ML20216B299

Annual Radioactive Effluents Rept

ML20216B299
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	12/31/1997
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20216B297	List: CY-98-063, Forwards Haddam Neck Plant Annual Radioactive Effluents Rept & Rev 8 to ODCM for Haddam Neck Plant. Rept Includes Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents ML20216B299 ML20216B307
References
NUDOCS 9805180026
Download: ML20216B299 (36)

Text

l Docket No. 50-213 CY-98-063 Attachment 1 Haddam Neck Plant Annual Radioactive Effluents Report April 1998 9005180026 900430 PDR ADOCK 05000213 R PDR

Annual Radioactive Effluent Report 1997 1

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

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Table of Contents l

Introduction j 1.0 Doses 1.1 Dose Calculations 1.2 Dose Results j 2.0 Radioactivity j l

2.1 Airborne and Liquid Efflueits 2.2 Solid Waste 1

3.0 REMODCM Changes 4.0 Inor ibleEffluentMonitors 5.0 Errata 1

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introduction This report is being submitted for Connecticut Yankee Atomic Power Company's Haddam Neck Plant in

! accordance with 10CFR50.36a and the Radiological Effluent Technical Specifications and in the US NRC i Regulatory Guide 1.21 format.

i The report provides radioactivity information for airborne and liquid effluents and solid waste. Doses and l regulatorylimits are provided for airborne and liquid effluents. Any changes to the REMODCM, description of l any effluent monitors inoperable for more than 30 days, and any corrections to previous reports are included. ;

The Haddam Neck plant had a permanentcessation of operation in December 1996. The plant is currently in the process of decommissioning.

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l 1.0 Doses This report provides a summary of the estimated off-site radiation doses from routine releases of radioactive materials in airbome and liquid effluents for the unit. Included are the annual population dose commitments (person-rem) for the area within 50 miles of the site, the annual average dose commitment (mrem) to the population, and the annual maximum dose commitment (mrem) to any real J member of the public. Also provided are the maximum gamma and beta air doses.

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[ 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 1.1 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 {

conservativeassumptions used in these models. More realistic estimates of the off-site dose can i l

be obtained by analysis of environmentalmonitoring 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 i 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 for a one year period and an associated dose commitment over a 50-year period from initial exposure, taking into account radioactive decay and biologicateliminationof the radioactivematerialscontributingto the dose. The population dose commitment (person-rem)is the sum of the individualdoses.

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 characterizedin the Effluent Activity section of this report. The site specific data includes:

meteorological data (e g. wind speed, direction, stability, etc.) to calculate the transped and dispersion of airborne 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). All these inputs are used in the appropriate dose models to calculate the population and individual dose commitments 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 particulateswere calculated using the computer code GASPAR (Ref 1).

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The GASPAR code is an NRC code which uses a semi-infinitecloud 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 (partidly elevated and partially ground) releases; and, Pasquilt stability classes are determined based upon the temperature gradient between the 33 ft and 196 ft meteorological towerlevels.

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 total airborne effluent dose.

1.1.1.2 Liquid Effluents Maximumindividualand population doses from the release of radioactiveliquid 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 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 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 j same organs listed above for the following pathways: direct exposure to the plume, I

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 l off-site location of highest decayed X/O where a potentialfor dose exists.

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

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For the vegetation pathway, the maximum individual dose is calculated at the vegetable garden of highest D/O. 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 l (Ref 5), the maximum indivi.fual whole body dose only includes the external pathways (i.e. Name and ground exposure) while the maximum individual organ dose only includes the internal pathways.

- Population doses include all applicable pahways.

The air dore includes only the dose frora nob!e gases in the plume. Hence, if the ground shine contribution was significant, thera may be cases where the maximum whole body or skin dose is greater than the maxirium 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 bosting. At Haddam Neck, the shellfish, the algae, drinking water, and irrigated food pathways do not exist; at:d, 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 small in comparison to the dose from natural background radiation. The statisticalexpectation of adverse health effects from the calculated radiation dose due to nuclear plant operationsis 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 doses from other sources such as naturally occurring background radiation. Also provided are the allowed 40CFR190 (Ref 6)leveh to a real member of the public. Note that the maximum individualin Tables 1-1,1-2, and 1-3 is conservativelyassumed 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 potentialdirect 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. Thus, the total dose to a member of the public is a small fraction of the 40CFH190 limits.

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, mar,uscript completed January 1980, published June 1980.

2. NRC Regulatory Guide 1.109 Calculation of Annual Doses to Man from Routine Releases of Reac+or Effluents for the Purpose of Evaluatina Compliance with 10 CFR Part 50. Accendix 1. Revision 1, October 1977.

3. NRC Regulatory Guide 1.111 Methods for Estimatina Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Liaht-Water-Cooled Reactors.

Revision 1, July 1977.

4. NUREG/CR-1276, ORNL/NUREG/TDMC-1 User's Manual for LADTAP ll - A Computer Proaram for Calculatina Radiation Exposure to Man from Routine Release of Nuclear Reactor Liauid 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 Enerav. Part 50 Domestic Licensina of Production and Utilization Facilities Appendix 1 Numerical G pides for Desian Objectives and Limitina Conditions for Operation to Meet the Criterion "As Low As Reasonably Achievable" for Radioactive Material in Licht-Water-Cooled NucleF Power Reactor Effluents 1 January 1994 Edition.

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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l Table 1-1 1997 Off-Site Dose Commitments from Airborne Effluents Connecticut Yankee CY tst Quarter 2nd Quarter 3rd Quarter 4th Quaner MIm Air (mrad) (mrad) (mrad) (mrad)

Bete 000E+00 1.14E-09 0 0 3 m NNW 0.00E+00 0.00E+00 Gamma 0 00E+00 1.00E-11 0 0 3 m NNW 0.00E+00 0.00E +00 MIm Individual (mrem) (mem) (mrem) (mrem Mole Body 1.65E-02 o O M m NW 4.74E-04 o O M m NW 000E+00 0 00E+00 Thyroid 1.37E-02 a 0 32 m NNW t0 1.84E-03 o 0 32 m NNW 0) 4.42E-03 o 0 32 m NNW m 2.27E-03 o 0 8 m SE (O SAin 1.93E-02 o o Mg NW 5 55E-04 o O M m NW 0.00E+00 0 00E+00 Population (person-rem) (personm) (person-rem) (person rem)

Mole Body 1.52E-02 9.12E-03 2.34E-02 2.87E-02 ThyroM 1.51 E-02 9.04E-03 2.34E-02 2.87E-02 Skin 1.65E-02 9 07E-03 2.34E-02 2.87E-02 Avg Individusi (mem) (mrem) (mem) (mrem)

Mole Body 4 06E-06 2.44E-06 6.26E-06 7.67E-06 Thyroid 4 04E-06 2.42E-06 6.26E-06 7.67E-06 SAin 4 41 E-06 2.43E-06 6.26E-06 7,67E-06 (a)= Adult. (c)=Chdd. (s)= Infant. (t)= Teen Table 1-2 l

1997 Off-Site Dose Commitments from Liquid Effluents Connecticut Yankee CY 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter mix Individual (miem) (mrem) (mrem) (mrem)

Mole Body 5.13E-04 (a) 2.48E-02 (a) 1.65E-04 (a) 6.75E-03 (a)

Thyroid 3.28E-04 (a) 3.70E-04 (a) 1.07E-04 (a) 1.42E-04 (a)

Max Organ 5.73E-04 (a) 00 3.90E-02 e) 00 1.61 E-04 (ai oo 1.06E-02 (u 00 Population (person rem) (person-rem) (person-rem) (persorvrem)

Mole Body 4 24E-04 1.87E-02 1.40E-04 5.10E-03 Thyroid 2.79E-04 2.66E-04 9 21 E-05 1.09E-04 Max organ 5 07E-04 on 3.46E-02 00 1.42E-04 00 9.45E-03 00 Avg Individual (mrem) (mrem) (mrom) (mrem)

Mole Body 1.13E-07 5.00E-06 3.74E-08 1.36E-06 Thyroid 7.46E-08 7.11 E-08 2.46E-08 2.91 E-08 Max Organ 1.36E-07 00 9.25E-06 00 3 80E-08 00 2.53E-06 00 (a)=AduR (c)=Chdd. (i)=lntant. (t)= Teen (bo)= Bone. (gi)=GI-LLI, (ki)= Kidney (h)= Liver. (lu)= Lung. (th)= Thyroid

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l 1997 Off-Site Dose Summary Connecticut Yankee l

l Population Dose Committments (person-rem)

Airborne Liquid Whole Body l Thyroid l Skin Whole Body l Thyroid l Max organ l Station 0 0764 0.0762 0.0777 0.0244 0 0007 0.0447 Max Individual Doses vs Limits Whole Body Thyroid Max Organ Skin Air Airborne l Liquid Airborne l Liquid Liquid Airborne Beta l Gamma (mrem) (miem) (mrem) (mrem) (mrad)

Unit Limit

• 5 3 15 10 f0 15 20 10 Unit Actual 00170 0 0322 0 0222 0 0009 0.0503 0 0199 0 0000 0 0000 Station Limit " 25 75 25 Station Actual 00492 0 0232 0 0503 Connecticut Resident Average Whole Body Doses (mrem)

Cosmic 27 Cosmogenic 1 Terrestial(Atlantic and Gulf Coastal Plain) 16 inhaled 200 in the Body 40 Average CT Resident Whole Body Dose from Background "* l 284 Average CT Raident (within 50 miles) Whole Body Dose from Connecticut Yankee Station Radioactive Ef!Iuents 0.0000

• 10CFR50 Appenchx 1

" 40CFR190

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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 and Sr-90. ,

1 2.3 Estimateof Errors 2.3.1 Airborne Fission and Activation Gases 14 %  !

! lod',',es

. 13 %

l= Particulates 14 %

Tritium 8%

2.3.2 Liquid l I

Fission and Activation Products 11 % i Tritium 3.5%

Dissolved and Entrained Gases 19%

Gross Alpha 8% l l

2.4 Batch Releases 2.4.1 Airborne Purge WGDT Summary Number of Batches 3 5 8 Total Time (min) 226,380 3,004 229,384 Maximum Time (min) 132,480 1,528 132,480 Average Time (min) 75,460 601 28,673 Minimum Time (min) 17,580 110 110 2.4.2 Liquid Number of Ba'.ches 31 Total Time (min) 13,305 Maximum Time (min) 2,746 Average Time (min) 429 Minimum Time (min) 7 Average Stream Flow (ft'/sec) 15,800 2.5 Abnormal Releases (Exceed Technical Specification Limits)

None.

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Effluent Release Tables Table 2-1 Airbome Effluents - Release Summary Table 2-2 Airborne Effluents - Mixed Batch - Containment PurgesNent Header 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  !

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Table 2-1 Haddam Neck Airborne Effluents - Release Summary 1997 Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Gases

1. Total Actmty Cl 1.39E-02 1.28E-06 - -

1.39E-02 Released

2. Average Period uCi/sec 1.758-03 1535~07 n/a n/a 4.41 E-04 Release Rate B. lodine-131 1, Total Actmty Cl - - - - -

Released

[ 2. Average Period uCi/sec n/a n/a n/a n/a n/a Release Rate C. Particulates

1. Total Actmty Cl 7.52E-04 1.97E-05 - -

7.72E-04

( Released

2. Average Period uCi/sec 9.6'/E-05 2.505-06 n/a n/a 2.45E-05 Release Rate l

I D. Gross Alpha

1. Total Activity Cl - - - - -

j Released E. Tritium

1. Total Actmty Cl 3.71 E+01 3.17E+00 1.09E+01 9.60E+00 6.08E+01 Released

2. Average Period uCi/sec 4.Ns+00 4.04E-01 1.37E+00 1.215+00 1.93E+00 Release Rate

- = Less than minimum detectable activity n/a = Not applicable i

k nr adeng\ effluent'attirpt\199 7it antesiactivit y\CY AIRsVM .mle

Table 2-2 Haddam Neck Airborne Effluents - Mixed Batch - Containment PurgesNent Header Nuclides 1997 Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Otr l Total A. Fission & Activation Gases l Ci 1 -

I -

I -

I -

1 -

Total Activity i Ci l -

I -

I -

I -

l -

B. lodines

• l-131 Ci -

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Ci -

I - - - -

Total Activity l Cl 1 -

I -

I -

I -

I -

C. Particulates

• l-131 Ci - - - - -

Cl - - - - -

Total Activity i Ci l -

I -

I -

I -

I -

D. Gross Alpha

• l Gross Alpha i Ci i -

I -

I -

I -

I -

l E. Tritium lH-3 I Ci I 3.21 E+01 I -

I 4.64E+00 1 5.56E+00 1 4.23E+01 l 1

• Reported with Mixed Continuous

- = Less than minimum detectable activity k % edeTaffluent'affIr pr\199 7\t ablesiectmty\CY AIRSUM.xis

Table 2-3 Haddam Neck Airborne Effluents - Mixed Batch - WGDT l

f Nuclides 1 .v 9 7 Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Gases Kr-85 I Ci i 1.39E-02 1 -

1 -

I -

1 1.39E-02 Total Activity l Cl i 1.39E-02 l -

1 -

I -

l 1.39E-02 B. lodines

• 1-131 Cl - - - - - l Cl - - - - -

Total Activity l Ci 1 -

I -

I -

l -

l -

C. Particulates

• i-i31 Ci - - - - -

Ci - - - - -

Total Activity l Cl 1 -

I -

I -

l -

I -

D. Gross Alpha

• l Gross Alpha i Ci I -

l -

I -

I -

I -

l F Tritium lH-3 i Cl i 1.03E-04 1 -

I -

l 1.02E-04 l 2.05E-04 l l

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• Reported with Mixed Continuous

= Less than minimum detectable activity l

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Table 2-4 Haddam Neck Airborne Effluents - Mixed Continuous Nuclides 1997 Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Gases Kr-85 i Ci 1 -

l 1.28E-06 I -

I -

l 1.28E-06 Total Activity i Ci 1 -

l 1.28E-06 l -

I -

l 1.28E-06 B. lodines 1131 Ci - - - - -

-~

Ci - - - - -

Total Activity i Cl 1 -

1 -

1 -

I -

I -

C. Particulates 1-131 Ci _- _

Co-58 Ci 5.22E-06 9.25E-07 - -

6.15E-06 Co-60 Ci 2.07E-04 3.39E-06 - -

2.10E-04 Cs-134 Ci 4.31 E-06 1.37E-06 - -

5.68E-06 dst 137 Ci 5.34E-04 1.40E-05 - -

5.48E-04 l Sr-89 Ci T 8.95E 67 - - -

8.95E-07 l Sr-90 Ci 5.59E-07 - - -

5.59E-07 Total Activity i Ci I 7.52E 04 1 1.97E-05 I -

I -

l 7.72E-04 D. Gross A!pha l Gross Alpha i Cl 1 -

l -

I -

I -

l -

l E. Tritium lH-3 l Ci I 4.97E+00 1 3.17E+00 I 6.27E+00 1 4.04E+00 1 1.85E+01 l

= Less than minimum detectable activity nua.nemo.nn.m,mu seram..uu evsevainsuu. i.

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Table 2-5 Haddam Neck l

Liquid Effluents - Release Summary l

1997 Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Otr l Total A. Fission and Activation Products

1. Total Actuity Ci 6.42E-05 4.44E-04 8.27E-06 1.32E:-05 5.30E-04 Released

2. Average Period uCi/ml 1.31 E-11 f75E-11 2.13E 12 7TSE-12 3.23E 11 Diluted Actwity B. Tritium

1. Total Actuity Cl 1.43E+00 1.52E+01 8.03E-01 3.40E-01 1.77E+01

2. Av rage Period uCl/mi 2.91 E-07 2.63E-06 2.07E-07 1.84E-07 1.08E-06 Diluted Actuity C. Dissolved and Entrained Gases

1. Total Actwity Cl - - - - -

Released

2. Average Period uCi/mi n/a n/a n/a n/a n/a Diluted Activity D. Gross Alpha

1. Total ActNity Cl * - - - -

Released E. Volume

1. Released Waste uters 1.12E+07 1.16E+07 1.13E+07 1.19E+07 4.61 E+07 Volume

2. Dilution volume uters 1.93E+09 2.64E+09 1.67E+09 6.27E+07 6.31 E+09 Dunng Releases

3. Dilution volume uters 4.90E+09 5.75E+09 3.88E+09 1.83E+09 1.64E+10 During Period

- = Less than minimum detectable activity n/a = Not applicable I

k:Vadeng' affluent'efflept\199 htables',actmty\CYLIQSUM. mis

Table 2-6 Haddam Neck Liquid Effluents - Batch Nuclides 1997 Released Units 1st Qtr l 2nd Qtr l 3rd Otr l 4th Qtr l Total A. Fission & Activation Products Co-60 Cl 4.32E-05 6.76E-05 - -

1.11E 04 Cs-134 Cl -

2.96E-05 - -

2.96E-05 Cs-137 Cl 2.02E 05 2.53E-04 4.43E-06 -

2.78E-04 Fe-55 Ci -

4.61 E-05 - -

4.61 E-05 Sr-89 Ci - 5.87E-07 1.76E-06 -

2.34E-06 Sr-90 Cl 7.96E-077 3.02E-06 2.09E-06 - 5.90E-06 Total Activity l Ci l 6.42E-05 I 4.00E-04 I 8.27E-06 l -

l 4.73E-04 B. Tritium  !

lH-3 i Ci I 4.65E-01 l 1.4SE+01 1 4.88E-01 1 -

l 1.56E+01 l I l

C. Dissolved & Entrained Gases i Cl 1 -

I -

I -

I -

I -

Total Activity l Cl 1 -

I -

I -

I -

1 -

I D. Gross Alpha i l Gross Alpha l Ci 1 -

I -

I -

I -

I -

l

= Less than minimum detectable activity l

l kNadeng effluent'affirpt\199 htablesiectivity(CYLIOSUM.nle j

Table 2-7 ]

Haddam Neck Liquid Effluents - Continuous Nuclides 1997 Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total l

A. Fission & Activation Products Cs-137 i Cl i .

l 4.36E-05 l -

1 1.32E-05 1 5.68E-05 ]

Total Activity I Cl 1 -

i 4.36E-05 I -

I 1.32E-05 i 5.68E-05 B. Tritium lH-3 i Cl l 9.64E-01 I 5.42E-01 i 3.15E-01 1 3.40E-01 1 2.16E+00 l )

l C. Dissolved & Entrained Gases l Ci 1 -

I -

I -

1 -

I -

j Total Activity l Ci 1 -

I - I -

I -

I -

D. Gross Alpha l Gross Alpha i Cl 1 -

I -

1 -

I -

I -

l l

- = Less than minimum detectable activity j r

k :V aderymtfluent'affirpt\1119 ht ables',4ctsysty\CYLIQSUM.ute

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.

l SolidificationAgent(s):

I No solidificationon site for 1997 Containers routinely used for radioactive waste shipment include:

l No offsite radioactive waste shipments for 1997 (offsite processing only) l l

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Table 2-8 i Haddam Neck l 1997 Solid Waste and Irradiated Fuel Shipments A. Solid waste shipped offsite for burial or disposal (not irradiated fuel) 12-Month Est Total l 1. Type of Waste Units Period Total Error %

a. Spent Resins, Filter Studges, m3 - 1.00E+01 Evaporator Bottom, etc. Ci -

I b Dry Compressible Waste, m3 - 1.00E+01 Contaminated Equipment, etc. Ci -

c. Irradiated Components m3 -

1.00E+01 Cl -

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

Type of Waste Nuclide a. b. c.

Am-241 - - -

C-14 - - -

Cm-242 - - -

Cm-243 - - -

Cm-244 - - -

Co-58 - - -

Co-60 - - -

Cs-134 - - -

Cs-137 - - -

Fe-55 - - -

H3 - - -

I-129 - - -

Mn-54 - - -

NL63 - - -

Np-237 - - -

Pu-238 - - -

Pu-239 - - -

Pu-240 - - -

Pu-241 - - -

Pu-242 - - -

Sr90 - - -

Tc-99 - - -

3. Solid waste disposition No. Shipments Mode of Transportation Destination None N/A N/A B. Irradiated fuel shipments (Disposition) None C. Offsite Processing Vendor No. Shipments Volume (m3) Activity (Ci)

SEG Incorporated 3 1.24E+02 1.86E+00 FW Hake 1 9.34E-01 8.63E-02

3.0 REMODCM Changes in 1997., there were five (5) changes to the REMODCM:

Section I (REMM) Change 971 February 1997 Change 97-6 May 1997 Section il (ODCM) Change 97-2 February 1997 Change 97-9 May 1997 Change 97-5 June 1997 These REMODCM changes have been reviewed by PORC and approved by the Unit Director. The changed pages for each REMODCM change are included in this report. In addition, a complete

updated copy of the REMODCM, as of 12/31/97, is provided to the Nuclear Regulatory Commission along with this report.

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RADIOLOGICAL ENVIRONMENTAL REVIEW

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for REMM Change 97-1 CY Radiological Effluent Monitoring Manual (Section I, REMODCM) l The proposed change to the CY REMM, section E, RadiologicalEnvironmental Monitoring, reflects changes in the monitoring program that are more in-line with the permanent shutdown J condition of Haddam Neck Station. Due to the shutdown and period of time since power I operation, anayses to measure 1 131 are no longer necessary. I-131 has an 8 day half life and therefore no longer exists in tha station. l The requirements to sample for and measure 1-131 in environmental media are being removed.

These include the collection of weekly canisters at seven locations to measure airborne iodine, the measurement ofI-131 in six monthly milk samples and the analysis of pasture grass for I- j 131. 1 I

Another change being proposed is to the performance of a Land Use Census as required in section E, Radiological EnvironmentalMonitoring. The Land Use Census identifies the location of milking animals within five miles of the station for the purposes ofidentifying critical sampling locations. The requirement to verify the validity of the census at least 'once per 12 months' is being changed to 'once per calendar year'. The performance of this census relies on information obtained from the State of Connecticut's Department of Agriculture. The State k updates their records once a year but its performance varies within a given year. The requirement change to perform the census once per calendar year allows the flexibility to obtain the State's information when it becomes available each year. The remaining changes to this section reflect only editorial and typo corrections.

The proposed changes do not constitute an unreviewed radiological environmental impact. A determination has been made that the change will maintain the level of radioactive effluent control required by 10CFR20.106,40CFR190,10CFR50.36a, and Appendix 1 to 10CFR50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

1 Prepared by: /// '

3/747

. J Eakin, Sr. Eng. I adiological Engineering Reviewed by: d.[hA[ Mr f7 R. A. Crandall, Sup(rvisor Radiological Engineering

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sumu RADIOLOGICAL EFFLUENT l MONITORING MANUAL FOR THE HADDAM NECK PLANT DOCKET NO. 50-213 l

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February 1997 Revision 9 D482XW.091 l

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2/28/97 Revision 9 HADDAM NECK PLANT G

RADIOLOGICAL EFFLUENT MONITORING MANUAL TABLE OF CONTENTS SECTION PAGE NO. REV.NO. DATE A. INTRODUCTION A-1 3 12/31/94 B. RESPONSIBILITIES B-1 3 12/31/94 C. LIQUID EFFLUENTS C.1 LIQUID EFFLUENTS SAMPLING AND ANALYSIS PROGRAM C-1 4 2/1/93 C-2 4 2/1/93 C-3 4 2/1/93 C-4 4 2/1/93 C.2 LQUID RADIOACTIVE WASTE (REATMENT C-5 4 2/1/93 1 D. GASEOUS EFFLUENTS D.1 GASEOUS EFFLUENTS SAMPLING AND ANALYSIS PROGRAM D-1 4 12/31/94 D-2 4 12/31/94 D-3 4 12/31/94 D.2 GASEOUS RADIOACTIVE WASTE TREATMENT D4 3 2/1/92 E. RADIOLOGICAL ENVIRONMENTAL MONITORING E.1 SAMPLING AND ANALYSIS E-1 5 2/28/97 l j E2 4 8/31/94 <

E-3 6 2/28/97 l l E-4 4 8/31/94 '

E-5 4 8/31/94 E-6 4 8/31/94 ,

E.2 LAND USE CENSUS E-7 5 2/28/97 l E.3 INTERLABORATORY COMPARISON l PROGRAM E-8 4 8/31/94 j F. REPORT CONTENT F.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL  ;

OPERATING REPORT F-1 3 10/15/95 i F.2 ANNUAL RADIOACTIVE EFFLUENT l REPORT F-2 3 8/31/94 oauww i

I 2/28/97 Revision 5 E. RADIOLOGICAL ENVIRONMETAL MONITORING E.1 Samolina and Analysis l

The radiological sampling and analyses provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionucfides which lead to the highest potential radiation exposures of individuals resulting ,

from plant operation. This monitoring program thereby supplements the I radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the i environmental exposure pathways. Program changes may be made based on l operational experience.

The sampling and analyses shall be conducted as specified in Table E-1 for the I locations shown in Appendix G of the ODCM. Deviations are permitted from the f required sampling schedule if specimens are unobtainable due to hazardous  !

conditions, seasonal unavailability, malfunction of automatic sampling equipment or other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period.

All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Section F.1. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable altemative media and locations may be chosen for the particular pathways in questions and appropriate substitutions made within 30 days in the radiological environmental monitoring program. In these instances, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next Annua / Radioactive Effluent Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).

If milk samples are unavailable from any one or more of the milk sample locations required by Table E 1, a grass sample shall be substituted and analyzed for gamma isotopes until a suitable milk location is evaluated as a replacement or l until milk is available from the original location. Such an occurrence will be documented in the Annual Radiological Environmental Operating Report. ,

If the level of radioactivity in an environmental sampling medium at one or more of the locations specified in Table E 1 exceeds the report levels of Table E-2 when averaged over any calendar quarter, prepare and submit to the Commission l within 30 days from the end of the affected calendar quarter, a Special Report i which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table E-2 to be exceeded. When more than one of the radionuclides in Table E 2 are detected in the sampling medium, this report shall be submitted if:

E-1 D482XW.001

2/28/97 Rsvisi::n 6 IABLEE-1

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HADDAM NECK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Sampling and Type and Frequency of and/or Sample Locations Collection Frequency Analysis ia. Gamma Dose - 14 Monthly Gamma Dose - Monthly Environmental TLD i b. Gamma Dose - 27 Quarteriy(*) N/A(')

Accident TLD

2. Airbome 7 Continuous sampler- Gross Beta - Weekly Particulate weekly filter change Gamma Spectrum - Quarterly on composite (by location),

and on individual sample if gross beta is greater than 10 times the mean of the weekly control station's gross beta results

3. Vegetation 4 One sample near middle Gamma Isotopic on each and one near end of- sample

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i growing season

4. Milk 6 Monthly Gamma Isotopic on each l sample - Monthly  !

' l Sr 89 and Sr 90 - Quarteriy j 4a. Pasture Grass 6 Sample as necessary to Gamma Isotopic l substitute for unavailable milk

5. Well Water 2 Quarterly Gamma Isotopic, and Tritium on each composite

6. Bottom Sediment 3 Semiannual Gamma Isotopic

7. River Water 2 Quarterly Sample - Quarterly- Gamma Isotopic l Indicator is continuous and Tritium Composite; Background is Composite of Six Weekly Gram Samples

8. Fish - bullheads 3 Quarterly Gamma Isotopic- Quarterly and,when available, Perch or l other edible fish

9. Shellfish 2 Quarterly Gamma Isotopic- Quarterly (a) Accident monitoring TLDs to be dedosed at least quarterly.

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2/28/97 Rovision 5 E.2 Land Use Census t.

The land use census ensures that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census. This census satisfies the requir6cnents of Section IV.B.3 of Appendix I to 10CFR Part 50. The land use census shall be '

maintained and shallidentify the location of the milk animals in each of the 16 meteorological sectors within a distance of five miles.*

The validity of the land use census shall be verified at least once per calendar l

year by either a door to-door survey, aerial survey, consulting local agriculture authorities, or any combination of these methods.*

4 With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the doses currently being calculated in the off-site dose models, make the appropriate changes in the sample locations used.

With a land use census identifying a location (s) which has a higher D/Q than a current indicator location the following shall apply:

(1) If the D/Q is at least 20% greater than the previously highest D/Q, replace one of the present sample locations with the new one within 30 days if milk is available.

(2) If the D/Q is not 20% greater than the previously highest D/Q, consider direction, distance, availability of milk, and D/Q in deciding whether to l replace one of the existing sample locations. If applicable, rephcoment should be within 30 days. If no replacement is made, sufficient justification should be given in the annual report.

Sample location changes shall be noted in the AnnualRadiologicalEnvironmental Operating Report.

• Broad leaf vegetation (a composite of at least 3 different kinds of vegetation) may be sampled at the site boundary in each of 2 different direction sectors with high D/O in lieu of a garden census.

E-7 D442XW.001

__ RADIOLOGICAL ENVIRONMENTAL REVIEW for REMM Change 97-6 CY Radiological Effluent Monitoring Manual (Section I, REMODCM)

The proposed changes to the CY REMM, section E, Radiological EnvironmentalMonitoring, reflect changes in the monitoring program specifications that are necessary to eliminate confusion and misinterpretation. There is no change in program performance.

Section E.1," Sampling and Analysis", is being reworded to explicitly define the requirements for sampling milk and the actions which should be taken when milk is either temporarlity or permanently unavailable. This change is in response to a recent QAS audit recommendation. A redundent specification in Section E.1 that appears in Section F for report content in the Annual Radioactive Effluent Report is being deleted.

Section E.3,"Interlaboratory Comparison Program", is also being changed by deleting the statement that the Interlaboratory Comparison Program be approved by the NRC. As stated in a recent NRC inspection, the Commission does not approve programs. It was the NRC inspector's recommendation that those words be removed from the REMM to eliminate misconceptions and confusion.

The proposed changes do not constitute an unreviewed radiological environmental impact. A determination has been made that the change will maintain the level of radioactive effluent control required by 10CFR20.106,40CFR190,10CFR50.36a, and Appendix 1 to 10CFR50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

Prepared by: Y '

I!N!f7 CJ Eakin, Sr. Eng.

diological Engineering Reviewed by- --J e Mb/@

y ' R. A.Crandall, Supervisor Radiological Engineering I

EEEdlQlil RADIOLOGICAL EFFLUENT Of9El.IQ8lU9.hf$hGl&L FOR THE HADDAM NECK PLANT DOCKET NO. 50-213 May 1997 Revision 10 D482XW 001. DOC

5/30/97 Rsvision 10

_ , , HADDAM NECK PLANT RADIOLOGICAL EFFLUENT MONITORING MANUAL TABLE OF CONTENTS SECTION PAGE NO. REV. NO. A QATE j A. INTRODUCTION A-1 3 12/31/94 B. RESPONSIBILITIES B-1 3 12/31/94 C. LIQUID EFFLUENTS C.1 LIQUID EFFLUENTS SAMPLING AND ANALYSIS PROGRAM C-1 4 2/1/93 C-2 4 2/1/93 C-3 4 2/1/93 C-4 4 2/1/93 C.2 LIQUID RADIOACTIVE WASTE I TREATMENT C-5 4 2/1/93 1 D. GASEOUS EFFLUENTS I i

D.1 GASEOUS EFFLUENTS SAMPLING l AND ANALYSIS PROGRAM D-1 4 12/31/94 D-2 4 12/31/94 D-3 4 12/31/94 D.2 GASEOUS RADIOACTIVE WASTE TREATMENT D-4 3 2/1/92 E. RADIOLOGICAL ENVIRONMENTAL MONITORING E.1 SAMPLING AND ANALYSIS E-1 6 5/30/97 E-2 5 5/30/97 E-3 6 2/28/97 E-4 4 8/31/94 E-5 4 8/31/94 E-6 4 8/31/94 E.2 LAND USE CENSUS E-7 5 2/28/97 E.3 INTERLABORATORY COMPARISON

PROGRAM E-8 5 5/30/97 F. REPORT CONTENT F.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT F-1 3 10/15/95 F.2 ANNUAL RADIOACTIVE EFFLUENT REPORT F-2 3 8/31/94 Dd82XW.001

S/30/97 RGvision G E. RADIOLOGICAL ENVIRONMENTAL MONITORING E.1 Samolina and Analysis The radiological sampling and analyses provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from plant operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Program changes may be made based on operational experience.

The sampling and analyses shall be conducted as specified in Table E-1 for the ,

locations shown in Appendix G of the ODCM. Deviations are permitted from the I required sampling schedule if specimens are unobtainable due to hazardous l conditions, seasonal unavailability, malfunction of automatic sampling equipment or other legitimate reasons. If specimens are unobtainable due to sampling .

equipment malfunction, every effort shall be made to complete corrective action I prior to the end of the next sampling period. j l

All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Section F.1. It is recognized that, at times, it may not be poscible or practicable to continue to i

obtain samples of the media of choice (excluding milk) at the most desired location I l

or time. In these instances suitable altemative media and locations may be i chosen for the particular pathways in questions and appropriate substitutions  ;

made within 30 days in the radiological environmental monitoring program.

If milk samples are temporarily unavailable from any one or more of the milk sample locations required by Table E-1, a grass sample shall be substituted during the growing season (Apr. - Dec.) and analyzed for gamma isotopes until milk is again available. Upon notification that milk samples will be unavailable for a prolonged period (>9 months) from any one or more of the milk sample locations ,

required by Table E-1., a suitable replacement milk location shall be evaluated and  :

I appropriate changes made in the radiological environmental monitoring program.

Reasonable attempts shall be made to sample the replacement milk location prior to the end of the next sampling period. Any of the above occurrences shall be documented in the Annual Radiological Environmental Operating Report which is submitted to the U.S. Nuclear Regulatory Commission prior to May 1 of each year.

Changes to sampling locations shall be identified in a revised table and figure (s) in Appendix G of the ODCM.

If the level of radioactivity in an environmental sampling medium at one or more of the locations specified in Table E-1 exceeds the report levels of Table E-2 when i

omxw-i ooc E-1

5/30.'97 Revision 5

'~~ averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table E 2 to be exceeded. When more than one of the radionuclides in Table E-2 are detected in the sampling medium, this report shall be submitted if; concentration (l) concentration (2) + ;t ,9 reporting level (1) reporting level (2)

When radionuclides other than those in Table E-2 are detected and are ti e result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the appropriate calendar year limit of the Technical Specification. This report is not required if the measured level of condition shall be reported and described in the Annual

, Radiological Environmental Operating Report.

The detection capabilities required by Table E-3 are state-of-the-art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an ,a priori (before the fact) limit representing the capability of a measurement system and not as an a costerior (after the fact) limit for a particular measurement. All analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.

Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will t>e identified and described in the Annual Radiological Environmental Operating Report I

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5/30/97 Ravision 5 E.3 Interfaboratorv Comoarison Program i-The interlaboratory Cornparison Program is provided te ensure that independent checks on the precision and accuracy of the measurements o' .rt.dioactive material in environmental sample matrices are performed as part o. a quality assurance program for environmental monitoring in order to demonstrate tl'at the results are reasonably valid.

Analyses shall be performed on radioactive materials supplied as part of an interlaboratory Comparison Program. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

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_ RADIOLOGICAL ENVIRONMENTAL REVIEW l for ODCM Change 97-2 l CY Offsite Dose Calculation Manual (Section II, REMODCM)

The proposed change to the CY ODCM Appendix G, EnvironmentalMonitoring Program Sampling Locations, reflects changes in the monitoring program that are more in-line with the ('

permanent shutdown condition of Haddam Neck Station. Due to the shutdown and period of time since power operation, analyses to measure I-131 are no longer necessary.1-131 has an 8 day half life and therefore no longer exists in the station.

l The requirements to sample for I 131 in environmental media are being removed. These inc'ude l the collection of weekly canisters at seven locations (i.e., locations 4,5,6,7,8,9 and 13) to I measure airborne iodine.

A goat milk farn used as a control location in the Haddam Neck Radiological Environmental Monitoring Program, location 23C, went out of business. A replacement farm was chosen that satisfies sampling criteria as specified in the REMM. This new farm is located 12 miles south of Haddam Neck.

The proposed changes do not constitute an unreviewed radiological environmental impact. A determination has been made that the change will maintain the level of radioactive effluent control required by 10CFR20.106,40CFR190,10CFR50.36a, and Appendix 1 to 10CFR50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

l Prepared by: d  ; I///97 l [(/J Eakin, Sr. Eng.

Radiological Engineering i Reviewed by: 6 [2/ 97 l

R. A. Crandall, Supervisor Radiological Engineering l

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