ML20206D090
| ML20206D090 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/31/1998 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20206D089 | List: |
| References | |
| NUDOCS 9905030297 | |
| Download: ML20206D090 (31) | |
Text
Annual i Radioactive Effluent Report 1998 i
l Connecticut Yankee Atomic Power Company Haddam Neck Plant License Docket DPR-61 50-213 DR DO K 05 0 213 R PDR
I Table of Contents introduction 1.0 Doses 1.1 Dose Calculations 1.2 Dose Results 2.0 Radioactivity 2.1 Airborne and Liquid Emuents 2.2 SolidWaste 3.0 REMODCM Changes 1 I
i 4.0 Inoperable Emuent Monitors 5.0' Errata l
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introduction This report, for the period of January through December of 1998, is being submitted for Connecticu Atomic Power Company's Haddam Neck Plant in accordance with 10CFR50.36a and the Ra Emuent Technical Specifications and is written in the US NRC Regulatory Guide 1.21 format.
The report provides radioactivity information for airborne and liquid emuents and solid waste. Doses I regulatory limits are provided for airborne end liquid effluents. Any changes to the REMODCM, de any emuent monitors inoperable for more than 30 days, and any corrections to previous reports are inclul The Haddam Neck plant had a permanent cessation of operation in December 1996. The pla the process of decommissioning.
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1.0 Doses This report provides a summary of the 1998 off-site radiation doses from releases of radioactive materials in airbome and liquid effluents for the Haddam Neck Plant.
Included are the annual population dose commitments (person-rem) for the area within 50 miles of the site, the annual aver dose commitment (mrem) to the population, and the annual maximum dose commitment (mrem) t real member of the public. Also provided are the maximum gamma and beta air doses.
The doses are compared with the regulatory limits and wah 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 obtained 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 Operating 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 site. The doses are based upon exposure to the airbome and liquid effluents over a one year period and an associated dc.a commitment over a 50-year period from initial exposure due to inhalation and ingestion, taking into account radioactive decay and biologicalelimination of the radioactive materials contributing to the dose. The population dose commitment (person-rem) is the integration of the doses for each compass sector in each of the radial distances with the population distribution in those areas.
Maximum Individual dose commitment is defined as the dose to the individual with 50 mile population who would receive the maximum dose from releases of airborne and liquid effluents. The doses are based upon exposure to lhe airbome and liquid effluents over a one year period and an associated dose commitment over a 50-year period from initial exposure due to inhalation and ingestion, taking into account radioactive decay and biological elimination of the radioactive materials contributing to the dose. Although the location of the maximum individual may vary each quarterly period, the annual dose is the sum of these quarterly doses. This conservatively assumes that the individual is at the location of maximum dose each quarter.
The dose calculations are based upon these three types of input: radioactive source term, site specific data, and generic factors. The radioactive source terms (Curies) are characterized in the Radioactivity 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 airbome 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 factors include 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 i
meat, fish, and shellfish) and occupancy factors (for air submersion and ground irradiation, shoreline activity, swimming, boating, etc.). All these inputs are used in the appropriate dose models to calculate the population and individual dose commitments from radioactive airbome and liquid effluents.
1.1.1.1 Airborne Effluents Maximum individual doses and population doses due to the release of noble gases, radioiodines, 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 con:puter storage.
Vent (175 ft) releases are considered mixed mode (partially elevated and partially ground) releases; and, Pasquill 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 through the vent (waste gas tanks, vent header, volume control tanks, and containment purges). These doses were summed to determine the total airbome 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 11 (Ref 4) code, which uses the dose models and parameters cited in NRC Regulatory Guide 1.109 and site specific inputs.
1.1.2 Gamma and Beta Air Doses Maximum gamma and beta air doses from the release of noble gases are calculated using the GASPAR code.
1.2 Dose Results 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
I 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.
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 the highest decayedX/O where a potential for dose exists.
For ground deposition, the maximum individual dose is calculated at the off-site maximum land location of the highest x/O and highest D/O where a potential for dose exists.
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 maximum deposition.
To determine compliance with 10CFR50, Appendix I (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 (inhalation and ingestion). 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 airbome effluents are presented in Table 1-1.
These doses are the maximum doses observed.
1.2.2 Liquid Effluents I The LADTAP 11 code performs calculations for the following pathways: fish, shellfish, algae, drinking water, irrigated food, shoreline activity, swimming, and boating. At Haddam Neck, the algae, drinking water, and irrigated food patnways 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.
1 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 quarterly doses presented in Table 1-1 and 1-2 are well below the permissible levels in 10CFR50 and the applicable Radiological Effluent Technical Specifications and are small in comparison to the dose from natural background radiation.
Refer to Table 1-3 for the summary of annual doses for the 50 mile population, the maximum, and average individual due to airborne and liquid effluents. Table 1-4 provides a quantitative comparison between the doses from the Haddam Neck Nuclear Plant and those doses from other sources such as naturally occurring background radiation.
For compliance with 40CFR190, (Reference 6), any direct dose from the site must be added to the dose due effluents 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 within storage criteria that ensures the public dose to be less than 1 mrem /yr for each storage area. Table 14 indicates the total dose to a member of the public from the site and all sources of the fuel cycle is well within the
' 40CFR190 limits.
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References 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 Reactor Regulation, US Nuclear Regulatory Commission, Washington, DC 20555, manuscript completed January 1980, published June 1980.
- 2. I NRC Regulatory Guide 1.109 Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Puroose of Evaluatino Comoliance with 10 CFR Part 50. Aooendix 1. Revision 1, October 1977, 3.
NRC Regulatory Guide 1.111 Methods for Estimatino Atmosoherie Transoort and Discersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reacto[s, Revision 1, July 1977.
- 4. NUREG/CR-1276, ORNUNUREG/TDMC-1 User's Manual for LADTAP ll - A Comouter Prooram for Calculatino Radiation Exoosure to Man from Routine Release of Nu Reactor Liouid Effluents. DB Simpson, BL McGill, prepared by Oak Ridge National Laboratory, Oak Ridge, TN 37830, for Office of Administration, US Nuclear Regulatory Commission, manuscript completed 17 March 1980.
- 5. 10 CFR Energy, Part 50 Domestic Licensino of Production and Utilization Facilities.
Appendix l Numerical Guides for Design Obiectives and Limiting Conditions for Ooeration to Meet the Criterion "As Low As Reasonablv Achievable" for Radicactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents.
6.
40 CFR Environmental Protection Agenev. Part 190 Environmental Radiation ProtectioD Standard for Nuclear Power Ooeration.
- 7. Engineering Record of Correspondence No.16103-ER-0005, Connecticut Yankee Chemistry inout to the 1998 Annual Effluent Reoort , Rev 0, April 20,1999.
Table 1-1 1998 Off-Site Dose Commitments from Airborne Effluents l
Connecticut Yankee CY 1st Quarter 2nd Quaner 3rd Quaner 4th Quener Max Air (mrod) (ano) (mrad) (mrad) 8ete 0 0 0 0 {
Gamrne 0 0 ;
0 0 Max individual (mrom) (mem) l (mrerro (mrem)
Mole Sody* 0 0 1.50E-04 eon =Nm 0 SAin' ~ 0 0 Thyroid 1.75E-04 e o n a Nm 0 8.64E-03 e e n m NNWM 4,08E-03 eennNmM 2.68E-02 con Nam Mas oroan* 8 64E-03 eonnNampeau 4.08E-03 e on=Numm.piu 2.68E-02 e o n m NNW M m e nu 1.16E-02 e e n = Na m Populetkm . 1.16E-02 e o n m NNW m m piM ,
Mrson*W prion. rem) emonam)
. Mole Body 3.27E-02 ersonom) l 2.42E-02 1.02E-01 SAh 3.27E-02 9.56E-02 )
2.42E-02 1.02E-01 9.56E-02 Thyroid 3.27E-02 2.42E-02 I
1.02E-01 9.56E-02 I Mar Orgen* 3.27E-02 mslu 2 42E-02 men u Avg Individual 1.02E-01 menu 9.56E-02 menu (mem) (mrom) (mrem) (mem)
Mole Body 8.54E-06 6.32E-06 2.66E-05 2.50E-05 S4m 8 54E-06 6 32E-06 2.66E-05 Thyroid 8.54E-06 2.50E-05 6.32E-06 2.66E-05 2.50E-05 l Mar organ
- 8.54E-06 m.esu 6.32E-06 men u 2.66E-05 men u 2.50E-05 men u (a)=Aduft, (c)=Cruid. (i)= infant, (t)= Teen (bo)= Bone, (gi)=GI-LLt, (lu)* Kidney, (h)=Lwer, (lu)=Lun0. ('h)*Thyrogj
- Extemal doses only ]
" Meximum of the following orDans Bone, GI-LLl, Kidney, Liver, Lung. Thyrous l
l Table 1-2 1998 Off-Site Dose Commitments from Liquid Effluents Connecticut Yankee CY tst Quaner 2nd Quarter 3rd Quarter 4th Quarter Max Individual (w.w (mem) (wem) Wem)
Mole Sorfy 5.50E-02 (a) 5.42E-02 (a) 3.58E-02 (a) 2.97E-03 (a)
Thyrod. 4.97E-04 (a) 1.06E-03 (a) 1.39E-03 (a)
Mar Orpen 1.92E-04 (a) 8.42E-02 m 00 8 24E-02 m 04 5.37E-02 m 00 Populatkm 4.69E-03 m 00 (r:=: err 9 prionam) Hmoa*rro ><sonam)
- Mole Body 9.11 E-01 8.89E-01 5 82E-01 4.94E-02 Thyroid 4.58E-03 2.99E-03 7.64E-03 1.47E-03
- Max orpen 1.64E+00 00 1.60E+00 00 1.04E+00 00 9.37E-02 co Avg Individual (mrom) . (mrerro (mrom) (mrem)
Mole Sody 2.38E-04 2.32E-04 1.52E-04 1.29E-05 Thyroid 1.20E-06 7.81 E-07 1,99E-06 3.84E-07 Mer Organ 4.28E-04 00 4.18E-04 on 2.72E-04 ca 2.45E-05 00 (a)= Adult. (c)= Child, (t)= Infant, (t)= Teen (bo)= Bone, (g<)=GI-LLI, (ki)=Ksdney. (h)=Lwer. (luPLung (th)=Thyront
Table 1-3 I
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_1998 Off-Site Dose Summarv fom Emuents i Haddam Neck Plant i I
Airborne Emuents Population Dose Commitments (person-tem)
Whole Body Thyroid Max organ Skin :
0.2545 0.2545 0.2545 0.2545 j
i Max Individual Dose / Dose Commitments vs Annual Radiological Effluent T';chnical Specifications Sete Air Gamma Air Whole Body
- . Thyroid Max Organ - Skin -
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- Does. . Dose !
(trummy ^ (nuem) (mrom) (mrom) (mrad) - ~ (mnedl UnitMETS 5* 15 15 15
- 20 to Site Total . 0.0002 0.0511 0.0511 0.0002 0.0000 0.0000
- 10CFR50. Appends I hmda l Liquid Emuents Population Dose Commitments (person-rem)
Whole Body : Thyroid Max Organ 2.4314 0.0167 4.3737 l
Max individual DosatDose Commitments vs i Annual Radiological Effluent Technical Specifications i
whole Body . Thyroid Max organ
'(mrom)- (memm)' (mrom)
UnetntTS 3 to 10
. Sete Total 0.1480 0 0031 0.2250 l
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Table 1-4 l 1998 Off-Site Dose Comoariann Haddam NaCk Plant Max Individual Dose / Dose Commitments vs 40CFR190 Limits Whole Body Max Organ (mrom) (mrom) 40CFR190 Limit 25 75 Airbome Effluents 00002 0 0511 Liquid Effluents 0.1460 0.2250 Radweete Stora0e 3 0000 3.0000 Station Total 3 148 3 276 Whole Body Dose from Haddam Neck Plant vs. Background Radiation Sources of Backaround Radiation:
Cosmc 27 Cosmogene 1 Terrestial (Atlante and Gulf Coastal Plain) 16 inhaled 200 in the Body 40 lCT Resident Whole Body Dose from Background " l 284 mrem l CT Resident (within 50 miles) Whole Body Dose from Haddam Neck Plant Airborne and Liquid Emuents 0.000701 mrem Maximum Individual (within 50 miles) Whole Body Dose from Haddam Neck Plant Airborne and Liquid Effluents 0.148 mrom Maximum indwidual (within 50 miles) Whole Body Dose from Haddam Neck Piard and all sources of the fuel cycle 3.148 mrom l
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2.0 Radioactivity 2.1 Airborne Effluents 2.1.1 Fission and Activation Gases Main Stack effluents were continuously monitored for gaseous fission and activation gases with an in-line scintillation detector. Gaseous grab samples were collected and analyzed for radioactivity with the gamma spectroscopy system.
2.1.2 lodines Main Stack effluents were continuously sampled with an in-line charcoal cartridge.
lodine samples were analyzed with the gamma spectroscopy system.
2.1.3 Particulates Main Stack effluents were continuously sampled with an in-line particulate filter.
Particulate filters were analyzed for gamma activity, gross alpha, Strontium 89 and 90.
2.2 Liquid Effluents 2.2.1 Batches Liquid Batch releases were sampled and analyzed prior to discharge for gamma and tritium activity, Liquids were monitored during release by two in-line scintillation detectors. Composite samples were analyzed for gross alpha, Fe-55, Sr-89 and 90.
2.2.2 Continuous Liquid Continuous release pathways were sampled and analyzed for gamma and tritium activity, if required, composite samples were analyzed for gross alpha, Fe-55, Sr-89 a' i Sr-90.
2.3 Estimate of Errors 2.3.1 Airbome Fission and Activation Gases 14 %
lodines 13%
Particulates 14 %
Tritium 8%
2.3.2 Liquid Fission and Activation Products 11 %
Tritium 3.5%
j Dissolved and Entrained Gases 19% '
Gross Alpha 8%
2.4 Batch Releases 2.4.1 Airborne Effluents Purge WGDT Summary Number of Batches 4 0 4 Total Time (min) 508,716 0 508,716 Maximum Time (min) 236,125 0 236,125 Average Time (min) 127,179 0 127,179 Minimum Time (min) 16,093 0 16,093 2.4.2 Liquid Effluents Number of Batches 49 Total Time (min) 15.597 Maximum Time (min) 798 Average Time (min) 318 Minimum Time (min) 16 Average Stream Flow (ft2/sec) 15,800 2.5 Abnormal Releases During the discharge to the Connecticut River of the 'B' Waste Test tank, a valve isolating the
'A' Waste Test tank from the discharge path (WD-V-133A) was inadvertently bumped partially open by a plant worker. Approximately 600 gallons of the 'A' Waste Test Tank were discharged along with the 'B' Waste Test Tank. This release started on 6/20/98 @ 0930 and ended on 6/20/98 @ 1115. The release of the tanks was secured automatically by the R-22 Test Tank radiation monitor high activity alarm. This radiation monitor's trip setpoint was set based on limiting the release to 10% of the Technical Specification limits. A total of -1700 microcuries were released to the Connecticut River from the 'A' Waste Test tank. The 'A' tank had been sampled prior to this event and was approved for release in accordance with normal plant operating procedures. The root cause of this everit was determined to be personnelin the area of the valve being unaware of plant conditions and evolutions in progress in their work area.
This inattention to detail was compounded by the lack of consistent management expectations for monitoring evolutions in progress. Corrective actions taken as a result of this event include the reinforcement of management expectations for monitoring evolutions in progress and the placement of a plant operator in the erea of the discharge path during the discharge. 'A' Waste Test tank was sampled and available for release, however, it was not to be released in conjunction with the 'B' Waste Test Tank. The calculated dose to the public associated with the material released from 'A' Test Tank was 0.003 mrem to the whole body and 0.005 mrem to the limiting organ. There were no personnel injuries or equipment damage as a result of the event.
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e Effluent Release Tables Table 2-1 Airborne Effluents - Release Summary Table 2-2 Airborne Effluents - Mixed Batch - Containment PurgesNent Header l Table 2-3 ' Airborne Effluents - Mixed Batch - WGDT Table 2-4 Airborne Effluents - Mixed Continuous Table 2-5 Liquid Effluents - Release Summary Table 2-6 Liquid Effluents - Batch Table 2-7 Liquid Effluents - Continuous I
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1 Table 2-1 Haddam Neck Airborne Effluents - Release Summary 1998 Units 1st Qtr l 2nd Qtr 3rd Qtr l l 4th Qtr l Total A. Fission & Activation Gases
- 1. Total ActMty Cl n/a j n/a l n/a l n/a j n/a Released No Activity Detected
- 2. Average Period uCVeec n/a n/a n/a n/a Release Rate n/a B. lodine-131
- 1. Total ActMty Cl n/a n/a l j n/a l n/a n/a Released {
No Activity Detected
- 2. Average Period uCVeec n/a n/a n/a n/a Release Rate n/a C. Particulates
- 1. Total ActMty Ci n/a n/a 1.25E-05 n/a 1.25E.05 Released
- 2. Average Period UCVsec n/a n/a 1.57E-06 n/a Release Rate 3.96E-07 ~
D. Gross Alpha 1
- 1. Total ActMty Cl n/a j n/a l n/a l n/a j n/a Released j No Activity Detected I E. Tritium
- 1. Total ActMty Cl i 1.80E+01 7.84E+00 2.41E+01 2.84E+01 Released 7.83E+01 i
- 2. Average Period uCusec 2.31E+00 9.97E-01 3.03E+00 3.57E+00 2.48E+00 Release Rate ;
n/a = Not applicable k:WeptdatveeVadongWffluertwffirpt\1998)teblee\ectnntyCYAIR$UM.ute
r Table 2-2 Haddam Neck Airbome Effluents - Mixed Batch - Containment Purges / Vent Header l
Nuclides 1gga Released Units 1st Qtr 2nd Qtr l l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Gases Cl - -
I - -
Total Activity Ci I I n/a l n/a n/a n/a i i n/a l n/a B. lodines
- l-131 Cl - . - -
n/a Ci - - -
Total Activity l n/a Cl I n/a n/a n/a 1 I i n/a i n/a C. Particulates
- l-131 Cl - - - -
n/a Ci - - -
Total Activity n/a l Cl I n/a i n/a n/a i i n/a i n/a D. Gross Alpha
- l Gross Alpha l Cl 1 -
I - -
I -
I I n/a l E. Tritium lH-3 l Cl i 6.10E+00 1 3.81 E+00 1 1.82E+01 l 9.87E+00 l 3.80E+01 l
- Reported with Mixed Continuous
= Less than minimum detectable activity n/a = Not applicable us.mv v nr.mnewn,,,uessa.ww, remsuu.*
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Table 2-3 Haddam Neck Airborne Effluents - Mixed Batch - WGDT
<< No Activity Detected >>
Nuclides 1998 Released Units 1st Qtr 2nd Qtr l l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Gases i Ci I -
) -
I -
Total Activity Ci j I -
i n/a l n/a I n/a n/a l i n/a i n/a B. lodines
- l-131 Ci - - - -
n/a Cl - - -
Total Activity l n/a Ci i n/a i n/a I n/a n/a l i n/a l
C. Particulates
- l l-131 Ci - - - -
n/a Ci - - -
Total Activity l n/a Cl I n/a i n/a n/a i i n/a i n/a D. Gross Alpha
- l Gross Alpha l Cl j - -
1 I -
I -
I n/a l E. Tritium lH-3 i Cl 1 - j -
I -
i 1 -
I n/a l
- Reported with Mixed Continuous
- = Less than minimum detectable activity n/a = Not applicable 1
i OndeptdatVeeVedong' effluent'effirpti19981tableeucwety\CYAIRSUMsJe
Table 2-4 Haddam Neck Airbome Effluents - Mixed Continuous l
Nuclides Released 1998 Units 1st Qtr 2nd Qtr {
l l 3rd Qtr l 4th Qtr l Total j A. Fission & Activation Gases i I Cl -
I -
i -
Total Activity i Ci I Wa n/a i n/a l n/a n/a i n/a B. lodines I-131 Ci - - - {
n/a 1 Ci - - -
Total Activity l Cl Na n/a i n/a n/a i n/a i n/a C. Pasticulates 1-131 Cl - - -
Cs-137 Ci -
n/a 1.25E-05 -
1.25E-05 Total Activity l Ci l n/a n/a i i 1.25E-05 I n/a i 1.25E-05 D. Gross Alpha l Gross Alpha l Cl 1 -
I -
I -
I -
i n/a l E. Tritium I
]H-3 i Cl i 1.19E+01 i 4.03E+00 1 5.90E+00 l 1.85E+01 1 4.03E+01 l
- = Less than minimum detectable activity n/a = Not applicable ew.cw, vmw==wamueenw.aimm4msvu,w
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Table 2-5 Haddam Neck Liquid Effluents - Release Summary 1
1998 l Units , 1st Otr l 2nd Otr l 3rd Qtr l 4th Otr l Total A. Fission and Activation Products
- 1. Total Activity 2.12E-02 3.94E-02 Released l Ci 5.46E-03 l 1.69E-02 q
l 8.29E-02 i i
- 2. Average Period 3.62E-09 r 8.19E-09 uCi/mi l 9.16E-10 ! 2.12E-09 3.37E-09 Diluted Activity i 8
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B. Tritium
- 1. Total Activity i Ci i 1.92E+00 . 2.55E+01 7.21 E+01 l 1.28E+01 1.12E+02 Released l I
- 2. Average Period uCi/mi ! 3.21 E-07 . 3.20E-06 1.23E-05 1 2.67E-06 , 4.57E-06 Diluted Activity . ! l !
C. Dissolved and Entrained Gases
- 1. Total Activity ;
Ci j n/a n/a ! n/a l n/a n/a Released 1 No Activity Detected
- 2. Average Period n/a n/a n/a n/a ! n/a uCi/ml l l l Diluted Activity !
D. Gross Alpha j
- 1. Total Activity Ci ; n/a j n/a j n/a j n/a n/a i Released ! No Activity Detected E. Volume
- 1. Released Waste 2.23E+06 2.60E+05 3.89E+06
, Liters j 6.43E+05 i 7.59E+05 volume l i
- 2. Dilution volume ! uters I ! 4.54E+09 ;i 6.54E+09 4.23E+09 3.30E+09 1.86E+10 During Releases i i i !
- 3. Dilution volume ; uters ! 5.96E+09 ; 7.96E+09 , 5.87E+09 , 4.81 E+09 2.46E+10 During Period I n/a = Not applicable k:\deptdatavesVedong\ effluent \ef fk pt\1998\ tables \ activity \CYLIOSUM.nle
Table 2-6 Haddam Neck Liquid Effluents - Batch Nuclides 1998 Released Units 1st Otr l 2nd Qtr 3rd Otr l l 4th Otr l Total A. Fission & Activation Products Ag-110m , Ci 1 i -
! 3.38E-04 7.45E-05 4.13E-04 Am-241 ! Ci i - --
1.19E-05 I -
1.19E-05 Co-60 ) Cl 5.26E-04 '
9.38E-03 1.15E-02 1.40E-03 2.28E-02 Cs-134 ! Ci 6.08E-04 6.44E-04 4.67E-04 3.55E-05 1.75E-03 Cs-137 i Ci
- 4.30E-03 5.56E-03 3.51 E-03 2.75E-04 1.36E-02 Fe-55 I Ci i -
1.17E-03 6 5.20E-03 I 3.76E-02 4.40E-02 Mn-54 i Ci - '
4.55E-05 i 8.42E-05 7.56E-06 1.37E-04 Ru-106 ! Ci -
i -
1 7.44E-05 i -
7.44E-05 Sb-125 ,
Ci -
t 5.67E-05 5.37E-05 '
1.10E-04 Total Activity Ci 5.43E-03 1.69E-02 2.12E-02 3.94E-02 8.29E-02 B. Tritium lH-3 '
Cl 1.22E+00 2.55E+01 7.21 E+01 1.28E+01 1.12E+02 l C. Dissolved & Entrained Gases Ci - - - -
n/a Total Activity Ci ! n/a !
n/a n/a n/a n/a D. Gross Alpha l Gross Alpha i Ci ) - i - -
! r -
n/a l
- = Less than minimum detectable activity n/a = Not applicable k:\deptdataVesVedeng\ettluent\effkpt\1998\ tables \ activity \CYUQSUM. mis
Table 2-7 Haddam Neck Liquid Effluents - Continuous Nuclides 1998 Released Units 1st Qtr 2nd Qtr 3rd Qtr l l l 4th Qtr l Total A. Fission & Activation Products Cs-137 Ci ! 2.39E-05 >
4.71E-08 -
i -
i 2.39E-05 Total Activity i Ci 1 2.39E-05 ; 4.71 E-08 i n/a i n/a 2.39E-05 B. Tritium lH-3 e Ci 6.95E-01 1.37E-02 1.07E-02 2.32E-02 7.43E-01 l C. Dissolved & Entrained Gases i Ci $ - - - i - .
n/a Total Activity Ci n/a n/a n/a n/a n/a D. Gross Alpha j
l Gross Alpha Ci - -
n/a l
- = Less than minimum detectable activity n/a = Not applicable 1
1 k :\dsptdatairesVadeng'. affluent \effirpt\ 1998 stables \activit y\CYLIOSUM. mis
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 (st No solidification on site for 1998.
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Containers routinalv used for radinndive waste shioment include-1 No radioactive waste shipments were sent for direct disposal from the site in 1998.
Waste is being shipped for offsite processing and disposal.
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r-Solid Waste and Irradiated Component Shipments Connecticut Yankee Atomic Power Company Haddam Neck Plant A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fu
- 1. Type of Waste
- a. Spent resins, filter sludge, evaporator bottoms, et::.
Disposition Units Annual Totals Est. Total Error %
From Haddam Neck to Chem Nuclear Systems m3 0 Bamwell, SC for disposal 25 %
Ci 0
- b. Dry compressible waste, contaminated equipment, etc.
Disposition Units i Annual Totals Est. Total !
Error %
From Haddam Neck to GTS Duratek - m3 533.6 Oak Ridge, TN for processing 25 %
Ci 2 442 From GTS Duratek to Chem Nuclear Systems, m3 15.71 Barnwell, SC for burial 25 %
Ci 0.995 .
From GTS Duratek to Envirocare, !
m3 S.2 Clive, UT for disposal 25 %
Ci 0.025 From Haddam Neck to Manufactunng m3 279.5 Sciences Corporation, Oak Ridge , TN for processing 25 %
Ci 0.133 From Manufactunng Scences Corporation to m3 0 Chem Nuclear Systems, Samwell, SC for burial 25 %
Ci 0 From American Ecology Corporaten m3 37.2 to Envirocare, Clive. UT for burial 25 %
Ci 0.235
- c. Irradiated components, control rods, etc.
Disposition Units Anrmal Totals Est. Total Error %
NONE SHIPPED IN 1998
- d. Other-(Oil, Oily Sludge)
Disposition Units Annual Totals Est. Total Error %
NONE SHIPPED IN 1998 1
- d. Other-(Mixed Waste)
Disposition Units Annual Totals Est. Total Error %
NONE SHIPPED IN 1998 2
- 2. Estimate of major nuclide composition (by type of waste)
- a. Spent resins, filter sludge, evaporator bottoms, etc.
Radionuclides % of Total (Estimate)
NONE SHIPPED
- b. Dry compressible waste, contaminated equipment, etc.
Radionuclides % of Total (Estimate)
Co 60 12.96 Cs 137 10.52 Ni 63 6.70 Fe 55 69.81
- c. Irradiated components, control rods, etc.
Radionuclides % of Total (Estimate)
NONE SHIPPED 3
- d. Other Radionuclides
% of Total (Estimate)
NONE SHIPPED l
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- 3. Solid Waste Disposition
- Number of Mode of Transportation Destination Containers Utilized Shipments 12 Truck (Sole Use Vehicle) GTS Duratek - Oak Ridge, TN Steelboxes, c-vans 6
Truck (Sole Use Vehicle) MSC - Oak Ridge, TN Steelboxes, c-vans B. IRRADIATED FUEL SHI?MENTS Number of Shipments Mode of Transportation NONE IN 1998 Destination i
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3.0 REMODCM Changes in 1998, there were no changes to the REMODCM.
Section I (REMM) None Section II (ODCM) None REMODCM changes are reviewed by PORC and approved by the Unit Director. The changed pages, if any, for each REMODCM change are included in this report. In adaition, a complete updated copy of the REMODCM, as of 12/31/98, is provided to the Nuclear Regulatory Commission along with this report.
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4.0 Inoperable Effluent Monitors i
During the period January 1 through December 31, 1998, the following eEuent monitors were inoperable for more than 30 consecutive days:
4.1 Test Tank Release Monitor (R-22)- from 11/16/98 to January 1999 The R-22 monitor was made inoperable during efforts to replace the monitor with a new !
Victoreen liquid radiation monitor. Efforts to install and calibrate the new monitor required l
removal of the old monitor. Processing of the design change documentation and performance l
of the calibration and procedure upgrades caused this monitor to be inoperable for greater than !
30 days. Compensatory sampling, calculations, and valve lineup verifications were performed l during the inoperability period. The new monitor has been installed, calibrated, and was i placed in service in January 1999.
4.2 Stack Flow Monitor (FE-1101)- from 5/11/98 to March 1999 On May 11,1998, the stack flow monitor was determined to be reading lower than expected for the ventilation configuration. An engineering evaluation of the plant ventilation ' systems determined that the flow monitor had an insufficient range for all plant operating conditions.
Additionally, there were no repair parts available since the manufacturer was no longer in business. The stack flow rate is being monitored by a temporary instrument which is verified by plant operators periodically. A design change is being processed to replace the stack flow monitor with a newer, more accurate model which has sufficient range for all plant conditions.
The new stack flow monitor has been installed, calibrated and was placed in service in March 1999. i i
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i 5.0 Errata There are no errata for the 1997 Annual Radioactive Effluent Report.
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g i Docket No. 50-213 CY-99-057 {
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Attachment 2 Haddam Neck Plant Radiological Effluent Monitoring and Offsite Dose Calculation Manual 4
April 1999 l
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