ML19296A763
| ML19296A763 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 01/28/1980 |
| From: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19296A759 | List: |
| References | |
| NUDOCS 8002190014 | |
| Download: ML19296A763 (13) | |
Text
.
DOCKET NO:
70-1100 LICENSEE:
Combustion Engineering, Inc.
FACILITY:
Fuel Fabrication Plant Windsor, Connecticut
SUBJECT:
RADIOLOGICAL ASSESSMENT OF INDIVIOUAL DOSE RESULTING FROM ROUTINE OPERAT ON - DEMONSTRATION OF COMPLIANCE WITH 40 CFR 190 I.
Background
The EPA urarium fuel cycle standacd, as specified in 40 CFR 190,1 limits the total dose to an individual from radioactivity associated with the routine operation of nuclear fuel cycle facilities to 25 mrem /yr to the total body, 75 mrem /yr to the thyroid, and 25 mrem /yr to any other organ.
The standard will become effective on December 1,1979, for all uranium fuel fabrication plants used for the production of LWR fuel.
The Combustion Engineering Company's (CE) (the licensee) plant is an existing uranium oxide fuel facility and is subject to the EPA standards.
Based on the most current plant operation, emission, and monitoring data, the NRC staff conducted the fol'owing radiological assessment to determine if the licensee will meet the EPA's standard on fuel cycle facilities. As a result of this assessment, an action level on the effluent release rate from routine operation of the facility will be established to provide reasonable assurance that the licensee complin with the standards for continued operation.
II.
Discussion A.
Description of the Facility 1.
Plant Operation - General CE owns and operates a nuclear fuel fabrication facility and nuclear laboratories on a 556-acre tract located in the town-ship of Windsor, Connecticut.
Nuclear fuel production as well as research and development activities have been performed at this site since 1957, although the present fuel production facilities in Building 17 were not constructed until 1968.
The Windsor facility is presently licensed to possess 500,000 kg 002 enriched to a maximum of 3.5% 23sV.
A license amendment application is under review to increase the maximum 23sU enrich-ment (with no change in the total UO2 quantity) to 4.1%.
A maximum of 4800g 2.s0 of any enrichment is allowed for research and development activities.
There is no large-scale chemical processing performed at the site.
~
2 2.
Processing In the fuel f abrication facility, the UO2 powder is blended, milled, mechanically treated and pressed into pellets. The pellets are sintered in a reducing atmosphere, ground to a desired diameter and welded into Zircaloy tubes.
The loaded fuel rods are assembled into bundles, tested and packaged for shipment.
In the nuclear laboratories, research fuel materials are developed -
and tested, chemical analyses associated with quality control of fuel are performed, and both mechanical and chemical testing are done on nonirradiated core materials such as fuel cladding, neutron poison materials, and fuel rod assembly materials.
B.
Waste Confinement and Effluent Controls 1.
Gasecus Effluents There are four separate exhaust systems in Building 17 (manu-facturing) from wnich airborne uranium dioxide particles can be drawn out of processing areas:
System 1 covers the powder preparation and pressing areas and has a capacity of 12,l00 SCFM.
It incorporates prefilters and a double bank of 12 absolute filters, each 99.97% efficient for 0.3 micron particles.
The air exhaust from this system, wnich is either returned to or released from the plant, is sampled 100%
of the time and analyzed each day.
The yearly average discharge level is < 2 x 10 ta Ci/cc.
p System 2 covers the hydrogen burn-off area and has a capacity or 1340 SCFM.
It incorporates prefilters and a single bank of four absolute filters, each 99.97% efficient for 0.3 micron particles. The air exhaust from this system is released from the plant, sampled 100% of the time and analyzed each day.
The yearly average discharge is < 3 X 10 13pCi/cc.
System 3 covers the pellet grinding and rod loading areas and has a capacity of 19,422 SCFM.
It incorporates prefilters and a single bank of 21 absolute filters, each 99.97% efficient for 0.3 micron particles.
The air exhaust from this system is released from the plant, sampled 100% of the time and anal,yzed eaca day. The yearly average discharge level is < 3 x 10 13 Ci/cc.
p System 4 covers the recycle powder area and has a capacity of 6,000 SCFM.
It incorporates prefilters and a double bank of six absolute filters, each 99.97% efficient for 0.3 micron particles. The air exhaust from this system is released from the plant, sampled 100% of the time and analyzgd each day.
The yearly average discharge level is < 5 x 10 "pCi/cc.
3 Operations in Building 5 (Nuclear Laboratories), associated with radioactive materials, are conducted in hoods.and other vented enclosures which are exhausted through absolute (HEPA) filters to roof stacks.
Discharges from the laboratories are monitored on a continuous basis whenever operations having a potential for dusting are cc.,ed out.
Samples are analyzed daily.
Two of the stacks exhaust the hot gases from hydrogen sintering furnaces and these two are not filtered.
Analyses show an average concentration of 1 x 10 13 Ci/cc in the unfil-p tered exhaust stream. Other exnaust streams, filtered before discharge, have averaged 5 x 10 14pCi/cc.
2.
Liouid Effluents a.
Process Liouid Wastes All controlled area liquid wastes from Buildings 5 and 17 are discharged to any one of ten 2,000 gallon waste holdup tanks. Wastes from these two buildings are not discharged to the tanks until the activity level has been reduced to 1 2 x 10 3pCi/cc.
The ten 2,000 gallon hold up tanks fill automatically in sequence.
A blinking light is activated to signal when eight tanks are filled to capacity.
This allows time to take the necessary action to prevent the tanks from overflowing.
The tanks are sampled prior to discharge.
If levels are in excess of one percent MPC, the waste liquid is circulated to one of two 5,000 gallon dilution tanks where the necessary dilution is made.
If necessary, the pH is adjusted to meet State of Connecticut requirements.
The liquid waste is then carried to the site creek which discharges to the Farmington River.
b.
Sanitarv Waste Water Effluents Sanitary wastes are processed tnrougn tne facility's-stancard sewage treatment plant from which chlorinated liquid effluent is discharged to the site creek and then the Farmington River.
Industrial Wastes Industrial Wastes include mainly the c.
piant cocling water flows plus other minor streams which Dass through the plant without physical or chemical change.
Re industrial waste stream bypasses the waste holdup
- anks and the sewage treatment plant, flowing directly into the site creek which flows into the Farmington River.
3.
Soi M lastes Solid wastes containing UO2 are generated in the form of rags, papers, polyethylene bags, reject emptied fuel tubes and other miscellaneous materials generated during normal processing operations.
The laboratory and research activities also produce solid wastes containing precipitated uranium from chemical
4 processes and analyses in solid form.
Radioactive solid waste is also generated in the form of scrapped unusable U02 powder in small quantities. All waste materials are loaded into 5 gallon pails which are then placed in an assay unit to determine the U-235 content.
The pails of waste are then emptied into 55 gallon steel drums which are sealed for delivery to a waste disposal contractor licensed by the NRC.
C.
Semiannual Effluents Emission Data Sections 70.59 of 10 CFR Part 70 and 40.65 of 10 CFR Part 40 require that the licensee submit effluent monitoring reports on a semiannual basis after January 1, 1976.
Table 1 summarizes the results of the radioactivity measured in airborne and liquid effluents for the past few years (1975-1979).
D.
Descriotion of the Site Environment Related to Radiolocical Assessment at tne Maximum r. rest Resicent The following description of the site environment provides only information specific to the assessment of the impact on individuals from radiological effluents released during normal plant operation.
Further information concerning the site environment can be found in the Environmental Impact Appraisal issued by the Commission and the Licensee's Environmental Report.2 1.
Site Location The CE Windsor site is a 556-acre tract located in tne townsnip of Windsor, Connecticut.
The Farmington River flows along the northern boundary of the site.
Figure 1 shows the boundaries of the Windsor site with respect to the town of Windsor, Connecticut, and the general distribution of facilities within the site boundaries. Transportation access to major highways and railroads is also shown in Figure 1.
Table 1 Reoortina Period Gaseous Release (Ci)
Liouid Release (Ci)
~
July 1, 1976 - Dec. 31, 1976 5.53 x 10 6 1.64 x 10 3
~
~
Jan. 1, 1977 - June 30, 1977 2.69 x 10 6 1.47 x 10 3
~
~
July 1, 1977 - Dec. 31, 1977 4.90 x 10 6 1.09 x 10 3
~
~
Jan. 1, 1978 - June 30, 1978 2.85 x 10 8 7.91 x 10 4 July 1, 1978 - Dec. 31, 1978 2.82 x 10"S 7.09 x 10 4
~
~
~
6 Months Average 3.76 x 10 8 1.14 x 10 3
~
~
Twice 6 Months Average 7.52 x 10 6 2.28 x 10 3
5 V
/
7d'O A
\\
/
r m
-w j \\\\1 t%E.!!Ik2c.
[
,.,., sea
(
5%
5
/
\\
sa M'
by 6
,a
. r J ' L L C n.
c
~
a =6=:
ni.rmnarai scad ca wLts
_ _ Figure 1
6 2.
Land and Water Uses The land adjacent to the North, East, West and South boundaries of the site consists of heavily wooded sections and open fields cultivated for the production of broad leaf tobacco.
The land area within 5 miles is predominantly rural and is characterized by rolling farm lands interspersed among sizeable woodland tracts.
Figure 2 snows the buildings and facilities presently located on the CE Windsor site.
There are 25 structures shown and identified by building name and number.
3.
Diffusion Climatolooy For annual atmospheric dispersion calculations, the joint fre-quency distributions of wind speed by direction were taken from observations made at Windsor Locks, Connecticut.3 The meteo-rological disperson factors (x/Q) were calculated using the Gaussian Plume model and diffusion coefficients for Pasquill type turbulence.4 Since the release points from the Windsor site are lower than two and one-half times the heights of the adjacent solid structures, a ground level release was conserva-tively assumed with credit given for a building wake effect.s The annual average X/Q's as a function of distance up to 50 miles from the site and in 16 sectors were calculated and are shown in Table 2.
4.
The Nearest Resident Figure 1 shows the Windsor area in relation to the Combustion Engineering plant site.
The nearest resident is located about 640 meters west of the fuel fabrication facility as reported by the licensee.
E.
Environmental Imoact from Routine Plant Ooeration 1.
Methodoloav for Radiolocical Assessment The general approach used to demonstrate compliance with the dose limits of the regulation (40 CFR 190) is as follows:
(i).
the quantities of radionuclides discharged into the environment from plant operation will be monitored.
(ii).
environmental dose models developed by the NRC to esti-mate dose commitment rates from all significant pathways will be used.
A detailed environmental monitoring program will be required to supplement effluent monitoring only if potential noncompliance is suspected. The above approaches to demonstrat' compliance
O i
7 5=
$2
$h il s:i N II" h c)
Y. L * 'k f
- 3 h 4.., 2. : 3
= x.
C I h{
6 gpi=-s
-.jj S i e ils fii 3*
Il i
a
- w
,i z
z a
o.
0, 3
7*
C,
{
$, 3 3 2-a
= -
,1 s.
g{
m v
=9
,o,2*
-yU.
NIg
,==
d
,3 c
i 5 3
- I,g !,g l
b'y]a gy
=
w 3
3
$E3*3*
3' :
C as
-x1.
l 4
t}o=o-lag Is:
13 j i 'I :!
- 5 j,g :lMij'i z
~g o
i a, s..,, g : s a < 3 2 -== 3 j i 'e t r e -
i I
j g
. s a
v<: -<31 g
- -gs*g
- *
g*33I**j 9
o za3 3 c'
3 '3 I 3
- 3 Yg TS U
I k*U5 y:-!:E*aa,.:!; 33 3
i-s-
'O k2!*ve A
=35 S
2 oow oss w
a w-e -
s
,oo E'
bI IYbif i 203 0#
2<
-~nson3-tosanuc1ca:segan; 9
1 x
~%se 2
g.
N(
N* * - \\a 2%g\\
A Q
r-.
s-is-n e ee
/
/
Q S
l
-G
~
R a
v<
L-,
4 r ml 8 f
.a g
f l
l 5
5.
i
- a
=
I*
r
a 8
C TC2CE C E **, C K 2' C C CT SCC CTC S T *= C C 24 2 C C f.
O &OOOO OS3 O OC
=4 3C DOOO DO OOO C OOScc 3 8 0 0 8 0 6 0 8 8 0 8 0 8 9 9 0 0 9 8 8 9 0 0 0 9 0 0 0 0 0 e 3 O
te. W m. 4..e..
. sm
.==
C
- m. l s -
O "a 4 C9 C C r, en gg C C gC C A
- NA 3== 1
- r?=='* C== 1
- ?
al"
&" C ="
=
7 O'*
W & 3 ** r ** me==== ?
-C
== CNC C A N e.
- 2 J' 4 - J' 8
@ OC CE 81 4 0 8 3 3 0 0 g 8 8 8 8 0 8 0 8 C
C A N # f* C &@== ef" 8#==
=*****4 O
- m9 m a g P= ** r O.e 4 W A ** C== C ge 4== N N se f O
w
.a.
. me m.
=.
4
- e 88
- * *
- e o e o e e e e e *
- e O
- 3m 3== y em
.1 %
- 9
3G N N **
C tr C s*= N O @ C em 3C ** W 4 ** @
O P. N 3 44eC a= a N se==== me #8*
If9 e e e e o e o e *
- e * * *
- e
>= C C C P P= P= s= Pm z C C C C. C e C C e C C P= ** P=> 9= t; C C C 2" CC OOC CCC C00 CCO CG OO C OGC CO COC UCC 2CC O CCC C* C C C Pm M C C C C CTC 0 0 8 0 9 0 t ee3 3 0 0 0 e s t 6 0 t t 4 3 3 % g 3 3 3 3 3 g OCO COOCOC OOOO TCC 8
.a
.a. ans an. naa.na is.e w
- a. line.ma e, ene ena Lea o
taa en. nee.e4 eine w ina
- n. en inie
.n.
ine O
g 9 3 0 $ 5 4 8 8 0 8 8 0 0 5 0 4
ed" Ja N a C n. N ll=
43 &== g C A. O 3 W* pm @ 4g.=
4 se y N P. 4
== N r. 4 C
4 in, e e.,a 6 nas tee em=== tem is. 6 w w in. ta.
8
@ O@ O
=P Pm N ** a* **
8 8'8* 4 N P= W* C== em C *a C==
8" C * * * =
- e 4======.e== Pm a'm O
c@ #% se== c Pm C== & 4 C" C N 4==
c== #8" NNNC4 O
C 4ft a 4 @====-@
g u8e N #% sy Pm e
e,f* #g A C e 884 89 C # @ @ 8'( f @ OM M
e e e e e e e o e e e o e e e o M
e o e e e e o e e e e o e e e e e
@ si9 N e e @ @==**(8*
N====**#-
at e e e o e e e e o e e o e o e e
- = @ C C ** P= Pm Pm Pm CCCC CCC Pm C C Pm km O'=
pm Pm >= Pm aC & C C C Pa.
Pm C C Sun Pm Pm h pm Pm em C T C C,C pm O OOCCOO4 OOC SCOOO C OOC 24 COO C1O OO 33 O OOO OO OCC OOOOOO C O
$ 0 0 8 9 0 0 S S S O 8 8 0 0 8 8 0 8 0 0 8 0 0 ee 8 8 9 9 8 6 5 0 8 8 0 8 0 0 8 0 0 0 4 4 4 3 O
ee en. W.na
- n. ina ea a..e es..a.e ene end O
ane nad as =ms ma.as a as and ena no ae =J 44 ene a.
O naJ w end W in. W
.a an. as a.
as - e.
O
== a== 3 e'* m P= @ % "W W 4me@ #
M N e4@ m c e
8=.2 am 2== ** A = = =
889 N 4 ** 4 O== ** pm N ** 4 6. **
- 1* **
e e C Pm # N "8' ** J* N C T
- 9 8'* C ** C 0
C Nh C # P= Pm C E - * ** ef 4 O
=e N 3 4@ Pm 3 3 -
4
.O.
"9 C 4 O gf.1 Pm C N N en p= q O
i #89 r,
====== N S # 89 N N afi P
C
4 3==== em N 894 e e eq
O sie 4. 4 as.==
sse a4 s81 e o e e e * * *
- e o e o e e e na e e o e o e e e e o e o e e o e N
e e e e e e o e e e e o e e e e Pe. O e em P= >= P= P= Pan Pm Pm C e C C pm C OO CCOCCCCO 3OcCO C
3 8 0 S S 0 0 8 0 0 0 0 0 8 0 8 N P* C Pm P'm h Pm Pm Pm Pm Pm C S C Pm >=
P's P= pm Pm pm P= Pm P Pm *m min g*
E T Pm Pm o
na,a te,;
.a..a w.ma and w is,.
4.
i.e ma
.a 4 OCOOO COC SOO OO OO OOOOOO OOO 2OO 3OO O O
4 &G 4@ # 4 N.f*
- i== @ G As T. 4
- 0 0 8 8 8 8 8 8 8 8 8 8 8 0 0 0 0 8 0 8 4 5 6 8 0 8 0 8 8 8 8 e
er a T e C ** **" >= C af* 3 P= C @ N 889 O
Laa tes laa in, w as es ana n,p.ns w as b W ieJ 6ed O
la# 1.aJ w and nad tad nad had taa w led end tad taJ no ed O
N C. 4 se Me N N N M== ens A 4 W@==
N O 4 PmP= O W es at9 4 9 ** uf* ** ** @ W N
Pm 83* @ G 4@ W T445@ @ 7 3 @
N e e e o e e e e o e o e oe e o O
Pm N A
====@
itt O P= N af* 4== 889 889 0 0
4 P= M== @ #89 4 edi U @ p 33.l% @
O M**@
N 889 M 889 4 @ na ** C Pm ** ** N O
N seeeN Npewgaer N e@ en C
.'t N m
. N se e e ee e e e o e o e o e o e e se e e e e o e e e e e e o e e e e 0=. P= en. pin p=. 9m pm km P= P= P= Pm PetPm Pm 9=
6 0 0 0 8 9 0 4 4 0 0 9 8 0 8 0 O
ea ted one ens Les== led
.ma ma en. w ena enn ned taJ O
O P.,,l%
O.t N@ O@== @ 3 ** *= pm==
>= P. Pm Pm > >= *= 4 4 pm H= pm Pm P= P= em P= pm P= pm P. P=. P4 0 *= pm Pm p= pm p= P=
o ar== 4 Pa. N @ @ @ C 9 W* t. N N M W9 OOOOOOOOOO 3O ODCO OOOO CO OOO OOO SCO O O
4N = ** @ ef9 J' 4 @ a8e N N==
8 8 8 0 9 0 8 9 0 t t S 9 0 8 9 9 0 0 8 0 f 9 0 4 0 8 0 0 4 e t
==
e o e o e e o ee e.
e e e e
- 9 w en,.ma na.ns is na,e had.ma tad ta' Las in, taa nas Ind 85 W W taa one las aus W w ins. W inJ one is. end w 4.#
iaJ O
@ N N O '89 ** O ars==== # @ C 4 Ne 6ad O O til @== -s ar se eu em e C @ oe4
.A==
M 889 It1 4 9 @ ** O W9 O @ 8% & & 4M J==== P= G W 4 Pm W== em Pm O,#9 @ 881 4 O 4 P. Pm em 4 4 4 4 4 4
- mm om em Pan P=
== 0
@ 889 N eti P= e 9==== 4 *9 N *= ** P89 @
- O pm W s89 A Pm e @
me P= gy ng== N em 4 O OO OCO OOOC
't C C C C O E W1 e * **
- e e a e e e *
- e *
- Z W4 e e e e o e o e oe e e o e e o et O t 4 5 4 0 0 8 0 0 5 8 0 0 0 0 tad O tas b ins nn ind Ina see teJ as, w is a lad t'. W w w 2
F3 2
=m (J
.f% edi A ed* O 4 9 *% 4 d4
- 47 N&O se ein so
- e e
p= C @ em #89 J' tt' C 4CO@ 8'% W ** fi 2
Z W4
== gft er 9 ** *= **== N== 4 =89 ** a89 4 @
- 9 4 Pm P= 4 4 4 4 4 4 4 Pm DeP=F* Pm 4 end WS 4 P= P= 404444 4 P= P= *= Pa= Pm o pq e e e 9 e' e e *
- e'
==
9 8 8 4 0 8 8 8 0 8 44 8 9 9 0 na **
9 8 8 8 8 8 8 0 t 8 0 8 4 4 4 0 t
ee a
tea h a4 W e6 6 ans nas w w to tee 6 ted w la.
WG Led nad te. has b had W w haJ ina b, 6 in. 6 ed
.D P= Pm 4444444P *= >*' Pm 8* 4
- E tfi
@ 4 8%s 4 *= N 4 3== C - * *
- 4 *= 8'%s==
Efa de @
C P= P* O EF C As== c C C C g a8= g 4 em he C CC O. C. C.
O. C C. c C.
CC COC Q8 O C N - 4 C C== = ne = 4 C C E0==
u 2.0
- 83. @C==== Id* *= @ esa== N. N.4. C.,A
,f* N.
C sz w=
=ue 0 8 0
.. w w ta. w s
,a. sa. sa.
=
'N 4.t
. e.= N.,=89
.=.c 5 M S 0
0 0
8 0 8 2=
w s t.0 e.
p. e =.e==
.e x e se.
a.
==
e e# e <.e..
2 =
<o e a e
e.-.
,,,4 4O W si a.8% C 4 Q ert @ Pan N P= 4 P=== 881 O
* Q e, t
e W== N ** @ *= N t/9 44 4 4 # Pm C M G
E C el W 2 me
'Nc4m N N N e8s== @ @ T q m se C
o e e o e e o e o e e o e e e e e=
c >=
CC 2
4 4 P= 4 4 <0 4 4 4.1 d Pm 9 f* 44 12 44444444 4 4 4 > pm p=
44 ese W
O OCOOC OOO OCO OO CO OW C COC C O O C.* ** C
- iCC C
>=
4 4 Pm 4 4 4 4 4 4 4 4 ** b P 44 I
O D 8 9 0 0 0 4 4 5
- 8 0 0 0 8
- = I 5 8 S $ 3 eae t 8 0 3 3 0 8 as C CO OOC CC @ CCCOcCC C
A tas 6 es. k e6 W W 6 had 6 =a. b h 6.ma 60 w h In. tw k tas E
.a. ts. 64 w 6 es. W h y
O 9 0 0 8 0 0 0 0 8 9 0 0 8 8 8 e naa @
- = 0 M tfi N O C O e== C *= *** m E laJ W Pm it' @ O m9 C O 4 C wt== no 4 s* O W C 4 4 s** 4 s=== iAi ec== P= 4 C'*
C M
==
O tw let hasb 4 6 w 66es. Wla.W 6 6 lee ef 0 0
C4 U1 8
==
sr C 4 na W= > M W" =89 N pm C* O== C a
O C 4@ pm C4CE O P= C NP T 4 4t%
- 81 M em Pm *= N N N 09 4== ** 4 hf% @ *e =e I
M
- b ** *= ** N As M. 888 M t%$ am P= bf P= a=
g 8 e C #% 1,f" C@
s** ** C >= As 4r e C s8* P= c en
- F ** e# e o e e e # e f e' 8 **
- C
' e a e* e ** a e e a e e* re e e8 o eg 79 prl en p Ag N a8% p8% s*4,tg fig me T, Pm pn as N g
- # e' 8 # e'
- e 8 ** f # **
- te.
E a8 83 taJ 444 4 4 4 4 4 t/t 4 4 4 4 4 4 4 444 4 4 4 4 4 4 4 4 4 P* ** 4 O EmA 444444444444.O4404 3
O CO OCOCCOCOCCOOO OCOOCC OCOOCC OO00 3
OOCO OOOOeeCOCOC O lan O
O 9 0 0 0 I O O O O O O O O 8 8 0 I 3 0 0 0 0 0 9 9 0 0 0 I O I
=J 0 0 0 0 4 4 6 4 4 #
4 8 0 S I I O
naa h 4 6 6 h 4 na ta w em ta 6.a. be. E b tea h h Aa, E h h w h h w w w h nad
- 8 his Is. w is eeJ4 is m L is. E em 6 ii6
.6 E
'O M4@== 889 @ Pm 4 4 M 4 Pm 8 e 1" *** *84
>=
M O@ C edi @ @== >= N M S 889 4 @ N tai 3D 889 4 4 afi 4 as @ ett N 4 #.sa & C@ W O
.e e
== sa P= e 88e O N== C N P* 119 ** 88% @ C 2
0
- 4 fV r= C 88" @== 4 C C =* *F & G3 h R
4 O Pm 4 Pm8% 4 4 C @ C a86 O== C
-n InJ'** N P* N== 'o" @e 4 4 P" *= W f%8 * ** *" f% M had N
L/t==== N 88' W W If P* #9 *= ** @ @ "'* N 2
N 889 N ** f%8 886 EE W @ it' *** N e'= =*====M 8
JC e e e e e e e e o e e e o e Z
e e oe e e 3 e e e e e e * *
- e=
e o e o e e e e ee o e e e o e u taa O
3C taa 2
23 tt'! 4 4 O t#9 nfi nf% t#' W1 W9 4 4 4 4 4 ttl WS U
O cC O 2OCOCC OO COO O
O 9 9 0 B e9 0 0 0 0 0 8 9 0 0 0
@ 4 4 4 4 41/g W W 4 4 4 4 =0.o e w
<o.c 4 4,o e n#9 spit att 4 4 4 4 4 <a 4 9EO h tad w Em Es. ene la. nee 6 w k b 6 h la, tee u
O COOOO OcoCCeOO C C
OoOO CO OOCOCCOCC O laJ O 9.=>c. 4 at9== *'t C *= M @ '89== et* O tr 4 at 9 8 0 0 0 8 8 0 9 0 0 9 0 9 #
E'4 0 g 3 3 3 0 e3 0 8 8 ea e8 0 e en e e Er
- m. 4 at 4.== A N O C 'S me P===
tas 4 nad W w tan esi, w naa w 6 Lea en, and has Las.
Las taa saa sad la. tan in, ta.s W ha 6 w lais u, 6 tad 2 w==
As em @======== N se== c W W W em==
Ad Pm C t#1 3 N 4 889 C ef% 4@ ? C O P' 88
=aJ A0
===O W== N 4 s ur C 4 ar,== **
=9 w9 2&
e e' # e e'
e
- e o e e e e e e' e W
G
- C O N P= 9 C== Pm @ W* L/* = A8 = = *
- 3 0
W 4OC W P.
O N s8* @ 4 9 ** #m na w Q%
C e-
== s89 N 4 e O====== 4 & N N N 4 J
=E se e ht* O 4C@== =e== c 4 N As N g om uu g
r se # # e* e er e* e # # # e'
- # e
- a#
e* e= ** a a e* # # ** # e e* ** e ens Wt ett @ @ It9 4#" n/L W W W W1 ef* W4 nf4 lt" 1/I C
g et eCc acsCOCOCCC OOO n=
O ** O O O O 8 0 8 8 8 9 0 8 9 5 0 0 8 C
- e et O
tea w w kn 4 m 6 m. See nas en/ tad k ins 4 and had T
Q O ef9 Pm %== O %D 40 W af% >= @== N 4== C att C
t#n 4/4 4 tf* 1#9 TJ4 Itt 1/9 t/9 l#t @ e 4 <0 W9 tt*
u itt igg ett tg't @ ett ;/t gtg q/t nf* @ 4 4 4 gJ= if*
2 **
- e== ** e C r89 6 f%s== 0 AJ et 4 ** W afi at O
C COCCC CCC CCO OO CO
- =
P= N== 889 @ 4 4 Pm em 4 N==== mon M u
eS 9 8 9 8 8 9 0 0 8 0 0 0 8 0 0 8 8 0 0 0 0 3 0 8 8 ea 0 e 8 22 e
- e o e e e e e o e e e e e e nas ted las w ess W has 4 ta. Lad and w tsa taa LaJ w fl teJ taJ W ted taJ w w ta, tad Las tad had k Lee w ta, W
2 ee W *r ame C 4 l#t J4 s** 4 889 4 ( 84 89 :" 3
- ===
G@ D f%s =0 0 Lti *= ** *** 9* C 3 ** af9 F*
e W
9 P* f% 3 (F Pm em N pun 4/5 As W 8 C W9 889 O 2
9 4 P= N O 4C *** 2 As C @ it" W mm em N O end
>=
'uf4 F8% as @
a= N s84 est est it". "%g so C P Pm em N 6se
^idi N ee== em N s89 M gr 3 As ao O >= 5== N 2O LaJ e
e' e# ** e e* e e e e e e'
e f e 1
e e e e' e ** f e e e e e' e' ** e e laJ d4 T.
O M
InJ 2" taa 2 tse u
e9 C 7 C >=
ena 2 taa 2 tsJ ee er====
.r.e Q o=
Q Q *=
a=
o= e3
.=
6
= =
99 3 u mm 9)
D= W9 3 as and T O
u
- = u en 3 S T tad F C
Lea T E 2 ** W nna hd Lad taa 1
4 T
J
==
2 C",
tad T
E 2
2 O
E O taa Las taa and 2
2 1
2 z sa, tad es ta, nnJ ina O206 2 taJ z n in,481 ean 7 12 x== a y
n av 2 as 22 z r e= cc z ins = n tas ei n 2 en 22 2 u *E 2 2 2 e saJesW3t#989 WiFI 2 2 2 2 2 u O n.E 2 2'iaJ*nJ meif3 F7 #9 Ef) W* 3 2 2 E 2 WI O aim E 2 2 eaJ 'eh$ ed III II II II 4 3 I2EE e
=
9 are in conformance with the recommendations specified by the EPA in their Final Environmental Statement (FES) for Environmental Radiation Prott.ction Requirements for Normal Operations of Activities in the Uranium Fuel Cycle.6 The source terms (radioactivity release rates) from the Windsor plant operations are actual measured values.
The atmospheric dispersion model is based on Regulatory Guide 1.111.7 Other environmental pathways and models are based on Regulatory Guide 1.1098 with the exception that for the inhalation pathway, the dose conversion factors for the organs of interest were gene-rated by use of the ICRP Task Group Lung Model.S72 The dose conversion factors from the Lung Model depend on particle size and the solubility of the radioactive coupounds released.
If this information is not available frcm the licensee, a reason-able or conservative approach will be applied for the radio-logical impact assessment.
For example, the particle size is assumed to have an average diameter (AMAD) of 0.3 pH for effluents passing througn HEPA filters and 1.0 pM AMAD for particles not passing through HEPA filters.
The particles were conservatively assumed to be 100% in insoluble form which will provide a maximum lung dose for the inhalation calculation and then 100% in soluble form which will provide a maximum bon.c dose for the ingestion pathway.
It is only when such conservat'ie assumptions are critical to the standards (i.e., near or exceed-ing 25 mrem /yr) that the licensee will be required to conduct studies to obtain site specific data for a more realistic assessment.
2.
Maximum Individual Dose The radiological impacts were assessed by calculating the maximum total body and organ doses to the closest resident, who is living at about 640 meters west of the Windsor plant.
Except where specified, the term " dose", as referred to in this assessment, is actually a 50 year dose commitment, that is, the total dose from one year's intake of radionuclides to the reference organ that will accrue during the remaining lifetime (50 years) of the individual.
Table I summarizes the semiannual release rates of airborne and liquid effluents which were used as source terms for the radio-logical assessment.
The release rates are measured values and were reported to the NRC by the licensee.
The semiannual release values were averaged for a representative six month figure and then doubled for use as the calculational source term.
v
10 Radioactive liquid effluents flow from Building Nos. 5 and 17 through the radiological waste lines which are routed to Building 6, the radiological waste water treatment plant.
After testing and possible dilution, the waste water flows into the indus-trial waste line where it is carried to the site creek and then to the Farmington River.
For this caculation 2.28 mci were assumed to be released to the Farmington River which will further dilute the effluent.
An average flow of 1045 cfs was measured downstream from the plant at a USGS gauging station at Rainbow, Connecticut.
Data was collected at that site for 37 years of record.
For airborne effluents released into the environment, the pathways considered in the individual dose estimate include (a) direct irradiation, (b) direct inhalation, and (c) ingestion pathways (vegetation, meat, milk) due to airborne deposition.
For liquid effluent releases, the pathways include (a) potable water, (b) aquatic food (fish), (c) and shoreline deposition.
The models and various assumptions used to calculate doses from the above environmental pathways can be referred to in greater detail in Regulatory Guide 1.109.
Table 5 summarizes the results of the estimated maximum annual dose to the nearest resident from airborne and liquid effluents.
As shown in Table 3, the critical pathway is due to inhalation which results in a maximum dose to the lung of 1.97 x 10 3 mrem /yr.
The staff also considered a critical individual at the nearest residence.
In the inhalation pathway, the critical individual is an infant 0 to 1 years of age. The lung dose to the infant, representing less than 0.02". of the environmental standard,,will be increased by a factor of about 1.8, i.e.,
3.55 x 10 3 mrem /yr.13 Therefore, the staff concluded that the maximum annual lung dose is well below the 25 mrem annual limit as specified in 40 CFR Part 190 and that there is expected to be no adverse effect due to effluent releases from the plant's normal operation.
F.
Conclusion and Recommendation The normal operation of the Windsor fuel fabrication plant results in the release of a minute quantity of radioactivity into the environment.
Based on current operation, the annual release of radioactivity includes 7.52 pCi of low enriched uranium in airborne effluents and 2.28 mci of U in liquid effluents.
The nearest resident is located about 640 meters west of the plant site.
The annual lung dose to the critical individual at the nearest residence was estimated under conservative assumptions to be about 0.004 mrem /yr.
This represents less than 0.02% of the EPA standard as specified in 40 CFR 190.
The staff therefore concludes that there is no adverse impact from the release of radioactivity due to routine operation of the Windsor fuel fabrication plano.
11 Table 3 Estimated Maximum Annual Dose from Airborne and Liouid Eftluents to tne Nearest Resicent Pathwavs Oroan Dose (millirems)
'~
Total-Body Lung Bone A.
Air Effluents 1.
Direct Irradiation 7.26 x 10'7 2.
Direct Inhalation **
1.03 x 10 6 1.97 x 10'3 1.66 x 10 5 3.
Ingestion Due to Airborne Deposit a.
Vegetation
- 4.73 x 10 6 7.65 x 10 5 b.
Meat 1.93 x 10 8 3.11 x 10 7 c.
Milk 7.99 x 10 a 1.60 x 106 8.
Liouid Effluents 1.
Potable Water 9.23x10:
5 1.49 x 10 3 2.
Aquatic Food (Fish) 5.32 x 10.4 8.60 x 10 5 3.
Shoreline Deposit 1.13 x 10 11 Total (millirem /yr) 6.31 x 10 4 1.97 x 10 3 1.67 x 103
- Includes nonleafy and leafy vegetable; since site specific information was not availaDle, the staff assumed 76% of the produce and 100% of the leafy vegatables ingested were grown in a garden at the nearest residence.
- Assume 80% residence time.
12 The staff realizes that the nearest resident located at 640 meters west of the plant might not represent the maximum impact from the Windsor plant operation. The staff estimated that the maximum impact in the unrestricted area is at the site boundary about 180 meters west of the site. The X/Q at this location is 2.04 x 10-5 sec/m3 If a critical individual lives at this location in the future, the annual lung dose is estimated to be 0.04 mrem /yr based on the existing release rates from plant operation.
This dose is still well below the 25 mrem limit. The staff estimated that the release rate of airborne effluents would have to be increased to about 5,322 uC/yr in future operations in order to exceed the 25 mrem limit for an infant living near the area of maximum impact.
To insure compliance with the regulations, the staff proposes a license condition requiring an action level on effluent releases.
Since the liquid effluent is not the major pathway in individual dose calculations, the action level will be based on measured airborne releases. Even though the staff's analysis shows that an effluent release of over 5,000 aCi/yr would be necessary to exceed the 25 mrem limit to the critical individual at the nearest site boundary, considering present release rates of approximately 6 uCi/yr it is the staff's opinion that in order not to violate principles of ALARA, a somewhat lower action level should be defined.
The proposed action level will be a reporting requirement unless circumstances warrant more strict enforcement.
The staff then recommends an action level on the release of airborne effluents to be at 3 uCi of U per quarter, which is equivalent to an annual lung dose to an infant at the nearest site boundary of about 0.014 mrem /yr.
Accordingly, the staff recommends that the following conditions be added to the license:
1.
If the radioactivity in plant gaseous effluents exceeds 3 uCi per calendar quarter, the licensee shall, within 30 days, prepare and submit to the Commission a report which identifies the cause for exceeding the limit and the correytive actions to be taken by the licensee to reduce release rates.
If the parameters important to a dose assessment change, a report shall be submitted within 30 days which describes the changes in parameters and i cludes an estimate of the resultant change in dose commitment 2.
In the event that the calculated dose to any member of the public in any consecutive 12-month period is about to exceed the limits specified in 40 CFR 190.10, the licensee shall take innediate steps to reduce emissions so as to comply with 40 CFR 190.10. As provided in 40 CFR 190.11, the licensee may petition the Nuclear Regulatory Commission for a variance from the requirements of 40 CFR 190.10.
If a petition for a variance is anticipated, the licensee shall submit the request at least 90 days prior to exceeding the limits specified in 40 CFR 190.10.
13 References 1.
Environmental Protection Agency, " Title 40 - Protection of the Environment, Part 190 - Environmental Radiation Protection Standards for Nuclear Power Operations," Federal Register 42(9):
2558-2561 (January 13, 1977).
2.
Combustion Engineering, Inc.
Environmental Imoact Information, Windsor, Connecticut Plant Site, Docket No. 70-1100, winosor Connecticut, (Octooer v 1974).
3.
STAR Program for On-Site Data Diffu:fon Climatology, WESD, Monroeville, Pennsylvania, (1972).
4.
" Meteorology and Atomic Energy," David H. Slade, Editor, USAEC, Division of Technical Information, pp.97-104, (July 1968).
5.
Snyder, W. H., and R. E. Lawson, Jr., " Determination of a Necessary Height for a Stack Close to a Building--A Wind Tunnel Study," Atmosoheric Environment, Vol. 10, pp. 683-691, Pergammon Press, (1975).
6.
40 CFR 190, Environmental Radiation Protection Requirements for Normal Operations of Activities in the Uranium Fuel Cycle, Final Environmental Statement, Vol. 1, pp. 143-146, USEPA, (November 1976).
7.
U.S. Nuclear Regulatory Commission - Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Oispersion of Gaseous Efflaents in Routine Releases from Light-Water-Cooled Reactors," Office of Standards Development, (July 1977).
S.
U.S. Nuclear Regulatory Commission, Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," (March 1976).
9.
Task Group of Committee 2, ICRP, Task Grouo on Luna Dvnamics for Committee II of the ICRP, Health Physics, Vol. 12, (1966).
10.
Task Group of Committee 2, ICRP, The Vetabolism of Comoounds of Plutonium and Other Actinides, ICRP Publication M, Pergammon Press, Oxford, (1972).
- 11. Houston, J. R., D. L. Strengh, and E. C. Watson, DACRIN - A Computer Program for Calculating Organ Dose from Acute 3r Chronic Radionuclide Inhalation, BNWL - B-389,.Battelle Pacific Northwest Laboratories, Richland, Washington, (1975).
12.
M. H. Momeni, Y. Yuan and A. J. Zielen, The Uranium Dispersion and Dosimetry (UDAD) Code, NUREG/CR-0553, ANL/ES-72, Version IX, (1979).
- 13. NUREG-0172, Age-Specific Radiation Dosi Commitment Factors for a One-Year Chronic Intake, BNWL, (November 1977).
_-