NRC-89-0138, Semiannual Radioactive Effluent Release Rept, Jan-June 1989

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Semiannual Radioactive Effluent Release Rept, Jan-June 1989
ML20246G402
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 06/30/1989
From: Sylvia B
DETROIT EDISON CO.
To:
References
CON-NRC-89-0138, CON-NRC-89-138 NUDOCS 8909010025
Download: ML20246G402 (19)
v • d • e


Text

. _ _ _ _ _ _ _ _ _ _ . - . _ _ _ .

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C.C%lph Syfvb

. Serwor Vice President

. ' 6400 North Dree Highway

' [s p. Newport. Michigan 48166

%se 4313t 58tr4150 August 28, 1989 NRC-89-0138 U. S. Nuclear Regulatory-Commission Attention: Document' Control Desk Wcshington, D. C. 20555

References:

(1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43 (2) Appendix A. Facility Operating License No..

NPF-43 Technical Specification 6.9.1.6

Subject:

1ami-Annun1 *t n el i o l o g i e n 1 Effluent Relence Rennre The Semi-Annual Effluent Release Report for Fermi 2 is atteched. This report is being transmitted in conpliance with Reference 2 and Regulatory Guide 1.21 Revision 1. The attached report covers the period from January 1 through June 30, 1989.

During this reporting period there were no instances of unmonitored or unplanned radioactive releases from the site.

Please direct any questions or requests for additional information to Joseph Pendergast at (313) 586-1682.

Sincerely, b

cc: A. B. Davis R. C. Rnop W. G. Rogers J. F. Stang Region III I

8909010025 890630 PDR ADOCK 05000341 R PNU

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_ _ 2 SEMIAXXUAL RADIOACTIVE EFFLUEXT RELEASE REPORT January 1,1989 through June 30, 1989

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i Prepared by: Radiological Effluents Group

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  • Effluent Rel aso R: port August 1989 TABLE OF CONTENTS PAGE' 1 1. Introduction 2 2. Regulatory limits 3 3. Maximum Permissible Concentration 4 4. Average Energy 4 5 Measurements and Apprommations of Total Activity 7 6. Abnormal Releases 8 7. Batch Releases 9 8. Liquid Effluent Summary 11 9. Gaseous Effluent Summary 14 10. Solid Waste and Irradiated Fuel Shipments 15 11. Radiation instrumentation 16 12. Changes to the Process Control Program (PCP) 16 13. Changes to the Offsite Dose Calculation Manual (ODCM)

Effluent Rclease Report August 1989 Page 1

1. INTitODUCTION

'Ibe Detroit Edison Ferm 2 Nuclear Power Plant is designed and operated to strictly control and monitor the release of radioactive efflucnts to the environment in accordance with Nuclear Regulatory Commission (NRC) and Detroit Edison Company requirements. This Semiannual Radioactive Effluent Release Report is submitted in accordance with Fermi-2 Technical Specification 6 9 LS 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
2. Summation of quantities of radioactive material contained in solid waste packaged and shipped for off-site disposal
3. Changes to the Process Control Program (PCP)
4. Changes to the Offsite Dose Calculation Manual (ODCM)

This report covers the period of January 1 through June 30,1989 During the first half of 1989, the total gaseous and liquid radioactive effluent releases were maintained As Low As Reasonably Achievable (A1. ARA). A summary of the dose due to radioactive effluents in comparison to NRC limits is shown below:

NRC DOSE LIMITS FERMI-2 ESTIMATED DOSE (10CFR50 APPLNDIX l} '

GASEOUS EFFLUENTS Noble Gases (Unrestricted Area) 510 gamma mrad / year to air To be summarized in next report *

$20 beta mrad / year to air To be summarized in next report

  • Dose to an individual from I-131,133, Tritium and Particulate

$15 mrem / year to any organ To be summarized in next report

  • UQUID EFFLUENTS

$3 mrem / year to the total body To be summarized in next report

  • I

$10 mrem / year to any organ To be summarized in next report *

  • Fermi 2 Technical Specification 6.9.1.8 states that the report to be submitted within 60 days after January 1 shall include an assessment of radiation doses for the previous calendar year.

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. ' ? Effluent Ralease R port .

. August 1989 Page 2

' 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 quantities and rates of release for radioactive effluents resulti.1g from .

normal operation of Fermi-2. The limits are defined in several ways to limit the overall impact on persons living near the plant. The limits are described below:

A. Gaseous Effluents li 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 500 mrem / year to the total body Less than or equal to 3000 mrem / 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 mrem / year to any organ.

2. Air dose due to noble gases released in gaseous effluents from the reactor to areas at and beyond the site boundary shall I e 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 from the termer 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 qt.arter l '.

l

b. Less than or equal to 15 mreins to any organ

-During any calendar year B. Liquid Effluents --

1. The concentration of radioactive material released in liquid effluents to l

unrestricted areas shf ill be limited to the concentrations specified in Title 10 of .

tiie Code of Federal Regulations Part 20 (Standards for Protection Against i Radiation) Appendix B, Table 12. Column 2 for radionuclides other than dissolved or entrained noblo gases. For dissolved or entrained noble gases, l'

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Effluent Release R: port August 1989 Page 3 l

the concentration shall be limited to 2x10-4 (.0002) microcuries/mi total activity.

2. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from the reactor to unrestricted areas shall be limited to:

l a. Less than or equal to 1.5 mrom 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)

As required by NRC Regulatory Guide 1.2' the MPC's used to calculate permissible release rates and concentrations are described below:

A. Gases The dose rate due to geseous effluents is calculated in accordance with the Fermi 2 Offsite Dose Calculation Manual (ODCM). The maximum permissible dose rates for gaseous releases are defined in Fermi 2 Technical Specifications:

Technical Specification 3.11.2.1.a (Dose rate at the site boundary from gaseous effluents in the the form of 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 (todine-131,133, tritium and particulate 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). The maximum permissible concentration (MPC) for liquids used for these calculations are taken from 10CFR20, Appendix B. Table 11, Coluran 2. The most restrictive MPC !s 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.

Efflu::nt R;, lease Report

_ August 1989 Page 4

4. AVERAGE ENERGY The Fermi 2 Technical Specifications limit the site boundary dose rates for fission and activation gases to less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin. Therefore, the average beta and gamma energies (E) for gaseous effluents required to be reported by Regulatory Guide 1.21 are not applicable to Fermi 2 and need not be reported.
5. MEASUREMENTS 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 Eftfuents

1. Fission and Activation Gases Samples are obtained from each of the seven plant radiation monitors which continuously monitor the six ventilation exhaust points. The fission and activation gases are quantified by gamma spectroscopy analysis of periodic samples. The following are typical fission and activation gases that are quantified for dose calculations:

Krypton (Kr)-87 Krypton (Kr)-88 Xenon (Xe)-133 Xenon (Xe)-133m Xenon (Xe)-135 Xenon (Xe)-138 The values reported in Section 9 are the sum., of all fission and activation gases quantified at all monitored release points.

Considering the inherent variability in radiation measurement and the uncertainties in sample volume, flow rate, and pressure measurements, Detroit Edison estimates that the total uncertainty of its fission and activation gas measurements is 7 percent low and 50 percent high.

2. Radiciodines Samples are obtained from each of the seven plant radiation monitors, which continuously monitor the six ventilation exhaust points. The radiciodines are l

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 radioiodines. From the flow rate of the ventilation system a rate of release can be determined.

The radioiodines usually quantified for dose calculations are the following:

lodine (1)-132 l lodine (1)-131 lodine (1)-133 lodine (1)-135 The values reported in Section 9 are the sums of all radiciodines quantified at l all contmucusly monitored release points. ]

e__-___.-________-__ _ - _ . - - _ _ - _ _ _

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Efflu nt Rtfease Report August 1989 Page 5 l

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, Considering the inherent variability in radiation measurements and the uncertainties in sample volume, flow rate, and pressure measurements, Detroit Edison estimates that the total uncertainty of these measurements is 23 percent low and 55 percent high.

3. Particulate Samples are obtained from each of the seven plant effluent radiation monitors, which continuously monitor the six ventilation exhaust points. The particulate 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 filter are used in determining the concentration of particulate. From the flow rate of the ventilation system a rate of release can be determined. The particulate usually quantified for dose calculations are the following:

Manganese (Mn)-54 Iron (Fe)-59 Cobalt (Co)-58 Cobalt (Co)-60 Zine (Zn)-65 Molybdenum (Mo)-99 Cerium (Ce)-141 Cesium (Cs)-134 Cesium (Cs)-137 Cerium (Ce)-144 (Also other c,uantified radionuclides with half lives greater than 8 days)

A composite of the filters from each ventilation release point are analyzed monthly for gross alpha radioactivity using gas proprotional counting methods. Quarterly the filters are 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 particulate quantified at all monitored release points.

Considering the inherent variability in radiation measurements and the uncertainties in sample volume, flow rate, and pressure measurements, Detroit Edison es>: mates that the totai uncertainty of these measurements is 23 percent low and 55 percent high.

4. Tritium Sampics are obtained for each of the seven plant effluent radiation monitors which continuous!y monitor the six venti:ation exhaust points. The sample is 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 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 ventilation 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.

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'* Effluent Rr, lease Report L. ,'

August 1989 Page 6 Considering the inherent variability in radiation measurement and the uncertainties in sample volume, f'ow rate, and pressure measurements, Detroit Edison estimates that the total uncertainty of these measurements is 12 percent low and 51 percent high.

B. Liquid Effluents The liquid radwas'e 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, b representative sample of the tanks contents is taken and retained. The sample allows for the determination of radioactive material concentrations and establishes the rate at which the radiot.ctive material can be discharged to the environment, Radioactive activation and fission prodects that are typically found include the following:

Manganese (Mn)-54 Iron (Fe)-59 Cerium (Ce)-144 Cobalt (Co)-58 Cobalt (Co)-60 ,

Zinc (Zn)-65 Molybdenum (Mo)-99 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 proportion.al to the volumes discharged. The composite sample is analyzed for Iron (Fe)-55 and Strontium (Sr)-89/90. Radiochemical separations and various enalytical methods are used to quantify the amounts of Sr-89/90 and Fe-65.

The values reported in Section 8 are the sums of all fission and activation products found in all batch releases.

Considering the inherent variability in radiation measurement and the uncertainties in sample flow rate and volume measurements, Detroit Edison estimates that the total uncertainty in liquid fission and activation product measurements is less than 14 percent.

2. Tritium Before the contents of each holding tank is discharged to the environrnent, a representative sample of the tank, contents is taken and retained. At the end of the calendar month a t.omposite sample is made of all discharge samples taken during the month. This composite sample consists of portions of each discharpe sample which are proportional 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.

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'* Effluent Releese Report-August 1989 Page 7 Considering the inherent ' variability in radiation mer.surement and the uncertairdies in flow rate and volume measurement, Detroit Edison estimates the total uncertainty in Tritium measurements is less than 14 percent.

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 tanks contents. The sample is examined using gamma spectroscopy to determine the dissolved and entrained noble gases. The following radiogases are typical of those which may be found:

Krypton (Kr)-85m Xenon (Xe)-131 Krypton (Kr)-85 Xenon (Xe)-133 Krypton (Kr)-88 Xenon (Xe)-137 Krypton (Kr)-89 Xenon (Xe)-138 The values reported in Section 8 are the sums of all radiogases found for all batch releases.

Considering the inherent variability in radiation measurement and the uncertainties in flow rate and volume measurements, Detroit Edison estimates that the total uncertainty in dissolved and entrained gases measurements is less than 15 percent.

4. Gross Alpha 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 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 discharged The composite sample is analyzed for gross alpha radioactivity by gas proportional counting.

' The values reported in Section 8 are the sums of the gross alpha radioactivity from all batch releases.

Considering the inherent variability in radiation measurement and the

l. uncertainty in flow rate and volume measurements, Detroit Edison estimates that the total uncertainty in liquid gross alpha activity measurements is less than 23 percent.

6 ABNORMAL RELEASES For the purpose of this report, an abnormal release is any release of radioactive material not performed in accordance the Fermi 2 license and implementing i procedures. No abnormal releases occurred during the reporting period.

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- Effluent Release Report August 1989 Page 8 l

'/. BATCH 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 January 1,1989 and June 30, 1989:

1 I

Number of releases: 3 Total time for all releases: 1339 minutes l Maximum time for a release: 502 minutes l Average time for a release: 446 minutes  !

Minimum time for a release: 381 minutes The only batch gaseous releases from Fermi 2 are the venting or purging of the primary containment (ttrywell) atmosphere. Since these releases pass through the reactor build!ng ventilation or standby gas treament system and are monitored by the final effluent monitors for these pathways, scoarate dr.ta on the individual releases are not reported. f

Effluent Release Report August 1989 Page 9

8. LIQUID EFFLUENT

SUMMARY

REPORT CATEGORY SEMIANNUAL SUMMMATION OF ALL RELEASES BY QUARTER TYPE OF ACTIVITY  : ALL LIQUID EFFLUENTS REPORTING PERIOD QUARTER 1 AND OUARTER 2 UNIT QUARTER 1 QUARTER 2 TYPE OF EFFLUENT A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM. GASES, ALPHA) CURIES 1.44E-02 . 1.73 E-02
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/mi 1.62E-09 1.75E-09 B. TRITIUM
1. TOTAL RELEASE CURIES 1.19E-01 7.95E-02
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCl/mi 1.34E-08 8.06E-09 C. DISSOLVED AND ENTRAINED GASES
1. TOTAL RELEASE CURIES 5.90E-05 2.61 E-C5
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/mi 6.62E-12 2.65E-12 D. GROSS ALPHA RADIOACTIVITY
1. TOTAL RELEASE CURIES 0.00E400 0.00E+ 00 E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 1.29E4 05 6.26E+ 04 F. TOTAL VOLUME DILUTION DISCHARGED LITERS 8.92E4 09 9 86E409

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8. LlOUID. EFFLUENT

SUMMARY

(continued)

REPORT CATEGORY . SEM%NNUAL UQU!D BATCH RELEASES g' 1+ TYPE OF ACTIVITY  : TOTALS FOR EACH NUCLIDE RELEASED-

ALL RADIONUCLIDES

'- REPORTING PERIOD OUARTER 1 AND OUARTER 2 k 1, BATCH RELEASES

U WIT.
QUARTER 1 OVARTER 2.

i NUCLIDE  : .

f ALL NUCUDES - __

H-3  : CURIES . 1.19E-01 . 7.95E-02 Na-24  : CURIES 4.43E-03,  : 2.40E-03 Cr-51  : CURIES 6.93E-03  : 1.18E-02

. Mn-54  : CURIES 1.52E-04  : 6.82E-05 Co-58 .' CURIES  : 4.05E-04 . 2.44E-04

- Cc-60 CURIES  : 1.81E-04 :1.05E-04

. Zn-65  : CURIES 2.47E-04 4.76E-04

' Mo-99  : CURIES . 6.06E-04  : 4.74E-04 Tc-99m .  : CURIES .1.02E  : 1.14E-03 1-131 . CURIES  : 2.00E-05 1.60E-05 l-133  : CURIES , 1.12 E-04 1.18E-04 Xe-132  : CUR!ES . 5.90E-05  :* < 4.6E-08 Xe-135  : CURIES  :* < 1.4 E-08  : 2.61E-05 Sr-89 . CURIES - 3.0$E-05  : 5.63E-06 Fe-55  : CURIES  :* < 1.0E-06 1.38E-04 Ba-731  : CURIES

  • 5.09E-05 . 2.55E-05 Re-188  : CURIES 1.85E-04 9.77E-05 As-76  : CURIES 3.96E-05 1.93E-04 Fe-59 CURIES  :* < 5.2 E-08  :* < 5.2E-08 Cs-134 . CURIES * < 1.3E-08  !* < 1.3E-08 CE-137 CURIES * < 1.6E-0 8 * < 1.6E-08 Ce-141 CURIES * < 2.4 E-0 8 .*<2.4E-08 Ce4144 CURIES * < 9.8E-08  :* < 0 AE-08 Total for Period CURIES 1.34E-01 9.68E-02
  • Less than Lower t.imit of Detection (LLD), i.e., the maximum sensitivity of measurement, in units of microcuries per milliliter (uCi/ml).

EfHucnt F.clene Rsport '

August 1989

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9. GASEOUS EFFLUENT

SUMMARY

REPORT CATEGORY . SEMIANNU AL SUMMMATION Or ALL RELEASES 9Y OUARTER

. TYPE OF ACTIVITY  : ALL AIRBORNE EFFLUENTS REPORTING PERIOD . QUARTER 1 AND OUARTER 2 UNIT QUARTER 1 , QUARTER 2 TVPE OF EFFLUENT '

A. FISSION AND ACTIVATION GASES _ , _ _ _ , _

l. TOTAL RELEASE CURIES 4.03F+ 01 .520E+01
2. AVERAGE RELEASE RATE FOR PERIOD uCi/ set 510E+ 00 7 25E+00 B. RADIOlODINES _. _ _ _ _ _ _ _

s

1. TOTAL LODINE - 131 CURIES 3.49E 04 7.1LE-04
2. AVERAGE RELNASE RATE FOR PERIOD uCi/sec 4.49E-05 9.09E-05  ;

i C. PARTICULATE

1. PARTICULATE (HALF- LIVES >B DAYS) CURIES 3.84E-03 3.4?E-03
2. AVERAGE RELEASE RATE FOR PERIOD . uCi/sec 4.94E-04 4.35E-0.1 CUit1ES 1.6S E - 07 . 217E-07
3. GROSS ALPNSADIOACTIVITY l

D; TRITIUM, _ l

1. TOTAL RELCASE CURIE,,S 0.00E400_

0.00E+ 00

2. AVERAGE RELEASE RATE FOR ped!OD uCi/sec _.0.00E+00, 0.00E+ 00 _

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Effluent Release Repoo L<~# August 1989

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- 9. GASEOUS EFFLUENT LUNITAAP.V (cont %ued) ll L REPOh! CATEGORY SFfAIANNUAL AIRBORitE CONTINUOU3 RELEASES TYPE OF ACTIVITY - FISSION GASES, IODINE 3, AND PARTICULATE REFDRT4hG PERIOD - QUARTER 1 AND QUARTER 2 GROUND RELEASES UNIT QUARTER 1 GUART ER 2 NUCUDE  :

1 PARTICULATE _

Crd1 CURIES . 2.97E-03  : 2.93E-03 Mn- 54 CURIES 6.51E-05 1.62E-05 C& E8 CURIES 1.97E-04 . 6.12E-05 Mo-99 CURifS * < 1.1 E - 13  : 4.90E-05 Ba-140 . CURIES 8.30E -05 1.68E-04 Lo -140 , CURIES . 7.01E-05 - 1.16E-04 Tc-90m . CURIES . 3.10E-02 176E-02 Ba-139 , CURIES  :.60E-01 .1.07E-01 Y-01m CURIES 1.41 E-03 1.67E-03 Sr -91 . CURIES 1.24 E-03 . 2.42E-03 Zn-65 CURIES 1.81 E-04  : 8.91E-05

.Co-60 CURtES . 3.88E-05 2.15E-05 Na-24 . CURIES . 9.71E-03  : 4.23E-03 Da-131 CURIES 215E-04 1.74E-05 Ba- 13Srn CURIES 3.60E-04 * < 4.7 E- 14 As-76 CUR 1ES 3.07 E-04 2.27E-04 Hb-89 Ct! RIES 1.17E-01 2.91E-01 Cs-138 - CURIES 5.66E-02 .8.88s-02 lAn-56 CURIES 1.97E-03 4.34E-04 Ag-110m CURIES 4.80E-05 * < 7.5 E- 14 He-188 CURIES 5.70E-04 1.42 E--04 Se-75 . CURIES 4.90E-06 8.57 E-07 Zn-69m CURIES 3.92E-05 5.67E-05 ]

Cu-64 CURIES 3.42E-02 2.33E-02 Tc-101 - CURIES 1.15E-03 #< 2.1 E - 13 Sr-89 CURIES 3.35E-0E 1.12E-04 Sr-90 GURIES 5.76E 06 7.21 E-06 Fe-59 CURIES * < 5.3E- 14 * < 5.3 E- 14 Cs-134 CURIES * < 1 ?F - 14 * < i .7 E-14 Cs-1S7 CURIES * < 1.5L-14 d < 1.5E-14 Cs-141 CURIES -* < 1.8E- 14 * < 1.8E- 14 Ce-144 .-- -

CURIES -*<1.0E-13 * < 1.0E- 13 Total for Periot' CUR 1ES 4.21E-01 6.19E- 01

  • Less than Lower Limii of Detection (Lt.D), i e . the maximum sensitivity of measurement in units of microcuries per myiBrier .(uCi/ml).

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9. GASEOUS EFFLUENT

SUMMARY

(continued)

REPORT CATEGORY SEMIANNUAL AIRBORNE CONTINUOUS RELEASES TYPE OF ACTIV l'Y FISSION GASES, IODINES, AND PARTICULATE REPORTING PERIOD QUARTER 1 AND OUARTER 2 l

- i GROUND RELEASES

. UNIT QUARTER 1 QUARTER 2 j NUCLIDE - a flSSION GASES _ _ _

Ar-41 . CURIES 9 28E+00 1.31 E+01  !

Kr-85m CURIFS 1.47E + 00 2.08E+00 Xe-129m  ! CURIES 811E+00 1.15E+ 01 Xe-135 CURIES L'0E-01 1.21E + 30 Xe-135m ' . CURIES 1.39 E + 00 1.96E + 00 Xe<137 . CURIES 1.49E + 01 2.11 E +01 Xe-138 CURIES 4.31E+ 00 6.09E+ 00 Kr-87 . CURlFS * < 2.8E-08 * < 2.8E- 08 i Kr-88 CUR:ES  :* < 5.1 E-08 * < 5.1 E-0 t3 {

Xe-133 . CURIES * < 2.9E-08 * < 2.9E-08 1 Xe-133m _

CURIES * < 1.3 E-0 7  :* < 1.3 E- 07 )

TOTAL FOR PERIOD  : CURIES 4.03E + 01 5.70E + 01 )

i I

i IODINES ii

-I l-131 CURIES 3,40E- 04 7.15E-04  !

l-132

  • CURIES
  • 3.73E< 04 1.54 E-03 1-133 CURIES 1.95E-03 5.17E-03 ,

1-134 CURIES 3 87E-04 * < 1.1 E- 13 1 1-135

  • CURIES 9.23E-04 ,

2.58E-03 .

l Total for Period CURIES 3.99E-03 1.0GE-02 _

  • Less than the Lower .imit of Detection (LLD), i.e., the maximum sensitivity of measurement in units of microcuries per milliliter (uCi/ml).

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l Effluent kelease Report <

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  • August 1989 j Pa9e 14
10. sot.lD WASTE AND IRRADIATED FUEL SHIPMENTS A. - Solid Waste Shipped Offsite for burial or disposal (not irradiated fuel) l- 6 month Est. Total
1. Type of Waste Unit period _ Error %
a. Spent resins, filter sludges, m 1.27E+ 02 +25 evaporator bottoms., etc. Curies 3.95E +02 +25 l b. Dry compressible waste, m 2.82E +01 +25 contaminated equipment, etc. Curies 4.69E-01 _ 225 I c. Irradiated components, i control rods, etc. O 0

___ d . Other l

2. Estimate of major nuclide composition (by type of waste)
a. Spent resins, filter studges evaporator bottoms, etc.

l l Percent of Nuclide Total Activity Curias Cr-51 36,2 1.43E+ 02 Mn-54 9.4 3.70E+ 01 1 Fe-55 27.3 1.08E402 Co-58 8.3 3.27E+ 01 Co-60 7.3 2.90E+ 01 Fe-59 0.5 1.91E+ 00 Zn-65 9.5 3.74E + 01 H-3 < 0.1 9.59E-03

! C-14 0.3 1.09E + 00 l Zr-95 0.2 6.86E-01

Ba-131 < 0.1 1.12E-01 Ni- 63 0.2 7.40E-01 Ag-t 10m 0.6 2.19E+ 00 Nb'95 0.4 1.59E + 00 Tc-99 < 0.1 3.34E-04 l-129 ( 0.1 4.00E-04 l

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Effluent Ralease Report August 1989 Paga 15

b. Dry compressible waste, contaminated equipment, etc.

Cr-51 8:7 4.09E-02 Mn-54 14.6 6.84 E-02 Fe-55 38.8 1.82E-01 Co-58 6.6 3.09E-02 Co-60 102 4.79E-02 Zn-65 6.4 3.01 E-02 Ni-63 3.0 1.41 E-02 C-14 11.6 5.46E-02 Fe-59 < 0.1 1.90E-04 Cs-137 < 0.1 9 24E-07 Note: Activities of all principal radionuclides were determir.ad by measurement.

3. Solid Waste Disposition (All waste was Class A and was shipped in LSA containers)

Type of shipment / Number ef Mode of solidifestion process shipments Transport. Destination Dewatered resin 16 truck Barnwell, SC Dry active waste 1 truck Channahon IL

4. Irradiated Fuel Shipments:

l None l

11. RADIATION INSTRUMENTATION Fermi 2 Technical Specifications 3.3.7.11, Radioactive Liquid Effluent Monitoring instrumentation, end 3.3.7.12, Radioactive Gaceous Effluent Monitoring instrumentation, require that those monitors whiih exceed the time specified for out l of service be reported in the next Semiannual Erfluent Release Report. During this report 5g period, January through June of 1989, the time specified in the action l

i statements for thesa monitors was not exceeded.

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Efflu nt Reisase Rsport August 1989

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Pags 16

12. CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

As required by the Fermi 2 license the operator (Detroit Edison) is required to establish a pragram that will reaso.1 ably assure the complete processing of radioactive wastes. This program assures processed wastes are completely solidified and are free of standing water. Changes to the PCP Manual are provided ta document changes to pre-established conditions and to ensure that contrcir, are in place to assure that the radioactive waste is solidified.

During this reporting period, January through June of 1989, there were no changes to the PCP.

I '4. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

During this reporting period, January through June of 1989, there were no changes to the ODCM.

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