ML19323G251

Forwards Comments & Suggested Changes to Tech Specs

ML19323G251
Person / Time
Site:	Armed Forces Radiobiology Research Institute
Issue date:	05/12/1980
From:	John Miller Office of Nuclear Reactor Regulation
To:	Tyler P NAVAL MEDICAL COMMAND, NATIONAL CAPITOL REGION, BETHE
References
NUDOCS 8006020032
Download: ML19323G251 (26)

Text

{{#Wiki_filter:___ '~ THIS DOCUMENT CONTAINS P0OR ~QUAUTY PAGES Pr , t;3a Docket No. 50-170 Capt. Paul Tyler AFFRI National Naval Medical Center ~ Bethesda,MD 20014

Dear Captain Tyler:

We have reviewed your submittal of the Technical Specifications (T-5) for the Armed Forces Radiobiology Reserach Institute. Enclosed is a copy of those pages that have comments and suggested changes. Followigg your review, we.should be pleased to meet with your staff to dis-cuss them. The Project Manager assigned to yoor reactor facility is H. Bernard (492-7435). Sincerely, 31 GIG 33 U 3p, MIM ! 0 James R. Miller, Chief Standardization and Special Projects Branch ~ Division of Licensing

Enclosure:

As stated DISTRIBUTION! SSPB Files Docket ~ Files HBernard RTedesco 6020 b.gQ 800 ,f, PB 0,L,, ,,AD,:DLh.., SSPB D SS 3 3,L orrice y l su.~aue{..H,B ern ard k b,,,,jM,1,l l e r,, ,,,gIgd esco,,, i ~ [80.,,, ,,5/1}/80,,,, l oave) 5,/, l,/8,0,,,, 5,/ [ ~.c e - m. ..,~.c m..

• o. s o m. ~. e ~,,.., ~ 1, ~

c

. cinced in this documen: are the Technical Specifica:Icts and the '3ases" for -J.e Technical Specificatens. These bases, which provide the technical su; pert for the individua.! :achnical specifications, are included for informatien pu ;cses enly. They are not part cf 2e Technics.1 Specifica:! cts, and Sey do ::t c:nstitute Smitatiens ce recuirements to which the !!censee mus: e.dhere. Reference NRC Rep:latory Guide 1.15 and ANSI N373-1974. LO DITINIT*ONS RIACTOR O?IRATING CONDIT'ONS ~ 1.1 RI.AC" CR SHi wOWN The.tacter is shut dcwn when de rese:ce is suberideal by a:less: :ne dcHar ci resetivi:7 1* 2 72 C'"OR SECURID ~he react:r is secured when all the fecewing eendidens are satisf.ed: a. O.e sact:r is shu: dcwn, b. The censcle key switch is in the eff' ;csiden and :te ke7 is removed ' rem tre conscle and under the cene:1 cf a licensed coerater er s:cred in a Iceked s:crage. area, and c_._, No werk is in pregess invel'.-ing jn-cere fuel handli:.g er refueling cpeations, mair.:enance of the reacter er its cen=ci =eenanisms, er insarten er withdrawal of in-e:re experi.:enu. unless sufficient fuel is es=cved to insure a 51.00 shutdown =arpn with the mes: reactve centrol .ed removed. ,3 = -

1. c w~ =.. C o. _v.a.1..*20 N r

Rase :r c;eratien is any c:ndi-icn wherein de. tac::r is.et secursd' , C,_ C....C A _r L. a u,i4, N M -d D.e. sac :r is in de c:Id e-i-ical c:ndi-icn when i: Is :-i-ical-a+-e %.evel a a .a.,,,..,...-- ~ L bod '080ur 40 C. .,,, g %

.e.

.s. .1...w..c..1..-- s.Aou.r C; era:i:n in de steady s a:e =cde shah -.ean steady s a:e cpe sten of y.e reae::r either-by manual :peratien f de cent 1 ::ds er by au c= ate

pera-i:n :f :ne cent:1 r:d iseric :ent:i' 1: pcwer.evsis.= : *,I?r, u U- :;.

. e 2:rans in Table ' and de in:er!ceks in Ta:1e H. e E ge . ~, -...,,, v ---r

r.1.r rs .V ',gg Tha AU.RA program (As Lev As Reasonsbly Achievable) is a progra= , for nain:aining occupational exposures to radiation and release D h -a e 1.05 CHANNIL CAI.IERATION A channel calibrstien censists of using a 'cown signal and ad'usting channel cu put c respctd wit'.in limi s specified by the manufac urer. / I 1.07 ON C ALL. / t A persen is censidered en W1 if: f - (1) the indvidual has been specifically designated and the cperater ' cows of a the desig.aticn; g (2) the individual keecs ce operater pested as to his whereabcuts, and phene number; and de indvidual is capable of get.1.; to the reae:ce facili'y within Sirry-(30) (3) minutes unter ncrmal cir==nstances. 2.0 SA::1Y LDLO AN.) LDITTING SA.:ITY SYSTIM Scru.SGS a,.i c.:.3..: _-.-v. r. e.2..: m _... _t_ry.. _.y... r_,.I.o _r, 2.. e-..e A:elicat!!!- / This specifica-icn applies to the temperature of the reacter fuel Obieetive The object.ve is to define the manimum fuel element tempera re that can be per=itted with c nfidence that no dam' ge to ce fuel element cladding will a result. Soecificatien pc eg,,, # ou The,tec; era:re in a s:andard T3CGA hel element shall. net exceed unde-any cenditiens f cpera:icn. [ g r o'L. T @M C4 f 3 asis ' he impc-.2n: ;arame:ar fcr a ' ?. IGA res.c:cr is de hel elemen: :e:pera:re. O.is pa ameter is weil sud ed as a single scecifica:ica especia!Iy since.it can ::e \\ measured. A less in te in eg. 7 cf the fuel element cladding : uld arise fr:m a build.= :f eneessive pressee betwee. the fuel-c: derat:r and :he :iaddhg !! 2e hei :s nera-re en:eeds ce safe:7 'Imi. The pressee is caused by ce ..,=...,.,s'. r... d. *. 3 '_= e.e..$.. d.. m"-. =..' '.'.-... ".. _".'.*. c ei..a..*....

u..

tyc egen :.-d :i cenium 5 the fuel-cedart:Or. The mag.i uce of tis pressu e is de ermined by :ne hei-ccders :: :e:pers:re and de ra:ic :f -:c :gt e.. :..

...e 1...:.

.._.:.,..,..s.--,.;..

c. : i... i :, as e'..-. *_ '. '....:.d.'..

_s..e .,a.i o. ., -.,.,e :..,.._,,yu.. enc =. ~~ ..e#. - -..,._-..,-=...'.--...-=..=._...- -~~' ~. s ..r-.....w.-. C....... ._ o ..\\ A channel calibra:icn consists of cer. paring a naasured talua \\ \\ k \\ fron :he naasuring channel vi:h a cerresp:nding knern valua cf :he parane:er sc :ha: :he =essuring channel cc:;u: can be k adjus:ed : res;:nd vi:h accep:abic accuracy :o 'ime.-. values cf :he =eas=rez., aries 1e.

o

es:s en t'.is fuel. These da:1 indicate da: the nress in the cladding due :o hydrogen pressee frem the dissccia*ien of ti cenium.hyd-ide wiE tar.'n belcw ce ';i!= ate nress pr:vided 22: 2e tempert:=e f de f;ti d:es.ct exceed 1000 C and the fuel eladding is water eccled.

.4,R 2.2 I.DHTING SAFITY SYSTEM SITTINGS w.

A:clicacEit! 4 This specifi:zin a;;1ies :: 2e scrz:n semings which prevent :he safe y !!ci: from being reached. Obiective The cbjecdve is to prevent the safe:7 2mi's f := being.eached. Scecifiesten De limit; safety syste:n seeings shall net exceed 500 0 as messe ed in en ins;: mented fuel element. Cr.e system wG udli:e an i.s===ented element in the ~5" ri.g and te other wO ur21:e en ins: =ented element in the C' ring. ( 51sts ..A 8.E The limits safety system set-ing is a temper 2 ure which. if exceeded, shah [ g b(/ esuse a reacter sc ant to be initiated preventi.g the safety lip;i: f cm being 'O ) g exceeded. A setting cf 500'C ;revides a safety margin cf 400*C fer nande~' 6 b' / g TF. IGA fuel elements. ,A - j During steady state cperaden, the fitz pea':s in the "C' -ing and dring pulse .n X'.,N cperstien, ce Eux peed in the "3" ring. 3y c""Wg :ne element it:m each j j ring a wcrs; esse indicatien is ressenably assced. 3.0 I DL'-NG CCN21 ONS ?C3 0;I..C*CN . _. s. m,.e. 1.. _ O :. _,. 1. m... y a.., ~ A:eIIeshili _ T..is specificaden ap;Iles : 2e energ7 senersted in te :ese::r 25.g nesd7 ' k. g,. s'

• gg stat = ~.~5 den.

0 M g\\ 2 ycf M....;.n. s u...,. C....;\\ M.W-1 ."%.~ ne -eze : steady nz:s ; ewer '.evel snaE =c: en:eed i.' eg2wans. The '..) .,.f:. ' ' N =cemai netcy na:e :pers:=g ;cwer Smi- :f : e rete::- sna.7 e .0 y' Objective The objective is to assure that the fuel temperature safety limit will not be exceeded during steady state operation. 4 k

The safety limit for the standard TRIGA fuel is based on data, including the large mass of experimental evidence obtained dsring high performance reactor tests on :his fuel. These data' indicate that the stress in the cladding due to hydrogen pres-sure from the dissociation of zirconium hydride will remain below the ultimat yms that the temperature of the fuel does not exceed 1830 F (1000 C and the fuel cladding is water cooTed. 2.2 LIMITING SAFETY SYSTEM SETTING Applicability This specification applies to the scram setting which prevents the safety limit from being reached. Objective The objective is to prevent the safety limits from being reached. Specification The limiting safety system setting shall be 525 C (975 F) as y measured in an instrumented fuel element. The instrumented W element shall be located adjacent to the central bundle with h M. the exception of the corner positions. M %d Basis h l-- The limiting safety system setting is a temperature which, if i I exceeded, shall cause a reactor scram to be initiated pgeventing I $g the safety limit from being exceeded. A setting of 525 C pro-vides a margin of 625 C for FLIP type fuel elements and a margin p of 475 C for standard TRIGA fuel alements. A part of this @g margin is used to account for the difference between the animum and measured temperatures resulting from the actual location of thf the thermocouple. If the thermocouple element were located in the hottest position in the core, the difference between the MN true and measured temperatures would be only a few degrees since the thermocouple junction is at the mid-plane of the element and close to the anticipated hot spot. However, this position is normally not available due to the location of the transient rod. The location of the instrumented element is therefore restricted to the positions closest to the central element. Calculations indicate that, for this case, the true temperature at the hottest location in the core will differ from the measured temperature by no more than 40%. Thus, when the temperature in the thermo-couple element reached the trip setting of 525 C, the true temperature at the hottest logation in a standard core would be no greater than 632 C and 690 C in a mixed core, providing a safgty margin of at least 368 C for standard fuel elements and 460 C for FLIP type elements. These margins are ample to account e y

~ ./ t.- ~ for the remaining uncertainty in the accuracy of the fuel temperature measurement channel and any overshoot in reactor power resulting from a reactor transient during steady state mode operation. In the pulse mode of operation, the same limiting safety system setting will apply. However, the temperature channel will have no effect on limiting the peak powers generated because of its relatively long time constant (seconds) as compared with the width of the pulse (milliseconds). In this mode, however, the temperature trip will act to reduce the amount of energy generated in the entire pulse transient by cutting the " tail" of the energy transient in the event the pulse rod remains stuck in the fully withdrawn position. e e l l l l o l

a Fer purpcses cf testing and calibraden. Ce reac :: :ay be megawa:.s. cpera:ed at pcwer levels net to exceed 1.1 megawat.s d==.g the :esti.g peried. f _ asis Ther=a.1 and hyd aul!c calculatiens 5dcate car T". IGA fuel may be safely cperated up to power levels cf at less: 2.0 megawatts with nan: al eenvective / eccling. 3 3.2. ?.73.C~,TI'Y LB1ITATIONS A: licatE!:v These specificatiens apply to de reactivity cendi:icn of the reae:ce and the.eactivity weres of ceneci rods and exneriments. They apply fer all modes c! cperaticn. Obie::ive .nW The c:feedve is to that the reactor ce.n be shut dcwn at all times l and t: a::s=e cka* the fuel temocran::e safet.ili: y.ww. w,) ' Scecificatiens 1 =animum av'Nble excess reactivity abcve e:id ..ical wi.h The a. er witheut all em:erimer.:s in place shall be s,.00 e.s,7. d. j o s O.e minimum shut down =argin provided by the re=ai.i.g c:nrel b.

4s with ce = cst :sactve cent:1 red fully wi-J.d awn er remcved shall be 51.00 (0.~0% Sk/k).

Bases The s ::down. =argin assets ;".a: the reae:ct esn te shut dewn frc: any - - ' ' - in

pers-i.g c ndi-ica even if de hig".est wer.h ::nr:1 ::d th:uld the i.:2-wit'.c swn pesi:icr

n_ _-_ viC D:_ n.:.. 2. 2 O N.-

a. 2.

...t_:..

This specifica:icr. applies tc _te enegJ gsnerated in -he :sse::: as a :ss--l-a.. n.._.:, e ___,,.,_.: cn..'.- *..* c.'.'u' ~... u.,...,-u.... .e. r,. . z. z. >:..... ...u,

s....

m...,..:e,.,a.,...s.. ua....

e en:eeded.

4 e 9 =e m. ,,e "'te- -* e

Y h. ,, J- .o ,g - Scecif!catien V' ' y> Z~-. The mai. mum step inserden cf reactvity shall be 2.5 6 Sk/k in 2e :uise mode. o Q Based upen the ?uchs-Nerdheim mae.e=at' cal mede! of ne A_3.7.:-75. GA reacter, an inserden cf 2.5g Sk/k wculd result in a ma.tmum ave-age fuel 4c s < ex m w.ce et.less than 4so,.c, ther&y staying w\\-w.A,the limiting -b ithin tepperat-w.v~ y yw >y My Am N -' #y 3.4 CONT'3.01. A.ND SAIITT SYSTEM ,>l ov.U,..Wef, o 0 c9. ;s.. Q 4 / 3.4.1 Sc-a. : Time p.

2. o1.:

c4 s v e #2 "

• W W )'~

This specificaden applies to the time recui ed fer P.he;FenecI reds'.s'fe-f c.ully inserted frem the $ne that a. safety channel varianle reache .e Safety f . v. s e e.e 4. Objective . The o' jec-ive is to achieve pecmpt shutdewn of the rese:ct to preven: fuet c ' damage. Sceci!!caden The time frem sc am ini.'.atien to fun inserten of any cent: ci red shal:. not f exceed :: e seccad. Basis

• his specif!caden e.:sres dat the react:r will be premptly shuc hwn when II;erience and analysis incicate ta: ':: the j a sc am sirnal is initated.

range ci ra.sie. s anticipated fer a T?. GA rese: r te specified sc am dme is adeg:.2:a s asrce 2e safe:7 ef the react:r. 3.4.2 ?.eac::: :en-ei Svstem A:clic1:il!- r This speci'!catien applies to the cha.nels =cnit:rt.; the eae:: =cre which g3......'.d e ' #.-.. a

9.. - =._= c..r.. e. a_... ^ _.-. = a...-..,. *. - _ '....

Obfeedve .......,.........._..n.... %...e ,,.e.. _. e.,......a....,. >,..,..,.:... ?.. e... c.. r. l ..N4 w.,

e .t. s.p4 4:. g. 3 e. " ' * * n *.'.s. a-s..,. .,,,,.z11, c t w..,. e.. A. o.t. a.gs *.... c o e""*"s * *.2" * *I ' icilewir.g.zY.e are ege:2:le. .yan. so.

.e,,..a. v u., d.

Coer =M e 5.5.

P sa

.3 .essurin: Cunnel v 9 x

... i :.,.

.. e... 1 1.ineer.-: ar uvei I I 0g p,3 !.0g ?c'ae.'- U'ItI X 3 r,. n~'.'.:. 6 Powe. Go.o v (2) (i) d '^- Q ' Safety Cunnels ~. A .C.. E,. .t,, m... ..wn <.3 a.E,-.a.VE.. s.. - p ~n . w ) s ?zsis

7. ".el.e..., ** *.~-. "e izv. =..3 a *. '.e c.r...i. s* 3 7 a *.-.r.*.'.".cus '.......a".n 3

en t'ls part=e:s: wb.ich P.15 a'specified sale:7 li:ni:. T'..e pcwer level cel : s -y t'.e sa_ct:r ': ewer level is adecua. elv =crl:: red for 'cet'. ste assure tha.: l vel .~ %; eien .,. ;,..ce~- - L.W.e st:en? The scec:.f'esticas e i i st.ite and ;cs.g. cces :: c. --.s..;..s. sin...a.. .ow., ,y.: i s- ..e. w .r..e.,..,.., -... m -...=5.

1. n. m... :,.,.z.

1.... w...,.e .st.cs.. :., .:,... a..a s 4,,- e,_.:n..e..a _.. ::,,... e .,.... a. e...: -.. a.- r d.. him. 3.y. -,. e z.,... .u., ..g ...,.i _g... g,..: . 1..,

r-

~ .a, -..:,. 2......,, e..: e. r e<- .-- e.' *.. = c e" n,...e -.. -s.. e ....,.u. .,.. s.,., s.,., s..... .....z... ; ,.,. a..a.u,,a :. u... .._..c.,-,.,.:,.. I I I { m - 4 g--m,mx w v

-ases ...ee.,_,,.-.y.............._....._. u.. eg_... _..,..ge.,,y. %..e.<...: d:wn belcre de sale:r limit en ne fuel elece.: ce : sat:ce er. ::e sr.t.: .... c,,,,,..... s i. ... c.. _.... :..... 3_: c.w.,.w. . s.. ..... e, _. .a._.. e x.w..s.. f.1.'.eeven: ef m.. ccw. r.e s se91f an t. safe er anner=al eendi-ica ecturs.fer :P.e safe ~ fzilure cf te ecwer sup;1v. w4.. w,.e. adec. z.. _+ -..-..*~= " en = -. =.v a..'s ed ~. '..e,.res e *. "_... e- ' _ -.s ".a s /".i A,/ i c c.\\ cwe level will reducs :: a Icw level af er pulsing. i a ce reac::: r e ,.=i L ' -.=..,s1.C. c..rl. , = - 1..,fm. I O.1 __,. s, a v.. o..n a. 3 %.w m s. u_d. M. ede :.. iP..i.e. T_.". a. '.. e G eS ... sse ,e. e.. _t_,. e: e..: _._..:__ e s.., ._s e.. .. %w I .I A

1. . ?c:st:. ewe.-

I'.0% mix ;cwer 1 .z / ~.t ) .C _, _ = 2: :,7. e ,e.:. w

w..

.t j 'ea.*.*#.1 G.= bCo. . tC'J.'3 M* *.a. D s I \\ (

• wL=..a e e r. ".'"

8..='=.._ .=f/ X/

• o 15 sec:nd.s f f M'd W

1. SU h*ICW

/ IY&Ie! leVe1 N'A.ct 3 !s. 30Cl'Ya:8.- [ eVel s, e.. r. a s:v 9' y

e. ~.

( '/. g A . a n@i 7 X-C T,.... n m. T C31 T.=CC.s 2

• 1-e
• C w.

.m 4 C.. :._.._:..._..._,..r..- 2 I I-

i. dependent e acneis';

500 C j .s. n,.. e. . _ *e .s '..:.4.... C.#. ."*s. .. G. 3.y w a. ~

*.a. :.. ?.,,ns

- a.p._.:.,: I I/ Fewer L.- b .,8M E. h . _ _b y. f %_ _ _. _r./._'._ _ _ _ _ g _ _ _ _ _= __". e 1

• 1

.a. 9 ---rt-- ,,,,,e -9 yv... +-. +*v

~. _ _. .y h.d.tM(' s p}.-l s..,_. a ..D W. y..:y_ a

.,.v C. 2

\\, su s lacde in 'h?ich F.!fecMye SS Pulse

. d

n ? evented

!. Si= 1:2.eces manual withd swal cf two standard X een:rel :ds. 7 3a a. ?ied awil e.f any eeneci element except 7 1 ...: *. d. - u i2 A 9$ X n s

3. Pe.ise bitiaticn EU;cwe '.evels prsater than 1 kwj j

u .f 'l '

A A A-q. E L 9 -- 0 4. IS - 2 '# [ ~ 7

'l, g, A n.e hter!cck :c ;revent de initiaden of a pulse above 1(kW is to assure that the / =ap.itude Of te :ulse will ct esese de fuel element tempw" ~ safe:7 hm::s te J i be exceeded, n.e" 5tericck to preven withdrawal :f me standard cen= 1 reds in te pulse mode is.o ;revent ~'e reseter from being pulsed while :n a pesitive peried. wall > h -3 w KW 3.4.4-Facili:; 5:erleck S :5.em .s.. n,..nns.f nds specifica-icn app!!es to the inter! cks which prevent zecidentzi expcsure cf an indi.idualin eite: expere.re recc. Obfective n.e ebjee:ive is to provide sufficient war-J. g and intedecks := preven: =cve-ment =f Oe reset:r core to 2.e ex;csure cem in which semeene may be werx=g. Sceci"est: s. Facilhy 5:aric; ta:' te ;r:vided such t'.z:: ~he.7 set:r es...ct be :pers:ed urless de lead s.lel* r d:ces within de / a. reae:::;cci are eie.er fully ::ened :: fdy ciesed. 2 [:. O.e sac :r canne: be cpersted uniess de expcsure recm plus deer ad.'acen: :s de rese::r ::re ;csi-ic: is fully ci: sed and ce' lead shieldin- ^ "y ciesed; :: if :he lead shielding d:c s *- ^ "y :p=_.ed, bets dec~ 2-= e= res ::cm ;ing deces mus: :e N!'y e.1:sec. 1 I l i o 4 e,ep s w -g

l

s. < '"

O" - s a-r- OtU J'd'..u n. The_;eacnt_cannet be_._epelsted unless a warning hern has scunded i:: an f c. e=;:cr.re cm whe:e cperat en er movement of the reacter wec.d cause an t. safe eend:icn. ~m. m p& Q MrbWyjyy.WI tASN" Af V \\* U

feve~mP.: cf de reacter from cne e pesure These inte:11cks physics.uy prevent [irst sounding a wara.ing so that an recm domain :o the ethe withcut.

in the aff ec:ed enesure reem can cperate the " Emergency S:cp" system :o alert the operater and preven: cere movement. 3.5 RADIATION MONITO?. LNG SYSTIM A:olic1bE!:: This specific.ziden app 1!ss o the radation menit: ring inferma: ion which mus-- be a.vailable o ce react:r coerster during reac:ce operaticn. Cbiective The cbjectve is te azree t'.at sufficient radatien meniter:. g i-ferma:icn is availatie to.he co. era:c: := ass =e safe co. ers:icn d -* -== -ar. Scecifica:ica ____ The rese::: s:.all nc be cpeated' :nless the TcIIcwing rada:!cn m'enitoring systems are cpeante: A minimum of :wo area radation mer.iters and a centinucus air menit:r in a the reae:ce room. The area meniter directly ever the reae:c poci. s=.'aee enc de centinucus air mcnit:r shall preduce audbie r.d visible alem sig.als in de cent 01 r:om..The secend area meni:ce in de reac :r

occ s;.all have a visible alarm in de cer.r:1 ccm.

. e Twc a es radatien menit:rs in the ;re;araden rea en de wa." d:ectly

( b. n,/ cypcTi!e bCO ?.2pCs;.:re 3Com il anC I.I' cTJTe 3com 42 ping doc!s : '/ 's AL serve as rada:icn steaming dete :crs, and previde a r.sihie a.a m in.he .-,., -{ - /g cenr:1 :cm. tsa c 1 ra zten detec=: system centnueusly sampling te eff.uent.! :c ne ~. rese::: tui.d:g ven:.lating system exhaus stack and capable cf pr:- m ~ -,1 , 6.. .7 duci..r. a visihie ale = in -he cer.rel :cm. , u.c.: :.y +s .t \\w ~ ' j.L t ' m 6 / 9 .Ab n P x C**OQ ..r LI h5 e - p . si a e ---aw-m g-ep ---,-w

'~ ~I. s*.L.M, d,'Jt. b 27D L. ' >t.'. ..p% 3..4 r \\, m u .G ss i L'- p< s i rf :'.- Bases l.\\. m.- el et any The radatica meniters previde hformaten :c cperatng pe. ~ impendng cr' enist g danger f::= radatien sc tha: :here wD1 be stdficient

.ma.s evacuate ce facility ar.d take the necessa.y 5:eps :o prevent ce spread of radcactivi:7 :s de sur-cundings.

3.S ARGON-41 DISC"ARGE I.DIIT a A:clicability ~ This specificaten a;;1les to the cencenraden cf A gen-41 tha: may be dscharged fr:= the T?. IGA reae:ce facuity. Obfectve To insure e.a: de health and safet7 cf 0.e pub'de is not endangeed by the discharge of Argen-41irem the TRIGA rese:cr facili:7 Soecif!csden An envirenmen 21 =enitcring pregam shall be maintained :: detemine a. effects of de facility en the envirens. If a desimeter read.g fer any envir nmental meniteri.g scaden 5dcates b. that an enpesure of 400 mr above backpotmd has been reached du-ing coeradens-which generate and release meas =ahle the vear, rese:ct 4 'J< -- q::aniides of ArgenN1 will be cur *. ailed to 2 mw/hr per mcnth fer [11./ f f the remainder cf the year. . e.P >l ,x c. If desi=eter read:g fer any envirencental meni:cri.g staden indcates t' 7 /' D c.a: an ex= cst:re cf 500 mr above backgeund has been.eached de.ng the year, reac::: cpendens which geneste and :elesse meast..ble 7 quantnes cf Argen-41 wD1 be ceased fcr te :st:ainder f te year. =.sses The basis fer these e.esces is 3 CF2 20..05, ?c=issible.evels cf adaten in unrestie:ed cess.' Cale=Iatens w. n rega-d :c ce c acentraden cf A :.-4.1 in ai 1: 'ecadens areund AI?.7! indca e tat even du-g sus-i ed coeranens de cener.- aten w~1 nc: appreae. an M?C (ref 5AR) fer en unres -ic:ed ces. Therefers de cenccIling fac cr is :c.21 dese.

4. *.

.O C C f 2". .:. 'y.f. -_ O.."..t. O. T T..1.".. T...T s . T 11., e

c. 2.

p......,.- -s. {g g u..i tt. e.J.,,...

1. ,w

..g,.4.w.. ...w. .,,,.4.....,.,,..,.,,..... a. u 7

cci

e. pes.: e.

..e I ~ A nm e, y,_,

Obieetive / .u4:/

• W -

To insu e ce Msgdt7 cf the resins in the water purifics:icn system. Sceci!!c1 den The reacter will not be cpe ated when the poci tuik water temperature exceeds .o oO C. Basis Manufactr e.ds data sta:es that t.he esins in the water Ou-Zicain systa= break dcwn with sustained cperatien in excess of 50*C. _T N' -NTTT TD _C.2._..i s.' ? 2.'2 "%'..T 'F_N. "i 2...C N ". _*_2 ~ 3... .w =_ A::1!cabE!v This speefficaden app 1!es :: tne cperaden cf the facil! y ven flatien sys:a=. Obiectve The cojec:ive is to assure :. rat the vent.lation system is in cperaden :: mi:igate the censegences cf te pessible release cf radcactive materials resti&g frem reactcr cpersticn. Scecl'iestcn The ete:cr shan net be cperated u:.less ce facility vendiaden sys em is eper-able except fer periods of time necessary :::ermit repair cf the sys em. 'a: the event cf a s.=s antal release of al :cene radcaedvig, the venr. laden system win te secured au:cma:icaHy by a sig.a1 frem de react:r deck centucts air menitcr. =.as.s .. a_.3

e.... g3..,g.,.' c...' ' '. e v *".."_= ~.'. u r. =.~. s: = ~.....*. e....c =... - =. ~....'.1 -. ~..~.-

dl l 11in. es :-ic:ed areas is teicw I'.e M?C. . :he event :f a su:sta. a re ease of ai.:cene.acicac:ivig, -he vent.aden system win te seen ed au :=atesi.-. Theref:re. :peraden :f -he rese:ce wi_". ce ventila:icn sp.am snu; dcwn f:e sher pe-feds of

e :: make repairs insures de same depte ci cen r:1 et release :f.adicac:ive materials.

Mereever, rsda:icn monitcrs wi;rd. :he tui d:g i.cepea. den: cf ecse in me ven-2.atien sys am win s.ve wa-.ing :f hign s.. e. +w.-.....,.,a n... ,s. u. . u.,..,...s.,.., c. ..y,5, c, ca.i.e,. .u..,. sys e = tac ered. 1 l 1

, n.r. ..,.C ;5 o g. e_r..= r.e..n... x. i 3 ...o. .. u. A:ci!cabiliti This specificaden a;;!!es to e::peicents insta led in ce react:r and its experi-mental faciSties. Objecdve

• The objective is to prevent damage to the reacter or ex i

et, 4 p.e. ec., io c.:.c_ <a 4 , ' d a y% O.4.A> .p wi.- y W.~-r 6 s Seceificadens The f: Hewing li=iuticcs call apply to de i-adaden of materials (e-J.er can airh / If a pessibilig exists that a release of adicactive gases er aerescis may ec==, the a=eunt and type of material ir adiated shall be !!mited to. a. assure the yearly compliance wim Table H 2.;;endz 3, of 10 CyR 2D assuming 100% of the gases er serescis escape. Each fueled expeiment shall be Ifmited such that de total invent ry of b. ledine iset: pes 121 creugh 135 in de experiment is net Feater dan 1.5 j curies and de maximum Sr-50 invent:ry is nct pea;er egn 5 minicuries. Enewn a=_._le__ rive. =aterials shah not be irradated la the reacter en, the pressure produced _- ~ e... inanddes pester can 25 miP.ipams. In addr. in the e=eriment container uocn detenatien of the ez;1csive sha.11 have be.rn e::;:e. mentally determined to be less than de desip press:re of ce cCn*Jiner. S /d. Samples sha.2 be d:utly enes;sulated when :::iF release of de centained = atrial c:uld cause c:rresten of de e.gei=ena.1 facillg. he su.:n cf de absciute reacdviv weres cf r.21 expeiments i. -J.e a. exceed react:r and in de assceiated e=erimental facilides shall net C.3 delu '<Ad. ~his i5.cindes de t:tal ;ctendal remed4g / 50.00 inse. cn which.ignt restit ' rec e=eri=ent -at'-'-"cc. accicen:s! ex:ci=ent fleedi.; er veidi.; and accidental es=cval :r inseden ci eZ;eri=ents. culadens.eprding e. e-icents the f::Ecwir.g assum;;! cts sna:1 te g '- -e =ade: .' 2e ef.".nent e.caust.s threugn a fCter ins 2 rad:n desig.ed f: pester can is % efficiency f:: 2.0 mic cr. ;c-ici- '=" '.09 et Oe terescis ;r:ducec.2n escape. .=* i l l 1 1 ... -. ~.

i l i l i Objec-ive The eciective is to verify the preger cperaticn of any system rela:ed :o reae:ce safetf. Sceci!!eatiens Any addtiens er mcdificatiens to the ventilatien system, the cere and its - A 'L,rs.. h ) v C 6 :, ::c.p V, assceinted su :cr s: ucere, ce ;cci, de pect ecciant o . - -O

e made and tested in f d-ive mechanism, er the reacter safety system sna21

,h neccrdance with 2e specifica-icr.s :o which me sp:e=s were,c-i:i;irgny .=- .y R^e_. ',.,&.w!'N desig.ed a.nd fabricated er to specificaticns a;;r=ved by 4e RRys%., A g., p.v Y', c. C 7 ...r ;3 C' sys s= shall not be censidered cperable t=:11 after it is successinny te ed. wW ci in ..._.4

1. aw C

This specifiestien relates to cha.nges in remeter systems which could~ di.ectly affect ce safe:y cf the reacter. As lcng as changes er replacements to dese systems centi.ue to meet the original design specificadens, : hen cey meet te presently accepted cperadng criteria. - _aL:

r. m......=.

4, .u. _.. v. L~.n,u--. v-_-t

_u.r.y. Ly. t

i...

AreliesbEltv This specificatica applies to de suri. mar:ce reg.drements cf the fuel element temperarre mearr.ri.g channel Chiec-ive The 2fectve '.s assire that the inel element te=;eratures are ;tegerly m..:..r.... s Scecif*ca:icns Whenever a reae:ce sera = caused by high fuel elemen: :emeera e z. =cers, an evalua-icn Ir.all:e enducted c determine whe.her ce -) / fuel element tempera re safe:7.imi was ex:eeded. ~ ~ A M" ra-icn cf the tempe arre measri g channels shan be b. perf:rmed a.nus.27 but at inter rais ne: ;c en:eed '4 menes. y ~ s '- ~. .s.- A :r.eck :f de fuel elemen-tem;e arre scrs= shan :e made Isil,- u '- e ~ whenever :he.eae::r 's :pera:ed. 3 a.ns , pe.2t:nal e.-:erience with .e !?l~-A ryste= gives assur.:e ea: e.e

e=;<rarres hate teen 2e.- nece pie measurements :i inei ele =ent

.e e c. g

sufficiently relia.ble to assure accurate indicatfen cf this parameter. I.DICG CONDCONS FOR O?I?.ATION 4.3 4.3.1-Resetidtv ?.ecuirements AcoUcabDity ,. These specifica:icns apply to the seveillanes reghements for re conecicf experiments and systems. Obiecdve - The cbjective-is to meas =e and veri'y the werth, pe-fermance, and ' cperabci:y of these systems a.ffectng the reactivity of the reacter. Seeeificadens the reactivity worth of each eenec1 red and de shutdewn margi:i f shall be determined annually but at intervais not to exce a. menths shall be estimated er The reactivity worth cf en e=periment mes.sured, as accrecriate, befcre rese:ce Ocwer cceratien with said b. 2 experiment, thEfirs time it is perfermed.' cent:1. reds shall be visuaIly inspected fer detericreden. c The

1. [

annually, not to exceed 14 months. On each dav that pulse mede ceeratien of the reacice is planned, a d-f d. d /[d fune:icnal jerfermance check of the cansien N h.M ments, ce : ansient (pulse) red dr-;ve cylinder and the associa:ad

• • d lubricated as e,% f

/ air su;;17 s7 stem shall te 5. spec:ad, beaad ..ttts3a:J. The e re excess eacdvi y shall he mensced a ce beginni.g :f s y each day cf cpers:ica er ;rier :: each :en:nucus egers: den ex:end-e. ing =cre han a day. cwer ecefficient cf.eactivity be: ween 100Ex and ; W wEl be The

f. / meas;ured annually not :c anceed 14 men:hs.

Basis 2.ssure ca: ce The rezetvi y wer-h :f :ne :enm:1 ds !s :easced :: and :: pr:v.de an acera:e.ea s regded shu:dewn ma gin is aveN-a f:r de:ermining te reac:id y 'ver-.s :! e.- erimen s '.serted in.at :cre.

4. :.

9 -. ~ -

Pas: experience with T7. IGA reae::-s gives assu-ance dat measurement of ce reactivity werth en an a J.ual basis is adecuate to insure tat no The visual sig.i"esnt changes in ce shu:dewn margin have cccur ed. evaluate c:rresien and wear inspeeden of the cent:1 ::ds is made :: chs acteristics caused by cpe stien in e.e reacter. 4.3.2-Cent:1 and Safety Systems A::licability o These specifica: fens apply to the sa-veillance requirements fer measure-ments, tests, and es.libratens =f de cent :1 and safety systems. ~ Objecdve The :bjective is to verify the ;erfermance and c;e2hilit7 of ecse systems and ecc:ponents which are drecty related to reacter safety. Sceci'.! cations The cent:1 ::d dr o times shall be measured semiarr.uaHv but at ~ a./ intervals not t: exceed S menths. b. A Channel Test cf each cf the reactcr safe y system channels fer the intended mede cf opeatien shall be performed prior to each day's cperatica er prict to each cperation e.nendng mere than ene /dav, except fer the poci water level channel which shall be tasted ~7 weeW.y. A Channel Calibraten shan be =ade of the powe level monit ring \\ c. j Aannels by the calcrimetri: =ethed annually but at intervals net is exceed 14 =caths. i. d. The wate cencuetvit7 shall be menit red a: 2ess: weekly duri.g / ner=al cpeaden. D.e water :enductivity shall:ct enceed 2 mic :- =he's per eer.t.=eter aversted ve a =en-h.

9. 9 t g

.f. 4, m

w. n ts-

-ases g,,.*. ; Mess:recent cf de sc.2= ene :n an semiannualbasis is a redeica-ica cf te sc-se systam elec=:nics, and is an i. des:icn cf de espa:Ei y of -he cent:1 ::ds :: ;er.'erm pr:peiy. The channel tas:s wS1 assure that ce safa 7 system dannels are :perstie en a M7 tesis er price :: a.: en ended..=. " he pcwer level chan.el calibesti:n wi2 assure -*.- -.- rese::: wi:1 te :pers:ed a the ;r:;er ;cwe ; eve.is. Trs.s:en :en:-:1 --d enee.b and seniz r"$1 main:enance i.sure ;r:;e

pera-i:n -f eis cen=:1 ::d.

t. c.

I I l 9

e ne water cenductivity is centrcHed to aveid actvatien of minersis in ce water and to avoid dete-icratien of cladding, piping, and other systems, 4.3.3-Radiarien Mcniter5; System ArcUcability This specificatien applies to the surveillance recui.ements fer the ares radaden menitering equipment and ce centinueus air menitering system. ~ .~ Obiective The ecfeedve is to assure that the adiatien menit:ri.g ecuipment is cperatng and to verify the appropriate alarm set.ings. Scecificatien q ) The area radatica menitoring system and the centinucus air meni system shall be celitrated annually but at intervals pet to p;eted 14C ~ / .' menes and shan be verifled to te coerable M-cr a; / n. Basis ?:cperience has shewn that quarterly verificatien of area radation and air monitering systa= set points in cenjuncticn with annual calibraden is adequate to ecerect fer any variation in the system due to a change cf "cperating characteristes over a long dme span. 4.3.4-Ventiladen System A:elicabE!tv This specificaden z.pplies is ce buildng c:nfinement ventSaden system. Obfective ne cbiectve is t 1.=ure ce pr:per cperaden cf -he vent'aden system in cenm-i".g releases cf adcactve =sterial inc te une:ntr:Eed enyt:n=en Soeciilc1dcn ,~ It s.. ail be verified mendly ', a v.5;al checic cat $e ven*2aten sys am is tpe atle. f M %- 1\\ h.h-i. % M~.' 'S h

-.m.T.

g-- O.-

e. w.c 4/5 N 4 20 ~_- .i N & -Ul'.'- 1(' cr~2[0-:./ & 1'." /. -. / r.>.a j. w 0. '{. .N, O,%. 6

/.e 4-.r /.

' c ' 'l " M d.,.A.C.* O p'

i. Basis y :perience accumulated over several years of cperaden has de=ctstra:ed Ztha: ce :ests of the ventiladen sys:em en a monthly : asis are rcfficient

c awee the ; roper cperaden of the system and cen=ci et 0.e :eles.se cf

/ radcactive material. ~\\ / /. y %6 '-'~ 4.4 RE>.C OR ?UEL EJ.EMENTS J.cclicacEi*v . /nis specificaden applies to the survema.ee requirements fer the fuel ele = e:ts. Obiecdve / The eclective is to verify de intepit7 of the fuel element claddi.g. Scecifendens >_:1 A:e1 elements shall be inspec:ed visually fer damage er deteriera:ica and =essured for leng-h and bow at intervals separated by net =cre -J:a:: 500 ;ulses of Inserten gester e.an 52.00 er annually (not :o exceed 14 Fuei~ elements indicating an elepgation menths), which ev/er ccers first. inch, a lateral bending gres:ar dan 1.45 = V e gester can 1/1 r/ signi'! cant visible da= age shall be censide ej.Jo. be damaged an. dA=" -

• 4

'. Ju l.rA 44 y be used in the reacter cere:. x s&4 TWA ~ k*

• 5gggy Tha frequency cf ins,.e: den and =eas:rement schedule is based en the parameters most likely to affect the fuel eladding cf a pu!si.C remeter and utili::ing fuelelements whose characteristes are well'c:own.

The.1=i: cf ransverse bend has been shewn to resul: in ::e diffleul y in disasse=bling the cere. 3.nalysis cf 0.e receval of hea fr:m tecc".i.; fuel elemen:s shows :..z: there wi:1 te se het spcts resultng in damage :c ce fuel caused by cis :cuchi..g. I:;erience with TRIG /. rese::rs '.as shewn dat fuel elemen; bewi.g : at eculd result in ::uchi.g has cecu: ed witcun dele:ericus effects. The alcnga:icn 1!=i: has been specified :o ass::e ta: de claddi.g material will net be su:fected :c streises ca: eculd cause a less cf intepity in de fuel centain:nen; and to assure adequate ecclan flew. e c.t v. :: m....ee 4, + ......... w - M*

== e. .ugum.au. .e ..e e O J = = ~. = = = =. m. + -.

l .m. Sasis i ne pcisen.equirements fer the cent 1 reds are satisfied by using neuren abscrbing berated g sphite,' 3 C powder er beren and its ecm;cunds, n ese materials must be contained iii a suitable claddng material, such as aluminum or stainless steel, te insure mechanical stability during movement and to Scram capabilities are isciate the poisen from the pool water environment. provided fer rapid insertion of the centrol reds which is the primary safety De t ansient cent::1 red is desip.ed for a reset:r 1 . fean:re of the reae:cr. u pu!se. 5.4 RADLCCN MONITOP.'NG SYSTIM Aeollestill This soecificatica describes the functiens and essential eccpenenu Of the area radiatien mcnit: ring equipment and the system fer centincusly mcnitcring eirectne adicaedvity. Obiective ne ebfectie is :: descrite te radatien menit:ri.; eg:!;=ent tha- !s av=N51e to the cpers:c te assure safe cperatien cf t.e remeter. Soecificatien i br%C' pe p' --sleh be "-" I. ? -- ne. radatien .onitoring equipmen: availacle !ct reae:ct operation. h Radiaden Meniterint Channel and Funeden Area Radiatien Moniter (gamma sea.si9ie s) /, Ty',}} b, g-7eneden - Meniter of radcactvi. .: tuildng.' alarm and i reae"* v ~ ----Leensci m.C?lm._ e:csi g cf ;,:s: tie se.u g dampers au cmn&.111. 7 i n . t. W* )" Gas and Particulate 5:ack Radiaden Meni cr (gan::a sensitve detec::: u U' y'~g.} i ) 'g/*,,, with ai ce!Iecten caca:H gFuncten - Menit:r eencenraden :f :sdcaci-te perde ey and radicaci ve gases,: bc..dng and annaust, alarm and reaccu 1: s,. . g ". y s f f \\1 ceneci c:= sele. F iw ..J-Basis ,\\e.a * ~'.e :2 dad:n meni : ring sys em is in: ended :: ;;c ride inf:r=ati:n :o :cers-i g

ha: :ners w-.3-

e s

nnel of any impend..; :r exis:1 g 1. anger f::m :sda-i:n 5:

e r.d 3 -- ' e t: evacua:e te facEi 7 and.aka :he

-=~m 7 s:eps ::

rtven

. e spread :f rad:actri 7 :: 2e r.:: :endngs.

24 l l i I.,

~ 5.5 FUZI. 5~ORAGE A:Olica:!lity This specification applies to the stcrage cf reacter fuel at ti.mes when it is net in the rese:ce cere. Obiective The objee:ive is to assure that fuel which is 5 cred wiH not beceme critical and will net resch an unsafe temperature. Scecificaticn AH fuel elements not in the reacterrat shall be st: red and handed !n. =M ~e: 9nta tr.e prov.stens ef 10 C75 -W Irradiated fuel elements 'and m.# w - fueled cevicel shah be s:cred in an ar cy which win per=ft sufficient natural ,. ? gg ccnvective cooling by water er air such that the fuel element er fueled device ~\\ q,j@ W] temperature wiH not exceed design vlaues. . n \\, C.. s.. a > casis f(7) The U=its im csed by this, specificatien are conservative and assure safe v~ y stcrage. & _ye ,t %,M. M.e N lO 5.5 REACTOR BUII DING AND VENTILATION SYSTEM f i 1 . wm-.;trJ. A:cUesiblitv . ~ ~ ~ ~~ This specificatien applies to the uildng wisch houses the reactor. Objective The cbiective is to res -ict the a=ctmt cf radcac:ivity released into the encen:nen:. Soecif!cstiens The reac:ce buildng, as a s: uer.:relly independent buildng in the Ay3RI a. complex. shan have !:s wn venr.la:ing system. The eff nen: f.em :he reac:ce buildi.g ven:-lats sys e= stall exhaus: threugn absciute filters

= a stack having a minimum elevatten '. hat is 13' theve the reef level of the hignes; building in the AERRI complex.

5. '.e ese::r -:cm shall :entsin a minimum free velu=e of ::.0c0 c::ic feet. " e ventilatg system zi-ducu :: he rese::: ce= shall :e ecui::e.f O, with pesi:ive sesiing dampers actisa:ed :y fai!-safe cen: :is ti:%i1 na = =r e e e 9". _ P __ y

i i clese eff the ventiladen to the reae:ce reem au cmatically pen sa alarm cf 2e rese:cr ::cm centinucus air meriter. d. The teacter cm shall be designed to restrict air leakage when e.e pcsitive sealing dampe:s are clesed. 3ases The facility is desig.ed such that the ventilation system wi!I ncrmally main: sin a negative ;ressure with respect to the atmesphere so dat there will be no / The free air velume w!:hin the tincen:rciled leakage :o :he environment. reacter tu!! ding is eenfined when there is s.. emergency shu:dewn cf the ventilatfen system. 5.0 AO*rDISTRAC/I CCN-'3OL5 ' 5.2 RI5? ONSI.:II.*.TT S.2.1-The Directer, A?R2I shall be responsible for everall facilit*' cperaden.. The Physicis:-in-Charge of de Reseter (PIC) will be respensible fer day to day cperzdens and fer determinatien of appi!cabuity cf precedures, experiment a.uthcrinz:::r.s, and mainta! ance cper1:icns. During the absence cf the ?tC ft:m the facill:7 fer mere than ene werking day, O.e Directer, AyR?.I. will designate, ancther SRO to discha.:ge these respere"ilities. 6.2 ORGANIZATION 5.2.1 - The crganir.aticn for facility management n:d cpers:icn shall be as ' shewn in I!;t: e 5. -1. 1

a. M!nf=um staff when de reacter is net secu ed shallinclude:

1

1. Senfer Reacter Operator (520) en "" bu. not neesssa rilycn si:e.

2. Radiatien cent :1:echnicina en esl1

3. Reac:ct C;ers::r.'?.0) at cenreis Ancthe persen within tr.e A??.RI c mplex atie :o ca y cc: wri::en 4.

emergency ;recedures. Insrucciens cf e.e coers:ce, cr := s== men hei; in case :.e cpersu:r tecemes incapaciated. A: *eas: :ne !! censed cperst:r shall be at t' e cen is when :t.e rene:ce Is nctsecured. I An indivite.ai ca: 's desig.ated by the '.icensee as :;ualified :: implemen: c.

nne.sdia:!cn pr::ecten ;rceed: es shall be ;resen; a: e.e facil!:7 Wr.t..evtr :he reae::: is r.c: secured er Wr.er.eVer 11*.*?

!.m er:- e n: c; en;cimer.:21 faci 2 7 s tei.; ser. iced. i x p u ~,. - .s ~ ng.-~. r.a : - M' a. m.a.- . d' Q

J '. f n M m..

-.- -.... ~.. .- ~

4 i (!) Sig.i!!cr.t perating a ncrcalities er var.sti:ns from ner=al and expected performance of facility ec.uipment dat affec: nucles: safety. (g) Events which have been repcried within 24 hcu:s to the NRC in writing. (h) Audt repers. 5..c..,.,

1. at Audi s of facility activities shall be perfermed under the ecgninance of de ?.RISC but in no esse by ^.e persennel responsible for the item c

auc1:ed at less: ence eve. IS months. Indvid.:a1 audts may be I_m be an identified RI?SC ,y/ y,./ perf:r=ed by ene individual wne need not I i m e=ter. These audu shall examine de cperatng recceds and i M, \\%. b enccmpass. gq (a) The cenfermance cf facilig cperaten to the tecinical speci!!- entiens and the !! cense. (b) ne perfer=ance, t aini.g, and T *"'icatiens of the entire facHity staff. (c) The results of all acticns taken :c ccrrect defleiencies ecm::-ing in facEity eguipment, struen:res, systems, er me2cds cf eperation -~. that aff_ect.. dear safety. ~ (o The facility emergency plan and Implementing precedures. (e) ne facill:7 security pian and i:nplementing prc' cec.:res. (f) Any other area cf facilig cperaten censidered appe:priate by :he ") ?.3ISC cr ite Direc:cr. ,J ' 5.\\ }."'.3.1.3 Au-3.cri v I l.) % e (cf) 62AA>J5 s Lar '.s a r 5 ~'.e EZISC shall reper :o de Direct:r, AIR.*.I. and t&dse de ?!C en -3.ese areas of respcasibnig specified in sectens 5.3.' 5 and 5.3.'.. ~ .e. _~,I~.. v.C r 1..-,.C y. e .-s.s 5.5.1 ne f:11cwing tetens sha te *.aken in the *.ven a safen !!mit is c:::eeded: If ne eme::r wC be stu dew. imme."z:aly and reac::e :peraten w I nc::e resumec wiccu: an::::i:s-icn by de C:=missien. 30 m e as. O g....

~ m K Qc. A( 6.3 EX?IRDIENTS Sefere issuance of a reacter autherizatien, experiments sheH be reviewed bv S~ 6.3.1 the fcHew kg: (1) Physicist-in-Charge (PIC) of the reacter (2) Essd, Radatien Scuress Div'sien (3) Safety Department Reac:ce and Radiaten Faci 11:7 Safety Ceccittee (RRESC) (4) ?rier := i s perfermance, an e ;ciment must be included under cne cf the 5.3.0 fenowi.g types of aucer-datens issued by the ERESC: Scecial Rese:cr Autheri aten for new exceriments or ex;ciments ' (1) not incinceo m a acu::.ne Reac: r Ausserinaten. These exnerimenu sha perfermed under the drect supervisien cf the ?!C cf the reac:ct er his desic.ee. Roudne Reseter Authcrization for ex::ciments safely perfcrmed at (2) These ex;c.ments may oe pefer=ed at the dscretien f the PIC least cnce. and ecctdi..ated with the Safety Depetment when ap.r:priate. c l 5.3.3. With 2e exceptien cf the routse measurement cf reacter pes =eters, the reacter cperater shan operate the reacter under de specific autherination of the ?!C cr his desipee. The Reae:ct Opere.:icts Sc;er-dscr =ay authcri:e ce .cudne measurement cf reactor parameters. S.S RI?ORTDiG RIOUIRILIINTS In addten te the applicable reperdng reg:frements cf Title 10, Ccde f the T.,i eet:r yede21 Replatens, the fc11owing reper s shan te s:2ci:.ed :: of te Appr:priate N2C Regicnal Cffice unless etterwise..cted. 5.3.1 Reu-i.e Re::cr.s a. Startu= Re:cr.: A su==ary eper: cf ;Ian str:np and ;cwer escsaanen :ss.ng shan de sucmi::ad f:Ecwing: (1) eceipt cf an ,cpest.g !! cense; (2) amendment cf de license invciv.; a pian: ed increase 5 pcwe level: (3) insa.12aten of fuel 2a: has a diferen, desir.: and (4) mcdifleadens tha: =ay have sipif!:sa:ly al:ered te nuclear, cer=21. er.ycrau!!c perfer.ance of 2e plan:. 2.e reper:

• shan address each ef 2e :ests identified in me FSA?. t.-d sha.2 i.

generalinclude a des:-iptien :f te =es.sured values :! ne :pera:f g =ncidens :r :.aracteristes :c:ained t. ring te ests pr:i : r.c a =mparisen :f : ese vaines wi.s des:p. ; reded: s and s;<:ifi:a:icns. Any cer ectve tcdens ca: wee reg. fred -r 3:w n isfa:::r.- sha". alsc te described. An7 M t: -?s. r .:.e- " c

pest:

reg: ired in 2eensa ~-- " '-* ased :n T wrv. r.enu 3..a.2 :e incinded != dis re;crt. . ~ ~. -. = *. * * + = -. -. P ' ~ * " ' ry

(c) Any new c untried experiments er tests perfermed during the ~ re:er:ing pericd : hat are not described in the Safety Analys s Repert. (6) A summan of the safety evaluatien made fer each change, test, er. experimen not summitted fer Ccomissien a;;reval pursuant to.10 C7R 50.55 which clearly shows the ressen leadng to de conclusien t!wt no unreviewed safety ques:!cn existed and that no technical s specifiestien change was required. (7) A sum =a y of te na:ure and amcunt of aftberne radicaedve effluents reiessed er dscharged to the environs beycnd the effeedve cent::1 ef the !!censee as deterv.ined at er prict to the point cfiuch release er dscha ge. (a) Total estimated quantity cf radcactivity released (in e=ies) determined by an a;;reved sa=;iing and coun-dng method. (b) Total estima ed quantit7 cf Argen-41' released (in curies) during ~ the repert..g pe-iod based en data f m an appr:priate meniter'ng system. (c) I.s:imated average atmospherie dluted c:ncentratien cf.Lgen-

• \\ A 41 released du-ing :he reperting peried in terms of microcefes/cc and fraedca of the Applicable M?C value.

wgy 3,- Ag Q ~ (d) Total est=ated qua.dg cf radicactivig in particulate fer= wid hal.f lives pester than eight days (in curies) released durig the \\ gC. reperting peried as deter =ined by an ap;repriate ; articulate ,g g .,.y ment:cring sys:em. 'q h( l ( (e) An estmate of the average eeneent aden cf cther sip.ifica. radentelides present in ce gasecus waste discha.ge in terms of mic::cu-ies/c and fracticn cf 0.e 1;plicable M?C value fer the repertng ;eried if the estmated :elease is g es:er e.an 0% et the applicable M?C. (S) A desc-iptien cf 2e :ssul.s cf any envi.enmenta.! adelegical surveys perfermed cuiside ce facilig. 6J.: ?.e:c a:1e 0eeu:-enees Repc :able cetu rencas, inc!:d..g causes, ;r: cable cense:.:ences. cc-eedve actens and =easures c preven: recu :ence. sha'.1 te :ept :ed :c :; e Nr. 5tmple= e.:21 repc-s may te required :c fully dese-ihe ..e final rese;u:icn cf 2.e ce:t-ene. "e cf cer ee:ed :: su;;;e=en:al re;cris. a.'. Amended 'Icensee even: e;cr s;.a.3 te ::c;Ie:=d

• -d -da ence s;.a.2 de made : the crig..ai re;c : da:e.

w"! I i I l 1 l

9 . e.sennel err:: :: precedu a.1 inadecuacy which prevents, er cedd (S) prevent,ty itself, the ful!!11 ment cf the funedenal requirements et systems required to ecpe with accidents analyzed in ce SM (-) Unscheduled cendt!cns arising f.=m natural er man-made events that, as a drect result cf the event, require cpettien of sa.fe:7 systems er etter protective measures required by tect.nical specif!:stiens. s (8) Imers dscovered In the transient er accident analyses er In the =etheds used f:r such analyses as desc-ibed in the safety analysis reper cr in ce bases f : the techniemi specificadens t"4: have er could have per=itted reac:c cceaden in a manner less con-sevatve than assumed in the analyses. (9) Perfc =ance ci stuctures, syste=s, er components that requires remedal action or cerrective measures te prevent operatien in a manner less censevative t'.an assumed in the accident ard.!?ses in the safety analysis report er technical.specificadens bases; er - dscovery curir.g plant life of cer:ddens net specifically censidered in ce safety analysis report er tecnnicals:ecificatiens t4t equi e remedal acticn er c rree:ive measu es to prevent the existence er deveic; ment ' n u. safe cendtien. G. 9.. ~6 W.A.M ',') 7 C 0 c' ,.. 3,..:2:N..: .I 5.10.; 2eecrds t: be.etained fer a peried cf at least five years: (a) C;e atingIcgs er data which s;.allidentify: 1 G) Completien of pre-star.:p checkcu., surtup. pcwe changes, and snu:down cf the :eacter. 1 (2) insu!1stien er remeval cf fuel elemens, cent :1 ::ds, er c=eriments cat uld a!!ec:::re reacdvi:7 l3) *ns $"aden er emcvel Of 'umpers, special ugs, er nedces er

tne tem;crary :hanges t bypass rese :r saie y circuin 7 (4' I d wcr-h measurements and Other reacdvit7 measuren; ens.

.-incipai =aintenance cpea: ices. (t) ':) Ee;cruble ec::=ences.

• d.'

5 --rei22nce acttides required :y = " '-C specif! =d:.s. it:- ?aciW/.ad!a0:n a.d cenumina-icn sur-leys. . f.' I. :eriments ;ci:rmed wi:3 2e rese:cr. 36 i h .--........,r.. v~ C j e L}}