Text

Semi-Annual Radioactive Effluent Release Rept for Period of 980701-1231
	ML20207E216
Person / Time
Site:	FitzPatrick
Issue date:	12/31/1998
From:	; POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	;
Shared Package
ML20207E214	List: JAFP-99-0071, Forwards Semi-Annual Radioactive Effluent Release Rept for Period of 980701-1231. Format Used for Effluent Data Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 4; ML20207E216;
References
	NUDOCS 9903100193
	Download: ML20207E216 (30)
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i NEW YORK POWER AUTilORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL '

SEMI-ANNUAL REPORT !

JULY 1,1998 - DECEMBER 31,1998 I

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DOCKET NO.: 50-333 I LICENSE NO.: DPR-59 l 1

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9903100193 990225' i- PDR ADOCK 05000333

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NEW YORK POWER AUTliORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ,

EFFLUENT AND WASTE DISPOSAL !

SEMI-ANNUAL REPORT JULY 1998 -DECEMBER 1998 i SUPPLEMENTAL INFORMATION !

J FACILITY: JAFNPP LICENSEE: NEW YORK POWER AUTIlORIIY l

1. Technical Specification Limits

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: j.

(a) Ler.s 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 i plant in gaseous effluent shall be limited:

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

b. Tritium, lodines and Particulates, Half Lives > 8 days: i i'

(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, ,

r (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 lodine-131, lodine-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 AUTIIORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998 - DECEMBER 1998 SUPPLEMENTAL INFORMATION (Continued)

c. Liquid Effluents:

l (1) The concentration of radioactive materials released to the unrestricted areas shall 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-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:

i (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 NONE 5.91 E-05 products (mixture MPC)

(pCi/ml)

(2) Tritium (pCi/ml) 3.00E-03 3.00E-03 l (3) Dissolved and entrained gases (pCi/ml) 2.00E-04 2.00E-04 Page 2 of 29

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NEW YORK POWER AUT110RITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 SUPPLEMENTAL INFORMATION (Continued)

3. Average _ Energy (None specified)

4. Measurements and Approximations of Total Radioactivity

a. Fission and Activation Gases: Continuous monitor on each release path calibrated to a ,

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marinelli grab sample analyzed by gamma spectroscopy; bubbler grab sample analyzed for Tritium.

b. lodines: Gamma spectral analysis of charcoal cartridge and paniculate 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 paniculate filter for each I release path for gross alpha. !

d. Liquid EfIluents: Gamma spectral analysis of each batch discharged, except composite analysis for Strontium-89, Strontium-90, Iron-55, Tritium, and Alpha. l 1

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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. ,

i Determinate - Pump flowrates, volume measurements and analysis collection yields Undeterminate - Random counting error estimated using accepted statistical calculations I

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NEW YORK POWER AU1110RITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998 - DECEMBER 1998 SUPPLEMENTAL INFORMATION (Continued) 1

5. Datch Reicases

a. Liquid: Ouarter 3 Ouarter 4 (1) Number of batch releases: NONE 1.00E+01 (2) Total time period for batch NONE 9.52E+02 release:(min)

(3) Maximum time period for NONE 3.44E+02 batch release: (min)

(4) Average time period for NONE 9.52E+01 ,

batch release:(min)

(5) Minimum time period for NONE 6.20E+01 batch release:(min)

b. Gaseous: NONE NONE There were no gaseous batch releases for this report period.

6. Abnormal Releases

a. Liquid: Quarter 3 Ouarter 4 (1) Number ofreleases: NONE NONE l (2) Total activity released: NONE NONE

b. Gaseous (1) Number ofreleases: NONE NONE (2) Total activity released: NONE NONE Page 4 of 29

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT !

EFFLUENT AND WASTE DISPOSAL l SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 l

TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES EST TOTAL UNIT OUARTER 3 OUARTER 4 ERROR %

) A. FISSION AND ACTIVATION GASES I 1. Total Release Ci 7.84E+00 1.47E+01 #2.50E+01

< 2. Average release rate for l period pCi/sec 9.86E-01 1.85E+00 i

3. Tech. Spec. Limit H. IODINE-131

1. Totallodine-131 Ci 1.14E-04 1.40E-03 #2.50E+01 2.' Average release rate for period Ci/sec 1.43E-05 1.76E-04

3. Tech. Spec. Limit %

C. PARTICULATES

1. Particulates with half-lives

>8 days Ci 3.68E-05 2.52E-04 #3.60E+01

2. Average release rate for period Ci/sec 4.63E-06 3.17E-05 Tech. Spec. Limit % * *

3. ',

4. Gross alpha radioactivity Ci 7.37E-07 3.22E-07 #2.50E+01 D. TRITIUM l

1. Total Release Ci 2.62E401 1.26E+01 #2.50E+01

2. Average release rate for j period Ci/sec 3.30E+00 1.59E+00 J

3. Tech. Spec. Limit % j

E. PERCENT OF TECIINICAL SPECIFICATION LIMITS FISSION AND ACTIVATION GASES

1. Quarterly gamma air dose limit % 4.00E-03 7.22E-03

2. Quarterly beta air dose limit % 3.44E-04 6.87E-04

3. Yearly gamma air dose limit % 2.00E-03 3.61E-03

4. Yearly beta air dose limit % 1.72E-04 3.44E-04

5. Whole body dose rate limit % 1.76E-03 2.32E-03

6. Skin dose rate limit % 3.82E-04 5.09E-04 IIALOGENS, TRITIUM AND PARTICULATES WITH IIALF. LIVES >8 DAYS 7; Quarterly dose limit (organ) % 2.46E-02 2.56E-01

8. Yearly dose limit (organ) % 1.23E-02 1.28E-01

9. Organ dose rate limit % 5.22E-05 3.30E-04 Page 5 of 29

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 i

. - TABLE IB GASEOUS EFFLUENTS--ELEVATED RELEASE CONTINUOUS MODE !

NUCLIDES RELEASED UNIT OUARTER3 OUARTER4

1. Fission Gases Argon-41 Ci 2.37E+00 1.14E+00 Krypton-85m Ci 3.76E-01 6.26E-01 i Krypton-87 Cl 1.14E+00 3.72E+00 Krypton-88 Ci 8.95E-01 2.52E+00 Xenon-133 Ci 3.38E-02 - - - - - - - -

Xenon-135 Ci 1.56E+00 4.18E+00 ;

Xenon-135m Ci 2.24E-01 6.SSE-01 Xenon-137 Ci 4.68E-01 2.58E-01 Xenon-138 Ci 7.66E-01 1.61E+00 '

TOTAL Ci 7.84E+00 1.47E+01

2. Iodines lodine-131 Cl 1.01E-04 9.80E-04 lodine-133 Ci 4.40E-05 1.13E-02 lodine-135 Ci 3.89E-05 1.37E-02 TOTAL Cl 1.84E-04 2.60E-02

3. Particulates l

Manganese-54 Ci 9.36E-07 1.69E-05 tron Ci 3.94E-07 7.38E-06 Cobalt-58 Ci -------- 5.91E-07 Cobalt-60 Ci 1.86E-07 5.92E-07 j Strontium-90 Ci -------- 1.17E-07 Cesium-137 Ci --------

1.77E-06 Barium / Lanthanum-140 Ci 5.2OE-07 1.10E-06 TOTAL Ci 2.04E-06 2.74E-05

4. Tritium Hydrogen-3 Ci 2.91E+00 1.73E+00 ;

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 SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 TABLE IC GASEOUS EFFLUENTS--GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED UNIT OUARTER 3 QUARTER 4

1. Fission Gases None Ci -------- --------

TOTAL Ci -------- --------

1 Lod.ints lodino-131 Cl 1.30E-05 4.16E-04 lodine-133 Ci 2.78E-04 1.63E-04 TOTAL Ci 2.91E-04 5.79E-04

3. Particulates Chromium-51 Ci --------

9.54E-06 Manganse-54 Ci 8.94E-07 5.50E-05 Cobalt-58 Cl --------

3.68E-06

- Cobalt-60 Cl 1.86E-05 1.40E-04 l Zinc-65 ' Cl --------

3.59E-06 l Strontium-89 Ci 1.53E-05 - - - - - - - -

I Ceslum-137 Ci --------

1.29E-05 TOTAL Ci 3.48E-05 2.25E-04

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4. Tritium Hydrogen-3 Ci 2.33E+01 1.09E+01 i

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 SEMI-ANNUAL REPORT JULY 1998 DECEMBER 1998 TABLE 1 - SUPPLEMENTAL GASEOUS EFFLUENTS--UNMONITORED SHORT-TERM RELEASE -

NUCLIDES REtEAS0]I) UNIT OUARTER3 OUARTER 4

1. Fission Gases None Ci -------- --------

TOTAL Ci -------- --------

2. Losines None Ci -------- --------

TOTAL Ci -------- --------

3. Particulates Cobalt-60 Cl --------

2.33E-07 Cesium-137 Cl --------

3.11E-07 TOTAL Ci --------

5.44E-07 ;

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4. Tritium

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i None Ci -------- --------

Note: See attachment 7. ,

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NEW YORK POWER AUTHORITY f

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL IGPORT JULY 1998-DELEMBER 1998

, . TABLE 2A l LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES EST TOTAL i

UNIT OUARTER 3 OUARTER 4 ERROR %

A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not including tritium, gases and alpha) Ci NONE 6.22E-05 52.50E+01 )

2. Average diluted concentra- ,

tion during period PCi/ml NONE 7.79E-13

3. Applicable limit % -----

I B. TRITIUM

1. Total Release Ci NONE 9.96E+00 #2.50E+01 i

2. Average diluted concentra-tion during period NONE 1.25E-07 Applicable limit PCi/ml )

3. % -----

I C. DISSOLVED AND ENTRAINED GASES J

1. Total Release Cl NONE 1.42E-05 #2.50E+01

2. Average diluted concentra- l tion during period PCi/ml NONE 1.78E-13

3. Applicable Limit % -----

D. GROSS ALPHA RADIOACTIVITY

1. Total Release Ci NONE -----

4.20E+01 l E. VOLUME OP WASTE RELEASED (PRIOR TO DILUTION) liters NONE 4.53E+05 i

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F. VOLUME OF DILUTION WATER

USED DURING PERIOD liters NONE 7.99E+10 I

'G. PERCENT OF TECHNICAL SPECIFICATION LIMITS l ,

1. Quarterly Whole Body Dose % -----

1.67E-03

2. Quarterly Organ Dose % -----

5.28E-04

3. AnnualWhole Body Dose % -----

8.37E-04

4. Annual Organ Dose % -----

2.64E-04 Page 9 of 29 i

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NEW YORK POWER AUTHORITY l ll ' JAMES A. FITZPATRICK NUCLEAR POWER PLANT l ll EFFLUENT AND WASTE DISfOSAL 1

SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 TABLE 2B LIQUID EFFLUENTS l'

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l BATCH MODE NUCLIDES RELEASED UNIT - OUARTER 3 OUARTER 4

1. Fission and Activation Products Manganese-54 Ci NONE 1.73E-05 Cobalt-60 ' Cl NONE 2.08E-05

- Zine-65 Ci NONE 2.41E-05 TOTAL Cl NONE 6.22E-05

2. Tritium Hydrogen-3 Ci NONE < 96E+00 f l TOTAL Ci NONE 9.FGE+00 i

3. Dissolved and Entrained Cases 4

Xenon 135 Ci NaNE 1.42E-05 I

TOTAL Ci NONE 1.42E-05 1 i

Note: There were no continuous mode discharges during this report period.

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 TABLE 3A SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SIIIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-month Period Est Total Unit Class A Class B Class C Error %

1. TVDC Of Wa$ti

a. Spent resins, filter sludges, m3 0.00E+00 0.00E+00 0.00E+00 N/A evaporator bottoms, etc. Ci 0.00E+00 0.00E+00 0.00D+00 N/A

b. Dry compressible waste, m3 0.00E+00 0.00E+00 0.00E+00 N/A contaminated equipment, etc. Ci 0.00E+00 0.00E+00 0.00E+00 N/A

e. Irradiated components, m3 0.00E+00 0.00E+00 0.00E+00 N/A control rods, etc. Ci 0.00E+00 0.00E+00 0.00E+00 N/A

d. Other: Dry Compressible Waste, m3 3.29E+02 0.00E+00 0.00E+00 1.00E+01 l contaminated equip., ect. for Ci 4.92E-01 0.00E+00 0.00E+00 1.00E+01 !

Volume reduction

2. _ Estimate of Ma_ior Nuclide Composition (by type of waste)

a. Spent resins, filter sludges, evaporator bottoms, etc.

None l

b. Dry compressible waste, contaminated equip, etc. ,

None l

c. Irradiated components, control rods, etc.

None

d. Other: Dry compressible waste, contaminated equip, ect. for Volume Reduction.

Isotope Percent Curies Isotone Percent Curies ;

Iron-55 4.59E+01 2.26E-01 E Cesium-137 5.98E+00 2.94E-02 E Cobalt-60 2.97E+01 1.46E-01 E Nickel-63 1.28E+00 6.43E-03 E Zinc-65 8.71E+00 4.29E-02 E Strontium-90 3.52E-02 1.73E-04 E Manganese-54 8.34E+00 4.11E-02 E Hydrogen-3 7.50E-03 3.70E-05 E 1

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. . NEW YORK POWER AttrHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT a

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 !

TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SIIIPMENTS l

3. Solid Waste Disposition No. of Shipments Mode of Transportation Destination 6 Truck *GTS Duratek/S.E.G. !

Oak Ridge, TN {

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Volume Reduction Facility l l

B. IRRADIATED FUEL SHIPMENTS (Disposition) i i

No. of Shioments Mode of Transportation Destination !

None _____ _____ l

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NEW YORK POWER AUTHORITY JAMES A.. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 TABLE 3B SOLID WASTE AND IRRADIATED FUEL SIIIPMENTS ;

A.NRC CLASS A SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Dry Compressible Non-Compacted 1040 ft' STC 10 Waste (DAW),

Contaminated Equipment, etc.

Dry Compressible Non-Compacted 2080 ft' STC 1 Waste (DAW),

Contaminated Equipment, etc.

B.NRC CLASS B SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS None ----- ----- ----- -----

C.NRC CLASS C SOURCE OF PROCESSING O.4TAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS None ----- ----- ----- -----

Solidification Acent: None i i

HIC - High Integrity Container STC - Strong Tight Container Page 13 of 29

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NEW YORK POWER AUTHORITY l JAMES A. FITZPATRICK NUCLEAR POWER PLANT l EFFLUENT AND WASTE DISPOSAL l SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 l ATTACHMENT NO.1 i

l CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM) I l

j 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 Manual l

(ODCM) during the reponing period shall be i,cluded in the Semi-Annual Radioactive j Ellluent Release Report.

There were no changes to the OfTsite Dose Calculation Manual (ODCM) this report period.

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NEW YORK POWER AUTHORITY ;

JAMES A. FITZPATRICK NUCLEAR POWER PLANT l EFFLUENT AND WASTE DISPOSAL j SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 ATTACHMENT NO.2

SUMMARY

OF CH ANGES TO THE PROCESS CONTROL PROGRAM 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 Process Control Program (PCP) during the reponing period shall be included in the Semi-Annual Radioactive Effluent Release Report.

There were no changes to the Process Control Program Procedure or implementing procedures ,

this report period. ;

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NEW YORK POWER AUTHORITY i l JAMES A. FITZPATRICK NUCLEAR POWER PLANT '

l EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 ATTACHMENT NO.3 l

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SUMMARY

OF CHANGES TO THE ENVIRONMENTAL MONITORING AND ,

l, 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. l lt l CHANGES IN ENVIRONMENTAL MONITORING LOCATIONS During the report period, no changes in the Environmental Monitoring Locations sampled to implement the requirements ofTechnical Specifications were made. Sample location selections !

. are based on the annual land use census and sample locations listed in the ODCM. !

l l Garden vegetation / food products were cellected from location #52 (ODCM, Table H-1) for the 1998 program. This location was unavailable for sampling in 1997. Location #52 is a routine sample location and is listed in the ODCM. No corrective actions were implemented as garden availability is dependent on owner cooperation and environmental conditions.

l NEW LOCATIONS FOR DOSE CALCULATIONS ;

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

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NEW YORK POWER AUTHORITY

! JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL IEPORT JULY 1998-DECEMBER 1998 i

ATTACHMENT NO.4 DEVIATIONS FROM THE REQUIRED l ENVIRONMENTAL SAMPLING SCHEDULE l

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 environmental samples required during the

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report period shall be included in the Semi-Annual Radioactive Efiluent Release Report.

EXCEPTIONS TO THE ENVIRONMENTAL SAMPLING PROGRAM Direct Radiation Measurements Thermoluminescent Dosimeter (TLD) No. 76 was found missing during the fourth quarter 1998 change-out. TLD No. 76 is located on the north security fence at Nine Mile Unit 2 (25 @ 0.1 miles). The TLD was replaced. No other corrective action was implemented.

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i' NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLAN'l EFFLUENT AND WASTE DISPOSAI.

SEMI-ANNUAL REPORT JULY 1998-DECE 4ER 1998 .

ATTACHMENT NO.5 l

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SEMI-ANNUAL

SUMMARY

OF HOUPLY METEOROLOGICAL DATA li The James A. FitzPatrick Nuclear Power Plant Radiological Environmental Technical 7

' Specification 7.3.c.2 states in part: "The Radioactive Effluent Release Report to be submitted ,

within 60 days after January 1 of each year may include an annual summary of meteorological l, 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."

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^ 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.

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 ATTACIIMENT NO.6 REPORT NOTES Table 2A Section A and B and Table 2B Normal Liauid Effluents The values for Tritum, Strontium-90, and Iron-55 were calculated from the most recent available san 11e data. If the actual sample data significatly alters the percent of allowable release limit's, the report will be revised and redistributed.

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 ATTACIIMENT NO.7 GASEOUS EFFLUENTS - UNMONITORED SIIORT-TERM RELEASE 4

a) Date: November 14,1998 b) ~ Location: Unmonitored Release from the Standby Gas Treatment Piping i

c) Duration: 1.20E+01 Hours d) Flowrate: 3.00E+02 cfm e) Volume Released: 2.16E+05 Ft' f) Nuclides Released: See Table 1 -Supplemental Gaseous Effluents - Unmonitored Short-Term Release g) Resultant Doses: See Addendum 1 - Assessment of Radiation Doses to the Public January-December 1998 Table 1.D h) Dose Calculations: Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Section 4.4.3 Short Term Releases l

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NEW YORK POWER AUTIIORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 ADDENDUM 1 ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 1998 l

1. INTRODUCTION

,! The James A. FitzPatrick Nuclear Power Plant Radiological Effluent Technical I- 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 A. DOSE FROM LIOUID EFFLUENTS (RETS 2.3)

Applicability Applies to doses from radioactive material in liquid effluents.

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

, The dose to a member of the public from radioactive materials released from the plant in liquid effluents to unrestricted areas shall be limited ;

as follows: i

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.

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

B. GASEOUS DOSE RATES (RETS 3.2) ;

! Applicability 1

Applies to the radiation dose from radioactive material in gaseous ellluents. l ll l l~

Page 21 of 29 1

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NEW YORK POWER' AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 ADDENDUM 1 - (continued) ;

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 i areas.

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

1. Less than or equal to 500 mrem / year to the whole body and less than or equal to 3000 mrem / year to the skin from noble gases; and, !

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

C. AIR DOSE. NOBLE GASES (RETS 3.3) i Anolicability 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.

L Specifications The air dose to areas at or beyon.! 'm site boundary from noble gases .

released from the plant in gaseous etnuents shall be limited: !

1. During any calendar quaner, to less than or equal to 5 mrad from gamma radiation, and less than or equal to 10 mrad from beta radiation; and,

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

) radiation and less than or equal to 20 mrad from beta radiation.

Page 22 of 29

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nw.~ ,_ , ._. . . _ . - _ _ _ __ - - . - . . . . _ _ . _

t NEW YORK POWER AUTHORITY L

JAMES A. FITZPATRICK NUCLEAR POWER PLANT l- EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 l

ADDENDUM 1 (continued)

D. DOSE DUE TO IODINE-131'. IODINE-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM (RETS 3.4) l Applicability Applies to the cumulative dose from Iodine-131, Iodine-133, Tritium, and radionuclides in particulate form with half-lives greater than 8 days in gascous effluents.

Obiective

To ensure that the dose limitations of 10 CFR 50, Appendix 1, are met.

- Specifications The dose to a member of the public at or beyond the site boundary from Iodine-131, Iodine-133, Tritium, and radionuclides in particulate form with

, half-lives greater than 8 days released from the plant in gaseous effluents shall be limited:

I

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.

l E. ' TOTAL DOSE FROM URANIUM FUEL CYCLE (RETS 5.1) !

Aeolicability-Applies to radiation dose from releases of radioactivity and radiation from uranium fuel cycle sources. j Obiective To ensure that the requirements of 40 CFR 190 are met.

i l'

L Page 23 of 29

g _ . . . _ _ _ , _ _ _ . _. ... _ _ . _ _ . _ . .

, NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l EFFLUENT AND WASTE DISPOSAL !

, . SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 l h*

ADDENDUM 1 ' (continued) 5 l i 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: )

I

1. ' Less than or equal to 25 mrem / year to the whole body; and, l

t

>- 2. Less than or equal to 25 mrem / year to any organ except the thyroid l which shall be limited to less than or equal to 75 mrem / year. !

3. DOSE ASSESSMENT j!

A. METHODOLOGY ;

The assessment of radiation doses to the public due to radioactive liquid and !

gaseous emuents is performed in accordance with the ODCM. The ODCM f is based on methodologies and models suggested by the " Guidance Manual l

For Preparation of Radiological Effluent Technical Specifications for l Nuclear Power Plants" (NUREG-0133) and " Calculation of Annual Doses

, to Man from Routine Releases of Reactor Emuents for the purpose of l l Evaluating Compliance with 10CFR50, Appendix I" (Regulatory Guide l' 1.109).

4 B. ASSUMPTIONS

Dose calculations are performed using formulas and constants defined in the 1 ODCM. Specific radioactive release activities used in the dose calculations are listed in the Semi-Annual Radioactive Efiluent Release Reports (1.21 Reports) for the period of January 1,1998 to December 31,1998. Historical meteorological data was used to generate tables of average dispersion 4

factors. Locations ofinterest were identified from the 1998 land use census.

Dispersion factors and locations ofinterest used in performing the dose j calculations are listed in Table 2.

C. ASSESSMENT RESULTS

SUMMARY

1 i

The calculated doses to the public due to radioactive effluents are listed in 1'

Table 1. The calculated doses are small fractions of their respective dose limits.

i l

Page 24 of 29

-- - . . - - - - -- - - - - - ~ ~ ' ~ ~ ~ ^ ^ " " ~ ~ ' ~ ^ ^^

'S ', .

NEW YORK POWER AUTHORITY i

JAMES A. FITZPATRICK NUCLEAR POWER PLANT i

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 ADDENDUM 1 (continued)

.t

4. .

40 CFR 190 DOSE ASSESSMENT A. METHODOLOGY i i

{

f 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 asmvuent is ,

. required to demonstrate compliance with 40 CFR 190 it is performed in i accordance with the ODCM.

B. RESULTS

SUMMARY

)

The cumulative dose contribution from liquid and gaseous effluents for this report period were calculated and are listed in Table 1. The cumulative dose contribution from direct radiation from the reactor unit and from radwaste '

storage tanks is measured by environmental thermoluminescent dosimeters for the report peilod. This data is contained in'the Annual Environmental

' Operating Report He calculated doses from liquid and gaseous effluents are less than twice tiieir respective 10 CFR 50 limits, therefore, additional calculations are not necessary to demonstrate compliance with 40 CFR 190 l dose limits (RETS 5.1.b).

1 1

l I

' Page 25 of 29 E

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

SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 I ADDENDUM 1 (continucd)

TABLE 1 ANNUAL DOSE ASSESSMENT 1998 A. LIQUIDS QUARTER J_ 2 3 4 ANNUAL ,

(a) (a)

Organ (mrem) NONE NONE NONE 2.64E-05 2.64E-05 l

% of Limit'- ------- - - - - --------

5.28E-04 2.64E-04 I (b) (b) ,

Whole Body (mrem) NONE NONE NONE 2.51E-05 2.51E-05

% of Limit -------- -------

1.67E-03 8.37E-04 t

(a) Dose to the Child Liver primarily from the potable water pathway (b) Dose to the Child Whole Body primarily from the potable water pathway.

B. NOBLE GASES i

OUARTER 1 2 3 4 ANNUAL T. tal r 2dy Pnrem/yr) 9.02E-05 8.16E-05 1.93E-04 3.47E-04 7.12E-04

% af Limit 1.80E-05 1.63E-05 3.86E-05 6.95E-05 1.42E-04 Skm (mrem /yr) 1.10E-04 1.02E-04 2.51 E-04 4.58E-04 9.21E-04

% of Limit 3.66E-06 3.42E-06 8.36E-06 1.53E-05 3.07E-05 Gamma (mrad) 9.34E-05 8.47E-05 2.00E-04 3.61E-04 7.39E-04

% of Limit 1.87E-03 1.69E-0.5 4.00E-03 7.22E-03 7.39E-03 ~

Beta (mrad) 8.30E-06 1.08E-05 3.44E-05 6.87E-05 1.22E-04

% of Limit 8.30E-05 1.08E-04 3.44E-04 6.87E-04 6.11E-04 Page 26 of 29

NEW YORK POWER AUTilORITY JAMES A. FIT 7 PATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 ADDENDUM 1 (continued)

TABLEI ANNUAL DOSE ASSESSMENT 1998 C. IODINES AND PARTICULATES t

OUARTER 1 2 3 4 ANNUAL ,

(a) (a) (a) (b) (b) l Organ (mrem) !

1.27E-03 1.73E-03 1.84E-03 1.92E-02 2.26E-02 >

% of Limit 1.69E-02 2.34E-02 2.46E-02 2.56E-01 1.51 E-01 1

Organ Dose Rate 1.79E-03 1.00E-03 7.83E-04 4.95E-03 4.95E-03 ;

(mrem /yr)

% of Limit 1.19E-04 6.70E-05 5.22E-05 3.30E-04 3.30E-04 j (a) Dose to the Child Thyroid primarily by the vegetation pathway.

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

D. UNMONITORED SHORT-TERM RELEASE QUARTER 4 IODINE AND PARTICULATES ;

(a) 4 Organ (mrem) 5.59E-05

of Limit 7.45E-04 '

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

Page 27 of 29

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT -

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 ADDENDUM 1 (continued)

TABLE 2 METEOROLOGICAL DATA AND LOCATIONS OFINTEREST GEOGRAPHIC ATMOSPHERIC RECEPTOR LOCATION DISPERSION FACTOR i A. IODINE & DISTANCE / RELEASE X/Q D/Q PARTICULATES DIRECTION POINT 2 2 ,

(sec/m ) (1/m)

l. Garden 0.93 mi @ 82EE ST 2.86E-08* 1.72E-09 Grazing Season RX 0.93 mi @ 82EE 1.94E-07* 4.76E-09 Cary TB 0.93 mi @ 82EE 1.76E-07* 4.57E-09 Location No. 78 0.93 mi @ 82EE RF 1.94E-07' 4.76E-09 0.93 mi@ 82EE RW 3.08E-07* 5.45E-09

2. Meat 1.24 mi @ 126ESE ST 1.70E-08* 6.51E-10 Grazing Season RX 1.24 mi @ 126ESE 5.17E-08

1.24E-09 Parkhurst TB 1.24 mi @ 126ESE 4.97E-08* 1.21E-09 Location No. 26 1.24 mi @ 126ESE RF 5.17E-08* 1.24E-09 1.24 mi @ 126ESE RW 8.74E-08* 1.39E-09

3. Cow 2.2 mi @ 138ESE ST 1.65E-08* 3.11E-10 )

Grazing Season RX 2.2 mi @ 138ESE 3.04E-08

5.07E-10 France l 2.2 mi @ 138ESE TB 2.98E-08

4.97E-10 Location No.10 !

2.2 mi @ 138ESE RF 3.04E-08* 5.07E-10 2.2 mi @ 138ESE RW 4.66E-08* 5.39E-10

4. Goat 2.5 mi @ 146ESE ST 1.67E-08* 2.65E-10 I Grazing Season RX 2.5 mi @ 146ESE 2.76E-08* 4.14E-10 Nickolas 2.5 mi @ 146ESE TB 2.71 E-08

4.07E-10 Location No. 61 2.5 mi @ 146ESE RF 2.76E-08* 4.14E-10 2.5 mi @ 146ESE RW 4.15E-08

4.36E-10

5. Resident '

Annual Average i

a. Inhalation 1.55 mi @ 90EE" ST 2.99E-08 -

0.93 mi @ 82EE RX 1.98E-07 -

0.93 mi @ 82EE TB 1.81E-07 -

0.93 mi @ 82EE RF 1.98E-07 -

0.93 mi @ 82EE RW 2.93E-07 -

Tritium Dose Calculation Only

" Highest Sector Average X/Q in a populated area.

Page 28 of 29

, , 1 NEW YORK POWER AUTHORITY

! JAMES A. FITZPATRICK NUCLEAR POWER PLANT l

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1998-DECEMBER 1998 ADDENDUM 1 (continued) l TABLE 2 METEOROLOGICAL DATA AND LOCATIONS OF INTEREST GEOGRAPIllC ATMOSPHERIC l'

RECEPTOR LOCATION DISPERSION FACTOR ,

A. IODINE & DISTANCE / RELEASE X/Q D/Q PARTICULATES DIRECTION POINT (sec/m') (1/m) 2 5 b. Deposition 0.70 mi @ l18EESE ST -

1.61E-09 0.70 mi @ l18EESE RX -

5.65E-09 0.70 mi @ l18EESE TB -

5.42E-09 0.70 mi @ l18EESE RF -

5.65E-09 0.70 mi @ l18EESE RW -

6.42E-09 B. NOBLE GASES

1. Air Dose 1.55 mi @ 90EE ST 2.99E-08 -

Annual Average 0.6 mi @ 90EE ST(fc) 1.16E-07 -

0.6 mi @ 90EE RX 3.58E-07 -

0.6 mi @ 90EE TB 3.19E-07 - !

0.6 mi @ 90EE RF 3.58E-07 -

0.6 mi @ 90EE RW 5.39E-07 -

2. Total Body 0.6 mi @ 90EE ST(fc) 1.16E-07 -

Annual Average 0.6 mi @ 90EE RX 3.58E-07 -

0.6 mi @ 90EE TB 3.19E-07 -

0.6 mi @ 90EE RF 3.58E-07 -

0.6 mi @ 90EE RW 5.39E-07 -

3. Skin 1.55 mi @ 90EE ST 2.99E-08 -

Annual Average 0.6 mi @ 90EE ST(fc) 1.16E-07 -

0.6 mi @ 90EE RX 3.58E-07 -

0.6 mi @ 90EE TB 3.19E-07 -

0.6 mi @ 90EE RF 3.58E-07 -

0.6 mi @ 90EE RW 5.39E-07 -

ST = Main Stack RX = Reactor Building

TB = Turbine Building Vent

! RF = Refuel Floor Vent j RW = Radwaste Vent fc = Finite Cloud Page 29 of 29

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