the edge of the tank. The reactor vessel is located as in figure 5-2 and is held in , place by five aluminum brackets welded to the sides of the , tank near the bottom. These brackets'are bolted to'the concrete floor. 16 . k , ak. _n - ,.a- . < ,o _ . 1 .w , n" . ~ J. . ; b, ! - i,,i A. . mm ?, .u. ^V ~,: , V g ,% +y.a.v,;%, s c _: --. ~..' - pte '9 7_ wr .y ' - ,- .n -.y b, m ~ ,. <*f g ,',. nn- + r. -- a '% =m ,vv..J.g 'y . i,*. 3 y . y'If (a

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- ..- ,< .. . .; . .; . . ~. ' my- r W' s ,; . - - .- , . , . ^ dThere;is no' reactor: coolant, or coolant' system oth,er thann p C Pe. t.~, ' .s ' I# p .;? ' d m. ,N. /[,. ^l Fm6arcw X'f,- ,the reactor. pool. 7. T t -L , e~ . , " ' ' ' . . c . m ,.s ~ _n !. e < ~A * + * - .. ;;a h.. n,. s e, ' ey ' .;L. ' ~, ' ' ,' , L;' i ~ GO - > . + s, e , . ., '- x

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• L5.3; Reactor Core, . Fuel! and Safety System; '

.L k j ~ s 15L3.1 . Reactor Core : , % .o g ._ A grid plate ' stand as shown in figures 5-4 and 5-5 isi -welded to' the bottom of the reactor tank.h A grid' plate is bolted to the. grid plate stand. The design of the plate including attachments thereto are:.as shown in. - Tiigure 5-6 . Fuel element hold down_ rods'are threaded ~ into the ' grid plate unless an approved program-l requires their removal. .The holes in the support cylinders' < for. the in-core fuel elements are plugged. < The shafts of these hold-down rods are made partly of ' aluminum and partly of lucite.as shown infigure 5-7

The lucite portion consists of a solid rod one inch in - -

diamete r. The threaded base of the hold-down rod is made of aluminum tubing _having a one eighth inch wall thickness.

The broad top of the hold-down rod, _which extends over the top of the fuel element is also made of aluminum. The-aluminum portions of the hold-down rod are securely fastened to the lucite by aluminum pins and epoxy cement.

16-41 P ( y i L  % f tf'. 0e- 9 e - h -, kk 4 iQ. o Mkk (+g 4, ,8 . a. . .is N M O ' }p. h t.1 __ a.. . _ _ _ _ . . _ - , qt - I e,.g-a q' ) P ..

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• ~ _ <

= < 8 . ... . _ .  : !The: design of a fully loaded element is as shown' oni ~ ' - figure 5-8. l The fuel portion 'of such elements ' consists:of, L Asix concentric' cylinders formed by mechanically joining-f and posit 1'oning eighteen curved fuel plates within grooves _ T of 3 : spacer l webs.1 - The fuel plates are mechanically _ held on ' the' grooves by roll bonding:- f the' bonding provides. Joint ' . . 4 ~ z strengths-of at least 200. pounds per linear inch. . ; The fueled ; , .s , ~ ~

portion of. the element is 24' inches long and is locate'dlwithinL

! m' 1/8 inch thick','. 3. 51 inch OD support cylinder which is' , 37 inches'long'. ?The' support cylinder extends 6-1/2 inches - 1.beyond1the' fueled region on_ either end:g this; axial.positionT =! is maintained'by 3 plug welds _ joining the _ spacer' webs and the' ,4

g. , , l support cylinder. Three~ 1ugs' are provided on'the inside of-the support cylinder, at each end.' ' At one end, .these lugs L position.the cylindrical fuel element in. the slots in the'

'! positioning 1ug'f attached to the grid plate and at the other , end are used to mate with.a fuel handling tool.- Partially .: loaded ~ elements, except for the number of fuel plates,' are . designed in accordance with this paragraph. The cylindrical fuel plate. con'sists of 0. 020. inch thick U-Al . alloy of.92% enriched uranium, clad on both sides with 0.015 inches of aluminum making the total plate thickness 0. 050: ~ , inches.; The' nominal U-235 content of each full fuel element is 200 grams.. .The inner diameter of the innermost cylinder ' is about 1. 25 inches and the spacing between adjacent cylinders (water channel width) is 0 118 inches. A ma:cimum of 15 fuel elements plus one partial fuel element, which may have some fuel plates missing, is used in the facility. The weight of a co_mplete fuel element is 4. 505 kg, Land the weight of the partial fuel element is 2. 527 kg.- In each full fuel element, the weight percent of U-235 is 4.45%, and in'the partial fuel element , the weight percent of U-235. is - 0.95%. These are percentages of the entire element including the uranium-aluminum alloy, the aluminum casing, and the - aluminum' cladding. i 16-46 1 -. 4 t' - J J O < 37 00" " , 6)" 24" active fuel -A 't g 6 r=i- [ = # =l g , I

r w .

i 1 j j xw = 1 ., ~. - l GUMD RING A d M TES i LIFTING LUG BARRIER TUBE SUPPORT CYLINDER MATING RING s4' ' i I \ l ,<f*?,, ; ~ . { f j %f6FWc Mrcs .y R ' I i s e \ ' .i.hT:- . W's f ( l !f k* f -

s 'ss f

o.ng" { Water Channel Width) 1 Figure 5-8, Fuel Element i 16-47 j l y w  ; . s p . y,- -

g

+ 8 se, g - s + t s [- , <l f .- ,y ~ 1:j 5;3'. 3_ Mactor Safety System - ~

The critica1' assembly.is controlled by two' Y-shaped control '

i ablades which pass in' the clearancejbetween adjacent fuel: '^ ' ~ ~ ~ ' elements.j Construction details and dimensions'are as shown 1 n figure 5-9. One control rod (the shim rod) is constructed - so that the blades;are formed by sandwiching a 1/16 inch L .- , sheet of cadmium between 1/16 inch layers of,stainle'es steel., - The 'other control rod is an all stainless" steel regulating rod.' c. ~ .' Either one of these control rods ls~ capable:of preventing the. reactor from becoming criticyl. l Each control blade.is ~ guided by a: guide assembly for the full ~ i , E ' ~ 1ength of the control rod stroke. These guide assemblies ; prevent any bearing of the control blades .on the' fuel elements.; - The guide, assemblies,lwhich are positioned on the' grid by . ,y l( , pins,iaiso act as sway bracing for the guide tubes. : . Details . of the guide' assembly,lthe ' methods for positioning on the grid ~ o plate, . and the method for connection to the guide _ tube are . , as shown inftigure 5-10.t The guide tube is bolted at the , . upper end to the control rod drive units.- .Each control rod is attached to its associated drive .

:. mechanism by an electromagnet and falls by gravity to' the least reactive position upon decrease.of magnet current as a result of scram action. A system is provided to give

, ' indication at the control console that a control rod is in I - contact with the magnet. L A reactor. platform is located over the reactor tank on the - second floor of the ZPR 1aboratory. The platform is bolted . to the concrete floor of this room. The neutron and gamma-ray detectors are suspended from this platform. The control rod drive mechanisms as shown in f igure 5-10 are bolted to the - ~ I structural members of the reactor platform. The_ control rod drive system is designed in accordance with these L specifications. Each control rod drive system is a cantilever ! . drive with a design drive speed no greater than 12 inches per

f. minute. Rod motion is controlled from the console by :

individual momentary contact toggle switches having an IN-OFF-OUT selection. Driving the control rods into the core by a reverse action as described in section 3.2.3 overrides, 'any manual selection. Each drive also has position indication i from the " full-in" to the " full-out" position. 16-48

i

,y . - . , . . - a .._ _ . t g4 1 ?. .f ENJ PIATE 1 i IfGTDC PI.N; CCCC. RCD CDL~.'OL ROD i GUIE CIDE Tu'BE FIAh, fM IDE*IUBE DRIVE RACK - j

• 1 N l 3

7 c- y +r-J>h OO , ._ _.. __ m . i ~ ~=.- , ,_ __ __ c > 2 - o n scz=ade - ku .i - ~ --- -- _ ._,c. 5 ,._ nu . b4 f SJ l C'M i  ! t+5.5"' 24 1/S" ) N 13'-2 7/6" r GUIDE'IUBE 4 BODY Sig {At,'4 _1 __. hp_ .187 g tj . p J # I EITENSION ES3 PI.ha '

1. Sir ~

,,tg Ca\* TROL ROD CIDE SECTION B-B SIC ION A-A SECTION C-C-l Figure 5-9, Control Rod Assembly' 16-49 g,...,-- - b $ .y

v. ..

- RACK HOUSING -w l LIMIT-SWITCH i / \ s i /l I i l l I POSITION INDICATOR GEAR TRAIN HOUSING ' l /g h DRIVE f MOTOR lr RACK DRIVE sl , I ? ~l 1 . v T =r b ( T RACK i , , _f D Figure 5-10, Rod Drive Mechanism 16-50 em m, = , y . ( = . f/ J Q ' p ' ' j.T 77 . 6 .. r . .g ' ~ y ,_ , g, /... , t }lk ' , !, f . , F, p 79? ' Theyosition sensing element is a potentiometer located & .in each rod drive' mechanism. Coarse position readoufis: ~ y . . herovidedgf the contyol console in the " form of two indicators ~ _ ,. - .'{rbading.from_0%.(fu11-in) to 7 100%:(fu11-out). The system- ~

, indicates"fod position with an accuracy of 2%. ' A fine position" N vipdicatidw system is'alsh provided tol indicate rod position-

,, pith an Ecssracylof 0.1% "4 .+ p. .,p SThe conteol; console for the; reactor is located as shown on . figure 5 'R Thel control console' contains'all the necessary. i switches,- lighQand indicating-instrumentation requir_ed to L operate the reactor. " Motion of the control rods out of the' , 'M'i reac' tor. ish possible only by, actuation of console control' ~ t ,",~ ' [ sw!t ches. ~;A moderator demineraliser. system i_s_ locate'd on the? first fl ,- laboratory. The ' system is ai clo, sed loop ,oor containingof the MCZPR a pump and.demineraliser. The flow A- -f rate).through~the domineraliser bed is' valve controlled to' be; ^ ~

betwdin 5 and 20 gallons / min /ft2, ,

y , The 'startup source is a Pu-Be source encapsulated in tantalum. . The minimum source strength is one (1) curie (approximately 10 6.' neutrons per second). . 'g ., * / 'f * '^ 9 ' _}' y % ~ . J x y b e in I s 9 $) s t* > ' kP ,, 4, ' 'b 7 7 t ,\ 5, [ g '. 4 *9 .$ F f' . c a; , 16-51 L .- .r . s , , .* r ,Y. -f 6 s. , .g 9 'l l, '1?: 1 / .* . / in,. ' s?' , 2* *o'~ _ . _ ._ . ,_ i .. ,, ..,-,.,,A .._.,._.-_._.______..m., _,_,_,._,,,,_....__I 3 7g < < r , c & ^;f - .: .i . a,i [i - < .27 _ 1 a

t '

5. 4  : Fissionable Material' Storage) r Fissionable". Material Storage Fuel elements' are permanently >

stored on the reactor grid plates with.the exception that' . thr9e fuel plates are'. permanently stored in a, locked steel container fastened to' the floor of the first floor of the'l " htC Z PR Labo rato ry. .- , - Y f . i }- t 16-52 1_ {h, s .g m , , . y , . J. . t - - s ./. ._[6 [ d'- : ADMINISTRATIVE CONTROLS - _ y 6[1 , - Organization . 6.1. Il Structure . LThS organization for the mana'gement'of the reactor' facility. ,  : shall be structured _as .sh~own in figure 6.1. ' Levels of '- , . authority indicated.' divide responsibility as follows: m ii  : Level 1:'l Responsible for the facility licens'e and ' site c a'dministration. + Level 2: . Responsible for the reactor facility operation! ' and management. , , ~ Level:3: Responsible for. daily operations f t The'.Reacto'r _ Operations' Committee shall be appointed by-- the Reactor Administrator and shall be responsible 1to himT ~ for. the review and evaluation of all proposed operations and procedures in order to insure that the reactor facility sha11L be' operated'in a safe and competent manner. 6.1. 2 Re s ponsibility . Individuals. at the various management levels shown in . Figure 6-1,-in addition' to having responsibility for the policies'- and operation of the facility,-_ shall be responsible for safe-gua.rding the public and facility personnel from undue' radiation exposures and for adhering to all r'equirements of the Operating - License and the Technical Specifications. , In all instances, responsibilities of one level may be assumed

s by designated alternates, or by higher levels, conditional-upon appropriate' qualifications.

~ The detailed description of duties of each individualin Level 2 and Level 3 are as follows:  ; !~ L A. The Reactor Administrator will provide final policy decisions ' on all phases of reactor operation and on regulations for the

facility as a whole, _ He will be advised in a.". matters concern- -

! . ing the safe operation of the reactor by the Reactor Operations [. Committee. 'The Reactor Administrator shall be responsible for the overall administration and supervision of the reactor 7 i f' . 16-53 % / A e e v W r++w@ v----r~gg-ev' - = -e 4 4 fw (e ty h of +-,b---W p.We. a e kmeg rg e

• F F w+s#4: w -8 T 8-'*

y - - . - . f -s.; . ,

v3 y m.e --

et:- MANHATTAN COLLEGE CCRPORATION BOARD OF TRUSTEES: F' - Level l ' " l . ll PRESIDENT OF THE COLLEGE l.; _ } , . l- - l EXECUTIVE VICE PRESIDENT l-l -- , l PROVOST l . I s ' l DEAN OF THE SCHOOL OF ENGINEERING l REACTOR ADMINISTRATOR Level 2 i e RADIATION RE ACTOR OPERATIONS SAFETY OFFICER COMMITTEE - l HE ALTH' PHYSICIST l C,HIEF REACTOR SUPERVISOR Level 3 - q l REACTOR SUPERVISORS l - REACTOR OPERATOR Level 4 p ~ CLERICAL STAFF, MAINTENANCE AIDES, ASSISTANTS PERSONNEL . Figure 6-1, Table of Organization , ) 16 - 3 k, >+ -- p g g , - - -=9 ) ..,,,.em.h, . - . . . - >,-h-- g 5.;;- , 1 N z s i =4 . - . .. . .. ,

facility. . He: shall appoint . qualified members to the-

~ ,f - H '~ ! Reactor. Operations Committee from time to time as - '! ~ > necessary. : He shall de'signate" Reactor; Supe rvisors, ,' 0 . . iname the. Chief. Reactor! Supervisor.; an'd appoint the - ~ - Radiation Safety, Officer. The Reactor JAdministrator . shall- approveand promulgate' all regulations, instructions. . , and procedures governing the, operation"of the reactor facility.

The Reactor : Administrator. shall be ' appointed by the Provost of Manhattan College.; ,

~ i1 - w 4 cB. :The React'or Operations Committee shall be responsible' to ; ~- thel Reactor. Administrator for the review and evalsation of-all proposed operations and procedures .. in.' order to insure that ; the reactor facility shall be operated in a; safe land_ competent' - manne r. Particular emphasis'shall be placed on the examina tion of 'new and untried operations' and procedures, and the-1 Committee'shall take' action on proposed new experiments. The Committee sh'all review and evaluate all propose'd changes- ~ 'in the reactor-system. The Reactor Operation's Committee sha11' advise on and be a.vailable for a~dvice and assistance on any problems relative to the. safe operation of the reactor ' facility.: The Radiation Safety Officer shall be responsible' for the C. promulgation and enforcement of rules,- regulations and-o'perating procedures which conform with the regulations -set forth in 10 CFR, Part 20. The Radiatio'n Safety Officer in conjunction with the Reactor Operations 1 Committee ,shall app' rove suggested procedures for the purchase, . possession, ~ storage, use ,and disposition of a11' radioisotopes, consistent - with general or sp~ecific licenses for use of by-product material issued to Manhattan College. The- Radiation Safety Officer in conjunction with the Reactor Operations Committee, shall be available' for advice and assistance on' problems involving ' radiological safety arising from the operation of the reactor facility. The Reactor Operations Committee shall evaluate - 1-and approve all proposed procedures leading to the production of radioisotopes with a half life longer than one (1) hour. All - operations le,ading to the production of more than one (1) millicurie of radioactivity, with any half life, must receive , s- prior approval of the ~ Reactor Operations Committee. i }? 1 4 16-55 . + b- e -- + < - - e , , - . ..,. d. ., , ,,s.- - % , . ,m#w , - er w..w.-am.'-,4 =-,e--e.h* - . . . , r, .._ _ . 7 - _ g/ ., 4 -4 . [; Q ' s .c

D.' ;The IHealth Physicist'shall be responsible:for mor.itoring;

,' - T records of. exposure.on film badges',7 maintenance lof a log von radiation tests and exposure records.- .He also shall ~ ~ review the reactor log. Periodic radiation surveys of the 7 4 . critic'al reactor laboratoryf the -suberitical laboratory and . ,T 1the counting' roomKandfother areas where radioactive- , ' ' materials are being.used,ishall be made by the Health Physicist:

under the direction of the Chief. Reactor Supervisor, J The ;

Radiation Safety Officer :shall be notified if an' abnormal" ' ' radiation problem is encountered. Results of the.se ' surveys N ' shall be reEorded or' filed in'the' log.: The Health Physicist ( _ - - shall'also be responsible for proper disposal ofisamples-andj . i'  : radioactive materials.- TheLHealth Physicist shall be. appointed ' ' by the ' Reactor 7Administsator 'after consultation with' thel Reactor Operations'Conimittee. 't' p, , _ E. The Reactor'Stipervisors shall Me' appointed by theLReactor . ,

Administrator. DThese individuals; shall have' general '

' ~ competence'in reactor' technology and associated fields. Each? . Esupervisor shall hold a Senior' Operator's License l issued by ' ' the Nuclear. Regulatory Commission. The ReactorLSupervisors 'shall be responsible' to the Reactor Administrator, through ' ~ j; the Chief Reactor Supervisor,- for' the' preparation and submission

of complete detailed proposed procedures, regulation'sland :

[ admininstrative rules to insure the maintenance.f safe o'peration, ^ proper and competent u'se, and security of the reactor equipment.' Appointment as a Reactor Supervisor shall in all case's be' ~ accompanied by appointment to'the~ Reactor Operations Committee, L . The . Reactor Supervisors shall be responsible for the preparation and submissio~n of operating schedules 'of the reactor facility,: , and shall insure that all:a'ctivitie.s and experiments involving the - T facility conform to both local and Commission _ regulations.- They shall establish in coordination with the Reactor Operations .. Committee, procedures for activities : to be' performed with i th'e reacto'r. They shall establish proc ~edures and be responsible , ^ U for the keeping of adequate, complete and currently accui ate: records for. the operation and maintenance of the facility. A Reactor Supervisor shall be in charge of the facility andJ  ; shall witness the startup and intentional shutdown procedures. In addition, he shall be responsible for prompt execution of emergency procedures. ' a 16-56 l- . t-4: W , 3 ., , . -a , , 4.~.._---.-,--,a..~._..;..;-_...~._;.__-..,_a...__~.--~;a.c. '~ ~- x- -

- 4 JF. The' Chief Reactor Supervisor shall hold a valid Senior.:

. Operator's License issued by the Commission. He shalll ibe responsible for the~ promulgation and enforcement of1 ~ ' administrative rules, regulations and operating procedures. 3 ~ He sha11' inform the ReactorLOperations Committee of any, . unusual operations proposed to be performed on the reactor, J or a'n y proposed changes in procedure. He.shall not1 authorize ~ = the operation or proceed with the proposed changes'until: ~ ' appropriate. evaluation and . approval has been made by the Reactor. Operations Committee,'and authorization given by .~ . ,~

the R$ actor -Administrator.' iThe Chief Reactor, Supervisor; shall ha've the authority;to authorize .anyl activities orz _

r ' procedures which have received prior. approval of the' . . g Reactor. Operations Committee. :He:shall be directly responsible - for enforcing operating. procedures and' insuring that the reactor-facility is operating in.a' safe, competent.and authorized manner ' at all times. In addition,1 he 'shall be-directly responsible for '.the preparation', authenticatiosand storage of all prescribed. ~ - loga -and operating records. G. The' Reactor'. Operators-shall: hold a. valid Operator's , License L issued by the Commission. : They must confo~rm to-the' rules, instructions and procedures for 'the start-up, operation, c and - . shut-down of the reactor' facilities. They must also conform. to the. specifications of the Emergency Plan. Within the . ~ constraints of the administrative and, supervisory controls out ; lined above, a reactor operator shall be in charge of the control-console at a11 times that the. reactor is. operating, ' The reactor ~ operator shall be required to maintain complete and accurate : records of all reactor operations.in the operational logs. ! H. . All other personnel using the facility shall be instructed in the i hazards involved, and given a copy of the laboratory regulations . concerning use of radioactive material. All personnel worldng ~ in the vicinity of the reactor shall wear film badges. - 6.1. 3 Staffing l 1. The minimum staffing when the reactor is not secured i shall be:

a. A-licensed Reactor Operator in the control room,

b. A licensed Senior Reactor Operator present in the l l Leo Engineering Building,

j. c. A health physics - qualified individual contactable L ~ by phone.

l-r 16-57 R ~ l l I , ,J J. ' . _ _ . . . _ _ _s ,, , . . _ , ......,.s_ ._,A_.-.-,,- , . - , _ , . , - - . % ., i v- - - -

g. . - ,

3 n - c .~; ~ I (.h ' ,, ^ -Q T ~ ' -. .'t ^ + - ;~ - -- + 'k.- s f Operating Pers[ >nnel. Requiremsnts , 4 m . ; 2 , . ~ . . . . ^ . a.~ . The c.ontrols of the reactor shall be. operated only , _ ? f(thA rea~ctor; controls 'are to be regarded?as- . ~ . operating 'if thel" Reactor-On't switch is turned to ""ON" and fuel is present in the core tank) with the: i 'spe_cific authorization 'of a Reactor Supervisor. , The' Rea'ctor Operator? shall be. responsible (for-o btaining' the authorizing. signature of a~ reactor - '

supervisor at the top of the check'out sheet. The:

~ ~ W ~ ' Re. actor. Supervisor' signing the authorization is: itheisupervisor "in charge"n

b. lWhenever the reactor controls are operated,ba:

~ ilicensed Reactor Operator'shall be present-and in ; Jt he immediate: vicinity of the console. tan.up-to-date:: ~ list' of licensed reactor' operators lwill be posted . (near ths; reacto'r console. ALperson is considered !'present"fif he is in the console room within view; y of the instruments on the console; .c. A' Reactor. Supervisorishall be present in the Leo -

Engineering Building at' all times that the. reactor -

controls are operated and'shall be cognizant oil th'e reactor l operation at all times. If the, supervisor lin' charge ~of the; operation must leave'the building. . the reactor controls must.either be turneCoff and - . locked or another supervisor mu'st accept responsi-bility. ! The Reactor' Operator shall be informed of such a transfer of authority. - A list of Reactor-Supervisors will be posted near the reactor console. 3.. Personnel Requirements for Fuel and Experimental Loading -

a. Any movement of fuel elements or of materialinto or-out of the reactor core can be done only on specific written authorization of or in the~ presence of a Reactor Supervisor.

' b. At least two persons, one a licensed Reactor . Operator, shall be in the ZPR laboratory when any fuel elements or any exp_eriment is moved in the reactor core. One person'shall be at the reactor console. t e r h 4 . ,  ! 'A, 4- - 16-58 . g *g ) + w , e + ---,er-4a-a-,- -- . --w.,.-. --..#.-< ,,.e--r , , w ' er . . , . ., .m.-mm. e --r -~ e-,..- .,

= --

y7 , _ L .; , - l J- .i 4 ^ s] g4.: , p -

c. LWhenever'-the final fuel-element necessary forc

' attainment of criticality is transferred into the core,7 a Reactor' Supervisor shall be_ present. 1 '

d. 'A Reactor Supervisor shall be present in.the ZPR

= room during the' loading of an experiment into the. core for the first time, 'or its removal from the t ' core. ! A Supervisor 'shall be present in the ZPR room or' give his written authorization for repetitive-insertions of an experiment.- 6.1. 4 : Selection and Training of Personne1 ' The selection, training, and requalification.of operators personnel-shall meet or exceed the' requirements of American National Standard for Selection and Training of Personnel for Research-ReactorsL ANSI / ANS 15. 4 - '1967, or its successor, and be'-in : accordance with the'Requalification Plan approved by the Nucle ar Re gulatory:Commis sion.- T n 4 4 f i ~ l r-l 16-59 ) 1 7 i. " ' N.i jT' * - t J i (_. ., ' .+ ~ s.r -

.3n' +

,:V - j:p 2 "1 . :e 6E21 -Review ^and AuditL - The ' Reactor- Operations Committee shallfperfdrm the-independent ~ ' review and audit'of thel safety aspectsf of reactor f acility>

ope rations,.

~ 6'. 2.' 1* Composition and . Qualifications" - ~ ' ~ LThe Reactor' Operations Committee shall bA compo' sed Ef the - -Reactor ' Administrator' and the. Health Physicist,:- both ex) officio,'land at least three other members having experti.se- ..g ~ in' reactor technology , Committee members shall be appointed ~ - , by thel Reactor Administrator.

6. 2. 2 r Charter and' Rules

< 1.~ The Reactor Operations Committee shall meet atl ':least: semiannually'and more frequently as circumstances ? ~ warrant, consistent with effective monitoring ~of i facility activities. . Written : records _ of its meetings shall be kept. 2 The' Reactor Operatio'ns Committee may. appoint on'e ~ or.more qualified individuals to. perform the. audit function.-- i 6.2.3 Review FunctionJ The following items shall.be reviewed: T

1. . Determination that proposed changes in equipment, .

syste'ms, tests, experiments,- or procedures do not involve an unreviewed safety question.- All new procedures and' major revisions thereto having : ~ F 2. i' safety significance and proposed changes in reactor facility equipment, or . systems having safety significance. , 3.. All new experiments or classes of experiments' that - could affect reactivity or result in the release of radio activity. t 4 Proposed changes in the Technical Specifications or the Operating License, t

5. Audit reports.

k 16-60 l' e k 1, .. _ _ . L - m ,- ., kc . 'h .j- ..d c p

6. 2.'.4" The; Atidit Function.

~ ' The: Audit Function'shall include, selective--(but comprehensive)- ~ examination of operating records,11ogs, 'and other documents. v;- ' The following items shall be audited:

91. Facility operations for conformance'to the Technical

' Specification'sLand. applicable; Operating License conditions, . ~

-at least once a year...

-2.- . .The' retraining and requalification program for.the . ope rating , st aff. 3;: .The results of. action taken to correct those-deficiencies that may occur in'the reactor facility equipment, systems; . structures,: or. methods of operation that affect reactor ~ safety, Tat least once;per calendar year.  ; .4 The reactor facilitp;- Emergency and Physical. Security Plans-and imple'menting procedure ~ at least once every other calendar year. 5 1 16-61 m- --g .. e _ e, r w f- .; 6.~ 3 ~ Procedures . Written procedures shall be prepared,! reviewed and approved . prior, to: initiating any of the activities ~1isted in this.section.' The ~ procedures shall be reviewed by the Reactor Operations Committee -

and approved by the Reactor -Administrator. ' The following activities, not.already described in the Technical Specifications, may be included in a ' set of procedures.

1. .'Startup, operation, and shutdown of the reactor. 'I 2 Fuel-loading,' unloading and movement within' the re acto r.

3. -Routine maintenance of major components of systems j that could have an'effect on~ reactor safety, i

'4 Surveillance tests.an'd calibrations required by the - ~ Technical Specifications or those that may have' an - effect on reactor ' safety. -5. Personnel radiation protection consistent with applicable regulations. 6 . Administrative controls for. operations and maintenance and for the conduct of irradiations-and use of experiments that could affect reactor safety or core activity.

7. Implementation of the Emergency and Physical-Security Plans. .

r l: i-T l. l l l^

16-62 l:

.-= i ~

• s i y

t- . -1 ~ /6[4 '.Expe rimental". Review and 'Approva'l-' - Apprqved laboratory exercises shd11 be. carried out in accordance with established arid approved proce' dure. All new exercises shall be; reviewed by the Reactor ~ ^ f l.  ; Operations Committee and approved by the Reactor ' ~ Administrator prior to initiation. . 2 Substantive changes to previo_usly approved experiments shall be.made only after_ they_ are reviewed by the Reactor Operatio'ns Committee and app:oved by the Reactor Administrator.~ I 1 P i l ~ 16-63 y y # - m 9 - g - - -y 7 -m ' prw4 -p .P y ^ 4 , , s , u& ,y? Q , '6.5' ' Required Actions : s L6. 5.1 %ction to be Taken in Case of Safe't y' Limit Violation: ~

14 The (reactor'shall be ' shut.down a.nd' reactor operations shall

-not be .^ resumed until authorized by the ' Nucle'ar . Re'gulatory_ Commission ~.(NRC)J y 12. , ~ The ~ safety' limit: violation shall.be promptly. reported - ni f to theL Reactor Administrator .or 'a l designated alternate.

3. Th'elsafety limit violation sh'all be reported to:

Nuclear Regulatory Commission, s . . ~ 4.1 A' safety. limit violatiori report 'shall bd prepared.' i The' report,. and any follow-up report shall be , reviewed by the Reactor Operations Committee and x shall be submitted to the Nuclear.' Regulatory Commission . when authorization is sought to resume operation of the reactor.7 The report shall describe the following:

a. . Applicable. circumstances leading to the violation

~ including, .when known', the cause and - 4 contributing . facto rs,

b. Effect of the violation upon reactor facility components, ' systems', or structures. and on

~ 'the health and safety of personnel and the public.

c. . Corrective action to be taken to prevent recurrence.

6. 5. 2 -. Action to.be Taken in the' Event of an Occurrence of the .

Type Identified in 6. 6. 2-1. b and '6. 6. 2-1 c. ~ 1. Reactor conditions shall be returned to normal or. the reactor: shall be shut down. If it is necessary to C ' shut down the reactor to correct the occurrence,. operations shall not be resumed unles's authorized by the Reactor Administrator or a designated alternate. l 2~ . Occurrence'shall be reponed to the Reactor Administrator p .or a designated ~ alternate and to the Nuclear' Regulatory !. - Commission.

3. Occurrence shall be reviewed by the Reactor Operations Committee at its next scheduled meeting.

ss 16-64 q-h ** i _ .5 e - u

, s 5' -

s b ~ 6'. 6' '-.'  ! Reports o - 6. 6. I LOperating ' Reports.- . .; Internal reports- are kept as' minutes lof the. semiannual ' , meetings of the' Reactor Operations Committee. J Reports' to the Nuclear: Regulatory Commis sion' (NRC) are c 1 1 made in response to reports made after inspection by NRC . to the? Reactor Administrator. Reports-to the Nuclear . Regulatory Commission may include': y 1. A narrative summary of reactor operating experience. . , 2 .A description 'of; unscheduled shutdowns including where - applicable, corrective . action taken to preclude' recurrence.

3. c Tabulation of major preventive and corrective rnairitanance operations having safety significance.

4.- Tabulation of major changes in the > reactor facility - and' procedures, and tabulation of new tests.or - experiments, 'or both, . that a're significantly different - from thos'e performed previou' sly and are not , described in the' Safety AnalysislReport,Jincluding conclusions that no unreviewed safety questions were involved.; y , '5. A summarized result of any radiation surveys-performed by the facility personnel.- 6.. A summary of exposures received by facility personnel and visitors where such exposures are greater than 25 percent of that allowed or recommended. ' 6.6.2 Special Reports - , 1 There shall be a report not later than the following working day by telephone and confirmed in writing by-telegraph or similar conveyance to_ Nuclear Regulatory Commission to be followed by a written report that . describes the circumstances of the event within 14 days of any of the following: a, Violation of safety limits (see 6. 5.1), b, Release of radioactivity from the site above allowed limits ~ (see 6. 5. 2). p , 16-65 . , . . . - . . . -.- , - - - , .. - - . ~. - - ^ 1 , l ~w i ; % .. ~# 4 a. -4)' 1 An unanticipated or unc6ntrolled change : in reactivity greater than the: licensed excess' reactivity,L or one dollar, .whichever is - smalle r. 5): Abnormal and significant degradation in reactor fuel,' 'or cladding, or both which ! could result in -xceeding prescribed radiation exposure limits'of. personnel or - . environment, or both. 6 ) T Ad ' observed inadequacy in t!he implementation of. ' administrative or procedural controls such that the' inadequacy causes or could have caused , th'e existence or development of an unsafe -condition.with' regard to reactor-operations. ~ 2 A written report within 30 days to the Nuclear Regulatory Commission concerning the following:

a. Permanent changes in the organization involving Lthe Reactor Administrator, Chief Reactor-Supervisor, or Radiation Safety Officer.

b. Significant changes in the transient or accident analysis as described in the Safety Analysis Re po rt.

c. Any of the following. (see 6.~ 5. 2):

1) Operation with actual safety system settings for re luired aystems less conservative than-the limiting safety system settings specified in the Technical Specifications.

-2) Operation in violation of limiting conditions - for operation established in the Technical Spe'cifications unless prompt remedial action is taken.

3) A reactor safety system component malfunction which renders or could render the system incapable of performing. Its intended safety function unless the malfunction or condition is discovered during .

maintenance tests or periods of reactor shutdown. 16-66 _ .~ .~ y  ; , 7 -

a -

~

+ , k ,

~

l. .

~ l L - / ~ 16i 7 = Records) 4 ' 6. 7. l' Records to be Retained for a Period of at. Least- Five , Years or ^ . for the. Life oflthe'.Componest if.Less than Five Years (1. . Normal reacto;r: facility operation (but not. including' . supportingido'cuments'such' as checklists',J1og sheets, . ' etc. . t which shall be maintained for a. period of at , 'l ' - least , one -ye ar). , ~ 2  : Principal maintenance operations.- J 3.  : Reportable occurrences. 4.1 . Sirveillance activities required by the Technical: Specifications. '5.. .. Reactor facility radiation' and contamination surveys where required b_y applicable regulatio'ns, c 6.. Laboratory exercises performed with the reactor.

- 7.= Fuel inventories, receipts, and shipments.

8. Approved changes in operating procedures.

9. . Records .of meetings and audit reports of the Reactor Operations Committee.

4 6. 7. Z Records to be Retained for at Least One-Training Cycle ' Retraining and requalification of licensed operators:  : Records of the' most recent complete cycle'shall be maintained at all times the individual is employed. 6~. 7. 3 Records.to be Retained for the Lifetime of the Reactor Facility Applicable annual reports, if they contain all of the required information, may be used as records in this section.

1. Gaseous and liquid radioactive effluents, if any, released to the environs.

- On-site environmental monitoring surveys required 2 by the Technical Specifications.

3. Radiation exposure for all personnel monitored.

4 . Drawings of the reactor facility. 16-67 A r- p N v k