ML20090A437
| ML20090A437 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 12/31/1991 |
| From: | Orser W DETROIT EDISON CO. |
| To: | |
| Shared Package | |
| ML20090A441 | List: |
| References | |
| NUDOCS 9203020335 | |
| Download: ML20090A437 (38) | |
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DETROIT EDISON COMPANY FERMI 2 NUCLEAR POWER PLANT Ol'F. RATING LICENSE NO. NPF - 43 SEMlANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT for the period of July 1.1991 through December 31,1991 h..
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. Effluent Release Report February 1992 PREFACE The Fermi 2 Nuclear Power Plant maintains a comprehensive program of monitoring and controlling the release of radioactive material from the site. The releases covered in this report are of three types: liquid releases, gaseous releases, and radioactive waste shipments.
In a liquid release, a tank containing radioactive water is sampled prior to discharge.
Based on the analysis of this sample, both the amount of radioactivity in the tank and the potential radiation dose to a member of the public are determined, and these figures are compared to federal limits. In calculating the radiation dose, very conservative assumptions are used. For example, it is assumed that an individual eats 46 pounds of fish per year from Lake Erie directly offshore of the Fermi 2 plant. The tank may be released only after it is determined that no federal limits are exceeded. As the tank is released, the contents of the tank are diluted by clean water in a ratio of approximately 400 gallons of clean water to one gallon of tank water. The release is continuously monitored by radiation detectors. In the second half of 1991, there were three liquid releases, down significantly from previous years. This small number is due 10 the plant operating in a steady state condition since the second refueling ending in June 1991.
Radioactive gaseous releases occur as part of the normal operation of Fermi 2. There are six ventilation system release points, or " stacks", each of which is monitored by a sophisticated radiation monitor which continuously extracts a sample from the stack effluent. Since any gaseous radioactive material is diluted by the building ventilation air flow, the stack concentrations are small. In fact, radioactive material is not detected in most stack samples. All sample results are compared with feder.'l limits to ensure they are not exceeded. If the amount of radioactivity in the effluent o:. any stack approaches a federal limit, an alarm will be activated in the Fermi 2 control room to alert operations personnel. After evaluating the situation, the operators may choose to order increased sampling, shut down building ventilation, or divert the effluent stream to a special gaseous treatment system so that federal limits are not exceeded. in the second half of 1991, gaseous releases were comparable to levels seen in previous non-c,utage periods, reflecting stable operating (.onditions.
Radioactive shipments of solid waste from the Fermi 2 site consist of waste generated
(
during water treatment, radioactive trash, and irrsdiated components. Federal regulations governing these shipments are extensive, and Formi 2 also complies with internal procedures. Shipment destinations are either licensed burial sites or intermediate
-processing facilities. In the second half of 1991, Fermi 2 did not ship any radioactive waste due to the exclusion of Michigan licensees from the burial sites.
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Efflu:nt Releass R: port February 1992 TABLE OF CONTENTS PAGE 1.
Introduction 1
2.
Regulatory Limits 1
3.
Maximum Permissible Concentration 3
4.
Average Energy 3
5, Measurements and Approximations of Total Activity 4
6.
Abnormal Releases 8
7.
Batch Releases 8
8.
Liquid Effluent Summary 9
9.
Gaseous Effluent Summary 11 10.
Solid Waste and irradiated Fuel Shipments 14 11.
Radiological Impact on the Public 14 12.
Radiation instrumentation 16 13.
Meteorological Data Summary 16 14.
Changes to the Process Control Program (PCP) 17 15.
Changes to Dose Calculation and Environmental 17 Monitoring Locations 16.
Changes to the Offsite Dose Calculation Manual (ODCM) 17 17.
Major Changes to Radioactive Waste Systems 17 18.
Liquid Holdup Tanks Exceeding Limits 17 Appendix A: Meteorological Data Tables Appendix B: Process Control Program Manual
A-Effluent Rslaase Report February 1992 Page_1 1.
INTRODUCTION The Detroit Edison Fermi 2 Nuclear Power. Plant is designed and operated in a manner
-which strictly controls and monitors the release of radioactive material to the environment in accordance with Nuclear Regulatory Commission (NRC) and Detroit Edison Company requirements. This Semlannual Radioactive Effluent Release Report, for the July through December 1991 period, is submitted in accordance with Fermi 2 Technical Specification 6.g.1.8 and NRC Regulatory Guide 1.21, This report provides the following information required by those references:
1.
Summation of the quantities of radioactive material (in the form of gases and liquids) released from the plant (Sections 8 and 9) 2.
Summation of quantitles of radioactive material contained in solid waste packaged and shipped for off-site disposal (Section 10) 3.
Changes to the Process Control Program (PCP) (Section 14) 4.
Changes to the Offsite Dose Calculation Manual (ODCM) (Section 16) 5.
A list and description _of any unplanned releases of radioactive materials to unrestricted areas (Section 6)
- 6.
A list of any new locations for dose calculation or environmental monitoring identified by the land use census (Section 15) 7.
A list of effluent monitors which were inoperable for a period longer than that specified in Technical Specifications 3.3.7.11 and 3.3.7.12, and an explanatiori of why the time limit was exceeded (Section 12) 8-A description of _ events leading up to any liquid holdup tanks exceeding the limit of Technical Specification 3.11.1.4 (Section 18) 9.
A description of any major changes to radioactive waste treatment systems i
_ (Section 17) l 10.
- An assessment of the radiological impact on the public in terms of dose due to liquid and gaseous effluents, both to the maximally exposed individual and to the population with a_50 mile radius of the plant (Section 11) 11.
A summary of 1991 meteorological data (wind spe.od and wind direction for different stability classes) which was used in calculating gaseous dispersion factors (Section 13)-
2.
REGULATORY LIMITS The Nuclear Regulatory Commission limits on liquid and gaseous effluents are incorporated in the Fermi 2 Technical Specifications. These limits prescribe tne maximum quantities and rates of release for radioactive effluents resulting from normal operation of Fermi 2. The hmits are defined in several ways to hmit the overall impact on persons living near the plant. The limits are aescribed in the following sections.
Eftluent R313ase Report February 1992 Page 2 A. Gaseous Effluents 1.
Dose rate due to radioactive materials released in geseous 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 500 mrem / year to the total body Less than or equal to 3000 mrem / year to the skin b.
10 dine 131,133, tritium, and for all radionuclidos in particulate form with half lives greater than 8 days Less than or equal to 1500 mrem / year to any organ.
2.
Air dose due to noble gases released in geseous effluents to areas at and briond the site boundary shall be limited to the following:
a.
Less than or equal to 5 mrads for gamma radiation Less than or equal to 10 mrads for beta radiation
-During any calendar quarter b.
Less than or equal to 10 mrads for gamma radiation Less than or equal to 20 mrads 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 than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:
a.
Less than or equal to 7.5 mrems to any organ
-During any calendar quarter b.
Less than or equal to 15 mrems to any organ
-During any calendar year B.
Liquid Effluents 1.
The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in Title 10 of the Code of Federal Regulatior.s Part 20 (Standards for Protection Against Radiation), Appendix B Table Il Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 (.0002) microcuries/ml total activity.
2.
The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the values in the following sections.
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. Effluont Release R0 port February 1992 Page 3 a.
Less than or equal to 1.5 mrem to the total body Less than or equal to 5 mrem to any organ
-During any calender quarter b.
Less than or equal to 3 mrem to the total body Less than or equal to 10 mrem to any organ
-During any calender year 3.
MAXIMUM PERMISSIBLE 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 limits:
A.
Gases The dose rate due to gaseous effluents is calculated in accordance with the Ferml 2 Offsite Dose Calculation Manual (ODCM) The maximum permissible cose rates for gaseous releases are defined in Fermt 2 Technical Specifications:
Technical Specification 3.11.2.1.a (Oose rate at the site boundary from noble.
gases):
-Less than or equal to 500 mrem / year to the total body
-Less than or equal to 3000 mrem / year to the skin -
Technical Specification 3.11.2.1.b (Oose rate at the site boundary from I-131, 1-133, and particulates with half lives greater than 8 days):
-Less than or equal to 1500 mrem / year to any organ B.
Liquids Allowable liquid release rates are calculated in accordance-with the Fermi 2 Offsite Dose Calculation Manual (ODCM). 'As required by Technical Specification 3.11.1.1, the
- maximum permissible concentrations (MPC) for liquids used for tnese calculations are taken from 10 CFR 20. Appendix B, Table ll, 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 dose, converted to an equivalent concentration in water as discussed in the international Commission on Radiological Protection (ICRP) Publication 2.
4.
- AVERAGE ENERGY 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.
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Effluent R313aso R: port February 1992 Page 4 1
5.
MEASUREMFNTS AND APPROXIMATIONS OF TOTAL ACTIVITY As required by NRC Regulatory Guide 1.21, this section describes the methods used to 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 Final Safety Analysis Report (UFSAR).
A.
Gaseous Effluents 1.
Fission and Activation Gases 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, mecnanical vacuum pump exhaust, and treated of10as streams. The Offgas Vent Pipe effluent is released through one of the six ventilation exhaust points (the reactor buildinD erhaust plenum). The fission and activation gases are quantified by gamma spectroscopy analysis of periodic samples.
The value; raported in Section 9 are the sums of all fission and activation gases quantified at all monitored release points.
Considering the inherent variability in radiation measurement, the variability in effluent stream composition, and the uncertainties in effluent flow rate and instrument calibration, Detroit Edison estimates that the uncertainty of the fission and activation gas total release figures is less than plus or minus 8 percent.
2.
Radiolodines Samples are obtained from each of the seven plant radiation monitors, which continuously monitor the six ventilation exhaust points. The radiciodines are entrained on charcoal and then quantified by gamma spectroscopy analysis.
For each sample the duration of sampling and continuous flow rate through the charcoal are used in determining the concentration of radiciodines. From the fiow rate of the ventilation system a rate of release can be determined.
The values reported in Section 9 are the sums of all radiciodines 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 radiolodine release figures is less than plus or minus 5 percent.
. - - ~
Effluent Ralsase Report February 1992 Page 5 3.
Particulates Samples are obtained from each of the seven plant effluent radiation monitors, which continuously monitor the six ventilation exhaust pomis. The particulates are collected on a filtor and then quantified by gamma spectroscopy analysis.
For each sample the duration of sampling and continuous flo'v rate through the filter are used in determining the concentration of particulates Frem the flow rate of the ventilation system a rate of release can be determined.
Quarterly the filters from each ventilation release point are composited and then radiochemically separated and analyzed for Strontium (Sr)-89/90 using various analytical methods If found these radionuclides are reported as total particulate activity.
The values reported in Section 9 are the sums of all particulates quantified at all monitored release points.
Considering the inherent variability in radiation measurements, the variability in effluent stream composition, and the uncertainties in instrument calibration 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 l
which continuously monitor the six ventilation exhaust points. The sample is l
passed through a bottle contelning water and the tritium is
- washed" out to the collecting water. Portions of the collecting water are analyzed for tritium using 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 ventilatlan system a release rate can be determined, l
The values reported in Section 9 are the sums of all tritium quantified at all monitored release points.-
Considering the inherent variability 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 tntium release figures is less than plus or minus 34 percent.
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Efflusnt Release Report February 1992 Page 6 5.
Gross Alpha The Oaseous particulate filters from the seven plant effluent 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 related. The quantity of alpha emitters relmed can then be determined from sample flow rate, sample duration, and stack flow. ate.
The values reported in Section 9 are the sums of all alpha emitters quantified at all monitored release points.
Considering the inherent variability in radiation measurements, the variability in effluent stream composition, and the uncertainties in instrument calibration and in sample and effluent flow rates. Detroit Edison estimates that the uncertainty of the total gaseous gross alpha release figures is less than plus or minus 10 percent.
B.
Liquid Effluents The liquid radwaste processing system and the liquid effluent monitoring system are described in the Fermi-2 UFSAR.
1.
Fission and activation products Before the contents of each holding tank is discharged to the environment, a representative sample of the tank's contenu is taken and retained. The sample allows for the determination of radioactive material concentrations and establishes the rate at which the radioactive material can be discharged to the environment.
At the end of the calendar quarter a composite sample is made of all discharge samples taken during the quarter. This composite sample consists of portions of each discharge sample which are proportional to the volumes discharged. The composite sample is analyzed for tron (Fe)-55 and Strontium (Sr)-89/90. Radiochemical separations and various analytical methods are used to quantify the amounts of Sr-89/90 and Fe-55.
The values reported in Section 8 are the sums of all fission and activation products founa in all batch releases. Also reported in Section 8 are the pre-dilution waste volume (the total volume of waste sample tanks released),
the post-dilution waste volume.(the total tank volume released plus the volume of circulating water released while the tanks were being released), and the total dilution volume discharged (the total volume of circulating water released during the reporting period).
Considering the inherent variability in radiation measurement and the uncertainties in volume measurements and instrument calibration. Detroit Edison estimates that the uncertainty in total liquid fission and activation product release figures is less than plus or minus 5 percent,
Effluent Helease Report February 1992 Page 7 1
2.
Tritium Before the contents of each holding tank is discharged to the environment, a representative sample of the tank contents is taken and retained. At the end of the calendar month a (;omposite sample is made of all discharge samples taken during the month. This comporite sample consists of portions of each discharge sample which are proportiunal to the volumes discharged. The composite sample is analyzed for tritium by liquid scintillation counting.
The values reported in Section 8 sums all tritium quantified from all batch releases.
Considering the inherent variability in radiation measurement and the uncertainties in volume measurement and instrument calibration, Detroit Edison estimates the uncerta.nty in total tritium release figures is less than plus or minus 15 porcent.
3.
Dissolved and Entrained Gases Prior to releasing liquid radioactive waste to the environment a sample is taken from the radwaste holding tank. This sample is representative of the tank's contents. The sample is examined using gamma spectroscopy to determine the dissolved and entrained noble gases.
The values reported in Section 8 are the sums of all radioactive gases found for all batch releases.
Considering the inherent variability in radiation measurement and the uncertainties 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 Alpha Before the contents of each holding tank is discharged to the environment, a representative sample of the tank's contents is taken and retained. At the end of the calendar month a composite sample is made of all discharge samples taken during the month. This composite sample consists of portions of each discharge sample which are proportional to the volumes discnarged. The composite sample is analyzed for gross alpha radioactivity by gas proportional-counting.
The values reported in Section 8 ate the sums of the gross alpha radioactivity frorr all hatch releases.
Considering the inherent variability iri radiation measurement and the uncertainty in volume rneasurements and instrument calibration, Detroit Edison estimates that the uncertainty in total liquid gross alpha release figures is less than plus or minus 43 percent.
ew.
Efflusnt Ralsese Report February 1992 Page 8.
6.
ABNORMAL RELEASES '
For the purpose of this report, an 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.
7, DATCH RELEASES.
As required by Regulatory Guide 1.21,-a summary of data for batch releases is provided below,- The following batch liquid releases from radwaste holding tanks to the Circulating Water Decant Line occurred between July 1,1991 and Decer.ber 31,-
1991 (all these releases. occurred during July 1991);
Number of releases:
3 Total time for all releases:-
1042 minutes Maximum time for a release:
482 minutes Average time for a release:
347 minutes Minimum tir.e for a release:
81 minutes The only batch gaseous releases from Fermi 2 are _the venting or purging of the primary. containment (drywell) atmosphere. 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 data on these j
venting or purging releases are not reported because the associated dats are already included in the gaseous effluent release data (Section 5,A and Section 9).
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Effluent Release Report February 1992 Page 9 8.
LlOUlD EFFLUENT
SUMMARY
REPORT CATEGORY
. SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER TYPE OF ACTIVITY ALL LIQUID EFFLUENTS REPORTING PERIOD
, OUARTER 3 AND QUARTER 4 TYPE OF EFFLUENT UNIT GUARTER 3 QUARTER 4 A FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM. GASES, ALPHA)
CURIES 8 33E-03 0 00E+00
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD
. uCi/mi 6.36 E-10 0 00E+00
- 3. MAXIMUM PERCENT OF TECHNICAL SPECIFICATION LIMIT FOR A SINGLE RELEASE 1.21E-01 0.00E+00 B. TRITlUM
- 1. TOTAL RELEASE CURIES 6.55E-02 0 00E+00
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/mi 5.00E-09 0.00E 00
- 3. PERCENT OF TECHNICAL
_ SPECIFICATION LIMIT 3.25E-02 0.00E + 00 C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 6.01E-06 0.00E+00
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ml 4.59E-13 0 00E+00
- 3. PERCENT OF TECHNICAL l
SPECIFICATION LIMIT 4 47E-05 0 00E+00 D. GROSS ALPHA RADIOACTIVITY (Note: N D. = No activity detected)
- 1. TOTAL RELEASE CURIES N D_
N.D.
E. WASTE VOL RELEASED l
(PRE-DILUTION)
LITERS 1.82E+05 0.00E+00 l
I F. WASTE VOL RELEASSD (POST-DILUTION)
LITERS 6 72E407 0.00 E + 00 G. TOTAL VOLUME DILUTION DISCHARGED L ITERS 131E+10 9 19 E + 09
Efflu:nt Rslasse Rsport l'i February 1992 Page 10
' 8.
LIQUID EFFLUENT
SUMMARY
(continued)l REPORT CATEGORY
- SEMIANNUAL LIQUID BATCH RELEASES TYPE OF ACTIVITY
-: TOTALS FOR EACH NUCLIDE RELEASED =
- ALL RADIONUCUDES REPORTING PERIOD-
- QUARTER 3 AND QUARTER e BATCH RELEASES
. UNIT OUARTER 3
- QUARTER 4
--NUCLIDE -
ALL NUCUDES
- H-3
- CURIES
. 6.55E-02 000E+00
- Cr : CURIES -
- 4.07E-03
- 0.00E+00
- Mn-54
. CURIES-6.57E 0.00E+00 Co-58
. CURIES 2.80E-04
- 0.00E+00 Co-60
- CURIES
. 8.09E-04
- 0.00E+00 Zn-65
- CURIES 1.56E-04
. 0.00E+00 Fe-59
- CURIES
- 2.5CE-06 0.00E+00
-- Xe-133
- CURIES
- 1.73E.0.00E+00
-Xe-135-
- CURIES 4.28E.0.00E+00 Fe-55
. CURIES
- 2.36E : 0.00E+00 Cs-134 CURIES
- < 2.5 E-08
.0.00E+00 u-Cs-137
- CURIES
- * < 3.1 E-08
- 0.00E+00 Co-141
. CURIES
- < 2.8E-08
- 0.00E+00 '
' Co-144 --
CURIES
- < 1.5E-07 0.00E+00 Total for Period -
CURIES 7.38E-02
-0.00E+00
- - Less than Lower Limit of _ Detection (LLD), i.e. the maximum sensitivity of measurement, in units -
of microcuries per milliliter (uCl/ml).
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Effluont R Isase Rsport Fcbruary 1992 Page 11 L t. -GASEOUS EFFLUENT
SUMMARY
REPORT CATEGORY
- SEMIANNUAL SUMMATION OF ALL RELEASES BY OUARTER U-TYPE OF ACTIVITY
- ALL AIRBORNE EFFLUENTS REPORTING PERIOD
- QUARTER 3 AND QUARTER 4
. UNIT QUARTER 3 OUARTER 4 TYPE OF EFFLUENT A. FISSION AND ACTIVATION GASES
- 1. TOTAL RELEASE CURIES 1.95E + 01 1.74 E +01
- 2. AVERAGE RELEASE RATE FOR PERIOD
' uCi/sec 2.45E+00 219E+ 00 B. RADIOIOD!NES
'1. TOTAL IODINE - 131
- CURIES
- 7.26E-04 7.74E-04
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/sec 9.13 E-05 9.74 E-05
-C. PARTICULATES
- 1. PARTICULATES -
(HALF-LIVES >8 DAYS)
. CURIES 1.21 E-03
- 9.13E-04
-2.-AVERAGE RELEASE RATE FOR PERIOD uCl/sec 1.52 E-04 1.15E-04
- 3. GROSS ALPHA RADIOACTIVITY = -
- CURIES 9.13 E-07 5.03E-07
.. D. TRITIUM (Note: N.D. = No activity detected)-
- 1. -TOTAL RELEASE CURIES N.D.
N. D.-
- 2. AVERAGE RELEASE RATE FOR PERIOD
. uCl/sec
- N.A.
N.A.
p I
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-7 Efflu:nt R:Isass Raport February 1992 Page 12
' 9.~
GASEOUS EFFLUENT
SUMMARY
(continued)-
REPORT CATEGORY
- SEMIANNUAL AIRBORNE CONTINUOUS RELEASES TYPE OF ACTIVITY
- FISSION GASES, IODINES, AND PARTICULATES r
REPORTING PERIOD-
- OUARTER 3 AND QUARTER 4 OROUND LEVEL RELEASES
- UNIT
- OUARTER 3
- OUARTER 4 NUCLIDE PARTICULATES
- Cr : CURIES
- 8.89E : 5.90E-04 Mn-54
- CURIES 1.13E-05 1.00E-05 Co-58
- CURIES
- 2.06E-05
- 1.78E-05 Co-60
- CURIES 6.99E-05 4.23E-05
-Na-24.
- CURIES
- 1.64E-03
. 2.35E-04 Zn-65
- CURIES
, 1.27 E-05
. 2.31E-05 Tc-99m
- CURIES
. 6.46E-03
- 1.05E-03 Ba-139
- CURIES
, 1,76 E-01
- 1.84 E-01 Ba-140
- CURIES
- 1.71 E-04 1.53E-04 La-140
- CURIES
- 1.06E-04 2.03E-04 Y-91m
- CURIES
- 1.45E-03 1.48E-03 Sr-91
- CURIES 2.08E-03
- 2.11E-03 Rb-89
- CURIES
- 1.65E-01
. 3.00E-01
- Cs-138
- CURIES
- 6.99E-02
- 9.84E-02 Ag-110m :
- CURIES
- < 1.6E : 8.94E-07
.Re-188-
. CURIES
. 7.81E-05
- < 9.8 E-14 Br-82
- CURIES
- 5.74E-05
- 5.38E-05
. Sn-113..
- CURIES
- < 6.0E-14 5.27E-06 Sr-89
- CURIES
. 3.33E-05
. 7.06E-05
- Sr-90
. CURIES
- 8 82E-07
- 4.61E-07
~Cs-134
- CURIES-
? < 3.6 C-14
- < 3.6 E-14 Cs-137-CURIES
- < 4.7E-4
- < 4.7E-14 Co-141:
- CURIES
? < 3.1 E-14
- < 3.1 E-14 Co-144 CURIES
- < 1.2 E-13
- < 1.2 E-13 Total for Period
- CURIES 4.24E-01 5.88E-01 Less than the Lower Limit of Detection (LLD), i.e. the maximum sensitivity of measurement in units of microcuries per milliliter (uCi/ml)-
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Efflusnt Rel:ase Report' February -1992 Page 13 '
9.
GASEOUS EFFLUENT
SUMMARY
.(continued).
1 REPORT-CATEGORY -
- SEMIANNUAL: AIRBORNE CONTINUOUS' RELEASES
= TYPE OF ACTIVITY
- FISSION GASES, IODINES, AND PARTICULATES REPORTING PERIOD
- PUARTER 3 AND OUARTER 4 GROUND LEVEL RELEASES
- UNIT
- QUARTER 3.
- QUARTER 4 NUCUDE-FISSION AND ACTIVATION GASES
- Ar-41
- CURIES 4.08E+00
. 2.98E+00 -
Xe-135m
- CURIES -
- 1.31E+00 1.31 E +00
.Xe-138-CURIES
- 3.13E+00 3.84 E+00 Xe-135 CURIES.
- < 2.7 E- 08
. 3.10E-01 Kr-85m CURIES 2.72E + 00
. 6.40E-01 Xe-137<
- CURIES 5.56E +00 3.58E+00 Kr-88
. CURIES
- 1.46E+00
- < 8.4 E-08 Kr-89 CURIES
- < 1.6E-06 4.38E+ 00 Xe-133 CURIES -
- 1.22 E+ 00 3.21E-01 Total for Period CURIES 1.95E + 01 1.74 E + 01 IODINES l-131 CURIES
. 7.26E-04 7.74E-04
- 1-132 CtJRIES -
.1.18E-03 4.73E-03 l-133--
- CURIES
- 3.78E-03
- 4.13E-03
'l-134 CURIES 4*<1.6E-13
- 7.41E-04
,.'~
1-135
- CURIES 2.13 E-03 1.09E-03 Total for Period CURIES 7.82E-03 1.15E-02
~ Less than the Lower Limit of Detection (LLD), i.e. the maximum sensitivity of measurement in-
.. units of microcuries per milliliter (uCi/ml) l-l
=
1 Effluent Reloese Repon February 1992
)
Page 14 10.
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.
Solid Waste Shipped Offsite for burial or disposal (not irradiated fuel): No shipments in this reporting period.
B.
Irradiated Fuel Shipments: No shipments in this reporting period.
II, RADIOLOGICAL IMPACT ON THE PUBLIC A.
Dose Due to Liquid Effluents As disecssed in Section 2.5.1 of the Fermi 2 Offsite Dose Calculation Manual, compliance with Technical Specification 3.11.1.2, which limits dose to a member of the public to any organ and to the total body due to liquid effluents, is evaluated by calculating the dose to a hypothetical individual who both eats fish from Lake Erie and drinks water extracted from Lake Erie at the water intake for the city of Monroe; Conservative assumptions from Regulatory Guide 1109 are made about the quantity of fish and water consumed. The individual organ and total body doses for 1991 to this hypothetical individual were calculated according to Section 2.5.1 of the ODCM and are listed below.
Organ 1991 Liquid Effluent Dose Bone 1.18 E-2 mrem Liver 3.66 E-2 mrem Thyroid 8 40 E-4 mrem Kidney 2.29 E-2 mrem Lung 6.85 E-4 mrem GI-LLI 3.72 E-2 mrem Total body 1.63 E-2 mrem The highest organ dose. 3.72 E-2 mrem to the GI-LLI tracts, is 0.37% of the Tech Spec 3.11.1.2 annual organ dose simit; the total body dose.1.63 E-2 mrem, is 0.54%
of the Technical Specification 3.11.1.2 annual total body dose limit.
B.
Dose Due to Gaseous Effluents As discussed in Section 3.8.1 of the Fermi 2 Offsite Dose Calcuiation Manual, compliance with Technical Specification 3.11.2.3. which limits dose due to 1-131.
1-133, H-3, and particulates with half lives greater than 8 days in gaseous effluents to any organ of a member of the public, is evaluated by calculating the dose to a hypothetical individual in an age group which would receive the nighest single organ dose of any member of the public. This hypothetical individual is an infant who is assumed to live at an offsite location which is known, based on the Land Use Census, to have milk animals. This infant is assumcd to drink milk from these animals, and to also be exposed by the inhalation and ground plane pathways. The individual organ and total body doses to this individual due to 1-131,1-133. H-3. and particulates with half lives greater than 8 days were calculated according to Section 3 8.1 of the ODCM and are listed below.
Efflunnt Rsisase Raport February 1992 PaDe 15
- 1991 Gaseous Effluent Dose to Receptor Organ with Highest Single Oro,.1 Dose Bone 5.39 E-4 mrem Liver 4.71 E-4 mrem Thyrold 7.32 E-2 mrem Kidney 4.97 E-4 mrem Lung 2.26 E-4 mrem
'GI-LLI 2.51 E-4 mrem c-Total body 3.31 E-4 rnrem The highest single organ dose to the maximally exposed receptor,7.32 E-2 mrem to the thyroid, is 0.49% of the Technical Specification 3.11.2 3 annual dose limit.
C.
Dose Due to Direct Radiation and Compliance with 40CFR190 Title 40, Part 190 of the Code of Federal Regulations requires that dose to an individual from the uranium fuel cycle be limited to 25 mrem /yr to the total body and 75 mrem /yr to the thyroid. The sources of fuel cycle dose not analyzed above are due to other fuel cycle facilities and dose due to direct radiation. As discussed in Section 4.2 of the Fermi 2 Offsite Dose Calculation Manual, no otaer fuel cycle facilities contribute significantly to dose in the vicinity of Fermi 2. With respect to direct radiation, none of the offsite TLD locations listed in Table 6.0-1 of the ODCM showed 1991 TLD readings which were consistently greater than the TLD readings at the control locations. Since other facilities and direct radiation did not contribute-significantly to offsite doseiand since the preceding sections of this report show compliance with the more restrictive requirements of 10CFR50 Appendix 1. Ferrni 2 was in compliance with 40CFR190 in 1991.
D.
Dose to Visitors on S!!e As discussed in Section 4.0 of the Fermt 2 Offsite Dose Calculation Manual, " visitors" to the Fermi 2 site may receive dose due to their activities within the site boundary.
For purposes of this analysis, visitors are members of the public who spend time
-within the site boundary and who do not do work associated with the operation of Fermi 2. The ODCM considers two categones of visitors: persons ice fishing on Lake Erie and persons spending time in the Fermi 2 Visitors Center.
Table 4.0-1 of the ODCM lists the maximum amount of time an individual is likely to spend in these activities and the exposure pathways wnich apply: An individual is assumed to spend 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> per year ice fishing near the site and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per year at the Visitors Center. Exposure by direct radiation from noble gases and by inhalation of radioactive particulates, lodines, and tritium are considered. The doses given below do not include dose due to the pathways already considered in part A of this section, namely dose due to water and fish ingestion.
Based on these assumptions, the maximum dose in 1991 to a visitor at the Visitors Center is 7.54 E-6 mrem to total body and 8.92 E-6 mrem to the maximally exposed organ (thyroid). The maximum dose in 1991 to an ice fisherman is 1.15 E-3 mrem to the total body and 1.37 E-3 mrem to the maximally exposed organ (thyroid).
l t
I
Efflucnt Release Repnet February 1992 Page 16 E.
Population f'ise
)
Dose to the 00pulation within a fifty mile radius of fermi 2 due to 1991 gaseous and liquid (. fluents was calculated.
For liquid effluents. the fish ingestion and drinking water pathwa/s were considered.
Since there is no significant commercial fishery in the Michigan waters of Lake Erie.
the dose due to fish in00stion was assumed to be due to ingestion by the local population of the entire sport fish catch in these waters. Parameters from Regulatory Guide 1100 were used, as was the UFSAR dilution f actor of 100. The dose due to water ingestion was determined by assummg that all residents served by the Monroe water intake drmk at the average rate given by Regulatory Guide 1,100. and by us6ng the UFSAR dilution factor to the intake of 77 lhe population total body dose due to drMing water was estimated to be 3 mrem and the total body dose aue to fish ingestion was estimated to be 27 mrem, for a total estimated population total body dose due to liquid effluents of 30 mrem Ior gaseous effluents, the code MICROAIRDOS was used to estimate the population dose. Inputs to the code were 1991 gaseous release data, wino direct 7 and wmd speed frequencies for each stability class. population m each of 10 segments of each of 16 sectors, stack release specifications. etc. The estimated 1991 collective effective dose due to gaseous effluents is 160 mrem F.
Site Doundary Air Dose Gamma and beta dose to air at the site boundary due to noble gases must be calculated to evaluate compliance with Technical Specification 3.11.2.2. In 1991, gamma air dose was 163 E-2 mrad, and beta air dose was 162 E 2 mraa lhese doses represent 010% and 0 08% of the Technical Specification 311.2.2 gamma and beta annual air dose limits, respectively.
12.
RADIATION INSTRUMENTATION Fermi 2 Technical Specifications 3.3 7.11. Radioactive Liquic fffluent Monitoring Instrumentation, and 3 3.7.12 Radioactive Oaseous Effluent Morntoreng instrumentation.
require that those monitors which exceed the time specified for out of service status be reported in the next Semiannual Effluent Release Report. Durmg this reporting period. July through December of 1991, the time specified in the action statements for these monitors was not exceeded.
13.
METEOROLOGICAL DATA
SUMMARY
The meteorological monitoring system is described in the Fermi 2 UFSAR. In accordance with Regulatory Oulde 1.21, data recorded by that system is provided here to permit the Nuclear Regulatory Commisslor to assess the radiological impact of Fermi 2 releases independently. The datt 'ormat required by Regulator / Guide 121 is used. Appendix A contains the meteorolog! cal data tables.
l
Effluent Releaso Report Fobiuary 1992 Page 17 14.
CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)
As required by the Fermi 2 license, the operator (Detroit Edison) is required to ustablish o i
program that will reasonably assure the complete processing of radioactive wastes. This program assures that processed wastes are completely solidified and are free of st uiding water. Changes to the PCP Manual are provided to document changes to established conditions and to ensure that controls are in place to assure that radioactive waste is solidified.
During this reporting period, July through December of 1901, a complete rewrite of the PCP Manual was approved. Subsequently, a minor change to the PCP Manual was approved which c'ianged the name of Chem Nuclear Systems incorported procedure SD-OP-Opn-48300 to reflect the fact that a Formi-specific version of this procedure had i
been appi,od. The new name of this procedure is Process Control Program for Coment Solidification of Oil, Oily Sludges and Oil Residues at fermi 2. The latest revision of the PCP Manual is contained in Appendix 0.
15.
CHANGES TO DOSE CALCULATION AND ENVIRONMENTAL MONITORING LOCATIONS i
During this reporting period, the TLD at location T-11 was rnoved to the corner of Milliman and Jefferson Roadb due to a high vandalism rate at the former location.
16.
CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)
During this rcporting period, July through December of 1991, the ODCM was not revised.
17.
MAJOR CHANGES TO RADIOACTIVE WASTE SYSTEMS Durin0 this reporting period, July throuDh December of 1991, there were no major changes to the liquid, gaseous, or solid radioactive waste treatment systems.
18.
LlOUID HOLDUP TANKS EXCEEDING LIMITS Fermi 2 Technical Specification 3.11.t.4 requires that the quantity of radioactive material contained in any outside temporary tank shall be limited to 10 curies. excluding tritium and l
dissolved or entrained noble gases During this reportmg period. July throu0h December of
(
1991, this activity limit for such tanks was not exceeded l
l
Efflu nt R:leano Haport Fchtuhry 1992 i
APPENDlX A: METEROLOGICAL DATA TABLES
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amLLituRTon uut DIRPotATim Att/9 4 10 LOGICAL PSOEmmIES DEPARTHEWT pee 6
PeOsman: J99 DEastem: PC-1.1 SECD FEABBt2 JfD AT 60MTERS FW 1991 SITE 19ESTIFIEe: Pfant2 DATA PEtt0B EnemiuES: 1/ 1/91 - 12/31/91
- M l
STABILITT SASED W 1*e.24....,7=G l
Wie EEASWE9 AT: 60.0 MTERS Wie fumESuGLD AT:
.75 MPs -
l TOTAL ImpWE OF WSEWWATIONS: 8750 i
TeiAL ensett or wette CBStowaTitars: 8758 TOTAL WMt OF 901SSIGG (WSEWWATICBIS:
2 1
PERCEeT DATA aECDUERY FOR TWIS PERIW: 100.0 %
l' MEAst Wie SPEED FOR TWIS PERIOD: 13.5 frW
. TOTAL InsquEt OF 00SEeWaitons WITW SACXUP DATA:
0' f
PERCEuTAGE OCQlRGEuCE OF STastLITY CLASSES j
A B
C D
E F
G l'
5.21 5.25 8.38 41.60 26.32 9.44 3.40 i
0I57t13u710110F Wie DIaECTION vs STastLITY WWE WE EaE'
.E ESE SE
$$E S
1sar saa tuand Catst j
l A
to 11 38 34 68 31 23 5
4 23 13 41 27 59 45 22 0
i s
11 11 21 19 47 40 27 to 14 58 31 52 30 36 26 27 0
i C
27 25 25
' 39 33 43 44 47 37 56 80 36 68 51 45 25 e
i D
1%
102 255 248 217 1%
146 158 156 230 361 451 335 193 191 212 0
l E
79 76 101 83 79 til 108 105 136 286 363 296 155 120 170 115 0
F 44 20 25 to 23 46 39 48 98 130 1C2 50 55 37 48 52 0
I C
15 27 26 5
3 15 14 19 31 34 t5 9
18 27 22 18 0
i TOTAL 380 272 491 438 490 480 401' 392 476 817 967 965 688 523 487 4 71 0
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Efflu:nt R:10:s3 Report February 1992 APl>ENDIX B: PROCESS CONTROL PROGRAM MANUAL
_ _ - _ _ _ _ - _.