JAFP-09-0055, Annual Radioactive Effluent Release Report, for the Period of January 1, 2008 Through December 31, 2008

From kanterella
Jump to navigation Jump to search
Annual Radioactive Effluent Release Report, for the Period of January 1, 2008 Through December 31, 2008
ML091320345
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/30/2009
From: Joseph Pechacek
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-09-0055
Download: ML091320345 (39)
v • d • e


Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. Fitzpatrick NPP Entergy P.O. Box 110 Lycoming, NY 13093 Tel 315-342-3840 Joseph Pechacek Licensing Manager April 30, 2009 JAFP-09-0055 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Subject:

Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 2008 Annual Radioactive Effluent Release Reoort

Dear Sir or Madam:

Enclosed is the Annual Radioactive Effluent Release Report for the period of January 1, 2008 through December 31, 2008. 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 2008 calendar year. The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1. Distribution is in accordance with Regulatory Guide 10.1, Revision 4.

There are no commitments contained in this letter.

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

Ve JIyor,S JOSE 'H EC ACEK LICEN SING MANAGER - JAF JP/CAB/jbh

Enclosure:

Annual Radioactive Effluent Release Report January 1, 2008 - December 31, 2008 Xc: NRC Resident Inspector B. Vaidya (USNRC Project Manager)

D. Sherman (ANI Library) P. Merges (NYSDEC)

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

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

J. McCann (ENOC/WPO) W. Hamblin (CHEM/JAF)

Samuel Collins (Region 1 Administrator)

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2008 - DECEMBER 31, 2008 DOCKET NO.: 50-333 LICENSE NO.: DPR-59

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 TABLE OF CONTENTS Annual Radiological Effluent Release Report 14 Pages Summary Changes to the Offsite Dose Calculation Manual 4 Pages Summary of Changes to the Process Control Program 1 Page Summary of changes to Environmental Monitoring and Dose Calculation Locations 1 Page Deviations From The Required Environmental Sampling Schedule 2 Pages Annual Summary of Hourly Meteorological Data 1 Page Major Modifications to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems 1 Page Onsite Ground Water Monitoring 1 Page Inoperative Effluent Sampling Equipment 1 Page Addendum 1 Assessment of Radiation Doses To The Public January -

December 2008 10 Pages PAGE 1 of 1

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 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.1 .a and 3.4.1 .c.1 .b as a result of burning contaminated oil.

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

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

PAGE 1 of 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 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 gCi/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. lodines: (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 products (mixture EC)

(.tCi/ml)

(2) Tritium (kCi/ml) 1.OOE-02 1.OOE-02 1.OOE-02 1.OOE-02 (3) Dissolved and entrained gases (pCi/ml) 2.OOE-04 2.OOE-04 2.OOE-04 2.00E-04 PAGE 2 of 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 SUPPLEMENTAL INFORMATION (continued)

3. Average Ener_qV (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. lodines: 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

&\

PAGE 3 of 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 SUPPLEMENTAL INFORMATION (continued)

5. Batch Releases
a. Liquid: Canal Quarter 1 Quarter 2 Quarter 3 Quarter 4 (1) Number of batch releases: 1.40E+01 1.50E+01 1.OOE+01 1.60E+01 (2) Total time period for batch 3.55E+02 2.93E+02 3.97E+02 9.OOE+02 release: (min)

(3) Maximum time period for 1.30E+02 1.50E+02 1.14E+02 1.02E+02 batch release: (min)

(4) Average time period for 2.55E+01 1.95E+01 3.97E+01 5.63E+01 batch release: (min)

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

(6) Total Activity Released (Ci) 1.14E-04 1.28E-04 9.04E-01 2.90E+00 (7) Total Volume Released (liters) 7.OOE+04 1.83E+04 1.20E+05 4.09E+05

b. Liquid: Non-Canal (1) Number of batch releases: 1.OOE+01 7.OOE+00 1.30E+01 3.OOE+00 (2) Total time period for batch 1.20E+01 7.30E+01 1 .14E+03 2.10E+01 release: (min)

(3) Maximum time period for 2.OOE+00 5.20E+01 3.46E+02 1.70E+01 batch release: (min)

(4) Average time period for 1.20E+00 1.04E+01 8.79E+01 7.OOE+00 batch release: (Min)

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

(6) Total Activity Released (Ci) 2.18E-05 6.29E-05 6.20E-04 8.45E-06 (7) Total Volume Released (liters) 5.22E+03 2.71 E+04 4.35E+05 7.95E+03

c. Gaseous:

There were no gaseous batch releases for this report period.

PAGE 4 of 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 SUPPLEMENTAL INFORMATION (continued)

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 PAGE 5 of 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 TABLE 1A GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES EST TOTAL UNIT QTR 1 QTR 2 QTR3 QTR 4 ERROR %

A. FISSION AND ACTIVATION GASES

1. Total Release Ci 2.90E+01 9.36E+01 5.33E+01 1.30E+01 <2.50E+01
2. Average release rate for period itCi/sec 3.68E+00 1.19E+01 6.70E+00 1.64E+00
3. Applicable ODCM Limit B. IODINE-131
1. Total Iodine-131 Ci 2.11E-04 2.05E-04 3.85E-04 1.55E-04 <2.50E+01
2. Average release rate for period iiCi/sec 2.68E-05 2.60E-05 4.85E-05 1.95E-05
3. Applicable ODCM Limit C. PARTICULATES
1. Particulates with half-lives Ci 3.69E-05 2.16E-05 1.10E-03 3.99E-05 <3.60E+01

>8 days

2. Average release rate for gCi/sec 4.96E-06 2.75E-06 1.38E-04 5.02E-06 period
3. Applicable ODCM Limit
4. Gross alpha radioactivity Ci 9.31 E-07 5.42E-07 5.56E-07 3.16E-07 <2.50E+01 D. TRITIUM
1. Total Release Ci 2.93E+00 2.67E+00 4.13E+00 5.25E+00 <2.50E+01
2. Average release rate for period gCi/sec 3.73E-01 3.39E-01 5.19E-01 6.60E-01
3. Applicable ODCM Limit
  • E. PERCENT OF APPLICABLE ODCM LIMITS FISSION AND ACTIVATION GASES
1. Quarterly gamma air dose limit 8.55E-03 3.83E-02 8.71 E-03 6.44E-03
2. Quarterly beta air dose limit 5.15E-04 3.03E-03 1.02E-03 4.59E-04
3. Yearly gamma air dose limit 4.28E-03 1.92E-02 4.36E-03 3.22E-03
4. Yearly beta air dose limit 2.57E-04 1.52E-03 5.09E-04 2.29E-04
5. Whole body dose rate limit 2.22E-03 8.24E-02 4.19E-03 8.35E-03
6. Skin dose rate limit 4.48E-04 1.77E-02 9.82E-04 1.80E-03 HALOGENS, TRITIUM AND PARTICULATES WITH HALF-LIVES >8 DAYS
7. Quarterly dose limit (organ)  % 4.OOE-02 3.55E-02 7.30E-02 2.37E-02
8. Yearly dose limit (organ)  % 2.OOE-02 1.78E-02 3.65E-02 1.19E-02
9. Organ dose rate limit  % 1.97E-05 2.25E-05 5.89E-05 1.95E-05 PAGE 6 of 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 TABLE 1B GASEOUS EFFLUENTS--ELEVATED RELEASE CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4

1. Fission Gases Argon-41 Ci 2.45E+00 1.81 E+00 1.36E+00 2.42E+00 Krypton-85m Ci 9.59E+00 7.67E+00 7.76E+00 1.29E+00 Krypton-87 Ci 8.09E+00 9.19E-02 1.22E400 5.04E+00 Krypton-88 Ci 9.20E+00 4.73E+00 1.09E+00 Xenon-133 Ci 1.17E+01 2.12E+01 3.1 OE+01 8.88E-01 Xenon-133m Ci 1.69E-01 2.06E-01 Xenon-135 Ci 3.15E-02 9.27E+00 5.91 E+00 1.46E+00 Xenon-1 35m Ci 7.93E+00 5.69E-01 1.08E+00 Xenon-1 38 Ci 1.73E-01 2.75E+01 1.51 E-02 3.59E+00 TOTAL Ci 2.90E+01 9.28E+01 5.16E+01 1.30E+01
2. lodines Iodine-131 Ci 1.19E-05 5.80E-05 4.34E-05 9.92E-05 Iodine-1 33 Ci 5.19E-05 9.20E-05 9.27E-05 2.09E-04 Iodine-135 Ci 1.82E-05 1.82E-05 5.16E-05 TOTAL Ci 6.38E-05 1.68E-04 1.54E-04 3.60E-04
3. Particulates Manganese-54 Ci 1.53E-07 3.06E-07 Strontium-89 Ci 1.12E-05 4.87E-06 5.93E-06 2.78E-06 Strontium-90 Ci 1.OOE-07 2.85E-08 Barium-140 Ci 1.50E-06 1.09E-06 TOTAL Ci 1.13E-05 6.52E-06 6.24E-06 3.90E-06
4. Tritium Hydrogen-3 Ci 2.11iE-01 3.65E-01 8.96Eý-01 .1.09E+00 Note: There were no batch releases for this report period.

PAGE 7 of 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 TABLE 1C GASEOUS EFFLUENTS--GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4

1. Fission Gases Xenon- 133 Ci ------------ ------------

Xenon- 135 Ci 3.03E-01 ------------

Xenon 135M Ci ------------ 8.03E-01 ------------

TOTAL Ci 8.03E-01 1.66E+00

2. lodines Iodine-131 Ci 1.99E-04 1.47E-04 3.42E-04 5.60E-05 Iodine-133 Ci 6.31 E-04 6.08E-04 1.32E-03 2.39E-04 Iodine-135 Ci 1.60E-04 TOTAL Ci 8.30E-04 7.55E-04 1.82E-03 2.95E-04
3. Particulates Manganese-54 Ci ------------ 6.92E-05 i.51E-06 Cobalt-58 Ci 3.68E-06 Cobalt-60 Ci 2.12E-06 2.41 E-05 1.01 E-06 Zinc-65 Ci 2.86E-04 2.OOE-05 Strontium-89 Ci 2.08E-05 1.07E-05 1.93E-05 1.02E-05 Strontium-90 Ci 1.13E-06 1.46E-07 1.48E-06 3.27E-06 Cadmium- 1i5M Ci 5.82E-04 Barium-140 Ci 1.58E-06 4.27E-06 1.07E-04 Cerium-141 Ci 1.46E-06 TOTAL Ci 2.56E-05 1.51 E-05 1.09E-03 3.60E-05
4. Tritium Hydrogen-3 Ci 2.72E+00 2.30E+00 3.23E+00 4.16E+00 Note: There were no batch releases for this report period.

PAGE 8 of 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 TABLE 2A LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES EST TOTAL UNIT QTR 1 QTR 2 QTR 3 QTR4 ERROR %

A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not including tritium, gases and alpha) Ci NONE NONE *!2.50E+01
2. Average diluted concentration during period RiCi/ml NONE NONE
3. Applicable ODCM Limit B. TRITIUM
1. Total Release Ci 1.36E-04 1.91 E-04 9.05E-01 2.90E+00 *ý2.50E+01
2. Average diluted concentration during period (Note 1) RCi/ml 2.90E-07 1.39E-06 1.43E-06 2.18E-06
3. Applicable ODCM Limit C. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci NONE NONE 9.91 E-05 <2.50E+01
2. Average diluted concentration during period RCi/ml NONE NONE ---------- 7.37E-1 1
3. Applicable ODCM Limit D. GROSS ALPHA RADIOACTIVITY
1. Total Release Ci NONE NONE *!4.20E+01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) liters 7.52E+04 4.54E+04 5.55E+05 4.17E+05 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 4.76E+08 4.22E+08 6.20E+08 1.32E+09
  • G. PERCENT OF APPLICABLE ODCM LIMITS
1. Quarterly Whole Body Dose 4.11 E-04 2.03E-04 2.33E-04 2.39E-04
2. Quarterly Organ Dose 1.23E-04 6.08E-05 6.99E-05 7.17E-05
3. Annual Whole Body Dose 2.05E-04 1.01 E-04 1.16E-04 1.19E-04
4. Annual Organ Dose 6.16E-05 3.04E-05 3.49E-05 3.58E-05 (Note 1) Concentration includes summation from diluted and undiluted values from Canal and Non-Canal releases (Table 2B).

PAGE 9 of 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 TABLE 2B LIQUID EFFLUENTS CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4

1. Fission and Activation Products NONE Ci
2. Tritium Hydrogen-3 Ci 1.14E-04 1.28E-04 9.04E-O1 2.90E+00
3. Dissolved and Entrained Gases Xenon--135 Ci 9.91 E-05 TOTAL 9.91 E-05 Note: There were no continuous mode discharges during this report period.

PAGE 10 of 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 TABLE 2B (SUPPLEMENT)

LIQUID EFFLUENTS NON-CANAL BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4

1. Fission and Activation Products NONE Ci
2. Tritium Hydrogen-3 Ci 2.18E-05 6.29E-05 6.20E-04 8.45E-06
3. Dissolved and Entrained Gases NONE Ci Note: There were no continuous mode discharges during this report period.

PAGE 11 of 14

ENTERGY NUCLEAR OPERATIONS, INC..

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 TABLE 3A SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

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

a. Spent resins, filter sludges mA3 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 evaporator bottoms, etc. Ci 0.OOE+00 0.00E+00 0.00E+00 0.00E+00
b. Dry compressible waste, mA3 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 contaminated equipment, etc. Ci 0.00E+00 0.OOE+00 0.00E+00- 0.OOE+00
c. Irradiated components, mA3 O.OOE+00 0.OOE+00 3.25E+00 1.OOE+01 control rods, etc. Ci 0.00E+00 0.00E+00 2.18E+04 1.00E+01
d. Other: Dry compressible mA3 7.58E+02 1.60E+01 3.41 E+00 1.OOE+01 waste, contaminated equipment, Ci 7.88E-01 1.16E+03 2.56E+03 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 Cobalt-58 1.32E-02 2.88E+00 E Cobalt-60 5.OOE+01 1.09E+04 E Iron-55 4.29E+01 9.35E+03 E Manganese-54 7.24E-01 1.58E+02 E Nickel-63 6.24E+00 1.36E+03 E Nickel-59 3.29E-02 7.17E+00 E Tantalum-182 6.59E-02 1.44E+01 E

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

Isotope Percent Curies Isotope Percent Curies Cerium-144 1.14E-02 4.25E-01 E Cobalt-58 2.92E-01 1.09E+01 E Cobalt-60 9.06E+00 3.38E+02 E Cesium-134 1.32E-01 4.91 E+00 E Cesium-137 3.25E-01 1.21 E+01 E Iron-55 7.43E+01 2.77E+03 E Iron-59 2.59E-01 9.66E+00 E Manganese-54 7.77E+00 2.90E+02 E Nickel-63 5.50E-01 2.05E+01 E Strontium-90 1.27E-01 4.75E+00 E Zinc-65 6.95E+00 2.59E+02 E Chromium-51 1.69E-01 6.31 E+00 E Niobium-95 1.47E-02 5.48E-01 E Antimony-124 5.60E-02 2.09E+00 E Antimony-125 1.90E-02 7.08E-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.

PAGE 12 of 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition No. of Shipments Mode of Transportation Destination 12 Truck
  • Energy Solutions Oak Ridge, TN Energy Solutions 2 Truck Barnwell, SC 2 Truck *Energy Solutions Kingston, TN 5 Truck
  • Studsvik Erwin, TN
  • - Volume Reduction Facility B. IRRADIATED FUEL SHIPMENTS (Disposition)

No. of Shipments Mode of Transportation Destination NONE PAGE 13 of 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 TABLE 3B SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. NRC CLASS A SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Dry compressible Waste (DAW), Non-compacted 1280 ftA3 STC 16 Contaminated Equipment, etc.

Dry compressible Waste (DAW), Non-compacted 49 ft^3 STC 1 Contaminated Equipment, etc.

Dry compressible Waste(DAW), Non-compacted 96 ftA3 STC 64 Contaminated Equipment, etc.

Dry compressible Waste(DAW), Non-compacted 108 ftA3 STC 1 Contaminated Equipment, etc.

B. NRC CLASS B Spent Resins, Filter Sludges, evaporator Air Drying 205.8 ftA3 HIC 1 Bottoms, etc. Non-compacted Spent Resins, Filter Sludges, evaporator\ Air Drying 120.3 ftA3 HIC 4 Bottoms, etc. Non-compacted C. NRC CLASS C Irradiated Hardware Non-compacted 57.4 ftA3 HIC 2 HIC- High Integrity Container STC- Strong Tight Container PAGE 14 of 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ATTACHMENT 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.

Revision 19 of the ODCM was approved by the Onsite Safety Review Committee on August 30, 2007 at Meeting Number [[::JAF-2007-011|JAF-2007-011]] and became effective on April 3, 2008. This revision does not reduce the accuracy or reliability of any dose calculations or setpoint determinations. Listed below is a brief summary of changes incorporated in this revision. Attached to this report is a revised copy of the ODCM.

The following changes were made as the result of a GAP Analysis performed between NUREG-1302 and the ODCM, Part I.

Rev 10 1. Through Part I, the format for terms listed in Section 1.3, Definitions was standardized to capitalize the first letter of each word when used in text in Part I. This change does not affect the accuracy of the ODCM.

2. Various minor editorial changes which do not change the intent of the content or requirements of the ODCM.
3. Part I Updated the Revision History of the ODCM. This Page 2 change does not affect the accuracy of the ODCM.

Sec. 1.2

4. Part I The Reference to 10CRF20.3(a)(17) was deleted as this Page 6 is a reference to the previous revision of 1 OCFR20. The Sec. 1.3.S correct reference to the current 1 OCFR 20 is retained in this section. This change improves the accuracy of the ODCM.
5. Part I The word "specification" was used in place of the Page 17 wording "Limiting Conditions for Operation". This change Sec. 2.3.3 was made to be consistent with working used in NUREG-1302.
6. Part I Table 3.1-3 lists the specific operability requirements for Page 25 & 26 gaseous effluent pathway (stack and building vents) flow Sec. 3.1.3 instrumentation and associated monitor flow rate instrumentation. Previous to this revision, operability requirements for flow instrumentation were contained in applicable plant procedures. Because the ODCM serves as a program document, the requirements were added to the ODCM to ensure that flow instrumentation operability requirements were identified. This change improves the accuracy of the ODCM.

PAGE 1 of 4

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ATTACHMENT 1 (CONTINUED)

7. Part I The number 500 mrem was corrected to 1500 mrem.

Page 28 This was a typographical error. This change makes the Sec. 3.2.3 ODCM consistent with NUREG-1302.

8. Part I The word "specification" was used in place of the Page 34 wording "Limiting Conditions for Operation". This change Sec. 3.3.3 was made to be consistent with wording used in NUREG-1302.
9. Part I Added the words "with half-lives greater than 8 days" to Page 35 further define the type of particulate material in gaseous Sec. 3.4.1.a effluents. This change increases the accuracy of the ODCM and is consistent with the wording in NUREG-1302.
10. Part I Added the words "with half-lives greater than 8. days" to Page 36 further define the type of particulate material in gaseous Sec. 3.4.2.a. effluents. This change increases the accuracy of the ODCM and is consistent with the wording in NUREG-1302.
11. Part I Added the words "with half-lives greater than 8 days" to Page 36 further define the type of particulate material in gaseous Sec. 3.4.2.b. effluents. This change increases the accuracy of th'e ODCM and is consistent with the wording in NUREG-1302.
12. Part I The wording "Limiting Condition of Operation" was Page 36 replaced with the word "specification". This change was Sec. 3.4.3 made to be consistent with wording used in NUREG-1302.
13. Part I Last line removed the word "not". The word "not" was a Page 39 typographical error and was deleted. This change Sec.3.6.1 .a increases the accuracy of the ODCM and is consistent with the wording in NUREG-1302.
14. Part I Reference appropriate TS section in ODCM section Page 39 3.6.1.c.2 and remove redundant shutdown statement Sec.3.6.1 .c.2 from ODCM. Add clarifying information to the ODCM Bases.
15. Part I ER JF-03-01442 has installed a logic changed to the Page 40 contact logic for the isolation of the Offgas system. The Sec.3.6.3 change involves only the isolation one and INOP alarms but does not impact the High-High Radiation isolation requirements.

PAGE 2 of 4

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ATTACHMENT 1 (CONTINUED)

16. Part I This specification used a distance of 8 km. The value was Page 44 converted to 5 miles to be consistent with other distances Sec.4.1.3 used in the ODCM, all of which are in miles. This change does not reduce the accuracy of the ODCM.
17. Part I Figure was updated to reflect the sale of the 9 Mile Point Page 45 Units 1 & 2 to Constellation Energy. This figure is now Sec.4.1.1 consistent with the Technical Specification figure. This change increases the accuracy of the ODCM.
18. Part I The term limit level in the equation was replaced with Page 47 reporting level to be consistent with NUREG-1302.

Sec.5.1.1.c.2

19. Part I The words "particulate samples" were added to the second Page 54 sentence for improved clarity and to make the note Table 5.1-1 consistent with NUREG-1 302. This change improves the Note (b) accuracy of the ODCM.
20. Part I Added to the table to provide a basis for using 30,000 uCi/I Page 55 for tritium and 20 pCi/I for 1-131. The note states that Sec.5.1-2 there is no drinking water pathway near the site.

Note (a)

21. Part I Added a footnote reference to provide a basis for using Page 56 the tritium in water LLD of 3000 pCi/I. This change Table 5.1-3 increases the accuracy of the ODCM.

Footnote (c)

22. Part I Revised to include the words "James A. FitzPatrick" Page 57 /Nine Mile Point sites for clarification. The words "1-131 Table 5.1.3 and 3000 pCi/liter is used for Tritium" were also added to Note (c) clarify that the values of 15 pCi/I and 3000 pCi/I were used as the required lower limits of detection because there is no drinking water pathway in the vicinity of the site. These changes increase the accuracy of the ODCM.
23. Part I Revise Offsite Dose Calculation Manual (ODCM) 8.1 .c.2 Page 65 by deleting the current shutdown requirement and replacing Table 8.1.c.2 it with a statement to enter the applicable Technical Specifications (TS) Conditions and Required Actions. In addition, add corresponding information to the ODCM Bases.
24. Part II Updated the Revision History of the ODCM. This change Page 2 does not affect the accuracy of the ODCM.

Sec. 1.3 PAGE 3 of 4

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ATTACHMENT 1 (CONTINUED)

25. Part II Update Reference 6.3, AP-02.08 was superseded. Added Page 82 EN-AD-1 03, Document Control and Records Management.

Sec. 6.3 Activities, Revision 03, April 29, 2005.

26. Part II Updated Reference 6.18, AP-03.04 to the current Revision, Page 83 Revision 12.

Sec. 6.18 Part II Updated Reference 6.19, changed wording of Hi Storm 100 Page 83 Cask System (ISFSI) to include Amendments 1 and 2.

Sec. 6.19

27. Part II Historical Noble gas releases from 1999 to 2003 for the Appendix E main stack were added to the table to update the release Table E-4 database with recent release totals and isotopic Page E-10 distribution. The historical data is used to develop effective dose transfer factors for dose calculations and stack and vent setpoint values. This change increases the accuracy of the ODCM.
28. Part II Fraction values for total elevated release (stack) were added Appendix E to the table for the years 1999 through 2003 to update the Table E-6 table with recent effluent data. The historical data is Page E-12 used in calculating setpoint values for the gaseous effluent pathways (stack and vents) for the plant. This change increases the accuracy of the ODCM.
29. Part II Rounded number to the nearest tenth.

Appendix H Table H-1 Page H-5

30. Part II Corrected typo on Garden Location No. 343, Appendix H Direction was corrected from ESE to E. This change Table H-1 increases the accuracy of the ODCM.

.0 Page H-9 PAGE 4 of 4

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ATTACHMENT 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.

Revision 1 to the Process Control Program, EN-RW-105 was approved by the Onsite Safety Review Committee on May 30, 2008 at Meeting [[::JAF-2008-008|JAF-2008-008]] and became effective on July 30, 2008. This revision does 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) Waste management practices section replaced dry and liquid waste management.
2) Waste stream sampling methods and frequency section added.
3) Waste classification Section added.
4) Quality Control section added.
5) Dewatering section added.
6) Waste packaging section added.
7) Miscellaneous section added for special tools/equipment & training requirements.

PAGE 1 of 1

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ATTACHMENT 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 2008 sampling program:

A. Sediment Sampling Program During the report period, one sample location for sediment from a shoreline area with existing or potential recreational value was changed. The ODCM required location was moved due to shoreline erosion. The new location is in the same geographical location and meteorological sector.

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

PAGE 1 of 1

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ATTACHMENT 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. The air sampling pump at the R-5 Offsite Environmental Sampling Station was inoperable for approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> during the sampling period of 8/19/08 to 8/26/08. 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.
2. The air sampling pump at the R-5 Offsite Environmental Sampling Station was inoperable for 46.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> during the sampling period of 8/26/08 to 9/03/08. 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 equipment failure. Air sample pump was replaced.
3. The air sampling pump at the R-5 Offsite Environmental Sampling Station was inoperable for 14.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> during the sampling period of 9/03/08 to 9/05/08. 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 air' sample vacuum pump and blower fan were replaced.

PAGE 1 of 2

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ATTACHMENT 4 (CONTINUED)

4. The air sampling pumps at the R-3 offsite and R-4 offsite Environmental Sampling Stations were inoperable for 30.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 31.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, respectively during the sampling period of 9/09/08 to 9/16/08. 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. The power outage was due to Hurricane Ike. No corrective actions were required to restore unit to service.
5. The air sampling pump at the R-5 Offsite Environmental Sampling Station was inoperable for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the sampling period of 10/28/08 to 11/04/08. 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 due to high winds.

No corrective actions were required to restore unit to service.

6. The air sampling pumps at the R-3 Offsite and R-4 Offsite Environmental Sampling Stations were each inoperable for 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the sampling period of 11/25/08 to 12/02/08. The air sample pumps were 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.

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 43,785 hours0.00909 days <br />0.218 hours <br />0.0013 weeks <br />2.986925e-4 months <br /> out of a possible 43,920 hours0.0106 days <br />0.256 hours <br />0.00152 weeks <br />3.5006e-4 months <br />. The air sampling availability factor for the report period was 99.69%.

PAGE 2 of 2

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ATTACHMENT 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.

PAGE 1 of 1

ENTERGY NUCLEAR OPERATIQNS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ATTACHMENT 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.

PAGE 1 of 1

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ATTACHMENT 7 ONSITE GROUND WATER MONITORING A) Gamma Isotopic Monitoring Monitoring Wells (5-9) were sampled and analyzed quarterly 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

(ýtCi/ml) (jtCi/ml)

Manganese-54 5.OE-7 lodine-131 1.OE-6 Cobalt-58 5.OE-7 Cesium-134 5.OE-7 Iron-59 5.OE-7 Cesium-137 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 5.0E-5 There were no plant related nuclides detected in the samples.

B) Tritium Monitoring Monitoring Wells (5-9) were sampled and analyzed quarterly 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 <1000 6 1000 <1000 7 1000 <1000 8 1000 <1000 9 1000 <1000 PAGE 1 of 1

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ATTACHMENT 8 INOPERATIVE EFFLUENT SAMPLING EQUIPMENT In accordance with the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Controls (REC) Section 3.1.1 .c.3.b, Inoperative Effluent Sampling Equipment that is not within 30 days requires an explanation of why the inoperability was not corrected within 30 days on the next Radioactive Release Report.

The refuel floor iodine and particulate sample pump, 17P-28, was found inoperable on 9/15/08. The cause was faulty motor overloads which caused the pump to trip when being supplied by alternate power during a plant shutdown for refueling outage. Temporary samples (Iodine & Particulate) were setup on refuel floor ventilation system in accordance with the ODCM.

The sample pump and motor were replaced with more robust overload protection. A faulty transformer was obsolete and an equivalent transformer was engineered as a replacement part.

On 1/26/09, the 600-120V and 120-24V transformers were replaced and 17P-28 and the installed iodine and particulate sample system was returned to service.

PAGE 1 of 1

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ADDENDUM 1 ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2008

1. INTRODUCTION The James A. FitzPatrick'Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Controls, requires an assessment of the radiation doses to the public due to radioactive liquid and gaseous effluents. This assessment of doses to the public is based on accepted methodologies found in the Offsite Dose Calculation Manual (ODCM).
2. DOSE LIMITS A. DOSE FROM LIQUID EFFLUENTS (ODCM, Part 1, REC 2.3)

Applicability Applies to doses from radioactive material in liquid effluents.

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

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

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

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

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

PAGE 1 of 10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 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.

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.

PAGE 2 of 10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 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-131, Iodine-133, Tritium, and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents.

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

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

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

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

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

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

PAGE 3 of 10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ADDENDUM 1 (continued)

Specifications The dose or dose commitment to any member of the public, due to.

releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited as follows:

1. Less than or equal to 25 mrem/year to the whole body; and,
2. Less than or equal to 25 mrem/year to any organ except the thyroid which shall be limited to less than or equal to 75 mrem/year.
3. DOSE ASSESSMENT A. METHODOLOGY The assessment of radiation doses to the public due to radioactive liquid and gaseous effluents is performed in accordance with the ODCM. The ODCM is based on methodologies and models suggested by the "Guidance Manual For Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREG-0133) and "Calculation of Annual Doses~to Man from Routine Releases of Reactor Effluents for the purpose of Evaluating Compliance with 10CFR50, Appendix I" (Regulatory Guide 1.109).

B. ASSUMPTIONS Dose calculations are performed using formulas and constants defined in the ODCM. Specific radioactive release activities used in the dose calculations are listed in the Annual Radioactive Effluent Release Report (1.21 Report) for the period of January 1, 2008 to December,31, 2008. Historical meteorological data was used to generate tables of average dispersion factors. Locations of interest were identified from the 2008 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.

PAGE 4 of 10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 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)

PAGE 5 of 10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 2008 A. LIQUIDS QUARTER 1 2 3 4 ANNUAL (a) (a) (a) (a) (a)

Organ (mrem) 6.16E-06 3.04E-06 3.49E-06 3.58E-06 1.63E-05

% of Limit 1.23E-04 6.08E-05 6.99E-05 7.17E-05 1.63E-04 (b) (b) (b) (b) (b)

Whole Body (mrem) 6.16E-06 3.04E-06 3.49E-06 3.58E-06 1.63E-05

% of Limit 4.11E-04 2.03E-04 2.33E-04 2.39E-04 5.43E-04 (a) Dose to the Child Liver primarily by the potable water pathway.

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

B. NOBLE GASES QUARTER 1 2 3 4 ANNUAL Total Body (mrem/yr) 1.11 E-02 4.12E-01 2.10E-02 4.18E-02 4.12E-01

% of Limit 2.22E-03 8.24E-02 4.19E-03 8.35E-03 8.24E-02 Skin (mrem/yr) 1.34E-02 5.31E-01 2.94E-02 5.39E-02 5.31E-01

% of Limit 4.48E-04 1.77E-02 9.82E-04 1.80E-03 1.77E-02 Gamma (mrad) 4.28E-04 1.92E-03 4.36E-04 3.22E-04 3.11E-03

% of Limit 8.55E-03 3.83E-02 8.71 E-03 6.44E-03 3.11E-02 Beta (mrad) 5.15E-05 3.03E-04 1.02E-04 4.59E-05 5.02E-04

% of Limit 5.15E-04 3.03E-03 1.02E-03 4.59E-04 2.51E-03 PAGE 6 of 10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 2008 C. IODINES AND PARTICULATES QUARTER 1 2 3 4 ANNUAL (a) (c) (c) (b) (c)

Organ (mrem) 3.OOE-03 2.66E-03 5.47E-03 1.78E-03 1.29E-02

% of Limit 4.OOE-02 3.55E-02 7.30E-02 2.37E-02 8.60E-02 (a) (a) (a) (a) ,(a)

Organ Dose Rate 2.96E-04 3.38E-04 8.84E-04 2.93E-04 8.84E-04 (mrem/yr)

% of Limit 1.97E-05 2.25E-05 5.89E-05 1.95E-05 5.89E-05 (a) Dose to the Child Thyroid primarily by the vegetation pathway.

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

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

PAGE 7 of 10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 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) (I/m2)

1. Garden 0.90 mi @ 830 E ST 2.83E-08* 1.75E-09 Grazing Season 0.90 mi @ 830E RX 2.02E-07* 5.01 E-09 Cary 0.90 mi @ 830E TB 1.83E-07* 4.80E-09 Location No. 78 0.90 mi @ 830E RF 2.02E-07* 5.01 E-09 0.90 mi @ 83 0 E RW 3.21 E-07* 5.76E-09
2. Meat 1.18 mi @ 127 0 SE 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 mi @ 127 0 SE TB 5.14E-08* 1.27E-09 Location No. 26 1.18 mi @ 127 0 SE RF 5.36E-08* 1.30E-09 1.18 mi @ 127 0 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 0 SE RX 2.76E-08* 4.14E-10 France 2.50 mi @ 139 0 SE TB, 2.71 E-08* 4.07E-10 Location No. 10 2.50 mi @ 139 0 SE RF 2.76E-08* 4.14E-10 2.50 mi @ 139 0 SE RW 4.15E-08* 4.36E-10
4. Goat (D/Q) 3.62 mi @ 113 0 ESE ST 2.28E-10 Grazing Season 3.62 mi @ 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 0 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 0SSE RW 3.59E-08*

PAGE 8 of 10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 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) (I/m2)

6. Resident Annual Average
a. Inhalation(2) 1.55 mi @ 900E('). ST 2.99E-08 Cary 0.90 mi @ 83 0E 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 0E RW 3.06E-07
b. Deposition(3) 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 0ESE 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 @ 90°E(1 ) ST 2.99E-08 Annual Average 0.60 mi @ 90 0 E ST(fc) 1.16E-07 Site Boundary 0.60 mi @ 90 0 E RX 3.58E-07 0.60 mi @ 90 0 E TB 3.19E-07 0.60 mi @ 90 0 E RF 3.58E-07 0.60 mi @ 90 0 E RW 5.39E-07
2. Total Body 0.60 mi @ 90 0 E ST(fc) 1.16E-07 -----------

Annual Average 0.60 mi @ 900 E RX 3.58E-07 -----------

Site Boundary 0.60 mi @ 90'E TB 3.19E-07 -----------

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

0.60 mi @ 90 0 E RW 5.39E-07 -----------

,PAGE 9 of 10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2008-DECEMBER 2008 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) (1/m2)

3. Skin 1.55 mi @ 90 0 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 0 E RF 3.58E-07 0.60 mi @ 90'E RW 5.39E-07
    • Based on ODCM X/Q, D/Q Values Rev. 08 (1) Highest Sector Average X/Q in a populated area, not an identified residence.

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

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

ST = Main Stack RX = Reactor Building Vent TB = Turbine Building Vent RF = Refuel Floor Vent RW = Radwaste Building Vent

  • fc = Finite Cloud PAGE 10 of 10
Retrieved from "https://kanterella.com/w/index.php?title=JAFP-09-0055,_Annual_Radioactive_Effluent_Release_Report,_for_the_Period_of_January_1,_2008_Through_December_31,_2008&oldid=2563435"