ML20037A652
| ML20037A652 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/15/1972 |
| From: | Benaroya V US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8003250668 | |
| Download: ML20037A652 (3) | |
Text
..
-. _ m.
.e m m #c y.
y 9
-g w _._..
...A,.
. x..
'y e,; r','-
x i
w m.
.m.,.-
x mm, Doc,e: R,e.
2 JUli15 is7z Dcchet No. 50-302 Richard C. DeYoung, Assistant Director for ?reasurized Water Reactors, L Thru: Robert L. Tedesco, Assistant Director for Contairmnt Safoty, L REUEST FOR ADDITICKAL EiFOKMTICK FOR CHYST.G RIV R, UNIT 3 Attached is our request for additic.a1 infor:stion on tha Crystal River, Unit 3 F3AR. This infor= tion is rc~iuired fer our evaluation or tce raa-vasta and mdiation protection systens. The applicant chould provide the rsquire:d infairatica by Auzant 22, 1972 to mintain th) current schedule.
360=1 sloed by vt:br 3enarsta Vice.or 2enarcy*-, Chief Efflu:nt T enWt Syst-::2s 3rsuch Directorate of ".icensing Encic3nre:
As Stated ObcVe yN-DI5IEIEUTION:
,){
Ecchetfile-(50-3C-2)
L Reading CS Heading gk ETSBEeadin(-w/oenclocure)
J. Hendrie A. Gia busso (w/o enclosure) b L:TR Assistant Directors
\\N.
L:TR 3 ranch Chiefs g
A. Schwencer
's G. Dicker E. Tau 1?ner D. Sells F.Zaras(2)
J. ma'# # (w/oenclosure)
ITS 3rsnch Staff
...,5... 3.[L l.- Em.. L l A.D../,0.4-
.e ; ~ 4 emct >
1
- .CTE/pv.........i...V3E".J.r~YA EEjC0
~
i suwwe >
s[.. /72,
_@j,(/72
.. s/l.5[T2.,,,
4,$,Q,0,2 c:sn [ h '
wir >
Form AIC-Sti Rev. 9-13) AECM 0240
- o en--to-H ee-t +eMis
'~
t
y
.~.m
...~<-.-..:-...
O;
<w RADIASTE AND RADIATION PROTECTION QUESTIONS FOR CRYSTAL RIVER, UNIT 3 11.1 Provide sufficient-inforcation to clarify the following discrepancies:
a.
The annual quantity of radioicotopes released frc= the radioactive liquid vaste syste= as estimated on page 11-5a does not agree with the esti= ate given on page 11-90 and page ll-37c.
b.
The liquid vaste' disposal diagrs=, Figure 11-1,-does not agree vith
' Figure 11-1B and Figure V-12 in the Environ = ental Eeport; e.g., no mixed bed de=ineralicers.
t c.
The writeup en page 11-4b states that laundr/ vastes vill be sent to the miscellaneous vaste storage tank, if the activity is creater than10-9uC1/=1afterdilutien. Figure-11-13 shows this stres being sent to the neutralicer tank.
d.
Figure V-12 in the Enviren= ental Eeport shows the deborating de=in-eralicer reganerants being sent to the neutralizer tank. Fig"re 11-lb in the Final Safety AnaIysis Esport shovs thes= vastes being sent to the miscellaneous vaste storage tank.
11.2 On the basis of the design and operation of the proposed radvaste treat-
=ent syste=, provide estimtes of the taxi =un whole bcdy dose to an individual and the max 1=um crgan dose to an individ"*'
- at vould be(..
received by che general public at the site boundarf as a result of the release of liquid.and gaseous effluents.
11 3 Figure 11-2a dees net show the turbine building, reactor building purge, and the condenser vacuu= pu=p air ejector release path.
Provide.a revised figure to show these release paths.
11.4 Provide additional details on the reactor building pt.rge exhaust duct (R=-A1) and the auxiliar/ building and fuel handling area exhaust duct (R=-A2) conitors, including, the distance of conitoring filter ele =ents
^
from the exhaust stream and the bases for this distance,'the location.
of the sample intake in the exhaust stream and bases for this locaticn.
i 11 5 Your present design per=its =anual readjustment of alar = set-points prior to planned gaseous releases. Justiff why you do not need to use a technique for reasuring planned releases that does not interfere with, alar = set-points.
11.6 rescribe the capability in the plant of caking periodic isotopic analyses co= parable to those outlined in Safety Guide 21 of noble gases, iodines, par iculates, and liquids released to environment.
gML
/
~-
~
.m_,m,_._
m
- m...m. m-.
-7
+. -
- _ ~ ~.. -... _ _. ~. _ _.
w.----
- - +
O r
)
2-11 7 For each logical grouping of instruments,.descrite the calibratien and preventive raintenance operations to be used.
11.8 Descrite the opemtional characteristics of radiation =cnitors, including (and their basesh, sensitivity, range, rethod of calibration, set-points type of detector the cri eria used to determine necessity for and ~
location of the rcnitors.
11 9 Provide an esti=ste of the' yearly onsite tan-rem exposures from the
.s plant. Cc= pare the esti=ated doses with experience from relevant-operating plants.
f r
a s
q 4
s 1
6 h
c' 6.
s.
, HED
~
4 6
i#
a
^
__i_m.___m______
___________._m_.
_ _