ML20090A304

From kanterella
Jump to navigation Jump to search
Ja Fitzpatrick Nuclear Power Plant Effluent & Waste Disposal Semiannual Rept,Jul-Dec 1991
ML20090A304
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 12/31/1991
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20090A302 List:
References
NUDOCS 9203020249
Download: ML20090A304 (38)
v • d • e


Text

.. .. . .. . - . - .- - - . . - . . - . . . _ ~ . . . . . . - . . . - . - . . . .

co :;

f

-i NEW YORK POWER AUTHORITY I JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1,1991 - DECEMBER 31,1991 DOCKET NO.: 50-333 LICENSE NO.: DPR-59 4-9203020249 920226 PDR ADOCK-OSOOO333-R PDR

. . ~ . . ~ . . . _ . - . .

NEW YORK POWER AUTHORITY JAMES A. FTI2 PATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991 - DECEMBER 1991 SUPPLEMENTAL INFORMATION FACILITY: JAFNEE LICENSEE: NEW YORK POWER AUTHORITY

1. Technical Snecincadon Limjit
a. Fission and Activation Gases:

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

1 (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 mrad from beta radiation; and, (b) Durir ; any calendar year, to less than or equal to 10 mrad from gamma radiation and less than or equal to 20 mrad from beta radiation.

b. Tritium, Iodines and Particulates, Half Lives > 8 days:

(1) The dose to a member of the public at 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) 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.

l l

1 l _ ,- -. _ . .

SUPPLEMENTAL INFORMATION (Continued)

(2) The dese 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, Icdine 133, Tritium and for radioactive materials in particulate form with half lives greater than 8 days (inhalation pathway only).

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-(M pCi/ml.

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

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

2. Maximum Permissible Concentrations
a. Fission and activation gases: (None specified)
b. Iodines: (None specified) c, Particulates, half lives > 8 days: (None specified)
d. Liquid effluents: Ouarter 3 Ouarter 4 (1) Fission and activation 5.60E 05 8.84E-05 products (mixture MPC)

(pCi/ml)

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

SUPPLEMENTAL INFORMATION (Coettaued)

3. Average Energy (None specified)
4. Measummants and Appmximations 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. todines: Gamma spectral analysis of charcoal cartridge and particulate filter on each release path. -
c. Particulates: Gamma spectral analysis of partictulate filter and charcoal cartridge on each release path,
d. Uquid Effluents: Gamma spectral analysis of each batch discharged, except composite analysis for Strontium 89, Strontium 90, Iron SS, Tritium, and Alpha.
c. Solid Waste: Gamma spectral analysis of a representative sample of each waste shipment. Scaling factors established from off site composite sample analyses to estimate concentration of non gamma emitters. Low activ.ty trash shipments, curie content estimated by dose rate measurement and application of appropriate scaling factors,
f. Error Estimation Method: Overall error for sampling .! analysis l estimated by combining individual errors using error pt agation methods. This l processs composed of determinate and undeterminate nrs.

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

Undeterminate Random counting error estimated using accepted statistical calculations 1

3

SUPPIEMENTAL INFORMATION (Cc:tinued)

?

5. : Batch.Raimaams Uquid:-- Onnrter 3 Ouarter 4 (1) Number of batch releases: 2.20E + 01 - 1.20E + 01 -

-(2) Total time period for batch 1.46E + 03 1.01E + 03 release: (min)-

1 (3) Maximum time period for 9.10E + 01 2.30E + 02 l batch release: (min)

(4) Average time period for 6.65E + 01 8.39E + 01 ,

batch release: (min)

(5) Minimum time period for 2.50E + 01 1.00E + 01 batch release: (min)- +

Gaseous: There were no gaseous batch releases for this report period.

- 6. - Ahacrmal Releases

a. Uguid: 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 L

L I

I-4 l

L o , . - - .. . . _ - _ . _ - - . _ .~. . . . . . . . _ . - _- . - ~ .

4

, NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI.ANNUAI; RHPORTf JULY 1991 DECEMEBER 1991 TABLE 1A-GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES EST TOTAL ,

,UM[I OUARTER 3 OUARTER 4 ERROR %

A. FISSION AND ACTIVATION GASES .

1. Total Release Cl 5.51E+02 4.45E+O2 $ 25
2. Avera0s release rate for period pCl/sec 6.93E+01 5.60E+01
3. Tech, Spec. Umk  % * *

. B. IODINE 131

1. Total lodine-131 C1 3.23E-05 3.39E-05 5 25
2. Avera0s release rate for period . pCl/sec 4.07E-06 4.27E-06
3. Tech. Spec. Umk  % *
  • l: C. IODINE 133 AND PARTICULATES p
1. lodine 133 and ParticJates ,

wkh half 4fves >8 days- C1 2.20E-04 3.04E-04 s 25

2. Average release rate for period pCl/sec 2.76E-05 3.83E-05 3 Tech. Spec Umk  % * *
4. Gross alpha radioactivky Cl 5.39E-06 7.92E-06 s 25 D. TRITIUM Total Release Cl 3.24E-01 2.74E+00 '
1. $ 25
2. Average release rate for period pCl/sec 4.08E-08 3.44E-07
3. Tech. Spec. Umk  % * *
  • E. PERCENT OF 1TCHNICAL SPECIFICATION LIMITS FISSION AND ACTIVATION GASES 1, Quartedy gamma air dose limk  % 2.32E-01 1.50E-01
2. Quartedy beta air dose limit  % 4.55E-02 1.9OE-02
3. _ Yeady gamma air dose limit  % 1.16E-01 7.52E-02

' 4;. Yeady beta air dose limit  % 2.28E-02 9.50E-03

5. Whole body dose rate limit  % 2.24E-03 1.45E-03 6J Skin does rate limit  % 5.53E-04 3.09E-04 HALOGENS, TRITIUM AND PARTICULATES WITH ' HAIE. LIVES >8 DAYS
7. Quarterly dose limit (organ)  % 9.00E-0.1 8.8OE-03
8. . Year 1y dose limk (organ)  % 4.50E-03 4.4OE-03
9. Organ dose rate limit  % 7.20E-05 8.03E-OS 5

NEW YORK. POWER AUTIlORITY JAMES A. FTI2 PATRICK NUCLEAR POWER PLANT EFFLUENT- AND WASE DISPOSAL SEMI ANNUAL REPORT JULY 1991 DECEMBER-1991 TABLE IB GASEOUS EFTLUENTS- ELEVATED RELEASE CONTINUOUS MODE NUCLIDES RL1 EASED .LWII OUARTER 3 OUARITR 4

1. H aalen G aans ArgorN1 Cl 1.25E+00 2.73E+00 Krypton 46m Cl 7.64E+01 5.78E+01 Krypton-67 Cl 1.98E+01 9.77E+00 Krypton-88 Cl 1.10E+02 7.29E+01 Xenon-131m Cl 4.59E+01 1.54E+01 Xenon-133 Cl 1.26E+02 1.71E+02 Xenon-133m Cl 3.52E-01 1.05E+00 Xenon-135 Cl 9.03E+01 4.32E+01

- Xenon-135m Cl 3.86E+00 1.79E+00 Xenon 137 Cl 1.83E+01 ---------

Xenon 138 Cl 1.33E+01 5.02E+00

2. todines lodine 131 Cl 2.32E-05 2.30E-05 lodine-133 Cl 1.90E-05 1.69E-04
3. Par $1culates Manganese Cl. 1.65E-07 1.76E-uu Strontium 40 Cl 4.11E-05 1.42E-06 Strontium-90 Cl 6.76E-08 --------

Ruthenium-103 Ci --------

2.25E-07

- S8ver 110m C1 --------

1.78E-06 Ceslurn-137 Cl 4.76E-07 7.04E-08 Barium / Lanthanum-140 Cl 3.91E-07 --------

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

l 6

= - - ._.. - - . - . . - - . - . . . . . - , , .. .

v NEW YORK POWER AUTIIORITY

'- JAMES A, FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND- WASTE DISPOSAL SEMI. ANNUAL REPORT JULY 1991.. DECEMBER 1991 TABLE IC GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RE114 SED .UN]I OUARITR 3 OUARITR 4

1. Flasles Gaans Argon 41 Cl 4.37E-01 3.30E-02 Krypton 46m Cl 8.25E+00 1.81E-01 Krypton 48 Cl 1.75E+00 2.52E+00 Xenon-131m - Cl 1.70E+01 2.72E+01 Xerm-133 Cl 1.76E+00 3.34E+01 Xenon-133m Cl 1.44E+00 1.86E-01 Xenon-135 Cl 8.57E+00 1.27E+00 Xenon-135m C1 2.86E-01 --------

Xenon-137 Cl 7.22E+00 --------

2. lodlaes lodir+131 Cl 9.16E-06 1.09E-05 lodine-133 Cl 6.51E-05 8.75E-05 3 farticulates Manganese-54 Cl 1.85E 3.02E-06 Cobalt-60 Cl 3.49E-05 1.02E-05 Zinc 46 _

Cl 5.72E-05 1.59E-05 Strontium-80 Cl 1.32E-08 8.12E-06 Strontium-90 Cl 7.25E-10 --------

Niobium-96 Cl 1.03E-06 --------

Barium /t.anthare140 Cl --------

4.90E-06 Note: There were no batch releases for this report period 7

... - .. .. - . _ . - . _ ~ - . - - . . - .

'l 1

NEW YORK POWER AUTilORITY l JAMES A. FITZPATRILK. NUCIEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991 DECEMBER 1991 TABLE 2A LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES EST TOTAL

.L%II Dlig LTJL} OUARTER 4 ERROk %

A. FISSION AND ACTIVATION PRODUC'IS

1. Total Release (not induding trtium and alpha) Cl 1.77E-03 2.46E-03 5 25
2. Average deuted concentra-tion during per6od 4Ci/mi 1.05E-11 1.42E-11
3. Applicable limit  % 1.87E-05 1.61E-05 R. TRITIUM
1. Total Release Cl 7.08E-01 4.19E-01 5 25
2. - Average dButed concentra-tion during period 4Ci/ml 4.19E-09 2.42E-09
3. Applicable limit  % 1.40E-04 8.06E-05 C. DISSOLVED AND ENTRAINED GASES
1. Total Release Cl --------

3.41E-04 s 25

2. Average d8uted concentra-tion during period #Ci/ml --------

1.97E-12

3. Applicable Umit  % --------

9.86E-07 D. GROSS ALPHA RADIOACTIVITY

1. Total Release Cl 5.85E-05 --------

5 25 E. VOLUME OF WASTE RELEASED

..UOR TO DILUTION) liters 8.63E+05 5.10E+05 F. VOLUME OF DILUFION WATER USED DURING PERIOD liters 1.69E+11 1.73E+11 G. PERCENT OF TECHNICAL SPECIFICATION LIMITS

1. Quarterly Whole Body Dose  % 4.18E-03 2.53E-03
2. Quarterly Organ Dose  % 2.24E-03 1.58E-03
3. Annual Whole Body Dose  % 2.09E-03 1.27E-03
4. Annual Organ Dose  % 1.12E-03 7.92E-04 4

8

NEW YORK POWER AU1110RITY JAMES A. FITZ. PATRICK NUCWAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991- . DECEMBER 1991 TABLE 2B LIQUID EFFLUENTS RATCH MODE NUCLIDES RELZASED UNIT OUARTERJ QUARTER 4 H#rogen 3 0 7.08E-01 4.19E-01 Ctvomium-51 0 --------

3.95E-04 Manganese-54 0 3.92E-04 3.56E-04

- Iron-59 0 --------

4.08E-05 Cobahc0 Cl 3.89E-04 3.35E-04 Zinc 66 Cl 7.43E-04 7.97E-04 Arsenic 76 01 --------

3.67E-05 Strontium-92 Cl 1.05E-05 5.79E-06 Niobium-95 Cl 1.12E-05 --------

Niobium-97 Cl 3.33E-05 1.76E-05 Technetium-99m C1 --------

5.29E-05 SIver 110m' Cl 1.19E-04 4.58E-05 Xenon 133 Cl -------- 2.42E-05 Cesium-134 C1 2.80E-05 ---~~---

Xenon 135 Cl --------

3.17E-04 Cesium-137 C1 4.32E-05 2.34E-05 Barium / Lanthanum-140 C1 --------

9.25E-06 Cerium-141 Cl 9.50E-07 --------

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

9

NEW YORK POWER AU'IRORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND VASTE DISPOSAL SEMI ANNUAL REPORT- JULY 1991 DECEMBER 1991 TABLE 3A SOLID WASTE AND IRRADIATED FUEL SIIIPMENTS A. SOLID WASTE SHIPPED OIT SITE FOR DISPOSAL OR BURIAL (NOT IRRADIATED FUEL) l EST SIX MONTH TOTAL i 1. .Tyne of Wang ,13HI PERIOD ERROR %

l-3

a. Spent resins, filter sludges m 66.8 10 evaporator bottoms, etc. Ci 248 25 l 3
b. Dry compressible waste, m 1382 10 contaminated equipment, etc. Ci 3.72 25 s
c. Irradiated components m N/A N/A Ci N/A N/A 3
d. Other m N/A N/A l

Ci N/A N/A

2. Estimate of Maior Nuclide Composition Isotope Ec Abundance Isotope  % Abundance l Zinc-65 48.330 Ruthinium.106 2.747 L Cobalt 60 17.689 Cobalt 58 1.714 l Iron 55 13.643 Cesium-134 1.345 Manganese 54 6.398 Chromium 51 1.291 Cesium-137 3.174 Carbon-14 0.252 Nickel-63 0.163
3. Solid Waste Disposition l

1 Shipment .QJy Transnortation Mode Destination

-Type A 32 Truck Barnwell, SC Type A 61 Truck Richlan3, WA l

l 10

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT

~

EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991 DECEMBER 1991 TABLE 3B SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. NRC CIASS A

1. 70% Powdered Resin /30% Bead Resin (ISA)

Container Type: 170.8 ft HIC Solidification Media: None 3

Total Volume: 170.8 ft No. of Shipments: 1 Type: Cask Mode: Truck Principal' Quantity >

Isotopes _Curiss  % Abundance Determination Zine-65 18.40 53.409 M Coba!t-60 4.48 13.004 M Ruthenium 106 2.70 7.837 E 1ron-55 2.68 7.779 E Cesium 137 1.37 3.977 M r M..nganese 54 1.23 3.570 M

' Silver 110m 1.12 3.251 M Cesium 134 0.67 1.930 M Zirconium 95 0.58 1.684 E Chromium-51 0.37 1.080 E Nickel-63 0.0. 0.149 E Nickel 59 0.01 0.(M4 E TOTAL: 34.5 Curies E = Estimated M = Measured l

l l

l 11 i

NEW YORK POWER AUTHORITY JAMES A. PTI. PATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 'l SEMI ANNUAL REPORT JULY 1991 -' DECEMBER 1991 TABLE 3B SOLID WASTE AND IRRADIATED FUEL SillPMENTS A. NRC CLASS A

2. .l00% Powdered Resin (LSA)

Container Type: 170.8 3ft IIIC Solidification Media: None Total Volume: 512.4 No. of Shipm:nts: 3 Type: Cask Mode: Truck Principal Quantity Isotopes ' Curies  % Abundance Determination Zinc-65 32.0 41.404 M Cobalt-60 20.9 27.115 M Iron-55 11.4 14.782 E Cesium-137 4.71 6.102 M Manganese-54 3.43 4.450 M Cobalt 58 2.05 2.652 M Cesium-134 1.32 1.711 M Chromium-51 1.20. 1.552 M Nickel-63 0.15 0.193 E TOTAL- 77.2 Curies E = Estimated .

M = Measured I

l 12 l

L j

NEW YORK IOWER AtJi'llORITY l

JAMES A. FITZPNTRICK NUCLEAR LOWER PIANT l EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991 DECEMBER 1991 T Alll E 311 SOLID WASTE AND IRRADIATCH FUEL SillPh1ENTS A. NRC CIASS.A 3 1011_IltadleilnDEll'owdc1cdlesin (LSA)

Container Type: 170.8 ft' lilC Solidification Media: None 3

Total Volume: 170.8 ft No. of Shipments: 1 Type: Cask Mode: Truck Principal Quantity hologes furits  % Abundance Determinatloa Zine 65 8.86 55.177 M Cobalt 60 2.35 14.635 M Iron 55 1.72 10.712 E Ruthenium 106 1.03 6.414 E Manganese 54 0.M 4.116 M Cesium 137 0.42 2.641 M Zirconium.95 0.22 1.370 E Cesium 134 0.17 1.077 M 12nthanum 140 0.16 1.003 M Nickel 63 0.03 0.166 E TOTAL: 16.1 Curies E = Estimated M = Measured 13

?

NEW YORK POWER AUTHORTI'Y JAMES A. FT12PA'! RICK -NUCLEAR POWER PLANT EFFLUENT AND WAS1E DISPOSAL  :

SEMI ANNUAL REIMT JULY 1991 DECEMBER 1991 I 1

TAB 11 3B  !

SOLID WASTE AND IRRADIATED FUEL SillPMEN13 l,

A. ERC CLASS A 4, 85% Powdered Resin /15% Resin U SA) '

3 Container Type: .

170.8 ft 111C Solidification Media: None 3

Total Volume: 170.8 ft No. of Shipments: 1 ,

Type: Cask Mode: Truck Principal Quantity '

h2 toga Curies _% Abundanec Determination Zine-65 0.250 41.295 M Cobalt 60 0.177 29.237 M i Iron 55 0.100 16.518 E Cesium 137 0.036 5.864 M ,

Manganese 54 0.028 4.658 M Cesium 134 0.009 1.568 M l Nickel-63 0.(X)2 0.334 E l

TOTAL: 0.60; Curies i

. E = Estimated M = Measured

(

14 >

L -.-.. - .-. -_ - . - . . - . . . . , . . . - - - - - . - . , ~ . -,-. - - -,- - - ---

NEW YORK POWER AUTilORrrY o - '

JAMES A. FITZPATRICK NUCLEAR POWER FfANT ,

EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991. DECEMBER 1991 i

t TABLE 3B  !

SOLID WASTE AND IRRADIATEL) FUEL SillPMENTS .

A. NRC CLASS A 5.18.8 ft' Pressure Vessel Charspal Filter Dewatered (LSA) t 3

Container Type: 18.8 ft Pressure Vessel Solidification Media: None 3

Total Volume: 56.4 ft No. of Shipments: l' Type: Cask Mode: Truck Principal Quantity h0100c5 Curies ,5 Abundanet DCicnnina110D Zinc 65 0.52 33.122 M 1ron 55 0.44 27.992 E Cobalt 60 0.43 27.486 M Manganese 54 0.14 8.917 M Carbon 14 0.02 1.056 E TOTAL: 1.58 Curies E = Estimated M = Measured

  • 3 Pressure Vessels out of one 7 Pressure Vessel Shipment combined with one Table 3B A6 (page 16) shipment.

L l 15

_ _ . _ _ _ _ _ . . _ . _ _. . . _ _ _ . _ . . . _ _ _ . ~ . _

NEW YORK POWER AUTilORrrY JAMES A. FrI2 PATRICK NUCLEAR POWER PLANT i

EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991 DECEMBER 1991 TABIE 3H SOLID WASTE AND 1RRADINTEI) FUEL SillPMENTS l A. hKC CLASS A  ;

6.18.8 ft' Prenurg Venels. Dewatered Bend Resin (ISA) 3 Container Type: 18.8 ft Pressure Vessel  !

Solidification Media: None 3

Total Volume: 733.2 ft No of Shipments: 6' Type: Cask Mode: Truck l

Principal Quantity 1 holopts Curici fe Abundance DetermluallDR Zine-65 5.90 49.910 M <

Iron 55 2.07 17.485 E Cobalt 60 2.03 17.193 M Manganese 54 0.98 8.239 M Cesium 137  :.17 1.404 M Chromium 51 0.13 1,131 M Antimony 125 0.12 1.046 M Ruthinium 106 0.12 1.042 E Carbon 14 0.08 0.662 E Nickel 63 0.02 0.160 E ,

TOTAL: 11.8 Curies E = Estimated ,

r M - Measured

, '5 Shipments of 7 Pressure Vessels and l

1 Shipment of _4 Pressure Vessels combined with 3 Pressure Vessels from one Table 3B A5 (page 15) shipment.

l 16

NEW YORK POWER AUTilORITY JAMES A. FITZPATRICK NUCUIAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991 DECEMBER 1991 TABLE 3B SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. NRC CLASS A 7.100% Dewaltted Bead Resin in a lile U SA)

Container Type: 170.8 3ft IfIC i Solidification Media: None 3

Total Volume: 341.6 ft l

%. of Shipments: 2 Type: Cask Mode: Truck Principal Quantity Isotopec Curies Ec Abundance Determination .

Zine65 11.90 43.(M6 M Iron 55 5.72 20.622 E Cobalt 60 5.62 20.261 M Manganese 54 3.18 11.454 M Cobalt 58 0.42 1.524 M Carbon 14 0.22 0.779 E Cesium 137 0.17 0.619 M Nickel 63 0.06 0.229 F 1 TOTAL:

27.7 Curies E = Estimated M - Measured ,

e 17

- - - - _ . . . _ - - -. . -. - . . _ ~ - _ _ _ - - . _ - - -

NEW YORK POWER AUTiiORITY JAMES A. FITZPATRICK NUCLEAR POWER PIANT EFFLUENT AND WASTE DISPOSAL '

SEMI ANNUAL REPORT JULY 1991 DECEMI3ER 1991 ,

t TABLE 3B SOLID WASTE AND IRRADIATED FUEL SillPMENTS A. NRC CLASS A 8.100% Dewatered Bead Resin in a IllC (13A) 3 Container Type: 205.8 ft lilC .

Solidification Media: None 3

Total Volume: 205.8 ft No. of Shipments: 1 Type: Cask Mode: Truck Principal Quantity Isotopes Curies  % Abundance Determination Zine-65 44.10 55.923 M Iron 55 8.38 10.627 E Cobalt 60 8.22 10.424 M Manganese 54 6.36 8.065 M Ruthinium 106 2.99 3.792 E Chrondum 51 1.46 1.851 M Cobalt 58 1.38 1.750 M Cesium 137 1.06 1.344 M Cesium 134 1.05 1.331 M Antimony 125 0.90 1.146 E Silver 110m . 0.82 1.039 E Carbon 14 0.32 0.401 E Nickel-63 0.09 0.118 E TOTAL: 78.9 Curies E = Estimated M = Measured l

18

NEW YORK POWER AUTilORITY JAMES A. FI'I2 PATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991 DECEMBER 1991 i TABLE 3B SOLID WASE AND IRRADIATED FUEL SHIPMENTS A. ERC CLASS A .

9. Compacted /Uncompacted Div Active Waste (LSA)

Container Type: LSA Box (various sizes)

Solidification Media: None 3

Total Volume: 3700 ft No. of Shipments: 5 Type: LSA Box Mode: Truck '

Principal Quantity Isotopes Curies  % Abundance Determination Zine65 0.742 57.175 M fron 55 0.155 11.967 E Cobalt-60 0.153 11.787 M Manganese 54 0.069 5.279 M Ruthinium 106 0.M7 5.196 M '

Cesium 137 0.028 2.190 M Chromium 51 0.020 1.534 E Antimony 125 0.014 1.108 M TOTAI; 1.297 Curies E = Estimated l-1 M = Measured ,

l l

19

. I NEW YORK POWER AUTilORrn' JAMES A. FrI2 PATRICK NUCLEAR POWER PLANT ,

Eri;LUENT AND WASTE DISPOSAL '

SEMI ANNUAL REPORT JULY 1991 DECEMBER 1991 i

TABLE 3B SOLID WASTE AND IRRADIATED FUEL SillPMENTS A. NRC CLASS A >

10. Uncomnacted Drv Active Waste (Dirt / Rock) (ISA)

Contalner Type: LSA Box (various sizes)

Solidification Media: None Total Volume: 33,339.76 ft 3 No. of Shipments: 69 ,

Type: LSA Boxes Mode: Truck .

Principal _

Quantity Isotopes Curies fe Abundance Determination Iron 55 2.250 94.149 E Zine 65 0.083 3.460 M Cchh-60 0.056 2.391 M TOTAL: 2.39 Curies E = Estimated M = Measured  :

20 -

NEW YORK IOWER AUTilORITY JAMES A. FI'I2 PATRICK NUCLEAR POWER PIANT EFFLUENT AND WASTE DISPOSAL '

SEMI ANNUAL REPORT JULY 1991. DECEMBER 1991 TABII 3B SOLID WASTE AND IRRAulATED FUEL SillPMENTS ,

A. NRC CLASS A ,

11. 40ft Sealand Van (LSA)

Container Type: 40 ft Sealand Van Solidification Media: None 3

Total Volume: 7464 ft No. of Shipments: 4 i Type: Sealand Van Mode: Truck Principal Quantity hotopes .Cutici  % Abundance nciermination Iron 55 0.0131 39.81 E Zine 65 0.0096 29.38 M Cobalt 60 0.0082 24.86 M Manganese 54 0.0009 2.63 M Nickel 63 0.0005 1.49 M

. TOTAL: 0.0328 Curies E = Estimated M = Measured 21

i NEW YORK POWER AUTilORrlY ,

JAMES A. FrI2 PATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI. ANNUAL REPORT JULY 1991. DECEMBER 1991 t

ATTACHMENT NO.1 i

CilANGES TO THE OFFSITE DOSE CALCUIATION AtANUAL (ODCM)

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 Semlannual Radioactive Effluent Release Repert. ,

No changes were made to the ODCM this report period.

P i

22  :

l

~_ . _ . , . . - . _ , . _ . _ . _ .__ . ,- _ ___.. _ _ .. _ ,. _ _ _.._...._.._.,_.___-

y NEW YORK POWER AUTilORITY

' JAMES A. FrI2 PATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991 DECEMBER 1991 ATTACHMENT No. 2

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM In acco' dance with Section 7.3.C. ) ' Amendment 93 to the James A. FitzPatrick Nuclear Power Plant Techrdcal Specifications, changes inade to the Process Control Program (PCP) during the reporting period shall be included in the Semiannual Radioactive Effluent Release Report.

Revision 4 to the Process Control Program (PCP) procedure AP 1.10 was approved for use on 7 03 91 (PORC Meeting No. 9165). This revision was made due to changing Waste Disposal Contractors. This change did not reduce conformance to existing criteria for solid waste.

Revision 5 to the Process Control Program (PCP) procedure AP 1.10 was approved for i use on 1106 91 (PORC Meeting No. 91109). This revision was made to respond to two Adverse Quality Control Reports (91053 and 91054). His change did not reduce conformance to existing criteria for solid waste.

Revision 6 to the Process Control Program (PCP) procedure AP-1.10 was approved for use on 1120 91 (PORC Meeting No. 91112). This revision was made to incorporate an additional Waste Contractor Quality Assurance Program. This change did not reduce conformance to existing criteria for solid waste.

t Revision 7 to the Process Control Program (PCP) procedure AP 1.10 was approved for use on 1212 91 (PORC Meeting No. 91117). This revision was made to add one additional Waste Contractor Procedures (FO AD-002), it also references a Waste Contractor Procedure (SD.OP N8) and indicates that PORC approval is required before using this procedure. This change did not reduce conformance to existing criteria for solid waste, 23

NEW YORK POWER A1JrilORrrY JAMES A. HTZPAT11CK NUCLEAR POWER PLANT EFFl.UENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991 DECFMBER 1991 A*ITACllMENT 2 (continued)

1. CONTRACTOR PROCEDURES:
a. During this time frame, we deleted former Waste Contractor LN Procedures and implemented new Chem Nuclear Systems Inc. procedures,
b. The current Chem Nuclear Systems, Inc. Procedures are as listed:

o CNSI Procedure, OA AD 0001 - Quality Assurance Program, Revision F, 4/25/91 (PORC Meeting No. 91-47),

o SEO Quality Assurance Program, Revision 3,11/20/91 (PORC Meeting No. 91 112).

o CNSI Procedure, FO OP 022-41802 - Ecodex Precoat/Powdex/Solka-Floc /Diatomaccous E sch Dewatering Procedure For CNSI 14 215 or Smaller Liners At James A. FitzPatrick Nuclear Power Plant, Revision N, 5/8/91 (PORC Meeting No. 9151).

CNSI Procedure, FO-OP-022-41802 Revision P was approved on 5/23/91 (PORC Meetir.g No. 9153). This change was made due to a change in South Carolina Certificate of Compliance for percent of oil and new requirement for documentation of an approved NRC O/A Program. This change did not reduce conformance to existing criteria for solid waste.

CNSI Procedure, FO OP 022-41802 Revision 15 was approved on 12/12/91 (PORC Meeting No. 91117). This change was made to incorporate in Chem Nuclear's procedure the use of Pneumatic lilC Lid Closure Tool. This change did not reduce conformance to existing criteria for solid waste, o CNSI Procedure, FO-OP-023-41802 - Bead Resin / Activated Carbon Dewatering Pro:edure For CNSI 14 215 or Smaller Liners At James A.

FitzPatrick Nuclear Power Plant, Revision 0,5/8/91 (PORC Meeting No.

91 51).

CNSI Procedure, FO OP-023-41802 Revision 0,12/12/91 (PORC Meeting No. 91117) This change was in addition to the initiated revision whereby it adds the valve line up. This change did not reduce conformance to existing criteria for solid waste.

24

NEW YORK POWER AtJrilORITY JAhiES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WAS'm DISPOSAL SEMI ANNUAL REPORT JULY 1991. DECEhtilER 1991 ATTACilhtENT 2 (continued)

1. CONTRACTOR PROCEDURES (Continued):

o CNSI Procedure FO OP-025-45230 - Dewatering Procedure for CNSI 24-inch Diameter Pressure Vessels at James A. FitzPatrick Nuc! car Power Plant, Revision 0,4/19/91 (PORC hiecting No. 91-45).

o CNSI Procedure, FO-OP 032-41802 Set up and Operating Procedure For <

RDS 1000 Unit Number 9 at Lucs A. FitzPatrick Nuclear Power Plant, l Revision 0,5/8/91 (PORC hiceting No. 9151).

CNSI Procedure, FO OP-032-41802 Revision A was approved on 7/17/91 (PORC hiceting No. 9170). These changes were made due to an engineering change to the fill head assembly of the RDS 1000 dewatering assembly. This change did not reduce conformance to existing criteria foi solid waste.

o CNSI Procedure, FO AD-002 Operating Guidelines For Use Of Polyethylene liigh Integrity Containers, o CNSI Procedure, SD OP-048 Process Control Program And Operating Procedure For in Situ Solidification Of Suspended Objects. This revision is in the approval stages.

25

NEW YORK POWER AUTilORITY JAhiES A. F112 PATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991 DECEMBER 1991 NITACHMENT NO. 3

SUMMARY

OF CHANGES TO THE ENVIRONMENTAL MONITORING AND DOSE CALCUIATION LOCATIONS in accordance with section 7.3,C.3 of Amendment 93 to the James A. FitzPatrick Nuclear Power Plant Technical Specifications, a listing of new locations for dose

- calculation and/or environmental monitodng identified by the land use census shall be included in the Semlannual Radioactive Effluent Release Reports.

1. CilANGES IN ENVIRONMENTAL MONITORING LOCATIONS No change in Environmental Monitoring 1.ocations was required based on the land use census.
2. NEW LOCATIONS FOR DOSE CALCULATIONS No changes in Dose Calculation Rcceptor Locations were required based on land use census. '

l 26

. _ ._ _- . . _ . . _ _.-____..__._m_.___._ . _ _ _ _ . -

4 NEW YORK POWER AUTilORITY 9

JAhiES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEhil ANNUAL REPORT JULY 1991. DECEhfBER 1991 ,

A1TActiMENT NO. 4 DEVIATIONS FROM Tile REQUIRED ENVIRONMENTAL SAMPLING SCilEDULE  ;

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

EXCEFf10N TO Tile ENVIRONMENTAL SAMPLING PROGRAM The air sampling pump at the R 2 offsite Environmental Sampling Station was inoperable for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (0630 to 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />) on December 3,1991. The ,

inoperability wra caused by a mechanical failure. The pump was replaced, t

F 4

27

. l NEW YORK POWER AUTilORITY 9

JAMES A. F112 PATRICK NUCLEAR 10WER PIANT  !

EFFLUENT AND WASTE DISPOSAL  ;

SEMI ANNUAL REPORT JULY 1991 DECEMBER 1991  !

A1 TAC 11 MENT NO 5 SEMI. ANNUAL

SUMMARY

OF llOUMLY METEOROLOGICAL DATA in accordance with Section 7.3.C.2 of Amendment 93 to the James A. FitzPatrick i Nuclear Power Plant Technical Specifications, an annual summary of rnetcorological data may be included and submitted in the Semiannual Radioactive Effluent Release Report ,

within 60 days after January 1 of each year.

Meteorological data for the period of January 1,1991 through December 31,1991 is not included in this report. it is on file and available upon request.

+

I I

l' 28

4 4

NEW YORK POWER AUTilORITY JAMES A. FITZPATRICK NUCLEAR POWER PIANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991 DECEMBER 1991  ;

NITACHMENT NO. 6 REPORT NOTES  !

Table 2A Section A and B and Table 2B Normal Linuld Emugg[3 The values for Tritium, Strontium 4 ltrontium 90, and Iron 55 were calculated from the most recent available sample data. If the actual sample data significantly alters the percent of allowable release limits, the report will be revised and redistributed.

L i

29

3 NEW YORK POWER AUTilORITY JAMES A. FrI2 PATRICK NUCLEAR POWER PLANT a

EFFLUENT AND WAS1T: DISPOSAL SEMI. ANNUAL REPORT JULY 1991 DECEMBER 1991 ADDENDUMI ASSESSMENT OF RADLATION DOSES TO Tile PUHLIC JANUARY . DECEMHER 1991 I

IN1RODUCTION 1.

The James A. FitzPatrick Nuclear Power Plant Radiological Efauent Technical Specifications (RLM) require an assessment of the radiation doses to the public due to radioactive liquid and gaseous effluents. This assessment of doses to the public is based on accepted methodologies found in the Offsite ,

Dose Calculation Manual (ODCM).

2. DOSE LIMITS ,

1 A. DOSE FROM LIOUID EEELUElfl3 (RETS 2.3)

Applicability Applies to doses from radioactive material in liquid effluents.

Ob.itrib'c To ensure that the dose limitations of 10 CFR 50, Appendix 1, are met. i 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.

I

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)

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

30

, , NEW YORK POWER AUTilORrrY JAhiES A. FI'l?. PATRICK NUCuiAR POWER PLANT EFF1.UENT AND WASTE DISPOSAL SEh11 ANNUAL REPORT JULY 1991 DECEhlllER 1991 AI)DENDUhl 1 (continued) i

.01deslits ,

1 To ensure that the dose rates at or beyond the site boundary from gaseous efnuer.ts do not exceed the annual dose limits of 10 CFR 20, for unrestricted areas.

SggriScations The dose rate at or beyond the $lte boundary due to radioactive materials  :

released from the plant in gaseous ef0uents shall be limited as follows:

1. Less than or equal to 1500 mrem / year to the whole body and less than or equal to 3000 mrem / year to the skin from noble gases.

C. AIR DOSE. NQBl II GASES (RETS 3.3)

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

.Qtdeclite To ensure that the noble gas dose limitations of 10 CFR 50, Appendix 1, 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 equal to 5 mrad from gamma radiation, and less than or equal to 10 mrad from beta radiation; and,
2. During any calendar year, to less than or equal to 10 mrad from gamma radiation and less than or equal to 20 mrad from beta radiation.

31 L

I '

NEW YORK POWER AUTilORITY JAMES A. FIT 7. PATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI. ANNUAL REPORT JULY 1991. DECEMBER 1991 ADDENDUM 1 (continued)

D. DOSE DUE TO 1QDINE 131. IODINE.133. 'IEITIUM AND RADIONUCUDES IN PARTICUIATE FORM (RETS 3.4)

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

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

Specificattom The dose to a member of the public at or beyond the site boundary from lodine 131, lodinc.133. Tritium, and radionuclides in particulate form with half lives greater than 8 days released from the plant in gaseous effluents shall be limited:

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

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

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

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

o 32

g '

NEW YORK POWER AtJIllORITY JAMES A. ITrZPATRICK NUCIE.AR POWER PIANT EITLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991. DECEMBER 1991 ADDENDUM 1 (coatlaued)

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

1. Less than or equal to 25 mrem / year to the whole body; and,
2. Less than or equal to 25 mrem / year to any organ except the thyroid which shall be limited to less than or equal to 75 rnrem/ year.
3. DOSE ASSESSMENT A. METilODOLOOY The assessment of radiation doses to the public due to radioactive liquid and gaseous effluents is performed in accordance with the ODCM, 'Ihe ODCM is based on methodologies and models suggested by the

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

  • Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the purpose of Evaluating Compliance with 10CFR50, Appendix I"(Regulatory Guide 1,109),

B. ASSUMPTIONS Dose calculations are performed using formulas and constants defined in the ODCM. Specific radioactive release activities used in the dose calculations are listed in the Semiannual Radioactive Effluent Release Reports (1.21 Reports) for the period of January 1,1991 to December 31,1991. llistorical meteorological data was used to generate tables of average dispersion factors, Locations of interest were identified from the 1991 land use census. Dispersion factors and locations of interest used in performing the dose calculations are listed in Table 2.

C. ASSESSMEtiT RESUL'I3

SUMMARY

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

33

g ,

, NEW YORK POWER AtJIllORTIY  !

JAMES A. F112 PATRICK NUClJIAR POWER PLANT EFFLUENT AND WASTE DISPOSAL .

SEMI. ANNUAL REPORT JULY 1991 DECEMBER 1991 ,

ADDENDUM 1 (continued)

4. 40 CFR IM DOSE ASSESSMENT A. METilODOLOGY Evaluation to demonstrate compliance with the 40 CFR 190 dose limits }

must be performed when the doses calculated for 10 CFR $0 compliance  !

exceed twice their respective limits. When additional dose assessment is required to demonstrated compliance with 40 CFR 190 it is performed in >

accordance with the ODCM. l B. RESULTS

SUMMARY

The cumulative dose contribution from liquid and gaseous efnuents for this report period were calculated and are listed on Table 1. The -

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

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

T 34

g NEW YORK POWER AUTIIORITY JAhtES A. FITZPAT.tlCK NUCLEAR POWER PLANT EFFLUENT AND WATTE DISIOSAL SEhil ANNUAL REPORT JULY 1991 DECEhtBER 1991 ADDENDUh11 (continued)

TABII 1 ANNUAL DOSE ASSESSh1ENT,1991 A. LIQUIDS OUARTER J 2 3 3 ANNUAL Organ (mrem) (a) 1.21E-01 5 31E4M 1.12E 04 7.92E-05 1.22E 01

% of Umit 2.42E400 1.06E-02 2.24E-03 1.58E-03 1.22E+ 00 Whole ik>dy (mrem) (b) 5.70E 02 2.85E4M 6.27E-05 3.80E 05 5.74E 02

% of Umit 3.801i400 1.90E-02 4.18E-03 2.53E-03 1.91E+ 00 B. NOBLE GASES OUARTER 1 2 3 3 AhNUAL Total Body (mrem /yr) 1.39E 02 8.37E 03 1.12E-02 7.23E 03 4.06E-t'2

% of Umit 1.11E 02 6.70E 03 8.94E-03 5.78E 03 8.13E 03 Skin (mrem /yr) 2.(ME 02 1.13E-02 1.66E 02 9.27E 03 5.76E.02

% of Umit 2.73E 03 1.51E-03 2.21E-03 1.24E-03 1.92E 03 Gamma (mrad) 1.45E 02 8.73E 03 1.16E-02 7.52E-03 4.23E 02

% of Umit 2.90E 01 1.75E 01 2.32E-01 1.50E 01 4.23E 01 Beta (mrad) 6.02E-03 2.39E-03 4.55E-03 1.90E-03 1.49E 02

% of Umit 6.02E 02 2.39E-02 4.55 E-02 1.90E-02 7.43E-02 C. IODINES AND PARTICULATES

_ QUARTER 1 2 3 3 ANNUAL Organ (mrem) (c) 2.66E 02 2.89E-02 6.75E4M 6.60E4M 5.68E-02

% of Limit 3.54E 01 3.85E-01 9.00E-03 8.80E 03 3.79E 01 (a) Dme to the Teen Liver primarily by the fish pathway.

(b) Dose to the Adult Whole llody primarily by the fish pathway.

(c) Dme to the Inf.mt Thyroid primarily by the goats milk pathway.

35

NEW YORK POWER AU1110RITY JAMES A. FITZPATRICK NUCIEAR POWER P! ANT t EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991 DECEMilER 1991 ADDENDUM 1 (continued)

TABLE 2 METEOROLOGICAL DATA AND LOCATIONS OF INTEREST GEOGRAPillC ATMOSPilERIC RECElrrOR LOCATION DISPERSION FACTOR A. IODINE & DISTANCII/ RELEASE X/O D/O 8 PARTICULATES DIRECTION POINT (sec/m') (1/m )

1. Garden 0.9 mi @ 82* E ST -

1.62E-09 Grazing Season 0.9 ml @ 82

  • H RX -

5.18E-09 Cary 0.9 mi @ 82*E TD -

4.74E 09 -

location No. 78 0.9 mi @ 82 *E RF -

5.18E-09 0.9 ml @ 82*E RW -

6.10E-09

2. Meat 1.2 ml @ 126*SE ST -

8.39E 10 Grazing Season 1.2 ml @ 126*SE RX -

1.72E 09 Parkhurst 1.2 ml @ 126*SE Til -

1.61E 09 location No. 26 1.2 ml @ 126*SE RF -

1.72E 09 1.2 mi @ 126*SE RW -

2.01E 09

3. Cor 2.2 ml @ 138'SE ST -

3.87E 10 Grazing Season 2.2 ml @ 138'SE RX -

6.57E 10 France 2.2 ml @ 138'SE Til -

6.30E.10 location No.10 2.2 ml @ 138*SE RF -

6.57E 10 2.2 mi @ 138'SE RW -

7.23E 10

4. Goat 2.5 mi @ 146*SE ST -

3.30E 10 Grazing Season 2.5 mi @ 146*SE RX -

5.33E 10 Nickolas 2.5 mi @ 146*SE Til -

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

5.33E 10 2.5 ml @ 146*SE RW -

5.80E 10

5. Resident Annual Average ,

a Inhalation 1.9 mi @ 90*E ST 3.16E 08 -

0.9 ml @ 82*E RX 2.81E-07 -

0.9 ml @ 82* E Til 2.41E-07 -

0.9 ml @ 82*E RF 2.81E-07 -

0.9 mi @ 82* E RW 4.38E-07 -

36

l NEW YORK POWER AlJIllORITY JAMES A. FITZPATRICK NUCLEAR POWER PLAhT I -

  • EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JULY 1991 DECEMBER 1991 ADDENDUMi (costlaued)

TABLE 2 METEOROLOGICAL DATA AND LOCATIONS OF INTEREST GEOGRAPlilC ATMOSPilERIC RECEI'f0R LOCATION DISPERSION FACTOR A. IODINE & DISTANCE / RELEASE X/O 8 D/O 2 PAR 11CULATES DIRECTION POINT (sec/m ) (1/m )

b. Deposition 0.9 mi @ 82*E ST -

1.63E 09 0.7 ml @ 118'ESE RX -

5.99E-09 0.7 mi @ 118'ESE TB -

5.45E-09 0.7 mi @ 118'ESE RF -

5.99E 09 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.%E 07 -

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

0.6 tal @ 90*E RW 7.47E-07 -

2. Total Body 0.6 ml @ 90* E ST(fe) 1.44 E-07 -

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

0.6 mi @ 90*E TB 3.%E 07 -

0.6 mi @ 90

  • E RF 4.83E-07 -

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

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

Annual Average 0.6 mi @ 90* E ST(fe) 1.44E 07 -

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

0.6 mi @ 90*E TB 3.%E-07 -

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

0.6 mi @ 90*E RW 7.47E 07 -

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

37 l

l

_ _._ __ . _ . . _ _ _ ,_ _ __ ._.

Retrieved from "https://kanterella.com/w/index.php?title=ML20090A304&oldid=2801759"