ML20029A813

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Radioactive Effluent Release Semiannual Rept for Jul-Dec 1990
ML20029A813
Person / Time
Site: Waterford Entergy icon.png
Issue date: 12/31/1990
From:
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
W3F1-91-0033, W3F1-91-33, NUDOCS 9103040298
Download: ML20029A813 (45)
v • d • e


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s. Entergy tai 'ev comuaa

'ac-i Operations W31'l-91-0033 A4.05 QA re tit ua r y 28, 1991 U.S. Nuclear 1(egulatory Commission ATTN:

Document Control Desh Washington, D.C. 20555 Subject :

Waterford 3 SES Docket No. 50-382 License No. NPF-38 Semlannual Itadioactive Effluent llelease Iteport Gentlemen:

Enclosed in the subject report of effluent releases which encompat.ves the period of July 'l through December 31, 1990.

This report is submitted por Section 0.9.1.8 in the Waterford 3 'l'echnical Specifications (NUllEG-1117) of Appendix A to Faellity Operating Licenso No. NPF-38 and 10CFil50.30a(n)(2), pursuant to 10CFit50.4.

If you have any questions, plenso contact T.J. Gaudet at (504) 739-0000.

Very truly yours, l,l N C N f 11.F. Iturski Dirt 4ctor, Nuclear Safety itFB / DAlt /ssf Enclosure (w/ Enclosure) cc:

Mr. it.D. Martin, NitC llegion IV NitC Itosident inspectors Office (w/o Enclosure) ec:

Messrs. D.L. Wigginton, NitC-Nitil E. L. Illa h o lt.B. McGehoo lM[p

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i Semiannual Radioactive T.ffluent Helense Report l

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July 1, 1990. Dert niber 31, 1990 i

Waterford 3 l'ntergy Operat ions, Inc.

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TABLE 01' CONTENTS 1.0 SCOPE 2.0 SUpP11 MENTAL INr0101AT10N 2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Average Energy 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch keleases 2.6 Unplanned Abnormal Releases 3.0 GASEOUS ETTLUENTS 4.0 - LIQUID EITLUENTS s

5.0 SOLID WASTES 6.0 METEOROLOGICAL DATA 7,0 ASSESSMENT OF DOSES 7.1: Doses due to Gascous Effluents-7.2 Domes due to Liquid Effluents t

7.3 40 CFR Part. 190 Done Evaluation

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7.4---Doses to-Public Inside-the Site Boundary 8.0' RELATED INFORMATION 8.1 ~ Changes to the Process Control Program-8.2 Cnanges to the Offsite Dose Calculation Manual 1

8.3 Unavailability of REMP Milk Sampling 8.4 Report of Technical Specification Required Instrument Inoperability 8.5:- Activity Released via Secondary. Pathways-

- 8.6 - Missed Ef fluentJ Samples 8.7' Additional Information 8.8 Corrections to Semiannual Radioactive Release Reports-9.0--TABLES 10.0 ATTACl!MENTS V31052611P -

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' e, 1.0 SCOPE This Semiannual Radioactive l'.f fluent Release Report is submitted as required by Waterford 3's Technical Specification 6.9.1.8.

It covers the period from July 1, 1990 through December 31, 1990.

Information in this q

report is presented in the f ormat outlined in Appendix 11 of Regulatory Guide 1.21.

The information contained in this report includest (1) A summary of the quantitics of radioactive liquid and gaseous effluents and solid wastes released from the plant during the reporting period; (2) A summary of the meteorological data collected during 1990; (3) Assessment of radiatlon doses due to liquid and gaseous radioactive effluents released during 1990; (4) Explanation of why certain instrumentation was not restored to operable status within the time specified in the AL' ION Statement, as per Waterford 3 Technical Specification 3/4.3.3.10 6 8 3/4.3.3.11; (5) A discussion of missed samples required by Waterford 3 Technical Specifications 4.11.1.1.1 and 4.11.2.1.2; and, (6) A summary of the quantities of radioactive gaseous eliluents released from identified miscellaneous secondary release pathways for 1990.

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2.0 StiPPIDit'.NTAl. INI'OletATION 2.1 Regul a t o ry_1 f mi t s.

'the Technical Specificat ion 1.imit s applicable to the telease of radioactive material in liquid and gaseous effluents. ate described in the following sections.

2.1.1 l'ission and Artivation Gases (Noble Gases)

The dose rate due to radioactive noble gases released in gaseous cifluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mren/yr to the total body and less than or equal to 3000 mrrm/yr to the skin.

The air dose due to noble pses released in gaseous elfluents from the site to areas at or teyond the site boundary shall be limited to the following a.

During any calendar quarter:

Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta 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 lodines; Particulates, llalf Lives > 8 Days; and Tritium The dose rate due to lodine-l.M and 133, t ritium, 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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The dose to a member bf the public from lodine 131 and 133, tritium, and all radionuclides in particulate form with half lives greater than eight (8) days in gaseous cffluents relrake1 to areas at and beyond the site boundary shall be limited to the following:

a.

During any calendar qusrter:

1.ess than or equal to 7.5 mrtm to any organ and, b.

During any calendar year:

1.ess than or equal to l$ mrem to any organ.

2.1.3 1,1 quid Effluents The concentration of radioactive material released in liquid ef fluents to enrest ricted areas shall be limited to the concentrations specified in 10 CI'R Part 20, Appendix D, Table ll, Column 2 for radionuclides other than dissolved or entrained noble gabes.

I'or disbolved or ent rained noble camen, the concentration shall be limited to 2.00-4 pCi/ml total activity.

The dose or dose conur.itment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas enail 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 $ mrem to any organ, and b.

During any calendur year to less than or equal to 3 mrem to the whole body and to ler.s than or equal to 10 mrem to any organ.

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2.1.4 tiranium fuel Cycle Sources

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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 from_ uranium fuel 1

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cycle sources shall be limited to less than or equal to 25

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mrem to the total body or any organ (except the thyroid, I

f which shall be limited to less than or equal to 7$ mrem) over i

12 consecutive months.

t 2.2 Maximum Permissible Concentrati.ono l

i 2.2.1 rission and Activation Cases; lodines; and Particulates, llalf

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Lives > 8 Days For gaseous effit.cnts, maximum permissible concentrations are j

not directly used in release rate calculations Nince the j

4 applicable limits are expressed in terms of dose rate at the site boundary.

2.2,2 Liquid Effluents 1

The maximum permissible concentration (MPC) values specified in 10 CFR Part 20, Appendix B, Table II, Column 2 are used as the parmissible concentrations of liquid radioactive effluents 1

at. the unrestricted area boundary. A value of 2.0E.4 pC1/ml is used as the HPC for dissolved and entrained noble gases b liquid effluents.

2.3 Average Energy,

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This is not applicable to Waterford 3's Radiological Effluent Technical Spe';ifications. E-Bars are not required to be calculated ~

=from effluent release data.

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a 2.4 Ligasurge!!R ani_A}Trginalions of Tot J Hadioactivit1

'Ibe quantificntion of radioactivity in liquid nd gasr ) s ofIluentt, was acct 3;aplished by performing the sampling nd radiol %: cal analysis of ef fluent s in accordrince with the requireinents of Tables. 4.11-1 and 4.11-2 of k'aterf ord 3's Technical Specif icativas.

2.4.1 Finnion and Activation Gases (Nome Cases) for continuous releases, a gas grab snaiple was anab red monthly for nobic gares.

Each week a Gas Ratio (GR) was calculated according to the fo1* lowing equation:

CR n Average k'eekl L oble Gao rionitor Reading N

tionitor Reading lharing Noble Gas Sampling i

The monthly sample analysis and weekly Las Hatio vere then used to determine noble gases discharged continuously for the previous week.

Ibr gas decay tank and containment purge batrh releases, a pas grab sample vari analyzed prior to release to det ermine noble gan v.oncentrations in the batch, in all cases the total radtonttivity in gaseous effluents was determined from measured concentrations of each radionuclide present and the total volutue discharged.

2.4.2 Iodines and Part iculates Iodines and e articulates discharged were tompled us.ing a continuous sorepler which contained a charcoal cartridge and a particulate filter. Y,ach week the charcoal cartridge and particulate filter were analyzed for gamma enitters using garama spectroscopy.

The determitied rudionuclide concentrations and elfluent volume discharged were used to calculate the i

previous veck's cetivity released.

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j The particulate.esmp1bs were composited and analyzed quarterly I

for St-89 and St-90 by a contract laboratory (Teledyne Isotopes).

f Particulate gross alpha activity was measured veckly using

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alpha scintillation counting techniques.

The determined q

i activities were used to estim<te effluent concentrations in subsequent releases until the celt scheduled analysis was I

performed.

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l Orub samples of continuous and batch reletsen were analyzed f

montb,y f or t ritium. The determined conece'. rations were und to estimate tritium activity in subsequent releases unt I tar next scheduled anilysis was pertemed.

P 2.4.3 Liquiu v U l a;'..t s 1

For f v ;inuvos releases, samples were collected weekly and analy ed using gamma spectroscopy. The measurac concentra-I cions were used to determine radionuclide concen'.' $;4ons in the previous week's releases.

For batch releasek, pea analysis was performed on the sample prior to relea d.

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N r 60th sntinuous and batch releases, composite samplet wer ana1 n 4 quarterly by a contract laboratory (%1edyne

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Isotopes) ( er Sr-89, Sr-90, and re-55.

Sampler were comps etod and analyr.ed monthly for tritium and grost, alpha using liquid i

- scint.{l htion-end gas flow proportional counting techniquea, respectively. For radionuclides measured in the composite saruples, t.he measured concentrations'in the composite samples him the previous month or quarter were used to estimate re M 3ed quantities of these isotopes in liquid effluents during t e current psnth or quarter.

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~ each radionuclide ps'sent and the total volume of the effluent discharged.

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C 2.5, Batch Heleases A summary of information for gaseous and liquid batch releases

'ir included in Table 1.

2.6 Unplanned Abnormal Re3 eases

' During this. reporting perio6, there were three instances of Unplanned Abnormal releases:

An unplaraed, but monitored, release from Gas Decay Tank '0 ;

A boric Ad'6 Conder.eate Tank 'D' telease tenninated by thC Radiation Monitor;

.Discorery of radioactivity in a sink drain aligned to a non-radioactive syst<;m.

These incidents are discussed in the following sections.

2.6.1 Unplanned Release-From the Gaseous Waste Hanagement System At 0525-on September 3, 1990, Waterford-3 was at 100% power when an unplanned release of Gas Decay Tank (GDT) 'C' occurred dering atrelease of GDT-'B'.

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Description of-Event:'

On September 3 - 1990, at 0525 a release of GDT 'B' conunenced.

Approximately 55 seconds later, the Gaseous Waste Management (Gkti) system ef fluent radiation monitor (PRM-1RE-0648) term-innted the release on high alarm. An alert -alarm was also received on both Plant Stack Radiation Mona tors just prior to the release being secured. The pre-release total noble gas activity in GDT 'B' was 4.773E-1 uCi/ce.

A sample from GDT 'B' after termination of the release indicated a total noble gas-activity of 4.150E-1 uCf/ce; thus, the samples were in agreement. A sample obtained from GDT 'C' after the radiation monitor high alarm had a total noble gas activity of 8.601E-1 uCi/cc.

Control Room personnel noted that 8.00E-1 uCi/ml was the maximum value that the Gk?! radiation monitor indicated after isolation of t.he release. This value observed in the Cont rol Room corresponds to the activity level of GDT

'C'.

Also, this activity corresponds with the highest recorded value of 7.14E-1 uCi/cc from the alarm history of the GWH Ef fluent Radiation Monitor (PRM-IRE-0648),

it appeared that,-due to leaking isolation valves, a portion of GDT 'C' was released along with GDT 'o'.

Conservative calculations were performed

. to determine if Technical Specification limits were exceeded at the time of release isolation. The instantaneous dose rates due to noble gases were determined to be: 29.1 mrem / year to the Total Body (5.8% of the limit) an'd, 69.7 mrem / year to the Skin (2.3% of the limit).. Licensee Event Report #90-013 was generated to document the partial release of-GDT "C" without a pre-release sample as required by Technical Specification Table 4.11-2.

Cause of Eventi The-likely cause-for this event is internal seat leakage of the discharge isolation valves GWM-305C and GWM-30510.

Internal leakage of the-discharge isolation valves could have l-caused a small volume of unsampled gas to be released from GDT

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'C' during the 55 setand gaseous release from GDT

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  • Corrective Actions:-

Work' Authorization 001063948 was initiated to investigate if GDT 'C discharge isolation valves GWM-305C and GWM-3051C have internal seat leakage and will be completed prior to the end of Refuel IV (May 1, 1991). All other possible paths of internal gaseoua leakage to the GWM discharge header will also be investigated.

Administrative-controls are currently in-place which require that all GDTs are sampled prior to any-reletse from the GWM system. These controls will remain in e'fect until the GWM system leakage is identified and corrected.

Actions Taken to Prevent Recurrence:

Design' Change #3091 proposes a long. term solution to the GWM-system leaking valve problem by replacing _ carbon steel piping and valves that are susceptible to corrosion with stainless

. steel components.

Stainicas steel components should improve the performance and reliability of tank isolatfor, capabilities.

2.6.2. Radiation Monitor Alarm During Liquid Release During release of Boric Acid Condensate' Tank 'D' (BACT D) on September 10, 1990, the effluent radiation monitor

.(PRM-IRE-0627)- for this release point terminated the v alease lafter receiving a high alarm signal.

At no time were any l

Technical Sptcification limits exceeded.

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Description of Event:

During a release of BACT 'D' to the circulating water system, the. release was terminated by a radiation monitor high alarm.

The radiation monitor setpoint was 1.00E-2 uCi/ml as per the Radiation Monitoring System Data Base Manual.

The Boron Waste Management (BWM) radiation monitor (PRM-1RE-0627) reading reached 8.55E-2 uCi/ml during the alarm condition and subsequent termination of the release. This value is below the maximum allowable setpoint of 3.469E-1 uCi/ml, as calculated per the ODCM. Additional waste water was added to the tank, aftt. the release, before sampling was performed.

In addition, the radiation monitor was purged and another BACT was aligned and released before a sample from the BWM radiation monitor was obtained. Therefore, no samples were obtained from BACT 'D' or from the radiation monitor to determine the i

validity of the alarm condition.

Potential Reportable Event

  1. 90-051 documents this event.

Calculations were done to ensure that Technical' Specification

-limits were not exceeded.

Results of the calculations revealed that all allowable concentrations and doses in unrestricted areas were within Technical Specification limits. A release permit (LB-90122) was generated to document the additional activity released and the corresponding additional _ doses.

The highest additional dose was_2.20E-5_ mrem to the adult gastrointestinal tract.

Causeaof Event:

Since followup actions were not adequate to determine if an -

electronic fluctuation or increased activity ceused the alarm-and subsequent. termination of the release, it was assumed that increased activity caused the: alarm.

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Corrective Action:

None. No attempt was made to restart the release from BACT j

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Actions Taken to Prevent Recurrence:

The administrative setpoint specified in HP-001-235, Calculation and Adjustment of Radiation Monitor-Setpoints, was established as the default computer setpoint for BWM releases. The new l

setpoint of 1.25E-1 uCi/ml was determined using a standard nuc1:de mixture at a level to ensure effluent concentrations do not exceed the limits of 10CFR20 Appendix B.

This value is used as the high alarm setpoint if the release specific setpoint, as per the OCDM, is a higher value.

Health Physics procedures for liquid release permits, HP-001-231,

-Liquid Radioactive Waste Release Permit (Manual), and HP-001-233,-

Liquid Radioactive Waste' Release Permit (Computer), have been revised to include instructions for actions required upon release termination by a radiation monitor alarm. These instructions will

-direct Health Physics personnel to initiate a Potential Reportable Event (PRE) for documentation and tracking, sample the affected tank and radiation monitor, and generate radiation monitor trend and alarm history printouts. This information will tur used to determine the validity _ of:the alarm and appropriate course of l

action.

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_2.6.3 Improper Usage of Sink Dra*in

- During implementation of Design Change #3177, a small amount of radioactive-water was discovered in the sink drain trap. The sink drain was aligned to the. sanitary system, a non-radioactive system.

Description of Event:

~ A sink installed in the -4 Reactor Auxiliary Building (RAB), serving an area that was being used as the -4 RAB Health Physics Counting Room, was determined to be of some risk to introduce radioactive water to a non-radioactive system. Design Change #3177 rerouted t.he sink drain to the radioactive Liquid Waste Management (LWM) System. During implementation of the design change, some water was collected from the drain trap and analyzed by: Health Physics.

The water contained the following nuclides :

CS-137, 1.556E-7 uCi/ml and CO-60, 2.081E-7-uC1/ml. Releases of' radio-active water via-the sanitary system is not allowed as per Technical

Specification' Table 4.11-1.

Sanitary system liquids are discharged to the Metal Waste Pond located'at Waterford 1 & 2 and the sludge is removed by truck. Trucks containing_

sanitary system sludge are_ sampled prior to allowing them to exit the

_ protected area.. No radioactive materials have been found in these. trucks.

Calculations were performed to determine the effect of releasing a one liter ~

L Waste Condensate Tank sample via the. sanitary system and Metal Waste' Pond to. the Mississippi River. The~ critical' organ doses calculated. from -

this' release resulted in: 5.47E-4 mrem to the liver (0.005% of the annual

< limit),;1.06E-5 mrem to the_ gastrointestinal tract (0.0001% of.the. annual-l limit), and 7.77E-6 mrem to the thyroid (0.0001% of the: annual' limit). Also, radionuclide concentrations in the effluent from the metal waste pond 4

would be well within the allowed limits of 10CFR20.- Since these doses-I represent small fractions of the allowable doses, the effect of disposal

' of_ a radioactive sample accidentally via the sanitary system would be L

insignificant and, therefore, would have_no effect on the public's health and safety.

W310526HP 13

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Cause of Event:

i The root cause of this event was personnel error. The sink was posted with a sign stating "NON-RADIOACTIVE SINK" prior to plusging the drain. The sink drain was plugged to prevent all liquids from entering the sanitary system in approximately mid-year 1987.

It is believed that, prior to plugging the sink drain, a radioactive sample was erroneously poured into the sink.

A contributing cause was that the sink drain should have been routed to a radioactive waste system to reduce the possibility of an accidental release of radioactive materials to the sanitary system.

The room that the sink serves was not originally designed to be a counting retm.

Corrective Action:

Smear surveys for removable contamination were performed in the accessable portion of piping immediately down stream of the sink drain trap.

No contamination was found.

The liquid collected from the sink drain trap was disposed of via the Liquid Waste rianagement System.

Action Taken to Prevent Recurrence:

Plant st.aff has completed the implementat. ion of Design Change #3177. Work in the -4 RAB Health Physics Counting Room was completed on November 8, 1990 and the sink drain is currently routed to the Liquid Waste Planagement system.

3.0 GASE011S EFFLUENTS The quantities of radioactive material released in gaseous ef fluents are summarized in Tables IA, IB, and IC.

Note that there were no elevated re-leases, since all Waterford 3 releases are considered to be at ground level.

The estimated total error in % is based upon several statistical uncertain-ties due to sample counting, efficiency, volume, etc.

Detailed statistical evaluations of error are not required as per Regulatory Guide 1.21.

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e 4.0 LIQUID EFFLUENTS The' quantities of radioactive material released in liquid ef fluents are summarized ~in Tables 2A and 2B.

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

Detailed statistical evaluations of error are not required as per Regulatory Guide 1.21, 5.0 SOLID WASTES The summary of radioactive solid wastes shipped offsite for disposal-is listed in Table 3.

For certain waste forms Waterford 3 is now using volume reduction _ services provided by Scientific Ecology Group, Inc. and 1

Alaron Corp. These waste forms are identified in Table 3 and volumes reported reflect the volume of waste shipped offsite, not final disposal volumes. Final disposal volumes are reported as they become available.

The estimated total-error in % is base.d upon several statistical uncertainties due to sample counting, efficiency, volume, etc.

Detailed statistical evaluations of error are not required as per Regulatory Guide 1.21.

-6.0~

METEOROLOGICAL DATA In Table 4 the hourly meteorological data from January 1, 1990 through

= December 31, 1990, is presented in the form of-joint f requency distribu-tions'of wind speed, wind direction, and_ atmospheric stability. The-LWaterford-3 data recovery results by parameter are as follows:

L i Parameter-January --June July - December-Entire' Year L

Delta T-99.0%

99.7%-

99.4%

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' Wind' Speed 98.3%

99.5%-

98.9%

' Wind Direction 98.3%

99.4%

98.9%

-Overall*

97.6%-

99.1%

98.4%

  • Simultaneous occurrence of valid data for all three parameters.

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7.0 ASSESSMENT

OF DOSES l

7.1 Dose Due to Gaseous Effluents 7.1.1 Air Doses at the Site Boundary Air doses from gaseous effluents were evalunted at the closest offsite location that could be occupied continuously during the term of plant operation and that would result in the highest dose.

This location was determined by examining the atmospheric dispersion parameters (x/Q's) at the closest offsite locations that could be continuously occupied during plant operation in each of the meteorological sectors surround-ing the plant.

The location that would have the highest dose would be that location having the most restrictave (largest)

X/Q value.

Based on actual meteorological data collected during 1990, this location was determined to be in the ENE sector at a distance of 966 meters from the plant.

Doses were assessed at t.his location in accordance with the methodology described in the Waterford 3 Of f site Dose Calculation Manual considering only beta and gamma exposures in air due to noble gas.

The results of these assessments for the year 1990 are summarized as follows:

Beta air dose:

2.77 mrad Gamma air dose:

1.01 mrad The beta and gamma air doses are 13.9% and 10.1% of the Annual Technical Specification Dose Limits, respectively. The results of the dose calculations by quarter are summarized in Table S.

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.3-7.1.2 Naximum Organ Dose to the Critical Receptor The. maximum organ dose to's MEMBER OF THE PUBLIC from 1-131, I-133, tritium, and all radionuclides in particulate form =

with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary was deter-mined for 1990.

An assessment of the maximum organ dose was performed for the critical receptor. The critical receptor was assumed to be located at the nearest residence to the plant having the most restrictive atmospheric dispersion (X/Q) and deposition (D/Q) parameters.

Furthermore, it was assumed that the receptor living at this residence consumed food products that-were either raised or produced at this residence. Using land use census and meteorological data for 1990, the residence with the highest X/Q and D/Q-values was determined-to be in the N sector at a distance of 1448 meters. The dose calcula-tion was' performed in accordance withithe methodology described

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in the Waterford 3 Offsite Dose Calculation Manual considering

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the inhalation, ground plane exposure, and ingestion pathways.

The maximum organ dose to the critical receptor was determined to be 0.63 mrem to the infant thyroid. This represents 4.2%

of the Annual Technical Specification Dose Limit.- Dose-

. calculation results are summarized by quarters in Table 5.

l 7.2 Doses Due to Liquid Effluents-i i

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The annual doses to the maximum exposed individual resulting from-L

- exposure to liquid effluents released.during 1990 from Waterford 3 l

l were 0.34 mrem total body:and 0.47 mrem to the maximum exposed organ (liver).'These values are 11.3% and 4.7% respectively, of the Annual

-Technical Specification-Dose Limits. Dose calculation results are summarized by quarters in Table 5.

The doses were calculated in accordance with the_ methodology described in the Waterford 3 Offsite Dose Calculation Manual.

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7.3 40 CFR Part 190 Dose Evaluation.

In accordance with Waterford 3 Offsite Dose Calculation Manual, Section 8.15, dose evaluations to demonstrate compliance with Surveil-lance' Requirements 4.11.4.1 and 4.11.4.2 of the Waterford Technical Specifications, dealing with dose from the uranium fuel cycle, need to be performed only if quarterly doses exceed 3 mrem to the total body (liquid releases), 10 mrem to any organ (liquid releases), 10 mrad gamma air dose, 20 mrad beta air dose, or 15 mrem to any organ from radiolodines and particulates.

At no time during 1990 were any of these limits exceeded; therefore, no evaluations were required.

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7.4 Doses to Public Inside the Site Boundary The Member of the Public inside the site boundary expected to have the maximum exposure due to gaseous effluents would be an employee at Waterford I and 2 fossil fuel plants, -located it, che NW sector, approximately 670 meters from the plant.

Based on an assumed occup-ancy of-25% (40- hour work week) and the fact -that all employees are adults, the maximum organ dose would be less than 0.024 mrem to the L

thyroid. Total body and skin doses were calculated to be 0.17 and-0.39 mrem, respectively. These doses were calculated according to.the methodology described in the Waterford 3 Offsite Dose Calculation g

l Manual considering only-the inhalation pathway.

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'.o changes to the Process Control Program for the period covered by this report.

8.2 Changes to the Offsite Dose Calculation Manual There were no changes made to the Waterford 3 Offsite Dose Calculation Manual during the period covered by this report.

8.3 Unavailability of REMP Milk Samples _

Due to the unavailability of three milk sampling locations within five kilometers of the plant, Broad Leaf sampling is performed in accordance with Technical Specification Table 3.12-1.

Milk is collected, when available, from the control location and three identified sampling locations as indicated in Waterford 3 Offsite Dose Calculation Manual, Table 2 and Table 3.

8.4 Report of Technical Specification Required Instrument Inoperability Technical Specifications, 3.3.3.10 and 3.3.3.11 requires reporting in the Semiannual Radioactive Effluent Release Report of why desig-nated inoperable instrumentation was not restored to operability within the time specified in the ACTION Statement.

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

W310526HP 19

..a

  • N 8.5 ' Activity Released Via Secondary Pathways i

Secondary release paths previously identified and discussed in previous-semi-annual effluent release reports were continuously monitored for radioactivity.

The areas monitored were:

1) the llot

-Machine-Shop Exhaust (AH-35), 2) Decontamination-Shop Exhaust (AH-34),

3) the RAB il&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 integrity of barriers separating primary and secondary venti-lation systems.

Sampling for these areas was limited to continuous particulate and iodine sampling and monthly noble gas grab sampling.

The activity released via these secondary pathways resulted from routine operations and remained below significant 1cvels. Table 6 contains a summary of activity released during 1990.

8.6 Missed Effluent Sampics:

8.6.1 No liquid effluent samples were missed during this reporting period. A gaseous effluent sample for Gas Decay Tank (GDT)

'C' was not obtained, before'the release of GDT

'C',

A

(-

discussion of this event is included in section 2.6.1 of this report.

8.6.2.A Waste Condensate Tank 'B' sample to be used in compositing was missing when the Liquid Waste Management (LWM) system 2 monthly composite for June,.1990 was prepared.1This event was reported in the last Semi-Annual Radioactive Release Report and in Licensee Event Report #90-009. :.The LWM composite had to be prepared using only the remaining samples.

The effect l.

of'the missing sample on the activity analysis was evaluated.

E Calculations were made using conservative estimates for Tritium,

-Sr-89, and Fe-55 activities. All additional calculated organ doses' were less than 0.001% of the quarterly Technical Specifi-cation-limits.

Since no abnormal situations or evolutions-occurred to the plant, it is likely that concentrations of Tritium, Sr-89/Sr-90, and Fe-55 remained constant. Thus, the calculations made were conservative and the health and safety of the public were not af fected.

W310526HP 20 1

8.7 Additional Information The most recent Reactor Coolant System E-Bar calculation yielded results of 1,4649 HeV/ Disintegration.from'a sample obtained on December 7, 1990. Reactor Coolant System E-Bar is supplied for information only and is not used for effluent dose calculat.fons.

8.8 Corrections to Semiannual Radioactive Release Reports 8.8.1 A correction to Semiannual Radioactive _ Release Report Table 2A for the period January 1, 1990 to June 30, 1990 is included in

-Attachment 1.

During review of 1990 release data and totals, it was noted that the waste volume reported was in error. The i

reason for the incorrect value to be specified in the report was a computer file oversight. Data used for liquid release LC-90016-was subtracted from the cumulative dose and isotope file._ During the Semiannual Radioactive Release Report generation program, waste volumes are summed from individual waste files that are within the time period of concern. The waste volume for LC-90016 was unintentionally included. ' The corrected value for waste volume also affected the reported average diluted concentrations for Fission and Activation

. Product *. Tritium, and Dissolved and Entrained Cases. This 7

correction does not affect-dose or isotope totals.

8,8.2 A correction to Semiannual Radioactive Release Report Table 3 -

for the period January 1, -1990 to June 30, 1990 is included in Attachment 2.

Samples submitted _for analysis yielded higher activities for Resin Waste Management Resin. - The new values' represent-cortected activities.

Also, final compacted volume is. reported for Non-Compacted Dry Active Waste Shipped to Scientific Ecology 0 oup-fo* ~olume reduction, since this information was recently.made avattable.

1 W310526HP 21

m___..

ue 9.0. TABLES m

l' Batch Release Summary 1A Semiannual Summation of all Releases by Quarter - All Airborne

-Effluents.

IB Semiannual Airborne Continuous Elevated and Grcund Lesel Releases 1C Semiannual Airborne Batch Elevated and Ground Level Releases 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

' Joint Frequency Distribution of Meteorological Data 5-Dose Calculation Results for 1990 6.

Activity Calculations for Secondary Release Pathways for 1990 10.0 ATTACHMENTS 1_

Corrections:to TABLE 2A of Semiannual Radioactive Release Report; January 1, 1990'- June 30, 1990. (2 pages) 2 Corrections to TABLE 3 of-Semiannual Radioactive Release Report; j

January 1,-1990 - June 30,-1990. (4 pages) l l'

o i.-

l -

h

. W31052611P.

22 I'

l I

l

-TABLE 1 I

(1 of 1)

I REPORTCATEGORY I MTCH RELEASE SUPT %RY RELEASE POINT IE-TYPE OF RELEASE I MTCH LIQUID MD OASEOUS PERIOD START TIE-4344 00 @S = 12:00AM JULY 1 1990 PERIOD DO TIE 8759:59 @ S = ll:59PM DECO 9ER 31 1990 1

s L10VIDRELEASES i

WMER OF RELEASES I

139 TOTAL TIME FOR ALL ELEASES 34911.0 MlWTES MAXIMUPt TIE FOR A RELEASE 301.0 MlWTES -

i AVERAGE TIME FOR A RELEASE I 251.2 MINUTES MINIMUM TIME FOR A RELEASE I 3.0 MIWTES l

AVERAGE STREAM FLOW I

024346.8 GPM GASEOUS RELEASES NUM E R OF RELEASES-t 3-TOTAL TIME.FOR E ELEASES '

649.0 MINIRES MA!!MUN TIE FOR A RELEASE 600.0 MINUTES AVERAGE TIE FOR A RELEASE

-?!6.3' MINUTES MINIMUM TIE FOR A RELEASE ' -

1.0 MINUTES i

I -

.W310526KP-23 l

TAB 12 1A l

(1 of 1)

REPORT CATEGORY I SEMIAWA, $UMMTION OF ALL RELEASES BY 0$ATER TYPE OF ACTIVITY t ALL AIR 90 rte EFFLUENTS REPORTINGPERIOD I 0#ATER 4 3 AND DJARTER t 4 t UNIT 10#ATER 3 IOJARTER 4 IEST.TOTAtt i

ItRRS naRS IERROR % i TYPE OF EFFllENT I

14345-6552 16553-8760 :

I A. FlSSION AND ACTIVATION PRODUCTS

1. TOTAL RELEA X CLRIES 2.32E 03 1.14E 03 1 1.50E Olt

=. _ _ _.

2. AVERACE RELEA X RATE FOR PERIOD IUCl/SEC 1 2.92E 02 1.43E 02 I
3. KRCENT OF APPLICABLE LIMIT I

i N/A I

N/A t

B. RAD 1010D!tES

1. TOTAL 10 DINE-131 ICLRIES
3.36E-05 6.64E-05 1 1.50E Olt
2. AVERAGE RELEASE RATE FCR PERIOD IVCl/SEC 4.22E-06 8.36E-06

.............. ~...... _........................................

3. PERCENT OF APPLICABLE LIMIT I

i N/A 1

N/A I

.....=

C. PARTICULATES

.......... = _--...=

1. PARTICIA.ATES(HALF-LlWS)8 DAYS) ICtRIES 2.17E-05 t 1.62E-05 1.50E 01:

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

_.=

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

2. AVERAGE RELEASE RATE FOR PERIOD IUCI/SEC I 2.73E-06 1 2.04E-06 I

=.......-

3. KRCENT OF APPLICABLE LIMli i

t N/A I

N/A 1

4. GROSS ALPHA RADIDACTIVITY ICURIES I 8.15E-05 1 3.64E-05I D. TRIT!UN
1. TOTAL RELEASE ICURIES t 6.07E 01 1 1.83E 01 : 1.50E 01:
2. AVERAGE RELEASE RATE FOR PERIOD tlCl/SEC 7.64E 00 t 2.30E 00 t
3. PERCENT CF APPLICABLE LIMIT I

i N/A 8

N/A t

W31052611P 24

0,.

4 c_

TABII 1B

+-

(1 of 1)

REPORT CATE00RY SEMIMUAL AIRir)RNE CONilWOUS El.EVATED AND OROUW t LEVEL RELEASES. TOTALS FOR EACH NLCLlDE RELEASED.

TYPE OF ACTIVITY t FISSION GASES 10 DINES AND PARilCtLATES REPORTING PERIOD QUARTER I 3 AND QUARTER 0 4 I ELEVATED RELEASES 1 OROUND RELEASES I I UN1i

QUARTER-3 IQUARTER 4 QUARTER 3 IQUARTER 4 I

IHOUR3 IHOWS HOURS IHOURS-I NUCLIDE I

4345-6552 16553-8760 4345-6552 16553-8760 FISSION CASES KR-82 CURIES 0.00E4110.00E4114.75E 001 1.84E 00 IE-133

CWlES I 0.00E-0110.00E-01 2.25E 03 1.09E 03 XE-135 CURIES I 0.00E-01 1 0.00E-01 1 6.57E 01 1 3.22E O!

TOTAL FOR PERIOD t CW lES t 0.00E-01 1 0.00E-01 2.32E 03 1.12E 03 I 9

100lNES 1-131

CWlES - t 0.00E-01 1 0.00E41 1 3.36E-051 6.64E-05 1-133
CURIES 0.00E-0110.00E41 0.76E-07 1 2.09E-06 I

TOTAL FOR PERIOD-I CUR!ES 10.00E-01 10.00E-01 3.45E-05 6.85E45 P

l PARTICULATES l

H-3

CURIES : 0.00E-01 1 0.00E 6.07E 01 1.79E 01 0 ALPHA-I CURIES - t 0.00E-01 10.00E41 t 8.15E-05 3. 3.64E-05 BR-82 CURIES I 0.00E-01 0.00E-01 8 2.17E-05 1.62E-05t l

TOTAL FOR PERIOD i CWlES 0.00E-0110.00E4116.07E 011 1.79E 01 l

-W310526HP 25

n.

(

'=

TABLE IC (1 of 1)

. REPORT CATE00RY I SOIIAPHJAL AIRBORIE BATCH ELEVATED 40 OROLND 1.EVEL RELEASES. TOTALS FOR EACH idjCLlDE RELEASED.

TYPE OF ACTIVITY FISSION OASES 10 DINES. f@ PARTICULATES REPORTINO PERIOD t QUARTER 0 3 MD GWARR 8 4 1 ELEVATED RELEASES I GROUhl) RELEASES I LN1T 1 QUARTER 3 IQUARTER 4 QUARTER 3 IQUARTER 4 i t}0URS IHOURS

! HOURS tH0lRS I

NUCLI0E 14345-6552 16553-8760 4345-6552 16553 4 760 I FISSION OASES KR-85M 8 CURIES I 0.00E41 10.00E-018 4.99E-05 8 1.37E-02 i KR-85 ClRIES I 0.00E-01 0.00E-0; I 4.12E-0310.00E-01 Ut t CURIES 10.00E 01 10.00E41 1 2.09E-05 t 0.00E-01 I.

XE-131M CURIES 0.00E-01-1 0.00E-01 1 3.56E-03 1 0.00E-01 XE-133M-1 CLRIES I 0.00E-01 1 0.00E-01 8 3.04E-031 1.49E-01 4 XE-133

CURIES 0.00E41 10.00E-018 4.60E-01 1.07E 01 1 XE-135
CtRIES ' i 0.00E-01 1 0.00E-01 1 1.79E-03 1 2.23E41 I AR-41 CURIES I 0.00E-01 1 0.00E-01 1 0.00E-01 1.21E41 :

TOTM. FOR PERIOD t CtRIES 0 00E-01 0.00E4114.73E41 t 1.12E 018 100!!ES NONE-PARTIClLATES--

It 3 4-CURIES 0.00E-01 1 0.00E-01 0.00E-01 1 4.2tE-01 I.

o i

W3105261[P 26

TABLE 2A (1 of 1)

REPORT CATE00RY SEM1AWJAL turt% TION OF ALL RELEASES BY QUARTER TYPE OF ACTIV!TY

ALL LIQUID EFFluiNTS REPORTINGPERIOD DARTER I 3 AND @JARTER I 4 I

LNIT 10)ARTER 3 IDJARTER 4 IEST.TOTAlt i

iHOU%

1WJURS ERR m 1 :

TYPE OF EFFLUENT I

14345-655216553-8760 t i

A. FISS!LN AND ACTIVATION PRODlITS

=.

1. TOTAL RCLEASE(NOT INCLUDING I

I I

t t

TRITIUM CASES. ALN m) 1 CURIES I 3.70E-01 1.88E-01 i 1.50E Oli

2. AVER G DILVTED CONCENTRATION t

i I

DURINGPERIOD IUCl/ML t 3.9AE-09 i 6.68E-09

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

3. PERCENT OF APPLICABLE LIMIT I

1 N/A I

N/A 1

B. TRIT!t.fi

1. TOTAL RELEASE ICURIES 4.90E 02 8.51E 01 1.50E Olt
2. AVERAGE DILUTED CONCENTRATION I

I i

1 DURING PERIOD IUCint.

t 5.30E-06 3.02E-06

3. PERCENT OF APPLICADLE LIMIT I

i N/A I

N/A I

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE ICLRIES 1.82E 01 1 3.88E 00 i 1.50E 011
2. AVER E DlLUTED CONCENTRATION I

I I

I DURINGPERIOD llCl#L i 1.93E-07 l 1.38E-07

3. PERCENT OF APPLICABLE LIMIT i

i N/A 1

N/A I

D. GROSS ALPHA RADIDACTIVITY

1. TOTAL RELEASE ICUR!ES
0.00E-01 1.05E-06 1.50E Oli

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

..=

E. WASTE V0L RELEASED (PRE-DILUT10tt) 10AL i 1.15E 06 1 4.59E 05 1.50E 01:

F. VOLUME OF DILUTION WATER USED 10AL i 2.4SE 10 : 7.45E 09 1 1.50E Olt 8

W310526HP 27 l

a TABII 2B (1 of 2)

REPORTCATE00RY I SOilAPRIAL LIQUID CONTlWJOUS Af0 BATCH RELEASES TOTALS Fm EACH KRIDE RELEASED.

TYPE OF ACTIVITY -

1 ALL RAD 1014)CLIIES EPORilND PERIOD QUARTER 4 3 AND QUARTER S 4 I CONTINUQUS RELEASES BATCH RELEASES I Wii QUARTER 3 10UARTER 4 19UARTER 3 QUARTER 4 :

I tHOURS IHOURS 1 HOURS HCIJRS t

  • EIDE 14345-6552 16553-8760 4345-6552 16553-8760 ALL NJCLIIES H-3 i CWlES i 0.00E-01 0.00E-0114.98E 02 8 8.51E 01 NA-24 i CURIES i 0.00E-01 10.00E-01 18.68E4510.00E41 CR-51 1 CURIES 0.00E-01 1 0.00E-01 I 1.83E-04 1 0.00E-01

'FN I CURIES 0.0(C-01 1 0.00E-01 1 4.16E44 1.64E44

'FE-55 CLRIES I 0.00E-01 1 0.00E-01 1.01E-02 1 9.72E-03 :

CO-58

CURIES 0.00E-01 1 0.00E41 1 6.93E43 1 1.06E-01 :

CO-60 t CURIES I 0.00E41 0.00E-01 14.77E4312.38E-031

-RB-88 CWlES t 0.00E-01 10.00E41 12.71E41 5.09E '

SR-89 CURIES I 0.00E-01 1 0.00E-01 1 2.38E-05 1 0.00E41 :

SR-92 i CURIES I 0.00E-01 1 0.00E-01 1 8.03E-05 1 2.64E45 ZR-95

CMIES I 0.00E-01 10.00E-01 t 1.17E4510.00E41 NB-95 CURIES 0.00E-01 1 0.00E-01 1 2.60E-04 1.BIE44 :

TC-99M t CW lES t 0.00E-01 1 0.00E-01 0.00E-01 1 4.32E-05 i RU-106 1 CLRIES 0.00E-01 1 0.00E-01 1.61E-05 t 0.00E-01 1-A0-110N

t. CURIES t 0.00E-01-t 0.00E-01 1 0.25E-04 1 1.51E-04 1 1-131 CURIES : 0.00E-01 1-0.00E-01 1 3.27E-05 1 2.44E-03 1-133 CURIES : 0.00E-01 1 0.00E-01 1 0.00E-01 1 4.44E-05 CS-134' CURIES -I 0.00E-01 1 0.00E-01 2.34E-02 8 2.05E-02 1

-CS-137

CWlES : 0.00E-01 10.00E-01 14.42E-02 t 3.61E-02 :

BA-139 i CURIES I 0.00E-01 : 0.00E-01 1 2.98E-04 1 0.00E-01 :

BA-140 CURIES 0.00E-01 1 0.00E 4 1 1 0.00E-01 1 3.89E-04 :

LA-140

-1 CURIES t 0.00E-01 1 0.00E-01 1 3.20E-04 7.22E-04 KR-85M i C W lES I 0.00E-01 1 0.00E-01 1 6.58E-03 1 2.63E-04 KR-85 1.

CURIES 0.00E-01 10.00E-01 8.45E4316.67E43 I KR-67 i CURIES - t 0.00E-01 10.00E41 I 7.21E-05 0.00E41 i KR-88 CURIES I 0.00E-01 t 0.00E41 13.30E-031 1.-19E44 XE-131M t CLRIES - t 0.00E-01 1 0.00E-01 i 9.39E-021 4.81E-02 XE-133M 1 CURIES I 0.00E-01 0.00E-01 1 2.09E-01 1 3.44E-02 W310526HP 28

TAB 12 2B (2 of 2)

REMRT CATEGORY SEMIAtRmL LIQUID CONilWAS AND BATCH RELEASES TOTALS FOR EACH NIllDE RELEASED.

TYPE OF ACTIVITY

ALL RADIONUCLIDES REPORTING PERIOD QUARTER 8 3 AND 0)ARTER 8 4
  • CONTINUQUS RELEASES BATCH RELEASES LNIT QUARTER 3 I N TER 4 QUARTER 3 I N TER 4 IR)LR$

IHotRS IH0lRS HOURS NUCLIDE 14345-6552 86553-8760 14345-6552 16553-8760 ALL NJCLIDES CONTI E D IE-133

CLRIES 0.00E-01 : 0.00E-01 1.77E 01 3.77E 00 XE-135
CLRIES : 0.00E41 : 0.00E-01 1.68E-01 2.3'l -02 G ALPtm CURIES : 0.00E-01 0.00E-01 0.00E41

1.0 5E-06

C0-57

CtRIES 0.00E41 0.00E-01 1.04E-05 1.39E-04 :

SB-124

CtRIES 0.00E-01 1 0.00E-01 1 6.19E-05 7.93E-04 :

SN-!!3

CtRIES : 0.00E-01 0.00E-01 7.12E-05 1 0.00E-01 NB-97
CURIEC : 0.00E-01 : 0.0(4-01 1 5.84E-04 0.00E-01 :

S8-122

CLRIES : 0.00E-01 10.00E-01 1 8.6SE-06 6.49E-05 :

50-125

CLRIES : 0.00E-01 : 0.00E-01 6.74E-03 2.37E-03 TOTAL FOR PERIOD CURIES : 0.00E-01 0.00E-01 8 5.17E 02 8.92E 01

.......... =

.. - = -

W310526HP 29

.. ~ __

<,,a TABLE 3 (1 of 3)

SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 7/1/90 THRU 12/31/90 WASTE.

CONTAINER WASTE TOTAL 3

3 TYPE VOLUME (ft )

VOLUME'(m )-

ACTIVITY (C1)

ERROR

  • Non Compacted Dry 1040 58.9 9.3E-2
  • 1 125%

Activity Waste Shipped to Scientific Ecology 13.44

' Group for Volume Burial' Volume

' Reduction

  • Non ' Compacted Dry 2425.28 6.85 2.6E-2
  • 1 125%

cActivity Waste

Shipped.to:

-Alaron' Corp

'GroupLfor Volume I

-Reduction l

l l

  • Waste' volumes shipped for volume reduction do not reflect' final burial waste volumes
  • 1: Activity determined by estimations.
  • 2 Activity determined by measurements.

W31052611P 30

TABLE 3 (2 of 3)

SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 7/1/90 THRU 12/31/90 WASTE TYPE NUCLIDE NAME

% ABUNDANCS CURIES Non-Compacted Mn-54 4.18 3.89E-3 Dry Activity Waste Fe-55 20.6 1.92E-2 Shipped to Scientific Co-58 37.1 3.45E-2 Ecology Group for Co-60 5.37 4.99E-3 Volume Reduction Ni-63 9.08 8.44E-3 Cs-134 8.55 7.95E-3 Cs-137 13.5 1.26E-2 Non-Compacted Mn-54 4.18 1.09E-3 Dry Activity Waste Fe-55 20.6 5.36E-3 Shipped to Scientific Co-58 37.1 9.65E-3 Ecology Group for Co-60 5.37 1.40E-3 Volume Reduction Ni-63 9.08 2.36E-3 Cs-134 8.55 2.22E-3 Cs-137 13.5 3.51E-3 W31052611P 31

TAllLE 3 (3 of 3)

SOLID WASTE SIIIPPED OFFSITE FOR DISPOSAL DURING PERIOD 7/1/90 THRU 12/31/90 NUMilER OF Si!IPMENTS

?! ODE OF TRANSPORTATION DESTINATION 3

TRUCK 1-Oak Ridge, TN 2-Wampum, PA WASTE

  1. OF TYFE OF CLASS

. SilIPMENTS TYPE CONTAINER MODE DESTINATION A

3 LSA Strong-tight Truck 1-Oakridge, TN LSA Strong-tight Truck 2-Wampum, PA W31052611P 32

TABLE 4 (1 of 4)

JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL DATA Jotes reteutm2T 0157tleutim of W1s We9 Am 01tfCflos 14 nWet

  1. AssulLL CLAtt &

Wim $PfE0 (4/t) RT 10 s ((WL Wie -

Ot4ECfle

.31.50.51.75.76 1.0 1.1 1.5 1.6 2.0 2.1 3.0 3.1 $.0 $.1 F.0 7.i 10. 10.1'l3 15_._148 C *180_fElAL _

B 0

0 0

4 18 29 46 22 5

0 0

0 124 auf C

0 1

6 5

14 8

2 0-0 C

0 34 IN -

0 0

1 10

' 18 '

32 54 3

0 0

0 0

til fut 0

0 1

4 27 68 83 11 2

0 0

0 196 i

O O

O 2

2 12 23 3

0 0

0 0

62 EM 0

0 1

0 1

7 21 1

0 0

0 0

31 SE O

O C

0 1'

6 37 17 3

0 9

0 64 SM 0

0=

-4 1

2 15 36 35 2

0 0

0 M

S 0

0 6

3 3

16 26 26 0

0 0

0 T4 SW 0

0 1

0 2

8 9

14 3

0 0

0 37 sW 0

0 0

2 6

4 to 5

0 0

0 0

20 WeW 0

l' 0'

1 2

6 5

A t

0 0

0 19 W

-0 0

0 2

1 4

2 1

0 0

0 4

E WW 0

0 0

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3 7

0 0

0 0

0 13 W

0 6

0 0

2 5

16 1

1 0

0 0

M tant 0

0 0

2 9

?8 44 1) 4 0

,10TAL 0

I 39 000 427 151 20 0

-0 0 -- R -

0 0

1061 las m a of CALMS f e A ffA8tt!TY 0

Jotsi fatelENCT DluelmJileu of W1ub MED AND Dl4ECil04 Ik MOURS PA9tJlLL CIM18

  • s WIW SPEfD W3) At 10 m LEm WW Olettite

.35.$0.51.75

'.76 1.0 1.1 1.5 1.6 2.0 P.1 3.0 3.1 5.9 5.17.0 L1 10. 10.1t13 1,1.1 ?8.0 >18,0 tota R

0

'O 8

-l 6

4'

' 14 10 1

0-0 0

36 uuE C

0 0

2 1

3 1

0 0

0 0

12 NE 1

0 1

0 6

7 6

0 0

D.

0 0

21 fat 0

0 0

1 6

11 12 5

0 0

0 0

3%

E o

'O 1

1 2

2 3

1 0

0 0

0 10 EW O

O O

0 0

1 0

3 0

0 0

0' 4-St 0

0 0

0 3

3 6

15

-2 0

0 0

~29 SSE

-O O'

O 1

2

-l 8

8 3

0 0

0 23 3

0-0 0

0 2

8 17 11 0

C 0

0 38 SW 0

0 1

2 0

3 8

4 1

0 0

0 19

-sw 0

0 0

1-3 8

8 3

0 0

0 0

23 W5W '

O

-0 0

0 1

6-9 2

0 0

0 0

13 W

0 0

0 0

2 3

11' 1

i 0

0

-0 18 tas 0

-0' 0

0 1

1 7

3' O

O O

9 12

-aw 0-0~

0 0-t 1

5 6

2 0

0 0

15

__ ' auw 0

0 0

1 3

8 IL

-3

'I O

O U

28 wtAt 0

3 is 40 es 129 76 it 0

0 0

341 temieER Of Cams tom - e StA41 tiff 0

W310526HP 33

t 4.-O g-.

6 y TABLE 4 (2 of 4)

JOINT FREQUENCY DISTRIBUTTON Of METEOROLOGICAL DATA Jole7 ME4W4Cf Olstaisuflou Or use et0 aWD N0fttt0e te NUES rAsanLL ctAtt C bit 4 $Pf tD Ut/U 67 J0 6 45WL eigt,ntpji: p.58.7s.n 1.0 1.1 1.5 1.at 2.s.3.,,3._1 5.0 s.v.r,0 7,1.i0. te.g.th tl 1. is,0_21sA gag,,,,,,, W 0 0 1 3 2 4 12 1 2 0 0 0 31 EK 0 0 0 5 3 1 4 2 9 e 0 0 15 IE C 0 8 2 3 J2 1 1 0 0 6 M M 0 0 0 2 2 to to a 0 0 g 35 i '1 C 0 0 - (; o 2 6 0 0 0 0 0 8-tw a 0 0 2 2 4 6 0 0 0 0 0 st 0 0 0 0 1 1 10 6 2 0 3 0 20 ' sit 0 0 0 0 1 4 16 12 1 .0 0 C La S 0 0 0 2 I F ll 2 0 0 0 R ( SW 0 0 0 0 1 4, 3 18 3 e o o il SW 9 0 0 2 0 y a 3 1 4 t' 0 21 Wev 0 0 0 1 0 4 4 2 0 0 0 0 11 W 0 0 0 2 4 1 ti 2 1 a 0 0 f) m 0 0 0 0 1 0 "i ( 0 0 0 0 14 el 0 0 0 0 1 3 4 5 3 0 6 e 16 MW 0 0 0 _0 1 6 8_ f ot AL - 0 0 2 in 24 73~ -il2 . E .9 0 0 t is M 22 ' 0 0~ 0 33) GAGER M Geses fat C SIMILilf 0 l i I J01st rateuthCt DIstteeWilan W seen SPES Mo (Isttism It scos PAsoulLL CLAst 9 - WI4D $*tet W S) AT 10 e Lt W L We ' gcTim .15.50.51.75 .76-1.0

1. h [ L t.6*2.0 E 3.0 3.1+5.0 5.1 7.0 7.1 90. 10.1 13 13.1 18.0 n10.6 70f4L e

1-0 2 8 12 16 44 $6 13 0 0 0 712 lum 1 0 1 5 T 16 57 42 6 0 0 0 835 l -- et '0 0' 6 10 20 41 63 20 0 51 0 0 160 l Ett 0 0- ~3 11 14 15 44 22 5 0 0 0 134 L E 0 0 l 4 1 ' 20 21 5 0 0 0 0 52 l* Est -0 1 0 1 2 9 23-4 0 0 0 0 4 SE O 1 0 4 1 10 94 56 - 3 0 0 0 13 SE O 0 1 1 5 26 114 T5 il - 0 0 0 23 ) 0-0 2 6 10 29 76 44 10 0 D 0 477 51W D 1 2 7 5 25 13-47-22 6 0 0 146 W 9 0 2 8 21 19 12-12 0 0 0 74 WeW 0 0 1 4 T 14 29 to 1 0 0 0 62 i U 1 2 .2 2 8 18 30 3 3 0 0 0 69 tend 0 1 2 3 6 12 18 le 5 0 0 0 51 abt 0 0 0 ~1 ? 20 44 39 1 0 0 4 118 Ised 0 0 0 4 13 31 _ 57 40 ?S J 0 0 170 smat 3 6 23 n u6 .w3 8c2 Se9 in 6 o o 2016 - NWWEA Of CA&M8 FGt 0 $1481 LIFT 2 W31052611P 34

TABLE 4 (3 of 4) %'d ! UQUENCY DISTRIBUYIN OF W.TLOROLOGICAL DATA 1 JotN1 FM'4eM M,etIAM15 DF W4J MD AJO Dh\\Cill la Inas Pagount Lt.tst t Wit IM(0 Wll At 10 2 Ltytt Wim Simils .55.50.51.75.76 1.0 1,11.5 I J f.0 2.113 3.1 5,0 5.1 7.0 T.1 10. 10.1-14 A l It.0 *18.0 1014L R 0 2 3 19 34 to 10T 22 2 0 0 0 269 But i 2 5 20 il 34 69 13 2 0 0 0 23 ut 0 2 8 19 21 56 61 l' 0 0 0 0 186 tot 0 0 6 14 28 64 TO 16 0 0 0 0 202 E D 1 6 M 34 T1 T1 Y 0 0 0 0 7c2 o EM 1 0 4 3 14 $3 59 9 0 0 0 0 l) St I l 4 8 31 61 145 10 0 0 0 0 M1 Stt 0 2 3 17 34 113 191 20 s 0 0 0 144 5 1 4 4 th 55 105 98 22 s 0 0 f 50!' $1W 1 4 11 23 24 35 38 4 1 0 0 0 153 W W 0 9 21 26 14 23 6 0 0 0 0 100 "W 1 2 0 14 .1 35 T 3 0 0 0 0 105 1_ W 0 2 9 22 'T 35 9 3 0 0 0 0 M? } tend 0 0 4 12 1T 14 T 0 0 0 0 'P W 0 0 5 13 45 29 40 8 1 0 0 0 M 19 27 51 54 10 3 0 0 t th WW 2

  1. " a) 29 64 s4 kwe la2 9"s 0

0 29N ' " icia a gacht OF CM MS f0n E STL54LITT I sy E k ( n J01tl FesaumCT Dl6Tl'eullou 0F WIW SPt!O Ase DlaECilm is Mouts tasastLL CLAst f Wi m F it0 & F 41 W a 14,PA Mn platCTie .35.50 .5 % h_.76 1.0 1.1 4.5 1.6 '2.0 2.1 1_. L 3.1 5,0 S y T,4 L1 10 19.1 11 11.1 18.0 518.0 tot 4L E O 3 6 8 16 20 2 0 0 0 0 0 55 IsE 1 T 9 ? if 9 2 1 c e 0 0 4T est t 1 2 15 15 18 6 0 0 =3 0 0 54 M 2 6 4 4 34 12 0 0 0 0 0 ft f 0 2 4 8 7 39 18 9 6 0 0 0 T8 L9E 1 5 T f 7 e 13 0 0 0 8 0 4T SA i 1 F F 6 13 5 0 0 0 0 0 40 SSE 'd 1 19 M 22 '2 ? 2 0 ts 0 0 0 80 8 2-3 21 SJ-56 R' A 0 0 0 0 0 1 73

  • sW 4

4 19 46 42 8 0 0 0 0 0 0 ul ~ m? 5 19 45 1'1 10 1 0 0 0 0 C 104 Nani 4-4 24 to 14 '5 6 fl 0 0 0 0 V5 W G T 13 12 W t 'O O O O O (9 neat 4 12 %1 th 4 4 0 f, 0 0 C 0 52 ind 0 6 7 10 5 ft 6 J ) 0 0 0 41 [ eset 1_ 4 13 __ to 9 - 2 0 3 0 0 0 52 r3:a a Tm un sn m n4 TO i 0 o 0 0 12n /R'ipel OF CALas tw t $1Asttt1T 21 I W3105.YHF 35 k l ,.7"%. DDea

~ _ _ _._.__..~.m. ..-._.-.~~._.m. .. _, _...... f-e, e,* 1 s TABLE 4 (4 of 4) JOINT rREQUENCY DISTRIBUTION OF MF.TEOROLOGICAL DATA s Jewt legelzect pistuteffle OF Wie aptse me Ot44com le Immal PAseWILL C* ut 0 blS 9Pfl0 (9/1) At l).g (gygg flAKlim .34*.98 31..M .P6 1.0 f.1 1.9 1 4 2.0 2.1 3.0 3 l.$.0_ 3.1 7.0 P.1 10. 10.1 13 13.1100 e u,0 19 q ___ 0 0 1 F 8 4 7-0 0 0 0 0 8 to est 2 3 8 10 3 1 0 0 0 0 0 0 27 E 2 1 3 11 5 2 1 0 0 0 0 0 M tee 0 0 t le S 4 0 0 0 0 0 e is t F 1 4 3 2 1 1 0 0 0 0 0 to E tt 0 0 2 2 1 8 0 0 0 0 0 0 5 N 1 0 3 2 1 1 0 C a 0 0 0 0 tw 0 3 e 3 0 0 0 0 0 0 24 9 1 7 12 le 1F 0 0 0 0 0 0 0 M StW 2 a 13 3r 'A 7 0 0 0 0 0 0 93 SW D 17 16 32 12 2 0 0 0 0 0 0 el Wuw F 16 33 M 11 2 0 0 0 0 0 0 95 W 6 Il 36 le 1 3 0 0 0 0 0 0 ft had 4 8 3r 11 5 0 0 0 0 0 0 0 65 m r s st 11 i s 0 0 0 0 0 0 ls anaf 3 1 F 13 1 0 0 0 0 0 L 9 79 team u se em rae er3 u a 0 0 0 0 0 rua IRARER Of Casel 90R.O SinglLily $4 ietu vue uses em alt stantires

  • me r

lefAL 194GLIO MeLas Pet ALL Stastiltsse %2 l: l: W310526th 36 + l, l .u

TABLE $ (1 of 2) DOSE CALCULATION RESULTS FOR 1990 (DOSES DUE TO GASEOUS RADIOACTIVE EFFLUENTS) H (Nii ! H QJMTER 1 5 1990 es

    • '.N!1 1 ** 0.M TER 2 (F 1990 et ICE FROM RADIO!0 DIES. PM11CVLATES AND TR!i!UM COSE FROM RAD 1010 DIES. PARTICtLATES, AND TRITIUM AT CCXTROLLIM LOCA110N Ai (XhTROLLl% L0tA110N 1

TOTAL [0SE (MREM) FCR KM i 7.56 M -05 TOTAL XISE (MREM) FOR SOE 8 $.0!!0E-01.494al-0} TOTAL LOX (RM) FOR ' IVER I 25791E-02 TOTAL XE (RM) FOR LlWR t TOTAL XEE (MREM) FOR TOTAL IODY 5.4284E42 TOTAL KM (SEM) FOR TOTAL BODY 2.5741E-02 TOTAL XrE (RM) FOR THYR 010 t 4.4257E-01 TOTAL COX (MREM) FOR THYROID I 5.4792E-02 TOTAL

0M (RM) Fm KII4Y 5.5146E-02 TOTAL [0M (MREM) FCR Kit 4Y 2.5006E-02 T3TAL JEE (RM) FOR LtN)

I

5. ')764E-02 TOT % pH (MEM) FOR LM i 2.5701-02 TOTAL IYE (REM) FOR 01-LLI 5.3906C-02 70fc CO2 NM) FW 01-LLI I 2.5706E-02 NORE GAS DOCE Al Sff T0fA M0Y (OSE TO'I'E DOUNDARY NORE GAS IOSE AT SITE ioMMyt (MREM)

I 1.0524E41 TOTAL BODY DLrSE TOTAL ( mEM) I 1.47tlE41 SKIN DCM TOTAL (MEM) 3.4377E-01 9 lN [0SE TOTAL (MRo.1 1 4.3637E-01 N0BLE GAS AIRDOSE Al SITE 10VNt#ft %RE MS A!RKr5E Al SITE 93.NDMY8 TOTAL GAM A!RICI (SAD) i 1.735N-01 10 Tit %9mA AIRI M (MRAD) i 2.1966E41 TOTAL BETA AIRICE ($AD) 4.7394E41 'l0 fit BETA AIRDM MAD) 6.1792E-01

    • LNIT 1 es DJARTER 3 Or 1990 **

.,LN!f I es QllARTER 4 0F 1990 #6 XISE FROM RAD 1010 DINES PARI!CtLATES AND TRIT!UM [0SE FRm RAD 10100!NES. PARilCULA%S. AND TRITIUM l AI CONTROLLi m LOCAil0N - t.T CfNTROLLI O LOCAtt m' i TOTAL 005E (MREM) FOR KM 8 7.3hl4E-05 TOTEL IOM imEM) FM 90E 1.445E-04 TOTAL J0M (EM) FM LIVER I 3.8396E-02 10Tts (OM (MM) Fm LIVER 1.1730E-02 TOTAL OSE 0* REM) FOR TOTAL 10DY I 3.S340E42 TOTAL DOSE (MREM) FOR TOTAL 90DY 1.163N-02 TOTAL ICSE (mEM) FM THYRotD 6.6400E42 TOTAL (03E tmEM) FOR THYR 0!D I 6.7155E-02 TOTAL COM (MREM) Fm KIDNEY t 3.8410E42 TOTAL [ TEE (MREM FOR Kl[NEY 1.1750E-02 1014 (OSE (MREM) FOR EUNG I 3.010E42 iciAL 0$t (MN Fm LUNG t 1.1561E-02 TOTAL DOSE (MREM) F% 01-LL1 1 3,8314E42 - TOTAt 10$E (HN FOR 01-LL1 8 1 1567E42 E BLE OAS [OSE Ai SITE B0lNDARY8 N0kE GAS D03E t.f SITE BOLNIMYi TOTAL EODY KrSE TOTAL (SEM) 3.4S60E41 igitt !ODY KtE TOTAL (mEM) I 1.7109E41 SKIN DOSE TOTAL ( MEM)- t 8.1884E41 9lh [0SE 10 Tit (MREM) 4.0130E-01 W RE %S AlRIOSE AT SITE BOUNDARY: ME GAS AIRIOT AT SITE PolMMY 101AL GAMMA AIRIOSE (SAD) 1 4.1091E41 TOTAL GMMA AntrM (*AD) I 2.0157E-01 i TOTAL PETA AIRKE (MAD) I 1.12 M 00 TOTAL 6 ETA AIRDOSE (MRADI 5.5017E-01 l 1 u UNIT 1 *e TOTALS FOR 1990 H [OM FROM RAD 1010DlWES. PMilCULATES, AND TRiliUM AT CONTR0LI.I O LOCATION TOTAL DM (MREM) FM DOE 1.3042E-03 TOTAL DOSE (MREM) FOR LIVER I 1.3086E41 T0Ttt (ME (MREM) FOR TOTAL KiDY 1.3001E-01 TOTAL (C E ( MEM) FOR THiR010 -t 6,5092E-01 r TOTAL [0 4 ( EEM) FOR KIDNEY 1.311?E-01 T0Ttt DM (MREM) FOR L'JNO I l.2934E-01 t l TOTAL DOSE (MREM) FOR 01-LLI I 1.29ME-01 ORE 0AS (OSE AT SITE TOMMY 1 TOTAL BODY DOSE TOTAL (MREM) 9.5211E-01 9'IN CO3E TOTAL (MREMI 2.0004E 00 HORE 6AS AIRDOSE AT SITE KI.NDARY: l TOTAL 0AMMA AIRDOSE (MRAD) 1.0057E 00 l TOTAL BETA AIRDJ5E (MRAD) 8 2.7660E 00 W3105261[P 37 1 I +

TABLE 5 (2 of 2) DOSE CALCULATION RESULTS FAR 1990 (DOSES DUE TO LIQUID RADIOACTIVE EITLUENTS) i soLNIT 1 #4 QUARTER 1 0F 1990*e TOT 4. [0E (RM) FOR 90ff I 3.!?26E42 TOT 4. DOSE ( R M) FOR LIVER t 5.3919E42 T014. DOSE (INEM) FOR TOTAL BODY I 3.9629E-02 T074. EM (EM) FOR THYR 0!D t 2.8t?0E-03 1014. ICE (RM) FOR K!IsEY t .7930E-02 TOTAL [0E (RM) Fm 01 tLI 0SE (MREM) fM LM t .000E 43 70T4.. .9791E-03 40 UNIT 1 88 QUARTER 2 0F !WO ** 7014 DOE (RM) F% 10E I ?.636X-02 TOT 4. XGE (WM) FOR LIVER I 4.46tE-02 T014. XE (MREM) FOR TOT 4.100Y I 3.2488E-02 10T4. (0% (MREN) FOR THYR 0!D t 1.6514E44 1014. DOSE (fmEM) FOR KID 8EY I 1.409(442 TOTAL IOSE (WM) FOR LM t 5.0399(H)3 107AL DOSE ( R M) FOR 01-LLI I 9.7464E-03

    • (NIT 1 es GUARTER 3 F !??0 64 i

-1014. DOSE (MREM) FOR BONE I 1.0471E41 TOTAL DOSE (MREM) F M LIVER I 1.7509E41 TOTAL DO$E (MREM) FOR TOTAL BODY I !.2668E-01 10TAL DOSE tPREN) FM THYROID t 5.9278E-04 TOTAL [0E (PREM) FOR KlDNEY 5.054X42 TOTAL [0E (MREM) FOR LWG t 1.9049E-02 TOTAL DDSE (MREM) FOR 014.LI 5.7634E-03

    • WIT 1**OVARTER 4 0F 1990 **

TOTAL ICE (MREM) FOR 10E I 1.1497E-01 TOTAL D0GE (MREM) FOR LIVER I 1.9316E41 TOTAL COSE (RM) FM TOTAL BODY I 1.4031E-01 TOTALDOSE(fREM)[0RTHYROID 1 1.1302E-03 TOTAL DOE (RM) FOR K!DIEY I 6.4298E-02 TOTAL (03E (PREM) FOR LWG 2.1459E-02 1014. DOSE (fREM) FOR 01-LLI I e,5175E43

    • LNIT 1 ** TOTALS FOR 1990 **

TOTAL XM (RM) FOR 90ff I 2.7729E-01 TOT 4. X6C OREM) FM LIVER - 1 - 4.6678E-01 TOTAL )0SE (imEM) FOR TOTAL BODY t 3.3911E-01 TOTAL DOSE (MREM) FOR THYROID I 4.700lE-03 TOTAL DOSE (PREM) FOR KIDIEY. I 1.5567E-01 TOTAL IOSE (MREM) FOR LUNG I 5.234'iE-02 TOTAL DOSE ffREM) FOR 01-i.LI I 3.0026E-02 .i. L W310526HP 38-1 .m .u.

_ _. ~ _ _ _ _ _ _... _ _ _ _ _ E .,. J.' ; .O g TAllLE 6 1 (1 of 1) ACTIVITY CALCULATIONS FOR SECONDARY RELEASE PATifWAYS FOR 1990 i 4- . VENTILATION SYSTEM TOTAL AC5'VITY RELEASED DURING 1990 (Curies) 1-131 1-133 Co-58 Xe-133-SWITCilGEAR AREA VENT (All-25) 4.03E-6 4.13E-7 <LLD (LLD

44611&V EQUIP".ENT ROOH (E-41A&ll) 2.31E 6 (LLD

<tLD 3.87E+0 ll0T MACllINE Sil0P (AH-35) 4.02E-6 <LLD <LLD " 94E-2 l DECONTAMINATION S110P (All-34) 1.83E-5 3.32E-7 1.13E-7 2.09E40 j TCTALS 2.87E-5 7.45E 7 1.15E-7 .6,06E+0 w { .i I: p W310526HP 39 ] y l ',

s 9 ATTACllMENT 1 (2 PAGES) CORRECTIONS TO TABI.E 2A-0F SEMIANNUA1. RADIOACTIVE RElf.ASE REPORT J January 1, 1990 - June 30, 1990 t W3105261[P : 40 ... ~,., ... _. _ = _ _ _. _..., _.. _ _ _ _ _.. _.. _.. _ _ _ ~ _..

.,=....o. o b TABLE 2A (1 of 1) HEPORTCATEGORY I SEMlW8A. SUMTION OF ALL RELEASES BY QUARTER 4 TYPEOFACTIVITY ALL LIQUID EFFLtENTS EPORTING MRIOD I OVARTER 01 AND 9)ARTER 0 2 I mli tDUARTER 1 IQUARTER 2 EST.TOTALt i iRR$ tKIJRS IERROR1 TYPE OF EFFLUENT t i 1 2160 12161-4344 I I ... ~.. A. FIS$10N AW ACTIVATim FH0 DUCTS

1. TOTAL FELEASE(WT INCLUDlW t

i I t TRITilN. 0ASES. ALP M L ICtRIES 1.! X-01 1 5.90E-02 i 1.50E 01

2. AVERA0E DILUTED CONCENTRATION I

I I I MINGPERIOD IUCint. I 6.87E-09 t 2.72E-09 t l

3. PERCENT Of APPLICABLE LIMIT

-I 1 N/A I N/A I B.TRlillM

1. TOTAL RELEASE CtRIES 4.15E 01 1 9.70E 0! ! !.*A 01
2. AVERAGE DILUTED CONCENTRAi!0N I

I I I M ING PERIOD LCint. I 2.51E-06 4.00E-06 l

3. PERCENT OF APPLICABLE LIMli i

.I_ N/A I N/A 8 C. DISSOLVED AND ENTRAllED CASES - l

1. 10T4. RELEASE CURIES 8.74E-01 2.30E 00 1.50E Olt
2. AVER E DILUTED CONCENTRAil0N I-t.

I I DURINGPERIOD-1(Cl/ML 5.29E-00 t 1.00E-07 I l l - 3. PERCENT OF APPLICABLE LIMIT I i N/A I N/A 't ~. -.

0. OROSS ALPHA RADICACilVITY
1. TOTAL RELEASE ICURIES I 0. E -01 : 0.00E-01 1.50E 01

'E. ESTE VOL RELEASED (PRE-DILUTION) ICAL I 2.79E 05 t 6.17E 05 1 1.50E Oli l - F. VOLVE OF DILUTim MTER USED CAL 4.37E 09 5.64E 09 8 1.50E 01: W350897HI-19 -.. =, w --a-

. o " 'o ' 'e 4 ATTACuMF'.i 4 (4 PAGES) CORRECTIONS TO TABLE 3 OY SEMIANNUAL RADI0 ACTIVE RELEASE REPORT January 1, 1990 - June 30, 1990

  • d310526HP 41

, s * *.o o 9 TABLE 3 (1 of 3) Solid Waste Shipped Offsite for Disposal During Period 01-01-90 thru 06-30-90 Container Waste Total Waste Type Volume ft3 Volume m8 Activity Ci Error Non Compacted Dry 1040 147.4 8.78E-1 *1 l 125 Active Waste 95 Before Volume Shipped to Reduction, Scientific Ecology Group for volume 19.23 reduction Burial Volume Resin Waste Manage-182.4 5.16 5.88E+2 *2 125 ment Resin dewatered in a high integrity container Liquid Waste Manage-181.7 10.29 2.15E+0 *2 1 125 ment Resin Dewatered Waste Oil Shipped to 7.5 7.43 9.40E-3 *2 1 125 Scientific Ecology Group for incineration Waste volumes shipped for volume reduction do not reflect final burial varte volumes.

  • 1 Activity determined by estimatioes.
  • 2 Activity determined by measurements.

W350897HP 22

l 4 s ' 'ea 8 6 4 0 tab 11 3 (2 of 3) 1:stimat.es of Major Nuclides Dy Waste Type Waste Type Nuclide_Name (Abundance _CJ_ J Non Compacted Dry Mn-54 2.7 2.37E-2 Active Water shipped re-55 33.2 2.91E-1 to Scientific Ecology Co-58 9.26 8.13E-2 Group for Volume 0o-60 U.63 7.580 2 reduction Ni-63 14.6 1.26E-1 Cs 134 11 9.66E-2 Cs-137 19.1 1.68E-1 Resin Waste Management Mn-54 1.32 7.760+0 Resin Dewatered in a re 55 3.29 1.93E+1 high integrity container Co-58 2.92 1.72E+1 Co-60 3.69 2.17E+1 Ni-63 13.7 8.06E+1 CS-134 24.9 1.46E42 C r.- 13 7 49.5 2.91E+2 Liquid Waste Management Mn-54 3.045 6.55E-2 Resin Dewatered re-55 19.85 4.270-1 Co-58 32.75 1.11E-1 Co-60 5.17 7.04E-1 Ni-63 13.27 2.85E-1 Cs-134 11.12 2.39E-1 Cs-137 17.15 3.69E-1 Waste 011 Shipped to Mn-54 2.67 2.51E-4 Scientific Ecology Fe-55 32.7 3.07E-3 Group for incineration Co-58 9.13 8.58E-4 Ni-63 14.4 1.35E-3 Cs-134 10.8 1.01E-3 Cs-137 18.8 1.77E-3 W350897HP 23

e.<0, 9 TABLE 3 (3 of 3) Solid Waste Disposition Summary Number of Shipments Mode of Transportation Destination i 7 Truck 4 Dak Ridge, TN 3 Barnwell, SC Type of Waste Class Shipments Type Container Mode Destination A 6 4-LSA Strong Tight Truck 4 Oak Ridga, TN 2-Type A 2 Barnwell, SC C 1 LSA HIC -Truck Barnwell, SC Type A l W350897HP 24 s}}

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