ML20203K431
| ML20203K431 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/31/1997 |
| From: | Michael Colomb POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20203K410 | List: |
| References | |
| NUDOCS 9803050084 | |
| Download: ML20203K431 (36) | |
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i NEW YORK POWER AUTIIORITY JAMES A.FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTEDISPOSAL SEMI-ANNUAL REPORT JULY 1,1997 - DECEMBER 31,1997 DOCKET NO.: 50-333 LICENSE NO.: DPR-59 1
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, .o g NEW YORK POWER AUTIIORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL
, SEMI-ANNUAL REPORT JULY 1997 - DECEMBER 1997 SUPPLEMENTAL INFORMATION FACILITY: JAFNPIL LICENSEE: NEW YORK POWER AUTIIORITY
- 1. Technical Specification Limits
- a. Fission and Activation Gases:
(1) The dose rate at or beyond the site boundary due to radioactive materials relea,ed from the plant in gaseous effluent shall be limited as follows:
j (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 frota noble gases.
l (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:
1 (a) During any cakndar quarter, to less than or equal to 5 mrad from gamma radiation, and less than or equal to 10 mrad from beta radiation; and, (b)- During any calendar year, to less than or equal to 10 mrad from gamma radiation and less than or equal to 20 mrad from beta radiation,
- b. Tritium, lodines and Particulates, Half Lives > 8 days:
(1) The dose to a member of the public at or beyond the site boundary from Iedine-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 :ess 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.
(2) The dose rate at or beyocid the site bmndary due to radioactive materials released from the plant it 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).
Page 1 of 27
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- NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1997 - DECEMBER 1997 SUPPLEMENTAL INFORMATION (Continued)
- c. Liquid Efnuents:
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'(1) The concentration of radioactive materials released to the unrestricted areas shall not exceed the values specified in 10 CFR 20, Appendix B, Table II,
, Column 2. For dissolved or entrained noble gases the concentration shall be limited to 2.00E-04 pCi/ml.
(2) The dose to a member of the public from radioactive materials released from the plant in liquid effluents to tmrestricted 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. lodines: (None specified)-
- c. Particulates, half-lives >8 days: (None speciDed) f d. Liquid ef0uents: Ouarter 3 Ouarter 4 (1) Fission and activation NONE NONE-products (mixture MPC)
(pCi/ml)
(2) Tritium ( Ci/ml) 3.00E-03 3.00E-03 (3) Dissolved and entrained gases (pCi/mD 2.00E-04 2.00E-04 4
Page 2 of 27
NEW YORK POWER AUTilORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1997 - DECEMBER 1997 SUPPLEMENTAL INFORM ATION (Continued)
- 3. Average Eneruv (None specified)
- 4. Measurements and Approximations of Total Radioatlivity
- 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.
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- b. lodines: 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 fcur week per quarter composite of particulate filters for each release path for Strontium-89 and Strontium-90. One week per month particulate filter for each release path for gross alpha,
- d. Liquid Efnuents: Gamma spectral analysis of each batc'.. discharged, except composite analysis for Strontium-89, Strontium-90, Iron-55, 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 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 flov: rates, volume measurements and analysis collection yields Undeterminate - Random counting error estimated using accepted statictical calculations Page 3 of 27 l
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' NEW YORK POWER AUTIlORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL
, SEMI-ANNUAL REPORT JULY 1997 - DECEMBER 1997 SUPPLEMENTAL INFORMATION (Continued)
- 5. Ilatch Heleases
- a. Liquid. Guarter 3 Ouarter 4 (1) Number of batch releases
- NONE NONE (2) Total time period for batch NONE NONE release: (min)
(3) Maximum time period for NONE NONE batch release: (min)
(4) Average time period for NONE NONE batch release: (min)
(5) Minimum time period for NONE NONE I
batch release: (min)
- b. Gaseous: NONE NONE Tnere were no gaseous batch releases for this report period.
- 6. Abnormal Releases
- a. Liquid: Ouarter 3 Ouarter 4 (1) Number of releases: NONE NONE (2) Total activity released: NONE NONE
- b. Gaseous (1) Number of releases: NONE NONE (2) Total activity released: NONE NONE Page 4 of 27 i
q NEW YORK POWER AUTilORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1997 - DECEMBER 1997 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL REI EASES EST TOTAL LL'll. OUARTER 3 OUARTER 4 ERROR %
A. FISSION AND ACTIVATION GASES
- 1. Total Release Ci 2.15E,00 2.57E+00 c2.50E+01
- 2. Average release rate for period pCi/sec 2.70E-01 3.23E-01
- 3. Tech. Spec. Limit % * *
- 11. IODINE 131 t
- 1. Total lodine-131 Ci 1.41E-05 3.82E-05 s2.50E+01
- 2. Average release rate for period pCi/sec 1.77E-06 4.81E-06 *
- 3. Tech. Spec. Limit % *
- C. PARTICULATES
- l. Particulates with half-lives
> 8 days Ci 9.15E-06 2.41E-05 s3.60E+01
- 2. Average release rate for period pCL/sec 1.15E-06 3.03E-06
- 3. Tech. Spec. Limit % * *
- 4. Gross alpha radioactivity Ci 3.02E-07 2.91E-07 s2.50E+01 H. TRITIUM
- 1. Total Release Ci 2.73E+01 1.64E+01 s2.50E+01
- 2. Average release rate for period pCi/sec 3.43E,00 2.06E+00
- 3. Tech. Spec. Limit % * *
- E. PERCENTOF TECilNICAL SPECIFICATION LIMITS FISSION AND ACTIVATION GASES
- 1. Quarterly gamma air dose limit % 1.31E-03 1.43E-03
- 2. Quarterly beta air dose limit % 8.39E-05 8.97E-05
- 3. Yearly gamma air dose limit % 6.56E-04 7.16E-04
- 4. Yearly beta air dose limit % 4.20E-05 4.49E-05
- 5. Whole body dose rate limit % 9.68E-05 1.15E-03
- 6. Skin dose rate limit % 2.06E-05 2.50E-04 IIALOGFNS, TRITIUM AND PARTICULATES WITil llALF-LIVES >8 DAYS
- 7. Quarterly dose limit (organ) % 1.24E-02 1.08E-02
- 8. Yearly dose limit (organ) % 6 , 21.E - 0 3 5.38E-03
- 9. Orgat dose rate limit % 4.87E-05 5.53E-05 Page 5 of 27
' NEW YORK POWER AUTIIORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL
. SEMI-ANN' .L REPORT IULY 1997 - DECEMBER 1997 TABLE IB -
GASEOb' IFFLUENTS-ELEVATFD RELEASE CONTINUOUS MODE NUCl.lDES REl, EASED UNIT OUARTER 3 OUARTER 4
- 1. Fitsion Gases Argon 41 Cl 1.32E+00 1.16E+00
rypton 85m Ci 2.09E-01 5.30E-02 Krypton-87 Ci --------
2.84E-01 Krypton-88 Ci 3.63E-03 2.71E-01 Xenon-133 Ci --------
4.09E-02 Xenon 135 Ci --------
1.88E-01 Xenon-135m Ci 2.29E-02 4.19E-01 Xenon-138 Ci 6.91E-02 1.59E-01 TOTAL Ci 1.62E+00 2.57E+00
- 2. lodines lodine-131 Ci 1.13E-05 3.50E-05 lodine-133 Ci 4.92E-05 2.89E-04 lodine-135 Ci --------
2.06E-04 TOTAL Ci 6.05E-05 5.30E-04
- 3. Particulates Strontium-89 Ci 8.30E-07 --------
TOTAL Ci 8.30E-07 --------
- 4. Tritium -
11ydrogen-3 Ci 5.66E+00 2.91E+00 Note: There were no batch releases for this report period.
Page 6 of 27 g _ ,. . . .
NEW YORK POWER AUTIlORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT '
Fr - ENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1997 - DECEMBER 1997 TABLEIC GASEOUS EFFLUENTS-GROUND LEVEL RELEASET CONTINUOUS MODI NUCl.jDES REl, EASED UNIT OUARTER 3 OUARTER 4 l
- l. Fission Gases Xenon-135M Ci 5.30E-01 --------
TOTAL Ci 5.30E-01 --------
a 2.Jodines lodine-131 Ci 2.76E-06 3.24E-06 lodine-133 Ci 5.40E-05 1.28E-05 TOTAL Ci 5.68E-05 1.60E-05
- 3. l' articulates Strontium-89 Ci 8.32E-06 2.41E-05
! TOTAL Ci 8.32E-06 2.41E-05
- 4. Tritium flydrogen-3 Ci 2.16E+01 1.35E+01 Note: There were no batch releases for this report period.
J Page 7 of 27
' NEW YORK POWER AUTIIORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY 1997 - DECEMBER 1997 TABLE 2A LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES EST TOTAL UN': OUARTER 3 DJIARTER 4 ERROR %
A. FISSION AND ACTIVATION PRODUCTS
- 1. Total Release (not including tritium, gases and alpha) Ci NONE NONE s2.50E+01
- 2. Average diluted concentra-tion during period pCi/ml NONE NONE
- 3. Applicable limit % -------- --------
II 'lRITIUhl
!. Total Reletse Ci NONE NONE s2.50E+01
- 2. Average diluted concentra-tion during period pCi/ml NONE NONE
- 3. Applicable limit % -------- --------
C. DISSOLVED AND ENTRAINEI1 GASES
- 1. Total Release Ci NONE NONE s2.50E+01
- 2. Average diluted concentra-tion during period pCi/ml NONE NONE
- 3. Applicable Limit % -------- --------
D. GROSS ALPilA RADIOACTIVITY
- 1. Total Release Ci NONE NONE s4.20E+01 E. VOLUhlEOF WASTE RELEASED (PRIOR TO DILUTION) liters NONE NONE F. VOLUhlEOF DILtTI'lON WATER USED DURING PERIOD liters NONE NONE G. PERCENTOF TECilNICAL SPECIFICATION LDilTS
- 1. Quarterly Whole Body Dose % -------- --------
- 2. Quarterly Organ Dose % -------- --------
- 3. Annual Whole Body Dose % -------- --------
- 4. Annual Organ Dose % -------- --------
Page 8 of 27
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NEW YORK POWER AUTIIORITY
-JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1997 - DECEMBER 1997 TABLE 2B LIQUID EFFLUENTS HATCil MODE NUCl, IDES REl. EASED UNIT OUARTER 3 OUARTER 4
- 1. Fission and Activation IYoducts Ci NONE NONE
- 2. Tritium flydrogen 3 Ci NONE NONE
- 3. Dissolved and Entrained Gasn Ci NONE NONE Note: Tliere were no continuous mode discharges during this report period.
Page 9 of 27
NEW YORK POWER AUTilORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1997 - DECEMBER 1997 TABLE 3A SOLID WASTE AND IRRADIATED FUEL SIIIPMENTS
- 4. SOLID WASTE SillPPED OFFSITE FOR HURIAL OR DISPOSAL (NOT IRRADIATED FUF.L) 6-month Period Est Total Unit Class A Class B Class C Error %
I. Iype of Waste 3
- a. Spent resins, filter sludges, m 1.75E+01 0.00E+00 0.00E+00 1.00E+01 evaporator bottoms, etc. Ci 3.60E+01 0.00E+00 0.00E+00 2.50E+01 3
b, Dry compressible waste, m 5.84E+00 0.00E+00 0.00E+00 1.00E+01 contaminated equipment, etc. Ci 5.98E-01 0.00E+00 -0 . 0 0 E + 0 0 2.50E+01 3
- 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 --------
- d. Other: Dry Compressible Waste, m3 0.00E+00 0.00E+00 0.00E+00 --------
contaminated equip., cct for Ci 0.00E+00 0.00E+00 0.00E+00 --------
volume reduction
- 2. Estinnte of Maior Nuclide Composition (hv type of waste)
- a. Spent resins, filter sludges, evaporator bottams, etc.
Isotone Percent Curies Isotone Perrin_[ Curies Iron 55 5.30E+01 1.91E+01 E Cesium-137 2.69E+00 9.70E-01 M Cobalt-60 2 35E+01 8.49E+00 M Nickel 63 1.42E+00 5.13E-01 E Zine-65 1.14E+03 4.12E+00 M Cerium-144 3.89E-01 1.40E-01 M Manganese-54 6.72E+00 2.42E+00 M Carbon-14 3.35E-01 1.21E-01 M i
l b Dry compressible waste, contaminated equipment, etc.
NONE I
Isotone Percent Curies isotone Percent Curies Iron 55 6.06E+01 3.62E-01 E Nickel-63 1.09E+00 6.56E-03 E Cobalt-60 2.26E+01 1.35E-01 E Cesium-137 9.04E-01 5.40E-03 E Manganese-54 7.86E+00 4.70E-02 E Carbon-14 6.41E-01 3.83E-03 E Zine-65 6.06E+00 3.62E-02 E Cerium-144 2.59E-01 1.55E-03 E
- c. Irradiated components, control rods, etc.
NONE Page 10 of 27 ,
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' NEW YORK POWER AUTilORITY JAulES A. FITZPATRICK NUCLEAR POWER . PLANT EFFLUENT AND WASTE DISPOSAL
, SEMI-ANNUAL REPORT JULY 1997 - DECEMBER 1997 TAllLE 3A (continued)
SOLID WASTE AND IRRADIATED FUEL SillPMENTS
- d. Other: Dry Compressible Waste, contaminated equip., ect, for volume reduction.
NONE (E - ESTIM/ TED M - MEASURED)
Percentage of nuclides and total activities are based on a combination of direct measurements and scaling for non-gamma emitting nuclides.
- 3. Solid Waste Disposition No. of Shinments Mode of Transnortation Destination 4 Truck Chem Nuclear Systems, Inc.
Harmvell, SC 0 Truck
- Scientific Ecology Group Oak Ridge, TN
- Volume Reduction Facility IL IRRADIATED FUEL SIIIPMENTS (Disposition)
No. of Shinments - Mode of Transnortation Destination None --- ---
Page 11 of 27
, NEW YORK POWER AUTilORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL
, SEMIANNUAL REPORT JULY 1997 - DECEMBER 1997 TABLE 38 SOLID WASTE AND IRRADIATED FUEL SillPMENTS A. NRC CLASS A SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERL Spent Resins, Filter Dewatering 205.8 ft' lilC 3 '
Sludges, Evaporator Bottoms, etc.
Dry Compressible NONE 206.1 ft' STC 1 Waste (DAW),
Contaminated Equipment, etc.
Solidification Agert. None lilC -liigh Integrity Container STC - Strong Tight Container Page 12 of 27
NEW YORK POWER AUT110RITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1997 - DECEMBER 1997 TABLE 3H--AMENDMENT JANUARY 1997 - JUNE 1997 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. NRC CLASS A SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTI! EMPLOYED VOLUME CONTAINER CONTAINERS Spent Resins, Filter Dewatering 205.8 ft 2 IllC 7 Sludges, Evaporator Bottoms, etc.
Spent Resins, Filter Dewatering 170.8 ft 3 IIIC 2 Sludges, Evaporator Bottoms, etc.
Dry Compressible Non-Compacted 1040 ft) STC 4 Waste (DAW),
Contaminated Equipment, etc.
B. NRC CLASS H SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Spent Resins, Filter Dewatering 170.8 ft' IIIC 1 Sludges, Evaporator Bottoms, etc.
Solidification Acent: None IIIC - High Integrity Container STC - Strong Tight Container Page 13 of 27
' NEW YORK POWER AUTilORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1997 - DECEMBER 1997 ATTACIIMENT NO.1 CHANGES TO TIIE OFFSITE DOSE CALCFLATION MANUAL (ODCM) l l
l In accordance with Section 7.3.C.3 of Amendment 93 to the James A. FitzPatrick Nuclear Power Plant Technical Specifications, changes made to the Offsite Dose Calculation Manual (ODCM) during the reporting period shall be included in the Semi-Annual Radioactive Ef0uent Release Report.
Revision 14 of the ODCM was approved by the Plant Operating Review Committee on October 28,1997 at Meeting No.97-063 and became effective on November 4,1997.
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 14 to the ODCM.
Ad&d AP-02.08, Quality Assurance Record Identification and Control to the list of References, Section 6,6.3.
Changed "32,000CFM" to "32,500"CFM (Typo Correction) on page 44 of the ODCM.
Corrected spelling error on page iii, REC, List of Tai'es.
Corrected typo in REC, Sec tion C.I. Changed " Table 2.1.1"to " Table 2.1-1".
Changed Table 2.1-2 and footnote to accurately reflect Tech Spec Amendment 233 which changes operating cycle from 18 months to 24 months. Changed footnote "f"and Table 2.1-2 Instrument Channel Calibration to once per 24 months.
Appendix II, Section 1.2,added additional sample media to the list of cross check samples i analyzed.
Table 11-1, deleted milk location #50 from the list of environmental samples collected. The farm designated as location No. 50 was sold and the Dairy is no longer in operation.
Figure 11-1, deleteci milk location No. 50. designated a Map Location No. 44 on the Sample Locction Map.
Minor editorial corrections.
Page 14 of 27 g .,
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NEW YORK POWER AUTIIORITY l JAMES A. FITZPaTRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL
, SEMIANNUAL REPORT JULY 1997 - DECEMBER 1997
, - ATTACllMENT NO. 2
SUMMARY
OF CIIANGES TO THE PROCESS CONTROL PROGRAM In accordance with Section 7.3.C.3 of Amendment 93 to the James A. FitzPatrick Nuclear Power Plant Technical Specifications, charces made to the Process Control Program (PCP) during the reporting period shall be included in the Semi-Annual Radioactive Effluent
, Release Report.
i 4
There were no changes to the Process Control Program Procedure or implementing procedures 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 1997 - DECEMBER 1997 ATTACIIMENT NO. 3
SUMMARY
OF CIIANGES TO TIIE ENVIRONMENTALMONITORING AND DOSE CALCULATION LOCATIONS In accordance with Section 7.3.C.3 of Amendment 93 to the James A. FitzPatrick Nuclear Power Piant 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.
Sample location selections are based on the annual land use census.
A routine milk sampling location (designated as location #50 in the Radiological Environmental Operating Report) was deleted from the sample program in October of 1997. The milk herd was sold off and milk samples were no longer available. This sample location was not replaced as it was not required by Technical Specifications.
N_EW LOCATIONS FOR DOSE CALCULATIONS During the repon period, no changes in Dose Calculation Receptor Locations were required based on the results of the land use census.
4 4
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e 4 NEW YOR.K POWER AUTIlORITY JAMES A. FITZPATRICK NUCLEAR POV'ER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY 1997 - DECEMBER 1997 ATTACliMENT NO. 4 DEVIATIONS FROM TIIE REQUIRED ENVIRONMENTAL SAMPLING SCIIEDULE 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 samples required during the report period shall be included in the Semi-Annual Radioactive Effluent Release Report.
EXCEPTIONS TO TIIE ENVIRONMENTAL SAMPLING PROGRAM
- 1. Due to severe weather, four Environmental Air Sampling Stations experienced power failure during the period of 10/27/97 and 10/28/97.
Station Annroximate Down Time R Off-site 14.2 hrs.
R Off-site 14.7 hrs.
R Off-site 3.7 hrs.
R J - Off-site 3.6 hrs.
No corrective actions were implemented.
- 2. The air sampling pumps at the R-1 and R-2 off-site Environmental Sampling Stations were inoperable for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The loss of power at the Environmental Air Sampling Station was the result of a local power outage. The air sample pumps were out of service for a four hour period on 12/02/97. No corrective action was implemented.
Page 17 of 27
NEW YORK POWER AUTIIORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1997 - DECEM13ER 1997 ATTACllMENT NO. 5 SEMI-ANNUAL
SUMMARY
OF llOURLY METEOROLOGICAL DATA The James A. FitzPatrick Nuclear Power Plant Radiological Environmental Technical Specification 7.3.c.2 states in part: "The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year may include an annual summary of 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 lite and is available upon request.
Page 18 of 27
NEW . YORK POWER AUTIIORITY JAMES A. FIT 7. PATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL "EPORT JULY 1997 - DECEMBER 1997 ADDENDUM 1 ASSESSMENT OF HADIATION DOSES TO TIiE PUBLIC JANUARY- DECEMBER 1996
- 1. INTRODUCTION The James A. FitzPatrick Nuclea Power Plant Radiological Efiluent Tiechnical Specificaticns (RETS) reqvire an assessment of the radiation doses to the public due to radioactive liquid and gaseous effluents This assessment of does to the public is based on accepted ucthodologies found in the Offsite Dose Calculation Manual (ODCM).
- 2. DOSE LIMITS A. DOSE FROM LIOUID EFFLUENTS (RETS 23)
Applicabliity Applies to doses from radioactive material in liquid effluents.
Obiective To ensure that the dose limitations of 10 CFR 50, Appendix 1, are met.
Snecificationg fhe dose to a member of the public from radioactive materials released from the plant in liquid enluents to unrestricted areas shall be limited as follows: ,
- 1. Duiing any cabndar quarter, limited to less than or equal to 1.3 mrem to the whole body and to less than or equal to 5 mrem to any organ.
- 2. During any .alendar 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. GASEOl'S DOSE RATES (RETS 3.2) by.plicability Applies to the radiation dose from radioactive material in gaseous effluents.
Page 19 of 27
i , NEW- YORK POWER AUTHORITY .
JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL
, SEMI-ANNU L REPORT JULY 1997 - DECEMBER 1997 ADDENDUM 1 (continued)
Obiective 4
To ensure that the dose rates at or beyond the site boundary from gaseous efauents do not execed the annual dose limits of 10 CFR 20, for i unrestricted areas.
Sneci0 cations l The dose rate at or beyond the site boundary due to radioactive materials released from the plant in gaseous efnuents shall be limited as follows:
4
- 1. Less than or equal to 500 mrem / year to the whole body and less than or equal to 3000 mrem / year to the skin from noble gases; and,
- 2. Less than or equal to 1500 mrem / year to any organ frc,m Iodine-131, 4
lodine-133, Tritium and for radioaciive materials in particulate form i with half-lives greater than 8 days (inhalation pathway only).
i C. AIR DOSR NOBI E GASES (RETS 3.3) f
- Applicability Applies to the air dose due to noble gases in gaseous efnuents.
- Obiective To ensure that the noble gas dose limitations of 10 CFR 50, Appendix 1, are met.
Speci0 cations 4
The air dose to areas at or beyond the site boundary from noble gases released from the plant in gaseous ef0uents 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 r>r equal to 10 mrad from gamma radiation and less than or equct to 20 mrad from beta radiation.
Page 20 of 27
i NEW YORK POWER AUTIl0RITY
-JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY 1997 - DECEMBER 1997 ADDENDUM 1 (continued)
D, DOSE DUE TO IODINE-131. IODINE-133. TRITIUM AND RADIONUCI.lDES IN PARTICUI. ATE FORh1 (RETS 3.4)
Annlicability Applies to the cumulative dose from lodine-131, lodine-133, Tritium, and radionuclides in particulate form with halflives greater than 8 days in gaseous effluents.
Obiective To ensure that the dose limitations of 10 CFR 50, Appendix 1, are met.
Snecifications The dose to a member of the public at or beyond the site boundary from lodine-131, lodine-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 equal to 15 mrem 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.
Obiective To ensure that the requirements of 40 CFR 190 are met.
Page 21 of 27
[
' N!!W YORK POWillt AtTrilOltlTY JAMiiS A. 1 ITZPATRICK NUCl.liAlt I'0WiiR PLANT liFl:LUl!NT AND WASTI! I)lSPOSAL SliMI ANNUAI, RiiPORT JULY 1997 Dl!CliMillitt 1997 -
ADI)lCNDUM 1 (continued)
SMdflGt191n The dose or dose coramitment to any member of the public, due to releases of *adioactivity and radiation, from uranium fuel cycle sources shall be limited as follows:
- 1. I.ess than or coual to 25 mrem / year to th.c whole body; and,
- 2. I.ess than or equal to 25 mrem / year to any organ except the thyroid which shall be limited to less than or equal to 75 mremlyr .
- 3. 1)OSIC ASSICSSMICNT A. Ml!TilODOi,0GY The assessment of radiation doses to the piblic due to radioactive liquid and gaseous effluents is perfi)rmed in accordance with the ODC5 '. The i ODChi is based on methodologies and models suggested by the " Guidance Manual l'or Preparution of Itadiological liftluent Technical Specifications liir Nuclear Power Plants" (NURl!G 0133) and " Calculation of Annual Doses to Man from Routine Releases of Reactor liftluents lbr the purpose of livaluating C-mpliance with 10Cl R50, Appendix 1" (Regulatory Guide 1.109),
- 11. ASS 11MPTIONS Dose calculations are perfbrmed using formulas and constants defined in the ODCM. Specific radioactive release activities used in the dose calculations are listed in the Semi Annual Radioactive liftluent Release Reports (1.21 Reports) for the period of hnuary 1,1997 to December 31, 1997. Ilistorical meteorological data svas used to generate tables of verage dispersion factors. l.ocations of interest were identified from the 1997 land use census. Dispersion factors and locations ofinterest used in performmg the dose calculations are listed in Table A C. ASSliSShiliNT Rl!SlII,TS SllMMARY The calculated doses to the public due to radioactive effluents are listed in Table 1. The calculated doses are small fractions of their respective dose limits.
j Page 22 of 27 i
=
' NEW YORK POWER AUT110RITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL
, SEMI ANNUAL REPORT JULY 1997 DECEMBER 1997 ADDENDUM i (continued)
- 4. 40 CFR 190 DOSE ASSESSMENT A. METilODOI.OGY Evaluation to demonstrate compliance with t..e 40 CFR 190 dose limits must be performed when the do:.es 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.
- 11. lESJI.TS
SUMMARY
The cumulative dose contribution from !! quid and gaseous efliuents for this report period were calculated and are list d in Table 1. The cumulative dose contribM!an from direct radiation from the reactor unit and from radwaste storage tanks is measured by enviretimental thermoluminescent dosimeters for the report period This data is contained in the Annual Environmental Operating Report. The calculated doses from liquid and gaseous effluesits are less than twice their respective 10 CFR 50 limits, therefore, additional calculations are not necessary to demonstrate compliance with 40 CFR :90 dose limits (RETS 5.1.b).
l Page 23 of 27
NEW YORK POWER AUT110RITY 4 -
JAMES A. FITZPNIRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL
, SEMI ANNUAL REPORT JULY 1997 - DECEMB!!R 1997 AI)DENDUM i (continued)
TAHLEI ANNUAL DOSE ASSESSMENT 1997 ,
A. LIQUIDS OUARTl!R, 1 2 2 f ANNUAL ,
! Organ (mrem) NONil NONE NONE NONE NONII
% of Limit +- - - - -- - - - - -- --- - -
i
- Whole llody (mrem) NONE NONE NON!! NONE NONE i % of Limit --- - - --- -- -- ---- -- - - - - -
l B. NOBLE GASES GJARTliR 1 2 1 4 ANNUAL
! Total llody (mrem /yr) 1.66E 03 1.50E 03 6.221I 05 6.89E 05 1.66E-03
, % of Limit 3.32E 04 3.00E-04 1.24E 05 1.38E-05 3.32E 04 Skin (mrem /yr) 2.66E-03 2.24E 03 7.98E 05 8.65E-05 2.66E-03
% of Limit 8.87E 05 7.47E 05 2.66E-06 2.88E 06 8.87E 05 -
Gamma (mrad) 1.74E 03 1.56E-03 6.56E 05 7.16E 05 3.44E 03
% of Limit 3.48E-02 3.12E-02 1.31 E-03 1.43E 03 3.44E 02 Ileta (mrad) 8.67E-04 6.12E-04 8.39E-06 8.97E-06 1.50E-03
% of Limit 8.67E-03 6.12E 03 8.39E 05 3.97E-05 7.50E Page 24 of 27
-. -.- -.....-.-.- - .~. - -
I '
- NEW YORK POWER AUT110RITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY 1997 DECEMBER 1997 Al)DENi>UM 1 (continued)
, TAHLE1 ANNUAL DOSE AS3ESSMENT 1997 C. IODINIIS AND PARTICULATES OUARTI!R j. 2 3. 4 ANNUN, Y
(a) (a) (a) (a) (a)
Organ (mrem) 1.64E 03 1.64E 03 9.31E 04 8.07E 04 5.02E 03
% of Limit 2.19E 02 2.191! 02 1.24E 02 1.08E 02 3.35E 02 Organ Dose Rate 9.52E-04 1.04E 03 7.31E 04 8.29E 04 1.04E 03 2
(mrem /yr)
- % of Limit 6.35E 05 6.93E 05 4.87E-05 5.53E 05 6.93E 05 (a) Dose to the Child Thyroid primarily by the vegetation pathway.
Page 25 of 27
- - '. NEW YORK POWER AUTilORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT I EFFLUENT AND WFTE DISPOSAL SEMIANNUAL REPORT JULY 1997 - DECEMBER 1997 ADDENDUM 1 (continaed)
TAHLE 2 METEOROLOGICAL DATA AND LOCATIONS OF INTEREST l
GEOGRAPillC ATMOSPilERIC I RECEPTOR LOCATION DISPERSION FACTOR l A. IODINE & DISTANCE / RELEASE X/Q D/Q PARTICULATES DIRECTION POINT (sec/m') (1/m )
2
- 1. - Garden 0.93 ml @ 82'E ST 2.86E 08' l.72E 09 Grazing Season 0.93 ml @ 82'E RX 1.94E-07* 4.76E 99 Cary 0.93 ml @ 82'E TB 1.76E 07* 4.57F 09 Location No. 78 0.93 ml @ 82'E RF 1.94E-07* 4.762 09 0,93 mi @ 82*E RW 3.08E 07* 5.45E 09
- 2. Meat 1.24 ml @ 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 ml @ 126'SE TD 4.97E 08* 1.21E 09 Location No. 26 1.24 mi @ 126'SE RF 5.17E-08* 1.24E 09 1.24 ml @ 126*SE RW 8.74E-08* 1.39E-09
- 3. Cow 2.2 mi @ 138'SE ST 1.65E-08* 3.11E 10 Urazing Season 2.2 mi @ 138'SE RX 3.04E 08' 5.07E 10 France 2.2 mi @ 138 SE TB 2.98E-08
- 4. Goat 2.5 mi @ 146'SE ST 1.67E 08' 2.65E-10 Gr zing Season 2.5 mi @ 146'SE RX 2.76E 08' 4.14E-10 Nickolas 2.5 mi @ 146*SE TB 2.71r 08* 4.07E 10 ,
Location No. 61 2.5 mi @ 146'SE RF 2.76E 08* 4.14E-10 2.5 mi @ 146*SE RW 4.15E 08' 4.36E 10
- 5. Resident Annual Average
- a. Inhalation 1.55 ml @ 90'E" ST 2.99E 08 -
0.93 mi @ 82*E RX l.98E-07 -
0.93 mi @ 82*E TB 1.81E 07 -
i 0.9' ml @ 82*E RF l.98E 07 -
! 0.9. mi @ 82*E RW 2.93E-07 -
- Tiitium Dose Calculation Only "llighest Sector Average X/Q in a populated area.
1 i
Page 26 of 27 l
'. NEW YORK POWER AUlllORITY JAMES - A. FITZPATRICK NUCLEAR POWER PLANT ,
EFFLUENT AND WASTE DISPOSAL l SEMIANNUAL REPORT JULY 1997 DECEMBER 1997 ADDENDUM i (continued) 4 TAHLE 2 METEOROLOGICAL DATA AND LOCATIONS OF INTEREST GEOGRAPillC ATMOSPilERIC Rl!CEPTOR LOCATION . DISPERSION FACTOR A. IODINE & DISTANCE / RELEASE X/Q D/Q PARTICULATES DIRECTION POINT (sec/m')
2 (1/m )
5 b. Deposition 0.70 ml @ 118'ESE ST -
1.61E 09 0.70 mi @ ll8*ESE RX -
5.65E-09 0.70 ml @ ll8'ESE TB - 5,42E 09 0.70 mi @ ll8'ESE RF - 5.651!09 0.70 ml @ ll8'ESE RW - 6.42E 09 H. NOHLE GASES
- 1. Air Dose 1.55 ml @ 90'E ST 2.99E 08 -
Annual Average 0.6 ml @ 90'E ST(fe) 1.16E 07 -
0.6 ml @ 90'E RX 3.58E 07 -
L 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 ml @ 90*E ST(fe) 1.16E 07 -
Annual Average "6 ml @ 90*E RX 3.58E 07 -
J.6 mi @ 90*E TD 3.19E 07 -
0.6 ml @ 90'E RF 3.58E-07 -
0.6 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(fe) 1.16E-07 -
0.6 mi @ 90*E RX 3.58E 07 -
0.6 mi @ 90'F TB 3.19E-07 -
c 0.6 ml @ 90*E RF 3.58E 07 -
0.6 mi @ 90*E RW 5.39E 07 -
ST = Main Stack RX = Reactor Building l
TH = Turbine Building Vent RF = Refuel Floor Vent RW = Radwaste Ven:
fc = Finite Cloud i
Page 27 of 27
.._-~_ , _ _ _ _ _ . _ . _ _ _ . . . _ . .
i
0.0 REFERENCES
0.1 Regulatory Guide 1.109, Rev.1, October 1977.
6.2 NUREG-0133, October 1978.
G.3 AP 02.08, Ounlity Assurance Record Identification and Control *, Revision 2 April 18,1995.
G.4 Technical Specifications, Apper. dix 8.
0.5 James A. FitzPatrick Nuclear Power Plant, Docket 50 333, Compliance with 10 CFR 50, Appendix 1.
0.0 Final Environmental impact Statement Related to Operation of James A.
FitzPatrick Nuclear Power Plant, New York Power Authority, Docket No. 50 333, March 1973.
0.7 Environmental Report, Operating License Stage, James A. FitzPatrick Plant, New York Power Authority, May 1971.
0.7.1 Supplement Environmental Report, Operating License Stage, November 1971.
0.7.2 Supplement #2 Environmental Report, Benefit / Cost Analysis, May 1972.
0.7.3 Supplement #3 Environmental Report, Answers to Atomic Energy Commission Questions, August 1982.
0.8 Final Safety Analysis Report, James A. FitzPatrick Plant, New York Power Authority, Docket No. 50 333, Operating License No. DPR 59, 0.9 New York Power Authority, Internal Memorandum from D. Dunning to G. Re, September 20,1988.
6.10 New York Power Authority, Corporate Radiological Engineering Calculation No.
JAF CALC-RAD 00025, Revision 1, Atmospheric Dispersion and Deposition Parameters for Routino Releases (1995).
6.11 CHAS. T. Main, Inc X/O and D/O Tables for Nine Mile Po,'nt Unit 1 Nine Mile Point Unit 2 and James A. FitzPatrick Nuclear Power Plant, November 1985 (Contain 5 years of meteorological data,1978 through 19"4 G.12 Idaho National Engineering Laboratory Technical Evalutation Report (TER) of the JAF ODCM for the NRC (EGG PHY-8153, July 1988).
Rev.No._L. Pone _79_ of ODCM
i ,
6 f
The l'. factors for the vents were calculated by multiplying the manufacturer's efficiency for Kr 85,1.11E 8 Cl/(cc-cpm), by the flow rate for the release point.
Flow rate K factor Eglease Point Jfm) (uCli/(sec com)
Turbine Building 107,000 0.50 Reactor Building 61,000 0.32 Refuel Floor 70,000 0.37 Radwaste 32,500 0.17
, Building i
Stack monitor K factors are reviewed on a periodic basis. A 4
conservative factor of 1.2 Cl/(sec cps) was selected taking into account potential worst case conditions of standby gas treatment in service. The setpoint limit for the stack was calcula'.M by dividing the setpoint release rate by the K factor. The setpoint limit for the stack follows, "i
Setpoint Releaue K factor Setpoint Rate (uCl/sec) fpcil/(see-cps) Limit (con)
Stack 300,000 1.2 250,000 4
The total body dose is more lim' ting than the calculated skin dose.
Therefore, the skin dose rate calculations are not required if the
' simplified dose rate calculation is used (i.e., using K,n to determine release rate limits).
The calculating processes of step 4.3.1.c are to be used if the actual releases of noble gases exceed the predetermined limits of 3.0E+5 Cl/sec for elevated stack releases or 6.98E+4 pCl/sec for vent releases.
Under these conditions, a nuclide-by nuclide evaluation is required to evaluate compliance with the dose rate limite of Technical Specifications, Appendix B, Section 3.2.a.1.
Rev,No. 5 Page _44 of ODCM
'. l
,' kist of Tables EA22 2.1 1 Radioactivs Liquid Effluent Monitoring Instrumentation 6 2.1 2 Minimum Test and Calibration Frequency for Radiation 7 Monitoring Systems 2.2 1 R6dioactive Liquid Waste Sampling and Analysis Program 11 3.1 1 Radiation Monitoring Systems that initiate and/or Isolate Systems 20 3.1 2 Minimum Test and Calibration Frequency for Radiation 21 Monitoring Systems 3.2 1 Radioactive Gbseous Waste Sampling and Analysis Program 25 5.1 1 Operational Radiological Environmental Monitoring Program
. 42 5.1 2 Reporting Level for Radioactivi*.y Concentrations in Unvironmental 40 Samples 5.1 3 Detection Capabilities for Environmental Sample Analysis - 47 Lower Limit of Detection 9
e ill
2.0 LIQUID EFFLUENTS 2.1 Liquid Effluent Monitors 2.1.1 Limiting Conditions For Operation
- u. Applicability Applies to the instrumentation required for monitoring radioactive liquid effluent discharges to the environment as specified in Table 2,1 1.
- b. Objective To ensure that radioactive liquid effluent discharges are properly monitored and recorded during release in accordance with 2,1 of Appendix B to the Technical Spec!fications,
- c. Specifications
- 1. The limiting conditions for operation of the instruments that monitor radioactive liquid effluents are given in Table 2,11. With a radioactive liquid effluent monitoring instrumentation channel alann/ trip set point less conservative than required by the ODCM, without delay suspend the release of radioactive liquid offluents monitoled by the affected channel, or declare the channel inoperable, or change the set point so it is acceptably conservative,
- 2. With less than the minimum number of radioactive liquid effluent monitoring Instrumentation channels operable, take the action shown in Table 2.1-1 Take corrective actions to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Semlannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner, NOTE- This reporting requirement does not apply to instruments which would not have been required to be operable during the 30 day period.
2.1.2 Surveillance Requirements
- a. Applicability Applies to the instrumentation for monitoring radioactive liquid effluent discharges.
Page 4 _ of _ R EC_
Rev.No.._5__
Table 2.12 MINIMUM TEST AND CAllPRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS
- Instrument Instrument Channel Instrument Logic System Instr
- ament Channela Check *' M'nctiona) Channel Function Test *' Calibration Test 'O
Liquid Radwante Daily When Discharge Quarterly Quarterly semiannually Diccharging Monitor / Isola-t i on "' '8' '"
Liquid Radwaste Daily Quarterly once per --
Discharge 18 monthe kadioactivity R e co rd e r
Liquid kadwaste Daily Quarterly once per ---
Discharge Flow Rate le months Measuring Devices
Normal Service Water Daily Quarterly Quarterly ---
Effluent NOTES FOR TABLE 2.1-2 (a) Functional tests, calibrations and instrument checks need not t 3 performed when these instruments are not required to be operable or are tripped.
(b) Instrument checks shall be performed at least once per day during these periods when the instruments are required to be operable.
(c) A source check shall be performed prior to each release.
(d) Liquid radwaste effluent line instrumentation surveillance requirements need not be performed when the instruments are not required as the result of the discharge path not being utilized.
(e) An instrument channel calibration shall be performed with knom. radioactive sources standardized on plant equipment which has been calibrated with NSS traceable standards.
(f) bculated automatic actuation shall be performed once per 24 months. Where possible, alllogic system functional tests will be performed using the test Jacks.
Rev.No. 5 Page 7 of REC
+
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS 1.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1.1 Sampling Stations / Locations The current sampling locations are specified on Table H 1 and Figures H 1, H 2 and H 3. The Radiological Environmental Monitoring Program is a joint effort between the Niagara Mohawk Power Corporation and the New York Power Authority, the own a and operators of the Nine Mile Point Unit 1, Nine Mile Point Unit 2 and the James A. FitzPatrick Nuclear Power Plant, respectively.
Sampling locations are chosen on the basis of historical average dispersion or deposition parameters from the three units.
The average dispersion and deposition parameters for the three reactors have been calculated for a five (5) year period,1978 through 1982 (Reference 0.11 i
C.T. Main Data). Ingestion sample location evaluations are based on calculations performed by C.T. Main as this report contains grazing season X/O and D/O calculations for each of the seven release sts in use at the JAF/NMP site Milk animallocations are evaluated using grazing season D/Os with the grazing season defined as (April to December). The April through December grazing season is used to coincide with the April through December milk sampling period required by the Technical Specifications. The deposition factor is evaluated at the census locations for each of seven release points (NMP 1 stack, NMP 2 stack, NMP 2 vent, JAF stack, JAF TB vent, JAF RW vent, and
- JAF RB vent). An arithmetic average of all relaase points is calculated and used in the evaluation. If it is determined that a milk samoling location exists at a location that yields a significantly higher (e.g. 50%) calculated D/Q rate, the new milk sampling location will be added to the monitoring program within 30 days. If a new location is added, the old location that yieldn the lowest calculated D/Q may be dropped from the program after October 31 of that year.
)
1.2 Interlaboratory Comparison Program Analyses shall be performed on samples containing known quantities of radioactive material that are supplied as part of a commission approved or sponsored Interlaboratory Comparison Program. Sample analysis shall be only for those media, (e.g. air, milk, water, etc.), that are included in the Nine Mile Point Environmental Monitoring Program and for which cross check samples are routinely available. The Quality Control sample results shall be reported in the Annual Radiological Environmental Operating Report so that the Commission staff may evaluate the results.
- . TABU H 1 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLING LOCATIONS MAP' TYPE OF LOCATION COLLECTION SITE LOCATION' SAMPLE (FlGURE NO.)
Radiolodine and 1 (H 1) Nins Mile Point Road 1.8 mi @ 88' E Particulates (air) North (R 1)
Radiolodine and 2 (H 1) Co Rt. 29 & Lake Road (R 2) 1.1 ml @ 104' ESE Particulates (air)
Radioiodine and 3 (H 1) Co. Rt. 29 (R 3) 1.5 ml @ 132* SE Particulates (air)
Radiciodine and 4 (H 1) Village of Lycoming, NY (R-4) 1.8 ml @ 143' SSE Particulates (air)
Radiolodine and 3 (H 1) Montario Point Road (R-5) 10.4 ml @ 42' NE Particulates (air) l l Direct Radiation (TLD) 0(H3) North Shoreline Area (75) 0.1 mi @ 5' N Direct Radiation (TLD) 7 (H 3) North Shoreline Area (76) 0.1 rni @ 25' NNE Direct Radiation (TLD) 8 (H-3) North Shoreline Area (77) 0.2 mi @ 45' NE Direct Radiat:r.,n (TLD) 9 (H 3) North Shoreline Area (23) 0.8 mi @ 70* NE l Direct Radiation (TLD) 10 (H 2,H 3) JAF East Boundary (78) 1.0 ml @ 90' E Direct Radiation (TLD) 11 (H 2,H 3) Rt. 20 (79) 1.1 ml @ 115' ESE Direct Radiation (TLD) 12 (H 2,H 3) Rt. 29 (80) 1.4 ml @ 133' SE Direct Radiation (TLD) 13 (H-2,H-3) Miner Road (81) 1.0 mi @ 159' SSE Direct Radiation (TLD) 14 (H 2.H 3) Miner Road (82) 1.6 ml @ 181* S Direct Radiation (TLD) 15 (H-2.H 3) Lakeviev' Road (83) 1.2 mi @ 200' SSW Direct Radiation (ll.D) 16 (H 2,H 3) Lakeview Road (84) 1.1 mi @ ' .:5' SW
- See Figures H-1, H-2 and H 3 for map locations
+ Based on 9 Mile Point Unit 2 Reactor Centeriino Rev.No. 5 Page H 5 of ODCM
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