Text

Radioactive Waste & Environ Monitoring, Annual Rept for 1978
	ML19296A528
Person / Time
Site:	Dresden
Issue date:	03/22/1979
From:	; COMMONWEALTH EDISON CO.
To:	;
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DRESDEN STATION RADI0 ACTIVE WASTE AND ENVIRONMENTAL MONITORING ANNUAL REPORT 1978 MARCll 1979 796NO3Ol67

TABLE OF CONTENTS PAGE Introduction..........................................................

1 Summary...............................................................

2 1.0 Effluents 1.1 Gaseous..................................................

3 1.2 Liquid...................................................

3 2.0 Solid Waste....................................................

3 3.0 Dose To Man 3.1 Gaseous Effluent Pathways................................

4 3.2 I,1 q u i d E f f l u e n t Pa t hwa y s.................................

5 4.0 Site Meteorology...............................................

5 5.0 En v i r o nme n t a l Mo n i t o r i n g.......................................

6 5.1 Gamma Radiation..........................................

6 5.2 Airborne I-131 and Par ticula te Radioac tivity.............

6 5.3 Aquatic Radioactivity....................................

7 5.4 M11k.....................................................

7 5.5 Special Co11ections......................................

7 6.0 Analytical Procedures..........................................

8 7.0 Milch Animal Census............................................

8 8.0 Environmental Dose Pathways Study (EDPS) Preliminary Report....

8 Appendix I - Fi gu r e s a nd Da t a Tab l e s.................................

10 Station Releases Caseous Effluents..............................................

11

1. i q u i d E f f l u e n t s...............................................

25 Solid Waste Shipments..........................................

34 Isodose and Concentration Contours.............................

37 Dose Calculation Parameters....................................

41 Dose Calculations.....

42 Environmental Monitoring Locations of Fixed Environmental Radiological Stations.........

43

~

Standard Radiological Monitoring Program.......................

44 S u mma r y Ta b l e s - Env i r o nm e n t a l.................................

46 Gamma Rad ia t ion Measuremen ts ( TLD).............................

50 Appendix II - Meteorological Data....................................

51 Appendix III - Erratc................................................

57

INTRODUCTION The Dresden Station is located approximately twelve miles southwest of Joliet, Illinois, at the confluence of the Des Plaines and Kankakee Rivers where they form the Illinois River. This station uses three boiling wa ter reac tors (GE design) to generate electricity. Unit 1 be-gan operating in 1960 and has a rated power output of 200 megawatts electrical (MWe). Units 2 and 3 began operating in 1970 and 1971, re-spectively, each with a rated power output of 800 MWe. The General Electric Morris Oneration Plant (GEMO) is located adjacent to Dresden.

Liquid effluents from Dresden are released to the Illinois River in con-trolled batches after radioassay of each batch.

Gaseous effluents are re-1"ased to the atmosphere after delay to permit decay of short half-life gaces.

Releases to the atmosphere are calculated on the basis of analyses of daily grab sampics of noble gases and continuously collected composite samples of iodine and particulate matter.

The results of effluent analyses summarized on a monthly basis and reported semiannually to the Nuclear are Regulatory Comission as required per Technical Specifications.

Airborne concentrations of nobic gases, I-131 and particulate radioactivity in off-site areas are calculated using effluent and meteorological data and data on isotopic composition of effluents.

Environmental monitoring is conducted by sampling at indicator and reference (background) stations in the vicinity of the Dresden plant to measure changes in radiation or radioactivity levels that may be attributable to plant operation.

If significant changes attributable to Dresden are measured, these changes are correlated with effluent releases.

External gamma radi-ation exposure from noble gases and I-131 in milk are the critical pathways at this site; however, a comprehensive environmental monitoring program is conducted which includes many other pathways of less importance.

1

SUMMARY

Gaseous and liquid ef fluents for the period remained below the Technical Specification limits. Calculations of environmental concentrations based on effluent, Illinois River flow, and meteorological data for the period indicate that consumption by the public of radioactive materials attribu-table to the plant are unlikely to exceed regulatory limits. Gamma radia-tion exposure from noble gases released to the atmosphere represented the critical pathway for the period with a maximum individual dose estimated to be 8 mrem for the year, when a shielding and occupancy factor of 1.4 is assumed. Environmental monitoring results confirm that dose via other pathways was not significant.

a 2

1.0 EFFLUENTS 1.1 GASEQUS EFFLUENTS TO TIIE AIMOSPHERE Measured concentrations and isotopic composition of noble gases, radioiodine, and particulate radioactivity released to the atmosphere during the year, are listed in Table 1.1-1. A total of 8.9 E+05 curies of noble gases was released with a maximum release rate of 5.9 E+04 uCi/sec from Dresden Unit

.1.

A total of 1.82 curies of I-131 was released during the year.

A total of 3.5 curies of beta-gamma emitters and non-detectable amounts of alpha emitters were released as airborne particulate matter.

1.2 LIOUIDS RELEASED TD ILLINOIS RIVER A total of 5.1 E+06 liters of radioactive liquid wastes containing 0.72 curies (excluding tritium) were discharged from the station. These wastes were released at a maximum monthly average concentration of 3.5 E-09 uCi/ml from Unit 1 and 7.5 E-09 uCi/ml from Units 2 and 3 which is 3.5 and 7.5%

respectively of the Technical Specification release limits for unidentified radioac tivity. During the same period, 32 curies of tritium and 1.55 E-02 curies of alpha radioactivity were released. Monthly release estimates and principal radionuclides in liquid ef fluents are given in Table 1.2-1.

2.0 SOCID RADI0 ACTIVE WASTE Solid radioactive wastes were shipped to Nuclear Engineering Company, Sheffield, Illinois and Barnwell Nuclear Center, South Carolina. The record of waste shipments is summarized in Table 2.0-1.

3

3.0 DOSE TO MAN 3.1 GASEOUS EFFLUENT PATHWAYS GAMbiA DOSE RATES Gamma air and whole body dose rates off-site were calculated based on measured release rates, isotopic composition of the noble gases, and meteor-ological data for the period (Table 3.1-1).

Isodose contours of whole body dose are shown in Figure 3.1-1 for the year.

Based on measured effluents and meteorological data, the maximum dose to an individual would be 8

mrem for the year, with an occupancy or shielding factor of 1.4 included. The maximum gamma air dose was 17.1 mrad.

BETA AIR AND SKIN RATES The range of beta particles in air is relatively small (on the order of a few meters of less):

consequently, plumes of gaseous effluents may be con-sidered " infinite" for purpose of calculating the dose from beta radiation incident on the skin. Ilowever, the actual dose to sensitive skin tissues is difficult to calculate because this depends on the beta particle energies, thickness of inert skin, and clothing covering sensitive tissues.

For pur-poses of this report the skin is taken to have a thickness of 0.7 mg/cm2 and an occupancy factor of 0.5 is used.

The skin dose from beta and gamma radiation for the year was 9.3 mrem.

The air concentrations of radioactive noble gases at the off-site re-ceptor locations are given in Figure 3.1-2.

The maximum off-site beta air dose for the year was 0.0 mrad.

RADIOACTIVE IODINE The human thyroid czhibits a significant capacity to concentrate in-gested or inhaled iodine, and the radioiodine, 1-131, released during routine operation of the plant, may be made available to man thus resulting in a dose to the thyroid.

The principal pathway of interest for this radionuclide is ingestion of radioiodine in milk by an infant.

Calculations made in previous years indicate that contributions to doses from inhalation of 1-131 and I-133, and I-133 in milk are negligibic.

10 DINE-131 CONCENTRATIONS IN AIR The calculated concentration contours for I-131 in air are shown in Figure 3.1-3.

Included in these calculations is an iodine cloud depletion factor which accounts for the phenomenon of elemental iodine deposition on the ground. The maximum off-site average concentration is estimated to bc 0.04 pCL/m for the year.

3 4

DOSE TO INFANTS *DIYROID The hypothetical thyroid dose to an infant living near the plant via ingestion of milk was calculated. The radionuclide considered was I-131 and the source of milk was taken to be the nearest dairy farm with the cows pastured f rom May to October. The maximum infant's thyroid dose was

0. 5 mrem during the year (Table 3.1-1).

CONCENTRATION OF PARTICULATES IN AIR Concentrations contours of radioactive airborne particulates are shown in Figure 3.1-4. The maximum off-site average level is estimated to be 0.02 pC1/m.

3

SUMMARY

OF DOSES Table 3.1-1 summarizes the doses resulting from releases of airborne radioactivity via the dif ferent exposure pathways.

3.2 LIQUID EFFLUENT PATHWAYS The three principal pathways through the aquatic environment for poten-tial doses to man from liquid waste are ingestion of potable water, eating aquatic foods, and exposure while walking on the shoreline. Not all of these pathways are applicable at a given time or station but a reasonable approxi-mation of the dose can be made by adjusting the dose formula for season of the year or type and degree of use of the aquatic environment. NRC* developed equations were used to calculate the doses to the whole body, lower GI tract, thyroid, bone and skin; specific parameters for use in the equations are given in Table 3.2-1. In general, the values of the parameters used were taken from HERMES **, a report which summarizes the living habits of persons in the North Central U.S.

These doses are summarized in Table 3.2-2. No organ dose exceeded 0.016 mrem for the year.

4.0 SITE METEOROLOGY A summary of the site meteorological measurements taken during each calendar quarter of the year is given in Appendix II. The data are presented as cumulative joint frequency distributions of 35' level wind direction and wind speed class by atmospheric stability class determined from the tempera-ture difference between the 300 and 35' levels. Data recovery for these measurements was 94%.

Nuclear Regulatory Commission, Regulatory Guide 1.109 (Rev 1).

-**J.

F. Fletcher and W. L. Dotson (compilers), " HERMES-A digital Computer Code for Estimating Regional Radiological Effects from the Nuclear Power Industry,"

USAEC Report HEDL-TME-71-168, Hanford Engineering Development Laboratory,1971.

5

5.0 ENVIRONMENTAL MONITURING Table 5.0-1 provides an outline of the radiological environmental monitoring program as required in current Technical Specifications. This program went into effect in November 1977 and dif fers f rom previous programs in the number and types of analyses performed. The routine program was supplemented during 1978 by an Environmental Dose Pathways Study which is designed to provide more sens' re measurements of actual concentrations ce of release. These measurements together in the environment and at the with extensive gamma dose measurements with TLD's and pressurized ion chambers intended to permit examination and refinement of the environmental dose are models. Tables 5.0-2 to 5.0-5 summarize data for the year.

In the Spring of the year increased levels of activity in a number of media were observed. The increases were the result mainly of nuclear explosions in the atmosphere by the People's Republic of China in late March.

Except for tables of special interest, tables listing all data are no longer included in the annual report. All data tables are availabic for inspec-tion at the Station.

Specific findings for various environmental media are discussed below.

5.1 GAMMA RADIATION External radiation dose from on-site sources and noble gases released to the atmosphere was measured at eight indicator and nine reference (back-ground) locations using solid lithium fluoride thermoluminescent dosimeters (TLD). A comparison of the TLD results for reference stations with on-site and off-site indicator stations in included in Table 5.1-1. Although a slight difference between the average on-site and off-site values was measured this le mainly due to a higher value from one station (On-Site 2, which is affected by N-16 turbine " shine") and not a generally elevated level throughout the

site, 5.2 AlttBORNE I-131 AND PARTICULATE RADIOACTIVITY Concentrations cf airborne 1-131 and particulate radioactivity at monitoring locations are summarized in Tables 5.0-2 through 5.0-5.

Locations of the samplers are the same as for direct radiation measurements, shown in Figure 5.0-1.

Airborne I-131 remained below the LLD of 0.10 pCi/m through-3 out the year.

3 were observed in late >brch Gross beta concentrations as high as 1.2 pCi/m af ter the Chinese nuclear explosion in the middle of that month. Similar

~

concentrations were observed in background stations (which, in this program, normally analyzed) during the same period. Gamma spectra of the fil-are not ters were typical of those containing "f resh" nuclear debris. The gross beta

~

6

concentrations tapered off as expected during the late Spring and by mid-Summer had reached the low levels expected at this season.

Fallout from a second Chinese nuclear test in mid-December was too diffuse to be distin-guishable in filters analyzed throughout the balance of 1978.

No radioactivity attributable to station operation was detected in any sample.

~

5.3 AQUATIC RADIOACTIVITY Cooling water samples were collected daily and composited for analysis weekly for the Unit 1 Inlet Canal and the Discharge Canal. Weekly grab sample:, were taken from the Illinois River at the EJ and E Railroad Bridge.

Analytical results did not indicate any measurable radioactivity attribu-table to plant operation.

No activity attributable to plant operations was detected in sediment or aquatic biota samples.

5.4 MILK Milk samples werc collected weekly during the grazing season and monthly during the balance of the year from the Davidson Farm located six miles northeast of Dresden, the Dorin Farm located about 10 miles south of the sta-tion and the Mather Farm (background station) located about 16 miles N.

E.

of Dresden.

1-131 was determined for each sample by gamma spectrometry or chemical separation of I~ and beta counting.

Elevated concentrations of I-131 in milk were measured in late March through April.

This activity is attrib-uted to debris from the Chinese nuclear test and agrees in temporal distrib-ution with similar observations throughout the midwest.

Iodine-131 in milk samples from Davidson and Fbther Farms was measured in the Environmental Dose Pathways Study. The findings of that program, to be reported in the Fall of 1979, do not affect the conclusions given in this report.

5.5 SPECIAL COLLECTIONS Service water contaminated by leaks in the LPCI heat exchanger was released into the cooling lake early in the year.

To monitor effects on the concentrations of radioactivity in the cooling canal a program was begun in October of collecting weekly grab samples of water at the Dresden Road and County Line Road crossings of the canal. Since the beginning of the program in October, concentrations of both gross beta and gamma activities have not indicated the presence of detectable concentrations of radioactivity due to

, the station with the possible exception of one sample from the County Line Road location on October 8th which contained 8 pCi/1 of Cs-137. Data are listed below.

7

RADIOACTIVITY IN WATER SAMPLES FROM DRESDEN COOLING LAKE Dresden Road County Line Road Crossing Crossing Collection Gross B y Emitters Gross 8 y Emitters Date pC1/1 pCi/1/nuclide pC1/1 pCi/1/nuclide 10/08/78 512

<10 922 Cs-137=812, others= <10 10/15/78 5!2

<10 612 610 10/22/78 5!2

<10 722

<10 10/29/78 2614

<10 2014

<10 11/05/78 1113

<10 813

<10 11/12/78 412

<10 512

<10 11/19/78 622

<10 63

<10 11/26/78 812

<10 9!2

<10 12/03/78 312

<10 3!3

<10 12/09/78 512

<10 4!2

<10 12/17/78 4!2

<10 52

<10 12/24/78 412

<10 32

<10 12/30/78

<5

<10

<5

<10 6.0 ANALYTICAL PROCEDURES summary of the procedures used for analyzing radioactivity in environ-1 mental samples is given in Appendix III of the report for the period January through June 1975.

Procedures used during the period covered by this report remain unchanged.

7.0 MILCll ANIMAL CENSUS WITHIN FIVE MILES OF STATION Name of Farm or Distance and Farmer Direction from Station Number and Type Larry Yunker Minooka 4.8 mi NNW 45 Cows Survey conducted by A. Lewis on 08,09,27 August 1978.

" Door to door" census.

8.0 LSVIRORIENTAL DOSE PATHWAYS STUDY (EDPS) - PRELIMINARY REPORT Since May 1978 EDPS projects have been performed at Dresden pursuant to Technical Specification 6.6.C.2.b. One of these studies compares measured cloud gamma exposure rates using pressurized-argon ion chambers (PIC's) to calculated rates using the models of Regulatory Guide 1.109 (Rev. 1).

Two models are used:

(1) computation of the hourly exposure rate using the finite 8

cloud model with summation to determine the total exposure for the month, and (2) determination of the total exposure for the month using the sector aver-age, joint frequency wind rose model.

The results for the August-October 1978 period, the only period when station noble gas releases were high enough to give measurable field data, show that the two modeling techniques give comparable results but that neither model accurately matches the measured PIC data.

The models underestimate the measured plume exposure by approximately a factor of 2.

This underestimation is believed due to the models assuming no contribution to exposure from plumes in adjacent sectors, when in actuality, because of the long relaxation length of gamma radiation in air, there appears to be significant contributions.

The Dresden EDPS report will be submitted in December 1979.

9

6 APPENDIX I DATA TABLES AND FIGURES 10

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's. Geirceus Tritium i)

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!<t iu(T OF IL'sDIOACTIVE FFFI UE! rS U M T NOS.
'" 1 A YEAR: 1970 L CILill: '.
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...i, 1 SEPT OCT NOV DEC 6 MO. TOTAL TECH. SPEC. ILE F.
1.
Greous Erfluents (contir ued) r:41TS JULY AUG ni!Ii.
1 3.
l' articulate Releases a) Gross Radioactivity (8/)
curies 40.18 c6.00 91.39 79 68 3.20
,,34 77i,79 n'l b) Gross Alpha Radioactivity
"' d c) Isotcpes Released cr-51 uci
.r-s ac; 0.13 0.03 0.01 0.12 0.11 0.02 0.42 co '8 nci 0.24 0.06 0.14 0.43 0.62 0.25 1.74 Co-0C nCi 1.50 0.18 0.58 1.99
1. 30 0.89 6.44 S '-8[
24.72 43.94 47.27 62.55 0.10 0.18 178.66 "Cl eo Sr-f 0 mci 0.61 OM 0.10 0.10 0.02 0.02 7r-95 nci 0.06 0.15 0.21
.; h-9 ',
mc1 0,04 0,09 0.18 0.11 0.42 Ft-' r. 3 mC f.
0.09 0.03
0. t,4 0.16
! lu mci 0.65 0.36 0.36 1.35 0.08 2.80 0.35 0.05 0.05 0.18 0.14 0.03
.80 n-1.v.
MCI Ch ni7 mC!
1.63 0.80 0.93 1.99 0.47 0.05 5.87 ha-143 mci 10.26 10.43 41.51 10.66 72.86 Ce-..I mci 0.02 0.21 0.13 0.06 0.42 C:-II4 mCt 0.05 0.05 1.24 0.05 0.021 0.71 d) Percent of chimne. IJmit 7
0.63 0.37 i _ r,7 3.5E-02 3.0E-02 i ?r-nt 5.0E-04 1.7E-02 e) Averar,e release rate uC1/sec SE-02 2.1E-02 b.
Sam of lodines & Particulates a) Percent of Chimney Linit 2.96 2.81 4.91 5 01 0.14 0.04 2.63 C.
Gar'eaus !ritium i) ml L:1c. r,
cu ries 3.0E00 1.6E01 1.8E01 5.0E-02 4.1E+00 3.2E+00 5.0E+01
,)
4a
.m ;telm o lett e di/O:e 3.4E00 5.8E00 7.1E00 1.9E-02 1.6E+00 1.2E+00 1.9E+01 9
Table 1.1-1 (Cont.)
Ut;. :'r OF iu ti;o s:rivt U t'll ia ' n b
CES Dresden Nuclear Power Station-Units 1/3 1.
Gaseous Effluents t' NITS JAN FIO
"^Y MARCH APRIL JUNE 6 PO. TOTA 1.
TECH. EC.
2.2.'-
1.
Gross Radioactivity Releases a) Tota el se curies 4.lE+03 3.6E + 03 l.8E+03 9.9E+02 9.4E+03 3.5E+03 2 ] +04 6.60.1.f. (I) 6.6E+03
3. lE + 03 2.4E+03 9.1[+02 1.5E+04 4.6E+03 1 5E+04 6.60.1.f. (2) b) Manimum Release Rate uti/sec 6.6D.I.f. (4) c) Isotopes Released Kr-85n curies 2.cE02 1.4E01 2 7E+02 2.5F+0!
U L+02 j
Kr-87 curies 4.3E01 6.4E+02 8.4E+01 M L+92
[
Kr-88 curies 4.3E01 3 2E+02 7.7E+01 4.4E+02 9.4E01 1.9E+02 3.5E+01 3 2E+02 y,_,33 l
Re-135 curies 1.lE03 6.4E02 1.8E03 9 9E+02 l.lE+03 3.3E+02 6.0E+03 g
Xe-135m curies 9.8E02 8.5E+01 l.lE+02 1.2E+03 xe-133 curies 2.8E03 1.8E03 6.8E+03 2.8E+03 l.4E+04 1
0.17 0.17 0.09 0.05 0.15 n.16 6.60.I.f. (3) 0.41 d) Percent of Chimney 1imit 1.5E+03 1.5E+03 6.6E+02 4.6t+02 3.5E+03 1 3E+03 1.5E+01 c) Average Release Rate uCi/sec i
f2.
Ehimney lodine Releases 6.60.1.f. (1) l a) Isotopes Released 6-131 curies 4.5E-02 6.3E-02 2.2E-02 9.lE-03 2.5E-02 4.8E-02 2.lE-01
/.7E-02 3.lE-01 3.9E-01 1.7E+00 1-133 curies 2.7E-01 6.3E-01 M E-02 l-135 curies 4.5E01 9.7E-01 1.5E-02 2.3E-Ol 3.8E-01 7.lE-01 4.7E+0!
l h) Percent of Chimney Limit 7.
O.39 0.63 0.22 0.10 0.30 0.43 1.3l 6.60.1.f. (3) c) Average Rele n d u uC i / s g;g 1.7E-02 2.6E-02 8.lE-03 3.5f-03 9.4E-03 1.8E-02 1.3E-02 1
Table 1.1-1 (Cont.)
J T o c' q.m W r. '; t.
6
_s 1978 50-237. 50-249 ya q*.
DroJ T No#s c
vi.-
Dresd-n Nuclear P* er Station-Units 2/3 1
Caseous rffluents UNITE JULY Aug SEPT OCT Nov DEC 6 P.O. TOTA.
TECH. S? C. C7 1.
Gross Radioactivity Relrases a) Total gelease curies 6.lE+03 1.3E+03 3.6E+03 2.5E+03 1.7E+03 1.4E+03 6.6D.I.f. (1)
, m 2/3 chimney b) Maximum Release Rate uCi/sec 3 9E+04 1.8E+03 5.6E+03 2.7E+03 2.0E+03 2.6E+03 3.9E+04
6. 6D.1. f. (2) 6.6D.I.f. (4) c) Isotopes Peleased Kr-85m curies 5.5E+01 3.9E+01 1.4E+02 1.2E+02 6.0E+01 1.5E+01 4.3E+02 Kr-87 curies 1.8E+02 2.7E+01 1.3E+02 7.3E+01 5.5E+01 8.8E+01 5.5E+02 Kr-83 curies 2.7E+02 6.CE+01 2.9E+02 2.0E+02 1.1E+02 9.3E+02 y..- l H curie.
3.1E+01 6.6E+01 1.6E+02 2.0E+02 1.1E+02 7.4E+02 1.3E+03 l
Xe-135 curies 5.5E+02 3.8E+02 1.0E+03 1.0E+03 4.3E+02 7.8E+01
3. 4 E+0 3 s
e. _.
Xe-135m curies 6.6E+02 1.2E+02 1.5E+02 5.9E+01 6.3E+01 1.1E+13 Xe-133 curies 4.4E+03 6.0E+02 1.9E+03 7.4E+02 8.8E+02 4.2E+02 8.9E+03 I.
6.6D.I.f. (3) 0.26 0.06 0.17 0.10 0.07 0.06 0.12 d) Percent of Chimney Limit 3E+03 4.8E+02 1.4E+03 9.4E+02 6.5E+02 5.2E+02 1.1E+03 e) Average Release Rate uC1/sec i
f 2.
Chimney lodine Releases 6.60.1.f. (1) l a) isotopes Released 1-131 curies 3.8E-02 5.2E-02 1.0E-01 1 3E-01 3.4E-02 3.8E-02 3.9E-01 i
.1-133 curies 4.0E-01 4.7E-01 3.6E-01 7.9E-01 3.1E-01 6.1E-02 2.4E+00 l-135 curies 7.1E-01 1.1E+00 4.0E-01 1.2E+00 5.3E-01 3.9E+00 6.60.1.f. (3) l h) Percent of Chimney Limit 0 34 0.47 1.00 1.11 0.31 0.35 0.57 c) Average Relea u Ro, uC1/se:
1.4E-02 1.9E-02 4.0E-02 4.8E-02 1.1r-ny 1.4E-02 2.5E-02 L
3 y c Ju L[O
.j\\o Table 1.1-1 (Cont.)
k> PORT OF RADIOACTIVE EFF1 UF NTS Fl.C IL LU : Dre93cn ?!uclear Power Station - Unit 2/3 LOCO.T NOS W-?)7. $0-?l.9 YEAR: y{
T.
Caseo.n Erriuents(continw 1) tJN IT S JAN FEB MAR APR MAY JUN 6 MO. TOTA 1.
TEcM. SPEC. ILE F.
3.
Chirney Particulate Release milli-a) Cross Radioactivity ( tl-Y )
curies 185.09 274.47 92.95 55.70 97.02 162.87 868.10 6.6D.1.r.(1) b) Cross Alrha Rajioactivity wCI c) Isotores Released f j p 1,r (1) mCl I.67 1.67 cr-51 mct 0.06 0.05 0.80 1.18 0.09 0.70 2.88 i.. - l. 3 ncs 0.24 0.24 g
u n.- f t:
mct 2.07 5.00 4.15 8.80 1.43 9.71 31.16 p<
75.,2 V.'
Wg W'
W fy 2g~
6-Q 2r-5 mci Sr-9 hb-95 mC1 g
,036g{
O I-l U nct
_R.75 63 41 3.66
_l.jj 2.12 6.45 92.32 C9-134 mci 0.55 0.55 e -117 mct 0.96 0.69 0.44 2.72 0.08 1.66 6.55 r.-11.0 mct 87.47 121.45 47.11 23.47 59.26 117.89 456.65 te-141 mc!
0.72 1.40 2.12 re-1/.I mct 1.02 1.02 Ru-103 mci 0.30 0.28 0.58 d) Percent of Chirnev Lirtit T
1.61 2._JO 0 3J_
__ 0.61 0.90 1.47 1.29 6 dD,1 f.(3) e) Anrage Reisase Rate _ __
uCi/sec 6._9 E-02 1.I E-01 3.5 E-02 2.1 E-02 3.6 E-02 6.3 E-02 5.6 E-02
1.. Vent itack Iodine Release ypgg1}
a) Irotopes ReleasM I-13 __.
curies 2.1 E-03 1.1 E-02 3.4 E-03 1.0E-03 3.4E-03
5. 3E -0 3 2.6E-02 1
I-133 curies 8.9E-03 4.0E-02 5.4E-03 4.2 E-03 3.0E-02 2.6E-02 1.1 E-01 1-135 curies 4.4E-03 5.5E-02 4.2E-02 1.0 E-01 b) Ibrm nt of Vent Stack Lirit.
.7 _
0.65 3.76 1.05
0. 12 1.05 1.70 1.39
/../o. l. r. 0 )
c) Averare Reinase Rate uC1/sec 7.8E-04 4.5E-0) 1.3E-0J_
Rfd '*
I tr-nt 2.0f-01 1.?r-03
Table 1.1-1 (Cont.)
l'Uh i OF l'.AUIOACTIVe E rr't ilt M rs D(C KET t.on -
5u_217 SMLv g; 1978 ggry. Erenten Lelear f owr Station - L' nit 2/3 UN II s JULY AUG SEPT OCT NOV OEC 6 MO. TOTAL TECit. SPEC. RFF.
T.
Cvems E fflu *nts(contin :~1) 3.
Chirney Particulate Release milli-6.6D.1.f.(1) a) Cross Radioactivity (/1-Y )
curies 175.94 202.31 204.22 371.29 66.65 32.49 nc, q,
b) Crcss Alpha Raficactivity
'Ci 6.6D.1.f.fli c) Isotoyes Released nCi Cr-51 mct 1.21 1.57 1.04 0.09 3 91 1-Co-Sa nci 0.45 0.33 0.78 C'" ' C "Ci 6.74 3.78 7.33 5.94 2.30 1.80 2 7. 89 67.35 84.00 53.73 137.56 29.79 20.27 392.70 "Ci Sr-90 mci
0. 61_ _.
0. 55__
0.16 0.48 0.09 0.06 2.01 I-13:
nci 4 38
_ 6.78 53.73
_59.48 8.33 3.76 136.46 mct o.19 0.30 0.03 0.13 0.65 1.01 1.66 2.53 0.54 0.20 7.05 Cs-134 C:.- 1 17 mC)
_ f.11 i
11u0 mei
_9 4. 29__.
_1_0J_. 69
. __8 3. 06 139.88 24.67 5.85 473.44 mc!
0.50 2.98 4.08 0.45 8.01 j
0-14!
Ce-14:
nCi d) Percent of Chimey Limit
_{_
l._54 1.86 1.98 3 22 0.60 0.31 1.54 6.f D 1.f.(3) 6.6E-02 7.6E-0?
7 9E-02 g,4t.01 2.6E-02 1.2E-02 6.6E-02 e) Average Release. Rate uCi/aec 1.fP.laf.(1)
L.
Ver.t Etack Todine Release a) Isotopes Released 1.8E-02 1.4E-02 1.lE-02 1.0E-02 7.8E-02 3.2E-02 1.3E-02 curies 3
I-131 _
I-133 curies 4.7E-02 6.4E-02
_Z g -03 7.7E-02 1 ?E-02 4.8E-03 2.6E-01 6.0E-Of I-135 curies 1.1E-01 1 5E-OL _
1.5E-01 1.9E-01 3.68 4.06 5.66 4.44 3-33 3.23 4.09 6.6D.1. f. (3) g b) _Tercent of Vent S. tack _ Lid.
c) Average Release Rate uC1/see 4.4E-03 4.9E-01 A Ar-qt 5.3E-03 4.1E-03 3.9E-03 4.9E-03 4
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j PF I'Ulti UF KAD!tMC r1VE FFF114 NTS F*CfLITY:
N., N...UCL;./d itJ J SIATIai - Gi!T 1 DOCKET tioS.
50-10 M:
J"N FEB MAREH APRit MAY JUNE 6 Mo. TOTAL TECH. SPEC. REF.
II.
Liquid Effluents UNITS 1.
Gross Radioactivity (8/)
2.3E-02 2.5E-02 6.6E-02 8.3 E -02 3 3E-02 1.2E-02 2.4E-01 a) Total Release Curies b) Average Concentration Raleased uci/ml 1.0E-09 1.3E-09 3.0E-09 J.yE-09 1.2E-09 4.5E-10 1.7E-09 6.6D.I.e.(1) c) Maximum Concentration Released uci/ml 2.9E-08 2.lE-08 4.5E-08 2.4E-08 2.6E-08 4.5E-08 6.6D. I.e.( h )
d) Fercent of Tech Spec Limit 1.0 1.3 3.0 17.0 1.2 0.45 1.7 6.6D.I.e.(5) based on average conc. releaser 6.6D.I.e.(6) 2.
Trittun a) Total Release Curie s 2.8E-03 1.2E-03 I.7 E-0 3 8.6E-03 3.8E-04 5.7E-03 2.0E-02 6.6D. I.e. ( 8 )
Nu b) Average Concentration Releasad uel/n1 1.3E-10 6.0E-Il 7.7E-Il 7.0E-Il 1.4E-Il 2.2E-10 1.5E-10 c)
Per-a,' or Taah Sr+c Limit g
NA NA NA NA NA NA NA e
3.
Dis olved Foble Cases a) Total Release Curies NONE NME
_ NOME
_NONF NONE NONF WPNF b) Average Concentration Released uci/ml c) Percent of Tech Spec Limit
"~
"~
"~
~"
~"
"~
"~
h.
Cross Alpha Radioactivity 2.5E-05 I.5E-05 7.0E-05 I.3E-02 3.8E-05 1.8E-05 1 3E-02 a) Total Release Curies b) Average Concentration Released uci/ml 1.lE-I2 7.8E-13 3.2E-12 5.4E-10 1.4E-12 7.0E-13 9.3E-Il 5.
Volume or Liquid Waste to Discharge Canal Liters 1.3E+05 1.4E+05 3.9E+05 3.3E*05 1.5E+05 1.0E+05
1. 2E e6 6.6D. I.e. ( ? )
j 6.
Volume of Dilution Water l ite rs 2.2E+10 2.0E+10 2.2E+10 2.4E+10 2.7E+10 2.6E+10 1.4E+11 6.6D. l. e. ( 3 )
-e ee_----e
Table 1.2-1 (Cont.)
b 6. U3T OF KAD 10 ACTIVE F FFL U E N TS 1
D(CKET P:0s.
11' E: 1978
.,; A ;I.
ctiL!ro
?.
. vi.
SEPT OCT NOV OEC 6 MO. TOTAL TECH. SPEC. REF.
!I.
Liquid r.ffluents UNITS JULY AUG 1.
Gross Radioactivity ((()
a) Total Release Curies 1.2E-02 9.9E-03 1.6E-02 1 9E-02 1.4E-02 1.5E-02 8.6E-02 b) Average Concentration heleased uci/ml 4.4E-10 3.7E-10 6. l f - t r>
M E-10 A ?r-in 7 DE-10 5.7E-10 6.6D.1.c. ( 1 )
c) Eaxinua Concen tra'. ion heleased uci/ml 2.lE-C8 2.0E-08 2.5E-08 2.6E-08 2.8E-08 2.4E-c8 2.8E-08 6.6D.I.e.(5) 0.69
_0_d 2 0.70 0.57 d) t a rce-t rf Tech Spec Linit 4
0.44 0 37 na 6.6D.I.e.(6) rele.sej bawJ on average conc.
2.
T ri ti um a) Tc,tal Release Cu rie s 6.8E-04 8.0E-01 1.2E01 4.4E-04 1.4E-02 1.6E-02 1.3E+01 6.6D. l.c. ( 8 )
y b) Avarare Coj. centra *1cn Pala'sai ud /n' 2.5E-Il
_3.0E-08 4.6E-07 L 6E-11 6.lE-10 7.3E-10 4 5-Q]._
r Ta4 R ec Linit I
NONE.__ _
N0$L_
.._NONE _,___
_RONL_.___
NONF NONr kour c)
Par-ant n 3.
Dis olved liebla Gases a,
Total Release Cu ria's NONE NONE NCNE NONE NONE NONE NONE b) Average Cor. centration Celeased uci/ml c) Percent of Tech Spec Limit 4
L.
Gross Alpha Radioactivity a) Total Release Curie s 2. 4 L-O i___
1 5E-05 __
8.8E-06 2.4E-05 3.2E-05 1.1E-04 73 06 f.IE-12 1.5E-12 7.3E-13 b) Average Concentration Heleased uci/ml 8.9E-13 2.7E-13 5.7E-I3 3 3g.g3 5.
volune of Liquid waste to 9 9E +0'-
7.5E+04 8.6E+04 5.2E+05 6.60.1.e. ( 2 )
Discharge Canal Liters 8.9E+04 9.2E+04 2.2E+10 1.5E+11 6.6D. I.e. ( 3)
,6.
Volume of Dilution Water Liters 2.7E+10 2.7E+10 2.6E+10 2.7E+l0 2 1E+10
i 1h i
F tI C
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Table 1.2-1 (Cont.)
HEPURT OF RADIDACTIVE LFFLLFNIS t
L.C 'L i rl:
ih ecde i :.uclear Pcuer Otstion, L' nit 1 DocrEr r;OS.
[O - 10 YEAR: 1978 II.
Lipid Effluents (continued)
UNITS JULY AUG SEPT OCT NOV DEC 6 M0. TOTAL TECH. SI EC. ELEF.
7.
Isotopes Released
,giu curies 11.83 9.87 16.03 18.52 14.17 15.08 65.50 Mn-54 mC1 0.35 0.88 1.35 0.64 0.55 3.77 Co-58 mci 1.35 0.24 0.41 0.39 0.30 2.12 4.81 Fe-59 mci co-60 0.39 0.25 0.64 mci 6.02 7.10 8.70 10.27 11.12 8.57-51.78 Zn-65 mci Sr-39 mC1 0.08 0.10 0.11 0 38 0.31 0.27 1.25 i
to mci 0.04 0.02 0.03 0.02 0.07 0.06 0.24 Sr-90 co Zr ;5 mci 0.39 0.03 0.14 0.56
">- 9 5 r Ci 0.51 0.01 0.21 0.22 0.95 Mu-103 nci
_ 0.31 0.12 0.27
0. 70 1-131
,C1 0.23 0.10 0.53 0.10 0.96 Cs-134 mc!
0.39 0.27 0.39 0.29 0.42 0.33 2.09 Cs-137 mci 1.29 0.69 1.16 0.87 1.15 1.01 6.17 Ba-140 mci 0.21 0.31 0.07 0.02 0.61 La-140 mci 0.24 0 36 0.09 0.02 0.71 Ce-141 mci 0.18 0.38 0.11 0.67 Ce-144 mci 0.92 0.75 1.67 MCI 0.28 4.26 2.40 0.56 7.50 Cr-51 M-NN Nee em.
e e
Table 1.2-1 (Cont.)
n ro:tr or outvec tive: t rarrvr.
'98 F ' C ll_ITY :
l'...ll i ;;UCl. a IV. fits SI'ATICil tt;} c 7/1 U( C D.T N0'...
70 ?]7. 50-M '
YF Alt:
IIB MAPCH april MAY Jues E 6 MO. TOTAL TECM. SPEC. REF.
I:. Liquid Effluents UNITS JAN I,
Cross Radioactivity (f/)
I.3E-Of 1.2E-01 0
9.4E-02 4.40-02 0
3 9E-01 a) Total Release Curies 1.5E-09 6.7E-09 0
7.5E-09
2. 2 y_og 0
2.9E-09 b) Average Concentration Relear.ed uct/mi c) Maximuri Concentratim Released uct/nl 2.5E-08 2.7E-08 0
5.ht-08 6.0E-08 0
6.ot-08 d) Perceat of Tech Spec 1.inir
__A___
'] _
6.7 0
7.5 2.2 0
29 based im average conc. r e t c.ised 2.
Tritiem a) Total Release Curies 3.lE+00 4.9E+00 0
6.9E+00 4.lE+00 0
1.9E+01 0
5 3E-07 2.0E-07 0
1.4E-07 b) Average Concentration Released u c i/.ll 3.6E-08 2.7E-07 c) Percent of Tech Srec Limit j
NA NA NA NA NA NA NA J.
Ulsr.olved Noble Cases Non:
a) Total Halease Curies None None None None b) Averar,e Concentration Raleased u ci/M
~"
c) Percent of Tech Spec Limit J
h.
Grose_ Alpha Radioactivity _
0 2.lt-03 1.lE-04 0
2.4E-03 a) Total Releasa Curies 1.3E-04 8.5D05 b) Averaec Concentration Released u ci/n1 1.6E-12 4.7E-12 0
1.7E-10 5.4E-12 0
1.7E-Il W
250E 7.7E 5.
Volu
.iquid Waste to,_
Liter::
. _ _0
.4E+06 7E 05 Ultcharge Canal 6 Vol e of Dilutloi Water Liter; 8.5E+10 1.8E+10 0
l.1[+l0-~~ "
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1
Table 1.2-1 (Cont.)
kr ro*tT O? RADIGACTIVE D a t'rNrs I
f4::ll.In:
".,wsden,bcle ir Pcrier Otaticm - Unit. 2/3 Docxtr t.cs.
r_'p.
&_ve yp R : g II.
Liquid Effluents (continued)
WITS JULY AUGUST SEPTET 3ER OCTOBER A0VEMBER CECEM5ER 6 MO. TOTAL TECH. SPEC. flr.
6.
Gross Radioactivity (6 7)
LPCI Service H O Heat Exchanger Milli-al Tntal Pateate
.luries 2.50 1.71 1.06 2.13 0.79 0.26 9.35 2
b5 Averace t w ertra*fnn Defease ec i r-1 1.5E-11 1.0E-11 1.2E-11 1.3f-11 5.3E-12 3.8E-12 1.1E-11 c) wu i mm cene--trarlon Release $
ucih1 2.5E-07 1.0E-07 1.0E-07 7.9E-08 7.7E-08 1.4E-07 2.5E-07 d) Percent of Tech Spec Limit t
C.02 0.01 0.01 0.01
<0.01
<0.01 0.01 based on avarj u qsc released 9.
Tritium
.1 Teral Pale ne c _. r t,,
5.EE-02 6.4E-02 1.5E-02 3.4E-02 5.2E-03 2.0E-3
'1.8E-01 tJ b) Averaae Concentration Released uct/ml 3.kE-10 3.8E-10 9.LE-11 2.1E-10 3.5E-11 2.9E-11 2.0E-10 w
c) Percent of Tech Spec Limit t
NA NA NA NA NA NA NA 10.
Dissolved Noble Cases a) Total Release Curies NONE NONE NONE NONE NONE NONE NONE b) _Ayera3e Concentration Released ucl/ml
~
~
c) Percent _of Tech _SE c Limit 2
11.
Gross Aloha Radiqactivity a) Total Release Curles 2.5E-07 1.BE-06 0
1.0E-06 0
3.1E-06 0
b) Averaqe Concentration Released _ucl/ml 1.5E-15 1.1E-14 6.7E-15 3.5E-15 12 Vale-e nf tto,Id_ Mute en tfrers 2.2E+04 2.0E+05 1.1E+05 2.CE+0E 6 fr+nfi 1.tr+nh A 3r.nr Discharce C mal 13.
Volume of Dilution Water Liters 1.7E+11 1.7E+11 1.6E+11 1.6E+11 1.CE+11 6.8E+10 R Pr+11
,I
Prior to dilution by 1275 acre cooling lake and subsequent discharge to Illinois River.
e
F E.
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34
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n n
i
. W c
r u a ao et n
i
= u a cW a
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R
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Table 2.0-1 (Cont.)
DRESDEN NUCLEAR POWER STATION SOLID WASTE DISPOSITION YEAR 1978_
MONTil__
NUMBER OF SilIPMENTS MODE OF TRANSPORTATION DESTINATION JANUARY 13 Motor Freight Sheffield Nuclear (Exclusive use only)
Center 1
Motor Freight Barnwell So.
(Exclusive use only)
Carolina FEBRUARY 23 Motor Freight Sheffield Nuclear (Exclusive use only)
Center MARCII 32 Motor Freight Sheffield Nuclear (Exclusive use only)
Center 4
Motor Freight Barnwell So.
(Exclusive use only)
Carolina APRIL 5
Exclusive use vehicle Sheffield Nuclear Center 7
Exclusive use vehicle Barnwell So.
Carolina MAY 21 Exclusive use vehicle Barnwell So.
Carolina JUNE 22 Exclusive use vehicle Barnwell So.
Carolina JULY 25 Motor Transport Barnwell, S.C.
Exclusive use vehicle AUGUST 34 Exclusive use vehicle Barawell, S.C.
SEPTEMBER 20 Exclusive use vehicle Barrc sell, 1. C.
OCTOBER 25 Exclusive use vehicle Barnvell, S.C.
NOVEMBER 34 Exclusive use vehicle Barnwell, S.C.
DECEMBER 21 Exclusive use vehicle Barnwell, S.C.
36
FIGURE 3.1-1 l
/O O h
a w <
w.
Estimated Cumulative Gamma Dose e
4[%
, hp
(,
284
/
T y
(mrem) f rom DNPS for the period January - December 1978 n
isopleth labels
)E_
g-r Small figure - multiply by 100 Lurge figure - multiply by 10-I SCALE O
2 m.t t s m
o e
2 3 su
==
/.O
y a.n.
,. /NI l
Ploinfield i
5
\\
1
f. 3,+*
6 4
1 k
E N
O A
L L
"21
/j yI ht4 M t 5'
e i e
v
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, *. t 7
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\\*
/
w
/
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/
w a
ts t
J
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I-
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ti-N i..o
(
/
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~
N
~
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[
,AL '
.f.
g,
~
\\
i c- -
g,
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nf 10 J
m,
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w,3.,
,,n p?
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'4 G
R U
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q N
aorm,
,o Santh W.8m.nge M
A N
K I
,;.trur SCALE 37
+9
,o
.,u,
bY.S.jg'\\n D
' 9 h in
'o
's
=
n p." D O D
LJ
J.
j FIGURE 3.1-2
.a
~
w s.co in 3
Estimated Total Concentration (pC!/m )-
of Noble Gases from DNPS for the K
/
I period January - December 1978 p-y g
"***(
Isopleth Labels Small figure - multiply by 10+b Large figure - multiply by 10+3 5
s SCALE o
,e 3 witts o
e 3
s au N Y h v.lle e
h S*
0!!
'af **id' 4
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K E
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l
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'st SCALE 38 o
s q
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FIGURE 3.1-3
$~
~
Estimated Total Concentration (pCi/m )
rg i
~
3 pI of Iodine from DtiPS for the period tgf,,
7 i
January - December 1978 0.
p,p g*j/g Isopleth Labels w
small figure - multiply by 10-2
(
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f
)
l.... Ax
-m Estimated Total Concentration (pCi/m ). gf Q%I -
3 Particulate Matter from DNPS for the period January - December 1978
,4,*p, I
w Ma lO gV
-r.
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TABLE 3.2-1 VALUES OF PARAMETERS USED TO MAKE DOSE ESTIMATES RESU1. TING FROM DRESDEN LIQUID WASTE DISCHARGES Pathway Parameter Unit Value or Source Potable Water M /F CFS-1 1/1.08 E+4 (a) p U
liters / month Max Adult 61, Av. Adult 31 p
Q1 Ci/mo Station Report ipr mrem /pCi Regulatory Guide 1.109 D
A br-I Table of Isotopes or other t
sources t
hr 35 (b) p Aquatic Food M /F CFS-3 1/1.08 E+4 (a) p U
kg/ month Max Adult 1.0, Av. Adult 0.1 p
Qi,Dipr Ai Same as Potable Water (QV.)
ip liter /kg Regulatory Guide 1.109 li t
hr 72 (c) p Shoreline Qi,Ai See Potable Water Activities M /F CFS-1 1/1.08 E+4 (a) p W
Unitiess 0.2 Table A2, Reg. Guide 1.109 Ti d
0. 029/A
( A-h r-1 )
t hr 1.35 E+5 (Midpoint of Plant operatine lifetime) t hr/ month Jan-Mar =0 Aug 2.6 hr/mo p
Apr
=1.5 hr/mo Sep 2.0 hr/mo May-Jun=2.6 hr/mo Oct 0.76 hr/mo July
=2.7 hr/mo Nov 0.16 hr/mo Dec 0.08 hr/mo (Ref. HERMES)
(a)
For potable water pathway it is assumed that total mixing in the river has occurred by the tire the radioactivity reaches Marseilles, 35 mi.
downstteam.
35 miles 1 mph.
(b)
A river flow of 1 mph is assumed; hence t =
(c) llERMES, pg. 118.
41
TABLE 3.1-1 DOSES RESULTING FROM AIRBORNE RELEASES DNPS 12/78 TYPE UNITS DOSE (DIRECTION) BY OUARTER GAMMA AIR (MRAD) 5.45 (ESE) 4.67 (NNW) 8.69 ( N )
2.38 (NN)
BETA AIR (MRAD) 0.00 ( E )
0.00 ( N )
0.00 ( N )
0.00 ( N)
W110LE BODY (MREM) 2.34 ( E )
1.33 ( SE) 3.23 ( NE) 1.27 ( E)
SKIN DOSE (MREM) 2.72 ( E )
1. 54 ( S E) 3.75 ( NE) 1.47 ( E)
INFANT DIYROID (MREM) 0.00 (
)
0.06 (NNE) 0.34 (NNE) 0.07 (NN)
POP W110LE BODY (PREM) 17.32 24.02 59.65 23.78 YEAR 10 DATE TYPE MAX DOSE MAX ALLOWABLE PERC ENT GAMMA AIR (MRAD) 17.10 30 56.993 BETA AIR (MRAD) 0.00 60 0.003 W110LE BODY (MREM) 8.01 15 53.400 SKIN DOSE (MR EM) 9.29 45 20.644 INFANT lilYROID (MREM) 0.47 45 1.053 TABLE 3.1-2 DOSES RESULTING FROM EXPOSURE 10 RADI0 ACTIVITY DISCHARGED IN LIQUID WASTE 1978 DOSE TO PADIWAY (MREM)
POTABLE AQUATIC 11IORELINE EXPOSED WATER FOODS gTIVITIES PERSON TUTAL BONE 111YROID TOTAL BONE THYROID TUTAL SKIN PER IOD BODY BODY BODY
" AVERAGE" ADULT
' ST Q'IR 0.000 0.002 0.000 0.000 0.000 0.000 0.000 0.000 2ND QTR 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 3RD QTR 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 4Di QTR 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000
" MAXIMUM" ADULT IST QTR 0.000 0.004 0.000 0.003 0.004 0.000 0.000 0.000 2ND Q1R 0.000 0.001 0.000 0.004 0.004 0.000 0.000 0.000 3RD Q1R 0.000 0.000 0.000 0.002 0.002 0.000 0.000 0.000 4Di Q1R 0.000 0.000 0.000 0.001 0.001 0.000 0.000 0.000 TOTAL ORGAN DOSE SINCE JANUARY FOR " AVERAGE" ADULT ORGAN TOTAL DOSE 10CFR50 APP I PERCENT OF APP I IOTAL BODY 0.19 E-02 9 MRD1 0.021 SKIN 0.35E-03 30 MREM 0.001 BONE 0.36E-02 30 MREM 0.012 111YROID
0. 40 E-03 30 MREM 0.001 42
LOLAiIONS OF FIXED ENVIRONMENTAL RADIOLOGICAL MONI 0 RING STATIONS I -Onsite Station i
l 2-Onsite Station 2
's
)
{p 3-Onsite Station 3 4-Collins Road
=N 5 -Bennitt Form
/ E i8 6 -Pheasant Trall is i2 '
f
,..o 7-Clay Products i3 f*
1 8-Prairie Park O
9-Coal City y
v 10-Goose Lake Village 116%,,,,, g, j.7 o
ll - Morris i~o' e l0
~
/
17 cooi 12-Lisbon u iis ci'r
/
43 9
13-Minooka 14-Channahon 15-Joliet g
6-Elwood
.c 17-Wilmington o
s io is to asitts 80 i ?_. _
to rs 30 ris c
j
TABLE 5.0-1 ORESDEN STANDARD RADIOLOGICAL K NITORING PROGRAM Non-Routine Sample Media Collection Site Type of Analysis Frequency Reporting Levels 0:
3 1.
Air Monitoring (a) Onsite and near field
1. Filter - gross beta 1.
Weekly Cs-13410, Cs-137 20 pCi/m o
3 (1) Onsite Station #1
2. Charcoal - I-131 2.
Si-Weekly
0.7 pCi/m (2) Onsite Station #2 (3) Onsite Station #3
3. Sampling Train -
3.
Weekly (4) Collins Road Test and Maintenance (5) Bennitt Farm (6) Pheasant Trail (b) Far Field (1) Clay Products
1. Filter Exchange 1.
Weekly same as 1(a)
(2) Prairie Park (3) Coal City
2. Charcoal Exchange 2.
Bi-Weekly
when analyses (4) Goose Lake Village (5) Morris
3. Sampling Train -
3.
Weekly are made (6) Lisbon Test and Knintenance (7) Minooka (8) Channahon (9) Joliet (10) Elwood (11) Wilmington 2.
TLD Same as 1 Ganns Radiation Quarterly Mn-54 3x10f, Fe-59 lx10f 3.
Fish Dresden Pool of Ganma Isotopic Semi-annual Co-58 3x10, Co-60 lx10 Illinois River 4
3 Zn-65 2x10 CS-134 lx10 3
Cs-137 2x10 p Ci/Kg wet weight 106 Amendment No. 22
TABLE 5.0-1 cont'd DRESDEN STANDARD RADIOLOGICAL MONITORING PROGRAM (CONT'0)
Non-Routine Samle Media Collection Site Type of Analysis Frecuency Reportino Levels A:
4.
Milk 2 dairy Farms I-131 1.
Weekly -
I-131 3 pCi/1 Grazing Season -
Cs-134 70 pCi/1 May to Oct.
Cs-137 60 pCi/l 2.
Monthly -
Nov to Apr Ba-La-140 300 p Ci/1 5.
Surface Water Illinois River at EJ&E RR Gama Isotopic Monthly Footnote **
Bridge Analysis of weekly compcsites 6.
Cooling Water Sample (a)
Inlet Gross Beta Weekly (1) Unit 1 (b) Discharge (1) Unit 1 (2) Unit 2/3 7.
Sediment (a) Dresden Lock and Dam Gama Isotopic Annual Note:
Bi-weekly shall mean that the frequency is once every other week.
a Average concentration over calendar quarter 4
3 2
2 2
2 2
H-3 2 x 10, Mn-54 1 x 10, Fe-59 1 x }0 Co-58 6 x 10, Co-60 2 x 10, 2n-65 2 x 10, Zr-Nb-95 4 x 10, I-131 3 Cs-134 30, Cs-137 60, Ba-La-140 1 x 10 pCi/1.
O A garrea isotopic analysis shall be performed whenever the gross beta concentration in a sample exceeds by five times (5x) the average concentration of the preceding calendar quarter for the sample location.
Amendment No. 22
TABLE 5.0-2 EN'.'IRONMENTAL RA0!CLOGICAL MON!!CR!NG PRCOMM QUARTER SLWRY Name of Tacility D*ehden %.elear her Station Dociet No. 50-10, 50-237,53-549 Location of Fatility C r ut.d y. !!!inois Reporting Period 1st Ouarter 1979 (County State)
Typa and immer Limit i
N aber of Medium or Patbay Total Nu-ber of All !r.dicator Locations Location with Miehest Quarter Mean Control Locations l Nenroutine Sa. pled of Analyses Detection Mean (f)b Name Mean (f)D Nean (f)b Reported i
(L'ni t of Mcamurement)
Performed (fLD)
Range Distance & Direction Range Rance Feasurcre9ts Air P.irticul. item Crna F 77 0.01 0.22 (77/77)
On site 2 0.24 (13/13) wt Me n ured 0
0 (pci / m ')
0.02 - 1.20 0.3 al, 50 0,10 - 1,30 AirN$rne todtnc 1-131 36 0.10 All I.I.D Not Applicable WL Me.uured 0
p (pC1/m ')
C.imma nac k g,r ound y Dose 17 j
19.2 (8/8)
On Site 2 2 '. 7 (1/l) 16.7 (9/9) 0 (mR/ Quarter) 16.6 - 24.7 0.3 mi. 50*
24.7 15.6 - 18.2 Milk 1-131 15 5
All 1.LD Not Applicable All 1.1.D 0
(pC1/1)
Cooling Water Cross P 36 5
6 (18/24)
Unit 1 Discharge 6 (A/12) 7 (7/12) 0 (pC1/1) 3 - 12 3 - 12 3 - 13 Surface Water y Spec.
3 10 All I.I.D Not Applicabic Not measured D
(pC1/1) b Mean and range based upon detectable measurements only. Traction of detectable measurements at specified locations is indicated in parentheses. (f)
TABLE 5.0-3 ENVIRChM7AL RA*IOLOGICAL MONITORINC PROGRAM Qt'IRTER S'.;??%RY Narse of Facility Dresden Noelcar Power Statien Docket No. 50-10, 50-217
$0-5/.9 Location of Facility Crundy. Illinois Report
1g Period 2nd Quarter 1978 (County, State)
Type and Lower Limit Number of Y.edium er Pathway Total Nu.ber of All Indicator cations Location with Hithest Qtirter Mean Control Locations Necroutine Sampled of Ar.alyses Detection Mean (f)
Name Mean (f)D Maan (f)b Reported (l'ntt of Me.1gurement)
Perforned (LLD)
Raere Distance & Direction Range Range Measurements Air P.irtteinlaces Crou F 78 0.01 0.21 (77/78)
On Site 2 0.23 (11/11)
Not Mc.nu rnt 0
(,<1/m ')
0.07 - 0.49 0.3 mi. 50" 0.12 - 0.49 Airborne Iodine I-131 42 0.10 All LLD A t Applicable Not Mcuured 0
(PC1/m')
Canna narkground y Nac 17 J
21.0 (8/8)
On Site 2 29.9 (1/1) 15.6 (9/9) 0 p
N (mR/Qtr.)
16.9 - 29.9 0.3 mt. 50" 29.9 14.3 - 16.9 Milk I-131 39 0.5 6.3 (6/'O)
Dorin Farm 8.9 (4/5)
All (0.5 0
0 (pC1/1) 0.5 - 21.0 7 mi. 220 0.5 - 21.0 Coo 11pg Water Cross 2 39 5
9 (22/26) 1: nit 1 Discharge 9
(12/13) 10 (11/13) 0 (pci/1) 3 - 24 3 - 24 5 - 21 Sarface Water y Spec.
3 10 All LLD Not Applicable Not Measured 0
Mean and range based upon detectable measurements only. Fraction of detectable measures.ents at specified locations is indicated in parentheses. (f) b
TABLE 5.0-4 LWIRCNMEN*AL RAD!CLOGICAL MCN!TORINC ?ROCRAM CUARTER SLWARY Name of Facility Oresden Nuclear Power Station Docket No. 50-10,53-717 53 519 Location of Facility Crundy, Illinois
, Reporting Period 3rd Asarter 1974 (County, State)
N mber of Type and Lower Limit Medium or Pathway Total Number of All Indicator Locations Location with Highest Quarter Fean Control Locations Nonroutine Sampled of Analyses Detection Mean (f)b Name Me an (f )3 Mesa (f)b Reported (Unit of Measure-ent)
Perfor-ed (LLD)
Range Oistance & Direction Rance Ran ge Measure-er.ts l
Air Particulates Cross 8 77 0.01 0.10 (77/77)
On Site 2 0.12 (13/13)
Not Measured 0
0.03 - 0.19 0.3 mi, 50 0.D6 - 0.17 I
(pC1/m')
Airborne lodine 1-131 36 0.10 All LLD Not Applicable Not Measured 0
2 (pC1/m )
Camma Background y Dose 17 Jr 18.8 (8/8) on Site 2 37.7 (1/1) 11.5 (9/9) 0 co 12.6 - 37.7 0.3 mi 50 37.7 10.5 - 13.0 (zR/Qtr.)
Milk 1-131 39 0.5 All LLD Not Applicable All LLD 0
(pC;/1)
Cooling Water Cross 8 42 5
8 (17/28)
Unit 1 Discharge 8 (9/14) 9 (8/14) 0 4 - 16 4 - 21 4 - 16 (pC1/1)
Surface Water y Spec.
3 10 All LLD Not Applicable Not Measured 0
(pC1/1) f I
(f) kraction of detectable measure =ents at specified locations is indicated in parentheses.
bMean and range based upon detectable measurements only.
TABLE 5.0-5 ENVIRONMENTA1. RA0101.0CICAL MONITORINO PROGRAM CCARTER SD?.ARY
%2ne of Tacility Dresden Eclear Power Stath Docket No. 50-10, 50-237, 50-549 location cf Facility Crundy. Illinois Reporting Period 4th Ouarter 1978 (County, State)
Lt.ber of Type and Lower Limit Medius or Pathway Total Number of All Indicator locations location with Highest Ouarter Mean Control 1.ocations Nonroutine Sampled
, of Analyses Detection Mean (f)b y,3, y,,3 (K y,33 (g)b Reported (Unit of .essurement) b Performed (t.LD)
Range Di:*ance t Direction Raege Ra e te "esourceents Air Particulates Cross 8 84 0.01 0.07 (83/84) on Site 2 0.08 (14/14) w t Measured 0
0.02 - 0.15 0.3 mi, 50*
0.05 - 0.15 (pC1/s))
Airborne lodine I-131 42 0.10 All 1.1.D Not Applicable Not Measured 0
(pC1/m )
3 Camma Backgr;und y Dose 17 3
21.1 (8/8)
On Site 2 33.8 (1/1) 15.5 (9/9) 0 16.9 - 33.8 33.8 13.0 - 16.9 (m'/Qtr.)
Milk 1-131 21 0.5 All LLD Not Applicable All 1.LD 0
(pC1/1)
Cooling Water Cross P 39 5
6 (18/26)
Unit 2/3 Discharge 6 (11/13) 5 (8/13) 0 4-9 4-9 4-9 (pC1/1)
Surface Water y Spec.
1 10 All LLD ht Applicable Not Measured 0
(pC1/1)
(f)
Traction of detectable measurements at specified locations is indicated in parentheses.
bMcan and range based upon detectable measurements only.
TABLE 5.1-1 CAW.A RA3IATION Average mR/Otr. Using Thercoluminescent Dosimeters Date Annealed:
12/16/7-03/20/78 36/12/78 09/11/78 Date Read:
03/27/78 06/19/78 09/22/78 12/18/78 Location 1_s_t Quarter 2nd Quarter 3rd Quarter _
4th Quarter On-Site Indicator Stations D-16 On-Site 1 18.2: 3.9 20.823.9 16.922.6 16.911.3 D-17 On-Site 2 24.7! 3.9 29.925.2 37.726.5 33.8:3.9 D-18 On-Site 3 20.82 2.6 22.122.6 19.522.6 20.823.9
D-46 Collins Road 18.22 2.6 22.122.6 15.6!1.3
-.ot2.6 Average 20.51 3.2 23.723.6 22.413.3
~~ 23.122.9 Off-Site Indicator Stations g
D-09 Bennitt Fara 19.52 3.9 19.521.3 19.522.6 20.822.6
D-15 Clay Products 16.92 2.6 18.2!2.6 12.612.2 16.921.3
D-45 Pheasant Trail 18.2,! 1.3 18.2!2.6 15.613.9 20.823.9
D-47 Prairie Park 16.92 3.9 16.9!1.3 13.022.6 18.223.9 Average 17.9211.7 18.212.0 15.212.8 19.2 2.9 Background Stations D-02 Elwood 16.9 3.9 14.311.3 10.722.6 14.321.3
D-03 Joliet Brandon Rd.
16.92 5.2 16.9t2.6 11.611.8 15.922.6 D-04 Wilmington 18.2! 1.3 16.9 1.3 11.421.7 16.922.6
D-06 lbrris 16.9! 2.6 14.321.3 11.2 1.3 13.021.3 D-07 Lisbon 15.6 2.6 15.621.3 11.721.8 15.622.6
D-08 Coal City 15.61 2.6 14.321.3 10.5 1.4 14.312.6
D-11 Channahon 16.92 2.6 15.6 1.3 12.6 1.6 15.6!3.9
D-14 Minocka 15.6! 2.6 15.621.3 12.722.9 15.621.3
D-44 Goose Lake Village 18.22 1.3 16.9!1.3 13.021.3 16.923.9 16.72 2.7 15.611.4 11.711.8 15.522.5 Average
Stations shared by Dresden and G.E.
APPENDIX II METEOR 0GICAL DATA e
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e e
APPENDIX III ERRATA A
57
Dresden Errata Januarv - June 1977 Renort Section 5.4, Page 34, Line 17 Change From To Sr-90 Sr-09 Se ction 8.0, Page 36 From To Tables 9 0-1 thra 9 0-3 Tables 8.0-1 thru 8.o-3 Insert Attached Table 5 2-2 Section 5 2, Page 33, Line 2 From To W6 W7 Section 5.4, Page 34, Line 21 See 5.0 Tables 5.4-3 thru 5.4-4 Table 8.0-4 Collection Date 06/12/77 under solids insert sample lost Insert Table " Additional Information for Table 5 02, 5 03, 5 04 5 05:
Annual Report 1977 Section 3,2, Page 3, last line Change Fror To Table Table 1.2-1 Replace Table 3 2-2 cont'd with attached Table 3 2-3 Section 3 2, Page 24, Line 3 Change From To whild while Tables 5 0-2 through 5 0 add footnote NR - Hot Required 4
58
Additional Information for Table 5 0-2, 5 0-3, 5 0-4 Dresden 5 0-5 1.
Air Samplers Location Distance (miles)
Direction (o) a.
Onsite Station #1 0.6 300 50 b.
Onsite Station #2 08' 180 c.
Onsite Station #3 0.
d.
Collins Road 09 260 e.
Bennitt Fam 0.9 60 f.
Pheasant Trail 09 140 g.
Clay Products 2.0 180 n.
Prairie Park 4.0 230 1.
Coal City 75 190 j.
Goose Lake Village 38 210 k.
Morris 6.0 250 1.
Lisbon 10.0 310 m.
Minooka 4.5 5
n.
Channahon 35 40 o.
Joliet 12 5 60 p.
Eltcmood 8.0 80 q.
Wilmington 8.0 130 2.
TLD Same as 1 3
Milk Location Distance Direction a.
Davidson Farm 6
10 b.
Mather Farm 16 40 c.
Dorin Farm 7
220 4.
Fish Location Distance Di_.*e cti on a.
Dresden Lock & Dam 0.5 270 5
Surface Water Location Distance Direction a.
Illinois River at E.J. E. R.R. Bridge 1
270 6.
Cooling Water Sample Location Distance Direction a.
Inlet-Unit 1 At Station b.
Discharge
1) Unit 1 At Station
2) Unit 2/3 59
7 Sediment Location Distance Direction
a. Dresden Lock and Dam 05 270 6
s 60
~
s TABLE 3.2 -3 OPESDEF 2 /3 NUCLEAD PCWFR STATION COSES RESULTINC FPOP F XPCSUR E TO PADIDACTIVIIY DISCHAPGED IN LIOUID WASTE OFCEMPFP 1077 ANP JANUADY TO DECEMBER 1977 DOSF PY PATHWAY (PREP)
PERIOD INCESTION SHORELINE SWIMMING BOATING WHDLE PODY GI-LLI THYPOID BONE SKIN WHDLF B 0 0.Y SKIN WHOLE BODY WHOLE BODY THIS MONTH
.001
.001
.004
.001
. COO
.000 0.000 0.000 0.000
~~ ES T 3 MONTHS
.0C1
.001
.004
.C01
.000
.000 0.000 0.000 0.000 L
LAST 6 MONTHS
.001
.001
.004
.001
.000
.000 0.000 0.000 0.00C
__SINCE_ JANUARY
.001
.001
.004
.001
.000
.000 0.000 0.000 0,000 TOTAL ORGAN DOSE SINCE JANUARY CPGAN TOTAL DOSE MAXIMUM ALLOWABLE PERCENT OF MAXIMUM WHOLE BODY
~
.001 500
.000
~
GI-LLI
.001 1500
.000 THYPOIO
.004 1500
.000 PONE
.001 500
.000 SKIN
.000 3000
.000

ML19296A528

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