ML19206A192

Forwards Proposed Interim Effluent Radiological Tech Specs. Util Proposes That Tech Specs Currently in Effect for Unit 1 Be Revised to Include Unit 2

ML19206A192
Person / Time
Site:	Crane
Issue date:	07/11/1977
From:	Jay Collins Office of Nuclear Reactor Regulation
To:	Regan W Office of Nuclear Reactor Regulation
References
NUDOCS 7904180372
Download: ML19206A192 (24)

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M:nitor ~ank 7.eleases Tvpa of Detectable Sy plice 7:ecuency Activity Analysis Ccreentraticns(3)

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q 2.0 L1111TII;G CONJITIO;;S FOR OPERATION a aca (Coat'd)

I.. uddition to the liuiting conditiona for operation 11uted under Speelfication b, the reporting requireraento of Specification e, in addition to the require. ento of Leetion S.6.2, delinente that the licenuce

t. hall idcatify the cauac whenever the rate of r..dioactive effluentu, excluding tritliua tud nolle gasca, exceeda 2.5 curies per rods *onche wasfe proJocin3

, reuc-rce durir.J any calendar quarter and deucribe o

the pn.jased progra... of actima to reduce auch raicane rate.

Thia report u.out be filed tuthin 30 daya following the calendar quarter in which the 2.5 curies releaue occurred.

a.3.2 Gr.wous Ef t'l uen t s gplicch11ity A,iplies to the controlled rolcano of radio-active gaucu froa 7tII Unit tjor. I oncl

.'2 y

CLj.3ctIve vi Objective C

To define the 11tr.ita and conditionu for the c

controlled release of radioactive effluento To ensure that radioactiva guacoua relenoca from the facility are within the limits of g

tu the environa to enoure that these releasca specifications.

7) are ao low au practicable. These releases h

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2.0 LIMiYING CONDITIONS F0lt OPEllATION Objective (Cont'd) cheuld not result in radiation exposurec in uarcatricted areaa greater than a few percent e

y of r.atural background expor.u rca.

The Inui.antaneoua releaue rate for all effluent d i:.clairges should he within the lluitu opecified in 10 CFR Part 20.

To aaaure that the releauca of radioactive gauea to unrestricted areau ueet the ao low na practicable concept the following objectiveu apply:

a.

The relcune rate of radioactive i t..s t o p e o,

averaged over a yearly interval, except I-131 and particulato radiolootopen with

, half 11vea greater thsn 8 days, diacharged from Unit Nc.s. I und 2 choulcl n'ecoli-in c4 Jose i-afe at tha site boundary of lecs than 10 uren/yr to r.he whole Lcdy or any organ.

CIT g

h.

The relecae rctu of I-131 and other a

particulace radioiuotopeu with half 11vea C

longer than u days, thould reuult in a (D

'douc in the unreotricted area of Icou than

%]

15 mrcu/yr by lahalation or to the thyrofa of a child through the cow-milk chain.

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'D 2.0 Ln!ITiMG C0:JDITIGliS FOR OPERATiOJ Specliication (Cont'd) jai >ec_i f ic a t ion (C_on t 'd )

(un} I : RM As i U,Jt 2 : HP-R-3236) averaged over a calendar quarter exceeda (lteactor nulld f ug) or alallar devicea.

The flow rate for radioactive effluent u t resuan Cl 3

and the Auxiliary and Fuel linadling Ilu11 ding g

E (MPC)1 -< 4.8 x 103 n:--

and the Rea; tor Ilu11 ding, shall be monitored b<

ucc and recorded.

(noble gases) or Gnneous effluento fron the Uante Cao Decay Tanka and the Reactor building Purge Exhaust chall be 0.024 pC1/oce (iodine and particulates) continuouuly saonitored and recorded. Whenever any of these monitorn in inoperable appropriate t!.c licenoce chall notify the Director, grab' samples shall be taken and analyzed daily, airccturnte of Licensiny, uithin 30 dayn, IGcatifying the causes and describing the Radioactive gaaeuun wante unnpling and activity proposed program of actica to reduce unch analyula shall be performed in accordance with releaue rates.

Table 2.

The waste gaa decay tank effluent c.oaltor,(0,n't I : RM-A'/ ; UnN-a : WDG-H CO)s.hnll 1,c tested using the installed check nource or equivalent prjor to aay releane of radioactive gaa from a holdup tar.k and nhall he calibrated at refueling intervalo.

T!,e ca ohration procedure.

for R:1-A7 and WOG-li} CO -J,qN cons M of c>yosir, Yhe defodor to a referenced calibration source in a control'q 1ed

,, ny reproducible geometry.

1p During power operation, the condenner vacuna putup C

d inc ha r;;e shall be continuouuly monitored for Q

groau radiogas activit y.

The monito,r chall

.ot be inoperable for more than a week.

Whenever thiu

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TAllLE 2 (Cont'd)

Detectable Concentration (

Scuple Type Sampliag Frequency Type of Activity Analynia Particulatea Monthly Composite of Sr-89 10 11 pCi/cc the Samples for the Month Quarterly Composite of Sr-90 10-11 pC1/cc the Samples for the Quarter Monthly Compoulte of

. Cross a 10 11 pCi/cc the Samplea for the lknL11 (1)The.. hove detectability limito are based on technical feasibility and on the potential uignificance in the cuvironment of the quantitica relenaed. For uome nuclidea, lower detection limito may be readily achievuhle and when nuelldes are rucasured below the stated limite, they should also be reported.

(2)For certain uixturco of gamma cuitters, it may not be pooulble to nenuure radionuclideo at le:elo near their uenuitivity limito when other nuclidea are present in the nample at much higher level.

g',

Under ihet,e circumotancen, it will be more appropriate to calculate the leveln of such radio-nucl1.le. using chaerved ration in the gaucous component in the reactor coolant for those T'

radioacclides which are meauuruhle.

")Analy:,1.i uhall alao be performed following each refueling period, startup or nimilar operational

,.y occurrence which could alter the alxture of radionuclidea.

The lo.lua and particulate collection device shall be analyzed to determine the releaue rate increase j

for.lodlacu and particulaten daily, when the average daily groso radioactivity release rate equalu or exceeda that given in 2.3.2 Specification C or ubca the utcady utate grosa radioactivity release

]

rate lacreuses by 50% over the previous corresponding power level steady state release rate.

gh

., a g e, s

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~ ~~~ ~-~~

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30 -

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2.0 LI:IITIliG CO:DITIO:IS FOR OPU MTIdit d

i O

0 1

[.pecification (Cont'd) monitor is inoperable a nrnb nample nhall be taken daily and analyzed for F;ross radioactivity (6,y)

Gs. '

Facility recorda of iodine end particulate relennen with half-liven greater than elp,ht daya ohn11 he

~

maintained. The error nococinted with each onmple analysis shall be retained.

Records shall be maintained and reports of the nampling and annlynin renulto chall be nubmitted in accordance with Section 5.6.1 of theoc Specifi-cations. Entimaten of the error nanociated with each reported value should be included.

At Icast annually, automatic initintion and clonure of the Unste Gao Decay Tank Dinchnrge valve on ninrm of Rit-A7,RM-AO,cthd WD6-j480 shcall be ver-ified.

The Auxiliary and Fuel llandlina lluildinrt and Uml-Nos. I 0"<IT^

R.R. Purge Exhnunt gns monitora Rt:-AT,, RM-A9, anJ llP-R-32b /

renpectively3 chall be en11brated at least-

<;untterly by menna of n known rndioactive source.

lui-A8, RM-A9, and HP-R-3236 shall have on insfromenh chonriel tent at leant monthly, and a neunor check at 1 cant daily to verify that the read-out device in indicating an expected.

.j

'y

..., o r 3 i

i-2.0 1.11;LTII!G COND1 TIC;iS K)R OPERATION Dancs Unora Tha opecified levelo provide reanonablo Specificationa n, b, and c above, require thnt annurance that the resulting annual expoourc cultabic equipment to monitor the radionctive rate from nobic gnaco at any location at the gnocous relcanen are operating during any period

(,.

9-nite boundary will not exceed 10 millirena thcee relennen are taking pince.

per year.

At the anac time thene npecifica-tionn permit t.he ficxibility of operation, The nurveillance requIrrmento given under the cc;npatibic with connideration of henith and remaining Specificat.toon above, provide annurance cafety, to annure that the public in provided that radionctive ganeoun ef fluento from the ntation n ucpendable cource of power under unununi are properly controlled and monitored over thr:

operating conditions which may temporarily life of the ntation. Thene ourveillance require-renuit in relennen higher than the design r: ento provide the data for the licennee and the objective levela but otill with1n the con-Comminnion t.o evaluate the otation'a performance centrt. tion limito specified In 10 CFR Part 20.

relative to radioactive gnocoun wanten releoned to It in expected t. hat using this operational the environment. Reporto on t he quantitlen of ficxibility under unusuni operating conditionn, radionctive materiala relenned in ganeoun effluentn anc. by exerting every ef fort to keep 1cveln of chnll be furnished to the Comminnion on t he banin radioactive materini in gnucono wanten as low of Section 5.6.1 of these Technical Specificationn.

na practicable, the annual relcanen will not On the banis of noch reporto and any additionni exce :d a small fraction of the annual con-information the Comminnion may obtain from the centration limita rf,iccified in 10 CFR Part 20.

licenoce or othern, the Comminolon may from time bi Theoc efforts should include consideration of to time require the licennee to take such action meteorological conditiono during relenoes.

- as the Commlnsion deemn appropriate.

Thn annuni objective 9 have been developed tcking into account a combination of oyntem

,,,f variablen including fuel failuren, primary uynten leakage, primary to cecondary ayuten

,p lenhage, and the performence of radioinotopo c

removal mechaniumo.

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