JAFP-07-0054, Annual Radioactive Effluent Release Report for the Period of January 1, 2006 Through December 31, 2006

From kanterella
Jump to navigation Jump to search
Annual Radioactive Effluent Release Report for the Period of January 1, 2006 Through December 31, 2006
ML071280520
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/26/2007
From: Peter Dietrich
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Document Control Desk, NRC/NRR/ADRO
References
JAFP-07-0054
Download: ML071280520 (38)
v • d • e


Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. Fitzpatrick NPP

'Entergy P.0. Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 Pete Dietrich Site Vice President - JAF April 26, 2007 JAFP-07-0054 U.S. Nuclear Regulatory Commission ATT'N: Document Control Desk Washington, D.C. 20555

SUBJECT:

James a. Fitzpatrick Nuclear Power Plant Docket No. 50-333, License No. DPR-59 Annual Radioactive Effluent Release Report Gentlemen:

Attachment 1 is the Annual Radioactive Effluent Release Report for the period of January 1, 2006 through December 31, 2006. This report is submitted in accordance with the requirements. of the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual, Part 1, Radiological Controls, Section 6.2.

This report includes, an assessment of the radiation doses to the public due to the radioactive liquid and gaseous effluents released during the 2006 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 and 10 CFR 50.4.

If you have any questions concerning the attached report, please contact Crystal A. Boucher, Chemistry Superintendent, at the James A. FitzPatrick Nuclear Power Plant at (315)349-6748.

Ther are no comimet tie There are no commitments c this letter.

Pete Dietri Site Vice President PD/CAB/jbh Attachments: 1) James A. FitzPatrick Nuclear Power Plant Annual Radioactive Effluent Release Report cc: Next Page

cc: Mr. Samuel Collins Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Resident Inspector's Office U. S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093 Mr. John Boska Plant Licensing Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop O-8-C2 Washington D.C. 20555 Mr. Don Sherman American Nuclear Insurers 95 Glastonbury Boulevard Glastonbury, CT 06033-4438 Paul Merges, PhD Chief, Bureau of Radiation Division of Hazardous Substance Regulation New York State Department of Environmental Conservation Albany, NY 12233 K. Mulligan (JAF)

C. Faison (ENOC/WPO)

J. McCann (ENOC/WPO)

J. Furfaro (ENOC/WPO)

W. Hamblin (CHEM/JAF)

T. Kurtz (NMPC) 2

JAFP-07-0054 ATTACHMENT 1 ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2006 - DECEMBER 31,2006 D)§CKET NO.: 50-333 LICENSE NO.: DPR-59

ENTERGY NUCLEAR OPERATIONS, INC..

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 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.l.a and 3.4.1.c.l.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 2006-DECEMBER 2006 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 j, 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. 1oX Effluent Concentrations
a. Fission and activation gases: (None specified)
b. Iodines: (None specified)
c. Particulates, half-lives >8 days: (None specified)
d. Liquid effluents: Ouarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Fission and activation None' None None 1.14E-04 products (mixture EC)

(pgCi/ml)

(2) Tritium ([tCi/ml) 1.OOE-02 1.OOE-02 1.OOE-02 1.OOE-02 (3) Dissolved and entrained gases (p.Ci/ml) 2.OOE-04 2.OOE-04 2.OOE-04 2.OOE-04 2

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 SUPPLEMENTAL INFORMATION (continued)

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

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

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 SUPPLEMENTAL INFORMATION (continued)

5. Batch Releases
a. Liquid: Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 2.OOE+00 6.OOE+00 4.OOE+00 3.1 OE+0 1 (2) Total time period for batch 1.01E+02 1.73E+02 1.55E+02 1.73E+03 release: (min)

(3) Maximum time period for 6.50E+01 6.30E+e01 7.OOE+01 1.05E+02 batch release: (min)

(4) Average time period for 5.05E+01 2.88E+01 3.89E+01 5.58E+01 batch release: (min)

(5) Minimum time period for 3.60E+01 2.OOE+00 3.OOE+00 5.OOE+00 batch release: (min)

(6) Total Activity Released (Ci) 3.94E-06 1.53E-04 2.28E-04 3.81E+00 (7) Total Volume Released (liters) 1.48E+03 6.35E+03 8.55E+03 8.68E+05

b. Liquid: Non-Canal (1) Number of batch releases: 4.OOE+00 1.20E+01 1.20E+01 1.20E+01 (2) Total time period for batch 4.OOE+00 3.36E+01 3.75E+02 1.72E+02 release: (min)

(3) Maximum time period for 1.00E+00 1.40E+01 8.OOE+01 1.11 E+02 batch release: (min)

(4) Average time period for 1.00E+00 2.80E+00 3.15E+01 1.43E+01 batch release: (min)

(5) Minimum time period for 1.00E+00 1.00E+00 2.OOE+00 1.OOE+00 batch release: (min)

(6) Total Activity Released (Ci) 3.87E-06 2.64E-05 3.19E-04 8.79E-05 (7) Total Volume Released (liters) 1.82E+03 1.27E+04 1.42E+05 6.56E+04 4

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 SUPPLEMENTAL INFORMATION (continued)

c. Gaseous:

There were no gaseous batch releases for this report period.

6. Abnormal Releases
a. Liquid: Ouarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of releases: NONE NONE NONE NONE (2) Total activity released: NONE NONE NONE NONE
b. Gaseous (1) Number of releases: NONE NONE NONE NONE (2) Total activity released: NONE NONE NONE NONE 5

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 TABLE 1A GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES EST TOTAL UNIT QTR 1 OTR 2 OTR 3 OTR 4 ERROR %

A. FISSION AND ACTIVATION GASES

1. Total Release Ci 4.14E+02 4.02E+02 3.87E+02 8.43E+01 52.50E+01
2. Average release rate for period giCi/sec 5.27E+01 5.11 E+01 4.86E+01 1.06E+01
3. Applicable ODCM Limit B. IODINE-131
1. Total Iodine-131 Ci 5.80E-04 5.84E-04 3.97E-04 2.21 E-03 <2.50E+01
2. Average release rate for period gCi/sec 7.37E-05 7.43E-05 4.99E-05 2.78E-04
3. Applicable ODCM Limit C. PARTICULATES
1. Particulates with half-lives Ci 4.82E-04 6.60E-04 5.93E-04 2.87E-04 <3.60E+01

>8 days

2. Average release rate for gCi/sec 6.14E-05 8.39E-05 7.46E-05 3.61 E-05 period 4 *
3. Applicable ODCM Limit
4. Gross alpha radioactivity Ci 4.52E-07 1.26E-07 3.88E-07 4.60E-07 *!2.50E+01 D. TRITIUM
1. Total Release Ci 3.99E+00 3.41E+00 4.48E+00 5.19E+00 <2.50E+01
2. Average release rate for period ltCi/sec 5.07E-01 4.34E-01 5.64E-01 6.52E-01
3. Applicable ODCM Limit
  • E. PERCENT OF APPLICABLE ODCM LIMITS FISSION AND ACTIVATION GASES
1. Quarterly gamma air dose limit  % 5.37E-02 9.25E-02 1.24E-01 2.34E-02
2. Quarterly beta air dose limit  % 2.12E-01 1.10E-01 7.34E-02 8.54E-03
3. Yearly gamma air dose limit  % 2.68E-02 4.62E-02 6.18E-02 1 .17E-02
4. Yearly beta air dose limit  % 1.06E-01 5.48E-02 3.67E-02 4.27E-03
5. Whole body dose rate limit  % 3.60E-02 5.50E-02 1.29E-02 1.24E-02
6. Skin dose rate limit  % 1.03E-02 1.53E-02 4.70E-03 3.46E-03 HALOGENS, TRITIUM AND PARTICULATES WITH HALF-LIVES >8 DAYS
7. Quarterly dose limit (organ)  % 9.01 E-02 9.28E-02 6.37E-02 3.72E-01
8. Yearly dose limit (organ)  % 4.51 E-02 4.64E-02 3.18E-02 1.86E-01
9. Organ dose rate limit  % 5.OOE-05 3.87E-05 2.01 E-05 6.18E-04 6

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 TABLE 1B GASEOUS EFFLUENTS--ELEVATED RELEASE CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4

1. Fission Gases Argon-41 Ci 2.32E+00 1.99E+00 1.83E+00 1.45E+00 Krypton-85 Ci .......................... 1.35E+01 Krypton-85m Ci 4.60E+01 4.76E+01 7.67E+01 1.69E+01 Krypton-87 Ci 1.15E+00 3.40E+00 6.76E+00 8.61 E-01 Krypton-88 Ci 2.57E+01 3.61 E+01 9.02E+01 1.66E+01 Krypton-89 Ci 5.53E+00 .........-- -------------

Xenon-1 33 Ci 5.71 E+01 5.36E+01 8.21 E+01 1.43E+01 Xenon-135 Ci 1.40E+00 2.64E+00 1.15E+00 7.40E-01 Xenon-1 35m Ci 6.28E+00 1.21 E+01 3.48E+00 9.63E-01 Xenon-1 37 Ci 3.12E+01 6.77E+01 1.33E+01 1.02E+00 Xenon-1 38 Ci 1.80E+01 3.82E+01 1.06E+01 1.68E+00 TOTAL Ci 1.88E+02 2.69E+02 2.86E+02 6.80E+01

2. Iodines Iodine-i 31 Ci 3.07E-04 2.56E-04 1.69E-04 5.05E-04 Iodine-1 33 Ci 1.56E-03 4.09E-04 2.28E-04 6.96E-05 Iodine-1 35 Ci 1.35E-03 3.93E-05 8.31 E-05 TOTAL Ci 3.22E-03 7.04E-04 4.80E-04 5.75E-04
3. Particulates Chromium-51 Ci 1.56E-06 Manganese-54 Ci 8.83E-07 Cobalt-60 Ci ------------ 4.34E-07 Strontium-89 Ci 4.64E-05 1.26E-04 1.51 E-04 1.13E-04 Strontium-90 Ci 3.58E-07 2.20E-07 3.61 E-07 5.74E-07 Cesium-1 37 Ci 6.35E-07 2.33E-07 2.18E-07 Barium-140 Ci 6.32E-05 7.31 E-05 2.97E-05 4.59E-05 TOTAL Ci 1.1OE-04 2.OOE-04 1.81 E-04 1.63E-04
4. Tritium Hydrogen-3 Ci 4.37E-01 4.48E-01 8.46E-01 1.23E+00 Note: There were no batch releases for this report period.

7

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 TABLE 1C GASEOUS EFFLUENTS--GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER4

1. Fission Gases Krypton-87 Ci 6.76E-02 Xenon-1 33 Ci 7.43E-01 1.54E+00 1.40E+00 7.28E+00 Xenon-135 Ci 3.86E+00 4.44E+00 3.19E+00 1.01 E+00 Xenon-135M Ci 1.83E+01 1.70E+01 1.32E+01 1.10E+00 Xenon-1 37 Ci 1.32E+02 5.1 OE+01 3.02E+01 3.16E+00 Xenon-1 38 Ci 7.01 E+01 5.94E+01 5.25E+01 3.80E+00 TOTAL Ci 2.25E+02 1.33E+02 1.OOE+02 1.64E+01
2. lodines Iodine-1 31 Ci 2.73E-04 3.28E-04 2.28E-04 1.71 E-03 Iodine-1 33 Ci 6.91 E-04 6.98E-04 6.07E-04 3.54E-04 TOTAL Ci 9.64E-04 1.03E-03 8.35E-04 2.06E-03
3. Particulates Manganese-54 Ci 6.23E-06 Cobalt-60 Ci 1.49E-06 1.92E-06 Zinc-65 Ci 7.66E-06 Strontium-89 Ci 1.68E-04 2.07E-04 2.38E-04 9.65E-05 Strontium-90 Ci 3.95E-08 1.27E-06 1.36E-06 2.08E-06 Barium-1 40 Ci 2.05E-04 2.50E-04 1.72E-04 7.14E-06 TOTAL Ci 3.73E-04 4.60E-04 4.11 E-04 1.22E-04
4. Tritium Hydrogen-3 Ci 3.55E+00 2.96E+00 3.64E+00 3.90E+00 Note: There were no batch releases for this report period.

8

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 TABLE 1D - SUPPLEMENTAL GASEOUS EFFLUENTS-UNMONITORED SHORT-TERM RELEASE CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER1 QUARTER 2 QUARTER 3 QUARTER4

1. Fission Gases None
2. Iodines None
3. Particulates Chromium-51 Ci 1.57E-08 Manganese-54 Ci 1.53E-07 Cobalt-58 Ci 5.40E-08 Iron-59 Ci 9.67E-09 Cobalt-60 Ci 1.55E-07 Zinc-65 Ci 2.09E-06 TOTAL Ci 2.48E-06
4. Tritium Hydrogen-3 Ci 6.24E-02 9

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 TABLE 2A LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES EST TOTAL UNIT OTR1 QTR2 OTR3 QTR4 ERROR %

A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not including tritium, gases and alpha) Ci NONE NONE NONE 3.67E-04 _<2.50E+01
2. Average diluted concentration during period JiCi/mi NONE NONE NONE 1.33E-10
3. Applicable ODCM Limit B. TRITIUM
1. Total Release Ci 7.82E-06 1.80E-04 5.46E-04 3.81 E+00 <_2.50E+01
2. Average diluted concentration during period (Note 1) gci/mi 1.17E-06 2.31 E-06 2.11 E-06 1.47E-06
3. Applicable ODCM Limit C. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci NONE NONE NONE < .50E+01
2. Average diluted concentration during period JiCi/ml NONE NONE NONE
3. Applicable ODCM Limit D. GROSS ALPHA RADIOACTIVITY
1. Total Release Ci NONE NONE NONE 5.17E-06 _<4.20E+01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) liters 3.30E+03 1.91 E+04 1.51 E+05 9.34E+05 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 1.51 E+08 2.47E+08 2.32E+08 2.57E+09
  • G. PERCENT OF APPLICABLE ODCM LIMITS
1. Quarterly Whole Body Dose 8.58E-05 3.19E-04 1.87E-04 8.50E-04
2. Quarterly Organ Dose 2.57E-05 9.57E-05 5.61 E-05 2.63E-04
3. Annual Whole Body Dose 4.29E-05 1.59E-04 9.34E-05 4.25E-04
4. Annual Organ Dose 1.29E-05 4.78E-05 2.80E-05 1.32E-04 (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 2006-DECEMBER 2006 TABLE 2B LIQUID EFFLUENTS CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER1 QUARTER 2 QUARTER 3 QUARTER4

1. Fission and Activation Products Manganese-54 Ci 1.04E-04 Iron-55 Ci 2.02E-04 Cobalt-60 Ci 1.59E-05 Zinc-65 Ci 3.83E-05 Strontium-90 Ci 7.06E-06 TOTAL Ci 3.67E-04
2. Tritium HYDROGEN-3 Ci 7.81 E-06 1.80E-04 5.47E-04 3.81 E+00
3. Dissolved and Entrained Gases NONE Ci Note: There were no continuous mode discharges during this report period.

11

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 TABLE 2B (SUPPLEMENT)

LIQUID EFFLUENTS NON-CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER1 QUARTER2 QUARTER3 QUARTER4

1. Fission and Activation Products NONE Ci
2. Tritium HYDROGEN-3 Ci 3.87E-06 2.64E-05 3.19E-04 8.79E-05
3. Dissolved and Entrained Gases NONE Ci Note: There were no continuous mode discharges during this report period.

12

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 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 mA3 0.OOE+00 O.OOE+00 0.O0E+00 0.OOE+00 evaporator bottoms, etc. Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
b. Dry compressible waste, mA3 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 contaminated equipment, etc. Ci 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00
c. Irradiated components, mA3 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 control rods, etc. Ci 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00
d. Other: Dry compressible mA3 1.08E+03 5.83E+00 0.OOE+00 1.OOE+01 waste, contaminated equipment, Ci 2.76E+01 5.13E+01 0.OOE+00 1.OOE+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 for volume reduction.

Isotope Percent Curies Isotorpe Percent Curies Iron-55 6.94E+01 5.47E+01 E Nickel-63 9.24E-01 7.29E-01 E Cobalt-60 1.09E+01 8.59E+00 E 'Tritium 5.39E-01 4.25E-01 E Manganese-54 2.67E+00 2.11 E+00 E Cesium-134 1.49E+00 1.17E+00 E Cesium-1 37 2.78E+00 2.19E+00 E Cobalt-58 1.60E-02 1.26E-02 E Zinc-65 1.06E+01 8.38E+00 E Cerium-141 1.47E-02 1.16E-02 E Plutonium-241 2.44E-02 1 .93E-02 E Strontium-90 3.13E-01 2.47E-01 E Cerium-144 3.15E-01 2.48E-01 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.

13

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition No. of Shipments Mode of Transportation Destination 14 Truck *Duratek Oak Ridge, TN 7 Truck
  • Studsvik Erwin, TN 10 Truck
  • Alaron Wampum, PA 7 Truck *Duratek GIC Kingston, TN 2 Truck *GE Global Nuclear Fuel Wilmington, NC
  • Volume Reduction Facility B. IRRADIATED FUEL SHIPMENTS (Disposition)

No. of Shipments Mode of Transportation Destination NONE 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 TABLE 3B SOLID WASTE AND IRRADIATED FUEL SHIPMENTS NRC CLASS A SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Spent Resins, Filter Sludges, evaporator Air Drying 205.8 ftA3 HIC 4 Bottoms, etc. Non-compacted Dry compressible Waste (DAW), Non-compacted 1280 ftA3 STC 13 Contaminated Equipment, etc.

Dry compressible Waste(DAW), Non-compacted 2560 ftA3 STC I Contaminated Eqiupment, etc.

Dry compressible Waste(DAW), Non-compacted 96 ftA3 STC 47 Contaminated Eqiupment, etc.

Contaminated Non-compacted 7.5 ftA3 STC 13 Oil Dry compressible Waste(DAW), Non-compacted 111 ftA3 STC 3 Contaminated Equipment Dry compressible Waste(DAW), Non-compacted 206.1 ftA3 STC 1 Contaminated Equipment Dry compressible Waste(DAW), Non-compacted 209.1 ftA3 STC I Contaminated Equipment Dry compressible Waste(DAW), Non-compacted 292 ftA3 STC 5 Contaminated Equipment Dry compressible Waste(DAW), Non-compacted 1033.5 ftA3 STC 11 Contaminated Equipment 15

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 B. NRC CLASS B SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Spent Resins, Filter Sludges, evaporator Air Drying 205.8 ftA3 HIC I Bottoms, etc. Non-compacted C. NRC CLASS C SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS NONE Solidification Agent: NONE HIC- High Integrity Container STC- Strong Tight Container 16

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 ATTACHMENT NO. 1 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

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

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

17

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 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.

Revisions to the Performance Reference procedures of the Process Control Program procedure were made and approved on 5/22/06. These revisions do not reduce the overall conformance of the solidified waste product to existing criteria for solid waste. Listed below is a brief summary of changes incorporated in this revision.

1) CNSI-FO-OP-032-41802, Setup and Operating Procedure for RDS-1000 Unit Number 9 at James A. FitzPatrick Nuclear Power Plant was withdrawn and replaced by CNSI-FO-P-033-41802. This was due to an equipment change to replace obsolete and unreliable equipment.
2) CNSI-FO-OP-023-41802, Bead Resin/Activated Carbon Dewatering Procedure for CNSI-14-215 or Smaller liners at James A. FitzPatrick Nuclear Plant was revised to dewater liners with new equipment. The major change was the new procedure uses multiple drying cycles instead of an air conditioning system to dewater liners.

18

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 ATTACHMENT NO. 3

SUMMARY

OF CHANGES TO THE ENVIRONMENTAL MONITORING AND DOSE CALCULATION LOCATIONS In accordance with the James A. FitzPatrick Nuclear Power Plant Off Site Dose Calculation Manual (ODCM), Part 1, Sections 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.

CHANGES IN ENVIRONMENTAL MONITORING LOCATIONS During the report period, no changes were made to the Environmental Monitoring Locations sampled to implement the requirements of the ODCM, Part 1, table 5.1-1.

Sample location selections were based on the 2006 annual land use census.

NEW LOCATIONS FOR DOSE CALCULATIONS During the report period, no changes in Dose Calculation Receptor Locations were required based on the results of the land use census.

19

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 ATTACHMENT NO. 4 DEVIATIONS FROM THE REQUIRED ENVIRONMENTAL SAMPLING SCHEDULE In accordance with the James A. FitzPatrick Nuclear Power Plant Off Site 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 I, Section 5.1.1.c.1 allows for deviations from the program due to hazardous conditions, seasonal unavailability, theft, uncooperative residents, or to malfunction of automatic sampling equipment.

DEVIATION AND EXCEPTIONS TO THE PROGRAM The noted exceptions to the 2006 sample program address only those samples or monitoring requirements which are required by the ODCM, Part I, Table 5.1-1. This section satisfies the reporting requirements of ODCM, Part I, Section 5.1.1.c. I.

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

1. The air sampling pump at the R5 Environmental Sampling Station was inoperable for approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> during the sample period of 1/17/06 through 1/24/06. The air sample pump was running at the time of sample collection. The sample pump out of service time was determined based on the sample pump run time integrator. The inoperability of the pump was due to a loss of power to the sampler. No corrective actions were required to restore the unit to service.
2. The air sampling pump at the R3 and R4 Environmental Sampling Stations were inoperable for approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> on 2/22/06 due to high winds that caused a power outage. The sample pump out of service times were determined based on the sample pump run time integrator. No corrective actions were implemented.
3. The air sampling pump at the R5 Environmental Sampling Station was inoperable for approximately 2.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> on 2/22/06 due to high winds that caused a power outage.

The sample pump out of service time was determined based on the sample pump run time integrator. No corrective action was implemented.

20

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 ATTACHMENT NO. 4 (Continued)

4. The air sampling pump at the RI and R2 Environmental Sampling Stations were inoperable for approximately 0.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> during the sample period of 3/28/06 through 4/4/06. The air sample pumps were running at the time of sample collection. The sample pump out of service times were determined based on the sample pump run time integrators. The inoperability of the pumps was due to a loss of power to the samplers. No corrective actions were required to restore these units to service.
5. The air sampling pump at the R5 Environmental Sampling Station was inoperable for approximately 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> on 6/6/06. The sample pump out of service time was determined based on the sample pump run time integrator. The inoperability of the pump was due to a loss of power to the sampler. No corrective actions were required to restore the unit to service.
6. The air sampling pump at the RI and R2 Environmental Sampling Stations were inoperable for approximately 0.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> on 8/1/06. The sample pump out of service times were determined based on the sample pump run time integrators. The inoperability of the pumps was due to a loss of power to the samplers. No corrective actions were required to restore the unit to service.
7. The air sampling pump at the R5 Environmental Sampling Stations was inoperable for approximately 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> during the sample period of 9/26/06 through 10/3/06.

The air sample pump was running at the time of sample collection. The sample pump out of service time was determined based on the sample pump run time integrator.

The inoperability of the pump was due to a loss of power to the sampler. No corrective actions were required to restore these units to service.

8. The air sampling pump at R1 and R2 Environmental Sampling Stations were inoperable for approximately 9.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> for the sample period 10/23/06 through 10/31/06. The sample pump out of service times were determined based on the sample pump run time integrators. The sample pumps were found running. The inoperability of the pumps was due to a loss of power caused by strong winds. No corrective actions were required to restore the unit to service.
9. The air sampling pump at the R5 Environmental Sampling Stations was inoperable for approximately 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> during the sample period of 12/05/06 through 12/12/06.

The air sample pump was running at the time of sample collection. The sample pump out of service time was determined based on the sample pump run time integrator.

The inoperability of the pump was due to a loss of power to the sampler. No corrective actions were required to restore these units to service.

21

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 ATTACHMENT NO. 4 (Continued)

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 43,763 hours0.00883 days <br />0.212 hours <br />0.00126 weeks <br />2.903215e-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 99.92%.

22

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 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.

23

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 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.

24

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 ATTACHMENT NO. 7 GASEOUS EFFLUENTS - UNMONTIORED SHORT-TERM RELEASE a) Date: October 28, 2006 b) Location: Unmonitored Release from the Reactor Building via the Decay Heat Removal System Basin c) Duration: 16 Hours and 32 minutes d) Flowrate: 2.80E+05 cfm e) Volume Released: 2.78E+08 f) Nuclides Released: See Table 1 - Supplemental Gaseous Effluents - Unmonitored Short-Term Release g) Resultant Doses: See Addendum 1-Assessment of Radiation Doses to the Public January-December 2006 Table 1..D h) Dose Calculations: Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Section 4.4.3 Short Term Releases 25

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 ADDENDUM 1 ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2006

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

This assessment of doses to the public is based on accepted methodologies found in the Offsite Dose Calculation Manual (ODCM).

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

Applicability Applies to doses from radioactive material in liquid effluents.

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

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

1. During any calendar quarter, limited to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ.
2. During any calendar year, limited to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.

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

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

26

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 ADDENDUM 1 (continued)

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.

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.

27

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 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.

28

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 ADDENDUM 1 (continued)

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.
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, 2006 to December 31, 2006.

Historical meteorological data was used to generate tables of average dispersion factors. Locations of interest were identified from the 2006 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.

29

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 ADDENDUM 1 (continued)

4. 40 CFR 190 DOSE ASSESSMENT A. METHODOLOGY Evaluation to demonstrate compliance with the 40 CFR 190 dose limits must be performed when the doses calculated for 10 CFR 50 compliance exceed twice their respective limits. When additional dose assessment is required to demonstrate compliance with 40 CFR 190 it is performed in accordance with the ODCM.

B. RESULTS

SUMMARY

The cumulative dose contribution from liquid and gaseous effluents for this report period were calculated and are listed in Table 1. The cumulative dose contribution from direct radiation from the reactor unit and from radwaste storage tanks is measured by environmental thermoluminescent dosimeters for the report period. This data is contained in the Annual Environmental Operating Report. The calculated doses from liquid and gaseous effluents are less than twice their respective 10 CFR 50 limits, therefore, additional calculations are not necessary to demonstrate compliance with 40 CFR 190 dose limits (ODCM, Part 1, REC 4.1.1.c) 30

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 2006 A. LIQUIDS QUARTER 1 2 3 4 ANNUAL (a) (a) (a) (a) (a)

Organ (mrem) 1.29E-06 4.78E-06 2.80E-06 1.32E-05 2.21E-05

% of Limit 2.57E-05 9.57E-05 5.61E-05 2.63E-04 2.21E-04 (b) (b) (b) (b) (b)

Whole Body (mrem) 1.29E-06 4.78E-06 2.80E-06 1.32E-05 2.21E-05

% of Limit 8.58E-05 3.19E-04 1.87E-04 8.50E-04 7.37E-04 (a) Dose to the Child Liver primarily by the potable water pathway.

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

B. NOBLE GASES QUARTER 1 2 3 4 ANNUAL Total Body (mrem/yr) 1.80E-01 2.75E-01 6.43E-02 6.20E-02 2.75E-01

% of Limit 3.60E-02 5.50E-02 1.29E-02 1.24E-02 5.50E-02 Skin (mrem/yr) 3.09E-01 4.60E-01 1.41E-01 1.04E-01 4.60E-01

% of Limit 1.03E-02 1.53E-02 4.70E-03 3.46E-03 1.53E-02 Gamma (mrad) 2.68E-03 4.62E-03 6.18E-03 1.17E-03 1.47E-02

% of Limit 5.37E-02 9.25E-02 1.24E-01 2.34E-02 1.47E-01 Beta (mrad) 2.12E-02 1.1OE-02 7.34E-03 8.54E-04 4.03E-02

% of Limit 2.12E-01 1.10E-02 7.34E-02 8.54E-03 2.02E-01 31

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 2006 C. IODINES AND PARTICULATES QUARTER 1 2 3 4 ANNUAL (a) (b) (a) (b) (b)

Organ (mrem) 6.76E-03 6.96E-03 4.78E-03 2.79E-02 4.64E-02

% of Limit 9.01E-02 9.28E-02 6.37E-02 3.72E-01 3.09E-01 (c) (c) (c) (c) (c)

Organ Dose Rate 7.51E-04 5.81E-04 3.01E-04 9.26E-03 9.26E-03 (mrem/yr)

% of Limit 5.OOE-05 3.87E-05 2.01E-05 6.17E-04 6.17E-04 (a) Dose to the Infant Thyroid primarily by the goats milk pathway.

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

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

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

Organ (mrem) 1.45E-04 1.45E-04

% of Limit 1.93E-03 9.67E-04 Organ Dose Rate 6.28E-04 6.28E-04 (mrem/yr)

% of Limit 4.19E-05 4.19E-05 (a) Dose to the Child Liver primarily by the vegetation pathway.

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

32

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 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/mr3) (1/M 2

)

1. Garden 0.90 mi @ 83 0 E ST 2.83E-08* 1.75E-09 Grazing Season 0.90 mi @ 83 0 E RX 2.02E-07* 5.01E-09 Cary 0.90 mi @ 83 0 E TB 1.83E-07* 4.80E-09 Location No. 78 0.90 mi @ 83 0 E RF 2.02E-07* 5.01E-09 0.90 mi @ 83 0 E RW 3.2 1E-07* 5.76E-09
2. Meat 1.18 mi @ 127°SE ST 1.72E-08* 6.80E-10 Grazing Season 1.18 mi @ 127 0SE RX 5.36E-08* 1.30E-09 Parkhurst 1.18 mi @ 127 0SE 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 0SE RW 9.12E-08* 1.46E-09
3. Cow 2.50 mi 139 0 SE ST 1.67E-08* 2.65E-10 Grazing Season 2.50 mi 139 0 SE RX 2.76E-08* 4.14E-10 France 2.50 mi 139 0 SE TB 2.71E-08* 4.07E-10 Location No. 10 2.50 mi 139 0 SE RF 2.76E-08* 4.14E-10 2.50 mi 139 0SE RW 4.15E-08* 4.36E-10 3.62 mi 113 0ESE ST 2.28E-10
4. Goat (D/Q) 3.62 mi 113 0ESE RX 3.40E-10 Grazing Season 3.62 mi 113 0ESE TB 3.33E-10 Showers 3.62 mi 113 0ESE RF 3.40E-10 Location No. 71 3.62 mi 113 0ESE RW 3.49E-10
5. Goat (X/Q) 2.64 mi @ 152°SSE ST 1.94E-08*

Grazing Season 2.64 mi @ 152 0SSE RX 2.58E-08*

Nickolas 2.64 mi 152 0SSE TB 2.57E-08*

Location No. 61 2.64 mi 152 0 SSE RF 2.58E-08*

2.64 mi 152 0 SSE RW 3.59E-08*

33

EN.TERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 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 @ 900E(') ST 2.99E-08 Cary 0.90 mi @ 83'E RX 2.07E-07 Location No. 78 0.90 mi @ 83 0 E TB 1.88E-07 0.90 mi @ 83 0 E RF 2.07E-07 0.90 mi @ 83 0 E RW 3.06E-07 3
b. Deposition( ) 0.71 mi @ 118 0ESE ST 1.60E-09 Whaley 0.71 mi @ 118 0ESE RX 5.52E-09 Location No. 199 0.71 mi @ 118 0ESE TB 5.30E-09 0.71 mi @ 118 0ESE RF 5.52E-09 0.71 mi @ 118 0ESE RW 6.28E-09 B. NOBLE GASES
1. Air Dose 1.55 mi @ 900E(') ST 2.99E-08 Annual Average 0.60 mi @ 90 0 E ST(fc) 1.16E-07 Site Boundary 0.60 mi @ 90 0 E RX 3.58E-07 0.60 mi @ 90'E TB 3.19E-07 0.60 mi @ 90 0 E RF 3.58E-07 0.60 mi @ 90 0 E RW 5.39E-07
2. Total Body 0.60 mi @ 90 0 E ST(fc) 1.16E-07 Annual Average 0.60 mi @ 90 0 E RX 3.58E-07 Site Boundary 0.60 mi @ 90'E TB 3.19E-07 0.60 mi @ 90'E RF 3.58E-07 0.60 mi @ 90'E RW 5.39E-07 34

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006-DECEMBER 2006 ADDENDUM 1 (continued)

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

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

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

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

Site Boundary 0.60 mi @ 90*E RX 3.58E-07 0.60 mi @ 90 0 E TB 3.19E-07--------

0.60 mi @ 90 0 E RF 3.58E-07--------

0.60 mi @ 90'E RW 5.39E-07

    • Based on ODCM X/Q, D/Q Values Rev. 08 (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 35

Retrieved from "https://kanterella.com/w/index.php?title=JAFP-07-0054,_Annual_Radioactive_Effluent_Release_Report_for_the_Period_of_January_1,_2006_Through_December_31,_2006&oldid=2577259"