JAFP-14-0051, 2013 Annual Radioactive Effluent Release Report

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2013 Annual Radioactive Effluent Release Report
ML14119A359
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/29/2014
From: Adner C
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-14-0051
Download: ML14119A359 (46)
v • d • e


Text

Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Lawrence M. Coyle Site Vice President - JAF JAFP-1 4-005 1 April 29, 2014 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001

SUBJECT:

2013 Annual Radioactive Effluent Release Report James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59

Dear Sir or Madam:

This letter transmits the James A. FitzPatrick Nuclear Power Plants (JAF) Annual Radioactive Effluent Release Report, for the period of January 1, 2013 through December 31, 2013. The enclosure is submitted in accordance with the Reporting Requirements of the Technical Specifications, Section 5.6.3 and Appendix H of the Technical Requirements Manual, Offsite Dose Calculation Manual (ODCM), Part 1 Section 6.2, 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 2013 calendar year. The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1. Distribution is in accordance with Regulatory Guide 10.1, Revision 4.

There are no commitments contained in this letter.

If you have any questions concerning the enclosed report, please contact Mr. Robert Heath, Chemistry Manager, at (315)349-6635.

Chris M. Adner Regulatory Assurance Manager JAF -

CMA/RH/ds

Enclosure:

Annual Radioactive Effluent Release Report, January 1 December 31, 2013 cc: next page

JAFP-14-0051 Page 2 of 2 cc:

Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Resident Inspectors Office U.S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093 Mr. Douglas Pickett, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8-C2A Washington, DC 20555-0001 R. Heath (CHEM/JAF)

B. Landers (CHEM/JAF)

K. Stoffle (NMP)

Document Contents:

001 Transmittal Letter, JAFP-14-0051 with enclosure

JAFP-14-0051 Enclosure 2013 Annual Radioactive Effluent Release Report (43 Pages)

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2013 - DECEMBER 31, 2013 DOCKET NO. 50-333 LICENSE NO. DPR-59

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 SUPPLEMENTAL INFORMATION FACILITY: JAFNPP LICENSEE: ENTERGY NUCLEAR OPERATIONS, INC.

1. Offsite Dose Calculation Manual Part 1 Radiological Controls
a. Fission and Activation Gases:

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

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

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

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

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

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

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

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

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

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

1

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 SUPPLEMENTAL INFORMATION (continued)

c. Liquid Effluents:

(1) The concentration of radioactive materials released to the unrestricted areas shall not exceed ten times the values specified in 10 CFR 20.1001-20.2402, Appendix B, Table 2, column 2. For dissolved or entrained noble gases the concentration shall be limited to 2.00E-04 Ci/ml.

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

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

2. 10X Effluent Concentrations
a. Fission and activation gases: (None specified)
b. Iodines: (None specified)
c. Particulates, half-lives >8 days: (None specified)
d. Liquid effluents: Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Fission and activation None None None None products (mixture EC)

( Ci/ml)

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

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 SUPPLEMENTAL INFORMATION (continued)

3. Average Energy (None specified)
4. Measurements and Approximations of Total Radioactivity
a. Fission and Activation Gases: Continuous monitor on each release path calibrated to a marinelli grab sample analyzed by gamma spectroscopy; bubbler grab sample analyzed for Tritium.
b. Iodines: Gamma spectral analysis of charcoal cartridge and particulate filter on each release path.
c. Particulates: Gamma spectral analysis of each particulate filter and charcoal cartridge for each release path. A four week per quarter composite of particulate filters for each release path for Strontium-89 and Strontium-90. One week per month particulate filter for each release path for gross alpha.
d. Liquid Effluents: Gamma spectral analysis of each batch discharged, except composite analysis for Strontium-89, Strontium-90, Iron-55, Tritium, and Alpha.
e. Solid Waste: Gamma spectral analysis of a representative sample of each waste shipment. Scaling factors established from off-site composite sample analyses to estimate concentration of non-gamma emitters. Low activity trash shipments curie content is estimated by dose rate measurement and application of appropriate scaling factors.
f. Error Estimation Method: Overall error for sampling and analysis estimated by combining individual errors using error propagation methods. This process is composed of determinate and undeterminate errors.

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

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 SUPPLEMENTAL INFORMATION (continued)

5. Batch Releases
a. Liquid: Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 3.00E+00 2.00E+00 3.00E+00 4.00E+00 (2) Total time period for batch 1.84E+02 1.40E+02 1.66E+02 1.90E+02 release: (min)

(3) Maximum time period for 7.00E+01 8.00E+01 7.40E+01 7.20E+01 batch release: (min)

(4) Average time period for 6.13E+01 7.00E+01 5.53E+01 4.75E+01 batch release: (min)

(5) Minimum time period for 5.00E+01 6.00E+01 3.00E+01 1.00E+00 batch release: (min)

(6) Total Activity Released (Ci) 5.02E-06 2.27E-06 1.72E-06 2.40E-06 (7) Total Volume Released (liters) 2.32E+03 1.44E+03 1.66E+03 2.93E+03

b. Liquid: Non-Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 8.00E+00 9.00E+00 1.10E+01 7.00E+00 (2) Total time period for batch 1.26E+03 1.16E+03 5.92E+02 6.99E+03 release: (min)

(3) Maximum time period for 4.87E+02 5.91E+02 2.80E+02 2.57E+03 batch release: (min)

(4) Average time period for 1.58E+02 1.29E+02 5.38E+01 9.98E+02 batch release: (min)

(5) Minimum time period for 1.00E+00 1.00E+00 7.00E+00 1.60E+01 batch release: (min)

(6) Total Activity Released (Ci) 9.02E-04 1.06E-03 5.46E-04 4.03E-03 (7) Total Volume Released (liters) 4.77E+05 4.38E+05 2.25E+05 2.65E+06

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

4

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 SUPPLEMENTAL INFORMATION (continued)

6. Continuous Releases
a. Liquid: Non-Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases: 2.60E+01 2.50E+01 2.80E+01 2.40E+01 (2) Total Activity Released (Ci) 6.39E-02 1.39E-02 1.08E-02 1.15E-02 (3) Total Volume Released (liters) 1.57E+07 5.23E+06 4.92E+06 7.67E+05
b. Liquid: Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases: 8.00E+00 3.00E+00 0 0 (2) Total Activity Released (Ci) 7.96E-04 1.61E-05 NA NA 5

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES EST TOTAL UNIT QTR 1 QTR 2 QTR 3 QTR 4 ERROR %

A. FISSION AND ACTIVATION GASES

1. Total Release Ci 1.00E+01 1.45E+01 1.14E+01 2.52E+01 2.50E+01
2. Average release rate for period Ci/sec 1.28E+00 1.84E+00 1.44E+00 3.17E+00
3. Applicable ODCM Limit  % * * *
1. Total Iodine-131 Ci 3.37E-05 6.83E-05 9.62E-05 1.39E-04 2.50E+01
2. Average release rate for period Ci/sec 4.28E-06 8.68E-06 1.21E-05 1.75E-05
3. Applicable ODCM Limit  % * * *
  • C. PARTICULATES
1. Particulates with half-lives >8 days Ci 3.20E-05 1.22E-06 7.72E-07 4.65E-07 3.60E+01
2. Average release rate for period Ci/sec 4.07E-06 1.56E-07 9.71E-08 5.85E-08
3. Applicable ODCM Limit  % * * * *
4. Gross alpha radioactivity Ci 3.28E-07 1.67E-07 3.81E-07 2.29E-07 2.50E+01 D. TRITIUM
1. Total Release Ci 3.10E+00 4.76E+00 6.68E+00 7.54E+00 2.50E+01
2. Average release rate for period Ci/sec 4.17E-08 2.13E-08 4.79E-08 2.88E-08
3. Applicable ODCM Limit  % * * *
  • F. PERCENT OF APPLICABLE ODCM LIMITS FISSION AND ACTIVATION GASES UNIT QTR 1 QTR 2 QTR 3 QTR 4
1. Quarterly gamma air dose limit  % 5.47E-03 7.48E-03 5.76E-03 1.32E-02
2. Quarterly beta air dose limit  % 7.54E-04 1.14E-03 7.77E-04 2.09E-03
3. Yearly gamma air dose limit  % 2.73E-03 3.74E-03 2.88E-03 6.58E-03
4. Yearly beta air dose limit  % 1.88E-04 2.85E-04 1.94E-04 5.23E-04
5. Whole body dose rate limit  % 4.09E-03 6.51E-03 9.48E-03 8.20E-03
6. Skin dose rate limit  % 8.78E-04 1.41E-03 2.06E-03 1.78E-03 HALOGENS, TRITIUM AND PARTICULATES WITH HALF-LIVES >8 DAYS
7. Quarterly dose limit (organ)  % 7.17E-03 1.43E-02 2.06E-02 2.84E-02
8. Yearly dose limit (organ)  % 3.59E-03 7.13E-03 1.03E-02 1.42E-02
9. Organ dose rate limit  % 1.42E-05 1.63E-05 2.55E-05 2.51E-05 6

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 TABLE 1B GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODE NUCLIDES RELEASED

1. Fission Gases UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Argon-41 Ci 3.54E+00 2.81E+00 3.45E+00 2.76E+00 Krypton-85m Ci 6.96E-01 6.87E-01 1.22E+00 8.64E-01 Krypton-87 Ci 9.58E-01 1.08E+00 4.98E-01 1.94E+00 Krypton-88 Ci 6.69E-01 6.32E-01 5.77E-01 8.81E-01 Xenon-133 Ci 1.18E-01 2.17E-01 8.63E-01 9.24E-02 Xenon-135 Ci 1.14E+00 1.48E+00 5.05E-01 2.00E+00 Xenon-135m Ci 6.64E-01 1.72E+00 9.80E-01 3.72E+00 Xenon-137 Ci ND 4.41E-01 2.65E-01 1.07E+00 Xenon-138 Ci 2.20E+00 5.36E+00 3.09E+00 1.18E+01 TOTAL Ci 9.98E+00 1.44E+01 1.14E+01 2.52E+01
2. Iodines Iodine-131 Ci 8.07E-06 1.03E-05 7.55E-06 1.63E-05 Iodine-132 Ci ND ND ND ND Iodine-133 Ci 1.79E-05 9.52E-06 5.73E-05 9.25E-04 Iodine-135 Ci 4.76E-05 ND 4.08E-05 ND TOTAL Ci 7.35E-05 1.98E-05 1.06E-04 1.09E-04
3. Particulates Cesium-137 Ci ND ND ND 2.74E-07 Manganese-54 Ci 1.30E-07 ND ND ND Strontium-89 Ci 7.93E-07 1.22E-06 7.72E-07 1.92E-07 TOTAL Ci 9.23E-07 1.22E-06 7.72E-07 4.65E-07
4. Tritium Hydrogen-3 Ci 5.08E-01 4.39E-01 5.94E-01 9.69E-01 Note: There were no batch releases for this report period.

7

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED

1. Fission Gases UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 TOTAL Ci ND ND ND ND
2. Iodines Iodine-131 Ci 2.56E-05 5.79E-05 8.86E-05 1.23E-04 Iodine-133 Ci 2.10E-04 4.75E-04 6.30E-04 9.04E-04 TOTAL Ci 2.36E-04 5.33E-04 7.19E-04 1.03E-03
3. Particulates Cobalt-58 Ci 6.10E-06 ND ND ND Cobalt-60 Ci 2.57E-06 ND ND ND Manganese-54 Ci 6.57E-06 ND ND ND Selenium-75 Ci 1.86E-06 ND ND ND Zinc-65 Ci 1.39E-05 ND ND ND TOTAL Ci 3.10E-05 ND ND ND
4. Tritium Hydrogen-3 Ci 2.59E+00 4.32E+00 6.09E+00 6.57E+00 8

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES BATCH MODE NUCLIDES RELEASED

1. Fission Gases UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Xenon-133 Ci 3.02E-02 1.22E-02 ND ND Xenon-135 Ci 2.07E-02 1.19E-02 ND ND Xenon-135M Ci 6.29E-04 3.36E-03 ND ND TOTAL Ci 5.16E-02 2.74E-02 ND ND
2. Iodines TOTAL Ci ND ND ND ND
3. Particulates TOTAL Ci ND ND ND ND
4. Tritium Hydrogen-3 Ci ND ND ND ND 9

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 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. Applicable ODCM Limit  % NA NA NA NA B. TRITIUM
1. Total Release Ci 6.56E-02 1.50E-02 1.14E-02 1.55E-02 2.50E+01
2. Average diluted concentration during period (Note 1) Ci/ml 3.95E-06 2.72E-06 2.34E-05 1.52E-06
3. Applicable 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. Applicable ODCM Limit  % NA NA NA NA D. GROSS ALPHA RADIOACTIVITY
1. Total Release Ci ND ND ND ND NA E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) liters 1.64+07 5.50E+06 4.84E+06 1.02E+07 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 4.29E+10 1.02E+10 2.55E+08 2.76E+08 G. PERCENT OF APPLICABLE ODCM LIMITS
1. Quarterly Whole Body Dose  % 4.69E-04 2.80E-04 2.73E-04 5.56E-05
2. Quarterly Organ Dose  % 1.41E-04 8.39E-05 8.19E-05 1.69E-05
3. Annual Whole Body Dose  % 2.35E-04 1.40E-04 1.37E-04 2.82E-05
4. Annual Organ Dose  % 7.04E-05 4.20E-05 4.10E-05 8.47E-06 Note 1: Concentration includes summation from diluted and undiluted values from Canal and Non-Canal releases (Table 2B).

10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 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 5.02E-06 2.27E-06 1.72E-06 2.40E-06
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 7.96E-04 1.61E-05 ND ND
3. Dissolved and Entrained Gases ND Ci ND ND ND ND 11

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 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 6.39E-02 1.39E-02 1.08E-02 1.15E-02
3. Dissolved and Entrained Gases ND Ci ND ND ND ND 12

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 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 9.02-04 1.06E-03 5.46E-04 4.03E-03
3. Dissolved and Entrained Gases ND Ci ND ND ND ND 13

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 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 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 TABLE 3A SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

EST. TOTAL

1. Type of Waste UNIT CLASS A CLASS B CLASS C ERROR %
a. Spent resins, filter sludges, m^3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 evaporator bottoms, etc. Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
b. Dry compressible waste, m^3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 contaminated equipment, etc. Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
c. Irradiated components, m^3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 control rods, etc. Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
d. Other: Dry compressible m^3 3.41E+02 1.13E+01 0.00E+00 2.50E+01 waste, contaminated equipment, Ci 2.37E+01 4.36E+02 0.00E+00 2.50E+01 spent resins for volume reduction.
2. Estimate of Major Nuclide Composition (by type of waste)
a. Spent resins, filter sludges, evaporator bottoms, etc.

None

b. Dry compressible waste, contaminated equipment, etc.

None

c. Irradiated components, control rods, etc.

None

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

Isotope Percent Curies Isotope Percent Curies H-3 5.20E-2 1.22E-01 E C-14 5.33E-01 1.26E+00 E Cr-51 1.40E-2 3.35E-02 E Mn-54 5.33E+00 1.26E+01 E Fe-55 5.06E+01 1.20E+02 E Fe-59 3.40E-02 8.02E-02 E Co-58 1.01E-01 2.38E-01 E Co-60 1.93E+01 4.56E+01 E Ni-63 2.49E+00 5.91E+00 E Zn-65 1.86E+01 4.39E+01 E Sr-89 1.80E-02 4.22E-02 E Sr-90 8.90E-01 2.10E-01 E Sb-124 7.00E-03 1.73E-02 E Sb-125 1.00E-02 2.44E-02 E Cs-134 1.77E-01 4.19E-01 E Cs-137 2.75E+00 6.50E+00 E Ce-144 1.00E-03 1.90E-03 E (E- Estimated M- Measured)

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

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition No. of Shipments Mode of Transportation Destination 26 Truck *Energy Solutions Oak Ridge, TN 11 Truck *Barnwell Processing Barnwell, SC 1 Truck *Perma-Fix of Florida, INC Gainesville, FL 1 Truck *TOXCO, Inc.

Oak Ridge, TN

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

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

16

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 TABLE 3B SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. NRC CLASS A SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Dry compressible Waste (DAW), Non-compacted 1280 ft^3 STC 7 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 96 ft^3 STC 11 Contaminated Equipment, etc.

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

Spent Resins, Filter Sludges, evaporator Air Drying 205.8 ft^3 HIC 17 Bottoms, etc. Non-compacted Spent Resins, Filter Sludges, evaporator Air Drying 120.3 ft^3 HIC 12 Bottoms, etc. Non-compacted Spent Resins, Filter Sludges, evaporator Air Drying 170.8 ft^3 HIC 5 Bottoms, etc. Non-compacted Dry compressible Waste (DAW), Non-compacted 17.9 ft^3 STC 2 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 7.5 ft^3 STC 6 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 4.1 ft^3 STC 1 Contaminated Equipment, etc.

17

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 TABLE 3B SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)

A. NRC CLASS A (Continued)

SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Dry compressible Waste (DAW), Non-compacted 1.64 ft^3 STC 1 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 0.7 ft^3 STC 3 Contaminated Equipment, etc.

B. NRC CLASS B SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS None C. NRC CLASS C SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS None HIC- High Integrity Container STC- Strong Tight Container 18

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ATTACHMENT NO. 1 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

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

REV CHANGE AND REASON FOR CHANGE 12 1. Cover Sheet Updated the use class from Informational Use to Reference Use in compliance with EN-AD-102 (which has been superseded by EN-HU-106). This change increases the accuracy of the ODCM.

2. Part 1 Updated the Revision History of the ODCM. This is an Page 2 editorial change.

Section 1.2

3. Part 1 Changed NMPNS to Nine Mile Point Nuclear Station Page 3 (NMPNS). This clarifies the acronym and increases the Definition E accuracy of the ODCM.
4. Part 1 Changed (NMPC) Niagara Mohawk Power Corporation Site Page 3 to Constellation Energy Nuclear Group Site. This updates Definition G the current owners of the Nine Mile Point Nuclear Site. This change increases the accuracy of the ODCM.
5. Part 1 Changed NMPC to Constellation Energy Nuclear Group.

Page 5 This updates the current owners of the Nine Mile Point Definition N Nuclear Site. This change increases the accuracy of the ODCM.

6. Part 2 Updated Section 3.4.2.b.2 under the Section, Limited Page 17 Analysis Approach, added following three sentences to the Section 3.4.2.b.2 first paragraph. Liquid effluent for the years 2002 through 2009 were also reviewed. Liquid releases have decreased dramatically as compared to 1980-1987. H-3 liquid releases have decreased; however, not as dramatically as the other nuclides and is added to this list. Critical pathways and critical age groups remained the same. This change increases the accuracy of the ODCM.

19

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ATTACHMENT NO. 1 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM) (Continued)

REV CHANGE AND REASON FOR CHANGE 12 7. Part 2 Under the Section, Limited Analysis Approach last sentence Page 17 in first paragraph, these radionuclides changed to these Section 3.4.2.b.2 six radionuclides. This was a result of updating Section 3.4.2.b. The critical pathways and age groups remained the same. This change increases the accuracy of the ODCM.

8. Part 2 Under the Section, Limited Analysis Approach, five was Page 17 changed to six. Tritium was the additional radionuclide. This Section 3.4.2.b.2 was a result of updating Section 3.4.2.b. The critical 2nd Paragraph pathways and age groups remained the same. This change 2nd Sentence increases the accuracy of the ODCM.
9. Part 2 Under Calculating Method, H-3 was added to the nuclides.

Page 18 This was a result of updating Section 3.4.2.b. The critical Section 3.4.2.c.6 pathways and age groups remained the same. This change 2nd Sentence increases the accuracy of the ODCM.

10. Part 2 H-3 was added to the nuclides in the table. This was a result Page 19 of updating Section 3.4.2.b. The critical pathways and age Table 3.4.2 groups remained the same. This change increases the accuracy of the ODCM.
11. Part 2 Typographical correction made to footnote. Changed Eq.

Page 19 3-6aIf to Eq. 3-6a If. This change clarifies the ODCM.

Table 3.4.2 20

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ATTACHMENT NO. 1 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM) (Continued)

REV CHANGE AND REASON FOR CHANGE 12 12. Part 2 Two Technical References (6.21 and 6.22) for Appendix B, Page 80 Table B-7, Quantification and Reporting of C-14 in JAF References Releases were added. This change increases the accuracy of the ODCM.

13. Part 2 Table B-7 added to Appendix B, Table of Contents. This Appendix B change increases the accuracy of the ODCM.

Table of Contents Page B-2

14. Part 2 Table B-7, Quantification and Reporting of C-14 in JAF Appendix B Releases, added to Appendix B. This change increases the Page B-47 accuracy of the ODCM.

Through B-52

15. Part 2 Added Table D-9, Calculation of Total Ci/yr Releases for Appendix D Liquids (2002 through 2009), to Table of Contents. This Table of Contents change increases the accuracy of the ODCM.

Page D-2

16. Part 2 Added last paragraph which discusses liquid effluent releases Appendix D for the years 2002 through 2009. This change increases the Page D-4 accuracy of the ODCM.
17. Part 2 Added Table D-9, which updated liquid effluent releases for Appendix D the years 2002 through 2009. This change increases the Table D-9 accuracy of the ODCM.

Page D-14

18. Part 2 In Section 5.4, Independent Spent Fuel Storage &

Page 78 Installation, changed 18 to 22 storage casks. And Section 5.4 changed 9 X 2 array to a 11 X 2 array. And also changed Rev. 1 to Rev. 2 on JAF-CALC-SFS-04025.

JAF Radiological calculations were revised to reflect a Phase I ISFSI consisting of 22 casks rather than 18.

21

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ATTACHMENT NO. 2

SUMMARY

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

There were no changes to the Process Control Program.

22

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ATTACHMENT NO. 3

SUMMARY

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

There were no new locations identified in the land use census.

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.

23

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ATTACHMENT NO. 4 DEVIATIONS FROM THE REQUIRED ENVIRONMENTAL SAMPLING SCHEDULE In accordance with the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1, Section 6.2.7, the cause for the unavailability of any environmental samples required during the report period shall be included in the Annual Radioactive Effluent Release Report.

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

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

1/14/13 Air Stations R1 and R2 lost power for 6.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Air Stations R3 and R4 lost power for 2.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

1/29/13 Sample Station R5 lost power for approximately 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

8/6/13 R-1 offsite environmental air sample station was found not running by the Constellation technician during the weekly sample change out. The vacuum pump was found to have failed and was replaced. The station was returned to service. From the flow rate data, the sample ran for about 2 minutes before failing.

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 44,336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> out of a possible 44,520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br />. The air sampling availability factor for the report period was 99.6%.

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

24

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ATTACHMENT NO. 5 ANNUAL

SUMMARY

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

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

25

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ATTACHMENT NO. 6 MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS In accordance with the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Controls (REC) Section 7.0, Major Modifications to Radioactive Waste Treatment Systems (liquid, gaseous and solid) shall be reported in the Annual Radioactive Effluent Release Report for the period in which the modification is completed and made operational.

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

26

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 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 338 pCi/l, and a maximum concentration of 6,643 pCi/l for a MW CST-B sample from 1/9/2013. Such levels are below the Reporting Level of the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1, Table 5.1-2, for tritium. The Reporting Level for tritium is 30,000 pCi/l. Approximately 240 ml was obtained from MW CST-B for the 1/9/2013 sample. The normal sample volume is one liter. MW CST-B is a shallow horizontal well and during periods of low precipitation, it yields very small sample volumes and elevated tritium concentrations. 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 2013 monitoring effort that is attributable to James A. FitzPatrick operations is tritium, and all concentrations were below any reporting criteria.

27

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ATTACHMENT NO. 7 (continued)

ONSITE GROUNDWATER MONITORING A) Gamma Isotopic Monitoring For 2013, the 24 monitoring wells were sampled 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.

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

Manganese-54 15 Zirconium/Niobium-95 15 Cobalt-58 15 Iodine-131 15 Iron-59 30 Cesium-134 15 Cobalt-60 15 Cesium-137 18 Zinc-65 30 Barium/Lanthanum-140 15 There were no plant related nuclides detected in the samples. Gross Beta and Hard to Detect nuclide analysis not required.

28

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ATTACHMENT NO. 7 (continued)

ONSITE GROUNDWATER MONITORING B) Tritium Summary

  1. Positive Minimum Maximum
  1. Samples Well Name Samples in Positive Positive in 2013 2013 Concentration Concentration MW-1A 9 3 416 497 MW-1B 9 0 MW-2A 9 8 421 641 MW-2B 9 0 MW-3A 8 6 440 720 MW-3B 8 7 338 521 MW-4A 8 3 372 455 MW-4B 8 0 MW-5 9 6 342 570 MW-6 9 9 342 666 MW-7 9 0 MW-8 9 3 374 385 MW-9 9 3 392 403 MW-10A 8 4 367 568 MW-10B 8 0 MW-13 8 6 355 499 MW-14 8 2 355 363 MW-15 8 1 361 361 MW-16 8 7 378 583 MW-19 1 0 MW-20 1 0 MW-21 1 0 MW-CSTA 6 5 423 553 MW-CSTB 8 8 1377 6643 Note 1: All results are in pCi/L.

Note 2: A total of 178 samples were analyzed for H-3 in 2013 with 81 positive results.

Note 3: Samples were analyzed to an LLD of 500 pCi/L.

29

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ATTACHMENT NO. 8 GASEOUS EFFLUENTS - CARBON-14 a) Date: January 01, 2013 - December 31, 2013 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 2.40E+00 2.43E+00 2.55E+00 2.65E+00 Ci/sec 3.09E-01 3.09E-01 3.21E-01 3.33E-01 h) Resultant Doses: See Addendum 1Assessment of Radiation Doses to the Public January-December 2013 Table 1E i) Dose Calculations: Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Section 4.4.1 (1)

Curies released calculated using the methodology in EPRI Technical Report 1021106 30

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents.

31

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 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 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.

32

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ADDENDUM 1 ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2013

1. INTRODUCTION The James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Controls, requires an assessment of the radiation doses to the 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 33

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 exceed the annual dose limits of 10 CFR 20, for unrestricted areas.

ADDENDUM 1 (continued)

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

1. Less than or equal to 500 mrem/year to the whole body and less than or equal to 3000 mrem/year to the skin from noble gases; and,
2. Less than or equal to 1500 mrem/year to any organ from Iodine-131, Iodine-133, Tritium and for radioactive materials in particulate form with half-lives greater than 8 days (inhalation pathway only).

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

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

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

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

1. During any calendar quarter, to less than or equal to 5 mrad from gamma radiation, and less than or equal to 10 mrad from beta radiation; and,
2. During any calendar year, to less than or equal to 10 mrad from gamma radiation and less than or equal to 20 mrad from beta radiation.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ADDENDUM 1 (continued)

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

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

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

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

1. During any calendar quarter to less than or equal to 7.5 mrem to any organ; and,
2. During any calendar year to less than or equal to 15 mrem to any organ.

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

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

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

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

1. Less than or equal to 25 mrem/year to the whole body; and,
2. Less than or equal to 25 mrem/year to any organ except the thyroid which shall be limited to less than or equal to 75 mrem/year.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ADDENDUM 1 (continued)

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

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

Specific radioactive release activities used in the dose calculations are listed in the Annual Radioactive Effluent Release Report (1.21 Report) for the period of January 1, 2013 to December 31, 2013. Historical meteorological data was used to generate tables of average dispersion factors. Locations of interest were identified from the 2013 land use census.

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

C. ASSESSMENT RESULTS

SUMMARY

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

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

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

B. RESULTS

SUMMARY

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

ADDENDUM 1 (continued) 36

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 TABLE 1 ANNUAL DOSE ASSESSMENT 2013 A. LIQUIDS QUARTER 1 2 3 4 ANNUAL (a) (a) (a) (a) (a)

Organ (mrem) 7.04E-06 4.20E-06 4.10E-06 8.47E-07 1.79E-05

% of Limit 1.41E-04 8.39E-05 8.19E-05 1.69E-05 1.79E-04 (b) (b) (b) (b) (b)

Whole Body (mrem) 7.04E-06 4.20E-06 4.10E-06 8.47E-07 1.79E-05

% of Limit 4.69E-04 2.80E-04 2.73E-04 5.65E-05 5.97E-04 (a) Dose to the Child Liver primarily by the potable water pathway.

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

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ADDENDUM 1 (continued)

TABLE 1 (cont)

ANNUAL DOSE ASSESSMENT 2013 B. NOBLE GASES QUARTER 1 2 3 4 ANNUAL Total Body (mrem/yr) 2.04E-02 3.26E-02 4.74E-02 4.10E-02 4.74E-02

% of Limit 4.09E-03 6.51E-03 9.48E-03 8.20E-03 9.48E-03 Skin (mrem/yr) 2.64E-02 4.24E-02 6.17E-02 5.34E-02 6.17E-02

% of Limit 8.78E-04 1.41E-03 2.06E-03 1.78E-03 2.06E-03 Gamma (mrad) 2.73E-04 3.74E-04 2.88E-04 6.58E-04 1.59E-03

% of Limit 5.47E-03 7.48E-03 5.76E-03 1.32E-02 1.59E-02 Beta (mrad) 3.77E-05 5.70E-05 3.88E-05 1.05E-04 2.38E-04

% of Limit 3.77E-04 5.70E-04 3.88E-04 1.05E-03 1.19E-03 C. IODINES AND PARTICULATES QUARTER 1 2 3 4 ANNUAL (a) (a) (a) (a) (a)

Organ (mrem) 5.38E-04 1.07E-03 1.55E-03 2.13E-03 5.28E-03

% of Limit 7.17E-03 1.43E-02 2.06E-02 2.84E-02 3.52E-02 (a) (a) (a) (a) (a)

Organ Dose Rate 2.13E-04 2.44E-04 3.83E-04 3.77E-04 3.83E-04 (mrem/yr)

% of Limit 1.42E-05 1.63E-05 2.55E-05 2.51E-05 2.55E-05 (a) Dose to the Child Thyroid primarily by the vegetation pathway.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ADDENDUM 1 (continued)

TABLE 1 (cont)

ANNUAL DOSE ASSESSMENT 2013 D. CARBON 14 QUARTER 1 2 3 4 ANNUAL (a) (a) (a) (a) (a)

Organ (mrem) 7.64E-03 7.73E-03 8.15E-03 8.46E-03 3.20E-02

% of Limit 1.02E-01 1.03E-01 1.09E-01 1.13E-01 2.13E-01 (a)

Organ Dose Rate NA NA NA NA 3.20E-02 (mrem/yr)

% of Limit NA NA NA NA 2.13E-03 (a) Dose to the Child Bone primarily by the vegetation pathway.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ADDENDUM 1 (continued)

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

RECEPTOR LOCATION DISPERSION FACTOR A. IODINE & DISTANCE/ RELEASE X/Q D/Q 3

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

1. Garden 0.90 mi @ 83 E ST 2.83E-08* 1.75E-09 Grazing Season 0.90 mi @ 83 E RX 2.02E-07* 5.01E-09 Cary 0.90 mi @ 83 E TB 1.83E-07* 4.80E-09 Location No. 78 0.90 mi @ 83 E RF 2.02E-07* 5.01E-09 0.90 mi @ 83 E RW 3.21E-07* 5.76E-09
2. Meat 1.18 mi @ 127 SE ST 1.72E-08* 6.80E-10 Grazing Season 1.18 mi @ 127 SE RX 5.36E-08* 1.30E-09 Parkhurst 1.18 mi @ 127 SE TB 5.14E-08* 1.27E-09 Location No. 26 1.18 mi @ 127 SE RF 5.36E-08* 1.30E-09 1.18 mi @ 127 SE RW 9.12E-08* 1.46E-09
3. Cow 2.50 mi @ 139 SE ST 1.67E-08* 2.65E-10 Grazing Season 2.50 mi @ 139 SE RX 2.76E-08* 4.14E-10 France 2.50 mi @ 139 SE TB 2.71E-08* 4.07E-10 Location No. 10 2.50 mi @ 139 SE RF 2.76E-08* 4.14E-10 2.50 mi @ 139 SE RW 4.15E-08* 4.36E-10
4. Goat (D/Q) 3.62 mi @ 113 ESE ST NA 2.28E-10 Grazing Season 3.62 mi @ 113 ESE RX NA 3.40E-10 Showers 3.62 mi @ 113 ESE TB NA 3.33E-10 Location No. 71 3.62 mi @ 113 ESE RF NA 3.40E-10 3.62 mi @ 113 ESE RW NA 3.49E-10
5. Goat (X/Q) 2.64 mi @ 152 SSE ST 1.94E-08* NA Grazing Season 2.64 mi @ 152 SSE RX 2.58E-08* NA Nickolas 2.64 mi @ 152 SSE TB 2.57E-08* NA Location No. 61 2.64 mi @ 152 SSE RF 2.58E-08* NA 2.64 mi @ 152 SSE RW 3.59E-08* NA 40

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ADDENDUM 1 (continued)

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

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

6. Resident Annual Average
a. Inhalation(2) 1.55 mi @ 90 E(1) ST 2.99E-08 NA Cary 0.90 mi @ 83 E RX 2.07E-07 NA Location No. 78 0.90 mi @ 83 E TB 1.88E-07 NA 0.90 mi @ 83 E RF 2.07E-07 NA 0.90 mi @ 83 E RW 3.06E-07 NA
b. Deposition(3) 0.71 mi @ 118 ESE ST NA 1.60E-09 Whaley 0.71 mi @ 118 ESE RX NA 5.52E-09 Location No. 199 0.71 mi @ 118 ESE TB NA 5.30E-09 0.71 mi @ 118 ESE RF NA 5.52E-09 0.71 mi @ 118 ESE RW NA 6.28E-09 B. NOBLE GASES
1. Air Dose 1.55 mi @ 90 E(1) ST 2.99E-08 NA Annual Average 0.60 mi @ 90 E ST(fc) 1.16E-07 NA Site Boundary 0.60 mi @ 90 E RX 3.58E-07 NA 0.60 mi @ 90 E TB 3.19E-07 NA 0.60 mi @ 90 E RF 3.58E-07 NA 0.60 mi @ 90 E RW 5.39E-07 NA
2. Total Body 0.60 mi @ 90 E ST(fc) 1.16E-07 NA Annual Average 0.60 mi @ 90 E RX 3.58E-07 NA Site Boundary 0.60 mi @ 90 E TB 3.19E-07 NA 0.60 mi @ 90 E RF 3.58E-07 NA 0.60 mi @ 90 E RW 5.39E-07 NA 41

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2013 - DECEMBER 2013 ADDENDUM 1 (continued)

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

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

3. Skin 1.55 mi @ 90 E ST 2.99E-08 NA Annual Average 0.60 mi @ 90 E ST(fc) 1.16E-07 NA Site Boundary 0.60 mi @ 90 E RX 3.58E-07 NA 0.60 mi @ 90 E TB 3.19E-07 NA 0.60 mi @ 90 E RF 3.58E-07 NA 0.60 mi @ 90 E RW 5.39E-07 NA
    • Based on ODCM X/Q, D/Q Values Rev. 11 (1) Highest Sector Average X/Q in a populated area, not an identified residence.

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

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

ST = Main Stack RX = Reactor Building Vent TB = Turbine Building Vent RF = Refuel Floor Vent RW = Radwaste Building Vent fc = Finite Cloud 42

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