JAFP-04-0054, Annual Radioactive Effluent Release Report for the Period of January 1, 2003 Through December 31, 2003

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Annual Radioactive Effluent Release Report for the Period of January 1, 2003 Through December 31, 2003
ML041260153
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/21/2004
From: Ted Sullivan
Entergy Nuclear Northeast, Entergy Nuclear Operations
To: Miller H
NRC Region 1
References
JAFP-04-0054, RG-1.021, Rev. 1, RG-10.001, Rev. 4
Download: ML041260153 (33)
v • d • e


Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. Fitzpatrick NPP I '(:

, Enterg RO. Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 April 21, 2004 T.A. Sullivan JAFP-04-0054 Site Vice President - JAF United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 ATTENTION: Mr. Hubert Miller Regional Administrator

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DTOCtKFT NO 50-snw I IrFNRP NO DPR-59 Gentlemen:

Attached is the Aninual Ra1dinartive Effluent Relea-e Report for the period of January 1, 2003 through December 31, 2003. 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 2003 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, SITE VICE PRESIDENT - JAF TAS/CAB/jbh Attachments Xc: Document Control Desk (USNRC) K. Mulligan NRC Resident Inspector D. Sherman (ANI Library) W. Maguire RMS (JAF)

B. O'Grady (ENOC/WPO) T. Kurtz (NMPC)

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

J. McCann (ENOC/WPO) P. Merges (NYSDEC)

PA0De

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1,2003 - DECEMBER 31,2003 DOCKET NO.: 50-333 LICENSE NO.: DPR-59

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 SUPPLEMENTAL INFORMATION FACILITY: .I-AEEP LICENSEE: FNTPR(W NTJVT FAR OPFRATTION.C IN(

1. Offgitp Dnqp Cralc1uatonn Mantial Part 1 Radin1ngiral ronnfrn'
a. Fission and Activation Gases:

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

(a) Less than or equal to 500 mrem/year to the whole body and less than or equal to 3000 mrem/year to the skin from noble gases.

(2) The air dose to areas at or beyond the site boundary from noble gases released from the plant in gaseous effluent shall be limited:

(a) During any calendar quarter, to less than or equal to 5 mrad from gamma radiation, and less than or equal to 10 mrad from beta radiation; and, (b) During any calendar year, to less than or equal to 10 mrad from gamma radiation and less than or equal to 20 mrad from beta radiation.

b. Tritium, Iodines and Particulates, Half Lives > 8 days:

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

(a) During any calendar quarter to less than or equal to 7.5 mrem to any organ; and, (b) During any calendar year to less than or equal to 15 mrem to any organ.

(c) Less than 0.1% of the limits of Specification 3.4.1.c.1.a and 3.4.1.c.l.b as a result of burning contaminated oil.

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

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

1

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 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. 1 nOXMffliipnt Cncpntrutionnq
a. Fission and activation gases: (None specified)
b. Iodines: (None specified)
c. Particulates, half-lives >8 days: (None specified)
d. Liquid effluents: Qularter I undrteL2 Oiadrtex-3 Qiadrter 4 (1) Fission and activation None None None None products (mixture EC)

(PCi/ml)

(2) Tritium (pCi/ml) 1.00E-02 1.00E-02 L.OOE-02 1.001E-02 (3) Dissolved and entrained gases (gCi/ml) 2.OOE-04 2.00E-04 2.OOE-04 2.OOE-04 2

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 SUPPLEMENTAL INFORMATION (continued)

3. Average .Energy (None specified)
4. MPcaqirPmentC anti Apprnyimatinnc nf Tntal Ra2dinrtivity
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 2003-DECEMBER 2003 SUPPLEMENTAL INFORMATION (continued)

5. Hatch RRlpesps
a. Tjiflid- anal uairter 1 nnrteL2 Dimrtern3 Onarter4 (1) Number of batch releases: 1.OOE+00 6.OOE+00 2.00E+00 6.00E+00 (2) Total time period for batch 4.00E+01 2.55E+02 5.OOE+01 1.78E+02 release: (min)

(3) Maximum time period for 4.OOE+01 7.OOE+01 5.00E+01 4.1 OE+0 1 batch release: (min)

(4) Average time period for 4.OOE+01 4.25E+01 2.55E+01 2.97E+01 batch release: (min)

(5) Minimum time period for 4.OOE+01 8.OOE+00 1.00E+00 1.70E+01 batch release: (min)

(6) Total Activity Released (Ci) 5.76E-06 1.34E-04 7.02E-05 2.34E-03 (7) Total Volume Released (liters) 6.93E+02 6.62E+03 1.09E+03 2.60E+04

b. Liquid- Non-Ctnnal (1) Number of batch releases: 9.OOE+00 6.OOE+00 8.OOE+00 3.OOE+00 (2) Total time period for batch 8.52E+02 8.59E+02 6.56E+02 1.49E+03 release: (min)

(3) Maximum time period for 4.89E+02 3.14E+02 2.64E+02 7.81E+02 batch release: (min)

(4) Average time period for 9.47E+01 1.43E+02 8.20E+01 4.97E+02 batch release: (min)

(5) Minimum time period for 5.OOE+00 1.80E+00 9.36E+00 6.06E+01 batch release: (min)

(6) Total Activity Released (Ci) 4.29E-04 3.27E-03 1.11 E-02 1.16E-03 (7) Total Volume Released (liters) 2.54E+05 4.01E+05 2.48E+05 5.62E+05 4

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 SUPPLEMENTAL INFORMATION (continued)

c. Gaseous:

There were no gaseous batch releases for this report period.

6. Abnnrmal Rplepsp9
a. Liquid: (indter I Qnarter2 (narter-a (Qurter4 (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 2003-DECEMBER 2003 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES EST TOTAL flMUN QE1 (T (TR 2 QIR _ OTR 4 FRRQR 0 A. FISSION AND ACTIVATION GASES

1. Total Release Ci 3.57E+00 4.49E+00 7.50E+00 7.09E+00 <2.50E+01
2. Average release rate for period pCi/sec 4.59E-01 5.71 E-01 9.44E-01 8.92E-01
3. Applicable ODCM Limit B. IODINE-131
1. Total lodine-131 Ci 6.86E-06 2.30E-08 3.70E-05 2.96E-06 :52.50E+01
2. Average release rate for period pCi/sec 8.82E-07 2.93E-09 4.65E-06 3.72E-07
3. Applicable ODCM Limit C. PARTICULATES
1. Particulates with half-lives

>8 days Ci 1.08E-05 1.45E-06 1.56E-05 1.00E-04 *3.60E+01

2. Average release rate for period pCisec I1.39E-06 1.84E-07 I1.96E-06 I1.26E-05
3. Applicable ODCM Limit
4. Gross alpha radioactivity Ci 7.35E-07 2.20E-07 I1.95E-07 2.48E-07 <52.50E+01 D. TRITIUM
1. Total Release Ci 4.23E+00 3.64E+00 4.87E+00 5.53E+00 .cs2.50E+01
2. Average release rate for period pCisec 5.44E-01 4.63E-01 6.13E-01 6.96E-01
3. Applicable ODCM Limit
  • E. PERCENT OF APPLICABLE ODCM LIMITS FISSION AND ACTIVATION GASES
1. Quarterly gamma air dose limit  % 2.04E-03 2.68E-03 4.47E-03 4.24E-03
2. Quarterly beta air dose limit  % 1.17E-04 1.26E-04 2.23E-04 I1.89E-04
3. Yearly gamma air dose limit  % 1.02E-03 1.34E-03 2.23E-03 2.12E-03
4. Yearly beta air dose limit  % 5.86E-05 6.31 E-05 1.11E-04 9.46E-05
5. Whole body dose rate limit  % 1.88E-03 1.94E-04 2.73E-03 2.86E-04
6. Skin dose rate limit  % 4.06E-04 3.91 E-05 5.89E-04 5.73E-05 HALOGENS, TRITIUM AND PARTICULATES WITH HALF-LIVES >8 DAYS
7. Quarterly dose limit (organ)  % 2.77E-03 I1.35E-03 6.OOE-03 3.71 E-03
8. Yearly dose limit (organ)  % 1.39E-03 6.73E-04 3.OOE-03 1.85E-03
9. Organ dose rate limit  % 7.81 E-06 6.84E-06 1.24E-05 9.16E-06 6

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 TABLE 1B GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE NlITCT.TDF. RFLFASFD ITNIT QITARTR I QITARTFR I QITARTER 3 QIUARTER 4

1. Ficcinn C.AqsuS Argon-41 Ci 2.21 E+00 3.67E+00 3.34E+00 4.57E+00 Krypton-85m Ci 4.46E-01 6.90E-01 1.1 IE+00 1.25E+00 Krypton-87 Ci 2.03E-01 2.96E-01 Krypton-88 Ci 1.34E-01 1.30E-01 1.41 E+00 9.40E-01 Xenon-133 Ci 4.34E-01 3.26E-01 Xenon-135 Ci 1.52E-01 2.92E-01 Xenon-1 35m Ci 9.03E-02 1.31E-01 Xenon-138 Ci 3.32E-01 4.82E-01 TOTAL Ci 3.57E+00 4.49E+00 7.50E+00 7.09E+00
2. Iadineg Iodine-131 Ci 5.31 E-06 2.30E-08 2.77E-05 Iodine-133 Ci 1.59E-05 TOTAL Ci 5.31 E-06 2.30E-08 4.36E-05
3. Partioclutes Manganese-54 Ci 3.52E-07 Strontium-89 CT 2.94E-07 2.85E-07 8.75E-07 6.66E-07 Strontium-90 Ci 2.42E-08 2.66E-08 4.65E-10 TOTAL Ci 6.70E-07 3.12E-07 8.75E-07 6.66E-07
4. Tritinm Hydrogen-3 Ci 5.07E41- 1.11 E+00 1.62E+00 9.28E-41 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 2003-DECEMBER 2003 TABLE IC GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTNITNUIOS MODE N1TCJTMFS RE!LEASFED J QIUARTIR 1 QUARTER 2 QWTARTFR 3 QIUARTER 4

1. Ficsinn Gases None Ci TOTAL Ci
2. ndines lodine-1 31 Ci 1.55E-06 9.28E-06 2.96E-06 Iodine-133 Ci 4.87E-06 TOTAL Ci 1.55E-06 1.42E-05 2.96E-06
3. PartrleIatnc Manganse-54 Ci 6.1 OE-06 4.05E-05 Cobalt-58 Ci 3.90E-07 1.44E-05 Iron-59 Ci 5.63E-06 Cobalt-60 Ci 3.68E-06 2.46E-06 1.49E-05 Zinc-65 Ci 4.43E-07 2.01 E-05 Strontium-89 Ci 6.11E-06 1.07E-06 5.26E-06 3.81 E-06 Strontium-90 Ci 2.85E-07 6.53E-08 2.55E-09 3.14E-07 TOTAL Ci 1.01 E-05 1.14E-06 1.47E-05 9.97E-05
4. Tritiim Hydrogen-3 CT 3.72E+00 2.53E+00 3.25E+00 4.60E+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 2003-DECEMBER 2003 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES EST TOTAL Tim QR I T2 QIQR I QIR 4 FRROR2/n A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not including tritium, gases and alpha) Ci NONE NONE NONE NONE <2.50E+01
2. Average diluted concentration during period ji1i/ml NONE NONE NONE NONE
3. Applicable ODCM Limit B. TRITIUM
1. Total Release Ci 4.41 E-04 3.38E-04 9.35E-04 1.06E-03 *2.50E+01
2. Average diluted concentration during period pCi/mi 1.71 E-06 1.34E-06 3.63E-06 7.05E-07
3. Applicable ODCM Limit * * *
  • C. DISSOLVED AND ENTRAINED GASES
1. Total Release Cl NONE NONE NONE NONE <2.50E+01
2. Average diluted concentration during period laCi/mi NONE NONE NONE NONE
3. Applicable ODCM Limit D. GROSS ALPHA RADIOACTIVITY
1. Total Release Ci NONE NONE NONE NONE <4.20E+01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) liters 2.55E+05 2.40E+05 2.49E+05 5.88E+05 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 5.72E+07 3.73E+08 7.64E+07 2.62E+08
  • G. PERCENT OF APPLICABLE ODCM LIMITS
1. Quarterly Whole Body Dose  % 1.24E-04 6.73E-05 3.81 E-04 1.76E-05
2. Quarterly Organ Dose  % 3.72E-05 2.02E-05 1.14E-04 5.29E-06
3. Annual Whole Body Dose  % 6.20E-05 3.36E-05 1.91 E-04 8.81 E-06
4. Annual Organ Dose  % 1.86E-05 1.01E-05 5.72E-05 2.64E-06 9

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 TABLE 2B LIQUID EFFLUENTS CANAL RATCTH MODE NTTCT! DES RFLF ASWD INIT QUIARTER I QUARTER 2 QUARTER 3 Q(1ARTER 4

1. Fisginn and Activatinn Prnoueftc NONE Ci
2. Triim HYDROGEN-3 Ci 5.76E-06 1.79E-05 2.99E-05 6.34E-04
3. MikgnIved and Fntrgined CGses NONE Ci Note: There were no continuous mode discharges during this report period.

10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 TABLE 2B (SUPPLEMENT)

LIQUID EFFLUENTS NON-CANAL RATCH MODE NIYCIIDFS RFL.EASED TuSWT QU ARTER 1 QITARTFIR X UARTER-3 Qf1ARTER 4

1. Figgion and Activatinn Prndmiets NONE Ci
2. TrItiim HYDROGEN-3 Ci 4.35E-04 3.20E-04 9.05E-04 4.15E-04
3. Dhqqnlvpd and Entrained Cases 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 2003-DECEMBER 2003 TABLE 3A SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-month Period Est. Total

1. Type of Waste Unit Class A Class R C qass C Error %
a. Spent resins, filter sludges mA3 1.17E+02 0.OOE+00 O.OOE+00 1.OOE+01 evaporator bottoms, etc. Ci 9.26E+01 0.OOE+00 O.OOE+00 1.OOE+01
b. Dry compressible waste, mA3 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 contaminated equipment, etc. Ci O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00
c. Irradiated components, mA3 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 control rods, etc. Ci O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00
d. Other: Dry compressible mA3 3.18E+02 O.OOE+00 O.OOE+00 1.OOE+01 waste, contaminated equipment, Ci 6.08E-01 O.OOE+00 O.OOE+00 1.OOE+01 spent resins for volume reduction.
2. Estimate of Major Nuclide Composition (by type of waste)
a. Spent resins, filter sludges, evaporator bottoms, etc.

Notopp PercAent Cnrips Isnotop Percent Curias Iron-55 5.89E+01 5.45E+01 E Cesium-1 37 1.45E+00 1.34E+00 E Cobalt-60 1.79E+01 1.66E+O1 M Nickel-63 1.39E+00 1.29E+00 M Manganese-54 1.31 E+01 1.21 E+01 M Carbon-14 1.20E+00 1.11 E+00 E Zinc-65 4.01 E+00 3.71 E+00 M Tritium 1.73E-01 1.61 E-01 E

b. Dry compressible waste, contaminated equipment, etc.

NONE

c. Irradiated components, control rods, etc.

NONE

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

Isotopp Percent r-tiis, Isatonp Percent Iron-55 5.03E+01 3.06E-01 E Zinc-65 2.81 E+00 1.71 E-02 E Cobalt-60 I1.25E+01 7.59E-02 E Carbon-14 1.37E+00 8.35E-03 E Manganese-54 6.56E+00 3.99E-02 E Nickel-63 8.03E-01 4.88E-03 E Cesium-137 I1.74E400 I1.06E-02 E Tritium 6.96E-01 4.23E-03 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 2003-DECEMBER 2003 TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition NnbnfShipments Mnde nfTranspnrtntinn De-ztinatnn 5 Truck *RACELLC Memphis TN I Truck *Diversified Scientific Services, Inc.

Kingston, TN 4 Truck

  • Duratek Oak Ridge, TN 17 Truck
  • Studsvik Erwin, TN
  • - Volume Reduction Facility B. IRRADIATED FUEL SHIPMENTS (Disposition)

Nn nf Shipmentcn Mnle of Transpnrtntinn Dlstinniinn NONE 13

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 TABLE 3B SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. NRC CLASS A SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPTLOXED yLT 1TMF CONTATNFR CONTAINERS Spent Resins, Filter Sludges, evaporator Air Drying 205.8 ftA3 HIC 20 Bottoms, etc. Non-compacted Dry compressible Waste (DAW), Non-compacted 1280 fi^3 STC 5 Contaminated Equipment, etc.

Dry compressible Waste(DAW), Non-compacted 87 fA3 STC 54 Contaminated Equipment, etc.

Contaminated Non-compacted 7 fRA3 STC 19 Oil B. NRC CLASS B SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTF EMPT(OYQn) VAT TTM CONTATNER CONTAINERS NONE C. NRC CLASS C SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE FMPTLOYXE VXTITM CONTATNFR CONTAINERS NONE Solidification Agent: NONE HIC- High Integrity Container STC- Strong Tight Container 14

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 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 revisions to the Offsite Dose Calculation Manual (ODCM) during this report period.

15

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 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.

Revision 13 to the PCP implementing procedure FO-OP-032-41802 Setup and Operating Procedure for RDS-1000 Unit #9 at James A. FitzPatrick was approved on May 21, 2003 and became effective June 6,2003. This revision does not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes. Listed below is a brief summary of the changes incorporated in this revision.

  • Added a step to dewater through each lateral at the completion of the fill sequence but prior to the actual start of the dewatering cycle.
  • Changed vacuum requirements for Precoat/Ecodex liners from less than 22" Hg to less than 25" Hg.
  • Revised Appendix B, Figure 1 for better appearance.
  • Revised Appendix B, Figure 2 to provide operating ranges.
  • Added Figure 3 to Appendix B to separate performance sheets for bead and powdex resins.

16

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 ATTACHMENT NO. 3

SUMMARY

OF CHANGES TO THE ENVIRONMENTAL MONITORING AND DOSE CALCULATION LOCATIONS In accordance with the James A. FitzPatrick Nuclear Power Plant ODCM, Part 1, Section 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 ILOCATTONS During the report period, no changes in the Environmental Monitoring Locations sampled to implement the requirements of ODCM, Part 1, Table 5.1-1 were made. There were no new locations identified in the 2003 Land Use census that required changes to the milch animal sampling program or dose receptor locations.

The 2003 sampling program did not utilize the optional food product vegetation location Fredette that was sampled in 2002. This sample location was replaced in the 2003 Sampling Program with the Kronenbitter location, which has a higherD/Q value. The Kronenbitter garden was not available for sampling in 2002.

NEW lOCATIONS FOR DOsR CATLCITHATIONS One of the receptors used for dose calculations for the 2003 release calculations changed from the previous year (2002). This change was the result of refining the distance and direction parameters from the JAF site using GPS technology. The previous distance and direction values were determined using map measurements. The GPS determinations are considered to be more accurate.

The change for the 2003 dose calculations was in the goat receptor. The goat receptor is now split between two locations. The goat receptor location for the X/Q grazing season is Nickolas (location 61); while the goat receptor for the grazing season D/Q value is Showers (location 71). The Nickolas location changed meteorological sectors from 1460 (SE) to 152° (SSE) as a result of the GPS evaluation of the receptor locations.

17

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 ATTACHMENT NO. 4 UNAVAILABILITY OF SAMPLES REQUIRED BY THE ENVIRONMENTAL SAMPLING SCHEDULE In accordance with the James A. FitzPatrick Nuclear Power Plant ODCM, Part 1, Section 6.2.7, the cause for unavailability of any environmental samples required during the report period shall be included in the Annual Radioactive Effluent Release Report.

The noted exceptions to the 2003 sample program address only those samples or monitoring requirements, which are required by the ODCM. This section reports samples that were a deviation from the requirements of ODCM Part 1,Table 5.1-1.

The following are deviations from the program specified by the ODCM:

Air Sampling Stations The ice storm of April 04, 2003 resulted in loss of power to the JAF/NMP site environmental monitoring stations. Due to the extent of damage to the municipal electrical distribution system and the wide area affected by the storm, 4 of the 5 stations required by the ODCM experienced a period of inoperability. The R-5 control station was not affected. The control station is located approximately 16 miles northeast of the site and was not within the ice storm area. As utility crews made repairs to the electrical distribution system, the environmental stations were returned to service. The length of the inoperability at each station was related to the time for restoration of municipal power lines. The specific inoperability times are listed in the table below:

Environmental Sample Station Tee Storm Power Loss (Anril 4-8. 2003)

Loss of Days Off Line Station Location Power Hours 4/4-8. 2003 RI-Offsite 79.3 3.3 R2-Offsite 79.3 3.3 R3-Offsite 43.6 1.8 R4-Offsite 43.6 1.8 18

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 ATTACHMENT NO. 4 (continued)

Radiological effluents records from the plant were reviewed and there was no indication of elevated releases during the inoperability period. Sample results from the environmental air sample station for the operable period during this sample week were normal and consistent with results from the previous week. No corrective action was implemented.

The air sampling pumps at the R-1 and R-2 Environmental Sampling Stations were inoperable for approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> during the period of September 15 through 22, 2003. The inoperability of the sampling pumps was caused by an electrical power outage that was weather related. No corrective action was implemented.

The air sampling pumps at the R-1 and R-2 Environmental Sampling Stations were inoperable for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> on 9/29/03. The inoperability of the sampling pumps was caused by a power outage that was weather related. No corrective action was implemented.

Environmental Thermoluminescent Dosimeter (TLD) number 14 was removed from a utility pole that was used to deploy the dosimeter during the third quarter 2003. The dosimeter was removed from the pole and placed on the ground by the utility maintenance crew that was replacing the pole.

The TLD was considered no longer in a position to correctly monitor direct radiation for that location. The results for this dosimeter are considered to be non-representative and therefore invalid. As a corrective action, the utility company was notified of this occurrence along with a list of all locations where TLDs are stationed on utility poles. Training material for instructing workers on removing and reinstalling dosimeters during maintenance was provided to the utility. The utility conducted a briefing on the subject with the line crew.

The Independent Spent Fuel Storage Installation (ISFSI) thermoluminescent dosimeter (TLD) number I-8 was found to be missing during the fourth quarter 2003 collection. The lost dosimeter was the result of high winds experienced during the deployment period. The damaged holder was replaced and a new dosimeter was installed.

Surface Water Sampling The Oswego Steam Station monthly composite sampler experienced an electrical trip during the period of 8/15/03 to 8/22/03. The GFI breaker on the system did not reset after power was restored.

Approximately four of the expected 15 gallons of water was collected during this period. The monthly composite is made up from weekly sample aliquots collected from the system. The GFI breaker was reset at the time of discovery. No additional corrective action was implemented.

The Oswego Steam Station monthly composite sampler experienced an electrical trip during the period of 9/12/03 to 9119103. The GFI breaker on the system did not reset after power was restored.

Approximately three of the expected 15 gallons of sample was collected during this period. The monthly composite is made up from weekly sample aliquots collected from the system. As a corrective action, the GF1 breaker was removed from the system. Subsequent failures of this system have not been experienced as of the date of this report.

19

ENTERGY NUCLEAR OPERATIONS, INC.

- JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 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 I 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.

20

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 ATTACHMENT NO. 6 MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS In accordance with the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part I Radiological 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.

21

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 ADDENDUM I ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2003

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 TIQUTI FTID FT.TTPN (ODCM, Part 1, REC 2.3)

Applirnhility Applies to doses from radioactive material in liquid effluents.

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

Sperifiratinns 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. GYASFOTD ToNF RATMS (ODCM, Part 1, REC 3.2)

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

22

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 ADDENDUM I (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.

ISpncifientinns 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 mremlyear 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. ATR ThON NORT.F GAPr'F (ODCM, Part 1, REC 3.3)

  • Aplicbility Applies to the air dose due to noble gases in gaseous effluents.

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

S!;pecifir atinns 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 mnrad from beta radiation.

23

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 ADDENDUM I (continued)

D. DO'F DTJF TO TODTNPF-1tl ,ODNF-13as TRTTHTTM AN R ADIONTT TELER TN PAR1TTT TATF FORM (ODCM, Part 1, REC 3.4)

Appliability 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.

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

ISpecifiratinns 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 DOqFFROMTJRANITTM FTPI. -(-CTF (ODCM,Part 1, REC 4.0)

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

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

24

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 ADDENDUM I (continued)

Speiflnains 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. METHODOLOG~Y 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 forNuclearPowerPlants" (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. ASTSMPTTONS 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, 2003 to December 31, 2003.

Historical meteorological data was used to generate tables of average dispersion factors. Locations of interest were identified from the 2003 land use census. Dispersion factors and locations of interest used in performing the dose calculations are listed in Table 2.

C. ARqF-qMPNTTR T RFMT5.TS WMMARY 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 2003-DECEMBER 2003 ADDENDUM I (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. REST TTTS T rIMMARY 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.I.c) 26

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 2003 A. LIQUIDS QIUARTER 1 2 a -4 ANNI AT (a) (a) (a) (a) (a)

Organ (mrem) 1.86E-06 1.OlE-06 5.72E-06 2.64E-07 8.85E-06

% of Limit 3.72E-05 2.02E-05 1.144E-04 5.29E-06 8.85E-05 (b) (b) (b) (b) (b)

Whole Body (mrem) 1.86E-06 1.OlE-06 5.72E-06 2.64E-07 8.85E-06

% of Limit 1.24E-04 6.73E-05 3.81E-04 1.76E-05 2.95E-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 O TARTER 2 a 4 A NUATL Total Body (mrem/yr) 9.39E-03 9.69E-04 1.36E-02 1.43E-03 1.36E-02

% of Limit 1.88E-03 1.94E-04 2.73E-03 2.86E-04 2.73E-03 Skin (mrem/yr) 1.22E-02 1.17E-03 1.77E-02 1.72E-03 1.77E-02

% of Limit 4.06E-04 3.91E-05 5.89E-04 5.73E-05 5.89E-04 Gamma (mrad) 1.02E-04 1.34E-04 2.23E-04 2.12E-04 6.71E-04

% of Limit 2.04E-03 2.68E-03 4.47E-03 4.24E-03 6.71E-03 Beta (mrad) 1.17E-05 1.26E-05 2.23E-05 1.89E-05 6.55E-05

% of Limit 1.17E-04 1.26E-04 2.23E-04 1.89E-04 3.28E-04 27

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 ADDENDUM I (continued)

TABLE I ANNUAL DOSE ASSESSMENT 2003 C. IODINES AND PARTICULATES QUART-ER 1 2 a -4 ANM TAT.

(a) (b) (a) (a) (a)

Organ (mrem) 2.08E-04 1.O1E-04 4.50E-04 2.78E-04 1.04E-03

% of Limit 2.77E-03 1.35E-03 6.00E-03 3.71E-03 6.91E-03 (a) (a) (a) (a) (a)

Organ Dose Rate 1.17E-04 1.03E-04 1.85E-04 1.37E-04 1.85E-04 (mrem/yr)

% of Limit 7.81E-06 6.84E-06 1.24E-05 9.16E-06 1.24E-05 (a) Dose to the Child Thyroid primarily by the vegetation pathway.

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

28

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 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) (/mr2)

1. Garden 0.90 mi @ 83 0 E ST 2.83E-08* 1.75E-09 Grazing Season 0.90 mi @ 830E RX 2.02E-07* 5.01E-09 Cary 0.90 mi @ 83 0 E TB 1.83E-07* 4.80E-09 Location No. 78 0.90mi@ 83°E RF 2.02E-07* 5.0IE-09 0.90 mi e 83°E RW 3.21E-07* 5.76E-09
2. Meat 1.18 mi @ 127 0SE ST 1.72E-08* 6.80E-10 Grazing Season 1.18 mi @ 1270SE RX 5.36E-08* 1.30E-09 Parkhurst 1.18 mi @ 127 0SE TB 5.14E-08* 1.27E-09 Location No.26 1.18 mi @ 127 0SE RF 5.36E-08* 1.30E-09 1.18 mi @ 127 0SE RW 9.12E-08* 1.46E-09
3. Cow 2.50 mi @ 139 0SE ST 1.67E-08* 2.65E-10 Grazing Season 2.50 mi @ 139 0SE RX 2.76E-08* 4.14E-10 France 2.50 mi @ 139 0SE TB 2.71E-08* 4.07E-10 Location No. 10 2.50 mi @ 1390SE RF 2.76E-08* 4.14E-10 2.50 mi @ 1390SE RW 4.15E-08* 4.36E-10
4. Goat (D/Q) 3.62 mi @ 1130ESE ST ---------- 2.28E-10 Grazing Season 3.62 mi @ 1130ESE RX ---------- 3.40E-10 Showers 3.62 mi @ 1130ESE TB -------- 3.33E-10 Location No. 71 3.62 mi @ 1130ESE RF ----- 3.40E-10 3.62 mi @ 113oESE RW 3.49E-10
5. Goat (X/Q) 2.64 mi @ 152°SSE ST 1.94E-08* ----------

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

Nickolas 2.64 mi @ 152°SSE TB 2.57E-08* ----------

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

2.64 mi @ 152°SSE RW 3.59E-08*

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I ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 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) (ltm2)

6. Resident Annual Average
a. Inhalation(') 1.55 mi @ 90E(0 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 0 E RF 2.07E-07 0.90 mi @ 83 0 E RW 3.06E-07
b. Deposition(3) 0.71 mi @ 118 0ESE ST 1.60E-09 Whaley 0.71 mi @ 118 0ESE RX ---------- 5.52E-09 Location No. 199 0.71 mi @ 118 0ESE TB 5.30E-09 0.71 mi @ 118oESE RF 5.52E-09 0.71 mi @ 118oESE RW 6.28E-09 B. NOBLE GASES
1. Air Dose 1.55 mi @ 90E 0 ) ST 2.99E-08 Annual Average 0.60 mi @ 90°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 @ 90 0 E RX 3.58E-07 Site Boundary 0.60 mi @ 900 E TB 3.19E-07 0.60 mi @ 900E RF 3.58E-07 0.60 mi @ 900 E RW 5.39E-07 30

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2003-DECEMBER 2003 ADDENDUM I (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) (11m2)

3. Skin 1.55 mi @ 900 E ST 2.99E-08 --

Annual Average 0.60 mi @ 90 0E ST(fc) 1.16E-07 -----------

Site Boundary 0.60 mi @ 900E RX 3.58E-07 0.60 mi @ 900E TB 3.19E-07 ------

0.60 mi @ 900E RF 3.58E-07 --

0.60 mi @ 900E RW 5.39E-07 -----------

  • Tritiumn Dose Calculation
    • Based on ODCM XIQ, D/Q Values Rev. 08 (I) Highest Sector Average X/Q in a populated area, not an identified residence.

(2) Inhalation uses Annual Average XIQ 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 31

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