ML20083J998
| ML20083J998 | |
| Person / Time | |
|---|---|
| Site: | Neely Research Reactor |
| Issue date: | 09/11/1978 |
| From: | Marlone Davis Neely Research Reactor, ATLANTA, GA |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML20083J996 | List: |
| References | |
| NUDOCS 7810030015 | |
| Download: ML20083J998 (15) | |
Text
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GEORGI A INSTITUTE OF TECHNOLOGY-ATLANTA GE ORGI A 30332 r
raaws M httav
- Ltaa arstamen ctwtsa Septe-M r 11, 19-'E U.S. IU: lea" iiec;1 atone Cox.'ssion, Fegion II
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i h is letter is n re:ponse t: you" ins;+:: ion rep:r: dated Auras: 2 3, 1 ~ -i, mga"iing an inspe:ti:.n of or facility t*,
you" sta'f.
Tne p5_ ti-~ath designations correspond to those in you" repsrt.
Written procedams for oreration of ey;eriren*d facilities
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A new proced.:N, desigiated 10. 3' 1, " Operation cf Dperim ge.. m..a_ _,....:......=--..:
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c e:ber 7, 197c. Eis procedre ine:morates the defieltion cf " Kin:r boerirent" and outlines the steps fcr using those experiren:C facilities n:t already covered t'y ey.isting proced a. es. A d"a*: copy cf the app" ved procedum is enclosed witt, this letter.
B.
Ibnthly masu"e en: of shi, roi d" p tim be schadaling for routina jobs such as the shir. rod drop tire reasremnts is dona using a mster calendar. Syster. Work Sneets (Procedum 19'C) are to 60 the work. Ze prepa"ed in advance and set to the app"opriate tt.1:
failure to perro:r. a reasure ent on rod drop tire in June,1975 was attributed to oversignt on the par. of the assiped work group and a lack of fellw.:r te vari.S' that schaduled mintenance wo"k was ccrpleted, base m ters wen discussed by the Ibelear Safecaa-ds Co r.ittee at its Septert>er 7,1975 reeting. %e Com.ittee requarted the follwing action:
1.
Caution all personnel responsit,le for perforing s:*eduled mintenance wark of the irpo:.ances of ccTleting the work in a tirely re.ne."
and forwaading the doctrentation pro::ptly. Tnis has been done.
2.
Institute a rcre vigorous ra.apmnt review and follw tr of stredaled Eis work so that appropriate a :!cn can be taken prior to me deadline.
is now inderwxe.
7810030015 PDR ADOCK 05000160 PDR G
aclear Rega1Etcrj Cc rission n
e2 j:e Ber 11, 1973 C.
Diily test of cen dn inr rrer.' channels r'
P-icr to discussior.s with yer stEff, we believed or daily che:Ps of sre cf the instrren: circuits wc e Ede: ste to satisfy the opcmting cau
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of a circuit.
Accordinsy, we have revised our Procedre 2303, "Inily Sts-tup Check List" to in : pora:e e test of the for inst. rent circuits.
21e te:ts are identical to th:se E1 ready perfered under ou-Procedre 2312,
" Week.ly Precritical S;E u; Check List." Tne revised Procedure 2033 ws.s reviewed arri app-oved by the N;;;es-S eged Comittee on Scptex>er 7, 1975.
A d at copy is enclosed witt. this letter.
D.
Pae'. Hind 11 E Pr: red re Yor inspection rap:rt 7E-1 identified as a. u. resolved iter., ou" 6:edre 1502, "Pael Handling in the Core."
Tr.'s 6:edre was recently revised to in:c:p: rate a criterie for neu'.r cor.ter o:.e-aillit:. and otner cr'te? L for terl.nating the rcverent of fuel. 'It e revised heedre was reviewed and app-oved by the Nu:ler Saeg as-is Cc rittee cr. Septerber 7,197E. A drel't copy is enclosed with this letter.
we believe we have responded to all cf the rette-s in you" inspection re;crt. If you would like to discuss a y ite. ir rcre oe:. ail, p'.eise ad.-ise re.
1;: n e c f tr e enterial we are subritti.g is proprie.E y.
Ve:j tral yours, j
!}Y 0,0M Fonte V. Davis Director K.'D: dr.
En:Iosres: D af:, copies of Pr.ocedures 1532, 2003, 3101 cc: Na:1ea-Safegaa-d Corrittee w/o en:losures T.E. Stelson, Vice President /Reserch E.E. Tenfro, Director /CCA L.E. Weaver, Dir= tor /S:hool of N; lea-Engi.ne-e.-inc W.F.
Sangst er, Trean/ College of Ercineerinc
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GEOK01 A TECF. PESE ARCr. REACTOR
- r. apter Procecure
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Approvct
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OPERATION OF EXPET.1 MEN ~A;. FAC:1.ITIES c.,,dary Systems pa g.e1 cf I
P'.73$E To assure safe and efficient operation of the experi, ental facilities of the CF.R.
2 This procedure applies to the use of the fc,11oving f acilities:
A.
Eorizontal bean ports T.1 through F.10 except E!.
j S.
.U E.
Eorizontal bes port E4 N.
C.
Eorizontal tangent tubes Ell and 12 p
't.
^g Vertical In-core positions V21 through V25 i.
E.
Vertical graphite positions V33 through V46 Note: Procedure 3050 covers operation of the Eio-Medicci fa:ility and Procedure 3100 the operation of the Pneumatic Transfer Systen..
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Approwl for use of the experirantal f acilities vill be a co:pleted l
"hequest for Approval" (forr.II(3-65) delineating the details of the experim nt.
Note: An approved cajor experimnt vill generally include specific operating and handling procedurcs.
Definition of Minor Enc riment
)*inor Experiment is a term applied to a general class of experiser.ts which require approval only by the CFh r:nagement and the Office of Radiological Safety.
Any irradiation of non--fissionable, non-explosive c.aterials which vill not evolve hazardous gases t.ay use the pneut.stic facilities or the s ta tic irradiation facilities if, in the estit.ation of the CTJi t.ar.a gemen t, the follo ing specifications are met.
Specifications
/.. The potential reactivity worth of each secured re:.ovable experir.cnt should be less than 0.006 4k/L.
If this value is exceeded, epproval of the Nuclear Safeguards Con itt ee vill be obtained before L.~.c e xpe r i r er.t is perforu d.
L.
The t gr.itudc of the poter.:.c.; rear. tivi:y of each uniecurd e xpt rit.cnt shall bc lee + t!.ar. 0.002 Li/L.
E.
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GEORCIA TECH RESEARCh REACTOL
,..nspter proCCCute '*,1Q1 l
-- 5 Approved Lates E e'v.' "
t xilsery Syste=s O?EMT10:;5 0F EXPEL 1CT AL TACII.! TIES foe 2 cf 5
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t C.
The rate of change of reactivity of any unsecured experin:nt, an; movable experiter.t. or any cc:Lination of such experiments havin; a total reactivity worth in excess of 0.0025 Lk/k ir.troduced 'cy intentionally setting the expcrinant (s) in cotion relative to tne reactor shall be less than 0.0025 Lk/k-sec.
l i
D.
The su: of the magnitudes of the static reactivity verths of all l
unsecured experiments which coexist shall be less than 0.015 ;k/c.
E.
The surf ace te:perature of the czterials which bounds or scpports any experiter.t in the dry irraciation f acilities sha".1 be less than 400*C.
t F.
laterials of construction and fabrication and assembly techniques utilized in expericants shall be so specified and used that e
assurance is provided that no stress failure can occur at stresses
[
twice those anticipated in the canipulation and conduct of the experiment or tviCC those which could occur as a result Cf un-intended but credible changes of, or within, the experi ent.
G.
The radioactive caterial content of any singly encapsulated e xperiment shall be limited so that Le co:picte release of al.
saseous, particulate, or volatile corponents from the encarro.ation vill not result in doses in excess of 5% of the equivalcat e r.nu;l coses stated in 10 CFR Part 20. This dose lindt appides to persons occupying (1) unrestricted areas cor.tinuously f or two hours starting at tire of release or (2) restrigted' areas during the length of time required to evacuate the restricted area, i
E.
The radioactive caterial content, including fission products of any doubly encapsulated or vented experirent shall be
_j lindted so that the complete release of all gaseous, particulate, or volatile components from the encapsulation or confining boundary of the expericent could not result in (1) a dose to any person occupying an unrestricted area continuously for a pcriod cf two hours starting at the time of reicase in excess of 0.5 ret to the whole-body or 1.5 rc= to the thyroid or (2) a dose to l
any person occupying a restricted area during the length of tame required to evacuate the restricted area in excess of five rc; to the whole body or 30 ret to the thyroid.
i All experiments out side this envelope vill require Reactor t
Safeguards Co::dttee review.
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CE07.01A TTCH RESEARCF. REACTOR hspter l
Procedure s.v.
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OPERATION OF E):?EF.1 MENTAL FACILITIES h'* *.!
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a Geners; Instructions 1.
Verify that an approved " Request For YJnor Experiment Approval" forn is on file in the Contrcl hoot.
Check the requested irradiation on the C'iEA Experincnt Schedule Ccid (Yellow Ccrd) to be sure the requested time, position, acterial etc. do not exceed the approved limits.
If any litita vould be exceeded, the expericent should not be done.
Secure a T.adiation Work Perndt (TJn7) for the job.
If the work is te bc 2.
done undcr an Approval for Self ranitoring, follow the instructior.sthereir..
e t
A.
Horizontal Bea Ports El through.rJO except E4 If the experimental use requires orly the opening or closing Note:
of the lead shutter, skip to step 2. below.
1.
Insertior./ Removal of graphite plug or collinator Verify reactor has been shutdown (if possible for 46 houra a.
or more) b.
paper the floor area benecth and directly avey fro; the sclected port.
O'otain a box for contaninated vaste For graphite insertio-/ removal, secure the special sup?crt c.
cradle and alutinum handling rod. To cir.inize contatir.stien from the graphite, withdraw the scringerinto a length ci previously prepared polyethylene tubing d.
Remove the concrete shield plug using the 2 ' Ton auxiliary Use special tool and open the lead shutter plug from the r(c: tor e.
top Note: Without graphite, the gat =a beam emerging f ro: a port cc.y be I
tens -of-rad per hour. Use appropriate health physics precedures.
l f.
Insert / remove the graphite plug. Close the covable Icad sho;.ur.
Insert the shield plug or special experisental plug in t:.e pcrt.
i.. Operation for an Erperiment a.
Verify placement of adequate shielding for the ecerpini. b eu.
If the expericent has not been run before or any changea hevc beer. made, request Health Pcysics monitoring.
b.
Use special tool to open/close the movable lead shutter plug from the reactor top L.
Horizontal Lean Port H4 1.
Estselish co;;ur.icetio:. betwed. reactor operator and fic1; c; cre:or at H' position
<nn.
h,, : valves CLOSE)
GEORCI A TECH RESE/J CH REACTOR procedure 31"1
.napter l
Approvcc 5
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.liary Systc 0?IRATION OT ETPER~.NE:.7/.1. F/,CILITIES Page 4 cf 5
. J.T I.
3.
Eequest control roor operator to energize the 1i4 syste:
4.
Open the sa pic inscrt port and, using tongs, insert the rabbit into the port and close the seal.
l.
l Note: The rabbits vill usually have holes drilled in tne plastic capsules to provide cooling to the sa pic.
The rabbit u.ay or rzy not be buoyant depending upo:.
the sc ple and its inner container.
5.
Ir.f e r the reactor operator that the sc:ple is being inser:c..
l lie vill log ir.itir.1 regulating rod position.
Open the c; rcpriate l
insert valves.
Insertior. will require 6-5 secords.
Rec c:c :
If int operator vill log " final" regulatin - rod positic.n.
required cocpensating regulating rod motion exceeds 2 incr.es, the reactor operator vill shut down the reactor.
Satple cc.oling flow is conitored by the flovr eter with a low 6.
flow alar: sig.a1 in the cc:. trol roos.
If coolin; flov for tne sa:ple is candatory-re f er to experic.cnt approval-the rca::cr vperator vill scra the reactor upon receip: of a lov flo-slar;.
If cooling is not Landa*ory, Continue rea0 tor CperatiCn.
"A*crnine cause of loV flow Condition and Correct.
completion of irradiction time, CLOSE both insert va;ves and 7.
At OPES both return valves.
Use radiation monitoring in. :ru:.cr.;s to r
deterr.ine the return of the rabbit. k~nen rabbit has re t L::.ca, request reactor operator to secure the purp.
6.
If the radiation rate fro: the sa=ple is ve y high it r23 oc desirable to let the rabbit decay in the sample tube.
If rec. oval is desired, open the receiving port.
CALTIOS: If the rabbit is buoyant the radiation level vill sher;1y increase when the rabbit comes to the surface.
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Vertical in-Core Position V21 through V26 D.
be shwtdown for all sa ple insertions er re-1.
The reactor cust movals fro: these experimental positions.
For saeple t w.al following reactor operation, wait at least 45 c.inutes befor.:
recoving the lower top shield plug.
the 2.
Remove the Icad cover plug and the upper top shield plu; f rc:
selected position 3.
Recove the lover top shield plug. The lover end of the pi g vill -
be very radioactive. Fove the plug away f roc the wordn; area.
For positions V17 and V26, it vill be necessary te f. ret Kote:
" unlock" the inner lower top shield plug using a sperial tool
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5 GEOh01A TECE RESEARCh REACTOR
.. apter procedure ^3 0; 5
Approved L a t es Ech "'
Mary Sys:e:
O? ERAT 105 OF D7ETJCCA1. TACILITIES Pafe5 of 5 f
sampics will be inserted or removed using the specic; 4.
Post
" fishing rod" with the three-prong hook.
Uti*.ize a mirror l
and light source to tinindre radiation exposure to person:.c; l
S.
Insert the shield plugs in reverse order. Check that the lower top shield plug is oriented proptrly to seat fully.
I Use appropriate health physics practices to clean any possibic 6.
contamination from the arca around the e>perimen:21 posit;cn.
E.
Vertical Graphite Positions V33 through V46 1.
The reactor should be shutdovt for resoval of the shield plugs fro: the graphite positions.
Note: Some sample irradia: Cons are cade without the shielcing re-installed. The conditiom for such irradiations are:
Eeactor power lindted to 250 Kk' cr-less and a.
b.
Special Health Pnysics monitoring required shoald be 2.
If the selected position has a graphite stringer, it I
4 removed and stored. Follow the general procedures in 5:cp A.I.
3.
Sa ples are generally handled per D.4. above Use appropriate health physics practices to cican any pessi:.;c 4.
radiactive contacina: ion f rom the area around the experizen:a1 position.
C.
Horizontal Tangen: Tubes Ell and E12 For use of these facilities, follow the steps given under /..; fer the Horizon:a1 Ports except that ports E11 and E12 do not have a novable lead shutter Eote: These ports are often used for engineering type cajor e xpe riment s.
Generally, special job plans vill be vrs: ten for these experiments.
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GEORGI A TECE F.ESEAECH REACTOR
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pte.
Procedure 2025 4
Approvec 5/2/74 Latest Rev.,
g e _"_.1 DAILY STAR 7i:P CRECK LIST Path 1 of 5
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Check ECO3 perp, hoses in place, Date:
fuci sup;1y sufficient Time:
k{
Check city water supply g 25 psig g
Opera ors _-
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C:.c c,: ICOS s:rcinless hose in place i
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. 0, E
, or helius Cncek I;;5 Valves 690, 691 closed
.stc. 3~.in ling' pipe tur.nci Cr.eck leva". in spent fuel basin
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4 1 34k ee:p va".ve air filter Coolir.; tower screen clear Take data in process equipment roo t
i Vacuu: Ereaker isol. valves open Check Kar.ne and Map 1 running Sv'
's in panels LO, LQ, PL Process E quip. R oo: clear and
.v.CC Ereakers ON locked Tans GR-;, 2 6 3 Ox E=crgency lights on overhead Sc p purps 1 6 2 on Auto (svitch E ergency air lock at a raiector each week)
Truck door sealed Ir. s t. air press 2 16 psig i
Personnel air lock sealed Air co:presour OK, Slowdown Systes air press. 2 30 psig Thermal colu=n OK Escrgcncy lock air 2 20 psig Sio-Med OK Truck;ock air 2 20 psig Shi blade dash pots checked Personnel lock air 2 30 psig El through K22b OK-list abnorma.
status belov Etitu: supply OK Reactor top OK-list abnormal j
Cas holder level OK (Co: pare elec, status below f
vs. cech. indicators)
At al Conditions or special operating instructions:
f.
i GEOROIA TECH RESEARCH REACTOR C.nspter Procedt.ro 2002 i
4 Approved
-Kor=al 1.ates: Rev.
Operation DAI;.Y STAR 7'JP CEECK 1.!ST Pafe, of $
j l-Pre-amp power ON Turn on followint recorders; chcrt 6 I
l Ink OR; Date 6 time stamp Auto-Aor. troller chassis power ON TR-1 Instrument power ON I
TR-2 Shutter Indication power ON CRA-1 LO Power supply 05
,,1 u -n Ercakers AU, AV ON TRA-D1 Turn Ke'v switch ON Powcr level recorder (on slow)
Shi Elades down Water 6 Cas Monitor recorder Annunciator Test OK Check following recorders ON; New chart and ink OK; Date 6 tir.e stanp k.
lator rese OK TRA-El Building PA test OK M *UI Interco: ON 60 cps check Clocks OK 120 cps check Isolation Selector to Check the following instruments 05 l
Do Eot Enter sign on " auto" I
Log N, Peri'od No. I
{
Radiction Control and Power Supply j
Chtssis ON Log N, Period No. 2
)
i HV Volts 73a A_p, go, 1 LV Volts C't.eck following recorders ON; Chart
& Ink OK; Oate 6 time sta:P Dual High Voltage power supply PS-1 Log N 6 Period (on slow)
Radiation Recorder Pos.
Volts
. anne Recorder Picoa=neter No.1 Picoa.cter No. 2
GEOROI A TECT. RESIAACE REACTOR Chapter Procedure 2L13 4
Approved 5/2/74
'*I*'I ECV-Nor r.1 Operations DAILY ST/,RTU? CEECK LIST Page > of 5 Check the following instruments ON (Cont)
Verify sprayblock valve open Kiter Jbnitor Verify reactor isolation valves open EV 05 Establish purification flow 60 sec. TC Open valve 50 Alar set @
cp Open valve 36 Gas Monitor Open valve 35A (L)
EV 05 S'6TE IC"3 (4) 20 sec. TC Throttle valve 39 to set 7 gp Alar set @
cp:
flow Filter Bank Monitor Close valve 50 EV ON (Nimbin)
Close valve 36 Kateneter ON Is primary valve check list nee-Alars set @
cp:
essary?
If "yes" perfort in accordance with CTRR Test LCRM Procedure 2150 LCRM EV OTT If "No" continue Precritical check-Tunction Switch to 10 cps list Check Meter reads OE Start ?D-2A Reset Trip (neutron countrate low)
Observe flow increase to 1550 gpn Svitch function switch to operate Is secondary valve check list If "Yes" D*C886'ry?
Observe low neutron countrate trip perform in accorcance with CITT.
at 2 cps Procedure 2203.
LCTE EV ON If "No" continue Precritical check. list Reset trip and annunciator Start MH-2A Discriminator set @
Tine base /caitiplier switch to 1 second Past/Nor;/ Hold switch to Norm Multiplier toggle switch to X 1
!s purification valve check list ssary?
If "Yes" o rt in accordance with C~T.T. Procedure 2050.
If "No" continue Precritical checilest
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GEORGIA TECH RESEARCH REACTOR onapter Procedure 20~3 4
Approved 5/2/74 Las"est Rev.
~
Normal DAILY STARTLP CHEC,'. LIST Page 4 of 5 Operation Check Permissive interlocks cicar Start,i5-3 Scfety rods out 1
Is helium valve check list necessary?
In strumen t Sv. Off Low If 'Tes" perform in accordance with CTLR Procedure 2350.
E!dn. Rad. Eich If "no" continue Precritical checklist Eev Neutron Countr-te delius level fro: 20 to 40 cu. ft.
E.crr. Core Coolant Svs.
Open valves 230, 231 Check all scra=s clear l
Start MHe-1 Reset magnet actuator a:p.
Relay current a:p.
de" flow >15 cfm Energize No. I clutch current a=p.
Is....; eld syste: valve check list Energize No. 2 clutch necessary; current c p.
Energize No. 3 clutch If 'Yes" perform ir accordance with current a=p.
GTRE Procedure 2250, Energize No. 4 clutch current a p.
If "no" continue Precritical checklist Raise No. I shio safety rod to 5' Start MS-1 (2)
Drive down to 30 Is Lis:uth syste= valve check list necessary?
Drop shic safety rod No. 1 If "Yes" perform in accordance with Repeat for No. 2 shim safety ro; GTRA Procedure 2300.
Repeat for No. 3 shic safety rod If So" continue Precritical checklist Repeat for No. 4 shic safety rod l
Start MB-1 Raise reg. rod to 2 inches TD-2 full Drive down to lov limit If not full, open valve 92 until level
' es over fl ow.
'4nergize clutches 1-4 rr C4.,e valve 92 Rest: TD-2 lov level pemissive
l GEORGI A TECE RESEARCE REACTOR
.napter Procedure,20:.g 4
A; proved.5/2/74.
Latest Rev.
' o r~~- I DAILY STARTUP CEECK LIST Pa[e 5 of 5 speration Connecto;onsigr.a/1cableon{rearof Conncer caele fro calib. uni'to "T".
Eclease ra p switch Flux A=p. 1 A]1ov period to stabilize Slowly cdjust calibration unit until Re se r Ac t ua t o r A=p.
Power trip is received Energize clutches 1-4 AsCorc _ar,p point On reset switch go to rat?
Observe Power Trip plate reset position Ma gne t act. amp.
- 0. 0 ta gne t current Observe Neg. Per. (1 (2)
Rod tag. Ind. I 6 2 Period Trip plate (3 6 4) 0.16 nag. current Shis blades 1-4 on Rod. Mag. Ind.1 6 2 cown licit (3 3 4) off Repe.. for Flux Arp. f2 Repeat for Log E Discont.ect cable to Flux Amp. 02 Resove jucper from TD 176 onsta.. Ju per from TD 176 to TD 134 to 73.134 Check reading on Log N (1 (2)
Keset Magnet Actuator Amp.
3;1/6" in the following position:
Encrr,ize Clutches 1-4 Zero 2
~
Zero 1 1501 10';
.3 av Go to period position.
Al~ov unit to stabilize, Reset period trsps. Reset actuator a=p. Energize clutches 1-4.
Go to fixed position on ra p svitc). (Hold until power level it.dicates 10->I)
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Obs pos per. il (2)
,... -10.: Trip plate O
- 1.....,. i a l ren a mit l'...
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GEORGIA TECE RESEARCE REACTOR
{
- asp;cr Procedure.;3g2 2
Approved 12-6-77 o:ponent Latest Rev*
a r. d l i r. g TUEL HANDLING IN TEE CORE p3 9-o f >:-. '..
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7;'7.?CF E s
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To establish guidelines and procedures for fuci. 4d11. -in core i
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jh the Georgia Tech Research Reactor.
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II.
L:M:TATIONS A'O REQi':RDINTS The Technical Spec'ifications establish certain linitations and require-cents for fuel handling. These are listed below:
A.
Tr.e reactor cust be suberitical by core than 0.0275 4c/c during loading changes (see 3.1.b.)
5.
Containment isolation sls be maintained during movement of irradiated fuel (see 3.3.c.)
h J.
Al* grid positions cust contain fuel elements, grid plugs or experimental facilities for operation in the forced convection code (see 3.6.c.)
D.
All fuel elements outside of the reactor shall be stored and handled such that the calculated r-effective is less than 0.85 under op:icu: conditions of water moderation and reflec:fon (see 3.6.a.)
E.
No = ore than four unirradiated fuel elements shall be together in any one roon outside of the reactor, shipping containers or fuel storage racks (see 3.8.b.)
F.
Provide a ninicun of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> cooling af ter 5 Ka' opers:for. befor.
renoving a f uel elecent (see 3.S.c.)
G.
Shic Safety blade reactivity worth shall be measured and the she:down margin calculated annually and whenever a ccre con-figuration is loaded for which shic safety blade worths have no: been measured (see 4.1.a.)
III.
/.?PLICABILITY I
1 This procedure should be implemented for any fuel elenen: change ate involving the core of the reactor. This would include (but not be I
ainited to) the following:
J A.
Add new fuel only
'. Add irradicted fuel only C.
L6 cove irradiated fuel only L.
K0:ove irradicted fuc1, add new fuc1 I.
kereve irradiated fuel, add irradisted fuel j
i
GEORGIA TICH RESEARCE REACTOR
.pte7 Procedure 1502 Approved 2
R*12-6-77
'*t V*
P a g e,'2 o f,3., '
FUEL HANDLING IN THE CORE nd.ing r
IV.
PT.OCELLRE
'A.
Operable neutron manitoring channel. Verify that one (or more) of the following neutron monitoring channels are operable:
1.
Startup Channel 2.
Picosameter Channel No.1 3.
Picoa aeter Channel No.2 If the signal from the monitoring channel (s) increase by a factor of 2 during f uel movement, tercinate the operation.
The reacter supcrviscr vill to continue. Addi:fona*1y, evaluate and specifically authorize the progra fuel handling should be terminated in case of unusual events such as fire, criticality etc.
B.
List below, in sequence, the fuel element movcs that are to be done.
Specify a "from" and "to" location explicitly.
estimate the reactivity addition t'o the reactor core C.
For each covement, (positive or negative).
The maximuc worth of a new 168 gc. element is 0.025 as/t.
Note:
D.
Estinate tht critical blade position using the inforzation in IV.E.
above and current shi: blade vorth calibrations.
y
-. -... - _ _ _. _. =
-e GEORGIA TECF. RES;ARCE REACTOR
."n ap t e r Procedure 1502-2 Approved
.22-6-77
'atest Rev'.
FUEL BANDI.ING IN THE CORE Page 3 of,9
- =ponent
.ndling i
E.
Deterc.ine if a tieasurement of shit. blade reactivity worth ano snuto vn nargin are required.
If so, they must be done prior to operation of l
the reactor for any other purpose, i
Are measureraents required?
File this co:pleted procedure. Retention time is 5 years.
t V.
ASPEOVAL AND VERTIF: CAT:05 i
t A.
Procedure reviewed and approved 3
i t
f i
i I
Reactor Supervisor or Reactor Engineer Date e
{
B.
Procedure cos:pleted f
i l
t I
I Date Reactor Shif Supervisor i
I
\\
.