Text

Semiannual Radioactive Effluent Release Rept Jan-June 1991
	ML20082L999
Person / Time
Site:	River Bend
Issue date:	06/30/1991
From:	Cargill E, Fantacci C; GULF STATES UTILITIES CO.
To:	;
Shared Package
ML20082L993	List: ML20082L999; ML20082M006; RBG-35-497, Forwards Semiannual Radioactive Effluent Release Rept for Jan-Jun 1991 & Rev 4 to RWS-0204, Radwaste Processing Control Program;
References
	NUDOCS 9109040504
	Download: ML20082L999 (34)
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.

RIVER BEND STATION, UNIT 1 i

f SEM1 ANNUAL RADIDACTIVE EFF UENT REl. EASE REPORT ADDENDUM REPORT PERIOD: January 1, 1991 Through June 30, 1991 i

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REVIEWED BY LY MnE LPLE FaAtacci, Radiologici.1 Engineering Supervisor i

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I APPROVED BY

~E.M.Carg1y. Director-Ratliol69ic61 Programs

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TABLE OF CONTENTS PAGE INTRODUCTION 3

11 SUPPLEMENTAL INFORMATION 2

A.

REGULATORY-LIMITS 2

B.-

MAXIMUM PERMISSIDLE CONCENTRATIONS 6

C.

AVERAGE ENERGY 6

D..

MEASUREMENTS AND APPR0XIMATIONS OF 6

TOTAL RADIDACTIVITY 6

E.

BATCH RELEASES 8

r F.

ABNORMAL RELEASES 9

G.

ESTIMATE OF TOTAL -ERROR 10 111.

GASEOUS EFFLUENTS

SUMMARY

INFORMATION 11 IV.-

LIQUID EFFLUENTS

SUMMARY

-INFORMA110N 11

~V.

SOLID WASTE-11 VI.

RADIOLOGICAL 1MPACT ON MAN 11 VII.

METEOROLOGICAL DATA 11 Vill.

RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERABILITY-11 IX.

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERABILITY 12 l

l-X.

LIQUID HOLD.UP TANKS 12 XI.

RAD 10 LOGICAL ENVIRONMENTAL MONITORING 12 XII.

LAND USE CENSUS 12 XIll.

OFFSITE DOSE CALCULATION MANUAL (ODCM)-

12

-XIV.

MAJOR CHANGES T0-RADI0ACilVE LIQUID.

GASE0US AND SOLID WASTE TREATMENT SYSTEMS 12 t

XV.

PROCESS CONTROL PROGRAM (PCP) 12 P

l P

i

I PAGE XVI.

TABLES l

TABLE 1 RADI0 ACTIVE GASEOUS WASTE j

SAMPLING AND ANALYSIS PROGRAM 14 i

e TABLE 2 RADIDACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 15 TABLE 3 GASEOUS EFFLUENTS - SUMMATION j

OF ALL RELEASES 16

}

~ TABLE 4

' GASEOUS EFFLUENTS - CONDITIONALLY ELEVATED RELEASES.

18 j

J TABLE 5 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 21 l

r TABLE 6' LIQUID EFFLUENTS - SUMMATION

.}

OF ALL-RELEASES 24 j

TABLE 7 SOLID WASTE AND 1RRADIATED FUEL SHIPMENTS 29 i :

Process Control Program (PCP) k I

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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT FACILITY:

River Bend Station, Unit 1 LICEhSEE:

Gulf States Utilities REPORT PERIOD: January 1, 1991 Through June 30, 1991 1.

INTRODUCTION Enclosed is the Semiannual Radioactive Effluent Release Report for the period of January 1, 1991 through June 30, 1991. This report is submitted in accordance with Technical Specification 6.9.1.8 of Appendix A to River Bend Station (RBS) License Number NPF-47.

SUMMARY

Gaseous release totals were a maximum of 6.74% of the quarterly whole body and critical organ technical specification limits.

Liquid releases were a maximum of 5.92% of their quarterly whole body and critical organ technical specification limits, l

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,SUfPIRIENTAl _1NFORtlAT10N f

11.

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A.

Regulatory Limits i

f 1.

10CTR20 Limits n.

Finnion and Activation Onwes In accordance with Tochi$ical Specification 3.11.2.1, tho

}

dose rat o due to nobin gases released in gaseous.

effluents from the site to areas at and beyond the S ITF.

BOUNDARY shall be limited to less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrer:s/yr to the akin:

=

Da rate to the total body Jn mremn/yr DRTB i

n 7

3.15 x 10 I K (X/Q) Qg 5 500 mrena./yr

=

g

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(

i=1

_a nd.

[

i DR w

D se rate to the skin in mrems/yr j

Mn u

7 g + 1.1H )(X/Q) Qg $ 3000 mrems/yr 3.15 x 10 I

(L

=

g i

i=1

[t (above terms defined in RBS ODCM).

t i,

i b.

Rjul,iolodisley and part iculat es In accordance with Technical Specification 3.11.2.1, tho i

dose rat o due to iodine 131, lodine-133, t ritium, and all

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radionuclideu.in particulate fern with half-lives greater

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than 6 days released in= gaseous cffluents'from. the i,ito

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to areau at and.beyond the SITE BOUNDARY shall bn limited to less than or equal to 1500 mrems/yr to any organi j

Done rate t'o the organ t

for the age DR

=

g3pp group of interest from iodines, tritium, i

and 8 day particulates via the inhalation

[

pathway in mrems/yr i

t t

n I

P3 (X/Q)D 9 5 1500 mrems/yr j

=

1 i=1 l

1 (above terms defined in HBS ODCM)

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....~, -. -. - - -... -..,.. -, _,,~,..-

-.-- -. -,-. - -..~...- - _, -,

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Idquid Effluents In accordance with Technical Specification 3.11.1.1, the concentration of radioactivo material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specifled in 10CTR20 Appendix it, Table 11, Column 2 for radionuclides other tian dissolved and entrained noble ganes. For dissolved or enttained noble

gases, the concentration shall be limited to 2 x 10 microct,rion/ml total activity.

2.

10CTR50, Appendix 1 1Amits a.

Tission and Act tvation Ganes In accordance with Technical Specification 3.11.2.2, tho air dosn due to noble gases released in gaseous offluonts to areas at or beyond the SITE DOUNDARY shall be limited to:

The gamma air dose from radioactivo nobic D

=

G

-Air gases in mrad g(5[d)Q 5 5 mrads/qtr I

H

=-

3 5_10 mrada/yr gg D,gg,

=

Beta air ~ dorno from radioactivo noble 3

gases in mrad n

g(M)Q 5 10 mrads/qtr 1-N

=

3

$ 20 mrads/yr pg (above terma defined in RBS-0DCH) b.

Radiciodines and_ Particulates In accordanco with Ti chnical Specification 3.11.2.3, t he doso to a_ MEMBER OF TiiE PUBLIC from lodino-131,-

todino 133,_ and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous offluents releases _to areas at and beyond the SITE BOUNDARY shall be limited to:

Dose in mrem to the organ _h) of _ a D

m I&SDPt specified age group from radiofodines.

tritium, and 8 day particulates via the pathway of interest 3

F

.- k_ i 8

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r P

+

n.

m-3.H x 10'8 I R

(X/Q)g Q

j

=

g 3

i=1 r

I aJ1 Ar d

3 I

3.17 x 10 I

R (D/Q) Q l

=

g g

i=1 f

. anji D-

=

Doso in mrem to the organ (t) of a specified f

age group from radiolodines, tritium, and 8 day particulates from all pathways t

a t

I D

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- "**!9

=

I&8DPt z=1

$ 15 mrems/yr

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(above terms defined RBS ODCM)-

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c.

I.iquid Effluents In accordance with Technical Specification 3.11.1.2, the dose or dose commitment to a MF6fBEk 0F TIIE PUBLIC from.

3 adioactivo 'materioln -in 1Iquid effluents released-to UNRESTRICTED MEAS nhall be limited to

.i A At Q D.t

=

lt g

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+

w

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D

=I 9

TOTALi it=

jm1 4

[-

'k

!)TOTALT -

organ (t) due to r

all releases during the desired time interval in mrom

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g y:

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,y, and D

5 1.5 mrems/qtr TOTAL-

-Total _ Body 3 trems/yr-0 5 mrems/qtr TOTAL Any Organ 10 mrems/yr

-(above te

. ined in 1C ODCM) 3.

40CFR190 Limits In accordance with Technical Specification 3.11.4, the ar.nual (calendar year) dose or dose commitment to any MEMBER _0F TllE PUBLIC, due to releases of radioactivity and_ to radiation from uranium fuel cycle sources, shall be-limited to:

1 25 mrems,to the total body or any organ (except-the-

-j 1

thyroid):

75 mrems to the thyroid 1

4.- Misec11aneous Limits-1 a.

Ventilation F- % ust Truatment System p'

In accordant, (th Technical Specification 3.11.2 5, the VENTILATION---EX11AUST' TREATMENT SYSTEM 'shall,he used to, reduce: radioactive materials in gaseous waste prior-to r-

__ +

l their -discharge when the projected dases, due to gaseous-l effluent -releases to areas at-and _beyond tha SITE

!=

BOUNDARY would exceed 0.3 mrom to any organ in a 31-day.

period.

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'b.

-Liquid Radwaste Treatment System

.In accordance with Technical Specification 3.11.1.3, _the liquid radwaste treatment system shall be used to recuce the radioactive materials in liquid wastes prior-to their -

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discharge when the projected : doses,'due to the liquid

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effluent, to UNRESTRICTED AREAS would exceed 0.06 mrem to-the total.' body or=_0.2 mrem-to any organ.in a 31 day period.

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3 B.

Maximum Permissible Concentrations 1.

Gaseous Releases The RBS Radiological Effluents Technical Specifications (RETS) for gaseous releases are based on the dose rate restrictions of 10CFR20, rather than the Maximum Permissible

--Concentrations (MPC) listed in-10CFR20 Appendix B Table 11, Column 1.

2.

Liquid Releases The Maximum Permissible Concentration of radioactive materials in liquid effluents is limited by 10CFR20, Appendix B.

Table.II, Column 2.

The MPC chosen is the most conservative value (i.e., the lowest) of either the soluble or insoluble MPC for each radionclide.

C.

Average Energy Period E-Bar-(Mev/ dis) 01/01/91 - 06/30/91 1.60 D.

Measurements and Approximations of Total Radioactivity 1.

Gaseous Effluents a.

Fission and A-tivation Gases Periodic grab samples-are obtained from the Main Plant Exhaust Duct. Fuel Building Exhaust Vent and Radwaste Building Exhaust Vent.

These samples are analyzed utilizing high resolution germanium detectors coupled to computerized pulse height analyzers.

The sampling and l

analysis frequencies are described in Table 1.

Sampling L

and analysis of these effluent' streams provide noble--gas radionuclide relative abundances which can then be applied to the noble _ gas gross cctivity and gross activity release rate to obtain nuclide specific-activities and release rates.

The noble gas-gross activity _ released within a speci f.ic time period is determined by integrating the stack. monitor release rate over the considered _ time period.

If no activity was detected between stack grab samples and significant increase in hourly averages were recorded, the nuclide L

relative abundances of the last sample which indicated l-the presence of activity was utilized to obtain nuclide.

j specific activities.

Correction factors for the monitors l

are derived and applied for each sampling period whenever noble gas radionuclides are detected in the effluent stream.

I 6

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4 b.

Particulates and Iodines Particulates and iodines are continuously sampled from each of the three release points utilizing a particulate filter and charcoal cartridge in line with a saniple pump (stack' monitor pump).

These filters and charcoal cartridges are removed _and analyzed in accordance with the frequencies specified--in Table 1.

Analysis-is performed to identi fy and quantify radionuclides utilizing high resolution germanium detectors coupled ~to computerized pulse height analyzers. Given the nuclide-specific activity concentrations, process flow rate, and time which the_ sample covered; the nuclide specific activity released to the environment can ;be obtained.

Due to the continuous sampling process it is assumed that the radioactive material i s' released to the environment at a constant rate within the sampling period.

Sr-89 and Sr-90 are quantitatively analyzed by counting the digested filter precipitate with a ys flow proportional counter.

Gross alpha analysis is performed usino a zinc sulfide scintillation counter.

c.

Tritium Tritium ~ grab samples are obtained from the three release

'poiits at the specified frequencies listed in Table 1 utilizing an ice bath condensation collection method.

The collected sample is then analyzed utilizing a Liquid Scintillation Counter. -Given the tritium concentratSn, process flow rate, t time period for which the le v

l is _ obtained, -the tritium activity released to the l

environment can be determined. Due to the frequency of

sampling, it. is assumed that the tritium is released to the environment at a constant rate within the time period for which the sample is obtaired.

2.

Liquid Effluents Representative. grab samples are obtained from the appropriate sample recovery tank and analyzed prior to' release of -the tank in accordance with the frequencies listed in Table 2.

Analysis for' gamma emitting nuclides (including dissolved and H

entrained noble gases) is performed utilizing a high i

resolution germanium detector coupled to.a computerized pulse hcight analyzer.

Tri tium -- concentration is determined H

utilizing a Liquid Scintillation Counter.

Sr_-89 and Sr-90 are quantitatively analyzed by counting the precipitate with a gas flow proportional counter.

Fe-55 is -counted. with a Liquid Scintillation Counter after digestion of the iron.

Gross alpha analysis is performed using a zinc sulfide scintillation counter.

Given the nuclide specific activity concentration and total volume of the tank that was released, the activity of each nuclide released to the environment can be determined.

7 f

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E.

Batch Releases 1.

Liquid 1st Quarter 1991 a.

Number of batch releases 67 b.

Total time period for batch re ases 442.5 hr c.

Maximum time period for batch rileases 7.85 hr d.

Average time period for batch releases 6.76 hr e.

Minimum time period for a batch release 0.32 hr f.

Average stream flow during periods of 3

release of effluent into a flowing stream : 971,667 ft /sec 2nd Quarter 1991 a.

Number of batch releases 50 b.

Total time period for batch releases

358.8 he c.

Maximum time period for batch releases 17.18 hr d.

Average time period 'or batch releases 7.18 hr e.

Minimum time period for a batch release 0.88 hr f.

Average stream flow during periods of 3

release of effluent into a flowing stream 919,000 ft /sec 2.

Gaseous All gaseous releases to River Bend Station are considered continuous releases.

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F.

Abnormal Releases 1.

Liquid l

{

1st Ouarter 1991 i

a, tumber of releases 0

b.

Total activity released

- 0 Curies 2nd Ouarter 1991 a.

Bumber of releases

0 b.

Total activity released 0 Curies

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.l 2.

Gaseous i

ist Ouarter 1991 a,

bumber of-releases-0 b.

. Total activity released

O Curies 2nd Quarter 1991 a.

Number of releases

0 b.

Total Activity released

0 Curies During the reporting period January 1,1991.through June 30, 1991, RBS

-i experienced no abnormal releases.

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G.

Estimate of Total Error 1.

Liquid The maximum error associated with sample collection, laboratory analysis, and discharge volume are collectively estimated to be:

Fission and Activation Products : 1 14.2%

Tritium : 1 14.2%

Dissolved and Entrained Noble Gases : 1 14.2%

Gross Alpha Radioactivity : 1 14.2%

2.

Gaseous The maximum errors (not including sample line loss) associated with r

sample flow, process flow, sample collection, monitor accuracy and laboratory analysis are collectively estimated to be:

Fission and Activation Gases : 1 37.0%

Iodines : 1 18.6%

Particulates : 1 18.6%

Tritium - 1 18.2%

3.

Deteroination of Total Error The total error (i.e., collective error due to sample collecticn, laboratory analysis, sample flow, process flow, monitor accuracy, etc.) is calculated using the following equation:

/(E)2

+ (E ) +... (E )

ET s

3 2

where:

=

t tal error ET individual errors due to sampic collection, Es E2... E

=

y laboratory analysis, sample flow,. process flow, monitor accuracy, etc.

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T I

r I I I.- GASE0US EFFLUENTS-

SUMMARY

INFORMATION

-Refer to Tables 3, 4 and 5 for Sumnation of All Releases and Nuclides Released, respectively.

It should be noted that an entry of "0. 00E + 00.Ci or uC1/sec in this section does not indicate the I

absence of a radionuclide; but, rather, indicates that the

-l concentration of the particular radionuclide was below the Lower l

~ Limit of Detection (LLD) as listed in Table 1.

t IV.

LIQUID EFFLUENTS

SUMMARY

INFORMATION j

Refer to Table 6 for Summation of All Releases and Nuclides Released.

It should be noted that an entry of "0.00E+00" Ci or uCi/ml in this

-section does not indicate the-absence of a. radionuclide; but, rather, i

V indicates; that the concentration of the particular radionuclide was l

below the Lower Limit of Detection (LLD) as listed in Table 2.

V.

SOLID WASTE Refer to Table 7.

VI.

RADIOLOGICAL IMPACT ON MAN i

l This information will be provided in the end-of-year report as described -in-Technical Specification 6.9.1.8.

VII, METEOROLOGICAL DATA This' information will be provided -in the end-of-year report as described in Technical Specification 6.9.1.8, VIII.-RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERABILITY The minimum number-of channels required to be OPERACLE_as described

)

.in Table 3.3.7.10-1 _of Technical Specification 3.3.7.10 were, if-t inoperable at any time in the period 01/01/91 through- 06/30/91, restored to-operable status within the required time.

Reporting of-

.these inoperable channels in this report is, therefore, not required.

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11-l --

i IX.

RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATIC;4 OPERABILITY f

The minimum -number of channels required to be OPERABLE as described in Table 3.3.7.11-1-of Technical.-Specification 3.3.7.11 were, if i

inoperable at any time in-the period 01/01/91 through 06/30/91, restored to operable status within the required time.

Reporting of these inoperable channels in this report is, therefore, not required.

X.

LIQUID HOLD UP TANKS The maximum quantity-of radioactive material, excluding tritium and dissolved or entrained noble gases, contained in any unprotected outdoor tank during the period of 01/01/91 through 06/30/91 was less than or equal to the 10 curie limit as required by Technical i

Specification 3.11.1.4.

X I.-

RADIOLOGICAL ENVIRONMENTAL MONITORING l

f There were no changes in sampling locations for the Radiological i

Environmental Monitoring Program (REMP) during the reporting period 01/01/91 through 06/30/91.

i t

XII.

LAND USE CENSUS This information will be presented in the end-of-year report. The i

-Lano-Use Census results will be available in September, 1991.

U II. 0FFSITE DOSE CALCULATION MANUAL (0DCM)

There were no changes to the ODCM for the period of 01/01/91 through

.06/30/91.

i L

XIV. MAJOR-CHANGES TO 'RADI0 ACTIVE-LIQUID, GASE0US, AND SOLID WASTE TREATMENT SYSTEMS i

There were no major changes to the radioactive liquid, gaseous', and solid waste. treatment systems for the period of 01/01/91 through 06/30/91.

i

'XV.

PROCESS CONTROL PROGRAM (PCP)

.[

The RBS Process Control Program (PCP) was revised in April 1991.

This revision incorporated the following char.ges:

a.

Committing to a compressive strength of 500 p.s.i. for solidified l

materials as outlined in the USNRC Branch Technical Position on low level radioactive waste forms.

12 l

+

3 t

1 I

b.

Changing the primary mode of processing spent radioactive resins j

from solidification to dewatering.

This included the j

incorporation -of the applicable references for the dewatering system.

i c,

. Incorporating USNRC Generic Letter 91-02 guidance outlining the reporting of mishaps involving low level radioactive waste forms

[

produced by River Bend Station.

r d.

Minor editorial changes, j is the revised PCP.

Changes are denoted with change bars in the margins.

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TABLE 1 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Gaseous Release Type Samplang Analysis Type of Detection (LLD)

Freauency Frequency Activity Analysis (uti/ml A.

Main Plant M

M Principal Gamma Emitters 1x10 #

Exhaust Duct Grab Sample 6-~~-~~~'

H-3 1x10-B.

Fuel Building M

M Principal Gama Emitters 1x10 Ventilation Grab Sample 6-~~~---

Exhaust Duct H-3 1x10-

-4 C.

Radwaste Building M

M Principal Gamma i.nitters 1x10 Ventilation Grab Sample Exhaust Duct

-12 D.

All Release Types Continuous W

I-131 1x10 as listed in A, B, Charcoal

eg------

C above.

Sample I-133 1x10-1

[

Continuous W

Principal Gama Emitters 1x10-11 Particulate (I-131,Others)

Sample Continuous M

Gross Alpha 1x10-II Composite Particulate Sample Continuous Q

SR-89, SR-90 1x10-II Composite Particulate Samt,le

-0 Continuous Noble Gas Noble Gases 1x10 Monitor Gross Beta or Gama W = At least once per 7 days M = At least once per 31 days Q = At least once per 92 days t

_ _ _,.,....., _,.. ~,

~...

1 TABLE E RADIDACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)

Type Frequency Frequency Analysis (ufi/ml)

A.

Batch Waste P

P Principal Gamma 5x10-7 Release Each Batch Each Batch Emitters; except (Liquid for Ce-144 5x10~6 Radwaste Recovery

-6 Sample 1-131 1x10 Tanks

-5 P

M Dissolved and 1x10 One Batch /M Entrained Gases (Gamma Emitters)

P M

H-3 1x10-5 Each Batch Composite Gross Alpha 1x10-7 P

Q Sr-89, Sr-90 5x10-8 Each Batch Composite Fe-55 1x10~0 P = Prior to each radioactive release M = At least once per 31 days Q = At least once per 92 days 15

TABLE 3 Effluent and W ste Disposal Semi-Annual Report 1991 Year Gaseous Effluents - Sunnation of All Releases 1/2 Quarters l

l l

1 l

Est.

l l

l Unit l

Quarter l Quarter l Total l

l l

1 l

2 l

Error, % l A.

Noble Gases I

I I

I l

l 1.

Total release Ci l 1.97F402 l 1.41E+02 l 3.70E+01 l

l l

2.

Average release rate

! uCi/sec l 2.50E+01 l 1.79E+01 l l

for period l

l l

l 3.

Percent of technical l

l 6.74E+00 l 5.36E+00 l l

specification limit (1) l B.

Iodines-l l

l-131 l

l l

1.

Total I-131 and 1-133 l Ci l 1.16E-02 l 1.03E-02 l 1.86E+01 l

l l

l-133 l

l l

l Ci l 1.16E-01 l 8.29E-02 l 1.86E+01 l

l l

1-131 l

~ l l

2.

Average release rate

! uCi l 1.47E-03 l 1.31E-03_j l

-for period

! sec l

l l

I-133 l 1.4_7E-02 l 1.05E-02 l l

l l

l 3.

1-131 + I-133 contribu-l l

l l

l-tion percent of techni-l l 5.25E+00 l 4.59E+00 l l

cal specification limit l

l l

l C.

Particulates l

l I

l l

l

-1.

Particulates with half-l Ci l

l l

l lives of > 8 days l

l 1.28E-03 l (2) l 1.86E+01 l

l l

2. ' Average release rate l uCi/sec l

l l

l far period l

l 1.62E-04 l (2) l l

I I

l l

l 3.

Percent of technical l

l l

specification limit l

l 5.15E-02 l (2) l i

l 4.

Gross alpha l

Ci l

l l

l radioactivity l

l 0.00E+00 l 0.00E+00 l l

16 l

~

l' l

l l

l

[st.

l l

Unit l Quarter l Qtiarter i Total l

l l

l 1

l 2

i Error, i l 0.

Tri tium l

l l

]

I l

l 1.

Total release l

Ci l 3.55E+00 l 3.81E+00 l 1.82E401 l

?

1 l

l t

t l

l l

l 2.

Average release rate

!uCi/sec

!4.51E-01!4.83E-01!

j for period l

l l

^l l

l l

3.

Percent of technical l

T l 4.93E-03 l 5.20E-03 i j

specification limit l

l l

l (1) Most limiting of Gamma airdose limit of 5 mrads/qtr. or Beta airdose of 10 mrads/qtr. (T.S.3.11.2.2.a)

(2) Not available for submission at this time, supplemental report to follow.

17

TABLE 4 Effluent and Waste Disposal Semi-Annual Report 1991 Year Gaseous Effluents - Conditionally Elevated Releases 1/2 Quarters Continuous Mode Batch Mode l~

l l

l Nuclides Released l

Unit l Quarter 1 l QJarter 2 l Quarter 1 l Quarter 2 l 1.

Fission Gases I

I I

l Argon-41 Ci l 0.00E+00 l 0.00E+00 N/A l

N/A l'

l l

l Krypton-85m j

Ci l 4.14E-01 l 2.61E+00 l

N/A l

l l

l 1

l l

Krypton-85 l

Ci j 0.00E+00

! 0.00E+00 l

N/A l

l 1

l l

l Krypton-87 i

Ci l 2.47E+00 l 0.00E+00 l

N/A l

'l l

l I

l l

-l-Krypton-88 i

Ci j 0.00E+00 l 0.00E+00 l

N/A l

N/A j

l l

l i

Xenon-133m l

Ci j 0.00E+00 1 0.00E+00 l

N/A l

N/A 1

l l

Xenon-133 l

Ci

! 2.76E+01 l 5.62E+00 l

N/A l

l l

Xenon-135m l

Ci l 1.64E+01 l 6.68E+00 l

N/A l

l l

Xenon-135 l

Ci l 1.71E+01 l 1.15E+01 l

N/A l

1 l

l l

Xenon-137 l

Ci l 0.00E+00 l 0.00E+00 l

N/A l

N/A j

l l

Xenon-138 i

Ci l 0.00E+00 ! 4.71E+00 l

N/A l

l l

unidentified l

Ci l

N/A l

N/A i

N/A l

l l

i l

l l

l Total for period l

Ci l 6.40E+01 j 3.11E+01 l

N/A l

2.

Gaseous Todines l

l l

l Iodine-131 l

Ci l 1.15E-02 l 1.01E-02 l

N/A l

l l

l lodine-132 i

Ci l 0.00E+00 l 0.00E+00 l

N/A l

l

-l l

l l

l Iodine-133 l

Ci l 1.16E-01 l 8.23E-02 l

N/A l

N/A-l l

I l

l l

l Iodine-134 l

Ci l 0.00E+00 l 0.00E+00 j

N/A l

l l

l j

Iodine-135 l

Ci l 0.00E+00 l 0.00E+00 l

N/A l

l l

Total Ci l 1.28E-01

! 9.24E-02 l

N/A l

N/A i

18

Continuous Mode Batch Mode l

l l

I I

I-

. I j

Nuclides Released

! Unit

! Quarter 1 1 Quarter 2 ! Quarter 1 l Quarter 2 l

'3.-

Particulates l-l 1

I l

l l

Strontium-89 l

Ci j-3.46E-04 l

(1) l N/A l

N/A l

l.

I i

i i

l Strontir.-90 Ci l 2.01E-06 (1) l N/A l

N/A l

I I

l 1'

j Cesium-134 Ci

! 0.00E+00 l-0.00E+00 l

N/A l

N/A j

-l l

l I

l l

Ci-

' O.00E+00 l 0.00E+00 l

N/A i

N/A l

j' Cesium-137 l

l

-i

-Barium-140 Ci 8.92E-04 l 1.24E-03 l

N/A N/A l

l I

i l

I i

l Lanthanum-140 Ci

! 0.00E+00- l 0.00E+00 i

N/A l-

.N/A I

1 l

l l

l j

Cobalt-60:

Ci i 0.00E+00 l 0.00E+00

)

N/A j

N/A I.

I l

1 I --

O.00E+00 l

N/A N/A l

l

-Chromium-51 l

Ci

'-0.00E+00 I

l l-i i

N/A N/A l

l-Zirconium-95 l

Ci-0.00E+00 l.0.00E+00 l

l i

l l

Niobium-95 i

Ci

' O.00E+00 1 0.00E+00 l

N/A l

N/A j

i-l-

-1 I

-l l

l l

l-Zinc l Ci 0.00E+00 l-0.00E+00- l N/A l

N/A l

i l

l 1

l l

l-

-l 1 Iron-59 l

Ci 1 0.00E+00 0.00E+00- !

N/A l

N/A j

j' Manaanese-54

'i l

l l

I' l

Ci l 0.00E+00

-0.00E+00 l

N/A-l N/A l

l l.

l l

l

-l.

.. Iodine-131 l

Ci l 0.00E+00 O.00E+00 N/A l

N/A i

p l-l I

I l

i

l

.. Cerium-141

.i _

Ci l 2.46E-05

4.02E-06' N/A l

N/A j

i l

l l

Ci-l 0.00E+00

! 0.00E400 l

N/A l

"erium-144

-l-i-

i i

i

=!

Cobalt-58'

[ Ci l1.48E-05

!0.00E-00 l

N/A l

N/A j.

-I' i

l l

1 l-

-l l

Silver-110m=

l Ci j 0.00E+00 j 0.00E+00

-l N/A l

N/A l

1 I

I I

l l-

-l--

- Molybdenum l Ci j 0.00E+00

! 0.00E+00 i

N/A l

L i

I i

L-I~

.I unidentified Ci j

N/A l

l I-l l

l l

I Total for period l

Ci l 1.28E-03 l

(1) l N/A l

'N/A l-l_

i-19

Continuous Mode Batch Mode

~

l l

I l

l I

l Nuclides Released l

Unit l Quar _ter 1 l Quarter 2 i Quarter 1 l Quarter 2 j 4.0 Tritium l ~

l l

Hydrogen-3 i

Ci l 2.92E+00 l 3.27E400 l

N/A l

Main Plant Exhaust Duct is considered a conditionally elevated release point.

(1) Not available for submissiori at this time, supplemental report to follov!.

20

.. ~

TABLE 3 Effluent and Waste Disposal Semi-Annual Report 1991 Year Gaseous Effluents - Ground Level Releaser.

1/2 Quarters Continuous Mode Batch Mode I

i l

I I

l l

Nuclides Released i

Unit j Quarter 1 i Quarter 2 l Quarter 1 ! Quarter 2 l 3.

Fission Gases l

I I

l

{

Argon-41 Ci 0.00E+00 l 0.00E+00 i

N/A l

l i

i l

l l

Krypton-85m l

Ci l 0.00E+00 l 0.00E+00 l

N/A l

N/A

]

l l

I I

I

_l Krypton-85 l

Ci l 0.00E+00 l 0.00E+00 l

N/A i

N/A l

l l

I l

l Krypton-87 Ci j 0.00E+00 i 0.00t:+00 l

N/A l

N/A j

I l

l l

Krypton-88 1

Ci j 0.00E+00

! 0,00E+00 i

N/A l

I l

l l

l Xenon-133m l

Ci j 0.00E+00 l 0.00E+00 l

N/A j

N/A l

i j

l l

l 1

Ci l 2.23E+01 l 2.77E+01 l

N/A l

N/A i

Xenon-133 l

l l

l

-Xenon-135m Ci l 1.43E+01 i 1.68E+01 N/A l

N/A l

l l

l 1

l l

l Xenon-135 l

Ci l 9.67E+01

6.54E+01 l

N/A l

l l

1 i

l l

l

-Xenon-137 l

Ci

! 0.00E+00 l 0.00E+00 l

N/A j

N/A l

~

I I

l' l

l Xenon-138 i

Ci

' O.00E+00 ; 0.00E+00 l

N/A l

N/A j

l l

unidentified Ci-N/A N/A l

N/A l

i i

i 1

1 I

i i

Total for period l

Ci l 1.33E+02 l 1.10E+02 N/A i

N/A j

l 2.

Gaseous Iodines l

l i

l l

Iodine-131 l

Ci l 9.85E-05 l 2.00E-04 l

N/A 1

N/A j

l l

l

\\

l j

Iodine-132 l

Ci' l 0.00E+00- l 0.00E+00 l

N/A i

N/A l'

l I

I I

l l

I l

Iodine-133 i

Ci j 3.42E-04 l 5.61E-04 N/A j

N/A l

l l

Iodine-134 l

Ci l 0.00E+00 l 0.00E+00 N/A l

N/A j

l l

l Iodine-135 l

Ci l 0.00E+00 l 0.00E+00 i N/A N/A j

l l

I l

Total l

Ci l 4.41E-04 l 7.61E-04 l

N/A i

N/A l

21

i I

Continuous Mode Batch Mode i

I I

I l

l

-l Nuclides Released Unit l Quarter 1 l Quarter 2 l Quarter 1 I Quarter 2 l 3.

Particulates l

i

=l I

I l

l l

Strontium-89 Ci

, 1.00E-06 (1) l N/A l

N/A l

l l

j Strontium-90 Ci l 0.00E+00 (1)

N/A l

I I

l l-i i

l N/A N/A 1

l Cesium-134 i

C1 l 0.00E400 l 0.00E+00 l

l

- Cesium-137

_ Ci O.00E+00 0.00E+00 N/A N/A l

l i

l-

)

l l.

Barium-140 Ci i 0.00E+00 l 0.00E400 1

N/A l

I I

l l

l i

{

i Lanthanum-140 Ci 1-0.00E+00 l 0.00E+00 l N/A l

N/A

'j

.i l-I i

l Cobalt-60 l

Ci j 0.00E+00

! 0.00E+00 1 N/A l

N/A l

l I

l l

-i

.. l Chromium-51 Ci

! 0.00E+00 0.00E+00 l N/A N/A l

I I

s 1

l Zirconium-95 Ci l 0.00E+00 l 0.00E+00 l

N/A N/A

-li i

i i

l i

i i

~ Niobium-95 l

Ci l 0.00E+00

!_0.00E+00 l

N/A N/A l

T l

1 r

l l

Zinc Ci l 0.00E+00 j 0.00E400 l

N/A N/A l

I I

l j

Iron-59

'l Ci 0.00E+00

' O.00E+00 l

'N/A i

N/A l

t l.

l i

I l

l I

_j Manganese l Ci l 0.00E+00 i 0.00E+00 l

N/A j

I I.

I l

i i

l 1

L l _-

Iodine-131-l' Ci

! 0.00E+00 1 0.00E+00 N/A l

-N/A l

i e

i 4

i i

e l

-Iodine-132 Ci l 1.00E+00 l-0.00E+00 N/A l

N/A l-1

.i 1

l 1

E I

i Ci j 0.00E+00

! 0.00E+00 N/A l

N/A l

-l

= Iodine-133 i-i 1

l 1-l H

[

Cerium-141 l'

Ci j 0.00E+00= l 0.00E+00 l

N/A l

l l

l L

l Ci j 0.00E+00 1 0.00E+00 i

N/A N/A l

l-Cerium-144-l l

l i

.l; l-Ci

! 0.00E+00- ! 0.00E+00.. l N/A l

N/A l

j Chbalt-58 i

I l

.i c

-l silver-110m Ci l 0.00E+00 l 0.00E-00 j N/A j

N/A j

L

-l-i l

l l

Molybdenum-99 l

Ci l 0.00E+00 j 0.00E+00 l

N/A j

N/A l

L l

l l

l j

unidentified l

Ci l

N/A

-l N/A l

N/A l

.N/A l

l 1

l l

Total for period l

Ci

! 1.00E-06 i

(1) l N/A l

N/A l

22 i

i 6

i.

t.

Continuous Mode Batch Mode

-~ I.

I.

l.

l j _ _Nuclides Released

! Unit

! Quarter 1 ! Quarter 2 l-Quarter 1 l Quarter 2 l t

4.0 Tritium

.i j

I I

I l

Hydrogen-3 l

Ci j 6.29E-01 1 5.35E-01 l

N/A N/A l

i 1

Fuel Building Exhaust Vent and Radwaste Building Exhaust Vent are considered i

I ground level release points..

-(1) Not available for submission at this time, supplemental report to follow.

f t

f l

i

(

I i

t

'~

l t-

)

i' l

.+

l f

?

i i

5 23 l

F

. ~... -..

I TABLE 6 Effluent and Waste Disposal Semi-Annual Peport 1991 Year Liquid Effluents - Sumation of All Releases 1/Tharters l

l l

1 l

Est.

l l

l Unit l

Quarter !

Quarter i Total l

l l

l 1

2 l

Error, % l A.

Fission and activation products l

l I

l l

1.

Total release (not in-l Ci l 7.39E-02 ;

(4) i 1.42E+01 l

l ciuding tritium, gases, i l

l l

j l

alpha l

j l

l l

I l

l l

2.

Average diluted concen- ! uCi/ml

! 5.32E-08 l (4) l l

tration during period j

l l

l 3.

Percent of applicable j

l 5.92E+00 t (4) l l

limit (1) l l

l l

B.

Tritium l

l l

l

\\

l l

1.

Total release l

Ci l 1.027C+01; 5.31E+00 l 1.42E+01 l

l l

I I

I l

l l

2.

Average diluted concen- ! uCi/ml

7.39E-06 l 3.38E-06 i j

tration durino period l

l l

I l

l 3.

Percent of applicable l

! 2,46E-01 l 1.12E-01 l l

limit (2) !

l l

l C.

Dissolved and entrained gases l

\\

l l

l 1.

Total release l

Ci

! 9.45E-02 l 4.48E-02 l 1.42E+01 l

l l

I l

l l

2.

Average diluted concen-I uCi/ml

! 6.80E-08 l 2.85E-08 l l

tration during period l

l l

3.

Percent of applicable l 3.40E-02 l 1.42E-02 l l

limit (3) l l

l l

24

- - _ - - ~ - - _ _ _ _ _ _ _ _ _ _ _ _ _

l l

l 1

l Est.

l

}

l Unit

Quarter j Quarter l Total l

l l

[_

1 l

2 l

Error, % l D.

Gross alpha radioactivity l

l l

1.

Total release l

Ci l 0.00E+00 1 0.00E+00 l 1.42E+01 l

l I

l 1

l I

l' l

l l

l E.

Volume of waste released i

liters l 3.57E+06 l 2.79E+09 l 8.73E-01 l

(prior to dilution) l l

l l

l F.

Volume of dilution water l

liters l 1.39E+09 l 1.57E+09 l 5.70E-01 used during period l

l l

(1) One quarter of 5 Ci annual limit (1.25 Ci) for liquid releases except for tritium and dissolved or enteained noble gases from 10CFR50 Appendix 1.

(2) 10CFR20, Appendix B. Table II, Column 2 MPC limit of 3.00E-03 uti/ml.

(3) Technical Specification 3.11.1.1 limit of 2.0E-04 uti/ml for dissolved or entrained noble gases in liquid effluents.

(4) Not available at this time, supplemental report to follow.

I 25

Effluent and Waste Disposal Semi-Annual Report 1991-- Year G.

Liquid Effluents 1/2 Quarters Continuous Mode Batch Mode l

l l

Nuclides Released j

Unit

! Quarter 1 i Quarter 2 ! Quarter 1 l Quarter 2 l l

I I

l l

l-Arsenic-76 l

Ci l

N/A l

N/A l 2.20E-05 l 2.91E-05 l

i i

i l

1 i

l Strontium-89 l

Ci l

N/A l

N/A y 6.10E-04 l

(1) l l

l l

Strontium-90 i

Ci l

N/A l

N/A l 4.74E-05 l

(1) l i

l l

l Yttrium-92 l

Ci l

N/A l

N/A j 2.07E-03 l 2.33E-04 l

l l

Cesium-134 l

Ci l

N/A l

N/A l 0.00E+00 l 0.00E+00 l

l l

Cesium-137 l

Ci l

N/A l

N/A l 1.98E-05 l 6.92E-06 l

l l

Iodine-131 l

Ci j

N/A j

N/A i 6.09E-04 l 3.19E-05 i

l l

\\

l Iodine-132 l

Ci l

N/A l

N/A l 0.00E+00 l 0.00E+00 l

1 l

l l

l lodine-133 l

Ci l

N/A l

N/A l 2.87E-04 l 2.16E-05 l

1 l

l l

l 1

l l

l~

lodine-13a l

Ci l

N/A l

N/A l 0.00E+00 j 0.00E+00 l

i l

l l

l Iodine-135 i

Ci i

N/A l

N/A i 0.00E+00 l 0.00E+00 l

l l

Sodium-24 l

Ci l

N/A l

N/A l 0.00E+00

! 0.00E+00 l

i I

I I

l l

l Cobalt-57 l

Ci l

N/A l

N/A

! 0.00E+00 l 0.00E+00 l

l l

t l

l l

l Cobalt-58 l

Ci l

N/A l

N/A l 1.03E-03 l 2.81E-04 l

l l

l l-Cobalt-60 i

Ci N/A l

N/A l 1.15E-02 l 2.94E-03 l

i i

l I

t Iron-55 l

Ci l

N/A l

N/A i 6.67E-03 i

(1) l l

l l

l Iron-59 l

Ci l

N/A l

N/A l 1.03E-03 l 3.54E-04 l

l l

l Zinc-65 l

Ci j

N/A l

N/A l 2.11E-04 l 5.27E-05 l

i l

1 l

l Manganese-54 i

Ci l

N/A l

N/A-l 3.98E-03 l 1.12E-03 l

l l

l

\\

l l

l Manganese-56 l

Ci l

N/A l

N/A l 0.00E+00 l 0.00E+00 l

\\

l l

l

\\

l l

l Chromium-51 l

Ci l

N/A j

N/A l 2.77E-02 l 4.61E-03 l'

l l

l j

Zirconium-95 i

Ci l

N/A l

N/A l 4.33E-05 ; 2.96E-05 l

l l

Molybdenum-99 l

Ci l

N/A l

N/A l 5.97E-04 j 1.89E-04 l

l l

I l

l l

l Technicium-99m l

Ci l

N/A l

N/A l 4.57E-04 l 1.55E-04 l

l l

I I

l l

Copper - 64 i

Ci N/A l

N/A l 0.00E+00 l 0.00E+00 l

\\

l l

I l

l Tin - 113 l

Ci l

N/A l

N/A l 0.00E+00 l 0.00E+00 l

l l

26

i G. (Cont'd)

Continuous Mode Batch Mode I

l l

l Nuclides Released l

Unit

! Quarter 1 i Quarter 2 l Quarter 1 j Ouarter 2_l l

l l

l I

j Lanthanum-140 Ci l

N/A N/A l 1.38E-02 l 3.34E-03 l

l-T l

l l

N/A l

N/A l 1.26E-03 l 1.50E-04 l

4, l

Cerium-141 Ci l

l l

Cerium-144 Ci l

N/A l

N/A l 0.00E+00 l 0.00E+00 l

l l

\\

l T

l l

l Antimony-122 l

Ci l

N/A l

N/A j 6.18E-05 l 3.38E-05

[

\\

l l

Antimony-124 l

Ci l

N/A l

N/A l 2.96E-04

8.96E-05 i

i l

l l

Ruthenium-103 Ci i

N/A l

N/A l 2.43E-04 l 5.54E-05 l

\\

l l

\\

l l

Rhodium - 105 i

Ci l

N/A l

N/A l 1.56E-04 l 8.91E-05 l

l 1

l l

Bromine - 82 Ci l

N/A l

N/A l 0.00E400 l 0.00E+00 i

l l

l Neptunium - 239 l

Ci l

N/A l

N/A l 1.21E-04 j 0.00E400 l

l l

Niobium - 95 I

Ci l

N/A i

N/A i 1.53E-04 l 3.87E-05 l

l l

Niobium - 97 i,

Ci N/A l

N/A l 5.33E-05 l 1.37E-05 l

i 3-i i

i i

6 i

i Silver - 110m l

Ci l

N/A l

N/A l 9.18E-06 l 9.93E-06 l

l l

l Strontium - 92 Ci l

N/A N/A l 0.00E+00 1 5.56E-06 l

l l

Tungsten - 187 l

Ci l

N/A l

N/A l 3.08E-05

0.00E+00

- --r i

i i

i l

i i

Tellurium - 132 l

Ci l

N/A l

N/A i 2.40E-05 i 0.00E+00 l

l l

l Yttrium - 91m i

Ci i

N/A l

N/A l 6.68E-05 l 1.62E-05 -4 i

i i

i f

1 I

I i

4 l

Barrium - 140 i

Ci l

N/A l

N/A 4.31E-04 l 3.24E-04 l

'd i

,i i

i i

i j

Ruthenium - 105 l

Ci l

N/A l

N/A l 3.51E-04 l 9.01E-05 l

\\

l l

Strontium - 91 _

l Ci i

N/A l

N/A l 0.00E+00 l1.48E-05 l

l l

Total for period j

Ci j

N/A l

N/A l 7.39E-02 i

(1) l (1) Not available at this time, supplemental report to follow.

27 l

i

ii. Dissolved and Entrained Gases Continuous Mode Batch Mode l

I l

l l

l Nuclides Released Unit l Guarter 1 l Quarter 2 l Quarter 1 l Quarter 2 l l

t l

l l

l Argon 41 l

Ci l

N/A l

N/A l 0.00E+00 l 0.00E400 l

l l

Krypton-85m Ci j

N/A N/A l 0.00E+00 l0.00E+00_l l

i i

i e

i i

l Krypton-85 l

Ci l

N/A l

N/A l 0.00E400 l 0.00E+00 l

l l

Krypton-87 l

Ci i

N/A l

N/A l 0.00E+00 l 0.00E+00 l

l l

l

,ypton-88 Ci l

N/A l

N/A l 0.0CE+00 l 0.00E+00-l l

Kr 1

i i

i l

1 I

I l

l l

l Xenon-131m l

Ci l

N/A N/A l 0.00E400 l 0.00E400 l

t i,

i i

i j

Xenon-133m l

Ci l

N/A l

N/A i 1.86E-03 l 6.16E-04 l

l l

Xenon-133 l

Ci l

N/A l

N/A l 3.83E -02

1.64E-02 l

I l

l l

l Xenon-135m l

Ci l

N/A

}

N/A l 0.00E+00 l 0.00E+00 l

l Xenon-135 l

Ci l

N/A l

N/A l 5.43E-02 l 2.78E-02 l

l l

Xenon-137 Ci l

N/A l

N/A l 0.00E+00 l 0.00E+00 l

l l

1 l

l l

l Xenon-138 l

Ci l

N/A l

N/A l 0.00E400 l 0.00E+00 l

l l

unidentified l

Ci l

N/A l

l l

I l

l

'l l

Total for period l

Ci l

N/A l

N/A l 9.45E-02 l 4.48E-02 l

(1) Not available at this time, supplemental report to follow.

28

Effluent and Waste Disposal Semiannual Report 1991'_ Year

. Solid Waste and-Irradiated Fuel Shipments Reporting Period 01/01/91 to'06/30/91 Qtr 1/2 A.

So'id-Waste l Shipped for Burial or_ Disposal (Not irradiated fuel)

-j j

l 6-month l Waste l Est. Total l l

1.

Type of waste Unit Period Class Error, %

l I

I I

a. Spent resins, filter sludges

- m j

0.00 l

N/A

! 0.00E+00 l 3

l-evaporator bottoms, etc.

Ci l

0.00 l

j j

j i

j I

l

.b. Dry compressible waste, l**m3 33.04 i

A-U See-l-

contaminated equip, etc.

Ci 2.67 Below j

c. Irradiated components,

[**m3 f 0.00E+00' N/A l 0.00E+00 a

i control rods, etc.

l Ci 0.00E+00' l

i l

l l'**m j

0.00E+00j N/A l 0.00E+00 l

-r 3-i d.Other(None)-

l 1

Ci l

0.00E+001 1

j RadwasteErrorI(%) Estimated Waste type considered are processed solid waste (i.e. resin, fi_lter media...)

= and-Non-compactable/Compactable Dry Active Waste.

1.

Possible Errors a.

Volume.

b.-

Representative Sampling c.

Instrument Counting d.

dose to Curie calculations 2.

Volume Error-Radwaste contractor personnel have stated that level indication can-be determined to

+-0.5-inches.

This correlates to approximately +-1.0%.

Container -manufacturer stated design allows

+-1.0%

deviation from dimensions.-

3.

Sampling Error.

Sampling' error for_ process solid waste is based on mixing tank contents to produce unifcrm matrix.

Sampling error for Dry Active Waste is based on obtaining a representative sample from the material being packaged.

This error is assumed to be +-10%, which is consistent with Industry Standards.

4 Instrument Error The - error caused-by. ample geometry, counting time, sample activity and-s instrument background is estimated by Chemistry to be +-20%.

The error for survey. instr-umentation 'is estimated by Radiation Protection to be

+-10%.

5.

Oose to Curie Calculations The Bowman-Swindle curves are used to calculate Dose to Curie activities.

The error caused by package geometry, Isotopic percent abundance and personnel error is assumed to be

+-25%,

which is consistent with Industry Standards.

Volume considered total disposal volume of container.

-29

.. _ _ _. _ -.. _ _, -. _. _. - _.. - _. -.. ~. _ _.. _ _. _ _ _.

+ -.

i

- 2.-

1

.YYPE OF

-j Spent Resins, filter. l Dry compressible l IrraJiated Components! Other l cWASTE-I sludges, evaporator j waste, contaminated l control rods, etc.

l (None)l l-l bottoms, etc.

i equip, etc.

I j

-l j

l Percent l

j

-l l Principle.

l Isotope

! Abundance-_ l Isotope

! Abundance!

N/A l

N/A l t

!Radiontclides l

l

-- l l

-l l

l j

l(Identity and l

N/A~

l N/A l

C-14 j 1.72E+00 l l

l

-l % Abundance)

- l l

l Co-58 l 3.60E-Oi l l

l l

{_6.15E401 l l

l l

Co-60 6.90E+00 l l

t l

l l

Cr-51 1

l-l Fe-55 l 2.23E401 l l

l l

l Mn-54 l 8.93E+00 l l

j j

j-l l

l Ni-63 l 1.28E400 l l

l t

-l-Zn-65 l 2.74E+00 t l

l l

l Cs-137

! 1.80E-01 l l

j l

l-l l

l Pu-238 l 1.00E-02 i l

l' l-l l

Pu-239 l 1.00E-02 l l-l l-l l

Pu-241 l-2.30E-01 l l

}

l i

i i

.l I

f 1

I I

4 i

I. -

l l

t 1Above Determined) l l

l 1

j

'!by:

l l

j l

l f

lA. measurement l l

l l

18. estimation-l N/A l

C l

N/A l

-lC_ measurement l

l l

l l and-correlation l

l t

l l

l

[

l TYPE OF-i N/A l Strong, Tight Drums i N/A j

N/A_ l l

l CONTAINER l

l l_

'j l-

. l l

l l

-l SOLIDIFICATION l-i N/A-l N/A i

N/A l

~

"l. AGENT OR l

-N/A l

l l

l

' ABSORBANT I

j j

3.=

SOLID, WASTE-0:SPOSIT10N L

Number of Shipments Mode cf Transportation Destination f

L:

6 Truck Barnwell,-S.C.

~ B.- IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination

.0 N/A-N/A i

t 5

i 9

t

[

II I

~

I h

i 1

)

30 s

=

m

---.,m-

+

.-r

ATTACHMENT #1 Process Control Program (PCP) l l

l.

l l-

ML20082L999

Contents

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