ML20214X129

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Semiannual Radioactive Effluent Release Rept,Jan-June 1986
ML20214X129
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 06/30/1986
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20214X108 List:
References
NUDOCS 8612100559
Download: ML20214X129 (35)
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Text

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

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY 1986 - JUNE 1986 DOCKET NO.: 50-333 LICENSE NO.: DPR-59 8612100559 860829 PDR ADOCK 05000333 R PDR

I' 1 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANN'JAL REPORT / JANUARY 1986 - JUNE 1986 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 radiations.and, (b) During any calendar year, to less than or equal to 10 mrad from gamma radiation and less than or equal to 20 mrad from beta radiation.

b. Tritium, 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 effluents shall be limited:

(a) During any calendar quarter to less than or equal to 7.5 mrem to any organs 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.

(1)

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:

(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 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 and to less than or equal to 5 mrem to any organs 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)

k SUPPLEMENTAL INFORMATION (continued)

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:

(1) 2.34E-03pci/ml* Quarter 1 (2) . 2.76E-03pci/ml* Quarter 2

3. Average Energy, E: (None Specified)
4. Measurements and Approximations of Total Radioactivity
a. Fission and activation gases: Continuous monitor on 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. Particulates: gamma spectral analysis of particulate filter on each release path. ,
d. Liquid effluents: gamma spectral analysis of each batch discharged, except composite analysis for Sr-89, Sr-90, Fe-55, and tritium.

--r r - - - , .---w-, .--4,--- , , , , - . , , - -,----,,g..- - - ,wn -,-, - ~ , n ,,-n.-_, , ney-,ne,..~mm,y-- , - - - -, ,

SUPPLEMENTAL INFORMATION (continued)

5. Batch Releases Liquid:

(1) Number of batch' releases: 4.40E+01 (2) Total time-period for' batch releases: 3.03E+03 (min)

(3) Maximum time period for batch release: 1.20E+02 (min)

-(4) Average time period for batch release: 6.88E+01 (min)

(5) Minimum time period for batch release: 5.00E+01 (min)

6. Abnormal Releases
a. Liquid: Quarter 1 Quarter 2 (1) Number of releases: None None (2) Total activity released: None None
b. Gaseous:

(1) Number of releases: None None (2) Total activity released: None None (4)

TABLE 1A NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1986 - JUNE 1986 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES EST.

TOTAL UNIT QUARTER 1 QUARTER 2 ERROR %

A. FISSION AND ACTIVATION GASES

1. Total release C1 2.01E+02 5.48E+02 <25%
2. Average release rate for period uCi/sec 2.58E+01 6.97E+01
3. Tech. Spec, limit  % *
  • B. 10 DINES-131 1.. Total iodine-131 Ci 2.34E-03 2.64E-03 -<25%
2. Average release rate for period uCi/sec 3.01E-04 3.36E-04
3. Tech.-Spec. limit  % *
  • C. IODINE-133 AND PARTICULATES
1. Iodine-133 and Particulates with half lives >8 days C1 1.38E-02 1.68E-02 -<25%
2. Average release rate for. period pCi/sec 1.77E-03 2.14E-03
3. Tech. Spec, limit  % * *
4. Gross alpha radioactivity Ci 5.12E-06 1.53E-06 <25%

D. TRITIUM

1. Total release Ci 4.62E-01 4.76E-01 -<25%
2. Average release rate'for period pCi/sec 5.94E-02 6.06E-02
  • E. PERCENT OF TECHNICAL SPECIFICATION LIMITS UNIT QUARTER 1 QUARTER 2 FISSION AND ACTIVATION GASE3
1. Quarterly gamma air dose limit  %- 7.98E-02 4.18E-01
2. Quarterly beta air dose limit  % 3.55E-02 3.84E-02
3. Yearly gamma air dose limit  % 3.99E-02 2.09E-01

. 4. Yearly beta air dose limit  % 1.78E-02 1.92E-02

< 5. Whole body dose rate limit  % 4.50E-04 1.83E-03

6. Skin dose rate limit  % 1.81E-04 5.53E-04 HALOGENS, TRITIUM AND PARTICULATES WITH HALF-LIVES >8 DAYS
7. Quarterly dose limit (organ)  % 8.33E-01 7.99E-01 8.-Yearly dose limit (organ)  % 4.17E-01 3.99E-01
9. Organ dose rate limit  % 1.18E-04 1.02E-04 (5)

' -- m --.

TABLE IB NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT'AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1986 - JUNE 1986 GASEOUS EFFLUENTS--ELEVATED RELEASE

-CONTINUOUS MODE NUCLIDES RELEASED UNIT' . QUARTER 1 QUARTER 2

1. Fission gases ArgonJ41 C1 1.47E+00 1.59E+01 Krypton-85m Ci 7.17E-01 7.85E+00 Krypton-87 Ci 4.61E+00 5.41E+01 Krypton-88 Ci- 4.03E+00 8,93E+01

, Xenon-133 Ci 3.88E+00 2.58E+01 Xenon-135 Ci 7.39E+00 1.06E+02 Xenon-135m Ci 4.45E+00 2.51E+01 Xenon-138 Ci- 1.60E+01 1.01E+02

2. Iodines

' Iodine-131- Ci 3.52E-04 1.56E-03 Iodine-133 Ci 2.01E-03 6.06E-03 4

3. Particulates Manganese-54 Ci 3.29E-07 6.94E-06 Cobalt-58 Ci ND 1.06E-06 Cobalt-60 Ci 4.42E-07 2.38E-06 Strontium-89 Ci 2.37E-05 1.76E-06 Strontium-90 Ci 8.89E-08 9.03E-08 Cesium-137 Ci 8.97E-06 5.84E-05 Barium-Lanthanum-140 Ci 1.44E-05 1.31E-04

. Cerium-141 Ci 3.21E-08 ND Silver-110m Ci ND 6.30E-06

c. Cesium-136 Ci ND 1.52E-06 4

There are no batch releases for this period.

ND - None detected.

(6) t , s~. - -,..-~p , - , . . - , -er- , m ,,m-,. ,----,-ww r----r-m-. .,w- - --- . , , , , , , , - , - -- -v, - - ---

c -

. i TABLE 1C NEW YORK POWER AUTHORITY.

-JAMES A. FITZPATRICK' NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1986 - JUNE 1986 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES-CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2

1. Fission gases Krypton-85m C1 1.48E+00 5.09E+00 Krypton-87 Ci 9.65E-01 ND Krypton-88 Ci 4.59E+00 1.33E+01 Xenon-131m Ci 8.01E+01 6.37E+00 Xenon-133 Ci 8.30E+00 1.78E+01 Xenon-133m Ci 5.56E-01 2.60E+01 Xenon-135 Ci 6.32E+00 1.61E+01 Xenon-135m Ci 2.27E+00 3.41E+00 Xenon-138 ~Ci 2.88E+01 3.48E+01 Xenon-137 Ci 2.45E+01 ND 2.- Iodines Iodine-131 C1 1.99E-03 1.08E-03 Iodine-133 Ci 1.08E-02 9.73E-03
3. Particulates Chromium-51 Ci 2.59E-05 ND Manganese-54 Ci 3.18E-05 2.52E-06 Cobalt-58 C1 1.25E-05 ND Cobalt-60. C1 1.20E-04 2.49E-05 Zinc-65 .

Ci 1.61E-06 8.61E-06 Strontium-89 Ci 3.37E-06 7.15E-08 Strontium-90 C1 1.26E-08 1.27E-08 Molybdenum-99 Ci 5.37E-05 ND Silver-110m Ci 5.07E-05 2.36E-05 Barium-Lanthanum-140 Ci 6.47E-04 7.44E-04 Cerium-141 Ci 1.52E-05 7.54E-07 Cobalt-57 C1 2.53E-07 3.58E-07 Antimony-124 Ci 1.63E-06 ND Cesium-134 Ci 1.34E-06 ND There are no b'atch releases for this period.

ND - None detected.

(7)

TABLE 2A NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1986 - JUNE 1986 LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES EST.

TOTAL UNIT QUARTER 1 QUARTER 2 ERROR %

A. FISSION AND ACTIVATION PRODUCTS

1. Total release (not including tritium and alpha) Ci 9.86E-03 1.65E-04 125%
2. Average diluted concentration during period pCi/ml 5.98E-11 8.59E-13
3. Applicable limit  % *
1. Total release C1 3.16E+00 1.44E-01 125%
2. Average diluted concentration during period pCi/ml 1.92E-08 7.50E-10
3. Applicable limit  % *
  • C. DISSOLVED AND ENTRAINED GASES
1. Total release Ci 6.82E-04 1.82E-05 125%
2. Average diluted concentration during period pCi/ml 4.13E-12 9.48E-14
3. Applicable limit  % *
  • D. GROSS ALPHA RADIOACTIVITY Total release C1 1.14E-05 1.90E-07 125%
  • - See attached " PERCENT TECHNICAL SPECIFICATION LIMITS".

ND - None detected.

NA - Not applicable.

(8)

LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES (continued)

UNIT QUARTER 1 QUARTER 2 E. VOLUME OF WASTE RELEASED (PRIOR.TO DILUTION) Liters 1.98E+06 9.01E+04 F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters 1.65E+11 1.92E+11

  • G. PERCENT TECHNICAL SPECIFICATION LIMITS UNIT QUARTER 1 QUARTER 2
1. Quarterly whole body dose  % 1.84E-01 1.54E-04
2. Quarterly organ dose  % 9.68E-03 1.16E-03
3. Annual whole body dose  % 9.20E 7.70E-05
4. Annual organ dose  % 4.84E-03 5.78E-04 4

J (9) t 5

g i TABLE 2B NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1986 - JUNE 1986 LIQUID EFFLUENTS BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 Manganese-54 Ci 6.34E-04 3.32E-05 Cobalt-60 Ci 7.05E-03 1.10E-04 Xenon-133 C1 1.01E-04 ND Xenon-135 Ci 5.82E-04 1.82E-05 Cerium-144 Ci 5.04E-06 1.22E-04

' Chromium-51 C1 2.95E-05 ND Cobalt-57 C1 1.29E-05 ND Zinc-65 Ci 7.15E-04 ND Zirconium-97 Ci 2.26E-04 ND Niobium-95 C1 1.20E-06 ND Technitium-99m Ci 3.10E-07 ND Cesium-134 Ci 3.25E-06 ND Cesium-137 Ci 4.65E-04 ND Barium Lanthanum-140 C1 2.61E-06 ND Cerium-141 C1 1.53E-06 ND Niobium-95m Ci ND 4.32E-06 There were no continuous mode discharges during this period.

ND - None detected.

I f

(10)

t TABLE 3A NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1986 - JUNE 1986 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 50.32 25%

evaporator bottoms, etc. C1 118.12 25%

b. Dry compressible waste, m3 160.94 25%

contaminated equipment, etc. C1 161.6 25%

c. Irradiated components (None)
d. Oil solidified in cement m3 9.09 25%

Ci 0.0094 25%

2. Estimate of Major Nuclide Composition Isotope  % Abundance Est. Error %

Cobalt-60 43.64% 10 Iron-55 36.00% 10 Manganese-54 5.33 % 10 Cesium-137 5.00 % 10 Zinc-65 3.08 % 10 Chromium-51 2.75 % 10 Cesium-134 2.04 % 10 Cobalt-58 1.57 % 10 Nickel-63 0.2  % 10 Iron-59 0.17 % 10 Carbon-14 0.03 % 10 Lanthanum-140 0.02 % 10 Strontium-89 0.01 % 10 Plutonium-241 0.01 % 10 Cerium-144 0.006% 10 i

Hydrogen-3 0.005% 10 Strontium-90 0.004% 10 Cerium-141 0.003% 10

3. Solid Waste Disposition TRANSPORTA-SHIPMENT QTY. TION MODE DESTINATION Type a 24 Truck Barnwell, SC Type b and d 4 Truck Richland, WA

! B. IRRADIATED FUEL SHIPMENTS (NONE)

(11)

TABLE 3B NEW. YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1986 - JUNE 1986 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. NRC CLASS "A"

1. Compacted /Noncompacted Dry Waste Container Type: 107 ft3 steel box (LSA)  ;

Solidification Media: None Total Volume: 3317 ft3 93.94 m3 No. of Shipments: 4 Type: Flat bed Mode: Truck Principal- Quantity Isotopes Curies  % Abundance Determination Cobalt-60 0.34S' 46.4  % E Iron-55 0.207 27.7  % E Chromium-51 -0.066 8.8  % E Cesium-137 0.044 5.86 % E i Manganese-54 0.044 5.8  % E Cesium-134 0.023 3.1  % E

-Zinc-65 0.018 2.4  %. E Carbon-14 0.00011 0.015% E Hydrogen-3 0.00001 0.001% E TOTAL: 0.750 curies (estimated)

E = Estimated (12)

s SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (continued)

A. NRC Class "A" (continued)

2. Compacted /Noncompacted Dry Waste Container Type
107 ft3 Steel Box (LSA)

Solidification Media: None Total Volume: 3317 ft3 93.94 m3 No. of Shipments: 4 Type: Flat Bed

Mode
Truck Principal Quantity s Isotopes Curies  % Abundance Determination Cobalt-60 0.348 46.4 % E Iron-55 0.207 27.7 % E Chromium-51 0.066 8.8 % E Cesium-137- 0.044 5.86 % E Manganese-54 0.044 5.8 % E
Cesium-134 0.023 3.1 % E i Zinc-65 0.018 2.4 % E Carbon-14 0.00011 0.015% E Hydrogen-3 0.00001 0.001% E TOTAL: 0.750 curies (estimated)

E = Estimated 1

l i

1 4

r 6

(13) l

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (continued)

' A. NRC Class "A" (continued)

3. Solified Powdered Resin / Filter Sludge Container Type: 182 ft' 107 ft 3 steel liner (LSA)

Solidification Media: Cement Tctal Volume: 685 ft3 19.39 m3 No. of Shipments: 5 ~

Type: Cask '

Mode: Truck Principal Quantity Isotopes Curies  % Abundance Determination Cobalt-60 43.1 42.4% M Iron-55 25.97 25.6% E Manganese-54 7.63 7.5% M Chromium-51 7.47 7.4% M Cesium-137 5.07 5.0% M Zinc-65 4.61 4.5% M Cobalt-58 3.87 3.8% M Cesium-134 2.17- 2.1% M Nickel-63 0.5 0.5% E Iron-59 0.47 0.5% E Cerium-144 0.014 0.01% E Carbon-14 0.013 0.01% E

. Plutonium-241 0.022 0.02% E Strontium-89 0.016 0.02% E Lanthanum-140 0.056 0.06%. E Nickel-59 0.006 0.006% E Cerium-141 0.003 0.003% E 4

TOTAL: 101.6 curies (measured / estimated)

M = Measured E = Estimated 4

(14)

SOLID' WASTE.AND IRRADIATED FUEL SHIPMENTS (continued) 1 A. NRC Class "A"-(continued)

4. -Solified Bead Resin Container Type: 182 ft3 steel liner (LSA)

Solidification Media: Cement Total Volume: 1092 ft3 30.93 m3 No. of Shipments: 6 Type: Cask Mode: Truck Principal Quantity Isotopes Curies  % Abundance Determination Cobalt-60 8.05 48.7  % M Iron-55 5.52 33.4  % E Manganese-54 0.851 5.2  % M Cesium-137 0.837 5.1  % M Zinc-65 0.504 3.1  % M Cesium-134 0.358 2.17 % M Cobalt-58 0.139 0.8  % M Chromium-51 0.120 0.7  % M Carbon-14 0.079 0.48 % E Nickel-63 0.028 0.2- % E Strontium-89 0.015 0.09 % E Cerium-141 0.005 0.03 % E-Iron-59 0.004 0.02 % E

., Hydrogen-3 0.004 0.02 % E Plutonium-241 0.003 0.02 % E Strontium-90 0.003 0.02 % E Lanthanum-140 0.003 0.017% M j Cerium-144 0.0005 0.003%- E d

TOTAL: 16.518 curies (measured / estimated)

M = Measured E = Estimated 1

4 (15)

u

+

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (continued)

A. NRC Class "A" (continued)

5. Solified Evaporator Bottoms Container Type: 182 ft3 steel liner (LSA)

Solidification Media: Cement Total Volume: 2366 ft3 67 m3 No. of Shipments: 13 Type: Cask Mode: Truck Principal Quantity Isotopes Curies  % Abundance Determination Cobalt-60 70.55 43.9 % M Iron-55 68.89 42.8 % E Cesium-137 7.98 5.0 % M Manganese-54 6.32 3.9 % M Zinc-65 3.49 2.2 % M Cesium-134 3.16 2.0 % M Cobalt-58 0.39 0.24 % M Nickel-63 0.034 0.02 % E Hydrogen-3 0.011 0.007% E Strontium-90 0.009 0.006% E TOTAL: 160.85 curies (measured / estimated)

M = Measured E = Estimated (16)

2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (continued)

B. NRC CLASS "B"

1. Solidified Powdered Resin / Filter Sludge Container Type: 107 ft3 steel liner (LSA)

Solidification Media: Gement Total Volume: 428 ft3 12.12 m3 No. of Shipments: 4 Type: Cask Mode: Truck Principal Quantity Isotopes- Curies  % Abundance Determination Cobalt-60 28.8- 34.7 % M Iron-55 27.2 32.8 % E Cesium-137 7.3 8.8 % M Manganese-54 5.6 6.7 % M Strontium-89 3.7 4.5 % E Cesium-134 3.28 3.9 % M Chromium-51 2.57 3.0 % M Zinc-65 1.77 2.0 % M i Strontium-90 1.01 1.2 % E Cobalt-58 0.85 1.0 % M Nickel-63 0.77 0.9 % E Nickel-59 0.3 0.4 % E

TOTAL
83.0 curies (measured / estimated) i-i (17)

TABLE 4 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL

-SEMIANNUAL REPORT / JANUARY 1986 - JUNE 1986 SEMIANNUAL

SUMMARY

OF HOURLY METEOROLOGICAL DATA 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 covered by this report will be included in the Semiannual Radioactive Effluent Release Report for the period of July 1, 1986 - December 31, 1986.

(18)

TABLE 5 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1, 1986 - JULY 31, 1986

SUMMARY

OF CHANGES 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 Surveillance Procedures (PSP) and Offsite Dose Calculation Manual (ODCM) 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 PSP during this report period.

(19)

TABLE 5 (Continued)

NEW YORK POWER AUTHORITY JAMES A. FITZPATR.ICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1986 - JUNE 1986

SUMMARY

OF CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL CHN. REVISION 3 DESCRIPTION OF CHANGE AFFECT ON NO. SECTION/PAGE (JUSTIFICATION) ACCURACY / RELIABILITY

1. Section 3.5 The calculational method This change Pages 17, 17a for projecting liquid doses improves the 17b, 17c was upgraded. Revised accuracy and Liquid Dose methodology provides for reliability of Proj ection, the use of historical dose the liquid dose Determination of factors (Ci/ gal, dose /Ci) projection need to operate which can be used in leiu calculational liquid radwaste of prior month dose factors methodology.

treatment system, when a no discharge con-dition exists for the prior month. Provisions are also made in the calculaticnal methodology for pertinent factor such plant status, systems operability and his-torical waste volumes to be used as appropriate Section 3.5.2.b. includes a method for calculating pro-jected dose prior to the re-leases of each rad waste discharge.

(20)

TABLE 5 (Continued)

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

SEMIANNUAL REPORT / JANUARY 1986 - JUNE 1986

SUMMARY

OF CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL CHN. REVISION 3 DESCRIPTION OF CHANGE AFFECT ON NO. SECTION/PAGE (JUSTIFICATION) ACCURACY / RELIABILITY

2. Table H-1 Sample. map location numbers The accuracy and pages 280, 281, were changed. Change was reliability of the 282 made so that sample ODCM calculations Radiation location numbers are not effected by Environmental were consistent with this change.

Monitoring those used for the Sample Locations Nine Mile Point Nuclear Power Station 1 Environmental Program which is a common program with the J. A. FitzPatrick NPP Environmental Monitoring Program.

Shoreline sediment loca- This change corrects tion collection site an error in the en-was incorrectly listed vironmental sample in the previous-revision location table which as NMPNS shoreline. This

! increases the accu-was corrected to' Sunset racy of the ODCM.

. Bay Shoreline which is the

actual sample location.

Table H-1 Sample locations for This change corrects pages 280, 281, Iodine and Particulate, sample location 282 Milk and Food Products description errors Radiation were listed as "to be identified in l Environmental determined" (TBD) in pre- Table H-1 and as a Monitoring vious revisions. These result increases Sample Locations sample locations were de- the accuracy of the fined in revison 3 in terms ODCM.

of sample location number, distance and direction.

l l

(21) i 1

{

TABLE 6 NEW YORK POWER AUTHORITY

~ JAMES A. FITZPATRICK-NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1986 - JUNE 1986 ,

DEVIATIONS FROM THE REQUIRED ENVIRONMENTAL SAMPLING SCHEDULE EXCEPTION TO THE PROGRAM

1. The air sampling pump at the R2 offsite environmental sampling station was inoperable from January _ 7, 1986 (1815 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.906075e-4 months <br />) to January 14, 1986 (0848 hours0.00981 days <br />0.236 hours <br />0.0014 weeks <br />3.22664e-4 months <br />). Inoperability was caused by an electrical malfunction.
2. The air sampling pump at the R3 offsite environmental sampling station was inoperable from May 14, 1986 (1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br />) to May 20, 1986 (0835). Inoperability was caused by an electrical malfunction.

(22)

TABLE 8 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1986 - JUNE 1986 REPORT NOTES

1) Table 2A,'Section B. Tritium and Table 2B Second Quarter liquid Tritium, Strontium-89, Strontium-90 and Iron-55 calculated from First Quarter Sample Data.
2) If actual sample data significantly alters the report release concentrations and percent of allowable release limits the report will be revised and redistributed.

s (23)

~

ATTACHMENT 1 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JANUARY 1986 ODCM Revision 3 Attached are the pages affected by revision 3 of the Off-site Dose Calculation Manual (ODCM).

(24)

h 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 76-/p Date J/g/B%

Approved By: / i ResidentManagqf Approved By: ky - A RadiologicalandEnvdnmental EFH G O ND Servi es Superintendent Page No.: 11 2 3 4 5 6 7 8 9 10 11 12 13 14 15 Rev. No.: 22 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 16 17abc 18 19 20 21 22 23 24 25 26 27 28 29 30 Rev. No.: 2 3333 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 31 37- 33 34 35 36 37 38 39 40 41 42 43 44 45 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 106 107 108 109 110 111 112 113 114 115 116 117 118 119 120 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2

} Page No.: 121 122 123 124 125 126 127 128 129 130 131 132 133 134 135 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 136 137 138 139 140 141 142 143 144 145 146 147 148 149 150 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No : 151 152 153 154 155 156 157 158 159 160 161 162 163 164 165 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 166 167 168 169 170 171 172 173 174 175 176 177 178 179 180 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 181 182 183 184 185 186 187 188 189 190 191 192 193 194 195 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 196 197 198 199 200 201 202 203 204 205 206 207 208 209 210 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 211 212 213 214 215 216 217 218 219 220 221 222 223 224 225 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 226 227 228 229 230 231 232 233 234 235 236 237 238 239 240 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 241 242 243 244 245 246 247 248 249 250 251 252 253 254 255 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 256 267 258 259 260 261 262 263 264 265 266 267 268 269 270 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 271 272 273 274 275 276 277 278 279 280 281 282 283a 284 285 Rev. No.: 2 2 2 2 2 2 2 2 2 3 3 3 33 , 2 2 Page No.: 286 287 288 289 290 291~292 293 294 Rev. No.: 2 2 2 2 2 2 2 2 2 Rev No. 3 Date 02/86 S - = C

, , REFERENCE ONLY 3.5 Dose Projections - Determination of Need to Operate Liquid Radwaste Treatment System 3.5.1 Requirements Technical Specifications Appendix B Section 2.4 requires that appropriate subsystems of the liquid radwaste treat-2 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

< the critical age group to be used for the dose projection.

The following calculating methodology is provided for per-forming this dose projection.

a. Monthly Dose Projection Each month the expected dose to man shall be pro-jected. Projections shall be based on historical or prior month dose / Curie and historical or prior month concentration conversion factors. The h;storical 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 Dept.

(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) Proj ected plant operational status (run, shutdown, refuel, etc.).

(b) Status of radwaste treatment equipment.

Equipment which is inoperable, such as the waste concentrator, should be fac-tored 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.)

Rev. No. 3 Date 02/86 Page 17 of ODCM

- , - - - - - - _ . - . - _..--e-.,. ~ , . , ,e,,

n REFERENCE ONLY '

(d) Additional factors. indicating ithat' ,.

actual liquid releases couldt differ /-

significantly in the next month.' '

i  ! ,

(e) Historical liquid waste discharge .

volumes. >

a (2) Determine which dose /Ci and Ci/ gal conversion j factors .should be used. Historicall' conversion factors can be used. Prior month ' conversion

+

. factors may be used if they are more represen- '

tative of current release conditions. In thh ' '

event that there was no release of liquid radwance ,

during the prior month, then the historical con- ,

version factors can be used if liquid releases are expected during the projection . month.

.r (a) The prior month dose /Ci convkrsion factor is calculated by obtaining the results of the prior month adult total body and adult liver dose calculation. /r

, r /L (b) Divide this' dose by the total,n'usber of ')

Curies released from the plant- during ,

this same time period. This. calculation yields a dose per Curie conversion fac-tor for the most recent prior enlendar month. g'k (c) The prior month Ci/ gal cencen$ ration factor is calculated by obtaining the-

total number of Curies released from l the plant during the prior' month.

Divide the Curie total by the total '

number of gallons of waste discharged 3 during this same time period.f This -

! calculation yields the Ci/ gal concen- '

tration conversion factor for the most,

~

i recent month. <

1 y( [

(3) Multiply the estimated volume of liquid,radwaste.

to be discharged, by the historicalc or >. prior' ,

month dose /Ci and Ci/ gal conversion > dhetors.!

This calculation yields a dose estitv.te to the -

j adult total body and adult liver for the pro-jected month. _ [

(a) T y xC g

xD etb "

t.F (Adult Total y Body Dose) ',

(b) Ty xC g xD el = TD 1 (Adult Liver '

' Dose) 4

- s

i' Rev. No. 3 .Date 02/86 i Page 17a_ of .ODCf f [

'3

___L__.__ __

REFERENCE ONLY Where:

Ty =

Total volume of radwaste to be dis-charged during the month in gallons l (estimated) 1

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

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 c 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, the l appropriate subsystems of the liquid radwaste system shall be used to reduce the radioactivity levels prior to release.

b. Batch Dose Projections The projected dose due to release of each batch can be made prior to the release of the batch. The proj ec-tion of the dose related to each batch allows for an accurate method of estimating the dose from each~ batch

! prior to release and confirms the need to operate the

subsystems of the radwaste system. The projection of i -dose based on each batch release helps to eliminate any inaccuracies as a result of using historical or estimated values in the monthly projection. The use of this dose proj ection on a batch release basis is not required by the technical specification and is used at the discretion of the Radiological and En-vironmental Services Management.

The method is has id on total body dose and critical organ dose O f ec'"; as calculated in step 3.4.2. The adult is tra gr' . f. cal age group to be used for the dose proj ect.1on.

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

(1) Obtain the latest result of the monthly calcula-tion of the adult total body and adult liver dose (step 3.4.2).

~

Rev. No. 3 Date 02/86 Page 17b of ODCM l

.,_ a44 he w .,% -

REFER ~ENCE ONLY (2) Divide this dose by the total number of Curies released from the plant during the month. This yields a dose per Curie conversion factor for the most recent calendar month.

(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 calculated in step (1), above. This yields the 31 day total dose proj ected for the release of the current batch.

(5) If the calculated dose is greater :han 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.

i ah e

l' I

Rev. No. 3 .Date 02/86 Page 17c of ODCM

4 REFERENCE ONLY  :

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

^

TABLE H-1 RADIATION ENVIRONMENTAL MONITORING SAMPLING LOCATIONS 4

Type of Map Semple Location Collection Site Location I

Redioiodine and 1 Nine Mile Point Road 1.8 mi @ 88* E Particulates (air) North Redioiodine and 2 Co. Rt. 29 & Lake Road 1.1 mi-@ 104* ESE Particulates (air)

Radioiodine and 3 Co. Rt. 29 1.5 mi @ 132* SE Particulates (air)

Radioiodine and 4 Village of Lycoming, NY 1.8 mi @ 143* SE Pcrticulates (air)

Radioiodine and 5 Montario Point Road 16.4 mi @ 42 NE Particulates (air)

Direct Radiation (TLD) 6 North Shoreline Area 0.1 mi @ 5* N Direct Radiation (TLD) 7 North Shoreline Area 0.1 mi @ 25* NNE Direct Radiation (TLD) 8 North Shoreline Area 0.2 mi @ 45 NE Direct Radiation (TLD) 9 North Shoreline Area 0.8 mi @ 70* ENE Direct Radiation (TLD) 10 JAF East Boundary 1.0 mi @ 90 E

Direct Radiation (TLD) 11 Rt. 29 1.1 mi @ 115 ESE Direct Radiation (TLD) 12 Rt. 29 1.4 mi @ 133* SE i

Direct Radiation (TLD) 13 Miner Road 1.6 mi @ 159 SSE Direct Radiation (TLD) 14 Miner Road 1.6 mi @ 181* S ~

i Direct Radiation (TLD) 15 Lakeview Road 1.2 mi @ 200 SSW Direct Radiation (TLD) 16 Lakeview Road 1.1 mi @ 225* SW 1

Site Meteorological Tower 0.7 mi @ 250* WSW

Direct Radiation (TLD) 17

! Direct Radiation (TLD) '

18 Energy Information Center 0.4 mi @ 265* W

- Date 02/86 Page 280 of ODCM g Rev.' No.

3

,..e.

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

TABLE H-1 (Continued)

RADIATION ENVIRONMENTAL MONITORING SAMPLING LOCATIONS Type of Map Sample Location Collection Site Location Direct Radiation (TLD) 19 North Shoreline Area 0.2 mi @ 294 WNW Direct Radiation (TLD) 20 North Shoreline Area 0.1 mi @ 315 NW Direct Radiation (TLD) 21 North Shoreline Area 0.1 mi @ 341 NNW Direct Radiation (TLD) 22 Demster Beach Road 4.8 mi @ 97* E Direct Radiation (TLD) 23 Leavitt Road 4.1 mi @ 111* ESE Direct Radiation (TLD) 24 Rt. 104 4.2 mi @ 135 SE Direct Radiation (TLD) 25 Rt. 51A 4.8 mi @ 156 SSE Direct Radiation (TLD) 26 Maiden Lane Road 4.4 mi @ 183* S Direct Radiation (TLD) 27 Rt. 53 4.4 mi @ 205* SSW Direct Radiation (TLD) 28 Co. Rt. 1 4.7 mi @ 223 SW Direct Radiation (TLD) 29 Lake Shoreline 4.1 mi @ 237* WSW Direct Radiation (TLD) 30 Phoenix, NY Control 19.8 mi @ 170 S-SSE Direct Radiation (TLD) 31 SW Oswego Control 12.6 mi @ 226* SW Direct Radiation (TLD) 32 Scriba, NY 3.6 mi @ 199* SSW Direct Radiation (TLD) 33 Alcan Aluminum, Rt. lA 3.1 mi @ 220 SW Direct Radiation (TLD) 34 Lycoming, NY 1.8 mi @ 143 SE Direct Radiation (TLD) 35 New Haven, NY 5.3 mi @ 123* ESE Direct Radiation (TLD) 36 W. Boundary, Bible Camp 0.9 mi @ 237 SW-WSW Direct Radiation (TLD) 37 Lake Road 1.2 mi @ 101* E-ESE Surface Water 38 OSS Inlet Canal 7.6 mi @ 235* SW-WSW Surface Water 39 JAFNPP Inlet Canal 0.5 mi @ 70* ENE l

Rev. No. 3 Date 02/86 Page 281 of ODCM ,

l

- . REFERENCE ONLY l JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE' DOSE CALCULATION MANUAL (ODCM)

, TABLE H-1 (Continued)

RADIATION ENVIRONMENTAL MONITORING SAMPLING LOCATIONS Type of Map Semple Location Collection Site Location Shoreline Sediment 40 Sunset Bay Shoreline 1.5 mi @ 80* E Fish 41 NMP Site Discharge Area 0.3 mi @ 315* NW and/or i Fish 42 NMP Site Discharge Area 0.6 mi @ 55 NE Fish 43 Oswego Harbor Area 6.2 mi @ 235* WSW Milk 44 Milk Location #50 9.3 mi @ 93* SE Milk 45 Milk Location #7 5.5 mi @ 107* ESE i Milk 46 Milk Location #16 5.9 mi @ 190* S i

Milk 47 Milk Location 140 15.0 mi @ 223* SW Food Product 48 Vegetation Location #1 0.6 mi @ 81.5* E (JAF Site Boundary)

Food Product 49 Vegetation Location #2 0.9 mi @ 75.0* ENE ,

(JAF Site Boundary)

Food Product 50 Vegetation Location #3 0.9 mi @ 105.5 ESE (JAF Site.Eoundary)

Food Product 54 Vegetation Location 14 15.0 mi @ 223 SW (McMillen)

Rev. No. 3 Date 02/86 Page 282 of ODCM ,

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

, , FIGURE H-1/ ENVIRONMENTAL SAMPLING LOCATION MAP REFERENCE -ONLY

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Rev. No. 3 Date 02/86 Page 283_ of ODCM

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- OFFSITE DOSE CALCULATION MANUAL (ODCM) 6 .* FIGURE H-1/ ENVIRONMENTAL SAMPLING LOCATION MAP

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