ML19220B662
| ML19220B662 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/15/1977 |
| From: | Jay Collins Office of Nuclear Reactor Regulation |
| To: | Regan W Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904270186 | |
| Download: ML19220B662 (17) | |
Text
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50*S2o DISTRIBUTIO*f:
n 15 El7 COCKET FILES 50-280/320 OSE Reading ETSB Reading Docket ;ios. 50-233/220 JTCollins reiOP1.'tDUh FCR:
W. H. Regan, Chief. Environ:r.ntal Projects Cranch 2. SSE FRCH:
J. T. Collins, Chief. Effluent Treatuent Systes Branch, OSE SUSJECT:
INTERIM EFFLUENT P.ADIOLOGICAL TECHNICAL SPECIFICATI0HS FCR TliREE HILE ISLMD NUCLEAR STATIC 3, UNIT HOS.1 MD2 REFEPE' ICE:
(1) PROPOSED INTERIM EFFLUENT PADIOLCGICAL TECIMICAL 5PECIFICATIC?is FOR THEEE MILE ISLAND HUCLEA7. STATION, UlIT NO. 2 transmitted under cover ac::orandua, same subject, fraca J. T. Collins to W. Regan, July 11,1977, and (2) EEVIEW CF APPLICMT'S ENVIRC'iME!!TAL TEGINICAL SPECIFICATIONS AND RADIOLOGICAL EMYIRONMENTAL TECINICAL SPECIFICATIONS PROCEDURES DOCU:EiT FOR TitREE ftILE ISilJtD,
'AIT NO. 2. ::eecrandiss from J. T. Cellins to W. Regan,Octoter 25, 1977 In responsa to your request and after discussions with your staff and with the applicant on Neverter 10, 1977, with raspect to the corres::ond-ence referenced abovo, we have prepared the enclosed effluent radiological Tecnnical Specifications for Three Mile Island Nuclear Statica, Unit
')
Mos. I and 2.
These are considered to be interim specifications and am based en the "as icw as practicable
- criteria in effect at the time of issuanca of the Unit 1 Tec.mical Specifications.
+
When the z.edel effluent radiological Technical Specificaticos, currently under davalopment by the staff to is:ple:nent the requirements of Apeendix I, bara been approved by NEC managesunt, we will revise L% specifications for Unit 3os. I and 2 to reflect these requirements.
! " 11
.2 J. T. Collins. Chief Effluent Treatment Systems Eranch 7904270\\@(o Division of Site Safetr and Environtental Analysis
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2.3 Radioactive Dischar es 2.3.1 Licuid Effluen s A c ol icabili ty Applies to the controlled release of radioactive liquids frcm TMI Unit Nos. I and 2.
Objective Objective To define the limits and conditions To ensure that radioactive liquid for the controlled release of liquid releases frcm the facility are radioactive effluents to the environs within the limits of Specifications 2.3.1 a. through e.
ta ensure that these releases are as i
I cw as practicable. These releases should not resul t in radiation exposures to of f site areas greater than a few percent of background ex po sures. The instantaneous re-leases rate for all effluent discharges should be within the limits specified in 10 CFR Part 200 To assure that the releases of radioactive liquids to off site areas meet the "as lcw as practicable" concept, the folicwing cbjectives apply:
- a. The annual total quantity of radioactive naterials in liquid waste, excludi.19 tritium and dis-solved gases, should not exceed 5 curies per radioactive waste-prcducing reactor, and the annual dos t to the whole bcdy or any organ of in individual should not exceed 5 rrem from the ccabined releases of Unit Nos. I and 2.
- b. The annual average concentration of radioactive materials in the effluent from the Mechanical Draft Cooling Towers prior to dilution in the Susquehanna River, excluding tritium and dissolved gases, should not exceed 2 x 10-8 uci/ml.
O 81'A94 C W ?, CJ::Di it % -c " S uti 2.u F.uMI W -
- CU'RTcl T5 i.
Objective (Cont' d}
- c. The annual average carcantration of tritium in licuid waste prior to dilution in the environment should not exceed 5 x 10-6 uCi/ml.
Soeci ficati on Specification a.
The radioactivity release Curing release of liquid radioactive concentration in liquid effluents wastes frca the Waste Evaporator frcm Unit Mos.1 and 2 to the.
Condensate Storage tank and the envirorment shall not exceed the Waste Evaporator Condensate Test values specified in 10 CFR 20, Tank, the following conditions shall Appendix B, for unrestricted areas.
be met.
b.
The total release of radioactive a.
The liquid gross activity liquid effluent frcm Unit Nos.1 and monitors (Unit 1: RM-L6; Unit 2:
2, excluding tritium and ncble gases, WCL-R-1311) or simil ar device, 2 l shall not exceed 10 curies per recorder on the radwaste effluent radioactive waste-producing reactor line shall be operable.
during any calendar quarter.
- b. The liquid gross activity f
c.
The equipment installed in the monitors (Unit 1: RM-L6: Unit 2:
liquid radioactive waste system WDL-R-1311) or simil ar device shall shall be naintained and shall be be set to alarm and autcmatically operated to process all radioactive close waste discharge valve (Unit 1:
liquid wastes prior to this discharge UDL-V-257; Unit 2: UCL-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 B for unrestricted art.as.
trititu 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 evaporator condensati excluding tritium and dissolved gases, test tank (Unit 2) shall be that can be discharged directly, to continuously monitored and rect ded the environs, shall not exceed 10 during release.
If this requirement curies.
cannot be met, continued release of 1iquid. effluents shall be permitted e.
Uhen the 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 /> radioactive ef fl uents, excluding provided that during this 48-hour tritium and dissolved gases, exceeds period two independent sampl es of 2.5 curies per radioactive waste-each tank shall be a ulyzed and two producing reactor during any calendar station personnel shall independently quarter, the licensee shall notify the check valve line-up prior to the NRC within 30 days, identifying the di sc ha rg e.
81 095
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t M i:CN 2.0 P ' i, 71M MOC 2' ;M T3 W
Scecification (Cent' d)
Sceci fication (Cont'd) causes and describing the : reposed d.
Facility records shall be main-program of action to recuce such tained of the radioactive ccccen-rel ase rates, trations and volume before dilution of each batch of licuid effluent released, and the average dilution flow and length of time over ahich each discharge occurred.
Radioactive liquid waste sampling e.
and activity analysis shall be perfor ned in accordance with Tabl e 2.3-1.
Prior to the relesse of each batch of liquid efflent, a sample shall be taken frcm that batch and analyzed for the concentration of each significant gamma emitter to demonstrate compliance with Specifica-tion "a" using the ficw into which the effluent is discharged.
f.
The licuid effluent adiation monitors RM-L6 and WDL-R-1311 shall be calibrated at least quarterly by means of a known radioactive source.
RM-L6 and UDL-R-1311 shall also have an instrument channel test monthly and a source check prior to each discharge to verify that the read-out device is indicating as expected.
g.
The ability of WDL-V-257 and KDL-V-99 to close autcmatically or receipt of a high radiation alam signal frcm RM-L6 and WOL-R-1311 shall be checked annually.
Bases Bases Liquid radioactive waste release
~ 1evels to unrestricted areas should Specifications a, b, and c, above be kept "as low as practicable" and require that suitable ecuipment to monitor the release of radioactive are not to exceed the concentration materials in liquid effluents are limits specified in 10 CFR 20.
The objective provides reasonable as-operating during any period these releases are taking place.
surance that the resulting annual exposure to an individual in of f site areas will not exceed 5 milli-The surveillance recuirenents given in the renaining specifications pro-rem per year. This assurance is based on the fact that the Suscue-vide assurancr that liquid wastes are preparly contro'11ed and monitored hanna River will dilute the licaid effluents upon their release from during any pl anned release of radio-active materials in liquid effluents81-096
-t-TABLE 2.3,-l Radioactive Liouid Uaste Scapl'ng and Analysis (4, 5)
A.
Monico.- Tank Releases Type of De tectabl e Samolino Frecuencv Activi ty Analysis Concentration (3)
-7 Each Batch Individual Gamma 5 x 10 uci/ml (2)
H-3 10 ' uci/ml Monthly Ccaposite (1)
Gross Aloha 10- uci/ml
-8 Sr-89 5 x 10 uci/ml
-8 Sr-90 5 x 10 uci/ml Notes (1) A ccmposite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged frcn the plant.
(2)
For certain mixtures of ganma enitters, it nay not be possible to neasure radionuclides in concentrations near this sensitivity limit when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using measured ratios with those radio-nuclides which are routinely identified and measured.
(3) The detectability limits for radioactivity analysis are based on the technical feasibility and on the potential significance in the envirarcent of the quantities released. For some nuclides, lower detection limits nay be readily achievable and when nuclides are measured bel cw the stated limits, t:iey shoul d al so be reported.
(4) The results of these analyses shculd be used as the basis for recording and reporting the quantities of radioactive material released in liquid effluents during the sampling period.
In estimating releases for a period when analyses were not performed, the average of the two adjacent data points spanninc this period should be used. Such estimates should be included in the effluent records and reports; however, they should be clearly identified as estimates, and the method used to obtain these data should be described.
(5) Deviations fecn the sin-iing/ analysis' regime will be notad in the report specified in
^
Sec tion 5. 5.1.
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IN RECHU " MT5 Bases (Cent' d)
B asas (Cont'd) the site. The ef fluents will be di-These surveillance recuirements - :-
luted by a fac:or of about 250 in the vide the data for the licensee and rsgion where finfi sh can exi st (with-the ccenission to evaluate the sta-in a one-quarter mile radius of the tion's performance rel ative to radio-di scnarge point). At the same time active liquid wastes released to the these specifications pennit tne flexi-env i rcrnen t.
Reports on the cuantities bility of operation, ccmpatible with of radioactive materials released in considerations of health and safety, to liquid effluents shall be furnished to assure that the public is provided a de-the Ccamission on the basis of Section pendable source of power under unusual 5.6.1 o# these Technical Specifica-operating conditions, which may tempor-tions. On the basis of such reports arily resul t in higher than normal re-and any additional infonnation obtained leases, but still within the concen-from 'he licensee or others, the Com-tration limis specified in ICCFR 20.
miss) ;n nay require the licensee to It is expected that by using this take appropriate action.
operational flexibility under unusual operating ccaditions, and exerting every effort to keep levels of radio-active material in liquid wastes as low as practicable, the annual -eleases will not exceed a small fractic..,f the annual average concentratio-
,i cs 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 nember of the general pub-lic can be exposed to liquids con-taining radioactive materials in excess of limits considered per-missible under the ccmmission's rules and regulations.
Specification b. above establishes an upper limit #ar the release of
.radioac tive liquid ef fl uents, ex-cluding tritium and dissolved gases, of 10 curies per unit dur-ing any calendar cuarter. The in-tent of this specification is to pennit the licensed the fl exibili-ty of operation to assure that the public is provided a dependable source of power under unusual cperating conditions, which nay temporarily resul t in releases higher than the levels normally 81-dS8
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2.3
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C SN: 2-D I5 C a s e s (C ont' d';
B ases (Cont'd) achievable when the scation and tne liquid radwasta equi nen: are func-tioning as designed. Releases of up to 10 curies per radicactiv e waste-cr:ducing reactor during acy calendar cuarter will resul t in concentrations of radioactive materials in liquid ef n cents at smali percentages of the limits specified in ICCFR 20.
Specification c. requires that the licensee shall maintain and operate the equipment installed in the liquid radioactive waste system to reduce the release of radioactive materials in liquid effluents to as icw as prac-ticable, consistent with tne require-ments of ICCFR 50.36a. ?!armal use and maintenance of installed ocuipment in the liquid radioactive system is expected to resul t in releases of not more than about five curies per radioactive waste-producing reactor per year, excluding trititm and dis-solved gases, during normal operations.
In order to keep releases of radio-active materials as low as practicable, i
the specification requires, as a min-imum, operation of equipment whenever 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 coeration listed under Specification b., the reporting recuirements of Speci-fication e.,
the requirenents of Section 5.6.2, delineate that the licensee shall identify the cause whenever the rate of radioactive ef fl uents, excluding tritium and noble gases, exceeds 2.5 curies per radioactive waste-procuci.1g reactor dur-ing any calendar quarter and describe the proposed program of action to re-duce such release rates. This report must be filed within 30 days folicwing the cal endar quarter in which the 2.5 curies rel ease occurred.
9 81-099
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2.3.2 Gasseus Ef fluen s Acolicabili v 4 plies to tne controlled elease of radioactive gases frcn EI Unit Nos. I and 2.
Cbjective Obfective To define the limits and conditions for the controlled release of radio-To ensure that radioactive gasecus active gaseous effluents to the releases fren the facility are with-environs to ensure that th=se releases in the limits of specifications.
are as icw as practicable. These releases should not resul t in radia-tion exposures in offsite areas great-er than a few percent of background ex po s ur.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 gases to offsite areas neet the as low as practicable concept, the foilowing cbiectives apply:
The release rate of radionuclides, a.
averaged over a yearly interval, ex-cept I-131 and particulate nuclides with half lives greater than 8 days, discharged frca Unit Nos. I and 2, should resul t in a dose rate at the site boundary of less than 5 nr~a/yr to the whole bcdy or any organ.
b.
The release rate of I-131 and other particulate radionuclides with hal f-lives lenger than 8 days, should resul t in a dose in the unrestricted area of less than 15 mrem /yr by in-halation or to the thyroid of a child through the cow-milk chain.
Specification Specification The instantaneous release rate of a.
gross gaseous activity except for Curing release of radioactive gasacus halcgens and particul ates with hal f-wastes, the following conditicns shall be ret:
lives icnger than eight days shall not exceed:
A.
During rele]se of gasecus waste frcn the waste gas decay tanks, the g.
3
};q h 1 1.5 x 10 following conditions shall be net:
5 Br 100
L a'-~ R; 2 0:- A c a ': Uria z.o
" 2 7 ^ m I # 9 rs W
W Scaci"ication I:caf )
Scecificacion (Conf di where Oj is the release rate in 1.
'..a ste gas discharge ren: tor uCi/ sec for isotoce i, and ";C i (Unit 1: RM-A7; Unit 2: UCG-R -l a2C )
(uCi/m ) i s t. e max imca pemi s-or simil ar device, shall b e crarable.
3 sible concen ration of isotope and defined in Accendix B, Table 2.
Auxiliary and Fuel Handline:
II, Column 1, ICCPR 20.
Cuilding and Unit Exhaust Vant exhaus:
gas, iodine and particulate acnitor b.
The instananeous release (Unit 1: PM-38; Unit 2: HP-R-219 ) cr rate of I-131 and particulates similar device, shall be operaole.
wi th hal f-lives greater than eight days, released to the en-3.
The waste gas decay tank discharge virons as part of airborne ef-valves (Unit 1: WCG-V47; Unit 2: WCG-fluents, shall not exceed 0.3 V-3CA or 303) s'1all be operable.
uCi/ sec.
4.
The waste gas decay tank discharge c.
The release rate of gross gase-valves (Unit 1: UDG-V?7; Unit 2: UCG-/-
ous activity shall not exceed:
30A or 303) shall be closed cn receipt of any one of the following conditions:
O i 4n 7(MPC)j - 2.4 x 10 a.
A high radiation sicnal frco the sec waste gas discharge nocitor (Unit 1:
RM-A7; Unit 2: WDG-R -1430 ).
when averaged over any calendar b.
A high radiation signal frcn the quarter.
Auxiliary and Fuel Building exhaust monitor (Unit 1: RM-A3; Unit 2: HP-d.
The elease rate of I-131 and R-219).
particulates with half-lives greater than eight days, shall not c.
A high ficw signal fecn the Waste exceed: 0.024 uCi/sec., when aver-Gas Decay Tank discharge ficw trans-aged cver any calendar c;uarter.
nitter (Unit 1: FT-123; Unit 2: WCG-FT-3923.
e.
Radioactive gaseous wastes coll ected in the gas decay tanks d.
Observation of loss of flcw shall be held up to a mininun of through the Unit vent.
45 days, except when the release rate shall not excead:
B.
During purge of the Reactor Buil-ding, the followings conditions shall Qi 3
be met:
3n
[MPCj - 3 x 10 1.
sec 1.
The deactor Building Purge Exhaus:
(noble gases)
Monitor (Unit 1: RM-A9; Unit 2: HP-R-225 and/or HP-R-226 and HP-R-219) or or sinilar device shall be operable.
2.
0.003 uCi/sec (icdine 131 and 2.
The Purge Exhaust Valves (Unit particul ates with AH-VIA and AH-V:3 and Dangers; hal f-lives grea ter Unit 2: C5125 A/D and D5129 S/C) tnan 8 days) shall be operable.81-101
Lir - a t.C3.:: :.
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9, b c.N 2.0 ru '-
- PfG5 i ' l -: 3 Sca:ification (Cc, t)
Sceci fication (Cont'd) f.
Radioactive 93s and particulates 3.
The valves (Unit 1: AH-7? A and purged frco tce reactor tuilding shall AMI3 and Dampers; Unit 2: 05129 A/O be fil tered tnrough tne nigh ef ficiancy and 35123 B/C) shall be intaricckea particul ate air fil ters and charcoal to cicse or recirculate, respectively 23sorcers on receipt of a high radiation sipai frco the Reactor Euilding Exhaust c.
The maxint.m activity to be con-Monitor (Unit 1: Pt-A9; Unit 2: H? -?. -
tained in one gas decay tank shall not 225 and HP-R-226 ) respec tively.
exceed 8800 curies (ecuivalent to Xe-133).
c.
The ficw rate for radioactive effluent streams and the Auxiliary h.
' hen the release rate of radio-and Fuel Handling Euilding and the active materials in gaseous wastes, Reactor Building, shall be monitored averaged over a calendar cuarter and recorded. Gaseous effluents frca
- exceeds, the !laste Gas Cecay Tanks and 3
?
Qi 3m the Reactor Building Purge Exhaust L
< 6 x 10 (MPC)1. -
sec shall be continuously ncnitored and recorded.
i (noble gas) or d.
0.005 uCi/sec (iodin *131 and Radioactive gaseous waste samoling and activity analysis shall be per-particulates with formed in accordance with Table 2.3-2.
hal f-lives greater than 8 days) e.
The waste gas decay tank effluent
.C monitor (Unit 1: RM-A7; Unit 2: ' CG the liceasee shall notify the !!RC with-in 30 days, identifying the causes and 1480) shall be tested using the in-stalled check source or ecuivalent describing the proposed pecgram of ac-prior to any release of radioactive tion to reduce such release rates.
gas frcn a holdup tank and shall be calibrated quarterly using a re-ferenced calibration source in a controlled reproducible gecmetry.
f.
During power operation, the con-densor vacuum pump discharge shall be continuously nonitored for gross gaseous activity.
The monitor shall not be inoperable for nore than a week. !lhenever this monitor is in-operable, a grab sample shall be taken daily and analy: ed for gross radioactivity. (3,Y ).
g.
Facility records shall be main-tained of radioactive concentration, release ratio and volune of each batch of gaseous effluents released 81 102 m
L.
' :.; CT,0iTIN R-
' D1 2.0 O TW G JU:PE: O T 5 Scecification (Cont'd) and the length of time over chich release cc:urred. Estimates of :ne error associated wi th each recorted value should be included in f acilicy records.
h.
At least annually, automatic initiation and closure of the Wasta Gas Decay Tank Discharge valve on alarm of (Unit 1: RM-A7 and RM-A8; Unit 2: WCG-R-1480) sball be verified.
- i. The Auxiliary and Fuel Handling Building and Reactor Building Purge Exhaust gas monitors for TMI-1 (RM-A8 and RM-A9) and the Unit ' lent monitors for BlI-2 (HP-R-219, HP-R-225, and HP-R-226), respectively, shall be calibrated at least every eighteen months by means of a known radioactive source. These detectors shall have an instrument channel test at 1 east monthly, and a sensor check at least daily, to verify that the read-cut device is indicating as ex pec ted.
Bases Bases The specified level s provide rea-Specificaticas a. through i. above, sonable assurance that the resulting recuire that suitable equipment to annual exposure rate fecm noble monitor the radioactive gaseous gases at any location.at the site releases are operating during any boundary will not exceed 1G millirens period these rel eases are taking per year. At the same time, these pl ace.
specifications permit the fl exibility of operation, ccmpatible with con-The surveillance requirements given sideration of health and safety, to under the renaining Specifications assure that the public is provided a above, provide assurance that dependable source of power under un-radioactive gaseous effl uents frca usual operating conditions, which may the station are properly controlled temporarily resul t in higher than the and monitored over the life of the design obj ective levels, but still station. These surveill ance within the concentration limits recuirements provide the data for the specified ICCFR 20.
It is expected licensee and the Ccamission to that using this operational flexi-evaluate the station's performance bility under unusual cperating con-relative to radioactive gasacus ditions, and by exerting every effort wastes released to the envircrmant.
to keep levels of radioactive material in gaseous wastes as lcw as practicable, Reports on the quantities of radio-the annual rel eases will not exceed a active material s rel easec in gasacus small fraction of the annual concentra-effluents shall be furnished :o tne tion limits specified in ICCFR 20.
Ccnmission on the basis of S!cti:n 81-103 TAELE 2.3-2 Radioacti/e Licuid Waste Sampling and Analysis (5) 5a.c a Tece Samoiinc.:recuency Tme of Activi ty Analysis Detectacle Ccncen ar o, !;,
Was e Gas Decav Tank Release Gas Each Tank H-3 10 uCi/cc
-6 Rel ease Individual Gamma Emitters 10' uCi/cc (2)
Reactor Buildinc Purce Relaases Gas Each Purge HI 10-6 uCi/cc Individual Gamma Emitters 10~ uCi/cc (2)
Condenser Vacuum Puno Releases Gas Monthl y-H-3 10~ uCi/cc Monthly (3)
Individual Gamma Emitters 10~ uCi/cc (2)
Auxiliary and Fuel Handlinc Suildino Exhaust Vent, Reactor Buildino Purce Vent and Uni t Exhaust (6 )
Vent Release Points Gas Monthly H-3 10-6 uCi/cc Individual Gamma Emitters 10- uCi/cc (2)
Cha rcoal Weekly (4)
I-131, I-133, I-135 10-12 uCi/cc Pa rticul ates Weekly Individual Gamma Emitters 10 ~ 0 uCi/cc (2) 1 Monthly Ccaposite Sr-89, Sr-90 10-l ~' uCi/cc Monthly Ccaposite Gross 10-" uCi/cc (1)
Tne above detectability limits are based on technical feasibility and' ca. the potential significance in the envircenent of the. quantities released.
For scce nuc.lides,,1 cue-detec tion limits may be readily achievable and '.inen nuclides are measured belcu the stated limi ts, they shoul d al so be recorted.81-104
- (2) For certain mixtures of ca. na e,itters, it nay not be tossibla to measure radicruclices at levels near -hair sensitivity lini:3 when other nuclides are present in the samnl e at much hi;rer l ev e's.
Urcer tnese circumstances, it will be more appropria te to calcu'. ate the level s of such raciacuclides using cbserved ratios in the gaseous ccaponent in the reactor c:cl ant for those raci0nuclides wnich are measurable.
(3) Analysi s shall also be performed folicwing each refueling period, start-up or similar operational occurrence which could alter the mixture of radionuclides.
(4) Sanpl ed during periods when no waste gas decay ta.:k release or reactor t:uilding purge is in progress.
(5) Deviations frca the sampling and analysis regime will be noted in the report specified in Section 5.6.1.
(6) The Auxiliary and Fuel Handling Guilding Exhaust Vent and Reactor Building Purge Vent per-tain to Unit 1 (TMI-1), while the unit exhaust vent pertains to Unit 2 (TMI-2).
s "e#
e e
81-105
Aa -
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2.u imM.,
200f0:~ C'il 5 ases ' Cont' d)
B asas (Ccnt' dl These ef forts shoul: include con-5.6.1 of these Technical Specifica-sideration of neteoroicgical ti on s.
On the basis of such reports c0nditions during rel eases, and any additional in forma tion tre Ccenission may obtain frcm the Tne annual cbj ectives ha>+ been licensee or others, the Commi ssion developed taking ir o account a may fecm time to time require the cenbination cf system variables licensee to take such action as the including fuel failures, primary Commission deems appecpriate, system leakage, primary to secondary systen leakage, and the performance of radionuclide removal mechanisms.
Specification a. above, requires the licensee to limit the con-centration of noble gases frem the station to levels specified in 10 CFR 20, Appendix B, for unrestric-ted areas. Based en a X/0 of 6.7 x 10 6 sec/m3, this specification provides assurance that no member of the general public would be exposed to radioactive materials in excess of limits specified in the Cctmi ssion's,rul es and regu-lations.
Specification b. above, requires the licensee to limit the concen-tration of I-131 and particulates with hal f-lives greater than eight days, released frcm the station to unrestricted areas to levels such that no individual will receive more than 1500 crem/yr to the thyroid. A grazing period of 6 montns has been applied to the radiciodines and to all radionuclides in particulate form with a half-lives greater than eight days, to allcw for the milk exposure pa thway. The release rate is de-termined by using the methodology of Regulatory Guide 1.109 (Rev.1) and a relative de osition factor (D/0) of 2.1 x 10-a n-2 The D/0 of 2.1 x 10-a m was calculated for the
-2 nearest cow located 1.2 miles SE of the station, using cn-site meteoro-logical data.
Specifications c. and d. above, estab-lish an upper limit for the release of gaseous activity at 15 percent of'instan-tanegus release linit of noble gases and 3t, algnt parcent nf the release rate of 1 31 and particul 3tes wi th hal f-lives81-106
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23595 (Cent' d) greater than 8 d3ys, averageo over any cal endar quarter, respectively.
The intent of tais s:ecif' cation is to permit the licensee the fl exicility of cphration to assure that the public is provided a decendable source of power under unusual operating conditions which may temporarily result in higher rel eases than the cbjectives.
Specification e. above, requires a 45 day holdup time for radioactive gaseous wastes collected in the gas decay tanks to assure decay of most radionuclides.
The whole body dose frca noble gases at the site boundary is expec*ed to be less than 10 meea/yr (primarily frcm -
K r-85 ). The thyroid dose frca radio-fadines and particulates at the nearest farm is expected to be less than 15 mren/yr.
Specification f. abcVe, limits the radioactivity that may be released to the environnent:to "as icw as prac-tic abl e. "
Specification g. above, limits the maxi-mum offsite dose to well belcw the limits of 10 CFR 1C0, postulating that the rup-ture of a Waste Gas Decay Tank holding the maximum activity reieases all of the contents to the atnosphere.
In addi tion to the limiting conditions for operation li.sted under a, b and c above, the reporting requirznents of Specification h. delineate that the licensee shall identify the cause when-ever the radioactive gaseous release rate exceeds 4 percent of Specification
- a. or 2 percent of Specification b.
above, averaged over a calendar quarter, and describe the proposed program of action to reduce such rel ease rates, The report must be filed within 30 days folicwing the calendar quarter in which more than twice the design release rate occurred.
o 81-107
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"e tacrol cgy and A cnic Energy, pp.112 d
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e 81 108