Text

Proposed Tech Specs for Conversion to Low Enriched U
	ML20215C181
Person / Time
Site:	Rensselaer Polytechnic Institute
Issue date:	06/30/1986
From:	; RENSSELAER POLYTECHNIC INSTITUTE, TROY, NY
To:	;
Shared Package
ML20215C151	List: ML20215C148; ML20215C167; ML20215C181;
References
	NUDOCS 8610100139
	Download: ML20215C181 (34)
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1 i

APPENDI/ c.- ,

1 TO' CACILITY LICENSE NC. Cs-2E TECHNICAL SPECIFICATIGraS AND 3ASES FCP THE 4

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6.3 E x p e.- i ne n t Pevii.m and noproval . .. ............ . . . . . . . . r -- 3 s,.4 Requ. red actions . ................................. . . . 6 *-

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. l u,, . . .-ro T ?. e ter ns Gafety Limit (SL). L i m i t i ne; Bafety System ie t + . .; !~hi 2

. 2 n - t i ng Condition for Operation (LCC1 and Leveillar.ce Recu . r y " .it: . - a d + r i c.e d in 50.36 of 10 CFR Part 50.

A. Ch.senel_Calibrattqn - The correlatton of channel a.tc..'> te .c.

input signals and cthe- known pa areters. C a l i t. r a i tra m.

Pr.:ancass t h e- entire channel. including equtamen' ac + 12 :c Ge- tciO.

9. Channel Cb e - t- - Cuolitative deter?.ination of acceptab M :p s . 1b : 1 .

y Yaservation of i ns t ru.ne n t behavio - duc i rq opccation. Ir ;

'T .h e determination shall incluJe. where possible, co.opartsco instrument with other independent i ns t r un.c n t s .-rancuring f. n - w. . n .:- .

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s. triable.

C. C_h a n ner l T. s t. - The i n ..t ec t i c n of a s i rnu l a t e d signal into the i r.s t r ueren t primary sensor to verify the pioper irstrument r ~ s p o n +c-olarm ard/or initiating action. -

D. Control Roi t Assembiv -A control mecheniqm consistino of a stainless steel banhet that houses two absorber sacticos. a t ie boe:

the other. These absorber sections may contain e i t h s: i enriched borun in iron, EuOr, in a stainicss steel cermet, stainless steel, or an alley of silver-cadmium-indium. All a t.s o r b e r sections e v e.up t the one containing silver-cadmlum-indium are clad ir stainless stenl. All are of the same dimensicos, ncminally E.6 in: hts

..qu a r e . With their poisons unif c e ml / dis tr ibu t=d . The abscrboc .

wher fully irserted. shall extend above the tcp and to wit'h:n cs inch of the bottom of the active core.

E. E,xcesc R o -a c t i v i t _. - The availab}e reactivity abo.e a c o l .i . Isar .

critical configuration which may be addad by manipulation .f ccatroin.

i F. E c c e r i ent'.t - C1' An a p o et r -a t u e . device, or material 7> ! .v:ed 1i ' N. .

resCtCr /ff s c e l . 6.nd/or (Ei any operat(On designet tc m a a!.a ,

, reactor charatteristics.

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G. r!.% s w i n q C!%r m i - Tt e noi^a ivu t i cit c - sencer . < < , :, , -

cc.c c tput devices which are connected f or the mcan

-no a sus titg t h e. value of a proctcc . a e s a t. l e .

H. Mo s.a r er d Value - The v a l os- inf the procesi ' a r i ai. ' e -ic --.-er .

02 the output of a .neasuring channel.

I. ljo.nble E rw r i mati - A movable e ': p e r i me n t. :s one i. o.- .

r~i t e r i e l may be i nser t ed , removed. or manipulated w: 1+ .

rew-tor is ccitical.

'. Cporab{3 - 4'. sy n t.n.n or comoonent ts capable of peri:cmi m .t ;

i, tended. function in its required manner.

b. Goeratino - (i 1vstem or comoonent is per f ormi nt; . t e, i n' t e nd e' f u n.: t i c n in its required manner.

L. Rpartor Sa f e t_y _Sy0 t err - Combination of safety channels 2nd associated circuitry v.hich forms the automatic protect;ve ., y 6 t s a for the reactor or providos information which reautrec wanual protective action to be initiated.

fl . Reactor 9eral - A gravity drop of the control rode at.c o mp a n i ed b, the opening of the moderator dump v a l v r= . The scram c .:n be initiated either manually or au to.na t ica l l y by the uafet. afsten.

N. Feartor Securod - (1) The ful1 insertion of al1 ortrc; rods has been verified, (2) the cons. ole key is removed, and '. 3' :o operation is in progresis 'ehich involve; moving fuel e l w r i t t. in t'M reactcr vessel, the .nserticr cr remc.al O f pn =er :c en t , r eca the e a c t C c vessel, or control rod -na i n te na nc e . .

O. Poactor Shujidown,- The control rods ar e fully ira'-tsd , nd the rESC ter :n shutdown by at least 11.00. The eactor i2 c. ; 15 ! <1

e u to b ee cperating whenev er this conditicn 13 ric t .n s

and i.;c - r '. h 3 i 60*/ of the total nurt b e r of fuel pins required for c r i t i ': s 1. t ; .

, gaven configuration (Core A cr Core 5) have bce: loade ! tn t: . ,

coro.

C. P.'adi1y Availablo on Cal 1 - The Ltcensed Sen ct Operator t i.30 ) or duty shall remain uithin a 15 mile radius or 30 m i iu t e .3 t r a .'o 1 time of the faci 1it/. wh t c h ev e r- is closer. a col 'ne .

0:wrator-On-duty shall know the e.vact l o c a t ; c r- .I n d t e l e n h a r.J number of the LSO on tlu t .

C. Figl,o r t ao l e Occurrence - The ccctic r 3.ics of sin , fa :11t, c a nd i t i a r-that:

1. C ai i wi a L i cii t i ng S a f e t i. 5 .< s t n . Setting tc e c =+ t: e .n t* . .a eetstl.sted in Esctror 'd o .' t .* o r ec t ri . c 11 Eae. t ft

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E:'cGEC9 ei L i T11 C I n g tiOnc3t10n 'u- 13;_e' .:i .; es -i t e+ts i >* ($ .

S c .; - i u . . 3 af the T e c t-' n i c a ; -3 4 -: r . C . si t ac 1:

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Cauces a r. / .mc o n t e c i l e d or unp l anr.ed re le ne ;+' ;d i _ s ,

c.a t e r ; a l from the restricted are6 of the fac'l.' -

4 Results in safety system component failurns <hi:' c o .. : e _

threaten tc. render the s y s t e:n incapable cf ra # ..i; .t intended safety functin as defined in the Tech 11:21 Specifications cc SAR;

5. Results i ri abrormal degradation af o r:2 of the se<er;.

caundaries which are designed to ce s it a i n the radivur' .:

nate-ials resulting from the fission processec;

6. Results in uncontro1 led or unaaticipated changeu ..

reactieity of greater than $ 0 . *7 ^.i :

7. Cau".;es conditions arining fron na tur al or offsite monmata everits that affect or threaten to affect sz.f e oper a t t o r. cf the facility, or:

R. Results in observed inadequaciec in the i mc i ernen t a t io n Of administrative or procedural cont.21s such that the inadcquacy causes or threatens to cause the exactence or development of an unsafe conditton in connection with the operation cf the faci 1ity.

R. Review and Ajig_r o v e - The reviewing grcup or person ahalI ca ry cut a review of the matter in question and may either aporove n-d i aappr ove it: before it can be implemented. the mattne in cuestion must eceive approval fran the r e v i e." i r ; g cup ;c puson.

5. S a f e t', Channel -A measuring channel in the coactar ,afety Systen.

T. Ger ur er! Experimer t - Any experimen'. e::per i men t a l facilitv. or c o rnp o ne n t of an e>.periment is deemed to oc securvd. ce t . .i Grcured cosition, if it is hvld in a stationary ccs tiar celati m tc the coactor. The res raining forces must te equal ta m greater than those nhich hold th; fuel eleeists t : ie.r.e ! e t t! the reactar core.

U. 5_curce - A r.eu t r o n-em i t t i ng ~udioactive A:,t e e : a l . O th .c than reactcr fuel, which is pos:t;oned .o or near the an ser.b l . tc pro.ide ati external source of -uutron:.

V. Su r v e i l l anc e Fr om e-c_c -- Un l e s . cth- wisc statcd to t h r.e

'i o G C. i f ! C a t i O f' s . OeriodIc G uI v o i '. l a nC 9 IOsIG. Check 1-t a l ib e'a l i C as . aild examinctions ShalI b. 'Pr r i .r e d w l t)t . the sCeCifiad kur ve i l i arc.e i n t G r V I.1 b . 1a case % 'd G e L P' e i' I J O C .e d i ti tP+ 'al h39 e :'. c e e d e d 1 a0' . of th*- sc?ctf.e1 nto al. *he +

t 9ur>di11anCE i n t ti r v a l shal! C 0.nmerC @ at tho n ^*' t't1 QJ .J'-al

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. Five-/-ra- ( : n t c e'-a '. not to e : c i2 e d si- ccAr= .

2. Two year (.nter<a1 not to e cc ?d two and ce9-' 1 =

3. An. aa l (:nte. cal not to e<ceed 15 montis .

4 Somi a nr iua l inte, val not to e rc ?ed S r e -E ! ) cod :r -he:

.cnth s >

5. 2: ar ter iy (irterral Tt t exceed four e.c n t % ' .

6. M e r.r h l y (interval act to e :ceed si" .:e ei s ' .

'. Wek1y rintcrval not ta exceed te n dass: .

8. Daily (must be dono d u s- i r g the calendse % rf .

W. Survei11ance Inter va1 - The surveii1ance i n t e r v ril is the ;a1endar time betv.een surveillanc.e tests, checks. calibrations, a r .f examinations to be per formed upon an i n > t r uer e n t o. :omsonent w h t- '

it is required to be operable.

/. True Vaby - The actual value at any instant of : ococcus cariable.

V. Unseruiod Egeriment - Any e >.p er i men ; . e ,- p e r i m erit a l facility. or c o mp o .'e n t of an exceriment is deemed to be unsecureed if it ts nat and when .t is not secured. Mo v i nc; parts of e cper i mes:ts are deemed t0 be unsecured when they are in motico.

a.O 3 .;9 T v t ! M i T 3 PJID L i M i T f Nr, 'if.FE T Y 5 '5TE'd SETTING 3 E.1 $afety I.imitt - Ccce E n e c a', Dergosttion 1

@ciicabt1ity fpplies to the amount of energy inserted in + h i. ;oce L: .

elther noen al operation o '- cransisnt affe;ts.

Cb3ective T c, identif, the ma eimum er.eegy deocs; tion alice.ec :r: it,_ - c2 - -

curs. above v;h i c h matarial degradation of t h r4 f ue '. and a: i '. i c i o;1d : r.g is e :pec ted .

Epecification Energy depasition in the fue1. resulting from no c.a i opv. a e i .a n or transient effects. Ghall be limited tc no more than 33'i : a l .'y U C ., .

E a s e_s E :m er i mer.ta t i o n regarding reactivity initiated <.ic c i d e n t s i-iight water reactors has identified energy depositico in the fuel to t; e the sinule mOtt impcrtant variable. The specification bere is a value which identifies the I cne ; t threshold for failure o f unir r ad i.a ted SPERT fus! obserso:1 in coactiv: tv i n t t t ea t ed accidents. To excocd this t h r a s.h a I d :: 'Sc RPI LEU Core would requiro a total energy depos'. tion un tna ci-Jer of 2.2 10 kJ, er more than a factcr of 10* gee tec than tnot incurred in the SAR design basis a::ident.

2-2 2.2 Limitino Safetv Svstem Settinos - Reactor Power Applicability Applies to the settings to initiate protective action for instruments monitoring perameters associated with the reector power limits.

Obiective To assure protective action before safety limits are enceeded.

Specification The limiting safety system settings on reactor power shall be as follows:

Maximum Power Level 135 watts Minimum Flux Level 2.0 counts /sec Minimum Period 5 seconds Bases The maximum power level trip setting of 135 watts on Log Fower and Period Channel 2(PP2) correlates with a reading of not greater than 90% on the highest. scale of either of the two Linear Power Channels (LP1, LP2) as established by activation techniques. These scram setpoints ensure reactor shutdown and prevent significant energy deposition or enthalpy rise in the core in the event of any credible accident scenario.

The minimum flu > level has been established at 2 cps to prevent a source-out start up and provide a positive indication of proper instrument function prior to any reactor startup.

The minimum 5-second period is specified so that the automatic safety system channels have sufficient time to respond in the event of a very rapid positive reactivity insertion. Power increase ard energy deposition subsequent to scram initiation are thereby limited to well below the identified safety limit.

3-1 f3.0 LIMITING CONDITIONS FOR OPERATION 3 '. 1 Reactor Control and Safety Systems Applicability Applies.to all methods of changing core reactivity available to the reactor operator.

Obiective-To assure that available shutdown method is' adequate and that positive reac'tivity insertion rates are within those analvred in the Hazards Summary Report (hereinafter safety analysis report).

Specifications

1. The excess reactivity of the reactor core above cold, clean critical shall not be greater than 5.60. The maximum reactivity worth of any clean fuel pin shall be $0.20.

, 2. .There shall be a minimum of three operable-control rods.

The reactor shall be subcritical by more than $.70 with the most reactive control rod fully withdrawn.

3. The maximum control rod reactivity rate shall be less than

$.12/sec up-to 10 times source level and $.05/sec at all higher levels.

4. The total control rod drop time for each control rod from its fully withdrawn position to its fully inserted position s h a~1 1 be less than or equal tc 900 milliseconds. This time shall include a maximum magnet release time of 50 a

milliseconds.

5. The auxiliary reactor scram (moderator-reflector water dump) shall add negative reactivity within one minute of its activation.

6. The normal moderator-reflector water level shall be established not greater than 10 inches above the top grid of the core.

7. The minimum safety channels that shall be operating during the reactor operation are listed in Table 1.

8. After a scram, the moderator dump valve may be reclosed by a senior reactor operator if the cause of the scram is known, all control rods are verified to have scrammed and it is daemed wise to retain the moderator shielding in the reactor tank.

9. The interlocks that shall be operable during reactor operations are listed in Table 2.

10. The thermal power level shall be controlled so as r.o t to exceed 100 watts, and the integrated thermal power for any consecutive 365 days shall not exceed 200 kilowatt-hours.

e-

3 -2 TABLE 1 Minimum Safety System C;aannelv.

Minimum P . t r. t m' Conditions - Pances Channe1s Number ~unc . io. t 2 ts: * - 2 cp*; - IC" cps . Lug Count Pate' 1 M i n i;nu r .,

'Jp Le<01 i % . << : 10 ' - 1 5 0 ". L.inear Power 2 High NN t re

_ t=. v e l Scian

- 10 7'

- 3 0 0'~ tog-N Period'"' 1 Neutron evel Indication Period Scram Manual Scram' > 2 Peacter 5ccam Building Power 1 Less cf Power Reactor Door 1 Roa: tot-Scram'< Scram

' 'ilas b ++ byp..wed when 1inear power channels are FrMdino arcater than 3-X 10 ' ' ' ar p s .

' Dur i nc} theady-utate operation. this safety channel m a ',, be bvpassed l

with the permi<;ston of the Operations Supervisor.

4

The manual scram 5 hall consist, of a regular manual scrum at t h .,

console and a manual electric switch which shsll dtstunnect the electrical power of the facility from the sa; tor, c at' , i n '] a lu so cf p e t. se r scram.

' ' Th e reactor door scram may be b y p a *-i s e d during mair.tEnance CtPcks ari radiation surveyG with the GP3Cific permicGICn Of tiro Up 9: a t 10.14 Suce: cisor provided that c.c ather tcram channels or e b yr. as u>J .

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Interlocks 4 I

. Inte-locks Action if I n t e r- luci fic ' L?: . i ' 0 :'

4 Feacter C .: n s c i t'eys (E) "On" Reactor Scram- i

[

4ea:tc c Periad 15 vec'+' Preven t.s Ce n tr o l Rud : S d c .ur 1 I

'buteon' Flu. E cps Prevents Conteoi Fod W 5 t h d c w. .. .

i I :#ailure af 4C0 Cycle.Eynchro Prevents Control Pod w i t he r .:. ..s a l ,

.~ o a~ n= u p a ,r v L 4

Fet lure o f Line Vol tage to Prevents, Control Pod W& thdr;wal l

i Ho or:n s t

e clo Jer a t o r-Re f 1*rc toi Water Fi11 On Stcps Uater Fi11

' a ter Lc.ei i n Reactor Tank 10 1.1 "

. Prevents Control Rod W i thcir awa l j f.b c s e Cere-Top Grid i

4 4

i i

l

'These inter lock's are available on only 1 of the 2 i_og-N cor lod l Mp l i fier s and. therefore, may be bspassed with the permi2sion cf t h .a i

j CpfrLti0nb SupersiEOr if that one a.mp1ifier is otit of uer.ii.c. .

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3-4 Baseq The minimum number of three control rods is specified to sseure that there is adequate shutdown capability even for the stuck control rod condition. Normally there are more than three control rods available for shutdown capability.

The insertion time of less than 900 milliseconds for each control rod from its fully withdrawn position is specified to assure that the insertion time does not e >: c eed that assumed when establishing the minimum period in Specification 2.2 as <

limiting safety system setting.

The au:: i l i a ry reactor scram is specified to assure that there is a cecondary mode of shutdown available during reactor operations. The requirement that negative reactivity be introduced in less than one minute following activation of the scram is established to minimize the consequences of any potential power transients.

The normal moderator-reflector water level of the reactor is established at not greater than 10 inches above the top grid of the core to assure that the moderator-reflector water ducp, back-up scram will introduce negative reactivity within the time essumed in the safety analysis by loss of reflector at the top of the core.

The safety system channels listed in Table 1 provide a high degree of redundancy to assure that human or mechanical failures will not endanger the reactor facility or the general public.

The interlock system listed in Table 2 assures that only authorized personnel can operate the reactor and the proper sequence of operations it performed. It also limits the actions that an operator can take. and assists him in safely operating the reactor.

Limitations imposed on core reactivity. control rod werth3 and reactor power preclude conditions which could allow the development of a potentially damaging accident. The limitations are conservative in view of core energy deposition, yet perntt adequate flexibility in the research and instruction for which the facility is intended.

3.2 Peactor Parametern Aoplicability These specifications apply to core parameters and reactivity coefficients.

Gbjective The ourpose of thece s p ec i f i c a t i o ns: le to assure toet the esc ;or is operated within tha range of paremete.s that have bee: anal.ned.

i 3-5 s

Specif_1 cations

1. Above LOO"F the isothermal temperature coe"ficient of reactivity shall be negative. The net pos:tive reactivity insertion from the minimum operating temper ature to the temperature at which the coefficient becomes negative sha1 1 be less that $0.15.

2. The void coefficient of reactivity shall be negative, when the moderator temperature is above 100 F, within all standard fuel assemblies and have a minimum average negative value of $0.OOO43/cc within the boundaries of the active fuel region.

3. The minimum operating temperature shall be SOoF.

Bases The minimum absolute value of the temperature coefficient of reactivity is specified to assure that negative reactivity is inserted when reactor temperature increases above 100oF. It is of note that even in the worst postulated accident scenario, such as considered in Section 4 of the SAR 3 reactivity insertion due to temperature change would be negligible. The minimum average negative value of the void coefficient is specified to ensure that the negative reactivity inserted due to void formation is greater than that which was calculated in the SAR.

The minimum operating temperature of 50oF establishes the temperature range for which the net positive reactivity limit can be applied.

3.3 Radiation Monitorina Anclicability These specifications apply to the minimum radiation monitoring requirements for reactor operations.

Objective The purpose of these specifications is to assure that adequate monitoring is available to preclude undetected radiation hazards or uncontrolled releases of radioactive material.

Specifications

1. The minimum complament of radiation monitoring equipment required to be operating for reactor operation shall include:

4 e 3e e

.i . -A cr . t ical i t- dstector systet which mcr: ', . . 'i n s.

. fuel =torage area and aluc functi'm. :

., s o .z x..

Thin system snall ha.e a "isible and /> n -M : - 1- ..- .

tre 20ctrci room.

.h . An area gaima a monitoring system wh i c r .hai' . i a . cs de t e c. t o r s at least in the fclicwing l e c c- t 0 : : :

Centrol room: (2) Peactoc room near the r u_i -au l ' - .: .

Reactcr econ (high le.el mon ter'. J. n d : ' . 3_' .S ;he (Cactor room V. i nd O W .

r. . I .'s t r u.tc- n t s tc continucusly c.r.p l e and n.o.a r s r o t-parti:_ulate activity in the reactnr u cia a t . u -O shall be operatir.g whene'.er the eac ter .4 to : e operated.

d. The endial. ion moni tor s required by 3.2.1 a. .. a q:1 c.

.nay be temporarily removed from ser. ice if repluced cv an equivalent portable unit.

2. Fortable detection and survey i ns t r urae n t s shalI be c~ovided.

Bases The contir.uous monitoring of radiation levels in the onctor room and other stations assures the warning of the existence of any ata no r ma l 1 y high radiation levels. The availaht1.ty oT instr uments tc measure the amount of particulate activtl in the reactor o c in air assures continued c oinp l i cinc e a t ti. ti:e requirements of 10 C R Part 20. The availaaility of equired pc t ab le- inoni turc provide assurance that per,annel will be abla d

to monitor potential' radiation fields befor- an acer it e n t e r -e J .

Ir all cases, the low poWor levc1s encounter ed in cperatior of the critical assembly minimizes the probable e ; i s t e n t s.: cf b i g" radiation levels.

3 . :< Escertments 4p1icabiIitv Thew specifications apply t r. all esperiments ;- l a c + d .n t r. e

'ooctor tant.

Ot i e. c t i v e_

O b se e

. 8 g .

Crite.la fOr ehpe'iMents to assur-s th9 s a f G l 'y Of the 9.ic t C F ><;

pCescnnH1.

1

t

, 3_-

a l

Sc ~e f : c a t . c n s.,

1. i!: n ev, e x.p e r i m e n t shalI be performed unt.1 .

procecure wnich has oeen deseloced to permir gu J underc.Canding cf the safety . asp ec i: s is e e v i e .s j c,: 1 3.. _ +

m .

by the fiuclear Safety Revin Scard and s o p r e s e. . ' _,

Ocerations Supervisor. E , p e r . .n a n t =6 that fc1' . ti c- g -a!

categcry, but with ainor deviations #rcm those p. ?. ;

2 ce-formed, may be acproved dit ectiv by tN 'h. e ' u t ; ,

Supervicor.

1

2. Na experiment shal1 ba conducted if tl.e asscc:a .+c ' 4 2 :per 2 eental equipment csulc interfere sith 'he c:c 4 1 functions or with the safety functicnc cf the nu-1 u:

instrumentation.

3. For .r.o v ab l e e v.p e r i me n i. s with an absciute wceth gieate. ' h ..s n 5.35. the maximum reactieity change for w i -hdr awa l anc incertion shall be 5.20/sec. Moving parts v.o r t h l e n. t'-aa .

$.'95 may be osci11ated at higher 'recuencies i r. the car;.

e. lhe ma :: i mum positive step insertion of reacti, t, u:ich c. 2 :

tr e caused by an experimentai accident or e pectm27tal equipment failure of a movable or unsecured e..:eriment s h .3 ! .

= not exceed 5.60.

'i. E,:periments shall vic t contain a materict v:h i c h c.a t, produce ;

icient chemical reaction and/or significant airbar c.

r ad ic,ac t i v i ty .

, a. E .:per imen t s containi,g known explosives- - righly fl mat le l materials shall r:c t be installed in the reactcr.

y 7 All emper2ments .sh i c h corrode easily and are . . cEntact ." 1 "

the reactor cociant shall be encacaulated Mith r c ci c 21 o .-

resictant cantainers.

3. The radioactive material content of any 9t.igly 2 n. a a ..-u ' . t a : .

e ..p e r i me r.t shal1 be 1imited ,uch that th2 complete , aleacc of all naseoua, p ar t iculate er sciatile cum;u n m : alre_ 'v i to the .eactor room wi11 not cesuli tn e.:pc sur es ;n : -c e t of 10 */. o f the equivalent annual t+ x cusu e s stated i ii '. 'O CFC RO for persons re nai ning 11 u r.. e s ' . c t ed a.eas 'vi * -c not w ..

<d ?.

or i r. r este ic ted a i =r a s due tng &h> 1ongPh of '2 V 's!

. ' i eeatuate the centric:ed area.

7. 'he i d i o <sc t i v e matertal c o n t 'P n t .f an c:i u b i _q1 os a la t.ed experi.wqt shall be 1:~ ted :.u c h tt.;* thu ocst la'_c.

O c ;r.p l e '. o relesw from the encap?u;at1 '

.: cu' '^ ' w i n .. .

a .w i t > :;. c - u : -

1; l

baundary c the e > c e uw t . auld mt i c~cas; uf appl c,a l e 1'm: ' c. in 10 F TP 3? u

a. ;. '.. c i ;

ic C . ? V i nrj an ' 4'

2 .i t r 2 c t O d 3 .' l a ~O:~ti'U Ls!, f' r6' . Od 11 f

mo tio u 4 f: ,e the t i m.;- c' ealease. ac en e .c -

of applicable '. t .~: '. t s .a 10 CFO So for p M acii ; .. ..

he res tr ic ted acea during th? leng tt- af '.u+ _-

c eeacua*.e the restricted a r e.i .

E a c, n s .

The basic experiments to be per for med ;n the r- a .: m .; 2 -

are described in the Safety A r.a l y s i 1; Poport (SAF'. The p ,o t pronrams are eriented towar d eactor cperatct tr e ir . . . 9 instruction of students, and with such research a x' '4.p4 v as is permitted under the terms of the #aci1it '. I t e : .c. ",

Ausure that all experiments are well planned end e .w ; ;; ':.s c pri_i to being performed, detailed ra r i '. t e n p r o c e .j u r es fcr .l. c+

enperiments must be reviewed by the N5PS a r.d apptOvmf m, tM Cperaticos Supersisor.

Since the control r o d =, enter the c o r te by gravlI, lod are required by other technical soecifications tc be operable, nu cquipment should be allcwed to interfere with thei: f une Llcnc.

To a s,s u r e that specified power limits are net e .< c e e d e d , the nuclear instrumentation must be capabla of accurately munitor :ng care parameters.

All new reactor experie.ents are reviewed and approved prior to their performance to assure that the e:;per imen t a l techniques a r.d procedures are safe and oroper and that the hazards from possible accidents are minimal. A maximum reactivity change is established for the remote positioning of e<pe-imental samoles l

and devices d ui- i ng reactor operations to assure that the reactcr contrcle are readily capable of controlling th.* reactor.

Al; experimental apparatuc placed in tne reactar musc be occperl/ secured. In consideration of potential accidents. t. N reactivitv effect of movable aoparatus must be limited La the ma,imon accidental 2tep reactivitv insarticn a n a ; , c.e d . Thi ccreesponde, to a $.60 positive step while operat.ng at f u l '.

power followed b/ one failure in the reactor safety syst*m.

Restrictions an irradiations of explosiveu a r.d h ig' l > f t .m. 2 b i c.

material =: are imposed to minimite the possibility -f e :: a l c - i t. n cr f i r e e. in the vicinity of the re ac tor .

To minimize the possibility of exposing facilit' m rsonnel ac the public to radioactive materials, no exper. ment Jill t;e performed ,,J i t h 7.a t e r t a l u at could result .n e . i c l -al i *- chea '. a l eaction. produce airbor.- 9 c *. i s i t , . or cause a cc. os: .- e a t t a; ,

Cn the fuel claeeing or u r t ,r. , r v c c. o l a n t r utmn.

.c _ .-,

y _ ,7

.I 6

-e

)[

QCjf1[dk On3 3I.b

d & I * '

. . .. .- . .._ _ _m_. .. a ..-- ...em.....+,. .; s ; n t-;

d C 10 at '.1 ' w - s u .s % w i am4L wwi+~a+**-~ - + - - - - -

5.M C h th6L Lheit f.3 i i t r G Wi11 0:3t (G3 git i! ti .po lut 9- *0 todividual: in rees t r i c t ed cr unrec.trtetsd areas *a ir : ; . s . .: -

, -t+:

M Ja r. ! r:Um al lO' Jab le E' .: 0,2 C u r G s stated in 10 CFR 20.

. 'i 'r. . +

rea 'n.a : imum iu die f i nvad' i n 10 CFP .0.10; and 1.; C 0 F.; ~'s--

ancestricted area en a r. i mum is def ned in 10 CFR ' ' 15 '

a: , i .i r-

,U

3.

. . ;' ' UF'/E )i_1 ANC ___P E DU 7 p r q g 7 3

" 0.?., c t a - Control _and nafet.

+ .'. 7

[go1icabi1ity Theue sp ec i f i cis t i o n s applo to the curve!iiance s' t .ar - <

controI apparatus and instrumentation of the faci!..,

Ob _i a; t : <e The purpece Of these speci#ications is to assure t h .s t :: -

and cortect equiomant ic cperable and will function as 4; c.

in Specit'icatica 3.1.

Specificat: ens

1. Tite total control rod drop time and m a g ite :. release t..ic.

shall be measured semiannually to verifv that the requirements of Specification 3.1. Item 'i , er e tro t .

, 3. The moderator-reflector water dump time snali be moeisurea semiannual 1y to v e r i f;. that the r equ1reinent o f Specifirati2.6 i

3.1. Item 4, is met, I

3. All instrument channels, including safet/ sycter. chinnels.

sha11 be calibrated annua 1ly.

4 .4 channel test of the saf e t;y system c '7 a nt :e l s (intermeciat3, and power range instruments) and a /isual inspcctica c '- ths reactcr shall be performed datly prior to re.ctcc ,tartuo.

The interlock system shali be checked to satisf f rcd dr, o permit. These sys te ns shall be ochecked following a shutdown in excesc of 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months .

5. The- moderator-ceflector water height shall bs chw t =d

/isually beface reactor startup ta verif, that th requirements of ;pecification 3.1. Item 5 are . .u t .

6. These tests mav be wa:ved when the instrument. :c n p o a r.t _

system .s not required to be opeiab1e, but the 1 m F ru nont.

component or syst:-m shall be tested pricr t. b e i r ';, d i c i a.'55 d o p e r .ib l e .

Eas05 Past aurformanCu Cf cCntrCl PCd5 a ns] C,nt el r <_ d nr.,"M and ti;e SOderatCe-rOfl9CtOr Water fii1 and dMc valve s '. L t s:f r !! i .' 5' d e m o n c,t r a t. e d t*:a t t a c t i. n g cemiannuall. : --. Keat.al e u w.E camp 1iarce .;th 5;; er. i f i c a t i a n 3.I 1tems 3. 4 e .7 d 5

t_ . . . _ _ . _ _ .

d J .

i e y .;

i 4

e i '

i 'l icual * ,no,ecticn c'

. the .eattar componert . . r. . - '.:. .

e co a t, c . rocc. pr ice tc each d a *, ' s o; er a t t o. .. .;

e=:u r ' a '.

' the esmpcnents have not been demagud c. c d that the . _ , 4 . - --

l p r :;; c r ecnditicP. 9ines. radundancy of all n.fet, ch . - i. -

+

l prosided. <andom failures should not jeopardize inv a + .t

' * ,0 the everal'. system to perform. i t c. required f u r.c t i o , . i

'~ ' '

j. iiiter loc; system for the resctor is designed sc '

i .t .t- a i ple_es the system in a, safe o' non-operating . c r u t '. : i. ;

.i Huwever, t c- assure that fail res in the safet u au . = s- i

! inteelock system are d .e t ec t ed as scan as p o s s i t, l s , f w't ,

! 'aurvei11 ante is destrable and thuu specified. Al. .: J: . -e i oroceduras are senumer a t ed in the d a i l ;. ntartup ch u > 1. : .

i Past experisnce has indicated that, in ccojunctinii a i '. " L :w daily check, calibiation of the e.a f e t y c h a tic.e l s arnusil. A s -.c c ; ,

! the proper accuracy is maintained.

4 .2 Re.2cter Paramete g l

i Applicabi!ity These sp ec i f i c e.i t i c os apply to the ver i f i c e. t i o n of c o a l.c a l rod L

reactivity worths, temperature and void coefficients of i j reactivity, and reactor power levels which are pertinent to the l reactor control.

i.

Objective l The purpose of these specifications is to assure that the l

analvtical bases are and rema6m valid and that ths eactor i =

safelv operated.

5ppc i f ica t t o r.s :

r The following parameters shall be deter mined during t. h e in . a '.

Lesting of an urknown or previ-Jusiv u n '; e s t e d co e .a r f I q:. a t . - .

a. CentroI rod bank reactieity warth:

u. Temperatu.e and scid coefficients of eacti. s:

c. Reuctor power mer sur str.r n t :

d. Shutdown margin.

Daces :

Measurements of the above are parameters nado whet e ww reac tcr .

configuratice is assembled. Whanever the core configuratiar i; !

a 1 t o r e:' .;cr.iidcrabi., to ait un1 ncun cc un t o t t c-:: ; c a f i g u . a t i ci n .

the core carameters are evaluated t, w i.u r a that theu a: r.: . *r .

O

. ..m'ts

. of thPse spr.c 1 + ic a t i c.n ot'd tb- u1 c 7 -- v29d .>> j I i

, _ _ _ _.__. .._._ . _ . _ _ . - . _. - . _ . _ . . -- _ _ _ . . =

t :

i I

> , ~:

j i

,! the lop. During the- nitial tesi perioc of the 3.. .sr i measueements a r.d calculations of c o r e- puametaes .s i t . A j c. t ~. nd a r d assembl:en which are tc be uttii:od in tr. --

l u p er <1 t i c n a 1 progeSm. i i 4 . '3 PaJia.ica l'on i tor i no l % c 1 i c a b i 1 : t s.

i These specifications apply to the <=urveillar.ce of '~ ar-; ., n d

tir radiation monitoring e qu i pir.e n t .

1 4

u5!cmtise The purpose of thetse specifications is to asc.uru the cc: c . eX

salidity of radiation protection standards in the faciltty.

i' Spec:fication i The criticality detcttor cystem. arua gamma moni tc rs , and the mcbtle particulate air monitor shall be checked dail, if the eactor is operated, tested aonthly, and calibrated l cemiannually.

i ,

E a s e s.

E per:ecce heis demonstrated that calibration of the critical;ts detectors, air gamma monitors, and the mobile air mon i tc:r i ng i ns i. r umer i t semiannually is act eq ua t e to asture that s:gnificant ceterioration in accuracy does nct occur. Pur the rna r e , t r a:: l cparability of these r acl i a t i o n monitor. it i nc. l ud ed in the 17: -/

., r e-s t k t ua check list.

f Ii h

I r

1 b

6 l

e ww ww , - , . ....wrww,.. . . .

..v---m. - - , , . - . . _ - - - ~ ~ - - ---- - - - - -

~ _ - . - - . _ _ - - - - -..---- . --- - - .-. . . - . - - - . - . _ - -

-J- '

e. ,,, ;. : . m, . c- _ r, m.p~e c .

c. . s. c. ,

t * "

The f a c i l i ts, is loca,ed on i t. t t e situcted c ., 5 -- 'r '

s :

the Mahav.h Riser i r; the City of Schenectady. i. , i w: I n . '. - .,

greater than 30 feet radius defines t h e r iis t. . icted - co i ; t c. .

fencs and c ver bant of greater than 50 feet r .rc i .. s mf.n the !

exclusion area. l f

es . w. . : ,w.. 1 . g e, .

The fac.iity is housed in the reactor building. The c :' c. u . .- ' :t~ f the facility . s maintained by the ace of two fencas: one at :w !

L t *. e ocur.dary and the ather defining the .estricled a r e .. , c o .d ,

t ~. e reac tor buildinc itsel#. -

l

\

6 i

O 3 P_.w: tor Room l l

TI .c- eactor room is a 12 inch re s i n f c. ced corcrete e r . l o c.ur e- w: tr sppro innte floor dimensions cf 40 K 30 feet. The he:ght f c.n the

ground floor to the celling shall be about '30 feet. Ths coo" i s: e l steel d e c l. coverad by 2 inches of light .v e i g h t conc efa cc , fise piles of felt and asphalt. with a gravel surface. f,ccess to tht:

sac tcr ecen is through a sliding fireprcof s t ere i dcor 9 h i c. 5 41s.:

tantains a smaller personnel door. Near the centur of the r a _ .i. is a pit 14.5 X 17.5 feet wide and 12 feet deep with a floor af IE inch concrete. This p .a r t contains thc- 3500 gallon water ctorag- ,

t a n! and Other piping and a u >.i 1 i a r v e q u l'a ' e n t . [

I

'f . . ' J < ,3 c t n. .r.

3.4.I r:eac tor T a n t-The st6inioss steel 1 i 'md cerc tot t,ini hau a c n ac t' : i t

aanroximately 2000 gallons Of w e t e. c . Tha t# v1. a. i dimensions are 7 feet - diametec a 'd feet n t a' T:n !

t csnk iE suppDetOd at flCor lev 9l abd Y t r. e O.M J. - . I i

3 tnch stcel ! beams. Thtve ar.3 oc 9 de i "= ; t 4 1 u e the (Gactcr (a n' . .

The rea<ter t an! ts acni tec ted to the :atar s to- agr ta- .t j

<t si' inch QU ! C 4 dudp l i i .e . -

Therec ace. it ;: recui ze t n a '; l tbG StoraGP tar.k be /0; ted t r. the 3 *. m L t . C, h 2 : ' '? 9. u . I . ' hat 5 :.

- +

k ga i Cm/. b [3 ) . 1,,. I d I -

9 -b *

& g 'W

}'. C 1 m m.sry 5 % G t 3 tit .

l 4

.a =

5. I . E - Pc a.-

c c C,0ee The r e ca c t c r cce shall wisist of ucaniva Fv t . ..=> .

the farm of 4.9 w/c enrichad UL pelletL -

.3 ; e 4 ':: d-steel clad. arranged in rcughly a :_ y 1 1 N c . _ 3 . =s';; ..

four cocitral rods placed symmctrically abo . r's periphery. Fuel ptrs, with an affective .. q S- ;'- in inches, are net on a r,quare pitch o ! . 4 H ".M ~ i

.-le 3 r-e#feCtive Core radiuG cf sp f F C :: 101 t e 1 y 25 cP ~.' .:. c.-

arrangemer.ts are provided fcr . The I r i t . e r v +-' .s av

" Core A", ts the so1id array of'ci u shczn . F;j A . _i : T the SAR. The second. eferred tc as " Core E' .c r-annular array of pins shown n Figuie 4.4 of "e ~UJ . t 'h-pins themselvec are supperted and posi+io.ied o' c ael _

support plate, dri1 led with 1 'c inch diametec N.1 % .

accept tips on the end oi each pin. The wooct t s l a t. e rests on a carcier plate which f o r :::s tire t, a s s, v' a three-tiered overall core sups.o r t structuce. An opp e fuel lattice plate rests on the tcp plat 2 anc cath c. e e dr.lled through with 1/2 inch diameter holes on thu p r esc e i t,ed pitch to accommodate the ucper endw Of the f u e l ' p . r. c . The lower fuel pin support plate. a middle plate, and t!w u p ,.m -

fuel pin lattice plate are secured with tie ads and bolti. The entire core structure is supp2rted v e r t i c _i l l :

and anchored by four posts set in the floor cf the eactcr tank. Finally, in the e v e n !. the fuel pins ar e bowi+d t;u t s t i l '. satisfactory for use in the coce. a p l a s t. i c scacer pleite may be installed on the middle plate. Figure w.6 2 .-

the SAR depicts t h e- to tal cc' e a f s er.b l ,.

E. 's .3 Fur.1 Pias Fuel pins to b+ util:.:,d are 4.3 w/o enriched SF'ERT/" :

f uc> l rods. Each fuel rod is made up of s.in:ered U )

pellets. encased in a stainless steel tube, cscped oc .. '

ends with a s t a i r. l e w. Steel can and neld t:> ple.e .tr ,

cFircmium-nicie1 upcing. An aluminum oaide 'AI O insulatar between the fuel pellsts anc s i: a i n l e s e c :: s e l ram on each end of the rod is installad. Gar gap _ le accommcdate fuel e"pansicn e. s also p r o 'c i d e d .4 t L c. L P !!w upper end and around the fuel peilete. Pigo a 4 . cf r. %

S4P depicts a single fuel pin :t o d its ps e it.ler.t dimensimr..

'i . /* .a Contrpl 90d.M ~4Gbiies c our centrci rod a s s.amb l i es are i vtali/. tpacee 00 degree % npar t at t h re core per1phe;,. EaCI "1 CC:.EL9'% .'

a 2.'5 inch :c c u a r e stainiss . s te ol t .b = wh ch 13 s '3 c +

c thrOugh IP 9 CCre inJ r e t. t c an - h ed _ o.21 i c b.'P' 22 th.

r.*. o t t a': c e r i t- r p1 ate of the 4.up a c e t ,

7 .tc t ; r & . A.u29; a OSC3 0i these " b a u l. P t '.', a i* G tWO & 5. .-h-' b O .- ' s h I .. 'i. e :'

'~

Cec *.On2 OFe c01 t' 'ri .? the O L i .; - :E ._ 2d . i

s e..*

Figure a.5 of :he SAR. The 13 ' pe i sn .:ntoni ,

sosorber section is held in a s ta itila=" s ': = .0 1 m. '. 'P,'

is also clad with stainless steel. Eac4- r .~ v han app r o v i .r a te l y the same raactivits ef+s;+. 4X R ;.

nuclear cliar ac ter i s t ice, are detelled lata i ..

The drive mechanism for each asscmbly ccrei.'. cf . : m/ ; c. .

and gear box coupled 5, a magnetic clu tch to W r; :c a: 1 pinion attached to the top of the rod #com an ;,erhe-3d cantilever mount.

5.5 '.ator j Handlinq Sy= tg Tho water hand 1ing_ system a1 lows remote fi11 n1 and uc.p t / t ng C' the reactor tank. It provides for a watee dump by mean; of a 4' sil safe butterfly-type gate valve when a eactor sc r air is i n i i: t a t s'l .

The filling system shall be controlled by the operatcc whc :ru s t s a t i c. f y the sequential interlock system before adding water w 'he .

tanL. A pump is provided to add the moderator-reflector water

. from the storage dump tank into the reactor t a r.1 . Slow and # a t. t f r. l l rates of about 10 gpm and 50 gpm. respectisely. are provided. A nominal siv inch valve is installed i r. the dump '. n o and has the capability of emptying the reactor tank an d e m.a n d of the operator or when a reactor scram is initiated, unless bypaswd v.ith the approval of the licensed senior operator on duty. A v e. l v e is installeo in the bottom drain line of the reactor tank tc provide for completely emptying the reactor tank.

5.6 F u e l_ S_tp r a c;e and Transfer Whea not in uso, the iuel pins shall be stored 'ti thin the e.to age vault located in the reactor room. The vault shall be closuJ b -

locked coor and shalI be providod with a crit 1cality em n i t o r .S : -

the vault door. The fuel shall be stored in cadmium clad . teel '

t u'a e s with no more than 1 kg fusi per tube .nc o n t ed on a : a+ + . . is t 1

. cact: . The center-to-center spacing of the storage tubes tu g w *.n ,

with the cadmium clad steel tubes aucures that the inf t i.i te multiolication factor is lesa that 0.9 when ficoded with wats: .

All fuel tcansfmes shall be conJucted under tha d , c e - ' t i- r et .i

.tcensed senicr operator.

Operating ce.sonnel shalI be fami1iar witP he.a l t b ph.: icG precedures and monitcrir.g t ec h n i q .: a s and s h a l '. x.c : . . o r the op3 ration with accropr i ate radiation instrumant4tinq.

Far a completely unknown or untested s y s. t cm , fuel l_adieg shall -

f C l l '.t w the i n's er CO multiplication acc r o ac h tl !~itica!.tv a!;d.

thereafter, meet 9pecificatior 4.2. 51.e u ' d ar, ster uptic,n a#

the lcacing c c t:u r !mcre the fa tr dass'. a l '. 'uoi m i r iu . '. s e cr~p' the initial icading cteo shal be r on.c = d frur tPc c r. c c 1 i c e se, s e CQQuince ind thG c;!*C a l ic O r9peatEd.

g..__._...___..-_____

e b

i ;

1 . l

(

5-..

?

Cc- a k. i . a w n systen, up tc a rtuadr an t of o!=meit- n.c. s ':-.

i l ,

'rnn the cce.e er a single stationacy fuel p i c. ce ria ' sc r. '.'-

a c.e the r Etat moary oin onl, urajec the fo l i s w i ne; ._. t. ..c.u i i--

4 t t i

1. The 7et ,-hange in reactt,tt, has bean pre.icu i ta '._r - - - ! O !

measurement er calculation to be negative Oc l e2 s ti e . 1.'O. {6

! 2. The eactor is cubcritical b. at least 11.00 :n e a : !. i . rs . l i

i I

3. Tiiere is iaittally only one vacant pas.itico n t t h' n the a c < i ,, e (

i fuel lattice.

I 4 Ttm nuclear i r.s t rumen ta t i on -ic cn s c si l e a r.c the uu.c ,si : te

! not tJ yp a s s ed .

B i

_ 5. The critical iod bank position is checkat a f' t e r tN coeca ice- 6 is complete. l i

l l -I i i i t f -

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6-1 6.0 A6MINISTRATIVE CONTROLS 6.1 Oroanization 6.1.1 Structure .

The organization for the management and operation of the Reactor Critical Facility shall incorporate the structure indicated in Figure 6.1.

Level 1: The Director of.the Critical-Facility is responsible to the Provost, via the chain of command, for. conduct in accordance with the facility license and for requisite site admininistration.

Level 2: The Supervisor of the Critical Facility is responsible to the Director for operation, maintenance.and management of the facility.

Level 3: Licensed senior operators are responsible for daily reactor operations.

Level 4: Licensed operators are the operating staff.

The Director, Office of Radiation and Nuclear Safety shall be a health physicist who is organizationally independent of the operations personnel depicted in Figure 6.1. It shall be his job to advise the Supervisor in matters

'concerning radiological safety. The office maintains inventories, provides consulting services, responds in emergencies, and conducts inspections in support of safety efforts. The Director of this office also has interdiction-responsibility and authority.

6.1.2 Responsibility The Supervisor of the Rensselaer Polytechnic. Institute Reactor Critical Facility shall be responsible for the safe operation of the facility. He shall be responsible for ensuring that all operations are conducted in a safe m'anner

and within the limits prescribed by the facility license, j including these technical specifications.

I j In all matters pertaining to the operation of the reactor and these technical specifications, the Facility Supervisor shall report and be directly responsible to the Facility Director, i

l.

6.1.3 Staffino a) The minimal staffing when the reactor is not shutdown

, as described in these specifications shall be:

1) An operator or senior operator licensed. pursuant to 10 CFR 55 be present at the controls.

2) A licensed senior operator shall be present or readily available on call.

. 6-2

3) The identity of and method for rapidly contacting the licensed senior operator on duty shall be known to the operator.

b) A list of reactor facility personnel by name and telephone number shall be readily available in the control room for use by the operator. The list must include:

1) Management personnel.

2) Radia, tion safety personnel.

e

3) Other operations personnel.

c) Events requiring the direction of the Operations Supervisor:

1) All fuel or control rod relocations within the reactor core.

2) Recovery from unplanned or unscheduled shutdown.

6.1.4 Selection and Trainino of Personnel The selection, training and requalification of operations perrannel shall meet or exceed the requirements of American National Standard for Selection and Training of Personnel for Research Reactors, ANSI /ANS-15.4-1977, Sections 4-6.

Additionally, the minimum requirements for the Operations Supervisor are at least four years of reactor operating experience and possession of a Senior Operator License for the RPI Critical Facility. Years spent in baccalaureate or graduate study may be substituted for operating experience on a one-for-one basis up to a maximum of two years.

6.1.5 Review and Audit A Nuclear Safety Review Board (NSRB) shall review and audit reactor operations and advise the Facility Director in matters relating to the health and safety of the public and the safety of facility operations.

6.1.5.1 Comoosition and Qualification The NSRB shall have at least four members of whom no more than the minority shall be from the line organization shown in Figure 6.1.

l The board shall be made up of senior personnel l who shall collectively provide a broad l

--3 v o e t i n.n. ut o :per .ue to i .+ -a c : , ,:. s_ '. . .

Qualt'ied aN a p a v .-d a.t2 , .vs . w ths .b u arec e of gu ai- i..A- 'c.*.

E.1.5.2 Charter and Rulos The Oevtow Eocrd shal1 fu r:: t i a .,,- t following rulec:

a) The Chairmar. c' thu t! IRS ib s ' t:e 4;c 0 by the Faci 1itv Director.

b) The Boa-d sh.1. moo

at . 9 :e :

semiannua..t4y.

ci The quorum shall corsist of in t leas 1na -

a ma.jority of the ful1 Board 12 vs.I aoclude the Chairnan-ar hts d e a a g r. 3 t +J alternate.

d) Minutes of each Board meeting rib. a t i be distributed to the Director. NE B rr e nta a u .

and such others as the Chair.ni.e. m. s v designate.

6.1.5.3 ik v i r-w and Approval '3u nc t t o. .

The following items shall be reviewed and approved before : .r.p l eme n t a t i a n .

a) Prapcsed e x p e r i me n t s, a c.d t e t. '. c u t i l :

i .1,;

the reactor faciltty w:i t ch -u +

s i g n i f i c a n t 1 s,. di f fereat f. c:n tests c. x e <per 1:ren t s prov laus l', c c r f o r m ut' 3L LW facilitv.

b) Reco table co urences.

c) P.cposed changes tc the T ac hi : : .: a i l

Specificatins and f. c o c e s e d amcMm a t P. -

I faci 1its 1 i "_ e n s e .

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o.l.5.4 Audit Fianc t i o n The audit functicn shai1 3: i 1w -el e : t /-

I (b t compiehensive' c .. a m ; r c. t i c : cf .:pr a t i n..

c .? c C r d G . logs. Snd C t h e .- d u c a.at:n t . 3e necessary. discussione m: .n ::;i,.:a.it p ra r 50 a t :e 1 t,h a 1 1 take p13ce, [? i.o ir_ e na1*

Ih9 5 'OiV1duS1 1 mate d i a ! 21 ^~ O r.6 0 '% 1 ! I O ~ 2 PI ?

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6-4 a) Reactor. operations and reactor op er .a t i o n a l records for compliance with internal rules, regulations, procedures, and wi+h licensed provisions; b) E::isting operating procedures for odequecy and to assure that they achieve their intended purpose in light of any changes since their implementation; c) Plant equipment pe-formance with particular attention to operating anomalies, abnormal occurrences, and the steps taken to identify and correct their use.

6.2 Procedures Written procedures shall be prepared, reviewed and approved prior to initiating any of the activities listed in this section. The procedures, including applicable check lists, shall be reviewed by the NSRB and followed for the following operations:

1) Startup, operation and shutdown of the reactor.

2) Installation and removal of fuel elements, control rods, experiments and experimental facilities.

3) Corrective actions to be taken to correct specific and foreseen malfunctions such as for power failures, reactor scrams, radiation emergency, responses to alarms, moderator leaks and abnormal reactivity changes.

4) Periodic surveillance of reactor instrumentation and safety systems 3 area monitors, and continuous air moniters.

5) Implementation of the facility security plan.

6) Implementation of facility emergency plan in accordance with 10 CFR 50, Appendi: E.

7) Maintenance procedures which could have en effect on reactor safety.

Substantive changes to the above proceduces shall be made only with the prior approval of the N3RB. Temporary changes to the procedures that do not change their original intent may be made i with the approval of the Operations Supervisor. All such temporary changes to the procedures shall be documented and subsequently reviewed by the Nuclear Sefety Review Board.

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t n , ; 1 -m an une>< towed safety quectit ., s h -11 -

Nu c le .c Gafety R s v ; e t.: Ecard. il5PG encca s% 1 a.4. .

c o rc '. i w 1c e tc the e equ i r en er. t s of the It; n , ; -- *~!.. t-g.9:ificaticos 2 P' a l I be documented.

2) Sabstan ive changes to prev'ouil, appi o md e .. . 1 i h .:. . .

be made only after ' e v i c .-s a 7d a.a p r o v a l i c. # "-

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Mtrcc c ". a nc e s that dc not signific ett alt.n ..m _ - O t- ee<'

m a ,- be iOprGvec by the Operatlan- D, c t- r -. i 5 0 : .

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Apprased pperimelt9. s h .n 1 1 ce carried cut .a n .ci 1 - t.

established .a a p r c v e d procedureu.

f' Friar to cevievi, an e <per imnt p l -i n or u opa mil -n.ils t>

repared deo: ~ibing the experiment ircluding an v. e, * ..

c a r t i d e r .a t i c ns .

5, Review c c.nmen t s of the N9PO settina foith any c o n d i t i c r.1 and/or Itmitations shall be documented .o c c mm i t t. e t miin .:- -

and submitted to the Facility Director.

n.e Peauired Actions 2.4.1 Ac t i <- n to be Taven in Cane of Safets L i c. : Violations at The reactor shall be shut dowr, and reactor operat:u.w chal1 not bo resumed unti1 au thor A c ed t; ' the i:c : 02:

-"Egaaa Cry t C tr.m i s s l o r i .

bi The cafet, limit violuttar shall be p .' -d

t. h e level ore authorit, cr d e s i g a a t c-d ;x 2 N to .1 _

to the NSRB.

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c' The safety 1tm:t violaticr shal. be 'opartud to 1 clear Regulatory C c a.m i s s i o n ic acccedan. It-Section 6.S.3.

d) A safet f 1 i m i t- vtalation r ep c r t, r. t '. I t v -, ,

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. c p c .- t shall das cibe t r. e f o l i v. . i . .g :

1) Applicatle :tec artances laadi>g % .ie ,.cla t ic:.

InC1uding, Wher l 'O t;n , t e C a fa 'l ia GFd C ', t ', t

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10 2; c u g r. t to c a =.u m e ope ation OT **9 . eact .

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2 ) Feactar c a n d t *. 1 o n s Gh611 be cetur d t; ; . 16

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operations chall not bc cesumed unless au e_

the Ca c i '. t t s Directcr cc d e n i g r.a t e d 21 e- *

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b) Cictur ence shall be sported tc the Fuc: 1 . e . ._ :

cr designated s i ': ec r n-s t e s and to &m c a .n . . i s -

required.

c) Al1 cuch condtticnc, . r.c l ud i ng at: t i o t te en t r. c r t-or reduce the probability of a recurrence, chal. be reviewed by the N3RE3, t.5 Pen.-ts In a d t t t t o ,1 to t- h e app l i c.1b l e rcpoiting ? :u i ca ent s. c TitIc l_

r e. , c r t s Cas of Federal Peguistions, the f e l lo w iiig i d e : t i f i :.M umil be submitted to the director of the appropriate 9egtenal O '~ r : c e of Inspection and Enforcecent unlets otherwise .attu.

.S.! O. .n e i a t i o n Pecor t .

I, rencet covering the c r a v 1 : u r. y e a: th il1 'J i - Tubm._. >c March . af each year. It shall include ". h e tcilca; . . .

a) Oppeations '; u m m a r , . A p :mmar , tf 2perat:ng e- .s c Occur r i ng during the epcrtina periec that a l n .; c ' . _

he s d f t.- L p tf r a t i di n C T' the ' .:s c i . 1 t y . i ~l, j; 1I Ch it nc O 3 In #aC'1't/ design * .

3} PC r #C r e? ..'.t ic e charSCter;stic3 l. ?.g. 2 r, _. 's . i t . _;

fuel perfo Tance:

3: EM 2n jes in Operating pccced.we. M.d. : lote ': ;. -i,+

Eafetv cf Iac 1it, . p e r .-21. O r- !

4} EGsult'- Of survci;larc: t e"; t t .snd ' ' c J e c t 1, r9 Quired b '. th9EO I9Chni;31 5ccc;f i c3t, . 3*

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. 6-7 6)- ' Changes in the plant operating stsif serving in tre following positions:

a) Facility Director; b) Operations Supervisor; c) Health Physicist; d) Nuclear Safety Review Board fleinbers, b) Power Generation. A tabulation of the integrated thermal power during the reporting period, c) Shutdowns. A list ng of unscheduled shutdowns ahich have occurred during the reporting period, tabulated according to cause, and a brief discussion of the preventive action taken to prevent recurrence.

d) Maintenance. A tabulation of corrective maintenance (excluding preventative maintenance) performed during the reporting period on safety related systems and components.

e) Chances. Tests and Experiments. A brief description and a summary of the safety evaluation for all changes, tests, and experiments which were carried out without prior Commission approval pursuant to the requirements of 10 CFR Part 50.59(b).

f) A summarv of the nattire. amount and maximum concentrations of radioactive effluents released or discharged to the envir. ins beyond the effective control of the licensee as measu ed at or prior to the point of such releass. or dischargi.

g) Radioactive Finitorir2 A summary of the TLD dose rates taken at ths <clusion area boundary and the site boundary during the reporting period, b) Occupational Personnel Padiation Exposure. A summary of radiation exposures greater than 25% of the values allowed by 10 CFR 20 received during the reporting period by facility personnel (faculty, students or experimenters).

6.5.E Non-Routine Reports a) Reportable Operational Occurrence Reoorts.

Notification shall be made within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone and telegraph to the Director of the appropriate Regional Office followed by a written report within 10 i

6-9 dar, tc the Director of the Regisnal CFf1M 'Me event of a reportat;1e operational c c c .n -

.c ? u. ;_. rx_

in Section 1.0. The wettten r e c. o r t un t%--- e c

, c '; ra i a operational ccCurrences. and to the . '; e : > ac+.=. . :.:. .

the preliminary telephone and telegcach' ne .

f - . - :m shall: (a) describe. analyze. and eva'.u.e sa ~1t imp 1ications: (b) out1ine the measurre tat . + ' *t.

that the cause of the condition is de te. rair'1:

indicate the corrective action s i nc l ut ! 1. u;. -i .t.. . ,e s made to the procedures and to the qual 1: . e a e c.c a p:ogram) taken tc prevent r2 petition of tre .:u- soce and of similar occurrences i r.v o l v i r.c, similar r. c e. : ., ' a n t -

or systems; and (d) evaluate the safet/ i in:: 1. c a ' . s f the incident in light of the c ,.;rr u l a t i v e e r.p e c i e a c e obtained from the record of previcus failures , r .;

malfunctions of similar systems and c ompc ne ri : 9 . '

b) t)frysual Events. 4 tr i t ter. iepart shalI be f o r .4a c h d within 30 days tc the director of the appecpriate Regional Office in the event af- 15 Dis cvery af e r. y substantial errors in the transieto or accident analyses or in the methods used for such analyses. .:

describec in the Safety Analysis Report or in the cas;t for the Techntcal Specificatin_.

e.5- Goeratino Rrcordg 6.5.1 The following records and logs . hall be maic.tainr-d at tna Facility or at Rensselaer for at least five /sa. c :

a) Normal facility operatica al.d maintenar.ce.

b) Repertable operational occurreaces.

r_ ) Tests, check, and measur emen ts dc c u.nen t i ng c n a l i c : c c-with survei1 lance recuirements.

di Pecceds o f e:< p e r i r.e n t s cerformeJ.

el Records, of radicacti.e shipuents.

6.6.P The following records a r. d logs , hall bc ma i n L4 nc- d a* 11:e Faci 1;tv ur at Ren;;sslaer for the 1ife c1 the Faci 1;* .

a$ Caseous and licuid radioacti/s ~eleas% fram t h --

f a C i 1 1 t ', .

.: ) 1LC En _ .r. 2 .

21 e y ac:- net ficittor. cay be m- on t n +2 ~. r2 : t wcM ing da. te trt o.i t 4;e F A t, '. e c o o r 2. t l a r a ; c c c _. c 2 n c e daring c fee: e^c ,- - .id2 4:ac t oc .

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c) P.viiation e <posur n for al! hoi C . t . _. a i 1

personnel 8ctudents, e x c e r i .r e c. t e r s i .

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i d' Fuel inventottes, offsite tr ns.fer ,

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tramsfers if they are not r e t u r .m e e. ; . o j c o r c- o r vault location during.the e w e. .o. : <- a in which the original t c <,nn f e r . s a :; .r. a c -2 .

c) Faci 11ty radiattore and c on tami na t lai. w se.,.

f ') The present as-butIt faci 11ty draw;ng, and ,e. .y; d .3 t arj cr corrected v er s t (,ns ,

g) Minutes of Nuclear Safety Re,iew Board mr e '- < .g a .

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Gr'E.REACTER CRITICAL FACILITY OPC-ANI Z AT IOt!AL STROl~ii d1.

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c T;1 DEAN, SCHOOL f5,, OF ENGINEERIt1G d 0 OlRECIOR, OFFICE OF PADIATION AtlO M N<JCLEAP SAFETY 55 N

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h m a m m m mEEtsa m 1 ENGINEERING AND SCIENCE d F4 3 fj m t DIRECTOR OF CRITICAL FACILITY 12shm .na .., O wa; N a -

U 3 Yi SUPERVISOR OF CRITICAL FACILITY NUCLEAR SAFET'y y REVIEW BOARD d

m LICENSED SENIOR REACTOR OPERATOR (SRO)

Ila LICENSED REACTOR GPEPATOR (RO)

Figure 6.1 i

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