L-81-375, Environ Radiological Monitoring Program Summary for Jan-June 1981
| 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 XRZCVmicOrr 5
FLORIDAPOWER 8( LIGHTCOMPANY August 28, 1981/.+c~
L-81-375 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:
2 5,5
~
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
7 J
4 F
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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.
INl'RODUCTI 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
~
which yielded detectable results is also provided.
a I
~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 g r>.
detection of
~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 II, 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:llTALRADIOLOGICAL MONITORING PROGRAM SUQMRY NA.'iE OF FACILITY Turkey Poin. Units 3 and 4
LOCATION OF FACILITY Dade County F)or'.&
DOCKET NO. 50-250,251 REPORTiiNG PERIOD January 1, 1981 -June 30, 1981 Page 1 of 9 Vedium or Pathway Sanipled Unit Analysis for Number of Sites Samples Results Location with Hichest Nean
's,'si A'.1 Indicator Locations Sample Location ance an Dire t Vean ange Ois t c ion f~eanl Range Control Location Number of Nonroutire Repaid Neasu~ts 1.1 Air Particulate Air Iodine pCi/1 Gross 8
PCi/1 '"I 8
~
199 8
196 26 196 25')
0.232
{196/196)
NA (0/199)
,053-.471 NA T58-Entrance Road on Site (1 mile-VSM) s 0.245 (24/24 NA NA NA
.054-0.238 0.417 (25/25) 0.060-0.458 1.2 Direct Radiation 1.3 Precipitation uRem/
hr pCi/1 Gross S-DJ Gross 8-UO 11 130 196) 130
)
65 results 19 19 5.2 2.1-7. 5 (130/130 13.1
- 3. 3-38.1 (16/19) 8.5 1 7.0-17.0 (10/19)
T64-Nato...a Substation (22 miles-N) Control Sample location T64-Natoma Svbstat':on (22 miles - N) Control Sample location T72-Boy Scout Camp (0.5 miles - SM) 6.4 12/12
',9,2 (5/5) 17.0 (1/4) 5.4-7.5 10.4-38.1 17.0-17.0 6.4 (12/12) 19.2 (5/5) 7.8 (3/5) 5,4-7.5 10.4-38.1 5.5-12.0 sY Scan s
'H 19 19 NA (0/19)
NA (0/ 9)
NA NA NA NA NA NA sNA IsA NA YA
.; DS - Dissolved Solids i UOS - Undissolved Solids INA - No Applicable s
TAGL=
1 ENVIRONHENTA'AD'.OLOGICALHONITORIHG Nnl/E OF FACILITY Turkey Poirt Units 3 ard 4 LOCATION OF FACILITY Dade County Florida PROGRAM i SUEtARY DOCKET NO. 50-250,251 REPORTING PERIOD January 1,
1981-June 30, 1981 Page 2 of 9 Viediura or Pathway Sar,:pled Uni~
Analysis for Hu~ber of Sites Sa;..ples Results r) ilean
,a~nge All inoicator Locations Control Location Sacple Location Distance and Directior.
Range Heanl Range ftean Locat on with Hichest Viean Hu.",ber of Nonroutine Re~'.ed Heas~;;en ts 2.1 Surface Hater 2.1.1 Estuarine pCi/1 pCi/1 pCi/1 pCi/1 Y Spectru~
H 89Sr "s.-
~IO 20 20 20 20.
20 NA )
(0/20) iiA (0/20)
NA (0/20)
NA (0/20)
NA SA NA NA NA HA NA
.NA NA NA NA NA NA HA NA HA iHA 2.1.2 Cooling Canal Sys m
, PC'/1 I pCi/1 i
I pCi/1 I
I
-,'pCi/1 Y Spectrun H
89S.
"Sr 122) 12 12 12 iiA )
(0/12)
~ 4200 (12/12)
NA.
(0/12)
NA (0/12) 3100-5600 NA NA iiA T-84-Cooling Canal South of Bridge (0 niles - SS~)
NA HA HA 4200 (6/6) iiA 3600-5500 NA i>n HA NA i'n HA
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 Hedivm or Pathway Samol ed Unit Analysis for Sites Number of Samples Results Location with Hionest Vean All Indicator Locations 1
1) tlean Range S mple Location V.ean Plunge Distance ard Direction Heanl Range 1)
Control Location Nv",her of Nonroutine Repo~
Neasur~ts 2.1.3 Fresh Mater Drainage Canal 2.2 Potable Mell Mater pCi/1 H
pCi/1 Gross 8-DS pCi/1 Gross 8 UDS pCi/1 H
pCi/1 Gross 9-DS
~
t pCi/1
'Gross 8 UDS 12 12 12 12 440 (4/12) 164 (11/12) 6.4 (1/12)
(0/6) 9.7 (5/6)
(0/6) 340-600 3.0-370 6.4-6.4 NA 4.7-14.0 NA T75-Fla. City Canal at Old Salinity Dam (1 mile MNH)
T75-Fla City Canal at Old Salinity Dam (1 raile MP)
T75-Fla City Canal at Old Sa'linity Dam (1 mile MNM)
NA T57-Dolan's from (4 miles NM)
NA 440 340-60 (4/6) 300 (6/6) 6.4 (1/6) 230-373 6A-6.)
NA NA 12.5 11.0-(2/2) 14.0 NA NA NA NA 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 t.;ediu;! or eoathwiiy Sar,:oled Unit Analysis
'ol Number of Sites Samples Res its Location with Hichest Mean 1
1)
Nean Range Y'ean l
/ange Distarce ard Direction 11 Indicator Locations Sa. pie Location Control Location
'ean Range I
1}
Number of Nor~tine Rated Neasure...ents 2.3 Ground Mater Miel1 s Sedieert
- 3. 1 Cooling Canal Sediment pCi/1 Y Spectrum pCi/1 H
pCi/1
~
Sr pCi/1 Sr 6.
12 12 12 ee) ee)
NA )
(0/12) 960 (7/12)
HA (o/6)
HA (o/6}
330-2800 NA T92-Mell 624A (4 miles - SSN)
NA e
NA NA HA NA NA 1910 1012-(2/2) 2800 NA NA HA NA HA HA I,'Ci/kg I
I pCi/kg I
- pCi/kg t
'Ci/kgt pCi/kg Y Spec rum "Co "Zr Others "Sr.
90Sr 4
ze) ze) 880 (4/4}
120 (2/4)
NA }
(0/4)
NA-(0/2}
(o/z) 230-1620 70-180 NA NA NA T85 - Cooling Canal Vest of 90o bend (0 niiles - SW) 7 Cooling Canal l est of 90 Bend (0 miles - SH}
NA NA
,NA 180 (1/2)
NA 180 HA NA NA it'A 920 230-(z/2) lezo iiA NA NA NA NA NA
,NA NA NA
TA8LE 1
ENYI RONNiENTAL RADIOLOGICAL HONITORIHG NAtiE OF FACILITY Turkey Point Units 3 and 4 LOCAT'0 i OF FACILITY Dade County Florida PROGRAM SM'JURY DOCKET tto. 50-250,251 REPORTING PERIOD Jaruary 1,
1981-June 30, 1981 Page 5'f 9 9
tieriivn or Path.ray Sai",.pl ed Unit Analysis for Nu".,:her of Si tes Sar.:pl es Results Rage t!ean at All Indicator Loi q+Co~s Location with Hiahest ttean Sa;..pie Location Distance and Drection t tean 1}
Range Control Location Yieani~~
Rance 1) er o
Quti Reporte tteasurer.
~
3,2 Estuarine Sedi,".,ent Aauatic 8iota 4.1 Crustaceaa) pCi/kg pCi/kg pCi/kg Y Spectrum Sr 9Os NA )
(0/7) tiA (0/7)
HA (o/7)
~ NA HA ttA HA ii'A HA itA NA NA NA 1
NA pCi/kg pCi/kg pCi/kg Y Spectrum 89Sr "Sr 06) 06)
(o/6)
KA NtA NA NA iNA NA NA HA NA NA LNA NA nA NA iNA iNA 4.2 Fish (Carnivore) pCi/kg pCi/kg pCi/kg Y Spectrum 89S
'OSr 72}
26) 26)
NA )
(0/7}
'tA
- (0/2) iNA (o/2)
~NA NA NA NA HA NA hA NA NA NA HA
TAGLE 1
EHYIRONNEHTAL RADIOLOGICAL HONITORING HAtIE OF FACILITY Tvrkey Point Units 3 and 4 LOCATION OF FACILITY Dade County Florida PRGGSB SUiI.'VRY DOCKET IiO. 50-250,251 REPOPTIHG PERIOD January 1, 1981-June 30, 1981 Page 6 of 9 Ilediv!n or Pathway Sa.pled Unit Analysis for Number o.
Sites Sa...ples R suits 1'iean Ra~nce
>.i All Indicator
'ocations Sample Location Distarce ard Direction 1) 1)
I:Iean Range Location,i',th Richest Hean
- Heanl pance 1)
Control Lo.at.;(')
Nv,"ber of Nonroutine Re
'ed Yeas.
..ents Fish Herbivore pCi/kg pCi/kg pCi/kg Y Spectrm Sr Sr 06) 06)
NA )
(0/6)
NA NA NiAil HA
'NA NA NA NA NA NA NA NA HA
-NA iIA 4.3 Turtle Grass pCi/kg Y Spectrun 95Z 230 (5/6) 110-490 T81-Card Sovnd (6 riles - S3 4oO (1/1) 490 HA HA pCi/kg pCi/kg
) pCi/kg I
Others 89S 90S 56) 56}
NA )
(0/6) iIA (0/5)
NA (0/5) nA HA NA NA NA NA NA iNA IIA iHA NA NA NA NA
TABLE 1 ENYIRONNEHTAL RADIOLOGICAL VONITORING NANE OF FACILITY Turkey Poirt L'nits 3 and 4
LOCA. >Op Oc FArILITY Dade County Florida PROGfQYi SUNDRY DOCKET NO. 50-250,251 REPORTING PFRIOD January 1,
1981-June 30, 19Bi Page 7 of 9 Viediuin or P'th:iay Sa,".pled Unit Analysis for Nu".Der of Sites Samples Results Location Mith Hichest Mean All Indicator Loca
'Ions Sample Locatior P~~lnge 0',stance and Direction Hean Vean Range Heanl Range 1)
Control Location Number of rted Y.easure.".en 4.3 Sponges Terrestrial Biota 5.2.1 Small Animal pCi/kg pCi/kg pCi/kg pCi/kg pCi/kg Y Spectrum 106Ru 952.
144C Others 6
450 (2/e) 230 (3/e}
1100 (1/e) 130 (i/e)
NAS)
(o/e) 410-520 90-510 1100 NA T93-Pelican Bank (1.5 miles '- E}
T93-Pelican Bank (1.5 miles - E)
T94-Pumpkin Key (B miles - SSE)
T95-Long Arsenicker (4 miles - SSE) iN 520 (1/1) 5i0 (1/1) 1100 (1/1) 130 (i/i)
NA 520 NA 510 1100 NA 130 iNA NA NA NA NA NA NA pCi/kg pCi/kg pCi/kg pCi/kg
'l Spectrum 137C 0th rs 89S'Sr 170 (i/i)
NA (o/1)
NA (0/1)
NA (o/1)
NA NA NA'5S-Entrance Road on site (i mile MSM)
NA NA NA 170
<</1)
NA 170 NA NA NA NA NA NA HA
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 h1ediur.: or Pathway Sa:::p) ed 5.2.2 Food Crops Unit Analysis for Sites Hur:,her of Sar,'pl es 32)
Resuits Hean ange All !rdicator Locations Sa,",pie Location Distance and Direction 1
1) hlean Range Location with Richest hfean Contr ol Location
'ean )
Range Nu-.her i
rout'ort<
measure."::
5,2,3 Nangrove Leaves pCi/kg 90Sr Y Spectru~
pCi/kg Zr pCi/kg ip Q
IipCi/kg 106R 0";ners "Sr pCi/kg Sr pCi/kg Y Spectrw pCi/kg Sr 3
26) 26) 36) 36)
HA (o/3)
NA (o/2)
NA (0/2}
740 (7/7) 520 (2/7)
NA (o/7)
NA (o/3}
NA (0/3)
NA 120-1680 400-640 NA NA NA T51-Homestead Bayfront Pa. k (2 niles - iN)
T51-Ho...estead Bayfront Park (2 niles -.N)
NA NA NA NA NA NA NA 640 (1/1)
NA 640 NA NA NA 1680 1680 (1/1)
NA NA NA NA NA iNA NA itA
TAGLE 1
ENVI RONHEHTAL RADIOLOGICAL NONITORIHG NNIE OF FACILITY Turkey Point Units 3 and 4
LOCATION OF FAC:LITY Dade County Florida PROGPA~I SUViLQY DOCKET NO, 50 250 251 REPORTIHG PERIOD January 1, 1981-June 30, 1981 Page 9 of 9 Vanadium or Pathway Sa-.,.pl ed Unit Analysis for Number of Sites Samples Results Location vitn Richest Yean Al', Ind:cator Locations 1) llean Range Sample Location f'iean g~ ~ga Distance and Direction IJ 7
Control.
Location I',ean
>j Range I)
Number of Nonroutine B~ted Nea~ment 5.3 Soil I
I PCi/kg pci/k pCi/k pCi/kg Y Spectrum 137C Others 89Sr 90Sr 200 (6/7)
HA (0/7)
NA (0/7)
HA (0/7) 100-360 NA NA T57-Dolan's 'Farm (4 miles - hd)
NA HA HA 360 (1/1)
HA 360 NA NA NA NA NA NA
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)
'o.
of samples analyzed 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)
Hissing Data Sample Location/Date Reason for Hissin Data Air Par ticul ate Air Particulate Air Particulate Ail Particulate T58 1/7/81 Pump Failure T72 2/18/81 Particulate Filter Missing T56 4/8/81 Particulate Filter Missing T56 4/22/81 Particulate Filter Missing Direct Radiation T57 3/0/81 Yandalism - TLD's Stolen
6)
Continued I
a Sample Precipitation Precipitation Precipitation Precipitation Le<<<lee/Date Reasoe tel'ljaajeg paaa 752 2/11/81 Insuffici ent Preci pitation T57 2/ll/81 Insuff'icient Precipitation T64 1/13/81 Insufficient Pr ecipitation T72 2/ll/81 Insuffici ent Precipitation Preci p1tati on T72 4/15/81 Insufficient Pr ecipitation Ground Hate r Wel 1 Ground Water Well Grout>d Water Well Ground Water Hell Ground Water 'Hell Ground ilater Well 89S
,90Sr
- 89Sr,9oSr 9Sr,90Sr
- 89Sr,gosr 89Sr 90Sr 89Sr 90Sr T87 5/8/81 T88 5/8/81 T89 5/8/81 T90 5/8/81 T91 5/28/81 T92 5/28/81 Analyses Incomplete Analyses Incomplete Analyses Incomplete Analyses Incomplete Analyses Incomplete 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 Crustacea
- 89Sr,90Sr Crustacea 89Sr,9"Sr Crustacea
- 89Sr,90Sr Crustacea 89Sr,90Sr Crustacea
-. 89Sr,90Sr T59 T66 T69 T94 T95 T81 3/27/81 3/27/81 3/27/81 3/27/81 3/27/81 5/14/81 Analyses
'nalyses Analyses Analyses Analyses Analyses Incomplete Incomplete Incomplete Incomplete Incomplete Incomplete Fish Carnivore - 89Sr,9"Sr Fish Carnivore - 89Sr,90Sr Fish Carnivore - 89Sr,90Sr Fish Carnivore - 8 Sr,'9 Sr Fish Carnivore - 89Sr,90Sr T66 3/27/81 Analyses Incomplete T94 1/28/81, Analyses Incomplete T95 1/29/81 Analyses Incomplete T81 5/29/81 Analyses Incomplete T84 5/20/81
" Analyses Incomplete
~ 1 I
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~
I ~
0
~
6)
Continued I
Sainpl e
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Location/Date Reason for Iiissing Data Fish Herbivore -
9Sr,g Sr Fish Herbivore - 89Sr,gDSr Fish Herbivore - 89Sr,9DSr Fish Herbivore -
9Sr,9 Sr Fish Herbivore - 8 Sr,9DSr Fish Herbivore - 89Sr,gDSr T59 T66 T69 T94 T95 T81 2/25/81 2/25/81 2/25/Gl 2/25/81 2/25/81 5/13/81 Analyses Incompl ete Analyses Incomplete Analyses Incomplete Analyses Incomplete Analyses Incomplete 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 Mangrove Leaves - 89Sr,gDSr Mangrove Leaves - 89Sr,9DSr thangrove Leaves -'=89Sr,9GSr T71 3/26/81 T72 3/26/81 T51 4/2/81 T86 5/13/81 Analyses Incompl ete Analyses Incenplete Analyses Incomplete 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
0
~
I I
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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
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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
< 10,000 m
, where Q.
= release 3
MPC.
sec and MPC.
= maximum
.th the i The release
- rate, Q., was determined by
.th released in Ci, for the i nuclide (t, quarter by the.econds in the quarter.
rate of i nuclide, Ci/sec
. th permissible concentration of
- nuclide, Ci/m3 dividing the total activity
> 8d), during the calendar 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:
% of limit x
x 100%
?PC.
~
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
().
4
0
~
l
YEAR 1981 iNUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE "RADIOACTIVE EFFLUENT RELFASES" PORl ION OF THE'EtlIANNUAL OPERATING REPORT Tf<BLl.: I Report of Radioactive Eff1 uents:
Liquid PAGE i.
) 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
1.3 E-08
[ 1.6 E-09
[
1.8 8-09 6.8 E-1O 9.5 E-1O
[ 4.O E-Og (uCi/ml 4;
Yiax Concentration Released 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
~
- 5. Percent of Technical Specification Limit for Total Activit Released
(/,)
I Tr1t 1 um 8.9 E-01 1.1 E+00
, 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-
)
C.
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 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. vol of Dilution liater Durin Rel Liters 2.69 E+11.
1 2.12 E+11 L~sl w+
I
+
9
.73 E+la 3.
Y 1 'it ti Iht f
!l"I0 3
+.
L~L. E-VOTE:.
Numbers in parenthesis represent maximum sensitivity in liCi/ml,-
YEAR 1981 NUCLEAR CHEHISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPOPT TABLE I Report of Radioactive Effluents:
Liquid - Tota1 PAGE 2
Isoto e
Unit Januarv Februar triarch 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 Co-58 mCi mCi
(<1.6 E-08) 1.09 E&0
(<1. 6 E-OS) 1.31 E-Ol
(<1.7
"-08) 4.8O EWO
(<2.1
-08) 2.49 E+00 3.62 E-03 5.44 E-Ol
(<2.8 E-<
6;92, E-01 Co-60 Cr-51 mCi mCi 7.6'+00
(<1.7 E-07 2.34 E+00
(<1,7 E-07) 7.53 EWO 9.13 E-01 4.48 E+30 1.58 EWO
- 6. 2 F+00 2.71 E+00 9.35 E-02
(<4.1 E-07)
Cs-134 Cs-137 F-18 1-131 1-132 T~133 1-134 mCi mCi mCi mCi m<Ci mCi mCi 6.44 E-01 1.19 E.oo 5.34 E-01 8.03 E-01 1.37 E".00 1.04 E+00 4.09 E-Ol 4.84 E+00 6.60 E+00 1.29 E+00 3.90 E-01 2.69 EWO 3.28 E+00 5.7 E-Ol 2.11 E+00 8 i E-02 1.78 E+00 5.48 E-ol 9.29 E-01 3.70 E+00
- 1. 14 EWO 873 Eol 2.63 E+00 2.53 E-Ol 7.08 E-01 8.78 F.-pl 1.0 E+00 3.29 FWO 3
~ 06 E-01 8.65 E
C 2.48 E+00 1.53 E-Ol 1.00 E-01 La-140 i~in-54 mCi mCi
(<1.2 E-OS) 1.75 E-01
(<2.4 E-08) 1.36 E-Ol
(<6.0 E-09)
<1.2 E-08)
(<3.9 E-06) 6.39 E-02 4.79 E-02 4.5 E-02
(<4.3 E-07)
(<3.0 E-07 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.
YEAR 1981 NUCLEAR CHFNISTRY PROCEDURE NC-3 PREPAPATION OF THE HONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT 1'ABLE I Report of Radioactive Effluents:
Liquid - Total PKGE. 3 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 sb-125 Sr-89 mCi mCi 4.7 E-03 3.29 E-03
(<2.2 E-08)
(<1.5 '-08)
(<6.7 E-08)
(<6.6 E-08) 1.69 E-01
(<3; 8 E-08) 9.98 E-02 7.28 E-02 8.41 E-02
(<9.9 E-08) 1.37 E-02 3.02 E-02 9.1 E-03 4.08 E-02 5.04 E-
- 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 1.12 E+Ol 6.21 E+00
- 2. 72 E&1
- 2. 10 E+Ol 1.85 E+Ol 1.32 E+Ol NOTE:
Numbers in parenthesis represent maximum sensitivity in pCi/ml,
YEAR 1981 NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF THE YiONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEHIANNUAL OPERATING REPORT TABLE I Report of Radioactive Eff1uents:
Liquid - Maste Disposa1 System PAGE 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 Co-57 mCi
(<1.3 E-07)
(<1.2 E-07)
(<1 6 E P8)
(<1.6 E-08)
(<1.4 E-07)
(<1.7 E-08)
<1.6 E-07
(<2.1 E-08) 1.52 E-Ol 3.62 E-03
(<2.2 E-07)
(<2. 8 i)
Co-58 Co-60 Cr-51 Cs-134 Cs-137 T-131 mCi mCi mCi mCi mCi mCi 9.12 E-01 1.88 E+00
(<1.7 E-07) 4.17 E-01 7.91 E-01 1.59 E-01 1.31 E-01 5.77 E-Ol 4.7 F,-
<2.2 F.-08 4.10 E+00 4.57 E+00 9.13 E-Ol 4.42 E-01 8.58 E-pl-.
3.51 E-Ol 2.33 E&0 3.14 EWO 1.58 EWO
- l. 87 E-01 2.86 E-Ol
<9.9 E-08 5.44 E-01 9.82 E-Ol 9.35 E-02.
1.02 E-Ol 1.79 E-01
(<5.2 E-08 6.92 E-01 1.71 E+00
<4.1 E-07 3.34 E-01 7.94 E-Ol
(<6.8 E-08)
La-140 i'-54
%)-95 mCi mCi mCi
<6 P
F P9
" (<1.2 E-08)
(<1.2 E-08) 9.35 E-02
(<2.4 E-08) 1.36 E-01 1.77 E-pl
(<2.3 E-08)
(<1.9 E-08
(<3.9 E-06) 6.39 E-02 3.87 E-01
(<4.3 E-07) 4.79 E-02
- 9. 76 E-02
(<3.0 E-07) 4.5
'.14 E-02 H,u-103 Sb-124 Sb-125 mCi mCi mCi
(<2. 2 E-08)
(<2, 1 E-08)
(<2,2 F.-08)
(<1.5 E-08)
(<6.7 E-08)
(<6.6 E-08) 4.01 E-02 1.69 E-Ol 8.41 E-02
(<4.7 E-08)
(<3.8 E-08)
(<9.9 E-08)
(<6. 5 E-08) 1.37 E-02 3.02 E-02
(<S.7 E-(
4
~ 08 E-02 5.04 E-02 Sr-89 Sr-90 mCi mCi 4,7 E-03 7.1 E-03 3.29 E-03 3.99 E-03 9.98 E-02 4.77 E-03 7.28 E-02
(<2.9 E-09)
- 9. 1 E-03
(<3.2 E-09) 1.16 E-02
(<2.6 E-09)
NOTE:
Numbers in parenthesis represent ma>.imum sensitivity in pCi/m'f.
YEAR 1981 NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SENIANNUAL OPERATING REPORT TABLE I Report of Radioactive Eff1uents:
Liquid.- Waste Disposal System
-. PAGE 5
Isotope Zr-95 Unit Januar
(<3.8 E-08 February
<3.3 F~8 8.24 E-Aoril 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.
YEAR 1981 NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF THE YiONTHLY "PRELIMINARY REPORT ON RADIOACTIYE RELEASES" AND THE "RADIOACTIYE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT TABLE I Report of Radioactive Eff1uents:
Liquid - Secondary System Isotope Co-58 Co-60 Cs-134.
Cs-137 F-18 I-131 I-132 I-133 I-134 1..3,35:
Mn-54 Na-24 mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi Januarv 1.75 E-01 5.7 E+00 2.27 E-Ol 3.96 E-01
- 3. 75 E-01 8.1 E-02 Februar 1.76 E+00 4.87 E-01 8.95 E-Ol 1.04 E+00 4.09 E-Ol 1.11 E-01 March 7.01'-Ol 2.96 E+00 4.40 EWO
- 5. 74 E+00
- 9. 39 E-01 3.90 E-01 Aoril 1.60 E-01 1.34 E+00 2.50 E+00 2.99 E,OO.
5.7 E-Ol
.2.11 E+00 8.1 E-02 1.78 E+00 1.07 E+00 Mav 5.2 E+00 4.46 E-01 7.50 E-01 3.70 EWO 1.14 E+00 8.73 E-Ol 2.63 E+00 2.53 E-01 7.08 E-01 4.41 E-Ol June l.00 EW 5.44 E-01 2.98 E- ~
3'. 29 EWO 3.06 E-01 8.65 E-01 2.48 E+00 l.53 E-01 1.00 E-01 j
I 3.99 E
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.
~
~
YEAR 1981 NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE
'ADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT TABLE I Report of Radioactive Effluenis:
Liquid - Dissolved Gas
,A PAGE. i Total Januarv Februarv Harch Anril June Kr-85 Xe-131m mCi mCi 2.05 E+01 9.40 H:00
(<1.2 E-06)
(<1.3 E-06)
- 1. 79 EW1
(<1.3 E-06) 7.8 E+00
(<1.3 H-06)
(<6.0 E-06)
(<5 ~ 3 E-07)
(<4.3 E-06'<5.2 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) mCi
(<2. 9 E-08) 2.59 E+01 3.92 E-01 5.83 E+01
(<3.0 H-08) 2.51 EW1
(<3.0 E-08) 1.37 H%1
(<1. 7 E-08),
3.39 E+00 1.16 E-Ol 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 Xe-135 mCi mCi
(<2.6 E-07)
(<2.8
-E-07)
(<2.9 E-08) 3.92 H-Ol
(<2.8 H-07)
(<3.0 E-08)
(<2 '
E-07)
(<3.0 H-08)
(<1.2 E-07)
(<1
~ 7 E-08)
(<1. 2 E-07) 1.16 E-Ol Secondary Svstem Kr-85 Xe-131 m Xe-133 Xe-133m Xe-135 mCi mCi mCi mCl mCi NOTE:
Numbers in parenthesis represent maximum sensitivity in pCi/ml.
YEAR 1981 NUCLEAR CHEMISTRY PROCEDURE NC-3
'REPARATION OF THE NONTHLY "PRELIitINARY REPORT ON RADIOACTIVE RELEASES" AND. THE "RADIOACTIVE EFFLUENT RELEASES" PORTIOf) OF THE SEMIANNUAL OPERATING REPORT TABLE II Report of Radioactive Effluents:
Airborne 0
~
PAGE 3
A. Fission and Activation Gases Jailllarv Februarv H v une
- 1. Total Release (ci)
Z.
Av Release Rate for Period uCi/sec 3.21 E+02 2.3 EW2 1.3 EW2 3.08 E+02 2.11 E+02 1.0 E+02 8.8 E+01 2.97 E&2 9.9 E&1 2.78 E+02
- 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 Z.
Av Release Rate =or Period Ci uCi/sec 5.9 E-04 2.7 E-04 1.5 E-02 5.5 E-04 3.5 E-04 8.3 E-05 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 2.
Av Release Rate for Period Ci uCi/sec 2.78 E-02 1.2 E-02 1.01 E-Ol 4.2 E-02 1.26 E-01 4.2 E-02 5. 64 E-02
- 1. 06 E-01
- 2. 4 E-02 3.5 E-02 3.3 E 2 E. Percent of A plicable Limit
- 1. Fission and Activation Gases Z. I-131 and Part tl/2>ad N TE:
0 r r I 1.3 E+00 2,0 E-Ol 8.3 E-01 1.2 E-02
YEAR 1981 NUCLEAR CHB)ISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY "PRELIHINARY REPORT ON RADIOACTIVE RELEASES" AND THE RADIOACTIVE EFFLUENT RELEASES'ORTION OF THE SEMIANNUAL OPERATING REPORT TABLE II Airborne Releases
- Particulates PAGE
~ I Isoto e
Sa-140 Co-58 Co-60 Cr-51 Cs-134 Cs-137 T.-131 La-140 Hn-54 Hb-95 Unit
. Ci Ci Ci Ci
.Ci Ci
.Ci Ci
.Ci
(<l.0 E-13) 9.4 E-06 l.0 E-04
(<1.6 E-13) 5,3 E-06 1.3 E-05 2.5 E-06
(<1. 5 E-14) 3.5 E-06
(<4.5 E-14)
Februar
(<5.2 E-14) 1.1 E-06 4.9 E-06
( 9.7 E-14)*
9.2 E-07 1.0 E-05
(<l. 2 E-14)
(<1.3 E-14)
(<1.7 E-14)
(<2.7 E-14)
March
(<l.5 E-13) 5.0 E-05 9.9 E-05 3.8 E-05 1.4 E-06 7.0 E-06
- 4. 1 E-06
(<5.4 E-14)
(<4. 3 E-14) 2.6 E-06 A ril
(<1.9 E-13) 1.3 E-05 8.3 E-06
(<3. 0 E-13) 3.1 E-06, 4.6 E-06
(<4.1 E-14)
(<1.1 E-13) 1.5 E-06 2.2 E-06
'fay
(<2.1. E-13) 9.0 E-06 1.6 E-05 2.4 E-06
(<7.3 E-14) 3.9 E-06
(<4. 8 E-14)
(<1.5 E-13) 4.0 E-07 3.2 E-06 June
(<1'.8'-1'3J
- 3. 7 F,-06 2.9 E-05
(<2. 7 E-J.
3.8 E-07 4.7 E-06
(<3.1 E-14)
(<6.6 E-14) 3.4 E-07
(<5.5 E-14)
Ru-103 Sb-125 Sr-89 Sr-90
.Ci Ci 1.3 E-06 1-2 E-06 3.8 E-08 Ci
(<2. 8 E-14)
(<1.4 E-14)
(<3.3 E-14) 4.1 E-06 3.8 E-08
(<3.9 E-14)
(<9.1 E-14) 1.5 E-06 1.4 E-07
(<5.0 E-14)
(<1.1 E-13) 9.3 E-07 4.7 E-08 2.6 E-07
(<1.4 E-13) 5.2 E-oj 5.2 E-08
(<3.5 E-14)
(<x.o z-0 4.2 E-07 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.
YEAR 1981 NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND.THE "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT TABLE II Airborne Releases
- Gaseous PAGE 3
Fission and Act iYat ion Gases Isotove Ar-'l Unit Ci January 7.35 E-01 Fe'oruary 6.97 E+00
~ilarcn 5
~ 96 E-Ol April
- 2. 5 E-01 iNay 3.07 E-01 June 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>
Kr-87 Kr-88 Xe-131n Xe-133 Ci Ci Ci Ci 2.33 E-02
( <3,. 5 E-06) 8.8 E-05 1.98 E-ol 5. 60 E+02
(<7 '
E-06)
.1.34 E-01 E-05 1.79 E-01
- 3. 11 E+02 3.05 EWZ 6.0 E-02
- 1. 30 E-02
(<1. 5 E-O5); (<1. 8 E-06) 1.5 E-02
(<3.5 E-06)
(<3.1 E-06) 1 ~ 07 E+00 2.09 E+02
- 8. 56 E-03
(<2.9 E-06)
(<3.3 E-06) 3'2 E-01 2'5 E+02 1.5O E-(<8.9 E-07)
( (<9. 1 E-07) 6.06 E-01 2.76 E+02 Xe-133'e-135 Xe-135m Xe-138 Tot a 1 Ci Ci Ci Ci
- 4. 75 E-01 6.82 E-OL 9.52 E-02
<1. 7 E-O6) 5.63 E+02 9.10 E-01 8.52 E-01
(<3.4 E-05)
(<4.8 E-05) 3'1 E+02
- 1. 21
. EWO
'6.31 E-Ol
(<4.9 E-O6)
(<1. 2 E-05 3.08 E+02
- 3. 23 E-01 2.02 E-01
(<2.4 E-05)
(<5. 8 E-05) 2.11 E+02 3.32 E-01 2.71 E-01
(<3.4 E-O6)
(<5.8 E-06) 2.97 E02 3.64 E-01 3.07 E-01
(<3.4 E-06)
(<7. 1 E-2.78 E+02 Halo ens Gaseous Isoto e
I-131 March Unit February E-O4 January 5.9 E-O4
- 1. 5
-E-02 Ci 3.4 E-03 7.3 E-04 4.9 E-04 Ci I-133
(<8. 4 E-14)
(<3.4 E-14) 1.08 E-03
(<l. 3 E-13)
(<1,3 E-13) 4.6 E-04 1.46 E-03 Ci I-135 Br-82 4.1 E-05 1.8 E-02 Ci Total Note:
sens'1tl Yltj 1 n pCi/111 uiil ers l n parent esl s represent 111axlBuli1 April 5.5 E-04 2.6 E-o4 2.2 E-O4 1.7 E-05 1.05 E-03 ifay 3.5 E-04
- 5. 2 E-04 3.7 E-05
- 3. 5 E-04
- l. 26 E-03 June 8.3 E-05 2.4 E-04 5.0 E-06 1.7 E-04 5.0 E-04
TVRKHY POINT PI>ANT RADIOACTIV].'.'ASIE R]il'ORT
.JAN 1,
1981 to JUNP. 30, 1981 Date of Shi 1-OGI-81 1-14-81 1-20-81 1-29-81 2-10-81 2-24-81 3-17-81 3-24-81 3-26-81 4-17-81 4-20-81 4-23-81 4-27-81 5-OG-81 5-19-81 5-19-8 ]
5-30-8 1
6-03-81 6-11-81 6-15-81 6-17-81 6-21-81 6-22-81 6-22-81 6-22-81 6-23-81 6-23-81 6-23-81 6-23-81 6-24-81 6-24-8 1
G-25-81 6-25-81 ment Curies 0.214 0.612 0 ~ 242
]2.2 0.423 0,314 0.482 1.61 3.219 6.71 0 '557 4.27 10.8 0.0507 10 '
F 7 1.93 7.93
- 9. 15)0
?.29 0 2445 2.092 0.00]74 0.00254
- 0. 00164 0.00086 0.00137 0.000855 0 563 0.00099 0.00092 0.00095 1
0.008835 Cu. PL.
852
]100 550 85 1100 1100 1100 170 170 85 1050 85
]50 1050 150 150 170 85 85 100 1050 170 562.5 555 570 555 562.5 555 170 555 532 '
532 '
525
~D3.8 OSItI.Oll Buried in Barnwell, SC II Buried in Richland, Washington Buried in Barbell, SC Buried in Richland, ]lashington 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
Wr
')