Text

Forwards Errata for Radwaste Environ Monitoring & Occupational Personnel Radiation Exposure Sections to Semiannual Rept for Jul-Dec 1974
	ML20037B481
Person / Time
Site:	Dresden
Issue date:	03/20/1975
From:	Stephenson B; COMMONWEALTH EDISON CO.
To:	James Keppler; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
	178-75, NUDOCS 8010100472
	Download: ML20037B481 (26)
	v • d • e

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@T Acdress Rept, One First Naticaal P aza. Chicago. I!Snois UlOf()7y

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'370." {r[i' James G. Keppler, Regicnal Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Comenission

.p fl 799 Roosevelt Road

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N G1en Ellyn, IL 60137 SURTECT: Dresden Nuclear Power Station Se:1-JLnnual Report ' 'd NRC Docke' e lCb 50-237 and 50-249

Dear Mr. Keppler:

The Drasden Nuclear Power Station Sen:1-JLnnual Repert as required by Section 6.6.A.3 of the Technical Specifications for the period of July 1, 1974 throu6h Dece=ber 31, 1974 was sulmtitted at the end of February 1975 Subsectent to this submission, the report was reviewed again and certain data 1rere found to be in error or omitted. Attached is an errata for the radioactive waste, ene m tal monitoring, and occupational personnel radiation exposure sections.

Thirty-nine (39) copies of this errata will be subnitted directly to the Directorate of Licensing.

Sincerely,

/

^

"B. B. St enson Superintendent Dreedon Nuclear Power Station E33:RAC sib ee

3. C. Rusche File /KRC 80.10100fp p

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Am;nd3dt (1) April,1975 OCCUPATI0 ITAL PERSOIllTEL HADIATICII EXPOSURE :i' ART 1 h[ -l g

STATION Dresden

~ ~ ~ ~ - - '

(Per Tech Spec 6.6.A.3 1.)

The following is a tabulation of the number of occupational personnel expocuroc for plant operationn personnel, (Permanent and temporary) for the g

l January - December 1974 reporting period:

s Number of Individualc Exposure Permanent Temporary' (in Rem)

Emp1pycen Employees 9

219 No Measurable Exposure 40 35 Measurable Exposure Less Than.100 l

.100 -

.250-20 18 35 12

.250 -

.500 15 6-

.500 -

.750 14 2

.750 -

1.0 46 3

1.0 2.0 62 1

2.0 1.0 63 o

3.0 4.0 4.0 5.0 51 0

5.0 6.0 15 0

2 0

6.0 7.0 0

0 7.0 8.0 O

O E.0 9.o 10.0 0

0 9.o 10.0

- i!.o 0

0 11.0 - 12.0 0

0 12.0 +

0 0

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(1) April, 1975 OCCUPATIONAL PERSOUNEL RADIATION EXPOGURE:l' ART 2 u =,,.,,,=., u,,, g g g [ ~

STATION Dresden

~

,b ;i Ii?:

( Per Tech Spec 6.6. A. 3 1. ) -

l receiving The numbers of plant operations pernonnel more than 500 mrem exposure in the reporting period are tab-ulated below according to duty function:

Humber of Individualc Duty Permanent Temporary Function Employeen Employees Routine plant surveillance &

inspection 62 2

Routine Plant maintenance 135 6

Routine Refueling Operations 18 0

Other 53 4

l 162 plant operations personnel roccived more than 2500 mrem during 1974.

One hundred and sixty-two (162) individuals received more than 2500 crem at Dresden during 1974 in performance of the regular duties.

Of the 162, 126 were classified as either (a) equipment operators, equipment attendants, auxilliary operators, (b) maintenance - mechanical, (c) radiation protection, or (d) fuel handlers.

No major maintenance jobs were performed and most of the doses are the result of two refueling outages during the year.

1.

'?lant operations pornonnel" to interpreted an excluding vicitors, tour groups and contractorc.

2.

H.A. - Hot applicable for the.Tn.nuary through June neriod.

3 One third of total, remainder J ~ aanigned to el',her n m, 1,, n. 0 m '1 Ci'iae. or Zion ';ta t i onn.

Dresden S t.a tion 1Q4 Rep rrt

'f' Occupaticc.nl Fersennel Rad ht.1,n P ~nca 2cm.m anwe al ti- :-: dis zn F,mployees Wrrk Functirn F.eac:.r r Operations Routine : hint. &

J

're Fune:i r.

& Surcelliance Inservice Inspecti?n

. Waste Processing F.cfteling cf pe cle T.an-H 'i

.= cf re rie r.an-rer

!! of pecple T.an-rcr

!! of pec ple /T.an-rem

=

1

c.in enance 3 / 5 75 111 / 338.12

.'rera 'ns 57 / 79.04 29 / 99.85 15 / 53 92

--:e a h. h:cs '.2 s 5 / 18.53 15 / 60.21 2 / 9.26 1 / 4.63 3 / 9 54 super cis :ry 21 / 8.11 12 / 26.14-53 / 3.19

101 / 14.81

Insite:r' ns 43 / 62.85 24 / 2.0.78

~i 5 / 4.16

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no DRESDEN NUCLEAR POWER STATION.

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RADIOACTIVE WASTE AND ENVIRONMENTAL MONITORING JULY THROUGH DECEMBER 1974 k

ERRATA g

P'.rE 64. Table 5.3-5 Correct Tritium pCi/1 October-December to read:

D-19 260 70 4

D-20-1 320t70 D-20-2/3

-1080 80 D-21 430 70 D-22 410!70 i

D 320 70 I

PAGE 66 Table 5.3-9 Correct pCi/g (Wet)to pCi/g (Dry) 4 e

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SUMMARY

OF PROCEDURES s

0

'USED FOR ANALYZING

~ RADI0 ACTIVITY IN EINIRONMENTAL SAMPLES i'A MARCH 1975 y

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q Environmental samples are collected at those locations and with those frequencies specified in the Technical Specifications.

The samples are then brought (or shipped) to the contractor's laboratory for ana]ysis by radiochemical methods which are essentially identical to those procedures of the U.S. AEC Health and Safety Laboratory (1) or the U.S. EPA (2, 3), or that procedure for measuring I-131 in milk suggested by the U.S. AEC in Regulatory Guide 4.3 (4).

These methods, which are summarily discussed below, achieve the analytical sensitivities listed in the attached table.

Air Samples The gross beta (or alpha) content of particles filtered from a measured volume of air is determined weekly by " low level" counting of the filters.

When a gamma scan is required by the Specifications the filters are usually composited to increase the sensitivity of the analysis on the GeLi detector system.*

Charcoal cartridges exposed at air sampling stations are analyzed weekly or bi-weekly, as the case may be, for I-131.

~ dine-131 measurement on these samples is by gamma counting c

using a h" x h" sodium iodide (thallium activated) crystal and i

a single channel pulse height spectrometer.

Except where otherwise noted, a GeLi system is used for making all gamma spectral analyses.

l

(( (z. _....

ANALYTICAL DETECTION AND REPORTING CAPABILITY Sample Medium Analysis SENSITIVITY O Airborne Particulate Gross Beta 0.01 pCi/m3 Gamma Scan / Isotope 0.01 Gross Alpha 0.005 Iodine-131 0.03 s

Gara Radiation TLD C 20 mrem /yee r Liauids Sr-89 5

pCi/ liter Sr-90 1

1-131 4*

Cs-134 10 Cs-137 10**

Tritium 200 Beta 1.0 Alpha 0.5

'legetation Alpha, Beta 1

pCi/g wet Sr-89, 80 1

Gamma Scan / Isotope 1

Scil Sediment Alpha, Beta 2

pCi/g dry Sr-89, 90 1

G1=a Scan / Isotope 1

Fish Tissue Cs-134, 137 0.1 PCi/s " wet" '

n. ri p C *t /2 on milk namplen collected duriny, the pacture nean.n.

p'" / ! on ml!k.:arnple

'* i a " wet' - eight is an "as received at the laboratory" weight and in some instances the samples exhibit water loss during handling.

O Minimum reported activity at the 995 (3 g') confidence level.

i q.-..- -

Water Samples Gr.oss alpha, beta, or gamma spectral analyses of (surface, well, precipitation) water samples are performed by evaporation of a measured aliquot of the sample, digestion, and planchetting of the processed sample, followed by radiometric assay.

Tritium analysis is performed on water samples to a sensitivity of 200 pCi/l by isotopic enrichment and liquid scintillation counting.

Strontium-89 and -90 analysis is performed on the samples by standard radiochernical procedures followed by low-level beta counting of total radiontrontium plun Y-90.

Then the Y -90 is ceparated and counted to determine 3r-90.

Sr-89 is determined by taking the difference.

Mud, Silt and Soil After being dried in an oven, samples of mud, silt or soil are analyzed by gamma spectral analysis; much smaller portions are analyzed for their gross beta (or alpha) content.

Strontium-89 and -90 analysis is performed on the samples by standard radiochemical procedures followed by low-level beta counting of total radiostrontium plus Y-90.

Then the

(-90 is separated and counted to determine Gr-90.

Sr-89 is determined by taking the difference.

Fish Fish and other samples of aquatic life are analyzed for gress beta, Sr-89, Sr-90 and gamma-emitting radionuclide content by the procedures used by E.P.A. or HASL.

IW

_4_

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Milk During the time cows are on pasture, weekly samples of fresh milk are analyzed for r:111oiodine _ (as I-131) immediately upon receipt of the samples in laboratory by techniques similar to those specified in Regulatory Guide 4.3 This method provides a sensitivity of 0 5 pci/1 with an overall error of analysis

~

of 25%.

During the remaining period of the year, I-131 is determined by gamma spectral analysis.

Other gamma-emitting radionuclides are determined by gamma spectral analysis.

Strontium-89 and -90 analyses are made with standard radiochemical.

techniques followed by beta -""nting.

Vegetation a

Vegetation samples include food stuffs, field forage crops, grass, cattic feeds and similar media.

The samples are analyzed for gross beta and gamma isotopic composition after being dried, wet ashed, and plancheted.

Sr-89 and -90 are h

measured using techniques similar to those used on mud, silt, and soil.

Wildlife L

Samples of wildlife, such as waterfowl and rabbits, I

are collected as scheduled and analyzed by the procedures i

I referred to previously for radiostrontium and the gamma emitters.

l Usually only an ashed portion of the bone is analyzed for radiostrontium while only the flesh is counted for gross beta r

and ':he gamma emitters.

l

. 7~

=-

4 4

References 1

(1) HASL P'rocedures Manual, HASL-3oo, edited by John H. Harley, Health.and Safety Laboratory, U.S. Atomic Energy Commission, 1972 Edition, revised-annually.

(2) Radiochemical Procedures for the Analysis of Nuclear Reactor Aqueous Solutions, edited by H. L. Krieger and S. Gold, Environmental Protection Agency, Division of Research, August, 1971.

(3) Radionuclide Analysis of Environmental Samples,'A Laboratory.

Manual of Methodology, edited 'oy H. L. Krieger, Richard J.

Velten and Frantz J. Burmann, U.S. Department of. Health,_

Education and Welfare, Division of Radiological Health, revised February 1966.

(4)-Regulatory Guide 4.3 Measurements of Radionuclides in the Environment:

Analysis of I-131 in Milk, U.S. Atomic Energy Commission, September, 1973 l'

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str.WJtY OF LIQUID t.!:D CASEOUS EFFLUENTS FACG DRESDCi UNIT fl JULY-DECDSER 1974 J

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EN:tT_OMMCACTI'!E ETFLUFNTS g: 1974 Dresden Nuclear Power Station - Unit 1 OWT 5:)1 50-10

g...y,.

lNovEt3ER DECCEER 6 P.O. TOTAL TECit. SPEC. REF.

UNITS JULY AUGUST TEFT".' EER OCT03ER d

I.

i v.-r e I.r fite. t.s 7.0E403 2.2E+04 2.6E+04 9.9E+04 I

1..Oros-E?.iioactivity Releases curies 2.0E+04 2.4E+04

,shutdevn a) Tet I Kelesse 1.25E404 1.37E404 7.80E403 1.20 E+04 1.32E404 1.37E+04 h

M P-i- x1 ?eleasa Pate

_uci/fcc n

0 I

c) Iratc7es Released 3.0E+02 4.0EM)2 9.12401 4.0E+02 4.2 E+02 1.61E+03 curies YrMrt_..__

curios 2.5E*03 2.fE+03 6.8E+02 2.3403 3.1E+03 1.14E404 77_-?7 1.5 E+03 5.66E+03 curies 1.2E403 1.5Er03 3.6 E +02 1.1E403

_2.10E+03 curies 3.0E+02 5.0E402 1.5E+02 4.2 E+02 7.3E+02 ir 03 1e.133 curios 2.2E403 2.3E403 6.1E402 2.0E403 2.9E+03

1. ore +0ti I

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3.9E403 5.1E+03 f

1.3Et03 4.4E +03 4.9E+03 1.96E+04 h-1Mm

. curies 3.8E403 1.1E+04 1.2E+04 4.74Ea04 cu-ios 9.6E*03 1.1 E+04 l

).?-136 I

i i

I 0.49 1.54 1.72 d) Tercent of Chir.r.cy Limit 1.4 1.6

[ Shetd own 2.63E+03 8.61E+03 9.65E+03 7.49E+03 7.58E+03 9.01E+03 l

e) A.:rugejtolea:o Rate-uC_i[coc_

i 4

2.

Iodir.- 2elaa:es a) Ir.ct: as Released I-131 curios 1.2E-02 60 E-03 l3.0E-03 3.0E-03 2.49E-01 1.3SE-01 4.gIE-01 I-U3 curio:

6.9E-02 1 9E-02 1.0E-03 2.8E-02 2 99E+00 1.31E+00 4.hlE+00 l

I-133 curies 1.J1E-01 5.99E+00 2.50E+00 8.66E+00

5) Per:er.t of Chinney Linit 7'

O.2 0.1 (0.1 (0.1 4.0 2.1

) h.r p Kelcare Rats uCi/coc 4.0E-03 2.0E-03 1.0F-03 1.0E-03 9.6 E-02 5.1E-02 2.58E-02 I

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4 REPORT OF RADIOACTIVE EFFLUENTS It.CILITY: Etesden Nuclect Power Station - Unit 1 DOCKET t:05. 50-10 YIAR: l e ? '.

II.

'4 raid Effluents UNITS Jg.Y At'CU ST ETEMFR CCTOP.ER YOtT** 1FR DECE U R 6 MO. 70 *A L TECH. SPEC. REF.

G o:s Radioactivity (JY)

I I

a) Total Release Curies

,7.63E-01 9.79E-01 7.55E-01 9.2SE-02 1.65E-01 2.37E-01

' 2.99 E+00 b) Ave-age Concentration Released uci/ml 2.82E-08 3.62E-08

. 83Z-08 3.725-09 7.69E-09 1.10E-08

'2.03E-06 S

2 g

c) Maxbum Concentration Released uct/ml 5.74E-08 1.5CE-07 7.C1E-08 6.36E-08 5.57E-08 6.18E-08G) 1.5E-07 d) Tercent of Tech Spec Limit 28.0 36.2 28.9 3.72 7.39 10.97 20.27 2.

T rith-a) Total Release Curies 1.48E-01 1.70E-01 5.16E-01 2.09E-6 9.29E-04 7.02E-04 8.36E-01 b,

AveraEe Concentration Released uci/ml 5.5E-09 6.3E-09 2.0 E-03 8.39E-14 4.44E-11 3.25E-11 5.67E-09 c'

Fercent of Tech Spec Limit 6

3.

Dic:olved Ncble Cases ND ND ND ND ND ND

$ ND' n) Tetal Release Curies I

b) Averace Concentration Released uct/n1 c) Percent of Tech Snec Limit

. Groes Alpha RadioncJivity a) Total Re casc Curles 1E-04 3E-04 7.4E-05 3.75E-05 1.53s-04 8.39E-05 7.43E-04 b) Averace Concentration Released u ci/n1 3.72E-02 1.11E-11 2.EC-12 1.51E-12 7.32E-12 3.88E-12 5.07E-12 7.

Volu.,e of Liquid Waste to Liters 3.44E+05 3.41E+05 2.?3E+05 2.94E405 1.19E+06 1.07E+06 2.57E+06 Dirchurre Canal t

1.

702-cf Dilution W ter Liters 2.69E+10

_2.70E+10 2.62E+10 2.49E+10 2.09E+10 2.16E+10 1.475E+11

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NOTO: Nd = Fot Determined NA = Not Applic.ble

. (1)' Unplanned release of MLDT during controlled release of B SSCBDT. Con;na isotopic analysis indicated that 0.83 MPCs were added to the discharge canal during periods of discharge of both MIST and B.SSD5DT.

(2) Cawna isotopic analysis indicated that during the unplanned release of B LDT 14.44 uuCi/L were added to the discharge canal.

J 4

9 4

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)

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+

StWJULY OF LIQUID AC CASEOUS EFFLUENTS FROf DRESDEN WITS #2 AIG #3 JULY-DECDiIrm 1974 I

s f

l I

l

R5.I'O.tT OP. RADICACTIVE EFR.UE*;TS yrAg 1974 DOCK 2.T t OS.. 50-2'i7 50-71, g C; iLIII: Erceder. l'uclecr Pcwr Station *,.' nits 2/3 i

l C;1TS JL" Y AUG'JST SEPTEY.EER CCTO? ER I !;0'IE!:VR DECE?nr:t

6 MO. TOTAL TECH. SPFC. REF.

I re---:.

fin -.t s l

1,

&cr Jr_dios:tivity Releases 6.7E+04 5.2D04 2.9E+04 i.5E+04

7. 4E+04 6.9E44 3.46E405 6.6D.l. f. u )

e n) Tetd. Ecler.se c;rles b)

!*-cci u, P.eler? R.to t.Ci/ oe 5.56E404 3.15E+04 2.31E+04 3.4F W4 1.11E405 4.38E+04 1.11E+05 6.6D.1.f.(2)

J 6.60.1.f.(L) e) I?.etoics Released ceries 8 6E43 2.75+03 1.51E+03 2.77E+03 3.36E43 3.1E+03 2.21E+04 4.98E+04 i

7. -S curlos 1.09D 04 9.5E+03 5.7E403 9.40:+03 7.51DO3 6.8E +03 j

i Er r*

curies 8.1D03 6.9 E+03

4. 3';vo3 6.50E403 1.71044 2.0E+04 6.35E+04 Tr-.7 curico 4.4E403 5.2E+03 3.7E+03 4.70E403 2.3tE404 1.5E+04 5.63E404 I

yc 131 1.54E+04 1.49EiO4 9.7E403 1.16E+04 2.23E 44 2.4D04 9.79E404 ye.115 curios

'ic-13 3n curies 7.5E403 5.9E403 3.1D03 6.20E403 9.5E+01 2.27C+04 1.40 D04 1.2D02 3.31D04 curies 1.21E404 6.9 D03 p 13S

--. P -cent of Chirr.ay_Li tit, 2.95 2.22 1 33 2.45 4.06 3.65 6.6D.l.f.(3)

NA NA 1:A IIA 1A IIA IIA 6.6D.l.f.(3) d)

c) Fe-cent of Vent Stack Linit g

f) Actrap Roleaca Rato uCi/coc 2.48E+04 1.bD04 1.11E+04 2.06E+04 2.88U04 2.56E+04 2.17E+04 6.6D.1.r.(1) 2.

Chi. r.cy Icline 2c1 cases n) h t qc.. Relcated

~~131 curlos 3.27 E-01 2.13 E-01 1d5E-01 1.49 E-01 6.27E-01 8.8E-02 1.559D00 curies 9.81E-01 9.39E-01 4 65E-01 6.84E-01 1.24E+C0 1.5IE-Of 4.456E+00 I -1. '

curios 1.54E+00 1.09E+00 4.87E-01 3.04E-01 1.78E+00 1.73E-01 5.872E+00 I-133, b) Preant of Chier.cy Iltit 3.0 1.9 1.6,

1.6 6.9 0..

_6.6D. L. f. (3 )

e),1 :-,p Ro 2 2n n._cto

.u01_/::oc. 't. 2 2 E-01 7.9E-02 5.fE-02 5.8E-02 2.42E-01 3.3E-02 9.87E-02 h.-..

"Q;,,....s

. www

KEI'O.tr 07 EADIDACTIVE EFTLUENTS E

IM' I. S:

00ccT N05..__3 SJJuw-N.9 r;,;gs,---(. Cror. den ::eelectr Power Station - Unit 2/3 l

U;;1TS JULY AUC'JS T SI TH:2,ER COTO ER N07RREP.

D:CEMBE;t 6 :'.O. TOT.M.

TECH. SPEC. RFF.

'~

i I.

I --- y Tf P:?ntr.(c cntinued )

) Cren Pr.dicacti city ( #-Y )

curies 2.0E-01.

3.17E-01 1.30E-01

.' 37E-01 3.38E-01 2.53E-01 1.53EH)0 6.65.1. f. (1) 3.

-ir m-Pc-ticulate Ecice.co e

F) re:.: Alp' a R-diosetivity cut 'on _

6 R.1,f fil c) Ir.te es Ralc ued JJE-_03 J2E-01 curies i

6.r. - 5 '.

C ?- O curies 3.6E-03 2 2E-03 1 6E-02 7_lAr-n?

t.92C-02 f.42E-02 1,,1R..p2 i

f. '9 curio:

1.0fE-Of

1. 4));-01 AHL-07

3. Mr -n >

L.lJr.ni 5.69E-02 6.7, ale -01 i

fr-90 cur'es 8.0E-04 6.0E-04

_5 R -D4 5.DE-nh 3,cML J.0F-04 IJQf.-01 l,

cifiO3 I

"c. ' '1 7.64E-02 _ 1. %fr-01 curica 1.82E-02 237E-02 53 E -0.L. IJtL-D7 2E3 I-131 _ __ _ __

7.CE-04 Ig-q4 curica

, _ _ _ C -1 %

curios 6.0E-04 2.4E-01 7.ar-nt 5 Imr3 C -137 5 291E-01 ljlE_-01 7,qq(-02 Lo2r n1 520-02 _. 3 7:r-n3 curios P.-jl.0 7.18E-02 7

curies Tr. -17.C 3.18E-02 8.ISE-02 curies

y.;.3 9 T c-?N

_ curio s.

2.23E-02 1.21E-n?

- +

._..-..-...C.-d 3.7 2.7 gg,gg d) P:re.nt of Chirr.cy I.irlt 1.8 2.8 2.5 1.6 c) ;

re.',c Relec:a R:.to_.

uCi/ cec 2.5E-02 1.18E-01 9.2E-02 6.7C-02 1,3g.01 9,4g-02 9.6E-02 LELLD) l

'. nt 't-e !ciir.e Uclecca

r. ), ctcp:: 2clearci I-1 b curios 3,0 E_-_0 3 1.0E-02 0E-03 1 3E-C 2 3.2E-02 2.0E-02 9.7E-02 I-i".3

curiot, 1.0E-02 1.7E-02 1.5E-02 1.EE-02 1.80-02 1.0E-02 J,Cr-n >

~

~~

~

etries 6.6D.I. f. (3) 2.6 3.6 4.1 1.8 10.7 9.1 2.0E-03 1.3E-02 1.lE-02 6.33E-O's

. of y,.. +

e. 4.

,.y if, c.a

.__..t ss

-.s 4.0t-03 5.CE-33 I' -I v.c P de uCi/::'ic,,3.05-03 7._..

.,y

~~.- -

.. -. ~

j' j

i

]

HEPC37 O' HADTDACTIVE EFFt.I'ENTS CJMU Irosden Nuclear Pcwor Ste'en - Unit 2/3 00 CRIT ?:CS.:,30-237. 50-249 YEAR: 1974 i

J. C m: n I'"*1ue nte (Con *;tnved) t31~S JULY AUGUST S~.PTDIEER (X TG7.R NO W 13ER OECE.M3CR 6 MO. TOTAL TECit. SP C. RfF.

t

5. *.'ent Otte% T rtical-to Releaso (s) c;.,-- hdic3cti tity (3-7 )

_ cries 3.0E-02 2.*E-02 2.4E-02 1 2E-02 5.25-02 1.8E-01 129 E601 (b) Crc:a.u-h. hdic: tivity c:.* :s

..s (e) Iro*:o :s Reics: d 6 JM _ r_ (1 )

i 4

Cr

~,1 cfries 4.0E-03 5.2E-03 5 3E-03 1.45E-02 6.63.1.T(1)

Co33/ CQo crios hN 8f hh'8[

((.M/

~/.9E-03 I*IkEh d I-h$!

k-N 2

Or-?) /S r-90 curies ja8(8h/

):8h:8f 3[:8f

):8h*8f d:8f dh"8M

[-[g*8}/

'M9 curlos 6.lE-03 6.1E-03 I'o-?)

CT188 3 3E-03 2.4E-03 E4E-03 f.3E-01 3.2E-01 75E-01 2.11 r-M l

I-131 curion 5.6E-03 3 2E-03 5.5E-03 2.4E-03 1.E4E-02 3.5E 7.01E-02 I'

cs-13'6 curies 1.6E-03 4.0E-04 8.0E-03 3 0E-04 2.BE-03 6.EE-03 1.29E-02 Cs-137 curios r.2-140 cries __

3_.0E-03 9 0E-04 1.3E-03 6.0E-04 5 5E-03 1.15E-02 2.33E-02 l

1.0E-03 8.0E-04 1 3E-03 8.0E-04 3.4E-03 1.2EE-02 2.0tE '

La-140 cuics 3.0E-03 8.0E-04 1 5E-03 9.0E-04 4.0E-03 1.37E-02 2.19E-07

! -23)

P cries 2.3E-03 1.70-03 2.2E-03 8.0E-04 1.5E-03 3.CE-03 1.230 02 Te.'i:2 cu-ics 3.7E-03 2.7E-03

3.. 7E-03 1.St-03 3.5E-03 8.3E-03 2.34E-02 (d) hrent Vent Sttch L1::.it 5

9.3 6.0 4.1-7.6 19.6 29.8

'6.f_II,1,r.P)

O!'

-.I*).MJ87"CQolucQt.to tCi/cae 1.1E-02 7.0E-03 5.0E-03 9.0E-03 2.4E-02 3.7E-02 1.55E-02

'J f.

D:n c.T ?-dina end P.'.rticulato n) ' re?.t of Chh r.v. Lie.it 4.8 4.7

.1 3.2 10.6 3.6 b)

I'c. cent er Vent Stack Lirr.it g

11.9 9.6 0.2 9.4 30.3 323

_6.(a.1..(3) i 7.

Cecous Tritiu 2 a) r.elcu e curies 5.0 2.37 1.1E-01 9.33 27.10 59.53 1.03E+02 b) Averate Release R te tJCi/sec 1.87 8.9E-01 4.0E-02 3.60 10.12 22.23 6.45

~

c) T+rct t Tech Spec Linit 4

NA ilA

!!A NA FA

A NA 1

1 j

4 l

.. -. ~ - _

REPORT OF RADIOACTIVE EFFLUENTS i

frCILITY: Dresden Nuclear Powr Station - ITnits 2/3 DOCKET ?;OS.

JQ-237. 50-249 YEAR: (gg Liquid iffluents-UNITS JULY At:CUST S E '. TT.:'R 00TCV3 tr/OtSER DECEr:7.ra 6 MO. TOTA 1.

TECH. $PEC. REF.

1.

Gross Kndiesetivity (/IY) a) Total Reicase Curic3 5.514 5.517 4.351 0.616 0.093 0.090 16.191 b) Aversco Concentration Released uei/nl 3.62E-08' 3.3SE-08 3.33E-08 8.97E-09 4.43E-09 1.07E-08 2.98E-08 6.6D.1.o.(1) g c) Maxinun Concentration Released uci/n1 4.69E-03 5.33E-08 7.13-08 7.80E-08 5.52E-08 4.51E-08 7.80E.08 6.6D.1.e.(la) W d) Tercent of Tech Spec Linit 36.2 33.8 33.5 8.97 4.43 10.7 29.76 6.6D.1.e.(5) l2.

Tri tt un 6.6D.1.e.(6) a) Total Release Curies 1.60 1.890 2.054 8.78E-5 1.97E-04 1.36E-03 5.55 6.6D.1.e. (0) '

b) Averace Cor. centration Released ucl/r.1 1.0E-08 1.2E-08 1.5)E-08 1.28E-12 9.38E-12 1.61E-10 1.02E-08 c) Per ?,t of Tech Spec Limit 3.

Dissolved Ncble Cases JD ND flD ND ND ND ND a) Total Release Curies b) Avern3e Concentration Released uci/n1 c) Percent of Tech Sp=c Limit 1

h.

Grose Alpha Radioactivity a) Totc1 Release Curles IE-03 5E-04 3.5E-04 1.52E-05 4.3dE-05 4.71E-05 1.96E-03

',j

))

b) Avege Concentration Released uel/n1 6.54E-12 3.1E-12 2.7E-12 2.21E-13 2.09E-12 5.57E-12 3.60E-12 y volu e er Liquid Waste to Discharge Canal Liters 1.43E+06 1.18E+06 1.29E+06

__6.74E+04 1.51E+06 1.05E-06 6.53E406 6.6D.I.e.(2) 6.

Velu:e of Dilbtion Water r

Liters 1.53E+11 1.63E+11 1.30E+11 6.87E+10 2.10E+10 8.45E+09

-5.44E+11

-6.63.1.e.( 3.)

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1;C12: }D = !*0t TMtermined

,13 = liot Applicable (1) Cr.11/9/74 9 0640 during tFc f 411ure of Unit 3 air ejector diaphragm.

r.uir am of f y,ar. release was 64fs,000 uCi/SEC for a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> period.

e e

e-e -.

g, e me p e

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a e

end =*

e G e

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e

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=

w e

e 5 g e aMee - e ogmee m e eep m e e

ee+6m@e ae.

8ma me

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Me4yM we-e 6

m e9 e u.e e

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Text

Dear Mr. Keppler:

SUMMARY

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