ML20140J322

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Annual Radioactive Effluent Rept for 1996
ML20140J322
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 12/31/1996
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20140J319 List:
References
NUDOCS 9705140046
Download: ML20140J322 (23)
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Text

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1 Annual

! Radioactive l Effluent Report 1996 f

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Connecticut Yankee Atomic Power Company Haddam Neck Plant License Docket DPR-61 50-213 i

9705140046 970501 PDR ADoCK 05000213 R PDR

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I Table of Contents '

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Introduction  !

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1.0 Doses l

1.1 Dose Calculations 1.2 Dose Results 2.0 Radioactivity f 2.1 Airborne and Liquid Effluents 2.2 Solid Waste 3.0 REMODCM Changes -

f 4.0 Inoperable Effluent Monitors 5.0 Errata i 4

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1 i introduction ,

$ This report is being sut;mitted for Connecticut Yankee Atomic Power Company's Haddam Neck Plant in l

] accordance with 10CF t150.36a and the Radiological Effluent Technical Specifications and in the US NRC l Regula',ory Guide 1.21 format. '

1 The report p avices radioactivity information for airbome and liquid effluents and solid waste. Doses and  !

l regulatory limits are provided for airbome and liquid effluents. If applicable, any changes to the REMODCM, i description of anj effluent monitors inoperable for more than 30 days, and any corrections to previous ]

reports are include,'. '

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3 The Haddam Neck plant had an annual capacity factor of 54.8%. Listed below are the major shutdowns for .,

1996:

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q Period Reason J 4 i j 07/22 - 12/04 Shutdown for CAR Fan inoperability and planned refueling l

{ 12/04 - 12/31 Permanent cessation of operation l

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1.0 Doses This report provides a summary of the estimated off ee radiation doses from routine releases of radioactive materials in airborne and liquid effluents for the unit. Included are the annual population dose commitments (person-rem) for the area within ,T miles of the site, the annual average dose commitment (mrem) to the population, and the annual maximum dose commitment (mrem) to any real member of the public. Also provided are the maximum gamma and beta air doses.

The doses are compared with the regulatory limits and with the annual average population dose commitments from natural background and other sources to provide perspective.

1.1 Dose Calculations The off-site dose to humans from radioactive airborne and liquid effluents have been calculated using measured radioactive effluent data, measured meteorological data, and dose computer models developed by the US Nuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA). These doses generally tend to be conservative because of the conservative assumptions used in these models. More realistic estimates of the off-site dose can be cotained by analysis of environmental monitoring data. A comparison of doses estimated by each of the above methods will be presented in the Annual Radiological Environmental Monitoring Report. ,

1.1.1 Population and Maximum Individual Dose Commitment Population dose commitment is defined as the total radiation dose received by the specified population in a specified time period from an identified radiation source. For this report, the specified population is defined as the population within 50 miles of the .

I Haddam Neck nuclear site. The doses are based upon continuous exposure to the airborne and liquid effluents fo; a one year period and an associated dose commitment ,

over a 50-year period from initial exposure, taking into account radioactive decay and l biological elimination of the radioactive materials contributing to the dose. The population dose commitment (person-rem) is the sum of the individual doses.

The dose, calculations are based upon these three types of input: radioactive source term, site specific data, and generic factors. The radioactive source term (Curies) is characterized in the Effluent Activity section of this report. The site specific data includes: meteorological data (e.g. wind speed, direction, stability, etc.) to calculate the transport and dispersion of airborno effluents, dilution factors for liquid effluents, the population distribution and demographic profile surrounding the site by compass sector.

Other site specific data include the average annual production of milk, meat, vegetation, fish, and shellfish. The generic data includes the average annual consumption rates (for inhalation of air and ingestion of fruits, vegetables, leafy vegetables, grains, milk, poultry, meat, fish, and shellfish) and occupancy factors (for air submersion and ground irradiation, shoreline activity, swimming, boating, etc.) for determining the dose to the individual who would receive the maximum dose (maximum individual). Ail these inputs are used in the appropriate dose models to calculate the population and individual dose commitme.its from radioactive site airborne and liquid effluents.

1.1.1.1 Airborne Effluents Maximum individual doses and population doses due to the release of noble gases, radiciodines, and particulates were calculated using the computer code GASPAR (Ref 1).

The GASPAR code is an NRC code which uses a semi-infinite cloud model to implement the NRC Regulatory Guide 1.109 (Ref 2) dose models.

The values of average relative effluent concentration (X/Q) and average relative deposition (D/Q) used in the GASPAR code were generated using a meteorological computer code which implements the assumptions cited in Section C, NRC Regulatory Guide 1.111 (Ref 3). The annual summary of hourly meteorological data (in 15-minute increments), which includes wind speed, direction, atmospheric stability, and joint frequency distribution, is not provided in the report but can be retrieved from computer storage.

Vent (175 ft) releases are considered mixed mode (partially elevated and partially ground) releases; and, Pasquilt stability classes are determined based upon the temperature gradient between the 33 ft and 196 ft meteorological tower levels.

GASPAR was used to calculate doses for continuous releases through the vent (building ventilation); and, doses for batch releases from the vent (waste gas tanks, vent header, volume control tanks, and containment purges)..

These doses were summed to determine the tcT .;irborne effluent dose.

1.1.1.2 Liquid Effluents Maximum individual and population doses from the release of radioactive  !

liquid effluents were calculated using the LADTAP (Ref 4) code, which uses the dose models and parameters cited in NRC Regulatory Guide 1.109.

1.1.2 Gamma and Beta Air Doses .

Maximum gamma and beta air doses from the release of noble gases were calculated - i using the GASPAR code. f 1

I 1.2 Dose Results r 1.2.1 Airborne Effluents For population doses, the GASPAR code calculates the dose to the whole body, GI-tract, bone, liver, kidney, thyroid, lung, and skin from each of the following pathways:

direct exposure from the plume and from ground deposition, inhalation, vegetation, cow's milk, and meat. The values presented are a total from all pathways; however, only the whole body, skin, and maximum organ dose are presented. i For the dose to the maximum individual, the GASPAR code calculates the dose to the same organs listed above for the following pathways: direct exposure to the plume, exposure from ground deposition, inhalation, and ingestion of vegetation, meat, cow's milk, and goat's milk. The doses are calculated for adults, teenagers, children, and infants separately.

For the plume and inhalation pathways, the maximum individual dose is calculated at the off-site location of highest decayed x/O where a potential for dose exists.

For ground deposition, the maximum individual dose it calculated at the off-site mavimum land location of highest x/O and highest D/O where a potential for dose exists.

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For the vegetation pathway, the maximum individual dose is calculated at the vegetable garden of highest D/Q. For the meat, cow's milk, and goat's milk pathways, the calculated dose is included for the maximum individual's dose only at locations and times where these pathways actually exist. Doses were calculated at the cow farm and ,

goat farm of rcaximum deposition. l.

To determine compliance with 10CFR50, Appendix l (Ref 5), the maximum individual whole body dose only includes the external pathways (i.e. plume and ground exposure) while the maximum individual organ dose only includes the internal pathways.

Population doses include all applicable pathways.

The air dose includes only the dose from noble gases in the plume. Hence, if the ground shine contribution was significant, there may be cases where the maximum whole body or skin dose is greater than the maximum gamma or beta air dose respectively.

The off-site dose commitments from airborne effluents are presented in Table 1-1.

These doses are the maximum doses observed.

1.2.2 Liquid Effluents The LADTAP code performs calculations for the following pathways: fish, shellfish, algae, drinking water, irrigated food, shoreline activity, swimming, and boating. At Haddam Neck, the shellfish, the algae, drinking water, and irrigated food pathways do not exist; and, thus, only the other pathways are included in the totals. Doses are calculated for the whole body, skin, thyroid, GI-LLI, bone, liver, kidney, and lung.

Calculations are performed separately for adults, teenagers, and children.

The off-site dose commitments from liquid effluents are presented in Table 1-2. These doses are the maximum doses observed.

1.2.3 Analysis of Results The doses are smallin comparison to the dose from natural background radiation. The statistical expectation of adverse health effects from the calculated radiation dose due to nuclear plant operations is essentially zero.

Refer to Table 1-3 for the annual effluent whole body airborne and liquid doses for the maximum and average individuals and a quantitative comparison between the doses from nuclear plant operations and those do7es from other sources such as naturally occurring background radiation. Also provided are legally allowed 40CFR190 (Ref 6) levels to a real member of the public. Note that the maximum individualin Tables 1-1, 1-2, and 1-3 is conservatively assumed to be a real member of the public.

For compliance with 40CFR190, any direct dose from the site must be added to the effluent dose to a "real member of the public." At Haddam Neck, the only potential direct dose of significance would be from radwaste storage. However, all radwaste storage during this year was well within storage enteria that ensure the public dose would be less than 1 mrem. Hence, the direct dose would be less than 1 mrem arid inconsequential for 40CFR190 compliance.

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1 i s j References l 1. NUREG-0597 User Guide to GASPAR Code. KF Eckerman, FJ Congel, AK Roecklien,

WJ Pasciak, Division of Site Safety and Environmental Analysis, Office of Nuclear i Reactor Regulatic,1, US Nuclear Regulatory Commission, Washington, DC 20555, j manuscript completed January 1980, published June 1980.

i j 2. NRC Regulatory Guide 1.109 Calculation of Annual Doses to Man from Routine  ;

j Releases of Reactor Effluents for the Purpose of Evaluatina Comoliance with 10 CFR Part 50. Accendix 1. Revision 1, October 1977.

I 3. NRC Regulatory Guide 1.111 Methods for Estimatina Atmospheric Trarisoort and  :

Dispersion of Gaseous Effluents in Routine Releases from Licht-Water-Cooled Reactors. Revision 1, July 1977, la

4. NUREG/CR-1276 ORNUNUREGrrDMC-1 User's Manual for LADTAP ll- A Computer

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Proaram for Calculatina Radiation Exposure to Man from Routine Release of Nuclear .

Reactor Liauld Effluents. DB Simpson, BL McGill, prepared by Oak Ridge National l

- Laboratory, Oak Ridge, TN 37830, for Office of Administration, US Nuclear Regulatory j

Commission, manuscript completed 17 March 1980.

! 5. 10 CFR Enerav. Part 50 Domestic Licensina of Production and Utilization Facilities.

l Appendix l Numerical Guides for Desian Obiectives and Limitina Conditions for

Operation to Meet the Criterion "As Low As Reasonably Achievable" for Radioactive j Material in Licht-Water-Cooled Nuclear Power Reactor Effluents.1 January 1994 Edition.

J 2 6. 40 CFR Environmental Protection Aaency. Part 190 Environmental Radiation Protection Standard for Nuclear Power Operation, Revision 0,13 January 1977.

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s Table 1-1 1996 Off-Site Dose Commitments from Airborne Effluents Connecticut Yankee l

l CY 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Mix Air (nad) (mred) (mad) (mrad)

Bets 9.03E-03 0 0 3 m NNW 3.81 E-02 a 0 3 m NNW 5.50E-01 o 0.3 m NNW 5.27E-05 o 0 3 mi NNW Gamma 5.77E-03 oC3m NNW 2.01E-02 a 0.3 m NNW j.1M-01 a 0 3 m NNW 4.65E-07 0 0 3 m NNW Mix Indiviteel (mrom) (wem) (wem) (mrem)

Mole Body 5.32E 02 0 0 3 n NW 3.79E-02 a 0 3 m NNW 1.63E-01 a 0 3 m NNW 3.81 E-02 0 0 3 m NW Thyroid 8.35E-04 d 0 3 m NNW m 1.23E-02 a 0.3 m NNW m 2.40E-02 o 0 3 = NNW m 1.67E-02 o0.3m NNW @

Skin 6 59E-02 0 0 3 m NW 6.41 E-02 o 0 3 m NNW 4.17E-01 a 0 3 m NNW 4.47E-02 o 0 3 m NW Population (peson <ew (person rem) (person-rem) (peson-rem)

Mole Body - 2.98E-02 1.02E-01 3.27E-01 1.13E41 Thyroid 2.96E-02 9.78E-02 3.24E-01 1.09E-01 Skin 5.33E-02 1.61 E-01 8.94E-01 1.12E-01 Avg individual (wem) (mrom) (mem) (mem)

- Mole Body 7.97E-06 2.73E-05 8.74E-05 3.02E-05 Thyroid 7.91 E-06 2.61E 05 8.66E-05 2.91 E-05 SAin 1.43E-05 4.30E-05 2.39E-04 2.99E-05 (c)= Adult. (c)=Chdd. (1)=intant, (t)= Teen Table 1-2 1996 Off-Site Dose Commitments from Liquid Effluents Connecticut Yankee CY 1st Quarter 2nd Quarter - 3rd Quarter - 4tts Quarter M:x individual (mrom) (wem) (mram) (mrem)

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. m oleBody 6.91 E-04 (a) 9.69E-04 (a) 5.42E-02 (a) 1.01 E-02 (a)

Thyroid 4.46E-04 (e) 1.35E-03 (a) 3.66E-03 (a) 2.06E-04 (a) -

Max organ 7.85E-04 (a) m 1.35E-03 (ei m) 7.52E-02 m ao 1.46E-02 mm ,

Pooulatbn (peson rem) (person 4em) (person-rem) (person-rem)

M oleBody 5.66E-04 8.30E-04 4.10E-02 7.72E-03 Thyroid 3.75E-04 9.06E-04 2.07E-03 1.55E-04 Max organ 6 92E44 m 9.06E-04 m) 6 69E-02 09 1.30E-02 m Avg Individual (mram) (mrom) (mrn) (mrem)

M oleSody 1.51E-07 2.22E-07 1.10E-05 2.0GE-06 Thyrokf 1.00E 07 2.42E-07 5 53E-07 4.14E-08 Max organ 1.85E-07 00 2.42E-07 m) 1.79E-05 00 3.48E-06 00 (sPAdult. (cFCrund. (IPintant. (tyTeen (bopBone; (gtMG14.U. (lapKidney, (Ilyuver. (luPlung, (thPThyroid l

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Table 1-3 1996 Off Site Dose Summary Connecticut Yankee j k-4 i

Population Dose Committments (person-rem) ii

, Airborne Liquid Whole Body l Thyroid l Skin Whole Body l Thyroid l Max organ l l Station 0.5718 05604 1.2203 0.0501 0.0035 0.0815 -

Max Individual Doses vs Limits 1

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Whole Body > ' Thyroid - Max organ Skin - Air -

j Airborne - l . Liquid Airborne l Uquid Liquid Airborne Beta l Gamma j (mrom)' (mrom) (mrem) (mrom) (mra J) - I Unit Limit

  • 5 3 15 10 10 15 20 10 Unit Actual '- 0.2922 0.0660 0.0538 0.0057 0.0919 0.5917 0.5972 0.2449 Station Limit" 25 75 25 l 4 Station Actual 0.3582 0.0505 0.0919 '

i l Connecticut Resident j Average Whole Body Doses (mrem) l 1 Cosmic 27 I Cosmogenic 1 l

J Terrestial (Atlantic and Gulf Coastal Plain) 16 Inhaled 200

. In the Body 40 Average CT Resident Whole Body Dose from Background *** 284 j l Average CT Resident (withm 50 miles) Whole Body Dose from Connecticut Yankee Station Radioactive Efiluents 0.0002

' 10CFR50 Appenex i i

" 40CFR190

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l 2.0 Radioactivity j 2.1 Airborne and Liquid Effluents 2.1.1 Measurement of Radioactivity ,

2.1.1.1 Fission and Activation Gases )

I Stack effluents are monitored by a scintillation detector in paral!el with an in-line G.M. detector. Gas samples are collected on the vent and are analyzed for low level fission and activation gases.

2.1.1.2 lodines Continuous in-line charcoal sample filter on main vent effluent. Charcoal filters are then analyzed for iodines. l 2.1.1.3 Particulates Continuous in-line particulate sample filter on main vent effluent. Particulate  !

samples are then counted for gamma activity. A monthly composita is made l from weekly samples. The monthly composite is checked for gross alpha, Sr-89, and Sr-90.

2.1.1.4 Liquid Effluents in-line scintillation detectors monitor liquid waste released. A sample is taken prior to discharge. A monthly composite of batch and weekly samples is analyzed for principal gamma emitters, entrained gases, and tntium. Gross alpha, Sr-89, Sr-90, and Fe-55 activities are determined.

2.1.2 Estimate of Errors 2.1.2.1 Airborne Fission and Activation Gases 14%

lodines 13%

Particulates 14 % l Tritium 8%

2.1.2.2 Liquid Fission and Activation Products 11 %

Tritium 3.5%

Dissolved and Entrained Gases 19%

Gross Alpha 8% ,

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i 2.1.3 Batch Releases 2.1.3.1 Airborne Purge WGDT Summary Number of Batches 4 8 12 Total Time (min) 236,415 5,955 242,370 Maximum Time (min) 70,560 3,674 70,560 Average Time (min) 59,104 744 20,198 Minimum Time (min) 20,160 24 24 2.1.3.2 Liquid Number of Batches 164 Total Time (min) 48,251 Maximum Time (min) 1,438 Average Time (min) 294 Minimum Time (min) 16 Average Stream Flow (ft /sec) 15,800 2.1.4 Abnormal Releases (Exceed Technical Specification Limits)

None.

i Effluent Release Tables i

Table 2-1 Airbome Effluents - Release Summary 1 Table 2-2 Airbome Emuents - Mixed Batch - Containment PurgesNent Header Table 2-3 Airborne Effluents - Mixed Batch - WGDT Table 2-4 Airborne Effluents - Mixed Continuous Tatle 2-5 Liquid Effluents - Release Summary Table 2-6 Liquid Effluents - Batch Table 2-7 Liquid Effluents - Continuous 4

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Haddam Neck i Airborne Effluents Release Summary l

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1 9 9'6 Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total  ;

1 A. Fission & Activation Gases I

1. Total Activity Cl 1.67E+01 6.53E+01 6.35E+02 6.71 E-02 7.17E+02 l

. Released l 1 2. Average Pened uCVsec 2.13E+00 8.31 E+00 7.98E+01 8.44E-03 2.27E+01 l Release Rate B. lodine-131

1. Total Actenty Ci N/D N/D 1.48E-05 N/D 1.48E-05 Released
2. Average Period uCVsec - - 1.86E-06 -

4.68E-07 Release Rate

, C. Particulates

1. Total Activity Cl 1.53E-03 1.38E-03 1.65E-03 1.74E-03 6.29E-03 Released
2. Average Period uCVsec 1.94E-04 1.76E-04 2.07E-04 2.19E-04 1.99E-04 Release Rate D. Gross Alpha
1. Total ActNity Cl N/D N/D 4.65E-07 3.76E-07 8.41 E-07 Released E. Tritium
1. Total Activity C1 2.12E+00 2.33E+01 2.53E+01 3.26E+01 8.33E+01 Released
2. Average Period uCVsec 2.70E-01 2.97E+00 3.18E+00 4.10E+00 2.63E+00 Release Rate N/D = Not Detected c

Table 2-2 Haddam Neck Airborne Effluents - Mixed Batch - Containment Purges / Vent Header Nuclides 1996 Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total 1

A. Fission & Actwation Gases Ar-41 Ci -

2.76E-03 - -

2.76E-03 Kr-85 Ci - -

7.24E-02 -

7.24E-02 Xe-131m Cl - -

5.11 E+01 - 5.11 E+01 Xe-133 Ci - 1.60E-02 2.91 E+02 - 2.91 E+02 Xe 133m Ci - -

9.24E-01 -

9.24E-01 Xe-135 Cl - -

6.08E-01 -

6.08E-01 Total Activity l Ci l l 1.88E-02 1 3.44E+02 l -

l 3.44E+02 B. lodines

  • l-131 Ci - - - - -

Ci - - - - -

Total Activity Ci 1 -

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  • 1131 Cl -

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Total Activity l Ci l -

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I l N/D D. Gross Alpha

  • l Gross Alpha  ! Ci l -

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l N/D l E. Tritium lH-3 l Cl 1 -

l 2.35E-02 l 1.78E+01 l 2.97E+01 ) 4.75E+01 l

  • Reported with Mixed Continuous i N/D = Not Detected i

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Nuclides 1996 Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Gases Ar-41 Cl 2.23E-02 5.26E-02 2.95E-03 - 7.79E-02 Kr-85 Ci 1.52E-02 5.36E-02 9.17E-02 6.71 E-02 2.28E-01 j Kr-85m Ci 8.08E-03 1.48E-02 1.51 E-03 - 2.44E-02  !

Kr-87 Cl 1.58E-02 2.60E-02 3.13E-03 -

4.49E-02 U

Kr-88 Ci 1.32E-02 2.30E-02 2.51 E-03 -

3.87E-02 Xe-1M m C1 - 5.48E-02 1.20E-01 -

1.75E-01 Xe-133 Cl 5.82E-02 3.45E+00 8.55E+00 -

1.21 E+01 Xe-133m Cl 1.59E-03 1.03E-02 7.49E-02 - 8.68E-02 Xe 135 Cl 4.82E-02 8.88E-02 8.19E-02 - 2.19E-01 Xe-135m Ci 1.42E-02 1.52E-02 1.58E-03 - 3.10E-02 Xe-137 Ci 5.39E-02 8.52E-02 1.23E-02 -

1.51E-01 Xe-138 Cl 4.20E-02 5.40E-02 8.88E-03 -

1.05E-01 Total Activity l Cl 2.93E-01 1 3.93E+00 1 8.95E+00 l 6 71E-02 l 1.32E+01 B. lodines

  • l-131 Ci -

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  • l-131 Ci - - - - -

Ci - - - - -

Total Activity l Ci l -

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  • l Gross Alpha l Ci l -

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I N/D l E. Tritium lH-3 i Ci i 2.07E-04 1 4.30E-03 1 1.08E-02 l 5.82E-04 l 1.59E-02 l

  • Reported with Mixed Continuous N/D = Not Detected

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Nuclides 1996 Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Gases Xe-133 Cl 8.98E+00 1 4.63E+01 2.30E+02 l - 2.85E+02 Xe-135 Ci 7.46E+00 l 1.51 E+01 5.19E+01 l -

7.45E+01 Total Activity Ci l 1.64E+01 1 6.14E+01 2.82E+02 l -

l 3.60E+02 B. lodines 1-131 Cl - - 1.48E-05 - 1.48E-05 j Ci - - - - -

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Total Activity l Cl 1 - -

l 1.48E-05 l -

l 1.48E-05 C. Particulates 1-131 Cl - - - - -

. Co-58 Ci - -

1.21 E-05 1.62E-05 2.83E-05 Co-60 Cl 5.19E-04 5.06E-04 6.21 E-04 6.49E-04 2.30E-03 Cs-134 Ci 3.10E-05 - - - 3.10E-05 Cs-137 Ci 9.66E-04 8.76E-04 1.01 E-03 1.07E-03 3.92E-03 Sr-89 Cl 1.06E-05 1.27E-07 1.24E-06 1.27E-06 1.32E-05 )

Sr-90 Ci 8.54E-08 1.64E-07 2.32E-06 1.39E-06 3.96E-06 Total Activity i Ci l 1.53E-03 l 1.38E-03 l 1.65E 03 l 1.74E-03 l 6.29E-03 D. Gross Alpha l Gross Alpha l Ci l -

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l 4.65E-07 l 3.76E-07 l 8.41 E-07 l E. Tritium lH-3 i Ci l 2.12E+00 l 2.33E+01 1 7.50E+00 1 2.85E+00 1 3.58E+01 l N/D = Not Detected i

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. t Table 2-5 Haddam Neck Liquid Effluents - Release Summary r

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Units 1st Qtr l 2nd Otr l 3rd Otr l 4th Qtr l Total A. Fission and Activation Products i

1. Total Activity C1 1.70E-03 2.34E-03 9.37E-03 3.71 E-04 1.38E-02 ,

Released

2. Average Period uCUml 8.97E-12 1.21E-11 9.39E-11 1.51E-11 2.72E-11 Diluted Activity B. Tritium
1. . Total Activity Cl 1.64E+02 2.60E+02 1.08E+02 7.78E+00 5.40E+02  ;

Released

2. Average Period uCi/ml 8.63E-07 1.35E-06 1.09E-06 3.17E-07 1.07E-06 Diluted Activity C. Dissolved and Entrained Gases
1. Total Activity Ci 5.74E-03 6.58E-03 2.99E-03 N/D 1.53E-02 Released
2. Average Period uCumi 3.02E-11 3.41E-11 2.99E-11 -

3.02E-11 Diluted Activity D. Gans Alpha

1. T Aal Activity Cl N/D j N/D N/D 4.66E-05 4.66E-05 l Released l E. Volume
1. Released Waste uters 8.94E+06 8.57E+06 3.16E+06 1.38E+06 2.21E+07 Volume
2. Diluton volume uters During Releases
3. Dilution volume uters 1.90E+11 1.93E+11 9.98E+10 2.45E+10 5.07E+11 During Period N/D = Not Detected i'

"* Not available at time of printing I

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Table 2-6 Haddam Neck I Liquid Effluents - Batch l i .,

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$ Nuclides 1996 ,

j Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Products j 3

Ba 140 Cl - - 2.93E-05 -

2.93E-05

< - ?.0 58 Ci - - 4.52E-05 - 4.52E-05 4 Uu-60 Ci 4.78E-04 2.17E-04 5.23E-04 3.92E-05 1.26E-03 l

Cs-134 Ci - - 6.46E-04 5.92E-05 7.05E-04 ,

Cs-137 Cl 5.53E-05 2.66E-05 1.09E-03 2.17E-04 1.39E-03 l l Fe-55 Cl 1.08E-03 4.29E-04 5.65E-04 1.51 E-05 . 2.09E-03 J Ci 2.10E-04 2.10E-04

)

1-131 - -

j Sr-89 C! 9.00E-06 2.04E-05 4.47E-04 2.51 E-05 5.02E-04 Sr-90 Ci 8.72E-06 2.43E-05 5.19E-05 1.56E-05 1.01 E-04 i Tc-99m Cl - - 2.09E 95 - 2.09E-05

'- Total Activity l Cl 1.63E-03 7.17E-04 l 3.63E-03 l 3.71E-04 i 6.35E-03 1 B. Tritium j , (H-3 l Ci i 1.59E+02 l 2.57E+02 l 1.08E+02 I 7.78E+00 l 5.32E+02 l l C. Dissolved & Entrained Gases Xe-133 Cl 5.71 E-03 6.23E-03 2.98E-03 -

1.49E-02 4 Xe-133m Ci 1.35E-05 - - - 1.35E 05

$. Xe-135 Cl 1.37E-05 6.76E-05 6.13E-06 - 8.7dE-05 l

! Total Activity l Ci l 5.74E-03 1 6.30E-03 l 2.99E-03 1 -

l 1.50t: 02_

l l D. Gross Alpha j [ Gross Alpha l Ci ! -  ; -

I -

l 4.66E-05 1 4.66E-05 l  !

i j N/D = Not Detected

_ __. . _ . . . . - . _ . _ . _ _ _ . _ . . . . . m.__ _ _ _ .

l a

~

Table 2-7 '

l Haddarn Neck I e Liquid Effluents - Continuous I

l 2

Nuclides 1996

. Released Units 1st Qtr l 2nd Otr l 3rd Qtr l 4th Qtr l Total 1

'. A. Fission & Activation Products Cs-134 Ci - -

1.59E-03 -

1.59E-03

. Cs-137 Ci - - 2.15E-03 -

2.15E-03 l-131 Ci - 8.68E-04 1.85E-03 -

2.72E-03 1-133 Ci - 5.92E-04 - - 5.92E-04 4 Sr 89 Cl 6.67E-05 6.08E-05 1.29E-04 -

2.57E-04 Sr-90 Ci 6.27E-06 9.90E-05 2.43E-05 -

1.30E-04 Total Activity l Ci l 7.30E-05 1 1.62E-03 l 5.74E-03 l -

l 7.44E-03 B. Tritium

{ ~lH-3 l Cl l 4.81E+00 1 2.84E+00 l 4.69E-01 1 -

l 8.12E+00 l 4

C. Dissolved & Entrained Gases j Xe-135 Cl j -

l 2.80E-04 l -

l -

l 2.80E-04

} Total Activity Ci 1 -

l 2.80E-04 1 -

l -

l 2.80E-04 i

D. Gross Alpha l Gross Alpha l Ci ( -

I - j -

1 l N/D l i'

r N/D = Not Detected l

b a

o 2.2 Solid Waste Refer to Table 2-8 for a solid waste shipment radioactivity summary. The principal radionuclides considered were those included on shipping manifests.

Solidification Agent (s):

No solidification on site for 1996 Containers routinely used for radioactive waste shipment include:

High integrity Container 120.3 ft 3 Steel " Sea Van 1,100 ft Steel Container 315 ft j

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

4

, e.

i- ,

! Table 2-8 Haddam Neck i 1996 Solid Waste and Irradiated Fuel Shipments l

1 i

A. Solid waste shipped offsite for burial or disposal (not irradiated fuel) a i i 12-Month Est Total

1. Type of Waste Units Period Total Error %

J a. Spent Resins, Filter Sludges, m3 3.75E+01 1.00E+01 Evaporator Bottom, etc. Cl 1.20E+03

b. Dry Compressible Waste, m3 1.01 E+01 1.00E+01 j Contaminated Equipment, etc. Cl 9.00E-01 {

m3 1.00E+01  !

i c. Irradiated Components -

. Cl -

l t

1 r 4

2. Estimate of major t.uclide composition (by type of waste) (% of total)

Type of Waste j 3 vtide a. b. c.

Am-241 8.72E-04 6.65E-03 -

C 14 6.29E-02 6.79E 01 -

Cm-242 6.82E44 4 51 E-04 -

Cm-243 2.84E-04 2.13E-03 -

Cm-244 2.84E-04 2.13E-03 -

Co-58 1.28E+00 1,14E+00 --

Co-60 8.35E+00 4.14E+00 -

Cs-134 192E+01 1.63E+01 -

Cs-137 5.01E+01 5.05E+01 -

Fe-55 1.56E+01 6.34E+00 -

H-3 6.98E-02 1.90E+01 -

I-129 5.87E-05 1.50E-01 -

Mn-54 1.92E+00 - -

Ni-63 3.24E+00 1.35E+00 -

Np-237 1.01 E-07 3.70E-04 -

Pu-238 2.84E-03 6.52E-03 -

Pu-239 3.72E 04 1.22E-03 -

Pu-240 3.72E-04 1.22E-03 -

Pu-241 6.35E-02 2.15E-01 -

Pu-242 1.27E-05 3.05E-04 -

Sr-90 7.20E-02 1.19E 01 -

Tc-99 3.95E-05 1.80E-02 -

3. Solid waste disposition No. Shipments Mode of Transpe:tation Destination 11 Truck Bamwell, NC 1

B. Irradiated fuel shipments (Dispositkn) None C. Offsite Processing ,  ?

Vendor No. Shipments Volume (m3) Actrvity (C0  !

SEG Incorporated 2 6.21 E +01 9.00E-01 {

AERC 7 2.13E+02 5.17E+00 6 e

_m.. - _ _ _ ___ ___ _ . . _ __ - _ . - - _. __ _ _ _ _.

s%'*  ;

. l

. i l

1 i

3.0 REMODCM Changu l In 1996, there were no changes to the REMODCM. l 4.0 Inoperable Effluent Monitors ,

1 During the period January 1 through December 31, 1996, the following effluent monitors were inoperable for more than 30 consecutive days: j 4.1 Service Water (R-18) and Primary Stack (R-14A) Effluent Monitors These effluent monitors were declared inoperable for the period 3/30/96-12/16/96 due to lockup problems associated with the new RMS ScanRad computer which were caused by incompatibilities between the ScanRad software and the UNIX operating system. During this I

period, Chemistry followed Technical Specification action statements that required sampling and analyzing the service water every twelve hours while R-18 was out of service. Also during this l

period, another steck monitor, R-148, was used to monitor stack effluents while R-14A was out of service. i 5.0 Errata Enclosed is an errata to the solid waste disposition section of the 1993 Annual Radioactive Effluent l Report. The errata provides information for 8 additional off-site shipments that were previously omitted.

{

\

i

+

l

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.4 " "*

i i

1 i

3. SOLID WASTE DISPOSITION NUMBER OF SHIPMENTS MODE OF TRANSPORATION DESTINATION l 13 Truck Barnwell, SC ADD m,

B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)

NONE C. OFF-SITE PROCESSING

1. VENDOR (S): SEG QUADREX
2. NUMBER OF SHIPhENTS: 4 4
3. VOLUME SHIPPED (m3): 248.491 117.800
4. ACTIVITY SHIPPED (Ci): 2.192 0.14745 4 Truck Quadrex i Oak Ridge, TN 4 Truck SEG Oak Ridge, TN

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