ML17345B326

Environ Radiological Monitoring Program Summary for Jan-June 1981. W/810828 Ltr

ML17345B326
Person / Time
Site:	Turkey Point
Issue date:	08/21/1981
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
L-81-375, NUDOCS 8311030086
Download: ML17345B326 (42)

Text

0 O. 5025100MIAMI,AL3315+ i 5

FLORIDA POWER 8( LIGHT COMPANY XRZCVmicOrr August 28, 1981/.+c~

L-81-375 2

5,5 ~

Mr. James P. O'Reil ly, Director, Region II Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 8I 50-251 Semiannual Radiolo ical Re orts Two copies of the Turkey Point Semiannual Radioactive Effluent Report and Semiannual Environmental Monitoring Report for the period of January 1 through June 30, 1981 are attached. These reports are submitted in compliance with Technical Specification 6.9.4.

Very truly yours, rt E. Uhrig Vice President Advanced Systems 8 Technology REU/PLP/ras Attachments cc: Director, Office of Inspection and Enforcement (6)

Director, Office of Nuclear Reactor Regulation (17)

Harold F. Reis, Esquire 83ii03008h 8i082i PDR ADQCK 05000250 R PDR PEOPLE... SERVING PEOPLE

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ENVIf(ONMENTAL RADIOLOGICAL t~OHITOf<ING f'ROGRAt1

SUMMARY

TURVEY POINT UNITS 3 5 4 DOCf'.ET NOS. 50-250, 251:

DADE COUNTY, FLORIDA 1-1-81 TO 6-30-81 PftEf'ARED 8/21/81

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1. I Nl'RODUCT I ON This report is submitted pursuant to Section 6.9 ot the Turkey Point Plant Units 3 8 4 Technical Specifications.

Radiological -environmental surveillance for the Turkey Point Plant is conducted in accordance with Section Rel? of the plant's Technical Specifications. A summary of the samples collected and analyses performed during the period January 1, 1981 through June 30, 1981 is provided in Table l.

2. 'JHE t1ONITORI NG PROGRlb~j Period Covered: This reports covers the period Trorrr January 1, 1981 through June 30, 1981.

Analytical Responsibility: Environmental radiological monitoring for the Turkey Point Plant is conducted by the State of Florida, D partment of.

rr fiealth and Rehabilitative Services (DHRS). All samples are collected and analyzed by D)tRS personnel.

Number of Samples: Dui"-ing the period, a total of 80? samples were collected from 35 different locations and analyzed for radioactivity.

Table 1 summarizes the highest;, low st and mean results from all sample locations and where applicable the highest, lowest and mean results of the sample locations yielding the highest mean levels. 1'he number of samples

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which yielded detectable results is also provided.

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~S)lit-Sample Analyses: 0urin9 tho period January 1, 1981 - Juno 30, 1981, 12 samples were collected for analysis by the DOE in accordance with the DHRS/DOE spl i t-sampl ing,progr am.

t1issing Data: Sample results for Sr09, Srg" in several sample media, as indicated and noted in Table 1, were not available in time for this report. When received these results wil l be transmitted in a supplemental report. This data is not expected to alter the conclusions in this report.

3. Evaluation of Data a) An evaluation of trending graphs for the radiological environmental samples collected in the vicinity of the Turkey Point Plant indicates a continuation in the trend for generally higher than normal levels for air particulate gross-beta results. This trend was first observed and noted in the Environmental Radiological Nonitoring Program Summary Report for furkey Point Units 3 E 4, 7/1/80 to 12/31/80.

Additionally, during this period there were observations ot g~Zr and Ru in some sample media as shown in Table l. In the process of evaluating thes observations it was also noted that similar trends in data were prevalent. for air particulate samples collected from other sample locations within the State of Florida during the same period, incl udi ng tne detection of gblr and 1O Ru fry)l gamma scans of the ai r particulate samples. For this reason it is concluded that the higher

than normal gross-beta levels in air particulate samples and the detection of g r>.

~Zr and "'Ru in the radiological environmental samples h

around Turkey Point not attributable to the operation ot'he nuclear units at the Turkey Point Plant.

b) All of the radiological environmental surveillance data for tnis period has been evaluated and compared to previous data. Except as noted above, all observations are found to be consistent with values previously reported and evaluated.

4. CONCLUSIONS The concentration level of'ny radionuclide reported in TMLF I v~ill contribute much less than the maximum permissible limits ol'ndividual or population group'xposure that could result if there had been a

'I continuous intake of r adionuclides having concentration values e<iual to those permitted by APPENDIX 8, TABLE I I, 10-CFR-ZO. Therefore, the operations of Turkey Point Plant Units 3 8. 4 are not contributing harmful effects of irreversible damage to either the environment or to the health and safety of individuals or population groups in the regions surrounding Turkey Point Plant.

TA8LE 1 ENYIRON'l:llTAL RADIOLOGICAL MONITORING PROGRAM SUQMRY NA.'iE OF FACILITY Turkey Poin. Units 3 and 4 DOCKET NO. 50-250,251 LOCATION OF FACILITY Dade County F)or'.& REPORTiiNG PERIOD January 1, 1981 -June 30, 1981 Page 1 of 9

's

,'si Location with Hichest A'.1 Indicator Nean Control Number of Number of Locations Sample Location Location Nonroutire Vedium or Pathway Analysis Sanipled Uni t for Sites Samples Results ange Ois t ance an Dire c t ion Repaid Vean f~eanl Range Neasu~ts 1.1 Air pCi/1 Gross 8 8 196 26 196 0.232 ,053-.471 T58-Entrance Road on 0.245 .054- 0.238 0.060-Particulate {196/196) Site (1 mile-VSM) (24/24 0.417 (25/25) 0.458 Air Iodine PCi/1 '"I 8 ~

199 25') NA NA s

NA NA NA (0/199) 1.2 Direct uRem/ 11 130 130 ) 5.2 2.1-7. 5 T64-Nato...a Substation 6.4 5.4- 6.4 5,4-7.5 Radiation hr 65 results (130/130 (22 miles-N) Control 12/12 7.5 (12/12)

Sample location 1.3 Precipitation pCi/1 196)

Gross S-DJ 19 13.1 3. 3-38.1 T64-Natoma Svbstat':on ',9,2 10.4- 19.2 10.4-38.1 (16/19) (22 miles - N) Control (5/5) 38.1 (5/5)

Sample location Gross 8-UO 19 8.5 1 7.0-17.0 T72-Boy Scout Camp 17.0 17.0- 7.8 5.5-12.0 (10/19) (0.5 miles - SM) (1/4) 17.0 (3/5) sY Scan 19 NA NA NA NA NA IsA s

(0/19)

'H 19 NA NA NA sNA NA YA (0/ 9)

.; DS - Dissolved Solids i UOS

- Undissolved Solids INA - No Applicable s

TAGL= 1 ENVIRONHENTA'AD'.OLOGICAL HONITORIHG PROGRAM i SUEtARY Nnl/E OF FACILITY Turkey Poirt Units 3 ard 4 DOCKET NO. 50-250,251 LOCATION OF FACILITY Dade County Florida REPORTING PERIOD January 1, 1981-June 30, 1981 Page 2 of 9 Locat on with Hichest Viean Control Hu.",ber of All inoicator Nonroutine Hu~ber of Locations Sacple Location Location Re~'.ed Viediura or Pathway Analysis r).

Sar,:pled Uni~ for Sites Sa;..ples Results ilean ,a~nge Distance and Directior. ftean Range Heanl Range Heas~;;en ts 2.1 Surface Hater 2.1.1 Estuarine ~

IO 20 pCi/1 Y Spectru~ 20 NA ) SA NA NA (0/20) pCi/1 H 20 iiA NA NA HA NA (0/20) pCi/1 89Sr 20. NA NA NA NA HA HA (0/20) pCi/1 "s.- 20 . NA NA .NA NA NA iHA (0/20) 2.1.2 Cooling 122)

Canal PC'/1 Y Spectrun 12 iiA ) iiA HA iiA i>n Sys m ,

(0/12) i'n I pCi/1 H ~ 4200 3100- T-84-Cooling Canal 4200 3600- HA i (12/12) 5600 South of Bridge (6/6) 5500 (0 niles - SS~)

I pCi/1 89S. 12 NA. NA NA I

(0/12)

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'pCi/1 "Sr 12 NA NA HA NA NA HA (0/12)

ENVIRONHENTAL RADIOLOGICAL HONITORING PROGRAH SU<"WRY NAllE OF FACILITY Turkey Point Units 3 ard 4 DOCKET NO. 50-250,251 LOCATION OF FACILITY Dade County Florida REPORTING PERiOD January 1, 1981-June 30, 1981 Pa e 3 of 9 All Indicator Location with Hionest Vean Control Nv",her of Number of Locations S mple Location 1 1) Location Nonroutine Hedivm or Pathway Analysis Repo~

Samol ed Unit for Sites Samples Results V.ean Plunge Distance ard Direction tlean Range Heanl Range 1) Neasur~ts 2.1.3 Fresh Mater 12 Drainage Canal pCi/1 H 12 440 340-600 T75-Fla. City Canal 440 340-60 NA NA (4/12) at Old Salinity Dam (4/6)

(1 mile MNH) pCi/1 Gross 8-DS 12 164 3.0-370 T75-Fla City Canal 300 230-373 NA (11/12) at Old Salinity Dam (6/6)

(1 raile MP) pCi/1 Gross 8 UDS 12 6.4 6.4-6.4 T75-Fla City Canal 6.4 (1/12) at Old Sa'linity 6A-6.) NA Dam (1/6)

(1 mile MNM) 2.2 Potable Mell Mater pCi/1 H NA NA NA NA NA (0/6) pCi/1 Gross 9-DS ~

9.7 4.7-14.0 T57-Dolan's from 12.5 11.0- NA t (5/6) (4 miles NM) (2/2) 14.0 pCi/1 'Gross 8 UDS (0/6) NA NA NA NA NA NA

TABLE 1 ENYIRONHENTAL RADIOLOGICAL HONITORIHG. PROGRAY SUl"'VY NAllE OF FACILITY Turkey Point Units 3 and 4 DOCKET NO. 50-250,251 LOCATION OF FACILITY Dade County Flor',da REPORTING PERIOD January 1, 1981-June 30, 1981 Page 4 of 9 Indicator Location with Hichest Mean Control Number of 11 Number of Locations Sa. pie Location 1 1) Location Nor~tine t.;ediu;! or eoathwiiy Analysis l Rated Sar,:oled Unit

'ol Sites Samples Res its Y'ean /ange Distarce ard Direction Nean Range I'ean Range 1} Neasure...ents 2.3 Ground Mater 6. 12 Miel1 s pCi/1 Y Spectrum 12 NA ) NA HA HA HA (0/12) pCi/1 H 12 960 330-2800 T92-Mell 624A 1910 1012-(7/12) (4 miles - SSN) (2/2) 2800 pCi/1 ~

Sr ee) HA NA NA NA NA NA (o/6) e pCi/1 Sr ee) HA NA NA NA HA (o/6}

Sedieert

3. 1 Cooling Canal Sediment Y Spec rum I

,'Ci/kg "Co 880 230-1620 T85 - Cooling Canal . 920 230- iiA NA (4/4} Vest of 90o bend (z/2) lezo (0 niiles - SW)

I "Zr 7 Cooling Canal I pCi/kg 120 70-180 l est of 90 Bend 180 180 NA I

(2/4) (0 miles - SH} (1/2)

pCi/kg Others 4 NA } NA NA NA NA ,NA t

(0/4)

'Ci/kgt "Sr. ze) NA- NA NA HA NA NA NA (0/2}

pCi/kg 90Sr ze) NA ,NA NA it'A NA NA (o/z)

TA8LE 1 ENY I RONNiENTAL RADIOLOGICAL HONITORIHG PROGRAM SM'JURY NAtiE OF FACILITY LOCAT'0 i OF FACILITY Dade County Turkey Point Units 3 and 4 Florida DOCKET tto. 50-250,251 REPORTING PERIOD Jaruary 1, 1981-June 30, 1981 9

Page 5'f 9 Location with Hiahest ttean Control er o All Indicator Quti tieriivn or Path.ray Analysis Nu".,:her of Loi q+Co~s Sa;..pie Location 1} Location at Reporte Sai",.pl ed Uni t for Si tes Sar.:pl es Results t!ean Rage Distance and Drection t tean Range Yieani~~ Rance 1) tteasurer. ~

3,2 Estuarine Sedi,".,ent pCi/kg Y Spectrum NA ) ttA HA NA (0/7) 1 pCi/kg Sr tiA ~ NA HA itA NA (0/7) pCi/kg 9Os HA HA ii'A NA NA (o/7)

Aauatic 8iota 4.1 Crustaceaa) pCi/kg Y Spectrum NA NA LNA NA (o/6) pCi/kg 89Sr 06) KA NA iNA HA NA iNA pCi/kg "Sr 06) NtA NA NA NA nA iNA 4.2 Fish 72}

(Carnivore) pCi/kg Y Spectrum NA ) ~

NA NA NA NA NA (0/7}

pCi/kg 89S 26) 'tA NA NA HA (0/2) pCi/kg 'OSr 26) iNA NA hA HA (o/2)

TAGLE 1

• EHYIRONNEHTAL RADIOLOGICAL HONITORING PRGGSB SUiI.'V RY HAtIE OF FACILITY Tvrkey Point Units 3 and 4 DOCKET IiO. 50-250,251 LOCATION OF FACILITY Dade County Florida REPOPTIHG PERIOD January 1, 1981-June 30, 1981 Page 6 of 9

>.i All Indicator Location,i',th Richest Hean Control Nv,"ber of Ilediv!n or Pathway Analysis Number o. 'ocations Sample Location 1) 1) Lo.at .;(') Nonroutine Re 'ed Sa .pled Uni t for Sites Sa...ples R suits 1'iean Ra~nce Distarce ard Direction I:Iean Range - Heanl pance 1) Yeas. ..ents Fish Herbivore pCi/kg Y Spectrm NA ) NiAil NA NA HA (0/6) pCi/kg Sr 06) NA HA NA NA -NA NA pCi/kg Sr 06) NA 'NA NA NA iIA 4.3 Turtle Grass Y Spectrun pCi/kg 95Z 230 110-490 T81-Card Sovnd 4oO 490 HA HA (5/6) (6 riles - S3 (1/1) pCi/kg Others NA ) NA iNA iHA NA (0/6) pCi/kg 89S 56) iIA nA NA NA IIA NA (0/5) pCi/kg 90S 56} NA HA NA NA NA NA

)

I (0/5)

TABLE 1 ENYIRONNEHTAL RADIOLOGICAL VONITORING PROGfQYi SUNDRY NANE OF FACILITY Turkey Poirt L'nits 3 and 4 DOCKET NO. 50-250,251 LOCA. >Op Oc FArILITY Dade County Florida REPORTING PFRIOD January 1, 1981-June 30, 19Bi Page 7 of 9 All Indicator Location Mi th Hi chest Mean Control Number of Viediuin or P'th:iay Analysis Nu".Der of Loca 'Ions Sample Locatior Location rted Sa,".pled Unit for Sites Samples Results Hean P~~lnge 0',stance and Direction Vean Range Heanl Range 1) Y.easure.".en 4.3 Sponges Y Spectrum pCi/kg 106Ru 450 410-520 T93-Pelican Bank 520 520 NA NA (2/e) (1.5 miles '- E} (1/1) pCi/kg 952. 6 230 90-510 T93-Pelican Bank 5i0 510 NA (3/e} (1.5 miles - E) (1/1) 144C pCi/kg 1100 1100 T94-Pumpkin Key 1100 1100 NA NA (1/e) (B miles - SSE) (1/1) pCi/kg 130 T95-Long Arsenicker 130 130 NA (i/e) (4 miles - SSE) (i/i) pCi/kg Others NAS) NA iN NA iNA NA NA (o/e)

Terrestrial Biota 5.2.1 Small Animal

'l Spectrum pCi/kg 137C 170 Road 170 170 NA NA (i/i) on site (i mile NA'5S-Entrance MSM) <</1) pCi/kg 0th rs NA NA NA NA NA (o/1) pCi/kg NA NA NA NA NA 89S'Sr (0/1) pCi/kg NA NA NA HA (o/1)

TABL"= 1 ENVIRONI',-NTAL RADIOLOGICAL NONITOR;NG PROGRAM SUt'JURY HA.'I"" Or" FACILITY Turkey Point Linits 3 and 4 DOC'(:"T No, 50-250,251 LOCATION OF FACILITY Dade County Florida REPORTING PFRIOD January 1, 1981 -June 30, 1981 Page 8 of 9 All !rdicator Location with Richest hfean Contr ol Nu-.her i h1ediur.: or Pathway Analysis Hur:,her of Locations Sa,",pie Location 1 1) Location rout'ort<

Sa:::p) ed Uni t for Sites Sar,'pl es Resuits Hean ange Distance and Direction hlean Range 'ean ) Range measure."::

5.2.2 Food Crops 32) pCi/kg Y Spectrw 3 HA NA NA NA (o/3) pCi/kg Sr 26) NA NA NA NA NA (o/2) pCi/kg 90Sr 26) NA NA NA NA (0/2}

5,2,3 Nangrove Leaves Y Spectru~

pCi/kg Zr 740 120-1680 T51-Homestead 1680 1680 NA (7/7) Bayfront Pa. k (1/1)

(2 niles - iN) pCi/kg 106R 520 400-640 T51-Ho...estead Bayfront 640 640 NA (2/7) Park (2 niles -.N) (1/1) ip Q 0";ners NA NA NA iNA (o/7)

I ipCi/kg "Sr 36) NA NA NA NA (o/3}

pCi/kg Sr 36) . NA NA NA NA NA itA (0/3)

TAGLE 1 ENV I RONHEHTAL RADIOLOGICAL NON ITORI HG PROGPA~I SUViLQY NNIE OF FACILITY Turkey Point Units 3 and 4 DOCKET NO, 50 250 251 LOCATION OF FAC:LITY Dade County Florida REPORTIHG PERIOD January 1, 1981-June 30, 1981 Page 9 of 9 Al', Ind:cator Location vitn Richest Yean Control. Number of or Pathway Analysis Number of Locations Sample Location 1) Location Nonroutine Vanadium Sa-.,.pl ed Uni t for Sites Samples Results f'iean IJ Distance and Direction B~ted I) Nea~ment g~ ~ga 7

llean Range I',ean >j Range 5.3 Soil I

Y Spectrum 137C I PCi/kg 200 100-360 T57-Dolan's 'Farm 360 360 NA NA (6/7) (4 miles - hd) (1/1) pci/k Others HA NA NA NA NA (0/7) pCi/k 89Sr NA HA (0/7) pCi/kg 90Sr HA NA HA HA NA NA (0/7)

Table 1 Notes Note a) Blue Crab Note b) Mixed Species Note c) Jack Note d) Mullet; Note 1) Numbers in parentheses indicate the ratio of samples which yielded detectable results (e.g. No. of samples with detectible results) of samples analyzed 'o.

The mean and range are based upon detectable measurements only.

Note 2} Not including DOE Split Samples.

Note 3) Air iodine filters are analyzed by a weekly composite. Individual counts are made for each location if iodine is detected.

Note 4) Direct-" radiation results are based on the average net response of two TLD dosimeters. For this period 65 results are reported for 130 dosimeter readings.

Note 5) Excluding <OK and/or 226Ra which are naturally occurring isotopes.

Note 6) Hi ssing Data Sample Location/Date Reason for Hissin Data Ai r Par ti cul ate T58 1/7/81 Pump Failure Air Particulate T72 2/18/81 Particulate Filter Missing Air Particulate T56 4/8/81 Particulate Filter Missing Ail Particulate T56 4/22/81 Particulate Filter Missing Direct Radiation T57 3/0/81 Yandalism - TLD's Stolen

6) Continued I

a Sample Le<<<lee/Date Reasoe tel'ljaajeg paaa Precipitation 752 2/11/81 Insuf f i ci ent Preci pi tation Precipitation T57 2/ll/81 Insuff'icient Precipitation Precipitation T64 1/13/81 Insufficient Pr ecipitation Precipitation T72 2/ll/81 Insuf fi ci ent Precipitation Preci p1tati on T72 4/15/81 Insufficient Pr ecipitation Ground Hate r Wel 1 89S ,90Sr T87 5/8/81 Analyses Incomplete Ground Water Well - 89Sr,9oSr T88 5/8/81 Analyses Incomplete Grout>d Water Well 9Sr,90Sr T89 5/8/81 Analyses Incomplete Ground Water Hell - 89Sr,gosr T90 5/8/81 Analyses Incomplete Ground Water 'Hell 89Sr 90Sr T91 5/28/81 Analyses Incomplete Ground ilater Well 89Sr 90Sr T92 5/28/81 Analyses Incomplete Cooling Canal Sedimen't - 8~Sr,90Sr T84 4/2/Gl Analyses Incomplete Cooling Canal Sediment - 89Sr,90Sr T85 4/2/Gl Analyses Incomplete Crustacea - 89Sr,90Sr T59 3/27/81 Analyses Incomplete Crustacea - 89Sr,90Sr T66 3/27/81 'nalyses Incomplete Crustacea 89Sr,9"Sr T69 3/27/81 Analyses Incomplete Crustacea - 89Sr,90Sr T94 3/27/81 Analyses Incomplete .

Crustacea 89Sr,90Sr T95 3/27/81 Analyses Incomplete Crustacea -. 89Sr,90Sr T81 5/14/81 Analyses Incomplete Fish Carnivore - 89Sr,9"Sr T66 3/27/81 Analyses Incomplete Fish Carnivore - 89Sr,90Sr T94 1/28/81, Analyses Incomplete Fish Carnivore - 89Sr,90Sr T95 1/29/81 Analyses Incomplete Fish Carnivore - 8 Sr,'9 Sr T81 5/29/81 Analyses Incomplete Fish Carnivore - 89Sr,90Sr T84 5/20/81 Analyses Incomplete

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6) Continued I

Sainpl e Location/Date Reason for Iiissing Data Fish Herbivore - 9Sr,g Sr T59 2/25/81 Analyses Incompl ete Fish Herbivore - 89Sr,gDSr T66 2/25/81 Analyses Incomplete Fish Herbivore - 89Sr,9DSr T69 2/25/Gl Analyses Incomplete Fish Herbivore - 9Sr,9 Sr T94 2/25/81 Analyses Incomplete Fish Herbivore - 8 Sr,9DSr T95 2/25/81 Analyses Incomplete Fish Herbivore - 89Sr,gDSr T81 5/13/81 Analyses Incomplete Turtle Grass - 89Sr,9DSr T81 5/13/81 Analyses Incompl ete Food Crops - 89Sr,9DSr T55 2/25/81 Analyses Incompl ete Mangrove Leaves - 89Sr,gDSr T71 3/26/81 Analyses Incompl ete Mangrove Leaves - 89Sr,gDSr T72 3/26/81 Analyses Incenplete Mangrove Leaves - 89Sr,9DSr T51 4/2/81 Analyses Incomplete thangrove Leaves -'=89Sr,9GSr T86 5/13/81 Analyses Incomplete

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RADIOACTIVE EFFLUENT RELEASE DATA JANUARY 1981 THROUGH JUNE 1981 SUBIKTTED BY NUCLEAR CIIENXSTRY DHPARTIIENT TURKEY POINT PI.ANT FJ.ORIDA PONER & LXGIIT COIIPANY DISTIGBUTXON A J GOULD (3)

D. N. IIAASH J. K. HAYS J. L. DANEK E. R. LAPIHRRE R. I.. LOGSDON J. S. UADH R. J. I'RECIIETTE

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SEMIANNUAL REPORT OF RADIOACTIVE EFFLUENT RELEASES PTP UNITS 3 & 4 1/81 6/81 Introduction All liquid and airborne discharges to the environment during this reporting period were 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 mul'tichannel analyzer, or evaporated and analyzed for gross beta-gamma activity in a 2>r gas flow proportional counter.

The efficiency of the gas flow proportional counter is adjusted so that the act-ivity determined by gross beta-gamma analysis approximates the isotopic activities determined by gamma spectrum analysis'nd 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. Prequent 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 xelease data presented in Table 1, pages 1 thxough 7.

1. The reported values in Table 1, page 1, include in their. computation the quantity of radioactivity released from both the waste disposal syst: em 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 fox 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.

2. The reported values in Table 1, pages 2 and 3 are the total quantities of radioactivity for individual nuclides released from the waste dis-posal system and the secondary system together. The values in Table. 1, pages 4 and 5 axe for the waste disposal syst: em only and page 6 is for the secondary system only.

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1/81 6/81

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 ( ).

4'eekly and monthly composite samples for the waste disposal system were prepared to give px'oportional weight to each liquid release made during the designated period of accumulation. The composites.

were analyzed for gamma emitting 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 was determined by use of a 2p gas flow proportional counter. All con-centxations 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 lease one representative batch of liquid effluent from the waste disposal system was analyzed monthly for dissolved fission and acti-vation 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 total dissolved gases released.

If'ore 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 7. Dissolved gases, if any, from secondary system releases were determined from the samples of the individual releases." Isotopic concentrations were multiplied by the'olume released to determine the quantity of radiogas nuclides r'eleased.

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.

I 1/0 6/81

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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 activation gases, b) Removal of particulate material by filtration and subsequent gamma-spcctrum 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) Condensation of water vapor in a gas sample followed by analysis for tritium using liquid scintillation techniques.

All sporadic gas releases 'from the plant which were not accounted for by the above methods were conservatively estimated as curieq of Xe-133 equivalent by use of the plant vent process monitor recorder chart and the current cali-bration curve ior the monitor.

The maximum rated capacity for. the hogging jets and the maximum measured flow rate for the con'denser air ejectors, and an estimate of the rate of exhaust from the atmospheric dumps were used to conservatively estimate the airborne releases from the secondary system whenever applicable.

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

1. Calculation of total radioactiv'ity of noble gases, L-131, and partic-ulates is based upon detectable radionuclides only.

2. The applicablc 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 100%

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

1/81 6/81

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

~

Z i MPC.

< 10,000 m 3

sec

, where Q. = release i rate of . th nuclide, Ci/sec and MPC. = maximum permissible concentration of the i.th nuclide, Ci/m3 The release rate, Q., was determined by dividing the total activity i

released in Ci, for the .th nuclide (t, > 8d), during the calendar quarter by the .econds in the quarter.

MPC. values were obtained from 10CPR20, Appendix 8, 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 x 100%

?PC.

% of limit ~ 3 3

10,000 m / sec The maximum gaseous release rate for each month is listed in Table II, page 1, under Section A, Line 3, The applicable limit for maximum allowable release rate is 6.7 H+04 pCi/sec,. average over one hour ~

5. All, values reported in Table XI, 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 was not calculated for an isotope, it will be listed as ( ) .

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iNUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE YEAR 1981 "RADIOACTIVE EFFLUENT RELFASES" PORl ION OF THE'EtlIANNUAL OPERATING REPORT PAGE i.

Tf<BLl.: I Report of Radioactive Eff1 uents: Liquid

)

A. TOTAJ Radioactivit 8-7 Januar rebruarv Karen April , av June j I. Total Release mci l a.a2 E+oa 6..21 E+oo 2.72 E-:oa I 2.10 Ewa 1.85 E+ol I 1.32 E+01 (

Z. Av Concentration Durin Releases uCi/mi I 4.2 E-11 I 2.9 E-11 1.8 E-10 1.9 E-10 [ 9.3 E-11 7.6 E

3. Av Concentration for tionth uCi/ml 3 7 E-11 I 2 3 E-11 I 1 6 E-10 ( 1.3 E-10 8.4 E-11 [ 7.4 E-11 ~

4; Yiax Concentration Released (uCi/ml 6.8 E-1O 9.5 E-1O [ 4.O E-Og 1.3 E-08 [ 1.6 E-09 [ 1.8 8-09

5. Percent of Technical Specification Limit for Total Activit Released (/,) I 8.9 E-01 1.1 E+00 Tr1 t 1 um

, Total Release ci 1 2.80 E+01 I 2.91 E+01 3.52 2+01 I 5.29 E+ol 2.92 E+01 I 2.12 F+01 RR~'RC, t. i Il i" 1 Cii 1.2 E-

3. Av Concentration for Nonth uCi/ml I 9.2 E-08 1.1 E-07 2.1 E-07 I 3.2 E-07 1.3 E-07 1.2 E-07

)

C. Dissolved Noble Gas

l. Total Reiease mlC1 ( 2.59 E+01 I 5.83 E+pl 2.51 E+01 1.37 Ewa 3.39 F+00 I . 8 +

2. Avo concentration Durin Releas s uci/aai 9.6 E-11. I 2.8 E-10 1.7 E-10 1.2 E-10 I 1.7 8-1 6.8~F.

3, Avq Concentration for Month uC'i/m1 8.5 E-ll 2.2 E-10 1.5 E-10 8.3 E-ll  ! 1.5 E-ll 6.6 E-12 Gross Al ha Radioactivity I. Total Release mC1 l(<6.5 E-09) l(<9.0 E-09) i(<8.0 E-og) (<6.6 E pg) <1.6 E p8 Z. AV COllCentrat10i1 Durin ReleaSeS uC1/ml ) )(<2.4 E-20) )(<4.2 E-20) I(<5.3 E-20) l(<5.9 E-.20) (<8.P E-20) <2.6 E-20

~3. II C uCi/ril (<2 1 E-20) '(<3.4 E-20)

~ (<4.8 E-20) '(<4.0 E-2p) t(< 7.3 E 20) lE Volumes

l. Vol of Li uid Haste to Dischar e (Liters I 2 ~ 85 1.16 E' 2.

3.

vol of Dilution Y 1 'it liater Durin ti Iht f !l" I0 Rel Liters 2.69 E+11.

3 1 2.12 E+11

. +.

L~sl w+

L~L.

I . + 9 E-

.73 E+la VOTE:. Numbers in parenthesis represent maximum sensitivity in liCi/ml,-

NUCLEAR CHEHISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE YEAR 1981 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPOPT -.. PAGE 2 TABLE I Report of Radioactive Effluents: Liquid - Tota1 triarch Isoto e Unit Januarv Februar Aoril lpga June Ag-llom (<4.1 E-08) (<3. 1 E- OS) (<4 ~ 9 E-08) 1.11 E-0< 2.07 E-02 2.38 E-02 Ea-140 (<8.6 E-08) (<8.2 E-08) (<1.1 E-07) (<3.2 E-07) (<2 ' E-07) (<2.8 E-07)

Ce-144 mCi (<1.3 E-07) (<<-.2 F 07) (<1.4 E-07) (<1.6 E-07) 1.52 E-Ol (<2.2 E-07)

Co-57 mCi (<1.6 E-08) (<1. 6 E-OS) (<1.7 "-08) (<2.1 -08) 3.62 E-03 (<2.8 E-<

Co-58 mCi 1.09 E&0 1.31 E-Ol 4.8O EWO 2.49 E+00 5.44 E-Ol 6;92, E-01 Co-60 mCi 7.6'+00 2.34 E+00 7.53 EWO 4.48 E+30 6. 2 F+00 2.71 E+00 Cr-51 mCi (<1.7 E-07 (<1,7 E-07) 9.13 E-01 1.58 EWO 9.35 E-02 (<4.1 E-07)

Cs-134 mCi 6.44 E-01 8.03 E-01 4.84 E+00 2.69 EWO 5.48 E-ol 8.78 F.-pl Cs-137 mCi 1.19 E.oo 1.37 E".00 6.60 E+00 3.28 E+00 9.29 E-01 1.0 E+00 F-18 mCi 5.7 E-Ol 3.70 E+00 3.29 FWO 1-131 mCi 5.34 E-01 1.04 E+00 1.29 E+00 2.11 E+00 1. 14 EWO 3 ~ 06 E-01 1-132 m<Ci 8 i E-02 873 Eol 8.65 E C T~133 4.09 E-Ol 3.90 E-01 1.78 E+00 2.63 E+00 2.48 E+00 1-134 2.53 E-Ol 1.53 E-Ol mCi mCi 7.08 E-01 1.00 E-01 La-140 (<1.2 E-OS) (<6.0 E-09) <1.2 E-08) (<3.9 E-06) (<4.3 E-07) (<3.0 E-07 mCi i~in-54 1.75 E-01 (<2.4 E-08) 1.36 E-Ol 6.39 E-02 4.79 E-02 4.5 E-02 mCi Xia-24 mCi 1.11 E-Ol 1.07 E+00 4.41 E-01 3.99 E-01 NOTE: Numbers in parenthesis represent maximum sensi privity in q<Ciiml.

NUCLEAR CHFNISTRY PROCEDURE NC-3 PREPAPATION OF THE HONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE YEAR 1981 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT PKGE . 3 1'ABLE I Report of Radioactive Effluents: Liquid - Total Isotope Unit Januar Feb ruar ~

Narch A ril ~mfa h"o-95 mCi (<2.3 E-08) (<1.9 E-08) ,1.77 E-01 3.87 E-01 9 . 76 E-02 5 '4 E-02 Ru-103 mCi (<2.2 E-08) (<2.1 E-08) 4.01 E-02 (<4.7 E-08) (<6.5 E-08) (<5.7 E-0 Sb-124 (<2.2 E-08) (<1.5 '-08) 1.69 E-01 (<3; 8 E-08) 1.37 E-02 4.08 E-02 sb-125 mCi (<6.7 E-08) (<6.6 E-08) 8.41 E-02 (<9.9 E-08) 3.02 E-02 5.04 E-Sr-89 mCi 4.7 E-03 3.29 E-03 9.98 E-02 7.28 E-02 9.1 E-03 1. 16 E-02 Sr-90 mCi 7.1 E-03 3.99 E-03 4.77 E-03 (<2.9 E-09) -

(<3.2 E-09) (<2.6 E-09)

Zr-95 mCi (<3.8 E-08) (<3.3 E-08 8.24 E-02 2.55 E-01 4.98 E-02 3.62 E-02 Total mGi 6.21 E+00 2. 72 E&1 2. 10 E+Ol 1.85 1.12 E+Ol E+Ol 1.32 E+Ol NOTE: Numbers in parenthesis represent maximum sensitivity in pCi/ml,

NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF THE YiONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE YEAR 1981 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEHIANNUAL OPERATING REPORT PAGE TABLE I Report of Radioactive Eff1uents: Liquid - Maste Disposa1 System Isoto e Unit Januar Februar March April ianna June Ag-llpm mCi (<4.1 E-08 (<3.1 E-08) (<4.9 E P8) .1.11 E-Ol 2.07 E-02 2.38 E-02 Sa-140 mCi (<8.6 E-08) (<8.2 E 08) (<1.1 E-07) <3. 2 E-07 (<2.9 E-07) (<2.8 E-07)

Ce-144 mCi

(<1.3 E-07) (<1.2 E-07) (<1.4 E-07) <1.6 E-07 1.52 E-Ol (<2.2 E-07)

Co-57 (<1 6 E P8) (<1.6 E-08) (<1.7 E-08) (<2.1 E-08) 3.62 E-03 (<2. 8 i)

Co-58 mCi 9.12 E-01 1.31 E-01 4.10 E+00 2.33 E&0 5.44 E-01 6.92 E-01 Co-60 mCi 1.88 E+00 5.77 E-Ol 4.57 E+00 3.14 EWO 9.82 E-Ol 1.71 E+00 Cr-51 mCi (<1.7 E-07) 9.13 E-Ol 1.58 EWO 9.35 E-02. <4.1 E-07 Cs-134 mCi 4.17 E-01 4.42 E-01 l. 87 E-01 1.02 E-Ol 3.34 E-01 Cs-137 mCi 7.91 E-01 4.7 F,- 8.58 E-pl-. 2.86 E-Ol 1.79 E-01 7.94 E-Ol T-131 mCi 1.59 E-01 <2.2 F.-08 3.51 E-Ol <9.9 E-08 (<5.2 E-08 (<6.8 E-08)

La-140 mCi (<1.2 E-08) <6 P F P9 (<1.2 E-08) (<3.9 E-06) (<4.3 E-07) (<3.0 E-07) mCi i'-54 9.35 E-02 (<2.4 E-08) 1.36 E-01 6.39 E-02 4.79 E-02 4.5

'.14 mCi (<2.3 E-08) (<1.9 E-08 1.77 E-pl 3.87 E-01 9. 76 E-02 E-02

%)-95 H,u-103 mCi (<2. 2 E-08) (<2, 1 E-08) 4.01 E-02 (<4.7 E-08) (<6. 5 E-08) (<S.7 E-(

mCi (<2,2 F.-08) (<1.5 E-08) 1.69 E-Ol (<3.8 E-08) 1.37 E-02 4 08 E-02 Sb-124 ~

Sb-125 mCi (<6.7 E-08) (<6.6 E-08) 8.41 E-02 (<9.9 E-08) 3.02 E-02 5.04 E-02 mCi 4,7 E-03 3.29 E-03 9.98 E-02 7.28 E-02 9. 1 E-03 1.16 E-02 Sr-89 mCi 7.1 E-03 3.99 E-03 (<2.9 E-09) (<3.2 E-09) (<2.6 E-09)

Sr-90 4.77 E-03 NOTE: Numbers in parenthesis represent ma>.imum sensitivity in pCi/m'f.

NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE YEAR 1981 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SENIANNUAL OPERATING REPORT - . PAGE 5 TABLE I Report of Radioactive Eff1uents: Liquid .- Waste Disposal System Isotope Unit Januar February Aoril Zr-95 (<3.8 E-08 <3.3 F~8 8.24 E- 4.98 '-02 Tol:al mCi 4. 26 EW0 1. 51 E+00 1 ~ 20 EW 8.41 E+00 2. 33 EWO 3~79 .+0~

NOTEl Numbers in parenthesis represent maximum sensitivity in pCi/ml.

NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF THE YiONTHLY "PRELIMINARY REPORT ON RADIOACTIYE RELEASES" AND THE YEAR 1981 "RADIOACTIYE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT TABLE I Report of Radioactive Eff1uents: Liquid - Secondary System Isotope Januarv Februar March Aoril Mav June Co-58 mCi 1.75 E-01 7.01'-Ol 1.60 E-01 Co-60 mCi 5.7 E+00 1.76 E+00 2.96 E+00 1.34 E+00 5.2 E+00 l. 00 EW Cs-134. mCi 2.27 E-Ol 4.87 E-01 4.40 EWO 2.50 E+00 4.46 E-01 5.44 E-01 Cs-137 mCi 3.96 E-01 8.95 E-Ol 5. 74 E+00 2.99 E,OO. 7.50 E-01 2.98 E- ~

F- 18 5.7 E-Ol 3.70 EWO 3'. 29 EWO I- 131 mCi 3. 75 E-01 1.04 E+00 9. 39 E-01 .2.11 E+00 1.14 E+00 3.06 E-01 I- 132 mCi 8.1 E-02 8.73 E-Ol 8.65 E-01 I- 133 mCi 4.09 E-Ol 3.90 E-01 1.78 E+00 2.63 E+00 2.48 E+00 I- 134 mCi 2.53 E-01 l. 53 E-01 1..3,35: mCi 7.08 E-01 1.00 E-01 j I

Mn-54 mCi 8.1 E-02 mCi 1.11 E-01 1.07 E+00 4.41 E-Ol 3.99 E Na-24 Total mCi 7.0 E+00 4. 70 E+00 '.51 E+01 1.26 E+01 1.61 E+01 9.44 E+OO j NOTE: Numbers in parenthesis represent maximum sensi".ivity in qCi/mi.

~ ~

NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE ,A YEAR 1981 'ADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT PAGE. i TABLE I Report of Radioactive Effluenis: Liquid - Dissolved Gas Total Januarv Februarv Harch Anril June Kr-85 mCi 2.05 E+01 9.40 H :00 1. 79 EW1 7.8 E+00 (<6.0 E-06) (<4.3 E-06'<5.2 Xe- 131m mCi (<1.2 E-06) (<1.3 E-06) (<1.3 E-06) (<1.3 H-06) (<5 3

~ E-07) E-07)

Xe-133- mCi 5. 39 E+00 4.85 H<l 7.15 E.OO 5.85 E+00 3.39 EWO 1.06 E+00 Xe-133m mCi (<2. 6 E-07) (<2. 8 E-07) (<2.8 E-07) (<2.8 E-07) (<1.2 E-07) (<1.2 E-Oj Xe-135 mC) (<2. 9 E-08) 3.92 E-01 (<3.0 H-08) (<3.0 E-08) (<1. 7 E-08), 1.16 E-Ol mCi 2.59 E+01 5.83 E+01 2.51 EW1 1.37 H%1 3.39 E+00 1.18 E+00 Was' isnosal System Kr-85 mCl 2.'05 . EWl 9.40 E+00 1.79 E+01 7.8 E".OO (<6.0 E-06) (<4.3 E-06)

Xe-131 m mCi (<1.2 E-06) (<1.3 E-06) <1.3 E-06) <1.3 H-06 <5. 3 E-07 <5.2 E-07 Xe-133 mCl 5. 39 E+00 4.85 EOOl 7.15 E+00 5.85 E+00 3.39 E+00 1.06 E+00 Xe-133m mCi (<2.6 E-07) (<2.8 -E-07) (<2.8 H-07) (<2 ' E-07) (<1.2 E-07) (<1. 2 E-07)

Xe-135 mCi (<2.9 E-08) . 3.92 H-Ol (<3.0 E-08) (<3.0 H-08) (<1 ~ 7 E-08) 1.16 E-Ol Secondary Svstem Kr-85 mCi Xe-131 m mCi Xe-133 mCi Xe-133m mCl Xe-135 mCi NOTE: Numbers in parenthesis represent maximum sensitivity in pCi/ml.

NUCLEAR CHEMISTRY PROCEDURE NC-3 OF THE NONTHLY "PRELIitINARY REPORT ON RADIOACTIVE RELEASES" AND. THE

'REPARATION 0 ~

YEAR 1981 "RADIOACTIVE EFFLUENT RELEASES" PORTIOf) OF THE SEMIANNUAL OPERATING REPORT PAGE 3 TABLE II Report of Radioactive Effluents: Airborne A. Fission and Activation Gases Jailllarv Februarv H v une

1. Total Release (ci) 3.21 E+02 3.08 E+02 2.11 E+02 2.97 E&2 2.78 E+02 Z. Av Release Rate for Period uCi/sec 2.3 EW2 1.3 EW2 1.0 E+02 8.8 E+01 9.9 E&1

• 3. Max Release Rate for Period pCi/sec 53 E&3 21 2. 3 E+04 6. 6 E+02 1.6 E&2 2. 7 E+02

"'Haximum airborne release rate'veraged over one hour =or each month. Techn'.cal Specifications limit is 6,7 E+O4 'sec averaged over one hour.

8=. Iodine 131

1. Total Iodine - 131 Ci 5.9 E-04 2.7 E-04 1.5 E-02 5.5 E-04 3.5 E-04 8.3 E-05 Z. Av Release Rate =or Period uCi/sec 2.5 E-04. 1.1 E-04 5.0 E-03 2.3 E-04 1.2 E-04 3.5 E-05 C. Particulates

1. Particulates (Wieh t:1/2>81) Ci 1.36 E-04 2.11 E-05 2.04 E-'4 3.37 E-05 3.57 E-05 3.86 E-05

2. Av Release Rate for Period uCi/sec 5.7 E-05 8.8 E-06 6.8 E-05 1.4 E-05 1.2 E-05 .1.6 E-05

3. Gross Al ha Radioactivit .

Ci 1.8 E-08 2.3 E-09 1.5 E-08 8.9 E-10 2.3 E-09 1.3 08 D. Tritium

1. Total R'elease Ci 2.78 E-02 1.01 E-Ol 1.26 E-01 5 . 64 E-02 1. 06 E-01

2. Av Release Rate for Period uCi/sec 1.2 E-02 4.2 E-02 4.2 E-02 2. 4 E-02 3.5 E-02 3.3 E 2 E. Percent of A plicable Limit 0 r rI Activation 1.3 E+00 8.3 E-01

1. Fission and Gases 2,0 E-Ol 1.2 E-02 Z. I-131 and Part tl/2>ad N TE:

NUCLEAR CHB)ISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY "PRELIHINARY REPORT ON RADIOACTIVE RELEASES" AND THE YEAR 1981 RADIOACTIVE EFFLUENT RELEASES'ORTION OF THE SEMIANNUAL OPERATING REPORT PAGE ~ I TABLE II Airborne Releases - Particulates Isoto e Unit Februar March A ril June Sa-140 . Ci (<l. 0 E-13) (<5.2 E-14) (< l. 5 E-13) (<1.9 E-13) (<2.1. E-13) (<1'.8'-1'3J Co-58 Co-60 Ci Ci 9.4

l. 0 E-06 E-04 1.1 4.9 E-06 E-06 5.0 9.9 E-05 E-05 1.3 8.3 E-05 E-06

'fay9.0 1.6 E-06 E-05

3. 7 2.9 F,-06 E-05 Cr-51 Ci (<1.6 E-13) ( 9.7 E-14)* 3.8 E-05 (<3. 0 E-13) 2.4 E-06 (<2. 7 E-J.

Cs-134 .Ci 5,3 E-06 9.2 E-07 1.4 E-06 3.1 E-06, (<7.3 E-14) 3.8 E-07 Cs-137 Ci 1.3 E-05 1.0 E-05 7.0 E-06 4.6 E-06 3.9 E-06 4.7 E-06 T.-131 .Ci 2.5 E-06 (<l. 2 E-14) 4. 1 E-06 (<4.1 E-14) (<4. 8 E-14) (<3.1 E-14)

La-140 Ci (<1. 5 E-14) (<1.3 E-14) (<5.4 E-14) (<1.1 E-13) (<1.5 E-13) (<6.6 E-14)

Hn-54 .Ci 3.5 E-06 (<1.7 E-14) (<4. 3 E-14) 1.5 E-06 4.0 E-07 3.4 E-07 Hb-95 (<4.5 E-14) (<2.7 E-14) 2.6 E-06 2.2 E-06 3.2 E-06 (<5.5 E-14)

Ru-103 Ci (<2. 8 E-14) (<1.4 E-14) (<3.9 E-14) (<5.0 E-14) 2.6 E-07 (<3.5 E-14)

Sb-125 .Ci 1.3 E-06 (<3.3 E-14) (<9.1 E-14) (<1.1 E-13) (<1.4 E-13) (<x.o z-0 Sr-89 Ci 1- 2 E-06 4.1 E-06 1.5 E-06 9.3 E-07 5.2 E-oj 4.2 E-07 Sr-90 3.8 E-08 3.8 E-08 1.4 E-07 4.7 E-08 5.2 E-08 5.8 E-08 Total , Ci 1.36 E-04 2.11. E-05 2.04 E-04 3.37 E-05 3.57 E-05 3.86 E-05 NOTE: Numbers in parenthesis represent maximum sensitivity in uCi/ml.

NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND .THE 1981 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT PAGE 3 YEAR TABLE II Airborne Releases - Gaseous Fission and Act iYat ion Gases Isotove Unit January Fe'oruary ~ilarcn April iNay June Ar-'l Ci 7.35 E-01 6.97 E+00 5 ~ 96 E-Ol 2. 5 E-01 3.07 E-01 3.07 E-02 Kr-85 Ci 4.01 E-01 7.65 E-Ol 3.31 E-01 1.55 E-01 , 1.52 E-01 5. 70 E-01 Kr-85r> Ci 2.33 E-02 6 .0 E-02 1. 30 E-02 1.5 E-02 8. 56 E-03 1.5O E-Kr-87 ( <3,. 5 E-06) (<1. 5 E-O5); (<1. 8 E-06) (<3.5 E-06) (<2.9 E-06) (<8.9 E-07) 8.8 E-05 (<7 ' E-06) E-05 (<3.1 E-06) (<3.3 E-06) (<9. 1 E-07)

Kr-88 Ci (

Xe-131n Ci 1.98 E-ol .1.34 E-01 1.79 E-01 1 07 E+00

~ 3 '2 E-01 6.06 E-01 Xe-133 Ci 5 . 60 E+02 3. 11 E+02 3.05 EWZ 2.09 E+02 2 '5 E+02 2.76 E+02 Xe- Ci 4. 75 E-01 9.10 E-01 1. 21 . EWO 3. 23 E-01 3.32 E-01 3.64 E-01 133'e-135 Ci 6.82 E-OL 8.52 E-01 '6.31 E-Ol 2.02 E-01 2.71 E-01 3.07 E-01 Xe- 135m Ci 9.52 E-02 (<3.4 E-05) (<4.9 E-O6) (<2.4 E-05) (<3.4 E-O6) (<3.4 E-06)

Xe-138 <1. 7 E-O6) (<4.8 E-05) (<1. 2 E-05 (<5. 8 E-05) (<5.8 E-06) (<7. 1 E-Tot a 1 Ci 5.63 E+02 3 '1 E+02 3.08 E+02 2.11 E+02 2.97 E02 2.78 E+02 Halo ens Gaseous Isoto e Unit January February March April ifay June I- 131 Ci 5.9 E-O4 E-O4 1. 5 -E-02 5.5 E-04 3.5 E-04 8.3 E-05 I-133 Ci 4.9 E-04 7.3 E-04 3.4 E-03 2.6 E-o4 5. 2 E-04 2.4 E-04 I-135 Ci (<8. 4 E-14) (<1,3 E-13) (<l. 3 E-13) 2.2 E-O4 3.7 E-05 5.0 E-06 Br-82 (<3.4 E-14) 4.6 E-04 4.1 E-05 1.7 E-05 3. 5 E-04 1.7 E-04 Total Ci 1.08 E-03 1.46 E-03 1.8 E-02 1.05 E-03 l. 26 E-03 5.0 E-04 Note: uiil ers l n parent esl s represent j 111axlBuli1 sens'1tl Ylt 1 n pCi/111

TVRKHY POINT PI>ANT RADIOACTIV].'.'ASIE R]il'ORT

.JAN 1, 1981 to JUNP. 30, 1981 Date of Shi ment Curies Cu. PL. ~D3.8 OSItI.Oll 1-OGI-81 0.214 852 Buried in Barnwell, SC 1-14-81 0.612 II

]100 1-20-81 0 242

~ 550 1-29-81 ]2.2 85 2-10-81 0.423 1100 2-24-81 0,314 1100 3-17-81 0.482 1100 3-24-81 1.61 170 3-26-81 3.219 170 4-17-81 6.71 85 4-20-81 0 '557 1050 4-23-81 4.27 85 4-27-81 10.8 ]50 5-OG-81 0.0507 1050 5-19-81 10 ' 150 5-19-8 ] F 7 150 5-30-8 1 1.93 170 6-03-81 7.93 85 6-11-81 9. 15)0 85 6-15-81  ?.29 100 6-17-81 0 2445 1050 6-21-81 2.092 170 6-22-81 0.00]74 562.5 Buried in Richland, Washington 6-22-81 0.00254 555 6-22-81 0. 00164 570 6-23-81 0.00086 555 6-23-81 0.00137 562.5 6-23-81 0.000855 555 6-23-81 0 563 170 Buried in Barbell, SC 6-24-81 0.00099 555 Buried in Richland, ]lashington 6-24-8 1 0.00092 532 '

G-25-81 0.00095 1 532 '

6-25-81 0.008835 525 Buried in Barbell, SC 33 Shipments 78.2226 Ci. 16,282 Cu. Pt.

On site as of July 1, 1981:

13 '95 'i. 2,965

W r ')