Text

Annual Radioactive Effluent Report for 2003
	ML041240436
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	04/29/2004
From:	Bouchard G; Connecticut Yankee Atomic Power Co
To:	; Document Control Desk, NRC/FSME
References
	-RFPFR, CY-04-072
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD

EAST HAMPTON, CT 06424-3099 APR 29 204 Docket No. 50-213 CY-04-072 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Haddam Neck Plant Annual Radioactive Effluent Report In accordance with the requirements of 10CFR50.36a and Technical Specifications, Section 6.7.3, a copy of the Annual Radioactive Effluent Report is included as . It covers the period of January through December 2003. This report includes a summary of the quantities of solid radioactive waste and liquid and gaseous effluents, as well as a summary of the assessment of maximum individual and population dose resulting from routine radioactive airborne and liquid effluents.

Additionally, this report is submitted to the Connecticut Department of Environmental Protection in accordance with Section 4(D) of the NPDES Permit (Permit ID:

CT00003123).

Revision 16 of the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM) and a list of the associated changes are included as Attachment 2.

If you have any questions regarding this submittal, please call Mr. Gerry van Noordennen, Manager of Regulatory Affairs at (860) 267-3938.

Sincerely, Director of Nuclear Safety/Regulatory Affairs Attachments: (1) Annual Radioactive Effluent Report (2) Revision 16 to Radiological Effluent Monitoring and Offsite Dose Calculation Manual, and List of Changes cc: H. J. Miller, NRC Region I Administrator T. B. Smith, NRC Project Manager R. R. Bellamy, Chief, Decommissioning and Laboratory Branch, NRC Region I Dr. E. L. Wilds, Jr., Director, CT DEP Monitoring and Radiation Division M. Rosenstein, US EPA, Region 1 4

Docket No. 50-213 CY-04-072 Attachment 1 Haddam Neck Plant Annual Radioactive Effluent Report

ANNUAL RADIOACTIVE EFFLUENT REPORT HADDAM NECK STATION RADIOLOGICAL EFFLUENT CONTROLS PROGRAM JANUARY 1, 2003 - DECEMBER 31, 2003 DOCKET NO. 50-213 LICENSE NO. DPR-61 CONNECTICUT YANKEE ATOMIC POWER COMPANY Haddam, Connecticut

TABLE OF CONTENTS 1.0 Introduction 2.0 Summary 3.0 Supplemental Information 3.1 Overview of the Radioactive Effluent Controls Program 3.2 Maximum Permissible Concentration 3.2.1 Gaseous Effluents 3.2.2 Liquid Effluents 3.3 Measurements and Approximation of Total Activity 3.3.1 Gaseous Radioactive Effluents 3.3.2 Liquid Radioactive Effluents 3.4 Batch Releases 3.4.1 Airborne Effluents 3.4.2 Liquid Effluents 3.5 Abnormal Releases 4.0 Dose Calculation Methodology 4.1 Airborne Effluents 4.2 Liquid Effluents 5.0 Evaluation of Results 5.1 Total Offsite Dose 5.2 Gaseous Effluents 5.3 Liquid Effluents 5.4 Solid Wastes 6.0 Related Information 6.1 Radiation Monitors Out of Service for Greater than Thirty Days 6.2 Radioactive Effluent Condition Reports 6.2.1 Monthly Dose Report Summation Error 7.0 Health Physics Technical Support Document 8.0 REMODCM Revisions in the Year 2003 2 of 38

LIST OF TABLES Table 1 2003 Off-Site Dose Commitments from Airborne Effluents Table 2 2003 Off-Site Dose Commitments from Liquid Effluents Table 3 2003 Off-Site Dose Summary Table 4 2003 Off-Site Dose Comparison Table 5 Airborne Effluents - Total Release Summary Table 6 Airborne Effluents - Mixed Mode Continuous (Main Stack)

Table 7 Airborne Effluents - Ground Continuous (Spent Fuel Building Exhaust)

Table 8 Airborne Effluents - Ground Continuous (Spent Fuel Spray Cooling)

Table 9 Airborne Effluents - Ground Continuous (Miscellaneous potential release points)

Table 10 Liquid Effluents - Total Release Summary Table 11 Liquid Effluents - Batch (Test and Temporary Tanks)

Table 12 Liquid Effluents - Continuous (RCA Yard Drains)

Table 13 Monthly Liquid Release Volumes for the Test and Temporary Tanks during 2003 Table 14 2003 Solid Waste and Irradiated Fuel Shipments LIST OF FIGURES Figure I Liquid Dose 2003 Figure 2 Test or Temporary Tank Activity Released 2003 Figure 3 RCA Yard Drain Co-60, Sr-90 and Cs-137 Activity Released 2003 Figure 4 RCA Yard Drain Tritium Activity Released 2003 Figure 5 Gaseous Effluent Dose 2003 Figure 6 Miscellaneous Gaseous Pathway Activity 2003 Figure 7 Spent Fuel Building Gaseous Tritium Released 2003 Figure 8 Spray Cooling Release Rates During 2003 System Operation (uCi/hr.)

Figure 9 Total Dose 2003 for 10 CFR Part 190 3 of 38

1.0 Introduction As required by the Haddam Neck Plant Technical Specification Safety Manual (TSSM),

Section 6.7.3, this Annual Radioactive Effluent Release Report for the year 2003 is submitted in accordance with 10 CFR 50.36a, "Technical Specifications on effluents from nuclear power reactors." A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the Haddam Neck Facility is presented in this document. The material provided is consistent with the objectives outlined in the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM).

The information submitted is formatted to the general outline described in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants."

Haddam Neck is currently in the process of decommissioning. In support of the decommissioning effort, radioactive liquid was processed and batch released from the Test and Temporary Tanks in 2003. The radwaste system utilized filters and demineralizers to process radioactive liquid prior to release to the environment. The RCA Yard Drain System is categorized as a continuous release liquid pathway. The major contributors to this release point during 2003 were the External Containment Sump and rainwater collecting in the system catch basins. The collected liquid will cascade flow as a release to the environment.

As the decommissioning project creates new potential gaseous release pathways, baseline data will be collected and, if necessary, the release point will be added to the monitoring program. The Alternate Containment Access, Cable Vault, Containment Foyer, Tank Farm Tent and Terry Turbine are examples of miscellaneous pathways that are routinely monitored.

2.0 Summary The radioactive effluent monitoring program for 2003 was conducted in accordance with Haddam Neck TSSM section 6.6.4. The results of the monitoring program indicate that the Haddam Neck Plant was successful in maintaining radioactive effluent releases to the environment as low as reasonably achievable.

A general overview of the radioactive gaseous releases to the environment during 2003 is summarized below:

The total whole body dose due to gaseous radioactivity released was 6.57E-03 mrem. This is approximately 0.13% of the allowable limit.

The maximum organ dose due to gaseous radioactivity was 7.76E-02 mrem.

This is approximately 0.52% of the allowable limit.

The calculated beta air dose due to noble gases was 0 mrad.

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The calculated gamma air dose due to noble gases was 0 mrad.

The total gaseous tritium released was 1.77 curies.

The total gaseous particulate activity released was 7.56E-05 curies.

The total gaseous gross alpha activity released was 0 curies.

The total gaseous Sr-90 activity released was 0 curies.

A general overview of the radioactive liquid releases to the environment during 2003 is summarized below:

The total whole body dose due to liquid radioactivity released was 0.308 mrem.

This is approximately 10.27% of the allowable limit.

The maximum organ dose due to liquid radioactivity released was 0.514 mrem.

This is approximately 5.14% of the allowable limit.

The total volume of radioactive liquid processed and batch released was 498,771 gallons. The estimated total volume of radioactive liquid released from the RCA Yard Drain System was 10,854,466 gallons.

The total amount of radioactivity from liquids released to the environment was 9.78 curies.

Of the total curies released, 9.75 were attributed to tritium and 0.03 curies from all other nuclides.

The effluent dose contributions for this report period are significantly less than regulatory limits and natural background dose contributions.

A review of the radioactive waste program showed 4,779 cubic meters of solid waste containing 23,197 curies of radioactivity was shipped offsite for processing or disposal.

3.0 Supplemental Information 3.1 Overview of the Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the dose to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program shall be contained in the REMODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation, including surveillance tests and set point determinations, in accordance with the methodology described in the REMODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to the pre-1994 5 of 38

concentration values in 10 CFR Part 20, Appendix B (to 20.1 to 20.602), Table II, Column 2;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters described in the REMODCM;

d. Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the facility to unrestricted areas, conforming to 10 CFR Part 50, Appendix I;

e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters described in the REMODCM (performed at least every 92 days);

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2%

of the guidelines for the annual dose or dose commitment, conforming to 10 CFR Part 50, Appendix I;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be as follows;

1. for noble gases: less than or equal to a dose rate of 500 mrem/yr to the total body and less than or equal to a dose of 3000 mrem/yr to the skin; and

2. for tritium and all radionuclides in particulate form with half-lives greater than 8 days: less than or equal to a dose rate of 1500 mrem/yr. to any organ;

h. Limitations on the annual and quarterly air doses from noble gases released in gaseous effluents from the unit to areas beyond the SITE BOUNDARY, conforming to 10 CFR Part 50, Appendix I;

i. Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each facility to areas beyond the SITE BOUNDARY, conforming to 10 CFR Part 50, Appendix I; and 6 of 38

j. Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC at points beyond the SITE BOUNDARY due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR Part 190.

3.2 Maximum Permissible Concentration 3.2.1 Gaseous Effluents The applicable limits for gaseous effluents are expressed in terms of dose rate at the site boundary.

3.2.2 Liquid Effluents The values specified in 10 CFR Part 20, Appendix B, Table 2, Column 2, (pre-1994 edition), were used as the limits for radioactive effluents released to unrestricted areas.

3.3 Measurements and Approximation of Total Activity 3.3.1 Gaseous Radioactive Effluents Gaseous effluent release pathways were sampled and analyzed weekly for tritium and noble gas. Particulate release pathways were continuously sampled using air filters. The particulate filters were analyzed weekly for gamma radioactivity, monthly for gross alpha and gross beta activity. Particulate filters exhibiting a positive gross beta were saved for quarterly Sr-90 analysis. The results for radioactivity from gaseous effluents and the effluent flow rate were used to determine the total amount of activity released.

The following estimates for the uncertainty associated with gaseous sample analysis stem from a composite of variances in effluent flow rates, instrumentation tolerances and low level counting statistics.

Tritium 25%

Fission and Activation Products 25%

Gross Alpha, Sr-90 25%

Noble Gas 25%

3.3.2 Liquid Radioactive Effluents Each batch release was sampled and analyzed for gamma emitting radionuclides prior to release. Composite samples were analyzed monthly for gross alpha and quarterly for Fe-55 and Sr-90. The results of the composite analyses from the previous month or quarter were used to estimate the quantities of these radionuclides in liquid effluents during the current month or quarter. The total radioactivity in liquid effluent releases was determined from the measured concentrations of 7 of 38

each radionuclide present and the total volume of the effluent released during periods of discharge.

If required, the RCA Yard Drain continuous release pathway was sampled with an automatic composite sampler or by obtaining daily grab samples. Composites were analyzed each week for gamma emitting radionuclides and tritium. Analyses were performed to the minimum detection levels for environmental media. Composite samples were analyzed monthly for gross alpha and quarterly for Fe-55 and Sr-90. The results of the composite analyses from the previous month or quarter were used to estimate the quantities of these radionuclides in liquid effluents during the current month or quarter.

The total radioactivity in liquid effluent releases was determined from the measured concentrations of each radionuclide present and the total volume of the effluent released during the period of discharge.

The following estimates for the uncertainty associated with liquid sample analysis stem from a composite of variances in effluent flow rates, instrumentation tolerances and low level counting statistics.

Tritium 25%

Fission and Activation Products 25%

Gross Alpha 25%

Sr-90, Fe-55 25%

3.4 Batch Releases 3.4.1 Airborne Effluents None 3.4.2 Liquid Effluents Number of Batches: 29 Total Time (min.): 6775 Maximum Time (min.): 532 Average Time (min.): 234 Minimum Time (min.): 38 Average dilution flow during releases: Batch = 214 cfs I Continuous = 34.5 cfs 3.5 Abnormal Releases None 8 of 38

4.0 Dose Calculation Methodology 4.1 Airborne Effluents Maximum individual doses and population doses due to the release of noble gases and particulates were calculated using the computer program GASPAR II.

GASPAR II is used by the staff of the NRC to perform environmental dose analyses for releases of radioactive effluents from nuclear power plants into the atmosphere. The program estimates radiation dose to individuals and population groups from inhalation, ingestion (terrestrial foods), and external-exposure (ground and plume) pathways. Additional information related to the GASPAR HI program is in NUREG/CR4653, "GASPAR II -Technical Reference and User Guide".

The values of average relative effluent concentration (X/Q) and average relative deposition (D/Q) used in GASPAR II to determine population doses were generated using a meteorological computer code which implements the assumptions cited in Section C, NRC Regulatory Guide 1.I11. These values were generated in 1999, the last year that real time data was collected. The X/Q and D/Q values used in the GASPAR II program to determine maximum individual doses were obtained from Appendix F of the REMODCM. Separate values were used for the growing season (defined as April-December) and non-growing season (defined as January-March).

Continuous mixed mode releases from the Main Stack (175 ft) include the Reactor Containment, temporary tent enclosing the tank farm and the Primary Auxiliary Building Ventilation. The Spent Fuel Pool Spray Cooling, Spent Fuel Building Exhaust and other miscellaneous monitored release points are considered continuous ground level releases.

GASPAR 11 calculates the maximum individual and population doses 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 ground deposition, inhalation, and ingestion of vegetation, cow's milk, and meat. The doses are calculated for adults, teenagers, children, and infants separately.

To determine compliance with I OCFR50, Appendix I, the maximum whole body dose to an individual only includes the external pathways (i.e. plume and ground exposure) while the maximum organ dose to an individual only includes the internal pathways (inhalation and ingestion). All applicable pathways were included for the population doses.

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

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4.2 Liquid Effluents Maximum individual and population doses from the release of radioactive liquid effluents were calculated using the computer program LADTAP II. LADTAP II is a NRC computer program, which performs environmental dose analyses for releases of radioactive effluents from nuclear power plants into surface waters.

The program estimates radiation dose to individuals, population groups, and biota from ingestion (aquatic foods, water, and terrestrial irrigated foods) and external exposure (shoreline, swimming, and boating) pathways. Additional information relating to the LADTAP II program is in NUREG/CR-4013, "LADTAP II -

Technical Reference and User Guide".

At Haddam Neck, the algae, drinking water, and irrigated food pathways do not exist; and therefore were not 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 2.

5.0 Evaluation of Results 5.1 Total Offsite Dose The dose commitments calculated using the release data for this report period are compared to 10 CFR Part 50, Appendix I, in Table 3, and compared to 40 CFR Part 190 limits in Table 4.

The whole body and maximum organ total doses for each month in this report period are presented in Figure 9. The contributions shown were calculated using Method 1 in the REMODCM for gaseous and liquid contributions. As expected, the total dose increased in the months corresponding to larger volumes of liquid being released.

The effluent dose contributions for this report period are significantly less than regulatory limits and natural backgrounds dose contribution.

5.2 Gaseous Effluents The total activity released from all gaseous effluent pathways is summarized in Table 5. Each pathway's contribution to the total activity released is shown in Tables 6-9. The figures described below were used to identify trends for this report period:

The monthly maximum organ dose compared to the total year to date dose is presented in Figure 5. The calculations were performed using Method 1 in 10 of 38

the REMODCM. The contribution for each month remained consistent throughout this report period.

The activity released for each month from miscellaneous gaseous pathways is presented in Figure 6.

The tritium released for each month from the Spent Fuel Building pathway is presented in Figure 7.

The release rates (uCilhr) for specific nuclides from the Spray Cooling System are shown in Figure 8. The release rates are consistent for this report period.

The monthly doses calculated using Method I in the REMODCM were conservatively higher than the calculations using GASPAR II for this report. The REMODCM includes adjustment factors for Method 1 that if used, would have corrected the monthly dose calculations to be within 23% of the doses calculated for this report (GASPAR II). This indicates the methodology currently used in the monthly calculations includes the necessary conservatism to ensure limitations are not exceeded.

5.3 Liquid Effluents The total activity released from all liquid effluent pathways is summarized in Table 10. Each pathway's contribution to the total activity released is presented in Tables 11 and 12. The volume released from batch discharges for this report period is presented in Table 13. The figures described below were used to identify trends for this report period:

The monthly whole body and maximum organ doses compared against the total year to date is presented in Figure 1. The calculations were performed using Method 1 in the REMODCM. As expected, the doses increase for the periods corresponding to large volumes of liquid waste being discharged.

Specific contributions from individual nuclides released to the environment from batch discharges are presented in Figure 2. As expected, increases in radioactivity released corresponded to larger volumes of water being discharged.

Specific contributions from individual nuclides released to the environment from the RCA Yard Drain System are presented in Figures 3 and 4. The major contributors to this release point were the External Containment Sump and rainfall that collects in the catch basins located in the RCA. A conservative estimate for the effluent volume is used in release calculations for this pathway.

The monthly doses calculated using Method I in the REMODCM were consistent with the calculations using LADTAP II for this report. The summed monthly 11 of38

doses calculated using Method 1 were within approximately 1% of the Whole Body and Maximum Organ calculations using LADTAPII for the year 2003. This indicates the methodology currently used in the monthly calculations includes the necessary conservatism to ensure limitations are not exceeded.

5.4 Solid Wastes The quantities of radioactive material shipped offsite for processing or disposal are summarized in Table 14.

6.0 Related Information 6.1 Radiation Monitors Out of Service for Greater than Thirty Days.

None 6.2 Radioactive Effluent Condition Reports 6.2.1 The summation dose for the January and December 2002 monthly 40 CFR 190 reports were found to be in error. Condition Report 03-0230 was generated to document the finding. The summations were corrected and properly reported in the 2002 Annual Report.

7.0 Health Physics Technical Support Document Health Physics Technical Support Document, HP-CY-0170, "Radioactivity Effluent Analysis for the Year 2003", was generated to document the calculations performed for this report. Site specific, environmental information and other input data that was necessary to complete this report are listed and discussed in the technical support document.

8.0 REMODCM Revisions in the Year 2003 Revision 16 to the REMODCM was issued July 15, 2003. A copy of revision 16 and the information to support the changes has been included with the submission of this annual report.

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Table 1 2003 Off-Site Dose Commitments from Airborne Effluents Haddam Neck CY 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Max Air (mrad) (mrad) (mrad) (mrad)

Beta 0 0 0 0 Gamma 0 0 0 0 Max Individual (mrem) (mrem) (mrem) (mrem)

Whole Body+ 7.45E-05 2.22E-03 4.04E-03 2.34E-04 Skin+ 8.71 E-05 2.60E-03 4.75E-03 2.73E-04 Thyroid 1.18E-02 1.17E-02 1.34E-02 1.16E-02 Max Organ+ 1.25E-02 2.56E-02 2.61E-02 1.33E-02 Population (person-rem) (person-rem) (person-rem) (person-rem)

Whole Body 1.38E-03 2.44E-03 3.79E-03 1.94E-03 Skin 1.37E-03 2.42E-03 3.86E-03 1.93E-03 Thyroid 1.37E-03 2.33E-03 3.69E-03 1.92E-03 Max Organ++ 1.40E-03 2.60E-03 4.11 E-03 1.96E-03 Avg Individual (mrem) (mrem) (mrem) (mrem)

Whole Body 3.61E-07 6.37E-07 9.89E-07 5.05E-07 Skin 3.58E-07 6.31E-07 1.01 E-06 5.05E-07 Thyroid 3.57E-07 6.08E-07 9.63E-07 5.02E-07 Max Organ++ 3.66E-07 6.78E-07 1.07E-06 5.11 E-07

+ External doses only

++Maximum of the followving organs: Bone, GI-LLI, Kidney, Liver, Lung, Thyroid 13 of 38

Table 2 2003 Off-Site Dose Commitments from Liquid Effluents Haddam Neck CY 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Max Individual (mrem) (mrem) (mrem) (mrem)

Whole Body 1.64E-01 1.20E-02 1.32E-01 3.95E-04 Thyroid 1.46E-03 2.62E-04 2.02E-03 1.99E-05 Max Organ 2.54E-01 3.06E-02 2.21E-01 8.71E-03 Population (person-rem) (person-rem) (person-rem) (person-rem)

Whole Body 2.95E+00 2.14E-01 2.36E+00 7.49E-03 Thyroid 6.92E-04 3.98E-04 1.06E-04 2.11 E-05 Max Organ 5.61 E+00 6.55E-01 4.69E+00 1.91 E-01 Avg Individual (mrem) (mrem) (mrem) (mrem)

Whole Body 7.70E-04 5.58E-05 6.16E-04 1.95E-06 Thyroid 1.81E-07 1.04E-07 2.77E-08 5.50E-09 Max Organ 1.46E-03 1.71E-04 1.22E-03 4.98E-05 14 of 38

Table 3 2003 Off-Site Dose Summary Haddam Neck Airborne Effluents Population Dose Commitments (total person-rem within 50 miles) l Whole Body I Thyroid I Max Organ l 9.55E-03 I 9.31E-03 I 1.01E-02 Max Individual Dose/Dose Commitments vs 10CFR50, Appendix I Gamma Beta Air Whole Body Max Organ Skin Air Dose Dose (mrem) (mrem) (mrem) (mrad) (mrad) l .B and l C Litsi Haddam Neck Total 6.57E-03 I 7.76E-02 I 7.71E-03 I 0 I 20 0

Liquid Effluents Population Dose Commitments (total person-rem within 50 miles)

Whole Body Thyroid I Max Organ 5.53 1.22E-03 11.15 Max Individual Dose/Dose Commitments vs 10CFR50, Appendix I Whole Body Max Organ (mrem) (mrem)

IL.A Limtits 3 10 Haddam Neck Total 3.08E-01 5.141_-01 15 of 38

Table 4 2003 Off-Site Dose Comparison Haddam Neck Max Individual Annual Dose vs 40CFR190 Limits Whole Body Any Organ Thyroid (mrem) (mrem) (mrem) 40CFRI90Lintit 25 25 75 Airborne Effluents 6.5713-03 7.76E-02 4.85E-02 Liquid Effluents 3.0813-01 5.14E-01 3.7613-03 Haddam Neck Total 3.1513-01 5.92E-01 5.2313-02 Whole Bodv Dose from Haddam Neck Plant vs. Background Radiation Sources of Background Radiation:

Cosmic 26 Cosmogenic 1 Terrestial (Atlantic and Gulf Coastal Plain) 23 Inhaled 200 In the Body 40 ICT Resident Whole Body Dose from Background l 290 mrem I ICT Resident (within 50 miles) Whole Body Dose from l I Haddam Neck Plant Airborne and Liquid Effluents I 1.45E-03 mrem Maximum Individual (within 50 miles) Whole Body Dose from l l IHaddam Neck Plant Airborne and Liquid Effluents I 3.15E-01 mrem 16 of 38

Table 5 Haddam Neck Airborne Effluents - Total Release Summary 2003 Units 1stQtr I 2ndQtr I 3rd Qtr I 4th Qtr I Total A. Fission & Activation Gases

1. Total Activity Ci -

Released

2. Average uCi/sec -

Release Rate B. Iodines

1. Total Activity Ci -

Released

2. Average uCi/sec -

Release Rate C. Particulates

1. Total Activity Ci 3.07E-06 3.61E-05 3.0313-05 6.19E-06 7.56E-05 Released

2. Average uCi/sec 3.95E-07 4.59E-06 3.811E-06 7.79E-07 2.40E-06 Release Rate D . G ross A lph a _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1. Total Activity Ci -

Released

2. Average uCi/sc Release Rateu/sI E. Tritium

1. Total Activity Ci 4.29E-01 4.2813-01 4.86E-01 4.23E-01 1.77E+00 Released

2. Average luCi/sec 5.52E-02 5.45E-02 6.12E-02 5.32E-02 5.60E-02 Release Rate _ _ _ I I I I 17 of 38

Table 6 Haddam Neck Airborne Effluents - Mixed Mode Continous Main Stack Nuclides l 1 2003 ]

Released I Units I 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total J A. Fission & Activation Gases II lTotalActivityl Ci I ci I I

I l -

I l

I I B. lodines I ~~I ciIIII I Total Activityl Ci I I C. Particulates lCs-137 I Ci [ 2.73E-06 [ - I l 4.02E-07 3.13E-06 ITotal Activity ICi l 2.73E-06 l - I l 4.02E-07 3.13E-06 D. Gross Alpha IGross Al ha Ci - - l E. Tritium LH-3 I Ci I - --

- (For Fission & Act Gas) = Not Required to be analyzed.

- (For Iodine's) = Not Required to be analyzed.

- (For Particulates) = <Lower Limit of Detection as specified in the REMODCM

- (For Gross Alpha) = <Lower Limit of Detection as specified in the REMODCM 18 of 38

Haddam Neck Airborne Effluents - Ground Continuous Spent Fuel Building Exhaust Nuclides 1 2003 Released I Units I Ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Total J A. Fission & Activation Gases lTo talAc tivit yICi Il - - - l l B. lodines 1 i - I - Ii Total Activityl Cil -

C. Particulates Total Activityl Ci Il

- - l -

D. Gross Alpha Gross Alpha Ci l -

E. Tritium lH-3 Ci I 4.29E-01 4.28E-01 4.86E-01 4.23E-01 I 1.77E+00l

- (For Fission & Act Gas) = < Lowcr Limit of Detection as specificd in the REMODCM

- (For Iodine's) = Not Required to be analyzed

- (For Particulates) = <Lower Limit of Detection as specified in thc REMODCM

- (For Gross Alpha) = < Lower Limit of Detection as specified in the REMODCM 19 of 38

Haddam Neck Airborne Effluents - Ground Continuous Spent Fuel Spray Cooling Nuclides 2003 Released Units 1st Qtr l 2nd Qtr 3rd Qtr 4th Qtr Total J A. Fission & Activation Gases I Ci I I - ! --

ITotalActivity Ci _

B. lodines l lTotal Activityl Ci l -l l I C. Particulates Fe-55 Ci 1.65E-05 3.66E-06 2.01E-05 Co-60 Ci 7.22E-08 1.92E-06 1.42E-06 2.98E-07 3.71 E-06 Cs-134 Ci 1.89E-08 6.86E-07 3.12E-07 - 1.02E-06 Cs-137 Ci 2.51 E-07 1.0813-05 1.12E-05 1.4213-06 2.37E-05 Total Activity Ci 3.42E-07 2.99E-05 1.29E-05 5.38E-06 4.85E-05 D. Gross Alpha Gross Al ha I Ci l -

E. Tritium lH-3 I Ci l 3.10E-06 l 1.83E-04 4.1813-04 1.25E-04 7.29E-04

- (For Fission & Act Gas) = Not Required to be analyzed.

- (For lodine's) = Not Required to be analyzed.

- (For Particulates) = < Lower Limit of Detection as specified in the REMODCM

- (For Gross Alpha) = < Lower Limit of Detection as specified in the REMODCM 20 of 38

Haddam Neck Airborne Effluents - Ground Continuous Miscellaneous potential release points (Alternate Access, Containment Foyer, Cable Vault, Terry Turbine, Temporary Tank Farm Tent, etc.)

Nuclides l 2003 Released I Units I 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total J A. Fission & Activation Gases jTotalActivityl Ci lI - l - l -l -

B. lodines Total ActivityICiI C. Particulates Co-60 Ci [ l 4.39E-06 1.66E-05 l 1.97E-07 2.12E-05 Cs-137 Ci [ 1.80E-06 7.84E-07 l 2.07E-07 2.79E-06 Total Activity Ci - 6.19E-06 l 1.74E-05 4.04E-07 2.40E-05 D. Gross Alpha Gross Al ha Ci - l l E. Tritium JH-3 I Ci I l l ]

- (For Fission & Act Gas) = Not Required to be analyzed.

- (For Iodine's) = Not Required to be analyzed.

- (For Particulates) = < Lower Limit of Detection as specified in the REMODCM

- (For tritium) = Not Required to be analyzed.

- (For Gross Alpha) = < Lower Limit of Detection as specified in the REMODCM 21 of 38

Table 10 Haddam Neck Liquid Effluents - Total Release Summary 1 2003 Units 1st Qtr I 2nd Qtr I 3rd Qtr I4th Qtr I Total A. Fission and Activation Products

1. Total Activity Ci 1.35E-02 3.69E-03 L.OIE-02 2.18E-04 2.75E-02 Released

2. Average Period uCi/m] 8.32E-10 3.42E-10 7.05E-10 2.60E-11 5.53E-10 Diluted Activity B. Tritium

1. Total Activity Ci 5.74E+00 3.24E+00 7.33E-01 4.45E-02 9.75E+00 Released

2. AveragePeriod uCi/rn 3.54E-07 3.OOE-07 5.13E-08 5.32E-09 1.96E-07 Diluted Activity I I I I C. Dissolved and Entrained Gases

1. Total Activity Ci - - -

Released

2. Average Diluted uCi/m] - - -

Activity D. Gross Alpha

1. Total Activity Released LCi

2. Average Diluted uCi/ml 6.73E-05 I 2.OOE-06 4.711E-12 l2.39E-13 6.93E-05 69l 1.40E-12 Activity E. Volume

1. Released Waste Liters 5.84E+06 1.12E+07 1.32E+07 1.27E+07 4.30E+07 Volume ________

2. Dilution Volume Liters 1.62E+10 1.08E+10 1.43E+10 8.37E+09 4.97E+10 During Releases l _ ________

3. DilutionVolum Liters 1.62E+10 1.08E+10 1.43E+10 8.37E+09 4.97E+10 During Period l 22 of 38

Table 11 Haddam Neck Liquid Effluents - Batch (Test and Temporary Tanks)

Nuclides I 2003 Released Units 1st Qtr 2nd-Qtr 3rd Qtr 4th Qtr Total l A. Fission & Activation Products Am-241 Ci 1.1 1E-04 1.1 E-04 Co-60 Ci 3.04E-03 1.06E-03 7.90E-03 1.09E-04 1.21 E-02 Cs-134 Ci 2.14E-04 6.59E-06 1.05E-04 3.26E-04 Cs-137 Ci 9.99E-03 7.19E-04 1.78E-04 1.31 E-05 1.09E-02 Eu-154 Ci Fe-55 Ci 1.62E-04 1.84E-03 1.68E-03 4.91 E-05 3.73E-03 Sb-125 Ci 1.52E-05 1.52E-05 Total Activity Ci 1.34E-02 3.63E-03 9.99E-03 1.71E-04 2.72E-02 B. Tritium lH-3 I Ci 5.73E+00 I 3.22E+00 I 7.04E-01 I 1.96E-02 I 9.67E+00 C. Dissolved & Entrained Gases I Cil Total Activity Ci l - - - l D. Gross Alpha lGross Alpha Ci - 6.73E-05l 2.OOE-06 6.93E-05l

- (For Fission & Act Products) = < Lower Limit of Detection as specified in the REMODCM

- (For Dissolved & Entrained Gases) = < Lower Limit of Detection as specified in the REMODCM

- (For Gross Alpha) = < Lower Limit of Detection as specified in the REMODCM 23 of 38

Table 12 Haddam Neck Liquid Effluents - Continuous (RCA Yard Drains)

Nuclides 2003 Released Unitsl Ist Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission & Activation Products Sr-90 Ci 3.60E-05 6.80E-05 8.53E-05 4.65E-05 2.36E-04 Co-60 Ci 2.93E-05 - - 2.93E-05 Cs-137 Ci - 8.61E-06 8.61E-06 Total Activity Ci l 6.53E-05 6.80E-05 I 9.39E-05 4.65E-05 2.74E-04 B. Tritium JH-3 l Ci I 7.86E-03 1.66E-02 2.91E-02 I 2.49E-02l 7.85E-02 C. Dissolved & Entrained Gases II Ci I - I - I - I - I -

iTotal Activity Ci I - I --

D. Gross Alpha Gross Al ha Ci - - l -

- (For Fission & Act Products) = < Lower Limit of Detection as specified in the REMODCM

- (For Dissolved & Entrained Gases) = Not Required to be analyzed

- (For Gross Alpha) = < Lower Limit of Detection as specified in the REMODCM 24 of 38

Table 13 Monthly Liquid Release Volumes for the Test and Temporary Tanks during 2003 Month Volunte Released (gallons)

January 168,900 February 80,000 March 0 April 96,700 May 20,000 June 0 July 0 August 97,624 September 19,547 October 0 November 0 December 16,000 YTD 498,771 25 of 38

Table 14 Haddam Neck 2003 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream

1. Type of Waste

a. Waste Stream: Resins, Filters, and Evap Bottoms Cavity Resin in 24" X 72" ADHUT Demins Waste Volume Curies %Error Class MA3 Shipped (Ci)

A 6.39E+00 3.49E+00 +/-25%

B 0.OOE+00 O.OOE+00 -

C 4.6313+00 2.85E+01 +/-25%

All IO1.1E+01 3.20E+01 +/-25%

b. Waste Stream : Dry Active Waste Dry Active Waste 20' DAW in Intermodal DAW in B-25 Dry Active Waste 40' Waste Volume Curies %Error Class MA3 Shipped (Ci)

A 3.7213+03 1.45E+01 +/-25%

B 0.0013+00 O.OOE+00 -

C 3.57E+00 4.64E-+01 +/-25%

All 3.72E+03 6.09E+01 +/-25%

26 of 38

Table 14 (continued)

c. Waste Stream : Irradiated Components Waste Volume Curies % Error Class MA3 Shipped (Ci)

A O.OOE+00 0.OOE+00 -

B 0.00E+00 0.00E+00 -

C 2.50E+02 2.3 1E+04 -

All 2.50E+02 2.31E+04 -

d. Waste Stream : Other Waste Combined Packages14-170 Insitu 2 Waste Volume Curies % Error Class MA3 Shipped (Ci)

A 7.89E+02 3.56E+00 +/-25%

B 0.00E+00 0.00E+00 -

C 5.29E+00 8.33E-01 +/-25%

All 7.95E+02 4.39E+00 +/-25%

e. Waste Stream : Sum of all 4 Waste Streams Waste Volume Curies % Error Class MA3 Shipped (Ci)

A 4.5 1E+03 2.16E+01 +/-25%

B 0.00E+00 0.00E+00 -

C 2.63E+02 2.3213+04 +/-25%

All 4.78E+03 2.32E+04 +/-25%

27of38

(continued)

2. Estimate of Major Nuclide Composition (by waste stream)

Composition In % for each waste stream Total Nuclide a. b. c. d. e. Curies H-3 0.106% 0.101% 0.000% 0.008% 0.000% 9.60E-02 C-14 0.062% 0.052% 0.016% 0.020% 0.016% 3.80E+00 Cr-5 1 0.000% 1.776% 0.000% 0.000% 0.005% 1.08E+00 Mn-54 0.000% 0.194% 0.085% 0.287% 0.085% 1.98E+01 Fe-55 66.532% 63.730% 34.994% 37.962% 35.114% 8.16E+03 Co-57 0.000% 0.000% 0.000% 0.000% 0.000% 4.40E-03 Co-58 0.000% 0.043% 0.000% 0.000% 0.000% 2.60E-02 Co-60 21.277% 23.404% 52.784% 40.081% 52.661% 1.22E+04 Ni-59 0.073% 0.072% 0.092% 0.047% 0.092% 2.13E+01 Ni-63 10.808% 8.880% 12.009% 7.481% 11.998% 2.79E+03 Sr-89 0.000% 0.000% 0.000% 0.000% 0.000% 1.166E-07 Sr-90 0.017% 0.017% 0.000% 0.024% 0.000% 3.69E-02 Nb-94 0.000% 0.000% 0.000% 0.000% 0.000% 5.90E-02 Tc-99 0.011% 0.008% 0.000% 0.309% 0.000% 4.14E-02 1-129 0.001% 0.001% 0.000% 0.001% 0.000% 7.24E-04 Cs-134 0.007% 0.087% 0.000% 0.003% 0.000% 5.54E-02 Cs-137 0.466% 1.029% 0.000% 0.021% 0.003% 7.77E-01 Cc-144 0.181% 0.244% 0.000% 0.032% 0.001% 2.08E-01 Eu-154 0.004% 0.006% 0.000% 0.171% 0.000% 1.24E-01 Eu-155 0.000% 0.000% 0.000% 0.022% 0.000% 9.50E-04 Np-237 0.000% 0.000% 0.000% 0.000% 0.000% 6.06E-04 Pu-238 0.019% 0.015% 0.001% 0.674% 0.001% 2.92E-01 Pu-239 0.004% 0.003% 0.000% 0.124% 0.000% 8.97E-02 Pu-240 0.004% 0.002% 0.000% 0.124% 0.000% 7.71 E-03 Pu-241 0.377% 0.296% 0.017% 11.897% 0.020% 4.70E+00 Am-241 0.034% 0.026% 0.001% 0.566% 0.001% 2.98E-01 Cm-242 0.000% 0.000% 0.000% 0.000% 0.000% 4.85E-05 Cm-243 0.009% 0.009% 0.000% 0.074% 0.000% 9.48E-02 Cm-244 0.009% 0.007% 0.000% 0.074% 0.000% 1.01 E-02 28 of 38

Table 14 (continued)

3. Solid Waste Disposition Mode of Transportation No. Shipments! Destination Bigge Crane and Rigging 1 'Barnwell Waste Management Facility Hittman Transport 1 10 IBarnwell Waste Management Facility Hittman Transport I 'Envirocare of Utah, Inc.

Landstar System, Inc. l 28 IEnvirocare of Utah, Inc.

Priority Transport Service, 6 1Envirocare of Utah, Inc.

Hittman Transport , 56 'TS Duratek, Inc. (BCO)

Hittman Transport 684 GTS Duratek, Inc. (GR)

B. Irradiated Fuel Shipments (disposition)

NONE 29 of 38

Figure 1 Liquid Dose 2003 Haddam Neck 2.50E-0 I - -

2.00E 0 Lo 1.50E . to 0

2 I-I E0

~ I .OOE-0 I- --. 2 E

5.00E-02 s O.OOE+00 -

Jan-03 Feb-03 Mar-03 Apr-03 May-03 Jun-03 Jul-03 Aug-03 Sep-03 Oct-03 Nov-03 Dec-03 Month

-- WB Dose -- Max. Organ Dose A WB YTD -*Max. Organ YTD 30 of 38 CG(Io

Figure 2 Test or Temporary Tank Activity Released 2003 Haddam Neck vi-2 U

Jan-03 Feb-03 Mar-03 Apr-03 May-03 Jun-03 Jul-03 Aug-03 Sep-03 Oct-03 Nov-03 Dec-03 Month

_Am-241 -- Gross Alpha X Co-60 *-Cs-134 -4Cs-137 I Eu-154 -4H-3 -Fe-55 -Sb-125 31 of 38 (Tx)2.

Figure 3 RCA Yard Drain Co-60, Sr-90 and Cs-137Activity Released 2003 Haddam Neck 3.50E 2.50E-05 3.00E - --- - -

2.OOE-05

-1.0E-05X C2.50E-05 \- 1 -- -------- ------------ ---- ---- --- ----- - --- ---e 1.50E-05

~. 2.OOE-06 LO00E-05 --------------- ---------------- ~~ ~ ~~~~~

t-------- ------------------- -

Jan-03 Feb-03 Mar-03 Apr-03 May-03 Jun-03 Jul-03 Aug-03 Sep-03 Oct-03 Nov-03 Dec-03 Month

-- MSr-90 -ECo-60 -*Cs-137l 32 of 38 C.03

Figure 4 RCA Yard Drain Tritium Activity Released 2003 Haddam Neck 1.20E-02 4 . OE 0 3 - -- -- -- - -- -- - -- -- -- - -- -- - -- -- -- - . .. . .. .. .. . .. .. . .. .. .. . .. .. . .. .. .. . .. .. . .. .. .. . .. .. . .. .. .. . .. .. . .. .. .. . .. .. . .. .. .. . .. .. .

2.002-03-..

O.OOE+00 Jan-03 Feb-03 Mar-03 Apr-03 May-03 Jun-03 Jul-03 Aug-03 Sep-03 Oct-03 Nov-03 Dec-03 Month

-U-Tritiuml 33 of 38

Figure 5 Gaseous Effluent Dose 2003 Haddam Neck 1.40E-01 1.20E-01 I .OOE41 8.OOE-02 6.OOE-02 4.OOE-02 2.OOE-02 O.OOE+OO I I I Jan-03 Feb-03 Mar-03 Apr-03 May-03 Jun-03 Jul-03 Aug-03 Sep-03 Oct-03 Nov-03 Dec-03 Month

+- Max Organ YTD 34 of 38

Figure 6 Miscellaneous Gaseous Pathway Activity 2003 (Cable Vault, Containment Alternate Access, Containment Foyer, Terry Turbine, etc)

I.80E+01 1.40E+00 1.20E+00 1.OOE+00 F-40 V. 8.OOE-01 0

La 0 Cu I.

U, 6.OOE-01 -2 4.OOE-01 2.OOE-01 0.OOE+0 I IV -- 0.00E+00 Jan-03 Feb-03 Mar-03 Apr-03 May-03 Jun-03 Jul03 Aug-03 Sep-03 Oct-03 Nov-03 Dec-03 Month

+--Co-60_Cs-137 35 of 38

Figure 7 Spent Fuel Building Gaseous Tritium Released 2003 Haddam Neck 2.50E+05 2.00E+05 I .50E+05 2

at I.OOE+05 5.OOE+04 0.00E+00 _-

Jan-03 Feb-03 Mar-03 Apr-03 May-03 Jun-03 Jul-03 Aug-03 Sep-03 Oct.03 Nov-03 Dec-03 Month I+T rtium 36 of 38

Figure 8 Spray Cooling Release Rates During 2003 System Operation (uCi/hr)

Haddam Neck I .OOE+00 900 800 I .OOE-01 700

,o 600 e I.OOE-02 500 I-C 400 V

-300 I .OOE-03 200 gI .OOE-03 100 0

00 0 0 0 > 0 0 0

- n zMont Month H-3 -U-Co-60 A Cs-I34 - Cs-137 -4Fe-55 -*-Run Times I 37 of 38

Figure 9 Total Dose 2003 for 40 CFR Part 190 Haddam Neck E

E0 S=

0 9? I9 I I 9 9? 9? I tC NnteU :lU

- %0 I U>

~

- LL. < 2-<W0 Month/Year l -Total Body Dose --*-Max Organ Dose I 38 of 38

. Docket No. 50-213 CY-04-072 Attachment 2 Haddam Neck Plant Revision 16 to Radiological Effluent Monitoring And Offsite Dose Calculation Manual And List of Changes

1- -

JUL 1 5 2003 a

...- t.',

41 RA-DIOLOGICAL: EFFLUENT.

MWONITORING MANUAL ForTho HADDAM NECK PLANT REMM Reviskon IS

I JUL 15 2003 Revision 16 HADDAM NECK PLANT RADIOLOGICAL EFFLUENT MONITORING MANUAL TAL FCOMMNT Section A.INTRODUCTION AND RESPONSIBILITIES

'XI Introduction - A-I A.2 Responsibilities' A-2 B. DEFINITONS B-I C. LIQUID EFFLUENTS C.1 Uquid Effluents. Sampling and C-I Analysis Program 0.2 Liquid Radioactive Waste Treatment 0-5 C.314 Liquid Effluent Controls and Surveillance C-6 Requirements D. GASEOUS EFFLUENTS DA1 Gaseous Effluents Sampling and D-1 Analysis Program D.2 Gaseous Radioactive Waste Treatment D-5 r% 1.2#A - A C .....

- - .. .-. - . r% --

E. RADIOLOGICAL ENVIRONMENTAL MONITORING . . -

E.I Sampling and Analysis..E-I E.2 Land Use Census E-7

---- E.3------Interlaboratory Comparison Program ~-

' L. a. - I .. .

. , : ., , 7 1 1 ": - : .. I .

I ,r

.. , .; !, I REMM REIMM TOC I of 2

JULRevision 15 200316 Section F. REPORT CONTENT F.1 -Annual Ra'diological Environmental F-I Operating Report 1 F.2 hnua Rdoactv Efunt Report F-2 F.3' Special Reports I - -.II F-3 G. TOTAL DOSE G.1 Total Dose from All Sources G41 G.2 Compliance with 40CFR190 Uimits G-2 G.314 Controls and Surveillancr. Requirements G-3 H. FIGURES H.1 Exclusion Area Boundary and Site H-I Boundary for Liquid and Gaseous Effluents H.2 Liquid Waste Treatment System H--2 REMM TOC 2of2

JUL 15 2003 Revision 16 A. INTRODUCTION AND RESPONSIBILITIES A.1 Introduction The purpose of this manual1 Is to provide the sampling and analysis programs that provide Input to tAhe 0ODCM for calculating liquid and gaseous effluent

-concentrations and.. offslte '.doses. `'-,Guidelines' are provided for operating

-RADIOACTIVE WASTE TREATMENT .SYSTEMS In order that offsite doses are kept As-Low-As,-Reasonably Achievable (ALARA).

The Radiological Environmental Monitodring Pro'gram outlined within this manual provides confirmation that the measurable concentrations of radioactive material released as a result of plant and ISFSI operations'at the Haddam Neck Plant are not higher than expected.

In addition, this manual outlines the information required for submittal to the NRC in bath the Annual Radiolc.,1cal Environmental Operating Report and the Annual Radioactive Effluent Report.

A-i REMM

JUL 1 5 2003 Revision 16 A.2 Responsibilities All changes to this manual shall be independently reviewed and approved by fth Unit Manager prior to Implementation.

All -changes and their rationa'le shall be documented'in'the Annual Radioactive, Effluent- ~Report In accordance with the administrative controls of Technical Specification 6.6.3.

It salbthreponsibyo h nt Maa er toesre that this manual Is used In the'lrmplementation of the Radiological Effluent Monitoring, Radioactive Effluent Controls, "and the Radiological Environmental Monitoring Programs. The Unit Manager 'shall ensure that the REMODCM Is maintained and controlled In' accordance with Technical Specification 6.6.3.

. -i A-2 REMM

.1 .

I -

JUL 1 5 2003 Revision 16 B. DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout

-the REMODCM.

g t. . t . . . : ,,. ., . - .df;

'B.1 ACTION: ;-.K t ACTION shall be that part of a Control which prescribes remedial measures requiredK';-' .

under designated conditions. ' --

B.2 CHANNEL OPERATIONAL TEST A CHANNEL OPERATIONAL TEST shall be the Injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock andlor trip functions. The CHANNEL OPERATIONAL TEST shall includd adjustments, as necessary, of the alarm, Interlock and/or Trip Setpoints such that the Setpoints are within the reqgired range and accuracy.

B.3 CHANNEL CALIBRATVON A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions, and may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

B.4 CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

~~~~_ ___*__-_-_-'______-___-'_________ - -- - . '--- -^-,,i','- ,_!.--.-_.

B.5 -FREQUENCY NOTATION

' -'-The--FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in-Table B.1.--- ------ ------------ --------

B.6 ISFSI - INDEPENDENT SPENT FUEL STORAGE INSTALLATION Dry storage facility for spent fuel.

B.7 MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include J',

persons who use 'portions of the site for 'recreational, occupational, or other purposes not associated with the plant.

REMNI

JUL 15 200.

Revision 16 B.8 OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when It Is capable of performing its specified function(s), and when.

all necessary attendant Instrumentation, controls, electrical power, cooling or seal

-water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of U performing their related support function(s)..

B.9 RADIOACTIVE WASTE TREATMENT SYSTEMS RADIOACTIVE WASTE TREATMENT SYSTEMS are those liquid, gaseous and solid waste systems which are required to maintain control over radioactive material -"

in order to meet the Controls set forth Inthe REMODCM.

B.10 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM)

A RADIOLOGICAL EFFLUENJT MONITORING MANUAL (REMM) shall be a manual containing the site and environmental sampling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures to individuals from station operation. An OFFSITE DOSE CALCULATION MANUAL (ODCM) shall be a manual containing the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation Alarm/Trip Setpoints. Requirements of the REMODCM are provided in Technical Specification 6.6.3.

B.11 SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. t B.12 SOURCE CHECK ; -

A SOURCE CHECK shall be the qualitative assessment of channel response when.: : -

: '-thechabne-isensor isexosed 10na source of increaseoradioactvyit;.' - -.....

B.13 _-ALL APPLICABLE LIQUID RADIOACTIVE WASTE TREATMENT SYSTEMS ALL APPLICABLE LIQUID RADIOACTIVE WASTE TREATMENT SYSTEMS is defined as that equipment applicable to any -waste stream responsible for greater than ten percent (10%) of the total projected dose. The liquid radioactive waste treatment system equipment at the Haddam Neck Plant consists of: filters, ion exchangers and various tanks (as required). The liquid radioactive waste treatment system is depicted in Figure H-2 Liquid Radwaste System. - -- -. -

B-2 RENI.

JUL 15 2003 Revision 16 B.14 ALL APPLICABLE GASEOUS RADIOACTIVE WASTE TREATMENTS SYSTEMS ALL APPLICABLE GASEOUS RADIOACTIVE WASTE TREATMENT SYSTEMS is

'defined as that equipment applicable to a waste stream responsible for greater than ,".-..- -

t:en percent 10% -of the 'total projeded dose. The gaseous radioactive waste'-.

treatment equipment 'at the -Haddam Neck Plant consists of ventilation system .

HEPK' ; ', .' '" *f>'l",," - ;.-;. a

~~~~~*.,' ,,.. .

I :. ,.

6-3

.REMM

JUL 15 2003 Revision 16

. FREQUENCYNOTATION*

NOTATION - - FREQUENCY S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W At last once per 7 days.

B At least once per 14 days (bMweekly)

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

P Prior to each release.

NA Not applicable.

.<1._....._......_..._

Each surveillance requirement shall be performed/completed within the specified surveillance Interval with a maximum allowable extension not to exceed 25% of the specified interval

.:, .1..

I

. I :j

,1: ;14:-1

- , -1 REMIM

_M - M JUL 15 20031 Revision 16-C. LIQUID EFFLUENTS C.I .Llquid Effluents Sampling and Analysis Program Radioactiv liquid wastes shall be sampled and analyzed in accordance with the ~

program specified In Table C-I for the Haddam Nedck Plant The results of fth radiloactive6 analyses shall be input to the methodologydo the ODCM to assure thatl the concentrations'at the point of release are maintained within the Controlsofti A REMODCM. ..

c-1 REMM

JUL 1 5 2003 Revision 16 T-aleCA RADIOACTIVE LiQI WSTE SAMPLING AND ANALYSIS PROGRAM "$1 Lower Limit .CTA Minimum -of Detection3 Sampling. 'Analysis Type of Activity (LLD)

Liquid Release Typo Frequency Frequency,, Analysis (iicvcc)

prS-A. Batch Release" Prior to . PrI& o Principal Gamma -5.OOE-07 S Eech Batch Each Batch' Ernittene~

From these sources: Release Release I Monthly Gross Alpha i.OOE-07 Temporary Tanks' Compositeb H-3 1.OOE-05 Quarterly Sr-90 5.OOE-08 CoMpoSiteke Fe-55 1.OOE-06 B. Continuous Release Daily Grab Weekly Principal Gammad 3.OOE-08 Sample Composite'c Emittersd From these sources:, H-3 2.OOE-06 Yard Drain #6 (Catch Basin 11) Monthly Gross Alpha 5.OOE-08 Compositeb.e Quarterly Sr-90 3.OOE-09 Compositeb F;.55 5.OOE-07

. -- . . . --. 1- l C-2 REMM

- -M JURL.

Revisi~onI5l?,003 1ABLERQ (Continued)

TABLE NOTATIONS

a. The lower limit of detection (LLD) is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5%probability of falsely concuding that a blank observation represents a rear signal.

For a particular measurement system (which may Include radiochemical separation):

D 4.66Sb E -V *(2.22E + 06) -.Y -exp(-A&)

where:

LLD Isthe lower limit of detecticr as defined above (microcuries per unit volume)

Sb Is the standard deviation of the background counting rate, or of the counting rate of a blank sample, as appropriate (counts per minute)

E is the counting efficiency (counts per transformation)

V is the sample size (volume) -

2.22E+06 is the number of transformations per minute per microcurie Y is the fractional radiochemical yield (when applicable) x is the radioactive decay constant for the particular radionuclide At is the elapsed time between sample collection (or midpoint of sample collection) and time of counting.

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 posteriori (after the fact) limit for a particular measurement.

b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of s-ampling employed results in a specimen which is representative of the liquid released.

c. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order

- --- for the composite sample to be representative of the effluents released. - -

d. The principal gamma emitters for which the LLD specification will apply are exclusively the following nuclides: Mn-54, Co-60, Zn-65,-Cs-134 and Cs-137. This does not mean that only these nuclides are to be reported. Other nuclides that are identified shall be reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual circumstances result in an a priori LLD

--- ---- being higher than-required,-the-reasons shall be documented in the Annual Radioactive------------- -

Effluent Report.

e. A grab sample will be obtained daily at least five (5) days per week. A composite sampler may be used in lieu of the daily grab sample for Yard Drain #6. Grab samples or.

composite sampler operation at yard Drain 6 (catch basin 11) Is only required when the' Mat Sump is operating.

C-3 REMM

JUL 15 2003 Revision 16

f. Prior to sampling, each batch shall be Isolated; at least two tank volumes shall be recirculated or equivalent mixing provided.

g. Releases can be made from other sources (e.g., temporary tanks) as long as these have ,4 met the programmatic requirements including, but not limited to monitoring through R-22 -

setpolnts and release rate determination action statements. etc.

.. 7 .h,'

REMM

JUL 1 5 200?

Revision 16 C.2 Liquid Radioactive Waste Treatment Monthly doses due toliquid effluents to unrestricted areas shall be projected at least once per 31 days,:onl If one or ALL APPLICABLE LIQUID RADIOACTIVE.,

WASTE TREATMENT ,SYSTEMS will not be lroutinly. oprted. W1henth

-projected monthly dos due to liquid effluents exceeds 0.08 mrem to the total body'

or 0.2 mremn to any' oraALL"APPLICABLE 11LIQUDRADIOACTiVE -WASE TREATMENT SYSTEMS will tb~ orated..

Wihrdoctive liquid waste being discharge wtottreatment and In excess of the above limits, prepare and submit to the Commission, within 30 days, pursuant to Subsection F.3, a special report that Includes the following information:

a. Explanation of why liquid radwaste was being discharged without treatment.

identification of any Inoperable equipment or subsystems. and the reason for the inoperability j

b. Actions taken to rest6re 'the Inoperable equipment to OPERABLE status; and

c. Summary description of actions taken to prevent a recurrence.

Figure H--2, "Liquid Radwaste Systems represents how the liquid radwaste system Is configured.

at the time of this revision. Since the plant Is undergoing decommissioning, tanks will be abandoned and dismantled. Temporary tanks may be used to replace them. This will not require a change to this figure (REMODCM) prior to use of these. This figure will be updated. if required, to reflect the current configuration of the liquid radwaste system, each time the REMODCM is revised.

C-.

REMM

JUL 15 2003 Revision 16 C.3/4 LIQUID EFFLUENT CONTROLS AND SURVEILLANCE REQUIREMENTS CONCENTRATION

'C.3'1 The concentraonof rdiote al ed fm the i (see Figure 1-1) not exceed the concentrations specifled In.10 CFR Part 20, Appendbc B. Table II, '

Column 2 (pre 1994version).

APPLICABILITY: -At all times. -

ACTION:

With the concentration of radioactive material released from the site exceeding the above limits, restore the concentration to within the above limits withIn 15 minutes.

SURVEILLANCE REQUIREMENS C.4.1.1 Radioactive liquid,,wastes shall be sampled and analyzed In accordance with the :

sampling and analysis program specified In Section I of the REMODC. .

C.4.1 2 The results of the'radioactive analysis shall be used In accordance with the methods of Section II of the REMODCM to assure that the concentration of the point of release are maintained within the limits of Control C.3.1.

.,, tA

, . - ,, , ,F

- -- F -- -':

C-6 REMM I1

IIIIIIIII JUL 1 5 2003 Revision 16 RADIOACTIVE EFFLUENTS

- BASIS C.3/4 LIQUID EFFLUENTS -;

C.314.1 CONCENTRATION This Control Is provided to ensure that the concentration of radioactive materials released hI lqud waste effluents frorn the site will be less than the concentration levels specified hI IO CFRPart20. Appendix B, Table II, Column 2 (pre 1994 version). This limitation provides additional assurance that th levels of radioactive materials In bodies of water outside the site win result In exposures within: (1) the Section IIA design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, ard (2) the limits of 10 CFR 20.106(e) to the population. .i: tzl

.~~ ...

a '.

t si ,

C-7 REMM

-JUL 1 5 2003 Revision 16 RADIOACTIVE EFFLUENTS DOSE. LIQUIDS--

COQNTROLS C.3.2. Te 'dose or dose commitment to any MEMBER OF THE PUBLIC from radiocie materials In liquid effluents; released from the site (see Figure H4-I) shal be Urrited:

a. During any calendar quarter to less than or equal to 1.5 mremn to the total body and to less than or equal to 5 mremn to any organ, and r

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrern to any organ.

APPLICABILiTY: At all times. 1 ACTION:

a. With the calculated dose fronm the release of radioactive materials in liquid efflents exceeding any of the above limits, prepare and submit to the Commission within 30 days.

pursuant to Control l".3. a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials In liquid effluents during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose or dose commitment to any MEMBER OF THE PUBLIC from such release during the calendar year iswithin 3 mrem to the total body and 10 mremn to any organ.

9URVEILANCE REQUIR3EMENTS5 C.4.2.1 Cumulative dose contributions for the current calendar quarter and current calendar year from liquid effluents shall be determined in accordance vwith Section II of the REMODCM once every 31 days.

A.4.2.2 Relative accuracy or conservatisms of the calculations shall be confirmed by.

- performance --of the Radiological Environmental Monilorig Porma ealdi

..Sectionlof-theREMODCM..-- ___-

C-8 REMM

JUL 15 2003 Revision 16 RADIOACTIVE EFFLUENTS BJASIS .I .4. F C.314 LIQUID EFFLUENTS;"' .-. . -

5.'

C.3/4.2 DOSE. LIQUIDS..

This Control Is provided to Implement the reiquirements of Sectinsh3'll4IlA-and IVA of Appendix I, ;

10 CFR Padt 50. The Limiting Conition for Operation Ip le~m elnts- fthe guiles, set forth InSection IIA of '..

Appendix I. The ACTION statements provide the required operating flexibility and at the, same time implement the guides set forth InSectionIV.A of Appendlx Ito assure that the releases d radloactive material In liquid effluents will, be -kept'alo as Is reasonably achievable'. The dose calculatic.;

methodology and parameters Inthe REMODCM Implement the requirements InSection l11A of Appendix I that conformance with the guides of Appendix I Is to be shown by calculatlonal proedures based on models and data. such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways Is unlikely to be substantially underestimated. The equations specified Inthe REMODCM for calculating the doses due to the actual release rates of radioactive materials In liquid effluents are consistent with the methodology prcvided In Regulatory Guide 1.1 09. "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I.' Revision 1. October 1977. and Regulatory Guide 1.1 13. 'Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I."April 1977.

REMMC-

I - _N J %l,515&003 evson INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CO)NTROL S-:--- M

- . Tal C. 3.3...

C.3.3 'The radioactive liquid effluent monitoring Instrumentation channels shown in Table C.3.3 .. . . .

shall be OPERABLE with applicable Alarm/Trip Setpoints set to ensure that the limits of , - . i Control C.3.1 are not exceeded. The Alarm/Trip Setpoints shall be determined In accordance with methodology and parameters described in the OFFSITE DOSE , ,:

CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times.

ACTION:

a. With a radioactive liquid Mluent monitoring Instrumentation channel Alarm/Trip Setpoint less conservative than required by the above Control, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the Alarm/Trip Setpoint so it Isacceptably conservative.

b. With the number of channels less than the minimum channels OPERABLE requiernent, take the ACTION shown InTable C.3.3. Exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days, and, if unsuccessful, explain in the next Annual Effluent Report why the inoperability was not corrected is,a timely manner.

Releases need not be terminated after 30 days provided the specified actions are continued.

SURVEILLANCE REQUIREMENTS C.4.3 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL OPERATIONAL TEST operations

- .-.--- atthefrequenciesshownin-Table'C.4.3. ---------- *------ -- ---- --- -

,:- . = : _.. :

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

At all times means that channel shall be OPERABLE and In service on a continuous,

-uninterrupted basis, except that outages of monitoring channels are perrnitted for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months each time for the purpose of maintenance and performance of required tests, checks, calibrations or sampling.

C-10 REMM

-- -Revisionl16 JUL 15 2003 INSTRUMENTATION 0ASES C.314.3RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radloactive liquid effluent insruentationIs providled 6to monwitor nd ontrl, s appcable.thej",

releases of radioactive materials.in liquid effluents during actual or potentalW releases of liqui effluents.

The AiarrnrTrfp Setpolnts for these Instruments Shal be calculated and adjusted Inaccordnce ih h methodology and parameters In the ODCM to ensure that the alarm/trp will occur pro oexceeding the limits of 10 CFR Part 20. The'OPERABILITY and use of this instrumentation Is consistent with the ,A requirements of General Design Criteria 60. 63, and 64 of Appendoc A to 10 CFR Part 50.

C-1Il REMM

-JUL 15 2003 I i Revision 16 RATI LI E TABLEN M RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION INSI rRUMENT I l ACTION

1. GROSS RADIOACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. RecycleTestTank 1 46 Discharge Line

2. FLOW RATE MEASUREMENT

- a. Recycle Test Tank l 1. . 47

,-. Discharge Line

b. Discharge Canal i NA,

I!

II iO.i I

U .C*12 REMM

* * . .*. . . , 4...

4. 1'.-

I --

JUL 15 2003 Revision 16

-I LEC.

(Continued)

-ACTIONSTATEMENTS Iv -*

ACTION 46 - With 'the number of channels OPERABLE less than'required by the Minimum' Channes OPERABLE requirements, effluent releases may continue provided that best efforts are made to repair the instrument and that prior to initiating a release:

a. At least two independent samples of the tank to be discharged am analyzed in accordance with Control C.4.1.1, and;

b. A second Individual independently verifies the original release rate calculations and discharge valving.

ACTION 47 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that the flow rate is estimated once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump perfcrnmance curves generated insitu may be used to estimate flow.

t i:,- - .

-- --.- .. .- -. ..-.- .. J

. *q

. .:r1,- - ..

.- I-. I C-13 REMM

JULIl15 200?,

I :Rev ision 16 EL LUTABLE RADV I C.4.

RADIOACTIVE LIQUID!EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUI REMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. GROSS RADIOACTVITY MONITORS :;i PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE(5) I

a. RecycleTest D(1) p R(2(3 Tank DIscharge Line

2. FLOW RATE MEASUREMENT

a. Recyle TestTank D(1) NA. R NA Discharge Line j r4-!

b. Discharge Canal I D(4) NA NA . NA R E, C014

': REMM .+ - q ,I - *. C *,' .2/.">-.4'< *q .

I 15 2003 JULRevision 16 (Continued)

TABLE NOTATIONS (1). CHANNEL CHECK need only be performed daily when discharges are made from thi pathway. The CHANNEL CHECK should be done when the discharge Is In process.

(2) CANLCALIBAM Nsalb promduigaknown radioactlv~e liquid or solid

'Source whose strength Is determined by a detector which has been calibrated to an NIS source. The radioactive source shall be In a known., reproducible geometry.-

(3) The CHANNEL OPERATIONAL TEST shall also demonstrate that control room or local (see (5) below) alarm annunciation occurs if any of the following conditions exist

1. Instrument Indicates measured levels above the alarmnhtrip setpoint.t

2. Instrument indicates a downscale failure or circuit failure.

3. Instrument controls not set in op,.ra te mode.

(4) Pump status should be cnecked at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for the purpose of determining flow rate.

(5) A responsible Individual (preferably an operator) shail be present and within audible range of the local alarm (to monitor the alarm function) during Test Tank Discharges.

.------ - - - - - - - ---- Z---

Automatic isolation shall also be demonstrate annually for the test tank discharge monto line.

C-I5 REMM

JUL 15 2003

-.I Revision 16 D. GASEOUS EFFLUENTS D.1 Gaseous Effluents SamDilna and Analysis Proaram Radioactive gaseous wastesshall be sampled ard analyzed In accordance with

.-the program specified In Table'D-1 for the Haddam Neck Plant The results of the radioactive analyses shag be Input to the methodology of the'ODCM to assure that the offsite dose rates are'maintalned within the Controls of the REMODCM.

- . - . . . .4......

, .: .. . :__ i.. . . , , ,

D-1 REMM

JUL 15 2003 Revision 16 U TABE SPL

. RADIOACTIVE GASEOUS WASTE SAMPLMINGAND ANALYSIS PROGRAM . .

I

.> i;

. . . ..., 1. . Lower Limit Minimum of Detection Sampling ' - Analysis Type of Activity (LLD)r .

)'"'>',

Gaseous Release Type Frequency Frequency Analysis (Ucvcc) _ .

5

, .91,;

', .t. i ff .

9. 4 - 4. - 4.

A.' Spent Fuel Pool Spray Weekly Weekly Prici Gamma 3.OOE-08 . ........... t. .

Cooling Liquid Grab - Emitters .S 11-3 2.OOE-06 .'.

Monthly Gross Alpha I.OOE-07 '.'

Liquid Composftet° ,.

Quarterty Sr-90 5.OOE-08 Liquid Fe-55 1.OOE-06 Composite'9 B. Containment Purge Prior to Prior to H-3 t.OOE-06 Each Purge Each Purge C. Spent Fuel Building Weekly Weekly Kr-85 I.OOE-04 Exhaust Gaseous Grab t-3 1.OOE-06 Continuousb- -:Weekly Principal Gamma - .OOE-11 Particulate Er.nitters _

= --- =--- Morthlyt -- 7Gioi'Aitia ----- ti.OOE-11--

Particulate

_---Composite _ - _

-u - uarterly- - Sr-gd - t.OOE-11 Particulate Composite Noble Gas Noble Gas 1.OOE-06 Monitor Gross Activity D-2 REMM

N --- = - - - - -N ---

iq evasion 15 20016 33 a.-.

, -7

. i, -

(Continued) . .; .,:

m.S Lower Umit . ' " '.'5,^o.',.

Minimum of Dtection '

-Sampling - Analysis Type of Activity (LLD Gaseous Release Type Frequency Frequency -Analysis (utCacc) W u . ,t,.,

D. Main Stack Weekly Weekly H-3 1.OOE-06 S,':t- S.

Gaseous Grab ,1_ ,t,t A .

_'tts)

Continuousb Weekly Princpal Gamma 1.OOE-11 Lf.S#'.

Particulate Emitters' '.y,

'.St"

.- s,. t,

">'S' t Monthly Gross Alpha 1.00E-11 Particulate .;,..,.. .

Composite Quarterly Sr-9(9 1.OOE-11 '_" '}

Particulate .'s,.

Composite . :

E. Miscellaneous Polntse Continuousb Weekly Principal Gamma 1.OOE-11 Particulate Emitters' For example:

Alternate Containment Access Monthly Gross Alpia 1.OOE-1 1

Tented Enclosures Particulate Composite

-Quarterly Q Sr-96 IOOE-11

-Particulate--

Composite

'I D-3 REMM t.

I."..-

0 JULRevision 15 200316

-.(Continued)

.TABLE NOTATIONS:

a. The lower limit of detection (LLD) Is defined In Table Notations of Table C-I.

b. The ratio of the sample flowirate'to'the 'sampled stream flow rate shall be known for the time period covered by each 'dose or'dose rate calculation made In accoiancewit REMODCM.

c. The principal gamma emitters for which the LLD specification win apply are exclusively be following radionuclides: Mn-54,Co-60, Zn-65, Cs-134. and Cs-137. The Iist does not mean that only these nuclides are to be detected and reported. Other nuclides, which are identified, shall be reported. Nuclides which are-below the LLD for the analyses should not be reported as being presenr at the LLD. When unusual circumstances result In an a Priori (before the fact) LLD being higher than required, the reasons shall be documented in the Annual Radioactiva Effluent Report.

d. Sample prior to purge will be obtained from the charging floor (refueling floor). Only required if reactor cavity is flooded.

Sample results from the charging floor will be used to account foe gaseous radioactivity released for the first 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; after 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , the radioactivity released will be accounted for from the Main Stack.

e. Samples shall be changed at least once per 7 days and analyses completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . The LLDs may be increased by a factor of 10 if sample collection is for less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

f. A composite sample Is one in which the quantity of liquid sampled is proportional to system operational time and In which the method of s~ff:pling employed results In a

-- -I specimen which is representative of the liquid released.' ji

- - '9."- Prirtoaas plestkerif-r the composite shal Ibe troughly mixed In order for the composite sample to be representative of the effluents released.

h. Release points included Inthis category are added if the radiological evaluation of the job or building indicates a potential for significant airborne radioactivity. This evaluation shall -

' --be performed in accordance with applicable radiological engineering programs.

i. Sr-90 analysis only required if Gross Beta is identified.

REMM

JULRevision 15 2-00?

16 D.2 Gaseous Radioactive Waste Treatment Monthly doses due to gaseous effluents to unrestricted areas shall be projected at-least once pr3 asol if one or ALL APPLICABLE; GASEOUS"'

RADIOACTIVE WASTE TREATMENT-SYSTEMS will not be routinely operated. -'-1.

Whnthe projected monthly'dose due to gaseous effluents exceeds 0.2 mrad for, gamma rad to,04mrad for beta radiationor 0.3 mrem to an organ det

gaseous-parcticlate: effuents, .ALL- APPLICABLE GASEOUS- RADIOACTIVE.

WASTE TREATMENT SYSTEMS will be operated.

'With radioactive gaseous waste being discharged without treatment and Inexcess of the above :limils, prepare and submit to the Commission, within 30 days.

pursuant to Subsection F.3, a special report that includes the following Informator~

a. Explanation 'of why gaseous radwaste was being dischagd wMtou treatment, Identification of any Inoperable equipment or subsystems, and the reason for the Inoperability;

b. Actions taken to restore bv Inoperable equipment to OPERABLE status; and C. Summary description of actions taken to prevent a recurrence.

-D-5 REMM

- MI iU u5lon,1161""I D.314 GASEOUS EFFLUENT CONTROLS AND SURVEILLANCE REQUIREMENTS DOSE RATE

'-' CONTROLS' - -'A 'I D.3.1 ' The dose rate, at any tUime6,;offsite '(see Figure H-1) due to radioactive mnaterias released in gaseous efflueintsfrom the site shall be lirnited to the following vaiu;s:'

a. The dose rate limit for noble'gases shall be less than or equal to 500 mrem~ry to the total body and less than or equal to 3000 mremnr to the skin, and

b. The dose rate limit due to Inhalation for tritium and for an radioactive materials in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mrem/yr to any organ.

APPLICABILITY: At all times.

ACTION:

With the dose rate(s) exceeding the above limits, decrease the release rate within 15 minutes to comply with the limit(s) given in Control D.3.1.

SURVEILLANCE REUREMES D.4.1.1 The release rate, at any time, of noble gases in gaseous effluents shall be controlled by the offsite dose rate as established above in Control D.3.1. The corresponding release rate shall be determined In accordance with the methodology of Section II of the REMODCM.

D.4.1.2 The noble gas effluent monitors of Control D.3.4 shall be used to control release rates to limit offsite doses within the values established in Control D.3.1.

D.4.1.3 The release rate of radioactive materials in gaseous effluents shall be determined by

- -obtainn -rpeetative samples a- performing _analyses in-.accordance wivth- the -

- sampling and-analysis-program specified in Section-I of the REMODCM (Table Dl1).

__ The corresponding dose rate shall be determined -using -the -methodology- and -- -

parameters given in the ODCM (Section II of the REMODCM).

___ _-~ -- .. --- -- .. * - - __- --_--- I* - * *I~-,.* ~---

D-6 REMM

M- --- M RADIOACTIVE EFFLUENTS D.314 'GASEOUS EFFLUENTS I-2:>

D.314.1 'DOSE RATE This Control Is provided to ensure that the dose rate at anytime from gaseous effluenft from the sfte winl be within the annual dose limit of IO CFR Part 20 for aln area offslte. The anniual dose limits are the' doses associated with the concentrations of IO CFR Part 20, Appendix: B. Table II (pre 1994 verslon)

These limits provide reasonable assurance that radkoactive material discharged In gaseous effluents wi,"

not result In the exposure of an Individual offslte toannual average concentration exceeding the limits specified in Appendix B. Table II (pre 1994 'version) of IOCFRPart2O (IOCFR20.106(b)). For Individuals who may at times be Within the SITE BOUNDARY, the occupancy of that kxdivdual will be sufficiently low to compensate for any increaqe In the atmospheric diffusion factor above that for the sITE BOUNDARY. The specified release rate limi%., restrict,'at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the SITE BOUNDARY to less than or equal to 500 mremlyear to the total body or to less than or equal to 3000 mremlyea to the skin. These release rate limits also restrict, at all times, the corresponding thyroid or other organ dose rate above background to a child to less than or equal to 1500 mreml~year from Inhalation.

D-7 REMM

I I JUL 15 2003 Revision 16 RADIOACTIVE EFFLUENTS DOSE, NOBLE GASES . -- /,,.

D.3.2 The air dose offsite (see Figure H-I) due to noble ga released In gaseous effuen shall be limited to the fllowing:i- :' ......

a. During any calendar quarter, to less than or equal to 5 mrad for gamma radiation' and less than or equal to 10 mrad for beta radiation, and

b. During any calendar year to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: -At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases In gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control F.3, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose during the calendar year is within 10 mrad for gamma radiation and 20 mrad for beta radiation.

SURVEILLANCE REQUIREMENTS D.4.2.1 Cumulative dose contributions for the current calendar quarter and current calendar year -for~noble ga-ses--shall -b6 zdete nl-ind In- accordance: wi% Section' II of the REMODCMonceevery3l days.: i - . ... . -

D.4.2.2 Relative accuracy or conservatism of the calculations shall be confirmed by

- - performance of-the -Radiological Environmental Monitoring Program as detailed in Section I of the REMODCM.

REMM

JUL 15 2003 Revision 16 RADIOACTIVE EFFLUENTS BASES .- .- :.

D.314 GASEOUS EFFLUENTS D.3/4.2DOSE. NOBLE GASES This Control Is provided to Implement the requirements of Sections II.B., IIIA and IVA of Appendix I.

10 CFR Part 50. The LImiting Condition for Operation implements the'guides set forth hI Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time Implement the guides set forth In Section IVA of Appendix I assure that the releases of radioactive material In gaseous effluents will be kept "as low as Is reasonably achievable." The Surveillancu Requirements Implement the requirements In Section IIIA of Appendix I that conform with the guides of ft Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an Individual through the appropriate'pathways Is unlikely to be substantially underestimated.

The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents ale consistent with the methodology provided in Regulatory Guide 1.109. "Calculational of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1." Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors.* Revision 1, July 1977.

The ODCM equations provided for determining the air doses at the SITE BOUNDARY are based upon utilizing successively more realistic dose calculational methodologies. More realistic dose calculational methods are used whenever simplified calculations indicate a dose approaching a substantial portion of the regulatory limits.

-'C I. - I , ,I

--I--,';

D-9 REMM

I -I 1111110 JUL 15 2003 Revision 16 RADIOACTIVE EFFLUENTS DOSE, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES CONTROLS D.3.3 The dose to any MEMBER OF THE PUBLIC from tritium and radioactive materla's 'i particulate form with half lives greater than 8 days In gaseous effluents released offshte (see Figure H-1) shall be limited to the following:

a. During any calendar quarter to less than or equal to 7.5 mrern to any organ;

b. During any calendar year to less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radionuclides, radioactive materials in particulate form, or radionuclides other than nioble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control F.3, a Special Report whici Identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose or dose commitment to any MEMBER OF THE PUBLIC from such releases during the calendar year is within 15 mrem to any organ.

SURVEII LANCE REQUIREMENTS

-D.4.3.1 -.Cumulative dose contributions for the current ca'endarcwzarter and current calendar

- ~year shall be determined in' accordance with Section 11of the REMODCM once every

--31 days..~ 7 J i 7.

-D.4.3.2 --Relative -accuracy or conservatism -of -the -calculations -shall -be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in the REMODCM.

D-10 REMM

JUL 15 2003

~ Revision 16 RADIOACTIVE EFFLUENTS D.314.3 DOSE.- RADOACTIVE MATERIALAIN PARTICULATE FORM AND-RADIO1C0E ,

OTHER TH-AN NOBLE GASES.""

This Control Is provided to Implement the requtirements of Sections Il.C. l11A and WVA of Appendix l, 10 CFR Part 50. The Limtn Codtosfor Oe atmn r the guides set forth InSection lI.C of Appendix

1. The ACTION statements provide the required operating flexibility and at the same Urns Implement the guides set forth In Section [V.A of Appendix' I to "assure that the releases of radioactive materials In gaseous effluents will be kept "as low as Is reasonably achievable.- The ODCM calculational method-z specified In the suiveiilance requirements Implement the requirements in Section lilA of Appendix I that conformance with the guides for Appendix I be shown by calculational procedures based on models -ad data such that the actual exposure of an:Indivdual through appropriate pathways Is unlikely to be substantially underestimated.' The OD)CM cnlculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided In Regulatory Guide 1.109. "Calculating of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50. Appendix I." Revision I. October 1977 and Regulatory Guide 1.111. "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision I,July 1977. The release rate Controls for radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man. The pathways which are examined in the development of these calculations are:

1) individual Inhalation of airborne radionuclides.

2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man,

3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and

- 4) -depositionbinithe grouhd With-subs6Cque-nt 'e'xpos~u_-re of man.

D-I1I REMM

M __

JUL 15 2003 Revision 16 INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONmTROLS

-D.3.4 The radioactive gaseous effluent 'monitoring' Instrumentation channels shown In Table D.3.4 shall be OPERABLE with applicable Alarm Setpolnts set to ensure that the Eimits of Control D.3.1 are not exceeded. The setpoints shall be determined In accordance with the methodology and parameters as described In the ODCMK APPLICABILITY: At all times' ACTION:

a. With a radioactive gas ous effluent monitoring Instrumentation channel Alarm Setpoint less conservative than required by the above Control. without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the Alk.m Setpoint so it is acceptably conservative.

b. With the number of channels less than the minimum channels OPERABLE requirement, take the ACTION shown in Table D.3.4. Exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Report why the inoperability was not corrected in a timely manner. Releases need not be terminated after 30 days provided the specified actions are continued.

SURVEILLANCE REQUIR1EMENT D.4.4 Each radioactive gaseous effluent monitoring instrumentation 'channel shall be

-demonstrated--OPERABLE--by-performance of -the-CHANNEL CHECK, SOURCE-_

. ' CHECK, CHANNEL'CALIBRATION, and ANALOGPCHANNEL OPERATIONAL TEST operations at the frequencies shown in Table D.4.4. --

At all times means that the channel shall be operable and in service on a continuous basis, excect that outages are permitted for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months each time for the purpose of maintenance and performance of required tests, checks, calibrations.

D-12

- REMM

JUL 1 5 2003 Revision 16 INSTRUMENTATION - -

R ^~~~~4~~ ' :-- -i j D.314.4RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous efuent Instrumentation Is provided to monitor and cnro-, 'sapl:c., -ie . '

releases of radioactive materials In gaseous'effluents during actualor potential releases of gaseous effluents. 'The Alarm/Trip Setpolnts for these Instruments shall be calculated aid adusted inacrnce .

with the methodology and parameters hI the REMODCM to ensure that the alarrn/tirp wil occur prior to -

exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation Is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

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JUL 15 2003 Revision 16 RADIOACTIVE GASEOUS EFFLUENTMONITORING

-~-: MINIMUM INSTRUMENT :.ERAiLm ACTIO

1. SPENT FUEL BUILDING EXHAUST MONITOR

a. Noble Gas Activity Monitor PrW i Alarm -

so

b. Particulate Sampler 1 .51

c. Stack Flow Rate Monitor .

52

d. Sample Flow Rate Monitor 1 52

2. MAIN STACK MONITOR

a. Particulate Sampler 51 1

b. Stack Flow Rate Monitor I 52

c. Sample Flow Rate Monitor I 52

, ... ' ,:, -: - ... ., -. , , - His:, - * , 4.

- D14 . .

REMM

JUL 1 5 2003 Revision 16

.'.(Continued)

ACTION STATEMENTS ACTION 50 - With the number, of channels' OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases'va this pathway may continue provided that best efforts are made to repair the instrument and grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 51 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue.'orovided that best efforts are made to repair the instrument and that samples are continuously collected with auxiliary sampling equipment for periods of seven (7) days and analyzed for principal gamma emitters with half lives greater than 8 days within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period. Auxiliary sampling shall be established within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of dedaring the channel inoperable.

ACTION 52 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that the best efforts are made to repair the instrument and that the flow rate is estimated once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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JUL 15 2002

- Revisikin 16 RADIOCTIV GASU ETABLE MIE RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT

1. SPENT FUEL BUILDING EXHAUST '

0 CHANNEL CHECK SOURCE CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST . .

MONITOR .

t a.Noble Gas Activity Monitor :

D(1) M R(2)

Q(3) b.Particulate Sampler w NA - NA:: NA

.',, Si c.Stack Flow Rate Monitor D(1) NA R

.. . I

-NA.

! - NA::

d.Sample Flow Rate Monitr , ,.,: .. di D NA r

2. MAIN STACK MONITOR . i i, .!

.. j l a.Particulate Sampler w N.A. NA NA s . .,.r .> [

I '.;, r b.Stack Flow Rate Monitor D(1) NA R NA

11.

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c.Sample Flow Rate Monitor D NA R NA l; ,

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4.

-,4, D.16

JUL 15 2003 Revision 16 (Continued) i, TABLE NOTATIONS kk (1) CHANNEL CHECK daily when releases exist via this pathway.,

(2). Calibration shall be performed using'a known source whs tent sdeemndby a detector, which has been calibrated to an NIST'source." These sources shall be In a known, reproducible geometry.

(3) The CHANNEL FUNCTIONAL TEST Shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist.

a. Instrument Indicates measured levels above the Alarm Setpoint.

b. instrument indicates a downscale failure or circuit failure.

C. Instrument controls not set Inoperate mode.

D-17 REMM

I JUL 15 2003 Revisn 16 E. RADIOLOGICAL ENVIRONMENTAL MONITORING E.1 Sampling and Analysis

-The radiological sampIig and analyses provide measurements of radiation and of radioactive materiais'jnthose exposure pathways and for those radlonucides

whIch lead to the highest potentIal radiation exposures of Individuals resultirg fro P

plant operation.:. This monitoringprogram thereby. supplements the radloiogIcal-effluent monitoring pr'p ramby 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 from plant or.ISFSI activities. 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 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 Seceon 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 (excluding milk) at the most desired location or time. In these instances suitable altemative media and locations may be chosen for the particular pathways in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program.

If the Land Use Census Identifies milking animals within 8 km (5 miles) from the site, milk sampling shall be initiated as follows:

-.Samples from milking animals shall be coW.cted frmm 3 indictor location within

.:5 km (3 miles) from.the site at the locations calclated to have the highest

--.--dose potential. ----

_ If no milking animals are located within 5nkmn(3-miles),.then.samples from milking animals shall be collected from 3 indicator locations between 5 to 8 km (3 to 5 miles) from the site at locations calculated to exceed I mrem per year.

(The dose shall be calculated for the maximum organ and age group, using the methodology and parameters Inthe ODCM.

If any samples of milking animals are collected, 1 control sample shall be collected from milking animals at a location 15 km to 30 km (10 to 18 miles) from the site and Inthe least prevalent wind direction.

Any and all changes to milking animal sample locations shall be documented In the Annual Radiological Environmental Operating Report which is submitted to the

. U.S. Nuclear Regulatory Cohmmision prior to My of each year.

El1 REMM

UI JUL 1 5 2003 Revision 16 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 averaged over any calendar quarter, prepare and submit to the Commission within 'C, 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(1) concentration (2) reportinglevel (1) reportinglevel (2) ' ' 1 When radionuclides other than those InTable E-2 are detected and are the 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 REMODCM. This report is not required if the measured level of radioactivity was not the result of plant effluents, however, in such an event, the 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. 1.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 posteriori (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 be identified and described in the Annual Radiological Environmental Operating Report.

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E-2

. I REMM.

JUL 15 2003 Revision 16 HADDAM NECK RADIOLOGICAL ENVIRONMENTAL MONITOIRING ;-1., .

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s

-'PROGRAM * ,

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. l ;gM!Mr ,t' i Exposure Pathway andlor Number of Sampling and Collection Type and Frequency of. . 'i'j, Sample -Locations Frequency Analysis - .X ' 8;k¢']

, At

1. Gamma Dose - 20 , Quarterly Gamma Dose - Qua :,, ' .: _ _

Environmental TLD it.s S grunt

2. Airbome Particulate 5 ContInuous sampler - biweekly Gross Beta - BiweeklyW

9 a, . .

S,f filter changiesGamma Spectrum - Quarterly on . . ;,'

composgee (by location), and ^n . . .

,.,id.dual sample ifgross beta Is greater than 10 times the mean of '. I' '.' A, the biweekly control stations .....

gross beta results. .....

3a. Vegetation - Fruits 2 Cie sample near middle and one Gamma Isotopic on each ' ",

and Vegetables near end of growing season sample 3b. Vegetation - Broad 3 Monthly during growing season Broad Leaf Vegetation at each of Leaf Vegetation, in lieu (April - December) be two indicator and one control of milk ocaStions. when avaitable.

Gamma Isotopic on each sample

4. Milk 4 Monthly, if required Gamma Isotopic on each sample

- MOfithly, if required Sr Quarterly. if required

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

6. Bottom Sediment 4 Semiannual Gamma Isotopic

7. River Water 2 Quarterly Sample - Indicator Is Ouarterly - Gamma Isotopic Continuous Composite; Control is and Tritium of continuous Composite of Six Consecutive Grab Samples collected biweekly indicator and control grab composites _I-

8. Fish (edible portion) -

- - bullheads and, when -

available. Perch orother edible fish 3

Iz Semiannual I. .. . . .- ...

.. .. .c...posi.e..

Garnma Isotopic - Semiannual

.. .. . .. . . 1 . -

t i-

9. Shellfish 2 Semiannual Gamma Isotopic - Semiannual A A.

More frequent filter replacement may be necessary, depending on filter media loading. Gross beta analysis frequency shall follow the frequency of the filter replacement.

Milk sampling and analysis is only required if the conditions specified in NUREG 1301.Table 3.12-1, are met Z_

(Samples are collected from milking animals In three locations within 3 miles when, and If. milking animals are .w identified in the annual Land Use Census. If no milking animals are found within 3 miles. then samples from A.

milking animals In one location between 3 and 5 miles are collected if the projected dose from milk consumption ;

exceeds 1 mremlyear via this pathway). The Land Use Census looks for and documents (when found) the presence of milk animals within 5 miles annually.

E-3 REMM

0 -- M JUL 15 2003 Revision 16

-REPORTING LEVELS FOR RADIOACTIVtTY CONCENTRATIONS

:: IN ENiRONMENTAL SAMPLES -

Reporting l evels: +/-4 "S Analysis Water ;,: M:rAbomo-e Fish ;; :'-Milk Vegetables Shellfish (pCIL) Particulate (pCVkg, wet) (pC/) (pCikg, wet) (pC/kg, et) or Gas (pCu 3)

H-3 2.OOE+04 -

Mn-54 1.00E+03 3.00E+04 IAOE+05 Co-60 3.OOE+02 1.00E+04 5.00E+04 Zn-65 3.OOE+02 2.00E+04 8.00E+04 Cs-134 3.00E+01 1.OOEt-O1 1.00E+03 6.OOE+01 1.OOE+03 5.00E+03 Cs-137 5.0OE+01 2.OOE+01 2.00E+03 7.OOE+01 2.00E+03 8.00E+03 E-4 REMM -; -

JUL 15 2003 Revision 16 MAXIMUM VALUES FOR LOWER LIMITS OF DETECTION (LLD)*'..--.

Analysis. Water Ajbm ihMilk Food Sedkmnti (PCII) artculato, (pCI/kg. wet) (pCIi rdcs (C/g r)~

¶ or~a (pC~kg. wet)

Gross Beta Ap.tn) _____0____

_ _ O.EO

_ _ _ __O E0 Mn-54 1.S0E.FOI 1.30E-42 ___

Co-60 1.50EtO1 .1.30E402 1.50E+02 Zn-65 3.OOEt-O1 2.60E402 Cs-134 1.50E401 5.OOE.-02 1.30E402 1.50E4O1 6.OOEO0I 1.50E402 Cs-137 1.80E4O1 6.00OE-02 1.50E+02 1.80E.O1 8.00E4O01 1.80E.+02 E-5 REMM

0 JUL 15 2003 Revision 16 (Continued)

. , TABLE NOTATIONS .

'a.Th'e wer limit of de on ( ) Is the smallest materi i ae

-:smple that will be detected With 95% probability with 5%probability of falsely concludi ;

-that a'blank observation represents a Rear signal. -

For a measurement system (which may include radiochemical separation)-

E V. 2.22. Y-Ycxp(-A) where:

I LLD is the lower limit of detection as defined above (mcrocuries per unit volume)

-I Sb is the standard deviation of the background counting rate, or of the counting rate of a blak sample, as appropriate (count per minute)

E Is the counting efficiency (counts per transformation)

V Is the sample size (volume) 2.22 is the number of transformations per minute per picncurie Y Is the fractional radiochemical yield (when applicable)

A.Is the radioactive decay constant for the particular radionuclide At Is the elapsed time between sample collection (or midpoint of sample collection) and time of counting.

It should be recognized that the LLD Is defined as an a oRio (before the fact) limit representing the capability of a measurement system and not as an a oosterlorl (after the fact) limit for a particular measurement.

Analyses shall be performed Insuch a manner that the stated LLDs wilt 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 be identified and dlxrirhed In the Annual Radiological Enfironmental Operating Repor-- - -

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E-6 REMM

JUL 15 2003 Revision 16 E.2 Land Use Census 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 cnsus satisfies, the requirement ofSection IV.B.3 of Appendix I to 10 CFR Part 50.'

The Land Use Census: shafll be dced"n shall Identify the. location 'of ftheiU:

-nearest resident, the nearest milk anilmal, and the nearest garden"~of greater than

'50 m2 (500 if) producing brio-ad leaf vegtationri'n each of the.16 meteorological sectors within a distance of 8 km (5 miles).

The validity of the ILand'Use Census shall be conducted'at least oncpe calendar year by either a door-to-door'survey, aerial survey, consulting local agriculture authorities, or any combinatin oftese methods. '

With a Land Use Census Identifying alocation(s) which yields a calculated dose or dose commitrw-nt 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) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained In accordance with Section E.I. add the new location(s) within 30 days. The sample location(s),

excludina the control location. havina the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which the Land Use Census is conducted.

With a Land Use Census identifying milking animals within 8 km (5 miles) fo the site, initiate sampling for milk in accordance with Section E.1 within 30 days.

-- Simple' location cha~nges shall be-nobted in'the'AMnuaI Radiological Environmental mrad leaf vegetation (a composite of 'atleast 3 different kinds of vegeain a e sampled at the SITE BOUNDARY In each of 2 different direction setrs,wth high DIQ in lieu of a garden census.

REMM E7

M JULReAsIon 15 2003 16 E.3 interlaboratory Comparison Program The Interlaboratory Comparison Program Is provided to ensure that Independent k 4"..

' checks on the precision and accuracy of the measurements of radioactive mate .6l

n environmental sample matrices are performed as 'part of a quality assurance gproram for environmental monitoring in order to demonstrate that the' results are re~.asoa~y vaiauld

-. Analyses 'shall be'pe'rformned,'on radioactive materials supplied as part of an

. .. terlaboratory Comparison Program. "A summary of the results obtained, as part

'ofthe above required Interlaboratory Comparison Program shall be Included in the

'Annual Radiological Environmental Operating Report. .04 With,'analyses not being performed as required above, report the corrective actions taken to prevent la recurrence to the Commission In the Annual Radiological Environmental Operating Report-

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JUL 15 2003 Revision 16 F. REPORT CONTENT F.1 Annual Radioloilcal Environmental ODeratina ReDort The Annual Radioactive Environment iOperating Reportshall include summaries,',

interpretations and statisticalevaluation' of the results of 'the radiobogical

'-environmental surveillance activities' fo the report period, including a comparison with the previous environmenalsurveillance reports and an assessment of the observed Impacts of the-plant operation'and ISFSI on the environment. The report :

shall also include the results of the land use census required by Section E.2 of thi 4M Y manual. If levels of radioactivity are detected that result In calculated doses "'

greater than 10 CFR Part 50 Appendix I Guidelines, the report shall provm an analysis of the cause and a planned course of action to alleviate the cause.

The report shall Include a summary table of all radiological environmental samples, which shall include the following information for each pathway sampled, and each type of analysis:

a. Total number of analyses performed at Indicator locations;

b. Total number of analyses performed at conitrol locations;

c. Lower limit of detection (LLD);

d. Mean and range of all indicator locations together,

e. Mean and average of all control locations together,

f. Name, distance and direction from discharge, mean and range for the location with the highest annual mean (indicator or control); and

- g. Number of nonroutine reported measurements as defined in these specifications. - -

_ ._ .- .-in-the event-that some results are not-available-for inclusion :with-the report,-the7.--=='-

report shall be submittedh6ting and explaining the reasonsfor the missing results.

The missing data shall be submitted in the next annual report. - -- - - -- -

The report shall also include a map of sampling locations keyed to a table giving distances and directions from the discharge; the report shall also include a _ -

-- ---- - -- -.--- summary of the interlaboratory Comparison-Data-required by Section E.3 of this manual.

.. ~~. .. ' -' 4. m.j F-i REMM

JUL 15 2003 Revision 16 F.2 Annual Radioactive Effluent Report The Annual Radioactive Effluent Report (ARER) shall Include quarterly quantities ,

of and an annual summary of radioactive liquid and gaseous effluents released from the unit Inthe Regulatory Guide 1.21 (Rev 1.'06174) format. Radiationdose assessments for these effluents shall be provided Inaccordance with IO CFR Part 50.36a and the REMODCM. An annual assessment of the radiation dose from the site to the most likely exposed MEMBER OF THE PUBLIC shall be Included to'...

'demonstrate conformance with 40 CFR Part 190. 'A table totaling and comparing' ,-, -,

doses from liquid and airborne sources to the 40 CFR 190 limit wil be provided In the Annual Radioactive Effluent Report. CY direct radiation from the she. Based on ERC-161-3-ER-99-012, direct dose will not be routinely included In the dose assessment. An evaluation of the direct dose aspect will be discussed In the' Annual Environmental Operating Report. This evaluation will Include the dose recorded on control TLDs and TLDs located near residents. Dose shall be calculated In accordance with the OFFSITE DOSE CALCULATION MANUAL The --

ARER shall be submitted by May I of each year for the period covering the previous calendar year.

The ARER shall include a summary of each type of solid radioactive waste shipped offsite for burial or final disposal during the report period and shall include the following Information for each type:

a. Type of waste (e.g., spent resin, compacted dry waste, irradiated components, etc.);

b. Solidification agent (e.g., cement);

c. Total curies;

d. Total volume and typical container volumes;

e. - Principal radionuclides (those greater than 10% of total activity); and Tyesw cntainers used (e.g.,-'LSA; Type A],-et;).

The ARER shall include the followinr' Formation for each abnormal release of -

radioactive liquid and gaseous effluen. . ' the site to unrestricted areas:

a. Description of the events and equipment :. :Xwpd;

b. Causes for the abnormal release;

c. Actions taken to. prevent recurrence; and .____

d. Consequences of the abnormal release.

Changes to-the RADIOLOGICAL-EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) shall be submitted to the NRC as appropriate, as part of or concurrent with the ARER for the period In which the changes were made.

F-2 -*-

REMM

U -M-JUL 15 2003 Revision 16 F.3 SPECIAL REPORTS Special reports shall be submitted to the U.S.- Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, with a copy to the appropriate Regional Ofce of the NRC, within the time period specified for each report 5 4

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VS I z F.3 jx REMM -

JUL 15 2003 Revision 16 G. TOTAL DOSE G.1 Total Dose from All Sources In addition to the dose limitations specified in sections C & D of the REMM, Ir 40 CFR 190 limits the total dose to an individual from all sources (liquid effluents, gaseous effluents, and direct dose from fixed sources) to less than or equal to 25 mrem per year to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem per year.

=,_ =. _ _ __ , _ _ _ _ _ =_ = _ _ _ .__

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JUL 15 2003 Revision 16 G.2 Compliance with 40CFRI90 Limits The following sources should be considered in determining the total dose to a real individual from uranium fuel cycle sources:

CY gaseous does from all release pathways.'-- ; -:

-b.- CY liquid doses from all release pathways. --

c. CY direct dose from the site (see Section D.5 Inthe ODCM).-

d. -Since all other uranium fuel cycle sources are greater than 20 miles away.

they need not be considered.

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JUL 15 2003 Revision 16 G.314 TOTAL DOSE CONTROLS AND SURVEILLANCE REQUIREMENTS CONTROLS G.3 The dose or dose commitment from the site to a MEMBER OF THE PUBLIC is limited to less than or equal to 25 mrem to the total bodybor any organ (except the thyroid, which 4 '

Is limited to less thanor equal to 75 mrem) over a period of 12 consecutive months.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification C.3.2, D.3.2, or D.3.3, prepare and submit a Special Report to Commission pursuant to Control F.3 and limit the subsequent releases such that the dose or dose commitment from the sin to any MEMBER OF THE PUBLIC Is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. This Special Report shall Include an analysis which demonstrates that radiation exposures from the site to any MEMBER OF THE PUBLIC (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. If the estimated doses exceed the above limits, the special report shall Include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

SURVEILLANCE REQUIREMENTS G.4 Cumulative dose contributions from liquid and gaseous effluents and direct radiation shall be determined in Specifications C.4.2.1, D.4.2.1 and D.4.3.1 and in accordance with Section II of the REMODCM once per 31 days.

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evtlon15 16 2003 BASES G.314 TOTAL DOSE This specification Is pr6vided to meet the reporting requirements of 40 CFR Part 190. For the purposes of the'Special Report, it may be'assumed that the dose commnitment to any MEMBER . ',-.. i OF THE PUBLIC from' ther fuel cycle sources'is negligible, with the exception that dose contributions fror other nudear fuel cycle facilities'at the same site or within a radius of 5 ,mIles'*.,.. ,

must be considered. - ' *:; -

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JUL 1 5 2002 Revision 16 Figure H-2 Liquid Radwaste System N

,.cai'u I

- Collection Point eTanEs (AsRequired

. I Filters, Ton Exchangers (As Required)

Tanks As Required

.I

.FRC. -FCV R-22

]- .1 . - -... .- w- - -.- . . ,

- I-".- , . .", -' - 11; I' - - - ' - - - -- 7 ' - - -- .-

Discharge Canal

s , !I7.7 /Discharge/ Header

-Circulating Water - . .-...- -.. ..

Discharge Tunnel FRC - Flow Contrioller FCV - Flow Control Valve H-:.

- REMM

ACP 1.2-2.48 Rev. 2 Attachment 2 Connecticut Yankee REMIODCM Change Request Check One: 03 REMM Change 0 ODCM Change Change Request / 03Q01 Originator Name (Print): K.Comiskv (Angacb mrlwp poge)

Section MiTle Pace No. Description Of C-ha . & . 21 A.1 Introduction and A-1 Description of Changre.

Responsibility Added iSFSr Basis for Change:

New ISFSI REMP Monitoring Locations B.6 Definitions B-I Description of Change:

Added defrnition of ISFSI Basis for Cbange:

ISFSI added to REMODCM B.13 Definitions B- 2 Description of Change:

Revised the description of the liquid radwaste treatment system to reflect current and planned equipment to be used.

Basis for Change:

The current description did not reflect the equipment in

. place.

C-l Radioactive Liquid C-2 Description or Change:

Waste Sampling and Removed recycle test tanks Analysis Program Basis for Change.

Abandoned equipment C.3.1 Controls C-6 Description of Change:

Added a clarifier to 10 CFR 20 App. B, rabie B, Counn 2 i(pre 1994 version)r Basis for Change:

To clarify correct version of !OCFR20 C3/4. 1 Concentration C-7 Description of Change:

Added a clarifier to 10 CFR 20 App. B, Table 11, Column 2'(pre 1994 versio)"!

Basis for Chauige:

To clarify correct version of ! 0CFR20 D. 3/4.1 Dose Rate D-7 Description of Change:

Added a clarifier to 10CFR 20 App. B, Table 11 '(pre 1994 version)-

Basis for Change:

To clarify correct version of IOCFR20 E.1 Radiological E- I Description of Change-Environmental Added -ISFSI' Monitoring Basis for Change:

New ISFSI REMP Monitoring Locations Table E-I Haddam Neck E-3 Description of Change.

Radiological Changed number of TLD and bottom sexiiment locations Environmental Basis for Change:

Monitoring Program New ISFSI REMP Monitoring Locations

ACP 1.2-2.48 Rev. 2 Attachment 2 Connecticut Yankee REM/ODCM Change Request W.1 Section No. Section Title Pape No. Dscrption of Change & RPeson II F.l Report Content F-I Description of Change: z.

Added "ISFSr Basi for Cbange: I New ISFSI REMP Monitorins Locations 14 F.2 Annual Radioactive F- 2 Description of Chang.

Effluent Report Added statement that the ARER would include a table totaling and comparing doses from liquid and airborne sources to the 40CFRI90 limits.

Added statement that direct dose will not be routinely included in the dose assessment. An evaluation will be discussed in the Annual Environmcntal Operating Report Bash for Change:

Provided specific guidance on how to document compliance with 40 CFR 190 limits.

1. 1 Exclusion Area H-I Description of Change:

Boundary and Site Modified the figure to show the CY property line now Boundary for Liquid & runs through the 345 kv switchyard.

Gaseous Effluents Basis for Change:

The switchyard property was divided up between the CY and NU equipmnct.

2 Liquid Radwaste System H-2 Description of Change:

Removed RlTs Basis for Change:

Abandoned equipment

I ---

JUL 1 5 Z0U2 ACP 1.2-2.48 Rev. 2 At .hpent 2 Connecticut Yankee Change Request CEMJODCM

~2of3 nI. List the procedures and/or setpoints that require revision in order to implement the proposed change.

Estimated date for Name of M ger imolementa ti on IeoM ible to itrn 1emfent Pr 1) 7. - I 9# (rr l t mI.

Technical Reviewers:

Approve or disapprove

If disapproving, attach bases.

List tles/setpoints t req ir revision in Section II.

A-307M (Approve X Disapprove El ; /Lb

-7(/Bechtel BP/CH l s IDate ApproveoDisapprovc 0 -V3 71 on a dl bhe mi stry Lead Date IV.

Radiological Environmental Review:

Unreviewed Environmental Impact? Yes 0 No s (Bases Attached)

Approve 0 Disapprove :.6 /6 Oj 11eath Phy'scs/Waste Managemrent Oversight Manager Date V.

HC2lth Physics &Safe versight Review:

ea r,)b 9r '(0/05 Approve lDisapprove El 6(/Vo3 He ith Physics & Safety Oversight Manager Datc VI.

Comnjiance Review:

_1C12,/,, W jc Approve 3 Disapprove El _ 6 lt43 Regulato&Affairs Manager Date 12 of 13

JUL 15 2002 ACP 1.2-2.48 Rev. 2 At ent2 Connecticut Yankee I:OD CM Change Request P3 of 3 PORC Rcy Meeting No Approve 1"approvec 0 6o 6 3 PORC Chainnan Date Unit = Apoa: //,.-

n f g. Approve IA"Disapprove 0 Unit Manager Date Ix.

CY NSAB Approval:

(As required)

Al /1lA Approve 0 Disapprove 0 NSAB Chairman Date X.

Verify that the Section II procedure and/or setpoint changes have been approved and arc consistent with this Change RequesL Efftctive Date of e 7- / 7_0, t rand Lead Date Changc dmrdrini~sta4 gti on:

XLI./ # . a / Z 7 -§etC4s

--E# 6iGntal~anadaemistiy Lead Date XII.- - -' '

Change docente q Annual Radioactive Effluent Report:

Environmental and C mistry Lead Date I

13 of 13

JUL 15 2003 I .

.1

. I

, il-.-

I:

OFFSITEDOSE CALCULATION MANUAL For The HADDAM NECK PLANT Docket 4N6.50-213 - . -..

a I. .

'. .. t ,

ODCM --

Revision 16

I JUL 15 2003 Revision 16 HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL TABLE OFECONTENT Section Paae A. INTRODUCTION - A-1 B. RESPONSIBILIES B-1 C. LIQUID DOSE CALCULATIONS C.1 Method I C-1 C.2 Method 2 C-2 C.3 Quarterly Dose Calculations for C-2 Annual Radioactive Effluent Report D. GASEOUS DOSE CALCULATIONS D.1 Site Dose Rate Limits ("Instantaneous") D-1

a. Total Body Dose Rate Due to Kr-85 D-1

b. Skin Dose Rate Due to Kr-85 D-2

c. Site Release Rate Limits For Noble Gas ("Instantaneous") D-2

d. Critical Organ Dose Rate from Particulates and Tritium D-3 D.2 10 CFR Part 50 Appendix I Limits (Noble Gases) D-4

a. Gamma Air Dose Due to Kr-85 D-5

b. Beta Air Dose Due to Kr-85 D-5

c. Annual Air Dose Due to Kr-85 D-6 D.3 10CFR50 Appendix I Limits (Particulates and Tritium) D-6

a. Critical Organ Doses D-6

b. Estimation of Annual Critical Organ Dose D-9

c. Annual Organ Dose Limit D-9 D.4 Quarterly Dose Calculations for Annual Radioactive D-9

--- : . -,-=--EffluentReport . -

D.5 Compliance wth 40CFR190 Limits D-9 E. LIQUID EFFLUENT INSTRUMENTATION SETPOINTS

-- -- ---- -E.1 --Recycle Test Tank Discharge Line -- - E-1 Monitor (R-22)

F. GASEOUS MONITOR SETPOINTS . -- .- -.

F.1 Spent Fuel Building Noble Gas Activity Monitor (R-1) F-1 G. REFERENCES G-1 ODCM Tof C- I

JUL 15 20nfl?

Revision 16 HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL Flaure ure reTtl aa 47 G-1 INNER TERRESTRIAL MONITORING STATIONS -APPG"2 G-2 AQUATIC AND WELL WATER SAMPLING STATIONS APP G-3

.7,--.

ODCM ,Tof C-2

JUL 15 20MM

, Revision 16 HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL

-AEP.

Apendix 'AD -,e-n, ndGx Title ,,,

A SECTION C.1 -' METHOD I DOSE CONVERSION FACTORS B SECTION C.1 - METHOD I DOSE CONVERSION FACTORS BASIS C LIQUID DOSE CALCULATIONS - LADTAP (OR EQUIVALENT)

D GASEOUS DOSE CONVERSION FACTORS (TRITIUM AND PARTICULATE)

E GASEOUS DOSE CALCULAlONS - GASPAR-2 (OR EQUIVALENT)

F METEOROLOGICAL DISPERSION FACTORS G ENVIRONMENTAL MONITORING PROGRAM H DOSE FACTORS FOR KR-85 ODCM .. Tof C-3

JUL 15?MP Revision 16 A. INTRODUCTION Technical Specification 6.6.3, Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM), requires that Section II contain the Offsite Dose Calculation Manual. This manual shall describe the methodology and parameters to be used in the following:

1. Calculation of offsite doses due to radioative gaseous and liquid effluents.

'v 4

2. Calculation of gaseous an'd liquid effluent monitoring Instrumentation alarmnrip setpolnts consistent with the applicable limiting conditions of operation contained In .1..-'.

Part I of the REMODCM.

This manual contains the methods to be used In performance of the Control surveillance requirements In Part I of the REMODCM but does not include the procedures and forms needed to document compliance with'the surveillance requirements.

In some sections, several methods mnay exist to perform the required Control. Generally.

the methods are listed in order of simplicity and conservatism (i.e. Method I being the most simple and most conservative). , If a limit is approached, then more detailed calculations need to be performed. A more detailed calculation may be used at any time in lieu of a more simple method.

-r.-,--. - -

... .- - ,.: -.- . -' :. ov X-ODCM A-1 , , , , , I,,, ,,,,,,jf,

JUL 15 2003 Revision 16 B. RESPONSIBILIES All changes to this manual shall be independently reviewed and approved by the Unit Manager prior to implementation.

It is the responsibility of the Unit Manager to ensure compliance with all the requirements -->It of this manual. r;.

t' .

" ';.'.4 I .

'1 '

.t..$,

.-..t 4, ODCM .B-1

E_

JUL 15 2003 Revision 16 C. LIQUID DOSE CALCULATIONS Liquid dose calculations are performed once every 31 days to comply with Controls C.3.2 and G.3 of Part I of this manual. The basis for the Method I used to calculate liquid dose is explained In Appendix B. The methods described below use source terms totaled by similar dilution flows. For example', If. during a period, there were releases at flows of 3,000 gpm and 189,000 gpm, then 'dose calculations must be performed for each different dilution flow and then summed to calculate the total doses. Initial circulation water (CW) dilution flow must be maintained for batch discharges until 125 million gallons of river water Is discharged following termination of the release.

(Note: Method 2 can be used at any time In lieu of Method 1.)

C.1 Method I

a. Monthly Method 1 is used primarily for calculating monthly liquid doses; however, it can also be used for any release period if both the radionuclide activities and dilution flow are for that same period.

Step I Determine the total activity (Cl) of each nuclide released with the same dilution flow (ft'/sec).

Step 2 Determine the maximum total body and maximum organ doses by using the following calculation logic:

(a) For each nuclide from Step I that is in Appendix A, calculate its age-organ

. dose -contribution .(e.g. -Adult -Thyroid) by dividinu its activ'y -(C).by the

-dilution flow: (ft/sec) and then multiplying that result by each of-the age- -

-" ' -'m 3 :o Appe a:e-' franse

=21 DCFs per nuclide).

(b) Sum all individual nuclide age-organ dose contributions by age-organ (e.g.

Adult Thyroid) for all the nuclides in Step 1.

(c) Select the maximum summed total body dose for Adult, Teen and Child as the whole body dose. Likewise, select the maximum summed organ dose

.-- for Adult, Teen and Child as the maximum organ dose.-

Repeat Steps I and 2 for each different dilution flow, as required.

Step 3

, ', 11

. e -1_,1

'Sum the whole body doses for 'each different dilution flow to derive the total ..- v!

whole body dose. Likewise, sum the maximum organ doses for each different dilution flow to derive the total maximum organ dose.

ODCM *,:-.:.C-1 I I.' .'

JUL 15 2002 Revision 16

b. Quarterly and Annually Quarterly total body and maximum organ liquid doses are calculated by summing the appropriate monthly total body and maximum organ doses, respectively.

Likewise, annual total body and maximum organ liquid doses are calculated by summing the appropriate-quarterly total body and maximum organ doses, respectively.

Control C.3.2 of Part I of this manual specifies the following limitations and actions for liquid effluent doses:

The dose or dose commitment to any MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from site shall be limited:

During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Suosection F.3 of the REMM, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the remainder of the current calendar year so that the cumulative dose or dose commitment to any MEMBER OF THE PUBLIC from such release during the calendar year is within 3 mrem to the total body and 10 mrem to any organ.

If the quarterly or annual liquid doses exceed, or are expected to exceed, the limits cited above, then Method 2 is to be used to refine liquid doses.

This method uses the methodology of NRC Regulatory GGuide 1I.09 (Rev1) to

--. .. .-. _calculate liquid effluent doses. The use of this modeland its associated input parameters are discussed in Appendix C.

By design, Method 2 is to be used to calculate quarterly and annual liquid effluent

- doses for the Annual -Radioactive Effluent Report; however, Method 2 shoula be used whenever Method I is determined to be inadequate or inappropriate. Method 2 can be used at any time in lieu of Method 1.

C.3 Quarterly Dose Calculations for Annual Radioactive Effluent Reoort Detailed quarterly dose calculations required for the Annual Radioactive Effluent Report shall be done using the NRC computer code LADTAP II, i.e. Method 2. or an equivalent code implementing the guidance In Regulatory Guide 1.109, Rev. 1. The use of this model and its associated input parameters are discussed in Appendix C.

ODCM C-2

JUL 1 5 ?fln Revision 16 D. GASEOUS DOSE CALCULATIONS The determination of doses from radioactive gaseous effluents to the maximum off-site receptor are' typically divided: Into two methods representing different levs of .; r conservatism. All hand calculation approaches discussed below (i.e., Method 1) provide -

simplified,-conservative operational tools to ensure that effluent releases are not likely to cause quarterly and annual off-site dose or dose rate limits to be exceeded. -se specific dose factors used In'Method I are based on long-term historical on-site meteorological dispersion 'estimates as described In Appendix H. options and parameters that may be used are summarized in Appendix E. In cases where additional analyses can justify a more accurate determination of dose, a Method 2 approach Is, also listed. Method 2 provides for a more detailed calculation using accepted computer models along with historical atmospheric dispersion parameters, to demonstrate regulatory compliance. Method 2 can be used whenever the Method I estimation approaches a regulatory limit, or if a more refined dose estimate Is desired. Method 2 is also used for preparation of the Anrual Radioactive Effluent Report that Includes the quarterly and annual dose impacts for all effluents recorded discharged to the atmosphere during the year cf record.

D.1. Site Dose Rate Limits ("Instantaneous")

The Technical Specifications requires that the instantaneous off-site dose rate from noble gas (Kr-85 Is the only remaining isotope) released to the atmosphere be limited not exceed 500 mremlyear at any time to the whole body or 3000 mremlyear to the skin from the external cloud. With the abandonment of the Waste Gas Decay System and isolation of the Spent Fuel Building ventilation from the plant stack, noble gas release potential is associated only with ground level sources.

For tritium and particulates (half-lives > 8 days), the inhalation pathway critical organ dose rate shall not exceed 1500 mremiyear at any time.

-a. Total Bo'dv'Dose Rate Due-to Kr-85 "- '- -- ---- - -- - .

L- - , , ... ;. , _..

The total body done rate limit (500 mnrem/yr) applothe combiration o iaofalV~'

- ---concurrent ground level sources on site.

I For -round-level releases (i.e., all releases points other than the plant stack), the total body dose rate is: -

=309 *Q0 DFB

i ;,...

(mrem) p= - secC X Ci mrem - m3 yr p ~Ci-rn 3 ) sec ) pCi-yr

. E :, - .

where: * .. . \8; Q. = Total release rate (pCi/second) to the envi ironment of Kr 85 via . . - .

- \ > * .

ground-level release pathways.

. . s ODCM D-1 ,

., .. : . .:X,

JUL 15 2003 Revision 16 309 = Site specific total body dose rate conversion constant for ground level releases (see Appendix H for derivation).

DFB = Total body dose factor from Appendix H. Table H-1 = 1.61E-5 mrem-m 3IpCi-yr.' .--

b. Skin Dose Rate Due to Kr485 The skin dose rate limit (3000 mrem/yr) applies to the combination of all concurrent ground level sources.

For œroundlevel release points (i.e., all releases other than the plant stack), the skin dose rate:

Q *' DF;.

(r ) (1 Ci (mrei -sec) where:

QC = The total release rate (pCi/second) of Kr-85 from all ground-level release points.

DFJ - The combined skin dose rate factor from Appendix H. Table H-1 =

4.20 E-1 mrem-secl/Ci-yr.

c. Site Release Rate Limits For Noble Gas ("Instantaneous")

The site noble gas dose rate limits (500 mrem/yr total body and 300v mremlyr skin) apply to the combination of concurrent effluents from all releases points, and are

- --directly- related to the radioactivity release rates measured for each discharge point.,

reBy limiting gaseous release rates to withintvalues wich correlate to the above dose, .

Byate limitig gaseusreleaserates toat the sit evMuent control dose rate its are o -. -

exceeded. Since the only remaining noble gas isotope is Kr-85, the above dose rate

--equations-and site dose rate limits show that the skin dose is the limiting exposure --

pathway.

The instantaneous noble gas release rate limit from the site shall be:

7,143 where:

Qg , - Kr-85 release rate from all ground level sources ( ' ;

Clsec).

7,143 = The Kr-85 release rate (pCilsec) from the groundlevel' sources equivalent to a skin dose rate of 3000 mrem/year.

ODCM D-2 . . .

JUL 15 2001 Revision 16 As long as the above is less than or equal to 1, the dose rate from Kr-85 will be less than or equal to 3000 mrernyr to the skin (and 500 mremlyr to the total body).

d. Critical Organ Dose Rate from Particulates and Tritium -

A .- '

The critical organ rate limit (1500 mrnemyr) applies to the combination of the plant stack releases and all concurrent ground level sources. It includes particulates With -,-

half lives greater than 8 days,' and tritium (Iodine-131 and 133 have been removed: p from the potential source term due to decay). Results of gross alpha analyse shall be considered as Am-241 for dose calculations. Dose rates from all concurrent !

T

'P ground sources and the plant stack are determined independently, and then summed to obtain the overall critical organ dose rate.

(1) Method I For elevated (mixed mode) releases from the plant stack, the critical organ dose rate to the maximum off-site receptor is determined as follows:

D5(o,) = Z ( .DFG;*E) i (mrem) y(.Xi (mrem-sec 1-1=11-I ) IO-Y where:

kro(e) = The off-site critical organ dose rate (mremlyr) due to particulates and tritium from plant stack releases;

-.- . IThe release. rate (,pCi/sv ond) of radionuc'ide fir (i.e.,._ 7

.. -.total activity measured -of radionuc!ide 7 averaged .

- :over-1he-tmec-period--forwhich-the-filter sample -~---=:

collector was in the effluent stream (plant stack).

DFG~v(E) = The site-specific critical organ dose rate factor for an elevated (mixed mode, plant stack) release (see Appendix D. Table D-5) ( em pUi -),

ODCM D-3

1 5 2003

-JULRevision 16 For ground-level releases (i.e., all releases point other than the plant stack), the critical organ dose rate to the maximum off-site receptor is determined as follows:

=~A XQ . ,.~

).r ;;e (mrem) I-I-IC(

where:

w = The off-site critical organ dose rate (mremlyr) due to particulates and tritium from a ground-level release.

= The release rate (pCi/second) of radionuclide jig.

DFG,',,g,I = The site-specific critical organ dose rate factor for a ground-level release (i.e., all releases other than from the plant stack)

(see Appendix D, Table D-5) (eni - sec foi-. - .

Note: For ground-level releases from other than a Temporary Tent Exhaust, the ground-level DFG values may be decreased, if desired, by multiplying them by a correction factor applicable to the specific ground-level release point being evaluated. The correction factors are listed in Appendix D. Table D.4.

--- - ~~-- - (2) -- Method 2--- -- ----I--

-i nece-;sary,-dleterm e maximumn organ doer tefrte TeUdMix of`-- - -"-

particulates utilizing the GASPAR code (or equivalent code model that

~-~--- ~--~---implements-Regulatory -Guide -1.109, --Rev.- dose-equations -and --maximum---

individual assumptions) to estimate the dose rate from tritium and particulates with half-lives greater than 8 days. For the identified radionuclide mix, dose rates

-- by critical organ and age group should be assessed to determine the limiting organ dose rate at the maximum exposure point offsite.

D.2 IOCFR50 Appendix I Limits (Noble Gases)

Effluent controls limit the off-site air dose from noble gases released in gaseous effluents to 5 mrad gamma, and 10 mrad beta for a calendar quarter (10 and 20 mrad gamma and beta, respectively, per calendar year). Effluent dose calculations are calculated at least once every 31 days. This part of the ODCM provides the calculation ' r.

methodology for determining air doses from noble gases. .:

ODCM D4

JUL 15 2003

- ' .. 'Revision 16

a. Gamma Air Dose Due to Kr-85 :, ,

-'Forgroundlevel releases (i.e.. all release points other than t plant stac),th ,,

.\gammaairdose Ls cal ated: ' .. ' . ... ,

~D d.06Q DFY ~ a~ i .. '.

-L:X

- S1~4 w6'whre:

'- ' Qg=

'9.8E4-6=

DF-.7. -.

Total quantity of' Kr-85 (jiCi)-'released from the: grounll -#A release points (all release'pbints other than the plant stack) during the period of interestt Site speaicma aird releases. See Appendix H fo i cvs n.

c nstant forgroun level I

DFr Gamma air dose factor for a uniform semi-infinite cloud of Kr-85 from Appendix H. Table H-I 1.72 E-5 mrad-m3 IpCI-yr. '. . .

b. Beta Air Dose Due to Kr-85 For ground-level release points (i.e.. all release points other than the plant stack),

the beta air dose is calculated:

-e ; ;- w~)=(9.8E-06).(,).(F')- ,; - :'

(rd ( pCi-yr ]

((nr~zd-m'Bm (mrad)tpCi-rn j p where:.-

DFB = Beta air dose factors for a uniform semi-infuiite coud of Kr-85 from Appendix H. Table H-i = 1.95 E-3 mrad-M IpCI-yr. .. .

,i,- ,- -9.8E-6 = .- Site 'specific beta air dose~conversion constant for ground; ',;..C.;.

level releases: See Appendix H for derivation. - . ,, ,

.- ;.. Quantity -of Kr5 (CI) 'released from the ground level ',

'-. '-'release points during te period of Interest. - .. .. >

M . .. ;

a-"; .4 : ':t.' ^' ": :. ' ' u' 'v S"'-'< f 00~~~ O D M . 40

I JUL 1 5 2003 Revision 16

c. Annual Air Dose Due to Kr.85 Determine DYA4 and Dyzq which equals the gamma air dose and beta air dose for the calendar year as followsi... ' ". - - '. - '; '

where the sum is over"th'fir quarter through the present quarter ioses.-'.

Ra@S\X$T"vw

' 'The following should beused as D& and D i . ."

'A - ue ueiaieuquaren dose calculation "required per Section D 5 forfr; th

't .*.9 -f"().'.lfth ie

,the Annual Radioactive Effluent Report are complete for any caender

-quarter, useti results. -

(2) if the 'detailed calculations are not complete'for a particular quarter,-".

',' .;' use the result as determined above in Seton D.2.a and b. - .

D.3. 'I OCFR50 Anpenglx I Limits (Particulates and TritIuN)

Effluent control requirements limit the off-site dose to a critical organ from tritium and particulates with half-lives greater than 8 days released In gaseous effluents to 7.5 mrem for a calendar quarter'and 15 mrem per calendar year. These dose lirmits '.".4-apply to the combination of plant stack and all concurrent ground kvel sources. (lodine-131 and 133 have been removed from the potential sources term due to radioactive decay.) Effluent dose calculations are performed at least once every 31 days. This part of the ODCM provides the calculation methodology for determining critical organ doses from atmospheric releases of tritium and particulates. Results of gross alpha analyses shall be considered as Am-241 for dose calculations.

a. Critical Organ Doses . -,

_ (1) Method1a I ,a , -,

,__':,-n ,n -l , ,a ,h~riia ,o ,_ :^ **

Foran -elevated .(m-i o e;le'sfnro 'the pnt b'c t critcaiogan dose__

-- -- a relea-seperiod of interqs-t (sulch'as 31 days,'quartery,'etc.) at thepostulatedJ - -'"'-

during

, rmaxdmum off-site receptor location can be calculated from:

_ ...- ---------- - -DFG- -

(mrem)=

where: - : - -

--. - -;,- toal activity in MCI of radionuclide Yi released to',-:

' tmospnere i', the elevated (,ixed m -

~~~~O~~rrelepse: point(pat.sck din

. .finterest. '.

DFGw,) -Te site-specific critical organ dose factor for O-,,,CM: .. , radlonucIide 1i" arnd the elevated release point, based '

-, DCM,,W'-'--;-

0-JUL 152003 Revision 16 on the'age group and organ with the largest dose

~factrs(se Apendi D, Table D6)

J ru _or,,..-

d1ie iee 6i-i."~a 'rfelese ,points, otheirtthanIib jheplnt -ia h '

et anatth oItret(suc as 31das quarey

"".btc atItpo0stulated imilidmum off-site.'re e-p-tor location lis alculted:

where: .~.

ah~tmosphereit In jCidof radionuclide or released to the perodphof from" ground1-level release ~points during the proofInterest".

DFGkqg = The site-specifi riia organ dose factor for radionuclide i" and ground-level release points, based on the age group and organ with the largest dose factor (see Appendix D.Table D-6).

Note: For ground-level releases from other than a Temporary Tent Exhaust. the ground-level DFG values may be decreased, if desired, by multiplying them by a correction faictor--ap'plicable to the specific. ground-level release, point being evaluated. Thecrcto factors are listed InAppendix D.Table DA4

':7~ 7-* 7: 'n W4.I

-It ODCMD-

__ M ___

JUL 15 2003 Revision 16 (2) Method lb (For ground level releases only)

With the elimination of the waste gas system operation as a batch mode release..*,.' +

source;:aniadditional dose'equation ,has been provided for the'situatonswhere,,

rouLti 'discharges'are 'Impacted with an identifiable short duration r'leaseof.', - '

particulatefradioactivity.,sucti as the breakthrough of 'actiyona temporary,

-l HEPA filter used during 'ismantiement activities. .Theime-adjusted XIQ valhe- ,

-; provides additional conservat sm to the dose calculation by substituting a short4 3 teriim XJQ estimate for thei`tandard annual average value(gr evel reli#ease's .

-'only). he time-adjusted MetIhod dose equation' for Particulate and Trltlum;3',

releases is'.,

D,) 9.864 -s2 OD-G

X(Qf)

.~~~~ ; ~ ~*. ~ . . *.; .; - I i--*-

where:

'Dio = The maximum critical organ dose from particulates and.

tritium accounting for single event short duration discrete release. -

9.86 = The ratio of the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months depleted X/Q (2.89E-03 sec/m3) at the maximum receptor location to the long term average (growing season) depleted X/Q (2.93E-04 seclm3).

= A unitless adjustment factor to account for a release with a total duration of "t hours.

= The total activity in pCi of radionuclide i released to the

-- - --- atmosphere during the short teem period of interest.

I

_- '--7'-'h- -. ,e sit;esp-eic.ic itical organ dosofacor-for 'adionucde

, based on the age group and organ with the largest dose ,

____,,__,,____ -'-factor (see Appendix D,Table D.6).

Note: For ground-level releases from other than a Temporary Tent Exhaust,- the ground-level DFG values may be'decreased, if desired, by multiplying them by a, .

correction' factor applicable, to the specific ground-level release point being .

evaluated. The correction factors are listed in Appendix D,Table D.4.

.a ,t ., .- - . -...* .

(3) Method 2--

The maximum critical organ dose can be calculated utilizing the GASPAR code -' ' t,@

(or equivalent code model that implements Regulatory Guide'.1.109, Rev. 1 dose ., 4"

':"equations and maximumindividual assumptions)-toestimato. . dose ,

tritium and particulates ithiiaN-lives greater than 8 4ays. The dose to the A critical organ and age group should be assessed using the most recent land use ,Th%-

census data to identify which exposure pathways need to be considered at actual receptor locations. Doses from vegetation consumption can be neglected dunng '>'. -r

ODCM :'~~~~-

, D-8 ,. , . .'; . 'I ,t'* t ' y

J U U-eb',Is~r'l the 1" and 4" quarters and the doses from-milk consumption can be neglected .

during the first quarter since winter conditions eliminate the out door growing of vegetation during these'Ume frames.

b.'tEstimatlon of Annual Critica O nD

, - ', 3'.

ii.- o b-.

The dete'rlnathn'of the'annual (cailendyear) 60ti6cal organ dose, from titlrnn

.. . .1'- and paOlat eieased Ingaseous'euents I the s presentc uaort o te m um organ.,' : -

the frst q r to c.'AnnualOr-anDo IsimIt ' k..F / .... .

Determine Dyowhich is the mmum organ dose for.the calendar.year. as fogows:

e the

,D sum oer fir quarter throug the present quarter, .i dosestothemaxlmu .;

',, . i ',, ,, ,.> , ,, ,... ...

D.4 Quarterly Dose Catcutiatlons for Annual Radioactive Effluent Reoort Detailed quarterly dose calculations required for the Annual Radioactive EMuent Report shall be done using the computer code GASPAR (or equivalent code implementing Regulatory Guide 1.109, Rev. 1).

.D.5 Compliance with 40CFR190 Limits The following sources should be considered in determining the total dose to a real J.

individual from uranium fuel cycle sources: .

a. CY gaseous effluents (doses calculated inSection Dabove).

. b. CY liquid effluents (doses calculated in Section C above). , -

c. CY direct radiation from the site.. Based on ERCf1G03 ER 9"012 direct'dose wiV r..-t-be-routinelyincluded in'the~dose'assessment.-Afevaluation-of the direct dose aspect wil: be discussed Inthe Annual Environmental Operating ReporL This

evaluation will include the dose recorded on control TLDs and TLDs located near -

residents. If an evaluation finds a significant direct dose Impact, information about the dose impact will be included In the 40CFR190 limit evaluation.'

d. Since all other uranium fuel cycle sources are greater than 20 miles'away,'they need. '

not be considered. . . ,

ODCM : , . D ....

JUL I5j nn,,

Revision 16 E. LIQUID EFFLUENT INSTRUMENTATION SETPOINTS Control C.3.3 of Part I of this manual requires that the radioactive liquid effluent Instrumentation In Table:C.3.3 have alarm setpoints In orderto ensure that the limits cf Control C.3.1'arenot exceeded.;' Control C.3.1 of Part l'of this manual 'requires"that the '.

concenhta on _of radioa jateal released .fromhthesite ;shallnot exceed t 'not " '

.'... -:.concentirtons'specified In 10 CFR Part 20, Appeidix B;.Table lI, Coumn 2. Cneicut Yank'ee uises'MPC values obtane fr'm 10 CF n In.eohtoR -ar22r)soplrt~n,94 E.1- Recvclo Test Tank Dlscharao'Llne'Monltor (R-22) .:.-:K!9.... .i ,.'.-ti

-The'RecycleTest Tank efuent monitor provides alarm and automatic termination of release 'prior to exceeding the ,concentraton limits. Normally the setpoint for R-k2 Is' at twice gamma the activity In'the tank to released. This v erifies that the sample.

results used Inrelease calculations were from a homogenous mixture..

- .'.-'Theilamitrip, setpoint Is determined prior to each batch release taking Into account.:

.. current values for'each ;variableparameter. The following steps are-used in determining the monitor setpolnt.:

Step I Determine the maximum allowable discharge flow (Fmax) in gpm, at which the test tank can be released. '

Fma= Fd I C, where: Fd = The actual or conservative estimate of the flow out of the discharge canal (gpm). The flow for I Circulating Water pump,:'-.

is 93,000 gpm and the flow for the Service Water system Is set

- -- Activity .,concenton =of ---each --radionucliidee- T 7((iC1&mi)`

determined to be In the test tank. This Includes gross alpha,

-Tritium, Fe-55 and Sr-90 either measured or estimated from the-- -'-

most recent composite sample analysis.

MPC; = The concentratin limit (uClmi) above background at the point

-, of disharg'e tothe'environment for radionuclides i'. taken from' 10 CFR.Part 20 Appendix B. Table'll, Column 2. For Gross..,

'Alpha'usie'thei MPC for Am-241.

,..-,,The selection of the actual discharge flow rate (Fm) from the test tanks compared ,tog,

>'~ - --.. iamum

'the allowable discharge ate Firm must satsfy the follong: ' ;. '- '.'

FMV. A, ODCM :, . '. El

JUL 15 2003 Revision 16 where: AF = Administrative 'Iiiiting factor. for the maximum allowable discharge rate.(usually between 0.1 and 0.7). This factor Is..'

conservative and will account for ongoing releases from other. ,

-sources tand. the presence of beta emitters .that cannot be '

detected by the radiation monitor. - .-

'-.If Frnax x' AF...Fm..hed..re.lc ,' 1sharge _ rate. inca ilutilow

' reproces ta=nksto'lwer actityi rep. ,

lse.¢ "-'-

i'.0

- .i

r. . -j.

i.6;*6it;;i;.

. ..;.;. te 3 7 : s*

C v*>vi~b~~b,/@ tS-SS-'-' 5

' .:Determine the'rm'onitor response: (Rm). In m.correponding o t t e tota i

concentration of gama ernitters.,

Rm 2 E - . .

'A;: - =xx

.where: E -- ; .Current monitoreffidency (cpm per ,uCrml) ,,

Aga m= Total concen1tratIon of gamma emitters In the tank (I Isotopic analysis of tank does not identify gamma emitters use 5E-07 jiCVml (LLD requirement) for Agai. -

Step4 Determine the limiting monitor response (RP) in cpm. The limiting monitor response is the calculated alarm setpoint at which an administrative MPC concentration limit would be exceeded.

Ram E x Anpc x (Fd/ Fm) -

where: Ampc Administrative MPC assocated with assumcd worse case mix of nuclides in accordance with 10 CFR 20 Appendix B, Footnotes.

.t D * - - *. - - ~- -- X Step 5 ;--~-'-s'-t

-.-.- Determine-test tankdischarge monitor alam etp () p, ee

-B Background count rate of monitor (cpm).

If RmrB > Rm, hen reduce dischargeflowrateincreasedilution flO ,or reprocess tank to lower activity levels. .

-.- If 2x B > RMm, - Then decontaminatermonitor -

-If Rm > Rm+ B 'Then If Rn > B. Then S Rm + B . .

- Else S= 2 x B

> At no time can the monitor setpoint (S) be greater than Ru -. ,

z: ' . ' '. . ','- .' -. , , ' ; ' : ' - .. ,., - .J<' .;' ' ' .'9*5

'00CM., E2

JUL 15 .2003, Revision 16 F. GASEOUS MONITOR SETPOINTS F.1S Fel Buildinc Noble Gas Activity Monitor-(R-1

'1t i.

,..As iAkscssed in D.1 .c','Site ~Release fimits~for- Noble',Ga (Insatnos) h skin'dose rate of 3000 mnrefii~ear isthm1Ung al e2,With thefulsoeinte -

Spent Fuel Building wth ain Irieedn vnia~ ytm teol oreo R-noble noR eesactivity gs gas monltorf{T&SB nbl i h petFe Buildi ngbwhichs besttoalar befre the release rate exceeds'%ofthislil.

..-R-1,Setpoint = 7I300*O5 7 .0012 cpm 9000*1.2*12.83E4,:,

Where: 7143 =the Kr-85 .slease rate (pCVsec) from the ground-level sources:.:

- . equivalent to a skint dose rate of 3000 mreirnlyear (see section Mix.).

0.01 I % factor applied to the dose rate limit.

60= seconds per minute conversion factor.'

5E7 =conservative radiation monitor efficiency for Kr-85 (cpm/pCVcc).

9000 cfmn nominal Spent Fuel Building ventilation flow rate.

1.2= a conservative factor applied to the ventilation flow rate.

2.83E4 =cubic centimeters per cubic foot conversion factor.

bDC F..

JUL 15 2003 Revision 16:

G. REFERENCES

1. -Health Physics Technical Support Document, CY-HP-0029, HEPA Units -

-Environmental Release Evaluation;.-,-.

- . '- -4 ' -. , ' , --,-;;j

-2. ,C Me'orandum HP-9 108, Justification To Eiiminate HEPA Unit Ehvst ,'

Airborne RadioactySarnpling BaedOn Wor cation Cntainat Levels-.

- -3:.. :- '. CYCacuatonREODM-01

~';'. 68SY~00, Connecticut Yankee Haddam Neck -. -e@:z

'. Facor.

'ntODCM,pris 'n

34. CY Calculaton REMODCMM01686-SY-00, Connecticut Yankee Haddam Neck" -,4 Plant ODCM,;,Terrain Da i otaors

-5. 'CY Calcubtion REMODCM-0168 Y00, CY Defueled State- ODCM Dose ---

- ~ - Converson Fact rfor' Gas'Releaes.'-;'

6. CY Calculation REMODCM-01689-SY-00, Connecticut Yankee Method NDose Equatons forO DCM Revision 13.

7. Northeast Utilities Service Company Document Trdnsmittal CY-DE-DT-002t-97, - t Spent Fuel Island, Resorcon Inc. Operating Manual ' --- ,t'

8. ERC 1610CER-99-00C1, Input Data for Offsite Dose CalcutCtion D -

9. DCR CY-98 042, Spent Fuel Building Ventilation. '

10. sn1 ER 610cER-99-012, Basis for40CFR190 Doses Used to Implement CY-REM ODCM.

11. ERC 161C0lEt R-E0C0004,'Techncal Basis Document Radionogical Etoironmental Monitoring Program Reduction1.Revision 1, Dated 6112/2000.

7.1. VeN0ortesUtltie01,s SEs m it -DE-DTi02sa97 j'. _

~-- -Factoefr~-fi nsumptonsu ... - '. po ~ ' 'E ' ' .'^S.' p

___j13._ Sendor/CYt Fulclanton No. CYOESGp01et01, Mndal Dilution Flows for Lquid -- - -

Release Dose Calculationp. Dt f O RECIDC. ..zDs C

. - su.pti.o'.C-Y)

-Fcofo~s - . 2-.- .'.-..-'ti';

13,,.'.

V.dr:~~lulto N. - .TdlDlto YEG011 . -. - FosfrLqi

- .iC.', ' :

Relea..

Do.

.::se -se

- ., .: ,..8

4 . : - : :, : . - . ...............

- f' ; 4. - - ' . 7- - . - .:i' .. , - i -

--'ODCM 'G 1;1~'"' --

- ... ..... ..... - H ;...,.~. :...........: : ... ....... ......... : . .

JUL 15 2003, Revision 16 SECTION 0.1 METHOD I DOSE CONVERSION FACTORS IL2-90 -it-oxJPSpOi .. Cwnm Fadu umOrp $M."

111.1 4114 as614 71.1 , 86141 2M31.0 103ma a"9.3 :181.2. 14730 810 t231.0D 5.2714 . 1102 1710 110 '22751.0 163.02 2221410 I111.0 fg.1641 .1161.1 117141I-219141 *0171. 424901

721431 66561-61.30O 4CM1.. mo,0tu.1390,142iue001 32E-00 64SNO40 24MOO4 140431. 8 200 682146.245403256100 243

-0204 422214 :221430 2221.0 A; 22243 IL4 2143E 204 & .o1041 200 510 20140 13 14 .-

16I34E-U*6325137.14 ~f0 .21914 7.1561. M15143 419402 SNOOD f6$.'l.0 S659101 307141 &165140 $071.00 4241410 256140 2231402 2651401 7461.0 194140 7461-0 3601Jil 1251.01 1.171.01 A 131.01 1121.01 11.1514 112101 3241-00

3021-01 S 151-M01 5611 3821-01 1302l 321-01 4271400 6E1 I 166OOD 27?1.O0 8 6001Z-0 SO.1 I OW01 127141

3 )6141 34)141 37r21.01 316141 236141 I161491 643-14 2001403 70614 321143 1071401 225143 6651WOW M111 4031403 5351403 1871403 150141 I183143 7201.02 90K061 21614-1 211141 219141 217141 211"FM 117t1) 215141 19611 8341181

-0 1 I' 044 O914 181 4334 75K141 6861.0 65831.01 6761.011 70614) 676.14) 43614 676140 4 TK140 112100 OM2-069 02E46 104140 206140

-. 00014O0 t171143 17,143 171143 I 71143 1.711403 1711.043 220140 44414 1 1R0611 2 2M010 14541 220140 337014

3611423 X2564 3 59123 259143 256143 15614232561400 1311 40 601.1 6651.01 6471-1 1SW140 £07"4 3 4221E

I WOOD0 12740, 140E14O 1327140 1.17140 1.43140 2751400

- 352140 3247140 246140 24714-0 30471w 3351tW 282140 5314n02 1.1614 26614153010 251*43 ,165143 .. 556143

-MO 2 3O231.07£fl1.046S7900, arM.04 IL 14" 6 73146'-2 ra14 4 MEOW461437J61M4 IN1014 709143 '. 81[45 711430 I25t~-*

-. ~ ., 1l140-11140--11740 1)710 3.161400-174 -830 263140' 226140 2011401 4101-0 121140£101 524 76043 791M43 6 -274 62614 £561366- 174 I16SO0 3561.01 513.01461 1604 1691M0 I510 O714

. 4S461.11.141400.255140 _44M141 4461.0 £46W1.0 -___4.. O --

2614-3 £83143 126143 1731I4890 151. M66102 27714 O.E50613,454143 .722E342 a336100 156103 151430 28614 O

... ,--.,1231401 1122141 1221401 1221401 1 23*14-1 t2X141 157-14 112141 1661 OK 0614 106141I O 1591 O41 I1OK-41 200C41 . .

4r7(01 ~16101[4 265101 3 -01 406146 01~-011 171141 8710 Oln- -4719*00 14400 S61-06 5061.06 .266140W I£701-010 .1OM I41143 1411-03 141143 141143 1411143 I41143 123140` 2 42.14 10014-1 1231400 1061.0$ .523140 28M014, 2041432 2011I43 201143 2011143 28-1143 201143 16)11c 1241400 1601.041 4521.0 3401-01 156140 3 AM41 144141i I5114I '76I1-01 7661.01 76714) 7671.0 6146141 13MOO 20014.0 A65140 .164 1NODM0 614 1614 1m-o 614K0 266140 7634 LI t15141 32429-14 1 1.11141 I IM602 M432 :236543 -~ .

26443428.66: ,361 0 142643 0421143Ž 4264B 7.

-ODCM: .-. jAPP A4I

JU%1.5 2Q8 ,,'

SECTION C.1 - METHOD I DOSE CONVERSION FACTORS BASIS -

E~~, -. , .& t Refer to- memorandum RB-98-069, - -subject: Verificatlon: of,;Ui6th PCLADTAP'lIt .Excel F

.Spreadsheet in Support of the roposed New CY REMODCM Method -1 Cadcluat~on for Liqid , , j

'- .EffluentDoses, 'Mrch 27,'1998 for the Method 1,lquld effluent dose J bs.

1aculanba"'t i

h '-basissubstantes the,,,use ( u fow " (2)w- a d

-compositem radlonucldeiage-organ dose conversion factors (DCFs)-(drldfrom 'the NRCI i L;ADTAP II software program which"conforms to' Regulatory Gulde 1.109) to calculte age- -

organ doses. -These composite". DCFs Include the contributions from aN pat Ys (incuing -

pathway age usage's':and radionuclide .age-organ"'DCFs) and 4ADTAP.. II site-specific .

parameters, and are'acceptable because LADTAP II is used for Method 2.- '

; . 'k. '-,.

- . , ;. .. ,,i:

V' ' "

ODCM - - ODCM APPB-1 -

- 0

.JUL 15 2003

~Revision 16 LIQUID DOSE CALCULATIONS - LADTAP (OR EQUIVALENT)

The LADTAP, codes .wr rlt~by the, ,NRC ,to ,compute dosesfrom liqui reeases.1-che-actual model sed In LADTAIl hcpefm calculatons In accordance wt eg lt, Guide 1.109,'Re&lson' 1. &X" c.. . . '.

For cau danr-a,-iown,.p

1. Real time, measured dilution fow.

2. 'Fresh water site,~no re~:concentratlon'.-.-

3. Shorewvidth factor 0.1 frdshre aa

5. On-hu discharge tasttimne'- appro'ximate time to reach ~4canal length.

1.6. Regulatory Guide 1.109 usage fctors; for maximum Individual for fish, shoreline, swimming and boating

,6.Zero usage for shellfish, algae, dninking water and irrigated food pathways. Shellfish.

algae and water are not consumed from the river. Bottled water isprovided onsite. The river isnot used for irrigation ODCM 'APPC-

JUL 15 2003 Revision 16

.6TEDIX

.GASEOUS DOSE CONVERSION FACTORS (TRITIUM AND PARTICULATE)

-.This appendix 'contalns a listing ofieosad dose rate conversion factors (DFG and DFG' ~

fo ueinhepliato o teCYODMduin hedcoinmIssloning phase othplnt The DFGsaefr aeosrlae to'the atophere of triiu ad particulate radlonucidesd n reflect the fo~llowingconditions: j~ -j~

(a ~ On{ron rcetrs2 t h dcosest 'distance' to te~sitebounidamy.(SB) 1for...

~ roud-level 'releases:~,~'ind 2at the' worst-case ofslireceptor for" elevated,-

,releaises, *

(b) Log-lived radionuclide (in view of the extended decay time since permanent plant shutdown on July 22, 1996),

(C) .The Inhalation 'pathwayfor dose-rate calculations, and all pathways combined for.

Odoecalculations (ru-siinatometIgstion, goat milk Ingestion,

-and vegetal neto) n d) The 'associated worst-cazse hypothetical individual (dlteenager, child o Infant) and critical oran(Total Body, GI Tract. Bone, Liver, Kidney. Thyroid.,

Lung, or Skin).

The DFGs were computed using the GASPAR-2 computer code aogwith site-specific:

atmospheric dispersion and deposition factors. Details on the basic data and assumptions employed in the derivations of these conversion factors are presented. In Section DA1 and the final tabulations are presented in Section D.2.

D.1 Basic Data and Assumptions (a) A total of 32 long-lived radionuclides were selected for computation of the DFGs. The list includes tritium, 1129, and 30 other particulate radionuclides.

(b) Use was made'of the GASPAR-2 default built-in data libraries for physical parameters, transfer data and usage factors, with the following exceptions (which were implemented

_ for consistency with Reg.,Guide 1.1 09() ___

- -666Th cumltifon time for ground contiminatiohictb) washangdil frm20 y~e'ar's --

to l5 years

.2. ___The transfer rate to meat pro6ducts. (F5) for Ni was changed from 5.3E-03 (cl/kg) to 5.312-02 (cl/kg)

3. The transfer rate to, goat-milk (Fm) for Fe was changed from 1.3E-03 (DIL) to

-- -1.31E.-0(DXL)

(c) iThe pathway parameters were assigned the values shown in Table DA1 [from GASPAR-2, with the exceptions, identified under.Item (b) above).

(1) - GASPAR-2 -,A Code System for Evaluation of Radiokogical Impacts Due to fte Release of Radioactve:. P Material to the Atmosphere During Normal Operation of Light Water Readors, Oak Ridge Natlon~aI Laboratory. RSIC Computer Code Collection CCC.463 (also released as NUREGICR-4653. -GASPAR-11 Technical Reference and User.Guide.* March 1987)

(2) 'NRC Regulatory Guide 1.109. CTalculatlonof Annual Doses to Man from 'Routrine Releao ot ec' r Effluents for the Purposeof Evalutn Copiance Ylth 10 CFR Past 50. Apoendix r, (Rev. 1.10.77)

ODCM APP D-1

JUL 15 2003:

Revision 16 '

Table DA1 VEGETATION INGESTION

'PATHWVAY:PARAMETER :-:--:~.i' PATIWAY;

p. . II t .St Agricultural Productivity (gn)..'

Soil Surface Density (kg/n?)! -z 240.24 Transport Time to User(lrs)~'- NA !NA;, I Soil Exposure Time (yr).<' 15 1

'Crop Exposure Time to Plume (rs),-,, -1440 1440 Holdup after Harvest (bns) .7y.- - ;-, 336 -24 Animal Daily Feed(kgfday) ,.; .. 7< NA' NA

-GOAT-MILK INGESTION PATHWAY PRMT PATHWAY

__ _ __ __ _ __ __ _Pasture Stored Feed Agricultural Productivity (kg/rn) .0.7 2 rV-

.7 ,_

11 Soil Surface Density (kg/rn) 240 240 -,.0.: Zr.

V Transport Time to User (hrS) .48 4 Soil Exposure Time (yrs) 1581 . "I.

1, A, --

.- . ,f.:

Crop Exposure Time to Plumne (hrs) 720 1440 Holdup after Harvest (hrs) 0 2160 Animal Daily Feed (kg/day) 6 6 PATHWAPARAMMEAT INGESTION PhWAPAAETER PATWAY Agricultural Productivity (kgfn?) Pasture___ 2trdFe SoilSurfaceDensity(kg/m 2 e)--.--- _ ------ - 2420 240

.. , --- -.Transport Timeto User (hrs), .. .. . 480.-- , . 40... -

Soil Exposure Time (yrs) . ~- -15 15 Crop Exposure Time to Plume (hrs) ~.720 1440 Holdup after Harvest (hrs) . 0 2160 Animal Daily Feed (kg/day) 50S [ S ODCM AP -2

JU.%V1.5 7' I.i 1.

(d) Site-specific pathway variables were assigned the following values:

Absolute humid ity.' . . ... 8.0(/ 3 Fraction of time leafy rown geeabe :.. 05

-'Fraction of gniiua from srwn: 07 indiidul vgetbleconumpIonq home gardenr 076 Q ratoiof Une-milk goat ar aon pastue -0.75 /

-Fractionof goat feed frmompatui-'re: !~,-- 7 1.0,-'

-Fractoion f tmebeefcattle are on-pasture11:"-.-: - ,,e. *"", j- 0.75 Frcin of beef-catl feed6 fro "astze ~ .

[Nte: ,The cow-milk pathway ises estricveta the goat-milk pafthwaypran was not

-used In the definition of the fina FsJ ~ ?.*:

(e) The usage factors and breathing rates are as listed in Table D.2.

ItTable D.2 .. * .. ,.

-Ingestion Pathwiay Usage Factors Inhalation Individual __ _ _ _ _ _ _ _ _ _(m I r Crp -Leafy Milk .Meat (kglyr) Vegetables (liters/yr) (kg~yr)

_________ ________ (kyr) _____ ___ _____

Adult 520 64 310 110 8000 Teenager 63 42 400 65 8000 Child 520 26 33 13700 Infant 0 .0 .. 330 0 . 1400 .

f) The applicable site-specific long-term atmospheric dispersion and deposition factors are*

presetedJn Table D.3. It is. noted~that. there are four. distinct release p oins a C ---

~Wh~h ~fibla~ rondleelreleases.' j'he-Values;Z-n-.TabI D.3 are 6rthe

~wort~asrelda's-e p oint. +i-:

.4, I, -

.. 4'>V -

- .*****J,'i ODCM . .. APP D-3

'., 2- ,

JULRevision 15 2003 16 Table D.3

RELEASEPOINT ,,-

. 1 Undepleted (X)

(seclm)

Depleted (XJQ)

- (seclm 2 )

Deposition.

i. Factor .

- (DIQ)A(m5)9 *>

Ground- - TemporaryTentExhaust Level (worstase release point)

I . .

'3.09E-04 - 2.93E-04

222E Releases 4 ____ `-

Elevated Primary Vent Stack 28;E- ; -2.85E05 ;--.3A5E-08 :

Releases

- - j I i D.2 DFG Tabulations '

- The DfGs for tntiurn and partculate radionuciides were computed through use of GASPAR-2.

along with the data and assumptions listed In :Section D.1. Summarnes'of the results are 'i---

presented in Table D.5 for the inhalation pathw.y (dose rate calculations), and Table D.6 for all'.:

pathways combined (dose calculations).'. - -

It Is noted that the DFGs for ground-level releases were based on the worst-case atmospheric' dispersion and deposition factors, and a3'such are conservatively applicable to all ground-level releases from the site.' Should some reduction be required to ensure that specified dose limits are not exceeded, then the ground-level DFGs In Tables D.5 and D.6 can be multiplied by the conservative adjustment factors in Table D.4. .

Table D.4 Conservative Adjustment Factor Applicable to the Ground-Level DFG In ...

Ground-Level Release Point '_._____-_-_-'__ .t Inhalation All Pathways Pathway Combined Spent Fuel Bldg Ventilation Exhaust .

___ T 'and Spray Cooler.-. :-:-;: -- 0.39 .- ---0.51' '

- ontainment Bldg 0.30 - -.--0.56

---Personnel Access Hatch -

'B' Switchgear Bldg _ 0.54 0.65 (potential Chemistry Fume Hood) ___. -.

Temporary Tent Exhaust - 1.0 1.0

Worstcase release point

-1 '- X.. O..

For instance, the Cs-137 limiting DFG for Containment Building releases and all exposure *l pathways combined is 9.64E-04 (Table D.6) x 0.56 (Table DA) = 5.40E-04 (mrem-seclpCi-yr).

l~~~~~~~ :-~,-' ,.4' , ' -* ~~~

ODCM - APP i -4".>-

I JUL 1 5 2003 Revision 16

- I Table D.5 CY ODCM - Dose Rate Conversion Factors (DFG) for Critical Receptor and Organ (Inhalation Pathway) :. , Ie

*..X~ -DoseRate Conversion Factor (re -s ciiiyr)

Radlnuclde~ -Ground-Level Releases Eeae H 3_... 2.24E-01

--- ~*~.* .-

'..20E0 Releases I!l MN54 ... . .O+2. 5.635El01 FE55 . . .3.63401 . 3.53EO00 FE 59 -4A48E+02,- 4.35E-g0i CO057 1.I72E+02 1.67E.OI COSS 3.94E+02 - 3.82E+0I

'94 CO 60 .- 2.5SE+03 .2.9E*02 ZN 65 . . *.63E+02 3.53E.01 SR 90 .13E+04 1~ 1.10E+03 ZR 95 7.89E+02 7.66E+01 NB 95 2.20E+02 2.14E+01 TC 99 4.07E+02 3.97E+01 RU 103 2.29E+02 2.23E401 RU106 4.70E+03 4.57E402 AGI 1M 1.98E+03 1.92E+02 SB125 8.OIE+02 7.79E+01 CS134 3.31E+02 3.22E401 CS137 2.66E.02 2.58E+01

-,, CE144 3.91E 03 3.82E+02

. EU152 1.17E+03 1.14E+02 EU 154 2.97E+03 2.89E+02 PU238 a

3.50E406 _ __3.4 IE+,b5_

-3.94E4OS

- -PU239 :74.07E+06 -

- _=_

7 ..- . 77_1=1_:__==_

`PU239 -.-: -- -- 'I 7- -- '--:4.UM+06 : - ..

. :..:1.94E+05.

_ PU240 _ , 4.04E+06 -c-3.91E+OS -----

PU241 8.77E+04 8.52E+03 . _. -

_._ __ AM241 -- 4.16E.06 -4.04E+OS CN1242 - .SE 1.54E+04 CM243 :.729E+06 2.71E-OS.

- CM244 -- 2.15E+06 Z09E+0S (a) Worst-case release point. Refer to Table D.4 for optional adjustments. -- ---.---

(b) C14.;N63, and 1129 are not included in this table as they do not pose a significant source for dose and are not included in the sampling tables of the REMM.

.; ,. :,,. ,-1 ,a. . . , .

o

- OD CM .-. f - . APP D-5 -- - -

M --

JUkeJ1§nThf3-Table D.6 CY ODCM - Dose Conversion Factors (DFG) for Critical Receptor and Organ (All Pathways Combined)

..ADosoConversion Factor,

ii , >*' (rnrenilizCI) 2> : Q7-I _________________________

RdnucIlde~': Ground-Level Releases Elevated

.~ \ ^zj-,2Relea5ss--:

.;k3.-DF,,2-.

-MN 54. . . .2.81E-05 U 3.30E-06 P*

-FE55. . 7.94E406. 1.21 E-06 'C..

,-FE 59 .2A43-05 -,3.67E-06.

N

Co 57 .6.8E-06 .7.36E-07 '1*

C058: 1.-05 -. 1.67E-06

-Co060 2.32E-04 - 3.14 E-05 .4.,

ZN 65 3.97E-05 6.12E-06 SR 90 1.64 E-02 2.54E-03 ZR 95 2.67E-05 3.52E.06 NB 95 4A48E-05 6.90E-06

-TC99 9.17E-05 1.42E-05 RU103 6.63E.05 1.02E-05 RU106 9.65E.04 1.4E.04 AG110M 8.70E.05 1.28E-05 SB125 4.33E-05 524E-06 CS134 1.01E-03 1.57E-04 CS137 9.64E-0 1.50E4 CE144 1.24E-04 1.58E-05 EU152 1.42E-04 1.gE-05

. I ill" I - caIn '2

~~ PU2. - . : _-

n---

PU239

_ - 7I IM---

~ 2 -

~

t- * :

--^--12E01

. 1 11.1 1 E 01 - ~

6E-01

.t26E02-

- :^.

0- .--

PU240 128E-01 1.25E-02 PU241 2.79E-03 2.72E-04 k AM241 1.32E-01 1.29E-02 CM242 5.02E-03 4.89E.04 - . >

CM243 8.88E-02 8.67E-03 CM244 6.86E-02 6.69E-03 (a) Worst-case release point. Refer to Table DA for optional adjustments.

(b) C14, Ni63, and 1129 are not included In this table as they do not pose a significent source for dose-i 'c '

and are not inciud h the sampling tables of the REMM. ' .. . '

' ,. r-..,

.4 ODCM -APP ;-;

I '

I JUL 15 2003 GASEOUS DOSE CALCULATIONS - GASPAR2 IOR QUIVLEN The GASPAR-2 co0de66as wnttei the 'NRC'to co6Mp~jute'do seds from g'aseous-relasetsusng theodeigiven InRegulatoryGu~di1O:Tervs~ldt fth oei eebr98*

Oth'er codesi which Imple mednt the guidance provickded in Reg`ulatoryGuide 1109. RevIsion 1,'are,-

also acceptable; includingMetho I 4,-f t ~?c ~~--

F~6rcaluIAfingthe -maxlnr'numlrddualAdose rom`HaddamiNeck, thefolwnoponad parameer mybe' used (MtX.,:>.-

1. HistorIcal meteorology using a XQ DIQ/6 moel which Incorporates the 'methodology

."of ReuaoyG~e11.;The, five, -ye'ar-.pe'riod of 1976I- 1980 was used to determine dispers on_ 'estlr 6s-e,.K. 2,

2. I100% -of 'vegetation, grw loaly, 6 of vegetation'Intake from garden, harvest

`-Season from April through 'September.-

3. Animals on pasture April through December - 100% pasture intake.

4. Air water concentration equals 8 g9m 3 .

5. Maximum Individual dose calculations for Method I were performed at the nearest land site boundary with maximum X/Q. For conservatism in the Method I model, this location is assumed to have a resident, vegetable garden, and milk and meat animal with the maximum DIQ value.

ODC M E-

JUL 1 5 2003 Revision 16 AEE~ENX METEOROLOGICAL DISPERSION FACTORS oispersion-heODCM actor er derived usi AEOLUS- computer

-AEOLUS3wa. written to implementregu-ltoirygudance ford rcotii ' `(Regulatory Guide

'1.111) and. intemiitterit.'eases (NRCcoputer.code XOQDOQ)a a he ode has varbious options includiri6 building'wake effects 'plumei:-depleton " Fd'¢dep iti'ndand an effet -,

.,,'.plume 'height that ,-ac'ounts -'fo'r ph 'sical'release 'heIght,' plumedow'n'wash, plurme 'rise. and -

terrain features. ' -' , ' '"' ' '

A set of atmospheric' dispersion factors' which 'are a function','of..release duration were i:-:generated. .NUREG/CR-2919 (the documentation'package for the NRC atmospheric dispersion

.computer code XOQDOQ,' Reference 1) presents a methodology'for.'determning atmospheric'

'dispersion factors (CHIVQ values) for Intermittent releases at user specified receptor locations -:

'i` (intermittent releases being 'defined as'releases: with durations betw'een "-and 8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months ).

.,The CHItQ values for Intermittent releases are determined by linearly interpolating (on a log-log

'"basis) between an hourly 15-percentile CHUiQ value and an annual average CHVQ value as a function of release duration. These time-dependent factors were derived using one-hour 15 percentile and long-term average atmospheric dispersion factors.

, The following assumptions were used in executing AEOLUS-3 to determine one-hour 15 percentile and long-term average atmospheric dispersion factors for each of the two release pathway categories (ground-level and Primary Vent Stack):

Plume centerline CHI/Q and DIQ values were used to generate the one-hour 15 percentile dispersion factors (an AEOLUS-3 default assumption); sector average CHI/O and D/Q values were used to generate the long-term average dispersion factors.

AEOLUS-3 default open terrain recirculation correction factors (Regulatory Guide 1.1 11)

- were used to generate the long-term average dispersion factors in order to consider the effects of recirculation of effluent.

,- .The ground evel-releasepathways(eg. SpentFuel Building ventilatic. exhaust vent,.

' : Spnt-uel--Building

--Set uleronVAccssfcomponent -spray,-cooler,7--Pesnl .;Aes-.ac-,on-the "Hatch -.~=

-on -h-~-'-

Containment 'uilding, potential Chemistry Fume Hood exhaust out of 'B' Switchgear Building, and for-a limiting condition associated with temporary tent exhaust for work on contaminated -components) were treated as Reg Guide 1.111 (Rev 1) ground-mode releases with releases emitted below the height of adjacent buildings.

.- 'The Primary Vent Stack was treated as a Reg Guide 1.111 mix-mode release since the vent is above (but less that 2 times above) the height of adjacent buildings. A stack conservative exit flow rate of 117,000 cfm was assumed.

- Lower level wind speed data were provided to the code for both types of release .

pathways. These data were used without adjustment to disperse the plume for the.:

ground level release pathways. For the mix-mode Primary Vent Stack release pathway, the lower level wind 'speed data were extrapolated up to the Primary Vent Stack release

- 'height for-evaltatinIplume entrainment effects -and for-detem'ining plume rise and '

.ODCM - . APP F-i

W- - I 4

. iA .1

- JUL 15 2003 Revision 16 . i dispersion for the elevated-mode portion of the plume. The lower level wind speed data were used to disperse the ground-mode portion of the Primary Vent Stack plumes.

- Lower.level wind direction data were provided to the code to determine plume transport-. ; '

for both-types of release pays : . ' i

- The ,19z '. -delta'tmperature7-data were provided to'the co

- -- ' atmosphe cstabilityor. types of release'pat ys..;.; :-...'; 'X, ', *

-:--. Tlhe Reg GGulde .1i . I I (Rev. 1). depletlon/depositlon model was used for deterning*X depleted'-.CHUOQ -and or: bothtype -,of rlaeplwy.

jDQala Wt-~.~

. depletion/depositon and decay-intransit were not considered. .

Meteorological data measured onsite b~r.the system from January 1978 throg' monitoring December,1980 -were used asirnput"to ;the AEOLUS-3computer code. Analssof .

data measured at the Haddam Neck Plant during the following five-yearperiods, meteorological 1976-1980,' 1988W1992,'1993 1997,'indicated that the lower level wind speed data' hive been influenced by"foliage growth over ;the yars and that the 'older'data set (1976-1980) is most appropriate for use in analyses. - .

Atmospheric dispersion factors were calculated for three time periods: . -

.. .Annual '

. Growing season (defined as April through December)

. . . Non-growing season (January through March)

The most conservative values from the three time periods were used to develop the dose factors.

The 'one-hour 15-percentile undepleted 'CHI/Q, depleted CHIIQ. and DIQ dispersion factors used in the time dependent equations.were derived by averaging the highest one-hour 15-percentile dispersion factors which occurred in each downwind sector, weighted by the fraction '

of the time .the wind blew towards each downwind sector. The long-term average undepleted...

CHI/Q, depleted CHI/Q, and DIQ dispersion factors used in the time dependent equations were .-

the highest long-term average dispersion'factors calculated for receptors at and beyond the

- .-.-.-. Site Boundary. At.

The time-dependent equation is: . ' ' .. - .

X;Q=XI ' A .1QA'v where XIQh, Is the weighted one-hour 15-percentile value and XWON, Is the long-term average value. For the derivation of the time-dependen equation, see Referene 1. '

-. I r I f", :-, -, ." .1 .. . I. - .. V.

1 '4 --I.: .. I .

I . .

ODCM '.APP F-2

JUL 15 2003..

Revision 16 The time-adjusted Method I dose equation for Particulate and Tritium releases can be written as:A (Y*~ -2 I--I -A tA D DFGl~f 41 r

_ _ _ _ _ _ A -)

5 ~..

Qe tA~

r~Y!

o?

where. -,~

D. The crtclora oefrom particulates-and tritium;

(.)= The 1-hour depleted atmospheric dispersion factor,

= The depleted atmospheric dispersion factor for the growing season (see Section Table F.1);

= A unitless adjustment factor to account for a release with a total.

duration of t hours; A.

Q = The total activity In p~Ci of radionuclide "i released to the atmospher during the period of Interest; PA;-he. site-specific critical1hc~6fi*-~ o the rougean oran iththelargest dose factor (see Table 3).

lncorp rting location-speiic -(iLe., temporary tent release point) atmospheric 'dispersion' factors and the time-adjustment factor (C) yields an equation for the determination of cntical--

organ dose. The substituted values are as follows: -- A

= 2.89E-03(scr)

(Q $ A~ 2.931E-04 (sec/rn)AA< A A,: Ar ODCM APP F-3:,

, - 96

-_. .Revision JUL15 2003 - -

16 .

I Q(

.- For-the~mdmim ~ofsite receptor llocation and a around level release condition; the above.xE- .

vaThesln ern hour sthe abeii atmopericdipendn reqaion facosfol lows:e nTbesF1; -

. 1

-DOS .: ,9 '.86Cz ' ' .:, .~.

e* , : ,

-Fo Ahe' -~ '- .r-el.e.se0

.. .w.e...re......

us o- .. ; .. , .as. .t ZOSI

a '-' *S '- ': -'6 -'ts' 'p 'e ab4tr 'phn eqato folw','.d;;,

_ __ . - _-'----.--'- -- '...'.--. .-...---. X

' \ t e ; ;; v

t ~~t _-... l ODCM .F-.. . .r -

r-4.;<

J~~~

t.-,0fP

. ... .s. . . .- . L, ..................... "...

-.. :_...:s

JUL.1.5. 2003

- Revision,16 I TABLE F.1 ATMOSPHERIC

.. ~' ! DISPERSION FACTORS KGOUND LEVEL RELEASES p....

Spent Fuel Cont. Bldg B" Switch Temporary Bldg Accei goar/now Tent Hatch I lChem i1~.iFume

I, Hood -.Tern. u LTen Dispersion Met Data 1-Hour Long-Term 1MHour: Long-Term 1-Hour Factor Period Long-Teim -Hour: Long i i. t I I Undep'. XtO Jan-Dec 1.41E-03 1.14E-04 8.80E204 8.98E-05 1.73E-03 1.60E-04 2.82E-03 2.75E-04 282E-03 2.75E-04 (secIm) - (537 mWNW) (503 m WNW) (457 m WNW) (360 m WNW)

Apr-Dec 1.53E-03 1.19E-04 9.56E-04'l 9.35E-05 1.88E-03 1.67E-04 3.07E-03 3.09E-04 3.07E 3.09E-04

- (537 m WNW) (503 mWNW) (457 mWNW) (383 m W)

Jan-MAr 1.08E-03 9.75E-05 6.75E-04 7.89E-05 1.34E-03 1.38E-04 2.18E-03,- 2.2E-042i.; -2;18EW3< 2.42E-04 (537 mWNW) (503 mWNW) (457 mWNW)

,.1 . {360 m WNW) e*L'L,'Mfiax-AUI _on i E.07' rt 3.09E-04 i.

DeOIXQ :Jan-D(ec 1.30E-03. 1.06E-04 8.14E-04I 8.42E-05 1.61E-03 1.51E04 2.68E 03'i - (38 m W~)- 2:Z-03 (seim~) (537 m WNW) 281E..-04 2.61 E204. I .

(503 m WNW) (457 m WNW) (360 m WNW) 1.41E-03 1.11E-04 8.85E-04t 8.76E-05 1.75E-03 1.58E-04 2.89E-03 .2.932E04 92-3 :2.93E-04 (537 mWNW) (503 m WNW) (457 m WNW)

Jan-Mur 9.95-04 9.11E-05 6.24E-04 7.39E-05 1.25E-03 1.30E-04

- (secrn2

) - 2.05E-03 2.312E-04 2.05E-03 -2.31E204 (537 mWNW) (503 m WNW) (457 m WNW) (360 m WNW)

.axll (383 Season5 mW) Z.89E-03i 293E-04

,,. ii DIeO: Jan-Dec 8.95E-07 1.11E-07 1.22E-07 1.05E-06 1.42E-07 1.48E-06 2.122E07: ,1.48E-06 (537 mWNW) 212E2-07 (503 m WNW) 457 m WNW) (383m W)

Apr4-oec 9.25E-07 1.13E-07 7.77E 07 . 1.25E-07 1.09E-06 1.45E-07 1.S4E2-0 2.22E-07:

(537 m WNW) (503 m WNW) (457 m WNW)

JanMar 7.05E-07 (383 mW):

1.03E-07 6212.07 1.14E-07 8.34E-07 1.33E-07 1.172-06 1.90E-07 1.72061.902-07 (537 m WNW) (503 m WNW) (457 m WNW) (36Om WNW)

-UEax-AI Seaon 1.54E-08 2.222E-07

.4.

4 . * .. q ta-....

.4 I..IV4 I ODCM ~~ APP F.5 I' j)%

JUL 15 2002 Revision 16

,ENVIRONMENTALMONIORING PROGRAM?,:.: '. --

'aZ

.. -. .. j<m^.cactin S

f>'The'f iwng ists the iiro mettal -ri -an types-_of

. obtaried at each locatlon. -'Sampling locations are also6shown on Figures G-1, and G2. .

Location : . DIrecton Dlstance From. .

Number ., -Name ,,Po ; , Samb-eT' t4,1F4.I On-site-Mouth ofd D argeCanal 1.IM. ESE (.5 A.'SSE IF) LD ' "-

24- -. Haddan-Park Rd. - .. .8PAS.

3.4 Haddarn-Jall Hill Rd. -. .,08 WSW TL 4- Haddarn-Ranger Rd. ' .8 USW;*

S*-5 O-site-lnjun Hollow Rd. (Site Boundary) 0.4 Lt. NW TLD. Ar Parlcuabte,

-64,. 1F . On-sAe-Subs.tan (In 10 mies) 0.5 M, NE (0.6 M. NW IF) TLD. Air Pariculate, Broadleaf Vegetation 74 Haddam 1.8 Li. SE TLD. Air Pariculate 8-I East Haddam 3.1 M,. ESE TLD 9-1 Higganum 4.3 M, WNW TLD. Air Particulate 10-1 Hurd Park Rd. 2.8 L. NNW TLD 11-C Mlddletown 9.0 PA. NW TLD 12-C Deep River 7.1i. SSE TLD 13-C North Madison 12.5 M. SW 14-C Colchester TLD. Air Particulate 10.5 M. NE TLD 15-I On-site Welts 0.5 AM.ESE Well Water 16-C East Haddam Torwn Office Buikling 2.8 M. SE Well Water 17-C Fruits & Vegetables Stand/Supply. normally Approx 13 M. SW Fruits & Vegetables In North Madison (beyond 10 miles; (beyond 10 miles) Broad Leaf Vegetation . * -

normally vwithin-2 miles oflobcatbn t3-C 184 Site Boundary (Within one mile of 0.4 M. NW, Broad Leaf Vegetation -'.'

Location 5-1) (within 10 miles) 25-1 Fruits& Vegetable Stand nomany wlin one Approx 1.0 Lile. NW Fnjit &Vegetables mile of Location 5-4 (in 10 miles) 26-I Conn. River-Near Intake 1.0M. WNW Fish 27-C Conn. River-higganum Light .._ .... 4.0 AM. WNW 21 Riii-E. Haddam Bridge: .- Shellfish - S -- ---- h 0---

1.8 .SEttr 1 . Vilqnityof Discharge:'-.---: ...- . ------00MPA- 7oneieL~h7~---

30-C ---- Conn. River-hiddletown - 9.0 9-- PQ NW

- - . River Wale, Btom Sediment 7.6 A. NW F, 31.1 MouthofSalmonRiver 0.8M. ESE Sheiflsh 48-IF Onsite Met Tower Shack 0.4 Li. WSW TLD 52-IF Schmidt Cemetery(onsilteO 05 NNE TLD -

53-IF ISFSI Haul Route (onsite) 0.2 Li. SSW TLD .

54-IF Route 149 (near Salmon River mouth) t.O M. ESE TLD 55-IF High Voltage Tower (onsite. NW of Pad) 0.4 PA. NW TLD - --

56-IF . Burrow Pit (onsite) 02 M; E TLD 57-IF Dibble Creek Sediment Sample 0.1 PA. SE Bottom Sediment :s 58-IF ISFSI Pad Endosure Soil Sample Coll. -. o HM Soil , .- 4 1= Indicator C = Control IF= ISFSI Indicator , . -

The release points are the stack for terrestrial lofatons and the end of the discharge canal 1or a ci..

The ISFSI pad Is the release point for the ISFSI Indicator.'..

'-D-* ;- a..

ODCM ' G1.-'".1:

-APP

JUL 15 200^

Revision 16 Niorth '-

jWestcheste r I

1354

.- II

! 163t 7 -

:L-f Salem

U ._l1' I.

j I

'-( A -1 Corners I W*

m 52 , .1' ord p .4 iKs; /

~Chesterfam oU.

CT IE'C

-< r 1+od 1 ptA 4 IIo t ;

/ FOREST?

,1' North w , . v -

Tokxworth ,'

17 -

. 1131 ire G- 1: Hadda m~ Neck Plant Inner Terrestrial Monitoring -Stations V.: V.

ODCM Figi APP G-2

; , I I 'JUL 1 5 2OW

.1 Revision 14 5

-ITO Bashah,.

ILittle J.Haddam, - PF Mourt f.434' .*1 ~ *,-IC nr r 1' k.IAd hseril

~ . 1 -V 13"Mrd~

-OCkv Centbr I . .

Figure C>- 1: Haddam' Neck Plant Inner Terrestrial Monitoring Stations ODCM APP G-2

~~~~ ** * .

-JUL 1 5 2003

- .Revision 16

-~I 'I (

1.g TNEC 1-I (own 1T -

.I-.. n ': b1 FE :Eto .

~C .4

~'

s,-j 4,' /

-;*j [j4 '

,~ .. ~~~

.- , , ,.,1 Rockt~

, U __rr 781mor 429 Figu're G- 2' Haddam' Necdk Plant Aquatic and Well Water Samiple Stations

. Af4lO *.#"f~ 'i

0-JUL 15 2003 Revision 16 DOSE FACTRJFRKr8

.H.1-Approach ,-

ThedRMM dses' andtotal bod n knds

,-.h6'EMMrequilres thei calculation of gamma an bet airndsinds ratesreultn fro the 'relesase of nobble gases (Ie.e Kr85)othatiphr.

Te garrima air and beta airdAoses, as wellas the total body'doere, wMl beT determined using the'dose facostknfo al - fRg., Guide 1.109 for ind tivdal raidionuclides.

The 'skin -dose factor, DR'. Is calculated for' lndivdual radionudlides (i.e.,' K-85 here)b 6cormbining the gamrma air dose and beta skin dose factor's to give a comrbinied skin dose factor.

The following subsection's"'detail the' dcveiopmeint of these',dose factor's "andthe'equation for calcuaingst seific doses with them. -

-Meteorological dispersion factors'are calculated for the CY site as described InAppendix F, and are summarized In Tables F.1 and F.2. These represent a long-term (5 years) site average meteorological history that was used to determine the location of minimum dispersion (maximum dose) for off-site receptors.

The Kr~-85 dose factors to be used in the ODCM Method I calculations are listed InTable I-1-.

H.2 Total Body Dose Rate Method I was derived from general equation B-B in Regulatory Guide 1.1 09 as follows:

Db =(1E+06)*[ ]Q DFB (H-I)

(mrm _pisec~ (P0 mrem-m where:

- Maximum undepleted XIQ for release point of Interest (see Tables F.I &

F.2),-

Q= Release r.~ '~the environment of Kr-85 (jtCi/sec);

_ DFB = Totalllbody

dose factor (see Table H.Iland Reg. Guide.1.109, Table B-I)...

ODCM APPH-I

UJUL 15 2003 Revision 16 Equation H-i reduces to the following for elevated (mixed mode) releases:

D4

n.'.'.. ".j., a.*

,'t ....................

i..p~ ,

.' i Note: Slnc'the 'permia'nent shutdown of the station, the'Spent Fuel.Building' t:zi ventilation has been isolated from the plant stack.' In addition, therwaste gas decay system, which was' used for gas holdup before release to the stack during .

plant operations,;has beenhabandoned. The result is that the potential for'nob' gas release'via theplant stack has been removed.

,~~~ - ; .... 4-;-

^- - , 3/4 and for ground level releas: 's'.i- -- -.- ',.

11 D,) 309 *Qg *DFB ' (H-3) mrem

- =e pCi- sec *.

{(pCi . mrem P r-m' yr )1w Ci-r)m3 sec pCi- yr) . .-

I~~s I t

H.3 Gamma Dose to Alr' For any Kr-85 release, in any period, the increment in dose is taken from Equations B-4 and B1-5 of Regulatory Guide 1.109, as follows:

Dr =(3.17E-o02) (DF (H4)-

- 2 -. mrad - '

=_=_ pas-sc J __

__ ,,.tptf _ __ __ _ _ ___ __ _

(mrad).( , _ _ . . _ ... -

where: -

3.17E-02 = - Number of pCi per piCi divided by the number of seconds per

-year,

= Maximum uundepleted X/Q for the release point of interest,

'.= ,-Ovintity'of Kr-85 released (pCi); -

DF7 = 'Gamma air dose factor for a uniform semi-infinite cloud of Kr-85 (from Regulatory Guide 1.109. Table B-1, 1.72 E-5).

ODCM APP H-2

JUL 1 5 2002 Revision 16

- - For elevated (mixed mode) releae'sk this'leads to: ,

-D.) -(E-07)Q '*D.

However, as noted above, the expectation'for'noble gas (Kr-85)'releases from the stack have been removed.,

and for ground level releases:

Dr) z =(9.8E-06) Q*DFimrad., (?-6:

-yr .- ,..

pCi-ynfpG

H.4 Beta Dose to Air ( p

'For any Kr-85 release, in any period, the increment in dose is taken from Equations B-4 and B-

.5 of Regulatory Guide 1.109:

D0;, (3.17E -02) (.)(Q).(DF') (H-7)

.PC (mrad)(I-sc(m)(i)(pir):.?.--

where:

DF- fairo Betairdo factorsfora-uni oud-fii ssremi- rb r i85.f (ffrb .3-Regulatory Guide 1.109, Table B-1, 1.95 E-3);

o = Quantity of Kr-85 released (pCi);'

(.~

t- = Maximum undepleted XIQ for the release point of interest.

Substituting the XJQ value, we have for elevated (mixed mode) releases: -

Ddj,(E) =(9.OE-07). (Q,).(DFP); (H-8)

As noted above, the expectation for noble gas'(Kr-85) releases' from the plant stack hve been removed due to changes in plant configuration since permanent shutdown.

1 ODCM APP H-3

JUL 15 2003 ....

Revision 16

-And for ground level releases:

.- )

Method (mra)

I was (~ ),y(PC)e rminrat Averagn , J o of X iRegulatory Guiden1.) 09 a followsn' ma r t fscm ay - ;L~

-- : - yr

--- . A.

Dhin, =Q.1i)*,4 (3.17E4O)()j~j(F) -H(-I10)

H.. .ki - .oeRt~. .~

DFnrem merivd e eqsua) C foiseinn'( mrem-ms 4..-'

yr )( mradfromaithe) greneral _ -- m p i-yr yrsec)L(yr)I where: -:1 1.11 = Average ratio of tissue to air abssorption coefficients (will convert mrad in air to mrem In tissue); .-

3 17E+04 = Conversion factor for curies to picocuries and seconds to years; DFS -Beta skin dose factor for a semi-infinite cloud of Kr-85 which includes the attenuation by the outer *dead" layer of the'skin; Dy'fr= (3.17E+o4)*(Q).L(.J.(DFY) *(-l MJI. ==z.I*I.,.7-7I7..

DF' Gamma air dose factor for a uniform semi-infinite cloud of Kr-85 (see

Table'H-I).

0 = ' Annual release of Kr-85 In curies per year.

- . , - ,-n~j ,. X !,,

ODCM - APPH4

JUL 15 2003-I.

Revision 16 Since Q =31.54Q where 31.54 Is the conversion factor for Ci to pCI and from years to .

seconds, then 1

.. *;. m K a 3.p p-r

.D£

- 4(,D =(I.1XIE+O6Ie(Q)(DI~).21E X¢).(DF).(D3) 's)

~rer'e 'CI(mJ

. - . -'I mrr 2,j 3 .

rp-sc-rmfnrdm3+p-sce~rnm-rn or,4 ' .

point: elevathe (ixe mode) . e the forbanelevated (mixedsode)a welaswsu release fo'r-

--Y~ -yr J ti--maxsec,(

mm 2 a - tppC-m sect pCi-nr J -'>e Susttuin te.I valu (.85-0 - ... >

where = DF, (ic-e pCiymad'.-m) C~~~~ . p(2Ci-sec pCi mrer--m-

P'y

- .- *1c

- - pci-r n sec, pCi-, . .

pithe exrsini

. aetee bva ohv:r.

or, D5 ,(,) = 31.6DF-' + 28.5DFS)." (-'-14)

For an elevated (mixed mode) release we substitute the Ocombined skin dose rate factor"for the expression in parentheses above, as follows:

"Combined Skin Dose Rate Factor= DF = 31 .6DF + 28.5DFS (H-15) where DF, = (31.6)4'(1.72E-5)+ (28.5)- .34E-3)=3.87E-2 (mremrne-S:

- . .DF, (H-16)

.rem : -

mrem. secj;.TZfi . .-v:. -~ ., ~ ,,7,',

I r ,='ecc ~iy Values of DF: may be found in TOM- 4-1.

ODCM APP H-5 .

JUL 1 5 2010 Revision 16 As noted above, noble gas (Kr-85) releases from.the plant stack have been eliminated due to

-changes in plant configuration'since permanent sudwn oeer ,tesame methodology for. the dedvelopm ent.'of a mbined skin -dose tg d level',-;

releases. .-. ' - ' -

' .?-< '

Substituting the ground level X/Qvalue (3.09E04 seilm), we aeor,round a level rela.. .

9...,'.wnt,, I,. .;,-

(343) I ) ' ' -,.1;--

Wm ) .pCI-sec-~mrem (onL~ (3 p~i)t mrad 9)(','(D-S*.H1< rnl' l sc~ CI(rrOnl

i )( 3

-mrai )r!- siSi-m pCI7 or,

-DSa() =Q343DF' + 309DFS) . (-118)

For an ground-level release we substitute the Ocombined skin dose rate factor for the expression in parentheses above, as follows: -

."Combined Skin Dose Rate Factor =DFs'=343DFP +309DFS, (H-119) where DF =(343)(1.72E-)+(309) * (33)*+ 3~jpCI za~-p (1.34E-3)= 0.42 (m) -yr) then:

sklia(g) = Qg

DFg;. (H--20) .

(mrem) = ('i).(mrem-scc) _

V Yr oJm seC f inT H Values of D)F; may be found in Table H-1.

.-J,.,e

.' eMQ,.',,:., . . - ;.

' ': ' ' S . . .

,,

t x, ODCM - :: APPM ':

JUL 1 5 2003 Revision 16 TABLE H.1 DOSE AND DOSE RATE FACTORS FOR Kr.85-(Combined Skin dose Rate Factors are derived in Sect. H.5; all other Dose Factors taken from Regulatory Gucide .109).

Gamma Total Bod" Beta Skin Combined Skin Combined Skin Beta Air Gamma Air.,i; Dose Factor Dose Factor - Dose Rate Factor Dose Rate Factor Dose Factor . :Dose Factor --

(mrenu m3 (mrenz-m Elevated Releases Ground Level Releasesmrdm DF(adm)

DFBm1 rSem___- (rs-sc'1 DF< r p, r ) pCi-yr) i E DF(F p' yr )i ( r j

-1.61E.O5 1.34E.0 3.7.24.20E-01 1.95E.03 - 172E05' 4 --

,. j ;,.. ..

, ., , * , -: . - j..

. - ~~.: '

C,' " " ' ' '.^ ' s,.,

0 '?0 0 'Va':,CM ' 'f APP. H-7 0 " "'"3-

I -W i I ACP 1.2-2.48 Rev. 2 Attachment 2 Connecticut Yankee REM/ODCM Change Request Check One: 0 REMM Change ODCM Change Change Request 0301 Originator Name (Print): K. Comzkv: (Attach ,unprkgp pages)

Section No. Section Ttle atm No. -'-: Descriptionochat&Reaso D. I .d. I Method I elevated mixed D-3 Description of Change:

mode release DFG Added -mixed mode" to the definition of DFG.

Basis for Change:

Clarified that a elevated plant stack release is considered a mixed mode type of rekase.

D.3.a. 1 Critical Organ Doses L'-6 Description of Change & Reason:

Added "mixed modc to the definition of DFG (ccXc).

Bash for Change:

Clarified that a elevated plant stack release is considered a mixed mode type of release..

D.5 Compliance with 40 CFR D-9 Description or Change:

190 Limits Added statement that infornnation about a significant dose input vill be included in the 40CFRI 90 limit evauation.

Basis for Change:

To clarify information about a significant direct dose imnpact.

G References G-1 Description or Change:

Added two references CY-ESG-01-01 and CY-ESG-02-001.

Basis for Chsnge:

Infornntion from these two references is used in Appesdix C. Licmid vxost Calculations.

Appendix G Environmental App G-1 Description of Change.

Monitoring Program Added ISFSI REMP monitoring locations Sampling Locations Basis for Change:

ISFSI new release point location.

Figure G-1 Haddam Neck Plant App G-2 Description of Change.

Inner Terrestrial Added ISFSI REMP monitoring locations Monitoring Station Basis for Change:

ISFSI new release point location

'.: r It of 13

- JU 150-

- ACP 1 5 2002 1 ~Rev.2 ACP 1.2-2.48 Connecticut Yankee REM4)DCMChange Request Page 2

-?3 II. List the procedures andlor setpoints that require revision in order to implement the proposed change.

- .9f Estimated date for N~ame of Manager I-tN inwmienmntaMn responsible to imtola ent ALP 1-)9o50 W-n-b3 3. N\<-

).-r Ia - ), 5'r ... /0 T- ft rlt. A m.

Technical Reviewers:

a Approve or disapprove Ifdis j attach bases.

List pro;Eesetpoints tha! . revision in Section II.

(1= [h1 A MN Approve t% Dir apmrove f S/8/0 -i JI I Dite Approve MDisapprove Q S-- -V 3 Date Radiological Environmental Review:

Unreviewed Ewuironmental Impact? Yes E No 3 (Bases Attached) 7 , c- Approve 0 Disapprovc P 6/2/

Health Physics/Waste Managemf ent Oversight Manager . Date V.

Health Physics & Safety Oversight Review:

r Approve N Disapprove 0 (o 101e Ueafth Physics & Safety Oversight Manager Date VI.

Compliance Review:

Approve & Disapprove LItk L 3I Rulatory Affairs Manager Date 12 of 13

JUL 15 2002 ACP 1.2-2.48 Rev. 2 Atbachmpnt2 Connecticut Yankee REM(ODCMthange Request Page 3 W PORV P7w: // Meeting No.c<;a/

F /

PORC Chai i)VZ / ApproveBRODisapproveO 1Se Date

/ °l-93

-i,?tA4 ~ ~// Approve Disapprove _

Unit Manager Date Ix.

CY NSAB Approval:

(As required)

( ul P2- Approve E Disapprove E NSAB Chairman Date X.

Verify that the Section II procedure and/or setpoint changes have been approved and are consistent uwith this Change Request.

Effective Date of REMIODCM Revision:

KE-ivirodii~ntal axpdtniistry Lead Date Changesent to Ad >por implementation:

)eiviZXm1 Z Z7 1a ft `

1,E~id'eiad0~msr a FDaze XII.

Da te2.

Date V

13 of 13

CY-04-072, Annual Radioactive Effluent Report for 2003

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