JAFP-08-0037, J. A. FitzPatrick - Annual Radiological Effluent Release Report for the Period of January 1, 2007 Through December 31, 2007

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J. A. FitzPatrick - Annual Radiological Effluent Release Report for the Period of January 1, 2007 Through December 31, 2007
ML081270074
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/30/2008
From: Jim Costedio
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-08-0037
Download: ML081270074 (34)
v • d • e


Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. Fitzpatrick NPP Entergyý P.O. Box 110 Lycoming, NY 13093 Tel 315 342 3840 April 30, 2008 JAFP-08-0037 U.S. Nuclear Regulatory Commission ATTN: Document Control.Desk Washington, D.C. 20555-0001

SUBJECT:

Entergy Nuclear Operations, Inc.

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

Dear Sir or Madam:

Attached is the Annual Radioactive Effluent Release Report for the period of January 1, 2007 through..

December 31, 2007. This report. is submitted in accordance with the requirements of the' James A.

FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual, Part I, Radiological :Controls',

Section6.2 .

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 2007 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.:

Very truly yours, JAMES COSTEDIO LICENSING MANAGER - JAF JC/CAB/jbh

Attachment:

Annual Radiological Effluent Release Rerport Xc: NRC Resident Inspector A. Muniz (USNRC Project Manager)

S. Collins (USNRC Region 1) P. Merges (NYSDEC)

D. Sherman (ANI Library) T. Kurtz (NMPC)

K. Mulligan (JAF) J. Furfaro (ENV/JAF)

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

W. Hamblin (CHEM/JAF)

JAFP-08-0037 Attachment 1 ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2007 - DECEMBER 31, 2007 DOCKET NO.: 50-333 LICENSE NO.: DPR-59

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 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 1:0 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-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 2007-DECEMBER 2007 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 itCi/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., ý'Fission and activation gases: (None specified)
b. Iodines: (None specified)
c. Particulates, half-lives >8 days: (None specified)
d. Liquid effluents: Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Fission and activation None None None 9.35E-05 products (mixture EC)

(kLCi/ml)

(2) Tritium (pCi/ml) 1.OOE-02 1.00E-02 1.OOE-02 1.OOE-02 (3) Dissolved and entrained gases (itCi/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 2007-DECEMBER 2007 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 2007-DECEMBER 2007 SUPPLEMENTAL INFORMATION (continued)

5. Batch Releases
a. Liquid: Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 6.OOE+00 1.00E+01 4.OOE+00 1.60E+01 (2) Total time period for batch 1.03E+02 2.44E+02 1.32E+02 7.90E+02 release: (min)

(3) Maximum time period for 5.60E+01 8.OOE+01 8.OOE+01 1.63E+02 batch release: (min)

(4) Average time period for 1.72E+01 2.44E+01 3.33E+01 4.94E+01 batchrelease: (min)

(5) Minimum time period for 1.00E+00 4.00E+00 1.00E+00 3.OOE+00 batch release: (min)

(6) Total Activity Released (Ci) 2.92E-05, 1.42E-04 4.24E-05 1.26E-01 (7) Total Volume Released (liters) 1.85E+04 2.03E+04 3.95E+03 2.43E+05

b. Liquid: Non-Canal (1) Number of batch releases: 1.00E+01 1.20E+01 1.20E+0l 1.00E+01 (2) Total time period for batch 9.60E+00 4.32E+01 1.06E+02 2.35E+02 release: (min)

(3) Maximum time period for 1.80E+00 2.52E+01 4.68E+01 1.19E+02 batch release: (min)

(4) Average time period for 9.60E-0 1 3.60E+00 8.85E+00 2.35E+01 batch release: (min)

(5) Minimum time period for 6.OOE-01 6.OOE-01 1.20E+00 6.OOE-01 batch release: (min)

(6) Total'Activity Released (Ci) 1.47E-05 5.76E-05 4.63E-05 2.15E-04 (7) Total Volume Released (liters) 3.63E+03 1.64E+04 4.02E+04 8.91E+04 4

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 SUPPLEMENTAL INFORMATION (continued)

c. Gaseous:

There were no gaseous batch releases for this report period.

6. Abnormal Releases
a. Liquid: Quarter 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 2007-DECEMBER 2007 TABLE 1A GASEOUS EFFLUENTS--SUMMATION-OF ALL RELEASES EST TOTAL UNIT OTR1 OTR2 OTR 3 OTR 4 ERROR %

A. FISSION AND ACTIVATION GASES

1. Total Release Ci 4.62E+01 2.67E+02 1.60E+02 1.50E+02 <2.50E+01
2. Average release rate for period pCi/sec 5.87E+00 3.40E+01 2.02E+01 1.89E+01
3. Applicable ODCM Limit B. IODINE-131
1. Total Iodine-131 Ci 2.04E-04 1.27E-03 9.26E-04 6.57E-04 <2.50E+01
2. Average release rate for period [tCi/sec 2.59E-05 1.62E-04 1.17E-04 8.27E-05
3. Applicable ODCM Limit C. PARTICULATES
1. Particulates with half-lives Ci 1.01E-04 1.30E-04 1.48E-04 7.72E-05 <3.60E+01

>8 days

2. Average release rate for p.Ci/sec 1.29E-05 1.65E-05 1.87E-05 9.71 E-06 period
3. Applicable ODCM Limit * *
4. Gross alpha radioactivity Ci 3.91 E-07 3.83E-07 6.97E-07 3.71E-07 <2.50E+01 D. TRITIUM
1. Total Release Ci 4.17E+00 3.11E+00 3.59E+00 3.09E+00 <2.50E+01
2. Average release rate for period pCi/sec 5.30E-01 3.97E-01 4.51 E-01 3.89E-01
3. Applicable ODCM Limit
  • E. PERCENT OF APPLICABLE ODCM LIMITS FISSION AND ACTIVATION GASES
1. Quarterly gamma air dose limit 1.43E-02 1.16E-01 6.70E-02 6.67E-02
2. Quarterly beta air dose limit 9.22E-04 9.76E-03 5.46E-03 4.91 E-03
3. Yearly gamma air dose limit 7.16E-03 5.80E-02 3.35E-02 3.34E-02
4. Yearly beta air dose limit 4.16E-04 4.88E-03 2.73E-03 2.46E-03
5. Whole body dose rate limit 1.97E-03 1.26E-01 3.25E-02 1.09E-01
6. Skin dose rate limit 3.99E-04 2.75E-02 7.15E-03 2.18E-02 HALOGENS, TRITIUM AND PARTICULATES WITH HALF-LIVES >8 DAYS
7. Quarterly dose limit (organ)  % 3.92E-02 1.65E-01 1.19E-01 8.96E-02
8. Yearly dose limit (organ)  % 1.96E-02 8.26E-02 5.97E-02 4.48E-02
9. Organ dose rate limit  % 2.13E-05 5.27E-05 3.70E-05 2.71 E-05 6

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 TABLE 1B GASEOUS EFFLUENTS--ELEVATED RELEASE CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER1I QUARTER 2 QUARTER3 QUARTER4

1. Fission Gases Argon-41 Ci 3.63E+00 2.76E+00 3.83E+00 5.55E+00 Krypton-85m Ci 1.37E+01 2.08E+01 2.70E+01 3.38E+01 Krypton-87 Ci 1.10E-01 3.68E+01 1*82E+01 4.86E+00 Krypton-88 Ci 8.52E+00 3.71 E+01 3.53E+01 4.20E+01 Xenon-1 33 Ci 1.82E+01 2.19E+01 2.68E+01 3.31 E+01 Xenon-1 35 Ci 7.43E-01 7.22E+01 2.87E+01 5.21 E+00 Xenon-1 35m Ci 1.96E-01 1.88E+01 4.OOE+00 3.44E+00 Xenon-137 Ci 4.85E+00 1.07E+01 Xenon-1 38 Ci 7.28E-01 5.71 E+01 1.18E+01 1.08E+01 TOTAL Ci 4.58E+01 2.67E+02 1.60E+02 1.49E+02
2. lodines Iodine-131 Cil 7.51 E-06 1.15E-03 8.31 E-04 5.19E-04 Iodine-133 Ci 2.75E-05 1.72E-03 1.05E-03 5.42E-04 Iodine-135 Ci 8.89E-04 1.11E-04 1.49E-04 TOTAL Ci 3.50E-05 3.76E-03 1.99E-03 1.21E-03
3. Particulates Manganese-54 Ci 2.24E-06 8.81 E-07 4.37E-07 Cobalt-60 Ci. 4.50E-07 Strontium-89 Ci 4.74E-05 2.43E-05 1.93E-05 2.01 E-05 Strontium-90 Ci 2.75E-07 1.69E-07 6.35E-08 1.87E-05 Cadmium-1i15m Ci 3.90E-05 Cesium-137 Ci 3.58E-07 Barium-140 Ci 3.76E-06 1.82E-05 TOTAL Ci 4.77E-05 2.71E-05 6.34E-05 3.89E-05
4. Tritium Hydrogen-3 Ci 4.26E-01 3.63E-01 6.05E-01 5.31 E-01 Note: There were no batch releases for this report period.

7

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 TABLE 1C GASEOUS EFFLUENTS--GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER2 QUARTER3 QUARTER4

1. Fission Gases Xenon-1 33 Ci ------------

Xenon-1 35 Ci 1.24E-01 8.85E-03 ------------ 3.65E-01 Xenon-135M Ci 2.33E-01 Xenon-1 38 Ci 7.58E-02 ------------

TOTAL Ci 3.57E-01 8.47E-02 8.18E-01

2. lodines Iodine-1 31 Ci 1.96E-04 1.23E-04 9.54E-05 1.38E-04 Iodine-1 33 Ci 7.12E-04 3.99E-04 2.24E-04 4.10E-04 TOTAL Ci 9.08E-04 5.22E-04 3.19E-04 5.48E-04
3. Particulates Chromium-51 Ci 1.28E-05 Manganese-54 Ci 2.25E-05 2.73E-05 3.07E-06 Cobalt-58 Ci 1.83E-06 Iron-59 Ci 2.01E-05 Cobalt-60 Ci 1.07E-05 1.48E-05 1.62E-06 Zinc-65 Ci 5.75E-06 6.39E-06 Strontium-89 Ci 1.12E-05 2.06E-05 5.77E-05 2.99E-05 Strontium-90 Ci 1.46E-06 5.21 E-07 3.20E-06 3.82E-06 Barium-140 Ci 1.94E-05 4.60E-06 TOTAL Ci 5.34E-05 1.03E-04 8.50E-05 3.83E-05
4. Tritium Hydrogen-3 Ci 3.74E+00 2.75E+00 2.98E+00 2.56E+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 2007-DECEMBER 2007 TABLE 2A LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES EST TOTAL UNIT O1 O TR 2 OTR3 OTR4 ERROR %

A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not including tritium, gases and alpha) Ci NONE NONE NONE 1.72E-05 <2.50E+01
2. Average diluted concentration during period ptCi/ml NONE NONE NONE 1.72E-11
3. Applicable ODCM Limit B. TRITIUM
1. Total Release Ci 4.39E-05 2.OOE-04 8.87E-05 1.26E-01 _<2.50E+01
2. Average diluted concentration during period (Note 1) [tCi/ml 6.65E-07 1.58E-06 1.05E-06 7.37E-07
3. Applicable ODCM Limit C. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci NONE NONE NONE 5 36E-04 <2.50E+01
2. Average diluted concentration during period jICi/ml NONE NONE NONE 3.90E-10
3. Applicable ODCM Limit D. GROSS ALPHA RADIOACTIVITY
1. Total Release Ci NONE NONE NONE 2.44E-06 _<4.20E+01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) liters 2.22E+04 3.67E+04 4.42E+04 3.33E+05 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 1.35E+08 3.37E+08 1.97E+08 1.01E+09
  • G. PERCENT OF APPLICABLE ODCM LIMITS
1. Quarterly Whole Body Dose  % 3.05E-04 6.50E-04 1.58E-04 1.97E-04
2. Quarterly Organ Dose  % 9.16E-05 1.95E-04 4.75E-05 5.78E-05
3. Annual Whole Body Dose  % 1.53E-04 3.25E-04 7.92E-05 9.85E-05
4. Annual Organ Dose  % 4.58E-05 9.75E-05 2.38E-05 2.89E-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 2007-DECEMBER 2007 TABLE 2B LIQUID EFFLUENTS CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER I QUARTER 2 QUARTER 3 QUARTER4

1. Fission and Activation Products Iron-55 Ci 1.17E-05 Strontium-89 Ci 5.05E-06 Strontium-90 Ci 5.44E-07 TOTAL Ci 1.73E-05
2. Tritium Hydrogen-3 Ci 2.92E-05 1.42E-04 4.24E-05 1.26E-01
3. Dissolved and Entrained Gases Xenon--133 Ci 5.36E-04 TOTAL 5.36E-04 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 2007-DECEMBER 2007 TABLE 2B (SUPPLEMENT)

LIQUID EFFLUENTS NON-CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER2 QUARTER3 QUARTER4

1. Fission and Activation Products NONE Ci
2. Tritium Hydrogen-3 Ci 1.47E-05 5.76E-05 4.63E-05 2.15E-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 2007-DECEMBER 2007 TABLE 3A SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

Est. Total 1 Type of Waste Unit Class A Class B Class C Error %

a. Spent resins, filter sludges m^3 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 evaporator bottoms, etc. Ci 0.00E+00 0.00E+00 0.00E+00 0.OOE+00
b. Dry compressible waste, mA3 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00.

contaminated equipment, etc. Ci 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00

c. Irradiated components, mA3 0.00E+00 0.00E+00 5.OOE-02 1.OOE+01 control rods, etc. Ci 0.00E+00 0.00E+00 7.47E-02 1.OOE+01
d. Other: Dry compressible mA3 4.85E+02 2.19E+01 5.71 E-03 1.OOE+01 waste, contaminated equipment, Ci 6.86E+01 5.21 E+02 5.33E+02 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.

Isotope Percent Curies Isotope Percent Curies Hydrogen-3 2.02E-02 1.51 E-05 E Iron-59 1.37E-02 1.02E-05 E Manganese-54 3.20E+00 2.39E-03 E Nickel-59 1.23E-02 9.16E-06 E Iron-55 4.77E+01 3.56E-02 E Cobalt-60 4.68E+01 3.50E-02 E Cobalt-58 . 3.98E-01 2.97E-04 E Nickel-63 1.86E+00 1.39E-03 E

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

Isotope Percent Curies Isotope Percent Curies Hydrogen-3 1.05E-01 1.18E+00 E Zinc-65 6.37E+00 7.15E+01 E Carbon-14 5.20E-02 5.83E-01 E Strontium-90 8.35E-02 9.37E-01 E Manganese-54 7.37E+00 8.27E+01 E Antimony-125 7.20E-02 8.08E-01 E Iron-55 6.68E+01 7.49E+02 E Cesium-134 4.71E-01 5.28E+00 E Cobalt-58 4.26E-02 4.78E-01 E Cesium-137 1.47E+00 1.65E+01 E Cobalt-60 1.57E+01 1.76E+02 E Cesium-144 6.75E-02 7.58E-01 E Nickel-63 1.44E+00 1.61E+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.

12

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition No. of Shipments Mode of Transportation Destination 8 Truck
  • Duratek Oak Ridge, TN 15 Truck
  • Studsvik Erwin, T
  • - 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 2007-DECEMBER 2007 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 Spent Resins, Filter Sludges, evaporator Air Drying 120.3 ftA3 HIC I Bottoms, etc. Non-compacted Dry compressible Waste (DAW), Non-compacted 1280 ftA3 STC 10 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 2560 ftA3 STC 1 Contaminated Equipment, etc.

Dry compressible Waste(DAW) Non-compacted 96 ftA3 STC 12 Contaminated Eqiupment, etc.

Contaminated Non-compacted 7.5 ftA3 STC 21 Oil Dry compressible Non-compacted 1033.5 ftA3 STC 2 Waste(DAW)

Contaminated Equipment 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 B. NRC CLASS B SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Sludges, evaporator Air Drying 205.8 ftA3 HIC 2 Bottoms, etc. Non-compacted Spent Resins, Filter Sludges, evaporator Air Drying 120.3 ftA3 HIC 2 Bottoms, etc. Non-compacted Dry compressible Non-compacted 120.3 ftA3 HIC I Waste(DAW)

Contaminated Equipment I

C. NRC CLASS C SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Dry compressible Non-compacted 120.3 ftA3 HIC 2 Waste(DAW)

Contaminated Equipment Irradiated Hardware Non-compacted 120.3 ftA3 STC I Solidification Agent: NONE HIC- High Integrity Container STC- Strong Tight Container 15

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 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).

16

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 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 procedure FO-OP-023-41802, Waste Transfer and Bead Resin/Activated Carbon Dewatering Procedure for Energy Solutions'14-215 or Smaller liners at James A. FitzPatrick Nuclear Plant was made and approved on 9/17/07.

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) Duratek changed to Energy Solutions throughout the procedure.
2) Changed to allow non-bed and carbon media to offsite processing facility.
3) Changed to allow Quality Assurance hold points to be waived if being sent to offsite processing facility.
4) Added caution to observe for traces of oil or water in the resin to terminate the process
5) Increased the number of dewatering cycles from 3 to 5 to improve dewatering process.
6) Changed routing of completion records to Energy Solutions project manager if processing for direct burial.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 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 CHANGES TO THE REMP PROGRAM The following changes were implemented during the 2007 sampling program:

A. Food Product Sampling Program During the reporting period, one new food product location was added and one food product location was removed from the Environmental Monitoring locations. These locations are used to implement the requirements of the ODCM, Part 1, Table 5.1-1.

Sample locations selected were based on the 2007 annual land use census and were utilized to implement the 2007 food product requirements.

B. Milk Sampling Program During the reporting period, one of the milk sample locations ceased millk production in May of 2007. Samples were obtained from Sample Location #4 during April and May of 2007. This location was used to implement the requirements of ODCM, Part 1, Table 5.1-1 even though its distance from the plant was greater than 5 miles.

C. Ground Water Monitoring Program During the reporting period, 5 ground water monitoring wells were drilled along the northern edge of the site property. Samples obtained from these wells were counted for tritium. These wells are used to implement the NEI Ground Water Protection Initiative.

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 2007-DECEMBER 2007 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.

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

1. Environmental Air sample station R-2 offsite flow control valve was found chattering during the sample period of 1/29/07 to 2/6/07. The volumetric flow rate was outside of the acceptable range of the procedure. The sample pump was replaced and -flowrate returned to acceptable range. Total air sample station out of service time was 0.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.
2. The air sampling pump at the R-1 and R-2 Environmental Sampling Station was inoperable for approximately 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 7/3/07 to 7/10/07. 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 loss of power to the sampler. No corrective actions were required to restore unit to service.
3. Continuous sampling was not maintained at Environmental Air sample stations R-1 Offsite and R-2 Offsite. During the sample period from 9/11/07 to 9/18/07, a period of 3.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> was lost due to a power outage. Pumps were found running during the weekly sample change out..
4. A loss of sample collection occurred at the R-1 Offsite station for a duration of 1.9 hrs and R-2 Offsite station for a duration of 1.2 hrs. The loss of sample is based on the station's air pump integrating time and was determined to be due to a power outage in the area.

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 43,790 hours0.00914 days <br />0.219 hours <br />0.00131 weeks <br />3.00595e-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 99.98%.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 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.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 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.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 ATTACHMENT NO. 7 ONSITE GROUND WATER MONITORING A) Gamma Isotopic Monitoring Monitoring Wells (5-9) were analyzed to below the required lower limits of detection in accordance with the Offsite Dose Calculation Manual (ODCM) Part 1, Table 2.2-1. These values are as follows:

Radionuclide LLD Value Radionuclide LLD Value (P.Ci/ml) (PtCi/ml)

Manganese-54 5.OE-7 lodine-131 1.OE-6 Cobalt-58 5.OE-7 Cesium-1 34 5.OE-7 Iron-59 5.OE-7 Cesium-1 37 5.OE-7 Cobalt-60 5.OE-7 Cerium-141 5.OE-5 Zinc-65 5.OE-7 Cerium-144 5.OE-5 Molybdenum-99 5.OE-5 There were no plant related nuclides detected in the samples.

B) Tritium Monitoring Monitoring Wells (5-9) were analyzed for tritium to below the required lower limit of detection in accordance with the Offsite Dose Calculation Manual (ODCM) of 3000 pCi/L.

The results are as follows:

Well Lower Limit of Detection Sample Result pCi/L pCi/L 5 1000 <909 6 1000 <909 7 1000 <909 8 1000 <909 9 1000 <909 22

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007

.ADDENDUM 1 ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2007

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.

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)

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 2007-DECEMBER 2007 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.

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 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.

Obiective 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.

Obiective 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 2007-DECEMBER 2007 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 limitedas 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, 2007 to December 31, 2007.

Historical meteorological data was used to generate tables of average dispersion factors. Locations of interest were identified from the 2007 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 2007-DECEMBER 2007 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. .c) 27

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 2007 A. LIQUIDS QUARTER 2 3 4 ANNUAL (a) (a) (a) (a) (a)

Organ (mrem) 4.58E-06 9.75E-06 2.38E-06 2.89E-06 1.96E-05

% of Limit 9.16E-05 1.95E-04 4.75E-05 5.78E-05 1.96E-04 (b) (b) (b) (b) (b)

Whole Body (mrem) 4.58E-06 9.75E-06 2.38E-06 2.96E-06 1.98E-05

% of Limit 3.05E-04 6.50E-04 1.58E-04 1.97E-04 6.56E-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) 9.84E-03 6.30E-01 1.62E-01 5.44E-01 6.30E-01

% of Limit 1.97E-03 1.26E-01 3.25E-02 1.09E-01 1.26E-01 Skin (mrem/yr) 1.20E-02 8.24E-01 2.15E-01 6.53E-01 8.24E'0 1

% of Limit 3.99E-04 2.75E-02 7.15E-03 2.18E-02 2.75E-02 Gamma (mrad) 7.16E-04 5.80E-03 3.35E-03 3.34E-03 1.32E-02

% of Limit 1.43E-02 1.16E-01 6.70E-02 6.67E-02 1.32E-01 Beta (mrad) 9.22E-05 9.76E-04 5.46E-04 4.91E-04 2.1OE-03

% of Limit 9.22E-04 9.76E-03 5.46E-03 4.91E-03 1.05E-02 28

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 2007 C. IODINES AND PARTICULATES QUARTER 1 2 3 4 1 ANNUAL (a) (b) (b) (b) (b)

Organ (mrem) 2.94E-03 1.24E-02 8.96E-03 6.72E-03 3.1OE-02

% of Limit 3.92E-02 1.65E-01 1.19E-01 8.96E-02 2.07E-0 1 (a) (a) (a) (a) (a)

Organ Dose Rate 3.20E-04 7.91E-04 1.50E-03 4.06E-04 1.50E-03 (mrem/yr)

% of Limit 2.13E-05 5.27E-05 3.70E-05 2.71E-05 3.70E-05 (a) Dose to the Child Thyroid primarily by the vegetation pathway.

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

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 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/m 3) (1/m2)

1. Garden 0.90 mi @ 830 E ST 2.83E-08* 1.75E-09 Grazing Season 0.90 mi @ 830 E RX 2.02E-07* 5.01E-09 Cary 0.90 mi @ 830 E TB 1.83E-07* 4.80E-09 Location No. 78 0.90 mi @ 830 E RF 2.02E-07* 5.01E-09 0.90 mi @ 830 E RW 3.21E-07* 5.76E-09
2. Meat 1.18 mi @ 127°SE ST 1.72E-08* 6.80E-10 Grazing Season 1.18 mi @ 127°SE RX 5.36E-08* 1.30E-09 Parkhurst 1.18 mi @ 127°SE TB 5.14E-08* 1.27E-09 Location No. 26 1.18 mi @ 127°SE RF 5.36E-08* 1.30E-09 1.18 mi @ 127°SE RW 9.12E-08* 1.46E-09
3. Cow 2.50 mi @ 139 0 SE ST 1.67E-08* 2.65E-10 Grazing Season 2.50 mi @ 139°SE RX 2.76E-08* 4.14E-10 France 2.50 mi @ 139°SE TB 2.71E-08* 4.07E-10 Location No. 10 2.50 mi @ 139 0 SE RF 2.76E-08* 4.14E-10 2.50 mi @ 139°SE RW 4.15E-08* 4.36E-10
4. Goat (D/Q) 3.62 mi @ 113 0 ESE ST 2.28E-10 Grazing Season 3.62mi @ 113 0 ESE RX 3.40E-10 Showers 3.62 mi @ 113 0 ESE TB 3.33E-10 Location No. 71 3.62 mi @ 113 0 ESE RF 3.40E-10 3.62 mi @ 113°ESE RW 3.49E- 10
5. Goat (X/Q) 2.64 mi @ 152 0 SSE ST 1.94E-08*

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

Nickolas 2.64 mi @ 152 0 SSE 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*

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ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007-DECEMBER 2007 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(1) 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°E RF 2.07E-07 -----------

0.90 mi @ 83°E RW 3.06E-07 3

b. Deposition( ) 0.71 mi @ 118°ESE ST 1.60E-09 Whaley 0.71 mi @ 118°ESE RX 5.52E-09 Location No. 199 0.71 mi @ 118°ESE TB 5.30E-09 0.71 mi @ 118°ESE RF 5.52E-09 0.71 mi @ 118°ESE RW 6.28E-09 B. NOBLE GASES
1. Air Dose 1.55 mi @ 900E(l) 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
2. Total Body 0.60 mi @ 90 0 E ST(fc) 1.16E-07 Annual Average 0.60 mi @ 90'E RX 3.58E-07 Site Boundary 0.60 mi @ 90 0 E TB 3.19E-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 2007-DECEMBER 2007 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'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 = Refuel Floor Vent RW = Radwaste Building Vent fc = Finite Cloud 32

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