ML19220C461
| ML19220C461 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/18/1978 |
| From: | Herbein J Metropolitan Edison Co |
| To: | Regan W Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19220C460 | List: |
| References | |
| 780119, GQL 25, GQL-0025, NUDOCS 7905100120 | |
| Download: ML19220C461 (15) | |
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TABLE 2.3 -1 Radioactive '
aid liaste Sampling and Analysis (i, 5)
A.
?!cnitor Tank Releases
--.-=..--;
- -g=
~
=R-35 o g : =.
. - _ _. - d ::
-cegggggy3 g
- ~ ~ E&oifho~ F?eNsnc9R-Mi-J-
Activity Analy si s
- -- -C6nc Ent?a Gbd-C T' Each 5atch Individual Gamma 5 x 10' uci/ml (2)
' 10- uci/al Mol1thly Ccaposite (1)
Grcss Alpha 10- uci/ml
-0 Sr-89 5 x 10 uci/ml
-8 Sr-90
- 5. 10 uci/ml
.s 7"
Metes (1) A ccmposite sample is one in which the quantity of liquid sampi ad is prcportional to the quantity of liquid waste discharged frcn the plant.
(2) For certain mixtures of ganma emitters, it nay not be possible to neasure radionuclides concentrations near this sensitivity liait when other nuclides are prescnt in the sample in nuch greater concentrations. Under these circumstances, it wili be nore appropriate calculate the concentrations of such radionuclides using measured ratios.with those radi nuclides which are routinely identified and ceasured.
[3) The detectability limits for radioactivity analysis are based en the technical feasibil.
and en the potential significance in the environment of the quantities released.
For sr nuclides, lower detection limits cay be readily achievable and when nuclides are measure below the stated limits, they should also be reported.
(4) The results of these analyses should be used as the basis for recording and reporting t>
c;uantities of radioactive naterial released in liquid effluents during the sampling pari In estimating releases for a period when cnalyses were not performed, the average of the two adjacent data points spanning this period should be used.
Such estimates should be included in the ef fluent records and repor s; however, they shcul d be clearly identifie; as estimates, and the method used to cbtain these data should be described.
(5) Deviations frcm the sampling / analysis regine will be noted in the report specified in Section 5.5.t.
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u.
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2.0
. ;:. i N- :7-G "ECUIR;'#ii~f
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Scecificatico (Cent' d)
Soeci fication (Cont'd) cause.> :nd describing the pr: posed d.
Facility records shall be main-progran of action to reduce such tained cf the radioactive concen-ralease rates.
trations and volene before dilution of each batch of liquid effluent released, and the average dilution p cR THE par fc'45 "( * 'L ficw and length of time over which each discharge occurred.
c s c,s t. t s u,
he FM A t n M u m u
,-es F
f-
- e. :Radicad.*e-lig"M msh sbaplin m
C nCeD _FA g i0 0 g p e) s.
Per_rrij; sit.bIC-
?
.- -end activity adalysis shaTT bF ^ -
perfor ed in accordance with
-ror X e. n o r-ir wA E R
- s..,.L Tabl e 2.3-1.
Prior to the release Sc T n <- w t u c...
z_is t e d IM
.MA-1 of each batch cf liquid efflent> a sample shall be taken frca that bat:
and analy:ed for the concentration o T Ec W N i c A t_
cc eci i c AT io s ca ns t each sign 1ricant gam:a coltter to R usT 2G.
Th e_ r c f og. r, A PA N -
demonst{ ate ccapliance with Specific.
tion a using J:e ficw into wn:cn t:
effl"an*' is dis"^"a'm d GRAPH %O L L D Se Added to cAo As D**
f.
The liquid effluent radiaticn
-r o ll ow s.
monitors Rii-L6 and 'JCL-R-1311 shall Fo R TH E.'Pu r P s e s o r Tuis be calibrated at least quarterly by means of a known radicactive source.
R;1-L6 and UDL-R-1311 shall al so have
,, E.c t e. I c A,,. I CN ; The M PC.,( 16 8 b 8I e
an instrument channel test monthly Foe Ye - 13 3 L-
-3 s x to
, Ci /m /,
and a source check prior to each TN M PCs (ic a gove) ;,,, )p, _ g g y Qnage yo Ne@ ting as expected.
Bat de read-cut device is indica
-3w u,/,/o is I X to c
( see, A TA C H M E N T) 9 The ability of 'ACL-V-257 and UCL "-99 to close aut:matically on receipt of a high radiation alar a signal frcm RM-L6 and !lDL-R-1311 shal be checked annually.
Bases Bases Liquisi radioactive waste release Spec.fications a, b, and c, abcVe
' levels to unrestricted areas should require that suitable equipaent to be kept "as 1cw as practicable" and monitor the release of radioactive are not to exceed the concentration materials. in liquid effluents are limits specified in 10 CFR 20. The operating during any period these cbjective provides reasonable as-releases are taking place.
surance that the resul ting annual exposure to an individual in off The surveillance recuirenents giv:-n site areas will not exceed 5 milli-in the renaining specifications pre.
rem per year. This assurance is vide assurance that liquid uastes arc bas 2d ca the fact that the Susque-properly controlled cnd monitored hanna River will dilute the licuid during any pl annad release of radio-ef fluents upon their rel ease fren active materials in liquid effluents 26 007
Bases (Cont'dl Base-fCont'd) achievable when the station and the liquic radwaste equi;nent are func-tioning as designed. P.eleases of up to 10 curies per radioactive waste-producing reactor during an; calendar quarter will resul t in concentrations of radioactive caterials in liquid ef fluents at small percentaces of the limits specified in ICCFR 20.
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Specification c. requires that the m__ licensee shall maintain and cperate
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"Mrs=.=2=-. The equipment installed in the liquid
' -~~
radioactive waste system to reduce the release of radioactive naterials in liquid ef fluents to as icv as prac-ticable, consistent with the require-cents of 10CFR 50.35a. Normal use and maintenanen of installed equipment in the liquid - 'Ioactive system is expected to result in releases cf not more than about five curies per radioactive waste-prcducing reactor per year, excluding tritium and dis-solved gases, dur'ing normal operations.
In order to keep releases of radic-active naterials as icw as practicable, the specificaticn requires, as a min-imum, operation of equipment wherever the rate of release exceeds 1.25 curies per radioactive waste-producing reactor per quarter, excluding tritium and dis-solved gases.
In addition to the limiting conditions for oceration listed ender Specification b., the reporting requirements of Speci-fication
, the requirenents of Section
- 5. 6 ?, delineata that the licensee shall identify the causa whenever the rate.of radioactive ef fl uents, excluding tritium and noble gases, exceeds 2.5 curies per radicactive wasta-producing reactor dur-ing any cal er.dar quarter and describe the proposed pecgrcm of action to re-duce such release rates. This report nust F
~' led within 30 dcys folicwing the c r quarter in which the 2.5 curie _ rei 3e cccurred.
LO ueo e
' 0 CO:.0:. M 5 iOR ;ai;;. 1CM 2.0 rmniiC. M G REcuiN rags Bases (Cont'd)
Bases (Cent'd) the site. The ef fluents will be di-These surveillance requirenants pre-luted by a factor c' abcut 250 in the vide the data for the licens?e and ragica where finfish can exist (with-the ccnnission to evaluate the sta-in a one-quarter mile racius of the tion's performance relative to radi.
cischarge point).
At the same time active liquid vastes released to the these specifications pennit the flexi-envircr;nent. Reports on the cuantic bility of operation, ccmpatible with of radioactive materials released in considerations of health and safety, to licuid ef fluents shall b.e furnished
--- -assure -that-the ~chblic isgrcvidEd.a di=~. b__the-Ccamissic:r en.the..ha si.s_ ci Secti
= --
. p?id?ol e -scu ;ct of. power-under._u?+ Teal
~~5d.1 of thas{ Techanfa'r-spectifci--
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operating conditions, which may tempor-tions.
On the basis of such reacrts arily result in higher than normal re-and any additional infonnation cbtai leases, but still within the concen-frca the licensee or others, the Ccm tration liais specified in ICCFR 20.
mission nay require the licensee to It is expected that by using this take apprc;riate action.
operational flexibility under unusual cperating conditions, and exerting every effort to keep levels of radio-active material in liquid vastes as law as practicable, the annual releases will not exceed a small fraction of the annual average concentration limits specified in ICCFR 20.
Specification a. above requires the licensee to limit the concentration of radioactive materials in liquid effluents frcn the station to lev-els specified in ICCFR 20, Appendix B, for unrestricted areas. This specification provides assurance that no member of the general pub-lic can be exposed to liquids con-taining radioactive materials in excess of limits considered per-missible under the cc=missien's rules and regulations.
Specification b. above establishes an upper linit for the release of
. radioactive liquid ef fluents,~ ex-cluding tritiun and dissolved gases, of 10 curies per unit dur-ing any calendar cuarter. The in-tent of this specification is to permit the licensee the fl exibili-ty of operation to acsure that the public is provided a dep?ndable source of pcuer under unusual operating conditicns, which may cem;crarily result in releases higher than the levels nor:a'ly 9'
OnO LO Uu/
..s a
g t;-nie Sneci fica-ion (.or ' t)
Scr fication (Cond) where Dj is the release rate in 1.
Uaste gas discharge ncn.itor cCi/sec for isa tape i, and M?C j (Unit 1: Pf t-A7; Unit 2: UCG-R-1 50' (uCi/a ) is the maxiaca permis-3 sible concentration of isotcpe or similar device, shall be operabl, 2nd defined in Appendix S, Table
~
2.
II, Column 1, ICCFR 20.
Auxiliary and Fuel Handling Building and Unit Exhaust Vent exh+
b.
The instantaneous rel ease gas, iodine and particulate acniter (Unit 1: RM-A8; Unit 2: HP-R-21 g) rate of I-13' and particulates with hal f-lives greater than similar device, shall be gpe-able.
7
' ' r;_ ~
eight days, released.to.the en-
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3.
The ita ste gas deFir-tink~~dl5' h3-e_
~~ virons as part of airborne ef-fluents, shall act excead 0.3 valves (Unit 1:' WC3-U7i Dnit' 2: 'ir uCi/sec.
V-3CA or 303) shall be operable.
4 The vaste gas decay tank discher The release ate of gross gase-valves (Unit 1: ilDG-V47; Unit 2: UC c.
ous activity shall not exceed:
30A or 3CS) shall be closed en recei of any ene 'of the follcwing conditi; Oi Em y- (MFC)j - 2*4 x
O a.
A high radiation signal frco the see waste gas discharce acnitor (Unit.
RM-A7; Unit 2: WDG-R-l ?EO ).
when averaged over any calendar b.
A high radiation signal frca the qua rte r.
Auxiliary and Fuel Building exhaust monitor (Unit 1: RM-A8; Unit 2: HP-d.
The release rate of I-131 and R-219).
~
particul ates *sith hal f-lives greater than eight days, shall not exceed: 0.024 uCi/sec.,.ihen a< er-A high fi cw sianal fecm the Vast-c.
Gas Decay Tank discharge ficw trans-aged cver any calendar quarter.
nitter (Unit 1: FT-123; Unit 2: UCG-
.FT-3923.
Radioactive gasecus wastes
.11 ec ted in the gas decay tanks d.
shall be held up to a ninimum of Ob:ervation of Icss of flcw 45 days, except when the release 1.hrcugh the Unit vent.
rate shall not exceed:
B.
Coriac purge of the Reactor Buil--
ding, the follcwings conditions shall
-- ~~
Oi 3
be met:
3m e
< 3 x 10 1._ i MPCj ser 1.
-The Reactor Sailding Purge Exhau-(ncele gases)
Monitor (Unit 1: RM-A9; Unit 2: HP-R -
s 225 and/or HP-R-225 and HP-R-219) or or similar device shall be operable.
2.
0.003 uCi/sec (icdine 131 and 2.
The Purge Exhaust Vaives (Unit particul ates with AH-VIA and AH-VIS and Dac;ers; hal f-lives greater Unit 2: D5129 A/D and 05L2g 3/C) than 8 days) shall be operable.
LU Ul V
. _. _.. = -
..v..
c.v
- : c.< : a.n:m :g:r;,g 2.2.2 geseous Ef fhe -
Acolicability Applies to the controlled release of radioactive gases frca '!I Unit
? c s. 1 and 2 ) en 'A. per<. MAcTM (2 m i g,
Cbjective Objective To define the limits and conditions To ensure that radioactive casecus for the controlled release of radio-releases frca the facility.are with active gasecus-ef fluents to the.
__ win. theilieits_o f specificaticas. -
._engrcas ta ensure that these releasas.2
~
- - - - - - - - - - - -. ~ ^ ' - -. "
n are as lcw a s practicable.
These rel eases s, 1d not resul t in radia-tion expost...s in offsite areas great-er than a few percent of background exposur.es. The instantaneous release rate for all effluent discharges should be within the limits specified in ICCFR 20.
To assure that the releases of radio-active cases to offsite areas neet the as icw as practicable concept, the follcwing cbjectives apply:
/
The release rate of radionuclides, a.-
averaged over a yearly interval, ex-cept I-131 and particalate nuclides with half lives greater than 8 days, discharged frcm Unit ?!cs.1 and 2, should result in a dose rate at the site b undary of less than 5 mrea/yr
'l' to th;. shole body or any organ.
b.
The release rate of I-131 and other particulate radionuclides with hal f-lives longer than 8 days, should result in a dose in the unrespred
__ G'o.g hacTog area of 1ess than 15 cren/yr7hy in-halacion er to the thyroid of a child through the cow-milk chain.
Scecification Specification a.
The instantaneous release rate of Curing release of radioactive gasecu:
gr0ss gaseous activity except for ucstes, the follcuing conditions hal ogens and particul a tes with hal f-sh211 be ret:
lives longer than eight days shall not exceed:
A.
During release of gasecu3,;a s t 3 frc-the vaste gas decay tanks, the y
Q4 g3 follcui.; condicions shall be ne t:
(ne !; - l.5 x 10~
-;.~
sec 26 011
'5r.eci Tication (Cont' di Sc=-ification (Cont' d) f.
Radioactive gas and particul ates 3.
The valves (Unit 1: AH-VIA c.d purged frcm the reactor building shall AH-VIS and Canpers; Unit 2: 05 29 e be fil tered through the high ef ficiency and D5129 8/C) shall be intarlockec particulate air fil tars and charcoal to close or recirculate, respecti n abscebers on receipt of a high radiation sipr frcm the Reactor Building Exhaust g.
The maximta activity to be con-tion tor (Unit 1: RM-A9; Unit 2: F?-
4 tained in One gas decay tank shall not 225 and HP-R-225) respectively.
exceed ESCO curies (equival ent to Xe-133).
c.
The fl ow rate for radioac tive g,- -Q iE t6_r_ei ea se ra te~ o f radi6._
m- - =A.ffhen;-5tveaps-ar.1;.he-EP31Try
-= =. =r.
a
~
- --M fpal_ Handling. Sail.6afans t.V
-ective m~ tern s in gaseous wa stes, -
' Reactor Euilding, shall be acnitort averaged c.
calendar cuarter and recorded. Ga seous effluents fr
- exceeds, the Waste Gas Decay Tanks and 3
[-
Qi 3m the Reactor Building Purge Exhaust
< 6 x 10 sec shall be continuously acnitored and (MPC)1 recorded..
o (neble gas) or d.
Radioactive gaseous waste sampl-0.0C6 uCi/sec (icdine-131 and and activity analysis shall be per-particulates with formed in accordance with Tabie 2.2-hal f-lives greater than 3 days) e.
The was'e gas decay tank effluer
. f, monitor (Unit 1: RM-A7; Unit 2: WCG-the licensee shall notify the ?!?C with-1480) shall. be tested using the in-in 30 days, identifying the causes and stalled check source or ecuivalent describing the prcposed progran of ac-prior to any release of radioactive tion to reduce such release rates.
gas frem a. holdup tank and shall be calibrated quarterly using a re-ferenced calibration source in a controll ed reproducibie geometry.
f.
During power operation, the cen-densor vacuum pump discharge shall b continuously monitored for gross gasecus activity.
The monitor shall not be inoperable for more than a week. Uhenever this monitor is in-operable, a grab sample shall be taken daily and analyred for gross radioactivity. (3 r ).
i g.
Fact' ~ty records shall be main-tained of. licactive concentration, release ratio and volune of each batch of gaseous efnuents released 26 0'.2
' ; * - ~ ~.' s..? ( e s,3 * ~ ~ < $ : r. ).
r.).~ ; s "s.m,.u y
f p s, l. (.)..; s.' ?3 i. ;r y.; ;.- : c ;.r $
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. e u.a Sceu. ficatica (Cont' d) and the length of time over v.hich rel ease cccurred. Estinates of the error associated with each reported value should be included in facility records.
h.
At least annually, autcoatic initiation and cl osure of the Wa s'.e Gas Decay Tank Discharge valve on
~
~
al ar: cf (Unit.1: RM-A7 and RM-A3; I? '__.._
~
WDR-R-id30) shall: be veri.fiec Unit 2:
c
- i. The Auxiliary and P:el Handling Building 31d Reac tor St ilding Purge Exhaust gas monitors f r THI-1 (RM-
~ ~~
A8 and R:1-A9) and the Init Vent monitars for'TMT-2 (HF R-219, HP-R-225, and HP-R-226), respectively, shall be calibrated at least every eighteen conths by means of a known radioactive source. These detectors shall have an instrument channel test at least =cathly, and a sensor check at least daily,. to verifv that the 5
.r read-cut device is indicating as expec ted.
~
Eases Bases The specified levels provide rea-Specifications a, thrcugh i. above, sonable assurance that the resul ting require that suitable ecuipment to annual exposure rate frca noble acnftar the radioactive gasecus gases at any location at the site releases are operating during eny bcundary will not exceed 10 millirems period these releases are taking per year. At the same time, these pl ac e.
specifications permit the flexibility of cperation, ccapatible with con-The surveillance recuirements given sideration of health and safety, to under the renaining Specifications assure that the public is provided a above, provide assurance that depencable source of power under un-radioactive gaseous effluents feca usual Operating conditions, which nay the station are properly controll ed tanpararily resul t in higher than the and monitored over the life of the design objective levels, but still station. These surveillance within the concentration liaits requirements provide the data for the specified ICCFR 20.
It is expected licensee and the Ccamissien to that using this operational flexi-evaluate the station's perfernance bility under unusual cperating con-relative to radioactive gasecus ditions, and by exerting e/ery effort va stes rel eased to the envircraent.
tn keep level.s of radicactive naterial in ga ecus,ta stes as Icw as prac ticable, Reports on the quantities cf radic-the annual releases aill r.ct exceed a active nateriais released in gasecus sna!! fra: tion of the annual concentra-ef fluents shall be furnished to the tion li-ics specified in ICCF? 20.
Cccaission er the basis of Sec;ica 26 0!3
' (2)
For cer ain nixtures of garna e.1itters, it nay not be cessible to measure radionucl des 5 12 Val s near their sensitivity limits when other nuclides are present in tna samnl e at r :c higher level s.
Uncer these circumstances, it will be nere appropriate to calculate the level 5 of such radianuclides using cbserved ratics in the gaseous ccaponent in the react:
coolant for those radionuclides which are mea:urable.
(3) Analysis shall also be performed follcwing each refueling period, start-up or similar
_._ _.caerational occurrence which coul d al ter the mixture of radionuclides.
.m e
--i41--5enpl ed during periods.. hen no waste gas decay tank rel ease er reactor bteilding purge' is prc'; ra s s.
(5) Deviations frca the sampling and analysis regime will be noted in the report specified ir Section 5.6.1.
(5) The Auxiliary and Fuel Handling Buil ding Exhaust ' lent and F.eact'..- Euil ding Purge Vent per-tain to Unit 1 (TMI-1), while the unit exhaust vent pertains to Unit 2 (T:!I-2).
O e
s
.-(
e-e i 1 LU
TABLE 2.3-2 Radioactive Licuid Masta Sampling and Analysis (5)
S aac' e T vre S amoline F recue.,cv Tvoe of Activity Analvsis Detectacle Concentra:icn (
Wasce Gas Decay Tank Release
_g
. _ _._Ga s Each Tan'<.
._. = = ::. =
.._g=._m=== 10x :.~V C f /.c c. n. r..
T=
_me
.., c _._._ a_._-
.m.
Rel ease Individual Gamma Emitters 10 ' uCi/cc (2)
Reactor Suildinc ? urge Releases Gas Each Purce H-3 10 5 uCi/cc Individual Gamma Emitters 10 UCi/cc (2 )
Condense-Vacuum Pumo Releases Gac Monthly-H-3 10- uCi/cc
-z Monthly (3)
Individual Garma Emitters 10 uCi/cc (2)
Auxiliary and Fuel Handline Buildinc Exhaust Vent, Reactor Buildinc Purce Vent and Unic Exnaust (6)
Vent Release Points (I)(:)
G A.S cog m uou c, R.o ss (@, D 10 6
Gas Monthly (4.)
H-3 10 uCi/cc
~,
Individual Gamma Enitters 10 ' uCi/cc (2)
~19 Charccal Ueekly Ckd I-131, I-133, I-135 10
~ Ci/cc u
-10 Particul ates Weekly Individual Gamma Emitters 10 Ci/cc (2)
Monthly Ccmposite Sr-89, Sr-90 10-11 tCi/cc 1
Monthly Cenposite Gross
?_e 10 ~1 uCi/cc (1) ine accve detectabilicy limits cre based on technical feasibility and cn the potential significance in the envircr,ent o f the. cuan ti tics rel eased. For some nuclides, ic :er detectica limits may be readily achievable and uren nuclides are measured belc., the stat :
l imi ts, they shoul d cl 30 be reported.
9' n1v c0 U1J
~~--
-- T.MC '. CC.':0. ~ ICM 5 ' C? 2?Fi ~ICM 2u O G'M DOI -
U
~
r Objective (Cont'd)
- c. The annual average concentration cf tritica in licuid waste prior to dilution in the envircement should not exceed 5 x 10-5 uCi/ml.
Saecification Saecification r
2
..,f a.
The radioactivity release
.Ru ring.rel ea ss~.o f-l iquid _radi c.acti v e
' ""^^ ~"
c;ncentration in licuid effluents wastes from the Uaste Evapora cr feca Unit Mos.1 and 2 to the.
Condensate Storage tank and the envircraent shall not exceed the Waste Evaporator Condensate Test values specified in 10 CFR 20, Tank, the follcwing cc.nditions shall Appendix B, for unrestricted areas.
be met.
b.
The t tal release of radioactive a.
The liquid gross activity liquic ef fluent feca Unit Hos. I and conitors (Unit 1: RM-L5; Unit 2:
2, excluding tritium and noble gases, WCL-R-1311) or similar device, and sha11 not exceed 10 curies per recorder on the rad.iaste effluent radioactive waste-prcducing reactor line shall be operable.
during any calendar quarter.
.f
- b. The licuid gross activity c.
The equipment installed in the monitors (Unit 1: RM-tS; Unit 2:
liquid radioactive waste system UDL-R-1311) er similar device shall shall be maintained and shall be be set to alarm and autccatically operated to process all radioactive close waste discharge valve (Unit 1:
liquid wastes prior to this dischar.ce UOL-V-257; Unit 2: WCL-V -99 )
when the activity release rate will respectively prior to exceeding the exceed 1.25 curies per radioactive limits specified. in 10 CFR 20.
waste producing reactor, excluding Appendix 9 for. unrestricted areas.
tritium and dissolved gases, during any calendar quarter.
c.
Liquid waste radioactivity and ficw rate frca the waste evaporator d.
The maximum radioactivity to be condensate storage tank (Unit 1) contained in one liquid radwaste tank, and the waste evaporatcr condensate excluding tritium and dissolved gases, test tank (Unit 2) shall be that can be discharged directly, to continuously monitored and recorded the environs, shall not exceed 10
_during rel else.
If this requirement curies.
cannot be met, continued release of liquid. effluents shall be permitted e.
Uhen t;e average release rate of only during the succeeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> redicactive effluents, excluding provided that during this 4S-hour tritium and dissolved gases, exceeds period tuo independent sanples of 2.5 curies per radicactive wa ste-each tank shall be analyzed and t,co producing reactor during any calendar station perso nel shall independentl:
qu2rter, the licensee shall noti fy the chec'< val ve line-up prior to the NP.C within 30 days, identi fying the discharge.
9i n i (J gg UI
J2. 3 c.adicactive Di schar;es 2.7.1 Licuid Ef fluen s Acalicability Apolies to the controlled release of radioactive liquid; from TMI Unit Mos. 1 and 2.
Objective-
_ Objective. _ _ _..
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To define the limits aEd' conditions
'Tc~ ensdPe tha t racicactiFE~ liquid '
for the controlled release of liquid releases frca the facility era radioactive effluents to the environs within the limits of Specifications to ensure that these releases are as
' i 2.3.1 a. through e.
i cw as practicable. These rel eases shoul d not. resul t in radiation exposures to off site areas greater than a few percent of background.
exposures. The instantaneous re-leases rate for all effluent discharges should be within the li its specified in 10 CFR Part 20; To assure that the releases of radicactive liquids to off site areas meet the "es icw as practicable" concept, the following cbjectives apply:
- a. The annual total quantity of radioactive materials in liquid waste, excluding tritium and dis-solved gases, should not exceed 5 curies per radioactive waste-producing reactor, and the annual dose to the whole body cr any organ of an individual should not exceed 5 cre.1 frca the ccabined releases of Unit Hos. 1 a'HH 2.
-~
- b. The annual average concentration
~
of radioactive materials in the ef fluent frca the Mechanical Draft Cooling Towers prior to dil~ tion in the Susquehanna River, excluding tri ti u.
and dissolved casas, should not exceed 2 x 10-3 uc'/nl.
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Sases (Cont'd) greater than 8 days, averaged ever any cal endar quarter, respectively.
The inter.t of this specification is to pennit the licensee the flexibility cf operation to assure tha: -he public is provided a dagendable scurce of po..er under unusual operati,ng conditions which may temcorarily resul t in higher rel eases than the objective.s._. - -. -..
-.".fc, =- 5 1-
- Specification e. above,~ recuires a 45
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day holdup time for radicactive gaseous wastes collected in the gas decay tanks to assure decay of cost radionuclides.
The whcle body dcse frca ncble cases at the site boundary is expected to be less than 10 cren/yr (primarily frcn K r-85 ).
The thyroid dose feca radio-iodines and particulates at the nearest farm is expected to be less than 15 cre.n/yr.
Specification f. above, limits the radioactivity that may be released to the environment:ta "as icw as prac-ticab l e. "
Specification 9. above, limits the maxi-cua offsite dcse to well belcw the linits of 10 CFR 1C0, postulating that the rup-ture of a 'Jaste Gas Decay Tank holding the maximun activity releases all of the contents to the atmosphere.
In addition to the limiting conditions for cperation listed under a, b and c abcve, the reporting requirements of Specification b. delineate that the licensee shall identify the cause when-ever the radioact.iye gasecus release rate exceeds 4 percent of Specification
- a. or 2 percent of Specification b.
above, averaged cver a calerdar quarter, and describe the proposed program of action to reduce such release rates.
The report rust be filed within 30 days follcuir.g the calendar cuarter in which more than twice the design release rate occurred.
26 010
n_ ; :: : w.u :_q (1) ifetecralegy and At:mic Energy, pp. 204 (2 )
l!etecr:Ic9y and At:nic Energy, pp.112
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