ML061300237

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Enclosure 1, Nine Mile Point, Unit 2 - Radioactive Effluent Release Report
ML061300237
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 05/01/2006
From:
Constellation Energy Group
To:
Office of Nuclear Reactor Regulation
References
Download: ML061300237 (24)
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Text

ENCLOSURE (1)

NINE MILE POINT NUCLEAR STATION, UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2005 - December 31, 2005 Facility Operating License NPF-69 Docket No. 50-410 Nine Mile Point Nuclear Station, LLC May 01, 2006

NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT January - December 2005 Constellation Energy-Nine Mile Point Nuclear Station

Page 1 of 2 NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2005 SUPPLEMENTAL INFORMATION Facilit : Nine Mile Point Unit #2 Licensee: Nine Mile Point Nuclear Station, LLC

1. TECHNICAL SPECIFICATIONIODCM LIMITS A) FISSION AND ACTIVATION GASES
1. The dose rate limit of noble gases released in gaseous effluents from the site to areas at or beyond the site boundary shall be less than or equal to 500 mrem/year to the whole body and less than or equal to 3000 mrem/year to the skin.
2. The air dose from noble gases released in gaseous effluents from Nine Mile Point Unit 2 to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and during any calendar year to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

B&C) TRITIUM, IODINES AND PARTICULATES, HALF LIVES > 8 DAYS

1. The dose rate limit of lodine-1 31, lodine-1 33, Tritium and all radionuclides in particulate form with half-lives greater than eight days, released in gaseous effluents from the site to areas at or beyond the site boundary shall be less than or equal to 1500 mremlyear to any organ.
2. The dose to a member of the public from lodine-1 31, lodine-1 33, Tritium and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from Nine Mile Point Unit 2 to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrem to any organ and, during any calendar year to less than or equal to 15 mrem to any organ.

D) LIQUID EFFLUENTS

1. Improved Technical Specifications (ITS) limits the concentration of radioactive material released in the liquid effluents to unrestricted areas to ten times the concentrations specified in 10CFR20.1001-20.2402, Appendix B,Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 microcuries/mi total activity.

Page 2 of 2

2. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 2 to unrestricted areas shall be limited during any calendar quarter 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 during any calendar year 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. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents.

A) FISSION AND ACTIVATION GASES Noble gas effluent activity is determined by on-line gamma spectroscopic monitoring (intrinsic germanium crystal) of an isokinetic sample stream.

B) IODINES Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled from an isokinetic sample stream.

C) PARTICULATES Activity released from the main stack and the combined Radwaste/Reactor Building vent is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from an isokinetic sample stream and composite analysis of the filters for non-gamma emitters.

D) TRITIUM Tritium effluent activity is measured by liquid scintillation or gas proportional counting of monthly samples taken with an air sparging/water trap apparatus.

E) LIQUID EFFLUENTS Isotopic contents of liquid effluents are determined by isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters.

F) SOLID EFFLUENTS Isotopic contents of waste shipments are determined by gamma spectroscopy analyses of a representative sample of each batch. Scaling factors established from primary composite sample analyses conducted off-site are applied, where appropriate, to find estimated concentration of non-gamma emitters. For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.

Attachment I Page 1 of 2 Summary Data Unit 1 Unit 2 X Reporting Period January -December2005 Liquid Effluents:

ODCM Required MEC = 10 x 10CFR20.1001-20.2402, Appendix B, Table 2, Column 2 There were no discharges of liquid radwaste requiring use of MEC to determine allowable release rate.

Average MEC - pCi/ml (Qtr. ) = NORELEASESl Average MEC - pCiml (Qtr. 3) = INO RELEASES Average MEC - pC/ml (Qtr. _) = INORELEASES Average MEC - pCiml (Qtr. 4) = INO RELEASES Average Energy (Fission and Activation gases - WeV):

Qrtr. 1: Ey = 6.46E-01 EO = 2.37E-01 Qrtr. 2: Ey = 6.24E-01 EP = 2.36E-01 Qrtr. 3: Ey = 8.97E-01 E3 = 3.03E-01 Qrtr. 4: Ey = 7.68E-01 E = 2.63E-01 Liquid:

Numbr of Batch Releases 0 Total Time Period for Batch Releases (hrs) N/A Maximum Time Period for a Batch Release (hrs) N/A Average Time Period for a Batch Release (hrs)N/A Minimum Time Period for a Batch Release N/A ITotal volume of water used to dilute the liquid i-2 2d 3 4 th effluent during the release period (L) I N/A NA' N/A N/A Total volume of water available to dilute the liquid I1t 2nd 3rd 4_

effluent during the release period (L) I N/A N/A NA N/A Gaseous (Emergency Condenser Vent): "Not applicable for Unit 2" Numbr of Batch Releases N/A ]

Total Time Period for Batch Releases (hrs) N/A Maximum Time Period for a Batch Release (hrs) N/A Average Time Period for a Batch Release (hrs) N/A J Minimum rime Period for a Batch Release N/A Gaseous (Primary Containment Purge):

Numbr of Batch Releases 10 Total Time Period for Batch Releases (hrs) 4.33E+02 Maximum Time Period for a Batch Release (hrs) 9.17E+01 Average Time Period for a Batch Release (hrs) 4.33E+01 Minimum Time Period for a Batch Release 7.48E+00

Attachment I Page 2 of 2 Summary Data Unit I _ Unit 2 X Reporting Period January - December 2005 Abnormal Releases:

A. Liquid:

INumber of Releases 0 lTotal Activity Released N/A Ci B. Gaseous:

INumber of Releases 0 ITotal Activity Released N/A Ci

Attachment 2 Page 1 of 1 Unit I Unit 2 X Reporting Period January - December 2005 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL 1st 2nd 3rd 4th Est. Total Quarter Quarter Quarter Quarter Error.%/6 A. F-ission & Activation Gases

1. Total release Ci 3.56E+01 4.12E+01 5.20E+01 4.59E+01 5.OOE+01
2. Average release rate pCilsec 4.60E+00 5.23E+00 6.55E+00 5.76E+00 B. lodines
1. Total lodine- 131 Ci 2.02E-05 4.74E-05 2.63E-04 1.08E-04 3.OOE+01
2. Average release rate for period pCi/sec 2.57E-06 6.02E-06 3.35E-05 1.38E-05 C. Particulates
1. Particulates vith half-lives >8 days Ci 1.50E-04 l 7.05E-05 l 9.53E-05 l 8.85E-05 3.OOE+01
2. Average release rate for period pCi/sec 1.90E-05 8.96E-06 1.21E-05 1.13E-05
3. Gross alpha radioactivity Ci 1.16E-05 2.37E-05 3.18E-05 1.91E-05 2.50E+01 D. Tritium
1. Total release Ci 2.33E+01 2.26E+01 4.26E+01 4.55E+01 5.OOE+01
2. Average release rate for period pCi/sec 2.96E+00 2.87E+00 5.41 E+00 5.78E+00 E. Percent of Tech. Spec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose 5.88E-02 1.08E-01 8.12E-02 5.27E-02 Limit (5 mR)

Percent of Quarterly Beta Air Dose Limit 9.38E-04 1.08E-03 1.74E-03 1.34E-03 (10 mrad)

Percent of Annual Gamma Air Dose 2.64E-02 5.58E-02 1.10E-01 1.50E-01 Limit to Date (10 mR)

Percent of Annual Beta Air Dose Limit to 4.69E-04 1.01 E-03 1.88E-03 2.56E-03 Date (20 mRad)

Percent of Whole Body Dose Rate Limit 2.07E-03 2.29E-03 4.15E-03 3.13E-03 (500 mrem/yr)

Percent of Skin Dose Rate Limit (3000 4.04E-04 4.46E-04 8.08E-04 6.09E-04 mrem/yr)

Tritium. lodines. and Particulates (with half-lives greater than 8 days)

Percent of Quarterly Dose Limit (7.5 7.96E-02 3.92E-02

%/ 1.29E-02 1.89E-02 mrem)

Percent of Annual Dose Limit to Date (15 1.60E-02 5.61 E-02 7.61 E-02 6.52E-03 mrem)

Percent of Organ Dose Limit (1500 3.79E-04 1.58E-03 7.79E-04 2.63E-04 mremtyr

Attachment 3 Page 1 of 1 Unit I Unit 2 X Reporting Period January - December 2005 GASEOUS EFFLUENTS - ELEVATED RELEASE Continuous Mode (2)

Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases (1)

Argon-41 Ci ** 5.83E-02 1.20E-01 Krypton-85 Ci ** **

Krypton-85m Ci 8.93E+00 1.09E+01 1.36E+01 1.48E+01 Krypton-87 C ** ** 1.56E+00 1.09E-01 Krypton-88 Ci 1.07E+01 1.19E+01 2.18E+01 1.64E+01 Xenon-127 Ci ** ** ** **

Xenon-131 m Ci Xenon-133 C 1.60E+01 1.84E+01 1.50E+01 1.44E+01 Xenon-133m Ci Xenon-135 Ci ** ** ** **

Xenon-135m Ci ** ** ** **

Xenon-137 Ci Xenon-138 Ci lodines (1) lodine-131 Ci 2.02E-05 4.74E-05 2.52E-04 1.02E-04 l lodine-133 Ci 5.21E-05 2.50E-04 2.44E-03 4.67E-04 Iodine-135 Ci *4 * ** 1 **

Particulates (1)

Strontium-89 Ci ** **

Strontium-90 Ci ** **

Cesium-134 Ci ** **

Cesium-137 Ci **

Cobalt-60 Ci 3.12E-06 1.32E-05 4.33E-05 Cobalt-58 Ci Manganese-54 Ci Barium-140 C 4* ** 44 **

Lanthanum-140 Ci Niobium-95 Ci ** ** ** **

44 Cerium-141 Ci ** ** **

Cerium-144 Ci ** ** ** **

Iron-59 Ci Cesium-136 Ci ** ** ** **

Chromium-51 Ci ** ** ** **

Zinc-65 Ci Iron-55 Ci ** **

Molybdenum-99 C ** **

Neodymium-147 Ci Zirconium-95 Ci Tritium (1) Ci l1.46E+01 i .15E+01 l .95E+01 l .87E+01OI (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk "**.

A lower limit of detection of 1.00E-04 pCiml for required noble gases, 1.OOE-1i1 pCi/ml for required particulates, 1.OOE-12 pCi/mi for required lodines, and 1.OOE-06 pCi/ml for Tritium as required by the ODCM, has been verified.

(2) Contributions from purges are included. There were no other batch releases during the reporting period.

Attachment 4 Page 1 of 1 Unit I _ Unit 2 X Reporting Period January - December 2005 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode (2)

Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases (1)

Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Kypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci **** *-* **7E0 Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci ** ** ** **

lodines (1)

Iodine-131 Ci **1E0 ** ** **

Iodine-133 Ci Iodine-135 Ci Particulates (1)

Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci ** ** ** **

Cesium-137 Ci Cobalt-60 Ci **8E0 **iE0 **iEO **8EO Cobalt-58 Ci Manganese-54 Ci Barium-140 Ci Lanthanum-140 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci Iron-59 Ci Cesium-136 Ci Chromium-51 Ci Zinc-65 Ci Iron-55 Ci Molybdenum-99 Ci Neodymium-147 Ci Zirconium-95 Ci Tritium (1) Ci (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk -"

A lower limit of detection of 1.OOE-04 pCiml for required noble gases, 1.OOE-1 1 pCi/ml for required particulates and gross alpha, 1.00E-12 pCiml for required iodines, and 1.OOE-06 pCi/ml for Tritium, as required by the ODCM, has been verified (2) There were no batch releases from this path during the reporting period.

Attachment 5 Page 1 of 2 Unit I Unit 2 X Reporting Period January - December 2005 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Es. T A. Fission & Activation Products

1. Total Release (not including Tritium, No Release 5.OOE+01 Ci No Release No Release No Release gases, alpha)
2. Average diluted concentration No Release No Release pCifml No Release No Release during reporting period B. Tritium I.Total release
2. Average diluted concentration Ci PCi/ml I No Release No Release No Release No Release No Release No Release No Release No Release 5.OOE+01 during the repoorting period C. Dissolved and Entrained Gases
1. Total release
2. Average diluted concentration Ci pCi/mI

[ No Release No Release No Release No Release

[No Release No Release

[No Release No Release 5.OOE+01 during the reporting period D. Gross AlDha Radioactivity

1. Total release Ci I No Release INo Release INo Release I No Release 5.00E+01 E. Volumes
1. Prior to Dilution Liters No Release No Release No Release No Release 5.OOE+01
2. Volume of dilution water used during No Release No Release I 5.OOE+01 Liters No Release No Release release period
3. Volume of dilution water available 1.27E+10 1.61E+10 1.36E+10 I 5.OOE+01 Liters 1.17E+10 during reporting period F. Percent of Tech. Spec. Limits Fission and Activation Gases Percent of Quarterly Whole Body Dose No Release No Release No Release No Release Limit (1.5 mrem)

Percent of Annual Whole Body Dose No Release No Release No Release No Release Limit to Date (3 mrem)

Percent of Quarterly Organ Dose Limit No Release No Release No Release No Release (5 mrem)

Percent of Annual Organ Dose Limit to No Release No Release No Release No Release Date (10 mrem)

Percent of 10CFR20 Concentration No Release No Release No Release No Release Limit Percent of Dissolved or Entrained No Release No Release No Release No Release Noble Gas Limit (2.OOE-04 luCi/ml) No Release No Release No Release No Release

Attachment 5 Page 2 of 2 Unit 1 _ Unit 2 X Reporting Period January - December 2005 LIQUID EFFLUENTS RELEASED Continuous Mode (1)

Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Nuclides Released Strontium-89 Ci No Release No Release No Release No Release Strontium-90 Ci No Release No Release No Release No Release Cesium-1 34 Ci No Release No Release No Release No Release Cesium-1 37 Ci No Release No Release No Release No Release Iodine-131 Ci No Release No Release No Release No Release Cobalt-58 Ci No Release No Release No Release No Release Cobalt-60 Ci No Release No Release No Release No Release Iron-59 Ci No Release No Release No Release No Release Zinc-65 Ci No Release No Release No Release No Release Manganese-54 Ci No Release No Release No Release No Release Chromium-51 Ci No Release No Release No Release I No Release Zirconium-95 Ci No Release No Release No Release No Release Niobium-95 Ci No Release No Release No Release No Release Molybdenum-99 Ci No Release No Release No Release No Release Technetium-99m Ci No Release No Release No Release No Release Barium-140 Ci No Release No Release No Release No Release Lanthanum-140 Ci No Release No Release No Release No Release Cerium-141 Ci No Release No Release No Release No Release Tungsten-187 Ci No Release No Release No Release No Release Arsenic-76 Ci No Release No Release No Release No Release Iodine-133 Ci No Release No Release No Release No Release Iron-55 Ci No Release No Release No Release No Release Neptunium-239 Ci No Release No Release No Release No Release Silver-11 Om Ci No Release No Release No Release No Release Gold-199 Ci No Release No Release No Release No Release Cerium-144 Ci No Release No Release No Release No Release Cesium-136 Ci No Release No Release No Release No Release Copper-64 Ci No Release No Release No Release No Release Manganese-56 Ci No Release No Release No Release No Release Sodium-24 Ci No Release No Release No Release No Release Nickel-65 Ci No Release No Release No Release No Release Antimony-124 Ci No Release No Release No Release No Release Strontium-92 Ci No Release No Release No Release No Release Tellurium-1 32 Ci No Release No Release No Release No Release Dissolved or Entrained Gases Ci I No Release I No Release I No Release No Release Tritium Ci I No Release I No Release I No Release I No Release (1) There were no Batch Mode releases during the report period. No continuous mode release occurred during the indicated by effluent monitoring.

Attachment 6 Page 1 of 4 Unit I Unit 2 X Reporting Period January- December 2005 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Al. TYPE Volume Activity (1) 3 (M ) (Ci)

Class Class A B C A B C a.1 Spent Resins 1.72E+02 3.41 E+00 O.OOE+00 2.49E+03 4.59E+02 O.OOE+00 (Dewatered) a.2 Filter Sludge O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 a.3 Concentrated Waste O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Totals 1.72E+02 3.41 E+00 0.OOE+00 2.49E+03 4.59E+02 0.00E+00 b.1 Dry, compactible waste 1.42E+02 O.OOE+00 O.OOE+00 3.35E+00 O.OOE+00 O.OOE+00 b.2 Dry, non-compactible waste (contaminated 3.56E+01 O.OOE+00 O.OOE+00 2.37E-02 O.OOE+00 O.OOE+00 equipment)

Totals 1.78E+02 0.OOE+00 0.OOE+00 3.37E+00 0.OOE+00 0.00E+00

c. Irradiated Components, Control Rods l

I 0.00E+00 l I

0.O0E+00 l I

O.00E+O0 I I

0.00E+00 T I

0.00E+00 II 0.00E+00

d. Other (to Vendor for Processing or Consolidation) d.1 Cooling Tower Silt 6.74E+01 O.OOE+00 0.OOE+00 9.75E-07 0.OOE+00 O.OOE+00 d.2 Tank Sediment 3.80E+00 O.OOE+00 0.OOE+00 9.68E+00 0.OOE+00 0.00E+00 (1) The estimated total error is 5.OE+01%

Attachment 6 Page 2 of 4 Unit I Unit 2 X Reporting Period January - December 2005 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Al. TYPE Container Package Solidification Agent a.1 Spent Resin (Dewatered) Poly Liner General Design Type A/Type B None a.2 Filter Sludge N/A N/A N/A a.3 Concentrated Waste N/A NIA NIA b.1 Dry, Compressible waste Metal Box General Design None b.2 Dry, non-compressible Metal Box General Design None waste

c. Irradiated Components, NIA N/AN/A Control Rods
d. Other (To vendor for processing) d.1 Cooling Tower Silt Metal Box General Design None d.2 Tank Sediment Poly Liner Type A None

Attachment 6 Page 3 of 4 Unit I _ Unit 2 X Reporting Period January - December 2005 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)

a. Spent Resins, Filter Sludges, Concentrated Waste Nuclide Percent Fe-55 43.1 Co-60 39.1 Mn-54 6.6 Zn-65 6.2 Ni-63 1.2 Ce-144 3.0 Other 0.8
b. Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment)

Nuclide Percent Fe-55 79.9 Co-60 16.3 Mn-54 3.1 Other 0.7

c. Irradiated Components, Control Rods Nuclide Percent N/A N/A
d. Other (To vendor for processing)
1. Cooling Tower Silt Nuclide Percent Co-60 67.7 Mn-54 25.2 Cs-137 7.1
2. Tank Sediment Nuclide Percent Fe-55 68.6 Co-60 24.5 Mn-54 4.1 Zn-65 2 Other 0.8

Attachment 6 Page 4 of 4 Unit I _ Unit 2 X Reporting Period January - December 2005 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A3. SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Detination 33 Hittman Transport Studsvik Processing Facility 2 Hittman Transport GTS Duratek 2 Hittman Transport Race, LLC 2 Race Logistics Race, LLC Tri State Motor Transit Studsvik Processing Facility B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination N/A N/A N/A D. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIAL There were no shipments of sewage sludge with detectable quantities of plant-related nuclides from NMP to the treatment facility during the reporting period.

Attachment 7 Page 1 of 1 Unit 1 Unit 2 X Reporting Period January - December 2005

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL (ODCM)

The Unit 2 Off-Site Dose Calculation Manual (ODCM) was revised during the reporting period to add a new food product sample location and a new milk sample location and to delete two milk sample locations because the samples are no longer available. These changes are in conformance with the ODCM Part I and S-ENVSP-1 8 procedural requirements. These changes do not affect the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50 Appendix I, and do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. A copy of the ODCM, Revision 26 is attached and a summary of the changes presented to and approved by the Station Operations Review Committee on December 20, 2005 is provided below. The summary also includes the justification for the change.

Revision 26 Page # New/Amended Description of Change Reason for Change Section #

1164 Table D 5.1 Added a new sample During the 2005 land use census a new food product location 11107 Figure D 5.1-2 location for food product, was selected. The new food location isat 1.52 miles @ 850 E.

map location 68/produce The current food location is 1.76 miles @97° E. This new location #18 (1.52 miles location is in the same sector of the current location and has East (850 E) of Nine Mile the same site average DIQ.

Point.

II 63 Table D 5.1 Added Milk location #76 Milk locations #50 and #60 are no longer available. These 11107 Figure D 5.1-2 and removed milk locations locations are not required by the ODCM. They are not within

  1. 50 and #60. 5 miles nor do the meet the requirements of a control location (9-20 miles distant and in the least prevailing wind direction).

This change is administrative, the new location is consistent the previous location #50, i.e. similar wind direction and within the 5 - 9 mile distance.

Attachment 8 Page 1 of 1 Unit 1 _ Unit 2 X Reporting Period January- December 2005

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

There were no changes to the NMP2 Process Control Program (PCP) during this report period.

Attachment 9 Page 1 of I Unit 1 Unit 2 X Reporting Period January - December 2005

SUMMARY

OF INOPERABLE MONITORS Monitor Dates mno erabilitv of Cause and Corrective Actions

1) Main Stack Effluent November 10, 2005 The Gaseous Effluent Monitoring System (GEMS) Main Stack Noble Gas Activity @ 08:10 to Effluent Noble Gas Activity Monitor and Flow-Rate Monitor Monitor, la) Flow- December 12, 2005 channels were declared inoperable due to the failure of a Rate Monitor @ 14:55 communication link between the GEMS computer and both the Stack and Vent Monitors. Additionally, there was a power supply failure associated with the GEMS stack monitor. The necessary computer communication/interface card repair was completed on 12/9/05. Successful restart of the GEMS stack monitor and associated flow-rate monitor occurred after repair was made to the power supply. Repairs were not timely due to the obsolescence of failed components. GEMS is a one-of-a-kind off line real time gamma spectroscopy system. Because of the system age and obsolescence, replacement parts rely on used parts that are refurbished. The station has approved the consideration of a system replacement under the corrective action program.
2) Radwaste/Reactor November 10, 2005 The Gaseous Effluent Monitoring System (GEMS)

Building Vent @ 08:10 to Radwaste/Reactor Building Vent Effluent Noble Gas Activity Effluent Noble Gas December 12, 2005 Monitor and Flow-Rate Monitor channels were declared Activity Monitor, 2a) c 10:58 inoperable due to the failure of a communication link between Flow-Rate Monitor the GEMS computer and both the Stack and Vent Monitors.

The necessary computer communication/interface card repair was completed on 1219/05. Successful restart of the GEMS vent monitor occurred on 12/9/05 and operability was restored on 12/12/05 after repairs to the stack monitor power supply were completed. Repairs were not timely due to the obsolescence of failed components. GEMS is a one-of-a-kind off line real time gamma spectroscopy system. Because of the system age and obsolescence, replacement parts rely on used parts that are refurbished. The station has approved the consideration of a system replacement under the corrective action program.

Attachment 10 Page 1 of 4 Unit I _ Unit 2 X Reporting Period January -December 2005 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Introduction An assessment of the radiation dose potentially received by a Member of the Public due to their activities inside the site boundary from Nine Mile Point Unit 2 (NMP2) liquid and gaseous effluents has been conducted for the period January through December 2005.

This assessment considers the maximum exposed individual and the various exposure pathways resulting from liquid and gaseous effluents to identify the maximum dose received by a Member of the Public during their activities within the site boundary.

Prior to September 11, 2001, the public had access to the Energy Information Center for purposes of observing the educational displays or for picnicking and associated activities. Fishing also occurred near the shoreline adjacent to the NMP. Fishing near the shoreline adjacent to the NMP Site was the onsite activity that resulted in the potential maximum dose received by a Member of the Public. Following September 11, 2001 public access to the Energy Information Center has been restricted and fishing by Members of the Public at locations on site is also prohibited. Although fishing was not conducted during 2005 the annual dose to a hypothetical fisherman was still evaluated to provide continuity of data for the location.

Dose Pathways Dose pathways considered for this evaluation included direct radiation, inhalation and external ground (shoreline sediment or soil doses). Other pathways, such as ingestion pathways, are not considered because they are either not applicable, insignificant, or are considered as part of the evaluation of the total dose to a member of the public located off-site. In addition, only releases from the NMP2 stack and vent were evaluated for the inhalation pathway. Dose due to aquatic pathways such as liquid effluents is not applicable since swimming is prohibited at the Nine Mile Point Site.

Dose to a hypothetical fisherman is received through the following pathways while standing on the shoreline fishing:

  • External ground pathway; this dose is received from plant related radionuclides detected in the shoreline sediment.
  • Inhalation pathway; this dose isreceived through inhalation of gaseous effluents released from NMP2 Stack and Vent.
  • Direct radiation pathway; dose resulting from the operation of NMP2, Nine Mile Point Unit 1 (NMP1) and the James A.

Fitzpatrick (JAF) Facilities.

Methodologies for Determining Dose for Applicable Pathways External Ground (Shoreline Sediment) pathwav Dose from the external ground (shoreline sediment) is based on the methodology in the Unit 2 Offsite Dose Calculation Manual (NMP2 ODCM) as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the hypothetical maximum exposed individual fished from the shoreline at all times.

  • The total dose received by the whole body and skin of the maximum exposed individual during 2005 was calculated using the following input parameters: Usage Factor = 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> (fishing 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per week, 39 weeks per year)
  • Density in grams per square meter = 40,000
  • Shore width factor = 0.3
  • Fractional portion of the year = I (used average radionuclide concentration over total time period)
  • Average Cs-1 37 concentration = 1.75E-01 pCi/g The total whole body and skin doses received by a hypothetical maximum exposed fisherman from the external ground pathway is presented in Table 1, Exposure Pathway Dose.

Attachment 10 Page 2 of 4 Unit1 _ Unit 2 X Reporting Period January - December 2005 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Inhalation Pathwa, The inhalation dose pathway is evaluated by utilizing the inhalation equation in the NMP2 00CM, as adapted from Regulatory Guide 1.109. The total whole body dose and organ dose received by the hypothetical maximum exposed fisherman during 2005 is calculated using the following input parameters for gaseous effluents released from both the NMP2 Stack and Vent for the time period exposure is received:

NMP 2 Stack:

Variable Fisherman

  • X/Q (sM3) 9.60E-07 Inhalation dose factor Table E-7 Regulatory Guide 1.109 Annual air intake m3/year) (adult) 8000 Fractional portion of the year (hours) 0.0356 H-3 (pCi/sec) 2.11 E+06 Co-60 (pCi/sec) 2.39E+00 1-131 (pCisec) 1.70E+01 1-133 (pCilsec) 1.34E+2 NMP2 Vent:

Variable Fisherman

  • 3 X/Q (s/rn )2.80E-06 Inhalation dose factor Table E-7 Regulatory Guide 1.109 Annual air intake (m3/year) (adult) 8000 Fractional portion of the year (hours) 0.0356 H-3 (pCi/sec) 2.59E+06 Co-60 (pCi/sec) 5.01 E+00 1-131 (pCisec) 7.83E-01 1-133 (pCUsec) 1.42E+00
  • The maximum exposed fisherman is assumed to be present on site during the period of April through December at a rate of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per week for 39 weeks per year equivalent to 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> for the year (fractional portion of the year =

0.0356). Therefore, the Average Stack and Vent flow rates and radionuclide concentrations used to determine the dose are represented by second, third and fourth quarter gaseous effluent flow and concentration values.

The total whole body dose and maximum organ dose received by the hypothetical maximum exposed fisherman is presented in Table 1, Exposure Pathway Dose.

Attachment 10 Page 3 of 4 Unit1 _ Unit 2 X Reporting Period January -December 2005 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Direct Radiation Pathway The direct radiation pathway is evaluated in accordance with the methodology found in the NMP2 00CM. This pathway considers four components: direct radiation from the generating facilities, direct radiation from any possible overhead plume, direct radiation from ground deposition and direct radiation from plume submersion. The direct radiation pathway is evaluated by the use of high sensitivity environmental Thermoluminescent Dosimeters (TLDs). Since fishing activities occur between April 1 - December 31, TLD data for the second, third, and fourth quarters of 2005 from TLDs placed in the general area where fishing once occurred were used to determine an average dose to the hypothetical maximum exposed fisherman from direct radiation. The following is a summary of the average dose rate and assumed time spent on site used to determine the total dose received:

Variable Fisherman Average Dose Rate (mRem/hr) 1.59E-03 Exposure time (hours) 312 Total Doses received by the hypothetical maximum exposed fisherman from direct radiation is presented in Table 1, Exposure Pathway Annual Dose.

Dose Received By A Hypothetical Maximum Exposed Member Of The Public Inside the Site Boundary During 2005 The following is a summary of the dose received by a hypothetical maximum exposed fisherman from Liquid and Gaseous effluents released from NMP2 during 2005:

Table I Exposure Pathway Annual Dose Exposure Pathway Dose Type Fisherman (mRem)

Extemal Ground Whole Body 2.79E-03 Skin of Whole Body 3.25E-03 Inhalation Whole Body 4.17E-04 I Maximum Organ Thyroid: 4.35E-04 Direct Radiation Whole Body 0.50

Attachment 10 Page 4 of 4 UnitI _ Unit 2 X Reporting Period January -December 2005 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Based on these values the total annual dose received by a hypothetical maximum exposed member of the public is as follows:

Table 2 Annual Dose Summary Total Annual Dose for 2005 Fisherman (mRem)

Total Whole Body 5.OOE-01 Skin of Whole Body 3.25E-03 Maximum Organ Thyroid: 4.35E-04

Attachment 11 Page 1 of 2 Unit 1 _ Unit 2 X Reporting Period January - December 2005 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Introduction An assessment of radiation doses potentially received by the likely most exposed member of the public located beyond the site boundary was conducted for the period January through December 2005 for comparison against the 40 CFR 190 annual dose limits.

The intent of 40 CFR 190 requires that the effluents of Nine Mile Point Unit 2 (NMP2), as well as other nearby uranium fuel cycle facilities, be considered. In this case, the effluents of NMP2, Nine Mile Point Unit 1 (NMP1) and the James A.

FitzPatrick (JAF) facilities must be considered.

40 CFR 190 requires the annual radiation dose received by members of the public in the general environment, as a result of plant operations, be limited to:

  • < 25 mRem wholebody
  • < 25 mRem any organ (except thyroid)
  • < 75 mRem thyroid This evaluation compares doses resulting from Liquid and Gaseous effluents and direct radiation originating from the site as a result of the operation of the NMP2, NMP1 and JAF nuclear facilities.

Dose Pathways Dose pathways considered for this evaluation included doses resulting from liquid effluents, gaseous effluents and direct radiation from all nuclear operating facilities located on the Nine Mile Point Site.

Dose to the most likely member of the public, outside the site boundary, is received through the following pathways:

  • Fish consumption pathway; this dose is received from plant radionuclides that have concentrated in fish that is consumed by a member of the public.
  • Shoreline Sediment; this dose is received as a result of an individual's exposure to plant radionuclides deposited in the shoreline sediment, which is used as a recreational area.
  • Deposition, Inhalation and Ingestion pathways resulting from gaseous effluents; this dose is received through exposure to gaseous effluents released from NMP1, NMP2 and JAF operating facilities.
  • Direct Radiation pathway; radiation dose resulting from the operation of NMP1, NMP2 and JAF facilities.

Methodologies for Determinina Dose for Applicable Pathways Fish ConsumDtion Dose received as a result of fish consumption is based on the methodology specified in the NMP2 Off-site Dose Calculation Manual (NMP2 ODCM) as adapted from Regulatory Guide 1.109. The dose for 2005 is calculated from actual analysis results of environmental fish samples taken near the site discharge points. For this evaluation it is assumed that the most likely exposed member of the public consumes fish taken near the site discharge points.

No radionuclides were detected in fish samples collected and analyzed during 2005; therefore no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2005.

Shoreline Sediment Dose received from shoreline sediment is based on the methodology in the NMP2 ODCM as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the most likely exposed member of the public spends 67 hour7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br />s/year along the shoreline for recreational purposes.

Attachment 11 Page 2 of 2 Unit 1 _ Unit 2 X Reporting Period January - December 2005 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Shoreline Sediment Continued:

The total dose received by the whole body and skin of the maximum exposed individual during 2005 is calculated using the following input parameters:

  • Usage Factor = 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> per year
  • Density in grams per square meter = 40,000
  • Shore width factor = 0.3
  • Fractional portion of the year = 1
  • Average Cs-137 Concentration = 0.076 pCi/g Dose Pathways Resulting From Gaseous Effluents Dose received by the likely most exposed member of the public due to gaseous effluents is calculated in accordance with the methodology provided in the NMP2 ODCM, NMPI Offsite Dose Calculation Manual, and the JAF Offsite Dose Calculation Manual. These calculations consider deposition, inhalation and ingestion pathways. The total sum of doses resulting from gaseous effluents from NMP1, NMP2 and JAF during 2005 provide a total dose to the whole body and maximum organ dose for this pathway.

Direct Radiation Pathwa, Dose as a result of direct gamma radiation from the site, encompasses doses from direct 'shine" from the generating facilities, direct radiation from any overhead gaseous plumes, plume submersion and from ground deposition. This total dose is measured by environmental TLDs. The critical location is based on the closest year-round residence from the generating facilities as well as the closest residence in the critical downwind sector in order to evaluate both direct radiation from the generating facilities and gaseous plumes as determined by the local meteorology. During 2005, the closest residence and the critical downwind residence are at the same location.

Dose Potentially Received by the Likely Most Exposed Member of the Public Outside the Site Boundar During 2005

- Exposure Pathway l Dose Type [ Dose (mRem) 1 Fish Consumption Total Whole Body No Dose Total Maximum Organ No Dose Shoreline Sediment Total Whole Body 2.58E-04 Total Skin of Whole Body 3.01 E-04 Gaseous Effluents Total Whole Body 1.69-02 Total Maximum Organ Thyroid: 1.55E-01 Direct Radiation Total Whole Body 1.49 Based on these values the maximum total annual dose potentially received by the most likely exposed member of the public during 2005 is as follows:

  • Total Whole Body: 1.51 mRem
  • Total Skin of Whole Body: 1.31E-02 mRem
  • Maximum Organ: Thyroid: 1.55E-01 mRem 40 CFR 190 Evaluation The maximum total doses presented in this attachment are the result of operations at the NMP1, NMP2 and the JAF facilities. The maximum organ dose (Thyroid: 0.155 mRem) and the maximum whole body dose (1.51 mRem) are below the 40 CFR 190 criteria of 25 mRem per calendar year to the maximum exposed organ or the whole body, and below 75 mRem per calendar year to the thyroid.
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