ML061430243

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Letter for Inclusion Into NRCs Agencywide Documents Access and Management System (ADAMS)
ML061430243
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 05/10/2006
From: Jim Costedio
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
JREG-06-014
Download: ML061430243 (35)
v • d • e


Text

-Entertgy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. Fitzpatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315 342 3840 May 10, 2006 JREG-06-014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Letter For Inclusion Into NRC's Agencywide Documents Access And Management System (ADAMS)

Dear Madam or Sir; Enclosed is a copy of the James A. FitzPatrick Nuclear Power Plant's (JAFNPP) Annual Radioactive Effluent Release Report (January 1, 2005 through December 31, 2005),

issued April 26, 2006 as required by the plant's Technical Specifications (TS). Presently, this report does not appear in the NRC's Agencywide Documents Access and

-J Management System (ADAMS). Please enter this letter, with enclosed report into ADAMS.

Should you have any questions concerning this submittal, please contact me at (315) 349-6358.

Sincerely, ames Costedio Regulatory Compliance Department Manager Attachment James A. FitzPatrick Nuclear Power Plant Annual Radioactive Effluent Release Report (January 1, 2005 through December 31, 2005) cc:

Mr. John P. Boska, Project Manager (w/out attachments)

Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop: O-8-C2 Washington, DC 20555 jA:4Lb

-Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. Fitzpatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 April 26,2006 JAFP-06-0067 Pete Dietrich Site Vice President - JAF United States Nuclear Regulatory Commission Mr. Samuel Collins Regional Administrator, Region 1 475 Allendale Road King of Prussia, PA 19406

SUBJECT:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333. License No. DPR-59 Gentlemen:

Attached is the Annual Radioactive Effluent Release Report for the period of January 1, 2005 through December 31, 2005. 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, as an Addendum, an Assessment of the Radiation Doses to the public due to the radioactive liquid and gaseous effluents released during the 2005 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.

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.

There are no commnitnns o

' ed i' this letter.

Site Vice President PD/CAB/jbh Attachments Xc:

Document Control Desk (USNRC)

D. Sherman (ANI Library)

K. Mulligan (JAF)

C. Faison (ENOC/WPO)

J. McCann (ENOC/WPO)

J. Boska, Project Manager, NRR NRC Resident Inspector P. Merges (NYSDEC)

T. Kurtz (NMPC)

J. Furfaro (ENOC/WPO)

W. Hamblin (CHEM/JAF)

ii.

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2005 - DECEMBER 31,2005 DOCKET NO.: 50-333 LICENSE NO.: DPR-59

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 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, lodines 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.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 2005-DECEMBER 2005 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.OOE-04 gLCi/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:

(1) Fission and activation products (mixture EC)

(OCi/ml)

(2) Tritium (VCi/ml)

Ouarter 1 None 1.001E-02 Ouarter 2 None 1.00E-02 Ouarter 3 Ouarter 4 None None 1.001E-02 1.OOE-02 (3) Dissolved and entrained gases (glCi/ml) 2.OOE-04 2.OOE-04 2.00E-04 2.OOE-04 2

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 SUPPLEMENTAL INFORMATION (continued)

3. Average Energy (None specified)
4. Measuremghts 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

P.

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 SUPPLEMENTAL INFORMATION (continued)

5. Batch Releases
a. Liquid:

Canal (1) Number of batch releases:

(2) Total time period for batch release: (min)

(3) Maximum time period for batch release: (min)

(4) Average time period for batch release: (min)

(5) Minimum time period for batch release: (min)

(6) Total Activity Released (Ci)

(7) Total Volume Released (liters) b._Liquid:

Non-Canal (1) Number of batch releases:

(2) Total time period for batch release: (min)

(3) Maximum time period for batch release: (min)

(4) Average time period for batch release: (min)

(5) Minimum time period for batch release: (min)

(6) Total Activity Released (Ci)

(7) Total Volume Released (liters)

Ouarter 1 6.OOE+00 2.13E+02 Ouarter 2 7.00E+00 9.50E+01 Ouarter 3 1.40E+01 2.06E+02 Ouarter 4 5.OOE+00 1.86E+02 7.50E+01 4.OOE+01 5.00E+01 6.00E+01 3.55E+01 1.36E+01 1.47E+01 3.72E+01 3.OOE+00 1.00E+00 1.00E+00 3.OOE+00 7.76E-05 1.29E+04 8.OOE+00 7.05E+05 5.04E+04 1.09E-04 1.07E+04 9.OOE+00 2.04E+04 6.62E-04 5.02E+04 1.80E+01 1.67E+03 1.1 8E-04 1.04E+04 5.OOE+00 3.03E+02 2.02E+04 4.37E+02 1.13E+02 8.8 lE+03 2.26E+03 9.27E+01 6.06E+01 3.OOE+00 1.00E+00 1.00E+00 1.00E+00 2.15E-03 1.82E+06 8.21E-04 4.85E+05 5.87E-03 5.17E+05 2.53E-04 1.14E+05 4

-ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 SUPPLEMENTAL INFORMATION (continued)

c. Gaseous:

There were no gaseous batch releases for this report period.

6. Abnormal Releases
a.

Liquid:

Ouarter I Ouarter 2 Ouarter 3 Ouarter 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

V ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES EST TOTAL UNIT OTR 1 OR 2 OTR 3 OTR4 ERROR %

A.

FISSION AND ACTIVATION GASES

1. Total Release
2. Average release rate for period
3. Applicable ODCM Limit Ci 1.13E+03 2.49E+02 2.22E+03 7.71E+02

<2.50E+01 pCi/sec 1.44E+02 3.17E+01 2.79E+02 9.70E+01 B. IODINE-131

1. Total lodine-131
2.

Average release rate for period

3.

Applicable ODCM Limit Ci 2.72E-03 7.85E-04 5.35E-03 4.93E-04

  • 2.50E+01 pCi/sec 3.46E-04 9.99E-05 6.73E-04 6.21 E-05 C. PARTICULATES
1.

Particulates with half-lives

>8 days

2.

Average release rate for

)

period

3.

Applicable ODCM Limit

4.

Gross alpha radioactivity Ci 6.52E-04 1.12E-03 9.94E-04 7.53E-04 s3.60E+01 pCi/sec 8.29E-05 1.42E-04 1.25E-04 9.47E-05 Ci 3.14E-07 3.82E-07 4.40E-07 6.54E-07

52.50E+01 D. TRITIUM
1.

Total Release

2.

Average release rate for period

3.

Applicable ODCM Limit Ci 3.81 E+00 3.24E+00 4.54E+00 5.55E+00

<2.50E+01 piCi/sec 4.84E-01 4.12E-01 5.71E-01 6.98E-01

  • E PERCENT OF APPLICABLE ODCM LIMITS FISSION AND ACTIVATION GASES
1. Quarterly gamma air dose limit 4.27E-01
2.

Quarterly beta air dose limit 6.71 E-02

3.

Yearly gamma air dose limit 2.13E-01

4.

Yearly beta air dose limit 3.36E-02

5.

Whole body dose rate limit 1.41E-01

6.

Skin dose rate limit 3.04E-02 HALOGENS, TRITIUM AND PARTICULATES WITH HALF-LIVES >8 DAYS

7.

Quarterly dose limit (organ) 3.69E-01

8. Yearly dose limit (organ) 1.84E-01
9. Organ dose rate limit 3.72E-04 5.31 E-02 3.42E-02 2.65E-02 1.71E-02 9.86E-03 2.57E-03 1.37E-41 6.87E-02 6.29E-05 1.10E+00 1.25E-01 5.51 E-01 6.25E-02 8.79E-01 1.89E-01 7.25E-01 3.63E-01 4.07E-04 3.03E-01 1.07E-01 1.52E-01 5.35E-02 7.64E-02 2.75E-02 8.34E-02 4.17E-02 6.08E-05 6

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 TABLE 1B GASiOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE NUCLIDES RELEASED UNIT OUARTERI OUARTER2 OUARTER3 OUARTER4

1. Fission Gases Argon-41 Ci 1.19E+00 2.01E+00 1.81E+00 4.60E+00 Krypton-85m Ci 8.84E+01 4.83E+01 1.87E+02 1.88E+02 Krypton-87 Ci 1.61E+02 1.09E+00 2.40E+02 1.78E+01 Krypton-88 Ci 2.07E+02 3.07E+01 3.60E+02 2.24E+02 Xenon-133 Ci 5.98E+01 4.89E+01 1.01E+02 1.51E+02 Xenon-133m Ci 4.13E-01 Xenon-135 Ci 4.49E+02 9.46E-01 3.24E+02 8.13E+00 Xenon-135m Ci 2.09E+01 3.55E+00 2.16E+02 8.08E+00 Xenon-137 Ci 1.62E+01 2.08E+01 2.80E+01 2.02E+01 Xenon-138 Ci 5.99E+01 1.19E+01 6.92E+02 2.46E+01 TOTAL Ci 1.06E+03 1.68E+02 2.15E+03 6.46E+02
2. lodines lodine-131 Ci 2.38E-03 1.82E-04 4.29E-03 1.49E-04 lodine-133 Ci 1.52E-02 5.73E-04 8.41E-03 2.20E-04 Iodine-135 Ci 6.90E-03 1.41 E-04 7.07E-03 1.71 E-05 TOTAL Ci 2.45E-02 8.96E-04 1.98E-02 3.86E-04
3. Particulates Chromium-51 Ci 1.57E-05 Manganese-54 Ci 5.19E-07 1.50E-07 Strontium-89 Ci 5.70E-05 3.68E-05 5.99E-05 6.76E-05 Strontium-90 Ci 1.84E-07 6.50E-08 8.48E-08 1.97E-07 Cesium-136 Ci 6.23E-07 Cesium-137 Ci 6.09E-07 Barium-140 Ci 2.82E-05 3.19E-05 6.92E-05 4.62E-05 TOTAL Ci 8.59E-05 6.88E-05 1.46E-04 1.15E-04
4. Tritium Hydrogen-3 Ci 4.65E-01 3.91E-01 1.02E+00 7.51 E-01 Note: There were no batch releases for this report period.

7

wENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 TABLE IC GASECRJS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED OUNT OUARTERI OUARTER2 OUARTER3 OUARTER4

1. Fission Gases Krypton-87 Ci 4.52E+00 2.74E+00 Krypton-88 Ci 8.89E-01 Xenon-133 Ci 1.29E-01 4.97E+00 6.31E+00 2.43E+00 Xenon-135 Ci 5.88E+00 7.21E+00 7.64E+00 5.23E+00 Xenon-135M Ci 1.32E+01 2.37E+01 1.24E+01 1.24E+01 Xenon-137 Ci 2.06E+01 4.50E+01 Xenon-138 Ci 5.31E+01 4.06E+01 2.76E+01 5.61E+01 TOTAL Ci 7.23E+01 8.10E+01 7.46E+01 1.25E+02
2. Jodines Iodine-131 Ci 3.39E-04 6.03E-04 1.06E-03 3.44E-04 lodine-133 Ci 1.47E-03 2.02E-03 3.37E-03 1.04E-03 Iodine-135 Ci 7.32E-05 1.90E-04 1.86E-04 TOTAL Ci 1.81 E-03 2.70E-03 4.62E-03 1.57E-03
3. Particulates Manganese-54 Ci 1.28E-06 Cobalt-57 Ci 1.08E-06 Strontium-89 Ci 3.91 E-04 6.89E-04 6.04E-04 3.69E-04 Strontium-90 Ci 4.49E-07 9.66E-07 5.03E-07 1.51 E-07 Barium-140 Ci 1.75E-04 3.58E-04 2.42E-04 2.69E-04 TOTAL Ci 5.66E-04 1.05E-03 8.48E-04 6.38E-04
4. Tritium Hydrogen-3 Ci 3.34E+00 2.85E+00 3.52E+00 4.80E+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 2005-DECEMBER 2005 TABLE 2A LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES EST TOTAL TR 2 0TR 3 OTR 4 ERROR %

UNIT OTR0 A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not including tritium, gases and alpha)
2.

Average diluted concentration during period

3. Applicable ODCM Limit Ci NONE NONE NONE NONE

<2.50E+01 NONE pCi/mi NONE NONE NONE B. TRITIUM

1. Total Release
2. Average diluted concentration during period (Note 1)
3.

Applicable ODCM Limit Ci 2.23E-03 9.30E-04 6.53E-03 3.71 E-04

<2.50E+01 pai/mi 1.17E-06 1.66E-06 1.03E-05 2.03E-06 DISSOLVED AND ENTRAINED GASES

1. Total Release
2. Average diluted concentration during period
3. Applicable ODCM Limit Ci NONE NONE NONE NONE NONE
  • 2.50E+01 j.LCiml NONE NONE NONE D. GROSS ALPHA RADIOACTIVITY
1. Total Release E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION)

Ci NONE NONE NONE NONE

  • 4.20E+01 lters 1.83E+06 4.96E+05 5.68E+05 1.25E+05 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 2.77E+08 1.34E+08 3.47E+08 1.63E+08
  • G. PERCENT OF APPLICABLE ODCM LIMS
1. Quarterly Whole Body Dose
2.

Quarterly Organ Dose

3. Annual Whole Body Dose
4.

Annual Organ Dose 6.60E-05

% 1.98E-05

% 3.30E-05

% 9.89E-06 8.19E-05 2.46E-05 4.10E-05 I1.23E-05 8.78E-04 2.63E-04 4.39E-04 I1.32E-04 9.28E-05 2.78E-05 4.64E-05 I1.39E-05 (Note 1) Concentration includes summation from diluted and undiluted values from Canal and Non-Canal releases (Table 2B).

9

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 TABLE 2B LIQUID EFFLUENTS CANAL BATCH MODE QUARTER 2 OUARTER 3 NUCLIDES RELEASED UNIT QUARTER I QUARTER 4

1. Fission and Activation Products NONE
2. Tritium HYDROGEN-3
3. Dissolved and Entrained Gases NONE Ci Ci 7.76E-05 1.09E-04 6.62E-04 1.18E-04 Ci Note: There were no continuous mode discharges during this report period.

)

10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 TABLE 2B (SUPPLEMENT)

-LIQUID EFFLUENTS NON-CANAL BATCH MODE OUARTER 2 QUARTER 3 NUCLIDES RELEASED UNIT OUARTERI OUARTER 4

1. Fission and Activation Products NONE
2. Tritium HYDROGEN-3
3. Dissolved and Entrained Gases Ci Ci 2.15E-03 8.21 E-04 5.87E-03 2.53E-04 NONE Ci Note: There were no continuous mode discharges during this report period.

11

I

.ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005

)

TABLE 3A SOLIITWASTE AND IRRADIATED FUEL SHIPMENTS A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

1.

Type of Waste

a. Spent resins, filter sludges evaporator bottoms, etc.

Unit mA3 Ci Class A 0.OOE+00 0.OOE+00 Class B 0.0oE+oO O.OOE+00 Class C O.OOE+00 O.OOE+00 Est. Total Error %

O.OOE+00 0.OOE+00

b. Dry compressible waste, contaminated equipment, etc.

mA3 0.OOE+00 0.OOE+00 Ci O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 0.OOE+00 O.OOE+00

c. Irradiated components, control rods, etc.

mA3 O.OOE+00 Ci 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

d. Other: Dry compressible waste, contaminated equipment, spent resins for volume reduction.

mA3 6.23E+02 Ci 1.31E+02 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+O0 1.OOE+01 1.OOE+01

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 Iron-55 Cobalt-60 Manganese-54 Cesium-137 Zinc-65 Iron-59 Cerium-144 Chromium-51 Percent 6.17E+01 9.40E+O0 7.73E+00 1.98E+00 1.58E+01 2.97E-01 2.56E-01 6.14E-02 Curies 8.11E+01 1.23E+01 1.01E+01 2.60E+00 2.07E+01 3.90E-01 3.36E-01 8.06E-02 E

E E

E E

E E

E Isotope Nickel-63 Tritium Cesium-134 Nickel-59 Carbon-14 Antimony-125 Cobalt-58 Strontium-90 Percent 8.40E-01 2.1 5E-01 1.03E+00 7.15E-02 1.62E-03 1.61E-02 3.92E-01 1.79E-01 Cunes 1.10E+00 2.82E-01 1.35E+00 9.39E-02 2.12E-03 2.12E-02 5.14E-01 2.35E-01 E

E E

E E

E E

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.

12

a ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 N)

TABLE 3A (continued)

SOLIDWASTE AND IRRADIATED FUEL SHIPMENTS

3.

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

Truck

  • RACE LLC Memphis, TN 8

Truck

  • Duratek Oak Ridge, TN 13 Truck
  • Studsvik Erwin, TN 10 Truck
  • Alaron Wampum, PA I

Truck

  • DSSI Kingston, TN
  • - Volume Reduction Facility B.

IRRADIATED FUEL SHIPMENTS (Disposition)

No. of Shipments Mode of Transportation Destination NONE 13

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 TABLE 3B SOLID5WASTE AND IRRADIATED FUEL SHIPMENTS NRC CLASS A SOURCE OF WASTE PROCESSING EMPLOYED CONTAINER VOLUME TYPE OF CONTAINER NUMBER OF CONTAINERS Spent Resins, Filter Sludges, evaporator Bottoms, etc.

Dry compressible Waste (DAW),

Contaminated Equipment, etc.

Dry compressible Waste(DAW),

Contaminated Eqiupment, etc.

Contaminated Oil

)wry compressible Waste(DAW),

Contaminated Equipment Dry compressible Waste(DAW),

Contaminated Equipment Air Drying Non-compacted Non-compacted Non-compacted Non-compacted Non-compacted Non-compacted 205.8 ftA3 1280 ftA3 96 ftA3 HIC 14 STC STC 10 50 7 fRA3 STC 33 206.1 ftA3 STC l

88 ftA3 STC 12 B.

NRC CLASS B SOURCE OF WASTE PROCESSING EMPLOYED CONTAINER VOLUME TYPE OF CONTAINER NUMBER OF CONTAINERS NONE C.

NRC CLASS C SOURCE OF WASTE PROCESSING EMPLOYED CONTAINER VOLUME TYPE OF CONTAINER NUMBER OF CONTAINERS NONE

, _olidification Agent:

HIC-High Integrity Container STC-Strong Tight Container NONE 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 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 Effluent Controls (REC) Section 6.2.3, changes made to the Offsite Dose Calculation Manual (ODCM) during the reporting period shall be included in the Annual Radioactive Effluent Release Report.

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

15

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 ATTACHMENT NO. 2

SUMMARY

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

There were no changes to the Process Control Program Procedure or implementing procedures.

16

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 ATTACHMENT NO. 3

SUMMARY

OF CHANGES TO TlHE 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 2005 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.

17

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 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.l, allows for deviations from the program due to hazardous conditions, seasonal unavailability, theft, uncooperative residents, or to malfunction of automatic sampling equipment.

EXCEPTIONS TO THE 2005 ENVIRONMENTAL SAMPLING PROGRAM The following are deviations from the program specified by the ODCM:

Air Sampling Stations

1. 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 /> during the sample period of 2/l/05 through 2/8/05. 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 broken wires on the transmission line to the air station. No corrective action was implemented.
2. 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 /> during the sample period of 5/17/05 through 5/24/05. 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 short power outage as a downed tree interrupted power during the sample period. No corrective action was implemented.
3. The air sampling pump at the R5 Environmental Sampling Station was temporarily inoperable during the sample period of 6/28/05 through 7/6/05. The inoperability was caused by a power outage in the local electrical power distribution system. The length of inoperability was approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Operability was restored as power was restored to the electrical grid. No corrective action was implemented.

18

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 ATTACHMENT NO. 4 (Continued)

EXCEPTIONS TO THE 2005 ENVIRONMENTAL SAMPLING PROGRAM

4. The air sampling pump at the R5 Environmental Sampling Station was temporarily inoperable during the sample period of 7/12/05 through 7/19/05. The inoperability was caused by a power outage in the local electrical power distribution system. The length of inoperability was approximately 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />. Operability was restored as power was restored to the electrical grid. No corrective action was implemented.
5. The air sampling pump at the R3 Environmental Sampling Station was temporarily inoperable during the sample period of 8/16/05 through 8/23/05. The inoperability was caused by a power outage in the local electrical power distribution system. The length of inoperability was approximately 7.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Operability was restored as power was restored to the electrical grid. No corrective action was implemented.
6. The air sampling pumps at the R3, R4, and R5 Environmental Sampling Stations were temporarily inoperable during the sample period of 7/26/05 through 8/2/05. The inoperability was caused by a power outage in the local electrical power distribution system. The length of inoperability was approximately 2.8, 1.6, and 2.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, respectively. Operability was restored as power was restored to the electrical grid. No corrective action was implemented.
7. The air sampling pumps at the R3 and R4 Environmental Sampling Stations were temporarily inoperable during the sample period of 8/23/05 through 8/30/05. The inoperability was caused by a power outage in the local electrical power distribution system. The length of inoperability was approximately 13 and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, respectively.

Operability was restored as power was restored to the electrical grid. No corrective action was implemented.

8. The air sampling pump at the R4 Environmental Sampling Station was temporarily inoperable during the sample period of 9/27/05 through 10/4/05. The inoperability was caused by a power outage in the local electrical power distribution system. The length of inoperability was approximately 4.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Operability was restored as power was restored to the electrical grid. No corrective action was implemented.

19

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 ATTACHMENT NO. 4 (Continued)

EXCEPTIONS TO THE 2005 ENVIRONMENTAL SAMPLING PROGRAM

9. The air sampling pump at the R5 Environmental Sampling Station was temporarily inoperable during the sample period of 11/29/05 through 12/6/05. The inoperability was caused by a power outage in the local electrical power distribution system. The length of inoperability was approximately 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Operability was restored as power was restored to the electrical grid. No corrective action was implemented.
10. The air sampling pumps at the RI and R2 Environmental Sampling Stations were temporarily inoperable during the sample period of 12/20/05 through 12/28/05. The inoperability was caused by a power outage in the local electrical power distribution system. The length of inoperability was approximately 1.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Operability was restored as power was restored to the electrical grid. No corrective action was implemented.

The unavailability of these samples was the result of equipment failure. No replacement samples or changes in sample locations were required. The ODCM was not revised as a result of the sample unavailability.

20

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 ATTACHMENT NO. 5 ANNUAL

SUMMARY

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

Part 1, Radiological Effluent Controls (REC) Section 6.2 and 6.2.2 states in part: The 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, ENO 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.

21

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 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 I Radiological Effluent Controls (REC) Section 7.0, Major Modifications to Radioactive Waste Treatment Systems (liquid, gaseous and solid) shall be reported in the Annual Radioactive Effluent Release Report for the period in which the modification is completed and made operational.

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

22

.ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 ADDENDUM 1 ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2005

1.

INTRODUCTION The James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Effluent 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 LIOUID EFFLUENTS (ODCM, Part 1, REC 2.3)

Avplicabilitv Applies to doses from radioactive material in liquid effluents.

)

Obiective 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)

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

23

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 ADDENDUM S (continued)

Obiective 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 mnrem/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.

Obiective 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.

24

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 ADDENDUM 1 (continued)

D.

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

ARplicabilily 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.

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

Snecifications 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.

25

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 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 I0CFR50, 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, 2005 to December 31, 2005.

Historical meteorological data was used to generate tables of average dispersion factors. Locations of interest were identified from the 2005 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.

26

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005

)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) 27

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005

)

'ADDENDUM 1 (continued)

TABLE I ANNUAL DOSE ASSESSMENT 2005 A. LIQUIDS QUARTER I

(a)

Organ (mrem)

% of Limit 9.89E-0'j I1.98E-O!

2 (a) 7 1.23E-06 5

2.46E-05 (b) 3 (a) 1.32E-05 2.63E-04 (b) 4 (a) 1.39E-06 2.78E-05 (b)

ANNUAL (a) 1.68E-05 1.68E-04 (b)

(b)

Whole Body (mrem)

% of Limit 9.89E-07 6.60E-05 1.23E-06 8.19E-05 1.32E-05 8.78E-04 1.39E-06 9.22E-05 1.68E-05 5.59E-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 Total Body (mrem/yr)

% of Limit 1

7.03E-01 1.41E-01 2

4.93E-02 9.86E-03 3

4.39E+00 8.79E-01 4

ANNUAL 3.82E-01 7.64E-02 4.39E+00 8.79E-01 Skin (mrem/yr)

% of Limit 9.12E-01 7.71E-02 3.04E-02 2.57E-03 5.67E+00 8.24E-01 5.67E+00 1.89E-01 2.75E-02 1.89E-01 Gamma (mrad)

% of Limit Beta (rnrad)

% of Limit 2.13E-02 4.27E-01 6.71E-03 6.71E-02 2.65E-03 5.3 lE-02 3.42E-03 3.42E-02 5.51E-02 1.52E-02 1.10E+00 3.03E-01 9.43E-02 9.43E-01 3.33E-02 1.67E-01 1.25E-02 1.25E-01 I.07E-02 1.07E-01 28

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005

)

ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 2005 C. IODINES AND PARTICULATES OUARTER I

(a) 2 (b) 1.03E-02 1.37E-01 (c) 3 (a) 5.44E-02 7.25E-01 (c) 4 ANNUAL Organ (mrem)

% of Limit 2.77E-02 3.69E-01 (b) 6.26E-03 8.34E-02 (c)

(a) 9.86E-02 6.58E-01 (c)

(c)

Organ Dose Rate (mremn/yr)

% of Limit 5.58E-03 9.44E-04 6.1 1E-03 9.12E-04 6.1 IE-03 3.72E-04 6.29E-05 4.07E-04 6.08E-05 4.07E-04 (a)

(b)

(C)

Dose to the Infant Thyroid primarily by the goats milk pathway.

Dose to the Infant Thyroid primarily by the cows milk pathway.

Dose to the Child Total Body primarily by the vegetation pathway.

29

)

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 ADDENDUM 1 (continued)

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

DISPERSION FACTOR RECEPTOR A.

IODINE &

DISTANCE/

RELEASE X/Q D/Q PARTICULATES DIRECTION POINT (sec/mr3)

(/rM 2)

1. Garden Grazing Season Cary Location No. 78
2. Meat Grazing Season Parkhurst Location No. 26
3. Cow Grazing Season France Location No. 10
4. Goat (D/Q)

Grazing Season Showers Location No. 71

5. Goat (X/Q)

Grazing Season Nickolas Location No. 61 0.90 mi @ 83-E 0.90 mi @ 83°E 0.90 mi @ 830E 0.90 mi @ 83-E 0.90 mi @ 83°E ST RX TB RF RW 2.83E-08*

2.02E-07*

1.83E-07*

2.02E-07*

3.2 1E-07*

1.75E-09 5.01E-09 4.80E-09 5.O1E-09 5.76E-09 1.18 mi @ 127°SE 1.18 mi @ 127°SE 1.18 mi @ 127°SE 1.18 mi @ 127°SE 1.18 mi @ 1270SE 2.50 mi @ 139°SE 2.50 mi @ 139°SE 2.50 mi @ 139°SE 2.50 mi @ 1390SE 2.50 mi @ 1390SE 3.62 mi @ 1130ESE 3.62 mi @ 113°ESE 3.62 mi @ 113°ESE 3.62 mi @ 1130ESE 3.62 mi @ 1130ESE 2.64 mi @ 152°SSE 2.64 mi @ 152°SSE 2.64 mi @ 152°SSE 2.64 mi @ 152°SSE 2.64 mi @ 152°SSE ST RX TB RF RW ST RX TB RF RW ST RX TB RF RW ST RX TB RF RW 1.72E-08*

5.36E-08*

5.14E-08*

5.36E-08*

9.12E-08*

1.67E-08*

2.76E-08*

2.71E-08*

2.76E-08*

4.15E-08*

6.80E-10 1.30E-09 1.27E-09 1.30E-09 1.46E-09 2.65E-10 4.14E-10 4.07E-10 4.14E-10 4.36E-10 2.28E-10 3.40E-10 3.33E-10 3.40E-10 3.49E-10 1.94E-08*

2.58E-08*

2.57E-08*

2.58E-08*

3.59E-08*

30

)

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 ADDENDUM 1 (continued)

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

DISPERSION FACTOR RECEPTOR A.

IODINE &

DISTANCE/

RELEASE X/Q D/Q PARTICULATES DIRECTION POINT (sec/m3)

(1/m2)

6. Resident Annual Average
a. Inhalation(2)

Cary Location No. 78 1.55 mi @ 900E(l) 0.90 mi@ 830E 0.90 mi @ 83°E 0.90 mi @ 830E 0.90 mi @ 830E ST RX TB RF RW 2.99E-08 2.07E-07 1.88E-07 2.07E-07 3.06E-07

b. Deposition(3)

Whaley Location No. 199 0.71 mi @ 1180ESE 0.71 mi @ 1180ESE 0.71 mi @ 1180ESE 0.71 mi @ 1180ESE 0.71 mi @ 118°ESE ST RX TB RF RW 1.60E-09 5.52E-09 5.30E-09 5.52E-09 6.28E-09 B. NOBLE GASES

1. Air Dose Annual Average Site Boundary
2. Total Body Annual Average Site Boundary 1.55 mi @ 900E(I) 0.60 mi @ 900E 0.60 mi @ 900E 0.60 mi @ 90°E 0.60 mi @ 900E 0.60 mi @ 900E 0.60 mi @ 900E 0.60 mi @ 900E 0.60 mi @ 900E 0.60 mi @ 900E 0.60 mi @ 900E ST ST(fc)

RX TB RF RW ST(fc)

RX TB RF RW 2.99E-08 1.16E-07 3.58E-07 3.19E-07 3.58E-07 5.39E-07 1.16E-07 3.58E-07 3.19E-07 3.58E-07 5.39E-07 31

e i

N)

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 ADDENDUM 1 (continued)

TABLE 2 METEOROLOGICAL DATA AND LOCATIONS OF INTEREST GEOGRAPHIC LOCATION ATMOSPHERIC" DISPERSION FACTOR RECEPTOR B.

NOBLE GASES DISTANCE/

RELEASE X/Q D/Q (continued)

DIRECTION POINT (sec/m3)

(1/m2)

3. Skin 1.55 mi ( 901E ST 2.99E-08 Annual Average 0.60 mi @ 900E ST(fc) 1.16E-07 Site Boundary 0.60 mi ( 901E RX 3.58E-07 0.60 mi @ 900E TB 3.19E-07 0.60 mi @ 90 0E RF 3.58E-07 0.60 mi @ 90'E RW 5.39E-07 Tritium Dose Calculation 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 32

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