ML20064A387
| ML20064A387 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 06/30/1990 |
| From: | DETROIT EDISON CO. |
| To: | |
| Shared Package | |
| ML20064A386 | List: |
| References | |
| NUDOCS 9009040140 | |
| Download: ML20064A387 (19) | |
Text
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l DETR0ff EDISON COMPANY ,
PEstMI 2 NUCLEAR POWER PLANT OPERATING USENSE NO. NPF. - 48 ,
SEMlANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT for the period of l
Januery 1,18s0 through June 30,1990
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, AuSust 1990 - 1 1
TABLE OF CONTENTS PAGE 1 1. Introduction
. l 1 2. Regulatory Umits
, 2 3. Maximum Permissible Concentration 3 4. Average Energy i
- 3. 5. Measurements and Approidmations of Total Activity l 7 8. Abnormal Releases 3 7.- Satch Releases .;
9 8. Uguld Effluent Summary ,
11 9. Gaseous Effluent Summary 14 10. Solid Weste and irradiated Fuel Shipments l
l.
14 11. Radiation instrumentation :
I 18 12. Changes to the Process Control Program (PCP) ,
16 13. Changes to Dose Calculation and Environmental Monitoring Locations ;
16 14. Changes to the Offsite Dose Calculation Manuel (ODCM) ,
l 16 15. Major Changes to Radioactive Weste Systems i Appendix A Revised ODCM Milk Sampling Tabik O
e
EtNuent Release Rep 3rt August 1990
- Page 1
- 1. 9NTRODUCTION The Detroit Edison Fermi 2 Nuclear Power Plant is designed and operate 6 to strictly control and monitor the release of radioactive effluents to the envirer.aent ln accordance with Nuclear Regulatory Commission (NRC) and Detroit Idison Company requirements. This Semlannual Radioactive Effluent Release Report is submitted in accordance with Fermi 2 Technical Specification 8.9.1.8 and NRC Regulatory Guide 1.21. This report provides the following informat6en requireo by those references:
- 1. Summat60n of the quantitles of radioactive meterial(in the form of gases and liquids) released from the plant and analysis of the radiological impact of these releases
- 1. Summation of quantitles of radioactive material contained in solid waste packaged and shipped far off-site disposal
- 3. Changes to the Process Control Program (PCP)
- 4. Changes to the Offsite Dose Calculation Manual (DDCM)
This report covers the period of January 1 through June 30,1990.
During the first half of 1990, the total gaseous and liquid radioactive effluent releases and resulting dose to the public were maintained As Low As Reasonably Achievable (ALARA). In accordance with Fermi 2 Technical Specification 6.9.1.8. the next Semiannual Radioactive Effluent Release Report--the one to be submitted within 60 days after January 1,1991--will contain dose assessments for all of 1990.
- 2. REGULATORY LIMITS The Nuclear Regulatory Commission limits on liquid and gaseous effluents are incorporated in the Fermi 2 Technical Specifications. These limits prescribe the maximum quantitles and rates of release for radioactive efficants resulting from normal operation of Fermi 2. The limits are defined in several ways to limit the overall impact on persons living near the plant. %e limits are described below:
A. Gaseous Effluents
- 1. Dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:
- a. Noble gases Less than or equal to 600 mrom/ year to the total body Less than or equal to 3000 mrom/ year to the skin
- b. lodine 131,133, tritium, and for all radionuclides in particulate form with half lives greater than 8 days Less than or equal to 1500 mrom/ year to any organ.
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Effluent Release Rep 3rt August 1990 Page 2 r
- 2. Air dose due to noble gases released in gaseous effluents from the reactor to areas at and beyond the alte boundary shall be llmited to the following:
- a. Less than or equal to 6 mrads9of m radiation <
Less than or equal to 10 mrada for s ..a rediation
-During any calender quarter
- b. Less than or equal to 10 mrada for gamma radiation ,
Less than or equal to 20 mreds for beta radiation
-During any calendar year
- 3. Dose to a member of the public from lodine-131,133, tritium, and all radionuclides in particulate form with half lives greater tt.an 8 days in gaseous offluents released from the reactor to areas et and beyo1d the alte boundary shall be limited to the following:
- a. Less than or equal to 7.5 mroms to any organ
-During any calendar quarter
- b. Less than or equal to Il mroms to any_ organ
-During any calendar year B. ' Liquid Effluents 1, The concentration of radioactive material released ln liquid affluents to.
unrestricted areas shall be limited to the concentrations speelfied in Title 10 of the Code of Federal Regulations Part 20 (Standards for Protection Against Radiation), Appendix 9. Table ll, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentrrtion shall be 46mited to 2E-4 (.0002) microcuries/mi total act ity.
- 2. The dose or dose commitment to a member M the public from radioactive materials in liquid effluents released from the reactor to unrestricted areas shall be limited to: ,
- s. Less than or equal to 1.5 mrom to tNo total body Less than or equal to 5 mrom to any organ
~During any calender quarter
- b. Less than or equal to 3 mrom to the total body Less than or equal to 10 mrom to any organ
-During any calender year
- 3. MAXIMUM PERMl851BLE CONCENTRATION (MPC)
Fermi 2 Technical Specifications implement the MPC requirements of 10 CFR 20 and NRC Regulatory Guide 1.21 by means of the following dose rate limits:
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Effluent Release Report August 1990 .
Page3
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A. . Geses l The dose rete due to passous effluents is seicuested in accordance with the Fermi 2 j Offsite Oose. Calculation Manuel (ODCM). The max 6 mum permissible dose rates for ;
gaseous releases are defined in Formi 2 Technical Specif6 cations:- ]
Technical Specification 3.11.1.1.s (Oose rete at the alte boundary from noble l gases): . j b
-Less than or equal to 500 mrom/ year to the total body
-Lass than or equal 30'3000 mrom/ year to the skin j Technical Spccification 3.11.1.1.6 (Dose rate at the alte boundary from I-131, 6-133, and particulates with half lives greater than 8 days):
-Loss than or equal to 1500 mrom/ year to any organ J
- 3. Liquids l
Allowable liquid release rates are calculated in accc,*dence with the Fermi 2 Offsite .
l Dose Calculation Manuel (ODCM). The maximum permissible concentration (MPC) for liquids used for these calculations are taken from 10 CFR 20, Appendix 8. Table 11, '
Column 2. The most restrictive MPC is used in all cases. For dissolved and entrained gases the MPC of 2E-4 microcuries/mi is applied. This MPC is based on the Xe-135 MPC in air (submersion dese) converted to en equivalent concentration in water as i discussed in the international Commission on Radiological Protection (ICRP)
Publication 2.
- 4. AVERAGE ENEROY The calculated site boundary dose rates for Fermi 2 are based on identification of Individual isotopes and on use of dose factors specific to each identified isotope or a highly conservative dose factor. Average energy values are not used in these calculations, and therefore need not be reported. , '
l S. MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY ;
As required by NRC Regulatory Guide 1.21, this section describes the methods used .
'o measure the total radioactivity in effluent releases and to estimate the overall -
errors associated with these measurements. The effluent monitoring systems are described in Chapter 11.4 of the Fermi 2 Updated 'inal Safety Analysis Report l (UFSAR).
A. Oaseous Effluents ,
1.
Fission and Activation Oases Samples are obtained from each of the seven plant radiation monitors which continuously monitor the six ventilation exhaust points and from the Offges Vent Pipe which carries the gland seal condenser exhaust. mechanical vacuum pump exhaust, and treated offges streams. The fission and a::tivation gases are quantified by gamma spectroscopy analysis of periodic samples. The following are typical fission and activation gases that are quantified for dose calculations:
I
Effluent Release Rep 3ft lx "
- August 1990 Page 4 Krypton (Kr)-85 n Xenon (Xe)-133 Xenon (Xe)-135 Xenon (Xe)-135m Xenon (Xe)-137 Xenon (Xe)-138 Argon (Ar) The values reported in Sect 6oh p are the sums of all fission and activation gases quantified at all monitored rNesse points.
Considering the inherent variability in radiation measurement, the variability in effluent stream composit6on, and the uncertelnt6es in effluent flow rate and ~
instrument calibration D@roit Edison estimates that the oncertainty of the
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fission and activation gas total release figures is less than plus or minue 8 percent.
- 3. Radiolod6nes Samples era obtained from each of the seven plant radiation monitors, which continuously monitor the six ventilation exhaust points. The radiolodines are entrained on charcoal and then queattfled by gamma spectroscopy analysis.
For each sample the duratloa. Or sampling and continuous flow rate through the charcoal are use,d e, determining the concentration of radiolodines. From the flow rate of the ventilation system a rate of release can be determined.
The radiolodines usually quantified for dose calculations are the following:
lodine (t)-131 lodine (1)-132 lodine (1)-133 lodine (I)-135 The values reported in Section 9 are the sums of all radiolodines quantified at all continuously monitored release points.
Considering the inherent variability in radiation measurements, the variability in effluent stream composition, and the uncertainty in sample and effluent flow rates, Detroit Edison estimates that the uncertainty of the total radiciodine release figures is less than plus or minus 5 percent.
- 3. Particulates Samples are obtained from each of the seven plant effluent radiation monitors, which continuously monitor th'six ventilation exhaust points. The particulates are collected on a filter and then quantified by gamma spectroscopy analysis.
For each sample the duration of sampling and continuous flow rate through the futer are used in determining the concentration of particulates. From the flow rate of the ventliation system a rate of release can be determined.
Radioactive activation and fission products that are typically found include the following:
Manganese (Mn)-54 Iron (Fe)-59 Cobalt (Co)-58
. Cobatt (Co)-60 Zinc (Zn)-65 Chromium (Cr)-51 Barium (Ba)-139 Barium (Be)-140 Lanthanum (La)-140 Yttrium (Y)-91m Strontium (Sr)-91 Rubidium (Rb)-89 Cesium (Cs)-138 Technetium (Tc)-99m U
Effluent Release Report ;
App;st 1990 !
page 5 c w l A compostte of the fitters from each ventilation release point are analysed monthly for gross alpha radioactivity using gas proportional counting i methods. Quarterly the filters are radiochemically separated and analyzed for c Strontium (Sr)-89/90 using various analytical methods, if found these me6onucl6 des are reported as, total particulate act6vity.
l TM values reported in Section 9 are the sums of all particulates quantif6ed at *
. all r.90nitored release points. .
Considering the inherent verleblitty in radiation measurements, the verlsbility in effluent stream composition, and the uncertaintles in instrument sal 6bration ,
and in sample and effluent flow rates, Detroit Edison estimates that the the ;
uncertainty of the total particulate release figures is less than plus or minus 3 ;
percent. ,
- 4. Tritium Samples are obtained for each of the seven plant effluent radiation monitors which continuously monitor the six ventilation exhaust points. The sample is j passed through a bottle containing water and the tritium is
- washed" out to '
the collecting water, portions'of the collecting water are analyzed for tritium us6ng liquid scintillation counting techniques. For each sample, the duration of ;
sample and sample flow rate is used to determine the concentration. From ,
the flow rate of the ventlistion system a release rate can be determined.
The values reported in Section 9 are the sums of all tritium quantified at all
- monitored release points.
Considering the inherent verlability in radiation measurement, the variability in ,
effluent stream composition, and the uncertainties in instrument calibration, sample and effluent flow rates, and collection efficiency, Detroit Edison estimates that the uncertainty of total gaseous tritium release figures !s less than plus or minus 34 percent. ;
- 5. Gross Alpha }
The gaseous particulate filters from the seve') plant effluSnt radiation monitors are stored for one week to allow for decay of naturally occurring alpha emitters. These filters are then analyzed for gross alpha radioactivity by gas proportional counting, and any such radioactivity found is assumed to be plant l-related. The quantity of alpha r c.itters released can then be determined from l sample flow rate, sample duration, and stack flow rate.
. t The values reported in Section 9 are the sums of all sipha emitters quantified at all monitored release points. -
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% h Etnuent Release Report August 13g0 Page 8 !
Cons 6dering the 6nherent var 6 ability in red 6stion measurements, the variability in ,
effluent stream temposition, and the uncertainties 6n instrument calibration j and in sample and enivent flow rates, Detroit Edison estimates that the uncertainty of the total passous gross alpha release i6sures is less than plus or minus 10 percent. .
B. Liquid Effluents The liquid redweste processing system and the 164uld effluent monitoring system are described in the Fermi-2 UFSAR.
- 1. Fission and activation products j Before the contents of each holding tank is discharged to the env6tenment, a l representative sample of the tank's contents is taken and retained. The j sample allows for the determination of red 60setive mater 6al concentrations and !
establishes the rate at which the radioactive material can be discharged to the environment. Radioactive activation and f6ssion produsts that tre typically a
found include the following:
-i g,
Manganese (Mn)-64 tron (Fe)-Eg Chromium (Cr)-51 .
Cobalt (Co)-SS Cobalt (Co)-80 Silver (Ag)-110m l Zinc (Zn)-86 Sarium (84)-131 Technetium (Tc)-ggm j At the end of the calender quarter a composite sample is enade of all ,
discharge samples taken during the quarter. This compos 6te sample consists l of portions of each discharge sample which are proportional to the volumes l' I- discharged. The composite sample is analysed for Iron (Fe)-66 and Strontium (Sr)-8g/g0. Radiochemical separations and various analytical methods are used to quantify the amounts of St-Sg/g0 and Fe-ll.
The values reported in Section 8 are the sums of all fission and activation ;
products found in all batch releases. ;
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Considering the inherent verlability in radlaitlen measurement and the uncertainties in volume measurements and instrument calibration, Detroit ,
Edison estimates that the uncertainty 6n total liquid fission and activation product release figures is less than plus or minus 5 percent. .
- 2. Tritium i Before the coatents of each holding tank is discharged to the environtrent, a representative sample of the tank content:la taken and retained. At the end (
of the calender month a composite sample is made of all discharge samples taken during the month. Tf.!s composite sample consists of portions of each discharge sample which are proportional to the volumes discharged. The >
composite sample is analyzed for tritium by liquid scintillation counting.
Sffluent Release Report i-
- August 1990 Pope 7 The values reported 6n Sec'6en 8 sums all tritium quantified from all batch rolesses.
Consider 6ng the 6nherent variability in redlet6on measurement and the oncertainties in volume measurement and instrument cellbration, Detroit Edison est6 mates the uncertainty in total tritium rolesse f6guF. la less then -
plus or minus il percent.
- 3. Dissolved and Entrained Geses Pr6er to releasing 164968 radioactive weste to the environment a sample is taken from the redweste holding tank. This semple is representative of the tank's contents. The semple is enemined using gamma spectroscopy to determine the dissolved and entralned noble gases. The following radiogeses are typical of those which may be found:
Xenon (Xe)-133 Xenon (Xe)-135 The values reported 6n Section 8 are the sums of all redlogeses found for all batch releases.
Considering the inherent verlebility in radiation measurement and the uncertelnties in instrument calibration and volume measurements, Detroit Edison estimates that the uncertainty in total dissolved and entrained gas release figures is less than plus or minus 15 percent.
- 4. Gross Alpna gefore the .Jntents of each holding tank is dischstged to the environment, a representative sample of the tank's contents is taken and retained. At the end of the calender month a composite sample is made of all discharge semples taken during the month. This composite sample consists of portions of each discharge semple which are proportional to the volumes discharged. The composite semple is analysed for gross alphe radioactivity by gas proportional counting. 2 The values reported in Section 8 a.'s the sums of the gross alpha radioactivity from all batch releases.
Considering the inherent variability in radiation measurement and the uncertainty in volume measurements and instrument cellbration, Detroit Edison estimates that the uncertainty in total liquid gross alpha release figures is less than plus or minus 43 percent .
- a. ABNORMAL RELEASES for the purpose of this report, en abnormal release is any release of radioactive material not performed in accordance with the Fermi 2 license and implementing procedures. No abnormal releases occurred during the reporting period.
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I Ifttuent Release Report !
App';st 1990 '
page 8
- 7. BATCH RELEASES As required by ReSulatory Guide 121. e summary of date for batch releases is provided below The following batch liguld releases from redweste holding tanks to l the Circulating Water Decent L6ne occurred between January 1,1990 and June 30. l 1990: ]
Number of releases: 12 i Total time for all releases: 5549 minutes '
Menimum time for a release: 583 minutes Average timt for a release: 462 minutes Minimum time for a release: 427 minutes )
1,,e only bete .essous ,eiesses ,,om re,mu e,e t,,e .emi,,3 0, purgi,,g of t,,e !
primary containment (drywell) etmosphere. These venting or purging releases pass through the reactor building ventilation or standby gas treatment system and are monitored by the final effluent monitors for these pathways. Separate date on these i venting or purging releases are not reported because the associated date are already included in the gaseous effluent release date (Section 5.A and Sect 60n 9),
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- Efnuent Release Rep 3r1 l August 1990 Page 9 i l
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- a. uou D PFLutwT suuuARY l
, REPORT CATE00RY : SEMIANNUAL SUMMMATION OF ALL RELEASES SY OUARTER TYPE OF ACTIVITY : ALL UQUID EFFLUENTS l REPORTING PERIOD : QUARTER 1 AND OUARTER 2 l 1
- UNIT : QUARTER 1 : QUARTER 2 TYPE OF EFFLUENT : : :
A FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDINO TRITIUM, OASES, ALPHA) : CURIES : 1.92E-01 :205E-02 I
- 2. AVERAGE DILUTED CONCENTRATION DURINO PERIOD :UCl/mi : 2.21E-08 : 3.01E-09 1 l
- 3. TRITIUM
- 1. TOTAL RELEASE : CURIES : 6.91E-01 :5.56E-02
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD : UCl/mi : 7.95E-08 : 6.33E-09 1
C. DISSOLVED AND ENTRAINED GASES ,
- 1. TOTAL RELEASE : CURIES : 2.09E-04 : 1.02E-04 l 2. AVERAGE DILUTED CONCENTRATION I
DURING PERIOD : vCl/mi : 2.41E-11 : 1.16E-11 .
l 0. OROSS ALPHA RADIOACTIVITY I
l 1. TOTAL RELEASE : CURIES : 0.00E+00 '
- 0.00E+00 l
l NASTE VOL RELEASED l (PRE-DILUTION) : LITERS : 7.69E+05 : 6.48E+04 F. TOTAL VOLUME DILUTION DISCHARGED : LITERS : 8.69E+09 : 8.79E+09
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'I Effluent Release Repor* 3 AuSust 1990 ee9e i0 l S. LIOUID SFFLUSNT
SUMMARY
(continued) )
1 l
REPORT CATEGORY : SEMIANNUAL UQUID SATCH RELEASES TYPE OF ACTMTY : TOTALS FOR EACH NUCUDE RELEASED
- ALL RADIONUCUDES ,
REPORTINO PERIOD : QUARTER l' AND QUARTER 2 l
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- SATCH RELEASES
- UNIT : QUARTSR 1 : QUARTER 2 :
NUCUDE : : :
ALL NUCLIDES H-3 : CURIES :8.91E-01 :5.56E-02 No-24 : CURIES : 4.48E-02 :8.23E-03 Cr-51 : CURIES : 1.27E-01 : 1.59E-02 Mn-54 : CURIES : 7.00E-04 : 8.62E-05 Co-88 : CURIES : 1.38E-03 : 1.93E-04 Co-60 .
- CURIES : 1.03E-03 : 1.51E-04 l :* < 1.7E-06 2n-65 : CURIES :2.34E-03 l Mo-99 : CURIES : 2.47E-03 : 4.15E-04 l Tc-99m : CURIES : 7.42E-03 : 1.03E-03 l-131 : CURIES : 2.43E-04 : 4.W-05 '
l-133 : CURIES :5.49E-04 : 1.44E-04 Xe-135 : CURIES : 2.09E-04 : 1.02E-04 St-89 : CURIES : 1.04E-04 : 3.20E-06 Sr-90 : CURIES : 5.45E-07 :* < 6.5E-09 Fe-55 : CURIES :6.47E-05 :* < 8.7E-07 Se-131 : CURIES : 1.61E-04 :* < 8.6E-07 A9-110m .URIES : 9.28E-06 :* < 1.7E-06 W-187 ' 'ilES : 2.78E-04 :*<1.4E-06 As-76 : .JRIES 1 : 2.42E-03 : 2.81E-04 ,
Sb-122 : CURIES : 1.84E-04 :* < 4.9E-07 Cs-134 : CURIES :* < 3.8E-07 :* < 3.8E-07 Cs-137 : CURIES :*<4.5E-07 :*<4.5E-07 Co-141 : CURIES :* < 4.9E-07 :*<4.9E-07 Co-144 : CURIES :* < 2.3E-06 :* < 2.3E-06 Total for Period : CURIES : 8.83E-01 : 8.21E-02
- Less then Lower Limit of Detection (LLD),i.e. the maximum sensitivity of measurement,in units l
I of microcuries per milliliter (uCl/ml).
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Eftfuent R;l:ese Reptrt !
August 1990 i Pepe 11 !
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I S. SASSOUS SPFLUENT
SUMMARY
REPORT CATEOORY : SEMIANNUAL SUMMMATION OF ALL RELEASES SY OUARTER TYPE OF ACTIVITY : ALL AIRBORNE EFFLUENTS REPORTING PERIOD : QUARTER 1 AND QUARTER 2
- UNIT : QUARTER 1 : QUARTER 2 !
TYPE OF EFFLUENT : : : i I
A. FlSSION AND ActVATION OASES l
- 1. TOTAL Al LEMf : CURIES : 2.91E+01 :8.47E+01
- 2. AVERAGE AELEASE RATE FOR PERIOD : uCl/sec : 3.74E+00 : 1.08E+01
- 9. RADIOIODINES r
- 1. TOTAL IODINE - 131 : CURIES : 9.52E-04 : 1.35E-03
- 2. AVERAGE RELEASE RATE FOR PERIOD : uCl/sec : 1.22E-04 : 1.72E-04 C. PARTICULATES
- 1. PARTICULATES (HALF-LIVES >8 DAYS)
CURIES 4.17E-03 2.44E-03 _
- 2. AVERAGE RELEASE RATE FOR PERIOD : uCl/sec :5.36E-04 : 3.10E-04 ,
- 3. GROSS ALPHA RADIOACTIVITY : CURIES : 6.59E-07 : 8.20E-07 D.TRfTIUM
- 1. TOTAL RELEASE : CURIES : 0.00E+00 : 0.00E+00
- 2. AVERAGE RELEASE RATE FOR PERIOD : uCl/sec : 0.00E+00 : 0.00E+00 4
9
Effluent Release Meport s
1 App;st 1990 Pe0s 12
- 9. SA88008 5%U89ff SUMMAR: (eentinued)
REPORT CATEGORY :8EMLANNUAL AIRBORNE CONTINUOUS RELEASES TYPE OF ACTMTY :Fl8810N OASE8,10 DINES, AND PARTICULATES REPORTING PERIOD : QUARTER 1 AND QUARTER 2
- MIXED MODE RELEASE 5
- UNIT :OUARTER 1 : QUARTER 2 NUCUDE PARTICULATE 5 Cr-51 : CURIES :8.30E-03 : 1.77E-03 Mn-54 : CURIES : 1.03E-05 :8.02E-05 Fe-59 : CURIES :*<1.5E-13 : 7.82E-06 Co-58 : CURIES :1.775-05 : 4.44E-05 Co-60 : CURIES : 1.70E-05 : 5.678-05 No-24 : CURIES :6.49E-03 : 1.69E-03 2n-65 : CURIES :2.88E-05 : 7.78E-05 Tc-99m : CURIES : 1.10E-02 : 5.07E-03 Ba-139 : CURIES : 7.69E-01 :6.30E-01 8a-140 : CURIES :5.50E-04 : 2.77E-04
'La-140 : CURIES : 3.66E-04 : 1.90E-04 Y-91m : CURIES : 4.54E-03 : 3.26E-03 St-91
- CURIES : 7.93E-03 :5.18E-03 Sa-131 : C O N T. :* < 1.2E-13 : 1.11E-06 As-76 : CURidS :5.87E-05 : 1.03E-04 Rb-99 : CURIES : 2.76E-01 : 6.79E-01 -
Cs-138 : CURIES : 4.17E-01 : 3.03E-01 Mn-56 : CURIES : 3.58E-04 : 1.24E-03
- CURIES :*<1.6E-13 : 3.29E-05 A9-110m
.So-75 : CURIES :*<5.BE-14 : 5.11E-07 2n-69m : CURIES : 1.66E-05 : 1.17E-05 W-187 : CURIES :* < 1.6E-13 : 4.14E-05 Sr-89 : CURIES :2.41E-04 : 1.38E-04 Sr-90 : CURIES : 3.10E-06 : 1.34E-06 Cs-134 : CURIES *- :*<5.1E-14 :*<5.1E-14 Co-137 : CURIES :*<6.4E-14 :* < 6.4E-14 Co-141 : CURIES :*<6.9E-14 :*<6.9E-14 Co-144 : CURIES :* < 2.9E-13 :* < 2.9E-13 Total for Period : CURIES : 1.50E+00 : 1.63E+00
- Less than the Lower Limit of Detection (LLD), l.a. the maximum sensitivhy of measurement in units of microcuries per milliliter (uCL/ml) .
-4
Effluent Release Report August 1990 l Pope 13 i
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! 8. 8488008 SFPLUENT
SUMMARY
(eentinued)
MEPORT CATEGORY : SEMIANNUAL AIRSORNE CONTINUOUS RELEASES d
TYPE OF ACTIVITY : FISSION GASES, IODINES, AND PARTICULATES REPORTING PERIOD : QUARTER 1 AND QUARTER 3 l
i
- MIXED MODE RELEASES ;
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- : UNIT GUARTER1 : QUARTER 2 1 980eL9E : : :
FISSION GASES l'
Ar-41 : CURIES : 1.60E+01 : 7.11E+01 Xe-135m : CURIES : 9.72E-01 : 1.03E+00 Xe-138 : CURIES : 3.38E+00 : 2.29E+00 Xe-135 : CURIES : 1.10E-01 : 1.82E-01 Kr-85m : CURIES :8.55E-01 : 9.59E-01 Xe-137 : CURIES : 7.01E+00 :6.43E+00 Kr-87 : CURIES :* < 5.3E-08 : 1.18E-01
. )
Kr-88 : CURIES : 3.87E-01 :8.99E-01 Kr-89 : CURIES : 1.25E+00 : 1.31E+00 Xe-133 : CURIES : 3.17E-01 : 3.41E-01 Total for Period : CURIES : 2.91E+01 :8.47E+01 l-tODINES l-131 : CURIES : 9.52E-04 : 1.35E-03 6-132 : CURIES : 1.88E-03 : 1.33E-02 1-133 : CURIES . : 4.20E-03 : 1.12E-02 1-134 : CURIES 5 :* < 2.0E-13 : 2.84E-03 6-135 : CURIES : 2.84E-03 : 1.83E-02 Total for Period : CURIES : 9.45E-03 : 4.50E-02
- Less than the Lower Limit of Detection (LLD), l.a. th( aeximum sensitivity of measurement in units of microcuries per milliliter (uCl/ml) l j
- - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ . + . . . , _ , . , _ . _ , , . , _ , , , . . , , _ _ _ , , _ , , _ _ , _ , _, ,
i ani.ent neie.se R.,m August 1990 Page 14
- 10. 80lJD WASTE AND IRRA04ATED PUBL SHIPMENTS A. Solid Weste Shipped Offsite for burial or disposal (not 6rroelsted fuel) 5 month Est. Total
- 1. Yvoe of Weste Unit oeriod Error %
3 +25
- e. Spent res6ns,960ter stodges, m 1.58E+02 ,
overeretor bottoms, etc. Curles 7.12E+02 a25
- b. Dry compressible weste, mI 1.85E+02 +25 contaminated ete!= ment, etc. Curles 1.33E+01 I25
- c. Irradiated components, control rods, etc. O
- d. Other 0 2 Estimate of major nuclide composition (by tvos of waste) _
- a. Spent resins, filter sludges, evaporator bottoms, etc.
percent of Nuclide Total Activity Curles Cr-51 4.5 321E+01 Mn-54 10.5 7.47E+01 Fe-55 53.5 3.81E+02 Co-58 3.1 2.21E+01 Co-60 12.4 S.83E+01 Fe 0.4 3.18E+00 Ni-63 0.4 : 3.04E+00 En-85 14.2 1.01E+02 to-131 40.1 1.18E-01 H-3 0.1 7.96E-01 C-14 0.2 1.73E+00 Ag-110m 0.5 3.87E+00 Tc-99 <0.1 1.16E-03 6-129 <0.1 4.68E-04 Co-144 <0.1 1.56E-01 Cm-243/244 <0.1 3.29E-03 4
f f August 1990
. . Page il
- b. Dry compressible waste, contaminated equipment, etc.
Percent of Nucl6de Total ActivMy Curles Cr-51 2.4 3.52E-01 Mn-54 6.3 9.04E-01 Fe-55 78.7 1.02E+01 Co-53 1.8 2.44E-01 Co-60 10.2 1.35E+00 Ni-83 0.3 3.40E-02 Tc-99 <0.1 5.19E-04 C-14 <0.1 1.45E-03 Fe-59 1.2 1.44E-01 1-129 <0.1 5.85E-04 Note: Ast6vitise of all prinalpel redienuelldes were determined by measurement.
- 3. Solid Weste Disposition (All weste was Class A and was shipped in LSA containers)
Type of shipment / Number of Mode of solidification process shipments Transport. Destination Dewatered resin 20 truck Bernwell SC Dry active waste and 3 truck Oak Ridge. TN contaminated equipment 2 truck Channehon. IL 1 truck Bernwell. SC
- 4. Irradiated Fuel Shipments: I None T
3
[' .g Effluent Release Rep 3rt ir August 1990
.. - P:pe it
- 11. RADIATION INSTRUMSNTATION
. Fermi 2 Technical Specifications 3.3.7.11, Radioactive uguld Effivent Monitoring betres.entation, and 32.7.12, Red 60setive Gessous Effluent Monitoring i instrumentation, require that those monitors which escoed the time specified for out
- of service be reported in the next Semleanuel Effluent Release Report. During this reporting period, January through June of 1990, the time specified in the action statements for these monitors was not exceeded.
- 12. CHANOSS 70 TME PROCESS ONTROL pM00 RAM (pCp)
As required by the Formi 2 Iloonse the operator (Detroit Edison) is required to estabilsh a program that will reasonably assure the complete processing of radioactive westes. This program assures processed westes are completely solidified
. and are free of standing water. Changes to the PCp Manuel are provided to document changes to established conditions and to ensure that controls are in place to assure that the radioactive weste is solidified.
During this reporting period, January through June of 1990, there were no changes to the PCp.
it. CHANGES TO DOSE CALCULATION AND ENVIRONMENTAL MONITORING LOCAtl0NS During March 1990, the milk sempling control location et 7512 N. Custer Rd. (Doty d Ferm) dropped out of the Radiological Environmental Monitoring Program, in April 1990, e new milk sampling control location at g334 Finsel Rd. (Calder Form) was i t added to the program. This location is 15.74 km from the reactor and is in the WNW
! sector et 287 degrees. The ODCM page reflecting this change is shown as Appendix A as it will appear in the next ODCM revision.
l
- 14. CHANGEE TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM) ,
During this reporting period, January through June of 1990, there were no changes to I the ODCM. :
- 18. MAJOR CHANGES TO RADICACTIVE WASTE SYSTSMS l
During this reporting period, January through June of 1990, there were no major changes to the liquid, gaseous or solid radioactive weste treatment systems. H j
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