Text

Radioactive Effluent Release Report for January 1 Through December 31, 2010
	ML11143A161
Person / Time
Site:	Pilgrim
Issue date:	05/13/2011
From:	Jeffery Lynch; Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	2.11.036
	Download: ML11143A161 (81)
	v • d • e

~En tergy Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 May 13, 2011 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

SUBJECT:

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 Radioactive Effluent Release Report for January 1 through December 31, 2010 LETTER NUMBER:

2.11.036

Dear Sir or Madam:

In accordance with Pilgrim Technical Specifications 5.6.3, Entergy Nuclear Operations, Inc. submits the attached Annual Radiological Effluent Release Report for January 1 through December 31, 2010.

Should you have questions or require additional information, I can be contacted at (508) 830-8403.

This letter contains no commitments.

Sincerely, Joseph R. Lyn Manager, Licensing JRL/wgl

Attachment:

Pilgrim Nuclear Power Station Radioactive Effluent Release Report January 1 through December 31, 2010 cc:

U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspeu.r Mr. Richard Guzman, Project Manager Plant Licensing Branch I-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North O-8C2 11555 Rockville Pike Rockville, MD 20852 k1 (LA

cc: Cont'd Enterqy Letter No. 2.11.036, paqe 2/2 Mr. Robert Maietta DEP-Division of Watershed Management 627 Main Street, 2nd Floor Worcester, MA 06108 Radiation Control Program Commonwealth of Massachusetts Executive Offices of Health & Human Services Dept. of Public Health 90 Washington St, 2 nd Floor Dorchester, MA 02121 American Nuclear Insurers 95 Glastonbury Blvd Glastonbury, CT 06033 Attention: ANI Librarian

Attachment to Entergy Letter No. 2.11.036 Pilgrim Nuclear Power Station Radioactive Effluent Release Report January I through December 31, 2010 (78 pages)

PILGRHM NUCLEAR POWER STATION Facility Operating License DPR-35 Annual Radioactive Effluent Release Report January 1 through December 31, 2010

=`---En tergy

4REntergy PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2010 Prepared by:

Reviewed by:

K.J. Sejkora (,_-,

C.,

Senior Chemistry Spi I

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Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report January-December 2010 TABLE OF CONTENTS SECTION 1.0 2.0 2.1 2.2 2.3 3.0 4.0 4.1 4.2 4.3 5.0 6.0 6.1 6.2 7.0 8.0 9.0 10.0 APPENDIX !

APPENDIX E APPENDIX C APPENDIX "

SECTION TITLE EXECUTIVE

SUMMARY

RADIOACTIVE EFFLUENT DATA Supplemental Effluent Release Data Gaseous Effluent Data Liquid Effluent Data METEOROLOGICAL DATA MAXIMUM INDIVIDUAL DOSES Doses From Noble Gas Releases Doses From Gaseous Effluent Releases Doses From Liquid Effluent Releases OFFSITE AMBIENT RADIATION MEASUREMENTS PERCENT OF ODCM EFFLUENT CONTROL LIMITS Gaseous Effluent Releases Liquid Effluent Releases RADIOACTIVE WASTE DISPOSAL DATA OFFSITE DOSE CALCULATION MANUAL REVISIONS PROCESS CONTROL PROGRAM REVISIONS REFERENCES Meteorological Joint Frequency Distributions Onsite Groundwater Monitoring Program Corrections to Previous Effluent Reports Changes to PNPS Offsite Dose Calculation Manual PAGE 5

8 8

8 9

19 20 S... 20.

22 28 34 37 37 40 43 45 46 47 48 69 75 78 3

J3

)

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Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Jan-Dec 2010 LIST OF TABLES TABLE TABLE TITLE PAGE 2.1 Supplemental Information 10 2.2-A Gaseous Effluents - Summation of All Releases 11 2.2-B Gaseous Effluents - Elevated Releases 12 2.2-C Gaseous Effluents - Ground Level Releases 14 2.3-A Liquid Effluents - Summation of All Releases 16 2.3-B Liquid Effluents 17 4.1 Maximum Doses from Noble Gas Releases During 2010 21

- 4.2-A Maximum Individual Organ Doses from Gaseous Effluents 23-Jan-Mar 2010 4.2-B Maximum Individual Organ Doses from Gaseous Effluents 24 Apr-Jun 2010 4.2-C Maximum Individual Organ Doses from Gaseous Effluents 25 JuI-Sep 2010 4.2-D Maximum Individual Organ Doses from Gaseous Effluents 26 Oct-Dec 2010 4.2-E Maximum Individual Organ Doses from Gaseous Effluents 27 Jan-Dec 2010 4.3-A Maximum Individual Organ Doses from Liquid Effluents 29 Jan-Mar 2010 4.3-B Maximum Individual Organ Doses from Liquid Effluents 30 Apr-Jun 2010 4.3-C Maximum Individual Organ Doses from Liquid Effluents 31 Jul-Sep 2010 4.3-D Maximum Individual Organ Doses from Liquid Effluents 32 Oct-Dec 2010 4.3-E Maximum Individual Organ Doses from Liquid Effluents 33 Jan-Dec 2010 5.0 Average TLD Exposures by Distance Zone During 2010 36 6.1 Percent of ODCM Effluent Control Limits for Gaseous Effluent 38 Releases During 2010 6.2 Percent of ODCM Effluent Control Limits for Liquid Effluent Releases 41 During 2010 7.0 Solid Waste and Irradiated Fuel Shipments 44 A-1 Joint Frequency Distribution of Wind Directions and Speeds for the 48 33-ft Level of the 220-ft Tower A-2 Joint Frequency Distribution of Wind Directions and Speeds for the 58 220-ft Level of the 220-ft Tower Page 4

EXECUTIVE

SUMMARY

PILGRIM NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2010 INTRODUCTION This report quantifies the radioactive gaseous, liquid, and radwaste releases, and summarizes the local meteorological data for the period from January 01 through December 31, 2010.

This document has been prepared in accordance with the requirements set forth in the Pilgrim Nuclear Power Station (PNPS) Technical Specifications and Revision 1 of Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluents from Light Water Cooled Nuclear Power Plants".

The quantity of radioactive material released from PNPS was determined from Isample analyses and continbois On-line monitoring -of gaseous releases from the main' stack; reactor-building Vent, turbine building, and various decontamination facilities, and liquid releases into the discharge canal.

The quantity and volume of radioactive waste shipped offsite from PNPS for processing and burial were determined from data contained on the radwaste shipping documentation. The meteorological data were obtained from monitoring instruments located on the 220-foot meteorological tower located at Pilgrim Station.

GASEOUS EFFLUENTS Gaseous radioactive releases for the reporting period are quantified in Tables 2.2-A, 2.2-B, and 2.2-C. Radioactive noble gases released during the period totaled 27.7 Curies. Releases of radioactive iodines and particulates with half-life of greater than 8 days totaled 0.00963 Curies, tritium releases totaled 43.3 Curies, and carbon-14 totaled 8.54 Curies. No gross alpha radioactivity was detected in gaseous effluents.

Noble gases released in gaseous effluents resulted in a maximum total body dose of 0.0078 mrem, with a corresponding skin dose of 0.025 mrem. The release of radioactive particulates, iodines, tritium, and carbon-14 in gaseous effluents from PNPS during the reporting period resulted in a total body dose to the maximum-exposed hypothetical individual of about 0.031 mrem. The maximum hypothetical dose to any organ from radioactive particulates, iodines, tritium, and carbon-14 was about 0.11 mrem. The maximum, hypothetical total body dose from the combined release of all airborne radioactivity in gaseous effluents was 0.12 mrem.

The maximum individual doses from gaseous radioactive effluents were compared to the applicable ODCM dose limits. Noble gas doses were less than 1.1% of the corresponding 10CFR50 dose objectives. Maximum doses resulting from releases of particulates, iodines, tritium, and carbon-14 in gaseous effluents were less than 0.73% of corresponding 10CFR50 objectives.

Page 5

LIQUID EFFLUENTS.

Liquid radioactive releases for the reporting period are quantified in Tables 2.3-A and 2.3-B.

Six discharges of liquid effluents containing radioactivity occurred during the reporting period.

The resulting maximum total body dose was 0.00197 mrem, with a corresponding organ dose of 0.00997 mrem. All doses from liquid discharges were less than 0.2% of corresponding 10CFR50 objectives.

METEOROLOGICAL DATA Meteorological joint frequency distributions are listed in Appendix A. Data recovery for the entire annual period was 86.3% for the 33-ft and 97.8% for the 220-ft levels of the tower.

The predominant wind direction was from the south-southwest, which occurred approximately 13% of the time during the reporting period.

The predominant stability class was Class D, which occurred about 39% of the time during the reporting period OFFSITE AMBIENT RADIATION MEASUREMENTS Ambient radiation exposure was evaluated to complete the assessment of radiological impact on humans.

A small number of thermoluminescent dosimeters (TLDs) indicated an elevation in ambient radiation exposure on Entergy property in close proximity to the station, when compared to background levels in the region. This elevation is due to nitrogen-16 contained within the plant steam system, as opposed to radioactive effluent released from the plant. The dose to the maximum-exposed member of the public at the PNPS Health Club, even though they are within the owner-controlled area, was estimated as being about 1.8 mrem during 2010.

There was no measurable increase during 2010 in ambient radiation measurements at the location of the nearest resident 0.8 km southeast of PNPS.

COMBINED DOSE IMPACT The collective total body dose to a maximum-exposed hypothetical member of the public from airborne radioactivity, liquid-borne radioactivity, and ambient radiation exposure resulting from PNPS operation during 2010 was calculated as being about 0.83 mrem.

This amount is about 0.2% of the typical dose of 300 to 400 mrem received each year by an average person from other sources of natural and man-made radiation. Although this calculated collective dose occurs to a maximum-exposed hypothetical individual, it is also well below the NRC dose limit of 100 mrem/yr specified in 10CFR20.1301, as well as the EPA dose limit of 25 mrem/yr specified in 40CFR190.

Both of these limits are to be applied to real members of the general public, so the fact that the dose to the hypothetical maximum-exposed individual is within the limits ensures that any dose received by a real member of the public would be smaller and well within any applicable limit.

RADIOACTIVE SOLID WASTE DISPOSAL Solid radioactive wastes shipped offsite for processing and disposal during the reporting period are described in Table 7.0. Approximately 375 cubic meters of solid waste, containing almost 958 Curies of radioactivity, were shipped during the reporting period.

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ONSITE GROUNDWATER MONITORING PROGRAM In response to the Nuclear Energy Institute Groundwater Protection Initiative, Pilgrim Station instituted a groundwater monitoring program during 2007.

Four monitoring wells were installed onsite during the fourth quarter of 2007, and the first samples were collected in late November 2007. This sampling program was continued in 2010, and twelve additional sampling wells were added to the program in 2010.

Low levels of tritium, a radioactive isotope of hydrogen, were detected in these onsite wells.

No other plant-related radioactivity was detected in the samples.

Concentrations of tritium ranged from non-detectable at less than 295 picoCuries per Liter up to 25,552 picoCuries per Liter.

The average concentration of tritium detected in these onsite monitoring wells was well below the voluntary communications reporting level established by the EPA Drinking Water Standard of 20,000 pCi/L. Although the EPA Standard provides a standard for comparison, no drinking water sources are affected by this tritium.

Results of the groundwater monitoring program are presented in Appendix B.

CONCLUSION The PNPS Offsite Dose Calculation Manual contains effluent controls to limit doses resulting from releases of radioactivity to the environment. None of the effluent controls associated with liquid or gaseous effluents were exceeded during the reporting period, as confirmed by conservative dose assessments performed at weekly and monthly intervals. Conformance to the PNPS ODCM effluent control limits ensures that releases of radioactivity in liquid and gaseous effluents are kept as low as reasonably achievable in accordance with 10 CFR Part 50, Appendix I. Compliance with the ODCM also demonstrates that requirements of the Environmental Protection Agency's nuclear fuel cycle standard, 40CFR190.10, Subpart B, have been met. Based on the dose assessment results for 2010, there was no significant radiological impact on the general public from PNPS operation.

Page 7

2.0 RADIOACTIVE EFFLUENT DATA Radioactive -gaseous and liquid releases for the reporting period are given in the standard format presented in Tables 1A, 1B, 1C, 2A, 2B, and Supplemental Information table from NRC Regulatory Guide 1.21 (Reference 1) format.

2.1 Supplemental Effluent Release Data Supplemental information related to radioactive gaseous and liquid releases for the reporting period are given in the standard NRC Regulatory Guide 1.21 format in Table 2.1.

2.2 Gaseous Effluent Data Gaseous radioactivity is released from Pilgrim Station to the atmosphere from the main stack, reactor building vent, turbine building, and various decontamination facilities. Combined-gaseous effluent releases from all 'release points are summarized in Table 2.2-A.

No alpha activity was detected on any of the particulate filters collected during the reporting period. The total gaseous releases for various categories of radionuclides, as well as the corresponding average release rates, can be summarized as follows:

Noble gases:

27.7 Ci, 0.879 gCi/sec lodines and particulates with 0.00963 Ci, 0.000305 iCi/sec half-life greater than 8 days

" Tritium:

43.3 Ci, 1.37 gCi/sec Carbon-14:

8.54 Ci, 0.271 uCi/sec Effluent releases from the main stack are detailed in Table 2.2-B. The main stack is 335 feet tall, and represents an elevated release point with a total height of approximately 400 feet above sea level. The main stack is located about 700 feet west-northwest of the reactor building.

Ground-level effluent releases are detailed in Table 2.2-C. Data in this table include releases from the reactor building vent, turbine building, and assorted equipment decontamination facilities (e.g.,

hot machine shop, carbon dioxide pellet decon trailer, plastic media decon trailer, etc.) used during the period.

Due to the close proximity of the reactor building, all of these release points are considered to be mixed-mode/ground level release points.

Following the revision of Regulatory Guide 1.21 in 2009, the nuclear industry re-assessed their gaseous effluent releases in accordance with the new definition of "principal radionuclide". Under this new definition, any radionuclide that contributed greater than 1% of the effluent dose calculated to demonstrate compliance with 10CFR50 Appendix I, or contributed more than 1% of the total activity for that type of effluent release, would be classified as a principal radionuclide. Although Carbon-14 (C-14) had been exempted from gaseous effluent calculations in the 1970s, industry assessments in 2009 revealed that Carbon-14 would qualify as a principal radionuclide. Based on this 2009 re-assessment, licensees were required to begin reporting C-14 gaseous effluents in the Annual Radioactive Effluent Release Report beginning with calendar-year 2010.

Carbon-14 releases are summarized in Tables 2.2-A through 2.2-C, and the dose consequences from C-14 are incorporated into the dose assessments documented in Section 4.2 of this report.

Page 8

2.3 Liquid Effluent Data Liquid radioactivity is released from PNPS to Cape Cod Bay via the circulating water discharge canal. These effluents enter Cape Cod Bay at the outfall of the canal, which is located about 1100 feet north of the reactor building.

Liquid effluent releases are summarized in Table 2.3-A.

Detailed breakdowns for individual radionuclides are listed in Table 2.3-B. There were six discharges of liquid effluents containing radioactivity during the reporting period. Total releases for the various categories of radionuclides, as well as their corresponding mean concentrations, can be summarized as follows:

" Total Effluent Volume:

Total Dilution Volume:

Fission/Activation products:

Tritium:

342,000 Liters 615 billion Liters 0.0369 Ci, 0.0000000000600 gCi/mL 2.48 Ci, 0.00000000404 pCi/mL Dissolved/entrained noble gases:

0 Ci, 0 gCi/mL Page 9

Table 2.1 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Supplemental Information January-December 2010 FACILITY: PILGRIM NUCLEAR POWER STATION LICENSE: DPR-35

1. REGULATORY LIMITS

a. Fission and activation gases:

500 mrem/yr total body and 3000 mrem/yr for skin at site boundary b,c. lodines, particulates with half-life:

1500 mrem/yr to any organ at site boundary

>8 days, tritium

d. Liquid effluents:

0.06 mrem/month for whole body and 0.2 mrem/month for any organ (without radwaste treatment)

2. EFFLUENT CONCENTRATION LIMITS.

a. Fission and activation gases:

10CFR20 Appendix B Table II

b. lodines:

10CFR20 Appendix B Table II

c. Particulates with half-life > 8 days:

10CFR20 Appendix B Table II

d. Liquid effluents:

2E-04 ltCi/mL for entrained noble gases; 10CFR20 Appendix B Table II values for all other radionuclides

3. AVERAGE ENERGY Not Applicable

4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY

a. Fission and activation gases:

High purity germanium gamma spectroscopy for all

b. lodines:

gamma emitters; radiochemistry analysis for H-3,

c. Particulates:

Fe-55 (liquid effluents), Sr-89, and Sr-90

d. Liquid effluents:

5. BATCH RELEASES Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec 2010 2010 2010 2010 2010

a. Liquid Effluents

1. Total number of releases:

0 5

0 1

6

2. Total time period (minutes):

0.OOE+00 3.76E+02 0.OOE+00 1.90E+02 5.66E+02

3. Maximum time period (minutes):

0.OOE+00 8.60E+01 0.OOE+00 1.90E+02 1.90E+02

4. Average time period (minutes):

0.OOE+00 7.52E+01 0.OOE+00 1.90E+02 9.43E+01

5. Minimum time period (minutes):

0.OOE+00 6.50E+01 0.OOE+00 1.90E+02 6.50E+01

6. Average stream flow during periods of release of efflueint perintos a lowinestN/A 1.15E+06 N/A 1.18E+06 1.16E+06 effluents into a flowing stream (Liters/min):

b. Gaseous Effluents None None None None None

6. ABNORMAL RELEASES

a. Liquid Effluents None None None None None

b. Gaseous Effluents None None None None None Page 10

Table 2.2-A Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Summation of All Releases January-December 2010 Est.

RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Total 2010 2010 2010 2010 2010 Error A. FISSION AND ACTIVATION GASES Total Release: Ci 4.24E+00 6.81 E+00 1.42E+01 2.43E+00 2.77E+01 Average Release Rate: 4Ci/sec 5.38E-01 8.64E-01 1.81 E+00 3.08E-01 8.79E-01

+/-22%

Percent of Effluent Control Limit*.

B. IODINE-131 Total Iodine-1 31 Release: Ci 3.87E-04. -

5.20E-04 5.63E-04 4.71 E-04 1.94E-03 Average Release Rate: 4Ci/sec.

4.9_1E-05

- 6:59E-05 7.14E-05 5.97E-05 6.15E-05

+/-20%.

Percent of Effluent Control Limit*

C. PARTICULATES WITH HALF-LIVES > 8 DAYS Total Release: Ci 8.03E-04 8.65E-04 9.65E-04 8.24E-04 3.46E-03 Average Release Rate: jCi/sec 1.02E-04 1.10E-04 1.22E-04 1.05E-04 1.10E-04 Percent of Effluent Control Lim it*.....

Gross Alpha Radioactivity: Ci NDA NDA NDA NDA NDA D. TRITIUM Total Release: Ci 6.56E+00 6.61 E+00 1.03E+01 1.99E+01 4.33E+01 Average Release Rate:

0Ci/sec 8.32E-01 8.39E-01 1.31 E+00 2.52E+00 1.37E+00

+/-20%

Percent of Effluent Control Limit*.

E. CARBON-14 Total Release: Ci 2.12E+00 2.13E+00 2.15E+00 2.14E+00 8.54E+00 Average Release Rate: jiCi/sec 2.68E-01 2.70E-01 2.73E-01 2.72E-01 2.71 E-01 N/A Percent of Effluent Control Limit*.

Notes for Table 2.2-A:

Percent of Effluent Control Limit values based on dose assessments are provided in Section 7 of this report.

1. NDA stands for No Detectable Activity.

2. LLD for airborne gross alpha activity listed as NDA is 1 E-1 1 pCi/cc.

3. N/A stands for not applicable.

Page 11

Table 2.2-B Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Elevated Release January-December 2010 CONTINUOUS MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released Jan-Mar2010 Apr-Jun2010 Jul-Sep2010 Oct-Dec2010 Jan-Dec2010

1. FISSION AND ACTIVATION GASES: Ci Ar-41 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 Kr-85 O.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Kr-85m 0.00E+00 0.00E+00 9.33E-02 0.00E+00 9.33E-02 Kr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Kr-88 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Xe-131 m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-133 0.OOE+00 0.OOE+00 7.75E-01 1.39E-01 9.14E-01 Xe-133m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

- Xe,135 2.62E-02 0.OOE+00 0.OOE+00 0.OOE+00 2.62E-02 Xe-135m 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Xe-137 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-138 0.OOE+00 0.OOE+00 4.03E-01 0.OOE+00 4.03E-01 Total for Period 2.62E-02 0.OOE+00 1.27E+00 1.39E-01 1.44E+00

2. IODINES: Ci 1-131 1.73E-05 2.52E-05 4.15E-05 2.60E-05 1.10E-04 1-133 1.69E-05 3.93E-05 8.26E-05 3.94E-05 1.78E-04 Total for Period 3.43E-05 6.44E-05 1.24E-04 6.54E-05 2.88E-04

3. PARTICULATES WITH HALF-LIVES > 8 DAYS: Ci Cr-51 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Mn-54 0.OOE+00 0.OOE+00 4.19E-07 0.OOE+00 4.19E-07 Fe-59 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zn-65 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Sr-89 2.71 E-06 9.66E-08 1.31 E-06 2.11 E-06 6.23E-06 Sr-90 0.OOE+00 3.42E-06 0.OOE+00 0.OOE+00 3.42E-06 Ru-1 03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-1 34 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-1 37 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba/La-140 Total for Period 2.71 E-06 3.52E-06 1.73E-06 2.11 E-06 1.01 E-05

4. TRITIUM: Ci H-3 2.63E-02 3.02E-02 7.21 E-02 2.91 E-02 1.58E-01

5. CARBON-14: Ci C-14 2.05E+00 2.07E+00 2.09E+00 2.08E+00 8.28E+00 Notes for Table 2.2-B:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

3. LLDs for airborne radionuclides listed as NDA are as follows:

Fission Gases:

1 E-04.tCi/cc lodines:

1 E-12 pCi/cc Particulates:

1 E-11 gCi/cc Page 12

Table 2.2-B (continued)

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Elevated Release January-December 2010 BATCH MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released I Jan-Mar2010 Apr-Jun2010 Jul-Sep2010 Oct-Dec2010 Jan-Dec2010

1. FISSION AND ACTIVATION GASES: Ci Ar-41 N/A N/A N/A N/A N/A Kr-85 N/A N/A N/A N/A N/A Kr-85m N/A N/A N/A N/A N/A Kr-87 N/A N/A N/A N/A N/A Kr-88 N/A N/A N/A N/A N/A Xe-131m N/A N/A N/A N/A N/A Xe-133 N/A N/A N/A N/A N/A Xe-133m N/A.

N/A N/A N/A N/A Xe-135 N/A N/A N/A

.N/A

_-N/A Xe-135m N/A N/A N/A N/A N/A Xe-1 37 N/A N/A N/A N/A N/A Xe-i 38 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A

2. IODINES: Ci 1-131 N/A N/A N/A N/A N/A 1-133 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A

3. PARTICULATES WITH HALF-LIVES > 8 DAYS: Ci Cr-51 N/A N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A N/A Co-58 N/A N/A N/A N/A N/A Co-60 N/A N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A N/A Ru-103 N/A N/A N/A N/A N/A Cs-i 34 N/A N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A N/A BaILa-140 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A

4. TRITIUM: Ci H-3 N/A N/A N/A N/A N/A

5. CARBON-14: Ci C-14 N/A N/A N/A N/A N/A Notes for Table 2.2-B:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

3. LLDs for airborne radionuclides listed as NDA are as follows:

Fission Gases:

1 E-04 pCi/cc lodines:

1 E-12 p.Ci/cc Particulates:

1 E-1 1 pCi/cc Page 13

Table 2.2-C Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Ground-Level Release January-December 2010 CONTINUOUS MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released I Jan-Mar2010 Apr-Jun2010 Jul-Sep2010 Oct-Dec2010 Jan-Dec2010

1. FISSION AND ACTIVATION GASES: Ci Ar-41 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kr-85 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kr-85m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kr-87 0.OOE+00 0.OOE+00 7.87E-01 0.OOE+00 7.87E-01 Kr-88 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-1 31m 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Xe-1 33 0.OOE+00 0.OOE+00 1.91 E+00 0.OOE+00 1.91 E+00 Xe-1 33m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-135 0.OOE+00-0.OOE+00 9.20E-01 9;83E-01 1.90E+00 Xe-1 35m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-1 37 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-138 4.21 E+00 6.81 E+00 9.35E+00 1.31 E+00 2.17E+01 Total for period 4.21 E+00 6.81 E+00 1.30E+01 2.29E+00 2.63E+01

2. IODINES: Ci 1-131 3.69E-04 4.94E-04 5.21E-04 4.45E-04 1.83E-03 1-133 8.62E-04 7.85E-04 1.23E-03 1.18E-03 4.05E-03 Total for period 1.23E-03 1.28E-03 1.75E-03 1.62E-03 5.88E-03

3. PARTICULATES WITH HALF-LIVES > 8 DAYS: Ci Cr-51 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Mn-54 4.31 E-06 0.OOE+00 0.OOE+00 5.36E-07 4.85E-06 Fe-59 0.OOE+00 0:00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zn-65 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Sr-89 9.08E-05 6.45E-06 9.36E-05 8.41 E-05 2.75E-04 Sr-90 0.OOE+00 2.75E-05 5.OOE-07 2.36E-06 3.04E-05 Ru-103 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-1 34 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-1 37 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba/La-140 7.05E-04 8.27E-04 8.70E-04 7.35E-04 3.14E-03 Total for period 8.OOE-04 8.61 E-04 9.64E-04 8.22E-04 3.45E-03

4. TRITIUM: Ci H-3 T

6.53E+00 6.58E+00 1.02E+01 1.98E+01I 4.32E+01

5. CARBON-14: Ci C-14 6.35E-02 6.39E-02 6.45E-02 6.43E-02 2.56E-01 Notes for Table 2.2-C:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

3. LLDs for airborne radionuclides listed as NDA are as follows:

Fission Gases:

1 E-04 pCi/cc lodines:

1 E-12 pCi/cc Particulates:

1 E-1 1 pCi/cc Page 14

Table 2.2-C (continued)

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Ground-Level Release January-December 2010 BATCH MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released IJan-Mar2010 Apr-Jun2010 Jul-Sep2010 Oct-Dec2010 Jan-Dec2010

1. FISSION AND ACTIVATION GASES: Ci Ar-41 N/A N/A N/A N/A N/A Kr-85 N/A N/A N/A N/A N/A Kr-85m N/A N/A N/A N/A N/A Kr-87 N/A N/A N/A N/A N/A Kr-88 N/A N/A N/A N/A N/A Xe-131m N/A N/A N/A N/A N/A Xe-i 33 N/A N/A N/A N/A N/A Xe-i 33m N/A N/A N/A N/A N/A Xe-1 35 N/A N/A N/A

ý,N/A N/A Xe-135m N/A N/A N/A N/A N/A Xe-i 37 N/A N/A N/A N/A N/A Xe-i 38 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A

2. IODINES: Ci 1-131 N/A N/A N/A N/A N/A 1-133 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A

3. PARTICULATES WITH HALF-LIVES > 8 DAYS: Ci Cr-51 N/A N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A N/A Co-58 N/A N/A N/A N/A N/A Co-60 N/A N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A N/A Ru-1 03 N/A N/A N/A N/A N/A Cs-i 34 N/A N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A N/A Ba/La-140 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A

4. TRITIUM: Ci H-3 N/A N/A N/A N/A N/A

5. CARBON-14: Ci C-14 N/A N/A N/A N/A N/A Notes for Table 2.2-C:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

3. LLDs for airborne radionuclides listed as NDA are as follows:

Fission Gases:

1 E-04 4Ci/cc lodines:

1E-12 4Ci/cc Particulates:

1 E-11 pCi/cc Page 15

Table 2.3-A Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents - Summation of All Releases January-December 2010 Est.

RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Total 2010 2010 2010 2010 2010 Error A. FISSION AND ACTIVATION PRODUCTS Total Release (not including N/A 3.69E-02 N/A 1.70E-05 3.69E-02 tritium, gases, alpha): Ci Average Diluted Concentration N/A 2.41 E-10 N/A 1.09E-13 6.OOE-11

+/-12%

During Period: jlCi/mL_

Percent of Effluent Concentration N/A 2.69E-03%

N/A 9.26E-06%

6.72E-04%

Limit*

B. TRITIUM Total Release: Ci N/A 2.46E+00 N/A 1.83E-02 2.48E+00 Average Diluted Concentration N/A 1.61 E-08 N/A 1.18E-10 4.40E-09 During Period: igCi/mL

-9.4%

Percent of Effluent Concentration N/A 1.61 E-03%

N/A 1.18E-05%

4.04E-04%

Limit*

I C. DISSOLVED AND ENTRAINED GASES Total Release: Ci N/A NDA N/A NDA NDA Average Diluted Concentration N/A NDA N/A NDA NDA During Period: itCi/mL

+/-16%

Percent of Effluent ConcentrationE+00 OE+00 Liit/A_____

0.00E+00 N/A 0.00E+00 0.00E0 Lim it*IIIIII D. GROSS ALPHA RADIOACTIVITY Total Release: Ci N/A NDA N/A NDA NDA

+/-34%

E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION Waste Volume: Liters N/A 3.11E+05 N/A 3.04E+04 3.42E+05

+/-5.7%

F. VOLUME OF DILUTION WATER USED DURING PERIOD Dilution Volume: Liters 1.52E+11 1.53E+11 1.55E+11 1.55E+11 6.15E+11

+/-10%

Notes for Table 2.3-A:

Additional percent of Effluent Control Limit values based on dose assessments are provided in Section 7 of this report.

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

3. LLD for dissolved and entrained gases listed as NDA is 1 E-05 ýtCi/mL.

4. LLD for liquid gross alpha activity listed as NDA is 1 E-07 !tCi/mL.

Page 16

Table 2.3-B Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2010 CONTINUOUS MODE RELEASES Nuclide Released Jan-Mar 2010 Apr-Jun 2010 Jul-Sep 2010 Oct-Dec 2010 Jan-Dec 2010

1. FISSION AND ACTIVATION PRODUCTS: Ci Cr-51 N/A N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A N/A Fe-55 N/A N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A N/A Co-58 N/A N/A N/A N/A N/A Co-60 N/A N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A N/A Zn-69m N/A N/A N/A N/A_

N/A Sr-89.

N/A N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A N/A Zr/Nb-95 N/A N/A N/A N/A N/A Mo/Tc-99 N/A N/A N/A N/A N/A Ag-110m N/A N/A N/A N/A N/A Sb-124 N/A N/A N/A N/A N/A 1-131 N/A N/A N/A N/A N/A 1-133 N/A N/A N/A N/A N/A Cs-134 N/A N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A N/A Ba/La-140 N/A N/A N/A N/A N/A Ce-141 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A

2. DISSOLVED AND ENTRAINED GASES: Ci Xe-133 N/A N/A N/A N/A N/A Xe-135 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A Notes for Table 2.3-B:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

3. LLDs for liquid radionuclides listed as NDA are as follows:

Strontium:

5E-08 itCi/mL lodines:

1 E-06 pCi/mL Noble Gases:

1 E-05 gCi/mL All Others:

5E-07 0Ci/mL Page 17

Table 2.3-B3 (continued)

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2010 BATCH MODE RELEASES Nuclide Released Jan-Mar 2010 Apr-Jun 2010 Jul-Sep 2010 Oct-Dec 2010 Jan-Dec 2010

1. FISSION AND ACTIVATION PRODUCTS: Ci Cr-51 N/A 4.01 E-04 N/A NDA 4.01 E-04 Mn-54 N/A 1.80E-02 N/A 1.78E-06 1.80E-02 Fe-55 N/A 5.93E-03 N/A NDA 5.93E-03 Fe-59 N/A 1.43E-04 N/A NDA 1.43E-04 Co-58 N/A 2.37E-04 N/A NDA 2.37E-04 Co-60 N/A 8.06E-03 N/A 1.71 E-06 8.06E-03 Zn-65 N/A 1.08E-03 N/A NDA 1.08E-03 Zn-69m N/A NDA N/A NDA NDA;.,.-.,.:

Sr-89 N/A 1.43E-05 N/A NDA 1.43E-05 Sr-90 N/A NDA N/A 7.65E-07 7.65E-07 Zr/Nb-95 N/A NDA N/A NDA NDA Mo/Tc-99 N/A NDA N/A NDA NDA Ag-110m N/A 2.51 E-03 N/A NDA 2.51 E-03 Sb-124 N/A NDA N/A NDA NDA 1-131 N/A NDA N/A NDA NDA 1-133 N/A NDA N/A 6.04E-07 6.04E-07 Cs-134 N/A NDA N/A NDA NDA Cs-137 N/A 5.86E-05 N/A 1.21 E-05 7.07E-05 Ba/La-140 N/A 4.18E-04 N/A NDA 4.18E-04 Ce-141 N/A 4.54E-05 N/A NDA 4.54E-05 Ce-144 N/A NDA N/A NDA NDA Total for period N/A 3.69E-02 N/A 1.70E-05 3.69E-02

2. DISSOLVED AND ENTRAINED GASES: Ci Xe-133 N/A NDA N/A NDA NDA Xe-135 N/A NDA N/A NDA NDA Total for period N/A NDA N/A NDA NDA Notes for Table 2.3-B:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

3. LLDs for liquid radionuclides listed as NDA are as follows:

Strontium:

5E-08 1tCi/mL lodines:

1 E-06 gCi/mL Noble Gases:

1 E-05 VCi/mL All Others:

5E-07 gCi/mL Page 18

3.0 METEOROLOGICAL DATA Meteorological data are summarized for the reporting period in Appendix A, in the standard joint frequency distribution format as given in NRC Regulatory Guide 1.21.

The predominant meteorological conditions observed during the annual reporting period can be summarized with their corresponding frequencies as follows:

" Stability Class:

Class D, 39%

33-ft Wind Direction (from):

South-southwest, 15%

33-ft Wind Speed:

3.5-7.5 mph, 56%

220-ft Wind Direction (from): West-northwest, 13%

220-ft Wind Speed:

12.5-18.5 mph, 35%

A problem was encountered during the first quarter of 2010 due to the failure of the datalogging channels for the lower level sensor that existed for several weeks until replacement electronics were procured. This resulted in a joint data recovery of 86.3%for the 33-ft level, which failed to meet the annual recovery goal of greater than 90%. However, data recovery for the upper level of the 220-ft tower was 97.8%, well in excess of the 90% annual data recovery goal specified by the NRC.

Page 19

4.0 MAXIMUM INDIVIDUAL DOSES Doses to the maximum exposed individual resulting from radionuclides in effluents released offsite were calculated using methods presented in the PNPS Offsite Dose Calculation Manual (ODCM, Reference 2), NRC Regulatory Guide 1.109 (Reference 3), NRC Regulatory Guide 1.111 (Reference 4), and the Pilgrim Station Unit 1 Appendix I Evaluation (Reference 5).

Maximum individual doses are calculated separately for: (1) noble gases in gaseous effluents, (2) particulates, iodines, and tritium in gaseous effluents; and, (3) liquid effluents. Maximum consumption and use factors for various pathways from Table E-5 of the PNPS ODCM are used for calculating the doses to the maximum exposed individual.

Information related to liquid and gaseous effluent releases are summarized Section 2 of this report.

These effluent release data were used as input to computer programs to calculate the resulting doses. PNPS ODCM methodologies were used to calculate the dose contributions to the various organs in each age class from major exposure pathways.

4.1 Doses From Noble Gas Releases Gaseous effluent release data presented in Tables 2.2-A, 2.2-B, and 2.2-C from this effluent release report were used as input to a dose assessment computer program to calculate radiation doses.

These data include gaseous releases from the PNPS main stack, reactor building vent, and turbine building roof exhausters.

Meteorological data obtained from the PNPS 220-foot meteorological tower during the 10-year period from 1994 through 2003 were used as input to the "AEOLUS-3" computer program (Reference 6).

This program was used to calculate the annual average atmospheric dispersion and deposition factors used in the dose assessment computer program to calculate maximum individual doses.

The maximum individual doses resulting from radioactive noble gases released in gaseous effluents are presented in Table 4.1 according to specific receptor locations. This table includes all noble gas doses for the individual calendar quarters and total calendar year.

Noble gases released in gaseous effluents from PNPS during 2010 resulted in a maximum total body dose of 0.0078 mrem.

The maximum skin dose was 0.025 mrem.

Both of these doses occurred to a hypothetical individual, assumed to be present 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per day, 365 days per year, at the site boundary location yielding the highest dose (0.64 km ESE of the Reactor Building). For the more "realistic" individuals at offsite locations, the maximum total body dose was 0.0060 mrem (nearest residence, 0.80 kilometers ESE from the Reactor Building), while the maximum skin dose was 0.018 mrem (nearest residence, 0.80 kilometers ESE from the Reactor Building).

Page 20

Table 4.1 Maximum Doses From Noble Gas Releases During 2 0 1 0 (a)

Gamma Beta Total Release Air Dose Air Dose Body Dose Skin Dose Period mrad/period mrad/period mrem/period mrem/period (location)

(location)

(location) 2.15E-03 3.21 E-03 1.45E-03 4.47E-03 (0.64 km ESE)

(0.64 km ESE)

(0.64 km ESE) 3.48E-03 5.19E-03 2.34E-03 7.22E-03 Apr-Jun (0.64 km ESE)

(0.64 km ESE)

(0.64 km ESE) 5.20E-03 9.11E-03 3.48E-03 1.18E-02 Jul-Sep (0.64 km ESE)

(0.64 km ESE)

(0.64 km ESE) 7.72E-04 1.38E-03 5.17E-04 1.76E-03 (0.64 km ESE)

(0.64 km ESE)

(0.64 km ESE) 1.16E-02 1.89E-02 7.78E-03 2.53E-02 (0.64 km ESE)

(0.64 km ESE)

(a) All directions and distances are with respect to the reactor building vent.

Page 21

4.2 Doses From Gaseous Effluent Releases Gaseous effluent release data presented in Tables 2.2-A, 2.2-B, and 2.2-C from this effluent release report were used as input to a dose assessment computer program to calculate radiation doses.

These data include gaseous releases from the PNPS main stack, reactor building vent, and turbine building roof exhausters.

Meteorological data obtained from the PNPS 220-foot meteorological tower during the 10-year period from 1994 through 2003 were used as input to the "AEOLUS-3" computer program (Reference 6).

This program was used to calculate the annual average atmospheric dispersion and deposition factors used in the dose assessment computer program to calculate maximum individual doses.

The maximum individual doses resulting from radioactive particulates, radioiodines, tritium and carbon-14 released in gaseous effluents are presented in Tables 4.2-A through 4.2-E. These tables cover the individual calendar quarters and the total calendar year, respectively. Doses resulting from releases of noble gases are addressed independently in the PNPS ODCM. Therefore, none of these tables for maximum individual doses include any dose contribution from noble gases. The presentation and-analysis of doses resulting from noble gases are addressed in-Section 4.1 of this report.

Tables 4.2-A through 4.2-E summarize the maximum total body and organ doses for the adult, teen, child, and infant age classes resulting from the major gaseous exposure pathways. These tables present the dose data according to specific receptor location and the exposure pathways assumed to occur at that location. For example, the second column of the tables presents the information for the hypothetical maximum-exposed at the most restrictive site boundary location, where only inhalation and ground deposition exposure pathways are assumed to occur.

Since this is a shoreline location controlled by Entergy, the other pathways of garden vegetable production, milk production, and meat production are assumed not to occur. Doses for other offsite locations not under Entergy control, where other exposure pathways can and do occur, are presented in subsequent columns of the tables, and represent the potential maximum doses to individuals at these locations.

Radioactivity (particulates, radioiodines, tritium, and carbon-14) released in gaseous effluents from PNPS during 2010 resulted in a maximum total body dose (child age class) of 0.0313 mrem (child age class at nearest garden location, 0.87 kilometers SE from the Reactor Building), while the maximum organ dose was 0.109 mrem (child bone at nearest garden location, 0.87 kilometers SE from the Reactor Building). Carbon-14 contributed 0.0178 mrem (57%) of the 0.0313 mrem child total body dose, and 0.0892 mrem (82%) of the 0.109 mrem child bone dose at the location of the nearest garden.

Page 22

Table 4.2-A Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Jan-Mar 2010 Receptor:

Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:

NNW ESE SE WSW W

S Distance':

0.28 km 0.80 km 0.87 km 3.97 km 5.77 km 3.80 km Pathway2:

DI DI DIV 3 DIVCG 3 DIVCM3 DIVM 3 Age Class: Adult Bone 1.99E-04 1.48E-04 5.98E-03 2.33E-03 2.04E-03 3.53E-03 GI-LLI 8.06E-04 5.46E-04 2.53E-03 5.77E-04 4.73E-04 7.87E-04 Kidney 7.72E-04 5.24E-04 2.45E-03 5.74E-04 4.72E-04 7.82E-04 Liver 7.69E-04 5.22E-04 2.44E-03 5.73E-04 4.71 E-04 7.82E-04 Lung 8.56E-04 I 5.80E-04..

2.48E-03 5.73E-04 4.71 E-04 7.83E-04 Thyroid 1;67E-03

-1,2E703

.,4.87E-03

-t1,31 E-03 8.66E-04 9.44E-04.,

T.Body 7.67E-04 5.21 E-04 2.44E-03 5.72E-04 4.71 E-04 7.82E-04 Age Class: Teen Bone 2.85E-04 2.12E-04 9.63E-03 3.92E-03 3.07E-03 4.99E-03 GI-LLI 8.30E-04 5.64E-04 3.37E-03 9.08E-04 6.86E-04 1.08E-03 Kidney 7.96E-04 5.41 E-04 3.29E-03 9.08E-04 6.86E-04 1.08E-03 Liver 7.92E-04 5.39E-04 3.28E-03 9.06E-04 6.84E-04 1.08E-03 Lung 9.35E-04 6.33E-04 3.35E-03 9.06E-04 6.85E-04 1.08E-03 Thyroid 1.93E-03 1.30E-03 5.49E-03 1.99E-03 1.26E-03 1.22E-03 T.Body 7.90E-04 5.37E-04 3.29E-03 9.05E-04 6.84E-04 1.08E-03 Age Class: Child Bone 3.93E-04 2.93E-04 2.30E-02 9.45E-03 7.22E-03 1.15E-02 GI-LLI 7.40E-04 5.05E-04 6.45E-03 2.06E-03 1.54E-03 2.41 E-03 Kidney 7.29E-04 4.97E-04 6.40E-03 2.06E-03 1.54E-03 2.41 E-03 Liver 7.26E-04 4.95E-04 6.40E-03 2.06E-03 1.54E-03 2.41 E-03 Lung 8.48E-04 5.76E-04 6.45E-03 2.06E-03 1.54E-03 2.41E-03 Thyroid 2.07E-03 1.39E-03 9.57E-03 4.14E-03 2.63E-03 2.61 E-03 T.Body 7.24E-04 4.94E-04 6.42E-03 2.06E-03 1.54E-03 2.41 E-03 Age Class: Infant Bone 2.89E-04 2.16E-04 1.80E-04 5.92E-03 4.11E-03 7.87E-05 GI-LLI 4.37E-04 2.99E-04 2.25E-04 1.35E-03 9.17E-04 2.62E-05 Kidney 4.35E-04 2.98E-04 2.24E-04 1.36E-03 9.25E-04 2.61 E-05 Liver 4.34E-04 2.97E-04 2.24E-04 1.36E-03 9.24E-04 2.61 E-05 Lung 5.47E-04 3.72E-04 2.79E-04 1.35E-03 9.18E-04 2.88E-05 Thyroid 1.67E-03 1.11E-03 8.26E-04 6.04E-03 3.35E-03 5.61E-05 T.Body 4.32E-04 2.95E-04 2.23E-04 1.35E-03 9.20E-04 2.60E-05 1

2 Distances are measured with respect to the reactor building vent.

Pathway designations are as follows:

D = Deposition (Ground Plane)

I = Inhalation V = Vegetable Garden C = Cow Milk G = Goat Milk M = Meat Doses are conservative since it is unlikely for vegetables to be grown outside or for animals to be fed on pasture during winter months.

Page 23

Table 4.2-B Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Apr-Jun 2010 Receptor:

Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:

NNW ESE SE WSW W

S Distance':

0.28 km 0.80 km 0.87 km 3.97 km 5.77 km 3.80 km Pathway2:

DI DI DIV DIVCG DIVCM DIVM Age Class: Adult Bone 3.12E-04 2.23E-04 1.17E-02 2.67E-03 2.23E-03 3.92E-03 GI-LLI 8.16E-04 5.53E-04 2.66E-03 5.88E-04 4.81E-04 8.00E-04 Kidney 7.78E-04 5.28E-04 2.47E-03 5.80E-04 4.76E-04 7.88E-04 Liver 7.75E-04 5.26E-04 2.46E-03 5.78E-04 4.75E-04 7.88E-04 Lung 8.95E-04 6.05E-04 2.51 E-03 5.78E-04 4.75E-04 7.90E-04 Thyroid 1-.87E-03 1.25E-03 I 5.63E-03 1,.55E-03,....- 1.00E-03..

1.00E-03

-: T.Body 7.75E-04 5.26E-04 2.58E-03 5.83E-04 4.78E-04 7.95E-04 Age Class: Teen Bone 4.14E-04 2.99E-04 1.72E-02 4.38E-03 3.33E-03 5.49E-03 GI-LLI 8.41E-04 5.71E-04 3.53E-03 9.24E-04 6.96E-04 1.1OE-03 Kidney 8.03E-04 5.46E-04 3.32E-03 9.17E-04 6.92E-04 1.08E-03 Liver 7.99E-04 5.43E-04 3.31E-03 9.14E-04 6.90E-04 1.08E-03 Lung 9.95E-04 6.73E-04 3.40E-03 9.14E-04 6.91E-04 1.09E-03 Thyroid 2.17E-03 1.45E-03 6.17E-03 2.35E-03 1.45E-03 1.27E-03 T.Body 7.99E-04 5.43E-04 3.46E-03 9.20E-04 6.94E-04 1.09E-03 Age Class: Child Bone 5.43E-04 3.93E-04 3.82E-02 1.04E-02 7.75E-03 1.25E-02 GI-LLI 7.48E-04 5.1OE-04 6.61E-03 2.08E-03 1.56E-03 2.43E-03 Kidney 7.36E-04 5.02E-04 6.46E-03 2.08E-03 1.56E-03 2.42E-03 Liver 7.32E-04 4.99E-04 6.45E-03 2.08E-03 1.55E-03 2.42E-03 Lung 9.02E-04 6.12E-04 6.52E-03 2.07E-03 1.55E-03 2.43E-03 Thyroid 2.32E-03 1.56E-03 1.06E-02 4.84E-03 3.01 E-03 2.69E-03 T.Body 7.32E-04 5.OOE-04 6.76E-03 2.09E-03 1.56E-03 2.44E-03 Age Class: Infant Bone 3.50E-04 2.56E-04 2.09E-04 6.07E-03 4.19E-03 8.08E-05 GI-LLI 4.41 E-04 3.02E-04 2.27E-04 1.36E-03 9.25E-04 2.64E-05 Kidney 4.39E-04 3.OOE-04 2.26E-04 1.38E-03 9.35E-04 2.63E-05 Liver 4.38E-04 3.00E-04 2.26E-04 1.37E-03 9.33E-04 2.63E-05 Lung 5.85E-04 3.97E-04 2.98E-04 1.36E-03 9.26E-04 2.99E-05 Thyroid 1.90E-03 1.27E-03 9.40E-04 7.61 E-03 4.17E-03 6.20E-05 T.Body 4.36E-04 2.99E-04 2.25E-04 1.37E-03 9.29E-04 2.63E-05 1 Distances are measured with respect to the reactor building vent.

2 Pathway designations are as follows:

D = Deposition (Ground Plane)

I = Inhalation C = Cow Milk G = Goat Milk V = Vegetable Garden M = Meat Page 24

Table 4.2-C Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Jul-Sep 2010 Receptor:

Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:

NNW ESE SE WSW W

S Distance1:

0.28 km 0.80 km 0.87 km 3.97 km 5.77 km 3.80 km Pathway2:

DI DI DIV DIVCG DIVCM DIVM Age Class: Adult Bone 2.06E-04 1.53E-04 6.19E-03 2.38E-03 2.07E-03 3.60E-03 GI-LLI 1.23E-03 8.32E-04 3.30E-03 6.47E-04 5.18E-04 8.44E-04 Kidney 1.19E-03 8.05E-04 3.20E-03 6.46E-04 5.17E-04 8.39E-04 Liver 1.19E-03 8.03E-04 3.20E-03 6.43E-04 5.15E-04 8.38E-04 Lung 1.29E-03

,8.71E-04 3.24E-03 6.43E-04 5.15E-04 8.40E-04 Thyroid 2.46E-03

ý1.65E-03 6;63E-03 1.70E-03 1.09E-03 I

,.07E-03.

T.Body 1.18E-03 8.01E-04 3.20E-03 6.42E-04 5.15E-04 8.38E-04 A e Class: Teen Bone 2.94E-04 2.19E-04 9.95E-03 3.99E-03 3.13E-03 5.08E-03 GI-LLI 1.26E-03 8.53E-04 4.22E-03 9.94E-04 7.38E-04 1.14E-03 Kidney 1.22E-03 8.26E-04 4.14E-03 9.95E-04 7.38E-04 1.14E-03 Liver 1.21 E-03 8.23E-04 4.13E-03 9.91E-04 7.36E-04 1.14E-03 Lung 1.38E-03 9.34E-04 4.20E-03 9.91E-04 7.36E-04 1.14E-03 Thyroid 2.83E-03 1.89E-03 7.25E-03 2.54E-03 1.56E-03 1.34E-03 T.Body 1.21 E-03 8.20E-04 4.14E-03 9.90E-04 7.35E-04 1.14E-03 Age Class: Child Bone 4.05E-04 3.02E-04 2.37E-02 9.62E-03 7.35E-03 1.17E-02 GI-LLI 1.11E-03 7.58E-04 7.65E-03 2.19E-03 1.62E-03 2.51E-03 Kidney 1.10E-03 7.50E-04 7.60E-03 2.20E-03 1.63E-03 2.51E-03 Liver 1.10E-03 7.47E-04 7.59E-03 2.20E-03 1.62E-03 2.51E-03 Lung 1.24E-03 8.42E-04 7.65E-03 2.19E-03 1.62E-03 2.51E-03 Thyroid 3.OOE-03 2.01E-03 1.21 E-02 5.18E-03 3.20E-03 2.81E-03 T.Body 1.09E-03 7.44E-04 7.62E-03 2.19E-03 1.62E-03 2.51E-03 Age Class: Infant Bone 2.98E-04 2.22E-04 1.84E-04 6.03E-03 4.18E-03 8.01E-05 GI-LLI 6.52E-04 4.44E-04 3.32E-04 1.42E-03 9.57E-04 3.23E-05 Kidney 6.51 E-04 4.43E-04 3.32E-04 1.44E-03 9.69E-04 3.23E-05 Liver 6.50E-04 4.43E-04 3.31 E-04 1.44E-03 9.67E-04 3.23E-05 Lung 7.82E-04 5.30E-04 3.96E-04 1.42E-03 9.58E-04 3.55E-05 Thyroid 2.40E-03 1.60E-03 1.19E-03 8.16E-03 4.48E-03 7.53E-05 T.Body 6.46E-04 4.40E-04 3.29E-04 1.43E-03 9.61 E-04 3.22E-05 1

2 Distances are measured with respect to the reactor building vent.

Pathway designations are as follows:

D = Deposition (Ground Plane)

I = Inhalation C = Cow Milk G = Goat Milk V = Vegetable Garden M = Meat Page 25

Table 4.2-D Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Oct-Dec 2010 Receptor:

Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:

NNW ESE SE WSW W

S Distance1 :

0.28 km 0.80 km 0.87 km 3.97 km 5.77 km 3.80 km Pathway:

DI DI DIV 3 DIVCG 3 DIVCM3 DIVM3 Age Class: Adult Bone 2.12E-04 1.57E-04 6.54E-03 2.39E-03 2.08E-03 3.60E-03 GI-LLI 2.29E-03 1.55E-03 5.18E-03 8.04E-04 6.11E-04 9.56E-04 Kidney 2.26E-03 1.53E-03 5.09E-03 8.02E-04 6.09E-04 9.50E-04 Liver 2.25E-03 1.52E-03 5.08E-03 8.OOE-04 6.08E-04 9.50E-04 Lung 2.35E-03 1.58E-03 5.12E-03,.

8.OOE-04 6.08E-04 9.52E-04

-Thyroid -

3.38E-03

-2.27E-03 8.04E 1.69E-03 -.. t09E-03 1.15E-03 T. Body 2.25E-03 1.52E-03 5.10EL03 *.

8.OOE-04 6.08E-04 9.51E-04 Age Class: Teen Bone 3.OOE-04 2.23E-04 1.04E-02 4.OOE-03 3.13E-03 5.09E-03 GI-LLI 2.33E-03 1.58E-03 6.31E-03 1.17E-03 8.40E-04 1.26E-03 Kidney 2.30E-03 1.55E-03 6.22E-03 1.17E-03 8.40E-04 1.26E-03 Liver 2.29E-03 1.55E-03 6.21E-03 1.17E-03 8.38E-04 1.26E-03 Lung 2.44E-03 1.65E-03 6.28E-03 1.17E-03 8.38E-04 1.26E-03 Thyroid 3.72E-03 2.50E-03 8.91 E-03 2.48E-03 1.53E-03 1.43E-03 T.Body 2.29E-03 1.55E-03 6.23E-03 1.17E-03 8.38E-04 1.26E-03 Age Class: Child Bone 4.12E-04 3.06E-04 2.46E-02 9.64E-03 7.35E-03 1.17E-02 GI-LLI 2.06E-03 1.40E-03 1.05E-02 2.45E-03 1.76E-03 2.67E-03 Kidney 2.05E-03 1.39E-03 1.05E-02 2.45E-03 1.77E-03 2.67E-03 Liver 2.05E-03 1.39E-03 1.05E-02 2.45E-03 1.77E-03 2.67E-03 Lung 2.18E-03 1.47E-03 1.05E-02 2.45E-03 1.76E-03 2.67E-03 Thyroid 3.74E-03 2.51E-03 1.43E-02 4.97E-03 3.1OE-03 2.92E-03 T.Body 2.05E-03 1.39E-03 1.05E-02 2.45E-03 1.77E-03 2.67E-03 Age Class: Infant Bone 2.99E-04 2.23E-04 1.85E-04 6.01E-03 4.17E-03 7.99E-05 GI-LLI 1.20E-03 8.13E-04 6.06E-04 1.54E-03 1.02E-03 4.73E-05 Kidney 1.20E-03 8.13E-04 6.05E-04 1.56E-03 1.03E-03 4.72E-05 Liver 1.20E-03 8.12E-04 6.05E-04 1.56E-03 1.03E-03 4.72E-05 Lung 1.31 E-03 8.89E-04 6.62E-04 1.55E-03 1.02E-03 5.OOE-05 Thyroid 2.75E-03 1.84E-03 1.36E-03 7.25E-03 3.98E-03 8.52E-05 T.Body 1.19E-03 8.1OE-04 6.03E-04 1.55E-03 1.02E-03 4.71E-05 1

2 Distances are measured with respect to the reactor building vent.

Pathway designations are as follows:

D = Deposition (Ground Plane)

C = Cow Milk I= Inhalation G = Goat Milk V = Vegetable Garden M = Meat 3 Doses are conservative since it is unlikely for vegetables to be grown outside or for animals to be fed on pasture during winter months.

Page 26

Table 4.2-E Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Jan-Dec 2010 Receptor:

Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:

NNW ESE SE WSW W

S Distance':

0.28 km 0.80 km 0.87 km 3.97 km 5.77 km 3.80 km Pathway2:

DI DI jDIV3 DIVCG 3 DIVCM3 DIVM 3 Age Class: Adult Bone 9.28E-04 6.82E-04 3.04E-02 9.76E-03 8.41 E-03 1.47E-02 GI-LLI 5.14E-03 3.48E-03 1.37E-02 2.62E-03 2.08E-03 3.39E-03 Kidney 5.OOE-03 3.38E-03 1.32E-02 2.60E-03 2.07E-03 3.36E-03 Liver 4.98E-03 3.38E-03 1.32E-02 2.59E-03 2.07E-03 3.36E-03 Lung 5.38E-03 3.64E-03 1.33E-02 2.59E-03 2.07E-03 3.36E-03 Thyroid 9.38E-03 6.29E-03

--2.52E-02

-..6.25E-03' 4.04E-03 4.16E-03 T.Body 4.98E-03 3.37E-03 1.33E-02 2.60E-03 2.07E-03 3.37E-03 Age Class: Teen Bone 1.29E-03 9.53E-04 4.71 E-02 1.63E-02 1.27E-02 2.06E-02 GI-LLI 5.26E-03 3.56E-03 1.74E-02 4.OOE-03 2.96E-03 4.58E-03 Kidney 5.11E-03 3.47E-03 1.70E-02 3.99E-03 2.96E-03 4.56E-03 Liver 5.1OE-03 3.46E-03 1.69E-02 3.98E-03 2.95E-03 4.55E-03 Lung 5.75E-03 3.89E-03 1.72E-02 3.98E-03 2.95E-03 4.57E-03 Thyroid 1.07E-02 7.14E-03 2.78E-02 9.36E-03 5.80E-03 5.26E-03 T.Body 5.09E-03 3.45E-03 1.71 E-02 3.98E-03 2.95E-03 4.57E-03 Age Class: Child Bone 1.75E-03 1.29E-03 1.09E-01 3.91 E-02 2.97E-02 4.75E-02 GI-LLI 4.67E-03 3.17E-03 3.12E-02 8.78E-03 6.48E-03 1.OOE-02 Kidney 4.62E-03 3.14E-03 3.09E-02 8.80E-03 6.50E-03 1.OOE-02 Liver 4.61E-03 3.13E-03 3.09E-02 8.78E-03 6.49E-03 1.OOE-02 Lung 5.17E-03 3.50E-03 3.11E-02 8.77E-03 6.48E-03 1.OOE-02 Thyroid 1.11E-02 7.46E-03 4.65E-02 1.91 E-02 1.19E-02 1.1OE-02 T.Body 4.60E-03 3.13E-03 3.13E-02 8.80E-03 6.49E-03 1.OOE-02 Age Class: Infant Bone 1.24E-03 9.16E-04 7.58E-04 2.40E-02 1.66E-02 3.19E-04 GI-LLI 2.73E-03 1.86E-03 1.39E-03 5.67E-03 3.82E-03 1.32E-04 Kidney 2.72E-03 1.85E-03 1.39E-03 5.74E-03 3.86E-03 1.32E-04 Liver 2.72E-03 1.85E-03 1.39E-03 5.73E-03 3.85E-03 1.32E-04 Lung 3.23E-03 2.19E-03 1.63E-03 5.67E-03 3.82E-03 1.44E-04 Thyroid 8.71 E-03 5.82E-03 4.31 E-03 2.91 E-02 1.60E-02 2.79E-04 T.Body 2.71 E-03 1.84E-03 1.38E-03 5.70E-03 3.83E-03 1.32E-04 1 Distances are measured with respect to the reactor building vent.

2 Pathway designations are as follows:

D = Deposition (Ground Plane)

C = Cow Milk I= Inhalation G = Goat Milk V = Vegetable Garden M = Meat 3 Doses are conservative since it is unlikely for vegetables to be grown outside or for animals to be fed on pasture during winter months.

Page 27

4.3 Doses From Liquid Effluent Releases Liquid effluent release data presented in Tables 2.3-A and 2.3-B were used as input to the dose assessment computer program to calculate radiation doses.

The maximum individual doses resulting from radionuclides released in liquid effluents are presented in Tables 4.3-A through 4.3-E.

These tables cover the individual calendar quarters and the total calendar year, respectively.

Tables 4.3-A through 4.3-E summarize the maximum total body and organ doses for the adult, teen, and child age classes resulting from the major liquid exposure pathways. NRC Regulatory Guide 1.109 does not recognize the infant age class as being exposed to the liquid effluent pathways.

Therefore, doses for this age class are not included in any of the tables.

It should be noted that doses calculated for the entire year might not equal the sum of the doses for the individual quarters. Doses from liquid effluents are based on the concentration (activity divided by volume) of radionuclides released in the effluent, as prescribed by the NRC in, Regulatory Guide 1.109. If a larger proportion of activity is released with a relatively smaller volume of dilution water during a given qUarter,'the resulting concentration for that quarter will be"hgheri6than-concentrations from other quarters. This will result in a proportionally higher dose for that quarter. However, when that quarter's activity values are included in the annual sum, and divided by the total annual dilution flow, the resulting dose contribution will be smaller. In such a situation, the annual dose will actually be less than the sum of the individual quarterly doses.

Radioactivity released in liquid effluents from PNPS during the reporting period resulted in a maximum total body dose (child age class) of 0.00197 mrem. The maximum organ dose (adult age class, GI-LLI) was 0.00997 mrem.

Page 28

Table 4.3-A Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jan-Mar 2010 Age Class Organ Dose - mrem

Organ Adult Teen Child Bone 0.OOE+00 O.OOE+00 0.OOE+00 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 Kidney O.OOE+00 O.OOE+00 0.OOE+00 Liver 0.OOE+00 O.OOE+00 0.OOE+00 Lung 0.OOE+00 0.OOE+00 O.OOE+00 Thyroid

.O00E4:00 0.OOE+00 O.OOE+00 T.Body 0.OOE+00 0.OOE+00 0.OOE+00

These doses are conservative since the same usage factor was applied for each quarter.

In reality, it is unlikely that anyone would be swimming or boating during the entire year.

However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose.

Page 29

Table 4.3-B Maximum Individual Organ Doses -- mrem From Liquid Release Period: Apr-Jun 2010 Age Class Organ Dose - mrem Organ Adult Teen Child Bone 2.26E-03 2.34E-03 2.74E-03 GI-LLI 1.OOE-02 6.80E-03 2.45E-03 Kidney 2.OOE-03 2.01 E-03 1.51 E-03 Liver 4.22E-03 4.14E-03 3.61 E-03

..Lung, 6.OOE-04 9.62E-04 6.48E-04 Thyroid 6.95E-05 3.75E-04 7.97'E-05" T.Body 1.75E-03 1.92E-03 1.98E-03 Page 30

Table 4.3-C Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jul-Sep 2010 Age Class Organ Dose - mrem Organ Adult Teen Child Bone 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI O.OOE+00 O.OOE+00 0.OOE+00 Kidney 0.OOE+00 0.OOE+00 0.OOE+00 Liver 0.OOE+00 0.OOE+00 0.OOE+00 Lung 0.OOE+00..

0.OOE+00 0.OOE+00 Thyroid 0.OOE+00 O.OOE+00 0.OOE+00 T.Body 0.OOE+00 O.OOE+00 0.OOE+00 Page 31

Table 4.3-D Maximum Individual Organ Doses -- mrem From Liquid Release Period: Oct-Dec 2010 Age Class Organ Dose - mrem

Organ Adult Teen Child Bone 7.98E-07 9.46E-07 8.18E-07 GI-LLI 4.57E-07 5.48E-07 1.63E-07 Kidney 2.35E-07 4.70E-07 2.20E-07 Liver 5.75E-07 8.11E-07 5.42E-07 Lung 1.20E-07 3.62E-07 1.22E707 Thyroid 8.98E-08 3.21 Er07 9.73E-08 T.Body 5.04E-07 5.73E-07 2.53E-07

These doses are conservative since the same usage factor was applied for each quarter.

In reality, it is unlikely that anyone would be swimming or boating during these months.

However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose.

Page 32

Table 4.3-E Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jan-Dec 2010 Age Class Organ Dose - mrem

Organ Adult Teen Child Bone 2.25E-03 2.33E-03 2.73E-03 GI-LLI 9.97E-03 6.77E-03 2.44E-03 Kidney 1.99E-03 2.OOE-03 1.50E-03 Liver 4.20E-03 4.13E-03 3.59E-03 Lung

_ 5.98E-04 9.58E-04 6.45E-04

'Thyroid 6.92E-05 3.74E-04 7.94E-05 T.Body 1.74E-03 1.91 E-03 1.97E-03

These doses are conservative since the same usage factor was applied for each quarter.

In reality, it is unlikely that anyone would be swimming or boating during the entire year.

However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose.

Page 33

5.0 OFFSITE AMBIENT RADIATION MEASUREMENTS The PNPS ODCM does not contain control limits related specifically to offsite ambient radiation exposure.

However, Regulatory Guide 1.21 (Reference 1) recommends calculation of ambient radiation exposure as part of the overall assessment of radiological impact on man.

Thermoluminescent dosimeters (TLDs) are located at 83 sites beyond the boundary of the PNPS restricted/protected area. A number of these TLDs are located within the site boundary, on Entergy property in close proximity to the station proper. The TLDs are collected on a quarterly basis and used to calculate the ambient radiation exposure in milliRoentgen (mR) over the exposure period.

These TLDs are grouped into four zones of increasing distance from the station. Average exposure values for each of these zones were calculated for each calendar quarter and the total year. The average exposure values (mR) for the four zones are presented in Table 5.0.

In addition to responding to ambient radiation exposure, TLDs will also record radiation resulting from noble gases (plumeand immersion exposure), particulate materials deposited on the ground, cosmic rays from Outer space, and--from naturally-occurring radioactivity in. the soil and air.

Typically, the exposure from cosmic rays and other natural radioactivity components is about 40 to 70 mR/year. As calculated in Sections 4.1 and 4.2 of this report, the ambient radiation component of doses from PNPS effluent emissions are below 1 mrem/yr and would not be discernible above the natural radiation exposure levels.

The major source of ambient radiation exposure from PNPS results from high-energy gamma rays emitted from nitrogen-16 (N-16) contained in steam flowing through the turbine. Although the N-16 is enclosed in the process lines and turbine and is not released into the environment, the ambient radiation exposure and sky shine from this contained source accounts for the majority of the radiation dose, especially in close proximity to the station.

Other sources of ambient radiation exposure include radiation emitted from contained radioactive materials and/or radwaste at the facility. Despite these sources of ambient radiation exposure at PNPS, increases in exposure from ambient radiation are typically not observable above background levels at locations beyond Entergy controlled property.

The average exposure values presented in Table 5.0 appear to indicate an elevation in ambient exposures in Zone 1, those TLDs within 2 miles of PNPS. Most of this elevation is due to increases in exposure levels measured at TLD locations on Entergy property in close proximity to the station proper. For example, the annual exposure at TLD location OA, located at the Overlook Area near the PNPS Health Club (I&S Building), was 215 mR for the entire year. This location is immediately adjacent to the station proper and overlooks the turbine building, therefore receiving the highest direct ambient and sky shine exposure. When the near-site TLDs (those located within 0.6 km of the Reactor Building) are removed from the calculation of averages, the mean annual exposure in Zone 1 falls from 74.2 +/- 28.8 mR/yr to 61.4 +/- 7.9 mR/yr. Such a corrected dose is not statistically different from the Zone 4 average of 59.8 _ 6.9 mR/yr, and is indicative of natural background radiation.

Although the annual exposure at TLD location OA was 155 mR above the average Zone 4 exposure, members of the general public do not continuously occupy this area. When adjusted for such occupancy, a hypothetical member of the public who was at this location for 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months per year would only receive an incremental dose of 0.7 mrem over natural background radiation levels. At the nearest residence 0.8 kilometers (0.5 miles) southeast of the PNPS Reactor Building, the annual exposure was calculated as being 58.5 +/- 8.0 mR (based on continuous occupancy at this location),

which compares quite well to the Zone 4 annual average background radiation level of 59.8 +/- 6.9 mR. Statistically, there is no difference between these two values.

Page 34

It must be emphasized that the projected ambient exposures discussed on the previous page are calculated to occur to a maximum-exposed hypothetical individual.

Even though conservative assumptions are made in the projection of these dose consequences, all of the projected doses are well below the NRC dose limit of 100 mrem/yr specified in 10CFR20.1301, as well as the EPA dose limit of 25 mrem/yr specified in 40CFR190. Both of these limits are to be applied to real members of the general public, so the fact that the dose to the hypothetical maximum-exposed individual is within the limits ensures that any dose received by a real member of the public would be smaller and well within any applicable limit.

In 1994, Pilgrim Station opened the old training facility (I&S Building) overlooking the plant as a health club for its employees. This site is immediately adjacent to the protected area boundary near monitoring location OA and receives appreciable amounts of direct ambient and sky shine exposure from the turbine building. Although personnel using this facility are employees of Entergy, they are considered to be members of the public. Due to their extended presence in the facility (500 hr/yr, assuming utilization of the facility for 2 hr/day, 5 days a week, for 50 weeks/yr), these personnel represent the most conservative case in regards to ambient radiation exposure to a member of the public within the PNPS owner controlled area.

Their annual ihCrementalV-radiation dose above background during 2010 is estimated as being about 1.8 mrem, based on the average exposure measured by the TLD in the building.

The exposures measured by the TLD located in the health club would also include any increase in ambient radiation resulting from noble gases and/or particulate activity deposited on the ground from gaseous releases. However, they would not indicate any internal dose received by personnel in this facility from inhalation of small amounts of PNPS-related radioactivity contained in the air. An environmental air sampler located immediately adjacent to the health club did not indicate any PNPS-related activity during 2010.

Dose calculations performed in the same manner as those outlined in Section 4.2 for airborne effluent releases yielded a projected total body dose to the maximum-exposed individual (500 hr/yr exposure) of about 0.0011 mrem, resulting from inhalation.

Again, it must be emphasized that the above-described exposures were received by personnel who are employees or contractors of Entergy, accessing areas or facilities on property under the ownership and control of Entergy.

Since this exposure was received within the owner-controlled area, it is not used for comparison to the annual dose limit of 25 mrem/yr specified in 40CFR190.

This regulation expressly applies to areas at or beyond the owner-controlled property, and is not applicable in this situation. As stated earlier, TLDs at and beyond the site boundary do not indicate elevated ambient radiation levels resulting from the operation of Pilgrim Station.

Although some of the TLDs in close proximity to PNPS indicate increases in exposure levels from ambient radiation, such increases are localized to areas under Entergy control. For members of the general public who are not employed or contracted with Entergy and are accessing Entergy controlled areas (e.g., parking lots, etc.), such increases in dose from ambient radiation exposure are estimated as being less than 1.0 mrem/year.

Page 35

Table 5.0 Average TLD Exposures By Distance Zone During 2010 Average Exposure +/- Standard Deviation: mR/period Exposure Zone 1*

I Zone 2 Zone 3 Zone 4 Period 0-3 km I

3-8 km 8-15 km

>15 km Jan-Mar 17.7 +/- 7.4 13.4 +/- 1.7 13.4 +/- 1.9 14.8 +/- 2.2 Apr-Jun 19.2 +/- 7.8 14.7 +/- 1.7 14.0 +/- 1.3 15.2 +/- 1.8 Jul-Sep 18.8+/- 6.5 14.5 +/- 1.8 14.2 +/- 1.5 15.4 +/- 1.5 Oct-Dec 18.4 +/- 7.1 14.1 +/- 1.6 13.5 +/- 1.3 14.4 +/- 1.5 Jan-Dec 74.2 +/- 28.8**

56.6 +/- 7.0 55.1 +/- 5.9 59.8 +/- 6.9 Zone 1 extends from the PNPS rdstricted/protected area boundary outward to 3 kilometers (2 miles), and includes severalTLDs located within the site boundary.

- When corrected for TLDs located within the site boundary, the Zone 1 annual average is calculated to be 61.4 +/- 7.9 mR/yr.

Page 36

6.0 PERCENT OF ODCM EFFLUENT CONTROL LIMITS The PNPS ODCM contains dose and concentration limits for radioactive effluents. In addition, the effluent controls specified ensure that radioactive releases are maintained as low as reasonably achievable. The percentage of the PNPS ODCM Control limit values were determined from doses calculated in Section 4, the effluent releases summarized in Section 2, and the ODCM Control limits/objectives listed in Tables 6.1 and 6.2.

The percent of applicable control limit values are provided to supplement the information provided in the Section 2 of this report. The format for the percent of applicable limits is modified from that prescribed in Regulatory Guide 1.21 (Reference 1) to accommodate the Radioactive Effluents Technical Specifications (RETS) that became effective March 01, 1986. The percentages have been grouped according to whether the releases were via liquid or gaseous effluent pathways.

6.1 Gaseous Effluent Releases Dose-based effluent controls related to exposures arising from gaseous effluent releases are presented in Table 6.1.

The maximum quarterly air doses and annual whole body doses listed in Table 4.1 were used to calculate the percentage values shown in Table 6.1.

All doses resulting from noble gas exposure were a small percentage of the applicable effluent control.

Organ dose limits for the maximum-exposed individual from radioactive particulates, iodines, and tritium from the PNPS ODCM are also shown in Table 6.1.

The maximum quarterly and annual organ doses from Tables 4.2-A through 4.2-E were used to calculate the percentages shown in Table 6.1. The resulting organ doses from Pilgrim Station's gaseous releases during 2010 were a small percentage of the corresponding effluent control.

Page 37

Table 6.1 Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2010 A.

Instantaneous Dose Rate Limit - Noble Gases PNPS ODCM Control 3.3.1.a Limit: 500 mrem/yr Total Body Dose Period Jan-Dec Value - mrem/yr 7.78E-03 Fraction of Limit 1.56E-03%

B.

Instantaneous Dose. Rate Limit - Noble Gases PNPS ODCM Control 3.3.1.a Limit:i 3000 mrebri/yr Skin Dose Period Jan-Dec Value - mrem/yr 2.53E-02 Fraction of Limit 8.42E-04%

C.

Instantaneous Dose Rate Limit - Particulates, lodines, & Tritium PNPS ODCM Control 3.3.1.b Limit: 1500 mrem/yr Organ Dose Period Jan-Dec Value - mrem/yr 1.09E-01 Fraction of Limit 7.30E-03%

D.

Quarterly Dose Objective - Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.a Objective: 5 mrad Gamma Air Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value - mrad 2.15E-03 3.48E-03 5.20E-03 7.72E-04 Fraction of Limit 4.31 E-02%

6.96E-02%

1.04E-01 %

1.54E-02%

E.

Annual Dose Objective - Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.b Objective: 10 mrad Gamma Air Dose Period Jan-Dec Value - mrad/yr 1.16E-02 Fraction of Limit 1.16E-01%

Page 38

Table 6.1 (c6ntinued)

Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2010 F.

Quarterly Dose Objective - Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.a Objective: 10 mrad Beta Air Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value - mrad 3.21 E-03 5.19E-03 9.11 E-03 1.38E-03 Fraction of Limit 3.21 E-02%

5.19E-02%

9.11 E-02%

1.38E-02%

G.

Annual Dose Objective - Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.b Objective: 20 mrad Beta Air Dose Period Jan-Dec Value - mrad/vr 1.89E-02 Fraction of Limit 9.45E-02%

H.

Quarterly Dose Objective - Particulates, lodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.a Objective: 7.5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value - mrem 2.30E-02 3.82E-02 2.37E-02 2.46E-02 Fraction of Limit 3.07E-01 %

5.09E-01 %

3.16E-01 %

3.28E-01%

Annual Dose Objective - Particulates, lodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.b Objective: 15 mrem Organ Dose Period Jan-Dec Value - mrem/yr 1.09E-01 Fraction of Limit 7.30E-01 %

Page 39

6.2 Liauid Effluent Releases Liquid effluent concentration limits and dose objectives from the PNPS ODCM are shown in Table 6.2. The quarterly average concentrations from Table 2.3-A were used to calculate the percent concentration limits. The maximum quarterly and annual whole body and organ doses from Tables 4.3-A through 4.3-E were used to calculate the percentages shown in Table 6.2. The resulting concentrations, as well as organ and total body doses from Pilgrim Station's liquid releases during the reporting period were a small percentage of the corresponding effluent controls.

Page 40

Table 6.2 Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2010 A.

Fission and Activation Product Effluent Concentration Limit PNPS ODCM Control 3.2.1 Limit: 10CFR20 Appendix B, Table 2, Column 2 Value Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value - uCi/mL 0.OOE+00 2.41 E-10 O.OOE+00 1.09E-13 6.OOE-1 1 Fraction of Limit 0.OOE+00%

2.69E-03%

0.OOE+00%

9.26E-06%

6.72E-04%

B.

Tritium Average Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1.OE-03 jiCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value - uCi/mL O.OOE+00 1.61 E-08 O.OOE+00 1.18E-10 4.04E-09 Fraction of Limit O.OOE+00%

1.61 E-03%

O.OOE+00%

1.18E-05%

4.04E-04%

C.

Dissolved and Entrained Noble Gases Concentration Limit PNPS ODCM Control 3.2.1 Limit: 2.OE-04 gCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value - LtCi/mL 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fraction of Limit O.OOE+00%

0.OOE+00%

O.OOE+00%

0.OOE+00%

Page 41

Table 6.2 (continued)

Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2010 D.

Quarterly Total Body Dose Objective PNPS ODCM Control 3.2.2.a Objective: 1.5 mrem Total Body Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value - mrem 0.OOE+00 1.98E-03 0.OOE+00 5.73E-07 Fraction of Limit 0.OOE+00%

1.32E-01 %

0.OOE+00%

3.82E-05%

E.

Annual Total Body Dose Objective PNPS ODCM Control 3.2.2.b Objective: 3 mrem Total Body Dose Period Jan-Dec Value - mrem 1.97E-03 Fraction of Limit 6.56E-02%

F.

Quarterly Organ Dose Objective PNPS ODCM Control 3.2.2.a Objective: 5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value - mrem 0.OOE+00 1.OOE-02 0.OOE+00 9.46E-07 Fraction of Limit O.00E+00%

2.OOE-01 %

O.OOE+00%

1.89E-05%

G.

Annual Organ Dose Objective PNPS ODCM Control 3.2.2.b Objective: 10 mrem Organ Dose Period Jan-Dec Value - mrem 9.97E-03 Fraction of Limit 9.97E-02%

Page 42

7.0 RADIOACTIVE WASTE DISPOSAL DATA Radioactive wastes that were shipped offsite for processing and disposal during the reporting period are described in Table 7.0, in the standard NRC Regulatory Guide 1.21 format.

The total quantity of radioactivity in Curies and the total volume in cubic meters are summarized in Table 7.0 for the following waste categories:

Spent resins, filter sludges, and evaporator bottoms; Dry activated wastes, contaminated equipment, etc.;

Irradiated components, control rods, etc.; and, Other.

During the reporting period approximately 5.89E+01 cubic meters of spent resins, filter sludges, etc., containing a total activity of about 9.54E+02 Curies were shipped from PNPS for processing and disposal. Dry activated wastes and contaminated equipment shipped during the period totaled 2.98E+02 cubic meters and contained 1.81 E+00 Curies of radioactivity. No shipment of irradiated components was shipped during the reporting period containing 0 cubic meters and 0 curies. The "Other" category, made up from "Hi Rad Trash" consisted of 1.79E+01 cubic meters and 1.93E+00 curies. No shipments of irradiated fuel were made during the reporting period.

Estimates of major radionuclides, those comprising greater than 1% of the total activity in each waste category shipped, are listed in Table 7.0. There were 9 shipments to Energy Solutions' Bear Creek Facility; 3 shipments to Energy Solutions' Gallaher Road Facility; 8 shipments to Studsvik in Erwin, TN and 1 shipment to Studsvik/Race in Oak Ridge, TN.

Page 43

Table 7.0 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments January-December 2010 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Estimate of volume and activity content by type of waste I _

_Jan-Dec 2010 Type of waste Volume - m3 Curies Total Error

a. Spent resins, filters, filter sludges, 5.89E+01 9.54E+02

+/- 25%

evaporator bottoms, etc.

b. Dry activated waste, contaminated 2.98E+02 1.81 E+00

+/- 25%

equipment, etc.

c. Irradiated components, control rods, etc.

Not Applicable Not Applicable N/A

d. Other (describe): Hi-Rad Trash/Metals 1.79E+01 1.93E+00

+/-25%

2. Estimate of major nuclide composition by type of waste' Type of waste

]

Radionuclide I

Abundance

]

Total Error

a. Spent resins, filters, filter sludges, Mn-54 13.97%

+/- 25%

evaporator bottoms, etc.

Fe-55 45.45%

+/- 25%

Co-58 1.33%

+/- 25%

Co-60 29.17%

+/- 25%

Zn-65 4.88%

+/- 25%

Cs-1 37 1.77%

+/- 25%

b. Dry activated waste, contaminated Mn-54 4.73%

+/- 25%

equipment, etc.

Fe-55 78.61%

+/- 25%

Co-60 13.32%

+/- 25%

Cs-137 1.95%

+25%

c. Irradiated components, control rods, etc.

Not Applicable Not Applicable

+/- 25%

d. Other (describe): Hi-Rad Trash/Metals Cr-51 3.47%

+/- 25%

Mn-54 21.51%

+/- 25%

Fe-55 21.71%

+/- 25%

Co-60 11.78%

+/- 25%

Ni-63 40.04%

+/- 25%

"Major" is defined as any radionuclide comprising > 1% of the total activity in the waste category.

3. Solid Waste Disposition Number of Shipments J

Mode of Transportation

[

Destination 9

Tractor-trailer Energy Solutions Bear Creek Facility2 (Hittman Transport)

Oak Ridge, TN Tractor-trailer Energy Solutions Gallaher Road Facility (Hittman Transport)

Kingston, TN Tractor-trailer Studsvik Processing Facility, z (Hittman Transport)

Erwin, TN Tractor-trailer Studsvik/RACE, LLC z (Hittman Transport)

Memphis, TN 2 This processor provides volume reduction services for dry compressible waste, contaminated equipment, etc.

Remaining radioactive wastes will be shipped to Chem Nuclear Systems, Inc. in Barnwell, SC, or Envirocare, Inc.

in Clive, UT for final disposal.

B. IRRADIATED FUEL SHIPMENTS & DISPOSITION Number of Shipments I

Mode of Transportation I

Destination None N/A N/A Page 44

8.0 OFFSITE DOSE CALCULATION MANUAL REVISIONS The PNPS Offsite Dose Calculation Manual (ODCM) was not revised during the calendar year of 2010. Information regarding revisions to the ODCM can be found attached as Appendix D of this report.

Page 45

9.0 PROCESS CONTROL PROGRAM REVISIONS The following site-specific procedures related to the Process Control Program have been retired and replaced by the Entergy fleet procedures.

Retired PNPS Procedures Process Control Program: PNPS 1.15.6, PNPS 1.15.4, and PNPS 1.15.3 Shipment of Radioactive Waste: PNPS 6.9-160 10CFR Part 61 Sampling: PNPS 6.9-211 Replacement Entercy Fleet Procedures Process Control Program: EN-RW-105 Radioactive Shipping Procedure: EN-RW-102 Radioactive Waste Tracking Procedure: EN-RW-103 Scaling Factors: EN-RW-104 Integrated Transportation Security Plan: EN-RW-106 These procedures cover the methods used to accomplish the processing and packaging of radioactive waste at Pilgrim Nuclear Power Station.

Page 46

10.0 REFERENCES

1. U.S. Nuclear Regulatory Commission, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants", Regulatory Guide 1.21, Revision 1, June 1974.

2.

"Pilgrim Nuclear Power Station Offsite Dose Calculation Manual", Revision 9, June 2003.

3. U.S. Nuclear Regulatory Commission, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50 Appendix I", Regulatory Guide 1.109, Revision 1, October 1977.

4. U.S. Nuclear Regulatory Commission, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors",

Regulatory Guide 1.111, July 1977.

-5. -Boston Edison Company, "Pilgrim Station Unit 1 Appendix I Evaluation";April 1977.

6. Entech Engineering Inc., P100-R19, "AEOLUS A Computer Code for the Determination of Atmospheric Dispersion and Deposition of Nuclear Power Plant Effluents During Continuous, Intermittent and Accident Conditions in Open-Terrain Sites, Coastal Sites and Deep-River Valleys" Page 47

APPENDIX A Meteorological Joint Frequency Distributions TABLE TABLE TITLE PAGE A-1 Joint Frequency Distribution of Wind Directions and Speeds for the 48 33-ft Level of the 220-ft Tower A-2 Joint Frequency Distribution of Wind Directions and Speeds for the 58 220-ft Level of the 220-ft Tower Page 48

Table A-1 Joint Frequency Distribution of Wind Directions and Speeds For the 33-ft level of the 220-ft Tower Jan-Mar 2010 Class A Fre(

0.111 mph I N NNE NE IENE I E ESE I sE [SSE I s [SSW v SW s

Is ]

IW WI NW [NNWI TOTAL Calm-0.95 0

0 0

0.95-3.5 1

0 0

0 1

0 0

1 3

3.5-7.5 0

7 10 6

1 1

3 1

3 0

0 2

7 18 15 0

74 7.5-12.5 0

15 0

0 0

0 1

3 1

0 1

7 2

0 30 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 1 1 22 110 16 2 I1 3 I1 4 1 3 I1 2

8 25 17 I1 107 Class B Freg: 0.024 mp.

N NNE I NE ENE I E*

SE SSE S [SSW] SW IWSWI W IWNW] NW I NNW I TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

1 1

0 2

3.5-7.5 1

0 0

1 1

0 0

0 1

3 1

2 2

0 12 7.5-12.5 0

3 0

0 0

0 1

2 0

0 0

2 0

0 8

12.5-18.5 0

0 1

0 0

0 1

18.5-24 0

0 0

>24 0

0 0

TOTAL 1

3 I 1 1 1[0 0

0 1 12 1

[3 1[ 5 13 101 23 Class C Freg:

0.046 mph_

I N INNE I N ENE E IESE I SE I SSE]

S

[SSW] SW IWSWI W IWNWI NW I NNWI TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

1 2

0 3

3.5-7.5 0

1 0

2 0

0 2

0 4

1 0

3 9

7 1

2 32 7.5-12.5 0

5 0

0 0

1 0

0 1

1 9

12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 10 0

2 0 1 0 1 2 1 0 1 4 12 1 0 1 3 I10 18 14 1 3 44 Class D Freg 0.531 mph N I NNE NE ENE E

ESE SE SSE I S ISSWvI SW IWSWl W

IWNWI NW I v

NNWI TOTAL Calm-0.95 0

0 0

1 0

0 2

0 3

0.95-3.5 9

5 3

4 7

3 0

3 2

2 4

2 8

14 5

3 74 3.5-7.5 8

2 3

14 6

7 8

11 3

6 6

31 60 52 31 4

252 7.5-12.5 4

30 14 10 10 1

0 13 6

8 2

0 33 10 13 6

160 12.5-18.5 0

6 2

12 1

0 0

0 21 18.5-24 0

0 0

>24 0

0 0

TOTAL 21 43 22 I 40 24 11 8 1 27 1 11 16 1 12 34 1101 76 51 I13 510 Page 49

Table A-1 (continued)

Jan-Mar 2010 Class E Fre:

0.219 mph I

[

I NNE INEI ENEE I ESE I SE I SSE I S W I SW WSW I W I WNW IVNW I NNW I TOTAL Calm-0.95 0

0 0

0 1

0 0

0 1

0.95-3.5 1

1 1

5 5

3 1

2 10 4

1 8

9 2

5 3

61 3.5-7.5 1

0 0

2 5

4 3

1 7

9 6

55 17 3

2 0

115 7.5-12.5 0

0 1

1 14 2

0 0

0 7

0 4

0 0

29 12.5-18.5 0

0 0

1 3

0 0

0 4

18.5-24 0

0 0

>24 0

0 0

TOTAL 2 1 1 12 1 9 1271 9 14 [ 3 117 [

20 1 8 [

67 1 26T 5-I 7 [ 3 1 210 Class F Freg 0.044 mph I

NI NNE I NEI ENE I E I ESE I SEI SSE I S I SSW I SW[ WSW W I WNW Nw ITNNW I TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

2 0

0 0

1 2

5 3

1 1

1 16 3.5-7.5 0

0 0

2 0

1 0

0 0

1 10 6

0 0

20 7.5-12.5 0

0 0

4 2

0 0

0 6

12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL I0 I 0 0

4 0 1

0 0

0 6

14 11 3

1 1

I 42 Class G Freg 0.026 mph N [ NNE INE I ENE EI ESE SE SSE S I SSW I S[W I S

I VW WNW NW NNW I TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

0 1

0 0

2 0

0 0

0 3

3.5-7.5 0

0 0

0 9

2 0

0 0

0 11 7.5-12.5 0

0 0

2 9

0 0

0 11 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL I0 00 0

0 010 1 0 1

2 18 4 10 0

0 I0I 25 Class All Freg.

1.000 mph I

N [ NNE NE I ENE I E I ESE SE SSE ISI SSW SW I WSW I W WNW I NW I NNW I TOTAL Calm-0.95 0

0 0

0 1

1 0

0 2

0 4

0.95-3.5 11 6

4 11 13 6

1 5

13 7

7 17 20 19 14 8

162 3.5-7.5 10 10 13 27 13 13 16 13 17 17 32 102 94 82 51 6

516 7.5-12.5 4

53 15 11 24 3

0 13 8

27 14 4

35 19 16 7

253 12.5-18.5 0

6 3

13 4

0 0

0 26 18.5-24 0

0 0

>24 0

0 0

TOTAL 1 25 [

75 1351 62 1541 22 1171 31 138 1 51 1541 124 11491 120 183 1 21 1 961 Page 50

Table A-1 (continued)

Apr-Jun 2010 Class A Freq: 0.154 mphI N

NNEI NE ENE I E IESE SE SSE] S W Isw SW IVSV W IWNvv NW INNWvl TOTAL Calm-0.95 0

0 0

0.95-3.5 5

5 3

3 2

0 0

0 2

1 21 3.5-7.5 16 26 25 24 20 15 6

3 3

10 12 14 22 19 13 14 242 7.5-12.5 0

0 1

1 2

0 0

0 6

35 5

1 16 5

0 2

74 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL I 21 31 129 28 [24 115 1 6 13 9 I 4

[17 115 138 124 [15 I[17 337 Class B Freg: 0.051 I I N INNEI NE IENE I E I ESE] SE ISSE4 S

[SSW[ SW IWSW1 W IwNW[ NW INNWI TOTAL Calm-0.95 0

0 0

0.95-3.5 3

1 1

3 1

2 4

0 0

0 1

1 4

2 23 3.5-7.5 0

5 3

6 12 10 4

2 1

10 11 6

5 1

2 1

79 7.5-12.5 0

0 0

0 1

4 3

1 1

0 0

0 10 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 13 1 614 9 113 12 8 12 2

[14 114 7 1 7

7 12

[

3 112 Class C Freg. 0.065 mph I

N NNE NE ENE E

ESE SE SSE S

SSW vSW IWSWv W IvWNWvlW IWNNWv TOTAL Calm-0.95 0

0 0

0.95-3.5 1

6 6

2 3

0 4

1 0

0 0

0 1

3 0

3 30 3.5-7.5 4

2 5

7 8

6 0

2 9

16 13 10 4

4 1

0 91 7.5-12.5 0

0 0

0 1

12 6

0 0

1 0

0 20 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL I51811119 1 8 1 1I4 I 3 [10 [28 119 110 [ 5 [8 1 I3I 141 Class D Fre: 0.339 mph I N [NNE NE lENE E lESE SE SSE[

S ISSW ISW IWSWI W IWNWI NW INNW[ TOTAL Calm-0.95 0

0 0

0.95-3.5 21 23 21 17 17 17 18 20 14 10 6

8 4

7 13 13 229 3.5-7.5 15 6

17 9

23 28 8

7 46 109 55 30 47 15 3

5 423 7.5-12.5 0

0 0

2 1

1 0

0 0

56 18 0

4 1

4 0

87 12.5-18.5 0

0 0

0 2

0 0

0 2

18.5-24 0

0 0

>24 0

0 0

TOTAL I36 29 38 128 41 46 126 27 60 175 181 38 55 [23 T20 I 18 I 741 Page 51

Table A-1 (continued)

Apr-Jun 2010 Class E Fre: 0.271 mph N INNE NE ENE]

E ESE SE SSE[

ISS W W

SW IWSWI W IWNWI NW INNWI TOTAL Calm-0.95 0

0 0

0 1

0 3

0.95-3.5 12 5

9 16 11 10 20 22 18 9

13 30 28 16 22 6

247 3.5-7.5 2

1 0

2 5

1 2

0 15 78 63 49 43 11 7

4 283 7.5-12.5 0

0 0

22 33 0

0 1

0 0

56 12.5-18.5 0

0 0

2 0

0 0

0 2

18.5-24 0

0 0

>24 0

0 0

TOTAL I 14 6 191 18] 16 I 11 22 22 1 33 111 1110 79 [ 72 I 28 30 I10I 591 Class F Freg 0.099 mphL N [NNEI NE IENtEI IESEI SE [SSEI S ISSW I SWIWSW[ W [WNWI NW]INNWI TO;TAL~

Calm-0.95 0

0 0

0 1

0 0

1 0

0 3

0.95-3.5 1

1 0

9 2

2 2

0 3

4 18 46 15 11 4

4 122 3.5-7.5 0

0 1

1 0

0 0

0 2

8 37 26 3

0 0

0 78 7.5-12.5 0

0 0

2 11 0

0 0

13 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL I1 I1 1

10 12 2 13 I0 15 1

6 1 73 [18 112 14 14I 216 Class G Freg: 0.021 mph IN NNE NE ENE E

ESE SE ISSE IsI SSW ISWIWSW W IWNWI NW INNW TOTAL Calm-0.95 0

0 0

0 1

0 0

0 1

0 0

0 3

0.95-3.5 0

0 0

0 4

9 2

3 1

0 19 3.5-7.5 0

0 0

0 15 6

1 0

0 0

22 7.5-12.5 0

0 0

1 1

0 0

0 2

12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 0 I0 I0 I0 1 0 0 0 1 1 115 3 3 1

3 1 0 46 Class All Freg.

1.000 Nph N

NNE] NE TENEI E [ESE SE SSE ISI SSW I SW [WSW[ W IWNW] NW INNWJ TOTAL Calm-0.95 0

0 0

0 1

0 2

1 1

0 9

0.95-3.5 43 41 40 50 36 31 48 43 35 23 41 93 51 41 46 29 691 3.5-7.5 37 40 51 49 68 60 20 14 76 231 206 141 125 50 26 24 1218 7.5-12.5 0

0 1

3 3

1 0

0 8

132 77 2

21 8

4 2

262 12.5-18.5 0

0 0

2 2

0 0

0 4

18.5-24 0

0 0

>24 0

0 0

TOTAL 80 81 92 1102 108 92 I 691 57 120 1388 1328 1237 1198 1001 77 551 2184 Page 52

Table A-1 (continued)

J ul-Sep 2010 Class A Fre: 0.068 mph N

NNE[ NE ENE]

E ESE SE [SSE S ISSW IVS IVVVI W I[NVI NW INNWv TOTAL Calm-0.95 0

0 0

0.95-3.5 8

4 13 6

4 0

1 0

0 0

3 4

3 2

48 3.5-7.5 10 15 17 8

4 6

5 1

3 6

3 1

0 7

4 2

92 7.5-12.5 0

0 0

0 1

6 3

0 0

0 10 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 18 19 30 114 1 8 6

6 1

4 12 6 I1 I3 7

4 150 Class B Freg 0.043

... rphI N

INNEI NE IENE E E ESE SE [SSE I ISSW SW IWSW[ W IWNWI NW INNWI TOTAL Calm-0.95 0

0 0

0.95-3.5 1

3 3

3 0

0 1

0 0

3 6

0 3

1 24 3.5-7.5 1

1 1

7 1

5 1

1 2

16 5

10 3

1 1

1 57 7.5-12.5 0

0 0

10 3

0 0

0 13 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 12 4 14 I10 I1 5

2 I 1 2 126 1 8 113 [9 I1 4 12 94 Class C Freg. 0.061 mph I N NNE NE IENE I IE I SE ISSE S ISSWI SW I[WSV W IWNWI NV INNWI TOTAL Calm-0.95 0

0 0

0.95-3.5 3

4 0

3 4

2 1

3 0

0 1

3 2

2 8

6 42 3.5-7.5 0

2 2

9 3

1 2

1 9

19 11 7

3 3

2 0

74 7.5-12.5 0

0 0

0 1

13 4

0 0

0 18 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 13 16 12 12 7 [3 13 4

10 32 116 110 1 5 I10 6

134 Class D Freg: 0.305 raph IN NNEI NE ENE [E IESE SE ISSE S Ivvl SW I[WSWV1 VV IWNWI NW INNWI TOTAL Calm-0.95 0

0 0

0.95-3.5 14 11 28 22 15 12 19 20 28 11 2

14 8

4 8

10 226 3.5-7.5 2

9 25 21 6

8 5

3 35 145 51 32 12 14 3

2 373 7.5-12.5 0

1 3

0 0

0 23 37 11 0

0 0

75 12.5-18.5 0

0 0

0,

0 0

0 18.5-24 0

0 0

>24 0

0 0

TOTAL 16 21 56 43 21 20 124 123 86 193 [64 46] 20 18 11 I12 1 674 Page 53

Table A-1 (continued)

Jul-Sep 2010 Class E Freq: 0.347 mph I N NNE[ NE ENEI E ESE SE [SSEI S I ssWl SW IWsWt W IWNWI NWvINNWvl TOTAL Calm-0.95 5

1 2

0 0

1 1

1 0

0 0

0 11 0.95-3.5 8

21 22 22 14 13 13 18 52 22 13 35 19 19 18 18 327 3.5-7.5 4

3 11 3

10 13 0

4 31 134 57 82 19 14 7

3 395 7.5-12.5 0

0 9

0 0

1 0

0 0

13 10 0

0 0

33 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 17 25 144 125 124 127 13 123 84 170 80 1117 [38 133 125 1211 766 Class F Freg 0.143 mph IN I NNE I -NE I ENE'--E I ESE [ SE [SSEI 5lSSW SW IWSWl W IWNWI NW-

]INNWTrOTAL Calm-0.95 0

0 0

0 1

0 3

1 1

0 0

0 6

0.95-3.5 5

1 3

3 0

3 3

4 13 21 30 44 16 13 4

5 168 3.5-7.5 1

1 0

1 3

0 0

24 77 23 4

3 0

1 138 7.5-12.5 0

0 0

0 3

0 0

0 3

12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 12 13 14 1313 1 4 4 116 4 Il 67 [ 20 116 14 18 6 315 Class G Freg. 0.034 mph N [NNEj NE] ENE lET ESE [SE I SSE S

ISSWvI SW tWSWI W IWNWI NW INNWv TOTAL Calm-0.95 0

0 0

1 0

2 0

1 0

0 0

0 4

0.95-3.5 0

0 0

0 1

0 2

3 11 15 13 2

0 0

47 3.5-7.5 0

0 0

0 20 3

0 0

23 7.5-12.5 0

0 0

0 1

0 0

0 1

12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 10 0 10 0

0 0 111 1

2 1 5 1 32 191131 2 10 I0. 1 75 Class All Freg 1.000 mph N

NNE] NE IENET E

[ESE I SE SSE S ISSWlSW WSWI W IWNWV NW INNWv TOTAL Calm-0.95 5

1 2

0 0

0 1

2 4

4 1

1 0

0 0

0 21 0.95-3.5 39 44 69 59 37 30 39 45 95 57 57 114 67 44 44 42 882 3.5-7.5 18 31 56 49 27 33 13 10 80 344 224 158 41 42 17 9

1152 7.5-12.5 0

1 12 0

0 1

0 0

25 79 35 0

0 0

153 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 162 77 139 1108 [64 [64 153 157 1204 1484 [317 [273 108 86 161 151 I 2208 Page 54

Table A-1 (continued)

Oct-Dec 2010

--4*&,

Class A Freq: 0.043 ph N

NNEI NE IENEI E ESE SE [SSE S I svvl SW tWSWI W IWWI NW I NNWvI TOTAL Calm-0.95 0

0 0

0.95-3.5 5

2 2

2 0

0 0

0 2

4 17 3.5-7.5 5

9 5

0 3

0 0

0 11 22 8

7 70 7.5-12.5 0

0 2

0 0

0 1

1 5

0 9

12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL I10111 9

2 I3 0

0 I0 0

0 I0 I 0 1121231 1 111 96 Class B Freg: 0.033 mph tN I[NNEI NE J ENE El IESIE SE ISSE] -S-SSW I SW IWSW[ W I[WNW W

"NNWI TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

0 1

0 0

0 1

1 0

1 4

3.5-7.5 2

4 3

0 1

1 1

0 0

3 2

6 13 14 8

2 60 7.5-12.5 0

3 1

0 0

1 4

0 0

0 9

12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 12 17 14 0 12 1

1 10 10 31 2 17 118 115 18 13 1 73 Class C Freg 0.048 mph I N INNEI NE JENI E I ESE I SE I SSE I S ISSWI SW IWSWl WV IWI NW INNWI TOTAL Calm-0.95 0

0 0

0.95-3.5 0

1 1

0 0

2 0

0 0

1 2

0 7

3.5-7.5 1

3 12 0

0 1

1 0

2 1

7 17 18 3

4 4

74 7.5-12.5 1

3 2

1 0

0 0

4 4

7 1

1 24 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 2

7 15 I1 I0 3

1 1 0 2 1 I2 7 1 21 1 22 I11I 7 I5 105 Class D Frecj 0.462 raph IN INNE] NE IENEI E IESE I SE ISSEI S

ISSWvI SW Iwswl W IWNW] NW INNWI TOTAL Calm-0.95 0

0 0

0.95-3.5 6

8 6

10 11 0

3 6

2 2

3 3

10 7

12 5

94 3.5-7.5 10 26 44 12 17 27 20 10 38 50 45 76 96 72 62 7

612 7.5-12.5 16 64 20 1

3 1

20 1

16 19 3

14 27 32 49 17 303 12.5-18.5 1

0 4

0 0

0 2

0 0

3 0

2 12 18.5-24 0

0 0

>24 0

0 0

TOTAL 33 98 174 123 31 128 143 117 158 71 51 1 93 1 133 114 1123 131I 1021 Page 55

Table A-1 (continued)

Oct-Dec 2010 Class E Freq: 0.329 phI N NNE NE IENE [ E ESE I SE] SSE S Isswl SW IWSWI W Iwwl NW I___W1 TOTAL Calm-0.95 0

0 0

1 0

0 0

1 1

0 1

0 0

0 4

0.95-3.5 4

8 1

3 1

5 11 13 23 26 13 37 33 21 11 4

214 3.5-7.5 4

6 3

0 1

13 14 20 14 39 55 121 72 35 26 2

425 7.5-12.5 1

9 0

0 0

3 5

2 3

12 9

6 15 5

6 0

76 12.5-18.5 1

4 2

0 0

0 7

18.5-24 0

0 0

>24 0

0 0

TOTAL 10 27 6

3 [2 22 30 ] 35 40 [ 78 [ 78 [164 11211 611 43 [6 726 Class.F Freg 0.075 I ENE I E j ESE I SE I SSE I S I

[sw SW IWSW l W JI WNWI 'NW LNNW TOTAL Calm-0.95 0

0 0

2 0

0 0

0 2

0.95-3.5 0

0 0

2 23 17 14 14 6

7 1

0 84 3.5-7.5 0

0 0

0 2

7 41 18 0

0 0

0 68 7.5-12.5 0

0 0

0 12 0

0 0

12 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 0

I0 i0 i0.

0.0 0 12 1 25126 1 67 32 6 1 7 1 [ 0 166 Class G Freg 0.010 mph_

I N N

NNE NE I ENE I E IESE SE ISSE I S ISSW ISW IWSwl W IWNWI NW [NNW TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

0 4

8 1

1 0

0 14 3.5-7.5 0

0 0

0 5

1 0

0 0

0 6

7.5-12.5 0

0 0

0 1

0 0

0 1

12.5-18.5 0

0 0

0 1

0 0

0 1

18.5-24 0

0 0

>24 0

0 0

TOTAL I0 I0 I0 I0 0I0I I00 I I I I 01 I 1 Ij 0 [0[ 22 Class All Freg: 1.000 N

mph N

NE ENE I

E J ESE SE SSE S

ISSWvv SW IWSWI W

IWNWI N

N INvW[ TOTAL Calm-0.95 0

0 0

1 0

0 0

3 1

0 1

0 0

0 6

0.95-3.5 15 19 10 15 13 7

14 21 48 45 34 62 51 38 28 14 434 3.5-7.5 22 48 67 12 22 42 36 30 56 100 155 239 210 146 108 22 1315 7.5-12.5 18 79 25 2

3 4

25 3

19 31 25 25 51 45 61 18 434 12.5-18.5 2

4 6

0 0

0 2

0 1

0 0

3 0

2 20 18.5-24 0

0 0

>24 0

0 0

TOTAL I57I 150 [108 I 29 J 38 ] 54 75 J 54 [125 179 216 326 313 f 232 [ 197 56 I 2209 Page 56

Table A-1 (continued)

Jan-Dec 2010 Class A Freq 0.091 mphI N L

NNE INE ENE1 E I ESE [SE SSE S ISSW SW IWSW[ W IWNW[ NW NNW I TOTAL Calm-0.95 0

0 0

0.95-3.5 19 11 18 11 7

0 1

0 0

0 3

4 7

8 89 3.5-7.5 31 57 57 38 28 22 14 5

9 16 15 17 40 66 40 23 478 7.5-12.5 0

15 3

1 2

0 0

0 8

44 9

1 18 13 7

2 123 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 50 183 78 150 137 122 15 5

17 60 24 18 61 83 4

33 690

-Class.B Freg 0.040 mph I N INNE I NE I ENE [ E I ESEI SS I ssE I

SW IwswS W IWNW[ NW INNW I TOTAL Calm-0.95 0

0 0

0.95-3.5 4

4 4

6 2

2 5

0 0

3 8

4 53 3.5-7.5 4

10 7

14 15 16 6

3 3

29 19 25 22 18 13 4

208 7.5-12.5 0

6 1

0 0

0 2

16 6

2 5

2 0

0 40 12.5-18.5 0

0 1

0 0

0 1

18.5-24 0

0 0

>24 0

0 0

TOTAL I8 20 113 120 17 18

[I1I 3

5 45 25 130 35 123 121 8

302 Class C Freg 0.056 mph N

N INNE [NE ENE I E ESE I SE] ss I

S]ISWw SW IWSWl W IWNWI NW I NNW I TOTAL Calm-0.95 0

0 0

0.95-3.5 4

11 7

5 7

4 5

4 0

0 1

3 3

7 12 9

82 3.5-7.5 5

8 19 18 11 8

5 3

24 37 31 37 34 17 8

6 271 7.5-12.5 1

8 2

1 0

0 0

0 2

26 10 4

5 8

2 2

71 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL 10 27 128 24 118 12 10 7

26 63 42 44 42 32 22 17 424 Class D Freg:

0.390 p

N NNE NE I ENE IIE SEI SE I SSEI S ISSW SW IWSW I W IWNWI NW NNW I TOTAL Calm-0.95 0

0 0

1 0

0 2

0 3

0.95-3.5 50 47 58 53 50 32 40 49 46 25 15 27 30 32 38 31 623 3.5-7.5 35 43 89 56 52 70 41 31 122 310 157 169 215 153 99 18 1660 7.5-12.5 20 95 37 13 14 3

20 14 45 120 34 14 64 43 66 23 625 12.5-18.5 1

6 6

12 1

0 0

0 2

0 0

3 0

2 35 18.5-24 0

0 0

>24 0

0 0

TOTAL 1106 191 190 134 117 105 J101 94 J215 455 208 ]211 J309 231 205 [ 74 [

2946 Page 57

Table A-1 (continued)

Jan-Dec 2010 Class E Fre:

0.303 maph I N NNE I NEI ENEI I ESE I SE I SSE I S I SSW I SWvlvvSW I [VV WNW I NW INV I TOTAL Calm-0.95 5

1 2

0 0

1 0

1 1

2 3

0 2

0 1

0 19 0.95-3.5 25 35 33 46 31 31 45 55 103 61 40 110 89 58 56 31 849 3.5-7.5 11 10 14 7

21 31 19 25 67 260 181 307 151 63 42 9

1218 7.5-12.5 1

9 10 1

14 6

5 2

3 54 52 10 15 6

6 0

194 12.5-18.5 1

4 2

1 3

0 0

2 0

0 0

0 13 18.5-24 0

0 0

>24 0

0 0

TOTAL 43 1591 61 55 J 69 69 1 69 1 83 11741 379 12761 427 1257 [127 1105 1 40 1 2293

.. 1¢Class, F Frea: -0:098

'lass. F Freq: -M98

-mphDi N

NNE I NEIENEI E IESEI SE ISSEI S ISSwlsWwsw;I W IWNW INWI NNWI TOTAL Calm-0.95 0

0 0

0 2

0 3

3 1

1 0

0 11 0.95-3.5 6

2 3

14 2

5 5

6 39 43 64 109 40 32 10 10 390 3.5-7.5 1

1 1

4 3

1 0

0 4

40 165 73 7

3 0

1 304 7.5-12.5 0

0 0

6 28 0

0 0

34 12.5-18.5 0

0 0

18.5-24 0

0 0

>24 0

0 0

TOTAL I7 3

4 118 15 6 17 6 146 I 92 12581 183 1 47 [ 36 110 1 11 I 739 Class G Freg:

0.022 Nph I NNE NE ENE E

ESE SE I SSE I S I SSW ISW WSW I W I WNW INW INNW I TOTAL Calm-0.95 0

0 0

0 1

0 0

1 1

2 1

1 0

0 0

0 7

0.95-3.5 0

0 0

0 1

0 3

3 19 34 16 6

1 0

83 3.5-7.5 0

0 0

0 49 12 1

0 0

0 62 7.5-12.5 0

0 0

3 12 0

0 0

15 12.5-18.5 0

0 0

0 1

0 0

0 1

18.5-24 0

0 0

>24 0

0 0

TOTAL 010 0

0 1

0J1O 1 41818214711716 I11 01 168 Class All Freg:

1.000 J2 1 N

NNE NE I ENE I E ESE I SE I SSE I S I SSW I SW I WSW I W IVNW INW[ NNW I TOTAL Calm-0.95 5

1 2

0 1

1 2

2 5

7 5

3 2

1 3

0 40 0.95-3.5 108 110 123 135 99 74 102 114 191 132 139 286 189 142 132 93 2169 3.5-7.5 87 129 187 137 130 148 85 67 229 692 617 640 470 320 202 61 4201 7.5-12.5 22 133 53 16 30 9

25 16 60 269 151 31 107 72 81 27 1102 12.5-18.5 2

10 9

13 4

0 0

0 2

2 3

0 0

3 0

2 50 18.5-24 0

0 0

>24 0

0 0

TOTAL 1 224 1 383 13741 301 12641 232 12141 199 14871 1102 19151 960 1768 1 538 1418[ 183 7562 Page 58

Table A-2 Joint Frequency Distribution of Wind Directions and Speeds For the 220-ft level of the 220-ft Tower Jan-Mar 2010 Class A Freq 0.137 mph I N INNE NE I

I SE [SSE I S ISSWI SW ISWVl W IVWWI NW INNW TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

3.5-7.5 1

2 3

1 2

1 0

0 0

0 1

1 3

1 16 7.5-12.5 5

5 4

3 0

0 0

3 6

13 5

4 48 12.5-18.5 7

11 3

4 1

1 3

3 2

2 1

3 17 29 18 4

109 18.5-24 5

8 2

0 0

1 0

0 0

1 0

0 6

28 3

7 61

>24 6

8 0

0 0

0 4

10 5

2 35 TOTAL 12 34 12 813 3

3 I3 2 3

1 6 1 34-811 34 118 269 Class B Freg:

0.034 mp9 N

[NNE NE ENE E

ESE SE SSE IS SSW I

w W

IWNWI NW I0NNW0 TOTAL Ca0m-0.95 0

0 0

0.95-3.5 0

0 0

3.5-7.5 2

1 0

2 2

0 0

2 1

1 11 7.5-12.5 1

0 0

0 1

0 0

2 2

2 0

2 10 12.5-18.5 1

0 0

1 3

0 0

0 2

1 0

2 4

4 2

1 21 18.5-24 0

1 0

0 1

3 0

0 0

0 3

4 0

1 13

>24 1

5 1

0 0

0 1

3 0

1 12 TOTAL 15 7 I1 3

7 13 0

0 12 1 I 0 4

10 15 3 1 6I 67 Class C Freg:

0.057 mph I

N NNE NE ENE E

ESE SE SSE S

SSW SW I WSW vv IW WNW INW vNN TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 1

1 0

0 0

1 3

3.5-7.5 1

0 0

1 0

0 0

0 1

4 1

1 9

7.5-12.5 3

1 1

1 0

1 1

0 4

1 0

2 5

5 0

0 25 12.5-18.5 0

1 1

3 1

1 1

0 4

4 1

2 12 2

0 1

34 18.5-24 1

2 1

0 0

1 0

0 0

0 3

5 1

2 16

>24 10 5

0 0

1 1

4 4

25 TOTAL 15 9

4 15 111 4 12 I0 [8 1 15 1 4 2211716 1 9 I 112 Class D Freg. 0.502 mph N I NNE I NE I ENE I E I ESE [SE I SSE [ S Issw [SW IWSW W IWNWI NW I NNWI TOTAL Calm-0.95 0

0 0

0.95-3.5 1

0 1

0 0

0 1

0 0

1 0

0 1

0 2

2 9

3.5-7.5 3

3 3

3 8

7 3

4 7

0 0

1 5

6 5

3 61 7.5-12.5 10 1

3 8

7 8

6 9

10 8

6 14 12 18 9

4 133 12.5-18.5 6

3 2

15 7

3 9

6 3

6 7

28 106 52 17 7

277 18.5-24 2

12 7

14 6

1 3

25 4

7 3

4 35 53 37 12 225

>24 41 39 9

29 13 1

1 15 0

2 0

0 24 53 31 25 283 TOTAL 63 58 25 69 41 20 23 59 24 1 24 1 16 1 47 183 1182 101 1 53 988 Page 59

Table A-2 (continued)

Jan-Mar 2010 Class E Freg:

0.208 mph I N I NNE NIE ENE I E ESE ISE SSE IS ISSWI Sw IWSW IWI WNW NW NNW I TOTAL Calm-0.95 0

0 0

0.95-3.5 1

1 0

2 2

1 0

1 1

1 3

0 0

3 17 3.5-7.5 2

4 2

3 2

2 3

0 2

5 2

0 3

2 1

0 33 7.5-12.5 0

0 1

1 8

7 5

18 4

4 6

10 18 12 3

4 101 12.5-18.5 5

2 0

1 2

4 4

7 0

1 11 16 59 18 4

2 136 18.5-24 1

2 0

1 2

1 3

1 0

3 0

10 26 10 7

7 74

>24 2

0 0

9 22 1

0 0

0 2

0 0

0 7

4 1

48 TOTAL I1 9 [

3I 1 17 1381 16 1151 27 161 16 1201 37 11091 49 1 191 17 1 409 ClassF...

Freg 0.050 mph I

N I NNE INE IENEI E IESE ISE ISSE I SSW I iSW I WSW I W I WNW INW I NNW I TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 3

0 0

1 1

1 0

0 0

0 3

0 9

3.5-7.5 0

0 0

0 2

1 0

0 1

4 3

1 0

2 15 7.5-12.5 1

0 0

2 0

1 0

6 9

5 3

0 27 12.5-18.5 0

0 0

0 2

5 3

1 4

6 3

5 0

0 29 18.5-24 0

0 0

2 8

5 0

0 0

0 15

>24 0

0 0

2 2

0 0

0 4

TOTAL 1

00 0121 2 13 8 I4 6 115 1 115 I11 16 2 1 99 Class G Freg:

0.013 mphl I N [NNE INEI ENE E I ESE I SE I SSE I S I SSW I SW I WSW IW I WNW INW I NNW I TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

0 1

0 0

0 1

0 2

3.5-7.5 0

0 0

0 1

1 0

0 0

0 1

0 3

7.5-12.5 0

0 0

0 1

1 5

0 0

0 7

12.5-18.5 0

0 0

0 2

1 0

0 0

0 3

18.5-24 0

0 0

0 3

4 0

0 0

0 7

>24 0

0 0

0 4

0 0

0 4

TOTAL I0o I 0 0 0 1 0 0I110 Ill1101 6 5

0 1210 26 Class All Freg 1.000 rp I*ph N NNE INE[ ENE I E I ESEISEISSEI S ISSW ISWI WSW I W I WNW INW I NN W I TOTAL Calm-0.95 0

0 0

0.95-3.5 2

1 5

3 2

2 3

2 0

2 1

1 4

0 6

6 40 3.5-7.5 9

10 8

9 16 12 6

4 11 6

3 5

13 16 12 8

148 7.5-12.5 20 7

9 13 16 16 12 29 18 14 13 38, 57 55 20 14 351 12.5-18.5 19 17 6

24 14 9

19 21 14 15 26 58 201 110 41 15 609 18.5-24 9

25 10 15 9

7 6

26 4

13 14 23 73 100 48 29 411

>24 60 57 10 38 35 2

1 15 0

6 6

0 30 74 44 33 411 TOTAL 1119!

117 1481 102 1921 48 471 97 1471 56 1631 125 [378 1 355 11711 105 1970 Page 60

Table A-2 (continued)

Apr-Jun 2010 Class A Freg 0.154 mph N

NNE NE1ENE I ESE [

S SSE S I s SSW I SW IWSWI W Ivj WI N

[NNW I TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

1 1

0 0

0 2

3.5-7.5 6

14 11 5

3 1

0 0

1 1

0 4

46 7.5-12.5 10 8

7 7

13 14 9

2 5

1 3

9 7

6 5

5 111 12.5-18.5 7

4 2

0 0

1 7

2 7

23 10 8

9 7

5 2

94 18.5-24 5

0 2

2 2

1 0

0 4

15 1

0 16 8

2 9

67

>24 0

0 0

0 1

0 0

0 6

6 1

3 17 TOTAL 128 126 122 15 120 117 116 4

16 39 114 117 39 128 13 123 337 Class B Freg.0.051 maph N I NNE JNE (ENE I E[ ESE] SE ISSE S

I SW Isw

[WSWIW W IvNWv NW NNWI TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 1

0 0

0 1

3.5-7.5 4

3 0

2 3

0 0

0 1

4 0

0 17 7.5-12.5 1

3 2

2 1

17 6

2 1

5 6

5 4

1 4

1 61 12.5-18.5 0

0 0

0 1

4 2

2

,1 5

7 2

1 1

1 0

27 18.5-24 0

0 0

4 1

0 1

0 0

0 6

>24 0

0 0

TOTAL 5I 6 3

4 5

211 8 4

2 J14 14 7 1 7 1 6 1 5 1

112 Class C Freg:

0.065 p

I N I NNEI NE IENE I E ESE I SE ISSEI S

ISSWvI SW IVWSWV IWNWI NW INNW I TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

1 1

3.5-7.5 1

6 3

2 2

4 0

0 2

1 1

0 0

1 0

2 25 7.5-12.5 0

5 4

2 0

5 7

5 1

5 6

3 2

1 1

2 49 12.5-18.5 2

1 0

2 1

3 1

0 5

13 5

5 4

0 1

0 43 18.5-24 1

0 0

0 1

0 0

8 7

0 1

2 0

1 21

>24 0

0 0

1 1

0 2

TOTAL 1 4 112 7 I6 4 112 I 5I8 I

27 I 18 I7 I7 5 3 6 141 Class D Freg 0.339 mph I N NNE]

E I ENE I E I ESE I SE I SSEI ISSW SW IVWSWVI W IWNWI NW I NNW I TOTAL Calm-0.95 0

0 0

0.95-3.5 2

8 7

1 0

0 0

1 19 3.5-7.5 10 5

8 8

7 10 11 9

3 5

2 3

1 4

4 10 100 7.5-12.5 6

13 10 3

10 24 17 9

26 35 19 11 5

4 6

12 210 12.5-18.5 4

6 2

3 8

13 4

4 20 83 41 13 16 21 3

5 246 18.5-24 7

0 2

4 4

4 3

1 1

58 17 1

20 11 1

9 143

>24 0

0 1

3 0

0 0

4 3

0 1

6 5

0 23 TOTAL 29 132 130 122 29 151 35 23 [50 1185 82 128 143 146 119 37 741 Page 61

Table A-2 (continued)

Apr-Jun 2010 Class E Freg:

0.271 mph N

I NNE INEI ENE I E SE IsEISSEI S I SSW I SW I WSW I W I WNW INW I

[NW TOTAL Calm-0.95 0

0 0

0.95-3.5 0

2 5

4 1

4 0

0 0

1 1

0 1

3 0

1 23 3.5-7.5 4

2 2

1 9

10 3

3 7

5 0

1 2

1 5

3 58 7.5-12.5 12 2

3 1

3 10 9

9 10 16 5

4 3

14 5

5 111 12.5-18.5 5

1 0

0 2

0 6

10 14 41 30 10 27 40 13 13 212 18.5-24 2

0 0

1 0

39 50 8

21 18 5

9 153

>24 0

0 0

12 10 0

1 10 1

0 34 TOTAL 1 23 1 7 110 16 1151 24 1181 23 131 1114 1961 23 1 551 86 1291 31l 591

--Class F Freg 0.099 mph I

N I NNE INEI ENE I E I ESE ISEI SSEI S ISSW ISWI WSW IW I WNW I NW NNW I TOTAL Calm-0.95 0

0 0

0.95-3.5 1

1 1

0 0

1 2

3 0

0 0

1 0

0 0

2 12 3.5-7.5 3

1 0

1 1

3 4

0 3

0 1

2 3

2 4

1 29 7.5-12.5 2

0 2

0 1

1 2

2 1

1 3

7 4

14 8

5 53 12.5-18.5 1

0 0

1 0

0 1

2 5

4 6

10 16 18 16 5

85 18.5-24 0

0 0

1 23 7

2 1

0 2

36

>24 0

0 0

1 0

0 0

0 1

TOTAL 7 I2 32 12[5 9[7 9 I 7

33 27 25 35 1281 15I 216 Class G Freg:

0.021 mph N

NNE NE EN E

SE I SE SSE [S[

SSW SW]

S I

W W

I WNW I

NW N

I TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 1

0 0

1 1

0 0

1 0

0 0

0 4

3.5-7.5 2

0 0

0 1

1 0

0.

2 0

0 0

6 7.5-12.5 0

0 0

0 4

0 0

1 3

4 2

1 15 12.5-18.5 0

0 0

0 1

0 4

3 5

3 1

0 17 18.5-24 0

0 0

0 1

0 2

0 0

0 3

>24 0

0 0

0 1

0 0

0 1

TOTAL 2

0 1 1 10 1612 1 61 4 1121[7 13[11 1 46 Class All Freg 1.000 mph NI NNE I NE NE EI ESE SE ISSEI S I SSW I SW I WSW I W I WNW I

NW I

NNW TOTAL Calm-0.95 0

0 0

0.95-3.5 3

11 15 6

2 6

3 3

0 2

1 1

1 3

0 5

62 3.5-7.5 30 31 24 19 25 28 18 12 16 12 4

6 10 13 13 20 281 7.5-12.5 31 31 28 15 28 71 50 29 48 63 42 40 28 44 31 31 610 12.5-18.5 19 12 4

6 12 21 21 20 53 169 103 51 78 90 40 25 724 18.5-24 15 0

4 6

7 5

3 2

5 125 100 16 63 40 8

30 429

>24 0

0 1

3 1

0 0

17 14 0

8 23 8

3 78 TOTAL 198 85 176 1 55 1751 131 I9g5 66 1122 1 388 1264 1 114 11881 213 11001 114 1 2184 Page 62

Table A-2 (continued)

Jul-Sep 2010 Class A Freq 0.068 mph N

NNE NE ENE 0E ESE SE SSE 0S SSW [SW WSW 0WWNWI NW I NNW I TOTAL Ca0m-0.95 0

0 0

0.95-3.5 0

0 0

3.5-7.5 1

5 9

3 3

0 0

1 3

2 0

0 27 7.5-12.5 16 3

12 4

5 4

3 0

1 0

3 0

1 5

1 1

59 12.5-18.5 7

0 3

2 1

3 5

1 6

7 2

0 0

8 1

4 50 18.5-24 4

0 0

1 0

0 0

1 1

0 0

1 8

>24 5

0 0

1 0

0 0

0 6

TOTAL 133 18 124 10 9

7 8

1 7

9 1

4 15 2 16 150 Class B Freg:

0.043 mph

[:N IJNNE[INEJIENE [E ESE [SE] SSE [

I SS5W I

]SW

~

IW WIW IWNWI NW {NNW[I TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

3.5-7.5 1

2 3

2 2

0 0

1 3

2 0

2 18 7.5-12.5 2

0 1

1 1

2 3

0 0

6 1

5 4

3 1

0 30 12.5-18.5 0

0 0

3 0

1 2

1 6

13 5

4 0

2 1

1 39 18.5-24 0

0 0

1 0

0 0

1 3

0 0

0 5

>24 0

0 0

2 0

0 0

0 2

TOTAL 13 12 14 7

3 3

5 I 1 16 22 1 9 10 1 7

2 13 94 Class C Freg 0.061 mph!L.

N I [N NE ]ENE [E ]ESE [SE ISSEI S ISSW I SW IWSW I W jWNWI NW INNWI TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

3.5-7.5 2

3 0

3 1

2 0

0 0

1 3

1 1

3 4

3 27 7.5-12.5 0

0 2

2 1

7 7

2 7

7 6

5 3

6 2

0 57 12.5-18.5 0

0 0

2 0

0 2

0 5

10 6

2 3

2 0

1 33 18.5-24 0

0 0

1 0

0 0

0 2

6 3

0 1

2 0

0 15

>24 2

0 0

0 2

TOTAL 4 3

2 8

2 9

9 2

14 24 118 8

8 113 6

4 134 Class D Freg: 0.305 mph I

N NNE NE ENE E

ESE SE SSE S

SSW SW I WSW I W IW NWI NW INW NNW TOTAL Calm-0.95 0

0 0

0.95-3.5 2

5 7

1 1

0 1

0 0

1 18 3.5-7.5 9

5 10 6

12 7

8 6

7 6

4 1

1 4

2 1

89 7.5-12.5 5

5 4

8 6

11 11 28 21 33 17 9

12 4

4 3

181 12.5-18.5 2

2 3

8 5

5 5

5 20 83 45 12 18 13 3

6 235 18.5-24 5

7 6

10 0

1 0

3 21 38 22 2

4 7

2 1

129

>24 3

4 4

2 0

0 0

0 3

1 5

0 0

0 22 TOTAL 126 28 134 35 124 124 125 42 172 [161 193 124 135 [28 11[12I 674 Page 63

Table A-2 (continued)

Jul-Sep 2010 Class E Fre:

0.347 mp I N I NNE I NE I ENE IE ESE I SE I SSE I S I SSW SW I WSW I W I W NW I

NW I TOTAL Calm-0.95 0

0 0

0.95-3.5 0

4 3

4 2

2 2

1 3

0 1

0 0

2 24 3.5-7.5 4

6 6

4 9

9 14 6

10 4

1 3

3 1

4 3

87 7.5-12.5 4

11 16 1

6 6

11 13 15 21 6

4 11 9

14 9

157 12.5-18.5 5

2 1

5 1

3 2

23 29 67 41 35 65 27 9

12 327 18.5-24 3

0 6

4 0

5 0

1 4

55 21 1

9 12 7

3 131

>24 2

1 11 8

3 0

0 0

0 3

2 0

0 3

5 2

40 TOTAL 18 124 1 43 1 26 1211 25 1291 44 11 1150 172 ]

43 188 I 52 1 39 31I 766 Class F Freg 0.143 m_!E I N NNE I NE I ENE I EI' ESE I SE I SSE I S I SSW I SW I WSW I W I WNW I NW I NNW I TOTAL Calm-0.95 0

0 0

0.95-3.5 1

0 2

1 1

1 0

0 1

0 0

0 7

3.5-7.5 1

1 3

0 5

4 4

0 5

4 1

1 1

0 1

2 33 7.5-12.5 3

1 1

2 0

7 6

5 5

7 6

11 6

17 10 9

96 12.5-18.5 5

1 0

0 0

2 3

9 5

12 15 13 30 24 7

4 130 18.5-24 1

0 0

4 16 4

6 11 2

2 46

>24 0

1 0

2 0

0 0 0 0

0 0

3 TOTAL 11 I4 6] 5 1 61 14 1131 14 1 1 I 27 1 38 1 29 1 43 1 52 1 20 [ 17 1 315 Class G Freg:

0.034 mp!

II N NNE NE IENE*I ESE I SE I SSEI S ISSWI SW WSWI WI WNW L [

N I TOTAL Calm-0.95 0

0 0

1 0

0 0

0 1

0.95-3.5 1

2 1

1 2

0 0

0 1

0 0

0 2

1 0

1 12 3.5-7.5 1

0 1

0 2

3 1

1 0

0 3

2 17 7.5-12.5 0

0 0

1 2

4 3

6 2

3 1

1 23 12.5-18.5 0

0 0

0 1

3 7

6 0

1 18 18.5-24 0

0 0

0 3

1 0

0 0

0 4

>24 0

0 0

TOTAL 2

2 212 310 211 15 7

8 11 11 10 4

5 I

75 Class All Freg:

1.000 mph N

NNE INE IENE E ESE SE SSEI S ISSW [SWI WSW IWIWNWIN I NNW I TOTAL Calm-0.95 0

0 0

1 0

0 0

0 1

0.95-3.5 4

11 13 7

6 3

3 1

5 0

1 0

2 1

0 4

61 3.5-7.5 19 22 32 18 33 22 28 12 24 18 10 9

12 12 14 13 298 7.5-12.5 30 20 36 18 19 37 41 49 51 78 42 40 39 47 33 23 603 12.5-18.5 19 5

7 20 7

14 19 39 71 192 115 69 123 82 21 29 832 18.5-24 13 7

12 17 0

6 0

4 27 10569 8

20 32 11 7

338

>24 12 6

15 12 3

0 0

0 3

7 7

0 0

3 5

2 75 TOTAL 1 97 [

71 11151 93 1681 82 1911 10511811 400 12441 126 11961 177 1841 78 1 2208 Page 64

Table A-2 (continued)

Oct-Dec 2010 Class A Fre: 0.043 mph

[

NNE [NE ENEI El ESE SE ISSEI S

I

_SSW S[ IvSWl W IVWNV NW I vNNW TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

3.5-7.5 3

1 1

2 0

0 0

0 2

0 9

7.5-12.5 2

4 2

0 0

2 0

0 0

0 2

7 1

7 27 12.5-18.5 2

1 1

0 0

1 0

0 0

0 3

14 5

3 30 18.5-24 5

0 0

0 2

8 2

2 19

>24 0

0 3

0 0

0 1

1 6

0 11 TOTAL 12 6 17 2 10 13 10 1010 10 10 10 8 1 301 161121 96 Class B Freg 0.033 mph IN NNE NE ENE E

IESEI SE ISSEI S

W s

SW s

WSW W

IWWNw NW NNW TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

3.5-7.5 0

0 0

1 2

1 1

1 6

7.5-12.5 0

0 1

1 0

0 0

1 2

2 4

5 0

0 17 12.5-18.5 0

3 1

0 0

1 1

0 2

0 0

4 7

3 3

3 28 18.5-24 0

1 2

0 0

0 6

4 5

0 18

>24 3

0 0

0 1

0 4

TOTAL 3

4 4

12 I1 1 2 L 7 ]

19 13 10 1o 4 I_73_

Class C Freg: 0.048 mph I

NNE NE IENE IE ESEI SE SSEI S ISSWI SW IWSWI IWNW NW INNWI TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

3.5-7.5 1

0 1

0 0

0 2

1 0

1 1

0 7

7.5-12.5 0

0 1

0 0

3 0

0 0

1 3

8 5

2 1

0 24 12.5-18.5 0

1 5

0 0

0 1

0 2

0 3

12 6

2 1

3 36 18.5-24 0

2 8

0 0

0 9

2 2

0 23

>24 2

1 0

0 0

5 4

2 15 TOTAL 3

4 115 1 0 I3 0 I2 1

8 [21 120 112 1 9 5

105 Class D Frec.

0.462 ph N NNE I

NEI ENE [E ESE SE I SSEI S

ISSW [SW IWSwl W

IWNWI NW INNWvI TOTAL Calm-0.95 0

0 0

0.95-3.5 3

0 2

1 0

0 0

1 0

4 11 3.5-7.5 1

1 5

6 5

7 3

2 0

2 3

1 1

6 3

1 47 7.5-12.5 3

5 9

5 6

5 5

3 5

7 21 9

6 14 10 2

115 12.5-18.5 7

5 20 6

11 12 17 7

26 48 34 41 58 49 10 5

356 18.5-24 11 10 21 5

4 5

6 1

11 10 3

19 28 37 43 2

216

>24 52 25 12 1

7 0

18 0

5 0

0 0

5 42 81 28 276 TOTAL 77 46 69 24 33 29 49 13 1 47 67 1 61 1 70 198 1 149 1147 1 42 1021 Page 65

Table A-2 (continued)

Oct-Dec 2010 Class E Freq: 0.329 mph INNNEl NE IENE (E

[ESE SE ]SSE IS I SSW SW IWSWI/ W FNNW INNW I TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

0 2

1 1

2 0

1 2

0 1

1 0

1 12 3.5-7.5 1

1 0

2 4

3 5

4 1

0 3

1 3

2 12 1

43 7.5-12.5 3

3 3

1 1

9 12 6

8 12 15 7

16 20 13 9

138 12.5-18.51 4

6 0

0 2

1 13 22 10 23 32 47 60 58 27 3

308 18.5-24 2

2 0

0 3

9 6

3 1

15 13 20 40 29 17 3

163

>24 5

10 2

1 1

0 6

0 0

0 4

0 3

15 12 3

62 TOTAL I 15I 22 5

4 13 23 43 37 1 20 1 51 69 j 75 1123 1125 81 2

20 726 Class F Freg 0.075 mph IN INNE INE IENE I E I ESE SE ISSEISI SSW [ SW Iwswl W NW I NW" NNWT "TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

0 1

0 0

1 0

0 1

1 0

0 4

3.5-7.5 0

3 0

1 1

1 2

0 2

2 0

0 2

0 1

2 17 7.5-12.5 3

1 0

0 1

1 15 10 6

6 8

5 8

6 2

0 72 12.5-18.5 0

0 0

0 1

5 1

4 9

4 16 13 0

4 57 18.5-24 0

0 0

0 6

8 1

0 0

0 15

>24 0

0 0

0 1

0 0

0 1

TOTAL 3

4 0

1 1 3

2 1 18 15 9

13 124 1 17 28 1 20 1 3 1 6 166 Class G Freg: 0.010 mp I

NNEI NE ENEI El ESEI SE SSE S I[SSW SW Ivswl VV WNWI NW I[NNW TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

1 0

0 2

0 0

0 3

3.5-7.5 1

2 3

0 0

1 0

0 1

0 0

0 8

7.5-12.5 0

0 0

2 1

4 0

0 0

0 7

12.5-18.5 0

0 0

0 1

0 0

1 0

0 2

18.5-24 0

0 0

1 0

0 0

0 1

>24 0

0 0

1 0

0 0

0 1

TOTAL l1 213 111011 12 0

1 13 121510 1

10101 22 Class All Freg 1.000 mph I

N INNE [ NE I ENEI E

IESE I SE SSE I S ISSW I SW IWSWI W IWNWl NW INNW[ TOTAL Calm-0.95 0

0 0

0.95-3.5 3

0 2

2 3

1 3

2 0

2 2

0 2

3 0

5 30 3.5-7.5 7

8 10 11 10 12 10 6

4 4

8 4

8 10 20 5

137 7.5-12.5 11 13 16 6

9 21 32 19 19 29 50 35 41 54 27 18 400 12.5-18.5 13 16 27 6

13 15 33 34 41 75 79 108 150 140 46 21 817 18.5-24 18 15 31 5

7 14 12 4

12 25 22 48 86 80 69 7

455

>24 62 36 17 3

8 0

24 0

5 1

5 0

9 63 104 33 370 TOTAL 1114 I 88 103 I 33 I 50 6 63 1114 L 65 81 1136 166 1 195 1296 1 350 1266 89 I 2209 Page 66

Table A-2 (continued)

Jan-Dec 2010 Class A Freq 0.099 mp N [NE NE I EE E

ESE SE SSE I S I[SSW SW IWSWv W

[WNWvI NW [NWl TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 0

1 1

0 0

0 2

3.5-7.5 11 22 24 11 8

2 0

0 0

1 5

4 5

5 98 7.5-12.5 33 20 25 14 18 20 12 2

6 1

6 12 16 31 12 17 245 12.5-18.5 23 16 9

6 2

6 15 6

15 32 13 11 29 58 29 13 283 18.5-24 19 8

4 3

2 2

0 0

4 17 2

0 24 44 7

19 155

>24 11 8

3 0

1 0

0 0

0 1

0 0

11 17 12 5

69 TOTAL 197 741 65 35 32 [30 27 [8 25 51 21 [24 85 154 5

59 852 Class B.Freg:

0.640' mph I

IN I NNE I NE ENE I E ESE I E SSE]I

[SSW ISW IWSW]

W IWNWl W I NNWI TOTAL Calm-o.g5 0

0 0

0.95-3.5 0

0 1

0 0

0 1

3.5-7.5 7

6 3

6 7

0 0

2 6

9 2

4 52 7.5-12.5 4

3 4

20 9

2 1

12 9

14 14 11 5

3 118 12.5-18.5 1

3 1

4 4

6 5

3 11 19 12 12 12 10 7

5 115 18.5-24 0

2 2

1 1

3 0

0 0

5 4

0 10 8

5 1

42

>24 4

5 1

0 0

2 0

0 1

3 1

1 18 TOTAL 1616 19 112 14 161291141 5 12 [38 125 28 143 41 1 20 114 346 Class C Freg:

0.057 mph I N NNE NE ENE E

ESE SE SSE I S I[SSW SW IWSWI W

IWNWI NW IvNNW TOTAL Calm-0.95 0

0 0

0.95-3.5 0

0 1

1 0

0 0

2 4

3.5-7.5 5

9 4

5 3

7 0

0 2

2 6

2 2

9 6

6 68 7.5-12.5 3

6 8

5 1

16 15 7

12 14 15 18 15 14 4

2 155 12.5-18.5 2

3 6

7 2

4 5

0 16 27 15 21 25 6

2 5

146 18.5-24 2

4 9

1 1

1 0

0 2

14 10 0

14 11 3

3 75

>24 14 6

0 1

0 0

1 7

9 6

44 TOTAL 26 28 28 120 7 128120 7 132 157 46 141 157 147 124124 492 Class D Frec 0.399 mph IN NNE NE I ENE I E ESE SE SSE S

SSW SW IWSWI W

IWNWl NW NNW I TOTAL Calm-0.95 0

0 0

0

0 0

0 0

0 0.95-3.5 8

13 17 3

1 0

2 0

0 1

0 0

1 1

2 8

57 3.5-7.5 23 14 26 23 32 31 25 21 17 13 9

6 8

20 14 15 297 7.5-12.5 24 24 26 24 29 48 39 49 62 83 63 43 35 40 29 21 639 12.5-18.5 19 16 27 32 31 33 35 22 69 220 127 94 198 135 33 23 1114 18.5-24 25 29 36 33 14 11 12 30 37 113 45 26 87 108 83 24 713

>24 96, 68 26 35 20 1

19 15 8

7 8

0 30 101 117 53 604 TOTAL 195 I 1641 158 150 127 124 [132 137 [193 1437 252 169 1359 1405 [278 144 J 3424 Page 67

Table A-2 (continued)

Jan-Dec 2010 Class E Freg:

0.291 mph I NI NNE NE ENE E ESE SE I SSE I S ISSW ISWI WSW I W I WNW INW NINW I TOTAL Calm-0.95 0

0 0

0.95-3.5 1

7 8

10 7

8 3

4 3

3 5

1 5

4 0

7 76 3.5-7.5 11 13 10 10 24 24 25 13 20 14 6

5 11 6

22 7

221 7.5-12.5 19 16 23 4

18 32 37 46 37 53 32 25 48 55 35 27 507 12.5-18.5 19 11 1

6 7

8 25 62 53 132 114 108 211 143 53 30 983 18.5-24 8

4 6

5 5

15 9

6 5

112 84 39 96 69 36 22 521

>24 9

11 13 18 26 1

6 0

0 17 16 0

4 35 22 6

184 TOTAL 167] 62 [61 I 53 187 1 88 11051 131 1 1181 331 12571 178 1375 1 312 11681 991 2492 C la s s..F..., F re g.

0.0 9 3

.1.,

mph 1

N I NNE INE IENE I__IES SE ISSE S ISSWISWI WSW I W I WVNW IJNW[INNW ITOTAL Calm-0.95 0

0 0

0.95-3.5 2

1 6

1 2

3 3

4 1

1 0

1 1

1 3

2 32 3.5-7.5 4

5 3

2 9

9 10 0

11 6

3 7

9 3

6 7

94 7.5-12.5 9

2 3

2 2

9 23 19 12 15 17 29 27 42 23 14 248 12.5-18.5 6

1 0

2 7

21 14 21 34 33 65 60 23 13 301 18.5-24 1

0 0

7 53 24 9

12 2

4 112

>24 0

1 0

2 0

0 0

3 3

0 0

0 9

TOTAL I 22 10 [12 8 113 23 143 44 138 1 53 11101 94 1111 1 118 1 57 [ 40 1 796 Class G Freg:

0.020 mp

[ N NI NE INE ENE E

ESE SE SSE S

SSW ISW] WSW [ W I WNW NIW NINW I TOTAL Calm-0.95 0

0 0

1 0

0 0

0 1

0.95-3.5 1

2 2

1 4

0 1

1 0

0 2

1 1

1 21 3.5-7.5 4

2 4

0 1

1 2

0 5

5 1

1 2

0 4

2 34 7.5-12.5 0

0 0

1 6

6 5

12 10 7

3 2

52 12.5-18.5 0

0 0

0 1

0 8

7 12 10 1

1 40 18.5-24 0

0 0

0 7

6 2

0 0

0 15

>24 0

0 0

1 5

0 0

0 6

TOTAL

[5 14 6

3I11 31 2[ 16 11131131261 26 1281 18 19 6

169 Class All Freg:

1.000 mp IN I N NE I ENE E

ESE I SE I SSE I S I SSW I SW I WSW I W IWNWINW[NNWI TOTAL Calm-0.95 0

0 0

1 0

0 0

0 1

0.95-3.5 12 23 35 18 13 12 12 8

5 6

5 2

9 7

6 20 193 3.5-7.5 65 71 74 57 84 74 62 34 55 40 25 24 43 51 59 46 864 7.5-12.5 92 71 89 52 72 145 135 126 136 184 147 153 165 200 111 86 1964 12.5-18.5 70 50 44 56 46 59 92 114 179 451 323 286 552 422 148 90 2982 18.5-24 55 47 57 43 23 32 21 36 48 268 205 95 242 252 136 73 1633

>24 134 99 43 56 47 2

25 15 8

31 32 0

47 163 161 71 934 TOTAL I428 361 13421 283 12851 324 13471 333 1431 [

980 17371 560 110581 1095 1621 1 386 1 8571 Page 68

APPENDIX B Results of Onsite Groundwater Monitoring Program In response to the Nuclear Energy Institute (NEI) Groundwater Protection Initiative, Pilgrim Station instituted a groundwater monitoring program during 2007.

Four monitoring wells were installed during the fourth quarter of 2007, and the first samples were collected in late November 2007. All four wells were installed onsite, within the protected area fence. Since these are onsite wells, they are not considered part of the Radiological Environmental Monitoring Program (REMP), and data from these wells are being reported in the annual Radiological Effluent Release Report. Also, there were no leaks or spills of radioactive material at Pilgrim Station during 2010 that could have affected onsite or offsite groundwater Two pre-existing wells were incorporated into the groundwater monitoring program in early 2008.

Monitoring well MW3 is located in the owner-controlled area near Rocky Hill Road, and was added to the program during the first quarter of 2008. Since monitoring well MW3 is located slightly uphill of Pilgrim Station approximately 0.2 mile southwest of the power block, it is upgradient of the PNPS:

power block and outside of natural groundwater flow direction. As such, it is considered to be a control well indicative of baseline levels in the vicinity of Pilgrim Station. Monitoring well MW4 is located-within the protected area near the main transformer, and was added to the program during the 2 nd quarter of 2008 as an additional onsite monitoring well.

In response to recommendations from assessments performed in 2009 by Entergy and NEI, six new monitoring wells were installed within the Pilgrim Station protected area in April 2010 to better characterize groundwater flow characteristics and perform monitoring closer to selected systems, structures and components (SSCs) the contain radioactive material and could lead to groundwater contamination if leaks were to develop. One of the wells MW202-1 was an intermediate-level (45-feet deep) well installed adjacent to MW202 that had been installed in 2007.

Monitoring well MW205 was a 25-ft well installed slightly down-gradient from the Condensate Storage Tanks (CSTs), and MW206 was a 25-ft well installed near the radwaste truck lock. MW207 was a 25-ft well installed on the southwest corner of the power block.

Two additional wells were installed upgradient, approximately 300 yards southeast of the power block; MW208-S was a 25-ft shallow-level well, and was installed adjacent to MW208-I, a 45-ft intermediate level well.

The first samples were collected from these new wells in May-2010, and the radioactivity content was assessed. Analyses of samples from wells MW202-I, MW207, MW208-S, and MW208-1 were consistent with the other wells installed in 2007. Tritium levels in MW205 and MW206 were higher than those observed from the wells installed in 2007, and the sampling frequency was changed from the normal quarterly sampling interval to once per week to obtain more information.

Both wells MW205 and MW206 continued to show wide fluctuations during the summer of 2010, and six additional sampling wells were installed in August 2010.

All six of the wells installed in August were shallow wells, approximately 25-ft in depth. Monitoring well MW209 was installed on the north side of the reactor building truck lock. Monitoring well MW210 was installed immediately adjacent to the condensate storage tank to provide indication of any CST leakage that would be anticipated to move toward MW205, one of the wells indicating higher concentrations.

Monitoring well MW211 was installed on the south side of the reactor building truck lock, in an area that could potentially be affected by storm drain leakage and the underground liquid radwaste discharge line.

MW212 was installed between the underground radwaste discharge line and the intake screenhouse, and was intended to monitor for lateral flow of groundwater at the site. MW213 was installed on the north side of the PNPS Warehouse, and was intended to characterize groundwater on the east side of the plant site.

Finally, MW214 was installed on the north side of the trash compaction facility to characterize groundwater flows along the northeast boundary of the site.

Additional efforts were undertaken to try to identify potential sources of the elevated tritium detected in the monitoring wells. A technical team was assembled to review various systems and processes Page 69

that might influence introduction of tritium into groundwater, and Pilgrim Station has contracted the services of a professional hydrogeological firm to assist in the effort. Samples of roof runoff, storm drain runoff, and accumulated water in manholes were collected and analyzed for tritium, but provided inconclusive results. Soil samples were collected from borings performed in the vicinity of wells MW205 and MW206 to determine the possibility of "pockets" of tritium that might be suspended above the water table that could lead to "spikes" of tritium as precipitation percolated through the soil. These results also proved inconclusive, as no detectable tritium was detected in the soil samples. A dye tracer study was conducted in January 2011 on four underground systems to detect any potential for leakage in these systems that might carry tritium to the monitoring wells.

However, due to slow rate of water movement through the soil (approximately 6-inches/day), it may take several months for dye to migrate from the underground systems to the monitoring wells.

Despite the extensive efforts to date, no likely candidates for the sources of tritium in the groundwater have been identified.

All samples collected were analyzed for tritium, a radioactive isotope of hydrogen, and well as for gamma emitting. radionuclides and hard-to-detect beta emitting nuclides.

In accordance with

-,industry practice established under the NEI initiative, lower limits of detection (LLDs) used for analysis of REMP samples were used when assessing these samples for the presence of radioactivity.

Tritium was the only radionuclide detected in the samples that is attributed to operations of Pilgrim Station. No plant-related gamma emitting radionuclides or hard-to-detect beta emitting radioactivity was detected in any of the samples.

Naturally-occurring radioactivity was detected in the samples. Such levels of natural radioactivity are expected as these radionuclides are dissolved into the groundwater from the rocks and soil.

The fact that these low levels of naturally-occurring radioactivity can be detected demonstrated the ability of the gamma spectroscopy analyses to detect radioactivity in groundwater. If any plant-related gamma activity was contained in the groundwater, the analytical techniques used would be able to detect them.

Results of the tritium analyses are presented in the following tables.

In these tables, a value of "NDA < xx" in the columns indicates that no activity was detected in the sample when analyzed to the minimum-detectable level following the "<" sign.

For example, the sample collected from MW202-1 on 11-Jun-2010 contained no detectable tritium, and a minimum detectable concentration of 404 pCi/L was achieved on that sample. The achieved sensitivity of 404 pCi/L is well below the required REMP LLD of 3000 pCi/L, and no tritium was detected even when counted to this more sensitive level of detection.

Analyses for hard-to-detect nuclides, such as iron-55 (Fe-55), nickel-63 (Ni-63), strontium-89 (Sr-89), strontium-90 (Sr-90), and gross alpha were performed on the samples collected during the fourth quarter of 2007 and the first quarter of 2008. Analyses for these hard-to-detect radionuclides were also performed on initial samples collected from all of the new wells installed during 2010.

Since no plant-related gamma activity and no Fe-55, Ni-63, Sr-89, or Sr-90 was detected in any of these samples, further analyses for these hard-to-detect nuclides will not be performed unless there is a significant increase in tritium levels, or if plant-related gamma activity is detected.

Low levels of tritium, a radioactive isotope of hydrogen, were detected in the onsite wells. Although gamma spectroscopy and gross alpha analyses indicated the presence of naturally-occurring radioactivity, such as potassium-40 and radon daughters from the uranium/thorium decay chains, there was no indication of any plant-related radioactivity in the samples, other than tritium.

Concentrations of tritium detected in the onsite wells ranged from non-detectable at less than 295 pCi/L, up to a maximum concentration of 25,552 pCi/L. The average concentrations from these onsite wells are well below the voluntary communication reporting level of 20,000 pCi/L as established by the EPA Drinking Water Standard. Although the EPA Standard provides a baseline for comparison, no drinking water sources are affected by this tritium.

All of the affected wells are onsite, and the general groundwater flow pathway is under Pilgrim Station and out into the salt water of Cape Cod Bay. As such, there is no potential to influence any off-site drinking water wells.

Even if worst-case assumptions were made and the water from monitoring well MW-205 (average Page 70

concentration = 9550 pCi/L) was consumed as drinking water, the maximum dose consequence would be less than 0.87 mrem/yr. In actuality, any dose consequence would be much less than this, as any tritium-laden water potentially leaving the site would be diluted into the seawater of Cape Cod Bay before being incorporated into any ingestion pathways.

No drinking water ingestion pathway exists.

The following tables list the tritium concentrations observed in the samples collected from the monitoring wells during 2010.

Sample Tritium Concentration by Monitoring Well - pCi/Liter Value +/- 1-sigma uncertainty Date MW201 MW202 MW202-1 MW203 MW204 MW205 02-Mar-2010 1180+/-110 1040+/-110 900+/-110 930+/-110 17-May-2010 910 130 900 +/-130 930 +/- 130 1060 +/-130 1230 +/-130 5810 +/- 160 11-Jun-2010 589 +/-127 NDA<404 8632 +/- 191 21-Jun-2010 660 128 529 +/- 126 11072 +/- 207 30-Jun-2010 499 +/-126 520 +/- 127 8477 +/-190 07-Jul-2010 718 +/-127 553 +/-126 471 +/- 125 447 +/-124 759 +/-128 25552 +/-282 15-Jul-2010 589 +/- 68.5 425 +/- 64.5 6870 +/- 79.0 22-Jul-2010 731 +/-222 390 +/-209 473 +/-212 12600 +/-495 26-Jul-2010 932 +/-156 580 +/-133 408 +/-121 10800.+/- 449 02-Aug-2010 576 +/- 163 579 +/- 164 NDA<460 NDA<465 794 +/- 170 17800 +/- 493 09-Aug-2010 961 +/-125 349 +/-107 390 +/-109 480 +/- 111 578 +/-114 12700 +/- 304 17-Aug-2010 1090 +/-126 371 +/- 108 NDA<322 712 +/-137 805 +/-141 7840 +/-233 26-Aug-2010 873+/-123 364+/-113 485+/-116 423+/-114 383+/-114 7960+/-264 30-Aug-2010 974 +/- 137 NDA<364 NDA<364 NDA<360 403 +/- 125 1390 +/- 148 07-Sep-2010 1200+/-137 352+/-112 417+/-101 375+/-101 455+/-116 3010+/-180 13-Sep-2010 1510 +/-167 461 +/-126 652 +/-134 NDA<380 415 +/-129 1840 +/-177 20-Sep-2010 1340 +/- 134 NDA<314 341 +/- 107 NDA<394 NDA<394 22000 +/- 398 27-Sep-201 0 958 +/- 143 400 +/- 126 522 +/- 130 NDA<364 596 +/- 113 25000 +/- 484 04-Oct-2010 1140 +/-124 17300 +/-332 12-Oct-2010 1040+/- 143 NDA<373 NDA<388 NDA<347 646+/- 124 1760 +/-157 18-Oct-2010 966+/- 129 5890 +/-228 25-Oct-2010 1340 +/- 160 NDA<390 NDA<390 NDA<322 532 +/- 112 2840 +/- 194 01-Nov-2010 1020 +/- 121 16700 +/-356 15-Nov-201 0 909 +/- 144 NDA<383 NDA<353 NDA<320 529 +/- 113 5730 +/- 259 22-Nov-2010 1290 +/-129 1810 +/- 141 29-Nov-201 0 1060 +/- 153 NDA<382 NDA<385 NDA<397 526 +/- 114 1960 +/- 177 09-Dec-2010 1150 +/-182 2300 +/-225 14-Dec-2010 781 +/-148 579 +/-139 486 +/-144 NDA<372 503 +/- 141 17800 +/- 532 29-Dec-2010 1190 +/- 171 579 +/-147 556 +/-146 NDA<356 372 +/- 118 3930 +/- 199 Page 71

Sample 1

Tritium Concentration by Monitoring Well - pCi/Liter Value +/- 1-sigma uncertainty Date MW206 MW207 MW208-S MW208-1 MW209 MW21 0 02-Mar-20 10 17-May-2010 1470 +/- 130 1090 130 630 +/- 130 380 +/- 120 11 -Jun-201 0 21-Jun-2010 30-Jun-201 0 07-Jul-2010 3352 +/- 151 488 +/- 125 NDA<402 NDA<402 15-Jul-2010 22-Jul-2010 1520 +/- 251 26-Jul-2010 2030 +/- 213 02-Aug-2010 1380 +/- 190 512 +/- 160 NDA<477 NDA<457 09-Aug-2010 4550 +/- 198 394 108 381 +/- 108 NDA<315 177Aug-201.0 5370 +/- 201 701 +/- 137 NDA<410 NDA<412 26-Aug-201 0 10500 +/- 243 453 +/- 116 NDA<303 NDA<348 2940 +/- 159 1280 +/- 131 30-Aug-2010 2790 +/- 177 421 +/- 112 NDA<322 NDA<357 1780 +/- 158 NDA<362 07-Sep-2010 3190 +/- 183 329 +/-112 NDA<295 NDA<304 1560 +/- 145 589 +/- 105 13-Sep-2010 6830 +/- 295 NDA<379 NDA<376 NDA<378 1590 +/- 168 641 +/- 134 20-Sep-2010 8290 +/- 242 NDA<394 NDA<390 NDA<394 1390 +/- 131 1020 +/- 123 27-Sep-2010 5040 +/-238 519 +/- 130 NDA<312 413 +/- 126 1760 +/- 168 816 +/-140 04-Oct-201 0 8210 +/- 239 12-Oct-2010 10100 +/-273 NDA<346 NDA<347 NDA<345 1440 +/- 151 610 +/-134 18-Oct-2010 5950 +/- 229 25-Oct-2010 12200 +/-343 NDA<321 NDA<320 NDA<321 1710 +/- 169 837 145 01-Nov-2010 13600 +/-324 15-Nov-2010 9250 +/-306 NDA<318 NDA<328 NDA<320 1830 +/- 171 1230 +/-155 22-Nov-2010 4720 +/- 190 29-Nov-201 0 5290 +/- 246 NDA<398 NDA<317 NDA<399 1550 +/- 166 NDA<385 09-Dec-2010 5270 +/- 225 14-Dec-201 0 10300 +/- 413 NDA<360 NDA<365 NDA<370 1940 +/- 208 1090 +/- 168 29-Dec-201 0 8950 +/- 353 NDA<350 NDA<365 NDA<340 1870 +/- 194 930 +/- 161 Page 72

Sample Tritium Concentration by Monitoring Well - pCi/Liter Value +/- 1-sigma uncertainty Date MW.11 MW212 MW213 MW214 MW3 MW4 02-Mar-201 0 360 +/- 100 590 +/- 100 17-May-201 0 500 +/- 130 830 +/- 120 11-Jun-2010 21 -Jun-201 0 30-Jun-201 0 07-Jul-2010 NDA<402 568 +/- 126 15-Jul-2010 22-Jul-201 0 26-Jul-2010 02-Aug-201 0 NDA<460 504 +/- 162 09-Aug-2010 NDA<313 491 +/- 111 17-Aug-2010 NDA<397 759 +/- 134 26-Aug-201 0 1540 +/-136 514 +/-117 NDA<346 NDA<345 NDA<345 557 +/- 116 30-Aug-2010, '1340 148 385 +/- 122 NDA<361 NDA<364 NDA-<320.

573 +/- 116 07-Sep-2010 1570 146 655 +/- 122 341 +/- 99 NDA<297 NDA<331 662 +/- 122 13-Sep-2010 1730 +/- 173 618 +/- 133 NDA<378 NDA<380 NDA<377 398 +/- 129 20-Sep-201 0 1200 +/- 127 462 +/- 110 NDA<420 NDA<396 NDA<395 493 +/- 128 27-Sep-2010 1090 +/-148 513 +/- 111 438 +/- 122 NDA<313 400 +/- 133 645 +/- 114 04-Oct-20 10 12-Oct-2010 1180 146 455 +/- 129 415 +/- 118 NDA<344 NDA<345 466 +/- 118 18-Oct-20 10 25-Oct-2010 870 +/- 146 568 +/- 137 NDA<321 NDA<318 NDA<321 556 +/- 113 01-Nov-2010 15-Nov-2010 1050 +/-150 745 +/- 118 NDA<312 NDA<302 NDA<305 491 +/- 107 22-Nov-20 10 29-Nov-2010 717 +/-142 533 +/- 136 NDA<398 NDA<318 NDA<317 607 +/- 117 09-Dec-201 0 14-Dec-2010 1250 +/- 181 620 +/- 146 NDA<353 NDA<368 534 +/- 143 740 +/- 156 29-Dec-2010 1110 +/- 136 830 +/- 157 NDA<334 NDA<282 NDA<358 NDA<347 Although there are no indications that the groundwater containing low concentrations of tritium is actually migrating offsite, a bounding calculation was performed to assess the potential dose impact of such a scenario. Based on the tritium concentrations detected during 2010, the annual average concentrations of tritium in groundwater in the four monitoring wells most closely adjacent to the shoreline (MW204, MW205, MW202, and MW201) were used to estimate tritium migration into the intake bay. Hydrological characteristics of the compacted backfill in the vicinity of these wells were measured in 2010 and indicate the hydraulic conductivity to 0.002 cm/sec to about 0.0006 cm/sec.

When coupled with the hydraulic slope of 0.014 and average porosity of 0.3, the flow velocity was calculated as being between 0.08 and 0.23 meters per day. Using an assumed horizontal shoreline interface area 236 meters long by 3 meters deep that could potentially transmit groundwater into the intake bay, the annual discharge of groundwater would be about 12.5 million Liters of water per year. Assuming this volume of 12.5 million liters contained the average concentration of 2380 pCi/L, the annual discharge of tritium into the intake bay under this hypothetical scenario would be 0.0297 Curies. This activity represents less than 0.07% of the annual airborne effluent of tritium released from the reactor building vent (see Table 2.2-C). Such airborne effluents can be washed down to the ground surface during precipitation events and infiltrate into the ground, thereby introducing tritium into the groundwater.

In the hypothetical scenario described above, the 0.0297 Curies of tritium entering the intake bay would be further diluted into the circulating water flow of the plant. As documented in Table 2.3-A, the total volume of circulating water flow during 2010 was 615 billion Liters, yielding an effective concentration of tritium in the intake bay of about 0.048 pCi/L. Such a concentration would be well Page 73

below the detection sensitivity of about 450 pCi/L used to analyze water collected from the discharge canal as part of the radiological environmental monitoring program (REMP).

The calculated dose to the maximum-exposed member of the public from such a hypothetical release would be 0.000000027 millirem, resulting from tritium incorporated into fish and shellfish. Since the tritium would be incorporated into seawater, there is no drinking water ingestion pathway in the described scenario.

The following table lists the hydrological characteristics in the vicinity of each of the monitoring wells used to estimate tritium migration. Predicted flow velocities, annual tritium concentrations, and hypothetical tritium discharges are listed represented by each monitoring well.

discharge volumes, average for each shoreline segment Shoreline Segment Number 1-2 3

4 Monitoring Well Number MW204 MW205 MW202 MW201 Hydraulic Conductivity - cm/sec 1.99E-03 4.27E-03 3.13E-03 5.64E-03 Hydraulic Slope 0.014 0.014 0.014 0.014 Porosity 0.300 0.300 0.300 0.300 Flow Velocity - m/day 8.02E-02 1.72E-01 1.26E-01 2.27E-01 Flow Velocity - ft/yr 9.61 E+01 2.06E+02 1.51 E+02 2.72E+02 Length of Shoreline Segment - m 61.0 38.1 45.7 91.4 Thickness of Water Layer - m 3.0 3.0 3.0 3.0 Volumetric Discharge - m3/day 4.40E+00 5.90E+00 5.19E+00 1.87E+01 Volumetric Discharge - Liter/yr 1.61 E+06 2.16E+06 1.90E+06 6.84E+06 Annual Average H-3 Concentration - pCi/L 6.30E+02 9.55E+03 5.46E+02 1.03E+03 Annual Segment Tritium Discharge - Ci/yr 1.01 E-03 2.06E-02 1.04E-03 7.06E-03 Total Volumetric Discharge - L/yr 1.25E+07 Total H-3 Discharge - Ci/yr 2.97E-02 Annual Circulating Water Flow - Liter/yr 6.15E+11 Discharge Canal H-3 Concentration - Ci/L 4.83E-14 Discharge Canal H-3 Concentration - pCi/L 4.83E-02 Max. Indiv. Dose Factor - mrem/yr per Ci/L 5.73E+05 Maximum Individual Dose - mrem/yr 2.77E-08 In conclusion, there were no known leaks or spills of radioactive material at Pilgrim Station during 2010 that could have affected onsite or offsite groundwater. The only radionuclide detected in groundwater during the 2010 monitoring effort that is attributable to Pilgrim Station operations is tritium, and all concentrations were well below any reporting criteria established in the Pilgrim Station Offsite Dose Calculation Manual and through EPA safe drinking water standards.

Page 74

APPENDIX C CORRECTIONS TO PREVIOUS EFFLUENT REPORTS Some minor discrepancies were identified in Effluent Release Reports issued in 2008 and 2009.

These discrepancies are addressed below.

D.1 Correction to Table 4.3-A from 2009 Effluent Report The first discrepancy involved confusing wording preceding Table 4.3-A depicting the doses from liquid effluent discharges during the first calendar quarter of 2009. A statement preceding the table of values indicated that "No Liquid Discharges Occurred During This Period". The table correctly reflected the dose consequence from a single discharge which was performed during that quarter, and the doses were correctly characterized in Section 6.2 of the 2009 Report where comparisons were made to ODCM limits. The corrected table is presented below:

Table 4.3-A Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jan-Mar 2009 Age Class Organ Dose - mrem

Organ Adult Teen Child Bone 1.70E-06 2.15E-06 1.74E-06 GI-LLI 1.67E-06 1.74E-06 5.36E-07 Kidney 5.28E-07 1.17E-06 5.02E-07 Liver 1.32E-06 1.96E-06 1.24E-06 Lung 2.72E-07 9.28E-07 2.85E-07 Thyroid 1.60E-07 7.95E-07 1.76E-07 T.Body 1.20E-06 1.47E-06 6.54E-07

These doses are conservative since the same usage factor was applied for each quarter.

In reality, it is unlikely that anyone would be swimming or boating during the entire year.

However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose.

D.2 Correction to Appendix C of 2008 Report Regarding Groundwater Tritium Calculations were performed regarding the hypothetical release of groundwater containing tritium into the PNPS intake bay due to normal groundwater flow gradient. In the calculations performed in 2008, the estimation of groundwater discharge into the bay did not properly account for the groundwater hydraulic slope and the soil porosity. In the 2008 report, the estimation erroneously assumed the groundwater flow velocity when calculating the total discharge was equal to the hydraulic conductivity of 0.019 cm/sec, resulting in a flow velocity of 16.4 meters/day.

When additional wells were installed in 2010 and additional soil and groundwater physical parameters were collected, the error was identified in the groundwater discharge calculation.

The correct calculation for groundwater discharge incorporates hydraulic conductivity, soil porosity, and groundwater hydraulic slope. The correct calculation of groundwater flow velocity is the product of the hydraulic conductivity multiplied by the hydraulic slope and divided by the soil porosity.

Page 75

Testing of new monitoring wells installed in 2010 indicated an average soil hydraulic conductivity value of 0.00376 cm/sec, a hydraulic slope of 0.014, and a porosity value of 0.3. Therefore, the correct groundwater flow velocity is estimated as:

0.00376 cm/sec

0.014 + 0.3 = 0.000176 cm/sec, or 0.152 meters/day This value is considerably lower than the value of 16.41 meters/day assumed in the 2008 calculations. When corrected for the proper groundwater flow velocity, the total hypothetical volume of groundwater discharged into the intake bay would be 55 million liters of water, as opposed to the original estimate of 6 billion liters. When the corrected volume of 55 million liters/year is multiplied by the average tritium concentration of 947 pCi/L, the hypothetical discharge of tritium into the intake bay would be 0.052 Curies, as opposed to the original estimate of 5.7 Curies. The resulting dose impact from discharging 0.052 Curies would be 4.84E-8 millirem.

The corrected wording for the 2008 report is shown below, with applicable changes denoted in bold text:

Although there are no indications that the groundwater containing low concentrations of tritium is actually migrating offsite, a bounding calculation was performed to assess the potential dose impact of such a scenario. Based on the tritium concentrations detected during 2008, the annual average concentration of tritium in groundwater in the vicinity of the onsite shorefront of the protected area would be 947 pCAiL.

Hydrological characteristics of the compacted backfill onsite indicate the hydraulic conductivity to be about 0.00376 cm/sec, resulting in a groundwater flow velocity of about 0. 152 meters per day. When coupled with an assumed horizontal interface area 200 meters long by 5 meters deep that could potentially transmit groundwater into the intake bay, the annual discharge of groundwater would be about 55 million Liters of water per year. Assuming this volume of 55 million liters contained the average concentration of 947 pCi/L, the annual discharge of tritium into the intake bay under this hypothetical scenario would be 0.052 Curies. This activity represents less than 0.1% of the annual airborne effluent of tritium released from the reactor building vent (see Table 2.2-C). Such airborne effluents can be washed down to the ground surface during precipitation events and infiltrate into the ground, thereby introducing tritium into the groundwater.

In the hypothetical scenario described above, the 0.052 Curies of tritium entering the intake bay would be further diluted into the circulating water flow of the plant. As documented in Table 2.3-A, the total volume of circulating water flow during 2008 was 615 billion Liters, yielding an effective concentration of tritium in the intake bay of about 0.085 pCi/L. Such a concentration would be well below the detection sensitivity of about 450 pCi/L used to analyze water collected from the discharge canal as part of the radiological environmental monitoring program (REMP).

The calculated dose to the maximum-exposed member of the public from such a hypothetical release would be 4.84E-8 millirem, resulting from tritium incorporated into fish and shellfish. Since the tritium would be incorporated into seawater, there is no drinking water ingestion pathway in the described scenario.

D.3 Correction to Appendix B of 2009 Report Regardinq Groundwater Tritium The same issues identified in the previous section also applied to the 2009 estimation of groundwater discharge into the intake bay.

The correct flow velocity of 0.052 meters/day is considerably lower than the value of 16.4 meters/day assumed in the 2009 calculations. When corrected for the proper groundwater flow velocity, the total hypothetical volume of groundwater discharged into the intake bay would be 55 million liters of water, as opposed to the original estimate of 6 billion liters. When the corrected volume of 55 million liters/year is multiplied by the average tritium concentration of 890 pCi/L, the hypothetical discharge of tritium into the intake bay would be 0.049 Curies, as opposed to the original estimate of 5.3 Curies. The resulting dose impact from discharging 0.049 Curies would be 4.90E-8 millirem.

Page 76

The corrected wording for the 2009 report is shown below, with applicable changes denoted in bold text:

Although there are no indications that the groundwater containing low concentrations of tritium is actually migrating offsite, a bounding calculation was performed to assess the potential dose impact of such a scenario. Based on the tritium concentrations detected during 2009, the annual average concentration of tritium in groundwater in the vicinity of the onsite shorefront of the protected area would be 890 pCi/L.

Hydrological characteristics of the compacted backfill onsite indicate the hydraulic conductivity to be about 0.00376 cm/sec, resulting in a groundwater flow velocity of about 0. 152 meters per day. When coupled with an assumed horizontal interface area 200 meters long by 5 meters deep that could potentially transmit groundwater into the intake bay, the annual discharge of groundwater would be about 55 million Liters of water per year. Assuming this volume of 55 million liters contained the average concentration of 890 pCi/L, the annual discharge of tritium into the intake bay under this hypothetical scenario would be 0.049 Curies. This activity represents less than 0.1% of the annual airborne effluent of tritium released from the reactor building vent. (see Table 2.2-C). Such airborne effluents can be washed down to the ground surface during precipitation events and infiltrate into the ground, thereby introducing tritium into the groundwater.

In the hypothetical scenario described above, the 0.049 Curies of tritium entering the intake bay would be further diluted into the circulating water flow of the plant. As documented in Table 2.3-A, the total volume of circulating water flow during 2009 was 571 billion Liters, yielding an effective concentration of tritium in the intake bay of about 0.085 pCi/L. Such a concentration would be well below the detection sensitivity of about 450 pCi/L used to analyze water collected from the discharge canal as part of the radiological environmental monitoring program (REMP).

The calculated dose to the maximum-exposed member of the public from such a hypothetical release would be 0.000000049 millirem, resulting from tritium incorporated into fish and shellfish. Since the tritium would be incorporated into seawater, there is no drinking water ingestion pathway in the described scenario.

Page 77

APPENDIX D CHANGES TO PNPS OFFSITE DOSE CALCULATION MANUAL No revisions were made to the PNPS Offsite Dose Calculation Manual (ODCM) during calendar year 2010.

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