JAFP-11-0055, 2010 Annual Radioactive Effluent Release Report, for the Period of January 1, 2010 Through December 31, 2010

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2010 Annual Radioactive Effluent Release Report, for the Period of January 1, 2010 Through December 31, 2010
ML111190561
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/29/2011
From: Joseph Pechacek
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-11-0055
Download: ML111190561 (44)
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 Joseph Pechacek Licensing Manager JAFP-11-0055 April 29, 2011 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

SUBJECT:

2010 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, 2010 through December 31, 2010. 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 2010 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.

SiZ" .

~sep Pechace Licens ng Manager JP/LR/jbh

Enclosure:

Annual Radioactive Effluent Release Report, January 1, 201 O-December 31, 2010 cc: next page

JAFP-11-0055 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. Bhalchandra Vaidya, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8-C2A Washington, DC 20555-0001 D. Sherman (ANI Library)

P. Merges (NYSDEC)

B. Sullivan (JAF)

C. Faison (ENOC/WPO)

J. McCann (ENOC/WPO)

W. Hamblin (CHEM/JAF)

K. Stoffle (NMP)

J. Furfaro (ENV/JAF)

Document Contents:

001 Transmittal Letter, JAFP-11-0055 with Report

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2010 - DECEMBER 31, 2010 DOCKET NO. 50-333 LICENSE NO. DPR-59

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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 2010 - DECEMBER 2010 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 2010 - DECEMBER 2010 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 2010 - DECEMBER 2010 SUPPLEMENTAL INFORMATION (continued)

5. Batch Releases
a. Liquid: Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 4.90E+01 5.20E+01 5.80E+01 7.20E+01 (2) Total time period for batch 2.51E+03 2.70E+03 5.49E+03 4.69E+03 release: (min)

(3) Maximum time period for 7.50E+01 8.00E+01 1.66E+03 6.66E+02 batch release: (min)

(4) Average time period for 5.12E+01 5.19E+01 9.47E+01 6.51E+01 batch release: (min)

(5) Minimum time period for 1.00E+00 2.00E+00 1.00E+00 8.00E+00 batch release: (min)

(6) Total Activity Released (Ci) 7.63E-03 2.04E-02 1.08E-01 4.88E-02 (7) Total Volume Released (liters) 2.74E+06 2.81E+06 3.14E+06 4.27E+06

b. Liquid: Non-Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 4.00E+00 8.00E+00 1.30E+01 5.00E+00 (2) Total time period for batch 8.13E+02 4.17E+02 1.09E+03 1.12E+03 release: (min)

(3) Maximum time period for 3.75E+02 1.90E+02 2.39E+02 4.94E+02 batch release: (min)

(4) Average time period for 2.03E+02 5.21E+01 8.39E+01 2.23E+02 batch release: (min)

(5) Minimum time period for 1.00E+00 5.00E+00 7.00E+00 1.00E+00 batch release: (min)

(6) Total Activity Released (Ci) 3.78E-03 6.33E-04 3.54E-03 1.14E-03 (7) Total Volume Released (liters) 2.57E+05 1.58E+05 4.13E+05 4.22E+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 2010 - DECEMBER 2010 SUPPLEMENTAL INFORMATION (continued)

6. Abnormal Releases
a. Liquid UNIT QTR 1 QTR 2 QTR 3 QTR 4 (1) Number of releases: 1.00E+00 --------- --------- ---------

(2) Total activity released Ci 5.20E-03 --------- --------- ---------

b. Gaseous (1) Number of releases: None None None None (2) Total activity released None None None None 5

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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 1.44E+01 2.52E+01 4.77E+01 1.45E+01 2.50E+01
2. Average release rate for period Ci/sec 1.83E+00 3.20E+00 6.00E+00 1.82E+00
3. Applicable ODCM Limit  % * * *
1. Total Iodine-131 Ci 1.03E-04 1.14E-04 1.04E-04 2.50E-05 2.50E+01
2. Average release rate for period Ci/sec 1.32E-05 1.45E-05 1.31E-05 3.15E-06
3. Applicable ODCM Limit  % * * *
  • C. PARTICULATES
1. Particulates with half-lives >8 days Ci 4.11E-06 1.34E-05 3.30E-05 3.37E-05 3.60E+01
2. Average release rate for period Ci/sec 5.23E-07 1.70E-06 4.15E-06 4.24E-06
3. Applicable ODCM Limit  % * * * *
4. Gross alpha radioactivity Ci 2.88E-07 4.29E-07 5.34E-07 4.34E-07 2.50E+01 D. TRITIUM
1. Total Release Ci 1.05E+01 1.12E+01 9.08E+00 5.41E+00 2.50E+01
2. Average release rate for period Ci/sec 1.33E+00 1.42E+00 1.14E+00 6.80E-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  % 2.58E-03 8.09E-03 1.63E-02 5.49E-03
2. Quarterly beta air dose limit  % 2.53E-04 4.69E-04 8.64E-04 3.98E-04
3. Yearly gamma air dose limit  % 1.29E-03 4.04E-03 8.16E-03 2.74E-03
4. Yearly beta air dose limit  % 1.27E-04 2.35E-04 4.32E-04 1.99E-04
5. Whole body dose rate limit  % 5.34E-03 2.62E-03 8.18E-03 1.89E-03
6. Skin dose rate limit  % 1.59E-03 9.23E-04 1.65E-03 4.07E-04 HALOGENS, TRITIUM AND PARTICULATES WITH HALF-LIVES >8 DAYS
7. Quarterly dose limit (organ)  % 2.40E-02 2.61E-02 2.34E-02 9.25E-03
8. Yearly dose limit (organ)  % 1.20E-02 1.31E-02 1.17E-02 4.63E-03
9. Organ dose rate limit  % 4.51E-05 4.51E-05 2.29E-05 1.63E-05 6

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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 2.31E+00 4.29E+00 3.42E+00 2.52E+00 Krypton-85m Ci 1.63E+00 5.24E+00 8.71E+00 6.94E+00 Krypton-87 Ci ------------ ------------ 4.91E-01 5.69E-01 Krypton-88 Ci 5.00E-01 3.96E+00 1.11E+01 1.63E+00 Xenon-133 Ci 9.83E+00 1.16E+01 2.39E+01 5.06E-01 Xenon-135 Ci ------------ ------------ ------------ 5.63E-01 Xenon-135m Ci ------------ ------------ ------------ 3.47E-01 Xenon-137 Ci ------------ ------------ ------------ 8.50E-02 Xenon-138 Ci ------------ ------------ ------------ 1.32E+00 TOTAL Ci 1.43E+01 2.51E+01 4.77E+01 1.45E+01
2. Iodines Iodine-131 Ci 3.03E-06 4.24E-06 7.34E-06 2.47E-05 Iodine-133 Ci 2.02E-05 2.52E-05 2.35E-05 4.87E-05 TOTAL Ci 2.32E-05 2.94E-05 3.08E-05 7.34E-05
3. Particulates Manganese-54 Ci ------------ ------------ 3.51E-07 ------------

Strontium-89 Ci 1.25E-06 2.48E-06 1.11E-06 1.15E-06 TOTAL Ci 1.25E-06 2.48E-06 1.46E-06 1.15E-06

4. Tritium Hydrogen-3 Ci 7.97E-01 5.17E-01 7.27E-01 8.64E-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 2010 - DECEMBER 2010 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 6.65E-02 5.06E-02 1.81E-02 7.30E-03 Xenon-133M Ci ------------ 1.72E-03 ------------ ------------

Xenon 135 Ci 7.02E-02 2.24E-02 8.34E-03 3.70E-03 Xenon-135M Ci 1.37E-02 6.98E-04 6.35E-04 ------------

TOTAL Ci 1.50E-01 7.54E-02 2.71E-02 1.10E-02

2. Iodines Iodine-131 Ci 1.00E-04 1.10E-04 9.59E-05 3.08E-07 Iodine-133 Ci 6.27E-04 6.69E-04 3.86E-04 ------------

Iodine-135 Ci ------------ 1.08E-04 ------------ ------------

TOTAL Ci 7.27E-04 8.87E-04 4.82E-04 3.08E-07

3. Particulates Manganese-54 Ci ------------ ------------ 2.95E-06 2.02E-05 Cobalt-60 Ci ------------ ------------ 4.05E-06 ------------

Zinc-65 Ci ------------ ------------ 4.36E-06 6.61E-06 Strontium-89 Ci 2.46E-06 1.09E-05 6.13E-06 2.20E-06 Strontium-90 Ci 3.99E-07 ------------ 7.99E-06 3.49E-06 Barium-140 Ci ------------ ------------ 5.00E-06 ------------

TOTAL Ci 2.86E-06 1.09E-05 3.05E-05 3.25E-05

4. Tritium Hydrogen-3 Ci 9.68E+00 1.07E+01 8.35E+00 4.54E+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 2010 - DECEMBER 2010 TABLE 1D GASEOUS EFFLUENTS - UNMONITORED SHORT-TERM RELEASE CONTINUOUS MODE NUCLIDES RELEASED

1. Fission Gases UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 None
2. Iodines Iodine-131 Ci ------------ ------------ 5.35E-07 3.81E-09
3. Particulates Cobalt-60 Ci ------------ ------------ 1.02E-06 ------------
4. Tritium None 9

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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 1.66E-02 2.10E-02 1.11E-01 5.02E-02 2.50E+01
2. Average diluted concentration during period (Note 1) Ci/ml 2.32E-06 2.18E-07 1.01E-06 3.09E-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 3.88E+06 2.97E+06 3.56E+06 4.69E+06 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 3.75E+09 4.09E+09 6.57E+09 5.21E+09 G. PERCENT OF APPLICABLE ODCM LIMITS
1. Quarterly Whole Body Dose  % 5.46E-04 2.92E-04 9.21E-04 9.80E-05
2. Quarterly Organ Dose  % 1.64E-04 8.75E-05 2.76E-04 2.94E-05
3. Annual Whole Body Dose  % 2.73E-04 1.46E-04 4.60E-04 4.90E-05
4. Annual Organ Dose  % 8.19E-05 4.38E-05 1.38E-04 1.47E-05 Note: Concentration includes summation from diluted and undiluted values from Canal and Non-Canal releases (Table 2B).

10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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 7.62E-03 2.04E-02 1.08E-01 4.88E-02
3. Dissolved and Entrained Gases None Ci ------------- ------------- -------------- ------------

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

11

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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 3.78E-03 6.33E-04 3.54E-03 1.41E-03
3. Dissolved and Entrained Gases None Ci ------------- ----------- -------------- ------------

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

12

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 TABLE 2B (CONTINUED)

ABNORMAL RELEASE 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 5.20E-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 2010 - DECEMBER 2010 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 vaporator 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 components, 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 6.23E+04 0.00E+00 0.00E+00 1.00E+01 waste, contaminated equipment, Ci 4.93E+01 0.00E+00 0.00E+00 1.00E+01 spent resins contaminated oil, glycol and water 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 4.11E-02 2.03E-02 E Cobalt-58 1.23E-02 6.06E-03 E Cobalt-60 1.36E+01 6.69E+00 E Cesium-134 5.31E-01 2.62E-01 E Cesium-137 3.88E+00 1.91E+00 E Iron-55 6.25E+01 3.08E+01 E Carbon-14 8.06E-01 3.98E-01 E Manganese-54 3.25E+00 1.61E+00 E Nickel-63 5.96E+00 2.94E+00 E Strontium-90 7.15E-01 3.53E-01 E Zinc-65 8.65E+00 4.27E+00 E Hydrogen-3 1.17E-01 5.78E-02 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 2010 - DECEMBER 2010 TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition No. of Shipments Mode of Transportation Destination 15 Truck *Energy Solutions Oak Ridge, TN 33 Truck *Energy Solutions Kingston, 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 2010 - DECEMBER 2010 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 17 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 96 ft^3 STC 36 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 1033 ft^3 STC 32 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 STC 11 Bottoms, etc. Non-compacted Spent Resins, Filter Sludges, evaporator Air Drying 120.3 ft^3 HIC 2 Bottoms, etc. Non-compacted Contaminated Oil Non-compacted 7.5 ft^3 STC 12 Glycol & Water Non-compacted 7.5 ft^3 STC 6 16

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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 17

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.

Revision 20 of the ODCM was approved by the Onsite Safety Review Committee on April 30, 2010 at Meeting Number [[::JAF-2010-007|JAF-2010-007]] and became effective on June 15, 2010. This revision does not reduce the accuracy or reliability of any dose calculations or setpoint determinations.

Listed below is a brief summary of changes incorporated in this revision.

Rev. 11 Part II Updated Table H-1. Shoreline Sediment - Sunset Bay Appendix H Shoreline was changed from 1.4 mi to 1.2 mi and from Page H-7 82°E to 84°E. This change increases the accuracy of Table H-1 the ODCM.

Part II Updated Table H-1. Garden Location 484 was added Appendix H to Food Products. This change increases the accuracy Page H-9 of the ODCM.

Table H-1 Part II Updated Table H-1. In Table H-1, ** was added to Appendix H Food Products for collection site R. Lee and Page H-9 Oldenberg. This change is an editorial correction.

Figure H-1 Part II Updated Figure H-1. Garden Location 484 was added Appendix H to Figure H-1. This change increases the accuracy of Page H-11 the ODCM.

Figure H-1 18

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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.

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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. The air sampling pumps at the R1 offsite & R2 offsite environmental sampling stations were inoperable for 3.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> each during the sampling period 5/18/10-5/25/10. The sample pump out of service time was determined based on the sample pump run time integrator. The inoperability of the pump was due to loss of power to the sampler. No corrective actions were required to restore unit to service.
2. The air sampling pumps at R1 offsite and R2 offsite environmental sampling stations were inoperable for 1.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> each during the sampling period of 8/17/10 to 8/24/10.

The sample pump out of service time was determined based on the sample pump run time integrator. The inoperability of the pump was due to loss of power to the sampler. No corrective actions were required to restore unit to service.

3. JAF Inlet Canal sampler found not working on 9/14/2010. Sampler out of service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Sampler pump was replaced.
4. JAF Inlet Canal sampler found not working on 9/18/2010. Sampler out of service for 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />. Sampler pump was replaced.
5. Notified by Nine Mile that the gas meter for at R1 offsite environmental sample station was taken out of service on 8/10/2010 due to variation in sample flow noted from 7/27/2010 to 8/10/2010. The gas meter was sent to a vendor to perform a calibration check. The calibration check indicated that the flow rate for the R1 offsite gas meter was low by 8.5%. Sample data from 7/27/2010 to 8/10/2010 were recalculated using a flow correction factor of -8.5%. The recalculated results met the ODCM lower limit of detection criteria. The gas meter has been retired.

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 ATTACHMENT NO. 4 (continued)

DEVIATIONS FROM THE REQUIRED ENVIRONMENTAL SAMPLING SCHEDULE

6. The air sampling pumps at the R5 offsite air sample station had a flow rate of 104 ft3/

hour for the sample period 11/2/10 to 11/9/10. The acceptance range is 108 ft3/ hour to 132 ft3 / hour. The sample pump out of service time was determined based on the sample pump run time integrator. The inoperability of the pump was due to loss of power to the sampler due to adverse weather conditions. No corrective actions were required to restore unit to service.

7. Loss of power to environmental air sample stations R1 and R2 offsite for 2.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> each, R5 offsite for 2.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, during the week of 11/16/10 to 11/23/10. The sample pump out of service time was determined based on the sample pump run time integrator. The inoperability of the pump was due to loss of power to the sampler due to adverse weather conditions. No corrective actions were required to restore unit to service.
8. The air sampling pumps at the R5 offsite air sample station lost 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of time for sample period 12/7/10 to 12/14/10. The station was found operating during normal weekly sample change. The sample pump out of service time was determined based on the sample pump run time integrator. The inoperability of the pump was due to loss of power to the sampler due to adverse weather conditions. No corrective actions were required to restore unit to service.

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 43,781 hours0.00904 days <br />0.217 hours <br />0.00129 weeks <br />2.971705e-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 99.96%.

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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.

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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. 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. The minimum detectable concentration (MDC) for tritium was lowered from1000 pCi/l to 500 pCi/l in the fourth quarter of 2010.

Analysis results of tritium ranged from non-detectable at less than 410 pCi/l, up to a maximum concentration of 2803 pCi/l. 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 less than 0.3 mrem/yr. 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 mile west of the JAF discharge).

Tritium results for MW CST-B for sampling date 12/2/10 indicated a tritium concentration of 2803 pCi/l. Based on exceeding site administrative limits, monitoring wells were analyzed. This sample was sent out for Fe-55, Ni-63, Sr-89, and Sr-90 analysis. Only Sr-90 was identified in a trace amount (2.6 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 a high uncertainty in the result for Sr-90, since it was very close to the analytical laboratorys detection capability.

In conclusion, the only radionuclide detected in groundwater during the 2010 monitoring effort that is attributable to James A. FitzPatrick operations is tritium, and all concentrations were well below any reporting criteria established in the JAF Offsite Dose Calculation Manual.

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 ATTACHMENT NO. 7 (continued)

ONSITE GROUNDWATER MONITORING A) Gamma Isotopic Monitoring For 2010, the five original Monitoring Wells were sampled and analyzed to below the required lower limits of detection in accordance with the Offsite Dose Calculation Manual (ODCM) Part 1, Table 5.1-3. Starting the fourth quarter of 2010, all monitoring wells were analyzed at least once, 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.

For the first three quarters of 2010, the sixteen Monitoring Wells installed in March, 2010 were sampled and analyzed to below the lower limits of detection in accordance with the Offsite Dose Calculation Manual (ODCM), Part I, Table 2.2.1. These values are as follows:

LLD Value LLD Value Radionuclide (Ci/ml) Radionuclide (Ci/ml)

Manganese-54 5.0E-7 Iodine-131 1.0E-6 Cobalt-58 5.0E-7 Cesium-134 5.0E-7 Iron-59 5.0E-7 Cesium-137 5.0E-7 Cobalt-60 5.0E-7 Cerium-141 5.0E-5 Zinc-65 5.0E-7 Cerium-144 5.0E-5 Molybdenum-99 5.0E-5 There were no plant related nuclides detected in the samples.

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 ATTACHMENT NO. 7 (continued)

ONSITE GROUNDWATER MONITORING B) Tritium Summary

  1. Positive
  1. Samples Samples in Min Pos Max Pos Well Name in 2010 2010 Act Act MW-5 20 2 788 830 MW-6 20 3 412 850 MW-7 20 0 - -

MW-8 20 0 - -

MW-9 20 0 - -

MW-1A 13 0 - -

MW-1B 12 0 - -

MW-2A 14 6 410 893 MW-2B 14 0 - -

MW-3A 11 2 494 922 MW-3B 14 0 - -

MW-4A 13 0 - -

MW-4B 10 0 - -

MW-10A 13 0 - -

MW-10B 14 0 - -

MW-13 11 2 435 805 MW-14 13 5 566 1049 MW-15 13 0 - -

MW-16 13 2 847 890 MW-CSTA 5 3 649 1055 MW-CSTB 7 6 913 2803 Note 1: All results are in pCi/L.

Note 2: A total of 290 samples were analyzed for H-3 in 2010 with 31 positive results.

Note 3: For the first three quarters of 2010, the MDC was 1000 pCi/L. The MDC was lowered to 500 pCi/L in the fourth quarter of 2010.

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 ATTACHMENT NO. 8 GASEOUS EFFLUENTS - UNMONITORED SHORT-TERM RELEASE a) Date: September 22, 2010 to September 30, 2010 b) Location: Steam Tunnel via the MG Set Room c) Duration: 1.94E+02 hours d) Flowrate: 1.55E+04 cfm e) Volume Released: 1.82E+08 Cubic Feet f) Nuclides Released: See Table 1D - Supplemental Gaseous Effluents - Unmonitored Short-Term Release g) Resultant Doses: See Addendum 1Assessment of Radiation Doses to the Public January-December 2010 Table 1F h) Dose Calculations: Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Section 4.4.3 Short Term Releases 28

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 ATTACHMENT NO. 9 GASEOUS EFFLUENTS - UNMONITORED SHORT-TERM RELEASE a) Date: September 16, 2010 to October 1, 2010 b) Location: Turbine Building Door c) Duration: 3.60E+02 hours d) Flowrate: 2.73E+03 cfm e) Volume Released: 5.90 E+07 Cubic Feet f) Nuclides Released: See Table 1D - Supplemental Gaseous Effluents - Unmonitored Short-Term Release g) Resultant Doses: See Addendum 1Assessment of Radiation Doses to the Public January-December 2010 Table 1F h) Dose Calculations: Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Section 4.4.3 Short Term Releases 29

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 ATTACHMENT NO. 10 GASEOUS EFFLUENTS - CARBON-14 a) Date: January 01, 2010 - December 31, 2010 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) Resultant Doses: See Addendum 1Assessment of Radiation Doses to the Public January-December 2010 Table 1E h) Dose Calculations: Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Section 4.4.1 30

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 ATTACHMENT NO. 11 LIQUID EFFLUENTS - ABNORMAL NON-CANAL RELEASE a) Date: January 01, 2010 - January 14, 2010 b) Location: Reactor Building Perimeter Sump to West Storm Drain c) Duration: 14 Days d) Flowrate: 1.15E+01 gpm e) Volume Released: 2.32E+05 gallons f) Nuclides Released: See Table 2B - Supplemental Liquid Effluents Non-Canal Release - Continuous Mode g) Resultant Doses: See Addendum 1Assessment of Radiation Doses to the Public January-December 2010 Table 1B h) Dose Calculations: Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Part 2, Section 3.4.3, Liquid Releases through the Storm Drain 31

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 ADDENDUM 1 ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2010

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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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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, 2010 to December 31, 2010. Historical meteorological data was used to generate tables of average dispersion factors. Locations of interest were identified from the 2010 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) 35

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 2010 A. LIQUIDS QUARTER 1 2 3 4 ANNUAL (a) (a) (a) (a) (a)

Organ (mrem) 6.97E-06 4.38E-06 1.38E-05 1.47E-06 2.66E-05

% of Limit 1.39E-04 8.75E-05 2.76E-04 2.94E-05 2.66E-04 (b) (b) (b) (b) (b)

Whole Body (mrem) 6.97E-06 4.38E-06 1.38E-05 1.47E-06 2.66E-05

% of Limit 4.65E-04 2.92E-04 9.21E-04 9.80E-05 8.88E-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.

B. ABNORMAL LIQUID NON-CANAL RELEASE QUARTER 1 2 3 4 ANNUAL (a) (a)

Organ (mrem) 1.23E-06 --------- --------- --------- 1.23E-06

% of Limit 2.45E-05 --------- --------- --------- 1.23E-05 (b) (b)

Whole Body (mrem) 1.23E-06 --------- --------- --------- 1.23E-06

% of Limit 8.17E-05 --------- --------- --------- 4.09E-05 (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 2010 - DECEMBER 2010 ADDENDUM 1 (continued)

TABLE 1 (cont)

ANNUAL DOSE ASSESSMENT 2010 C. NOBLE GASES QUARTER 1 2 3 4 ANNUAL Total Body (mrem/yr) 2.67E-02 1.31E-02 4.09E-02 9.43E-03 4.09E-02

% of Limit 5.34E-03 2.62E-03 8.18E-03 1.89E-03 8.18E-03 Skin (mrem/yr) 4.76E-02 2.77E-02 4.94E-02 1.22E-02 4.94E-02

% of Limit 1.59E-03 9.23E-04 1.65E-03 4.07E-04 1.65E-03 Gamma (mrad) 1.29E-04 4.04E-04 8.16E-04 2.74E-04 1.62E-03

% of Limit 2.58E-03 8.09E-03 1.63E-02 5.49E-03 1.62E-02 Beta (mrad) 2.53E-05 4.69E-05 8.64E-05 3.98E-05 1.98E-04

% of Limit 2.53E-04 4.69E-04 8.64E-04 3.98E-04 9.92E-04 D. IODINES AND PARTICULATES QUARTER 1 2 3 4 ANNUAL (a) (a) (a) (b) (a)

Organ (mrem) 1.80E-03 1.96E-03 1.69E-03 6.94E-04 5.79E-03

% of Limit 2.40E-02 2.61E-02 2.26E-02 9.25E-03 3.86E-02 (a) (a) (a) (a) (a)

Organ Dose Rate 6.77E-04 6.77E-04 3.43E-04 2.44E-04 6.77E-04 (mrem/yr)

% of Limit 4.51E-05 4.51E-05 2.29E-05 1.63E-05 4.51E-05 (a) Dose to the Child Thyroid primarily by the vegetation pathway.

(b) 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 2010 - DECEMBER 2010 ADDENDUM 1 (continued)

TABLE 1 (cont)

ANNUAL DOSE ASSESSMENT 2010 E. CARBON 14 QUARTER 1 2 3 4 ANNUAL (a) (a) (a) (a) (a)

Organ (mrem) 7.84E-03 7.81E-03 6.10E-03 6.27E-03 2.80E-02

% of Limit 1.05E-01 1.04E-01 8.13E-02 8.36E-02 3.73E-01 (a) (a) (a) (a) (a)

Organ Dose Rate 2.80E-02 2.80E-02 2.80E-02 2.80E-02 2.80E-02 (mrem/yr)

% of Limit 1.87E-03 1.87E-03 1.87E-03 1.87E-03 1.87E-03 (a) Dose to the Child Bone primarily by the vegetation pathway.

F. UNMONITORED SHORT-TERM RELEASE QUARTER 1 2 3 4 ANNUAL (a) (a) (a)

Organ (mrem) --------- --------- 7.53E-05 3.97E-07 7.57E-05

% of Limit --------- --------- 1.00E-03 5.29E-06 5.05E-04 (b) (b) (b)

Organ Dose Rate --------- --------- 4.67E-06 1.16E-06 4.67E-06 (mrem/yr)

% of Limit --------- --------- 3.11E-07 7.75E-08 3.11E-07 (a) Dose to the Infant Thyroid primarily by the cows milk pathway.

(b) Dose to the Child Thyroid primarily by the cows milk pathway.

38

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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* -----------

39

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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 -----------

40

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2010 - DECEMBER 2010 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 -----------

    • 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 41

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