ML081420302
| ML081420302 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 05/08/2008 |
| From: | Jeffery Lynch Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2.08.028, FOIA/PA-2010-0209 | |
| Download: ML081420302 (76) | |
Text
" Entergy Entergy Nuclear Operations, Inc.
Pilgrim Station 600 Rocky Hill Road Plymouth, MA 02360 May 8, 2008 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
SUBJECT:
Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 Radioactive Effluent Release Report for January 1 through December 31, 2007 LETTER NUMBER:
2.08.028
Dear Sir or Madam:
In accordance with Pilgrim Technical Specification 5.6.3, Entergy Nuclear Operations, Inc.
submits the enclosed Radioactive Effluent Release Report for January 1 through December 31, 2007.
Should you have questions or require additional information, I can be contacted at (508) 830-8403.
This letter contains no commitments.
Sincerely, Joseph R.Lynch Licensing Manager MJG/dl
Enclosure:
Pilgrim Nuclear Power Station Radioactive Effluent Release Report for January 1 through December 31, 2007 cc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Mr. James S. Kim, Project Manager Plant Licensing Branch I-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North O-8C2 11555 Rockville Pike Rockville, MD 20852 208027
PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 Radioactive Effluent Release Report January 1 through December 31, 2007
Enterg
p I
PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 RADIOACTIVE EFFLUENT RELEASE REPORT.
JANUARY 01 THROUGH DECEMBER 31, 2007 U
Prepared by:
Reviewed by:
K.J. S4kdraaj Senior HP/Cemistry Specialist
,/
"- 1X'.cEIhinney Chemistry Superintendent Reviewed by:
,/
J.C. Henderson Radiation Protection Manager Page 2
Pilgrim Nuclear Power Station Radioactive Effluent Release Report January-December 2007 TABLE OF CONTENTS SECTION SECTION TITLE PAGE 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 APPENDIX A APPENDIX B APPENDIX C APPENDIX D EXECUTIVE
SUMMARY
RADIOACTIVE EFFLUENT DATA Supplemental Effluent Release Data Gaseous Effluent Data Liquid Effluent Data METEOROLOGICAL DATA MAXIMUM INDIVIDUAL DOSES Doses From Noble Gas Releases Doses From Gaseous Effluent Releases Doses From Liquid Effluent Releases OFFSITE AMBIENT RADIATION MEASUREMENTS PERCENT OF ODCM EFFLUENT CONTROL LIMITS Gaseous Effluent Releases Liquid Effluent Releases' RADIOACTIVE WASTE DISPOSAL DATA OFFSITE DOSE CALCULATION MANUAL REVISIONS REFERENCES Meteorological Joint Frequency Distributions Offsite Dose Calculation Manual Onsite Groundwater Monitoring Program Assessment of Reactor Building Vent Sample Probe Issue 5
8 8
8 9
19 20 20 22 28 34 37 37 40 43 45 46 47 68 69 72 Page 3
Pilgrim Nuclear Power Station Radioactive Effluent Release Report Jan-Dec 2007 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 2007 21 4.2-A Maximum Individual Organ Doses from Gaseous Effluents 23 Jan-Mar 2007 4.2-B Maximum Individual Organ Doses from Gaseous Effluents 24 Apr-Jun 2007 4.2-C Maximum Individual Organ Doses from Gaseous Effluents 25 Jul-Sep 2007 4.2-D Maximum Individual Organ Doses from Gaseous Effluents 26 Oct-Dec 2007 4.2-E Maximum Individual Organ Doses from Gaseous Effluents 27 Jan-Dec 2007.
4.3-A Maximum Individual Organ Doses from Liquid Effluents 29 Jan-Mar 2007 4.3-B Maximum Individual Organ Doses from Liquid Effluents 30 Apr-Jun 2007 4.3-C Maximum Individual Organ Doses from Liquid Effluents 31 Jul-Sep 2007 4.3-D Maximum Individual Organ Doses-from Liquid Effluents 32 Oct-Dec 2007 4.3-E Maximum Individual Organ Doses from Liquid Effluents 33 Jan-Dec 2007 5.0 Average TLD Exposures by Distance Zone During 2007 36 6.1 Percent of ODCM Effluent Control Limits for Gaseous Effluent 38 Releases During 2007 6.2 Percent of ODCM Effluent Control Limits for Liquid Effluent Releases 41 During 2007 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 2204t 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 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2007 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, 2007.
This document has been prepared in accordance with the requirements set forth in the Pilgrim Nuclear Power Station (PNPS) Technical Specifications and Revision 1 of Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluents from Light Water Cooled Nuclear Power Plants".
The quantity of radioactive material released from PNPS was determined from 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 1550 Curies.
Releases of radioactive iodines and particulates with half-life of greater than 8 days totaled 0.067 Curies, and tritium releases totaled 58.6 Curies. No gross alpha radioactivity was detected in gaseous effluents.
Noble gases released in gaseous effluents resulted in a maximum total-body dose of 0.55 mrem, with a corresponding skin dose of 2.4 mrem. The release of radioactivity in gaseous effluents from PNPS during 2007 resulted inca total body dose to the maximum-exposed hypothetical individual of about 0.022 mrem from radioactive particulates, iodines, and tritium. The maximum hypothetical dose to any organ from radioactive particulates, iodines, and tritium was about 0.16 mrem. The maximum, hypothetical total body dose from the combined release of radioactivity in gaseous effluents was 0.57 mrem.
The maximum individual doses from gaseous radioactive effluents were compared to the applicable ODCM dose limits. Noble gas doses were less than 11% of the corresponding 10CFR50 dose objectives. Maximum doses resulting from releases of particulates, iodines, and tritium in gaseous effluents were less than 2% 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. Three discharges of liquid effluents containing radioactivity occurred during calendar year 2007. The resulting maximum total body dose was 0.0000049 mrem, with a corresponding organ dose of 0.0000076 mrem.
All doses from liquid discharges were less than 0.00021% of corresponding 1 OCFR50 objectives.
METEOROLOGICAL DATA Meteorological joint frequency distributions are listed in Appendix A. Data recovery for the entire annual period was about 99.7% for both the 33-ft and 220-ft levels of the tower. The predominant wind direction was from the south-southwest, which occurred approximately 14% of the time during the reporting period. The predominant stability class was Class D, which occurred about 42% 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 National Guard, who is considered members of the public even though they are within the owner-controlled area, was estimated as being about 5.4 mrem during 2007. There was no measurable increase during 2007 in ambient radiation measurements at the location of the nearest resident to PNPS.
COMBINED DOSE IMPACT The collective total body dose to a maximum-exposed hypothetical member of the public from radioactive gases, liquids, and ambient radiation exposure resulting from-PNPS operation during 2007 was calculated as being about 6.0 mrem. This amount is less than 2% of the typical dose of 300 to 400 mrem received each year by an average person from other sources of natural and man-made radiation. Although this calculated collective dose occurs to a maximum-exposed hypothetical individual, it is also well below the NRC dose limit of 100 mrem/yr specified in 10CFR20.1301, as well as the EPA dose limit of 25 mrem/yr specified in 40CFR190. Both of these limits are to be applied to real members of the general public, so the fact that the dose to the hypothetical maximum-exposed individual is within the limits ensures that any dose received by a real member of the public would be smaller and well within any applicable limit.
RADIOACTIVE SOLID WASTE DISPOSAL Solid radioactive wastes shipped offsite for processing and disposal during the reporting period are described in Table 7.0. Approximately 838 cubic meters of solid waste, containing 94.7 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. Low levels of tritium, a radioactive isotope of hydrogen, were detected in these onsite wells.
No other plant-related radioactivity was detected in the samples. Concentrations of tritium ranged from 450 to 3300 picoCuries per Liter, well below 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 C.
ASSESSMENT OF REACTOR BUILDING VENT SAMPLE PROBE ISSUE During collection of supporting data for an NRC Effluents Inspection performed in 2006, Pilgrim Station identified that incorrect dimensions had been assumed for the isokinetic probe used to sample the exhaust of the Reactor Building Vent (RBV). The sampling protocol which had been in place since at least the early 1980s had assumed a larger probe diameter that what actually existed, resulting in potential non-representative sampling for particulate radioactivity. This problem did not affect measurements of noble gases, tritium, or radioiodines released from the RBV, nor did it affect measurements of gaseous effluents released from the main stack. An evaluation was performed to determine the impact of the potential non-representative sampling. Results of this assessment are presented in Appendix D. Because particulate activity released from the RBV accounts for such a small fraction of the total activity of tritium, radioiodines, and particulates released from the Main Stack and RBV combined, this potential non-representative sampling had minimal impact on the activity reported as being released, and on any additional dose resulting from these releases.
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 2007, 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:
1550 Ci, 49.2 gCi/sec lodines and particulates with 0.0674 Ci, 0.00214 gCi/sec half-life greater than 8 days
" Tritium:
58.6 Ci, 1.86 iiCi/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.
On 15-Jun-2006 while collecting supporting information for an NRC effluent inspection, Pilgrim Station personnel identified that the isokinetic sample flow rate at-the reactor building vent (RBV) was incorrectly based on an erroneous value for the sample probe diameter. The isokinetic ratio currently in use was based on an assumed probe diameter of 0.2 inches for each of the four probes in the sampling array. Based on measurements taken during the 2007 refueling outage, the actual probe diameter is 0.135 inches. This assumption of incorrect probe size has been in use since at least 1982. This sampling anomaly would result in an non-conservative under-representation of large particles, and has been documented in CR-PNP-2006-2282. As part of the corrective action to this discovered anomaly, the NRC has requested that Pilgrim Station evaluate and document in the effluent report the impact of sampling at the incorrect flow rate. A detailed assessmentof the impact of this sampling anomaly is presented in Appendix D.
Due to limitations in the system design of the flow controller used in the RBV sampling system, it is impractical to set the system down to the targeted isokinetic sampling flow rate of 0.6 to 0.7 cfm. As such, this problem with anisokinetic sampling still exists. The isokinetic probes in the RBV sampling system are scheduled to be modified in 2008, which will correct this issue, and ensure representative sampling. Because the problem still existed in 2007, particulate activity released Page 8
from the RBV for reporting year 2007, as reported in Table 2.2-C, were corrected upward by a nominal isokinetic correction factor of 1.25; assuming that the actual particle size is distributed around a mean particle diameter of 3 microns.
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 was only one discharge of liquid effluents containing radioactivity during the calendar year of 2007.
-Total releases for the various categories of radionuclides, as well as their corresponding mean concentrations, can be summarized as follows:
Total Effluent Volume:
Total Dilution Volume:
Fission/Activation products:
Tritium:
107,000 Liters 571,000,000,000 Liters 0.00013 Ci, 0.00000000000022 gCi/mL 0.23 Ci, 0.00000000039 g-Ci/mL Dissolved/entrained noble gases:
0 Ci, 0 gCi/mL Page 9
Table 2.1 Pilgrim Nuclear Power Station Radioactive Effluent Release Report Supplemental Information January-December 2007 FACILITY: PILGRIM NUCLEAR POWER STATION LICENSE: DPR-35
- 1. REGULATORY LIMITS
- a. Fission and activation gases:
500 mrem/yr total body and 3000 mrem/yr for skin at site boundary b,c. lodines, particulates with half-life:
1500 mrem/yr to any organ at site boundary
>8 days, tritium
- d. Liquid effluents:
0.06 mrem/month for whole. body and 0.2 mrem/month for any organ (without radwaste treatment)
- 2. EFFLUENT CONCENTRATION LIMITS
- a. Fission and activation gases:
10CFR20 Appendix B Table II
- b. lodines:
10CFR20 Appendix B Table 11
- c. Particulates with half-life > 8 days:
10CFR20 Appendix B Table II
- d. Liquid effluents:
2E-04 pCi/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:
1 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 2007 2007 2007 2007 2007
- a. Liquid Effluents
- 1. Total number of releases:
0 1
1 1
3
- 2. Total time-period (minutes):
0.OOE+00 1.OOE+02 1.70E+02 1.20E+02 3.90E+02
- 3. Maximum time period (minutes):
0.OOE+00 1.OOE+02 1.70E+02 1.20E+02 3.90E+02
- 4. Average time period (minutes):
0.OOE+00 1.OOE+02 1.70E+02 1.20E+02 3.90E+02
- 5. Minimum time period (minutes):
0.OOE+00' 1.OOE+02 1.70E+02 1.20E+02 3.90E+02
- 6. Average stream flow during periods of release ofe 0.OOE+00 5.98E+05 1.19E+06.
1 19E+06 1.04E+06 effluents into a flowing stream.
(Liters/min):
- 6. ABNORMAL RELEASES
- a. Liquid Effluents I
None
Table 2.2-A Pilgrim Nuclear Power Station Radioactive Effluent Release Report Gaseous Effluents - Summation of All Releases January-December 2007 Est.
RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Total
- 2007, 2007 2007 2007.
2007 Error A. FISSION AND ACTIVATION GASES Total Release: Ci 5.13E+02 2.25E+02 4.33E+02 3.82E+02 1.55E+03 Average Release Rate:
ftCi/se 6.51 E+01 2.85E+01 5.49E+01 4.84E+01 4.92E+01
+/-22%
Percent of Effluent Control Limit*...
B. IODINE-131 Total Iodine-1 31 Release: Ci 4.95E-03 4.64E-03 2.63E-03 2.41 E-03 1.46E-02 Average Release Rate: gCi/sec 6.28E-04 5.88E-04 3.34E-04 3.06E-04 4.64E-04
+/-20%
Percent of Effluent Control Limit*
C. PARTICULATES WITH HALF-LIVES > 8 DAYS Total Release: Ci 1.41 E-03 2.95E-03 6.11E-03 6.77E-03 1.72E-02 Average Release Rate: giCi/sec 1.79E-04 3.74E-04 7.75E-04 8.59E-04 5.47E-04 21%
Percent of Effluent Control Limit*
Gross Alpha Radioactivity: Ci NDA NDA NDA NDA NDA D. TRITIUM Total Release: Ci 2.22E+01 1.06E+01 1.39E+01 1.19E+01 5.86E+01 Average Release Rate:
ft Ci/sec 2.81 E+00 1.34E+00 1.77E+00 1.51 E+00 1.86E+00
+/-20%
Percent of Effluent Control Limit*
"F*+00*
Notes for Table 2.2-A:
- Percent of Effluent Control Limit values based on dose assessments are provided in Section 7 of this report.
- 1. NDA stands for No Detectable Activity.
Page 11
Table 2.2-B Pilgrim Nuclear Power Station Radioactive Effluent Release Report Gaseous Effluents - Elevated Release January-December 2007 CONTINUOUS MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released Jan-Mar 2007 Apr-Jun 2007 Jul-Sep 2007 Oct-Dec 2007 Jan-Dec 2007
- 1. FISSION AND ACTIVATION GASES: Ci Ar-41 7.15E-02 1.74E-01 1.88E-01 2.42E-02 4.57E-01 Kr-85 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Kr-85m 2.95E+01 1.74E+01 2.30E+01 1:53E+01 8.53E+01 Kr-87 1.84E+00 8.75E+00 2.32E+00 1.98E+00 1.49E+01 Kr-88 3.13E+01 2.22E+01 2.11E+01
-1.09E+01 8.54E+01 Xe-131 m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-133 1.05E+02 2.27E+01 2.96E+01 2.64E+01 1.84E+02 Xe-133m 5.53E-01 0.OOE+00 0.OOE+00 0.OOE+00 5.53E-01 Xe-135 4.48E+00 9.54E+00 9.26E+00 4.91 E+00 2.82E+01
- Xe-135m 2.90E+00 7.08E+00 1.75E+01 1.33E+01 4.07E+01 Xe-137 0.OOE+00 0.OOE+00 3.43E+01 1.46E+01 4.89E+01 Xe-138 1.18E+01 2.38E+01 4.45E+01 4.81E+01 1.28E+02 Total for Period 1.88E+02 1.12E+02 1.82E+02 1.36E+02 6.17E+02
- 2. IODINES: Ci 1-131 1.71E-03 7.21E-04 8.76E-04 6.21E-04 3.93E-03 1-133 2.20E-03 2.15E-03 2.79E-03 1.21E-03 8.35E-03 Total for Period 3.91 E-03 2.87E-03 3.67E-03 1.83E-03 1.23E-02
- 3. PARTICULATES WITH HALF-LIVES > 8 DAYS: Ci Cr-51 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Mn-54 0.OOE+00 8.03E-07 1.92E-06 0.OOE+00 2.73E-06 Fe-59 0.OOE+00 9.05E-07 1.45E-06 0.OOE+00 2.36E-06 Co-58 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 0.OOE+00 1.04E-06 0.OOE+00 1.90E-06 2.94E-06 Zn-65 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Sr-89 4.16E-05 1.18E-04 6.87E-05 7.14E-05 2.99E-04 Sr-90 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ru-1 03 7.38E-07 0.OOE+00 9.84E-07 0.OOE+00 1.72E-06 Cs-134 2.02E-06 0.OOE+00 0.OOE+00 1.60E-06 3.62E-06 Cs-1 37 4.96E-07 9.76E-07 0.OOE+00 8.04E-06 9.51 E-06 Ba/La-140 1.43E-04 4.84E-04 7.73E-04 4.57E-04 1.86E-03 Total for Period 1.88E-04 6.06E-04 8.46E-04 5.40E-04 2.18E-03
- 4. TRITIUM: Ci H-3 4.12E-01 3.09E-01 6.92E-01 2.72E-01 1.68E+00 Notes for Table 2.2-B:
- 1. N/A stands for not applicable.
- 2. NDA stands for No Detectable Activity.
Fission Gases: 1 E-04 gCi/cc lodines:
1 E-12 tCi/cc Particulates:
1 E-1 1 Ci/cc Page 12
Table 2.2-B (continued)
Pilgrim Nuclear Power Station Radioactive Effluent Release Report Gaseous Effluents - Elevated Release January-December 2007 BATCH MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released Jan-Mar 2007 Apr-Jun 2007 Jul-Sep 2007 Oct-Dec 2007 Jan-Dec 2007
- 1. FISSION AND ACTIVATION GASES: Ci Ar-41 N/A N/A N/A N/A N/A Kr-85 N/A N/A N/A N/A N/A Kr-85m N/A N/A N/A N/A N/A Kr-87 N/A N/A N/A N/A N/A Kr-88 N/A N/A N/A N/A N/A Xe-131m N/A N/A N/A N/A N/A Xe-i 33 N/A N/A N/A N/A N/A Xe-1 33m N/A N/A N/A N/A N/A Xe-i 35 N/A N/A N/A N/A N/A Xe-1 35m 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-i 03 N/A N/A N/A N/A N/A Cs-i 34 N/A N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A N/A Ba/La-140 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A
- 4. TRITIUM: Ci H-3 N/A N/A N/A N/A N/A Notes for Table 2.2-B:
- 1. N/A stands for not applicable.
- 2. NDA stands for No Detectable Activity.
Fission Gases: 1 E-04 pCi/cc lodines:
1E-12 gCi/cc Particulates:
1 E-1 1 gCi/cc Page 13
Table 2.2-C Pilgrim Nuclear Power Station Radioactive Effluent Release Report Gaseous Effluents - Ground-Level Release January-December 2007 CONTINUOUS MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released I Jan-Mar 2007 Apr-Jun 2007 Jul-Sep 2007 Oct-Dec 2007 Jan-Dec 2007
- 1. FISSION AND ACTIVATION GASES: Ci Ar-41 6.76E-01 0.OOE+00 0.OOE+00 0.OOE+00 6.76E-01 Kr-85 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kr-85m 4.40E-01 1.16E+00 5.85E-01 3.1OE+00 5.29E+00 Kr-87 9.02E+00 8.76E+00 2.54E+01 2.22E+01 6.54E+01 Kr-88 1.14E+01 3.89E+00 9.65E+00 1.27E+01 3.76E+01 Xe-131m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-1 33 2.46E-01 8.32E+00 0.OOE+00 5.44E+00 1.40E+01 Xe-1 33m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-135 1.78E+01 8.43E+00 2.52E+01 2.84E+01 7.99E+01 Xe-135m 6.60E+01 1.62E+01 4.07E+01 3.72E+01 1.60E+02 Xe-1 37 0.OOE+00 1.36E+01 1.59E+01 1.66E+01 4.61 E+01 Xe-1 38 2.20E+02 5.28E+01 1.34E+02 1.21 E+02 5.27E+02 Total for period 3.25E+02 1.13E+02 2.51 E+02 2.46E+02 9.36E+02
- 2. IODINES: Ci 1-131 3.23E-03 3.92E-03 1.75E-03 1.79E-03 1.07E-02 1-133 6.65E-03 6.26E-03 8.35E-03 5.91 E-03 2.72E-02 Total for period 9.88E-03 1.02E-02 1.01 E-02 7.71 E-03 3.79E-02
- 3. PARTICULATES WITH HALF-LIVES > 8 DAYS: Ci Cr-51 0.OOE+00 3.95E-05 0.OOE+00 0.OOE+00 3.95E-05 Mn-54 0.OOE+00 3.20E-05 7.50E-06 0.OOE+00 3.95E-05 Fe-59 0.OOE+00 1.35E-05 0.OOE+00 0.OOE+00 1.35E-05 Co-58 0.OOE+00 5.50E-06 0.OOE+00 0.OOE+00 5.50E-06 Co-60 0.OOE+00 6.39E-05 0.OOE+00 0.OOE+00 6.39E-05 Zn-65 0.OOE+00 3.75E-05 0.OOE+00 0.OOE+00 3.75E-05 Sr-89 5.73E-04 7.39E-04 1.18E-03 1.OOE-03 3.49E-03 Sr-90 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ru-103 0.OOE+00 1.66E-06 6.1OE-07 0.OOE+00 2.27E-06 Cs-1 34 1.07E-05 2.18E-06 0.OOE+00 0.OOE+00 1.28E-05 Cs-1 37 8.05E-06 9.70E-06 0.OOE+00 6.40E-06 2.41 E-05 Ba/La-140 6.29E-04 1.40E-03 4.08E-03 5.23E-03 1.13E-02 Total for period 1.22E-03 2.34E-03 5.26E-03 6.23E-03 1.51 E-02
- 4. TRITIUM: Ci H-3 2.18E+01 i1.03E+01 i1.32E+01.
i1.16E+01i 5.69E+01 Notes for Table 2.2-C:
- 1. N/A stands for not applicable.
- 2. NDA stands for No Detectable Activity.
Fission Gases: 1E-04 0Ci/cc lodines:
1E-12 4Ci/cc Particulates:
1 E-11 pCi/cc Page 14
Table 2.2-C (continued)
Pilgrim Nuclear Power Station Radioactive Effluent Release Report Gaseous Effluents - Ground-Level Release January-December 2007 BATCH MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released Jan-Mar 2007 Apr-Jun 2007 Jul-Sep 2007 Oct-Dec 2007 Jan-Dec 2007
- 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-131 m N/A N/A N/A N/A N/A Xe-1 33 N/A N/A N/A N/A N/A Xe-1 33m N/A N/A N/A N/A N/A Xe-135 N/A N/A N/A N/A N/A Xe-135m N/A N/A N/A N/A N/A Xe-1 37 N/A N/A N/A N/A N/A Xe-1 38 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A
- 2. IODINES: Ci 1-131 N/A N/A N/A N/A N/A 1-133 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A
- 3. PARTICULATES WITH HALF-LIVES > 8 DAYS: Ci Cr-51 N/A N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A N/A Co-58 N/A N/A N/A N/A N/A Co-60 N/A N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A N/A Ru-1 03 N/A N/A N/A N/A N/A Cs-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 Notes for Table 2.2-C:
- 1. N/A stands for not applicable.
- 2. NDA stands for No Detectable Activity.
Fission Gases: 1 E-04 giCi/cc lodines:
1E-12 iCi/cc Particulates:
1E-11 0Ci/cc Page 15
Table 2.3-A Pilgrim Nuclear Power Station Radioactive Effluent Release Report Liquid Effluents - Summation of All Releases January-December 2007 Est.
RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Total 2007 2007 2007 2007 2007 Error A. FISSION AND ACTIVATION PRODUCTS Total Release (not including N/A 2.29E-06 3.91 E-05 8.60E-05 1.27E-04 tritium, gases, alpha): Ci Average Diluted Concentration N/A 2.04E-14 2.55E-13 5.60E-13 2.23E-13
+/-12%
During Period: 4Ci/mL Percent of Effluent Concentration Limit*
I N/A 2.04E-06%
2.09E-05%
5.17E-05%
1.99E-05%
Limit*
B. TRITIUM I
C. DISSOLVED AND ENTRAINED GASES I
Lim it*
I'Ji
/
I l//'
I II"'
I D. GROSS ALPHA RADIOACTIVITY Total Release: Ci N/A N/A N/A N/A N/A
+/-34%
E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION Waste Volume: Liters N/A 3.60E+04 3.54E+04 3.60E+04 1.07E+05
+/-5.7%
F. VOLUME OF DILUTION WATER USED DURING PERIOD Dilution Volume: Liters 1.52E+11 1.12E+11 1.53E+11 1.54E+11 5.71E+11
+/-10%
Notes for Table 2.3-A:
- Additional percent of Effluent Control Limit values based on dose assessments are this report.
- 1. N/A stands for not applicable.
- 2. NDA stands for No Detectable Activity.
provided in Section 7 of Page 16
Table 2.3-B Pilgrim Nuclear Power Station Radioactive Effluent Release Report Liquid Effluents January-December 2007 CONTINUOUS MODE RELEASES Nuclide Released Jan-Mar 2007 Apr-Jun 2007 Jul-Sep 2007 Oct-Dec 2007 Jan-Dec 2007
- 1. FISSION AND ACTIVATION PRODUCTS: Ci Cr-51 N/A N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A N/A Fe-55 N/A N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A N/A Co-58 N/A N/A N/A N/A N/A Co-60 N/A N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A N/A Zn-69m N/A N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A N/A Zr/Nb-95 N/A N/A N/A N/A N/A Mo/Tc-99 N/A N/A N/A N/A N/A Ag-110m N/A N/A N/A N/A N/A Sb-124 N/A N/A N/A N/A N/A 1-131 N/A N/A N/A N/A N/A 1-133 N/A N/A N/A N/A N/A Cs-134 N/A N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A N/A Ba/La-140 N/A N/A N/A N/A N/A Ce-141 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A
- 2. DISSOLVED AND ENTRAINED GASES: Ci Xe-i 33 N/A N/A N/A N/A N/A Xe-i 35 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.
Strontium:
5E-08 giCi/mL lodines:
1 E-06 jCi/mL Noble Gases:
1 E-05 0Ci/mL All Others:
5E-07 gCi/mL Page 17
Table 2.3-B (continued)
Pilgrim Nuclear Power Station Radioactive Effluent Release Report Liquid Effluents January-December 2007 BATCH MODE RELEASES Nuclide Released Jan-Mar 2007 Apr-Jun 2007 Jul-Sep 2007 Oct-Dec 2007 Jan-Dec 2007
- 1. FISSION AND ACTIVATION PRODUCTS: Ci Cr-51 N/A NDA NDA NDA NDA Mn-54 N/A NDA NDA NDA NDA Fe-55 N/A NDA NDA NDA NDA Fe-59 N/A NDA NDA NDA NDA Co-58 N/A NDA NDA NDA NDA Co-60 N/A NDA 5.41 E-06 1.21 E-05 1.76E-05 Zn-65 N/A NDA NDA NDA NDA Zn-69m N/A NDA NDA NDA NDA Sr-89 N/A NDA NDA NDA NDA Sr-90 N/A NDA NDA NDA NDA Zr/Nb-95 N/A NDA NDA NDA NDA Mo/Tc-99 N/A NDA NDA NDA NDA Ag-110m N/A NDA NDA NDA NDA Sb-124 N/A NDA NDA NDA NDA 1-131 N/A NDA NDA NDA NDA 1-133 N/A NDA NDA NDA NDA Cs-1 34 N/A NDA 3.03E-06 1.34E-05 1.64E-05 Cs-1 37 N/A 2.29E-06 2.64E-05 6.05E-05 8.92E-05 Ba/La-140 N/A NDA 4.32E-06 NDA 4.32E-06 Ce-141 N/A NDA NDA NDA NDA Total for period N/A 2.29E-06 3.91 E-05 8.60E-05 1.27E-04
- 2. DISSOLVED AND ENTRAINED GASES: Ci Xe-i 33 N/A NDA NDA NDA NDA Xe-i 35 N/A NDA NDA NDA NDA Total for period N/A NDA NDA NDA NDA Notes for Table 2.3-B:
- 1. N/A stands for not applicable.
- 2. NDA stands for No Detectable Activity.
Strontium:
5E-08 pCi/mL lodines:
1E-06 laCi/m L Noble Gases:
1 E-05 ItCi/mL All Others:
5E-07 jICi/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:
0 0
0 0
0 Stability Class:
33-ft Wind Direction (from):
33-ft Wind Speed:
220-ft Wind Direction (from):
220-ft Wind Speed:
Class D, 42%
South-southwest, 16%
3.5-7.5 mph, 52%
South-southwest, 12%
12.5-18.5 mph, 33%
Recent upgrades to the equipment on the.220-ft primary meteorological tower have improved overall data recovery and reliability. Data recovery for both levels of the 220-ft tower was 99.7%,
well in excess of the 90% annual data recovery goal specified by the NRC.
Page 19
4.0 MAXIMUM INDIVIDUAL DOSES Doses to the maximum exposed individual resulting from radionuclides in effluents released offsite were calculated using methods presented in the PNPS Offsite Dose Calculation Manual (ODCM, Reference 2), NRC Regulatory Guide 1.109 (Reference 3), NRC Regulatory Guide 1.111 (Reference 4), and the Pilgrim Station Unit 1 Appendix I Evaluation (Reference 5).
Maximum individual doses are calculated separately for: (1) noble gases in gaseous effluents, (2) particulates, iodines, and tritium in gaseous effluents; and, (3) liquid effluents. Maximum consumption and use factors for various pathways from Table E-5 of the PNPS ODCM are used for calculating the doses to the maximum exposed individual.
Information related to liquid and gaseous effluent releases are summarized Section 2 of this report.
These effluent release data were used as input to computer programs to calculate the resulting doses. PNPS ODCM methodologies were used to calculate the dose contributions to the various organs in each age class from major exposure pathways.
4.1 Doses From Noble Gas Releases Gaseous effluent release data presented in Tables 2.2-A, 2.2-B, and 2.2-C from this effluent release report were used as input to a dose assessment computer program to calculate radiation doses.
These data include gaseous releases from the PNPS main stack, reactor building vent, and turbine building roof exhausters.
Meteorological data obtained from the PNPS 220-foot meteorological tower during the 10-year period from 1994 through 2003 were used as input to the "AEOLUS-3" computer program (Reference 6).
This program was used to calculate the annual average atmospheric dispersion and deposition factors used in the dose assessment computer program to calculate maximum individual doses.
The maximum individual doses resulting from radioactive noble gases released in gaseous effluents are presented in Table 4.1 according to specific receptor locations. This table includes all noble gas doses for the individual calendar quarters and total calendar year.
Noble gases released in gaseous effluents from PNPS during 2007 resulted in a maximum total body dose of 0.55 mrem. The maximum skin dose was 2.4 mrem. Both of these doses occurred to a hypothetical individual, assumed to be present 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 365 days per year, at the site boundary location yielding the highest dose (0.33 km ESE of the Reactor Building for total body dose, 0.28 km NNW of the Reactor Building for skin dose). For the more "realistic" individuals at offsite locations, the maximum total body dose was 0.20 mrem (nearest residence, 0.80 kilometers ESE from the Reactor Building), while the maximum skin dose was 0.62 mrem (nearest residence, 0.80 kilometers ESE from the Reactor Building).
Page 20
Table 4.1 Maximum Doses From Noble Gas Releases Durina 2 0 0 7 (a)
Gamma Beta Total Release Air Dose Air Dose Body Dose Skin Dose Period (location)
(location)
(location)
(location)
J 3.10E-01 6.05E-01 2.08E-01 7.58E-01 (0.33 km ESE)
(0.28 km NNW)
(0.33 km ESE)
(0.28 km NNW)
Apr-Jun 8.81 E-02 2.72E-01 5.90E-02 3.08E-01 (0.33 km ESE)
(0.28 km NNW)
(0.33 km ESE)
(0.28 km NNW)
Jul-Sep 2.17E-01 5.83E-01 1.46E-01 6.82E-01 (0.33 km ESE)
(0.28 km NNW)
(0.33 km ESE)
(0.28 km NNW) 2.05E-01 5.55E-01 1.37E-01 6.45E-01 Oct-Dec (0.33 km ESE)
(0.28 km NNW)
(0.33 km ESE)
(0.28 km NNW)
Jan-Dec 8.21 E-01 2.02E+00 5.50E-01 2.39E+00 (0.33 km ESE)
(0.28 km NNW)
(0.33 km ESE)
(0.28 km NNW)
(a) All directions and distances are with respect to the reactor building vent.
0 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, iodines, and tritium released in gaseous effluents are presented in Tables 4.2-A through 4.2-E. These tables cover the individual calendar quarters and the total calendar year, respectively. Doses resulting from releases of noble gases are addressed independently in the PNPS ODCM.
Therefore, none of these tables for maximum individual doses include any dose contribution from noble gases. The presentation and analysis of doses resulting from noble gases are addressed in Section 4.1 of this report.
Tables 4.2-A through 4.2-E summarize the maximum total body and organ doses for the adult, teen, child, and infant age classes resulting from the major gaseous exposure pathways. These tables present the dose data according to specific receptor location and the exposure pathways assumed to occur at that location. For example, the second column of the tables presents the information for the hypothetical maximum-exposed at the most restrictive site boundary location, where only inhalation and ground deposition exposure pathways are assumed to occur..
Since this is a shoreline location controlled by Entergy, the 'other pathways of garden vegetable production, milk production, and meat production are assumed not to occur. Doses for other offsite locations not under Entergy control, where other exposure pathways can and do occur, are presented in subsequent columns of the tables, and represent the potential maximum doses to individuals at these locations.
Radioactivity (particulates, radioiodines, and tritium) released in gaseous effluents from PNPS during 2007 resulted in a maximum total body dose.(teen age class) of 0.022 mrem (child age class at nearest garden location, 0.87 kilometers SE from the Reactor Building), while the maximum organ dose was 0.16 mrem (infant thyroid at nearest milk animal location, 3.97 kilometers WSW from the Reactor Building).
Page 22
Table 4.2-A Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Jan-Mar 2007 Receptor:
Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:
NNW ESE SE WSW W
S Distance1:
0.28 km 0.80 km 0.87 km 3.97 km 5.77 km 3.80 km Pathway2 :
DI DI DIV 3 DIVCG 3 DIVCM3 DIVM 3 Age Class: Adult Bone 1.53E-04 3.20E-05 1.92E-03 1.39E-04 7.57E-05 1.24E-04 GI-LLI 7.70E-03 1.69E-03 5.31 E-03 4.46E-04 2.65E-04 3.34E-04 Kidney 7.65E-03 1.68E-03 5.08E-03 4.63E-04 2.74E-04 3.21 E-04 Liver 7.58E-03 1.66E-03 5.07E-03 4.51 E-04 2.67E-04 3.20E-04 Lung 8.05E-03 1.76E-03 5.03E-03 4.23E-04 2.52E-04 3.14E-04 Thyroid 3.17E-02 6.72E-03 2.57E-02 8.48E-03 4.86E-03 2;22E-03 T.Body 7.53E-03 1.65E-03 5.08E-03 4.41 E-04 2.62E-04 3.19E-04 Age Class: Teen Bone 2.17E-04 4.54E-05 2.96E-03 2.25E-04 1.20E-04 1.88E-04 GI-LLI 7.79E-03 1.71 E-03 5.96E-03 5.18E-04 2.96E-04 3.60E-04 Kidney 7.78E-03 1.70E-03 5.71 E-03 5.60E-04 3.20E-04 3.47E-04 Liver 7.69E-03 1.69E-03 5.72E-03 5:40E-04 3.08E-04 3.47E-04 Lung 8.51 E-03 1.86E-03 5.71 E-03 4.94E-04 2.83E-04 3.43E-04 Thyroid 3.82E-02 8.07E-03 2.45E-02 1.23E-02 6.94E-03 1.99E-03 T.Body 7.61E-03 1.67E-03 5.71E-03 5.17E-04 2.95E-04 3.45E-04 Age Class: Child Bone 2.97E-04 6.21 E-05 7.03E-03 5.40E-04 2.86E-04 4.44E-04 GI-LLI 6.78E-03 1.49E-03 8.17E-03 7.29E-04 4.14E-04 4.90E-04 Kidney 6.89E-03 1.51 E-03 8.07E-03 8.26E-04 4.67E-04 4.86E-04 Liver 6.81 E-03 1.49E-03 8.12E-03 7.99E-04 4.50E-04 4.89E-04 Lung 7.51E-03 1.64E-03 8.01E-03 7.13E-04 4.05E-04 4.78E-04 Thyroid 4.25E-02 8.97E-03 3.52E-02 2.35E-02 1.32E-02 2.90E-03 T.Body 6.73E-03 1.48E-03 8.14E-03 7.60E-04 4.30E-04 4.89E-04 Age Class: Infant Bone 2.13E-04 4.46E-05 3.16E-05 3.31E-04 1.61 E-04 1.76E-06 GI-LLI 3.88E-03 8.50E-04 6.04E-04 3.09E-04 1.52E-04 3.47E-05 Kidney 3.98E-03 8.72E-04 6.19E-04 4.93E-04 2.52E-04 3.56E-05 Liver 3.96E-03 8.68E-04 6.17E-04 4.90E-04 2.47E-04 3.55E-05 Lung 4.62E-03 1;01 E-03 7.14E-04 3.09E-04 1.51 E-04 4.06E-05 Thyroid 3.67E-02 7.73E-03 5.49E-03 5.18E-02 2.86E-02 3.24E-04 T.Body 3.88E-03 8.51 E-04 6.05E-04 3.76E-04 1.88E-04 3.48E-05 1
2 Distances are measured with respect to the reactor building vent.
Pathway designations are as follows:
D = Deposition (Ground Plane)
I = Inhalation V= Vegetable Garden C = Cow Milk G = Goat Milk M = Meat 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 2007 Receptor:
Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:
NNW ESE SE WSW WS Distance1:
0.28 km 0.80 km 0.87 km 3.97 km 5.77 km 3.80 km Pathway2:
DI DI DIV DIVCG DIVCM DIVM Age Class: Adult
-Bone 1.89E-04 3.96E-05 2.47E-03 1.81 E-04 9.97E-05 1.69E-04 GI-LLI 3.91 E-03 8.55E-04 2.94E-03 2.44E-04 1.46E-04 1.92E-04 Kidney 3.72E-03 8.14E-04 2.49E-03 2.46E-04 1.45E-04 1.59E-04 Liver 3.64E-03 7.98E-04 2.47E-03 2.32E-04 1.37E-04 1.58E-04 Lung 4.68E-03 1.01 E-03 2.51 E-03 2.08E-04 1.24E-04 1.56E-04 Thyroid 3.11 E-02 6.55E-03 2.68E-02 8.52E-03 4.69E-03 2.02E-03 T.Body 3.59E-03 7.87E-04 2.49E-03 2.22E-04 1.31 E-04 1.58E-04 Age Class: Teen Bone 2.68E-04 5.61 E-05 3.81 E-03 2.92E-04 1.57E-04 2.56E-04 GI-LLI 3.97E-03 8.67E-04 3.28E-03 2.82E-04 1.62E-04 2.04E-04 Kidney 3.82E-03 8.35E-04 2.80E-03 3.09E-04 1.75E-04 1.71 E-04 Liver 3.72E-03 8.14E-04 2.80E-03 2.86E-04 1.63E-04 1.71 E-04 Lung 5.42E-03 1.17E-03 2.91E-03 2.47E-04 1.41 E-04 1.74E-04 Thyroid 3.83E-02 8.04E-03 2.49E-02 1.25E-02 6.74E-03 1.79E-03 T.Body 3.64E-03 7.97E-04 2.82E-03 2.65E-04 1.51 E-04 1.72E-04 Age Class: Child Bone 3.67E-04 7.68E-05 9.06E-03 7.00E-04 3.75E-04 6.05E-04 GI-LLI 3.33E-03 7.29E-04 4.19E-03 3.72E-04 2.11E-04 2.55E-04 Kidney 3.39E-03 7.41 E-04 3.94E-03 4.61 E-04 2.58E-04 2.39E-04 Liver 3.30E-03 7.22E-04 3.97E-03 4.29E-04 2.41 E-04 2.41 E-04 Lung 4.76E-03 1.03E-03 3.97E-03 3.49E-04 1.98E-04 2.37E-04 Thyroid 4.34E-02 9.11 E-03 3.58E-02 2.39E-02 1.29E-02 2.61 E-03 T.Body 3.23E-03 7.07E-04 4.09E-03 3.99E-04 2.26E-04 2.49E-04 Age Class: Infant Bone 2.63E-04 5.50E-05 3.90E-05 3.95E-04 1.90E-04 2.14E-06 GI-LLI 1.88E-03 4.12E-04 2.93E-04 1.64E-04 8.20E-05 1.69E-05 Kidney 1.97E-03 4.30E-04 3.06E-04 3.43E-04 1.76E-04 1.76E-05 Liver 1.95E-03 4.26E-04 3.03E-04 3.35E-04 1.71 E-04 1.74E-05 Lung 3.23E-03 6.94E-04 4.93E-04 1.56E-04 7.73E-05 2.79E-05 Thyroid 3.87E-02 8.12E-03 5.75E-03 5.33E-02 2.82E-02 3.18E-04 T.Body 1.87E-03 4.09E-04 2.91E-04 2.26E-04 1.14E-04 1.67E-05 1
2 Distances are measured with respect to the reactor building vent.
Pathway designations are as follows:
D = Deposition (Ground Plane)
I = Inhalation C
Cow Milk G = Goat Milk V = Vegetable Garden M = Meat Page 24
Table 4.2-C Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Jul-Sep 2007 Receptor:
Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:
NNW ESE SE WSW W
S Distance: I 0.28 km 0.80 km 0.87 km 3.97 km 5.77 km 3.80 km Pathway2:
DI DI DIV DIVCG DIVCM DIVM Age Class: Adult Bone 2.54E-04 5.32E-05 3.85E-03 2.52E-04 1.37E-04 2.46E-04 GI-LLI 5.41E-03 1.18E-03 3.93E-03 3.18E-04 1.88E-04 2.52E-04 Kidney 4.70E-03 1.03E-03 3.08E-03 2.80E-04 1.66E-04 1.96E-04 Liver 4.63E-03 1.02E-03 3.05E-03 2.69E-04 1.60E-04 1.94E-04 Lung 6.63E-03 1.43E-03 3.31 E-03 2.74E-04 1.62E-04 2.06E-04 Thyroid 2.24E-02 4.74E-03 1.53E-02 4.70E-03 2.68E-03 1.27E-03 T. Body 4.59E-03 1.01 E-03 3.14E-03 2.70E-04 1.60E-04 1.99E-04 Age Class-Teen Bone 3.61E-04 7.55E-05 5.95E-03 4.03E-04 2.15E-04 3.73E-04 GI-LLI 5.50E-03 1.20E-03 4.37E-03 3.66E-04 2.09E-04 2.69E-04 Kidney 4.79E-03 1.05E-03 3.46E-03 3.36E-04 1.92E-04 2.12E-04 Liver 4.71 E-03 1.03E-03 3.43E-03 3.19E-04 1.83E-04 2.09E-04 Lung 8.OOE-03 1.72E-03 3.88E-03 3.26E-04 1.87E-04 2.32E-04 Thyroid 2.76E-02 5.82E-03 1.49E-02 6.84E-03 3.83E-03 1.16E-03 T.Body 4.64E-03 1.02E-03 3.57E-03 3.19E-04 1.82E-04 2.18E-04 Age Class: Child Bone 4.96E-04 1.04E-04 1.42E-02 9.66E-04 5.13E-04 8.83E-04 GI-LLI 4.47E-03 9.77E-04 5.50E-03 4.81 E-04 2.73E-04 3.34E-04 Kidney 4.25E-03 9.30E-04 4.88E-03 4.95E-04 2.81 E-04 2.97E-04 Liver 4.17E-03 9.14E-04 4.85E-03 4.69E-04 2.66E-04 2.94E-04 Lung 7.02E-03 1.51 E-03 5.23E-03 4.56E-04 2.59E-04 3.13E-04 Thyroid 3.19E-02 6.72E-03 2.14E-02 1.30E-02 7.27E-03 1.70E-03 T.Body 4.12E-03 9.03E-04 5.23E-03 4.78E-04 2.71E-04 3.17E-04 Age Class: Infant Bone 3.49E-04 7.29E-05 5.16E-05 4.39E-04 2.05E-04 2.79E-06 GI-LLI 2.49E-03 5.45E-04 3.87E-04 1.98E-04 9.72E-05 2.24E-05 Kidney 2.46E-03 5.38E-04 3.83E-04 2.87E-04 1.47E-04 2.22E-05 Liver 2.44E-03 5.34E-04 3.80E-04 2.72E-04 1.38E-04 2.21 E-05 Lung508E-03 1.09E-03 7.71 E-04 2.08E-04 1.03E-04 4.30E-05 Thyroid 2.79E-02 5.87E-03 4.16E-03 2.85E-02 1.57E-02 2.43E-04 T.Body 2.38E-03 5.21E-04 3.70E-04 2.31E-04 1.15E-04 2.15E-05 1 Distances are measured with respect to the reactor building vent.
2 Pathway designations are as follows:
D = Deposition (Ground Plane)
I = Inhalation C = Cow Milk G = Goat Milk V = Vegetable Garden M = Meat Page 25
Table 4.2-D Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Oct-Dec 2007 Receptor:
Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:
NNW ESE SE WSW W
S Distance1:
0.28 km 0.80 km 0.87 km 3.97 km 5.77 km 3.80 km Pathway2:
DI DI DIV 3 DIVCG 3 DIVCM3 DIVM3 Age Class: Adult Bone 2.32E-04 4.86E-05 3.33E-03 2.22E-04 1.21 E-04 2.16E-04 GI-LLI 4.99E-03 1.09E-03 3.55E-03 2.83E-04 1.68E-04 2.26E-04 Kidney 4.11E-03 9.01E-04 2.72E-03 2.47E-04 1.46E-04 1.72E-04 Liver 4.06E-03 8.91 E-04 2.70E-03 2.41 E-04 1.43E-04 1.71 E-04 Lung 6.32E-03 1.36E-03 2.98E-03 2.44E-04 1.45E-04 1.84E-04 Thyroid 1.96E-02 4.15E-03 1.46E-02 4.41 E-03 2.48E-03 1.15E-03 T.Body 4.03E-03 8.84E-04 2.77E-03 2.39E-04 1.42E-04 1.75E-04 Age Class: Teen Bone 3.30E-04 6.89E-05 5.13E-03 3.55E-04 1.90E-04 3.26E-04 GI-LLI 5.09E-03 1.11E-03 3.91E-03 3.25E-04 1.86E-04 2.39E-04 Kidney 4.19E-03 9.19E-04 3.05E-03 2.99E-04 1.70E-04 1.86E-04 Liver 4.13E-03 9.04E-04 3.04E-03 2.88E-04 1.64E-04 1.86E-04 Lung 7.83E-03 1.68E-03 3.53E-03 2.93E-04 1.68E-04 2.09E-04 Thyroid 2.40E-02 5.06E-03 1.40E-02 6.41 E-03 3.54E-03 1.04E-03 T.Body 4.08E-03 8.94E-04 3.15E-03 2.82E-04 1.61 E-04 1.91 E-04 Age Class: Child Bone 4.52E-04 9.45E-05 1.22E-02 8.50E-04 4.52E-04 7.70E-04 GI-LLI 4.04E-03 8.82E-04 4.86E-03 4.23E-04 2.40E-04 2.94E-04 Kidney 3.71E-03 8.13E-04 4.31E-03 4.40E-04 2.49E-04 2.60E-04 Liver 3.65E-03 8.01 E-04 4.31 E-03 4.26E-04 2.41 E-04 2.63E-04 Lung 6.86E-03 1.47E-03 4.70E-03 4.07E-04 2.31 E-04 2.78E-04 Thyroid 2.74E-02 5.76E-03 2.01 E-02 1.22E-02 6.71 E-03 1.52E-03 T.Body 3.61 E-03 7.92E-04 4.59E-03 4.21 E-04 2.38E-04 2.77E-04 Age Class: Infant Bone 3.19E-04 6.67E-05 4.72E-05 4.OOE-04 1.87E-04 2.52E-06 GI-LLI 2.23E-03 4.87E-04 3.46E-04 1.74E-04 8.55E-05 1.98E-05 Kidney 2.15E-03 4.71 E-04 3.34E-04 2.61 E-04 1.33E-04 1.92E-05 Liver 2.14E-03 4.68E-04 3.32E-04 2,60E-04 1.31 E-04 1.91 E-05 Lung 5.09E-03 1.09E-03 7.70E-04 1 E89E-04 9.41 E-05 4.21 E-05 Thyroid 2.39E-02 5.02E-03 3.56E-03 2.68E-02 1.45E-02 2.01 E-04 T.Body 2.09E-03 4.57E-04 3.25E-04 2.06E-04 1.02E-04 1.87E-05 1 Distances are measured with respect 2 Pathway designations are as follows:
D = Deposition (Ground Plane)
C = Cow Milk to the reactor, building vent.
I = Inhalation G = Goat Milk V = Vegetable Garden M = Meat Doses are conservative since it is unlikely for vegetables to be grown outside or for animals to be fed on pasture during winter months.
Page 26
Table 4.2-E Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Jan-Dec 2007 Receptor:
Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:
NNW ESE SE WSW W
S Distance1:'
0.28 km 0.80 km 0.87 km 3.97 km 5.77 km 3.80 km Pathway2 :
DI DI DIV 3 DIVCG3 DIVCM3 DIVM3 Age Class: Adult Bone 8.29E-04 1.73E-04 1.16E-02 7.94E-04 4.33E-04 7.56E-04 GI-LLI 2.20E-02 4.81 E-03 1.57E-02 1.29E-03 7.67E-04 1.OOE-03 Kidney 2.02E-02 4.42E-03 1.34E-02 1.24E-03 7.31 E-04 8.48E-04 Liver 1.99E-02 4.37E-03 1.33E-02 1.19E-03 7.07E-04 8.42E-04 Lung 2.57E-02 5.57E-03 1.38E-02 1.15E-03 6.82E-04 8.60E-04 Thyroid 1.05E-01 2.22E-02 8.24E-02 2.61 E-02 1.47E-02 6.66E-03 T.Body 1.97E-02 4.33E-03 1.35E-02 1.17E-03 6.95E-04 8.51E-04 A e Class: Teen Bone 1.18E-03 2.46E-04 1.78E-02 1.28E-03 6.82E-04 1.14E-03 GI-LLI 2.24E-02 4.88E-03 1.75E-02 1.49E-03 8.53E-04 1.07E-03 Kidney 2.06E-02 4.51E-03 1.50E-02 1.50E-03 8.57E-04 9.15E-04 Liver 2.02E-02 4.44E-03 1.50E-02 1.43E-03 8.17E-04 9.13E-04 Lung 2.98E-02 6.43E-03 1.60E-02 1.36E-03 7.79E-04 9.58E-04 Thyroid 1.28E-01 2.70E-02 7.82E-02 3.81E-02 2.11E-02 5.99E-03 T.Body' 2.OOE-02 4.38E-03 1.53E-02
- 1. 38E-03 7.90E-04 9.26E-04 Age Class: Child Bone 1.61 E-03 3.37E-04 4.24E-02 3.06E-03 1.63E-03 2.70E-03 GI-LLI 1.86E-02 4.07E-03 2.27E-02 2.01E-03 1.14E-03 1.37E-03 Kidney 1.82E-02 3.99E-03 2.12E-02 2.22E-03 1.26E-03 1.28E-03 Liver 1.79E-02 3.93E-03 2.12E-02 2.12E-03 1.20E-03 1.29E-03 Lung 2.61E-02 5.65E-03 2.19E-02 1.93E-03 1.09E-03 1.31 E-03 Thyroid 1.45E-01 3.06E-02 1.12E-01 7.27E-02 4.OOE-02 8.73E-03 T.Body 1.77E-02 3.88E-03 2.20E-02 2.06E-03 1.16E-03 1.33E-03 Age Class: Infant Bone 1.14E-03 2.39E-04 1.69E-04 1.57E-03 7.43E-04 9.21 E-06 GI-LLI 1.05E-02 2.29E-03 1.63E-03 8.44E-04 4.16E-04 9.38E-05 Kidney 1.06E-02 2.31 E-03 1.64E-03 1.38E-03 7.08E-04 9.47E-05 Liver 1.05E-02 2.30E-03 1.63E-03 1.36E-03 6.87E-04 9.41 E-05 Lung 1.80E-02 3.87E-03 2.75E-03 8.62E-04 4.26E-04 1.54E-04 Thyroid 1.27E-01 2.67E-02 1.90E-02 1.60E-01 8.70E-02 1.09E-03 T.Body 1.02E-02 2.24E-03 1.59E-03 1.04E-03 5.20E-04 9.18E-05 1 Distances are measured with respect to the reactor building vent.
Pathway designations are as follows:
D = Deposition (Ground Plane)
I = Inhalation V =Vegetable Garden C = Cow Milk G = Goat Milk M = Meat 3 Doses are conservative since it is unlikely for vegetables to be grown outside or for animals to be fed on pasture during winter months.
Page 27
4.3 Doses From Liquid Effluent Releases Liquid effluent release-data presented in Tables 2.3-A and 2.3-B were used as input to the dose assessment computer program to calculate radiation doses.
The maximum individual doses resulting from radionuclides released in liquid effluents are presentedin 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 a proportionally higher dose for that quarter. However, when that quarter's activity values are included in the annual sum, and divided by the total annual dilution flow, the resulting dose contribution will be smaller. In such a situation, the annual dose will actually be less than the sum of the individual quarterly doses.
Radioactivity released in liquid effluents from PNPS during 2007 resulted in a maximum total body dose (teen age class) of 0.0000049 mrem. The maximum organ dose (teen age class, liver) was 0.0000076 mrem.
Page 28
Table 4.3-A Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jan-Mar 2007 No Liquid Effluent Discharges Occurred During This Period Age Class Organ Dose - mrem
- Organ Adult
[
Teen Child Bone 0.OOE+00 0.OOE+00 0.OOE+O0 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 0.OOE+00 0.OOE+00 0.OOE+00 Liver 0.OOE+00 0.OOE+00 0.OOE+00 Lung 0.OOE+00 0.OOE+00 0.OOE+00 Thyroid 0.OOE+00 0.OOE+00 0.OOE+00 T.Body O.OOE+00 O.OOE+00 0.OOE+00 These doses are conservative since the same usage factor was applied for each quarter.
In reality, it is unlikely that anyone would be swimming or boating during the entire year.
However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose.
Page 29
Table 4.3-B Maximum Individual Organ Doses,-- mrem From Liquid Release Period: Apr-Jun 2007 Age Class Organ Dose - mrem Organ Adult I
Teen I
Child Bone 9.70E-08 1.48E-07 1.29E-07 GI-LLI 7.43E-08 1.05E-07 5.21 E-08 Kidney 1.12E-07 1.44E-07 8.79E-08 Liver 1.91 E-07 2.23E-07 1.64E-07 Lung 8.53E-08 1.1 9E-07 6.45E-08 Thyroid 7.20E-08 1.03E-07 5.14E-08 T.Body 1.50E-07 1.45E-07 6.79E-08 Page 30
Table 4.3-C Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jul-Sep 2007 Age Class Organ Dose - mrem Organ Adult Teen Child Bone 9.41 E-07 1.57E-06 1.24E-06 GI-LLI 1.50E-06 1.64E-06 5.81 E-07 Kidney 6.38E-07 1.21 E-06 5.77E-07 Liver 1.44E-06 2.02E-06 1.34E-06 Lung 3.78E-07 9.70E-07 3.53E-07 Thyroid 2.49E-07 8.17E-07 2.28E-07 T.Body 1.12E-06 1.33E-06 4.98E-07 J
Page 31
Table 4.3-D Maximum Individual Organ Doses -- mrem From Liquid Release Period: Oct-Dec 2007 Age Class Organ Dose - mrem
- Organ Adult Teen I
Child Bone 2.27E-06 3.77E-06 2.98E-06 GI-LLI 2.18E-06 2.92E-06 8.38E-07 Kidney 1.36E-06 2.78E-06 1.28E-06 Liver 3.43E-06 4.86E-06 3.22E-06 Lung 6.91E-07 2.16E-06 7.13E-07 Thyroid 3.59E-07 1.77E-06 3.94E-07 T.Body 2.62E-06 3.09E-06 1.06E-06
- 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 2007 Age Class Organ Dose - mrem
- Organ Adult Teen Child Bone 3.53E-06.
5.86E-06 4.64E-06 GI-LLI 4.01 E-06 4.98E-06 1.57E-06
-Kidney 2.23E-06 4.40E-06 "
2.07E-06 Liver 5.39E-06 7.57E-06 5.03E-06 Luna 1.22E-06 3.46E-Q6 1.20E-06 Thyroid 7.1 OE-07 2.87E-06 7.08E-07 T.Body 4.15E-06 4.86E-06 1.73E-06
- 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 281 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 79.7 t 45.0 mR/yr to 64.6 +/- 8.3 mR/yr. Such a corrected dose is not statistically different from the Zone 4 average of 65.2 _ 9.2 mR/yr, and is indicative of natural background radiation.
Although the annuaI exposure at TLD location OA was 216 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 <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per year would only receive an incremental dose of 1.0 mrem over natural background radiation levels. At the nearest residence 0.80 kilometers (0.5 miles) southeast of the PNPS Reactor Building, the annual exposure was calculated as being 61.8 +/- 9.3 mR (based on continuous occupancy at this location), which compares quite well to the Zone 4 annual average background radiation level of 65.2 +/- 9.2 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 40CFR1 90. Both of these limits are to be applied to real members of the general public, so the fact that the dose to the hypothetical maximum-exposed individual is within the limits ensures that any dose received by a real member of the public would be smaller and well within any applicable limit.
In 1994, Pilgrim Station opened the old training facility (I&S Building) overlooking the plant as a health club for its employees. This site is immediately adjacent to the protected area boundary near monitoring location OA and receives appreciable amounts of direct ambient'and sky shine exposure from the turbine building. Although most personnel using this facility are employees of Entergy, they are considered to be members of the public. Due to their extended presence in the facility (500 hr/yr, assuming utilization of the facility for 2 hr/day, 5 days a week, for 50 weeks/yr), these personnel represent the most conservative case in regards to ambient radiation exposure to a member of the public within the PNPS owner controlled area. Their annual incremental radiation dose above background during 2007 is estimated as being about 2.2 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 2007.
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 0.0049 mrem, resulting from inhalation.
In response to the September 11, 2001 terrorism event, access to areas in the immediate vicinity of Pilgrim Station by members of the general public has been discontinued.
A number of.. National Guard troops have been posted at Pilgrim Station to patrol the owner-controlled areas beyond the protected area. However, since these individuals are not employees of Pilgrim Station, they are considered to be members of the public for dose assessment purposes.
Considering that their location is not fixed and they are patrolling areas within the site boundary, their annual exposure was estimated based on the average of those TLDs between the protected area fence and site boundary. The maximum ambient dose received by a member of the National Guard is estimated to be about 5.4 mrem, with the corresponding inhalation dose as described above equaling about 0.022 mrem.
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 2007 Average Exposure +/- Standard Deviation: mR/period Exposure Zone 1*
Zone 2 Zone 3 Zone 4 Period 0-3 km 3-8 km 8-15 km
>15 km Jan-Mar 22.1 + 18.3 14.5 +/- 1.9 i4.1 +/- 1.4 16.4 +/- 2.7 Apr-Jun.
19.3 +/-8.3 15.0 +/- 1.8 14.8 +/- 1.8 16.5 +/- 2.6 Jul-Sep 18.9 +/-6.9 15.1 +/- 2.2
.14.7 1.7 16.1 +/- 2.5 Oct-Dec 19.3 6.8 15.4 +/- 2.0 14.5 2.0 16.3+/-2.1 Jan-Dec 79.7 +/- 45.0**
60.0 +/- 7.9 58.0 +/- 6.7 65.2 +/- 9.2 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 64.6 +/- 8.3 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 2007 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 2007 A.
Instantaneous Dose Rate Limit.- Noble Gases PNPS ODCM Control 3.3.1.a Limit: 500 mrem/yr Total Body Dose Period Jan-Dec Value - mrem/yr 5.50E-01 Fraction of Limit 1.10E-01%
B.
Instantaneous Dose Rate Limit - Noble Gases PNPS ODCM Control'3.3.1.a Limit: 3000 mrem/yr Skin Dose Period Jan-Dec Value - mrem/yr 2.39E+00 Fraction of Limit 7.98E-02%
C.
Instantaneous Dose Rate Limit - Particulates, lodines, & Tritium PNPS ODCM Control 3.3.1.b Limit: 1500 mrem/yr Organ Dose Period Jan-Dec Value - mrem/yr 1.60E-01 Fraction of Limit 1.07E-02%
D.
Quarterly Dose Objective - Noble Gas Gamma Air-Dose PNPS ODCM Control 3.3.2.a Objective: 5 mrad Gamma Air Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value - mrad 3.1OE-01 8.81 E-02 2.17E-01 2.05E-01 Fraction of Limit 6.21 E+00%
1.76E+00%
4.35E+00%
4.1 OE+00%
E.
Annual Dose Objective - Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.b Objective: 10 mrad Gamma Air Dose Period Jan-Dec Value - mrad/yr 8.21 E-01 Fraction of Limit 8.21 E+00%
Page 38
Table 6.1 (continued)
Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2007 F.
Quarterly Dose Objective - Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.a Objective: 10 mrad Beta Air Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value - mrad 6.05E-01 2.72E-01 5.83E-01 5.55E-01 Fraction of Limit 6.05E+00%
2.72E+00%
5.83E+00%
5.55E+00%
G.
Annual Dose Objective - Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.b Objective: 20 mrad Beta Air Dose Period Jan-Dec Value - mrad/vr 2.02E+00 Fraction of Limit 1.01 E+01%
H.
Quarterly Dose Objective - Particulates, lodines, & Tritium PNPS ODCM Control 3.3.3.a Objective: 7.5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value - mrem 5.18E-02 5.33E-02 3.19E-02 2.74E-02 Fraction of Limit 6.91 E-01%
7.1OE-01%
4.25E-01 %
3.65E-01 %
I.
Annual Dose Objective - Particulates, lodines, & Tritium PNPS ODCM Control 3.3.3.b Objective: 15 mrem Organ Dose Period Jan-Dec Value - mrem/yr 1.60E-01 Fraction of Limit 1.07E+00%
Page 39
6.2 Liquid Effluent Releases Liquid effluent concentration limits and dose objectives from the PNPS ODCM are shown in Table 6.2. The quarterly average concentrations from Table 2.3-A were used to calculate the percent concentration limits. The maximum quarterly and annual whole body and organ doses from Tables 4.3-A through 4.3-E were used to calculate the percentages shown in Table 6.2. The resulting concentrations, as well as organ and total body doses from Pilgrim Station's liquid releases during 2007 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 2007 A.
Fission and Activation Product Effluent Concentration Limit PNPS ODCM Control 3.2.1 Limit: 10CFR20 Appendix B, Table 2, Column 2 Value Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value - iCi/mL O.00E+00 2.04E-14 2.55E-13 5.60E-13 2.23E-13 Fraction of Limit 0.00E+00%
2.04E-06%
2.09E-05%
5.17E-05%
1.99E-05%
B.
Tritium Average Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1.OE-03 pCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value - uCi/mL 0.00E+00 4.31 E-1 0 8.22E-10 3.28E-10 3.94E-10 Fraction of Limit 0.00E+00%
4.31 E-05%
8.22E-05%
3.28E-05%
3.94E-05%
C.
Dissolved and Entrained Noble Gases Concentration Limit PNPS ODCM Control 3.2.1 Limit: 2.OE-04 gCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value - aCi/mL 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Fraction of Limit 0.00E+00%
0.00E+00%
0.00E+00%
0.OOE+00%
0.OOE+00%
Page 41
Table 6.2 (continued)
Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2007 D.
Quarterly Total Body Dose Objective PNPS ODCM Control 3.2.2.a Objective: 1.5 mrem Total Body Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value - mrem 0.OOE+00 1.50E-07 1.33E-06 3.09E-06 Fraction of Limit 0.OOE+00%
9.98E-06%
8.85E-05%
2.06E-04%
E.
Annual Total Body Dose Objective PNPS ODCM Control 3.2.2.b Objective: 3 mrem Total Body Dose Period Jan-Dec Value - mrem 4.86E-06 Fraction of Limit 1.62E-04%
F.
Quarterly Organ Dose Objective PNPS ODCM Control 3.2.2.a Objective: 5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value - mrem O.OOE+00 2.23E-07 2.02E-06 4.86E-06 Fraction of Limit 0.OOE+00%
4.47E-06%
4.04E-05%
9.71 E-05%
G.
Annual Organ Dose Objective PNPS ODCM Control 3.2.2.b Objective: 10 mrem Organ Dose Period Jan-Dec Value - mrem 7.57E-06 Fraction of Limit 7.57E-05%
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 35.7 cubic meters of spent resins, filter sludges, etc.,
containing a total activity of about 79.8 Curies were shipped from PNPS for processing and disposal. Dry activated wastes and contaminated equipment shipped during the period totaled 768 cubic meters and contained 2.08 Curies of radioactivity. No shipments of irradiated components were shipped during the reporting period; therefore, the values are 0.00 cubic meters and 0.00 curies. The "Other" category, made up from "Hi Rad Trash" consisted of 34.3 cubic meters and 12.8 curies. No shipments of irradiated fuel were made during the reporting period.
Estimates of major radionuclide's comprising of greater than 1% of the total activity in each waste category shipped, are listed in Table 7.0. There were 26 shipments to Oak Ridge, TN (Energy Solutions); 1 shipment to Memphis, TN (Studsvik/RACE,LLC) and 9 shipments to Erwin, TN (Studsvik Processing Facility).
Page 43
Table 7.0 Pilgrim Nuclear Power Station Radioactive Effluent-Release Report Solid Waste and Irradiated Fuel Shipments January-December 2007 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:2007 Type of waste Volume - m" Curies Total Error
- a. Spent resins, filters, filter sludges, 3.57E+01 7.98E+01
+/- 25%
evaporator bottoms, etc.
- b. Dry activated waste, contaminated 7.68E+02 2.08E+00
+/- 25%
equipment, etc.
- c. Irradiated components, control rods, etc.
0.OOE+00 0.00E+00'
+/-25%
- d. Other (describe): "Hi Rad"Trash 3.43E+01 1.28E+01
+/-25%
- 2. Estimate of major nuclide composition by type of waste1 Type of waste Radionuclide Abundance Total Error
- a. Spent resins, filters, filter sludges, C-14 32.67%
+/- 25%
evaporator bottoms, etc.
Mn-54 2.30 %
+/- 25%
Fe-55 14.89%
+/- 25%
Co-60 15.94%
+/- 25%
Zn-65 16.93%
+/-25%
Cs-134 5.04%
+/-25%
Cs-137 10.13%
+/-25%
- b. Dry activated waste, contaminated Mn-54 4.15 %
+/- 25%
equipment, etc.
Fe-55 80.44 %
+/- 25%
Co-60 12.52%
+/-25%
Tc-99 1.18%
+/-25%
- c. Irradiated components, control rods, etc.
N/A
- d. Other (describe): "Hi Rad" Trash Cr-51 8.79 %
+/- 25%
Mn-54 3.65%
+/- 25%
Fe-55 41.02%
+/- 25%
Co-58 1.26%
+/-25%
Co-60 10.40 %
+/- 25%
Ni-63 29.99 %
+/- 25%
Zn-65 1.37_%
+/- 25%
"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 J
Destination Tractor-trailer Energy Solutions, (Hittman Transport Services)
Oak Ridge, TN 1
Tractor-trailer Studsvik/RACE LLC, *
(Studsvik/RACE Logistics, LLC)
Memphis, TN 9
Tractor-trailer Studsvik Processing Facility, z I (Hittman Transport Services)
Erwin, TN z This processor provides volume reduction services for dry compressible waste, contaminated equipment, etc.
Remaining radioactive wastes will be shipped to Chem Nuclear Systems, Inc. in Barnwell, SC, or Envirocare, Inc.
in Clive, UT for final disposal.
B. IRRADIATED FUEL SHIPMENTS & DISPOSITION
==Number of Shipments I
Mode of Transportation I
Destination k
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 2007. Information regarding revisions to the ODCM can be found attached as Appendix B of this report.
Page 45
9.0 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 46
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 47
-Table A-1 Joint Frequency Distribution of Wind Directions and Speeds For the 33-ft level of the 220-ft Tower Jan-Mar 2007 Class A Freg: 0.141 mphLI N JNNE NE [ENE E
IESE SE ISSEI S ISSWlI SW IWSW W IJWNW[NW I 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
1 3
0 0
0 0
'0 0
0 0
0 1
0 0
0 6
3.5-7.5 13 19 7
9
-8 1
1 0
0 0
2 6'
27' 24 24
- 16.
157 7.5-12.5 3
0 5
"0 0
0 0
0 1
17 0
8 46 31 18 5
134 12.5-18.5 0
0 0
0 0
0 0
0 0
1 0
0 0
7 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 117[ 20 15 9
8 I 1 1
0 1 18 2 14 1 74162 42 12 305 Class B Freg 0.039 mph__
N INNE INE IENE IEISEISE ISSE I S ISSW, ISW jWSWI WW NW INNW 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 0,
1 0
0 2
0 0
0 0
0 0
0 0
0 0
1 4
3.5-7.5 0
0 0
2 2
2 0
1 1
1 1
6 12 7
6 1
42 7,5-12.5
- 0.
0 2
0 0
0 0
0 2
10 '
0 4
7 10 1
1.
37 12.5-18.5 0
0 0
0 0
0 0
'0 0
0 0
0 0
0 1
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 I0 2 I2 I4 2
0 1
3 11 I1 10 19 17 [8 13 84 Class C Freg: 0.055 aph N
NNE N EI N
ENE E IESEI SE ISSE I S ISSW SWISWWI W IIWNWI NW INNWI 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
3 0
2 1
0 0
0,0 0
- 0.
0 0
0 2
0 8
3.5-7.5 0
3 2
2 1
1 0
2 4
4 5
9 3
.8.
12 4
60 7.5-12.5 1
'0 2
0 0
0 0
0 1
7 5
2 18 6
4 2
48 12.5-18.5 0
0 0
0 0
.0 0
0 0
2 0
0 0
- 1.
0
.0 3
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[
6 4
4 2 I1 0 I2I 5 113 101 11 1 21 115 118
[71719 Class D Freg:
0.527
_mph N
NNE I NE I ENE I E I ESE I SE SSE S
SSW SW IWSW W IWNWl NW INNW ITOTAL Calm-0.95 0
0 0
0 0
0 0
0 0
0 0
0 0'
0 0
01 0
0.95-3.5 7
13 5
6
- 4.
6 8
2 4
1 7
8 10 15 11 6
113 3.5-7.5 8
13 18 7
17 9
9 13 14 44 42 100 153 62 40 19 568 7.5-12.5 1
6 2
6 10 9
2 3
9 96 29 20 103 65
.51 22 434 12.5-18.5 0
0 3
4 0
1 1
0 1
3 1
0 4
6 0
0 24 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 32 128 123 [ 31] 25 20 18 1 28 1441 79 128 1270 1148 1102 I 47 1 1197 Page 48
Table A-1 (continued)
Jan-Mar 2007 Class E Fre :
0.194 mph NI NNE INEI ENEI EI sEISEISSEI IsSSWISWL WSW WNW INW INNW I TOTAL Calm-0.95 0
0 0
0 0
0 0
0 1
0 0
0
- 0.
0 0
0 1
0.95-3.5 3
0 6
4 5
2 4
7 12 18 13 17 18 6
1 1
117 3.5-7.5 6
1 2
0.0 0
2 8
10 22 39 58 41 17 18 8
232 7.5-12.5 0
0 0
0 1
0 3
6 3
29 11 2
7 0
3 0
65 12.5-18.5 0
0 0
0 1
1 0
0 0
1 0
0 0
0 0
0 3
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 I9 1
814 17 3 191 21 1261 70 1631 77 1661 23 1221 9 1 418 Class F Frea:
0.041 raph ImN ]
NNE NE I ENE I E I ESE I SE I SSE [ S SW SW I WSW I W I WNW I NW NNW TOTAL Calm-0.95 0
0 0
1 0
0 0
0 0
0 0
0 0
.0 0
0 1
0.95-3.5 0
0 0
0 0
0 1
1 7
4 5
9 4
1 0
0 32 3.5-7.5 1
0 0
0 0
0 0
1 2
5 13 12 3
12 3
3 45 7.5-12.5 0
0 0
0 0
0 0
0 0
2 8
0 0
0 0
0 10 12.5-18.5 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
18.S-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
[
0 1 I0 0112 1 91 11
[26 21 71 3 13 31 88 Class G Fre:
0.003 ph N
NNE INE*
ENEI IESEISE SSEI SI SSW ISWI SW I W
W I WNW INW I 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 0
0 0
0 0
0 0
0 1
0 0
0 1
0 0
0 2
3.5-7.5 0
0 0
0 0
- 0.
0 0
0 0
5 0
0 0
0 0
5 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 0 0 0 0 0 1 1 1 0 I 0 I1 1 0 0I I0 7
Class All Frec 1.000 mph I
m IN NNE INEI ENE I E ESE SE ISSEI S ISSW ISWI WSW I W I WN W
I V I NNW I TOTAL Calm-0.95 0
0 0
1 0
0 0
0 1
0 0
0 0
0 0
0 2
0.95-3.5 11 18 14 12 12 8
13 10 24 23 25 34 34 22 14 8
282 3.5-7.5 28 36 29 20 28 13 12 25 31 76 107 191 239 120 103 51 1109 7.5-12.5 5
6 11 6
11 9
5 9
16 161 53 36 181 112 77 30 728 12.5-18.5 0
0 3
4 1
2 1
0 1
7 1
0 4
14 1
0 39 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 [
44 [
60 157 143 1521 32 131 144 1731 267 11861 261 14581 268 1195189 1 2160 Page 49
Table A-1 (continued)
Apr-Jun 2007 Class A Fre: 0.203 mphI N NNE N E ENE E IESE I SE SSEj S
ISSWvl SWV IWSWI W [WNWI NW [VNNW 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 8
5 5
2 3
0 0
0 0
0 0
0 0
1 3
2 29 3.5-7.5 40 36 45 9
27 9
3 1
5 15 23 12 19 39 21 10 314 7.5-12.5 0
15 7
1 1
0 0
1 1
36 15 2
12 5
0 0
96 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 48 56 57 12 131 9
3 2
6 51 38 14 1
31 45 124 112 1 439 Class B Freg: 0.054
[]
mph N
NNE NE [ENE]
E IESEI SE ISSE I S ISSWI SW IVSVI W IWNWI NW I NNWWITOTAL 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
5 2
2 1
0 1
0 0
0 0
1 0
0 0
2 16 3.5-7.5 4
3 9
6 7
5 2
2 1
13 2
2 6
1 3
5 71 7.5-12.5 0
4 4
1 0
5 1
0 0
10 3
0 1
0 0
0 29 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 6
12 15 9
8 10 4
2 1
23 5
3 17 1
3 17 116 Class C Freg: 0.063 mph I N NNE NE I ENE I E I ESE I SE I SSE I S ISSWj SW IWSwl W IWNWI NW I NNWITOTAL Calm-0.95 0
0 0
0 0
0 0
0 0
0 0
0 0
ý0 0
0 0
0.95-3.5 6
6 4
3 4
0 3
0 1
1 1
1 0
1 0
2 33 3.5-7.5 1
9 6
1 6
3 2
2 3
10 2
7 7
2 1
1 63 7.5-12.5 0"
10 1
1 2
5 0
2 2
11 2
1 2
1 0
0 40 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 17 [25 1 i 5 112 8 J 5 6 ]22 5
9 9 1 4 [1 I_3 I 136 Class D Freg:
0.356 Smph IN NNE NE I ENE I E I ESEI SE SSE I S ISSWI SW IWSwl W IWNwl NW INNWI TOTAL Calm-0.95 0
0 0
0 0
0 0
0 1
0 0
0 0
1 0
0 2
0.95-3.5 21 21 13 6
14 5
8 14 11 6
3 4
6 10 7
17 166 3.5-7.5 7
47 9
16 25 16 28 6
13 60 34 20 53 16 11 9
370 7.5-12.5 6
30 10 3
0 32 3
3 0
56 34 6
15 6
2 0
206 12.5-18.5 0
11 1
0 0
13 0
0 0
0 0
0 0ý 0
0 0
25 18.5-24 0
0 0
0 0
1 0
0 0
0 0
0 0
0 0
0 1
>24 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
TOTAL 34 1109 133 1 25 39 67 39 23 25 1 122 171 1 30 1 74 1 33 20 26 770 Page 50
Table A-1 (continued)
Apr-Jun 2007 Class E Freg:
0.218 mph N
NNE NE ENE E
ESE ISE SSE[ S IsSW( SW IWSWv W IW]
NNW IvTOTAL Calm-0.95 0
0 1
0 0
0 0
0 0
0 0
0 0
0 0
0 1
0.95-3.5 13 9
.3 10 10 3
10 15 6
7 11 14 21 23 12 8
175 3.5-7.5 7
5 0
1 9
5 0
0 1
36 41 51 27 18 6
4 211 7.5-12.5 1
1 0
0 0
0 0
1 0
36 37 5
0 3
0 0
84 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 21 115 4 I11 119 I8 10 I 16 [ 7 80 [ 89 I 70 [ 48 1 44 [18 [12 472 Class F Freg:
0.087 mph IN INNE NE IENE I E ESE SE SSE S
I SSWI SW IWSWl W
IWNWI NW INNW I 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 8
1 0
2 2
0 0
1 3
5 13 23 17 12 0
4 91 3.5-7.5 2
1 0
2 2
0 0
0 1
3 37 22 10 0
0 1
81 7.5-12.5 0
0 0
0 0
0 0
0 0
0 11 4
0 0
0 0
15 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 10 2 I0 4
I4 0 0 I1 4
8 161 149 127 113 1 0 5
188 Class G Freg:
0.019 mph N I INNE[ NE I'ENE E TESE!
SE ISSEI S ISSWI SW IWSWI 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 0
0 0
0 0
0 0
0 3
1 3
6 1
2 0
1 17 3.5-7.5 0
0 0
0 0
0 0
0 0
1 9
3 1
0 0
0 14 7.5-12.5 0
0 0
0 0
0 0
0 0
0 9
2 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 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 0I I
I I00 0 0I0 I0 I
0 3
2 121 1
21 2 0
1 42 Class All Freg:
1.000 mph IN NNE N E E I E SE E
E S
SS I
W*S I
SW IWSWI W IWNWI NW [wINNW TOTAL Calm-0.95 0
-0 1
0 0
0 0
0 1
0 0
0 0
2 0
0 4
0,95-3.5 58 47 27 25 34 8
22 30 24 20 31 49 45 49 22 36 527 3.5-7.5 61 101 69 35 76 38 35 11 24 138 148 117 123 76 42 30 1124 7.5-12.5 7
60 22 6
3 42 4
7 3
149 111 20 30 15 2
0 481 12.5-1"8.5 0
11 1
0 0
13 0
.0 "0
1, 0
0 0
0 0
0 26 18.5-24 0
0 0
0 0
1 0
'00 0
0 0
0 0
0
'1
>24 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
TOTAL 1126 1 219'1 120 1 66 1113 1 102 1 61 [ 48 1 52 1308 1290 1186 1198 1 142 1 66 1 66 12163 Page 51
Table A-1 (continued)
Jul-Sep 2007 Class A Freg:
0.154 mph IN NNE NE I ENE*
ESEI SE [SSE] S [SSWI SW IWSV W, IVVWI NW INNW 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 15 24 6
9 7
0 2
0 0
0 3
0 2
4 7
5 84 3.5-7.5 17 31 28 19 22 4
1 2
10 28 24 5
8 1
3 9
212 7.5-12.5 0
0 0
0 0
0 0
0 1
31 8
0 1
2 1
0 44 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 32 55 134 28 129 4
3 2 11 59 1 35 5 111 7 I.11 114.I 340 Class B Freg:
0.045 mph IN (NNE NE I ENE I E ESE I SE I SSE I -S ISSwI SW Iwswl W IWNWl 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
5 7
3 1
0 1
0 0
0 0
0 2
3 2
1 28 3.5-7.5 0
0 2
1 2
0 1
2 7
18 12 4
5 0
0 0
54 7.5-12.5 0
0 0
0 0
0 0
0 0
15 3
0 0
0 0
0 18 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
TOTALI 3 15 9 14 13 0
2 17 1331 151 17 13 1 2 1 1100 Class C Freg: 0.054 r*h IN INNE] NE LENE E IESEI SE ISSEI S ISsW SW IWSWI W IWNW NW I NNWITOTAL Calm-0.95 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.95-3.5 7
9 5
4 5
3 0
2 0
0 1
0 1
2 2
1 42 3.5-7.5 1
0 2
2 7
2 0
1 7
21 10 3
2 2
2 0
62 7.5-12.5 0
0 0
0 0
0 0
0 0
12 3
0 0
0 0
0 15 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 18 1 917 16 1612 15 '1 0 13 17 1 33 1 314 13 1
14 1 1[ I 11 Class D Freg 0.317 mph I N NNE NE ENEI E
IE ESE SE ]SSE I S ISSW [SW IWSWl W 1WNWI NW INNWTOTAL Calm-0.95 0
0 0
0 0
0 0
0 1
0 0
0 0
0 0
0 1
0.95-3.5 18 35 36 24 39 14 i6 16 14 13 9
10
- 8.
6 6
14 278 3.5-7.5 2
2 16 8
13 12 3
3 38 134 61 19 11 7
4 3
336 7.5-12.5 0
0 0
0 0
0 0
0
-3 60 21 0
0 0
0 0
84 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 120 137 152 32 5 12 6 19 ]19 56 1207 1 91 129 19 13 10 117 699 Page 52
Table A-1 (continued)
Jul-Sep 2007 Class E Freq 0.275 aph I N NNE I NE I ENE I E ESE I SE SSE S
ISSW IWSW I
W vWNWI[
NW INNW (TOTAL Calm-0.95 0
1 0
0 0
0 0
1 1
0 0
1 0
1 0
0 5
0.95-3.5 9
7 9
17 30 9
19 17 28 17 13 21 26 27 29 13 291 3.5-7.5 1
5 11 4
6 3
1 1
17 102 49 55 9
4 7
2 277 7.5-12.5 0
0 0
0 0
0 0
0 2
19 13 0
0 0
0 0
34 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
1 0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
TOTAL 10 13 20 21 36 12 20 19 48 138 75 177 35 32 1 36 15 607 Class F Freg 0.130 mph IN NNE NE ENE E
ESE SE SSE I S SSW SW IWSWI W IWNWl NW INNW TOTAL Calm-0.95 0
0 0
0 0
0 0
0 1
3 1
0 1
0 0
0 6
0.95-3.5 0
0 1
3 0
0 4
3 22 24 18 43 38 17 6
6 185 3.5-7.5 1
0 0
0 0
0 0
0 1
10 61 11 2
2 2
3 93 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
0 1
3 0
0 24 37 84 154 141 119 I8 9 I288 Class G Freg:
0.025 p
N INNEI NE IENEI E
SEI SE ISSE]
S I[SSW] SW I[WSWV IWWNWV N
IW NNW lTOTAL 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 7
8 9
0 1
0 27 3.5-7,5 0
0 0
0 0
0 0
0 0
1 25 2
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
>24 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
TOTL I0 0
0 0
0 0
0 0
[3 32 10 19 10 1
0 155 Class All Freg: 1.000 mph I"N NNE] NE IENEI E IESEI SE I SSE I S ISSWl SW IWSWI W IWNWI NW INNWITOTAL Calm-0.95 0
1 0
0 0
0 0
1 3
3 1
1 1
1 0
0 12 0.95-3.5 52 80 64 60 82 26 42 38 64 56 51 82 86 59 53 40 935 3.5-7.5 22 38 59 34 50 21 6
9 80 314 242 99 37 16 18 17 1062 7.5-12.5 0
0 0
0 0
0 0
0 6
137 52 0
1 2
1 0
199 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 74 119 123 94 1 132 1 47 48 48 1153 1510 1346 1 182 1 125 1 78 1 72 1 57 12208 Page 53
Table A-1 (continued)
Oct-Dec 2007 Class A Frea:
0.088 mph IN ]NNE NE ]ENE E
ESE SE*ISSE I S IsSW[I SV IWSWl W IVNWl 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 2
5 4
0 4
0 0
0 0
0 0
0 0
5 4
4 28 3.5-7.5 13 11 8
2 10 0
0 0
0 0
0 8
30 31 18 9
140 7.5-12.5 2
2 3
0 0
0 0
0 0
0 0
1 10 3
2 2
25 12.5-18.5 0
0 0
0 0
0 0
0 0
0 0
0 0
2 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 17 18 [15 I2 114 0
0 0
0 10 10 1 9 1 40 1 41 124 115 1195 Class B Freg:
0.032 mph' IN
] NNE NE IENE!
E I ESE I SE JSSE I S ISSWI SW IWSWI W
IWNWI 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 2
1 0
0 0
0 0
0 0
0 0
0 1
3 3
1 11 3.5-7.5 1'
2 5
1 7
0 0
0 0
1 6
10 6
1 1
1 42 7.5-12.5 1
6 3
0 0
0 0
0 0
4 2
1 0
0 1
0 18 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 4
9 18 1 7 0 0 0 I0 15 8 111 I7 1 4 1W5 2
711 Class C Freg:
0.047 mph IN INNE I NE IENEI E IESEl SE [SSEI S
ISSW] SW IWSW]
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 0
2 0
3 0
0 1
0 0
1 0
0 4
2 2
2 17 3.5-7.5 1
8 9
4 0
1 1
0 1
4 5
7 5
4 3
1 54 7.5-12.5 1
1 6
2 0
0 0
0 1
7 1
2 7
3 2
0 33 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 2
11 15 9
0 1
2 0 12 12 1 6 91 16 9 17 3
104 Class D Freg:
0.473 mph N
ISSW ISW IWSWl W IWNWI NW NNW TOTAL Calm-0.95 0
0 1
0 1
0 0
0 0
0 0
0 0
0 0
0 2
0.95-3.5 10 13 19 8
12 9
7 10 12 17 17 18 17 16 8
7 200 3.5-7.5 15 35 52 28 31 22 14 15 35 70 35 59 85 56 36 9
597 7.5-12.5 1
4 15 6
9 5
0 8
19 61 17 4
49 16 10 3
227 12.5-18.5 6
5 0
0 3
0 0
0 2
1 0
0 1
0 0
0 18 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 1.32 I I 87 I42 I56I 36 I 21 33 68 1149 169 81 1i52 1 88 J 54 1 19 1044 Page 54
Table A-1 (continued)
Oct-Dec 2007 Class E Freq 0.267 nph I N [NNE NE IENEI E I ESE SE ISSEI S ISSWI SW IWSWI W
_wNw_
NW INNWJI'TOTAL Caim-0.95 1
0 0
0 0
0 0
0 0
0 0
0 2
0 0
1 4
0.95-3.5 4
4 2
3 9
9 16 37 27 9
15 19 16 9
12 3
194 3.5-7.5 1
2 2
1 9
3 10 16 16 50 61 94 53 17 11 0
346 7.5-12.5 0
1 5
2 0
0 0
4 1
12 8
7 10 1
0 0
42 12.5-18.5 0
0 0
0 0
0 0
0 2
0 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 6 I7 1 9 6 I1812 12 57 46 71 1 84 1120 1 72 1 27 1 23 4
588 Class F Frea:
0.073 mph I N INNE I NE I ENE E
ESE I SE I SSE I S ISSWl SW IWSWl W IWNWl NW] NNWlTOTAL Calm-0.95 0
0 0
0 0
0 0
0 0
0 0
1 0ý 0
0 0
1 0.95-3.5 0
0 0
0 1
0 0
3 5-20 16 21 19 5
0 0
90 3.5-7.5 0
1 0
0 0
0 0
0 0
8 45 14 1
0 0
0 69 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 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 I0 1
0 0 I1 0
0 3 15 128 61136120] 5 [0 0
160 Class G Freq:
0.020 m I 2!
N NNE I
NE IENEI E I ESE SE SSE SI SSW SW IWswl W[
IWNWI NW NNW IwTOTAL 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 1
1 7
10 0
0 0
0 19 3.5-7.5 0
0 0
0 0
0 0
0 0
0 20 1
0 0
0 0
21 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 I0 I0 I0[0 I 0 1 0 1 0 1 0 I 1 I 131 I11 1 0 1 0 1 0 1 0 1 44 Class All Fre(
1.000 mph I N I NNE NE I ENE [E IESE I SE I SSE I S ISSWI SW IWSWI W IWNWl NW NNW TOTAL Calm-0.95 1
0 1
0 1
0 0
0 0
0 0
1 2
0 0
1 7
0.95-3.5 18 25 25 14 26 18 24 50 45 48 55 68 57 40 29 17 559 3.5-7.5 31 59 76 36 57 26 25 31 52 133 172 193 180 109 69 20 1269 7.5-12.5 5
14 32 10 9
5 0
12 21 84 32 15 67 23 15 5
349 12.5-18.5 6
.5 0
0 3
0 0
0 4
1 0
0 11, 2
0 0
22 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 I61 103 134 60 [ 96 I 49 I 49 93 1122 266 259 277 1 307 1174 1113 I 43 12206 Page 55
Table A-1 (continued)
Jan-Dec 2007 Class A Freq: 0.146 m.ph I N NNE NE ENE E jESE SES SE S
S L SSW SW IWSWI W IvWNWv NW IN TOTAN Calm-0.95 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.95-3.5 26 35 18 11 14 0
2 0
0 0
3 0
3 10 14 11 147 3.5-7.5 83 97 88 39 67 14 5
3 15 43 49 31 84 95 66 44 823 7.5-12.5 5
17 15 1
1 0
0 1
3 84 23 11 69 41 21 7
299 12.5-18.5 0
0 0
0 0
0 0
0 0
1 0
0 0
9 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 114 149 11 51 82 14 7 [4 18 128 175 42 1561 1101 62 11279 Class B Freg. 0.042 mph I N I NNEI NE IENEI E IESE I SSE S
I SW IWSWI W IWNWS 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 7
12 9
5 4
0 2
0 0
0 0
1
- 3.
6 5
5 59 3.5-7.5 5
5 16 10 18 7
3 5
9 33 21 22 29 9
10 7
209 7.5-12.5 1
10 9
1 0
5 1
0 2
39 8
5 8
10 2
1 102 12.5-18.5 0
0 0
0 0
0 0
- 0.
0 0
0 0
0 0
1 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 ]13 27 34 [ 16 22 [12 ]6 [5]
11 72 29 J28 40 25 [18 ]13 1371 Class C Freg 0.055 mph IN NNE NE ENE E
"ESE SE [SSEI S 1SSWI SW IWSWWI W'IwNWI NW I NNWTOTAL Calm-0.95 0
0 0
0 0
0 0
0 0
0 0
0 0
0
.0 0
0 0.95-3.5 13 20 9
12 10 3
4 2
1 2
2 1
5 5
6 5
100 3.5-7.5 3
20 19 9
14 7
3 5
15 39 22 26 17 16 18 6
239 7.5-12.5 2
11 9
3 2
5 0
2 4
37 11 5
27 10 6
2 136 12.5-18.5 0
0 0
0 0
0 0
0 0
2 0
0 0
1 0
0 3
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 18 51 37 24 126 15 7
9 20 180 35 32 49 132 130 113 1478 Class D Freg: 0.418 mh N NE NE ENE E
ESE SE ISSE [S ISSW ISW WSW[ W 1WNWI NW I NNW I TOTAL Calm-0.95 0
0 1
0 1
0 0
0 2
0 0
0
- 0.
1 0
0 5
0.95-3.5 56 82 73 44 69 34 39 42 41 37 36 40 41
.47 32 44 757 3.5-7.5 32 97 95 59 86
- 59 54 37 100 308 172 198 302 141 91 40 1871 7.5-12.5 8
40 27 15 19 46 5
14 31 273 101 30 167 87 63 25 951 12.5-18.5 6
16 4
4 3
14 1
0 3
4 1
0 5
6 0
0 67 18.5-24 0
0 0
0 0
1 0
0 0
0 0
0 0
0 0
0 1
>24 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
TOTAL 10 2 235 ]
200-122 178 J 154 J 99 j93[
177 622 [310] 268 1515 282 J 186 I109 3652 Page 56
Table A-1 (continued)
Jan-Dec 2007 Class E Fre:
0.239 mp.
N I NNE INE IENEI E EISE I SE I SSE I S I SSW I SW I WSW I W I W NW I NW I NNW I TOTAL Calm-0.95 1"
1 1
0 0
0 0
1 2
0 0
1 2
1 0
1 11 0.95-3.5 29 20 20 34 54 23 49 76 73 51 52 71 81 65 54 25 777 3.5-7.5 15 13 15 6
24 11 13
.25 44 210 190 258 130 56 42 14 1066 7.5-12.5 1
2 5
2 1
0 3
11 6
96 69 14 8
4 3
0 225 12.5-18,5 0
0 0
0 1
1 0
0 2
2 0
0 0
0 0
0 6
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 46 36 41 42 [80 35 165 1113 11271 359 1311 1 344 1221 1 126 199 1 40 1 2085 Class F Freq 0.083 mp NJ NNE NE ENE E
ESE ISE ISSE S
SSWISW JWSW [W 1WNW NW NNW TOTAL Calm-0.95 0
0 0
1 0
0 0
0 1
3 1
1 1
1 0
0 9
0.95-3.5 8
1 1
5 3
0 5
8 37 53 52
- 96.
78 35 6
10 398 3.5-7.5 4
2 0
2 2
0 0
- 1 4
26 156 59 16 4
5 7
288 7.5-12.5 0
0 0
0 0
0 0
o 0
2 23 4
0 0
0 0
29 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 3 IIL 1I0 15 9 42 84 232 160 95 40 11 17 724 Class G Fre:
0.017 Nph1* NNE NE ENE E
ESE SE SSE S SSW SW] WSW IW IWNW 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 5
4 17 24 11 2
1 1
65 3.5-7.5 0
0 0
0 0
0 0
0 0
2 59 6
1 0
0 0
68 7.5-12.5
,0 0
0 0
0 0
0 0
0 0
13 2
0 0
0 0
15 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[ 0 1 0 0 0 5 6 19 132 12 I2 1 1 148 Class All Frec 1.000 mph N
NNE NE ENE E
ESE SE ISSE I S I SSWI SVW IVWSW IV IW NW IINNW IvTOTAL Calm-0.95 1
1 2
1 1
0 0
1 5
3 1
2 3
3 0
1 25 0.95-3.5 139 170
.130 111 154 60 101 128 157 147 162 233 222 170 118 101 2303 3.5-7.5 142 234 233 125 211 98 78 76 187 661 669 600 579 321 232 118 4564 7.5-12.5 17 80 65 22 23 56 9
28 46 531 248 71 279 152 95 35 1757 12.5-18.5 6
16 4
4 4
15 1
0 5
9 1
0 5
16 1
0 87 18.5-24 0
0 0
0 0
1 0
0 0
0 0
0 0
0 0
0 1
>24 0
0 0
0 0
0 00 0
0 00 0
0 0
0 0
TOTAL 1 305 1 501 14341 263 13931 230 1189 1 233 1400 11351 11081 1 906 1088 1 662 1446 1 255 1 8737 Page 57
Table A-2 Joint Frequency Distribution of Wind Directions and Speeds For the 220-ft level of the 220-ft Tower Jan-Mar 2007 Class A Freq 0.141 m2ph INI NNE NE [ENE I E I ESE SE SSE[ S ISSW[ SW W I[
W N
IWvW[ NW NNW VTOTAL 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 5
8 4
6 2
1 0
0 0
0 0
0 2
3 4
2 37 7.5-12.5 10 5
0 1
4 2
0 0
0 0
1 2
8 13 7
5 58 12.5-18.5 5
2 0
0 0
1 1
0 0
8 1
8 24 3
12 4
69 18.5-24 2
1 5
0 0
0 0
0 2
5 1
0 21 15 12 4
68
>24 2
0 0
0 0
0 0
0 0
0 2
0 16 19 25 9
73 TOTAL [24 16] 9 I 7 6
i 1 0
2 13 5
10 171 153 160 124 1305 Class B Freg:
0.039 mph9 N
NNE NE SE SE SNW I 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 10 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0 10 3.5-7.5 1
0 1
2 1
1 0
0 0
0 0
0 0
2 3
0 11 7.5-12.5 0
0 0
0 0
1 2
1 1
1 0
0 2
1 0
0 9
12.5-18.5 0
0 0
0 0
0 0
0 2
7 1
8 10ý 5
2 0
35 18.5-24 0
0 2
0 0
0 0
0 0
2 1
0 3
3 3
0 14
>24 0
0 0
0 0
0 0
0 0
0 0
0 2
-8 3
2 15 TOTAL 1 I0 3
2 1
2 2
1 3 10 2,18 17 [19 11
'2. 84 Class C Freg:
0.055 mp N
NNE NE ENE E
SIS wWIW ININW INNW 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 0
0 2
0 0
0 0
0 0
0 0
0 0
0 0
0 2
3.5-7.5 2
.1 0
0 1
2 0
0 0
0 2
0 1
2 1
2 14 7.5-12.5 0
4
- 0 0
1 0
0 1
4 2
3 2
2 1
2 0
22 12.5-18.5 0
1 0
0 0
1 0
0 3
3 4
5 5
3 4
0 29 18.5-24 0
0 2
0 0
0 0
0 0
2 4
0 8
3 6
4 29
>24 0
0 0
0 0
0 0
0 0
2 0
1 5
8 4
3 23-TOTAL 2
6 [4]
0 2
3 0
i 7 [9 13 8
21 117 171 9 119 Class D Freg: 0.527 mph IN
.NNE INE IENE IE I ESE I SE [ SSE IjS SSW ISW j WSWI WIWNWI 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 1
1 0
2 0
2 0
0 2
1 0
1 0'
0 0
.0 10 3.5-7.5 2
8 9
6 1
4
.2 3
1 1
4 0
3' 5
6 8
63 7.5-12.5 5
5 5
6 1
7 7
11 10 10 11 21 17 16 14 6
152 12.5-18.5 7
12 1
7 12 4
3 7
5 32 52 62 91 51 37 11 394 18.5-24 5
1 1
5 2
2 2
4 4
43 38 13 58 48 31 11 268.
>24 0
5 0
8 9
6 4
0.2 22 6
1 22 66 67 34 252 TOTAL I 20 32 1
34 1 25 1 25 18 [25 24 109 I111 98 1191 J 186 155 70 1139 Page 58
Table A-2 (continued)
Jan-Mar 2007 Class E Frea:
0.194 mph I
N I NNE INE IENEI E I ESE I SE I SSE I S I SSW I SW I WSW I W I WNW I NW I NNW I TOTAL Calm-0.95 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0.95-3.5 1
0 1
0 1
2 0
0 1
1 0
0 0
1 1
1 10 3.5-7.5 0
.0 4
3 4
1 3
- 1.
1 3
3 1
2 5
3 4
38 7.5-12.5 0
1 2
3 0
0 2
5 6
6 19 12 13 10 3
0 82 12.5-18.5 3
0 0
0 0
0 2
8 7
8 23 28 33 24 11 3
150 18.5-24 4
1 0
0 0
- 0.
1 4
3 0
37 6
8 18 11 9
102
>24 1
0 0
0 2
1 2
3 0
7 6
0 1
2 6
5 36 TOTAL 9
2 1 7 I
6 1 7
4 1101 21 1181 25 188 1 47 157 [ 60 135 !
22 1 418 Class IF Fre 0.041 rnph I
N ] NNE INE I ENE I ESE ISE ISse S ISSW ISWI WSW I W I WNW INW I 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 0
0 1
0 0
0 1
0 1
0 0
0 0
0 0
2 5
3.5-7.5 0
0 0
0 1
0 0
0 2
3 1
3 1
3 0
1 15 7.5-12.5 0
0 0
0 0
0 0
2 4
2 2
1 2
8 1
0 22 12.5-18.5 0
0 0
0 0
0 0
1 2
1 3
6 5
3 2
0 23 18.5-24 1
0 0
0 0
0 0
0 0
0 4
4 0
4 2
3 18
>24 0
0 0
0 0
0 0
0 0
0 3
0 0
0 1
1 5
TOTAL I1 I 0 [I 0 1 0 1]11 3 191 6 1131 14 18118 1617 88 Class G Freq 0.003 mph I
N I NNE INE*
ENEI E I ESE I SE SSE I S I SSW I SW I WSW I W I WNW I I 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 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
3.5-7.5 0
0.0 0
0 0
0 0
0 0
1 0
0 0
0 0
1 7.5-12.5 0
0 0
0 0
0 0
0 0
0 1
1 0
0 0
0 2
12.5-18.5 0
0 0
0 0
0 0
0 0
0 1
2 0
0 0
0 3
18.5-24 0
0 0
0 0
0 0
0 0
0 1
0 0
0 0
0 1
'>24 0
0 0
0 0
0 0 0 0
0
'0 0
0 0
0 0
0 TOTAL I o0 0 0 0.0 0 I0 10 L
0 0 41 3 10 0 10 0I 7 Class All Fre q 1.000 rmph I
N NNE IE IE*NE E
ESE I SE -SSE S
SSW ISWV WSW I W I WNW 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 2
1 4
2 1
4 1
0 4
2 0
1 0
1 1
3 27 3.5-7.5 10 17 18 17 10 9
5 4
4 7
11 4
9 20 17 17 179 7.5-12.5 15 15 7
10 6
10 11 20 25 21 37 39 44 49 27 11 347 12.5-18.5 15 15' 1
7 12 6
6 16 19 59 85 119 168 89 68 18 703 18.5-24 12 3
10 5
2 2
3 8
9 52 86 23 98 91 65 31 500
>24 3
5 0
8 11 7
6 3
2 31 17 2
46 103 106 54 404 TOTAL [ 57 56 140 1 49 1421 38 1321' 51 1631 172 12361 188 13651 353 1 2841 134 1 2160 Page 59
Table A-2 (continued)
Apr-Jun 2007 Class A Frea:
0.203
- p.
N NNE NE
( ENE IE I ESESE[SSE I SSW SW,IWSW I
W IsNwlNW I 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 0
1 0
1 0
0 0
0 0
0.0 0
0 0
0 0
2 3.5-7.5 9
14 10 3
7 3
0 0
1 0
0 1
3 2
1 4
58 7.5-12.5 20 16 15 2
7 18 3
1 4
14 16 8
8 7
4 6
149 12.5-18.5 21 12 10 1
2 1
5 0
3 15 16 7
9 29 7
8 146 18.5-24
- 8 9
2 0
0 0
0 0
3 17 3
0 10 17 4
5 78
>24 1
3 0
0 0
0 0
1 0
0 0
0 0
0 1
0 6
TOTAL I59 55 37 [ 7 ]1 1 22 W 8
2 146 135 116 130 155 17 23 439 Class B Freg: 0.054 mp IN NNE NE I ENE I E I ESE I SE SSE S ISSWI SW IVWSWI W IWNWI NW INNW 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 0
0 0
0 0
0 0
0 0
0 0
0 0
0 1
3.5-7.5 4
2 4
3 2
0 2
'0 0
0 0
1 0
0 0
0 18 7.5-12.5 1
3 2
0 1
5 3
2 2
6 1
2 1
0 0
0 29 12.5-18.5 3
3 5
3 0
2 0
0 2
7 2
2 3
2 1
5 40 18.5-24 0
3 1
3 0
5 0
0 0
7 1
0 1
1 2
1 25
>24 0
2 0
0 0
0 0
1 0
0 0
0 0
0 0
0 3
TOTAL 9 [13 112 9
3 12 [ 5 3
4 20 4 15 51 3 3 6 116 Class C Fre 0.063 mph I N NNE NE IEN I E I ESE SE SSE I S ISSWvI SW IVWSWv IWWNWv N
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 0'
1 2
1 0
0 0
0 0
0 0
0 0
0 0
0 4
3.5-7.5 6
5 2
3 4
1 0
1 1
2 1
1 0
0 0
0 27 7.5-12.5 3
2 0
0 1
2 5
2 3
2 3
3 2
1 0
1 30 12.5-18.5 3
8 3
0 1
1 0
0 2
10 2
1 4
2 2
0 39 18.5-24 1
4 0
1 1
4 0
2 0
6 2
1 1
4 1
0 28
>24 0"
6 0
0 0
2 0
0 0
0 0
0
'0 0
0 0
8 TOTAL 13I 26 7 15 7
101 515 1 6 20 8 16 17 17 3
1 1 136 Class D Freg:
0.356 mh IN NNE NE ENE E
[SSVW SW IV WSW] VW IVWNWV IW 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' 5
1 3
2 1
3 3
0 1
1 0
1 1
0 0
1 23 3.5-7.5 6
10 15 4
9 10 5
9 3
5 5
1 2
4 5
9 102 7.5-12.5 19 12 4
6 3
13 10 10 8
14 8
4 7
9 4
7 138 12.5-18.5 21 18 3
2 7
12 17 5
4 40 25 6
32 15 7
11 225 18.5-24 8
11 4
1 3
12 8
2 0
42 38 3
16 22 3
3 176
>24 17 24 1
0 2
25 7
0 0
11 11 0
0 4
3 1
106 TOTAL 76 76 30 15 25 75 50 26 16 [113 87 115 58 54 I22 132 770 Page 60
Table A-2 (continued)
Apr-Jun 2007 f1i 4
mph NJI NNE INELIE[EI EIESE[ISE1I SSE IS]I SSW ISW IWSW IjWI WNW IJNW I 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 2
1 3
2 2
0 0
1 4
0 0
0 0
1 0
2 18 3.5-7.5 4
5 1
1 4
5 6
2 1
4 4
1 4
1 1
7 51 7.5-12.5 6
2 3
1 3
10 9
4 5
7 3
2 4
10 9
5 83 12.5-18.5 5
6 1
0 1
0 2
0 1
15 20 11 24 25 22 9
142 18.5-24 8
4 0
0 2
0 0
0 0
21 60 5
11 23 6
6 146
>24 2
0 0
0 0
1 0
1 0
8 16 0
0 1
3 0
32 TOTAL _
27 1
1 8 4
1 112 8 Ill1 55 1 03]1 19 1 431 61 1411 29 1 472 Class F Fre(
0.087 mjph NI NNE NE ENE E ESE SE SSE S
SSW SW WSW WI 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 0
2 0
3 0
1 1
0 0
0 0
0 1
0 0
0 8
3.5-7.5 1
2 2
0 0
1 4
3 2
1 1
1 0
2 5
2 27 7.5-12.5 4
1 0
0 0
0 2
2 2
2 2
5 8
9 7
9 53 12.5-18.5 4
2 1
0 0
0 0
0 0
1 9
13 15 12 7
3 67 18.5-24 4
0 0
0 0
0 0
0 0
1 13 4
5 1
0 2
30
>24 2
0 0
0 0
0 0
0 0
0 0
1 0
0 0
0 3
TOTAL 1
7 3
3 0
2 7
5 4
5 125 24 29 24 19 116 88 Class G Fre q 0.019 m~phL N]I NNE INEIENEI E IESEISEISSE S ISSW [SWI WSW IW[I WNW INW INNW IITOTAL 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
1 1
0 0
0 0
0 0
0 0
0 1
0 4
3.5-7.5 0
1 0
0 0
0 0
1 1
2 0
0 0
0 0
0 5
7.5-12.5 1
0 0
0 0
0 0
0 2
2 0
0 2
0 1
1 9
12.5-18.5 0
2 0
0 0
0 0
0 0
0 0
8 1
2 0
0 13 18.5-24 0
0 0
0 0
0 0
0 0
0 3
3 3
0 0
0 9
>24 0
0 0
0 0
0 0
0 0
0 2
0 0
0 0
0 2
TOTAL I1 3
1 1
11 0 0[1 131 4 5111 61 2 [211 42 Class All Frei 1.000 Np IN NNE NE ENE E
ESE SE SSE IS SSW [SWI WSW IW WNW NW NNW JTOTAL 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 9
10 4
4 4
1 5
1 0
1 2
1 1
3 60 3.5-7.5 30 39 34 14 26 20 17 16 9
14 11 6
9 9
12 22 288 7.5-12.5 54 36 24 9
15 48 32 21 26 47 33 24 32 36
'25 29 491 12.5-18.5 57 51 23 6
11 16 24 5
12 88 74 48 88 87 46 36 672 18.5-24 29 31 7
5 6
21 8
4 3
94 120 16 47 68 16 17 492
>24 22 35 1
0 2
28 7
3 0
19 29 1
0 5
7 1
160 TOTAL 1 200 198 198 1 44 1641 137 192 [ 50 1551 263 1267 1 96 1178 1 206 1107] 108 1 2163 Page 61,
Table A-2 (continued)
Jul-Sep 2007 Class A Fre(
0.154 mph I N INNEI NE IENE E [ESE] SE SSE.
S ISSwl SW IWS W W IWN NW INN 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
1 0
0 0
0 0
0 0
0 0
0 0
0 2
3.5-7.5 9
11 18 5
3 0
0
.0 1
0 3
3 4
4 2
4 67 7.5-12.5 25 13 4
13 14 9
3 1
9 10 11 3
3 1
2 6
127 12.5-18.5 24 5
0 8
2 1
0 2
12 25 15 0
0 1
1 11 107 18.5-24 5
0 0
0 0
0 0
0 3
11 5
0 4
1 0
3 32
>24 0
0 0
0 0
0 0
0 0
0 0
0 0
2 2
1' 5
TOTAL 163 130 2
27 19 10 3
3 25 146134 6 II 9
7 125 134 Class B Freg: 0.045 mph N
NNE NE I ENE I E ESE I SE I SSE S
SSW S[ Wsv 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 3
0 0
0 0
0 0
0 0
0 0
0 0
0 3
3.5-7.5 2
3 3
0 2
2 0
0 0
0 1
1 1
1 3
0 19 7.5-12.5 1
3 1
1 0
1 1
0 5
2 2
3 2
1
'0 1
24 12.5-18.5 1
0 0
0 0
0 0
1 10 17 9
4 1
1 0
0 44 18.5-24 0
0 0
0 0
0 1
0 0
7 1
0 0
0 0
0 9
>24 0
0 0
0 0
0 0
0 0
0 0
0 0
1 0
0 1
TOTAL 4
6 7
1 2
3 2
1 15 26 13 8
4 4
3 1 1100 Class C Free: 0.054 mph IN NNE NE I ENE I E ESE I SE SSE I S ISSW[ SWSWWI W IwWNWI NW INNWI 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 1
0 0
0 0
0 0
0 0
0 0
0 0
0 3
3.5-7.5 2
3 1
3 3
1 0
1 1
1 0
1 2
0 1
0 20 7.5-12.5 7
0 3
0 5
6 3
1 4
2 3
0 2
.2 1
2 41 12.5-18.5 4
0 0
1 0
0 0
1 7
15 9
1 0
1 0
1 40 18.5-24 0
0 0
0 0
0 0
0 0
8 3
0 1
0 0
0 12
>24 0
0 0
0 0
0 0
0 0
1 0
0 0
0 2
0 3
TOTAL 14 4
5 4
8 7
3 3
12 27 15 2 I 5 3 1 4 3 [119 Class D.
Freg:
0.317 mph__
N' NNE NE ENE I E
ISSWI SW IWSWV W IWNWI NW NNWIToTAL 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
7 3
3 3
1 0
0 0
0 1
0 0
0 2
1 23 3.5-7.5 13 10 23 18 7
14 5
3 8
9 3
2 3
4 5
4 131 7.5-12.5 12 13 9
12 17 14 15 10 27 25 17 13 7
2 1
8 202*
12.5-18.5 5
0 3
6 2
3 8
.7 20 85 40 10 6
8 2
5 210 18.5-24 1
0 0
0 0
0 0
0 3
67 34 0
0 1
5 8
119
>24 0
0 0
0 0
0 0
0 1
9 2
0 0
1 1
0 14 TOTAL 33 130 138 139 [29 132 [28 202i 59 1195 197 125 16 [16 16 26 699 Page 62
Table A-2 (continued)
Jul-Sep 2007 Class E re:
0.275 NI I NNE INE IENEI E I ESE ISE I SSE I S I SSW I SWvI WSW I W I WNW INW I NNNW 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
4 1
2 2
0 0
2 1
0 0
0 0
0 3
2 18 3.5-7.5 4
7 12 6
6 8
9 2
7 8
7 3
5 7
4 3
98 7.5-12.5 4
5 9
8 7
3 12 9
13 14 8
5 4
6 7
13 127 12.5-18.5 12 2
0 11 7
2 4
7 16 37 30 15 32 24 13 17 229 18.5-24
.2 0
0 0
0 0
0 3
9 41 40 6
5 1
6 7
120
>24 0
0 0
0 0
0 0
0 0
9 6
0 0
0 0
0 15 TOTAL 23 1 18 122 1 27 1221 13 1251 23 146 1109 1 91 29 1461 38 133 1 42 607 Class F Fre:
0.130 mph I
N I NNE INE ENE El ESE I SEISSE S I SSW I SW I WSW I W I WNW INW I 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 0
2 1
0 1
2 1
1 2
0 0
0 0
2 13 3.5-7.5 4
0 0
0 2
3 2
2 2
1 1
2 2
5 6
6 38 7.5-12.5 4
0 0
0 0
2 18 7
0 3
8 3
11 6
16 19 97 12.5-18.5 3
0 0
0 0
0 6
17 3
5 8
10 11 18 12 5
98 18.5-24 3
0 0
0 01 0
0 0
0 6
12 9
0 2
1 2
35
>24 0
0 0
0 0
0 0
0 0
0 0
0 0
0 1
6 7
TOTAL I15 0
0 2 3 5
27 28 [
16 31 24 24I 31 36 40 288 Class G Fre(:
0.025 ph I
N I NNE INEE I E IESEI SEI SSEI S i SSW I SW I WSW I W I W NW I NW I
.M 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 2
0 1
0 0
0 0
0 1
0 0
0 0
0 5
3.5-7.5 5
1 0
0 0
1 1
2 0
2 0
1 1
0 0
2 16 7.5-12.5 0
0 0
0 0
0 0
1 0
2 0
3 4
4 0
0 14 12.5-18.5 0
0 0
0 0
0 0
0 1
0 2
4 8
1 0
0 16 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
ý0 0
0 0
0
- 0.
0 0
0 0
TOTAL 16 1 2 0 11 1 Il 311 14 7I 8I1 5 101 2 55 Class All Frec 1.000 mph IN NNE I NE I E I E I ESE I SE I SSE ISI SSW vSWI WSW I W I WN W I*N*
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 6
13 10 8
7 1
1 4
2 1
4 0
0 0
5 5
67 3.5-7.5 39 35 57 32 23 29 17 10 19 21 15 13 18 21 21 19 389 7.5-12.5 53 34 26 34 43 35 52 29 58 58 49 30 33 22 27 49 632 12.5-18.5 49 7
3 26 11 6
18
.35 69 184
- 113, 44 58 54 28 39 744 18.5-24 11 0
0 0
0 0
1 3
15 140
",99 15 10 5
12 20 331
>24 0
0 0
0 0
0 0
0 1
19 8
0 0
4 6
7 45 TOTAL 1158 ]
89 1961 100 1841 71 1891 [81 11641 423 12881 102"-1 1191 106 199 1 139 1 2208 Page 63
Table A-2 (continued)
Oct-Dec 2007 Class A Fre: 0.088 mph I
IANNEI NE ENE E
ESE SE ISSEI s Issw swI wsw Iw I 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 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
3.5-7.5 6
2 4
0 1
0 0
'0 0
0 0
0 1
4 7
1 26 7.5-12.5 4
2 5
0 7
2 0
0 0
0 1
4 22 11 5
1 64 12.5-18.5 5
7 2
0 3
0 0
0 0
0 0
3 10 15 8
7 60 18.5-24 0
3 0
1 2
0 0
0 0
0 0
0 1
7 2
8 24
>24
-2 0
0 0
0 0
0 0
0 0
0 0
7 7
4 1
21 TOTAL 117 14 I 1 13 12 0 10 0
0 117 41 44 126 18 1195 Class B Freg: 0.032 mph N
NNE NE ENE E
ESE SE ISSE S
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
1 0
0 0
0 0
0 0
0 0
0 0
0 0
,0 1
3.5-7.5 2
0 0
1 0
0 0
0 0
0 0
0 1
5 2
1 12 7.5-12.5 0
1 4
0 3
2 0
0 0
1 6
7 0
1 0
- 0.
25 12.5-18.5 1
2 2
0 1
0 0
0 0
2 4
1 5
1 0
0 19 18.5-24 0
3 0
0 1
0 0
0 0
2 0
1 0
0 1
1 9
>24 4
1 0
0 0
0 0
0 0
0 0
0 0
0 0
0 5
TOTAL 7 8 6 I1 15 2 0 0 I0 5
10 9 16
[
7 3 2 71 Class C Freg:
0.047 Cmph N
NNE NE ENE E
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 1
1 0
0 0
0 0
0 0
0 0
0 0
0 1
0 3
3.5-7.5 0
0 1
2 0
0 1
0 0
0 1
2 2
3 3
0 15 7.5-12.5 0
3 4
0 0
1 1
0 0
2 0
3 3
1 0
0 18 12.5-18.5 2
5 8
6 0
0 0
0 1
5 4
3 3
2 2
0 41 18.5-24 0
1 1
0 0
0 0
0 1
3 1
1 1
3 2
0 14
>24 1
0 0
0 0
0 0
0 0
1 0
0 2
6 2
1 13 TOTAL 14 110 114 Y8I0 V 2I0IT Il I 2 1 6
9 11I 15 10 J 1 1104 Class D Freg.
0.473 mph N I NNEI NE I E NEI E I SE E
SSE I S ISSWI SW IwswN W INw r
WW I NWlTOTAL 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 4
3 2
2 0
1 1
2 1
0 0
0 1
1 20 3.5-7.5 4
8 16 1
5 11 5
4 4
10 12 10 6
3 3
2 104 7.5-12.5 10 21 20 14 11 8
10 8
15 16 18 15 15 13 8
6 208 12.5-18.5 9
13 18 18 11 6
8 9
25 53 35 37 41 31 9
10 333 18.5-24 4
5 3
25 14 4
1 11 19 37 13 9
23 34 35 3
240
>24 10 5
0 6
9 3
0 5
2 12 4
0 22 38 11 12 139 TOTAL 37 I 54 [ 61 67 [ 52 1 34 1 24 38 1 66 1130 8
83 J 71 ] 107 1119 1 67 [ 34 [ 10, Page 64
Table A-2 (continued)
.Oct-Dec 2007 Class E Freg: 0.267 mpI N NNE NE ENE I E I ESE SE ISSE I S IsSW[
WSIWsv Vw IV NNW IvTOTAL 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
2 2
2 1
1 1
0 0
0 0
0 9
3.5-7.5 2
3 4
0 3
1 9
4 2
3 3
2 2
3 1.
1 43 7.5-12.5 1
3 1
1 4
7 24 14 15 10 10 8
6 20 8
4 136 12.5-18.5 1
1 4
0
,1, 4
19 20 2
23 44 43 48 31 20' 9
270 18.5-24 0
0 2
5 3
0 2
6 2
9 29 19 23 7
4 0
111
>24 1
1 0
2 1
0 0
3 1
3 3
1 1
2 0
0 19 TOTAL 51 8
11 8
12 14 1 56 I49 23 49 190 173 80 163 33 14 588 Class F Freg:
0.073 m* h N
INNE NE] ENE E IESEI SE ISSE S
ISSW I SW IWSwl W IWNWIW INNW 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 0
1 0
0 0
0 1
0 1
0 1
0 1
0 0
0 5
3.5-7.5 4
0 0
1 1
1 -
3 3
2 2
0 1
2 5
6 4
35' 7.5-12.5 0
0 0
0 0
0 3
9 8
2 5
6 3
8 4
7 55 12.5-18.5 0
0 0
0 0
0 1
5 3
4 13 13 16 2
1 1
59 18.5-24 0
0 0
0 0
0 0
0 0
0 3
2 0
0 0
0 5
>24 1
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 1
TOTAL 5
1 0
1 i1 I 1
8 17 14 8
22 I22 122 15 5 11 12 160 Class G Freg: 0.020 mphmph N NNE NE IENE E
ESE SE 1SSEI S
I SSW SW IWsW l W IWNWl NW INNW TOTAL Calm-0.951 0
0 0
0
.0 0
0 0
0 0
0 0
0 0
0 0
0 0.95-3.5 1
1 1
0 0
0 0
0 0
1 0
0 0
1 1
0 6
3.5-7.5 0
1 0
0 3
0 0
0 0
1 1
1 2
0 0
0 9
7.5-12.5 0
0 0
0 0
0 0
0 3
0 2
6 2-1 2
0 16 12.5-18.5 0
0 0
0 0
0 0
0 1
0 1
4 5
0 0
0 11 18.5-24 "0
0 0
0
- 0.
0 0
0 0
0 2
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 I 1JI 2 I I 0 3
0o 0
0 4 1 2 6
1 1 9 2
3 0
44 Class All Freg:
1.000 mph I N I NNE I NE I ENE I E I ESE I SE ISSE IS ISSWl SW IwsWl W IWNW 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 2
6 5
3 2
4 3
3 3
4 3
0 1
1 3
1 44 3.5-7.5 18 14 25 5
13 13 18 11 8
16 17 16 16 23 22 9
244 7.5-12.5 15 30 34 15 25 20 38 31 41 31 42 49 51 55 27 18 522 12.5-18.5 18 28 34 24 16 10 28 34 32 87 101 104 128 82 40 27 793 18.5-24 4
12 6
31 20 4
3 17 22 51 48 32 48 51 44 12 405
>24 19 7
0 8
10 3
0 8
3 16 7
1 32 53 17 14 198 TOTAL 876 97 104 86 86 [54 1 90 [104 1109 12051218 1202 1276 1[265 153 1 81 12206 Page 65
Table A-2 (continued)
Jan-Dec 2007 Class A Freq 0.146 mph N
NNE NE ENE E
ISSWI SW IWSWl W
IWNWI NW INNWlTOTA' 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
2 0
0 0
0 0
0 0
0 0
0 0
0 4
3.5-7.5 29 35 36 14 13 4
0 0
2 0
3 4
10 13 14 11 188 7.5-12.5 59 36 24 16 32 31 6
2 13 24 29
- 17.
41 32 18 18 398 12.5-18.5 55 26 12 9
7 3
6 2
15 48 32 18 43 48 28 30 382 18.5-24 15 13 7
1 2
0 0
0 8
33 9
0 36 40 18 20 202
>24 5
3 0
0 0
0 0
1 0
0 2
0 23 28 32 11 105 TOTAL 1163 115 79 I 42 54 [38 ] 12 5I 38 I105 I 75 39 153 1161 [110 ] 90 11279 Class B Fre: 0.042 mfph I N NN NE ENE EI ESE I
SSSE S 'ISSW SW IWSWI W IJNw[ NW INNWITOTAL Calm-0.95 0
0 0
0 0
0 0
- 0.
0 0
0 0 '1 0
0 0
0 0
0.95-3.5 1
1 3
0 0
0 0
0
- 0.
0 0
0 0
0 0
0 5
3.5-7.5 9
5 8
6 5
3 2
0 0
0 1
2 2
8 8
1 60 7.5-12.5 2
7 7
1 4
9 6
3 8
10 9
12 5
3 0
1 87 12.5-18.5 5
5 7
3 1
2 0
1 14 33 16 15 19 9
3 5
138 18.5-24 0
6 3
3 1
5 1
0 0
18 3
1 4
4 6
2 57
>24 4
3 0
0 0
0 0
1 0
0 0
0 2
9 3
2 24 TOTAL 121 127 28 1311 19 9 15 22 161 129 130 [32 133 12 I20 I
37d Class C Freg: 0.055
.mph I
ISSW SW I WSW W. IWNWI NW INNW 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 2
3 5
1 0
0 0
0 0
0 0
0 0
0 1
0 12 3.5-7.5 10 9
4 8
8 4
1 2
2 3
4 4
5 5
5 2
76 7.5-12.5 10 9
7 0
7 9
9 4
11 8
9 8
9 5
3 3
111 12.5-18.5 9
14 11 7
1 2
0 1
13 33 19 10 12 8
8 1
149 18.5-24 1
5 3
1 1
4 0
2 1
19 10 2
11 10 9
4 83
>24 1
6 0
0 0
2 0
0 0
4 0
1 7
14 8
4 47 TOTAL [33 46 130 [17 17 21 10 ]9 127 67 142 25 44 142 134 [14[478 Class D Freg: 0.418 mph N [NNEI NE IENEI EI ESE SE SS S Is Iw SW IWSW IWWNW 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 8
11 10 10 6
8 3
1 4
4 2
2 1
0 3
3 76 3.5-7.5 25 36 63 29 22 39 17 19 16 25 24 13 14 16 19 23 400 7.5-12.5 46 51 38 38 32 42 42 39 60 65 54 53 46 40 27 27 700 12.5-18.5 42 43 25 33 32 25 36 28 54 210 152 115 170 105 55 37 1162 18.5-24 18 17 8
31 19 18 11 17 26 189 123 25
- 97 105 74 25 803
>24 27 34 1
14 20 34 11 5
5 54 23 1
44 109 82 47 511 TOTAL 1166 192 1145 155 1131 116 1120 109 165 1547 1378 1209 1372 [375 260 1162 13652 Page 66
Table A-2 (continued)
Jan-Dec 2007 Class E Freq:
0.239 mph N
I NNE INE IENEI E I ESE I SE I SSE I S I SSW I SW I WSW I W I W NW INW I NNW TOTA 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
5 5
4 5
4 2
5 7
2 1
0 0
2 4
5 55 3.5-7.5 10 15 21 10 17
.15 27 9
11 18 17 7
13 16 9
15 230 7.5-12.5 11 11 15 13 14 20 47
'32 39 37 40 27 27 46 27 22 428 12.5-18.5 21 9
5 11 9
6 27 35 26 83 117 97 137 104 66 38 791 18.5-24 14 5
2 5
5 0
3 13 14 71 166 36 47 49 27 22 479
>24 4
1 0
2 3
2 2
7 1
27 31 1
2 5
9 5
102 TOTAL 64 46 148 45 1 53 [ 47 11081101 [ 98 1238 1372 1 168 12261 222 11421 107 1 2085 Class F Freq 0.083 mph N
NNE NE ENE E
I ISE SE SSE ISI SSW I SW I WSW I W 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
3 1
5 1
1 4
2 3
1 3
0 2
0 0
4 31 3.5-7.5 9
2 2
1 4
5 9
8 8
7 3
7 5
15 17 13 115 7.5-12.5 8
1 0
0 0
2 23 20 14 9
17 15 24 31 28 35 227 12.5-18.5 7
2 1
0 0
0 7
23 8
11 33 42 47 35 22 9
247 18.5-24 8
0 0
0 0
0 0
0 0
7 32 19 5
7 3
7 88
>24 3
0 0
0 0
0 0
0 0
0 3
1 0
0 2
7 16 TOTAL 136 8
4 16 5 8 43 53 33 35 1 [84 183 88 72 75 1 724 Class G Fre.:
0.017
.mph N
NNE N
E E
IE SE SE ISSEI S LSSW ISW WSWI W IWNW 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 2
1 4
1 2
0 0
0 0
1 1
0 0
1 2
0 15 3.5-7.5 5
3 0
0 3
1 1
3 1
5 2
2 3
0 0
2 31 7.5-12.5 1
0 0
0 0
0 0
1 5
4 3
10 8
5 3
1 41 12.5-18.5 0
2 0
0 0
0 0
0 2
0 4
18 14 3
0 0
43
.18.5-24 0
0 0
0 0
0 0
0 0
0 10 3
3 0
0 0
16
>24 0
0 0
0 0
0 0
0 0
- 0.
2 0
0 0
0 0
2 TOTAL 6
114 1
5 1
1 4
8 I10 22 33 [28 9
5 I3 148 Class All Fre:
1.000 mph I N NNE NE ENE E
ESE SE SSE S SSW SW WSW WI 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 18 26 28 23 14 13 9
8 14 8
7 2
3 3
10 12 198 3.5-7.5 97 105 134 68 72 71 57 41 40 58 54 39 52 73 72 67 1100 7.5-12.5 137 115 91 68 89 113 133 101 150 157 161 142 160 162 106 107 1992 12.5-18.5 139 101 61 63 50 38 76 90 132 418 373 315 442 312 182 120 2912 18.5-24 56 46 23 41 28 27 15 32 49 337 353 86 203 215 137 80 1728
>24 44 47 1
1623 38 13 14 6
85 61 4
78 165136 76 807 TOTAL I491I44O[ 138[I279 1276I 30 1303[2861391 110631 1009 588 19381 930 1643] 462 1 8737 Page 67
APPENDIX B PILGRIM NUCLEAR POWER STATION.
OFFSITE DOSE CALCULATION MANUAL No revisions were made to the PNPS Offsite Dose Calculation Manual (ODCM) during calendar year 2007.
Page 68
APPENDIX C Results of Onsite Groundwater Monitoring Program In response to the Nuclear Energy Institute (NEI) Groundwater Protection Initiative, Pilgrim Station instituted a groundwater monitoring program during 2007. Four monitoring wells were installed during the fourth quarter of 2007, and the first samples were collected in late November 2007. All four wells were installed onsite, within the protected area fence. Since these are onsite wells, they are not considered part of the Radiological Environmental Monitoring Program (REMP), and data from these wells are being reported in the annual Radiological Effluent Release Report.
All samples collected were analyzed for tritium, a radioactive isotope of hydrogen, and well as for gamma emitting radionuclides and hard-to-detect beta emitting nuclides.
In accordance with industry practice established under the NEI initiative, lower limits of detection (LLDs) used for analysis of REMP samples were used when assessing these samples for the presence of radioactivity.
Low levels of tritium, a radioactive isotope of hydrogen, were detected in these onsite wells.
Although gamma spectroscopy analyses indicated the presence of naturally-occurring radioactivity, such as potassium-40 and radon daughters form the uranium/thorium decay chains, there was no indication of any plant-related radioactivity in the samples, other than tritium.
Concentrations of tritium ranged from non-detectable at less than 450 pCi/L, up to a maximum concentration of 3300 pCi/L, well below the EPA Drinking Water Standard of 20,000 pCi/L.
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-201 (3300 pCi/L) was consumed as drinking water, the maximum dose consequence would be less than 0.2 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.
Results of the November 2007 samples are presented in the following tables. These wells are scheduled to be sampled on a quarterly basis, and samples collected in January 2008 indicated similar levels of tritium in these wells. The next samples are scheduled for collection during the third week of April 2008. In these tables, a value of "NDA < xx" in the right-most column 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 MW-201 was analyzed by gamma spectroscopy for manganese-54 (Mn-54), and a minimum detectable concentration of 6.9 pCi/L was achieved on that sample. The achieved sensitivity of 6.9 pCi/L is well below the required REMP LLD of 15 pCi/L, and no Mn-54 activity was detected even when counted to this more sensitive level of detection.
As discussed earlier, naturally-occurring activity was detected in the samples. Such levels of natural radioactivity are expected as these radionuclides are dissolved into the groundwater from the rocks and soil.
The fact that these low levels of naturally-occurring radioactivity can be detected demonstrated the ability of the gamma spectroscopy analyses to detect radioactivity in groundwater.
If any plant-related gamma activity was contained in the groundwater, the analytical techniques used would be able to detect them.
Page 69
Monitoring Well MW-201 Results - 2007, Radionuclide Concentration in Water,- pCi/L LLD Monitoring Well-201 Nuclide pCi/L Qtr-1 Qtr-2 Qtr-3 Qtr-4 H-3 3000 3300 +/- 164 K-40 Natural 208 +/- 35 Mn-54 15 NDA < 6.9 Fe-59 30 NDA < 20.2 Co-58 15 NDA < 6.7 Co-60 15 NDA < 7.7 Zn-,65 30 NDA < 10.0 Zr-95 30 NDA < 11.5 Nb-95 15 NDA < 6.0 1-131 15 NDA < 7.7 Cs-134 15 NDA < 7.9 Cs-137 18 NDA < 7.7 Ba/La-140 15 NDA*< 10.9 Fe-55 N/A NDA < 17 Ni-63 N/A NDA < 21 Sr-89 N/A NDA < 8.3 Sr-90 N/A NDA < 3.0 Gross alpha N/A NDA < 3.8 Monitoring Well MW-202 Results - 2007 Radionuclide Concentration in Water - pCi/L Required LLD Monitoring Well-202 Nuclide pCi/L Qtr-1 Qtr-2 Qtr-3 Qtr-4 H-3 3000 733+/- 142 K-40 Natural 147 +/- 36 Mn-54 15 NDA < 8.9 Fe-59 30
. NDA < 19.1 Co-58 15 NDA < 9.7 Co-60 15 NDA < 8.5 Zn-65 30 NDA < 12.2 Zr-95 30 NDA < 14.3 Nb-95 15 NDA < 6.7 1-131 15 NDA < 9.2 Cs-134 15 NDA < 6.9 Cs-137 18 NDA < 5.4 Ba/La-140 15 NDA < 9.3 Fe-55 N/A NDA < 14 Ni-63 N/A NDA < 22 Sr-89 N/A NDA < 8.4 Sr-90 N/A NDA < 3.1 Gross alpha N/A NDA < 20 Page 70
Monitoring Well MW-203 Results.- 2007 Radionuclide Concentration in Water - pCi/L LLD Monitorinc Well-203 Nuclide pCi/L Qtr-1 Qtr-2 Qtr-3 Qtr-4 H-3 3000 NDA < 447 K-40 Natural 282 +/- 37 Mn-54 15 NDA < 6.5 Fe-59 30 NDA < 14.9 Co-58 15 NDA < 5.5 Co-60 15 NDA < 7.9 Zn-65 30 NDA < 10.1 Zr-95 30 NDA < 10.7 Nb-95 15 NDA < 5.1 1-131 15 NDA < 6.0 Cs-134 15 NDA < 6.6 Cs-137 18 NDA < 6.3 Ba/La-140 15 NDA<8.4 Fe-55 N/A NDA < 14 Ni-63 N/A NDA < 22 Sr-89 N/A NDA < 8.6 Sr-90 N/A NDA < 3.2 Gross alpha N/A NDA < 2.4 Monitoring Well MW-204 Results - 2007 Radionuclide Concentration in Water - pCi/L Required LLD Monitoring Well-204 Nuclide pCi/L Qtr-1 Qtr-2 Qtr-3 Qtr-4 H-3 3000 1586 +/- 150 K-40 Natural 113 +/- 32 Mn-54 15 NDA < 7.9 Fe-59 30 NDA < 15.7 Co-58 15 NDA < 8.5 Co-60 15 NDA < 8.1 Zn-65 30 NDA < 11.9 Zr-95 30 NDA < 12.5 Nb-95 15 NDA < 7.2 1-131 15 NDA < 8.5 Cs-134 15 NDA < 7.1 Cs-137 18 NDA < 8.6 Ba/La-140 15 NDA < 6.8 Fe-55 N/A NDA < 14 Ni-63 N/A NDA < 22 Sr-89 N/A NDA < 8.2 Sr-90 N/A NDA < 3.0 Gross alpha N/A NDA < 7.5 Page 71
APPENDIX D, Assessment of Reactor Building Vent Sample Probe Issue On 15-Jun-2006 while collecting supporting information for an NRC effluent inspection, Pilgrim Station personnel identified that the isokinetic sample flow rate at the reactor building vent (RBV) was incorrectly based on an erroneous value for the sample probe diameter. The isokinetic ratio currently in use was based on an assumed probe diameter of 0.2 inches for each of the four probes in the sampling array. Based on measurements taken during the 2007 refueling outage, the actual probe diameter is 0.135 inches.
This assumption of incorrect probe size has been in use since-at least 1982. This sampling anomaly would result in an non-conservative under-representation of large particles, and has been documented in CR-PNP-2006-2282. As part of the corrective action to this discovered anomaly, the' NRC has requested that Pilgrim Station evaluate and document in the effluent report the impact of sampling at the incorrect flow rate.
Derivation of an applicable correction factor for past particulate effluent releases would require an assessment of particle size distribution for each release period. No records of a particle size 'study at Pilgrim Station could be located. Thus, such a particle size distribution would have to be based on a review of particulate size distributions in published literature and at other nuclear power plants.
According to a statement in the American Society of Heating, Refrigerating and Air-Conditioning Engineers (ASHRAE) handbook, 99.9% of ambient particles in ventilation air streams are less than 1 micrometer in size.
Mass filter loading studies at the Columbia Generating Station found negligible mass gains on particulate filters collected over a several week period, implying very little particulate material in typical process flow streams.
A study performed at the Hanford DOE Site (M. Carter and R. Blanchard. 1993. "NESHAP Compliance Evaluation or The Hanford Site") found that the majority of particles in their sampled air streams are less than 3.5 um in size. Furthermore, Carter and Blanchard emphasized that 3.5 microns represents an upper range for respirable particle size, and that such smaller particles contribute the significant portion of the annual effective dose equivalent to the maximum exposed individual.
It would also be anticipated that any particles greater than >10 umr in size, if present in the effluent stream, would exhibit relatively high settling/deposition rates, and would likely fall out of the plume prior to leaving the site. All of these facts provide compelling arguments for assuming that most particles in gaseous waste streams at a nuclear power plant are less that 3 um in diameter.
Isokinetic sampling corrections were calculated for various sized particles according to equations provided in Chapter 10 of the reference text "Aerosol Technology: Properties, Behavior, and Measurement of Airborne Particles" (W.C. Hinds, 1982). A review of actual process flow velocities in the RBV indicated that the flows range from 500 ft/min to 1800 ft/min, with an average flow velocity of 1500 ft/min. According to Equation 10.7 from the referenced text, the following correction factors were derived for various sized particles:
Particle Diameter C/Co at C/C0 at C/Co at um 500 ft/min 1500 ft/min 1800 ft/min 0.01 1.00 1.00 1.00 0.1 1.00 1.00 1.00 1
1.01 1.02 1.03 31
.08~
1.t22*>-
1.26 10 1.41 1.73 1.78 30 1.94 2.10 2.11 100 2.17 2.19 2.19 Page 72
As described by Equation 10.6 of the reference text, the maximum conservative correction applicable to the largest particles would be equivalent to the ratio of actual/assumed sample flow rate to ideal flow rate. The exact value of 2.195 was derived as the square of the assumed probe diameter to the ideal probe diameter. As can be seen in the above table, the calculated correction factors for large particles are in the vicinity of 2.19. In actuality, for particles of -3.5 um as outlined in previous discussion, the estimated correction factor would be 1.25.
In other words, past particulate release rates for the RBV would need to be increased only by 25% to correct for the anisokinetic sampling conditions. This more realistic correction factor is significantly less than the maximum/conservative correction that would be applied to particles larger than 30 microns. As a point of reference, the 1-sigma pooled uncertainty value for particulate releases that has historically been listed in the Annual Regulatory Guide 1.21 Effluent Release Report is +/-21%. This pooled value incorporates all of the various uncertainties or "errors" associated with sample flow measurements, process flow measurements, sample volumes, calibrations, counting statistics, etc.
The projected correction factor for anisokinetic sampling of 3 um particles (+25%) is approximately equivalent to this reported uncertainty value.
In order to bound the potential impact of anisokinetic sampling on calculated doses, effluent release data from two years (1992, 2005) were compiled. While 2005 represents a "typical" release year, 1992 was characterized by higher-than-typical releases of particulates and iodines following a fuel defect. Dose calculations were first performed based on the data initially reported in the annual effluent release reports. Particulate releases from the RBV, including any radioiodines detected on particulate filters, were then multiplied by the worst-case correction factor of 2.19 times, and the doses were then recalculated.
Doses were calculated both for the hypothetical "fencepost" individual at the maximum site boundary location, as well as the maximum dose to more realistic individuals at the location of the nearest resident, garden, milk animal, etc. The following results were obtained:
1992 Effluent Data:
Site Boundary-mrem /period Maximum Individual - mrem/period Original Corrected Original Corrected Particulate Particulate Particulate Particulate Period Activity Activity Increase Activity Activity Increase Qtr1-1992 2.78E+0 3.06E+0 9.95%
2.39E-1 2.55E-1 6.91%
Qtr2-1992 6.02E-1 6.61E-1 9.78%
1.24E-1 1.28E-1 3.13%.
Qtr3-1992 9.67E-1 1.06E+0 9.61%
1.34E-1 1.40E-1 4.62%
Qtr4-1992 6.01E-1 6.72E-1 11.85%
9.51 E-2 9.88E-2 3.92%
Annual-1992 4.95E+0 5.45E+0 10.09%
5.92E-1 6.22E-1 5.12%
2005 Effluent Data:
Site Boundary-mrem/period Maximum Individual - mrem/period Original Corrected Original Corrected Particulate Particulate Particulate Particulate Period Activity Activity Increase Activity Activity Increase Qtr1-2005 7.59E-1 7.67E-1 1.14%
4.07E-2 4.1OE-2 0.79%
Qtr2-2005 3.34E-1 3.53E-1 5.83%
1.70E-2 1.73E-2 1.67%
Qtr3-2005 2.93E-1 2.97E-1 1.17%
1.50E-2 1.51 E-2 0.57%
Qtr4-2005 1.77E+0 1.78E+0 0.41%
9.74E-2 9.76E-2 0.18%
Annual-2005 3.16E+0 3.20E+0 1.23%
1.70E-1 1.71E-1 0.51%
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Considering that RBV particulate activity values were increased by a worst-case factor of 2.2-times, the maximum increase in offsite dose impact for a real individual offsite was only 5.1% for the annual maximum organ dose. In actuality, if the majority of particles are assumed to be in the 3 micron range, the effluent releases would only be corrected by a factor 25%, instead of the 2.2-times factor used. This would imply that the increase in dose due to isokinetic corrections would actually be much less than 5.1%. Such a change is well within the +/-21% effluent uncertainties reported in the annual release reports.
In addition, propagated uncertainties for effluent dose models would be much greater than those for releases, and would be expected to vary by one to two orders of magnitude. Various values used in dose equations such as X/Q and D/Q dispersion and deposition factors, biological uptake factors, buildup and retention factors, food consumption rates, etc. are all accurate only within an order of magnitude, and the pooled uncertainty on projected dose is likely accurate only within a factor of about 20 to 500 times. An increase in dose of only 5.1% due to isokinetic corrections would be completely overshadowed by the propagated uncertainty in dose models.
Another factor that must be considered is the fraction of total dose resulting from particulate radioactivity. In accordance with PNPS ODCM Effluent Control 3/4.3.3, dose must be assessed for particulates -with half-life of greater than eight days, iodine-131, iodine-133, and tritium.
If the annual doses presented in the earlier tables are broken down according to nuclide type, it is clear that the anisokinetic sampling at the RBV has minimal impact on doses. Although doses from particulate nuclides may exhibit increases of over one hundred percent, particulate activity contributes such a small fraction of the total dose that worst-case correction from isokinetic sampling result in less than a 10% increase in total dose.
1992 Annual Effluent Dose by Radionuclide Type:
Site Boundary mrem/yr Maximum Individual - mrem/yr Original Corrected Original
.Corrected Particulate Particulate Particulate Particulate Period Activity Activity Increase Activity Activity Increase Tritium 1.26E-1 1.26E-1 0%
8.04E-4 8.04E-4 0%
lodines 4.81E+0 5.29E+0 10.0%
5.91E-1 6.21E-1 5.1%
Particulates 1.57E-2 3.45E-2 120%
1.25E-5 2.65E-5 112%
Total 4.95E+0 5.45E+0 10.1%
5.92E-1 6.22E-1
.5.12%
2005 Annual Effluent Dose by Radionuclide Type Site Boundary-mrem/yr Maximum Individual - mrem/yr Original Corrected Original Corrected Particulate Particulate Particulate Particulate Period Activity Activity Increase Activity Activity Increase Tritium 2.85E+0 2.85E+0 0%
1.60E-1 1.60E-1 0%
lodines 2.89E-1 3.09E-1 6.9%
9.72E-3 1.03E-2 6.0%
Particulates 1.57E-2 3.46E-2 120%
2.32E-4 5.08E-4 119%
Total 3.16E+0 3.20E+0 1.23%
1.70E-1
.1.71 E-1 0.51%
In conclusion, isokinetic corrections to past release reports would be unwarranted when the impact on offsite dose is considered. Although RBV particulate releases would be expected to increase by a factor from 1.25 to 2.2 times, particulate releases from the main stack would remain unchanged.
Particulate radioactivity contributes such a small fraction to collective offsite dose from particulates, iodines, and tritium that the impact on dose is negligible.
Isokinetic corrections to historic RBV releases would increase resulting doses from 0.5% to 5%, values which are well within the uncertainties in the range of +/-20-25% reported for effluent release values.
Considering that maximum individual doses from particulates, iodines, and tritium have historically been less than Page 74
2 mrem/yr, and represent a small fraction of the 15 mrem/yr 10CFR50 dose objective, any such corrections for anisokinetic conditions would be considered inconsequential.
Due to limitations in the system design of the flow controller used in the RBV sampling system, it is impractical to set the system down to the targeted isokinetic sampling flow rate of 0.6 to 0.7 cfm.
As such, this problem with anisokinetic sampling still exists.
The isokinetic probes in the RBV sampling system are scheduled to be. modified in 2008, which will correct this issue, and ensure representative sampling.
Because the problem still existed in 2007, particulate activity released from the RBV for reporting year 2007, as reported in Table 2.2-C, were corrected upward by a nominal isokinetic correction factor of 1.25, assuming that the actual particle size is distributed around a mean particle diameter of 3 microns.
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