LG-85-003, Semiannual Radioactive Effluent Release Rept for Period 850320-850630
| ML20134P286 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 06/30/1985 |
| From: | Jens W DETROIT EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| RC-LG-85-0032, RC-LG-85-32, NUDOCS 8509060228 | |
| Download: ML20134P286 (30) | |
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l DETROIT EDISON COMPANY FERMI-2 *sTOMIC POWER PLANT ,
OPERATING LICENSE NO. NPF - 43 SEMI-ANNUAL RADIOACTIVE EFFLUEUT RELEASE REPORT FOR THE PERIOD MARCH 20,1985 THROUGH JUNE 30, 1985 i
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Page ii TABLE OF CONTENTS TOPIC PAGE LIST OF TABLES iii INTRODUCTION 1 A. SUPPLEMENTAL INFORMATION 2
- 1. Regulatory Limits 2
- 2. Maximum Permissible Concentrations 3
- 3. Average Energy 3
- 4. Messurements and Approximations of Total Radioactivity 4
- 5. Batch Releases 6
- 6. Abnormal Releases 7 B. GASEOUS EFFLUENTS 7
- 1. Summation of All Releases 7
- 2. Continuous Releases 7
- 3. Batch Releases 7 C. LIQUID EFFLUENTS 7
- 1. Summation of All Releases 7
- 2. Liquid Releasa Summary by Mode 7 D. SOLID WASTE 8 E. RADIATION DOSES TO THE FUELIC 8
- 1. Doses Due to Liquid Effluents 8
- 2. Doses Due to Gaseous Effluents 8 F. METEOROLOGICAL DATA 8 G. NOTIFICATION OF CHANGES 8
- 1. Changes,to the Process Control Programs 8
- 2. Changes to the Offsite Dose Calculation Manual 8 i
Page lii LIST OF TABLES NUMBER TITLE PAGE A4.1 Radioactive Liquid Weste Sampling and Analysis Program 9 A4.2 Radioactive Gaseous Waste Sampling and Analysis Program 12 AS.1 Batch Release Summary Table 15 51.1 Gaseous Effluents - Summation of All Releases 16 32.1 Gaseous Effluents - Continuous Releases 17 C1.1 Liquid Effluents - Summation of All Releaseu 21 C2.1 Liquid Effluents - Batch Releases 22 D1.1 f,olid Waste and Irradiated Fuel Shipments 26 t .
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INTRODUCTION This Semi-Annual Radioactive Effluent Release Report, hereinafter referred to as this REPORT, for the period March 20, 1985 through June 30, 1985 is submitted in accordance with Appendix A to Fermi-2 Plant, License No.
NPF-43. The appendix will be referred to hereinaf ter as the Fermi-2 Technical Specifications, or Tech Specs. ,
All liquid and airborne discharges to the environment during this reporting period were analyzed in accordance with requirements in the Tech Specs.
For all effluent releases, the concentrations of radioactive material were within the required limits.
The low power license (No. NPF-33) was issued on March 20, 1985, initial criticality was attained in the Fermi-2 reactor on June 21, 1985, and the operating license (No. NPF-43) was issued on July 15, 1985.
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P:ge 2 of 26 A. Supplemental Information A.1 Regulatory Limits
- a. Liquid Effluents
- 1) Concentration (Tech. Spec. 3.11.1.1)
The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-4 microcuries/ml total acti rity.
- 2) Dose (Tech. Spec. 3.11.1.2)
The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS shall be limited:
a) During any calendar quarter to less tbsn or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ.
b) During any calendar year to less than or equal to 3 mrems to the total body and to less than or '
equal to 10 mrems to any organ,
- b. Gaseous Effluents
- 1) Unrestricted Area Boundary Dose Rate (Tech. Spec.
3.11.2.1)
The dose rate due to radioactive materials released in gaseous effluent from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:
a) For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and, b) For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
- 2) Unrestricted /.rea Air Dose (Tech. Spec. 3.11.2.2)
The air dose due to noble gases released in gaseous effluent, from each reactor unit, to areas at and
. Pege 3 of 26 beyond the SITE BOUNDARY shall be limited to the
! following: (
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i a) During any calendar quarter: Less than or equal :
to 5 meads for gamma radiation and less than or !
equal to 10 mrads for beta radiation. !
I b) During any calendar year: Less than or equal to i 10 mrads for gamma radiation and-less than or equal to 20 mrads for beta radiation.
- 3. Unrestricted Area Dose to Individual (Tech. Spec.
3.11.2.3)
The dose to a MEMBER OF THE PUBLIC from I-131, I-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents-released from each reactor unit, to areas at and beyond the SITE BOUNDARY shall-be limited to the following:
I a) During any calendar quarter: Less than or equal to 7.5 mrems to any organ.
f b) During any calendar year: Less than or equal to l 15 mrems to any organ.
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- c. Calculations Equations and constants used to verify compliance with the above criteria are given in the Of fsite Dose Calculation Manual (ODCM), previously submitted via Detroit Edison to NRC letter EF2-71988, dated October 11, 1984.
A.2 Maximum Permissible Concentrations
- a. Liquids The Maximum Permissible Concentrations (MPC) in liquids are those in 10 CFR 20, Appendix B, Table II, Column 2, with the lower of the soluble and insoluble MPC being used in all cases. For.
dissolved and entrained noble gases, an MPC of 2.0 E-4 microcuries/mi is applied.
- b. Gases The Fermi-2 Technical Specifications for gaseous effluents do not
,contain a concentration requirement.. Therefore, MPC for gases does not apply.
A.3 Average Energy Average Energy of effluent radionuclide mixtures does not apply to the Fermi-2 Technical Specifications or the ODCM.
- Pege 4 of 26 A.4 Measurements and Approximations of Total Radioactivity The following discussion summarizes the methods used to measure total radioactivity in gascous and liquid effluents. Tables A4.2 and A4.1 give the sampling and analysis frequencies of gaseous and liquid effluents respectively.
- a. Gaseous Effluents Table A4.2 (which is Table 4.11.2.1.2-1 of Fermi-2 Technical Specifications) summarizes the gaseous waste sampling and analysis program. The four types of total radioactivity listed in Table Bl.1 of this REPORT are discussed separately below.
Note that in accord with the ODCM, gaseous effluent stack flow rstes are always assumed to be the maximum design values. As a result, estimates of radioactivity are high, and error estimates are large in a conservative manner.
- 1) Fission and Activation Gases Fission and activation gases are quantified by the gamma-ray analysis of appropriate samples using germanium detectors and multichannel analyzers. The radionuclides measured and included in the dose calculations (when present in measurable quantities as defined in Table A4.2) include the following:
Kr-85m Kr-88 Xe-135m Kr-85 Xe-133m Xe-135 Kr-87 Xe-133 Xe-138 The reported total of fission and activation gases is the maximum value of the sum of the releases of.the above gases in all botch and continuous releases.
Considering uncertainties in radiation counting and in volume, flowrate, and pressure measurements, total fission and activation gases estimates are expected to be in error by less than 7.4% low and 50.3% high.
- 2) Radioiodines and Particulates Radioiodines and particulates are quantified by the gamma-ray analysis of charcoal and filter cartridges using
~ high-resolution germanium detectors and multichannel analyzers.. In each case, the sampling flowrate for these continuous effluent samplers, the maximum flowrate in the sampled effluent paths, and the length of the sample are known. The radionuclides measured and included in the dose calculations-(when present in measurable quantities as defined in Table A4.2) include the following:
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. . = . . -. - - - . . .- .
. Pagn 5 of 26 Mn-54 Zn-65 Cs-134 other nu-Fe-59 Mo-99 Cs-137 clides Co-58 I-131 Ce-141 with half-Co-60 I-133 Ce-144 lives greater than 8 days The filters are also composited and separately analyzed for Sr-89, Sr-90, and gross alpha radioactivity. When detectable, these totals are included in the reported total particulate releases.
Considering uncertainties in radiation counting and in
- volume, flowrate, and pressure measurements, total radioiodine and particulate estimates are expected to be in 4 error by less than 22.9% low and 54.8% high.
3)- Tritium Tritium is analyzed by liquid scintillation counting of special grab samples. The sum of the tritium results for all batch and continuous grab samples is reported as the total tritium release.
Considering uncertainties in radiation. counting and in volume, flowrate and pressure measurements, total tritium estimates are expected to be in error by less than 12.3% low and 51.2% high,
- b. Liquid Effluents Table A4.1 (which is Table 4.11.1.1.1-1 of the Fermi-2 Technical Specifications) summarizes the liquid waste sampling and analysis program. 1me four types of total radioactivity given in Table C1.1 of this REPORT are discussed below.
- 1) Fission and Activation Products Fission and activation products are quantified by the gamma-ray analysis of appropriate batch,_ grab and composite samples using high-resolution germanium detectors and multichannel analyzers. The radionuclides measured and
, included in the dose calculations (when present in j measurable quantities as defined in Table A4.1) include the following:
Mn-54 Zn-65 Ce-144 Fe-59 Mo-99 Ba/La-140
-Co-58 Cs-134 Other radio-Co-60 Cs-137 nuclides as Ce-141 appropriate Composite samples are also analyzed for Fe-55 (by chemical
, separation and liquid scintillation counting), ,and for Sr-89
- and Sr-90 (by -chemical separation and proportional counting).
P ge 6 of 26 The total release given in this REPORT is the sum of all the above radionuclides in all batch and continuous releases.
Considering uncertainties in radiation counting and flowrate and volume measurements, total fission and activation product estimates are expected to be in error by less than 14.3%.
- 2) Tritium Tritium in batch or continuous releases is quantified by liquid scintillation counting of an appropriate composite sample. The total tritium activity reported is the sum of the tritium activities in all batch and continuous releases.
Considering uncertainties in radiation counting and in flow rate and volume measurements, total tritium estimates are expected to be in error by less than 14.3%
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- 3) Dissolved and Entrained Gases Dissolved and entrained gases are quantified by the gamma-ray analysis of monthly grab samples, using high-resolution germanium detectors and multichannel analyzers. The radionuclides measured and included in the dose calculations (when present in measurable quantities as defined in Table A4.1) include the following:
Ar-41 Kr-90 Xe-135m Kr-85m Xe-131 Xe-135 Kr-85 Xe-133m Xe-137 Kr-88 Xe-133 Xe-138 Kr-89 Kr-87 Considering uncertainties in radiation counting and in flowrate and volume measurements, total dissolved and entrained gases estimates are expected to be in error by less than 15.0%.
- 4) Gross Alpha Gross Alpha-emitting radionuclides are quantified by the counting of appropriate composite samples in a 2 pi geometry gas flow proportional counter. Considering uncertainties in radiation counting and in flowrate and volume measurements, total gross alpha estimates are expected to be in error by less than 22.5%.
A.5 Batch Release Summary A sunmary of statistical data for batch releases is found in Table A5.1 of this REPORT. The stream flow shown for liquid releases is that of the dilution stream (the Circulating Water Reservoir Decant Line).
. Pzge 7 of 26 A.6 Abnormal Releases The following summarizes releases during the six month reporting period which required prompt or thirty-day notification of NRC.
- a. Liquid
- 1) Number of releases : 1, as reported in LER 85-007.
- 2) Total activity released : None
- b. Gaseous
- 1) Number of releases: 1, as reported in LER 85-020.
- 2) Total activity released: None B. Gaseous Effluents B.1 Summation of all Releases The Gaseous Effluent Summation for the Fermi-2 Plant is given in Table Bl.l. Because the Fermi-2 Technical Specifications are dose-based, not curie-based, the lines labeled "% of Technical Specification Limit" do not apply, but are included in the standard report software used.
B.2 Continuous Relesses Continuous gaseous releases from the Fermi-2 Plant are summarized by release height in Table B2.1. No credit is taken for elevated releases, thus all releases are considered to occur at ground level, per the ODCM.
B.3 Batch Releassa No batch gaseous releases are made from the Fermi-2 Plant.
C. Liquid Effluents C.1 Summation of all Releases The Lio"id Effluent Summation for the Fermi-2 Plant is given in Table M 4.'
C.2 Liquid Release Summary by Mode Liquid releases by mode for the Fermi-2 Plant are summarized in Table C2.1. No continuous liquid releases were made from the Fermi-2 Plant.
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D.- Solid' Waste The volume, activity, and disposition of solid waste shipments during the reporting period are summarized in Table Dl.1 E. Radiation Dose to the Public I This.information will be provided in annual report in accordance with Technical Specification 6.9.1.8.
t F. Meteorological Data This information will be provided in annual report in accordance with Technical Specification 6.9.1.8.
G. Notification of Changes G.1 Changes to the Process Control Program (PCP)
The PCP was not approved until af ter the period of this report.
G.2 Changes to the Offsite Dose Calculation Manual (ODCM)
No changes to the ODCM occurred during the period of this report.
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I TABLE A 4.1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detectjon Liquid Release Sampling Analysis Type of Activity (LLD)
Frequency Frequency Analysis (pCi/al)
Type _
A.BatchVgste P .P ~7 Each Batch Principa} Gamma 5x10 Release Each Batch .
Sample Emitters Tanks (3)
' -6
'I-131 1x10
' -5 P M Dissolved and 1x10 One Batch /M Entrained Gases (Gama Emitters) 1x10
-5 P M H-3 d . _ ,
Each Batch Composite _
Gross Alpha 1x10 1
P Q r-89, Sr-90 5x10 d
Each Batch toe;esite
-6 Fe-55 1x10
~
7 B. M Principa) Gamma 5 x10 Continuoys d Releases Composite Emitters General Service NA
-6 Water System 1-131 1x10 (G5W) (If 3 Contaminated) w M Dissolved and 1x10 Grab Sample Entrained Gases (Gama Emitters)
-5 H-3 1x10 d ~7 NA Composi e Gross Alpha 1x10 8
Q d St-89, Sr-90 5x10 NA Composite 6
Fe-55 1x10 ,-
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~k TABLE NOTATION
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'The LLD is defined, for purposes of these specifications, as'the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blink observation represents a "real" signal.
For a particular seasurement system, which may include radiochemical separation:
b LD=
E.V 2.22 x 105 Y exp-(-Aat)
Where:
LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, s is the standard deviation of the background counting rate or of e
tne counting rate of a blank sample as appropriate, as counts per minute,
- E is the counting efficiency, as counts per disintegration,
V is the sar.ple size in units of mass or volume, 2.22 x 108 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.
Typical values of E, V, Y, and at should be used in the calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteeieri (after the fact) limit for a particular measurement.
A batch release is the discharge of liquid wastes of a . discrete volume.
Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the 00CM to assure representative sampling.
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TABLE A 4.1 (Continued)
TABLE NOTATION
- The principal ~ gamma emitters for which the LLD specification applies exclusively are: Hn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This does not mean that only these nuclides are to be
, considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8.
A composite sample is one in which the quantity of liquid samples is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. This may be accomplished through composites of grab samples obtained prior to discharge after the tanks have been recirculated.
'A continuous relt.se is the discharge of liquid wastes of a nondiscrete
- volume; e.g., from a volume of a system that has an input flow during the continuous release.
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_T_AB L E A 4.2 RA!Q0 ACTIVE _ Cast 005 W.IE_5AMPLlhG AND ANALYSIS PROGRAM Minimim Lc=*r Limit of
$ampilng Analysis Type of Detection (tt0)*
, Caseous Release Type frequency frequency Activity Analysis (pCl/,el)
I I P. 5 P. 5 b -4 A. Containment PURGE Each PtEE lach rtEF Principal Camma Initters 1 10 -6 Grab Sample P H-3 1 10 (Pre treatment)
M *d*' Principal Camma imitters" C C 1:10'4 R. Reactor Building M C -6 Enhaust Plenum Grab Sample M H-3 la10 StandbyGasigeat-eent Systen b 1n10'*6 C. Radwaste Building M M Principal G.imma [altters Turbine Building Grab Sample M H-3 1x10 Service Buildinu On-site Storage facility .
O. All Release Types Continuous' @ l-131 lul0 as listed in 8 Adsorbent I-133 Into and C above. Sample I @ Principal Gamma [mitters' Im10'II Continuous Particulate (1-131,others)
Sample Continuous I
M Gross Alpha It10' AI Composite
- Pasticulate Sample Continuous' Q Sr-89, Sr-90 1x10'll Composite Particulate Sample Continuous' Noble Gas Moble Cases 1:10
e Monitor Gross 8 eta er Gamma i
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page 13 of 26 TABLE A 4.2 (Continued) -
TABLE NOTATION
- The LLD is defined, for purposes of these specifications, as the smallest
. concentration of radioactive material in a sample that will yield a n2t count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
D LLD =
E. V 2.22 x 105 Y exp.(-Aat)
Where:
LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, s is the standard deviation of the background counting rate or of tNecountingrateofablanksampleasappropriate,ascountsper minute, E is the counting e'ficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 105 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable.
A is the radioactive decay constant for.the particular radionuclide, and at for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.
Typical values of E, y, Y, and at should be used in the calculation.
It should be recognized that the LLD is defined as an a priori (before the )
fact) limit representing the capability of a measurement system and not as i an a posteriori (after the fact) limit for a particular measurement.
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5 A 4.2 (Continued) g TABl.E TABLE NOTATIONS ,
DThe principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, 1-131, Cs-134 Cs-137, Ce-141 and Ce-144 in todine and particulate releases.
This list does not mean that only these nuclides are to be considered.
Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8.
E Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period. This requirement does not apply if (1) analysis shows that the DOSE' EQUIVALENT I-131 concentration in the prir.ary coolant has not increaseo more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
diritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when either the reactor well or the dryer-separator storage pool is flooded.
' Tritium grab samples shall be taken at least once per 7 days from the y ventilation exhaust from the spent fuel pool area, whenever spent fuel is
- . in the spent fuel pool.
IThe ratio of the saWe flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation sade in accorcance with Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.
95amples shall be changed at least once per 7 deys and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or af ter removal from sampler.
Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup ur THERMAL POWER change exceedin2 15% of RATED THERMAL POWER in I hour and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10.
- This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
" Required when the SGTS is in operation.
IThe containment shall be sampled and analyzed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the start of any VENTING or PURGING and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during VENTING or PURGIh3 of the drywell through other than the SGTS.
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- Table A 5.1 Page Ib of 2tr REPORT CATEGORY : BATOI RELEASE SUl!!!ARY RELEASE POINT : ALL TYPE OF RELEASE : BATCH LIQUID A!!D G ASEOUS PERIOD START TIllE : 0: 00 IIRS = 12: 00Ali J ANUARY 1,1985 PERIOD END TIME : 43 43 : 59 HRS = ll : 5 9 Pl1 JUllE 3 0, 1985 LIQUID RELEASES NUI1BER OF RELEASES : 51 TOTAL TI!!E NR ALL RELEASES : 23863.0 !!INUTES 11AXII'Ull TIME MR A RELEASE : 1837.0 till1UTES AVERAGE TI!!E FOR A RELEASE : 467.9 NI!!UTES HINIEUM TIliE FOR A RELEASE : 99.0 MINUTES AVERIGE STREA!! FLON : 11947.8 GPM NOTE: Stream flow data do not apply since Fermi 2 effluents pass directly into Lake Erie.
GASEOUS RELEASES EUl!3ER OF RELEASES '
- 0 TOTAL TIME FOR ALL RELEASES : 0.0 liI!1UTES IIAXIEUll TI!!E FOR A RELEASE : 0.0 !!INUTES AVERIGE TIME FOR A RELEASE : 0.0 !!INUTES I!INII:Ul! TIEE FOR A RELEASE : 0.0 MINUTES b
- e
eage io or go Table B 1.1 f
REPORT CATEGORY : SENIA!!!!UAL SUl!!ATION OF ALL RELI ASES BY QUARTER '
TYPE OF ACTIVITY : ALL AIRBORNE EFFLUENTS REPORTING PERIOD : QUARTER t 1 AND QUARTER f 2
- UNIT : QUARTER 1 :QUASTER 2 :EST. TOTAL:
- : HOURS :llOU RS : ERROR % :
TYPE OF EFFLUENT : : 1-2160 :2161-4344 : :
A. PISSIdN AND ACTIVATIO!! PRODUCTS 1VTAL RELEASE : CURIES
- ___'_ ____ ______ _____ . __ ______ ____: __ 0.00E-01 : 0.00E-01 :
l.
- 2. AVERIGE RELEASE RATE FOR PERIOD :UCI/SEC : 0. 00 E-01 : 0.00E-01 :
B. RADIOIODIN ES
- CURIES : 0.00E-01 : 0.00E-01 :
- 1. '_IOTAL IODINE-131
- 2. AVERAGE RELEASE RATE FOR PERIOD :UCI/SEC : 0.00E-01 : 0.00E-01 :
C. PARTICULATES
- 1. PARTICULATES(liALF-LIVES >8 DAYS) : CURIES : 0.00E 01 : 0.00E-01 : *
- 2. AVERIGE RELEASE ' RATE FOR PERIOD :UCI/SEC : 0.00E-01 : 0.00E-01 :
- 4. GROSS ALPIIA RADIOACTIVITY : CURIES : 0.00 E-01 : 0.00E-01 :
D. TRITIUf1
- l. TOTAL RELEASE : CURIES : 0.00E-01 :-0.00E-01 :
- 2. AVERIGE RELEASE RATE FOR PERIOD :UCI/SEC : 0.00E-01 : 0.00E-01 :
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NOTE: Zero curies-indicates activity was not detected, per Table A4.
- Error estimates are given in Section A4.
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Table 8 2.1 Page 17 of 26
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REPORT . CATEGORY : SEMIANNUAL AIRBORNE CONTINUOUS ELEVATED AND GROUND
- LEVEL RELEASES. TOTALS FOR EACll NUCLIDE RELEASED.
TYPE OF ACTIVITY : FISSION GASES, IODIN ES, AND PARTICULATES REPORTING PERIOD : QUARTER C 1 AND QUARTER # 2 r-----------------
- ELEVATED RELEASES : GRQUND R ELEAS ES : <
. : UNIT : QUARTER 1 : QUARTER 2 : QUARTER 1 : QUARTER 2 :
- : : HOURS : HOURS :llOURS :llOURS :
NUCLIDE : : 1-2160 :2161-4344 : 1-2160 :2161-4344 :
FISSION GASES KR-83M : CURIES : 0.00 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
KR-85H : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01.: 0.00E-01 :
KR-85 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
KR-87 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
KR-88 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
KR-89 : CURIES : 0.00 E-01 : 0.0 0 E-01 :.0.00E-01.: 0.00E-01 : ;
KR-90 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
XE-131H : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
XE-133M ':: CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
XE-133 CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
XE-135M : CURIES : 0.00E-01 : 0.00E-01 : 0. 0 0 E-01 : 0.00E-01 :
XE-135 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
XE-137 : CURIES : 0. 0 0 E-01 : 0.00E-01 : 0. 0 0 E-01 : 0.00E-01 :
XE-13 8 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
AR-41 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TOTAL FOR PERIOD : CURIES : 0.00 E-01 : 0.'0 0 E-01 : 0.00E-01 : 0.00E-01 :
IODINES I-130 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
I-131 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
I-132 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
I-133 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
I-134 : CURIES : 0.00E-01 : 'O.00E-01 : 0.00E-01 : 0.00E-01 :
I-135 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TOTAL FOR PERIOD : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
NOTE: Zero curies indicates activity was not detected, per Table A4.
Table B 2.1 Pa92 16 of Zb REPORT CAT $ GORY : SENIANNUAL AIRBORNE CONTINUOUS ELEVATED NID GROUND
- L EV EL RELElo ES. TOTALS FOR EACH NUCLIDE RELEASED.
, TYPE OF ACTIVITY : FISSION GASES, IODIN ES, AND PARTICULATES REPORTING PERIOD : QUARTER # 1 AND QUARTER # 2
r-----------------
- ELEVATED RELEASES : GROUND R ELEAS ES :
. : U NIT : QUARTER 1 : QUARTER 2 : QUARTER 1 : QUARTER 2 :
- : :H OU RS :HOU RS :H OU RS :HOU RS :
NUCLIDE : : 1-2160 :2161-4344 : 1-2160 :2161-4344 :
PARTICULATES U-3 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
NA-24 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CR-51 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
NN-54 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
HN-56 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
FE-55 : CURIES : 0. 00 E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
FE-59 : CU RIES : 0.0 0 E-01 : 0.00E-01 : 0. 00 E-01 : 0.00E-01 :
CD-58 i: CU RIES : 0.0 0 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CO-60 : CURIES : 0.00 E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
NI-63 : CURIES : 0.00E-01 : 0.0 0 E-01 : 0.00E-01 : 0.00E-01 :
NI-65 : CURIES : 0.0 0 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CU-6 4 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
Z N-6 5 : CU RIES : 0.0 0 E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
ZU-69 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
BR-83 : CURIES : 0.0 0 E-01 : 0.00 E-01 : 0.00E-01 : 0.00 E-01 :
BR-84 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
B R-85 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
RB-86 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
RB-88 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
RD-89 : CURIES : 0.0 0 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
SR-89 : CURIES : 0.00E-01 : 0.00E-01 : 0.00 E-01 : 1.67E-06 :
S R-91 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
SR-92 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
Y-91M : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-Cl :
Y-91 : CURIES : 0. 0 0 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
NOTE: Zero curies indicates activity was not detected, per Table A4.
L
Table B 2.1 Page 19 or zo REPORT CATEGORY : SEllIANilUAL AIRCORNE CONTINUOUS ELEVATED A!!D GROUT!D
fTYPE OF ACTIVITY : FISSION GAS ES, IODIN ES, AND PARTICULATES i REPORTING PERIOD : QUARTER i 1 AND QUARTER i 2
- ELEVATED RELEASES : G ROU ND RI: LEAS ES :
, : UNIT : QUARTER 1 : QUARTER 2 : QUARTER 1 : QUARTER 2 :
. : :HOU RS :H OU RS :llOU RS :llOU RS :
NUCLIDE : : 1-2160 :2161-4344 : 1-2160 :2161-4344 :
l PARTICULATES CONTINUED Y-92 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
Y-93 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00 E-01 : '
Z R-95 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
ZR-97 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
US-95 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
HO-99 : CU RIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TC-99M : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TC-101 : CU RIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
RU-103 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
RU-105 i: CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
RU-106 : CURIES : 0. 00 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
AG-110H : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TE-125M : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : i TE-127H : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : +
TE-127 : CURIES : 0.00E-01 : 0.00E-01 : 0.00 E-01 : 0.00E-01 :
TE-129H : CURIES : 0. 0 0 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
, TE-129 : CURIES : 0. 00 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TE-131!! : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
i TE-131 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
TE-13 2 : > CURIES : 0.0 0 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
I-130 : CURIES : 0.00 E-01 : 0.00E-01 : 0. 00 E-01 : 0.00E-01 :
i I-131 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 : ;
I-132 : CURIES : 0.00 E-01 : 0.00 E-01 : 0.00E-01 : 0. 00 E- 01 :
I-133 : CU RIES : 0.00 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
I-134 : CURIES : 0.00 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
I-135 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
i CS-134 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
- CS-136 : CURIES : 0.00 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
NOTE: Zero curies indicates activity was not detected, per Table A4.
l
A . - - - _ -
A- __
Table B 2.1 Page 20 of 26 T.EPORT CATEGORY : SEllIAll!!UAL AIRDORt1E CollTIllUOUS ELEVATED AND GROUllD
- L LVEL RELEAS ES. 'IDTALS FOR EACl! NUCLIDE RELEASED.
TYPE OF ACTIVITY : FISSION GASES, IODIN ES, AllD PARTICULATES REPORTING PERIOD : QUARTER # 1 AllD QUARTER # 2
- ELEVATED RELEASES : GROUND R ELEAS ES :
. : - UNIT : QUARTER 1 : QUARTER 2 : QUARTER 1 : QUARTER 2 :
- : HOURS :llOU RS :llOURS :llOU RS :
NUCLIDE : : 1-2160 :2161-4344 : 1-2160 :2161-4344 :
PARTICULATES CO!!TIl1UED CS-137 : CURIES : 0.00E-01 : 0 '. 0 0 E-01 : 0. 00 E-01 : 0.00E-01 :
CS-138 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
B A-13 9 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0. 0 0 E-01 :
BA-140 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
D A-141 : CURIES : 0. 0 0 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
B A-142 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
LA-140 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0. 00 E-01 :
LA-142 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CE-141 : CURIES : 0. 00 E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
CE-143 : CURIES : 0.00E-01 : 0. 00 E-01 : 0.00E-01 : 0.00E-01 :
CE-144 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
PR-143 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
PR-144 : CURIES : 0.00 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
ND-147 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
U-187 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : -
, HP-23 9 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
SR-90 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
G ALPl!A : CURIES : 0.0 0 E-01 : : 0.00E-01 : 0.00E-01 .
________________________________________________0.00E-01 ____ _________________________ .
TOTAL FOR PERIOD : CURIES : 0 .0 0 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 .:
NOTEi These small amounts of Sr-90 and alpha emitters were not detected, but were entered into the data base intentionally to overcome a software problem.
NOTE: Zere curies indicates activity was not detected, per Table A4.
Y u
' 9 r
. Table C 1.1 Page 21 of 26 REPORT CATEGORY : SEMIAMllUAL SUll!1ATION OF ALL RELEASES BY QUARTER TYPE OF ACTIVITY : ALL LIQUID EPPLUENTS
' REPORTING PERIOD : QUARTER # 1 AND QUARTER f 2
- UNIT : QUARTER 1 : QUAI}TER 2 :EST. TOTAL:
- :llOU RS :l!OU RS : ERROR % :
TYPE OF EPFLUENT : : 1-2160 :2161-4344 : :
A. FISSIO!! AND ACTIVATION PRODUCTS
- 1. 'IOTAL RELEASE (NOT INCLUDING : : : : ,
TR ITIUll, GASES, ALPHA) : CURIES : 0. 0 0 E-01 : 0.00E-01 :
- 2. AVERAGE DILUTED CONCENTRATION : : : :
DURING PFRIOD :UCI/ML : 0. 0 0 E-01 : 0. 0 0 E-01 :
B. TRITIUll
- CURIES : 0.00E-01 : 0.00E.01 :
- 1. '_IOTAL RELEASE
- 2. AVERAGE DILUTED CONCENTRATION : : : :
DURING PERIOD :UCI/l!L : 0.00E-01 : U.00E.01 :
C. DISSOLVED AND ENTRAINED G ASES
- 1. TOTAL RELEASE : CURIES : 0.00E 01 : 0.00E-01 : *
- 2. AVERAGE DILUTED CONCENTRATION : : : :
DURING PERIOD :UCI/ML : 0.00E-01 : 0.00E-01 :
- 3. PERCENT OF APPLICABLE LIIIIT : % : 0.00E-01 : 0.00E-01 :
D. GROSS ALPHA RADIOACTIVITY
- CURIES : 0.0 0 E-01 : 0.00E-01 : *
- 1. '_IDTAL _RELEASE E. WASTE VOL RELEASED (PRE-DILUTION) : GAL : 0.00E-01 : 9.95E 05 :
- F. VOLUME OF DILUTION WATER USED : GAL : 0.00E-01 : 2.84E 0 8 :
NOTE: Zero curies indicates activity was not detected, per Table A4 t
- Error estimates are given in Section A4.
b A-.
4
-' Table C 2.1 Page 22 of 26 REPORT CATEGORY : SE!!I AN!!UAL LIQUID CO!!TI!!UOUS A!!D B ATCH RELEASES ,
4
- TOTALS FOR EACH NUCLIDE RELEASED ,
TYPE OF ACTIVITY : ALL RADIO!10CLIDES REPORTING PERIOD : QUARTER # 1 A!!D QUARTER 4 2 li
. : UNIT : QUARTER 1 : QUARTER 2 : QUARTER 1 : QUARTER 2 :
. . : : HOURS :1100 RS : HOURS :HOU RS :
j NUCLIDE : : 1-2160 :2161-4344 : 1-2160 :2161-4344 :
i ALL NUCLIDES l H-3 : CU RIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
NA-24 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 .
4 CR-51 : CURIES : 0.00 E-01 : 0.00E-01': 0.00E-01 : 0.00E-01 :
UII-5 4 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 : ,
UH-56 -
- CURIES : 0.00E-01 : 0.0 0 E-01 : 0.00 E-01 : 0.00E-01 :
FE-55 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
FE-59 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
- CO-5 8
- : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
- CO-60 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
UI-63 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
UI-65 : CU RIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
CU-64 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
ZU-65 : CURIES : 0.00 E-01 : 0.00E-01 : 0. 0 0 E-01 : 0.00E-01 :
2 N-6 9 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
- ' BR-83 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
BR-84 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
BR-85 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
-RD- 86 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
- RE-88
- CURIES : 0.00 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
RB-89 : CURIES : 0.00E-01': 0.00E-01 : 0.00E-01 : 0.00E-01 :
SR-89 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
i SR-91 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0. 0 0 E-01 :
4 l SR-92 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
4 Y-91!1 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
Y-91 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
I l
NOTE: Measurement of P-32 and C-14 is not required per Table A4.
NOTE: Zero curies indicates activity was not detected, per Table A4.
i
= . _- ._ ,. . -. - - . - - . - - .. . . . . . . - . -
I Table C 2.1 Page 23 of 26 1
i 4 .
REPORT CATEGORY : SEMIANNUAL LIQUID CONTINUOUS AND BATCH PELEASES
- TOTALS FOR EACH NUCLIDE RELEASED.
TYPE OF ACTIVITY : ALL RADIONUCLIDES
! REPORTING PERIOD : QUARTER # 1 AND QUARTER # 2
7
, : UNIT : QUARTER 1 QUARTER 2 : QUARTER 1 : QUARTER 2 :
. : :H OU RS :H OU RS :H OU RS :H OU RS :
NUCLIDE : : 1-2160 :2161-4344 : 1-2160 :2161-4344 :
ALL NUCLIDES CONTIUUED
! Y-92 : CURIES ': 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
1 Y-S3 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
2 R.-95 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
2 R-97 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
j NB-95 : CU RIES : 0.00 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
' UO-99 : CURIES : 0.00 E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
l.TC-99M : CURIES : 0.00 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
i TC-101 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
- RU-103
- CURIES : 0. 00 E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
} RU-105 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
J RU-106 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : C.00E-01 :
- AG-110M
- CURIES : 0.00 E-01 : G .0 0 E-01 : 0.00E-01 : 0.00E-01 :
- ' TE-125M
- CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
TE-127M : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
, TE-127 : CURIES : 0. 0 0 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
1 TE-129M : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
- TE-129 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
! TE-1310 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00 E-01 :
i TE-131 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
- TE-132
- CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
i I-130 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
} I-131 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
I-132 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
! I-133 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
4 I-134 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
! I-135 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
i CS-134 : CURIES : 0.00 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
! .CS-136 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
i .
1 4
NOTE: Zero curies indicates activity was not detected, per Table A4.
f j . ,
Table C 2.1 Page 14 c,f 26 REPORT CATEGORY : SEliIAUNUAL L7 QUID CONTINUOUS AND BATG RELEASES
- TOTALS FOR EACH NUCLIDE RELEASED.
!. TYPE OF ACTIVITY : ALL RADIONUCLIDES
} REIORTING PERIOD : QUARTER 4 1 AND QUARTER 8 2 j ___________________________,_________________
l : CONTINUOUS RELEASES : BATCH RELEAS ES :
! . : UNIT : QUARTER 1 : QUARTER 2 : QUARTER 1 : QUARTER 2 :
- :llOU RS : HOURS : HOURS :H OURS :
UUCLIDE : : 1-2160 :2161-4344 : 1-2160 :2161-4344 :
i ALL NUCLIDES CONTINU ED CS-137 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
CS-13 8 : CURIES : 0.00E-01 : 0. 00 E-01 : 0.00E-01 : 0.00 E-01 :
l B A-13 9 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
1 BA-140 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
i B A-141 : CURIES : 0.00E-01 : 0.00E-01 : 0. 00 E-01 : 0.00E-01 :
1 B A-142 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00 E-01 :
LA-140 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
1 LA-142 : CU RIES : 0.00E-01 : 0.0 0 E-01 : 0.00E-01 : 0.00 E-01 :
CE-141 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.0 0 E-01 :
CE-143 i: CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
, CE-144 : CURIES : 0.00E-01 : 0. 0 0 E-01 :-0.00E-01 : 0.00E-01 :
} PR-143 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
PR-144 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
UD-147 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00 E-01 :
i W-187 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.005-01 :
! NP-239 : CURIES : . 0.00 E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
KR-83!! : CURIES : 0.00 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
KR- 85!! : CURIES : 0.00 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
I KR-85 : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
. KR-87 : CURIES : 0.00 E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
l KR-88 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
I KR-89 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0. 00 E-01 :
KR-90 : CURIES : 0.00E-01 : 0. 0 0 E-01 : 0.00E-01 : 0.00 E-01 :
XE-13111 : CURIES : 0.00E-01 : 0. 00 E-01 : 0.00E-01 : 0.00 E-01 :
, XE-133H : CURIES : 0.00E-01 : 0.00 E-01 : 0.00E-01 : 0.00E-01 :
XE-133 : CURIES : 0.00c-01 : 0. 0 0 E-01 : 0.00E-01 : 0.00E-01 :
XE-135M : CURIES : 0.00E-01 : 0. 0 0 E-01 : 0.00E-01 : 0.00E-01 :
f ZE-135 : CURIES : 0.00E-01 : 0.00E-01
- 0.00E-01 : 0.00E-01 :
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NOTE: Zero curies indicates activity was not detected, per Table A4.
L_ .J
. Table C 2.1 rage to or to REPORT CATEGORY : SE!!IANNUAL LIQUID CONTIllUOUS AND BATCll RELEASES
- TOTALS FOR EACil llUCLIDE RELEASED.
TYPE OF ACTIVITY : ALL RADIONUCLIDES REPORTING PERIOD : QUARTER # 1 AND QUARTER # 2
- COllTINUOUS RELEASES : BATCil RELEAS ES :
- UNIT : QUARTER 1 : QUARTER 2 : QUARTER 1 : QUARTER 2 :
- :llOU RS :llOU RS :llOU RS :llOU RS :
NUCLIDE ~ : : 1-2160 :2161-4344 : 1-2160 :2161-4344 :
ALL NUCLIDES CONTINU ED XE-137 : CURIES : 0. 0 0 E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :
XE-138 : CURIES : 0.00E-01 : 0. 0 0 E-01 : 0. 0 0 E-01 : 0.00E-01 :
AR-41 : CURIES : 0.00E-01 : 0. 0 0 E-01 : 0.00E-01 : 0. 0 0 E-01 :
SR-90 : CURIES : 0.00E-01 : 0. 0 0 E-01 : 0.00E-01 : 0.00E-01 :
G ALPIIA : CURIES : 0. 0 0 E-01 : 0. 0 0 E-01 : 0.00E-01 : 0.00E-01 :
OTfiER : CURIES : 0.00E-01 : 0. 0 0 E-01 : 0. 00 E-01 : 0.00E-01 :
TOTAL FOR PERIOD : CU RIES : 0.00 E-01 : 0.00E-01 : 0.00E-01 : U.UUE-01 :
NOTE: Zero curies indicates activity was not detected, per Table A4.
-4
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P.tge 26 of 26'
.i ad Table D 1.1 Solid Waste and Irradiated Fuel Shipmeats '
i No shipments of solid waste or irradiated fuel occurred during the period
. 'of this Report.
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. Wayne M.Jene
- Vee PnneJert Nuclear Operatons Detroit 6400 North Onue Highway IW Edison ~~~
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Au3ust 30, 19SS i --
OPwadons RC-LG-85-C032 1
Er, Jance C. Reppler !
Rc;ional Administrator pgt@1TY ROUTIEG Region III IEC 3gd U. S. Nuclear Regulatory Cocaission 799 ,,c a a s e v e l t Pead D_
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Glen Ellyn, Illinoic '2 0 1 3 7 M A #} ( __' -
Dear i. r . aeppler:
F lLi1L l W
~ FILE /
Leference. (1) Fermi 2 NRC Docket No. 50-341 (2) Attachment A to liRC Operating License Ho.
UPT-43 Technical Specification 6.9.1.8
Subject:
Ser i-Innual R;,td i o l o r ic a l Effluent Relence Report The initial Semi-Annual Effluent Release P.c p o r t for Feral 2 is attcched. This report is being trancaitted in compliance with Reference 2 and Regulatory Gu i.d e 1.21, Revision 1. Technical Specification 6.9.1.8 states that the initial report period is to b e ;; in with the date of initial c rit ic a li ty (i.e., June 21, 1935) and end on June 30, 1985. The attached report p rov id e s a more comprehensive sunmary in that it covers a period beginning uith issuance of the Fermi 2 low pouer license on March 20, 1985 and ending on June 30, 1935.
Picase direct any questionc or requests for add it iona l inforaation to '4 r . Robert L. Uoolley at (313) SG6-4211.
Sincerely, cc: It r . P. II . Byron l' r . !! . David Lynch Mr. C. C. Uright USURC Docucent Control Desk Usshington, D.C. 20555
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