ML20209D464

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Semiannual Radioactive Effluent Release Rept for Jan-June 1986
ML20209D464
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 06/30/1986
From: Sylvia B
DETROIT EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
VP-86-0125, VP-86-125, NUDOCS 8609090321
Download: ML20209D464 (48)
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Text

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DE'mOIT EDISON COMPANY FEBMI - 2 NUCLEAR POWER PLANT OPERATDG LICENSE NO. NPF - 43 SEMI-ANNUAL RADIOACTIVE EFhLUENT REMASE REPORT POR 'IEE PERIG) OF

, JANUARY 1,1986 'mRGE JUNE 30, 1986 8609090321 860630 M PDR ADOCK 05000341 R PDR

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Table of Contents Topic PM List of Tables 1 1

Introduction 2 l A. Supplemental Information 3

1. Regulatory Limits 3
2. Maximum Permissible Concentrations 4
3. Average Energy 5
4. Measurements and Approximations of Total Radioactivity 5
5. Batch Releases 8
6. Abnormal Releases 8 B. Gaseous Effluents 9
1. Stamation of All Releases 9
2. Continuous Releases 9
3. Batch Releases 9 C. Liquid Effluents 9
1. Stamation of All Releases 9
2. Liquid Releases Sunmary by Mode 9 4

D. Solid Waste 9 E. Radiation Doses to the Public 9 F. Meteorological Data 10 G. Notification of Changes 10

1. Onanges to the Process Control Progran 10
2. Changes to the Offsite Dose Calculation Manual 10 i l l

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, Page 1 List of Tables

}EJMBER TI'1LE PAGE A4.1 Radioactive Gaseous Waste Sapling and Analysis Progran A4.2 Radioactive Liquid Waste Sapling and Analysis Progran 11 AS.1 14 Batch Release Stenary Table 17

- Bl.1 Gaseous Effluents - Stannation of All Releases 18 B2,1 Gaseous Effluents - Continuous Releases 19 Cl.1 Liquid Effluents - Stamation of All Releases 23 C2.1 Liquid Effluents - Batch Releases 24 DI.1 Solid Waste and Irradiated Fuel Shipnents 28 Gl.1 Sununary of Changes to the Process Control Program (PCP) 30 G2.1 Stenary of Changes to the Offsite Dose CaletCation Manual 34 (CE m )

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. Page 2 Introduction i

Wis Seni-Annual Radiactive Effluent Release Report, hereinafter referred to as this REPORT, for the period of January 1 through June 30, 1986, is subnitted in acoordance with Section 6.9.1.8 of Appendix A to the Fermi-2 Plant, License No. WF-43. Mis appendix will be l referred to in the REKRT as the Fermi-2 Technical Specification  !

All airborne discharges at Fermi-2 are ground level releases. All liquid and ~ airborne discharges to the environment are analyzed in accordance with Fermi-2 Technical Specifications. All effluent  ;

releases of radioactive material were within the required limits as '

specified in the Technical Specifications.

1 4

. Page 3 A. Supplemental Information

) A.1 Regulatory Limits l

a. Liquid Effluents
1) Concentration (Technical Specification 3.11.1.1)

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'the concentration of radioactive material released in liquid effluents to UIRESTRICTED AREAS shall be limited to the concentrations specified in 10CFR20, Appendix B, Table II, Coltam 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 microcuries/ml total activity.

a

2) Dose (Technical Specification 3.11.1.2) h dose or dose cannitment to a IG!NBER CF 'IBE PUBLIC fr e radioactive materials in liquid effluents released, fra each reactor unit, to UtEESTRICTI!D AREAS shall be limited: During any calender quarter to less than or equal to 1.5 mrens to the total body and to less than or equal to 5 mreas to any organ; and during any calender year to less than or equal to l 3 mrens to the total body and to less or equal to 10 '

areas to any organ. )

b. Gaseous Effluents
1) Unrestricted Aten Boundary Dose Rate (Technical Specificatior. 3.11.2.1) h dose rate, due to radioactive materials releases a' in gaseous effluent frcra the site to areas at and .

beyond the SITE BOUtmRY shall be limited to the l following:

a) For noble gases: Less than or equal to 500 mrems/  ;

year to the total body and less than or equal to i 3000 mrens/ year to the skin, and; b) For iodine-131, iodine-133, trititan, and for all I radionuclides in particulate form, with half-lives greater than 8 days: Less than or equal to 1500

! mrens/ year to any organ.

4

. Page 4

2) Unrestricted Area Air Dose (Technical Specification ,3.11.2.2)

'Ihe air dose due to noble gases released in gaseous effluents, fran each reactor unit, to areas at and

, beyond the SITE BOUmMar shall be limited to the follwing:

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a) During any calender quarter: Less than or equal to 5 mrads for gama radiation and less than or equal to 10 mrads for beta radiation.

b) During any calender year: Less than or equal to 10 mrads for gama radiation and less than or equal to 20 mrads for beta radiation.

3) Unrestricted Area Dose to Individual (Technical Specification 3.11.2.3)

'Ihe dose to a MEMBER OF 'IBE PUBLIC fra iodine-131, iodine-133, trititan, and all radionuclides in partic-ulate form with half-lives greater than eight days, in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNRIE shall be limited to the following:

a) During any calender quarter: Less than or equal to 7.5 mrems to any organ.

b) During any calender quarter: Less than or equal to 15 mrems to any organ.

c. Calcu)ations Equations and constants used to verify coupliance with above criteria are h m ted in the Fermi-2 Offsite Dose Calculation Manual (CDCM), previously sub-mitted on October 11, 1984.

A.2 Maximum Permissible Concentrations

a. Liquids 1

'Ihe Maximian Permissible Concentration (MPC) in liquids l are those in 10CFR20, Appendix B, Table II, Coltan 2,

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Page 5 I

with the lower of the soluble and insoluble MPC being used in all cases. For dissolved and entrained noble gases, and MPC of 2.0E-4 microcuries/ml is applied.

b. Gases Fermi-2 Technical Specifications for gaseous

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effluents do not contain a MPC requirements. Therefore, concentration requirenents are not applicable.

A.3 Average Energy Average Erergy of effluent radionuclid!O mixtures does not apply to Fermi-2 Technical Specifications or CDCM.

A.4 Measurenents and Approximations of Total Radioactivity We section stamarizes the methods used to quantify the total radioactivity.in gaseous and liquid effluents.

Tables A4.1 and A4.2 give the sanpling and analysis fre-quencies of liquid and gaseous effluents.

a. Gaseous Effluents Table A4.1 (Table 4.11.2.1.2-1 of the Fermi-2 Technical Specifications) stmunarizes the gaseous waste effluent sanpling and analysis progran. S e four types of total radioactivity listed in Table Bl.1 of this REPORP are discussed below. In accordance with the QXM, gaseous effluent stack flow rates are always at maximum designed values. % erefore the estimates of radioactivity are high, and error estimates are large in a conservative manner.
1) Fission and Activation Gases Fission and activation gases are quantified by gansna l spectroscopy analysis of appropriate sanples using  !

germanitan detectors and multichannel analymrs. Se l radionuclides measured and included in the dose cal- l i culations include the following if detected:

Kr-85m Kr-88 Xe-135m L Kr-85 Xe-133n Xe-135 Kr Xe-133 Xe-138 f

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. Page 6^

he reported total of fission and activation gases

i is the maxinun value of the sum of the releases of the abwe gases, in all continuous releases.

Considering the uncertainties in radiation counting and in volume, flow rate, and pressure measurements, total fission and activation gases estimates are expected to be in error by less than 7.4% low and 3' 50.3% high.

2) Radioiodines and Particulates-Radioiodines and particulates are quantified by the gama spectroscopy analysis of charcoal' cartridges and particulate filters, using germanium detectors and multichannel analyzers. For each effluent path-way the sampling flow rate and the length of supling period and maxinun ficw rate of the discharge pathway are known. me radionuclides measured and included in the dose calculations include the following if detected.

Mn-54 Zn-65 Cs-134 Other nuclides Fe-59 Mo-99 Cs-137 with greater Co-58 I-131 Ce-141~ than 8 day c Co-60 . I-133 Ce-144 half lives he filters are cmposited for each individual effluent pathway and analyzed for Sr-89/90, and gross alpha radioactivity. When detected, these totals are included and reported as total particulate releases.

Considering the uncertainties in radiation counting and in volme, flow rate, and pressure measureirents, total radioicaine and particulate estimates are expected to be in error try less than 22.9% and 54.8%

high.

3) Tritim '

Tritiurn is analyzed by liquid scintillation counting of grab sa ples. % e sum of the tritium results for all continuous grab sanples is reported as total trititan release.

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Considering the uncertainties in radiation counting

, and in voltane, flw rate, and pressure measurenents, total trititan estimates are expected to be in error

' by less than 12.3% l w and 51.2% high.

b. Liquid Effluents Table A4.2 (Table 4.11.1.1.1-1 of the Fermi-2 Technical Specifications) simmarizes the liquid waste sampling and analysis program. h four types of radio-

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activity analyzed are discussed belw:

1)' Fission and Activation Products j Fission and activation products are quantified by gansna spectroscopy analysis for each grab saiple for the appropriate batch release, using germanitan detectors and multichannel analyzers. h radio-nuclides measured include in the dose calculations are as follows when detected:

. Mn-54 Zn-65 Bayh-140

, Fe-59 Mo-99 Other radionuclides Co-58 Cs-134 as appropriate.

Co-60 Cs-137 Ce-141 Ce-144 Cceposite sanples are analyzed for Fe-55 (chanical separation and liquid scintillation counting), and for Sr-89/90 (chanical separation and proportional

- counting).

h total release given in this REPORT is the stan of all the above radionuclides in all batch releases.

Considering uncertainties in radiation counting, f1w rate and volume measurements, total fission and activation product estimates are expected to be in error by less than 14.3%.

2) Trititan Trititun in batch releases is quantified by liquid scintillation counting of an appropriate conposite sanple. The total trititan activity reported is the trititan activity in all batch releases.

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. Page 8 Considering uncertainties in radiation counting, flw rate, and voltane measurenents, total trititan estimates are expected to be in error by less than 14.3%.

3) Dissolved and Entrained Gases Dissolved and entrained gases are quantified by the ryu-a spectroscopy analysis of monthly grab sanples, using germanitun detectors and multichannel analyzers. '1he radionuclides measured and included in the dose calculations are as follows when detected:

' Ar-41 Kr-90 Xe-135m Kr-85m Xe-131 Xe-135 Kr-88 Xe-133 Xe-137 Kr-89 Xe-133m Xe-138 Considering the uncertainties in radiation counting and in f1w rate and voltane measurements, total dissolved and entrained gases estimates are expected to be in error by less than 15.0%.

l

4) Gross Alpha Gross alpha enitting radionuclides are quantified by counting an aliquot of the arpropriate ccuposite sanple in a gas flw proportional counter. Consid-ering the uncertainties in radiation counting, flw rate and voltane measurements, total gross alpha estimates are expected to be in error by less than 22.5%.

A.5 Batch Release Sununary A sununary of statistical data for liquid batch releases is found in Table A5.1 of this Report. Since Fermi-2 effluents are discharged directly into Lake Erie strean flw is not applicable.

A.6 Abnormal Releases During' the time period cwered by this REPORT there were no occurrences of abnormal or unplanned liquid or gaseous releases.

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Page 9 B. Gaseous Effluents B.1 Sumation of all Releases

%e Gaseous Effluent Stanmation for Fermi-2 is given in Table Bl.l.

The Effluent Technical Specifications for Fermi-2 are based on off site dose. Therefore, no curie limits are applicable.

B.2 Continuous Releases Continuous gaseous releases from Fermi-2 are stanmarized by release height in Tabic B2.1. All gaseous releases are considered to occur at ground level in accordance with CDCM.

B.3 Batch Releases All gaseous releases made fra Fermi-2 are on a continuous bases. Batch releases are not applicable.

C. Liquid Releases C.1 Stamation of all Releases he Liquid Effluent Sumation for Fermi-2 is presented in Table C1.1. W e Effluent Technical Specifications for Fermi-2 are based on off site dose. M erefore, no curie limit is applicable.

C.2 Liquid Release Stamary by Mode Liquid releases by isotope and quarter for Fermi-2 is presented in Table C2.1. No continuous liquid releases are made frcan the Fermi-2 plant. q D. Solid Waste D.1 he voltane, activity and disposition of solid waste shipments during this reporting period are stamarized in Table Dl.l.

E. Radiation Dose to the Public E.1 Radiation Dose to the Public Offsite his information will be provided in the annual effluent report in accordance with Fermi-2 Technical Specification 6.9.1.8.

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. Page 10 E.2 Radiation Dose to the Public inside the Site Boundary The thermolminescent dosimeters ('ILD) of the Radiological Erwiror1 mental Monitoring Progran (REMP), located at defined sectors at the Site Boundary measured no dose above background levels. Values measured are provided in the Annual Environmental Operating Reports as required by section 6.9.1.7 of the Fermi-2 Technical Specifications.

Members of the Public inside the Site Protected Area are required to be under constant surveillance by their site escort. S e site escort is required to have the appropriate dosimetry in order to enter the Site Protected Area.

F. Meteorological Data h is information will be provided in the annual effluent report in accordance with Fermi-2 Technical Specification 6.9.1.8.

G. Notification of Changes G.1 Changes to the Process Control Progran (PCP)

Changes to the Process Control Program are presented in Table Gl.l.

G.2 Changes to the Offsite Dose Calculation Manual (CDCM)

Changes to the Offsite Dose Calculation Manual (CECM) are presented in Table G2.1.

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! TABLE A4.1 RADIDACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Sampling Analysis Type of - Detection (LLD)*

Frequency Activity Analysis (pCi/al)

Gaseous Release Type Frequency P, S I i

P. S b -

A. Containment PURGE Each PURGE Each PURGE Principal Gamma Emitters 1x10 4 6 Grab Sample P H-3 Iw10 (Pre treatment)

B. Reactor Building M C 'd

M C Principal Gamma Esitters* 1x10'.l C 1x10 Exhaust Plenum Grab Sample M H-3 StandbyGasTgest-ment System C. Radweste Building M M Principal Gamma Esitters" 1x10l Turbine Building Grab Sample M H-3 1x10 Service Building Dn-site Storage Facility

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D. All Release Types Continuous f yo 3 131 1x10y 1-133 1x10 as listed in 8 Adsorbent and C above. Sample b

Continuous' WE Principal Gamma Esitters 1x10'll Particulate (1-131,others)

Sample

-Al Continuous # M Gross Alpha 1x10 Composite Particulate Sample Continuous' Q Sr89, Sr-90 1x10'll Composite '

Particulate Sample

-6 Continuous I

Noble Gas Noble Gases 1x10 Monitor Gross Beta or Gamma e

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  • Pege 12 TABtE A4.1 CONTINUED _ _

TABLE NOTATION "The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a '"real" signal.

For e particular measurement system, which may include radiochemical separation:

"b LLD =

E V 2.22 x 108 Y exp (-Aat)

Where:

LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, sb is the standard deviation of the background counting rate ur of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 10s is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, whan applicable, A is the radioactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V, Y, and at should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (af ter the f act) linit for a particular measurement.

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-- yg,,- eW--p a- - - , , -. ,.-,w-, -- >--y- - --,-.y- ,.

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Page 13 TABLE A4.1 CONTINUED, TABLE NOTATIONS .

b The principal gamma emitters for which the LLO specification applies exclusively i are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, -

1-131, Cs-134, Cs-137, Ce-141 and Ce-144 in iodine and particulate releases.

This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8.

C Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

d Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when either the reactor well or the dryer-separator storage pool is flooded.

' Tritium grab samples shall be taken at least once per 7 days from Oe ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.

95amples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler. 1 Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least i 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10.

This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

h Required when the SGTS is in operation.

I The containment shall be sampled and analyzed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the start of any VENTING or PURGING and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during VENTING or PURGING of the drywell through other than the SGTS.

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,, Page 14 TABLE A4.2 RADIDACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM .

Lower Limit Minimum ofDetectjon Liquid Release '

Sampling Analysis Type of Activity (LLD)

Type Frequency Frequency Analysis (pCi/ml)

A. Batch Wgste P P 7

Release Each Batch Each Batch Principa} Gamma 5x10 Sample Emitters Tanks (3)

-6 I-131 1x10 P M Dissolved and 1x10

-5 One Batch /M Entrained Gases (Gamma Emitters) 1x10

-5 P M H-3 d

Each Batch Composite _

Gross Alpha 1x10 P Sr-89, Sr-90 5x10 4

Q d Each Batch Composite Fe-55 1x10

-6

~7 B. Continuogs M d Principa} Gamma 5 x10 Releases Composite Emitters General Service NA Water System I-131 1x10

-6 (GSW) (If Contaminated) Dissolved and -5 W M 1x10 Grab Sample Entrained Gases (Gamma Emitters)

H-3

-5 1x10 d ~7 NA Composi e Gross Alpha 1x10

~8 Q d Sr-89, Sr-90 5x10 NA Composite

-6 Fe-55 1x10

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. k 4 @-" e,e pp g..

  • '4*MM-- .m.. g_.gs ,

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- Page 15 TABLE A4.1 CO_NTINUED . _

TARLE NOTATION ,

"The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

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For a particular measurement system, which may include radiochemical separation:

4.66 s b '

E V 2.22 x 108 Y exp (-Aat)

Where:

LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, s is the standard deviation of the background counting rate or of b

tne counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 10s is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and At for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V, Y, and at should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

bA batch release is the discharge of liquid wastes of a discrete volume. I Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling.

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, l TABLE A4.1 CONTINUED _ __ __ _ . .

TABLE NOTATION C

The principal gamma emitters for which the LLD specification applies exclusively are: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8.

d A fomposite sample is one in which the quantity of liquid samples is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. This may be accomplished through composites of grab samples obtained prior to d'scharge after the tanks have been recirculated.

'A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of a system that has an input flow during the continuous release.

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TABLE A5.1 P.o n e _17 REPORT CATEGORY  : BATOi RELEASE SU!! MARY RELEASE POINT  : ALL TYPE OF RELEASE  : BATOI LIQUID AND GASEOUS PERIOD START TIME  : 0: 00 HRS = 12 :00AM JANUARY 1,1986 PERIOD END TI!1E  : 4343:59 HRS = 11:59PM JUNE 30, 1986

. LIQUID RELEASES NUFBER OF RELEASES  : 31 TOTAL TIME FOR 'ALL RELEASES : 14083.0 MINUTES MAXIMUf! TIME FOR A RELEASE  : 510.0 MINUTES AVERAGE TIME FOR A RELEASE  : 454.3 MINU TES NINIMUlf TIME FOR A RELEASE : 1 81 .0 MINUTES AVERAGE STREAM FLGi  : 8289.7 GPM t

GASEOUS RELEASES NUtEER OF RELEASES  : 0

'IOTAL TIME FOR ALL RELEASES : 0.0 MINUTES MAXIMUM TIME FOR A RELEASE  : 0.0 MINUTES AVERAGE TIME FOR A RELEASE  : 0.0 ' MINUTES MINIMUli TIME FOR A RELEASE  : 0 .0 -MINUTES f

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. . TABLE Bl.1 Page 18 _ _

REPORT CATEGORY  : SEMIANNUAL SUMhATIOJI OF ALL RELEASES BY QUARTER TYPE OF ACTIVITY  : ALL AIRBORNE EFFLUENTS REPORTING PERIOD  : QUARTER f 1 AND QUARTER 4 2

UNIT  : QUARTER 1 :OUARTER 2
:HOU RS :HOU RS TYPE OF EFFLUENT  :  : 1-2160 :2161-4344 A. FISSION AND ACTIVATIO!! PRODUCTS
1. 'IOTAL . RELEASE :CU RIES  : 0.00E-01 : 0. 0 0 E-01 :

1

2. AVERME RELEASE RATE FOR PERIOD UCI/SEC  : 0.0 0 E-01 : 0.0 0 E-01 :

, D. RADIOIODINES l . 'IOTAL IODINE-131 :CU RIES  : 0.0 0 E-01 : 0.0 0 E-01 :

2. AVERME RELEASE RATE EOR PERIOD :UCI/SEC  : 0.00E-01 : 0.0 0 E-01 :

)

C. PARTICULATES

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l . PARTIOJLATES(HALF-LIVES >8 DAYS) :CU RIES  : li.60E  :

_ __ . _ . _ __ _ ___ . __ _..___________ }_-01 ~ f ~~0.00'E-01_ __

~

~

2. AVERME RELEASE RATE FOR PERIOD :UCI/SEC  : 0. 60E. 01 l. 0700E.01 ;
3. GROSS ALPil A RADIOACTIVITY  : CURIES  : 0.0 0 E-01 : 0.0 0 E-01 :

D. _'IR _ _ _ ITIU

_ _ M_ _ _ . . _ _ _ _ _ . . _ . _ _ _ . _ _ _ _ . .

1. '!OTAL RELEASE
CURIES  : 0.0 0 E-01 : 0. 0 0 E-01 :
2. AVERME RELEASE RATE EOR PERIOD U CI/SEC  : 0.0 0 E-01 : 0.0 0 E-01 :

e l

1 i

,Y,.N,..-...--,--,

~

S -'

, ..r--- .,- - -------e - - - - - - + - - ~ ~ ' - - - - ' ' ~ ~ ' ' ' * ^ ' ' - ^ - ^ ^ " ~ ' ' ' ' ' ^ ' ' ' ^ ~ ' ' " ' '

", TABLE B2.1 . _ ..Page.19 _.

REPORT CATEGORY SEMI ANNUAL AIRBORNE CONTINUOUS GROUND

LEVEL RELEASES. 'IOTALS FOR EA01 NUCLIDE RELEASED.

TYPE OF ACTIVITY  : FISSIO!! GASES, IODIN ES, AND PARTIQJL ATES REPORTING PERIOD  : QUARTER i 1 AND QUARTER 6 2

GROU ND RELEAS ES l'  : UNIT  : QUARTER 1 : QUARTER 2
: HOURS :H OU RS
NUCLIDE ,
: 1-2160 :2161-4344  :

~

i FISSION GASES .

KR- 83M  : CU RIES  : 0.00 E-01 : 0.00 E-01  ;

KR-85M  : CU RIES  : 0.0 0 E-01 : 0.00E-01 .

KR-85  : CU RIES  : 0. 00 E-01 : 0.00E-01  :

KR- 87  : CU RIES  : 0.0 0 E-01 : 0.00E-01 KR-88  : CU RIES  : 0.00E-01 : 0.0 0 E-01 1 KR- 89  : CU RIES  : 0.00 E-01 : 0.0 0 E-01 4

KR-90  : CU RIES  : 0.00 E-01 : 0.00E-01 XE-131ti  : CU RIES  : 0.00 E-01 : 0. 0 0 E-01

, XE-133!1  : . CURIES  : 0.00E-01 : 0.00 E-01 XE-133  : CU RIES  : 0. 0 0 E-01 : 0.0 0 E-01 I XE-135M  : CU RIES  : 0.00 E-01 : 0.0 0 E-01 XE-135  : CU RIES  : 0.00 E-01 : 0.00 E-01 i XE-137  : CURIES  : 0.0 0 E-01 : 0.0 0 E-01 XE-13 8  : CU RIES  : 0.0 0 E-01 : 0.0 0 E-01 i AR-41  : CU RIES  : 0.00E-01 : 0.00 E-01 .

.I TOTAL FOR PERIOD  : CU RIES  : 0.00 E-01 : 0.0 0 E-01 .

, IODINES I-130  : CU RIES  : 0.00 E-01 : 0.0 0 E-01 I-131  : CURIES  : 0.0 0 E-01 : 0.0 0 E-01 i I-132  : Q) RIES  : 0.0 0 E-01 : 0.0 0 E-01 I-133  : QJRIES  : 0.0 0 E-01 : 0.0 0 E-01

I-134
CU RIES  : 0.0 0 E-01 : 0. 0 0 E-01 I-135  : CURIES  : 0.0 0 E-01 : 0.0 0 E-01 TOTAL FOR PERIOD  : CU RIES  : 0.00 E-01 : 0.00 E-01 1

i e-

m. - +- _ . . , . _ - - - __.,_..._c__.,;_;.n_._._J_*,C_,___,__2..____._.,_._.._,__._.__..

TABLE B2.1 .__

_ _ P a g e_ 2_0_.

REP, ORT CATEGORY SEMI AN11UAL AIRDORNE GROUND

LEJEL RELEASES. 'IOTALS EDR EAG MJCLIDE RELEASED.

TYPE OF ACTIVITY  : FISSION GASES, IODIN ES, AND PARTIGL ATES REPORTING PERIOD  : QUARTER # 1 AND QUARTER # 2

GROUND RELEASES 1
UNIT  : QUARTER 1 QUARTER 2
:H OU RS  : HOURS NUCLIDE ,
: 1-2160 :2161-4344

~

i PARTIG LATES 11 - 3 .

CU RIES  : 0.0 0 E-01. : 0.00E-01 _ _

~ ~~

NA-24  : CU RIES  : 0.00 E-01 : 0.0 0'E-01

~ ~

0.00 E-01 : 0.00E-01'~~

~ ~ ~

CR-51
' CU RIES MN-54  : CU RIES  : 0.0 0 E-01 : 0.00 E-01 MN-56  : CU RIES  : 0.0 0 E-01 : 0.00E-01 FE-55  : CU RIES  : 0.0 0 E-01 : 0.00E-01 FE-59  : CU RIES  : 0.0 0 E-01 : 0.00 E-01 CO-58  : CU RIES  : 0.00E-01 : 0.00E-01 CO-60  : CU RIES  : 0.0 0 E-01 : 0.00E-01 NI-63  : CU RIES  : 0.0 0 E-01 : 0.0 0 E-01 l NI-65  : CURIES  : 0.00 E-01 : 0.00E-01 CU-64  : CU RIES  : 0.00E-01 : 0.00E-01 ZN-65  : CU RIES  : 0.00 E-01 : 0.0 0 E-01 Z N-6 9  : Q RIES  : 0.00E-01 : 0.0 0 E-01

) BR- 83  : CU RIES  : 0.0 0 E-01 0.00 E-01 BR- 84  : CU RIES  : 0.00 E-01 : 0.0 0 E-01 B R- 85  : CU RIES  : 0.00 E-01 : 0.00E-01 RB- 86  : G RIES  : 0.0 0 E-01 : 0.0 0 E-01 RB-88  : CU RIES  : 0.00 E-01 : 0.00E-01 RB- 89  : G RIES  : 0. 0 0 E-01 : 0.00E-01 S R- 89  : CJRIES  : 0.00E-01 : 0.00E-01 S R-91  : CU RIES  : ' O .0 0 E-01 : 0.00E-01 S R-92 _. . .

CU RIES  : 0.00E-01 : 0.0 0 E-01

! Y-91M  : CURIES  : 0.0 0 E-01 : 0.00E-01 Y-91  : G RIES  : 0.00E-01 : 0.000-01 l

i N

--.-----.--._--r=_2.---.=_-.-.. . - _ - - . . - _ _ _ _ - -

TABLE B2.1 Pege'21 _ _ __

REPO'RT CA'TEGORY  : SEMI ANNUAL AIRBORNR GROUND

LEVEL RELEASES. '!DTALS TUR EA01 NUCLIDE RELEASED.

TYPE OF ACTIVITY  : FISSION GASES, IO DIN ES, AND PARTIGLATES l REPORTING PERIOD  : QUARTER ( l A!!D QUARTER ( 2

GROUND REL EASES j
UNIT  : QUARTER 1 QUARTER 2
:H OURS :H OURS NUCLIDE *
: 1-2160 :2161-4344 PARTIGLATES ~ CON TINU ED Y-92  : G RIES  : 0.00 E-01 : 0.00 E-01 Y-93  : CU RIES  : 0.0 0 E-01 : 0.0 0 E-01 E R-95  : CU RIES  : 0.00 E-01 : 0.00 E-01 Z R-97  : CU RIES  : 0. 00 E-01 : 0.00E-01 NB-95  : CU RIES  : 0.00 E-01 : 0.0 0 E-01 MO-99  : CU RIES  : 0.0 0 E-01 : 0. 00 E-01 TC-9911  : CU RIES  : 0.00E-01 : 0.0 0 E-01 TC-101  : CURIES  : 0.00 E-01 : 0.0 0 E-01 RU-103  : CU RIES  : 0.0 0 E-01 : 0.00E-01 RU-105  : CURIES  : 0.00E-01 : 0.00 E-01 RU-106  : CU RIES  : 0.00 E-01 : 0.00E-01 AG-11011  : CU RIES  : 0.00E-01 : 0.00 E-01 TE-125M  : CU RIES  : 0.00 E-01 : 0.00E-01 TE-127M  : CU RIES  : 0.00 E-01 : 0.00E-01 TE-127  : CU RIES  : 0.00E-01 : 0.00E-01 TE-129M  : CU RIES  : 0.0 0 E-01 : 0.00E-01 TE-129  : CU RIES  : 0.00 E-01 : 0.00E-01 TE-131M  : CU RIES  : 0.00 E-01 : 0.00 E-01 TE-131  : CURIES  : 0.00 E-01 : 0.00E-01 TE-132  : CU RIES  : 0.00E-01  : 0.00E-01 I-130  : CURIES  : 0.00E-01  : 0.00E-01 I-131  : CU RIES  : 0.00E-01  : 0.00E-01 I-132  : CURIES  : 0.00E-01  : 0.00E-01 I-133  : CU RIES  : 0.00E-01  : 0.00E-01 I-134  : CU RIES  : 0.00E-01  : 0.00E-01 I-135  : CURIES  : 0.00E-01  : 0.00E-01 CS-134  : CU RIES  : 0.00E-01  : 0.00E-01 CS-136  : CU RIES  : 0.00E-01  : 0.00E-01 e

P***T = , , + = =

--**tM4CS**ep+-"'r M*d***

TABLE B2.1 _ _ _

Page 22 .

REPORT CATEGORY  : SEMIANNUAL AIRBORNE GROUND

LEVEL RELEASES. 'JOTALS EUR EAG NUCLIDE RELEASED.

TYPE OF ACTIVITY  : FISSION GASES, IODIN ES, AND PARTIQJLATES REPORTING PERIOD  : QUARTER 6 1 AND QUARTER 6 2

GROUND RELEAS ES  :
U NIT  : QUARTER 1 : QUARTER 2 :
:H OURS :HGJRS  :

NUCLIDE ,

: 1-2160 2161-4344  :

PARTIGLATES ~ CON TINU ED CS-137  : CU RIES  : 0.00 E-01 : 0.00E-01 :

CS-13 8  : CU RIES  : 0.00E-01 : 0.00E-01 :

B A-13 9  : CU RIES  : 0.00 E-01 : 0.00E-01 :

BA-140  : CU RIES  : 0.00E-01 : 0.00E-01 :

DA-141  : CU RIES  : 0.0 0 E-01 : 0.00E-01 B A-14 2  : CU RIES  : 0.00 E-01 : 0.00E-01 LA-140  : CURIES  : 0.00E-01 : 0.00 E-01 LA-142  : CU RIES  : 0.00 E-01 : 0.00E-01 CE-141  : CU RIES  : 0.0 0 E-01 : 0.00 E-01 CE-143  : CURIES  : 0.00 E-01 : 0.00E-01 CE-144 -  : CU RIES  : 0.00 E-01 : 0.00E-01 PR-143  : CU RIES  : 0.0 0 E-01 : 0.00E-01 PR-144  : CU RIES  : 0.00 E-01 : 0.00 E-01 ND-147  : CU RIES  : 0.0 0 E-01 : 0.00 E-01 W-187  : CURIES  : 0.00 E-01 0.00E-01 NP-23 9  : CU RIES 0.00E-01 : 0.00E-01 S R-90  : W RIES  :: ~h00E-01

  • _0.00E-01 G ALPH A  : CU RIES  : 0.00E  : 0.00E. ___

___________-03

___________________________________________-01

'IOTAL FOR PERIOD  : CURIES  : 0.00E-01 : 0.00E-01 es s

--- *,-e% _ _ _ _ _

-q pw. w. .. .--.9.. .

TABLE C1.1 Page 23 REPO5tT CATEGORY  : SEMIANNUAL SUl1MATION OF ALL RELEASES BY QUARTER TYPE OF ACTIVITY  : ALL LIQUID EFFLUENTS REPORTING PERIOD  : QUARTER 4 1 AND QUARTER 4 2

U NIT  : QUARTER 1 : QUARTER 2
:HOU RS :H OU RS TYPE OF EFFLUENT  :  : 1-2160 :2161-4344 A. FISSION AND ACTIVATION PRODUCTS

_____________________e_______________________________________________.

4

1. 'IOTAL. RELEASE (NOT INCLUDING  :  :  :  :

TRITIUM, GASES, ALPHA)  : CURIES  : 0.0 0 E-01 : 6.13E-04 :

' 2. AVERAGE DILUTED CONCEN'IRATION  :  :  :  :

DURING PERIOD :UCI/ML  : 0.0 0 E-01 : 4.04E-09 :

B. TRITIU M

1. '.IOTAL.. RELEASE
CURIES  : 0.0 0 E-01 : 2.88E-02 :

! 2. AVERAGE DILUTED CONCENTRATION  :  :  :  :

DURING PERIOD :UCI/ML  : 0.0 0 E-01 : 1.91 E-07 :

1 i

C. DISSOLVED AND ENTRAINED GASES

1. '_IOTAL RELEASE  : CURIES  : 0.0 0 E-01 : 0.00E-01 :

i

2. AVER /GE DILUTED CONCEN'IRATION  :  :  :  :

DURING PERIOD

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
UCI/ML _ _ _ _ _ _ _ :_0.0 _ _0_E-01 _ _ _: _0.0 _ _0_E-O _ _ ._: _ _ _ _ _ _ _ _

D. GROSS ALPH A RADIOACTIVITY i 1. '!OTAL RELEASE  : CURIES  : 0.00E-01 : 0.0 0 E-01 :

i E..

WASTE VOL RELEASED (PRE-DILUTION) : GAL  : 0.000-01 : 6.09E 05 :

F. VOLUME OF DILUTION WATER USED GAL  : 0.00E-01 : 1.16 E O S :

e i

b* -% .

--m%y+- -. ,.w w g. 4-..

, . . , , .,-4-,,.r... -e r- o :r -- ---- =- N~---* v^-- ~~''*'"#' * ' ' ' " ~ ' ' ~ ' ' ' ' ' - ' ~ ' ~ ~ ' ~ ~ ~ ~ ~ ~

'~" ~ ."

, , TABLE C2.1 _

_Ppge 24 ,

REPORT CATEGORY  : SEMI ANNUAL LIQUID DATG RELEASES TOTALS FOR EAG NUCLIDE RELI;ASED.

TYPE OF ACTIVITY  : ALL RADIONUCLIDES REPORTING PERIOD  : QUARTER 4 1 AND QUARTER 4 2 B ATG RELEAS ES  :

UNIT  : QUARTER 1 : QUARTER 2 : !
: HOURS  : HOURS :1 NUCLIDE  :  : 1-2160 :2161-4344  :

_____________________u____________________________________. ,

ALL 10CLIDES -

11 - 3 _ . .

CU RIES  : 0.00 E-01 : 2. 8 8 E-0 2_ .:

~

~

NA-24  : OJRIES  : 0. 0 0'E-01 : 0.0 0 E-0'l' ~:

~ ~~~ ~ ~

CR-51'~  : OJRIES  : 0.0 0 E-01 : 0.0 0 E-01 ': ~

MN-54  : CU RIES  : 0.0 0 E-01 : 0.00E-01 :

MN-56  : CU RIES  : 0.0 0 E-01 : 0.0 0 E-01 :

FE-55  : G RIES  : 0.00 E-01 : 6.13 E-04 :

FE-59  : CU RIES  : 0.00 E-01 : 0.0 0 E-01 :

CO-58  : CU RIES  : 0.0 0 E-01 : 0.00 E-01 :

CO-60  : CU RIES  : 0.00 E-01 : 0.0 0 E-01 : i

, NI-63  : CU RIES  : 0.0 0 E-01 : 0.0 0 E-01 : :

NI-65  : CU RIES  : 0.0 0 E-01 : 0.0 0 E-01 :

CU-64  : CU RIES  : 0.0 0 E-01 : 0.00E-01 :

ZN-65  : CU RIES  : 0.00E-01 : 0.0 0 E-01 :

ZN-69  : CU RIES  : 0.0 0 E-01 : 0.00 E-01  ;

B R- 83  : Q) RIES  : 0.00E-01 : 0.0 0 E-01 : :

BR- 84  : CU RIES  : 0.00 E-01 : 0.0 0 E-01 :

B R- 85  : CU RIES  : 0.0 0 E-01 : 0.0 0 E-01 :

RB- 86  : CU RIES  : 0.00 E-01 : 0.00E-01 : ,

RB-88  : CU RIES  : 0.0 0 E-01 : 0.0 0 E-01 :

RB-89  : OJRIES  : 0.00 E-01 : 0.0 0 E-01 :

S R- 89  : G RIES  : 0.00 E-01 : 0.00E-01 :

SR- 91  : CU RIES  : 0.0 0 E-01 : 0.0 0 E-01 :

S R- 92 , . . _ _ _ _ ,.

Gl_ RIES  : .,0.00E_01 : 0.0 0 E _01 : ,_ _

Y-91M  : G RIES  : 0.00 E-01 0.00E-01 :

Y- 91  : G RIES  : 0.00 E-01 : 0.00 E-01 :

e f

..,4 .-[_._-,,:_,,_,.___.m.__4-_.,.y,.._ I,7 ~ ' .,,_,__.,_.,2.-,,-___. .. -__.,m,_~

. . TABLE C2.1 __._ Pone 25 REPORT CATEGORY  : SEMIANUUAL LIQUID BAT 01 RELEASES TOTALS FOR EACH 20CLIDE RELEASED.

TYPE OF ACTIVITY  : ALL RACIONUC13 IDES '

f REPORTING PERIOD  : QUARTER # 1 $1D QUARTER # 2 J

i  : B AT01 RELEASES

UNIT  : QUARTER 1 : QUARTER 2
:H OU RS :H OU PS NUCLIDE  :  : 1-2160 2161-4344 ALL IUCLlDES .. CON TINU ED

, Y-92  : CU RIES  : 0.00 E-01 : 0.00E-01 Y-93  : CU RIES  : 0.00 E-01 : 0.00E-01 Z R-95  : CU RIES  : 0.00E-01 : 0.00E-01 Z R-97  : CU RIES  : 0.0 0 E-01 : 0.00E-01 NB-05  : CU RIES  : 0.0 0 E-01 0.00E-01 MO-99  : CU RIES  : 0.00 E-01 : 0.0 0 E-01 TC-99M  : CU RIES  : 0.00E-01 : 0.00E-01 TC-101  : CU RIES  : 0.0 0 E-01 : 0.0 0 E-01 RU-103  : CU RIES  : 0.0 0 E-01 : 0.00 E-01 RU-105  : CU RIES  : 0.00E-01 : 0.00E-01 RU-106  : CU RIES  : 0. 0 0 E-01 : 0.0 0 E-01 AG-110H  : CU RIES  : 0.0 0 E-01 : 0.00 E-01 J TE-125M  : CU RIES  : 0.00 E-01 : 0.00E-01

'TE-127M  : CU RIES  : 0.0 0 E-01 : 0.00E-01

TE-127  : CU RIES  : 0.0 0 E-01 : 0.00E-01

' TE-12 9M  : CURIES  : 0.00 E-01 r 0.00E-01 TE-129  : CU RIES  : 0.0 0 E-01 : 0.0 0 E-01 4

TE-131M  : CU RIES  : 0.0 0 E-01 : 0.00E-01 TE-131  : CU RIES  : 0.0 0 E-01 : 0.00E-01 TE-13 2  : CURIES  : 0.0 0 E-01 : 0.00E-01 I-130  : CURIES  : 0. 0 0 E-01 : 0.00E-01 1-131  : CU RIES  : 0.0 0 E-01 : 0.0 0 E-01

> I-132  : CU RIES  : 0.0 0 E-01 : 0.00E-01 I-133  : W RIES  : 0.00E-01 : 0.00E-01

, I-134  : QJRIES  : 0.00E-01 : 0.00E-01 I-135  : CU RIES  : 0.0 0 E-01 : 0.00E-01 CS-134  : G RIES  : 0.00E-01 : 0.00E-01 CS-136  : CU RIES  : 0.00E-01 : 0.00E-01 j l

I l

c l

l l

'~.'":*_--,_,.,7 . ,2T - . , . - - + - -,  :. ' C :,T:: . ., -. i w -,. ._- - . -. . , . _, .- . .. .

, , TABLE C2.1 _ _ _ . . [ Pane 26 REPOltT CATEGORY  : SEMIANNUAt LIQUID BATG RELEASES TOTALS FOR EAG NUCLIDE RELEASED.

TYPE OF ACTIVITY  : ALL RADIONUCLIDES REPORTING PERIOD  : QUARTER f 1 AND QUARTER f 2 s

B ATCH RELEAS ES
UNIT QUARTER 1 : QUARTER 2
:H OURS :H(11RS NUCLIDE  :  : 1-2160 :2161-4344 ALL MICLIDES - CON TINU ED CS-137  : CU RIES  : 0.00 E-01 : 0.0 0 E-01 CS-13 8  : CU RIES  : 0. 0 0 E-01 : 0. 00 E-01 B A-139  : CURIES  : 0.00 E-01 : 0.0 0 E-01 BA-140  : CU RIES  : 0.0 0 E-01 : 0.00 E-01 BA-141  : CU RIES  : 0.00E-01 : 0.0 0 E-01 BA-142  : CU RIES  : 0.00 E-01 : 0.00 E-01 LA-140  : 0.0 0 E-01 : 0.00 E-01
CO RIES
LA-142  : CU RIES  : 0.0 0 E-01 : 0.00 E-01 CE-141  : CU RIES  : 0.00 E-01 : 0.00 E-01 CE-143  : CU RIES  : 0.00 E-01 : 0.0 0 E-01 CE-144  : CU RIES  : 0.0 0 E-01 : 0.00 E-01 PR-143  : CU RIES  : 0.0 0 E-01 : 0.00E-01 PR-144  : CU RIES  : 0.0 0 E-01 : 0.00 E-01 ND-147  : CU RIES  : 0.00 E-01 : 0.0 0 E-01 W-187  : CU RIES  : 0.00 E-01 : 0. 00 E-01 NP-23 9  : CIIRIES  : 0.00 E-01 : 0.00 E-01 KR- 83 M *
CU RIES  : 0.0 0 E-01 : 0.0 0 E-01 KR-85M  : CIIRIES  : 0. 00 E-01 : 0.00 E-01 KR- 85  : CU RIES  : 0.00 E-01 : 0.00E-01 KR- 87  : CURIES  : 0.00 E-01 : 0.00 E-01 KR-88  : CU RIES  : 0.0 0 E-01 : 0.00E-01 KR- 89  : G RIES  : 0.0 0 E-01 : 0.00E-01 KR-90  : CURIES  : 0.0 0 E-01 : 0.00 E-01 XE-131M  : CU RIES  : 0.0 0 E-01 : 0.0 0 E-01 XE-133H  : CURIES  : 0.0 0 E-01 : 0.0 0 E-01 XE-133  : CU RIES  : 0.0 0 E-01 : 0. 0 0 E-01 XE-13 5M  : CU RIES  : 0.0 0 E-01 : 0.00E-01 XE-135  : CURIES  : 0.0 0 E-01 : 0.00 E-01 <

1 4

4 l

d 1

1 l

Y TT. ~.-_ ,L _ , - , , . l T  : --_,.- - ,L .C .L*.._ _ - __.-.. ~._ - _ _

Page 27 TABLE C2.1

~ - - ~ ~ '

REPORT CATEGORY  : SEMIANNUAL LIQUID DATG RELEASES

TOTALS FOR EA01 NUCLIDE RELEASED.

TYPE OP ACTIVITY  : EL RADIONUCLIDES REPORTING PERIOD  : QUARTER 4 1 AND QUARTER i 2

BATQI RELEASES
UNIT  : QUARTER 1 QUARTER 2
HOURS HOU RS NUCLIDE  :  : 1-2160 22161-4344 EL IUCLIDES ~ CONTINU ED XE-137  : CU RIES  : 0.00 E-01 : 0.0 0 E-01 XE-138  : QIRIES  : 0.00 E-01 : 0.00 E-01 AR-41  : CU RIES  : 0. 0 0 E-01 : 0.0 0 E-01 S R- 90  : CU RIES  : 0.00E-01 : 0.00E-01 G EPH A  : CU RIES  : 0.00 E-01 : 0.00 E-01 OTH ER  : CU RIES  : 0.00 E-01 : 0.00E-01

'IOTE FOR PERIOD  : QJ RIES  : 0.00E-01 : 2.94 E-02 1

h a

b f

6 t

~ ' ~ - ~ ~ ~ ~ . - = . +- _.

en. .

T ~ - - g ----- -- __._m. ,_ g , , , . ,, _ _ , , , , _ , _

. . Page 28 TABLE Dl.1 SOLID WASTE SLDORRY .,

Soltd Weste Cetegory hD,C)c0 hlgr A/p,,b . Sheet I of I Reporting Period: . s m .v 1. Aer, through mac v , Att

~

Parame ter Shi puent Number Total

. 1 2 3 4 5

~

1. Dete (No/Ds/Yr) l 2/24[fL 6[MSA
2. Volume (m3 ) so 5 4.g IXXXX
3. Radioactivity Content (C1) a . c(2 E I 267 c-4 -

A.6t e-4

b. up54 a ss E-4 s'oc, e-4 7.4 r-4 c . FE 59 - -
d. Co 60 s.545r-3 /,.rofe-3 I .is>2 E-f5 A 1
e. Co Sif ' 3. Fi? C-3 3 GGE 3 s. f4 E -2.
f. to S 1 - -.

S 2rJ6 5 --- -

h. 2 ist - -

r 1. C si .f.584 c-5 i s58 c-3 4 4nc-3

.1

  • N s b b- 1 l'1 C-4 s 28 E-4 2 46 E-+
k. N 241 J.3sq E-(, i.33, r. G 2 Mfc4 1 14-3 _ g o C-C Str.S s. iq c m.

M.

xAAAA

4. Total Redto- i,m c a. izz7F-1 3 co# c.7.

activity (C1) 4

5. Type of Container STc sTc.
6. Source of Waste I Powtr.ech %%

enma m .s

7. Processing Employed ** *T'" wneug
8. Solidification gf Agent
    • s..

o *. m' . s'

.-.-,-,,??_.---.-,.-,-.,_.-__..--,_~: _.,- _ . ~ , y ~,."L_-_ - - *,2 ~.:, L ---. ,-- ..--... -.,., - - - - - - - - - - , -

p .7__ , ,

Page 29

- - TABLE Dl.1 SOLID WASTES

SUMMARY

~

~

_ SOLID WASTE AND IRRADIATED FUEL SHIPMEhTS *

- A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSA

1. Type of Waste Unit 6-Month Est. Total Period Error I
a. Spent resins, filter sludges, m3 6.1 E evaporator bottoms, etc. C1 3.t 4 E-2 . E
b. Dry compressible waste, m3 E contaminated equip, etc. Ci

. E . E

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

Ci . E . E

d. Other (describe) m3 . E Ci . E . E 2.

Estimate of major nuclide composition (by type of waste)

a. _CRsl F. f72 1 2 62 E-4 Mose 3630 1 e _ ft40

&f 6f2 1 er .4 E-4

  1. . _ Coi? 4/. 7, t 1 i swt E -t

_ di4 .24 E -t

,./.it? 1 4 441 E -g E L.'S c.rg 1 pr _ pu w a.4s E-4 l _ 64 %

oref 1 2 64r E-6,

' r. sfi,1 a . i'i E -4_

l 4.s. 1 . E l 1 . E -

l 1 . E 1 . E

3. Solid Waste Disposition

_ Number of Shipments Mode of Transportation De stina tion

.t CN8*^'A**3**CRMNb)ftga temm eAnawe (case.uu 64&%S c,

3. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation -

Destina tion s AkMr Ahwc M

e .

s . Pcan 30 1

TABLE Gl.1 Phort55 CON 1 ROi PROCR/M CHANGl REQUE51

, T /14 h d Dat e : t/1s/P4 Chann Requested by: '

f/

//, , ,.

Departnent/Section: .

Applicable Section(s): //p, - o , E "m (/cd f

/Y,O 7,,.e v ,2M [w w Change (Attach Markups to the PCP): Me# # '

GM;/ A- V _

keaker. f or Chan;:c/ Justification (Include suf ficiently Attach detailed inf ormat additional sheetsior.

t o tota 11v support the rationale for the

  • ii necers'ary): (2 N ,;7 ( h 1.C ,[ J/)/phange.-f',L x.. , X s. o . i cf7 -a od:/t X

.i1,~. ./ r;/ict. ML ._

A , f.. .: /. f an .

A T s C. c. ~ /lt /& ,2~ - .<._ht . A- "

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fz ,. s,..

o,. a t'~ FK,,J 2. A t t fl2 ' L .,i ..lJ ,,W

-i, Lta Y: s.,) n..,a - s r o - e - cc-onur " uL . run c

~,s.x a, 1.:t~a -CL < s r s).K .n-cec i 31,(.11l<il"~: S ., X. rm nu > ~ n.J t r l[O . w. ~tt' 'NJ lbu fr 2 u/ 2 IA T b IC A r u al A su. LL. iC~ > * - a*- t sd-k-t3'cri *ky- si e .. di<as C~p up5 "(bJ LL.Y'i t fu ) %s .. o...<f

(), n u.. . -TC: & Np*</l /"a~. Datc: f /yf/gr .

, ist f. < C/G $.$. L . e.,<fus

")<.~'

Enie. Periormed by 81,;, M 4(s. _

ener'e l Supervi sor - Radwa s t e 7 5+

Radchem I.ngineer has determined, as evidenced by his siFneture Iq:ow, that this charge does not reduce the overall conf o mance of the solidified waste product to existing criteria for solid wastes.

4 . ,( f f Date:

~'

/(> 8d Approved by:_ Radchem Enginee

/

, w/ Date: d'"*/%i/-84 Recommended by: '

" 6""Ma IL"n

wm 5 /

~

Date: .I /0!&Io Approved by:

Assis1 ant Manager-ll'uclear Produet son L_ , _ . _ $ 9 , , . - . - . _ - , _ _ , ,

Page 31 -

' TABLE Gl.1 FERMI 2 PROCESS CONTROL PROGRAM 1

sses fo'r Th3 Fermi 2 Process Control Program (FCP) covers five distinct The five processes are proce colidification or dewater.ing of radioactive, waste.

d2:cribed below: id 1.

For the devatering of NUS Corporation "TRANSPII" i l follow temporary liqu redwaste syr, tem disposable pressure vessels. i .x Fermi 2 which2was wl the submitted PCPindescribed a letter to the inNBC the dated NUS October document 11, F1-002 Revis 1954. ,

For the solidification of radioactive vaste using the NUS ill 2.

Corporation temporary radvaste solidification system. Fermi 2 w with approved Procedure Change Requests (PC Section 9.3. 9.4. 9 5. and 9.7 of SS-001/I-2 and SS-001/I-3.

this procedure are used.

i2 l

3.

For the solidification of radioactive waste using the Ferm FCF permanent solid radwaste system. Fermi 2 will follow the l

described in Attachment 1.

l 4.

For the dewatering of radioactive powdered resins in steel ibed containers using the Hittman Nuclear Incorporated 2.

in the Hittman Nuclear Document STD-PCP-03-001 Revis 5.

For the dewatering of radioactive bead resins in steel containers using the Hittman Nuclear Incorporated temporary dradwaste in the processing system. Fermi 2 will follow the PCP describe i Hittman Nuclear document STD-P-04-002 Revision tion of 5 the The General Supervisor - Radweste is responsible in for the in Fermi 2 PCP.

dewatering of radioactive waste including record keeping activities accordance with QAPR 24.

in Nu 2!/d (6 _

Recommended: - 'dw ze fe r 1 Superv o

'! d

<* e '

/

Noted: _ R ch - Engineer

/- /

N,//d /_k /

daw ~/ ,

Approved: '

OSRO Chairman i

NOTE: The NUS and Rittman Nuclear documents referenced above proprietary information, are not published as Fermi 2 documents, and are available only from the General Supervisor, j Radweste. I 1

I i ..

.,n..,,--.,-mg,- ,m.--..-.,----,.,~.s--,

~

-n-.-n...,,-n-----r--,,--..,.,.-..._.,,----,-,-,--,---n.a

-- lf/[ AlF Page 32

\,l, ,

TABLE Gl.1 w

PROCESS CONTROL PROGRAM CEANCE REQUEST Change Requested by: -

M, M Date:

~

Department /section: e Applicable Section(s): Y.

Caenge (Attach Marku to the PCF): c& eI~/CA l

Fm A Wt. r ad

  • Mri.,A MW A LA A

' ~2% b.~i1..eV2 s-L./ f;~,mlu.,u,. "a Gk 2 .~ ad 3/2 kt L " _ ' '

l ina' "ML ka L. G

,.r. .

i Reason for Change / Justification (Include sufficiently detailed information to totally suppor the ratipo 1 for the change. Attach additional sheets if necessary): 2: r,"$ $~,/ / 1 e

/Lfd,as ue.- d,u,, arH d _

uwlr; s4 A 1. 3 y -C.. 9 3 2 I . f>> %.cLL/ n -a; a*M1d>M, L, /wn

,1. A re~t

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Ald? 7~L a LL:M i,L& 212 %

Cf n2 ',17.6 L a Be n t/o.L -- ~ ."LM JL A-/ :7. L M EA_ ' '

~ '

++> < L t~ua - 6 JaMI. a i

j Review Ferformed by: hu,. g/}- -

t(nerald upervisor - Radweste Date: S/ 7/[d j j i

The Radchen Ingineer has determined, as evidenced by his signature below, i

that this change does not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.

Approved by: f,, , Dete: J de a gagineer ' /

Recommended by se a uM} Date: 8 50C 'rean .

Approved by:

Date:- ' '

M l Assistant Manager-Nuclear Mr' retic: ARMS.INFORMATION gYSTEMS DTC7 PAGE M O NREV.,_ 1 .,_,, 1DSNJE;k,,,,M Mg

. j fp j

  1. M4ubf s-s-W JUL 151986,4 ~7 dde

( yy ? g g ,y r -IND4 MS - - _ _ _ _

< = _ v -

092085

( { j M/ // S APPROVAL REtTD: YES RF lPIENT NO

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Lg.gs/$ds .

CONTROLLED O #

9 8 9

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LDv. >J

'

  • Page 33

>* TABLE Gl.1

( . FERMI 2 PROCESS C0h*IROL PROGRAM The Fermi 2 Process Control Program (PCP) covers five distinct processes for solidification or dewetering of radioactive waste. The five processes are

  • described below:

1

1. For the dewatering of NUS Corporation " TRANSFIX" temporary liquid radvaste system disposable pressure vessels, Fermi 2 will follow ,

t.he PCP described in the NUS document FI-002 Revision C which was submitted in a letter to the NRC dated October 11, 1984.

l 2. For the solidification of radioactive waste using the NUS _

Corporation temporary radweste solidification system, Fermi 2 will follow the PCP described in the NUS document 85-001 Revision I, with approved Procedure Change Requests (PCR) SS-001/I-1 SS-001/I-2, and SS-001/I-3. Section 9.3, 9.4. 9.5, and 9.7 of this procedure are used.

3. For the solidification of radioactive waste using the Feral 2 j permanent solid radwaste system, Fermi 2 will follow the PCP 1 described in Attachment 1.

4 For the dewatering of radioactive powdered resins in steel containers using the Mittman Nuclear Incorporated temporary radwaste processing system, Fermi 2 will follow the PCP described

( {

in the Mittman Nuclear Document STD-PCP-03-001 Revision 3. 3

5. For the dewatering of radioactive bend resins in steel containers using the Hittman Nuclear Inc,orporated temporary radweste processing system, Termi 2 vill follow the PCP described in the Hit tman Nuclear document STD-P-04-002 Revision 5.

The General Supervisor - Radwaste is responsible for the implementation of the Fermi 2 FCP. Nuclear Quality Assurance will audit the solidification and dewatering of radioactive waste including record keeping activities in accordance with QAPR 24. ,

Recommended: _ I: 74I v > G5 1 Supervisor adweste'

Gen M7 .3 /d Noted: /'

RIJ he - ' Engineer '

Approved: # jiP

~'

f4

~#

OSRO Chairman NOTE: The NUS and Mittman Nuclear documents referenced above contain l proprietary information, are not published as Termi i document s, and are available only f rom the General Supervisor, Radweste.

\

Page 34 f,3f.3 A'I TABLE G2.1 - 1 p.'s. /

' ( k fY'l H" '" N' ']

( DTTSITE DDSI CALCULATION MANUAL. CHAX:I Ff QUEFT)

~

J Change Requested by
C . WFJ S ( Date: . 5h% j

,[ Departeent/seetion:kt'<dIeden f{[a ~/ e._

i , h V4NfnsMd (w M..%4 .

{i See ion
A E
  • s O ~h . D ~ \ d C) 3 ,

, .y u \ *[y *'

Change (Attach Ma kups to the CDCM, each page shall be susbered an'd rrovided with an approval sad,(ate,b g ):_ AA Mfc_U m gM M talk w .o -t e ,_ _ A c, _t h 3 . e s . -

3 7eason for Change /Nstification (Include sufficiently detailed infer =atier.

to totally support the rationale for the change and appropriate analyser er evaluations justifying the change. Attach additional sheets if necessary):

  • STP17h) /b IJfitrikW t141bJcf //Gs/stfG &ErfJ5G /Kivw' B EddHl.- $MA A J8 A!N M C.M*9 $ h MN1.
  • STM7t.W - I% MIAJG A DDl(D ta Rern s' AG M ti K SWWt Y ACHD bleter AA&Ynd AIA1r N DL /x 47onl
  • 31RT:Os WS 1 1 -Lts SENC, ADLYo To RemP 'i4s DIRECT RnOiAT1od MOU ITroeldG t_nt M oras j e"T24/c rc6vset ra. inca STg a.a.M.?AS (sv dn~*F eedseJTm s'T7=T. ese rifAd figert 08edhf~t ' t&tw M bests.,Ac rrgs4FE4 Technich) Review Parformed by: & f m:_'

2,9 Date: iia /st_

f The RadcheIEngineer has determined, as evidenced by his si5 nature below, that this thange does not resdit in a reduction of the accura:y or reliability of dose calculations or setpoint determinations.

Approved by: m_ E Date: G/ 8d Ra ches Engined'Ir / /

Recommended by: w Date:_ [ O RO Chairman Approved by: -c -- - M/ Date! (- /b Assistant Nasager-Suclear Productaen

'Jhe Assistant Manager-Nuclear Production shall also approve esth page of the attached markups af the ODCM.

Amus.oa0RMATON SYSTEMS DTCTlhoffR, psu m e naperdt Fe ,

0920e5 PAGE REV A Pts l CONTROLLED .tiiN 171986 pis M 20 RECIPIENT '

wa#0 Vat REQD YES- NO_

l

Page 35 TABLE G2.1 SECTION 3.0 RADIOLOGICAL ENVIRONMEtr.AL MONITORING PROGRAM 3.1 SAMPLING LOCATIONS

. Sampling locations as required in Technical Specification 3/4.12.1 are described in Table 3.0-1 and shown on the maps in

~

Figures 3.0-1, 3.0-2, 3.0-3.

NOTE: For the purpose of implementing Technical Specification 3.12.2, sampling locations will be modified as required to reflect the findings of the Land Use Census.

,c f9

)

CDCM, Fennii-2 3.0-1 APPROVAL:

DATE: L h6/M

- . .. ~~~

, Pega 35 TABLE G2.1 TABLE 3.0-1 Radiological Environmental Monitoring Program, Fermi .

C Sample Locations and Associated Media Meteorological Stetion Sector / Azimuth Distance from Numbtr Direction Reactor (Approx) Description Media Frequency 1 ' NE/38*.- 1.4 mi. Estral Beach (community) Direct Radiation 0 Pole on Lakeshore, 18 Radioiodine W Poles S. of Lakeview Particulates W 2 NNE/21* 1.1 mi. Tree at the termination Direct Radiation Q Brancho Street (private residence) 3 N/4* 1.1 mi . Pole at NW corner of Swan Direct Radiation Q Boat Club Fence (Community) 4 NNW/340* 0.6 mi. Site Boundary and Toll Direct Radiation Q Road, on Site Fence by Radiciodine W APS #4 Particulates W 5 NW/321* 0.6 mi. Site Boundary and Toll Direct Radiation Q Road on Site Fence by Radioiodine W APS #5 Particulates W 6 WNW/296* 0.6 mi. Pole NE corner of bridge Direc: Radiation Q over Toll Road 7* W/269* 14.2 mi. Pole, behind Doty Farm, Direct Radiation O 7512 N. Custer Road Radioiodine W (control) Particulates W 1 Milk H-SM  !

Fodder A S-1 NW/304* 1.9 mi. Pole NE corner Dixie Direct Rad ia t ion Q Highway and Post Road S-2 NNW/333* 1.5 mi. Pole NW corner Trombley Direct Radiation 0 Road and Swan View Road S-3 N/6* ' 2.2 mi. Pole on S side Massarant Direct Radiation Q

- 2 Poles W of Chinavarre S-4 NNE/25' 6.3 mi. Pointe Mouillee - W. Direct Radiation Q Jef ferson and Carapau Road, Pole on SE corner of Bridge S-5 NNE/33' 6.1 mi . Pointe Mouillee Game Area Direct Radiaion Q

- Field Of fice, Pole near tree north area of parking l ot P Olndicates Control Location APPROVAL- A 3.0-2 7 4 DATE:, /Iedf 1

  • Pega 37 .

TABLE G2.1

~

TABLE 3.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Meteorological Station Sector / Azimuth Distance from Media Frequency Number Direction

  • Reactor (Approx) Description 5-6 N/357' 4.1 mi. Labo and Dixie Highway - Direct Radiaion Q Pole on SW corner with light S-7 NNW/338' 4.4 mi. Labo and Brandon - Pole Direct Radiation Q on SE corner near RR S-8 NW/318' 3.9 mi. Pole NW corner Newport Direct Radiation Q and Brandon Roads S-9 WNW/282* 4.8 mi. Pole on SE of War and Direct Radiation Q Post Roads S-10 W/273* 5.2 mi. Pole on NE corner Nadeau Direct Radiation Q and Laprad near mobile home park S-11 WSW/245' 4.8 mi. Pole on NW corner Mentel Direct Radiation Q and Hurd S-12 SW/234' 5.0 mi. Pole in parking lot of Direct Radiation Q Department Natural Re-sources Office Boiling -

Sterling State Park S-13 WSs/253* 2.6 mi. Pole S side Williams Road Direct Radiation Q

- 8 Poles W of Dixie Rwy.

(Special Area)

S-14 WSW/237' 2.7 mi. Pole N side of Pearl at Direct Radiation Q Parkview - Woodland Beach (populated area)

S-15 SSE/168* 1.2 mi. Pole N side of Point Aux Direct Radiation Q Peaux 2 Poles W of Long (site boundary)

S-16 SSW/193* 1.1 mi. Pole S side of Point Aux Direct Radiation Q Peaux - 1 Pole W of Huron next to vent pipe (site boundary)

S-17 SW/222* 1.2 mi. Fermi gate along Point Aux Direct Radiation Q Peaux Road - on fence post '

W of gate (site boundary) .

3.0-3 APPROVAL:

ODCM, Fermi-2 DATE: (ado /14 i

Page 38 e

TABLE G2.1 TABLE 3.0-1 Radiological Environmental Monitoring Program Fermi 2

-}

Sample Locations and Associated Media Meteorological Stction Sector / Azimuth Distance from Numb 7r Direction _R,eactor (Approx) Description Media Frecuency S WSW/249' 1.4 mi. Pole on Toll Road - 13 Direct Radiation Q Poles S of Fermi Drive 5-19 W5W/258' 3.1 mi. Pole on Toll Road 6 Poles Direct Radiation 0 S of Fermi Drive S-20 SW/223' 7.0 mi. Pole NE corner McMillan Direct Radiation Q and East Front Street (Special Area)

S-21* FW/227* 10.6 mi. Pole SE corner of Mortar Direct Radiation Q Creek and Laplaisance S-22* WSW/237* 10.3 mi. Pole E side of S. Dixie, Direct Radiation Q 1 Pole S of Albain S-23 WSW/247' 7.8 mi. Pole Custer (St. Mary's) Direct Radiation Q Park corner of N Custer and Dixie (Monroe St.) #1k (N side, next to river) Nd$

(Special Area)

S-24* WSW/254* 8.9 mi. Pole Milton " Pat" Munson Direct Radiation Q Recreational Rer>erve -

N Custer Road (Control)

S-25 WNW/296* 10.3 mi. Pole corner Stony Creek Direct Radiation Q and Finzel Roads S-26 NW/318' 9.3 mi. Pole W side Grafton Road, Direct Radiation O 1 Pole N of Ash /Grafton intersection 5-27 NNW/339' 9.7 mi. -

Pole E side of Port Creek, Direct Radiation Q 1 Pole S of Will-Carlton Road S-28 N/360* 7.0 mi. Pole on S side of S. Huron Direct Radiation Q River Drive across from Pace St. (Special Area)

S-29 N/360* 9.2 mi. Pole NE corner of Gibraltar Direct Radiation Q and Cahill Roads CIndicates Control Location APPROVAL:  %

ODCM, Fermi-2 3.0-4 DATE: l-[/o/$f

_ - . ..~

Pcg= 39 TABLE G2.1 f TABLE 3.0-1 g,

Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Meteorological Station Sector / Azimuth Distance from Number Direction. Reactor (Approx) Description Media Frecuene 1-30 NNE/23' 9.9 mi. Pole S corner of Adams Direct Radiation Q and Gibraltar (across from Humbug Marina) 8 S 0.9 mi. Point Aux Peaux, 100-300f t . Sediment SA offshore sighting directly to land based water tower 9 E 0.2 mi. Fermi-2 discharge, approx. Sediment SA 200 f t. offshore 10 NE 1.1 mi. Estral Beach, approx. 200ft. Sediment SA offshore sighting directly to land based windmill 11* NNE 9.5 mi. Celeron Island Fish SA 12 SSE 0.4 mi. Fermi Unit 1 Raw Lake Water Surface Water M Intake Structure a

13 S 1.2 mi. Monroe Water Station Drinking Water M N side of Pointe Aux Peaux 1/2 block W of Long Rd.

14* NE 13 mi. DECO's Trenton Channel Surface Water M Power Plant Intake Structure (Screenhouse #2) 15* NNE 20 mi. Detroit (Allen Park) Water Drinking Water M Station 14700 Moran Rd.

- 16 E 0.4 mi. Fermi-2 discharge (approx. Fish SA 1200 ft. offshore) 17 SW l.0 mi. Corner of Erie Street and Radioiodine W Point Aux Peaux Roads Particulates W 18 WSW 2.0 mi. Residence Crass M-S?

4352 Pointe Aux Peaux In lieu of milk 19 WNW/289* 1.7 mi. Residence Milk M-S!

6494 N. Dixie Hwy. Direct Radiation Q 20 NW 5.7 mi. Resume Farm Milk M-S?

2705 East Labo  ; Fodder A i 1

  • Indicates Control Location 3.0-5 APPROVAL: 7 ODCM, Fermi-2 DATE: M

Page 40 e

TABLE G2.1 TABLE 3.0-1 Radiclogical Environmental Monitoring Program, Fermi 2

{

Sample Locations and Associated Media Meteorological Station Sector / Azimuth Distance from Numb1 r_ Direction Reactor (Approx) Description Media Frequency 22 . W 0.6 mi. Outlet Fermi-2 Storm Drains Sediment SA 31 NW -4.5 mi. Yoas Farm Milk M-SM 3239 Newport Rd. Fodder A 32 NNE 4.0 mi. Roland Farm Milk M-SM 9501 Turnpike Hwy. Fodder A W1 S 0.4 mi. Approx. 100 ft. W of Groundwa ter On flow Lake Erie, S end of reversal former plant clubhouse site W2 SSW 1.0 mi. 4 f t. S of Pointe Aux Groundwater On flow Peaux (PAP) Rd. fence, reversal 427 ft. W of where PAP crosses over Stoney Point's western dike W3 SW 1.0 mi. 143 f t . W of PAP Rd . Groundwater On flor gate, 62 f t. N of PAP revers al Rd. fence W4 WNW 0.6 mi. 42 f t . N o f Lang t on Rd. , Ground wa ter On flow 8 ft. E of Toll Rd. fence reversal L1 SSE/147* 0.17 S.E. Corner Protected Direct Radiation Q Area Fence (PAF)

L2 SE/139' O.16 Midway along OBA - PAF Direct Radiation Q L3 SE/133' O.15 Midway between OBA Direct Radiation Q and Shield Wall - PAF L4 SE/125' O.15 Midway along Shield Direct Radiation Q Wall - PAF L5 ESE/114' O.14 Midway between Shield Wall Direct Radiation Q and Aux. Boilers - PAF L6 E/101* 0.14 Opposite OSSB door - PAF Direct Radiation. Q L7 E/84* 0.16 N.E. Corner - PAF L8 ENE/71* 0.2 NE side barge slip - Direct Radiation 0 on fence ODCM, Fermi-2 3.0-6 APPROVAL: J a/

DATE: $'f/O lW

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ODCH, Fermi-2 3.0-9 APPROVAL: -

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Page 44 TABLE G2.1 (DFFSITEDOSECALCULATIONMANUALCHANGEREQUEST) f/U3 N) f , (DcF)oy Change Requested by: William V. Lioten Date: May 12, 1986 %

.- j Nuclear Production /Radchem lL ODGVn %d) h/ y

. . h partment/Section:

Applicable

, . Section(s): 2.5 Change (Attach Markups to the CDCM, each page shall be numbered and

. provided with an approval ind date box): Delete last sentence of text.

Reason for Change /.7ustification (Include sufficiently detailed information to totally support the rationale for the change and appropriate analyses or evaluations justifying the change. Attach additional abeets if necessary):

This change is to provide consistenev between the text and n gur. 2 . 5 .1.

Technical iteview Performed by: Date: / M The Radchen Engineer has determined, as evidenced by his signature below, that this change does not result in a reducti a of the accuracy or reliability of dose calculations or s tpoi determinations.

Approved by: -- Date: 4 ,

Radchen Engineer / i Recommended by: y - N Date: [ O

- OSRO Chairman

. Approved by: #m N Date: $0 8 Assistant Manager-Ruclear Production

~

The Assistant Manager-1tuelear Production shall also approve 4ach page of the attached markups of the OOCN. ARMS.

OTc T m o p s ORMATION SYSTEMS m _,y Paar REv- at pis "2885 JllN 171986 CONTROLLED pis M@d

._Ap,,,oy m m Laaisut_a

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Page 45 TABLE G2.1 ,

l - ...

2.5 GASE0L5 RA>fASTE EFTLUDG SYSTD4 APC YCNTILATION EXHAtJS1 TRCATHENT SYSTD_4 l f

~

Figure 2.5-1 is a schematic of the Caseous Radwaste Effluent System showing the release points to unrestr!cted areas. The Ventilation Exhaust Treatment Systern is also presented in Figure 2.5-1. --7.; ',';c.tihtic . SM=t ? ::t r.t Sy t: weht: Of %."" filt::: frat;1hd ir, tt.: ::;rvi:: ";11dn; Wntih'th ,

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, 0004, Femi-2 2.0-72 h t 267M/0051W. 05/24/84 g

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- C. Ralph Sylvia Group %ce President Toi.t me 6400 North Disse Highway l n Newport, Mechigan 48166 pia sa6-4is August 28, 1986 VP-86-0125 PRIORITY RCUTING rst e 3nd i

, NF in -

Mr. James G. Keppler .

WIS NL Regional Administrator Region III Q/ Q p Pna U. S. Nuclear Regulatory Commission FILE /% -

799 Roosevelt Road Glen Ellyn, Illinois 60137

Dear Mr. Keppler:

Reference:

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

Subject:

Semi-Annual Radiolooical Effluent Release Renort The Semi-Annual Ef fluent Release Repor t 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, 1986.

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 Mr. Lewis Bregni at (313) 586-5313.

Sincerely, d[

Attachment cc: W. G. Rogers Director of Inspection and Enforcement M. D. Lynch USNRC Document Control Desk G. C. Uright Washington, D. C. 20555

/

$b ip SEP 2 566

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