ML17345B324

Radiological Environ Monitoring Rept,Jan-June 1982. W/ 820831 Ltr

ML17345B324
Person / Time
Site:	Turkey Point
Issue date:	08/31/1982
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
L-83-379, NUDOCS 8311030056
Download: ML17345B324 (48)

Text

RADIOLOGICAL ENYIRONMENTAL MONITORING REPORT TURKEY POINT UNITS 3 5 4 DOCKET NOS. 50-250, 251 DADE COUNTY, FLORIDA 1-1-82 TO 6-30-82 PREPARED AUGUST -1982 83ii03005b 82083i PDR ADOCK 05000250 R PDR

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l. IHTRODUCT ION This report is submitted pursuant to Section 6.9 of the Turkey Point Plant Units 3 & 4 Technical Specifications.

Radiological envi rormental surveillance for the Turkey Point Plant is conducted in accordance with Section 4.12 of the plant's Technical Specifications. A summary of the samples collected and analyses performed during the period January 1, 1982 through June 30, 1982 is provided in Table 1.

2. THE MONITORING PROGRNA Period Covered: This report covers the period frcm January 1, 1982 through June 30, 1982.

Anal tical Responsibility: Envirormental radiological monitoring for the Turkey Point Plant is conducted by the State of Florida, Department of Health and Rehabilitative Services (DHRS). All samples are collected and analyzed by DHRS personnel.

~NfS i: i i, 1 f687

'col 1 ected from 35 di f ferent locations to be analyzed for radioactivity.

Table 1'summarizes the highest, lowest and mean results for all sample locations, and where applicable the highest, lowest and mean results for the sample locations which yielded the highest mean levels. Tne values in Taole 1 are based upon only those analyses which yielded detectable measurements.

For any sample yielding detectable results, the number of samples with detectable results compared to the total number of samples collected for that analysis is also indicated.

Split-Sample: During the period January 1, 1982 - June 30, 1982, 14 samples were collected for comparative analysis by the 00E in accordance with the DHRS/DOE split-sampling program.

Missing Data: Radiation exposure rates on samples collected during January, February and March 1982 have not oeen reported oy DHRS for the locations specified by Table 4.12-1 of the plant's Technical Specifications. See Section 3 of this report for more detailed information.

3. DISCOSSION AND INTERPRETATION OF DATA Air Monitoring: Continous air sampling is conducted at 8 aifferent locations surrounding the Turkey Point Plant. Samples are collected and analyzed by Florida DHRS for gross radioactivity and radioiodines (I-)3))

on a sleekly basis. All samples from this reporting perioa were within the normal range of background measurements. Table 1 provides a summary of these results.

Direct Radiation Monitorin  : Continuous monitoring of. ambient radiation exposure rate is provided routinely at eleven different sample locations surrounding the Turkey Point Plant. Samples are collected and analyzed by Florida DHRS on a monthly basis.

Due to an instrument malfunction which produced suspiciously low readings in some samples, the repor ti.ng of all readings for the TLD samples collected during the first three months of this period has been deferred until the results have been carefully studied as to their validity. In

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addition to the eleven sample locations monitored for exposure rate on a monthly basis however, Florida DHRS has an additional forty two dosimeters (two at each of twenty-one locations) deployed around Turkey Point Plant.

These samples are collected and analyzed by DHRS semi-annually. Results for these dosimeters which were collected and analyzed in March are all within the normal range of background. The period covered overlaps the period of unreported data. These results are reported in Table 1.

Results from the second three months of this period are all within normal range of background measurements. Table 1 provides a summary of these resul ts.

OTHER SAMPLES In addition to the air and dosimeter samples previously discussed, several other environmental samples are collected frcm areas surrounding the Turkey Point Plant. Samples of water, drinking water, sediment, aquatic biota and terrestrial samples including food crops, soil, vegetation and other terrestrial biota are collected and analyzed by DHRS personnel.

These results for the period January 1, - June 30, 1982, are summarized in Table 1. Fxcept as noted below, the results of al l environmental sampling

l 0

\

indicates that radioact1vity levels in the area around the Turkey Point

.Plant are within the normal range of background measurements.

The average concentration of trit1um 1n water samples collected fran the Turkey Point closed cooling canal system during this period was 3970 pCi/l.

Because some interchange occurs with the groundwater, tritium was sometimes detected, although at much lower concentrations, in water samples from sites adjacent to the cool1ng system. Other than naturally occurring radioactivity and tritium, no other'isotopes were detected in any of these water samples. Low levels of cobalt and cesium were found however, in some samples of bottom sediment collected fran inside the closed cooling system. Theses observations are consistent with what has been observed fran previous surveillance per1ods, with no evidence of a continuing buildup.

The concentration of tritium in the Turkey Point closed cooling system is equivalent to approximately 0.13 percent of the unrestricted area concentration lim1t specified by 10CFR 20. 106. Further, although the Turkey Point cooling system is saline and therefore not fit as a source of drinking water, the concentration of radioactivity 1s still well below established federal standards for canmuni ty dri nk1ng water systems.

4. CONCLUSIONS The concentration of all radionuclides reported in Table I is much less than that permitted for release to unrestricted areas as specified in lU

CfR 20, Appendix B, Table I I. The Radiological Environmental Monitoring program establishes that radioactivity released as a result of operation of the Turkey Point Plant Units 3 8 4 is not contributing significantly to the radiation exposure of any individual or population group.

TABLE 1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

NAME OF FACILITY TURKEY POINT PLANT UNITS 3 6 4 DOCKET NO. 50-250 251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JANUARY 1, 1982 - JUNE 30, 1982 All Indicator Location with Highest Mean Control" ) No of Number of Locations Location Nonroutine Mediun or Pathway alysis Samp e Locat on keporteo Sam led Uni t for Sites Sam les Anal ses Meanl) Ran el) Distance 5 Direction eanl) Ran el) Meani) Rani e ) Measurenents lol AIR 8 415

.1. Particulates pCi/m3 Gross 8 8 207 2075)6) .019 .001- T64-Hatoma Suostation. .020 .001- oUZU o001-

{207/207) .048 (22 miles - N) (26/26) .039 (26/Zo) ,039 .

2. Radioiodine pCi/m3 1311 8 208 208 ) NA 1.Z DIRECT RADIATION 132

1. TLD uRem/hr Exposure 132 66'>>) 4.8 203 T64-Hatoma Suostation 6.0 5.5- 6+U 5.5-Rate (66/66) 6.3 (22 miles - N) (6/6) 6.3 (6/6) 6.3 1.3 PRECIPITATION 17

1. Rainwater 17 Rainwater pCi/1 Gross 8-DS 17 5.7 1.0- T52-Florida City Suo- 9.6 1.5- 1.8 1.0-

{12/17) 22.8 station (7 Miles-W) (5/5) 22.8 (2/3) 2.7 Gross 8-UOS 17 4.3 2.7- T52-Florida City 4.3 2.7- ND NA (2/17) 5.9 Suostation (7 Miles-N) (2/5) 5.9 Tritium 17 ND HA NA ND NA Y-emitting4) 17 ND isotopes DS - Dissolved Solids UDS >> Undissolved Solids ND - Not Detectaole NA - Not Applicaoie

TAULE 1 ENVIRONMENTAL RADIOLOGICAL HONITORING PROGRAH SUNHARY NAME OF. FACILITY TURKEY POINT PLANT UNITS 3 6 4 DOCKET NO. 50-250 251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JANUARY 1 198Z - JUN'E 30 1982 All Indicator Location with Hignest Hean ControlZ) No. of Number of Locations Location Nunroutine Medium or Pathway Analysis Samp e Locat on Reported Sampled Unit for Sites Samples Analyses Mean ) .Rangel) Distance I Direction Heanl> Ran e1) Neanl) Ran ei) Neasurements Z.l SURFACE MATERS )4 44

1. Estuarine 10 20 Surface Mater pCi/1 Tritium 20 260 T81 - Card Sound 260 (I/20) *(6 miles - S) (1/2) 89Sr 20 HD HA HA NA NA HA 90Sr 20 ND NA HA NA NA NA Y emmi ting 20 ND NA NA NA NA HA isotopes Z. Cooling Canal 125)

Surface Mater pCi/1 Tritium . 12 3970 3000- T84-Closed 4083 3100-(12/12) 5800 Cooling Canal (6/6) b800 (Onsite - SM) 89Sr 12 ND HA 90Sr 12 1.1 T97 - Locn Rosetta 1~1 (I/12) (Unsite >> E) (1/6)

Y emitting4 12 NO NA HA isotopes DS - Dissolved Solids UDS - Undissolved Solids NO - Hot Oetectaole NA - Not Appltcaole

TABLE 1 ENVIRONMENTAL'ADIOLOGICAL HOtlITORItlG PROGRAM

SUMMARY

NAME OF FACILITY TURKEY POINT PLANT UHITS 3 A 4 DOCKET NO. 50-250 Z51 LOCATIOH OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JANUARY I, 1982 - JUNE 30 1982 All Indicator Location with HigheSt Mean ControlZ) tlo. of Numner of Locations Location t<onroutine Medium or Pathway Analysi s amp e ocatton Repurtea Sam led Unit for Sites Sam les Anal ses Heanl) Ran el) Distance & Direction Mean ) Ran e ) Mean j Ran ei) Measurements

3. Fresh Water Drainage Canals 12 Surface Mater pCi/I Gross 8-DS 12 138.5 30 3 - Floriaa City 270 Z10- NA (12/12) 330 Canal (2 miles - WNM) (6/6) 330 NA Gross B-UDS 10.8 HA T96 - Hoael land canal 10.8 (1/12) 630'75 (4 miles - SM) (1/6)

Tritium 440 270- T75-Fla. City Canal 440 Z70-(5/12) (2 Miles - MNM) (5/6) 630 2.2 MELLS 9 18

1. Potable Well 3 6 Water Drinking pCi/1 Gross 8-DS 7.2 4.3- T57-Dolan's- Fata 9.5 8.7- NA Mater (6/6) 10.3 (4 .Hiles - NM) (2/2) 10.3 NA Gross 8-VDS ND HA HA Tritium tlD NA NA DS - Dissolved Solids UDS >> Undissolved Solias NO - Hot Detectable NA - tlot Applicaole

TABLE,l ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

NAME OF FACILITY TURKEY POINT PLANT UNITS 3 f 4 DOCKET NO. 50-250 251 LOCATION OF FACILITY OAOE COUNTY FLORIDA REPORTIHG PERIOD -

JANUARY 1, 1982 JUNE 3U 1982 All Indicator Locatton with Highest,Mean Control2) No. of Number of Locations Location Honrouttne Medium or Pathway Analysts Samp e Locat>on Sam led Unft for Sites kepurtea Sam les Anal ses Mean>> Ran e>> Uistance 5 Direction M an>> Ran e>> Mean>> Nan >> Measurene'nts

2. Ground Mater 12 Ground Mater pCi/1 Tritium 710 350- TU7-Groundwa ter Mel 1 2600 Mells (5/12) 1340 E-10 (2 Miles -

BgSr S) (2/2) 1340 12 NO HA HA 90Sr 12 ND HA NA Y emfttfng4 12 HD NA isotopes

.0 BOTTOM SED IMEHTS

1. Cooling Canal Bottom pCi/kg 89Sr Sediments gOSr ND Y emitttng4) isotopes 60Co 398 353- T84-Closed Cooling 420 380-(3/4) '460 Canal (Onsfte.- SM) (2/2) 4bU 2 58Co 250 HA T84-Closed Cooling 250 (I/4) Canal (Onstte - SM) (1/4) 144Ce 310 T84-Closed Cooling 310 (1/4) Canal (Onstte - SM) (1/4)

4. Others ND ",HA DS - Otssolved Solids UDS - Undissolved Solids- ND - Hot Detectable NA - NOt APPIICaole

TABLE )

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAN SUGARY HANE OF FACILITY TURKEY POINT PLANT UNITS 3 6 4 DOCKET NO. 50-250 251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JANUARY 1 1982 - JUNE, 30 1982 All Indicator Location with Nighest Nean Control2) No. of Number of Locations Location Nonruutine diun or Pathway Analysis Samp e Location Keuurteu Sam led Unit for Sites Sam les Anal ses Nean ) Ran el) Distance 6 Direction Neanl) Ran el> xeanl> Ran eI) eeasurenents

2. Estuarine ~

Bottom pCi/kg Sr

.Sediments 90Sr Y emitting4 NO isotopes 32

1. Crustacea 6

{Blue Crab) pCi/kg 89Sr 6 ND NA HA HA NA 9'Sr 6 NO NA HA NA NA Y emitting4 6 ND NA NA NA NA isotopes DS - Dissolved Solids UOS - Undissolved Solids ND - Not Detectable NA - Not -Apu iicaole

TAULE 1 ENVIRONHEHTAL RADIOLOGICAL HONI TURING PROGRAN SU%CRY HANE OF FACILITY TURKEY POINT PLANT UNITS 3 & 4 DOCKET NO. 50-250 251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JANUARY I 1982 - JUNE 30 1982 All Indicator Location with Highest Nean Control2) No. of Number of Locations Location Nonroutine Hedium or Pathway Analysis Samp e Locat on Keportea Sam led Unit for Sites Sam les Anal se Hean ) Ran el) Distance & Di rectibn Neanl) Ran e1) Neanl) an el) Heasurenents

2. Fish, Carnivore (Hixed Species) pCi/kg 89Sr 6 ND NA HA 90Sr 6 38 36- T66 - Card Sound, 41 (2/8) 41 North of Causeway (1/1)

(10 miles - SSM)

Y emitting 4) isotopes 137C 85 70- T84 - Closed Cooling 85 70-(2/8) 100 Canal (Onsite - Sw) (2/2) 100

2. Other NO NA HA

3. Fish, Herbivore (Mullet) pCi/kg 89Sr HO NA NA II 90Sr HD NA NA Y emitting NO HA isotopes DS - Dissolved Solids UDS - Undissolved Solids ND - Not Detectable NA - Not Applicable

a TABLE 1 ENVIRONHEHTAL'RAD IOLOG ICAL HOHI TONING PROGRAH SUHHARY NAHE OF FACILITY TURKEY POINT PLANT UNITS 3 A 4 DOCKET HO. 50-250 251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JANUARY 1 1982 - JUNE 30 1982 All Indicator Location with Nignest Hean Control2) Ho ~ ot Henber of Locations Location ttonroutlne Hediun or Pathway Analysi s S@np e Locatson Reported Sam led Uni t for Sites Sam les Anal ses Hean ) Ran el) Distance a Direction Heanl) Ran e1) Hean1) san el) Heasurenents

4. Turtle Grass Turtle Grass pCi/kg 895r HO 90Sr ND Y emitting 4) ND isotopes

5. Sponges 6 Sponge Y. emi t ting 4) isotopes pCi/kg 1. 95Zr 130 70- T93-Pelican Bank 170-(3/6) 170 (1.5 miles - E) (1/1)

2. Others ND HA NA NA 5.0 TERRESTRIAL 12 18

a. ~ama An ma 1 1 (Opossum) pCi/kg 89Sr ND NA NA NA NA NA 90Sr 13 T58 - Entrance Road 13 NA NA NA (1/1) (0 Hiles - W) (1/1)

Y emitting4) isotopes 137Cs 57 HA T58 - Entrance Road 57 HA (I/1) (0 Hiles - M) (I/I)

2. Others ND HA DS - Dissolved Solids UDS - Undissolved Solids AD - Hot Detectaole ttA - Hot'pplicaole k

TAULE I ENVIRONMENTAL RADIOLOGICAL MOttITURIHG PROGRAM

SUMMARY

NAME OF'FACILITY TURKEY POIttT PLANT UNITS 3 tI 4 DOCKET NO. 50-250 25I LOCATION OF FACILITY DADE COUHTY FLORIDA REPOKTING PERIOD JAttUARY I 1982 - JUNE 30 1982 All Indicator Location with Hignest ttean Cuntrol2) No. of Number of Locations Location. Nonroutine Mediun or Pathway Analysi s Samp e Locat>on Kuyortea Sampled Unit for Sites Sam les Analyses Mean~) Rane ) Distance ti Direction MeanI) Ran eI) MeanI j Kan eI) Measurenents

2. Food Crops 35)

(Potatoes) pCi/kg 89Sr tt0 NA NA HA N 90Sr 2.9 2.2-3.6 T57 - Dolan's Farm 3.6 .

(2/3) (4 Miles - NXj (I/I)

Y emitting 4) ND ttA NA isotopes

3. Vegetation (Mangrove Leaves) pCi/kg 89Sr ND ttA NU 9OSr ND NA Y emitting 4) ND NA ND isotopes DS - Dissolved olids UDS - Undissolved solids ND - Not Detectable HA - Not Apylicaole 4S

TABLE 1

... EHYIROtNENTAL RADIOLOGICAL HONITORING PROGRIN SURNARY HARE OF FACILITY TURKEY POINT PLANT UNITS 3 8 4 DOCKET NO. 50-250 251 LOCATION OF FACILITY'ADE COUHTY FLORIDA REPORTING PERIOD JANUARY 1, 1982 - JUNE 30 1982 All Indicator Location with Nighest Mean Control2) NO. Ot Numoer of Locations Location Nonroutine edium or Pathway Ana lysi s Samp e Location Reported Sam led Uni t for Sf tes Sam les Anal ses Neani) Ran e1) Distance a Direction Nean>> Ran el) tieanl) Ran e1) measurement

4. Ground Samples (Soil) pCi/kg 89Sr 7 ND NA NA II 90Sr 7 ND NA NU Y emftting4) 7 isotopes 137Cs 193 110- T55-Silver Palm Dr. 320 NU (6/7) 320 E of AllaPatah Rd. (1/1)

(7 miles - NNW)

2. 58Co 140 T56-Princeton Sun- 140 (I/7) station (8 ttiles-NM) (I/1)

3. Others ND HA NA DS - Dissolved Solids DS - Undissolved Solids NU - Not Uetectaole NA - NOt Applfcaole

TABLE 1 NOTES

1. Mean and Range values based upon data with detectable results only.

Numbers in parentheses indicate the ratio of analyses which yielded detectable results to the total number of analyses performed for that medium.

, 2. Control location - T64, Florida Power 5 Light Company - Nat'orna Substation (22 Miles - N)

3. Due to an instrument malfunction which produced suspiciously low readings

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in some samples, exposure rates for all samples collected during the fi rst three months of this period have not yet been reported. This data is still being evaulated by Florida DHRS. In addition to the eleven locat'ions monitored monthly however, DHRS has twenty-one TLD dosimeters deployed 'around the Turkey Point Plant at distances of one, five and ten miles radially. A summary of that data which overlaps the period of unreported data is provided below:

Sample Location with

,Exposure Period No. of. Samples Mean Range Highest Reading 8/5/81-3/16/82 20* 6.032uR/hr 3.5-8.8uR/hr 10 Mil es - Northwest The above results are considered to be within the normal range of background radiation for Florida

4. Exgjuding Potassium 40 ( K), Radon - 226 (

(2~~Th) which are naturally occurring radioisotopes

'a) and Thorium -

detectable in 232 many environmental specimens.

5. Does not include split samples analyzed by DOE.

6. Particulate filter at one location missing upon sample collection: T-56 (Princeton substation - 8 miles NNW) - 2/10/82.

7. Exposure rate is based upon average readings of two TLD's.

The TLD's fran one location (10 miles west) were missing at time of sample collection.

RADXOACTDfE WASTE REPORT J ary 1, 1982 to June 30, 1982 Date of Shi ment Curies Cu. Pt. Dis osition 1-06-82 0 ~ 13077 170 Buried in Barnwell, SC 1-08-82 0-234: 170 1-1 1-82 '-370 200 1-12-82 407.000 84 1-14-82 .- 0.370 200 1-18-82 0.260 1050 Buried in h'ashington 1-19-82 2.200 200 Buried in Barnwell, SC 1-20-82 0.380 1050 Buried in Washington 1-21-82 0.822 170 Buried in Barnwell, SC 1-22-82 0. 197 1050 Buried in Washington 1-22-82 1.380 170 Buried in Barnwell, 'C II 1-29-82 197.620 84 2-02-82 0.605 170 2-03-82 0.312 1050 Buried in Washington 2-04-82 0 ~ 169 170 Buried in Barnwell, SC 2-05-82 0- 120 1050 Buried in Washington 2-09-82 0 ~ 206 1050 2-11-82 0.609 170 Buried in Barnwell, SC 2-13-82 0.445 170 2-16-82 0. 24587 1050 Buried in Washington 2-18-82 0.371 170 Buried in Barnwell, SC 2-19-82 0.291 1050 Buried in Washington 3-03-82 0. 176 1050 Buried in Barnwell, SC 3-17-82 1. 146 170 3-19-82 0-484 170 3-23-82 0. 770 85 4-05-82 0 160

~ 1050 Buried in Washington 4-06-82 0. 925 200 Buried in Barnwell, SC 4-07-82 0; 107 1050 Buried in Washington 4-09-82 0.108 1050 4-12-82 2. 504 170 Buried in Barnwell, SC 4-14-82 1.158 100 4-20-82 139.500 84 4-28-82 0.072 1050 Buried in Washington 4-29-82 0.172 1050 5-11-82 0.020 S40 Buried in Barnwell, SC 5-26-82 0.079 1050 Buried in Washington 5-28-82 74 .400 S4 Bur ied in Barnwell, SC It

~ 6-21-82 2.610 170 6-23-82 1.911 170 840.6396 2029!

40 Shipments On sitea as of July 1, 1982 8.852 1210

SEMIANNUAL REPORT OF RADIOACTIVE EFFLUENT RELEASES PTP UNITS 3 2 0 I/82 - 6/82 Introduction All liquid and airborne discharges to the environment during this reporting period

'ere analyzed in accordance with Technical Specification requirements. The minimum frequency of analysis as required by Safety Guide 21 was met or exceeded.

Li uid Releases Aliquots of representative pre-release samples were either isotopically analyzed for gamma emitting isotopes on a multichannel analyzer, or evaporated and analyzed for gross beta-gamma activity in a 2z gas flow proportional counter. The efficiency of the gas flow proportional counter is adjusted so that the activity determined by gross beta-gamma analysis approximates the isotopic activities determined by gamma spectrum analysis and selected beta determinations, exclusive of tritium and dissolved gases.

The above procedure was followed for all releases from the waste disposal system and for secondary system batch releases. Frequent periodic sampling and analysis were used to conservatively estimate the quantity of radioactivity released via the steam generator blowdown system.

The following comments will aid in the interpretation and evaluation of the liquid release data presented in Table I, pages 1 through S.

1. The reported values in Table I, page 1, include in their computation the h

quantity of radioactivity released from both the waste disposal system and the secondary system. The secondary system releases occurred when contaminated water was blown down from the steam generators during primary to secondary leakage conditions, or when the generators were drained for repair or refueling. Activity that entered the plant storm drain system

, was also included in the secondary system activity released and in the total activity released.

I/82 - 6/82

2. The reported values in Table I, pages 2 and 3 are the total quantities of radioactivity for individual nuclides released from the waste disposal system and the secondary system together. The values in Table I, pages 4 and 5 are for the waste disposal system only and pages 6 and 7 are for the secondary system only-

3. During primary to secondary leakage, release of several short-lived nuclides from the secondary system occurs. These short-lived nuclides are not generally detected in batch released from the waste disposal system due to the long holdup time of processed water. Only those isotopes that were detected in the secondary system releases were reported..All non-detectable isotopes are listed as ( ).

0. Weekly and monthly composite samples for the waste disposal system were prepared to give proportional weight to each liquid release made during the designated period of accumulation. The composites were analyzed for gamma emmitting isotopes on a multichannel analyzer attached to a high resolution Ge(Li) detector, and for Sr-89 and Sr-90, using a chemical separation and subsequent beta determination with a 2m gas flow proportional counter.

Tritium was determined by use of liquid scintillation techniques and gross alpha radioactivity w'as determined by use of a 2m gas flow proportional counter. All concentrations for radioactivity determined from analysis of a composite were multiplied by the total represented volume of the liquid waste released to determine the total quantity of each isotope and of gross alpha activity released during the compositing period.

5. At least one representative batch of liquid effluent from the waste disposal system'was analyzed monthly for dissolved fission and activation gases by use of gamma spectrum analysis. The resulting isotope concentrations were multiplied by the total volume released for the month in order to estimate the

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I/82 - 6/S2 total dissolved gases released. If more than one batch of effluent was analyzed, the concentrations were weighted in an appropriate manner. The results are totaled on a monthly basis in Table I, page S. Oissolved gases, if any, from secondary system releases were determined from the samples of the individual releases. Isotopic concentrations were multiplied by th'e volume released to determine the quantity of radiogas nuclides released.

6. Representative samples of secondary system batch releases were analyzed individually for gamma emitting isotopes. Analysis of a representative composite for tritium was made for releases which occurred due to primary to secondary leakage.

7. The applicable limit for release of radioactive material in liquid waste is five curies per quarter excluding tritium and dissolved gases.

Airborne Releases Airborne releases to the atmosphere occurred from: release of gas decay tanks, the instrument bleedline, containment purges, and the secondary system during conditions of primary to secondary leakage. The techniques employed in determining the radioactivity in airborne releases are:

a) Gamma spectrum analysis for fission and act'ivation gases, b) Removal of particulate material by. filtration and subsequent'gamma-spectrum analysis, Sr-89-90 determination, gross alpha analysis, and gross beta-gamma analysis, c) Absorption of halogen radionuclides on a charcoal filter and subsequent gamma-spectrum analysis, and d) 'ondensation of water vapor in a gas sample followed by analysis for tritium using liquid scintillation techniques.

3

1/82 - 6/82 All sporadic gas releases from the plant which were not accounted for by the above methods were conservatively estimated as curies of Xe-133 equivalent by'use of the plant vent process monitor recorder chart and the current calibration curve for the monitor.

The maximum rated capacity for the hogging jets and the maximum measured flow rate for the condenser air ejectors, and an estimate of the rate of exhaust from the atmoshperic dumps were used to conservatively estimate the airborne releases from the s

secondary system whenever applicable.

The following comments will aid in the interpretation and evaluation of the airborne release data presented in Table II.

1. Calculation of total radioactivity of noble gases, I-131, and particulates is based upon detectable radionuclides only.

2. The applicable limit for release of total radioactive materials in gaseous waste is 0.012 Ci/sec when averaged over the calendar quarter. The percent of the applicable limit for total gaseous release was computed as follows:

Total curies released in gaseous waste durin uarter x 1 00 96 off Limit I t=

(.012 Ci/sec) (Seconds in quarter)

3. The applicable limit for the release of I-131 and particulate "radionuclides with half-lives greater than eight days in airborne waste is:

Z Qi < l0,000 m3, where Q; = release rate of it" nuclide, Ci/sec IvlPCf . sec and MPC; = maximum permissible concentration of the ith nuclide, Ci/m3 The release rate, Qi, was determined by dividing the total activity released in Ci, for the ith nuclide (ty, > 8d), during the calendar quarter by the seconds in the quarter.

I/P,2 6/S2 E

MPC; values were obtained from 10CFR20, App endix B Table II, Column l.

The MPC chosen was the most conservative value of either the soluble or insoluble MPC for each isotope.

The percent of applicable limit was determined as follows:

x l00%

% of Limit = MPCi 10,000 m3 / sec The maximum gaseous re Ieasee rate ra e for o each month is listed in Table II, page 1, under Section A, Line 3. Th e app l'cable i limit for maximum allowable release rate is 6.7 2+00 gCi/sec, average over one hour.

5. All values reporte d in a bl e Il pages 2 and 3, include the particulate, gaseous, and halogen activity released from the containments during purging, auxiliary building (leakage from pumps, valves, etc), the gas waste disposal system and the secondary system during conditions of primary to secondary system leakage. If a minimum detectable activity value iwas a not calculated for an isotope, it will be listed as ( )..

PEHDIX-11 PREPARATIOH OF TIIE I'10HTIILY "I'RI=.LININARY REPORT OH INDIOACTIYE I'LL/Qt> usu AR~ "RADIOACTIVE EFFLUEHT RELLASES" PORTION OF TIIL SEMIANNUAL OPERATING REPOIIT TMLE I Report of Aadioacttv~ EFPlueots: Liquid Gross Radioactivit Januar Februa Mar h A z$ M 7

1. Total Release mCi 1.27 E+02 2.61 E+02 6.19 E+Ol 5.47 E+02 1.94 EH4

2. Av Concentration Durin Releases Ci/ml 5.8 E-10'.7 . E-10 2.0 E-09 3.1 E-10 1.8 E-09 7.4 E-l

3. Av Concentration for Ilonth Ci%11 4.6 E-10 7.7 E-10 1.9 E-09 3.1 E-10 1.8 H-09 7.4 E-1'.

a b E-09 e Max Concentration Released Ci/m I 8. 2 E-08 5. 4 E-08 2. 7 E-08 2. 7 4. 8 E-08 3.5 E-0

~i. Percent of Technical Specificat on Limit for Total Activit Released 9.8 E+00 1.61 E+Ol Tri tl um I. Total Release Ci 2.61 E+01 5.66 E+Ol 4.11 8+01 4.20 EWl 8.55 E+Ol 5.90 E+0

2. Av Concentration Ourin Releases Ci/ml 1.5 E-07 3.4, E-07 3.1 E-07 2.1 E-07 2.8 E-07 2.3 E-0

3. Avc Concentration for tionth 'iCi/ml 1.2 E-07 3.4 E-07 3.0 E-07 2.1 E-07 2.8 E-07 2.3 E-0 C. Disso ve Ho e Gas

1. Total Release mCi 6.53 E+00 2.87 E+01 8.34 E-.01 1.63 E+02 6.62 E+01 1.15 E+0

2. Av Concentrati on Duri n Rel eases >Ci/ml 3. 8 E-ll 1.7 E-10 '.3 E-'12 8.1 E-lo 2.1 E-10 4.4 E-z

3. Av Concentra ti on for Month i Cl /ml 3. 0 E-11 1. 7 E-10 6 .1 E-12 8. 1 E-10 2. 1 E-10 4. 4 E-3 D. Gross Al ha Radioactivity

1. Total Release mCl ( 2.9 1'.-08) 2;2 E-08) ( 1.8 E-08) 1.9 E-08) 3.38 E-02 l. 3 E-(

2. Av Concentration Durin Releases <Ci/m] (<1-7 H-19) <1.3 E-19) (<1.4 E-19) <9.4 E-20) 1 1 E 13 3 E ~

3. Av Concentration for Month iCi/ml ~ (<1.3 E-19) <1.3 E-19) (<1.3 E-19) <9.4 E-20) 1.1 E-13 - 3.9 E-:

Volumes

1. Vol of Li uid Waste to Dischar e Liters 1.71 E+07 1.88 E+07 i.28 E+07 1.19 E+07 3.04 E+07 1.74 E+i

2. Vol of Dilution Water Durin Rel. Liters 1.71 E+ll 1.65 8+11 . 1.32'E+il 2.02 E+ll 3.08 E+ll 2.61 E+

3. Vol of Dilution Water for tenth Liters 2.18 E+11 1.65 E+11 1.37 E+ll 2.02 E+ll 3.08 E+ll 2.61 E+

NOTE'umbers in parentheses represent maximum sensitivity in,iiCi/inl.

a C/HPC = 0.0014 c includes 122 mCi from II4 1NST d -..'.includes 232 mCi of Na-24 used in steam b C/HPC = 0.039 overflow; R.O. I/251-82-02. generator moisture carryover test e C/HL'C = 0.0053 f C/HPC = 0.093

PLHU I X I I I'l

'LlilJ illfi~I g y, ll . ~ AR 1982 "RRi) IORCTIVE EFFLUEHT RELEASES" PORTIOH OF TIIE SEIIIAHHUAL OPERATIHG RLPORl PNiL'RIILE I Report of Radioactive Effluents: Liquid ToLal tsoto e Un t Januar Feb ruar Mar el> -'-'! 'a A -llom 3. 89 E940 l. 26 H.H)Q H-H)0 l. 29 H-ol 8.04 H-02-'une2.93 I".-02 I Ba-140 mCi (< l. 1 E-06) (<8. 4, E-07) (<5.1 H-O7) (<2.8 H-07) (<2.1 H-07) (<1.5 E-07) Co-57 1.64 E-ol 1.46 E-01 2.3 E-ol (<2.6 E-o8) (<2.0 E-08) (<l. 8 E-08) Co-58.= 4.07 H+01 2.57 H+Ol 6.72 E&1 1.34 E+00 6.71 E-ol 2.12 E+00 Co-60 mCi 3.66 E+Ol 3.98 H+01 '5.69 E+01 2.31 EKO 3.51 E+OO 3.42 Cr-51 mCl 8.49 E+00 7.69 E+00 5.34 8+00 1.89 E-ol (<2.5 E-07 ) 8.06 E-02 Cs-134 2.16 .E-02 8.51 H-ol 1.35 E+QQ 4.72 E-01 2.28 E+00 3. 39 E+00 Cs-136 mCi (<3.1 H-07) (<3.2 E-07) 3.34 E-01 (<1.0 E-07) 8.10 E-01 1.10 E+00 Cs-137 mCi 4.07 E-01 1. 69 H+00 3.62 E+00 1.03 E+00 4.33 E+00 7.24 E+00 Cs-138 mCi 1.81 H-ol 8.1 E-02 3.68 H+00 1.58 E+00 F -18 mCi 2.24 E-ol 5. 2 E-01 1.33 H+00 1.30 E+00 8.53 E+00 1.34 E+00 Fe-5 E-O7) <1.4 E-07 <8.7 E-08) (<7.0 E-08) I -131 3. 28 E-ol 1.56 H+01 9.30 E+01 3.52 E+01 .1.88 E+02 1.38 2 I .132 . mCi 2.23 E-01 6;39 E-Ol 1.03 E+00 4.99 E+00 7.63 E-Ol I .-133 mCi 8.1 E-02 5. 39 H+00 2.19 E+01 1.45 E+Ol 7.77 E+Ol 3.12 E+01 I -134 mCi 1.05 H-Ol 1.89 E+00 4.40 F;Ol I -135 mCi 7.4 H-ol 4.10 E&0 3. 81. E+00 1.67 E+01 2.80 E+00 La-140 (<7.. 9 E-08) 3. 39 H-02 (<4. 4 E-08) (<3.0 E-O8) (<2.8 E-O8) (<1.7 E-08) NOTE: Humbers in palentheses represent maximum sensitivity in I)Ci/)))l. IWIWU LVI'i'4 I i Y 4 LI I LVLu I li44l I'ldi 4 I Vjw I aOaa v ~ TABLE I Report of Radioactive Effluents: Liquid Toeal lsoto e Unl t Januar Pebruar Mnrrh A ril Hn-54 mCi 2.02 E+00 7.60 E-ol 6. 73 E-ol 5.54 E-02 6.01 H-02 9.20 H-02 Ho-99/Tc.-99m (<6.1 E-07) 3.99'-03. (<5. 7 E-07) (<1.3 H-07) (<1.6 H-07) 3.22 E-01 Na-24 mCi 4. 1 E-02 2.33 H+02 3.5 E-02 Nb-95 mCi 3.29 E+00 - 4.98 H-ol 7.5 E-ol 1.07 E-ol 5.06 H-02 (<3.6 E-08) sb-124 mCi 3.41 E-01 8.87 E+00 6.98 H-01 <5.9 E-08 <4.5 E-08 <4.6 E-08 Sb-125 mCi 1. 25 E+00 1.46 E+01 1.78 E+00 8.54 E-02 5.65 H-02 (<8.2 'a) Sr-89 mCi 1.4 E-Ol 1.8 E+OO (<7.5 H-09) H-Ol 6.93 H-ol 2.01 H-ol Sr-90 mCi 3. 8 E-02 <5. 7 E-09 3.14 H-02 2.79 E-02 1.05 E-01 8 E-0 Zn-65 mCi 5.04 E-01 (<4.4 E-07) (<2.1 E-07) <1.5 E-07) (<1.0 E-07) (<6.8 E-08) Zr-95 mCi 6. 87 E-01 (<3;0 E-07) 9.37 E-02 <1. 1 E-07) (<7.2 E-08) (<5.0 E-08) Total mCi 9.96 E+Ol 1.27 8+02 2. 61 E+02 6.19 H+Ol 5. 47 E+02 1. 94 HHO2 NOTE: Numbers in parentheses-represent maximum sensitivity in'"i<Ci/ml. . PEHOIX II PREPARATION OF TIIE I'IOHTIILY "PtiL'LIIIINRILYALPOIiT OH RADIOACTIVE RELLRSLS" RNU lilt Rll~g "l<AOIOACTIVE EFFLUEHT RLLEASES" I'ORTIOH OF TIIE SEMIAHHUAI OPERATING REPORT PAGE TABLE I Report of Radioactive ~Pfluents: Liquw - Waste Disposal System Isoto e Unit Januar Februar l larch Ag-,llom mCi 3.89 E+00 1.26 H+00 7.91 H-ol l. 29 E-ol 8.04 E-02 2.93 E-02 Ha-140 mCi (< l. 1 H-06) (<8. 4" E-07) (<5.1 H-O7) (<2.8 E-07) (<2.1 E-07) (<1 ~ 5 E-07) Co-5 7 mCi 1. 64 E-01 1. 46 E-01 (<4.6 E-08) (<2.6 E-08) (<2.0 E-08) (<1.8 E-08) Co-58 mCi 4. 07 H+01 2.52 H+Ol 4.10 E+00 1.31 E+00 5. 72 E-01 1.40 E+00 Co-60 mCi 3.61 E&l 3.80 E+Ol - 6.48 H-H)0 1.99 r+OO 2 0 EWA Cr-51 8.49 E+00 7.69 E+00 1.14 . E+00 1.89 H-ol (<2.5 E-07) 8.06 E-02 Cs-134- 0 E-D8 1.56 E-02 2.69 E-ol Cs-136 (<3. 1 E-07) (<3. 2 H-07) 2.60 E-01 (<1.0 E-07 <8.1 E-08 <5.9 E-08 Cs-137 mCi 3.89 H-ol 4.97 E-01 2.06 E+00 9.64 E-02 1.23 E-Ol 5.38 E-Ol Pe-59 mCi 4.38 E-ol 1.46 E-pl (<] 9 E-P7) (< l. 4 H-07) (<8.7 E-08) (< 7.0 E-08) I -131 (< 2. 4 E-07) '.08 E+00 3.68 r+00 3.77 H-ol 4.08 E-ol 6.75 H-0> La-140 mCi (<7.9 E-O8) 3:39 H-02 (<4.4 H-08) (< 3. 0 H-08) (< 2. 8 E-08) (< 1. 7 E-08) Mn-54 mCi 2. 02 E+00 7.60 E-ol 2.13 H-ol 5.54 E-02 6.01 E-02 9: 20 -02 Mo-99/Tc-99m mCi (<6.1 E-07) 3.99 E-01 (<5.7 E-O7) (<1. 3 E-O7) (<1.6 H-07) 3.22 E-Ol Nb-95 mCi 3.29 E+00 4.98 E-01 (<1.2 H-07) 1.07 E-ol 5.06 E-02 (< 3. 6 E-08) sb-124 mCi 3.41 E-01 8.87 E+OO 1.98 E-ol (<5.9 E-08) .( 4.5 H-O8) (<4.6 E 08) Sb-125 mCi l. 25 .H+00 1.46 E+01 5.75 E-01 8.54 H-02 5.65 H-02 (<8.2 H-08) Sr-89 mCi 1'. 4 E-ol 1. 8 I'.+00 (< 7. 5 I'.-09) 6 . 66 H-02 2.21 H-ol 1.50 ,H-ol HOTE'umbers in parentheses represent maximka sensitivity in pCi/ml. NUCLEAR CNEtilSTRY PROCEDURE HC-3 .NOIX 11 PREPARATION OF TllE HOHTllLY "Pl(liLININARY RLI'ORT ON RADIOACTIVE RELEASES" AHO TIIE 1982 "RAOIOACTIYE EFFLUEHT RELEASES"'ORTION OF T)IE SEMIANNUAL OPERATIHG REPORT PAGE 5 TAO LE Report of Radioactivetttf uents: Liquid itasca Disposal system oto e Untt Jan uar Ma r-90 3. 8 E-02 <5. 7 H-09 3. 14 E-0 (,4.9 E-09) n-65 5.04 E-01 (<4. 4 E-07) (<2.1 H-07 (<1.5 E-07 <1.0 E-07 <6.8 E-08 s r-95 mCi 6. 87 E-01 (<3.0 E-07 9.37 H-02 1.1 E-9.85 E+01 1.02 8+02 2.06 E+01 4.42 H+00 3. 76 E+00 4.97 E+00 Total mCi NOTE: Numbers in parentheses represent ioaxiioum sensitivi ty in i~Ci/ml. lllllwlI hi% ~ 'PENI)IX 11 PREPRINTIOH OF TftE NOHTllLY "I'fICLIHIHRfIYfiCf'OlIT OH RRl) IOACTI YE RLLCASES" AHD TIIE AR 1982 "INDIOACTIVE EFFLUEHT fILLEASES" POfiTIOH Of. TffE SEf1IAHHUAL OPEIIATING fkLPORT PAGEl TAOLE I Report of Radioactive Effluents: Liquid - Secondary System Isoto)e Januar Feb ruar March April tiay June Ag-llom mCi 3.2 E-ol Co-57 mCi 2. 3 E-01 Co-58 mCi 6.O E-O3 5.1 - E-ol 6.31 E+Ol 2.66 E-02 9.9 E-02 7:23 E-ol Co-60 mCi 4 '5 E-Ol 1; 76 E+00 5.04 8+01 3.21 E-ol l. 42 E+00 2.01 E+00 Cr-51 mCi 4.2 E+00 Cs-134 mCi 8.51 E-Ol 3.82. E-ol 4.72 L-01 2.26 E+00 3.12 E+00 . Cs-136 mCi 7. 4 E-02 8. 10 E-ol 1. 10 .E+00 Cs-137 mCi 1.8 '-02 1.19 E+00 1.56 E+00 9.34 E-Ol 4. 21 Edgo 6.70 E+OO 's-138 mCi 1.81 E-ol 8.1 E-02 3.68 E+00 l. 58 E+00 F -18 mCi 2.24 E-Ol 5. 2 E-01 1.33 E+00 1.30 E+00 8.53 E+00 l. 3~) 8+00 I-131 mCi 3.28 '-.ol 1.35 E+Ol 8 '3 E+01 3.48 E+01 1.88 E+02 1.37 E+02 I-132 mCi ,2.23 E-01 6. 39 E-ol 1.03 E+00 4.99 E&0 7.63 .-Ol I-133 mCi '8.1 E-02 $ .39 E+00 2. 19 E901- 1.45 E+01 7. 77 E+Ol 3. 12 E+Ol l-134 1.05 E-01 1.89 E&0 4.40 E=ol I<<135 mCi 7.4 E-Ol 4. 10 E&0 3.81 E+00 1.67 E+01 2. 80 E+00 Mn-54 mCi 4.6 E-ol Va-24 mCi 4.1 E-02 2; 33 E+02 3.5 E-02 Nb-95 mCi E-Ol NOTE Numbers in parentheses represent maximum sensitivity- in 1>Ci/ml. NUCLEAR CIILHIS Il<Y VROCI'OUI(L HC-3 EHI)IX I I PREPARATION OF TIIE HOHTIILY. "I'RELIflIHRRY RLI'ORT ON RROIOACTIVE RELEASES" RHO TIIE R 1982 "RRDIORCTIYE EFFLUEHT IILLEASE'" I'ORTION OF TIIE SLNIAHNURL OPLRRTIHG RLPORT , PAGE7 TRI3LE I Report of Radioactive Effluents: Liquid - Secondary System soto)e Unit January I'eb ruary March April . May June sb-124 mCi 5.0 E-ol Sb-125 mCi 1.2 E+00 Sr-89 mCi 8.9 E-02 4.72 E-01 5.05 E-02 Sr-90 mCi 4.8 E-03 2.53 E-02 8.4 E-03 Total 1.14 EH@0 2.47 E+01 2. 41 E-~-02 5. 75 E&1 5.44 E&2 1.89 E+02 NOTE: Numbers in parentheses represent maximum sensitivity in iiCi/l)ll. lav'4t a lalw 4ala sss>s s ~ a ~ 'END I X I I PREPARRTIOH OF TIIE IIOHTIILY "I'IIELIHIHAIIYRLI'OIIT OH l\AOIORCTIVE IIELEASES" AHU II R 1982 "IIAOIOACTIVE EFFLUEHT RELEASES" PORTIOH OF TIIE SEI~IAHHuAL OPERATIHG REPORT PAGE ~ TAOLE I Report of Radioactive EfA uents: Liquid - Dissolved Gas Januar Ma Kr-,05 mCi (<8-5 E-05) (<4.9 E-05) '(<7.6 E-06 '4.6 E-06 Xe-131ni mCi (<6 . 4 E-06) ( <4. 5 E-'06) (<6 . 3 E-07) 1.14 E+pl I < .3 E-07 2. 5 1 E+00 Xe-133 mCi 6.53 E+00 2. 4 E+Ol 4 51 E-pl 1.50 E+02 6. 41 E+Ol 8.52 E+00 Xe-133m (<1.6 E-06) (<1.1 E-06) 3. 14 E-01 1.17 E+00 1 13 EWO Xe-135 mCi (<2. 1 E-07) 4.7 E+00 . 6.86 E-02 2.58 E-Ol 9 06 E-pl 1.30 1 Haste Dis osa S stem Kr-05 mCl (<8.5 E-05) (<4.9 I.'-05) (<7.6 E-p6) (<4.6 E p6) (<4.4 E-06) '<4.S E-06) Xe-131m mCi (<6.4 E-06) (<4.S E-06) (<6.3 E-07) 1.14 8+pl (<7.3 E-07) 2.51 E+00 Xe-133 mCi 6.53 E+00 2. 4 E+01 4.51 E-01 1.50 E+02 6.41 E+01 8.52 E+00 Xe-133m (<1.6 E-06) (<1.1 E-06) 3.14 E-01 1.17 E+00 1.13 EHOO 3.84 E-pl XB-135 inCi (<2.1 E-07) 4.7 E+00 6.86 E-02 2 '8 E-pl 9.06 E-Ol 1.30 E-Ol Secon ar S stem Kr-05 mCi Xe-13lni niCi XQ-133 mCi Xe-133m mCi Xe-135 mCi NOTE: Humbers in parentl~eses represent niaximuni sensi tivi ty in IiC1/ml. 0 .AR 1982 "I\ADIOACTIVE El FLUENT RELEASES" PORTION Ol= TIIE SEIIIRHHURL OPEINTIHG RLPORT TABLE II Ileport of Radioactive E Iuents: Rirborne A. Fi sss on an . ctivats on Gases .Januar Hebruaz March April May June 5.01 H+02 9.57, EH02 2.32 E+03 1.52 H+03 1.61 E+03 3.'44 E+03

1. Total Release

2. Av Release Rate for Period )Ci/sec 2.1 .. E+02 4.0'+02 9.6 E+02 6.3 E+02 5.3 E+02 1.4 E+03

• 3. Ilax Release. Bate for Period Ci/sec 3.0 H+04 2.8 E+03 4.0 E+04 3.6 E+04 4.5 E+04 4.0 E+04

• l1ax>o)uo) a>r orne re ease rate average over one >our or eac> mont). Tec n ca Specs cat]ons im) t ss 6.7 E<04 )ICi s averaged over one hour.

B. Io i ne 131 - 4.3 H-04 1.6 E-03 6.0 E-03 9.0 E-03 2.6 E-02 4.3 E-Oc

1. Total Iodine l.31

2. Av Release Rate for Period >Ci /sec 1.4 E-04 6 6 E-04 2.5 H-03 3.7 E-03 8.6 E-03 l. 8 E-Oi C. Particula,tes

1. Particulates with t 1/ )0 days Ci 3.8 E-05 1.36 H-05 . 1.3 E-04 1.3 E-04 2.7 E-04 3.1 H-0~

2. Av Release Rate for Period )Ci/sec 1.3 E-05 5.62 E-06 5 4 E-05 5.4 H-05 8.9 E-05 1.3 E-0~

1.6 E-09 (<9.2 E-17) (<1.5 H-16) 6.6 E-09 5 .4 E-09 2.0 E-0)

3. Gross Al ha Radioactivit

0. Tr ti u)o

1. Total Release 6.73 H-02 2.9 E-02 7.33 H-02 5.62 E-02 l. 83 E-01 9; 44 E-0',

Release Rate for Period )Ci/sec 2.23 E-02 1.2 H-02 3.03 E-02 2.32 H-02 6.06 E-02 3.90 E-O',

2. Av E. Percent o A >ca e 1m>t 'uarter I tarter TT

1. Fi ss i on and Acti vati on Gases 4.0 E+00 7.0 E+00 tl/2)0d 1.0 HM1 9. 9 E-01

2. I-131 and Part .

HOTE: Huo)bers n parentheses represent o)axio)uo) sens>t)v)ty )0 ))Cl o), NUCLEAR CIII:IIISIftY PltOCI.I)VIVE HC-3 I'EHDIX I I I PREPARATION OF TIIE IIOHTIILY "PltELIHIHAIIY ItEI'OINT OH INI)IOACTIVL I\ELEASES" AHD TIIE AR 1982 "RADIOACTIYE LFFLUENT RELEASCS" PORTION OF TIIL SLHIAHHUAL OPERATING RLPORT , PAGE: TAIILE II Airborne Releases - Particulates F . lsoto e Unl t Februar March A ril mfa -j Ullo pa~140 . Ci a (<6 7 E 14) (<6 3 E 14) <6 . 0 E-14): (<9.3 E-14) (<l. 3 'E-l3) (< 1. 1 E-.l3) Co-57 (<8. 7 E-15) (<7. 2 E-15) (<8.7 E-15) (<8.4 E-15) (<1.3 E-14) 3.6 E-07 Co-58 Ci 1.8 E-06 1.2 E-06 (<2.1 E 14) 5.5 E-07 1.4 E-06 1.1 E-04 Co-60 3.1 E-05 5. 3 E-06 1.3 E-04 1.0 E-04 l. 3 E-04 Cr-51 (<1.2 E-13) (<1.0 E-13) (<1.1 E-13) (<1.3 E-13) (<1.9 E-13) 5.8 E-06 Cs-134 (<2.9 E-14) 4.8 E-07 (<2.6 E-14) 9.6 E-06 2.3 E-05 5.8 E-06 Cs-136 (<4. 8 E-14) (<3.0 I:;14) (<2.0 E-14) (<3.6 E-14) 4.2 E-06 7.0 E-07 Cs-137 Ci 2.0 E-06 1.0 E-06 (<1.6 E-14) 1.6 E-05 4.0 E-05 F Ei Q5 6.7 E-07 4 8 Ei Q6 9.9 E-07 4.3 E-06 5 6 E-05 2.9 E-05 LQ-140 Ci (<2.6 E-14) (<3.1 E-14) (<2.9 E-14) (<4.0 E-14) (<4.2 E-14) (<2. 2 E-14) Hn-54 Ci 3.9 E-07 (<1.8 E-14) (<1.6 E-14) (<3.6 E-14) 3.9 E-06 3.4 . E-06 Nb-95 <1. 8 E-14 <2.4 E-14 <1.9 E-14 <2.3 E-14 <2.1 E-14 3.0 Sr-89 7. 2 E-07 8.0 - E-07 1.1 E-06 2.1 E-06 1.2 E-05 1.2 E-06 Sr-90 2.3 E-08 2.3 E-08 2.3 E-08 4.9 E-08 4.9 E-08 4.9 E-08 Zn-65 Ci 9.6 E-07 (<4.2 E-14) (<7.2, E-14) (<5.1 E-14) (<6.9 E-14) (<4.7 E-14) Total Ci 3.8 E-05. 1.36 E-05 1. 3 I'.-04 1.3 E-04 2.7 E-04 3.1 E-04 NOTE: Numbers in parentl>eses represent; inaxiinuln sensitivity, in i>Ci/inl. 0 P C HUCLERR CIIEHISTRY PROCLDURE NC-3 PPENDIX III PREPARATION OF TIIE I'IONTIILY "PRELII'IINRRY RCPORT OH RRDIORCTIVE RLLEASES" AND TIIE ERR 1982 "RADIOACl IVE EFFLUEHT RELEASES" PORTIOH OF TIIE SEllIRNHUAL OPERRTIHG RCI'ORT PAGE TABLE II Airborne R~eeases -'Gaseous I-ission and Rctlvat>on Gases Pebruary Harch April Hay June, Iso to )e Unit January 7.83 E-al 2.6 E-ol 2.94 EMO 5.27 E+00 2.27 E+01 3.42 E+00 , Ar-ill Ci (<8-4 E-05) (<8 ~ 7 E-05) (<8.6 E-05) 3. 29 E-al 9.43 E-02 2 05 E-Ol Kr-05 Ci

6. 72 E-02 1. 6 E-02 3. 89 E-02 2.03 E-01 1.38 E+00 5. 34 ~ E-ol Kr-05m Ci

( <8. 8 E-07) ( <8. 6 E-07) ( <8.9 E-oj) 1.08 E-al 9.07 E-01 Kr-07 Ci Kr-00 Ci (<8 4 E 07) (<9 8 E 07) (<8 6 E 07) 2.00 E-al 1.82 E+aa 5.89 E-01 Xe-131m Ci 1.48 EWO 2.9 r.-al 1.98 E+00 1.88 E+00 5 .50 E+00 1. 57 E.)DO 4.95 E+02 9.56 E+O2 E+O3 1.51 E+03 1.55 E+03 3.42 E+03 Xe-133 Ci 1.41 E+OO 3.7 E-01 1.52 E+00 1.81 E+00 1.10 E+ol 4.88 E+00 Xe-133m Ci Xe-l.35 Ci 1.74 E+00 4. 3 E-01 8. 35 '-01 2.92 E+00 l. 58 2+0 1 7.95 E+00 Xe-135m (<4.0 E-06) (<3.7 E-06) 4.8 E-04 3. 21 . E-Ol 3. 26 EHOO 3. 35'-al Xe-130 Ci (<7.1 E-06) (<8.1 E-06) (<8;9 E-06) 8.97 E-02 6.50 E-Ol 6.61 E-02 Total Ci 5.01 E+02 9.57 E+02 2. 32 E+03 1.52 E+03 1.61 E+03 3.44 E+Q3 llalo ens Gaseous [soto e Unst January February Harch April Hay June I-131 Ci 4.3 E-04 1.6 E-03 6.a E-a3 9 .0 E-03 2.6 E-02 4. 3 E-02 I-133 9.3 E-04 3.1 E-04 2.2 E-03 3.4 E-03 1.1 E-02 1.0 E-02 I-135 Ci 2.6 E-04 4.0 E-.05 6.2 E-04 2,.0 E-04 2.4 E-03 9 .0 E-05 Ci -1.3 E-04 (<6.3 E-14) (<5.8 E-14) 5;.5. E-04 8.7 E-04 1.6 E-04 r.-03 8.82 r.-03 1.32 E-02 4.03 E-02 '.95 To ta'l Ci 1.75 E-03 5.33 E-02 ote: um >ers n paren >ese s re >resen ma X imum sens iv> 1n jtflfitr 'I pb 1