ML20059G505

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Semiannual Radioactive Effluent Release Rept for Jan-June 1990
ML20059G505
Person / Time
Site: Callaway Ameren icon.png
Issue date: 06/30/1990
From:
UNION ELECTRIC CO.
To:
Shared Package
ML20059G503 List:
References
NUDOCS 9009130005
Download: ML20059G505 (13)
v • d • e


Text

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CALLAWAY ' PLANT Semiannual; Radioactive Effluent Release l Report January - June, 1990 l,

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, 1.0' INTRODUCTIONL h^

- 2.0: SUPPLEMENTAL.INFORMATION 2.1 Regulatory Limits t

2.2 Maximum Permissible Concentrations.  ;

4. 2.3 1 Average Energy.

2.4 Measurements.and Approximations'of Total Radioactivity

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2.5' Batch' Releases 2.6 ' Abnormal Releaces-3.0 '

SUMMARY

OF' GASEOUS RADIOACTIVE EFFLUENTS f 4.0

SUMMARY

OF LIQUID RADIOACTIVE EFFLUENTS "5;0 '

SOLID WASTES-SHIPMENTS 6.0 RELATED INFORMATION f6.1 Unplanned Releases 6.2. Changes to the Process. Control-Program  ;

6.3L l Changes:to the Offsite Dose Calculation-Manual 6.4 Major Changes'to Radwaste Treatment Systems 'l 6.5- Land Use Census' Changes 6.6i Inoperability of Effluent Monitoring Instrumentation a

Table lAt Semiannual Summation of Gaseous Releases y

Table IB '

Semiannual Airborne Continuous and Batch Releases

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' Table 2A:- Semiannual Summation of Liquid Releases  ;

Table 2B Semiannual Liquid Continuous and Batch Releases Table 3 Solid Waste and Irradiated Fuel Shipments JAttachment'1 APA-ZZ-01003, Offsite Dose Calculation Manual, Revision 0 t

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!/ L1.0.. ~ INTRODUCTION-re 3, ,

/s' f-  : - This ^ Semiannual Radioactive.1 Effluent = Release Report -is; for :l Union I '

Electric Company's Callaway Plant and ~ is 1 submitted in' accordance 1 -

. with the requirements . 'of - APA-ZZ-01003, Section ' 7.2. The report '

o covers the period. from. January l',1990 through June 30,1990 - -(

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- This' report includes a summary of the quantities of . radioactive" c . liquid . and gaseous ef fluents and solid ' waste. released from the. .

+ plant.. The information '1s presented in accorda*1cc with- the format-

- outlined "in Appendix B of Regulatory Guide 1.21, Revision 1, June  ;

i 1974.~

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All liquid and gaseous effluents discharged. during . this ?. reporting-period were in compliance with the limits of the . Callaway Plant :

. 0ffsite Dose Calculation Manual.

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3 2.0l SUPPLEMENTAL.INFORMATION

.2.1; Regul'atory Lim'its . ,

Specified as;follows-are the. technical specification limits applica-

. ble' to the release of radioactive material- in liquid and gaseous

, effluents.-

2.1.1' Fission and Activation Cases (Noble Gaoes)

The dhse; rate due to radioactive noble gases released in gaseous

-effluents from the site to areas at 'and beyond the- site - boundary -

shall'.be limited to less than or equal _to 500 mrem /yr to the-total body'and_less than or equal to 3000. mrem /yr to the skin.

u The air dose = due. to noble gases released?in gaseous ef fluents, from j each unit, to areas at.and beyond the site boundary shall be limited 1 to the<following:-  !

.a. During any calendar quarter: Less than or equal to 5 mrad for s

gamma radiation and less than or equal to 10 mrs6 for beta' M~ radiation and,

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for. beta-radiation.

2.1.2' Radioiodine, Tritium, and Particulates The dose' rate,'due to . Iodine 131 and 133, tritium and all radionuclides in particulate form with half lives greater-than eight J

.(8) days released in gaseous effluents from the site to areas at and i

, beyond the site boundary shall be limited to less than or equal.to j!

1500' mrem /yr to any organ, The dose to a member.of the public from Iodine 131 and 133, tritium, l and all: radionuclides in _ particulate form with half-lives greater j than eight (8) ' days in gaseous ef fluents _ released to areas at 'and i beyond the site boundary shall be limited to the following:  !

a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, J f
b. During any calendar year: Less than or equal to 15 mrem to any 2 organ.

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  • The concentration'of radioactive material released in, liquid.efflu--

ents to -unrestricted areas: shall be - limited to the ' concentrations b specified = -in - 10 CFR Part 20 Appendix B, . Table 11, Column ; 2 ~ for :  !

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. radionuclides other' than dissolved or entrained noble gases. _!

me dissolved or entrained' noble' gases,- the' concentration shal1~ be - 'l limited!to 2.0E-04 microcuries/ml total activity.

~The dose- or dose commitment' to an Individual from'. radioactive materials in liquid effluents released to unrestricted areas'shall be limited:

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a. During any calendar quarter to less than_or equal to 1.~5 mrem .'

.to- the , total body and less than or equal to ' S mrem to any 4 organ,.and 6_

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b. During any calendar year to less than_or equal to 3 mrem-to the ~

whole body and to less than or equal to 10 mrem to any organ.

a 2 .1 '. 4 Uranium' Fuel ~ Cycle Sources The. annual-(calendar year) dose or dose commitment to any member of the public> due to releases of radioactivity and to radiation from I uranium fuel cycle sources shall be '.imited to less.than or equal;to e 25 mrem to the total body or any organ, except the thyroid, which shall.be limited to less than or equal to 75 mrem.

2.2 Maximum Permissible Concentrations i

2.2.1 _ The ' maximum permissible concentration values specified in 10CFR20,

Appendix B, Table II.- Column 2 are used to calculate release rates ,

and L permissible concentrations of liquid. . radioactive ef fluents at .  ;

e the unrestricted area boundary. A value of 2.0E-4 microcuries/m1'is _t

  • used as the MPC for dissolved and entrained noble ~ gases in liquid effluents.

2.2.2. For _ gaseous ' ef fluents, maximum permissible concentrations are not .f directly. used in release rate calculations since the applicable limits.ars stated in terms of dose rate at the unrestricted area boundary.-

1 2.3 Average Energy , 7 This is not applicable to the Callaway Plant's radiological effluent technical specifications.

1 2.4 Measurements and Approximations of Total Radioactivity The quantification of radioactivity in liquid and gaseous effluents i was accomplished by performing the sampling and radiological analy-sis.of effluents in accordance with the requirements of Table 9.3-A 7 and Table 9.6-A of APA-ZZ-01003, Offsite Dose Calculation Manual.

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p - Gammaj spectroscopy. was -the primary -analysis: technique used: to.

[ determine, the- radionuclide composition and concentrationo ofH liquid-

and gaseous effluents. . Composite samples were analyzed for Sr-89, Sr-90, ~and- Fe-55 lby an -independent . laboratory. Tritium and alpha were Jmeasured for both liquid and gaseous effluents using' liquid >

. scintillation counting .and gas flow . proportional . counting. tech- J r - niques,'respectively.

-The total radioactivity in effluent releases was determined from thei ,

measured concentrations of each radionuclide . present and the. total:

volume 'of' effluents discharged. Gross- beta or gamma -rai.ioac tivity . ,

measurement; techniques, were- not . utilized to approximate the total ,

radicactivity in effluents.

2.5: Batch Releases:

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[215.1 Liquid- ,

, . Number bf batch ' releases: 108

--. Total time period'for batch releases: 44,901 minutes

' Maximum time period for a batch release: 1453 minutes-Average time' period'for batch releases: 416 minutes =

Minimum time period for a batch relerce: 198 minute Average stream flow during periods of release of effluent into a flowing stream: 107,582 cfs*

'?! '*Ref ? Letter, Greg Vaughn (US Geological Survey) to T. M. Baxter (Union Electric Co.) dated July 5, 1990

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p 2.5.2 Gaseous Total for theJ ~Non-Outage -

, Reporting Period Related

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' Number of batch releases ~ 51 51 Total time period for . batch releases 9.335 minutes 9,335 minutes Maximum time period ~for a batch release 1,184 minutes 1,184 minutes ,

b - Average time period for batch releases 183 minutes '183 minutes Minimum time period for a batch release 48 minutes 48 minutes "2,6' Abnormal Releases  :

2.6.1 . Liquid-Number of releases: 0 Total Activity released: 0 y .

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-2.6.2.1- ' Number of releases: 'O *

2;6.2.2 . Total' Activity' released
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SUMMARY

-0F GASEOUS RADIOACTIVE EFFLUENTS ,

3.1$ The quantities of radioactive material released in-gaseous effluents,are summarized in Table 1A and IB. Note that for this reporting period no

[- gaseous effluents.were considered as elevated releases. ,;

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SUMMARY

OF LIQUID RADI0 ACTIVE EFFLUENTS ,

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4.1 _ The quantities of radioactive material released in liquid effluents arc -[

summarized in Table 2A and 2B.

5.0 - - SOLID WASTES

~541; The' quantities.of radioactive material released in-shipments of solid' '[

waste andLirradiated fuel transported from the site during the reporting.

period art surmaarized in Table 3. The activity and fractional abundance ,

of each nuclide was determined for each waste type by an independent  ;

laboratory based upon radiochemical analysis of samples of that waste

,  : type. The curie amount of each nuclide listed in Table 3 was determined-as the product of the fractional abundance and the total curies shipped.' 'i Those nuclides which comprise at least 1% of the total activity for a

, particular waste type are presented in Table 3. '

~ 6.0 > RELATED INFORMATION

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-6.1 Unplanned Releases Unplanned releases are inadvertent or accidental releases of radioactive.

material, or releases of radioactive material via normal pathways without' i a release permit or proper authorization, or without proper sampling and- '

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analysis,-or releases which are conducted in such a manner as to result- ,

in significant deviation from the requirements of the release permit.

There were no unplanned release during the reporting period. ,;

6,2" Changes to the Process Control Program NRC Generic Letter 89-01, " Implementation of Programmatic Controls for

,g Radiological Effluent Technical Specifications In the Administrative

. < . Controls Section of the Technical Specifications and the Relocation of Procedural' Details of RETS to the Offsite Dose Calculation Manual or to j l' the Process Control Program" requested that the Process Control Program be brought under programmatic administrative controls. In accordance with Generic Letter 89-01, Rev. 9 of the Process Control Program (PCP) was converted to Administrative Procedure APA-ZZ-01011, PROCESS CONTROL

- PROGRAM MANUAL (PCP). api-ZZ-01011, Rev. O, was approved by ORC on 8-4-89 in Meeting #891 and issued on 5/8/90 following NRC approval of Operating L4aanse Change #10e .

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-A complete. copy:ds available,to the NRC'upon' request.-The_ revised PCP'is~ J' not' included with this report _due to contained proprietary formulations-and information.- g (o _

6 . 6.3 Changes To The Offaite Dose Calculation-Manual NRC Generic Letter 89-01 requested that_the Radiological Effluent- d

Technical Spe'cifications (RETS).be relocated to the Offsite Dose Calculation Manual--(ODCM) or the Process Control Program. In'accordance with Generic Letter 89-01, Rev.J6 of the ODCM was combined.with the RETS T <

to' form APA-ZZ-01003, Of f site Dose Calculation Manual. APA-ZZ-01003, Rev. ' t :

0,-0DCM was approved by ORC on'7-21-89 in Meeting #887 and: issued on 5/7/90 following NRC approval of Operating License Change #1087. 1 Table 5. Pathway Dose Factors (R4 ) for Radionuclides O'ther Than Noble

. Gases, was appended to include: adult pathway dose factors; This addition occurred prior to issue and was approved.by' ORC on 3-2-90.

A complete copy of APA-ZZ-01003, OFFSITE DOSE CALCULATION MANUAL, Rev 0.

is included as attachment 1. i 6.4

  • Major Changes to Radwaste Treatment Systems There were no major changes to the-Liquid, Gaseous or Solid Radwaste

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j Treatment Systems during the reporting period. '

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6.5 Land Use Census-Changes.

There were no changes in critical receptor locations for dose 4 calculations during the reporting period.

16.6 .Inoperability of Effluent Monitoring Instrumentation All. effluent monitoring instrumentation was OPERABLE within the' limits

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specified by APA-ZZ-01003 Sections 9.1.1 and_9.2.1 during the reporting #

period. .

t 6.7 Instances of Liquid Holdup Tanks or Waste Gas Decay Tanks Exceeding Technical Specification Limits All liquid' tanks and waste gas decay tanks were wi' thin the limits of I

-Specifications 3.11.1.4 and 3.11.2.6 during the reporting period.-

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TABLE 2A SEMIRNNUAL SUMMATION OF LIQUID RELEASES ALL LIQUID. EFFLUENTS 1 QUARTERS 1 AND 2, 1990

=

FIRST SECOND EST TOTAL- _

TYPE OF EFFLUENT UNIT QUARTER QUARTER ERROR %

_~l g A. FISSION AND ACTIVATION PRODUCTS _

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1. TOTAL RELEASE (NOT-INCLUDING 1 TRITIUM, GASES, ALPHA) CURIE 3 4.01E-04-3.37E-04 - 20. -
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.11E-10 6.79E-10 m
3. PERCENT OF APPLICABLE LIMIT t N/A N/A- c B. TRITIUM fl. TOTAL RELEASE CURIES 3.93E+02 3.64E+02 14 2.LAVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 6.98E-04_7.34E - - - - - - - - - - - - - - - - - - - - - _ _ - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - _ - - - - - - - - . - _ _ _ _ - - -
3. PEnCENT OF' APPLICABLE LIMIT  % N/A N/A C. DISSOLVED-AND ENTRAINED GASES ,

1.? TOTAL RELEASE 1 CURIES 6.93E-02 2.17E-01 27

2. AVERAGE DILUTED CONCENTRATION '

DURING-PERIOD UCi/ML 1.23E-07 4.38E-07 -

D.t GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 9.99E-04 5.10E-04 29 E. WASTE VOL RELEASED (PRE-DILUTION) GAL 5.19E+06 4.83E+06 10

'F. VOLUME OF DILUTION WATER USED GAL 1.44E+08 1.26E+08 10 PAGE 1 OF 1

_____ _ __ __-.____ _ ___ _ _ __ ___ __m___ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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/ ALL: AIRBORNE EFFLUENTS =

3 QUARTERS- 1 AND 2,11990 i UNIT FIRST SECOND EST TOTAL TYPE OF EFFLUENT

,____________________'__________________________________._______ QUARTER QUARTER _________ HERROR %

-A.' FISSION AND ACTIVATION GASES

_____________________________________n__________________________________-

, , 1.nTOTAL' RELEASE CURIES l 20-

.______________________________________________'.18E+02-2.12E+02 _________________________

.2. AVERAGE RELEASE RATE FOR PERIOD .uCi/SEC 1.52E+01

.______________________________________________________'2.70E+01 __________________  ;

.3..PERCENTLOF TECH-SPEC LIMIT ___________% N/A j

______________________________ ________________N/A _______________ q B.-RADIOIODINES TOTAL IODINE-131 CURIES 2.84E-06 1.04E-05 23 l

'_1.

L' 2. AVERAGE RELEASE RATE OF PERIOD uCi/SEC 3.66E-07 1.33E-06 g _____________________________________________'___________________________  ;

p 3. PERCENT 0F-TECH LIMIT  % N/A N/A l

-___________________3PEC _____________________________________________________

1 J C. PARTICULATES 4

=1. PARTICULATE (HALF-LIVES > 8 DAYS) CURIES 0.00E+00 1.29E-06 30

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . u

'2. AVERAGE RELEASE RATE OF: PERIOD- Luci/SEC 0.00E+00-1.61E-07 l L3.E PERCENT SPEC LIMIT  % N/A N/A- l

___________'OF-TECH _____________________________________________________________: 3 0 4. GROSS CURIES 1.06E-06 9.89E-07 i ALPHA RADIOACTIVITY j

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1. TOTAL RELEASE CURIES 7.31E+00 6.42E+00 14 'I
2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 9.40E-01 8.17E-01
3. PERCNT'OF TECH SPEC-LIMIT  % N/A N/A k

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TABLE 1B  :

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' SEMIANNUAL' AIRBORNE: CONTINUOUS AND BATCH RELEASES-

, GROUND LEVEL' RELEASES' FISSION; GASES, IODINES, AND'PARTICULATES QUARTERS 1.AND 2, 1990 i 1

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CONTINUOUS RELEASES .

. .----__-._------___------- ----___----_______-__.- __ BATCH RELEASES' -------------------

g, FIRST SECOND FIRST SECOND ,

NUCLIDE~ UNIT QUARTER QUARTER QUARTER QUARTER

.----__ -......----____---_---___-.....------_-__--------------__.------__=

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1. FISSION GASES .

- - - - - _ - . _ _ _ - - - - _ - - _ _ - - _ - _ _ - - - - _ _ _ - _ _ - - - - - - _ _ - - _ - _ . - _ - _ _ _ _ _ - _ - - - - - - - - - . . 1' Kr-85 CURIES 3.'28E-01 3.10E-01 0.00E+00 6.77E-04.

Kr-85M CURIES 0.00E+00 6.35E+01- 2.07E-01'3.78E+00 Kr-87 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88' CURIES- 0.00E+00 0.00E+00 0.00E+00'3.48E-05 '

-Xe-131M- CURIES ~0.00E+00 5.71E-01 4.34E-01 7.57E-01 i Xe-133- -CURIES 8.79E+01 9.85E+01 2.10E+01-3.27E+01

+ 'Xe-133M CURIES- 0.00E+00 0.00E+00 l'04E-01 1.61E-01--

, Xe-135i CURIES 8.17E+00 1.20E+01: 9.69E-03 2.70E-02 L i Xe-135M CURIES 0.00E+00.0.00E+00 0.00E+00 0.00E+00

l. .Xe-138 CURIES 0.00E+00 0.00E+00 0.00E+00-0.00E+00

'Ar CURIES: 0.00E+00 0.00E+00 1.26E-01.l.38E-01 ,

l TOTAL'FOR PERIOD CURIES 9.63E+01 1.75E+02 2.19E+01 3.76E+01 2 ^.1 I O D I N E S -

O -----__--------._-----------------.....--------_-----------------_-----_

R I-131' CURIES 2.84E-06 1.04E-05 0.00E+00 0.00E+00 L I-132 CURIES 0.00E+00'O.00E+00 0.00E+00 0.00E+00 I-133 CURIES 6.42E-08 5.'77E-08 0.00E+00 0.00E+00. l I-135' . CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00  :'

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' TOTAL! FOR-PERIOD CURIES- 2.91E-06 1.05E-05 0.00E+00 0.00E+00'

3. 'PARTICU' ATES Br-82 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3

'Co-60 CURIES 0.00E+00 1.27E-06 0.00E+00 0.00E+00 Rb-88 CURIES- 0.00E+00 0.00E+00 0.00E+00 1.55E-07 Sr-89^ CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 CURIES 0.00E+00 1.S7E-08 0.00E+00 0.00E+00  ;

Cs-134 CURIES .0.00E+00 0.00E+00 0.00E+00 0.00E+00

'Cs-137 CURIES 0.00E+00 0.00E+00 0.00E+00 0'.00E+00 Ce-141 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00-Gl ALPHA CURIES 1.04E-06 9.71E-07 1.73E-08 1.84E-08

-TOTAL FOR PERIOD CURIES 1.04E-06 2.26E-06 1.73E-08 1.74E-07.

'4.' TRITIUM  !

'H-3 CURIES 7.10E+00 6.22E+00 2.12E-01 2.00E-01 PAGE 1 OF 1 m 9

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- SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED  :

,, _ QUARTERS 1 AND 2,'1990

....____________________________________________________________________. y NUCLIDE CONTINUOUS RELEASES BATCH RELEASES l FIRST SECOND FIRST SECOND

____________,_____________. UNIT QUARTER _____ QUARTER QUARTER- QUARTER

_______'____________________________ 1

___-ALL NUCLIDES 1 H-3 . CURIES 0.00E+00 0.00E+00 3.93E+02 3.64E+02 j

Na-24 CURIES ~ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j Rb-88 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '

.Cr-511 :CURIF,S 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j Mn CURIES 0.00E+00 0.00E+00 5.29E-05-1.24E-05 I Fe-55 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00' l Fe-59 CURIES 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 -J Co-57 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00-Co-58 CURIES- 0.00E+00 0.00E+00 5.51E-05 2.20E ]

. -Co-60 CURIES 0.00E+00 0.00E+00 2.36E-04 1.82E-04 -

Zn-65 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 L Sr-89 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 L

Sr-90 CURIES 0 00E+00 0.00E+00 0.00E+00 0.00E+00' 1 i Zr-95 'CURIEC 0.00E+00 0.00E+00 0.00E+00 0.00E+00- .!

Nb-95 CURIES 0.00E+00 0.00E+00- 0.00E+00.0.00E+00 l Mo CURIES 0.00E+00 0.00E+00 0.00E+00-0.00E+00 l 7

'Tc-99M-Ag-110M CURIES-CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l l p

Cs-134 CURIES 0.00E+00 0.00E+00 0.00E+00 3.35E-05 l

-Cs-136 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 CURIES- 0.00E+00 0.00E+00 0.00E+00 4.10E La-140 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00

'Ce-141 CURIES- 0.00E+00 0.00E+00 0.00E+00 0.00E+00

.Ce-144- ' CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00

'Ru-105 CURIES- 0.00E+00 0.00E+00 0.00E+00 0.00E+00.

W-187 CURIES 0.00E+00 0.00E+00' O.00E+00 0.00E+00-Hf-181 CURIES 0.00E+00-0.00E+00 0.00E+00 0.00E+00 Ba-140 CURIES 0.00E+00 0.00E+00 2.39E-05 0.00E+00 I-131' CURIES 0.00E+00 0.00E+00 3'.24E-05 4.62E-05

.I-132 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-133 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 )

g I-135 CURIES 0.00E+00 0.00E+00 0.00E+00.0.00E+00 LXe-131M CURIES 0.00E+00 0.00E+00 1.12E-03 1.05E-03 Xe-133 CURIES 0.00E+00 0.00E+00 6.76E-02 2.12E-01 Xe-133M CURIES 0.00E+00 0.00E+00 5.11E-04 2.36E-03

~Xe-135 CURIES 0.00E+00 0.00E+00 7.28E-05 2.07E-03 Xe-135M CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 G ALPHA- CURIES 0.00E+00 0.00E+00 9.99E-04 5.10E  !

UNIDENTIFIED CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00

? TOTALS FOR PERIOD CURIES 0.00E+00 0.00E+00 3.93E+02 3.64E+02 PAGE 1 OF 1 l

l

y ,

v p 31" w .f,- *

' \ ;~ Y '

E R. , y

, ,'} : );'

p l ; g. /.!d -;w .

h < _

,f ,

-TABLE 3

,7 4 ..

.g o SOLID WASTE & IRRADIATED' FUEL SHIPMENTS. t Lfl '&, QUARTERS 1 & 2. 1990 G' -,

c. i A. SOLID WASTE SHIPPED- 0FFSITE FOR EURIAL OR DISPOSAL (DOES NOT INCLUDE

? IRRADIATED FUEL)-

by ' *

'.y TYPE OF WASTE L6-MONT: -EST. TOTAL. 'i PERIOD- ERROR'(%)-

.a.- . Spent resins, filter sludges' ~ 40'. 3 : m8 125%

& evaporator-bottoms', etc.- 54.4 Ci Fe-55 57.152% 3.11E+01 Ci H-3' 40.348% 2.20E+01 Ci ,

Cs-137, 1.184% 6.45E-01 Ci-f Co-60 1.110% 6.04E-01-Ci

b. Dry compressible waste, O m8

'J contaminated equipment, etc. -0 Ci

p; ?t
-

ily;- ,

9 x

ji[ , c. Irradiated components, control' 0' 8 m-

pl rods, etc. O Ci'
d. Other O' ms

'O' Ci Solid Waste Disposition Number of Mode of Class of Solid .' Type of Shipments Transportation. Destination Waste Shipped Container .j i

. I 5 Truck Richland, WA A LSA~ .:

a m Solidification Agent y.

Cement..(applicable to waste type "A" only) 4

,  ?! B. IRRADIATED FUEL-SHIPMENTS (DISPOSITION)

Number of Shipments Mode of Transportation Destination

,Et,o 0 N/A N/A-4-

l 1%

E Y'

i . . - _ . ___ _ _ _ _ _

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