JAFP-03-0056, Annual Radioactive Effluent Release Report for January 1, 2002 Through December 31, 2002

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Annual Radioactive Effluent Release Report for January 1, 2002 Through December 31, 2002
ML053420227
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/23/2003
From: Ted Sullivan
FitzPatrick, Entergy Nuclear Northeast, Entergy Nuclear Operations
To: Miller H
NRC Region 1
References
JAFP-03-0056, JREG-05-045
Download: ML053420227 (35)
v • d • e


Text

'-Entergy Entergy Nuclear Northeast Entergy Nuclear Operations. Inc.

James A. Fitzpatrick NPP P.O. Box 110 Lycoming. NY 13093 Tel 315 349 6024 Fax 315 349 6480 April 23, 2003 JAFP-03-0056 TA. Sullivan Vice President. Operations-AF United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 ATTENTION:

SUBJECT:

Mr. Hubert Miller Regional Administrator JAMES A. FITZPATRICK NUCLEAR POWER PLANT DKFlO T NO T l.Tr7IJWqFNP 1WO R-5Q ii)

Gentlemen:

Attached is the Anmini Rsfinnnhivt Fffliint Rel-mgee Rea=t for the period of January 1, 2002 through December 31, 2002. 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 2002 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 Very truly yoig, VICE PRESIDENT - OPERATIONS TAS/CAB/jbh Attachments Xc:

Document Control Desk (USNRC)

D. Sherman (ANM Library)

J. Knubel (ENOC/WPO)

C. Faison (ENOCIWPO)

J. Kelly (ENOC/WPO)

B. O'Grady W. Maguire T. Kurtz (NMPC)

J. Furfaro (ENOC/WPO)

P. Merges (NYSDEC)

NRC Resident Inspector RMS (JAF)

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 1, 2002 - DECEMBER 31,2002 DOCKET NO.: 50-333 LICENSE NO.: DPR-59

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002

')

SUPPLEMENTAL INFORMATION FACILITY: IAFNPP LICENSEE:

WNTERGCYNTTI.PAR OP.PRATTON5R NC

1.

Offsitp Once Cq nrlmlatinn Mamial Part 1 RadtinIngiral Cnnfrn1c

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 sldn 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 orbeyond 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).

1

)

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 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 pCi/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 mnrem 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.

AX Pffhinf nnepntratinng a.

b.

C.

d.

Fission and activation gases:

Iodines:

Particulates, half-lives >8 days:

Liquid effluents:

(1) Fission and activation products (mixture EC)

(p1Ci/ml)

(2) Tritium (pCi/ml)

(3) Dissolved and entrained gases (jiCi/ml)

(None specified)

(None specified)

(None specified)

(1afrter I Quarter 1 None None Quarter 3 None 1.00E-02 2.OOE-04 On girer 4 7.1OE-05 L.OOE-02 2.00E-04 1.OOE-02 1.OOE-02 2.OOE-04 2.00E-04 2

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 SUPPLEMENTAL INFORMATION (Continued)

3.

Average Energy (None specified)

4.

MP-aRiIrPtmPntc annd ArrrnYmahfnini nf Tntal Rain amxEv#ty

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, NC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 SUPPLEMENTAL INFORMATION (Continued)

5. BOe RAaBeies
a. Liquid-Canal (1) Number of batch releases:

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

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

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

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

(6) Total Activity Released (Ci)

(7) Total Volume Released (liters)

b. Tigituidi Non-Cnnil (1) Number of batch releases:

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

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

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

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

(6) Total Activity Released (Ci)

(7) Total Volume Released (liters)

O -grter I QudrteLr v 2mrter I

uiiarter4 NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE 1.00E+00 6.94E+02 6.94E+02 3.OOE+00 3.25E+02 1.80E+02 1.08E+02 7.OOE+01 2.13E-03 9.29E+04 9.OOE+00 5.74E+02 1.75E+02 6.94E+02 6.38E+01 6.94E+02 5.00E+01 3.66E-05 2.95E+04 3.69E-04 2.09E+05 4

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 SUPPLEMENTAL INFORMATION (Continued)

c. Gaseous:

There were no gaseous batch releases for this report period.

6.

Ahnnrmnl ]R1iages

a. Liquid:

lumrter I Quarter.

f uarfi I

Quarter4 (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 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES EST TOTAL 4=

aIIm a FRRQR 0 Fl f

QI1 CML A. FISSION AND ACTIVATION GASES

1. Total Release
2.

Average release rate for period

3.

Tech. Spec. Limit Ci 4.72E+00 7.94E+00 8.63E+01 8.53E+00 52.50E+01 pzCvsec 6.0IE-01 1.O1E+00 1.OBE+01 1.07E+00 B. IODINE-131

1.

Total lodine-131

2.

Average release rate for period

3.

Tech. Spec. Limit Ci 4.35E-05 5.17E-05 7.31E-05 1.14E-04

  • 2.50E+01

-CI/sec 5.53E-06 6.57E-06 9.16E-06 1.44E-05 C. PARTICULATES

1. Particulates with half-lives

>8 days

2.

Average release rate for a) period

3.

Tech. Spec. Limit

4.

Gross alpha radioactivity Ci 1.06E2-05 3.62E-06 2.68E-05 1.26E-04

53.60E+01 pCi/sec ci I1.35E-06 3.79E-07 4.62E-07 3.06E-07 3.37E-06 6.69E-07 I1.59E-05 4.19E-07 a2.5OE+01 D. TRIT7UM
1. Total Release
2.

Average release rate for period

3.

Tech. Spec. Limit Ci 8.48E+00 6.04E+DO 6A9E+00 2.79E+00

  • 2.50E+01 pCisec 1.08E+00 7.68E-01 8.16E-01 3.50E-01
  • E. PERCENT OF TECHNICAL SPECIFICATION LDMITS FISSION AND ACTIVATION GASES 1.

2.

3.

4.

5.

6.

Quarterly gamma air dose limit Quarterly beta air dose limit Yearly gamma air dose limit Yearly beta air dose limit Whole body dose rate limit Skin dose rate limit 2.91E-03 I1.36E-04 1 A5E-03 6.80E-05 1.86E-04 3.78E-05 4.54E-03 2.52E-D4 2.27E-03 1.26E-D4 2.36E-03 5.07E-D4 4.23E-02 3.32E-03 2.11E-02 1.66E-03 9.80E-03 2.12E-03 5.02E-03 3.28E-04 2.51E-03 1.64E-04 2.18E-03 4.64E-04 HALOGENS, TITIUM AND PARTICULATES WITH HALF-LIVES >8 DAYS 7.

8.

9.

Quarterly dose limit (organ)

Yearly dose limit (organ)

Organ dose rate limit 1.21 E-02 6.03E-03 1.71E-05 1.05E-02 5.27E-03 1.37E-05 1.63E-02 8.17E-03 1.35E-05 2.35E-02 1.17E-02 2.27E-05 6

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 TABLE 1B GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE NlTCLJ TFN RPL EARFl.

C

.I)iI QIJARIER I QTDAR77ER I QTTARTBR 3 (TTARTER 4

1. Fgtion n5assc Argon-41 Ci 4.26E+00 4.73E+00 1.03E+01 2.31 E+00 Krypton-85m\\

Ci 4.60E-01 8.00E-01 6.72E+00 6.12E-01 Krypton-87 Ci 3.50E-01 1.53E+01 9.64E-01 Krypton-88 Ci 3.64E-01 1.82E+01 1.13E+00 Xenon-133 Ci 1.-6IE-01 3.29E+00 2.63E-01 Xenon-135 Ci 3.30E-01 2.57E+01 6.35E-01 Xenon-135m Ci 2.96E-01 1.78E+00 3.60E-01 Xenon-137 Ci 1.61E-01 Xenon-138 Ci 8.78E-01 4.84E+00 2.26E+00 TOTAL Ci 4.72E+00 7.94E+00 8.63E+01 8.53E+00

2. Indinps lodine-131 Ci 2.13E-05 1.34E-05 8.95E-05 Iodine-133

-Ci-2.47E-06 2.29E-06 8.66E-04 Iodine-135 Ci 9.52E-04 TOTAL Ci 2.38E-05 1.57E-05 1.91 E-03

3. Particulafteps Manganese-54 Ci 7.76E-07 8.84E-08 1.64E-06 Cobalt-60 Ci 4.22E-07 3.05E-08 1.61 E-07 Arsenic-76 Ci 1.63E-06 Strontium-89 Ci 4.67E-07 7.16E-07 1.27E-06 4.14E-07 Strontium-90 Ci 1.56E-08 6.87E-08 1.1 9E-07 6.61 E-04 Cerium-144 Ci 3.10E-08 3.47E-07 TOTAL Ci 4.83E-07 1.98E-06 1.54E-06 4.26E-06
4. Tritium Hydrogen-3 Ci 5.54E-01 7.05E-41 1.20E+00 6.58E-01 Note: There were no batch releases for this report period.

7

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 TABLE IC GASEOUS EFFLUENTS-GROUND LEVEL RELEASES Cf)NTIItITTCS MW1DE QIfARTR 2 QTTARTR 3 Ntl JDF. RITFEA.F.1)

XTNTT QlARTF.R I QMAUER A

1. Firsdn rasc None TOTAL CI Cl
2. Jodinies Iodine-131 lodine-1 33 TOTAL CI CI 4.35E-05 1.42E-04 1.86E-04 3.04E-05 2.69E-05 5.73E-05 5.97E-05 2.10E-04 2.70E-04 2.48E-05 2.48E-05 Ci
3. Earfirtelntes Chromium-51 Manganse-54 Cobalt-58 Iron-59 Cobalt-60 Zinc-65 Strontium-89 Strontium-90 Antimony-124 TOTAL
4. Tritlium Hydrogen-3 Ci CI Ci CI Ci CI CI Ci CI 928E-06 8.38E-07 1.01E-05 6.43E-07 1.00E-06 1.64E-06 2.02E-05 5.1I E-06 2.53E-05 2.61 E-05 4.11E-05 3.90E-06 1.70E-05 1.66E-05 5.76E-06 3.19E-06 7.20E-06 1 27E-06 1.22E-04 Ci Ci 7.93E+00 5.33E+00 5.28E+00 2.13E+o0 Note: There were no batch releases for this report period.

8

ENTERGY NUCLEAR OPERATIONS, NC.

JAMES A. FilTZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES EST TOTAL QTR I QTR f CM QIRA ERRQR 0e/

TNTm A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not including tritium, gases and alpha)
2. Average diluted concentration during period
3.

Applicable limit Ci NONE NONE 2.75E-03

1. Total Release
2.

Average diluted concentration during period

3.

Applicable limit Ci NONE NONE 3.66E-05 6.25E-01

<2.50E+01 ACi/mi NONE NONE 1.24E-06 2.11 E-06

.) C. DISSOLVED AND ENTRAINED GASES

1. Total Release
2.

Average diluted concentration during period

3.

Applicable Limit Ci NONE NONE

  • 2.50E+01 pCi/mi NONE NONE D. GROSS ALPHA RADIOACTIVITY
1. Total Release Ci NONE NONE 3.62E-07

<4.20E+01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION)

F. VOLUME OF DILUTION WATER USED DURING PERIOD iters liter NONE NONE NONE 2.95E404 3.01 E+05 NONE 2.17E+08

  • G. PERCENT OF TECHNICAL SPECIFICATION LIMTS
1. Quarterly Whole Body Dose
2.

Quarterly Organ Dose

3. Annual Whole Body Dose
4.

Annual Organ Dose 1.17E-06 3.50E-07 5.84E-07 1.75E-07 1.40E-03 7.98E-04 6.98E-04 3.99E-04 9

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 TABLE 2B LIQUID EFFLUENTS CANAL RATCH MOlDE NTTCHDIFS R

.FRTAS1)

TITN" QITARTFR I LITARTFR 2 QfTARTFR I QIIARTFR 4

1. Flk'nn snd Aetivntinn Prnductc Manganese-54 Ci 9.76E-04 Iron-55 Ci 6.32E-04 Iron-59 Ci 1.88E-04 Cobalt-60 Ci 8.44E-04 Zinc-65 Cl 7.88E-05 Strontium-89 Cl 2.74E-07 Strontium-90 Ci 5.47E-07 Cesium-137 Ci 3.14E-05 TOTAL Cl 2.75E-03 2.Irtilm HYDROGEN-3 Ci 6.25E-01

) 3. Diccn~ved and Fntrained tasci NONE Ci Note: There were no continuous mode discharges during this report period.

10

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 TABLE 2B (SUPPLEMENT)

LIQUID EFFLUENTS NON-CANAL

)

BRATr MOMF.

QIUARTFR 2 QUARTER I NTTCJ ThF. RF.1FACWFT NIT QIARTER I (OIARTER 4

1. Figginn and Aefyvstinn Prndurts NONE Ci
2. Tritium HYDROGEN-3
3. Dkcnived and TEntralned (a *es NONE Ci 3.66E-05 3.69E-04 Ci Note: There were no continuous mode discharges during this report period.

)

11

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. Fn PATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 TABLE 3A SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

)

A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 12-month Period

1. Type of Waste Unt CIas&A Claqq R Clagnss
a. Spent resins, filter sludges mA3 1.17E+01 O.OOE+O0 O.OOE+00 evaporator bottoms, etc.

Ci 9.18E+01 O.00E+00 O.OOE+00 Est. Total Eror Ye 1.00E+01 1.OOE+01 O.OOE+00 O.OOE+00

b. Dry compressible waste, contaminated equipment, etc.

mA3 Cl O.OOE+00 O.OOE400 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

c. Irradiated components, control rods, etc.
d. Other Dry compressible waste, contaminated equipment, spent resins for volume reduction.

mA3 O.OOE+00 O.OOE+00 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE4-00 O.OOE+00 O.OOE+00 1.OOE+01 1.00E+01 mA3 Cl 6.1OE.02 O.OOE.OO 6.02E..01 O.OOE+00

2.

Estimate of Major Nuclide Composition (by type of waste)

a.

Spent resins, filter sludges, evaporator bottoms, etc.

IaM t pf Iron-55 Cobaft-60

,- Manganese-54

.,/Zinc-65 6.48E+01 1.93E+01 7.OOE+OD 3.70E+00 5.95E+01 1.77E+01 6.42E+00 3.40E+00 E

M M

M Cesium-137 Nickel-63 Carbon-14 Tritium 3.26E+00 1.46E400 4.54E-01 1.OOE-03 Curie 2.99E400 1.34E+00 4.17E-01 8.94E-04 E

M E

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.

Isotop Iron-55 Cobalt-60 Manganese-54 Cesium-137 1 26E+02 4.15E+01 1.11 E+01 7.62E+00 3.68E+01 I1.38E+O1 2.87E+00 2.78E4.00 E

E E

E Zinc-65 Carbon-14 Nickel-63 Tritium 5.41E+00 4.38E+0o 2.63E+00 7.91 E-01 1.58E+00 I1.25E+00 8.77E-01 2.24E-01 E

E E

E (E-Estimated M-Measured)

Percentage of nuclides and total activities are based on a combination of direct measurements and scaling for non-gamma emitting nuclides.

12

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3.

Solid Waste Disposition n nf Shipmcnts MDdt-nf Trnsstinn esinAtinn 2

Truck Chem-Nuclear Systems, Inc.

Barnwell, SC 1

Truck

  • Diversified Scientific Services, Inc.

Kingston, TN 10 Truck

  • Duratek Oak Ridge, TN 5

Truck

  • Studsvik Erwin, TN
  • - Volume Reduction Facility B.

IRRADIATED FUEL SHIPMENTS (Disposition)

NnfS ipmentq Moe nf Trisportntinn DeatinAtion NONE 13

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 TABLE 3B SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

)

A.

NRC CLASS A SOURCE OF WAqSW PROCESSING FMPT MMf CONTAINER V)ITm TYPE OF CQNrTATNER NUMBER OF CONTAINERS Spent Resins, Filter Sludges, evaporator Bottoms, etc.

Dry compressible Waste (DAW),

Contaminated Equipment, etc.

Dry compressible Waste(DAW),

Contaminated Equipment, etc.

Air Drying Non-compacted Non-compacted Non-compacted 205.8 flA3 1280 ftA3 SAC 10 STC 14 87 W3 STC 21 Contaminated Oil B.

NRC CLASS B Non-compacted 7 ftA3 STC 21 SOURCE OF WARST PROCESSING EMPTLnOXE CONTAINER VIOTUMF TYPE OF rDNIAThNVR NUMBER OF r-NTA1MPRS NONE C.

NRC CLASS C SOURCE OF WASTE PROCESSING EPLOEvUFn CONTAINER VT I WE TYPE OF COWNTANFR NUMBER OF CrNTA1NFRR NONE Solidification Agent:

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

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 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.

Revision 17 of the ODCM was approved by the Plant Operating Review Committee on January 29, 2002 at Meeting No.02-002 and became effective on August 6, 2002. This revision does not reduce the accuracy or reliability of any dose calculations or setpoint determinations. Listed below is a brief summary of the changes incorporated in this revision. Attached to this report is a revised copy of the ODCM.

- Specified current revision number in Section 1.2 of Part 1 (REC) and Section 1.3 of Part 2 (ODCM).

- Changed Part 1 Section 1.3 definition title of Instrument Channel Calibration, Instrument Channel Functional Test, Instrument Check, and Logic System Function Test to Channel Calibration, Channel Functional Test Channel Check, and Logical System Functional Test respectively to be consistent with the titles used in the Improved Technical Specifications. As a result, the order of the definitions were revised to be in alphabetical order.

Changed references in Part I and Part 2 from Appendix A Technical Specifications to Technical Specifications in various locations since the Improved Technical Specifications only includes Appendix B. In addition, references to Appendix B of the Technical Specifications have been deleted since these Specifications have been relocated to this document. The appropriate Part 1 Section has replaced it, as applicable.

Definition of Dose Equivalent I-13 1 has been revised to be consistent with CTS/ITS definition.

The following definitions have been added to Part 1, Section 1.3: Mode, Process Control Program, Solidification, Surveillance Frequency Notation/Intervals.

Revised Part 1, Section 1.3 and Part 2, Section 2.0 definition of Unrestricted Area to be consistent with regulations.

Part 1, Section 1.4, Rules for Limiting Conditions for Operation and Surveillance Requirements.

Part 1 Specifications reference the ODCM. The explicit Part 2 Section has been included for clarity.

15

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 ATTACHMENT NO. 1 (Continued)

CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

The Semiannual Radioactive Effluent Release Report has been changed to Radioactive Effluent Release Report to be consistent with changes made to Technical Specifications. In addition, Section 6 has been added to include requirements of both the Radioactive Release Report and the Annual Radiological Environmental Operating Report.

The clarifying Note in Section 2.1.1.c.2 has been deleted since Section 2.1.1.c.2 clearly identifies when the Report is necessary.

Part 1, Section 2.1.3 Bases references the limits of 10 CFR 20. This reference has been replaced with Part 1, Section 2.2.1.c.1 since it better prescribes the limit.

The Frequency of the Logical System Functional Test in Part 1, Table 2.1-2 has been changed from Semiannually to "once per 24 months" to be consistent with the CTS requirements in CTS RETS Table 3.10-2.

Quarterly Channel Functional Test in Table 2.1-2 for Normal Service Water Effluent monitors has been deleted since it covered by the quarterly Channel Calibration Test. In addition, the quarterly Channel Functional Test in Table 3.1-2 for all Functions has been deleted for the same reason.

Table 2.1-2 Notes (g) and (h) have been deleted. Note (g) is deleted since there is no time delay relays associated with the logic circuits of this table. The first portion of Note (h) has been deleted since the Channel Functional Test definition in the Technical Specifications provides adequate guidance. The description on the method of calibration has been deleted since it implies a sensor calibration is not required. The same change has been made in Part 1, Table 3.1-2 for Notes (d) and (e).

NBS replaced with NIST in Part 1, Table 2.1-2 Note (e).

Part 1 Table 2.1-2 Note (f) and Table 3.1-2 Note (c) require a simulated automatic actuation test to be performed. The definition in the CTS has been deleted. The definition has been included in Note (f) and Note (c), respectively.

Part 1 Table 2.1-2 Note (g) replaces the old Note (g) that was deleted as described above.

This Note describes the proper method for performing a Channel Functional Test of a relay.

This detail is consistent with details found in the Inproved Technical Specification Bases for Technical Specification equipment. This same Note has been added to Part 1 Table 3.1-2 as Note (d).

Part 1, 2.2.1.c limit has been changed to be consistent with the limit specified in Improved Technical Specification 5.5.4 (10 CFR 20, Appendix B, Table II, Column 2 has been changed to Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402). The Part 1, Section 2.2.3 Bases and Part 2 (ODCM) has been changed to reflect the new limit.

16

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 ATTACHMENT NO. 1 (Continued)

CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

Details of Part 1, Section 3.1.l.c.4 concerning how the Alarm/trip set points are determined has been included in Part 1, Table 3.1-1 Note (b) since most of the details currently reside in the Note.

CTS numbers changed to appropriate Improved Technical Specifications Sections, as applicable.

Changed the word 'operable' to 'inoperable' in Part 1, Table 3.1-1 Note (a).

Main Stack Exhaust Function has been included in Table 3.1-1 to be consistent with Part 1, Section 3.1.1.c.1.a and Part 1 Table 3.1-2.

Title of Table 3.1-1 changed from "Radiation Monitors Systems that Initiate and/or Isolate Systems" to "Radiation Monitoring Systems" since the Main Stack Exhaust Function does not isolate its associated pathway. Notes (c), (d), and (e) have been added to prescribe the appropriate Operability requirements.

The original Note (c), cease operation of the refueling equipment, and Note (d) to isolate secondary containment and start the SBGTS, changed to refer to the Technical Specification 3.3.6.2 for the appropriate actions and in addition the requirements in Note (f) were also added since these requirements are consistent with requirements for the other Functions and also required by Part 1, Section 3.1.l.c.3.

The Frequency of the Logical System Functional Test in Part 1, Table 3.1-2 changed from Semiannually to "R" to be consistent with the CTS requirements in CTS RETS Table 3.10-2.

Section 5.0, Part 2 (ODCM) changed to include reference to 10 CFR 20.130.1(a)(1).

Section now states that compliance with the limits of 40 CFR 190 are deemed to demonstrate compliance with the 100 mrem/hr limits of 10 CFR 20.1301.

- Section 5.5, Part 2 (ODCM) added to describe how compliance with limits of 10 CFR 20.1301 is evaluated.

- The following Specifications have been added consistent with Improved Technical Specification Licensing Amendment:

- 3.6 Main Condenser Steam Jet Air Ejector Radiation Monitors 7.0 Major Modifications to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems 8.0 Purging of the Primary Containment

- Part 2 References to total body changed to whole body consistent with Part 1 Specifications.

17

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 ATTACHMENT NO. 1 (Continued)

CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

Added ECL definition to Part 2, Section 2.0 definitions and deleted MPC definition. Revised Section 3.0 calculation methodology to reflect new ECL definition. Incorporated new ECL limits in Table A-1.

Changed "Radiological and Enviromnental Services Management" to Chemistry/

Environmental Management" in Part 1, Section 3.5.b.

Deleted Appendix B, Table B-i (Unrestricted Area MPCs) and renumbered subsequent Appendix B tables.

Revised Appendix Figure F-4 to delete the 2nd recombiner.

Changed "On Site Storage" to "Temporary On Site Storage" in Appendix Figure F-6.

18

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 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 11 to the PCP implementing procedure FO-OP-032-41802 Setup and Operating Procedure for RDS-I000 Unit #9 at James A. FitzPatrick Nuclear was approved by the Plant Operating Review Committee on March 19, 2002 at Meeting #02-0078 and became effective on March 22, 2002. 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.

Incorporated changes to vendor procedure during revisions 8, 9, 10 and 11.

Revision 8

  • Identified four new references
  • Identifies the use of preventative maintenance procedure completion prior to operating RDS-1000.
  • Allows operator the option to protect the Hi-Hi float from exposure to the waste stream.
  • Incorporates lessons learned to prevent dewatering precoat media in used resin liners.
  • Ensures the float is free to operate.

Revision 9

  • Added the following statement: This procedure also allows liners to be filled and gross dewatered to meet the shipping cask Certificate of Compliance specifications for free standing water for shipment to an offsite processor for furither processing.
  • Added Caution and Note about liner to be shipped to offsite vendor for further processing.

Revision 10

  • Added a step that had been dropped between Revision 8 and Revision 9.

19

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 ATTACHMENT NO. 2 (CONTINUED)

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM Revision 11

  • Added a step to allow inline sampling
  • Revised Appendix B to clarify signature responsibilities
  • Corrected the following referenced steps:

4.1 Bead Resin Liners Bead Resin Liners will be considered dewatered when the following are performed in accordance with Step 6.12 and all the following acceptance criteria are met:

4.1.1 The dewatering pump has been run for one hour after the final flush.

4.1.2 The RDS 1000 has been run for a minimum of four hours 4.1.3 The moisture separator sight glass level does not increase more than l/2 inch during a 30-minute period.

4.2 Precoat Type Liners Precoat Type Liners will be considered dewatered when the following are performed in accordance with Step 6.13 and all the following acceptance criteria are met:

4.2.1 The dewatering pump has been run (after final flush) until requirements of Step 6.13.2 have been met.

4.2.2 The RDS 1000 has been run for a minimum of ( 1) eleven hours.

4.2.3 The moisture separator sight glass level does not increase more than 1 inch during a 30-minute period.

Revision 12 to the PCP implementing procedure FO-OP-032-41802 Setup and Operating Procedure for RDS-I000 Unit #9 at James A. FitzPatrick Nuclear was approved by the Plant Operating Review Committee on August 14, 2002 at Meeting 02-017 and became effective on August 23, 2002. 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 requirement that all dewatering performance data for resin and powdex liners be reviewed and signed by the vendor project manager prior to being declared to meet the dewatering requirements.

20

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 ATTACHMENT NO. 3

SUMMARY

OF CHANGES TO THE ENVIRONMENTAL MONITORING AND DOSE CALCULATION LOCATIONS In accordance with the James A. FitzPatrick Nuclear Power Plant Off Site Dose Calculation Manual (ODCM), Part 1, Sections 6.2.3 and 6.2.8 a listing of new locations for dose calculation and/or environmental monitoring identified by the land use census shall be included in the Annual Radioactive Effluent Release Report.

CHANGES IN ENVIRONMENTAL MONITORING LOCATIONS During the report period, no changes were made to the Environmental Monitoring Locations sampled to implement the requirements of the ODCM, Part 1, table 5.1-1. Sample location selections were based on the 2002 annual land use census. The 2002 land use census identified a new garden location that was sampled as an optional sample for the 2002 Radiological Environmental Monitoring Program. The garden is located in the east sector (96°) at a distance of 1.7 miles.

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

21

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 ATTACHMENT NO. 4 DEVIATIONS FROM THE REQUIRED ENVIRONMENTAL SAMPLING SCHEDULE In accordance with the James A. FitzPatrick Nuclear Power Plant Off Site Dose Calculation Manual (ODCM), Part 1, Section 6.2.7 the cause for the unavailability of any environmental samples required during the report period shall be included in the Annual Radioactive Effluent Release Report.

EXCEPTIONS TO THE 2002 ENVIRONMENTAL SAMPLNG PROGRAM

1.

The air sampling pump at the R-1 Environmental Sampling Station was inoperable for approximately 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> during the period of 02/05/02 through 02/12/02.

The inoperability of the sampling pump was the result of an electrical power failure caused by high winds. No corrective action was implemented.

2.

The air sampling pumps at the R-1 and R-2 Environmental Sampling Stations were inoperable for approximately 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> on 05/05/02. The inoperability of the sampling pumps was due to an electrical power outage caused by a tree falling on the near by electrical supply line. The damaged electrical line was repaired and pump operability was restored. No corrective action was implemented.

3.

Environmental Thermoluminescent Dosimeter (TLD) at ODCM location no. 91 was found to be missing during the first quarter 2002 change-out. TLD no. 91 is located on County Route 51A (156 degrees @ 4.8 miles). The TLD loss was the result of the phone company replacing the pole on which the TLD was deployed. The TLD was replaced during the quarterly change-out. There is no previous history of TLDs missing from this location. No corrective action was implemented.

4.

The air sampling pump at the R-1 Environmental Sampling Station was inoperable for approximately 1.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> on 11/02/02. The inoperability of the sampling pumps was the result of an electrical power outage that was weather related. No corrective action was implemented.

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

22

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 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 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 technical specification, meteorological data is not included in this report. It is retained on file and is available upon request.

23

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 ATTACHMENT NO. 6 MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS In accordance with the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part 1 Radiological Controls (REC) Section 7.0, Major Modifications to Radioactive Waste 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.

24

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 ADDENDUM 1 ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 2002

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 ER QM TITMI FT) TMT1TNTS (ODCM, Part 1, REC 2.3)

Applicabhility Applies to doses from radioactive material in liquid effluents.

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

Snpeifinaticn=

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.

G.ASEOTTUS DOSE RATPES (ODCK Part 1, REC 3.2)

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

25

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 ADDENDUM 1 (continued) objentive 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.

Sprcikatinns 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 mrcm/year to the skin from noble gases; and,
2. Less than or equal to lS00 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 OISEF NOLETP GASES (ODCM, Part 1, REC 3.3)

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

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

Soecficatnn 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.

26

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 ADDENDUM 1 (continued)

D.

lOPFl T)TOTO1Tf)TJFR-111 TTOlT)NF--l1 TRTTIM ANT)

RAT)TOWiTMTC SFT N PARTrTJM ATF PORM (ODCM, Part 1, REC 3.4)

Awplicab l it 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.

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

SpIeificadtfln 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.

TOTATT.YOPRFPTR M TTRAN1TTM TNOTFT. -(T

.F (ODCM, Part 1, REC 4.0)

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

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

27

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 ADDENDUM 1 (continued)

Rpenificatinsc 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.

MEIUQ110DLGXi 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 IOCFR50, Appendix r, (Regulatory Guide 1.109).

B.

ARSTTMPTTfONS 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 Semi-Annual Radioactive Effluent Release Reports (1.21 Reports) for the period of January 1, 2002 to December 31, 2002. Historical meteorological data was used to generate tables of average dispersion factors. Locations of interest were identified from the 2002 land use census. Dispersion factors and locations of interest used in performing the dose calculations are listed in Table 2.

C.

A SFRR MPNTRP'RT5r.T5R B ARY 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.

28

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 ADDENDUM 1 (continued)

4.

40 CFR 190 DOSE ASSESSMENT A.

MlFTIQT)fTLQry 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.

RESTLTST TThMARY The cumulative dose contribution from liquid and gaseous effluents for this report period were calculated and are listed in Table 1. The cumulative dose contribution from direct radiation from the reactor unit and from radwaste storage tanks is measured by environmental thermoluminescent dosimeters for the report period. This data is contained in the Annual Environmental Operating Report. The

)

calculated doses from liquid and gaseous effluents are less than twice their respective 10 CFR 50 limits, therefore, additional calculations are not necessary to demonstrate compliance with 40 CFR 190 dose limits (ODCM, Part 1, REC 4.1..c) 29

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FlTZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002

. ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 2002 A. LIQUIDS OTTARTFR 1-2 a

4 (c)

ANNTAT (C)

(a)

Organ (mrem)

% of Limit NONE NONE 1.75E-08 3.50E-07 (b) 3.99E-05 7.98E-04 (d) 2.09E-05 1.40E-03 3.99E-05 3.99E-04 (d) 2.09E-05 6.98E-04 Whole Body (mrem)

% of Limit NONE NONE 1.75E-08 1.17E-06

)

(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.

(c) Dose to the Teen Liver primarily by the fresh water fish pathway.

(d) Dose to the Adult Whole Body primarily by the fresh water fish pathway.

B. NOBLE GASES QUTARIER Total Body (mrem/yr)

% of Limit Skin (mremlyr)

% of Limit Gamma (mrad)

% of Limit Beta (mrad)

% of Limit 9.29E-04 1.86E-04 1.14E-03 3.78E-05 1.45E-04 2.91E-03 1.36E-05 1.36E-04 2

1.18E-02 2.36E-03 1.52E-02 5.07E-04 2.27E-04 4.54E-03 2.52E-05 2.52E-04 4.90E-02 9.80E-03 6.37E-02 2.12E-03 2.1 lE-03 4.23E-02 3.32E-04 3.32E-03 A

ANNUATL 1.09E-02 2.18E-03 1.39E-02 4.64E-04 2.51E-04 5.02E-03 3.28E-05 3.28E-04 4.90E-02 9.80E-03 6.37E-02 2.12E-03 2.74E-03 2.74E-02 4.04E-04 2.02E-03 30

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 ADDENDUM I (continued)

TABLE I ANNUAL DOSE ASSESSMENT 2002 C. IODINES AND PARTICULATES QTTARTFR 1

(a) 2 (b) 7.90E-04 1.05E-02 (d) a (b) 1.23E-03 1.63E-02 (d)

Organ (mrem)

% of Limit 9.05E-04 1.21E-02 4

(c) 1.76E-03 2.35E-02 (d)

ANNTTAT (b) 4.39E-03 2.92E-02 (d)

(d)

Organ Dose Rate (mrem./yr)

% of Limit 2.56E-04 2.05E-04 2.02E-04 3.40E-04 3.40E-04 1.71E-05 1.37E-05 1.35E-05 2.27E-05 2.27E-05

)

(a)

(b)

(c)

(d)

Dose to the Child Thyroid primarily by the vegetation pathway.

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

Dose to the Child Bone primarily by the vegetation pathway.

Dose to the Child Thyroid by the inhalation pathway.

31

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 ADDENDUM 1 (continued)

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

IODINE &

DISTANCE/

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

(1/n)

1. Garden Grazing Season Cary Location No. 78 0.93 mi 0.93 mi @

0.93 mi 0.93 mi @

0.93 mi @

820E 82°E 820E 820E 82°E ST RX TB RF RW 2.86E-08*

1.94E-07*

1.76E-07*

1.94E-07*

3.08E-07*

1.72E-09 4.76E-09 4.57E-09 4.76E-09 5.45E-09

2. Meat Grazing Season Parkhurst Location No. 26
3. Cow Grazing Season France Location No. 10 1.24 mi @ 1260SE 1.24 mi @ 1260SE 1.24 mi @ 126°SE 1.24 mi @ 1260SE 1.24 mi @ 126°SE 2.2 mi @ 1380SE 2.2 mi @ 1380SE 2.2 mi @ 138°SE 2.2 mi @ 1380SE 2.2 mi @ 1380SE ST RX TB RF RW ST RX TB RF RW 1.70E-08*

5.17E-08*

4.97E-08*

5.17E-08*

8.74E-08*

1.65E-08*

3.04E-08*

2.98E-08*

3.04E-08*

4.66E-08*

6.51E-10 1.24E-09 1.21E-09 1.24E-09 1.39E-09 3.1 lE-10 5.07E-10 4.97E-10 5.07E-10 5.39E-1 0

4. Goat Grazing Season Nickolas Location No. 61
5. Resident Annual Average 2.5 mi @ 146-SE 2.5 mi @ 1460SE 2.5 mi @ 1460SE 2.5 mi @ 1460SE 2.5 mi @ 1460SE ST RX TB RF RW 1.67E-08*

2.76E-08*

2.71E-08*

2.76E-08*

4.15E-08*

2.65E-10 4.14E-10 4.07E-10 4.14E-10 4.36E-10

a. Inhalation 1.55 mi @ 90E**

0.93 mi @ 820E 0.93 mi @ 820E 0.93 mi @ 820E 0.93 mi @ 820E ST RX TB RF RW 2.99E-08 1.98E-07 1.81E-07 1.98E-07 2.93E-07

  • Tritium Dose Calculation Only
    • Highest Sector Average X/Q in a populated area.

32

)

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY 2002-DECEMBER 2002 ADDENDUM 1 (continued)

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

IODINE &

DISTANCE/

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

(1/m2)

Sb. Deposition 0.70mi1 118 0SE ST 1.61E-09 0.70 mi @

11 80ESE RX 5.65E-09 0.70mi @ I18 0ESE TB 5.42E-09 0.70 mi @ 1 1SESE RF 5.65E-09 0.70 mi @ 1 180ESE RW 6.42E-09 B. NOBLE GASES

1. Air Dose 1.55 mi @ 900E ST 2.99E-08 Annual Average 0.6 mi @ 90°E ST(fc) 1.16E-07 0.6 mi @ 90°E RX 3.58E-07 0.6 mi @ 900E TB 3.19E-07 0.6 mi @ 900E RF 3.58E-07 0.6 mi @ 900E RW 5.39E-07
2. Total Body 0.6 mi @ 900E ST(fc) 1.16E-07 Annual Average 0.6 mi @ 900E RX 3.58E-07 0.6 mi @ 90°E TB 3.19E-07 0.6 mi @ 900E RF 3.58E-07 0.6 mi @ 900E RW 5.39E-07
3. Skin 1.55 mi @ 90 0E ST 2.99E-08 Annual Average 0.6 mi @ 90°E ST(fc) 1.16E-07 0.6 mi @ 900E RX 3.58E-07 0.6 mi @ 90°E TB 3.19E-07 0.6 mi @ 900E RF 3.58E-07 0.6 mi @ 900E RW 5.39E-07 ST = Main Stack RX - Reactor Building TB - Turbine Building Vent RF = Refuel Floor Vent RW - Radwaste Vent fc - Finite Cloud 33
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