ML19220B971
| ML19220B971 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/19/1977 |
| From: | Regan W Office of Nuclear Reactor Regulation |
| To: | Herbein J METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7904280019 | |
| Download: ML19220B971 (18) | |
Text
..,
s%
DEC 19 #
DISTRIBUTI0f1
[ Dockets (EttVIR0:1)
Docket Ro. 50-320 gc p3g Local PDR f1RR Reading DSE Reading Metropolitan Edison Company EP-2 Reading Am: Mr. J. G. Herbein WRegan/J:lorris Vice President itDuncan P. O. Scx 542 RBores, Region I.
Rsading, Pennsylvania 19603 JMcGurren, OELD RVollmer Gentle: ten:
WKreger Enclosed are proposed interim radiological Technicb hbications for Three Mile Island & clear Station, Unit No. 2.
These specifications represent agnement mached between cur technical staff and your representatives. They are interim specifications and are based ca the "as low as practicable" criteria in eff:a at the tir.e of issuance of the Unit Ha.1 Technical Specifications.
When the codel effluent radiological Technical Specificaticns, currently under develop:ent by the staff to implement the requirenents of Appendix I, have been approved by NRC ranagement, we will revise the specificaticas for Unit nos. I and 2 to reflect these requirenents.
'If you wish to discuss these specifications further with our staff, please contact Mr. Jan A. hoevis, Envirer-tal Project Manager, at (301) 492-8437.
Sincerely.
Drain 3 siced by W. if. %
Wa. K. Pagan, Jr., Chief Envirmtsi Projects Branch 2 Division of S1ta Safety and Envircreental Jaalysis Enclosura:
1
)QRh,,b Tech. Spec. for DCTd g g6 43%I@
d Eb Gai c o,
mm.
UC/
L D SE S - ?.
DSE:EP 2 DSE:EP,2 t
.,,,,s, M
JNaNi h M
n summau s >
\\
_Q/.}f /.7J...
..-.-12/M/-77--.
M/I'l/-77---
04?s >
NEC POR.M 318 (9 7e) NECM 0240 W un e. eovummu swr ememme arric s een - ese.4s4 7 00428 0Dt9 '
l
2-tetrcoolitar tcison Lormany cc w/ enc 1:
GFU Service Corporation ATTN: Mr. T. Gary Broughten Safety and Licensing Manager 260 Cherry Hill Road Parsippany, New Jersey 07054 C. F. Trewbridge, Esquire Shaw, Pitt: nan Potts & Trownridge 1800 M Street, N. W.
Washington, D. C.
20036 Dr. Chauncay R. Kepford Bcx 1093 Jackson Wyoming 83001 The Henorahla Karin W. Cartar Assistant Attorney General Office of Enforcement Dept. of Environmntal Rescurces 709 Health and Welfare Building Harrisburg. Pennsylvania 17120 Lawrence Sager, Esquire Sager and Sagar Associates 45 High Street Pottstown. Pemsylvania 19464 Dr. Chauncay Kapford Citizens for a Safe Envircreent
& York Coccittee for a Safe Envirement 2586 Broad Street York, Pennsylvania 17404
~'
}
F 84-212 o-.-
WURMAart &
DATS >
NRC PORM 318 (9-76) NRCM 0260
- k u. s. eav e.=wemy em= sea ornc., s.ve - ea*4a4
. Lili!ILG COSII E1# WCh M
fCIII
!D'G ECUIRF.f EtlTS 2.3 Radioactive Discharces 2.3.1 Licuid Effluents A cai tcability Applies to the controlled release of radioactive liquids frca 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 frca the facility are radioactive ef fluents to the environs within the limits of Specifications to ensure that these releases are as 2.3.1 a. through e.
i I cw as practicable. These releases should 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 limits specified in 10 CFR Part 20; To assure that the releases of J
radioactive liquids to off site areas meet the "as icw as practicable" concept, the following objectives apply:
- a. The annual total quantity of radioactive naterials 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 or any organ of an individual should not exceed 5 mrem from the combined releases of Unit Hos.1 ali[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.
84~213 s
. ~. -
t.
, M 7 ? ' C C h 0 I i G N 5
' '9En !CN 2.0 ftCN ii:
% REQUIR$%1TS Objective (Cont'd)
- c. The annual average concentration of tritium in licuid waste prior to dilution in the envicornent should not exceed 5 x 10-6 uCi/m).
Soecification Scecification a.
The radioactivity release During release of liquid radioactive concentration in licuid effluents frcm Unit Mos.1 and 2 to the.
wastes frca the Naste Evaporator enviror. ment shall not exceed the Condensate Storage tank and the values specified in 10 CFR 20, Waste Evaporator Condensate Test Tan't, the following conditions shall Appendix B, for unrestricted areas, be met.
b.
The total release of radioactive liquid effluent frem Unit Mos.1 and The liquid gross activity e.
monitors (Unit 1: RM-L6; Unit 2:
2, excluding tritium and noble gases, WDL-R-1311) or similar device, and shall not exceed 10 curies per radioactive waste-producing reactor recorder on the radwaste effluent during any calendar quarter.
line shall be operable-f c.
The equipneht installed in the
- b. The liquid gross activity monitors (Unit 1: RM-L6; Unit 2:
liquid radioactive waste system shall be naintained and shall be WDL-R-1311) or similar device shall operated to prccess all radioactive be set to alarm and autcmatically close waste discharge valve (Unit 1:
liquid wastes prior to this discharge UDL-V-257; Unit 2: WDL-V-99 )
when the activity release rate will exceed 1.25 curies per radioactive respectively prior to exceeding the limits specified.in 10 CFR 20.
waste producing reactor, excluding Appendix B for unrestricted areas.
tritium and dissolved gases, during any calendar quarter.
Liquid waste radioactivity and c.
ficw rate frca the wasta d.
The maximum radioactivity to be craporatcr contained in one liquid radwaste tank, condensate storage tank (Unit 1) excluding tritium and dissolved gases, and the waste evaporator condensate that can be discharged directly, to test tank (Unit 2) shall be the environs, shall not exceed 10 continuously monitored and recorded curies.
_during release.
If this requirement cannot be met, continued release of When the average release rate of liquid. effluents shall be permitted e.
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 effluents, excluding provided that during this 48-hour tr"tir, and dissolved gases, exceeds 2.5 curies 'per radioactive waste-period two independent -' pies of producing reactor during any calenuar each tan'< shsll ue analyzed and two station personnel shall indeper.dently quarter, the licensee shall notify the check valve line-up prior to the NRC within 30 days, identifying the discharge.
84^214 o,-,pm*
m
L.
~ ~~3 x.G i ~: m ; : >
v.;. !:C1 2.0
- % TO WG HECulR :. M T5 Scecification (C ont' d)
Scecification (Cent'd) causes and cescribing the pecposed d.
pecgran of action to reduce such Facility records shall be rain-release rates, tained of the radioactive ccreen-trations and volume before dilution of each batch of licuid ef fluent released, and the averace dilution ficw and length of time over ahich each discharge occurred.
Radioactive liquid waste sampling e.
s and activity analysis shall be perfonned in accordance with Tabl e 2. 3-1.
Prior to the release of each batch of liquid efflent, a sample shall be taken frcm that batch and analyzed for the concentration of each significant gamma enitter to demonstrate ccmpliance with Scecifica-tion "a" using the ficw into which the ef fluent is discharged.
f.
The liquid effluent radiation monitors RM-L6 and WDL-R-1311 shall be calibrated at least cuarterly by means of a known radioactive source.
RM-L6 and UDL-R-1311 shall al so hrte 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 WCL-V-257 and UDL-V-99 to close autcmatically on receipt of a high radiation alarm signal frcn RM-L6 and WDL-R-1311 shall be checked annually.
Bases Bases Liquid radioactive waste release
' levels to unrestricted areas should Specifications a, b, and c, above be kept "as low as practicable" and recuire that suitable equipment to are not to exceed the concentration monitor the release of radioactive materials. in liquid effluents are limits specified in 10 CFR 20. The objective provides reasonable as-operating dtring any period these surance that the resul ting annual releases are taking place.
tzposure to an individual in off site creas will not exceed 5 milli-The surveillance recuirenents given ren per yc3r. This assurance is in the renaining specifications pro-based on the fact that the Susque-vide assurance that licuid wastes are hanna River wili dilute the licoid proparly controlled and monitored effluents upon their c? lease fren during :ny planned release of radio-active materials in liquid effluents m
84 215
==
_c_
TA9LE 2.3-1
~
Radioactive 1.iquid Haste Sampling and Analysis (4, 5)
A.
Monitor Tank Releases Type of Detectabl e Samolinc Frecuency Activity Analysis Concentration (3)
Each Batch Individual Gamma 5 x 10-7 uci/:nl (2)
H-3 10-5 g jg)
Monthly Ccaposite (1)
Gross Alpha 10' uci/ml Sr-89 5 x 10-8 uci/nl
-0 Sr-90 5 x 10 uci/ml Hotes (1) A ccaposite sample is one in which the quantity of liquid sampled is proportional to the
. quantity of liquid waste discharged fren tSe plant.
(2) For certain mixtures of ganma emitters, it nay not be possible to measure radionuclides in concentrations near this sensitivity limit when other nuclides are present in the sample in nuch greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentretions 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 V.e potential significance in the env~f rorcent of the quantities ~ released For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated 1imits, they should also be reported.
(4) The results of these analyses should 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 tne two adjacent data points spanning 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 frca the sampling / analysis' regine will be noted in the report specified in Section 5.6.1.
84 216 e.
=
-o-L. 3r".G CO 2 - g
, a I::. W,1
%.0 re:n R 9 r.
'Ecu!.'~r W S Bases (Cont'd) f_is e s (C o n t ' d '
the site. Tre ef fluen s will be di-luted by a factor of about 250 in the These surveillance retuiremants pre-vide the data for the licens?e and ragica t here finfi sh can exist (wi th-the ccrmission to evaluate the sta-in a one-quarter mile radius of the tion's performance relative to radic-discharge point). At the same time active liquid wastes released to the these specifications pennit the flexi-env i ro rnen t.
Reports on the cuantiti bility of operation, ccmpatible with of radioactive materials released in considerations of health and safety, to licuid ef fluents shall be furnished t assure that the public is pecvided a de-the Ccenission en the basis of Sectic-pendable source of power under unusual 5.5.1 of these Technical Specifica-operating conditions, which may tempor-tions. On the basis of such reports arily result in higher than normal re-and any additional information cbtaint leases, but still within the concen-froa the licensee or others, the Ccm-tration limis specified in ICCFR 20.
It is expected that by using this mission naj recuire the licensee to take appropriate action.
operational flexibility under unusual cperating conditions, and exerting every effort to keep levels of radio-active material in liquid wastes as lcw as practicable, the annual releases will not exceed a 57all 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 ef fluents fecn the station to lev-els specified in ICCFR 20, Appendix B, for unrestricted areas. This specification provides assurance that n o member of the general pub-lic ca1 be exposed to liquids con-tainir.a radioactive materials in excess of limits considered per-missible under the commission's rules and regulations.
Specification b. above establishes an upper limit for the release of
. radioactive liquid ef fluents, ex-cluding tritium 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 flexibili-ty of operation to assure that the public is provided a dependable source of power under unusual operating conditions, which may temporarily resul t in releases higher than the levels normally f _ g3 (g7 o
O
L.:i!!:.3 CCNCI"Q -')
<;r u i;0:1 t.u
!?!! N P ', R RUIi!F 91T S Bases (Cont'dl Bases (Cont'd) achievable when the station and the liquic radwas;e equipment are func-tioning as designed. Releases of up
- 10 curies ;er radioactive waste-producing reactor during any calendar quarter will resul t in ctncentrations of radioactive materials in liquid ef n uents at small percentaces of the limits specified in ICCFP. 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 naterials in liquid effluents to as lov as prac-ticable, consistent. ith the recuire-ments of 10CFR 50.36a. Nornal use and naintenance of installed equipment in the liquid radioactive systa9 is expected to result in releases of not more than about five. curies per radioactive waste-producing reactor per year, excluding tritiun and dis-solved gases, during normal cperations.
In order to keep releases of radio-active naterials as icw as practicable, the specification requires, as a min-imum, operation of equipmerc 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 li iting conditions for operation listed under Specification b., the reporting requirements of Speci-fication e., the requirements of Section.
5.6.2, delineate that the licensee shall identify the cause whenever the rate of radioactive effluents excluding tritiun and noble gases, excee,ds 2.5 curies per radioactive waste-producing reactor dur-ing any calendar quarter and describe the proposed progran of action to re-duce such release rates. This re;crt must be filed within 30 days folicwing the calendar quarter in which the E.5 curies release occurred.
84 218 w
.a u,
. 'M Im i :::. ic:!
2.0
- m !TR I!G M CU REfTMTS 2.3.2 Sasecus Ef f'uan:s Acclicabili v
- pplies to the controlled release of radioactive gases frca O!I Unit Ncs. 1 and 2.
Objective Cb.iective To define the limits and conditicos for the controlled release of radio-To ensure tha t radioactive gasecus active gasecus effluents to the releases frco the facility are with-environs to ensure that these releases in the limits of specifications.
are as icw as practicable. These releases should not result in radia-tion exposures in offsite areas great-er than a few percent of background exposures. 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 meet the as low as pr.acticable concept, the folicwing cb.iectives 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 frcn Unit Nos. I and 2, should result in a dose rate at the site boundary of less than 5 meem/yr to the whole body or any organ.
b.
The release ate of I-131 and other particulate radionuclides with hal f-lives longer than 8 days, should result in a dose in the unrestricted area of less than 15 mren/yr by in-halation or to the thyroid of a child
' th. rough the cow-milk chain.
Specification Specification The instantaneous release rate of a.
gross gaseous activity except for During release of radioac;ive gaseous halogens and particulates wit:t half-wastes, the folicwing conditions lives icnger than eight days shall not shall be ret:
exceed:
A.
During -elease of gasecus waste frcn the waste gas decay tanks, the Oi 3
- '( a p c ) j' i 1.5 x 10 follodng conditions shall be net:
5m
~
sec 84-219 e
L.. ;l *.* sG C:hD
- T s. 5 U ; :& cn 2.0 i C '..' iC ' ' 'i * ? C UTTH IS SceciFication
,ont't) 5:ecification (Con:' d) where Oi is the release rate in 1.
Uaste gas discharge monitor uCi/sec for isotope i, and M:Cj (Unit 1. R"-A7; Unit 2: W CG-R -l aEC )
3 (uC' /n ) is the maxinun pe ris-sible concentration of iso to e c
simil ar device, shall be ccerable.
ar.d defined in Appercix 5, Table 2.
hxiliary and Fuel Handling II, Coh.mn 1, ICCFR 20.
Building and Unit Exhaust Vent exhaus-b.
The instantaneous rel ease gas, iodine and particulate monitor
~
(Unit 1: RM-A8; Unic 2: HP-R-219) er rate of I-131 and particulates wi th hal f-lives greater than similar device, shall be cperabie.
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 r.ot exceed 0.3 uCi/sec.
V-30A or 3CS) shall be operaole, 4.
The waste gas decay tank discharge The release rate of gross gase-valves (Unit 1: WDG-747; Unit 2: WCG-i c.
cus activity shall not exceed:
30A or 303) shall be closed on receipt of any one ~of the folicwing conditions O
3 i
4n E(NPC)j i
a.
A high radiation sicnal frco the sec waste gas discharge non'itor (Unit 1:
RM-A7; Unit 2: WCG -R -1480 ).
when averaged cver any calendar b.
A high radiation signal frcn the quarter.
Auxiliary and Fuel Building exhaust nonitor (Unit 1: RM-A8; Unit 2: HP-d.
The release rate of I-131 and R-219).
particul ates with hal f-lives greater than eight days, shall not exceed: 0.024 uCi/sec., when aver-A high ficw sinnal fecn the Waste c.
aged cver any calendar quarter.
Gas Decay Tank discharge fi cw trans-nitter (Unit 1: FT-123; Unit 2: WCG-FT-3923.
e.
Radioactive gasecus wastes coll ected in the gas decay tanks d,
Observation of loss of flow shall be held up to a niniaun of 45 days, except when the rel ease through the Unit vent.
rate shall not excaed:
B.
During purge of the Reactor Buil-ding, the followings conditions shall Qi 3
ba met:
3xM[ec 5 MPCj i 1.
1.
-The Reactor Building Purge Exhaust (noble gases)
Monitor (Unit 1: RM-A9; Unit 2: HP-R -
225 and/or HP-R-225 and HP-R-210) or or similar device shall be operable.
2.
0.003 uCi/sec (iodine 131 and 2.
The Purge Exhaust Valves (Unit particul ates with AH-VIA and AH-VIB and Dampert; hal f-lives greater Unit 2: D5129 A/D and 05129 B/C) than 8 days) shall be operable.
84^220 e
u.:.., n.::** Rh -:- ~?:,:Ln
?.O wn:~Mi% uiCUMEH:5 Sceci fication (Cent'.
Scecit a?'on (Cont'd) f.
Radioactive gas and particulates 3.
The valves (Unit 1: AH-VIA and purged fecm the reactor building shall AH-VI3 and Campers; Unit 2: 05129 AT be filterec through the 5ign ef ficiency and 05129 B/C) shall be intariccxed particulate air filters and charcoal to cicse or recirculate, res:ectivel a3sorbers on receipt of a high radiation sigra frco the Reactor Building Exhaust g.
The maxinun activity to be con-Monitor (Unit 1: R:1-A9; Unit 2: H? -?. -
tained in one gas decay tank shall not exceed 8800 curies (equivalent to Xe-225 and HP-R-226) respectively.
133).
c.
The ficw rate for radioactive h.
When the release rate of radio-ef fluent streams and the Auxiliary and Fuel Fandling Euilding and the active materials in gaseous wastes, Reactor Euilding, shall be nonitored averaged cver a calendar quarter and recorded. Ga seous ef fluents frca ex ce eds,
the Waste Gas Decay Tanks and 3
[-
01 3m the Reactor Building Purge Exhaust
. i sec shall be continuously ecnitored and (NPC)1 i
recorded.
(ncble gas) or d.
0.006 uCi/sec (iodine-131 and Radioactive gaseous waste samplin; and activity analysis shall be per-particulates with formed in accordance with Table 2.3-2.
hal f-lives greater than 8 days)
The waste gas decay tank effluent e.
monitor (Unit 1: RM-A7; Unit 2: WCG the licensee shall noti fy the PRC with-1480) shall be tested using the in-in 30 days, ider.-ifying the causes and stalled check source or ecuivalent describing the proposed progral of ac-prior to any release of radioactive tion to reduce such release rates.
gas frcn a bolcup tank and shall be calibrated quarterly using a re-ferenced calibration source in a controlled reproducible gecmetry.
f.
During power operation, the con-densor vacutn pump discharge shall be continuously monitored for gross gaseous activity.
The monitor shall not be inoperable for more than a week. Whenever this monitor is in-operable, a grab sample shall be taken daily and analyzed for gross radioactivity. (S lf ).
g.
Facility records shall be main-tained of radioactive concentration, release ratio and volune of each batch of gaseous efnuents released 84 221 E
P
Li'
- J C0:,0:7:
.5 m 7:Fi 2.0 r2.'ti a i' HOUE WS Specificatien (Cont' d) and the length of th,e over which rel ea se cccurred. Estimates of the error associated with each reportec value should be included in facility records.
h.
At least annually, autcmatic initiation and closure of the Waste Gas Cecay Tank Discharge valve en alarm of (Unit 1: RM-A7 and Pfi-A8; Unit 2: WCG-R-1480) shall be verified.
- i. ' The Auxiliary and Fuel Handling Building and Reactor Building Purge Exhaust ges monitors for TMI-1 (RM-A8 and RM-A9) cnd the Unit Vent monitors for' TMI-2 (HP-R-219, HP-R-225, and HP-R-226), respectively, shall be calibrated at least every eighteen months by means of a kncwn radioactive source. These detectors shall have an instrument channel test at least monthly, and a sensor check at least daily, to verify that the read-out device is indicating as ex pec ted.
~
Bases Bases The specified levels provide rea-Specifications a. through f. above, sonable assurance that the resulting recuire that suitable equipnent to annual exposure rate fecn noble monitor the radioactive gaseous gases at any location at the site releases are operating during any boundary will not exceed 13 nillirems period these releases are taking per year. At thw same time, these place.
specifications permit the flexibilit/
of operation, ccapatible with con-The surveillance requirements given sideration of heal th and safety, tr under the re7aining Specifications assure that the public is provided a above, provide assurance that dependable source of power under un-radioactive gaseous effluents frca usual aparating conditions, which aay the station are properly controlled temporarily resul t in higher than the and monitored over the life of the design objective levels, but still station. These surveillance within the concentration linits requirements provide the d' ta for the a
specified ICCFR 20.
It is expected licensee and the Cccmission to that using this operational flexi-evaluate the station's perfornance bility under unusual cperating con-relative to radioactive gaseous ditions, and by exerting every effort wa stes rel eased to the envircr. ment.
to keep levels of radioactive material in gaseous wastes as icw as practica'le, Reports on the quantities of radio-o the annual releases will not exceed a active materials released in garacus small fraction of tne annual concentra-ef fluents shall be furnished to the tion licics specified in ICCFR 20.
Commission on the basis of Secticn g
.oon z,...
e
e TA3tE 2.3-2 Radioactive Licuid Haste Sampling and Analysis (5)
Samo'a z a Samoline Frecuency
? :e of Acciv:ty Andly;1s Detect 2cle Ccacentracion (7
'Ja s e G a s D ecay T ank R el ea s_e Gas Each Tank H-3 10-6 uCi/cc Rel ease Individual Gamma Emitters 10 uCi/cc (2)
Reactor Buildinc Purce' Releases Gas Each Purge HI 10-6 uCi/cc Individual Gamma Emitters 10- uCf/cc (2)
Condenser Vacuum Puno Releases Gas t-!c n thl,y-H-3 10-6 uCi/cc F.cnthly (3 )
Individual Gamma Emitcers 10- uCi/cc (2)
Auxiliarv and Fuel Handline Suildina Exhaust Vent, Reacter Buildina Purre Vent and Unic Exnaust (6)
Vent Release Points Gas
!1onthly H-3 10-6 uCi/cc Individual Gamma Emitters 10-' uCi/cc (2 )
Charcoal Weekly (4)
I-131, I-133, I-135 10-12 uCi/cc Particulates Weekly Individual Gamma-Emitters 10-10 uCi/cc (2) l'.onthiy Ccmposite Sr-89, Sr-90 10-11 uCi/cc tionthly Ccaposite Gross 10' I uCi/cc (1) Tne aoove cetectability limits are based on technical significance in the envircraent of the. cuantities released. feasibility and en the potential For some nuclides, lcuer detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported.
84 223 9
(2) For certain mixtures of ga na enitters, it nay not be ecssible to measure radiont.clides at levels near their sensitivity limits t.nen other ruclides are present in the sample at muc."
hig*er l evel s.
Uncar t. ese circumstances, it will be noce appropriata to calcul ate the level s of such radionuclides using cbserved ra tios in the gaseous ccaponent in the reactor c:clant for thosa raci0nuclides w.iich are ceasurable.
(3) Analyn s shall al so be perfarned folicwing each refuelirg period, start-up or similar cperational occurrerce which could alter tne mixture of radionoclides.
(4) Sanpled during periods when no waste gas decay tank release ce reactor building purge is r pecgress.
-( 5 ) Deviations from the sa:apling and analysis regime will be noted in the report specified in Sec tion 5.6.1.
(6) The Auxiliary and Fuel Handling Building 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).
/
r 84 224
12 -
(2) For certain nixtures of garma emitters, it may not be pcssible to measure radionuclides ac level s near their sensitivi y limits when other nuclides are present in the sample at much hig: er level s.
Unde
- these cir:;mstances, it will be more appropriate to calcul 3te the lavsi s of such radioruclides using cbserved ratios in the gaseous component in the reactor coc' ant for those radionuclices -hich are measurable.
(3) Analysi s shall also be performed following each refueling period, start-up or similar cperations' - :currence which could alter the mixture of radionuclides.
(4) Sanpl ed during periods when no waste gas decay tank release or reactor building purge is it prog res s.
-( 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 Building Exhaust Vent and Reactar Building Purge Vent per-tain to Unit 1 (TMI-1), while the unit exhaust vent pertains to Unit 2 (TMI-2).
o#
e mm-e 84~225 e
L p
. 1 e r7,. -
..:Od 9.C
?N R'). D.G W E0':[ME:i G Bases (Cont'd)
Bases (Cont'd)
These efforts should incluce con-sideration of meteorolcgitai 5.6.1 of these Technical Specifica-tion s.
Cn the basis of such rescets conditions during rel eases.
and any additional in fornation the The annual obj ecti.'es "av e b een Ccrnission nay obtain frcm the developed taking in o act:unt a licensee or others, the Ccmaission ccabination of system vari 3bles may feca time to time recuire the licensee to take such action as the including fuel failures, prinary Ccrmission deeas appropriate.
system leakage, prinary to secondary system leakage, and.the performance of radionuclide removal nechanir-.
Specification a. above, re fres the licensee to limit the
.o -
centration of noble gases feco the station to levels specified in la CFR 20, Appendix B, for un --tric-ted areas. Based on a X,,
.t 6.7 x 10 ~5 sec/ m3, this snecifice aon provides assurance 't.at no c e of the general publi
-culd te exposed to radioactive no.er :s in excess of limits speni:
ad ir the Ccamission's ru. es lations.
.tca-Specification b. above, requires the licensee to limit the concen-tration of I-131 and particulates with half-lives greater than eight days, released fecm the station to unrestricted areas to levels such that no individual will receive more than 15C0 mrea/yr to the thyroid. A grazing period of 6 months has been applied to the radiciodices 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 degosition factor (0/0) of 2.1 x 10-8 m.
The 0/Q of 2.1 x 10-8 n-2 was calculated for the nearest cow located 1.2 miles SE of the station, usinp cn-site meteoro-logical data.
Specifications c. and d. above, estab-lish an upper limit for the release of gaseous activity at 16 percent of'instan-taneous release linit o# ncble gases and 4t gight percent of the release rate of 1-1s1 and particul ates witn hal f-lives g' 4 - 2'^)G
~.
N
t
.~;, ' C 0';0 ! T.P . 5 -5
'a-Ti;9 2.0
! N ii n i f-Gu iPEi9 f 3 B ases (Cont'd) greater than 8 days, averaged cver any calendar quarter, respectively.
The intent of this specifica-ion is to per7it the license 2 the flexibility of operation to assure that the public is provided a dependable scurce of power under unusual operati.ng conditions which may temporarily resul t in higher rel eases than the cbj ectives.
Specification e. above, recuires a 45 s
day holdup time for radioactive gaseous wastes collected in the gas decay tanks to assure decay of most radionuclides.
The whole body dose frcm noble gases at the site boundary is expected to be less than 10 crem/yr (primarily fecm K r-85 ). The thyroid dose feca radio-iodines and particulates at the nearest farm is expected to be less than 15 cren/yr.
Specification f. above, limits the radioactivity that may be released to the environment tc "as icw as prac-ticable."
Specification g. above, limits the maxi-mun offsite dose to well belew the limits of 10 CFR 100, postulating that the rup-ture of a Waste Gas Decay Tank holding the maximum activity releases all of the contents to the atnosphere.
In addition to the limiting conditions for operation listed under a, b and c above, the reporting require 7ents of Specification h. delineate that the licensee shall identify the cause when-ever the r'adioactive 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 progran of action to reduce such release rates.
The report nust be filed within 30 days following the calendar quarter in which mere than twice the design release rate occurred.
84,?id7 m
4 u.:':ThG CC'rc: :2.5 :
cai CIC'!
2.0 t'ott i ic'
,G v.20u P /.t e; rs R _:.: : 2. _:.v, u : a-(1) t'eteorology and At:mic Energy, pp. 204 (2)
"eteorology and A: nic Energy pp. 112 O
e
-sl=
O e
4 4
84^228 9