ML19256F412

From kanterella
Jump to navigation Jump to search
Excerpts of Semiannual Rept,Jul-Dec 1971,Section II: Radwaste & Environ Monitoring.
ML19256F412
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 12/31/1971
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML19256F405 List:
References
FOIA-79-491 NUDOCS 7912190106
Download: ML19256F412 (11)
v • d • e


Text

. ..

f'

? l 3

,/ O c^&

N i

. ,O QUAD-CITIES STATION SEMI-ANNUAL REPORT

, JULY 1,1971 THROUGH DECEMBER 31, 1971 SECTION II: RADIC ACTIVE WASTE & ENVIRONMENTAL MONITORING cxce ntr_s 1625 153

^--

7912190 b,b _

A, Int-c a ::i : .-

Quad- Ci:ie s 5:1: ion, two General Electric hoiling water reactors, generatin;; 500 :.;~.'7e (2511 A1W t

) each at full load, received an AEC license :n Octche: 1, 1971 to operate Unit 1 at 25 MW t . At this power level, love pov.e e s:ing of the reactor was conducted without steam being for~.ed in :he reactor and control instruments, and other reactor systems checked. Testing of the reactor did cause fission product radioactivity to be produced, thereby requiring processing of liquid and gaseous effluents in the radwaste system. During the fourth quarte r of the year, about 4/10 mci (excluding tritium) was released in liquid wa ste and only a few picoeuries per second of particulate radioactivity were released as airborne activity to the environs. Most of this latter activity was not distinguishable from that of background origin.

For reporting purposes the radiological monitoring program went into the operational phase upon reception by the station of the license. However, for all practical purpo ses, the results of environmental monitoring reported herein reflect only background activity, The field sampling program in effect at Quad-Cities Station was established to systematically study the environment to determine its radiological characteristics, to ascertain the identity and concentrations of radioac'ive naterials in the various segments of the environment, and to identify probable sources of radioactivity. In order to meet these objectives the Quad-Cities surveillance program monitors air, precipitation, surface and ground water, soil and vegetation, milk and animal forage, acjuatic biota and bot'om sediments, and the exposure from ambient gamma radiation.

The sampling locations are listed in Table 1. The locations of three j onsite and 13 offsite air samplers are shown in Figure 1. The sample i codes used in this study are presented in Table 2. The types of samples collected at each location and the frequency of collections are presented in Table 3.

B. Gasecus Wa ste The total cuantities of gaseous radioactive waste discharged from the Quad-Citie s Station during the reporting pe riod were as follows: noble ga ses 0 Ci; iodines C Ci; and particulates < 1. To x 10-4 Ci. The measured ,

concentrations of particulates in the chimrey and vent stacks were 0. 3 pCi/m 3 or less which indica:es that most of this activitf was of background ot igin.

Gaseous vastes ri_essed from the station are summarized in Table 4.

1625 154 _

e

. o g3eous radioactive waste released from Un:: I wa s discha. ;c :-or-g Units 1/2 chimney at the icilowin; rates: nobleCi/ gases 0 aCi sec.

sec, whici. acn it f, jodines O Ci/ sec; and pa rticulates 13. 3 x 10-0 as noted above, was not distinguishable from that of background ori;in. '

The percentages (Q of release limits fo- noble gases, and iodic.es :.us pa rticulate s during the reporting pe riod . vere: 0 and 1. 4 x 10 -M ,

re spectively. Average discharge rates cr Unit 1 out of its ventilati:n stack were: iodines 0. 0 Ci/ sec and particulates 13 x 1.0-0 9Ci/ s ec.

Percentage limit for the Quad-Cities Unit I vent stack was o.5 x 10-3%

for the iodines plus particulates. Gaseous release rate data are shown in Table 5.

Maximum station gaseous activity discharge rates for a 24-hour period are presented in Table 6. The maximum station iodines plus particulates discharge rate through the chimney and vent stack for a 24-hour period, 5 x 10-2% of the annual average release limit, occurred during the period November 8 to 15,1971. This activity was not distinguishable f rom that of background origin.

Isotopic analyses of Quad-Cities Unit 1 off gas were not conducted during the reporting period because only 1% power was attained and no steaming occurred.

C. The Air Environuent

1. Airborne Particulates The airborne particulates were collected weekly from 16 locations.

The collection dates during the second six months of 1971 were as follows:

July 10, 16, 24, 31 August 7, 14, ?.1, 28 September 4, 11, 18, 25 October 2, 9, 17, 23, 31 Novembe r 7, 14, 20, 27 December 4, 12, 18', 24, 31 The results of the airborne particulate analyses for gross alpha and gross beta activities are given in Tables 7-22 and graphically presented for eight locations in Figures 2-9. Weekly and monthly averages of all onsite and off site airbo rne particulate activities are given in Figures 10-14.

Generally the airbo rne concent ra tions of g ross beta activit'f decreased throughout the reporting period Icom its peak of 0.6 pCi/m 3 in 313 .. Beta activitf at the end of December was only one-tenth of the spring peak which was similar to the pattern ob served at both Dresden and Zicn Sta;ians during the same period. hiont:tly are: a ge acti. itie s at the onsite stations we re highe r by O.1 pCi/ m 3 than offsite stations during the spring and ~~e'.

=

Howeve r, the levels vere nn-ilar .c. the fall an' winter of 13 1.

l.,

2 I m/- -

iu1 t t 0 O 0 0 ii r n -

Ti l 5 b I - ' - -

t 0 0 o l

0 1 1 1 i

n i

t x x x x l t A n 1 8 5 7 s Ve 6 2 7 4 e 1 2 5 4 t

l a

u 2 c /

i t 1 r t a i 5 4 P n - ' ~ -

U 0 0 0 0 1 1 y 1 1 e

n x x x x i

m 9 4 3 1 h 3 0 7 3 C 4 5

3 1

yd r e 1 agn7 mrai o9 1 mh uca r t 1 t

i t

n 4 S sS e i U E eDs b t L

t em n e

0 0 0 0 s si e B aet c i V A WirCe D s T s u e J3J >

u C. da - n 2 1 " (gy ~ J,;% h m a$

  • = J &, C Nt *WM C C"T".

- i / " is ol uy -

d .

e t

e 1 '

s taQlu o g ao J I

i t

n GT U y

e n 0 0 0 0 i

m i

l C s e

s y

l a

n a

/ 2 ,

s

. e I. / l 1 e p s s e t l

" " m a y s n i

- n l a a U n a s G

i n e y .

a t l

ee r c

i s

a n r 0 0 0 0 i

> o nom p [

p

> o Mih ( t m

o C t s o = .

o i c eOw

=

= .

N " " n n  %

. o o

- d d e e

_ s s a k i

i 3

1 I h .

l a

t n y g t p t v c t / /

o . l u o e 1

s . I n

\ S e

J c

N D 5 I

l 1 2

TABLE 5 i

Average Gaseous Waste Discharge Rates Unit 1 * '

Quad-Citics Station July - Decembe r 1971

~

r

\P_e rce n,t]E [L l}- [s - i_Iskit $

~

A he ih[lkr(( h th j h h h ((,, [ _ , ,

__ _thebel Ga mes . Io.li ne s Pa r ticula t e s Nobt.e' Ga s c o ~~ ~ I. .

  • a t e lii:;cha rge lla te l'erceni 3/ Date Iodine Discharge Date Pa r ti cula l e 1 )a t e l'e rcent ' (pt:i/::cc) of I .iinit Itate (pCi/sec) Discha rge of I.iinit llate (p Ci/:.cc) .loly Not Operational' T Aug. " " ( ) O h.ei>t. ,, ,, Z Oc t . (all <la t e s) 0 y
    • g0 Oct. (all dates) 0 10/26-11/1 1. 94 x 10- 5 10/26-11/ I 3. 21 x 1 CfD Nov, (all dates) 0 -0
    "'P" Nov.(all dates) 0 11/8-11/15 3. 3 7 x 10-5 11/8-11/15 5. 62 x I a-Dec. (all ilates) 0 D 0 Dec.(all dates) 0 12/13-12/20 1. 9 8 x 10 - 5 12/13-12/20 5. 3 0 x I \ _.. 1,/ Value.s a re based on routine isotopic analysis. 2/halues a re baseil on routine analysis of a continuously collected sample. N J/ W ech. Spec. I.iinit is 0. 3 Ci/ sec for 1 Unit operation. _ m ___ 16fei h. tipcc. 1.iinit is 6 x 10- Ci/sec for 1 Unit operation.] CO -
    • ~
    ./ ---_--u ----.n.....,_..._.. - - - - um.m.m _ _ _ e & . _ ...._. .._ T TABLE 52 O lladioactive Waste Summary Z Units 1/2 C"") Quad-Cities Station -s.g C July - December 1971 , C"3 Total Curien,1I Total Liquid 1/ Total Dilution .2,/ Aver. Outfall _/ 3 Total Cu ries 1/
    Di s cha rg ed Waste Volume Volume Concentration Percent i of Tritium p at h hxclutling tritium) (gallons) (gallonn) ( Ci/ml) of Limit 11 el e a g l ,
    .luly NOT O P Elt ATIO N A L Au; . NOT O P E l( A T I O N A L Sept. NOT O P E II A T IO N A L ~4 10 - Oct. 1.27 x 10 1. 2 3 x 10 6 2.23 x 10 1. 5 x 10 ' O 7,08 x 10 5 10 Nov. 6.09 x 10- 2.01 x 10 8. 0 x 10-I 3 8. 0 x 10 'I O 1 -4 10 Dec. 2. 21 x 10 1. I 1 x 10 6 2.21 x 10 2. 7 x 10-12 2. 7 x 10 0 To t a l l.09 x 10-4 3. 05 x 106 6.45 x 1010 5. 0 x 10-12 5. 0 x 10 0 1/ Sum of releases froin Unit I /2 waste tanks. Total circulation water flow thiuugh Unit 1/2 during the month. L.n Ave rage concentration in outfall, excluding backg round. (Total curies discharged + total dilution volume) [ 1.imit for average inonthly release is assumed to be limit for instantaneous release of 1. 0 x 10-I p(:i / ml. p_/ Av. r. ige t ritium content multiplied by gallons of waste released. i v TAI 3LE 53 "C3 Weekly Maximum Concentration of Radioactivity Above Background O Unit I/2 Discharge Canal O Quad-Cities Station N July-December 1971 O ' x'2 . . ..- g I/ 2 _ 11.i t e Tiene of Itclease Wa ste Tank Discha rge Ci / ml- Pe rcent of 1.innit% / ~3 sst % .luly Not Ope rational August Not Ope rational Se pt . Not Ope rational (ht. 4 1722-2035 A FDST1/ 2. 98 x 10 -II 2. 98 x 10-2 Utt. 12 1725-1750 A FDST 3. 07 x 10-II 3. 07 x 10-2 d/ ()ct. 15-16 2130-0435 Unit // l (ht. 17-17 1030-0455 1. 7 9 x 10- 11 1. 79 x 10-z Reactor Torus Oct . 30 0310-0350 13 LDT5/ 1. 72 x 10-II 1. 72 x 10-2 Nov. 7-8 2030-0510 4. 23 x 10-II 4. 2 3 x 10-2 Nov. 12-13 2130-0450 A WS A FDSJ'l T- 1.12 x 10- 10 1.12 x 10- I 4 7/ Nov. 18 2200-2230 ALDT 8.69 x 10-I2 8. 69 x 10-3 Nov. 26 0855-1140 A FDST 3. 95 x 10-Il 3. 95 x 10-2 I )er . 2 1235-1900 AFDST 4I
    1. 09 x 10 - 10 1. 09 x lo-I 1)e c. 10 1110-1810 11FDST 4. 85 x 10-II 4. 85 x 10-2 1)cc. 18 0525-1145 11 W S T 9. 74 x 10-12 9,74 x 10-3 1 ).: c . 22 0023-0615 HWST 1. 06 x 10-11 1. 06 x 10 -2 Ch N
    Ln hlaximum concentration in canal above background computed from activity in tank, flow rate of condenser cooling water and duration of release. - $I l'e rce nta ge of unidentified relea se limit of 10-7 Ci/ ml. O il 1'l >ST - Floo r Drain Sa mple Tank. O 'I ' t.1. .nl iil y ma xi n nim. 'f 1.l sT i,ausniry D rain Tanh. ' ' ' , M ST - Waste Sample Tank. e M.iximum of six month repo rting pe riod. __ --u- _ - - - . ~ am _ _ _ ' - . ._ _._ a a:_ TA13LE 5 '- 7 Radioactive Waste Isotopic Analysis Units 1/2 Quad- Citic 2 Station July-Decem acr 1971 Compo site Sample 1/ Results:
    • Is otones 2 / Activity
    • lo . uCi/ ml Pe rcent of Comoosition Cobalt-58 & -60 (1. 87
    • 0. 25) x 10-8 o Strontium-8 9 & -90 (5. 30
    • 0. 99) x 10-8 18.6 Cesium-134 & - 137 (4. 5 2
    • 0. 46) x 10-8 15.8 3rd Quarter Not Ooerational 4th Quarter Curies Released Month Total Curies Co Mn Sr
    - Cs Oct . 1. 27 -- 10-4 8. 35 x 10-5 0 2. 36 x 10-5 2. 01 x 10-5 Nov. 6. 09 x 10-5 4,00 x 10-5 0 1.13 x 10-5 0. 96 x 10-5 Dec. 2. 21 x 10-4 1.45 x 10-4 0 4.11 x 10-5 3. 49 x 10-5 Total 4. 09 x 10-4 2.68 x 10-4 0 7. 60 x 10-5 6. 46 x 10-5 Average MPC Value = MPC = ( Ci) / (
    • Ci/ MP Ci) i Average Concentration4 /
    Is otoce 3 / C. u Ci/ ml MPC. uCi/ ml C / MPC 60 Co 1.10 x 10 - 12 5. 0 x 10-3 2. 20 x 10-8 Mn 0 1.O x 10-4 0 90 5: 3.11 x 10-13 3. 0 x 10-7 1. 04 x 10-6 134 Cs 2. 6 5 x 10- 13 9. 0 x 10-6 2. 94 x 10-3--
    1. 67 x 10-12 1,og x lo-o Ave rage MFC = 1. 54 x 10-6 Ci/ ml 1625 161 1
    T:.e compcsite sample analyaed wa s compos ed of the m.onthly J.oc.- drai . La , "'aste sa:mple composites for Octche:, ..ovember, ' a nd Decem c: . r T..: U activity levels present made identification of specific .uclicies npractical. _ T'.2 r:clide listed has the mo st rest ricti-ce '.:PC value of those :satopes 2-mmed present. r/ Tctal cu rie s of those isotones -- Total dilution voinmo. TAllLE 65 Solid Radioactive Waste Summary ) Units 1/2 Quad-Cities Station July-December 1971 Volume (ft3) Volume (ft ) 3 Curies Cu rie n . 1 ).i t i- 1)i:.13> sit ion of Male rial Per Shipment Per Month Per Shipment _l'e r Mynt h .icly No Shipment Au ;.e Ho Shi tunent ()ct. C No Shipment Nov. No Shipment C 1)ec. 8 "$ d Nuclea r Enginee ring
    1. 01 x 10-2 8 Co. , Sheffield, Ill. 551.25 E
    1)e c . 16 Nuclea r Engineering D 507.15 5. 85 x 10-3 H Co., Sheffield, Ill. Dec. 22 Nuclea r Engineering Co. , Sheffield, Ill. 536.55 5. 84 x 10-3 I)ec. 30 Nuclea r Engineering Co. , Sheffield, Ill. 514.50 5.60 x 10-3 TOTAL. 2109.45 2. 71 x 10- __.._.~____ --- - N G Cn o-i N 108 TABLE 67 Waste and Floor Drain Water Samples Analysis 1I for Tritium Quad-Cities Station Samole Date T ritium Floor Drain November Composite 0.55
    • 0.20 December Composite 0.41
    • 0.20 Waste Water Tank November Composite 0.51
    • 0.20 December Composite 0.57
    • 0.20 1/
    Activities given are in pCi/ml. The error given is the probable counting error for the 95% confidence level. i i 1625 163 l *
    • Retrieved from "https://kanterella.com/w/index.php?title=ML19256F412&oldid=2611498"