Text

Semi-Annual Radioactive Effluent Release Rept for Period 960701-1231
	ML20135D027
Person / Time
Site:	FitzPatrick
Issue date:	12/31/1996
From:	Michael Colomb; POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	;
Shared Package
ML20135D029	List: JAFP-97-0073, Forwards Semi-Annual Radioactive Effluent Release Rept for Period of 960701-1231 & Rev 4 to Radiological Effluent Controls & Odcm; ML20135D027; ML20135D031;
References
	NUDOCS 9703050018
	Download: ML20135D027 (30)
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l NEW YORK POWER AUTIIORITY JAMES A.FITZPATRICK NUCLEAR POWER PLANT )

EFFLUENT AND WASTEDISPOSAL SEMI-ANNUAL REPORT 1

JULY 1,1996 - DECEMBER 31,1996 iJ DOCKET NO.: 50-333 LICENSE NO.: DPR-59 l

9703050018 970228 PDR ADOCK 05000333 PDR, R

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i NEW YORK POWER AUTIIORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996

$ SUPPLEMENTAL INFORMATION FACILITY: JAFNPP LICENSEE: NEW YORK POWER AUTHORITY

1. Technical Specification Limits

a. Fission and Activation Gases:

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

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

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

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

and, l

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

b. Tritium, lodines and Particulates, Half Lives > 8 days: l (1) The dose to a member of the public at or beyond the site boundary from Iodme-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. ,

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(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: i i

(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 i

half-lives greater than 8 days (inhalation pathway only).

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j 1 e i NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL i

- SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 '

- SUPPLEMENTAL INFORMATION (Continued)

c. Liquid Effluents: ;

(1) The concentration of radioactive materials released to the unrestricted areas

' shall not exceed the values specified in 10 CFR 20, Appendix B, Table II,-

Column 2. For dissolved or entrained noble gases the concentration shall be i limited to 2.00E-04 Ci/ml. ;

4 (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 j follows: .

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(a) During any calendar quarter, limited to less than or equal to 1.5 mrem to !

i the whole body and to less than or equal to 5 mrem to any organ; and, !

i l' (b) During any calendar year, limited to less than or equal to 3 mrem to the l whole body and to less than or equal to 10 mrem to any organ. .l.

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2. Maximum Permissible Concentrations j l

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a. Fission and activation gases: (None specified) ;

i b. Iodines: (None specified)

c. Particulates, half-lives >8 days: (None specified)

d. Liquid effluents: Ouader 3 Ouarter 4 ;

(1) Fission and activation NONE 6.% E-05 products (mixture MPC)

(pCi/ml) i (2) Tritium (pCi/ml) 3.00E-03 3.00E-03 l l

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

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l NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 l SUPPLEMENTAL INFORMATION (Continued) l

3. Averaee Enerev (None specified) l

4. Measurements and Approximations of Total Radioactivity

a. Fission and Activation Gases: Continuous monitor on each release path calibrated to a marinelli grab sample analyzed by gamma spectroscopy; bubbler grab sample analyzed for Tritium.

b. Iodines: Gamma spectral analysis of charcoal cartridge and particulate filter on each release path.

c. Particulates: Gamma spectral analysis of each particulate filter and charcoal cartridge for each release path. A four week per quarter composite of ,

patticulate filters for each release path for Strontium-89 and Strontium-90. One w:ek per month particulate filter for each release path for gross alpha.

d. ~ Liquid Effluents: Gamma spectral analysis of each batch discharged, except composite ar.alysis for Strontium-89, Strontium-90, Iron-55, Tritium, and Alpha. j

e. Solid Waste: Gamma spectral analysis of a representative sample of each waste shipment. Scaling factors established from off-site composite sample analyses to ,

estimate concentration of non-gamma emitters. Low activity trash shipments, curie content estimated by dose rate measurement and application of appropriate scaling factors.

f. Error Estimation Method: Overall error for sampling and analysis estimated by combining individual errors using error propagation methods. This process is composed of determinate and undeterminate errors.

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

Undeterminate - Random counting error estimated using accepted statistical l calculations Page 3 of 29 l

NEW YORK POWER AUTIIORITY l l ,

JAMES A FITZPATRICK NUCLEAR POWER PLANT i

! EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 i SUPPLEMENTAL INFORMATION (Continued) l I

l :. Batch Releases l

l a. Liquid: Ouarter 3 Ouarter 4 (1) Number of batch releases: NONE 6.00E+00 1

(2) Total time period for batch NONE 4.64E+02

release: (min)

(3) Maximum time period for NONE 1.02E +02 batch release: (min) l j (4) Average time period for NONE 7.73E+01 j batch release: (min) l l

(5) Minimum time period for NONE 6.80E+01 l

l batch release: (min) j

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

6. Abnormal Releases

a. Liquid: Ouarter 3 Ouarter 4 (1) Number of releases: NONE NONE (2) Total activity released: NONE NONE i

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b. Gaseous (1) Number of releases: NONE NONE ;

(2) Total activity released: NONE NONE l

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NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES EST TOTAL

. UNIT OUARTER 3 OUARTER 4 ERROR %

A. FISSION AND ACTIVATION GASES

1. Total Release Ci 1.66E+02 4.28E+02 s2.50E+01

2. . Average release rate for period pCi/sec 2.09E+01 5.38E+01

3. Tech. Spec. Limit B. IODLNE-131

1. Total lodine-131 Ci 5.80E-04 1.24E-03 s2.50E+01

2. Average release rate for period pCi/sec 7.29E-05 1.55E-04

3. Tech. Spec. Limit C. PARTICULATES

1. Particulates with half-lives

> 8 days Ci 6.27E-05 1.02E-04 s3.60E+01

2. Average release rate for period pCi/sec 7.89E-06 1.28E-05

3. Tech. Spec. Limit

4. Gross alpha radioactivity Ci 5.SSE-07 3.49E-06 s2.50E+01 l). TRITIUM

1. Total Release Ci 8.80E+00 3.99E+00 s2.50E+01

2. Average release rate for l period pCi/sec 1.11E+00 5.06E-01

3. Tech. Spec. Limit %

E. PERCENT OF TECllNICAL ,

SPECIFICATION LIMITS ;

I FISSION AND ACTIVATION GASES

1. Quarterly gamma air dose limit % 8.57E-02 2.30E-01 ;

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2. Quanerly beta air dose limit % 7.71E-03 1.88E-02 I

3. Yearly gamma air dose limit % 4.29E-02 1.15E-01

4. Yearly beta air dose limit % 3.86E-03 9.40E-03

5. Whole body dose rate limit % 4.46E-02 4.16E-02

6. Skin dose rate limit % 9.74E-03 9.08E-03 IIALOGENS, TRITIUM AND PARTICULATES l WITil IIALF-LIVES >8 DAYS i

7. Quarterly dose limit (organ) % 1.06E-01 1.95E-01

8. Yearly dose limit (organ) % 5.28E-02 9.73E-02

9. Organ dose rate limit % 1.99E+00 1.01E+00 Page 5 of 29

NEW YORK POWER AUTIIORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 TABLE IB GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE NUCLIDES RELEASED UNIT OUARTER 3 OUARTER 4

1. Fission Gases Argon-41 Ci 6.37E+00 1.95E+00 Krypton-85m Ci 5.90E+00 7.07E+00 Krypton-87 Ci 1.31E+01 5.04E+01 Krypton-88 Ci 9.07E+00 2.99E+01 Xenon-133 Ci 2.07E+00 1.95E+00 Xenon-135 Ci 1.03E+01 4.37E+01 Xenon-135m Ci 2.30E+01 6.18E+01 Xenon-137 Ci 1.33E+01 1.12E+01 Xenon-138 Ci 8.25E+01 2.20E+02 TOTAL Ci 1.66E+02 4.28E+02

2. lodines i

Ci 3.61E-04 1.11E-03 l Iodine-131 Iodine-133 Ci 2.54E-03 6.06E-03 l Iodine-135 Ci 2.66E-03 4.16E-03 TOTAL Ci 5.56E-03 1.13E-02

3. Particulates Manganese-54 Ci 4.15E-06 8.89E-07 Iron-55 Ci 8.81E-09 1.02E-06 Iron-59 Ci 1.36E-06 --------

Cobalt-60 Ci -------- 2.74E-07 Strontium-89 Ci 1.99E-06 4.34E-06 Cesium-137 Ci 2.45E-07 1.55E-07 Barium / Lanthanum-140 Ci 1.47E-07 --------

TOTAL ,

Ci 7.90E-06 6.68E-06

4. Tdtlum Hydrogen-3 Ci 2.72E+00 1.77E-01 Note: There were no batch releases for this report period.

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 TABLEIC GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE l NUCLIDES RELEASED UNIT OUARTER 3 OUARTER 4

1. Fission Gases Xenon-135 Ci 1.22E-01 3.32E-01 Xenon-138 Ci 3.38E-01 --------

TOTAL Ci 4.60E-01 3.32E-01

2. Iodines Iodine-131 Ci 2.19E-04 1.26E-04 lodine-133 Ci 7.58E-04 7.83E-05

! Iodine-135 Ci 1.62E-04 --------

l TOTAL Ci 1.14E-03 2.04E-04

! 3. Particulates Chromium-51 Ci -------- 3.45E-06 Manganese-54 Ci 1.42E-05 2.09E-05 Iron-55 Ci 4.40E-08 --------

Cobalt-60 Ci 7.27E-06 3.45E-05 Zinc-65 Ci 2.51E-06 5.63E-06 Strontium-89 Ci 3.08E-05 2.71E-05 Arsenic-76 Ci -------- 3.32E-06 TOTAL Ci 5.48E-05 9.49E-05

4. Tritium i

i liydrogen-3 Ci 6.03E+00 3.81E+00 Note: There were no batch releases for this report period.

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1 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 4

TABLE 1 - SUPPLEMENTAL GASEOUS EFFLUENTS-UNMONITORED SHORT-TERM RELEASE NUCLIDES RELEASED UNIT OUARTER 3 OUARTER 4

1. Fission Gases

, Krypton-85m Ci 9.18E-05 --------

Krypton-87 Ci 3.13E-04 --------

Krypton-88 Ci 1.51E-04 --------

Xenon-133 Ci 2.15E-05 --------

Xenon 135 Ci 2.15E-04 --------

Xenon-138 Ci 5.59E-03 --------

TOTAL Ci 6.38E-03 --------

2. lodines Iodine-131 Ci 5.79E-08 --------

lodine-133 Ci 7.80E-07 --------

Iodine-135 Ci 2.12E-06 ---- ---

TOTAL' Ci 2.96E-06 --------

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3. Particulates NONE Ci - - - - - - - - - --------

4. Tritium flydrogen-3 Ci 5.19E-02 --------

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NEW YORK POWER AUTHORITY

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 l l

TABLE 2A l LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES ]

EST TOTAL l UNIT OUARTER 3 OUARTER 4 ERROR %

A. FISSION AND ACTIVATION PRODUCTS :

1. Total Release (not including tritium. gases and alpha) Ci NONE 8.81E-03 s2.50E+01 ,

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2. Average diluted concentra-tion during period pCi/ml NONE 7.34E-11 j

3. Applicable limit % -------- 1.21E-04 1

l B. TRITIUM i

1. Total Release Ci NONE 4.55E+00 s2.50E+01

2. Average diluted concentra-tion during period pCi/ml NONE 3.80E-08 l

3. Applicable limit % -------- 1.27E-03 C. DISSOLVED AND ENTRAINEDGASES

1. Total Release Ci NONE -------

s2.50E+01

2. Average diluted concentra-tion during period pCi/mi NONE ---- ---

3. Applicable Limit % -------- --------

1 D. GROSS ALPIIA RADIOACTIVITY j

1. Total Release Ci NONE -------- s4.20E+01 E. VOLUMEOF WASTE RELEASED (PRIOR TO DILUTION) liters NONE 2.85E+05 F. V' OLUMEOF DILUTION WATER USED DURING PERIOD liters NONE 1.20E+11 G. PERCENTOF TECILNICAL SPECIFICATION LIMITS

1. Quarterly Whole Body Dose % -------- 7.40E-03

2. Quarterly Organ Dose % -------- 4.82E-03

3. Annual Whole Body Dose % -------- 3.70E-03

4. Annual Organ Dose % -------- 2.41E-03 Page 9 of 29

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 TABLE 2B LIQUID EFFLUENTS BATCil MODE NUCLIDES RELEASED UNIT OUARTER 3 OUARTER 4

1. Fission and Activation Products Chromium-51 Ci --------

1.02E-03 Manganese-54 Ci --------

3.14E-03 Iron-59 Ci --------

9.87E-04 Cobalt-58 Ci --------

1.72E-04 Cobalt-60 Ci --------

2.35E-03 Zine-65 Ci --------

8.70E-04 Niobium-95 Ci --------

3.04E-05 Technetium-99m Ci --------

5.46E-06 Tin.ll3 Ci --------

3.87E-05 Antimony-124 Ci --------

1.02E-04 Cesium-137 Ci --------

9.45E-05 TOTAL Ci --------

8.81E-03

2. Tritium Hydrogen-3 Ci NONE 4.55E+00

3. Dissolved and Entrained Gases Ci NONE --------

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

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l NEW YORK POWER AUTIIORITY l

JAMES A. FITZPATRICK NUCLEAR POWER PLANT l EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 l

TABLE 3A SOLID WASTE AND IRRADIATED FUEL SHIPMENTS t

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

1. Tvoeof Waste 3

a. Spent resins, filter sludges, m 4.08E+01 0.00E+00 4.84E+00 2.50E+01 evaporator bottoms, etc. Ci 3.26E+01 0.00E+00 6.73E+01 2.50E+01 3

b. Dry compressible waste, m 0.00E+00 0.00E+00 0.00E+00 --

contaminated equipment, etc. Ci 0.00E+00 0.00E+00 0.00E+00 --

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

control rods, etc. Ci 0.00E+00 0.00E+00 0.00E+00 --

3

d. Other: Dry Compressible Waste, m 1.70E+02 0.00E+00 0.00E+00 2.50E+01 contaminated equip., ect. for Ci 4.25E-01 0.00E+00 0.00E+00 2.50E+01 volume reduction

2. Estimate of Maior Nuclide Composition (hv type ot' waste)

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

Isotone Percent Curies Isotope Percent Curies Iron-55 6.96E+01 6.96E+01 E Cesium-137 1.36'E+00 1.36E+00 M Cobalt-60 1.49E+01 1.49E+01 M Nickel-63 6.59E-01 6.58E-01 E Zinc-65 6.64E+00 6 63E+00 M Chromiiun-51 6.19E-0' 6.18E-01 M Manganese-54 4.64E+00 4.64E;00 M Cobalt-58 5 . 6.' ' 4 5.60E-01 M

b. Dry compressible waste, contaminated equipment, etc.

NONE l

c. Irradiated components, control rods, etc.

NONE l

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NEW YORK POWER AUTIf0RITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 i

TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SilIPMENTS

d. Other: Dry Compressible Waste, contaminated equip., ect. for volume reduction.

l Isotone Percent Curies Isotope Percent Curies Iron-55 6.00E+01 2.55E-01 E Nickel-63 1.03E+00 4.38E-03 E E ;

Cobalt-60 2.19E+01 9.30E-02 E Cesium-137 8.55E-01 3.62E-03 Manganese-54 8.69E+00 3.70E-02 E Carbon-14 6.00E-01 2.55E-03 E {

Zinc-65 7.03E+00 2.99E-02 E llydrogen-3 4.27E-02 1.82E-04 E !

(E - ESTIMATED M - MEASURED)

Percentage of nuclides and total activities are based on a combination of direct measurements and scaling'for non-gamma emitting nuclides. i 1

3. Solid Waste Disposition No. of Shinments Mode of Transportation Destination 8 Truck Chem-Nuclear Systems, Inc.

Barnwell, SC 3 Truck

Scientific Ecology Group Oak Ridge, TN

Volume Reduction Facility B. IRRADIATED FUEL SIIIPMENTS (Disposition)

No. of Shinments Mode of Transportation Destination None N/A N/A 1

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l NEW YORK POWER AUTIIORITY t

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

l SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 ,

i TABLE 3B ,

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS l

l A. NRC CLASS A :

l SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS i

Spent Resins, Filter Dewatering 205.8 ft' HIC 7 :

Sludges, Evaporator :

Bottoms, etc.

Spent Resins, Filter Dewatering 170.8 ft' IIIC 1 ,

Sludges, Evaporator Bottoms, etc. l Dry Compressible Non-Compacted 1040 ft' STC 6 Waste (DAW),

Contaminated Equipment, etc. l Solidification Acent: None l IIIC -Iligh Integrity Container STC - Strong Tight Container i

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d NEW YORK POWER AUTIIORITY

. JAMES A. FITZPATRICK NUCLEAR POWER PLANT :

EFFLUENT AND WASTE DISPOSAL l

SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 i i t i

ATTACHMENT NO.1 i

CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (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 j Calculation Manual (ODCM) during the reporting period shall be included in the Semi-Annual Radioactive Effluent Release Report. l Revision 13 of the ODCM was approved by the Plant Operating Review Committee on :

July 30,1996 at Meeting No. %-072 and became effective on August 1,1996. This [

revision does not reduce the accuracy or reliability of any dose calculations or setpoint _

determinations. Listed below is a brief summary of the changes incorporated in this '(

revision. Attached to this report is a copy of the pages affected by revision 13 to the !

ODCM. !

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-i Revised steps 3.3. land 4.3.2.A of the ODCM to require that an implementation plan be [

developed for any ODCM revisions that require any liquid or gaseous monitor'setpoints to be .

i changed.

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NEW YORK POWER AUTIIORITY l

- JAMES A. FITZPATRICK NUCLEAR POWER PLANT I EFFLUENT AND WASTE DISPOSAL l SEMI-ANNUAL IEPORT JULY 1996 - DECEMBER 1996 l

ATTACHMENT NO. 2 l

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM In accordance with Section 7.3.C.3 of Amendment 93 to the James A. FitzPatrick Nuclear i Power Plant Technical Specifications, changes made to the Process Control Program (PCP) ):

during the reporting period shall be included in the Semi-Annual Radioactive Effluent Release Report. I There were no changes to the Process Control Program Procedure or Contractor Procedures this report period.

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NEW YORK POWER AUTIIORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 ATTACIIMENT NO. 3 :

SUMMARY

OF CHANGES TO THE ENVIRONMENTAL MONITORING AND DOSE CALCULATION LOCATIONS In accordance with Section 7.3.C.3 of Amendment 93 to the James A. FitzPatrick Nuclear Power Plant Technical Specifications, a listing of new locations for dose calculation and/or environmental monitoring identified by the land use census shall be included in the Semi-Annual Radioactive Effluent Release Report.

CIIANGES IN ENVIRONMENTAL MONITORING LOCATIONS ;

During the report period, no changes in the Environmental Monitoring Locations sampled to implement the requirements of Technical Specifications were made. l Sample location selections are based on the annual land use census. l l

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l NEW LOCATIONS FOR DOSE CALCULATIONS During the rerort period, no changes in Dose Calculation Receptor Locations were required based on the results of the land use census.

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, .t g NEW YORK POWER AUTHORITY !

JAMES A. FITZPATRICK NUCLEAR POWER PLANT l l

EFFLUENT AND WASTE DISPOSAL .

I SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 ATTACHMENT NO. 4 I

DEVIATIONS FROM THE REQUIRED ENVIRONMENTAL SAMPLING SCHEDULE :

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l In accordance with Section 7.3.C.7 of Amendment 93 to the James A'. FitzPatrick Nuclear Power Plant Technical Specifications, the cause for unavailability of any environmental i samples required .during the repon period shall be included in the Semi-Annual Radioactive Effluent Release Report.

EXCEPTIONS TO THE ENVIRONMENTAL SAMPLING PROGRAM

1. The air sampling pump at the R-5 offsite Environmental Sampling Station was inoperable for approximately 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . The loss of power at the Environmental Air l Sampling Station was the result of a scheduled power outage by th: local utility.

The air sample pump was out of service from 08/20/% (09:00 hrs) to 08/20/96 (12:00 hrs). i

2. Thermoluminescent Dosimeter (TLD) No. 76 was found to be missing during the l fourth quarter 1996 change-out. TLD No. 76 is located on the nonh security fence at Nine Mile Point Unit 2 (25* @ 0.1 miles).

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, NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 '

1 ATTACHMENT NO. 5 j SEMI-ANNUAL

SUMMARY

OF HOURLY METEOROLOGICAL DATA l

The James A. FitzPatrick Nuclear Power Plant Radiological Environmental Technical l Specification 7.3.c.2 states in pan: "The Radioactive Effluent Release Report to be l submitted within 60 days after January 1 of each year may include an annual summary of l meteorological data collected over the previous year. If the meteorological data is not included, the licensee shall retain it on file and provide it to the U.S. Nuclear Regulatory Commission upon request " In accordance with the aforementioned technical specification, meteorological data is not included in this report. It is retained on file and is available upon request. I t

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

! EFFLUENT AND WASTE DISPOSAL l SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 l ATTACHMENT NO. 6 l

REPORT NOTES 1

11\bk2A Section A and B and Table 2B Normal Liquid Ef0uents The values for Tritum, Strontium-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 Table 1 A Section C Gaseous Effluents and Table 2A Section D Liquid Efnuents ,

The estimated total error percent on previous Semi-Annual Effluent Release Reports for gaseous particulates and liquid gross alpha was based on an average estimate of total error for all parameters reported in Table 1 A and Table 2A respectfully. The estimated total error percent values now reported for gaseous particulates and liquid gross alpha are based on the gross estimated error for each of these parameters.

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 l ATTACHMENT NO. 7 1

GASEOUS EFFLUENTS - UNMONITORED SHORT-TERM RELEASE l l

l a) Date: September 16,1996 b) Location: Unmonitored Release from the Turbine Building .

c) Duration: 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months d) Flowrate: 1.12E+03 cfm

\

e) Volume Released: 2.70E+05 ft' f) Nuclides Released: See Table 1 - Supplemental

, Gasons Effluents - Unmonitored Short-Term Release g) Resultant Doses: See Addendum 1--Assessment of Radiation Doses to the Public January-December 1996 Table 1.D h) Dose Calculations: Doses were calculated in accordance with the Offsite Dose Calculation Manual (ODCM) Section 4.4.3 Short Term _

Releases l l

i i

Page 20 of 29 i i

l e '. .

NEW YORK POWER AUTHORITY j JAMES A. FITZPATRICK NUCLEAR POWER PLANT l EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 (

ADDENDUM 1 ASSESSMENT OF RADIATION DOSES TO TIIE PUBLIC JANUARY- DECEMBER 1995 ,

1

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

l

2. DOSE LIMITS l A. DOSE FROM IIOUID EFFLUENTS (RETS 2.3)

Anolicability Applies to doses from radioactive material in liquid effluents.

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

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

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

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

B. GASEOUS DOSE RATES (RETS 3.2)

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

Page 21 of 29

, e ', . :

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

EFFLUENT AND WASTE DISPOSAL ;

l SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 ADDENDUM 1 (continued) l Obiective To ensure that the dose rates at or beyond the site boundary from gaseous

, effluents do not exceed the annual dose limits of 10 CFR 20, for unrestricted areas.

Speci0 cations ,

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

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

2. Less than or equal to 1500 mrem / year to any organ from lodine-131, lodine-133, Tritium and for radioactive materials in particulate form >

with half-lives greater than 8 days (inhalation pathway only).

C. AIR DOSE. NOBLE GASES (RETS 3.3)

Annlicability Applies to the air dose due to noble gases in gaseous effluents.

r Obiective To ensure that the noble gas dose limitations of 10 CFR 50, Appendix I, ,

are met.

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

l' l. During any calendar quaner, to less than or equal to 5 mrad from gamma radiation, and less than or equal to 10 mrad from beta radiation; and, i 2. During any calendar year, to less than or equal to 10 mrad from gamma j

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

i Page 22 of 29 l

! I

. 3 ', .

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

( SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 l

ADDENDUM I (continued)

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

Obiective ,

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

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

1. During any calendar quarter to less than or equal to 7.5 mrem to any )

organ; and, ;

2. During any calendar year to less than or equal to 15 mrem to any organ.

E. TOTAL DOSE FROM URANIUM FUEL CYCLE (RETS 5.1) l Anolicability Applies to radiation dose from releases of radioactivity and radiation from uranium fuel cycle sources.

Obiective i

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

t Page 23 of 29

._ _ _ .. _ _. _ _ . . _ _ _ _ _ . . . _ _ . . _ . _ _.__..__m -

.. g '. .

NEW YORK POWER AUTHORITY I JAMES A. . FITZPATRICK - NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL i SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 ,

4 ADDENDUM 1 (continued) l

< -l Specifications l

. l

' The dose or dose commitment to any member of the public, due to releases l of radioactivity and radiation, from uranium fuel cycle sources shall be ]

l limited as follows: !

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

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

i

3. DOSE ASSESSMENT

[

]- A. METHODOLOGY l The assessment of radiation doses to the public due to radioactive liquid I and gaseous effluents is performed in accordance with the ODCM. The

! ODCM is based on methodologies and models suggested by the " Guidance Manual For Preparation of Radiological' Effluent Technical Specifications i 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).

i

B. ASSUMPTIONS i

l Dose calculations are performed using formulas and constants defined in 4 the ODCM. Specific radioactive release uctivities used in the dose calculations are listed in the Semi-Annual Radioactive Effluent Release i Reports (1.21 Reports) for the period of January 1,1996 to December 31,

1996. Historical meteorological data was used to generate tables of average dispersion factors. Locations of interest were identified from the 1996 land use census. Dispersion factors and locations ofinterest used in performing j 4: the dose calculations are listed in Table 2.

C. ASSESSMENT RESULTS

SUMMARY

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

Page 24 of 29

NEW YORK POWER AUTIiORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT t EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 '

ADDENDUM 1 (continued) 1

4. 40 CFR 190 DOSE ASSESSMENT l

A. METHODOLOGY Evaluation to demonstrate compliance with the 40 CFR 190 dose limits l must be performed when the doses calculated for 10 CFR 50 compliance !

exceed twice their respective limits. When additional dose assessment is >

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

B. RESULTS

SUMMARY

The cumulative dose contribution from liquid and gaseous effluents for this ,

report period were calculated and are listed in Table 1. The calculated i.

doses are less than twice their respective 10 CFR 50 limits, therefore, ,

additional calculations are not necessary to demonstrate compliance with 40 CFR 190 dose limits (RETS 5.1.b).

I Page 25 of 29

I e g o ', .

l NEW YORK POWER AUTIIORITY JAMES A. FITZPATRICK NUCLEAR POWER PIANT EFFLUENT AND WASTE DISPOSAL !

SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 I l

ADDENDUM 1 (continued)

TABLE 1 ANNUAL DOSE ASSESSMENT 1996 A. LIQUIDS OUARTER 1 2 3 4 ANNUAL I (a) (a)

Organ (mre.n) NONE NONE NONE 2.41 E-04 2.41E-04

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

4.82E-03 2.41E-03 (b) (b)

Whole Body (mrem) NONE NONE NONE 1.11 E-04 1.11E-04 l

% of Limit -------- -------- -------- 7.40E-03 3.70E-03 (a) Dose to the Adult GI-LLI primarily by the fish pathway.

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

1 B. NOBLE GASES OUARTER 1 2 1 4 ANNUAL Total Body (mrem /yr) 2.35E-02 3.96E-02 2.23E-01 2.08E-01 2.23E-01 l

% of Limit 4.70E-03 7.92E-03 4.46E-02 4.16E-02 4.46E-02 Skin (mrem /yr) 3.04E-02 5.09E-02 2.92E-01 2.73E-01 2.92E-01

% of Limit 1.01E-03 1.70E-03 9.74E-03 9.10E-03 9.74E-03 i Gamma (mrad) 8.27E-04 5.52E-04 4.29E-03 1.15E-02 1.72E-02

% of Limit 1.65E-02 1.10E-02 8.57E-02 2.30E-01 1.72E-01 i

Beta (mrad) 1.06E-04 7.30E-05 7.71E-04 1.88E-03 2.83E-03

% of Limit 1.06E-03 7.30E-04 7.71E-03 1.88E-02 1.42E-02 i Page 26 of 29

, g, ', , NEW YORK POWER AUTHORITY ;

JAMES A. FITZPATRICK NUCLEAR POWER PLANT l

, EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 ADDENDUM 1 (continued) !

TABLE 1 ANNUAL DOSE ASSESSMENT 1996 i

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

Organ (mrem) 8.41 E-04 1.16E-03 8.00E-03 1.46E-02 2.46E-02

% of Limit 1.12E-02 1.55E-02 1.07E-01 1.95E-01 1.64E-01 Organ Dose Rate 9.26E-01 3.32E-01 3.01E-01 1.34E-03 9.26E-01 (mrem /yr)

% of Limit 6.17E-02 2.21 E-02 2.01E-02 8.93E-05 6.17E-02 (a) Dose to the Infant Thyroid primarily by the goats milk pathway.

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

D. UNMONITORED SHORT-TERM RELEASE QUARTER 3 NOBLE GASES Total Body (mrem /yr) 1.25E-13 Gamma (mrad) 4.09E-09

% of Limit 2.50E-14 % of Limit 8.18E-08 Skin (miem/yr) 1.01E-11 Beta (mrad) 6.18E-08

% of Limit 3.37E-13 % of Limit 6.18E-07 IODINE AND PARTICULATES (a)

Organ (mrem) 8.16E-05 l % of Limit 1.09E-03 (a) Dose to the Infant Thyroid primarily by the goats milk pathway.

l Page 27 of 29

. e ', . NEW YORK POWER AUTHORITY JAMES A. FITZ< PATRICK NUCLEAR POWER PLANT ,

EFFLUENT AND WASTE DISPOSAL i SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 i

! ADDENDUM 1 (continued)

TABLE 2 METEOROLOGICAL DATA AND LOCATIONS OF INTEREST GEOGRAPHIC ATMOSPHERIC RECEPTOR LOCATION DISPERSION FACTOR !

A. IODINE & DISTANCE / RELEASE X/Q D/Q 2

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

1. Garden 0.93 mi @ 82*E ST 2.86E-08* 1.72E-09 Grazing Season 0.93 mi @ 82 E RX 1.94 E-07* 4.76E-09 Cary 0.93 mi @ 82 E TB 1.76E-07

4.57E-09 Location No. 78 0.93 mi @ 82*E RF 1.94 E-07* 4.76E-09 0.93 mi @ 82 E RW 3.08E-07* 5.45E-09

2. Meat 1.24 mi @ 126 SE ST 1.70E-08* 6.51E-10 Grazing Season 1.24 mi @ 126 SE RX 5.17E-08* 1.24E-09 Parkhurst 1.24 mi @ 126 SE TB 4.97E-08* 1.21E-09 Location No. 26 1.24 mi @ 126 SE RF 5.17E-08

1.24E-09 1.24 mi @ 126*SE RW 8.74E-08* 1.39E-09

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

Grazing Season RX 3.04E-08* 5.07E-10 l 2.2 mi @ 138 SE France 2.2 mi @ 138 SE TB 2.98E-08* 4.97E-10 ;

Location No.10 2.2 mi @ 138*SE RF 3.04E-08* 5.07E-10 2.2 mi @ 138 SE RW 4.66E-08* 5.39E-10 i

4. Goat 2.5 mi @ 146*SE ST 1.67E-08* 2.65E-10 Grazing Season 2.5 mi @ 146 SE RX 2.76E-08* 4.14E-10 Nickolas 2.5 mi @ 146 SE TB 2.71 E-08* 4.07E-10 Location No. 61 2.5 mi @ 146 SE RF 2.76E-08* 4.14E-10 RW 4.15E-08* 4.36E-10 2.5 mi @ 146 SE

5. Resident Annual Average ST 2.99E-08 -

I

a. Inhalation 1.55 mi @ 90 E" 0.93 mi @ 82*E RX 1.98E-07 -

! 0.93 mi @ 82*E TB 1.81E-07 -

0.93 mi @ 82*E RF 1.98E-07 - l l 0.93 mi @ 82 E RW 2.93E-07 -

Tritium Dose Calculation Only

(

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

Page 28 of 29

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

. SEMI-ANNUAL REPORT JULY 1996 - DECEMBER 1996 l

ADDENDUM 1 (continued) 1 TABLE 2 l METEOROLOGICAL DATA AND LOCATIONS OF INTEREST !

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

PARTICULATES DIRECTION POINT (sec/m') (1/m) 5 b. Deposition 0.70 mi @ ll8"ESE ST -

1.61 E-09 ,

0.70 mi @ l18 ESE RX -

5.65E-09 )

0.70 mi @ ll8*ESE TB -

5.42E-09

]

0.70 mi @ 118*ESE RF -

5.65E-09 )

0.70 mi @ l18 ESE RW -

6.42E-09 l B. NOBLE GASES

1. Air Dose 1.55 mi @ 90 E ST 7.99E-08 -

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

0.6 mi @ 90 E RX 3.58E-07 -

0.6 mi @ 90*E TB 3.19E-07 -

0.6 mi @ 90 E RF 3.58E-07 -

0.6 mi @ 90*E RW 5.39E-07 -

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

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

0.6 mi @ 90 E TB 3.19E-07 -

j IG 0.6 mi @ 90*E 3.58E-07 -

O.6 mi @ 90 E RW 5.39E-07 -

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

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

0.6 mi @ 90 E RX 3.58E-07 -

0.6 mi @ 90*E TB 3.19E-07 -

0.6 mi @ 90 E RF 3.58E-07 -

0.6 mi @ 90 E RW 5.39E-07 -

i ST = Main Stack RX = Reactor Building TB = Turbine Building Vent RF = Refuel Floor Vent RW = Radwaste Vent fc = Finite Cloud Page 29 of 29

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