ML20114C619

Semiannual Radioactive Effluent Release Rept,Jan-June 1992 Waterford 3 Steam Electric Station

ML20114C619
Person / Time
Site:	Waterford
Issue date:	06/30/1992
From:	Burski R ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20114C621	List: ML20114C619 ML20114C769 ML20114C771
References
NUDOCS 9209030005
Download: ML20114C619 (36)

Text

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i Semiannual Radioactive Effluent Release Report l

l Janua ry 1, 1992 - June 30, 1992 1.

Waterford 3 SES l

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Entergy Operations, Inc.

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TABLE OF CONTENTS 1.0 SCOPE 2.0 SUPPLEttENTAL INFORMATION 2.1 Regulatory Limits-2.2 Maximum Permissibit Concentrations 2.3 Average Energy 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Unplanned Releases 3.0 GASEOUS EFFLUENTS

-4.0 LIQUID EFFLUENTS 5.0 SOLID WASTES 6,0 METEOROLOGICAL DATA l

7.0. ASSESSMENT OF DOSES l

8.0 RELATED INFORMATICN 8.1.

Changes to the Process Control Program 8.2 Cfianges to the Offsite Dose Calculation Manual 8.3 Unavailability of REMP Milk Sampling

8. 4-Report of Requi red Ef fluent Inst rument Inoperability l

~8.5--Activity Released via-Secondary Pathways

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8.6 Additional Information 8.7, Corrections to Semiannual Radioactive Release Reports

9. 0 ' TABLES' 10.O ATTACH $ENTS W50897HP 1

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l.0 SCOPE __

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This Semiannual Radioactive Effluent Release Report is submitted as-L required by Waterford 3's Technical Specification 6.9.1.8.

It covers the l_

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period from January 1, 1992 through June 30, 1992.

Information in this' iL report is presented in-the format outlined in Appendix 'B'of Regulatory h

Guide 1.21.

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The information contained in this report includes:

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(1) A summary 'of the quanti ties of radioactive liquid and gaseous ef fluents and solid vastes released from the plant during the reporting period; (2) A discussion regarding cadioactive gaseous effluents released from identified and monitored secondary release pa hs during the ceporting period; and, (3) A summary of changes'to the Offsite Dose Calculation Manual during this reporting period.

'The summary-of meteorological data and results from the assessment of radioactive doses due to the_ release of liquid and gaseous radioactive

-effluents will be included in the Semiannual Radioactive Effluent. Release Report to be submitted within 60 days after January 1, 1993.

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'2.0 SUPPLEMENTAL INFORMATION 2.1 Ryegulatory Limits The Limits ipplicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections.

These limits are addressed in UNT-005-014 offsite Dose calculation 7

Manual.

2.1.1 - Fission and Activation Gases (Noble Cases)

The dose rate due to radioactive noble gases released in gaseoits effluents.f rom 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.

The air dose due to noble gases released in gaseous effluents from the site to areas at or beyond the site boundary shall be lin.ited to the following:

During any calendar quarter:

Less than or equal to 5 a.

mrad for gamma radiation. and less than or equal to 10 mrad f or beta radiation and, b.

During any calendar year:

Lens than or equal to 10 mrad

-for gamma radiation and less than or equal to 20 mrad for l-beta radiation.

2.1.2 Iodines; Particulates, Half Lives > 8 Days; and Tri tium l --

The dose rate due to Iodine-131 and 133, tritium, and-all radionuclides in particulate form with half lives greater than eight (8) days, released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to less than or equal to 1500 mrem /yr to any organ.

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.a.

The dose to a member of the public from lodine 131 and 133, tritium, and all radionuclides in particulate form with half j

lives greater than eight (8) days in gaseous efflutats released I

to areas at and 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, b.

Puring any calendar year:

Less than or equal to 15 mrem to any organ.

2.1.3 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 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 pCi/ml total activity.

The dose or dose congnitment to a member of the public from radioactive materials in liquid effluents released to unre-stricted areas shall be limited to the following:

a.

During any calendar quarter to less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ, and 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

'ny organ.

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. 2.1.4 --Urani'um fuel Cycle Sources i

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The dose or dose commitment to any member of the public due

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to releases of radioactivity and radiation f rom. uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid,:

which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

I 2.2 Maximum Permissible Concentrations 2.2.1 Fission and Activation Gases; lodines; and Particulates, IIalf

.i Lives >:8 Days For gaseous ef fluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable limits are expressed in terms of dose rate at the site boundary.

2.2.2 Liquid Effluents The maximum permissible concentration (MPC) values specified in 10 CFR Part 20, Appendix B, Table 11, Column 2 are used as the permissible concentrations of liquid radioactive eff2uents at the unrestricted area boundary. A value of 2.0E-4 pCi/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents, l

=2. 6-Average Energy Average energy is not applicable to Waterford 3's Radiological Effluent Technical Specifications.

E-Bars are not. required to be calculated from effluent release data.

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4-2,4 Measurements and Approximations of Total Radioactivig The quantification of radioactivity in' liquid and gaseous ef fluents was accomplished by performing the sampling and-radiologicalfanalysis

'of effluents in accordance with the requirements of Tables 5.3-1 and

-5,4 1Lof UNT-005-014, Offsite Dose. Calculation Manual.

2.4.1 Fission and Activation Gases (Noble Gases)

-For continuous releases, a gas grab sample was analyzed monthly for noble gases.

Each week a Gas Ratio (GR) was calculated according to the following equation:

'GR = Average Weekly Noble Gas Monitor Reading Monitor Reading During Noble Gas Sampling The monthly sample analysis and weekly Gas Ratio were then used.to determine noble gases discharged continuously for the previon week, For gas decay tank and containment purge batch releases, a gas grab sample was analyzed prior to release to determine noble gas concentrations in the batch.

In all cases the total radioactivity in gaseous effluents was determined from measured concentrations of each radionuclide present and the total volume discharged.

2.4.2 Iodines and Particulates Iodines and particulates discharged were sampled using a continuous sampler which contained a charcoal' cartridge and a-particulate filter-Each week the charcoal cartridge and particulate filter-were analyzed for gamma emitters using gamma spectroscopy. The determined radionuclide concentrations and effluent volume discharged were used to calculate the previous-week's activity released.

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The particulate. samples were compot ted and analyzed quarterly for Sr-89 and Sr-90 by a contract laboratory (Teledyne Isotopes).

Particulate gross alpha act.ivity was measured eekly using alpha scintillation counting techniques. The determined activities were used to estimate effluent' concentrations in subsequent releases until-the next scheduled analysis was

. performed..

I Grab samples of continuous and batch releases were analyzed monthly-for tritium. The determined concentrations were used to estimate tritium activity in subsequent raleases i

until the next scheduled analysis was performed.

2.4.3 Liquid Effluents i

For continuous releases, samples were collected weekly and analyzed using gamma spectroscopy.

The measured concentra-tions were used to determine radionuclide concentrations in the previous week's releases.

For batch releases, gamma analysis was performed on the sample prior to release.

For both continuous and batch releases, composite samples were analyzed quarterly by a contract laboratory (Teledyne 1sotopes) for Sr-89, Sr-90, and Fe-55.

Samples were composited and analyzed monthly for tritium and gross alpha using liquid scintillation and gas flow' proportional counting techniques, respectively. For radionuclides measured in the composite samples, the measured concentrations.in the composite samples from the previous month or' quarter were used to estimate released quantities of these isotopes in liquid effluents during; the current month or quarter.

The total radioactivity in liquid effluent releases was determined trom the measured and estimated concentrations-of each radionuclide present and the total volume of the effluent I

discharged.

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2.5 Batch Releases The summarization of information for gaseous and liquid batch releases is included in Table 1.

2.6 thiplanned Abnormal Releases During this reporting period, there were no instances of unplanned abunrmal releases.

3.0 GASEOUS EFFLUENTS The quantities of radioactive :.iaerial released in gr.2eous et fluents are summarized in Tables IA, Ib, and IC.

Note that there were no elevated releases, since all Waterford 3's release are considered to be at ground level.

The estimated total error in % is based upon several statistical uncertaintres due to sample counting, efficiency, voltue, etc.

4.0 LlQUID EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables 2A and 2B.

The estimated total error in % is based upon several statistical uncertainties dte to sample counting, efficiency, volume, etc.

5.0 SOLID WASTES The sununary of radioactive solid wastes shipped of fsite for disposal is

-listed in Table 3.

For certain waste forms Waterford 3 is now using volume reduction services provided by Scientific Ecol gy Group, Inc., Allied Technologies Group, and Alaron Corp.

These waste forms are identified in Table 3 and volumes reported reflect the volume of waste shipped of fsite, not final disposal volumes.

Final disposal volwnes are reported as they become available. The estimated total error in % is based upon several statistical uncectainties due to sample counting, efficiency, volume, etc.

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6.0 METEOROLOGIC C DATA The summary of the hourly meteorological data for this reporting period will be included on the Semiannual Effluent Release Report to, be submitted -

within'60 days after January 1, 1993.

7.0 ASSESSMENT

OF DOSES:

The sunanary of doses due to ' gaseous and liquid effluents for this reporting period will be includel in the Semiannual Effluent Release Report to be J

submitted within 60 days after January 1, 1993.

-8.0 RELATED INFORMATION 8.1. Changes to the Process Control Program No changes were made to the Process Control Program duing this-reporting period.

8.2 Changes to the Offsite Dose Calculation Manual l

A revision was made to the Waterford-3 Offsite Dose Calculation Manual.(ODCtt) during the period covered by this report.

l Environmental Thermoluminescent Dosimeter location-descriptions were l-updated, added requirement to analyze samples within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in ACTION 29 in table 5.6-1, corrected some typographical errors, and incorporated items from Revision 1, change 1.

A copy of the:0DCM is t

. included in Attachment 10.1.

8.3 Unavailability of REMP Milk Samp h s Due'to-the unavailability of three milk sampling locations within five kilometers 'of the plant,- Broad Leaf sampling is performed in accordance with ODCM Table _5.8-1.

Milk is. collected, when available,

_ f roni the control l location and three identified sampling locations 'as

' indicated in Waterford 3 Offsite Dose Calculation Manual, Attachment 6.14.

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8.4 Report of Required Effluent Ins t rument Inoperabi1ity ODCM Specifications 5.6.1.6 and 5.6.2.6 require the reporting, in the Semi-annual Radioactive Effluent Release Report of why d

designated inoperable instrumentation was not restored to operability within the t ime speci fien in the ACTION statement.

During the reporting period, there were no cases when instrumentation was not restored to operability within the time specified.

8.5 Activity Released via Secondary Pathways Secondary r elease paths previously identified ami discussed in prior Semi-annual Effluent Release Reports were continuously monit ored f or radioactivity.

The areas monitored were:

(1) the Hot Machine Shop Exhaust (AH-35), (2) Decontamination Shop Exhaust (AH-34), (3) the rah H&V Equipment Room Ventilation System Exhaust (E-41A and E-41B), and (4) the Switchgear/ Cable Vault Area Ventilation System (AH-25).

Continuous sampling for these areas is maintained in order to demonstrate the operability of installed treatment systems and to verify the integrity of barriers separating primary and setondary ventilation systems Sampling for these areas was limited to continuous particulate and iodine sampling and monthly grab noble gas s ampl. i n g. The activity released via these secondary pathways resulted from routine operations and remained below significant levels (1 1%

of annual Technical Specification limits).

No corrective actions are

required, Release data will be included on the report to be submitted within 60 days after January 1, 1993 for these areas.

8.6 Additional Information S.6.1 Reactor Coolant Svetem E-bar The most recent Reactor Coolant System E-Bar calculation yielded results of 1.1005 MeV/ Disintegration from a sample obtained on December 22, 1991.

Reactor Coolant System E-Pa.r is supplied for information only and is not used for effluent dose calculations W50897Hp 10

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8.7 Corrections to Semiannual Radioactive Release Report Corrections to Table 3 of Semi Annual Radioactive Release Report covering the period f rom July 1, 1991 te December 31, 1991 are presented in Attachment 10.2, These changes are due to submittal of actual burial volumes and activities from volume reduction and disposal facilities, which was not available when the last report was submitted to the Nuclear Regulatory Commission.

9.0 TABLES 1

Batch Release Summary 1A Semiannual Summation of all Releases by Quarter - All Airborne Effluents 1B Semiannual Airborne Continuous Elevated and Ground Level Releases 1C Semiannual Airborne Batch Elevated and Ground Level Releases I

2A Semiannual Summation of All Releases by Quarter - All Liquid Effluents 2B Semiannual Liquid Continuous and Batch Releases 3

Solid Waste Shipped Offsite for Disposal 4

Not Used (Reserved foc Meteorological Data) 10.0 ATTACHMENTS 10.' Changes to UNT-005-014, Offsite Dose Calculation Manual (103 sheets) 10.2 Correction to Table 3 of Semiannual Radioactive Release Report for July 1, 1991 to December 31, 1991.

Submitt.a1 of burial volumes and activities from volume reduction and disposal facilities.

(3 sheets)

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TABII 1 (1 of 1)

REPORT CATEGORY

BATCH PELEASE SlftHRY RELEASE POINT

ALL TYPE OF RELEASE

BATCH LIQUID Af0 CASE 0US PERIOD START TIME

0:00 FRS = 12:00AM JANUARY 1.1992 PERIOD Et0 Tit 1E

4367:59 HRS = 11:59PM JtkE 30.1992

.-..................... =-==

LIQUID RELEASES NtkEER OF RELEASES 69 TOTAL TIE FOR ALL kELEASES :

17741.0 MINUTES MAXltitt TifE FOR A RELEASE :

306.0 MIMJTES AVERAGE T!?E FOR A RELEASE :

257.1 MINUTES MINittfi Tite FOR A RELEASE :

192.0 MIRJTES AVERAGE STREAM FLOW 827282.3 GPM t

GASEDUS RELEASES NUMBER OF RELEASES 2

TOTAL TIME FOR ALL RELEASES :

1282.0 MIRITES MAXIMUM T!!E FOR A RELEASE :

1101.0 MlHUTES AVERAGE TIME FOR A RELEASE :

641.0 MlHLITES MINIMLkt ilE FOR A PILEASE :

181.0 MIMJTES

...........................................................==_

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TABLE 1A' (1 of 1) l 4

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i REPORT CATEGORY

SEMIAHHUAL SumATION OF ALL RELEASES BY QUARTER TYPE (F ACTIVITY

ALL AIR 80 rte EFFLUENTS REPORTlHG PERIOD

QUARTER 41 A@ QUARTER 4 2 INii

QUARTER 1 :0UARTER 2 :EST. TOTAL:

HOlRS

HDLRS

ERROR % i TYPE OF EFFLLENT 1-2160 2161 4344 :

A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE

CURIES

5.83E 02 : 2.86E 01 : 1.50E 01:

2. AVERACE RELEASE RATE FCR PERIOD :UCl/SEC

7.50E 01 : 3.65E 00 :

3. PERCENT (V APPLICABLE LIMIT 4-WA WA B. RA01010 DIES

1. TOTAL 1001 E-131

CURIES

4.21E-06 : 0.00E-01 : 1.50E 01:

2. AVERAGE RELEASE RATE FOR PERIOD :UC16EC

5.41E-07 0.00E-01 :

3. PERCENT OF APPLICABLE LIMIT 4

WA WA C. PARTICULATES

1. PARTICULATES(HALF. LIVES)0 DAYS) : CURIES

5.05E-06 : 4.87E-07 : 1.50E 01:

2. AVERAGE RELEASE RATE FOR PERIOD :UC!/SEC

6.50E-07 : 6.20E-08 :

3. PERCENT OF APPLICA8LE LIMIT 4

WA WA

4. GROSS ALPHA RA010 ACTIVITY

ClRIES

2.75E-06 : 7.71E-06 :

D. TRITIUM

1. TOTAL RELEASE CLRIES

-9 E E 01 : 1.14E 02 : 1.50E 01:-

2. AVERAGE RELEASE RATE FOR PERIOD :UCI/SEC

1.22E 01 1 1.45E 01 :

3. PERCENT OF APPLICA0LE LIMIT WA 2

WA l

I I

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TABLE IB (1 of 1)

REPORT CATEGORY

SEMIMHR AIR 80RE CONTlWOUS ELEVATED #0 GROL}0

LEVEL RELEASES. TOTALS FOR EEH HUCLIDE RELEASED.

TYPE OF ACTIVITY

FISSION GASES.1001ES. 40 PARTICtLATES REPORTING PERIOD

QUARTER 4 1 #0 QUARTER 4 2 ELEVATED RELEASES : GR0l}0 RELEASES :

LNIT

00ARTER 1 :0UARTER 2 :0UARTER 1 :0UARTER 2 :

HOURS

. HOURS

H0lRS

H0lRS WCLIDE 1-2160 :2161 4344 :

1-2160 :2161-4344 :

FISSION GASES KR-85M CURIES : 0.00E-01 : 0.00E.01 : 1.43E 01 : 0.00E-01 :

KR-87

CtRIES : 0.00E-01 : 0.00E-01 : 4.41E 00 : 0.00E-01 :

XE-133

. CLRIES : 0.00E-01 : 0.00E.01 2 3.57E 02 : 2.16E 01 :

XE.135

CUR!ES : 0.00E-01 : 0.00E-01 : 1.67E 02 : 6.46E 00 :

AR.41

CURIES : 0.00E-01 : 0.00E-01 3.65E 01 : 0.00E-01 :

TOTAL FOR PERIOD

CLRIES : 0.00E-01 1 0.00E.01 : 5.79E 02 : 2.81E 01 :

100lHES 1-131

CLRIES : 0.00E-01 : 0.00E-01 4.21E-06 0.00E-01 :

PARTICLLA1ES H-3

CURIES : 0.00E-01 : 0.00E-01 : 9.43E 01 : 1.14E 62 :

C0-58

CURIES : 0.00E-01 : 0.00E-01 : 4.86E-36 : 0.00E.01 :

CS-137

CLRIES~: 0.60E-01 : 0.00E-01 : 1.94E.07 : 4.87E-07 :

S ALPHA

CtRIES : 0.00E-01 : 0.00E-01 : 2.75E-06 : 7.71E-06 :

TOTAL FOR PERl00

CLRIES : 0.00E-01 : 0.00E-01 : 9.43E 01. 1.14E 02 :

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TAllLE IC (1 of 1)

REPORT CATEGORY

SEMIANHUAL AIR 90RT BATCH El.EVATED A@ GROLIO

LEVEL RELEASES. TOTALS FOR EACH NUCLIDE RELEASED.

TYPE OF ACTIVITY

FISSION GASES.1001ES. A@ PARTIClLATES REPORTlHG PER100

OtrRTER 41 AfD QUMTER 4 2

$~~kLkhbT[bl[1.E EE~~$~~hElib~~lkLkI[E5"$

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UNIT

Ol#RTER 1 :0tyRTER 2 :00ARTER 1 : QUARTER 2 :

HOURS

HOLRS

HOLR$

H0lfG NUCLIDE 1-2160 :2161 4344 :

1-2160 :2161 4344 :

FISS!0H GASES KR-95M

CLRIES : 0.00E-01 : 0.00E-01 : 1.40E 02 : 0.00E.01 :

XE.133

ClRIES : 0.00E-01 : 0.00E.01 1 3.17E 00 : 4.85E-01 :

XE.135

CLRIES : 0.00E.01 1 0.00E-01 : 3.01E.01 : 1.31E-02 :

rR.41

CtRIES : 0.00E-01 : 0.00E.01 : 2.83E-01 : 9.12E-02 :

TOTAL FOR PERIOD

CLRIES : 0.00E-01 : 0.00E-01. 3.77E 00 : 5.89E-01 :

............... = = - -.

100lNES NOW PARTICtLATES H.3

CURIES : 0.00E.01 : 0.00E-01 : 2.37E-01 : 0.00E-01 :

.=

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4 TABLE 2A (1 of 1)

REPORT CATEGORY

! SEMIMNUAL SumAT10N Or ALL RELEASES Bf 004RTER TYPE OF ACTIVITY

ALL LIQUID EFFLUDUS REPORTING PERl(D

QUARTER 41 #0 QUMTER 6 2 UNIT 200ARTER 1 :0UARTER 2 IEST. TOTAL:

HOLRS HOURS

ERROR % :

TYPE OF EFFLLENT 1-2160 :2161 4344 :

A. F!SS!0H # 0 ACTIVATI N P900LETS

1. TOTAL RELEASE (NOT INCLLOlHG TRIT!UN. GASES ALPHA)

ClRIES

2.13E-01 : 9.94E-02 : 1.50E 01:

............................. ~ - - - -

-2. AVERACE DILUTED CONCENTRATIDH DURING PERIOD

UCl/ML

9.35E.09 3.03E.09 :

3. PERCENT OF APPLICABLE LIMIT t

4 N/A N/A B. TRITIUM

1. TOTAL RELEASE

CLRIES

1.73E 02 : 1.22E 02 : 1.50E 01:

2. AVERAGE DILUTED CONCENTRATION DLRING PERIOD IUCI/ML t 7.59E-06 3.71E.06 :

3. PERCENT OF APPLICABLE Linii N/A N/A

........................... =

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES

-: 5.71E-02 : 2.32E.01-: 1.50E 01:

2. AVERAGE DILUTED C(NCENTRATION DURING PERIOD

tCl/ft i 2.51E-09 : 7,00E-09 :

3. PERCENT J APPLICABLE LIMIT N/A N/A

.=_

D. GROSS ALPHA RADIDACTIVITY

1. TOTAL RELEASE

CURIES

0.00E-01 : 0.00E-01 : 1.50E 01:

=.......................................... -........................

E. WAS E VOL RELEASED (PRE-DILUTION) : GAL

3.87E 05 : 4.26E 05 : 1.50E 01:

F. VOLUME OF DILUTION WATER USED

GAL

6.02E 09 : 8.66E 09 : 1.50E 01:

W50897HP 16

TABLE 2B (1 of 2)

REPORT CATEGORY

SEMINNUAL LIQUID CONTINUQUS AHD BATCH RELEASES

TOTALS FOR EACH HUCLIDE RELEASED.

TYPE OF ACTIVITY

ALL RA010t0CLIDES REPOR11NG PER100

3.lARTER 41 AND OlyiRTER 4 2

COHTINUOUS RELEASES BATCH RELEASES :

UHli

QUARTER 1200ARTER 2 :00ARTER 1 :DUARTER 2 :

l

WLRS

HOURS

HOLRS

WLRS L

WCL1DE 1 2160 :2161-4344 :

1-2160 12161-4344 :

ALL HUCLIDEC

..................~.........................................................

H.)

CLRIES : 0.00E-01 : 0.00E-01 : 1.73E 02 : 1.22E 02 :

NA-24

CWlES : 0.00E-01 0.00E-01 : 1.06E-04 : 0.00E.01 :

CR-51

CLRIES : 0.00E-01 0.00E-01 : 7.08E-02 : 9.81E-0?

i NH-54

CURIES : 0.00E-01 0.00E-01 : 1.72E.03 1.91E-G3 i FE.55

CLRIES : 0.00E-01 : 0.00E-01 : 6.83E-03 : 9.54E-03 :

FE-59

CLRIES : 0.00E-01 1 0.00E.01 6.68E-03 : 3.27E-04 :

CD-50

ClRIES 0.00E-01 : 0.00E-01 : 4.59E-02 : 1.90E-02 :

CD-60

CURIES : 0.00E-01 : 0.00E-01 : 7.14E.03 : 1.41E-02 :

SR-92

CLRIES : 0.uCE.01 0.00E-01 : 2.57E-05 : 1.14E.04 :

ZR-95

CtRIES : 0.00E-01 : 0.00E-01 : 8.83E-03 : 2.05E-03 :

ZR-97

CLRIES : 0.00E-01 0.00E-01 : 1.53E-05 1.36E-05 :

NB-95

CURIES : 0.00E-01 1 0.00E-01 : 1.10E-02 : 3.37E-03 :

NLM9

CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 8.80E-05 :

TC 99M

CtRIES : 0.00E.01 0.00E.01 2.95E-04 : 1.68E-04 :

RU-103

CtRIES : 0.00E-01 : 0.00E-01 1 4.04E-04 : 0.00E-01 :

RU-106

CLRIES : 0.00E.01 : 0.00E-01 : 0.00E-01 4.63E-04 :

AG-110N

CLEIES : 0.00E-01 : 0.00E-01 : 3.4aE-04 : 1.05E-03 :

TE-132

CWlES : 0,00E-01 : C.00E-01 : 1.07E-04 : 0.00E-01 1-131

CtRIES : 0.00E-01 : 0.00E-01 : 1.14E-03 : 3.96E-03 :

1-132

CWlES : 0.00E-01 : 0.00E.01 : 1.35E-04 : 2.02E-05 :

1 133

CLRIES : 0.00E-01 : 0.00E-01 : 4.76E-04 : 2.36E-03 :

l-135

CURIES : 0.00E-01 : 0.00E-01 : 6.03E-05 : 3.85E-04 :

1 CS-134

CLRIES

• 0.00E-01 : 0.00E-01 : 1.12E 04 : 3.18E-04 :

k-CS-137

CURIES : 0.00E-01 : 0.00E-01 : 1.11E-03 : 1.30E-03 :

BA-139

CLRIES : 0.00E-01 : 0.006-01 : 0.00E.01 : 3.27E-05 :

LA-140

CWlES : 0.00E-01 : 0.00E-01 : 4 57E-03 : 1.08E-04 d[N41

CURIES : 0.00E-01 : 0.00E-01 : 5.70E-05 : 0.00E-01 :

144

CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.81E-04 :

W50897HP 17

6 TABII 2B (2 of 2)

REPORT CATEERY

SEM14NJAL LIQUID CONTIRDUS Am DATCH RELIASES

TOTALS FOR EACH RICL10E RELEASED.

TYPE OF ACTIVilY

ALL PMICHILIDES REPORTitlG PERIOD-1 0LARTER 4 1 NO QUARTER 4 2

CONTINU0US RELEASES :

BATCH RELEASES

'Nli

0lMRTER 1 :0UARTER 2 :0UARTER 1 :00ARTER 2 :

HOLRS

HO' R$

H0lRS H0lRS J

i NUCLIDE 1

1 2160 :2161-4344 1 2160 12161 4344 :

1 l

ALL RELIDES CINTIRED W.187

ClRIES : 0,00E-01 0.00E.01 : 1.55E.04 : 1.56E.04 :

KR-85M

CLRIES : 0.00E.01 : 0.00E.01 1.97E.05 3.51E.05 :

XE.131M CLRIES : 0.00E.01 : 0.00E.01 : 0.00E-01 : 1.81E.03 :

XE-133M

CLRIES : 0.00E.01 : 0.00E-01 : 5.36E-04 : 2.00E-03 :

XE.133

. ClRIES : 0.00E.01 1 0.00E.01 : 5.08E.02 2 2.24E.01 XE.135

CLRIES : 0.00E-01 0.00E.01 5.80E-63 4.03E-03 :

C0-57

CLRIES : 0.00E-01 : 0.00E.01 : 5.86E.05 : 2.76E-05

- % 124

CLRIES : 0.00E-01 : 0.00E.01 1 4.82E.0) 1.12E-03 :

SH.113

CtRIES : 0.00E.01 0.00E.01 : 1.08E.03 3 3.64E.04 :

N8 97

CLRIES : 0.00E-01 : 0.00E 01 : 9.30E-04 1.40E.03 :

% 122

C'"JIFS : 0.00E-01 : 0.00E 01 : 2.41E.03 : 4.46E.05 :

58-125

CLRIES : 0.00E-01 : 0.00E-01 3.52E-02 : 2.56E.02 :

% 127

CLRIES : 0.00E-01 : 0.00E-01 : 1.11E-04 0.00E.01 :

5 126 i CURIES 0.00E-01 0.00E.01 : 3.78E.04 : 0.00E-01 :

TOTAL FOR PERIOD

CtRIES : 0.00E.01 : 0.00E.01 : 1.73E 02 : 1.22E 02 :

4 W50897HP 18

l L

TABLE 3 L

-(1 of 12) p j.-

SOLID WASTE Sif1PPED OFFSITE FOR DISPOSAL DURING PERIOD 1/1/92 THRU 6/30/92 p

L 4

WASTE CONTAINER WASTE TOTAL

' TYPE VOLUME (fta)-

VOLUME-(m )

ACTIVITY (Ci)

ERROR 3

1;.

j.

- (B)Non Compacted Dry 1040 29.44 1.65E-2 *2 125%

i L

Active Waste e

[

Shipped to j-Scientific-Ecology

! Group for volume 3.12-1.20E-1

[--

reduction (Sea Land Burial Volume Furial Activity l-Container)*

l

- (B)No'n Compacted Dry 95 10.7 2.00E-4 *2

.125%

l Active Waste Shipped to l

Scientific Ecology Group.for-Folume Reduction (B-25 Box)*

L Waste volumes shipped for volume reduction do not reflect final burial I

waste. volumes, unless otherwise stated.

• 1 Activity determined by estimations.

l t-l

• 2 Activity determined by measurements.

~

L:

W50897HP-19

_f b

L.

2

.-......./

1.

1 TABLE 3 (2 of 12)

SOLID WASTE S1111' PED OFTSITE FOR DISPOSAL DURING PERIOD 6/1/92 THRU 6/30/92 WASTE CONTAINER WASTE TOTAL TYPE VOLUME (ft3)

VOLUME (m )

ACTIVITY (Cl)

LRROR 3

(B)Non-compacted 120.3 3.06 1.03E+0 h2 125%

Dry Active Waste Shipped in a High Integrity Container (A) Liquid Waste 180.1 5.09 6.40E-1

• 2 125%

Management Dewatered Resin in a Carbon Steel Liner (CNSI Bead Resin)

\\

Waste volumes shipped for volume reduction do not reflect final burial waste volumes, unless otherwise stated.

• 1 Activity determined by estimations.

<2 Activity determined by measurements.

W50897HP 20

TABLF 3 (3 of 12)

SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 1/1/92 THRU 6/30/92 WASTE CONTAINER WASTE TOTAL TYPE VOLUME (ft3)

YOLUME (m )

ACTIVITY (Ci)

ERROR 3

(A) Mechanical Filters 120.3 0.34 8.54E+0

• 2 125%

Dewatered Shipped in a High Integrity Container (C)1rradiated 57.4 1,62 3.00E+3 h2 125%

Components, Control Rods, etc.

Waste volumes shipped for volume reduction do not reflect final burial waste volures, unless otherwise stated.

kl Activity determined by eatimations.

h2 Activity determined by measurements.

WS0897HP 21

1 TABLE 3 (4 of 12)

SOLID WASTE SilIPPED OffSITE FOR DISPOSAL DURING PERIOD 1/1/92 TIIRU 6/30/92 WASTE TYPE NUCLlDE NAME

% ABUNDANCE CURIES

<sufr-seuse e.e (B)Non Compacted Mn-54 1.88 3.11E-4 Dry Active Waste Fe-55 2.24 3.74E-4 Shipped to Scientific Co-58 71.18 1.18E-2 Ecology Grct.p for Co-60 3.76 6.24E-4 Volume Reduction Ni-63 8.99 1.49E-3 (Sea Land Container)

Cs-134 4.45 7.3BE-4 Cs-137 7.06 1.17E-3 11 - 3 0.41 6.72E-5 C-14 0.04 6.12E-6 TC-99 N/A LLD 1.12E-8 1-129 N/A LLD 1.28E-8 (B)Non-Compacted Mn-54 2.13 2.28E-4 Dry Active Waste Fe-55 2.54 3.16E-2 m

Shipped to Scientific Co-58 80.77 3.11E-3 Ecology Group for Co-60 4.27 1.66E-3 Volume Reduction Ni-63 10.22 3.70E-3 (B-25 Boxes)

CS-134 1.17 1.55E-7 Cs-137 1.86 2.06E-5 Ce-144 4.35 1.82E-5 11 - 3 0.03 4.67E-8 C-14 0.04 2.76E-4 Tc-99 N/A LLD 4.48E-8 I-129 N/A LLD 5.12E-8 W5089711P 22

-4 TABLE 3 (5 of 12)

SOLID WASTE SHIPPED OFFSlTE FOR DISPOSAL DURING PERIOD 1/1/92 Tl[RU 6/30/92 WASTE TYPE NUCLIDE NAME

% ABUNDANCE CURIES (B)Non Compacted Ma-54 3.20 3.26E-2 Dry Active Waste Fe-55 4.90 5.07E-2 Shipped in Co-58 32.40 3.35E-1 a High Integrity Co-60 8.90 9.18E-2 Container Ni-63 22.50 2.33E-1 Cs-134 9.50 9.84E-2 Cs-137 17.60 1.32E-1 H-3 1.00 1.03E-2 C-14 0.10 9.58E-4 TC-99 N/A LLD 1.12E-8 I-129 N/A LLD 1.28E-8 (A)Liquio Waste Mn~54 5.70 3.68E-2 Management Resin Fe-55 2.20 1 42E-2 Dewatered in a Co-58 8.00 5.18E-2 Carbon Steel Liner Co 60 37.60 2.44E-1 (CNSI Bend Resin)

Ni 63 5.20 3.40E-2 CS-134 13.20 8.54E-2 Cs-137 28.10 1.82E-1 H-3 0.10 3.93E-4 C-14 0.00 1.79E-4 TC-99 N/A LLD 4.80E-8 1-129 N/A LLD 1.12E-8 W50897HP 23

-. - - - - - - - - -... -. -. -.. ~ - -.-. -. ~ ~.

4; TABLE:3 (6 of.12)

SOLID WASTE SillPPED-OFFS]TE FOR DISPOSAL DURING PERIOD 1/1/92 THRU 6/30/92 1

WASTE TYPE NUCLIDE NAME.

% ABUNDANCE CURIES R

(A) Mechanical.

Fe-55 81.20 6.93E+0 Filters Dewatered-Co-58 1.90 1.59E-1 and' shipped-in_a Co-60 4.80 4.13E-1 High Integrity Ni-63 11.20 9,53E-1 Container Cs-137 0.10 5.65E-3 H-3 N/A LLD 4.00E-8 C-14 0.90 7.66E-2:

TC-99

'N/A LLD

.2.00E-8 I-129 N/A LLD 8.00E-9 Pu-238 0.00 7.85E-5 Pu-239/240 0.00 6.07E-5 Cm-243/244 0.00 1.21E -.

W50897HP-24

4....._.-c_--

- ~ _ _ _. _ _

n

>i i

.c TABLE 3 (7.of:12)

L i

SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 1/1/92 THRU 6/30/92 I.

I

-WASTE TYPE-

.NUCLIDE NAME

% ABUNDANCE CURIES 1 --

(C)1rradiated Mn-54 1.20-3.61E+1 Components, 1Fe-55 14.20 4.26E+2 Control Rods,'etc.

Co-58 0.70 2.23E+1 Co-60 77.30 2.32E+3

[

-Ni-59 0.10 1.56E+0-NI-63 6.50 1.94Et2 Nb-94 10.00 7.33E-4 C-14 0.00 9.72E-2 Tc-99 0.00 1.92E-6 Pu-238 0,00' 1.49E-9 Pu-239/240 0.00 1.48E-9 Pu-241 0,00 1.67E-7 Am-241 0.00 4.59E-10 Cm-242 0.00 1.77E-8

.Cm-243/244 0.00 4.18E-9 J

'T i..

a L

i MiO897HP 25 V

4 4

9 %.,..,..,,,,y.--,,-,-w,.m,,,,,,,,.~..._..%..--_.,,-__.

. _ -... _ _ _ _ -,., - - +

.--s.

.. ~ -.. -.. ~ -.

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

7; 4

l TABLE 3-p:

. (8 of-12)-

.j o

SOLID W..STE SillPPED OFFSITE FOR DISPOSAL-1 DlIRING PERIOD 6/1/92 TIIRU 6/"J/92 i

i NUMBER OF SillPMENTS MODE OF TRANSPORTATION DESTINATION 1

-3' Scle Use Cask Barnwell, SC

-1 Sole Use Flatbed Oak Ridge, TN o-WASTE

1. OF.

TYPE OF CLASS SHIPMENTS TYPE CONTAINER MODE DESTINATION

'B 1-Type A Poly-IIIC Truck Barnwell, S.C.

-AU 1

-Type A Steel Liner Truck Barnwell, S.C.

-C' 1-Type B Steel Liner-Truck Barnwell,-S C.

AU

-1 LSA Strong-Tight Truck 0ak Ridge, T.N.

i i[

a i

f e

s e

\\

i W50897]IP 26 1

i l

-u.,a.. a.-,, _-.,... -. -,.... ~. -....

4 1

4 j

e p

TA111.E 3

)

(9 of 12) g 1

i

. SOLID WASTE SillPPED OFFSITE FOR DISPOSAL DURING PERIOD 1/1/92 'lllRU 6/30/92 i-I i

3

SUMMARY

BY MA.)0R WASTE TYPES i

9 2-i (A) Spenc Resins, filter Sludges, Evaporetor Bottoms, etc.

=

(D) Dry Compressible Waste, Contaminate d Equipment, etc.

)

i (C)

Irriaded Components, Control Rods, etc.

(D) 'Other (Vaste 011) t WASTE WASTE TOTAL f

3 TYPE VOLUME (M )

ACTIVITY (Ci)

ERROR 1

t (A) 5.43 9.19E40 125%

(B) 43.2 1.09E40-125%

r

.i.

(C) 1,62 3.00E+3 125%

(D)

NONE N/A N/A

- i t

i W5089711P 27

.,,..w~~_,._,.a,-.~r

...-.-.-i.

9 TAllLE 3 (10 of 12)

SOLID WASTE SillPPED OITSl'IE LOR DISPOSA1, DURING PERIOD 1/1/92 TilRU 6/30/92 SUlltlARY llY t1AJOR WASTE TYPI: (Cont'd)

WASTE TYPE NUCLil)E NAtlE 1 AliUNDANCl; CURll;S (ii)

Co-58 2.29 2.11E-1 Co-60 7.15 6.5 71;- 1 Ct,-134 0.93 8.54E-2 Cs-137 2.04 1.E8E-1 re-55 75.59 6.94f.+0 lin-54 0.40 3.68E-2 N1-63 10,74 9. 8 71;- 1 11 - 3 0.00 3.93E-4 C-14 0.84 7.68E-2 TC-99 0.00 6.80E-8 T-129 0.00 1.92E-8 Pu-238 0.00 7.850-5 Pu-239/240 0.00 6.07E-5 Cm-243/244 0.00 1.21E-4 W5089711P 28

TAltl.E 3 (11 of 12)

SOLID WASTE SilllTED OFFS 11E 1014 DISL >0 SAL DliltlNG PEll10D 1/1/92111110 6/30/92 Sti?N\\1(Y ltY liAJult WASTE TYPl. (Cont 'd)

WASlE TYPE NUCLIDE NA!!E

% A1:UNDANCE CUl(IES

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

(11)

Co-58 32.04 3.50E-1 Co-60 8.6.

9.4]E-2 Cs-134 9.08 9.91E-2 Cs-137 16.78 1.83E-1 Fe-55 7.57 8.270-2 Fin-54 3.07 1.31E-2 Ni-63 21.81 2.38E-1 Ce-144 0.00 1.820-5 11 - 3 0.95 1.04E-2 C-14 0.I1 1.24E-3 TC-99 0.00 6.72E-8 I-129 0.00 7.68E-8 W5089711P 29

TABII 3 (12 of 12)

SOLID WASTE SHIPPED OITSITE FOR DISPOSAL DURING PERIOD 1/1/92 THRU 6/30/92

SUMMARY

llY MAJOR WASTE TYPE (Cont'd) t.

WASTE TYPE NUClIDE NAME

% AllUNDANCE CURIES 1

I (C)

Co-58 0.74 2.23E+1 Co-60 77.33 2.32E+3 Fe-55 14.20 4.26E+2 Mn-54 1.20 3.61E+1 Ni-63 6.47 1.94E+2 i

Ni-59 0.05 1.56E40 Nb 0.00 7.33E-4 i

C-14 0.00 9.72E-2 Tc-99 0.00 1.92E-6 Pu-238 0.00 1.49E-9

-l Pu-239/240 0.00 1.48E-9 Pu-241 0.00 1.67E-7 Am-241 0.00 4.59E-10 Cm-242 0.00 1.77E-8 Cm-243/244 0.00 4.18E-9

+

F

^

W50897HP-30

_._._.;___._____.-.._._a_;_;._..,___.;_;-...

TAllLE 4 (1 of 1)

NOT USED (Reserved for Meterological Data) l l

l-l W50897HP 31 4

...mm-.

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

r, (l

l

^

ATTACllMENT 10.1 E. Li

'~

(103 SilEETS)

,r W

i i

P.

f:: ? :

i i

1

?

5 Clh 'GES TO'UNT-005-014, I

GITSITE DOSE CALCULATION MANUAL (ODCM)

January 1, 1992 To June 30, 1992 i

NOTE :

Procedure is copied on two sided paper.

.F I

l' l

i f.

l IW50897HP 32

--~

..~..

~

ATTACilMENT 10.2 (3 Slif:E'IS)

C01:1<ECT10NS TO "!AllLE 3 0F SEM1 ANNUAL ItADI0 ACTIVE RELEl SE ItEl' ORT July 1, 1991 to December 31, 1991 Submittal of Burial Volumes and Activities from Volume reduction and disposal facilities, r-l{

9 W5089711P 33

O l Alil.1; 3 (l of 10)

Sul.lD WASTI: SilllTI.D Orl Sill: I DH DISPOS Al.

Dl' RING l'l:R10D 7/1/91 TllRl! 12/31/91

]

WASfE CUNTAINER WAS I1.

TO'l AI, TYl'l:

Vol.l!!!f: (ft 3)

YOI.l'ME (md)

ACllVITY (Ci)

ERROR

~

(II) Noti Compacted Dry 104C 115.3 2.%E-1

?!

12 %,

Activity Waste Sltipped to Scientifit li.c ol o gy

(,8. 7 9 5.75E-1 125%

Group for Volume lharial Volume l;uried Activity Reduct. ion (11) Nori Compacted Dry 1040 117.79 I.15E-1 il 1251 Activity Waste Shipped to Alarch T(erp for Vo imie 12. 2 fs 1. 1.11: - 1 Reductinn butial Volume liuried Activity t

<h f h h o $$bk'b5 b7 l I l I.

oI VII kIllIe l l*( kk( I kIf k k ')

$IkI k I'

. I' b kkk$

Ikl [ d b s h It o l l):lle b tiil l e S S olberWiSe Stalfd.

'c l,,, lLivity det etmined by ( st imat ions, eg 42 Activity determined by measurements, i

W310526HP 21

,e' s

TAllLE 3 (2 of 10)

SOLID WASTE SillPPED OITSITE FOR DISPOSAL DURING PERIOD 7/1/91 TilRU 12/31/91 WASTE CONTAINER WASTE TOTAL 3

a TYPE VOLUf!E (ft )

V01.UFIE (m )

ACTIVITY (Ci)

ERROR (A) Resin Waste flanagement 170.8 4.8 2.97E+02

• 2 125%

Resin Dewatered in a liigh Integrity Container (Bead Resin)

(A) llechanical Filters 120.3 3.4 1.55E+02

• 2 125%

Dewatered Shipped in a liigh Integrity Container (A) Liquid-Waste ?!anagement 177.5 5.0 3.20E400

• 2 125%

Resin Dewatered in a Carbon Steel Liner (Bead Resin)

(D) Waste Oil Shipped to 7,5 2.97 1.78E-03

• 1 125%

Scientific Ecology Group for Incineration

• Incit.2 ra ted Incinerated l

• Waste volumes shipped for volume reduction do not reflect final burial waste volumes unless otherwise stated, l

l

• 1 Activity determined by estimations.

l

• 2 Activity determined by measurements.

l W31052611P 24

_ - _ _ _ _. _ _ - - _ _ _ _., _ _ _ __. _ _ _ _ _ _ _