ML20133N284
| ML20133N284 | |
| Person / Time | |
|---|---|
| Site: | 05000077 |
| Issue date: | 10/22/1985 |
| From: | CATHOLIC UNIV. OF AMERICA, WASHINGTON, DC |
| To: | |
| Shared Package | |
| ML20133N272 | List: |
| References | |
| NUDOCS 8510280478 | |
| Download: ML20133N284 (28) | |
Text
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Proposed Amendment to CHAPTER 16.0 TECHNICAL SPECIFICATIONS Facility License R-31 (Docket Number 50-77) 8510280478 851022 PDR ADOCK 05000077 P PDR
. ? . , Tech. Specs.
.' TABLE OF CONTENTS
- PAGE i- . ., . . . ,
1 .
l 16.1 DEFINITIONS .................................................... 16-1 1
16;2 S AFETY-LI MITS- AND -LIMITING-S AFETY SYSTEM SETTINGS-'. . . . . . . . . . . . . . 16; 3 ~
i 16.2.-1 -Se fe ty L I mi t W. . . . . . . . . . . ./. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 - - -
- ---- 16; 2 ; 2- Limi t i ng-S a fe ty-Sys tent-Se t t i ngs . . . . . . . . . .' . . . . . .v. . . . . . . . . . . . 16-4 --
I j 16.3 LIMITING-CONDITIONS-FOR-OPERATION ...............................-16-5 4
16 3 1 - Reac t i v i ty - L i m i ts ...................................l...... ,
16-5
. - 16. 3 2 - Con t rol - and -Sa fe ty-Sys tems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 1 . '
i- ----- 16. 3 3 - L i mi t a t l on - on - Expe . I me n t s - . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ,. . . 8 - -
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- 16. 3. Sh i e l d i ng m . . . . r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ' . . . . . . . . . . . . 8 -
- 16. 4 - SURVE I LLANC E- REQU I REMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S
-16. 4.1 - Re ac ti vi ty L i mi t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .nu r. . . 16- B a j
!t 16. 4. 2 - Cont rol and S a fe ty Sys tem, . . . . . . . . . . . . . . . . . . . . . . . . .mr. r. . .-16-9 -- - -
- a
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- 16. 4 3 - Re ac t o r- S t r uc t u re -. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . 16 - 1 1
- ' 16.5 DESIGN FEATURES ................................................ 16-11 1'i 16.5.I Re a c t o r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 - 1 1
- 16.5.2 Fuel Storage ................................................ 16-12 1
16.5.3 Re a c t o r Room . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 - 12
' 16.6. ADMINSTRATIVE CONTROLS ......................................... 16-12 j .
16.6.1 Organization ..............................................,.. 16-12
. 16.6. 2- S t a f f-Que l l f i ca ti ons - . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16-15 a
- 16. 6. 3 -T r a i n i n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .T.~ 16 - 15 I
(~ 16 ;6-4 Reactor-Safety-Commi ttee-Reviews r Audi ts . ._
16-15 l 8
And - Auth o r i ty . . . . .v. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 - 15 t
16 . 6 ; 5 - Ap p ro va i s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 - 1 7_ -
16.6.6 - Ope ra t i ng - P rocedu res,Tzm.Tr. . . r.urc. . . . . . . .w . . v. . v . .vsr. . 16-17 t
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' 16.6. Experi ments . . . . . . . . . . . . . . re a vinrrrr. . rr. . n . . vv. r. . .v. . . . . . 16-I 8 1
16 ;6; 8-S a fe ty-i.imi t-Vi ol at ion . . . . . ; n . . . . . . . .Tre.r.Tr.wr. .n c. . . .A 16-I 8 l
--- - 16.6 2 9 - Report i ng Requi remen ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 1
,! 16.6.10 Re co rd Re t e n t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 -2 2 h .I b
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_-__._.____o: ,__________:_,_,__._____,,_______ ,. _ __
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.I 16.1.0 x
- - The tenns Safety kmit (SL), Limiting Safety Syst;m Setting (LSSS), /
' cnd Limiting Conditions for Operation (LCO) are as defined in 50.36 ./ .
\ of 10 CFR part 50. \ '
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Channel Calibration - A channel calibration is an adjustment of 16'l'.1 the channel sucn that its ' output respon'ds, within acceptable ran
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, Nand accuracy, to kno seasures.
Calibratica shall'encompa'ss equipment, acutation, alann, or trip.
s Channel Check - A channel chgd is a qualitative verification of the entire channel, including 16.1.2 acceptacle perfomance by observatibq of channel behaviof. This verification may include cc'moarison oft the channel with' other indep ndent channels or efthods measurt g the same variable.
16.1.3 Channel T'est - A channel test is the introduction of a signal into '
the channel to verify that it is operable. ,
O-16.1.4 Experimer_st_ - _ ,
\ a. An expe9teent\is any of the followipi;:
x (1) Ar}/ activity \ utilizing the react'or system or its components s
N ' or the neut or radiation jgenerated therein;
\ (2) An evaluation o test of a/ reactor system operatiort 1, surveillance, or intenance technique; (3) An experimental or esting activity which is conducted th-in the confinement orXcontainment system of the reactor; or
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\, (4) The material content of'any of the foregoing, including N
);
\ and contained fl61ds or solids. structural components, en' capsulat
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/ b. "Se\ cured Experiment - Any experim\eqt, or component of an experim is deemed to bejsecured, or in a secured position, if it is held
/ in a stationary position relative to the reactor by mechanical s means. 'The restraint shall exert sufficient force on the experiment
" to overcome /the expected effects of hy'draulic, pneumatic, bouyant, or other f6rces which are nonnal to the' operating environment of the experiment or which might arise as a ' result of credible ~ mal-functions.
- c. .Unsec'ured Experinent - Any experiment, or component of an experiment
'is dee.aed to be unsecured whenever it is not sAcured as defined in 16.1.4.b. above. Moving parts of experiments are deemed to be unsecured when they 2tre in motion. \
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- d( Movable Experiment - A movable experiment is one which may be j
ulated while the reactor iss eritical.
inserted, removed, or manip \ \
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' e. Removable Exoeriment - A removable experiment is an.y experiment,
/ experimental facility, or component of an experiment, othe,rgthan
a permnently attached appurtenance to the reactor system, which can reasonably be anticipated to.be moved one or more times during
,' ' the life of the reactor.
s 16-1
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'---16c1z5-fiperimental-Facilities- -Experimental facilitibre those portions '
of the reactor assefclyJhat-are~used for the introduction of experi-ments intpadjacenT to the reac' tor core-region or allow beams of radiatich to exist frem the reactor shielding. ExperimentaLfacilities~
shall include the thennal column, glory hole, and access ports. N ~
16.1.6 Explosive Material - Explosive material is any solid or liquid which is categorized as a Severe, Dangerous, or Very Dangerous
- - Explosion Hazard in " Dangerous Properties of Industrial Materials" by N.1. Sax, Third Ed. (1968), or is given an Identification of Reactivity (Stability) index of 2, 3, or 4 by the National Fire Protection Association in its publication 705-M,1966, " Identification System for Fire Hazards of Materials," also enumerated in the
" Handbook forLaboratory Safety" 2nd Ed. (1971) published by The Chemical Rubber Co. . .x
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1017=Measurino-Channel -A-measuring-channel-is-the-combination-of-sensorI
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lines, amplifiers , Jtdevices-whicriettToEIected for the urpose of-measurin or responding to the value of a process variabler-i 16.1.8 Operable - Operable means a comnonent or system is capable of nerforming its iiitended function in its normal manner.
16.1.9 Ooeratina - Operating means a component or system is perforcing its intendec tunction in its nonnal manner.
g nto-PotentiahReactivity-Worth -The potential reactiJity worttrE an experiment is tne maximum-absolut alue-of'the reactivity
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change that would occunas-a-re u t of Tnte5dbrer anticipat C' changes pr_ credit 71ETnalfunctions that alter experiment position ortoTfiguration, ---
16.1.11 Reactor Comoonent - A reactor comconent is any aoparatus, device, or .
material tnat is a normal part of the reactor assembly.
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16.1.12 Rcactor Ooeration - Reactor operation is any condition wherein the reactor is not snutdown.
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The-reactor-safety-system is- that _7 coe i
'1671113-Reactor Safety System - ;
of safety channels and associated circuitry which forms the automatic
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\ protective system requires manual protective action for the reactor or provi be initiated.
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16.1.14-Reacte& Shutdown- -The ' reactor-shall-be-considered sh6tdown whene
] lly withdrawn frcm a.eith r* 1. All safety an4 ' control mds are the core, or ,
- 2. The core fuse melts res61 ting in separation of the core, t?
and: .
- b. The reactor console ke tch is in the "off" position and , .
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'4 the key is removed fro;n e console and under the control of a licensed operator. .
y .
measuring ch~annel~in'~the~~ reactor i
- 1671:15-Safety-Channel -;Psafety channel-is
- safety system /
- 16.1.164tatic Reactivity-Worth-The-static-reactivity w' orth of an experi --~
ment,is the absolute value of the reactivity chang (which is measurable by calibrated control or regulating md comparison siethods between two defined teminal positions or configurations of the experiment. For removable experiments, the temihal positions are fully removed from the reactor and fully inserted or installed '
- in the normal functioning or intended position.
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16.2 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS /
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16'.2.1 Safety Limits ,
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= \ Applicability - k'
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This specification applies ,to the maximum steady state / power level and maximum core temperature during steady state or tt;ansient op-
. e rat ion. /
0&Jective f N / 1 To assure that the Integrity of the fuel mater,lal is maintained and all fission fragments are retained in the core matrix.
N Speci fication '
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- a. The re\actor power level shall notrexceed 100 watts. *
- b. Themaxim\ug core temperature shel'1 not exceed 200*C either stea state or transien*. operation.
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U Bases /
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The polyethylene core materlaVdoes not melt below 200*C and is 'ex-pected to maintain its iktegrity and retain essentially all of the fission fragments at temp 4(atures below 200*C. The Hazards Sumary Report dated February 1962\ submitted on Docket F-15 by Acrc,iet-General ~
Nucleonics (AGN) calculat'ed 'ag steady state core average temperature rise of 0.044C/ watt. The re fore a steady state power level of 100 watts would result inj$n averagkcore temperature rise of 4i00. The
,; corresponding maximum core temperature would be below 200*C thus assuring integrity df the core and\ retention of fission fragments.
Speci fica tion
- c. The reactor shield tank water temperature shall be maintained o above IQFC, and the water level in the tank shall not be more
! than 1 inches below the highest point n the manhole opening.'
Bases -
Low r,eactor shield tank water temperature may res it in freezing of the water. The resultant expansion due to freezkg of the wat'er may damage the shield tank and other reactor c6mponents.
Th'is condition would degrade core containment and shlSiding
, jcapability. A safety limit of 10*C provides a margin for
' j confidence that the reactor will not be operated with frb en
/ shielding water. ,
The shield tank water level of 10 inches below the highest paint on tha j / manhole opening provides adequate biological shiciding during' eactor operatton.
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, . 16-3
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l 16.2.2 Limiting Safety Systems Settings /' .
Applicability , ,
This specification applies to the parts of the reactor safety system which will limit maximum power and core temperature.
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- Objective -
To assure that automatic pirotective action is in tlated to prevent a safety limit f rom being exceeded.
Specification N
N
- a. The safety channels shall initiate apeactor scram at the fol-lowing liniiting safety system setti gs: ,
Channel Condition LSSS Nuclear Safety 11, HJgh Power < 0.2 watts -
Nuclear Safety #2 . Igh Power 30.2 watts Nuclear Safety #3 High Power < 0.2 watts
- b. The core thermal fuse shall melt when heated to a temperature
. of about 1200C resultiQ in core separation and a reactivity 9!
" loss greater than St/ak.
Bases , .
. Based on instrumeptation response tigs and scram tests, the AGN Hazards Report concluded that reactor periods in excess of 30-50 milli-seconds would be adequately arrest \d by the scram system.
Since the maxfmum available excess reacti'v'ty in the reactor is less than one dollar the reactor cannot be .e prompt critical and the corresp'onding shortest possible period is reater than 200 milli-seconds./ The high power LSSS of 0.2 watts in c njunction with auto-matic pafety systems and/or manual scram capabi(ll{ies will assure that the safety limits will not be exceeded during steady state or as a# result of the most severe credible transient.
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in the event of failure of the reactor to scram, the se(f-limiting characteristics due to the high negative temperature coerficient.
and the melting of the thermal fuse at a temperature at about 120 C will assure safe shutdown without exceeding a core /emperat' ore of 200*C.
- . l 16-4 l
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/ 16.3 [lMITING CONDITIONS FOR OPERATION 6.3.1 _ Reactivity Limits N
Applicability /
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This specification applies to the reactivity condition of j 'the
. reactor and the reactivity worths of control rods and experiments.
F Objective
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To ogsure that the reactor can be shut down at a 1 times and that the safety limits will not be exceeded.
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Speci fication ,
- a. The av\ailable excess reactivity wit -
rods fully inserted and includingp,h he potential all control reactivityand .sdfety worth of a'1(experiments shall t exceed 0.65% Ak/k re- .
ferenced to 20*C.
- b. The shutdown m in with th most reactive safety or control rod fully inserte shall be'at least 2% Ak/k.
- c. The reactivity worth of the control and safety rods shall i ensure sub-criticalit on the withdrawal of the coarse control rod or any one s fety rod.
3 .-
Bases The limitations on t'otal core excess reactivity assure reactor per-lods of sufficien,t /length so that the (eactor protection system and/or operator action will be able to shut the reactor down with-ii out exceeding any safety limits. The shdtdown margin and control and safety rod reactivity limitations assu that the reactor can be brought e$d maintained suberitical if the highest reactivity rod fails t'o scram and remains in its most rea'et i ve pos i t ion .
16.3 2 Control /and safety systems ,
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! Appil'cability
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Th
/ ;ese specifications apply to the reactor control and safety system
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\ Objective , ,
To specify lowest acceptable level of performance, inst rument set points ,
l a'nd the minimum number of operable components for .the reactor control a'nd safety systems . .
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1 Speci fica tion The reactor N '
shall not be made critical *unless the following specifications l are met: N
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S a. The tota'1, scram withdrawal time of the safety rods an coarse control t rod shall'be less than 200 milliseconds .
- b. The maximum N reactivity addition rate for each rod shall not exceed 0.04% Ak/k/sec ,
/ - -
l c. The safety rods and coarse control rod shall be interlocked such .
that:
- . 1. Reactor startup cannot cornnence unip s both safety rods and coarse control rod are fully withdra.<n from the core.
N te d a t a t ime .
2.
Only one safety rod ca\be inser/
The coarse control rod be canno /
inserted unless both safety rods 8
3
! are fully inserted.
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} d. All reactor safety system Iry trumentation shall be operable in accord-i ance with Table 16-1 with the following allowable exceptions:
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Nuclear Safety Chanpe/' No.1 may be bypassed for a perio
- 1. l l' exceed twelve consecutive hours prov(ded Nuclear Safety Channel Nos. 2 and 3 are,verifled to be operable.
i / Channel No. 3 may r 2. Nuclear Safety' passedbeforby\a period not to e
exceed 12 con'secutive hours provided NuclAar Safety Channel Nos.
I and 2 are' verified to be operable. . ,
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- 3. The seistnic displacement scram may be out of s rvice during reactor operatfon for no rmre than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 3-rmrnh period.
3.
9 A loss of electric power shall cause the reactor to ser m.
N Bases 1 The spe/cification on scram reactivity in conjunction with the safgty system
^
- instyumentation and set points assure safe reactor shutdown during the rnost ,
-i severe foreseeable transients. The limitations on reactivity addition rates i ,
kitcw only relatively slow increases of reactivity so that ample time ill be
,available for manual or automatic scram during any operating conditions. l l
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\ Interlocks on control and safety rods assure an orderly approach to critl[ality ' f Kandanadequateshutdowncapability.
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T neutron detector c'hannels (nuclear safety channels 1 through 3 ss ure thats reactor power levels are adequately monitored during reactor t a r,t up
'.- and o'peration. Requirements on minimum neutron levels will pre startu;) gunless channels are operable and responding, ause and awill c'yent reactor scram in the event of instrumentation failur,e'. The powe r le ve l s c rl.-.s i n i t i a te ugh to assure redundant ' automatic protective action at power levels low e[iod scram conser-safe shutdoh wi thout exceeding any safety limi ts . The p9e vatively limi'ts the rate of rise of reactor power to per)ods which are manually controllable and will automatically scram the reactor ji n the event of unexpected large reactivi ty\addi tions . In order to provide someftime to correct channel detects , a maximuEt f 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is allowed for operapon with either Nuclear Safety Channels Nos I or 3 bypassed i f the remaln ng two channels are veri fled
. to be operable. Alt ough some redundancy in the r)eactor protection system is lost during the lim'Isted time interval, all s ~ jam functions and monitoring capabilities are still a'vailable. -
N The AGN-201's negative temperature coefficipnt of reactivity causes a reactivity increase with decreasing coregtemperature / The shield water temperature safety channel will prevent reactor o>eration at' temperatures below 15*C thereby limiting potential reactivity additions / associated with temperature decreases.
Water in the shield tank is an im nt component of the reactor shield, and operation without the water may produce excessive radiation levels. The shield tank water level safety channel w(ll p'revent reactor operation without adequate water levels in the shield tank /
The reactor is designed to withstand 0.69 accelerations and 6 cm displacements.
A seismic instrument cause /a reactor scram 'wbenever the instrument rece i ves a horizontal acceleration that causes a horizontal displacement of 1/I6 inch or grea te r. The seismic dj placement safety channel assures that the reactor
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will be scrammed and byought to a subcritical configuration during any seismic disturbance that mayj cause damage to the reactor or\its components. Due to the low probabilityjof earthquake damage, the seismit instrument can be out of service duringjreactor operation for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in an 3-conth period .
i The manual scram / the operator to manually shut do allows the reactor if an unsafe or otherwise abnormal condition occurs that does got otherwise scram .
the reactor / A loss of electrical power de-energizes the sa(ety and coarse control rod holding magnets causing a reactor scram thus asso ing safe and immediate/ shutdown in case of a power outage.
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A radia' tion monitor must always be available to operating personne gto provide an inification of any abnormally high radiation levels so that appropqiate actfon can be taken to shut the reactor down and assess the hazards to gpersonnel .
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. ;. 16.3 3 _Limi tetions on Exoeriments / '
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Appil cabil i ty This specification applies to experiments installed in e reactor and its experimental facilities.
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- L Objective To\prevent damage to the re" actor or excessive ry ease of radio-acti've materials in the e/ent of an experimental failure.
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9 Spe ci fication t
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- a. Expe ripn ts containing materials cc3 rosive to reactor compo-nents or which contain liquid or g cous, fissionable materials shall.b doubly encapsulated. ,
- b. Explosive materials shall not e inserted into experirEintal facilities the reactor.
- c. The radioactiv material ntent, including fission products of any experime shall e limited so that the complete release of all gaseous, arti ate, or volatile components from the experiment will no' uits in doses in excess of 10% of the
{' -
equivalent annual d ses stated in 10 CFR Part 20 for persons occupying (1) unr tr eted areas continu. <,1y for two hours starting at time of re(lease or (2) restricted areas during the j length of time equi re to evacuate the res tricted area. '
- d. The radioactive material content, including fission products 1 of any dou y encapsulated hxperiment shall be limited so that the comp te release of all scous, particulate, or volatile cynpone ts of the experiment all not results in exposures in ex ss of 0.5 Rem whole body or 1.5 Rem thyroid to persons occupying an unrestricted area tinuously for a period of two' hours starting at the time o release or exposure in e;lcess of 5 Rem whole body or 30 Reg thyroid to persons occupying 6 restricted area during the length of time required to evacuate
.- the res tricted area. -
Bases -
These specifications are intended to reduce the likelihood of damage to reactor components and/or radioactivity releases resulting from an experimental failure and to protect operating rsonnel and the public from excessive radiation doses in the event f an experimental failure.
16.3.4 Shielding AppilcabiIIty This specification applies to reactor shielding required dur ng reactor operation.
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Objectiva .
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. The objective is to protect facility personnel and the pubtle from! '
radiation exposure. ,
y Specification j, The following shielding requirements shall be fullfilled p or to i reactor startup and during reactor operation:
- a. The reactor shleid tank shall be filled with waterj o a height within 10 Inches of the highest point on the manho / opening.
- b. e thermal column shall be filled with watgr or graphi.. . .
j Bases \
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The Inher/nt reactor shielding in conjuncti n with designat.ed re-stricted radiation areas is designed to 1)$lt radiation doses to facility pe'rsonnel y and to the public to 4f level belcw 10CFR20 limits ,
under operating conditions, and to a 1pvel below Criterion 19, Ap-pendix A,10CFR50 recommendations un r accident conditions.
. 16.4 SURVEILLANCE REQ (REMENTS t
i i .
Actions specified in this sect on are not required to be performed
'j If during the specifi d survp 11ance period the reactor has not been brought critical or is hairy (ained in a shutdown condition extending
, beyond the specified survpillance period. Hcwever, the surveillance requirements must be fu f f led prior to subsequent startup of the reactor.
j- 16.4.1 Reactivity Limits
- j. Appilcability . -
This specifipation applies to the surveillance requirements for ~
reactivityjlimits.
Objective /
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To assure 7 that reactivity limits for Specif tgation 16.3.1 are not l1
- excdeded. K
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$pecification
- a. Safety and control rod reactivity worths shall be measured annually, but at intervals not to exceed 16 months .
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- b. Total excess reactivity and shutdcwn margin shall be determined -
. annually, but at intervals not to exceed 16 months.
- c. The reactivity worth of an experiment shall be estimated or measured, as appropriate, before or during the first s.t'artup subsequent to the experiment's insertion.
' Bases ,
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The control and safety rods'are inspected and the) reactivi ty worths measured annually to assure that no degradation or unexpected changes have occurred which could adversely af det reactor shutdcun margin or total excess reactivity. The shut n margin and total excess reactivity are determined to assure hat the reactor can al-ays be shutdcwn safely .with one rod not f nctioning and that the maximum possible reactivity insertion wi)' not result in periods sho'rter than those that can be terminat/d adequately by either s
operaqor or automatic action. Based experience with AGti reactors, significant s
changes in reactivity or rod worth .are not expected within a 16 month period. .
~16.4.2 Control a Safety System
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Appilcability fi This specificatlog applief to the survelliance requirements of the
' - reactor control and safety systems.
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Objective To assure that tn/ react'ors control and safety systems are operable i:
as required by Specificatt n 16.3 2 ,
f Specification . .
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- a. Safety and control rod scram (ime and insertion rates shall be measurdd annually, but at InteYvals not to exceed 16 months.
- b. deterioration Safe / control ty and rods and drive shall be inspected for at intervals not to ceed 2 years.
li c A channel test of the following safet gehannels shall be performed prior to each day's operation or prior to each operation extending imore than one day:
Nuclear Safety #1, #2, and #3 Manual scram Area radiation monitor
- d. A' channel test of the following safety chan.els sh 11 be per- I
. . formed quarterly:
1 l
. I 16-9 j.
l I
4, s
I i . .
r .,
Shloid water taparctura , .
\\' Shield water level Seismic displacement ,'
\ /
\ e. A channel check of the following safety channels shall b6
\ performed daily or whenever the reactor is in operation':
[ Nuclear Safety #1, #2, and #3 Area radiation moni tor
\ /
\
, N f. Daily, prior to startuh, each of the two safet ' rods shall be inserted and scramened to veri fy operabili ty.
\
. \ The period, count rate, and power level ryasuring channels shall
- . g.
\ be calibrated and set points verified an ually, but at in te rvals Nnot to exceed 16 months.
N t h. Th'es shield tank water level and te rature and seismic '
disp'lacement safety channels shall/ calibrated by perturbing the sen, sing element to the appro These ,
calibrations shall be performed'priate setbut annually, point.
at in te rvals not to ex'eeed 16 non ths.
j l. The radiati gmoni toring ljts trumentation shall be calib rated t annually, but at interva s not to exceed 16 months.
Bases
! The channel tests and hks required daily or before each startup will assure that the afetkchannels and scram functions are operable.
the annual 3
i Based on operating s (c((perienca with scram measurements channel ca(ibrations ,and set point verifications reactors 4 are of sufficient' frequency to assure, with a high degree of confi-5 de.a ce , th a t the/ safety sys tem set \ing will be within acceptable i dri f t toleragde for operation. The\ periodic surveillance and calibration /of the radiation moni toring instrumentation will assure that the radiation monitoring equipments is operable during reactor ope ra t ion'. \
N8 -
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- e o
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' '. 16-10 *
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- n. ,
t j, . 16.4.3 Reactor Structure N .
N(App 11cabi11tv his specification
/
applies to surveillance , req'uirements for reactor components other than control and safety rods.
N .
. Objectibe ,
The object is to assure,fntegrity of the reactor structures.
Specification
] a. The shield, tink shal 4e visually inspected every two years.
6 f f apparent excessive c%crosion or other damage is observed,
, cor,re(tive measures shal1% taken prior to subsequent reac-tor operatien. .
\
~b. Visual inspection for water leakaghfrom the shield tank shall be performed every year. Leakage shal(be corrected prior to .
subsequent reactor operation.
Bases j Based on experience with reactors of this type, the freq ncy of h inspection and leak test requirements of the shield tank we assure y capability for radiation protection _during reactor-operation.-
16.5.0 DESIGN FEATURES -
- 16.5.1 Reactor
! a. The reactor core, including control and safety rods, contains approximately 675 grams of U-235, in the form of 19.9% enriched i UO dispersed in approximately 11 kilograms of polethylene.
2 The 1mer section of the core is supported by an aluminum rod
, , hanging from a fuse link. The fuse melts at fuse temperatures of i about- 120*C causing the lower core section to fall away f rom the
, upper section reducing reactivity by at least 5% ak/k. sufficient
~
- . clearance between core and reflector is provided to insure free I fall of the bottom half of the core during the most severe trans-lent.
- b. . 'The core is surrounded by a 20 cm thick high density (1.75 gm/cm3 )
graphite reflector followed by a 10 cm thick lead gamma shield.
The core and part of the graphite reflector are sealed in a fluid-tight aluminum core tank designed to contain any fission gases that might leak f rom the core.
- c. The core, reflector, and lead shielding are enclosed in and sup-
. ported by a fluid-tight steel reactor tank. An upper or " thermal column tank" may serve as a shield tank when filled with water or a thermal column when filled with graphite. .
- d. The 61 foot diameter, fluid-tight shield tank is filled with water l .
16-11 .-
t -
.I.
. constituting a 55 cm thick fast neutron shield. Tha fest nautron shield is formed by filling the tank with 1000 gallons of water., "
The complete reactor shield shall limit doses to operating per-sonnel in restricted and unrestricted areas to levels less than permitted in 10 CF 20 under operating conditions.
- e. Two safety rods and one control rod (identical in size) contain less than 15 grams of U-235 each in the same form as the core ma te ri a l . These rods are lif ted into the .. ore by electromagnets, driven by reversible DC, motors through lead screw assemblies.
Deenergizing the magnets causes a spring-driven, gravity-assisted s cram. The fourth rod or fine control rod (approximately one-half the diameter of the other rods) is driven directly by a lead s crew. This rod contains unfueled polyethylene.
16.5.2 Fuel Storace Fuel, including fueled experiments and fuel devices, not in the reactor shall be stored in a. locked safe in the reactor room. The' storage array shall be such that K ff is no greater than 0.8 for all conditions
- of moderation and reflecti8n.
'16.5.3 Reactor Room
- a. The reactor room houses the reactor assembly and accessories required for its operation and maintenance.
'I /
b b. The reactor room is a separate room in the Pangborn Engineering
, building, constructed with adequate shielding and other radiation protective features to Ilmit doses in restricted and unres tricted areas to levels no greater than permitted by 10 CFR 20, under normal operating conditions, and to a level below criterion 19, Appendix A, 10 CFR 50 recommendations under accident condi tions.
. c. The reactor room doors are self-closing and-locking.
- 16.6 ADMINSTRATIVE CONTROLS 16.6.1 ORG ANIZATION The administrative organization for control cf the rea-
~
tor f acility and its operation shall be as set forth in Figure 16-1
. attached hereto. The authorities and responsibilities set forth
- below are designed to comply with the intent and requirements for .
administrative controls of the reactor facility as set forth by the Nuclear Regulatory Commission.
16.6.1.1 PRESIDENT The President is the chief Administrative Officer respon-sible for the University and in whose name the application for licens-Ing is made.
16.6.1.2 EXECUTIVE VICE PRESIDENT AND PROVOST. The executive Vice President and Provost reports to the President and is responsible for the in-ternal administration of the University, both academic and non-academic. In this capacity he represents the President in all matters
. pertaining to the reactor except in those cases of health and safety for which the Radiation Safety Committee has authority.
". . 16-12 ,
j
--r - - -
a w-
16.6.1.3 DEAN OF ENGINEERING AND ARCHITECTURE. The Decn of Engineering cnd .
Architecture is responsible to the Executive Vice President and -
Provost for all departments in the School of Engineering and Archi-tecture. In this capacity he shall have final authority and ulti-mate responsibility for the reactor faci 11ty and, within the limita-tions set forth by the facIIIty IIcense, make final policy decisions
. with respect to reactor operation; appoint the Reactor Admi.nistrator,
' wlth the advice of the Chairman of the Department of Mechahical Engineering; be advised on all matters concerning reactor safety by the Reactor Safety Comitt,ee.
16.6.1.4 CHAIRMAN, DEPARTMENT OF MECHANICAL ENGINEERING. The Chairman of the Department of Mechanical Engineering is responsible to the Dean of
- Engineering and Architecture for the routine functionli ; of the rea-
- tor facility. He shall advise the Dean of Engineering and Architec-ture concerning the appointment of the, Reactor Administrator; and appoint the members of the Reactor Safety Conrnittee.
16.6.1.5 REACTOR ADMINISTRATOR The Reactor Administrator is responsible to the Chairman of Mechanical Engineering Departme'nt for the daily admin- .
Istration of the reactor facility. In this capacity, he shall, within l
- the policies set forth by the Chairman and the facility license, pre-pare all regulations for the facility, review and approve all pro-1 . cedures, seek approval of all procedures and proposals for changes
- and experiments from the Radiation .
Safety Comittee, and
> be responsible for the health and safety of all personnel in the reac-
! tor facility. He shall be responsible for the official flies of the facility, including storage of such prescribed logs and records of the
-- facility which are no longer required for current operations. Prior
. to periods of scheduled absence, he shall designate an alternate and notify the Chai rman.
. x
- 16.6.1.6NREACTOR SUPERVISOR The RS shall be a IIcensed SRO. He shall be
- responsible for the preparation, promulgation, and enforcement of
' i administrative controls including all rules, regulations, instructions !
and operating procedures to ensure that the facility is operated in a safe, competent, ald' authorized manner at all times. He shall direct the activities of Operators and Technicians in the daily oper-ation of the reactor; schedule reacto(operations and maintenance; be
. , responsible for the preparation and authentication of all prescribed logs and operating records of the facility;3Dthor,lze all experiments, ri procedures, and changes thereto which have first receivsd approval of the Reactor Safety Committee, the Radiation Safety mittee, and the Reactor Administrator, and be responsible for thex
\ Com-
- preparation of all instructional manuals and experimental procedures
- Involving use of the reactor. The Reactor Supervisor shall advise the Reactor Administrator of any scheduled periods 'of absence.
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16.6.1.7 REACTOR OPERATORS Reactor Operators shall be responsible for-the manipulation of the reactor controls, monitoring opnst'rnentation, operation of reactor related equipment, anjdaintenance of complete
.. and curreWrecords during operation of-the faci.lity. The Reactor Operator shall be I'n' direct charge'of the reactor <onsole at all times during reactor operation-en~d when the -cca'ctor is not secured and con-form to the rulesf-intructions, and procelu'res-established by tne Reactor Administrator and Reactor Supervisor for opelalTon-okthe
./ -N'
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16 -13
- - . w----ye- - - - -ye-2* --+-- - , . - ,=m 7 e -e , -.ws w.,w---.g g --g , . , . ,,.y-
j, rGactor cnd the parformanca of experiments. - .
16.'6.1.8 REACTOR SAFETY COMMITTEE _ The Reactor Safety Committee (RSC) shcIl j',
g be responsible for independant reviews cnd audits of feel 1Ity oper- .
s ations to insure that the reactor is operated in a safe and compe- -
!* tent manner and advise the Reactor Administrator in all matters related to reactor safety and personnel safety. ,-
i j 16.6.1.3 RADI A7 ION SAFETY COMMITTEE. The Chairman of the Radiation Safety Comittee shall be appointed by the Executive Vice President and
]1 Provost (EVPF). Additional members of the Committee shall be appoint-I* ed by the EVPP with the advice of the Chairman. The Committee shall i advise the EVPP in all matters concerning radiological aspects of i the health and safety of personnel who might be exposed to radiation
]* produced by University owned and/or operated sources or equipment.
2 The committee shall review, approve and promulgate a Radiation Safety Manual for the University. The Committee shall be informed f .
of all occurrences related to radiation health and safety and reactor s
I safety which are reportable to any authorities outside the University
} and advise the EVPP of such occurrences and make recommendations to the EVPP with regard to such matters. .' -
l 16.6.1.10 RADIATION SAFETY OFFICER. The Radiation Safety Officer (RS0) shall .
be appointed by the Executive Vice President and Provost, with the
' - advice of the Chairman of the Radiation Safety Committee. He is responsible to the Chairman for the day-to-day administration of the j radiation safety program and shall serve as the Secretary of the j Radiation Safety Comittee and as an ex officio member of the Reactor 1 Safety Comi ttee. He shall prepare the University's Radiation Safety i Manual and have the authority to enforce the regulations , rules and j procedures set forth in the Radiation Safety Manual, suspend the oper-
.ation and use of radiation producing devices when their use is in 1 violation of these rules, and secure such sources of radiation until
- corrective action is taken. He shall also have the authori ty to dis-l approve the acquisition of radiation producing sources until satis-i factory evidence is presented to ensure the safe storage and use of these facilities. The Radiation Safety Officer is also responsible il for preparing, for the signature of the Chairman of the Radiation Safety Committee, reports of all reportable occurrences to the appro-priate regulatory agency and for ensuring that appropriate follow-up N x action is taken.
N .
5 -
16.6.1.11 OPERATING STAFF * -
N ,
aNThe minimum staff during any time in which the reacto Is-not shutdwr1 (1) shall consist of:
- 1. A licensed-reactor operator in th ett ol room (RO).
- 2. A second person prey.n t the facility compicx capable of carrying out4 ny prescribed written instructions and s
instructio~ns of operators and to simunon help in the event the licensed operator becomes inclpacitated.
1 Unexpected absence for a period of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or'les tfor
'i this person is accepta obtain a replacement.(gle providing action is taken't'oN (1) Reactor Shutd6wh is- defined in Section 16.1 (2) See page' 16-15 -
s 9 .
l* 16-14 i
. . , ds- msamenenaug scactor vpet.aor utsv/. ITTRitere are more than one licensed operators at ,the facility, shall .
. .ba readily available on call. If there is only ona
. [ licensed operator, he shall be an SRO and shall also ,
fulfill sub paragraph 1 above. /- ,
% ,/
- a. "Readily Availabic on Call: is defined to mean /
.an individual who (1) has been specifically designated and whose designation is known to N , the RO, (2) keeps the RO informed of where he
\ may be rapidly contacted by phone, and (3)/is
\ capabic of getting,to the reactor facilit'y
\ within a reasonabic time period under normal
\ conditions (e.g.', 30 minutes or within' a 20
__ y mile radius). /
\ .
/
16.6.2 \ STAFF QUAllFICATIONS The Reactor Administ/ator, Reactor Supervisor,
\ Reactor Operator, and any Technicians pe7f orming work on the reactor
'shall meet the minimum quali f.ications s,e~t forth in ANS 15.4 "Standarde fsq Selection and Training of Personnel for Research Pea c t o,rs".
s The qualifications of the Reactor fety Sa/
Committee membe'rs shall be five (5) years of professional ex in the field represented by the m:mber or a baccalaureate'p'erience degree plus at least two years -
expe ri enc'e. Generally, these /ommittee members will be made uo of University \facul ty; but outsi edexperience may be sought in areas where additi'onal experience /Is considered necessary by the Chairman of
.I Mechanical En'gineering Dep6rtment. In this case, a baccalaureate
.! degree plus five, (5) year's expericnce will be required.
N /
16.6.3 TRAINING The Reactor for the f aciIity retrainin 'p/rogram.Administrator shall be responsible
\
16.6.4 REACTOR SAFETY C ITTEE REVIEVS, AUDITS, AND AUTHORITY
/ \
16.6.4.1 MEETINGS AND QUORUM The Reactor Safety Committee shall meet as
- necessary but at least twihe each calendar year. A quorum for review shall consist of the ' chairman, or his designated alternate, and two pt'her members , or alt'ernate members as long as' a majori ty of thos,e present shall be regular members, and shall include repre-sentat/on in reactor operations and radiation protection. However, the operating staff shall not be hvoting majority.
. . / \
.i
- 16.6.4.2 ALTERNATES Alternate members may be appointed by the Chairman of chanical Engineering Department to s'arve on a temporary basis; each appointment shall be in writing. No more than two alt'ernates shall participate on a voting basis in Re' actor Safety Committee activities at any one time.
16.6,4.3 REVIEVS The Reactor Safety Committee shall review:
- a. Safety evaluations for (1) changes to proce es, equipment or
- systems and (2) tests or experiments , conducted, without Nuclear Regulatory Commission approval under the provision of Section 50.59, 10 CFR, to verify that such actions do not constitute an
. / - unreviewed safety question.
~
/ \
) Persons capable of performing emergency procedures shall be autho'rized by b / the Reactor Supervisor; be familiar with the Emergency Plan and capable of l / InltIating the Evacuation Alarm; know the locations and be capable of, using '
,/, emergency and radiation survey equipment.
/ - .
[ . 16-15
w
"- -; b. Proposed changes to procedures, squipmsnt or systcms that chang's ;
the original intent or use, and are non-conservative, or thos'e -
1 that involve an unreviewed safety quest' ion as defined in Section 50.59, 10CFR.
j/
- c. Proposed tes ts or experiments which are signi ficantly'di f ferent l7 ,.
f.om previous approved tests or experiments , or those that involve
.- an unreviewed safety question as defined in Section/50.59,10 CFR.
.'? /
- d. Proposed changes in Tec,hnical Specifications or licenses,
- e. Violations of applicable s tatutes, codes, reg,ulations, orders, Technical Specifications, license requirements, or of internal
- z. procedures or instructions having nuclear [afety significance.
. . . i
- f. Significant operating abnormalities or , deviations from normal and xpected performance of facility equipment that affect nuclear saf y
- g. Events wgich have been reported i,n writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to .
the Nucleer Regulatory Commission.
- h. Audit repor 5
_, 16.6.4.4 AUDITS Audits of facIIIty act vities shall be performed under the cognizance of the Re' actor Saf'ety Comittee but in no case by the personnel responsibleMor the item audited. Individual audits may be performed by one indivi' dual who need not be an identified Reactor Safety Committee member.' These audits shall examine the operating records and encompass:
- a. The conformance/of facility operation to the Technical Specifications'and appilcab e license conditions, at least once per 12 m'onths.
- b. The performance, training and q 'alifications of the entire facili staff, at least once pe 24 months.
- c. The results of all actions taken to correct deficien~cies occo' ring in facility equipment, struc1;ures, , systems or method
. y .~
of' operation that affect nuclear safet'? at least once per-calendar year.
d./The Facility Emergency Plan and implementin procedures , at
/ 'least once per 24 months.
j e. The Facility Security Plan and implementing pro dures, at least
/ once per 24 months.
- f. Any other area of facility operation considered appro riate by the Reactor Safety Comittee or the Chairman of Mecha cal Engin-
/"
., eering Department.
f l
16.6.4.5' AUTHORITY The Reactor Safety Committee shall report to the Chairman of Mechanical Engineering Department and advise the Reactor Adminis-j trator on those areas of responsibility specified in sections 16.'6.4.3
.and 1*6.6.4.4. '
.16-16
. ir t "P. , _ _ _ _ _ . .
l.
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. g .' -
y-s 16.6.4.6 _ RECORDS AND REPORTS OF THE REACTOR SAFETY COMMITTEE Tha chairm:n/of the Reactor Safety Commi ttee shall prepare, maintain, and distribute *
/
\ records of its activities as Indicated below:
\ ,/
- a. Minutes of each Reactor Safety Comittee meeting shall b'e pre-pared, and forwarded to the Chairman of Mechanical Engineering
'- each meeting.
and the Committee members within 30 days follwing/ c
\*
\ b. Reports of all reviews and audits shall be prepardd and forwarded
\ to the Chai rman of Mechanical Engineering withip 30 days folim-N Ing completion of the review or immediately upon completion if
\ corrective action is requi red.
' c. Reviews of approvals requested by the Reactor Administrator for i
\ proposed Engineeringchanges shall be forwarded to ttfe Chairman of Me upon completion.
16.6.5 APPROVALS The procedure for obtaining, approval for any change, mod-Ification, or other item which requires approva,1 of the Reactor Saf-ety Committee s shall be as follms: .
\
- 1. The Reactor Supervisor shall, prepare a proposal for review of the Reactor Administrator who shall submit it for approval to I the Reacto'r, Safety Commi ttee. The Reactor Safety Committee 4 shall be res'ponsible for/ review and audit as prescribed in
'( Section 16.6.4 A copy of the findings of this committee shall
- be submitted to'\the Radiation Safety Officer for action as re-t quired by the University Radiation Safety Comittee.
'/
The Reactor Adminis\rator shall submit copies of proposals
~
2.
- reviewed by the/ Reachor Safety Committee to the Chairman of Mechanical Engineering \ -
- / \
The Reactor' Administratorishall upon receipt of the required i 3 approvals /f rom the Reactor Safety Commi ttee and the Radiation Safety , Committee authorize th,e Reactor Supervisor to proceed with the proposed change or modification.
/ .\
PROCEDURES There shall be written operating procedures that cover 16.6.6 i -
the following activities. They shall'be approved by the Reactor
! Ad I61strator.
- a. Conduct of irradiations and experiment \ that could affect the operation or safety of the reactor.
/ .
- b. Startup, operation, and shutdown of the reactor.
\
- c. Fuel movement and changes to the core and expe(iments that j
/. can effect the reactivity. N
. ,.! d. Preventive or corrective maintenance which could ave an effect
/" on the safety of the reactor.
f
/ e. Surveillance, testing and calibration of instruments, components and systems involving nuclear safety.
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- 16-17 s
,- N
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L . _. _ _ _ _ _ _ __ _ _ _ _ _
V. . .
- e. <N -
, .r .,
. f. R view cnd cpproval of changes to proceduras. .
I .
- g. Personnel radiation protection consistent with 10 CFR Part 20.
- h. Implementation of the Security Plan and Emergency Plan.
- i. Administrative control of operation and maintenance. /
/
]) /
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Though substantive changes to the above procedures shall/be made only I s changes to the s with approval procedures thatbydothe notReactor, Administrator, chadge their original intenttemporary ma 'y be made by the Reactor Supervisor. All such temporary changes shall be docu-f
.- mented, and subsequently approved by the Reactor Administrator within 4 \ 14 days. ,e
,t t 16.6.7 EXPERIMENTS /
j 3 x
.j a.
f Prior to initiating any new reactor experiment, e.g. , class of experiments that could affect reactlyf ty of the reactor or result in ' release of radioactive materials, an experiment plan shall be .
prepared, reviewed by the Reactor, safety Committee, and the Radiation Safety Committee and approved by the Reactor Administra-tor. \N
'.I *
- b. Each experiment plan shall (1) Identify the type of experiment (previously ' approved or ree'ently reviewed per 16.6.4), (2) identify
.{ the experimenters and (3 / have been approved by the licensed
-- senior operator \in charg)e of reactor operation.
I _
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- 16.6.8 SAFETY LIMIT VIOLATIONN .The following actions shall be taken in the event a Safety Limit is' violated:
- a. The reactor wilJ[be '\ shd( down irrrnediately and reactor op c
will not be res~umed without authorization by the Nuclear Regula-3 tory Comissjon (NRC). K
/ \
- b. The Safety' Limit violation shqll be reported to the Director of the appropriate NRC Regional Offir.e of Inspection and Enforcement (or his designee), the Chairman \f Mechanical Engineering and to
, the Reactor Safety Con.nittee not later than,the next work day.
. /
A ,S'fety Limit Violation Report shal be prepared. The report
- c. a shall be reviewed by the Reactor Safe g Committee. This report
/shall describe (i) applicable circumstances preceding the viola-
/ tion, (2) effects of the violation upon fhcility components,
/ systems or s tructures , and (3) corrective A tion taken to prevent j
,/ recurrence.
/ d. The Safety Limit Violation Report shall be submitted to theNRC ,
Radiation Safety Comi ttee, the Chairnan of Mechdqical Engineering and the Reactor Administrator within 14 days of the 7; violation. -
/
,I6.6.9 REPORTlHG REQUIREMENTS in addition to the acalicable reporting re-j quirements of TITLE 10, Code of Federal Regulations, the follwing j reports shall be submitted to the Directo: of the appropriate N C
,/ 16-18 \x
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. UG D E N J. ,
1 . . ,
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R .~ .,
/
'\ g I Regional Office unless otherwise noted. -
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- 16.6.9.1 ROUTINE REPORTS
,/
g a. Startup Report. A summary report of plant startup add ng (1)
N powerescalationtestingshallbesubmittedfollow)the/ license l ,\' receipt of an operating license, (2) amendment to 4 \ involving a planned increase in poker level, (3T installation of fuel that has a di fferent design, and (4) 'ridifications N that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The/ report shall
\N address each of the tests identified in th'e Hazards Summary I Report (hereinaf ter Safety Analysis Report) and shall In i
\N general include a description of the me'asured values of
\ the operating conditions or charagteristics obtained during i 'the tes t program and a comparison of' these values with '
! design predictions and specifications. Any corrective
' actions that were required to obt'ain satisfactory operation shall aiso be described. Any additional specific details -
requir\d in license condi tion.s' based on other commitments
- shall b'e included in this refort.
x /
Startup reports shall bej$ubmitted within (1) 90 days ie folicwing completion of/the startup test program, (2) 90 days folicwing resufnption or commencement of pcwer operation, (3)'9 morgths following initial criticality,
' *i~
whichever is ear' lies t. If the Startup Report does not cover all three events (i.e. Initial criticality, completion of startup test,f ro'g(am and resumption or commencement of power operation), supplementary s
reports shall be submitted at least eve 7y three months untill all three events have t been completed.
- - b. , Annual Ooerating Report Routine operating reports covering the opyration of the unit du' ring the previous calendar year should be submitted prior to Narch 31 of each year.
T annual operating reports. mad by licensees shall provide e' comprehensive sumary of the opehating experience having
- safety significance that was gained 'during the year, even though some repetition of previously reported information may be involved. References in the annual operating report
.to previously submitted reports shall be' clear.
Each annual operating report shall include:
(1) A brief narrative sumary of .
' ~
(a) Changes in fact ilty design, performance characteristics.
' I and operating procedures related to reactbr safety that
' occured during the reporting period.
I I
k (b) 'Results of major surveillance tests and inspect. ions. N
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. 16-19 \ \
\
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I L
(2) A monthly tabulation showing the hours the reactor ,
is operating.
(3) List of the unscheduled shutdowns, including the reasons therefore and corrective action taken, i f any.
[
/
(4) Discussion of the major safety related correctJve maintenance performed during the period, including 7
\N the effects, if any, on the safe operation pf the reactor, and the seasons for the corrective maintenance required. *
/
/
(5) A brief description of:
(a) Each change to the facility to the extent that it changes a description of the/ facility in the appli-
\' cation for IIcense and amendments thereto.
/ .-
(b) Changes to the procedur,es as described in Facility Technical Spect flcations. ,
(c) Any new or untried,e'yperiments or tests performed during the reporting period.
,^ N /
- (6) A summary of the safety evaluation made for each change,
,! test, or ' experiment not submitted for NRC approval pur-
' suant to 10 gCFR 50.59 which clearly shows the reason
. leading to thejconclusion that no unreviewed safety question exi and that no technical specification change was yequ' ed.
)
(7) A summary /of the n released or discharg(ure e to the and amount environs of radioactive beyond the effective effluen '
contr,o1 of the licens s determined at or prior to the point of such release o di s cha rge. -
/
. (a) Liquid Vaste (sumari d on a 3 month basis)
, (I) Total estimated quan (ty of radioactivir.y released (in curies) and Total volume (in liters) of
- effluent water (includin diluent) released.
-(b) Airborne Waste (Sumarized on aQ month basis)'
/ -
(1) Total estimated quantity of radioactivity
\
/
/ released (in curies) determined y an approved sampling and counting method.
/.
j! (c) Soild Waste (suminarized on an annual bas'is (1) Total amount of solid waste packaged (I cubic j/ !, meters)
\
/
/
(2) Total activity in solid waste (in curies) \
\
(3) The dates of shipments and disposition (if \
shipped off sJte).
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16-20 1 /< /
\
Q
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e (8) description of the results of any environmental radiological .
' [.Y surveys performed outside the facility. .
I \ (9) Radiation Exposure - A sumary of radiation exposures gre'ater than 100 mrem (50 mrem for persons under 18 years of ag'e) received
,k during the reporting period by facility personnel or,vistors.
'l j
- W ~ ,
REPORTABLE OCCURENCES Reportable occurences, includin9 causes y 16.6,9 2
-@ . probable consequences, corrective actions and measure's to prevent 2 recurrence, shall be reported to the NRC. Supplem9ntal reports may 7
be required to fully describe final resolution of/the occurrence.
,ga in case of corrected or supplemental reports, W amended IIcensee event report shall be completed and reference shall be made to the original report date. /
J[Je ? -
/
a.\\ Prompt Notification With Vrltten Followuo. The types of events
. .,g.
1,*
b listed below shall be reported as expeditiously as possible by N telephone s
and confirmed by telegraph, mailgram, or facsi'mlie
- transmission to the Director of the appropriate NRC Regional Office, or his designated representative no' later than the first
- work day follwing the event,,w'ith a written follwup report within two weeks. Information provided shall contain narrative materia 1\ to provide complete' explanation of the circumstances
- th ,/
surroundin'g\eevent.
't (1) Failure of the rea/ctor protection system or other systems
,T subject thglimiting safety system settings to initiate the required protec'tive function by the time a monitored para-meter reacheW(the setpoint specified as the limiting safety
- system setti'nggin the technical specifications or failure to complete the required protective function.
Operatjon / of the\ react >r or affected systems when any para-3 (2) f meterfor operation hbject to a limiting condition is less
d conservative than the\ limiting condition for operation est'ablished in the technical specifications without taking permitted remedial acti .
(3)' Abnormal degradation discovgred in a fission product barrier, i.e. , cracked fuel disc, primary gas-tight seals.
c.:[ ,
N
% Reactivity balance anomalies involving:
l '" (4) ,
,- (a) disagreement between expecte Kand actual critical positions of approximately 0.3 ak/k; (b)
,+
exceeding excess reactivity limit;\
(c) shutdmn margin less conservative th' specified in l technical specifications;
{
- l .y
/* ' (d) unexpected short-term reactivity changes that resulted
[ ., In a period of 10 seconds or less;
/ (e) If sub-critical, an unplanned reactivity insertion of l
i more than approximately 0.5% ak/k or any unpla'nned
\
'e - criticality. .
16-21
\x
\ '
~
'v 1
- \ . (5) Follure or malfunction of cna (or more) component (s) which pre- -
' N vents or could prevent, by itself, the fulfillment of the/ function- i al requirements of system (s) used to cope with accidents / analyzed in the Safety Analysis Report. /
. /
(6) Personnel error or procedural inadequacy which prevents, or could 3
prevent, by itself, the fulfillment of the funt t.lon'ai requi re-
.; x ments of systems required to cope with accidents 'nalyzed in
- \ Safety Analysis Report.
e
. (7) Unscheduled Conditions' arising f rom natural or man-made events N that, as a direct result of the event requJ/e reactor shutdown,
\ operation of safety systems, cr other protective measures required
\ b Technical Specifications. /
\(8) Errors discovered in the transient or/ accident -
analyses or in the
\ methods used for such analyses as de' scribed in the Safety Analysis i Report or in the bases for the Tech'nical Specifications that have '
o'rycould have permitted reactor o$eration in a manner less con-servative than assumed in the slyses. ,
\
(9) Perfomance of structures , s, stems , or components that requi res remedialg action or correctJve measures to prevent operation in
- a manner 'less conservative than assumed in the accident analysis
- in the Safety Analysis pdport or technical specifications bases;
_ or discovery \during plant life of conditions not specifically 2 *! considered in'the Safdty Analysis Report or Technical Speci fica-I tions that require 7emedial action or corrective measures to prevent .the existence or development of an unsafe condition.
t 16.6.9 3 SPECIAl. REPORTS Spe/\
ciai\ reports which may be required by the Nuclear 4 Regulatory Comis,sion shar) b'e submitted to the Director of the 4 appropriate NRC Regional Office within the time period specified for each report.
16.6.10 RECORDRETEdl0N
/
16.6.10.1 Records to be Retained for ,a Periodsof at least five years:
Ope
\
/ logs or data which shallgidentify:
- a. rating ,
/ \
'j1. Completion of pre-startup checkout, startup, power changes, and shutdcun of the reactor.
- 2. Installation or removal of fuel elem'ents , control rods or experiments that could af fect core reac,tivity.
\
3 Installation or removal of Jumpers, speci'ai tags or notices ,
or other temporary changes to reactor safety, circuitry.
- 4. Rod worth measurements and other reactivity measurements.
\
\
.b. Principal maintenance operations. -
- c. Reportable occurrences.
\x
\
\
,' l 16-22 \
., /
~ ~ -
ess.. er sse.
- r ,
d' "
\ d. Survelliance activities required by technical specifications. *
- e. Facility radiation and contamination surveys.
. f.
N .
Experiments performed with the reactor.
\
This requirement may:be-satisfied by the normal operations / log book P l us,
[ "
- 1. Records of radioaptIve malerlal transferred from the facility as required by IIcense.
- 2. - Records required by the Reactor Safety Cbnvoittee for the performance of new or special experiments.
i N
- g. Changes to operating procedures.
N 16.6.10.2 Records to be retained for the life of the facility: -
- a. Gaseous and IIquid radioactive effluents released to the environs. .
- b. Appropriate off-site environmental monitoring surveys.
1 c. Fuel inventories and fuel transfers.
'r
,I d. Radiation exposures for all personnel.
- e. Updated as-built drawings of the facility.
- f. Records of transient or operational cycles for those components ,
designed for a limited number of transients or cycles.
- g. Records of training and qualification for members of the facility
- staff,
- h. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10CFR 50.59 .
. 1. Records of meetings of the Reactor Safety Committee.
1
. I
- l j
t-i 16-23 i
.4
4
( =
Vech Epscs. '
. . .~ . .
LIMITING CONDITIO!!S FOR OPERATION, lilSTRUMENTATION K
. TABLE 16-1 v
\\ -
/
Ng . ,
/
Safety Channel Set Point Function j/
Nuclea ' Safety #1 Lcw count rate -
> 120 cpm scra9 elow b 120 cpm N , ./ .
Nuclear Safettx#2 (log) ,
j' r High power \ < 0.2 watts 7 scram at pcwer > 0.2 watts Low power > 0.5 x 10-I3 amps / scram at soygce levels
. s / < 0.5 x to amps t Reactor period > 8 sec / scram at period < B sec Nuclear safety #3 (linear)\
k $ 0.2 waty /
High power scram 'at powe r >. 0.2 wat t Low power \> 5% full scale scram at source levels T '
< 5% of full scale .
s
, Shield water temperature 15'C scram at temperature < 15*C Shield water level < 10.5
~
ches scram at water levels > 10.5
/ Inches below highest point
/ \s on manhold opening
.i '
Seismic displacement'
/
$ /16" 1
NN scram at di:; placements
> 1/16" Manual scra.T -- ' scram at operator option
- Radiation /
monitor --
\
alargat or below level set toxp et requi rements of 10 CF Part 20
/
N x
e 4
O ef e
I
,l-i i 16-24 M
l'
+ i . . ,
' ~
a
- I l- UNIVERSITY EXECUTIVE AUTHORITY .
8 lL L
PRESIDENT '
RADIATION SAFETY -------- EXECUTIVf VICE PRESIDENT AND PROVOST COMMITTEE t.
DEAN, ENGINEERING AND ARCHITECTURE ,
REACTOR '
SAFETY --------- CHAIRMAN, MECHANICAL ENGINEERING COMMITTEE 8
t I
I E
. . . . . . . . . . . . . . . . . . . - REACTOR ADMINISTRATOR REACTOR SUPERVISOR
~
~
REACTOR OPERATORS e
Fid.16-1 ADMINISTRATIVE ORGANIZATION FOR REACTOR CONTROL AND SAFETY
. 16-25
- 3 0
9 ==e.e. . * * .
- m -- - - _ _ _
- _ ___ _ _ _ _ _ _ __ _, ,