NRC-88-0206, Semiannual Radiological Effluent Release Rept, Jan-June 1988

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Semiannual Radiological Effluent Release Rept, Jan-June 1988
ML20153D638
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 06/30/1988
From: Sylvia B
DETROIT EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CON-NRC-88-0206, CON-NRC-88-206 NUDOCS 8809020271
Download: ML20153D638 (24)
v • d • e


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SEMI- ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT JAN'JARY.1,1988 to JUNE 30, 1988 l

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Prepared by: Radiological Engineering Group l

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DETROIT EDISON COMPANY FERMI - 2 NtKLEAR POWER PLANT OPERATING LICENSC NO. NPF - 43 SEMIANNUAL RADIOACTIVE DTLUENT RELEASE REPORT for the period of January 1, 1988 through June 30, 1988 L

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_ _ _ _ _ _ _ _ _ _ _ _ Effluent R21 case Report

' August, 1988

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TABLE OF 00W1DITS Page 3 1. Introduction 4 2. Regulatory Limits .

5 3 Maximum Permissible Concentration l

6 4. Average Energy 6 5 Heasurements and Approsisations of Total Activity ~

10 6. Batch Releases 10 7. Abnormal Releases 11

8. Batch Release Data 12 9 Liquid Effluent Summary 14 10. Gaseous Effluent Summary 16 11. Solid Waste and Irradiated Fuel Shipments 19 12. Changes to the Process Control Program (PCP) 19
13. Changes to the offsite Dose Calculation Manual (ODCH) 19
14. Radiation Instrumentation l

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I

. Effluent Releasa Report

. August, 1988 i Page 3

1. INTRODUCTIO'l Fermi 2 is designed and operated to strictly control the celease of radioactive effluents to the environment in accordance with Nuclear Regulatory Comnission (NRC) regulations. This Semiannual Radioactive ')

Effluent Release Report provides the following information:

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1. Sunnation of the quantitica of radioactive material (in the form of gases and liquids) released from the plant
2. Sunnation of the quantities of radioactive material contained in ,

solid waste packaged and shipped for off-site disposal at federally approved sites 3 Changes to the Process Control Program (PCP)

4. Changes to the Offsite Dose Calculation Manual (ODCH)

During the reporting year, the total gascous and liquid offluent releases and resulting potential dose to the public were in compliance with all regulation limits (described below) and maintained As Low As Reaoonably Achievable (ALARA). A summary of radioactive effluents released end potential dose in comparison to NRC limits are shown below:

NRC Limits Fermi 2 Potential Dose Gascous Erfluents Noble gases (Unrestricted Area)

$ 10 mrad gamna / year To be sunmarized in Final Effluent Report 3 20 mrad beta / year To be sunnarized in Final Effluent Report  !

Dose to an individual from I-131, 133, Tritium, and Particulates 5 15 mren/yr - Any Organ To be sunnarized in Final Effluent Report ,

Liquid Effluents 5 3 mren/yr - Total Body To be sunnarized in Final Effluent Report

$ 10 mren/yr - Any organ To be sunnarized in Final Effluent Report This report contains the portinent data in support of the above summation. L i

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- . Effluent R210ers Report August, 1988 P:g3 4

2. REGULA'K)RY LIMITS A. Gascous 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 500 ares /vear to the total body

- Leas than or atqual to 3000 ares / year to the skin

b. Iodine - 131, 133, Tritius, and for all radionuclides in particulate form with half-lives greater than 8 days

- Less than or equal to 1500 ares / year to any organ

2. Air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the site boundary shr'l be limited to the following:

.- a. Less than or equal to 5 arads for ganna 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 Iodine - 131, 133, Tritius, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the site boundary shall be limited to the following:
a. Less than or equal to 7 5 areas to any organ

- During any calendar quarter

b. Less than or equal to 15 areas 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 Regulations Part 20 (Standards for Prot 3ction Against Radiation),

Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. Fordissolvedorentrgined iBb829"itbo!D?i:1921"Blal actHllyP """*d ' 2*'~

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Effluent Relenca R: port August, 1988 P:ge 5

2. The dose or dora commiteent to a member of the public from radioactive materials in liquid effluents released, from each reactor unit, to unrestricted areas shall be limited:
a. Less than or equal to 1.5 area to the total bcdy Less than or equal to 5 ares to any organ

- During any calend.c quarter

b. Less than or equal to 3 mren to the total body Less than or equal to 10 area to any organ

- During any calendar year

3. MAIINUM PERMISSIBLE CONCENTRATION A. Liquids
1. The maximum permissible concentrations ( ?C) for liquids are those listed in 10CFR20, Appendix B, Table II, Column 2, with the most restrictive HPC being used in all For dissolved and entrainedgasestheMPCof2x10~ gases.microcuries/a1 is applied.

This MPC is based on 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.

B. Gaseous

1. The sampling and analysis required by the Fermi-2 Technical Specification is used to evaluate the rate at which radioactive material is released. The approved Offsite Dose Calculation Manual (ODCH) provides the calculational methodologies to determine the maximum permissible dose rate.
2. The maximum permissible dose rates for gaseous releases are defined in plant Technical Specifications.
a. Technical Specification 3 11.2.1.a (Dose rate at site boundary from gaseous effluents in the form of noble gases):

- Less than or equal to 500 aren/ year to total body

- Less than or equal to 3000 ares / year to skin

b. Technical Specification 311.2.1.b (Iodine - 131, 133, Tritium, and particulates with half-lives greater than 8 days):

- Less than or equal to 1500 ares /yr to any organ

-, --n c - ,. -- .,

- - Effluent Release Report )

August,1983 Pego 6

4. AVERAGE ENERGY The Fermi 2 Technical Specifications limit the release 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 as described in Regulatory Guide 1.21 "Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" are not applicable.
5. MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY A. Gaseous Effluents
1. Fission and Activation Gases
a. Samples are obtained from each of the seven plant effluent radiation monitors, which monitor the six ventilation exhaust pointt The fission and activation gases are quantified by gamma spectroscopy analysis.

Those radionuclides that are quantified for dose calculations due to fission and activation gases are typical of the following:

Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-138 The value reported is the sum of all fission and activation gases quantified at all monitored release points.

Considering the random nature of radioactive decay and the inherent variability in radiation measurement along with sample volume, flow rate, and pressure measurements, the total fission a.1d activation gases measurement of uncertainties may be less than 7.4 percent low and 50.3 percent high.

2. Radiolodines
a. Samples are obtained from each of the seven plant effluent radiation monitors, which monitor the six ventilation exhaust points. The radiolodines are entralned on a charcoal media, then quantified by gamma spectroscopy analysis. For each sample, the duration of sampling and continuous flow rate through the media are used in determining the concentration in each case the flow rate of the ventilation system is known such that a rate of release can be determined. The radiolodines that are quantified for dose calculations are typical of the following:

1-131 1-133 1-135 The value reported is the sum of all radiolodines quantified at all monitored release points.

Effluent Release Report August, 1988 Page 7

3. Particulates
a. Sampics are obtained fron each r,f the seven plant effluent radiation nonitors, which nonitor the six ventilation exhaust points. The particulates are collected on a filter media, then quantified by ganma spectroscopy analysis. For each sanple, the duration of sampling and continuous flow rate through the filter are used in determining the concentration. In each case the flow rate of the ventilation systen is known such that a rate of release can be deternined. The particulates that are quantified for dose calculations are typical of the following:

Hn-54 Fe-59 Co-58 Co-60 Zn-65 Ho-99 Cs-134 Cs-137 Ce-141 Cc-144 (Also other quantified radionuclides with half-lives greater than 8 days)

A composite of the filters obtained fron each ventilation release point are analyzed nonthly for gross alpha radioactivity, by propertional counting. Quarterly, the filters are radiochenically seper:ted and analyzed for Strontiun (SP) 89/90 by gas proportional counting. If quantified, these totals are reported as total particulate Ectivity.

The value reported is the sum of all particulate quantified at all monitored release points.

Considering the randon nature of radioact.ivo decay and the inherent variability in radiation neasurement along with sanple volume, flow rate, and pressure neasurenents, the total radiolodine and particulate measurenent of uncertainties nay se less than 22 9 percent low and 54.8 percent high.

4. Tritiun
a. Sampics are obtained fron each of the seven plant effluent radiation nonitors which nonitor the six ventilation exhaust points. The sanple is passed through a bottle containing water. While the sanple is being Iissed through the bottle the Trillun is "washed" out to the collecting water. Portions of the collecting water are analyzed for Trittun using 11guld scintillation counting techniques. For each sanple, the duration of sampling and sample flow rate is used to deternine the concentration.

The value reported is the sum of all Tritium quantified at all nonitored release points.

Considering the randon n. ure of radioactive decay and the inherent variability in radiation neasurement along with sanple

. Efflu nt R31 case R port

. August, 1988 Page 8 volune, flow rate, and pressure measurements, total Tritium measurenent of uncertainties may be less than 12 3 percent low and 51.2 percent high.

D. Liquid Effluents

1. Fission and activation products
a. Prior to releasing liquid radioactive waste to the environnent a sample is taken from the Radwaste !!olding Tank. This sample is representative of the tanks radicactive contents. The sample not only allows for the determination of radioactivo material but also establishes the rate at which the radioactive material can be discharged to the environnent. Radioactive activation and fission prodacts that are typically quantified are the following:

Mn-54 Fe-59 Co-58 co-60 Zn-65 Ho-99 Cs-134 cs-137 Co-141 Ce-144 (Othcr radionuclides as quantified)

For each holding tank that is discharged to the environment a representative sample of the tanks contents is retained. At the end of the calendar quarter a composite sample is made of all discharges occuring during the quarter. A composite is defined as a quantity of sampic that is proportional to the total discharged during the quarterly period. The composite sample is analyzed for Iron (Fe)-55 and strontion (Sr) 89/90. Both analytical methods involved radiochemical separation and quantification by liquid scintillation and gas proportional counting respectively.

The value reported is the sum of all fission and activation produc's quantified in all batch releases.

Considering the random iature of radioactivo decay and the inherent variability in radiation neasurenent along with flow rate and voluno measurcnonts, total fission and activation product noasurement of uncertainties may be icss than 14 3 percent.

2. Tritiun
a. For each holding tank that is discharged to tho environment a representative sample of the tanks contents is retained. At the end of the calendar month a conposito sample is made of all discharges occuring during the nonth. A composito is defined as a quantity of sample that is proportional to the total discharged during the calendar nonth. The composite sanple is

Effluent R1100se R; port August, 1988 P ge 9 analyzed for Hydrogen (H)-3 (Tritium) by Liquid scintillation counting.

The value reported is the sua of all Tritius quantified from all batch releases.

Considering the randon nature of radioactive decay and the inherent variability in radiation measurement along with flow rate and volur,e measurements, total fission and activation product measurement of uncertainties may be less than 14 3 percent.

3. Dissolved and Entrained Gases
a. Dissolved and entrained gases are quantified by gamma

! spectroscopy for each batch re' ease. The following radiogases i

are typical of those considered when quantified:

Kr-85a Xe-131 Kr-85 -

Xe-133 Kr-88 Xe-137 Kr-89 Xe-138 The value reported is the sua of all radiogases quantified for all batch sample tank reported releases.

Considering the random nature of radioactive decay and the inherent variability in radiation seasurement along with flow rate and volume measurements, total dissolved and entrained gases seasurement of uncertainties may be less than 15 percent.

4. Cross Alpha
a. For each holding tank that is discharged to the environment a representative sample of the tank contents is retained. At the end of the calendar month a composite sample is made of all discharges occurring during the sonth. A composite is defined as a quantity of sample that is proportional to the total discharged during the calendar month. The composite sample is analyzed for Gross Alpha radioactivity by gas proportional counting.

The value reported is the sua of Cross Alpha radioactivity quantified from all batch releases.

Considering the random nature of radioactive decay and the inherent variability in radiation measurement along with flow rate, volume and measurements, and compositing acasurements, i total gross alpha measurement of uncertainties may be less than 22 5 percent.

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l Efflu;nt R11 case Report

  • August, 1988 Page 10
6. BATCH RELEASES A summary of data for batch releases is provided in Section 8. Included are the number of releases, total time period for batch releases, and the maximum, average, and minimum time period of release.
7. ABNORMAL RELEASES No abnormal releases of radioactive material to the environment have occurred during this reporting period.

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Effluent Release Report August, 1988 Pago 11

8. BATCH RELEASE DATA REPORT CATEGORY  : BATCH RELEASE

SUMMARY

RELEASE POINT  : CIRCULATING WATER DECANT LINE TYPE OF RELEASE  : BATCH LIQUID FROM RADWASTE PERIOD START TIME  : 0000:00 HRS = 12:00AM JANUARY, 1988 PERIOD END TIME  : 4367:59 HRS = 11:59PM JUNE 30, 1988 LIQUID RELEASES NUMBER OF RELEA3ES  : 15 TOTAL TIME FOR ALL RELEASES : 6626.0 MINUTES MAXIMUM TIME FOR A RELEASE : 1076.0 MINUTES AVERAGE TIME FOR A RELEASE : 4417 MINUTES MINIMUM TIME FOR A RELEASE : 41.0 MINUTES e

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Effluent Relr.s3 Report August, 1988 *

  • P;ge 12
9. LIQUID EFFLUENT

SUMMARY

REPORT CATEGORY  : SEMIANNUAL SUMMMATION OF ALL RELEASES BY QUARTER TYPE OF ACTIVITY  : ALL LIQUID EFFLUENTS REPORTING PERIOD  : QUARTER 1 AND QUARTER 2

UNIT  : QUARTER 1 : QUARTER 2
: HOURS  : HOURS TYPE OF EFFLUENT  :  : 1-2184  : 2185-4368 A. FISSION AND ACTIVATION PRODUL75
1. TOTAL RELEASE (NOT INCLUDING l, TRITIUM, CASES, ALPHA)  : CURIES  : 2.67E-02  : 1.51E-G2
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD  : uCi/mi  : 1.15E-07  : 6.96E-08 B. TRITIUM
1. TOTAL RELEASE  : CURIES  : 2.73E-01  : 2 34E-01
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD -

uC1/ml  : 1.17E-06  : 1.08E-06 C. DISSOLVED AND ENTRAINED CASFS

1. TOTAL RELEASE  : CURIES  : 2.20E-04  : 4.98E-06
2. AVERAGE DILUTED CONCENTRATION DURING FERIOD  : uCi/e1  : 9 44E-10 2.30E-11 l

D. CROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE  : CURIES  : 5.23E-06  : 0.00E-01 l

E. WASTE VOL RELEASED (PRE-DILUTION)  : LITERS  : 3.82E+05 4.96E+05 l F. VOLUME OF DILUTION WATER USED  : LITERS  : 2.33E+08 : 2.17E+08 G. TOTAL VOLUME DILUTION WATER DISCRARCE  : LITERS  : 9.87E+09  : 9 49E+09 i

- . Effluent Release Report l

. August, 1988 )

Pcg3 13 9 '. LIQUID EHLUENT

SUMMARY

(continued)

REPORT CATEGORY  : SEMIANNUAL LIQUID BATCH RELEASES  ;

TYPE 0F ACTIVITY  : TOTALS FOR EACH NUCLIDE RELEASED

ALL RADION'CLIDES u

REPORTING PERIOD  : QUARTER 1 AND QUARTER 2 4

sBATCH RELEASES

UNIT QUARTER 1 : QUARTER 2
HOURS  : HOURS NUCLIDE  :  : 1-2184 2185-4368 ALL NUCLIDES H-3  : CURIES  : 2 73E-01  : 2 34-01 NA-24  : CURIES  : 7.47E-04  :

CR-51  : CURIES  : 6.50E-03 : 6.96E-03 MN-54  : CURIES  : 1.67E-03 : 1.70E-03 FE-59  : CURIES  : 6.81E-04 : 1.40E-03 Co-58  : CURIES  : 2.20E-03 : 2 33E-03 -

CO-60  : CURIES  : 5.60E-04 1.13E-03 ZN-65  : CURIES  : 5.20E-04 : 1.16E-03 SR-83  : CURIES  : 2.63E-03 :

SR-89  : CURIES  : 1.59E-04 : 7.99E-06 2R-95  : CURIES  :  : 1.78E-04 NB-95  : CURIES  :  : 2.22E-04 HO-99  : CURIES  : 9 74E-05 l'<1.4E-07 RU-103  : CURIES  : 3 09E-03 4.57E-05 TC-99H  : CURIES  : 5 35E-04 :

1-133  : CURIES  : 5.45E-05 :

CS-134  : CURIES  :'<1.0E-06 :8<1.0E-06 CS-137  : CURIES l*<2.0E-06 t*<2.0E-06 CE-141  : CURIES s'<2.0E-06 t'<2.0E-06 CE-144  : CURIES  : 1 33E-03 t'<4.0E-06 ND-147  : CURIES  : 1.29E-04 :

XE-135  : CURIES  : 2.20E-04 : 4.98E-06 SR-90  : CURIES  : 1.00E-05 :

G. ALPHA  : CURIES  : 5.23E-06 :

OTHER  : CURIES  : 5 77E-03 : 1 33E-05 TOTAL FOR PERIOD  : CURIES  : 3 00E-01  : 2.49E-01

  • Less than saximum sensitivity of seasurement in uCi/sl.

Effluent Release Report August, 1988 Paga 14

10. GASEOUS EFM,UENT

SUMMARY

REPORT CATEGORY  : SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER TYPE OF ACTIVITY  : ALL AIRBORNE EFFLUENTS REPORTING PERIOD  : QUARTER 1 AND QUARTER 2

UNIT  : QUARTER 1 : QUARTER 2
: HOURS  : HOURS TYPE OF EFFLUENT  :  : 1-2184  : 2185-4368 A. FISSION AND ACTITATION CASES
1. TOTAL RELEASE  : CURIES  : 4.26E-01  : 0.00E-01
2. AVERAGE RELEASE RATE FOR PERIOD : uC1/sec : 5.42E-02 : 0.00E-01 B. RADIOIODINES
1. TOTAL IODINE - 131  : CURIES  : 0.00E-01  : 1.66E-06
2. AVERAGE RELEASE RATE FOR PERIOD : uti/sec : 0.00E-01  : 2.13E-07 C. PARTICULATES -

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1. PARTICULATES l (HALF-LIVES >8 DAYS)  : CURIES  : 2.41E-04  : 8.53E-04
2. AVERAGE RELEASE RATE FOR PERIOD : uC1/sec : 3.07E-05 : 1.10E-04 f
3. CROSS ALPHA RADIOACTIVITY  : CURIES  : 5.64E-07  : 1.07E-07 D. TRITIUM
1. TOTAL RELEASE  : CURIES  : 0.00E-01  : 0.00E-01
2. AVERAGE RELEASE RATE FOR PERIOD : uC1/sec : 0.00E-01  : 0.00E-01

- Efflecnt Relenco Report

- August, 1988 Page 15

10. GASEOUS EFFLUENT

SUMMARY

(continued)

REPORT CATEGORY  : SEMIANNUAL AIRBORNE CONTINUOUS REuEASES TYPE OF ACTIVITY  : FISSION OASES, IODINES, AND PARTICCt.A7ES REPORTING PERIOD  : QUARTER 1 AND QUARTER 2

GROUND RELEASES
UNIT  : QUARTER 1 : QUARTER 2
: HOURS  : HOURS NUCLIDE  :  : 1-2184  : 2185-4368 PARTICULATES HO-99  : CURIES  : '<1.0E-10 '<1.0E-10 TC-99H  : CURIES  : 1 90E-04 I-131  : CURIES  : '<1.0E-10 : 1.66E-06 NA-24  : CURIES  : '<1.0E-10 : '<1.0E-10

. CR-51  : CURIES  :  : 4.14E-04 HN-54  : CURIES  : '<1.0E-10 : 4.64E-05 FE-59  : CURIES  : '<1.0E-10 : '<1.0E-10 C0-58  : CURIES  : 1.75E-05 : 7.04E-05 C0-60  : CURIES  : '<1.0E-10 3 3 12E-05 CU-64  : CURIES  : '<1.0E-10 '<1.0E-10 ZN-65  : CURIES  : 1.89E-04 : 3 51E-05 SR-89  : CURIES  : 1.99E-05 5.40E-05 CS-134  : CURIES  : '<1.0E-10 : '<1.0E-10 CS-137  : CURIES  : '<1.0E-10 : '<1.0E-10 CE-141  : CURIES  : '<1.0E-10 '<1.0E-10 CE-144  : CURIES  : 8<1.0E-10 : '<1.0E-10 SR-90  : CURIES s'1.44E-05  : 1.13E-05 G ALPHA  : CURIES  : 5.64E-07  : 1.07E-07 TOTAL FOR PERIOD  : CURIES  : 2.41E-04  : 8.53E-04 FISSION CASES KR-85H  : CURIES  : 4.26E-01 :

KR-87  : CURIES :8<0.1E-04  : '<0.1E-04 KR-88  : CURIES **<0.1E-04  : '<0.1E-04 XE-133H  : CURIES  : # < 0.1 E-O'4  : '<0.1E-04 XE-133  : CURIES  :'<0.1E-04  : '<0.1E-04 XE-135  : CURIES s'<0.1E-04  : '<0.1E-04 XE-138  : CURIES s'<0.1E-04  : '<0.1E-04 TOTAL FOR PERIOD  : CURIES  : 4.26E-01 : <0.1E-04

  • Less than maximum sensitivity of measurement in uCi/al.
  • Effluent R;1 cts 3 Report August, 1988 P:ge 16
11. SOLID WASTE AND IRr*.DIATED FUEL SHIPMElnS A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)
1. Type of Waste Unit 6-Honth Est. Total Period Error,5
a. S' pent resins, filter sludges, a3 9.18E+1  ! 25 evaporator bottoms, etc. C1 2.75E+2 + 25
b. Dry compressible waste, a3 1.87E+1 1 25 contaminated equip, etc. Ci 3 27E-1 + 25
c. Irradiated components, control m3 wong rods, etc. Ci NONE NONE m3 wong
d. Other (describe)

Ci NONE NONE

2. Estimate of major nuclide composition (by type of waste)
a. See Attachment #1 (Spent Resins) $ E

$ E

% E

b. See Attachment #2 (Dry Waste)  % E

% E

% E

o. None  % E_

% E

% E E ___

d. None  %

% E

$ E!~

3 Solid Waste Disposition Number of Shipconts Mode of Transportation Destination 11 Truck Barnwell, S.C.

2 Truck Interim Processor-Barnwell, S.C.

B. Irradiated Funi Shipments (Disposition)

Number of Shipacnts Mode of Trar.sportation Destinaticn None None None Completed by T. Duberville /s/ Date 7/12/88 I

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- - Effluent R21e32;3 R3 port August, 1988 1

P ge 17 I I

ATTACHMENT 1 ESTIMATE OF MAJOR NUCLIDE COMPOSITION ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF NASTE) 2a. Spent resins, filter sludges, evaporator bottoms, etc.

Percent Abundance Total Curles Cr-51 42.979 1.18E+2 Mn-54 13 913 3.82E+1 Fe-59 3 788 1.04E+1 Co-60 5.645 1.55E+1 Co-58 15.990 4 39E+1 Zn-65 7.758 2.13E+1 C-14 0.543 1.49 H-3 0.188 5 16E-1 Cs-137 0.062 1.69E-1 Fe-55 6.410 1.76E+1 Ba-131 1.599 4.39 Cd-109 1.125 3 09 100.000 2.75E+2 ,

Approved by T.Duberville /s/ Date 7/12/88 t

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Efflugnt Rele:co R; port August, 1988 Page 18 ATTACIDENT 2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION ESTIMATE OF HAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE) 2b. Dry Compressible Waste, Contaminated equipment, etc.

Percent Abundance Total Curles Cr-51 6.516 2.13E-2 Mn-54 17 712 5.79E-2 Fe-55 17.284 5.65E-2 Co-58 30.132 9.85E-2 Co-60 21.475 7.02E-2 Zn-65 6.730 2.20E-2 H-3 0.053 1.73E-4 C-4 0.098 3 21E-4 100.000 3 27E-1 All DAW was shipped in 55 gallon drums to an intermediate waste processor and af ter processing will be shipped to Barnwell for final disposal, r

Spproved by T. Duberville /s/ Date 7/12/88

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SOLID WASTE SuunsARY WORKSHEET Enclosure 1 Page 1 of 3 ,

Solid haste Category Spent Rostn Filter Stud 9es. Evap Bottoms, etc.

Reporting Period January 1 1988 through June 30, 1988 l l Shipment Number l l Parameter 1 l 2 3 4 5 TOTAL l l i i

11. Date  ! l l 1 ,

1 l (Mo/ca/Yr) ll 01/t3/88 1 01/26/88 l 02/13/88 1 02/15/88 ll 02/24/88 l l h i I I I i

12. Volume (m3) l l l l l l a. maste '

8.7 l 8.5 l 5.18 5.04 7.99 l h b. Burtal 9.3 l 9.3 1 5.8 5.8 1 9.3 1 39.5 i 1

3. Radioacttwity 1 l l H Content (Ct) l I H ll a. Cr51 7.46E-2 '

9.41E-2 1.43E+1 5.19E+1 1.81E-1 6.65E+1 l i b. un 54 1.0?E-1 9.15E-2 7.41 1.18E*1 2.14E-t 1.96E+1 l c. Fe 5 '3 4.10 E-3 1.4?E-2 4.55 5.45E-2 4.62 I o. Co 57 I .. Co 60 4.55E-2 4.26E-2 1.17 4.35 8.79E-2 5.70 I e. Co 5a H.M46-2 H.9me-7 5.54 1.75E+1 2.hbE-t 2.35E+1

g. 2n 65 5.68E-2 5,02E-2 3.09 6.40 7.58E-2 9.67
n. Ct4 4 4MF-3 4.H3F-3 2.01F-2 7.96F-2 2.04E-2 1.40E-1 4 H3 2.09E-3 2.OSE-3 4.48E-3 1.75E-2 4.28E-3 1.04E-2 h J. 50 924 l h. I 131 l t, La ta0 l 1 m. em 140 l l n. (s 137 i l

1 o. F. 55 3.8 E-2 3.44E-2 1.52 5.64 7.06E-2 7.30 l l p. Sa IJ1 3.16 3.16 1 l q. l l r. l

14. Total Radio- , , ,

I I acttwity (C1) ll 4.22E-1 1 4.29E-l I 33.1 l 1.05E+2 9.94E-1 l 1.4E+2 1 1 1 I I i

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e Effluent Reic:se RIport August., 1988 Page 19

. 12. CHANGES M 11{E PROCESS COKTR)L TROGRAM (PCP)

There were no changes to the Process Control Program during the first half reporting year.

13. CHANGES TO 11tE OFT SITE DOSE CALCULATION MANUAL (ODOO There were no changes to the Off Site Dose Calculation Manual during the first half reporting year.
14. RADIATION INSTRUMENTATION No Radiation Instrumentation as listed in tables 3 3 7.11-1 and 3 3 7.12-1 of the Fermi 2 Technical Specifications exceeded the 30 day limiting condition of operation.

.. e j

  • B. Ralph 5ylvb c sen a v.c ereseent l k

!,I 64ao smn ome ssn..,

ROOM Newport. M(hegan 48166 ICVI I oi:, w&4 tw 4

August 29, 1988 l NRC-88-0206 I 1

U. S. Nuclear Regulatory Commission Attention: Document Control Desk l l

Washington, 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 6.9.1.8

Subject:

Semi-Annual Radiological Effluent Release Report The Semi-Annual Effluent Release Report for Fermi 2 is attached. This report is being transmitted in compliance with Reference 2 and Regulatory Guide 1.21 Revision 1. The attached report covers the period from January 1 through June 30, 1988.

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.

$fatpAO cc A. B. Davis R. C. Knop T. R. Quay W. G. Rogers Region III 4

! I

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