ML20237G249

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Effluent & Waste Disposal Semiannual Rept,Jan-June 1987
ML20237G249
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 06/30/1987
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20237F917 List:
References
NUDOCS 8709020165
Download: ML20237G249 (29)
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Text

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NEW YORK POWER AUTHORITY

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i JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY 1987 - JUNE 1987 l

DOCKET NO.: 50-333 LICENSE NO.: DPR-59 ura mme R

9 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987 SUPPLEMENTAL INFORMATION FACILITY: JAFNPP LICENSEE: NEW -YORK POWER AUTHORITY

1. Regulatory 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 effluents 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 effluents 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 irom beta radiation.

b. Tritium, iodines and particulate,_ 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 effluents shall tur limited:

(a) During any calendar quarter to less than or equal to 7.5 mrem to any organ; and, (b) During any calendar year to less than or equal to 15 mrem to any organ, (c) Less than 0.1% of the limits of Specification-3.4.a.1 and 3.4.a.2 as a result of burning contaminated oil. I I

(1)

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SUPPLEMENTAL INFORMATION (continued)

(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).

c. Liquid effluents: ,

I (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 l noble gases the concentration shall be limited to i 2E-4 pCi/ml.

(2) The dose to a member of the public from radioac-tive 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 i 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)

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e SUPPLEMENTAL INFORMATION (continued) j

2. Maximum Permissible Concentrations
a. Fission and activation gases: (None specified)
b. Iodines: (None specified)
c. Particulate, half-lives >8 days: (None specified)
d. Liquid effluents:

Quarter 1 Quarter 2 ]

(1) Fission and Activation 3.56E-05 3.76E-05 Products (Mixture MPC)

(2) Tritium 3.00E-03 3.00E-03 (3) Dissolved and Entrained Gases 2.00E-04 2.00E-04

3. Average Energy, E: (None Specified)
4. Measurements and Approximations of Total Radioactivity
a. Fission and activation gases: Continuous monitor on I each release path calibrated to Marinelli grab sample analyzed by gamma spectrospeopy; bubbler grab sample analyzed for tritium.
b. Iodines: gamma spectral analysis of charcoal cartridge and particulate filter on each release path,
c. Particulate: gamma spectral analysis of particulate filter on each release path.

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d. Liquid effluents: gamma spectral analysis of each batch discharged, except composite analysis for Sr-89, Sr-90, Fe-55, and tritium.

(3)

4 SUPPLEMENTAL INFORMATION (continued)

5. Batch Releases Liquid:

(1) Number of batch releases: 5.70E+01 (2) Total time period for batch releases: 5.48E+03 (min)

(3) Maximum time period for batch release: 3.82E+02 (min)

(4) Average time period for batch release: 9.61E+01 (min) l (5) Minimum time period l

for batch release: 6.50E+01 (min)

6. Abnormal Releases
a. Liquid: Quarter 3 Quarter 4 (1) Number of releases: None None l (2) Total activity released: None None l

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b. Gaseous:

(1) Number of releases: None None (2) Total activity released: None None l

l (4)

TABLE 1A NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES EST.

TOTAL UNIT QUARTER 1 QUARTER 2 ERROR %

A. FISSION AND ACTIVATION GASES

1. Total release Ci 2.63E+02 8.74E+02 -<25%
2. Average release rate for period uCi/sec 3.38E+01 1.11E+02
3. Tech. Spec. limit  %
1. Total iodine-131 C1 1.90E-03 3.70E-03 -<25%
2. Average release rate for period uCi/sec 2.45E-04 4.71E-04
3. Tech. Spec. limit  % *
  • C. 10 DINE-133 AND PARTICULATE
1. Iodine-133 and Particulate with half lives >8 days Ci 5.30E-03 6.85E-03 -<25%
2. Average relea. ate for period uCi/sec 6.82E-04 8.71E-04
3. Tech. Spec. limit  % * *
4. Gross alpha radioa ivity C1 1.28E-05 6.65E-05 <25%

D. TRITIUM

1. Total release Ci 5.54E-01 2.88E+00 -<25%
2. Average release rate for period pCi/sec 7.13E-02 3.66E-01
  • E. PERCENT OF TECHNICAL SPECIFICATION LIMITS UNIT QUARTER 1 QUARTER 2 FISSION AND ACTIVATION GASES l
1. Quarterly gamma air dose limit  % 5.00E-02 6.96E-02 l
2. Quarterly beta air dose limit  % 1.53E-02 3.15E-02 l
3. Yearly gamma air dose limit  % 2.50E-02 3.48E-02 l
4. Yearly beta air dose limit  % 7.65E-03 1.58E-02
5. Whole body dose rate limit  % 4.68E-04 1.81E-03 )
6. Skin dose rate limit  % 1.25E-04 4.47E-04 i HALOGENS, TRITIUM AND PARTICULATE WITH HALF-LIVES >8 DAYS
7. Quarterly dose limit (organ)  % 5.40E-01 9.89E-01
8. Yearly dose limit (organ)  % 2.70E-01 4.95E-01
9. Organ dose rate limit  % 3.68E-05 5.60E-05 (5)

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(- TABLE IB NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL I SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987 GASEOUS EFFLUENTS--ELEVATED RELEASE CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2

1. Fission gases Argon-41 Ci 3.11E+01 3.75E-01 Krypton-85m Ci ND 2.94E+02 Krypton-87 Ci ND 7.54E+00 Krypton-88 Ci ND 2.46E+01 Xenon-133 Ci 5.28E+01 2.96E+02  !

Xenon-135 Ci 3.04E+01 4.39E+01 Xenon-135m Ci ND 3.49E+01 Xenon-131m Ci 2.30E+00 ND Xenon-138 Ci 5.98E+01 1.33E+01

2. Iodines Iodine-131 C1 1.24E-03 2.45E-03 Iodine-133 Ci 1.76E-03 1.90E-03 l
3. Particulate Cobalt-60 Ci 2.18E-07 4.59E-07 Strontium-89 C1 1.65E-07 1.59E-05 Strontium-90 Ci 1.11E-07 5.62E-08 Cesium-137 C1 1.21E-06 ND Barium-Lanthanum-140 Ci 2.63E-05 7.17E-06 Cerium-141 Ci 5.58E-07 ND There are no batch releases for this period.

ND - None detected.

(6)

I TABLE 1C NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES CONTINUOUS MODE l

NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2

1. Fission gases Krypton-85m Ci 1.22E+00 2.24E+01 Krypton-87 Ci ND 3.35E+00 Krypton-88 Ci 9.79E+00 9.38E+00 Xenon-133 C1 1.66E+01 1.00E+02 l Xenon-135 Ci 6.04E+00 8.60E+00 '

Xenon-135m Ci 7.36E-01 1.03E+00 Xenon-131m Ci 1.19E+01 ND Xenon-133m Ci 3.31E+01 2.82E+00 Xenon-138 Ci 7.06E+00 1.17E+01

2. Iodines Iodine-131 Ci 6.63E-04 1.25E-03 Iodine-133 Ci 2.23E-03 1.51E-03 l
3. Particulate  !

Chromium-51 Ci 2.98E-04 2.43E-03 Manganese-54 C1 1.09E-04 5.79E-05 Cobalt-58 Ci 3.07E-05 1.18E-04 Cobalt-60 Ci 6.63E-04 3.16E-04 Zinc-65 Ci 3.26E-05 1.76E-04 Strontium-89 Ci 8.24E-07 9.35E-05 Strontium-90 Ci ND 5.98E-07 Antimony-124 Ci ND 1.28E-10 Cesium-134 Ci ND 3.46E-05 Cesium-137 Ci ND 1.20E-04 Barium-Lanthanum-140 Ci 1.39E-04 7.57E-05 Cerium-141 Ci 2.75E-06 5.72E-07 There are no batch releases for this period.

l ND - None detected.

(7) l l

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i TABLE 2A )

i NEW YORK POWER AUTHORITY i JAMES A. FITZPATRICK NUCLEAR POWER PLANT 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987 i LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES l EST. j TOTAL -

A. FISSION AND ACTIVATION PRODUCTS UNIT QUARTER 1 QUARTER 2 ERROR %

1. Total release (not including tritium and alpha) C1 3.86E-02 3.98E-02 125%
2. Average diluted concentration during period pCi/ml 4.85E-10 2.55E-10
3. Applicable limit  % 1.56E-03 6.78E-04 B. TRITIt.
1. Total release Ci 1.14E+00 1.34E+00 125%
2. Average diluted concentration during period pCi/ml 1.43E-08 8.59E-09 Q
3. Applicable limit  % 4.77E-04 2.86E-04 i

C. DISSOLVED AND ENTRAINED GASES l

1. Total release Ci 4.51E-05 ND 125%
2. Average diluted concentration during period pCi/ml 5.68E-13 ND
3. Applicable limit  % 2.84E-07 ND D. GROSS ALPHA RADIOACTIVITY Total release Ci 5.05E-05 3.64E-07 125%

ND - None detected.

(8)

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i LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES (continued)

UNIT QUARTER 1 QUARTER 2 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) liters 1.35E+06 1.60E+06 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 7.95E+10 1.56E+11

  • G. PERCENT TECHNICAL SPECIFICATION LIMITS ,

UNIT QUARTER 1 QUARTER 2 i

1. Quarterly whole body dose  % 1.61E+00 1.79E-01 l l
2. Quarterly organ dose  % 7.50E-01 8.48E-02
3. Annual who.le body dose  % 8,03E-01 8.93E-03 4 Annual organ

! dose  % 3.75E-01 4.24E-02 l

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(9) l l

L___.____.___________________..__________________._________._ _ _ _ _ . _

TABLE 2B NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987 LIQUID EFFLUENTS BATCH F J?'

NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 Hydrogen-3 C1 1.14E+00 1.34E+00 Sodium-24 Ci ND 2.78E-04 Manganese-54 Ci 6.66E-03 9.35E-03 Iron-55 C1 3.11E-03 3.67E-03 Iron-59 C1 1.21E-04 2.28E-04 Cobalt-58 Ci 9.38E-04 1.96E-03 Cobalt-60 C1 2.32E-02 2.00E-02 Zinc-65 Ci 4.44E-04 2.33E-05 Antimony-124 Ci ND 1.27E-04 Cesium-134 Ci 6.54E-04 8.11E-04 Xenon-133 Ci 4.51E-05 ND Cesium-137 Ci 3.37E-03 3.28E-03 Barium-Lanthanum-140 Ci ND 2.58E-05 Tungsten-187 Ci 3.42E-05 ND ALPHA Ci 5.05E-05 3.64E-07 There were no continuous mode discharges during this period.

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l ND - None detected.

Note: 1st quarter H3 and Fe-55 values used for 2nd quarter calculations, i

(10)

TABLE 3A NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAP POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

EST.

SIX-MONTH TOTAL UNIT PERIOD ERROR %

1. Type of Waste
a. Spent resins, filter sludges m3 87.6 10 %

evaporator bottoms, etc. Ci 284 125%

b. Dry compressible waste, m3 217.9 10 %

contaminated equipment, etc. Ci 8.75 125%

c. Irradiated components (None)
d. Waste oil m3 9.2 10 %

Ci 0.0745 125%

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2. Estimate of Major Nuclide Composition  ;

l Isotope  % Abundance Est. Error %

Cobalt-60 51.092% 10 Iron-55 25.575% 10 Manganese-54 10.174% 10 Cesium-137 4.462% 10 Zinc-65 3.081% 10 Cobalt-58 1.547% 10 Chromium-51 1.544% 10 i Cesium-134 1.107% 10 l Nickel-63 0.866% 10 l Iron-59 0.458% 10 l Carbon-14 0.040% 10 l Strontium-89 0.013% 10 Strontium-90 0.009% 10 Nickel-59 0.008% 10 Hydrogen-3 0.006% 10 Plutonium-241 0.005% 10 Barium-Lanthanum-140 0.005% 10 Cerium-144 0.002% 10 Cobalt-57 0.002% 10 Cerium-141 0.001% 10 i 1

3. Solid Waste Disposition TRANSPORTA-SHIPMENT QTY. TION MODE DESTINATION Type a 19 Truck Barnwell, SC Type b 6 Truck Richland, WA Type b & d 1 Truck Richland, WA (l1)

1 TABLE 3B l

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE-DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987 i SOLID WASTE AND IRRADIATED FUEL SHIPMENTS l

A. NRC CLASS "A" l

1. Compacted /Noncompacted Dry Waste  !

l Container Type: 7.5 ft 3 55 gallon drum Solidification Media: None Total Volume: 210 ft3 5.9 m3 i No. of Shipments: 2 Type: Cask Mode: Truck Principal Quantity Isotopes Curies  % Abundance Determination Cobalt-60 3.520 49.308% E Iron-55 1.770 24.816% E Cesium-137 0.512 7.166% E Manganese-54 0.463 6.479% E Chromium-51 0.333 4.665% E Cesium-134 0.236 3.298% E Zinc-65 0.202 2.834% E I Nickel-63 0.075 1.050% E l

Carbon-14 0.001 0.016% E Strontium-90 0.0004 0.006% E Hydrogen-3 0.0003 0.004% E TOTAL: 7.14 curies (estimated)

E = Estimated (12)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (continued) l A. NRC Class "A" (continued)

2. Compacted /Noncompacted Dry Waste 3

Container Type: 107 ft steel box (LSA) i I

Solidification Media: None Total Volume: 7490 ft 3 212 m3 No. of Shipments: 7 Type: Flatbed i Mode: Truck

, Principal Quantity Isotopes Curies  % Abundance Determination Cobalt-60 0.795 49.516% E Iron-55 0.400 24.939% E Cesium-137 0.116 7.205% E Manganese-54 0.104 6.503% E Chromium-51 0.074 4.609% E Cesium-134 0.053 3.313% E Zinc-65 0.046 2.839% E l Nickel-63 0.017 1.056% E Carbon-14 0.0003 0.016% E Hydrogen-3 0.0001 0.004% E l

l TOTAL: 1.61 curies (estimated) l l E = Estimated l

l l

(13)

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SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (continued)

A. NRC Class "A" (continued)

3. Solidified Powdered Resin / Filter Sludge Container Type: 182 ft steel liner (LSA)

Solidification Media: Gement Total Volume: 728 ft3 20.6 m3 No. of Shipments: 4 Type: Cask

, Mode: Truck l

Principal Quantity Isotopes Curies  % Abundance Determination Cobalt-60 87.100 49.807% M Iron-55 43.900 25.095% E Manganese-54 18.900 10.818% M Cesium-137 6.850 3.916% M Zine-65 6.400 3.661% M Chromium-51 3.520 2.013% M Cobalt-58 3.280 1.875% M Nickel-63 1.850 1.059% 'E Carbon-14 0.018 0.010% E Nickel-59 0.016 0.009% E Strontium-90 0.014 0.008% E Plutonium-241 0.012 0.007% E Hydrogen-3 0.004 0.002% E TOTAL: 175.0 curies (measured / estimated)

M = Measured E = Estimated (14)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (continued)

A. NRC Class "A" (continued)

4. Solidified Bead Resin Container _ Type 182 ft 3 steel liner (LSA)

Solidification Media: Cement Total Volume.- 1092 ft3 30.9 m3 No. of Shipments: 6 Type: Cask Mode: Truck Principal Quantity Isotopes Curies  % Abundance Determination l Cobalt-60 13.100 58.022% M Manganese-54 6.270 27.847% M l Iron-55 0.934 4.147% E i Cobalt-58 0.914 4.060% M

! Zinc-65 0.420 1.865% M Cesium-137 0.352 1.561% M Nickel-63 0.166 0.737% E Carbon-14 0.093 0.411% E Nickel-59 0.006 0.026% E Hydrogen-3 0.006 0.026% E Strontium-90 0.005 0.023% E Plutonium-241 0.001 0.004% E l

TOTAL: 22.5 curies (measured / estimated)

M = Measured E = Estimated i

(15) l 1

t SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (continued)

A. NRC Class "A" (continued) l 5. Solidified Evaporator Bottoms Container Type: 182 ft 3 steel liner (LSA)

Solidification Media: Cement Total Volume: 1092 ft 3 30.9 m3 No. of Shipments: 6 Type: Cask Mode: Truck Principal Quantity Isotopes _ Curies  % Abundance Determination Cobalt-60. 39.900 53.012% M Iron-55 . 25.400 33.697f, E Cesiem-137 5.010 6.653% M Manganeser54 2.220 2.951% M Zinc-65 1.380 1.838% M Cesium-134 1.060 1.403% M Nickel-63 0.316 0.420% E Hydrogen-3 0.008 0.010% E Strontium-90 0.007 0.009% E Carbor.-14 0.004 0.005% E TOTAL: 75.2 curies (measured / estimated)

M = Measured E = Estimated

)

~

I (16s

-~.~u-~__

I SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (continued)

A. NRC Class "A" (continued)

I

6. Solidified Bead Resin / Powdered Resin Container Type: 182 ft 3 steel liner (LSA)

Solidification Media: Cement Total Volume: 182 ft3 5.2 m3 No. of Shipments: 1 4 Type: Cask Mode: Truck

)

1 i

Principal Quantity Isotopes Curies %Abundan_ce Determination Cobalt-60 5.250 45.803% M i Iron-55 2.550 22.247% E

, Manganese-54 1.820 15.879% M l Zinc-65 0.571 4.982% M i Chromium-51 0.490 4.275% M  !

Cobalt-58 0.314 2.739% M i Cesium-137 0.231 2.015% M i l Nickel-63 0.110 0.960% E Plutonium-241 0.002 0.014% E Nickel-59 0.001 0.009% E Strontium-90 0.0006 0.005% E Carbon-14 0.0003 0.003% E l Hydrogen-3 0.0002 0.002% E i l

TOTAL: 11.5 curies (measured / estimated)

M = Measured E = Estimated (17)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (continued)

A. NRC Class "A" (continued)

7. Solidified Waste Oil Container Type: 107 ft3 steel liner (LSA)

Solidification Media: Cement Total Volume: 321 ft 3 9.2 m3 No. of Shipments: 1 Type: Flatbed Mode: Truck Principal Quantity Isotopes Curies  % Abundance Determination Cobalt-60 0.0391 52.485% M Iron-55 0.0195 26.172% E Cesium-137 0.0059 7.847% M l Manganese-54 0.0030 4.056% M Chromium-51 0.0017 2.319% M Zinc-65 0.0014 1.945% M Cesium-134 0.0013 1.802% M Plutonium-241 0.0012 1.583% E Nickel-63 0.0008 1.085% E Carbon-14 0.00001 0.017% E Hydrogen-3 0.000003 0.005% E l

TOTAL: 0.0745 curies (measured / estimated)

M = Measured E = Estimated 1

(18)

4 TABLE 4 i NEW YORK POWER AUTHORITY 1 JAMES A. FITZPATRICK NUCLEAR POWER PLANT l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987 SEMIANNUAL

SUMMARY

OF HOURLY METEOROLOGICAL DATA I

I In accordance with Amendment 93 of the James A. FitzPatrick  !

Nuclear Power Plant Technical Specifications, an annual summary of  !

hourly meteorological data shall be included and submitted in the  !

Semiannual Radioactive Effluent Release Report within 60 days )

after January 1 of each year. Meteorological data for period of j January 1, 1987 through June 30, 1987 will be included in the second half of the 1987 report. i l

d (19)

TABLE 5 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987

SUMMARY

OF LdANGES TO THE OFFSITE DOSE CALCULATION MANUAL 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) and Offsite Dose Calculation Manual (0DCM) during the reporting period are to be included in the Semiannual Radiological Effluent Release Report.

The table below describes and provides justification for recent changes to the Off-site Dose Calculation Manual and explains why these changes will not adversely offset the accuracy or reliability of monitor alarm setpoint determinations. Copies of the revised pages of the Off-site Dose Calculation Manual are included as attachment 1.

No changes were made to the PCP during this report period.

l 1

j 1

I (20)

TABLE r (Continued)

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987

SUMMARY

OF CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL CIIANGE REVISION 5 DESCRIPTION OF CHANGE AFFECT ON i90 . PAGE/SECTION (JUSTIFICATION) ACCURACY / RELIABILITY

1. Page 9, 10, 11, 12 In Revision 5 of Section This change increases the Section 3.3 3.3 the setpoint technical accuracy of the determination for the ODCM.

liquid waste effluent monitor and the service water effluent monitor are specificly addressed.

Section 3.3.4 was added to address the service water monitor. Prior to this revision the alarm setpoints for all liquid effluent monitors were generically addressed.

2. Page 15 The unit of milliliters This change increases the Section 3.4.2.b.1 was specifiec for the descriptive accuracy of (DF)3 Dilution Flow the ODCM.

variable in the definition of terms for equation 3-5.

3. Page 16 The time interval for the This change increases the Section 3.4.2.C.(2) liquid release calculation descriptive accuracy of term 6 ty, was specified the ODCM.

to be in units of hours.

The units ere not previously specified.

(21)

1 4

e TABLE 5 (Continued)

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT j EFFLUENT AND WASTE DISPOSAL i SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987

SUMMARY

OF CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL CHANGE REVISION 5 DESCRIPTION OF CHANGE AFFECT ON ,

NO. PAGE/SECTION (JUSTIFICATION) ACCURACY / RELIABILITY l ll l

4. Page 18 The DOSE PROJECTION - This change increases the Section 3.5.2 DETERMINATION OF NEED T0 technical accuracy of the OPERATE LIQUID RADWASTE ODCM.

TREATMENT SYSTEM section was revised. Under the calculation methodology a statement was added which noted that other age groups and/or critical organs may be used if previous dose calculations indicate that the adult is not the critical age group and the liver is not the critical organ.

5. Pages 21, 22, 23 The DOSE PROJECTION - This change increases the Section 3.5.2.C DETERMINATION OF NEED T0 technical accuracy of the OPERATE LIQUID RADWASTE ODCM. l TREATMENT SYSTEM section 1 was revised. A methodology was added to perform liquid dose projections for continous releases, dose l projections for continous releases was not specifically addressed in previous revisions.
6. Page A-2 The Appendix A index was This change does not effect revised to reflect new the accuracy of the ODCM.

page numbers.

i (22) 1

TABLE 5 (Continued)

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987

SUMMARY

OF CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL CHANGE REVISION 5 DESCRIPTION OF CHANGE AFFECT ON NO. PAGE/SECTION (JUSTIFICATION) ACCURACY / RELIABILITY

7. Page 86 The table of contents for This change does not Table L-4 index Table L-4 was revised to effect the accuracy of the reflect additions to the ODCM.

table, i

I

8. Pages A-87, A-88, Table L-4.1, LIQUID DOSE This change increases the A-89, A-90 FACTOR DETERMINATION was descriptive accuracy of Table L-4.1 revised. The derivation the ODCM.

of liquid dose factors for all pathways used in dose calculations were added.

The derivation of liquid dose factors for the potable water, fresh water fish, lake shoreline deposits, swin ing and boating pathways were added to Table L-4.1.

9. Pages A-94, A-95 Table L-4.4 was added to This change increases the Table L-4.4 the ODCM. This table descriptive accuracy of lists the dose conversion the ODCM.

factors for the swining and boating pathways.

10. Page A-96 A Table of contents for This change does not Table L-5 Table L-5 was added. effect the accuracy of the ODCM.

(23)

TABLE 5 (Continued)

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 JUNE 1987

SUMMARY

OF CHANGES TO THE OFFSITE DOS 2 CALCULATION MANUAL l

CHANGE REVISION 5 DESCRIPTION OF CHANGE AFFECT ON NO. PAGE/SECTION (JUSTIFICATION) ACCURACY / RELIABILITY

11. Page B-90 The table of contents for This change does not Table G-7 Table G-7 was revised to effect the accuracy of the reflect additions to the ODCM.

table.

12. Page B-91 The identification of This change does not Table G-7.Al Table G-7.1, DERIVATION OF effect the accuracy of the (Pg) VALUES, was changed ODCM.

to G-7.lA derivation of (P1 ) values.

13. Pages B-92, B-93, Table G-7.lB, DERIVATION This change increases B-94, B-95, B-96, OF GASEOUS DOSE FACTORS the descriptive accuracy B-97 (Pg ) was added. This of the ODCM. l Table G-7.lB table contains the l derivation of iodine and l particulate dose factors I for the inhalation, ground plane disposition, fresh fruits and vegetables, stored fruits and vegetables, meat (contaminated forage),

cows milk and goats milk pathways.

14. Pages C-1, C-2 A header for Appendix C, This change does not Meteorological Data was effect the accuracy of the added and the index for ODCM.

Appendix C was revised to reflect pa8e changes. l (24) i

TABLE 5 (Continued)

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987

SUMMARY

OF CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL CHANGE REVISION 5 DESCRIPTION OF CHANGE AFFECT ON NO. PAGE/SECTION (JUSTIFICATION) ACCURACY / RELIABILITY I l;

15. Page C-5 Table M-4 was added to the This change increases the )

Table M-4 ODCM. This table lists descriptive accuracy of the j the dispersion parameter ODCM.

description and appropriate i critical receptors. l l

16. Page E-2 A table of contents was This change does not effect Appendix E added for appendix E. the accuracy of the ODCM.
17. Page F-2 A table of contents was This change does not effect Appendix F added for Appendix F. the accuracy of the ODCM. l
18. Page F-7 Figure F-2 was upgraded This change does not effect 1 Appendix F so that the map was more the accuracy of the ODCM.

legible.

19. Page G-2 A table of contents was This change does not effect Appendix G added for Appendix G. the accuracy of the ODCM.

l

20. Page H-2 A table of contents was This change does not effect i Appendix H added for Appendix H. the accuracy of the ODCM.
21. Page I-2 A table of contents was This change does not effect Appendix I added for Appendix 1. the accuracy of the ODCM. l l

l l

l l

l (25) l

TABLE 6 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987 DEVIATIONS FROM THE REQUIRED ENVIRONMENTAL SAMPLING SCHEDULE EXCEPTION TO THE PROGRAM

1. The air sampling pump at the R-3 off-site Environmental I Sampling Station was inoperable from April 14, 1987 (1550 hours0.0179 days <br />0.431 hours <br />0.00256 weeks <br />5.89775e-4 months <br />) to April 16, 1987 (0919 hours0.0106 days <br />0.255 hours <br />0.00152 weeks <br />3.496795e-4 months <br />). Inoperability was caused by a pump electrical failure.

l

)

)

l (26) i

1 TABLE 7 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987 REPORT NOTES

1) Table 2A, Section B. Tritium and Table 2B Second Quarter liquid Tritium, Strontium-89, Strontium-90 and Iron-55 values were calculated from First Quarter Sample Data.

First Quarter Sample Data for Strontium-89 and Strontium-90 were LLD values.

2) If actual sample data significantly alters the report release l concentrations and percent of allowable release limits the report will be revised and redistributed.

l l

I l

l l

l l

l l

l l

l (27)

ATTACHMENT 1 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1987 - JUNE 1987 ODCM Revision 5 Attached are the pages affected by revision 5 of the off-site Dose Calculation Manual (ODCM).

(28)

I NEW YORK POWER' AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT RADIOLOGICAL AND ENVIRONMENTAL SERVICES DEPARTMENT PROCEDURE NO.: N/A

. TITLE: OFFSITE DOSE CALCULATION MANUAL (ODCM)*

PORC Review No./Date Meeting No. [f 7-6 37 Date $ 6 f7 Approved By: g c/k ad Resident _ Manager Approved By: A a -

Radiolo h al and Environ d tal Services Superintendent

-Page No.: 11 2 3 4 5 6 7 8 9 10 11 12 13 14 15 Rev. No.: 52 2 2 2 2 2 4 2 5- 5 5 5 4 4 5 Page No.: 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 Rev. No.: 5 2 5 3 3 5 5 5 4 2 4 4 4 4 4 Page No.: 31 32 33 34 35 36 37 38 39 40 41 42 43 44= 45 Rev. No.: 4 3 4 4 4 4 4 2 4 4 4 4 4 4 4 Page No.: 46 47 48 49 50 51 A-1 A-2 A-3 A-4 A-5 A-6 A-7 A-8 A-9 Rev. No.: 5 5 5 4 4 2 2 5 4 2 2 2 2 2 2 Page No.: A-10 A-11 A-12 A-13 A-14 A-15 A-16 A-17 A-18 A-19 A-20 A-21 Rev. No.: 2 '2 2 2 2 2 2 2 2 2 2 2 Page No.: A-22 A-23 A-24 A-25 A-26 A-27 A-28 A-29 A-30 A-31 A-32 A-33 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2' Page No.: A-34 A-35 A-36 A-37 A-38 A-39 A-40 A-41 A-42 A-43 A-44 A-45 Rev No.: 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: A-46 A-47 A-48 A-49 A-50 A-51 A-52 A-53 A-54 A-55 A-56 A-57 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: A-58 A-59 A-60 A-61 A-62 A-63 A-64 A-65 A-66 A-67 A-68 A-69 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: A-70 A-71 A-72 A-73 A-74 A-75 A-76 A-77 A-78 A-79 A-80 A-81 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: A-82 A-83 A-84'A-85 A-86 A-87 A-88 A-89 A-90 A-91 A-92 A-93 Rev. No.: 2 2 2 2 5 5 5 5 5 2 2 2 Page No.: A-94 A-95 A-96 A-97 A-98 A-99 B-1 B-2 B-3 B-4 B-5 B-6 B-7 Rev. No.: 5 5 5 2 2 2 2 5 2 2 2 4 4 Page No.: B-8 B-9 B-10 B-11 B-12 B-13 B-14 B-15 B-16 B-17 B-18 B-19 Rev. No.: 4 2 2 2 2 2 2 2 2 2 2 2 Page No.: B-20 B-21 B-22 B-23 B-24 B-25 B-26 B-27 B-28 B-29-B-30 B-31 Rev. No.: 2 2 2 2 2 2 2 2 2 2- 2 2 Page No.: B-32 B-33 B-34 B-35 B-36 B-37 B-38 B-39 B-40 B-41 B-42 B-43 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 .2 Page No.: B-44 B-45 B-46 B-47 B-48 B-49 B-50 B-51 B-52 B-53 B-54 B-55 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: B-56 B-57 B-58 B-59 B-60 B-61 B-62 B-63 B-64 B-65 B-66 B-67 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 l

Page No.: B-68 B-69 B-70 B-71 B-72 B-73 B-74 B-75 B-76 B-77 B-78 B-79 l Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: B-80 B-81 B-82 B-83 B-84 B-85 B-86 B-87 B-88 B-89 B-90 B-91 Rev. No.: 2 2 2 2 2 2 2 2 2 2 5 5 Page No.: B-92 B-93 B-94 B-95 B-96 B-97 B-98 B-99 B-100 B-101 B-102 Rev. No.: 5 5 5 5 5 5 2 2 2 2 2 Rev No. 5 Date 03/87

~87@Ys#425m/4y

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

RADIOLOGICAL AND ENVIRONMENTAL SERVICES DEPARTMENT PROCEDURE NO.: N/A TITLE: OFFSITE DOSE CALCULATION MANUAL-(ODCM)*

PORC Review No./Date Meeting No. U-o37, Date3/,%,',(([. ,

Approved By: j y oo, _

-- ~~

Resident Manager Approved By: [ /

RadiologicalandEnvirdental-Services Superintendent Page No.: B-103 B-104 B-105 B-106 B-107 C-1 C-2-C-3 C-4 C-5 C-6 D-1 Rev. No.: 2 2 2 2 2 5 5 2 2 2 5 2 Page No.: D-2 D-3 D-4 D-5 D-6 D-7 E-1 E-2 E-3 E-4 E-5 E-6 E-7 E-8' Rev No.: 2 2 2 2 2 2 2 5 2 2 2 2 2' 2 Page No.: E-9 E-10 E-11 E-12 F-1 F-2 F-3 F-4 F-5 F-6 F-7.F-8 F-9 Rev. No.: 2 2 2 2 2 5 2 4 4 2 5 2 2 Page No.: F-10 G,-1 G-2 G-3 H-1 H-2 H-3 H-4 H-5 H-6 H-7 H-8 H-9 Rev No.: 2 2 5 2 2 5 4 4 4 4 4 '4 4 Page No.: H-10 I-1 1-2 I-3 I-4 I-5 I-6 I-7 I-8 I-9 I-10 Rev. No.: 2 2 5 2 2 2 2 2 2 2 2 Rev No. 5 Date 03/87

I 0FFSITE DOSE CALCULATION MANUAL (ODCM)*

Table of Contents Page 1.0 Introduction 1 l 1.1 Purpose 1 1.2 Methodologies and Parameters 1 j 2.0 GLOSSARY OF TERMS 2 j 3.0 LIQUID EFFLUENT METHODOLOGY 6 3.1 Applicable Site Characteristics 6 3.2 10 CFR 20 MPC Limits-Determination of Fraction (FL) of Release Limits and Minimum Required Dilution 6 l 3.3 Determination of Set Points for Radioactive Liquid l

Effluent Monitors 9 )

3.4 Dose Determination for Radioactive Liquid Effluents 12 3.5 Dose Projections-Determination of Need to Operate Liquid Radwaste Treatment System 18 4.0 GASEOUS EFFLUENT METHODOLOGY 24 4.1 Gaseous Waste Streams 24 4.2 Data Requirements for Gaseous Effluent Calculations 24 {

4.3 Instantaneous Release Rate and Set Point Determination 25 4.4 Dose Determination for Radioactive Gaseous Effluents 36 4.5 Dose Projection-Determination of Need to Operate Offgas Radwaste 46 5.0 40 CFR 190 DOSE EVALUATION 49 5.1 Evaluation Bases 49 5.2 Doses from Liquid Releases 49 5.3 Doses from Atmospheric Releases 50 j 5.4 Doses from Direct Radiation 50 l

6.0 REFERENCES

50 l 6.1 Background References 50 6.2 Essential References / Controlled Documents 50 7.0 APPENDICES 51 l

l Rev. No. 5 Date 03/87 Page i of ODCM j

1 3.3 Determination of Setpoints for Radioactive Liquid Effluent Monitors 3.3.1 Requirements Technical Specifications Appendix B Section 2.1.a re-quires that the radioactive liquid effluent monitor be operable and set to initiate an alarm and/or trip in the event that the limits of Technical Specifications Appen-dix B Section 2.2 are approached. The alarm and/or trip set points shall be determined and adjusted by the methodology which follows. The set point values should be applied above normal background levels.

The alarm set point for the liquid effluent radiation monitor is derived from the concentration limit provided in 10 CFR 20 Appendix B Table II Column 2 applied at the unrestricted area boundary where the discharge tunnel flows into Lake Ontario.

3.3.2 Methodology The alarm set points do not consider dilution, disper-  !

sion, or decay of radioactive material beyond the unre-stricted area boundary 1.e., the alarm setpoints are I based on a concentration limit at the end of the dis-charge tunnel.

3.3.3 Radwaste Liquid Effluent Monitor

a. A sample of each batch of liquid radwaste is analyzed for I-131 and other principal gamma emitters prior to release. The fraction F of 10 CFR 20 MPC limits and the minimum required diltItion factor to achieve F =1 is determined in accordance with the preceding sebtion for the activity to be released.
b. A conservative alarm and/or trip setpoint (pCi/ml) is determined in accordance with the following equation.

S = 0.5 x pb-Where:

S = The alarm and/or trip set point above background corresponding to the limiting concentration of undiluted liquid effluent (uCi/ml). '

O.5 =

Conservatism factor to account for releases from multiple points.

C = Total gamma isotopic or gross activity concen-tration (uCi/ml) of sample as determined in the laboratory.

Rev. No. 5 Date 03/87 Page 9 of ODCM

l F =

The fraction of 10 CFR 20 MPC limits for unre- i L

stricted areas resulting from the release source being discharged.

1 3.3.3.1 Calculating Process i The following section provides a procedure for i determining the radwaste liquid effluent monitor set point. Typical parimeter values are used for illustration.

a. Determine C.from laboratory analysis of the liquid effluent sample. For the purpose of'this example, assume a value of 3E-5 uCi/ml -in a- gross i beta-gamma activity analysis. I
b. Determine f from pump curves and current plant 4 operating configuration. . A typical value is )

3.78E+5 gpm. j

c. Determine the minimum required dilution factor in accordance with equation 3-2.

E C 2 "

f Lk i=1 (MPC) min l For a gross activity determination, the unidentified MPC of 3E-8 uCi/ml is' used. I Therefore

[f 1 min

= 3E-5/3E-8 = 1,000

)

d.

Calculate the required f at the liquid effluent monitor location. Atypibalvalueis100gpm.

e. A typical value of the dilution. factor from current plant operating conditions is:

(3.78E+5 gpm)/100 gpm = 3,780, which is

>1,000. Therefore the release can be made at the current release rates and concentrations maintained within the 10 CFR 20 limits.

f. Determine F , the fraction of 10 CFR 20.MPC limits resulting fhom the release source being discharged q at a dilution factor of 3,780, in accordance with i equation 3-1.

]

l Rev. No. 5 Date 03/87 Page 10 of ODCM i i

E C F 1 f h" f

  • i=1 3

(MPC)1

= (100/3.78E+5) x (3E-5/3E-8)

= (2.65E-4) x 1,000

= 0.265

g. The liquid effluent monitor set point, S in uCi/ml, from equation 3-3 is:

Eq. 3-3.a S = 0.5 x hL

= 0.5 x [(3E-5)/(0.265)]

= 5.66E-5 uCi/ml

h. Appropriate calibration factors are applied to this limiting concentration determined in step 3.3.3.g to determine an effluent monitor alarm potentiometer set point.

3.3.4 Service Water Liquid Effluent Monitor

a. A conservative alarm setpoint (cps) for the service water liquid effluent monitor is determined in accordance with the following methodology:

E DF = 2 Eq. 3-3.b l f I l

where:

DF = the dilution factor which results from the flow rate in the discharge structure in gpm divided by the undiluted release rate of the effluent release source.

fl= the undiluted release rate of the effluent source measured at the service water liquid effluent monitor (gpm).

the discharge structure flow rate in g7m f

2= (summation of circulating water pumps minus the flow redirected for tempering (gpm).

SP = 0.5 x MPC f x DF + Bkg Eq. 3-3.c Eff Rev. No. 5 Date 03/87 Page 11 of ODCM

I l

where:

SP = set point of liquid effluent monitor in cps. 3 l

0.5 = conservatism factor to account for releases I l

from multiple aoints or a reduction in the DF value due to changes in discharge canal flow.

MPC 1 = maximum permissible concentration of radio- q nuclides in service water (see section b  ;

below).

Eff = efficiency of the liquid effluent monitor in l uCi/ml/ cps.  !

Bkg = normal monitor background (cps).

I

b. Those nuclides present in previous batch releases from 1 the liquid radwaste effluent system, nuclides present in historical Semi-annual Radioactive Effluent Release ,

Reports or those nuclides present in the service water {

system may be used to calculate the MPC value. Other  !

values for MPC may be used based on pfant conditions j (i.e: in the bvent of known leakage into the RBCLC J I

system).

3.4 Dose Determination for Radioactive Liquid Effluents 3.4.1 Annual Dose Assessment-Radioactive Effluent Release Re-port Submittal

a. Requirements i Technical Specifications Appendix B Section 7.3 re-quires a semi-annual Radioactive Effluent Release Report to be submitted that includes an assessment of the radiation doses to the public due to the radio-active liquid and gaseous effluents released from the unit during the previous calendar year. The dose assessment required by this report is due annually 90 days after January first of each year.
b. Methodology This section provides the methodology to calculate the doses to all age groups and organs from all radionu-clides identified in the liquid effluents. The method is based on the methodology suggested by NUREG-0133 October 1978 Sections 4.3 and 4.3.1. The site-related dose factors for all viable pathways are listed in Appendix A Tables L-2 and L-3. Table L-3 dose factors are compiled by age groups, for all organs and radio-nuclides common to a BWR environment.

Rev. No. 5 Date 03/87 Page 12 of ODCM

1 1

1 Where:

D = Dose commitment in mrem received by organ T f'

of age group (to be specified) from release time interval at 1' ~

A = The composite dose factor for the fresh water f'

fish pathway and potable water pathway for nuclide (i) for organ T of age group (to be specified). The A values listed in Ap-pendix A Table L-2f In this manual have the units mrem-ml/uCi-hr.

aty = The number of hours over which the release occurs.

l Qf y = The total quantity of nuclide (i) released in uC1.

during the time period aty l

(DF)y =during The total volume of dilution that occurred the release time period t (i.e., the circulating water flow multipik.ed by the time) in milliliters. l (2) Limited Analysis Approach Based on the radionuclides distribution typical in radioactive effluents at JAFNPP, the calcu-lated dose to individuals are dominated by the radionuclides, Cs-134, Cs-137, 2n-65, Mn-54 and 1 '

Co-60. These nuclides typically contribute over i

95 percent of the total body dose and over 95 percent of the liver dose, which is the critical organ. Therefore, the dose commitment due to radioactivity in liquid effluents may be reason-ably evaluated by limiting the dose calculating process to these radionuclides for the adult i total body and adult liver dose. To . allow for 1 any unexpected variability in the radionuclides i distribution, a conservatism factor of 0.9 is introduced into the equation. After calculating the dose based on these five nuclides, the l cumulative dose should therefore be divided by O.9. (Refer to Appendix D for a detailed eval-uation and explanation of this limited analysis approach).

If the limited analysis approach is used, the calculation should be limited to the adult total body dose and adult liver dose from the fish and potable water pathways. Only the five previous-ly specified nuclides need be evaluated.

l Rev. No. 5 Date 03/87 Page 15 of ODCM

I (3) Approach Selection Criteria The limited analysis approach fully satisfies the requirements specified in step 3.4.2.a and 4 can thus be.used at all times. The more general l approach may be used for more refined calcula-tions.

c. Calculating Method The methodology that follows is a step-by-step break-down to calculate doses based on equation 3-5. If the limited. analysis approach is . used, the calculation should be limited to the adult total body dose and q i adult liver dose from the fish and. aotable water .

previousf.y pathways. Only' the five specified  !

radionuclides need to be evaluated.

NOTE: Table 3.4.2 provides a convenient form for com-piling the dose accounting information. ,

(1) Determine the time interval at y over ' which the release took place in hours. l l

(2) Obtain f the time period at 1 for the release (DF)dce sou s)(or of interest. DF is the total volume of dilution, (i.e. the circulating water flow multiplied by the time) in milliliters.

(3) Obtain Ql1 (uci) for nuclide (i) .for the time period at y (4) Obtain A from the appropriate Liquid Dose FactorTA5le: Appendix A Table L-2 for the fish and potable water pathways: Appendix A Table L-3 for all other pathways.

(5) Solve for Dose (1)

D "

Ay ,. aty .

Qy t

it (DF)y (6) Repeat steps 3.4.2.c.(3) through 3.4.2.c.(5) for each nuclide reported and each organ required.

If the limited analysis method is used, limit the radionuclides to-Co-60, Mn-54, Zn-65, Cs-134 and Cs-137 and determine the adult total- body dose and the adult liver dose.

(7) Sum the D vaines to obtain the total dose to organ frod'the' fish.'and potable water pathways.

If the limited analysis method is being used, divide the cumulative dose by a conservatism.

factor of 0.9 -to account. for any unexpected variability in radionuclides distribution.

Rev. No. 5 Date 03/87 Page 16 of ODCM 1

l _ _ - _ _ _ _ _ . - - _ _ - - _ _ _ _ _ _ _ - - - -

3.5 Dose Projections - Determination of Need to Operate Liquid l Radwaste Treatment System l l

3.5.1 Requirements l l

Technical Specifications Appendix B Section 2.4 requires I that appropriate subsystems of the liquid radwaste treat-ment system be used to reduce radioactive material in un-treated liquid effluents when the projected monthly dose due to liquid releases to unrestricted areas, when aver-aged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ. Doses are to be projected at least once per month.

3.5.2 Calculating Methodology The method is based on total body dose and critical organ dose (liver) as calculated in step 3.4.2. The adult is j normally the critical age group to be used for the dose  ;

proj e c tion . Other age groups and/or critical organs '

maybe used if previous dose calculations indicate that the adult is not the critical age group and the liver is not the critical organ.

The following calculating methodology is provided for performing this dose projection.

a. Monthly Dose Projection Each month the expected dose to man shall be gro-jected. Projections shall be based on historica: or i prior month dose / Curie and historical or prior month concentration conversion factors. The historical factors are calculated from historical release data for both a refuel outage year and a non-refuel outage year. The current historical factors are on file within the RES Department.

(1) Each month make an estimate of the volume of liquid radwaste to be discharged during that month. The following variables should be con-sidered in estimating radwaste volumes to be released:

(a) Projected plant operational status (run, shutdown, refuel, etc.).

(b) Status of radwaste treatment equipment.

Equipment which is inoperable, such as the waste concentrator, should be factored into the source term or volume of liquid waste to be discharged from the plant.

(c) Use of the plant laundry (increased use of laundry due to plant maintenance, etc.)

RG% W@o _____5_____ Dego 0318_7_ Parse 18 of ODCM

(3) Maintain a running total of the Curies released during the past 30 days. Add to this the Curie content of the current batch to be released (31 day total).

(4) Multiply the 31 day total from . step (3), above by the dose per Curie conversion factor calcu-lated in step (1), above. This yields the 31 day total dose projected for the release of the current batch.

(5) If the calculated dose is greater than 0.06 mrem to the total body or 0.2 mrem to the liver, the appropriate subsystems of the liquid radwaste system shall be used to reduce the radioactivity levels prior to release,

c. Continuous Liquid Release Dose Projections Each month that a continuous liquid release is in progress, or is anticipated, the expected dose to man can be proj ected. The proj ection shall be based on historical, prior month or current dose / Curie and nuclide concentration (Curie / gallon) conversion
factors. The historical conversion factors are l calculated from prior releases. The prior month conversion factors are calculated from the prior month continuous liquid releases if such releases occurred.

Current conversion factors are calculated from samples obtained at or near the beginning of the dose projec-tion month.

l (1) Determine which dose /Ci and Ci/ gal conversion factors should be used. Historical conversion factors can be used. Prior month or current conversion factors should be used if they are more representative of current release condi- l tions.

l (a) The current month Ci/ gal concentration is l calculated by using current sample results for radionuclides concentration and con-verting the results to Ci/ gal.

(b) The current month estimated Curie's released is calculated by multiplying the concentration by the known or expected flow rates for the effluent pathway times the period of release.

(c) Using the dose assessment methodology specified in section 3.4, calculate the dose to man using known or estimated flow l rates and dilution factors.

Rev. No. 5 Date 03/87 Page' 21 of ODCM l

I l

I (d) Divide the dose calculated in section (b) above by the estimated number of Curies to be released. This calculation yields a dose per Curie conversion factor for the l current release parameters. j (e) The prior month dose /Ci conversion factor is calculated by obtaining the results of the prior month adult total body and adult  !

liver dose calculation. j (f) Divide this dose by the total number of Curies released from the plant via contin-uous releases during this same time period. This calculation yields a dose per Curie conversion factor for the most recent prior calendar month.

(g) The prior month Ci/ gal concentration fac-tor is calculated by obtaining the total number of Curies released from the plant via continuous releases during the prior month. Divide the Curie total by the j total number of gallons of waste dis-charged during this same time period.

This calculation yields the Ci/ gal concen- l tration conversion factor for the most j recent month.

(2) Multiply the estimated volume of continuouc ,

liquid effluent to be discharged, by the histor-ical prior month or current dose /Ci and Ci/ gal 4 conversion factors. This calculation yields a dose estimate to the adult total body and adult liver for the projected month.

(a) Ty xC g xD etb = TDtb (Adult Total Body Dose)

(b) Ty xC g

xD el

= TD 1 (Adult Liver Dose)  !

Where:

T V

= Total volume of radwaste to be dis-charged during the month in gallons (estimated)

C = Curies per gallon conversion factor i 8 historical or prior month) i l

1 Rev. No. 5 Date 03/87 Page 22 of ODCM

. _ _ _ _ __-_____-__-_D

D = Dose per Curies. adult total body (his-etb torical or prior month).in mrem TD = Total dose for adult total body in mrem-tb D = Dose per Curie adult liver (historical el or prior month) in mrem TD y = Total dose for adult liver in mrem If the calculated dose is greater than 0.06-mrem to the total' body or 0.2 mrem to the liver or other critical organ. Efforts should be made to reduce the effluent release rate or concentra-tion. The dose contribution from liquid batch l

releases (proj ec ted) should be' evaluated in I addition to continuous releane dose.

l-l 1

Rev. No. 5 Date 03/87 Page 23 of ODCM

Section 3.4.a.1 for radioiodines and particulate by only evaluating the infant's thyroid dose due to the release of radioiodines via the contaminated l forage / cow / goat / milk pathway.

The calculating method to be used includes a conservatism factor of 0.8 which assures that the calculated dose is always greater than or equal to the actual dose despite

,I possible atypical distributions of radio-nuclides in the gaseous effluent. The simplified dose equation reduces to:

Eq.4-28 l I

Dt =

(3.17E-8 (D7Q)iod nes R1 ,x Qt ) / 0.8 (b) Approach Selection Criteria The limited analysis may be used in all l cases to demonstrate compliance with the I dose limit of Technical Specifications )

Appendix B Section 3.4.2.1 (7.5 mrem /qt')

for radiciodines and particulate.

However, for the dose assessment included in the semi-annual Radioactive Effluent )

Release Report, doses will be evaluated l for all designated age groups and organs via all designated pathways from radio-iodines and particulate measured in the gaseous effluents according to sampling and analyses required by Technical Speci-fication.

4.5 Dose Projections - Determination of Need to Operate Offgas Radwaste Treatment System 4.5.1 Requirement Technical Specifications Appendix B Section 3.6.a re-quires that the Offgas Radwaste Treatment System be used to reduce radioactive material in waste prior to dis-charge with the offgas treatment system not in use, doses due to gaseous releases from the site will be projected monthly.

l Rev. No. 5 Date 03/87 Page 46 of ODCM

'4.5.2 Methodology The following calculation method is provided for deter-mining the projected doses.

PD = 31 x D x 1.2. Eq. 4-29 Y g- Y v g < s PD = 31 x D x 1.2 Eq. 4-30 8 g-- 8 PD 7gp = xD 7gp x 1.2 Eq. 4-31 W sre:

PD = Projected air dose due to noble gas gamma radi-7 ation during the current month (mrad) from all routine effluent pathways PD = Projected air dose due to noble gas beta radia-8

, tion during the current . month (mrad) from all i routine effluent pathways PD ygp = Projected dose to any organ due to Tritium Iodine-231, Iodine-133 and particulate with half-lives greater than 8.5 days (mrem) 31 - Maximum number of days in a month X = Number of days to date during the current month i D = Air dose due to noble gas gamma radiation'during  ;

Y the month-to-date (mrad)

Dg = Air dose due to noble gas beta radiation during the month-to-date (mrad)

D I&P1

= Organ dose due to Iodines and . Particulate during the month to date (mrem) 1.2 = Conservatism factor to provide a margin for

changes in mixture and operational line up, etc.

A formal dose projection would be based on the latest re-sults of the monthly calculations of the gamma air dose ]

(step 4.4.2.a), the beta air dose (step 4.4.2.b), and the i organ dose due to Tritium, Iodines 'and particulate  !

greater than 8.5 days (step 4.4.2.c) . The doses calcu-lated would -be ~ divided by the number of days that the ,

plant was operational during that month. The ' per-day l doses (gamma and beta) would be multiplied by the number -

of days the plant is projected to be operational during  ;

the coming month. The product is the projected dose for the coming month. Its value may need to be adjusted to  !

account for any changes in operating conditions- that could significantly alter the actual releases, such as  !

failed fuel.  ;

Rev. No. : 5 Date 03/87 Page '47 'of ODCM I

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a. Limited Analysis Approach and Selection _ Criteria A .st'mpler . approach l ' a linear extrapolation of the l

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4 APPENDIX A LIQUID DOSE CALCULATION DATA I

TAB? L TITLE hAGE l L-1 Unrestricted Area MPC's A-3 L-2 Dose Factors, Limited Analysis Approach A-4 .

L-3 Dose Factors, All Pathways A-13 L-4 Dose Factor Derivation A-86 L-5 JAF Liquid Effluent Pathway Parameters A-96 I

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4 Rev. No. 5 Date 03/87 Page A-2 of ODCM

TABLE L-4 Dose Factor (At) Derivation L-4.1 Dose Factor (At) Derivation L-4.2 Calculation of A g Liquid Dose Factors - Input Data L-4.34 Calculation of (Ab) Liquid Dose Factors Selected Pathway Computations 1

L-4.3B Calculation of (AtT) Liquid Dose Factors - Usage Factors by Pathway and Age Group L-4.4 Dose Conversion Factors for Swimming and Boating l

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Rev. No. 5 Date 03/87 Page A-86 of ODCM

TABLE L-4.1 Liquid Dose Factor (Af) Derivation For purposes of calculating the dose contribution to organs of various receptor age groups, a pathway dose factor A4 is used for each nuclide i. This dose factor embodies pathtray transfer factors (e.g. bioaccumulation factors), pathway usage factors, organ dose conversion factors, and dilution factors for the points of pathway origin. The pathway dose factor A fT may be expressed as:

A = Ko (Uw/Dw + Uf BFi/Df + ZWTi Ush/Dsh (1-exp -AiTb) +

tT Us/Ds + Cf Ub/Db)DFi (L-4.1)

Where:

A t'

= is the composite dose parameter for the total body or organ of an age group for nuclide, i, for all appropriate pathways, mrem /hr per uCi/ml.

Ko = is a unit conversion factor.

Uw = water consumption rate for age group of interest (from Reg. Guide 1.109, Table E-5).

Uf = fresh water fish consumption rate for age group of interest (from Reg. Guide 1.109, Table E-5).

{

Ush = duration of time an individual is located on the beach (from Reg. Guide 1.109, Table E-5).

Ub = duration of time an individual is boating. 1 1

i Us = duration of time an individual is swimming.

Dw, = mixing ratio which reflects the dilution from the point Df, of release to the nearest potable water intake (Dw),

Dsh, nearest point assumed for catching fish (Df), nearest Db, point for shoreline deposit (Dsh), nearest point assumed Ds for boating (Db), and nearest point assumed for swimming (Ds).

BFi = bioaccumulation factor for nuclide, 1, in fresh water fish, pCi/kg per pCi/1, from Table A-1 of Reg. Guide 1.109.

Dfi = dose conversion factor for nuclide, i, for organ for age group of interest. Used to calculate the radiation dose from an intake of a radionuclides or the radiation dose from an external exposure of a radionuclides.

Rev. No. 5 Date 03/87 " age A-87 of ODCM

1 1

Ti = is the radiological half-life of nuclide, i, in days.

Ai = is the radiological decay constant for nuclide, i, in secs. j i

W =

is the shoreline width factor. l l

Tb = the period of time for which sediment or soil is exposed to the contaminated water.

Kc = assumed transfer constant from water to sediment, in liters /kg per hr. j Ms = mass of sediment, in Kg/m2 of surface.

Z = Kc x Mc x (24/.693), in 1 per m2-day.

Cf =

correction factor for boating, 0.5. DFi for swimming and I boating assumes that exposure is from a 4 n geometry. I This factor corrects the exposure from boating to a 2 n geometry.

Example calculations:

1. Potable Water For the potable water pathway, the following usage factors are equal to zero: Uf, Ush, Us, and Ub . For the potable water pathway equation L-4.1 reduces to the following:

A ty = Ko (Uw/Dw) DFi For Co-60, total body dose factor for an adult from exposure l from liquid effluents:

1 DFi =

4.72E-06 mrem /pCi (Reg. Guide 1.109, Table E-11)

Uw = 730 liters /yr.

Dw =

165 Ko = 1.14E5 yr-pCi-ml per pCi-hr-1 These values will yield an A factor of 2.38 mrem-m1 per pCi-hr as listed on page A-5. t'

2. Fresh Water Fish For the fresh waster pathway, the following usage factors are equal to zero: Uw, Ush, Us, and Ub. For the fresh water pathway equation L-4.1 reduces to the following:

A1 ,f = Ko (Uf BFi/Df)DFi For Co-60, total body dose factor for an adult from exposure from liquid effluents:

Rev. No. 5 Date 03/87 Page A-88 of ODCM

DFi =

4.72E-6 mrem /pCi (Reg. Guide 1.109, Table E-11)

Uf = 21 Kg/yr.

Df = 12 BFi = 50 pCi/kg per pCi/1 Ko = 1.14E5 yr-pCi-ml per uCi-hr-1 1

These values will yield an A f actor of 47.1 mrem-ml per pCi-hr as listed on page A-9.tT

3. Lake Shoreline Deposits For the lake shoreline deposit pathway, the following usage factors are equal to zero: Uw, Uf, Ub and Us. For the lake .

shoreline deposit pathway equation L-4.1 reduces to the i following:

Ai sh = KoZ (WTi Ush/Dsh) (1-exp -AiTb) DFi For Co-60, total body dose factor for an adult from exposure I from liquid effluents-  !

DFi = 1.70E-8 mrem /hr per pCi/m2 (Reg. Guide 1.109, Table E-6)

Ush =

12 hrs /yr. .

Dsh = 18 W = 0.30 Ti = 1 924E3 days l Tb = 15 years or 4.73E8 sec.

Ko =

1.14E5 yr-pCi-ml per uCi-hr-1 Ms = 40 Kg/m2 2 = 100 1 per m2/ day A1 =

4.2E-9 sec.

These values will yield an A f actor of 64.3 mrem-m1 per pCi-hr as listed on page A-14.t'

4. Swimming For the swimming pathway, the following usage factors are equal to zero: Uw, Uf, Ush, and Ub. For the swimming pathway equation L-4.4 reduces to the following:

A irs = Ko (Us/Ds)DFi For Co-60, total body dose factor for an adult from exposure from liquid effluents:

DFi = 4.6E-6 mrem /hr per pC1/1 (See Table L-4-2)

Us = 100 hrs /yr.

Ds = 18 Ko = 1.14E5 yr-pCi-m1 per uCi-hr-1 These values will yield an A factor of 2.92 mrem-ml per uCi-hr as listed on page A-18.t' Rev. No. 5 Date 03/87 Page A-89 of ODCM

i.

5. Boating For the boating pathway, the following usage factors are equal to zero: Uw, Uf, Ush and Us. For the boating pathway equation L-4.1 reduces to the following:

Af ,3 = Ko Cf(Ub/Db) DFi For Co-60, total body dose factor for an adult from exposure i from liquid effluents: )

DFi = 4.6E-6 (See Table L-4-4) l Ub = 500 hrs /yr. ,

Db = 12 )

Cf = .5 K; = 1.14E5 yr-pCi-m1 per pCi-hr-1 These values will yield an A factor of 10.9 mrem-ml per pCi-hr as listed on page A-22.t*

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Rev. No. 5 Date 03/87 Page A-90 of ODCM L_ _ _ _ _ _ _ _ _ _ _ _ _ _

T.ABLE L-4.4 DOSE CONVERSION FACTORS FOR SWIMMING AND BOATING Swimming and Boating Dose Factors (mrem /hr)/(pci/1)

Isotope Total Body

  • H-3 0 C-14 0 Na-24 7.8E-06 P-32 6.4E-09 Cr-51 5.2E-08 l Mn-54 1.5E-06 l Mn-56 3.2E-06 l Fe-55 6.4E-11 l Fe-59 2.2E-06 Co-58 1.8E-06 i Co-60 4.6E-06 i Ni-63 0 Ni-65 1.0E-06 Cu-64 3.7E-07 l Zn-65 1.1E-06 l Zn-69 1.6E-09 Br-83 1.7E-08 Br-84 3.5E-06 Br-85 1.4E-08 Rb-86 1.7E-07 Rb-88 1.2E-06 Rb-89 4.5E-06 i Sr-89 4.6E-09 Sr-90 5.4E-10 l Sr-91 1.9E-06 Sr-92 2.6E-06 Y-90 1.3E-08 Y-91m 0 Y-91 6.7E-09 Y-92 4.6E-07 Y-93 1.9E-07 Zr-93 0 Zr-95 1.5E-06 Zr-97 1.5E-06 Nb-93m 0 Nb-95 0 Nb-97 1.2E-06 Mo-99 0 Tc-99m 2.4E-07 Tc-99 1.3E-10 Tc-101 6.8E-07 Ru-103 0 Ru-105 1.2E-06 Ru-106 0 Rh-105 1.7E-07 Rev. No. 5 Date 03/87 Page A-94 of ODCM

TABLE L-4.4 (continued)

DOSE CONVERSION FACTORS FOR SWIMMING AND BOATING Swimming and Boating Dose Factors (mrem /hr)/(pCi/1)

Isotope Total Body

  • Ag-110m 4.9E-06 Te-125m 3.7E-09 Te-127m 2.6E-10 Te-127 2.8E-09 Te-129m 2.1E-07 Te-129 1.9E-07 Te-131m 2.2E-06 Te-131 7.4E-07 Te-132 4.0E-07 I-129 1.7E-08 I-130 3.9E-06 I-131 7.8E-07 I-132 0 1-133 9.6E-07 I-134 4.2E-06 I-135 0 Cs-134 2.9E-06 Cs-135 6.6E-11 Cs-136 4.1E-06 Cs-137 1.0E-06 Cs-138 4.0E-06 Ba-139 7.7E-08 ba-140 4.9E-07 Ba-141 1.1E-06  :

Ba-142 2.2E-06 I La-140 0 l 5.1E-08 La-141 l La-142 4.5E-06 Ce-141 1.3E-07 Ce-143 5.7E-07 l Ce-144 8.6E-08  ;

Pr-143 0  !

Pr-144 5.6E-08 Nd-147 0 Pm-147 7.5E-11 l W-187 8.3E-07 Ra-223 4.0E-07 Ac-227 4.4E-07 Th-227 1.3E-07 Pa-231 5.0E-07 U-235 2.7E-07 Np-239 2.4E-07 Pu-239 0

  • Dose factors were generated from Impell Corporation's RG109 Computer Analyis, Impell Version 2, Rev. O.

Rev. No. 5 Date 03/87 Page A-95 of ODCM

TABLE L-5 JAF Liquid Effluent Pathway Parameters Calculation of A ft Liquid Dose Factors l

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Rev. No. 5 Date 03/87 Page A-96 of ODCM

APPENDIX B i

GASEOUS DOSE CALCULATION DATA TABLE TITLE PAGE G-1 Unrestricted Area MPC's B-3 G-2 Noble Gas Data Transfer Factors (K , L )

f f B-4 G-3 Air Dose Transfer Factors (M,N) f f B-5 G-4 Inhalation Environmental Pathway Dose B-6 l Conversion Factors (P f) - Instantaneous j i

G-5 Limited Analysis Approach - Gaseous B-9 l Discharge Environmental Pathway Dose l Conversion Factors (R f)

G-6 Environmental Pathway Dose Conversion B-15 Factors (R ) for All Pathways f

G-7 Derivation of Gaseous Dose Factors B-90 I

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Rev. No. 5 Date 03/87 Page B-2 of ODCM

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l TABLE G-7 j 1

Derivation of Gaseous Dose Factors Table G-7.1A Derivation of (P t) Values Table G-7.1B Derivation of Gaseous Dose Factors (Rt)

Table G.7.2 Gaseous Release Isotopes Table G-7.3 Gaseous Pathway Data 1 ,

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Rev. No. 5 Date 03/87 Page B-90 of ODCM

TABLE G-7.1A DERIVATION OF (Pi) VALUES The pathway dose factor, P for iodines and 8-day particulate includes transport paramethr,s of the ith nuclide , the receptor usage rate of the pathway media, the appropriate dose conversion factor. For the inhalation pathway, the value of P1 is calculat-ed as follows:

P1 = K (BR) DFA1 (mrem /y per uCi/m3) where:

K = a constant of unit conversion, 10 0 pCi/uCi BR = the breathing rate of the age group, in m3/yr (Table E-5 of Reg. Guide 1.109) l DFA f

= the maximum organ inhalation dose factor for the appropriate age group for the ith radionuclides, in mrem /pCi. (Tables E-7 to E-10 of Reg. Guide 1.109) l l

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i Rev. No. 5 Date 03/87 Page B-91 of ODCM

TABLE G-7.1B Derivation of Gaseous Dose Factors (Ri)

The pathway dose factor Ri for iodines and 8 day particulate includes transport parameters of the ith nuclide, the receptor usage rate of the pathway media, and the appropriate dose conver-sion factor. In developing the Ri values, separate expressions are written for each of the potential pathways.

I. INHALATION For the inhalation pathway, the value of Ri is calculated as follows:

Ri = K'(BR)a (DFAi) (mrem /yr per pCi/m3)

Where:

K' = a constant of unit conversion, 106 pCi/uC1.

(BR)a = the breathing rate of the receptor of age group (a) in m3/yr. (Table E-5 of Reg. Guide 1.109).

(DFAi) = the organ inhalation cose factor for the rece of age group (a) for the ith nuclide, in mrem /ptor pC1.

(Tables E-7 to E-10 of Reg. Guide 1.109), j Example Calculation:

For the Co-60 child total body dose factor for exposure from inhalation:

DFAi = 6.12E-6 mrem /pCi (BR)a = 3700 m3/yr These values will yield a Ri factor of 2.26E4 mrem /yr per pCi/m3 as listed on page B-6.

11. GROUND PLANE For the ground plane pathway, the value of Ri is calculated as follows:

Ri = K'K"(SF)DFGi[(1-exp-Ait)/Ai]

(m2-mrem /yr per pCi/sec)

Rev. No. 5 Date 03/87 Page B-92 of ODCM

I Where:

K' = a constant of unit conversion, 106 pCi/pCi. j l

K" = a constant of unit conversion, 8760 hr/yr.

]

1 Ai = the decay constant for the ith radionuclides, sec1 j i

t = the exposure time, 4.73E8 sec (15 years). j DFGi = the ground plane dose conversion factor for the ith radionuclides (mrem /hr per pCi/m 2). (Table E-6 of Reg. Guide 1.109).

SF = the shielding factor, 0.7 (dimensionless). (Table E-15 of Reg. Guide 1.109).

Example Calculation: J For the Co-60 child total lody dose factor for exposure to the ground:

Ai = 4.20E-9 sec 1 I DFGi = 1.70E-8 mrem /hr per pCi/m2 These values will yield a Ri factor of 2.15E10 m2-mrem /yr per pCi/sec as listed on page B-15. j III. FRESH FRUITS AND VEGETABLES l For the fresh fruits and vegetables pathway, Ri is calculat-ed as follows:

Ri = K' [(r) / (Yv(Ai + Aw))) (DFLi) a [Ua l F1 exp-AiTl]

(m2-mrem /yr per uCi/sec)

Where:

K' = a constant of unit conversion, 106 pCi/uCi r = fraction of deposited activity retained on cow's feed grass.

Yv = the vegetation areal density, in Kg/m 2, Ai = the decay constant for the ith radionuclides, in sec1 Rev. No. 5 Date 03/87 Page B-93 of ODCM

I Aw = the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73E-7 sec 1 (corre-sponding to a 14 day half-life).

(DFLi)a = the maximum organ dose factor for the ith radionuclides for the receptor in age group (a), in mrem /pci.

(Tables E-11, E-12, E-13 and E-14 of Reg. Guide 1.109).

l Ua = the consumption rate of fresh leafy vegetation by the receptor in age group (a), in Kg/yr.

F1 = the fraction of the annual intake of fresh leafy vegetation grown locally.

T1 = the average time between harvest of leafy vegetation and its consumption, in seconds.

Example calculation:

For the Co-60 child total body dose factor for exposure from fresh fruits and vegetation:

r = 0.2 Yv = 2 Kg/m Ai = 4.2E-9 see Aw = 5.73E-7 sec (DFLi{ = 1.56E-5 mrem /pci Ua = 26 Kg/yr F1 = 1 T1 = 8.6E4 see 2

These values will yield a Ri factor of 7.00E7 m -mrem /yr per uCi/sec as listed on page B-24.

IV. STORED FRUITS AND VEGETABLES For the stored fruits and vegetables pathway, Ri is calcu-lated as follows:

Ri = K'((r) / (Yv(Ai + Aw))) (DFLi)a (Ua s Fg exp-AiTh]

(m2-mrem /yr per pCi/sec)

Where:

Uas = the consumption rate of stored vegetation by the receptor in age group (a), in Kg/yr.

Rev. No. 5 Date 03/87 Page B-94 of ODCM

1 l

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i Fg = the fraction of annual intake of stored vegeter'm I grown locally.  !

Th = the average time between harvest of stored vegetation and its consumption, in seconds.

All other parameters were defined previously.

Example calculation: )

j For the Co-60 child total body dose factor for exposure from stored fruits and vegetables.

s l Ua = 520 Kg/yr Fg = 0.76 Th = 5.18E6 secs These values will yield a Ri factor of 1.04E9 m2-mrem /yr per )

pCi/sec as listed on page B-21. )

l V. MEAT (CONTAM'INATED FORAGE)

For the meat pathway, Ri is calculated as follows:_

Ri = K',Qf(Uap) Ff(r)(DFLi)a FpFs + (1-FpFs)e- e-Ai + Aw Yp Ys (m2-mrem /yr per uCi/sec) ,

l Where: l Uap = the receptor's meat consumption r e.t e for age (a), in Kg/yr.

Ff = the stable element transfer coefficients, in days /kg.

(Table E-1 of Reg. Guide 1.109).

Tf = the transport time from pasture to receptor, in sec.

Th = the transport time from crop field to receptor, in sec.

Yp = the agricultural productivity by unit area of pasture feed grass, in kg/m2, Ys = the agricultural productivity by unit area of stored feed, in kg/m2 Rev. No. 5 Date 03/87 Page B-95 of ODCM

Fp = fraction of the year that the cow is on pasture.

Fs = fraction of the cow feed that is pasture grass while the cow is on pasture.

Qf = the cow's consumption rate, in kg/ day (wet weight).

All other parameters were defined previously.

Example calculation:

For the Co-60 child total body dose factor for exposure from meat:

Uap = 41 kg/yr Ff = 1.3E-2 d/kg Th =

7.78E6 see Tf = 1.73E6 see Fp = 2/12 = 0.167 Fs = 0.5  !

(DFLi)a = 1.56E-5 mrem /pCi j Yp = 0.7 kg/m2 Ys =

2.0 kg/m2 Qf = 50 kg/ day These values will yield a Ri factor of 8.09E7 m2-mrem /yr per pCi/sec as listed on page B-27.

VI. COWS MILK (CONTAMINATED FORAGE)

For the cows milk pathway, Ri is calculated as follows:

Ri = K' Qf(Uap) Fm(r)(DFLi)a FpFs + (1-FpFs)e-AiTh -AiTf e

Ai + Aw Yp Ys (m2-mrem /yr per uCi/sec)

Where:

Uap = the receptor's milk consumption rate for age (a), in liters /yr.

Fm = the stable element transfer coefficients, in days /

liter. (From Reg. Guide 1.109, Table E-1).

All other parameters were defined previously.

Rev. No. 5 Date 03/87 Page B-96 of ODCM

Example calculation:

For the Co-60 child total body dose factor for exposure from milk:

Uap = 330 1/yr Fm = 1.0E-3 days /1 These values will yield a Ri factor of 5.04E7 m 2 -mree/yr per pCi/sec as listed on page B-9.

VII. GOATS MILK (CONTAMINATED FORAGE)

For the goats milk pathway, R1 is calculated as follows:

l Ri = K' Qf(Uap) Fm(r)(DFLi)a FpFs + (1-FpFs)e -A TE e -A Tf Ai + As Yp Ys (m2-mrem /yr per uCi/sec) l Where:

Fm = the stable element transfer coefficient. For the l radionuclides in question, use Table E-2 of Reg. Guide 1.109. If the radionuclides is not listed in Table E-2, use Table E-1 (i.e., the same value used for the cows milk pathway).

1 All other parameters were defined previously.

Example calculation:

For the Co-60 child total body dose factor for exposure from goats milk:

Qf = 6 kg/ day (wet weight)

Fm = 1.0E-3 day /1 Tf = 4.32E4 see 2

These values will yield a Ri factor of 6.06E6 m -mrem /yr per uCi/sec as listed on page B-12.

i Rev. No. 5 Date 03/87 Page B-97 of ODCM

APPENDIX C METEOROLOGICAL DATA I

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l Rev. No. 5 Date 03/87 Page C-1 of ODCM L________._

APPENDIX C METEOROLOGICAL DATA TABLE TITLE .PAGE M-1 (CH1/Q), (D7Q), and (CMT7Q) Depleted and 8-Day Decayed C-3 M-2 Ground Level Release Meteorological Data C-4 M-3 Elevated Release Meteorological Data C-5 M-4 Critical Receptor Dispersion Parameters For Ground and Elevated Releases C-6 l

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TABLE M-4 l Critical Receptor Dispersion Parameters J For Ground and Elevated Releases Dispersion Parameter Description Critical Receptor X/Q - Skins Stack Site Boundary X/Q - Skin Reactor Site Boundary X/Q - Skins Turbine. Site Boundary X/Q - Skins Refuel Site Boundary X/Q - Sking Radwaste Site Boundary X/Q - Gamma: Elevated Site Boundary X/Q - Gamma; Ground . Site Boundary X/Q - Betas Elevated Site Boundary X/Q - Beta: Ground Site Boundary D/Q - GFDs Stack Critical Resident X/Q - Dep. Inhal.: Stack Critical Resident D/Q - SFV & FFV: Stack Critical Garden D/Q'- Cows Stack Critical Milk Animal D/Q - Goat: Stack Critical Milk Animal D/Q - GPD: Reactor Critical Resident X/Q - Dept Inhal.: Reactor Critical Resident ,

D/Q - SFV & FFV: Reactor Critical Garden D/Q - Cow; Reactor Critical Milk Animal D/Q - Goat: Reactor Critical Milk Animal D/Q - GFDs Turbine Critical Resident X/Q - Dep. Inhal.: Turbine Critical Resident D/Q - SFV & FFV Turbine Critical Garden D/Q - Cow: Turbine Critical Milk Animal D/Q - Goat; Turbine Critical Milk Animal D/Q GFDs Refuel Critical Resident X/Q - Dep. Inhal.: Refuel Critical Resident D/Q - SFV & FFV: Refuel Critical Garden D/Q - Cow Refuel Critical Milk Animal D/Q - Goat: Refuel Critical Milk Animal D/Q - GPD: Radwaste Critical. Resident X/Q - Dep. Inhal.: Radwaste Critical Resident D/Q - SFV & FFV: Radwaste Critical Garden D/Q - Cows Radwaste Critical Milk Animal D/Q - Goat Radwaste Critical Milk Animal Rev. No. 5 Date 03/87 Page C-6 of ODCM

APPENDIX E TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS TABLE TITLE PAGE E-1 Effective Dose Factors for Noble Gases -

Total Body Effective Dose (Keff) E Effective Dose Factors for Noble

~

E-2 Gases - Air Doses (M eff and Neff) E-6 E-3 Effective Dose Factor for Noble Gases -

Skin Effective Dose (L + 1.1 M,ff) E-7 E-4 Tables of Source Terms Used for Development of Effective Dose Transfer Factors E-8 E-5 Tables of Source Terms Used for Development of Effective Dose Transfer Factors (Ground Level Release) E-10 E-6 Radionuclides Distribution of Ground and Elevated Releases E-12 I

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Rev. No. 5 Date 03/87 Page E-2 of ODCM' j

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APPENDIX F EFFLUENT MONITOR SAMPLING LOCATIONS AND DESCRIPTIONS TABLE TITLE PAGE F-1 Atmospheric Gaseous Release Point Data F-3 F-2 Effluent Monitoring System Data F-4 FIGURE F-1 Gaseous Release Points Building Elevations F-6 F-2 Gaseous Release Points Plant Yard Layout F-7 F-3 Liquid Release Point F-8 {

t F-4 Gaseous Effluent Release Paths F-9 F-5 Liquid Effluent Release Paths F-10

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Rev. No. 5 Date 03/87 Page F-2 of ODCM

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APPENDIX F UNRESTRICTED AREA MAP FIGURE TITLE PAGE G-1 JAFNPP Site Boundary Map G-1 i

Rev. No. 5 Date 03/87 Page _ G-2 of ODCM

JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM)

APPENDIX H ENVIRONMENTAL SAMPLE LOCATIONS TABLE TITLE PAGE H-1 Radiation Environmental H-5 Monitoring Sampling Locations FIGURE H-1 Environmental Sampling H-8 Location Map i

H-2 Environmental Sampling H-9 Location Map H-3 Liquid Effluent Pathway - H-10

, Water Intake Points Rev. No. 5 Date 03/87 Page H-2 of ODCM l

_. y APPENDIX F i

ODCM

SUMMARY

TABLES TABLE TITLE PAGE I-1 Radioactive Effluent Release Limits Summary Table I-3 I-2 ODCM Summary I-4 i

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Rev. No. 5 Date 03/87 Page I-2 of ODCM f

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