ML19242A360
| ML19242A360 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 07/25/1979 |
| From: | Parker W Duke Power Co |
| To: | Baer R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7908010485 | |
| Download: ML19242A360 (74) | |
Text
. g DUKE POWER COMPANY Powan BUILDING 422 SocTn Cncucu Srazzi, Cinaz.oriz. N. C. 28242 WI L LI AM O. p4 A M E A, J A.
occ pacs,0c~r July 25, 1979 c.c -c~c: aa c* 7c.
sec. p.ac c o 273-.ce3 Mr. 'icrold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Robert L. Baer, Chief Light Water Reactor Project Branch No. 2 Re: McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369, 50-370
Dear Mr. Denton:
Attached is the second draft of the McGuire Nuclear Station Radiological Effluent Technical Specifications. This draft supersedes those previously transmitted by my letters of December 18, 1978 and March 23, 1979.
In the sections on gaseous effluent monitoring, monitors have been added and deleted in Tables 3.3-13 and 4.3-13 to indicate final effluent monitoring points. Previously the tables included the containment purge, auxiliary building exhaust, air ejectors, and waste gas decay tanks which are monitored by the unit vent. The unit vent does not contain a flow measuring device, but each of the effluent streams entering the unit vent contains flow measuring devices and readcut in the control room.
The gas monitoring requirement has been deleted from Table 4.11-2 since it is not a sampling and analysis requirement. Even if left in the specification, it would be difficult to maintain that sensitivity under all operating con-ditions. It would also be difficult to correlate gas grab samples with monitor readings when the laboratory analytical sensitivities are a factor of 100 higher than the =cnitor sensitivity.
O s
g~s,c , 39 1 s sc 7 g '
Ei F 0 ~i 7 2'
p' *: 9' y w s yAnniversary ay,o c 7908010 % 3' /Q
Mrs Harold R. Denton, Director July 25, 1979 Page Two The specification on liquid holdup tanks has been deleted since there is no need for outside radwaste tanks with the powdex backwash recovery system.
If the powdex should be determined to be radioactive, it will be treated as radioactive waste. De minimus levels and solidification activity levels will be specified in either the ODCM or PCP.
The attached specifications do not include the changes to Section 6.0, Administrative Controls. These will be submitted at a later date.
Ve truly yours,
/
/
ML k - -
Willian 0. Parker, Jr.
GAC/sch Attachment D ~7 "I r, !. r UiU
/
f 4' .
.,.y er 9.,-
DRAFT PADI0 LOGICAL EFFLUENT TECHNICAL SPECIFICATI0flS FOR ,P ' :
P.c CtulE E V M I T I
~
M' 1979
~Zun e. T;
. /; 5 079
e <
4 l.0 DEFINITIONS -
DEFINED TERMS 1.1 The CEFINED TEPFS of this section appear in capitalized tyre and are g applicable throughout these Technical Speci fi ca ti o ns.L OPERAPLE - OPERABILITY 1.6 A system, subsystem, train, ccnpanent or device shall be OPERAPLE or have CPERAPILITY wnen it is capable of per#oming its specified function (s).
Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, nomal and energency electrical power sources, cooling or seal water, l ub rication or other auxiliary equi p-
$d ment, that are requi red for the system, subsysten, train, component or device to perfom its functions (s), are also capable of perfaming their rel ated support functi ans( s) .
CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds wi th the necessary range and accuracy to known values of the paraneter which the channel monitors. The CHANNEL CALIBRATION shall enccmpass the enti re channel including the sensor and N alarm and/or trip functions, and shall include the CHANNEL FUNCTIOFAL TEST.
The CHANNEL CALIBRATION may be perfomed by any series of sequential, over-lappi ng or total channel steps such that the enti re channel i s calib rated.
CHANNEL CHECK 1.10 A CHANNEL CHECX shall be the qualititive assessment of channel be-havior during operation by observation. Thi s detemi nation shall incl ude, where possible, comparison of the channel indication and/or status with N other indications and/or status derived from independent instrumentation channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST 1.11 A CHANNEL FUNCTIONAL TEST shall be:
- a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify k CPERABILITY including alam and/or trip functions.
- m. ~;_. u'?, "~ ^'*? :-f 'i':~ ~2C: ::;- ta -d ;;'-: M 9::' " :: P . ; 7; ~ ^ ' ;" .
h r$ri 1-1 $ /-J f1e qytr.a -CART l
- r r.
-' Lq , > u
f.0 DEFINITIONS (Continued)
- b. Bistable channels - the injection of a simulated signal into the sensor to verify CPERABILITY including alam and/or trip functions.
DOSE EOUIVALENT I-131 1.19 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (pCi/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present.
Std The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors q /d for Power and Test Reactor Sites."
a
- Ausberes 't. SfamrA Tesistrieel 3fwificatt' arts -
g- _ SOURCE CHECK 1,29 A SOURCE CHECK shall be the qualitative assessment of channel response fj when the channel sensor is exposed to a radioactive source.
T PROCESS CONTROL PROGRAM (PCP) 1.30 A PROCESS CONTROL PROGRAM shall contain the sampling, analysis, and fomulation detemination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured.
SOLIDIFICATION SWry SOLIDIFICATION shall be the conversion 3 tes hem of radioactiv l1.31
- 4f d 03
- tc. : to an': cg::::.: Gn: '; d4:t-9;tedT, : 01'tc, immobilized solid.with de'in'tc vc hm: :nd s'apc, bcunded by : : :ble sor' ace c' distirct cutlire 09 all sides (# 0c stand 4 g).
OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.32 The CFFSITE COSE CALCULATION MANUAL shall contain the methodology and parameters used in the calculation of of fsite doses due to radio-active gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alam/ trip setpoints.
"' " T N M l-J Mc,Gul25 UNIT I a<r ra1 lJ L. .) l
i '
,1.0 DEFIfl!TICMS (Continued) .
GASEOUS RADWASTE TREATMENT SYSTEM 1.33 A GASE00S RACWASTE TREATMENT SYSTEu is any s3 ten de9 i ned and in-stal1ed to reduce radioact ive gas eous ef fl uents by c011 ectinq p rinary cool ant s ys t en of fgas s f rm the p rima ry s ys t en and p rov id ing fo r del ay o r hol dup for the purpos e of reducing the total radioactivity p rior to rel eas e to the enyirortnent.
VENTILATION EXHAUST TREATFENT SYSTEM 1.34 A VENTILATION EXHAUST TREATMENT SYSTEM is any sys ten de igned and ins tall ed to reduce gas eous radiciodine or radioactive material in pa rti-culate fonn in effl uents by pass ing ventil ation or vent exhaus t gas es through charcoal adsorters and/or HERA filters for the pumose of renoving iodins or particul ates f rm the g-as ects exhaus t s tream p rior to the rel eas e to the eny irorment, b "-" 2::t'r 4 --t ::T W M '. t .:-: ;
eJ': ' '- :b': p: : : ';'. Engineered Safety Feature (ESF) atmospheric cleanup systens are not cors idered to be VENTILATION EXHAUST TREATPErfT SYSTEP components .
PURCE - PURGING l.35 PURGE or PURGING is the controlled procss of discharging air or gas f rm a confinement to maintain te perature, p rss ure, humidity, concentra-tion or other cperating condition, in s uch a manner that replace 7ent air or gas is required to purify the confinenent.
VENTI NG 1.36 VENTING is the controlled process of discharging air or gas from a confinenent to maintain te perature, presure, humidity, concentration or other operating condition, in s uch a manner that rTl ace"ent air or gas is not provided or required during VENTING. Vent , us ed in s ys t en names , d oes not imply a VENTING p rocess .
PWR-STS-1 M l-T HeCGIRS 3 UNIT *I
- t. s_ 022
TAPLF 1.2 FRFDl!EPCY FOTATIOf1 NOTATICP FRF0l!FMCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D At l eas t once per ?4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> .
W At l eas t once per 7 days .
M At l east once per 31 days .
Q At least cnce per o? days .
SA At l east once per 184 days .
R At l eas t once per 18 months .
S/t! Prior to each reactor startup. .
P Porpl eted Prior to each rel ease.
N.A. Not applicable, eue_e-r - p g.g (4c.QGlE2 UNITI eca w,..
i ? INSTRUMENTATION RADitacTIVE LIOUID EFFLUENT INSTRUMENTATION LIMITING CONDITICN FOR OPERATION 3.3.3.9 The radicactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alam/ trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alam/ trip setpoints of these channels shall be de-temined in accordance with the Offsite Dose Calculation Manual (OCCM).
APPLICABILITY: At all times.
ACTION:
- a. With a radioactive liquid effluent monitoring ir.strumentation channel alam/ trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.
- b. With one or more radioactive liquid effluent monitoring in-strumentation channels inoperable, take the ACTION shown in Table 3.3-12.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by perromance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12.
~ " -: : J 3/4 3-64 He.QdtR.E. UNIT l l
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TABLE 3.3-]2_ _
1 J!
o RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 1'
2\
S' j MINIMUN CllANNELS ACTION M$. OPERABLE INSTRUMENT c_ ~~
'R.
~
-i ). Gross Radioactivity Monitors Providing Autnmatic Tenuination of Release tJaets
- a. Liquid H;L;;tc Ef t .t Line 1 28 4
-b.- Stearii Genera tor Blowdown- E f fluent- Line - (1) --2 9-
- c. Tu rb i n e- B u i l d i n g-( Fl oo r- D ra i n s-)iumps---
-tffluent+ine (1) 30-w
~
h Con 44aime.4 %el.Inke'n Unil fendusole bine l So u
m 2. Gross Radioactivity Monitors Not Providing
~1 a
Autoritatic Terinination of Release T1xtcar
- a. , Service Wd I :sfem Peseg er ,S p L.. Efr aamt Line {ll 30
- b. 0. ventsenal (destcia4fer Treatmenf(inlet) Line {ll 30 CD C, foslainur,t-LknirlafsndnlVCondenssL--Line 30 i I U1 I CD C;3 L*C")
C'D
- '3 X:71
- 7. m::M, e.
eLn u
- h-
B 9
=
C
- - - -- a, e ~ ~ ~
D-= M M 01 P) 01 M f7 N) M U l l
, a l0 i . -
= v, w e t e-Q Eya W ,==. m e 13
- =we * . - - - - - i
>- x=<
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I I o
o e
= -=c ,
ruo i w i r I i
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= c p l
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=
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- i. T.
o a e .ac t e
c N r & W i e c .C -&
4 Q) tJ w
= a o M. w
=
a - u - L M C % C % Q C a e . W y 4 % -
W 6 a w I w @ C s b m
a n. .
6 3 i 1
e 5' k
e m !
.ta;a r c u i;
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=
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, w e- 3 co- 3 3 4 L e
e - o s. o -. e a
=
m a m.
w e m s.
u m
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I -
a Z " ? *) l **
w = = v - ul ,D o L e
~
- 3 % 0 +> M E T 3 m
a o
e,
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g e
w 11 .C m
.. l. -
i
. w
= e ib , i e U 6
,' > w 4 @ 3 L Q Og T -
< - :3 e 3 e - e !, !
o -ec ,
m -g e c = I C
e c. ei e v -
O L @ e,. ca-4 a ' - s-
< z -, e -
1 t- ,C , i so .y m e-
.C u
m
.iE
- 15 1cr e e
vQ *t'=t i I
I e
h g - a Q .c. .o.a 4; is ,
z e. a a o e _, e as i
?
3n
- 3 o
I L2 T.
l
. . ,e + . . . r.
6 @ of2
- C ei d2 - 'O .D '
(> y D x
E 4
w m v
-i -
9 S': 3/4 3-66 HeQUIR.E ONST I P
T:.,VWQ gj
- 'r:sr P siibGrj Q.s.
0 n .-oo
, o.s u. cib rh, ..
m y, .
w
i M
$,k ,
TABLE 3.3-12 (Continued) _
hLi l RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION f
f MINIMUM q CilANNELS INSTRUMENT OPERABLE ACTION ff. Continuous Composite Samplers and Sampler Flow Monitor
- a. Consent,jngl[A6kadAYdffTIA / sin Line#
f1{
- b. Nininmed Ll<d.la%dil deadcasafe. Line 30 Jl{
-:[
b ', w g
CD
'~~.
, - Naj c wiCs b llCC N d ein 3 C cm C"2
.~. O C)
Da*
v . , , ,
g RTG e: :
g-p-.m
TABLE 3.3-12 (Continued)
~
TABLE NOTATION ACTION 28 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue release:
for up to 14 days, provided that prior to initiating a 1.
At least two independent samples are analyzed in accord-ance with Specification 4.11.1.1.3, a nd; 2.
'At least two technically qualified memb'es of the Facility '
Staff independently verifyp release rate calculations and discharge valving.
f mpu, g ga ecmpu gg Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 29 With the number of channels CPERABLE 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 analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 pci/ gram; 1.
At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of i the secondary coolant is > 0.01 pC1/ gram COSE EQUIVALENT I-131.
2.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific act1vity of the secondary coolant is ,< 0.01 pCi/ gram DOSE EQUIVALENT I-131. _
ACTION 30 With the numbers of channels CPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10-7pC1/ml .
ACTION 31 With the number of channels OPERABLE less than required by the Minimum Channels CPERABLE requirement, effluent releses via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate ficw.
"'" N 1 3/4 3-68
}iefqClR.6 V M T l
.~ ' r q n ,,
L'
TABLE 3.3-12 (Continued)
TABLE NOTAT' _
ACTION 32 With the numbers of channels CPERABLE less than required by the Minimum Channels CPERABLE requirement, liquid additions to this tank may continue for up to 30 days provided the tank liquid level is estimated during all liquid additions to the tank.
ACTION 33 With the number of channels CPERABLE less than required by the Minimum Channels CPERABLE requirement, effluent releases via the affected pathway may continue for up to 14 days provided the gross radioactivity level is detennined at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual release.
ACTION 34 With the number of channels CPERABLE less than required by the Minimum Channels CPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided the gross radioactivity level is detennined at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual release.
""" c' '
3/4 3-69 He.Qutcr 04tTI qYnn
TABLE 4.3-12 ey I
{, ;
RADIDACTIVE LIQUID EffluEtiT MONITORING litSTRUMEriTATI0ri SURVEILLAt4CE REQUIREMEtiTS CilAt4NEL h ,,$
CilAtitiEL SOURCE CilAtitlEL f utiCT10tiAL CilECK CilECK CAtlBRAT10!1 TEST lilSTRUMEriT Q
- 1. Gross Bet s or Gamma Radioactivity Monitors Providing Alarm and Auto-matic isolation klu tw.
- a. 3 Liquid N L ute Ef' her!c Line D P R(3) Q(1)
- 6. ' team-Geneeatee-Blowdown-Ef fluen t D H R(3) Q(1)
Line
-e---Turbine-Building (Floor-Drains)
-D---- H R(3) -Q(1)
-Sumps-Ef Fluent-Idne -
O R a
- b. Con 4ain msal WoGletbJet Uu*'E D 'cdd"5dd H b in R(M Q(4
_, 2. Gross Beta or Ganina Radioactivity ca 7 Monitors Providing Alann But tiot 5 Providing Automatic isolation SN 4 l
!)alu0 % . y;.,_nt L Line D H R(3) Q(2) I T a. , Service Water ,S fsim...
- b. Ceacat.enal kksfevafer7'ceGenT6a/<dliac.
r D H R(3) Q(2)
CelcnTaintneet4utaintionum;T Condensde ti"t._p n y q l Continuous Composite Samplers and 3.
% Sample flow Measurement Device ,
D a. c nve.t.co I uk&wterTreah t M L/nc 0 ft/A R Q CCD
%C 6. Contaiwent Ventolathn Und Musnk th,e o rgjg g q m
U -?!.,
L?::i L'/ .a
=m C.:
,.x . 2 e
ki^ ,
a I>
ri - ,
IABLE 4.3-12 (Continued). -
RADI0 ACTIVE LIQUID EFFLUEf1T MONITORING INSTRUMEtiTATION SURVEILLANCE REQUIREMENTS 0:
c r CilANNEL CilANNEL SOURCE CNANNEL INSIRUMENT FUNCTIOiAL
} CHECK CilECK CALIBRATION TEST
- 1. Aet Mty-Recorder r-
- c. L ittuid-Hadwos t e-Ef f luen t
_4g ne . . _ , _ _ _ _ _ _ _ _ . . . . _ _ _
_ D--
N.A. Il Q-
-in -S t eam-Genero ter- B lowdown-
-f tH uent- L ine --
N;A. - - R - -- Q O.;>.
ya f/-Idrik-Level-Moni tors-( f or -tanks
@ 3 out s ide- the- bu i ld ing)--
- e. L% (- Ha id up -%d -- - -- - -- D* - -- - N . A . -- -- R Q, w_____..__.----- --
0* - N.A.--
-R--- -- - Q
-e . -
D' N.A. R -
-Q
- 4. -- -
D* N.A. -
-R -- - -- Q - -
T 6/. Flow Rate Monitors O ida *It Q a. 3 Liquid Redweste Eff h.ent Line D(4) N.A. R Q
-b. Steam-Generator Blowdown Line- - D(4) N.A. - - - R --- Q-h 4,e D ischar.ge_.Caaal D(4) "A.
. R Q C
- a
- t
. . TABLE 4.3-12 (Continued)
EBLE NOTATION
- During liquid additions to the tank.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control rocm alam annunciation occurs if crj of t'c 'oct4ag ccaditicas ed ;t-O
% dnstrument indicates measured levels above the alam/ trip ,
setpoio need sisalt dewerrsirde 4,a4 con 4rol reem akrmannonierho'es c ce.vvs t$
A M e + e 6 f f e tofei g eml ih esi s ev e tF :
I l. Circuit failure.
A f. Instrument indicates a downscale failure.
3 7. Instrument cor.trols not set in operate mode.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alam annunciation occurs if any of the following conditions exist:
- 1. Instrument indicates measured levels above tne alam/ trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
4 Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION shall be perfomed using one or more of the reference standards certified by the National Bureau of Stan-dards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall pemit calibrating the system over its intended range of energy and measurement rarge. For subsequent CHANNEL CALISRATION, sources that have been related to the initial calibration shall be used. [;; ;t'ng ;l;nts n;; : tstit t; ;r;.i; 31, c;;;blish;d c;libr;-
t i;. ,. . e d . - _ . T ; . ;h i; . ;;u i r;.. ;n;. '
(4) CHANNEL CHECK shall consist of verifying indicatio7 of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which. continuous, periodic, or batch releases are made.
"i :T -1 3/4 3 '
Mc.QutEE. 09tTl ll j'
INSTRUMENTATION RADI0 ACTIVE GASECUS EFFLUENT MONITCRING INSTPUMENTATION LIMITING CONDITION FCR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be CPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / trip setpoints of these channels shall be deterM ned in accordance with the CDCM.
APPLICARILITY: As shown in Table 3.3-13.
ACTION:
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification immediately suspend the release of radio-active gaseous effluents monitored by the affected channel or declare the channel inoperable.
- b. With one or more radioactive gaseous effluent monitoring instru-mentation channels inoperable, take the ACTICN shown in Table 3.3-13.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not appli-cable.
SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated CPERABLE by performance of the CHANNEL CHECK, SCURCE CHECX, CHANNEL CALIRRATION, .and CHANNEL FUNCTICNAL TEST operations at the frequencies shown in Table 4.3-13.
N ' C': =1 3/4 3-73 Mr./q dLA.E V MIT 1
'l Oj
TABLE 3.3-13 .
r o?
- h. f jI RAD 10ACIIVE GASEGUS EFFLUEflT N0tilTORIttG 1tiSTRut1EttIAI10N V. MittlMUM CllAttr4EL5 APPLICABILITY Q- It1STRUMErlT OPEllABL E AC110ti A 1, 'h t t e O n 11aJ4up Sys t e"'
[Q s
^
d elet ,_ ;gtritn e nsfe .' u n c , . m u n , n- n -
, r 4aug Yff UE Ytntt gf drhec_ rt/g4Je/ 4>r-4odine-Sampler- -
-- ( 1-}
41 -
Utrougl < uaff try( ,
e-Particulate Sampler -- (1) - -- --
41 m
bf. Effluent System flow Rate Heasuring Device fl{
- 36
'n
- m e-S amp ler-Flow- R a te-Heasur-ing (-1-) 36 -
4 -Dev k e--
- n u
_d
(.n
-2ArWaste--Gas tiolduHystem-Explosive-4io s-Nort i t or i ng - S ys t e*-( fee-ws tems-CD -designed- to-wi t hs t and-the- e f f eeh--
O -oM+yumyon-explosion) -
'.u- 39-
-+-4tydrogen- Mon i t or - ---( I ) --
T -b;--Ilydrogen or Oxygen Monitor - - - ( 1 ) - -- - - -
- 3b g
(C
& LJ rr-m .,
E g 1 CD ti:' ;
C'
[ffj =,
TABLE 3.3-13 (Continued) *
~
, RADIOACTIVE GASEOUS EffLUErlT M0tilTORiflG INSTRUMEllTATI0tt i;
, MitilMUM CilAtitlELS c, IrlSTRUMEt1T OPERABLE APPLICABILITY ACT10tl r,
4 2. Waste Gas Holdup System Explosive Gas Monitoring System Hoe-systems-not
-des igned to withs tand-the-ef fects-of-a hydrogen explosiert)-
- a. ilydrogen ilonitor 1 ** 40
- b. Ilydrogen or Oxygen Monitor f ** 40 dddg #,J. +3. Containment rurge Monitoring Systea
&ct'rost .sinx tz dwe r
it<o/cV/rioc$[%pu/y/
- a. tioble Gas Activity Monitor ll[
- 38 vnd *
- b. Iodine Sampler
{lf
- 41 t.,
_g
- c. !' articulate Sampler }l(
- 41 j d. Effluent System Flow Rate Measuring Device J1)
- 36
- U
- Sampler Flow Rate Measuring g e. flp
- 36 g Device X
?"D t:-.
- . a
[' . d g ~ :;
f;.
e
TABLE 3.3-13(Continued), -
l RADI0 ACTIVE GASEOUS EFFLUEffT MONITORING If1STRUMENTATIOf4 o
% ,],
~
b ,' MINIMUM
- c. CNANNELS INSTRUMEriT OPERABLE APPLICABILITY ACTION
- 1. % o,,;r out
- a. floble Gas Activity Monitor (l(
- 37 lodine Sampler *
- b. {1{ 41
- c. Particulate Sampler
- 21) 41 T e" D d. Effluent System Flow Rate Measuring Devices *#{1y
- Q 'r' 36
& 5
- c. Sampler Flow Rate y Measuring Device j'l[
- 36 m .4 L h . .::.- g e a e g:'y'JT p.
y_ '; a. ble Qas Actis;fy thni.ibr i K l M* : k. 6Hloes lowk'aie g I
,yk tieasurin cc gg g,, c.c.mprarh/,st, y 3c.
49 ca re nam 4s l ' n Meassemy
.- _a De V*c e
- u. ,L . .~
'?s f ca vel **'Af k y &Lior / \ 31 Stv%e u,M vanF. S n 7.
ul Buildin[utdab.
N cs . nowe Has Iluov.i tIIra*ITr I n af ,
(%%nn.s Pay aa k\taast Elair/5rs Toen on MI' I'~I d'"! 3' *) s ro,6visst
- EFiloruificu,s esder.,ig Jhe fslack shail Asce //cuo este nwa/sn.
1hrse ffaa c/1a//6e 5'unr#eo aa/ww<*&//,e loee,<,4e/rwse oprm4s.g ,,
9 8 e
5
% % q h Q Q 9
u dl k
- 1. " 4 m A 4 T k 4 4
.i : i fjL ~~~ ~
%JO % %
O 4,
+
s . -
P3 4
$d4 w+ sQ 4 +
- s t Ax d t\ .
i .:t l- d.e $d +J j Ys s f l *b < d h,d d d
'I 4 . 5 .i s ="eL.7 m .i
- 9 $ i~R'
- x =
- w% %T 2 4t
-t sw t ~ K. {s d % N l k k 4 RN E E
QQQ% k e se $ lAA3
, , W a < s s% N{ e k' d m
e
-, . v :v . . .
,, p -( L su 3- 1s e - -
TABLE 3.3-13 (Continued) .
TABLE NOTATION
- At all times.
- 0uring waste gas holdup system operation (treatment for primary system offgases).
ACTION 35 With the number of channels CPERABLE less than required by the Minimum Channels CPERABLE 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:
- 1. At least two independent samples of the tank's contents are analyzed, and
- 2. At least two technically qualified members of the Facility Staff independently verifyA4e and discharge valve lineup;k release gg rate calculations'g Othen,ise, suspend release of radioative effluents via this pathway.
ACTION 36 With the number of channels CPERABLE less than recuired by the Minimum Channels CPERABLE requirement, ef'luent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTICN 37 With the nurrber of channels CPERABLE less than required by the Minimum Channels CPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 '9urs and these samples are analyzed for gross activity within . ' bours.
ACTION 38 With the number of channels CPERABLE less than require <1 by the Minimum Channels CPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.
ACTICN 39 ' t' t' '
v bc ;~ :'a- c': ":' "L : ::: ;- :g' :j b, c F i. '.;n- ': ^?:7 AT.L: .;,.m.c..;, ,c.;ti;n ;f ;. .c su.c s;2 ..v.l. y : c.. of C....a f;> . t: 3 0 d;j . g . dcd i
- T :: ;r: ::c tcj :t '::: : :: ;: * ': : :-j : ', :d
'- : mt * '^ r: . (4 tleted ) .
ACTION 40 With the number of channels CPERABLE one less than required by the Minimum Channels CPERABLE recuire ent, oceration of this system may continue for up to 14 days. With (two) channels ia-operable, be in at least HOT STANCBY witnin 6 nours.
me M 3/4 3-77 d401EE W IT )
b ,j r PQC t!,U
TABLE 3.3-13 (Continued)
TARLE NOTATION ACTION 41 With the numoer of channels CPERAELE less than required by the Minimum Channels OPERABLE requirenent, ef fluent releases via this pathway may continue for up to 30 days, provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.
S' "' - !' T J 3/4 3-78 Mc$0(F'E CN 7 /
G E qQO
- /,; J L. / /
TABLE 4.3-13 x~!
- b2c, RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS P
CilANNEL H0 DES IN WillCil CllAriflEL SOURCE CilANt1EL FUtiCTIONAL SURVEILLANCC c INSTRUMENT CilECK CilECK CALIBRATI0tt TEST REQtilRED c -
Q blo gi. was te Gas 'Tiuluup System-
~
Ud* a. . cl,lm Gas !k.tivity !!aniter l' l' H(3) Q(1-) *-
regovaf'*at ( M ... a te a u >
g,3 gg3 44 N/A N/A N/A -
ePaet ieulale- Sainpler W N/A -N/A N/A
^
b g. System Effluent flow Rate P N/A R Q
- Heasuring Device
-e-Sampler- F low- R a te Measur ing ---- D-- ---- N/A---- -- R Q- *-
3 1% waste Gas lloldup System Explosive y Gas Monitoring System M a. llydrogen Monitor D N/A Q(4) H **
12 llydrogen Mealtor (alternate) D N/A Q(4) M **
~
n c. Oxygen Monitor D N/A Q(5) M **
b th---Oxygen Moni tor (alternate) - - - -D--- N/A Q(5) M **---
O CD \
TABLE 4.3-13 (Continuedl Ty RADIGACTIVE GASE0US EFFLUENT M0illTORING IllSTRUMENTATION SURVEILLANCE REQUIREMENTS
[n , '
E! i CilANf4EL H0 DES IN WillCil k',- CilAtJNEL CliECK SOURCE CilANNEL CALIBRATION FUNCTIONAL TESI SURVEILLANCE INSTRUMENT CilECK REQUIRED c
z Il d ic 4 4A k D m inment Purge Vent System tre u s $c Y -
ye ugyerittstf a5
- H a,tioble Gas Activity -
- j 3, r D P R(3)
- b. lodine Sampler N/A t il/A *
- c. Particulate Sampler W fl/A fl/A *
- d. System Ef fluent Flow Rate D N/A R Q
- Measuring Device
- e. Sa ow Rate Measuring D N/A R Q a
,e C
. Tl
_ S.
(_ 71
_ . =
es
TABLE 4.3-13 (Continued)
[
mi
[ RADI0 ACTIVE GASEOUS EfftUEtJT M0tilTORitiG If4STRUMEtJTAT10ti SURVEILLAf1CE REQUIREMENTS .
Si ' ';
IfiSTRUMENT CitAfif4EL SOURCE CilAfitiEL CilAforiEL FuriCT10t4AL H0 DES Ifi WillCl!
M, ,
CllECK CilECK CALIBRAT10ti TEST SURVEILLAriCE N '" REQUIRED
- c. 2- . W Onit %t a
] a. fioble Gas Activity Monitor D M R(3) Q(2) *
- b. lodine Sampler W N.A. fi . A. N.A. *
- c. Particulate Sampler W ti . A . ft. A. N.A. *
- d. System Effluent Flow Rate Measurement Device D fl . A . R Q *
- e. Sampler Flow Rate Measurement Device D H.A. R Q
- s
- 5 Gnaene Air E3 uiar f
h abl n Aelivity Heahr o H R(0 Q( 1)
\ t> . EH tvent Fleso <
newein, pesiec 0 ti. A. e o e kIsle.O c. Lampier A .o fate wc,;,W t% nr,e'9 Devi<e o R Q X r,l,vs,ia*
os g .taush. I"-A '" " ' ~ T 0"'Id '"1 d#"IH
- a. Webte a ou,ry ris,ator b n mj n(2 ,
a 7.yd Gel-%!d,&, Je.tMdar, ts 2
2s k-Nobicl$as4leidTT!!c a:Cr & ti i~'(5) Q (2) F-
-- y eI~,
,m Ceirlani. h/cd 3rf s $baf g n'. trarchoosc
'n' h _a. Q, Mcbfe Gas AeWuhfic <: lor D H Tll5) OIC +
~
QN, 6 Tod..a s q w w a m na v g; _~ c. (hrheatde %pler y yy gg og +
i L SMlasorenu stem ERlahce.kle-a F Flow p gg g Q &
C. c, . . ~ e , . .e u .,, ca , b A/# PL o & .
t e
ud 2
3 4f
.1 Os - 2 ],5 ! Y kkTk ,1 19 9 4 k dd G2 2 o' d
+
d J: C22ed a a L , D
,,: . AA>
is ' p% v sJ 4-a s, g
. N* Q 24
- L f 4
} }.3 U wg 1 +E ?
8 Yk m s. k 2 .2,i -ics
') ll i 7CFf I e4 e -a e 72 S! .C P " ' ', T "; i :1 3y g_ g e [h:O a
tt e.,<. .i; .< : .c , .w U5 103
TABLE 4.3-13 (Continued) TABLE NOTATION
*At all times.
**During waste gas. holdup system operation (treatment for primary system offgases).
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isogion of this pathway and control room alam annunciation occurs if _ , c' the 'cil:U a; coadit4ca ex st: i K Instrument indicates measured levels above the alam/ trip . setpoiDC ased shall dos eushafe Hedexh/rcomoh w annonfiabch ocews t$ s n a y af fAe MUcauy OxMMr aid: [f. Circuit failure. f,/. Instrument indicates a downscale failure. 3 /. Instrument controls not set in operate mode. (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alam annunciation occurs if any of the following conditions exist:
- 1. Instrument indicates measured levels above the alam/ trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
4 Instrument controls not set in operate mode. (3) The initial CHANNEL CALIBRATION shall be per#omed using one or more of the reference standards certified by the National Bureau of Stan-dards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NPS. These standards shall pemit calibrating the system over its intended range of energy and measurement range. For subsecuent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. -C ; ; . . '. . . ; ,. ' ; . : ; y : b;;f; :-; gr:. :.:', ::t d:Md ::' 'b :
' : pr:::d c :: ';r t'f: :p-.c;r:.;
-.s- 3/4 3-82 H40t EE 08tTI E/r
^;J i,dt p ':
TABLE 4.3-13 (Continued) TABLE NOTATION (4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a ncminal:
- 1. One volume p rcent hydrogen, balance nitrogen; and
- 2. Four volume percent hydrogen, balance nitrogen.
(5) The CHANNEL CALIBRATION shall include the use of standard gas saroles containing a noniqal-
- 1. One volume percent oxygen, balance nitregen; and
- 2. Four volume percent oxygen, balance nitrogen.
"' ' - C ' L-1 3/4 3-83 Mc.40lE O NtT I 105
' Ez
3/4.11 RAD!naCTTVF FFFLUENTS 3/4.11.1 LICUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATICN 3.11.1.1 The concentration of radioactive material released from the site (see Figure 5.14) 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 10-4uCi/ml total activity. APPLICABILITY: At all times. ACTION: With the concentration of radioactive material released from the site exceeding the above limits, immediately restore the concentration to within the above limits. SURVEILLANCE REQUIREVENTS 4.11.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be detemined prior to release by sampling and analysis in accordance with Table 4.11-1. The results of pre-release analyses shall be used with the calculational methods in the CDCM to assure that the con-centration at the point of release is maintained within the limits of Specification 3.11.1.1. 4.11.1.1.2 Post-release analyses of samples composited frcm batch releases shall be pertomed in accordance with Table 4.11-1. The results of the previous post-release analyses shall be used with the calculational methods in the 00CM to assure that the concentrations at the point of re-lease were maintained within the limits of Specification 3.11.1.1. 4.11.1.1.3 The radioactivity concentration of licuids discharged from continuous release points shall be detemined by collection and analysis of samples in accordance with Table 4.11-1. The results of the analyses shall be used with the calculational methods in the 00CM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.
~~--1 3/4 11-1 Mc.QUt22 QNITl R /: 5 106
TABLE 4.11-1 RADIOACTIVE LIOUID WASTE SAMPLIfiG A*;D AtJALYSIS PROGRAM - Lower Limit Liquid Release Type Sampling Minimum Type of Activity of Detection trequency Analysis Analysis (LLD) Frequency (uCi/ml)a P P A. Batch Waste Re- Each Batch Each Batch 5 x 10-7 - lease Tanksd Principa} Gamma Emitters I-131 1 x 10-6 p Dissolved and Entrained Gases One Batch /M M 1 x 10-5 (Gama Emitters) P H-3 1 x 10-5 Each Batch M b Composite Gross alpha 1 x 10-7 P-32 1 x 10-6 Each Batch Q b Composite Fe-55 1 x 10-6
- 8. Plant Continuous Continuous c W Principal Gamma Releasese Composite c Emittersf 5 x 10-7 I-131 1 x 10-6 g Dissolved and Grab Sample M Entrained Gases (Gamma Emitters) 1 x 10-5 Continuous C M I*
e Composite Gross alpha 1 x 10-7 P-32 1 x 10-6 Continuous' Q c Sr-89, Sr-90 5 x 10-8 Composite Fe 55 1 x 10 -6
"" :~ M 3/4 11-2 flat;0ttG UNIT 1 c, /, 5 i0_/
TABLE 4.11-1 (Continued) TABLE NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radicchemical separation): 4 s LLD = b E V- 2.22 f. exp t -A a t ) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) sb is the standard deviation of the hackground counting rate or of the counting rate of a blank sample as appropriate (as counts per minute) E is the counting efficiency (as counts per transfomation) V is the sample size (in units of mass or volume) 2.22 is the number of transfomations per minute per picocurie Y is the fractional radicchemical yield (when applicable) A is the radioactive decay constant for the particular radionuclide at is the elapsed time between midcoint of sample collection and time of counting (for plant effluents, not environmental samples). The value of sh used in the calculation of the LLD for a detec-tion system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide de-temined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides nomally present in the samples. Typical values of E, V, Y, at shall be used in the calculation. The background count rate is calculated from the back-ground counts that are detemined to be within + ane FWM (Full-Width-Half Vaximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide.
" 7 92 3/4 11-3 Mc.Qoms untT I rfc'd n
f U, O
TABLE 4.11-1 (Continued 1 TABLE NOTATION -
- b. A composite sample is one in which the quantity of licuid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is repre-sentative of the liquids released.
- c. To be representative of the quantities and concentrations of radio-active materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream.
Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representa-tive of the effluent release.
- d. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isciated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sampling.
- e. A continuous release is the discharge of liquid wastes of a non-discrete volume; e.g., from a volume of system that has an input -
flow during the continuous release.
- f. The principal gamma emitters for which the LLD specification apolies exclusively are the following radionuclides: Pn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are belcw the LLD for the analyses shall be reported as "less than" the nuclide's LLD, and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations.
" I'N 3/4 11-4 k.QthRE UNIT I
$5 jg7
RADI0 ACTIVE EFFLUENTS , DOSE LIMITING CCNDITICN FCR OPERATION _ .. 3.11.1.2 The dose or dose cermitment to an individual from radioactive materials in liouid effluents released from the site (see Figure 5.1-4) shall be limited:
- a. During any calendar quarter: f 1.5 mrem to the total body and f 5 mrem to any organ, and
- b. During any calendar year: 13 mrem to the total body and I 10 mrem to any organ.
APPLICAPILITY: At all times. ACTION:
- a. With the calculated dose from the release of radioactive materials in licuid effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in licuid effluents duri the r erent calendar cuarter and during the f8fgM[emgn,dgfg1g3M so that the cumula- elcoue tA tive dose or dose c;mmitment to an individual from such releases e in 44 during these tour calendar quarters is within 3 mrem to the total body and 10 mrem to any-organ. :LThis Special Peport shall also include (1) the results of radiological analyses of the drinking
%&)
water source, and (2) the radiological impact on finished drinkirg water supplies with regard to the requirements of 40 CFR lal, Safe Crinking Water Act.9
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIPEMENTS 4.11.1.2 Dose Calculations. Cumulative dose contributions frcm licuid effluents snall te cetemined in accordance with the CCCM at least once per 31 days.
*' :' c n i: : ,. 'j;- ^3 ::: :,::', : t. :'r" ::: ';
~ t:- be t .
PT - ~54 3/4 11-5 McQutCE. ONsT \ E/'Jr ; en t G
i PADI0 ACTIVE EFFLUENTS . QJ!DWASTETREATMENT LIMITING CONDITION FCR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be CFERABLE. The app *opriate cortions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected dose due to liquid effluent frcn tne site (see Figure 5.1-4) when averaged over 31 days would exceed .046 mrem to the total body or M mrem to any organ. (,, 2f C,7 APPLICABILITY: At all times. ACTION:
- a. With the liquid radwaste system inoperable for more than 31 days or with radioactive liquid waste being discharged without treat-ment and in excess of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commissich within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the follcwing infomation:
- 1. Identification of the inoperable equipment or subsystems cnd the reason for inoperability.
- 2. Action (s) taken to restore the incperable equipment to OPERABLE status.
- 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 RECUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with the OCCM. 4.11.1.3.2 The liquid radwaste treatment system shall be demonstrated OPERABLE t' operating the liquid radwaste treatment system equipment for at least minutes at least once per 92 days unless the liquid radwaste systec has ceen utilized to process radioactive liquid effluents durinn the previous 92 days.
" " T ': '. 3/4 11-6 tkQQt2E MIT l C /: E i1 1
. ' 'i J l l l
~
RADICACTIVE EFFL'!ENTS L!DUID HOLCUP TANKS
- Rfdc%As . ,
c. Sh4toa $10.5 flubeX Y95t n LIMITING CCNDITION FCR CPERATICN bacb.uukvee_coer 4cm ks. J ...d,Tue % a m i a v .' , 2u . a ;; ' ,_ ;;cr. 1 :: : ' cd ' :::' ' fo wing tanks shall be limited to < /d curies, excluding triti' and disso ed or entrained noble gases,
- a. venteenal Wa.redcy Treatet Wstere Gf.41 #st P Pead.
.l5 ~\
- 2. \
by. Outs 1ce emporary tank. M7' 5ILITY: At a times. ACT!CN:
- a. With the quantity of = dica .ive material in any of the above listed tanks exceeding . above limit, immediately suspend all additions of radioacti- . terial to the tank and within 48 hrs reduce the tank cont ..ts to ithin the 'Imit,
- b. The prosisions Specifications 3.0.3 and 3.0.4 are not applicabi3.
SURVE!LLANCE pr. IREMENTS -
- s 4.11.1.4 ihe quantity of radicactive material containe in each of the above ,sted tanks shall be determined to be within the ab ve limit by ant jzing a representative sample of the tank's contents at ast once
.a o n ,4 4 n i c. 4. . o - 2 + o .- 4 21- w 3 ,. o o_ 4 ~,. ,aso_s_ -
+we_ +4_
-T... ..m.c. .. :h. ^,c..'.c;;i;.. a.; :h:5e :a d::r ::r'.- tt:t cr:
- :...: .did b l'ncrs, dites, ;r mcil :20:57: Of '01di 9 t'c '.0 '
- t. . i . c . . a s..d tret de ;t 'c.c ::.-L .: #'?-< :"d 0 7 7 "" g 3-a-4c44ns
- r ::::d to t'c ;/ d :c-c;:: t ::: c-t :):'.:'"
" TH 3/4 11-7
,McQillfE (JN IT I
" '.:' " t' " . n" .
g-Pl N' "h u ~1bb , b ; N od j U J t IL
RADICACTIVE EFFLUENTS , 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 sit? (see Figure 5.1-3) shall be limited to the followi ng: .
- a. For noble gases: < 500 mrem /yr to the total body and f 3000 mrem /yr to The skin, and
- b. For all radiciodines and for all radioactive materials in parti-culate form and radionuclides (other than noble gases) with half lives greater than 8 days: 11500 mrem /yr to any organ.
APPLICABILITY: At all times. ACTION: With the dose rate (s) exceeding the above limits, immediately decrease the release rate to within the above limit (s). SURVEILLANCE REQUIREMENTS 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 methods and procedures of the ODCM. 4.11.2.1.4 The dose rate due to radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the 00CM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 4.11-2. Fw r _~ '. 3/4 11-8 McQVIAS CNIT l bdb l!)
TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAf1PLING AND ANALYSIS PROGRAM {[l], Sampling Minimum Analysis Type of Lower Limit of g i Gaseous Release Type Frequency Frequency Activity Analysis Detection (LLD) bh ---- (uci/ml)a P P
- c. A. Waste Gas Storage Each Tank Each Tank Principal Garivia Emitters 9 IX M'4 E Tank Grab
-1 Sample li b P
B. Containment Purge Each Purge Each Purge Principal Ganina Emilters 9 1 x 10-4 Grab gg_3 1 x jo-6 Sample _ C. E-
- M,gcb gb Principal Gansna Emitters 9 1 x 10 ~4 Co1 denser A,v deh Grab Sample 11- 3 1 x 10-6 R
4 O n E 5 W __ d -12 D. gUnWeuf Continuous' u i-iai i x 10 Charcoal
.Skewl oah Re,l,*
t Sample I-133 1 x 10-10 d
" '"" " f
, Mondam[nafed S(3 Par iculate Principal Gama Emitters 9
,e Sample (I-131,Others) 1 x 10 -3) h3 Sfzvaie [thrchoose. f' Og,g
*e Continuous M ,
Gross alpha' 1 x 10-))
, Compostte Pa rticula te - Sample
[ Continuous Q Composite Sr-89, Sr-90 1 x 10 "
,' M_ Particulate o Sample
'f' gg % Conti"'m # I ng,;e go, cm, gg,g g33g h ; ;gg jwo _
' l i,uu 1 Lu, lk ta ? t - >
*4
TABLE 4.11-2 (Continued) TABLE NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation): LLD = 4.66 s b E V- 2.22 - Y exp(-Aa t ) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute) E is the counting efficiency (as counts per transfonnation) V is the sample size (in units of mass or volume) 2.22 is the number of transfomation per minute per picacurie Y is the fractional radiocnemical yield (when applicable) A is the radioactive decay constant for the particular radionuclide at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental umples). The value of sb used in the calculatior, of the LLD for a detection system shall be based on the actual observed variance of the back-ground counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically pre-dicted variance. In calculating the LLD for a radionuclide deter-mined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides nornally present in the samples. Typical values of E, V, Y and at shall be used in the calculation. The background count rate is calculated fran the background counts that are detemined to be within + one FWHM (Full-Width-Half-Maximum) energy band about the ene7 9y of the gamma ' ray peak used for the quantitative analysis for that radionuclide. i
'" " N 3/4 11-10 He QUIT 6 VNIT I g a
TABLE 4.11-2 (Continued) TABLE NOTATION
- b. Analyses shall also be perfomed follcwing shutdown, startuo, or similar operational occurrence which could alter the mixture of radionuclides.
- c. Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flecded,
- d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after charging (cr after removal from sampl e r) . Sampling, and analyses shall also be perfon"ed at least once cer 24 hours for at least 7 days follcwing each shutdown, startup or thernal pcwer level change exceeding 15" of RATED THERMAL PCWER in one hour. When samples collected for 24 hours are analyzed, the cor-responding LLD's may be increased by a factor of 10.
C. 'i t i . "' gr b : mcl e: :ha!! be-taken at least-ence-per 7 day: ' o- _ th . c r t i' :t i o n -exhaus t '-ca the-spent fuel poc1 a ca.
- f. The ratio of the sample, ficw rate to the sampled stream ficw rate shall be known for the time period covered by each dose or dose rate calculation made in accorcance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
- g. The principal gamma emitters for which the LLD specification applies exclusively are the folicwing radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gasecus emissions and Mn-54, Fe-59, Co-58, Co-60, In-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list dces not mean that only these nuc-lides are to be detected and reported. Other peaks which are measur-able and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are belcw the LLD for the analyses shall be reported as "less than" the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclide.
The "less than" values shall not be used in the required dose calcula-tions.
- h. The noble gas continuous monitor shall be calibrated using laboratory analyses of the grab samples fecrn A, 3 and C on Table 4.11-2.
~
L' The. ecmpcs;te filler fap edull be analtf ied Act P ^I k "N sec}rck so f %t [ ope par vndTape Icq/h % assert Mal MGl Y Sec.hodt aft anafytr.dpr d'o//seEengrrid,
~ ^ ~ ~ '
3/4 11-11 McfbbEGAllTl
- /, C, ;I,
RADI0 ACTIVE EFFLUENTS DOSE, NOBLE GASES . LIMITING CONDITION FOR CPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents from the site (see Figure 5.1-3) shall be limited to the .follcwing:
- a. During any calendar q;arter: f 5 mrad for gamma radiation and f 10 mrad for beta radi3 tion and,
- b. During any calendar year: 110 mrad for gamma radiation and f 20 mrad for beta radiation.
(The dose design objectives shall be reduced based on pre-dicted noble gas releases freci the turbine building if effluent sampling is not provided. The dose design objectives shall also be reduced based on expected public occupancy of areas, e.g., beaches and visitor centers within the site boundary.) i APPLICABILITY: At all times. ACTION: l a. With the calculated air dose from radioactive noble gases in gase-ous effluents exceeding any of the above limits, in lieu of any other report required by Scecification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, l a Special Report which identifies the cause(s) for exceeding the j limit (s) and define the corrective actions to be taken to reduce
. l the releases of radioactive noble gases in gaseous effluents during
/Ovt M1 _ % th ain er 4 (N t'ne /
"'PgJ4reg 3g-Ogf atgcyent a calendar quarter and during the %b-3 % so that the cumulative
- ' these four calendar cuarters is within (10) mrad for gamma radia-D i l
tion and (20) mrad for beta radiation. I b. The provisions of Specifications 3.0.3 and 3.0.a are not applicable.
' SURVEILLANCE REOUIREMENTS l4.11.2.2 Dese Calculations Cumulative dose t "ributions for the cur-irent calendar cuarter and current calendar yea. ; hall be detemined in accordance with the CCCM at least once every 31 days.
~C 3/4 11-12 "cQ0125 t]MIT I
[ i;_
'/ I lI i !.
RADI0 ACTIVE EFFLUENTS . DOSE, RADIGICDINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM, AND PADIONUCLIOES OTHER THAN NCBLE GASES LIMITIP!G CONDITION FCR OPERATION 3.11.2.3 The dose to an individual from radioicdines and radioactive materials in particulate fom, and radionuclides (other than noble gases) with half-lives greater than 8 days in gasecus effluents released frca the site (see Figure 5.1-3) shall be limited to the following: -
- a. During any calendar quar +er. f 7.5 mrem to any organ and,
- b. During any calendar year: f 15 mrem to any organ.
(The dose design objective shall be reduced based on predicted carbon-14 releases and turbine building releases if effluent sampl.ng is not provided.) APPLICABILITY: At all times. ACTICN.
- a. With the calculated dose frcn the release of radiciodines, radio-active materials in particulate 'om, or radionuclides (other than noble gases) with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report recuired by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and. defines the corrective actions to be taken to reduce the releases of radiciodines and radioactive materials in particulate [eaucp, fom, and radionuclides (ether thaa nuble gases) with half-lives ,j e f p a./
greater the currentthan 8 days calendar in and quarter gaseous curing . .effluengt.cfrgggggcgg1,
~ ~ _c . _m c;.-
e-da cua-te-s so that the cumulative dose cr dos;e commitment to an individual from such releases during these four calendar cuarters is within (15) arem to any organ.
- b. The crovisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations Cumulative dose contributions for the current calendar quarter anc current calendar year shall be detemined in accordance with the CCCM at least once every 31 cays.
":: '. 3/4 11-13
'Mc @tes cutt \ E /l 5, lO
ADI0 ACTIVE EFFLUENTS GASECUS RADWASTE TREATMENT LIMITidG CONDITION FOR OPERATION 3.11.2.4 The gaseous radwaste treatment system and the ventilation exhaust treatment system shall be CPERABLE. The appropriate portions of the gaseous radwaste treatment system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releas from the site (see Figure 5.1-3) w . n averaged over 31 days would exceed rg(i crad for gamma radiation and mrad for beta radiation and the appropriate portions of the ventilation exhaust treatment system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases fran the site (see Figure 5.1-3) when averaged over 31 days would exceed D 5 mrem to any organ. APPLICABILITY: At all times. ACTION:
- a. With the gaseous radwaste treatment system and/or the ventilation exhaust treatment system inoperable for more than 31 days or with gaseous waste being discharged without treatment and in ex-cess of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report, which includes the following information:
- 1. Identification of the inoperable equipment of subsystems and the reason for incperability.
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status.
- 3. Summary description of action (s) taken to prevent a re-currence.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
W. 3/4 11-14
,&Gdt25 UUlf I I
/r 110
'J l I /
SURVEILLANCE RECUIRE.ENTS M 4.11.2.4.1 Doses cue to gasecus releases from the site shall be projected at least once per 31 days, in accordance with the OCCM. 4.11.2.4.2 The gaseous radwas:1 treatment system and ventilation exhaust system shall be demonstrated OPERABLE by operating th( gaseous radwaste treatment system ecuipment and ventilation exhaust treatment system ecuto-
. rent for at least <?O minutes, at least once per 92 days unless the appro-priate ;ystem has been utilized to process radioactive gaseous effluents durirg the previous 92 days.
n- -- -
~'*' 3/4 11-15 Mc QCtEE Omr j 4 on
, i t-
RADI0 ACTIVE EFFLUENTS DOSE . LIMITING CONDITION FOR OPERATION 3.11.2.5 The dose or dose cannitment to any real individual from uranium fuel cycle sources shall be limited to < 25 mrem to the total body or any organ (except the thyroid, which shall be limited to < 75 mrem) over 12 consecutive months. APPLICABILITY: At all times. ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a , or 3.11.2.3.b, in li eu of any other report required by Specification 6.9.1, orepare and submit a Special Report to the Canmission pursuant to Specification 6.9.2 and limit the subsequent releases releases such that the dose or dose conmitment to any real individual from uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except thyroid, which is limited to < 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures to any real irdividual from uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a var'ance from the Commission to permit releases which exceed the 40 CFR Part 190 Sta nda rd.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicaole.
SURVEILLANCE RECUIREMENTS 4.11.2.5 Dnse Calculations Cumulative dose contributions from liouid and gaseous ef fluents shaTT be determined in accordance with Scecifi-cations 4.11.1.2, 4.11.2.2, a nd '4.11.2.3, and in accordance wi th the COCM.
* ^ ri a ".- 3/4 11-16 HeGWRS QUIT I
!q1
_ r . 5r; j lI
RADI0 ACTIVE EFFLUENTS , . EXPLOSIVE GAS MIXTURE {3p m..; at de ';"ed to u th:t ed a hyd :::= 2 7' ::' ^ ^' LIMITING CONDITION FOR OPERATION 3.11.2.5[ The concentration of hydrogen and/or oxygen in the waste gas holdup system shall be limited to < I". by volume.
~3 APPLICABILITY: At all times.
ACTION:
- a. With the concentration of hydrogen and/or oxygen in the waste gas holdup system > p. by volume but 14' by volume, restore the concentration or hydrogen and/or oxygen to within the limit 48 hours.
- b. With the concentration of hydrogen and/or oxygen in the waste gas holdup system > 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentra-tion of hydrogen and/or oxygen to f /% within 48 hours.
3
- c. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREPENTS 4.11.2.6/ The concentrations of hydrogen and/or oxygen in the waste gas holduo system shall be detemined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the hydrogen and/or oxygen monitors required CPERABLE by Table 3.3-13 of Specificaticn ' 3.3.10. O
~ : ~ > '. 3/4 11-2
?teGUITE vNtr I f[b,
) O ^d
RADI0 ACTIVE EFFLUENTS
- GAS S102 AGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.7 The quantity of radioactivity contained in each gas storage tank shall be limited to <'(fgyz curies noble gases (considered as Xe-133).
APPLICARILITY: At all times. ACTION:
- a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all addi-tions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be detennined to be within the above lim 1t at least once per 24 hours when radioactive materials are being added to the tank. It
^' " :': ' 3/4 11->&'
McCno tes UNIT I I c77 9li; s,
PADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLIO RADI0 ACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3.1 The solid radwaste systen shall be OPERABLE and used, as applic-able in accordance with a PROCESS CONTROL PROGRA.M, for the SOLIDIFICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site. APPLICABILITY: At all times. ACTION:
- a. With the packaging requirements of 10 CFR Part 20 and/or 10 CFR Part 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastes from the site.
- b. With the solid radwaste system inoperable for more than 31 days, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
- 1. Identification of the inoperable equipment of subsystems and the reasons for inoperability.
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status.
- 3. A description of alternative used for SOLIDIFICATION and packaging of wastes.
4 Summary description of action (s) taken to prevent a re-currence.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.3.1.1 The solid radwaste system shall be demonstrated CPERA2LE at least once per 92 days by:
\$
"M. 3/4 11-M MeQates UNCT I 19,1 c f. Jr 4L9
. . SURVEILLANCE REQUIREMENTS (Continued)
- a. Perfomance of functional tests of the equipment and components of the solid radwaste system,
- b. Operating the solid radwaste system at least once in the pre-vious 92 days in accordance with the PROCESS CONTROL PROGRAM, or
- c. Wi44c-at4on as the 6xistence of a valid contract for SOLIDIFI-CATION to be perfomed by a contractor in accordance with a PROCESS CONTROL PRCGRAM.
4.11.3.1.2 The PROCESS CONTROL PROGRAM shall be used to verify the SOLI-DIFICATION of at least cac ep-eceatati"e 'ee' e~+ '-c at least 88 % tenth batch of each type of wet radioactNe"/dsIb :.ea
- g. , 'i!!c ! d get ,
;c"t -es'rs, avaporat:- bott w W ic-acid solutions, and sediar : ;t:
0'utions'. deJef any test specimen fails to verify SOLIDIFICATION, the SOLI-gfg DIF ' ION of the batch under test shall be suspended unt' such ti. as additional test specimens can be obtaine , al-ternative IDIFICATON parameters can be detemia. in accordance wit 'he PROCESS CONTROL PROGRAM, a subsequent test verifies SOL w ICATION. SOLIDIFICA' i of the batch may then be resumed using he alternative e IDIFICATION parareters detemined by the PRCCES "0NTROL * ' GRAM.
/ If the initial test specir fr a batch of waste fails to se66u verify SOLIDIFICATION . e PRC"ESS J NTROL PROGRAM shall pro-vide for the colier .on and testing of resentative test specimens from ch consecutive batch of t . same type of wet waste t oil at least 3 consecutive initia 'est specimens demons
- te SOLIDIFICATION. The PROCESS CONTROL ' GRAM shall be dified as required, as provided in Specificatio .14, to ssure SOL!DIFICATION of subsequent batches of waste.
De 55 '. 3/4 11-JI
&$) LEE CNLT 1 F"' r f b ,
I t_ J
3/4.12 RADICLOGICAL ENVIRONMENTAL PONITORING 3/4.12.1 MONITORING PROGRAM - LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be con-ducted as specified in Table 3.12-1. APPLICABILITY: At all times. ACTICN:
- a. With the rai ulogical e7virormental monitoring prcgram not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
- b. With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Conmission within 30 days from the end of the affected calendar quarter a re:: ort pursuant to 6.9.1.13. 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 limit level (1)(1)
- concentration limit level (2) (2) + ..11.0 When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifications 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; how-ever, in such an event, the condition shall be reported and des-cribed in the Annual Radiological Envirorcental Operating Report,
- c. With milk er #b '::#y /cg^tabi c ':re c ha#Mi om one or more of the sample locations requbed by Table 3.12-1, in lieu of any other report required by Scecification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report, which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples. The locations frem which samples were un-available may then be deleted from those required by Table 3.12-1, P.? : : '. 3/4 12-1 HeQ9 TEE QM\T \
F /; [ ic0
3/4.12 RACICLCGICAL ENVIRONf' ENTAL MONITORING 3/4.12.1 MCNITCRING PP0 GRAM . LIMITING CCNDITION FCR OPERATION (Continued) provided the locations from which the replacement samples were obtained are added to the envircreental monitoring program as replacement locations.
- d. The provisions of Specifications 3.0.3 and .3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be col-lected pursuant to Table 3.12-1 from the locations given in the table and figure in the 00CM and shall be analyzed pursuant to the requirements of Tables 3.12-1 and 4.12-1. P :: : 3/4 12-2 ncQUt28 UNIT I rcr 1, a? 7
TABLE 3.12-1 RADIOLOGICAL EtiVIR0flMEflTAL M0filTORifiG PROGRAM y '! w E i ;> Exposure Pathway N< Sampling and in i and/or Sample Sample Locationsa
- Type and Frequency Collection Frequency of Analysis C 1. AIRBORfiE 9 $ b c.p A i O 4 S
--i a. Radiciodine (Lutouiund i-a) and Partic- Continuous operation of Radioiodine canister..
ula tes sampler with sample col- frf*mA Tw%ie ^ ^115' 5 lection as required by P'f E l31 onenth G w q\e dust loading but at least once per 7 days. Particulate sampler.
^ ": ' S n. f e: you beta
<, J i _ t ;.# i.' il '.t, _ j ....'s M ;
f',11... ' .hamma i so top ic
&=
m . analysis on each sample L> ,,.. n,rmec. --- ~ < 10 L ;, . t;,u yerly a,c,u . ef 31 a ntre! :......!m;. ." . Ta .a 9mma i i; tor,ic m..ol,s,a un - , . - po,.R (t,, loa t. ..) : c!c u s. i co n unuc pa ;c uays.
~a N /[ [ty( $i005 Cc0 % dug id eqO" Q;) c) n
- 2. DIRECT RADIATI0fl -ftroentterrr-1-M w;w ootieeu o e Leas + od eMg &osi ghe C.
pg o v,<,
--,m. , n ., s
- - i.
gge , per 92 d nys . Garrviia dosen ^t .2st
..a 1 r,s t ; A fc: =
,,m. .n. a_ _m,, c .-
(y t' .as ly
- ca su. imj --At-t ea s t o r c m i,er ^2 Jays. "
,y. j a: ' . ecor ""g dose
- ,. q. -(kuud vut ;7 y ,_ ;= i e s 2 , . n v. m ,tnse w1 rate--a t-uch l ec 2 t i e" . it _; '
b3 typ of desi-At i m t nnce -.e, [ '. . (?? d2ys-.
- n. n. .,, - .te <_ <91 oc t ort )-
b5 W Sample loca tions are given on figure and t..ble in Offsite Dose Calculation Manual (00CM)
TABLE 3.12-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM f2 . e::
- s. :
- i xposure E Pathway Sampling and g _ani[or Sainple Type and frequency Sample Locations ** Collection frequency of Analysis 9-
- 3. WATERBORNE ,
Q b egltoDS
- a. Surface (Loc'tiens 0 and 10) Composite
- sample collected Ganina isotopic analysis over a period of < 31 days. of each compostte sample l by location. Tritium analy-sis of composite sample at least once per 92 days.
y L. ' v u,4 (L uca t i s,,3 11 m.,J l@ At-Icest o cc i.cr 92 J;ys. C; ; i;Jtch ic . ' tr i t ' - r-a: 1,;m; c f s :c' m ,Im. M
, j, b. Drinking (Lo atim.2 131"d Cc.pc;!!'.* c2 ple ce" acted '
131 c r lys i s o f c :6 M c d 'O M 3 C i- 2 IU^0d 0# O# U Y E* ' "' " 3 ' l ' " "' l ' I E - i ji4-l};c61,2,5 ^ i.c c- -- Composite
- sample collected Gross beta and ganina N' over a period of 131 days. isotopic analysis of each l C composite sample. Tritiom analysis of composite sample at least once per 92 days.
3 loeds.oAIS C . B. Sediment from ( Loca t i m... 1") At least once per 184 days. Shoreline Ganina isotopic analysis of each sample. Composite samples shall be collected by collecting an aliquot at intervals not ex
** Sample locations are shown on figure in the Ofisite Dose Calculation Manual (ODCM) ceeding 2 hours.
l CA- 1 1\{ . . [IsNA>d I,} '!
. )Mp. :.3 n
r ', c I, k*' i I i .j g a M fi d.. ttW r$- . .; -. f . , ,'; .,s; - *
- T_ABLE3.12-1(Continued)_
p . o i RADIOLOGICAL ENVIRONMErlTAL M0 tilt 0 RING PROGRNi e' c ,l y A Exposure Pathway c Sampling and Type and frequency and/or Sample Sainple Locations ** Collection Frequency c . . . _ of Analysis 9 4. IflGESTION . 4 LocA44045
- a. Milk (cuca u uns i7-hut At least once per 15 days Gamma isotopic and I-131 when animals are on pasture; analysis of each sample, at least once per 31 days a t other llines.
it . Fish and In-0UY k. (cuuauiuna c o, M 0:. vertebrates 12 c!e i" seesan. er kt Gamma isotopic analysis least once per 184 days if e" edible nactinne. OM t c e n ~u! . One sample of eck S a m.ple Mn each of the foilowing species: U 1. D 6 b, 3 Lockh, ops
- 2. ~ g;A 1ffsk SS
- c. f c e J ' ' : c t (Luath... 23 25) ~
Broad Lea pgg e Ganana isotopic analysis j ... m.o.m ,~,m.m... y gge 4 AKoD P'P ' _n s _1 tn ,>
-3
[}'] (Lu'a u mEM A t t . ...m m f ',a r;c t . One : 131 ;,,;lp h, c-) a o.y,1 m m f ' , 22 i !e3r N etatien. Sariiple liIcations are~shcwn on figure in Offsite Dose Calculation Manual
'3
-'s
,,-s 1 h, S'.
I
.. o /-, _ .
)
H H 's
-' ' ' i mg s t-r' j.
i 4 i b ati"21
- o .-
>j \ i g l's 4Q) t? ' * ' ' ,
TABLE 3.12-2 ei
' REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES S$
$[1 c
Reporting Levels 5 Water Airborne Particulate Fish Hilk Food Products j Analysis (pCi/l) or Gases (pC1/m3 ) (pC1/Kg. wet) (pCi/1) (pCi/Kg, wet) H-3 2 x 104 ( } 3 Mn-54 1 ' x 10 3 x 10 4 Fe-59 4 x 10 2 1 x 10 4 4 R Co-58 1 x 10 3 x 10 s. 2 4 n g Co-60 3 x 10 1 x 10 Zn-65 3 x 10 2 2 x 10 4 2m Zr-Nb-95 4 x 10
] I-131 2N % 9- ).D 3 1 x 10 2 Cs-134 30 10 1 x 10 3 60 1 x 10 3 Cs-137 50 20 2 x 10 3 70 2 x 10 3 g 2 g ! W)
Q Ba-La-140 2 x 10 3 x 10 2 y y ForTet2' drinking water samples. This is *40CFR Part 141 value. fer pareat and d>unhton, s, Mt PC b** lb) 10 totalevel I- 131 Malyses [L$
??f.
13 %
?K y_e r'
~ TABLE 4.12-1 RL' g, ', LOWER LIMITS Of DETECTION (LLD)"
P< I P c, b rea leg
$ Water Airborne Particulate Analysis Fish Milk f . cts Sediment (pCi/1) (pCi/kg, wet) (pCi/1) d3) (rCi/%,,.et) (pCi/kg. dry) gross beta h 4 1 10' 3
tl 2000 M So 15 gn 130 w 59 30 Fe 260 4 g 58,60 15 Co 130
.{ 6S jg 30 260 9b
/r-Nb 15 E
7x 10 -2 y 131, 18 1 60
- ' ? 134,13/
Cs ) . 18 5, b x 10
-2 130, @ 15$ 6 MD 150 140g ,_g3 15' 15' mux I _ _
C hb nn l 7 -u ,;.-
TARLE 4.12-1 (Continued) Ta8LE NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95", probability. ' 't' ""
;c ;b b i' t, :' ' ':c'; :0^:'W "; :t 2 b'2"' :b:2 "2ti:"
rc; :::-t: 2 " e2i" 4;":'. For a particular measurement system (which may include radio-chemical separation): s LLD = . b E V 2.22 Y exp(-AaT) where LLD is the icwer limit of detection as defined above (as pCi per unit mass or volume) sb is the standard deviation of the background counting rate or of the countir.g rate of a blank sample as appropriate (as counts per minute) E is the counting efficiency (as counts per transfor nation) V is the sample size (in units of mass or volume) 2.22 is the number of transformations per minute per picocurie Y is the fractional radicchemical yield (when applicab!e) A is the radioactive decay constant for the particular radionuclide
- aT is the elapsed time between sample coliection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples).
The value of ssused in the calculation of the LLD for a detec-tion system shaTI be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified N 3/4 12-8 ttAvt EF OWIT t R /; F; 17)
TABLE 4.12-1 (Continued) TABLE NOTATION theoretically credicted variance. In calculating the LLD for a radionuclide determined by gamma-cay spectrorretry, the back-ground shall include the typical contributions of other radio-nuclides nomally present in the samples (e.g. , potassium-40 in milk samples). Typical values of E, V, Y and aT should be used in the calculations.
- b. LLD for drinking water.
er or hpu, AdW ' 5 WW c-Q ,6g"e"~* p ue-d f: O' F. 4 d eht
- d. This does not mean that only the radionuclides in Table 4.12-1 are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall be identified and reported.
- e. %e e4 I ex Md dos e ya T- 131 ladwalslag tJme A4 A ll LocA +/oe/. is Less +he / m rem Gw I < v< l A N+1ys es wll\
Pto for , %se Qoc< Mo t h e rotd: cely p e r (o r hved , (og g ey, J I. / 3j AOMyses w; t\ b< p.tr (or d i( ab4ormal 06IE^5e5 otek r whit.h cold d e <A s ogab/7 resa.lf id IPCl /ll+er c[ I -131 i n driWhie$ W*4" ir g le.., ', -
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RADIOLOGICAL ENVIRC.'WENTAL MONITOPING 3/4.12.2 LAND USE CENSUS : LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall he conducted and shall identify the loca-tion of the nearest milk animal the nearest residence e-f e :2 ect
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APPLICA9fLITY: At all times. ACTION:
- a. With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3.1, pre-pare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report, in leiu of any other report, which identifies the new location (s).
- b. With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report, in lieu of any other report, which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days, if possible. The sampling, location excluding the control station location having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after (October 31) of the year in which this land use census was conducted,
- c. The provisient of Specifications 3.0.3 and 3.0.4 are not applicable.
_ Groac leaf vegetation sampling ray%Mbe perfomed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.
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RADIOLOGICAL ENVIRONMENTAL MONITORING . 3/4.12.3 INTERLABOPATORY COMPARISON PROGRAM j v'1clud.e. tn g@ LIMITING CONDITICfl FOR OPERATION
..3 Analyses shall be per#ormed on radioactive materials supplied pa rt an Interlaboratory Comparison Program which has been apper d by NRC.
APPL!CABILITY: all times. ACTION:
- a. With analyses not bei, "a .orred as required above, report the corrective action .a . to prevent a recurrence to the Cannission in th nual Radi ' qical Environmental Operating R epo rt ,
- b. The e visions of Specification 3.0.3 an 0.4 are not icable.
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. . INSTRUMENTATION _ BASES I 3/4.3.3.9 RADI0 ACTIVE LIOUID EFFLUENT INSTRUMENTATION 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. The alam/ trip setpoints for these instruments shall be calculated in accordance with procedures in the Offsite Dose Calculation Manual (0DCM) 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. 3/4.3.3.10 RADI0 ACTIVE GASECUS EFFLUENT INSTRUMENTATION The radioactive gasecus effluent instrumentation is provided to monitor and contrr', as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarn/ trip setpoints for these instruments shall be calculated in accordance with procedures in the Offsite Cose Calculation Manual (0DCM) to ensure that the alam/ trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and control-ing) the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is con-sistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. N B 3/4 3 4 Mc.40tRE VMIT 1 5/ 5
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3/4.11 RADI0 ACTIVE EFFLUENTS
*l BASES 3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioactive mateHals released in liquid waste effluents fren the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix 8 Table II, Column 2. Thi s limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II. A design objectives of Appendix I,10 CFR Pa rt 50, to an individual and (2) the linits of 10 CFR Part 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 i s the controlling radioi sotope and its MPC i n ai r (submersion) was converted to an equivalent concentration in water using the methods descMbed in International Commission on Radiological Protection (ICPP)
Publication 2. 3/4.11.1.2 DOSE Thi s specification is provided to impi enent the recui renents of Sections II. A, III. A and IV. A of Aapendix I,10 CFR Pa rt 50. The Liniting Condition for Operation impl ements the guides set forth in Section I!. A of Appendix I. The ACTION statements provide the requi red operating flexi-bility and at the same time implement the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the opera-tion of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirerents of 40 CFR 131. The dose calculations in the CDCM implement the requi rements in Section III. A of Appendix I that conformance with the guides of Appendix I i s to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equati ons speci fi ed in the CCCM for calculating the doses due to tne actual release rates of radioactive materials in liquid effluents are consi stent vd th the methodo-legy provided in Pegulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Peleases of Reactor Effluents for the Purpose of Evaluating Compliance vd th 10 CFD Part 50, Appendix I," Revi sion 1, Octcber 1977, and Regulatory Guide 1.113, " Estimating Acuatic Di spersion of Effluents #ren Accidental and Routine Reector Releases for the Purpose o# Impl e enting Apcendix I," Acril 1977 NUREG-0132 provides methods for dose calcul ations consi stent wi th Regulatory Guides 1.100 and 1.113.
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Y RAD'n AC !VE EFFLUE'T S RA STS This s;ecification a;nlies to the release of licuid ef fl uen ts f rom each reactor at the site. For units with shared radwaste treatment sys ter s , t he liquid e"l uents frrxn the s hared sys ten are propo rtioned anong the units sharing that sys tem. 3 /d .11.1.3 LICUID WAS'E T PEAT ?'ENT The OPERAPILITY of the liquid radwaste treatment sys tem ensures that this sys tem will be avail &le for us e whenever liquid effluents require treatment prior to release to the environment. The recuirenents that the appropriate portions cf this sys tem be used when specified provides assur-ance that the releases of radioactive materials in licuid ef#luents will be kept "as low as is reason &ly achievable." This specification impl e-ments the recuirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix I to 10 CFR Part 50 and desion objective and in Section II.D of Appendix A to 10 CFR Part 50. '"e :;ec i' icd ' i-i t: geve-aia; the = ^ c' ap p op - f a te ;^ rMens-of t N -14 9 u44--radwas t e t rc R c-t :p t r ' ^ 0 ;;cc-i-9 :d c; ;;/t ' c ' :c t i c c' t he dos e des iga cbj ec t i t es t c t 'a -t h da Oc;ian !!. A c' Arrendix I, In CF' ' art M, 'c 'iqud c'"uca*e. i 3/4.11.1.4 LICCID HOLCUP T Af7S Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled rel ease of the tanks ' contents , the res ul ting concentrations would be less than the limits of 10 CFR Part PO, 4pendix P Table II, Colunn 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area. 3/4.11.2 GASE0tlS EFFLUE?T S 3/4.11.2.1 CO SE RATE This specification is provided to ensure that the dose rate at any time at the site boundary fron gaseous effluents fran all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted a reas . The annual dose limits are the doses associated with the concentra-tions of 10 CFR Part 20, 4pendix B, Table II, Colunn 2. These limits provide reasonile assurance that radioactive material discharged in gaseous ef#l uents will not resul t in the expos ure of an individual in an un res tricted area, either within or outside the site boundary, to annual averace cnneen-trations exceeding the limits specified in Aopendix R, Table II of In CFR Part 20 (10 CFR Part 20.1C6(b)(1)). For individuals who may at times be within the site boundary, the occupancy of the individual will be suf ficiently Icw to co pensate for any increase in the atnospheric v. F-3/d 11-2 Me-@ TEE UN T l E/ 8,
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RADIO ACTIVE EFFLUENT S , BASE S di f f ts i o n fac to r ab ov e t ha t fo r t he s i te b ounda ry. T he specified rel ease rate limits restrict, at all times , the corresponding garca and beta dose rates above background to an individual at or beyond the site boundary to i 500 mren/ year to the total bcdy or to 13,000 mren/ year to the skin. These release rate limits also restrict, at all tines , the corresponding thyroid dose rate above background to an infant via the cow-nilk-infant pathway to i 1500 mren/ year for the nearest cow to the plant. This specification applies to the release of gaseous ef#luents from all reactors at the site. For units with s hared radwas te tre:tnent systems , the gaseous ef #i uents frm the s hared sys ten a re propo rtioned anong the units sharing that sys tem. 3/4.11.2.2 00 SE , t0 BL E G A SE S This specification is provided to implement the requirments of Sections II.8, III. A and IV. A of Appendix I,10 CFR Part 50. The Liniting Condition fcr Operation implenents the guides set forth in Sec+1on II.R of Appendix 1. The ACTION statenents provide the recuired operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." T he Su rv eil-lance Requirements impl e1ent the requirements in Section III. A of Acpendix I that confom with the guides of Appendix I to be shown by calculational procedures based on nodels and data such that the actual expos ure of an individual through the approcriate pathways is unlikely to be stbstantially und e res t ina ted . The dose calculations establis hed in the OCCM for calcu-lating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the nethodol~;y provided in Regul atory Guide 1.109, " Cal cul ation c# Annual Doses to Pan fror Poutine
eleases of Reactor Ef #1 cents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, Cctober In77 and Degulatory Guide 1.111, "Pethods fo r Es tinating Atmos phe ric T rars po rt and Dispers ion of Gaseous Effl uents in Routine Releases #rm Light 'e ater-Cooled Reactors ,"
l Pevision 1, July 1977. The ODCM ecuations provided #or detemining the air doses at the site boundary are based upon the bistorical average atmos-pheric condi tions . N!! REG-0133 provides rethods for dose calcul ations cons istent wi th Pegul ato ry Guides 1.109 and 1.111. 3/4.11.2.3 Dn SE , CACI 0ICDIPE S, RADIO AC'IVE PAT EPI AL I M PAC I rt'L AT : Fn ou AND RADIONUCLIDt'S OTH ER TH AN 'O PLi C A SE S This specification is prnvided to irpl erent the racui re'ents o# Sections II.C, III. A and IV. A of Appendix I,10 CFR Pa rt 50 he Liriting
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PADI0 ACTIVE EFFLUENTS . PA SE S : Conditians for Operation are the guides set forth in Section II.C of Appendix 1. The ACTION statements provide the requi red ocerating flexi-bility and at the 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 will be kept "as icw as is reasonably achievable." The CDCM calculational methods specified in the surveillance requi rements impl ement the requi re,ents in Section III. A of Appendix I that conforn-ance with the guides of Appendix I he shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are recui red to be consi stent with the methodology provided in Regulatory Guide 1.109, " Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Eval uating Compliance with 10 CFR Pa rt 50, Appendix I," Revi sien I, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Trans-po . and Dispersion of Gaseous Effluents in Poutine Releases from Light-Wa ter-Cool ed Reactors ," Revi sion 1, July 1977. These equations also pro-vide for detennining the actual doses based upon the historical average ~ atmospheric conditions. The release rate specifications for radiciodines, radioactive material in particulate form and radionuclides other than ncble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these cal cul ations were: 1) individual inhalation of ai rborne 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 subsequent exposure of man.
3/4.11.2.4 GASEDUS WASTE TREATMENT The CPERARILITY of the gaseous radwaste treatment systen and the ventilation exhaust treatment systems ensures that the systens will be available for use whenever gaseous effluents requi re treatnent orior to rel ease to the envi ronnent. The requi rement that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous ef#luents will be kept "as 1ow as is reasonably achievable." Thi s specification impl ements the requi re,ents of 10 CFR PaM 50.36a, General Design Criterion 60 of Appen-dix A to 10 CFR Part 50, and design objective Section !ID of Appendix I to 10 CFR Pa rt 50 S e spec #i-ed ' "i ts ;cve-ai~; the use :# ap -cr-iate pe-eti o ns -of tbc sys'es 9 e s?ci'i ed as a s"i tam e '*acti on # the dose d e ;i g :Mec t-ives-s** fe+t ' ! - "c:Mor,s I! . r>a nd !! . C of-Qpendi x I,^"" ra n !", fe r p scoz "l ueM-s,-- E ~~-1 R 3/4 11-4 11c Gpli2.5 GU(T l Qb \ \
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RADI0 ACTIVE EFFLUENTS RASE S 3/4.11.2.5 DOSE This specification is provided to meet the dose limitations of 40 CFR 190. The Speci fication requi res the prepa ration and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a real indivi-dual will exceed 40 CFR 190 if the individual reactors remain within the reco rti ng requi renent l evel . The Spacial Repor* will describe a course of action which should result in the limitation of dose to a real individual for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose connitnent to the real individual from other uranitn fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facili-ties at the same site or within a radius of 5 miles must be considered. 3/4.11.2.6 EXPLOSIVE CAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treatment system i s maintained bel cw the flammability limits of hyd rogen and oxygen. ( Automatic control features are included in the systen to prevent the hy-drogen and oxygen concentrations frca reaching these flammability limits. These autcmatic control features include isolation of the source of hydm-gen and/or oxygen, autcmatic diversion to recombiners, or injection o' di-lutants to reduce the concentration belcw the #lammability limits.) Main-taining the concentration of hydmgen and cxygen below their flammability limits provides assurance that the releases of radioactive materials will be centrolled in confomance with the requi renents of General Design Criterion 60 of Appendix A to 10 CFR Part 50. 3/4.11.2.7 GAS STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to an individual at the nea rest exclusion area bounda ry will not exceed 0.5 ren. Thi s i s consi stent wi th Sta nda rd Revi ew Pl a n 15. 7.1, "Wa st e Ga s Syst en Fai l ure. "
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hADICACTIVE EFF1.';ENTS BASES 3/4.11.3 SOLID DADIO/CT!VE WASTE The OPERAB!LITY of the solid radwaste syste, ensures that the system will be available for use whenever solid radwastes requi re processing and packaging prior to being shipped o'fsite. Thi s speci ficati on impl ements the requirments of 10 CFR Part 50.36a and General Design Criteria @ of Appendix A to 10 CFR Pa rt 50. The process pa rameters used in establi sh-ing the PROCESS CCNTRCL PROGRAM nay incluce, but are not limited to waste type, waste pH, waste / liquid / solidi fication acent/ catalyst ratios, wa ste oil content, waste principal chemical consti tuents, mixing and curing times. C-: M R 3/4 11-6 He.80t2.5 0y17 e
3/4.12 RADIOLOGICAL ENVIRCNMENTAL MONITCRING -
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BASES 3/4.12.1 MONITCRING PRCGRAM The radiological monitoring program required by this soecificatien provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation expsures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than ex-pected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience. The detection capabilities required by Table 4.12.-1 are state-of-the-art for routine envirorcental measurements in industrial laboratories. The LLD's for drinking water meet the reouirements of 40 CFR 141. For more complete discussion of the LLD and other detection limits, see the following: (1) HASL Procedures Manual, HASL-300 (revised annually). (2) Currie, L. A. , " Limits for Qualitative Detection and Quantitative Deter-nination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968). (3) Hartrwell, J. K. , " Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Ccacany Report APH-2537, (June 22,1972). f3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use af unrestricted areas are identified and that modifications to the monitoring orogran are made if required by the results of this census. The best survey infor: nation from the door-to-door, aerial or consulting with local agricul-i tural authorities, shall be used. This census satisfies the reouirements I of Section IV.S.3 of Appendix I to 10 CFR Part 50. ~
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. 5.0 DESIGN FEATURES - 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area -hll be as shown in Figure 5.1-1. LOW POPULA' ' 5.1.2 The low population zone shall be as shown in Figure 5.1-2. SITE BOUNDARY FOR GASECUS EFFLUENTS 5.1.3 The site boundary for gaseous effluents shall be shcwn in Figure 5.1-3. SITE BOUNDARY FOR LICUID EFFLUENTS 5.1.4 The site boundary for liquid effluents shall be shcwn in Figure 5.1-4
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