ML12131A520

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Radioactive Effluent Release Report, January - December 2011
ML12131A520
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 05/01/2012
From: Dosa J
Constellation Energy Nuclear Group, EDF Group, Nine Mile Point
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12131A520 (33)
v • d • e


Text

op P.O. Box63 CENGS.

a joint venture of Lycoming, NY 13093 eeDF Constellation O Energy 10%

NINE MILE POINT NUCLEAR STATION May 1, 2012 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

Nine Mile Point Nuclear Station Unit No. 2; Docket No. 50-410 Radioactive Effluent Release Report, January - December 2011 In accordance with 10 CFR 50.36a and the Nine Mile Point Unit 2 (NMP2) Technical Specifications, enclosed is the Radioactive Effluent Release Report for the period January through December 2011.

Included in this report is a summary of gaseous and liquid effluents and solid waste released from the station during the reporting period (Attachments 1 - 6), a summary of revisions to the Offsite Dose Calculation Manual (ODCM) and the Radwaste Process Control Program during the reporting period (Attachments 7 and 8), and an explanation as to the cause and corrective actions regarding any station liquid and/or gaseous effluent monitoring instrumentation that was non-functional for greater than 30 days (Attachment 9). Attachments 10 and 11 provide a summary and assessment of radiation doses to Members of the Public within and outside the site boundary, respectively, from liquid and gaseous effluents, as well as direct radiation, in accordance with 40 CFR 190. Attachment 12 provides a summary of the tritium results from the groundwater protection program. Attachment 13 is a copy of Revision 33 and 34 of the ODCM.

The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1.

Dose assessments were made in accordance with the NMP2 ODCM. During the reporting period from January through December 2011, NMP2 did not exceed any 10 CFR 20, 10 CFR 50, Technical Specification, or ODCM limits for gaseous or liquid effluents.

Should you have questions regarding the information in this submittal, please contact me at (315) 349-5219.

Very truly yours, John J. Dosa Director Licensing JJD/KES moo!

I(JaJL6

Document Control Desk May 1, 2012 Page 2

Enclosure:

Nine Mile Point Nuclear Station, Unit 2, Radioactive Effluent Release Report, January -

December 2011 cc: Regional Administrator, Region I, NRC Project Manager, NRC Resident Inspector, NRC B. Dionne, NRC

ENCLOSURE NINE MILE POINT NUCLEAR STATION, UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT January - December 2011 Nine Mile Point Nuclear Station, LLC May 1, 2012

p NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT January- December 2011 CENGS.

a joint venture of 0Contlion *-'weDF NINE MILE POINT NUCLEAR STATION

a Page 1 of 2 NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2011 SUPPLEMENTAL INFORMATION Facility: Nine Mile Point Unit 2 Licensee: Nine Mile Point Nuclear Station, LLC

1. TECHNICAL SPECIFICATION/ODCM 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 Iodine-131, Iodine-133, 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 mrem/year to any organ.
2. The dose to a member of the public from Iodine-13 1, Iodine-133, 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) limit 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/ml total activity.
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.

Page 2 of 2

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 an on-line scintillation detector (calibrated against gamma isotopic analysis of a 4.OL Marinelli grab sample) 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.

G) C-14 The production of C-14 and the effluent dose consequences are estimates based on EPRI methodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010 and NUREG-00 16, Calculation of Releases of Radioactive Materials in Gaseous and LiquidEffluents for Boiling Water Reactors (BWR-GALE Code).

ATTACHMENT 1

SUMMARY

DATA Page 1 of 2 Unit I Unit 2 X Reporting Period January - December 2011 Liquid Effluents:

ODCM Required Maximum Effluent Concentration (MEC) = 10 x 10CFR20.1001 - 20.2402, Appendix B, Table 2, Column 2 Average MEC - pCi/mI (Qtr. 1) NO RELEASES Average MEC - pCi/mI (Qtr. 3) = EEASES Average MEC - pCi/ml (Qtr. 2) =NO RELEASES Average MEC - pCi/ml (Qtr. 4) = NOREEASES Average Energy (Fission and Activation gases - MEV):

Qrtr. 1: Ey = 8.97E-01 E13 = 2.98E-01 Qrtr. 2: Ey = 9.51E-01 EP = 3.57E-01 Qrtr. 3: Ey = 5.78E-01 EP3 = 2.38E-01 Qrtr. 4: Ey = 8.68E-01 EP = 3.75E-01 Liquid:

Number of Batch Releases 0 Total Time Period for Batch Releases (hrs) 0.0 Maximum Time Period for a Batch Release (hrs) 0.00 Average Time Period for a Batch Release (hrs) 0.00 Minimum Time Period for a Batch Release 0.00 Total volume of water used to dilute the liquid I 1st 2nd 3rd 4th during the release period (L) N/A N/A N/A N/A ITotal volume of water available to dilute the liquid I 1st 2nd 3rd 4th effluent during the report period (L) 1.11E+10 1.19E+10 1.37E+10 1.32E+10 Gaseous (Emergency Condenser Vent) "Not applicable for Unit 2" Number 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 Minimum Time Period for a Batch Release N/A Gaseous (Primary Containment Purge)

Number of Batch Releases 13 Total Time Period for Batch Releases (hrs) 298.7 Maximum Time Period for a Batch Release (hrs) 103.8 Average Time Period for a Batch Release (hrs) 23.0 Minimum Time Period for a Batch Release (hrs) 0.07

ATTACHMENT

SUMMARY

DATA1 Page 2 of 2 Unit I Unit 2 X Reporting Period January - December 2011 Abnormal Releases:

A. Liquids:

Number of Releases 0 Total Activity Released N/A Ci B. Gaseous:

Number of Releases 0 Total Activity Released N/A ci

ATTACHMENT 2 Page 1 of 1 Unit I Unit 2 X Reporting Period January - December 2011 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL 1st 2nd 3rd 4th Est. Total Quarter Quarter Quarter Quarter Error %

A. Fission & Activation Gases

1. Total Release Ci 8.24E+01 9.84E+01 1.11E+02 4.74E+01 5.OOE+01
2. Average Release Rate pCi/sec 1.06E+01 1.25E+01 1.40E+01 5.96E+00 B. lodines
1. Total Iodine - 131 Ci 5.19E-04 5.87E-04 8.86E-04 6.95E-04 3.OOE+01
2. Average Release Rate for Period pCi/sec 6.62E-05 7.45E-05 1.13E-04 8.83E-05 C. Particulates Ci
1. Particulates with Half-lives>8days 1.18E-04 5.1OE-04 5.68E-04 4.96E-04 3.OOE+01
2. Average Release Rate for Period pCi/sec 1.50E-05 6.47E-05 7.23E-05 6.30E-05
3. Gross Alpha Radioactivity Ci 0.OOE+00 0.OOE+00 7.86E-07 0.00E+00 2.50E+01 D. Tritium
1. Total Release Ci 2.17E+01 1.37E+01 1.49E+01 1.66E+01 5.OOE+01
2. Average Release Rate for Period pCi/sec 2.76E+00 1.74E+00 1.90E+00 2.11E+00 E. Percent of Tech. Spec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose 1.75E-01 2.16E-01 1.54E-01 9.70E-02 Limit (5 mR)

Percent of Quarterly Beta Air Dose Limit 8.70E-03 4.40E-03 6.53E-03 3.27E-03 (10 mrad)

Percent of Annual Gamma Air Dose 8.73E-02 1.95E-01 2.71E-01 3.19E-01 Limit to Date (10 mR)

Percent of Annual Beta Air Dose Limit to 4.35E-03 6.55E-03 9.80E-03 1.15E-02 Date (20 mrad)

Percent of Whole Body Dose Rate Limit 6.85E-03 8.41 E-03 5.90E-03 3.70E-03 (500 mrem/yr)

Percent of Skin Dose Rate Limit (3000 1.36E-03 1.66E-03 1.20E-03 7.45E-04 mrem/yr)

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

Percent of Quarterly Dose Limit (7.5 1.44E-01 1.60E-01 2.30E-01 1.88E-01 mrem)

Percent of Annual Dose Limit to Date 7.24E-02 1.53E-01 2.69E-01 3.64E-01 (15 mrem)

Percent of Organ Dose Limit (1500 2.92E-03 3.21E-03 4.57E-03 3.81 E-03 mrem/yr

ATTACHMENT 3 Page 1 of 1 Unit I Unit 2 X Reporting Period January - December 2011 GASEOUS EFFLUENTS - ELEVATED RELEASE 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 2.05E+01 2.57E+01 1.52E+01 8.86E+00 Krypton-87 Ci 2.16E+00 7.22E+00 ** 4.93E-01 Krypton-88 Ci 3.47E+01 4.24E+01 2.34E+01 9.86E+00 Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci 1.59E+01 2.23E+01 2.61E+01 5.91E+00 Xenon-133m Ci Xenon-135 Ci **_ 2.48E+01 2.51 E+00 Xenon-135m Ci 1.80E+01 4.07E+00 Xenon-137 Ci Xenon-138 Ci ..... 1.46E+01 lodines (1)

Iodine-131 Ci 4.25E-04 4.48E-04 7.27E-04 6.29E-04 Iodine-133 Ci 5.81E-03 6.55E-03 7.17E-03 8.69E-03 Iodine-135 Ci Particulates (1)

Chromium-51 Ci Manganese-54 Ci ** ** 1.69E-06 4.54E-06 Iron-55 Ci 1.22E-05 3.79E-05 ....

Iron-59 Ci Cobalt-58 Ci Cobalt-60 Ci 8.43E-06 2.37E-05 1.33E-05 1.96E-05 Neodymium-147 Ci .... _____ 2.55E-06 **

Zinc-65 Ci Strontium-89 Ci ...... 5.25E-05 Strontium-90 Ci Niobium-95 Ci Zirconium-95 Ci Molybdenum-99 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-144 Ci Tritium (I) Ci I1.11E+01 9.35E+00 1.11E+01 I .33E+01I (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 pCi/ml for required noble gases, 1.OOE-11 pCi/ml for required particulates and gross alpha, 1.OOE-12 pCi/ml for required lodines, 1.00E-11 pCi/ml for Sr-89/90 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 2011 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 Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci 9.01E+00 7.49E-01 3.05E-01 3.63E-01 Xenon-133m Ci Xenon-135 Ci 8.19E-02 1.68E+00 6.95E-01 Xenon-135m Ci ... 1.82E+00 **

Xenon-1i37 Ci Xenon-1 38 Ci lodines (1) **** I ** **

Iodine-131 Ci 9.42E-05 1.39E-04 1.60E-04 6.53E-05 Iodine-133 Ci 1.72E-03 1.87E-03 9.35E-04 8.12E-04 Iodine-135 Ci Particulates (1)

Chromium-51 Ci ....

  • 4.44E-04 **

Manganese-54 Ci ** 3.47E-06 3.87E-06 4.05E-05 Iron-55 Ci 7.10E-05 3.91E-04 4.21E-05 2.66E-04 Iron-59 Ci Cobalt-58 Ci .... 5.83E-06 **

Cobalt-60 Ci 2.66E-05 5.33E-05 4.03E-05 1.01 E-04 Neodymium-147 Ci ** 3.73E-06 **

Zinc-65 Ci .... 1.07E-05 1.23E-05 Strontium-89 Ci Strontium-90 Ci Niobium-95 Ci Zirconium-95 Ci Molybdenum-99 Ci .... 4.74E-06 **

Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-144 Ci Tritium (1) Ci i1.06E+01 4.34E+00 3.78E+00 3.27E+00 (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 jpCi/ml for required noble gases, 1.OOE-1 i pCi/ml for required particulates and gross alpha, 1.00E-1 2 iCi/ml for required iodines, 1.OOE-1 1 pCi/ml for Sr-89/90 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 2011 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (1) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, %

A. Fission & Activation Products 1, Total Release (not including Tritium, gases, alpha)

Ci 5.OOE+01 No Releases No Releases I No Releases No Releases I 2, Average diluted concentration during reporting period pCi/ml No Releases I No Releases No Releases I No Releases B. Tritium 1 Total release Ci No Releases No Releases No Releases No Releases 5.OOE+01 2, Average diluted concentration during the pCi/mI No Releases No Releases No Releases No Releases reporting period C. Dissolved and Entrained Gases

1. Total release Ci No Releases No Releases No Releases No Releases 5.OOE+01
2. Average diluted concentration during the pCi/mI No Releases No Releases No Releases No Releases reporting period D. Gross Alpha Radioactivity
1. Total release 5.OOE+01 Ci I No Releases I No Releases I No Releases I No ReleasesI E. Volumes
1. Prior to Dilution Liters No Releases No Releases No Releases No Releases 5.OOE+01
2. Volume of dilution water used during release period Liters No Releases No Releases No Releases No Releases 5.OOE+01
3. Volume of dilution water available during Liters 1.11E+10 1.19E+10 1.37E+10 1,32E+10 5.OOE+01 reporting period F. Percent of Tech. Spec. Limits Percent of Quarterly Whole Body Dose 0.00E+00 0.00E+00 0.00E+00 0,00E+00 Limit (1.5 mrem)

Percent of Annual Whole Body Dose Limit 0.OOE+00 0.OOE+00 0.OOE+00 0OOE+00 to Date (3 mrem)

Percent of Quarterly Organ Dose Limit (5 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 mrem)

Percent of Annual Organ Dose Limit to Date (10 mrem) 0OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Percent of 10CFR20 Concentration Limit 0.OOE+00 0.OOE+00 0.OOE+00 0OOE+00 (2), (3)

Percent of Dissolved or Entrained Noble 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Gas Limit (2.OOE-04 pCi/ml)

(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 5.OOE-07 pCi/ml for required gamma emitting nuclides, 1.OOE-05 pCi/ml for required dissolved and entrained noble gases and tritium, 5.OOE-08 pCi/ml for Sr-89/90, 1.O0E-06 pCi/mt for 1-131 and Fe-55, and 1.OOE-07 pCi/ml for gross alpha radioactivity, as required by the Off-Site Dose Calculation Manual (ODCM), has been verified.

(2) The percent of 10CFR20 concentration limit is based on the average concentration during the quarter.

(3) Improved Technical Specifications limit 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. Maximum Effluent Concentrations (MEC) numerically equal to ten times the 10CFR20.1001 - 20.2402 concentrations were adopted to evaluate liquid effluents.

ATTACHMENT 5 Page 2 of 2 Unit 1 Unit 2 X Reporting Period January - December 2011 LIQUID EFFLUENTS RELEASED Batch Mode (1),(2)

Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Nuclides Released Strontium-89 Ci No Releases No Releases No Releases No Releases Strontium-90 Ci No Releases No Releases No Releases No Releases Cesium-134 Ci No Releases No Releases No Releases No Releases Cesium-137 Ci No Releases No Releases No Releases No Releases Iodine-131 Ci No Releases No Releases No Releases No Releases Cobalt-58 Ci No Releases No Releases No Releases No Releases Cobalt-60 Ci No Releases No Releases No Releases No Releases Iron-59 Ci No Releases No Releases No Releases No Releases Zinc-65 Ci No Releases No Releases No Releases No Releases Manganese-54 Ci No Releases No Releases No Releases No Releases Chromium-51 Ci No Releases No Releases No Releases No Releases Zirconium-95 Ci No Releases No Releases No Releases No Releases Niobium-95 Ci No Releases No Releases No Releases No Releases Molybdenum-99 Ci No Releases No Releases No Releases No Releases Technetium-99m Ci No Releases No Releases No Releases No Releases Barium-140 Ci No Releases No Releases No Releases No Releases Lanthanum-140 Ci No Releases No Releases No Releases No Releases Cerium-141 Ci No Releases No Releases No Releases No Releases Tungsten-187 Ci No Releases No Releases No Releases No Releases Arsenic-76 Ci No Releases No Releases No Releases No Releases Iodine-1 33 Ci No Releases No Releases No Releases No Releases Iron-55 Ci No Releases No Releases No Releases No Releases Neptunium-239 Ci No Releases No Releases No Releases No Releases Silver- 110m Ci No Releases No Releases No Releases No Releases Gold-199 Ci No Releases No Releases No Releases No Releases Cerium-144 Ci No Releases No Releases No Releases No Releases Cesium-136 Ci No Releases No Releases No Releases No Releases Copper-64 Ci No Releases No Releases No Releases No Releases Dissolved or Entrained Gases Ci I No Releases I No Releases I No Releases I No Releases I Tritium Ci I No Releases I No Releases I No Releases I No Releases I (1) No continuous mode release occurred during the report period as indicated by effluent sampling.

(2) 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 5.OOE-07 pCi/ml for required gamma emitting nuclides, 1.OOE-05 pCi/mI for required dissolved and entrained noble gases and tritium, 5.OOE-08 pCi/mI for Sr-89/90, 1.OOE-06 pCi/mI for 1-131 and Fe-55, and 1.00E-07 pCi/ml for gross alpha radioactivity, as identified in the ODCM, has been verified.

ATTACHMENT 6 Page 1 of 4 Unit I Unit 2 X Reporting Period January - December 2011 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 Resin (Dewatered) 2.21E+01 O.OOE+00 O.OOE+O0 9.92E+01 O.OOE+00 0.OOE+00 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+O0 O.OOE+00 O.OOE+00 O.OOE+00 Totals 2.21 E+01 O.OOE+00 O.OOE+00 9.92E+01 O.OOE+00 O.OOE+00 b.1 Dry Compressible Waste 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 b.2 Dry Non-Compressible OOOE+00 O.OOE+0O 0.OOE+0O O.OOE+OO 0.OOE+OO O.OOE+OO Waste (Contaminated . 0.00E+00 0.00E+00

_.00E+00 0.00E+00 0.00E+0 Totals 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00

c. Irradiated Components, O.OOE+0o O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
d. Other (to vendor for processing) d.1 WCSFilterSepta I 4.96E+00 O.OOE+00 O.OOE+O0 1.36E+00 O.OOE+00 O.OOE*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 2011 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Al. TYPE Container Package Solidification Agent a.1 Spent Resin (Dewatered) Poly Liner General Design None a.2 Filter Sludge b.1 Dry Compressible Waste b.2 Dry Non-Compressible

c. Irradiated Components, Control Rods
d. Other (To vendor for processing) d.1 WCS Filter Septa I Steel Liner General Design None

ATTACHMENT 6 Page 3 of 4 Unit I Unit 2 X Reporting Period January - December 2011 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 45.1 Co-60 41.6 Mn-54 6.5 Zn-65 3.5 Ni-63 2.1 H-3, Cr-51, Fe-59, Co-58, Sr-90, Cs-134, Cs-137, Ce-144, Pu-238, 1.2 Pu-239, Am-241, Cm-242, Cm-243
b. Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment)

Nuclide Percent

c. Irradiated Components, Control Rods: There were no shipments.

Nuclide Percent

d. Other: (To vendor for processing)
1. WCS Filter Septa Nuclide Percent Fe-55 46.9 Co-60 39.8 Zn-65 5.4 Mn-54 3.7 Ni-63 2.6 Cs-137 1.0 H-3, Sr-90, Cs-1 34, Ce-144, Pu-238, Pu-239, Am-241, Cm-242, 0.6 Cm-243

ATTACHMENT 6 Page 4 of 4 Unit 1 Unit 2 X Reporting Period January - December 2011 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A3. SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 1 Hittman Transport Studsvik Processing Faciility, Memphis, TN 6 Hittman Transport Studsvik Processing Facility, Erwin, TN B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination D. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIAL There are 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 I Unit 2 X Reporting Period January - December 2011

SUMMARY

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

The Unit 2 Off-Site Dose Calculation Manual (ODCM) was revised twice during the reporting period.

REVISION 33 Page New/Amended Section Description of Change Reason for Change Deleted Instrument 1. This change eliminates the requirement to estimate Cg offgas sample flow every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, when the I 3.3-13 Table D 3.3.2-1 Offgas Sample Flow indicating device is inoperable. This change Device. eliminates an unnecessary action and is consistent with NUREG-1302.

REVISION 34 Page New/Amended Section Description of Change Reason for Change I 3.3-9 D 3.3.2 Required Action E.1 Editorial change for clarification.

wording was revised.

I 3.3-10 D 3.3.2 Required Action H.1 was This change was made to avoid putting the plant through modified by replacing the an unnecessary transient and so that gaseous action to suspend radioactive releases can be more readily estimated while gaseous effluent releases the radiation monitoring equipment is out of service.

with an action to Suspending releases via the stack or vent, (which for the implement appropriate stack would mean shutting down the plant), would result compensatory actions. in continued releases via other unmonitored pathways that would have been unquantifiable.

II 63 Table D 5.1 Changed the name of Facility changed ownership and was renamed.

Sample Location 33 from Alcan Aluminum to Novelis.

ATTACHMENT 8 Page 1of 1 Unit I Unit 2 X Reporting Period January - December 2011

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP) I There were no changes to the NMP2 Process Control Program (PCP) during the reporting period.

ATTACHMENT 9 Page 1of 1 Unit I Unit 2 X Reporting Period January - December 2011

SUMMARY

OF NON-FUNCTIONAL MONITORS Monitor Dates Monitor was Cause and Corrective Actions Non-Functional 2RMS-CAB170A, June 15, 2011 to The cause of the non-functional event was a system lock up Stack WRGMS July 25, 2011 during performance of the quarterly functional testing surveillance. The non-functional duration was extended by the work stoppage experienced in July 2012. Vendor support was obtained, the cabinet cooler was cleaned to provide adequate cooling to the local system cooler, and the system was restarted with vendor assistance.

2LWS-CAB206, January 1, 2011 to This monitor exceeded 30 days non-functional twice during 2011.

Liquid Waste September 7, 2011 The cause of the non-functionality was an intentional lapse of the Discharge Monitor and required surveillances since no liquid discharges were planned or November 4, 2011 scheduled. On September 7, 2011, all surveillances were to December 31, brought current and the monitor was declared functional in 2010 anticipation of a possible discharge. No discharge was performed. The second non-functionality commenced on November 4, 2011, when the surveillances were allowed to exceed their grace dates. While the monitor is non-functional, the manual discharge isolation valves are locked in the closed position. The current non-functionality is tracked under ESL 2011 0243.

ATTACHMENT 10 Page 1of 5 Unit I Unit 2 X Reporting Period: January - December 2011 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 2011.

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 Nine Mile Point (NMP) site. 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 2011 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 Radwaste/Reactor Building 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 NMP 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 is received through inhalation of gaseous effluents released from the NMP2 Stack and Radwaste/Reactor Building Vent.

" Direct radiation pathway; dose resulting from the operation of Nine Mile Point Unit I (NMP1), NMP2 and the James A. Fitzpatrick Nuclear Power Plant (JAFNPP) Facilities.

Methodologies for Determininp_ Dose for Applicable Pathways External Ground (Shoreline Sediment) Pathway Dose from the external ground (shoreline sediment) is based on the methodology in the NMP2 Offsite Dose Calculation Manual (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.

ATTACHMENT 10 Page 2 of 5 Unit I Unit 2 X Reporting Period: January - December 2011 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY The total dose received by the whole body and skin of the maximum exposed individual during 2011 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 = 1 (used average radionuclide concentration over total time period)
  • Average Cs-137 concentration = 1.35E-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 Annual Dose.

Inhalation Pathway The inhalation dose pathway is evaluated by utilizing the inhalation equation in the NMP2 ODCM, as adapted from Regulatory Guide 1.109. The total whole body dose and organ dose received by the hypothetical maximum exposed fisherman during 2011 calculated using the following input parameters for gaseous effluents released from both the NMP2 Stack and Radwaste/Reactor Building Vent for the time period exposure is received:

NMP2 Stack:

Variable Fisherman' 3 9.6 E-07 X/Q (s/m )

Inhalation dose factor Table E-7, Regulatory Guide 1.109 Annual air intake (m3/year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) 1.43 E+06 C- 14 (pCi/sec)2 7.14E+05 Mn-54 (pCi/sec) 2.64 E-01 Fe-55 (pCi/sec) 1.61 E+00 Co-60 (pCI/sec) 2.41 E+00 Sr-89 (pCI/sec) 2.23 E+00 1-131 (pCi/sec) 7.64 E+01 1-133 (pCi/sec) 9.58 E+02 Nd-147 (pCi/sec) 1.08 E-01

ATTACHMENT 10 Page 3 of 5 Unit I Unit 2 X Reporting Period: January - December 2011 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY NMP2 Radwaste/ReactorBuilding Vent:

Variable Fisherman X/Q (s/m 3) 2.8 E-06 Inhalation dose factor Table E-7, Regulatory Guide 1.109 Annual air intake (m3/year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) 4.83 E+05 Cr-51 (pCi/sec) 1.88 E+01 Mn-54 (pCi/sec) 2.03 E+00 Fe-55 (pCi/sec) 3.46 E+01 Co-58 (pCi/sec) 2.47 E-01 Co-60 (pCi/sec) 8.23E+00 Zn-65 (pCi/sec) 9.75 E-01 Mo-99 (pCi/sec) 2.01E-01 1-131 (pCi/sec) 1.54 E+01 1-133 (pCi/sec) 1.53 E+02 Nd-147 (pCi/sec) 1.58E-01

1. 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 Radwaste/Reactor Building 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.
2. C-14 release rate determined from NUREG-0016, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code),"

and EPRI Technical Report 1021106, "Estimation of Carbon- 14 in Nuclear Power Plant Gaseous Effluents."

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

ATTACHMENT 10 Page 4 of 5 Unit 1 Unit 2 X Reporting Period: January - December 2011 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 ODCM. 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 and December 31, TLD data for the second, third, and fourth quarters of 2011 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) 1.65 E-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 2011 The following is a summary of the dose received by a hypothetical maximum exposed fisherman from liquid and gaseous effluents released from NMP2 during 2011:

TABLE 1 Exposure Pathway Annual Dose Fisherman Exposure Pathway Dose Type (mrem)

External Ground Whole Body 2.12 E-03 Skin of Whole Body 2.48 E-03 Inhalation Whole Body 2.09 E-04 Maximum Organ Bone: 4.44 E-04 Thyroid 3.59 E-04 Direct Radiation Whole Body 0.52

ATTACHMENT 10 Page 5 of 5 Unit 1 Unit 2 X Reporting Period: January - December 2011 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 inside the site boundary is as follows:

TABLE 2 Annual Dose Summary Fisherman Total Annual Dose for 2011 (mrem)

Total Whole Body 5.19 E-01 Skin of Whole Body 2.48 E-03 Maximum Organ Bone: 4.44 E-04 Thyroid 3.59 E-04

ATTACHMENT 11 Page 1of 5 Unit I Unit 2 X Reporting Period: January - December 2011 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 2011 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 Nine Mile Point Unit I (NMP1), NMP2 and the James A. FitzPatrick Nuclear Power Plant (JAFNPP) 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:

S< 25 mRem whole body

  • < 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 NMP1, NMP2 and JAFNPP 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 likely most exposed 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.

  • Vegetation consumption pathway; this dose is received from plant radionuclides that have concentrated in vegetation 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 JAFNPP operating facilities.
  • Direct Radiation pathway; radiation dose resulting from the operation ofNMP1, NMP2 and JAFNPP facilities.

Methodologies for Determining Dose for Applicable Pathways Fish Consumption Dose received as a result of fish consumption is based on the methodology specified in the NMP2 Off-Site Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. The dose for 2011 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 2011; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2011.

ATTACHMENT 11 Page 2 of 5 Unit I Unit 2 X Reporting Period: January - December 2011 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Vegetation Consumption Dose received as a result of vegetation consumption is based on the methodology specified in the NMP2 ODCM as adapted from Regulatory Guide 1.109. The dose for 2011 is calculated from actual analysis results of environnmental vegetation samples taken near the likely most exposed Member of the Public.

No radionuclides were detected in vegetation samples collected and analyzed during 2011; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2011.

For estimating C-14, dose received as a result of vegetation consumption is based on the methodology specified in the NMP2 ODCM as adapted from Regulatory Guide 1.109. The estimated concentration of C-14 in vegetation is based on the estimated concentration of C-14 in the plant gaseous effluents.

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.

No radionuclides were detected in shoreline sediment samples collected and analyzed during 2011; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2011.

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 NMPI ODCM, NMP2 ODCM, and the JAFNPP ODCM. These calculations consider deposition, inhalation and ingestion pathways. The total sum of doses resulting from gaseous effluents from NMPI, NMP2 and JAFNPP during 2011 provides a total dose to the whole body and maximum organ dose for this pathway.

Carbon-14 Dose Pathways Resulting from Gaseous Effluents The Carbon-14 (C-14) effluent source terms are used to estimate radiological doses from C-14 in site gaseous waste effluents. These estimates were generated in order to meet the NRC requirement to incorporate C-14 in nuclear power plant 2011 Annual Radiological Effluent Release Reports (ARERRs). The C-14 production and effluent source term estimates were based on EPRI methodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010. The following methodology was used to estimate C-14 gaseous release activity and dose components for the 2011 ARERR.

EPRI Methodology for Estimating C-14 Production Rates in Boiling Water Reactors (BWRs):

For BWRs, EPRI Report 1021106 summarized the distribution of C-14 in release pathways as follows: gaseous 95% to 99%, liquid <0.5% and solid 1% to 5%. The report also states that -95% of C-14 in BWR gaseous waste effluents exists in the carbon dioxide form, which contributes to population dose via photosynthesis uptake in the food consumption cycle.

ATTACHMENT 11 Page 3 of 5 Unit I Unit 2 X Reporting Period: January - December 2011 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY For NMP1 and NMP2, C-14 gaseous dose calculations in the site ARERR are made using the following assumptions for each unit: (1) continuous release of the estimated C-14 generated during power operation based on the number of Effective Full Power Days (EFPDs) for the period, (2) maximum C-14 activity from literature values cited in EPRI Report 1021106, and (3) typical fraction as carbon dioxide for gaseous releases from literature values also cited in EPRI Report 1021106.

Equation I estimates the maximum annual production of C-14, PRMAx, for each BWR unit.

PR ,X = 5.1 # MWT / 1000 [Eq 1]

Where:

5.1 BWR Normalized Production (Ci/GWt-yr)

MWT = MegaWatts Thermal (MWt) 1000 Conversion Factor (MWt to GWt)

Equation 2 estimates the C-14 activity released, A c-14, into the gaseous pathway during the time period for each BWR unit.

A C-14 PR MAx

  • 0. 99
  • EFPD / 365, Ci (for time period) [Eq 2]

Where:

PR AX- = maximum annual production rate of C-14, 0.99 = fraction C-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also see Table 1),

EFPD = number of effective full power days for the unit during the time period; e.g., yearly (Table 1),

365 conversion factor, 365 days in a typical year

ATTACHMENT 11 Page 4 of 5 Unit I Unit 2 X Reporting Period: January - December 2011 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Equation 3 estimates the C-14 activity released in carbon dioxide form, A c-14. Co2, into the gaseous pathway during the time period for each BWR unit.

A c-14, c02 = PR ,

  • 0.99
  • 0.95
  • EFPD / 365, Ci (for time period) [Eq 3]

Where:

PR MX = maximum annual production rate of C- 14, 0.99 = fraction of C-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also Table 1),

0.95 fraction of C-14 as carbon dioxide in BWR gaseous pathway releases (typical literature value in EPRI Report 1021106, also Table 1),

EFPD = number of effective full power days for the unit during the time period, e.g., yearly (Table 1),

365 = conversion factor, 365 days in a typical average year For each BWR unit, the 2011 estimated C-14 activity releases (total and carbon dioxide chemical form) are summarized in Table 1.

Table 1 2011 BWR Estimated C-14 Gaseous Releases Gaseous C02 Form Max. Annual 2011 Total Release 2011 CO2 Release BWR Release Release EFPD Operation Prod. Rate (Eq 2) (Eq 3)

(Eq 1) (Eq 2) (Eq 3)

Fraction(a) Fraction(b) 358 EFPD NMP1 0.99 0.95 (98.08%) 9.44 Ci/yr 8.01 Ci 7.61 Ci 328 EFPD NMP2 0.99 0.95 (98 (89.86%) 17.68 Ci/yr 16.85 Ci 16.0 Ci JAFNPP 0.99 0.95 358 EFPD 10.82 Ci/yr 10.64 Ci 10.0 Ci (98.08%)

(a) Maximum literature values from EPRI Report 1021106.

(b) Typical value from EPRI Report 1021106.

As long as the core designs and power ratings are not significantly changed, the maximum annual production rates and annual total and carbon dioxide activity releases in Table I should be acceptable for use in estimating C-14 gaseous release activity and dose components for the ARERR.

ATTACHMENT 11 Page 5 of 5 Unit I Unit 2 X Reporting Period: January - December 2011 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Direct Radiation Pathway 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 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 2011, the closest residence and the critical downwind residence are at the same location.

Table 2 Dose Potentially Received by the Likely Most Exposed Member of the Public Outside the Site Boundary Durinn 2011 Exposure Pathway Dose Type Dose (mrem)

Fish Consumption Total Whole Body No Dose Total Maximum Organ No Dose Shoreline Sediment Total Whole Body No Dose Total Skin of Whole Body No Dose Gaseous Effluents Total Whole Body 1.28 E-03 Thyroid 3.55 E-03 Maximum Organ Lung: 1.42 E -03 Gaseous Effluent Total Whole Body 4.05 E-02 (C-14) Maximum Organ Bone: 2.03 E-01 Direct Radiation Total Whole Body 2.9 Based on these values the maximum total annual dose potentially received by the likely most exposed Member of the Public during 2011 is as follows:

" Total Whole Body: 2.9 E+00 mrem

  • Total Thyroid: 3.55 E-03 mrem

" Maximum Organ: Bone: 2.03 E-01 mrem 40 CFR 190 Evaluation The maximum total doses presented in this attachment are the result of operations at the NMP1, NMP2 and JAFNPP facilities. The maximum organ dose (Bone: 0.203 mrem), maximum thyroid dose (0.04 mrem) and the maximum whole body dose (2.9 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.

ATTACHMENT 12 Page.1 of 2 GROUNDWATER MONITORING DATA Reporting Period January - December 2011 CONCENTRATION OF TRITIUM IN GROUNDWATER SAMPLES (pCi/I +/-1 sigma)

Control LocaIon*m Date Tritium [

Indicator Location*

Dt Date Tritium Indicator Loctin*

Location* II Date Tritium

ý indicator Date Tritium GMX-MW1 1/11/2011 <424 MW-1 1/11/2011 <424 MW-7 9/13/2011 <408 1/3/2011 <407 GMX-MW1 5/16/2011 <417 MW-1 9/12/2011 <408 MW-7 11/2/2011 <415 1/10/2011 <407 GMX-MW1 9/13/2011 <408 MW-1 11/1/2011 <415 MW-8 1/12/2011 <424 1/17/2011 <410 GMX-MW1 11/2/2011 <415 MW-4 5/17/2011 <410 MW-8 5/18/2011 <410 3/21/2011 <430 NMP2 GMX-MW2 1/12/2011 <424 MW-5 1/11/2011 <424 MW-8 9/13/2011 <408 4/4/2011 <428 Depression MW-B119 5/17/2011 <410 MW-5 5/17/2011 <410 MW-8 11/2/2011 <415 Conet 8/1/2011 <423 MW-B119 9/14/2011 <408 MW-5 9/12/2011 <408 MW-11 9/13/2011 <408 9/6/2011 <407 MW-B119 11/3/2011 <414 MW-5 11/1/2011 <415 MW-11 11/1/2011 <415 9/26/2011 <420 MW-6 1/11/2011 <424 MW-12 9/12/2011 <408 10/3/2011 <412 MW-6 5/17/2011 <410 MW-12 11/1/2011 <415 1 11/22/2011 <420 MW-6 9/13/2011 <408 MW-13 9/12/2011 <408 MW-6 11/1/2011 <415 MW-13 11/1/2011 <415 MW-7 1/12/2011 <424 MW-7 5/18/2011 <410

  • Corresponds to sample location on Figure 1 t Sample collected from storm drain, discharge point of Depression Cone sumps
  • . . I A Page 2 of 2 FIGURE 1 NMP ON-SITE GROUNDWATER MONITORING WELLS AND UNIT 2 A~ LAKE ONTARIO STORM DRAIN OUTFALL

- Monitoring Well Location 11.25 Z* - Storm Drain Outfall 001 303.75 200 IMW-B1 191 Ground Water Monitoring well Is located south of Lake Road at a distance and direction of FGIIXIVWI 1,355 yrds @ 195 degrees, (SSW). Based on NMP2 Rx Building./

ATTACHMENT 13 Unit 1 Unit 2 X Reporting Period January - December 2011 OFF-SITE DOSE CALCULATION MANIJAL (ODCM*

OFF-SITE D(hSECALCjILATLO_ýLM AWLA Revision 33 and Revision 34

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