ML20034F112

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Effluent & Waste Disposal Semiannual Rept for Jul-Dec 1992
ML20034F112
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 12/31/1992
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20034F103 List:
References
NUDOCS 9303020286
Download: ML20034F112 (26)
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER FIANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1,1992 - DECEMBER 31,1992 DOCKET NO.: 50-333 LICENSE NO.: DPR-59 I

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NEW YORK POWER AUTHORITY i

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 SUPPLEMENTAL INFORMATION FACILITY: JAFNPP LICENSEE: NEW YORK POWER AUTHORITY r

1.

Technical Specification Limits a.

Fission and Activation Gases:

f (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:

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

1 (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.

l 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 rele-ased 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 i

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.a.1 and 3.4.a.2 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).

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 SUPPLEMENTAL INFORMATION (Continued) c.

Liquid Effluents:

(1) The concentration of radioactive materials released to the unrestricted areas shall not exceed the values specified in 10 CFR 20, Appendix B, Table II, Column 2. For dissolved or entrained noble gases the concentration shall be limited to 2.00E-N Ci/ml.

i (2) The dose to a member of the public from radioactive materials released from the plant in liquid effluents to unrestricted areas shall be limite

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is 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.

Maximum Permissible Concentrations a.

Fission and activation gases:

(None specified) b.

Iodines:

(None specified) c.

Particulates, half-lives >8 days:

(None specified) d.

Liquid effluents:

Ouarter 3 Ouarter 4 (1) Fission and activation 5.51E-05 1.10E-M products (mixture MPC)

(pCi/ml)

(2) Tritium (pCi/ml) 3.00E-03 3.00E-03 (3) Dissolved and entrained gases (pCi/ml) 2.00E-M 2.00E-M 2

.e NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT' EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 l

SUPPLEMENTAL INFORMATION (Continued)

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3.

Averane Enerry (None specified)

I 4.

Measurements and Anoroximations of Total Radioactivity 3

a.

Fission and Activation Gases: Continuous monitor on each release path calibrated to a marinelli grab sample analyzed by gamma spectroscopy; bubbler l

grab sample analyzed for Tritium.

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s b.

Iodines: Gamma spectral analysis of charcoal cartridge and particulate filter on l

each release path.

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Particulates: Gamma spectral analysis of each particulate filter and charcoal i

cartridge for each release path. A four week per quarter composite of j

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.

I e.

Solid Waste: Gamma spectral analysis of a representative sample of each waste l

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.

l f.

Error Estimation Method: Overall error for sampling and analysis estimated by combining individual errors using error propagation methods. This processs-composed of determinate and undeterminate errors.

Determinate - Pump flowrates, volume measurements and analysis collection yields j

Undeterminate - Random counting error estimated using accepted statistical

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calculations J

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NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 SUPPLEMENTAL INFORMATION (Continued) 5.

Batch Releases

a. Liquid:

Ouarter 3 Ouarter 4 L

(1) Number of batch releases:

3.70E + 01 1.10E + 01 (2) Total time period for batch 2.90E + 03 7.75E + 0?

release: (min)

(3) Maximum time period for 1.10E + 02 7.90E + 01 batch release: (min)

(4) Average time period for 7.84E+ 01 7.05E + 01 batch release: (min)

(5) Minimum time period for 6.00E + 01 5.40E + 01 batch release: (min)

b. Gaseous:

There were no gaseous batch releases for this report period.

6.

Abnormal Releases a.

Liquid:

Ouarter 3 Ouarter 4 (1) Number of releases:

None None (2) Total activity released:

None None b.

Gaseous i

(1) Number of releases:

None None (2) Total activity released:

None None i

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NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PIJuNT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES EST TOTAL UNIT OUARTER 3 OUARTER 4 ERROR %

A.

FISSION AND ACTIVATION GASES 1.

Total Release Cl 3.24E+01 2.95E+01 52.50E+01 2.

Average release rate for period pCl/sec 4.07E+00 3.71E+00 3.

Tech. Spec. Limit B. IODINE.131

$2.50E+01 1.

Total lodine-131 C1 2.

Average release rate for period Ci/sec 3.

Tech. Spec. Umit C. IODINE-133 AND PARTICULA 1ES 1.

todine-133 and Particulates with half-lives >8 days Cl 5.73E-05 1.07E-05 s2.50E+01 2.

Average release rate for period pCi/sec 7.21E-06 1.35E-06 3.

Tech. Spec. Limit 4.

Gross alpha radioactivity Cl 1.12E-06 1.05E-06

$2.50E+01 l

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D. TRITIU51 1.

Total Release Ci 3.62E-01 2.24E-01 52.50E+01 2.

Average release rate for period pCi/sec 4.56E-02 2.81E-02 3.

Tech. Spec. Limit l

  • E. PERCENT OF TECHNICAL SPECIFICATION LINIITS l

FISSION AND ACTIVATION GASES 1.

Quartetty gamma air dose limit 4.09E-03 1.35E-02 2.

Quarterly beta air dose limit 7.72E-03 8.13E-03 3.

Yearty gamma air dose limit 2.O5E-03 6.76E-03 4.

Yearty beta air dose limit 3.86E-03 4.07E-03 5.

Whole body dose rate limit 4.11E-04 2.95E-03 6.

Skin dose rate limit 3.31E-04 8.22E-04 HALOGENS, TRITIUM AND PARTICULATES WITH HALF. LIVES >8 DAYS 7.

Quarterty dose limit (organ) 2.36E-03 7.28E-04 8.

Yearty dose limit (organ) 1.18E-03 3.64E-04 9.

Organ dose rate limit 7.96E-04 6.31E-05 5

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NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PIJuNT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 r

TABLE IB GASEOUS EFFLUENTS-ELEVATED RELEASE i

CONTINUOUS MODE NUCLIDES RELEASED UNIT OUARTER 3 OUARTER 4

1. Fission Gases 1.50E-01 Krypton-85m Cl Krypton-88 Cl 1.31E-02 2.80E-02 Xenon-131m Cl 5.65E-01 6.44E-01 Xenon-133 Ci 4.44E-02 1.37E-01 Xenon-133m Ci 2.87E-02 3.09E-01 Xenon-135 Ci 2.09E-02 TOTAL Cl 6.72E-01 1.27E+00
2. Iodines lodine-131 Ci lodine-133 Ci TOTAL Ci
3. Particulates Ruthenium-103 Ci 5.77E-08 2.20E-07 Cesium-137 Ci TOTAL Ci 5.77E-08 2.20E-07
4. Tritturn Hydrogen-3 Ci 2.19E-03 3.31E-03 Note: There were no batch releases for this report period.

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL -

i SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 I

TABLE IC GASEOUS EFFLUENTS--GROUND LEVEL RELEASES i

CONTINUOUS MODE NUCLIDES RELEASED UNIT OUARTER 3 OUARTER 4 l

1. F1ssion Gases 3.91E+00 i

Krypton-85m Cl Krypton-87 Cl 1.89E-01 6.81E-_01 l

1.95E+00 i

Krypton-88 Cl Xenon-131m Cl 2.77E+01 9.59E+00 Xenon-133 Cl 3.24E+00 Xenon-133m Ci 6.45E-01 8.69E+00 i

Xenon-135 Ci 3.17E+00 1.66E-01 TOTAL Cl

.3.17E+01 2.82E+01 t

2. h din _rs f

lodine-131 Ci lodine-133 Ci TOTAL Cl f

3. Particulates Manganese-54 Cl 1.04E-06 Cobatt40 Cl 3.38E-05 1.02E-05 Zinc 45 Cl 2.24E-05 2.95E-07 Ruthenium-103 Cl t

TOTAL Ci 5.72E-05 1.05E-05

4. Tritium f

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Hydrogen-3 Ci 3.60E-01 2.20E-.01 l

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Note: There were no batch releases for this report period.

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I NEW YORK POWER AUTHORITY l

JAMES A. FITZPATRICK NUCLEAR POWER PIJuNT EFFLUENT AND WASTE DISPOSAL l

SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 t

t TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES EST TOTAL ISTT OUARTER 3 QUARTER 4 ERROR %

A. FISSION AND ACTIVATION PRODUCTS i

1.

Total Release (not including j

tritium, gases and alpha)

Cl 1.85E-03 6.46E-04

$2.50E+01 l

2.

Average diluted concentra-l tion during period pCi/ml 3.17E-11 9.51E-12 l

3.

Applicable limit 5.76E-05 8.65E-06 f

I B. TRITIUM i

j 1.

Total Release Cl 1.25E+00 3.12E-01

$2.50E+01' 2.

Average diluted concentra-l tion during period pCi/ml 2.14E-08 4.59E-09 j

3.

Applicable limit 7.13E-04 1.53E-04 ii C. DISSOLVED AND ENTRAINED GASES i

$2.50E+01 j

1.

Total Release Ci 2.

Average diluted concentra-tion during period pCi/ml l

3.

Applicable Limit f

D. GROSS ALPHA RADIOACTIVI1Y 1.

Total Release Ci 1.69E-05 4.86E-06 52.50E+01 E. VOLUME OF WASTE RELEASED j

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(PRIOR TO DILUTION) liters 1.64E+06 4.'72E+05 F. VOLUME OF DILUTION WATER t

USED DURING PERIOD liters 5.83E+10 6.79E+10 G. PERCENT OF YECHNICAL' SPECIFICATION LIMITS 1.

Quarterly Whole Body Dose 9.20E-03 1.26E-03 i

2.

Quarterly Organ Dose 5.32E-03 6.84E-04 3.

Annual Whole Body Dose -

4.60E-03 6.30E-04

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4 Annual Organ Dose 2.66E-03 3.42E-04 l

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 L

TABLE 2B LIQUID EFFLUENTS i

BATCli MODE NUCLIDES RELEASED UNIT OUARTER 3 OUARTER 4

1. Fission and Activation Products Chromium-51 Cl 6.59E-06 Manganese-54 Ci 2.03E-04 8.91E-05 Cobatt@

Ci 7.88E-04 4.48E-04 Zine-65 Cl 7.4OE-04 9.82E-05 Niobium-97 Cl 5.6OE-05 Silver-110m Ci 1.59E-05 Antimony-125 Ci 3.75E-06 Cesium-134 Cl 7.96E-06 1.41E-06 Cesium-137 Cl 3.44E-05 3.05E-06 TOTAL Cl 1.85E-03 6.46E-04

2. Tritium Hydrogen-3 Cl 1.25E+00 3.12E-01
3. Dissolved and Entrained Gases TOTAL Cl Note: There were no continuous mode discharges during this report period.

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l NEW YORK POWER AUTHORITY i

JAMES A. FITZPATRICK NUCLEAR POWER PLANT i

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 TABLE 3 i

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-month Period Est Total Jlmi Class A Class B Class C Error %

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1. Tvne of Waste 3

a.' Spent resins, filter sludges, m

2.78E+01 N/A N/A evaporator bottoms, etc.

Ci 1.73E+02 N/A N/A 2.50E+01 3

b. Dry compressible waste, m

5.65E+01 N/A N/A contaminated equipment, etc.

Ci 2.10E+00 N/A N/A 2.50E+01 c.

Irradiated components, m

N/A N/A N/A l

3 control rods, etc.

Ci N/A N/A N/A l

d. Other (describe) m N/A N/A N/A 3

Ci N/A N/A N/A l

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2. Estimate of Maior Nuclide Composition (by tvue of waste)
a. Spent resins, filter sludges, evaporator bottoms, etc.

Isotope Percent Curies Isotope Percent Curies Zinc-65 3.24E+01 5.61E+01 Cesium-137 1.83E+00 3.17E+00

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Iron-55 3.15E+01 5.45E+01 Nickel-63 1.18E+00 2.04E+00 i

Cobalt-60 2.77E+01 4.79E+01 Cesium-134 9.48E-01 1.64E+00 Manganese-54 4.27E+00 7.39E+00 Nickel-59 1.19E-01 2.06E-01 j

b. Dry compressible waste, contaminated equipment, etc.

Isotope Percent Curies Isotope EcI. cent Curies Zinc-65 6.35E+01 1.33E+00 Cesium-137 2.36E+00 4.95E-02 Iron-55 1.43E+01 2.99E-01 Carbon-14 4.74E-01 9.97E-03 i

Cobalt-60 1.34E+01 2.82E-01 Nickel-63 1.37E-01 2.87E-03 Manganese-54 5.83E+00 1.23E-01

c. Irradiated components, control rods, etc.

None i

d. Other None Percentage of nuclides and total activities are based on a combination of direct measurements and scaling for non-gamma emitting nuclides.

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NEW YORK. POWER AUTIIORITY

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 TABLE 3 (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

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3.

Solid Waste Disposition i

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No. of Shioments Mode of Transportation Destination i

6 Truck Barnwell, SC j

0 N/A Richland, WA

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1 Rail

  • Alaron Corp.

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Wampum, PA j

11 Truck

  • Scientific Ecology Group.

Oak Ridge, TN

  • Waste Reduction Facility B. IRRADIATED FUEL SHIPMENTS (Disposition) v No. of Shioments Mode of Transoortation Destination None N/A N/A e

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NEW YORK POWER AUTHORITY JAhfES A. FITZPATRICK NUCLEAR POWER PIANT i

EFFLUENT AND WASTE DISPOSAL 1

SEhil-ANNUAL REPORT JULY 1992 - DECEhiBER.1992 ATTACH 51ENT NO.1 CHANGES TO THE OFFSITE DOSE CALCULATION h1ANUAL (ODChi) i In accordance with Section 7.3.C.3 of Amendment 93 to the James A. FitzPatrick Nuclear Power Plant Technical Specifications, changes made to the Offsite Dose Calculation hianual (ODChi) during the reporting period shall be included in the Semi-Annual Radioactive Effluent Release Report.

No changes were made to the ODChi this report period.

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NEW YORK POWER AUTHORITY

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 ATTACHMENT NO. 2

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM In accordance with Section 7.3.C3 of Amendment 93 to the James A. FitzPatrick Nuclear Power Plant Technical Specifications, changes made to the Process Control Program (PCP) during the reporting period shall be included in the Semi-Annual Radioactive Effluent Release Report.

~ Revision 9 to the Process Control Program (PCP) procedure AP-1.10 was approved for use on November 5,1992 (PORC Meeting No.92-148). This revision was made to delete Section 7.4.1.a describing manual calculations for 10CFR61 classification to backup the computer program. This section was added in 1984 when there was only one computer available for these calculations. Backup capability and the availability of numerous computers onsite made this section of the procedure unnecessary. This change did not reduce the conformance to existing criteria for solid waste.

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NEW YORK POWER AUTHORITY JAMES A. FIT 2 PATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 ATTACHMENT NO. 3

SUMMARY

OF CHANGES TO THE ENVIRONMENTAL MONITORING AND DOSE CALCULATION LOCATIONS In accordance with Section 7.3.C.3 of Amendment 93 to the James A. FitzPatrick Nuclear Power Plant Technical Specifications, a listing of new locations for dose calculation and/or environmental monitoring identified by the land use census shall be included in the Semi-Annual Radioactive Effluent Release Report.

CHANGES IN ENVIRONMENTAL MONITORING LOCATIONS 1.

No changes in the Environmental Monitoring Locations required by Technical Specificatious were made based on the land use census.

2.

The Jones farm was deleted from the milk sampling program with the last sample collected on July 20,1992. The milk herd was sold by the farmer and samples are no longer available. This sample locatiorgas not required by Technical Specifications but was sampled as a long term, historical milk location. The farm was designated as location No.16 in the past radiological Emironmental Surveillance reports and was geographically located 5.9 miles from the site at 190 NEW LOCATIONS FOR DOSE CALCULATIONS 1.

No changes in Dose Calculation Receptor Locations were required based on land use census.

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NEW YORK POWER AUTHORITY l

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 i

ATI ACHMENT NO. 4 i

DEVIATIONS FROM THE REQUIRED 7

ENVIRONMENTAL SAMPLING SCHEDULE In accordance with Section 7.3.C.7 of Amendment 93 to the James A. FitzPatrick Nuclear Power Plant Technical Specifications, the cause for unavailability of any emironmental samples required during the report period shall be included in the Semi-Annual Radioactive Effluent Release Report.

EXCEPTTON TO THE ENVIRONMENTAL SAMPLING PROGRAM 1)

Surface Water Samole. Monthly Comoosite (RETS, Table 6.1-1)

The Composite sampler used to collect the surface water offsite control sample was found to be inoperative for a period of seven days due to an electrical failure. The period of pump inoperability was from July 10,1992 (1105 hrs.) to July 17,1992 (1049 hrs.) The deviatian from the normal sample period of 31 days had no significance on the validity of the sample. This sample serves as a control station which is located upstream from the site and is used to measure background. As a corrective action, the 3 ample pump is now checked twice per week by the technician staff to provide for earlier detection of equipment failures.

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1 NEW YORK POWER AUTHORITY

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT -

EFFLUENT' AND WASTE DISPOSAL

. SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 A'ITACHMENT NO. 5 SEMI-ANNUAL

SUMMARY

OF HOURLY METEOROLOGICAL DATA In accordance with Section 7.3.C.2 of Amendment 93 to the James A. FitzPatrick Nuclear Power Plant Technical Specifications, an annual summary of meteorological data may be included and submitted in the Semi-Annual Radioactive Efauent Release Report within 60 days after January 1 of each year.

Meteorological data for the period of January 1,1992 through December 31,1992 is not included in this report. It is on file and available upon request.

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 ADDENDUMi ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 1992 1.

INTRODUCTION The James A. FitzPatrick Nuclear Power Plant Radiological Effluent l

Technical Specifications (RETS) require 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 1

A.

DOSE FROM LIOUID EFFLUENTS (RETS 2.3)

Acolicability Applies to doses from radioactive materialin liquid effluents.

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

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

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

B.

GASEOUS DOSE RATES (RETS 3.2)

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

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL i

SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 i

ADDENDUM 1 (cor;tinued)

Obiective 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.

i Specifications ne dose rate at or beyond the site boundary due to radioactive materials released from the plant in gaseous effluents shall be limited as follows:

1. Less than or equal to 500 mrem / year to the whole body and less than or equal to 3000 mrem / year to the skin from noble gases; and,
2. I2ss than or equal to 1500 mrem / year to any organ from Iodine-131, Iodine-133, Tritium and for radioactive materials in particulate form with half-lives greater than 8 days (inhalation pathway only).

C.

AIR DOSE. NOBLE GASES (RETS 3.3)

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

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

Soecifications 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 1 is than or equal to 5 mrad from gamma radiation, and less tha, r equal to 10 mrad from beta t

radiation; and, i

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

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NEW YORK POWER' AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE ~ DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992

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ADDENDUM 1 (continued) j D.

DOSE DUE TO IODINE-131. IODINE-133. TRITIUM AND

' l RADIONUCLIDES IN PARTICULATE FORM (REE 3.4)

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I An..olicability

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Applies to the cumulative dose from Iodine-131, Iodine-133, Tritium, and radionuclides in particulate form with half-lives greater than 8 days in-i gaseous effluents.

Obiective

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

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Soecifications j

The dose to a member of the public at or beyond the site boundary from-

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Iodine-131, Iodine-133, Tritium, and radionuclides in particulate form l

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, i
2. During any calendar year to less than or equal to 15 mrem to any l

a organ.

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E.

TOTAL DOSE FROM URANIUM FUEL CYCLE (RETS 5.1)

Applicability Applies to radiation dose from releases of radioactivity and radiation l

from uranium fuel cycle sources.

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

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR. POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1992 - DECEMBER 1992 ADDENDUM 1 (continued)

Specifications The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited as follows:

1. Iess than or equal to 25 mrem / year to the whole body; and, 2.12ss than or equal to 25 mrem / year to any organ except the thyroid which shall be limited to less than or equal to 75 mrem / year.

3.

DOSE ASSESSMENT A.

METHODOLOGY The assessment of radiation doses to the public due to radioactive liquid and gaseous effluents is performed in accordance with the ODCM. The ODCM is based on methodologies and models suggested by the

" Guidance Manual For Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREG-0133) and

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the purpose of Evaluating Compliance with 10CFR50, t

Appendix I" (Regulatory Guide 1.109).

B.

ASSUMPTIONS Dose calculations are performed using formulas and constants defined in the ODCM. Specific radioactive release activities used in the dose calculations are listed in the Semi-Annual Radioactive Effluent Release Reports (1.21 Reports) for the period of January 1,1992 to December 31,1992. Historical meteorological data was used to generate tables of average dispersion factors. Locations of interest were identified from the 1992 land use census. Dispersion factors and locations of interest used in performing the dose calculations are listed in Table 2.

C.

ASSESSMENT RESULTS

SUMMARY

The calculated doses to the public due to radioactive effluents are listed in Table 1. The calculated doses are small fractions of their respective dose limits.

20 I

I

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PIANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 ADDENDUM 1 (continued) 4.

40 CFR 190 DOSE ASSESSMENT A.

METHODOLOGY Evaluation to demonstrate compliance with the 40 CFR 190 dose limits must be performed when the doses calculated for 10 CFR 50 compliance exceed twice their respective limits. When additional dose assessment is required to demonstrate compliance with 40 CFR 190 it is performed in accordance with the ODCM.

-t B.

RESULTS

SUMMARY

The cumulative dose contribution ftam liquid and gaseous effluents for i

this report period were calculated and are listed in Table 1. The l

calculated doses are less than twice their respective 10 CFR 50 limits, i

I therefore, additional calculations are not necessary to demonstrate compliance with 40 CFR 190 dose limits (RETS 5.1.6).

i f

b t

1 t

I 21

NEW. YORK POWER ' AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 1992 A. LIQUIDS OUARTER l

2 2

1 ANNUAL (a)

(b)

-(b)

(b)

(b)

Organ (mrem) 137E-04 333E-M 2.66E-04 3.42E-05 7.22E-04

% of Limit 2.74E-03 6.66E-03 5.32E-03 6.84E-04 7.22E-03 (c)

(d)

(d)

(c)

(d)

Whole Body (mrem) 8.70E-05 2.14E-04 138E-04 1.89E-05 3.98E-M

% of Limit 5.80E-03 1.43E-02 9.20E-03 1.26E-03 133E-02 (a) Dose to the Teen GI-LLI primarily by the fish pathway.

(b) Dose to the Teen Liver primarily by the fish pathway.

(c) Dose to the Teen Whole Body primarily by the fish pathway.

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

B. NOBLE GASES OUARTER 1

2 3

4 ANNUAL Total Body (mrem /yr) 2.60E-02 1.84E-02 2.06E-03 1.47E-02 2.60E-02

% of Limit 5.20E-03 3.68E-03 4.12E-M 2.94E-03 5.20E-03 Skin (mrem /yr) 4.67E-02 331E-02 9.93E-03 2.47E-02 4.67E-02

% of Limit 1.57E-03 7.10E-03 331E-04 8.23E-04 1.57E-03 Gamma (mrad) 2.54E-03 6.91E-04 2.05E-04 6.76E-04 4.11E-03

% of Limit

.5.08E-02 138E-02 4.10E-03 135E-02 4.11E-02 Beta (mrad) 2.56E-03 1.22E-03 7.72E-04 8.13E-M 537E-03

% of Limit 2.56E-02 1.22E-02 7.72E-03 8.13E-03 2.69E-02 22

NEW YORK POWER AlJIIIORITY k

JAMES A. FITZPATRICK-NUCLEAR POWER PIANT EFFLUENT - AND. WASTE DISPOSAL f

SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992.

i ADDENDUM 1 (continued) i

' TABLE 1-ANNUAL DOSE ASSESSMENT 1992 i

C. IODINES AND PARTICULATES

-l t

OUARTER 1

2 3

1 ANNUAL i

(a)

(b)

(c)

(d)

(a)

{

Organ (mrem) 2.45E-03 2.78E-M 1.77E-N 5.46E-05 2.83E-03

% of Limit 3.27E-02 3.71E-03 2.36E-03 7.28E-M 1.89E-02 l

t Organ Dose Rate 3.99E400 3.77E-02 1.99E-02 9.47E-04 3.99E+00 j

(mrem /yr)

j Tc of Limit 2.26E-01 2.51E-03 7.96E-04 631E-05 2.26E-01 l

~.l I

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

(b) Dose to the Child Liver primarily by the ground plane deposition pathway.

l (c) Dose to the Teen GI-LLI primarily by the ground plane deposition pathway.

j (d) Dose to the Child GI-LLI primarily by the ground planc deposition pathway.

y l

.i i

I i

)

1 i

a I

.?

NEW YORK' POWER-AUTHORITY I

JAMES A. FITZPATRICK NUCLEAR POWER PLANT l

EFFLUENT AND WASTE DISPOSAL j

SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992

]

ADDENDUM 1 (continued) j TABLE 2 METEOROLOGICAL DATA AND LOCATIONS OF INTEREST i

GEOGRAPHIC ATMOSPHERIC j

RECEPTOR LOCATION DISPERSION FACTOR

)

A.

IODINE &

DISTANCE /

RELEASE

.X/Q D/O 2

PARTICULATES DIRECTION POINT (sec/m')

(1/m )

j i

1.

Garden 0.9 mi @ 82*E ST 1.62E-09 I

Grazing Season 0.9 mi @ 82*E RX 5.18E-09 Cary 0.9 mi @ 82 E TB 4.74E-09 i

Location No. 78 0.9 mi @ 82*E RF 5.18E-09 i

0.9 mi @ 82*E RW 6.10E-09 l

2.

Meat 1.2 mi @ 126*SE ST 839E-10 Grazing Season 1.2 mi @ 126*SE RX 1.72E-09 f

Parkhurst 1.2 mi @ 126*SE -

TB 1.61E-09 I.ocation No. 26 1.2 mi @ 126*SE RF 1.72E-09 j

1.2 mi @ 126*SE RW 2.01E-09 3.

Cow 2.2 mi @ 138 SE ST 3.87E-10 I

Grazing Season 2.2 mi @ 138*SE RX 6.57E-10 France 2.2 mi @ 138*SE TB 630E-10 location No.10 2.2 mi @ 138*SE RF 6.57E t 2.2 mi @ 138*SE RW 7.23E-10 1

4.

Goat 2.5 mi @ 146*SE ST 3.30E-10 Grazing Season 2.5 mi @ 146 SE RX 533E-10 i

Nickolas 2.5 mi @ 146 SE TB 5.13E-10 1

I.ocation No. 61 2.5 mi @ 146*SE RF 533E-10 2.5 mi @ 146*SE RW 5.80E-10 l

5.

Resident Annual Average

a. Inhalation 1.9 mi @ 90 E ST 3.16E-08 l

0.9 mi @ 82*E RX 2.81E-07 0.9 mi @ 82*E TB 2.41E-07 l

0.9 mi @ 82*E RF 2.81E -

0.9 mi @ 82*E RW 438E-07

]

24

)

T' NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT

~

EFFLUENT AND WASTE-DISPOSAL SEMI-ANNUAL REPORT JULY 1992 - DECEMBER 1992 ADDENDUM 1 (continued)

.l l

TABLE 2 METEOROLOGICAL DATA AND_ LOCATIONS OF INTEREST j

GEOGRAPHIC ATMOSPHERIC l

RECEPTOR LOCATION DISPERSION FACTOR l

A.

IODINE &

DISTANCE /

RELEASE X/O D/O PARTICULATES DIRECTION POINT (sec/m')

(1/m) 2 1.63E-09 5 b. Deposition 0.9 mi @ 82*E ST 0.7 mi @ 118'ESE RX 5.99E-09 0.7 mi @ 118'ESE.

TB 5.45E-09 0.7 mi @ 118*ESE RF 5.99E-09 i

0.7 mi @ 118 ESE RW 7.06E-09 B. NOBLE GASES

1. Air Dose 1.9 mi @' 90 E ST 3.16E-08 Annual Average 0.6 mi @ 90*E ST(fc) 1.44E-07 O.6 mi @ 90*E RX 4.83E-07 l

0.6 mi @ 90 E TB 3.96E-07 0.6 mi @ 90 E RF 4.83E-07 0.6 mi @ 90*E RW 7.47E-07 3

Annual Average 0.6 mi @ 90'E RX 4.83E-07

2. Total Body 0.6 mi @ 90*E

.ST(fc) 1.44E-07 O.6 mi @ 90 E TB 3.96E-07 0.6 mi @ 90'E RF 4.83E-07 t

0.6 mi @ 90*E RW 7.47E-07 l

3. Skin 1.9 mi @ 90*E ST 3.16E-08 Annual Average 0.6 mi @ 90"E ST(fc) 1.44E-07 0.6 mi @ 90*E RX 4.83E-07 0.6 mi @ 90 E TB 3.96E-07.

O.6 mi @ 90*E RF 4.83E-07 0.6 mi @ 90*E RW 7.47E-07 ST = Main Stack RX = Reactor Buildmg TB = Turbine Building Vent i

RF = Refuel Floor Vent RW = Radwaste Vent i

fc = Finite Cloud l

i 25

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