Text

Semiannual Radiological Effluent Release Rept,Jan-June 1987
	ML20237G285
Person / Time
Site:	Fermi
Issue date:	06/30/1987
From:	Sylvia B; DETROIT EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	CON-NRC-87-0142, CON-NRC-87-142, RTR-REGGD-01.021, RTR-REGGD-1.021 NUDOCS 8709020181
	Download: ML20237G285 (53)
	v • d • e

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S3Y:- AXXUA:1 RAJ:~.0:10 GIC A:1 3:U:1UEX" :R3:1E ASE

R3?O:RT JANUARY 1,1987 to JUNE 30, 1987 O

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Prepared by: Radiological Engineering Group y g6 lM'E8E!i858llp

DETROIT EDISON COMPANY FERMI - 2 NUCLEAR POWER PLANT OPERATING LICENSE NO, NPF - 43 GEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD OF JANUARY 1,1987, THROUGH JUNE 30,1937 n

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- TABLE OF CONTENTS l Page 3 Introduction 4 Regulatory Limits l l

j 5 Maximum Permissible Concentration 5 Average Energy i 6 Measurements and Approximations of Total Activity 1

9 Batch Releases I 9 Abnormal Releases 10 Batch Release Data l 11 Liquid Effluent Summary 13 Gaseous Effluent Summary ,

15 Solid Waste and Irradiated Fuel Shipments i 23 Changes to the Process Control Program (PCP) 36 Changes to the Offsite Dose Calculation Manual (ODCM) l l

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FERMI-2 SEMIANNUAL RADIOLOGICAL EFFLUENT REPORT l

INTRODUCTION Fermi 2 is designed and operated to strictly control the release of radioactive effluents to the environment in accordance with the Nuclear Regulatory Commission (NRC) regulations. This Semlannual Radioactive Effluent Report provides the following information:

o summation of the quantities of radioactive material (in the form of gases and liquids) released from the plant o Summation of the quantities of radioactive material contained in solid waste packaged and shipped for offsite disposal at federally approved sites.

o Changes to the Process Control Program (PCP) l s Changes to the Offsite Dose Calculation Manual (ODCM) in the reporting period, January through June 1987, the total gaseous and liquid effluent releases were maintained As Low As Reasonably Achievable (ALARA).

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1. Regulatory Limits A. Gaseous Effluents

1. Dose rate due to radioactive materials releared in gaseous effluerits from the ;

site to areas at and beyond the site boundary shall be limited to the following: l

a. Noble gases - Less than or equal to 500 mrem /y6ar 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 er equal to 1500 mrem / year to any organ

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

a. Less than or equal to 5 mrads for gamma radiation ,

Less than or equal tc 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 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 mrems to any organ

- During any calendar quarter l

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 Regulations Part 20 (Standards for Protection Against Radiation), Appendix B, Table 11, Column 2 for Radionuclides other than dissolved or entrained noble gases. For dissgived or entrained noble gases, the concentration shall be limited to 2 X 10~ (.0002) microcuries/mi total {

activity. :

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2. The dose or dose commitment to a member of the public from radioactive ,

materials in liquid effluents released, from each Reactor Unit to unrestricted areas shall be limited: J

a. Less than or equal to 1.5 mrem to the total body Less than or equal to 5 mrem to any organ l

- During any calendar quarter

b. Less than or equal to 3 mrem to the total body Less than or equal to 10 mrem to any organ l - During any calendar year

2. MAXIMUM PERMIS. tele CONCENTRATION

l. A. Liquids 1

1. The maximum permissible concentrations (MPC) for liquids are those listed in 1 10 CFR 20, Appendix B, Table 11, Column 2, with the most restrictive MPC bemg ;

used in all cases. For dissolved and entrained gases the MPC of 2.OE -4 1 microcuries/ml is applied. This MPC is based on Xe-135 MPC in air 3 (submersion Dose) converted to an equivalent concentration in water as !

discus' sed in the International Commission on Radiological Protection (ICMP) ]

Publication 2. i B. Gaseous j

)

1. The maximum perniissible dose rate for gaseous releases are defined in plant. l Technical Specifications. j

a. Technical Specification 3.11.2.1.a (Dose rate at site boundary from j gaseous effiuents in the form of noble gases) 1

- Less than or equal to 500 mrem / year to total body 1

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

b. Technical Specification 3.11.2.1.b (lodine - 131,133, Tritium, and particulate with half-lives greater than 8 days.)

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

3. AVERAGE ENERGY The Fermi 2 Technical Specifications limit the re. lease retes for fission and activation ga.ses to less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the sicin. Therefore, the averene beta and gamma energies (E) for gaseous efflyants as described in Regulatory Guide 1.21 " Measuring, Evaluatmg and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" is not applicable, 1

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4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY A. Gaseous Effluents

1. Fission and Activation Gases

a. Samples are obtained from each of the seven pitnt eff uent radiation monitors, which monitor the six ventilation exhaust poirits. 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 reported total of fission and activation gases is the value of the sum of all the monitored releases.

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 and activation gases measurement of uncertainties may be less than 7.4% low and 50.3% high.

2. Radiolodines

a. Samples are obtained frorn each of the seven plant effluent radiation monitors, which monitor the six ventilation exhaust points. The radiciodines are entrained on a charcoal media. The radiciodines are 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 radioiodines tha; are quantified for dose calculations are the following:

1-133 1-130 1-131 1-132 1-133 1-134 1~134 l-135 The reported total of radiciodines is the value of the sum all the rnonitored releases.

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3. Particulate 1 i

a. Samples are obtained from eech of the seven plant effluent' radiation monitors which monitor the six ventilation exhaust points. The particulate are entrained on a filter media. The particulate are then j 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, in each case the flow rate of the . q ventilation system is known such that a rate of release can be . .]

determined. The particulate that are quantified for dose calculations are typical of the following*

I Mn-54 Fe-59 Co-58 l Co-60 Zn-65 Mo-99 Cs-134 Cs-137 Ce-141 '

Ce-144 (Also other radionuclides with half-lives greater than 8 days) 1 A compocite of the filters obtained from each ventilation release point are )

analyzed monthly for gross alpha radioactivity, by proportional counting, I and quarterly for Sr 89/90 activity by radiochemical seperation and gas proportional counting. If quantified, these totals are. reported as total particulate activity. )

l The reported total particulate activity is the value of the sum all the monitored releases.

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1 l 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 radiolodine and particulate l measurement of uncertainties may be less than 22.9% tow and 54.8% high.

l 4. Tritium

a. Samples are obtained from each of the seven plant effluent radiation ,

monitors which monitor the six ventilation exhaust points. The sample is J passed through a bottle containing water, While the sample is being passed through the bottle the Tritium is " washed" out to the collecting water. Portions of the collecting water are analyzed for Tritium using I liquid scintillation counting techniques. For each sample, the duration of sampling and sample flow rate is used to determine the concentration, if quantified the reported total Tritium release is the value of the sum of the monitored releases.

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Page 8 Considering the random nature of radioactive decay and the inherent J variability Iri radiation measurement along with sample volume, flow rate, j and pressure measurements, total Tritium measurement of uncertainties i may be less than 12.3% low and 51.2% high.

B. Liquid Effluents:

1. Fission and activation products I

a. Prior to the release of a waste sample tank, representative samples are obtained. Fission and activation products are quantified by gamma spectroscopy analysis. The radionuclides quantified are included in the dose calculations. Fission and activation products quantified are typical of the following:

Mn-54 Fe-59 Co-58 Co-60 3 Zn-65 Mo-99 1 Cs-134 Cs-137 Ce-141 Co-144 I

l (Other radionuclides as quantified)

From each batch release a purtion of the sample is retained as a composite. A composite is defined as a quantity of sample that is proportional to the amount of the total discharged, anc representative of the amount discharged. The composite sample is analyzed for Fe-55 and Sr-89/90. Both methods involve radiochemical separation along with l quantification by liquid scintillation and proportional counting respectively, !

I The total radionuclides released in this report is the sum of all ;

radionuclides in all batch releases. I Considering the random nature of radioactive decay and the inhereat l variability in radiation measurement along with flow rate and volume measurements, total fission and activation product measurement of uncertainties may be less than 14.3%

2. Tritium

a. From each batch release, a portion of the sample is retained for compositing. A composite is defined as a quantity of sample tl'at is proportional to the amount of the total discharged, and is reprr.sentative of the amount discharged. The composite sample is analyzed for Tritium by liquid scintillation counting. The total Tritium activity reperted is the sum of the Tritium activities for all batch releases.

. Page 9 Considering the random nature of radioactive decay and the inherent vanability in radiatlan measurement along with flow rate and voiamo measurements, total fission and activation product measurement of uncertainties may be less than 14.3%

3. Dissolved and Entrained Gases

a. Dissolved and entrained gases are quantified by gamma spectroscopy for each batch release. The following radiogases are typical of those considered when quantified:

Kr-8bm Xe-131 Kr-85 Xe-133 Kr-88 Xe-137 Kr-89 Xe-138 The total reported is the sum of all radiogases quantified 1or all hatch sampie tank reported releases.

Considering the random nature of radiohetive decay and the inherent variability in radiation measurement along with flow rate and volume measurements, tote.1 dissolved and entrained gases measurement of uncertainties may be less than 15%.

4. Gross Alpha

a. From each batch release, a portion of the sample is retained for compositing. A composite is defined as a quantity of sampie that is proportional to the amount of the total discharged, and is representative of the amount discharged. The composite sarr.ple is analyzed for gross aloha by gas proportional counting. The total grecs alpha activity reported is the sum of the gross activities for 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 measurements, total gross alpha measurement of uncertainties may be less than 22.5%.

5. BATCH RELEASES A. A summary of data for batch releases is provided on Page 10. Included are the number of releases, total time period for batch releases, and the maximum, average, and minimum time period of release.

6. ABNORMAL RELEASES i i

No abnormai releases of radioactive material to the envirot, ment have occurred during this reporting period.

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>i REPORT CATEGORY

BATCH RELEASE

SUMMARY

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RELEASE POINT

CIRCULATING WATER DECANT LINE l TYPE OF RELEASE : BATCH LIQUID FROM RADWASTE

. PERIOD START TIME : 00:00:00 = 12:00AM JANUARY,1987 ;

PERIOD END TIME r

43:43.59 HRS = 11:59PM JUNE 30,1987 LIQUID RELEASES I

NUMBER OF RELEASES : 75 i TOTAL TIME FOR ALL RELEASES : MINUTES 39005 l MAXIMUM TIME FOR A RELEASE : MINUTES 656 AVERAGE TIME FOR A RELEASE : MINUTES 520.1 MINIMUM TIME FOR A RELEASE : MINUTES 1 i

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Page 11 1.lOUID 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 : O'UARTER 1 . QUARTER 2

HOURS . HOURS TYPE OF EFFLUENT -

1-2160 .2161-4344 A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL REL EASE (NOT INCLUDING TRITIUM, OASES, ALPHA) CURIES 4.92E-03 1.04E-03

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ml 4.33E-09 7.51 E- 10 B. TRITIUM

1. TOTAL RELEASE CURIES : 1.00 E-01 3.96E-01

2. AVERAGE DlLUTED CONCENTRATION DURING PERIOD uCi/ml 8.81 E-08 2.86E-07 C. DISSOLVED AND ENTRAINED GASES __

1. TOTAL RELEASE CURIES 9.67E-05 4.78E-05 _

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ml 8.52E-11

3.45E-11 D. GROSS ALPHA RADIDACATIVITY

1. TOTAL RELEASE CURIES 0110E-01 0.00E-01 E. WASTE VOL RELEASED (PRE-DlLUTION) LITERS 2.49E+06 3.00E+06 F. VOLUME OF OlLUTION WATER USED LITERS :1.14E+09 1.39E+ 09 l

G. TOTAL VOLUME DILUTION DISCHARGED LliERS 8.40E+ 09 9.90E+ 09

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REPORT CATEGORY : SEMIANNUAL LIQUID BATCH RELEASES TYPE OF ACTIVITY : TOTALS FOR EACH NUCLIDE RELEASED ALL RADIONUCLIDES REPORTING PERIOD QUARTER 1 AND QUARTER 2 l

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1 BATCH RELEASES UNIT QUARTER 1 : QUARTER 2 HOURS HOURS NUCUDE -

1-2160 2151-4344 ALL NUCLIDES ,

H-3 : CURIES 1.00 E-01 : 3.96E-01 NA-24 : CURIES 3.60E-04 2.43E-05 CR-51 . CURIES . 1.52 E-03 3.47E-04 MN-54 CURIES . 4.54E-04 6.04E-05 FE-59 CURIES * < 0.5E-07 * < 0.5 E-07 CO-58 CURIES 1.82 E-03 . 3.67E-04 CO-60 CURIES 1.45E-05 . 1.53 E-05 CU-64 CURIES 1.24 E-04 ZN-65 CURIES * < 0.5E-07 * < 0.5E-07 BR-83 : CURIES 5.35E-04 -

MO-99 CURIES * < 1.4 E-07 * < 1.4E-07 TC-99M CURIES 7.73E-05 -

I-133 : CURIES 7.41E-06 :

CS-134 CURIES . * < 0.1 E-07 : * < 0.1 E-07 CS-137 : CURIES . * < 0.2 E-07 : 4.96E-05 CE-141 . CURIES . * < 0.2 E-07 * < 0.2 E-07 CE-144 CURIES * < 0.4E-07 * < 0.4E-07 XE-133 : CURIES 5.62E-05 3.01 E-05 XE-135M : CURIES . 4.05E-05 : 1.77E-05 OTHER CURIES 5.10E-05 TOTAL FOR PERIOD CURIES 1.05 E-01 3.97E-01

Less than the maximum sensitivity of measurement in uCl/mi L___________-___

T Page 13 GASEOUS EFFLUENT

SUMMARY

REPORT CATEGORY : SEMlANNUAL'SUMMMATION OF ALL RELEASES BY OUARTER '

TYPE OF ACTIVITY : ALL AIRBORNE EFFLUENTS REPORTING PERIOD : QUARTER 1 AND QUARTER 2 -

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UNIT : QUARTER 1 : QUARTER 2

: HOURS HOURS TYPE OF EFFLUENT : : 1-2160 : 2161-4344-A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 0.'00E-01 0.00E-01 l

2. AVERAGE RELEASE RATE FOR PERIOD uCl/sec 0.00E-01 0.00 E-01 )

B. RADIOlODINES

1. TOTAL LODINE - 131 CURIES : 0.00E-01 0.00E-01 2,. AVERAGE RELEASE RATE FOR PERIOD uCl/sec .0.00E-01 : 0.00E-01 .

C. PARTICULATE

1. PARTICULATE (HALF-L'VES >8 DAYS) CURIES 1.44E-04 9.29E-04

2. AVERAGE RELEASE RATE FOR PERIOD : uCi/sec 1.85E-05 : 1.18E-04

3. GROSS ALPHA RADIOACTIVITY : CURIES 5.42E-07 . 5.24E-07 D. TRITlUM j l

1. TOTAL RELEASE CURIES 0.00E-01 *0.00E-01 !

2. AVERAGE RELEASE RATE FOR PERIOD . uCi/sec 0.00E-01 0.00E-01

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REPORT CATEGORY : SEMIANNUAL AIRBORNE CONTINUOUS RELEASES l TYPE OF ACTIVITY FISSION OASES, IODINES, AND PARTICULATE REPORTING PERIOD - QUARTER 1 AND QUARTER 2 l : GROUND RELEASES 1

UNIT : QUARTER 1 : QUARTER 2

. HOURS . HOURS NUCLIDE 1-2160 2161-4344 PARTICULATE l

MO-99 CURIES : * < 0.1 E-11 : * < 0.1 E-11 1 TC-99M CURIES -

5.33E-05 l I l-131 CURIES * < 0.1 E- 1 1 . * < 0.1 E- 1 1 CS-134 . CURIES : * < 0.1 E-11 * < 0.1 E- 11 NA-24 CURIES . 2.21 E-04 CR-51 CURIES . 5.29E-05 3.92E-04 MN-54* : CURICS * < 0.1 E- 11 : 7.65E-05 MN-56 CURIES , 2.03E-03 FE-59* . CURIES : * < 0.1 E-11 * < 0.1 E- 11 CO-60* CURIES * < 0.1 E- 1 1 : * < 0.1 E-11 CU-64 CURIES . . 5.87E-03 l ZN-65 CURIES * < 0.1 E- 1 1 . 1.12 E-0 5 SR-89 CURIES . 2.176-06 : 8.38E-06 CS-137 CURIES * < 0.1 E- 11 . * < 0.1 E- 1 1 BA-139 . CURIES 3.82E-04 : 2.71E-04 l CE-141 CURIES * < 0.1 E- 11 . * < 0.1 E-11 l CE-144 CURIES * < 0.1 E- 1 1 . * < 0.1 E- 11 l

SR-90 CURIES 5.66E-05 2.09 E-04 I G ALPHA CURIES 5.42E-07 5.24E-07 TOTAL FOR PERIOD CURIES 5.26E-04 9.37E-03 l

FISSION GASES KR-87 CURIES . * < 0.1 E-04 : * < 0.1 E-04 KR-88 . CURIES * < 0.1 E-04 : * < 0.1 E-04 XE-133M . CURIES . * < 0.1 E-04 * < 0.1 E-04 l XE-133 CURIES : * < 0.1 E-04 : * < 0.1 E-04 l XE-135M CURIES : * < 0.1 E-04 : * < 0.1 E-04 XE-135 CURIES . * < 0.1 E-04 . * < 0.1 E-04 XE-138 CURIES * < 0.1 E-04 * < 0.1 E-04 l

TOTAL FOR PERIOD CURIES -

<0.1E-04 <0.1E-04

Less than the maximum sensitivity of measurement in uCl/ml

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SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

1. Type of Waste Unit 6-Month Est. Total Period Error, %

m3

a. Spent resins, filter sludges, 3.38E+2 evaporator bottoms, etc. Cl 1.609E + 1

b. Dry compressible waste, m3 0.000E contaminated equip, etc. Ci 0.000E E

c. Irradiated components, control m3 0.000E rods, etc. Cl 0.000E E

d. Other (describe) m3 E Cl E E

2. Estimate of majo nuclide composition (by type of waste)

a. See Attachment #1 % E

% E

b. None % E

% E

c. None % E

% E

d. None % E

% E

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 23 Common Carrier (Flatbed Barnwell, S.C.

w/ Shipping Cask)

B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination None None None Approved by [ fjt Date NM

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- Page 16 ATTACHMENT 1: ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE) 2a. Spent resins. filter sludges, evaporator bottoms, etc.

Percent Abundance Total Curies Cr51 44.18 7.108E +0 Mn54 6.23 1.002E+0 Co60 0.17 1.314E+0 CoS8 35.94 5.782E+ 0 C14

0.42 6.774E-2 NiS3 0.17 2.759E-2 H3 0.04 6.345E-3 Fe59 2.10 3.378E-1 CoS7 - 0.03 5.370E-3 Zn65 2.52 4.051 E- 1 1131 0.02 3.124 E-3 Sb124 0.05 7.412E-3 l Ce141 0.04 7.062E-3 Ba140 0.01 1.401 E-3 Cs137 0.08 1.265E-2 l Sr90 < 0.01 5.202E-4 l Pu241 < 0.01 5.817E-5 l La140 < 0.01 2.244E-6 Total: 100 % 1.609E1 - 1 l

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M-87 .

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Page 17 SOLID WASTE

SUMMARY

WORKSHEET Sheet 1 of 1 Solid Waste Category Spent Resin, Filter Sludges, Evap Bottoms, etc.

Reporting Period: 1, January 1987 through 30, June 1987 Totals Page 1 of 1 thru 1 of 5 Parameter l Shipment Number Total l 1 2 3 4 5 Page Page Page Page Page

1. Date (Mo/Da/Yr) 1 of 5 2 of 5 3 of 5 4 of 5 5 of 5 l

3 g 2a. Volume (m )

b. Burial Volume 24.4 24.4 25.35 36.11 27.93 138.19

3. Radioactivity Content (Ci)

a. Cr51 1.838E+0 2.579E+0 1.371 E- 1 2.426E+0 1.283E-1 7.108E+0 I

b. Mn54 1.400 E- 1 1.672 E- 1 1.212E-2 5.310E-1 1.520 E- 1 1.002 E+ 0 l c.Co60 6.404E-1 1.997 E-1 1.923E-2 3.377 E-1 1.172 E- 1 1.314 E + 0 l d.CoS8 1.723 E+0 1.047 E + 0 6.849E-2 2.405E+0 5.382E-1 5.782E+0 l e.C14 1.118E-2 1.204E-2 7.686E-3 2.067E-2 1.616 E-2 6.774 E-2 l

f. Ni63 1.345E-2 4.192 E-3 4.039E-4 7.089E-3 2.460E-3 2.7 59 E-2 l g.H3 3.901 E-4 3.712E-4 3.867E-4 2.294 E-3 2.903E-3 6.345E-3 l1 h.Fr59 1.937E-2 5.595E-2 4.551 E-3 2.401 E- 1 1.781 E-2 3.378E-1 l

i. CoS7 2.630E-3 9.164 E-4 1.7 74 E-3 5.320E-3 ll j.Zn65 6.017E-2 8.109 E-2 6.508E-3 1.994E- 1 5.794E-2 4.051 E-1 ll k.1131 1.204 E-3 8.356E-5 9.389E-4 8.977E-4 3.124 E-3 l ,

I.Sb124 1.782E-3 5.630E-3 7.412E-3 l

m. Ce141 5.035E-3 2.027E-3 7.062E-3 l n.Ba140 3.094 E-4 1.092 E-3 1.401 E-3 l o.Cs137 3.873E-4 1.226 E-2 1.265E-2 l

p. Gr90 2.029E-5 4.999 E-4 5.202E-4 q.Pu241 5.817E-5 5.817E-5 r.La140 2.244E-6 2.244E-6

4. Total Radio-activity (Ci) ' 4.449 E + 0 4.155E+ 0 2.573E- 1 ' 6.180 E+ 0 1.047 E+0 1.609 E- 1

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- Page 18 SOLID WASTE

SUMMARY

WORKSHEET

~ Sheet 1 of 5 Solid Waste Category Spent Resin, Filter Sludges, Evan Bottoms, etc.

Reporting Period: 1, January 1987 through 30, June 1987 Parameter ; Shipment Number Total 1 2 3 4 5

1. Date (Mo/Da/Yr) .

01/13/87 01/20/87 01/23/87 01/26/87 01/30/87 3 l 3.824 3.790 3.857 4.057 19.55 2a. Volume (m ) l 4.024 l

b. Burial Volume 4 88 4.88 4.88 4.88 4.88 24.4

3. Radioactivity Content (Cl) i

a. Cr51 1.994E-2 1.875E-2 8.439E-3 3.109E-3 1.788E +0 1.838

b. Mn54 1.828E-3 1.246E-3 9.099E-4 4.308E-4 1.356E- 1 1.400 E- 1

.c.Co60 7.083E-3 2.573E-3 1.508E-3 1.089E-3 6.281 E-1 6.404 E- 1 d.CoS8 1.916E-2 9.575E-3 6.615E-3 3.651 E-3 1.684 E+ 0 1.723E+ 0 i e.C14 1.925E-3 1.306E-3 1.077E-3 9.719E-4 5.903E-3 1.118E-2 ,

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f. Ni63 1.488E-4 5.404E-5 3.166E-5 2.286E-5 1.319E-2 1.345E-2 g.H3 8.573E-5 3.148E-5 7.218E-5 7.346E-5 7.726E-5 3.901 E-4 l l 1.93 7 E-2 h.Fe59 1.937E-2 1.CoS7 2.630E-3 2.630E-3 j.Zn65 6.017E-2 6.017E-2 j k.

l. j m.

n.

o.

p.

4 r.

4. Total Radio-activity (Cl) 5.017E-2 3.359E-2 1.865E-2 9.354E-3 4.337 E+ 0 4.449E+0 .

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5. Type of l Container STC STC 'STC .STC lSTC

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6. Source of Waste Cndnsate Cndnsate ICndnsate lCndnsate lCndnsate j & RWCU

7. Processing L Employed Dewater Dewater Dewater Dewater Dewater

8. Solidification Agent None None None None INone l l _ _ . _'

n 1 Approved by Mr , , _

Date [~/bb

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Page 19 SOLID WASTE

SUMMARY

WORKSHEET i

Sheet 2 of 5 j i

Solid Waste Category Spent Resin, Filter Sludges, Evap Bottoms, etc. 1 Reporting Period: 1 Janubry 1987 through 30, June 1987

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l l

I l Parameter i Shipment Number Total l l 1 2 3 4 5 l l

1. Date (Mo/Da/Yr) 02/03/87 02/10/87 .02/18/87 02/24/87 '

02/25/87 3 '

2a. Volume (m ) waste l 3.846 4.057 3.924 3.870 3.794 19.491 l

b. Burial Volume 4.88 4.88 4.88 4.88 4.88 24.4 I !

I

3. Radioactivity l l j Content (Ci) l j

a. Cr51 3.999E-2 1.037E-2 1.467 E-2 2.479 E + 0 3.476E-2 2.579 E + 0

b. Mn54 1.785E-2 4.568E-3 3.107 E-3 1.346E- 1 7.087 E-3 1.672E- 1 c.Co60 1.729E-2 4.933 E-3 3.437E-3 1.479E- 1 2.610E-2 1.997E- 1 ~l ,

d.CoS8 1.158 E- 1 2.795E-2 1.605E-2 8.354E-1 5.204E-2 1.047 E + 0~ lI e.C14 2.553E-3 1.704 E-3 1.470E-3 3.385E-3 2.923E-3 1.204 E-2 ll

f. M63 3.631E-4 1.036E-4 7.218E-5 3.105E-3 5.481 E-4 4.192 E-3 l l g. H3 7.325E-5 7.726E-5 7.473 E-5 7.370E-5 7.224E-5 3.71 ?E-4 l l h.Fe59 1.467 E-3 6.147 E-4 5.387E-2 5.595E-2 l i.CoS7 9.164 E-4 9.164 E-4 l j.Zn65 2.709E-3 2.697 E-4 4.528E-4 7.378E-2 3.880E-3 8.109E-2 l k.1131 1.204E-3 1.204 E-3 l 1.Sb124 1.782E-3 1.782 E-3 l

m. Ce141 5.035E-3 5.035E-3 l ,

n. l j

o. l' P. I

q. l

r. l' l

4. Total Radio-l activity (Ci) l 1.981 E-1 5.059E-2 3.933E-2 3.740E + 0 1.274E- 1 4.155E +0 1

5. Type of Container STC STC STC STC STC

6. Source of Waste Cndnsate Cndnsate Cndnsate Cndnsate Cndnsate l

& RWCU l

, 7. Processing Employed i Dewater Dewater Dewater Dewater Dewater I l l l 8. Solidification l l l l l Agent lNone lNone 'None lNone ',None l l

l l l l l Approved by /ty Date [/)

i J

) '

Page 20 ,

SOLID WASTE

SUMMARY

WORKSHEET Sheet 3 of 5 Solid Waste Category Spent Resin, Filter Sludges, Evap Bottoms, etc.

Reporting Period: 1, January 1987 through 30, June 1987 I

Parameter Shipment Number Total l j 1 2 3 4 5 l l l

1. Date (Mo/Da/Yr) 02/26/87 02/27/87 02/28/87 03/03/87 .03/19/87 i

3 1 28. Volume (m ) waste 4.268 4.186 4.016 3.255 4.879 20.604

b. Burial Volume 4.88 4.88 4.88 4.88 5.83 25.35 1 l ll '

3. Radioactivity ) l Content (Cl) l

a. f'.r51 4.073E-2 2.334E-2 5.787E-2 8.11 E-4 1.432 E-2 1.371 E- 1 l

~

b Mn54 2.546E-3 2.115E-3 4.123E-3 7.133E-4 2.627 E-3 1.212 E-2 l c.Co60 3.392E-3 5.446E-3 6.414E-3 1.501 E-3 2.477 E-3 1.923 E-2 l d.CoS8 1.480E-2 1.413E-2 2.471 E-2 3.22 7 E-3 1.162E-2 6.849 E- 2 l

e. C14 1.545 E-3 1.801 E-3 1.856E-3 9.738E-4 1.510 E-3 7.686E-3 l-

f. Ni63 7.124 E-5 1.144 E-4 1.347E-4 3.152 E-5 5.199E-5 4.039E-4 l g.H3 8.128E-5 7.972E-5 7.648E-5 5.635E-5 9.290E-5 3.867E-4 l h.Fe59 1.245E-3 4.788E-4 1.565E ,3 1.262E-3 4.551 E-3 l{

i.CoS7 j 1.556E-3 1.439E-3 2.307E-3 1.206E-3 6.508E-3 J.Zn65 _ 8.356E-5 l

l M131 7.069E-5 1.287E-5 ,

I.Sb124 ~

l1 l

) m. Ce141 l n.Ba140 3.094E-4 3.094E-4 l o.Cs137 3.873E-4 3.873E-4 ll

p. Sr90 2.029E-5 2.029E-5 ll q.Pu241 5.817E-5 5.817 E-5 ~l

r. l

4. Total Radio- 1 activity (Cl) 6.635E-2 4.894E-2 9.906E-2 7.722 E-3 3.518E-2 -2.573E- 1

5. Type of Container STC 'STC STC STC STC l l

6. Source of Waste Cndnsate Cndnsate lCndnsate Bead Cndnsate l 1 I i, l

! 7. Processing Q l l Employed Dewater Dewater Dewater lDewater ,Dewater (

f i

! I f 8. Solidification l l Agent lNone None None lNone lNone l 1 L i l I I Approved by _/ /M Date [-M-[)

Page 21 SOLID WASTE

SUMMARY

WORKSHEET Sheet 4 of 5 Solid' Waste Category Spent Resin, Filter Sludges, Evap Bottoms, etc.

Renorting Period: 1, January 1987 through 30, June 1987 l

1 Parameter Shipment Number Total 1 2 3 4 5

1. Date (Mo/Da/Yr) 03/26/87 04/02/87 04/09/07 04/15/87 05/14/87 3 l L !

2a. Volume (m ) waste l 4.930 'I 4.562 5.077 8.374 8.518 31.46 j b.8urial Volume 5.83 5.83 5.83 9.31 9.31. 36.11 j l

3. Radioactivity Contant (Ci)

a. Cr51 1.262 E-2 1.942 2.407 E-2 3.525E-1 9.513E-2 2.426E+ 0

b. Mn54 1.452 E-3 3.292E-1 5.068E-3 1.256E-1 6.97 E-2 l5.310E- 1 c.Co60 1.612 E-3 1.825E-1 3.628E-3 9.922E-2 5.075E-2 3.377E-1 l.

d.CoS8 6.142 E-3 1.471 2.112 E-2 6.301 E-1 2.763E-1 2.405 e.C14 1.308E-3 3.600E-3 1.712E-3 7.805E-3 6.241 E-3 2.067E-2 i f. Ni63 3.386E-5 3.830E-3 7.616 E-5 2.083E-3 1.066E-3 7.089E-3 j.

g,H3 9.387 E-5 8.687E-5 9.43CE-5 1.001 E-3 1.018E-3 2.294E-3 h.Fe59 1.397 E-3 1.642 E- 1 2.288E-3 5.455E-2 1.764E-2 2.401 E- 1 1.CoS7 1.774E-3 1.774E-3 1.Zn65 7.197 E-4 1.376E-1 2.150E-3 4.113E-2 1.783E-2 1.994E- 1 k.1131 1.692 E-4 7.697E-4 9.389E-4 1.Sb124 5.245E-3 3.847E-4 5.630E-3

m. Ce141 2.027E-3 2.027 E-3 n.Ba140 6.344 E-4 4.574E-4 1.072E-3 o.Cs137

p. Sr90 ,

q.Pu241 r.La140 2.244E-6 2.244E-6 .!

4. Total Radio-activity (Cl) 2.6185-2 4.244E+ 0 6.021 E-2 1.314E+ 0 5.361E-1 0.1-80E + 0

5. Type of j Container .STC STC STC STC STC i l ,

6. Source of Waste 'Cndnsate Cndnsate jCodnsate Cndnsate Cndnsate l I

& RWCU l& Bead

7. ProcessinD Dewater Dewater 'Dewater lDewater Dewater Employed

8. Solidification l Agent None None 'None None None i Approved by /#7 Date /YY7 '

. Page 22 SOLID WASTE

SUMMARY

WORKSHEET Sheet 5 of 5

~ Solid Westo Category Spent Resin, Filter Sludges, Evap Bottoms, etc.

Reporting Period: 1, January 1987 through 30, June 1987 Parameter j Shipment Number Total j 1 2 3 4 5 {

1. Date (Mo/Da/Yr) 05/28/87 06/23/87 06/29/87 3 1 - I i 2aNolume(m ) waste - 7.892 ' 8.575 7.924 27.93 :

b. Burial Volume 9.31 9.31 9.31 :

4

3. Radioactivity 1 Content (Cl) 1

a. Cr51 3.297E-2 4.530E-2 5.006E-2 1.283E-1 l

b. Mn54 2.123E-2 4.595E-2 8.485 E-2 1.520E- 1 j c.Co60 2.087E-2 3.529E-2 6.099E-2 1.172 E- 1 l d.CoS8 7.725E-2 1.641 E- 1 2.968E- 1 5.382E-1 e.C14 4.292 E-3 5.519E-3 6.350E-3 1.616E-2 j f. Ni63 4.382 E-4 7.410E-4 1.281 E-3 2.460E-3

g. H3 9.312E-4 1.025E-3 9.468E-4 2.903E-3 h.Fe59 3.557E-3 6.628E-3 7.624E-3 1.781 E-2

' i. CoS7 J.Zn65 -6.136E-3 3.603E-2 1.577E-2 5.794E-2 k.1131 8.977 E-4 8.977 E-4 l 1. Sb124

m. Ce141 -

n.Ba140 o.Cs137 9.288E-3 2.494 E-3 4.758E-4 1.226E-2

p. Sr90 4.099E-4 9.001E-5 4.999E-4 q.Pu241 r.La140 _

1.151E-4 1.151 E-4

4. Total Radio-activity (Cl) l1.774E-1 3.432 E-1 5.262E-1 1.047E+0 l5.Typeof l Container STC STC STC

6. Source of Waste l Powdered '

Powdered Powdered

, w/B Resa Resin Resin I , !

7. Processing l l Employed Dewater Dewater Dewater

8. Solidification Agent None .None lNone I

Approved by .

! 4/ Date /~M7-87

1 l

Pago 23 PROCESS CONTROL PROGRAM CHANGE REQUEST i DTC: TMOPER

File: 1715 l Change Requested by: ' b . /. (4/6664 Date: $f30 '7 Change requested to PCP, Rev. [>

Dehrtment/Section: N,uA _ /_dI' MM l Change (Attach markups of the PCP): [ee AMsc4e/ mar du/ Joce3 /,/ / , l

Na )

t Am om% / be a e 3, no me t), "

a,a'e" _ca,j' m ,, t , , j' AWA,,,+ 1 - ]

m ae / a a 2 10.' f->daie,-

+s.4,f7

I Reason for Change / Justification (include sufficiently detailed information to totally support the rationale for the change. Attech additional sheets tf necessary): (4,,a rs an,,1,/ -

hv"10* sre ejerla:sfrahre an /s u MA rtf mea do f t u s + /'de llaa. ,

L'"> -- ( A - a nr e an r ked Le *le

Ma, I wM A e r A n a*e r h s'L *.

AssL h-e % lftem4faa fe e .n o Fr<=i '2 - Rems ont so kd swfuesh r 1 s Mem . 74 !. e ha -,e asvore==omlad haWee w n to (Arg ' (oraord/on n14A o stas:Ju d4fr 1 stfoa. 4e Fre nr : 2 . 'YA e n + + ,a l o / (,de s tr (A o n \

rernrr Min, lo ?Hr~ era's:Jo s ,i n c + flrd:a n ./b r . h is eda n a r. -

i r

Review Performed by: */ Date: 4 p'7 ;

j

' General Supervisor, Redweste

(

The Superintendent. Operations has determined, as evidenced by his signature below, that this change does not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.

Approved by: e Date: 6[2f97 Superintendent, Operations l Recommended by: > 21 w Date: / 77 OSRO Chairman Approved by:- r Date: / '

O Plant Manager POM 12.000.108 (SR) Attachment 2.033187 END 1

(.

l l

'i Page 21i"-~* .!

WasteChem WesteChem Corporation .

One Ke6se Woy .

Paramos. NJ 07652 l s01/See 2900 Totes: 8863831 May 29, 1987 i t l Mr. L.E. Schuerman The Detroit Edison Campany Fermi 2 6400 North Dizik Eighway Newport, Michigan 48166 RE: DECO Letter No. RE-RS-37-0154, dated May 12, 1987

Subject:

Recommended Change to PCP Asphalt Specification

Dear Mr. Schuerman:

This letter is intended to respond to the concern *axpressed in your letter of May 12, 1987 (Reference) regarding revision of the PCP to accomodate minor changes in asphalt properties, e.g. increase in softening point, due to storage at elevated temperature.

We would like to confirm that an increase in softening point beyond 2050F (96'C) does technically violate the limit specified indirectly in the PCP (via ASTM D-312, Type III requirements); however, this phenomenon will have an l insignificant effect upon waste form performance and the nonconformance can be rectified by a simple revision to the PCP.

Asphalts are cosmonly purchased to specifications established by either the American Society for Testing and Materials (ASTM) or the American Association of State Highway and Transportatism Officials (AASNTO). When WasteChem Corporation originally wrote the PCP draft, we wanted to make sure that VRS System users could procure the appropriate grade of asphalt to a recognized national standard. Of the various families of asphalts used commercially, Wastechen found that oxidised asphalts conforming to ASTM D-312, Type III requirements most closely exhibited the combination of physical properties deemed desirable for a vaste solidification / stabilization medium. We therefore specified that ASTM D-312, Type III asphalts be used in the system.

What we failed to do is provide guidance in the PCP to accomodate changes in physical properties of asphalt due to storage at elevated temperatures.. It is well recognized that asphalts will harden when stored for prolonged periods at elevated temperature. Although various properties can be affected, e.g.

softening point and viscosity, and can exceed limits established by the specification, the magnitude of physical property changes which can take place are not great enough to jeopardize the stability of the product.

l Page 25 ,,,

j i

SAVasteChem l

1 Mr. L.E. Schuerman The Detroit Edison Company May 29, 1987 .

Page 2 l

. l For instance, the viscosity of asphalt at its storage temperature can experience a two or three fold increase. This is equivalent to that which would be experledced by reducing the storage temperature by less than 500F.

The magnitude of this change is not sufficiently significant to have any moticible effect on either the process or the product.

To accomodate the change of properties experienced by asphalts stored at elevated temperature for prolonged periods, we recomunend revising the PCP to specify that ASTM D-312, Type III requirements apply only to the purchase specification and to asphalt in its as-delivered state.

We trust that this oversight has not caused undue concern or confusion.

Very truly yours, WasteChem Corporation h

William J. Klein l Assistant to the President, Technology WJK/bg

. cc R.J. Beaudry C.T. Weber S. Gerges, NUS

}

Page 26 , , ,

PCP Manual Revision 6 .

Page1 of1 FERM12 PROCESS CONTROL. PROGRAM ,

The Fermi 2 Process Cor.tre,I Program (PCP) covers the following distinct processes for solidsfacetion or dewatering of 18dioactive. waste. These processes are described below:

1. For the solidification of rsciioactiva wiss.e using the Fermi 2 parmanent solid radweste ,

I system. Fermi 2 will follow thie PCP. desscrif,rd in Attachment 1.

\,

2. For the dowatering of radioactive pow'dered resins in steel cetniners using the Hittman Nucisar incorporated tempo <rry radwr,ste processing systerr' fsrmi 2 will follow th' sPCP described in the t'llumen Nutfcer Document STD-PCP-03-001 Revision

3. ,

3. ' For the dowatering of radioactive bead resins in steel containers using the Hittman Nuclest incorporated ta'nporary redweste processing system, Fermi 2 will follow the PCP described in the Mkiman Nucisar document STD-P-04-002 Revision 5.

For the dewatering of radioactive powdered resins in Radiok D High Integrity 4.

Containers (HIC's) using the Mittman Nuclear incorporated temporary radweste processing system, Fermi 2 will follow the PCP described in the Hittman Nuc'sar Document STD-PCP-03-002 Revision 1.

5. For the dewatering of radioactive powdered and bead resins in steel containers and HIC's using the Chem-Nuclear incorporated tempora'y RDS-1000 dewatering system, Fermi 2 will fol'ow the PCP describet' in Attachme.t2.

Thc General Supervisor - Madwaste is respo'nsible for the implementation of the Fermi 2 PCP. Nuclear Quality Assurance will audit ttu soflolfication and dewatering of radioactive

( waste includinD r3 cord keeping activit!*s in accctdance with QAPR 24.

Recommended: d' M/ ,2/ 74/-fZ Noted: IksC Approved: _

f g &J OSRO Ctairman Date NOTE: The Hittraen Nuclear documents referenced above contain proprietary information, are not published as Fermi 2 documents, and are available j from the General Supervisor. Madweste. 1 Licensing Commitment Review: The followde~ommitments are listed against this procedure: 6546. O Action ha been taken to fa.swe these I;o:nmitments have not been negated. l sf $$1 _ ,

Sb $~/h'*7 Date Signature cf Originator '

APMS - INFORMATION SYSTEMS DSN *R t tweeum Rev 6 Date L('6 -8"I OTC.7M M EE _

Pts PIS File 1715 Recipient 57 34 =3_

i CONTROLLED

_ , _ _ , [_

}

PCP Manual

- Revision 6 Attachment 1, Page 3 of 6 e

4 .

In accorda%ce with the foregomg timitotitms,the foHowing variables influence the propert' and consistency si the final solid product )

l A. Asphalt type, l

~

S. Weste chemiset species W encogeested tuto1hs asphalt metrix; C. Ratio of - - E-2 : ; tit; and

. I D. Process tempersters l

A detailed diseaselon of1he oNect sad timetations placed an each of the foregoing items follows:

l A. Asphett Type g g.g[ .g f WPC recommends.ase of en oxidised roleum-based esphalt, conforming to 4 Type 111 vequhements his grade of asphaft has a low, residust, ASTM-D-31 volatile con nt, and a high moleculer weight. At focm temperature, and at all normal emblent conditions, shia maatarial is a freestanding monolith.

B. Waste Chemiset apostos The waste chemical makeup might be expected to influence the ability of the .

extruder / evaporator to form a satisfactory product. in their Topical Report, WPC ,,

( describes resufts tpfiseting performed to demonstrate the ability of tt e

'. extruder /eveperster systemte produce en adeguate product. The simulated weste

' systems tested are conservatively representative of the Formt wastes expected to be processed by the autruder/ evaporator (tistic acid and sodium sulfate should not be present in formigeeste).

In support of theformt 2 instatistion,WPC performed additional testing to confirm the adequacy of operation with Wry feeds such as those resulting from processing by the centrifuge. Theaetssales confirm the adequacy of prodcct produced using the dry feed mode.

WPC has placed a limit of 1 percent oil in the waste feed streams. An extensive '

review of the enthe Fermiliguld and solid redweste processing systems felled to -

identify a tradible mechanism for concentration of oil in solid waste processing feed streams,such that the 1 percent limit would tre approached. Nevertheless, a process limit of 1 percent ollin the weste-food stroom to the extruder will be maintained, implementing proceduves arNI detaR the methods used to ensure this limit is met.

k

Page 28 pCP Manual .

Revision 6 .

Attachment 1, Pope 4 of 6 .

(

C. Ratio of Weste to Asphalt The Emits for the ratio of weste 4o-esphalt to ensure en acceptable product are G prl .Lmed in Table 1A. If the ratio of weste-to-asphalt were to exceed the limits, the end product viscosity will increase and the end product may exhibit a grainy texture.

i This apuid result in " pyramiding" of the product in the container with a loss of filling '

officleppy. With lower than specified ratios, product properties approach those of pure asphalt, resulting in loss of volume reduction. In any event, the product will be s Seestending monolith upon cooling. Constant viewing of the product texture during )

eentainer Ruing is evaliable to the operator through a Closed Circuit Television Camers.

Desired weste-to-esphett retlos in the product are maintained automatically by a e coordinated proportioning feed system to the extruder /eveporator, in all feed modes, the solids content of the wsue stream is measured prior to initiation of feed flow.

The measured solids content is used to determine the proper waste and asphalt feed j control settings by consulting a graph in the operating procedure. A separate graph will be provided for each waste species and each food mode.

In the centrifuge feed mode, the flow rete to the centrifuge is controlled automatically using a flow control volve. With a uniform feed, the centrifuge will provide a uniform flow of dried (approximately 40-50 w/o solids). product as feed to the extruder / evaporator.

In both slurry feed modes and in the concentrates feed mode, constant waste flow /

rates are maintained by flow measurement with feed back control to variable speed 5 metering pumps.

D. Process Temperature Prefile j

A proper temperature profile along the length of the extruder is recluired to ensure that free water is not dischstged. The process temperature ranges for each of the l Fermi 2 waste types are given in Table IA.

Low temperature alarms are provided to alert the operator to e low temperature out-of-specif6 cation condition. l Should en out-of-specification condition persist for two (2) minutes, the extruder / evaporator will be automatically tripped to prevent free water from being discharged into the container. Under this condition, residual free water in the extruder /evaporotor cannot be dischstged since the residual heat content pf the machine itself is sufficient to evaporate it.

I i

j Page 29 -

- PCP Manuel 1 Revision 6, !

Attachment 1. Page 5 of 6 l

)

IV. Spent Filters Spent cartridge filters will either be elf-dried, compacted, and disposed of as Dry Active ) '

Weste (DAW), placed in drums with an absorbent es required. or placed in drums to be filled with esphalt.

Spent cettridge bundles from the Weste Collector Oil Coalescer or from the Floor Drain Oil Coalescot will be encapsulated in asphalt. Each bundle will be thoroughly drip dried, placed in a* drum, transferred to the tumtsble of the solidification system, and there@on fliled with asphalt / waste mlature from the outruder/eveporstar.

This method of oil filter encapsulation will be proven during the pre-operational test.

V. c Conformance to 10CFR Part $1 i (Land Disposal of Radioactive Weste) <

A. Farm 2 will meet the waste classification requirements of 10CFR61.55 by the following: p1

1. Measuring gamma-omitting radionuclides and using interim correlation factors based ,

on calculational methods described in the Atomic industrial Forum's Determining the Classification of Low-Level Radioactive NuclearWastes Power g, frorip Fasnts.* i&t)gp},l 1 I Carrying out e sempting and analysis program necessary to determine subsequent l 2.

specific correlation factors to be used for the plant.

2 t

3. If the subsequent sampling and analysis program indicates results such that the l correlation factors being used may not give upper-bound limits, then the wastes will be stored until they can be classifies on the basis of correlation factors developed from actual sample analysis.

B. Fermi 2 will meet the waste form requirements of 10CFR61.56 when solidifying weste using the extruder / evaporator by the following: ,

1. Class A wastes which are not otherwise required by the burial sites to meet the requirements of 10CFR61.56(b) shall be termed

Unstable". Unstable waste processed by the Fermi 2 permanent redweste system shall meet the parameter requirements listed in Table 1A.

2. Class 8 and C wastes and those class A wastes which are required by the burial site to aneet the requirement of 10CFR61.56(b) shall be termed

Stable". Prior to the sollt',6 fica, tion of stable wastes with the installed Formt 2 asphalt extruder system, waste-form test data will be submitted to the NRC for opproval. Prior to such approval, stable wastes will either be: a) dowatered and shipped in approved High-integrity Containers, or b) solidified into a stable waste form by a mobile vendor.

~ ~

Page 30 PCP Manuel Revision 6 Attachment 1. Pope 6 of 6 k\

(. \,

TABLE 1A i

PROCESS PARAMETERS '

TO ENSURE THE MINIMUM REQUIREMENTS AS AN

" UNSTABLE" WASTE FORM ARE MET TEMPERATURE PRd[ PILES

Bead Resins owdered Resins (ECODEK% Studges Zone 1 2 3 4 5 Sn 8 Temperature p3 (0 ."

200 980 320 350 300 19G i

Evaporator Concentrates Zone 1 2 3 4 5 60 8 Temperature (O F )"*

" 2DD 280 320 350 350 280 WASTE / ASPHALT RATIO

Eysporator Concentrates S 50/50 T

, Bond Resins / Powdered Mesins (E' CODEX h Saudges 3, 50/50 UMIT ON OIL IN FEED STREAM One percent ASPHALT TYPE Meet ASTM D-312% Type lliidw Pn Jp u4c. ,

b

The values given in this section are tentsttve The pre-operational test program will determine the high and low ranges of these variebtes for acceptable solidification. Finst operating peints and acceptable sanges will then be incorporated in a revision to this PCP.

" This barrel has no heating or tempersauve monitoring capability and thus is approximately at emblent temperature.

"* These temperatures ten tm verted by up to 10% of the setpoint without effecting the quality of the end protiuct.

(

Page 31

~

PCP Manual Revision 6 Attachment 2, Page 1 of 11 l l

I ROS-1000 PROCESS CONTROL. PROGRAM The purpose of the Process Control Program for Chem Nuclear Systems,Inc. (CNSI) RDS-1000 Radioactive Weste Dewatering System is to establish processing conditions assuring safe and >

effective dewatering of various low-level radioactive slurries including resins and filter media

! j produced by PyVR and BWR Nuctee,r Power Electrical Generating Stations.

CNSI has been providing conventional dewetering services since 1975 and has en NRC approved Topical Report for these processes. These processes are currently being used to dowater lon-exchange resin, acthrsted carbon, and verlous types of filter media. The dowatering process is accomplished in CNSI's high integetty and steel process containers / liners (including the 21-300).

CNSI has developed and tested a mechanical system for the rapid dewstering of bead resins and filter media. The Rapid Dewatering System (RDS-1000) employs a high flow vacuum system in conjunction with CNSI media specific waste containers.

Redundant tests were performed on full scale steel and High integrity Containers (HICS). . Testing'I included dewatering of bead resin, activated carbon and other filter media. These materiefs represent the worst case simulated weste forms to dowater commonly found in the nuclear industry. Certification of ths ADS-1000 using the largest containers and most difficutt media certifies the equipment for use with other containers of smaller size and similar design. Resutts of these tests are included as Enclosure (1).

The test results obtained clearly demonstrate that the RDS-1000, when used in conjunction with Chem Nuclear liners (21-300 and smaller) and Chem Nuclear Operating Procedure FO-OP-032, or other CNSI derivatives is capable of rapidly dowatering these materials to meet the limits for free standing water imposed by the disposal sites es well as 10CF 61. pj i

G 4

e 1

1 i

I

' Fage 32 PCP Manual l Revision G .

Attachment 2, Page 10 of 11 l

l l

2.0 TEST MEDIA ,

Seed Rosin TM get resin mancfectured by The bead resin media used in all bead tests was MR-3 Rohm-Heas. The beag several years old, depleted and astursted with crud and fines.

end fines, with some carbon, as considered the worst casu bead This mixture of MR-3 ,

test media. !

Fitter Medi6 1

\f The filter r eedia use pil precost tests, except test Number 7, was Ecodex. Ecodex is manufactured by Or er-Water. The some batch of Ecodex was used in tests 4,5, and 6. O lI!

Ecodex is a mixed powstered resin / fibre percoat meterial having less than 2% whole resin -

beads. 4 The test media batch of Ecodex is several years old and was obtained from Zimmer utility . ;

in a crud-saturated and depleted condition, The media contains trace amounts of c:1. a l

The media is considered the ' worst case.

Filter Media - Test Number 7 ,

j Test Number 7 was performed to evaluate operation of the RDS unit with a larger liner.

The precost media used during test Number 7 consisted of the Ecodex used in tests 4,5, and 6, plus en additionet mixture of Ecodex, bead resin and diatomacoon.s earth. This was necessary to completely fill the larger liner.

The additionalvnisture tensisted of approximately 80 volume percent used Ecodex. The remaining volume is 15 percent depleted M*-3 gad resin and four percent diatomaceous earth. The rernsining 1 percent was Solka-floc . The exact composition of Ecodex is not publishegormation, but it is known to consist of organic fibrous matarlais similar '

to Solka-Floc .

The presence of the bead resin in the mixture is known to reduce the water retention capacity (WRC) of the media. The presence of diatomaceous certh and Solka-Floc is ,

known to increase the WRC of the media. The WRC of the additional mixture is approximately caust to that of Ecodex, and has very little effee; on uverall performance.

Mixtures such as this are encountered in the field.

Therefore, at represents en equivalent worst case media. The diatomaceous earth is manufactured by the Menville Corporation. Solka-Floc is manufactured by Orefco, Inc. <

Cerben One test was conducted with carbon media. The carbon was manufactured by CECA. inc.-

The media was type OAC40W.

The OAC40W type estbon is one of the most commonly used carbon types in the nuclear industry. Successful tasting of the OAC40W slie qualifies the RDS System to be used for fewatering carbons of larger granular slees. However, carbons of a smaller granufer slae shall be evalusted on e case by case basis until sufficient dets is estabilshed to verify the dowatering efficiency.

t e

f

I' age 33 i I

PROCESS CONTROL PROGRAM CHANGE REQUEST l DTC: TMOPCR

, File: 1715 j Change Requested by: C,84/64- /7 4/EME4 Date: 6/a/97 ;

Change requested to PCP, Rev. 7 _

Departments $ection: JVoe /ec & bclvef% -$$daWSM Change (Attach markups of the TCP): c' C 41 h a c / r / g s r 4 g l

l Reason for Change / Justification (include sufficiently detailed Information to totally suppert the rationale for the change. Attach addid9nal sheets if ngcessary): 7~- po a l, /p_;

St.),'rll f'e a% e C $' / lea. </t h e e...',$ m d re<lo er a A n ,* a a or le e' .

ec e h , o + G , m l '1 4Ao fr / :e "h i '- i. sr .. d. ./', ed /. ,'n e /a ds e, f ewess !

4. '),.s c 'e/.[ke 4 cat a<;ee 4+e 1./l A .a Ner ein . 'T**s a s e > r .i ' h o-ss/py l

,e ;/: ez. / : , i2 Jos aa//,eJ.e eAA.,JiJ ' /

Qm,, t e., l Review Performed by:

[ .t General Su>

M '_

p ervisor, Racwaste _

Dste: [/ f7 /

h The Super!ntendent. Operations hac determined. as evidenced by his s!gnature balow, that this change does r)ct reduce the overall confomstnce of the solidified waste product to existing criteria for solid wastes. ,

. , '; h?l

Approved by: _M' . ' ' ' (, - Date: D D Superintendent, Operations

/

Reconimended by: Data:

OSRO Chairman

I Approv,ed by". Date:

Plant Manager l

l POM 12.000.108 (SN, Attachment 2, c'33187 j END ,

I l

I

Pake 34 -

^'

PCP Man'Ja!

-? Revision 7.

Page 1 of 1 ;

Q. '

( $ FRRMI 2 PROCESS CONTROL. PROGRAM b

' The Formi 2 Process Control Program (PCP) covers the following distinct processes for l 4 solidificailon or dowatering of radios::tive waste. These processes are described below: 1 N

1. For the solidification of radioactive waste using the Fermi 2 Permanent Solid Radweste System, Fermi 2 will follow the MP described in Attachment 1.

2. For the dewatering of radioactive powdered rasins In' steel containers asing the Hittman 1 y ' Nuclear incorporated Temporary Asdweste Proccasing System, Fermi 2 will follow the PCP 4 desenbod in the Hittman Nuclear Document STD-PCP-03-001 Revision 3.

3 For the dowatering of radioactive bead resins in steel containers using the Hittman Nuclear

[ ( incorporated Temporary Radweste Processing fystem, Fermi 2 will follow the PCP described g in the Hittman Nuclear Document STD-P-04-002 Revialon 5.

g 4. Fw the dowatering of radioactive powdered resins in RadiokTM High integrity Containers I Yyg]&

4*

(HIC's) using the Hittman Nuclear ! incorporated Temporary Redwaate Processing System.

Fermi 2 will follow the PCP descrPaed in the Hittman Nuclear Documsnt STD-PCP-03-002

[fw Revision 1.

k %

5. For the dowatering of radioactive powdered and bead resins in steel containers and HIC's using the Chem-Nuclear incorporated Temporary RDS-1000 Dewatering System, Fermi 2 will g y,,

g f $ follow k e the k N PCP m arf,n, described in Attachment 2.

(,f% ;5 g **, The General Supervisor - Redweste is responsible for the implementation of the Fermi 2 PCP.

l g. g Nuclear Quality Assurance will audit the solidification and dowatering of radioactive waste

! .;. % D including record keeping tivities in accordance twith OAPR 24.

Recommended: bd Wg - 6 eg SN [, gn 71 )gaA 84pagyisor - Racwaste Ostil.

N.6 MM Noted: /f/ ML 6/2 /K7 Approved: / __

t, OSRO Chairman 'Dete j l N, .$ t NOTE: The Hittman Nuclear documents referenced above contain proprietary Information, are I % not Fublished as Fermi 2 docvfrients, and are available from the General Supervisor, Radweste.

s as g b Uconsing Commitment Review: The following committr.ents are listed against this procedure: .l kC a

9 6546,6547 -!

.q O <0 '1 gQ ~-j Action has Dean taken to ensure these commitments have not been negated. 4 kY d la *1"W Si$isture of Originator

//% 30 DateF '

/9f]

y s M, = f i

ARMS - ;NFORMATION 5,YSTEMS OTC TMOPER OSN ILf hud Rev 7 _Date L -t W - T "l PIS PIS File 17t5 Recipientf 3 T3

(

CONTROLLED l

-i

7

/

Page.35 l

.N HITTMAN 1256 N. CHURCH STRE

- INUCOLEAR MOORESTOWN, NJ 08057

\ M' (609) 722-5700 l

l 1

l Refer 2b:

HN-4184 A ma 23, 1987 Mr. Craig Maber I ansesta swervisor Det:roit Ediscm My Farmi 2 Power Plant 6400 North Dixie Eighway Newport, Mitt 11gan 48166 Sutdect: Crupliance of F475-POO7, Rev. 2 with burial site an$ federal guidelines

Dear Mr. Weber:

Westinghouse Hittman's a n.h F475-P-C37, Revision 2 as issued on 6/17/87 is applicable at the Fermi Power Plant for solidificaticm of liners ocidaining powdered resin classified as either Class A Unstable er stable, class B or class C wasta and granular carbon classified as Class A IInstable vasta undar the requi. J.a of 10CFR61.55, Nasta Classification.. Class A Stable wastes must meet the same stability requirements of Class B and C wastas under the critaria of 10CFR61.56, Wasta Charactaristias, as reglized by the States of Scuth Carolina and Washington.

Should you have any questions ce ocncerns please call me at 312-232-6133.

e

LWy V :

bb ' c= And Dou.1as sai ;

sr. Techni .

antative ;

f

-......... T.*~~~~'~'~~~P-~~

lit i t a, t**.!1i.1

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i Page 36, T.

m . ..

Ume

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Atta hment i, see. 1 of a

!!M86 WFBITE MSR Sel555M385 MBu&L adBGE EqEST Shoese tageseted by bd/6dd Date s _ !/f!/7 togersment/sectient b leas &'res d drae n

=sioene Sentieste): T4ht E.0-1 M6 Mdf5 fo. sums 4.5 b R l each etesse presided (atteen with asarkope approwel se the andestas,este ten): Mae 'KNST shell Afbe *dsembered bknre od andMTesMb

-'faLr ke*/ Ada of an 9hs a;s , t Seases for mense/Jostifisettes (teclade soffistently detailed infermot' u to tetelly espport the retteeste for the ches.e and appropriate emelysee w evetentiene justifyles the chasse. Attach addittenet sheets if esseessry): ~

S E t' A rrnedra Joks-r O __

i rahasset antes perfer.ed 6 7: ,Mdr o note:h/**/4-

~

l

. The sedches begiseer bee deternised, se evideseed by his eigasters below, ;

that this sheese does set reesit is a redesties f the esserees er !

variability of dose setestet e er se ist ermi tiene.

moter [/J O

~

Approved by: V CJ1C -- er

~

asse Besteedr ,y ~/ /

ame== ded bi - - .- _ _ p te: E 4t- F7 .

asao chetsmen j ApprerFJ hy8_ *-- Dates I I!I7 no. or the Fleet Sleseger she11 aise approve seek page of the e,tpened neders of ARus.sepoeMATION S'/ STEMS grpg YMO$KL 99N000 M NLOWiML Y caan arv o _ m._

JtfN 10 987

,i. -

_ ,, .#3ka-ancomu APPeCNAl. FEQ1k YEil _ _ __ 90 0

' Page 37 u.

i List of Revisions to offsite Dose Calculation Mswal )

Section 3.0-1

- Stations - FS, Ell, 9-12, F24f F35 anS W4 chages are repaired due to incorrect statlan loostian information in previens (Int revision an8 to eso better location descriptions.

- Omntrol St.ations - 11,14,15, S-21, ano >22 removed typheno*

j and footnote at botten of applicable pages and than adood word >

loontrol) after description for these locations for better table consistency. ,

- Stations -Ie7 and 19 asola and frequency were aSono, previous GOt revision informative was incomplete. .

- Stations - 32, 33, 34 and 3))were a$6ed as foco product locations (garden greater than 500 ft . ProvW somplire andia, frequency, annual tracking and does evaluations.

- Azimuths were a$6eS to all locations for better table information. Previous Ga revision only listed azimths for dirtet radiation locaticms.

- 52 Table 3.0-1 format has been revised by sept. rating aanpling

( media, locations ano frequency. Tuis provides for ease of locating the various types of andia, their location and collection frequency of the sample for analysis.

- The 1ccations that t.sve ' coon inbntified as the closest residences l in the 1stest land use census (1996) are being aS6ed as a yearly trachire of those individuals living cicaest to the site boundary and to provide a basis ror year:1y dose evaluations.

- Maps - Figures 1, 2 an5 3 were revised to incorporate new food product incr$1ms and legend symbols.

4

m

)

Page 38 SECTION 3.0 RADIOLOGICAL 59NWLONMENTAL MONITORING PROGWAM 3.1 SAMPLING LOCATIONS Sempileg locations, es reqdred in Technical SpecNicetion 3/4.12.1, are descrit>ed i Toole 3.0-1 and shown on me maps in Figures 3D-1,3.0-2,3.0-3.

900TE: #F9e the purpose of implementing Technical Specification 3.12.2, sempling locations will be modified so required to renect the findings of the Land Use Census.

p l

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s APPROVAL:_ t U ,

ODCM, Fermi-2 3.0-1 DATE: gn/r7 !

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Reg. Guide 1.21 B. Ralph Sylvia 6 Group Vice Presid snt DOIr0} ,,,,,, n m ,,,y August 28, 1987 Newpod %chman 48166 (313,Shfr4150 IJ R C- 8 7 - 014 2 U. S. Nuclear Regulatory Commiccion Attention: Document Control Desk Washington, D. C. 20555

Reference:

(1) Fermi 2 NRC Docket No. 50-341 (2) Appendix A, Facility Operating License No. UPF-43 Technical Specification 6.9.1.8 l i

l

Subject:

Semi-Annual Radiological Effluent Release Report !

The Semi-Annual Effluent Release Report for Fermi 2 is attached. This report is being tranctitted in compliance with Reference 2 and Rebulatory Guide 1.21, Revision 1. The attached report coverc the period from January 1 through June 30, 1987. l During this reporting period there were no instancoc of unmonitored or unplanned radioactive releaces from the site.

Pleace direct any questionc or requects for additional information to !! r . Girija Shukla at (313) 586-1617.

Sincerely i

l l

Attachment cc: A. B. Davis E. G. Greenman U. G. Rogerc J. J. Stefano S $Y

,ip o- - - - - -- -

NRC-87-0142, Semiannual Radiological Effluent Release Rept,Jan-June 1987

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Dear Mr. Weber:

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NRC-87-0142, Semiannual Radiological Effluent Release Rept,Jan-June 1987

Text

SUMMARY

SUMMARY

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Dear Mr. Schuerman:

Dear Mr. Weber:

Reference:

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