ML061280296

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Rev. 19 to Section II, Offsite Dose Calculation Manual for the Haddam Neck Plant
ML061280296
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Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 12/21/2005
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120050 SECTIOUNI OFFSITE DOSE CALCULATION MANUAL For The HADDAM NECK PLANT Docket No. 50-213 ODCM Revision 19

Revisio 200 Revision 19 HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS Section Page A. INTRODUCTION A-1 B. RESPONSIBILITIES B-1 C. LIQUID DOSE CALCULATIONS C.1 Method 1 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. Critical Organ Dose Rate from Particulates and Tritium D-1 D.2 I OCFR50 Appendix I Limits (Particulates and Tritium) D-2
a. Critical Organ Doses D-3
b. Estimation of Annual Critical Organ Dose D-5
c. Annual Organ Dose Limit D-5 D.4 Quarterly Dose Calculations for Annual Radioactive D-5 Effluent Report D.5 Compliance with 4OCFR19O Limits D-5 E. LICQUID EFFLUENT RELEASE CALCULATIONS E.1 Discharge Line Flow Rates E-1 F. REFERENCES F-1 ODCM T of C - 1

DEC 21 2005 Revision 19 HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL LIST OF FIGURES Figure- Figure Title Page G-1 INNER TERRESTRIAL MONITORING STATIONS APP G-2 G-2 AQUATIC AND WELL WATER SAMPLING STATIONS APP G-3 ODCM TofC-2

Revision ~ 9 U~

HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL APPENDICES Appendix Appendix Title A SECTION C.1 - METHOD 1 DOSE CONVERSION FACTORS B SECTION C.1 - METHOD 1 DOSE CONVERSION FACTORS BASIS C LIQUID DOSE CALCULATIONS - LADTAP (OR EQUIVALENT)

D GASEOUS DOSE CONVERSION FACTORS (TRITIUM AND PARTICULATE)

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

F METEOROLOGICAL DISPERSION FACTORS G ENVIRONMENTAL MONITORING PROGRAM ODCM T ofC-3

DEC ", 1 2005 Revision 19 A. INTRODUCTION Connecticut Yankee Quality Assurance Program (CY QAP), requires that Section 11of the RE:MODCM 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 radioactive gaseous and liquid effluents.
2. Calculation of gaseous and liquid effluent monitoring instrumentation alarm,/trip setpoints consistent with the applicable limiting conditions of operation contained in 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 may exist to perform the required Control. Generally, the methods are listed in order of simplicity and conservatism (i.e. Method 1 being the mcst 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.

ODCM A-1

R&e4v6'sjn'~ £.UUJ B. RESPONSIBILITIES All changes to this manual shall be independently reviewed and approved by the designated manager prior to implementation. I It is the responsibility of the designated Manager to ensure compliance with all the requirements of this manual.

ODCM B-1

fE ("I2 130 5 Revision 19 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 1 used to calculate liquid dose is explained in Appendix B. The methods described below use source terms totaled by similar dilution flows. As required for dose consideration, plant supplied 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, if the flow will be included dose calculations, in lieu of Method 1.)

C.1 Method 1

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 1 Determine the total activity (Ci) of each nuclide released with the same dilution flow (ft3 /sec).

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

(a) For each nuclide from Step 1 that is in Appendix A, calculate its age-organ dose contribution (e.g. Adult Thyroid) by dividing its activity (Ci) by the dilution flow (ft3 /sec) and then multiplying that result by each of the a'ge-organ dose conversion factors (DCFs) from Appendix A (3 ages x 7 organs

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

ODCM C-1

DEC', 2,O Revision 19

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 Subsection 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.

C.2 Method 2 This method uses the methodology of NRC Regulatory Guide 1.109 (Rev 1) to calculate liquid effluent doses. The use of this model and 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 should 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 Report 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

UFCa;12rT Revision 19 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 levels of 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. Site 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 1 estimation approaches a regulatory limit, or if a more refined dose estimate is desired. Method 2 is also used for preparation of the Annual Radioactive Effluent Report that includes the quarterly and annual dose impacts for all effluents recorded discharged to the atmosphere during the year of record.

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

The REMM requires that the instantaneous off-site dose rate from tritium and particulates (half-lives > 8 days) released to the atmosphere not exceed 1500 mrem/year at any time for the inhalation pathway critical organ.

a. Critical Organ Dose Rate from Particulates and Tritium The critical organ rate limit (1500 mrem/yr) applies to the combination -of all concurrent ground level sources. It includes particulates with half lives greater than 8 days, and tritium (lodine-131 and 133 have been removed from the potential source term due to decay). Results of gross alpha analyses shall be considered as Am-241 for dose calculations. Dose rates from all concurrent ground sources are determined independently, and then summed to obtain the overall critical organ dose rate.

ODCM D-1

Revision 19 (1) Method 1 For ground-level releases the critical organ dose rate to the maximum off-site receptor is determined as follows:

co(g) = (Q

  • DFG!co(g))

mrem- _C

  • mrem -sec yr JL tsec p)0Ci-yr where:

D co(g) = The off-site critical organ dose rate (mrem/yr) due to particulates and tritium from a ground-level release.

= The release rate (iCi/second) of radionuclide 1i".

DFGtco(g) = The site-specific critical organ dose rate factor for a ground-level release (see Appendix D,Table D-5) ( ) c ]

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 DA.4 (2) Method 2 If necessary, determine the maximum organ dose rate for the identified mix of particulates utilizing the GASPAR code (or equivalent code model that implements Regulatory Guide 1.109, Rev. 1 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 (Particulates and Tritium)

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 limits apply to all concurrent ground level sources. (lodine-131 and 133 have been removed from the potential sources term due to radioactive decay, tritium no longer considered after SFP bulk drain). 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.

ODCM D-2

C 2i1 ,)23J5 Revision 19

a. Critical Organ Doses (1) Method la For ground-level releases the critical organ dose during a release period of interest (such as 31 days, quarterly, etc) at the postulated maximum off-site receptor location is calculated:
  • ~ g = Z(Qj(g) *DFGic (g))

(Mrem) =(C *nrem)

Ci where:

Q,(g) = The total activity in ftCi of radionuclide Yi" released to the atmosphere from ground-level release points during the period of interest.

DFGjco(g) = The site-specific critical 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 factor applicable to the specific ground-level release point being evaluated. The correction factors are listed in Appendix D, Table D.4.

ODCM D-3

Revision 19 (2) Method l b (For ground level releases)

With the elimination of the waste gas system operation as a batch mode release source, an additional dose equation has been provided for the situations where routine discharges are impacted with an identifiable short duration release of particulate radioactivity, such as the breakthrough of activity on a tempo. ary HEPA filter used during dismantlement activities. The time-adjusted X/Q value provides additional conservatism to the dose calculation by substituting a short-term X/Q estimate for the standard annual average value (ground-level releases only). The time-adjusted Method 1 dose equation for Particulate and Tritium releases is:

Dco(g) =9.86* t 252 *(Qj(g) *DFGiCo(g))

(mrem)=( )*( )*Z(Ci* irem) where:

- Do = 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 sec/m3).

t -=A unitless adjustment factor to account for a release wi:h a total duration of "t" hours.

Qi = The total activity in jiCi of radionuclide i" released to the atmosphere during the short term period of interest.

DFGico = The site-specific critical organ dose factor for radionuclide "i",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.

(3) Method 2 The maximum critical organ dose can be calculated utilizing the GASPAR code (or equivalent code model that implements Regulatory Guide 1.109, Rev. 1 dose equations and maximum individual assumptions) to estimate the dose from tritium and particulates with half-lives greater than 8 days. The dose to the critical organ and age group should be assessed using the most recent land use census data to identify which exposure pathways need to be considered at actual receptor locations. Doses from vegetation consumption can be neglected during ODCM D-4

I 2005.

ALEC '?s19 Revision the 1s'and 4 th 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 time frames.

b. Estimation of Annual Critical Organ Dose The determination of the annual (calendar year) critical organ dose, Dyo from tritium and particulates released in gaseous effluents is the sum over the first quarter to the present quarter doses to the maximum organ.
c. Annual Organ Dose Limit Determine Dyo which is the maximum organ dose for the calendar year, as follows:

Dyo= DQMO where the sum is over the first quarter through the present quarter doses to the maximum organ.

D.4 Quarterly Dose Calculations for Annual Radioactive Effluent Report Detailed quarterly dose calculations required for the Annual Radioactive Effluent Report shall be done using the computer code GASPAR (or equivalent code implementing Regulatory Guide 1.109, Rev. 1).

D.5 Compliance with 40CFRI90 Limits The following sources should be considered in determining the total dose to a real individual from uranium fuel cycle sources:

a. CY gaseous effluents (doses calculated in Section D above).
b. CY liquid effluents (doses calculated in Section C above).
c. CY direct radiation from the site. Based on ERC-16103-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. If an evaluation finds a significant direct dose impact, information about the dose impact will be included in the 40CFR1 90 limit evaluation.
d. Since all other uranium fuel cycle sources are greater than 20 miles away, they need not be considered.

ODCM D-5

Revision 19 E. LIQUID EFFLUENT RELEASE CALCULATIONS Control C.3.3 of Part I of this manual requires that the radioactive liquid effluent instrumentation in Table C.3.3 are available in order to ensure that the limits of Control C.3.1 are not exceeded. Control C.3.1 of Part I of this manual requires that the concentration of radioactive material released from the site shall not exceed the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2. Connecticut Yankee uses MPC values obtained from 10 CFR Part 20 revision prior to Jan 1, 1994.

E.1 Discharge Line Flow Rates Prior to releasing radioactive liquid to the environment, calculations are performed to ensure that Control C.3.1 of Part 1 of this manual is not exceeded. The known or estimated nuclides present are compared to each individual MPC. If the sum of the ratios is above the Administrative Factor then the maximum discharge flow rate is estimated and the minimum dilution flow required for the release is calculated.

Step 1 Determine the ratio between each individual activity concentration known or estimated to be present in the waste stream to the MPC value associated with the nuclide of interest. The sum of the ratios is compared to an administrative limit.

SR E.I j-MPC1 where: SR = Summation of the MPC ratios CI = Activity concentration of each radionuclide 'i" (uCi/mi) determine to be in the test tank. This includes Gross Alpha, Tritum, Fe-55 and Sr-90 either measured or estimated from the most recent composite sample analysis.

MPC, = The concentration limit (uCi/mI) above background at the point of discharge to the environment for radionuclides "i", taken from 10 CFR Part 20 Appendix B, Table II, Column 2. For Gross Alpha use the MPC for Am-241.

ODCM E-1

HE f12 .005 Revision 19 Step 2 If the summation of the ratios is less than or equal to the AF (SR < AF) then the rate of release to the environment is not restricted.

If the summation of the ratios is greater than the AF (SR >AF) then a conservative dilution flow is required. The minimum required dilution flow calculation is based upon an estimated discharge flow rate.

SR DFmin = FmaxX)- 1

_AF -

where: DFmin = Minimum required dilution flow for the radioactive liquid release based upon Fmax (gpm).

Fmax = Estimated maximum radioactive liquid discharge flow rate to the environment (gpm).

AF -= Administrative Factor for SR (between 0.1 and 0.7) used to set the threshold for performing additional release rate and dilu:ion flow calculations. This factor is conservative and will account for ongoing releases from other sources.

If the plant supplied dilution flow is less than DFmin then reduce the discharge flow rate, reprocess liquid to lower activity levels or increase the available dilution flDw.

The radioactive release shall not be performed until the minimum dilution flow is available.

ODCM E-2

DEC 2 I 9On.

Revision 19 F. REFERENCES

1. Health Physics Technical Support Document, CY-HP-0029, HEPA Units Environmental Release Evaluation
2. CY Memorandum HP-99-108, Justification To Eliminate HEPA Unit Exhaust Airborne Radioactivity Sampling Based On Work Location Contamination Levels.
3. CY Calculation REMODCM-01686-SY-00, Connecticut Yankee Haddam Neck Plant ODCM, Atmospheric Dispersion Factors.
4. CY Calculation REMODCM-01687-SY-00, Connecticut Yankee Haddam Neck Plant ODCM, Terrain Data.
5. CY Calculation REMODCM-01688-SY-00, CY Defueled State- ODCM Dose Conversion Factors for Gaseous Releases.
6. CY Calculation REMODCM-01689-SY-00, Connecticut Yankee Method 1 Dose Equations for ODCM Revision 13.
7. ERC 16103-ER-99-001 1, Input Data for Offsite Dose Calculation
8. ERC-16103-ER-99-012, Basis for 40CFR190 Doses Used to Implement CY REMM/ODCM.
9. ERC 16103-ER-00-0004, "Technical Basis Document, Radiological Environmental Monitoring Program Reduction", Revision 1, Dated 6/12/2000.

IC1. Vendor/CY Calculation No. CY-ESG-02-001, "Estimating the Site-Specific Usage Factor for Fish Consumption (CY)".

11. Vendor/CY Calculation No. CY-ESG-01-001, "Tidal Dilution Flows for Liquid Release Dose Calculations".

ODCM F-1

DE C 2 1 2005 Revision 19 SECTION CA - METHOD 1 DOSE CONVERSION FACTORS LADTAP 11Age-Organ Dose Conversion Factors (rwerrsyr per Clt3/sec)

(For Activity S I Cude; Dilution FPw

  • 1 cis] I 4.44E+02 4.15E+02 3.25E+01 7.48E-01 2.40E+02 7.48E-01 4.43E+01 1.24E-01 1.17E-01 1.13E-01 1.12E4-1 1.15E-01 1.12E-01 3.98E+00 3.02E-01 5.07E-01 E.43E-01 3.022-01 3.02E-01 3.02E-01 5.51E+00 8.00E-01 1.67E+00 2.74E+00 8.00E-01 8.00E-01 8.00E-01 1.84E+01 3.16E+01 3.41E+01 3.71E+01 3.16E+01 3.16E+01 3.16E+01 7.88E+01 2.93E+03 8.96E+03 5.69E+03 1.02E+01 2.26E+03 7.57E+02 1.32E+02 3.76E+03 5.14E+03 3.37E+03 1.50E+01 1.75E+03 5.93E+02 1.14E+02 2.1tE+01 2.18E+01 2.18E+01 2.17E+01 2.19E+01 2.17E+01 3.88E+01 1.96E+01 1.93E+01 1.92E+01 1.92E+01 1.94E+01 1.92E+01 5.14E+01 7.29E-01 8.85E-01 8.83E-01 6.78E-01 7.11E-01 6.78E401 6.32E+00 8.46E+00 4.46E+00 1.04E+00 9.02E-06 9.02E-06 2.49E+00 2.56E+00 0.00E+00 2.22E-03 2.22E-03 2.22E-03 2.224-03 2.22E-03 2.22E-03 2.20E+00 4.51E+01 1.04E+01 2.20E200 1.50E+01 2.20E+00 1.33E+02 3.61E-02 3.59E202 3.59E402 3.594-02 3.59E-02 3.59E-02 4.19E+00 1.25E+00 6.07E201 6.89E401 6.07E-01 1.85E+00 6.07E-1 4.24E+01 1.43E+00 1.37E+00 1.402+00 1.37E+00 1.37E+00 1.42E+00 3.22E+00 1.52E+00 3.47E+00 3.48E+00 3.47E+00 3.47E+00 3.51E+00 3.94E+00 5.45E+02 1.10E+01 2.48E+01 9.12E+00 2.85E-02 2.85E-02 6.80E+03 2.14E+02 6.79E404 6.14E+00 6.79E-04 8.79E-04 6.79E-04 3.43E+01 5.34E+03 7.81E-05 1.31E+03 7.61E-O5 7.81E-05 7.612E-5 1.54E+02 3.58E+02 3.38E+02. 2.85E+01 7.48E-01 1.94E+02 7.48E-01 3.80E+01 125E-1 1.17E-01 1.13E-01 1.12E-01 1.15E-01 1.12E201 3.24E+00 3.02E-01 5.15E401 6.58E401 3.02E-01 . 3.02E-01 3.02E401 4.27E+00 8.OOE-01 1.86E+00 2.78E+00 8.00E-01 8.00E-01 8.00E-01 1.27E+01 3.16E+01 3.41E+01 3.72E+01 3.16E+01 3.16E+01 3.16E+01 6.43E+01 3.OOE+03 7.06E+03 3.28E+03 1.02E+01 2.25E+03 8.65E+02 9.79E+01 4.03E+03 5.35E+03 1.87E+03 1.50E+01 1.83E+03 720E+02 9.09E+01 2.18E+01 2.18E+01 2.18E+01 2.17E+01 2.19E+01 2.17E+01 . 3.15E+01 1.98E+01 1.93E+01 1.92E+01 1.92E+01 1.94E+01 1.92E+01 4.33E+01 7.56E-01 6.86E-01 6.83E-01 8.78E-01 7.08E-01 6.78E-01 4.38E+01 8.76E+00 4.79E+00 1.12E+00 9.022-08 9.02E-08 3.04E+00 2.08E+OO 0.WE+00 1.71E-03 1.71E-03 1.71E-03 1.71E-03 1.71E-03 1.71E-03 2.20E400 4.44E+01, 1.06E+01 2.20E+00 1.48E+01 2.20E+20 8.87E+01 3.81E-02 3.89E-02 3.59E-02 3.59E-02 3.59E-02 3.59E-02 3.56E+00 131E+00 6.07E-01 . 6.95E-01 6.07E41 1.98E+00 6.07E-01 3.42E+01 1A4400 1.37E+00 1.40E+00 1.37E+00 1.37E+00 1.43E+00 2.75E+00 3.52E+00 3.47E+00 3.48E+00 3.47E+00 3.47E+00 3.51E+00 3.82E+OO 5.93E+02 1.18E+01 2.68E+01 9.30E+00 2.85E202 2.85E-02 5.58E+03 2.33E+02 6.79E-04 6.67E+00 6.79E-04 6.79E-04 6.79E-04 2.77E+01 4.46E+03 7.61E405 1.102+03 7.61E-05 7.61E-45 7.61E-5 125E+02 2 63E+02 2.28E+02 2.01E+01 4.19E-01 1.21E+02 4.19E401 1.52E+01 7.89E-02 6.79E-02 6.37E-02 828E-02 6.56E-02 6.28E-02 1.37E+00 1.69E-01 3.59E-01 5.53E-01 1.69E-01 1.69E-01 1.69E-01 1.72E+00 4.48E-01 1.14E+00 2.55E+00 4.48E-01 4.49E-01 4.48E-01 4.46E+00 1.77E+01 1.97E401 2.37E+01 1.77E+01 1.77E+01 1.77E+01 2.90E401 3.82E+03 5.93E+03 1.26E+03 5.73E+00 1.84E403 6.64E+02 3.77E+01 5.06E+03 4.84E+03 722E+02 8.382+00 1.58E+03 5.75E+02 3.86E+01 1.23E+01 1.22E+01 1.22E+01 1.22E+01 1.23E+01 122E+01 1.57E+01 1.12E+01 1.08E+01 1.08E+01 1.08E+01 1.09E+01 1.08E+01 2.00E+01 4.73E-01 3.862-01 3.85E-01 3.80E-01 4.05E-01 3.80E-01 1.71E+01 8.87E+OO 4.712400 1.46E+OO 5.05E-06 5.05E-06 2.86E+00 8.72E-01 O.WOE+001.41E-03 1.41E-03 1.41E-03 1.41E-03 1.41E-03 1.41E-03 1,23E+OO 3.42E+01 1.OOE+01 1.23E+00 1.05E+01 123E+00 2.89E+01 2.04E-02 2.01 E-02 2.01 E-02 2.01E-02 2.01E-02 2.01E-02 1.81E+00 124E+00 3.40E401 4.52E-01 3.40E-01 1.56E+00 3.40E-01 1.44E+01 8.51E-01 7.68E-01 7.96E-01 7.87E-01 7.87E-01 8.14E-01 1.30E+00 2.OOE+00 1.95E+00 1.96E+00 1.95E+00 1.95E+00 1.98E+00 2.08E+00 7.63E+02 1.15E+01 3.42E+01 1.19E+01 1.60E-02 1.60E-02 2.36E+03 3.01E+02 3.80E-04 8.61E+fB 3.80E-04 3.80E-04 3.80E-04 1.17E+01 3.94E+03 4.26E-05 9.98E+02 426E-05 4.26E-5 4.26E-05 5.30E+01 2 .12E02 5 63E+02 3 S0E+02 6 87E401 3 5SE+02 6 87E401 9.94E+01 ODCM APP A-1

0 E C .; 2005 Revision 19 APPENDIX B SECTION C.A - METHOD 1 DOSE CONVERSION FACTORS BASIS Refer to memorandum RB-98-069, subject: Verification of the PCLADTAP.xlt Excel Spreadsheet in Support of the Proposed New CY REMODCM Method 1 Calculation for Liquid Effluent Doses, March 27, 1998 for the Method 1 liquid effluent dose calculation basis.

The basis substantiates the use of: (1) dilution flow, (2) radionuclide activities and (3)

"composite" radionuclide age-organ dose conversion factors (DCFs) (derived from the NRC LADTAF II software program which conforms to Regulatory Guide 1.109) to calculate age-organ doses. These "composite" DCFs include the contributions from all pathways (including pathway age usage's and radionuclide age-organ DCFs) and LADTAP II site-specific parameters, and are acceptable because LADTAP II is used for Method 2.

ODCM APP B-1

DECS212005:

Revision 19 APPENDIX C LIQUID DOSE CALCULATIONS - LADTAP (OR EQUIVALENT)

The LADTAP codes were written by the NRC to compute doses from liquid releases. The actual model used in LADTAP II which performs calculations in. accordance with Regulatory Guide 1.109, Revision 1.

For calculating the maximum individual dose from Haddam Neck, the following options and parameters are used:

1.' Real time, measured dilution flow

2. Fresh water site, no re-concentration
3. Shorewidth factor = 0.1 for discharge canal
4. No dilution for maximum individual pathways
5. One-hour discharge transit time
6. RFegulatory Guide 1.109 usage factors for maximum individual for fish, shoreline, swimming and boating. Site specific fish consumption usage may be used as documented in reference 12.
7. Zero usage for shellfish, algae, drinking water and irrigated food pathways. Shellfish, algae and water are not consumed from the river. Bottled water is provided onsite. The river is not used for irrigation ODCM APP C-1

Revision 19 APPENDIX D GASEOUS DOSE CONVERSION FACTORS (TRITIUM AND PARTICULATE)

This appendix contains a listing of the dose and dose rate conversion factors (DFG and DFG')

for use in the application of the CY ODCM during the decommissioning phase of the plant. The DFGs are for gaseous releases to the atmosphere of tritium and particulate radionuclides, find reflect the following conditions:

(a) On-ground receptors at the closest distance to the site boundary (SB) for ground-level releases, and at the worst-case offsite receptor for elevated releases, (b) Long-lived radionuclides (in view of the extended decay time since permanent plant shutdown on July 22, 1996),

(c) The inhalation pathway for dose-rate calculations, and all pathways combined for dose calculations (ground-shine, inhalation, meat ingestion, goat milk ingestion, and vegetable ingestion), and (cl) The associated worst-case hypothetical individual (adult, teenager, child or infant) and critical organ (Total Body, GI Tract, Bone, Liver, Kidney, Thyroid, Lung, or Skin).

The DFGs were computed using the GASPAR-2 computer code (1), along with 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 D.1 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 1.109(')):

1. The accumulation time for ground contamination (tb) was changed from 20 years to 15 years
2. The transfer rate to meat products (Ff) for Ni was changed from 5.3E-03 (d/kgil to 5.3E-02 (d/kg)
3. The transfer rate to goat-milk (Fm) for Fe was changed from 1.3E-03 (D/L) to 1.3E-04 (D/L)

(c) Tie pathway parameters were assigned the values shown in Table D.1 [from GASPAR-

2. with the exceptions identified under item (b) above].

(1) "GASPAR A Code System for Evaluation of Radiological Impacts Due to the Release of Radioactive Material to the Atmosphere During Normal Operation of Light Water Reactors," Oak Ridge National Laboratory, RSIC Computer Code Collection CCC463 (also released as NUREG/CR-4653, "GASPAR-Il -

Technical Reference and User Guide," March 1987)

(2) NRC Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Rea-tor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", (Rev. 1, 10/77)

.I ODCM APP D-1

D)E C 2 1 6OU0 Revision 19 Table D.1 VEGETATION INGESTION PATHWAY PARAMETER PATHWAY Stored Leafy Agricultural Productivity (kg/m2 ) 2 2 Soil Surface Density (kg/rn 2 ) 240 Transport Time to User(hrs) NA NA Soil Exposure Time (yrs) 15 15 Crop Exposure Time to Plume (hrs) 1440 1440 Holdup after Harvest (hrs) 336 24 Animal Daily Feed(kg/day) NA NA GOAT-MILK INGESTION PATHWAY PARAMETER PATHWAY Pasture Stored Feed Agricultural Productivity (kg/m2 ) 0.7 2 Soil Surface Density (kg/m 2 ) 240 240 Transport Time to User (hrs). 48 48 Soil Exposure Time (yrs) 15 15 Crop Exposure Time to Plume (hrs) 720 1440 Holdup after Harvest (hrs) 0 2160 An::rmal Daily Feed (kg/day) 6 6 MEAT INGESTION PATHWAY PARAMETER PATHWAY Pasture Stored Feed Agricultural Productivity (kg/m2 ) 0.7 2 Soil Surface Density (kg/m2 ) 240 240 Transport Time to User (hrs) 480 480 Soil Exposure Time (yrs) 15 15 Crop Exposure Time to Plume (irs) 720 1440 Holdup after Harvest (hrs) 0 2160 Animal Daily Feed (kg/day) 50 50 ODCM APP D-2

I-.1 %1 a J05 Revision 19 (d) Ste-specific pathway variables were assigned the following values:

Absolute humidity: 8.0 (g/m 3)

Fraction of time leafy vegetables are grown: 0.50 Fraction of individual vegetable consumption from home garden: 0.76 F.action of time milk goats are on pasture: 0.75 Fraction of goat feed from pasture: 1.0 Fraction of time beef cattle are on pasture: 0.75 Fraction of beef-cattle feed from pasture: 1.0

[Note: The cow-milk pathway is less restrictive than the goat-milk pathway and was nDt used in the definition of the final DFGs.]

(e) The usage factors and breathing rates are as listed in Table D.2.

Table D.2 Ingestion Pathway Usage Factors Inhalation Individual (m3 lyr)

Crop Leafy Milk Meat (kg/yr) Vegetables (liters/yr) (kg/yr)

.__.__::___- (kg/yr) . ._.

Adult 520 64 310 110 8000 Teenager 630 42 400 65 8000 Child 520. 26 330 41 3700 Infant 0 0 330 0 1400 (f) The applicable site-specific long-term atmospheric dispersion and deposition factors are presented in Table D.3. It is noted that there are four distinct release points at CY which are classifiable as ground-level releases. The values in Table D.3 are for the worst-case release point.

ODCM APP D-3

U %-1; , +/-4 I j6u1 Revision 19 Table D.3 Undepleted Depleted Deposition RELEASE POINT (X/Q) (X/Q) Factor (sec/m 3 ) (sec/m 3 ) (DIQ) (mu)

Ground- Temporary Tent Exhaust Level (worst-case release point) 3.09E-04 2.93E-04 2.22E-07 Releases Alternate Stack Elevated Primary Vent Stack 2.85E-05 2.85E-05 3.45E-08 Re'eases D.2 D)FG Tabulations The DFGs for tritium and particulate radionuclides were computed through use of GASPAR-2, along with the data and assumptions listed in Section D.1. Summaries of the results are presented in Table D.5 for the inhalation pathway (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 as 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 Inhalation All Pathways Pathway Combined Spent Fuel Bldg Ventilation Exhaust and Spray Cooler 0.39 0.51 Containment Bldg 0.30 0.56 (Terry Turbine Access)

'B' Switchgear Bldg 0.54 0.65 otential Chemistry Fume Hood)

Temporary Tent Exhaust 1.0 1.0

  • Worst-case release point For instance, the Cs-137 limiting DFG for Containment Building releases and all exposure pathways combined is 9.64E-04 (Table D.6) x 0.56 (Table D.4) = 5.40E-04 (mrem-sec/pCi-yr).

ODCM APP D-4

RevCiso 219 Revision 19 Table D.5 CY ODCM - Dose Rate Conversion Factors (DFG')

for Critical Receptor and Organ (Inhalation Pathway)

Dose Rate Conversion Factor (mrem-s clp Ci-yr)

Radionuclide(b) Ground-Level Releases Elevated (a) Releases DFG'ICO(q) DFG'Icoee)

H 3 2.24E-01 2.07E-02

  • MN 54 5.80E+02 :5.65E+0I FE 55 3.63E+01 3.53E+O0 FE 59 4.48E+02 4.35E+01 CO 57 1.72E+02 1.67E+01 CO 58 3.94E+02 3.82E+01 CO 60 2.55E+03 2.49E+02 ZN 65 3.63E+02 3.53E+01 SR 90 1.13E+04 1.1 OE+03 ZR 95 7.89E+02 7.66E+0I NB 95 2.20E+02 2.14E+01 TC99 4.07E+02 3.97E+01 RU103 2.29E+02 2.23 E+O I RU106 4.70E+03 4.57E+02 AGIIOM 1.98E+03 1.92E+02 SB125 8.01E+02 7.79E+01 CS134 3.31 E+02 3.22E+01 CS137 2.66E+02 2.58E+01 CE144 3.91E+03 3.82E+02 EU152 1.17E+03 1.14E+02 EU154 2.97E+03 2.89E+02 PU238 3.50E+06 3.41E+05 PU239 4.07E+06 3.94E+05 PU240 4.04E+06 3.91 E+05 PU241 8.77E+04 8.52E+03 AM241 4.16E+06 4.04E+05 CM242 1.58E+05 1.54E+04 CM243 2.79E+06 2.71 E+05 CM244 2.15E+06 2.09E+05 (a) 'Norst-case release point. Refer to Table D.4 for optional adjustments.

(b) C14, Ni63, 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.

ODCM APP D-5

Revio 5 I 201 Revision 19 Table D.6 CY ODCM - Dose Conversion Factors (DFG) for Critical Receptor and Organ (All Pathways Combined)

Dose Conversion Factor (mremlpCi)

Radionuclide(b) Ground-Level Releases Elevated (a) Releases DFGico(g) DFGico(e)

H 3 4.76E-08 4.39E-09 MN 54 2.81 E-05 3.30E-06 FE 55 7.94E-06 1.21 E-06 FE 59 2.43E-05 3.67E-06 CO 57 6.78E-06 7.36E-07 CO 58 1.52E-05 1.67E-06 CO 60 2.32E-04 3.14E-05 ZN 65 3.97E-05 6.12E-06 SR 90 1.64E-02 2.54E-03 ZR 95 2.67E-05 3.52E-06 NB 95 4.48E-05 6.90E-06 TC 99 9.17E-05 1.42E-05 RU103 6.63E-05 1.02E-05 RU106 9.65E-04 1.49E-04 AG110M 8.70E-05 1.28E-05 SB125 4.33E-05 5.24E-06 CS134 1.01 E-03 1.57E-04 CS137 9.64E-04 1.50E-04 CE144 .1.24E-04 1.58E-05 EU152 1.42E-04 1.99E-05 EU154 1.88E-04 2.37E-05 PU238 1.1IE-01 1.09E-02 PU239 1.29E-01 1.26E-02 PU240 1.28E-01 1.25E-02 PU241 2.79E-03 2.72E-04 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 D.4 for optional adjustments.

(b) C14, Ni63, 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.

ODCM APP D-6

- FDEH: P2 1 2r0 5 Revision 19 APPENDIX E GASEOUS DOSE CALCULATIONS - GASPAR-2 (OR EQUIVALENT)

The GA',PAR-2 code was written by the NRC to compute doses from gaseous releases using the models given in Regulatory Guide 1.109. The revision date of the code is December 1986.

Other codes which implement the guidance provided in Regulatory Guide 1.109, Revision 1, are also acceptable, including Method 1.

For calculating the maximum individual dose from Haddam Neck, the following options and parameters may be used (Method 1):

1. Historical meteorology using a XIQ, D/Q model which incorporates the methodology of Regulatory Guide 1.111. The five year period of 1976 - 1980 was used to determine dispersion estimates.
2. 100% of vegetation grown locally, 76% 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 g/m3.
5. Maximum individual dose calculations for Method 1 were performed at the nearest land site boundary with maximum X/Q. For conservatism in the Method 1 model, this location is assumed to have a resident, vegetable garden, and milk and meat animal with the maximum D/Q value.

ODCM APP E-1

Revision 19 APPENDIX F METEOROLOGICAL DISPERSION FACTORS The ODCM atmospheric dispersion factors were derived using the AEOLUS-3 computer code.

AEOLU.S-3 was written to implement regulatory guidance for continuous (Regulatory Guide 1.111) and intermittent releases (NRC computer code XOQDOQ). The code has various options including building wake effects, plume depletion via dry deposition, and an effective plume height that accounts for physical release height, plume downwash, plume rise, and terrain features.

A set cf atmospheric dispersion factors which are a function of release duration were generated. NUREG/CR-2919 (the documentation package for the NRC atmospheric dispersion computer code XOQDOQ, Reference 1) presents a methodology for determining atmospheric dispersion factors (CHI/Q values) for intermittent releases at user specified receptor locations (intermittent releases being defined as releases with durations between 1 and 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br />).

The CHIUQ values for intermittent releases are determined by linearly interpolating (on a log-log basis) between an hourly 15-percentile CHI/Q value and an annual average CHI/Q 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/Q 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 level release pathways (e.g., Spent Fuel Building ventilation exhaust vent, Spent Fuel Building component spray cooler, Personnel Access Hatch on the Containment Building, 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 evaluating plume entrainment effects and for determining plume rise and ODCM APP F-1

DrC~I, l2 Revision 19 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 pathways.

- The 196'-33' delta-temperature data were provided to the code to determine atmospheric stability for both types of release pathways.

- The Reg Guide 1.111 (Rev. 1) depletion/deposition model was used for determining depleted CHI/Q and DIQ values for both types of release pathways. WVet depletion/deposition and decay-in-transit were not considered.

Meteorological data measured by the onsite monitoring system from January 1976 through December 1980 were used as input to the AEOLUS-3 computer code. Analysis of meteorological data measured at the Haddam Neck Plant during the following five-year periods, 1976-19,30, 1988-1992, 1993-1997, indicated that the lower level wind speed data have been influenced by foliage growth over the years 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 CHI/Q, and D/Q 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 D/Q 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.

The time-dependent equation is:

X/Q=X/Qhrt QAQb (X where X/Qhr is the weighted one-hour 15-percentile value and X/Qht is the long-term average value. For the derivation of the time-dependent equation, see Reference 1.

ODCM APP F-2

Ut)C2'1 2005 Revision 19 The time-adjusted Method 1 dose equation for Particulate and Tritium releases can be written as:

D. QdepIlhr *th- *Z(Q *DFG,.o)

Q depl,Apr-Dec (mre) =  ::2sec/:m3*(

sec/ m

)* E

  • r (mrem) mrem where DCo = The critical organ dose from particulates and tritium;

( =r The 1-hour depleted atmospheric dispersion factor;

  • deplal hr (QJe .A . = -The depleted atmospheric. dispersion factor for the growing t epl,Apr-Dec season (see Section Table F.1);
  • = A unitless adjustment factor to account for a release with a total duration of t hours;
  • = The total activity in [iCi of radionuclide "i" released to the atmosphere during the period of interest; L)FGic, = The site-specific critical organ dose factor for radionuclide "i", based on the age group and organ with the largest dose factor (see Table 3).

Incorporating location-specific (i.e., temporary tent release point) atmospheric dispersion factors and the time-adjustment factor (fa) yields an equation for the determination of critical organ dose. The substituted values are as follows:

8 , hr - 2.89E-03 (sec/m 3 )

(.Q depl,lhpr x- 2.93E-04 (sec/m3) t.Q Jdepl,Apr-Dec ODCIV APP F-3

C,21I(fn>

Revision 19 CDdepljlhr Q = 9.86 (Q depl,Apr-Dec tea .f= to.252 For the maximum off-site receptor location and a ground level release condition, the above values were used to simplify the above time-dependent equation as follows:

Dco(g) =9.86 *U- 2 5 2 *X(Q() *DFGijo(g))

(Inrem)=(.)*(.)*X,(ci*r em)

The long term and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> site specific atmospheric dispersion factors are listed on Tables F.1 and F.2.

ODCM APP F-4

Revision 19

.TABLE F.1 ATMOSPHERIC DISPERSION FACTORS GROUND LEVEL RELEASES Spent Fuei Cont. Bldg 'B" Switch Temporary Max Bldg Access gear/new Tent Ground Hatch Chem Level Pt.

Fume Hood Dispersion Met Data 1-Hour Long-Term 1-Hour Long-Term 1-Hour Long-Term 1-Hour Long-Term 1-Hour Long-Term Factor Period 1- I 1- I i Undepl. X/Q Jan-Dec 1.41 E-03 1.14E-04 8.80E-04 8.98E-05 1.73E-03 1.60E-04 2.82E-03 2.75E-04 2.82E-03 2.75E-04 (sec/m 3) (537 m WNW) (503 m WNW) (457 m WNW) -(360 m WNW)

Apr-Dec 1.53E-03 1.19E-04 9.56E-04 9.35E-05 1.88E-03 1.67E-04 3.07E-03 3.09E-04 3.07E-03 3.09E-04 (537 m WNW) (503 m WNW) (457 m WNW) (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 2.42E-04 2.18E-03 2.42E-04 (537 m WNW) (503 m WNW) (457 m WNW) (360 m WNW)

Max-All Seasons 3.07E-03 3.09E-04 Depl.XIQ Jan-Dec 1.30E-03 1.06E-04 8.14E-04 8.42E-05 1.61 E-03 1.51E-04 2.66E-03 - 2.61 E-04 2.66E-03 2.61E-04 (sec/m 3) (537 m WNW) (503 m WNW) (457 m WNW) (360 m WNW)

Apr-Dec 1.41 E-03 1.11E-04 8.85E-04 8.76E-05 1.75E-03 -1.58E-04 2.89E-03 2.93E-04 2.89E-03 2.93E-04 (537 m WNW) (503 m WNW) (457 m WNW) (383 m W)

Jan-Mar 9.95E-04 9.11E-05 6.24E-04. 7.39E-05 1.25E-03 1.30E-04 2.05E-03 2.31 E-04 2.05E-03 2.31E-04 (537 m WNW) (503 m WNW) (457 m WNW) (360 m WNW)

Max-All Seasons 2.89E-03 2.93E-04 D/Q Jan-Dec 8.95E-07 1.11E-07 7.56E-07 1.22E-07 1.05E-06 1.42E-07 1.48E-06 2.12E-07 1.48E-06 2.12E-07 2

(1/M ) (537 m WNW) (503 m WNW) (457 m WNW) (383 m W)

Apr-Dec 9.25E-07 1.13E-07 7.77E-07 1.25E-07 1.09E-06 1.45E-07 1.54E-06 2.22E-07 1.54E-06 2.22E-07 (537 m WNW) (503 m WNW) (457 m WNW) (383 m W)

Jan-Mar 7.05E-07 1.03E-07 6.21 E-07 1.14E-07 8.34E-07 1.33E-07 1.17E-06 1.90E-07 1.17E-06 1.90E-07 (537 m WNW) (503 m WNW) -* (457 m WNW) (360 m WNW)

Max-All Seasons 1.54E-06 2.22E-07 ODCM APP F-5

Revisior. 19 TABLE F2 ATMOSPHERIC DISPERSION FACTORS ELEVATED (MIXED MODE) RELEASES Primary Vent Stack Dispersion Met Data 1-Hour Long-Term Factor Period Undepl. X/Q Jan-Dec 2.64E-04 2.64E-05 (sec/m 3 ) (617 m NE)

Apr-Dec 2.86E-04 2.85E-05 (617 m NE)

Jan-Mar 2.19E-04 2.02E-05 (617 m NE)

Max - All 2.86E-04 2.85E-05 Seasons Depl.XtQ Jan-Dec 2.65E-04 2.64E-05 (sec/m 3 ) (617 m NE)

, Apr-Dec 2.86E-04. 2.85E-05 (617 m NE)

Jan-Mar 2.19E-04 2.81E-05 (617.m NE)

Max - All 2.86E-04 2.85E-05 Seasons

- D,'Q Jan-Dec i .54E-07 2.33E-08 (Iim2) (932 m E)

Apr-Dec 1.56E-07 2.24E-08 (583 m NNE)

Jan-Mar 1.56E-07 3.45E-08 (1572 m ESE)

Max - All 1.56E-07 3.45E-08 Seasons

References:

1. NUREG/CR-2919, "XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations", September 1982.

ODCM APP F-6

ReJHP§f n1' 2005 ENVIRONMENTAL MONITORING PROGRAM' Sampling Locations The following lists the environmental sampling locations and the types of samples obtained at each location. Sampling locations are also shown on Figures G-1, and G-2.

Location Direction & Distance From Number Name Release Point*** Sample Types 1-lIF On-site-Mouth of Discharge Canal 1.1 Mi, ESE (0.5 Mi, SSE IF) TLD 2-1 1Haddam-Park Rd.- 0.8 Mi, S TLD 3-I Haddam-Jail Hill Rd. 0.8 Mi, WSW TLD 4-1 Haddam-Ranger Rd. 1.8 Mi, SW TLD 5-I On-site-Injun Hollow Rd. (Site Boundary) 0.4 Mi, NW TLD 6-1, IF On-site-Substation (wrin 10 miles) 0.5 Mi, NE (0.6 Mi, NW IF) TLD 7-1 -laddam 1.8 Mi, SE TLD 8-I East Haddam 3.1 Mi, ESE TLD 9-l -ligganum 4.3 Mi, WNW TLD 10-I Hurd Park Rd. 2.8 Mi, NNW TLD 11-C Middletown 9.0 Mi, NW TLD 12-C Deep River 7.1 Mi, SSE TLD 13-C North Madison 12.5 Mi, SW TLD 14-C Colchester 10.5 Mi, NE TLD 15-I On-site Wells 0.5 MI,-ESE Well Water

.16-C East Haddam Town Office Building 2.8 Mi, SE Well Water 17-C Fruits & Vegetables Stand/Supply, normally Approx. 13 Mi, SW Fruits &Vegetables in North Madison (beyond 10 miles; (beyond 10 miles) Broad Leaf Vegetation normally within -2 miles of location 13-C 18-I Site Boundary (Within one mile of 0.4 Mi,'NW Broad Leaf Vegetation Location 5-I) (within 10 miles) 25-I Fruits & Vegetable Stand normally vwin one Approx. 1.0 Mile, NW Fruit & Vegetables mile of Location 5-I (w/in 10 miles) 26-I Conn. River-Near Intake 1.0 Mi, WNW Fish

.27-C .Conn. River-Higganum Light 4.0 Mi, WNW Shellfish 28-I Conn. River-E. Haddam Bridge 1.8 Mi, SE Bottom Sediment, River Water 29-I Vicinity of Discharge 0.0 Mi Bottom Sediment, Fish 30-C Conn. River-Middletown 9.0 Mi, NW River Water, Bottom Sedimen:

7.6 Mi, NW Fish 31-I Mouth of Salmon River 0.8 Mi, ESE Shellfish 48-1 F Onsite Met Tower Shack 0.4 Mi, WSW TLD 52-IF Schmidt Cemetery(onsiteO 0.5 Mi, NNE TLD 53-IF ISFSI Haul Route (onsite) 0.2 Mi, SSW TLD 54-IF Route 149 (near Salmon River mouth) 1.0 Mi, ESE TLD 55-IF High Voltage Tower (onsile, NW of Pad) 0.4 Mi, NW TLD 56-IF Burrow Pit (onsite) 0.2 Mi, E TLD 57-I F Dibble Creek Sediment Sample 0.1 Mi, SE Bottom Sediment 58-IF ISFSI Pad Enclosure Soil Sample Coll. 0.0 Mi Soil

'This table does not require updating based on the elimination of sampling as described In the REMM.

I= Indicator C = Control IF= ISFSI Indicator The release points are the center of the site for terrestrial locations and the end of the discharge canal for aquatic location:;.

The ISFSI pad is the release point for the ISFSI indicators.

ODCM APP G-1

E2 2 'I12Q0R Figure _-

13-A -

1I; Haddiim NecK Piant inner Terresiriai Monitoring Siations ODCM APP. G-2

DEC 2 1 2005 Figure G- 2: Haddam Neck Plant Aquatic and Well Water Sample Stations ODCM APP. G-3

JUL 5 2005 ACP 1;2-2.90 -

Rev. 4 Maj Dr ATTACHMENT 8 Connecticut Yankee REMIODCM Change Request Page 1 of 3 I.

Originator Name (Print): Joe Bourassa (Attach mnrkup pages)

Section No. I Section Title . Page No. . Description of Change & Reason Table E-1 Haddam Neck E-3 Changed items 2, 4, 5 to Annual and added REMP additional information to Note (1). These changes are being made to require one additional sampling event to occur after the bulk SFP water has been discharged. One would not have been required based on the schedule .for performing a discharge by December 2005. No sample is needed in the fall of 2005 because the discharges were very limited and of low activity since June of 2005. Indication over the history of the plant have not indicated any discernable impact on these sample media. No environmental impacts have been identified

.during periods of significantly higher.activity releases from these sampling activities. This change to an annual sample will ensure that one final is obtained after the major radioactive discharges have been made. Obtaining an annual sample of sediment for ISFSI related samples is sufficient to identify any long term trends since radioactive leakage is not from the VCCs and not expected.

F-2 Annual Rad Effluent F-2 Deleted "CY direct radiation from the site" Release Report because it should have been deleted in a previous change and was missed.

Various Various Various Changed "Unit Manager" to "Designated Manager" to reflect the change to the CYQAP.

Table C-I Radioactive Waste C-2&4 Changed Table to reflect the Groundwater Sampling and Treatment is the only discharge remaining from Analysis Program this pathway.

Originato: signature: _ _ _ _ _ _ __ Date: )I 19Jfi5

JUL 5 2005 ACP 1.2-2.90 Rev. 4 Major ATTACHMENT 8 Connecticut Yankee REM/ODCM Change Request Page 2 of 3 II. List the procedures and/or setpoints that require revision in order to implement the proposed change.

Estimated date for Name of Manager implementation responsible to implement ACP 1.2-2.90 11-30-05 Harvey Farr/Kerrv Comi sky III. Technical Reviewers:

Approve or disapprove If disapproving, attach bases.

List procedures/setpoints that require revision in Section II.

Approve [ Disapprove 1i4- - O-5 C emistvy S rvisor Date IV. Radiological Environmental Review:

See change description. Unreviewed Environmental Impact? Yes [ No (3ases Attached)

___ ___ __ ___ ___ __ Approve Disapprove L ,'Il l Technmcal Reviewer Date V. Radiatio1rotectio anager Review:

_ Approve Disapprove Li /zf/y//

Radiation. Protectio i nager Date VI. ComDliance Review:

G Approve Lr*sapprove Li /gjj> § Regulatory Affairs Manager Date

JUL 5 2005 ACP 1.2-2.90 Rev. 4 Major ATTACHMENT 8 Connecticut Yankee REM/ODCM Change Request Page 3 of 3 VII. ISR Review:

(1-&L £G~InCt.g., Approve 'Disapprove D 1 -/'/if gSR Reviewer Date VyI. U 9FSIManager Approval: .

_____X ____________Approve. Disapprove LI /ZJ- -b $

LUnit/ISFSI Manager Date IX.CY ILAC Approval:

(As required).

N/A Approve LI Disapprove'

.IRAC Chairman Date

.X. Verify that the.Section II procedure and/or setpoint changes have been approved and are consistent with this C'hange Request.

Effective Date of REM/ODCM Revision: Nc<

Rersnttv Date Rad tionp P'tection Department Representative :Dt XI. Change sent to Administration for implementation:

RiationProtection Department Representative Date XII. Change documented in Annual Radioactive Effluent Report:

Radiation Protection Department Representative Date

CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD . EAST HAMPTON, CT 06424-3099 December 14, 2005 RP-05-077 To: File Frorm: R. Gault

Subject:

Radiological Environmental Review The change to the REMODCM is being made to correct several minor errors from previous changes, to provide clarifications to several sections and to change the frequency for-sampling and analyzing several Radiological Environmental Monitoring Program (REMP) sampling frequencies.

The changes are minor in nature and have no impact on the program. The administrative and editorial changes are clarification only and do not change the Radiological Effluent Controls Program (RECP) or the REMP. The changes to the sampling and analysis frequencies for the REMP do not have an impact on the program. The data being obtained for the REMP is to validate the effectiveness of the RECP as described in the REMODCM. The liquid radiological effluents released during the second half of 2005 was minimal and had vfery low radiological constituents. There would be notimpact on the environment even at the immediate discharge point based on the amount of water released and the activity concentrations. There is significant dilution water in the canal and it would not have been even detectable in the canal or the Connecticut River. There have been no major indications of environmental impacts identified as part of the REMP sampling activities in the past with much high concentrations of radioactivity released and much greater volumes. The change being made ensures that one additional REMP sampling event will be performed to ensure the effectiveness of the RECP after the Spent Fuel Pool water will be discharged. This will be performed in the May or June timeframe.

This evaluation documents the fact that this change will maintain the level of radioactive effluent control required by 10CFR20.1302, 40CFRI 90, 10CF:R50.36a and 10CFR50 Appendix I and will not adversely impact the accuracy or reliability of effluent dose or setpoint calculations. No Unreviewed Environmental Impact has been identified with this change.

CC: H. Farr File

JJUL D tUM ACP 1.2-2.90 I Rev. 4 Major Attachment 3 Radiological Environmental Review Page 1 of 1 NOTE The following questions relate to the normal use of the proposed change. Any radioactive release resulting from the failure of the proposed change are addressed in a separate 50.59 Evaluation.

Initial "Yes" or "Nit" Yes I No

1. Will the change cause an increase or potential increase in the amounts of radioactive airborne effluents or liquid effluents, or significantly alter the nuclide mix of such effluents?
2. Will the change result in a new radioactive liquid or gaseous discharge point, or decrease the ability to sample or monitor existing release paths?
3. Will the hange significantly increase the eventual number of solid waste shipmenls?
4. Will the Lhange cause movement and subsequent storage of radioactive material in an unshielded area without evaluating RCA boundary dose rate and site boundary dose limitations (10 CFR 20.1301 40 CFR 190)?
5. Will the -hange, in the judgment of the individual performing this review, constitute iL an increased Radiological Environmental Impact for reasons not already considered above?

If the answer is "Yes" to ANY of the above questions, develop a plan to address the issue with Radiological Engineering. This determination was made by:

Th 4 L - X6 Re v+gSt/I i r D t ea o<

IJ2J6 7 Reviewer Date 11 of 22

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