ML20063L960

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Ja FitzPatrick Nuclear Power Plant Effluent & Waste Disposal Semiannual Rept Jul-Dec 1993
ML20063L960
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Site: FitzPatrick Constellation icon.png
Issue date: 12/31/1993
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POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
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ML20063L959 List:
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NUDOCS 9403080149
Download: ML20063L960 (28)
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT

} JULY I,1993 - DECEMBER 31,1993 DOCKET NO.: 50-333 LICENSE NO.: DPR-59

$R DO K O 33 R PDR

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 SUPPLEMENTAL INFORMATION FACILITY: JAFNPP LICENSEE: NEW YORK POWER AUTHORITY

1. Technical Specification Limits
a. Fission and Activation Gases:

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

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

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

(a) During any calendar quarter, to less than or equal to 5 mrad from gamma radiation, and less than or equal to 10 mrac om 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 a.ad Particulates, Half Lives > 8 days:

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

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

(c) Ixss 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) Ixss 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 1993 - DECEMBER 1993 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-04 Ci/ml.

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

(a) During any calendar quarter, limited to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ; and, (b) During any calendar year, limited to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.

2. Maximum Permissible Concentrations
a. Fission and activation gases: (None specified)
b. Iodines: (None specified)
c. Particulates, half-lives b8days: (None specified)
d. Liquid effluents: Ouarter 3 Ouarter 4 (1) Fission and activation 4.94E-06 4.29E-06 products (mixture MPC)

( Ci/ml)

(2) Tritium ( Ci/ml) 3.00E-03 3.00E-03 (3) Dissolved and entrained gases ( Ci/ml) 2.00E-04 2.00E-04 i

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NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 SUPPLEMENTAL INFORMATION (Continued)

3. Averace Eneruv (None specified)
4. Measurements and Anoroximations of Total Radioactivity .
a. Fission and Activation Gases: Continuous monitor on each release path calibrated to a marinelli grab sample analyzed by gamma spectroscopy; bubbler grab sample analyzed for Tritium.

\ b. 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. Imw activity trash shipments, curie content estimated by dose rate measurement and application of appropriate scaling factors.

m 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 Undeterminate - Random counting error estimated using accepted statistical calculations 3

NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 SUPPLEMENTAL INFORMATION (Continued)

5. Batch Releases
a. Liquid: Ouarter 3 Ouarter 4 (1) Number of batch releases: 1.20E+ 01 2.00E+ 00 (2) Total time period for batch 9.15E+ 02 1.74E+ 02 release: (min)

(3) Maximum time period for 8.50E + 01 9.10E+ 01 batch release: (min)

(4) Average time period for 7.63E+ 01 8.70E+ 01 batch release: (min)

(5) Minimum time period for 7.00E+ 01 8.30E + 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 (1) Number of releases: None None (2) Total activity released: None None 4

NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 TABLE 1A GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES EST TOTAL UNIT OUARTER 3 _ QUARTER 4 ERROR %

A. FISSION AND ACTIVATION GASFS

1. Total Release Cl 8.39E+01 2.12E+01 52,50E+01
2. Average release rate for period pCl/sec 1.06E+01 2.67E+00
3. Tech. Spec. Umit  % *
1. Total lodine-131 Cl 3.7BE-03 1.22E-03 52.50E+01
2. Average release rate for period pCi/sec 4.75E-04 1.54E-04
3. Tech. Spec. Umit  % *
  • C. IODINE 133 AND PARTICULATES
1. lodine-133 and Particulates with half-lives >8 days Cl 4.28E-04 8.36E-05 52.50E+01
2. Average release rate for period pCl/sec 5.38E-05 1.05E-05
3. Tech. Spec. Umit  % * *
4. Gross alpha radioactivity Cl 6.8SE-05 8.60E-05 52.50E+03 D. TRITIUM
1. Total Release Ci 2.45E+00 6.14E-01 52.50E+01
2. Average release rate for period pCl/sec 3.09E-01 7.73E-02
3. Tech. Spec. Umit  % * *
  • E. PERCENT OF TECIINICAL SPECIFICATION LIMITS FISSION AND ACTIVATION GASES
1. Quarterly gamma air dose limit  % 5.92E-02 2.86E-02
2. Quarterly beta air dose limit  % 1.53E-02 5.13E-03
3. Yearly gamma air dose limit  % 2.96E-02 1.43E-02
4. Yearly beta air dose limit  % 7.67E-03 2.56E-03
5. Whole body dose rate limit  % 2.46E-02 6.44E-03
6. Skin dose rate limit  % 5.19E-03 1.72E-03 IIALOGENS, TRITIUM AND PARTICULATES WITil IIALF LIVES >8 DAYS
7. Quarterly dose limit (organ)  % 5.80E-02 2.01E-02
8. Yearly dose limit (organ)  % 2.90E-02 1.01E-02
9. Organ dose rate limit  % 8.53E-02 3.49E-02 5

NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 TABLE IB GASEOUS EFFLUENTS-EMVATED RELEASE CONTINUOUS MODE NUCLIDES RELEASED UNIT OUARTER 3 OUARTER 4

1. Fission Gases Argon-41 Cl 5.31E+00 2.93E+00 Krypton-85m Cl 1.77E+00 4.51E-01 Krypton-87 Ci 3.45E+00 5.21E-01 Krypton-88 Cl 3.12E+00 7.29E-01 Xenon-133 Cl 2.35E+01 1.02E+00 Xenon-135 Cl 6.17E+00 1.04E+00 Xenon-135m Cl 3.24E+00 6.00E-01 Xenon-137 C1 --------

1.23E+00 Xenon-138 Cl 9.13E+00 2.09E+00 TOTAL Cl 5.57E+01 1.06E+01

2. Iodines lodine-131 Cl 4.22E-05 6.55E-06 lodine-133 Cl 1.52E-04 6.84E-05 lodine-135 Ci 7.42E-05 4.72E-05 TOTAL Cl 2.68E-04 1.22E-04
3. Particulates Manganese-54 Cl 2.45E-07 --------

Strontium-89 Cl 4.87E-07 8.85E-07 Cerium-144 Cl 1.56E-06 --------

TOTAL Ci 2.29E-06 8.85E-07

4. Tritium Hydrogen-3 Cl 2.40E-01 1.26E-01 Note: There were no batch releases for this report period.

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT I EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 TABLE 1C GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED UNIT OUARTER 3 OUARTER 4

1. Fission Gases Krypton-85m Cl --------

8 58E-01 Kryptona38 Cl 5.88E-02 3.*t6E+00 Xenon-133 Cl 9.96E+00 1.71E+00 Xenon-133m Cl --------

8.21E-01

( Xenon-135 Cl 7.49E+00 9.26E-01 Xenon-138 Cl 1.07E+01 3.12E+00 TOTAL Cl 2.82E+01 1.06E+01

2. Iodines lodine-131 Cl 1.55E-04 6.32E-05 lodine-133 Cl 1.64E-03 5.05E-04 lodine-135 Cl 6.01E-04 2.07E-04 TOTAL Ci 2.40E-03 7.73E-04
3. Particulates Chromium-51 Cl 1.79E-04 --------

Manganese-54 Cl 2.53E-06 --------

Cobalt-58 Cl 6.96E-06 --------

Cobalt-60 Cl 3.52E-05 3.41E-06 Zinc-65 Cl 2.40E-05 --------

Strontium-89 Cl 1.24E-05 8.89E-06 Niobium-95M Cl 3.81E-06 --------

Barium / Lanthanum-140 Cl 1.00E-05 1.9SE-06 TOTAL Cl 2.74E-04 1.43E-05

4. Tritium Hydrogen-G Cl 2.21E+00 4.88E-01 Note: There were no batch releases for this report period.

7 k . .

_. - - = . - -. . .

NEW YORK POWER AUDIORITY JAMES A.' FITZPATRICK NUCLEAR POWER PIANT ,

I EFFLU'ENT AND WASTE DISPOSAL' SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 l TABLE 2A LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES EST TOTAL UNIT OUARTER 3 OUARTER 4 ERROR %

A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not including 1 tritium, gases and alpha) Cl 6.27E-04 9.24E-05 $2.50E+01 )
2. Average diluted concentra-tion during period pCi/ml 3.42E-12 6.62E-13
3. Applicable limit  % 6.92E-05 1.54E-05 B. TRITIUM
1. Total Release Cl 7.45E-01 1.26E-01 $2.50E+01
2. Average diluted concentra-tion during period gCi/mi 4.06E-09 9.04E-10
3. Applicable limit  % 1.35E-04 3.01E-05 C. DISSOLVED AND ENTRAINED GASES i

l' 1. Total Release Cl 1.48E-05 --------

$2.50E+01

2. Average diluted concentra-l tion during period pCi/ml 8.06E-14 --------

l 3. Applicable Umit  % 4.03E-08 --------

l D. GROSS ALPilA RADIOACTIVITY

1. Total Release Cl -------- --------

52.50E+01 1

l E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) liters 5.32E+05 9.01E+04 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 1.83E+11 1.4OE+11 G. PERCENT OF TECilNICAL SPECIFICATION LIMITS i

! L Ouarterly Whole Body Dose  % 1.23E-04 2.27E-05  !

! 2. Quarterly Organ Dose  % 6.38E-05 1.64E-05 l

3. Annual Whole Body Dose  % 6.17E-05 1.13E-05
4. Annual Organ Dose  % 3.19E-05 8.19E-06 8

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSA.L SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 TABLE 2B LIQUID EFFLUENTS BATCH MODE NUCLIDES RELEASED UNIT OUARTER 3 OUARTER 4

1. Fission and Activation Productg Chromium-51 Cl 1.23E-04 --------

Manganese-54 Cl 1.06E-05 1.37E-05

- Cobalt-58 Cl 1.03E-06 1.0SE-06 Cobalt-60 Ci 8.3SE-05 1.46E-05 Zinc 45 Cl 3.47E-05 --------

Strontium-89 Ci 3.72E-04 6.31E-05 Technetium-99M Cl 1.81E-06 --------

TOTAL Ci 6.27E-04 9.25E-05

2. Tritium Hydrogen-3 Cl 7.45E-01 1.26E-01
3. Dissolved and Entrained Gases Xenon-135 Cl 1.48E-05 --------

TOTAL Cl 1.48E-05 --------

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

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

EFFLUENT AND WASTE DISPOSAL i SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 1

TABLE 3A

, SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 1 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-month Period Est Total Unit Class A Class B Class C Error % ,

1. Tvoe of Waste 3

, a. Spent resins, filter sludges, m 4.65E+01 0.00E+00 0.00E+00 --

evaporator bottoms, etc. ci 2.22E+02 0.00E+00 0.00E+00 2.50E+01

b. Dry compressible waste, m3 2.84E+02 0.00E+00 0.00E+00 --

contaminated equipment, etc. Ci 3.20E+00 0.00E+00 0.00E+00 2.50E+01 3

c. Irradiated components, m 0.00E+00 3.85E+00 4.89E+00 --

control rods, etc. Ci 0.00E+00 7.09E+01 3.40E+04 2.50E+01 l d. Other: Water and Water / Oil m3 1.08E+01 0.00E+00 0.00E+00 --

Mixtures C1 2.76E-04 0.00E+00 0.00E+00 2.50E+01

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

Isotope Percent Curies Isotope Percent Curies Cobalt-60 3.22E+01 7.14E+01 M Chromium-51 3.64E+00 8.09E+00 M Zinc-65 2.35E+01 5.22E+01 M Cobalt-58 3.36E+00 7.45E+00 E Iron-55 2.17E+01 4.82E+01 E Cesium-137 2.50E+00 5.55E+00 M Manganese-54 1.06E+01 2.35E+01 M Cesium-134 9.77E-01 2.17E+00 M j

b. Dry compressible waste, contaminated equipment, etc. l Isotope Percent Curies Isotope Percent Curies Cobalt-60 4.62E+01 1.48E+00 E Nickel-63 3.05E+00 9.75E-02 E Iron-55 2.87E+01 9.18E-01 E Cesium-137 5.82E-01 1.86E-02 E Hydrogen-3 1.68E+03 5.37E-01 E Manganese-54 3.79E-01 1.21E-02 E Zinc-65 3.92E+00 1.25E-01 E Cesium-134 3.48E-01 1.11E-02 E
c. Irradiated components, control rods, etc.

Isotope Percent Curies Isotope Percent Curies Cobalt-60 4.76E+01 1.62E+04 E Nickel-59 2.72E-02 9.29E+00 E Iron-55 4.69E+01 1.60E+04 E Carbon-14 8.15E-03 2.78E+00 E Nickel-63 4.96E+00 1.69E+03 E Hydrogen-3 1.73E-04 5.90E-02 E

, Manganese-54 5.20E-01 1.77E+02 E Niobium-94 7.94E-05 2.71E-02 E 10

NEW YORK POWER AUTHORITY JA.MES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 l

l TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS  !

l i

d. Other: Water and water / oil mixtures.

Isotone Percent Curies Isotope Pe_rgenf Curies Cobalt-60 5.34E+01 1.47E-04 E Cesium-137 1.16E+00 3.20E-06 E Iron-55 2.30E+01 6.34E-05 E Nickel-63 7.40E-01 2.04E-06 E Zinc-65 1. 3 9E+01. 3. 8 3 E-05 E Carbon-14 1.80E-01 4.96E-07 E Manganese-54 7.56E+00 2.08E-05 E Hydrogen-3 9.00E-02 2.48E-07 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.

3. Solid Waste Disposition Eo. of Shipments Mode of Transportation Destination 13 Truck Barnwell, SC 5 Truck *Alaron Corp.

Wampum, PA l 1 Truck 'Quadrex Corporation

! I Oak Ridge, TN 1 Truck

  • Scientific Ecology Group
  • Volume Reduction Facility B. IRRADIATED FUEL SHIPMENTS (Disposition) l l

No. of Shioments Mode of Transportation Destination None N/A N/A l

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i NEW YORK POWER AUTHORITY

, JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 TABLE 3B SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. NRC CLASS A i l

SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Dry Active 3 j

i Waste (DAW) Uncompacted 2080.0 ft STC 5 l Irradiated 3 Metal Dewatered 380.0 ft STC 1 Spent Resin &

3 Filter Media Dewatered 205.8 ft HIC 3 Spent Resin &

3 Filter Media Dewatered 170.8 ft HIC 6 3

j Oil / Water Liquid 7.5 ft STC 51 B. NRC CLASS B SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Irradiated 3

Hardware Dewatered 135.8 ft STC 1 C. NRC CLASS C SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Irradiated 3

Hardware Dewatered 57.8 ft STC 1 Irradiated 3

Hardware Dewatered 57.4 ft STC 2 Solidification Acent: None HIC - High Integrity Container STC - Strong Tight Container 12

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 ATTACHMENT NO.1 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM) 1 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 (ODCM) during the reporting period shall be included in the Semi-Annual Radioactive Effluent Release Report.

Revision 9 of the ODCM was approved by the Plant Operating Review Committee on December 22,1993 at Meeting No.93-170 and became effective on December 28,1993.

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 copy of revision 9 to the ODCM excluding the maps.

1. The procedural requirements of the Radiological Effluent Technical Specification (RETS) were added as Part 1 pages 1 - 51 of REC.
2. Section 3.4.3, Dose Assessment Methodology for Liquid Releases through the Storm Drains was added (pages 21 - 25 of ODCM).

l 3. Section 4.3.1, Determining Instantaneous Noble Gas Release Rates and Section 4.3.2, Set Point Determination (pages 33 - 44 of ODCM) were revised based on

updated meteorological dispersion data and updated effective dose factor data.

i

4. Section 4.4.2, Monthly Dose Assessment Verification of Comphance with 10 CFR 50 Appendix I was revised based on updated meteorological dispersion data and updated effective dose factor data (pages 56 - 66 of ODCM).
5. Section 4.4.3, Short Term Releases was added to present the methodology for )'

calculating the offsite radiation exposures from short term gaseous release (pages 67 - 75 of ODCM).

4

6. Meteorological Index, Appendix C (pages C C-42 of ODCM) were revised.
7. Technical Bases for Effective Dose Factors, Appendix E (pages E E-11 of ODCM) were revised.

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NEW YORK POWER AUTHORITY i JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 ATTACHMENT NO. 2

SUMMARY

OF CHANGES TO THE 1*ROCESS 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 reporting period shall be included in the Semi-Annual j Radioactive Effluent Release Report.

1. CONTRACTOR PROCEDURES:
a. The current Chem-Nuclear Systems, Inc. Procedures are as listed:

o CNSI Procedure, DM-OP-046-45230 - Operation of FTDS at James A. FitzPatrick Nuclear Power Plant, Revision 3, 9/29/93 (PORC Meeting No.93-121). This revision incorporated changes per vendor recommendations, as documented in memo dated 9/16/93.

o CNSI Procedure FO-OP-025-45230 - Dewatering Procedure for CNSI 24-inch Diameter Pressure Vessels at James A.

FitzPatrick Nuclear Power Plant. This procedure was deleted 10/93. It was no longer needed.

o CNSI Procedure FO-OP-019-45230 - Polyethylene High Integrity Container Overpack Handling Procedure at James A. FitzPatrick Nuclear Power Plant. This procedure was i I

deleted 10/93. It was no longer needed.

o SEG Quality Assurance Program, Revision 3,11/20/91 (PORC Meeting No.91-112). This procedure was deleted 11/93 it was no longer needed.

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

EFFLUENT AND WASTE DISPOSAL i SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 i l

NITACHMENT NO. 3 1

SUMMARY

OF. CHANGES TO THE ENVIRONMENTAL MONITORING AND  ;

DOSE CALCULATION LOCATIONS 4

l In accordance with Section 7.3.C.3 of Amendment 93 to the James A. FitzPatrick I

Nuclear Power Plant Technical Specifications, a listing of new locations for dose j calculation and/or environmental monitoring identified by the land use census shall be i included in the Semi-Annual Radioactive Effluent Release Report.  :

CHANGES IN ENVIRONMENTAL MONITORINO LOCATIONS 1

1. The control milk sampling location was changed in August of 1993. The new l

! control location is designated as location No. 63 and is located 13.9 miles from

the site in the SW sector at 234". The original control milk location was sold j by the owner and ceased milk production.

NEW LOCATIONS FOR DOSE CALCULATIONS j

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

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)

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d 4

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i NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 ATTACHMENT NO. 4 DEVIATIONS FROM THE REQUIRED

-ENVIRONMENTAL SAMPLING SCHEDULE In accordance with Section 7.3.C.7 of Amendment 93 to the James A. FitzPatrick l

Nuclear Power Plant Technical Specifications, the cause for unavailability of any environmental samples required during the report period shall be included in the Semi-Annual Radioactive Effluent Release Report.

EXCEPTION TO THE ENVIRONMENTAI. SAMPLING PROGRAM

1. The air sampling pump at the R-5, offsite Environmental Sampling Station was inoperable from July 6,1993 (1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br />) to July 7,1993 (1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />). The inoperability was caused by technician error, failure to reset pump.
2. The air sampling pump at the R-4, offsite Environmental Sampling Station was inoperable from October 14,1993 (1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />) to October 14, 1993 (1545 l hours). The inoperability was caused by maintenance on electrical lines l feeding the station sampling . pump.

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 ATTACHMENT 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 smnmary of meteorological data may be included and submitted in the Semi-Annual Radioactive Effluent Release Report within 60 days after January 1 of each year.

Meteorological data for the period of January 1,1993 through December 31,1993 is not

! included in this report. It is on file and available upon request.

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1 17 I. .- -. - .. -. .- . _ _

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 A'ITACHMENT NO. 6 REPORT NOTES Table 2A Section A and B and Table 2B Normal Liguid Effluents The values for Tritium, Strontium-89, Strontium-90, and Iron-55 were calculated from the most recen". ...vailable sample data. If the actual sample data significantly alters the percent of allowable release limits, the report will be revised and redistributed.

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l NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 ADDENDUM 1 ASSESSMENT OF RADIATION DOSES TO THE PUBLIC JANUARY - DECEMBER 1993

1. INTRODUCTION The James A. FitzPatrick Nuclear Power Plant Radiological Effluent Technical Specifications (RETS) require an assessment of the radiation doses to the public due to radioactive liquid and gaseous effluents. This assessment l of doses to the public is based on accepted methodologies found in the Offsite l l Dose Calculation Manual (ODCM).

l l 2. DOSE LIMITS A. DOSE FROM LIOUID EFFLUENTS (RETS 23)

Applicability Applies to doses from radioactive material in liquid effluents.

Obiective i

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

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

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

the whole body and to less than or equal to 10 mrem to any organ.  !

B. GASEOUS DOSE RATES (RETS 3.2)

Anolicability i

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

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 ADDENDUM 1 (continued)

Objective l

To ensure that the dose rates at or beyond the site boundary from l l

gaseous effluents do not exceed the annual dose limits of 10 CFR 20, for '

unrestricted areas.

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

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

! C. AIR DOSE. NOBLE OASES (RETS 3.3) l l Applicability Applies to the air dose due to noble gases in gaseous effluents.

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

Specifications The air dose to areas at or beyond the site boundary from noble gases released from the plant in gaseous effluents shall be limited:

1. During any calendar quarter, to less than or equa~ 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.

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4 l NEW YORK POWER AUTHORITY 4

JAMES A. FITZPATRICK NUCLEAR POWER PLANT l l EFFLUENT AND WASTE DISPOSAL '

i SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 l

l 1

ADDENDUM 1 (continued) ,

D. DOSE DUE TO IODINE-131. IODINE-133. TRITIUM AND j RADIONUCLIDES IN PARTICULATE FORM (RETS 3.4) i Applicability l

i Applies to the cumulative dose from Iodine-131, Iodine-133, Tritium, and I

radionuclides in particulate form with half-lives greater than 8 days in

, gaseous effluents. l i

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

< Specifications

The dose to a member of the public at or beyond the site boundary from 1

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

with half-lives greater than 8 days released from the plant in gaseous i j

effluents shall be limited: l i i d

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

i j E. TOTAL DOSE FROM URANIUM FUEL CYCLE (RETS 5.1)

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

Objective

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

)

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NEW YORK. POWER AUTHORITY I JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 ADDENDUM 1 (continued) l l

Specifications  !

] l 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. I2ss 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 Reaccor i Effluents for the purpose of Evaluating Compliance with 10CFR50, Appendix I" (Regulatory Guide 1.109).

B. ASSUMIrTIONS Dose calculations are performed using formulas and constants defined in i

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 1,1993 to December 31,1993. Historical meteorological data was used to generate tables of average dispersion factors. Locations of interest were identified from the 1993 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.

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NEW YORK POWER AUTHORITY  ;

JAMES A. FITZPATRICK NUCLEAR POWER PLANT I EFFLUENT AND WASTE DISPOSAL i I

SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 ADDENDUM 1 (continued)

4. 40 CFR 190 DOSE ASSESSMENT A. METHODOLOGY Evaluation to demonstrate compliance with the 40 CFR 190 dose limits must be performed when the doses calculated for 10 CFR 50 compliance exceed twice their respective limits. When additional dose assessment is required to demonstrate compliance with 40 CFR 190 it is performed in accordance with the ODCM.

B. RESULTS

SUMMARY

The cumulative dose contribution from liquid and gaseous effluents for this report period were calculated and are listed in Table 1. The Cdiculated doses 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 (RETS 5.1.6).

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7 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 1993 l

A. LIQUIDS OUARTER 1 2 3 4 ANNUAL (b) (a) (b) (e) (b)

Organ (mrem) 8.05E-05 7.57E-07 3.19E-06 8.19E-07 8.46E-05 l

% of Limit 1.61E-03 1.51E-05 6.38E-05 1.64E-05 8.46E-04 (d) (c) (c) (b) (d)

Whole Body (mrem) 4.80E-05 5.01E-07 1.85E-06 3.40E-07 5.02E-05

% of Limit 3.20E-03 3.34E-05 1.23E-04 2.27E-05 1.67E-03 i

i (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.

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

(e) Dose to the Adult GI-LLI primarily by the fish pathway.

! B. NOBLE GASES OUARTER 1 2 3 4 ANNUAL l

Total Body (mrem /yr) 8.13E-02 7.31E-02 1.23E-01 3.22E-02 1.23E-01

% of Limit 1.63E-02 1.46E-02 2.46E-02 6.44E-03 2.46E-02 l Skin (mrem /yr) 1.13E-01 1.02E-01 1.56E-01 5.16E-02 1.56E-01 1  % of Limit 3.75E-03 3.40E-03 5.19E-03 1.72E-03 5.19E-03 a

$ 1.40E-03 1.35E-03 2.96E-03 1.43E-03 7.14E-03 Gamma (mrad)

% of Lim.it 2.79E-02 2.70E-02 5.92E-02 2.86E-02 7.14E-02 l Beta (mrad) 9.02E-04 9.21E-04 1.53E-03 5.13E-04 3.87E-03 1  % of Limit 9.02E-03 9.21E-03 1.53E-03 5.13E-03 1.93E-03 24

1 NEW YORK POWER AUTHORITY i JAMES A. FITZPATRICK NUCLEAR POWER PLWI' EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 ADDENDUM 1 (continued) l TABLE 1 1 ANNUAL DOSE ASSESSMENT 1993 l

l C. IODINES AND PARTICULATES l OUARTER 1 2 2 4 ANNUAL (a) (b) (b) (b) (b)

Organ (mrem) 3.76E-03 2.17E-03 4.35E-03 1.51E-03 1.16E-02 l  % of Limit 5.01E-02 2.89E-02 5.80E-02 2.01E-02 7.73E-02 Organ Dose Rate 2.88E+00 5.74E-01 1.28E+00 5.23E-01 2.88E+ 00 (mrem /yr)

% of Limit 1.92E-01 3.83E-0'2 8.53E-02 3.49E-02 1.92E-01 1

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

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

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( NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 ADDENDUM 1 (continued)

TABLE 2 I METEOROLOGICAL DATA AND LOCATIONS OF INTEREST GEOGRAPHIC ATMOSPHERIC RECEPTOR LOCATION DISPERSION FACTOR A. IODINE & DISTANCE / RELEASE X/O D/O 2 3

PARTICULATES DIRECTION POINT (sec/m ) (1/m)

1. Garden 0.9 mi @ 82 E ST -

1.62E-09 Grazing Season 0.9 mi @ 82 E RX -

5.18E-09 Cary 0.9 mi @ 82 E TB -

4.74E-09 Location No. 78 0.9 mi @ 82 E RF -

5.18E-09 0.9 mi @ 82 E RW -

6.10E-09

2. Meat 1.2 mi @ 126'SE ST. -

839E-10 Grazing Season 1.2 mi @ 126 SE RX -

1.72E-09 Parkhurst 1.2 mi @ 126 SE TB -

1.61E-09 Location No. 26 1.2 mi @ 126 SE RF -

1.72E-09 l 1.2 mi @ 126 SE RW -

2.01E-09 f 3. Cow 2.2 mi @ 138 SE ST -

3.87E-10 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-10 2.2 mi @ 138 SE RW -

7.23E-10

4. Goat 2.5 mi @ 146 SE ST -

330E-10 Grazing Season 2.5 mi @ 146 SE RX -

533E-10 Nickolas 2.5 mi @ 146 SE TB -

5.13E-10 Location No. 61 2.5 mi @ 146 SE RF -

533E-10 2.5 mi @ 146 SE RW -

5.80E-10

5. Resident Annual Average
a. Inhalation 1.9 mi @ 90 E ST 3.16E-08 -

0.9 mi @ 82 E RX 2.81E-07 -

0.9 mi @ 82 E TB 2.41E-07 -

0.9 mi @ 82 E RF 2.81E-07 -

0.9 mi @ 82 E RW 438E-07 -

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. NEW YORK POWER AUTHORITY j JAMES A. FITZPATRICK NUCLEAR POWER PLANT i EFFLUENT AND WASTE DISPOSAL l SEMI-ANNUAL REPORT JULY 1993 - DECEMBER 1993 i

ADDENDUM 1 (continued) i TABLE 2

! METEOROLOGICAL DATA AND LOCATIONS OF INTEREST i'

l- GEOGRAPHIC ATMOSPHERIC i RECEPTOR LOCATION DISPERSION FACTOR A. IODINE & DISTANCE / RELEASE X/O D/Q 2

PARTICULATES DIRECTION POINT- (sec/m3) (1/m)

, 5 b. Deposition 0.9 mi @ 82"E ST -

1.63E-09 y 0.7 mi @ 118 ESE RX -

5.99E-09 j l 0.7 mi @ 118 ESE TB -

5.45E-09 '

i 0.7 mi @ 118 ESE RF -

5.99E-09 j 0.7 mi @ 118 ESE RW -

7.%E-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 -

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

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 -

l 2. Total Body 0.6 mi @ 90 E ST(fc) 1.44E-07 -

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

0.6 mi @ 90 E TB 3.96E-07 -

0.6 mi @ 90 E RF 4.83E-07 -

j 0.6 mi @ 90 E RW 7.47E-07 -

! 3. Skin 1.9 mi @ 90 E ST 3.16E-08 -

j 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 -
0.6 mi @ 90 E RF 4.83E-07 -

j 0.6 mi @ 90 E RW 7.47E-07 -

2 ST = Main Stack

RX = Reactor Building
TB = Turbine Building Vent j RF = Refuel Floor Vent i RW = Radwaste Vent j fc = Finite Cloud i

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