JAFP-16-0070, Transmittal of 2015 Annual Radioactive Effluent Release Report: Difference between revisions

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ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 1 SUPPLEMENTAL INFORMATION  
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 1 SUPPLEMENTAL INFORMATION  


FACILITY:  JAFNPP  LICENSEE:  ENTERGY NUCLEAR OPERATIONS, INC.  
FACILITY:  JAFNPP  LICENSEE:  ENTERGY NUCLEAR OPERATIONS, INC.
: 1. Offsite Dose Calculation Manual Part 1 Radiological Effluent Controls  a. Fission and Activation Gases:  
: 1. Offsite Dose Calculation Manual Part 1 Radiological Effluent 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:  
(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.  
(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:  
(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.  
(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:  
: 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:  
(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,  
(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.  
(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.  
(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:  
(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).
(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).
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 2 SUPPLEMENTAL INFORMATION (continued)  
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 2 SUPPLEMENTAL INFORMATION (continued)
: c. Liquid Effluents:  
: 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.
(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:  
(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.  
(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  
: 2. 10X Effluent Concentrations
: a. Fission and activation gases: (None specified)  
: a. Fission and activation gases: (None specified)
: b. Iodines:    (None specified)  
: b. Iodines:    (None specified)
: c. Particulates, half-lives >8 days: (None specified)  
: c. Particulates, half-lives >8 days: (None specified)
: d. Liquid effluents:  Quarter 1 Quarter 2 Quarter 3 Quarter 4  
: d. Liquid effluents:  Quarter 1 Quarter 2 Quarter 3 Quarter 4  


  (1) Fission and activation  None    None    None    None products (mixture EC)  
(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  
(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  
(3) Dissolved and entrained gases (Ci/ml)  2.00E-04 2.00E-04 2.00E-04 2.00E-04  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 3 SUPPLEMENTAL INFORMATION (continued)  
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 3 SUPPLEMENTAL INFORMATION (continued)
: 3. Average Energy  (None specified)  
: 3. Average Energy  (None specified)
: 4. Measurements and Approximations of Total Radioactivity  
: 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.  
: 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.  
: 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.  
: 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.  
: 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  
: 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.  
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.
: 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  
Determinate  - Pump flowrates, volume measurements and analysis collection yields  Undeterminate - Random counting error estimated using accepted statistical calculations  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 4 SUPPLEMENTAL INFORMATION (continued)  
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 4 SUPPLEMENTAL INFORMATION (continued)
: 5. Batch Releases  
: 5. Batch Releases
: a. Liquid:  Canal  Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 4.00E+00 9.00E+00 5.00E+00 8.00E+00  
: a. Liquid:  Canal  Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 4.00E+00 9.00E+00 5.00E+00 8.00E+00  


  (2) Total time period for batch 4.80E+01 2.45E+02 1.88E+02 1.78E+02 release: (min)  
(2) Total time period for batch 4.80E+01 2.45E+02 1.88E+02 1.78E+02 release: (min)  


  (3) Maximum time period for 3.40E+01 7.20E+01 9.00E+01 5.80E+01 batch release: (min)  
(3) Maximum time period for 3.40E+01 7.20E+01 9.00E+01 5.80E+01 batch release: (min)  


  (4) Average time period for 1.20E+01 2.72E+01 3.76E+01 2.22E+01 batch release: (min)  
(4) Average time period for 1.20E+01 2.72E+01 3.76E+01 2.22E+01 batch release: (min)  


  (5) Minimum time period for 1.00E+00 3.00E+00 2.00E+00 2.00E+00 batch release: (min)  
(5) Minimum time period for 1.00E+00 3.00E+00 2.00E+00 2.00E+00 batch release: (min)  


  (6) Total Activity Released (Ci) 1.31E-04 8.27E-04 1.85E-04 2.07E-04  
(6) Total Activity Released (Ci) 1.31E-04 8.27E-04 1.85E-04 2.07E-04  


  (7) Total Volume Released (liters) 4.13E+03 5.85E+04 8.24E+03 2.75E+04  
(7) Total Volume Released (liters) 4.13E+03 5.85E+04 8.24E+03 2.75E+04
: b. Liquid:  Non-Canal  Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 6.00E+00 1.10E+01 1.60E+01 2.00E+01  
: b. Liquid:  Non-Canal  Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 6.00E+00 1.10E+01 1.60E+01 2.00E+01  


  (2) Total time period for batch 2.55E+02 6.73E+02 2.96E+02 6.10E+01 release: (min)  
(2) Total time period for batch 2.55E+02 6.73E+02 2.96E+02 6.10E+01 release: (min)  


  (3) Maximum time period for 2.47E+02 3.89E+02 3.70E+01 7.00E+00 batch release: (min)  
(3) Maximum time period for 2.47E+02 3.89E+02 3.70E+01 7.00E+00 batch release: (min)  


  (4) Average time period for 4.25E+01 6.12E+01 1.85E+01 3.15E+00 batch release: (min)  
(4) Average time period for 4.25E+01 6.12E+01 1.85E+01 3.15E+00 batch release: (min)  


  (5) Minimum time period for 1.00E+00 1.00E+00 1.00E+00 1.00E+00 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) 5.89E-03 7.48E-04 5.09E-04 4.69E-05  
(6) Total Activity Released (Ci) 5.89E-03 7.48E-04 5.09E-04 4.69E-05  


  (7) Total Volume Released (liters) 9.58E+04 2.28E+05 1.12E+05 2.34E+04  
(7) Total Volume Released (liters) 9.58E+04 2.28E+05 1.12E+05 2.34E+04
: c. Gaseous  
: c. Gaseous  


There were no gaseous batch releases for this report period.
There were no gaseous batch releases for this report period.
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 5 SUPPLEMENTAL INFORMATION (continued)  
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 5 SUPPLEMENTAL INFORMATION (continued)
: 6. Continuous Releases  
: 6. Continuous Releases
: a. Liquid:  Non-Canal  Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases: 1.20E+01 1.40E+01 1.40E+01 1.30E+01  
: a. Liquid:  Non-Canal  Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases: 1.20E+01 1.40E+01 1.40E+01 1.30E+01  


  (2) Total Activity Released (Ci) 4.57E-03 6.76E-03 8.37E-03 8.59E-03  
(2) Total Activity Released (Ci) 4.57E-03 6.76E-03 8.37E-03 8.59E-03  


  (3) Total Volume Released (liters) 3.16E+06 4.61E+06 4.31E+06 5.92E+06  
(3) Total Volume Released (liters) 3.16E+06 4.61E+06 4.31E+06 5.92E+06
: b. Liquid:  Canal    Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases:        0        0                  0        0  
: b. Liquid:  Canal    Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases:        0        0                  0        0  


  (2) Total Activity Released (Ci)      N/A      N/A                N/A      N/A  
(2) Total Activity Released (Ci)      N/A      N/A                N/A      N/A  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 6 TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES      EST TOTAL    UNIT QTR 1 QTR 2 QTR 3 QTR 4  ERROR %   
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 6 TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES      EST TOTAL    UNIT QTR 1 QTR 2 QTR 3 QTR 4  ERROR %   
Line 158: Line 158:
52E+00 3.77E+00  2.50E+01  2. Average release rate for period Ci/sec 4.22E-01 4.70E-01 5.69E-01 4.74E-01  3. Percentage ODCM Limit % * * *
52E+00 3.77E+00  2.50E+01  2. Average release rate for period Ci/sec 4.22E-01 4.70E-01 5.69E-01 4.74E-01  3. Percentage ODCM Limit % * * *
* E. CARBON-14 (See attachment 8)  
* E. CARBON-14 (See attachment 8)  
  *F. PERCENT OF APPLICABLE ODCM LIMITS FISSION AND ACTIVATION GASES UNIT QTR 1 QTR 2 QTR 3 QTR 4  1. Quarterly gamma air dose limit % 5.32E-03 1.29E-02 6.03E-03 3.21E-03  2. Quarterly beta air dose limit % 2.69E-04 5.86E-04 3.00E-04 1.71E-04  
  *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 % 5.32E-03 1.29E-02 6.03E-03 3.21E-03  2. Quarterly beta air dose limit % 2.69E-04 5.86E-04 3.00E-04 1.71E-04
: 3. Yearly gamma air dose limit % 2.66E-03 6.46E-03 3.02E-03 1.61E-03  
: 3. Yearly gamma air dose limit % 2.66E-03 6.46E-03 3.02E-03 1.61E-03
: 4. Yearly beta air dose limit % 1.34E-04 2.93E-04 1.50E-04 8.56E-05  
: 4. Yearly beta air dose limit % 1.34E-04 2.93E-04 1.50E-04 8.56E-05
: 5. Whole body dose rate limit % 4.32E-03 2.70E-03 2.86E-03 1.22E-03  
: 5. Whole body dose rate limit % 4.32E-03 2.70E-03 2.86E-03 1.22E-03
: 6. Skin dose rate limit % 1.37E-03 7.86E-04 8.65E-04 4.23E-04 HALOGENS, TRITIUM AND PARTICULA TES WITH HALF-LIVES >8 DAYS  7. Quarterly dose limit (organ) % 1.18E-02 8.23E-03 2.96E-02 3.49E-02  8. Yearly dose limit (organ) % 5.89E-03 4.11E-03 1.48E-02 1.75E-02  
: 6. Skin dose rate limit % 1.37E-03 7.86E-04 8.65E-04 4.23E-04 HALOGENS, TRITIUM AND PARTICULA TES WITH HALF-LIVES >8 DAYS  7. Quarterly dose limit (organ) % 1.18E-02 8.23E-03 2.96E-02 3.49E-02  8. Yearly dose limit (organ) % 5.89E-03 4.11E-03 1.48E-02 1.75E-02
: 9. Organ dose rate limit % 2.04E-05 1.15E-05 3.03E-05 2.11E-05 ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 7 TABLE 1B GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODE NUCLIDES RELEASED  
: 9. Organ dose rate limit % 2.04E-05 1.15E-05 3.03E-05 2.11E-05 ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 7 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  6.65E+00 1.15E+01 5.61E+00 3.29E+00 Krypton-85 Ci                    ND                        ND                        ND                        ND Krypton-85m Ci 1.40E+00 3.16E+00 1.40E+00 8.11E-01 Krypton-87 Ci                    ND                        ND                        ND                        ND Krypton-88 Ci 5.98E-01 4.02E+00 1.24E+00 2.98E-01 Xenon-133 Ci 3.49E-01 3.32E+00 1.25E+00 7.67E-01 Xenon-133m Ci                    ND                        ND                        ND                        ND Xenon-135 Ci                    ND                        ND                    2.19E-02                  ND Xenon-135m Ci                    ND                        ND                    1.82E-01              1.89E-01 Xenon-137 Ci                    ND  ND                        ND                        ND Xenon-138 Ci                    ND                  4.31E-01                9.38E-01              7.69E-01  
: 1. Fission Gases UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Argon-41 Ci  6.65E+00 1.15E+01 5.61E+00 3.29E+00 Krypton-85 Ci                    ND                        ND                        ND                        ND Krypton-85m Ci 1.40E+00 3.16E+00 1.40E+00 8.11E-01 Krypton-87 Ci                    ND                        ND                        ND                        ND Krypton-88 Ci 5.98E-01 4.02E+00 1.24E+00 2.98E-01 Xenon-133 Ci 3.49E-01 3.32E+00 1.25E+00 7.67E-01 Xenon-133m Ci                    ND                        ND                        ND                        ND Xenon-135 Ci                    ND                        ND                    2.19E-02                  ND Xenon-135m Ci                    ND                        ND                    1.82E-01              1.89E-01 Xenon-137 Ci                    ND  ND                        ND                        ND Xenon-138 Ci                    ND                  4.31E-01                9.38E-01              7.69E-01  


Line 172: Line 172:
TOTAL Ci 3.80E-07                1.15E-06 2.61E-06 3.47E-06
TOTAL Ci 3.80E-07                1.15E-06 2.61E-06 3.47E-06
: 4. Tritium Hydrogen-3 Ci 2.39E-01 2.25E-01 4.06E-01 3.41E-01 Note:  There were no batch releases for this report period.
: 4. Tritium Hydrogen-3 Ci 2.39E-01 2.25E-01 4.06E-01 3.41E-01 Note:  There were no batch releases for this report period.
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 8 TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED  
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 8 TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED
: 1. Fission Gases UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Argon-41  Ci                    ND                        ND                        ND                        ND Krypton-85 Ci                    ND                        ND                        ND                        ND Krypton-85m  Ci                    ND                        ND                        ND                        ND Krypton-87 Ci                    ND                        ND                        ND                        ND Krypton-88  Ci                    ND                        ND                        ND                        ND Xenon-133  Ci                2.04E-02    8.66E-03              9.72E-03                  9.63E-03 Xenon-133m Ci                    ND                        ND                        ND                        ND Xenon-135  Ci                4.44E-02              3.71E-02              2.73E-02                  1.02E-02 Xenon-135m  Ci                1.17E-02              1.51E-02              1.68E-02                  2.21E-03 Xenon-137 Ci                    ND  ND                        ND                        ND Xenon-138  Ci                    ND                        ND                        ND                        ND  
: 1. Fission Gases UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Argon-41  Ci                    ND                        ND                        ND                        ND Krypton-85 Ci                    ND                        ND                        ND                        ND Krypton-85m  Ci                    ND                        ND                        ND                        ND Krypton-87 Ci                    ND                        ND                        ND                        ND Krypton-88  Ci                    ND                        ND                        ND                        ND Xenon-133  Ci                2.04E-02    8.66E-03              9.72E-03                  9.63E-03 Xenon-133m Ci                    ND                        ND                        ND                        ND Xenon-135  Ci                4.44E-02              3.71E-02              2.73E-02                  1.02E-02 Xenon-135m  Ci                1.17E-02              1.51E-02              1.68E-02                  2.21E-03 Xenon-137 Ci                    ND  ND                        ND                        ND Xenon-138  Ci                    ND                        ND                        ND                        ND  


TOTAL                                            Ci                  7.65E-02                6.09E-02              5.39E-02 2.21E-02  
TOTAL                                            Ci                  7.65E-02                6.09E-02              5.39E-02 2.21E-02
: 2. Iodines Iodine-131 Ci 5.11E-05 3.09E-05 1.34E-04 1.64E-04 Iodine-132                                        Ci                        ND                      ND                      1.1 9E-04                    ND Iodine-133 Ci 4.48E-04 3.13E-04 1.03E-03 1.23E-03 Iodine-135                                        Ci                        ND                    ND                      3.8 9E-04                    ND  
: 2. Iodines Iodine-131 Ci 5.11E-05 3.09E-05 1.34E-04 1.64E-04 Iodine-132                                        Ci                        ND                      ND                      1.1 9E-04                    ND Iodine-133 Ci 4.48E-04 3.13E-04 1.03E-03 1.23E-03 Iodine-135                                        Ci                        ND                    ND                      3.8 9E-04                    ND  


TOTAL Ci 4.99E-04 3.44E-04                1.67E-03    1.39E-03  
TOTAL Ci 4.99E-04 3.44E-04                1.67E-03    1.39E-03
: 3. Particulates Silver-110M Ci                        ND                      ND                          ND  ND Cobalt-58 Ci                        ND                      ND                          ND                    ND Cobalt-60 Ci                        ND                      ND            1.59E-06                1.90E-06 Manganese-54 Ci                        ND                      ND                2.02E-06          ND Selenium-75 Ci                        ND                      ND                          ND                        ND Strontium-89 Ci                    4.38E-05  ND                          ND                        ND Zinc-65 Ci                    2.13E-06                  ND                      1.72E-06                    ND  
: 3. Particulates Silver-110M Ci                        ND                      ND                          ND  ND Cobalt-58 Ci                        ND                      ND                          ND                    ND Cobalt-60 Ci                        ND                      ND            1.59E-06                1.90E-06 Manganese-54 Ci                        ND                      ND                2.02E-06          ND Selenium-75 Ci                        ND                      ND                          ND                        ND Strontium-89 Ci                    4.38E-05  ND                          ND                        ND Zinc-65 Ci                    2.13E-06                  ND                      1.72E-06                    ND  


TOTAL Ci                    4.60E-05                  ND                      5.33E-06                1.90E-06  
TOTAL Ci                    4.60E-05                  ND                      5.33E-06                1.90E-06
: 4. Tritium Hydrogen-3 Ci 3.04E+00 3.47E+00    4.11E+
: 4. Tritium Hydrogen-3 Ci 3.04E+00 3.47E+00    4.11E+
00                3.43E+00 Note:  There were no batch releases for this report period.
00                3.43E+00 Note:  There were no batch releases for this report period.


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 9  TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES EST TOTAL    UNIT QTR 1 QTR 2 QTR 3 QTR 4    ERROR %
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 9  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 ND                ND                    ND                ND              NA  
A. FISSION AND ACTIVATION PRODUCTS  1. Total Release (not including                  tritium, gases and alpha) Ci ND                ND                    ND                ND              NA
: 2. Average diluted concentration  during period Ci/ml ND    ND        ND                ND          3. Percentage ODCM Limit                            %                      NA                NA NA                NA  
: 2. Average diluted concentration  during period Ci/ml ND    ND        ND                ND          3. Percentage ODCM Limit                            %                      NA                NA NA                NA  


B. TRITIUM  1. Total Release Ci 1.06E-02  8.33E-03 9.06E-03 8.84E-03 2.50E+01  2. Average diluted concentration  during period (Note 1) Ci/ml 3.20E-06  1.53E-06          2.01E-06 1.45E-06  3. Percentage ODCM Limit  % * * *
B. TRITIUM  1. Total Release Ci 1.06E-02  8.33E-03 9.06E-03 8.84E-03 2.50E+01  2. Average diluted concentration  during period (Note 1) Ci/ml 3.20E-06  1.53E-06          2.01E-06 1.45E-06  3. Percentage ODCM Limit  % * * *
* C. DISSOLVED AND ENTRAINED GASES  1. Total Release Ci ND    ND    ND                ND                NA
* C. DISSOLVED AND ENTRAINED GASES  1. Total Release Ci ND    ND    ND                ND                NA
: 2. Average diluted concentration  during period Ci/ml ND    ND        ND                ND
: 2. Average diluted concentration  during period Ci/ml ND    ND        ND                ND
: 3. Percentage ODCM Limit %    NA                NA                  NA                NA  
: 3. Percentage ODCM Limit %    NA                NA                  NA                NA  


D. GROSS ALPHA RADIOACTIVITY  1. Total Release Ci ND    ND    ND          2.39E-07        4.20E+01  E. VOLUME OF WASTE RELEASED  (PRIOR TO DILUTION) liters 3.26E+06  4.89E+06          4.43E+06  5.97E+06 F. VOLUME OF DILUTION WATER  USED DURING PERIOD liters 7.07E+07  3.79E+08 3.04E+08 2.87E+08 G. PERCENT OF APPLICABLE ODCM LIMITS  1. Quarterly Whole Body Dose %  9.11E-04  3.48E-04          5.69E-04 3.25E-04  2. Quarterly Organ Dose %  2.73E-04  1.04E-04 1.71E-04 9.74E-05  
D. GROSS ALPHA RADIOACTIVITY  1. Total Release Ci ND    ND    ND          2.39E-07        4.20E+01  E. VOLUME OF WASTE RELEASED  (PRIOR TO DILUTION) liters 3.26E+06  4.89E+06          4.43E+06  5.97E+06 F. VOLUME OF DILUTION WATER  USED DURING PERIOD liters 7.07E+07  3.79E+08 3.04E+08 2.87E+08 G. PERCENT OF APPLICABLE ODCM LIMITS  1. Quarterly Whole Body Dose %  9.11E-04  3.48E-04          5.69E-04 3.25E-04  2. Quarterly Organ Dose %  2.73E-04  1.04E-04 1.71E-04 9.74E-05
: 3. Annual Whole Body Dose %  4.55E-04  1.74E-04          2.85E-04  1.62E-04  
: 3. Annual Whole Body Dose %  4.55E-04  1.74E-04          2.85E-04  1.62E-04
: 4. Annual Organ Dose %  1.37E-04  5.22E-05 8.54E-05 4.87E-05  
: 4. Annual Organ Dose %  1.37E-04  5.22E-05 8.54E-05 4.87E-05  


Note 1:  Concentration includes summation from diluted and undiluted values from Canal and Non-Canal releases (Table 2B).  
Note 1:  Concentration includes summation from diluted and undiluted values from Canal and Non-Canal releases (Table 2B).  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 10  TABLE 2B LIQUID EFFLUENTS CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4  
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 10  TABLE 2B LIQUID EFFLUENTS CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4
: 1. Fission and Activation Products  
: 1. Fission and Activation Products  


ND Ci                      ND                        ND                        ND                      ND  
ND Ci                      ND                        ND                        ND                      ND
: 2. Tritium Hydrogen-3 Ci                        1.31E-04 8.27E-04 1.85E-04 2.07E-04
: 2. Tritium Hydrogen-3 Ci                        1.31E-04 8.27E-04 1.85E-04 2.07E-04
: 3. Dissolved and Entrained Gases  
: 3. Dissolved and Entrained Gases  
Line 209: Line 209:
ND Ci                        ND                        ND                        ND                        ND  
ND Ci                        ND                        ND                        ND                        ND  


TABLE 2B LIQUID EFFLUENTS CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4  
TABLE 2B LIQUID EFFLUENTS CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4
: 1. Fission and Activation Products  
: 1. Fission and Activation Products  


ND Ci                    ND                        ND                        ND                      ND  
ND Ci                    ND                        ND                        ND                      ND
: 2. Tritium Hydrogen-3 Ci    ND                          ND                        ND                      ND  
: 2. Tritium Hydrogen-3 Ci    ND                          ND                        ND                      ND
: 3. Dissolved and Entrained Gases  
: 3. Dissolved and Entrained Gases  


Line 219: Line 219:


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 11  TABLE 2B (SUPPLEMENT)
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 11  TABLE 2B (SUPPLEMENT)
LIQUID EFFLUENTS NON-CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4  
LIQUID EFFLUENTS NON-CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4
: 1. Fission and Activation Products  
: 1. Fission and Activation Products  


ND Ci                        ND                        ND                        ND                        ND  
ND Ci                        ND                        ND                        ND                        ND
: 2. Tritium Hydrogen-3 Ci 4.57E-03 6.76E-03 8.37E-03 8.59E-03  
: 2. Tritium Hydrogen-3 Ci 4.57E-03 6.76E-03 8.37E-03 8.59E-03
: 3. Dissolved and Entrained Gases ND Ci                        ND                        ND                        ND                        ND  
: 3. Dissolved and Entrained Gases ND Ci                        ND                        ND                        ND                        ND  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 12  TABLE 2B (SUPPLEMENT)
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 12  TABLE 2B (SUPPLEMENT)
LIQUID EFFLUENTS NON-CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4  
LIQUID EFFLUENTS NON-CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4
: 1. Fission and Activation Products  
: 1. Fission and Activation Products  


ND Ci                        ND                        ND                        ND                      ND  
ND Ci                        ND                        ND                        ND                      ND
: 2. Tritium Hydrogen-3 Ci 5.89E-03 7.48E-04 5.09E-04 4.69E-05  
: 2. Tritium Hydrogen-3 Ci 5.89E-03 7.48E-04 5.09E-04 4.69E-05
: 3. Dissolved and Entrained Gases ND Ci                        ND                        ND                        ND                      ND  
: 3. Dissolved and Entrained Gases ND Ci                        ND                        ND                        ND                      ND  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 13  TABLE 2B (continued)
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 13  TABLE 2B (continued)
ABNORMAL RELEASE LIQUID EFFLUENTS CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4  
ABNORMAL RELEASE LIQUID EFFLUENTS CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4
: 1. Fission and Activation Products ND Ci                        ND                        ND                        ND                        ND  
: 1. Fission and Activation Products ND Ci                        ND                        ND                        ND                        ND
: 2. Tritium ND Ci                        ND                        ND                        ND                        ND  
: 2. Tritium ND Ci                        ND                        ND                        ND                        ND
: 3. Dissolved and Entrained Gases ND Ci                        ND                        ND                        ND                        ND  
: 3. Dissolved and Entrained Gases ND Ci                        ND                        ND                        ND                        ND  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 14 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 %
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 14 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 6.51E+01 0.00E+00 0.00E+00      evaporator bottoms, etc. Ci 6.05E+01 0.00E+00 0.00E+00 1.00E+01      
: a. Spent resins, filter sludges, m 3 6.51E+01 0.00E+00 0.00E+00      evaporator bottoms, etc. Ci 6.05E+01 0.00E+00 0.00E+00 1.00E+01
: b. Dry compressible waste, m 3 3.62E+02 0.00E+00 0.00E+00      contaminated equipment, etc. Ci 1.16E+00 0.00E+
: b. Dry compressible waste, m 3 3.62E+02 0.00E+00 0.00E+00      contaminated equipment, etc. Ci 1.16E+00 0.00E+
00 0.00E+00 1.00E+01      
00 0.00E+00 1.00E+01
: c. Irradiated components, m 3 4.96E+00 0.00E+00 3.58E-01      control rods, etc. Ci 2.28E-01 0.00E+00 2.86E+04 1.00E+01      
: c. Irradiated components, m 3 4.96E+00 0.00E+00 3.58E-01      control rods, etc. Ci 2.28E-01 0.00E+00 2.86E+04 1.00E+01
: d. Other: Dry compressible m 3 7.14E+00  0.00E+00 0.00E+00      waste, contaminated equipment, Ci 3.25E-02 0.00E+
: d. Other: Dry compressible m 3 7.14E+00  0.00E+00 0.00E+00      waste, contaminated equipment, Ci 3.25E-02 0.00E+
00 0.00E+00 1.00E+01    spent resins for volume reduction.  
00 0.00E+00 1.00E+01    spent resins for volume reduction.
: 2. Estimate of Major Nuclide Composition (by type of waste)  
: 2. Estimate of Major Nuclide Composition (by type of waste)
: a. Spent resins, filter sludges, evaporator bottoms, etc.
: a. Spent resins, filter sludges, evaporator bottoms, etc.
Isotope Percent Curies  Isotope Percent Curies Ce-144 9.00E-02 5.16E-02  E Co-58 7.00E-02 4.33E-02    E Co-60 3.67E+01 2.23E+01  E Fe-59 1.00E-02 3.89E-03    E Cs-137 5.20E-01 3.16E-01  E Fe-55 1.41E+01 8.53E+00  E C-14 2.10E-01 1.28E-01  E Mn-54 2.02E+01 1.22E+01  E Ni-63 7.10E-01 4.28E-01  E Tc-99 4.00E-02 2.18E-02    E Zn-65 2.71E+01 1.64E+01  E H-3 2.00E-01 1.19E-01    E Sb-125 1.50E-01 9.23E-02  E   
Isotope Percent Curies  Isotope Percent Curies Ce-144 9.00E-02 5.16E-02  E Co-58 7.00E-02 4.33E-02    E Co-60 3.67E+01 2.23E+01  E Fe-59 1.00E-02 3.89E-03    E Cs-137 5.20E-01 3.16E-01  E Fe-55 1.41E+01 8.53E+00  E C-14 2.10E-01 1.28E-01  E Mn-54 2.02E+01 1.22E+01  E Ni-63 7.10E-01 4.28E-01  E Tc-99 4.00E-02 2.18E-02    E Zn-65 2.71E+01 1.64E+01  E H-3 2.00E-01 1.19E-01    E Sb-125 1.50E-01 9.23E-02  E   


(E- Estimated M- Measured)  
(E- Estimated M- Measured)
: b. Dry compressible waste, contaminated equipment, etc.
: b. Dry compressible waste, contaminated equipment, etc.
Isotope Percent Curies  Isotope Percent Curies  
Isotope Percent Curies  Isotope Percent Curies  
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Ce-144 1.00E-02 2.88E-04  E Co-58 2.00E-02 1.18E-03    E Co-60 2.62E+00 1.45E-01  E Fe-59 6.00E-02 3.21E-03    E Cs-137 3.10E-01 1.71E-02  E Fe-55 1.36E+01 7.52E-01    E C-14 2.76E+01 1.53E+00  E Mn-54 1.15E+00 6.34E-02    E Ni-63 6.10E-01 3.37E-02  E I-129 7.90E-01 4.37E-02    E Zn-65 2.03E+00 1.12E-01  E H-3 4.11E+01 2.27E+00  E Sb-124 1.00E-02 7.92E-04  E Tc-99 1.01E+01 5.59E-01    E Sb-125 1.00E-02 5.53E-04  E Cr-51 5.00E-02 3.04E-03    E  
Ce-144 1.00E-02 2.88E-04  E Co-58 2.00E-02 1.18E-03    E Co-60 2.62E+00 1.45E-01  E Fe-59 6.00E-02 3.21E-03    E Cs-137 3.10E-01 1.71E-02  E Fe-55 1.36E+01 7.52E-01    E C-14 2.76E+01 1.53E+00  E Mn-54 1.15E+00 6.34E-02    E Ni-63 6.10E-01 3.37E-02  E I-129 7.90E-01 4.37E-02    E Zn-65 2.03E+00 1.12E-01  E H-3 4.11E+01 2.27E+00  E Sb-124 1.00E-02 7.92E-04  E Tc-99 1.01E+01 5.59E-01    E Sb-125 1.00E-02 5.53E-04  E Cr-51 5.00E-02 3.04E-03    E  


(E- Estimated M- Measured)  
(E- Estimated M- Measured)  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 15  TABLE 3A (continued)
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 15  TABLE 3A (continued)
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Isotope Percent Curies  Isotope Percent Curies C-14 1.00E-02 1.76E+00  E Co-58 5.00E-02 1.43E+01    E Co-60 6.01E+01 1.72E+04  E Zn-65 2.00E-02 5.74E+00    E Ni-59 7.00E-02 1.96E+01  E Fe-55 3.47E+01 9.92E+03    E  Ni-63 4.19E+00 1.20E+03  E Mn-54 8.60E-01 2.46E+02    E  
Isotope Percent Curies  Isotope Percent Curies C-14 1.00E-02 1.76E+00  E Co-58 5.00E-02 1.43E+01    E Co-60 6.01E+01 1.72E+04  E Zn-65 2.00E-02 5.74E+00    E Ni-59 7.00E-02 1.96E+01  E Fe-55 3.47E+01 9.92E+03    E  Ni-63 4.19E+00 1.20E+03  E Mn-54 8.60E-01 2.46E+02    E  


    (E- Estimated  M- Measured)  
(E- Estimated  M- Measured)
: d. Other:  Dry compressible waste, contaminated equipment, spent resins contaminated oil, glycol and water for volume reduction.  
: d. Other:  Dry compressible waste, contaminated equipment, spent resins contaminated oil, glycol and water for volume reduction.  


Isotope Percent Curies  Isotope Percent Curies H-3 9.98E+01 3.25E-02  E Cs-137 4.00E-02 1.25E-05    E Fe-55 1.00E-01 3.33E-05  E Co-60 1.00E-02 2.77E-06    E  
Isotope Percent Curies  Isotope Percent Curies H-3 9.98E+01 3.25E-02  E Cs-137 4.00E-02 1.25E-05    E Fe-55 1.00E-01 3.33E-05  E Co-60 1.00E-02 2.77E-06    E  


(E- Estimated M- Measured)  
(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.
Percentage of nuclides and total activities are based on a combination of direct measurements and scaling for non-gamma emitting nuclides.
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Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Part 2, Section 4.4.1  
Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Part 2, 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".   
(1)Curies released calculated using the methodology in EPRI Technical Report 1021106    "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents".   


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 29 ATTACHMENT NO. 9 EVENTS LEADING TO CONDITIONS WHICH RESULTED IN EXCEEDING RADIOACTIVITY LIMITS.
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 29 ATTACHMENT NO. 9 EVENTS LEADING TO CONDITIONS WHICH RESULTED IN EXCEEDING RADIOACTIVITY LIMITS.
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ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2015
ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2015
: 1. INTRODUCTION The James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Effluent Controls (REC), requires an assessment of the radiation doses to the likely most exposed member of the public due to radioactive liquid and gaseous effluents. This assessment of doses to the likely most exposed member of the public is based on accepted methodologies found in the Offsite Dose Calculation Manual (ODCM).  
: 1. INTRODUCTION The James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Effluent Controls (REC), requires an assessment of the radiation doses to the likely most exposed member of the public due to radioactive liquid and gaseous effluents. This assessment of doses to the likely most exposed member of 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)  
: 2. DOSE LIMITS A. DOSE FROM LIQUID EFFLUENTS (ODCM, Part 1, REC 2.3)  


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To ensure that the dose limitations of 10 CFR 50, Appendix I, are met.  
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:  
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.  
: 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.
: 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)  
B. GASEOUS DOSE RATES (ODCM, Part 1, REC 3.2)  
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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.
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.
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 31  ADDENDUM 1 (continued)
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 31  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:  
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,
: 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).
: 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)  
C. AIR DOSE, NOBLE GASES (ODCM, Part 1, REC 3.3)  
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Objective To ensure that the noble gas dose limitations of 10 CFR 50, Appendix I, are met.  
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:  
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,
: 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.  
: 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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To ensure that the dose limitations of 10 CFR 50, Appendix I, are met.
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:  
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:
: a. During any calendar quarter to less than or equal to 7.5 mrem to any organ; and,  
: 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.  
: 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 Specifications 3.4.1.c.1.a and 3.4.1.c.1.b as a result of burning contaminated oil.
: c. Less than 0.1% of the limits of Specifications 3.4.1.c.1.a and 3.4.1.c.1.b as a result of burning contaminated oil.
E. TOTAL DOSE FROM URANIUM FUEL CYCLE (ODCM, Part 1, REC 4.0)  
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  
Applicability Applies to radiation dose from releases of radioactivity and radiation from uranium fuel cycle sources. Objective
: 1. To assure that the requirements of 40 CFR 190 are met.  
: 1. To assure that the requirements of 40 CFR 190 are met.
: 2. To assure that the requirements of 10 CFR 72.104 are met in accordance with Section 3.2.3, Required Action A.2, Certificate of Compliance 1014 Appendix A, Technical Specifications for the Hi-Storm 100 Cask System.
: 2. To assure that the requirements of 10 CFR 72.104 are met in accordance with Section 3.2.3, Required Action A.2, Certificate of Compliance 1014 Appendix A, Technical Specifications for the Hi-Storm 100 Cask System.
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:  
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,  
: 1. Less than or equal to 25 mrem/year to the whole body; and,
: 2. Less than or equal to 25 mrem/year to a ny organ except the thyroid which shall be limited to less than or equal to 75 mrem/year.
: 2. Less than or equal to 25 mrem/year to a ny organ except the thyroid which shall be limited to less than or equal to 75 mrem/year.
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 33 ADDENDUM 1 (continued)
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 33 ADDENDUM 1 (continued)
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==SUMMARY==
==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.  
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.
: 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  
B. RESULTS  
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TABLE 1 ANNUAL DOSE ASSESSMENT 2015 A. LIQUIDS QUARTER 1 2 3 4 ANNUAL  
TABLE 1 ANNUAL DOSE ASSESSMENT 2015 A. LIQUIDS QUARTER 1 2 3 4 ANNUAL  


(a) (a) (a) (a) (a)  
(a) (a) (a) (a) (a)  


Organ (mrem)      1.37E-05 5.22E-06 8.54E-06 4.87E-06 3.23E-05 % of Limit 2.73E-04 1.04E-04 1.71E-04 9.74E-05 3.23E-04  
Organ (mrem)      1.37E-05 5.22E-06 8.54E-06 4.87E-06 3.23E-05 % of Limit 2.73E-04 1.04E-04 1.71E-04 9.74E-05 3.23E-04  


(b) (b) (b) (b) (b)  
(b) (b) (b) (b) (b)  


Whole Body (mrem) 1.37E-05 5.22E-06 8.54E-06 4.87E-06 3.23E-05 % of Limit 9.11E-04 3.48E-04 5.69E-04 3.25E-04 1.08E-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.  
Whole Body (mrem) 1.37E-05 5.22E-06 8.54E-06 4.87E-06 3.23E-05 % of Limit 9.11E-04 3.48E-04 5.69E-04 3.25E-04 1.08E-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.  
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Beta (mrad) 2.69E-05 5.86E-05 3.00E-05 1.71E-05 1.33E-04 % of Limit 2.69E-04 5.86E-04 3.00E-04 1.71E-04 6.63E-04 C. IODINES AND PARTICULATES QUARTER  1  2  3  4        ANNUAL  
Beta (mrad) 2.69E-05 5.86E-05 3.00E-05 1.71E-05 1.33E-04 % of Limit 2.69E-04 5.86E-04 3.00E-04 1.71E-04 6.63E-04 C. IODINES AND PARTICULATES QUARTER  1  2  3  4        ANNUAL  


(a) (a) (a) (a) (a)  
(a) (a) (a) (a) (a)  


Organ (mrem) 8.84E-04 6.17E-04 2.22E-03 2.67E-03 6.39E-03 % of Limit 1.18E-02 8.23E-03 2.96E-02 3.56E-02 4.26E-02  
Organ (mrem) 8.84E-04 6.17E-04 2.22E-03 2.67E-03 6.39E-03 % of Limit 1.18E-02 8.23E-03 2.96E-02 3.56E-02 4.26E-02  


(a) (a) (a) (a) (a)  
(a) (a) (a) (a) (a)  


Organ Dose Rate 3.07E-04 1.73E-04 4.55E-04 3.17E-04 4.55E-04 (mrem/yr)  
Organ Dose Rate 3.07E-04 1.73E-04 4.55E-04 3.17E-04 4.55E-04 (mrem/yr)  
% of Limit 2.04E-05 1.15E-05 3.03E-05 2.11E-05 3.03E-05  
% of Limit 2.04E-05 1.15E-05 3.03E-05 2.11E-05 3.03E-05  


    (a)  Dose to the Child Thyroid primarily by the vegetation pathway.
(a)  Dose to the Child Thyroid primarily by the vegetation pathway.
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 36 ADDENDUM 1 (continued)
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 36 ADDENDUM 1 (continued)
TABLE 1 (cont)
TABLE 1 (cont)
ANNUAL DOSE ASSESSMENT 2015 D. CARBON 14 QUARTER  1  2    3  4      ANNUAL  
ANNUAL DOSE ASSESSMENT 2015 D. CARBON 14 QUARTER  1  2    3  4      ANNUAL  


(a) (a) (a) (a) (a)  
(a) (a) (a) (a) (a)  


Organ (mrem) 8.43E-03 8.52E-03 8.59E-03 8.62E-03 3.42E-02 % of Limit 1.12E-01 1.14E-01 1.14E-01 1.15E-01 2.28E-01  
Organ (mrem) 8.43E-03 8.52E-03 8.59E-03 8.62E-03 3.42E-02 % of Limit 1.12E-01 1.14E-01 1.14E-01 1.15E-01 2.28E-01  


    (a)  
(a)  


Organ Dose Rate NA    NA    NA  NA 3.42E-02  (mrem/yr)  
Organ Dose Rate NA    NA    NA  NA 3.42E-02  (mrem/yr)  
% of Limit    NA    NA    NA                  NA 2.28E-03  
% of Limit    NA    NA    NA                  NA 2.28E-03  


    (a)  Dose to the Child Bone primarily by the vegetation pathway.
(a)  Dose to the Child Bone primarily by the vegetation pathway.
* JAFP-16-0070 April 28, 2016 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001  
* JAFP-16-0070 April 28, 2016 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001  


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ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 1 SUPPLEMENTAL INFORMATION  
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 1 SUPPLEMENTAL INFORMATION  


FACILITY:  JAFNPP  LICENSEE:  ENTERGY NUCLEAR OPERATIONS, INC.  
FACILITY:  JAFNPP  LICENSEE:  ENTERGY NUCLEAR OPERATIONS, INC.
: 1. Offsite Dose Calculation Manual Part 1 Radiological Effluent Controls  a. Fission and Activation Gases:  
: 1. Offsite Dose Calculation Manual Part 1 Radiological Effluent 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:  
(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.  
(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:  
(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.  
(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:  
: 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:  
(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,  
(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.  
(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.  
(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:  
(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).
(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).
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 2 SUPPLEMENTAL INFORMATION (continued)  
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 2 SUPPLEMENTAL INFORMATION (continued)
: c. Liquid Effluents:  
: 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.
(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:  
(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.  
(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  
: 2. 10X Effluent Concentrations
: a. Fission and activation gases: (None specified)  
: a. Fission and activation gases: (None specified)
: b. Iodines:    (None specified)  
: b. Iodines:    (None specified)
: c. Particulates, half-lives >8 days: (None specified)  
: c. Particulates, half-lives >8 days: (None specified)
: d. Liquid effluents:  Quarter 1 Quarter 2 Quarter 3 Quarter 4  
: d. Liquid effluents:  Quarter 1 Quarter 2 Quarter 3 Quarter 4  


  (1) Fission and activation  None    None    None    None products (mixture EC)  
(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  
(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  
(3) Dissolved and entrained gases (Ci/ml)  2.00E-04 2.00E-04 2.00E-04 2.00E-04  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 3 SUPPLEMENTAL INFORMATION (continued)  
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 3 SUPPLEMENTAL INFORMATION (continued)
: 3. Average Energy  (None specified)  
: 3. Average Energy  (None specified)
: 4. Measurements and Approximations of Total Radioactivity  
: 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.  
: 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.  
: 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.  
: 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.  
: 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  
: 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.  
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.
: 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  
Determinate  - Pump flowrates, volume measurements and analysis collection yields  Undeterminate - Random counting error estimated using accepted statistical calculations  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 4 SUPPLEMENTAL INFORMATION (continued)  
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 4 SUPPLEMENTAL INFORMATION (continued)
: 5. Batch Releases  
: 5. Batch Releases
: a. Liquid:  Canal  Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 4.00E+00 9.00E+00 5.00E+00 8.00E+00  
: a. Liquid:  Canal  Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 4.00E+00 9.00E+00 5.00E+00 8.00E+00  


  (2) Total time period for batch 4.80E+01 2.45E+02 1.88E+02 1.78E+02 release: (min)  
(2) Total time period for batch 4.80E+01 2.45E+02 1.88E+02 1.78E+02 release: (min)  


  (3) Maximum time period for 3.40E+01 7.20E+01 9.00E+01 5.80E+01 batch release: (min)  
(3) Maximum time period for 3.40E+01 7.20E+01 9.00E+01 5.80E+01 batch release: (min)  


  (4) Average time period for 1.20E+01 2.72E+01 3.76E+01 2.22E+01 batch release: (min)  
(4) Average time period for 1.20E+01 2.72E+01 3.76E+01 2.22E+01 batch release: (min)  


  (5) Minimum time period for 1.00E+00 3.00E+00 2.00E+00 2.00E+00 batch release: (min)  
(5) Minimum time period for 1.00E+00 3.00E+00 2.00E+00 2.00E+00 batch release: (min)  


  (6) Total Activity Released (Ci) 1.31E-04 8.27E-04 1.85E-04 2.07E-04  
(6) Total Activity Released (Ci) 1.31E-04 8.27E-04 1.85E-04 2.07E-04  


  (7) Total Volume Released (liters) 4.13E+03 5.85E+04 8.24E+03 2.75E+04  
(7) Total Volume Released (liters) 4.13E+03 5.85E+04 8.24E+03 2.75E+04
: b. Liquid:  Non-Canal  Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 6.00E+00 1.10E+01 1.60E+01 2.00E+01  
: b. Liquid:  Non-Canal  Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 6.00E+00 1.10E+01 1.60E+01 2.00E+01  


  (2) Total time period for batch 2.55E+02 6.73E+02 2.96E+02 6.10E+01 release: (min)  
(2) Total time period for batch 2.55E+02 6.73E+02 2.96E+02 6.10E+01 release: (min)  


  (3) Maximum time period for 2.47E+02 3.89E+02 3.70E+01 7.00E+00 batch release: (min)  
(3) Maximum time period for 2.47E+02 3.89E+02 3.70E+01 7.00E+00 batch release: (min)  


  (4) Average time period for 4.25E+01 6.12E+01 1.85E+01 3.15E+00 batch release: (min)  
(4) Average time period for 4.25E+01 6.12E+01 1.85E+01 3.15E+00 batch release: (min)  


  (5) Minimum time period for 1.00E+00 1.00E+00 1.00E+00 1.00E+00 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) 5.89E-03 7.48E-04 5.09E-04 4.69E-05  
(6) Total Activity Released (Ci) 5.89E-03 7.48E-04 5.09E-04 4.69E-05  


  (7) Total Volume Released (liters) 9.58E+04 2.28E+05 1.12E+05 2.34E+04  
(7) Total Volume Released (liters) 9.58E+04 2.28E+05 1.12E+05 2.34E+04
: c. Gaseous  
: c. Gaseous  


There were no gaseous batch releases for this report period.
There were no gaseous batch releases for this report period.
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 5 SUPPLEMENTAL INFORMATION (continued)  
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 5 SUPPLEMENTAL INFORMATION (continued)
: 6. Continuous Releases  
: 6. Continuous Releases
: a. Liquid:  Non-Canal  Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases: 1.20E+01 1.40E+01 1.40E+01 1.30E+01  
: a. Liquid:  Non-Canal  Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases: 1.20E+01 1.40E+01 1.40E+01 1.30E+01  


  (2) Total Activity Released (Ci) 4.57E-03 6.76E-03 8.37E-03 8.59E-03  
(2) Total Activity Released (Ci) 4.57E-03 6.76E-03 8.37E-03 8.59E-03  


  (3) Total Volume Released (liters) 3.16E+06 4.61E+06 4.31E+06 5.92E+06  
(3) Total Volume Released (liters) 3.16E+06 4.61E+06 4.31E+06 5.92E+06
: b. Liquid:  Canal    Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases:        0        0                  0        0  
: b. Liquid:  Canal    Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases:        0        0                  0        0  


  (2) Total Activity Released (Ci)      N/A      N/A                N/A      N/A  
(2) Total Activity Released (Ci)      N/A      N/A                N/A      N/A  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 6 TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES      EST TOTAL    UNIT QTR 1 QTR 2 QTR 3 QTR 4  ERROR %   
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 6 TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES      EST TOTAL    UNIT QTR 1 QTR 2 QTR 3 QTR 4  ERROR %   
Line 654: Line 654:
52E+00 3.77E+00  2.50E+01  2. Average release rate for period Ci/sec 4.22E-01 4.70E-01 5.69E-01 4.74E-01  3. Percentage ODCM Limit % * * *
52E+00 3.77E+00  2.50E+01  2. Average release rate for period Ci/sec 4.22E-01 4.70E-01 5.69E-01 4.74E-01  3. Percentage ODCM Limit % * * *
* E. CARBON-14 (See attachment 8)  
* E. CARBON-14 (See attachment 8)  
  *F. PERCENT OF APPLICABLE ODCM LIMITS FISSION AND ACTIVATION GASES UNIT QTR 1 QTR 2 QTR 3 QTR 4  1. Quarterly gamma air dose limit % 5.32E-03 1.29E-02 6.03E-03 3.21E-03  2. Quarterly beta air dose limit % 2.69E-04 5.86E-04 3.00E-04 1.71E-04  
  *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 % 5.32E-03 1.29E-02 6.03E-03 3.21E-03  2. Quarterly beta air dose limit % 2.69E-04 5.86E-04 3.00E-04 1.71E-04
: 3. Yearly gamma air dose limit % 2.66E-03 6.46E-03 3.02E-03 1.61E-03  
: 3. Yearly gamma air dose limit % 2.66E-03 6.46E-03 3.02E-03 1.61E-03
: 4. Yearly beta air dose limit % 1.34E-04 2.93E-04 1.50E-04 8.56E-05  
: 4. Yearly beta air dose limit % 1.34E-04 2.93E-04 1.50E-04 8.56E-05
: 5. Whole body dose rate limit % 4.32E-03 2.70E-03 2.86E-03 1.22E-03  
: 5. Whole body dose rate limit % 4.32E-03 2.70E-03 2.86E-03 1.22E-03
: 6. Skin dose rate limit % 1.37E-03 7.86E-04 8.65E-04 4.23E-04 HALOGENS, TRITIUM AND PARTICULA TES WITH HALF-LIVES >8 DAYS  7. Quarterly dose limit (organ) % 1.18E-02 8.23E-03 2.96E-02 3.49E-02  8. Yearly dose limit (organ) % 5.89E-03 4.11E-03 1.48E-02 1.75E-02  
: 6. Skin dose rate limit % 1.37E-03 7.86E-04 8.65E-04 4.23E-04 HALOGENS, TRITIUM AND PARTICULA TES WITH HALF-LIVES >8 DAYS  7. Quarterly dose limit (organ) % 1.18E-02 8.23E-03 2.96E-02 3.49E-02  8. Yearly dose limit (organ) % 5.89E-03 4.11E-03 1.48E-02 1.75E-02
: 9. Organ dose rate limit % 2.04E-05 1.15E-05 3.03E-05 2.11E-05 ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 7 TABLE 1B GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODE NUCLIDES RELEASED  
: 9. Organ dose rate limit % 2.04E-05 1.15E-05 3.03E-05 2.11E-05 ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 7 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  6.65E+00 1.15E+01 5.61E+00 3.29E+00 Krypton-85 Ci                    ND                        ND                        ND                        ND Krypton-85m Ci 1.40E+00 3.16E+00 1.40E+00 8.11E-01 Krypton-87 Ci                    ND                        ND                        ND                        ND Krypton-88 Ci 5.98E-01 4.02E+00 1.24E+00 2.98E-01 Xenon-133 Ci 3.49E-01 3.32E+00 1.25E+00 7.67E-01 Xenon-133m Ci                    ND                        ND                        ND                        ND Xenon-135 Ci                    ND                        ND                    2.19E-02                  ND Xenon-135m Ci                    ND                        ND                    1.82E-01              1.89E-01 Xenon-137 Ci                    ND  ND                        ND                        ND Xenon-138 Ci                    ND                  4.31E-01                9.38E-01              7.69E-01  
: 1. Fission Gases UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Argon-41 Ci  6.65E+00 1.15E+01 5.61E+00 3.29E+00 Krypton-85 Ci                    ND                        ND                        ND                        ND Krypton-85m Ci 1.40E+00 3.16E+00 1.40E+00 8.11E-01 Krypton-87 Ci                    ND                        ND                        ND                        ND Krypton-88 Ci 5.98E-01 4.02E+00 1.24E+00 2.98E-01 Xenon-133 Ci 3.49E-01 3.32E+00 1.25E+00 7.67E-01 Xenon-133m Ci                    ND                        ND                        ND                        ND Xenon-135 Ci                    ND                        ND                    2.19E-02                  ND Xenon-135m Ci                    ND                        ND                    1.82E-01              1.89E-01 Xenon-137 Ci                    ND  ND                        ND                        ND Xenon-138 Ci                    ND                  4.31E-01                9.38E-01              7.69E-01  


Line 668: Line 668:
TOTAL Ci 3.80E-07                1.15E-06 2.61E-06 3.47E-06
TOTAL Ci 3.80E-07                1.15E-06 2.61E-06 3.47E-06
: 4. Tritium Hydrogen-3 Ci 2.39E-01 2.25E-01 4.06E-01 3.41E-01 Note:  There were no batch releases for this report period.
: 4. Tritium Hydrogen-3 Ci 2.39E-01 2.25E-01 4.06E-01 3.41E-01 Note:  There were no batch releases for this report period.
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 8 TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED  
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 8 TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED
: 1. Fission Gases UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Argon-41  Ci                    ND                        ND                        ND                        ND Krypton-85 Ci                    ND                        ND                        ND                        ND Krypton-85m  Ci                    ND                        ND                        ND                        ND Krypton-87 Ci                    ND                        ND                        ND                        ND Krypton-88  Ci                    ND                        ND                        ND                        ND Xenon-133  Ci                2.04E-02    8.66E-03              9.72E-03                  9.63E-03 Xenon-133m Ci                    ND                        ND                        ND                        ND Xenon-135  Ci                4.44E-02              3.71E-02              2.73E-02                  1.02E-02 Xenon-135m  Ci                1.17E-02              1.51E-02              1.68E-02                  2.21E-03 Xenon-137 Ci                    ND  ND                        ND                        ND Xenon-138  Ci                    ND                        ND                        ND                        ND  
: 1. Fission Gases UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Argon-41  Ci                    ND                        ND                        ND                        ND Krypton-85 Ci                    ND                        ND                        ND                        ND Krypton-85m  Ci                    ND                        ND                        ND                        ND Krypton-87 Ci                    ND                        ND                        ND                        ND Krypton-88  Ci                    ND                        ND                        ND                        ND Xenon-133  Ci                2.04E-02    8.66E-03              9.72E-03                  9.63E-03 Xenon-133m Ci                    ND                        ND                        ND                        ND Xenon-135  Ci                4.44E-02              3.71E-02              2.73E-02                  1.02E-02 Xenon-135m  Ci                1.17E-02              1.51E-02              1.68E-02                  2.21E-03 Xenon-137 Ci                    ND  ND                        ND                        ND Xenon-138  Ci                    ND                        ND                        ND                        ND  


TOTAL                                            Ci                  7.65E-02                6.09E-02              5.39E-02 2.21E-02  
TOTAL                                            Ci                  7.65E-02                6.09E-02              5.39E-02 2.21E-02
: 2. Iodines Iodine-131 Ci 5.11E-05 3.09E-05 1.34E-04 1.64E-04 Iodine-132                                        Ci                        ND                      ND                      1.1 9E-04                    ND Iodine-133 Ci 4.48E-04 3.13E-04 1.03E-03 1.23E-03 Iodine-135                                        Ci                        ND                    ND                      3.8 9E-04                    ND  
: 2. Iodines Iodine-131 Ci 5.11E-05 3.09E-05 1.34E-04 1.64E-04 Iodine-132                                        Ci                        ND                      ND                      1.1 9E-04                    ND Iodine-133 Ci 4.48E-04 3.13E-04 1.03E-03 1.23E-03 Iodine-135                                        Ci                        ND                    ND                      3.8 9E-04                    ND  


TOTAL Ci 4.99E-04 3.44E-04                1.67E-03    1.39E-03  
TOTAL Ci 4.99E-04 3.44E-04                1.67E-03    1.39E-03
: 3. Particulates Silver-110M Ci                        ND                      ND                          ND  ND Cobalt-58 Ci                        ND                      ND                          ND                    ND Cobalt-60 Ci                        ND                      ND            1.59E-06                1.90E-06 Manganese-54 Ci                        ND                      ND                2.02E-06          ND Selenium-75 Ci                        ND                      ND                          ND                        ND Strontium-89 Ci                    4.38E-05  ND                          ND                        ND Zinc-65 Ci                    2.13E-06                  ND                      1.72E-06                    ND  
: 3. Particulates Silver-110M Ci                        ND                      ND                          ND  ND Cobalt-58 Ci                        ND                      ND                          ND                    ND Cobalt-60 Ci                        ND                      ND            1.59E-06                1.90E-06 Manganese-54 Ci                        ND                      ND                2.02E-06          ND Selenium-75 Ci                        ND                      ND                          ND                        ND Strontium-89 Ci                    4.38E-05  ND                          ND                        ND Zinc-65 Ci                    2.13E-06                  ND                      1.72E-06                    ND  


TOTAL Ci                    4.60E-05                  ND                      5.33E-06                1.90E-06  
TOTAL Ci                    4.60E-05                  ND                      5.33E-06                1.90E-06
: 4. Tritium Hydrogen-3 Ci 3.04E+00 3.47E+00    4.11E+
: 4. Tritium Hydrogen-3 Ci 3.04E+00 3.47E+00    4.11E+
00                3.43E+00 Note:  There were no batch releases for this report period.
00                3.43E+00 Note:  There were no batch releases for this report period.


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 9  TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES EST TOTAL    UNIT QTR 1 QTR 2 QTR 3 QTR 4    ERROR %
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 9  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 ND                ND                    ND                ND              NA  
A. FISSION AND ACTIVATION PRODUCTS  1. Total Release (not including                  tritium, gases and alpha) Ci ND                ND                    ND                ND              NA
: 2. Average diluted concentration  during period Ci/ml ND    ND        ND                ND          3. Percentage ODCM Limit                            %                      NA                NA NA                NA  
: 2. Average diluted concentration  during period Ci/ml ND    ND        ND                ND          3. Percentage ODCM Limit                            %                      NA                NA NA                NA  


B. TRITIUM  1. Total Release Ci 1.06E-02  8.33E-03 9.06E-03 8.84E-03 2.50E+01  2. Average diluted concentration  during period (Note 1) Ci/ml 3.20E-06  1.53E-06          2.01E-06 1.45E-06  3. Percentage ODCM Limit  % * * *
B. TRITIUM  1. Total Release Ci 1.06E-02  8.33E-03 9.06E-03 8.84E-03 2.50E+01  2. Average diluted concentration  during period (Note 1) Ci/ml 3.20E-06  1.53E-06          2.01E-06 1.45E-06  3. Percentage ODCM Limit  % * * *
* C. DISSOLVED AND ENTRAINED GASES  1. Total Release Ci ND    ND    ND                ND                NA
* C. DISSOLVED AND ENTRAINED GASES  1. Total Release Ci ND    ND    ND                ND                NA
: 2. Average diluted concentration  during period Ci/ml ND    ND        ND                ND
: 2. Average diluted concentration  during period Ci/ml ND    ND        ND                ND
: 3. Percentage ODCM Limit %    NA                NA                  NA                NA  
: 3. Percentage ODCM Limit %    NA                NA                  NA                NA  


D. GROSS ALPHA RADIOACTIVITY  1. Total Release Ci ND    ND    ND          2.39E-07        4.20E+01  E. VOLUME OF WASTE RELEASED  (PRIOR TO DILUTION) liters 3.26E+06  4.89E+06          4.43E+06  5.97E+06 F. VOLUME OF DILUTION WATER  USED DURING PERIOD liters 7.07E+07  3.79E+08 3.04E+08 2.87E+08 G. PERCENT OF APPLICABLE ODCM LIMITS  1. Quarterly Whole Body Dose %  9.11E-04  3.48E-04          5.69E-04 3.25E-04  2. Quarterly Organ Dose %  2.73E-04  1.04E-04 1.71E-04 9.74E-05  
D. GROSS ALPHA RADIOACTIVITY  1. Total Release Ci ND    ND    ND          2.39E-07        4.20E+01  E. VOLUME OF WASTE RELEASED  (PRIOR TO DILUTION) liters 3.26E+06  4.89E+06          4.43E+06  5.97E+06 F. VOLUME OF DILUTION WATER  USED DURING PERIOD liters 7.07E+07  3.79E+08 3.04E+08 2.87E+08 G. PERCENT OF APPLICABLE ODCM LIMITS  1. Quarterly Whole Body Dose %  9.11E-04  3.48E-04          5.69E-04 3.25E-04  2. Quarterly Organ Dose %  2.73E-04  1.04E-04 1.71E-04 9.74E-05
: 3. Annual Whole Body Dose %  4.55E-04  1.74E-04          2.85E-04  1.62E-04  
: 3. Annual Whole Body Dose %  4.55E-04  1.74E-04          2.85E-04  1.62E-04
: 4. Annual Organ Dose %  1.37E-04  5.22E-05 8.54E-05 4.87E-05  
: 4. Annual Organ Dose %  1.37E-04  5.22E-05 8.54E-05 4.87E-05  


Note 1:  Concentration includes summation from diluted and undiluted values from Canal and Non-Canal releases (Table 2B).  
Note 1:  Concentration includes summation from diluted and undiluted values from Canal and Non-Canal releases (Table 2B).  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 10  TABLE 2B LIQUID EFFLUENTS CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4  
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 10  TABLE 2B LIQUID EFFLUENTS CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4
: 1. Fission and Activation Products  
: 1. Fission and Activation Products  


ND Ci                      ND                        ND                        ND                      ND  
ND Ci                      ND                        ND                        ND                      ND
: 2. Tritium Hydrogen-3 Ci                        1.31E-04 8.27E-04 1.85E-04 2.07E-04
: 2. Tritium Hydrogen-3 Ci                        1.31E-04 8.27E-04 1.85E-04 2.07E-04
: 3. Dissolved and Entrained Gases  
: 3. Dissolved and Entrained Gases  
Line 705: Line 705:
ND Ci                        ND                        ND                        ND                        ND  
ND Ci                        ND                        ND                        ND                        ND  


TABLE 2B LIQUID EFFLUENTS CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4  
TABLE 2B LIQUID EFFLUENTS CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4
: 1. Fission and Activation Products  
: 1. Fission and Activation Products  


ND Ci                    ND                        ND                        ND                      ND  
ND Ci                    ND                        ND                        ND                      ND
: 2. Tritium Hydrogen-3 Ci    ND                          ND                        ND                      ND  
: 2. Tritium Hydrogen-3 Ci    ND                          ND                        ND                      ND
: 3. Dissolved and Entrained Gases  
: 3. Dissolved and Entrained Gases  


Line 715: Line 715:


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 11  TABLE 2B (SUPPLEMENT)
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 11  TABLE 2B (SUPPLEMENT)
LIQUID EFFLUENTS NON-CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4  
LIQUID EFFLUENTS NON-CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4
: 1. Fission and Activation Products  
: 1. Fission and Activation Products  


ND Ci                        ND                        ND                        ND                        ND  
ND Ci                        ND                        ND                        ND                        ND
: 2. Tritium Hydrogen-3 Ci 4.57E-03 6.76E-03 8.37E-03 8.59E-03  
: 2. Tritium Hydrogen-3 Ci 4.57E-03 6.76E-03 8.37E-03 8.59E-03
: 3. Dissolved and Entrained Gases ND Ci                        ND                        ND                        ND                        ND  
: 3. Dissolved and Entrained Gases ND Ci                        ND                        ND                        ND                        ND  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 12  TABLE 2B (SUPPLEMENT)
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 12  TABLE 2B (SUPPLEMENT)
LIQUID EFFLUENTS NON-CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4  
LIQUID EFFLUENTS NON-CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4
: 1. Fission and Activation Products  
: 1. Fission and Activation Products  


ND Ci                        ND                        ND                        ND                      ND  
ND Ci                        ND                        ND                        ND                      ND
: 2. Tritium Hydrogen-3 Ci 5.89E-03 7.48E-04 5.09E-04 4.69E-05  
: 2. Tritium Hydrogen-3 Ci 5.89E-03 7.48E-04 5.09E-04 4.69E-05
: 3. Dissolved and Entrained Gases ND Ci                        ND                        ND                        ND                      ND  
: 3. Dissolved and Entrained Gases ND Ci                        ND                        ND                        ND                      ND  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 13  TABLE 2B (continued)
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 13  TABLE 2B (continued)
ABNORMAL RELEASE LIQUID EFFLUENTS CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4  
ABNORMAL RELEASE LIQUID EFFLUENTS CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4
: 1. Fission and Activation Products ND Ci                        ND                        ND                        ND                        ND  
: 1. Fission and Activation Products ND Ci                        ND                        ND                        ND                        ND
: 2. Tritium ND Ci                        ND                        ND                        ND                        ND  
: 2. Tritium ND Ci                        ND                        ND                        ND                        ND
: 3. Dissolved and Entrained Gases ND Ci                        ND                        ND                        ND                        ND  
: 3. Dissolved and Entrained Gases ND Ci                        ND                        ND                        ND                        ND  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 14 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 %
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 14 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 6.51E+01 0.00E+00 0.00E+00      evaporator bottoms, etc. Ci 6.05E+01 0.00E+00 0.00E+00 1.00E+01      
: a. Spent resins, filter sludges, m 3 6.51E+01 0.00E+00 0.00E+00      evaporator bottoms, etc. Ci 6.05E+01 0.00E+00 0.00E+00 1.00E+01
: b. Dry compressible waste, m 3 3.62E+02 0.00E+00 0.00E+00      contaminated equipment, etc. Ci 1.16E+00 0.00E+
: b. Dry compressible waste, m 3 3.62E+02 0.00E+00 0.00E+00      contaminated equipment, etc. Ci 1.16E+00 0.00E+
00 0.00E+00 1.00E+01      
00 0.00E+00 1.00E+01
: c. Irradiated components, m 3 4.96E+00 0.00E+00 3.58E-01      control rods, etc. Ci 2.28E-01 0.00E+00 2.86E+04 1.00E+01      
: c. Irradiated components, m 3 4.96E+00 0.00E+00 3.58E-01      control rods, etc. Ci 2.28E-01 0.00E+00 2.86E+04 1.00E+01
: d. Other: Dry compressible m 3 7.14E+00  0.00E+00 0.00E+00      waste, contaminated equipment, Ci 3.25E-02 0.00E+
: d. Other: Dry compressible m 3 7.14E+00  0.00E+00 0.00E+00      waste, contaminated equipment, Ci 3.25E-02 0.00E+
00 0.00E+00 1.00E+01    spent resins for volume reduction.  
00 0.00E+00 1.00E+01    spent resins for volume reduction.
: 2. Estimate of Major Nuclide Composition (by type of waste)  
: 2. Estimate of Major Nuclide Composition (by type of waste)
: a. Spent resins, filter sludges, evaporator bottoms, etc.
: a. Spent resins, filter sludges, evaporator bottoms, etc.
Isotope Percent Curies  Isotope Percent Curies Ce-144 9.00E-02 5.16E-02  E Co-58 7.00E-02 4.33E-02    E Co-60 3.67E+01 2.23E+01  E Fe-59 1.00E-02 3.89E-03    E Cs-137 5.20E-01 3.16E-01  E Fe-55 1.41E+01 8.53E+00  E C-14 2.10E-01 1.28E-01  E Mn-54 2.02E+01 1.22E+01  E Ni-63 7.10E-01 4.28E-01  E Tc-99 4.00E-02 2.18E-02    E Zn-65 2.71E+01 1.64E+01  E H-3 2.00E-01 1.19E-01    E Sb-125 1.50E-01 9.23E-02  E   
Isotope Percent Curies  Isotope Percent Curies Ce-144 9.00E-02 5.16E-02  E Co-58 7.00E-02 4.33E-02    E Co-60 3.67E+01 2.23E+01  E Fe-59 1.00E-02 3.89E-03    E Cs-137 5.20E-01 3.16E-01  E Fe-55 1.41E+01 8.53E+00  E C-14 2.10E-01 1.28E-01  E Mn-54 2.02E+01 1.22E+01  E Ni-63 7.10E-01 4.28E-01  E Tc-99 4.00E-02 2.18E-02    E Zn-65 2.71E+01 1.64E+01  E H-3 2.00E-01 1.19E-01    E Sb-125 1.50E-01 9.23E-02  E   


(E- Estimated M- Measured)  
(E- Estimated M- Measured)
: b. Dry compressible waste, contaminated equipment, etc.
: b. Dry compressible waste, contaminated equipment, etc.
Isotope Percent Curies  Isotope Percent Curies  
Isotope Percent Curies  Isotope Percent Curies  
Line 753: Line 753:
Ce-144 1.00E-02 2.88E-04  E Co-58 2.00E-02 1.18E-03    E Co-60 2.62E+00 1.45E-01  E Fe-59 6.00E-02 3.21E-03    E Cs-137 3.10E-01 1.71E-02  E Fe-55 1.36E+01 7.52E-01    E C-14 2.76E+01 1.53E+00  E Mn-54 1.15E+00 6.34E-02    E Ni-63 6.10E-01 3.37E-02  E I-129 7.90E-01 4.37E-02    E Zn-65 2.03E+00 1.12E-01  E H-3 4.11E+01 2.27E+00  E Sb-124 1.00E-02 7.92E-04  E Tc-99 1.01E+01 5.59E-01    E Sb-125 1.00E-02 5.53E-04  E Cr-51 5.00E-02 3.04E-03    E  
Ce-144 1.00E-02 2.88E-04  E Co-58 2.00E-02 1.18E-03    E Co-60 2.62E+00 1.45E-01  E Fe-59 6.00E-02 3.21E-03    E Cs-137 3.10E-01 1.71E-02  E Fe-55 1.36E+01 7.52E-01    E C-14 2.76E+01 1.53E+00  E Mn-54 1.15E+00 6.34E-02    E Ni-63 6.10E-01 3.37E-02  E I-129 7.90E-01 4.37E-02    E Zn-65 2.03E+00 1.12E-01  E H-3 4.11E+01 2.27E+00  E Sb-124 1.00E-02 7.92E-04  E Tc-99 1.01E+01 5.59E-01    E Sb-125 1.00E-02 5.53E-04  E Cr-51 5.00E-02 3.04E-03    E  


(E- Estimated M- Measured)  
(E- Estimated M- Measured)  


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 15  TABLE 3A (continued)
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 15  TABLE 3A (continued)
Line 761: Line 761:
Isotope Percent Curies  Isotope Percent Curies C-14 1.00E-02 1.76E+00  E Co-58 5.00E-02 1.43E+01    E Co-60 6.01E+01 1.72E+04  E Zn-65 2.00E-02 5.74E+00    E Ni-59 7.00E-02 1.96E+01  E Fe-55 3.47E+01 9.92E+03    E  Ni-63 4.19E+00 1.20E+03  E Mn-54 8.60E-01 2.46E+02    E  
Isotope Percent Curies  Isotope Percent Curies C-14 1.00E-02 1.76E+00  E Co-58 5.00E-02 1.43E+01    E Co-60 6.01E+01 1.72E+04  E Zn-65 2.00E-02 5.74E+00    E Ni-59 7.00E-02 1.96E+01  E Fe-55 3.47E+01 9.92E+03    E  Ni-63 4.19E+00 1.20E+03  E Mn-54 8.60E-01 2.46E+02    E  


    (E- Estimated  M- Measured)  
(E- Estimated  M- Measured)
: d. Other:  Dry compressible waste, contaminated equipment, spent resins contaminated oil, glycol and water for volume reduction.  
: d. Other:  Dry compressible waste, contaminated equipment, spent resins contaminated oil, glycol and water for volume reduction.  


Isotope Percent Curies  Isotope Percent Curies H-3 9.98E+01 3.25E-02  E Cs-137 4.00E-02 1.25E-05    E Fe-55 1.00E-01 3.33E-05  E Co-60 1.00E-02 2.77E-06    E  
Isotope Percent Curies  Isotope Percent Curies H-3 9.98E+01 3.25E-02  E Cs-137 4.00E-02 1.25E-05    E Fe-55 1.00E-01 3.33E-05  E Co-60 1.00E-02 2.77E-06    E  


(E- Estimated M- Measured)  
(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.
Percentage of nuclides and total activities are based on a combination of direct measurements and scaling for non-gamma emitting nuclides.
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Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Part 2, Section 4.4.1  
Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Part 2, 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".   
(1)Curies released calculated using the methodology in EPRI Technical Report 1021106    "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents".   


ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 29 ATTACHMENT NO. 9 EVENTS LEADING TO CONDITIONS WHICH RESULTED IN EXCEEDING RADIOACTIVITY LIMITS.
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 29 ATTACHMENT NO. 9 EVENTS LEADING TO CONDITIONS WHICH RESULTED IN EXCEEDING RADIOACTIVITY LIMITS.
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ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2015
ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2015
: 1. INTRODUCTION The James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Effluent Controls (REC), requires an assessment of the radiation doses to the likely most exposed member of the public due to radioactive liquid and gaseous effluents. This assessment of doses to the likely most exposed member of the public is based on accepted methodologies found in the Offsite Dose Calculation Manual (ODCM).  
: 1. INTRODUCTION The James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Effluent Controls (REC), requires an assessment of the radiation doses to the likely most exposed member of the public due to radioactive liquid and gaseous effluents. This assessment of doses to the likely most exposed member of 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)  
: 2. DOSE LIMITS A. DOSE FROM LIQUID EFFLUENTS (ODCM, Part 1, REC 2.3)  


Line 901: Line 901:
To ensure that the dose limitations of 10 CFR 50, Appendix I, are met.  
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:  
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.  
: 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.
: 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)  
B. GASEOUS DOSE RATES (ODCM, Part 1, REC 3.2)  
Line 910: Line 910:
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.
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.
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 31  ADDENDUM 1 (continued)
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 31  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:  
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,
: 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).
: 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)  
C. AIR DOSE, NOBLE GASES (ODCM, Part 1, REC 3.3)  
Line 919: Line 919:
Objective To ensure that the noble gas dose limitations of 10 CFR 50, Appendix I, are met.  
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:  
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,
: 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.  
: 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.  


Line 931: Line 931:


To ensure that the dose limitations of 10 CFR 50, Appendix I, are met.
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:  
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:
: a. During any calendar quarter to less than or equal to 7.5 mrem to any organ; and,  
: 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.  
: 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 Specifications 3.4.1.c.1.a and 3.4.1.c.1.b as a result of burning contaminated oil.
: c. Less than 0.1% of the limits of Specifications 3.4.1.c.1.a and 3.4.1.c.1.b as a result of burning contaminated oil.
E. TOTAL DOSE FROM URANIUM FUEL CYCLE (ODCM, Part 1, REC 4.0)  
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  
Applicability Applies to radiation dose from releases of radioactivity and radiation from uranium fuel cycle sources. Objective
: 1. To assure that the requirements of 40 CFR 190 are met.  
: 1. To assure that the requirements of 40 CFR 190 are met.
: 2. To assure that the requirements of 10 CFR 72.104 are met in accordance with Section 3.2.3, Required Action A.2, Certificate of Compliance 1014 Appendix A, Technical Specifications for the Hi-Storm 100 Cask System.
: 2. To assure that the requirements of 10 CFR 72.104 are met in accordance with Section 3.2.3, Required Action A.2, Certificate of Compliance 1014 Appendix A, Technical Specifications for the Hi-Storm 100 Cask System.
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:  
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,  
: 1. Less than or equal to 25 mrem/year to the whole body; and,
: 2. Less than or equal to 25 mrem/year to a ny organ except the thyroid which shall be limited to less than or equal to 75 mrem/year.
: 2. Less than or equal to 25 mrem/year to a ny organ except the thyroid which shall be limited to less than or equal to 75 mrem/year.
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 33 ADDENDUM 1 (continued)
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 33 ADDENDUM 1 (continued)
Line 954: Line 954:
==SUMMARY==
==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.  
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.
: 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  
B. RESULTS  
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TABLE 1 ANNUAL DOSE ASSESSMENT 2015 A. LIQUIDS QUARTER 1 2 3 4 ANNUAL  
TABLE 1 ANNUAL DOSE ASSESSMENT 2015 A. LIQUIDS QUARTER 1 2 3 4 ANNUAL  


(a) (a) (a) (a) (a)  
(a) (a) (a) (a) (a)  


Organ (mrem)      1.37E-05 5.22E-06 8.54E-06 4.87E-06 3.23E-05 % of Limit 2.73E-04 1.04E-04 1.71E-04 9.74E-05 3.23E-04  
Organ (mrem)      1.37E-05 5.22E-06 8.54E-06 4.87E-06 3.23E-05 % of Limit 2.73E-04 1.04E-04 1.71E-04 9.74E-05 3.23E-04  


(b) (b) (b) (b) (b)  
(b) (b) (b) (b) (b)  


Whole Body (mrem) 1.37E-05 5.22E-06 8.54E-06 4.87E-06 3.23E-05 % of Limit 9.11E-04 3.48E-04 5.69E-04 3.25E-04 1.08E-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.  
Whole Body (mrem) 1.37E-05 5.22E-06 8.54E-06 4.87E-06 3.23E-05 % of Limit 9.11E-04 3.48E-04 5.69E-04 3.25E-04 1.08E-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.  
Line 985: Line 985:
Beta (mrad) 2.69E-05 5.86E-05 3.00E-05 1.71E-05 1.33E-04 % of Limit 2.69E-04 5.86E-04 3.00E-04 1.71E-04 6.63E-04 C. IODINES AND PARTICULATES QUARTER  1  2  3  4        ANNUAL  
Beta (mrad) 2.69E-05 5.86E-05 3.00E-05 1.71E-05 1.33E-04 % of Limit 2.69E-04 5.86E-04 3.00E-04 1.71E-04 6.63E-04 C. IODINES AND PARTICULATES QUARTER  1  2  3  4        ANNUAL  


(a) (a) (a) (a) (a)  
(a) (a) (a) (a) (a)  


Organ (mrem) 8.84E-04 6.17E-04 2.22E-03 2.67E-03 6.39E-03 % of Limit 1.18E-02 8.23E-03 2.96E-02 3.56E-02 4.26E-02  
Organ (mrem) 8.84E-04 6.17E-04 2.22E-03 2.67E-03 6.39E-03 % of Limit 1.18E-02 8.23E-03 2.96E-02 3.56E-02 4.26E-02  


(a) (a) (a) (a) (a)  
(a) (a) (a) (a) (a)  


Organ Dose Rate 3.07E-04 1.73E-04 4.55E-04 3.17E-04 4.55E-04 (mrem/yr)  
Organ Dose Rate 3.07E-04 1.73E-04 4.55E-04 3.17E-04 4.55E-04 (mrem/yr)  
% of Limit 2.04E-05 1.15E-05 3.03E-05 2.11E-05 3.03E-05  
% of Limit 2.04E-05 1.15E-05 3.03E-05 2.11E-05 3.03E-05  


    (a)  Dose to the Child Thyroid primarily by the vegetation pathway.
(a)  Dose to the Child Thyroid primarily by the vegetation pathway.
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 36 ADDENDUM 1 (continued)
ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 36 ADDENDUM 1 (continued)
TABLE 1 (cont)
TABLE 1 (cont)
ANNUAL DOSE ASSESSMENT 2015 D. CARBON 14 QUARTER  1  2    3  4      ANNUAL  
ANNUAL DOSE ASSESSMENT 2015 D. CARBON 14 QUARTER  1  2    3  4      ANNUAL  


(a) (a) (a) (a) (a)  
(a) (a) (a) (a) (a)  


Organ (mrem) 8.43E-03 8.52E-03 8.59E-03 8.62E-03 3.42E-02 % of Limit 1.12E-01 1.14E-01 1.14E-01 1.15E-01 2.28E-01  
Organ (mrem) 8.43E-03 8.52E-03 8.59E-03 8.62E-03 3.42E-02 % of Limit 1.12E-01 1.14E-01 1.14E-01 1.15E-01 2.28E-01  


    (a)  
(a)  


Organ Dose Rate NA    NA    NA  NA 3.42E-02  (mrem/yr)  
Organ Dose Rate NA    NA    NA  NA 3.42E-02  (mrem/yr)  
% of Limit    NA    NA    NA                  NA 2.28E-03  
% of Limit    NA    NA    NA                  NA 2.28E-03  


    (a)  Dose to the Child Bone primarily by the vegetation pathway.}}
(a)  Dose to the Child Bone primarily by the vegetation pathway.}}

Revision as of 07:53, 27 April 2019

Transmittal of 2015 Annual Radioactive Effluent Release Report
ML16119A415
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/28/2016
From: William Drews
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-16-0070
Download: ML16119A415 (40)
v • d • e


Text

JAFP-16-0070 April 28, 2016 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001

SUBJECT:

2015 Annual Radioactive Effluent Release Report James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59

Dear Sir or Madam:

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc. James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 315-342-3840 William C Drews Regulatory Assurance Manager -JAF This letter transmits the James A. FitzPatrick Nuclear Power Plant's (JAF) Annual Radioactive Effluent Release Report, for the period of January 1, 2015 through December 31, 2015. The enclosure is submitted in accordance with the reporting requirements of Technical Specification Section 5.6.3 and Technical Requirements Manual Appendix H Offsite Dose Calculation Manual (ODCM) Part 1 Section 6.2 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 2015 calendar year. The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21 Revision 1. There are no new regulatory commitments contained in this letter. If you have any questions concerning the enclosed report, please contact Mr. Michael Ponzo, Chemistry Manager, at (315)349-6168.

Sincerely, {)

William C. Drews Regulatory Assurance Manager -JAF WCD/MP/dc

Enclosure:

cc: next page 2015 Annual Radioactive Effluent Release Report JAFP-16-0070 Page 2 of 2 cc:

USNRC Regional Administrator, Region I

USNRC Resident Inspector

USNRC NRR Project Manager

M. Ponzo (CHEM/JAF)

B. Landers (CHEM/JAF)

K. Stoffle (NMP)

JAFP-16-0070 Enclosure

2015 Annual Radioactive Effluent Release Report (37 Pages)

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

JANUARY 1, 2015 - DECEMBER 31, 2015

DOCKET NO. 50-333 LICENSE NO. DPR-59

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 1 SUPPLEMENTAL INFORMATION

FACILITY: JAFNPP LICENSEE: ENTERGY NUCLEAR OPERATIONS, INC.

1. Offsite Dose Calculation Manual Part 1 Radiological Effluent 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).

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 2 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

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 3 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

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 4 SUPPLEMENTAL INFORMATION (continued)

5. Batch Releases
a. Liquid: Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 4.00E+00 9.00E+00 5.00E+00 8.00E+00

(2) Total time period for batch 4.80E+01 2.45E+02 1.88E+02 1.78E+02 release: (min)

(3) Maximum time period for 3.40E+01 7.20E+01 9.00E+01 5.80E+01 batch release: (min)

(4) Average time period for 1.20E+01 2.72E+01 3.76E+01 2.22E+01 batch release: (min)

(5) Minimum time period for 1.00E+00 3.00E+00 2.00E+00 2.00E+00 batch release: (min)

(6) Total Activity Released (Ci) 1.31E-04 8.27E-04 1.85E-04 2.07E-04

(7) Total Volume Released (liters) 4.13E+03 5.85E+04 8.24E+03 2.75E+04

b. Liquid: Non-Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 6.00E+00 1.10E+01 1.60E+01 2.00E+01

(2) Total time period for batch 2.55E+02 6.73E+02 2.96E+02 6.10E+01 release: (min)

(3) Maximum time period for 2.47E+02 3.89E+02 3.70E+01 7.00E+00 batch release: (min)

(4) Average time period for 4.25E+01 6.12E+01 1.85E+01 3.15E+00 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) 5.89E-03 7.48E-04 5.09E-04 4.69E-05

(7) Total Volume Released (liters) 9.58E+04 2.28E+05 1.12E+05 2.34E+04

c. Gaseous

There were no gaseous batch releases for this report period.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 5 SUPPLEMENTAL INFORMATION (continued)

6. Continuous Releases
a. Liquid: Non-Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases: 1.20E+01 1.40E+01 1.40E+01 1.30E+01

(2) Total Activity Released (Ci) 4.57E-03 6.76E-03 8.37E-03 8.59E-03

(3) Total Volume Released (liters) 3.16E+06 4.61E+06 4.31E+06 5.92E+06

b. Liquid: Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases: 0 0 0 0

(2) Total Activity Released (Ci) N/A N/A N/A N/A

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 6 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 9.07E+00 2.25E+01 1.07E+01 6.14E+00 2.50E+01 2. Average release rate for period Ci/sec 1.17E+00 2.86E+00 1.34E+00 7.73E-01 3. Percentage ODCM Limit % * * *

  • B. IODINE-131 1. Total Iodine-131 Ci 5.41E-05 3.50E-05 1.52E-04 1.82E-04 2.50E+01 2. Average release rate for period Ci/sec 6.96E-06 4.45E-06 1.91E-05 2.28E-05 3. Percentage ODCM Limit % * * *
  • C. PARTICULATES 1. Particulates with half-lives >8 days Ci 4.64E-05 1.15E-06 7.94E-06 5.37E-06 3.60E+01 2. Average release rate for period Ci/sec 5.96E-06 1.47E-07 9.99E-07 6.75E-07 3. Percentage ODCM Limit % * * *
  • 4. Gross alpha radioactivity Ci 3.94E-07 1.84E-07 3.52E-07 3.31E-07 2.50E+01 D. TRITIUM 1. Total Release Ci 3.28E+00 3.69E+00 4.

52E+00 3.77E+00 2.50E+01 2. Average release rate for period Ci/sec 4.22E-01 4.70E-01 5.69E-01 4.74E-01 3. Percentage 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 % 5.32E-03 1.29E-02 6.03E-03 3.21E-03 2. Quarterly beta air dose limit % 2.69E-04 5.86E-04 3.00E-04 1.71E-04
3. Yearly gamma air dose limit % 2.66E-03 6.46E-03 3.02E-03 1.61E-03
4. Yearly beta air dose limit % 1.34E-04 2.93E-04 1.50E-04 8.56E-05
5. Whole body dose rate limit % 4.32E-03 2.70E-03 2.86E-03 1.22E-03
6. Skin dose rate limit % 1.37E-03 7.86E-04 8.65E-04 4.23E-04 HALOGENS, TRITIUM AND PARTICULA TES WITH HALF-LIVES >8 DAYS 7. Quarterly dose limit (organ) % 1.18E-02 8.23E-03 2.96E-02 3.49E-02 8. Yearly dose limit (organ) % 5.89E-03 4.11E-03 1.48E-02 1.75E-02
9. Organ dose rate limit % 2.04E-05 1.15E-05 3.03E-05 2.11E-05 ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 7 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 6.65E+00 1.15E+01 5.61E+00 3.29E+00 Krypton-85 Ci ND ND ND ND Krypton-85m Ci 1.40E+00 3.16E+00 1.40E+00 8.11E-01 Krypton-87 Ci ND ND ND ND Krypton-88 Ci 5.98E-01 4.02E+00 1.24E+00 2.98E-01 Xenon-133 Ci 3.49E-01 3.32E+00 1.25E+00 7.67E-01 Xenon-133m Ci ND ND ND ND Xenon-135 Ci ND ND 2.19E-02 ND Xenon-135m Ci ND ND 1.82E-01 1.89E-01 Xenon-137 Ci ND ND ND ND Xenon-138 Ci ND 4.31E-01 9.38E-01 7.69E-01

TOTAL Ci 9.00E+00 2.24E+01 1.06E+01 6.12E+00

2. Iodines Iodine-131 Ci 3.05E-06 4.07E-06 1.75E-05 1.77E-05 Iodine-132 Ci ND ND ND ND Iodine-133 Ci 2.68E-05 2.47E-05 7.34E-05 6.30E-05 Iodine-135 Ci ND ND ND ND TOTAL Ci 2.98E-05 2.88E-05 9.09E-05 8.07E-05
3. Particulates Cobalt-60 Ci ND ND ND ND Cesium-137 Ci ND ND ND ND Manganese-54 Ci ND ND ND ND Strontium-89 Ci 3.80E-07 1.15E-06 2.61E-06 3.47E-06 Zinc-65 Ci ND ND ND ND

TOTAL Ci 3.80E-07 1.15E-06 2.61E-06 3.47E-06

4. Tritium Hydrogen-3 Ci 2.39E-01 2.25E-01 4.06E-01 3.41E-01 Note: There were no batch releases for this report period.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 8 TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED

1. Fission Gases UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Argon-41 Ci ND ND ND ND Krypton-85 Ci ND ND ND ND Krypton-85m Ci ND ND ND ND Krypton-87 Ci ND ND ND ND Krypton-88 Ci ND ND ND ND Xenon-133 Ci 2.04E-02 8.66E-03 9.72E-03 9.63E-03 Xenon-133m Ci ND ND ND ND Xenon-135 Ci 4.44E-02 3.71E-02 2.73E-02 1.02E-02 Xenon-135m Ci 1.17E-02 1.51E-02 1.68E-02 2.21E-03 Xenon-137 Ci ND ND ND ND Xenon-138 Ci ND ND ND ND

TOTAL Ci 7.65E-02 6.09E-02 5.39E-02 2.21E-02

2. Iodines Iodine-131 Ci 5.11E-05 3.09E-05 1.34E-04 1.64E-04 Iodine-132 Ci ND ND 1.1 9E-04 ND Iodine-133 Ci 4.48E-04 3.13E-04 1.03E-03 1.23E-03 Iodine-135 Ci ND ND 3.8 9E-04 ND

TOTAL Ci 4.99E-04 3.44E-04 1.67E-03 1.39E-03

3. Particulates Silver-110M Ci ND ND ND ND Cobalt-58 Ci ND ND ND ND Cobalt-60 Ci ND ND 1.59E-06 1.90E-06 Manganese-54 Ci ND ND 2.02E-06 ND Selenium-75 Ci ND ND ND ND Strontium-89 Ci 4.38E-05 ND ND ND Zinc-65 Ci 2.13E-06 ND 1.72E-06 ND

TOTAL Ci 4.60E-05 ND 5.33E-06 1.90E-06

4. Tritium Hydrogen-3 Ci 3.04E+00 3.47E+00 4.11E+

00 3.43E+00 Note: There were no batch releases for this report period.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 9 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 ND ND ND ND NA

2. Average diluted concentration during period Ci/ml ND ND ND ND 3. Percentage ODCM Limit  % NA NA NA NA

B. TRITIUM 1. Total Release Ci 1.06E-02 8.33E-03 9.06E-03 8.84E-03 2.50E+01 2. Average diluted concentration during period (Note 1) Ci/ml 3.20E-06 1.53E-06 2.01E-06 1.45E-06 3. Percentage ODCM Limit  % * * *

  • C. DISSOLVED AND ENTRAINED GASES 1. Total Release Ci ND ND ND ND NA
2. Average diluted concentration during period Ci/ml ND ND ND ND
3. Percentage ODCM Limit % NA NA NA NA

D. GROSS ALPHA RADIOACTIVITY 1. Total Release Ci ND ND ND 2.39E-07 4.20E+01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) liters 3.26E+06 4.89E+06 4.43E+06 5.97E+06 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 7.07E+07 3.79E+08 3.04E+08 2.87E+08 G. PERCENT OF APPLICABLE ODCM LIMITS 1. Quarterly Whole Body Dose % 9.11E-04 3.48E-04 5.69E-04 3.25E-04 2. Quarterly Organ Dose % 2.73E-04 1.04E-04 1.71E-04 9.74E-05

3. Annual Whole Body Dose % 4.55E-04 1.74E-04 2.85E-04 1.62E-04
4. Annual Organ Dose % 1.37E-04 5.22E-05 8.54E-05 4.87E-05

Note 1: Concentration includes summation from diluted and undiluted values from Canal and Non-Canal releases (Table 2B).

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 10 TABLE 2B LIQUID EFFLUENTS CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4

1. Fission and Activation Products

ND Ci ND ND ND ND

2. Tritium Hydrogen-3 Ci 1.31E-04 8.27E-04 1.85E-04 2.07E-04
3. Dissolved and Entrained Gases

ND Ci ND ND ND ND

TABLE 2B LIQUID EFFLUENTS CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4

1. Fission and Activation Products

ND Ci ND ND ND ND

2. Tritium Hydrogen-3 Ci ND ND ND ND
3. Dissolved and Entrained Gases

ND Ci ND ND ND ND

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 11 TABLE 2B (SUPPLEMENT)

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

1. Fission and Activation Products

ND Ci ND ND ND ND

2. Tritium Hydrogen-3 Ci 4.57E-03 6.76E-03 8.37E-03 8.59E-03
3. Dissolved and Entrained Gases ND Ci ND ND ND ND

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 12 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

ND Ci ND ND ND ND

2. Tritium Hydrogen-3 Ci 5.89E-03 7.48E-04 5.09E-04 4.69E-05
3. Dissolved and Entrained Gases ND Ci ND ND ND ND

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 13 TABLE 2B (continued)

ABNORMAL RELEASE LIQUID EFFLUENTS CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4

1. Fission and Activation Products ND Ci ND ND ND ND
2. Tritium ND Ci ND ND ND ND
3. Dissolved and Entrained Gases ND Ci ND ND ND ND

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 14 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 6.51E+01 0.00E+00 0.00E+00 evaporator bottoms, etc. Ci 6.05E+01 0.00E+00 0.00E+00 1.00E+01
b. Dry compressible waste, m 3 3.62E+02 0.00E+00 0.00E+00 contaminated equipment, etc. Ci 1.16E+00 0.00E+

00 0.00E+00 1.00E+01

c. Irradiated components, m 3 4.96E+00 0.00E+00 3.58E-01 control rods, etc. Ci 2.28E-01 0.00E+00 2.86E+04 1.00E+01
d. Other: Dry compressible m 3 7.14E+00 0.00E+00 0.00E+00 waste, contaminated equipment, Ci 3.25E-02 0.00E+

00 0.00E+00 1.00E+01 spent resins for volume reduction.

2. Estimate of Major Nuclide Composition (by type of waste)
a. Spent resins, filter sludges, evaporator bottoms, etc.

Isotope Percent Curies Isotope Percent Curies Ce-144 9.00E-02 5.16E-02 E Co-58 7.00E-02 4.33E-02 E Co-60 3.67E+01 2.23E+01 E Fe-59 1.00E-02 3.89E-03 E Cs-137 5.20E-01 3.16E-01 E Fe-55 1.41E+01 8.53E+00 E C-14 2.10E-01 1.28E-01 E Mn-54 2.02E+01 1.22E+01 E Ni-63 7.10E-01 4.28E-01 E Tc-99 4.00E-02 2.18E-02 E Zn-65 2.71E+01 1.64E+01 E H-3 2.00E-01 1.19E-01 E Sb-125 1.50E-01 9.23E-02 E

(E- Estimated M- Measured)

b. Dry compressible waste, contaminated equipment, etc.

Isotope Percent Curies Isotope Percent Curies

Ce-144 1.00E-02 2.88E-04 E Co-58 2.00E-02 1.18E-03 E Co-60 2.62E+00 1.45E-01 E Fe-59 6.00E-02 3.21E-03 E Cs-137 3.10E-01 1.71E-02 E Fe-55 1.36E+01 7.52E-01 E C-14 2.76E+01 1.53E+00 E Mn-54 1.15E+00 6.34E-02 E Ni-63 6.10E-01 3.37E-02 E I-129 7.90E-01 4.37E-02 E Zn-65 2.03E+00 1.12E-01 E H-3 4.11E+01 2.27E+00 E Sb-124 1.00E-02 7.92E-04 E Tc-99 1.01E+01 5.59E-01 E Sb-125 1.00E-02 5.53E-04 E Cr-51 5.00E-02 3.04E-03 E

(E- Estimated M- Measured)

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 15 TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

c. Irradiated components, control rods, etc.

Isotope Percent Curies Isotope Percent Curies C-14 1.00E-02 1.76E+00 E Co-58 5.00E-02 1.43E+01 E Co-60 6.01E+01 1.72E+04 E Zn-65 2.00E-02 5.74E+00 E Ni-59 7.00E-02 1.96E+01 E Fe-55 3.47E+01 9.92E+03 E Ni-63 4.19E+00 1.20E+03 E Mn-54 8.60E-01 2.46E+02 E

(E- Estimated M- Measured)

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

Isotope Percent Curies Isotope Percent Curies H-3 9.98E+01 3.25E-02 E Cs-137 4.00E-02 1.25E-05 E Fe-55 1.00E-01 3.33E-05 E Co-60 1.00E-02 2.77E-06 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.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 16 TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition No. of Shipments Mode of Transportation Destination

19 Trucks *Energy Solutions Oak Ridge, TN

3 Trucks *Energy Solutions Kingston, TN

2 Trucks *Energy Solutions Oak Ridge, TN

3 Trucks Waste Control Specialists, LLC Andrews, TX

1 Truck *Energy Solutions Oak Ridge, TN

1 Truck *Energy Solutions Oak Ridge, TN

  • Volume Reduction Facility

B. IRRADIATED FUEL SHIPMENTS (Disposition)

No. of Shipments Mode of Transportation Destination

None ----------- ---------------

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 17 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 (36.2 m 3) STC 9 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 96 ft 3 (2.72 m 3) STC 12 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 1033 ft 3 (29.3 m 3) STC 4 Contaminated Equipment, etc.

Spent Resins, Filter Sludges, evaporator Air Drying 205.8 ft 3 (5.83 m 3) HIC 14 Bottoms, etc. Non-compacted

Spent Resins, Filter Sludges, evaporator Air Drying 120.3 ft 3 (3.41 m 3) HIC 2 Bottoms, etc. Non-compacted

Contaminated Oil/Water. Non-compacted 1280 ft 3 (36.2 m 3) STC 1

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

Irradiated Hardware Non-compacted 58 ft 3 (1.64 m 3) HIC 3

HIC- High Integrity Container STC- Strong Tight Container ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 18 ATTACHMENT NO. 1 CHANGES TO THE OFFSITE DO SE CALCULATION MANUAL (ODCM)

In accordance with the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Effluent 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 made to the ODCM during this reporting period.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 19 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 Effluent 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.

EN-RW-105 Process Control Program Revision 5 became Headquarters effective 8/27/15. There were no changes to the James A. FitzPatrick Process Control Program (PCP) as a result of Revision 5. EN-RW-105 Process Control Program Revision 5 incorporates a temporary change for an Entergy Site.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 20 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, Radiological Effluent Controls (REC) 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.

There was one new milk location identified in the land use census, consisting of 20 milking cows and 15 heifers. The location is at address 6729 State Route 3 in the town of Richland. This location is outside the five-mile radius of the plant.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 21 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, Radiological Effluent Controls (REC) 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:

01/10/2015 - 01/14/2015 Air Station R-5 Offsite sample pump was inoperable for approximately 108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br />. Out of service time was determined based upon sample pump run time integrator. The inoperability was due to loss of power to the sample station. No corrective actions were required to restore power to the air station.

03/02/2015 - 03/10/2015 Air Station R-1 Offsite sample pump was inoperable for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Out of service time was determined based upon sample pump run time integrator. The inoperability was due to loss of power to the sample station. No corrective actions were required to restore power to the air station.

03/02/2015 - 03/10/2015 Air Station R-2 Offsite sample pump was inoperable for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Out of service time was determined based upon sample pump run time integrator. The inoperability was due to loss of power to the sample station. No corrective actions were required to

restore power to the air station.

10/27/2015 - 11/03/2015 Air Station R-2 Offsite sample pump was inoperable for approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. Out of service time was determined based upon sample pump run time integrator. The inoperability was due to loss of power to the sample station. No corrective actions were required to restore power to the air station.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 22 10/27/2015 - 11/03/2015 Air Station R-3 Offsite sample pump was inoperable for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Out of service time was determined based upon sample pump run time integrator. The inoperability was due to loss of power to the sample station. No corrective actions were required to restore power to the air station.

10/27/2015 - 11/03/2015 Air Station R-4 Offsite sample pump was inoperable for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Out of service time was determined based upon sample pump run time integrator. The inoperability was due to loss of power to the sample station. No corrective actions were required to restore power to the air station.

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 43,670 hours0.00775 days <br />0.186 hours <br />0.00111 weeks <br />2.54935e-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 99.7%.

Air sampling equipment found inoperable was returned to service. Identification of locations for obtaining replacement samples was not required.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 23 ATTACHMENT NO. 5 ANNUAL

SUMMARY

OF HOURLY METEOROLOGICAL DATA The James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1, Radiological Effluent 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.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 24 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 Effluent 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.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 25 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. In August 2013, 3 additional wells and 2 piezometers were installed on site.

All samples collected were analyzed for tritium and gamma emitting radionuclides. The detection limits and results are reported in the following tables. Analysis results of tritium ranged from non-detectable, a minimum positive indication of 1149 pCi/L, and a maximum concentration of 4379 pCi/L for a CST-B sample from 11/04/15. 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. 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. 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).

In conclusion, the only radionuclide detected in groundwater during the 2015 monitoring effort that is attributable to James A. FitzPatrick operations is tritium, and all concentrations were below any reporting criteria.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 26 ATTACHMENT NO. 7 (continued)

ONSITE GROUNDWATER MONITORING A) Gamma Isotopic Monitoring For 2015, the 24 monitoring wells were samp led quarterly, providing enough water was present, and analyzed below the required lower limits of detection in accordance with the Offsite Dose Calculation Manual (ODCM) Part 1, Table 5.1-3.

Radionuclide LLD Value (pCi/L) Radionuclide LLD Value (pCi/L) Tritium (H-3) 3000 Zirconium-95 15 Manganese-54 15 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 gamma emitting nuclides detected in the samples. Gross Beta and Hard to Detect nuclide analysis not required.

Per Note 2 on page 27, 2 groundwater monitoring samples detected tritium (H-3). One of the 2 sample results was greater than the LLD value of 3,000 pCi/L for H-3.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 27 ATTACHMENT NO. 7 (continued)

ONSITE GROUNDWATER MONITORING B) Tritium Summary Well Name # Samples in 2015 # Positive Samples in 2015 Minimum Positive Concentration Maximum Positive Concentration MW-1A 3 0 MW-1B 1 0 MW-2A 4 0 MW-2B 4 0 MW-3A 4 0 MW-3B 4 1 1149 1149 MW-4A 3 0 MW-4B 3 0 MW-5 4 0 MW-6 4 0 MW-7 4 0 MW-8 3 0 MW-9 3 0 MW-10A 4 0 MW-10B 4 0 MW-13 4 0 MW-14 3 0 MW-15 4 0 MW-16 3 0 MW-19 4 0 MW-20 3 0 MW-21 3 0 CST-A 0 0 CST-B 1 1 4379 4379 Note 1: All results are in pCi/L.

Note 2: A total of 77 samples were analyzed for H-3 in 2015 with 2 positive results.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 28 ATTACHMENT NO. 8 GASEOUS EFFLUENTS - CARBON-14 a) Date: January 01, 2015 - December 31, 2015 b) Location: Elevated Release - Main Stack c) Duration: 365 Days d) Flow rate:

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 2.64E+00 2.67E+00 2.69E+00 2.70E+00 Ci/sec 3.40E-01 3.40E-01 3.40E-01 3.40E-01 h) Resultant Doses: See Addendum 1-Assessment of Radiation Doses to the Public January-December 2015 Table 1D

i) Dose Calculations:

Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Part 2, 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".

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 29 ATTACHMENT NO. 9 EVENTS LEADING TO CONDITIONS WHICH RESULTED IN EXCEEDING RADIOACTIVITY LIMITS.

In accordance with the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Effluent Controls (REC) Section 6.2.9, the report shall contain the events leading to the conditions which resulted in exceeding the radioactivity limits for the specified outdoor radioactive radwaste tanks specified in the Technical Requirements Manual, TRM 3.7.E

The radioactivity limits for the specified outdoor radioactive radwaste tanks were not exceeded.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 30 ADDENDUM 1

ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2015

1. INTRODUCTION The James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Effluent Controls (REC), requires an assessment of the radiation doses to the likely most exposed member of the public due to radioactive liquid and gaseous effluents. This assessment of doses to the likely most exposed member of 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.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 31 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.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 32 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:

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 Specifications 3.4.1.c.1.a and 3.4.1.c.1.b as a result of burning contaminated oil.

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

1. To assure that the requirements of 40 CFR 190 are met.
2. To assure that the requirements of 10 CFR 72.104 are met in accordance with Section 3.2.3, Required Action A.2, Certificate of Compliance 1014 Appendix A, Technical Specifications for the Hi-Storm 100 Cask System.

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 a ny organ except the thyroid which shall be limited to less than or equal to 75 mrem/year.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 33 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 th e 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, 2015 to December 31, 2015. Historical meteorological data was used to generate tables of average dispersion factors. Locations of interest were identified from the 2015 land use census.

These tables are available upon request.

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 th e 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.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 34 ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 2015 A. LIQUIDS QUARTER 1 2 3 4 ANNUAL

(a) (a) (a) (a) (a)

Organ (mrem) 1.37E-05 5.22E-06 8.54E-06 4.87E-06 3.23E-05 % of Limit 2.73E-04 1.04E-04 1.71E-04 9.74E-05 3.23E-04

(b) (b) (b) (b) (b)

Whole Body (mrem) 1.37E-05 5.22E-06 8.54E-06 4.87E-06 3.23E-05 % of Limit 9.11E-04 3.48E-04 5.69E-04 3.25E-04 1.08E-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.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 35 ADDENDUM 1 (continued)

TABLE 1 (cont)

ANNUAL DOSE ASSESSMENT 2015 B. NOBLE GASES QUARTER 1 2 3 4 ANNUAL

Total Body (mrem/yr) 2.16E-02 1.35E-02 1.43E-02 6.12E-03 2.16E-02 % of Limit 4.32E-03 2.70E-03 2.86E-03 1.22E-03 4.32E-03

Skin (mrem/yr) 4.12E-02 2.36E-02 2.59E-02 1.27E-02 4.12E-02 % of Limit 1.37E-03 7.86E-04 8.65E-04 4.23E-04 1.37E-03

Gamma (mrad) 2.66E-04 6.46E-04 3.02E-04 1.61E-04 1.37E-03 % of Limit 5.32E-03 1.29E-02 6.03E-03 3.21E-03 1.37E-02

Beta (mrad) 2.69E-05 5.86E-05 3.00E-05 1.71E-05 1.33E-04 % of Limit 2.69E-04 5.86E-04 3.00E-04 1.71E-04 6.63E-04 C. IODINES AND PARTICULATES QUARTER 1 2 3 4 ANNUAL

(a) (a) (a) (a) (a)

Organ (mrem) 8.84E-04 6.17E-04 2.22E-03 2.67E-03 6.39E-03 % of Limit 1.18E-02 8.23E-03 2.96E-02 3.56E-02 4.26E-02

(a) (a) (a) (a) (a)

Organ Dose Rate 3.07E-04 1.73E-04 4.55E-04 3.17E-04 4.55E-04 (mrem/yr)

% of Limit 2.04E-05 1.15E-05 3.03E-05 2.11E-05 3.03E-05

(a) Dose to the Child Thyroid primarily by the vegetation pathway.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 36 ADDENDUM 1 (continued)

TABLE 1 (cont)

ANNUAL DOSE ASSESSMENT 2015 D. CARBON 14 QUARTER 1 2 3 4 ANNUAL

(a) (a) (a) (a) (a)

Organ (mrem) 8.43E-03 8.52E-03 8.59E-03 8.62E-03 3.42E-02 % of Limit 1.12E-01 1.14E-01 1.14E-01 1.15E-01 2.28E-01

(a)

Organ Dose Rate NA NA NA NA 3.42E-02 (mrem/yr)

% of Limit NA NA NA NA 2.28E-03

(a) Dose to the Child Bone primarily by the vegetation pathway.

  • JAFP-16-0070 April 28, 2016 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001

SUBJECT:

2015 Annual Radioactive Effluent Release Report James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59

Dear Sir or Madam:

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc. James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 315-342-3840 William C Drews Regulatory Assurance Manager -JAF This letter transmits the James A. FitzPatrick Nuclear Power Plant's (JAF) Annual Radioactive Effluent Release Report, for the period of January 1, 2015 through December 31, 2015. The enclosure is submitted in accordance with the reporting requirements of Technical Specification Section 5.6.3 and Technical Requirements Manual Appendix H Offsite Dose Calculation Manual (ODCM) Part 1 Section 6.2 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 2015 calendar year. The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21 Revision 1. There are no new regulatory commitments contained in this letter. If you have any questions concerning the enclosed report, please contact Mr. Michael Ponzo, Chemistry Manager, at (315)349-6168.

Sincerely, {)

William C. Drews Regulatory Assurance Manager -JAF WCD/MP/dc

Enclosure:

cc: next page 2015 Annual Radioactive Effluent Release Report JAFP-16-0070 Page 2 of 2 cc:

USNRC Regional Administrator, Region I

USNRC Resident Inspector

USNRC NRR Project Manager

M. Ponzo (CHEM/JAF)

B. Landers (CHEM/JAF)

K. Stoffle (NMP)

JAFP-16-0070 Enclosure

2015 Annual Radioactive Effluent Release Report (37 Pages)

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

JANUARY 1, 2015 - DECEMBER 31, 2015

DOCKET NO. 50-333 LICENSE NO. DPR-59

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 1 SUPPLEMENTAL INFORMATION

FACILITY: JAFNPP LICENSEE: ENTERGY NUCLEAR OPERATIONS, INC.

1. Offsite Dose Calculation Manual Part 1 Radiological Effluent 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).

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 2 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

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 3 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

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 4 SUPPLEMENTAL INFORMATION (continued)

5. Batch Releases
a. Liquid: Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 4.00E+00 9.00E+00 5.00E+00 8.00E+00

(2) Total time period for batch 4.80E+01 2.45E+02 1.88E+02 1.78E+02 release: (min)

(3) Maximum time period for 3.40E+01 7.20E+01 9.00E+01 5.80E+01 batch release: (min)

(4) Average time period for 1.20E+01 2.72E+01 3.76E+01 2.22E+01 batch release: (min)

(5) Minimum time period for 1.00E+00 3.00E+00 2.00E+00 2.00E+00 batch release: (min)

(6) Total Activity Released (Ci) 1.31E-04 8.27E-04 1.85E-04 2.07E-04

(7) Total Volume Released (liters) 4.13E+03 5.85E+04 8.24E+03 2.75E+04

b. Liquid: Non-Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 6.00E+00 1.10E+01 1.60E+01 2.00E+01

(2) Total time period for batch 2.55E+02 6.73E+02 2.96E+02 6.10E+01 release: (min)

(3) Maximum time period for 2.47E+02 3.89E+02 3.70E+01 7.00E+00 batch release: (min)

(4) Average time period for 4.25E+01 6.12E+01 1.85E+01 3.15E+00 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) 5.89E-03 7.48E-04 5.09E-04 4.69E-05

(7) Total Volume Released (liters) 9.58E+04 2.28E+05 1.12E+05 2.34E+04

c. Gaseous

There were no gaseous batch releases for this report period.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 5 SUPPLEMENTAL INFORMATION (continued)

6. Continuous Releases
a. Liquid: Non-Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases: 1.20E+01 1.40E+01 1.40E+01 1.30E+01

(2) Total Activity Released (Ci) 4.57E-03 6.76E-03 8.37E-03 8.59E-03

(3) Total Volume Released (liters) 3.16E+06 4.61E+06 4.31E+06 5.92E+06

b. Liquid: Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases: 0 0 0 0

(2) Total Activity Released (Ci) N/A N/A N/A N/A

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 6 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 9.07E+00 2.25E+01 1.07E+01 6.14E+00 2.50E+01 2. Average release rate for period Ci/sec 1.17E+00 2.86E+00 1.34E+00 7.73E-01 3. Percentage ODCM Limit % * * *

  • B. IODINE-131 1. Total Iodine-131 Ci 5.41E-05 3.50E-05 1.52E-04 1.82E-04 2.50E+01 2. Average release rate for period Ci/sec 6.96E-06 4.45E-06 1.91E-05 2.28E-05 3. Percentage ODCM Limit % * * *
  • C. PARTICULATES 1. Particulates with half-lives >8 days Ci 4.64E-05 1.15E-06 7.94E-06 5.37E-06 3.60E+01 2. Average release rate for period Ci/sec 5.96E-06 1.47E-07 9.99E-07 6.75E-07 3. Percentage ODCM Limit % * * *
  • 4. Gross alpha radioactivity Ci 3.94E-07 1.84E-07 3.52E-07 3.31E-07 2.50E+01 D. TRITIUM 1. Total Release Ci 3.28E+00 3.69E+00 4.

52E+00 3.77E+00 2.50E+01 2. Average release rate for period Ci/sec 4.22E-01 4.70E-01 5.69E-01 4.74E-01 3. Percentage 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 % 5.32E-03 1.29E-02 6.03E-03 3.21E-03 2. Quarterly beta air dose limit % 2.69E-04 5.86E-04 3.00E-04 1.71E-04
3. Yearly gamma air dose limit % 2.66E-03 6.46E-03 3.02E-03 1.61E-03
4. Yearly beta air dose limit % 1.34E-04 2.93E-04 1.50E-04 8.56E-05
5. Whole body dose rate limit % 4.32E-03 2.70E-03 2.86E-03 1.22E-03
6. Skin dose rate limit % 1.37E-03 7.86E-04 8.65E-04 4.23E-04 HALOGENS, TRITIUM AND PARTICULA TES WITH HALF-LIVES >8 DAYS 7. Quarterly dose limit (organ) % 1.18E-02 8.23E-03 2.96E-02 3.49E-02 8. Yearly dose limit (organ) % 5.89E-03 4.11E-03 1.48E-02 1.75E-02
9. Organ dose rate limit % 2.04E-05 1.15E-05 3.03E-05 2.11E-05 ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 7 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 6.65E+00 1.15E+01 5.61E+00 3.29E+00 Krypton-85 Ci ND ND ND ND Krypton-85m Ci 1.40E+00 3.16E+00 1.40E+00 8.11E-01 Krypton-87 Ci ND ND ND ND Krypton-88 Ci 5.98E-01 4.02E+00 1.24E+00 2.98E-01 Xenon-133 Ci 3.49E-01 3.32E+00 1.25E+00 7.67E-01 Xenon-133m Ci ND ND ND ND Xenon-135 Ci ND ND 2.19E-02 ND Xenon-135m Ci ND ND 1.82E-01 1.89E-01 Xenon-137 Ci ND ND ND ND Xenon-138 Ci ND 4.31E-01 9.38E-01 7.69E-01

TOTAL Ci 9.00E+00 2.24E+01 1.06E+01 6.12E+00

2. Iodines Iodine-131 Ci 3.05E-06 4.07E-06 1.75E-05 1.77E-05 Iodine-132 Ci ND ND ND ND Iodine-133 Ci 2.68E-05 2.47E-05 7.34E-05 6.30E-05 Iodine-135 Ci ND ND ND ND TOTAL Ci 2.98E-05 2.88E-05 9.09E-05 8.07E-05
3. Particulates Cobalt-60 Ci ND ND ND ND Cesium-137 Ci ND ND ND ND Manganese-54 Ci ND ND ND ND Strontium-89 Ci 3.80E-07 1.15E-06 2.61E-06 3.47E-06 Zinc-65 Ci ND ND ND ND

TOTAL Ci 3.80E-07 1.15E-06 2.61E-06 3.47E-06

4. Tritium Hydrogen-3 Ci 2.39E-01 2.25E-01 4.06E-01 3.41E-01 Note: There were no batch releases for this report period.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 8 TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED

1. Fission Gases UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Argon-41 Ci ND ND ND ND Krypton-85 Ci ND ND ND ND Krypton-85m Ci ND ND ND ND Krypton-87 Ci ND ND ND ND Krypton-88 Ci ND ND ND ND Xenon-133 Ci 2.04E-02 8.66E-03 9.72E-03 9.63E-03 Xenon-133m Ci ND ND ND ND Xenon-135 Ci 4.44E-02 3.71E-02 2.73E-02 1.02E-02 Xenon-135m Ci 1.17E-02 1.51E-02 1.68E-02 2.21E-03 Xenon-137 Ci ND ND ND ND Xenon-138 Ci ND ND ND ND

TOTAL Ci 7.65E-02 6.09E-02 5.39E-02 2.21E-02

2. Iodines Iodine-131 Ci 5.11E-05 3.09E-05 1.34E-04 1.64E-04 Iodine-132 Ci ND ND 1.1 9E-04 ND Iodine-133 Ci 4.48E-04 3.13E-04 1.03E-03 1.23E-03 Iodine-135 Ci ND ND 3.8 9E-04 ND

TOTAL Ci 4.99E-04 3.44E-04 1.67E-03 1.39E-03

3. Particulates Silver-110M Ci ND ND ND ND Cobalt-58 Ci ND ND ND ND Cobalt-60 Ci ND ND 1.59E-06 1.90E-06 Manganese-54 Ci ND ND 2.02E-06 ND Selenium-75 Ci ND ND ND ND Strontium-89 Ci 4.38E-05 ND ND ND Zinc-65 Ci 2.13E-06 ND 1.72E-06 ND

TOTAL Ci 4.60E-05 ND 5.33E-06 1.90E-06

4. Tritium Hydrogen-3 Ci 3.04E+00 3.47E+00 4.11E+

00 3.43E+00 Note: There were no batch releases for this report period.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 9 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 ND ND ND ND NA

2. Average diluted concentration during period Ci/ml ND ND ND ND 3. Percentage ODCM Limit  % NA NA NA NA

B. TRITIUM 1. Total Release Ci 1.06E-02 8.33E-03 9.06E-03 8.84E-03 2.50E+01 2. Average diluted concentration during period (Note 1) Ci/ml 3.20E-06 1.53E-06 2.01E-06 1.45E-06 3. Percentage ODCM Limit  % * * *

  • C. DISSOLVED AND ENTRAINED GASES 1. Total Release Ci ND ND ND ND NA
2. Average diluted concentration during period Ci/ml ND ND ND ND
3. Percentage ODCM Limit % NA NA NA NA

D. GROSS ALPHA RADIOACTIVITY 1. Total Release Ci ND ND ND 2.39E-07 4.20E+01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) liters 3.26E+06 4.89E+06 4.43E+06 5.97E+06 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 7.07E+07 3.79E+08 3.04E+08 2.87E+08 G. PERCENT OF APPLICABLE ODCM LIMITS 1. Quarterly Whole Body Dose % 9.11E-04 3.48E-04 5.69E-04 3.25E-04 2. Quarterly Organ Dose % 2.73E-04 1.04E-04 1.71E-04 9.74E-05

3. Annual Whole Body Dose % 4.55E-04 1.74E-04 2.85E-04 1.62E-04
4. Annual Organ Dose % 1.37E-04 5.22E-05 8.54E-05 4.87E-05

Note 1: Concentration includes summation from diluted and undiluted values from Canal and Non-Canal releases (Table 2B).

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 10 TABLE 2B LIQUID EFFLUENTS CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4

1. Fission and Activation Products

ND Ci ND ND ND ND

2. Tritium Hydrogen-3 Ci 1.31E-04 8.27E-04 1.85E-04 2.07E-04
3. Dissolved and Entrained Gases

ND Ci ND ND ND ND

TABLE 2B LIQUID EFFLUENTS CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4

1. Fission and Activation Products

ND Ci ND ND ND ND

2. Tritium Hydrogen-3 Ci ND ND ND ND
3. Dissolved and Entrained Gases

ND Ci ND ND ND ND

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 11 TABLE 2B (SUPPLEMENT)

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

1. Fission and Activation Products

ND Ci ND ND ND ND

2. Tritium Hydrogen-3 Ci 4.57E-03 6.76E-03 8.37E-03 8.59E-03
3. Dissolved and Entrained Gases ND Ci ND ND ND ND

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 12 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

ND Ci ND ND ND ND

2. Tritium Hydrogen-3 Ci 5.89E-03 7.48E-04 5.09E-04 4.69E-05
3. Dissolved and Entrained Gases ND Ci ND ND ND ND

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 13 TABLE 2B (continued)

ABNORMAL RELEASE LIQUID EFFLUENTS CANAL CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4

1. Fission and Activation Products ND Ci ND ND ND ND
2. Tritium ND Ci ND ND ND ND
3. Dissolved and Entrained Gases ND Ci ND ND ND ND

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 14 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 6.51E+01 0.00E+00 0.00E+00 evaporator bottoms, etc. Ci 6.05E+01 0.00E+00 0.00E+00 1.00E+01
b. Dry compressible waste, m 3 3.62E+02 0.00E+00 0.00E+00 contaminated equipment, etc. Ci 1.16E+00 0.00E+

00 0.00E+00 1.00E+01

c. Irradiated components, m 3 4.96E+00 0.00E+00 3.58E-01 control rods, etc. Ci 2.28E-01 0.00E+00 2.86E+04 1.00E+01
d. Other: Dry compressible m 3 7.14E+00 0.00E+00 0.00E+00 waste, contaminated equipment, Ci 3.25E-02 0.00E+

00 0.00E+00 1.00E+01 spent resins for volume reduction.

2. Estimate of Major Nuclide Composition (by type of waste)
a. Spent resins, filter sludges, evaporator bottoms, etc.

Isotope Percent Curies Isotope Percent Curies Ce-144 9.00E-02 5.16E-02 E Co-58 7.00E-02 4.33E-02 E Co-60 3.67E+01 2.23E+01 E Fe-59 1.00E-02 3.89E-03 E Cs-137 5.20E-01 3.16E-01 E Fe-55 1.41E+01 8.53E+00 E C-14 2.10E-01 1.28E-01 E Mn-54 2.02E+01 1.22E+01 E Ni-63 7.10E-01 4.28E-01 E Tc-99 4.00E-02 2.18E-02 E Zn-65 2.71E+01 1.64E+01 E H-3 2.00E-01 1.19E-01 E Sb-125 1.50E-01 9.23E-02 E

(E- Estimated M- Measured)

b. Dry compressible waste, contaminated equipment, etc.

Isotope Percent Curies Isotope Percent Curies

Ce-144 1.00E-02 2.88E-04 E Co-58 2.00E-02 1.18E-03 E Co-60 2.62E+00 1.45E-01 E Fe-59 6.00E-02 3.21E-03 E Cs-137 3.10E-01 1.71E-02 E Fe-55 1.36E+01 7.52E-01 E C-14 2.76E+01 1.53E+00 E Mn-54 1.15E+00 6.34E-02 E Ni-63 6.10E-01 3.37E-02 E I-129 7.90E-01 4.37E-02 E Zn-65 2.03E+00 1.12E-01 E H-3 4.11E+01 2.27E+00 E Sb-124 1.00E-02 7.92E-04 E Tc-99 1.01E+01 5.59E-01 E Sb-125 1.00E-02 5.53E-04 E Cr-51 5.00E-02 3.04E-03 E

(E- Estimated M- Measured)

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 15 TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

c. Irradiated components, control rods, etc.

Isotope Percent Curies Isotope Percent Curies C-14 1.00E-02 1.76E+00 E Co-58 5.00E-02 1.43E+01 E Co-60 6.01E+01 1.72E+04 E Zn-65 2.00E-02 5.74E+00 E Ni-59 7.00E-02 1.96E+01 E Fe-55 3.47E+01 9.92E+03 E Ni-63 4.19E+00 1.20E+03 E Mn-54 8.60E-01 2.46E+02 E

(E- Estimated M- Measured)

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

Isotope Percent Curies Isotope Percent Curies H-3 9.98E+01 3.25E-02 E Cs-137 4.00E-02 1.25E-05 E Fe-55 1.00E-01 3.33E-05 E Co-60 1.00E-02 2.77E-06 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.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 16 TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition No. of Shipments Mode of Transportation Destination

19 Trucks *Energy Solutions Oak Ridge, TN

3 Trucks *Energy Solutions Kingston, TN

2 Trucks *Energy Solutions Oak Ridge, TN

3 Trucks Waste Control Specialists, LLC Andrews, TX

1 Truck *Energy Solutions Oak Ridge, TN

1 Truck *Energy Solutions Oak Ridge, TN

  • Volume Reduction Facility

B. IRRADIATED FUEL SHIPMENTS (Disposition)

No. of Shipments Mode of Transportation Destination

None ----------- ---------------

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 17 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 (36.2 m 3) STC 9 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 96 ft 3 (2.72 m 3) STC 12 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 1033 ft 3 (29.3 m 3) STC 4 Contaminated Equipment, etc.

Spent Resins, Filter Sludges, evaporator Air Drying 205.8 ft 3 (5.83 m 3) HIC 14 Bottoms, etc. Non-compacted

Spent Resins, Filter Sludges, evaporator Air Drying 120.3 ft 3 (3.41 m 3) HIC 2 Bottoms, etc. Non-compacted

Contaminated Oil/Water. Non-compacted 1280 ft 3 (36.2 m 3) STC 1

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

Irradiated Hardware Non-compacted 58 ft 3 (1.64 m 3) HIC 3

HIC- High Integrity Container STC- Strong Tight Container ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 18 ATTACHMENT NO. 1 CHANGES TO THE OFFSITE DO SE CALCULATION MANUAL (ODCM)

In accordance with the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Effluent 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 made to the ODCM during this reporting period.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 19 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 Effluent 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.

EN-RW-105 Process Control Program Revision 5 became Headquarters effective 8/27/15. There were no changes to the James A. FitzPatrick Process Control Program (PCP) as a result of Revision 5. EN-RW-105 Process Control Program Revision 5 incorporates a temporary change for an Entergy Site.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 20 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, Radiological Effluent Controls (REC) 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.

There was one new milk location identified in the land use census, consisting of 20 milking cows and 15 heifers. The location is at address 6729 State Route 3 in the town of Richland. This location is outside the five-mile radius of the plant.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 21 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, Radiological Effluent Controls (REC) 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:

01/10/2015 - 01/14/2015 Air Station R-5 Offsite sample pump was inoperable for approximately 108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br />. Out of service time was determined based upon sample pump run time integrator. The inoperability was due to loss of power to the sample station. No corrective actions were required to restore power to the air station.

03/02/2015 - 03/10/2015 Air Station R-1 Offsite sample pump was inoperable for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Out of service time was determined based upon sample pump run time integrator. The inoperability was due to loss of power to the sample station. No corrective actions were required to restore power to the air station.

03/02/2015 - 03/10/2015 Air Station R-2 Offsite sample pump was inoperable for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Out of service time was determined based upon sample pump run time integrator. The inoperability was due to loss of power to the sample station. No corrective actions were required to

restore power to the air station.

10/27/2015 - 11/03/2015 Air Station R-2 Offsite sample pump was inoperable for approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. Out of service time was determined based upon sample pump run time integrator. The inoperability was due to loss of power to the sample station. No corrective actions were required to restore power to the air station.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 22 10/27/2015 - 11/03/2015 Air Station R-3 Offsite sample pump was inoperable for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Out of service time was determined based upon sample pump run time integrator. The inoperability was due to loss of power to the sample station. No corrective actions were required to restore power to the air station.

10/27/2015 - 11/03/2015 Air Station R-4 Offsite sample pump was inoperable for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Out of service time was determined based upon sample pump run time integrator. The inoperability was due to loss of power to the sample station. No corrective actions were required to restore power to the air station.

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 43,670 hours0.00775 days <br />0.186 hours <br />0.00111 weeks <br />2.54935e-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 99.7%.

Air sampling equipment found inoperable was returned to service. Identification of locations for obtaining replacement samples was not required.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 23 ATTACHMENT NO. 5 ANNUAL

SUMMARY

OF HOURLY METEOROLOGICAL DATA The James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1, Radiological Effluent 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.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 24 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 Effluent 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.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 25 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. In August 2013, 3 additional wells and 2 piezometers were installed on site.

All samples collected were analyzed for tritium and gamma emitting radionuclides. The detection limits and results are reported in the following tables. Analysis results of tritium ranged from non-detectable, a minimum positive indication of 1149 pCi/L, and a maximum concentration of 4379 pCi/L for a CST-B sample from 11/04/15. 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. 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. 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).

In conclusion, the only radionuclide detected in groundwater during the 2015 monitoring effort that is attributable to James A. FitzPatrick operations is tritium, and all concentrations were below any reporting criteria.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 26 ATTACHMENT NO. 7 (continued)

ONSITE GROUNDWATER MONITORING A) Gamma Isotopic Monitoring For 2015, the 24 monitoring wells were samp led quarterly, providing enough water was present, and analyzed below the required lower limits of detection in accordance with the Offsite Dose Calculation Manual (ODCM) Part 1, Table 5.1-3.

Radionuclide LLD Value (pCi/L) Radionuclide LLD Value (pCi/L) Tritium (H-3) 3000 Zirconium-95 15 Manganese-54 15 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 gamma emitting nuclides detected in the samples. Gross Beta and Hard to Detect nuclide analysis not required.

Per Note 2 on page 27, 2 groundwater monitoring samples detected tritium (H-3). One of the 2 sample results was greater than the LLD value of 3,000 pCi/L for H-3.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 27 ATTACHMENT NO. 7 (continued)

ONSITE GROUNDWATER MONITORING B) Tritium Summary Well Name # Samples in 2015 # Positive Samples in 2015 Minimum Positive Concentration Maximum Positive Concentration MW-1A 3 0 MW-1B 1 0 MW-2A 4 0 MW-2B 4 0 MW-3A 4 0 MW-3B 4 1 1149 1149 MW-4A 3 0 MW-4B 3 0 MW-5 4 0 MW-6 4 0 MW-7 4 0 MW-8 3 0 MW-9 3 0 MW-10A 4 0 MW-10B 4 0 MW-13 4 0 MW-14 3 0 MW-15 4 0 MW-16 3 0 MW-19 4 0 MW-20 3 0 MW-21 3 0 CST-A 0 0 CST-B 1 1 4379 4379 Note 1: All results are in pCi/L.

Note 2: A total of 77 samples were analyzed for H-3 in 2015 with 2 positive results.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 28 ATTACHMENT NO. 8 GASEOUS EFFLUENTS - CARBON-14 a) Date: January 01, 2015 - December 31, 2015 b) Location: Elevated Release - Main Stack c) Duration: 365 Days d) Flow rate:

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 2.64E+00 2.67E+00 2.69E+00 2.70E+00 Ci/sec 3.40E-01 3.40E-01 3.40E-01 3.40E-01 h) Resultant Doses: See Addendum 1-Assessment of Radiation Doses to the Public January-December 2015 Table 1D

i) Dose Calculations:

Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Part 2, 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".

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 29 ATTACHMENT NO. 9 EVENTS LEADING TO CONDITIONS WHICH RESULTED IN EXCEEDING RADIOACTIVITY LIMITS.

In accordance with the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Effluent Controls (REC) Section 6.2.9, the report shall contain the events leading to the conditions which resulted in exceeding the radioactivity limits for the specified outdoor radioactive radwaste tanks specified in the Technical Requirements Manual, TRM 3.7.E

The radioactivity limits for the specified outdoor radioactive radwaste tanks were not exceeded.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 30 ADDENDUM 1

ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2015

1. INTRODUCTION The James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Effluent Controls (REC), requires an assessment of the radiation doses to the likely most exposed member of the public due to radioactive liquid and gaseous effluents. This assessment of doses to the likely most exposed member of 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.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 31 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.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 32 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:

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 Specifications 3.4.1.c.1.a and 3.4.1.c.1.b as a result of burning contaminated oil.

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

1. To assure that the requirements of 40 CFR 190 are met.
2. To assure that the requirements of 10 CFR 72.104 are met in accordance with Section 3.2.3, Required Action A.2, Certificate of Compliance 1014 Appendix A, Technical Specifications for the Hi-Storm 100 Cask System.

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 a ny organ except the thyroid which shall be limited to less than or equal to 75 mrem/year.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 33 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 th e 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, 2015 to December 31, 2015. Historical meteorological data was used to generate tables of average dispersion factors. Locations of interest were identified from the 2015 land use census.

These tables are available upon request.

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 th e 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.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 34 ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 2015 A. LIQUIDS QUARTER 1 2 3 4 ANNUAL

(a) (a) (a) (a) (a)

Organ (mrem) 1.37E-05 5.22E-06 8.54E-06 4.87E-06 3.23E-05 % of Limit 2.73E-04 1.04E-04 1.71E-04 9.74E-05 3.23E-04

(b) (b) (b) (b) (b)

Whole Body (mrem) 1.37E-05 5.22E-06 8.54E-06 4.87E-06 3.23E-05 % of Limit 9.11E-04 3.48E-04 5.69E-04 3.25E-04 1.08E-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.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 35 ADDENDUM 1 (continued)

TABLE 1 (cont)

ANNUAL DOSE ASSESSMENT 2015 B. NOBLE GASES QUARTER 1 2 3 4 ANNUAL

Total Body (mrem/yr) 2.16E-02 1.35E-02 1.43E-02 6.12E-03 2.16E-02 % of Limit 4.32E-03 2.70E-03 2.86E-03 1.22E-03 4.32E-03

Skin (mrem/yr) 4.12E-02 2.36E-02 2.59E-02 1.27E-02 4.12E-02 % of Limit 1.37E-03 7.86E-04 8.65E-04 4.23E-04 1.37E-03

Gamma (mrad) 2.66E-04 6.46E-04 3.02E-04 1.61E-04 1.37E-03 % of Limit 5.32E-03 1.29E-02 6.03E-03 3.21E-03 1.37E-02

Beta (mrad) 2.69E-05 5.86E-05 3.00E-05 1.71E-05 1.33E-04 % of Limit 2.69E-04 5.86E-04 3.00E-04 1.71E-04 6.63E-04 C. IODINES AND PARTICULATES QUARTER 1 2 3 4 ANNUAL

(a) (a) (a) (a) (a)

Organ (mrem) 8.84E-04 6.17E-04 2.22E-03 2.67E-03 6.39E-03 % of Limit 1.18E-02 8.23E-03 2.96E-02 3.56E-02 4.26E-02

(a) (a) (a) (a) (a)

Organ Dose Rate 3.07E-04 1.73E-04 4.55E-04 3.17E-04 4.55E-04 (mrem/yr)

% of Limit 2.04E-05 1.15E-05 3.03E-05 2.11E-05 3.03E-05

(a) Dose to the Child Thyroid primarily by the vegetation pathway.

ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2015 - DECEMBER 2015 36 ADDENDUM 1 (continued)

TABLE 1 (cont)

ANNUAL DOSE ASSESSMENT 2015 D. CARBON 14 QUARTER 1 2 3 4 ANNUAL

(a) (a) (a) (a) (a)

Organ (mrem) 8.43E-03 8.52E-03 8.59E-03 8.62E-03 3.42E-02 % of Limit 1.12E-01 1.14E-01 1.14E-01 1.15E-01 2.28E-01

(a)

Organ Dose Rate NA NA NA NA 3.42E-02 (mrem/yr)

% of Limit NA NA NA NA 2.28E-03

(a) Dose to the Child Bone primarily by the vegetation pathway.

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