ML061280276

Rev. 18 to Section II, Offsite Dose Calculation Manual for the Haddam Neck Plant

ML061280276
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Issue date:	03/30/2005
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MAR 3 0 2005 SECT[QNA1 OFFSiTE DOSE CALCULATION MANUAL For The HADDAM NECK PLANT Docket No. 50-213 ODCM Revision 18

MAR 1 ( 2005 Revision 18 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-A

a. Critical Organ Dose Rate from Particulates and Tritium D-A D.2 10CFR50 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 40CFR1 90 Limits D-5 E. LIQUID EFFLUENT RELEASE CALCULATIONS E.1 Discharge Line Flow Rates E-1 F. REFERENCES F-1 ODCM T of C -I

MAR 3 0 2005 Revision 18 HADDAM NECK PLANT OFFSITEDOSE 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 T ofC-2

MAR 3 0 2005 f3evision1.8 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

MAR 3 0 2005

.. . ............. Revision

.... 18 A. INTRODUCTION Connecticut Yankee Quality Assurance Program (CY QAP), requires that Section II of the REEMODCM 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 I 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

MAR 3 Go 2005 Revision 18 B. RESPONSIBILITIES 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 of this manual.

ODCMIB B-1

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 I

a. Monthiv 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 maximum organ doses-by using Ihe 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 (Cl) by the dilution flow (ft3lsec) and then multiplying that result by each of the age-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 1 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

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 do.ses, 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 1 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

MARS 3 () 2005

- Reevision 18 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 like y to cause quarterly and annual off-site dose or dose rate limits to be exceeded. Site specific dose factors used in Method 1 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 compiter 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 tha n 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-2.41 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

MAR 3 0 2005 Revision, 18 (1) Method 1 For ground-level releases the critical organ dose rate to the maximum off-site receptor is determined as follows:

DCo(g) = E(Q*DFG!co:(g))

_ CmremJ

• mrem -sec yr sec uCi-yr )

where:

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

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

DFGjcO(g) = The site-specific critical organ dose rate factor for a ground-level release (see Appendix D, Table D-5) (m )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.4X (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 tnat implements Regulatory Guide 1.109, Rev. I 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. 10CFR50 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

MAR 3 0 2005 Revision 18

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 receDtor location is calculated:

Dco(g) = E(Qi(g) DFGcO(g)S)

(mren)= 1iPci* ci )

where:

Qj(g) The total activity in piCi of radionuclide gi released to the atmosphere from ground-level release points during the period of interest.

DFGico(g) The site-specific critical organ dose factor for radionuclide Ui., 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

MAR 3 O2005

-- Revisio- 18 (2) Method lb (For around 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 temporary 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 I dose equation for Particulate and Tritium releases is:

Dco(g) =9.86* -t22* (Qi(g): *DFGICO(g) i mrern)=( )*( )*Z(PCi* cin)ren where:

Dc, 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).

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

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

DFGio = 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 tle 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

MAR 3 0 2005 Revision 18 -

the 1 st and 4th quarters and the doses from milk consumption can be neglected during the first quarter since winter conditions eliminate the out door growirg 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 tri:ium 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= ZDQMO 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 40CFR190 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 40CFRI90 limit evaluation.

d. Since all other uranium fuel cycle sources are greater than 20 miles away, they need not be considered.

ODCM D-5

MAR 3 0 2005 Revision 18 E. LIQUID EFFLUENT RELEASE CALCULATIONS I

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 I 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 I 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.

CD.- .

ore - Lai -

MPC, where: SR = Summation of the MPC ratios

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

ODCM E-1

MAR 3 01 2005 Revisicn 18 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.

rSR DFmin = FmaxX 1 QAF )

where: DFmIn = Minimum required dilution flow for the radioactive liquid release based upon Fm. (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 dilution 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 flow.

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

ODCM E-2

MAR 3 0 2005 Revision 18 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 Levers.

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-99-0011, 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.

10. 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

MAR 3 0 2005 Revision 18 APPENDIX A SECTION C.1 - METHOD I DOSE CONVERSION FACTORS LADTAP 11Age-Organ Dose Conversion Factors (rsenVyr per CIt3Irsec)

[For Activity

• I Cudle;Dilution Flow

• 1 cdsj I s 66000 5.66E+00 5.66E+00 5.65E+00 5.67E+00 5.65E+00 8.91E+00 4.440+02 4.15E+02 3.25E+01 7.48E-01 2.40E+02 7.48E-01 4.43Et01 1.24E-01 1.17E-01 1.13E-01 1.12E-01 1.15E401 1.12E0-1 3.98E+00 3.02E-01 5.07E-01 6.43E-01 3.02E-01 3.02E401 3.02E-01 5.51E+00 8.00E-01 1.67E+00 2.74E+00 8.00E-01 8.00-01 8.00E401 1.84E+01 3.18E+01 3.41E+01 3.71E+01 .,3.16E+01 3.16E+01 3.16E+01 7.66E+01 2.93E+03 6.96E+03 5.69E+03 1.02E+01 2.26Et03 757E+02 1.32E+02 3.760+03 5.14E+03 3.37E+03 1.50E+01 1.75E+03 5.93E+02 1.14E+02 2.19E+01 2.18E+01 2.18E+01 2.17E+01 2.19E+01 2.17E+01 3.68E+01 1.96E0o1 1.93E+01 1.92E+01 1.92E+01 1.94E+01 1.92E+01, 5.14E+01 7.29E4-1 6.85E401 6.83E401 67SE-01 7.11E401 6.SE-01 6.32E+00 6.460+00 4.46E+00 1.04E+00 9.02E406 9.02E406 2.49E+00 2.56E+00

.000E+00 222E-03 2.22E-03 222E043 2.22E403 2.22E403 222E-03 2.200+00 4.51E+01 1.04E+01 2.20E+00 1.50E+01 2.20E+00 1.33E+02 3.61E-02 3.5sE-02 3.59E-02 3.59E-02 3.59E-02 3.59E-02 4.19E+00 1.25E400 6.07E-01 6.89E401 8.07E-01 1.85E+00 6.07E-01 4.24E+01 1.43E+00 1.37Et00 1.40E+00 1.37E+00 1.37E+00 1.42E+00 3.22E+00 3.520+00 3.47E+00 3.48E+00 3.47E+00 3.47E+00 3.51E+00 3.94E+00 SA.5E+02 1.10E+01 2.74E+01 9.12E+00 2.85E-02 2.sE0-02 61.0E+43 2 .1401 6 3.4104 3.14E+00 6.7E604 6.79E104 3.7E604 3.43Et01 5.34E+03 7.01405 1.31.E+03 15.1E045 7.61E204 7.618E84 19.4E+02 2 s~2 723E+02 3,27E+02 1 3E+00 4.s4E+02 I 23E+00 45 0e~o 4.650403 5.350403 1.66E+00 .67E+3 51. .6700 5.20E+009.09E+00 3.8Et02 3.32E102 2.61E*01 7.4sE41 1.94E+02 72.140E1 3.60E+01 1.25E041 1.17E041 1.13E041 1.12E401 1.15E401 1.12E401 3024E+00 3.02E-01 5618E-01 6.58E-01 3.02E4-01 3.02E-01 3.02E-01 4.27E+00 0.00E401 1.66E+00 2.78E+00 1.E1-01 8.00E-01 8.00E-01 1.27E+01 3.16E+01 3.41E+01 3.72E+01 3.16EtO1 3.16E+01 3.16E+01 6.43E+01 32.2E+03 7.06E+03 3.20E+03 1.02E+01 2.18E+03 8.62E+02 9.70E+01 4.03.E+03 5.35E+03 -

1.87E+03 .50E+01 1.83E+03 7.20E+02 3.60E+41 2.18E+1 26.0E+01 26.9E+01 2.17E+01 2.15E+01 2.17E+01 3.12E+01 1.94E+01 1.93E+01 1.42E+O0 1.327+01. 1.34E+01 1.42E+01 4.33E+01 53401 6.86E401 6.83E401 9.637401 7.8E0-01 6278E-01 453.E+01 6.76E+00 4.79E+00 1.12E+00 .02E-04 9.02E-046 3.04E+00 2.08E+40 0.00E+O 1.71E403 1.71E043 .71E-3 1.71E-03 1.71 E-4 1.21E403 z.20E+00 4.44E+01 1.06E+01 2.20E+00 4.SE+01 2.203+00 3047E+01 3.17E402 3.597042 3.51E402 3.19E042 3.51E802 3.51E402 3.56E+00 7.30E+0 68.79-01 6.39E-01 6.07E-02 1.56E+00 6.280-021 372E+01 1.04E+0 1.37E0-0

. AOE+00 1.37E+00 1.37E+00 1.43E+00 21.7E+00 3s2E+Do 3.47E+00 3.48E+00 3.47E+00 3.47E+DO 3.51E+00 3.s2E+00 5.93E+02 1.18E+01 2.64E+01 9.30E+D0 2.85E-02 2.48E-02 4.48E+03 1.33E+02 6.79E404 65.7E+00 1.770404 B.770404 6.7-0401 2.77E+01 4.42E+03 7.619E-0 1.10E403 7.71E30o 7.61.E405 7.640-02 .25E+02 1.0604 4.0 .223402 .123E+00 4.58E+02 71E+ 5.23E+00 3.04E+02 3.7+0 3.17E+00 3.17E+00 3.17E+00 3.18E+00 3.17E+00 3.s3E+00

.253+02 2.26E+02 2.01E+01 4.2E401 1.21E+02 4l12E401 1.52E+01 7.12E402 .879E402 6.37E402 6128E402 6.s6E402 8.20E402 1.37E+00 146.E-01 3.59E-01 5.53E401 13.8E-01 140E5-01 1368E-01 1.72E+00

.487E401 .71E400 2.54E+00 454sE.01 44sE0-01 42.sE401 4.46E+00 1.77E+01 1.97E+01 2.37E+4 1 1.77E+01 1.77E+01 1.77E+01 21.0E+-1 3.62E+03 5.s3E+03 1.26E+03 5.73E+00 1.84E+03 E.64E+D2 3.77E+01 5.06E+03 4.84E+03 722E+02 8.3sE+Do 1.58E+03 5.75E+02 3.86E+01 123E+01 t22E+01 1.22E+01 1.22E+01 1.23E+01 1.22E+01 12.7E+01 1.12E+01 1.0E+01 12.0E+01 12.0E+01 12.0E+01 12.0E+01 2 .00E+01 4.73E401 3.E6E401 3.4.5201 3.40E-01 1.5E041 3.80E-01 1.71E+01 s.87E+00 4.71E+00 7.45E+6 0 7.05E-06 7.7E-016 2.66E+00 8.72E040 0.00E+00 1.41E403 1441E403 1.41E403 1.41E43 1.41E403 1A41E403 123E+00 3A1E501 1.0E+01 1.23E+00 1.95E+01 123E+00 2.80E+O0 2.04E402 2.01E402 2.01E402 2.01E402 2.01E42 2.01E402 1.61E+00 1.24E+00 3.40E401 4.52E401 3.40E401 1.56E+00 3.40E401 1A44E+01 8.51E-01 7.68E-1 7.96E-01 7.87E401 7.67E401 8.14E401 1.30E+00 2.00E+oo 1.95E+00 1.96E+00 1.95E+00 1.ssE+00 1.s8E+00 z 08E+0 7.63E+02 1.1SE+01 3.42E+01 1.19E+01 1.60E-02 1.60E-02 2.36E+03 3.01E+02 3.80E004 8.61E+00 3.80E-04 3.80E-04 3.80E.04 1.17E+01 3.94E+03 42-E45 9.90E+02 4.26E-05 4.26E0- 4.26E-05 5.30E+01 2.12E+02 5 63E+02 3,50E+02 887E-01 3 55E+02 8 87E-01 9 94E+O1 ODOM APP A-1

MAR 3 { 2005 Revision 18 -

APPENDIX B SECTION C.1 - 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 N.RC 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

MIAR ', 0 2005 Revision 18 APPENDX-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. ',horewidth factor = 0.1 for discharge canal

4. No dilution for maximum individual pathways

5. One-hour discharge transit time

6. Regulatory 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.aThe river is not used for irrigation ODCM APP C-1

MAPFRevision~l 3 0 20 APPENDIX D GASEOUS DOSE CONVERSION FACTORS (TRITIUM AND PARTICULATE)

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

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, and reflect the following conditions:

(;3) 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 (d) 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 fcr consistency with Reg. Guide 1.109l')):

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/kg) 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) The 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 CCC-463 (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 Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I",(Rev. 1, 10/77)

ODCIV APP D-1

MAIR 3 0 2005 Revision 18 Table D.1 VEGETATION INGESTION PATHWAY PARAMETER PATHWAY Stored Leafy Agricultural Productivity (kg/n 2 ) 2 2 Soil Surface Density (kg/n 2) 240 240 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/rn2 ) 0.7 2 Soil Surface Density (kg/m2 ) 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 Animal Daily Feed (kg/day) 6 *6.

MEAT INGESTION PATHWAY PARAMETER PATHWAY

. Pasture Stored Feed Agicultural Productivity (kg/rm2 ) 0.7 2 Soil Surface Density (kg/mr2) 240 240 Transport Time to User (hrs) 480 480 Soil Exposure Time (yrs) 15 15 Crcp Exposure Time to Plume (hrs) 720 1440 Holdup after Harvest (hrs) 0 2160.

Animal Daily Feed (kg/day) 50 50 ODCM APP D-2

MAR 3 0 2005 Revision 18 (d) Site-specific pathway variables were assigned the following values:

Absolute humidity: 8.0 (gfm3)

Fraction of time leafy vegetables are grown: 0.50 F:raction of individual vegetable consumption from home garden: .0.76 Fraction of time milk goats are on pasture: 0.75 F:raction of goat feed from pasture: 1.0 F:raction 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 not used in the definition of the final DFGs.]

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

Table D.2 Ingestion Pathway Usage Factors Inhalation Individual . ._._._. (m3 /yr)

Crop Leafy Milk Meat (kglyr) 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

NkvPi' is on J)82005 Table D.3 Undepleted Depleted Deposition RELEASE POINT (X/Q) (X/Q) Factor

_ (sec/M 3 ) (sec/M 3) (D/Q) (m)

Ground- Temporary Tent Exhaust L.evel (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-OE; Releases D.2 DFG 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 DA4.

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 (potential 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

Revision 18

. MAR 3 0 2005 Table D.5 CY ODCM - Dose Rate Conversion Factors (DFG')

for Critical Receptor and Organ (Inhalation Pathway)

Dose Rate Conversion Factor (mrem-s c/lpCi-yr)

Radionuclide(b) Ground-Level Releases Elevated (a) Releases DFG'icotal DFG'ic e H 3 2.24E-01 2.07E-02 MN 54 5.80E+02 5.65E+01 FE 55 3.63E+01 3.53E+00 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.IOE+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

- RUI03 - 2.29E+02 2.23E+O I RU106 4.70E+03 4.57E+02 AGIIOM 1.98E+03 1.92E+02 SB125 8.01E+02 7.79E+01 CS134 .3.31E+02 . 3.22E+01 CS137 2.66E+02 2.58E+01 CE144 3.91E+03 3.82E+02 EU152 1.I.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) 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 dDse and are not included in the sampling tables of the REMM.

ODCM APP D-5

Revision 18

-MAR 3 (- 200S Table D.6 CY ODCM - Dose Conversion Factors (DFG) for Critical Receptor and Organ (All Pathways Combined)

Dose Conversion Factor (mrem/pCi)

Radionuclide(b) Ground-Level Releases Elevated (a) - Releases DFGicofp) DFGIcofel H 3 4.76E-08 4.39E-09 MN 54 2.81E-05 3.30E-06 FE 55 7.94E-06 1.21E-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 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 1.11E-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

Revisicon 18 II8PAR 3 0 2005 GASEOUS DOSE CALCULATIONS - GASPAR-2 (OR EQUIVALENT)

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

Other o:des 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 X/Q, 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 I 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 18.

APPENDIX F MAR 3 0 2005 METEOROLOGICAL DISPERSION FACTORS The ODCM atmospheric dispersion factors were derived using the AEOLUS-3 computer code.

AEOLUS-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 of 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 CHIIQ 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 D/Q 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-mcode 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

- -IV.A-3 0 2005 Revision 18 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 D/Q values for both types of release pathways. Wet 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, 1976-1980, 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 frac:ion 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=XlQhrt ( X/Q,,()

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

MAR 3 0 2005 -Revision 18 The time-adjusted Method 1 dose equation for Particulate and Tritium releases can be written as:

Dc. - Qjd ,, *tea *E(Q.* DFGi.o)

Q tepl, Apr-Dec (mrein) = c 3 *(

)*E(UCi)*(m7reLm "1 (sec/ m3 where

= The critical organ dose from particulates and tritium;

= The 1-hour depleted atmospheric dispersion factor; (iQ deplj1 hr

[Xl - The depleted atmospheric dispersion factor for the growing QQdepltiApr-Dec season (see Section Table F.1);

= A unitless adjustment factor~to account for a release with a'total duration of t hours; i = The total activity in jiCi of radionuclide "il"released to the atmosphere during the 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 Table 3).

Incorporating location-specific (i.e., temporary tent release point) atmospheric dispersion factors aid the time-adjustment factor ((8) yields an equation for the determination of critical organ dose. The substituted values are as follows:

( X 2.89E-03 (sec/n 3

)

Q deptJhr

_X 2.93E-04 (sec/n?)

2 depl,Apr-Dec ODCM APP F-3

MAR 3 0 2006evision 18 Q dept ,lhr hi) =9.86 tIQ depl,Apr-Dec 25 2 ta .t-.

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:

.D,(g) =9.86*t 52 * (Qg(g) *DFGJc.(g))

• mrem )=

(*(*E(ci*"cm)

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.

ODCIV APP F-4

Revision 18 TABLE F.1 MAR 43 0 2005 ATMOSPHERIC DISPERSION FACTORS GROUND LEVEL RELEASES Spent Fuel 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

. .4 Undepl. XIQ 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/r 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-t03 .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 1.382-04 2.18E-433 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.XlQ Jan-Dec 1.30E-03 1.06E-04 8.14E-04 8.42E-05 1.612E-03 1.51 E-04 2.66E-I03 2.61 E-04 2.66E-03 2.61 E-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-I33 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-i 03 2.31E-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 DIQ 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 6.21E-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 I 1.54E-06 2.22E-07 ODCM APP F-5

Revisio., 18 TABLE F2 MAR 3 O2005 ATMOSPHERIC DISPERSION FACTORS ELEVATED (MIXED MODE) RELEASES Primary Vent Stack Dispersion Met Data 1-Hour Long-Termn Factor Period Undepl. XIQ 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.XJQ ian-Dec I 2.65E-04 2.64E-05 (sec/m3) (617 m NE)

Apr-Dec 2.86E-04

• 2.85E-05

- (617 m NE)

Jan-Mar 2.19E-04 2.01 E-05 (617 m NE)

Max - All 2.86E-04 2.85E-05 Seasons D/Q Jan-Dec 1.54E-07 2.33E-08 (I m2)

(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 ol Routine Effluent Releases at Nuclear Power Stations", September 1982.

ODCM APP F-6

Revision 18 APPENDIX G MAR 3 0 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 TVpes 1-I,IF On-site-Mouth of Discharge Canal 1.1 Mi, ESE (0.5 Mi, SSE IF) TLD 2-1 Haddam-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 Haddam 1.8 Mi, SE TLD 8-l East Haddam 3.1 Mi, ESE TLD 9-l Higganum 4.3 Mi, WNW TLD 10-1 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) 25-1 Fruits & Vegetable Stand normally w/in one Approx. 1.0 Mile, NW Fruit & Vegetables mile of Location 5-I (w/in 10 miles) 26-1 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 29-1 vicinity of Discharge 0.0 Mi Bottom Sediment, Fish 30-C ^onn. River-Middletown 9.0 Mi, NW River Water, Bottom Sediment 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 (onsite, NW of Pad) 0.4 Mi, NW TLD 56-IF B3urrow Pit (onsite) 0.2 Mi, E TLD 57-IF Dibble Creek Sediment Sample 0.1 Mi, SE Bottom Sediment 58-IF ISFSI Pad Enclosure Soil Sample Coll. 0.0 Mi Soil

'This table coes 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 locations.

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

ODCM APP G-1

MAR 3 02005 R'verdeleWscetr C Ihse+/-rj>

• astlampon('

>/t- ilrth2: '

DeSeck f" a

1/4ad p '9 *t~ 4% JSalem WaliU Ld 0 E~~astHtda 55n -. 92d-

,Cheser

~ AcimmiCe{

ad e~r e' Ceterbo r "1/4t nnrMoiorn rIII ODCM APP.iG-2

iMAR 3 0 2005

- 'Coalt Mddle

'II O. -

f '

CO3 1T 1 ER T C -

Lees-,V F2 Oll Figure G- 2: Haddam. Neck Plant Aquatic and Well Water Sample Stations ODCM APP. G-3

MAR 3 0 2005

, . S .. ... . .NOV-10-204 ...

ACP 1.2-2.48 Rev. 4 Attachment 2 Connecticut Yankee REM/ODCM Change Request Page 1 of 3 Check One: R REMM Change R ODCM CChange hange Request # 2005-02 I.

Originator Name (Print): Allen Yates (Attach mrrarkup pages)

Section No. Section Title Page No. Description of.Change & Reason

. nChanged reference from Technical Specification to CY A. Introduction A-Il . QP

________QAP.

Page numbers and section updated to incorporate this Table of Contents TOG 1Ieiin

. revision.

Removed example, CW and SW flow no longer available, C. Liquid Dose Calculations C-I clarified the requirement for flushing 125 million gallons C. . . is only required if the dilution flow rate (other than tidal)

__ is going to be used in the Dose Calculations.

Reworded "Site Dose Rate Limits" to include particulate and tritium only. Noble Gas (Kr-85) is no longer:

considered a release source after the spent fuel has been transferred to the ISFSI.

Removed portions of sections associated with Kr-85 dose calculations and release limits. Spent Fuel transfen-ed to D-l through the ISFSI.

Gaseous Dose D-7 of the D. Calculations current Removed portions of sections associated with Elevated revision. Release - Mixed Mode Releases, the plant Stack hzs been removed and this release pathway is no longer valicd Ground Level releases are the only pathways available for monitoring.

Sections and pages were renumbered to account for the above changes.

Revised opening discussion to clarify that the instrument required in the REMM does not have an associated alarm.

This was necessary since the operational requirements for the Radiation Monitor R-22 is no longer required in the applicable sections of the REMM.

E. Liquid Effluent Release E-1 Revised the title for section E.l to remove the reference to Calculations R-22 operation. Flow rate instrument associated with the release will be required to be in service or applicable action statements in the REMM are in place prior to liquid releases.

MAR 2 0 2Inns

- -_ NOV102004 ACP 1.2-2.48 Rev. 4 Attachment 2 Connecticut Yankee REM/ODCM Change Request Step I and Step 2 calculations were revised to implement calculating release limits based upon release rate aid dilution flow. An Administrative Factor (AF) will be utilized in a manner similar to the current revision. The AF will be included in procedure guidance that will require the Unit Manager approval for revision. The method will determine the sum of the MPC ratios and if Liquid Effluent Release E. E-1 less than a certain AF, release rate is not restricted. In Calculations other words if the activity in the liquid to be released is a certain factor below the MPC limits at the site boundary, then the release is not limited by flow rates since the radioactivity concentrations were very low. If the cum of the MPC is greater than the AF, then the estimated flow rate and required dilution flow will be set in a conservative manner.

o MRemoved the Spent Fuel Building Noble Gas Activity F.  :-F- Monitor R-1. This monitor is not required after the spent F. Setpoints -fuel has been transferred to the ISFSI.

Removed reference 7 and 9 that dealt with Spent Fuel R nBuilding ventilation. Not applicable to future operation of the ventilation system that will be in service after fuel transfer.

Liquid Dose Calculations Removed the statement placed in #5 that discussed the Appendix C - LADTAP (or APP C-1 approximate time to reach 12 canal length equivalent)

Environmental Added note to clarify that the elimination of sample.s in Appendix (3 Mnv i rogme APP G-1 the REMM does not necessitate an update to this table.

___ __ ___ ___ ___ ___ _ _ ___ ___ __ Reworded reference to stack, no longer on Ltmd P Removed Appendix H, Kr-85 dose factors will no longer be required after the transfer of the spent fuel to the ISFSI.

Table H.I Dose and Dose Rate APP. H-7 Removed table associated with Kr-85 dose rate factors.

Factors for Kr-85 O signature: &/ L47 Date: 3 -

0

-NOV-10 MI1P on2flji5.

26ifT.

.~- . . .- . .2. . .L .

ACP 1.2-2.48 Rev. 4 Attachment 2 Connecticut Yankee REMIODCM 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 imlementation responsible to implement CGG~~~~~-~) - -- s< r v--8_

.-.  ? 'r - .Vy ?7-2 -b. b'I

)A...r-y .

-- (?%kis A 0dO3 ..kA *-F'-yT 3-2~-

9 - A~.in- 02 \ -4:Y-r III. --

Technical Reviewers:

• -Approve or disapprove

. If disapproving, attach bases.

• Jsraced etpoints that require revision in Section II.

Approvffr[Disapprove E 0 3 eeistyupervisor Date 2-5<J>6ta t7 - \0 -) at O5 zt Radiological Environmental Review: *

• Unreviewed Environmental Impact? Yes El No  :

(Bases Attached)

_ _ __ _ __ _ _ __ _ _ _ QApprove Disapprove E1 __ __ __ __

-cchnical Reviewer Date V.

ajrr c ti ectio Manager Review:

_ '_ / Approve E:Disapprove 0 3- -&

Radiation PrttLcon Manager Date VI.

Compliance Review:

b 'ac & VA) Approve E/Disapprove Mn 3 . o05 Regulatorf Affairs Manager ,? Date

MAR .902lfl NOYVJ0-2004.

ACP 1.2-2.48 Rev. 4 Attachment 2 Connecticut Yankee REMIODCM Change Request Page 3 of 3 VII.

ISR Review:

+i x) viewer Approve B*isapprove 73 iDatje5 1 R Reviewer Date VIEI.

Unit/[SF~~Ianager Approval:

UnioI[S M /1X1. SApprove Al. EP'Disapprove L 3 / Oe Unit/ISFSI Manager Date CY IRAC Approval:

(As required)

_ __ _ _ _Approve Disapprove v _

IRAC Chairman Date X.

Verifiy that the Section II procedure and/or setpoint changes have been approved and are consistent with this Change Request.

Effective Date of REM! CM Revision: Ad 6oI6G Radiation Protectio Depa ent Representative Date XI.

I Change sent to Adminis ion for imp2lnrentation:

Radiation Protection ep!+/-ef t Representative Date I XII. kJ Change documented in Annual Radioactive Effluent Report:

Radiation Protection Department Representative Date I

m .,i nvn ;

nel

'4 1,IO2AID Rev. 4 Attachment 2 Connecticut Yankee REMIODCM Change Request Page 1 of3 Check One: Z REMM Change [ ODCM Change Change Request # 2005-(1I I.

Originator Name (Print): Allen Yates (Attach markup pages)

Section No. Section Title Page No. Description of Change & Reason:

Table of Contents TOG I Page numbers associated with listed sections updated to incorporate this revision Changed reference from Technical Specifications toCY QAP. Technical Specifications will be incorporated into

. CY QAP Program. The CY QAP maintains contrcl over the submittal of the Annual Radioactive Effluent Report.

B. Definitions BClarified the definition for "Members of the Public" to be

.__ _ consistent with regulatory definitions..

Changed reference from Technical Specifications to CY B. Definitions B-2 QAP. Technical Specifications will be incorporated into CY QAP Program. The CY QAP maintains control over the submittal of the Annual Radioactive Effluent Report.

Add notation "h" to Continuous Release Source block.

Table C-1, "Radioactive Notation "e" revised to allow monitoring from individual C.1 Liquid Waste Sampling C-2 release sources to Yard Drain 6. This will provide and Analysis Program" guidance for other groundwater related releases tha:

require monitoring and will be discharged to the canal.

Liquid Effluents Revised LLD equation to include parameters associated C.I Sampling and Analysis C-3 with gross analysis.

Program Revised notation "e" to require sampling whenever releases are ongoing, removed the "only when mat sump N%

C Table C-I, Table Cin operation" requirement. Added guidance for obtaining

. Notations samples from individual release points that may be applicable if multiple sources are discharging to the YD6 concurrently.

Table C-l, Table Revised notation "g" to remove reference to R-22. This C.alNotations Cal monitor is being removed as a requirement in this revision of the REMODCM.

Added notation "h". This additional notation describes the flexibility needed for designating release points in a decommissioning atmosphere. As the yard drain system is removed the release of groundwater will still be monitored C. Notations C-4 in accordance with the REMODCM, just at another location. An example of other locations would be the next downstream catch basin, effluent of groundwater water treatment system or other piping designed for release purposes.

1\,

MAR n 0 PA11.5 NOV 10 2004 CP i.2:2A,.

Rev. 4 Attachment 2 Connecticut Yankee REM/ODCM Change Request Instrumentation, Removed the "AlarmlTrip" from applicable area-3. No C.3/4 Radioactive Liquid C 10 longer needed since R-22 monitor is not required.

Effluent Monitoring Instrumentation Instrumentation, Removed the asterick from applicability section amd the Radioactive Liquid associated explanation at the bottom of the page. The 0.314 Effluent Monitoring guidance for the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> operability statement is no longer Instrumentation needed since R-22 is no longer required.

nr o :Removed the channel checks associated with R-2.2 Radioactive Liquid operation from the surveillance requirements. Since R-22 C.34 R vC-10 is no longer included in the REMODCM these checks are Effluent Monitoring no longer required. Not applicable to remaining Instrumentation

. instrumentation.

Instrumentation, Modified the bases to coincide with the removal of R-22 C.3/4 Radioactive Liquid C-l I from operation. Compliance for release rate monitor is

. Effluent Monitoring still effective.

Instrumentation '

Removed the Gross Monitor (R-22) from the required monitoring instrumentation table for the following reasons:

• The reduction in available dilution water flow has significantly decreased the gamma concentration level allowed to be released. The acceptable level is less than the required minimum detection level of the monitor as described in the FSAR.

• The release tank is a single entity that cannot be c:-oss connected to other systems. The piping is separate from C.3.4 Table C.3.3

.- 12 all other plant systems. There is no possible release of the wrong tank or turning the wrong valve to initiate the release.

• The release rate monitor will stay in service and applicable conservative restrictions are already implemented.

• The release rate is expected to be limited by the tritium concentration. Tritium cannot be measured by the monitor.

Removed flow rate requirement for discharge canal. Tidal flow is used for dose calculation in accordance with the C.3.4 Table C.3.3 C-12 ODCM. Actual flow rate used for release rate calculations in accordance with the ODCM. This is no longer an effective monitoring parameter.

C.3.4 Table C.3.3 C-12 Removed the asterisk from the bottom of page, statement 3is no longer applicable.

C.3.4 Table C.3.3 Action C-13 Removed action 46 since R-22 is no longer required.

_ _ Statements

MAR S 0 2005 NOV 10 2004

- - - -ACP i.2;24;3 - -

Rev. 4 Attachment 2 Connecticut Yankee REMIODCM Change Request C.3.4 Table C.4.3 C 14 Removed Gross Radioactivity Monitor (R-22)

Csurveillance requirements, no longer in service.

Removed discharge flow rate requirement. No longer a useful requirement since releases are of short duration and

.. Tab C.. tidal flow used for dose calculation in accordance with the ODCM.

Removed notation 2, 3 and 5 since R-22 no longer included in the REMODCM.

Removed notation 4, no longer required. This C.3.4 Table C.4.3, Table C-15 requirement is associated with continuous around the

. Notations clock releases. These type releases are no longer performed.

Removed annotation at bottom of page, no longer required since R-22 removed.

Table D-I, "Radioactive Remove Spray Cooling System from Table D-l.

D. IuThis system will no longer be required after fuel transfer D1Gaseous Waste Sampling D-2 i opee and Analysis Program" I"Radioactive Remove Spent Fuel Building Exhaust from Table D-1.

TlX, .Spent Fuel no longer stored in the SFP. Release psthway

-D. 1 Gaseous Waste Sampling Dwill transition to miscellaneous sample point.

and Analysis Program" Table D-1, "Radioactive Remove Main Stack / Alternate Stack from Table 1)-i.

D. 1 Gaseous Waste Sampling D-2 This release point is no longer in service.

and Analysis Program"_

Ra i.Add weekly sampling requirement for tritium to Table D-1, Miscellaneous Points. Tritium sampling will be'required D.lI Gaseous Waste Sampling D-2 D. Analysis Program"i C - from a Spent Fuel Building exhaust point until the liquid and Ais drained from the Spent Fuel Pool.

Table D-l, "Radioactive Modify Table D-1, Table Notations, "b", to include the D.1 Gaseous Waste Sampling D-3 ability to use a conservative estimate for stream flow rate.

and Analysis Program" Modify Table D-1, Table Notations, "d", remove th2 frequency and analysis completed requirement. The Table D-1I "Radioactive frequency can be based upon procedural guidance relative Tabeou Wast "Radiot to the effluent point and the analysis completion D.aG aseousWaste Sampling D-3 requirement is based upon short lived nuclide and Analysis Program" accountability. This is not applicable at a decommissioning plant.

Table D-l, "Radioactive Modify Table D-l, Table Notations, "e", "f', remove D.l Gaseous Waste Sampling D-3 these two, no longer applicable.

and Analysis Program" Add to Table D-l, Table Notation "g" to explain tritium is only required from the Spent Fuel Building pathway while Table D-I, "Radioactive liquid is in the Spent Fuel Pool. After the bulk Speni Fuel D. I Gaseous Waste Sampling D-3 Pool has been drained this will not be required. The bulk and Analysis Program" volume has been achieved when the level in the pool has been decreased to less than 12 ft.

MA~P 2 C)2flfl NOV 10 2004 Rev. 4 Attachment 2 Connecticut Yankee REM/ODCM Change Request o RRemoved reference to dose limits associated with Noble D.2 Was Treatment te D-4 Gas releases. Noble gases monitoring has been removed Wast Tratmnt rom REMODCM.

Gaseous Effluent Remove D.3.1.a, dose rate limit for noble gases i; no Controls and longer applicable. The spent fuel was the only noble gas

. Surveillance source and it has been removed from the SFP. D3se rate Requirements limit for particulate and tritium now D.3.1.

Gaseous Effluent Add "Tritium is only required until the SFP is drm.ined" at D.3/4 Controls and the end of D.3.1, Applicability. The SFP liquid is; the last Surveillance - significant airborne tritium source.

Requirements Gaseous Effluent Remove Surveillance Requirements D.4. 1.1 and D).4.1.2.

Controls and Since the spent fuel is no longer stored in the SFP, noble D.314 Surveillance D5 gas is no longer monitored. Particulate and tritiur Requirements Surveillance Requirements renumbered.

Gaseous Effluent Remove the entire Noble Gases Dose control section.

D.3/4 Controls and D-7 Since the spent fuel is no longer stored in the SFP, noble Surveillance gas is no longer monitored. Particulate and Tritiuin Requirements section renumbered.

Gaseous Effluent Remove the entire bases for Noble Gases Dose. Since the D.3/4 Controls and D-8 spent fuel is no longer stored in the SFP, noble gas is no Surveillance longer monitored. Particulate and Tritium section Requirements - renumbered.

. a i Remove the entire controls, table D.3.4 is no longer Radioactive Gaseous D.314 Effluent Monitoring D-8 applicable since associated monitors are no longer D.nstruentatin required to be in service post fuel transfer. Section Instrumentation renumbered.

Remove the entire bases, table D.3.4 is no longer Radioactive Gaseous D.3/4 Effluent Monitoring D-8 applicable since associated monitors are no longer Instrumentation required to be in service post fuel transfer. Section renumbered.

Table D.3.4, Remove Table D.3.4. Gaseous Effluent Monitoring

/4 "Radioactive Gaseous D-8 Instrumentation is no longer applicable after Spent Fuel is D.34.4 Effluent Monitoring removed from SFP. Sections renumbered.

Instrumentation"_

Table D.4.3, Remove Table D.3.4, Action Statements, no longer D.3/4.4 "Radioactive Gaseous D-8 required with the removal of Table D.3.4. Sections Effluent Monitoring renumbered.

Instrumentation" Table D.4.4, Remove Table D.4.4, No longer required after Table D-l "Radioactive Gaseous modification and removal of Table D.3.4. Section Effluent Monitoring D-8 Renumbered.

D.3/4.4 Instrumentation Surveillance Requirements Table D.4.4, These pages were deleted due to reduction in monitoring "Radioactive Gaseous requirements associated with the various sections. A.ll Effluent Monitoring D-9 to D-18 sections were renumbered thus reducing the total pages.

D.3/4.4 Instrumentation Surveillance

_ Requirements rkW5

\ C\Y

IVIIA '-U ZI.};Il NOV 10 2004

_ _ _ _ _ _ --- R--

evCPi.4 42X0 Rev. 4 Attachment 2 Connecticut Yankee REMIODCM Change Request Remove references to milk in the third paragraph and remove the section discussing Land Use Census relative to E. I Sampling and Analysis E-l milk and reporting criteria for milk sampling locations.

With the reduction in onsite release sources, milk: is not a meaningful indicator for environmental monitoring.

From Table E-1, remove pathway #4, Milk. With the E.1 Sampling and Analysis E-3 reduction in onsite release sources, milk is not a meaningful indicator for environmental monitorirg.

From Table E-l, remove pathway #5, Well Water. Onsite well water is not a source of potential environmental E. I Sampling and Analysis E-3 monitoring releases due to reduction in dilution flow and liquid releases. Well water is not consumed onsit. and is

_____ not a meaningful indicator for environmental sampling.

From Table E-l, remove pathway #7, River Water. The

. . Sactivity concentrations released via liquids to the liver are

. very low, thus the composite sampling of the river is not a

. meaningful indicator for environmental monitoring.

Added footnote "I" to reduce the amount of sediment, fish and water samples are required to be sampled after the SFP liquid has been released. Due to the current Frogress E.I Sampling and Analysis E-3 of the Decommissioning Project these sample points will no longer be valid Environmental Samples after the removal of the SFP liquid source term. Sample locations

-_ associated with ISFSI monitoring will still be monitored.

Removed requirements for sampling particulate and vegetation from Table E-l. Due to the current progress of the Decommissioning Project these sample points will E. I Sampling and Analysis E-3 no longer useful for evaluating offsite dose pathways.

The source term associated with future releases are negligible for these sample points when the spent ffiel is

-_ no longer stored in the pool.

ayE-3 From Table E-l, remove the subscript pertaining to milk E. 1 Sampling and Analysis ____sampling and analysis. Milk sampling has been removed.

Reporting Levels for Removed reporting levels associated with particulate, milk Table E-2 Radioactivity E4 and vegetation. No longer sampled.

Concentrations in Environmental Samples Maximum Values for Removed LLD values associated with particulate, milk Table E-3 Lower Limits of E-5 and vegetation. No longer sampled.

Detection (LLD)'

MAR 3 0 tn005 NOV 10 2004

___ _ _ -. -- --- AGP-1.2 2A48--

Rev. 4 Attachment 2 Connecticut Yankee REM/ODCM Change Request Reworded second paragraph to reduce the frequency of performing a land use census. Due to the progres.3 associated with the Decommissioning Project the performance of this census is no longer a useful tc ol for E.2 Land Use Census E-7 evaluating environmental sampling program. If needed, Unit Manager can direct the performance of the census.

Remove the reference to nearest milk animal from the second paragraph. Remove bullet item four. Milk

__ . sampling is not longer required.

G.4 Surveillance G-3Changed action to reference correct specification ections

.______ Requirements -_._

H. I Exclusion Area Map H-I Renamed stack location, Plant stack has been removed.

Figure H- 2 Liquid Radwaste System H-2Removed R-22 from drawing. This monitor has been r Lremoved from the REMODCM on this revision.

Originatcir signature: b Date: mes3

IVU4I' 3 U UJU5 NOV 10 2004

_.ACP-.2P12'-.4-Rev. 4 Attachment 2 Connecticut Yankee REM/ODCM Change Request Page 2 of 3 II. List ihe procedures and/or setpoints that require revision in order to implement the proposed change.

Estimated date for Name of Manager implementation responsible to implement

ttU-R-Ms 3z js. Starr

'DX E _9ttcl a-7, 3-2zD! U- -(w

--ruf

'by Pit 0 ,5-3ZS~A -. - ay-r III.

Technical Reviewers:

• Approve or disapprove

• If disapproving, attach gb s.

• at require revision in Section II.

ApprovAe Disapprove 2 2-2 w 0) s

. e.£ rnistj ufeisor :Date IV.

-_R adi logical-Enviromena[Rtview .

. Unreviewed Environmental Impact? Yes ] No W .

(Bases Attached)

Approve Disapprove 0l 3 /l/t L Technical Reviewer Date V.

Radigon Prot ion Manager Review:

/ _________ _ Approve [:J Disapprove R LII3 7/

Radiation lrotection Manager Date VI.

Compliance Review:

-A-r 6.. v.aYuevicc Approve [f Disapprove a 3 / 'bar tRcgulatory Affairs Manager Date CQ-T- x k /

.. .. I. A M al' LUULJ NOV 10 2004

_ ___ , _, __ _ __ _ _ _ _ _ __ __ _ _ _ __,_'ACP-1.2-2.48 -' - -- --

Rev. 4 Attachment 2 Connecticut Yankee REMIODCM Change Request Page 3 of 3 VII.

ISR Review:

__ _ __ _ __ _ Approves Disapprove E3 Z tJIR Reviewer Date VIII.

Unit/l SManager Approval:

- A x A iK Approve I Disapprove E 3/S9 / 5 tJnit/ISFSI Manager Date Ix.

CY IRAC Approval:

(As required)

-N Al Pt Approve l Disapprove E IRAC Chairman Date X.

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

Effective Date of IODCM Revision: ________

Radiation Protec ion De a ment Representative Date I

XI.

Chang! sent to Adminis 'on for implementation.

Radialtion Protection *art!Ent Representative Date I XII.

Change documented in Annual Radioactive Effluent Report:

Radial ion Protection Department Representative Date II

Docket No. 50-213 CY-06-062 Attachment 3 Revision 19 to Radiolo-gical Effluent Monitorinq and Offsite Dose Calculation Manual, and List of Changes May 2006