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Annual Radioactive Effluent Release Report for January 1 Through December 31, 2013
	ML14241A018
Person / Time
Site:	Pilgrim
Issue date:	05/15/2014
From:	Jeffery Lynch; Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	2.14.039
	Download: ML14241A018 (78)
	v • d • e

S'Entergy Entergy Nuclear Operations, Inc.

600 Rocky Hill Road Plymouth, MA 02360 Pilgrim Nuclear Power Station May 15, 2014 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

'

SUBJECT:

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Docket No.: 50-293 License No.: DPR-35.

Annual Radioactive.Effluent Release Report for January 1 through .December 31,,2013 LETTER NUMBER: 2.14.039

Dear Sir or Madam:

In accordance with Pilgrim Technical Specification 5.6.3, Entergy Nuclear Operations,; Inc submits the attached Annual Radioactive Effluent Release Report for January 1, 2013 through December 31, 2013.

This letter contains no commitments.

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

,8403.

Sincerely, Joseph R Lynch i Manager, Regulatory'Assurance

Attachment:

Pilgrim Annual Radioactive Effluent Release Report for January 1, 2013 through December 31, 2013 cc: U.S. Nucl:ear Regulatory Commission Ms. Nadiya.h Morgan, P.roje ct Manager Region 1 Division of Operating Reactor Licensing 2100 Renaissance- Blvd, .Suite 100 Office of Nuýlear: Reýctor Regulation King of Prussia, PA 19406-2713.. U.Sr.Nuclea Regulatory.Commission Mail..Stop- O-8-F2, .

11555 Rockvil e Pike; USNRC Senior Resident- Inspector Pilgrim Nuclear.Power Station' Rockvill, MM`2852

. .. .....: . .,* .

." . "8

Attachment I Letter Number 2.14.039 Pilgrim Annual Radioactive Effluent Release Report for January 1, 2013 through December 31, 2013

PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 Annual Radioactive Effluent Release Report January 1 through December 31, 2013

En tergy PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2013 Prepared by: A,-

K.-J.

6/ýora C -

onl- mxv -270W, SeniVr HP/Chemistry Specialist Reviewed by

..Blanlkenbil~ler.. -*--.,

Chemistry Manager Reviewed by ad1tioBroewer Radiation Protection Manager Page 2

'M Gok,;,

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report January-December 2013 TABLE OF CONTENTS SECTION SECTION TITLE PAGE 1.0 EXECUTIVE

SUMMARY

5 2.0 RADIOACTIVE EFFLUENT DATA 8 2.1 Supplemental Effluent. Release Data 8 2.2 Gaseous Effluent Data 8 2.3 Liquid Effluent Data 9 3.0 METEOROLOGICAL DATA 19 4.0 MAXIMUM INDIVIDUAL DOSES 20 4.1 Doses From Noble Gas Releases 20

4.2 Doses From Gaseous Effluent Releases 22 4.3 Doses From Liquid Effluent Releases 28 5.0 OFFSITE AMBIENT RADIATION MEASUREMENTS 34 6.0 PERCENT OF oDCM EFFLUENT CONTROL LIMITS 37 6.1 Gaseous Effluent Releases 37 6.2 Liquid Effluent Releases 40 7.0 RADIOACTIVE WASTE DISPOSAL DATA 43 8.0 OFFSITE DOSE CALCULATION MANUAL REVISIONS 45 9.0 PROCESS CONTROL PROGRAM REVISIONS 46

10.0 REFERENCES

47 APPENDIX A Meteorological Joint Frequency Distributions 48 APPENDIX B Onsite Groundwater Monitoring Program 69 APPENDIX C Corrections to Previous Effluent Reports 75 APPENDIX D Changes to PNPS Offsite Dose Calculation Manual 76

.Page 3

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Jan-Dec 2013 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 2013 21 4.2-A Maximum Individual Organ Doses from Gaseous Effluents 23 Jan-Mar 2013 4.2-B Maximum Individual Organ Doses from Gaseous Effluents 24 Apr-Jun 2013 4.2-C Maximum Individual Organ Doses from Gaseous Effluents 25 Jul-Sep 2013 4.2-D Maximum Individual Organ Doses from Gaseous Effluents 26 Oct-Dec 2013 4.2-E Maximum Individual Organ Doses from Gaseous Effluents 27 Jan-Dec 2013 4.3-A Maximum Individual Organ Doses from Liquid Effluents 29 Jan-Mar 2013 4.3-B Maximum Individual Organ Doses from Liquid Effluents 30 Apr-Jun 2013 4.3-C Maximum Individual Organ Doses from Liquid Effluents 31 Jul-Sep 2013 4.3-D Maximum Individual Organ Doses from Liquid Effluents 32 Oct-Dec 2013 4.3-E Maximum Individual Organ Doses from Liquid Effluents' 33 Jan-Dec 2013 5.0 Average TLD Exposures by Distance Zone During 2013 36 6.1 Percent of ODCM Effluent Control Limits for Gaseous Effluent 38 Releases During 2013 6.2 Percent of ODCM Effluent Control Limits for Liquid Effluent Releases 41 During 2013 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 31,2013 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, 2013. 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". This document has been prepared in accordance with the requirements of PNPS Technical Specifications section 5.6.3.

The quantity of radioactive material released from PNPS was determined from sample analyses and continuous 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 0.29 Curies. Releases of radioactive iodines and particulates with half-life of greater than 8 days totaled 0.0027 Curies, tritium releases totaled 64 Curies, and carbon-14 totaled 6.3 Curies. No gross alpha radioactivity was detected in gaseous effluents.

Noble gases released in gaseous effluents resulted in a maximum total body dose of 0.0000021 mrem, with a corresponding skin dose of 0.0000049 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 0.032 mrem. The maximum hypothetical dose to any organ from radioactive particulates, iodines, tritium, and carbon-14 was about 0.066 mrem. The maximum, hypothetical total body dose from the combined release of all airborne radioactivity in gaseous effluents was 0.032 mrem.

The maximum individual doses from gaseous radioactive effluents were compared to the-applicable ODCM dose limits. Noble gas doses were less than 0.000065% of the corresponding 1OCFR50 dose objectives. Maximum doses resulting from releases of particulates, iodines, tritium, and carbon-14 in gaseous effluents were less than 0.44% 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.

Twenty-one discharges of liquid effluents containing, radioactivity occurred during the reporting period. These discharges contained 6.2 Curies of tritium, and 0.019 Curies of fission and activation products. The resulting maximum total body dose was 0.0027 mrem, with a corresponding organ dose of 0.0096 mrem. All doses from liquid discharges were less than 0.25%

of corresponding 10CFR50 objectives.

METEOROLOGICAL DATA Meteorological joint frequency distributions are listed in Appendix A. Data recovery for the entire annual period was 89.8% for the 33-ft and 89.8% for the 220-ft levels of the tower. The predominant wind direction was from the south-southwest, which occurred approximately 16% of the time during the reporting period. The predominant stability class was Class D, which occurred about 47% 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 0.9 mrem during 2013. There was no measurable increase during 2013 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-bome radioactivity, and ambient radiation exposure resulting from PNPS operation during 2013 was calculated as being about 0.46 mrem. This amount is about 0.13% 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 1159 cubic meters of solid waste, containing almost 82 Curies of radioactivity, were shipped during the reporting period.

Page 6

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. Additional sampling wells were added in 2010, 2011, 2012, and 2013. As of the end of 2013, samples are being collected from a total of 22 monitoring wells. Low levels of tritium, a radioactive isotope of hydrogen, were detected in several of these onsite wells. No other plant-related radioactivity was detected in the groundwater samples. Concentrations of tritium ranged from non-detectable at less than 337 picoCuries per Liter up to 69,000 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 2013, 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: 0.29 Ci, 0.0092 J4Ci/sec lIodines and particulates with 0.0027 Ci, 0.000084 !.Ci/sec

'half-life greater than 8 days 0 Tritium: 64.0 Ci, 2.03 p.Ci/sec

Carbon-14: 6.3 Ci, 0.20 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 1OCFR50 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 for 2013 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 five 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:

0 Total Effluent Volume: 1,180,000 Liters

Total Dilution Volume: 565 billion Liters 0 Fission/Activation products: 0.0189 Ci, 0.0000000000336 lLCi/mL

Tritium: 6.21 Ci, 0.0000000110 IRCi/mL

Dissolved/entrained noble gases: 0.00 Ci, 0.00 RiCi/mL Page 9

Table 2.1 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Supplemental Information January-December 2013 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. Iodines: 10CFR20 Appendix B Table II

c. Particulates with half-life > 8 days: IOCFR20 Appendix B Table II

d. Liquid effluents: 2E-04 .LCi/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 2013 2013 2013 2013 2013

a. Liquid Effluents

1. Total number of releases: 5.OOE+00 1.20E+01 N/A 4.OOE+00 2.10E+01

2. Total time period (minutes): 6.29E+02 1.18E+03 N/A 2.36E+03 4.16E+03

3. Maximum time period 1.70E+02 1.22E+02 N/A 6.35E+02 6.35E+02 (minutes):

4. Average time period (minutes): 1.26E+02 9.81 E+01 N/A 5.89E+02 2.71 E+02

5. Minimum time period (minutes): 9.90E+01 7.50E+01 N/A 5.20E+02 7.50E+01

6. Average stream flow during periods of release of efflueintpeintosa lowingest1.20E+06 9.39E+05 N/A 1.17E+06 effluents into a flowing stream 1.11E+06 (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 2013 Est.

RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Total 2013 2013 2013 2013 2013 Error A. FISSION AND ACTIVATION GASES Total Release: Ci 0.00E+00 0.00E+00 J 2.91E-01 0.00E+00 2.91 E-01 I Average Release Rate: jiCi/sec 0.OOE+00 0.00E+00 3.69E-02 0.00E+00 9.23E-03 j +/-22%

Percent of Effluent Control Limit* _ * * *

B. IODINE-131 Total Iodine-131 Release: Ci 1.84E-04 9.29E-05 5.91E-05 1.71E-04 [.08E-04 Average Release Rate: +/-Ci/sec 2.34E-05 1.18E-05 7.50E-06 2.17E-05 1.61E-05 +/-20%

Percent of Effluent Control Limit* * ....

C. PARTICULATES WITH HALF-LIVES > 8 DAYS Total Release: Ci 2.78E-04 1.72E-04 5.50E-05 1.62E-04 6.67E-04 Average Release Rate: MCi/sec 3.53E-05 2.18E-05 6.97E-06 2.05E-05 2.12E-05 Percent of Effluent Control Limit .. +/-21%

Gross Alpha Radioactivity: Ci NDA NDA NDA NDA NDA D. TRITIUM Total Release: Ci 6.24E+00 6.44E+-00 2.34E+01 2.79E+01 6.40E+01 I Average Release Rate: pCi/sec 7.91E-01 8.17E-01 2.97E+00 3.53E+00 2.03E+00 1 +/-20%

Percent of Effluent Control Limit* _ ....

E. CARBON-14 Total Release: Ci 1.51E+00 9.73E-01 1.90E+00 1.87E+00 6.26E+00 1 Average Release Rate: itCi/sec 1.91 E-01 1.23E-01 2.41 E-01 2.38E-01 1.98E-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 6 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 i.LCiicc.

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 2013 CONTINUOUS MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released I Jan-Mar 2013 Apr-Jun 2013 Jul-Sep 2013 Oct-Dec 2013 Jan-Dec 2013

1. FISSION AND ACTIVATION GASES: Ci Ar-41 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kr-85 0.00E+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 0.00E+00 0.00E+00 0.OOE+00 Kr-88 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-131m O.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 Xe-133 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-133m 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Xe-135 f* 0.OOE+00 0.OOE+00 2.91E-01 0.00E+00 2.91E-01 Xe-135m O.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 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Total for Period 0.OOE+00 0.00E+00 2.91 E-01 0.OOE+00 2.91 E-01

2. IODINES: CI 1-131 1.24E-05 1.52E-06 4.34E-06 3.90E-06 2.21 E-05 1-133 1.14E-05 0.OOE+00 0.OOE+00 0.00E+00 1.14E-05 Total for Period 2.38E-05 1.52E-06 4.34E-06 3.90E-06 3.35E-05

3. PARTICULATES WITH HALF-LIVES > 8 DAYS: Ci Cr-51 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Mn-54 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Fe-59 0.OOE+00 0.00E+00 0.OOE+00 0.O0E+00 0.OOE+00 Co-58 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.OOE+00 Co-60 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zn-65 0.O0E+00 0.O0E+00 0.OOE+00 0.OOE+00 0.O0E+00 Sr-89 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Sr-90 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ru- 103 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-134 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Cs-137 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba/La-140 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 Total for Period 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

4. TRITIUM: Ci H-3 1.53E-02 2.97E-02 5.30E-02 3.77E-02 1.36E-01

5. CARBON-14: Ci C-14 I1.46E+00 9.43E-01 I1.85E+00 I1.82E*00 I6.07E+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: 1E-04 pCi/cc lodines: 1 E-12 ipCi/cc Particulates: 1E-11 liCi/cc Page 12

Table 2.2-8 (continued)

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents.- Elevated Release January-December 2013 BATCH MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released I Jan-Mar 2013 Apr-Jun 2013 Jul-Sep 2013 Oct-Dec2013 Jan-Dec 2013

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-137 N/A N/A N/A N/A N/A Xe-138 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-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 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 radionudides listed as NDA are as follows:

' Fission Gases: 1E-04 pCi/cc lodines: 1E-12 PCi/cc Particulates: 1E- 11 ý.Ci/cc Page 13

Table 2.2-C Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Ground-Level Release January-December 2013 CONTINUOUS MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released Jan-Mar2013 Apr-Jun2013 Jul-Sep2013 Oct-Dec2013 Jan-Dec2013

1. FISSION AND ACTIVATION GASES: Ci Ar-41 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 Kr-85 0.00E+00 0.OOE+00 0.00E+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 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Kr-88 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Xe-131m 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Xe-133 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 O.OOE+00 Xe-133m 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Xe-135 0.00E+00 O.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 Xe-135m 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Xe-137 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Xe-138 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 Total for period 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00

2. IODINES: Ci 1-131 1.72E-04 9.14E-05 5,48E-05 1.68E-04 4.85E-04 1-133 6.23E-04 1.39E-04 1,80E-04 5.21 E-04 1.46E-03 Total for period 7.94E-04 2.30E-04 2,35E-04 6.89E-04 1.95E-03

3. PARTICULATES WITH HALF-LIVES > 8 DAYS: Ci Cr-51 0.00E+00 2.1OE-05 0.OOE+00 0.OOE+00 2.10E-05 Mn-54 2.84E-06 1.56E-05 5.08E-06 1.42E-05 3.77E-05 Fe-59 0.OOE+00 0.OOE+00 0.00E+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 6.34E-05 1.63E 2.74E-05 1.07E-04 Zn-65 0.OOE+00 1.73E-05 0.OOE+00 6.14E-06 2.34E-05 Sr-89 O.OOE+00 0.60E+00 1.02E-05 1.96E-05 2.98E-05 Sr-90 0.OOE+00 0.05E+00 0.OOE+00 0.OOE+00 0.OOE+00 Ru-103 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-134 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 Cs-1 37 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 Ba/La-140 2.75E-04 5.47E-05 2.34E-05 9.45E-05 4.48E-04 Total for period 2.78E-04 1.72E-04 5.50E-05 1.62E-04 6.67E-04

4. TRITIUM: Ci H-3 6.22E+00 6.41 E+00 2.34E+01 2.78E+01 6.38E+01

5. CARBON-14: Ci C-14 4.53E-02 2.92E-02 5.71E-02 5.62E-02 1.88E-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: 1E-04 gCi/cc lodines: 1E-12 1,Ci/cc Particulates: 1E-11 p.Ci/cc Page 14

Table 2.2-C (continued)

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Ground-Level Release January-December 2013 BATCH MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released Jan-Mar 2013 A r-Jun 2013 Jul-Sep 2013 Oct-Dec 2013 F Jan-Dec 2013

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-1i35 N/A N/A N/A N/A N/A Xe-135m N/A N/A N/A N/A N/A Xe-137 N/A N/A N/A N/A N/A Xe-138 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-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 Total for period N/A N/A N/A N/A N/A 4.. TRITIUM: Ci H-3 I N/A I N/A I N/A I N/A I N/A

5. CARBON-14: Ci C-14 I N/A I NIA I N/A I N/A I 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: IE-04 pCi/cc lodines: 1 E-12j+/-Ci/cc Particulates: 1E-i1 jICi/cc Page 15

Table 2.3-A Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid -Effluents - Summation* of All Releases January-December 2013 Est.

RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Total 2013 2013 2013 2013 2013 Error A. FISSION AND ACTIVATION PRODUCTS' Total Release (not including Totareleum ases (not induig 3.98E-06 1.89E-02 N/A 2.93E-05 1.89E-02 tritium, gases, alpha): Ci on Average Diluted Concentration 2.73E-14 1.74E-10 N/A 1.89E-13 3.36El1 +/-12%

During Period: .tCi/ml Percent of Effluent 9.11E-08% :2.47E-03% N/A 132E-05% 4.81E-04%

Concentration Limit* 9.1 E0% _ 2_-0_N 1:32E-05% 4.81E-04%

B. TRITIUM Total Release: Ci 8.10E-01 5.25E+00 N/A 1.57E-01 6.21E+00 Average Diluted Concentration 5.57E-09 4.81E-08 N/A 1.01E-09 !.10E-08 During Period: gCi/mL 59.4%

Percent of Effluent 5.57E-04% 4.81 E-03% N/A 1.01 E-04% 1.1 OE-03%

Concentration Limit*

C. DISSOLVED AND ENTRAINED GASES Total Release: Ci NDA NDA N/A NDA NDA Average Diluted Concentration NDA NDA N/A During Period: p.Ci/mL_ NDA NDA +/-16%

Percent of Effluent Concentration Limit* .O.00E+00% O.OOE+00% N/A O.OOE+00% O.OOE+00%

D. GROSS ALPHA RADIOACTIVITY Total Release: Ci NDA N/A N/A N/A NDA +/-34%

E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION Waste Volume: Liters 2.11E+05 I 8.30E+05 N/A 1.37E+05 1.18E+06 +/-5.7%

F. VOLUME OF DILUTION WATER USED DURING PERIOD Dilution Volume: Liters .1.46E+11 1 1.09E+11 I 1.55E+11 1.55E+11 5.65E+11 +/-Q10%.

Notes for Table 2.3-A:

Additional percent of Effluent Control Limit values based on dose assessments are provided in Section 6 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 1E-05 pCi/mL.

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

Page 16

Table 2.3-B Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2013 CONTINUOUS MODE RELEASES Nuclide Released Jan-Mar 2013 1 Apr-Jun 2013 Jul-Sep 2013 Oct-Dec 2013 Jan-Dec 2013

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-1 34 N/A N/A N/A N/A N/A Cs-1 37 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: 1E-06 p.Ci/mL Noble Gases: 1E-05 itCi/mL All Others: 5E-07 pCi/mL Page 17

Table 2.3-B3 (continued)

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2013 BATCH MODE RELEASES Nuclide Released. Jan-Mar 2013 1 Apr-Jun 2013 Jul-Sep 2013 Oct-Dec 2013 Jan-Dec 2013

1. FISSION AND ACTIVATION PRODUCTS: Ci Na-24 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00 Cr-51 0.OOE+00 4.50E-03 N/A 0.00E+00 4.50E-03 Mn-54 3.98E-06 3.73E-03 N/A 3.02E-06 3.74E-03 Fe-55 0.OOE+00 5.72E-04 N/A 0.OOE+00 5.72E-04 Fe-59 0.OOE+00 1.11E-03 N/A 0.OOE+00 1.11E-03 Co-58 0.OOE+00 4.89E-04 N/A 0.OOE+00 4.89E-04 Co-60 0.OOE+00 5.73E-03 N/A 8.86E-06 5.74E-03 Zn-65 0.00E+00 1.57E-03 N/A 0.OOE+00 1.57E-03 Zn-69m 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00 Sr-89 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00 Sr-90 0.00E+00 0.OOE+00 N/A 0.00E+00 0.OOE+00 Zr/Nb-95 0.OOE+00 4.69E-05 N/A 0.00E+00 4.69E-05 Mo/Tc-99 0.OOE+00 O.O0E+00 N/A 0.OOE+00 0.00E+00 Aq-110rm 0.OOE+00 1.08E-03 N/A 0.OOE+00 1.08E-03 Sb-124 0.OOE+00 9.60E-05 N/A 0.OOE+00 9.60E-05 1-131 0.OOE+00 0.00E+00 N/A 0.OOE+00 0.OOE+00 1-133 0.OOE+00 0.00E+00 N/A 0.00E+00 0.00E+00 Cs-134 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00 Cs-137 0.OOE+00 0.OOE+00 N/A .1.74E-05 1.74E-05 Ba/La-140 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00 Ce-141 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00 Ce-144 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.00E+00 Total for period 3.98E-06 1.89E-02 N/A 2.93E-05 1.89E-02

2. DISSOLVED AND ENTRAINED GASES: Ci Xe-1 33 NDA NDA N/A NDA NDA Xe-1 35 NDA NDA N/A NDA NDA Total for period NDA 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 g.Ci/mL lodines: 1E-06 LCi/mL Noble Gases: 1E-05 i.LCi/mL All Others: 5E-07 l.Ci/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, 47%

33-ft Wind Direction (from): South-southwest, 17%

" 33-ft Wind Speed: 3.5-7.5 mph, 58%

220-ft Wind Direction (from): South-southwest, 15%

220-ft Wind Speed: 12.5-18.5 mph, 37%

Joint data recovery for both the 33-ft level and 220-ft level of the tower was 89.8%, which did not meet the 90% annual data recovery goal specified by the NRC. This failure to meet the annual recovery goal was documented in Condition Report CR-PNP-2013-3335. High winds during winter storm Nemo in early February resulted in the elevator cable for the wind sensors breaking. This event resulted in the loss of all meteorological data for 786 hours0.0091 days 0.218 hours 0.0013 weeks 2.99073e-4 months between 08-Feb-2013 and 13-Mar-2013, and is described in Condition Reports CR-PNP-2013-0916 and CR-PNP-2012-1254.

During the refueling outage in April, site power to the meteorological tower was interrupted between 26-Apr and 30-Apr-2013, resulting in the loss of all meteorological data for 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months . This event is described in Condition Report CR-PNP-2013-3081.

The failure to meet the 90% data recovery goal for two consecutive years was identified as a concern during the NRC inspection of the Radiological Environmental Monitoring Program in August 2013. That NRC concern was described in Condition Report CR-PNP-2013-5742.

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 effluentreleases 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 2013 resulted in a maximum total body dose of 0.0000021-mrem. The maximum skin dose was 0.0000049 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 (0.63 km SSW of the Reactor Building). For the more "realistic" individuals at offsite locations, the maximum total body dose was 0.0000020 mrem (nearest residence, 0.86 kilometers WNW from the Reactor Building), while the maximum skin dose was 0.0000028 mrem (nearest residence, 0.86 kilometers WNW from the Reactor Building).

Page 20

Table 4.1 Maximum Doses From Noble Gas Releases During 2013(1)

Gamma Beta Total Release Air Dose Air Dose Body Dose Skin Dose Period mrad/period mrad/period mrem/period mrem/period (location) (location) (location) (location) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Jan-Mar (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Apr-Jun (0.64km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) 3.25E-06 3.10E-06 2.14E-06 4.87E-06 Jul-Sep (0.63 km SSW) (0.63 km SSW) (0.63 km SSW) (0.63 km SSW) 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Oct-Dec (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) 3.25E-06 3.1OE-06 2.14E-06 4.87E-06 Jan-Dec (0.63 kmSSW) (0.63 km SSW) (0.63 km SSW) (0.63 km SSW)

(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. For consistency, all distances listed in the first row of Tables 4.2-A through 4.2-E are measured from the Reactor Building Vent. However, doses at the specific receptor locations are calculated based on the actual distances from the applicable release points (PNPS main stack, reactor building vent, and turbine building roof exhausters).

Radioactivity (particulates, radioiodines, tritium, and carbon-14) released in gaseous effluents from PNPS during 2013 resulted in a maximum total body dose of 0.032 mrem (child age class at nearest garden location, 0.84 kilometers SE from the Reactor Building), while the maximum organ dose was 0.066 mrem (child bone at nearest garden location, 0.84 kilometers SE from the Reactor Building). Carbon-14 contributed 0.013 mrem (40%) of the 0.032 mrem child total body dose, and 0.065 mrem (99%) of the 0.066 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 2013 Receptor: Bound Resident Garden Cow/Goat Cow/Meat Meat Direction: ESE ESE SE WSW W S Distance 1: 0.33 km 0.80 km 0.84 km 3.97 km3 5.77 km3 3.80 km Pathway 2: DI DI DIV 3 DIVCG DIVCM DIVM 3 Age Class: Adult Bone 1.54E-04 1.03E-04 4.08E-03 1.65E-03 1.44E-03 2.51 E-03 GI-LLI 7.61E-04 4.98E-04 2.07E-03 4.34E-04 3.51E-04 5.77E-04 Kidney 7.50E-04 4.91 E-04 2.05E-03 4.35E-04 3.51 E-04 5.76E-04 Liver 7.48E-04 4.90E-04 2.05E-03 4.34E-04 3.51 E-04 5.76E-04 Luna 7.75E-04 5.07E-04 2.06E-03 4.33E-04 3.51 E-04 5.76E-04 Thyroid 1.25E-03 8.13E-04 3.23E-03 7.85E-04 5.40E-04 6.55E-04 T.Body 7.47E-04 4.89E-04 2.05E-03 4.33E-04 3.51E-04 5.76E-04 Age Class: Teen Bone 2.20E-04 1.48E-04 6.60E-03 2.77E-03 2.18E-03 3.54E-03 GI-LLI 7.80E-04 5.11E-04 2.70E-03 6.74E-04 5.04E-04 7.87E-04 Kidney 7.'70E-04 5.04E-04 2.69E-03 6.76E-04 5.05E-04 7.86E-04 Liver 7.68E-04 5.03E-04 2.68E-03 6.74E-04 5.04E-04 7.86E-04 Lung 8.11E-04 5.31E-04 2.70E-03 6.74E-04 5.04E-04 7.87E-04 Thyroid 1.41E-03 9.16E-04 3.77E-03 1.19E-03 7.78E-04 8.56E-04 T.Body 7.66E-04 5.02E-04 2.68E-03 6.74E-04 5.04E-04 7.86E-04 Age Class: Child Bone 3.03E-04 2.04E-04 1.58E-02 6.69E-03 5.12E-03 8.17E-03 GI-LLI 7.03E-04 4.61E-04 5.04E-03 1.51E-03 1.12E-03 1.74E-03 Kidney 7.OOE-04 4.59E-04 5.04E-03 1.51E-03 1.12E-03 1.74E-03 Liver 6..98E-04 4.58E-04 5.03E-03 1.51 E-03 1.12E-03 1.74E-03 Lung 7.35E-04 4.82E-04 5.05E-03 1.51 E-03 1.12E-03 1.74E-03 Thyroid 1.47E-03 9.53E-04 6.60E-03 2.50E-03 1.65E-03 1.84E-03 T.Body 6.97E-04 4.57E-04 5.03E-03 1.51E-03 1.12E-03 1.74E-03 Age Class: Infant Bone 2.24E-04 1.51 E-04 1.26E-04 4.20E-03 2.92E-03 5.60E-05 GI-LLI 4.15E-04 2.72E-04 2.04E-04 9-80E-04 6.64E-04 2.11E-05 Kidney 4.15E-04 2.72E-04 2.04E-04 9.88E-04 6.68E-04 2.11E-05 Liver 4.15E-04 2.72E-04 2.04E-04 9.87E-04 6.67E-04 2.11E-05 Lung 4.48E-04 2.94E-04 2.20E-04 9.81E-04 6.64E-04 2.18E-05 Thyroid 1.12E-03 7.27E-04 5.40E-04 3.22E-03 1.83E-03 3.78E-05 T.Body 4.13E-04 2.71E-04 2.03E-04 9.83E-04 6.65E-04 2.1OE-05 1 Distances are measured with respect to the reactor building vent.

2 Pathway designations are as follows:

D = Deposition (Ground Plane) I = Inhalation V = Vegetable Garden C = Cow Milk G = Goat Milk 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 23

Table 4.2-B Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Apr-Jun 2013 Receptor: Bound Resident Garden Cow/Goat Cow/Meat Meat Direction: ESE ESE SE WSW W S Distance': 0.33 km 0.80 km 0.84 km 3.97 km 5.77 km 3.80 km Pathway 2: DI DI DIV DIVCG DIVCM DIVM Age Class: Adult Bone 9.86E-05 6.63E-05 2.63E-03 1.06E-03 9.32E-04 1.62E-03 GI-LLI 7.63E-04 5.OOE-04 1.86E-03 3.23E-04 2.53E-04 4.06E-04 Kidney 7.59E-04 4.97E-04 1.80E-03 3.21E-04 2.51E-04 4.01E-04 Liver 7.59E-04 4.96E-04 1.81E-03 3.21E-04 2.51E-04 4.01E-04 Lung 8.25E-04 5.39E-04 1.83E-03 3.21 E-04 2.51 E-04 4.02E-04 Thyroid 9.64E-04 6.29E-04 2.38E-03 4.96E-04 3.45E-04 4.38E-04 T.Body 7.58E-04 4.96E-04 1.80E-03 3.20E-04 2.51E-04 4.01E-04 Age Class: Teen Bone 1.41E-04 9.49E-05 4.26E-03 1.79E-03 1.41E-03 2.28E-03 GI-LLI 7.78E-04 5.09E-04 2.32E-03 4.85E-04 3.54E-04 5.42E-04 Kidney 7.74E-04 5.07E-04 2.26E-03 4.83E-04 3.53E-04 5.38E-04 Liver 7.73E-04 5.06E-04 2.27E-03 4.83E-04 3.53E-04 5.39E-04 Lung 8.71E-04 5.69E-04 2.30E-03 4.82E-04 3.53E-04 5.40E-04 Thyroid 1.03E-03 6.72E-04 2.78E-03 7.41E-04 4.88E-04 5.71 E-04 T.Body 7.73E-04 5.06E-04 2.27E-03 4.82E-04 3.52E-04 5.39E-04 Age Class: Child Bone 1.95E-04 1.31 E-04 1.02E-02 4.32E-03 3.31E-03 5.27E-03 GI-LLI 6.97E-04 4.57E-04 4.01E-03 1.04E-03 7.62E-04 1.17E-03 Kidney 6.97E-04 4.56E-04 3.98E-03 1.04E-03 7.63E-04 1.17E-03 Liver 6.96E-04 4.56E-04 3.99E-03 1.04E-03 7.64E-04 1.17E-03 Lung 7.75E-04 5.07E-04 4.01E-03 1.04E-03 7.611E-04 1.17E-03 Thyroid 9.95E-04 6.48E-04 4.73E-03 1.54E-03 1.02E-03 1.21E-03 T.Body 6.96E-04 4.56E-04 4.OOE-03 1.04E-03 7.63E-04 1.17E-03 Age Class: Infant Bone 1.44E-04 9.65E-05 8.06E-05 2.71 E-03 1.88E-03 3.61E-05 GI-LLI 4.08E-04 2.68E-04 2.OOE-04 6.70E-04 4.47E-04 1.73E-05 Kidney 4.09E-04 2.68E-04 2.OOE-04 6.72E-04 4.48E-04 '1.73E-05 Liver 4.09E-04 2.68E-04 2.OOE-04 6.74E-04 4.49E-04 1;73E-05 Lung 4.61E-04 3.02E-04 2.25E-04 6.66E-04 4.45E-04 1.86E-05 Thyroid 6.82E-04 4.44E-04 3.30E-04 1.80E-03 1.03E-03 2.38E-05 T.Body 4.08E-04 2.67E-04 2.OOE-04 6.69E-04 4.47E-04 1.73E-05 1 Distances are measured with respect to the reactor building vent.

2 Pathway designations are as follows:

D = Deposition (Ground Plane) I = Inhalation V Vegetable Garden C = Cow Milk G = Goat Milk M =Meat Page 24

Table 4.2-C Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Jul-Sep 2013 Receptor: Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:

Distance 1 : ESE 0.33 km ESE 0.80 km SE 0.84 km WSW 3.97 km W 5.77 km S 3.80 km Pathway 2: DI DI DIV DIVCG DIVCM DIVM Age Class: Adult Bone 1.92E-04 1.29E-04 5.17E-03 2.08E-03 1.82E-03 3.16E-03 GI-LLI 2.73E-03 1.79E-03 5.67E-03 8.05E-04 5.97E-04 9.14E-04 Kidney 2.73E-03 1.79E-03 5.65E-03 8.04E-04 5.97E-04 9.13E-04 Liver 2.73E-03 1.79E-03 5.65E-03 8.04E-04 5.97E-04 9.13E-04 Lung 2.75E-03 1.80E-03 5.66E-03 8.04E-04 5.97E-04 9.13E-04 Thyroid 2.89E-03 1.89E-03 6.03E-03 9.16E-04 6.57E-04 9.38E-04 T.Body 2.73E-03 1.79E-03 5.66E-03 8.04E-04 5.97E-04 9.13E-04 Age Class: Teen Bone 2.75E-04 1.85E-04 8.36E-03 3.50E-03 2.75E-03 4.47E-03 GI-LLI 2.77E-03 1.81E-03 6.80E-03 1.15E-03 8.06E-04 1.19E-03 Kidney 2.77E-03 1.81E-03 6.78E-03 1.15E-03 8.06E-04 1.19E-03 Liver 2.77E-03 1.81E-03 6.78E-03 1.15E-03 8.06E-04 1.19E-03 Lung 2.80E-03 1.83E-03 6.79E-03 1.15E-03 8.06E-04 1.19E-03 Thyroid 2.97E-03 1.94E-03 7.12E-03 1.31 E-03 8.93E-04 1.21E-03 T.Body 2.77E-03 1.81E-03 6.78E-03 1.15E-03 8.06E-04 1.19E-03 Age Class: Child Bone 3.79E-04 2.55E-04 2.OOE-02 8.44E-03 6.47E-03 1.03E-02 GI-LLI 2.47E-03 1.62E-03 1.1OE-02 2.33E-03 1.66E-03 2.47E-03 Kidney 2.47E-03 1.62E-03 1.10E-02 2.33E-03 1.66E-03 2.47E-03 Liver 2.47E-03 1.62E-03 1.1OE-02 2.33E-03 1.66E-03 2.47E-03 Lung 2.50E-03 1.63E-03 1.1OE-02 2.33E-03 1.65E-03 2.47E-03 Thyroid 2.71E-03 1.77E-03 1.15E-02 2.64E-03 1.82E-03 2.50E-03 T.Body 2.47E-03 1.62E-03 2.47E-03 Age Class: Infant Bone 2.80E-04 1.88E-04 1.57E-04 5.30E-03 3.68E-03 7.06E-05 GI-LLI 1.44E-03 9.41E-04 7.OOE-04 1.45E-03 9.42E-04 5.09E-05 Kidney 1.44E-03 9.42E-04 7.OOE-04 1.45E-03 9.43E-04 5.09E-05 Liver 1.44E-03 9.41E-04 7.OOE-04 1.45E-03 9.43E-04 5.09E-05 Lung 1.45E-03 9.52E-04 7.08E-04 1.45E-03 9.42E-04 5.13E-05 Thyroid 1.65E-03 1.08E-03 8.03E-04 2.16E-03 1.31E-03 5.60E-05 T.Body 1.44E-03 9.41 E-04 7.OOE-04 1.45E-03 9.42E-04 5.09E-05 1 Distances are measured with respect to the reactor building vent.

.2 Pathway designations are as follows:

D = Deposition (Ground Plane) I = Inhalation V = Vegetable Garden C = Cow Milk G = Goat Milk M = Meat Page 25

Table 4.2-D Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Oct-Dec 2013 Receptor: Bound Resident Garden Cow/Goat Cow/Meat Meat.

Direction: ESE ESE SE WSW W S Distance 1 : 0.33 km 0.80 km 0.84 km 3.97 km3 5.77 km3 3.80 km Pathway2 : DI DI DIV 3 DIVCG DIVCM DIVM 3 Age Class: Adult Bone 1.91E-04 1.28E-04 5.12E-03 2.05E-03 1.80E-03 3.12E-03 GI-LLI 3.25E-03 2.13E-03 6.56E-03 8.74E-04 6.37E-04 9.59E-04 Kidney 3.25E-03 2.12E-03 6.52E-03 8.73E-04 6.36E-04 9.57E-04 Liver 3.24E-03 2.12E-03 6.52E-03 8.73E-04 6.36E-04 9.57E-04 Lung 3.28E-03 2.15E-03 6.53E-03 8.72E-04 6.35E-04 9.57E-04 Thyroid 3.71 E-03 2.42E-03 7.65E-03 1.20E-03 8.13E-04 1.03E-03 T.Body 3.24E-03 2.12E-03 6.52E-03 8.72E-04 6.35E-04 *9.56E-04 Age Class: Teen Bone 2.73E-04 1.83E-04 8.27E-03 3.45E-03 2.71E-03 4.40E-03 GI-LLI 3.29E-03 2.16E-03 7.76E-03 1.22E-03 8.47E-04 "1.23E-03 Kidney 3.29E-03 2.15E-03 7.73E-03 1.22E-03 8.47E-04 1.23E-03 Liver 3.29E-03 2.15E-03 7.73E-03 1.22E-03 8.47E-04 1.23E-03 Lung 3.35E-03 2.19E-03 7.75E-03 1.22E-03 8.46E-04 1.23E-03 Thyroid 3.88E-03 2.53E-03 8.76E-03. 1.71E-03 1.10E-03 1.30E-03 T.Body 3.29E-03 2.15E-03 7.73E-03 1.22E-03 8.46E-04 1.23E-03 Age Class: Child.

Bone 3.76E-04 2.53E-04 1.98E-02 8.32E-03 6.37E-03 1.02E-02 GI-LLI 2.93E-03 1.92E-03 1.23E-02 2.42E-03 1.70E-03 2.51E-03 Kidney 2.93E-03 1.92E-03 1.23E-02 2.43E-03 1.71 E-03 2.51E-03 Liver 2.93E-03 1.92E-03 1.23E-02 2.43E-03 1.71 E-03 2.51E-03 Lung 2.98E-03 1.95E-03 1.23E-02 2.42E-03 .1.70E-03 2.51E-03 Thyroid 3.63E-03 2.37E-03 1.38E-02 3.36E-03 2.20E-03 2.61E-03 T.Bod 2.93E-03 1.92E-03 1.23E-02 2.42E-03 1.71E-03 2.51E-03 Age Class: Infant Bone 2.77E-04 1.87E-04 1.56E-04 5.22E-03 3.63E-03 6.95E-05 GI-LLI 1.70E-03 1.11E-03 8.27E-04 1.49E-03 9.60E-04 5.77E605 Kidney 1.70E-03 1.11E-03 8.28E-04 1.50E-03 9.64E-04 5.77E-05 Liver 1.70E-03 1.11E-03 8.28E-04 1.50E-03 9.64E-04 5.77E-05 Lung 1.74E-03 1.14E-03 8.45E-04 1.49E-03 9.60E-04 5.85E-05 Thyroid 2.34E-03 1.53E-03 1.13E-03 3.61E-03 2.05E-03 7.28E-05 T.Body. 1.70E-03 1.11E-03 8.27E-04 1.50E-03 9.61E-04 5.76E-05 Distances are measured with respect to the reactor building vent.

2 Pathway designations are as follows:

D = Deposition (Ground Plane). I = Inhalation V =.Vegetable Garden C =Cow Milk . G= Goat Milk 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 2013 Receptor: Bound Resident Garden Cow/Goat Cow/Meat Meat Direction: ESE ESE SE WSW W S Distance 1 : 0.33 km 0.80 km 0.84 km 3.97 km3 5.77 km3 3.80 km Pathway2 : DI DI DIV 3 DIVCG DIVCM DIVM 3 Age Class: Adult Bone 6.35E-04 4.27E-04 1.70E-02 6.85E-03 6.00E-03 1.04E-02 GI-LLI 7.51 E-03 4.91 E-03 1.62E-02 2.44E-03 1.84E-03 2.86E-03 Kidney 7.49E-03 4.90E-03 1.60E-02 2.43E-03 1.84E-03 2.85E-03 Liver 7.48E-03 4.90E-03 1.60E-02 2.43E-03. 1.83E-03 2.85E-03 Lunt 7.63E-03 4.99E-03 1.61E-02 2.43E-03 1.83E-03 2.85E-03 Thyroid 8.80E-03 5.75E-03 1.93E-02 3.40E-03 2.36E-03 3.06E-03 T.Body 7.48E-03 4.89E-03 1.60E-02 2.43E-03 1.83E-03 2.85E-03 Age Class: Teen Bone 9.09E-04 6.11E-04 2.75E-02 1.15E-02 9.05E-03 1.47E-02 GI-LLI 7.62E-03 4.99E-03 1.96E-02 3.53E-03 2.51 E-03 3.75E-03 Kidney 7.61E-03 4.98E-03 1.94E-02 3.53E-03 2.51E-03 3.74E-03 Liver 7.60E-03 4.97E-03 1.95E-02 3.53E-03. 2.51 E-03 3.74E-03 Lung 7.83E-03 5.12E-03 1.95E-02 3.52E-03 2.51E-03 3.75E-03 Thyroid 9.28E-03 6.06E-03 2.24E-02 4.95E-03. 3.26E-03 3.93E-03 T.Body 7.60E-03 4.97E-03 1.95E-02 3.52E-03 2.51E-03 3.74E-03 Age Class: Child Bone 1.25E-03 8.43E-04 6.57E-02 2.78E-02 2.13E-02 3.39E-02 GI-LLI 6.80E-03 4.45E-03 3.24E-02 7.30E-03 5.24E-03 7.89E-03 Kidney 6.80E-03 4.45E-03 3.24E-02 7.31 E-03 5.25E-03 7.89E-03 Liver 6.80E-03 4.45E-03 3.24E-02 7.31 E-03 5.25E-03 7.89E-03 Lung 6.99E-03 4.57E-03 3.24E-02 7.30E-03 5.24E-03 7.89E-03 Thyroid 8.80E-03 5.74E-03 3.67E-02 1.OOE-02 6.69E-03 8.16E-03 T.Body 6.79E-03 4.45E-03 3.24E-02 7.30E-03 5.24E-03 7.89E-03 Age Class: Infant Bone 9.25E-04 6.22E-04 5.19E-04 1.74E-02 1.21E-02 2.32E-04 GI-LLI 3.96E-03 2.59E-03 1.93E-03 4.59E-03 3.01 E-03 1..47E-04 Kidney 3.96E-03 2.60E-03 1.93E-03 4.61E-03 3.02E-03 1.47E-04 Liver 3.96E-03 2.59E-03 1.93E-03 4.61E&03 3.02E-03 1.47E-04 Lung 4.1OE-03 2.68E-03 2.OOE-03 4.59E-03 3.01E-03 1.50E-04 Thyroid 5.80E-03 3.78E-03 2.81 E-03 1'.08E-02 6.23E-03 1.90E-04 T.Body 3.96E-03 2.59E-03 .1.93E-03 4.60E-03 3.01E-03 1.47E-04 Distances are measured with respect to the reactor building vent.

2 Pathway designations are as follows:

D = Deposition (Ground Plane) I = Inhalation V = Vegetable Garden C = Cow Milk G= Goat Milk 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

Table 4.3-A Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jan-Mar 2013 Age Class Organ Dose - mrem

Organ Adult Teen Child Bone 1.88E-09 1.04E-08 2.18E-09 GI-LLI 1.09E-06 7.85E-07 .5.72E-07 Kidney 8.27E-07 6.27E-07 5.31 E-07 Liver 8.94E-07 6.90E-07 5.84E-07 Lung. 7.99E-07 6.OOE-07 5.11E-07 Thyroid 7.99E-07 6.OOE-07 5.11E-07 T. Body 8.17E-07 6.18E-07 5.30E-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.

Page 29

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 higher than concentrations from other quarters. This will result in aproportionally 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 (adult age class). of 0.0027 mrem. The maximum organ dose (adult age class, GI-LLI) was 0.0096,mrem.

Page 28

Table 4.3-B Maximum Individual Organ Doses -- mrem From Liquid Release Period: Apr-Jun 2013 Age Class Organ Dose - mrem Organ Adult J Teen Child Bone 2.48E-03 2.37E-03 2.60E-03 GI-LLI 1.24E-02 8.20E-03 3.09E-03 Kidney 3.74E-03 3.43E-03 2.81 E-03 Liver 7.05E-03 6.55E-03 5.72E-03 Lung 4.83E-04 7.81 E-04 4.62E-04 Thyroid 6.75E-05 3.42E-04 7.49E-05 T.Body 3.19E-03 3.19E-03 3;50E-03 Page 30

Table 4.3-C Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jul-Sep 2013 Age Class Organ Dose - mrem Organ Adult Teen Child Bone 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 0.OOE+00 0.OOE+00 0.OOE+00 Liver O.OOE+00 0.OOE+00 0.OOE+00 Luna 0.OOE+00 0.OOE+00 O.OOE+00 Thyroid 0.OOE+00 0.OOE+00 0.00E+00 T.Body O.OOE+00 0.O0E+00 0.OOE+00 Page 31

Table 4.3-D Maximum Individual Organ Doses -- mrem From Liquid Release Period: Oct-Dec 2013 Age Class Organ Dose - mrem

Organ Adult Teen ] Child Bone 5.95E-07 1.16E-06 7.83E-07 GI-LLI 1.76E-06 1.70E-06 5.87E-07 Kidney 5.05E-07 1.01E-06 4.46E-07 Liver 1.05E-06 1.55E-06 9.55E-07 Lung 3.37E-07 8.55E-07 3.03E-07 Thyroid 2.63E-07 7.68E-07 2.31 E-07 T.Body 8.53E-07 1.15E-06 5.OOE-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 2013 Age Class Organ Dose - mrem

Organ Adult Teen Child Bone 1.91 E-03 1.84E-03 2.01E-03 GI-LLI 9.58E-03 6.34E-03 2.39E-03 Kidney 2.89E-03 2.65E-03 2.17E-03 Liver 5.44E-03 5.06E-03 4.42E-03 Lung 3.74E-04 6.05E-04 3.57E-04 Thyroid. 5.32E-05 2.66E-04 5.86E-05 T.Body 2.47E-03 2.47E-03 2.70E-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 (plume and 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 154 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 71.6 +/- 21.3 mR/yr to 62.2 +/- 8.9 mR/yr. Such a corrected dose is not statistically different from the Zone 4 average of 60.2 +/- 10.9 mR/yr, and is indicative of natural background radiation.

Although the annual exposure at TLD location OA was 94 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 0.43 mrem over natural background radiation levels, At the nearest residence 0.8 kilometers (0.5 miles) southeast of the PNPS Reactor B uilding, the annual exposure was calculated as being 62.1 +/- 7.7 mR (based on continuous occupancy at this location), which compares quite well to the Zone 4 annual average background radiation level of 60.2 +/- 10.9 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 (l&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 hrlday, 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 incremental radiation dose above background during 2013 is estimated as being about 0.9 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 2013. 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 0.0016 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 2013 Average Exposure +/- Standard Deviation: mR/ edod Exposure Zone 1* Zone 2 Zone 3 Zone 4 Period 0-3 km 3-8 km 8-15 km >15 km Jan-Mar 17.1 +/- 5.1 14.2 +/- 2.3 13.8 +/- 1.1 14.7 +/- 2.9 Apr-Jun 16.5 +/- 4.8 13.0 +/- 1.9 13.0 +/- 1.7 13.9 +/- 3.0 Jul-Sep 18.4 +/- 5.8 14.8 +/- 2.0 14.1 +/- 1.7 15.2 +/- 2.6 Oct-Dec 19.6 +/- 5.2 15.9 +/- 2.0 15.9 +/- 1.9 16.4 +/- 2.5 Jan-Dec 71.6 +/- 21.3** 57.8 +/- 9.0 56.7 +/- 7.6 60.2 +/- 10.9

Zone 1 extends from the PNPS restricted/protected area boundary outward to 3 kilometers (2 miles), and includes several TLDs located within the site boundary.

- When corrected for TLDs located within the site boundary, the Zone 1 annual average is calculated to be 62.2 +/- 8.9 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 2013 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 2013 A. Instantaneous Dose Rate Limit - Noble Gases PNPS ODCM Control 3.3.1 .a Limit: 500 mrem/yr Total Body Dose Period Value - mrem/yr Fraction of Limit Jan-Dec 2.14E-06 4.28E-07%

B. Instantaneous Dose Rate Limit - Noble Gases PNPS ODCM Control 3.3.1 .a Limit: 3000 mrem/yr Skin Dose Period Value - mrem/yr Fraction of Limit Jan-Dec 4.87E-06 1.62E-07%

C. Instantaneous Dose Rate Limit - Particulates, lodines, & Tritium PNPS ODCM Control 3.3.1.b Limit: 1500 mrem/yr Organ Dose Period Value - mrem/yr Fraction of Limit Jan-Dec 6.57E-02 4.38E-03%

D. Quarterly Dose Objective - Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.a Objective: 5 mrad Gamma Air Dose Period Value - mrad Fraction of Limit Jan-Mar 0.00E+00 0.OOE+00%

Apr-Jun 0.OOE+00 0.OOE+00%

Jul-Sep 3.25E-06 6.49E-05%

Oct-Dec 0.OOE+00 0.OOE+00%

E. Annual Dose Objective - Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.b Objective: 10 mrad Gamma Air Dose Period Value - mrad/vr Fraction of Limit Jan-Dec 3.25E-06 3.25E-05%

Page 38

Table 6.1 (continued)

Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2013 F. Quarterly Dose Objective - Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.a Objective: 10 mrad Beta Air Dose Period Value - mrad Fraction of Limit Jan-Mar 0.00E+00 0.OOE+00%

Apr-Jun 0.OOE+00 O.OOE+00%

Jul-Sep 3.10E-06 3.1OE-05%

Oct-Dec 0.OOE+00 0.OOE+00%

G. Annual Dose Objective - Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.b Objective: 20. mrad Beta Air Dose Period Value - mrad/vr Fraction of Limit Jan-Dec 3.10E-06 1.55E-05%

H. Quarterly Dose Objective - Particulates, lodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.a Objective: 7.5 mrem Organ Dose Period Value - mrem Fraction of Limit Jan-Mar 1.58E-02 2.10E-01%

Apr-Jun 1.02E-02 1.36E-01%

Jul-Sep 2.OOE-02 2.67E-01 %

Oct-Dec .1.98E-02 2.64E-01%

I. Annual Dose Objective - Particulates, lodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.b Objective: 15 mrem Organ Dose Period Value - mrem/vr Fraction of Limit Jan-Dec 6.57E-02 4.38E-01%

Page 39 :

6.2 Liquid Effluent Releases Liquid effluent concentration limits and doseobjectives 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 2013 A. Fission and Activation Product Effluent Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1OCFR20 Appendix B, Table 2, Column 2 Value Period Value - 4Ci/mL Fraction of Limit Jan-Mar 2.73E-14 9.11 E-08%

Apr-Jun 1.74E-10 2.47E-03%

Jul-Sep 0.OOE+00 0.OOE+00%

Oct-Dec 1.89E-1 3 1.32E-05%

Jan-Dec 3.36E-1 1 4.81 E-04%

B. Tritium Average Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1.OE-03 jiCi/mL Period Value - i.Ci/mL Fraction of Limit Jan-Mar 5.57E-09 5.57E-04%

Apr-Jun 4.81 E-08 4.81 E-03%

Jul-Sep 0.00E+00 0.OOE+00%

Oct-Dec 1.01 E-09 1.01 E-04%

Jan-Dec 1.1OE-08 1.10E-03%

C. Dissolved and Entrained Noble Gases Concentration Limit PNPS ODCM Control 3.2.1 Limit: 2.OE-04 ,iCi/mL Period Value - ljCi/mL Fraction of Limit Jan-Mar 0.OOE+00 0.OOE+00%

Apr-Jun 0.OOE+00 0.OOE+00%

Jul-Sep 0.OOE+00 0.OOE+00%

Oct-Dec 0.OOE+00 0.OOE+00%

Jan-Dec 0.OOE+00 0.OOE+00%

Page 41

Table 6.2 (continued)

Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2013 D. Quarterly Total Body Dose Objective PNPS ODCM Control 3.2.2.a Objective: 1.5 mrem Total Body Dose Period Value - mrem Fraction of Limit Jan-Mar 8.17E-07 5.45E-05%

Apr-Jun 3.50E-03 2.33E-01%

Jul-Sep 0.OOE+00 0.OOE+00%

Oct-Dec 1.15E-06 7.66E-05%

E. Annual Total Body Dose Objective PNPS ODCM Control 3.2.2.b Objective: 3 mrem Total Body Dose Period Value - mrem Fraction of Limit Jan-Dec 2.70E-03 9.01 E-02%

F. Quarterly Organ Dose Objective PNPS ODCM Control 3.2.2.a Objective: 5 mrem Organ Dose Period Value - mrem Fraction of Limit Jan-Mar 1.09E-06 2.18E-05%

Apr-Jun 1.24E-02 2.48E-01%.

Jul-Sep O.00E+00 0.OOE+00%

Oct-Dec 1.76E-06 3.51 E-05%

G. Annual Organ Dose Objective PNPS ODCM Control 3.2.2.b Objective: 10 mrem Organ Dose Period Value - mrem Fraction of Limit Jan-Dec 9.58E-03 9.58E-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 59.3 cubic meters of spent resins, filter sludges, etc.,

containing a total activity of about 76.4 Curies were shipped from PNPS for processing and disposal. Dry activated wastes and contaminated equipment shipped during the period totaled 1100 cubic meters and contained 6.08 Curies of radioactivity. No shipment of irradiated components was shipped during the reporting period. 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 22 shipments to Energy Solutions' Bear Creek Facility in Oak Ridge, TN; 1 shipment to Energy Solutions' Gallaher Road Facility in Kingston, TN; 9 shipments to Studsvik Processing Facility in Erwin, TN; 4 shipments to Energy Solutions Facility in Memphis, TN; and 2 shipments to Eastern Technologies in Ashford, AL.

Page 43

Table 7.0 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments January-December 2013 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Estimate of volume and activity content by type of waste Jan-Dec 2013 Type of waste Volume - m, J Curies Total Error

a. Spent resins, filters, filter sludges, 5.93E+01 7.64E+01 +/- 25%

evaporator bottoms, etc.

b. Dry activated waste, contaminated 1.10E+03 6.08E+00 +/- 25%

equipment, etc.

c. Irradiated components, control rods, etc. 0.OOE+00 0.00E+00 N/A

d. Other (describe): 0.OOE+00 0.OOE+00 N/A

2. Estimate of major nuclide composition by type of waste1 Type of waste Radionuclide Abundance Total Error

a. Spent resins, filters, filter sludges, Mn-54 10.91% +/- 25%

evaporator bottoms, etc. Fe-55 29.78% +/- 25%

Co-60 30.98% +/-25%

Zn-65 16.47% +/-25%

Cs-1 37 7.57% +/- 25%

b. Dry activated waste, contaminated Mn-54 9.49% +/- 25%

equipment, etc. Fe-55 59.67% +/- 25%

Co-60 22.02% +/- 25%

Ni-63 1.02% +/- 25%

Zn-65 6.20% +/- 25%

c. Irradiated components, control rods, etc. Not licable Not Applicable N/A

d. Other (describe): j Not Applicable Not Applicable N/A "Major"is defined as any radionuclide comprising >1% of the total activity in the waste category.

3. Solid Waste Disposition

-Number of Shipments Mode of Transportation Destination Tractor-trailer Energy Solutions Bear Creek Facility 2 (Hittman Transport) . Oak Ridge, TN Tractor-trailer Energy Solutions Gallaher Road Facility L (Hittman Transport) Kingston, TN 9 Tractor-trailer Studsvik Processing Facility, z (Hittman Transport) Erwin, TN 4 Tractor-trailer Energy Solutions Facility (Hittman Transport) Memphis, TN 2 Tractor-trailer Eastern Technologies Inc.

(Hittman Transport) Ashford, AL 2 This processor provides volume reduction services for dry compressible waste, contaminated equipment, etc.

Remaining radioactivewastes will be shipped to Envirocare,Inc. in Clive, UT for final disposal.

B. IRRADIATED FUEL SHIPMENTS & DISPOSITION Number of Ship ments Mode of Transportation 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 2013. Information regarding revisions to the ODCM can be found attached as Appendix D of this report.

Page 45

9.0 PROCESS CONTROL PROGRAM REVISIONS There were no significant changes to the PNPS Process Control Program (PCP) during the calendar year of 2013. Although Pilgrim Station adopted the Entergy fleet-wide PCP in 2010 as indicated in the 2010 Annual Effluent Release Report, fleet procedure EN-RW-105, "Process Control Program", was not revised until 2011 to reflect the inclusion of Pilgrim Station under the fleet-wide PCP. This revision was strictly administrative in nature, and did not impact the requirements or conduct of the PCP.

The following list summarizes changes made during 2013 to various procedures related to the Process Control Program:

EN-RW-1 03, "Radioactive Waste Tracking Procedure", Rev.4: Editorial revision to clarify and update the following items: Adjust the range of densities for metals; Titles in responsibilities section updated; Clarification on liability reports to management.

EN-RW-104, "Scaling Factors", Rev.9: Editorial revision to address the following items:

Enhancement to initiate a Condition Report for independent lab result discrepancies as compared to in-house analyses; Enhancement to share waste stream data results to Chemistry/Environmental personnel responsible for effluents.

EN-RW-105, "Process Control Program", Rev.3: Editorial revision to recognize organizational titles at Palisades Nuclear Plant.

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 2013 Class A Freq: 0.082 m rhN NNE NE IENS E SE I SEI SSE S Svv I s I W IWvWw NW I NW I TOTAL Calm-0.95 0 0 0. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 3.5-7.5 16 13 3 7 3 2 0 0 0 0 0 0 7. 16 16 7 90 7.5-12.5 0 0 0 2 0 0 0 0 0 0 0 0 3 12 2 2 21 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0.0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 0. 0 0 0 0 0 0 .0 0 0. 0 0 0 TOTAL 16 14 .3" 9 3 2 0" 0 0 0 0 0 10 28 18 9 112 Class B Frec 0.035 mph N N.NE NEI ENE 1 E ESEI SE iSSE] S S ISW swIWSW[ W WNW[ NWINNWI TOTAL Calm-0.95 0. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 2 3.5-7.5 3 3 1 2 1 0 0 0 0 0 0 0 -9 7 5 3 34 7.5-12.5 0 0 1 1 0 0 0 0 .1 0 0 0 8 1 0 0 12 12ý5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 .0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 "0 0 0 0 0 TOTAL 4 3 3 3 1 0 0 0 1 IOTa0 1. T1J7L 8 5 3 I 48 Class C Freq 0.043 mph N I NNE N1EIENE E Is ISE SSE S s S s IWSW SIW W WNWvNWINNWI TOTAL Calm-0.95 0 0 0 .0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 1 3.5-7.5 2 3 2 0 1 1 0 0 0 1 1 1 15 10 4 3 44 7:5-12.5 0 0 1 0 0 0 0 0 i 1 0 0 8 2 1 0 14 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 10 0 .0 0 0 10 0 0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0. 0 TOTAL 2 I3 3 0 2, 11 0 Io0 1 I2 1 1 123 112.1 5 I3 I 59 Class D 0.544 mph I N 1 NNEI NE IENE E IESE ISE ISSEj S jSSW SW IWSWl W IWNwl NW IWNNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 0.95-3.5 4 6 8 7 10 7 6 0 1 5 3 11 12 10 13 7 110 3.5-7.5 15 4 5 4 6 8 11 10 15 19 20 50 147 70 28 22 434 7.5-12.5 3 5 7 1 22 3 0 1 4 33 15 12 41 29 4 2 182 12.5-18.5 0 0' 1 2 0 0 0 0 3 11 2 0 0 0 0 0 19 18.5-24 0 0 0 0 0 10 0 0 2 0 0 0 0 0 10 0 2

>24 0 0 0 0 0 0 0 0 0 a 0 0 0 TOTAL 22 15 21 14 38 118 17 73 200 109 1 4 1 748 Page 49

Table A-1 (continued)

Jan-Mar 2013 Class E Fre: 0.250 mph N jNNEINEIENE IEj ESE ~SE SSE I S jSSW SW IWSWI W WNW NW NN4W TOTAL Calm-0.95 0 1 0 1 0 1 0 0 0 1 1 0 0 1 0 0 6 0.95-3.5 4 3 5 2 3 .4 3 8 8 8 16 15 23 12 4 6 124 3.5-7.5 1. 1 1 0 1 0 3 8 9 17 38 48 43 20 6 4 200 7.5-12.5 1 0 0 0 1 1 0 1 1 0 4 1 2 1 0 0 13 12.5-18.5 0 0 1 0 0 0 0 0 0 0. 0 0 0 0 0 0 1 18.5-24 0 0 0 0 0 0 0 0 0

>24 .0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 6I5.7.3.5 6.1.6L171 18 .1.2 . 1...L 59 1.64 1,68, 134110 1J10[ 344 Class F Freq 0.039 mphN INE INN I ENE ESE Isw I WSW I NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 .0 0 0.95-3.5 0 0 0 0 0 0 0 1 2 6 .3 11 2 0 0 .0 25 3.5-7.5 0 0 0 1 0 0 0 0 0 4 14 9 0 0 0 0 28 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 .0 0 0 0 0 .0 12.5-18.5 0 0. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.

18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 .0 .0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 0 1 .01 0 10 1 1 1 2 1 10 1'1 1 20 2 1 0 1 0 1 0 1 53 Class G Freq 00.007 mph N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0. 0 0 0 2 0 0 0 0 0 2

.3.5-7.5 0 0 0 0 0 0 0 0 0 0 6 1 0 0 0 0 7 7.5-12.5 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0.. 1 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.0 0'

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 Tj 0 010 0 010 01a a 1* L L0 01 0 . 10 Class All Fr 1.000 mph IN I NNE I"NEENE I EE I ES I SEI SSE I S I SSW SW I WSW IW WNW NW _NNW TOTAL Calm-0.95 0 1 0 1 0 1 0 0 0 1 1 0 0 1 1 0 ,7 0.95-3.5 9 10 14 9 14 11 9 9 11 19 24 37. 37 22 17 13. 265 3.5-7.5 37 24 12 14 12 11 14 18 24 41 79 109 221 123 59 39 837 7.5-12.5 4 5 9 4 23 4 0 2 7 34 20 13 62 45 7 4 243 12.5-18.5 0 0 2 2 0 0 0 .0 3 11 2 0 0 0 0 0 20 18.5-24 0 0 0 0 0 0 0 0 2 0 0 .0 0 0 0 0 2

>24 0 0 00 0 0 0 0 00 0 0 0 0 0 0 0 0 TOTAL 50 40 37 1 30 1412 231, 29. 147 1~ 10 ý 1 15 121 191~ 84 56 _ 1374 Page 50

Table A-1 (continued).

Apr-Jun 2013 Class A 0.098 mph N NNE NE IENE E (ESEI SE] SSE I S Issw SW IWSWI WIwNw Iw TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 2 1 1 0 1 0 0 1 0 0 0 0 0 0 0 0 6 3.5-7.5 20 26 28 24 19 5 2 1 1 2 2 9 10 9 6 10 174, 7.5-12.5 0 0 0 5 0 1 0 0 1 6 0 0 8 1 1 0 23 12.5-18.5 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 22 27 1 29 29 I20 I I 2 91L18I I10 I 10 1 20 Class B Fred: 0.056 mph IN N INE IEN I ESEI E 'SSEI S ISSWl SW IWswI W IwNwlW NNwl TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 0 1 1 2 1 1 0 0 0 0 0 0 .0 0 0 7 3.5-7.5 2 3 2 4 12 7 2 '1 2 10 7' 7 13 6 1 1 80 7.5-12.5 1 0 0 0 0 0 0 1 5 .18 1 1 1 0 0 0 28 12.5-18.5 0 0 .0 0 0 0 0 -0 0 1 0 0 0 0 0 0 1 18.5-24 0 0 0 0 0 0 0 0 0 0.0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 . 0 0 0 0' 0 0 0 TOTAL 4 3 14 8 3 2 7 2I 8 8 1 1 1I 116 Class C F 0.073 mrh N INNEI NE ENE E ESEJ SE ISSEI S Issw SW WSWI W IWNWI NW INNWl TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 3 1 2 1 2 2 1 0 0 0 1 0 2 0 3 0 18 3.5-7.5 0 3 5 8 6 5 6 0 2 14 11 9 12 11 4 2 98 7.5-12.5 0 2 0 0 0 0 0 0 5 23 1 0 2 0 0 0 33 12.5-18.5 0 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 2 18.5-24 0 0 0. 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 00 0 0 0 0 0 0 0 00 0 TOTAL [ 3I 7 9 8167 7 0 1 39 13IS1 116_L 11 1 7 " '2 151 Class D F 0.462 Mph N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 12 11 19 26 30 13 18 10 9 9 7, 6 5 4 7 4 190 3.5-7.5 18 19 27 25 32 34 13 14 57 124 38 36 44 23 14 11 529 7.5-12.5 5 15 6 5 6 3 1 1 18 139 11 1 16 3 1 2 233 12.5-18.5 0 0 0 0 0 0 0 0 3 5 0 0 0 0 0 0 8 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0.0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 35 45 52 56 68 50 32 25 87 277 56 43 65 30 22 17 960 Page 51

Table A-1 (continued)

Apr-Jun 2013 Class E Frea: 0.209 IN[NNEI Nph NE IENEf] I E I SEISS S' S SW I W IwNwl NW INNWl TOTAL Calm-O.95 0 0. 0 0 0 0 0 0 0 0 0 0 1 0 0 0 :1 0.95-3.5 8 5 4 15 15 19 8 13 16 2 12 12 8 9 9 4 159 3.5-7.5 0 5 9 4 12 2 5 9 19 43 47 29 21 .8 8 3 224 7.5-i2.5 0 0 0 0 0 0 0. 0 .2 31 17 0 0 0 0. .0 50 12.5-18.5 0 0 0 0 0 0. 0 0 0 .1 0 0 '0. 0 0 0 1 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.- 0 0.

>24 0 0 0 0 .0o0 0 0 0 .0 0 0 0 0 0 0 TOTAL 1 8 10 13 19] 27 21 13 J 22 37 77 [ 76[ 411 30117117 7 I 435 Class F Fre:0,081 mph IN [NNEE H IEEIN E ESEI SE ISSEl S ISSW I SW IWSWI W IWNW NW [NNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0'1 0 0 1 0 0 0 0 1 0.95-3.5 0 0 0 0 .2 3 2 3 11 11 7 13 9 7 0 1 69 3.5-7.5 1 *0 0 1 1 1 2 1 2 10 -56 10 0 2 0 0 87 7.5-12.5 0 0 0 0 0 0 0 0- 0 1 10 0 0 0 0 0 11 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 d0 0 0 0 0 0 0 0 0.

>24 0. 0 0 0 0 0 0 0 .0 0 0 0 0 0 0 0 0 TOTAL.I0 o I 4I 4 1 1221

.. 731 241 9 9I 0 11 16 Class G 0.022 h IN NNEI NEIENE E ESEI SE SSE] S ISSW SW WSW W WNWlJNW NNWJ TOTAL Calm-0.95 0 0 0 0 0 *0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 1 0 0 2 0 2 5 6 2 0 0 0 18 3.5-7.5 0 0 0 0 0" 0' 0 0 0 2 22 2 0 0 0 0 26 7.5-12.5 0 0 0 0 0. 0 0 0 0 0 1 0 0 0 0 0 1 12.5-18.5 0 0 0 0 0 0 ;0 0 0" 0 0 0 0 0 0 0 0 18.5-24 0 0 0. 0 0 .0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0" 0 0 0 0 0 0 0 0 0 0 0 0 0' TOTAL o 0 0 I0 1 0 0 2[0 I28 8 -2 0 0 0 45 Class All 1.000 mnh

'"r N INNEI NE IENEI N.I.N.E.N. . I. E..I.

F.

E I ESE

...S I SE ISSF

.

I ~ I~swI ~w IW~wI.

.I.S.SS..I.S.....

W

..

IWNWI

......

NW

....

INNWI.rnTAi

......

NW I TOTAL .

I Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 1 1 0 0 0 2 0.95-3.5 26 18 27: 43 53 38 30 29 .36 24 32 37 26 20 19 9 467 3.5-7.5. 41 56 71 66 82 54 30 26 83 205 183 102 100 59 33 27 1218 7.5-12.5 6. 17 6 10 6 4 1 '2 31 218 41 2 27 4 2 2 379 12.5-18.5 0 0 0 0 0 0 0 0 3 10 0 0 0 0 0 . 0 13 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24: 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 73 91 104 119 141 96 61 57 153 457 256 142 154 83 54 38 2079 Page 52

Table A-1 (continued)

Jul-Sep 2013 Class A 0.070 mph I. N [NNEI NEIENEI E I ESE I SE I.SSE I S .Issw I SW IWSWl W IWvNWNWtINNWvI TOTAL Calm-0.95 0 0 0 0 o 0 0 0. 0 0. 0 0. 0 0 0 0 0 0.95-3.5 12 13 9 8 2 0 0 0 0 0 0 0 2 0 1 4 51 3.5-7.5 9 38 17 5 5 1. 0 0 3 2 1 1 6 5 7 3 103 7.5-12.5 0 0 0 0 0 0 0 .0 0 0 0 0 0 0 0 0 0 12.5-18.51 0 0 0 0 0 to o 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 o 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1 21 51 26 13 7 1 0 o0 3 2 .1 1 I_81 5 I 154 Class B F 0.019 mph I N INNEI NEIENEI E I ESE SE ISSE*IS ISSW SWV IWSW[ W7I"WNW N INNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 . 0 0.95-3.5 1 5 1 1 2 0 0 1 0 0 0 0 3 2 2 .0 18 3.5-7.5 1 2 5 1 2 0 0 0 1 0 0 1 4 6 1 0 24 7.5-12.5 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 12.5-18.5 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 o 0 0 0 0.0 0 "0 0 I0.0 0 0 0 TOTAL 12 17 6 2 i 0I I4I I1 I01 I 1.1 1I o I 1. I. I 0 43 Class C F 0.052 phI N I NNE NE ENEI E ESE SE ISSE S ISSsw WSW W Www 1NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 o0 0 0 0 0 0 0.95-3.5 4 4 7 7 .5 0 2' 1 0 0 1 0 4 ' 5 11 1 52 3.5-7.5 1 5 0 1 1 2 1 0 7 11 7 12 7 2 0 3 60 7.5-12.5 0 0 0 0 *0 0 0 0 0 3 0 0 0 0 0 0 3 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0. 0- 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 *0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 51 91 71 8 6 21 3 1 7 1 14 8 112 11 7_ 11 115 Class D F 0.393 mph N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 o 0 0 0 0 0 0 0 0 0 0 0.95-3.5 23 31 32 30 44 21 18 9 16 16 12 14 22 13 12 18 331 3.5-7.5 9 49 4 5 10 7 5 1 55 216 92 19 18 4 2 4 500 7.5-12.5 0 0 0 0 0 0 0 0 4 27 6 0 0 0 0 0 37 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0. 0 0_ 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 .0 0 0 0 0 0 TOTAL 32 80 36 35 54 28 23 10 75 259 110 33 40 17 14 22 868 Page 53

Table A-1 (continued)

Jul-Sep 2013 Class E

____h I F 0.313 IN I NEI iNI

ISI SE Isse S I~vlSW IWsw .W IwNwl NW I""w ITTA Calm-0.95 1 .0 0 0 0 2 0 0 1 0 0 0 2 0 2 1 9 0.95-3.5 11 19 15 24 11 12 22 17 27 21 22 45 27 17 19 9 318 3.5-7.5- 6 6 0 0 0 0 1 4 24 128 97 50 10 7 7 7 347 7.5-12.5 0 0 0 0 0 0 0 ,S0 1 I 7 W0 0 0 0 0 17 .

12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 TOTAL 18 25 15 24 11 14 23 21 53 11561128I 95 39 1 24 28 17I 691 Class F mph IF:NINNEI 0.117 NE IENEIE IESEI sE I SSEIJ S Is lSW IWsWv VItWNWJNW INNWJ TOTAL Calm-0.95 0. 0 0 0 0 0 0 1 0 1 0 0 2 0 0 0 4 0.95-3.5 1 0 1 4 0 0 0 3 10 19 19 36 13 9 1 0 116 3.5-7.5 :'0 0 0 0 0 0 0 0 3 25 96 10 0 0 0 0 134 7.5-12.5 0 0 0 0 0 0 0 0 0 0 4 0 0 0 0 0 4 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 .0 0 0 . 0 0 0 0 0 -0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.

TOTAL 1 I0 1 14 1 0 1l0 1 4 1 13 45 1119 1 46 15 1 9I 11 10I 258 Class G. Fom 0.036 mph N [NNE NE ENEI E ESE SE I SSE S S SSW SW IWSWI W IWNW NW NNWI TOTAL Calm-0.95 0 0 1 1 0 0 0 0 0 1 0 1 0 0 0 0 4 0.95-3.5 0 0 0 0 0 0 0 0 0 4 11 15 10 0 1 0 41 3.5-7.5 0 0 0 0 0 0 0 0 0 34 0 0 0 0 0 34 7.5-12.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 -0. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 .0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TTAL 0 0 I 1 0 01 05 0 45 16 1I 11 0 79 Class All 1.000 mph N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.95 1 0 1 1 0 2 0 1 1 2 0 1 4 0 2 1. 17 0.95-3.5 52 72 65 74 64 33' 42 31 53 60 65 110 81 46 47 32 927 3.5-7.5 26 100 26 .12 18 10 7 5 93 382 327 93 45 24 17 17 1202 7.5-12.5 0 0 0 0 0 0 0 0 5 38 19 0 0 0 0 0. 62 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 79 172 92 87 82 45 49 37 152 482 411 204 130 70 66 50 2208 Page 54

I Table A-1 (continued)

Oct-Dec 2013 Class A mph N 0.043 NNIEI NE IENEI E IESEI SE ISSE S ISSWtsSWIw l WvIwSwlIW I N~WlNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 5 6 5 3 1 0 0 0 0 0 0 0 0 1 1 0 22 3.5-7.5 8 12 17 4 1 0 0 0 0 1 1 0 15 8 3 1 71 7.5-12.5 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 12.5-18.50 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 2 18.5-24 0 0 0 0 0. .0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 113 18 22 1 7 2 [01 0 10 013 12 01151 914 I4 l Class 8 Freq 0.022 mph N NNEI NE IENEI E IESEI SE ISSEI S Isswl SW IWSw W IWNWI NW INNWl TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 4 1 0 0 1 0 0 0 0 0 0 1 1 1 1 10 3.5-7.5 3 2 1 5 4 0 0 0 0 0 2 4 5 7 2 3 38 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0. 0 0 0 0 o o 0 0 0 0 o 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALTOTLI T 3 1.2.1.1 10 01- 0 J14 00 214161913141 6 4 494 Class C F 0.025 mph N NINEl NE ENE E IESEI SE SSE I S IISS SW wswl W WNWIVNWI NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 1 2 2 1 0 0 0 0 0 0 0 0 1 0 0 8 3.5-7.5 0 0 0 2 0 0 0 0 0 4 4 6 8 4 10 4 42 7.5-12.5 0 0 0 0 0 0 0 0 0 1 1 0 0 3 1 0 6 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1 2I41 1 0I 0 0 0 5 5 1 6 8 8 1 1 4I Class D Fr 0.509 mph N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 17 21 28 8 5 3 3 10 4 6 17 14 13 12 27 19 207 3.5-7.5 15 21 12 22 14 16 24 32 22 67 60 90 137 81 101 34 748 7.5-12.5 0 0 0 0 8 4 0 0 15 37 21 3 37 22 12 4 163 12.5-18.5 0 0 2 1 0 0 0 2 0 0 0 0 0 0 5 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 32 42 40 30 29 24 27 42 41 112 98 107 187 115 140 57 1123 Page 55

Table A-1 (continued)

Oct-Dec 2013 Class E Fre ,:.314 mph INI NNEI IN IEE ESE SE ISSEI S ISSWI SW IWSWl vIlWNWI NWv INWl TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 1 0 1 0 0. 0 0 2 0.95-3.5 2 13 16 11 9 7 13 20 33 33 35 37 30 12 14 8 293 3.5-7.5 2 3 10 8 0 3 8 15 20 49 64 111 43 5 7 3 351 7.5-12.5 0 0 0 0 1 1 4 1 9 15 6 1 1 1 0 0 40 12.5-18.5 0 0 0 0 1 1 0 2 4 0 0 0 0 0 0 0 8 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 .0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 4I i.16 26 I 19 I 11 I12iI 25 ( 38 66 98I 105 150 74.I..8 21 117 .694 Class F Fre: 0.071 mph ININNEI NEIENEI IE SEI SE ISSE I S Issw sw SIWIw IWNA NW INNW TOTAL Calm-0.95 0. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 2 3 8 23 12 16 8 3 0 0 75 3.5-7.5 0 0 0 0 0 0 0 0 2 7 55- 10 2 0 0 0 76 7.5-12.5 0 0" 0 0 0 0 0 0 0 1 5 .0 0 0 0 a 6 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 0 0. 0 0 0 -0 0 0 0 0 TOTAL I0 0003 12 I 1 1 1 0 3 0 J 0 1 157 Class G Fre: 0.015 mph I N NNE NE ENE E ESEI SE SSE S Isswl swlwsw W IWNW NWI NNW TOTAL Caim-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 1 0 0 0 1 0 2 5 15 1 '0 0 0 25 3.5-7.5 0 0 0 0 0 0 0 0 0 0 8 0 0 0 0 .0 8 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 9 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 o0 0 0 0 0 o0 0 :"0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 0 I 0 0 0 1I 0 2 113 15 I 0 0 . 0 33 Class All Fr: 1.000 mph N NNE NE ENE E ESE SE SSE S SSW SW WSW 'W WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 1 0. 1 0 0 0 0 2 0.95-3.5 25 45 52 25 16 11 18 34 45 64 69 82 53 . 30 43 ,28 640 3.5-7.5 28 38 40 41 19 19 32 47 44 128 194 221 210 105 123 45 1334 7.5-12.5 0 0 .0 0 9 5 4 1 24 54 34 4 38 27 13 4 217 12.5-18.5 0 0 0 0 .3 2 0 2 4 4 0 .0 0 0 0 0 15 18.5-24. 0 0 0 00 0 0 0 0 0 0 0 10 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 .0 0 0 0 0 TOTAL 53 83 92 66 47 37 54 84 117 251 297 308 301 162 179 77 2208 Page 56

Table A-1 (continued)

Jan-Dec 2013 Class A Freq: 0.072 mph N NE NE ENE E SEI SE ISSE S ISSW SWIWSWI W IWNW1 NWVNNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 19 21 15 11 4 0 0 1 0 0 0 0 2 1 2 4 80 3.5-7.5 53 89 65 40 28 8 2 1 4 5 4 10 38 38 32 21 438 7.5-12.5 0 0 0 7 0 1 0 0 1 6 1 0 11 13 .3 2 45 12.5-18.5 0 0 0 0 0 0 0 0 0 3 0 0 0 0 0 0 3 18.5-24 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 *0 0

>24 0 0 0 0 0 0 0 0 0 0. 0 0 0 0 0 0 0 TOTAL 72 110 I80 I58 I32 I9 2 2 I5 14 5 10 51 152 37 27 566 Class B Frec 0.033 mph N NNE NE IENEI E IESE S I SSEI S ISW SW IWSWl W IWNwl NW IWNNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 . 0 0 0 0 0 0 0.95-3.5 3 9 4 2 4 2 1 1 0 0 0 0 4 3 3 1 37 3.5-7.5 9 10 9 12 19 7. 2 1 3 .10 9 12 31 26 9 7 176 7.5-12.5 1 0 1 1 0 . 0 0 1 6 19 1 1 9 2 0 0 42 12.5-18.5 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 113 119 I 4 15 23 I 1 3 9 1]9 30 10 13 44 I31 12 8 2 Class C Fref 0.048 N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 8 6 11 10 9 2 3 1 0 0 2 0 6 6 14 1 79 3.5-7.5 3 11 7 11 8 8 7 0 9 30 23 28 42 27 18 12 244 7.5-12.5 0 2 1 0 0 0 0 0 6 28 2 0 10 5 2 0 56 12.5-18.5 0 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 2 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL I 1

____-71-r-1190 7 J7 10 10-I815 0I 2 ]38 2 158 4I 13 3II 381 Class D Fr 0.470 raph N NNI NE IENEI E I ESEI SE ISSE I S ISSWI SW Iwsw W wNWI NW I NNWl TOTAL Calm-0.95 0 0 0 0 0 0 0 *0 0 0 0 0 0 .0 1 0 1 0.95-3.5 56 - 69 87 71 89 44 45 29 30 36 39 45 52 39 59 48 838 3.5-7.5 57 93 48 56 62 65 53 57 149 '426 210 195 346 178 145 71 2211 7.5-12.5 8 20 13 6 36 10 1 2 41 236 53 16 94 54 17 8 615 12.5-18.5 0 0 1 2 2 1 0 .0 6 .18 2 0 0 0 0 0 32 18.5-24 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 0 2

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 121 1182 14 9 13 5 189 1 20 9 9 1-88 1228 1716 1 304 1256 1 492 271 1222 127 1 3699 Page 57

Table A-1 (continued)

Jan-Dec 2013 Classlasp E

E Freq: . -N5E 0.275 N E E ESE S S ISSE SSW SW WSW W WNW NWNNWv TOTAL Calm-0.95 1 1 0 1 0 3 0 0 1 2 .1 1 3 1 2 1 .18 0.95-3.5 25 40 40 52 38 42 46 58 84 64 85 109 88 50 46 27 894 3.5-7.5 9 15 20 12 13 5 17 36 72 237 246 238 1117 40 28 17 1122 7.5-12.5 1 0 0 .0 2 2 4 2 13 53 36 2 3 2 0 0 .120 12.5-18.5 0 0 1 .. 0 1 1 0 2 4 1 0 0 0 0 0. 0 10

18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 .0 0. 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL I 36 56 1 1 1 65 1 54 153 167 198 11741 357 368 1 35012111 93 1 45 [ 2164 Class F Frea- 0.081 mph ININNE.N E IE ESEI SEI SSEI S SS5W E SW WSWj W WNW NW NNW[ TOTAL Calm-O0.95 0 0 0. 0 0 1 0 1 0 .1 2 0 0 0 5 0.95-3.5 1 0 1 4 2 3 4 10 31 59 41 76. 32 19 1 1 285 3.5-7.5 1 0 0 2 1 1 2 1 7 46 221 39 2 2 0 0 325 7.5-12.5 0 .0 0 0 0 0 0 0 0 2 19 0 0 0 0 0 21 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 12 I 0 [ I6 1.I3 4I 61 1 2 1r38 1 1*8 281 116* 36 21 I 1 636 Class G F:0.021 mph N NNE' NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.95 0 0 1 1 0. 0 0 0 0 1 0 1 0 0 0 0 4*

0.95-3.5 0 0 0 1 1 0 0 3 0 8 23 36 13 0 .1 0 86 3.5-7.5 0 0 0 0 0 0 0 0 0 2 70 3 0 0 0 0 75 7.5-12.5 0 0 0 0 0 0 0 0 0 0 2 0 0 :0 0 0 2 12.5-18.5. 0 0 0 0 0 0 .0 0 0 0 0 0 .0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0T 0 0 0 .0 0 10 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 1 2 1 0 0 3 10 11 95 1 40 113 j0 Il 0 167 Class All IrY 1.000 mph N NNE I NE I E I E I ESE I SisE S ssSW I I wwIw I NNw I TOTAL Calm-0.95 1 1 1 2 0 3 0 1 1. 4 1 3 5 1 .3 .1 28 0.95-3.5 112 145 158 151 147 93 99 103 145. 167 190 . 266 197 118 126 82 2299 3.5-7.5 132 218 149 133 131 94 83 96 244 756 783. .525 576 311, 232 128 4591 7.5-12.5 10 22 15 14 38 13 5 5 67 344 114 19 127 76 22 10 901 12.5-18.5 0 0 2 2 3 2 0 2 10 25 2 0 0 0 0 0 48 18.5-24 0 0 0 0 0 0 0 0 2 0 01 0 0 0 0 0 2

>24 0 0 0 0 0 0 0 0.0 0 0 0 0 0 0 0 0 TOTAL 255 388 3251 302 319 205 187 207 469] 1296 (1090 813 1905 5106 383 221 789 Page. 58

Table A-2 Joint Freq uency Distributionlof Wind Directions and Speeds For the 220-ft level of the -220-ft Tower Jan-Mar 2013 rh IN NNE NE IENEI E EASE SE ISSE S ISSW IS IWSvv W IWNvv NV I.NWl TOTAL Calm-0.95 0 0 0 0 0 0. 0 0 0 0 0 0 0 0 0 0 .0 128 5 4 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 03 1, 11 0 0 0 0 1 0 10 0

.3.5-7:5 0 1 1 0 0 0 0 0 0 0 00 0 0 0 0 0 2 0 0 5 2 0 3 0 0 0 0 0 .0 1 4 5 5 31 7.5-12.5 '1 3.

12 1 2 12.5-18.5 13 0-2 0 0 1 0 0 0. 0 0 0 0 , 0 6 5 8 4 37 18.5-24

>24 0 0 0 0 0 0 0 1 0 0 1 0 0 0 913 2 14 TOTAL T20-1 3 1 1 1 6 1 4 1I "2 0 1 0 1 0 01 0 0 10 I 29 [21 15 112 Class B FreQ 0.035 N NNE INE [ENE[ E 'IESE [SE ISSEISJSS .W SW JWSW W I NW NNW TOTAL Ca.m-7.5 0 10 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 1 0 1 0. 0 0 0 0 0 0 0 1 0 0 .0 3

7.5-12.5 1 1 0 0 1 0 0 0 0 0 0 0 4 1 .2 0 10 12.5-18.5 3 1 0 1 0 0 0 0 1 0 0 0 5 5 3 1 20 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 4 0 0 2. 6

>24 0 0 0 2 0 0 0 0 0 0 0 0 3 3 .0 1 9 TOTAL 4 3 0 4 1 0 0 0 1 0 0 0 17 9 5 4 48 ClassC Fr: 0,043 __= = _ 1 1wI mph N INNNE INE EIE ESEI SE SSE S SSWl*w ws w_ w.wlNWlNNWl TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 1 1 0 0 0 0 0 0 0 0 0 0 0 0 1 3 7.5-12.5 1 1 0 0 2 1 0 0 0 1 1 1 3 1 1 1 14 12.5-18.5 2 0 0 0 0 0 0 0 0 2 0 0 9 6 3 2 24 18.5-24 0 0 0 0 0 1 0 0 0 0 0 0 0 5 -6 1 0 12

>24 0 0 1 0 0 0 0 0 0 0 0 0 0 4 1 0 6 Class D Fr: 0.544 mph N NNE NE ENE E. ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 1 2 0 1 0 0 1 1 0 0 0 0 2 1 9 3.5-7.5. 2 0 4 6 5 8 2 .2 2 3 2 7 5 4 3 2 57.

7.5-12.5 9 4 3 4 6 2 6 4 5 11 6 14 21 18 .'19 5 137 12.5-18.5 6 0 1 2 4 3 11 5 3 13 24 27 74. 34 14 9 230 18.5-24 3 1 6 0 2 0 2 0 4 22 9 12 34 70 21 16 202

>24 2 3 2 4 23 0 0 0 6 14 5 1 5 36 6 6 113 TOTAL 22 1 8 17 18 40 14 I 21 111 21 64 46 61 139 12 5 39 748 Page 59

Table A-2 (continued) .

Jan-Mar 2013 CI*L* F Fren " .250 mph INI NNE*NE ENE E [ESE I S SSW SWWS*. W NIV W NW N TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0. 0 0 0 0 0 0 0.95-3.5 0 0 0 1 0 1 0 0 3 2 1 0 1 0 0 0 9 3.5-7.5 0 1 2 1 0 1 7 4 8 4 4. 1 4 6 5 1 49 7.5-12.5 4. 1 2 1 1 1 3 1 1 9 7 6. 9 17 5 _9 77 12.5-18.5 3 1 0 0 1 0 0 11 2 12 19 22 39 22 13 4 149 18.5-24 1 0 0 0 0 1 0 3 2 0 5 8 10 17 3 2 52

>24 1 0 1 0 2 0 0 0 0 0 0 0 0 4 0 0 8 TOTAL 9 3' 3 4 1 4 1101 19 (161 27 136 [ 37*631 66 [ 26 16 344 Class F FrL 0.039 mph N I NNE I0NE ENE0 IEl SE I SSE1CS S SW[ WSW IWWNW I NWtNNWJ TOTAL Calm-0.95 0 0 0 10 0 10 0 0 0 0 0 0- 0 0 0 0 0 0.95-3.5 1 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 2 3.5-7.5 0 0 0 0 2 0 2 0 1 1 2 2 3 1 3 0 17

.7.5-12.5 0 0 0 0 0 0 0 2 0 4 2 2 7 1 3 0 21 12.5-18.5 0 0 0 0 0 0 0 0 0 0 6 3 4 0 0 0 13 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL I1 0 , o0 2 0 2 21 6 1L0 7 14 2 6 0 53 Class G Fre: 0.007 mph N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 3.5-7.5 0 0 0 0 0 0 0 0 0 2 0 0 0 1 0 0 3 7.5-12.5 0 0 0 0 0 0 0 0 0 1 0 1 2 1 0 0 5 12.5-18.5 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 09 0 1 01 0 1 11 3 10 1 13 2 101 00 10 Class All Fre 1.000 mph N N NEI-E E. ESEISE SSE S I SSW S WSW[W I WNW NW NNW I TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 0 1 3 0 2 0 0 4 4 1 0 2 0 2 1 21 3.5-7.5 2 4 8 8 7 9 11 6 11 10 8 10 13 12 11 4 134 7.5-12.5 20 9 5 8 13 5 11 7 6 26 16 24 47 43 35 20 295 12.5-18.5 27 2 1 4 5 3 11 16 7 27 49 52 137 72 41 20 474 18.5-24 6 1 6 2 3 1 2 3 6 22 14 20 56 104 30 24 300

>24 3 3 4 6 25,0 0 0 6 14 5 1 8 56 10 9 150 TOTAL 59 19 125 31 1 [31 20 1351 32 140 4 03 93 '17 263 28 11291 78 11374 Page 60

Table A-2 (continued)

Apr-Jun 2013 Class A Frej 0.098 mph IN INNE NE IENE E 1 ESE SE SSE S SSW SW Iw lI W WIWWI NW I"NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 1 4 7 4 4 0 0 0 1 0 0 0 2 0 2 0 25 7.5-12.5 4 12 13 7 11 6 1 0 0 1 0 4 3 2 0 4 68 12.5-18.5 12 4 4 2. 2 5 2 1 2 4 2 3 8 5 0 5 61 18.5-24 3 4 0 2 6 0 0 0 2 2 0 0 6 5 2 12 44

>24 0 0 0 0 0 0 0 0. 0 0 0 0 2 0 3 1 6 TOTAL I 20 24 24 15 23 1 3 1I 5 [ [2 7 7 21 1 12 7 2 20 Class B re 0.056 ca hl IN0 NNE1NE5ENE E ESE E SSE S IS TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 1 2 1 0 3 1 0 0 0 0 0 0 0 0 0 0 8 7.5-12.5 0 0 1 0. 5 13 3 1 0 3 4 *6 5 2 0 1 44 12,5-18.5 2 0 0 0 0 2 1 1 7 17 3 2 7 1 0 2 45 18.5-24 0 0 0 1 0 0 0 0 3 5 0 0 1 5 0 1 16

>24 1 0 0 0 0 0 0 0 1 0 0 0 1 0 0 0 3 TOTAL 1412 2 1181 16 1 2412 125171 8 148I07T4 116 Class C Freq 0.073 mph N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 2 3 5 1 5 2 1 0 0 0 0 1 1 2 1 0 24 7.5-12.5 2 1 0 0 3 5 2 0 1 2 8 8 8 1 2 0 43 12.5-18.5 0 0 1 3 0 0 6 1 8 17 4 2 3 3 3 1 52 18.5-24 1 0 0 1 .0 0 0 0 0 13 1 0 5 4 0 1 26

>24 2 1 0 0 0 0 0 0 0 1 0 0 0 1 1 0 6 TOTAL 7 5 5 8I 7 I I 1 9 33 13 I 117 IH I I 151 Class D 0.462 mph_ N_ INEINEIEN_ E IESEI SE S. IA SSW[I SW IWSW] W ]WNWI NW I NNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 2 0 1 1 0 2 1 *0 0 0 0 1 0 1 1 10 3.5-7.5 8 8 12 9 17 12 9 3 3 7 5 5 3 4 7 7 119 7.5-12.5 4 4 5 7 22 22 22 16 12 40 11 16 8 4 1 2 196 12.5-18.5 11 3 13 21 6 14. 10 11 32 114 24 13 22 8 5 7 314 18.5-24 8 3 7 10 7 1 2 3 15 100 19 3 16 22 7 5 228

>24 16 7 6 2 8 2 0 0 3 16 0 0 7 13 4 9 3 TOA [7 271 43]50j61 5 4 _[34 [6527~ 5j3 5 5 25 31 96 Page 61

Table A-2 (continued)

Apr-Jun 2013 rt- r! 1: n Ina mph IN NNE EiENE7 sS S S SSW W NNW__, TO-AL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 2 2 2 2 1 1 3 0 1 1 1 0 0 1 0 0 17 3.5-7.5 1 3 4 8 5 11 5 2 5 2 0 1 1 3 3 0 54 7.5-12.5 7 3 5 3 4 10 15 2 8 7 9 10 4 1 2 7 97 12.5-18.5 2 4 4 2 1 1 8 7 15 22 23 21 17 18 7 1 153 18.5-24 1 1 0 1 0 0 1 3 1 45 14 5 3 12 6 3 96

>24 0 0 0 0 0 0 0 0 0 9 2 1 0 2 2 2 18 TOTAL 1 3 1 13 1151 16 11 23 32 14 30 86 49 [ 38 25 37 20 13 1 435 Class F Fre7 0.081 mph IN 1 NNE INE ENEI E ESE SEI SSE [S SSWJSWlWSvw WW vNw NNW vNWl TOTAL Calm-0.95 0 0 0 0 0 0 .0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 2 0 1 0 1 1 1 1 2 1 0 0 0 1 0 12 3.5-7.5 2 1 0 2 5 5 1 1 1 2 2 *2 1 2 0 0 27 7.5-12.5 1 0 0 0 0 0 7 5 6 3 4 1 2 2 4 3 38 12.5-18.5 0 1 0 0 1 0 0 1 3 .5 10 21 7 7. 3 2 61 18.5-24 1 0 0 0 0 0 0. 0 0 1 19 1 1 2 0 0 25

>24 0 0 0 0 0 0 0 0 0 0 5. 0 0 0 0 TOTAL I5 4 Io0I 3 16I 6 9. 8 11 13 41 I25 1 13I 5 168 Class G Fr:0.022 mph N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0-0.95-3.5 0 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 2 3.5-7.5 1 1 1 0 0 0 0 0 0 0 2 1 2 1 0 1 10 7.5-12.5 0 0 0 0 0 0 0 0 3 0 1 6 1 1 0 0 12 12.5-18.5 0 0 0 0 0 0 0 0 3 0 5 2 6 1 0 0 17 18.5-24 0 0 0 0 0 0 0 0 0 0 4 0 0 0 0 0 4

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 a T 1 - r . . r , . . . . * . .

TOTAL I

... -

1 i i 1

I i1 0 I-oln i o 0 161 2I I 121 9 I nI 3 3- I Io I 1

1 .

45 4

Class All 1.000 mph I N I NNE I NEI ENE E_ ESE I JISSEJI S I SSW ISW IWSW I WIWNW INWI NNW [TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 3 6 2 4 2 2 6 2 2 5 2 0 1 1 2 1 41 3.5-7.5 16 22 30 24 39 31 16 6 10 11 9 10 10 12 13 8 267 7.5-12.5 18 20 24 17 45 56 50 24 30 56 37 51 31 13 9 17 498 12.5-18.5 27 12 22 28 10 22 27 22 70 179 71 64 70 43 18 18 703 18.5-24 14 8 7 15 13 1 3 6 21 166 57 9 32 50 15 22 439

>24 19 8 6 2 8 2 0 0 4 26 7 1 10 16 10 12 131 1 54 TOTAL I97[ 76 1911 90 1117j 114 1021 60 +/-1371 443 1183 135 1 135 1671 78 1 2079 Page 62

Table A-2 (continued)

Jul-Sep 2013 Class A Frea: 0.070 I

mph' IZN]INENIEN I ESEI SE S I SSW SW Iw*w W IWNW NWINNWI TOTAL Calm-0.95I 0 1 0 1 0 1 0 1 0 1 0 0 1 0 0 10 0 1 0 1 .0 1 0 10 0 1 0 0 mo-3.5 1 01 0 1 0 0 0 0 0 a 0 1 ololalalo a a 3.5-7.5 8 11 6 3 6 0 0 0 0 0 0 0 1 0 0 1 36 7.5-12.5 15 5 8 0 9 0 1 0 3 2 0 1 1 3 2 9 59.

12.5-18.5 23 6 2 0 0 1 0 0 0 1 0 0 5 7 3 2 50 18.5-24 6 1 0 0 0 0 0 0 0 0 0 0 1 0 8

>24 0 1 0 0 0 0 0 0 0 0 0 0 0. 0 0 0 11 TOTAL 52 24 11I 3 I1 1 1 1 10 13 [ 3 10 1 I 7= i 10I6 1 12.. 154 Class B FreS 0.019 S r_ _ "

N NE ENE E I S SSW

=SW S I I W IwNvv NW I NW I TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 1 1 1 3 0 0 0 0 0 0 0 0 1 1 0 0 8 7.5-12.5 0 4 0 0 3 0 0. 0 2 0 0 1 6 6 0 1 23 12.5-18.5 2 1 3 0 0 0 0 0 0 1 0 0 0 3 0 0 10 18.5-24 0 1 0 0 0 0 0 0 0 0 0 0 1 0 0 0 2

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL [I I [3 [I0 I0 I0 I2 1 1 8 110 0 [1 43 Class C Fre: 0.052 "h N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 2 1 4 2 4 3 0 0 0 0 1 0 0 5 6 3 31 7.5-12.5 1 1 4 0 0 5 4 1 2 3 2 10 10 4 1 1 49 12.5-18.5 1 3 2 0 0 0 0 0 7 6 4 2 2 0 1 2 30 18.5-24 0 0 0 0 0 0 01 0 1 0 0 0 1 0 1 0 3

>24 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 TOTAL I 65 10 1 2 I _ 8 4 1 1 110I 9 J 7I 1 13. 9 I9 I6I 115 Class D Frea: 0.393 mnh N NNFI NE .I *N* F NNE NEJN E ES I I SE I SS S I SSW I SWI WSW I .. W4 I.WNW. 1 NW:. I NNW __ITOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 9 6 3 1 0 0 0 0 1 0 0 0 1 2 1 1 25 3.5-7.5 8 11 11 15 15 21 6 8 4 10 13 3 6 3 7 9 150 7.5-12.5 7 9 12 9 12 18 26 9 19 58 28 21 21 13 8 10 280 12.5-18.5 6 10 2 0 5 2 0 6 30 132 84 12 8 4 4 3 308 18.5-24 12 16 0 0 0 0 0 0 4 29 12 0 0 7 1 0 81

>24 10 4 0 0 0 0 0 0 0 1 0 0 0 0 0 9 24 TOTAL [52156 78- 25 32 ~i 1 1112I_ W 5 30 17 36 36 2912113 868 Page 63

Table A-2 (continued)

Jul-Sep 2013 Class E FreL 0.313 mp~h N NNE iNEIENE E I_ ESE ISE SSE_ S

_ S WWIN N -S-S OA Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 4 1 3 6 5 2 1 2 3 4 0 0 0 0 1 1 33 3.5-7.5 4 6 4 4 7 10 9 5 4 2 4 9 2 7 5 3 85 7.5-12.5 7 5 2 4 1 5 13 16 11 17 10 16 6 20 10 5 .148 12.5-18.5 6 4 0 0 0 0 3 6 15 74 63 33 45 28 10 8 295 18.5-24 3 3 0 0 0 0 0 2 1 42 40 2 0 10 9 12 124

>24 1 0 0 0 0 0 0 0 0 0 2 0 0 0 0 3 6 TOTAL I25 19 1 91 14 11 72631 1 341 139 11191 60 1531 65 1351 32 1 691 Class F 0.117 mph I N I NNE INE[ ENE I+/-E I S_ SE S S SS SW WSW_ W N W N OA Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 2 0 0 1 2 0 0 1 1 0 1 0 0 1 0 9 3.5-7.5 2 1 1 1 3 3 1 3 0 1 2 0 2 2 3 6 31 7.5-12.5 0 1 0 0 1 1 1 3 7 6 9 *2 4 17 2 9 63 12.5-18.5 1 0 0 0 0 0 2 2 5 16 21 27 23 12 1 114 18.5-24 0 0 0 0 0 0 0 1 0 .5 29 6 0 0 10 0 41

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL I3 I4 11 1 5 6 14 9 3 29 61 1 36 29 31 10 16 258 mph N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.95 0 1 0 0 0 0 0 0 0 0. 1 0 0 0 0 0 2 0.95-3.5 0 0 0 0 0 0 0 0 3 2 2 0 0 1 0 1 9 3.5-7.5 1 2 2 2 1 0 0 0 0 2 3 3 0 0 0 3 19 7.5-12.5 0 0 0 0 0 0 0 0 2 3 3 4 4 1 3 4 24

.12.5-18.5 0 0 0 0 0 0 0 0 0 0 6 5 11 0 0 0 22 18.5-24 0 0 0 0 0 0 0 0 0 0 2 1 0 0 0 0 3

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 11 3 1 2 2 1 1 0o 0 0 5 17 17113 158 79 Class All F 1.000 mph N -NNEINEI ENE E I ESE I SE I SSE IS ISSW ISW j WSW jW WN JN NNW jTOTAL_

Calm-0.95 0 1 .0 0 0 0 0 0 0 0 1 0 0 0 0 0 2 0.95-3.5 13 9 6 7 6 4 1 2 8 7 2 1 1 3 3 3 76 3.5-7.5 26 33 29 30 36 37 16 16 8 15 23 15 12 18 .21 25 360 7.5-12.5 30 25 26 13 26 29 45 29 46 89 52 55 52 64 26 39 646 12.5-18.5 39 24 9 0 5 3 5 14 57 230 178 79 94 54 22 16 829 18.5-24 21 21 0 0 0 0 0 3 6 76 83 9 2 17 12 12 262

>24 12 6 0 0 0 -0 0 0 01 1 2 0 0 0 0 12 33 TOTAL 1141 19 17050 1731 73 16 7 1 64 1125 1 418 134 11 159 1161 1 156 184 1 107 2208 Page 64

Table A-2 (continued)

Oct-Dec 2013 Class A F 0.043 mph I N INNEI NE IENEI E IESE SE I SSEI S Issw SW Iwswl W IvNw NWI INNwl TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 .0 0 0 3.5-7.5 1 1 5 1 1 0 0 0 0 0 0 0 0 1 0 1 11 7.5-12.5 2 5 9 1 3 0 0 0 0 0 0 0 1 4 2 0 27 12.5-18.5 7 3 5 2 0 0 0 0 0 1 2 0 12 4 1 5 42 18.5-24 5 2 1 1 0 0 0 0 0 0 0 0 1 2 0 1 13

>24 1 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 3 TOTAL 116 1 20 5 410 01010 13 12 0 14I ". 1'. 1. 96 Class B Freq 0.022 maph N NNEl NE IENEI E IESE SE ISSEI S Isswl SW IWSW W IWvNWNNW I[NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 1 0 0 0 0 0 0 0 0 1 0 1 1 4 7.5-12.5 1 0 1 1 0 1 0 0 0 0 0 2 0 3 0 0 10 0 0 0 1 3 4 5 0 3 22 12.5-18.5 1 3 0 2 0 0 0 18.5-24 0 1 1 4 0 0 0 0 0 0 0 0 1 0 0 2 9 d24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 2 1 4 TOTAL I2 4' 2 18 1 1 0 I0 I0 10 1 I 5 1 6 9 317 '

Class C 0.025 mph N INNEI NE ENEI E IESEI SE ] SSE I S 1SSW SW IWSW W IWNWI NW NNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 1 2 1 0 0 0 0 0 0 0 0 2 0 0 6 7.5-12.5 0 0 2 0 0 0 0 0 0 2 2 4 1 1 0 0 12 12.5-18.5 0 0 0 0 1 0 0 0 0 3 2 2 5 2 4 1 20 18.5-24 0 0 0 1 0 0 0 0 0 0 0 0 2 2 5 3 13

>24 0 0 0 a 0 0 0 0 0 0 0 3 2 0 5 TOTAL 0 0 I I I2 I0 0 0 0 _5 1 8 10 11 4 56 Class D F 0.509 --

mph N NNE NE ENE E ESE SE SSE S SSW SW WSW W. WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 3 0 4 1 1 1 0 0 0 0 0 0 0 1 1 1 0 12 3.5-7.5 10 5 12 2 2 3 2 2 2 2 5 4 5 4 7 8 75 7.5-12.5 11 4 16 6 2 2 5 6 10 19 39 26 24 18 24 16 228 12.5-18.5 6 3 2 18 7 7 28 21 6 55 37 59 87 39 43 17 435 18.5-24 8 3 1 12 10 1 2 5 10 25 19 6 30 52 53 27 264

>24 12 0 0 0 13 1 0 0 0 3 4 0 12 32 23 9 109

-0 39 37 10 1 - 1 -5 -

TTL 50 15 35 39 35 15 137 34_ 28 1104 104 9541158 1468 151 177 1123 Page 65

Table A-2 (continued)

Oct-Dec 2013 Class E Frea. 0.314 mph N INNE NE IENEI E IESEI SE ISSE I S ISSW I SW IWSw W IWNWI NW INNWl TOTAL Calm-0.95 0 .0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 1 2 0 1 2 3 0 0 0 1 0 0 0 1 2 0 12 3.5-7.5 7 1 9 3 7 1 4 1 2 1 1 5 8 5 5 6 66 7.5-12.5 2 8 6 8 11 1 6 16 7 20 27 24 19 18 7 6 186 12.5-18.5 1 3 5 14 4 4 17 17 11 26 52 44 72 22 13 5 310 18.5-24 1 1 5 0 0 1 1 1 6 18 23 3 21 14 0 2 97

>24 0 0 0 0 3 1 5 4 3 0 1 1 0 2 2 1 23 TOTAL 11 14 27 25I 26 10 316A 3=9 29 65 1105 177 120 161 29 [ 201 694 Class F Freq 0.071 mph I NINNE N IENE E IESEI SE I SSE I S ISSWISW WSw W IWNWI NW INNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 3 2 1 0 1 0 0 0 0 0 0 1 0 0 0 0 8 3:5-7.5 0 0 0 4 2 0 1 2 2 2 0 2 3 4 2 0 24 7.5-12.5 0 0 0 0 0 1 1 7 6 2 5 4 3 4 5 1 39 12.5-18.5 0 0 0 0 0 0 V 4 5 5 12 23 16 7 0 0 73 18.5-24 0 0 0 0 0 0 0 0 0 2 8 1 1 0 0 0 12

>24 0 0 0 TOA0 2 1 04 3 I10 I30 I130 I130 I110 I261 I310 I230 I150 I-7f0 0 0 1 1 I 157; Class G Freq 0.015 mph N INNE NEIENEI E ESEI SE SSEI S ISSW SW IWSWI W IWNWI NW INNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1 0.95-3.5 0 0 1 0 1 1 0 1 0 0 0 1 1 2 2 0 10 3.5-7.5 0 0 0 1 1 1 0 1 0 3 1 0 1 0 0 0 9 7.5-12.5 0 0 0 0 0 0 0 0 0 0 1 1 1 3 0 0 6 12.5-18.5 0 0 0 0 0 0 0 0 1 0 1 0 5 0 0 0 7 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL o 01111 212[0l2 1[ 31 10 33 Class All Fr 1.000 mph N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1 0.95-3.5 6 3 8 1 4 4 3 1 0 0 1 2 1 3 5 0 42 3.5-7.5 18 7 27 14 14 5 7 6 6 8 7 11 18 16 15 16 195 7.5-12.5 16 17 34 16 17 5 12 29 23 43 74 61 49 51 38 23 508 12.5-18.5 15 12 12 36 12 11 46 42 23 90 107 131 201 79 61 31 909 18.5-24 14 7 8 18 10 2 3 6 16 45 50 10 56 70 58 35 408

>24 13 0 0 0 16 2 5 4 3 5 6 1 12 38 29 11 145 TOTAL 82 46 89 85 73 29 76 88 71 191 245 216 337 258 206 116 2208 Page 66

Table A-2 (continued)

Jan-Dec 2013 Class A Fre: 0.072 mDh N INNE[NIE N. E ESE SE SSE S Issw SW IWSWl w NW INNNW TOTAL Calm-0.95 0 0 0 0 0 00 . 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 10 17 19 8 11 0 0 0 1 0 0 0 3 1 2 2 74 7.5-12.5 26 24 30 11 26 7 4 0 3 3 0 5 6 13 9 18 185 12.5-18.5 55 13 11 5 2 6 2 1 2 6 4 3 31 21 12 16 190 18.5-24 16 7 1 5 7 0 0 0 2 2 0 0 10 18 8 17 93

>24 1 TOTAL I108 62 1 0 61 0

29 1 46 0 .0 13 I6 0

1I8 0 0 I13 2 0 4

0 8 52 2 9 62 6

3 I 3 24 56 6 Class B Fre: 0.033

.m Ph ININNEI NE ENEE E IESEI SE*ISSEI S ISSWvI SW IWSWJ WJ WI TOTAL "NWNNWl Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

,3.5-7.5 2 4 2 5 3 1 0 0 0 0 0 0 3 1 1 1 23 7.5-12.5 2 5 2 1 10 14 3 1 2 3 4 9 15 12 2 2 87 12.5-18.5 8 .5 3. 3 0 2 1 1 8 18 4 5 16 14 3 6 .97 18.5-24 0 2 1 5 0 0 0 013 5 0 0 7 5 0 5 33

>24. 1, 0 0 2 0 0 0 0 1 0 0 0 4 4 2 2 16 TOTAL. I 13 161 8 Ie16 13 17 4 12 14 [26 [8 114 45 36 I8I 1 256 Class C Fre 0.048 mph N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 4 5 11 5 10 5 1 0 0 0 1 1 1 9 7 4 64 7.5-12.5 4 3 6 0 5 11 6 1 3 8 13 23 22 7 4 2 118 12.5-18.5 3 3 3 3 1 0 6 1 15 28 10 6 19 11 11 6 126 18.5-24 1 0 0 2 0 0 0 0 1 13 1 0 13 12 7 4 54

>24 3 2 1 0 0 0 0 0 0 1 0 0 0 8 4 0 19 TOTAL 15 13 21 10 16 16 13 2 19 50 25 30 55 47 133 16j 381 Class D F 0.470

m. h N NI. N EI NE EI E E ESE I SE I SSE I S ISSWSW WSW l w W w v JNW I.vlN TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 12 8 8 5 2 2 2 1 2 1" 0 0 2 3 5 3 56 3.5-7.5 28 24 39 32 39 44 19 15 11 22 25 19 19 15 24 26 401 7.5-12.5 31 21 36 26 42 44 59 35 46 128" 84 77 74 53" 52 33 841 12.5-18.5 29 16 18 41 22 26 49 43 71 314 169 111 191 85 66 36 1287 18.5-24 31 23 14 22 19 2 6 8 33 176 59 21 80 151 82 48 775

>24 40 14 8 6 44 3 0 0 9 34 " 9 1 24 81 33 33 339 TOTAL 1j171 10 1123 1132 118 1121 1135 102 172 675 1346 1229 390 13I 1 262 1179 3699 Page 67

Table A-2 (continued)

Jan-Dec 2013 Class E 0.275 mph INI NNEN* ENE IE IESE sE ISSEI I ssw sw wsw w vWNW NW NN TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 6 4 7 9 7 6 7 2 7 7 3 0 1 1 3 1 71 3.5-7.5 12 11 19 16 19 23 25 12 19 9 9 16 15 21 18 10 254 7.5-12.5 20 17 15 16 17 17 37 35 27 53 53 56 38 56 24 27 508 12.5-18.5 12 12 9 16 6 5 28 41 43 134 157 120 173 90 43 18 907 18.5-24 6 5 5 1 0 2 2 9 10 105 82 18 34 53 18 19 369

>24 2 0 1 0 5 1 5 4 3 9 5 2 0 8 4 6 55 TOTAL 1 58 49 1561 1 54 1 54 I1041 10311091 317 13091 212 12611 229 I101 81 [ 2164 Class F F 0.081 p __ N ENE ESE SE SS S SSW SW WSW W I WNW I N.W I TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 5 6 1 1 2 3 1 1 2 4 1 2 0 0 2 0 31 3.5-7.5 4 2 1 7 12 8 5 6 4 6 6 6 9 9 8 6 99 7.5-12.5 1 1 0 0 1 2 9 17 19 15 20 9 16 24 14 13 161 12.5-18.5 1 1 0 0 1 0 3 7 13 26 49 74 50 26 7 3 261 2 2 0 0 78 1 0 8 56 8

>24 01 0 0 0 0 0 0 0 0 0 0 0 0 6 0 0 0 0 0 6 18.5-24 TOTAL l 12 I 10 I 2II 8 16 118 32 78 59 11381 I9977 1 61 131 1636 Class G FrL 0.021 mph N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL Calm-0.95 0 1 0 0 0 0 0 0 0 0 1 0 0 1 0 0 3 0.95-3.5 0 0 1 0 1 1 0 1 3 4 2 1 2 3 2 1 22 3.5-7.5 2 3 3 3 2 1 0 1 0 7 6 4 3 2 0 4 41 7.5-12.5 0 0 0 0 0 0 0 0 5 4 5 12 8 6 3 4 47 12.5-18.5 0 0 0 0 0 0 0 0 5 0 12 7 22 1 0 0 47 18.5-24 0 0 0 0 0 0 0 0 0 0 6 1 0 0 0 0 7

>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 21414 1 31 3 21012 15 32 25 35 13 5 9I 167 Class All 1.000 mph IN INNE INEIENE IE IESE SEI SSE S SSW ISW IWSW I W WNW IIN WI TOTAL Calm-0.95 0 1 0 0 0 0 0 0 0 0 1 0 0 1 0 0 3 0.95-3.5 23 18 17 15 12 12 10 5 14 16 6 3 5 7 12 5 180 3.5-7.5 62 66 94 76 96 82 50 34 35 44 '47 46 53 58 60 53 956 7.5-12.5 84 71 89 54 101 95 118 89 105 214 179 191 179 171 108 99 1947 12.5-18.5 108 50 44 68 32 39 89 94 157 526 405 326 502 248 142 85 2915 18.5-24 55 37 21 35 26 4 8 18 49 309 204 48 1 115 93 1409

>24 47 17 10 8 49 4 5 4 13 48 20 3 :30 110 49 44 459 TOTAL [ 370 260 12756 L6O 13161 23 280[ 244 373 1155 1862 [ 1 1915 836 14861 379 I786 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 inside the protected area fence during the fourth quarter of 2007. The first samples were collected in November 2007. 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. Two pre-existing wells were incorporated into the groundwater monitoring program in early 2008. Additional wells were added to the program in 2010 (12 wells), 2011 (2 wells), 2012 (1 well), and 2013 (3 wells). A total of 22 wells are being sampled on a routine basis.

In addition to sampling the onsite monitoring wells, samples of surface water are collected from two locations in the PNPS Intake Canal. These locations are along the shoreline in the same direction as the groundwater flow gradient.

All samples collected are analyzed for tritium, a radioactive isotope of hydrogen, and also for gamma emitting radionuclides. 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. Low levels of tritium were detected in the many of the onsite wells. Although gamma spectroscopy 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 groundwater samples, other than tritium. 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 demonstrates the ability of the gamma spectroscopy analyses to detect radioactivity in groundwater. Analyses are also performed for hard-to-detect radionuclides, including Iron-55, Nickel-63, Strontium-89, and Strontium-90 on a less frequent basis. These hard-to-detect radionuclides were also non-detectable in all of the wells sampled and analyzed during 2013.

A summary of the results of the tritium analyses conducted in 2013 are presented in the following table. In this table, 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 MW201 on 30-Apr-2013 contained no detectable tritium, and a minimum

.detectable concentration of 333 pCi/L was achieved on that sample. The achieved sensitivity of 333 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 No plant-related radioactivity (other than tritium) was detected in any of the monitoring wells, and no tritium or plant-related radioactivity was detected in surface water samples collected from the intake canal.

Page 69

Monitoring Well Installation Number of J Number of Positive Minimum Concentration Maximum Concentration M o Date W I Samples Results pCi/L pCi/L MW201 Nov-2007 28 5 NDA < 333 540 MW202 Nov-2007 4 3 NDA < 372 1010 MW202-1 Apr-2010 4 4 474 833 MW203 Nov-2007 2 0 NDA < 422 NDA < 425 MW204 Nov-2007 4 0 NDA < 369 NDA < 427 MW205 Apr-2010 28 22 NDA < 351 3080 MW206 Apr-2010 28 16 NDA < 337 3590 MW207 Apr-2010 4 0 NDA < 366 NDA < 453 MW208-S Apr-2010 4 0 NDA < 369 NDA < 427 MW208-1 Apr-2010 4 0 NDA < 369 NDA < 426 MW209 Aug-2010 41 40 NDA < 430 1370 MW210 Aug-2010 4 4 428 1580 MW211 Aug-2010 44 44 665 1580 MW212 Aug-2010 4 2 NDA < 373 560 MW213 Aug-2010 4 0 NDA < 367 NDA < 423 MW214 Aug-2010 4 0 NDA < 370 NDA < 437 MW215 Dec-2011 28 28 587 1450 MW216 Sep-2012 52 52 630 8700 MW217 Dec-2011 4 3 , NDA < 373 492 MW218 Nov-2013 7 7 2630 5810 MW219 Dec-2013 4 4 2120 69000 MW3 Jul-1987 4 0 NDA < 358 NDA < 426 MW4 Jul-1997 4 4 460 762 MW4-R Nov-2013 7 7 451 724 All Wells - 321 245 NDA < 333 69000 Intake Canal West -- 27 0 NDA < 308 NDA < 439 Intake Canal East - 4 0 NDA < 356 NDA < 432 Concentrations of tritium detected in the onsite wells ranged from non-detectable at less than 333 pCi/L, up to a maximum concentration of 69,000 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-216 (average concentration = 4083 pCi/L) was consumed as drinking water for an entire year, the maximum dose consequence would be less than 0.35 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 at the Pilgrim Station site.

Page 70

Although there are no indications that the groundwater containing detectable 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 2013, 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 potential 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 ranges from 0.002 cm/sec to about 0.006 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 segment-weighted average concentration of 571 pCi/L, the annual discharge of tritium into the intake bay under this hypothetical scenario would be 0.00714 Curies. This activity represents less than 0.011% 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 0.00714 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 2013 was 565 billion Liters, yielding an effective concentration of tritium in the intake bay of about 0.013 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 0.0000000072 millirem, resulting from ingestion of 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 discharge volumes, average tritium concentrations, and hypothetical tritium discharges are listed for each shoreline segment represented by each monitoring well. Although all four samples collected from monitoring well MW204 indicated no detectable activity, for purposes of conservatism the well was assumed to contain tritium at the average of the detection limits achieved on the four quarterly samples.

Page'71

Shoreline Segment Number 1 2 3 1 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 9.61E+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. im 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 3.79E+02 3.67E+03 9.90E+02 6.50E+02 Annual Segment Tritium Discharge - Ci/yr 6.09E-04 7.91E-03 1.88E-03 4.44E-03 Total Volumetric Discharge - L/yr 1.25E+07 Total H-3 Discharge - Ci/yr 7.14E-03 Annual Circulating Water Flow - Liter/yr 5.65E+1 1 Discharge Canal H-3 Concentration - Ci/L 1.27E-14 Discharge Canal H-3 Concentration - pCi/L 1.27E-02 VMax. Indiv. Dose Factor - mrem/yr per Ci/L 5.73E+05 Maximum Individual Dose - mrem/yr 7.24E-09 In March 2013, four permitted discharge of radioactive water were made from the neutralizing sump via the neutralizing sump discharge line that exits the west side of the Auxiliary Building and runs underground to storm drain Catch Basin #10. During the fourth discharge on 25-Mar-2013, water was observed emanating from a conduit that enters the Auxiliary Building from the west side of the building. The release was terminated, and water flow from the conduit stopped. A chemical and radiological analysis of the water from the conduit indicated the water chemistry matched that being discharged from the neutralizing sump. Due to the nature of this event, a voluntary communication was made to notify the NRC and stakeholders of this abnormal event. The line'was isolated to prevent- any additional releases from the line. This event was entered into Pilgrim, Station's 1OCFR50.75(g) decommissioning database. The only radioactivity detected in this wastewater was tritium. As part of the impact assessment, a worst-case bounding calculation was made that 38,410 gallons of wastewater containing 0.34 Curies of tritium was released into the groundwater.

This groundwater was assumed to migrate into the saltwater environment of the Pilgrim Station Intake Canal and Cape Cod Bay. Since there are no drinking water wells affected by the presumed leak of this wastewater to the groundwater, the dose impact was determined from ingestion of contaminated fish and shellfish that accumulated tritium from the seawater after it had passed through the circulating pumps. Using such worst-case assumptions, the calculated dose from this event was estimated at 0.00000034 mrem/yr.

In April 2013, an internal inspection of the neutralizing sump discharge line identified a separation in the line approximately 5-feet below the ground surface where the line exits the foundation of the building. The inspection also identified two additional anomalies in the line closer to where it terminates in Catch Basin #10. The locations of the line separation and the two anomalies were excavated in July 2013 to inspect the condition of the line and collect soil samples for radioactivity analyses. The line was found to be intact at the two anomalies, and soil samples collected in the vicinity of these anomalies was non-detectable for plant-related radioactivity, including tritium, gamma emitters, and hard-to-detect radionuclides. However, in the soil immediately adjacent to the line separation, low levels of plant-related gamma activity were identified in the soil. Tritium was also detected in the water contained in the soil at this location, at concentrations lower than

. Page 72

that assumed to have leaked from the line during the March discharge. All of the radiological survey information was entered into Pilgrim Station's 10CFR50.75(g) decommissioning database, and another voluntary notification was made to the NRC and interested stakeholders. Because the neutralizing sump discharge line was still intact at the location of the separation, it was determined that most of the volume discharged during the four permitted releases in March 2013 would have continued to flow down the line to Catch Basin #10, as originally intended. The original bounding calculation assuming over 38,000 gallons of contaminated water entering the groundwater was very conservative, as the actual volume entering the soil at the line separation was much smaller, most likely less than a few hundred gallons. Increased well sampling throughout 2013 at monitoring wells downgradient of the line separation have not identified any increased concentrations of tritium, and no gamma activity has been identified in any well samples. The gamma nuclides identified tend to chemically bind to the soil particles, and likely moved only a few inches from the location of the separation. This would explain why the activity would not reach the groundwater at a depth of about 18-feet below the ground surface, or 13-feet below the line separation. Since there is no evidence of this gamma activity having entered the groundwater, no ingestion exposure pathways exist for this radioactivity.

Due to these events involving the neutralizing sump discharge line, two new wells were installed in November and December of 2013 to further characterize the movement of tritiated water along the west side of the building. MW218 was installed downgradient of the line separation to monitor for radioactivity entering the groundwater from this location. MW219 was installed immediately adjacent to Catch Basin #10 to monitor for any potential leakage from this catch basin. Tritium results from these wells are listed in the earlier tables.

In the case of MW218 downgradient of the neutralizing sump discharge line separation, the tritium concentrations have been ranging from 1550 pCi/L to 5810 pCi/L. The concentrations in this well immediately downgradient of the line separation are significantly less than the concentration of tritium contained in the permitted discharges. Based on these results, it does not appear that any significant fraction of the discharges actually made it to the groundwater.

In October 2013, a temporary discharge hose was put into place to facilitate continued permitted discharges from the neutralizing sump, since the original discharge line was isolated in March-2013. One such discharge was made in October, and three discharges occurred in December, the latest on 20-Dec-2013, about 9-days after MW219 was installed. The sample collected on 30-Dec from MW219, approximately 10-days following the permitted discharge into Catch Basin #10, indicated a.tritium concentration of 69,000 pCi/L. The time delay between the permitted discharge and the elevated tritium result is consistent with the groundwater moving about 4-feet from the catch basin to the well at a rate of about 6-inches/day. The information surrounding this event was entered into Pilgrim Station's 10CFR50.75(g) decommissioning database, and another voluntary notification was made to the NRC and interested stakeholders. No elevated tritium concentrations have been detected at additional wells downgradient of MW219, indicating that the concentration of 69,000 pCi/L is very localized in the vicinity of MW219, and becomes diluted within a short distance of Catch Basin #10.

A bounding calculation was performed to assess the potential dose impact from leakage occurring from Catch Basin #10. It is assumed that 280 gallons of water containing tritium at a concentration of 550,000 pCi/L leaked from the catch basin from the discharges that occurred in Dec-2013.

Based on groundwater flow rates, it would take approximately 18-months for this tritium to reach the saltwater environment at the Pilgrims Station Intake Canal. Over that time period, the tritium would be diluted by the groundwater flowing through the area, resulting in a maximum diluted concentration of about 170 pCi/L upon entry into the seawater. Since there are no drinking water wells affected by the presumed leak of this wastewater to the groundwater, the dose impact was determined from ingestion of contaminated fish and shellfish that accumulated tritium from the seawater after it had passed through the circulating pumps. Using such worst-case assumptions, the calculated dose from this event was estimated at 0.00000000059 mrem/yr.

Page 73

In conclusion, the only radionuclide detected in groundwater during the 2013 monitoring effort that is attributable to Pilgrim Station operations is tritium. Even in the case of the three reportable events that occurred in 2013, the total dose impact to a maximally-exposed member of the public would have been much less than 1 mrem/yr.

Page 74

APPENDIX C CORRECTIONS TO PREVIOUS EFFLUENT REPORTS There were no corrections to past effluent reports to include in the 2013 annual report.

Page.75

APPENDIX D CHANGES TO PNPS OFFSITE DOSE CALCULATION MANUAL No revisions were made to the PNPS Offsite Dose Calculation Manual (ODCM) during calendar year 2013.

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@@ Line 16: / Line 16: @@
 =Text=
-{{#Wiki_filter:S'Entergy Entergy Nuclear Operations, Inc.600 Rocky Hill Road Plymouth, MA 02360 Pilgrim Nuclear Power Station May 15, 2014 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555'
+{{#Wiki_filter:S'Entergy                                                                                       Entergy Nuclear Operations, Inc.
+Rocky Hill Road Plymouth, MA 02360 Pilgrim Nuclear Power Station May 15, 2014 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
+     '
 ==SUBJECT:==
-Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station Docket No.: 50-293 License No.: DPR-35.Annual Radioactive.Effluent Release Report for January 1 through .December 31,,2013 LETTER NUMBER: 2.14.039
+Entergy Nuclear Operations, Inc.
+Pilgrim Nuclear Power Station Docket No.: 50-293 License No.: DPR-35.
+Annual Radioactive.Effluent Release Report for January 1 through .December 31,,2013 LETTER NUMBER: 2.14.039
 ==Dear Sir or Madam:==
-In accordance with Pilgrim Technical Specification 5.6.3, Entergy Nuclear Operations,;
-Inc submits the attached Annual Radioactive Effluent Release Report for January 1, 2013 through December 31, 2013.This letter contains no commitments.
+In accordance with Pilgrim Technical Specification 5.6.3, Entergy Nuclear Operations,; Inc submits the attached Annual Radioactive Effluent Release Report for January 1, 2013 through December 31, 2013.
-Should you have questions or require additional information, I can be contacted at (508) 830-,8403.Sincerely, Joseph R Lynch i Manager, Regulatory'Assurance
+This letter contains no commitments.
+Should you have questions or require additional information, I can be contacted at (508) 830-
+     ,8403.
+Sincerely, Joseph R Lynch i Manager, Regulatory'Assurance
 ==Attachment:==
+Pilgrim Annual Radioactive Effluent Release Report for January 1, 2013 through December 31, 2013 cc:  U.S. Nucl:ear Regulatory Commission             Ms. Nadiya.h Morgan, P.roje ct Manager Region 1                                        Division of Operating Reactor Licensing 2100 Renaissance- Blvd, .Suite 100              Office of Nu&#xfd;lear: Re&#xfd;ctor Regulation King of Prussia, PA 19406-2713..                U.Sr.Nuclea Regulatory.Commission Mail..Stop- O-8-F2,                 .
+Rockvil e Pike; USNRC Senior Resident- Inspector Pilgrim Nuclear.Power Station'                  Rockvill, MM`2852
+                                                                            . .. .....: . .,* .
+                                                                                                                 ."   .    "8
-Pilgrim Annual Radioactive Effluent Release Report for January 1, 2013 through December 31, 2013 cc: U.S. Nucl:ear Regulatory Commission Region 1 2100 Renaissance-Blvd, .Suite 100 King of Prussia, PA 19406-2713..
+Attachment I Letter Number 2.14.039 Pilgrim Annual Radioactive Effluent Release Report for January 1, 2013 through December 31, 2013
-USNRC Senior Resident-Inspector Pilgrim Nuclear.Power Station'Ms. Nadiya.h Morgan, P.roje ct Manager Division of Operating Reactor Licensing Office of Nu&#xfd;lear: Re&#xfd;ctor Regulation U.Sr.Nuclea Regulatory .Commission Mail..Stop-O-8-F2, .11555 Rockvil e Pike;Rockvill, MM`2852." ."8........... :
-Attachment I Letter Number 2.14.039 Pilgrim Annual Radioactive Effluent Release Report for January 1, 2013 through December 31, 2013 PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 Annual Radioactive Effluent Release Report January 1 through December 31, 2013
+PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 Annual Radioactive Effluent Release Report January 1 through December 31, 2013
-*En tergy PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2013 A,- 6/&#xfd;Prepared by: Reviewed by Reviewed by onl- mxv -270W, K.-J. ora C -SeniVr HP/Chemistry Specialist Chemistry Manager ad1tioBroewer Radiation Protection Manager Page 2'M Gok,;,
-Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report January-December 2013 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 A APPENDIX B APPENDIX C APPENDIX D SECTION TITLE EXECUTIVE
+            *En tergy PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2013 Prepared by:   A,-
+K.-J.
+/&#xfd;ora C        -
+onl- mxv -270W, SeniVr HP/Chemistry Specialist Reviewed by
+                        *..Blanlkenbil~ler..   -*--.,
+Chemistry Manager Reviewed by ad1tioBroewer Radiation Protection Manager Page 2
+                                        'M      Gok,;,
+Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report January-December 2013 TABLE OF CONTENTS SECTION   SECTION TITLE                                      PAGE 1.0   EXECUTIVE
 ==SUMMARY==
-RADIOACTIVE EFFLUENT DATA Supplemental Effluent.
+2.0   RADIOACTIVE EFFLUENT DATA                            8 2.1   Supplemental Effluent. Release Data                  8 2.2   Gaseous Effluent Data                                8 2.3   Liquid Effluent Data                                 9 3.0   METEOROLOGICAL DATA                                 19 4.0   MAXIMUM INDIVIDUAL DOSES                            20 4.1   Doses From Noble Gas Releases                       20
-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 20 22 28 34 37 37 40 43 45 46 47 48 69 75 76.Page 3 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Jan-Dec 2013 LIST OF TABLES TABLE TABLE TITLE PAGE 2.1 Supplemental Information 10 2.2-A Gaseous Effluents
+* 4.2   Doses From Gaseous Effluent Releases                22 4.3   Doses From Liquid Effluent Releases                 28 5.0   OFFSITE AMBIENT RADIATION MEASUREMENTS              34 6.0   PERCENT OF oDCM EFFLUENT CONTROL LIMITS             37 6.1   Gaseous Effluent Releases                           37 6.2   Liquid Effluent Releases                            40 7.0   RADIOACTIVE WASTE DISPOSAL DATA                     43 8.0   OFFSITE DOSE CALCULATION MANUAL REVISIONS           45 9.0   PROCESS CONTROL PROGRAM REVISIONS                   46
--Summation of All Releases 11 2.2-B Gaseous Effluents
--Elevated Releases 12 2.2-C Gaseous Effluents
+==10.0   REFERENCES==
--Ground Level Releases 14 2.3-A Liquid Effluents
+APPENDIX A Meteorological Joint Frequency Distributions        48 APPENDIX B Onsite Groundwater Monitoring Program               69 APPENDIX C Corrections to Previous Effluent Reports            75 APPENDIX D Changes to PNPS Offsite Dose Calculation Manual     76
--Summation of All Releases 16 2.3-B Liquid Effluents 17 4.1 Maximum Doses from Noble Gas Releases During 2013 21 4.2-A Maximum Individual Organ Doses from Gaseous Effluents 23 Jan-Mar 2013 4.2-B Maximum Individual Organ Doses from Gaseous Effluents 24 Apr-Jun 2013 4.2-C Maximum Individual Organ Doses from Gaseous Effluents 25 Jul-Sep 2013 4.2-D Maximum Individual Organ Doses from Gaseous Effluents 26 Oct-Dec 2013 4.2-E Maximum Individual Organ Doses from Gaseous Effluents 27 Jan-Dec 2013 4.3-A Maximum Individual Organ Doses from Liquid Effluents 29 Jan-Mar 2013 4.3-B Maximum Individual Organ Doses from Liquid Effluents 30 Apr-Jun 2013 4.3-C Maximum Individual Organ Doses from Liquid Effluents 31 Jul-Sep 2013 4.3-D Maximum Individual Organ Doses from Liquid Effluents 32 Oct-Dec 2013 4.3-E Maximum Individual Organ Doses from Liquid Effluents' 33 Jan-Dec 2013 5.0 Average TLD Exposures by Distance Zone During 2013 36 6.1 Percent of ODCM Effluent Control Limits for Gaseous Effluent 38 Releases During 2013 6.2 Percent of ODCM Effluent Control Limits for Liquid Effluent Releases 41 During 2013 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
+                                    .Page 3
+Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Jan-Dec 2013 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 2013                     21 4.2-A Maximum Individual Organ Doses from Gaseous Effluents                 23 Jan-Mar 2013 4.2-B Maximum Individual Organ Doses from Gaseous Effluents                 24 Apr-Jun 2013 4.2-C Maximum Individual Organ Doses from Gaseous Effluents                 25 Jul-Sep 2013 4.2-D Maximum Individual Organ Doses from Gaseous Effluents                 26 Oct-Dec 2013 4.2-E Maximum Individual Organ Doses from Gaseous Effluents                 27 Jan-Dec 2013 4.3-A Maximum Individual Organ Doses from Liquid Effluents                  29 Jan-Mar 2013 4.3-B Maximum Individual Organ Doses from Liquid Effluents                  30 Apr-Jun 2013 4.3-C Maximum Individual Organ Doses from Liquid Effluents                  31 Jul-Sep 2013 4.3-D Maximum Individual Organ Doses from Liquid Effluents                  32 Oct-Dec 2013 4.3-E Maximum Individual Organ Doses from Liquid Effluents'                 33 Jan-Dec 2013 5.0  Average TLD Exposures by Distance Zone During 2013                    36 6.1  Percent of ODCM Effluent Control Limits for Gaseous Effluent          38 Releases During 2013 6.2  Percent of ODCM Effluent Control Limits for Liquid Effluent Releases  41 During 2013 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 31,2013 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, 2013. 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". This document has been prepared in accordance with the requirements of PNPS Technical Specifications section 5.6.3.The quantity of radioactive material released from PNPS was determined from sample analyses and continuous 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 0.29 Curies. Releases of radioactive iodines and particulates with half-life of greater than 8 days totaled 0.0027 Curies, tritium releases totaled 64 Curies, and carbon-14 totaled 6.3 Curies. No gross alpha radioactivity was detected in gaseous effluents.
+PILGRIM NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31,2013 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, 2013. 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". This document has been prepared in accordance with the requirements of PNPS Technical Specifications section 5.6.3.
-Noble gases released in gaseous effluents resulted in a maximum total body dose of 0.0000021 mrem, with a corresponding skin dose of 0.0000049 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 0.032 mrem. The maximum hypothetical dose to any organ from radioactive particulates, iodines, tritium, and carbon-14 was about 0.066 mrem. The maximum, hypothetical total body dose from the combined release of all airborne radioactivity in gaseous effluents was 0.032 mrem.The maximum individual doses from gaseous radioactive effluents were compared to the-applicable ODCM dose limits. Noble gas doses were less than 0.000065%
+The quantity of radioactive material released from PNPS was determined from sample analyses and continuous 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.
-of the corresponding 1 OCFR50 dose objectives.
+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.
-Maximum doses resulting from releases of particulates, iodines, tritium, and carbon-14 in gaseous effluents were less than 0.44% of corresponding 10CFR50 objectives.
+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 0.29 Curies. Releases of radioactive iodines and particulates with half-life of greater than 8 days totaled 0.0027 Curies, tritium releases totaled 64 Curies, and carbon-14 totaled 6.3 Curies. No gross alpha radioactivity was detected in gaseous effluents.
-Page 5 LIQUID EFFLUENTS Liquid radioactive releases for the reporting period are quantified in Tables 2.3-A and 2.3-B.Twenty-one discharges of liquid effluents containing, radioactivity occurred during the reporting period. These discharges contained 6.2 Curies of tritium, and 0.019 Curies of fission and activation products.
+Noble gases released in gaseous effluents resulted in a maximum total body dose of 0.0000021 mrem, with a corresponding skin dose of 0.0000049 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 0.032 mrem. The maximum hypothetical dose to any organ from radioactive particulates, iodines, tritium, and carbon-14 was about 0.066 mrem. The maximum, hypothetical total body dose from the combined release of all airborne radioactivity in gaseous effluents was 0.032 mrem.
-The resulting maximum total body dose was 0.0027 mrem, with a corresponding organ dose of 0.0096 mrem. All doses from liquid discharges were less than 0.25%of corresponding 10CFR50 objectives.
+The maximum individual doses from gaseous radioactive effluents were compared to the-applicable ODCM dose limits. Noble gas doses were less than 0.000065% of the corresponding 1OCFR50 dose objectives. Maximum doses resulting from releases of particulates, iodines, tritium, and carbon-14 in gaseous effluents were less than 0.44% of corresponding 10CFR50 objectives.
-METEOROLOGICAL DATA Meteorological joint frequency distributions are listed in Appendix A. Data recovery for the entire annual period was 89.8% for the 33-ft and 89.8% for the 220-ft levels of the tower. The predominant wind direction was from the south-southwest, which occurred approximately 16% of the time during the reporting period. The predominant stability class was Class D, which occurred about 47% 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 0.9 mrem during 2013. There was no measurable increase during 2013 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-bome radioactivity, and ambient radiation exposure resulting from PNPS operation during 2013 was calculated as being about 0.46 mrem. This amount is about 0.13% 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.
+Page 5
-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 1159 cubic meters of solid waste, containing almost 82 Curies of radioactivity, were shipped during the reporting period.Page 6 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. Additional sampling wells were added in 2010, 2011, 2012, and 2013. As of the end of 2013, samples are being collected from a total of 22 monitoring wells. Low levels of tritium, a radioactive isotope of hydrogen, were detected in several of these onsite wells. No other plant-related radioactivity was detected in the groundwater samples. Concentrations of tritium ranged from non-detectable at less than 337 picoCuries per Liter up to 69,000 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.
+LIQUID EFFLUENTS Liquid radioactive releases for the reporting period are quantified in Tables 2.3-A and 2.3-B.
-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 2013, there was no significant radiological impact on the general public from PNPS operation.
+Twenty-one discharges of liquid effluents containing, radioactivity occurred during the reporting period. These discharges contained 6.2 Curies of tritium, and 0.019 Curies of fission and activation products. The resulting maximum total body dose was 0.0027 mrem, with a corresponding organ dose of 0.0096 mrem. All doses from liquid discharges were less than 0.25%
-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
+of corresponding 10CFR50 objectives.
-: 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.
+METEOROLOGICAL DATA Meteorological joint frequency distributions are listed in Appendix A. Data recovery for the entire annual period was 89.8% for the 33-ft and 89.8% for the 220-ft levels of the tower. The predominant wind direction was from the south-southwest, which occurred approximately 16% of the time during the reporting period. The predominant stability class was Class D, which occurred about 47% 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 0.9 mrem during 2013. There was no measurable increase during 2013 in ambient radiation measurements at the location of the nearest resident 0.8 km southeast of PNPS.
-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: 0.29 Ci, 0.0092 J4Ci/sec l Iodines and particulates with 0.0027 Ci, 0.000084 !.Ci/sec'half-life greater than 8 days 0 Tritium: 64.0 Ci, 2.03 p.Ci/sec* Carbon-14:
+COMBINED DOSE IMPACT The collective total body dose to a maximum-exposed hypothetical member of the public from airborne radioactivity, liquid-bome radioactivity, and ambient radiation exposure resulting from PNPS operation during 2013 was calculated as being about 0.46 mrem. This amount is about 0.13% 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.
-.3 Ci, 0.20 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".
+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.
-Under this new definition, any radionuclide that contributed greater than 1% of the effluent dose calculated to demonstrate compliance with 1OCFR50 Appendix I, or contributed more than 1% of the total activity for that type of effluent release, would be classified as a principal radionuclide.
+RADIOACTIVE SOLID WASTE DISPOSAL Solid radioactive wastes shipped offsite for processing and disposal during the reporting period are described in Table 7.0. Approximately 1159 cubic meters of solid waste, containing almost 82 Curies of radioactivity, were shipped during the reporting period.
+Page 6
+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. Additional sampling wells were added in 2010, 2011, 2012, and 2013. As of the end of 2013, samples are being collected from a total of 22 monitoring wells. Low levels of tritium, a radioactive isotope of hydrogen, were detected in several of these onsite wells. No other plant-related radioactivity was detected in the groundwater samples. Concentrations of tritium ranged from non-detectable at less than 337 picoCuries per Liter up to 69,000 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 2013, there was no significant radiological impact on the general public from PNPS operation.
+Page 7
+.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.
+.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      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:                          0.29 Ci, 0.0092 J4Ci/sec lIodines and particulates with        0.0027 Ci, 0.000084 !.Ci/sec
+        'half-life greater than 8 days 0    Tritium:                             64.0 Ci, 2.03 p.Ci/sec
+* Carbon-14:                          6.3 Ci, 0.20 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 1OCFR50 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 for 2013 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.
+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.
-Liquid effluent releases are summarized in Table 2.3-A. Detailed breakdowns for individual radionuclides are listed in Table 2.3-B. There were five 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: 0 Total Effluent Volume:* Total Dilution Volume: 0 Fission/Activation products:* Tritium: 1,180,000 Liters 565 billion Liters 0.0189 Ci, 0.0000000000336 lLCi/mL 6.21 Ci, 0.0000000110 IRCi/mL* Dissolved/entrained noble gases: 0.00 Ci, 0.00 RiCi/mL Page 9 Table 2.1 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Supplemental Information January-December 2013 FACILITY:
+Carbon-14 releases for 2013 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.
-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:
+Page 8
-'mrem/yr to any organ at site boundary>8 days, tritium d. Liquid effluents:
-.06 mrem/month for whole body and 0.2 mrem/month for any organ (without radwaste treatment)
+.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.
-: 2. EFFLUENT CONCENTRATION LIMITS a. Fission and activation gases: 10CFR20 Appendix B Table II b. Iodines: 10CFR20 Appendix B Table II c. Particulates with half-life
+Liquid effluent releases are summarized in Table 2.3-A. Detailed breakdowns for individual radionuclides are listed in Table 2.3-B. There were five 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:
-> 8 days: IOCFR20 Appendix B Table II d. Liquid effluents:
+  Total Effluent Volume:               1,180,000 Liters
-E-04 .LCi/mL for entrained noble gases;10CFR20 Appendix B Table II values for all other radionuclides
+* Total Dilution Volume:               565 billion Liters 0   Fission/Activation products:         0.0189 Ci, 0.0000000000336 lLCi/mL
-: 3. AVERAGE ENERGY Not Applicable
+* Tritium:                             6.21 Ci, 0.0000000110 IRCi/mL
+* Dissolved/entrained noble gases:     0.00 Ci, 0.00 RiCi/mL Page 9
+Table 2.1 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Supplemental Information January-December 2013 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. Iodines:                                            10CFR20 Appendix B Table II
+: c. Particulates with half-life > 8 days:               IOCFR20 Appendix B Table II
+: d. Liquid effluents:                                  2E-04 .LCi/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:
+: a. Fission and activation gases:                       High purity germanium gamma spectroscopy for all
-Fe-55 (liquid effluents), Sr-89, and Sr-90 d. Liquid effluents:
+: 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 2013               2013       2013 2013          2013
+: a. Liquid Effluents
+: 1. Total number of releases:               5.OOE+00       1.20E+01
 During the refueling outage in April, site power to the meteorological tower was interrupted between 26-Apr and 30-Apr-2013, resulting in the loss of all meteorological data for 96 hours. This event is described in Condition Report CR-PNP-2013-3081.
 The failure to meet the 90% data recovery goal for two consecutive years was identified as a concern during the NRC inspection of the Radiological Environmental Monitoring Program in August 2013. That NRC concern was described in Condition Report CR-PNP-2013-5742.
-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
+Page 19
+.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
 Page 35*
-Table 5.0 Average TLD Exposures By Distance Zone During 2013 Average Exposure +/- Standard Deviation:
-mR/ edod Exposure Zone 1* Zone 2 Zone 3 Zone 4 Period 0-3 km 3-8 km 8-15 km >15 km Jan-Mar 17.1 +/- 5.1 14.2 +/- 2.3 13.8 +/- 1.1 14.7 +/- 2.9 Apr-Jun 16.5 +/- 4.8 13.0 +/- 1.9 13.0 +/- 1.7 13.9 +/- 3.0 Jul-Sep 18.4 +/- 5.8 14.8 +/- 2.0 14.1 +/- 1.7 15.2 +/- 2.6 Oct-Dec 19.6 +/- 5.2 15.9 +/- 2.0 15.9 +/- 1.9 16.4 +/- 2.5 Jan-Dec 71.6 +/- 21.3** 57.8 +/- 9.0 56.7 +/- 7.6 60.2 +/- 10.9* Zone 1 extends from the PNPS restricted/protected area boundary outward to 3 kilometers (2 miles), and includes several TLDs located within the site boundary.** When corrected for TLDs located within the site boundary, the Zone 1 annual average is calculated to be 62.2 +/- 8.9 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 2013 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 2013 A. Instantaneous Dose Rate Limit -Noble Gases PNPS ODCM Control 3.3.1 .a Limit: 500 mrem/yr Total Body Dose Period Value -mrem/yr Fraction of Limit Jan-Dec 2.14E-06 4.28E-07%B. Instantaneous Dose Rate Limit -Noble Gases PNPS ODCM Control 3.3.1 .a Limit: 3000 mrem/yr Skin Dose Period Value -mrem/yr Fraction of Limit Jan-Dec 4.87E-06 1.62E-07%C. Instantaneous Dose Rate Limit -Particulates, lodines, & Tritium PNPS ODCM Control 3.3.1.b Limit: 1500 mrem/yr Organ Dose Period Value -mrem/yr Fraction of Limit Jan-Dec 6.57E-02 4.38E-03%D. Quarterly Dose Objective
--Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.a Objective:
-mrad Gamma Air Dose Period Value -mrad Fraction of Limit Jan-Mar 0.00E+00 0.OOE+00%Apr-Jun 0.OOE+00 0.OOE+00%Jul-Sep 3.25E-06 6.49E-05%Oct-Dec 0.OOE+00 0.OOE+00%E. Annual Dose Objective
--Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.b Objective:
-mrad Gamma Air Dose Period Value -mrad/vr Fraction of Limit Jan-Dec 3.25E-06 3.25E-05%Page 38 Table 6.1 (continued)
-Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2013 F. Quarterly Dose Objective
--Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.a Objective:
-mrad Beta Air Dose Period Value -mrad Fraction of Limit Jan-Mar 0.00E+00 0.OOE+00%Apr-Jun 0.OOE+00 O.OOE+00%Jul-Sep 3.10E-06 3.1OE-05%Oct-Dec 0.OOE+00 0.OOE+00%G. Annual Dose Objective
--Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.b Objective:
-: 20. mrad Beta Air Dose Period Value -mrad/vr Fraction of Limit Jan-Dec 3.10E-06 1.55E-05%H. Quarterly Dose Objective
--Particulates, lodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.a Objective:
-.5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrem 1.58E-02 1.02E-02 2.OOE-02.1.98E-02 Fraction of Limit 2.10E-01%1.36E-01%2.67E-01 %2.64E-01%I. Annual Dose Objective
--Particulates, lodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.b Objective:
-mrem Organ Dose Period Jan-Dec Value -mrem/vr 6.57E-02 Fraction of Limit 4.38E-01%Page 39 :
-.2 Liquid Effluent Releases Liquid effluent concentration limits and doseobjectives 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 2013 A. Fission and Activation Product Effluent Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1OCFR20 Appendix B, Table 2, Column 2 Value Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -4Ci/mL 2.73E-14 1.74E-10 0.OOE+00 1.89E-1 3 3.36E-1 1 Fraction of Limit 9.11 E-08%2.47E-03%0.OOE+00%1.32E-05%4.81 E-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 -i.Ci/mL 5.57E-09 4.81 E-08 0.00E+00 1.01 E-09 1.1OE-08 Fraction of Limit 5.57E-04%4.81 E-03%0.OOE+00%1.01 E-04%1.10E-03%C. Dissolved and Entrained Noble Gases Concentration Limit PNPS ODCM Control 3.2.1 Limit: 2.OE-04 ,iCi/mL Period Value -ljCi/mL Fraction of Limit Jan-Mar 0.OOE+00 0.OOE+00%Apr-Jun 0.OOE+00 0.OOE+00%Jul-Sep 0.OOE+00 0.OOE+00%Oct-Dec 0.OOE+00 0.OOE+00%Jan-Dec 0.OOE+00 0.OOE+00%Page 41 Table 6.2 (continued)
-Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2013 D. Quarterly Total Body Dose Objective PNPS ODCM Control 3.2.2.a Objective:
-.5 mrem Total Body Dose Period Value -mrem Fraction of Limit Jan-Mar 8.17E-07 5.45E-05%Apr-Jun 3.50E-03 2.33E-01%Jul-Sep 0.OOE+00 0.OOE+00%Oct-Dec 1.15E-06 7.66E-05%E. Annual Total Body Dose Objective PNPS ODCM Control 3.2.2.b Objective:
-mrem Total Body Dose Period Value -mrem Fraction of Limit Jan-Dec 2.70E-03 9.01 E-02%F. Quarterly Organ Dose Objective PNPS ODCM Control 3.2.2.a Objective:
-mrem Organ Dose Period Value -mrem Fraction of Limit Jan-Mar 1.09E-06 2.18E-05%Apr-Jun 1.24E-02 2.48E-01%.
-Jul-Sep O.00E+00 0.OOE+00%Oct-Dec 1.76E-06 3.51 E-05%G. Annual Organ Dose Objective PNPS ODCM Control 3.2.2.b Objective:
-mrem Organ Dose Period Value -mrem Fraction of Limit Jan-Dec 9.58E-03 9.58E-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 59.3 cubic meters of spent resins, filter sludges, etc., containing a total activity of about 76.4 Curies were shipped from PNPS for processing and disposal.
-Dry activated wastes and contaminated equipment shipped during the period totaled 1100 cubic meters and contained 6.08 Curies of radioactivity.
-No shipment of irradiated components was shipped during the reporting period. 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 22 shipments to Energy Solutions' Bear Creek Facility in Oak Ridge, TN; 1 shipment to Energy Solutions' Gallaher Road Facility in Kingston, TN; 9 shipments to Studsvik Processing Facility in Erwin, TN; 4 shipments to Energy Solutions Facility in Memphis, TN; and 2 shipments to Eastern Technologies in Ashford, AL.Page 43 Table 7.0 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments January-December 2013 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)1. Estimate of volume and activity content by type of waste Jan-Dec 2013 Type of waste Volume -m, J Curies Total Error a. Spent resins, filters, filter sludges, 5.93E+01 7.64E+01 +/- 25%evaporator bottoms, etc.b. Dry activated waste, contaminated 1.10E+03 6.08E+00 +/- 25%equipment, etc.c. Irradiated components, control rods, etc. 0.OOE+00 0.00E+00 N/A* d. Other (describe):
-.OOE+00 0.OOE+00 N/A 2. Estimate of major nuclide composition by type of waste 1 Type of waste Radionuclide Abundance Total Error a. Spent resins, filters, filter sludges, Mn-54 10.91% +/- 25%evaporator bottoms, etc. Fe-55 29.78% +/- 25%Co-60 30.98% +/-25%Zn-65 16.47% +/-25%Cs-1 37 7.57% +/- 25%b. Dry activated waste, contaminated Mn-54 9.49% +/- 25%equipment, etc. Fe-55 59.67% +/- 25%Co-60 22.02% +/- 25%Ni-63 1.02% +/- 25%Zn-65 6.20% +/- 25%c. Irradiated components, control rods, etc. Not licable Not Applicable N/A d. Other (describe):
-j Not Applicable Not Applicable N/A"Major" is defined as any radionuclide comprising
->1% of the total activity in the waste category.3. Solid Waste Disposition-Number of Shipments Mode of Transportation Destination Tractor-trailer Energy Solutions Bear Creek Facility 2 (Hittman Transport)
-.Oak Ridge, TN Tractor-trailer Energy Solutions Gallaher Road Facility L (Hittman Transport)
-Kingston, TN 9 Tractor-trailer Studsvik Processing Facility, z (Hittman Transport)
-Erwin, TN 4 Tractor-trailer Energy Solutions Facility (Hittman Transport)
-Memphis, TN 2 Tractor-trailer Eastern Technologies Inc.(Hittman Transport)
-Ashford, AL 2 This processor provides volume reduction services for dry compressible waste, contaminated equipment, etc.Remaining radioactive wastes will be shipped to Envirocare, Inc. in Clive, UT for final disposal.B. IRRADIATED FUEL SHIPMENTS
-& DISPOSITION Number of Ship ments Mode of Transportation 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 2013. Information regarding revisions to the ODCM can be found attached as Appendix D of this report.Page 45 9.0 PROCESS CONTROL PROGRAM REVISIONS There were no significant changes to the PNPS Process Control Program (PCP) during the calendar year of 2013. Although Pilgrim Station adopted the Entergy fleet-wide PCP in 2010 as indicated in the 2010 Annual Effluent Release Report, fleet procedure EN-RW-105, "Process Control Program", was not revised until 2011 to reflect the inclusion of Pilgrim Station under the fleet-wide PCP. This revision was strictly administrative in nature, and did not impact the requirements or conduct of the PCP.The following list summarizes changes made during 2013 to various procedures related to the Process Control Program: EN-RW-1 03, "Radioactive Waste Tracking Procedure", Rev.4: Editorial revision to clarify and update the following items: Adjust the range of densities for metals; Titles in responsibilities section updated; Clarification on liability reports to management.
-EN-RW-104, "Scaling Factors", Rev.9: Editorial revision to address the following items: Enhancement to initiate a Condition Report for independent lab result discrepancies as compared to in-house analyses; Enhancement to share waste stream data results to Chemistry/Environmental personnel responsible for effluents.
-EN-RW-105, "Process Control Program", Rev.3: Editorial revision to recognize organizational titles at Palisades Nuclear Plant.Page 46
-==10.0 REFERENCES==
+Table 5.0 Average TLD Exposures By Distance Zone During 2013 Average Exposure +/- Standard Deviation: mR/ edod Exposure           Zone 1*           Zone 2             Zone 3         Zone 4 Period            0-3 km           3-8 km             8-15 km        >15 km Jan-Mar          17.1 +/- 5.1       14.2 +/- 2.3          13.8 +/- 1.1     14.7 +/- 2.9 Apr-Jun          16.5 +/- 4.8        13.0 +/- 1.9         13.0 +/- 1.7     13.9 +/- 3.0 Jul-Sep          18.4 +/- 5.8        14.8 +/- 2.0         14.1 +/- 1.7     15.2 +/- 2.6 Oct-Dec           19.6 +/- 5.2        15.9 +/- 2.0         15.9 +/- 1.9     16.4 +/- 2.5 Jan-Dec         71.6 +/- 21.3**      57.8 +/- 9.0          56.7 +/- 7.6    60.2 +/- 10.9
-: 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
+* Zone 1 extends from the PNPS restricted/protected area boundary outward to 3 kilometers (2 miles), and includes several TLDs located within the site boundary.
+** When corrected for TLDs located within the site boundary, the Zone 1 annual average is calculated to be 62.2 +/- 8.9 mR/yr.
+Page 36
+.0      PERCENT OF ODCM EFFLUENT CONTROL LIMITS The PNPS ODCM contains dose and

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