JAFP-13-0055, 2012 Annual Radioactive Effluent Release Report

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2012 Annual Radioactive Effluent Release Report
ML13119A231
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/30/2013
From: Adner C
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
JAFP-13-0055
Download: ML13119A231 (42)
v • d • e


Text

~ Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. FitzPatrick NPP P.O. Box 110 Lycoming , NY 13093 Tel 315-342-3840 Chris Adner Licensing Manager JAFP-13-0055 April 30, 2013 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

SUBJECT:

2012 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, 2012 through December 31, 2012. This document is submitted in 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 2012 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 Bernie Landers, Acting Chemistry Manager at (315) 349-6995.

Chris Adner CA/BUjo

Enclosure:

Annual Radioactive Effluent Release Report, January 1, 2012-December 31, 2012 cc: next page

JAFP-13-0055 Page 2 of 2 Mr. William Dean Regional Administrator, Region I U. S. Nuclear Regulatory Commission 2100 Renaissance Boulevard, Suite 100 King of Prussia, PA 19406-2713 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)

B. Landers (CHEM/JAF)

K. Stoffle (NMP)

J. Furfaro (ENV/JAF)

Document Contents:

001 Transmittal Letter, JAFP-13-0055 with enclosure

JAFP-13-0055 Enclosure 2012 Annual Radioactive Effluent Release Report (39 Pages)

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2012 - DECEMBER 31, 2012 DOCKET NO. 50-333 LICENSE NO. DPR-59

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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 2012 - DECEMBER 2012 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 2012 - DECEMBER 2012 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 is 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 2012 - DECEMBER 2012 SUPPLEMENTAL INFORMATION (continued)

5. Batch Releases
a. Liquid: Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 1.40E+01 2.00E+00 2.00E+00 3.00E+00 (2) Total time period for batch 7.78E+02 1.42E+02 7.30E+01 3.73E+02 release: (min)

(3) Maximum time period for 1.10E+02 9.20E+01 4.10E+01 1.94E+02 batch release: (min)

(4) Average time period for 5.56E+01 7.10E+01 3.65E+01 1.24E+02 batch release: (min)

(5) Minimum time period for 4.00E+00 5.00E+01 3.20E+01 5.20E+01 batch release: (min)

(6) Total Activity Released (Ci) 8.79E-04 2.98E-03 3.32E-06 5.45E-06 (7) Total Volume Released (liters) 6.47E+05 3.12E+04 1.32E+03 2.24E+03

b. Liquid: Non-Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 1.60E+01 1.30E+01 1.30E+01 7.00E+00 (2) Total time period for batch 1.92E+04 6.40E+02 7.40E+02 5.85E+02 release: (min)

(3) Maximum time period for 1.89E+04 1.89E+02 1.86E+02 3.26E+02 batch release: (min)

(4) Average time period for 3.21E+03 4.92E+01 5.69E+01 8.36E+01 batch release: (min)

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

(6) Total Activity Released (Ci) 2.75E-04 9.61E-04 3.12E-03 2.34E-04 (7) Total Volume Released (liters) 1.31E+05 2.42E+05 2.79E+05 2.21E+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 2012 - DECEMBER 2012 SUPPLEMENTAL INFORMATION (continued)

6. Continuous Releases
a. Liquid: Non-Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases: 1.00E+00 1.00E+00 1.00E+00 1.00E+00 (2) Total Activity Released (Ci) 2.72E-02 4.81E-02 5.34E-02 7.37E-02 (2) Total Volume Released (liters) 1.31E+05 2.42E+05 2.79E+05 2.21E+05
7. Abnormal Releases
a. Liquid: Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases: ------------ 1.00E+00 ------------ ------------

(2) Total Activity Released (Ci) ------------ 2.97E-03 ------------ ------------

5

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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 9.10E+00 1.12E+01 1.78E+01 2.31E+01 2.50E+01
2. Average release rate for period Ci/sec 1.16E+00 1.43E+00 2.24E+00 2.91E+00
3. Applicable ODCM Limit  % * * *
1. Total Iodine-131 Ci 1.24E-04 2.05E-04 3.03E-04 1.32E-04 2.50E+01
2. Average release rate for period Ci/sec 1.58E-05 2.61E-05 3.82E-05 1.66E-05
3. Applicable ODCM Limit  % * * *
  • C. PARTICULATES
1. Particulates with half-lives >8 days Ci 8.20E-07 3.00E-06 7.57E-05 1.10E-04 3.60E+01
2. Average release rate for period Ci/sec 1.04E-07 3.81E-07 9.52E-06 1.38E-05
3. Applicable ODCM Limit  % * * * *
4. Gross alpha radioactivity Ci 4.29E-07 1.98E-07 3.95E-07 1.03E-06 2.50E+01 D. TRITIUM
1. Total Release Ci 7.66E+00 1.01E+01 1.08E+01 7.33E+00 2.50E+01
2. Average release rate for period Ci/sec 9.74E-01 1.29E+00 1.36E+00 9.22E-01
3. Applicable ODCM Limit  % * * *
  • 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  % 4.55E-03 5.27E-03 7.88E-03 1.24E-02
2. Quarterly beta air dose limit  % 3.28E-04 4.13E-04 6.50E-04 8.96E-04
3. Yearly gamma air dose limit  % 2.28E-03 2.63E-03 3.94E-03 6.20E-03
4. Yearly beta air dose limit  % 1.64E-04 2.06E-04 3.25E-04 4.48E-04
5. Whole body dose rate limit  % 5.23E-03 7.94E-03 1.50E-02 7.79E-03
6. Skin dose rate limit  % 1.12E-03 1.73E-03 3.28E-03 1.68E-03 HALOGENS, TRITIUM AND PARTICULATES WITH HALF-LIVES >8 DAYS
7. Quarterly dose limit (organ)  % 2.50E-02 4.27E-02 6.01E-02 1.90E-02
8. Yearly dose limit (organ)  % 1.25E-02 2.13E-02 3.01E-02 9.52E-03
9. Organ dose rate limit  % 3.04E-05 3.84E-05 5.71E-05 3.04E-05 6

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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 2.23E+00 2.05E+00 1.14E+00 3.43E+00 Krypton-85m Ci 8.10E-01 9.79E-01 1.48E+00 1.30E+00 Krypton-87 Ci 7.18E-01 6.11E-01 1.22E+00 2.95E+00 Krypton-88 Ci 4.73E-01 3.75E-01 1.34E+00 2.84E+00 Xenon-133 Ci 2.31E-01 7.47E-01 2.08E+00 2.52E-01 Xenon-135 Ci 1.14E+00 8.21E-01 1.78E+00 3.90E+00 Xenon-135m Ci 9.65E-01 1.38E+00 2.27E+00 1.95E+00 Xenon-137 Ci ------------ 4.35E-01 5.86E-01 ------------

Xenon-138 Ci 2.48E+00 3.80E+00 5.85E+00 6.53E+00 TOTAL Ci 9.05E+00 1.12E+01 1.77E+01 2.32E+01

2. Iodines Iodine-131 Ci 2.35E-05 1.66E-05 3.03E-05 1.12E-04 Iodine-132 Ci ------------ ------------ ------------ 1.36E-04 Iodine-133 Ci 1.21E-04 1.60E-04 1.39E-04 5.04E-04 Iodine-135 Ci ------------ 1.17E-04 ----------- 4.06E-04 TOTAL Ci 1.45E-04 2.94E-04 1.69E-04 1.16E-03
3. Particulates Cobalt-60 Ci ------------ ------------ 4.45E-07 2.88E-07 Chromium-51 Ci ------------ ------------ ------------ 8.48E-07 Iron-59 Ci ------------ ------------ ------------ 7.04E-07 Manganese-54 Ci ------------ ------------ 6.92E-07 1.23E-06 Strontium-89 Ci 8.20E-07 4.76E-07 1.04E-06 5.88E-07 TOTAL Ci 8.20E-07 4.76E-07 2.18E-06 3.66E-06
4. Tritium Hydrogen-3 Ci 6.77E-01 7.59E-01 6.42E-01 5.51E-01 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 2012 - DECEMBER 2012 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 1.03E-02 2.19E-02 1.95E-02 ------------

Xenon 135 Ci 2.97E-02 1.68E-04 4.03E-02 ------------

Xenon-135M Ci 1.46E-02 ------------ 4.77E-03 ------------

TOTAL Ci 5.46E-02 2.21E-02 6.46E-02 ------------

2. Iodines Iodine-131 Ci 1.01E-04 1.89E-04 2.73E-04 1.93E-05 Iodine-132 Ci 1.91E-04 9.65E-05 4.50E-04 ------------

Iodine-133 Ci 7.76E-04 1.47E-03 1.72E-03 7.10E-05 Iodine-135 Ci 1.55E-04 4.37E-04 1.25E-03 ------------

TOTAL Ci 1.22E-03 2.19E-03 3.69E-03 9.03E-03

3. Particulates Barium-140 Ci ------------ ------------ 1.71E-05 ------------

Cobalt-58 Ci ------------ ------------ 1.71E-06 1.54E-06 Cobalt-60 Ci ------------ ------------ 9.60E-06 5.34E-06 Chromium-51 Ci ------------ ------------ ------------ 2.90E-05 Iron-59 Ci ------------ ------------ ------------ 1.07E-05 Manganese-54 Ci ------------ ------------ 5.52E-06 2.25E-05 Selenium-75 Ci ------------ ------------ ----------- 3.93E-06 Strontium-89 Ci ------------ 2.52E-06 2.36E-05 1.23E-05 Zinc-65 Ci ------------ ------------ 1.60E-05 2.11E-05 TOTAL Ci ------------ 2.52E-06 7.35E-05 1.06E-04

4. Tritium Hydrogen-3 Ci 6.98E+00 9.36E+00 1.02E+01 6.78E+00 Note: There were no batch releases for this report period.

8

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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 2.84E-02 5.21E-02 5.65E-02 7.40E-02 2.50E+01
2. Average diluted concentration during period (Note 1) Ci/ml 3.88E-06 8.91E-06 1.25E-05 6.62E-06
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 7.07E+06 5.51E+06 4.51E+06 1.12E+07 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 1.14E+09 1.18E+10 1.14E+08 3.40E+08 G. PERCENT OF APPLICABLE ODCM LIMITS
1. Quarterly Whole Body Dose  % 3.15E-04 1.06E-03 1.63E-03 4.58E-04
2. Quarterly Organ Dose  % 9.46E-05 3.17E-04 4.89E-04 1.37E-04
3. Annual Whole Body Dose  % 1.58E-04 5.29E-04 8.14E-04 2.29E-04
4. Annual Organ Dose  % 4.73E-05 1.59E-04 2.44E-04 6.87E-05 Note: Concentration includes summation from diluted and undiluted values from Canal and Non-Canal releases (Table 2B).

9

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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 8.80E-04 4.31E-06 3.32E-06 5.45E-06
3. Dissolved and Entrained Gases None Ci ------------- ------------- -------------- ------------

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

TABLE 2B (SUPPLEMENT) 10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 LIQUID EFFLUENTS NON-CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4

1. Fission and Activation Products None Ci ------------- ----------- -------------- ------------
2. Tritium Hydrogen-3 Ci 2.72E-02 4.81E-02 5.34E-02 7.37E-02
3. Dissolved and Entrained Gases None Ci ------------- ----------- -------------- ------------

TABLE 2B (SUPPLEMENT) 11

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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 2.74E-04 9.61E-04 3.12E-03 2.39E-04
3. Dissolved and Entrained Gases None Ci ------------- ----------- -------------- ------------

TABLE 2B (CONTINUED)

ABNORMAL RELEASE 12

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 LIQUID EFFLUENTS CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4

1. Fission and Activation Products None Ci ------------- ----------- -------------- ------------
2. Tritium Hydrogen-3 Ci ------------ 2.97E-03 ------------- -------------
3. Dissolved and Entrained Gases None Ci ------------- ----------- -------------- ------------

13

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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 8.48E+02 1.13E+01 0.00E+00 2.50E+01 waste, contaminated equipment, Ci 5.95E+01 4.36E+02 0.00E+00 2.50E+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 1.20E-02 6.04E-02 E Cobalt-58 1.00E-03 4.85E-03 E Cobalt-60 1.85E+01 7.85E+01 E Cesium-134 2.27E-01 1.12E+00 E Cesium-137 2.36E+00 1.17E+01 E Iron-55 7.16E+01 3.55E+02 E Carbon-14 1.52E-01 7.54E-01 E Manganese-54 1.99E+00 9.87E+00 E Nickel-63 3.00E+00 1.49E+01 E Strontium-90 1.89E-01 9.39E-01 E Zinc-65 4.56E+00 2.26E+01 E Hydrogen-3 5.80E-02 2.87E-01 E Plutonium-238 1.00E-03 4.30E-03 E Iron-59 2.00E-03 8.06E-03 E Curium-243 1.00E-03 6.49E-03 E Curium-244 1.00E-03 4.84E-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.

14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition No. of Shipments Mode of Transportation Destination 23 Truck *Energy Solutions Oak Ridge, TN 15 Truck *Energy Solutions Kingston, TN 4 Truck *Studsvik Processing Facility Erwin, TN
  • Volume Reduction Facility B. IRRADIATED FUEL SHIPMENTS (Disposition)

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

15

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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 16 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 96 ft^3 STC 31 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 1033 ft^3 STC 11 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 206.1 ft^3 STC 1 Contaminated Equipment, etc.

Spent Resins, Filter Sludges, evaporator Air Drying 205.8 ft^3 HIC 15 Bottoms, etc. Non-compacted Spent Resins, Filter Sludges, evaporator Air Drying 120.3 ft^3 HIC 3 Bottoms, etc. Non-compacted B. NRC CLASS B SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Spent Resins, Filter Sludges, evaporator Air Drying 120.3 ft^3 HIC 4 Bottoms, etc. Non-compacted 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 16

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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).

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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.

18

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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 reports samples that were a deviation from the requirements of ODCM Part 1, Table 5.1-1. ODCM Part 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 approximately 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> during the week of 03/27/12 to 04/03/12. The air sample stations were found operating during normal weekly sample change outs. Sample volumes for the period were acceptable. Confirmed power outages in the area of the stations during sampling duration.
2. Loss of power to environmental air sample stations R5 Offsite for 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, for sample period 7/3/12 to 7/10/12. The air sample station was found operating during normal weekly sample change outs. Sample volume for the period was acceptable.

Rain and windstorms in the area during sampling duration.

3. Loss of power to environmental air sample station R5 offsite for 5.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for sample period 7/24/12 to 8/7/12. The air sample station was found operating during normal weekly change out. Sample volume for the period was acceptable. Rain, high winds, and lightening storms in the area during sampling duration.
4. Loss of power to environmental air sample station R5 Offsite for 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> between 8/14/12 and 8/21/12. The air sample station was found operating during normal weekly sample change outs. Sample volume for the period was acceptable. Power outage due to utility maintenance in the area.
5. Loss of power to environmental air sample stations R1, R2, R3, and R4 Offsite found during weekly surveillances. R1 and R2 were lost for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> each and R3 and R4 were lost for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> each during the sample period from 10/23/12 to 10/30/12. This was evident from the lack of time on the pump integrators. Perceived cause was loss of power from hurricane Sandy. Sample volume for the period was acceptable.

20

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 ATTACHMENT NO. 4 (continued)

DEVIATIONS FROM THE REQUIRED ENVIRONMENTAL SAMPLING SCHEDULE 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 43,876 hours0.0101 days <br />0.243 hours <br />0.00145 weeks <br />3.33318e-4 months <br /> out of a possible 43,920 hours0.0106 days <br />0.256 hours <br />0.00152 weeks <br />3.5006e-4 months <br />. The air sampling availability factor for the report period was 99.9%.

21

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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.

22

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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 less than the Lower Limit Of Detection (LLD), up to a maximum concentration of 29,894 pCi/l for a MW CST-B sample from 4/11/12. Such levels are below the Reporting Level of the James A.

FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1, Table 5.1-2, for tritium. The Reporting Level for tritium is 30,000 pCi/l. Approximately 180 ml was obtained from MW CST-B for the 4/11/12 sample. The normal sample volume is one liter. MW CST-B is a shallow horizontal well and during periods of low precipitation, it yields very small sample volumes and elevated tritium concentrations. All of the affected 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 MW CST-B was consumed as drinking water, the maximum dose would be 3.1 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).

For 2012, the MW CST-B samples were analyzed for Sr-90 on a quarterly basis. The exception was the 3rd quarter, 2012 where a significant volume was not able to be obtained from the well for analysis due to extremely dry conditions. The Sr-90 concentrations detected were in trace amounts. The range was 1.2 to 2.5 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 2012 monitoring effort that is attributable to James A. FitzPatrick operations is tritium, and all concentrations were below any reporting criteria.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 ATTACHMENT NO. 7 (continued)

ONSITE GROUNDWATER MONITORING A) Gamma Isotopic Monitoring For 2012, 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.

25

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 ATTACHMENT NO. 7 (continued)

ONSITE GROUNDWATER MONITORING B) Tritium Summary

  1. Positive Minimum Maximum
  1. Samples Samples in Positive Positive Well Name in 2012 2012 Concentration Concentration MW-5 13 13 419 1036 MW-6 13 13 455 891 MW-7 12 3 367 472 MW-8 12 8 363 659 MW-9 12 4 400 487 MW-1A 12 4 378 476 MW-1B 12 0 0 0 MW-2A 12 11 479 787 MW-2B 12 1 352 352 MW-3A 12 12 438 742 MW-3B 12 10 356 603 MW-4A 12 9 409 538 MW-4B 12 0 0 0 MW-10A 11 8 341 475 MW-10B 12 0 0 0 MW-13 12 8 432 629 MW-14 11 0 0 0 MW-15 12 3 410 529 MW-16 12 11 404 675 MW-CSTA 13 13 460 884 MW-CSTB 14 14 1245 29894 Note 1: All results are in pCi/L.

Note 2: A total of 255 samples were analyzed for H-3 in 2012 with 145 positive results.

Note 3: The LLD was 500 pCi/L.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 ATTACHMENT NO. 8 GASEOUS EFFLUENTS - CARBON-14 a) Date: January 01, 2012 - December 31, 2012 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(1):

UNIT QTR 1 QTR 2 QTR 3 QTR 4 Ci 2.60E+00 2.58E+00 2.18E+00 1.53E+00 Ci/sec 3.40E-01 3.40E-01 3.40E-01 3.39E-01 h) Resultant Doses: See Addendum 1Assessment of Radiation Doses to the Public January-December 2012 Table 1E i) Dose Calculations: Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Section 4.4.1 (1)

Curies released calculated using the methodology in EPRI Technical Report 1021106 Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents.

27

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 ATTACHMENT NO. 9 LIQUID EFFLUENTS - ABNORMAL CANAL RELEASE a) Date: May 03, 2012 - May 08, 2012 b) Location: C Service Water Strainer to Defish Flange c) Duration: 8.41E+03 Minutes d) Flowrate: 9.33E-01 gpm e) Volume Released: 7.85+03 gallons f) Nuclides Released: See Table 2B - Supplemental Abnormal Release Liquid Effluents Canal- Continuous mode g) Resultant Doses: See Addendum 1Assessment of Radiation Doses to the Public January-December 2012 Table 1B h) Dose Calculations: Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Part 2, Section 3.4.1, Annual Dose Assessment-Radioactive Effluent Release Report Submittal.

ADDENDUM 1 28

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2012

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.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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, 2012 to December 31, 2012. Historical meteorological data was used to generate tables of average dispersion factors. Locations of interest were identified from the 2012 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) 32

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 2012 A. LIQUIDS QUARTER 1 2 3 4 ANNUAL (a) (a) (a) (a) (a)

Organ (mrem) 4.73E-06 1.59E-05 2.44E-05 6.87E-06 5.19E-05

% of Limit 9.46E-05 3.17E-04 4.89E-04 1.37E-04 5.19E-04 (b) (b) (b) (b) (b)

Whole Body (mrem) 4.73E-06 1.59E-05 2.44E-05 6.87E-06 5.19E-05

% of Limit 3.15E-04 1.06E-03 1.63E-03 4.58E-04 1.73E-03 (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.

B. ABNORMAL LIQUID CANAL RELEASE QUARTER 1 2 3 4 ANNUAL

(-) (a) (-) (-) (a)

Organ (mrem) ---------- 3.04E-09 ---------- ---------- 3.31E-09

% of Limit ---------- 6.07E-08 ---------- ---------- 3.31E-08

(-) (b) (-) (-) (b)

Whole Body (mrem) ---------- 3.04E-09 ---------- ---------- 3.31E-09

% of Limit ---------- 2.02E-07 ---------- ---------- 1.10E-07 (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.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 ADDENDUM 1 (continued)

TABLE 1 (cont)

ANNUAL DOSE ASSESSMENT 2012 C. NOBLE GASES QUARTER 1 2 3 4 ANNUAL Total Body (mrem/yr) 2.61E-02 3.97E-02 7.50E-02 3.90E-02 7.50E-02

% of Limit 5.23E-03 7.94E-03 1.50E-02 7.79E-03 1.50E-02 Skin (mrem/yr) 3.37E-02 5.18E-02 9.84E-02 5.03E-02 9.84E-02

% of Limit 1.12E-03 1.73E-03 3.28E-03 1.68E-03 3.28E-03 Gamma (mrad) 2.28E-04 2.63E-04 3.94E-04 6.20E-04 1.51E-03

% of Limit 4.55E-03 5.27E-03 7.88E-03 1.24E-02 1.51E-02 Beta (mrad) 3.28E-05 4.13E-05 6.50E-05 8.96E-05 2.29E-04

% of Limit 3.28E-04 4.13E-04 6.50E-04 8.96E-04 1.14E-03 D. IODINES AND PARTICULATES QUARTER 1 2 3 4 ANNUAL (a) (a) (a) (a) (a)

Organ (mrem) 1.88E-03 3.20E-03 4.51E-03 1.43E-03 1.09E-02

% of Limit 2.50E-02 4.27E-02 6.01E-02 1.90E-02 7.26E-02 (a) (a) (a) (a) (a)

Organ Dose Rate 4.56E-04 5.75E-04 8.56E-04 4.57E-04 8.56E-04 (mrem/yr)

% of Limit 3.04E-05 3.84E-05 5.71E-05 3.04E-05 5.71E-05 (a) Dose to the Child Thyroid primarily by the vegetation pathway.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 ADDENDUM 1 (continued)

TABLE 1 (cont)

ANNUAL DOSE ASSESSMENT 2012 E. CARBON 14 QUARTER 1 2 3 4 ANNUAL (a) (a) (a) (a) (a)

Organ (mrem) 8.30E-03 8.24E-03 6.95E-03 4.89E-03 2.84E-02

% of Limit 1.11E-01 1.10E-01 9.27E-02 6.52E-02 1.89E-01 (a)

Organ Dose Rate ------------ ---------- ----------- ---------- 2.84E-02 (mrem/yr)

% of Limit ------------ ---------- ------------ ---------- 1.89E-03 (a) Dose to the Child Bone primarily by the vegetation pathway.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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)

1. Garden 0.90 mi @ 83E ST 2.83E-08* 1.75E-09 Grazing Season 0.90 mi @ 83E RX 2.02E-07* 5.01E-09 Cary 0.90 mi @ 83E TB 1.83E-07* 4.80E-09 Location No. 78 0.90 mi @ 83E RF 2.02E-07* 5.01E-09 0.90 mi @ 83E RW 3.21E-07* 5.76E-09
2. Meat 1.18 mi @ 127SE ST 1.72E-08* 6.80E-10 Grazing Season 1.18 mi @ 127SE RX 5.36E-08* 1.30E-09 Parkhurst 1.18 mi @ 127SE TB 5.14E-08* 1.27E-09 Location No. 26 1.18 mi @ 127SE RF 5.36E-08* 1.30E-09 1.18 mi @ 127SE RW 9.12E-08* 1.46E-09
3. Cow 2.50 mi @ 139SE ST 1.67E-08* 2.65E-10 Grazing Season 2.50 mi @ 139SE RX 2.76E-08* 4.14E-10 France 2.50 mi @ 139SE TB 2.71E-08* 4.07E-10 Location No. 10 2.50 mi @ 139SE RF 2.76E-08* 4.14E-10 2.50 mi @ 139SE RW 4.15E-08* 4.36E-10
4. Goat (D/Q) 3.62 mi @ 113ESE ST ----------- 2.28E-10 Grazing Season 3.62 mi @ 113ESE RX ----------- 3.40E-10 Showers 3.62 mi @ 113ESE TB ----------- 3.33E-10 Location No. 71 3.62 mi @ 113ESE RF ----------- 3.40E-10 3.62 mi @ 113ESE RW ----------- 3.49E-10
5. Goat (X/Q) 2.64 mi @ 152SSE ST 1.94E-08* -----------

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

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

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

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

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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 @ 90E(1) ST 2.99E-08 -----------

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

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

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

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

b. Deposition(3) 0.71 mi @ 118ESE ST ----------- 1.60E-09 Whaley 0.71 mi @ 118ESE RX ----------- 5.52E-09 Location No. 199 0.71 mi @ 118ESE TB ----------- 5.30E-09 0.71 mi @ 118ESE RF ----------- 5.52E-09 0.71 mi @ 118ESE RW ----------- 6.28E-09 B. NOBLE GASES
1. Air Dose 1.55 mi @ 90E(1) ST 2.99E-08 -----------

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

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

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

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

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

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

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

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

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

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

37

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2012 - DECEMBER 2012 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 @ 90E ST 2.99E-08 -----------

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

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

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

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

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

    • 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 38

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