ML20082N878
| ML20082N878 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/02/1983 |
| From: | UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20082N874 | List: |
| References | |
| NUDOCS 8312080004 | |
| Download: ML20082N878 (130) | |
Text
{{#Wiki_filter:'
~
~
} '
DEFINITIONS ' " . t 7 w.
.,, :~."
.* ... : u ...v 4
, i. -
. . . . . . . - . .. .v , s .~ , ~ ,
g , MEMBER (S) 0F THE PUBLIC..
. g.c bMr Q J,, . 6 .6'i. M N<. r
" ~
{
.--p W :xc:.. yu.,- 9::,
~;sy_ Kp ' M; .?y ^ N. -i ';.y- .
i
\
1.16 MEMBER (S) 0F THE PUBLIC shall. include all persons' who are 'not"5 ." -;~~ ' occupationally associated with the plant. This category does not include 1 -
)
)
employees of the licensee, its contractors or' vendors. ., Also excluded from 4 . - <
. this category deliveries. are persons who enter the site to service equipment or to make' .c, e
_' ' This category does includ.e persons whatuse portions of the site :s 4, ' . for recreational, occupational, or other purposes not associated with the W. " S ' ) 2 plant a ;. - O%~
' J mN :w Qp.e c/3 w.
. w . , g. a,.7 .L $;Q %. @7 d r.W %:m M M r q chWH - " v ',
g.iy?lbytil
.,2 w.gm
-l 0FFSITE DOSE CALCULATION : M;- M;O c w MANUAL.vT...% v.w,N w
. :n .N.. - d,.:w .
M.:72n .u.P *
. p.
W -
. . e c . ..s.y.:9x. .x
- a. , :n .w y:v.T s.a.b. .
w.m . a s n. - m;m . L17' The OFFSITE DOSE CALCULATION MANUAL'(00CM) shallicontain the metho
- l. and parameters used in the calculation of offsite doses due to radioactive - ':...> ~
,q' V gaseous and liquid effluents, in the calculation of gaseous and liquid effluent.
; monitoring Alarm / Trip Setpoints, and in_ the conduct of. the Environmental. ~
.. Radiological Monitoring .Progranch , ,- , sc.to o~ew;7%@x.W:.L::,:. : e J .
v - .. .~ 3 OPERABLE - OPERABILITY' Jthf.O., -:-
- ._ , ;nw.m. T. n. ,. ,, d_ .,
s e py y .Q, Y. . q,.y. M.. A^ .m a . -, dJi[M/ 1 g N:# . s#, n_ ..m, .g. x,#.. . 3. ; E, ' 1.18
. a- s. -
A system, subsystem, train, component or device shall be OPERABLE or.. '-
' ,:'C
~ have OPERABILITY when it is capable of performing its 'specified function (s)..T .
and when all necessary attendant instrumentation, controls, . electrical power, '
#', cooling or seal water, lubrication 'or other auxiliary equipment that are Js.
}h[F . c _required for.the system, subsystem, train, component, or device.to perform its ~
~
funct. ion (s) are also capable of-performing their related support function (s).. .q/ 4
~
'4 0PERTIONAL' MODE-M00h a y..
;f .1;
.g
_1.19
. . ... p. ;f:. ..~~ v., .
ff.( n g - w w . m :y;~ +.. g
...h.
[.. 4K"s q:n . . coolant temperature s An OPERATIONAL MODE (i.e.+, MODE).shall. correspond to,any o combination of core reactivity. condition, power level ".and avera :. M % ',j! p .A C l-C?,yQ,yLp;mg g g @pecified Qtig@hdh, in' Table 1.2 M W 6 %, %@x.b g, .' g.:.; n :PHYSICS TESTS ..g:.c.-7:g:s.gJN;m'geg%g g. . g f g ,fh;fp .,g {g.f .j, :.WL p rh MgFf 1220' PHYSICS TESTS shall befthose tests performed m .wy ?c: WG ':' nuclear characteristics of the. core and related. ins;to: meas 1 7/.7 %% E trumentation:7.(1). described % 1T;GSVL
% 10tCFR in Chapter 50.59,' or (3) 14.0 otiherwise" of. the approved FSAR,Tord(2)Tauthorized by.the Cosmiisitori. MT' under 's th $@di.1DF 4MV. QAE W.@E 4W%W %%R p EI, a BOUNDARY LEAKAGE $t%y@fhMM29@
PRESSUR $
-M-*
g, g k h e , gR g 1.21' PRESSURE ' BOUNDARY. c . NDN LEAKAGE hfM e5W hhill'k.hN(k NE pgy"Y,y J:. leakage) through a nonisolable- fau bel S aakage ' except; steam?g@nerator MQRT body, pipe 1 wall,4.oi vessel;,wallM,;lt?in'.a Mdp r '. i 'i Reactor. Coolant!S stem componentfp W fsp. '. ' Ns.MO
@9 FYev,%h"hyMW M*** 1 gp%pft
*/ ,,
4 ^$w.mM : & 8312080004 831202 7*""lis5iM,.sg,. R ~ s W.gndkF-n, &Mg E
- 4Mwwwms;MSAMM+
wC wwwmwnn WWF Min % wy$mm>Q www MWhd.n w:+3M n yQmQm AmQJEg a b w aw 9& a. m ; w ym xi.J:8:
- m.y
$ WWMhe.w.e U My4M 'I .
% . Mes W &&.w.% $% .
hWM3ILdh$gf W WowsNRM nh JM r MJM& & W <hhMA %W
% %E
DEFINITIONS
.." q i
% ~)u....__.___.,____.3.,
i PROCESS CONTROL PROGRAM -
.Mq '
1.22 ,.t._
.. n
.. o..r
. r e. .e e....u.,.o. ,..
.n. ,. n.om. ..
.o .m. _u.._,.,. ___.... . ,_
. . ... . . . . . . . . . . . ..__u..,, ,
- !y:::, t::t:, ;r.dtct:-;inctier.; t: 5: ::d: t: :n: r: th:t the pr;; ::ing and p::E:ging-of solid +edioecthe estes based on-demontreted F,recessLs of 20tur! Or 34. :itel:ted w:t :0?id w::t:: wi'l bc :::;;;11:hed
~.. m, . . . . ,. n e. e n. .o .. .e.n. , , n in :::',, : w:y :: t: >
_.m_._... ~.. . __ o
... 3,, ...2 c. m_ _. ._ . ...2 e...._
, .. .. .. . .. e..e. n..o __
ege!:ti:n:, buriel gr:end r: eir rente, and other requir:::nts geverW; - the di;;esai cf the redi:::tiv: w:-t . - i 1 PURGE - PURGING c ' 1.23 PURGE or PURGING shall be any controlled process of discharging air or - gas from a confinement to maintain temperature, pressure, humidity, concentra-tion or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. . QUADRANT POWER TILT RATIO 1.24 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector cali- , brated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whi:hever is greater. With one excore detector inoperable, the remaining three detectors shall be used fc computing the average. ' l - _ RATED THERMAL POWER -
.d .h .
.p. -1.25 RATED THERMAL POWER shall be a total core heat transfer rate to the
- '\-,n reacter coolant of 3411 MWt.. .
. . s .
- REACTOR TRIP. SYSTEM RESPONSE TIME . - .
\ < > . . f' ' 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from , a when the monitored parameter exceeds its Trip Setpoint at the. channel sensor : ,
' ] , ., - until loss of stationary gripper coil voltage.g. ., .. m.w.p . .:.
- j. .
~.
7 .E 3- ?"
~ REPORTABLE EVENT '
._; w - y q i.g..
3:m@.
). r. ,
1.27 A REPORTABLE EVENT shall be anylf'those conditions specified in !LHC Section 50.73 to 10 CFR Part 50. .A im /A p .m - 3,
- . - 9 % w
@fLW&, h a;- - -
, m .. ,~. .y.a$9.g:@.@NP&,el~Q.%QQd' M& '- .
P..D .o$ y e . SHUTDOWN MARGIN - .! L s - ?-;i.l/- y 1.;' A, f. as.s J . '
.t.
u 6 ', ' ' - .. . s,
~, ~ L28 SHUTDOWN MARGIN shall be'the instantaneous amountFof reactiv'ity by whiche ,
the reactor is subcritical or would be subcritical from its present condition' N. : s,. assuming all full-length rod cluster assemblies (shutdown and control) are 's v. . ,
- f. , JLn~ fully inserted except for the single rod cluster assembly of highest reactivity;. ...
N 4 ' n-.'r worth which is assumed to be fully withdrawn.;u C~ m% m$4:y
- ~ . . . ,.
NM, w &~.i % a ..kJ..l m., o. 4v=:m
. a. 9%. , .~m... v n . . . v. c .s.::,<.1 8 .% ..: %.w. -
7 m *
. ! s.
&n. &> ~.i..N& W~A'$.i~.Q'Wd;. .W F:s. & uf ;^' ., n&?.,, *Y .,w. % NGy~f, h s$ [ y W 4f H l5: .h@ ::: h$ eybm m ,, id:Q ?W-A % y.Iy*W'M '.l:Q*4}Qhk*i..H&l .f3'h,,,q. W T :kf:';.hh Sm a -g6Q:n5[,*i2?.M;hp 9 f.M&..W. 4'h.(.,;;% * /d.f ,S.y f. 4 ; .y .y. . . .m.s a,. 1 . . y ..M h:: e,w a;9 ' .n ~. Q., cm * - r, t..t s .+%:Wik:(
, .-.W .,..mWMp ? W.s.M.m.ji, ., a.N@.. . M4.p::3Q'?.,7 A< f C.W
'y&p. .fm . . . .
.m.4;....s.s.w
y . . ; awWW :Q?.,y f . w+s* 3
.s h..~ .)
O t.r% .. .
* ,y ,:,ky. .k.
w.4;;,&;t
- ..e s 9 s .
i:: 3 W : r i ..o v .
; &n, rO ,.;3y
.+ . . . w . r .- -
, , .. '3 r,l- s o e.
- *s,2 v<?k.,
. .- w < 3:
- v ... ,% % ':" .? ,
. ~/ *~~: .
N ?l % ~ ' . ; . r,. , s . .. n. .. . . . .
-7 ;'. r'.:.n; . :.
. ..: P . m : ^; c,.M:<'-n. . W ,% .
-l l w.; . _ r.
- y
, , .n , ,
..L,~; .
3 ... hhk
.. ,.. ..CALLAWAY - UNIT.1- .
'.V. . .I 5 . I',+ . , *If y 'd
.. .: : .4 ,. m..e ' +
" ~ .'~
., *. :4 .
. : - s
,'e &l.j. *
.. . p k, .m, y. '. ' ._, g *%, [ .. . .. .
- r. > .y s
~1 _, fZ* .;'
'..% ' t. . , * ~ -
?q* ~
. . . . . ,.3 ., , v I * - ' ' '
{ 8 ' i . ., I . .
'M : - .N i,* * '
~ .. *... e.~ n r' Q,t g.y$D . . k .-
-1*
y .Y.J. . , *u" ~i ,'!"5 .'k "C'
*5:..!., . 4"t:.nr~: ovr,if-C J.
- .,,,. 4 w.w-
.,.3 y .
.,~j'~y?
- '. O. ":~u.' ' .7.1
. e: .~;: . .-
1<
.,. w.{' y%.
h~y~t"-W 4ss u~t.;.1 . u ., 5' Q'.4.$sC.ef.
. l. x. m..
, . . . .~ u i -
e;W. .i .,$. s
- ,y
INSERT Process Control Program (PCP) 1.22 The PROCESS CONTROL PROGRAM is the sampling, tests, analyses, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured.
.f i ,
i I C e l
I Definition 1.22 JUSTIFICATION: The proposed definition is a more concise explaination and does not compromise or alter the intent of the original definition. It is understood the program defined will be formulated to assure compliance with appropriate Title 10 to assure Code of Federal Regulations, General Design Interim and Objectives, Regulatory Guides and industry practices. Adding requirements and reference to basic regw\ntiony will not enhance the overall program objectives, i i b 9 i
.. ... .- c -
.6 ~. ....y .. . . . .. - . s .
- 3. :n :. ~- t- ,:
a.u.-
; ,_ _. - m q, . . . r z.y 9.; ; ,. >>
.- t .
~
OEFINITIONS '
~
s . _.,. . ,.;. ..._g. , p ,. n . . . . . .: . mx .. ~. . , . , . . . . .
. ; . , m c . , , ; y-
. .n3 ,- ..
..n.y. - .s:n
; g , ,.
A: ' SITE BOUNDARY.A r M. W .M.p. 4 , O ,'MichMQ/4 # M;:. %. w.c.,M;, 1 . , ._/
. . ~ ~
' _m.:L . _...
"' uu; MbMWMMyM&jiWM:::MM':. W C % g M . g M y :. : ,
l'* -
' ~
1.29 The SITE BOUNDARY shall be that line' beyond which the land is neither4'i J: . a n - owned., nor. leased, nor otherwise contro.lled by th licensee. h. 6 '.*.
< . n . i.
my
* = ' " .p ._ m ......;.- l ; s ?. .:.;
SLAVE RELAY TESThM-:n ..%%s#.2. Mid;W.gaJh:,,,u.u. SNF4.!Ny .a.y, y:W.y.. n..g,N m,. e lT. .. 1,7
? m 94m'. >.Y%b
- a. , y .
g M.2 y:n .: y+-
- n. M.: .
' L 30 . A SLAVE. RELAY TEST shall be the oc :n v. . Mi.s%QMRs.m . n.
n ofenergizatio;u.c -sq,p4yAv,d.
/??h 7 each slave ~ relay and Y; % m
' N .' 2.n .l verification of OPERABILITY of 'each relay. The SLAVE RELAY. TEST shalliincluder.g. . ,1 :
- /. .d r.9 -
a a. continuityn.,.a check,;as ... a;;; minimum, of associated testable actuation devices
.1% 7 m. m. ; .3 1
. . - . .: Y.i? \
~' '
aw a. .w .n -
. SOLIDIFICATION . .:
- g.drsy:.. t,.:;M. M wneTa:+
.;w y . .asuW w.,u>w. %m,.3.g.w. - Aw kww: g.m.e . -s % m p ;w ;,: %. .. .
m ..
'..n ~. m..:ye.2.pp:%w.2 :- . C-w::.n.n&
pe.%w.w .
.~ & *Mm-v kW +W*W.,x:w:w m.u: hv. + -
y4:.@W '. rae..W:M: s
' , 1.31, SOLIDIFICATION shall be ne ~ conversion:of wet ' wastes .into a form that V "
- f. q i.:if.'A .' meets s:
~ shipping and burial ground 9 requirementsDg:;1M
.a Lupc.&. ,w.p+.ga ,
c~..;. :,n, , M ? ' ~.
;.wy*: g: ,.~ .~- ..
v- m r. u ,. m :, w v. nm.e. g . .. ! wpp.n. .. g c ;m . , . ; , .
- n. . .
ga y;p
.. ;g -
SOURCE CHECK v.y.cn . v; :x : . vg.y ;< i :.[fggv;.g.g;Q. f"5Q.Q3u.=Q3@9_\[n~,g,.,:a
.p.n:. ;.QWy, : 9 ,. m y , .+,:;c'.,7..e p
, 9E,Wf ~ '1.32 A SOURCE CHECK shall be the qualitative assessment of channel response # iQ<
. when the channel sensor is exposed to a source of increased radioactivity ~. . ". , .
..%. .. .. . .. y . .. i. A. . .iaq. w g,a.?: ,
jQ.[ ' STAGGERED TEST BASISj.h:y.,a ., kf.
- a - M@M- c. y w y g y
.% u;;.,w%h@,q
.i q[]. $'n.4 6fl W.;, .y ..:;4.s g,d@ .
-9g WM1 x 'Y 21.33 ' A STAGGERED TEST BASIS 'shall con'sisdo'fMWNMW;.m. .w -
g.,%. W..; ~. . .yq+r. . y;. . ..g~..;;;: Mp. b G '- A test schedule .- u n for'n ; systems, subsystessi. train
- c. .
g>n.+.pi-b.i! H .f 4 a. or other designated s
;- $M the-spectfiedftest. interval into n.
Aq(AM:7: ide. M <~ l . i components obtained by Hdividing 4-g.MU5%g;M';@yw# t... 1 n.gw .y t wy . ' . e . . equal
- a. p s.,ubidtervals,
- p. n . . . . .-+c.a. .. n.-c andiSr&.*W7.,.4p
.w
. J '
V Wmg:. g..c.L. 4,.,. r..&, .- Wi !;p;. e. 96m . &. <A :-.
- cj& W g. ,p%m.
M3...,- .,..n, . .g.7: b.
.s Yp. kdW.c.. , ;The testing,.of one system, .subsy. .steertraint or,other, designated Ng x e ; %vM; Q? ~ ww_ component'at .m the beginning .of,each . -
me subintervalgug?g4w<;f-M.h .- .n
$wMy n
Msha s. -' . Ws T =Qh mt , UgM, y. ,.'p.:pme". e. .Q.omvyn.mNrp.y% c: ' u a%%g?p.h; - - THERMAL w 3P M POWERM+%:w%;Wy$$gM.W . heWmt:i ygdWS.W;.W7 te:,g.g:341
.Y VC.G.L r::c THERMAL .=.2.~. m PO.;WERfshall,be' totaPeore .;< ,
the.m. heat transfer;l rate. to. the reactorff,W:.c
<< .q.p., a;gs.y. m.m. m
,p. . -
.c ,qyp.g;.g.. y w..w...x:m;
.;q m% gy Q%q.yx,; .w .
mlpp.. cooia"nt.w: W Q Q @ M.; Q m W W W W %q gum. =,
- i. a lg &g; ppg- TRIP ACTUATING w.a. a w - DEVICE' w :.M w M.WI;WQ.NiR$ 44 OPERATIONAL'TEpffy? A%g..,m kWp$Ch W W t CLW;*;&+j.$$d A
4 dw{yVL35" A TRIP ACTUATING DEVICE ~0PERATIONAL; TEST'/shall? consist :. , .
%.iMMTrip' Actuating Device and verifying.0PERABILITY of alarm,. interlock' and/org ; ..
l,h4" %tr.ip functionstcThe TRIP. ACTUATING DEVICE ?t .0P l, y-V..M2 a.t:the.s adjustment',srequi r.eit :S. .a. p bas t. poi.necessary!fof:
. .
- n, t. swi t. hi nithieireqidred ss the? .accura Trip" .' Actuating'
. }j $1'M4W
-- -s-Device such tha 6,,.- .e > d c
i 4 d
- aM \ P e'
J .
.' w.gv.$v..N WA UNIDENTIFIED' LEAKAGE ^ <
a:w
&*tW'T'TWJWi& . .
I .. u , . . , .. *W-^ ..:': . W N
- N A f
^ ^.'1 1 be d1 Fleakage;whi istnot'. IDENTIFIED LEAKAGE $.W ;
#n [1.36EUNIDENTIFIED7 LEAKAGE's U
lh or/ CONTROLLED LEAKAGE'%WW . Mf ?pi W~ 4 m' . wwww *fQW2N4%ga&x& N2Y n$$t w - . mo&n.m,F"%j%M v k? 2
$g m ,m.
~
. .. ~
,hf. m.lhcw h 5? f m, h?NY. ,k.Y. hh w.=,.Y
~
.' 5 4 m ,la.. n.hh. m. n . en.n. a
- w'a*
W qc p 1*R. ,1-6N,~ nWA. . . n4 Myt:* w ..:~. a n. a%! / m . w.* D * %. -. m. ... n .... . g;@*:. e Ty , p #r. s4. > J t '. ': i. n'5- N ~A.Q h W. ?.y $,1%* , . N.'s.' ) *1r.%,q,Q 3 -% *% e
=
9 1g #9- ,
#ny, .% g' i.CALL.A.WAY.+
u .
- m. UNI,T/1 igs 4~.
1:.'.Mp W. : , % M} M.popf2,,$t,:.rn~.
. O,"smsg:,%g:::ww. .
.M.w ky. ..s,s. x nm w L - s.p%n.cg.y . .,,kb*p.. m.-.gg W..t.s.g
. ,.w:. . A.w)sg;;. ... ; . ,
.v .
n g.
~ ,.tgj+. q d. v., e ..y ggw m e w.q.
.e wa r. <
. c. ' M* '
b i.-A N y- T "e, p *n
- W,g. .w .".t. , s
,3
': *"I ' - *
,L % S,.,',d
.x g ;-
s
&s M. , ..I'?&y R 5 %g;;h%p. M s dh? GM.W
g 43W 4Wg;.Q.).wV, P &' > nMq g,q . N &&ktdaWM
- r,
$r-um:m&.
M&i$n-?6%
- b W MV.d@%y W Yh~W .
. W. .-nS. &...dc% p%g "v*t.W.,n.y%.a%.*;
- 5. .?&y W,$a. .g;*q?A un 4ts
. . -.s -W.gy --
W-W ... g.2... 1.&y kk
'~
1 DEFINITIONS UNRESTRICTED AREA 1.37 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters.or for ini: trial, c crcial, S:titution:1, :nfer recre: tion:1 perpe:::.
" ^ #'
VENTILATION EXHAUST TREATMENT SYSTEM
' }'
1.38 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate
'orm in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing f odines or partic-ulates from the gaseous exhaust stream prior to the release to the environment.
~ Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features (ESF) Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. . VENTING 1.39 VENTING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not pro-vided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
? - WASTE GAS HOLDUP SYSTEM T.-
.["
a 1.40 A WASTE GAS HOLDUP SYSTEM shall be any :,ystem designed and installed to
,- reduce radioactive gaseous effluents by collecting Reactor Coolant System off :
AJ' gases from the Reactor Coolant System and providing for delay or. holdup for' ' f ? >D ' the purpose of reducing the total. radioactivity prior to release to the . P u .M.m::.:-environment...). sp . . . , ..
..~..
.c 9 .
- t., 4, :- , w.. .+. -a ,
x .24 i
,,~ ~
& ff:h.y. <..s ,,'. .[ A.s.
.'}'..;.',
~ . M.- ,.. *. . , f.* g: - Tr. . > f. M. l,.
. mp ,;.w},'. I-[ ; . 7.-3.e,y' >..7, ;~- e ,:.j.* -L,..y. ;;6.'N^
'.g., , , ;,.,- , QQ O <
,n
,, h. '~ ' 4 . g ?,7 .. .~ '.9M.Md,c WU P w,.c%*M~" *
.. .i WDEATME r . A v,.,.c 3.J #.wW.*& .W.yf.fi.gt
3/ . ... 5.. - ^
g"h,9',4;i^l_Tggtr
- g. y' QAb9@AsTE/. T4% TEM . rg Gn:w%
- Q q(.yy. . . . ., , g. , . , -(f.',.
d.4Qg,Qph,7.MM , .;pgiy-y:Qm g;;gM k
;:~ ., . ,. .
f.; p "j A.*W - M . %,yn. . g % # G M & M G M 4 e A # i 4 % u n co, % @ &g ..R%ak L h h.h M $h' Nkb' b Tl'$NQ%@AbbMMMg$ e u
- .~e .. e 8 r N d M %a .a @w ya:: n N .. w k .c' w , W M :TN d$g -
g~.M'.. hhh 6,~ ..d " $ Wh,'g?b@h ' { n .<? a c O* q -: ~ s
.v . N .. :.
f.g ! a ;,:.,{ ,? -
~
.,. Q* V .5.,.a *$%
. .'*,.' p ,Y ,,"*k,,.Y h
- .. .$0.m y.. $ _y.cr.> w' H r., . :;
. ;,e M;' s.g.,. u . Y.e.YN, m. ?*, .W Y :'" "lR~M .-' 3 VW?D,&C %.y:,IQ6W[
y &. ph... C,.t .. C;n,@*$ s ; ~ C. r
- 5.y g ,.
k ~ v o.
... b .
y . y, f -
,. =, . .<
-r .-
. : .u. . . / .. ' :.
; M..3.&.u.M .n :,i:. . ~. : . p .. :
r .y ~ < ,. . ,
? ; M.' ;< .: , ;
l(,~*.,.. (' A;;. '
~a-CALLAWAY - UNIT 1 o d.
, ,, si ',.-
1 .7 A ' k ..
"4 % ; * 's. ' t
.. .r u. , .
..j.
1 Mj.h.pk.f.. mr c . . ., . :L 'l - - y" ch:'8 . h' h~ ./*~ y%:. Et: 9 . .,
. . c. v
.>y' gg.
t,. 5. t . . . . , .e, .
.1,.. p. .,
k 6%m,B'5..UN 99 . w .i. . . .@t-@+?.I v-W.. -@-r - ,,: M . M n . %.hI" A ~. W,.x.s.. ..ic W.'.Qj$" r .m'5h * $, xid~ . . . . ~ d5
[. DEFINITION 1.37 l. JUSTIFICATION: The definition as modified is consistent with 10CFR20.3a(17), which states:
" Unrestricted area means any area access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, and any area used for residential quarters."
" Unrestricted area" as defined in 10CFR20 does not state or imply that it includes areas used for industrial, commercial institutional or recreational purposes.
Definition 1.41 1 JUSTIFICATION This definition is added to define terminology used in Specification 3.11.1.3 and 4.11.1.3.2 which was previously undefined. I l 1
?
b i-
- .tz.
- 99 Technical Specification 3.3.3.1 Table 3.3-6 Table 4.3-3
. Technical Specification 3.3.3.1 and its associated tables have been included as a portion of the Radiological Effluent Technical Specifications (RETS) as opposed to the Safety Technical Specifications (STS) in order to provide consistency with similar instrumentation tables in Technical Specification 3.3.3.10.
Oi 3:e .
.fi I
I r l
$,7't -
l o. b {. i _ - , . . - _, _ . . . _ . . _ . _ _ ____ ._ _
. .., .-- w . . . .
~
.e 1 ..
. m,_ . .~
INSTRUMENTATION- o. >.' . , c. , A .v < , g . w' .
.~.a s . ' ;+ x.. : .
.t . . .
w, 3/4.3.3 MONITORING INSTRUMENTATION .5. oli F... + . m ; .s 2." k.0.o .. _ , . _ ,. -. ..,.,,.s@..' i.6. q.a.c.uw ;c. v. . , .
.g_ wwm. -
,9 r, , .
.* p. u. .. . .y.o . . ~ .,,%:
me. RAOIATION MONITORING . FOR PLANTy.c . OPERATIONS
. n e c.<,s MOYMdm .,n...,D,.. ,se v,a O...,,.
,E.:.x.
v ..... .. 3,..N..a' M. . .n. .E . . T
- N.
-.,.x...-
. .,x: .ya , ., .J. c . , ..
.. . . . e ;.a :.
. m*m^. 4w. x.n.g ~y. n. . _c..
- e. . ..
. LIMITING CONDITION FOR OPERATION . ~ ' C ' ' "-
M Ns - W' 'r '. ~~ . . 5 - . S4
.w..
(-p. P. . e:2.s . 2 ,. *3.,m 7. c.: Mu,e 3...j,.*%p;f s
.m: :,_3 cs4,"=.g,,j.
s . ;, . .*f -@. . . ., I s. '*f
.,' ','e 4..-
'.... ..D.
.st c..,.9.
nC M.' ',..Mey'. ,b .Q. t. .q,e.
. g$ b.?-:.-7,.J .
m .. ._ .., . ..a . . 3.3.3.1 The radiation monitoring instrumentation channeld fo'r plant operations b' W=.- .. . shown in' Table 3.3-6 shall.be OPERABLE'with'their. Alarm / Trip Setpoints within ' W Y 6 the specified limits. . . .~, .. a.s :.em ' ,' .4.e. 9.v*n. *
-C~
re ..Au
;;..A 4. g g.
.i .w m w .. . v
. g._, .p 3:. g. .s, v.. ,9.p.glyQ:g!4
- w. . .. .
u-, y ;g %q y.*Q.3 p-
- APPLICABILITY; , '. , ..
5 As . shown 'in Table .3.3-6.".r;M 48 tMT.W 9:.W %. . .;x.
& w%
. ACTION:
~
.a y- .
x.
.- M..:u@,y7'
~ .n.. :.%%%N: M & m t % h,;: m, .&cgcs
.W e ,..+nmMn- e 2A.-
m
. s.:c .. r.. :: t. ,x u..; g..s
~
, . ,;mm.s.t:..r._
n v; n _:ww . g.g. gr y +tw o.. N ;-v. w
.v
.u. ~
gc J a. With.a radiation'menitoring ch'annel Alarm / Trip'Setpoint for pla'nt
^..f .
a ' operations exceeding the value shown in Table 3.3-6, adjust the .x. 1
. V; ' Setpoint to within the limit within 4 hours or declare the' channel- ~. . ,~
n c ': ~ ~ a ~ L m.: :. - =:2- . . inoperabie. w . . ::k: ). , . ;.. 3 :.:: ,.y.:
. .( - 4 .w m m. sr..m ;;:w. . %p &. '.:. ~ :+
w w
.u. .
.w .
. n..
q.. . ,a.. y .,
- b. With one or more radiation monitoring channels for plant operations ', e ~..
j.x - a y ,y.
' inoperable, .take the ACTION shown in Table 3.3.6.,. J w v..f C -
e .. A, u .a : . v.,. m a y.. w:v.y.u.w.,. ,g x. :.. ws w. y ,
.w- -
x! '. .g-,.. j,. , r c c.. The provisions.cf Specifications
- y . ,-
..cw. 4 . .+ .3;0J3 and '3@.'4' are not applicable'.M.f2. .. .
. .<,.t .p.. g ;m.;.e.-p , ., . y ..q .s
^f.
. . ;M ;f%. : , f f f Wy.M; ,;.c.s .Q '. s m4 1,i :[ y :'yM}'.Q %y. , M k. e. p?- ,.g.;m
, .W.W::n?.n & .. :;i;+
.*.,m...
. x v .-
- w. . . t.W'.
w / y',, .. m . v- . ,.c.
.y: ,;x;; '. #:/:1.k g : % :D ::w w.+. Wm.\.~.m.mwww ..gm; >w n. ymr a;y.n.u g . :rw.e.
p &v @
. L; n,: :7 mv.:.v..n. m p.
y,n
.?
. a. .u. w.t- . , ~ - - % r..~ .s 3.g <;. o .
y'J..;. m .-p e, . . , , .. . y.v , .n ; a p
; v y,.,g .$.c. ;.,c gr y;;:;:.,;.y g.;.r <- m.;1._r, p;,s, y.,..;p. Au-5:y.
3y g;,;g ,.
- .:....+,- -y.
- ..n -n ., , Mi;Q A-W.:wq@::u nW.:6.Q.%w..m , ive+x.m, :s - ;. ?Q W-y;p'.4,g*; :.d: HTS $NMk'%yg.y.n-Q,.4.g. H m.
Q k% [.., ::: StIRVEILLANCIREhuIREkE MS'Y55Y2$N5N;w%%: N M M N bc.,: c t,.[
. .h.mk 3
e r a.w . %w .. t en,ac. $c. w :. u. s _s
.w. .:... e
...mqw. . .q %,.
4 w,m e , e.:
;QR : e c.:;.r u m m ::4' - wnn > m.,.y. .
3,g,Ny,;@Q.n;m.u 9 p...,: e%,. oM.. ..m,gg,e* A y g. ;w.w.t,
. . m i,w m.,9.. ..1.3gg::.f; w m. mw?py 4.'3.3.1" Each radiation ~ monitoring in;strumentation channel'for plant operationsEE t SdEm . shall be demonstrated OPERABLE by-the performance;of.theiCHANNEL CHECK,. CHANNEL V %
- y. TM*' CALIBRATION innd ANALOG' CHANNEL OPERATIONAL. TEST'opei atio'ns Wor' tn MODES and 'atN.5 "
Ng$.W,'JQs. .,e . N M J U. t.he n< N $.+;( ,frequenc..ie.s N.c . m.d.S 4.s.. ..$. . M. ,. n . oY.M shown O M. n ., %. MEM. sn F,'M, % in Table Qd gg M d.i M M.n t a.n:s 2.%ne E . 54.3-3...C 4
.ih Dj @
w
' k.h' c. . c,. e z
- j b.$. . n M- s .ikM
~
n%. . gis
!N w.m.v'i@h,,' w@h:i;khh.g.L.Nk,Nihh
.m g p J q gw& %my:...
.n$;v,,. .x)Ief* i4r.atWp. ;c
.M.w. As D kV.h .My M.W%,r..e@
M w W M.m..,,d. d-: ..M"#. NMg64
- v jQQiwmyge. ..my M n.
et.?$ w g v. yfs q p .f;&m:. qW l&&w~ ' . [ y , Y .w ' n
. $gf '
s a . N
*$:nNWNWMT50ht - e %; % t* ,. %&
~
bMWQ 5X.O' h*$,2,,e. @%AMMM 28Y W.:; s Ww;u hQ g g $w w .xyg~N. $m % Ni^ $?~4( ' w. %6p lb e? %r&?&bM WL h%$$WW+W
. @%:w %
at
- z.+j , n.
u y4 %4%:d 9.W"U;
;R:e.v r .W. .hM M p %s;M@&p.41jn.%yM+x.g;%e;;-fem.WWW i .2: l.:.=:
MN '-
> :??g
%p..y4
&h w . . ~: *-
x~ M-w . Ax: ~ .,...y . .s~ m-..yz w w. b b h h . 3-h $ Yggc g pg ~. g~ u %p, p ,.. W.w).w, ; .x .. .->s%.n .my:.w; .M yp - . g. .:9. . :s.m. c . &. . , kk b$$$Yh,@; UNIT >1., h. k '. .;e.cu.qws:y:3/4 $,40 g., g.r a y%y,g WWF2.c CALLAWAY g m .n y t. m g g g h $ h W : @W b Y $ h Y SMMiicMM%a .m OEMMMS$iMMMMMMsWMR n _ 4Wim_ _: X+#mw% M h %.K%M +@.%
%. h_w%. &. -
P+w:eMn%mpaw: _
=
d::TD.T. 'm.n
.. .. - , . a .
., a -
'!' .y ,,~ s 4
.? .
;;,- y i Yh, e l' '"..,.'T..y. .. y '
*s-
- s I . *- ._.? *~
,';.,.~*
s
,. -,. ?., , ,
. *y, ~ * :. r. _.J ., , ,
s d. -e '
*g f.8
'. 9
.I==
A
.r & .
s ,- ,-
.% , y..s x r.c
,.- s
.o..
. ) ...: . ..
.:-. . .,s-q r-; w:
ep . . .p,.,.
,.w. . , . ,*y ** , . .
s'
?
., , . u: s . .:, ...
- m . ; <.. . ..z . .p.w: w , 0,. ,J.~ : ' ' ' .
.:. -~ - . '
(' % ,; . .* .. , . , . : ;;, , . .m,. : (.a
.: v. w. e , n . w .,, .~.m.. .: . . . . . r -
-[E., .' .]:. . ~, -+,., :; . _ ; j 3. p y
..-<,; , . . j-y 3 *$ , . .s p. :; t i, .i..*;g,gg,--w ,Ap:.
~.
.** e , fr; * .,
.w,. m n..
,, wg ,: ,,. .,,e.m~. e:
.., , ~.
- w. v.,p .e. , ,mm.w.f
- m . ~ v . . . . .
f q r.s.u n,m w,,# . ,m ,-p.m.
+..+
. ~..W.. r.. . .3f.a.~. p,. ...,tw. .:#. -xT.c.H. .. ...y
-. t
. . -;. ..- . c...,. :.; w , .,;, ,+,. >c.. ..,rw
<g . . ,.. ~s.,y.e.,s,9
- wr v n,. -
. .. e . .a . . ,d 2... .,....e c,.
w,. g
.. ~ ,.x,.<,-.,'..... ..
.r e... ., z <<s.,..
y e n. , . r.&87 a;;- .,s . . -
- a. 1 9..
.a',.
'(3 ,. eq [.ye,& 4. c .. f .f.* al., r-.u*
- g /; -;. . .,yf ,4,, . ?)c.Ag 3.r3-, P -%,^1i%t ![j,4-j 7,... . ,.- .. .. .
o
- y .:.y y :~ : - . ' ' 'c.. ! : ,
3 n ;,; . , , 4A. :: q ;. P. v b p t. .
~
T .-;;g, M .: .;p- , . , .<,;, b L ... . . ; . ; ; ' . . b
< u.. . en v, m;e n~ r. 3-. gw:.;.;g,$;w;. ,:L;:2';,; '.Q@W n r. 4
.. n . . n a k,: y .' ..% c. g.,;,.M N :: Vnn ' '.;M. .'
.\ % n
- 3. .n . .tc. /
q.q
.s. :;.p - , .u . . ,: ,g. w,p...;
, - ~ . ., . ..
a .i
. . , ,... . + .
t ne a ' r .. .'! o,
- n. ,..c ,,
- o. s .:; ,:,t . .. . '. A,v . , .
m , . .;1 .. . .y.s ,,. . ,a. : 8-
. - . . w.a .. f,Q.g .
. g,.w 4. m.
+.. y .a,s
- w. m..y; -
g"
. mn +;&p.;m.m.?;m,/,
~ .-m
- g ;v s.- .c;fp,^,p.t
- n. a .:.:
- r.n. e . 3 vm,nu,n.w; ~ .,
. 4 . - : s.y:y.6.w..+, -
.~v '
3v . A. w. .; ,! .. .
.. .T... .ht&n'YN.>'dgy;..,g c.
.D.b.,.g ..M.u* a.m..,w;: 3+*2
- 9. . . ;.
"n ',
1
.C
~
. , .'.i'$
- O_~ :~
s<
. ' An e . 'L :1. *# . M./ M*i(,' o i% ";?a *T 'Fy%'.t:' " '
.g:..,
=4 J T*W A?..w' -- .:.a
, 9--N 1* i.b q.m ;,, : . , w.-; = . . .,s : k.L .C ?W.p*P k .:' *i-L:sm..W'
- x. a ,~;.':
s a *% ag w
- i. . .~ :
- 4. - , >z ,.
.> " n
- r. ,
( J'
- y.<w8E ..O='",='.
W;. ~ '--
'"'~'a .
..,.A,
. -M. u.- * .~. re . w'- ' -'. 7. - g . 1 .E
%. % % ' ==yA f'- -
E - w*%..,M.q:.r...
,#.. - . Axt.
.A . : r . ' r -; ~~. . ' *a. v-5k ? , + L. - :,.;@n. ,t y y ::n y <,,a,&y.',. u&2 IM.
s ..- t l h:
~
p n m ~-
-. W t' G2p q; &,,Dac t -
. m z
aw - _,
.. . . . , z an,,' g ,y< . .,,c :,.W.$7 .da e a-cM<Q-*4%g' ~ n ulea ?;A.%cJW @>; M t.'.f. W.i 6W. . 1m
-! m .. <w vIAm
.o
+W.&M. ,n. e m;:.
.: u;, r p ~ v. .c -
. , -...rz- .< m vm. . - ~ s ., ,. ; :mA .sm# .%.M .w.g v m b 4 v O &.:e,,9.~v iq. .i W. , . .
. . - + w :. -
.s sv :a.
u . c : . -- m s w
.. < . .m :w , O.. ,u. ::',;q w;r w.
%-' . ~ a
' T - 9,2.- #.y.'M 4w H:c:=. y.ww:h w.e.J;. s. -v,. - -- ..
W-
. og ~ ..
w a N' .' . -s' .- ?' L:, -
# .u-5 W4.1 -
*v
-'-f.
. .. . . . :; R r *gs,. g %,n .g d..?.:t y.:iQ'-
q,j?:.i.- -+R.r. r.,ty ' t g ."';:;'.;:.,. L, g, ggg y %: 4a
'...>** o g m, m ' -'ir::1.} _. lb.,.Q'
.p : C'fpe: L*,( g.M ' ._ ,u[.;fg.
's ,9 i .
~ ' 'c , . n m a.., v
. : .;r;t}p.p?yu g' )y* g.a.g:@.v .:%. . ,;"..;?, .;n .
x aw - g- ,, N,N -i
. c.
. Gj . *:-
- a. m - m y- . , .c r y~?
< +
W+ - u mp
. ' n .9 +<'w
- 9 -
47-
,,.a a, - 4 .x.:C . Iwm.9y
.o. u. ..h u.y e,y/ + p- : >;M .
<M a.
a:
. : q'-rE;. . k. . sz +- . - <
e, .c.e - ac . .r .u. r.
.. $a: s. .y-+
2 -
.e, e
- w. . n ..
. . u.p.. l~.f.. * *e.f ~...,e. .. . ,.,,.,',e., i... , , . .. ,. . ., .
y.p% : o, . . :
~ , .
y
, t. ., ;.c. - . 0,s ,1 -g,e . , tQ. #yy.
W
-: o
- c ve.- .n
.: q:. -
- g,.
u,, 1aa mW
- n. . .c.
= g.. . .. s w, np .w.
w .g '.v
&- . . y:>.54.
- e. .n.
- w. .M. >.gs g..Y,f., .s. g;,k. ~.s..wy nw.a s 2.p; .,.er
c
.s ,
"::(.
x < , , .
- QwQ M.h ,W
'!M$'"'MQ: pj;.; c- %x.:%y p,;.:u >-
n% 2 - : ' , f.
- -u- & M J(SL&. : c ;A
- %- -M. . , sa w z e w Ecc . L%e ., g w.q& . . , 2,c
'.; ~
.A ~ n 4~,
i
< z =y a,. . ,,Ac .p - f:@Q o e;om p w Ac ~m;A,w.;4r.M.;T.M.-Q._y,ih;
.c .-d=4 W(5.C. s .si4..':.'isJ&in w
w: a,zz ..,.# o.
-. s,.a.pw 4.w w. e.w.,.m.w .. . tm L 4. w\e.v. w-yu..
m.
.. ir s o .
- ~. aa : u N-:. . .
y#_A
. ~t
.. a -. m ..
z ,
.>. + ;S.s.
.n -,- M. , -
. 4 m n - ~ m.
y). -.a.etw.h
. g 7.,jgy 4+c;;gg. .- 3 w m. hag M
gc-.i.g.
,. .. a , s.n 1,......,..,e ,w< . .j.; m r. &ny.' - < m . a: .e. N < 4 };;yT. . .:. fi ;.y g r ,5'fQWMQ.n B . ?,:'y ySpr.nn?.; mi.w: % .~ . . mM. ..'.a--l .- n Yr;;* .)n %.; . . . . .x.c).m.. ,, . w W8-?.mt .~ g ;* r; i.. @ -J %w } .G. ',,,';;) f y k,$ w. -x .q: W i % . - rv':sp q. 'S% -a. .m'yw;:: '~%:, w @y12.Qp%';Q.if y.W.A .e.w O. q~f*p~R g?'Q.Q, w - m .4 r. : r, n: 5 w. - MM;+.M?.' . Q; ,#;p qW. -QTsw "p .n w . A.y.j qr g '+ @p 2 g'9 .r.ag @e.g sv.,yE. E f g.s a a, , .S, ! c.d, yr4*~.e,~.;.. (Q 2> u:.g. f. W -) pt;pM . ; , t,P, . - v ga.(cr v.g W 9 ., i.-N y- @3.,.,,. gig,. i uQ< y.82W t#7,D,6,. s ,q,.S. . p,,. W .c . p~p@ ,. a r; i ' Ft 9.st@J.. Je-.7.. o g . $ o. 1,J. W @;; m,Kp'i W
- s 3.+w;.gp, FQ ' , @M'ff.+3%,;,,e :%
~,f, ., .. jet ,&. t M4%fi s... * > A ~ yp
- & ::6.Q.
. ,a Wy.r;? e g ,.e u 3.. 4.W . e &.2 g*Y . . A. * % 4. Eg.a a W '%c . ,& f.9
- y. s.m.4 .
-e ;.,, 9 .x .;, 4..- w- - lr ; .:mm.w W.m. -:7w h':., i %c.gdQ' W'1 t<x;.w,.x&%r='?o&,h' .%.ht.:Mx d 'm b. ' Y s> i 2 M4w w rh W:& .W rg .. 'qg. n n% $ v. .~:.Wc:<m..e.. W k de4W 7: wq ir . ,, k &.w m,,%,7,n n .- + o .g' : g e N'.'". 9:: ...w :. 5 < . - s. W o n 4tDs'Tb.2 h5%> c w. .gcc:?f 4 pH P%'*%w&.K,'4*%v.%.W~y.;a %R. % : ph m r W .qd.y -:1q.7 ' ^ = -. s. ;# o f s.;.co%nW u e . .F>..W s. - .. 2, ~w..e 4 M.h,Mq.9 e .or;y-86 5"i:q g . 1 . - - +M'dNWYT 4: -.c w:z,"M.Y$iny.-ykg.3 M~nMdM... . ' N, NhMMO. w .@ < nr;. - o-dN t no a..y.::e .,GaN'.<3@W.s_.pm p.:. .< = .e.o o .o + e.a .pw '"- sn~ ,: wye M gmm. ..>. Ra:z ^o: o . s i a -w - m n' ,.I '- t i i - e owe. o >e 1:n-e e g:.W,~rh=e-@.g' 4w%p;Ve,.,:q/.J-r.. - e .< .c.:..a.u ,g g.,.. .. wy g n.Q .<. v n 9ytai-i%2'QW .J.:.v,/s; v u.A .-s.4,.cc t . . a .+.. o . . .<., .,w_,. e.m 4 p.:Q ; , , '.e, C.> . R. g< ra :\ l , e o . sqs tl:n,
- o. del.:
e "e,a,,- , > Of
- w. ant;*
e 2 ~*~w : x.,.e t'n a .*e..s- .a c ww--y.;- EThm..M%#m~%.#,nt .4:4 e.~. ,q " i* - NW. h? so [.-: l e.y- o T m .: ea e>O e % gy ,,o e. g .&..;p
- 7. o
%g .s .., , 4,; ._cm e,n eu- d8 4 c a'u-Wm ..;,r.p s 4 L- .~ 3 . w%ms.m,m ~ la ,p.,3 %.g.hj , . f.,4 - ew t y-a._u .6..P c 1- e o a i [ i o - e m..;m em u =g e t - uems s o sof-sco A .~ uuse - a du- I*+u o* c--a - u: 1. y v~ }j%7 f. l.g.F t @.; v....;:,r M 6 b"fo<gw- .* ,ee ., .S ,%ep, u.,pa.p.W; , c.w,. . .-] - . . gai, : r, a::u y - o-.,.a . , o "b, c,y,,a p. o m .s a a.r.,.,:s+ %. - o. - , .. e ;4 . s % '. > 4rs:2.;r . ev ,. e: s w t, 3g. .,c... -@e. e. .ol .
- . f M'%*d.O J 1 co$
- :y :
pqc, n...:. ug- s. e ung a . e uJ e e ( 3,,pc3 < , ..g - e.e d .. L= *ke4 .MW w M*~ kg/i' .c c 'd 8"' 4. d8' I' 8 8"' '* 88 88e'" '
- w dd'E l',.
wy M.h, .~8 5 .8 .'c :
- M..p:,W:KM.et W: ~g ..,
%'$bT ~. 5 .i ,- $ @>3 h.~p, m;&m. n.- : 9.' .- :on une q w . w h W?c. % % = . nA-o u .s~ Ot :- s%wwc - p?.$.,/w% f* m. %#. m 3!w-LW
- , w M.a:: .s >i .v W sw 0 M w:JiL ~~ pe .
e eM..x:fh..nM A d M**M., % ?S h' 5 ?.i. M.,.c..' W i 3 np b ar.tWsps.gw(' . en> - m'*% l@:*m4 Mw. ,vr% ' [2 k h T M. O N b k . .. D. $y[p' M #N.NM l f i %.[lsM l' hk he-S , ' . Y. ., .Nb . 2 Jew g[c[W,4:.:;w%yu%, -[:"' utm. : pW W. c e m3.e Mpn W W W.;;M W,'iy+,4ysg ;o., e.. .. m-. .... .. @Vw ME .n.v.f.m_ &;x<&o%9 b :vg,M,.: - !yd @%.yk, v. w c-M Cf: ?W+r 1 .,p...y. . AW+. )+c.rA &*%M.% g& we, .,- .. . . ,(m< . .., ,.. .~., a. .a. .r . a w. .t . - . . . ..c%e . .K, ,t , .m /n,. - < 6 e. . r .c.. ,. . . w.QM , . . - m :.. q n n -c dh - ay. . a -:r..My x W[;$t;Q!QM.';CQ;& '. a Y.;.? l. M u,<? 5'-W'Qv& fe$?.'! >g%qi . 4':q,, ..,d.m.. ,% g*rL &. 4 .. $wg .s U,w, z. . . . .. *i-.n gl.fn ~ vi.SW@.w&CAU.AWAYs W aces W W d W .W M d' W 9 U W -UNIT 4e@,$<1&;p$$ #gh e W M.h.fy,"?h$fh b MOMp W6 Q ~P;.i Q W M M' p ti3w ssWW 44%Gd9 i' M@MTg #e5544.: $w hw 4pMpw .umem,.n: ,Mhp.en W mSmM & 1WWW #m M@ , W+. gX S mn M MB uY%.e - - Q ~@h M M&W: Mg . .=p? % h M &M . ce . .h fc L , . - , . , v. . . . , .n n ~ s :; . ;. . .-. vv .
- .5L
.-- -J - '- _ ;.. J :r.; . ?. TABLE 3.3-6 (Continued) - f.;im. ; ... . L. .a_
- s. .. % .,z
.w x.. , . ... .*-v*" . . : .a*.P ..*..:'" u,:... v. e n-r .t. .< , s~. D' N.? "' w ~ a e.~ . ' ~ s, w .. - .>. c p.. w. ,." m n..v. '. m TABL~e NOTATIONS' .M:M 2 . . . . g " : #; - . . W ...s 1:.zG . %'" , . M , _ _ ,; < ','y ,.% .W ' <. . "m. R W: y. MW. r;; .} v.y L t'gj. ;\'.' Q. ^ ;K . ., ~ . l,Q
- v. y . ,.. . ,,
*With fuel in the fuel storage areas or-fuel building.) ~ C W;5 % M J. . . . c. "*With m..... irradiated fuel.in the, ,fuel .. . ... . e___,,,_..,__...., _,--. ........ . , , storage areas or fuel . buildinge $$Q%]; . ,_.4.__ ___., ..a.m.1 . .. m ,... c.o 4,:yy: m.p.s.. ai a;m*:. .
- n.: ? .: +..
.;, y . ,, . . , , c',, S, " +' 3 . p..Jf. ,:,;e p W :,e,g . r' ACTIOA~ STATEMENTS , . ~. ; ~w,gmn.zq)p,.MMM._M;.ww M., #o .$$wwww;% MN
- q. :5. " v a , . .
.<;n , e . p., m ? M. :gy; m.~..M.e e. y ':y;( O.M..- y ACTION 26 - With:less than the Minimum Channels 0PERABLE' requirement," operation;. ' 'lN9. may continue provided the containment purge valves .are maintainedu.. . ,
- g .n.w i, e d '
- .E.h.[
- .
o ~. g Closed.3 _n. y ~, g e. g.w g g y:o w c_(.'~fg g g.p g ,;.ng..;t. ,g gg.f ' . _' With the number of OPERABLE ' -~ - . . .7 . ACTION 27 - channels one1.less' than the Minimum' I ~,l'M . Channels OPERABLE requirement, within 1 hour isolate the Control l' '.' fy'- :!- 4 Room Emergency Ventilation System and initiate operation' of tne' 4 "- ~ ^'- . / ' Control Room Emergency Ventilation System in.the. recirculation mode..
- a :c - ..
- g. ..: ;.g n y ., , x _ .g . , y,a , . y.y .. . . . . . ~ -
S - %, ?~: *g '_ACTION 28 - may With less than the Minimum Ch'annels OPERABLE requireme'nt; operation' continue for up to 30 days provided an appropriate portable . Mt.s $7; f. , . continuous monitor with the same Alarm Setpoint is provided-in the~, !~ 9.%;d fuel area. Restore the inoperable ~m'nitors.to o OPERABLE status m. 4 ' WJ y;F ' JK within 30 days or susperd .all. operations involving fuel movement - in.the Fuel Bu g%;. f y w &.' l y t.g. } p:;. yg.ilidng .:h%giQq:yg@i;.t!';dpW.,d.@ . g.:g.?;pp n NNy tz.QGQ.g.4pqi: <. g :4 M..- Ge ACTION 29~- MustJsatisfy the' ACTION requirement for Specification 3J4.6.E ~- hY,.,0.., ~. e y ?$ w w'.&.,..,').hl.8h.[.t&&. n-.c.. n.u... A ~..e,dll$. >$&.~..hi!h.,, hN:s_}0lh.$kw 5h 3.4W - ..r w - . ?, . . r.... s .gc c.%p r. NN*s[h.ha \ y1' . .p. . c . ~. # . e r . n y. .s.w . w$/-Nh[M,*l$'.dM$dN,'.N NkE Mh: .~ z.-M3 n n.m: h >e ..;m. &m k %.+: ms g. ..w;ih. . .. w n.+'M f m'ansm' w x s,M&n ~ . yp n@y..w %+ w f . W4W M} W.a C . h amg.iwc : Y sMN.. hME. .M@. &.. :.i.w* m. n r n kh.. 2 N,/21M.b.W,mem'%rs%' w kNIe g . yX ,N%.4@. x .~PWWh.6~hkIk.a?![ - Ws.r/ Wmy* n r, \ M u se > e.xis 4e g Wh e n. u Q -L n 4 r ~.y::v * ~ y.;.M. % fA a n.w. . Q.,A g.*- hd.., gagN5~M. n W W. g .l'w ~.. n 7M.uLnkn.s t&. v g. . .w.y r ,$ky .9,;. f. A;i 3 .esc n r QW
- ~.s g.k 8 w 0 d -Y. ,: W~* w r . .. .
$g&e*&yllWw%$%.f.R'fWl@l&g'k"h. 3:g .r. , ury;va gwwnw&' ?:gWN. '. 9:w w &. j.&l&G @h}$"%h.SQt:-jf,+*Wl[w.* % . ym.7 .c vt n.n
- s s .?
$$h$
- w. yen.qm .:
m+hh ,v: m ::. y m c.. h
- m
- c:
eo>w g . .. m n .-H. w ar.ast.m e g w e. % $w hk y: W di s u c 9 p ay ..9.mw:m-t. se w w .. ~?f &.m - ww$ nu..%ca. m .. . mw:. a m c n~. .~...; .c.. Y m;.i l p , h . h' .h* w:syf h~r:'h-thMINf5Ni . . _. Q.l.; AfY:W .w., m W$$.g0 UWRJWff(d.A _Ym&.4j. f*E9: h 3MjM2g i Nt M 6 2 ^ M M.ww@@w%w%w;s4%g4.M&WKG m" M,4 m.amwww%. <IM K. gg ggg g&., gg[h.N .l, ;Q l g'y*g ? c:2k~ , ,p. wW @,h,ay,, &m.m nW9,.m.m&u.W~ ; n d.m %.. C b :: u j p?.~,&.~kpW.L ^V.-- 3.q,pmh!: 5. % r h.,.g. p.a h ,*.*<.,.D. l .L +- . r - .m . * .y;;.+. 9 . :T..5 m w+ y .w/.- . .,. .:+:.&'?CN..-- ~ . - - . n.. ~~ ~ r
- 9
- . ,..- ~ O ' -
- h. . - - -
>? WW^'i" W ' WD " - Technical Specification: Tables 3.3-6 C p.,. {, Justification: (5-(1) The generic standard technical specification table does not reflect the SNUPPS Plant design. The table has been revised to reflect actual site specific design -in regard to radiation monitoring instrumentation. Monitor instrument numbers were incorporated to clarify site specific-changes. (2) According to Specification 3.6.1.1 and 3.9.4, containment integrity is not required to be maintained during modes -5 & 6 with the exception of Core Alterations during mode 6. The proposed change deletes operability requirements for item 1.a in' modes where initiating signals from these monitors are not required to function or to be operable. (3) Operability and surveillance requirements for item 1.b, Containment Purge Exhaust Radioactivity-High, are delineated in Table 3.3-13 and 4.3-9. It was, therefore, deleted from Table 3.3-6. gn, (4) The proposed change in MINIMUM CHANNELS OPERABLE continues $;' to assure operabiltiy of the radiation monitoring J#i instrumentation and ensures appropriate initiating signals \3' - which will result in appropriate system actuation levels. This change also reduces redundant specification require-ments which must be tracked to assure operabiltiy. In addition, related actuation logic and relays associated with containment purge, fuel building isolation, and control room ventilation, are surveilled per Technical Specification 3.3.2. Specification 3.9.13 tests the actuation logic associated with high radiation in the spent fuel pool. Specification 3.7.6 also tests the logic associated with the automatic functions of the control room ventilation. (5) The function of the Containment Atmosphere Monitors are to detect high airborne radioactivity levels in Containment and initiate the Containment Purge Isolation System (CPIS), thereby controlling the release of radioactivity to the environs. A setpoint to initiate the automatic isolation function is, therefore, applicable only when purge pathways are open. The *.LARM/ TRIP SETPOINT requirement for item 1.a has been modified to reflect this. When a setpoint is applicable, it shall be determined such that the off-g73 site dose rate limits of Specification 3.11.2.1 are met. 'u 11,k{. %C) r -. -3 1 <U; Qi (6) In accordance with SNUPPS FSAR Section 7.3.4.1.1.a. Table 7.3-7 and Table 11.5-3, the ALARM / TRIP SETPOINT for item 2.a and 3.a are specified at 10 times MPC for Kr-85. The proposed setpoint is at a level that will detect accident conditions and initiate necessary engineered safety features and yet preclude spurious initiation of these engineered safety features due to operational airborne radioactive levels. Os ^41, fit ' s- + s, . N , ,. s . . - - r, .--s % e , o ..'- . . -...a . g-. ,, . . p , 2 g * , 7 . . . - = . .. ,y , ,
- s' - , . . .
,,.y,.,./....,- g ..<. '* 'i ^ ,lV 5 ;. ..,,,,.4. . .n , .s w ,, . .,... .. * , . ,, .s . . :n.v. ws 6. a ,4 m. , ., a. .;c .h . p . .< . ... .-4 , ..w v.;n. e '. l T ':.ee sm. \ s'ca.6,,se. ,..s ,I, u. - g .% .;. o #. " - ' ' ' , , . . h;** ,, j,.s ; ., ., s ' N - * , yQ. jc:[,f] *, * . *4- (qq* , ..J ;.,** * ,-<"f :, e * ' / * * ' '. s.![.i . - ,(" f / ', g p .'f,, \' * ; ",- ., - ,. ."' ' . ^ * . . n . ,~ g{ .> . , ; t .- i - . ,: . . s y. .. . , *1 E , ., , l,se, .g '. *- i. ~,
- m. ...s ,,..~ .},, ., ( / .p .. ,'. ,' y,[ , '. ' 5 J y,Y ,7j. .. ,,
, _ .em, u, g.,p w s % u,.a . ' . . . ;. .. - . - (-... ~ g*- ..3 ,.,i c., , . 6r ;. * .,.....e a y' . , . , s; e . , r . t. W . . .;J., ,,,, ;;- .J. + g,:.- ,'-f. 3...n..,; * . t -4,- . a s ~~ ~ , *s* %f4. ,s; -.
- L?.e t
s . y + 4 . ... -p., .. .4. 4;. > .': ? . 's.s.. .,ly .)7*p. ; .}, p .. .;.e ,- .. 4 ,. . ;' S - g * . ,, .4 - y - , og *.; ? j 'q...q. ..r! .. .m...l Q 'y.i v aq=. "#,y ag=r ,:6 ".* .4g .1 /.vf :y..53 _w *s . g i ,l,.,
- Js L.9 N.s - f* ,*
.- 1 gm 3 a ' ,/ ' j. NAiv()e,9.y:.h;t.(.;;W C,-' n 1w; ei :i '.?,e a'A :;? .K3. A9 4-M'i I c'. :: m pcL,;M,* r /
- s. e s M},. :>
,g s > ""'s O ' - ' - n;.. u-.' .. . #. g % e . t - w;g meew f . *.:( .'* V t: P , V o. m:e'r.<.r; fir71 ,.Y, g??,V.^z"K ^. .-. . . , ' , - . 5 ' .'
- , ~^., , g ,:
o.'..f, e =c..:y.e =..,- Q .. f.ff,y'.n . ,jf 7 .
- w. :,
C o'd e 's=* " ',".. ye .n.. c = , - ,e- q. .;. p- 3. . em w p . . s,",3,Q.J . . "' - N ':/ +.<a4 .<...'9. u- .D , E ce m :c.? c4 ^4 .' a ; - , .=,? _, ',:~-. ' ,=.v .. ; gc 7 .n;.f*x.;y=. .y .J,i:. h.t.'p/. r < . . - - % ** s;%,,._< . .;m' ' :u.g.; , y - {. .f ;9.. '. %a s,+= ,,5. . .? . < Q. f ,c. . A ~>~_ - - g i .* x: 8' -,. . . .w .Vl; , .+.a:m ,;: g y; ;;^y',;;.g. . .. , ,a <, e , , f m.s. n l9...M .. . a- . .e - ..u ' . 3: . < ac ;,1 .+- ; ,-*,?. ;;. + . ,. ,, uz < ;',j i,.:;,mM..m" : .:.'", a,..i Az g3:, <_. r-. .z y=.;...- .: pf yg , .,p:j. m,. .. ;. 7*fy;L . : . 7,. . r .~;N, ,p . , ^ *. . ~> .,J e o - u .. ,. ,. g q. c 4, * ....s , +. -.?' -i , 3 ., ,,, . . f. . , e y a . .;_5 t,.. 4 ,, ;; ( 'h ). ?. -#- , Y. " i h; f & .a z cm w '.~,,, ?? .'y ef..SN r. - ' ,u*L '~ . - ' , ,. ..+>a,,..;-.. .. cl. W m g ,$wm eC" g, w '., .y e 4,, '. 1
- 4. - .
A c.,;;,,',w.m$ 'e.,-. 3-c Q.. ,ygl, (bz- ~ - - ,y .. =3
- l. 7s . Cl2 eC U o P= ,- E 3: ~.E, ,E E E- E .c
- xN t o Zy ** ', _t . ' . -, ,p4, 7,.. . i , i p~ .s-s .4.. ,' ..,- u. y = ,3., ,; 3 . 'zo . g * ,- . .t-C .'.Y'*,,,#' -z , , w , .g;'1 Q'.'t . 3.-; . ,.'.g, ..;, y
- gW.*J 1.. .. ? $. ., C, ,.'2 f,L.;Jg s- #
.,g,,, o g:g , .,7 j , p ,t:..s.p.ia . a.< - paf . j; . . n.a . ,.4 3 c %- 3 e-o ==e = e-o :. eJ ' 't..."',
- N f.* -*,
*r e1. 3.</'=P. f.*g.=- m A e.f3s e, ', ,y* ~. W D. .r A W ^..,, .- . >= > , ~,% .r 7 .' ; :? -' ' ===. 'O % ~ < o .a <c ' y;y!". ' 's .',s. arc% n.4 ..i^@k, m ',?? ,.; :.w,y:I-?g . :%m.j,, .- - : W:, r ?.;:;o o . ~ * ~ - - . d - .. . .r...- - >- w w cc * .t,.- . ,je t
- 5.: -we ..
L s === 5.' f c.. 9 . ..w ~ r,e} E w . -g, 1lE ,-,b, ' .': 'N.f ,.: , s .f'Q .r;e'-p... -. u .;; Ty< ...kth.:. ~ _e: *;4 /s . ..c . .$bQhf.Eh' .- ~ a,a.*' Q.:','g . . - ,.f * .. . . k( o 3 ,g e . m. mz y 5 s yy c - . cgu 4 r :c :j'og .y s . ,(.s oc w'aoS:elq 3:2. X . .cce,,,. "ca .~m . .' >-r."y etCCie *+ ., ,'4. .c" e 9 ec 7 ,'.( & ba ,G . , p V o %,\ ? . ,;.f*',* . ; h& >q .hjR:, $.h* ,',eh [- l . , . b e** .(.j- ;* *- [e$p' . . . . , w a ze m e l-.. i.,J ,. , .a..,,.;,, 'h ; , ' 3. . ;Lb t. .;s e u .w4 :-
- y, s.
o 4-w f to w - -d' -,. c.c:3 ,g U:= c',x z se - s t ? a..'l'.'=r: .a f.- .c.ee . ~ '+.'.4.l.,Qd. . b.&%: .N;*qQ's *'.*+?.'. . .. a A. :.. . s .f. &,;6:.,. ~a. ,,, ..;.,' .:,y.f. ,. ** ' : . ' 6. O % Q, k ' e.?A.4., A.%,:,,' r.). m E ,.s f zQ * . -[. . Yi $== . .k ' ' . , ~ .;b > 3'[ N *b'O k .%[o ?. .c 7.m - => .- . =z ; sc w , .- a,:
- g.&. ' :w .f.. omy
&. . qf. '.;.~y'[.]. 5.;. y< ;,, ; , -. oc o m yv ,2 m y ,. .-. o s icr.m:.9.2c 4,m
- .;G. y c.-h.' ;n.q~
.m mN.g . , m;f.y ' M;;w,.y .. . c,: .st ~s. ,,.,.-;W m ,, e. s ,. ,.' ~ g" .e 1:'k+ .p :* 1,3 f c s -
- n. c' . ~ p . . - m .- . ...; .. s - vap: -
- 7.m <;: L y . h .' L. . .. m m S Y =. Y
- )bk m.m.ye s . . . > , .,. a -<c 1.
- m. : ' w;.-o..- om h k h. h..e5w ' .. om.
k a.,m .. . e2..= ~ up ,: '? h .. , :.f r d $f.. i:$$$ w,s,:n S1 m -e o .im. J ub D -s ' E CC 4 4- '~I. n . ea o 4 a10 . .- n - . u . .c Q M + w- - - .C - -- as= O M 1 7 a"ii").K sw [s3 .. >r - .o c. w e ; . ,. 32,.w,' 2 *aan= : -#,n.:. J':f ar= ** 4l% ;2.k . :> .-
- c. y . . s O . > aC."
m enMi n.. w. ~;S,o. .a <a r g;" e .u,c.%a. . ~ .c + , ,. - g - - ,I6 r. -C+s ,, d*:';-!,G'Nlv,d,%,M:;,e c.m..ny . .- c =os - - . +.' ' m' . .c.. g %q y.m p~.; h' w.~ g o r-O- M y @. < r .' ' ac .c+..'@e n.a - p;. .v'.s. n . / .. .a., m, %s. u, .P.ao u eetye..s : es. ae; =; m - e a<"w.,y.: . . ;,=,. 4,'. .. r m'2 Mp: M...-....o. W t E. 4Av%.. .,.M.pi':N, . e A % >> ar:go-$e2. ,- g e- +r %.m
- o. .:5. s.o cc, . a . e..eA c
-oc., .# o .n. c .q!c. .a c >.../. 3s e 3 ,v &,.n.-p.:W @m:+ a a;w.e
- %y .a- as,.&g...d.
, n.;,. @ . y. a%n.6. . i._W; m: , mO . o' d. au. >. .. cnen -rce 4:- ->..>r seam >., q *. .;w..,.; . -,s 4.~.r ., w .: . .:.:. J. d r. 4* -j< :,.;'.f. %. ,69> 9.y;..;v,f,h;h .. ,.g . . gc x e u. . c. .>,= cN iC: : o s.a . n ,e 2.0 e c,*c%n.. . 3 e-; f et t P w=,g as= C ,3 - . . . .M ar= .E ~ "'l'3 ,m. .a e m .x me gg nsum a <a *= f5 .u a c:::su: .; e a E uagl ..p- ra e M::m,M.4 ..,,,%-. q;.a Y,q 0.ha,yy> .'.g uW e o ao' j.mCm u.s g' ~t-).. ; ea :: e 4.- x,, .2. y. s ?: +L -
- e s%r r
G r? .:.: . ; e *-n C ~ MClw l n - ~'- m e d u to e 2 to as ' a ug . C. . .a- ^ 0 g Jeas- pp O pJt .p > rs ,J .+.*.:'. ,.Sy, .3 s E e e a , . . . 'o
- . O. ni U nad O
.. sii:3 ar== * - mO I. *** '
- p n* 3. :e"? f::.9 *...v.~, sv'
- j.q'.e , 4.y: - .;q.g.g ...s A, .r:tI g:.\.
- m. A,;,,f - . p r 4a .O p ap ,g: g 8
, =::lpf,s. =.e 10 De. ' .' ,% =ts- g ;:e<,- =3 c =c q *f FDM gn_,a m y u<g m z t ,\ U
- g. . 1M.) p ;. -c. <
J w= . Om . e evm >6mc m >n. oc i:C* . mU m r5 u I Lm . tw i aca$ b agn O ir == m JM e _ E 1. s,:.g = ,,,f4p,8#*[r(I'w.Ud';.k))4,,,Y]k,cG' M:.~.' t a oc A . ec m y r , kh n4n r ?,h 4~ p h. m~ ~u ;. y m y y kk n$$m, . fp.>$hh ..n,
- h. e$ . .. : Y.. Y a. xk wn - n.: n
~ 3,w . - - N, ffhyk .s,~. s LIk b.3 bNb~ m,,y m w;~ ' M.u # 'r 3 6 9 m ? p m 9 yyw, q # P M 'g- W e.,[ 4 4 AQ."idWMJ.MWW; % .efwppM e4 a w W.s..# Mf d ,4.W.p MM 4 m g A W eg s6 - * %ptmn . p..w.tw4 <.~ . ww%q@s.v d.4 M - h SO.$ r.w.kggr wze#p3 9p%W9;N#wg%.ipNt@.. '":rA MiMcm4My(, gagp+;.~eNo.w , % q.u % v e . y.,e.c .,. ..n w.c.,- ss.wn n.'mnm :r,:w.g::psk1+. y;wv +y.c .%w.: . - m ,w r.m:m.i. m. +nw@aya'.:.+>;g&mg:,a n$+N#1$4#hp(ThW&9&M,$hN A %,.t w~ mm w%,.yx.,;c2 .c.u%,..- Q.R,m.. . n, gy mw-*s.~ w, *.. N, . f . v.s: c , r r,a.- . .r , * .w. . ~ r a. . . ; .,wp : .A. s .g. 4g y c 1,%. %me:.:.u %. dl .*.;:.&. ; ,.l&rg*~.M.,C , , , V ' s,y ,5 w , , , .. . *. _g. , , 7:;.~ .;;. .%'g. ,7, [TL .y; , i a& <,&.nb Mg- ~t . . .;. s : / w:5. S.?*.!:':py ' ' v .. ...rw.,, " .t . .d. .y, 4 n ,- - ,4% *d- ...? 35m.n$QTM.4'.:$s, *a.o%.;n.w._ ;j:e!p:d.af;e%;i 'G ' ;e:-:' rf. 9.'.QT.\,.y;!
- N .. ,p%
C t, %y#$"+,,,f.g . . , ?- . . C r* .y :. s, s.M..f[.h.d.m_*y.I.AEQ.WQ%.~ . ;?i.M.%..Wv y;7Oi%. j,hl. ,K. ';;* &;/ .%:: .w. - %, '?.,.h:iu,.f.%-n'R, Q- >,.fikpr%m..k. u ':!.'.. .or ,%,.,.?[,d t h;. p:4 b $. %
- s .4 < O a .j r; %...,y;g,p,.,~.s.,r.M : . V f.:w'..?. :c: ./. -
.. C - S. . m, 3 =d *[g #.c.. .+s. .. .# - 3 . i . . . .w .,+:.-. . . ;m .. . q . 5 .e se . W . v Q LQ.s.;sx~.M. s,. . .. . w y -.,., c ,. ..s . , -- - .... .c, - .. m. %.a.t.*2 . , ** r s Q A, S. -SN.$ y.i w1.yht3 d 4 e w f'p.]p***. + Lj/, #.'4... 8. . - 4** - f7eg,, . . .N. . i: s . V: WWWWW, qc',,, L ern* Y4W+.ge 4, .e Mr= . ,3 " n.'
- N *)> v. . , zg g :^;* M :.Y. .r-te k e. ..Afla .
% )MQiWW, :1,qJ'.q; 8 1; % p,A,. Ig*A.ps ,.b g. .}g'se 4WT*g.;4.@@w;w, -SkMb . r * ;."*,4 ",, :' _"7- ' ' -Technical Specification: Tables 4.3-3 ~~ Justification: (1) The generic standard technical specification table does not reflect the SNUPPS Plant design. The table has been revised to reflect actual site specific design in regard to radiation monitoring instrumentation. Monitor instrument numbers were incorporated to clarify site specific changes. (2) According to ' specification 3.6.1.1, and 3.9.4, containment integrity is not required to be maintained during modes 5 and '6 with the exception of Core Alterations during mode 6. The pro-posed change deletes surveillance and operabiltiy require-ments for item 1.a in modes where initiating signals from these monitors are not required to function or to be operable. (3) Operability and surveillance requirements for item 1.b, Containment Purge Exhaust Radioactivity High are delineated in Table 3.3-13 and 4.3-9. It was, therefore, deleted from Table 3.3-6. g7, (4) The proposed change in MINIMUM CHANNELS OPERABLE in 'i, combination with the specified surveillance frequencies . ,] continues to assure operabiltiy of the radiation
- monitoring instrumentation and ensures appropriate initiating signals which.will result in appropriate system actuation levels. This change also reduces redundant specification requirements which must be tracked to assure operabiltiy. In addition, related actuation logic and relays associated with containment purge, fuel building isolation, and control room ventilation, are surveilled per Technical Specification 3.3.2.
Specification 3.9.13 tests the actuation logic associated with high radiation in the spent fuel pool. Specification 3.7.6 also tests the logic associated with the automatic functions of the control room ventilation. Ln h INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION .- 3f n eA I'd b. . . "g9 ' LIMITING CONDITION FOR OPERATION / \ 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels - shown in Table 3.3-12 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3. 11.1.1 are not exceeded. The Alarm / Trip Setpoints of these channels shall beM etermined 2-d adjr *-d in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL - (00CM). APPLICABILITY: Atalltimes[ . ~ ' Obd th CM(M sc> ACTION: .M.g d.y h. '. Ocd hiS ggOdLEpkoMi
- a. With a radioactive liquid effluent montiorin instrumentation channel Alarm / Trip Setpoint less nservative than riquired by the above
. specification, immediate1 uspendthereleapeofradioactiveliquid effluents monitored by the affected channel, gor declare the channel s inoperable. . ~
- b. With less than the minimum number of radioactive liquid affluent '
monitoring instrumentation channels OPERABLE, take the ACTION shown , p in Table 3.3-12. Restore the inoperable instrumentation to OPERABLE .y status within the time specified in the ACTION, or explain in the 5 next semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7, why this inoperability was not corrected within the time specified. ~ 2 ,. l . c. The provisions of Specifications 3.0.3 and 3.0.4.are not applicable. 9 . .w - - , .,.. -5y...,-'" ., ;M . ,4* . 5,, l1 .. , [- 4 . .. f ,. . ; - : ,. SURVEILLANCE REQUIREMENTS , ~ . . , w - .W ' 4.3.3.10 'Each radioactive liquild effluent moriitoiing instrumentation channe*l..f. ,. .'shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE * /.~ . . CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at; . ;^ .~ 1' s..,*' # ' ,e the frequencies shown in Table 4.3-8.,. , f* , .- 'q. w *' ,: .fi... .s, ' , ,, ; - . f , c,w' n . . s - Tr.i v N ',:~ V. ~< & n,*i v - y . ., r- &.t e r-v .'% % . . ',m. '. ,. C L- ;*.r
- v. .
' .5 c.'3} ':- ^ 3.' W- .l"' '
- l r *
.- 4 . t d.'* 9.x. r. N.g Y.}[tf *}/>d;'M*g.',U h ' . h 7;., ! .7 .'N,$- hl,_Afd M #h. k.4, M'? Id[ , glf ' d .4 'O Df/* N- ". - . . yh?4. ,; *. . ...WM.':.*'I et..h-M//-ra;,;. Q - ~ . ; * : ,'M Q, . 3[.;.f.(:e%le[:Miyq . 't . . . . .; * ^t ;h a .A I i LM A m,b - D... Y. M "d ;:p, .* *g *_ .c4 % .4X6 : ? ye F y$ 91g%MWp:? %gi.;Q:p V @AP @W s.h g. y J.p. W g{p% M @-k.Qif$@a ' te@M .. . . e . . . , ev. t,;. , ?
- r.*
4%.~ f ='y.fsgy &; V i w s'.: 7, . A ?R: g .:. . U;D.v:':*;1:~Y' W W..a .b, ,T. ; ;d..arr.t z.,- vy p . .;,',*.: . y.'Q.f:L.V : ,'. G.pt. c '. . s-.', iw,.- [: ,:. Q + in l:~r <O 3 ..,w'w, W.i;.s.A; .C+ . ./ a..+%...: V
- f. % .e i *: .1 .. n.?,e .,, Ap ;noiMy .khrR. . -<:' .', ,.' .' nr.w.?lNb
- -9' :h::'; z. .: r.;.,.;.
r a 5.5M ..:*v. G.l.n* 1 ...>1: Q. c .; + .s . . e ; s. i,sa)g;- * ~ . . ?;a ~r ',.?9 %l.yr:l7 .4 ; ' .* 5 - ' , , , y. " p .. . . . ' , .z v.4 ,. y~o. , .r, * . pF y .. is. ; . w .%..v.:.M.y. r.p.'*. r . v.', . .:( t' ):- .... . t . ..- e./..- . L x ,,,t. q .s. .c. . . . .. c t .. , ..2 f. W.. s y .< t .! r r , w - ..- 9._ i , .t c . ,..' e . m ,; a%"- . . g:,f s . . ., .. c, - r.z..cN. 3/4 3 .. -'
- CALLAWAY - UNIT 1 .,.
- 7. p' n . ... . . . . x. . , . w . ; a ,1 . u - .' . w' * * #',:< .
,f ? k ,_'y,',, ,'.(.. ,.e j}..? (%. 4 , y ,;3 J 4,..' , , i ,. ;. . , , 0, , ( . g: * * . . d. ; p, . .\ . ,* .gg. - * * * * * - ,-J.' j- 1c * . , s y ,. g * - . [ .I . %- .*' 8 ** . . g . a - SPECIFICATION 3.3.3.10 JUSTIFICATION: (1) The specification has been modified to clarify the requirement for_ adjustment of setpoints. (2) Operational considerations preclude instantaneously . accomplishing the required action. .The proposed wording (initiate action to) clarifies the intended action and ensures that steps to rectify the condition are immediately started and corrective action is completed as soon as possible. (3) The proposed wording in regard to changing -the setpoint is justified since it is an action that can reasonably be accomplished and if implemented would result in a condition that is in compliance with the specification. s-r i..' 9 _r_,,.y,-.,___.-- , ,,, ,, ,,,, _ ___ ..., ._- ,,,. n- e 9. i . ..',.. r
- s. . .
-s . g .. <. . .j -. , _ .' , ,- "
- v. u. .
, . . 3.., .
- x. v. ., . .. . .-a,v e. . :;- ,0
~..~e - ' .- . . r,
- ; . >:m + > .... a,w Y ..c,..,.l, ' . ; 1e r . . : ;. ~
~ V .:. , a . .v. r.. u.. ,- ; <= -g m .
- c. . .
. - s y t. . . .q., , , 3.(w, :. .n;;.r. .y,. E. ,. +. , r _ ..,,e.. a c ; 4 ... - ,. j,. . . . , , . + . , . , < . . cg r.. a. w , n :.Q n m m. .. ... . . cy ,, p ,. ,. . .. - g --., w e. m y .~<.. . : u . me m p. m ' ;p .3+-?mm , m . ,- .i.s,.na'iM-?; .w.V c '-. + . .i vi .' .%
- 4. >.y:.".;.. ' *:L-.m . ..; - / a:. :; 1. ?.
v ' 4.* d cR' Q 4 ' *y .* u.< o .a .., . . D. . < u ,; '.% -d ;-li.'. why. ;.:; p. ., * = ,2. ; ,< . : .' - e m;d. -. . . u ., . j u,s;. w .s '.g T., p.C'v., . .. ., , . . m;; Mye 4. .; a ,. . % r .p o,, s . s c - Y . %p.n.{ f,:r ,.s MQ: r -W.w.p;^;;u-Qe;'r,&.g. T.c b.,.,c. w m. ;,Qn: ;; ...,..,.-:.- . ,. ,; ., y - d. a ., . .na.. 9.. d .~ ~ .p ,a. r.: , ..m, 4e 7 ; .c w .1q, - , ., ..s. f. , . ?.r . ...g.; , .. . . .,- , . . .. . . ,.,v; ;. . W, .... .. . _ w.w; .; i,. .c .,.. 4.2 t.w g.. y2 , w ?:.m .., c< ,.,s. ,c.a. , .. ;,a...g. 9. e .1,.%. m. .n u.sc c4,3. ,u-psg.a.p .f. -. . . z.a,; .,c %. _ . , . . . , ~ ,4 ,.- H,,, .3,v. .,4 . f.. . .,.z, . / . . . ,,.,,,.3, .p,:;u. .. ~ . .,5. ;,.;o., .c., w.x ,, . .g, , e,. L -
- 7. , .x %,,, . , ,
s pee . ,j .; y. r ;. m m.<~ . e. .. s. .. , , o. .m;7.g. ,,,e.s.. ' , j-}7l a:,:2,0; s & &. .<h..f.? .'.,q,~ &,Y,,&h*N,a.g.7 . ,$,.9 :pp.
- j. l-l -yw,
,?* ., O ...:.;e * $W, ,hV. '$ j&e. ,;I w r: a .s.u.:. .~x%;%&," .nlr.NW
- s. . ;
> u . .:..~ . s t.: . p ; - . . m: . nm; R::1:.:,tn..:...:t; %.z.y#.;,w + . - . , . . ~ . .- .c.m l ayw.by;g.m:.:.1 e :: ...- b$
- I ;f. .
h f ll
- 5
,: n . ,. . . Q . x' . , e . + . .ee .. . w n.*. .:: 4.<. n., y ;.:'e.e n.. . e< ;y ,. e i a e4 m .: ., - ;m. .t >- z w f yp q:Al . ,w.p.g, - MM..p .,.u ,.,,ev,.s. . m. . < ~-g i, .9:...gy,.. nm. #j., . .j .@ y .>Su...M -;x A.1 ?l..MU ;l..r -c -.
- xu -n. .,
, e;:2.v.ar. .r ,. .-s 7. ::q..i J . .,yif.1 a . . m , .,..,t.., ~ ,.: .. . . .- <. g.g... . . ,c. - ac, a. 4r ,. p,:.,. ~s.a.u, m .. .v> .r 6 . . y .' ~a- , m y . . :.%. ,.+3,-. .
- n. .p . , ,
.;-e:. . c . ,.y. .e: .. . , : , : - w, ,. v. . s + c.., . c .v. . e x.m;p.
- s. .- . s , . n. . - .. ;. .. .3, .t,. .. .p+.,7.g. . ;g:. y.
w%,w.;.o. o .'b. . ?y . . g ' ' . @ gqfg,, ,4 m.:m. ,,.c;@.gi n, v. ,c c w. , -:... ,...,%~ f. .._ j;- .s . ,q.'y,p.5 ' .
- 3. ,
. . . p . ,c. . 3e ,,#g.g_ z . m. . e.x .,. , *. 3 c- yp . , p..'.@.. .P.fl%pc .q t * .i;/,..(,. , %. (Qg.V. 9 d.y.o. '.:. !. .:'. w . ,;., b . g s n ;.. 4, ;, , ,,;- .,a ... ,.g..<.
- , A. s. , < . +
- e.v ...n:.,,. ;i).m l.@, .e. ,.f .;b; 9 s .. *g. c,.g 7 y - . . .y o..m. ' p w. . ~;- .a, ... ... p e g ~, . p y ;.~. + , p -(y,;.Q.gpfr..yq:, g..g;;,:.i.g.:. . + ' t. . <: . v.s y ...,. gia..m. 5 n,.. n. ;;. y , p . n . .. ; n . ..n .> . ' ~ y .;,., m. r , .. . . , .7'.+ ' f;;.7.:. , e 'T . . , . ; ., ,- J j,@:._ph.if/f. ;e s.s.7.wwe..;,+;-r .y;M ~ c.p.~...m c, . , , wi..m.y m, .w. .. , , M. . y.;:,:p%ugk.g@pfg,@bQ,Qg
- . . . m. . ;. . -t a.. u p- .34. . .-w. ., . *&_ < ..s,, -
+- .,. r :..:. :. . p, . . .nr .g, , w.n ..s.,s ~',p A ...-s.>J,:q= .m O. - ; m..z. ..e.. .; ., :.,:;.%a, L,w,,w< y.p.. . e.. .v . . . + . t. - s:. . a .- ' . y.,.9.,a .:, , w .,,a ,z w . u a, q .. . g , , W r ;.,e .- . , . c& , d. s, y.v 7 ; - [:..ry -' w m. ,-; ,;g .. m'. .:s y. .- ,.* .. r * . , ..s . s f',b. :, %. . '" . k , iE [ ,h'. - ~ 5DC'f..', ' . . . h' . [jj i r ? . n .:a . w. u,, -- c- n wy+.: .* ,u j
- f. .y u b .*,
..w.< . .~;.. .;.'.: , 3.v. .w.. s. W. . . . -'wu. . '- 7 ., e-w .grm u. 'K,. :.:. . 2 1 .
- .y e c . . E. ',- % .4 E .. .
.. En - . . m +,y.x, W M-i w 5w.y,U,;W n a l$.'" ' : P e ..~5,,,$. 9 ,* . . - .% .4 .:. . &..n a. .ny:;. m. .. . ;,.,..- e S&L.n : \w55 r.":.a Q w - . , . .c. Y,.+1 . u az u - Q.a, w.- $.c4 V.c.*i' 8,&..%,;n,. 3>~;r.y5-w;3 u :.,: ua.pu 4 m +*M h, t9:,,, ;%f'; . , . % a. og .. e.n.:. u :,M*O1,' / y . .n,, - 3Rr.'.:-l.'S;'$ ,: r'. :-W .Te .%;.E ?d' .?.' kk,-$"&..p%* J* . 5.YlC 2 "'.s. W h h f n h **.,.h. M .? ta g~ M *M,. ., u/..'.+ n.r7 n . w, dg .'k, .'s,e*~ Ej'.y;. -t i ~ sl 3 a ci u m: o,s . . . - es.&s e
- s. y. ,.v a-..
'.w$l u -( /E u ev-s.5 u k..s. 3 W.E $W}"k.4 :t
- 5. .*;- .e"?;.
- 2. 4-9 ;,. : a
.4; w s , Q$g y <.* ve 0,y.bM %**.P.q.".lM.:*E,7 / w 3 , ca m. e - g m ; o . e- , .j,c n . c we ;;;a
- t. m'O,s.Im,.; < ; e A.,a;;L
- ,*m o..Mm m .
d.;.e . .*A*#&%.+@. ,2 . . m o e ,;.'.h- * ;- g M ..*. % o., ,54
- g. .. . , .
clr.g y ,; e.. wp ;e
- - e& ,-:. .
Me&..: v* t-v ,ueo in ' .so c e 'e m.S L:v.- w ~w @ N: Cze m. i.p. a. p,:>,lp~;~.J - m , ' t.'. . ,: . o .'. ." ,.':zw 4.W u.( "S.: '.'.4/3 +y>c .,-Qy t.,ym.r..: .y
- 7. .it .1.
n m-r .o m .t. w(.:m... . N.c . > e a.e ; .v
- i. C Y e ' :: ul .c-c.ndW<> ?? w4 t' :: f:(' +,, M.4 k.pg+hN*iU tAEqu b;' 'N.0:u.: :.. ~-
. $,g ;s;.q%.jf . - 2*v.p:r: es c.ON"' k" . mn - m. 8*o" M. a '.DMN; Eq e .a.$}uN .3 ~ e u- ? P.l.; W1 .m eM b .;3?e kYd:t N.,Y. 79 g'bh,J.s./:u '9INb p N., . . .a . : .v-n - : 'a a w. s . - 1;- . p:- j ' E e. '. # 9 I Y e. $.. . /.:~b
- bq M '"; $:a m e YlM.v;y q*
- %.9.t4*c.,
- s. c :; m M...'.. s'%h - a a .,. a
.w.e . 3 u. 8, %; a:%c s. w. a ,..:- - ., .; ,.,,ia ,s.:: Jw .,. .Y. Mbk. .g Nki%.g.,:7": $, . ' ,[,
- ~.~, ese a e
- a . -a *g " .,4 g,.. wzw
,,& ,[ ;,. ( t . *;*.S - t.sg c./, ?,7;%y 'pn,. ,, c"., f 'a, e' c
- n. / .,
. ,;. ..; J'.e.. {t'&sw # -f. :. 2 *1; ..ce.e*.'eu.;.'s.,.l..-,."--^' .- .* -.s 'e :*, *O <f. v c fl'..a H. s & asp , ;i. .' . g o . ,s* a; .? *; Q .w%,%* r.a p. T,%s ' ~ - - , . ' ~;g,.. $ g 1- ,:s ,)* 5 3Ol'F.,,,l% u.; ' ' m;a.W%d ?:> l ' ##g n $'M3 % de h dN?w T' D..K,M ~ Q M M C r.r-[f4ff W 7~ ~ .e ' ,Y f Dg C..\"?.* % ;s g % . vt n42=m Mshwrex e.f+$&'#f7.;e . Gm Q:pQh %;.'In v+g w,-v c w> m. ,x s.e. s.s& h:8 Qs ~n 3.u.w.n.. ygt 7 o .g e"..Jr - . ,y g n +.y . y ,y ,q -; mm y# M> ; .iy,u. d,4 * - - u ~.E .w r - e3 9 '- - 3- .og3 .5-ug" o eWg e . m m,:2 nr ow. e +. ~4: e * .nwe 'M,s'.#ec, V <- y,l'.c y' arm?r{;*. .L;;i u e,an sk:ey'-(%.'f >,, .su 64.~ m . J ' n.y a s JdsA/V.'4 WK M *Lf . M .' %,d 4 N 3 , . , u .a.W.h r. ;n.*c . L~. 2 ,..:. ~. . o n.;n y a sav Y s c+. t * % f"+ r" '. O h. .. ." i ' k:.% f *$ . - [ 4 h)y, L. Y %s ~ .'* n Q MW .w . QW. 4 - besps f,95 %Q.Y/M. 9 g 3'Q bMit$= 3 A .0.+9 A 4%:.% A 4 9%'O.M - w. $i* %.f gh,.u- -. 4K.(p se W.Q- Nny. N F'r @m mwy.r,,3 s c. . n. 1 Gr?A%p*m.p .p y. , % MM.:ss hmm+w.. m en .-e + . aMCw.m.Sqq,hp .n NAJw'0 *u.W-m[pAM,$M .ww"HMM&* %:% M*- ' My. r M.Ns w% ~ $ gWpj ! 7 ?,: ?.; ( ;;' Q'h-Q &p W ;bc-?2.' gk%QV 2,.Af?'.2d.pJ',. .Qg&.hb* hf h'QkW d V Q t d4.[F ' PW ,_ O C h .{f* 4k.QeW-3.Q*4'f?#{'~].4 ; .,o TQ+*}j.Wyh. ~ ' f
- ?
wwy ,Y.h.Q'T;.*Q'T.,'M . a e, .y '. ..a . . . u
- ~ - ~
w$$[m$.:ena$w IY *s W.5' ??,g..n.h?p)pe&;.W.Q-%*h.$Q n . bN h y3/4"3-65 v y w y$ m . 4 NkN. nYk . h5h Mt . &v. .t. .cg w .u. .q CAU.AWAY. - UNIT 1ppQ
- ,<,.5.g.%.p4~J.h.
W@;;;f .ew w - ed...d.~s . m we u.-s,s...y. 2. .;w.ca..;;,m m @& w $ ,,e. : .1 m i. g,h.w m W $...W,M:N&w!.9.h
- .w,es,m w W i'. %.% S yM: m
,%r,i:p.m..e y n , e ,- ., .w.q - v J Wr4
- 4. gW M,.t
,-.W-M.V.. %,r.,y.*M.yr4 y*, u3 .. .w), g 4'f.Q pt .254',* .y # .w/W. c- ..ROr?%;7..: f *,.Wc,c.' $ ?W M '. ,c.a
- e. .c ag.
.c
- w. ,f, N.yGT .msg~ +- m. *C.M
.@, yW<.m..M.p ' ** ?it m(.,. ::::p, .e a a .h . .f;.M@,.a m.A,.t.-&.. . .Jyp,,w.ga ,:~. , /~ b % d , 9-@)x P Ly*p y ..u. re-
- p, Qpr :y. :.w 3,
MyM,9';' ..w..M.a- p;;$1, a$.v.M. g: . Y y e ..:- z. g .n:~r.;R
- JpW.9Mr9e.*W*d.i i*
96, der:sw.:~~ t A -Ym-e ,t.S */ lN, !Mf@w,h a . s yf~n:%(>n3YJT%. QOg.3%, J &.'r.w, ia - .~ # v1.%. '-~ -r-j r e- a-M r - .- ew.e .,.4 . - ,~-.-- -~w- -- ' -- u -- *NN%' : D t < . .... = 't ;< .~ ~. . .. . . .v. .~ ~ 4-a a i ' , f. . u - Table 3.3-12 (Continued) @:- c. .e C . e .. s.. - m. .. m. .. . + n. , ACTION' STATEMENTS t,c 3. .. 4 . . . If. 1 p;;. w j g. 3.g ' S i-< C .J ' = n .a . ,, c. . . m , . ,:. ..., a. nw . . .. . ..... .4 ...-~ .:.,/ ~..s m. p .m. w ... ;...w ..e... ACTION 31 '- With the ' number of channels OPERABLE less than required by the ' ' -16 ',' - = 1 - . ' Minimum Channels OPERABLE requirement, effluent releases via 1this} ,J '5. T i , ... ..n . y- , ' ., initiating a rele,asan a .:...u Wh.w.m:!w;% t: A W . C:m- O +:- N n" uN w
- q. 9 '. s . ). .:. : .v: a: :x +:n-m . x.wM.M p.wgt;if4.qm:, w( <.+Q , 1'
.h : = ~, " ~ W.. ,. a. At least two independent samples.are. analyze
- e. w n . ..
- n. - 1."W.4 J# E ' ' ' .r %. . sy:.,.,. 'm. with Specification 4.11.1.1.r. and$ll3.1. 4 @d:in accordan ',.^y:c n.nw %.vyw,g.auMtq& $fMy+k&Y:R& 'l. pf 2 g " b. At least' two technically: qualified members of the facility -Q.' e -J' - - staff independently. verify. th.e. release rate calculations and ;(dacyalp?-4 '.' e4, % ut t c .: gp Msg , discharge ;.. o , . line ; ;p +valving ,y. c 0 v . 4 e?.G@ym m'm;q: c cm c. c~'W3M % .Dr.:lg. . . . e 4.=, c. ] ,f , 'c Otherwise, suspend release of radioactive' effluents' via thisM .:a...,1 e
- w. > . .. . pathway.- .i . 2 o . ~ l 'HA p .O "
.. s. x. .; , . . ~ :, y.,. . ' ;c.x.. m.r.:n. .M,.;p:pn., em.,n. .q4.. n: c...;,. w:s. . ,. ;. p:W 2Y:: - . 2,l
- . ACTION 32- With the number of channels OPERABLE Less than required by the'. '
i 2./.:. - Minimum Channels OPERABLE requirement, effluent releases via this' ~
- m
, pathway may continue provided grab samples.are analyzed for. .'-- 7 .r. . . .m, qg e .r:di ::t!"ity for up to 30 days at a lower limit of detection-e4. '- ' - , e :- tg Ic ? -t: r;.-w-g wg p (;g p p g g .g -- ;.:y,.: : >. .v.: < - n . 1.~ . .. . c . .'.. . ,: . .. . , . .g.a. .s m . p . .: .a s u . m. . - , N. <.9 . 7'y At least once per 12 hours when the specific ,activity.of . ~p-- a. g - ' the'... Rgyp . M.v.3',WQ.. g,j:@W, .. secondary coolant'is greater than.0.01 microcurie / gram DOSE % . . . A., '.. % e "w ;xr .l n. . g w EQUIVALENT . y -. ry I-131,' ,G- .- . ; or.~ c W',~.%,3 . s5$. $.f?6'g% n ~. .. a %y' - yl:'.3, ';:y :M %@u . - i M - = .. : . : . M ..? C - ' =b.'". At least once per 74 hours when the specific activity of the . j % ' j .9 % .' A ;.g## .(_. , secondary coolant. is less.than or equal to 0.01 microcurie / gram ? -- a 1 %.Q:$f-:6 .,NgA&. R M;w, '<*N.M s , DOSE' N EQUIVALENT& m es!N W I-131L @ W p-W .MQ;p&a&mggf..regg% WWT& 3% - ' ~ & ACTION 33 - With the number of channels OPERABLE 2Less than required by the: WL f
- 4
%j $w x.@E .%g ;gMinimum Channels OPERABLE?requiremenkefflUent' releases'via thin tf . ' .3 t 1 ::ta V.. d [. bN'YNf9MNb: h a.? W A. 6 dphp.#fe :.-:4pathway ' ^ ^ ~ " - " " ^ " " ""'" may continue "T !! 2 for 00""Nd up'to!"d 302^2 day O ~siroviund.?that,h:'25 @%jf.gofb?.5.:T --d'rrt1"**"
- i:f. -.4 s ; .p
-t 4 'e- ' 4 4 t e* tteth- af ne --- t"- . la-W .% , - . < 'E E N & W W t%.:if655 mber.ofW Mfh.dw%.x.N.vACTION '34 - With the nu%.6 E W M h h ak W R Ec$d d 52 # - channels OPERABLE ~1ess;than required by the%1 ::; " $#A Q 4' . releases via this C $. a N[@-YNk5Nd.4d@$f.MinimumChannelsOPERABLE. pathway may continue for up to 30 days'provided the flow rate'.isF .s estimated at least once per 4 hoursiduring actual. releases. ; Pump. n r requirement',1 S. ' qGQ;@.F.gpe.".w, p ~ -i WgM .f.1 performance curves generated,in. place.may:bef.used to estimategM )h '.,;%w ;, w.*s, v , b .j u@e&f{%)ny,w-t . n 9$%ppw f A m y* :%' g' m ,n. -- ~ r p, wr W ., f g , %es.wh,h ,3 f- .Wqp~;gg.. fra D v. m.j;i -y .s. .; d hi 6 .W W hm Yhp:.y- o qe ' g, g@Y W W. - N - bhW' ' % CQ M ?: n M l., . M u %6 . k Y r ? W. OA h b db W G b h hW k.W kruohich W. w\m ~ ?{.awigww:MW%CMWMMtkM*W&hWW; MM aW EAS.%. . 3 3 '.lm& h %.p.. 4pr w,LLAWAY.M;sp? W CA ; UNIT'.14 .. - :,. y ~ . ,m. . h Co. ewS k &. . o W t1 3/4 w.:Mn. m :" c{. m .:.y D> 3-66d 4 . S W . $ -.q%mJ. .y A %m {m ts+' % p.% p - m wr p. c. . O. v.%:.m #n8 a y .h. qh $ $ h kh pm$ w$hh .y$? g (Y?h.m&_ A n, "l I 3 A;1p%. n.y.1 pw.oQ_&m%,-$+,k5'k !YQ W d .q.p.@w.w.ww_. pp- pd.. e .vem -- he+lTW4h~ m m.-.m.~ --- me ..yh:... ~ we$p ~-w.m.#p.un..w.m;@a;,'. . w . #. . $.wcF%ws : W- M m .W m. & y tf5 =. % J ,-~, t. j: , Table 3.3-12 Justification: (1) System designators have been added to the monitor identification numbers to ensure each monitor identifier is unique and consistent with the plant equipment identification scheme. (2) Action 33 as modified is appropriate since the Secondary Liquid Waste System Monitor is for batch type releases vice a continuous release. (3) Action 32: The inserted wording was added to clarify radioactive analysis requirements for grab samples collecten when the effluent monitors are inoperable. As previously worded, the action statement was vague in regard to which analyses are required. The specified analyses and LLD reference provides consistency with the r7 ; requirements of Table 4.11-1, Radioactive Liquid Wasce ,, Sampling and Analysis Program. bj DI , u ., q; . I Q _ ~:- , n TABLE 4.3-8 . 2-
- l. U
% RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUNENTATION SURVEILLANCE RE $ ANALOG , i g. CHANNEL SOURCE CHANNEL q INSTRUMENT ' CHECK CHECK CHANNEL CAtlBRATION OPERAT10NAL TEST
- 1. Radioactivity Monitors Providing Alare and Automatic Termination of Release MS-
- a. Liquid Radwaste Discharge Monitor QtE-18) D P R(2) Q(1)
- b. ' Steam Generator Blowdown Discharge Monitor \ D' M R(2) Q(1) m c..
S) (RE-52 LE-TurbineBuildingDrainMonitorQE-59) D M s R(2) Q(1) [ d. Secondary Liquid Waste System D 4 Monitor (,RE-45) - ff R(2) Q(1) w . fp -
- 2. Flow Rate Measurement Devices
~
- a. Liquid Radwaste Discharge Line D(3) N. A.- R Q
- b. Steam Generator 810wdown Discharge line D(3) N.A. R Q
- c. Secondary Liquid Waste System Discharge D(3) N.A. R Line - Q
- d. Cooling Tower Blowdown Line D(3) N.A. R Q
h I = TABLE 4.3-8 (Continued) (~ \ TABLE NOTATIONS (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and4 control room alarm annunciation occur g if M any of the following conditions exists: pgopriod3L. a. Instrument indicates measured levels above the Alarm / Trip Setpoing or
- b. Circuit fail , r b A
- c. Instrument indicates a downscale failure %& 0%)
g or
- d. Instrument controls not set in operate mode (alarm only).
initial CHANNEL CALIBRATION shall be performed using one or m .the te dards certified by the National Bure ndards [ 7 (HBS) or using stan a ve been ob om suppliers that part,icipate in measurement assur s with NBS. These standards s N11 permit calibrat system over its inte of energy and measuremen . or subsequent CHANNEL CALIBRATION, sources < ated to the initial calibration shall be used. (3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK sh days on which continuous, per.all iodic, be madereleases or batch at least are once per 24 hours on made. (e ( - g C.BMNE L 0.AtISEATtord-W bt pec{ormasS. ely
- 4. om. or More 366 ads 4ractcW b N 4dima.Q.
brtAu- 04 SW6xegor ~
- b. 5%m6arAs oMrdmB. Grundqpkrs hh pctk;ph M msu.c(M mwevea_ oc.E wg wh ha AcN+\aQ Gurmx cd- 9Mrg , gt t..
Wu-b edCA<& b gre esw2 cch% WD- % 00 s cv) ou . - 9
- 4
.$ \ P CALLAWAY - UNIT 1 3/4 3-68 ~ ~ ~ _~ \ . _ . _ . _ . * ~
- ' m _ . _
F.\ .', . Table 4.3-8 Justification: (1) The source check frequency for the Secondary Liquid Waste System Monitor has been changed to a " prior to release" frequency notation since the Secondary Liquid Waste System is a batch release system vice continuous release. (2) The changes to' notation (1) were made to reflect the designed capabilities and characteristics of the SNUPPS effluent monitoring system. Although the monitors will provide an alarm indication when each of the 4 specified conditions exist, alarm and isolation vill occur only when the Alarm / Trip setpoint is exceeded. (3) In reference to Table notation (2), these monitors are calibrated by the manufacturer using NBS traceable standards for principal radionuclide energies and cencentrations. (Calibration of these monitors is addressed in FSAR Section 11.5.2.1.5.) In view of this fact, the alternate wording is proposed to clarify $[.) CHANNEL CLAIBRATION reference standard requirements and is directed towards c,alibrations to be performed concurrent {t.'] with and subsequent to initial plant startup. The proposed wording is consistent with Reg. Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment and the intent of the original footnote. l ~ .y 4 4 n aI)uMcdde NLVD S4 INSTRUMENTATION 6 j RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION e 3'"b 3
- 0 'd 3.3.3.11 The radioactive gaseous affluent moni ; Fing instrumentation channels shown in Table 3.3-13 shall be OPERA 8LE with tho Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.2.. re not exceeded. The Alarm / Trip Setpoints of these channels shall begdetermined 2nd dj=ted in accordance with the methodology and parameters in the 00CM.
APPLICABILITY: As shown in Table 3.3-13. OdMd P % ACTION: h'Q g d'y kO thd ikiS NLehb% N fIdGIi %
- a. With a radioactive gaseous eff1 nt montioring instr mentation channel Alarm / Trip Setpoint less conservative than r equired by the above specification, immediatelygsuspend the release of radioactive gaseous effluents monitored by the affected channel,Agor declare the <
channel inoperable.
- b. Witn less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next semiannual Radioactive Effluent Release Report, pursuant to
? Specification 6.9.1.7, why this inoperability was not corrected within the time specified.
- c. The provisions of Specifications 3.0.3 anti 3.0.4 are not applicable.
i SURVEILLANCE REQUIREMENTS 4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-9.
I e
C CALLAWAY - UNIT 1 3/4 3-69
SPECIFICATION 3.3.3.11 JUSTIFICATION:
(1) The specification has been modified to clarify the requirement for adjustment of setpoints.
(2) Operational censiderations preclude instantaneously accomplishing the required action. The proposed wording (initiate action to) clarifies the intended action and ensures that steps to rectify the condition are immediately started and corrective action is completed as soon as possible.
(3) The proposed wording in regard to changing the setpoint is justified since it is an action that can reasonably be accomplished and if implemented would result in a condition that is in compliance with the specification.
9
l 5!'
/
~
i i , .
i ~i ~ c, TABLE 3.3-13 Il
?
g '
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
't: J
1
- 39
- i. 4 H
9 5 e , *
* # \ e 6 1 *'Y*- ,%
?> . n.: c. c.
- e. .
.s
. ; ,r. .. - - < < .
x.. ,
,I t
a
# ' $5 f y
'e, ,
, e 9
e I
TABLE 3.3-13 (Continued)
TABLE NOTATIONS At all times.
"* During WASTE GAS HOLD UP SYSTEM operation.
N tildiN Mddu @f AC ON A E ENS ACTION 38 - With the number of channels CPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:
- a. At least two independent samples of the tank's contents are analyzed, and
- b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve ifneup.
Otherwise, suspend release of radioactive affluents via this pathway.
ACTION 39 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided ,the flow rate is D,%.. estimated at least once per 4 hours.
' Q;. ,
ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are i taken at least once per 12 hours and these samples are analyzed
~ for radioactivity within 24 hours.'
ACTION 41 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive affluents via this pathway.
ACTION 42 - With the ovktth t n=.tr : Opp:nn:wo&WCknne.Y.::ir&gerkkV: -
. . . . 1: 0"E"f"LE ::: : 2:n r:;;ir:d by the-
"Sirr Ch:nn:1: ^"E.""."'! r:;;inznt, operation of this system may continue provided grab samples are taken and analyzed at least I
^
every 24 hours. With both channels inoperable, operation may continue provided grab samples are taken and analyzed every 4 hours during degassing operations and.at least every 24 hours during other operations.. c.
. . p;.
7 ,
<g . _ .
ACTION 43 - With the number of channels OPERABLE less than required by the -
Minimum Channels'0PERABLE requirement, effluent releases via the
]gg4 effected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as l .
required in Table 4.11-2.-
l a ACTION 44 - With the number of channels OPERABLE one less than required by the l ,kW Minimum Channels OPERABLE requirement, suspend oxygen supply to l _the recombiner.
l CALLAWAY - UNIT 1 3/4 3-72 l -
...g..,v....-......._.g_._...
n-
- g, zh[g INSERT A ACTION 45 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, addition of waste gas to the Waste Gas Holdup System may continue provided grab samples are collected from the on-service gas decay tank and analyzed:
- a. At least once per 4 hours during primary coolant system degassing cperations.
- b. At least once per 24 hours during other operations.
m..
5:s '
55 9 .
t E
l a
^ lll l'
l I
+ - . . . _ .-- . . - . -. . . - . .
1
- #3
' fld TABLE-3.3-13 wn 9*m JUSTIFICATION:
(' 1) System designators have been added to the monitor r identification. numbers to ensure each monitor ;
- identifier is unique and consistent with the plant equipment identification scheme.
(2) Containment integrity.is not required to be maintained during modes 5 and 6 with'the exception of Core Alterations during mode 6. The proposed change' deletes surveillance
- and operability requirements for the Containment Purge noble gas monitors in modes where initiating signals from these monitors are not required to function or to be operable.
, .(3) The SNUPPS plant design does not provide for flow indication on che Unit Vent or Radwaste Building Vent effluent streams. Therefore, operability and surveillance
, requirements for.these effluent stream flow rate monitors have.been deleted. Release pathway flowrates are derived g_, - via fan status (i.e., on/off) and designed flowrate
^
R;g (reference, FSAR Table ll.lA-4). In lieu of actual flow
>h - measurement and indicati'on, this method of flow Ed# determination is utilized.
- . (4) . ACTION 42
- .Since two oxygen monitors are provided per re-combiner, implementation of grab sampling and lab analysis is not warranted if the inlet channel'is declared inoperable.
~
Provided the outlet oxygen monitor is functional, sufficient on-line monitoring is provided to measure and 4 control oxygen concentrations and ensure safe operttion ,
of the Waste Gas Holdup. System.
, -In the event that the inlet channel is. inoperable, the most appropriate action from an operational and safety standpoint is to isolate the oxygen supply and monitor the outlet channel.
In the event that the outlet channel is inoperable,
- the most appropriate action is to isolate the oxygen supply
, -and implement sampling and analysis as indicated. In the event that both channels are inoperable, grab sampling is warranted and should be implemented.
(5) ACTION 44: As described in FSAR Section 11.3.6, the Gaseous Radwaste System prevents flammable mixtures by monitoring and controlling the oxygen concentration at appropriate l~ levels. It is, therefore, appropriate that ACTION 44, which serves to prevent explosive gas mixtures through
~ fP,d oxygen control, be applied to the specific monitor which i UI$f provides the control function. (In the Callaway design, S$2 this is the oxygen monitor vice the hydrogen monitor.)
-This approach is consistent with Technical Specification
- 3.11.2.5. ,
i t
-me-,, + - ---,-r, ,-,-,,-..e--,-. , - - - - , , - ..-..-.y ,.--,=-+,,.--vr.,r.,w-r -,,,w.---~c.-,e, ~ me.v..-,_y
i (6) ACTION 45: Modifies ACTION 42 such that it is
. compatible with the minimum channels operable requirement for hydrogen monitors.
t t
i .
a p%
- Q)
N' l\
kjj '
[} N.
TABLE'4.3-9 9
Q { RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS c *
;;j 4 ANALOG j i 4 c CllANNEL MODES IN WillCil CilANNEL SOURCE CHANNEL Ij $ INSTRUMENT CllECK OPERATIONAL SURVEILLANCE ii * ,
CHECK CALIBRATION TEST REQUIRED
- 1. WASTE GAS HOLDUP SYSTEM Explosive Gas Monitoring System ,
jl' a. Inlet Hydrogen Monitor. D N.A. **
Q(4) M d '
- b. Outlet Hydrogen
] .
Monitor D N.A. Q(4) M **
n
, c. tInlet Oxygen Monitor D N.A. **
Q(S) M -
! c . . .
- d. Outlet Oxygen Monitor. N.A.
R :V
. D Q) M **
i
*- 2.
l ~ Unit Vent' System
- y. -
4 d '
a..' Noble Gas Activity Monitor
D M R(3) Q(2) *
{ ,(Providing~ Alarm (RE-21)
- b. ; Iodine sampler 0*D
, W N.A. N. A. ; N.A. *
- c. Particulate Sampler '
W N.A. N.A. *
,. . N.A.
ri_ n... - a.-- g g,;, ; q
- d. f. Sampler Flow Rate Monitor D N.A. R
- Q I 3. Containment Purge System Noble Gas Activity Monitor - s Providing Alarm and Automatic I Termination of Release D P R(3) g/) ***
{RE-22,RE-33,RE-31,RE-32)
GT- 4T- GT- 4T-i
,c , M.
lW.
jf il } j]. ~
s};
w d
, i g TABLE 4.3-1 (Continued) r-
.! g RADIDACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
.. r lf -< -ANALOG
., , CHANNEL MODES IN WillCil 1 g GIANNEL SOURCE CilANNEL OPERATIONAL SURVEILLANCE fj q INSTRUMENT CHECK CilECK CALIBRATION TEST REQUIRED 7 6-8
.) . 4. Radwaste Building Vent System
- a. Noble Gas Activity Monitor - D, P MP R(3) Q(1) j Providing Alarm and Automatic
'j -TerminationofRelease(RE-10) l b. Iedine Sampier
- O W H.A. N.A. N.A. *
' c.- ~ Particulate Sampler W N.A. N.A. N.A. *
~
l '
FW %te %!t ~- "
n.". ; ^ '
^
k]- .D N.A.
- - -s 4
+ d.f.,,'.SamplerFlowRateMonitor'. ..,;-
R Q
's . .,*'/,-q; * ~, s
. g. e 9
.r. -
g .
l1 ' . . .-. .; . . i; i
j .
. j.
~,
1 .
, s .
}.'
6
] .4.
,' , ,, h'{::
~
. c .ie 4 p .
l;. '; -
, .. s 1: '
s .%
i Y-l:
7 TABLE 4.3-9 (Continued)
(b 0
% I TABLE NOTATIONS At all times. -
** Ouring WASTE GAS HOLDUP SYSTEM operation.
I AA A Ig 3 84 And d#ing ($R 4t CAWF)S (1) The# ANALOGCHANNELOPERATIONLTEbshallalsodemonstratethatauto isolation of this pathway andacontrol room alarm annunciation occur if
/F any of the following conditions exists:
a.
(,lSolaM0fMnMd(hl Instrument indicates measered levels above the Alarm / Trip Setpoin'NI or
- b. bemon%')
Circuit failure g or l c. Instrument indicates a downscale failure (alarm only), or
- d. Instrument controls not set in operate mode (alare only).
(2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control i
room alarm annunciation occurs if any of the following conditions exists:
- a. Instrument indicates measured levels above the Alarm Setpoint, or
- b. Circuit failure, or I - c. Instrument indicates a downscale failure, or -
- q. d. Instrument controls not set in operate mode.
(0) The initici Of*=L 0", LISP 2TIOM :h:P 5: p:rf:c:d ering ene er =e e e r the r:fer:=: :t=d:.rd; =rtif t:d by th: hti=:1 Bu== cf St=d:-d:
(MSS) 07 using su nderd: that h= ; b = ; :b ui = d f m eupplier; that YNb parti:ip:t: 1. ::=:r==t ==r== =thitin with MSS. Th=: :t=d:rd:
th:P p: =it :: lib = ting th: :y;t= :=r it; int =d;d =;; cf :=rg =d
> -measur=;nt r=ge. Fer re5:: _ -t C!i".MMEL C'LISPATIOM, ;;;rces that have b:= r:!:ted t: +2: *-iti:1 ='.97:tien th:!' 5: :::d.
(4) The CHANNEL CALIBRATION.shall include th use of standard gas samples containing a nominal: l
- a. One volume percent hydrogen, balance nitrogen, and i
- b. Four volume percent hydrogen, balance nitrogen. '
I -
I (5) The CHANNEL CALIBRATION shall. include the use of standard gas samples containing a nominal: c :- a-f .mn. .. w: v i . .- ; -
a~.
- a. One volume percent oxygen, balance nitrogen, and *
~ ~
- b. Four volume percent oxygen, balance nitro'en.. g ~
. ~
q;W.t
*t .
Cli) L- SELT D CALLAWAY - UNIT 1 3/4 3-75~
I- *
[ 2 *
[ ** _ _ _ _ _ *** ' **f
- M i*___C_~_._%=Ow*
. k' A INSERT C
.Y?.E (3) CHANNEL CALIBRATION shall be performed using:
- a. One or more standards traceable to the National Bureau of Standards, or
- b. Standards obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards, or
- c. Standards related to previous calibrations using (a) or (b) above.
INSERT D C.
% (6) The CHANNEL CALIBRATION shall include the use of g) standard gas samples containing a nominal:
- a. 10 ppm by volume oxygen, balance nitrogen, and
- b. 80 ppm by volume oxygen, balance nitrogen.
wg
l
(" TABLE 4.3-9 fA A/-
JUSTIFICATION:
1 l
(1) The generic standard technical specification table does not reflect the SNUPPS Plant design. The table has been revised to reflect actual site specific design in regard to gaseous effluent monitoring instrumentation.
(2) According to Specifications 3.6.1.1 and 3.9.4, containment I integrity is not required to be maintained during modes 5 l and 6 with the exception of Core Alterations during mode 6. l The proposed change to item 3 deletes surveillance requirements for Containment Purge Noble Gas Monitors in modes where initiating signals from these monitors are not required to function or to be operable.
(3) The SNUPPS plant design does nct provide for flow indication on the Unit Vent or Radwaste Building Vent effluent streams. Therefore, operability and surveillance requirements for these effluent stream flow rate monitors have been deleted. Release pathway flowrates are derived via fan status (i.e., on/off) and designed flowrate
- (reference FSAR Table ll.lA-4). In lieu of actual flow f" ' measurement and indication, this method of flow determination
- y. is utilized.
ea (4) The changes to table notation (1) were made to reflect the designed capabilities and characteristics of the subject monitoring system. Although the monitors will provide an alarm indication when each of the four specified conditions exist, alarm and isolation will occur only when the Alarm /
Trip setpoint is exceeded.
(5) In reference to table notation (3), these monitors are calibrated by the manufacturer using NBS traceable standards for principal radionuclide energies and concentrations.
(Calibration of these monitors is addressed in FSAR Section 11.5.2.1.5.) In view of this fact, the alternate wording is proposed to clarify CHANNEL CALIBRATION reference standard requirements and is directed towards calibrations to be performed concurrent with and subsequent to initial plant startup. The proposed wording is consistent with Reg. Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment and the intent of the original footnote.
(6) A table notation (6) was added to address the range and specific calibration requirements of the outlet oxygen p., monitor. Readout of this monitor is in ppm vice percent.
The calibration concentrations specified for CHANNEL CALIBRATION cover both high and low points of the monitor
response.
-= . _ _ _ _ -- . _
t$$.
W 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LICUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 5.1-4) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 4 microC.irie/ml total activity.
APPLICABILITY: At all times. **
ACTION: jait,iate. %Ckio A a.With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately3 restore the concen-tretien to within the above limits, b N pe's%r j 5 acificabens p 3.03 ( 3.o.+ e<c nut applicalole.
SURVEILLANCE REOUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.
a.11.1.1.2 The results of the radioactivity analysis shall be used in accordance i with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintaiaed vithin the limits of Specification 3.11.1.1.
l b@?+
CALLAWAY - UNIT 1 3/4 11-1
w
. A
,$$ SPECIFICATION 3.11.1.1
- c9r s JUSTIFICATION:.
- (1) Operational considerations preclude instantaneously accomplishing the required action. The proposed wording clarifies the intended action and ensures that steps to rectify the condition are immediately started and corrective action is completed as soon as possible.
(2) Action b:
A change in the operational status of the unit will have little or no impact on the release of liquid radioactive materials to the environment, as this is controlled by the liquid radwaste treatment system and its associated pumps, valves, etc. , furthermore, the unit cannot be placed in a condition whereby this specification is not applicable. Therefore, the provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
C tL
.r s
'st
' f:
bd/ >
,o TABLE 4.11-1 1: ;
s RADI0 ACTIVE LICUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM OFDETECTg
' LIQUID RELEASE SAMPLING ; ANALYSIS TYPE OF ACTIVITY (LLD)
TYPE FREQUENCY ; FREQUENCY ANALYSIS (pCi/mi)
I
- a. Saten Waste P i P Release Each Batch ~7
!EachBatch Principal Gartma 5x10 Tanks (2) t Emitters (3)
I-131 1x10
-6
{
Monitor Tank P I
t M Dissolved and 1x10
-5 One Batch /M 1 Entrained Gases I (Gamma Emitters) ,
- 2. Secondary I
Liquid
'!;ter West
. P M 1x10 Monitor Each Batch l Composite (4)H-3 Tank _7 Gross Alpha 1x10 t
P Sr-89, Sr-90 5x10
-8 Q
Each Batch Composite (4)
Fe-55 1x10
-6
- b. Continuous b W q Principal Gamma 5x10'7 Releases (5) g;nt$====;(6) Composite (#) Emitters (3)
Grab SamP' I
-6 I-131 1x10 Steam Generator Blowdown Dissolved a.nd -5 M M 1x10 6 Grab Sample Entrained Gases (Gamma Emitters)
D M d H-3 1x10'E I I
C:ntinueur(6) Composite (#) _7 d vak Sample.
i Gross Alpha 1x10 9 Sr-89, Sr-90 5x10
-8 3 Q C:ntinu:::(6) Composite ( _
Grek bple Fe-55 1x10 *
.o c.
CALLAWAY - UNIT 1 3/4 11-2
c t
'( s. f TABLE 4.11-1 (Continued) ;
TABLE NOTATIONS (1)The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
i 4.66 s b E V 2.22 x 10s y . exp (. Mt) -
Where:
LLO = the "a priori" lower limit of detection (microcuries per unit mass or volume),
sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), *
- t. 9 E = tne counting efficiency (counts per disintegration),
V = the sample size (units of mass or volume),
2.22 x 108 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (s 1), and at = the elapsed time between the midpoint of sample collection and the time of counting (s).
Typical values of E, V, Y, and at should be used in the calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the c:? ability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
(2)A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isclated, and then thoroughly mixed by : ::th:d d::c-ib:d '- th: 000" to assure representative sampling.
hl w
CALL WAY - UNIT 1 3/4 11-3
r n.
y' TABLE 4.11-1 (Contin.ued) a TABLE NOTATI0i45 (Continued)
(3)The principal gamma emitters for which the LLD specification applies cyclusial 3 an. 4~
!ude the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, In-CL Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the gemiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7./i- :n: for::: Outlined in ~1;;;;;;;ry Guide 1. 21, appendi" E, ';i:ier 1, Jun: 197'.
(4)A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the
- method of sampling employed results in a specimen that is representative of the liquids released.
(5)A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g. , from a volume of a system that has an input flow during the continuous release.
(OT: 5 pre:entativ: cf th qu;ntitic: :nd :n;;ntrati n: c' radic :tive
-::teri:1: in liquid affluents, 3aa+1e3 3 hell be cei b c.e; cm m n ;y .o p-eper+ic- to the rate of 'le.: ef the ef'luent :tr::- "-ice t: :n:1y:::,
(,?; all semples tekea #ca the : ; :it:
- h:!' 50 thercu;;hly H d ' Order C "--
--- :ite ::mple :: k r ;r:sant;;i.; af the af fLec.; '. elea3e.
(O wkW <dem. .b. occuerin$.
kucS wb;c_k m. bek +he M b the and3 sis 5 % bs_ r y A s). e. *W thw '- tk n u e.(:cG w Lt. D , hA sAstt uk be . ego <hei as 6.&) puse.d-
- 'a 4 4 4- Lt6 level Soc t4av n uc.(th . The. " I os b
- l 9 al we.s shad wot for. ugd in rka_ a a:nd do se.
s ( edC udBA le H S .
O (sw..
CALL WAY - UNIT 1 3/4 11-4
m,jv TABLE 4.11-1
.'E JUSTIFICATION:
(1) The table was revised to incorporate the SNUPPS liquid release types and site specific system terminology.
Since the SNUPPS Plant design does not include continuous composite samplers on the steam generator blowdown, daily grab samples while the release is occurring, is proposed as an acceptable alternative.
(2) Fcotnote 2: The methods for the mixing of the liquid waste tanks to ensure representative mixing is described in plant operating procedures as opposed to the ODCM.
(3) Footnote 3: 2n-65 was deleted since Zn-65 analyses are primarily applicable to BWR's with admiralty metal condenser tubes. Per FSAR 4.5.1.1, the primary system does not contain any zine based steel alloys; therefore, there is no zine to be activated to Zn-65.
The proposed modification prcvides clarification that the 5 specification's LLD value applies only to the listed nuclides (ik),i p . and not to a virtually limitless number of gamma emitting
(;3;i nuclides. The requirement to report.all other identifiable radionuclides is not changed by the proposed modification.
The deletion of the reference to Reg. Guide 1.21 is to ensure consistency with Specification 6.9.1.7 (which augments the Reg. Guide 1.21 requirements) and to eliminate redundancy of Specifications.
The indicated text was added to clarify use and application of LLD values specified within the table.
(4) Footnote 6: Since the SNUPPS plant design does not include continuous composite samplers on the steam generator blowdown i footnote 6 was deleted as not applicable. Daily grab samples while the release is occurring is proposed as an acceptable alternative to continuous composite samplers.
Footnote 6 original wording was replaced with "while release is occurring" to clarify the sampling frequency requirement for continuous releases.
t?
L
r RA0f0 ACTIVE EFFLUENTS T
v DOSE LIMITING CONDITION FOR OPERATION an Tyvd ual 3.11.1.2 The dose or dose commitment to : ".5"SE". CF T"E """.'IC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-4) shall be limited:
- a. Duringanycalendarquartertolessthanorequalto1.5mremfto thewholebodyandtolessthanorequalto5meem/toanyorgan, and
- b. During any calendar year to less than or equal to 3 mrem wholebodyandtolessthanorequalto10 mrem /toany/tothe organ.
APPLICABILITY: At all times.
ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specifica-
^ tion 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken kip to reduce t.he releases and the preposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include: (1) the i
results of radiological analyses of the cinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141, Clean Drinking Water Act."
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS l
4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
l "Tne requirements of ACTION a.(1) and (2) are applicable only if drinking water supply is taken from the receiving water body within 3 miles of the plant discharge. In the case of river-sited plants this is 3 miles downstream only.
~Q0 i CALLAWAY - UNIT 1 3/4 11-5 l ,
i_
[ SPECIFICATION 3.11.1.2 JUSTIFICATION:
(1) The term " MEMBER OF THE PUBLIC" has been replaced with the term " Individual" in that:
- a. 10CFR20 and 10CFR50, Appendix I. require that Radioactive Effluent Concentrations, Doses and Dose Rates be calculated for Individuals at or beyond the SITE BOUNDARY and/or in UNRESTRICTED AREAS. These regulations neither expressly or implicitly require that these calculations be performed for persons, real or imaginary, who may occupy areas within the SITE BOUNDARY for some fraction of the time.
- b. The use of the term " MEMBER OF THE PUBLIC" as defined in Specification 1.16, is inconsistent with the requirements of the Specification that doses be calculated for i UNRESTRICTED AREAS. Therefore, its use would cause the '
Specification to be internally inconsistent.
- c. As stated in the bases, the purpose of this Specification is to provide for compliance with 10CFR20 and 10CFR50, gg, Appendix-1, limits. The use of " MEMBER OF THE PUBLIC"
;4 is inconsistent with the stated purpose of this
;{ Specification. -
- d. The design of the Callaway Plant is such that it precludes.
the possibility of exposure to an individual within the SITE BOUNDARY from liquid effluents.
Therefore, the use of the term " MEMBER OF THE PUBLIC" is inconsistent with the expressed purpose of the Specification and requires inconsistency on the part of the Licensee in complying with the Specification. Additionally, there are no legal requirements for its use in this specification.
( Thus, the use of the-term " MEMBER OF THE PUBLIC", while l
appropriate for Specifications implementing 40CFR190 requirements, is inappropriate in this Specification, and should be deleted in favor of the term " Individual".
l l
I
**3
- m I
RADI0ACTTVE EFFLUENTS p
Q LIOUID RA0 WASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 4
3.11.1 3 The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-4) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31 day period.
APPLICABILITY: At all times.
ACTION:
- a. With radicactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission ,
j within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:
- 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or
. z., subsystems, and the reason for the inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent a recurrence,
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
l SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.
4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.
I l
1 CALLAWAY - UNIT 1 3/4 11-6
r RADI0 ACTIVE EFFLUENTS LIOUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The-quantity of radioactive material contained in each of the following snprotected outdoor tanks shall be limited to less than or equal to 150 Curies, excluding tritium and dissolved or entrained noble gases:
- a. Reactor Makeuo Water Storage Tank,
's . Is;fu;1ing i';ter Stcr;;; T nk,
- b. r. Condensate Storage Tank, and
- c. d". Outside temporary tanks, excluding liner being used to solidify radioactive waste and dem;ner al 38 ' 9essels .
APPLICABILITY: At all times.
ACTION: *
- a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours reduce the tank contents to within the limit, and describe the avents leading to this condition in the next semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
i ,
SURVEILLANCE REOUIREMENTS
. 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at 1:::t ence per 7 days when radioactive materials cr; ';ing added ta the tank. \ \ within have been
.CALLAWAY - UNIT 1 3/4 11-7 4
.-.-,y - . , , - - - ,.,,r---e.-. - , _ - - - , + r . - r
f-k I
L SPECIFICATION 3.11.1.4 JUSTIFICATION:
(1) Deletion of the Refueling Water Storage Tank (RWST):
- a. Althought.the RWST has the greatest pobability of containing significant levels of radioactivity, it is a Seismic Category I structure, with over-flows to the liquid radwaste system. It should therefore be exempt from this Specification.
(Ref: .FSAR Section 6.3.2.2 and FSAR Table 3.2-1 (Sheet 5)).
Modification of the LCO as proposed ensures applicabiltiy of the Specification to the SNUPPS Plant design, while maintaining the intent and purpose of the Specification.
(2) Surveillance Requirements 4.11.1.4 Due to the low level of activity available for addition to these tanks, a sample every 7 days is adequate only if additions have been made. The wording provided by the Standard Tech Specs would require a separate sample for each addition to the tank -- no matter how small.
This restriction is not warranted on these outside tanks.
l
RADIOACTIVE EFFLUENTS
;, m,
'; D 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:
- a. For noble gases: Lessthanorequalto500mremh/yrto-hewhole body and less than or equal to 3000 mrem (/yr to the skin, and
- b. For Iodine-131 and 133, for tritium, and for all radionuclides
.in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem (/yr to any organf.gfm MC W\A% p on%.
APPLICABILITY: At all times.
ACTION: 'gqi\; gMor) h a
7 () With the dose rate (s) exceeding the above limits, immediately^' restore the
.h ' release rate to within the above limit (s).
(6) TN. pues:.m o f spei fica u.as s.o. 3 *a d 3. o. + are cat applica ble.
SURVEILLANCE REOUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the 00CM.
-4.11.2.1.2 The dose rate due to Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the metnodology and parameters in the 00CM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.
4 h
CALLAWAY - UNIT 1 3/4 11-8 l
m-v -- e m m-re , wwa --- t-- r rme- r, y m ---r- w ww-e~w,,--- w -m- -w e+w~-m- --~ - -
r-c..
[
SPECIFICATION 3.11.2.1 JUSTIFICATION:
(1) This specification implements 10CFR20 concentration limits at the unrestricted area boundary. The MPC values specified in 10CFR20 were determined using ICRP 2 methodology and are therefore based on the inhalation pathway only. It is therefore appropriate that doses calculated to verify compliance with this specification consider only the inhalation pathway. The proposed wording has been added to clarify the LCO requirement.
(2) Operational considerations preclude instantaneously accomplishing the required action. The proposed wording clarifies the intended action and ensures that steps to rectify the condition ere immediately started and corrective action (i.e., restoration of release rate to within limits) is completed as soon as practical.
fr w (3) Action b;
}
(f A change -in the operational. status of the unit will have little or no impact on the release of radioactive-materials to the environment, as,this is controlled by the HVAC and its dampers, fans, etc., furthermore, the unit cannot be placed in a condition whereby this specification is not applicable. Therefore, the provisions of Specification 3.0.3 and 3.0.4 are not applicable.
i l
#I*
i b t, CLY i-
~
TABlf 4.11-2 9
{E RADI0 ACTIVE CASE 005 WASTE SA{1Pl.IllG AliD AtlALYSIS PROGRAli
-< ~
~
. HllilHitti HRIEliTffilT6F III c SAMPLING ANAL.YSIS IYPE 01 DETEC110rl(ILD) 2'i GASEOUS, RELEASE TYPE FREQUENCY FREQUfNCY ACTIVI1Y ANALYSIS ._
(pCi/ml)
- P P
" ) ~4
- 1. Waste Gas Decay Each Tank Each Tank Principal Ganana Emitters 1x10 Tank Grab Sample
~4
- 2. Containment. Purge Each PilRGE Each PURGE Principal Gamma Emitters (2)W 1x10 or Vent Grab -
Sample M H-3 (oxide) ' lx10 -6 3 Vents ~4
- a. Unit Vent C M'3Y'I4) Principal Gamma Emitters (2)N 1x10 t' Grab M -6
- Sample 11-3 (oddd 1x10
"' '- ' " ~ r -' ' "' 4
- h. Radwaste Building "
l
- Vent "..^...c....,'.-
'_g g'
..s mu _l M Principal Ganuna Emitters lx10 Grab Sample M
-12
- 4. All Release Types Continuous W I-131 1x10 as listed in 1., 2., Charcoal 1 -10 and 3. above. 5 Sample I-/33 lx10 f Principal Gamma Emitters f2)
~II Continuous Wh 1x10 Particulate s Sample Continuous f M Gross Alpha lx10'II Composite Particulate S Sample Continuous f Q Sr-89, Sr-90 1x10~
Composite Particulate Scijple _ _ . _ , _ . , , , . _ _ _ _ , _ _ , , _ . ._
F l l
I TABLE 4.11-2 (Continued)
TABLE NOTATIONS (1)The LLD is defined, for purposes of these specifications, as the smallest !
concentration of radioactive material in a sample that will yield a net count, above system background, that will be Setected with 95% probability i with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiocnemical separation:
- 4. s LLD = b E V 2.22 x 108 Y exp (-Aat)
Where:
LLD = the "a priori" lower limit of detection (microCuries per unit mass or volume),
s b = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),
(B.
x-E = the counting efficiency (counts per disintegration),
'V = the sample size (units of mass or volume),
2.22 x 108 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (s 1), and At = the elapsed time between the midpoint of sample collection and the time of counting (s).
Typical values of E, V, Y, and at should be used in the calculation.
It should be recognized that the LLD is defined as an a oriori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
M w
e CALLfdAY-UNIT 1 3/4 11-10
, w ,,y,,----- - -_ w v--
D TABLE 4.11-2 (Continued)
TABLE NOTATIONS (Coatinued) ,
(2)The principal gamma emitters for which the LLD specification applies f.1ch$idt.\g art # c'"d- the following radionuclides: Kr-87, Kr-88, Xe-133, Xa-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, I.M 5, Mo-99, I-131, Cs-134, Cs-137, Ce-141, and-Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the semiannual Radioactive Effluent Release Report pursuant to Specification 'e- et cut!' ed '- o.eguht: y Cu'd 1.21, e--- m o o_.4,4-. 6.9.1.7,
. the
,au
.r-- -, - - - -- -u - - - - - - - -
g g
(3) Sampling and analysis shall also be performed following shutdowg STARTUPg or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within 1 hour period. DD M d%) dier EATGD (4) Tritium grab samoles shall be taken pt 'ert a ce paa. 24 hours m4 the TtW.084L refueling canal is flooded,anft g g(g Pows.rt WML tht n- w _4 4 m_ ..u OdoAfd,,sog
.-_- _, ,u,, u- ..o__
CM%, \ i<,(g4
. gp 7h y og\ood . , . . .
. _ . i ,4 , . , e < , . . , . m unm+" e n a hs ee; we a m .6 -- =* # =* -- --- ----.d..=, Ja
~ ~~ '"-"' '-' " ~ ' ~ " ' "'' '"'"' '"' ' '
, - ~ ; d.. ';. ,; .. ~. __,. ,.;i ' a,3 (f)The ratio of the sample flow rate to the sampled stream ficw rate shall be known for the time period covered by each dose er dose rate calculation made in accordance with Specifications 3.11.'2.1, 3.11.2.2, and 3.11.2.3.
in Oom 2. E % EATEDT H.*AL PodEG- to E 152 httbTwEeA4. 9bt44 (7) Samples shall be changed at ast once per days and analyses shall be completed within 48 hours af r thanging, r after removal from sampler.
Sampling shall also be perfo d at leas once per 24 hours for at least 7 days following each shutdow STARTUPaor THERMAL POWER change exceeding 15% of RATED THERMAL POWER wi in a 1-hour period and analyses shall be com-i_ pleted within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs mr.y be increased by a factor of 10.
This requirement does not apply if: (1) analysis shows that the DOSE l EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
' h m. k $ W f h GC(. hd w h LL.D hr b . A m S@
M be_ n.vorWD- as "k% %an" tw( hc_Udis LL.D d She ned b(, QpotigA, c3 @ ppgelqk a.k kht
@g \ 2 M M k e % \ s t S 6 c. . T n t N c3 % " g \ w e g Shau nok bt gstO. (o %g., rg gggf}, doc.g cgggo CALL WAY - UNIT 1 3/4 11-11
e
'h$
4.s TABLE 4.11-2 JUSTIFICATION:
(1) ' This table was marked up to reflect site specific SNUPPS Plant design.
(2) Footnote _(3).for Containment Purge and the Unit Vent was repositioned from the " Sampling Frequency" column -
to " Principal Gamma Emitters"oto indicate that only a radioisotopic analysis is required for a 15% power i change.- Analyzing only for gamma emitters (fission i
. products) following a power change is appropriate since it is unlikely that tritium levels would be greatly affected by changes in reactor power.
(3) The footnote for three of the " Principal Gamma Emitters" was changed to (2) it is the appropriate and applicable footnote.for that type of anlaysis.
(4) Footnote 2: Zn-65 was deleted since Zn-65 analyses are primarily applicable to BWR's with admiralty metal condenser (fp tubes. Per FSAR 4.5.1.1 the primary system does not Fyg contain any zine based steel alloys: therefore, there is Qfi
. no zine to.be activated to Zn-65.
!- The proposed.v.odification provides clarification that the specification's LLD value applie's only to the. listed nuclides and not to a virtually limitless number of gamma
, emitting nuclides. The requirement to report all other I identifiable radionuclides is not changed by the proposed
! modification. The proposed modification is consistant l . with the equivalent notation of Table 4.11-1.
The inserted text was added to clarify use and application of LLD values specified within the table.
(5) Footnote 3: The additional wording is proposed to clarify-
.the performance of sampling and activity analysis associated with changes in reactor power levels.
(6) Footnote 4: The extended tritium sampling frequency is justified since airborne tritium levels are not subject to rapid variations or fluctuations, and are, therefore, relatively stable after initial flooding of the canal.
The proposed sampling requirements ensure adequate monitoring and surveillance of airborne tritium concentrations.
f$h[ (7) Footnote 5: Footnote (5) was deleted and subsequent l7l!y footnotes renumbered. It is proposed that the normal 02r tritium sampling of the Unit Vent is sufficient to monitor the tritium concentration in the fuel pool area ventilation exhaust. Justification for this position is as follows:
p h$
h/J (7) Continued e
' a'. The SNUPPS Plant is designed such that the Fuel Building ventilation exhaust is discharged through the Unit Vent. Therefore, the routine tritium sampling of the Unit Vent also monitors the fuel pool' area exhaust (FSAR Section 9.4.2.2.3).
- b. .The Spent Fuel Pool Cooling System (FPCS)
(FSAR Section 9.1.3.2.3.1) provides constant removal of decay heat, maintaining the water temp-erature below 135'F. The FPCS is a Seismic Category I system with separate and redundant loops. It, therefore, provides reasonable assurance of relatively constant Fuel Pool temperatures and thus relatively constant tritium levels from fuel pool water evaporation. It is, therefore, reasonable that the tritium sampling freque.ncy be extended as proposed.
- c. Protection of personnel who may be working in the vicinity of the spent fuel pool is partially provided by the Fuel Building HVAC, which takes a suction on
[SQ the area above the spent fuel pool (FSAR Section a 9.4.2.2.3) and is ensured by the tritium sampling (jf performed as part of the Radiation Work Permit program.
(8) ' Footnote 6: The additional wording is proposed to clarify the change out and analysis of charcoal and paper filter samples associated with changes in reactor power levels.
l l
r t
^-
7,-
J'
, -.-r- - ., -., - , . - , , , , ,. , . , ,- .-- - ., - - - - - - ,
RADIOACTIVE EFFLUENTS (R:( 00SE 0 - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to ncble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-2) shall be limited to the following:
- a. During any calendar quarter: Lessthanorequalto5 mrad /for gamma radiation and less than or equal to 10 mraq/ for beta radiation, and
- b. During any calendar year: Lessthanorequalto10 mrad /forgamma radiationandlessthanorequalto20 mrad /forbetaradiation.
APPLICABILITY: At all times.
i ACTION:
- a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a
,, Special Report that identifies the cause(s) for exceeding the limit (s)
(2 j. and defines the corrective actions that have been taken to reduce
'i J the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS
$ 4.11.2.2 Cumulativeddhpcontributionsforthecurrentcalendarquarterand
\ current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
l l
f
!?
! k t<'
l CALLAWAY - UNIT 1 3/4 11-12 r . _ __
r RADIOACTIVE EFFLUENTS O
,g 00SE - 10 DINE-131 AND 133. TP.ITIUM, AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM LIMITING CONDITICN FOR OPERATION an T Lhal 3.11.2.3 The dose to ".E"SEP, OF T"E P'JSLIO from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than S days in gaseous effluents released, from each unit, to areas at and beycnd the SITE BOUNDAP.Y (see Figure 5.1-3) shall be limited to the following:
- a. During any calendar quarter: Lessthanorequalto7.5 mrem /toany organ, and
- b. During any calendar year: Lessthanorequalto15 mrem [toany organ.
APPLICABILITY: At all times.
ACTION:
- a. With the calculated dose from the release of Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and. submit to the Commission within 30 days, pursuant to Speci-h, fication 6.9.2, a Special Report that identifies the cause(s) for
% exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
. SURVEILLANCE REOUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days, ff-W CALLAWAY - UNIT 1 3/4 11-13
Wh kf ; SPECIFICATION 3.11.2.3 JUSTIFICATION:
The term " MEMBER OF THE PUBLIC" has been replaced with the term " Individual" in that:
- a. 10CFR20 and 10CFR50, Appendix I, require that Radioactive Effluent Concentrations, Doses and Dose Rates be calculated for Individuals at or beyond the SITE BOUNDARY and/or in UNRESTRICTED AREAS. These regulations neither expressly or implicitly require that these calculations be performed for persons, real or imaginary, who may occupy areas within the SITE BOUNDARY for some fraction of the time.
- b. The use of the term " MEMBER OF THE PUBLIC" as defined in Specification 1.16, is inconsistent with the requirements of the Specification that doses be calculated at the SITE BOUNDARY. Therefore, its use would cause the Specification to be internally inconsistent.
- c. As stated in the bases, the purpose of this Specification eps is to provide for compliance with 10CFR20 and 10CFR50, Appendix 1, limits. The use of '41 EMBER OF THE PUBLIC" is
}f inconsistent with the stated purpose of this Specification.
Therefore, the use of the term " MEMBER OF THE PUBLIC" is inconsistent with the expressed purpose of the Specification and requires inconsistency on the part of the Licensee in complying with the Specification. Additionally, there are no legal requirements for its use in this specification.
Thus, the use of the term " MEMBER OF THE PUBLIC", while-appropriate for specifications implementing 40CFR190 require-ments, is inappropriate in this Specification, and should be deleted in favor of the term " Individual".
e.
4
=
RADIOACTIVE EFFLUENTS R.
y' GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLD SYSTEM shall be OPERABLE and appropriate porions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) would exceed:
- a. 0.2 mrad to air from gacea radiation, or
- b. 0.4 mrad to air frem beta radiation o
- c. an Ld v re(ual 0.3 mrem to any organ of c "EMSER 0" THE TL' L:C.
APPLICABILITY: At all times.
ACTION:
- a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and ibmit to the Commission within 30 days, pursuant to Specificacion 6.9.2, a Q Special Report that includes the following information:
- 1. Identification of any inoperable equipment or suosystems, and the reason for the inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent a recurrence.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.
4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM ano the WASTE GAS HOLDUP SYSTEMS shall be considered OPERABLE by meeting Specifications 3.11.2.1 and 3.11.2.2 or 3.11.2.3.
Cf3 ~
Q?
CALLAWAY - UNIT 1 3/4 11-14
n.
nn
' mUD3..
[$.t g ..
SPECIFICATION 3.11.2.4
- JUSTIFICATION:
The term " MEMBER OF THE PlTBLIC" has been replaced with the term " Individual" in that:
- a. 10CFR20 and 10CFR50, Appendix I, require that Radioactive Effluent Concentrations Doses and Dose Rates be calculated
~
for Individuals at or beyond the SITE BOUNDARY and/or in UNRESTRICTED AREAS. These regulations neither expressly or implicitly require that these calculations be performed for persons, real or imaginary, who may occupy areas within the-SITE BOUNDARY for some fraction of the time,
- b. The use of the term ' MEMBER OF THE' PUBLIC" as defined in Specification 1.16, is inconsistent with the requirements lof the Specification that doses be calculated at the SITE BOUNDARY. Therefore, its use would cause the Specification-to be internally inconsistent.
- c. As stated in the bases, the purpose of this Specification
/TL is to provide for compliance with 10CFR20 and 10CFR50, hi (ic-Appendix I, limits. The use of " MEMBER OF THE PUBLIC" is inconsistent with the stated purpose of this, Specification.
Therefore, the use of the term " MEMBER OF THE PUBLIC" is inconsistent with the' expressed purpose of the Specification and requires inconsistency on the part of the Licensee in complying with the Specification. Additionally, there are no legal requirements for its use in this Specification.
J' Thus, the use of the term "MEMEER OF THE PUBLIC", while
, appropriate for specifications implementing 40CFR190 require-
- ments, is inappropriate in this Specification, and should be deleted in favor of the term " Individual".
i
.I
?
s b
I:
RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in tne WASTE GAS HOLDUP SYSTEM shall be limited to less than or equal to f by volume whenever the hydrogen concentration exceeds 4% by volume. 4 .5%
3 APPLICABILITY: At all times.
ACTION: 3.57-
- a. With the conce tration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than fll by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours.
- b. With the concentration of oxygen in the WASTE GAS HOLOUP SYSTEM greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 4% by volume, then take ACTION a. above.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
l SURVEILLANCE REQUIREMENTS 4.11.2.5 .The concentrations of hydrogen and oxygen in the WASTE GAS HOLDUP SYSTEM shall be determined to be within the above limits by continuously monitoring the waste gases in the WASTE GAS HOLDUP SYSTEM with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.11.
CALLAWAY - UNIT 1 3/4 11-15
SPECIFICATION 3.11.2.5 JUSTIFICATION:
The proposed limit reflects the design of the SNUPPS Plant WASTE GAS HOLDUP SYSTEM.
Since the SNUPPS Plant system is designed to operate with hydrogen concentrations of up to 6 volume percent, up to 3 volume percent. oxygen is necessary for operation of the catalytic recombiner. Termination of oxygen feed _at 2 volume percent is therefore inappropriate for this particular system design.
This design has automatic safety control features which serve to limit the oxygen concentration to well below the limits of flammabiltiy.
If the oxygen concentration in the recombiner feed reaches 3 percent by volume, an alarm sounds and oxygen feed flow is limited so that no further increase in flow is possible.
This control maintains the system oxygen concentration at 3 percent or less, which is below the flammable limit for.
hydrogen-oxygen mixtures.
If the oxygen-concentration in the recombiner feed reaches 3.5 percent by volume, an alarm sounds and the oxygen feed flow is terminated.
Since the minimum oxygen concentration necessary to support combustion at 4 percent by volume hydrogen concentrations is 5 percent, the hi-alarm setpoint of 3 percent provides sufficient margin (i.e., 60 percent of the limit) to flammability.
RADI0 ACTIVE EFFLUENTS k.A t,
GAS STORAGE TANKS LIMITING CONDITION FOR OPERATI0li 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 2.5 x los Curies of noble gases (considered as Xe-133 equivalent).
APPLICABILITY: At all times.
w;4ba delay , bywto
- a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and,- ::r' ~e "cu 1, recuce the tank contents to within the limit, and describe the events leading to this condition in the next gemiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS
<= .
' 11.2.$
I: QC:nIiII f r:di:::IiVC m:I ri:l :nI:ined i" ::ch Q:: t:r:Q:
tar) 05:!' be deter- Sed to be with4- th: :50 :: 'i-it :t it :t Once p r 21 heu : 'her radie:cti" ?. terial: Or being Odd:d te the t:nt.
Inserth a
CALLAWAY - UNIT 1 3/4 11-16
INSERT F 4.11.2.6.1 The quantity of radioactive material contained in the inservice' Waste Gas Decay Tank shall be determined to be within the above limit at least once per 24 hours when:
- a. Primary coolant system degassing operations are occurring, and
- b. Conditions of confirmed 1% or greater failed fuel exist, and
- c. Radioactive materials have been added to the tank.
4.11.2.6.2 The quantity of radioactive material contained in the inservice Waste Gas Decay Tank shall be determined to be within the above limit at least once per 7 days when:
k a. Condit'pns of confirmed 1% or greater failed fuel exist, and
- b. Radioactive materials have been added to the tank.
y
^
&ty . -.
pS - SPECIFICATION 3.11.2.6
..c-JUSTIFICATION:
. Action a:
Depending on operating conditons at the time, it may prove inadvisable to place restrictions on the length of time given to accomplish the activity reduction.
The proposed wording allows the operator to assess the various parameters and to make a reasonable decision, balancing the risks involved (e.g., excessive dose to
- the public vs. possibility of tank rupture).
The restriction to a finite time limitation could result
' in circumstances whereby this specification is in direct opposition to the satisfaction of Specifications 3.11.2.2, 3.11.2.3, and 3.11.2.4. Such a restriction could result in a situation whereby the operator would be forced to
- vent the affected tank under unfavorable conditions'(e.g.,
heavy precipitation, temperature inversion, extremely stable
$]
.b QO, conditions) and thereby result in-an unnecessarily high dose to-the'public.
The propo'ed s wording is also consistent with the proposed
- i. modification to Specification 3.11.2.5.
i 1
r 1
4 4
4 t4 f;
e r
, , - - , - -, , , .~,-.._,._,.-,...--,_m...__,,..-m,_ . _ _ . . .-,_...-._.-...-...,-,--..,,-,m.-.,__--..,mm,__..,,.m,..._,
v Q:
l$h
- (';;^y SPECIFICATION 4.11.2.6 JUSTIFICATION:
(1) . FSAR Section 15.7.1 describes the analysis of a postulated
-Waste Gas Decay Tank failure and its projected radiological consequences. This evaluation utilized the fission product accumulation and release assumptions identified in
. Regulatory Guide 1.24. Some of these assumptions are: !
The maximum amount of waste gases stored in any one
~
a.
tank occurs after a refueling shutdown, at which time the Waste Gas Decay Tanks store the radioactive gases stripped from the reactor coolant.
- b. The accumulated activity in the gaseous waste processing system after 40 years' operation and immediately following plant shutdown (with .zero decay) assumed to be in the Waste Gas Decay Tank, is based on 1% failed fuel, which is 8 times greater
, than that assumed under normal operating conditions.
All noble gas activity has been removed from the
'j,(J reactor coolant system and transferred to the Waste j ' 'i" Gas Decay Tank that is postulated to fail.
l, The calculated maximum activity in the Waste Gas Decay .
Tank under these conditions is presented in FSAR Table 15.7-3, and is approximately 2.1 E04 Curies.
The calculated whole body dose to an individual at the Exclusion Area Boundary. (EAB) is presented in FSAR Table 15.7-4, and is 33 mrem.
From the aforementioned analysis, we can conservatively establish the following conclusions:
l_
- a. The maximum amount of. activity in a Waste Gas Decay Tank during normal operations is the result of primary system degassing operations.
- b. The maximum amount of activity in the primary coolant system, and thus'the Waste Gas Decay Tank, occurs during periods of 1% or greater failed fuel.
- c. The maximum Waste Gas Decay Tank activity, after 40 years of operation with 1% failed fuel and gg- immediately following total primary coolant system
'ff! degassing, is conservatively estimated as approximately e
fj 8% of the limit of Specification 3.11.2.6 (2.5E+5 Curies),
F b
- fy om@ d. The projected whole body dose to an individual
'~
at the EAB, using the limiting short-term X/Q, is conservatively estimated as approximately 7% of the 500 mrem NUREG 0133 objective and approximately 1%
of the 10CFR100.ll limit.
- e. Due to the relatively low amount of activity available to be added to the Waste Gas Decay Tank under normal operations, sampling is unwarranted until such time as the condition of 1% failed fuel is encountered.
(2) It is the expressed purpose of 10CFR20 (10CFR20.l(c)) that radiation exposures and releases of radioactive materials in effluents to unrestricted areas be maintained ALARA.
It is not in keeping with the concept of ALARA to require sampling and analysis activities which result in unnecessary occupational radiation exposure and releases of radioactive materials to the environment.
The proposed sampling and analysis requirements serve to implement good ALARA principles and thus reduce the g expended man-rem, both occupationally and to the public.
11 0 k.e b (3) The intent of Specification 3.11.2.6 as stated in the Bases, -
is to provide assurance that in the event of an uncontrolled release of the Waste Gas Dechy Tank's contents, the resulting whole body dose to an individual at the EAB will not exceed 500 mrem, which is substantially below the dose limits of 10CFR100 for a postulated event.
The analysis of a postulated Waste Gas Decay Tank rupture, conducted in accordance with Nuclear Regulatory Commission Guidelines and recommendations, using greatly conservative assumptions, conclusively demonstrates that the proposed surveillance requirements maintain a significant margin of.
safety with respect to the expressed objective of Specification 3.11.2.6, thus assuring that the limits of 10CFR100 are not approached.
(4) The proposed modification requiring Surveillance of the inservice Gas Decay Tank is appropriate since the SNUPPS WASTE GAS HOLDUP SYSTEM is designed with multiple tanks, only one of which can be inservice at any one time.
'?^
t'
RADIOACTIVE EFFLUENTS f0'
- 3/4.11.3 SOLID RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.3 Radioactive wastes shall be solidified or dewatered in accordance with
. the PROCESS CONTROL PROGRAM to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.
APPLICABILITY: At all times.
ACTION: 4
- a. With SOLIDIFICATION or dewatering not meeting disposal site and shipping and transportation requirements, suspend shipment of the inadequately processed wastes and correct the PROCESS CONTROL PROGRAM,
-the procedures and/or the Solid Waste System as necessary to prevent recurrence.
< b. With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, test tne improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and take appropriate administrative action to prevent recurrence.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS f .
( - 4.11.3 SOLIDIFICATION of at least one representative test. specimen from at least every tenth batch of each type of wet radioactive wastes (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions and sodium sulfate solutions) shall be verified in accordance with the PROCESS CONTROL PROGRAM:
- a. If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM;
- b. If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste; and
- c. With the installed equipment incapable of meeting Specification 3.11.3 or declared out-of-service, restere the equipment to operable status or provide for contract capability to process wastes as necessary to satisfy all applicable transpo-tation and disposal requirements.
$e.)
CALLAWAY - UNIT 1 3/4 11-17 i
,- -- --r - - - . . n-- -.,. , - - , - , . - . . , -, - , - - - - . - ---,--,----r-,,,-,_ -- ,- - , - - ,--,.w,- .- , ,, , , ,
, .RADI0 ACTIVE EFF3.UENTS 3/4.11.4 TOTAL 00SE LIMITING CONDITIdN FOR OPERATION 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle. sources shall be limited to less than or equal to 25 mrems to the whole body'or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
APPLICABILITY: At all times.
ACTION:
- a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b.,
3.11.2.3a., or 3.11.2.3b., calculations should be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Specification 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce sub-sequent releases to prevent recurrence of exceeding the above limits C@"; and includes the schedule for achieving conformance with the above
^
limits. This Special Report, as defined in~ 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentra-tions. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not alreadybeencorrected,theSpecialReportshallincludearequ/est f( ,
for a variance in accordance with the provisions of 40 CFR Part 190.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the 00CM.
4.11.4.2 Cumulative dose contributions frca direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the
('c,4. methodology and parameters in the 00CM. This requirement is applicable only y under conditions set forth in ACTION a. of Specification 3.11.4.
CALLAWAY - UNIT 1 3/4 11-18
/'
(< 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The Radiological Environmental Monitoring Program shall be conducted as specified in Table 3.12-1.
APPLICABILITY: At all times.
ACTION:
- a. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.6, a description of the reasons for not conducting the program as required and tha plans for preventing a recurrence.
- b. With the level of radioactivity as the result of plant effluents in g an environmental sampling medium at a specified location exceeding 140kg the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) ano defines the corrective o actions to be taken to reduce radioactive effluents so that the
*(1' potential E9EE 0F '95 ?L'SLIO is less than the calen'dar annual cose" year limits to p "ifications 3.11.1.2, 3.11.2.2, and of Spec 3.11.2.3. When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) . concentration (2) + * * * > 1. 0 reporting level (1) reporting level (2) -
When radionuclides other than those in Table 3.12-2 are cetected and are the result of plant effluents, this report shall be submitted if M the potential annual dose" to'?. "E."SE?, OF *"E FUOLIC from all radio-MMdM nuclides is equal to or greater than the calendar ' year limits of Speci-fications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant
- effluents; however, in such an event, the condition shall be reported l and de::cribed in the Annual Radiological Environmental Operating Reoort, l required by Specification 6.9.1.6.
- c. With m er fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the 00CM7F The specific locations from which samples "ine metnocology and parameters used to estimate tne potential annual dose to
~ a MEMBER OF THE PUBLIC shall De indicated in this report.
4 b Miy bebhCAor % garguvuodiM ,
CALLAWAY - UNIT 1 3/4 12-1 ,,
RA0XOLOGXCAL ENVIRONMENTAL MONXTORING LIMITING CONDITION FOR OPERATION ACTION (Centinued) were unavailable may then be deleted from the monitoring program.
Pursuant to Specification 6.14, submit in the next semiannual Radio-active Effluent Release Report documentation for a change in the 00CM, including a revised figure (s) and table for the ODCM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location (s) for obtaining samples.
- d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilitics required by Table 4.12-1.
+
hh o b
)
CALLAWAY - UNIT 1 3/4 12-2 l
.??. -
t kj SPECIFICATION 3/4.12.1, " Monitoring Program" JUSTIFICATION:
(1) The term " MEMBER OF THE PUBLIC" has been replaced with the term " Individual" in that:
- a. The purpose of this Specification and the Radiological Environmental Monitoring Program (REMP) is to supplement the Radiological Effluent Monitoring Program, thus assuring compliance with 10CFR50 Appendix I. Accordingly, the REMP is not designed to assess dose within the SITE BOUNDARY.
Thus, the use of the term " MEMBER OF THE PUBLIC" is. inconsistent with the stated purpose of the Specification.
- b. 10CFR20 and 10CFR50,' Appendix I, require that Radioactive Effluent Concentrations, Doses and Dose Rates be calculated for Individuals at or beyond the SITE BOUNDARY and/or in UNRESTRICTED pg s .
AREAS. These regulations neither expressly or PE .~ implicitly require that these calculations be
- . $j performed for persons, real or imaginary, who c may occupy areas within the SITE BOUNDARY for some fraction of the time.
- c. The use of the term ' MEMBER OF THE PUBLIC" as defined in Specification 1.16, is inconsistent with the requirements of the Specification that doses be calculated at the SITE BOUNDARY. There-fore, its use would cause the Specification to be internally inconsistent.
Therefore, the use of the term " MEMBER OF THE PUBLIC" is inconsistent with the expressed purpose of the Specification and requires inconsistency on the part of the Licensee in complying with the Specification. Additionally, there are p no legal requirements for its use in this Specification.
Thus, the use of the term " MEMBER OF THE PUBLIC", while appropriate for specifications implementing 40CFR190 requirements, is inappropriate in the Specification, and should be deleted in favor of the term " Individual".
4 r$5 09- l 4?
u I
l TAllLE 3.12-1 9
r RADIOLOGICAL ENVIRONMENTAL N0tilIORING PROGRAM
- C h HUMBER OF
, REPRESENTATIVE c EXPOSURE PAlllWAY SAMPLES AND SAMPLING AND z AND/OR SAMPLE g) TYPE AND FREQUENCY SAMPLE LOCATIONS COLLECTIGN FREQUENCY OF ANALYSIS
- 1. Direct Radiation (2) Forty routine monitoring stations " . . _ ; t ,. . ; , . Gaimaa dose .,,2ricr!y.
either with two or more A+ teas + once pu 'k b =s dosimeters or with one 9L dags ,* oaw- P instrument for measuring and q gT recording dose rate continuously, placed as follows:
sIKiten An inner ring of4 stations, one in each meteorological sector in the
, general area of the SITE BOUNDARY;
} sit 4een
, An outer ring ofratations, one in y each meteorological sector in w the 5- to 8-km range from the stTrc munwt %-+44e; and T'
E ght Et:me cf th stati9ns to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.
i O N O.
' I
, , j}
IABLE 3.12 ,1j c_ontinued}
o y RADIOLOGICAL ENVIRot!hENTAL HONIl0 RING PROGRAll*
E NUMBER OF
$; REPRESENTATIVE
' EXPOSURE PATHWAY SAMPLES AND SAflPLING AND lYPE AND FREQUENCY AND/0R SAMPLE SAMPLE LOCATIONSf1) COLLECTIDH FREQUENCY OF ANALYSIS
.] 2. Airborne af. lese ow<e pt< 'l dan at le=o .uc per <; Jec e Radiolodine and Samples from five locations: Continuous sampler. Radioiodine Cannister:
Particulates operation with sample I-131 analysis .;;;! ly.-
Three samples from close to the collection ute!y; or three SITE BOUNDARY locations, atore frequently if in different sectors, of the required by dust Patta cu l a t.e sanip i e r.
highest calculated annual average loading. Gro beta radioac ity ground level D/Q. , analys folio 9 y filter cha and One sample from the vicinity ganuna i opi nalysis g
a of a community having the highest y of posite (by w calculated annual average ground-s h H ation) quarterly.
level D/Q.
M One sample from a control i A location, as for example 15 to 30 ka: distant and in the least direction.gvalentwind a po;.1 el S: 31 days (g,) .
- 3. Waterborne I"'d 1
- a. Surface One sample upstream. sotopic a s One sample downstream.
,Compositesamigover i
! I w~nu. pc.ieu month 1 te for
. ium analysis quar b Crcur. " - L.c.,,1;; 're cr. cr t.;c ;curcc; "uarterlj. C;;=:a i;cte;9c ::" ' " f t !"-
;;-)'[1f}c15t;b; uG;13 ;i; :iu = L =17-
- c. Dr . One sample of each of one to Ccmposite sample I-131 analysis n :
ee of the nearest water g) g over 2-week period c ien the dose supplie ould be when I-131 as calculated for the consump-
-+> affected by its is '
, ormed, monthly tion of the water is D osite otherwise. than1mremperyear.pygater Com-e On rom a control
< location. positeforgrossbetaag) amma isotopic analyses H monti - nnosite ror
< a i n. , u n 1 u<: i <. on., e,
I hl,j m.m 6f-y INSERT 1 4
'7.,
.:g
.# - Particulate Sampler:
I -4 -s Analyze for gross beta radioactivity >,24 hours following .
', a filter change. Perform gamma isotopic analysis (4) on those samples for which the gross beta activity is > 10 l
J'
,t , times the yearly mean of :ontrol samples. Perform gamma
( isotopic analysis (4) on composite samples (by location) at least once per 92 days.
t l
.i ( .
l L
L y l&,-
t 4
I c"
.p;.
D,- .
J'
!l 6.'
INSERT 2 Gamma isotopic analysis (4) at least once per 31
' days. Tritium analysis of composite sample (by location) at least once per 92 days.
>h. p f+5 ?
ldd
(7-'Q
- 7. , .
,r f '3
~
, '~7g 7
INSERT 3
- b. Drinking One sample of.the nearest Grab sample collected . Gamma isotopic (4) and gross drinking water supply that at least once per 31 beta analyses at least once could be affected by liquid days. per 31 days. Tritium analyses effluent discharge, of composite sample (by location) at.least once per 92 days.
One sample from a control Composite sample (6) location. over a period of less than or equal to 31 days.
l l
l i
1 I Alli E 3.12-1 (Continucil) o r- RADIOLOGICAL ENVIRONMINIAL MONIIORING PROGRAW-C 5' NtfMBER OF
-< REPRESENTAllVE ;
- EXPOSilRE PAlllWAY SAMPLES AND SAMPLING ANil IYPE AND FREQtiLHCY c AND/OR SAMPLE SAMPLE LOCATIONS (1) COLIECII0t3 FREQUENCY OF ANALYSIS z
e-g
-4 s -
wui. ..ucu) s r. -
>. u_ .- a. .,,, . . .m g
d Scd hr. cat 0;;c ;a;.ple f ra;;; dow;tstream-area Sc= ianrusal-ly. Cc : i'ete;;ic 2:;21y'i;(5) ,
-free with-existing e petential --! n uz!!y.
.shre!'ne recr:2tienc! valec.
- 4. Ingestion
- a. " ilk S;;plc; f rca HMtuf-enimah SemimentMy ;.ncr. Co. c.. i;ctepic(S) 7,d , __ ; 3 ;,
^ thr r !ccation'. wRM;; ani=ci'; crc c;; analysis-seminenthly wh; . l
-5 '- 1ht2:::e hav ::;g the ' s'.._;t p.uti. c, asathly at
. anh;;al; ma en i.u;ti. 6, y de'.c pcicatial If therc arc athcr ti;;;c;. ;;;onthly et othcr tiac;. l 4- m ac, ther., cnc sempic !ica !
y ;;;ilking eni;;;als in cach of thicc
- crea; betucer 5 to 8 km ;'ista;;t
- whcre ds;c; arc calculated te bc 3rcater th;r. I r rc;;; pcr A.
Ot:c ';; ple f rc;;; ;.ilking ani ch
-t cc':tr^' " at !^ :, !S te 30 k 1l'.!;nt ani in the ita'.t prevale;;t wi "! direct i. -
One sample of each commercially Sample in season, or Gaum<i isotopic analysis a.[.Fishand.
inu ric- aul recreationally important semiannually if they on edible portions.
t ra t e', species in vicinity of plant are not seasonal.
discharge area.
One sample of same species in areas not influenced by plant discharge. (9,q) b.y. Food One sample of each principal AttimeofharvestN Ganaa isotopic ar.alyses N
Products class of food products from any on edible portion.
avea that is irrigated by water in which liquid plant wastes leave been elischar.pd.
TABLE 3.12-1 (Continue.1) 9 r- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- C' g NUMBER OF
-< REPRESENTATIVE
- EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY SAMPLE LOCATIONS (g OF ANAL.YSIS g AND/OR SAMPLE _ COLLECTION FREQUENCY Z
g 4. Injestion (Continued)
Samples of.Weee different kinds Monthly when Gamma isotopicI ) and 1-131 h p. Food analysis.
Products of broad leaf vegetation grown available. I (cont'd) nearest each of two different offsite locations of highest predicted annual average _ ground-level D/Q if milk sampling is not j performed.
One sample of each of the Monthly when GammaisotopicN)and1-131 y similar broad leaf vegetation available. analysis. 4 9 grown 15 to 30 ke distant in T
the least prevalent wind direction if milk sampling is not performed.
TABLE 3.12-1 (Continued)
U,,
TABLE NOTATIONS a (1) $pecific parameters of di in the ODCM.for each and every sample lof one unit, r ption where pertinent e centerline Refer to NUREG-0133, Technical Specifications ocation for Nin Table"Prepa3.12-1 in a ,tablshall be provide Radiological Assessment Branch T 1979.
uclear Power Plants," October 1978 rati specimens ability are unobtainable echnical Position, due he required sampl Revisionto, November hDeviations 1
, and to are reasons.,
tion malfuntion of automatic sampling equi the e,nd of the period.
nextue samplingevery pment, and other legitimateseason to sampling equipment malfunc effort that, at timesOperating i
p Report All ete corrective deviations pursuant from action prior the to rampli o
t Sschedul cbtai e Annual or pRadiological Environment l time.n samples,of t pecification 6 ng 1 may not be possible .9.1.6. a tions mayIn these the instances be chosen media for thasuitable of choice racticable spat thetomcontinue toIt is recogniz ost desired location or Monitoring Program particular given ecific in pathway thsubstitutions in question media made alternative - wit and loca and appropriate tation for a change for the 00CM reflecting the s in the Radiologicalin Environme e 00 cme in the 00CMsubmit a the next se identifying the cause ofnew th location oactive Effluent Release R includin .
(g a revised figure (s)eport documen-and justifying the selection e unavailability of th of samples and table for ths) with suppo f,-
4 (2) One or more instruments e new location (s) for obtaining sat pathway 1
1 and recording addition to dose rate continu
, such as a pressurized ion chamber amples.
integrating dosimeters ously may thermolumine, scent dosimeter . (Tbe used in place , or in o,ffor measuring t
or more phosphore in a packet a ) is considered tFor Film b LD e, a the purposes of t tion. adges shall not be used as dosimeters f i radiation limitations monitoring ostationsThe ute numberor measuring 40osimeters.
stations direct radia-is not an a may be reduc that the num;bere.g. , atofandosimet ocean site, some 'ed The acco.number of direct rding to geographical of the specific system used andof
;ectors will be overanalysis water so or readou information with minimal ng.
ystemsfadi will depend upon the charThe frequency (3) The purpose of this sampl should be selected to obtain acteristics opti mum dose distance and wind directionnot o practical on.
to establish contr l background data may be sub ti s criteria, tuted. other sites that Ife itprovidlocations is in e valid CALLAWAY - UNIT 1 3/4 12-7 e * .
,s --'
TABLE 3.12-1 (Continued)
TABLE NOTATIONS (4}-Mcberne-paeticulate-sample-f44ters--shal1-be-analyzed for--gross beta-radioactivity 44-hours-orwore-af ter-sampMng-to-aMow-fee-eadon :nd thoron-dacghten-decayr---4f-gross-beta-activity-4e-air-part4cu14te :=plet is-greater-than-10-times-the-yearly-sean-of--control-s amples , - g=ma i s o t o p ic-analy s is-sham-be-pe r formed-on-the-i nd Md ua l-s emp l e s .
([) Gamma isotopic analysis means the identification and quantification of q gamma-emitting radionuclides that may be attributable to the effluents from the facility.
(f)The"upstreamsample"shallbetakenatadistancebeyondsignificant g influence of the discharge. The " downstream" sample chall be taken in an area beyond but near the mixing zone. %pstr =" :=ples in an estuary must be taker far encugh upstr = t; be bey:nd the plant influence. Salt-
-atar shall be sampled only when t.he receivir.g water is utilized fcr r;;r;;tional = tivit h
-(7) ', 00mpo+fte-sample-4s-one-in which-the-quantity (aliquet) Of 'iquid
- mpi d i: pr porticn:1 to the quantity Of '! cuing 'iquid and " whi:5 th; mcthcd Of :=pling ap10yed re:elt: *: Opecimer that is represer-y t:tive af the liquid ficw. In this progra ;cmpo:ite :=pic :.liquet:
- shel' be cellected at time- intervais-that are very chcrt (e.g. , h;uriy)-
rel.tivt to the : = positing pcriod (e.g., m;nthly) in ordcr t: = ur;
=0btaining-a-representative : =p10.
-(S) Crcundwater :=ple; :h H-be-teken-when thi nurce i: tapped f0r dr - H g 4 er 4-igatier purpose: in areas where the hydraulic gradient er *echarge wer+ies are suitable for enotamination.-
7(h The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the 00CM.
(?d) If harvest occurs more than once a year, sampling s5all be performed g during each discrete harvest. If harvest occurs continuously, samoling l shall be monthly. Attention shall be paid to including samples of tuberous l
and root food products.
l
~
b pr%MW g ( 0 9 9 h M \.) d k M % (, Ak{ h gy WM d 4M MWva\s AcA W shel b4 butIp f t\ONC. Av Q pgo,.,Sgb W to6L m. m m\ht 1-
- In sm -
t I CALLAWAY - UNIT 1 3/4 12-8
r'"
INSERT 4 (9) Sampling and analysis to commence when food products grown in areas irrigated by Missouri River Water are identified by the Annual Land Use Census, conducted pursuant to Specification 3.12.2.
I ok TABLE 3.12-1, " Radiological Environmental Monitoring Progra
QP JUSTIFICATION:
(1) Changes to frequency verbage: We propose the following changes to the frequency notation in the interest of clarity:
weekly' - no more than 7 days monthly - no more than 31 days quarterly - no more than 92 days semi-annually - no more than 184 days semi-monthly - no more than 15 days (2) Deletion of Groundwater sampling requirements:
Section 5.2.2.1.1.1 of the Callaway Plant Environmental Report, Operating License Stage, states that, "Since routine plant releases will be discharged directly to the Missouri River by pipeline, there will be no impact on the local ground-water system (s) from this source". We, therefore,
,, propose to delete the Groundwater sampling requirements
- Y per Notation (8).
Q:
- i. (3) Change in the number of required Drinking Water Samples:
Section 5.2.4.1 of the Callaway Plant Environmental Report, Operating License State, states that: "No drinking water is drawn from the Missouri River within 50 miles downstream of the Callaway Plant discharge". We, therefore, propose to obtain Drinking Water samples from only one downstream location, which is at, or near, the water intake for the City of St. Louis, which, according to Section 11.2.3.3.3 of the Callaway Plant's FSAR, is the closest municipal user of Missouri River water downstream of the Callaway Plant, located approximately 78 river miles downstream of the Callaway Plant discharge.
(4) Change in the Drinking Water sample collection methodology:
Due to the relatively extreme distance (approximately 78 river miles downstream of the Callaway Plant discharge) of the nearest possible Drinking Water sampling locatien and, the extreme dilution of any liquid effluents, and with respect to the existing sampling equipment and the significant cost of establishing a continuous sampling station at this location, we propose to collect a single grab sample at s least each 31 days in order to fulfill the requirements of j the Technical Specifications.
>M!
O Page 1 of 4
g.. . ..
b vZ Ufy '
TABLE 3.12-1 (Continued)
(5) Deletion of Drinking Water I-131 analysis requirements:
Although no Drinking Water is drawn from the Missouri River within 50. miles of the plant' discharge, Section 5.2.4.1 of the Callaway Plant Environmental Report, Operating License State, states that for the hypothetical case of an individual who obtains his entire annual water requirement from the Missouri River 264 feet down-stream of the plant discharge, the maximum accumulated dose to a single organ would be 0.152 mrem / year to an infant's liver. This dose is much lower than the 1 mrem / year given as guidance, and would be reduced to a much lower dose at the nearest Drinking Water intake on the Missouri River.
Therefore, we propose that the requirement to perform I-131 analysis on Drinking Water be deleted from the Technical Specifications.
gg, (6) Elimination of the requirement regarding Milk Sampling
'1 -
Stations:
a, '
NN, Because of the lack of adequate milk sampling _ stations ,
. satisfying the specified criteria, it is proposed that milk sampling be deleted. Sampling and analysis of food products will be performed in lieu of milk sampling.
(7) Deletion of the sampling Invertebrates: NUREG-0133, Section 4.3.1, indicates that the consideration of invertebrates as being a significant contributor to the dose from liquid effluents, is not applicable to fresh water sites such as the Callaway Plant. We,'therefore, propose that this requirement be deleted from the Technical Specifications.
s e
b* : ,
t
'407O Page 2 of 4
l TABLE 3.12-1 (Continued)
(8) Deletion and modification of various Table 3.12-1 Notations:
- a. Notation 4: We propose to relocate this notation into the context of Table 3.12-1 as indicated, for the purposes of clarity and conciseness.
- b. Notation 6: We propose to modify this notation as indicated, auch that it is applicable to the site-specific location of the Callaway Plant.
- c. Notation 7: This notation was modified due to the impracticality of obtaining a composite comple, at the required sampling frequency, which is representative of the Missouri River flow during the sampling period.
The great variability in the flow of the Missouri River necessitates a constant volume aliquot over the sampling period. For example: The ten year high flow is 610,000 cfs, whereas the 7 day, 10 year low flow is
. 9,900 cfs (refer to Environmental Report, Operating License Stage Tables 2.4-5 and 2.4-6). Therefore, it is neither practical or reasonable to perform weighted composite sampling of this free flowing, highly variable river. The current composite samplers are designed as constant volume samplers and perform as indicated in the proposed text.
- d. Notation 8: We propose to delete this notation based on the deletion of the requirements to perform Ground Water sampling for the Callaway Plant (see 2, above).
- e. Addition of Footnote 9:
Section 5.2.4.1 of the Callaway Plant Environmental Report, Operating License Stage, states " Crop irrigation is not considered a potential pathway of liquid effluents to man.
This is because most water used for irrigation by local farmers comes from small streams in the vicinity rather than the Missouri River". Table 2.1-19 of the Callaway Flant Environmental Report, Operating License Stage further supports this statement, in that the closest downstream intake for irrigation water on the Missouri River is approximately 51 river miles from the plant's discharge.
Therefore, this pathway should be exempted froe ;ampling and analyses requirements until such time as the Annual Land Use Census identifies a location (s) which could be substantially affected by the plant's discharge.
Page 3 of 4
r-TABLE 3.12-1 (Continued)
(9) Deletion of requirement to perform Sediment from Shoreline sampling:
As stated in the Environmental Report, OLS, Section 2.1.3.5.2, "According to MDC (Missouri Department of Conservation), no public access points exist on the Missouri River downstream of the discitarge. The shore near the plant discharge is privately owned, and only boat anglers would generally be expected to fish near there". Section 2.1.3.4.2 further states, "These waters (within 50 miles of the plant discharge) are accessible to boat anglers, but public access along the shoreline is limited".
Owing mostly to this inaccessibility, there are no areas downstream of the discharge with existing or potential recreational value.
I We, therefore, propose that requirements to perform l sampling of Sediment from Shoreline be deleted.
(10) Deletion of the number of broad leaf vegetation samples:
Based on data collected to date in the conduct of vegetation sampling operations, it is unlikely that it will be possible to obtain three different kinds of broadleaf vegetation during various times of the year, owing to the relatively short growing season of many of the types grown in the general area.
Page 4 of 4
G3 N g./ '
f') 7l IAllLL 3.12-2 r
9 REPORTING LEVELS FOR RADIDAC11VITY CONCLHIRATIONS IN ENVIRONMENTAL SAMPLES Ec Q REPORTING LEVELS g WATER AIRBORNE PARTICULA 1E FISil MILK F000 PRODUCTS y ANALYSIS (pCi/t) OR GASES (pci/m3 ) (pti/kg, wet) (pCi/t) (pci/kg, wet) s .
ll-3 20,000*
Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000
, C0-60 300 10,000 s
[ Zr-C5 200 20,000 to E Zr-Nb-95 400**
l-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300**
*For drinking water samples. This is 40 CFR Part 141 value. I f r.: dr!r.him; unter ;:;i!=2y critte, a value of 30,000 pCI/t may be used. dfc sacf a c.c. wWA< samplu ,
Total activih 3 p2ntnt phasd8] M .
f r.
.t't
!)f TABLE 3.12-2, " Reporting Levels for Radioactivity Concentration in Environmental Samples" (1) Deletion of Zn-65: As identified in FSAR Section 4.5.1.1, only_ stainless steels, nickel-chromium-iron, and cobalt based alloys are used in the primary system. We propose, therefore, to delete Zn-65, as there is no zine to be activated.
(2) Change to footnote: The proposed modification provides clarification as to the reporting limits for non-drinking water samples.
(3) Addition of footnote: We propose the addition of this footnote in the interest of clarity.
s.- .
." I b 4 e.
j ..c4; b'
l AllLL 4.12-1 III r- DETECTION CAPABILITIES FOR ENVIR0llMLHIAL SAllPLE ANALYSIS L
h LOWER LIMIT Of DE[IECT1014 (LLD)(2),(3) g WATER AIRBORNE PARTICULATE FISit MILK FOOD PRODUCTS SEDlHENI q ANALYSIS (pCi/f) 3 OR GAS (pCl/m ) (pCi/kg, wet) (pCi/2) (pCi/kg, wet) (pCi/kg, dry)
I e
Gross Beta 4 0.01 11- 3 2000*
Hn-54 15 130 le-59 30 260 C0-58,60 15 130 m
o D Za C5 30 25^ l g
so
$ Zr-Nb-95 15t#
l-131 I I4) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 100 15 ti 15 N lla-La-140
- Ff n; ;!ri;d'ai; water pathway ex!;t;, a value of 3000 pCi/1 may be used.
dfor StAfStue Wa% Aqb y II Tota \ aci;y; , gay et p63 d kiV.
h; c.
TABLE 4.12-1 (Continued *,
TABLE NOTATIONS (1) This list does not mean that only these nuclides are to be considered.
Other peaks that are identifiable, together with those of the aeove {
l nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.5.
Rec.. mae add (2) h a i n d detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13, RM.i@l3191N.
(3) The LLD is defined, for purposes of these specifications, as the smallest concentration of redioactive material in a sample that will yield a net count, abcve system background, that will be detected with 95% probability l with only 5% probability of falsely concluding that a blank observation l represents a "real" signal.
For a particular measurement system, which may include radiochemical separation: i 4.66 s b E V 2.22 Y exp (-Aat) p Where:
~
j LLD = the "a priori" lower limit of detection (picoCuries per unit l mass or volume),
s b = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),
E = the counting efficiency (counts per disintegration),
V = the sample size (units of mass or volume),
2.22 = the number of disintegrations per minute per picocurie, i
Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (s 1), and at = the elapsed time between sample collection, or end of the sample collection period, and time of counting (s).
Typical values of E, V, Y, and at should be used in the calculation.
.dD e CALLAWAY - UNIT 1 3/4 12-11
f t
yp TABLE 4.12-1 (Continuec)
({y M
TABLE NOTATIONS (Continued 1 It should be recognized that the LLD is defined as an a oriori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit fur ~a particular measurement.
Analysts shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors shall be identified and cascribed in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.
F. , su<f=ut w = % - 5 W ' s (4) LLD for drinking water samples. If n; drinking eter p;thway ;xi;t:, the LLD of gamma isotopic analysis may be used.
( k,I4 :.
+6
- k .
CALLAWAY - UNIT 1 3/4 12-12
r TABLE 4.12-1, " Detection Capabilities for Environmental Samnle Analysis" JUSTlFICATION:
(1) Deletion of Zn-65: As identified in FSAR Section 4.5.1.1, only stainless steels, nickel-chromium-iron, and cobalt based alloys are used in the primary system. We propose, therefore, to delete Zn-65, as there is no zine to be activated.
(2) Change to footnote: The proposed modification provides clarification as to the LLD for H-3 for non-drinking water sampics.
(3) Addition of footnote: We propose the addition of the indicated footnote in the interest of clarity.
(4) Changes to Notation 2:
- a. We propose to substitute the word " recommended" for the word " required", to be consistent with the fact that it is not the intended purpose of Regulatory Guides to establish requirements, but instead to offer guidelines for meeting requirements. As stated in Reg. Guide 4.13. "the requirements and recommendations" of ANSI N545 are " generally r eceptable to the NRC staf f".
- b. Since Regulatory Guides art subject to revision, we propose to establish a braeline document which can then be used for obtaining gnidance in the development and operation of the Radiological Environmental Monitoring Program.
(5) Changes to Notation 4:
The proposed modification provides clarification as to the detection limits for non-drinking water samples, i
RADX0 LOGICAL ENVIRONMENTAL MONXTORXNG 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden
- of greater than 50 m2 (500 ft 2) producing broad leaf vegetation.
APPLICABILITY: At all times.
ACTION:
- a. With a Land Use Census identifying a Tocation(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, identify the new loca-tion (s) in the next gemiannual Rad pursuant to Specification 6.9.1.7.,ioactive Effluent Release Report,
- b. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) within 30 days to the Radiological Environmental Moni-toring Program given in the ODCM. The sampling loc. tion (s), excluding the control station location, having the lowest calculated dose or
- . dose commitment (s), via the same exposure pathway, may be deleted 7,c a from this monitoring program after (October 31) of the year in which
'@ ~
this Land Use Census was conducted. Pursuant to Specification 6.14, submit in.the next semiannual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and taole(s) for the 00CM reflecting the new location (s) with infor-mation supporting the change in sampling locations.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.
- Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.12-1, Part 4.c. shall be followed, including analysis of control samples.
Oh
'Qi CALLAWAY - UNIT 1 3/4 12-13
RADIOLOGICAL ENVIRONMENTAL MONITORING O
s 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials suppled as part of an Interlaboratory Comoarison Program that has been approved by the Commission.
APPLICABILITY: At all times.
ACTION:
- a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.12.3 The ! .tcrieborc.tcry C;mparison Progra ; shall ba d;s;ribed in th; OCCM A summary of the results obtained as part of the above required Interlaboratory Ccmparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.
O'
% Justification for Proposed Changes to Technical Specification 3/4.12.3,
- f. "Interlaboratory Comparison Program" D' 'i 4
- 1. Changes to Surveillance Requirement 4.12.3: We propose that the description of the Interlaboratory Comparison Program not be included in the ODCM, as the Callaway Plant contracts the analysis of environ-mental samples to third-party, independent laboratories. Therefore, the exact program is established by the independent laboratory, and although said program satisfies NRC requirements, it is not conducted under the auspices of the Union Electric Company and should thereby not be described in the ODCM.
i i u i
Mi
ADMINISTRATIVE CONTROLS Mi
'M ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 6.9.1.6. Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality. ,
I The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a compar-ison with preoperational studies, with operational controls and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of Land Use Censuses required by Specification 3.12.2.
The Annual Radiological Environmental Operating Reports shall include the results t of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations speci-fied in the Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.
In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for
,- the missing results. The missing data shall be submitted as soon as possible
., in a supplementary report. ,
The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps **
covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; ths results of licensee participation in the Interlaboratory Comparison Program and the corrective action being taken if the specified program is not being performed as required by Specification 3.12.3; reasons for not conducting the Radiological Environmental Monitoring Program as required by Specification 3.12.1 and discussion of all deviations from the sampling schadule of Table 3.12-1; discussion of environmental sample measure-ments that exceed the reporting levels of Table 3.12-2 but.are not the result of the plant affluents, pursuant to Specification 3.12.1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.
- ~
.. .g , ~ . . . :n -mm. -
,y - x ,
*; ~
*A single submittal may be made for a multiple unit station. "" ~
**0ne map shall cover stations near the site boundary; a second shall include the more distant stations. ,
s.
' l. . a:. )...
.G . .
CALLAWAY - UNIT 1 . 6-18 1
*c- 4[ '.. .i I Q [ - D '
, -l'Z(; C N.'Gg Ti7 .T.~Q ,'j I'f. % , ~ 79."~l~ **y g,P?'
r ADMfNISTRATIVE CONTROLS jY.N. : EMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
- 6.9.1.7 Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality.
The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating,
. and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional cate-gories: class of solid waste (as defined by 10 CFR Part 60), typ= of container (e.g., LSA, Type A, Type B, Large Quantity), and SOLIDICATION agent or absor' bent (e.g., cement, urea formaldehyde).
The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind
- ,- direction, atmospheric stability, and precipitation (if measured), or in the
- ( ("% form of joint frequency distributions of wind speed, wind direction, and g -7 atmospheric stability."" This same report shall include an assessment of the .
G radiati.on doses due to the radioactive liquid and gaseous. effluents released As RyuRM from the unit or station during the previous calendar year. This same report g y;Q shall also includefan assessment of the radiation doses from radioactive 1 liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figures 5.1-3 and 5.1-4) during the report period.
$. rtech'ez 3.11.L\
All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports. Th; .;;;t;; ;
10;;f r? r:diti=: = : = JJ;;0 rith th: tin Of ninn Of =dhrth: =t:rkh
" ;recer :"'ernte, = deu=in:d by : " g "meen y =d erurznt, e h!' be u: d #:r d:t: = h'n; th: ;= ==: p:th:y d= =. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
, u . .
The Radioactive Effluent Release Report to be submitted 60 days after January 1 p fqu's of each year shall also includekan assessment of radiation doses to the likely ggh mest exposed MEMBER OF THE PUBLIC from Reactor releases and other nearby uranium -
fuel cycle sources, including doses from primary effluent pathways and direct Dgl'g,*
radiation, for the previous calendar year-to show conformance with 40 CFR
%.11.4 Part 190, " Environmental Radiation Protection Standards for Nuclear Power
~
~; .g ,; .a
~.
*A single submittal may be made for a multiple unit station. The submittal
. should combine those sections that are common to all units at the station;
, however, for units with separate radwaste systems, the submittal shall specify L
the releases of radioactive material from each unit.
*n g e:E*In lieu of submission,' the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
CALLAWAY - UNIT 1 6-19;x p .
. . . . . 3 .
{ [ .~ ? 'I,
", * ~ i e *?/ n, l *
** b $lr ,
S . {. Y* ? ' ~ ' ' ' ~ ~ ' '
I SPECIFICATION 6.9.1.7 JUSTIFICATION: ,
(1) Technical Specification 3.11.1.2, 3.11.2.2 and 3.11.2.3 require a routine assessment of doses received at the SITE BOUNDARY or beyond. Only Technical Specification 3.11.4 requires the calculation of dose to a MEMBER OF THE PUBLIC from activities inside the SITE BOUNDARY. The proposed change relates the requirements for calculating and reporting the dose to a MEMBER OF THE PUBLIC from activities inside the SITE BOUNDARY to Specification 3.11.4 and its initiating conditions.
The suggested change provides consistency with surveillance requirements 4.11.4.1 and 4.11.4.2, and would require that dose assessments, performed to demonstrate compliance aith 40CFR190 limits, are reported in the Semi-annual Effluent Release Report.
(2) The requirement to calculate effluent dose and dose commitment utilizing meterological conditions concurrent with time of release was deleted pursuant to published NRC guidance in order to provide consistency with Specifications 3.11.2.2, 3.11.2.2, B3/4.11.2.2, B3/4.11.2.3, and 6.9.1.7.
Specifically:
(a) Specifications 3.11.2.2, 3.11.7.3, and 6.9.1.7 require that doses be calculated in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM). An examination of the bases for these Specifications reveals the methodology upon which the ODCM (and thus the calculation of offsite doses) is to be based.
Bases 3/4.11.2.2 states:
"The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmo-spheric conditions."
Bases 3/4.11.2.3 states:
"These equations also provide for determining
- the actual doses based upon the historical average atmospheric conditions."
(b) Regulatory Guide 1.11. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Ccoled Reactors", Revision 1 July 1977, states:
"If emiasions are continuous, annual data summaries should be used",
and:
"Use of annual average conditions for consideration of intermittent releases will be acceptable only if it is estab-lished that releases will be random in time. Otherwise the method of evalu-ation of intermittent releases should follow the methodology outlined in Section 2.3.4 of NUREG-75/087. This method uses an appropriate X/Q probability level, as well as the annual average X/Q ... for adjustments reflecting more adverse diffusion conditions than indicated by the annual average. These adjustments are applied to the annual average X/Q and D/Q for the total number of hours associated with intermittent releases per year." (Pages 1.111-13,14)
It further states:
"For calculation of doses through ingertion pathways, particularly through the cows-milk pathway, meterological data for only the grazing or growing season should be used." (Page 1.111-14)
Regulatory Guide 1.111, therefore, explicitly requires that historical X/Q and D/Q values be used to calculate doses from routine gaseous releases.
(c) NUREG 0800 (formerly issued as NUREG-75/087), " Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants", July 1981, states:
" Regulatory Guide 1.111 provides criteria for characterizing atmospheric transport and diffusion conditions for evaluating the consequences of routine releases." (Section II, page 2.3.5-2)
It specifically requires that: " Relative concentration (X/Q) and relative deposition (D/Q) values used for assessment of con-sequences of routine radioactive gas releases" be provided by the applicant in the Safety Analysis Report (SAR). (Section II, page 2.3.5-2)
NUREG 0800 therefore requires the utilization of historical X/Q and 0/Q values.
(d) Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977, consistently defines X/Q as:
"The annual average (gaseous, atmo-sphereie, etc.) dispersion factor".
(Equations 7, 9, B-4, B-7, C-3, others)
Regulatory Guide 1.109, therefore, clearly requires that annual average X/Q and D/Q values be used to calculate doses to individuals and populations. 1 (e) NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", October 1978, describes one of its purposes as:
"(This) manual additionally describes current staff positions on the method-ology for estimating radiation exposure due to the release of radioactive materials in effluents". (Section 1.1, Page 1)
With respect to the use of X/Q values, it states:
" Determination of doses due to long-term releases should use the historical annual average relative concentration (X/Q) based on meteorological data summarized, as recommended in Reg-ulatory Guide 1.111."
" Determination of doses due to short-term releases can use the annual average relative concentration (long-term) if it can be demonstrated that
, past short-term releases were sufficiently random in both time of day and duration ... to be represented by the annual average dispersion con-ditions. Otherweise, the short-term relative concentration value should be calculated in accordance with.the guidelines provided in NUREG-0324 for short-term release." (Section 3.3.,
Page 8)
Section 3.6, Page 9 describes the ODCM:
"The ODCM shall contain the methodology and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents pursuant to Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3, and the established limits of Specifications 3.11.1.1 and 3.11.2.1."
Sections 5.2.1 and 5.3.1 provide acceptable methodology for calculating offsite doses:
"The relationships presented ...
are acceptable for inclusion in the ODCM". (Pages 22 & 28)
These relationships define X/Q and D/Q values as:
"The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary",
and:
"The highest calculated annual avera e dispersion parameter for estimating the dose to an individual et the controlling location ...". (Section 5.2.1, Page 23)
Section 5.3.1 defines X/Q and D/Q as the highest cal-culated annual average (relative concentration, dis-persion parameter) for (long, short) term releases.
NUREG 0133, therefore, requires that annual average X/Q and D/Q values be utilized to determine offsite doses from gaseous effluents.
(f) Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Caseous Effluents from Light-Water-Cooled Nuclear Power Plants", Revision
- 1. June 1974, states:
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ J
i
" Dose calculations should be made using the measured effluent and meteorological data and acceptable dose models such as those provided in draft regulatory guides for implementation of numerical guides."
Although it would appear that this requires the use of concurrent meterological data in the calculation of dose estimates, two points should be noted:
(1) The " draft regulatory guides" referenced in Regulatory Guide 1.21 have subsequently been issued as Regulatory Guides 1.109 and Regulatory Guide 1.111, neither requiring the use ci concurrent X/Q and D/Q values, but historical values instead.
(2) Regulatory Guides 1.109 and 1.111 are referenced by and post-date Regulatory Guide 1.21, and therefore, provide clarification of its requirements.
(g) It is therefore apparant, that pursuant to published documents describing methods acceptable to the NRC staff (Regulatory Guide 1.21, Regulatory Guide 1.109, Regulatory Guide 1.111, NUREG 0133, and NUREG 0800),
and pursuant to Specifications 3.11.2.2, 3.11.2.3, B3/4.11.2.2, B3/4.11.2.3, and 6.9.1.7, that the use of historical X/Q and D/Q values is an acceptable and appropriate method for the calculation of offsite doses.
. lC .tk /
ADMINISTRATIVE CONTRDLS -- - - _./
- -- ~-
SEMIANNUAL RADIDACTIVE EFFLUENT-REPORT-(Continu(d)
Oceration." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1, October 1977. -
The Radinactive Effluent Release Reoorts shall include a ilst and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM and to the CDCM, pursuant to specification 6.13 and 6.-14, .respectively, as well as any major enange to Lioufd.. Gaseous, or Solid Radwaste Treatment Systems, pursuant to Specifica-tion 6.15. It shall also include a listing of new incations for dose calcula-tions and/oc_ environmental monitoring identified by the.. Land Use Cainsus pursua'nt to Specification 3.12.2.
The Radioactive Effluent Rel.' ease Reports shall also include the following information: An explanation as to why the inonerability of liouid or gaseous affluent monitoring instrumentation was not corrected within the time soecified in Specification 3.3.3.10 on 3.3.3.11, respectively; and description. of the events leading to linuid holdup tanks or gas storage tanks exceeding the
~L. " ' limits of Specification 3.11;1.4 or 3.11.2.5, respectively.
MONTHLY OPERATING REPORT
. 6. 9.1. 8 RoGtine reports of operating statistics and shutdown experience, including documentation of aill challenges to the pressurizar PORVs or RCS safety valves, shall be subm:itted on a monthly basis to the Director, Office of Resource Management U.S. Nuclear Regulatory Cummission. Washington. 0.C.
20555, with a copy to the NRC Regional Office, no later than the 15th of each conth following the calendar: month covered by the report.
MDIAL PEAKING FACTOR L1 HIT REPORT 4- -"- - --
_ _. . .-w _- . -=- -u --
~_. -6.9"1.5 the NRC The F{y. ltmits .for RAIED TilElatal..'PDWEll (h' Directo
~~ '
Regional Administrat6r:.with li copy to .the. _
L tegulation Attention: .
Chief,- Core Pe rformance Sr.anch, U.S.'. Nuclear Regulatory
, Commission, Washington.. D.C.; 20555 fc.- 411, core 9,3. ants.containing Bank "D" .
~
control rods and.all' unrodded core planes-and th't plot, of )erdicted (F;. pre 1I.
vs Axial-CFre-Height $with-th6-limit.envelone.at least-40 days prior to cycle--
initial criticality unless otherwise approved.by the Commission by letter. In addltion;.-in' the event.that!- the limit should. change.. requiring.a-new. submittal -
.(/~
- or,an amenced: submittal"to the reckli t g FactordLimittReport, it.shall be X suomitted SD days prioi to trie dste the ' limit.would become effective unless
\ othenvise acproved by the Codmission by letter. 2 Any information needed to support F'gp~ will be by reo,uest from the NRC.and need not be included in this report.
y -
CALIA.%Y - UNIT'1 6-20'
,s HIGH RA01AT10Ne AREA (Continu d) e h, otherwise following high radiation areas. plant radiation protection following: enter such areas shall be providedAny individual or group o
- a. with or accompanied by one or mv duals pereit ore of tha A radiation monitoring device whi
- b. radiation dose rate in the , orch area continuously indicates the A radiation monitoring device radiation dose dose rate in which is received. tha are continuously integrates e th may be made after Entry into such the dose rate l areas with this ma and alarms lished and personnel have bee c.
n made knowledgeable of themevels An individual qualified ina radi ti , or radiation dose rate monitoring de i providing positive control over v ce, th who is responsible foron pr and shall perform periodic radiatio 6.12.2 specified by Health Physicsemanag activities within the area ement personnel in the RWP.n sur accessible to personnel with radiatiIn addition to the requ 45 cm pecification 6.12.1, areas tion pe(netrates shall beon pr18 levelsin.) fromthan greater the 1000radiationmR/h source at Shift Supervisorentry, ovided and thewith keyslocked shall bedoors maintto i preventor from any su -
Doors shall rema/ Operating Supervisor on duty unauthorized and/oa ned under the a approved RWP in which locked shallexcept specifyduring th periods of rolhealth of the physics areas of the stayand time sthe maximum e dose allowable rate levels sta in the immediateaccess by .
circuit TV cameras)pecification y time of theforRWP, individuals direct in orthat area work -
in radiation protection proced continuous performedsurveillance may be made(suchbas closed-In lieu the activities being remote ures wi*,hinto theprovide area. positive exposure co ty personnel q For individual high radiation n rol over levels of greater than 1000 mR/h as PWR containment areas accessible to personnel with r di that individual areawhere that where no enclosurenoare located exists enclosure,can within for purp be rea ation large areas, such 6.13 light shall be activated shall as bea barricaded, wa rning device.
conspicuously ual area, pasonably osted, and a flashing 6.13.1 PROCESS CONTROL PROGRAM (PCP)
The r*P shall be approved by the C 6.13.2 a.
Licensee-initiated changes: to the PCPommission prior to implem Shall beRelease Effluent made.
submitted Report to the Commi for the p This submittal shall ssion ininwhich contain:
eriod the the semiannual change (s) was Radioactive M WAY - UNIT 1 6-23
- M%
9.--
m'** " . aim
-sem
ADMINTSTRATIVE CONTROLS
.f PROCESS CONTROL PROGPAM (PCP) (Continued)
- 1) Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information;
- 2) A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and
- 3) Documentation of the fact that the. change has been reviewed and found acceptable by the ORC.
- b. Shall become effective upon review and approval by the ORC and in accordance with Specification 6.5.3.1.
6.14 0FFSITE DOSE CALCULATION MANUAL (00CM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee-initiated changes to the ODCM:
- a. Shall be submitted ta the Commission in the semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain:
?R.
hb 1) Sufficiently detailed i'nformation to totally support the rationale for the change without benefit of additional or
. .-. supplemental information. Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered, dated and containing the revision number together with appropriate analyses or evaluations justifying the change (s);
- 2) A determination that the change will'not reduce the accuracy or reliability of dose calculations or setpoint determinations; and - ,
- 3) Documentation of the fact that the change has been reviewed and found acceptable by the ORC.., -
- b. Shall become effective upon review and approval by the CRC and in accordance with Specification 6.5.3.1.
.. .......i.,..-?.:.. . . .
. , . ,. ? ' ~ m - : . .4 .. 3 :- ,
, N'. ; .i p '4. C, , . ,U f,-f.'[ . .. , ,l-D. ,
- ;, -i? -
,r,. ,
' ' ~^
.~ %' ., .f.; y j. __
. u ;;;
- 3. .s
~
9 =
.-r. .
- 7. . {
~ '
- 1. .
~
V > -~y j -
CALLAWAY - UNIT 1~ 6-24
%.W
* ^ }W W:. Gl'*.n.R; ?:"" ?:.:+ - ~._,.2
, . ~ .g:].j Ws,..,,.s- Y-*,-&xg.-- 5-"7. ,, .~.~gg. . .:~s :y.a. - . - , ;.-m-~~. .
-- s
ADMINISTRATIVE CONTROLS
.My 1.
- fi . 6.15 MAJOR CHANGES TO LIOUID. GASEOUS. AND SCLID RADWASTE TREATMENT SYSTEMS
- 6.15.1 Licensee-initiated major changes to the Radwaste Treatment Systems (liquid, gaseous, and solid):
- a. Shall be reported to the Commission in the semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the ORC. The discussion of each change shall contain:
- 1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;
- 2) Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;
- 3) A detailed description of the equipment, components ano processes i nvolved and the interfaces with other plant systems;
- 4) An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the License application and amendments thereto;
- 5) An evaluation of the change, which shows the expected maximum
,G % exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and N' -
to the general population that differ from those previously estimated in the License application and amendments thereto;
~
- 6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the pe,riod prior to when the changes are to be made;
- 7) An estimate of the exposure to plant operating personnel as a result of the change; and . ,
- 8) Documentation of the fact that the change was reviewed and found
~-
acceptable by the ORC. '
- b. Shall become effective upon review and approval by the ORC and in accordance with Specification 6.5.3.1.
y
. .a .
. ~ ...;._; v s L-fx .. ;.; g
- Licensees may chose to submit the informat.fon called for in'this specification as part of the annual FSAR update. ...
s . , - i' :s..-
. /
<?
e CALLAWAY - UNIT 1 5-25
=p;;'~
GQ.n ."
=
, . Q .'Q .] ' Q _ nj,',. &" F~ 5:'_ .;.j. ; __ . q f -
- _ _ - __ - _.-. = - - - - - - -
INSTRUMENTATION BASES
$ Engineered Safety Features Actuation System Interlocks The Engineered Safety Features Actuation System interlocks perform the following functions:
P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater valves on T,yg bel w setpoint, prevents the opening of the main feedwater valves which were closed by a Safety Injection or High Steam Generator Water Level signal, allows Safety Injection block so that components can be reset or tripped.
Reactor not tripped prevents mancal block of Safety Injection.
P-11 On increasing pressure P-11 automatically reinstates Safety Injection actuation on low pressurizer pressure and low steam line pressure and autematically blocks steam line isolation on negative steam line pressure rate. On decreasing pressure, P-11 allows the manual block of Safety Injection one low pressurizer pressure and low steam line pressure and allows steam line isolation on negative steam line pressure rate to become active upon manual block of low steam line pressure SI.
3/4.3.3 MONITORING INSTRUMENTATION b ,
3/4.3.3.1 RADIATION' MONITORING FOR PLANT OPERATIONS The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that: (1) the associated action will be initiated when the radiation level monitored by each channel or combination thereof reaches its setpoint, (2) the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to permit a channel to be out of service for testing or maintenance. The radiation monitors for plant ooerations senses radiation levels in selected plant systems and locations and determines whether or not predetermined limits are being exceeded. If they are, the signals are combined into logic matrices sensitive to combinations indicative of various accidents and abnormal conditions. Once the required logic combination is completed, the system sends actuation signals to initiate alarms or automatic isolation action and acutation of Emergency Exhaust or Control Room Emergency Ventilation Systems.
3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY.of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the core. The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.
For the purpose of measuringq F (Z) or Fh a full ircore flux map is used.
Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in y recalibration of the Excore Neutron Flux Detection System, and full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Neutron Flux Channel is inoperable.
CALLAWAY - UNIT 1 B 3/4 3-3
INSTRUMENTATION BASES 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning cac Aility is available for the prompt detection of fires and that Fire Suppress, ion Systems, that are actuated by fire detectors, will discharge extinguishing agents in a timely manner. Prompt detection and suppression of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility Fire Protection Program.
Fire detectors that are used to actuate fire suppression systems represent a more critically important component of a facility's Fire Protection Program than detectors that are insta11ea solely for early fire warning and notification. Consequently, the minimum number of OPERABLE fire detectors must be greater.
The loss of detection capability for fire suppression systems, actuated by fire detectors, represents a significant aegradation of fire protection for any area. As a result, the establishment of a fire watch patrol must be initiated at an earlier stage than would be warranted for the loss of detectors that provide only early fire warning. The establishment of frequent fire patrols in the affected areas is required to provide detection capsbility until the inoperable instrumentation is restored to OPERABILITY.
3/4.3.3.9 LOOSE-PART DETECTION INSTRUMENTATION The OPERABILITY of the loose part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the Reactor Coolant System and avoid or mitigate damage to Reactor Coolant System components. The allowable out-of-service times and Surveillance Requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981. MWdbOM 3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONIT ING INSTPUMENTATL The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm /
, Trip Setpoints for these instruments shall bencalculated :.d :dj = ted in accordance with the methodology and parameters in the 00CM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. % e--
pr;m ef teak ie.el indieeting deviees is te ees re the deteetier. end eentrol
' # C'W
~ b....Nf .m N. ..'b....a
_'~'"U9i'NS
- o. onns, . nm m15$d3".1N.
n-n . E53ib' 'E IA CALLAWAY - UNIT 1 B 3/4 3-5
J l
4
; BASES B3/4.3.3.10 JUSTIFICATION:
Tables 3.3-12 and 4.3-12 do not include any tank level indicating device. This statement is, there-fore, not applicable.
The bases has been modified to clarify the requirement for adjustment of setpoints.
i-1 f
I l-l L.
l
INSTRUMENTATION BASES
,3djusted to um\ue' 3/4.3.3.11 RAPI0 ACTIVE GASEOUS EFFLUENT MONI"0 RING INSTRUMENTATION The radioactive gaseous effluent instrumantation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm /
Trip Setpoints for these instruments shall be3 calculated - " "'"-' ' in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERA 8ILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The sensitivity of any noble gas activity monitor used to show compliance with the gaseous effluent release requirements of Specifica-tion 3.11.2.2 shall be such that concentrations as low as 1 x 10.s pCi/cc are meacurable. 7 3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could gaaerate potentially damaging missiles which could impact and damage safety-related ccmponents, equipment, or structures.
CALLAWAY - UNIT 1 8 3/4 3-6
BASES B3/4.3.3.11 JUSTIFICATION.
(1) The bases has baen modified to clarify the requirement for adjustment of setpoints.
t
- 4. >
0
3/4.11 RADI0 ACTIVE EFFLUENTS (p'yz o
BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioactive materials released in liquid wasta effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appen-dix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS
$ will result in exposures within: (1) the Section II.A design objectives of Appen-
.'" dix I, 10 CFR Part 50, gto ... . .., .. .... .. .., and (2) the limits of 10 CFR Part 20.106(e) to the population. The concentration limit for dissolved or H entrained noble gases is based upon the assumption that xe-135 is the control-c ling radioisotope and its MPC in air (submersion) was converted to an equivalent
<5 concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
vut. ....,,,_..: _ ...,,.. .. .u. ..,.... .,..a4..,+4e. ..+. 4,,,
' ~ ~ ' '
4.
,, . . o. L. . . . E..". . ;. _. ' '.,'. ." '.' ' ' , F...E. . C. . . ". .'.'C.
,., ._ y. . . . . .'. 7 2. . " ~ ' ' ' ' ' ' ' ' ' ' ' ~ '
b The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A. , " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," A_nal. Chem. 40, 586-93 (1968), and Hartwell, J. K. , " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
3/4.11.1.2 DOSE This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II. A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appen-dix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for . fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished .
drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in the 00CM implement the require-
_d ments in Section III.A of Appendix I that conformance with the guides of
,_ j Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of'c "E""E" Of T"E """.LIC through appropriate pathways bfc74 is unlikely to be substantiS11y underestimated. The equations specified in the H 00CM for calculating the doses due to the actual release rates of radioactive g materials in liquid effluents are consistent with the methodology provided in o
CALLAWAY - UNIT 1 B 3/4 11-1 l
l L
. l'
' M BASES B3/4.ll.1.1 JUSTIFICATION (1) The term " MEMBER OF THE PUBLIC" has been replaced with the term
" Individual" in that:
(a) 10CFR20 and 10Crn50, Appendix I, require that Radioactive Effluent Concentrations, Doses and. Dose Rates be calculated for Individuals at or beyond the SITE BOUNDARY and/or in UNRESTRICTED AREAS. These regulations neither expressly or implicitly require that these calculations be performed for persons, real or imaginary, who may occupy areas within the SITE BOUNDARY for some fraction of the time.
(b) The use of the term " MEMBER OF THE PUBLIC" as defined in Specification 1.16, is inconsistent with the requirements of the Specification that concentrations be calculated for UNRESTRICTED AREAS.- Therefore, its use would cause the Specification to be internally inconsistent.
fr- (c) As stated in the bases, the purpose of this Specification k, is to provide for compliance with 10CFR20 and 10CFR50, Appendix jf ' I, limits. The use of " MEMBER OF THE PUBLIC" is inconsisten,t with the. stated purpose of this Specification.
(.{
(d) 10CFR50, Appendix I, states: " ... shall be demonstrated by calculational procedures based upon models and data such that the actual exposure of an individual through appropriate
' pathways is unlikely to be substantially underestimated ...".
Therefore, the uise of the term " MEMBER OF THE PUBLIC" is inconsistaat with the expressed purpose of the Specification and requires inconsistency on the part of the Licensee in complying with the Specification.,_ Additionally, there are no legal requirements for its
- - use in7his specif1. cation. -
Thus, the use of the term " MEMBER OF THE PUBLIC", while appropriate for specifications implementing 40CFR190 requirements, is inappropriate -
in this Specification, and should be deleted in favor of the term-
" Individual" (2) The SNUPPS Plants are single reactor unit sites, therefore, this. -
statement is not applicable.
.s .
4
I l
l- l J; .7 e( BASES 3/4.11.1.2 I
JUSTIFICATION (1) The term " MEMBER OF THE PUBLIC" has been replaced with the term
" Individual" in that:
(a) 10CFR20 and 10CFR50, Appendix I, require that Radioactive Effluent Concentrations Duses and Dose Rates be calculated for Individuals at or beyond the SITE BOUNDARY and/or in UNRESTRICTED AREAS. These regulations neither expressly or implicitly require that these calculations be performed for persons, real or imaginary, who may occupy areas within the SITE BOUNDARY for some fraction of the time.
(b) The use of the term " MEMBER OF THE PUBLIC" as defined in Specification 1.16, is inconsistent with the requirements of the Specification that doses be calculated for UNRESTRICTED AREAS. Therefore, its use would cause the Specification to be internally inconsistent.
f~ , (c) As stated in the bases, the purpose of this Specification g is to provide for compliance with 10CFR20 and 10CFR50, Appendix pc> I, limits. The use of " MEMBER OF THE PUBLIC" is inconsistent
( vith the stated purpose of this Specification.
(d) 10CFR50, Appendix I, states: "... shall be demonstrated by calculational procedures based upon models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially un'derestimated ...".
Therefore, the use of the term " MEMBER OF THE PUBLIC" is inconsistant with the expressed purpose of the Specification and requires inconsistency on the,part of the Licensee in complying with the
~
Spec ~ification. _ Additionally, there are no legal requirements for its
.r -use in this specification.
~
Thus,- the use of the terni " MEMBER OF THE PUBLIC", while appropriate lor-specifications implementing,40CFR190 requirements, is inappropriate in._.this Specification, and should be deleted in favor of the term
" Individual". .
- ~
. (2) Since the SNUPPS Plants are single reactor unit sites, and consequenitly
- .have no shared radwaste treatment systems, this paragraph is not applicable.
Q -- -
~
^
e e
l l
i
(?.y RADIOACTIVE EFFLUENTS Li ' BASES .
l t_- !
i DOSE (Continued) i Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113,
" Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
T'i: :pe f'fe: tier :ppife: t: 4a 3 4.v . . 4. a.... ., ., ., .. .. ..... . ..._ .._,....u. the relette
.,.. e'_redferet9fe um_ ..a -aterfe!
_ _...._ _v..._.._
..__.u.
._ .u...... _ _ _e._2 ,.....
e.,...___ . . . . . . . .... . .-.. ___..;u,.. __
.m..__.
.. . . . . . .............,..m..
..a. .....___.. u.,m .. .. ... .a.. _ 4. _. 4. . . . , . .u. ..3........... ..__ . . . . . . .+
._ 4. . ._ a_ <. m.
. . ... .. .u. . . . . _ _ . . . , . . . .. . _ _ . . . . _ . , , . __ _ .
+ . 3. ,m w._
._ _ .. 46 a...
.. .,... .,,4.
.m_,.
. . . . . .a. ,
. . _ . . . .. _ u.._ 3. 2 u. __2.-
. . . . .. .. . u.
+.46m.4...
.,+4m4... ... .....
,___ ...u 4.__
.._4.
.u....
...a
,__... ___2,.,___
,__m,_ .<_
m-
__2 __2,__
..m
__g
- u. _33.....a....,,,,
. . . _ . . . u - , c. u. . ._.a_a... 4m.._. m.... __a..4.. ..4..
, _ _ . . , . _ _ _ . . .. .. . . ..__." " - - - " r --- ' "a - - - - ' -
chcr'n; th:..<.., 9:d:::::,___'r::tr:r.t .u. "y:t: .
o.2.....
":r d:t:r:f 'n; :: ':r :::: t: LCO:,
..___. e.. .___ .. u. .22.2 .. .u.
+u. ...___ _.33.. .....a_
..i..... ...
r-"'
4,4..,,m .. . . _4 u . . . .a ..
...u
.g.......
.u. 4. .u.
" ' ' " - " - " ' ' " ' " " " " " r"'
-w44, lPb 3/4.11.1.3 LIQUID RA0 WASTE TREATMENT SYSTEM f
The OPERABILITY of the Liquid Radwaste Treatment System ensures that this ,
{"$*3 system will be available for' use whenever liquid effluents require treatment j prior to release to the environmer.t. The requirement that the appropriate l portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.0 of Appendix I to 10 CFR Part 50.
The specified limits govening the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
,us. _.,.... .,
.. . , . . . . . . . . . . . . .,,.. .. ..... .u.
. . . ....... .. ... .-. .... - _ . . . . 2 s. . . . . z . . . _... 4._.,. ._
4.
,,..,J _ ,,,..__._ ,___ ___L . . _ , . .. .k_ _,._ Um__ __J n_2..... v_ ..___.
.y.. .. . . . . . . . .,. . . . . . . . . . . .. . . . . .... . . . . . . _u.
Sy:ter: tre ::d 53 ::r: th:n :n: un't :n : :it:, th: a::t:: 'r:: :1' un't:
... :..a ... .u_2
.....___ . u. ..._u
.u. . , , , . . . . _ ,..... ..___.
. , + w.
. . . . . . . . . , u. ____,u_2 ._ ____,,,_ . :. ._ _.,_... .u m,a u. ..a.
___.....,m .. .... .... .. . .,...... . . . . . m,. ... .. ...... .. ---- .. ....
Centributfen: 'r:: :::P unit 5:::d Or 'nput ::nditten:, e.g., #1:e rate trd
. . a. z. . . . 4. m. 4. . ,. . ............,___
. . . . . __.. r..........: .u,., ...u.. ......a..,,,...... _ _ . . .
reler::: ::; 5: :ll:::ted : ::11y t: :::h :" th: r:dt:::tf": er te produrf ;
v.. . . . . . . . .e,...._
._ .u..<_. .u. o 2.__._ _ ..___. e. 2. __4.<_.
..4.. . . . . . . . . . . , . . . . .. . .... ... . . . . ... . - . .. , . . . . . . . _ . . _ , --
LCO , th::: :11:::ti:n: 'r.r. :hcred .9:ta :t: Tr::t::nt Sy:t :: cre te 5: dded
.. .u. ..,. ___ _ _ _ _ , , , _ _ , , . _._,u..._2 .. ___m . _1. .. _u..,_ .u. ...., ..,.....
L" 3/4.11.1.4 LIQUID HOLOUp TANKS L
di' The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.
CALLAWAY - UNIT 1 B 3/4 11-2
lt L, ,11 N;;>
BASES 3/4.11.1.3 JUSTIFICATION Since the SNUPPS Plants are single reactor unit sites, and consequently have no shared radwaste treatment systems, this
_ paragraph is not applicable.
= .;
1 ',
e.
l-
*t
? \
A ym O
e lIS[ish Q,;F
1 RADIOACTIVE EFFLUENTS BASES 7
LIQUID HOLDUP TANKS (Continued)
, Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous affluents will not aq l result in the exposure ofk: ""."."5", OF T": FU"LIO in an UNRESTRICTED AREA, gfg l Oith:r eith' :r outside the SITE BOUNDARY, to annual average concentrations l % exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 s (10 CFR 20.106(b)). Fori" "";"4 Or m; "=LK who may at times ce winnin 3dMdWd3 the SITE BOUNDARY, the occupancy or tnati"[Z:" 07 TllC ICOLIC will usually be k' # ] sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. " - - - ' - - ' - ' " " ' - - ' - - "
! "C"" "i ^i "iE I""LIC, with th; ;ppr;;rict: ::::p::c., f::t:rt, :hal' he give" Trdvdua) i- th: 0^0". The specified release rate limits restrict, at all times, the ovi .
l corresponding gamma and beta dose rates above background toka-NEMB&445.JME. __TWidul .L
-P6EL4C- at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the whole body or to less than or equal to 3000 arems/ year to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/ year.
Thi: :p ffi:: tion :ppli:: t the rele::: ef r:di:::tiv: :teria! 4"
;!!:::: ##12:nt: #rt: : P it: It th: :it:.
The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A. , " Limits for Qualitative Detection and Quantitative Determination - Application to Radio-chemistry," Anal. Chem. 40,~586-93 (1968), and'Hartwell, J. K.,." Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
l p- 3/4.11.2.2 DOSE - NOBLE GASES I
hv This specification is provided to implement the requirements of Sections II.8, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting CALLAWAY - UNIT 1 B 3/4 11-3 l
[5%
. { D' 1
(' .,
BASES 3/4.11.2.1 JUSTIFICATION (1) The term " MEMBER OF THE PUBLIC" has been replaced with the term
" Individual" in that:
(a) 10CFR20 and 10CFR50, Appendix I, require that Radioactive Effluent. Concentrations, Doses and Dose Ratec be calculatad for Individuals at or beyond the SITE BOUNDARY and/or in UNRESTRICTED AREAS. These regdlations neither expressly or implicitly require that these calculations be performed for persons, real or imaginary, who may occupy areas within the SITE BOUNDARY for some fraction of the time.
(b) The use of the term " MEMBER OF THE PUBLIC" as defined in Specification 1.16, is inconsistent with the requirements of the Specificati 7 that doses be calculated at the SITE BOUNDARY. Therefore, its use would cause the Specification to be internally inconsistent.
x
. - .0 (c) As stated in the bases, the purpose of this Specification I .' is to provide,for compliance with 10CFR20 and 10CFR50, Appendix I, limits. The use of " MEMBER OF THE PUBLIC" is inconsistent 4
@D with the stated purpose of this Specification.
(d) 10CFR50, ..ppendix I, states: "... shall be demonstrated by calculational procedures based upon models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated ...".
Therefore, the use of the term " MEMBER OF THE PUBLIC" is inconsistent with the expressed purpose of the Specification and requires inconsistency on the part of the Licensee in complying with the Specification.~ Additionally, there are no. legal requirements for-its
~~ -
use in this specification.
~
Thus,~ the use of the term " MEMBER OF THE PUBLIC", while appropriate--
-~ ~~
for specifications implementing 40CFR190 requirements, is inappropriate in this Specification, and_should be deleted in favor of the term ~
" Individual".~-- --
( (2) As defined in NUREG 0133 (October 1978) and in Technical Specification
% Definition -1.17, the'ODCM is intended to provide the methodology and k^
'"~
parameters ' utilized to perform off-site dose calculations, gaseous and 4 liquid ~ effluent monitor setpoint determinations, and a' description of the d . Environmental Radiological Monitroing Program. The proposed deletion is to ensure that the ODCM remains within its intended scope and does not become a~ forum for justifications and example calculations.
l (3) The SNUPPS Plants are single reactor unit sites, therefore, this statement is not applicable.
, . , .ADICACTIVE EF:LUENTS 3ASES DCSE - NCELE GASES (Continued)
Condition for Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the recuired operating flexicility and at the same time imolement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will ce kept "as low as is reasonably achievaole." The Sur-vei' lance Requirements implement the requirements in Section III.A of Accencix I tnat conformance with the guides of Appendix I be snown by calculational proce-cures based on models and cata such that the actual exposuref of : ":"::: OF T.: 'U:LI: through appropriate pathways is unlikely to be substantially uncer-MpgM estimated. The cose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine hiecses of Reactor Effluents for the Purpose of Evaluating Comoliance with 10 CFR Part 50, Appenaix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methocs for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977.
The CDCM ecuations provided for determining the air doses at and beyond the SITE SOUNCARY are based upon the historical average atmospheric conditions.
inis speca rication appaies to tne release o* racloactive materials in gaseo fluents from each unit at the site. When shared Radwaste .c. ment w Systems are u. d v more than one unit on a site, tne waste # ... all units are.
cixed for shared tres.. t- by such mixing, the effl' . releases cannot accur-ately be ascribed to a speci ~ nit. An est' . shouldbemadeofthecontril-butions from each unit based on inp . ~ tions, e.g., flow rates and radio-3ctivity concentrations, or, i e practico the treated effluent releases may oe allocated equall each of the radioactive "e producing units shari ng the Racwaste Tr *
.. nt System. For determining conformanc / CDs, these allc-cations # . shared Radwaste Treatment Systems are to be adaed to w. eleases
<* . 1cally attributed to each unit to obtain the total rela = <ps ser un, _
an& M 3/4.11.2.3 00SE - IODINE-131 TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM I' This specification is provided to implement the requirements of SectionsII.C,III.AandIV.AofAppendixI,10CFRPartg0. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.
The ACTION statements provide the required operating flexibility and at tne same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The 00CM calculational metnocs specified in the Surveillance Requirements implement the requirements in Sec. ion III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the g actual exposure of': ":"::2 07 'M: 'UCLIC through appropriate pathways is unlikelytobesubStantiallyunderestimated. The 00CM calculational metnoc- ggJ
{; ology anc parameters for calculating the doses due to the actual release rates p of the subject materials are consistent with the metnccology provided in Regula-G tory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance wi.tn 10 CFR Dart 50, 1
CALLAWAY - UNIT 1 S 3/2 11-a
I p ?? ,
Ik ?
. p .. ' !
BASES 3/4.11.2.2 JUSTIFICATION (1) The term " MEMBER OF THE PUBLIC" has been replaced with the term
" Individual" in that:
(a) 10CFR20 and 10CFR50, Appendix I, require that Radioactive Effluent Concentrations, Doses and Dose Rates be calculated for Individuals at or beyond the SITE BOUNDARY and/or in UNRESTRICTED AREAS. These regulations neither expressly or implicitly require that these calculations be performed for persons, real or imaginary, who may occupy areas within the SITE BOUNDARY for some fraction of the time.
(b) The use of the term " MEMBER OF THE PUBLIC" as defined in Specification 1.16, is inconsistent with the requirements of the Specification that doses be calculated at the SITE BOUNDARY. Therefore, its use would cause the Specification to be internally inconsistent.
H (c) As stated in the bases, the purpose of this Specification e is to provide for compliance with 10C'FR20 and 10CFR50, Appendix iO I, limits. The use of " MEMBER- OF THE PUBLIC" is inconsistent
- with the stated purpose of this Specification.
(d) 10CFR50, Appendix I, states: "... shall be demonstrated by calculational procedures based upon models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated ...".
Therefore, the use of the term " MEMBER.0F THE PUBLIC" is inconsistent with the expressed purpose of the Specification and requires inconsistency on the part of the Licensee in complying with the Specification. Additionallys there'are no legal' requirements for its
. use in this specification 7
' ~
Thus, th'e use of' the term " MEMBER OF THE PUBLIC", while appropriate for-specification.s implementing 40CFR190 requirements, is inappropriate in this. Specification, and should be deleted in favor of the term
" Individual".
-(2) NUREG 0133 provides for the use of annual average (historical) 7( atmospher'ic data in the calculation of offsite doses, whereas
#4 Regulatory Guide 1.111 provides 'for the use of hourly measured (real time) values. The bases has'therefore been modifed to (C? reflect the acceptability of either method.
(3) Since the SNUPPS Plants are single reactor unit sites, and consequently have no shared radwaste treatment systems, this paragraph is not applicable.
s
UDI0 ACTIVE EF:LUENTS fU' EASES e6L M "
COSE - IODINE-1311. TRITIUM, AND RADI0 ACTIVE MATERIAL IN FAR ICULATE FORClContinued) -
i Appendix I," Revision 1, Octcber 1977 and Regulatory Guide 1.111, " Methods for -
Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine -
Releases frca Light-Water-Cooled Reactors," Revision 1, July 1977. These equa-tions also previce for determining the actual doses based upon the historical average attescheric ccnditions. The release rate specifications for Iodine-131 and 133, tritiuc, anc racioactive material in particulate form witn half-lives greater tnan 3 cays are cependent upon the existing radionuclice pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual inhala-tion of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with sucsequent exposure of man.
Thi; ;p+;i' ice;ica epc, lie; t; .he celca;e ;f radic;;ti s; .ct:rici; ir gasev
'fluents from each reactor unit at the site. When shared Radw '
Treatment y~ are used by more than one unit on a site, the .. s from all units are mixec shared treatment; by such mixin '
effluent releases cannot accurately be ascr1 a specific unit. estimate should be made L
of the contributions from each un1. ed ,put conditions, e. g. , flow rates and radioactivity concentrations, . . racticaole, the treated effluent releases may be allocated e ' y to eacn of the i active waste producing units sharing the R- . e Treatment System. For ceterm -
conformance to LCOs, these = ations from shared Radwaste Treatment Systems . o be acded to th eases specifically attributed to each unit to obtain the tot. - leaseo
;.. ; nit.
3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment priort o release to the environment. The a requirement that the appropriatt: portions of / these systems be used, when specified, provides reasonable assurance that tha releases of radioactive materials in gaseous effluents will be kept "as iow as is reasonably achievable".
This specification imolements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.0 of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a
' suitaole fraction of the dose design objectives set fortn in Sections II.B and II.C of Appendix I,10 CFR Part 50, for gaseous effluents.
s specification applies to the release of radioactive materia '
gaseous e om each unit at the site. When share we Treatment Systems are used by more . e unit on a s .. wastes from all units are mixed for shared treatment; by su the effluent reienes cannot accur-p' ately be ascribed to a .:..c unit.
An estima 'd be made of the contri-l Dutions fro unit based on input conditions, e.g., ficw . 2nd radio-
[c r** - y cnncontratienc or- if nnt -rac-icain -5, ~on>ad -d'inant -o.
CALLAWAY - UNIT 1 3 3/4 11-5
1(.
BASES 3/4.11.2.3 JUSTIFICATION (1) The term " MEMBER OF THE PUBLIC" has been replaced with the term
" Individual" in that:
(a) 10CFR20 and 10CFR50, Appendix I, require that Radioactive Effluent Concentrations, Doses and Dose Rates 'ue calculated for Individuals at or beyond the SITE BOUNDARY and/or in UNRESTRICTED AREAS. These regulations neither expressly or implicitly require that these calculations be performed for persons, real or imaginary, who may occupy areas within the SITE BOUNDARY for some fraction of the time. ,
(b) The use of the term '1HEHBER OF THE PUBLIC" as defined in Specification 1.16, is inconsistent with the requirements of the Specification that doses be calculated at the SITE BOUNDARY. Therefore, its use would cause the Specification to be internally inconsistent.
(c) As stated in the bases, the purpose of this Specification is to provide for compliance wit.h 10CFR20 and 10CFR50, Appendix 0 I, limits. . The use of " MEMBER OF THE PUBLIC" is inconsistent b with the stated purpose ~ of this Specification.
(d) 10CFR50, Appendix I, states: "... shall be demonstrated by calculational procedures based upon models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated ...".
Therefore, the'use of the term " MEMBER OF THE PUBLIC" is inconsistent with the expressed purpose of the Specification and requires inconsistency on the part of the Licensee in complying with the Specification. Additionally, there are no legal requirements for its
~~
use in this-specification.
Thus, the use of,the ~ term " MEMBER-O'F THE PUBLIC", while appropriate
~
~
for specifications implementing 40CFR190 requirements, is inappropriate in.this Specification, and should be deleted in favor of the term
" Individual".
(2) Since the SNUPPS Plants are single reactor. unit sites, and consequently o, have no shared radwaste treatment systems, this paragraph is not applicable.
h p:. _
L (M.
(?, .,a.
- l 3;;i -
e B3/4.11.2.4 JUSTIFICATION Since the SNUPPS Plants are single reactor unit sites and consequently have no shared radwaste treatment systems, this paragraph is not
. applicable.
5'
((_ -
..a e
b s ,. a e'
Q?l
^
9 RADI0 ACTIVE EFFLUENTS I' .
BASES e
GASEOUS RA0 WASTE TREATMENT SYSTEM (Continued) may b; : lice:t:d :qurily t: ;;;h of th: radi;;;tive anst: producing units sharing the Reca:st; Tr::t;;nt Syst: . Ter dete;;;ining ;;nfors:n:: t: LOC:, th::: all:-
cations frea shared Red aste Treat..ent Systems are te be added to the releases
- p::ific lly :ttribtted t: ;;;h unit te obtain the total releases per unit.
3/4.11.2.5 EXPLOSIVE GAS MIXTURE g g %% h This specification is provided to ensure that the concentr tion of potentially explosive gas mixtures contained in the waste gas h 1 dup system is maintainedbelowtheflammabilitylimitsofihydrogenandoxyge (Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. These automatic control features include isolation of the source of hydrogen and/or oxygen,f) cut;::ti:
diver:ica t; r;;;;biner:, or injecti;n of dilatants to reduce the concentration belew the fim.cbility limits.)- Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
3/4.11.2.6 GAS STORAGE TANKS fy)Q-{~ g k5 -TN. tanks included in this specification.are th;;; tanks for which th; quantity of radicactivity centained is not limited directly or indirectly by = the T chnicci Sp;;ification t; a quantity that is i;s: than th qu n-tity that pr;vides assurance that in the e, nt of en wuce.d.. wiled celease of the t:nt:' ::nt:nt: th: r::uitin; _h:1: b;d3 cxp = r; t;,,; ":""E" 0F T": PU"LIC at the nearest SIT: 000NOA"Y iil net .xceed 0.0 rea, che annual d;se limit in 10 CFi Pu t 20.
ExcW si.
M ea. Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the ON tank's contents, the re lting whole body exposure to "E"SER OF THE PUSLN M td. h at the T::r::t !!TE B ARYwillnotexceed0.5 rem.(:Thisisconsistentwith Standard Review Plan .3, Branch Technical Position ETSB 11-5, " Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure," in NUREG-0800, aqi Tow)k. July 1981,,dtAf(M ESAC QC@dvd ono)% Q g M,k @c, W 3/4.11. SOLID RADWASTE TREATMENT SYSTEM ,
This specification implements the requirements of 10 CFR 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste / liquid / SOLIDIFICATION agent /
catalyst ratios, waste oil content, waste principal chemical constituents, and n.ixing and curing times.
,n : i y.
CALLAWAY - UNIT 1 B 3/4 11-6
3-
- ,-s, INSERT G fj This specification considers postulated. radioactive releases due to a waste gas system leak or failure, and limits the quantity of radioactivity' contained in each' pressurized gas storage tank in the WASTE GAS HOLDUP SYSTEM to assure that in the event of a-release of the tank's contents, the resulting whole bcdy exposure to an Individual at the nearest Exclusion Area Boundary will not exceed 0.5 rem, the annual limit in 10CFR Part 20.
9 M$--
2
}
I
,J.
,p,yy
. . f h; 1::*, :4 DN
l k
$.ff
- fN
. $ r:.p;1t B3/4.11.2.5 JUSTIFICATION Since Specification 3.11.2.5 does not require automatic control features on the Waste Gas Hold Up Systeni, the indicated portion was deleted as not applicable, a
f:l,e! .
f.
*!I
%25' s
e
+
e
*e 59 q.
BASES 3/4.11.2.6 .
JUSTIFICATION:
(1) The term " MEMBER OF THE PUBLIC" has been deleted in favor of the term " Individual" to provide consistency with NLREG 0133 and 10CFR100.
(2) The FSAR accident analysis for a Waste Gas Decay Tank failure. conducted in compliance with guidance given by Regulatory Guide 1.24, was utilized to a great extent in the development of this specification, and should, therefore, be part of its Bases.
(3) The deleted portion of the Bases as written, could be interpreted to apply to any tank containing radioactivity in gaseous form, thereby necessitating unwarranted and unrealistic sampling and analysis of those tanks. The primary intent of Specification 3.11.26, as noted in NuReg 0133, Section 5.6.1 and NuReg 0472 is to limit radioactive material in gas storage tanks of the Waste Gas Holdup System to a level such that in the event of rupture or leakage of the tank the resulting off-site dose consequence would not exceed 0.5 Rem total body.
Alternate wording has been proposed to clarify that the specification is applicable to Waste Gas Holdup System Storage Tanks.
RADIOACTIVE EFFLUENTS' ;
O h2 BASES -
3/4.11.4 TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and the radia-tion from uranium fuel cycle sources exceed 25 areas to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 areas. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and from outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 Timits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR y
Part 190, the Special Report with a request for a variance (provided the W release conditions resulting in violation of 40 CFR Part 190 have not already Wd been corrected), in :ccordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of
, 40 CFR Part 190 until NRC staff action is completed. The variance only relates i
to the limits of 40 CFR Part 190, and does not apply in any way to the other l requirements for dose limitation of 10 CFR Part 20, as addressed in Specifica-tions 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any opera-tion that is part of the nuclear fuel cycle.
1 l
r*y a
CALLAWAY - UNIT 1 B 3/4 11-7
=
(
l _ . _ . _ , _ _ , , ._ . _ _ _ . _ _ _ _ . _ _ _ _ _ . - . _ . - _ , . . . . . , _ , . . . . . - . _ . _ . . _ . - . _ _ - . , _ . .
i 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING (n.
f.b 4 l
; BASES
, 3/4.12.1 MONITORING PROGRAM c-
{
E The Radiological Environmental Monitoring Program required by this specification provides representative measurements of radiation and of radio-g active materials in those exposure pathways and for those radionuclides that
%, lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC
,Q resulting from the station operation. This monitoring program implements f Section IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable i
1 2$ concentrations of radioactive materials and levels of radiation are not higher
""E.
than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is 9Fi provided by the Radiological Assessment Branch Technical Position on Environ-j>
qg7 mental f et 'Monitoring
- t the (' ret ? y r:-The '-itic'l; Of ::- :rti:1 :;::i'i; dr:::rit:r'n; tier -F pr:gr::
er _i
i 5: Offect!'?:
; thi!
; ried.fprogram changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs gli required by Table 4.12-1 are considered optimum for routine environmental F. . f measurements in industrial laboratories. It should be recognized that the
*L-LLD is defined as an a priori (before the fact) limit representing the capa-bility of a measurement system and not as an a posteriori (after the fact) -
limit for a particular measurement.
Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A. , " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K. , " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
Y~
m CALLAWAY - UNIT 1 B 3/4 12-1
a ~ . m ;-!;[
~~ '
(:'d10e . .,
~
~ - 4: i BASES 3/4.12.1 JUSTIFICATION
~
(1) The proposed addition to the referenced BTP provides clarification as to the exact referenced document and establishes a baseline document.
.(2) The proposed modification allows the Union Electric Company
~
greater flexibility in suggesting progna change based on operational cxperience.
e
[j ,,3s t:,
e,;). '
o .
0 1
~
4h 4
e um I
l$ ' ' 1 b -
- ) . -
1 I
l
~3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiolotical Environmental Monitoring Program given in the 00CM are made if requirec. by the results of this censusA. Th; 5::t ir,f - : tier 'rt the deer-te-deer ;urse,, fra eeriel eursey, er f ca ser,sultir.; with le::1 :gri:;1--
te .1 eutheritie; ; hell b; ;;;d. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gar-dens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required 'to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made:
(1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2, 3/4.12/3 INTERLABORATORY COMPARISON PROGRAM g The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accu-racy of the measurements of radioact'ive material in environmental sample matrices are performed as part of the quality assurance program for environ-mental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
-W (
TA(Fevdio') M wij\ proo Ic\t.[ bad OMM ,%
"* M door- ha- Aoor gun % c.c.Nd quN% i Or*
b#W M i W. W ]d. d yieu1Awu. Q g;ug c 'a ,
4 CALLAWAY - UNIT 1 B 3/4 12-2
- 3 m p -
, 1, ,
' ~
,3 ~
3
-j .,y ., . . -
Justification for Proposed Changes to " Bases, 3/4.12.2 Land Use Census" i , c. - ,
j /
, , . }
~~ ~ -cy. '
- ' , l' . )
Change of wording in 2nd sentence: The proposed wording of this
[j ';! sentence is more consistent with the wording of a similar sentence
>f.. ; .} in Surveillance Requirement 4.12.2.
e, < g ,
4- j y ,
s- 4
,s c i
y
/
w ll// ,
t - . c.
't .
I h(*
,e L. ' >
lI ,1 s. s *
. .t i
i) }e ^
y l *,
( ' *, " ,
i . .
,'e r , -M -
;2 . 6
;.y , ,
t k-a-
t
.(?
. . - ~
M
'6 9
%s w
, bi 3 q f-9 94* s Wi -
1,T' * * *q -
-g = . sw ew , v.a eu,e -
+,ey,es.}}