JAFP-12-0044, 2011 Annual Radioactive Effluent Release Report

2011 Annual Radioactive Effluent Release Report

ML12122A014
Person / Time
Site:	FitzPatrick
Issue date:	04/30/2012
From:	Joseph Pechacek Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
JAFP-12-0044
Download: ML12122A014 (38)

Text

~Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. FitzPatrick NPP P.O. Box 110 lycoming, NY 13093 Tel 315-342-3840 Joseph Pechacek Licensing Manager JAFP-12-0044 April 30, 2012 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

SUBJECT:

2011 Annual Radioactive Effluent Release Report James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59

Dear Sir or Madam:

This letter transmits the James A. FitzPatrick Nuclear Power Plant's (JAF) Annual Radioactive Effluent Release Report, for the period of January 1,2011 through December 31, 2011. This document is sCl.bm.itted iii accordance with the Reporting Requirements of the Technical Specifications, Section 5.6.3 and Appendix H of the Technical Requirements Manual, "Offsite Dose Calculation Manual (ODCM)," Part 1 Section 6.2, Annual Radioactive Effluent Release Report.

This report (Enclosure) includes, as an Addendum, an Assessment of the Radiation Doses to the Public due to the radioactive liquid and gaseous effluents released during the 2011 calendar year.

The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision

1. Distribution is in accordance with Regulatory Guide 10.1, Revision 4.

There are no commitments contained in this letter.

If you have any questions concerning the enclosed report, please contact Laurie Rayle, Chemistry Manager at (315) 349-6748.

JP/LR/ed

Enclosure:

Annual Radioactive Effluent Release Report, January 1, 2011-December 31,2011 cc: next page

JAFP-12-0044 Page 2 of 2 Mr. William Dean Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Resident Inspectors Office U.S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093 Mr. Mohan Thadani, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 D. Sherman (ANI Library)

P. Merges (NYSDEC)

C. Faison (ENOC/WPO)

J. McCann (ENOC/WPO)

B. Landers (CHEM/JAF)

K. Stoffle (NMP)

B. Sullivan (JAF)

J. Furfaro (ENV/JAF)

Document Contents:

001 Transmittal Letter, JAFP-12-0044 with enclosure

JAFP-12-0044 Enclosure 2011 Annual Radioactive Effluent Release Report (35 Pages)

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 - DECEMBER 31, 2011 DOCKET NO. 50-333 LICENSE NO. DPR-59

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 SUPPLEMENTAL INFORMATION FACILITY: JAFNPP LICENSEE: ENTERGY NUCLEAR OPERATIONS, INC.

1. Offsite Dose Calculation Manual Part 1 Radiological Controls

a. Fission and Activation Gases:

(1) The dose rate at or beyond the site boundary due to radioactive materials released from the plant in gaseous effluent shall be limited as follows:

(a) Less than or equal to 500 mrem/year to the whole body and less than or equal to 3000 mrem/year to the skin from noble gases.

(2) The air dose to areas at or beyond the site boundary from noble gases released from the plant in gaseous effluent shall be limited:

(a) During any calendar quarter, to less than or equal to 5 mrad from gamma radiation, and less than or equal to 10 mrad from beta radiation; and, (b) During any calendar year, to less than or equal to 10 mrad from gamma radiation and less than or equal to 20 mrad from beta radiation.

b. Tritium, Iodines and Particulates, Half Lives > 8 days:

(1) The dose to a member of the public at or beyond the site boundary from Iodine-131, Iodine-133, Tritium, and radionuclides in particulate form with half-lives greater than 8 days released from the plant in gaseous effluent shall be limited:

(a) During any calendar quarter to less than or equal to 7.5 mrem to any organ; and, (b) During any calendar year to less than or equal to 15 mrem to any organ.

(c) Less than 0.1% of the limits of Specification 3.4.1.c.1.a and 3.4.1.c.1.b as a result of burning contaminated oil.

(2) The dose rate at or beyond the site boundary due to radioactive materials released from the plant in gaseous effluents shall be limited as follows:

(a) Less than or equal to 1500 mrem/year to any organ from Iodine-131, Iodine-133, Tritium and for radioactive materials in particulate form with half-lives greater than 8 days (inhalation pathway only).

1

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 SUPPLEMENTAL INFORMATION (continued)

c. Liquid Effluents:

(1) The concentration of radioactive materials released to the unrestricted areas shall not exceed ten times the values specified in 10 CFR 20.1001-20.2402, Appendix B, Table 2, Column 2.

For dissolved or entrained noble gases the concentration shall be limited to 2.00E-04 Ci/ml.

(2) The dose to a member of the public from radioactive materials released from the plant in liquid effluents to unrestricted areas shall be limited as follows:

(a) During any calendar quarter, limited to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ; and, (b) During any calendar year, limited to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.

2. 10X Effluent Concentrations

a. Fission and activation gases: (None specified)

b. Iodines: (None specified)

c. Particulates, half-lives >8 days: (None specified)

d. Liquid effluents: Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Fission and activation None None None None products (mixture EC)

(Ci/ml)

(2) Tritium (Ci/ml) 1.00E-02 1.00E-02 1.00E-02 1.00E-02 (3) Dissolved and entrained gases (Ci/ml) 2.00E-04 2.00E-04 2.00E-04 2.00E-04 2

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 SUPPLEMENTAL INFORMATION (continued)

3. Average Energy (None specified)

4. Measurements and Approximations of Total Radioactivity

a. Fission and Activation Gases: Continuous monitor on each release path calibrated to a marinelli grab sample analyzed by gamma spectroscopy; bubbler grab sample analyzed for Tritium.

b. Iodines: Gamma spectral analysis of charcoal cartridge and particulate filter on each release path.

c. Particulates: Gamma spectral analysis of each particulate filter and charcoal cartridge for each release path. A four week per quarter composite of particulate filters for each release path for Strontium-89 and Strontium-90. One week per month particulate filter for each release path for gross alpha.

d. Liquid Effluents: Gamma spectral analysis of each batch discharged, except composite analysis for Strontium-89, Strontium-90, Iron-55, Tritium, and Alpha.

e. Solid Waste: Gamma spectral analysis of a representative sample of each waste shipment. Scaling factors established from off-site composite sample analyses to estimate concentration of non-gamma emitters. Low activity trash shipments, curie content estimated by dose rate measurement and application of appropriate scaling factors.

f. Error Estimation Method: Overall error for sampling and analysis estimated by combining individual errors using error propagation methods. This process is composed of determinate and undeterminate errors.

Determinate - Pump flowrates, volume measurements and analysis collection yields Undeterminate - Random counting error estimated using accepted statistical calculations 3

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 SUPPLEMENTAL INFORMATION (continued)

5. Batch Releases

a. Liquid: Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 7.20E+01 7.20E+01 6.10E+01 8.00E+01 (2) Total time period for batch 4.03E+03 4.48E+03 3.26E+03 4.21E+03 release: (min)

(3) Maximum time period for 7.00E+01 5.35E+02 9.50E+01 8.70E+01 batch release: (min)

(4) Average time period for 5.60E+01 6.22E+01 5.35E+01 5.26E+01 batch release: (min)

(5) Minimum time period for 2.00E+00 1.00E+00 1.00E+00 1.00E+00 batch release: (min)

(6) Total Activity Released (Ci) 2.25E-02 1.32E-02 9.85E-03 7.93E-03 (7) Total Volume Released (liters) 4.39E+06 4.26E+06 3.57E+06 4.39E+06

b. Liquid: Non-Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: ----------- 9.00E+00 1.30E+01 6.00E+00 (2) Total time period for batch ----------- 7.81E+02 1.63E+03 7.01E+02 release: (min)

(3) Maximum time period for ----------- 3.00E+02 6.07E+02 3.76E+02 batch release: (min)

(4) Average time period for ------------ 8.68E+01 1.26E+02 1.17E+02 batch release: (min)

(5) Minimum time period for ------------ 1.00E+00 2.00E+00 1.00E+00 batch release: (min)

(6) Total Activity Released (Ci) ------------ 7.93E-04 1.66E-03 9.26E-04 (7) Total Volume Released (liters) ------------ 2.89E+05 6.40E+05 2.66E+05

c. Gaseous There were no gaseous batch releases for this report period.

4

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES EST TOTAL UNIT QTR 1 QTR 2 QTR 3 QTR 4 ERROR %

A. FISSION AND ACTIVATION GASES

1. Total Release Ci 8.20E+00 1.92E+01 8.45E+00 7.20E+00 2.50E+01

2. Average release rate for period Ci/sec 1.04E+00 2.45E+00 1.06E+00 9.05E-01

3. Applicable ODCM Limit  % * * *

• B. IODINE-131

1. Total Iodine-131 Ci 1.04E-05 5.03E-05 3.75E-05 6.76E-05 2.50E+01

2. Average release rate for period Ci/sec 1.32E-06 6.40E-06 4.72E-06 8.51E-06

3. Applicable ODCM Limit  % * * *

• C. PARTICULATES

1. Particulates with half-lives >8 days Ci 5.08E-06 2.26E-06 2.19E-06 4.56E-05 3.60E+01

2. Average release rate for period Ci/sec 6.46E-07 2.87E-07 2.75E-07 5.74E-06

3. Applicable ODCM Limit  % * * * *

4. Gross alpha radioactivity Ci 2.77E-07 3.14E-07 2.55E-07 3.95E-07 2.50E+01 D. TRITIUM

1. Total Release Ci 5.06E+00 7.26E+00 6.86E+00 5.98E+00 2.50E+01

2. Average release rate for period Ci/sec 6.43E-01 9.23E-01 8.63E-01 7.52E-01

3. Applicable ODCM Limit  % * * *

• E. CARBON (See attachment 8)

• F. PERCENT OF APPLICABLE ODCM LIMITS FISSION AND ACTIVATION GASES UNIT QTR 1 QTR 2 QTR 3 QTR 4

1. Quarterly gamma air dose limit  % 3.79E-03 9.86E-03 3.46E-03 3.33E-03

2. Quarterly beta air dose limit  % 2.43E-04 7.92E-04 1.89E-04 2.61E-04

3. Yearly gamma air dose limit  % 1.89E-03 4.93E-03 1.73E-03 1.67E-03

4. Yearly beta air dose limit  % 1.21E-04 3.96E-04 9.44E-05 1.31E-04

5. Whole body dose rate limit  % 4.02E-03 1.46E-02 1.48E-03 2.09E-03

6. Skin dose rate limit  % 8.62E-04 3.15E-03 4.36E-04 6.32E-04 HALOGENS, TRITIUM AND PARTICULATES WITH HALF-LIVES >8 DAYS

7. Quarterly dose limit (organ)  % 3.48E-03 9.24E-03 9.84E-03 1.59E-02

8. Yearly dose limit (organ)  % 1.74E-03 4.62E-03 4.92E-03 7.94E-03

9. Organ dose rate limit  % 1.60E-05 1.81E-05 1.61E-05 1.78E-05 5

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 TABLE 1B GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODE NUCLIDES RELEASED

1. Fission Gases UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Argon-41 Ci 3.67E+00 2.25E+00 3.03E+00 2.68E+00 Krypton-85m Ci 7.51E-01 1.25E+00 2.41E+00 1.05E+00 Krypton-87 Ci 2.88E-01 1.27E+00 ------------ ------------

Krypton-88 Ci 1.93E-01 1.31E+00 1.02E+00 5.05E-01 Xenon-133 Ci 1.43E+00 5.51E-01 1.96E+00 9.03E-01 Xenon-133m Ci ------------ 6.54E-02 ----------- -----------

Xenon-135 Ci 4.02E-01 1.24E+00 ------------ 6.04E-02 Xenon-135m Ci 3.96E-01 2.36E+00 ------------ 2.85E-01 Xenon-137 Ci ------------ 1.11E+00 ------------ 6.60E-01 Xenon-138 Ci 1.03E+00 7.81E+00 ------------ 1.01E+00 TOTAL Ci 8.16E+00 1.92E+01 8.42E+00 7.15E+00

2. Iodines Iodine-131 Ci 7.38E-06 3.88E-05 2.49E-07 2.67E-07 Iodine-133 Ci 1.14E-05 2.76E-04 4.45E-06 2.22E-06 Iodine-135 Ci ------------ 4.94E-04 ----------- -----------

TOTAL Ci 1.88E-05 8.09E-04 4.70E-06 2.49E-06

3. Particulates Barium-140 Ci ------------ 3.64E-07 ----------- ------------

Strontium-89 Ci 8.10E-07 1.04E-06 8.96E-07 1.81E-07 TOTAL Ci 8.10E-07 1.40E-06 8.96E-07 1.81E-07

4. Tritium Hydrogen-3 Ci 4.38E-01 3.63E-01 8.95E-01 1.00E+00 Note: There were no batch releases for this report period.

6

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED

1. Fission Gases UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Xenon-133 Ci 2.52E-02 8.75E-03 9.48E-03 2.65E-02 Xenon 135 Ci 1.96E-02 6.97E-03 8.33E-03 1.50E-02 Xenon-135M Ci 2.18E-03 6.55E-03 4.30E-03 3.59E-03 TOTAL Ci 4.70E-02 2.23E-02 2.21E-02 4.51E-02

2. Iodines Iodine-131 Ci 2.98E-06 1.15E-05 3.73E-05 6.73E-05 Iodine-133 Ci 7.42E-06 1.31E-04 1.75E-04 4.92E-04 Iodine-135 Ci ------------ ------------ ------------ 1.14E-05 TOTAL Ci 1.04E-05 1.43E-04 2.12E-04 5.71E-04

3. Particulates Cobalt-58 Ci ------------ ------------ ------------ 1.61E-05 Cobalt-60 Ci 1.26E-06 ------------ ------------ 6.96E-06 Manganese-54 Ci 4.32E-07 ------------ ------------ 1.61E-05 Strontium-89 Ci 2.57E-06 8.52E-07 1.29E-06 6.87E-07 Zinc-65 Ci ------------ ------------ ------------ 5.59E-06 TOTAL Ci 4.26E-06 8.52E-07 1.29E-06 4.54E-05

4. Tritium Hydrogen-3 Ci 4.62E+00 6.90E+00 5.96E+00 4.98E+00 Note: There were no batch releases for this report period.

7

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES EST TOTAL UNIT QTR 1 QTR 2 QTR 3 QTR 4 ERROR %

A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not including tritium, gases and alpha) Ci None None None None 2.50E+01

2. Average diluted concentration during period Ci/ml None None None None

3. Applicable ODCM Limit  % ---------- ---------- ---------- ----------

B. TRITIUM

1. Total Release Ci 2.25E-02 1.40E-02 1.15E-02 8.86E-03 2.50E+01

2. Average diluted concentration during period (Note 1) Ci/ml 3.72E-09 1.76E-07 3.94E-07 2.00E-07

3. Applicable ODCM Limit  % * * *

• C. DISSOLVED AND ENTRAINED GASES

1. Total Release Ci None None None None 2.50E+01

2. Average diluted concentration during period Ci/ml None None None None

3. Applicable ODCM Limit  % * * *

• D. GROSS ALPHA RADIOACTIVITY

1. Total Release Ci None None None None 4.20E+01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) liters 4.39E+06 4.55E+06 4.21E+06 4.66E+06 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 6.03E+09 6.60E+09 5.09E+09 6.29E+09 G. PERCENT OF APPLICABLE ODCM LIMITS

1. Quarterly Whole Body Dose  % 1.54E-06 3.50E-04 3.39E-04 3.29E-04

2. Quarterly Organ Dose  % 4.63E-07 1.05E-04 1.02E-04 9.86E-05

3. Annual Whole Body Dose  % 7.71E-07 1.75E-04 1.70E-04 1.64E-04

4. Annual Organ Dose  % 2.31E-07 5.25E-05 5.09E-05 4.93E-05 Note: Concentration includes summation from diluted and undiluted values from Canal and Non-Canal releases (Table 2B).

8

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 TABLE 2B LIQUID EFFLUENTS CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4

1. Fission and Activation Products None Ci ------------- ----------- -------------- ----------

2. Tritium Hydrogen-3 Ci 2.25E-02 1.32E-02 9.85E-03 7.93E-03

3. Dissolved and Entrained Gases None Ci ------------- ------------- -------------- ------------

Note: There were no continuous mode discharges during this report period.

9

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 TABLE 2B (SUPPLEMENT)

LIQUID EFFLUENTS NON-CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4

1. Fission and Activation Products None Ci ------------- ----------- -------------- ------------

2. Tritium Hydrogen-3 Ci ------------- 7.93E-04 1.66E-03 9.26E-04

3. Dissolved and Entrained Gases None Ci ------------- ----------- -------------- ------------

Note: There were no continuous mode discharges during this report period.

10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 TABLE 3A SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

EST. TOTAL

1. Type of Waste UNIT CLASS A CLASS B CLASS C ERROR %

a. Spent resins, filter sludges, m^3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 evaporator bottoms, etc. Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

b. Dry compressible waste, m^3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 contaminated equipment, etc. Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

c. Irradiated componants, m^3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 control rods, etc. Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

d. Other: Dry compressible m^3 9.66E+02 0.00E+00 0.00E+00 1.00E+01 waste, contaminated equipment, Ci 4.74E+01 0.00E+00 0.00E+00 1.00E+01 spent resins for volume reduction.

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

a. Spent resins, filter sludges, evaporator bottoms, etc.

None

b. Dry compressible waste, contaminated equipment, etc.

None

c. Irradiated components, control rods, etc.

None

d. Other: Dry compressible waste, contaminated equipment, spent resins contaminated oil, glycol and water for volume reduction.

Isotope Percent Curies Isotope Percent Curies Cerium-144 1.73E-02 8.22E-03 E Cobalt-58 1.83E-01 8.68E-02 E Cobalt-60 1.20E+01 5.70E+00 E Cesium-134 1.26E-01 5.97E-02 E Cesium-137 9.08E-01 4.31E-01 E Iron-55 6.01E+01 2.85E+01 E Carbon-14 9.15E-01 4.31E-01 E Manganese-54 6.43E+00 3.05E+00 E Nickel-63 5.89E+00 2.80E+00 E Strontium-90 2.03E-01 9.64E-02 E Zinc-65 1.30E+01 6.14E+00 E Hydrogen-3 2.63E-02 1.25E-02 E Chromium-51 3.89E-02 1.85E-02 E Iron-59 1.28E-01 6.07E-02 E Antimony-124 3.64E-02 1.83E-02 E Antimony-125 1.99E-02 9.42E-03 E (E- Estimated M- Measured)

Percentage of nuclides and total activities are based on a combination of direct measurements and scaling for non-gamma emitting nuclides.

11

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition No. of Shipments Mode of Transportation Destination 12 Truck *Energy Solutions Oak Ridge, TN 27 Truck *Energy Solutions Kingston, TN 1 Truck *Perma-Fix of Florida Gainsville, Fl

• Volume Reduction Facility B. IRRADIATED FUEL SHIPMENTS (Disposition)

No. of Shipments Mode of Transportation Destination None ----------- ---------------

12

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 TABLE 3B SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. NRC CLASS A SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Dry compressible Waste (DAW), Non-compacted 1280 ft^3 STC 9 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 96 ft^3 STC 28 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 1033 ft^3 STC 16 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 4.1 ft^3 STC 3 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 7.5 ft^3 STC 2 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 38.4 ft^3 STC 1 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 159 ft^3 STC 1 Contaminated Equipment, etc.

Spent Resins, Filter Sludges, evaporator Air Drying 205.8 ft^3 STC 8 Bottoms, etc. Non-compacted Spent Resins, Filter Sludges, evaporator Air Drying 120.3 ft^3 HIC 2 Bottoms, etc. Non-compacted 13

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 Contaminated Oil Non-compacted 7.5 ft^3 STC 8 TABLE 3B SOLID WASTE AND IRRADIATED FUEL SHIPMENTS B. NRC CLASS B SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS None C. NRC CLASS C SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS None HIC- High Integrity Container STC- Strong Tight Container 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 ATTACHMENT NO. 1 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

In accordance with the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Controls (REC) Section 6.2.3, changes made to the Offsite Dose Calculation Manual (ODCM) during the reporting period shall be included in the Annual Radioactive Effluent Release Report.

There were no changes to the Offsite Dose Calculation Manual (ODCM).

15

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ATTACHMENT NO. 2

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM In accordance with the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Controls (REC) Section 6.2.3, changes made to the Process Control Program (PCP) during the reporting period shall be included in the Annual Radioactive Effluent Release Report.

There were no changes to the Process Control Program.

16

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ATTACHMENT NO. 3

SUMMARY

OF CHANGES TO THE ENVIRONMENTAL MONITORING AND DOSE CALCULATION LOCATIONS In accordance with the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1, Section 6.2.3 a listing of new locations for dose calculation and/or environmental monitoring identified by the land use census shall be included in the Annual Radioactive Effluent Release Report.

During the reporting period, no changes in Dose Calculation Receptor Locations and/or the Environmental Monitoring were required based on the results of the land use census.

17

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ATTACHMENT NO. 4 DEVIATIONS FROM THE REQUIRED ENVIRONMENTAL SAMPLING SCHEDULE In accordance with the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1, Section 6.2.7, the cause for the unavailability of any environmental samples required during the report period shall be included in the Annual Radioactive Effluent Release Report.

The following is a report of samples that were a deviation from the requirements of ODCM Part 1, Table 5.1-1. ODCM Part 1, Section 5.1.1.c.1 allows for deviations from the program due to hazardous conditions, seasonal unavailability, theft, uncooperative residents, or to a malfunction of automatic sampling equipment.

A. ODCM Program Deviations The following are deviations from the program specified by the ODCM:

1. Loss of power to environmental air sample stations R1 and R2 Offsite for 6.9 hrs each during the week of 2/1/11 to 2/8/11. The stations were found operating during normal weekly sample change outs. Sample volumes for the period are acceptable.

2. Loss of power to environmental air sample stations R3 and R4 Offsite for 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> each during the sample period 3/8/11 to 3/15/11. The stations were found operating during sample change outs. Sample volumes for the period are acceptable.

3. Loss of power to environmental air sample stations R3 and R4 for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> each during the week of 5/10/11 to 5/17/11. The air sample stations were found operating during normal weekly sample change outs. Sample volumes for the period are acceptable.

4. Loss of power to environmental air sample station R5 for 7.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the week of 6/7/11 to 6/14/11. The station was found operating during normal weekly change outs.

Sample volume for the period was acceptable

5. Loss of power to environmental air sample station R3 Offsite for 6 days during the week of 7/12/11 to 7/19/11. NMP technician found cabinet blower fan inoperable upon arrival.

The cabinet blower fan and air sample pump were replaced.

6. Oswego Steam Station (OSS) Inlet Canal Sampler found not working on 7/22/2011.

There was no power to the pump. Found that the GFI had been tripped. Building lost power on 7/21/2011 at 0810 hrs. Sampler was out of service for 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />.

B. Air Sampling Station Operability Assessment The ODCM required air sampling program consists of 5 individual sampling locations. The collective operable time period for the air monitoring stations was 43,622 hours0.0072 days <br />0.173 hours <br />0.00103 weeks <br />2.36671e-4 months <br /> out of a possible 43,800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />. The air sampling availability factor for the report period was 99.59%.

18

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ATTACHMENT NO. 5 ANNUAL

SUMMARY

OF HOURLY METEOROLOGICAL DATA The James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1, Radiological Controls (REC) Section 6.2 and 6.2.2 states in part: The Annual Radioactive Effluent Release Report submitted prior to May 1 of each year may include an annual summary of meteorological data collected over the previous year. If the meteorological data is not included, the licensee shall retain it on file and provide it to the U.S. Nuclear Regulatory Commission upon request.

In accordance with the aforementioned ODCM requirement, meteorological data is not included in this report. It is retained on file and is available upon request.

19

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ATTACHMENT NO. 6 MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS In accordance with the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Controls (REC) Section 7.0, Major Modifications to Radioactive Waste Treatment Systems (liquid, gaseous and solid) shall be reported in the Annual Radioactive Effluent Release Report for the period in which the modification is completed and made operational.

There were no major modifications to any liquid, gaseous, or solid radioactive waste treatment systems.

20

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ATTACHMENT NO. 7 ONSITE GROUNDWATER MONITORING In response to the Nuclear Energy Institute (NEI) Groundwater Protection Initiative, JAF instituted a groundwater monitoring program in 2007. Five monitoring wells were installed during the fourth quarter of 2007. The first samples were collected in November 2007. Starting in March 2010, 16 additional monitoring wells were drilled in the area of the reactor building and nearby SSCs.

All samples collected were analyzed for tritium, and gamma emitting radionuclides. The detection limits and results are reported in the following tables. Analysis results of tritium ranged from non-detectable at less than 408 pCi/l, up to a maximum concentration of 10,660 pCi/l for a MW CST-B sample from 4/6/11. Such levels are well below the voluntary communication reporting level of 20,000 pCi/l as established by the EPA drinking water standard. Although the EPA Standard provides a baseline for comparison, no drinking water sources are affected by this tritium. All of the effected wells are onsite. As such, there is no potential to influence any off-site drinking well.

Even if worst case assumptions were made and the water from monitoring well CST-B was consumed as drinking water, the maximum dose would be 1.1 mrem/yr to the whole body. No drinking water pathway exists at the James A. Fitzpatrick site under normal operating conditions due to the direction and distance of the nearest water intake (Oswego, 8.5 miles west of the JAF discharge).

Starting in February 2011, the MW CST-B samples have been analyzed for Sr-90 on a monthly basis. The Sr-90 concentrations detected were in trace amounts. The range was 0.77 to 3.09 pCi/l. The Sr-90 could be from fallout, or from previous plant operations, or possibly a leak. The last two are highly unlikely since no plant-related gamma activity, especially Cs-137, or other hard-to-detects were identified. There was also high uncertainty in the results for Sr-90, since they were very close to the analytical laboratorys detection capability.

In conclusion, the only radionuclide detected in groundwater during the 2011 monitoring effort that is attributable to James A. FitzPatrick operations is tritium, and all concentrations were well below any reporting criteria.

21

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ATTACHMENT NO. 7 (continued)

ONSITE GROUNDWATER MONITORING A) Gamma Isotopic Monitoring For 2011, the 21 monitoring wells were sampled and analyzed below the required lower limits of detection in accordance with the Offsite Dose Calculation Manual (ODCM) Part 1, Table 5.1-3. All 21 monitoring wells were analyzed at least quarterly, down to these values.

These values are as follows:

LLD Value LLD Value Radionuclide (pCi/l) Radionuclide (pCi/l)

Manganese-54 15 Zirconium/Niobium-95 15 Cobalt-58 15 Iodine-131 15 Iron-59 30 Cesium-134 15 Cobalt-60 15 Cesium-137 18 Zinc-65 30 Barium/Lanthanum-140 15 There were no plant related nuclides detected in the samples.

22

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ATTACHMENT NO. 7 (continued)

ONSITE GROUNDWATER MONITORING B) Tritium Summary

1. Positive Minimum Maximum

1. Samples Samples in Positive Positive Well Name in 2011 2011 Concentration Concentration MW-5 17 8 396 536 MW-6 17 12 403 594 MW-7 17 1 458 458 MW-8 17 3 395 449 MW-9 17 2 404 431 MW-1A 14 0 0 10 0

MW-1B 14 0 0 0 MW-2A 14 13 407 667 MW-2B 14 0 0 0 MW-3A 14 12 390 689 MW-3B 14 2 410 518 MW-4A 14 4 392 479 MW-4B 13 0 0 0 MW-10A 14 0 0 0 MW-10B 14 0 0 0 MW-13 14 8 399 575 MW-14 11 2 464 625 MW-15 14 0 0 0 MW-16 14 8 391 603 MW-CSTA 13 13 438 719 MW-CSTB 13 13 1506 10660 Note 1: All results are in pCi/L.

Note 2: A total of 303 samples were analyzed for H-3 in 2011 with 101 positive results.

Note 3: The LLD was 500 pCi/L.

23

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ATTACHMENT NO. 8 GASEOUS EFFLUENTS - CARBON-14 a) Date: January 01, 2011 - December 31, 2011 b) Location: Elevated Release - Main Stack c) Duration: 365 Days d) Flowrate: N/A e) Volume Released: N/A f) Nuclides Released: Carbon-14 g) Curies Released: 10.53 Ci h) Resultant Doses: See Addendum 1Assessment of Radiation Doses to the Public January-December 2011 Table 1D i) Dose Calculations: Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Section 4.4.1 24

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ADDENDUM 1 ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2011

1. INTRODUCTION The James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Controls, requires an assessment of the radiation doses to the public due to radioactive liquid and gaseous effluents. This assessment of doses to the public is based on accepted methodologies found in the Offsite Dose Calculation Manual (ODCM).

2. DOSE LIMITS A. DOSE FROM LIQUID EFFLUENTS (ODCM, Part 1, REC 2.3)

Applicability Applies to doses from radioactive material in liquid effluents.

Objective To ensure that the dose limitations of 10 CFR 50, Appendix I, are met.

Specifications The dose to a member of the public from radioactive materials released from the plant in liquid effluents to unrestricted areas shall be limited as follows:

1. During any calendar quarter, limited to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ.

2. During any calendar year, limited to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.

B. GASEOUS DOSE RATES (ODCM, Part 1, REC 3.2)

Applicability Applies to the radiation dose from radioactive material in gaseous effluents.

Objective To ensure that the dose rates at or beyond the site boundary from gaseous effluents do not exceed the annual dose limits of 10 CFR 20, for unrestricted areas.

25

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ADDENDUM 1 (continued)

Specifications The dose rate at or beyond the site boundary due to radioactive materials released from the plant in gaseous effluents shall be limited as follows:

1. Less than or equal to 500 mrem/year to the whole body and less than or equal to 3000 mrem/year to the skin from noble gases; and,

2. Less than or equal to 1500 mrem/year to any organ from Iodine-131, Iodine-133, Tritium and for radioactive materials in particulate form with half-lives greater than 8 days (inhalation pathway only).

C. AIR DOSE, NOBLE GASES (ODCM, Part 1, REC 3.3)

Applicability Applies to the air dose due to noble gases in gaseous effluents.

Objective To ensure that the noble gas dose limitations of 10 CFR 50, Appendix I, are met.

Specifications The air dose to areas at or beyond the site boundary from noble gases released from the plant in gaseous effluents shall be limited:

1. During any calendar quarter, to less than or equal to 5 mrad from gamma radiation, and less than or equal to 10 mrad from beta radiation; and,

2. During any calendar year, to less than or equal to 10 mrad from gamma radiation and less than or equal to 20 mrad from beta radiation.

26

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ADDENDUM 1 (continued)

D. DOSE DUE TO IODINE-131, IODINE-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM (ODCM, Part 1, REC 3.4)

Applicability Applies to the cumulative dose from Iodine-131, Iodine-133, Tritium, and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents.

Objective To ensure that the dose limitations of 10 CFR 50, Appendix I, are met.

Specifications The dose to a member of the public at or beyond the site boundary from Iodine-131, Iodine-133, Tritium, and radionuclides in particulate form with half-lives greater than 8 days released from the plant in gaseous effluents shall be limited:

1. During any calendar quarter to less than or equal to 7.5 mrem to any organ; and,

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

E. TOTAL DOSE FROM URANIUM FUEL CYCLE (ODCM, Part 1, REC 4.0)

Applicability Applies to radiation dose from releases of radioactivity and radiation from uranium fuel cycle sources.

Objective To ensure that the requirements of 40 CFR 190 are met.

Specifications The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited as follows:

1. Less than or equal to 25 mrem/year to the whole body; and,

2. Less than or equal to 25 mrem/year to any organ except the thyroid which shall be limited to less than or equal to 75 mrem/year.

27

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ADDENDUM 1 (continued)

3. DOSE ASSESSMENT A. METHODOLOGY The assessment of radiation doses to the public due to radioactive liquid and gaseous effluents is performed in accordance with the ODCM. The ODCM is based on methodologies and models suggested by the "Guidance Manual For Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREG-0133) and "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the purpose of Evaluating Compliance with 10CFR50, Appendix I" (Regulatory Guide 1.109).

B. ASSUMPTIONS Dose calculations are performed using formulas and constants defined in the ODCM.

Specific radioactive release activities used in the dose calculations are listed in the Annual Radioactive Effluent Release Report (1.21 Report) for the period of January 1, 2011 to December 31, 2011. Historical meteorological data was used to generate tables of average dispersion factors. Locations of interest were identified from the 2011 land use census.

Dispersion factors and locations of interest used in performing the dose calculations are listed in Table 2.

C. ASSESSMENT RESULTS

SUMMARY

The calculated doses to the public due to radioactive effluents are listed in Table 1. The calculated doses are small fractions of their respective dose limits.

4. 40 CFR 190 DOSE ASSESSMENT A. METHODOLOGY Evaluation to demonstrate compliance with the 40 CFR 190 dose limits must be performed when the doses calculated for 10 CFR 50 compliance exceed twice their respective limits.

When additional dose assessment is required to demonstrate compliance with 40 CFR 190 it is performed in accordance with the ODCM.

B. RESULTS

SUMMARY

The cumulative dose contribution from liquid and gaseous effluents for this report period were calculated and are listed in Table 1. The cumulative dose contribution from direct radiation from the reactor unit and from radwaste storage tanks is measured by environmental thermoluminescent dosimeters for the report period. This data is contained in the Annual Environmental Operating Report. The calculated doses from liquid and gaseous effluents are less than twice their respective 10 CFR 50 limits; therefore, additional calculations are not necessary to demonstrate compliance with 40 CFR 190 dose limits (ODCM, Part 1, REC 4.1.1.c) 28

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 2011 A. LIQUIDS QUARTER 1 2 3 4 ANNUAL (a) (a) (a) (a) (a)

Organ (mrem) 2.31E-08 5.25E-06 5.09E-06 4.93E-06 1.53E-05

% of Limit 4.63E-07 1.05E-04 1.02E-04 9.86E-05 1.53E-04 (b) (b) (b) (b) (b)

Whole Body (mrem) 2.31E-08 5.25E-06 5.09E-06 4.93E-06 1.53E-05

% of Limit 1.54E-06 3.50E-04 3.39E-04 3.29E-04 5.10E-04 (a) Dose to the Child Liver primarily by the potable water pathway.

(b) Dose to the Child Whole Body primarily by the potable water pathway.

29

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ADDENDUM 1 (continued)

TABLE 1 (cont)

ANNUAL DOSE ASSESSMENT 2011 B. NOBLE GASES QUARTER 1 2 3 4 ANNUAL Total Body (mrem/yr) 2.01E-02 7.28E-02 7.38E-03 1.04E-02 7.28E-02

% of Limit 4.02E-03 1.46E-02 1.48E-03 2.09E-03 1.46E-02 Skin (mrem/yr) 2.59E-02 9.46E-02 1.31E-02 1.90E-02 9.46E-02

% of Limit 8.62E-04 3.15E-03 4.36E-04 6.32E-04 3.15E-03 Gamma (mrad) 1.89E-04 4.93E-04 1.73E-04 1.67E-04 1.02E-03

% of Limit 3.79E-03 9.86E-03 3.46E-03 3.33E-03 1.02E-02 Beta (mrad) 2.43E-05 7.92E-05 1.89E-05 2.61E-05 1.49E-04

% of Limit 2.43E-04 7.92E-04 1.89E-04 2.61E-04 7.43E-04 C. IODINES AND PARTICULATES QUARTER 1 2 3 4 ANNUAL (a) (a) (a) (a) (a)

Organ (mrem) 2.61E-04 6.93E-04 7.38E-04 1.19E-03 2.88E-03

% of Limit 3.48E-03 9.24E-03 9.84E-03 1.59E-02 1.92E-02 (a) (a) (a) (a) (a)

Organ Dose Rate 2.40E-04 2.72E-04 2.41E-04 2.67E-04 2.72E-04 (mrem/yr)

% of Limit 1.60E-05 1.81E-05 1.61E-05 1.78E-05 1.81E-05 (a) Dose to the Child Thyroid primarily by the vegetation pathway.

30

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ADDENDUM 1 (continued)

TABLE 1 (cont)

ANNUAL DOSE ASSESSMENT 2011 D. CARBON 14 QUARTER 1 2 3 4 ANNUAL (a) (a) (a) (a) (a)

Organ (mrem) 8.27E-03 8.30E-03 8.59E-03 8.43E-03 3.36E-02

% of Limit 1.10E-01 1.11E-01 1.14E-01 1.12E-01 2.24E-01 (a)

Organ Dose Rate ------------ ---------- ----------- ---------- 3.36E-02 (mrem/yr)

% of Limit ------------ ---------- ------------ ---------- 2.24E-03 (a) Dose to the Child Bone primarily by the vegetation pathway.

31

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ADDENDUM 1 (continued)

TABLE 2 METEOROLOGICAL DATA AND LOCATIONS OF INTEREST GEOGRAPHIC ATMOSPHERIC**

RECEPTOR LOCATION DISPERSION FACTOR

___________________________________________________________________________

A. IODINE & DISTANCE/ RELEASE X/Q D/Q 3

PARTICULATES DIRECTION POINT (sec/m ) (l/m2)

___________________________________________________________________________

1. Garden 0.90 mi @ 83°E ST 2.83E-08* 1.75E-09 Grazing Season 0.90 mi @ 83°E RX 2.02E-07* 5.01E-09 Cary 0.90 mi @ 83°E TB 1.83E-07* 4.80E-09 Location No. 78 0.90 mi @ 83°E RF 2.02E-07* 5.01E-09 0.90 mi @ 83°E RW 3.21E-07* 5.76E-09

2. Meat 1.18 mi @ 127°SE ST 1.72E-08* 6.80E-10 Grazing Season 1.18 mi @ 127°SE RX 5.36E-08* 1.30E-09 Parkhurst 1.18 mi @ 127°SE TB 5.14E-08* 1.27E-09 Location No. 26 1.18 mi @ 127°SE RF 5.36E-08* 1.30E-09 1.18 mi @ 127°SE RW 9.12E-08* 1.46E-09

3. Cow 2.50 mi @ 139°SE ST 1.67E-08* 2.65E-10 Grazing Season 2.50 mi @ 139°SE RX 2.76E-08* 4.14E-10 France 2.50 mi @ 139°SE TB 2.71E-08* 4.07E-10 Location No. 10 2.50 mi @ 139°SE RF 2.76E-08* 4.14E-10 2.50 mi @ 139°SE RW 4.15E-08* 4.36E-10

4. Goat (D/Q) 3.62 mi @ 113°ESE ST ----------- 2.28E-10 Grazing Season 3.62 mi @ 113°ESE RX ----------- 3.40E-10 Showers 3.62 mi @ 113°ESE TB ----------- 3.33E-10 Location No. 71 3.62 mi @ 113°ESE RF ----------- 3.40E-10 3.62 mi @ 113°ESE RW ----------- 3.49E-10

5. Goat (X/Q) 2.64 mi @ 152°SSE ST 1.94E-08* -----------

Grazing Season 2.64 mi @ 152°SSE RX 2.58E-08* -----------

Nickolas 2.64 mi @ 152°SSE TB 2.57E-08* -----------

Location No. 61 2.64 mi @ 152°SSE RF 2.58E-08* -----------

2.64 mi @ 152°SSE RW 3.59E-08* -----------

32

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ADDENDUM 1 (continued)

TABLE 2 METEOROLOGICAL DATA AND LOCATIONS OF INTEREST GEOGRAPHIC ATMOSPHERIC**

RECEPTOR LOCATION DISPERSION FACTOR

___________________________________________________________________________

A. IODINE & DISTANCE/ RELEASE X/Q D/Q PARTICULATES DIRECTION POINT (sec/m3) (l/m2)

___________________________________________________________________________

6. Resident Annual Average

a. Inhalation(2) 1.55 mi @ 90°E(1) ST 2.99E-08 -----------

Cary 0.90 mi @ 83°E RX 2.07E-07 -----------

Location No. 78 0.90 mi @ 83°E TB 1.88E-07 -----------

0.90 mi @ 83°E RF 2.07E-07 -----------

0.90 mi @ 83°E RW 3.06E-07 -----------

b. Deposition(3) 0.71 mi @ 118°ESE ST ----------- 1.60E-09 Whaley 0.71 mi @ 118°ESE RX ----------- 5.52E-09 Location No. 199 0.71 mi @ 118°ESE TB ----------- 5.30E-09 0.71 mi @ 118°ESE RF ----------- 5.52E-09 0.71 mi @ 118°ESE RW ----------- 6.28E-09

______________________________________________________________________________

B. NOBLE GASES

1. Air Dose 1.55 mi @ 90°E(1) ST 2.99E-08 -----------

Annual Average 0.60 mi @ 90°E ST(fc) 1.16E-07 -----------

Site Boundary 0.60 mi @ 90°E RX 3.58E-07 -----------

0.60 mi @ 90°E TB 3.19E-07 -----------

0.60 mi @ 90°E RF 3.58E-07 -----------

0.60 mi @ 90°E RW 5.39E-07 -----------

2. Total Body 0.60 mi @ 90°E ST(fc) 1.16E-07 -----------

Annual Average 0.60 mi @ 90°E RX 3.58E-07 -----------

Site Boundary 0.60 mi @ 90°E TB 3.19E-07 -----------

0.60 mi @ 90°E RF 3.58E-07 -----------

0.60 mi @ 90°E RW 5.39E-07 -----------

33

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2011 - DECEMBER 2011 ADDENDUM 1 (continued)

TABLE 2 METEOROLOGICAL DATA AND LOCATIONS OF INTEREST GEOGRAPHIC ATMOSPHERIC**

RECEPTOR LOCATION DISPERSION FACTOR

___________________________________________________________________________

B. NOBLE GASES DISTANCE/ RELEASE X/Q D/Q (continued) DIRECTION POINT (sec/m3) (l/m2)

___________________________________________________________________________

3. Skin 1.55 mi @ 90°E ST 2.99E-08 -----------

Annual Average 0.60 mi @ 90°E ST(fc) 1.16E-07 -----------

Site Boundary 0.60 mi @ 90°E RX 3.58E-07 -----------

0.60 mi @ 90°E TB 3.19E-07 -----------

0.60 mi @ 90°E RF 3.58E-07 -----------

0.60 mi @ 90°E RW 5.39E-07 -----------

_________________________________________________________________________

• Tritium Dose Calculation

• • Based on ODCM X/Q, D/Q Values Rev. 11 (1) Highest Sector Average X/Q in a populated area, not an identified residence.

(2) Inhalation uses Annual Average X/Q values. All other receptors use grazing season meteorology.

(3) Deposition uses Annual Average D/Q values. All other receptors use grazing season meteorology.

ST = Main Stack RX = Reactor Building Vent TB = Turbine Building Vent RF = Refuel Floor Vent RW = Radwaste Building Vent fc = Finite Cloud 34