ML19224C723

Amend 4 to License R-97 Incorporating Organizational Change, Reactivity Limits & Surveillance Changes & Permitting 2-mode Power Operation

ML19224C723
Person / Time
Site:	Neely Research Reactor
Issue date:	05/30/1979
From:	Reid R Office of Nuclear Reactor Regulation
To:
Shared Package
ML19224C720	List: ML19224C719 ML19224C723 ML19224C729
References
R-079-A-004, R-79-A-4, NUDOCS 7907060098
Download: ML19224C723 (12)

Text

[

\\

UNITED ST A1ES NUCLEAR REGULATORY COMMISslCN

~'

y%

W ASHINGTON, D. C. 20555

{,.

s Wvf I g

j v b a a k @h06h, 6

r df GEORGIA INSTITUTE OF TECHNOLOGY 00CXET NO. 50-160 AMENDMENT TO FACILITY OPERATING LICENSE Amencment ?!o. 4 License No. R-97 1.

The Nuclear Regulatory Ccemission (the Ccemission) has found that:

A.

The application for amendment by Georgia Institute of Technology (the licensee) dated September 13, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the j

Act) and the Comission's rules and regulations set forth in.10 CFR i

Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of tne Cemission; C.

There is reasonable assurance (i) that the activities authorized by this amencment can be conducted without endangering the healtn and safety of the public, and (ii) that such activities will be conducted in cmipliance with the Ccenission's regulations; 0.

The issuance cf this amendment will not be inimical to tne ccmmon defense and security or tc the health and safety of the putiic; E.

The issuance of this amencment is in accordance with 10 CFR Part 51 of :ne Ccemission's regulations and all aopiicable recuirements have been satisfied; and F.

Publication of notice of this amendment is not required since it does not involve a significant hazarcs consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).

o r.

Cy to 7 9070 '00 PP 6

. Accordingly, the license is amended by changes to the Technical 2.

Specification, as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. R-97 is hereby amended to read as folicws:

(2) lechnical Soecifications The Technical Specifications contained in Appendi x A as revised thrcugh Amendment tio. I, are hereby incorporated in the license. The licensee shall c;erate the facility in acccedance with the Technical Specifications.

This license amendment is effective as of the date of its issuance.

3.

FOR THE NUCLEAR REGULATCRY CCtiMISSION h ' I h-f/

Robert W. Reid, Chief

~

Operating Reactors Branch M Division of Operating Re:ctors

Attachment:

Changes to the Technical Speci fications Date of Issuance: May 30, 1979

/ O O kt & n d i!E n d!L J

k 6

w no

~

I i

t I

ATTACHMENT TO LICENSE AMEN 0 MENT NO. 4

' FACILITY OPERATING LICENSE NO. R-97 DOCXET NC. 50-160 Appendix A of the Technical Specifications is revised by removing the pages listed below and replacing with identically numbered pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

5 7

8 Fig. II-1 9

11 13 28 39 q

FJ!g$FjdfOd)u[u@gnnr

~n l

J Nij g

egu wo aha eu

'e r; -

r, e a

1.27 Surveillance Frecuenev - Unless otheraise stated in these specifica-tions, periodic surveillance tes ts, checks, calib rations, and examinations shall be performed within the specified surveillance intervals.

These intervals =ay be adjusted plus or ninus 25%.

Io cases where the elapsed interval has exceeded 100% of the specified interval, the next surveillante interval shall cer=ence at the end et the original specified interval.

1.23 Surveillance Interval - The surveillance interval is the calendar time be tween surveillance tests, checks, calib ra tions, and examinations to be perfor=ed upon an ins trument or ce=penent when it is required to be operable.

• hese tests may be waived when the ins trument, co=ponent, er syste= is not required to be operable, but the ins trument, compenent, or sys te= shall be tested prior to being declared operable.

1.29 Mode 1 Oreration - Mode 1 operation is dee=el to be in effect whenever the reactor is operating at a thermal power level which is less than or equal to ona =egavatt.

g 1.30 Mode 2 Ooeration - Mede 2 operation is dee=ed to be in ef fect whenever the reactor is operating at a ther=al power level which is greater than one =egawatt but not to exceed five =egawatts.

1 l

r

(

t Ob l

i

}

o L

.., ~Q

[?.. a..m

(

,[

\\

y

..g 1-v.

r j

3^

^-[,*'

• +

N.

bd

- bd d

f r

a

-. SAFETY L!MITS IN THE NATU?.AI. CON"lECTION MOLE 2.1.2 APPL!CABIL!~~f This specification applies to the interrelated variables asso-ciated with the core thernal and hydraulic perfor ance in the natural convection mode of operation.

SPECIFICACCN The reactor thermal power shall not exceed two (2) kW, B ASIS no da: age to the core Experience with the C'~lR has shown that and no boiling occurs without forced convection coolact flew at power levels up to two k~a'.

2.2 LIMITING S AFE*Y SYSTEM SE~~ RINGS SYSTEM SETTINGS IN THE FORCED CON ~ECTION }0DE_

2.2.1 LIMITING SAr:..I A??LICA3 ILI~~l Applies to the settings of those instru=ents cenitori:g the safety limits.

OBJECTIVE To assure automatic protective action is initiated before a safety li=it is exceeded.

SPECITICATIOt{

The safety system trip settings for levels greater than one W shall be as follows:

5.5W Thermal Power Reactor Coolant Flov 1625 GPM Reactor Outle: Temperature 139 F The safety system trip settings for power levels less than or equal to one MW shall be as follows:

Thermal Fever 1.25 W

'O~

1 0 >

Reactor Coolant Flov 1000 G?M Reactor Outle: Te=perature 123 F IfI3f y U n v;u m u m s j

i

_ g_

i i

BASIS The : rip settings are chosen so that the reactor is cperated i

i I

with'no incipien: boiling. An analysis was made showing that at 1800 gallons per minute total coolant flow, five MW ther:21 power f

an inlet reactor coolant te=perature of 114 F and the applica:1on of all the engineering uncertainty f actors, a maximum fuel surf ace temperature 8 7 less than the local D;0 saturation te=perature migh: occur. (1)

Operation during the period 1964 to 1973 has de= castrated that a 1000 CFMof th i

f flow trip setting provides for safe operationThe 1.25 MW power trip setting has been chose less than or equal to one MW.

flow.

to ensure that no incipient boiling occurs with the reduced coolant r

I REFERINCE (1) Letter, R. S. Kirkland to USAIC, October 22, 1971, Response No.

10.

TING S AFE'"Y SYSTEM SETTINGS IN NATUR.M CONVECTION MODE 2.2.2 LIT.

APPLICA3ILITY Applies to tne values of safety system se::ings when operating in the natural convection mode.

OBJECTIVE To assure the re.. tor is not operated at a pcwer level suf ficient to cause fuel da= age.

SPECIFICATION exceed

• The reactor ther al pcwer safety system setting. shall not 1.1 kW when operating in the natural convection = ode.

3 ASIS _

In the natural convec:icn =cde of reactor operation the =ain The reacect isciation valves coolant pu=ps are not cperating.

may be closed so that only internal, natural convectica is available

he react:

fer cociing. Experience with the GTRE has shewn tha:

ene kW indefini:ely without exceeding a bulk can be operated at reac:cr te=perature of 123 F.

q -,

q J

l

l f

I I*[

I S *' 7

. 1: a d'

! _g. _. _ _il. -l~ _ )_,.7l1 f

'I f ', i c.

.j: i l,.

't

,a

__ ' _..f..

p

.. ' '. f }f ', :I*

k ' I-f.

l

'l ' !

'=

g

,. I I

l a

g I

e-

,l

.-l-=

.__i : '.... /G.TRR _ S AFE.IY: LIMIT _.. F..O R '

i-

...F s

1. ~j

_i _._iJ-..

O I

.t. '.' !_1 EOR CE D C, C ONVECTiO N L._ _:.!

'h :l: t.1 1-l iTiT1 T.!

}

..[:

.R U

l

1 i 4 l

j

,.l.

i, a

.a

.l

.......q-q i

-~ ; -~.. i,.. i..... l.

.c r b'~ mln :

i

.i..

.r-

.ii e

3

-- S A S E S d MODER ATOR_ VITHIN.12 IEHE5 0..

i.

. : 15 I-T "

I23[?"

HEN

• EOS-EN EIZ~Cl l

Ll 1..__':__!_____L...__[

lIN, 4-1 i- :& 80'a'ER 15 MAXIMIZEDi APPLICABLEi 4 i l.jl

-. +

J N u:. 2.vM.i

.h.n i

. 1 a rv I

1 m

F '--

i.

,. E. 9 i

9

-a e-t-

.i

.l.

.e

1. h L.,.;- t1

.l. 4. t :p

.;. i,,

i r

-l t ;l3 4.. ;.

q l

[

j. 4 i

. :l. _

i

.cj

. L_i h_3.,:-

j 4!

j.

r I

.i 1

_... _____i

~

I 1 1

! i JP 1 e 1: '.l.. T I

?. 7!

l i

I j

l. 3 1 nj p L ta l J i

I i

i L

c.i __

F__ _.__d :. !. +.ll f

,F

_4 l il t F 1:

I i

i l

6 i;

. 1

.l-

1. _... __J i

e t.

I p

i. ::...

j

.l.

l I

i.. - ~I-

~

~

i

.R o...DEPARTUR E..EROM T

f

.NU CLE ATE.! SOILIN G-. _'.$I_I1L E h l_.

M

!_b:..j. k O_._i_.;-

i S

' ' "~ I I'

T

+ I E S "' l

• o Ti i

l c:' _

(.DN S)_LLIN

7. SAFE ! OPER ATIN G i..

F I

.}

m', W

- i +

.;.p + g.

i

.f

-[..f.

. l..[ j..i. d

.[ -lp { G l Q h l-

.; :1

....z. :-

l' l

• O

[ :8

p:.:

i.

l '

I. d d.:..-i, i

F :: 1 l

l...'s-

--F..._d+ d.. I' : h i a-

.l i 4 ;j f,1 p j. j l *.i j

i

_J l ] :! f jr.[ ii'

r.

..___._.__.___..__J..i:.

! 1-

.r.l..i..l. $.ji

_j.

.I_ _,....... _1

i 1 j.:

i

^^

L_

_.n _:

q.

p q...i. :l. :j.l:..

.t.

p-

. -..[. i..l.

{

j r

r -

c

.C

.n. t.

j h.

w I:.

'E P JI l

l

! =1--

l..

I-F. i ' i:

. 3: iI 'i' i.

! o ' t f ^ ll i. j j

u__

r j.

441 i ::p--@ @*

.p.4 q. '

p 0-

[

j

.f :b 4.c.l i, ;._. j 5

.c:[

i-i__

J i

li i

i. NOMIN Al.; 'OPER ATING !

i lm l

?. :,..I li :i.e @ t :l; a:

.. [a. F. 1

. jL

.l

.li T l

CONbii!ONS '

o

'$~ T i

... [g 4 F

...;i:7 'N J. 1..,..l

. h.

.j.

-i q

p.p 4.h.

.p -

I

-l..-

i

,w p.

b.. L.. :p p :.p l: d., a. ; ;,. _

p. m t. ".,.

. j. 7..

i..

e- -- : -- l.

a..

[.h:hi::.{ f h.[. ' I ]: l '['1'"

i;.) h-

[} [

[ ] j j.

1

f. ':l ll i

i J

..j':l-g,-l...f:'_.-l-..

._. gl..'!';

.[.

q.

l

.,i I

i-

_ w:L OPS &HiQ CcW1' / CC -

./.

. ;}, !. a.

. _. l....... ? "

r i.

i

_po...-

l

_j

, TiW//U i

i t

i

- a ---

2500 i

o; ' 500 m

1000

15 C O ECCC

_-.x

., 7i

.. q,/- (, e,. o g,,/

4 p' O.,.. g N, :

r_v, g.

t_ m.

.i.

-"; m i V,i v

i.' t : : = ;~li O. 4 C

', O [

b, k b'n fB 9 A " ; g m

. #j9, *m g m /m.g a

g 7

qG i

~s : r.3 m l

. nl w,:

q. - % e.

e 3.0 LIMITINC CONDITIONS FCR OPERATION 3.1 REACTIVITY LIETS_

A??LICA3ILITY This specifica:icn applies to the reactivity conditica of the reactor and the reactivity worths of centrol blades and experi=en:s.

OBJECTIVE To assure : hat the reac:cr can be shut dcwn at all times and tha:

i r

[

the safety li=1:s will not be exceeded.

I.

SPECIFICATION The shutdcwn margin relative to the cold xenen free critical a.

condition shall be at leas: 0.01 ak/k with the mes t resetive shin-safety blade and the regulating rod fully -ithstawn, b.

The reactor shall be suberitical by nore than 0.0275 ak/k during leading changes.

A shim-safety blade shall not "be renoved frc= the core if the c.

shutdown cargin is less than 0.01 Ak/k with the cos: reae:1ve remaining shim-safety rod fully withdrawn.

d.

Prior to criticality each shi=-saf ety blade which is withdrawn above full insertion shall be pcsitioned so that a free fall of the blade towards its full inserted positica will result in a reaccor scra activated by a negative period scrs=.

The excess reactivity of the core shall be limited to 11.9% ak/k.

e.

BASIS The shutdewn =argin required by Specifica:ica 3.1.a assures that the reactor can be shut down frem any operating condition and will re=ain shu dewn af ter cool down and xenen decay even if the control blade of the highest reactivity worth sheuld be in the fully withdrawn position.

Specifications 3.1.b, 3.1.c, and 3.2.e provides assurance that the core will re=ain subcritical during leading changes and shi -safety t

blade maintenance or inspectien.

a The restrie:1cn on shim blade position fer criticality assures that, of a shi= blade f ailure which resul:s in the shi= blade in the even:

passing through its nernal inser:ica 11:10 te a ;ceiti:n which resul:s in a pcsitive reactivity insertion, a negative peried will be generated by the firs : 10* insertien that will cause the three ranaining shi -

j cafe:y blades to scran.

l 1

I wqw 4

mh)M i L s

m u cen t

qb$bp!i3N0La 3~!0) 3 O'Ulu U h j

a e

TAllI.E 3.1 c.

- a l(EQllll(ED S AFETY CllANilEI.S flode 1 Flode 2 flinimum tio.

Channel

_S e r p_o i _n__t-Setpoint gequired Function Start up (cpu) 2 2

1

!!!nimum contrate permissive rod withdrawal interlock

~

2(C)

Scram Period trip (sec e)

<10

-10 2 *)

Scram -

l Power trip (t!U) 1.25 5.5 2(b)(c)

Scram 1.ow D 0 flow ( gpm) 1000 1625 2

2 ')

Scram

,L liigh D 0 'l eanpe rat ure

(* F) 125 139 l

6-.

3 1

Isolate reactor vessel t

I.ow D 0 1.evel (incFeu below

$12"

$ 12 2

Scram overflow)

Initiate ECCS tio D 0 Overtlow 1

Scram cp 2

E itannal neiam 1

Scram m:_CQ)

MJ lteflector drain 1

llackup scram e JJ g --- -

W.r O Con t a i ninen t iloora open 1 per airlock Scram C.)

1(cactor tuolation valves closed 2

per valve Scram r

1 decade' overlap between the startup channel an h G I} lte<pi t red lur i ng u t ar t up and for operation with less than gi. -a the pico-ainmeter channel.

c==,

{.'-

.'.]

(b)llot resgu i reil for un t e il convection operation w.a s Olie of Ilhe twelve 1esgulfed Safety channels Inay he bypassed [or a period not to exceed O houTS for LO3L,

']

@T ', g) repair

• or calibration J

C",W EDd

{ iR

TAllt.E 3. 2 SAFETY REl.ATED lilSTRillfEllTATIOff REQUIRED FOR OPERATIOri Hinimum tio. Reflu i red Fu n c t-l o n Inntrumentation Setpoint tfode 1 timle 2 f.incar power level nica n u r e me n t a n.1 Pico.umnet er channel 1

1 input l'or t he autom.it ic cont rol mode lIlighbuildini; radiation

<10 mr/hr or 2x normal 5 (a) 5" Alarm and prevents startup SMu Itackground N

(b) y Init.

con t a lnu.e n t isolatton lGaumonitor 1

I H

(b) 3(b)

Initiates containment isolation Y

1 l Filter assembly monitor (b) '

3(b)

Initiates contaisunent isolatton 1

l Kanne chan.ber

}

1(b)

Initiates containment isolation lDuI.eakaletectionayutem 1

y

'}

1 1

Initiates containment isolation l Particulat e monitor Eme r 3;ency coo l i n g;,,t a nk level

<280 gnl.

2 Alarm and prevente startup a

a n

flo D 0 Overflow No overflou 1

1 2

(" Area n.onitors shall he located on the experimental level, the reactor top, in the reactor haucment, and in an area that will he allow changeu in reactor coolant radioactivity to be detected.

(b)

Either channel umy be hypassed for a period not to exceed 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> for test, repair or cal !ieration.

J se

- O r] r\\ D."1 3

. bt ji ) 'j fNk P @ $e)..

3,;g g,a wqqwuu se em 3

g y

, St*RVIILLANCE REOUIRIENTS l+. 0 4.1 REACTIVITf L!MITS_

APPLICA3!LITI This specif t:ation applies to the surveillance requirenents for reactivity limits.

OBJECTIVE _

the reactivity limits of Specifics:icn 3.1 are To assure that not exceedef.

SPECI?ICATIONS_

Shim-saf ety blade reactivity worths and the shutdown margin

=easured annually and whenever a core configuratica is loaded for a.

Prior to which shi=-sefety blade worths have not been nessured.

shim-saf ety blade calibration, the reactor shall be confir:ed to be suberitical in the cold xenon free conditions with any single blade fully withdrawn and all other shim-safety blades fully inserted, The reactivity worth of experiments inserted in the CTRR shall be measured during the first startup subsequent to the experi-b.

ments insertion, and shall be verified if core eccfiguration changes cause increases in experiment reactivity verth which specified may cause :he experiment worth to exceed the values in Specificatien 3.4.

3 ASIS _

Specification 4.1.a vill assure that shi -saf ety rod reac:ivity verths are not degraded or changed by core canipula tions which cause these rods to operate in regions where their ef fectiveness is reduced.

The specified surveillance relating to the reactivi:7 vorth of the reac :: is nc cperated for experiments will assure that extended periods before determining the reactivity verth of This specifica:1cn vill also provide assurance experiments.

that experiment reactivity verths do not increase beycnd the established lini:s due to core configuration changes.

4 h

v,u q i. m ~,.j < t w i pQMp8u 0/ La u ' hLib ud;'pys,i,i

j g,p I >

s f

I

_39_

PFIS!CES'T I

Cecrrfa Tech e

Vice President for Radiolo gical

h. clear Research Safe:v Cffi:er u

Saf e guar., s j

C =it:ee 1

Dean i

Engineering g

I I

i I

Director h'u cle a r En ci"a a ' a e I

1 t

t Director i

Nuclear Research Cente; F.eac:or Super /iser Reactor Engineer i

L Reactor Operating S:sff 9

6 o

_i i

r 'g i

h}

1.

. e.f, f

<i b b b h 'O A U

o-

, o, p.