JAFP-06-0067, Annual Radioactive Effluent Release Report for 2005

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Annual Radioactive Effluent Release Report for 2005
ML062630300
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/26/2006
From: Peter Dietrich
Entergy Nuclear Northeast, Entergy Nuclear Operations
To: Collins S
Region 1 Administrator
References
JAFP-06-0067
Download: ML062630300 (34)
v • d • e


Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. Fitzpatrick NPP Enterg P.O. Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 Pete Dietrich April 26, 2006 Site Vice President - JAF JAFP-06-0067 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 commitmae~t cx, *nedi this letter.

Site Vice President PD! CAB/jbh Attachments Xc: Document Control Desk (USNRC) NRC Resident Inspector D. Sherman (AMI Library) P. Merges (NYSDEC)

K. Mulligan (JAF) T. Kurtz (NMPC)

C. Faison (ENOC/WPO) J. Furfaro (ENOC/WPO)

J. McCann (ENOCIWPO) W. Hamblin (CHEM/JAF)

J. Boska, Project Manager, NRR

v ENTERGY NUCLEAR OPERATIONS, INC.

JAMIES A. FTITZPATRICK 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 nirad 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- 13 1, 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 nirem to any organ; and, (b) During any calendar year to less than or equal to 15 nirem. to any organ.

(c) Less than 0. 1%of the limits of Specification 3.4.lI.c.1La and 3.4.lI.c. Lb 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 mirem/year to any organ from Iodine- 13 1, 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 ýtCi/mnl.

(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 niremn to any organ.

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

(Rji/im)

(2) Tritium (pCi/ml) 1.O0-02 1 OOE-02 1.OOE-02 1.OOE-02 (3) Dissolved and entrained gases (iiCi/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 2005-DECEMBER 2005 SUTPPLEMENTAL INFORMATION (continued)

3. Average Energy (None specified)
4. Measurements and Approximatio-hs 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 2005-DECEMBER 2005 SUPPLEMENTAL INFORMATION (continued)

5. Batch Releases
a. Liquid: Canal Ouarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 6.OOE+00 7.OOE+00 1.40E+01 5.0013+00 (2) Total time period for batch 2.1 3E+02 9.50E+0 1 2.06E+02 1.86E+02 release: (min)

(3) Maximum time period for 7.50E+01 4.OOE+Ol 5.OOE+O1 6.OOE+01 batch release: (min)

(4) Average time period for 3.55E+01 1.36E+0 1 1.47E+0 1 3.72E+01 batch release: (min)

(5) Minimum time period for 3.001E+00 1.OOE+O0 1.OOE+O0 3.00E+00 batch release: (min)

(6) Total Activity Released (Ci) 7.76E-05 1.09E-04 6.62E-04 1.1 8E-04 (7) Total Volume Released (liters) 1.29E+04 1.07E+04 5.02E+04 1.04E+04 b...Liquid: Non-Canal (1) Number of batch releases: 8.OOE+00 9.OOE+00 1.80E+01 5.OOE+O0 (2) Total time period for batch 7.05E+05 2.04E+04 1.67E+03 3.03E+02 release: (min)

(3) Maximum time period for 5.04E+04 2.02E+04 4.37E+02 1.13E+02 batch release: (min)

(4) Average time period for 8.81 E+03 2.26E+03 9.27E+01I 6.06E+0 1 batch release: (min)

(5) Minimum time period for 3 .00E+00 1.OOE+00 1.OOE+00 1.OOE+00 batch release: (min)

(6) Total Activity Released (Ci) 2.15E-03 8.2 1E-04 5.87E-03 2.53E-04 (7) Total Volume Released (liters) 1.82E+06 4.85E+05 5.17E+05 1.14E+05 4

ENTERGY NUCLEAR OPERATIONS, INC.

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

c. Gaseous:

There were no gaseous batch releases for this report period.

6. Abnormal Releases
a. Liquid: Quarter 1 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

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 OTR 2 QTR 3 OTR4 ERROR %

A. FISSION AND ACTIVATION GASES

1. Total Release Ci 1.13E+03 2.49E+02 2.22E+03 7.71 E+02 :52.50E+01
2. Average release rate for period jpCi/sec: 1.44E+02 3.17E+01 2.79E+02 9.70E+01
3. Applicable ODCM Limit B. IODINE-131
1. Total lodine-131 Ci 2.72E-03 7.85E-04 5.35E-03 4.93E-04 :!2.50E+01
2. Average release rate for period pCi/sec 3.46E-04 9-99E-05 6.73E-04 6.21E-05
3. Applicable ODCM Limit C. PARTICULATES
1. Particulates with half-lives

>8 days Ci 6.52E-04 1.12E-03 9.94E-04 7.53E-04 :53.60E+01

2. Average release rate for period pCi/sec 8.29E-05 1.42E-04 1.25E-04 9.47E-05
3. Applicable ODCM Limit
4. Gross alpha radioactivity Ci 3.14E-07 3.82E-07 4.40E-07 6.54E-07 :52.50E+01 D. TRITIUM
1. Total Release Ci 3.81 E+00 3.24E+00 4.54E+00 5.55E+00  :!2.50E+01
2. Average release rate for period pCi/sec: 4.84E-01 4.12E-01 5.71 E-01 6.98E-01
3. Applicable ODCM Limit
  • E. PERCENT OF APPLICABLE ODCM LIMITS FISSION AND ACTIVATION GASES
1. Quarterly gamma air dose limit 4.27E-01 5.31 E-02 1.10E+00 3.03E-01
2. Quarterly beta air dose limit 6.71 E-02 3.42E-02 1.25E-01 1.07E-01
3. Yearly gamma air dose limit 2.13E-01 2.65E-02 5.51 E-01 1.52E-01
4. Yearly beta air dose limit 3.36E-02 1.71 E-02 6.25E-02 5.35E-02
5. Whole body dose rate limit 1.41 E-01 9.86E-03 8.79E-01 7.64 E-02
6. Skin dose rate limit 3.04E-02 2.57E-03 1.89E-01 2.75E-02 HALOGENS, TRITIUM AND PARTICULATES WITH HALF-LIVES >8 DAYS
7. Quarterly dose limit (organ)  % 3.69E-01 1.37E-01 7.25E-01 8.34E-02
8. Yearly dose limit (organ) " 1.84E-01 6.87E-02 3.63E-01 4.1 7E-02
9. Organ dose rate limit " 3.72E-04 6.29E-05 4.07E-04 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 GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE NUCLIDES RELEASED UNIT OUARTER 1 QUARTER 2 OUARTER 3 OUARTER 4

1. Fission Gases Argo n-41 Ci 1.19E+00 2.01 E+00 1.81 E+00 4.60E+00 Krypton-85m Ci 8.84E+01 4.83E+01 1.87E+02 I1.88E+02 Krypton-87 Ci 1.61 E+02 I1.09E+00 2.40E+02 I1.78E+01 Krypton-88 Ci 2.07E+02 3.07E+01 3.60E+02 2.24E+02 Xenon-I 33 Ci 5.98E+01 4.89E+01 1.01 E+02 1.51 E+02 Xenon-I 33m Ci 4.1 3E-01 Xenon-1 35 Ci 4.49E+02 9.46E-01 3.24E+02 8.1 3E+00 Xenon-I 35m Ci 2.09E+01 3.55E+00 2.16E+02 8.08E+00 Xenon-I 37 Ci I1.62E+01 2.08E+01 2.80E+01 2.02E+01 Xenon-I 38 Ci 5.99E+01 1.19E+01 6.92E+02 2.46E+01 TOTAL Ci I1.06E+03 1.68E+02 2.15E+03 6.46E+02
2. lodines Iodine-I 31 Ci 2.38E-03 I1.82E-04 4.29E-03 I1.49E-04 Iodine-I 33 Ci 1 .52E-02 5.73E-04 8.41 E-03 2.20E-04 Iodine-I 35 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-5I Ci I1.57E-05 Manganese-54 Ci 5.19E-07 I1.50E-07 Strontiumn-89 Ci 5.70E-05 3.68E-05 5.99E-05 6.76E-05 Strontium-90 Ci I1.84E-07 6.50E-08 8.48E-08 I1.97E-07 Cesium-I 36 Ci 6.23E-07 Cesium-I 37 Ci 6.09E-07 Barium-I 40 Ci 2.82E-05 3.19E-05 6.92 E-05 4.62E-05 TOTAL Ci 8.59E-05 6.88E-05 1.46E-04 1.15E-04
4. Tritiunm Hydrogen-3 Ci 4.65E-01 3.91 E-01 1.02E+00 7.51 E-0 I 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 2005-DECEMBER 2005 TABLE 1C GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED UNIT OUARTER I OUARTER2 OUAR ER 3 OUARTER 4

1. Fission Gases Krypton-87 Ci 4.52E+00 2.74E+00 Krypton-88 Ci 8.89E-01 Xenon-I 33 Ci 1.29E-01 4.97E+00 6.31 E+00 2.43E+00 Xenon-I 35 Ci 5.88E+00 7.21 E+00 7.64E+00 5.23E+00 Xenon-I 35M Ci 1.32E+01 2.37E+01 1 .24E+01 1.24E+01 Xenon-1 37 Ci 2.06E+01 4.50E+01 Xenon-I 38 Ci 5.31 E+01 4.06E+01 2.76E+01 5.61 E+01 TOTAL Ci 7.23E+01 8.1OE+01 7.46E+01 1.25E+02
2. lodines Iodine-I 31 Ci 3.39E-04 6.03E-04 1 .06E-03 3.44E-04 Iodine-I 33 Ci 1.47E-03 2.02E-03 3.37E-03 1.04E-03 Iodine-I 35 Qi 7.32E-05 I1.90E-04 I1.86E-04 TOTAL Ci 1.81 E-03 2.70E-03 4.62 E-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 6.04 E-04 3.69E-04 Strontium-90 Ci 4.49E-07 9.66E-07 5.03E-07 1.51 E-07 Barium-I 40 Ci 1 .75E-04 3.58E-04 2.42E-04 2.69E-04 TOTAL Ci 5.66E-04 1.05E-03 8.48E-04 6.38 E-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 UNIT 0Th1 OTR 2 OTR 3 0LTR 4 ERROR %

A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not including tritium, gases and alpha) Ci NONE NONE NONE NONE :52.50E+01
2. Average diluted concentration during period gci/mi NONE NONE NONE NONE
3. Applicable ODCM Limit B. TRITIUM
1. Total Release Ci 2.23E-03 9.30E-04 6.53E-03 3.71E-04 :52.50E+01
2. Average diluted concentration during period (Note 1) pCi/mi 1.17E-06 1.66E-06 1.03E-05 2.03E-06
3. Applicable ODCM Limit C. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci NONE NONE NONE NONE :52.50E+01
2. Average diluted concentration during period pLCi/mi NONE NONE NONE NONE
3. Applicable ODCM Limit D. GROSS ALPHA RADIOACTIVITY
1. Total Release Ci NONE NONE NONE NONE -<4.20E+01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) liters 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 LIMITS
1. Quarterly Whole Body Dose 6.60E-05 8.19E-05 8.78E-04 9.28E-05
2. Quarterly Organ Dose 1.98E-05 2.46E-05 2.63E-04 2.78E-05
3. Annual Whole Body Dose 3.30E-05 4.1 OE-05 4.39E-04 4.64E-05
4. Annual Organ Dose 9.89E-06 1.23E-05 1.32E-04 1.39E-05 (Note 1) Concentration includes summation from diluted and undiluted values from Canal and Non-Canal releases (Table 213).

9

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMB3ER 2005 TABLE 2B LIQUID EFFLUENTS CANAL BATCH MODE NUCLIDES RELEASED UNIT OU1ARTER I QUARTER 2 QUARTER 3, OUARTER 4

1. Fission and Activation Products NONE Ci
2. Tritium HYDROGEN-3 Ci 7.76E-05 1.09E-04 6.62E-04 1.18E-04
3. Dissolved and Entrained Gases NONE 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 NUCLIDES RELEASED UNIT OUARI-ER I QUARTER 2 OUARTER 3 OUARTER 4

1. Fission and Activation Products NONE Ci
2. Tritium HYDROGEN-3 Ci 2.15E-03 8.21 E-04 5.87E-03 2.53E-04
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 2005-DECEMBER 2005 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 MA 3 O.OOE+00 0.OOE+OO o.ooE:,.o 0.OOE+O0 evaporator bottoms, etc. Ci 0.OOE+O0 O.OOE+00 0.OOE+00 0.OOE+00
b. Dry compressible waste, MA 3 0.OOE+00 0.OOE+0O O.OOE+00 O.OOE+O0 contaminated equipment, etc. Ci 0.OOE+00 O.OOE+00 0.OOE+OO 0.OOE+00
c. Irradiated components, MA 3 0.OOE+0O 0.OOE+00 O.OOE+00 0.OOE+O0 control rods, etc. Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 d.Other Dry compressible MA 3 6.23E+02 0.OOE+00 0.OOE+O0 I .OOE+01 waste, contaminated equipment, Ci 1.31 E+02 0.OOE+00 0.OOE+00 I .OQE+0I 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 Isotope Percent Curies Iron-55 6.17E+01 8.11IE+01 E Nickel-63 8.40E-01 1.1OE+00 E Cobalt-60 9.40E+00 I1.23E+01 E Tritium 2.15SE-01 2.82E-01 E Manganese-54 7.73E+00 1.01 E+01 E Cesium-I 34 1.03E+00 1.35E+00 E Cesium-I 37 I1.98E+00 2.60E+00 E Nickel-59 7.15E-02 9.39E-02 E Zinc-65 1.58E+01 2.07E+01 E Carbon-14 1.62E-03 2. 12E-03 E Iron-59 2.97E-01 3.90E-01 E Antimony-I 25 1.61 E-02 2.12E-02 E Cerium-144 2.56E-01 3.36E-01 E Cobalt-58 3.92E-01 5.14E-01 E Chromium-51 6.14E-02 8.06E-02 E Strontium-90 1.79E-01 2.35 E-01I 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

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 TABLE 3A (continued)

SOLIJY'WASTE AND IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition No. of Shinments Mode of Transnortation 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 Shivments Mode of Transuortation Destination NONE 13

ENTERGY NUCLEAR OPERATIONS, INC.

JAMIES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 TABLE 3B SOLIIP.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 14 Bottoms, etc. Non-compacted Dry compressible Waste (DAW), Non-compacted 1280 ftA3 STC 10 Contaminated Equipment, etc.

Dry compressible Waste(DAW), Non-compacted 96 ftA3 STC 50 Contaminated Eqiupment, etc.

Contaminated Non-compacted 7 ftA3 STC 33 Oil Dry compressible Waste(DAW), Non-compacted 206.1 ftA3 STC I Contaminated Equipment Dry compressible Waste(DAW), Non-compacted 88 ftA3 STC 12 Contaminated Equipment B. NRC CLASS B SOURCE OF PROCESSING CONTAINER TYPE OF NUMB3ER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS NONE C. NRC CLASS C SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS NONE Solidification Agent: NONE HIC- High Integrity Container STC- Strong Tight Container 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 ATTACHMEENT NO. 1 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

In accordance with the James A. -FitzPatriek 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, changesmta-de 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 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 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.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 ATTACHMENT NO. 4 DEVIATIONS FIROM THRE 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.Ic. 1, 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 2/1/05 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 baised 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.

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ENTERGY NUCLEAR OPERATIONS, INC.

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

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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.

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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.

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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 1 Radiological Effluent Controls (REC) Section 7.0, Major Modifications to Radioactive Waste Treatment Systems (liquid, gaseous and solid) shall be reported in the Annual Radioactive Effluent Release Report for the period in which the modification is completed and made operational.

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

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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 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 1,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 nirem 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.

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ENTERGY NUCLEAR OPERATIONS, INC.

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

Objective To ensure that the dose rates at or beyond the site boundary from gaseous effluents do not exceed thre annual dose limits of 1(Y-CFR 20, for unrestricted areas.

Sv~ecifications 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- 13 1, 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.

S12ecifications The air dose to areas at or beyond the site boundary from noble gases released from the plant in gaseous effluents shall be limited:

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

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ENTERGY NUCLEAR OPERATIONS, INC.

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

D. DOSE DUE TO IODINE-1 31. IODINE- 133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM (ODCM, Part 1, REC 3.4)

Applicability Applies to the cumulative dose from Iodine- 13 1, Iodine- 13 3, 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-13 1, 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.

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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 conmnitment 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 mremlyear to the whole body; and,
2. Less than or equal to 25 nirem/year to any organ except the thyroid which shall be limited to less than or equal to 75 mremlyear.
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 I1OCFR50, 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.

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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. 1.1Lc) 27

ENTERGY NUCLEAR OPERATIONS, INC.

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

'ADDENDUJM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 2005 A. LIQUIDS QUARTER 1 2 3 4 ANNUAL (a) (a) (a) (a) (a)

Organ (mrem) 9.8913-07 1.23E-06 1.32E-05 1.39E-06 1.68E-05

% of Limit 1.9813-05 2.46E-05 2.63E-04 2.78E-05 1.68E-04 (b) (b) (b) (b) (b)

Whole Body (mrem) 9.89E-07 1.23E-06 1.32E-05 1.39E-06 1.68E-05

% of Limit 6.60E-05 8.1913-05 8.78E-04 9.2213-05 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 1 2 3 4 ANNUAL Total Body (mrem/yr) 7.03E-0 1 4.93E-02 4.39E+00 3.82E-01 4.39E+00

% of Limit 1.4113-01 9.86E-03 8.79E-01 7.64E-02 8.79E-01 Skin (mrem/yr) 9.1 2E-0 1 7.71 E-02 5.67E+00 8.24E-0 1 5.67E+00

% of Limit 3.04E-02 2.57E-03 1.89E-01 2.7513-02 1.89E-01 Gamma (mrad) 2.13E-02 2.65E-03 5.5 1E-02 1.52E-02 9.43E-02

% of Limit 4.27E-0 1 5.3 IE-02 1.IOE+00 3.03E-01 9.43E-0 1 Beta (mmad) 6.71E-03 3.42E-03 1.25E-02 1.07E-02 3 .33E-02

% of Limit 6.71E-02 3.42E-02 1.25E-01 1.07E-01 1.6713-01 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 QUARTER 1 2 3 4 ANNUAL (a) (b) (a) (b) (a)

Organ (mremn) 2.77E-02 1.03E-02 5.44E-02 6.26E-03 9.86E-02

% of Limit 3.69E-01 1.37E-01 7.25E-01 8.34E-02 6.58E-01 (C) (c) (c) (C) (c)

Organ Dose Rate 5.58E-03 9.44E-04 6.11 E-03 9.12E-04 6.11 E-03 (nirem/yr)

% of Limit 3.72E-04 6.29E-05 4.07E-04 6.08E-05 4.07E-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 Total Body primarily by the vegetation pathway.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005-DECEMBER 2005 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/rn 3 ) (Urn 2 )

1. Garden 0.90 mi @ 83 0OE ST 2.83E-08* 1.75E-09 Grazing Season 0.90 mi @ 83 0 E RX 2.02E-07* 5.01 E-09 Cary 0.90 mi @ 83*E TB 1.83E-07* 4.80E-09 Location No. 78 0.90 ml @ 83-E RF 2.02E-07* 5.01E-09 0.9Omi @ 83 0 E RW 3.21E-07* 5.76E-09
2. Meat 1.18 mi @ 127 0SE ST 1.72E-08* 6.80E-10 Grazing Season 1.18 mi @ 127 0 SE RX 5.36E-08* 1.30E-09 Parkhurst 1.18 ml @ 1271SE TB 5. 14E-08*' 1.27E-09 Location No. 26 1.18 mi @ 127 0 SE RF 5.3 6E-08* 1.30E-09 1.18 mi @ 127*SE 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 ml @ 139 0SE RX 2.76E-08* 4.14E-10 France 2.50 ml @ 139 0SE TB 2.71E-08* 4.07E- 10 Location No. 10 2.50 ml @ 139-SE RF 2.76E-08* 4.14E-10 2.50 mi @ 139 0SE RW 4.15E-08* 4.3 6E- 10
4. Goat (D/Q) 3.62 mi @ 113 0 ESE ST --------- 2.28E-10 Grazing Season 3.62 mi @ 113 0 ESE RX --------- 3.40E- 10 Showers 3.62 mi @ 113-ESE TB --------- 3.33E-10 Location No..71 3.62 ml@ 113 0 ESE RF --------- 3.40E- 10 3.62 ml @ 113 0 ESE RW --------- 3.49E-10
5. Goat (X/Q) 2.64 mi @ 152 0 SSE ST 1.94E-08* ------

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

Nickolas 2.64 ml @ 152 0 SSE TB 2.57E-08* ------

Location No. 61 2.64 ml @ 152 0 55E RF 2.58E-08* ------

2.64 ml @ 152 0 SSE RW 3.59E-08* ------

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMIES 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 ATMOSPHERIC" RECEPTOR LOCATION DISPERSION FACTOR A. IODINE & DISTANCE/ RELEASE X/Q D/Q PARTICULATES DIRECTION POINT (sec/m3) (1/m2)

6. Resident Annual Average
a. Inhalation( 2 ) 1.55 mi @ 900E(l) ST 2.99E-08 Cary 0.90 mi @ 83*E RX 2.07E-07 Location No. 78 0.90 mi @ 83*E TB 1.88E-07 0.90 mi @ 83 0 E RF 2.07E-07 0.90 mi @ 83*E RW 3 .06E-07
b. Deposition( 3 ) 0.71 mi @ 118'ESE ST 1.6013-09 Whaley 0.71 mi @ 118*ESE RX ---------

5.52E-09 Location No. 199 0.71 mi @ 11 8-ESE TB ---------

5.30E-09 0.71 mi @ 118*ESE RF ---------

5.52E-09 0.71 mi @ 118ESE RW ---------

6.28E-09 B. NOBLE GASES

1. Air Dose 1.55 ml @ 9000'l) ST 2.99E-08 Annual Average 0.60 mi @ 90 0 E ST(fc) 1.16E-07 Site Boundary 0.60 mi @ 90*E RX 3.58E-07 0.60 mi @ 90'E TB 3.1 9E-07 0.60 mi @ 90-E RF 3.58E-07 0.60 mi @ 90*E RW 5.3913-07
2. Total Body 0.60 mi @ 90'E ST(fc) 1.1 6E-07 Annual Average 0.60 m @ 90-E RX 3.58E-07 Site Boundary 0.60 mi @ 90'E TB 3.1 9E-07 0.60 mi @ 90'E RF 3.58E-07 0.60 mi @ 90'E RW 5 .39E-07 31

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 ATMOSPHERIC*

  • RECEPTOR LOCATION DISPERSION FACTOR B. NOBLE GASES DISTANCE! RELEASE XIQ D/Q (continued) DIRECTION POINT (sec/m3) (1/m2)
3. Skin 1.55 mi @~ 90-E ST 2.99E-08 ----------

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

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

0.60 mi @90*E TB 3.19E-07 ----------

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

0.60 mi @ 90-E RW 5.39E-07 ----------

    • Based on ODCM X/Q, D/Q Values Rev. 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 =Refuiel Floor Vent RW = Radwaste Building Vent fc = Finite Cloud 32

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