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Annual Radioactive Effluent Release Report for January 1 Through December 31, 2017
	ML18141A428
Person / Time
Site:	Pilgrim
Issue date:	05/15/2018
From:	Miner P; Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	2.18.040
	Download: ML18141A428 (224)
	v • d • e

{{#Wiki_filter:* Entergy -===* Entergy Nuclear Operations, Inc. Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 May 15, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Annual Radioactive Effluent Release Report for January 1 through December 31, 2017 Pilgrim Nuclear Power Station Docket No. 50-293 Renewed License No. DPR-35 LETTER NUMBER: 2.18.040

Dear Sir or Madam:

In accordance with Pilgrim Nuclear Power Station Technical Specification 5.6.3, Entergy Nuclear Operations, Inc. submits the attached Annual Radioactive Effluent Release Report for January 1 through December 31, 2017. If you have any questions or require additional information, please contact me at (508) 830-7127. There are no regulatory commitments contained in this letter. Sincerely, pt12~ Manager, Regulatory Assurance PJM/mp

Attachment:

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report

Entergy Nuclear Operations, Inc. Letter No. 2.18.040 Pilgrim Nuclear Power Station Page 2 of 2 cc: Mr. David C. Lew Acting Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Boulevard, Suite 100 King of Prussia, PA 19406-2713 Mr. John Lamb, Senior Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 8 81A Washington, DC 20555 Mr. John Giarrusso, Jr. Planning, Preparedness & Nuclear Section Chief Mass. Emergency Management Agency 400 Worcester Road Framingham, MA 01702 NRC Senior Resident Inspector Pilgrim Nuclear Power Station

Attachment Letter Number 2.18.040 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report

PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 Annual Radioactive Effluent Release Report January 1 through December 31, 2017

           *--=-*Entergy Page 1

           *--=-::=-Entergy PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2017 Reviewed b y : > ~ ~ -
                   ~Blankenbiller Chemist~/~anager, Reviewed by:     _,,,'.@~ 26:-----

S. Brewer acting for L. Pepple Radiation Protection Manager Page 2 2

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report January-December 2017 TABLE OF CONTENTS SECTION SECTION TITLE PAGE 1.0 EXECUTIVE

SUMMARY

5 2.0 RADIOACTIVE EFFLUENT DATA 8 2.1 Supplemental Effluent Release Data 8 2.2 Gaseous Effluent Data 8 2.3 Liquid Effluent Data 9 3.0 METEOROLOGICAL DATA 19 4.0 MAXIMUM INDIVIDUAL DOSES 20 4.1 Doses From Noble Gas Releases 20 4.2 Doses From Gaseous Effluent Releases 22 4.3 Doses From Liquid Effluent Releases 28 5.0 OFFSITE AMBIENT RADIATION MEASUREMENTS 34 6.0 PERCENT OF ODCM EFFLUENT CONTROL LIMITS 37 6.1 Gaseous Effluent Releases 37 6.2 Liquid Effluent Releases 40 7.0 RADIOACTIVE WASTE DISPOSAL DATA 43 . 8.0 OFFSITE DOSE CALCULATION MANUAL REVISIONS 45 9.0 PROCESS CONTROL PROGRAM REVISIONS 46

10.0 REFERENCES

47 APPENDIX A Meteorological Joint Frequency Distributions 48 APPENDIX B Onsite Groundwater Monitoring Program 69 APPENDIX C Corrections to Previous Effluent Reports 73 APPENDIX D Changes to PNPS Offsite Dose Calculation Manual 74 Page 3 3

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Jan-Dec 2017 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 2017 21 4.2-A Maximum Individual Organ Doses from Gaseous Effluents 23 Jan-Mar 2017 4.2-B Maximum Individual Organ Doses from Gaseous Effluents 24 Apr-Jun 2017 4.2-C Maximum Individual Organ Doses from Gase'?us Effluents 25 Jul-Sep 2017 4.2-D Maximum Individual Organ Doses from Gaseous Effluents 26 Oct-Dec 2017 4.2-E Maximum Individual Organ Doses from Gaseous Effluents 27 Jan-Dec 2017 4.3-A Maximum Individual Organ Doses from Liquid Effluents 29 Jan-Mar 2017 4.3-B Maximum Individual Organ Doses from Liquid Effluents 30 Apr-Jun 2017 4.3-C Maximum Individual Organ Doses from Liquid Effluents 31 Jul-Sep 2017 4.3-D Maximum Individual Organ Doses from Liquid Effluents 32 Oct-Dec 2017 4.3-E Maximum Individual Organ Doses from Liquid Effluents 33 Jan-Dec 2017 5.0 Average TLD Exposures by Distance Zone During 2017 36 6.1 Percent of ODCM Effluent Control Limits for Gaseous Effluent 38 Releases During 2017 6.2 Percent of ODCM Effluent Control Limits for Liquid Effluent Releases 41 During 2017 7.0 Solid Waste and Irradiated Fuel Shipments 44 A-1 Joint Frequency Distribution of Wind Directions and Speeds for the 49 33-ft Level of the 220-ft Tower A-2 Joint Frequency Distribution of Wind Directions and Speeds for the 59 220-ft Level of the 220-ft Tower Page4 4

PILGRIM NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2017 1.0 EXECUTIVE

SUMMARY

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, 2017. This document has been prepared in accordance with the requirements set forth in the Pilgrim Nuclear Power Station (PNPS) Technical Specifications and Revision 1 of Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluents from Light Water Cooled Nuclear Power Plants". This document has been prepared in accordance with the requirements of PNPS Technical Specifications section 5.6.3. The quantity of radioactive material released from PNPS was determined from sample analyses and continuous on-line monitoring of gaseous releases from the main stack, reactor building vent, turbine building, and various decontamination facilities, and liquid releases into the discharge canal. The quantity and volume of radioactive waste shipped offsite from PNPS for processing and burial were determined from data contained on the radwaste shipping documentation. The meteorological data were obtained from monitoring instruments located on the 220-foot meteorological tower located at Pilgrim Station. GASEOUS EFFLUENTS Gaseous radioactive releases for the reporting period are quantified in Tables 2.2-A, 2.2-B, and 2.2-C. Radioactive noble gases released during the period totaled 0.00 Curies. Releases of radioactive iodines and particulates with half-life of greater than 8 days totaled 0.00026 Curies, tritium releases totaled 48 Curies, and carbon-14 totaled 7.2 Curies. No gross alpha radioactivity was detected in gaseous effluents. There were no noble gas releases during 2017 ,therefore all quarterly and annual dose consequences are zero. The release of radioactive particulates, iodines, tritium, and carbon-14 in gaseous effluents from PNPS during the reporting period resulted in a total body dose to the maximum-exposed hypothetical individual of approximately 0.015 mrem. The maximum hypothetical dose to any organ from radioactive particulates, iodines, tritium, and carbon-14 was approximately 0.071 mrem. The maximum, hypothetical total body dose from the combined release of all airborne radioactivity in gaseous effluents was 0.015 mrem. The maximum individual doses from gaseous radioactive effluents were compared to the applicable ODCM dose limits. Noble gas doses were 0.0% of the corresponding 10CFR50 dose objectives. Maximum doses resulting from releases of particulates, iodines, tritium, and carbon-14 in gaseous effluents were less than 0.48% of corresponding 10CFR50 objectives. Page 5 5

LIQUID EFFLUENTS Liquid radioactive releases for the reporting period are quantified in Tables 2.3-A and 2.3-B. Two discharges of liquid effluents containing radioactivity occurred during the reporting period. These discharges contained 0.00082 Curies of tritium, and 0.0000018 Curies of fission and activation products. The resulting maximum total body dose was 0.000000062 mrem, with a corresponding organ dose of 0.00000011 mrem. All doses from liquid discharges were. less than 0.0000055% of corresponding 10CFR50 objectives. METEOROLOGICAL DATA Meteorological joint frequency distributions are listed in Appendix A. Data recovery for the entire annual period was 98% for the 33-ft and 98% for the 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 approximately 44% of the time during the reporting period OFFSITE AMBIENT RADIATION MEASUREMENTS Ambient radiation exposure was evaluated to complete the assessment of radiological impact on humans. A small number of thermoluminescent dosimeters (TLDs) indicated an elevation in ambient radiation exposure on Entergy property in close proximity to the station, when compared to background levels in the region. This elevation is due to nitrogen-16 contained within the plant steam system, as opposed to radioactive effluent released from the plant. The dose to the maximum-exposed member of the public at the PNPS Health Club, even though they are within the owner-controlled area, was estimated as being approximately 1.9 mrem during 2017. There was no measurable increase during 2017 in ambient radiation measurements at the location of the nearest resident 0.8 km southeast of PNPS. COMBINED DOSE IMPACT The collective total body dose to a maximum-exposed hypothetical member of the public from airborne radioactivity, liquid-borne radioactivity, and ambient radiation exposure resulting from PNPS operation during 2017 was calculated as being approximately 0.76 mrem. This amount is approximately 0.12% of the typical dose of 620 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 40CFR 190. 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 981 cubic meters of solid waste, containing 195 Curies of radioactivity, were shipped during the reporting period. Page6 6

ONSITE GROUNDWATER MONITORING PROGRAM In response to the Nuclear Energy Institute Groundwater Protection Initiative, Pilgrim Station instituted a groundwater monitoring program during 2007. Four monitoring wells were installed onsite during the fourth quarter of 2007, and the first samples were collected in late November 2007. Additional sampling wells were added in 2010, 2011, 2012, 2013, and 2014. As of the end of 2017, samples are being collected from a total of 23 monitoring wells. Low levels of tritium, a radioactive isotope of hydrogen, were detected in several of these onsite wells. No other plant-related radioactivity was detected in the groundwater samples. The average concentration of tritium detected in these onsite monitoring wells during 2017 was well below the voluntary communications reporting level established by the EPA Drinking Water Standard of 20,000 pCi/L. Although the EPA Standard provides a standard for comparison, no drinking water sources are affected by this tritium. The maximum hypothetical dose resulting from tritium in groundwater presumed to enter Cape Cod Bay is calculated to be 0.0000000055 mrem/yr. Results of the groundwater monitoring program are presented in Appendix B. CONCLUSION The PNPS Offsite Dose Calculation Manual contains effluent controls to limit doses resulting from releases of radioactivity to the environment. None of the effluent controls associated with liquid or gaseous effluents were exceeded during the reporting period, as confirmed by conservative dose assessments performed at weekly and monthly intervals. Conformance to the PNPS ODCM effluent control limits ensures that releases of radioactivity in liquid and gaseous effluents are kept as low as reasonably achievable in accordance with 10 CFR Part 50, Appendix I. Compliance with the ODCM also demonstrates that requirements of the Environmental Protection Agency's nuclear fuel cycle standard, 40CFR190.10, Subpart B, have been met. Based on the dose assessment results for 2017, there was no significant radiological impact on the general public from PNPS operation. Page 7 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, 28, 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 re.lease 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: NOA, 0.00 µCi/sec
Iodines and particulates with 0.00227 Ci, 0.0000719 µCi/sec half-life greater than 8 days
Tritium: 48.1 Ci, 1.53 µCi/sec
Carbon-14: 7.22 Ci, 0.229 µCi/sec Effluent releases from the main stack are detailed in Table 2.2-8. 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 approximately 700 feet west-northwest of the reactor building.

Ground-level effluent releases are detailed in Table 2.2-C. Data in this table include releases from the reactor building vent, turbine building, and assorted equipment decontamination facilities (e.g., hot machine shop, carbon dioxide pellet decon trailer, plastic media decon trailer, etc.) used during the period. Due to the close proximity of the reactor building, all of these release points are considered to be mixed-mode/ground level release points. Following the revision of Regulatory Guide 1.21 in 2009, the nuclear industry re-assessed their gaseous effluent releases in accordance with the new definition of "principal radionuclide". Under this new definition, any radionuclide that contributed greater than 1% of the effluent dose calculated to demonstrate compliance with 10CFR50 Appendix I, or contributed more than 1% of the total activity for that type of effluent release, would be classified as a principal radionuclide. Although Carbon-14 (C-14) had been exempted from gaseous effluent calculations in the 1970s, industry assessments in 2009 revealed that Carbon-14 would qualify as a principal radionuclide. Based on this 2009 re-assessment, licensees were required to begin reporting C-14 gaseous effluents in the Annual Radioactive Effluent Release Report beginning with calendar-year 2010. Carbon-14 releases for 2017 are summarized in Tables 2.2-A through 2.2-C, and the dose consequences from C-14 are incorporated into the dose assessments documented in Section 4.2 of this report. Table 3.1-2 of the PNPS ODCM requires that if any of the gaseous effluent monitors are inoperable for more than 30-days, such events are to be reported in the Annual Radioactive Effluent Release Report with an explanation of why the affected monitor was not returned to operable status in a Page 8 8

timely manner. During 2017, there were no instances when the Turbine Building Gaseous Effluent Monitor (C-3003) or the Feed Pump Gaseous Effluent Monitor (C-3004) was out of service for more than a 30 consecutive day period. There were no instances in 2017 when both channels of a dual-channel effluent monitor (Main Stack, Reactor Building Vent) were out of service at the same time during a 30 consecutive day period. 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 approximately 1100 feet north of the reactor building. Liquid effluent releases are summarized in Table 2.3-A. Detailed breakdowns for individual radionuclides are listed in Table 2.3-B. There were two discharges of liquid effluents containing radioactivity during the reporting period. Total releases for the various categories of radionuclides, as well as their corresponding mean concentrations, can be summarized as follows:

Total Effluent Volume: 73,600 Liters
Total Dilution Volume: 612 billion Liters
Fission/Activation products: 0.00000806 Ci, 0.0000000000000132 µCi/ml
Tritium: '0.00147 Ci, 0.00000000000240 µCi/ml
Dissolved/entrained noble gases: 0.00 Ci, 0.00 µCi/ml Page 9 9

Table 2.1 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Supplemental Information January-December 2017 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. Iodines, particulates with half-life: 1500 mrem/yr to any organ at site boundary

        >8 days, tritium

d. Liquid effluents: 0.06 mrem/month for whole body and 0.2 mrem/month for any organ (without radwaste treatment)

2. EFFLUENT CONCENTRATION LIMITS

a. Fission and activation gases: 10CFR20 Appendix B Table II

b. Iodines: 10CFR20 Appendix B Table II

c. Particulates with half-life > 8 days: 10CFR20 Appendix B Table II

d. Liquid effluents: 2E-04 µCi/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. Iodines: gamma emitters; radiochemistry analysis for H-3, C. Particulates: Fe-55 (liquid effluents), Sr-89, and Sr-90

d. Liquid effluents:

5. BATCH RELEASES Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec 2017 2017 2017 2017 2017

a. Liquid Effluents

1. Total number of releases: 1.00E+OO 1.00E+OO N/A N/A 2.00E+OO

2. Total time period (minutes): 9.30E+02 8.90E+02 N/A N/A 1.82E+03

3. Maximum time period (minutes): 9.30E+02 8.90E+02 N/A N/A 9.30E+02

4. Average time period (minutes): 9.30E+02 8.90E+02 N/A N/A 9.10E+02

5. Minimum time period (minutes): 9.30E+02 8.90E+02 N/A N/A 8.90E+02

6. Average stream flow during periods of release of 1.18E+06 6.81 E+04 N/A N/A 6.26E+05 effluents into a flowing stream (Liters/min):

b. Gaseous Effluents None None None None None

6. ABNORMAL RELEASES

a. Liquid Effluents None None None None None

b. Gaseous Effluents None None None None None Page 10 10

Table 2.2-A Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Summation of All Releases January-December 2017 Est. RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Total 2017 2017 2017 2017 2017 Error A. FISSION AND ACTIVATION GASES Total Release: Ci NOA NOA NOA NOA NOA Averaqe Release Rate: uCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO +/-22% Percent of Effluent Control Limit* * * * * *

8. IODINE-131 Total lodine-131 Release: Ci 1.25E-04 6.51E-05 4.30E-05 2.86E-05 2.62E-04 Average Release Rate: uCi/sec 1.59E-05 8.25E-06 5.45E-06 3.63E-06 8.30E-06 +/-20%

Percent of Effluent Control Limit* * * * *

C. PARTICULATES WITH HALF-LIVES> 8 DAYS Total Release: Ci 2.62E-04 4.07E-04 1.38E-05 O.OOE+OO 6.83E-04 Average Release Rate: uCi/sec 3.33E-05 5.16E-05 1.75E-06 O.OOE+OO 2.17E-05

                                                                                                      +/-21%

Percent of Effluent Control Limit* * * * *

Gross Alpha Radioactivity: Ci NOA NOA NOA NOA NOA D. TRITIUM Total Release: Ci 1.68E+01 7.57E+OO 1.18E+01 1.19E+01 4.81E+01 AveraQe Release Rate: uCi/sec 2.13E+OO 9.60E-01 1.50E+OO 1.51E+OO 1.53E+OO +/-20%

Percent of Effluent Control Limit* * * * *

E. CARBON-14 Total Release: Ci 1.95E+OO 1.06E+OO 2.10E+OO 2.10E+OO 7.22E+OO Average Release Rate: uCi/sec 2.48E-01 1.34E-01 2.66E-01 2.67E-01 2.29E-01 N/A Percent of Effluent Control Limit* * * * *
Notes for Table 2.2-A:
Percent of Effluent Control Limit values based on dose assessments are provided in Section 6 of this report.

1. NOA stands for No Detectable Activity.

2. LLD for airborne gross alpha activity listed as NOA is 1E-11 µCi/cc.

3. N/A stands for not applicable.

Page 11 11

Table 2.2-B Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Elevated Release January-December 2017 CONTINUOUS MODE RELEASES FROM ELEVATED RELEASE POINT

. Nuclide Released             Jan-Mar 2017       Apr-Jun 2017    Jul-Sep 2017 Oct-Dec 2017 Jan-Dec 2017

1. FISSION AND ACTIVATION GASES: Ci Ar-41 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-87 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-131m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-133m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total for Period O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

2. IODINES: Ci 1-131 5.81 E-07 3.07E-07 O.OOE+OO 4.84E-07 1.37E-06 1-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total for Period 5.81E-07 3.07E-07 O.OOE+OO 4.84E-07 1.37E-06

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

4. TRITIUM: Ci H-3 3.25E-02 1.61 E-02 4.58E-02 4.72E-02 1.42E-01

5. CARBON-14: Ci C-14 1.90E+OO 1.03E+OO 2.04E+OO 2.04E+OO 7.00E+OO Notes for Table 2.2-B:

1. N/A stands for not applicable.

2. NOA stands for No Detectable Activity.

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

Fission Gases: 1E-04 µCi/cc Iodines: 1E-12 µCi/cc Particulates: 1E-11 µCi/cc Page 12 12

Table 2.2-B (continued) Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Elevated Release January-December 2017 BATCH MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released Jan-Mar 2017 Apr-Jun 2017 Jul-Sep 2017 Oct-Dec 2017 Jan-Dec 2017

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 NIA N/A N/A N/A Kr-87 N/A N/A N/A N/A N/A Kr-88 NIA N/A N/A NIA NIA Xe-131m NIA NIA NIA NIA N/A Xe-133 NIA NIA NIA NIA NIA Xe-133m NIA NIA N/A NIA NIA Xe-135 NIA NIA NIA NIA N/A Xe-135m N/A NIA NIA NIA N/A Xe-137 NIA NIA NIA N/A NIA Xe-138 NIA NIA NIA NIA N/A Total for period NIA NIA NIA N/A NIA

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

3. PARTICULATES WITH HALF-LIVES > 8 DA VS: Ci Cr-51 NIA N/A NIA NIA NIA Mn-54 N/A NIA NIA NIA NIA Fe-59 NIA NIA NIA NIA NIA Co-58 N/A NIA NIA N/A NIA Co-60 NIA NIA NIA NIA NIA Zn-65 NIA NIA N/A NIA NIA Sr-89 NIA NIA NIA N/A NIA Sr-90 N/A N/A N/A NIA N/A Ru-103 NIA N/A NIA NIA NIA Cs-134 N/A NIA NIA NIA NIA Cs-137 NIA NIA NIA NIA NIA Ba/La-140 NIA NIA NIA N/A N/A Total for period N/A NIA N/A NIA NIA

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

5. CARBON-14: Ci C-14 NIA NIA N/A NIA NIA Notes for Table 2.2-8:

1. N/A stands for not applicable.

2. NOA stands for No Detectable Activity.

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

Fission Gases: 1E-04 µCi/cc Iodines: 1E-12 µCi/cc Particulates: 1E-11 µCi/cc Page 13 13

Table 2.2-C Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Ground-Level Release January-December 2017 CONTINUOUS MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released Jan-Mar 2017 , Apr-Jun 2017 Jul-Sep 2017 Oct-Dec 2017 Jan-Dec 2017

1. FISSION AND ACTIVATION GASES: Ci Ar-41 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-87 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-131m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-133m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total for period O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

2. IODINES: Ci 1-131 1.25E-04 6.48E-05 4.30E-05 2.81 E-05 2.60E-04 1-133 6.86E-04 2.12E-04 1.90E-04 2.34E-04 1.32E-03 Total for period 8.11 E-04 2.77E-04 2.33E-04 2.62E-04 1.58E-03

3. PARTICULATES WITH HALF-LIVES > 8 DAYS: Ci Cr-51 O.OOE+OO 7.10E-05 O.OOE+OO O.OOE+OO 7.10E-05 Mn-54 9.33E-05 1.24E-04 O.OOE+OO O.OOE+OO 2.17E-04 Fe-59 O.OOE+OO 1.22E-05 O.OOE+OO O.OOE+OO 1.22E-05 Co-58 1.13E-05 9.83E-06 O.OOE+OO O.OOE+OO 2.11 E-05 Co-60 6.54E-05 8.64E-05 O.OOE+OO O.OOE+OO 1.52E-04 Zn-65 5.19E-05 8.16E-05 O.OOE+OO O.OOE+OO 1.33E-04 Sr-89 1.65E-05 2.24E-05 1.38E-05 O.OOE+OO 5.28E-05 Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO Cs-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba/La-140 2.41 E-05 O.OOE+OO O.OOE+OO 0.00E+OO 2.41 E-05 Total for period 2.62E-04 4.0?E-04 1.38E-05 O.OOE+OO 6.83E-04

4. TRITIUM: Ci H-3 1.68E+01 7.55E+OO 1.18E+01 1.19E+01 4.80E+01

5. CARBON-14: Ci C-14 5.86E-02 3.24E-02 6.23E-02 6.31 E-02 2.16E-01 Notes for Table 2.2-C:

1. N/A stands for not applicable.

2. NOA stands for No Detectable Activity.

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

Fission Gases: 1E-04 µCi/cc Iodines: 1E-12 µCi/cc Particulates: 1E-11 µCi/cc Page 14 14

Table 2.2-C (continued) Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Ground-Level Release January-December 2017 BATCH MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released Jan-Mar 2017 Apr-Jun 2017 Jul-Seo 2017 Oct-Dec 2017 Jan-Dec 2017

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 NIA N/A N/A NIA N/A Kr-87 N/A N/A N/A N/A N/A Kr-88 N/A N/A N/A N/A N/A Xe-131m N/A N/A N/A N/A N/A Xe-133 N/A N/A N/A N/A N/A Xe-133m N/A N/A N/A N/A N/A Xe-135 N/A N/A N/A N/A NIA Xe-135m N/A N/A N/A N/A N/A Xe-137 N/A NIA N/A N/A NIA 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 DAVS: Ci Cr-51 N/A N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A N/A Co-58 N/A N/A N/A N/A N/A Co-60 N/A N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A N/A Ru-103 N/A N/A N/A N/A NIA 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 NIA N/A N/A N/A N/A

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

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

1. N/A stands for not applicable.

2. NOA stands for No Detectable Activity.

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

Fission Gases: 1E-04 µCi/cc Iodines: 1E-12 µCi/cc Particulates: 1E-11 µCi/cc Page 15 15

Table 2.3-A Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents - Summation of All Releases January-December 2017 Est. RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Total 2017 2017 2017 2017 2017 Error A. FISSION AND ACTIVATION PRODUCTS Total Release (not including NOA 1.77E-06 N/A N/A 1.77E-06 tritium, gases, alpha): Ci Average Diluted Concentration NOA 1.68E-14 N/A N/A 3.14E-15 +/-12% During Period: µCi/ml Percent of Effluent Concentration O.OOE+OO% 1.68E-06% N/A N/A 3.14E-0% Limit* B. TRITIUM Total Release: Ci 4.18E-4 3.98E-04 N/A N/A 8.16E-04 Average Diluted Concentration 2.83E-12 3.79E-12 N/A N/A 1.45E-12 +/-9.4% During Period: µCi/ml Percent of Effluent Concentration 2.83E-07% 3.79E-07% N/A N/A 1.45E-07% Limit* C. DISSOLVED AND ENTRAINED GASES Total Release: Ci N/A NOA NOA N/A NOA Average Diluted Concentration N/A NOA NOA N/A NOA +/-16% Durinq Period: uCi/mL Percent of Effluent Concentration NIA O.OOE+OO% O.OOE+OO% N/A O.OOE+00% Limit* D. GROSS ALPHA RADIOACTIVITY Total Release: Ci N/A NOA NOA N/A NOA +/-34% E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION Waste Volume: Liters 3.67E+04 3.29E+04 O.OOE+OO O.OOE+OO 6.95E+04 +/-5.7% F. VOLUME OF DILUTION WATER USED DURING PERIOD Dilution Volume: Liters 1.48E+11 1.05E+11 1.55E+11 1.55E+11 5.63E+11 +/-10% Notes for Table 2.3-A:

Additional percent of Effluent Control Limit values based on dose assessments are provided in Section 6 of this report.

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

4. LLD for liquid gross alpha activity listed as NDA is 1E-07 µCi/ml.

Page 16 16

Table 2.3-8 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2017 CONTINUOUS MODE RELEASES Nuclide Released Jan-Mar 2017 Apr-Jun 2017 Jul-Sep 2017 *Oct-Dec 2017 Jan-Dec 2017

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 NIA N/A 8a/la-140 N/A N/A N/A N/A N/A Ce-141 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A

2. DISSOLVED AND ENTRAINED GASES: Ci Xe-133 N/A N/A N/A N/A N/A Xe-135 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A Notes for Table 2.3-8:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

Strontium: SE-08 µCi/ml Iodines: 1E-06 µCi/ml Noble Gases: 1E-05 µCi/ml All Others: SE-07 µCi/ml Page 17 17

Table 2.3-B (continued) Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2017 BATCH MODE RELEASES Nuclide Released Jan-Mar 2017 Apr-Jun 2017 Jul-Sep 2017 Oct-Dec 2017 Jan-Dec 2017

1. FISSION AND ACTIVATION PRODUCTS: Ci Na-24 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Cr-51 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Mn-54 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Fe-55 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Fe-59 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Co-58 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Co-60 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Zn-65 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Zn-69m O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Sr-89 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Sr-90 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Zr/Nb-95 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Mo/Tc-99 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Ag-110m O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Sb-124 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO 1-131 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO 1-133 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Cs-134 0.00E+OO O.OOE+OO NIA NIA O.OOE+OO Cs-137 O.OOE+OO 1.77E-06 NIA NIA 1.77E-06 Ba/la-140 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Ce-141 O.OOE+OO O.OOE+OO NIA NIA O.OOE+OO Ce-144 O.OOE+OO O.OOE+OO NIA N/A O.OOE+OO Total for period O.OOE+OO 1.77E-06 NIA NIA 1.77E-06

2. DISSOLVED AND ENTRAINED GASES: Ci Xe-133 NOA NOA NIA NIA NOA Xe-135 NOA NOA NIA NIA NOA Total for period NOA NOA NIA NIA NOA Notes for Table 2.3-B:

1. N/A stands for not applicable.

2. NOA stands for No Detectable Activity.

3. llDs for liquid radionuclides listed as NOA are as follows:

Strontium: 5E-08 µCi/ml Iodines: 1E-06 µCi/ml Noble Gases: 1E-05 ~tCi/ml All Others: 5E-07 ~tCi/ml Page 18 18

3.0 METEOROLOGICAL DATA Meteorological data are summarized for the reporting period in Appendix A, in the standard joint frequency distribution format as given in NRC Regulatory Guide 1.21. The predominant meteorological conditions observed during the annual reporting period can be summarized with their corresponding frequencies as follows:

Stability Class: Class D, 44%
33-ft Wind Direction (from): South-southwest, 14%
33-ft Wind Speed: 3.5-7.5 mph, 57%
220-ft Wind Direction (from): South-southwest, 13%
220-ft Wind Speed: 12.5-18.5 mph, 36%

Joint data recovery for the 33-ft level was 97.9% and for the 220-ft level of the tower was 97.8%, both of which meet the 90% annual data recovery goal specified by the NRC. Problems were encountered in late September 2016 and continued through the end of February 2017, regarding some anomalous delta-T readings observed on the 220-ft tower, until the temperature elements could be replaced. Wind speed and wind direction values from the 220-ft tower were not affected. Issues with ultrasonic wind sensor heaters were typical for the reporting period winter months. Ice and snow occasionally plugged the sensors until the low current heaters melted the ice pack, the weather subsided or the sensors Page 19 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, 2.2-8, 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. There were no noble gas releases during 2017 ,therefore all quarterly and annual dose consequences are zero. Page 20 20

Table 4.1 Maximum Doses From Noble Gas Releases During 2017<a> Gamma Beta Total Release Air Dose Air,Dose Body Dose Skin Dose Period mrad/period mrad/period mrem/period mrem/period (location) (location) (location) (location) Jan-Mar O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (0.52 km SSE) (0.64 km ESE) (0.52 km SSE) (0.54 km NW) Apr-Jun O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (0.52 km SSE) (0.64 km ESE) (0.52 km SSE) (0.54 km NW) Jul-Sep O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (0.52 km SSE) (0.64 km ESE) (0.52 km SSE) (0.54 km NW) Oct-Dec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (0.52 km SSE) (0.64 km ESE) (0.52 km SSE) (0.54 km NW) Jan-Dec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (0.52 km SSE) (0.64 km ESE) (0.52 km SSE) (0.54 km NW) Cal All directions and distances are with respect to the reactor building vent. Page 21 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 2005 through 2014 were used as input to the NRC XOQDOQ computer program (Reference 7). This program was used to calculate the annual average atmospheric dispersion and deposition factors used in the dose assessment computer program to calculate maximum individual doses. The maximum individual doses resulting from radioactive particulates, radioiodines, tritium and carbon-14 released in gaseous effluents are presented in Tables 4.2-A through 4.2-E. These tables cover the individual calendar quarters and the total calendar year, respectively. Doses resulting from releases of noble gases are addressed independently in the PNPS ODCM. Therefore, none of these tables for maximum individual doses include any dose contribution from noble gases. The presentation and analysis of doses resulting from noble gases are addressed in Section 4.1 of this report. Tables 4.2-A through 4.2-E summarize the maximum total body and organ doses for the adult, teen, child, and infant age classes resulting from the major gaseous exposure pathways. These tables present the dose data according to specific receptor location and the exposure pathways assumed to occur at that location. For'example, the second column of the tables presents the information for the hypothetical maximum-exposed at the most restrictive site boundary location, where only inhalation and ground deposition exposure pathways are assumed to occur. Since this is a shoreline location controlled by Entergy, the other pathways of garden vegetable production, milk production, and meat production are assumed not to occur. Doses for other offsite locations not under Entergy control, where other exposure pathways can and do occur, are presented in subsequent columns of the tables, and represent the potential maximum doses to individuals at these locations. For consistency, all distances listed in the first row of Tables 4.2-A through 4.2-E are measured from the Reactor Building Vent. However, doses at the specific receptor locations are calculated based on the actual distances from the applicable release points (PNPS main stack, reactor building vent, and turbine building roof exhausters). Radioactivity (particulates, radioiodines, tritium, and carbon-14) released in gaseous effluents from PNPS during 2017 resulted in a maximum total body dose of 0.0152 mrem (child age class at nearest meat animal, 3.82 kilometers S from the Reactor Building), while the maximum organ dose was 0.0714 mrem (child bone at nearest meat animal, 3.82 kilometers S from the Reactor Building). Carbon-14 contributed 93% of the child total body dose and >99% of the child bone dose at the location of the nearest meat animal. Page 22 22

Table 4.2-A Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Jan-Mar 2017 Receptor: Bound Resident Garden Cow/Goat Cow/Meat Meat Direction: WNW s s w w s Distance 1: 0.24km 2.22 km 3.44 km 3.75 km 5.17 km 3.82 km Pathway2 : DI DI DIV 3 DIVCG 3 DIVCM 3 DIVM 3 Age Class: Adult Bone 6.07E-05 1.39E-04 4.40E-03 2.55E-03 2.25E-03 5.95E-03 GI-LLI 1.04E-04 9.74E-05 1.09E-03 8.02E-04 6.46E-04 1.42E-03 Kidney 1.03E-04 9.73E-05 1.0BE-03 7.98E-04 6.43E-04 1.41 E-03 Liver 1.03E-04 9.73E-05 1.0BE-03 8.00E-04 6.44E-04 1.41 E-03 Lung 1.0BE-04 1.01 E-04 1.09E-03 7.97E-04 6.41 E-04 1.41 E-03 Thyroid 1.25E-04 1.14E-04 1.14E-03 1.05E-03 7.86E-04 1.47E-03 T.Body 1.03E-04 9.72E-05 1.0BE-03 7.97E-04 6.42E-04 1.41 E-03 Age Class: Teen Bone 8.70E-05 2.00E-04 7.12E-03 4.29E-03 3.40E-03 8.39E-03 GI-LLI 1.09E-04 1.09E-04 1.65E-03 1.19E-03 8.94E-04 1.92E-03 Kidney 1.09E-04 1.09E-04 1.65E-03 1.19E-03 8.92E-04 1.91 E-03 Liver 1.09E-04 1.09E-04 1.65E-03 1.19E-03 8.94E-04 1.92E-03 Lung 1.16E-04 1.14E-04 1.65E-03 1.19E-03 8.90E-04 1.92E-03 Thyroid 1.37E-04 1.31 E-04 1.70E-03 1.55E-03 1.10E-03 1.97E-03 T.Body 1.09E-04 1.09E-04 1.65E-03 1.19E-03 8.91E-04 1.91 E-03 Age Class: Child Bone 1.20E-04 2.76E-04 1.70E-02 1.04E-02 7.99E-03 1.94E-02 GI-LLI 1.04E-04 1.15E-04 3.71E-03 2.54E-03 1.90E-03 4.20E-03 Kidney 1.05E-04 1.15E-04 3.71E-03 2.55E-03 1.90E-03 4.20E-03 Liver 1.05E-04 1.15E-04 3.71 E-03 2.55E-03 1.90E-03 4.20E-03 Lunq 1.10E-04 1.19E-04 3.71 E-03 2.54E-03 1.89E-03 4.20E-03 Thyroid 1.38E-04 1.42E-04 3.79E-03 3.25E-03 2.29E-03 4.28E-03 T.Body 1.04E-04 1.15E-04 3.71E-03 2.55E-03 1.90E-03 4.20E-03 Age Class: Infant Bone 8.85E-05 2.03E-04 1.34E-04 6.50E-03 4.55E-03 1.33E-04 GI-LLI 6.49E-05 7.71E-05 5.64E-05 1.63E-03 1.11 E-03 5.57E-05 Kidney 6.50E-05 7.72E-05 5.64E-05 1.63E-03 1.11 E-03 5.58E-05 Liver 6.50E-05 7.72E-05 5.64E-05 1.64E-03 1.11 E-03 5.58E-05 Lung 6.84E-05 7.99E-05 5.85E-05 1.62E-03 1.10E-03 5.78E-05 Thyroid 9.61E-05 1.02E-04 7.59E-05 3.21 E-03 1.98E-03 7.49E-05 T.Bodv 6.49E-05 7.71E-05 5.64E-05 1.63E-03 1.10E-03 5.57E-05 1 Distances are measured with respect to the reactor building vent. 2 Pathway designations are as follows:

D Deposition (Ground Plane) I = Inhalation = V Vegetable Garden 3

C Cow Milk = G Goat Milk = M Meat Doses are conservative since it is unlikely for vegetables to be grown outside or for animals to be fed on pasture during winter months. Page 23 23

Table 4.2-B Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Apr-Jun 2017 Receptor: Bound Resident Garden Cow/Goat Cow/Meat Meat Direction: WNW s s w w s Distance 1: 0.24km 2.22 km 3.44 km 3.75 km 5.17 km 3.82 km Pathway2 : DI DI DIV 3 DIVCG 3 D1VCM 3 DIVM 3 Age Class: Adult Bone 3.31 E-05 7.57E-05 2.39E-03 1.39E-03 1.23E-03 3.23E-03 GI-LLI 4.79E-05 4.64E-05 5.77E-04 4.16E-04 3.39E-04 7.58E-04 Kidney 4.76E-05 4.62E-05 5.70E-04 4.10E-04 3.34E-04 7.47E-04 Liver 4.76E-05 4.62E-05 5.71E-04 4.13E-04 3.36E-04 7.SOE-04 Lung 5.34E-05 5.08E-05 5.72E-04 4.09E-04 3.32E-04 7.48E-04 Thyroid 5.65E-05 5.32E-05 5.96E-04 5.32E-04 4.03E-04 7.76E-04 T.Body 4.76E-05 4.61E-05 5.70E-04 4.09E-04 3.33E-04 7.47E-04 Age Class: Teen Bone 4.73E-05 1.08E-04 3.87E-03 2.34E-03 1.85E-03 4.56E-03 GI-LLI 5.09E-05 5.28E-05 8.81 E-04 6.25E-04 4.71E-04 1.03E-03 Kidney 5.07E-05 5.26E-05 8.74E-04 6.21E-04 4.69E-04 1.02E-03 Liver 5.07E-05 5.26E-05 8.76E-04 6.26E-04 4.72E-04 1.02E-03 Lung 5.92E-05 5.93E-05 8.78E-04 6.19E-04 4.66E-04 1.02E-03 Thyroid 6.20E-05 6.15E-05 8.98E-04 8.00E-04 5.69E-04 1.04E-03 T.Body 5.06E-05 5.25E-05 8.75E-04 6.20E-04 4.68E-04 1.02E-03 Age Class: Child Bone 6.53E-05 1.SOE-04 9.24E-03 5.64E-03 4.35E-03 1.0SE-02 GI-LLI 4.92E-05 5.66E-05 1.99E-03 1.34E-03 1.01 E-03 2.25E-03 Kidney 4.92E-05 5.66E-05 1.99E-03 1.35E-03 1.01 E-03 2.25E-03 Liver 4.92E-05 5.66E-05 1.99E-03 1.35E-03 1.01 E-03 2.25E-03 Lunq 5.61E-05 6.20E-05 1.99E-03 1.34E-03 1.00E-03 2.25E-03 Thyroid 6.27E-05 6.72E-05 2.02E-03 1.69E-03 1.20E-03 2.29E-03 T.Body 4.91 E-05 5.65E-05 1.99E-03 1.35E-03 1.01 E-03 2.25E-03 Age Class: Infant Bone 4.81E-05 1.10E-04 7.27E-05 3.54E-03 2.48E-03 7.20E-05 GI-LLI 3.09E-05 3.85E-05 2.79E-05 8.79E-04 5.99E-04 2.76E-05 Kidney 3.09E-05 3.85E-05 2.79E-05 8.72E-04 5.94E-04 2.76E-05 Liver 3.09E-05 3.85E:..QS 2.79E-05 8.85E-04 6.03E-04 2.76E-05 Lung 3.54E-05 4.21E-05 3.07E-05 8.61E-04 5.86E-04 3.03E-05 Thyroid 4.33E-05 4.83E-05 3.56E-05 1.66E-03 1.03E-03 3.52E-05 T.Bodv 3.09E-05 3.85E-05 2.79E-05 8.71E-04 5.93E-04 2.75E-05 1 Distances are measured with respect to the reactor building vent. 2 Pathway designations are as follows:

D Deposition (Ground Plane) I = Inhalation V = Vegetable Garden

C Cow Milk = G Goat Milk M = Meat Page 24 24

Table 4.2-C Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Jul-Sep 2017 Receptor: Bound Resident Garden Cow/Goat Cow/Meat Meat Direction: WNW s s w w s Distance 1: 0.24km 2.22 km 3.44 km 3.75 km 5.17 km 3.82 km Pathway2: DI DI DIV3 DIVCG 3 DIVCM 3 DIVM 3 AQe Class: Adult Bone 6.SOE-05 1.SOE-04 4.72E-03 2.74E-03 2.41 E-03 6.38E-03 GI-LU 7.68E-05 7.80E-05 1.09E-03 7.47E-04 6.16E-04 1.43E-03 Kidney 7.68E-05 7.80E-05 1.09E-03 7.47E-04 6.16E-04 1.43E-03 Liver 7.68E-05 7.80E-05 1.09E-03 7.46E-04 6.16E-04 1.43E-03 Lung 7.69E-05 7.81 E-05 1.09E-03 7.46E-04 6.15E-04 1.43E-03 Thyroid 8.35E-05 8.33E-05 1.10E-03 8.32E-04 6.65E-04 1.45E-03 T.Body 7.68E-05 7.80E-05 1.09E-03 7.46E-04 6.16E-04 1.43E-03 Age Class: Teen Bone 9.31 E-05 2.14E-04 7.63E-03 4.60E-03 3.64E-03 9.01 E-03 GI-LU 8.26E-05 9.0SE-05 1.68E-03 1.15E-03 8.75E-04 1.96E-03 Kidney 8.26E-05 9.0SE-05 1.68E-03 1.15E-03 8.75E-04 1.96E-03 Liver 8.26E-05 9.0SE-05 1.68E-03 1.15E-03 8.75E-04 1.96E-03 Lung 8.28E-05 9.07E-05 1.68E-03 1.15E-03 8.74E-04 1.96E-03 Thyroid 9.12E-05 9.73E-05 1.70E-03 1.27E-03 9.46E-04 1.98E-03 T.Bodv 8.26E-05 9.0SE-05 1.68E-03 1.15E-03 8.74E-04 1.96E-03 Age Class: Child Bone 1.29E-04 2.96E-04 1.83E-02 1.11 E-02 8.56E-03 2.0SE-02 GI-LU 8.16E-05 9.99E-05 3.87E-03 2.SSE-03 1.92E-03 4.38E-03 Kidney 8.17E-05 1.00E-04 3.87E-03 2.SSE-03 1.92E-03 4.38E-03 Liver 8.16E-05 1.00E-04 3.87E-03 2.SSE-03 1.92E-03 4.38E-03 Lung 8.18E-05 1.00E-04 3.87E-03 2.SSE-03 1.92E-03 4.38E-03 Thyroid 9.20E-05 1.08E-04 3.89E-03 2.79E-03 2.0SE-03 4.41E-03 T.Body 8.16E-05 9.99E-05 3.87E-03 2.SSE-03 1.92E-03 4.38E-03 Age Class: Infant Bone 9.47E-05 2.18E-04 1.44E-04 6.96E-03 4.87E-03 1.42E-04 GI-LU 5.21 E-05 6.93E-05 4.95E-05 1.65E-03 1.13E-03 4.90E-05 Kidney 5.21 E-05 6.93E-05 4.96E-05 1.65E-03 1.13E-03 4.90E-05 Liver 5.21 E-05 6.93E-05 4.96E-05 1.65E-03 1.13E-03 4.90E-05 Lung 5.23E-05 6.94E-05 4.97E-05 1.65E-03 1.13E-03 4.91E-05 Thyroid 6.16E-05 7.68E-05 5.SSE-05 2.19E-03 1.43E-03 5.49E-05 T.Body 5.21E-05 6.93E-05 4.95E-05 1.65E-03 1.13E-03 4.90E-05 1 Distances are measured with respect to the reactor building vent. 2 Pathway designations are as follows: D = Deposition (Ground Plane) I = Inhalation V = Vegetable Garden C = Cow Milk G = Goat Milk M = Meat Page 25 25

Table 4.2-D Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Oct-Dec 2017 Receptor: Bound Resident Garden Cow/Goat Cow/Meat Meat Direction: WNW s s w w s Distance 1: 0.24km 2.22 km 3.44 km 3.75 km 5.17 km 3.82 km Pathway2: DI DI DIV 3 DIVCG 3 DIVCM 3 DIVM 3 Age Class: Adult Bone 6.51E-05 1.SOE-04 4.72E-03 2.74E-03 2.42E-03 6.38E-03 GI-LLI 7.73E-05 7.84E-05 1.09E-03 7.49E-04 6.17E-04 1.43E-03 Kidney 7.74E-05 7.85E-05 1.09E-03 7.49E-04 6.18E-04 1.43E-03 Liver 7.73E-05 7.84E-05 1.09E-03 7.49E-04 6.17E-04 1.43E-03 Lung 7.73E-05 7.84E-05 1.09E-03 7.49E-04 6.17E-04 1.43E-03 Thyroid 8.34E-05 8.32E-05 1.10E-03 8.08E-04 6.52E-04 1.45E-03 T.Body 7.73E-05 7.84E-05 1.09E-03 7.49E-04 6.17E-04 1.43E-03 Age Class: Teen Bone 9.32E-05 2.14E-04 7.64E-03 4.61E-03. 3.64E-03 9.01 E-03 GI-LLI 8.32E-05 9.09E-05 1.69E-03 1.15E-03 8.77E-04 1.97E-03 Kidney 8.32E-05 9.10E-05 1.69E-03 1.15E-03 8.77E-04 1.97E-03 Liver 8.32E-05 9.10E-05 1.69E-03 1.15E-03 8.77E-04 1.97E-03 Lung 8.31E-05 9.09E-05 1.69E-03 1.15E-03 8.77E-04 1.97E-03 Thyroid 9.11 E-05 9.72E-05 1.70E-03 1.24E-03 9.26E-04 1.98E-03 T.Body 8.31 E-05 9.09E-05 1.69E-03 1.15E-03 8.77E-04 1.97E-03 Age Class: Child Bone 1.29E-04 2.96E-04 1.83E-02 1.11 E-02 8.57E-03 2.0SE-02 GI-LLI 8.21 E-05 1.00E-04 3.87E-03 2.SSE-03 1.92E-03 4.39E-03 Kidney 8.22E-05 1.00E-04 3.87E-03 2.SSE-03 1.92E-03 4.39E-03 Liver 8.22E-05 1.00E-04 3.87E-03 2.SSE-03 1.92E-03 4.39E-03 Lung 8.21E-05 1.00E-04 3.87E-03 2.SSE-03 1.92E-03 4.39E-03 Thyroid 9.20E-05 1.08E-04 3.89E-03 2.72E-03 2.02E-03 4.41 E-03 T.Body- 8.22E-05 1.00E-04 3.87E-03 2.55E-03 1.92E-03 4.39E-03 Age Class: Infant Bone 9.49E-05 2.18E-04 1.44E-04 6.97E-03 4.88E-03 1.42E-04 GI-LLI 5.24E-05 6.95E-05 4.97E-05 1.65E-03 1.13E-03 4.92E-05 Kidney 5.24E-05 6.96E-05 4.98E-05 1.65E-03 1.13E-03 4.92E-05 Liver 5.24E-05 6.96E-05 4.97E-05 1.65E-03 1.13E-03 4.92E-05 Lung 5.24E-05 6.95E-05 4.97E-05 1.65E-03 1.13E-03 4.92E-05 Thyroid 6.15E-05 7.67E-05 5.54E-05 2.02E-03 1.34E-03 5.48E-05 T.Body 5.24E-05 6.95E-05 4.97E-05 1.65E-03 1.13E-03 4.92E-05 1 Distances are measured with respect to the reactor building vent. 2 Pathway designations are as follows: D =Deposition (Ground Plane) I =Inhalation V =Vegetable Garden C =Cow Milk G =Goat Milk M = Meat 3 Doses are conservative since it is unlikely for vegetables to be grown outside or for animals to be fed on pasture during winter months. Page 26 26

Table 4.2-E Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Jan-Dec 2017 Receptor: Bound Resident Garden Cow/Goat Cow/Meat Meat Direction: WNW s s w w s Distance 1: 0.24km 2.22 km 3.44 km 3.75 km 5.17 km 3.82 km Pathway2: DI DI DIV3 D1VCG 3 DIVCM 3 DIVM 3 Age Class: Adult Bone 2.24E-04 5.14E-04 1.62E-02 9.41 E-03 8.29E-03 2.19E-02 GI-LLI 3.0SE-04 3.00E-04 3.83E-03 2.71E-03 2.21E-03 5.03E-03 Kidney 3.0SE-04 3.00E-04 3.82E-03 2.70E-03 2.21 E-03 5.02E-03 Liver 3.0SE-04 3.00E-04 3.82E-03 2.70E-03 2.21 E-03 5.02E-03 Lung 3.15E-04 3.08E-04 3.83E-03 2.70E-03 2.20E-03 5.02E-03 Thyroid 3.48E-04 3.33E-04 3.94E-03 3.21 E-03 2.SOE-03 5.14E-03 T.Body 3.0SE-04 2.99E-04 3.82E-03 2.70E-03 2.20E-03 5.02E-03 Age Class: Teen Bone 3.20E-04 7.35E-04 2.62E-02 1.58E-02 1.25E-02 3.09E-02 GI-LLI 3.26E-04 3.43E-04 5.89E-03 4.11 E-03 3.11 E-03 6.87E-03 Kidney 3.25E-04 3.43E-04 5.88E-03 4.11 E-03 3.11 E-03 6.85E-03 Liver 3.25E-04 3.43E-04 5.89E-03 4.12E-03 3.11E-03 6.86E-03 Lung 3.40E-04 3.55E-04 5.89E-03 4.10E-03 3.10E-03 6.86E-03 Thyroid 3.81 E-04 3.86E-04 5.99E-03 4.86E-03 3.53E-03 6.97E-03 T.Body 3.25E-04 3.43E-04 5.88E-03 4.10E-03 3.11 E-03 6.85E-03 Age Class: Child Bone 4.42E-04 1.02E-03 6.27E-02 3.82E-02 2.94E-02 7.14E-02 GI-LLI 3.17E-04 3.71E-04 1.34E-02 8.97E-03 6.73E-03 1.52E-02 Kidney 3.17E-04 3.72E-04 1.34E-02 8.98E-03 6.74E-03 1.52E-02 Liver 3.17E-04 3.72E-04 1.34E-02 8.99E-03 6.75E-03 1.52E-02 Lung 3.29E-04 3.81 E-04 1.34E-02 8.97E-03 6.73E-03 1.52E-02 Thyroid 3.85E-04 4.25E-04 1.36E-02 1.04E-02 7.56E-03 1.54E-02 T.Body 3.17E-04 3.71 E-04 1.34E-02 8.98E-03 6.74E-03 1.52E-02 Age Class: Infant Bone 3.26E-04 7.48E-04 4.93E-04 2.39E-02 1.67E-02 4.89E-04 GI-LLI 2.00E-04 2.54E-04 1.83E-04 5.80E-03 3.96E-03 1.81 E-04 Kidney 2.00E-04 2.54E-04 1.83E-04 5.80E-03 3.96E-03 1.81 E-04 Liver 2.00E-04 2.54E-04 1.83E-04 5.82E-03 3.97E-03 1.81 E-04 Lung 2.08E-04 2.61E-04 1.88E-04 5.78E-03 3.94E-03 1.86E-04 Thyroid 2.62E-04 3.03E-04 2.22E-04 9.06E-03 5.77E-03 2.19E-04 T.Body 2.00E-04 2.54E-04 1.83E-04 5.79E-03 3.95E-03 1.81 E-04 1 Distances are measured with respect to the reactor building vent. 2 Pathway designations are as follows: D =Deposition (Ground Plane) I =Inhalation V =Vegetable Garden C =Cow Milk G =Goat Milk M = Meat 3 Doses are conservative since it is unlikely for vegetables to be grown outside or for animals to be fed on pasture during winter months. Page 27 27

4.3 Doses From Liquid Effluent Releases Liquid effluent release data presented in Tables 2.3-A and 2.3-8 were used as input to the dose assessment computer program to calculate radiation doses. The maximum individual doses resulting from radionuclides released in liquid effluents are presented in Tables 4.3-A through 4.3-E. These tables cover the individual calendar quarters and the total calendar year, respectively. Tables 4.3-A through 4.3-E summarize the maximum total body and organ doses for the adult, teen, and child age classes resulting from the major liquid exposure pathways. NRC Regulatory Guide 1.109 does not recognize the infant age class as being exposed to the liquid effluent pathways. Therefore, doses for this age class are not included in any of the tables. It should be noted that doses calculated for the entire year might not equal the sum of the doses for the individual quarters. Doses from liquid effluents are based on the concentration (activity divided by volume) of radionuclides released in the effluent, as prescribed by the NRC in Regulatory Guide 1.109. If a larger proportion of activity is released with a relatively smaller volume of dilution water during a given quarter, the resulting concentration for that quarter will be higher than concentrations from other quarters. This will result in a proportionally higher dose for that quarter. However, when that quarter's activity values are included in the annual sum, and divided by the total annual dilution flow, the resulting dose contribution will be smaller. In such a situation, the annual dose will actually be less than the sum of the individual quarterly doses. Radioactivity released in liquid effluents from PNPS during the reporting period resulted in a maximum total body dose (teen age class) of 0.000000062 mrem. The maximum organ dose (teen age class, Liver) was 0.00000011 mrem. Page 28 28

Table 4.3-A Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jan-Mar 2017 Age Class Organ Dose - mrem

Organ Adult Teen Child Bone O.OOE+OO O.OOE+OO O.OOE+OO GI-LLI 4.04E-10 2.99E-10 2.58E-10 Kidney 4.04E-10 2.99E-10 2.58E-10 Liver 4.04E-10 2.99E-10 2.58E-10 Lung 4.04E-10 2.99E-10 2.58E-10 Thyroid 4.04E-10 2.99E-10 2.58E-10 T.Body 4.04E-10 2.99E-10 2.58E-10
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.

      - Highest total body dose and highest organ dose are balded.

Page 29 29

Table 4.3-B Maximum Individual Organ Doses -- mrem From Liquid Release Period: Apr-Jun 2017 Age Class Organ Dose - mrem Organ Adult Teen Child Bone 7.98E-08 1.22E-07 1.06E-07 GI-LLI 1.09E-08 4.91 E-08 1.08E-08 Kidney 4.21 E-08 8.14E-08 4.03E-08 Liver 1.07E-07 1.47E-07 1.03E-07 Lung 2.00E-08 6.08E-08 2.11 E-08 Thyroid 9.03E-09 4.77E-08 1.02E-08 T.Body 7.29E-08 8.22E-08 2.39E-08

         -Highest total body dose and highest organ dose are balded.

Page 30 30

Table 4.3-C Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jul-Sep 2017 Age Class Organ Dose - mrem Organ Adult Teen Child Bone N/A N/A N/A GI-LLI N/A N/A N/A Kidney N/A N/A N/A Liver N/A N/A N/A Lung N/A N/A N/A Thyroid N/A N/A N/A T.Body N/A N/A N/A Page 31 31

Table 4.3-D Maximum Individual Organ Doses -- mrem From Liquid Release Period: Oct-Dec 2017 Age Class Organ Dose - mrem

Organ Adult Teen Child Bone N/A N/A N/A GI-LLI N/A N/A N/A Kidney N/A N/A N/A Liver N/A N/A N/A Lung N/A N/A N/A Thyroid N/A N/A N/A T.Body N/A N/A N/A
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

                                                                                          , 32

Table 4.3-E Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jan-Dec 2017 Age Class Organ Dose - mrem

Organ Adult Teen Child Bone 5.95E-08 9.08E-08 7.93E-08 GI-LU 8.57E-09 3.70E-08 8.34E-09 Kidney 3.19E-08 6.10E-08 3.04E-08 Liver 7.99E-08 1.10E-07 7.68E-08 Lung 1.54E-08 4.57E-08 1.60E-08 Thyroid 7.16E-09 3.59E-08 7.91 E-09 T.Body 5.48E-08 6.16E-08 1.81 E-08
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. -Highest total body dose and highest organ dose are balded. Page 33 . 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 86 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 approximately 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 (l&S Building), was 216 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 78.8 +/- 29.5 mR/yr to 65.3 +/- 7.9 mR/yr. Such a corrected dose is not statistically different from the Zone 4 average of 62.6 +/- 8.8 mR/yr, and is indicative of natural background radiation. Although the annual exposure at TLD location OA was 151 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 hours per year would only receive an incremental dose of 2.7 mrem over natural background radiation levels. At the nearest residence 0.8 kilometers (0.5 miles) southeast of the PNPS Reactor Building, the annual exposure was calculated as being 63.3 +/- 2.1 mR (based on continuous occupancy at this location), which compares quite well to the Zone 4 annual average background radiation level of 62.6 +/- 8.9 mR. Statistically, there is no difference between these two values. Page 34 34

Pilgrim Station began moving spent fuel to the Independent Spent Fuel Storage Installation (ISFSI) located within the protected area immediately west of the PNPS Reactor Building. Three new TLDs were installed at the beginning of 2016 to monitor any incremental dose from this facility. TLD ISF-1 was located on Rocky Hill Road 0.35 km (0.21 mi) southwest of the reactor building. The annual exposure at this location was calculated as being 79.2 +/- 4.3 mR (based on continuous occupancy at this location), or 16.6 mR above the Zone 4 average of 62.6 mR. However, the area is not continuously occupied, and when corrected for an exposure time of 365 hours/year, the estimated exposure to a person walking along this section of Rocky Hill Road would be 0.69 mR/year. It must be emphasized that the projected ambient exposures discussed above and 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 40CFR 190. Both of these limits are to be applied to real members of the general public, so the fact that the dose to the hypothetical maximum-exposed individual is within the limits ensures that any dose received by a real member of the public would be smaller and well within any applicable limit. In 1994, Pilgrim Station opened the old training facility (l&S Building) overlooking the plant as a health club for its employees. This site is immediately adjacent to the protected area boundary near monitoring location OA and receives appreciable amounts of direct ambient and sky shine exposure from the turbine building. Although personnel using this facility are employees of Entergy, they are considered to be members of the public. Due to their extended presence in the facility (500 hr/yr, assuming utilization of the facility for 2 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 2017 is estimated as being approximately 1.9 mrem, based on the average exposure measured by the TLD in the building. The exposures measured by the TLD located in the health club would also include any increase in ambient radiation resulting from noble gases and/or particulate activity deposited on the ground from gaseous releases. However, they would not indicate any internal dose received by personnel in this facility from inhalation of small amounts of PNPS-related radioactivity contained in the air. An environmental air sampler located immediately adjacent to the health club did not indicate any PNPS-related activity during 2017. 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 approximately 0.0012 mrem, resulting from inhalation. Again, it must be emphasized that the above-described exposures were received by personnel who are employees or contractors of Entergy, accessing areas or facilities on property under the ownership and control of Entergy. Since this exposure was received within the owner-controlled area, it is not used for comparison to the annual dose limit of 25 mrem/yr specified in 40CFR 190. This regulation explicitly 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 0.7 mrem/year. Page 35 35

Table 5.0 Average TLD Exposures By Distance Zone During 2017 Average Exposure+/- Standard Deviation: mR/:>eriod Exposure Zone 1* Zone 2 Zone 3 Zone 4 Period 0-3 km 3-8 km 8-15 km >15 km Jan-Mar 18.8 +/- 5.4 15.0+/-1.9 14.7 +/- 1.8 15.5 +/- 2.1 Apr-Jun 19.2 +/- 6.4 14.8 +/- 2.0 14.1 +/- 1.5 15.3 +/- 2.3 Jul-Sep 20.6 +/- 9.4 15.1 +/- 1.8 15.1+/-1.4 16.0 +/- 2.2 Oct-Dec 20.2 +/- 7.8 15.4 +/- 2.2 14.9 +/- 1.8 15.9 +/- 2.7 Jan-Dec 78.8 +/- 29.5 60.3 +/- 7.8 58.7 +/- 6.3 62.6 +/- 8.8

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 65.3 +/- 7.9 mR/yr.

Page 36 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 2017 were a small percentage of the corresponding effluent control. Page 37 37

Table 6.1 Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2017 A. Instantaneous Dose Rate Limit - Noble Gases PNPS ODCM Control 3.3.1.a Limit: 500 mrem/yr Total Body Dose Period Value - mrem/yr Fraction of Limit Jan-Dec O.OOE+OO O.OOE+OO% B. Instantaneous Dose Rate Limit - Noble Gases PNPS ODCM Control 3.3.1.a Limit: 3000 mrem/yr Skin Dose Period Value - mrem/yr Fraction of Limit Jan-Dec O.OOE+OO O.OOE+OO% C. Instantaneous Dose Rate Limit - Particulates, Iodines, & Tritium PNPS ODCM Control 3.3.1.b Limit: 1500 mrem/yr Organ Dose Period Value - mrem/yr Fraction of Limit Jan-Dec 7.14E-02 4.76E-03% D. Quarterly Dose Objective - Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.a Objective: 5 mrad Gamma Air Dose Period Value- mrad Fraction of Limit Jan-Mar O.OOE+OO O.OOE+OO% Apr-Jun O.OOE+OO O.OOE+OO% Jul-Sep O.OOE+OO O.OOE+OO% Oct-Dec O.OOE+OO O.OOE+OO% E. Annual Dose Objective - Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.b Objective: 10 mrad Gamma Air Dose Period Value - mrad/yr Fraction of Limit Jan-Dec O.OOE+OO O.OOE+OO% Page 38 38

Table 6.1 (continued) Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2017 F. Quarterly Dose Objective - Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.a Objective: 1O mrad Beta Air Dose Period Value - mrad Fraction of Limit Jan-Mar O.OOE+OO O.OOE+OO% Apr-Jun O.OOE+OO O.OOE+OO% Jul-Sep O.OOE+OO O.OOE+00% Oct-Dec O.OOE+OO O.OOE+OO% G. Annual Dose Objective - Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.b Objective: 20 mrad Beta Air Dose Period Value - mrad/yr Fraction of Limit Jan-Dec O.OOE+OO O.OOE+OO% H. Quarterly Dose Objective - Particulates, Iodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.a Objective: 7.5 mrem Organ Dose Period Value - mrem Fraction of Limit Jan-Mar 1.94E-02 2.59E-01% Apr-Jun 1.05E-02 1.40E-01% Jul-Sep 2.0SE-02 2.77E-01% Oct-Dec 2.0SE-02 2.77E-01% I. Annual Dose Objective - Particulates, Iodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.b Objective: 15 mrem Organ Dose Period Value - mrem/yr Fraction of Limit Jan-Dec 7.14E-02 4.76E-01% Page 39 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 the reporting period were a small percentage of the corresponding effluent controls. Page 40 40

Table 6.2 Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2017 A. Fission and Activation Product Effluent Concentration Limit PNPS ODCM Control 3.2.1 Limit: 10CFR20 Appendix B, Table 2, Column 2 Value Period Value - µCi/ml Fraction of Limit Jan-Mar O.OOE+OO 0.00% Apr-Jun 1.68E-14 1.68E-06% Jul-Sep N/A N/A Oct-Dec N/A N/A Jan-Dec 3.14E-15 3.14E-07% B. Tritium Average Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1.0E-03 µCi/ml Period Value - µCi/ml Fraction of Limit Jan-Mar 2.83E-12 2.83E-07% Apr-Jun 3.79E-12 3.79E-07% Jul-Sep N/A N/A Oct-Dec N/A N/A Jan-Dec 1.45E-12 1.45E-07% C. Dissolved and Entrained Noble Gases Concentration Limit PNPS ODCM Control 3.2.1 Limit: 2.0E-04 µCi/ml Period Value - µCi/ml Fraction of Limit Jan-Mar O.OOE+OO O.OOE+OO% Apr-Jun O.OOE+OO O.OOE+OO% Jul-Sep N/A NIA Oct-Dec N/A N/A Jan-Dec O.OOE+OO O.OOE+00% Page 41 41

Table 6.2 (continued) Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2017 . D. Quarterly Total Body Dose Objective PNPS ODCM Control 3.2.2.a Objective: 1.5 mrem Total Body Dose Period Value - mrem Fraction of Limit Jan-Mar 4.04E-10 2.?0E-08% Apr-Jun 8.22E-08 5.48E-06% Jul-Sep N/A N/A Oct-Dec N/A N/A E. Annual Total Body Dose Objective PNPS ODCM Control 3.2.2.b Objective: 3 mrem Total Body Dose Period Value - mrem Fraction of Limit Jan-Dec 6.16E-08 2.0SE-06% F. Quarterly Organ Dose Objective PNPS ODCM Control 3.2.2.a Objective: 5 mrem Organ Dose Period Value - mrem Fraction of Limit Jan-Mar 4.04E-10 8.09E-09% Apr-Jun 1.47E-07 2.93E-06% Jul-Sep N/A N/A Oct-Dec N/A N/A G. Annual Organ Dose Objective PNPS ODCM Control 3.2.2.b Objective: 1O mrem Organ Dose Period Value - mrem Fraction of Limit Jan-Dec 1.10E-07 1.10E-06% Page 42 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 th~ 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 61.6 cubic meters of spent resins, filter sludges, etc., containing a total activity of approximately 192 Curies were shipped from PNPS for processing and disposal. Dry activated wastes and contaminated equipment shipped during the period totaled 919 cubic meters and contained 2.56 Curies of radioactivity. There were no shipments of irradiated components during the reporting period. There were no shipments of "Other wastes" during the reporting period. There were no shipments of irradiated fuel during the reporting period. Estimates of principal radionuclides, those comprising greater than 1% of the total activity in each waste category shipped, are listed in Table 7.0. There were 25 shipments to Energy Solutions' Bear Creek Facility in Oak Ridge, TN; 3 shipments to Energy Solutions Erwin Resin Solutions' Facility in Erwin, TN.; and 2 shipments to Energy Solutions, Memphis Facility, Memphis, TN. Page 43 43

Table 7.0 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments January-December 2017 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 2017 Type of waste Volume-m" Curies Total Error

a. Spent resins, filters, filter sludges, 6.16E+01 1.92E+02 +/-25%

evaporator bottoms, etc.

b. Dry activated waste, contaminated 9.19E+02 2.56E+OO +/-25%

equipment, etc. C. Irradiated components, control rods, etc. O.OOE+OO O.OOE+OO N/A

d. Other (describe): O.OOE+OO O.OOE+OO N/A

2. Estimate of major nuclide composition by type of waste 1 Type of waste Radionuclide Abundance Total Error

a. Spent resins, filters, filter sludge's, Mn-54 29.70% +/-25%

evaporator bottoms, etc. Fe-55 11.29% +/-25% Co-60 23.19% +/-25% Zn-65 17.17% +/-25% Ni-63 1.25% +/-25% Cs-137 14.03% +/-25%

b. Dry activated waste, contaminated Mn-54 2.46% +/-25%

equipment, etc. Fe-55 78.50% +/-25% Co-60 14.60% +/-25% Ni-63 1.29% +/-25%

c. Irradiated components, control rods, etc. N/A N/A N/A

d. Other (describe): Contaminated oil and water N/A N/A N/A 1 "

Ma1or 1s defmed as any rad1onucltde compnsmg >1 0% of the total activity m the waste category.

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination Tractor-trailer Energy Solutions, Bear Creek Facility" 25 (Hittman Transport) Oak Ridqe, TN Tractor-trailer Energy Solutions, Erwin Resin Solutions" 3

(Hittman Transport) Erwin, TN Tractor-trailer Energy Solutions, Memphis Facility" 1 (Hittman Transport) Memphis, TN L This processor provides volume reduction services for dry compressible waste, contammated eqwpment, etc. Remaining radioactive wastes will be shipped to Envirocare, Inc. in Clive, UT for final disposal. B. IRRADIATED FUEL SHIPMENTS & DISPOSITION Number of Shi ments Mode of Trans ortation Destination None N/A N/A Page 44 44

8.0 OFFSITE DOSE CALCULATION MANUAL REVISIONS The PNPS Offsite Dose Calculation Manual (ODCM) was revised during the calendar year of 2017. Information regarding revisions to the ODCM can be found attached as Appendix D of this report. Page 45 45

9.0 PROCESS CONTROL PROGRAM REVISIONS The following list summarizes changes made during 2017 to various procedures related to the Process Control Program (PCP): EN-RW-102, "Radioactive Shipping Procedure", Rev.14: The purpose of this revision is remove GGNS section 8.0 items that are not commitments. This revision is non-editorial for GGNS and editorial for the rest of the fleet.

Deleted GGNS line items from section 8.0 that are not actually commitments.
Updated coversheet EN-RW-104, "Scaling Factors, Rev 13 The purpose of this revision is to add a revised NRC Branch Technical Position to the list of documents and to make changes as recommended by CR-HQN-2016-00106, CA-2.
Added step 2.0[10]
Section 3.0: deleted definition for "Not Present" because phrase is removed from procedure with this Rev.
Revised step 5.2[2](a) for sampling resin media
Revised step 5.3[2] deleting step (a)
Section 5.4 is rewritten
Section 5.5 for Radman version 8.3 as it appears in Rev. 12 is deleted
Section 5.5 for current version (formerly section 5.6) of Radman is rewritten
Section 6.0: deleted interface for WMG-P-065
Attachment 9.1, sheet 1: deleted "Not Present"
Attachment 9.1, sheet 2: deleted "Not Present" columns from 10CFR20 and RADMAN nuclide tables
Attachment 9.1, sheet 3: removed the "Not Present" column from Table 1 and Table 2
Attachment 9.1, sheet 4: modified parenthetical for 10 CFR 20 Appendix G nuclides
Attachment 9.1, sheet 3: converted units of nCi/g to units of µCi/g
EN-RW-106, "Integrated Transportation Security Plan", Rev.6
The purpose of this revision is to add requirements for refresher training per 10 CFR 37.43 in response to CR-WF3-2016-02243.
Added step 5.6[6]

Add Check off for attachment 9.6 and 9. 7 to verify Department of Homeland Security and MARS EC levels prior to shipment of Category 1 and Category 2 quantities of radioactive material. EN-RW-108, "Radioactive Shipment Accident Response", Rev.2: The purpose of this revision is to address the issue identified in CR-HQN-2016-00530 and CR-HQN-2016-00873 regarding contacting ANI.

Step 2.0[9]: added reference to ANI Information Bulletin 11-01
Step 2.0[1 OJ: added reference to ANI Guideline 15-02
Step 5.4[1]: simplified step for contacting Licensing Step 5.4[2]: added step addressing how to contact ANI Page 46 46

10.0 REFERENCES

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

2. "Pilgrim Nuclear Power Station Offsite Dose Calculation Manual", Revision 10, May 2009.

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 10CFRSO 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".

7. U.S. Nuclear Regulatory Commission, "XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations", NUREG/CR2919, September 1982.

Page 47 47

APPENDIX A Meteorological Joint Frequency Distributions TABLE TABLE TITLE PAGE A-1 Joint Frequency Distribution of Wind Directions and Speeds for the 49 33-ft Level of the 220-ft Tower A-2 Joint Frequency Distribution of Wind Directions and Speeds for the 59 220-ft Level of the 220-ft Tower Page 48 48

Table A-1 Joint Frequency Distribution of Wind Directions and Speeds For the 33-ft level of the 220-ft Tower Jan-Mar 2017 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 6 0 2 2 1 0 0 0 0 0 0 0 0 4 4 4 23 3.5-7.5 16 9 18 15 6 0 0 1 0 0 1 5 22 42 24 8 167 7.5-12.5 4 4 1 4 0 0 0 0 0 0 0 5 27 30 14 0 89 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 1 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                26           13            21     21  7     0     0     1     0     0     1   10 50    76 42   12  280 mph              N        NNE              NE   ENE   E    ESE  SE    SSE     s   SSW    SW  WSW w    WNW NW  NNW TOTAL Calm-0.95                 0             0            0      0  0     0     0     0     0     0     0    0  0     0  0    0    0 0.95-3.5               2             1            1      1  3     0     0     0     0     0     0    0  1     0  0    1   10 3.5-7.5             0             1            2      2  4     0     2     0     0     1     4    8  9     4  1    1   39 7.5-12.5              0             4            5      3  0     0     0     0     2     8     3    6  8     8  4    0   51 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             6            8      6  7     0     2     0     2     9     7   14 18    12  5    2  100

_........... - I '"""t* ............ mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 1 0 2 3 1 0 0 0 0 1 0 1 0 0 1 10 3.5-7.5 2 1 2 10 4 4 0 2 1 3 10 10 11 7 4 5 76 7.5-12.5 1 0 6 6 0 0 1 0 1 10 2 3 7 3 13 0 53 12.5-18.5 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 18.5-24 0 0 0 0 0 0 0 0 0 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             2           8     18  7      5    1     2      2   13     13  13 19    10  17   6  140
   ...., ................ I '""'"t*  .................

mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 9 6 4 9 4 3 2 6 7 9 8 9 11 4 8 10 109 3.5-7.5 15 14 13 29 49 21 11 14 31 45 46 72 120 59 47 22 608 7.5-12.5 4 7 12 9 4 4 19 18 39 53 15 15 39 14 17 4 273 12.5-18.5 0 4 1 2 0 0 1 0 0 0 0 0 0 0 0 0 8 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

               >24             0             0            0     0   0     0    0      0     0    0      0   0   0    0   0   0    0 TOTAL               28           31            30    49  57    28   33     38    77   107    69  96 170   77  72  36   998 Page 49 49

Table A-1 (continued) Jan-Mar 2017 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 o o o o o o o o o o o o o o o o o 0.95-3.5 4 4 1 3 3 3 5 3 2 8 15 22 27 14 11 3 128 3.5-7.5 5 6 4 3 6 2 1 8 13 35 31 38 28 5 14 1 200 7.5-12.5 1 o o o 2 1 3 10 2 22 o 4 3 o o 1 49 12.5-18.5 o o o o o o o o o o o o o o o o o 18.5-24 o o o o o o o o o o o o o o o o o

            >24      o     o    o   o   o  o    o    o    o    o     o    o   o    o   o   o     o TOTAL      10     10   5   6  11  6    9   21   17   65   46    64  58   19  25   5   377 Class F      Freg: 0.039 mph       N    NNE  NE ENE   E ESE SE SSE      s  SSW SW     WSW  w   WNW  NW  NNW TOTAL Calm-0.95    o      o   o   o   o  o    o    o    o    o     o    o   o    o   o   o     o 0.95-3.5    2      o   o   1   o  o    1    1    2    1     3   18   9    1   o   1    40 3.5-7.5    o      o   o   o   o  o    o    2    2    4    13    7   o    o   o   o    28 7.5-12.5    o      o   o   o   o  o    o    2    o    1    6     o   o    o   o   o     9 12.5-18.5     o     o   o   o   o  o    o    o    o    o     o    o   o    o   o    o    o 18.5-24      o     o   o   o   o  o    o    o    o    o     o    o   o    o   o   o     o
            >24       o     o   o   o   o  o    o    o    o    o     o    o   o    o   o   o     o TOTAL       2      o   o   1   o  o    1    5    4    6    22   25   9    1   o   1    77 mph      N    NNE  NE ENE   E ESE SE SSE      s  SSW  SW    WSW  w   WNW  NW  NNW TOTAL Calm-0.95     o     o   o   o   o  o     o   o    o    o     o    o   o    o   o    o    o 0.95-3.5     o     o   o   o   o  o     o   o    1    o     o    o   o    o   o   o     1 3.5-7.5     o     o   o   o   o  o     o   o    o    o     5    2   o    o   o    o    7 7.5-12.5     o     o   o   o   o   o    o   o    o    2     5    o   o    o   o    o    7 12.5-18.5     o     o   o   o   o  o     o   o    o     o    o    o   o    o   o    o    o 18.5-24      o     o   o   o   o  o     o   o    o    o     o    o   o    o   o    o    o
            >24       o     o   o   o   o  o     o   o    o    o     o    o   o    o   o    o    o TOTAL       o     o   o   o   o  o     o   o    1    2    10    2   o    o   o    o   15 Class All    Freg: 1.000 mph       N   NNE  NE ENE   E ESE SE SSE      s  SSW SW     WSW   w  WNW  NW  NNW TOTAL Calm-0.95     o     o   o    o  o   o    o   o    o     o    o    o   o    o   o    o    o 0.95-3.5    23    12   8  18  14  7     8  10   12    18   27   49  49   23  23   20  321 3.5-7.5    38    31  39  59  69  27   14  27   47    88  11 o  142 190  117  90  37  1125 7.5-12.5    10    15  24   22  6   5   23  30   44    96   31   33  84   55  48    5  531 12.5-18.5     1     4   1   2   o   o    1   o    o     o    o    o   1    o    o   o   10 18.5-24     o     o   o    o  o   o    o   o    o     o    o    o   o    o    o   o    o
            >24       o     o   o    o  o   o    o   o    o     o    o    o   o    o    o   o    o TOTAL      72    62  72  101 89  39   46  67   103  202  168   224 324  195 161  62  1987 Page 50 50

Table A-1 (continued) Apr-Jun 2017 moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 5 3 4 1 6 1 0 0 0 0 0 1 2 1 1 4 29 3.5-7.5 22 27 31 29 24 6 6 0 0 0 1 6 18 22 9 5 206 7.5-12.5 0 0 0 1 0 4 10 1 6 17 4 2 0 4 0 0 49 12.5-18.5 0 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 2 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

           >24      0       0   0   0  0   0    0   0     0     0    0 0   0   0  0  0     0 TOTAL      27      30  35  31 30  11   16   1     6    19   5  9  20  27 10  9   286 mph       N     NNE  NE ENE E  ESE  SE   SSE    s   SSW  SW WSW w  WNW NW NNW TOTAL Calm-0.95    0       0   0   0  0   0    0   0     0     0    0 0   0   0  0  0     0 0.95-3.5    2       4   3   6  3   0    0   0     0     0    0 0   3   6  3  2    32 3.5-7.5    2       4   2   4  2   9    3   1     1     9    8 2   5   3  6  1    62 7.5-12.5    0       4   0   0  0   0    1   2    17    16   5  0   1   0  1  0    47 12.5-18.5    0       0   0   0  0   0    0   0     0     2    0 0   0   0  0  0     2 18.5-24     0       0   0   0  0   0    0   0     0      0   0 0   0   0  0  0     0
           >24      0       0   0   0  0   0    0   0     0      0   0 0   0   0  0  0     0 TOTAL      4      12   5  10  5   9    4   3    18    27   13 2   9   9 10  3   143 mph      N     NNE  NE ENE  E ESE   SE  SSE    s   SSW  SW WSW w  WNW NW NNW TOTAL Calm-0.95     0      0   0   0  0   0    0   0      0     0   0 0   0   0  0  0     0 0.95-3.5    0       1   4   3  4   1    1   0      0     0   0 0   1   1  1  0    17 3.5-7.5    6       8   4   3  3   4    5   3     5     8    7 6   5   2  1  1    71 7.5-12.5    0       3   1   0  0   2    2   2    13    18    3 0   0   0  2  0    46 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   9   6  7   7    8   5    18    26   10 6   6   3  4  1   134 Class D   Fre_g_: 0.415 mph      N     NNE  NE ENE  E ESE   SE  SSE    s   SSW  SW WSW w  WNW NW NNW TOTAL Calm-0.95     0      0   0   0  0   0    0    0     0     0   0  0  0   0  0  0     0 0.95-3.5    24     27  15  22 23   5    9   10    11     6   3  2  7   8 21  7   200 3.5-7.5    18     25  28  20 41  27   42   44   72     69  24 23 31  22  9  9   504 7.5-12.5    4       7   6   2  4  15   14   12   41     72  15  0  0   0  0  3   195 12.5-18.5     0      0   0   0  0   2    2    1     2     0   0  0  0   0  0   0    7 18.5-24     0      0   0   0  0   0    0    0     0     0   0  0  0   0  0   0    0
           >24       0      0   0   0  0   0    0    0     0     0   0  0  0   0  0   0    0 TOTAL      46     59  49  44 68  49   67   67   126   147  42 25 38  30 30  19  906 Page 51 51

Table A-1 (continued) Apr-Jun 2017 Class E F 0.22 - mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 1 1 0 0 1 0 0 0 3 0.95-3.5 6 9 4 8 16 3* 5 14 8 4 9 24 7 12 14 8 151 3.5-7.5 2 7 3 2 2 15 5 21 28 70 37 39 15 5 4 1 256 7.5-12.5 0 0 0 0 0 0 9 4 1 37 10 1 3 0 0 0 65 12.5-18.5 0 0 0 0 0 0 0 1 0 10 0 0 0 0 0 0 11 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      8      16    7   10  18   18   19   40   38    122  56 64  26   17 18   9   486 Class F            0 mph      N     NNE   NE  ENE   E  ESE  SE   SSE    s   SSW  SW WSW  w   WNW NW  NNW TOTAL Calm-0.95    0       0    0    0   0    0    0    0    0      0   0  0   0    0  0   0     0 0.95-3.5    2       1    0    1   3    0    0    1    5      3  14 13   5   4   2   0    54 3.5-7.5    0       0    0    0   0    0    2    0    7     17  60 12   6    1  0   0   105 7.5-12.5    0       0    0    0   0    0    0    0    0     13   7  0   0    0  0   0    20 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        1   0    1   3    0    2    1   12     33  81 25  11    5  2   0   179 Class G            0.02 mph      N     NNE   NE  ENE   E  ESE   SE  SSE    s   SSW  SW WSW   w  WNW NW  NNW TOTAL Calm-0.95    0        0   0    0   0    0    0     0    0     0   0   0   0   0  0    0    0 0.95-3.5   1        1   0    0   0    0    0     0    0     3   6  3    0   0  0    0   14 3.5-7.5    0        0   0    0   0    0    0     0    0     2  14  4    1   0  0    0   21 7.5-12.5    0        0   0    0   0    0    0     0    0     2   9  0    0   0  0    0   11 12.5-18.5    0       0   0    0    0   0    0     0    0     0   2   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       1       1   0    0    0   0    0     0    0     7  31   7   1   0   0   0   48 Class All  Fre_g: 1.000 mph       N    NNE   NE  ENE   E  ESE   SE  SSE    s   SSW  SW WSW   w  WNW NW  NNW TOTAL Calm-0.95     0       0   0    0    0   0    0     0    1     1   0   0   1   0   0   0    3 0.95-3.5   40      46  30   41   55  10   15    25   24    16  32  43  25  32  42  21  497 3.5-7.5   50      71  68   58   72  61   63   69   113   175 151  92  81  55 29   17  1225 7.5-12.5   4       14   7    3   4   21   36    21   78   175  53   3   4   4   3   3  433 12.5-18.5    0       0   0    0    0   2    2     2    2    14   2   0   0   0   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      94     131  105  102 131  94  116   117  218   381 238 138 111  91  74  41  2182 Page 52 52

Table A-1 (continued) Jul-Sep 2017 Class A Freq: 0.087 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 21 15 14 5 5 2 0 0 0 0 0 0 3 5 4 10 84 3.5-7.5 10 12 8 7 10 7 3 2 5 6 1 2 8 14 3 4 102 7.5-12.5 0 0 0 0 0 0 0 1 4 0 0 0 0 0 0 0 5 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      31    27  22  12 15  9     3   3      9    6    1  2  11  19  7  14  191 Class B    Freq: O mph        N   NNE  NE ENE E  ESE  SE   SSE    s  SSW   SW  WSW w  WNW NW NNW TOTAL Calm-0.95     0     0   0   0  0  0     0   0      0    0    0  0   0   0  0   0    0 0.95-3.5     2     3   1  4   3  1     0   0      0    0    0  0   5  2   3   1   25 3.5-7.5     1     0   4  2   0  3     2   2      9   10   4   8   8   0  1   1   55 7.5-12.5     0     0   0   0  0  0     0   0     11    6    0  0   0  0   0  0    17 12.5-18.5     0     0   0   0  0  0     0   0      0    0    0  0   0   0  0  0    0 18.5-24     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       3     3   5   6  3  4     2   2    20    16    4  8  13  2   4  2    97 Class C mph       N   NNE  NE ENE E  ESE   SE  SSE    s   SSW  SW  WSW w  WNW NW NNW TOTAL Calm-0.95     0     0   0   0  0   0    0   0      0     0   0  0   0   0  0   0    0 0.95-3.5     4     0   6   6  3   0    0   0      0     1   1  0   4   3  1   3   32 3.5-7.5     2     5   0   0  4  2     4   1     17    7    8  8   4   2  0   0   64 7.5-12.5     0     0   0   0  0  0     0   1      5    7    0  0   0   0  0  0    13 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     5   6   6  7   2    4   2     22    15   9   8  8   5  1   3  109 Class D    Freg: 0.377 mph       N   NNE  NE ENE  E ESE   SE  SSE     s  SSW  SW  WSW w  WNW NW NNW TOTAL Calm-0.95     0     0   0   0  0   0    0    0     0     0   0   0  0   1  0   0    1 0.95-3.5    12    28  25  51 28  25    9    9     9    17   9   6 14   9 10  13  274 3.5-7.5    16    70   7   2  7  16   20   27   111    89  51  16  7   3 10   7  459 7.5-12.5     5    32   0   0  0   3    7    1    22   25    0   0  0   0  0   0   95 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      33    130 32  53 35  44   36   37   142   131  60  22 21  13 20  20  829 Page 53 53

Table A-1 (continued) Jul-Sep 2017 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 2 3 0.95-3.5 12 12 *5 38 18 12 17 15 29 14 13 24 26 25 10 8 278 3.5-7.5 5 7 5 4 1 8 5 15 44 99 74 32 2 3 6 7 317 7.5-12.5 0 6 0 0 0 0 0 0 0 10 5 0 0 0 0 0 21 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

            >24      0       0      0   0   0   0    0    0    0      0   0   0   0    0  0   0     0 TOTAL      17      25     10  42  19  20   22   30   73    123 92   56  29   28 16   17  619 mph       N     NNE    NE  ENE  E  ESE   SE  SSE    s   SSW  SW  WSW  w   WNW NW  NNW TOTAL Calm-0.95     0       0      0   0   0   0    0    0    0      1   0   0   0    0  0   0     1 0.95-3.5    1       1      0   4   0   0    2    5   11     12 26   37  28    7  0   0   134 3.5-7.5    0       0      0   0   0   0    0    8    7    33  73    9   0    0  0   0   130 7.5-12.5    0       0      0   0   0   0    0    0    0      3   5   0   0    0  0   0     8 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        1     0   4   0   0    2   13   18     49 104  46  28    7  0    0  273 mph      N     NNE    NE  ENE   E ESE   SE  SSE    s   SSW  SW  WSW   w  WNW NW  NNW TOTAL Calm-0.95    0        0     0   0   0   0    0    0     0     0   0    0  0    0  0    0    0 0.95-3.5    0        0     0   0   0   0    0    2     1     4  11  34   9    0  0    0   61 3.5-7.5    0        0     0   0   0   0    0    0     0     0  18    1  0    0  0    0   19 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    2     1     4  29   35   9   0  0    0   80 Class All  Fre_g: 1.000 mph      N     NNE    NE  ENE   E ESE   SE  SSE    s   SSW  SW  WSW   w  WNW NW  NNW TOTAL Calm-0.95    0        0     0   0   0   0    0    0     0     1   0    0   1   1   0   2    5*

0.95-3.5 52 59 51 108 57 40 28 31 50 48 60 101 89 51 28 35 888 3.5-7.5 34 94 24 15 22 36 34 55 193 244 229 76 29 22 20 19 1146 7.5-12.5 5 38 0 0 0 3 7 3 42 51 10 0 0 0 0 0 159 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     91      191    75  123 79  79   69   89   285   344 299  177 119  74  48  56  2198 Page 54 54

Table A-1 (continued) Oct-Dec2017 Class A F 0.117 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 3 5 6 2 0 1 0 1 0 0 1 0 0 1 0 0 20 3.5-7.5 8 19 8 2 8 4 0 0 2 3 1 19 53 33 9 4 173 7.5-12.5 0 2 0 0 0 0 1 0 8 2 1 9 23 11 2 0 59 12.5-18.5 0 0 0 0 0 0 0 2 3 1 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      11     26  14  4  8   5     1   3    13     6    3 28  76   45 11   4   258 Class B    F      0.053 mph       N    NNE  NE ENE E  ESE  SE   SSE   s    SSW  SW WSW  w   WNW NW  NNW TOTAL Calm-0.95     0      0   0  0  0   0     0   0     0     0    0  0   0    0  0   0     0 0.95-3.5    1      0   0  1  0   1     0   0     0     0    1  0   0    2  0    1    7 3.5-7.5    3     10   1  0  0   4     1   0     5    10    6 16  18    3  2   6    85 7.5-12.5    0      0   0  0  0   0     3   0     1     6    2  0   7    3  0   0    22 12.5-18.5    0      0   0  0  0   0     0   1     1     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       4     10   1  1  0   5     4   1     7    16    9 16  25    8  2   7   116 Class C    F      0.089 mph       N    NNE  NE ENE E  ESE   SE  SSE   s    SSW  SW WSW   w  WNW NW  NNW TOTAL Calm-0.95     0      0   0  0  0   0     0   0     0      0   0   0  0    0  0    0    0 0.95-3.5    2      3   0  0  0   0     1   0     1     2    1   1  3    3  0    1   18 3.5-7.5    5     27   2  1  0   5     3   2     8    12    4 22  35    5  6    2  139 7.5-12.5    0      1   0  2  0   0     3   2     4    10    3  0  11    1  1    0   38 12.5-18.5    0      0   0   0 0   0     0    1    1      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      7     31   2   3 0   5     7   5    14    24    8 23  49    9  7    3  197 Class D    Fre_g: 0.482 mph      N    NNE  NE ENE E  ESE   SE  SSE    s   SSW  SW WSW   w  WNW NW  NNW TOTAL Calm-0.95    0      0   0   0 0   0     0   0     0      0   0   0   0   0   0   0    0 0.95-3.5   16     18  15   8 10  2    11   10    9     15  16  18  28  19  14  14  223 3.5-7.5   21     31  18  11 6   30   48   32   47     73  41  86 117  42 46   31  680 7.5-12.5    1      2   0   3 0   0    28   33   16    40    5   2  17   3   0   0  150 12.5-18.5    0      0   0   0  0   2    3    7    0      0   0   0   0   0   0   0   12 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     38     51  33  22 16  34   90   82   72    128  62 106 162  64  60  45  1065 Page 55 55

Table A-1 (continued) Oct-Dec 2017 moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0.95-3.5 2 2 1 8 7 1 8 11 23 17 ' 18 35 20 8 8 2 171 3.5-7.5 0 0 0 0 3 0 21 43 25 43 58 26 5 3 4 1 232 7.5-12.5 0 0 0 0 0 0 0 7 5 5 3 1 0 0 0 0 21 12.5-18.5 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 1 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       3        2     1  8  10  2    30   61   53     65    79 62   25   11 12  3   427 moh       N      NNE    NE ENE E  ESE  SE   SSE    s   SSW    SW WSW   w  WNW NW  NNW TOTAL Calm-0.95     0        0     0  0   0  0     0    0     0     0     0   0   0    0  0  0      0 0.95-3.5    0        0     0  0   1   1    0   10    4      6     9 24    8    4  0  0     67 3.5-7.5    0        0     0  0   0  0     0    2    3     15    17  4    0    0  0  0     41 7.5-12.5    0        0     0  0   0  0     0    0    0      0     6   0   0    0  0  0      6 12.5-18.5    0        0     0  0   0  0     0    0    0      0     0   0   0    0 0   0      0 18.5-24     0        0     0  0   0  0     0    0     0     0     0   0   0    0  0  0      0
           >24      0        0     0  0   0  0     0    0     0     0     0   0   0    0  0  0      0 TOTAL       0        0     0  0   1   1    0   12    7     21    32 28    8    4  0  0   114 moh       N      NNE    NE ENE  E ESE  SE   SSE    s   SSW    SW WSW   w  WNW NW  NNW TOTAL Calm-0.95    0        0     0  0   0   0    0    0     0     0     0   0   0    0  0  0      0 0.95-3.5    0        0     0  0   0   0    0    0     0     0     7  14   0    1  0  0     22 3.5-7.5    0        0     0  0   0   0    0    0     0     1     5   0   0    0  0  0      6 7.5-12.5    0        0     0  0   0   0    0    0     0     0     3   0   0    0  0  0      3 12.5-18.5    0        0     0  0   0   0    0    0     0     0     0   0   0    0  0   0     0 18.5-24     0        0     0  0   0   0    0    0     0     0     0   0   0    0  0   0     0
           >24      0        0     0  0   0   0    0    0     0     0     0   0   0    0  0   0     0 TOTAL      0        0     0  0   0   0    0    0     0     1    15  14   0    1  0   0    31 Class All  Fre.9.: 1.000 moh      N      NNE    NE ENE  E ESE  SE   SSE    s   SSW    SW WSW   w  WNW NW  NNW TOTAL Calm-0.95    1        0     0   0  0   0    0    0     0     0     0   0   0    0  0   0     1 0.95-3.5   24       28    22  19 18   6   20   32    37    40    53  92  59   38 22  18  528 3.5-7.5   37       87    29  14 17  43   73   79    90   157   132 173 228  86  67  44  1356 7.5-12.5    1        5     0  5   0   0   35   42    34    63    23  12  58   18  3   0   299 12.5-18.5    0        0     0   0  0   2    4   11     5     1     0   0   0    0  0   0    23 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     63      120    51  38 35  52  132  164   166   261   208 277 345  142 92  62  2208 Page 56 56

Table A-1 (continued) Jan-Dec 2017 Class A Frea: 0.118 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 35 23 26 10 12 4 0 1 *o 0 1 1 5 11 9 18 156 3.5-7.5 56 67 65 53 48 17 9 3 7 9 4 32 101 111 45 21 648 7.5-12.5 4 6 1 5 0 4 11 2 18 19 5 16 50 45 16 0 202 12.5-18.5 0 0 0 0 0 0 0 2 3 3 0 0 1 0 0 0 9 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      95      96 92   68  60   25  20    8    28    31   10  49  157  167 70   39   1015 Class B    Freq: 0.053 mph       N     NNE NE  ENE   E  ESE SE   SSE    s    SSW  SW  WSW   w  WNW  NW  NNW  TOTAL Calm-0.95    0       0  0    0   0    0   0    0     0      0   0   0    0    0  0    0     0 0.95-3.5    7       8  5   12   9    2   0    0     0      0   1   0    9   10  6    5    74 3.5-7.5    6      15  9    8   6   16   8    3    15    30   22  34   40   10 10    9   241 7.5-12.5    0       8  5    3   0    0   4    2    31    36   10   6   16   11  5    0    137 12.5-18.5    0       0  0    0   0    0   0    1     1      2   0   0    0    0  0    0     4 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      31 19   23  15   18  12    6    47    68   33  40   65   31 21   14   456 I

I Class C Frea: 0.068 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 6 5 10 11 10 2 2 0 1 3 3 1 9 7 2 5 77 3.5-7.5 15 41 8 14 11 15 12 8 31 30 29 46 55 16 11 8 350

7.5-12.5 1 4 7 8 0 2 6 5 23 45 8 3 18 4 16 0 150 12.5-18.5 1 0 0 0 0 0 0 1 1 0 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     23      50 25   33  21   19  20   14    56     78  40  50   82   27 29   13    580 i

Class D Freq: 0.443 I mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1 0.95-3.5 61 79 59 90 65 35 31 35 36 47 36 35 60 40 53 44 806 3.5-7.5 70 140 66 62 103 94 121 117 261 276 162 197 275 126 112 69 2251 7.5-12.5 14 48 18 14 8 22 68 64 118 190 35 17 56 17 17 7 713 12.5-18.5 0 4 1 2 0 4 6 8 2 0 0 0 0 0 0 0 27 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     145    271 144  168 176 155 226   224  417    513 233  249 391  184 182  120  3798 Page 57 57

Table A-1 (continued) Jan-Dec 2017 mph N NNE NE ENE E ESE SE. SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 1 0 0 0 0 0 0 0 1 1 0 0 2 0 0 2 7 0.95-3.5 24 27 11 57 44 19 35 , 43 62 43 55 105 80 59 43 21 . 728 3.5-7.5 12 20 12 9 12 25 32 87 110 247 200 135 50 16 28 10 1005 7.5-12.5 1 6 0 0 2 1 12 21 8 74 18 6 6 0 0 1 156 12.5-18.5 0 0 0 0 0 0 1 1 0 10 0 0 0 0 0 0 12 18.5-24 0 0 0 b 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       38      53 23   66  58   46  80   152    181   375  273 246  138  75  71   34   1909 Class F    Fre_g: 0.075 mph        N     NNE NE  ENE   E  ESE  SE   SSE     s   SSW   SW  WSW   w  WNW  NW  NNW  TOTAL Calm-0.95      0       0  0    0   0    0   0     0      0     1    0    0   0   0   0    0      1 0.95-3.5     5       2  0    6   4    1   3    17     22    22   52   92  50  16   2    1    295 3.5-7.5     0       0  0    0   0    0   2    12     19    69  163   32   6   1   0    0    304 7.5-12.5     0       0  0    0   0    0   0     2      0    17   24    0   0   0   0    0     43 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        5       2   0   6   4    1   5    31     41   109  239  124  56  17   2    1    643 Class G    Freq:  0.020 mph        N     NNE NE  ENE   E  ESE  SE   SSE      s  SSW   SW  WSW   w  WNW  NW  NNW  TOTAL Calm-0.95     0       0   0   0   0    0   0     0      0     0    0    0   0   0   0    0      0 0.95-3.5     1       1   0   0   0    0   0     2      2     7   24   51   9   1   0    0     98 3.5-7.5     0       0   0   0   0    0   0     0      0     3   42    7   1   0   0    0     53 7.5-12.5     0       0   0   0    0   0   0     0      0     4   17    0   0   0    0    0    21 12.5-18.5     0       0   0   0   0    0   0     0      0     0    2    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        1       1   0   0   0    0   0     2      2    14   85   58  10   1   0     0   174 Class All  Fre_g: 1.000 mph        N     NNE NE  ENE    E ESE  SE   SSE      s  SSW   SW  WSW   w  WNW  NW  NNW  TOTAL Calm-0.95     1       0   0   0    0   0   0     0      1     2    0    0   2   1    0   2      9 0.95-3.5   139     145 111  186 144  63  71    98    123   122  172  285 222  144 115   94  2234 3.5-7.5   159     283 160  146 180  167 184  230    443   664  622  483 528  280 206  117  4852 7.5-12.5    20      72  31  30   10  29  101   96    198   385  117   48 146  77   54    8  1422 12.5-18.5     1       4   1   2    0   4   7    13      7    15    2    0   1   0    0    0    57 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     320     504 303  364 334 264  363  437    772   1188 913  816 899  502 375  221   8575 Page 58 58

Table A-2 Joint Frequency Distribution of Wind Directions and Speeds For the 220-ft level of the 220-ft Tower Jan-Mar 2017 Class A Fre_g: 0.142 mph N NNE NE ENE E , ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 5 2 7 5 2 1 0 0 0 0 0 0 0 1 8 3 34 7.5-12.5 2 3 6 0 3 4 0 1 0 0 0 0 1 5 7 8 40 12.5-18.5 5 2 4 5 3 0 0 0 0 0 1 10 11 18 9 2 70 18.5-24 5 2 1 1 0 0 0 0 0 0 0 0 9 29 9 6 62

        >24        6     2   0    5    0     0     0     0     0     0     0   0   5   33  24   0   75 TOTAL       23    11  18    16   8     5     0     1     0     0     1  10  26   86  57  19  281 Class B mph       N    NNE  NE   ENE   E    ESE   SE    SSE    s   SSW   SW WSW    w  WNW NW  NNW TOTAL Calm-0.95      0     0   0     0   0     0     0     0     0     0     0   0   0    0   0   0    0 0.95-3.5     0     1   0     0   0     0     0     0     0     0     0   0   0    0   0   0    1 3.5-7.5     1     0   1     2   2      0    0      0    0     0     0   1   2     0  0   1   10 7.5-12.5     2     0   0     0   1      0    2      0    0     2     2   4   2     0  0   0   15 12.5-18.5     0      1  1    2    0      1    0     0     0     4     5   7   3    4   1   1   30 18.5-24      0     0   0     0   0      0    0      0    0     2     1   2   2    6   0   1   14
         >24       1     2   2     6   3      0    0     0     0     0     0   0   3    2  11   3   33 TOTAL        4     4   4    10   6      1    2      0    0      8    8  14   12   12 12   6  103 Class C    Fre_g: 0.071 mph        N   NNE  NE   ENE   E    ESE   SE    SSE    s   SSW   SW WSW    w  WNW NW  NNW TOTAL Calm-0.95      0     0   0     0   0      0    0      0    0     0     0   0   0     0  0   0    0 0.95-3.5     0      0  1     0    0     0    0      0    0      0    0   0    0    0  0   0    1 3.5-7.5     0      0  0     0    1     5    0      1    0      0    0   2    0    0  1   0   10 7.5-12.5     1      0  0     2   0      1    0      1    0      3    1   7    3    0  0   0   19 12.5-18.5     1      0  1     2   0      3    0      0    0     7     6   6    8    0  3   0   37 18.5-24      1     0   0     8   2      0    0      1    0      1    2   3   3     5  3   2   31
         >24       2      0  1    11    2     0    0      0    0      0    0    0   1    6 16   3   42 TOTAL        5      0  3    23   5      9    0      3    0     11    9  18   15   11 23   5  140 Class D    Freq:  0.499 mph        N   NNE  NE   ENE   E    ESE   SE    SSE    s   SSW   SW WSW    w  WNW NW  NNW TOTAL Calm-0.95      0      0  0     0    0     0    0      0    0      0    0    0   0    0  0   0    0 0.95-3.5     0      1  0     0    0     1    0      0    0      0    0    0   0    0  0   0    2 3.5-7.5     3      3  4     4    4     4    7      4    1      4    5    8   3    2  0   0   56 7.5-12.5     5      5  7     9    6    12    3     11   15     23   19  19   18   11  5   2  170 12.5-18.5    11      4  4     2   13    11   10     19   13     45   48  56   67   19 22  12  356 18.5-24      5      0  2    14   29     7    4      1    1     26   34   11  27   51 30  12  254
         >24      12      7  5    16   14     1    0      0    0      3    0    0   2   34 40  17  151 TOTAL       36     20 22    45   66    36   24     35   30    101  106  94  117  117 97  43  989 Page 59 59

Table A-2 (continued) Jan-Mar 2017 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 0 .1 0 0 1 1 1 1 0 0 0 0 1 . 1 0 8 3.5-7.5 2 1 0 3 7.5-12.5 6 1 4 1 0 1 1 3

                                                . 50   1 4

1 4 3 6 4 7 2 4 1 5 0 16 7 10 2 16 29 92 12.5-18.5 1 1 3 2 3 0 3 6 10 14 35 19 21 20 12 5 155 18.5-24 0 1 0 2 1 0 0 5 0 6 13 5 8 11 7 6 65

            >24        7     1   0   0  3   1      0   0   0    1   9    0   0    2    2    2    28 TOTAL       17     8   6   4  9   8      9  17  16   30  68   30  35   50   39   31   377 Class F       Fre_g: 0.039 mph        N    NNE NE ENE  E ESE SE SSE       s SSW SW    WSW   w  WNW   NW  NNW  TOTAL Calm-0.95      0     0    0  0  0   0      0   0   0    0   0    0   0    0    0    0     0 0.95-3.5      0     0    0  1  0   0      0   0   0    1   0    0   0    0    1    1     4 3.5-7.5      2     1    1  1  0   1      0   0   2    2   1    1   1    2    3    5    23 7.5-12.5      0     0    0  0  0   0      0   0   0    1   3    0   1    2    6    3    16 12.5-18.5      0     1    0  0  0   0      0   1   2    3   3    5   2    2    3    0    22 18.5-24      0     0    0  0  0   0      0   0   0    0   9    2   0    0    0    0    11
            >24        0     0    0  0  0   0      0   0   0    1   0    0   0    0    0    0     1 TOTAL        2     2    1  2  0   1      0   1   4    8  16    8   4    6    13   9    77 Class G      F      0.008 mph        N    NNE  NE ENE E ESE SE SSE       s  SSW SW   WSW   w  WNW   NW  NNW  TOTAL Calm-0.95      0      0   0  0  0   0      0   0   0    0   0    0   0    0     0   0     0 0.95-3.5      0      0   0  0  0   0      0   0   0    0   0    0   0    0     0   0     0 3.5-7.5      0      0   0  0  0   0      0   0   0    0   0    0   0    1     0   0     1 7.5-12.5     0      0   0   0 0   0      0   0   0    1    0   1    1   1     0   0     4 12.5-18.5     0      0   0   0 0   0      0   0   0    1    1   2    3   1     0   0     8 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        0      0   0   0 0   0      0   0   0    2    3   3   4    3     0   0    15 Class All    Fre_g: 1.000 mph        N    NNE  NE ENE  E ESE SE SSE      s  SSW SW   WSW   w  WNW   NW  NNW  TOTAL Calm-0.95      0      0   0   0 0   0      0   0   0    0    0   0    0   0     0    0    0 0.95-3.5     1      2   2   1 0   2      1   1   1    1    0   0    0   1     2   1    16 3.5-7.5    13      7  14  12 10  14     7   6   4    9   10   14   7   6    19   11  163 7.5-12.5    16     12  14  11 11  20    10   17  19  36   32   35  31   35   28   29  356 12.5-18.5    18      9  13  13 19  15    13   26  25  74   99  105 115   64   50  20   678 18.5-24     11      3   3  25 32   7     4    7   1  35   61   23  49  102   49  27   439
             >24      28     12   8  38 22  2      0    0   0   5    9    0  11  77    93  25   330 TOTAL       87     45  54 100 94  60   35    57  50  160 211  177 213  285  241  113  1982 Page 60 60

Table A-2 (continued) Apr-Jun 2017 ClassA Freq: 0.131 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 1 o* 0 0 0 0 0 0 0 0 0 0 0 0 1 3.5-7.5 4 4 7 6 12 1 0 0 0 0 0 0 1 2 0 2 39 7.5-12.5 11 7 15 4 9 20 5 0 0 0 1 0 10 11 2 3 98 12.5-18.5 15 10 3 4 8 4 12 2 3 7 7 3 10 11 3 5 107 18.5-24 2 4 1 0 0 0 3 0 0 10 2 0 2 6 1 5 36

          >24      0      0  0  0   0   1   0    0     0     0    0 0   0   3  1   0     5 TOTAL      32     25 27  14 29  26  20    2     3    17   10 3  23  33  7   15  286 Cl               0.066 mph       N   NNE  NE ENE  E ESE  SE   SSE   s    SSW  SW WSW w  WNW NW  NNW TOTAL Calm-0.95     0      0  0   0  0   0   0    0     0     0    0 0   0   0  0   0     0 0.95-3.5    0      0  1   0  0   0   0    0     0     0    0 0   0   0  0   0     1 3.5-7.5    3      2  0   3  4   1   1    0     0     0    0 0   2   4  3   3    26 7.5-12.5    1      1  3   1  1   8   4    1     1     6    9 3   2   3  2   1    47 12.5-18.5    1      0  1   0  2   2   2    1     4    21    5 3   3   3  0   2    50 18.5-24     0      2  0   0  0   0   0    0     0     5    3 0   0   1  0    0   11
          >24      1      3  1   0  0   0   0    0     0     0    0 0   0   0  3    0    8 TOTAL      6      8  6   4  7  11   7    2     5    32   17 6   7  11  8    6  143 Class C    F     0.061 mph       N   NNE  NE ENE  E ESE  SE   SSE    s   SSW  SW WSW w  WNW NW  NNW TOTAL Calm-0.95     0      0  0   0  0   0   0    0     0     0    0 0   0   0  0    0    0 0.95-3.5    0      1  0   0  0   0   0    0     0     0    0 0   0   0  0    0    1 3.5-7.5    1      2  2   3  2   0   1    0     1     0    1 0   1   2  0    0   16 7.5-12.5    0      1  1   1  1   3   5    3     2     4    5 6   2   0  0    0   34 12.5-18.5    2      1  2   0  5   2   3    2     2    19    7 2   1   2  0    1   51 18.5-24    3      1  2   0  0   1   0    0     0    10    1 0   0   3  1    1   23
          >24      2      1  2   1  0   1   0    0     0     0    0 0   0   0  2    0    9 TOTAL      8      7  9   5  8   7   9    5     5    33   14 8   4   7  3    2  134 Class D    F     0.415 mph      N    NNE NE ENE  E ESE  SE   SSE    s   SSW  SW WSW w  WNW NW  NNW TOTAL Calm-0.95     0      0  0   0  0   0   0    0     0     0    0 0   0   0  0    0    0 0.95-3.5    2      0  7   5  3   0   2    0     1     0    0 0   0   0  1    0   21 3.5-7.5   12      7  8  10  7   6    8   13   13     10   3  1  0   2  2    6  108 7.5-12.5    7     21 13  14  9   9   23   28   35     35  16 4   8   2  12  14  250 12.5-18.5   19      5 10  14 21  10   15   10   14     98  40 13 23   6   6  10  314 18.5-24    3      2  6   8 16  17    9    3    1     37  28  0  4   7   5  13   159
          >24      8      3  2   7 10   5    1    0    1      0   2  0  0   8   3   4    54 TOTAL     51     38 46  58 66  47   58   54   65    180  89 18 35  25  29  47   906

Page 61 61

Table A-2 (continued) Apr-Jun 2017 Cl ass E Frea: 0 223 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 2 1 3 4 0 1 1 1 3 1 1 1 0 0 0 19 3.5-7.5 6 3 3 7 2 3 4 3 2 5 2 2 2 2 3 3 52 7.5-12.5 3 2 2 3 0 0 15 7 11 11 4 4 13 13 6 3 97 12.5-18.5 4 2 1 2 3 4 13 14 7 26 39 15 28 13 6 5 182 18.5-24 2 6 0 0 0 0 5 3 0 19 46 0 10 8 2 3 104

             >24       0      0  0  0   0    0    0     1    0  13    12  0  1    1   3   1   32 TOTAL      15     15  7  15  9   7    38    29   21  77   104 22 55   37  20  15  486 Class F       Freq: 0.082 mph        N    NNE NE ENE  E  ESE SE     SSE    s SSW SW WSW    w  WNW NW  NNW TOTAL Calm-0.95      0     0  0   0  0    0    0     0    0   0     0  0  0    0   0   0    0 0.95-3.5      1     1  1  2   0    0    2     0    1   1     0  0  0    0   0   0    9 3.5-7.5     4      0  0  0   1   2     2     1    1   0     0  0  0    1   1   1   14 7.5-12.5      1     1  0  0   0    1    1     1    0   4     4 4   5    2   7  2    33 12.5-18.5     0     2   0   0  0    0    0     4    4   5     6 14 22   15   5  4    81 18.5-24      0     0  0   0  0    0    0     0    0   5    14  7  3    0   1  2    32
             >24        0     0  0   0  0    0    0     0    0   0     9  0  0    1   0   0   10 TOTAL        6     4  1  2   1    3    5     6    6  15    33 25 30   19  14   9  179 Cl ass G      Freq: 0 022 mph         N   NNE NE ENE  E  ESE SE     SSE    s SSW SW WSW    w  WNW NW  NNW TOTAL Calm-0.95      0     0  0   0  0    0    0     0    0   0     0  0  0    0   0   0    0 0.95-3.5      0     0  0   0  0    0    0     1    0   0     0  0  0    0   0   0    1 3.5-7.5      1     0  0   0  0    0    0     0    1   1     3  1  0    0   0   0    7 7.5-12.5      0     0  0   0  0    0    0     0    0    1    3  2  2    3   2   0   13 12.5-18.5     0     0  1   0  0    0    0     0    0    1    2  3  6    2   1   0   16 18.5-24      0     1  0   0  0    0    0     0    0    0    5  4  0    0   0   0   10
             >24        0     0  0   0  0    0    0     0    0    0    0  1  0    0   0   0    1 TOTAL        1     1  1   0  0    0    0     1    1   3    13 11  8    5   3   0   48 Class All     Freq: 1.000 mph        N   NNE NE ENE  E  ESE   SE   SSE    s SSW SW WSW    w  WNW NW  NNW TOTAL Calm-0.95      0     0  0   0  0    0    0     0    0    0    0  0   0   0   0   0    0 0.95-3.5      3     4 11  10  7    0    5     2    3   4     1  1   1   0   1   0   53 3.5-7.5     31    18 20  29 28   13    16   17   18   16    9  4   6  13   9  15  262 7.5-12.5     23    33 34  23 20   41   53    40

49 61 42 23 42 34 31 23 572 12.5-18.5 41 20 18 20 39 22 45 33 34 177 106 53 93 52 21 27 801 18.5-24 10 16 9 8 16 18 17 6 1 86 99 11 19 25 10 24 375

             >24       11     7  5   8  10   7     1    1    1   13   23  1   1  13  12   5  119 TOTAL      119    98 97  98 120 101   137   99  106  357  280 93 162  137 84  94  2182 Page 62 62

Table A-2 (continued) Jul-Sep 2017 Cl ass A Freq: O 087 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 6 7 7 4 4 2 2 0 0 2 1 0 1 0 4 2 42 7.5-12.5 14 8 8 2 2 10 5 1 2 7 1 0 9 7 2 4 82 12.5-18.5 9 5 1 4 3 0 0 1 4 0 0 0 0 10 2 9 48 18.5-24 8 2 0 1 1 0 0 0 0 0 0 0 0 3 1 3 19

          >24      0     0    0   0  0   0   0    0     0     0   0   0   0   0  0   0     0 TOTAL      37    22   16  11 10  12   7    2    6      9   2   0  10  20  9   18  191 Class B    Freq: 0.044 mph       N   NNE   NE ENE E  ESE  SE   SSE   s    SSW  SW  WSW w  WNW NW  NNW TOTAL Calm-0.95     0     0    0   0  0   0   0    0     0     0   0   0   0   0  0    0    0 0.95-3.5    0     0    0   0  0   0   0    0     0     0   0   0   0   0  0    0    0 3.5-7.5    2     1    3   2  3   1   0    0     0     1   0   1  2    1  2    1   20 7.5-12.5    2     0    1   1  0   4   2    1     3     8   3   3   9   3  2   1    43 12.5-18.5    0     0    0   1  0   0   0    0     4    19    1  0  4    0  0    1   30 18.5-24     0     0    0   1  0   0   0    0     0      1  0   0   0   0  0    0    2
          >24      0     0    0   0  0   0   0    0     0     0   0   0   0   0  0   2     2 TOTAL      4     1    4   5  3   5   2    1     7    29   4   4  15   4  4    5   97 Cl ass C   Freq: O.0 50 mph      N   NNE   NE ENE E  ESE  SE   SSE   s    SSW  SW  WSW w  WNW NW  NNW TOTAL Calm-0.95     0     0    0   0  0   0   0    0     0     0   0   0   0   0  0    0    0 0.95-3.5    0     0    1   0  0   0   0    0     0     0   0   0   0   0  0    0    1 3.5-7.5    1     4    1   0  5   2   0    0     0     2    1  3   0   4  2    1   26 7.5-12.5    2      0   0   2  1   3    5   0    12      3  10  3   4   1  0    1   47 12.5-18.5    1     2    1   0  0   0    0   1     4     11   1  0   3   3  0    1   28 18.5-24     1      3   0   0  0   0    0   0     0      1   0  0   0   0  1    0    6
          >24      0      0   0   0  0   0    0   0     0      0   0  0   0   0  0    1    1 TOTAL      5      9   3   2  6   5    5   1    16     17  12  6   7   8  3    4  109 Class D    Freq: 0.377 mph      N   NNE   NE ENE  E ESE  SE   SSE    s   SSW  SW  WSW w  WNW NW  NNW TOTAL Calm-0.95     0      0   0   0  0   0    0    0    0      0   0  0   0   0  0    0    0 0.95-3.5    1      7   6   3  8   2    0    0    1      2   3  3   0   0  1    2   39 3.5-7.5    7      2   7  10 15  25   21    6    4     12   7  5   2   5  1    6  135 7.5-12.5    3      4  18  17  2  16   14   10   29     68  35  14  9   4  7    4  254 12.5-18.5    6      9  10   2  7   7    2    2   20    101  36  3  11   4  7    4  231 18.5-24   13     22   3   1  1   3    3    0    0     24   3  0   2   0  2    5   82
          >24     28     47   1   1  0   4    0    0    0      0   0  0   0   0  0    7   88 TOTAL      58    91  45  34 33  57   40   18   54    207  84  25 24  13  18  28   829 Page 63 63

Table A-2 (continued) Jul-Sep 2017 moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 4 1 0 2 6 3 2 1 2 1 ' 2 1 1 2 1 1 30 3.5-7.5 2 5 1 1 3 23 19 11 4 10 6 2 3 4 3 5 102 7.5-12.5 3 3 7 3 4 9 4 6 14 26 12 7 10 14 10 10 142 12.5-18.5 0 4 1 1 4 3 5 1 10 48 69 36 21 8 11 14 236 18.5-24 7 5 3 4 2 0 0 0 1 19 25 4 3 2 4 9 88

             >24       3      6  1  2   2   0    0    0   0    2      3   0   0    0   0   2    21 TOTAL       19     24 13  13 21  38   30   19  31   106   117  50  38   30  29  41   619 Class F      Fre_g: 0.124 mph        N    NNE NE ENE  E ESE   SE SSE    s  SSW    SW  WSW  w   WNW  NW NNW  TOTAL Calm-0.95     0      0  0   0  0   0    0    0   0     0     0   0   0    0   0   0      0 0.95-3.5     1      1  0   1  0   0    3    0   1     0    4    0   0    0   0   1    12 3.5-7.5     4      1  0   1  1   3    0    3   3    5      1   3   2    0   3   0    30 7.5-12.5     1      0  0   1  2   2    1    3   6    5     4    6   7    8  23  13    82 12.5-18.5     0      0  0   0  0   0    5    6   4    12    18  29  13   25   3   3   118 18.5-24      0      0  0   0  0   0    0    0   0     1    26   1   3    0   0   0    31
             >24       0      0  0   0  0   0    0    0   0     0     0   0   0    0   0   0      0 TOTAL        6      2  0   3  3   5    9   12  14   23     53  39  25   33  29  17   273 Class G      F      0 moh        N    NNE NE ENE  E ESE   SE SSE    s  SSW    SW  WSW  w   WNW  NW NNW  TOTAL Calm-0.95     0      0  0   0  0   0    0    0   0     0     0   0   0    0   0   0      0 0.95-3.5     2      0  1   0  2   1    1    0   0     0     1   0   0    0   0    1     9 3.5-7.5     2      2  4   3  1   0    0    1   1    2     4    2   0    0   1   4    27 7.5-12.5     2      1  0   0  0   0    0    1   1     3    10   3   2    5   3   3     34 12.5-18.5     0      0  0   0  0   0    0    0   0     0     2   1   2    4   0   0      9 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        6      3  5   3  3   1    1    2   2     5    18   6   4    9   4   8     80 Class All   Fre_g: 1.000 mph        N    NNE NE ENE  E ESE   SE  SSE   s  SSW    SW  WSW   w  WNW  NW NNW  TOTAL Calm-0.95     0      0  0   0  0   0    0    0   0     0     0   0   0    0   0   0      0 0.95-3.5     8      9  8   6 16   6    6    1   4     3    10   4   1    2   2   5     91 3.5-7.5    24     22 23  21 32  56   42   21   12   34    20   16  10   14 16   19   382 7.5-12.5    27     16 34  26 11  44   31   22  67   120    75  36  50   42  47  36    684 12.5-18.5    16     20 13   8 14  10   12   11  46   191   127  69  54   54  23  32    700 18.5-24     29     32  6   7  4   3    3    0   1    46    55   5   8    5   8   17  229
             >24      31     53  2   3  2   4    0    0   0     2     3   0   0    0   0   12   112 TOTAL      135   152 86  71 79 123   94   55  130  396   290  130 123  117 96  121  2198 Page 64 64

Table A-2 (continued) Oct-Dec 2017 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 ' 0 0 0 0 0 0 0 0 0 3.5-7.5 1 5 3 0 2 0 0 0 0 0 0 0 0 0 0 0 11 7.5-12.5 3 6 2 3 2 4 0 0 1 2 0 5 10 8 4 1 51 12.5-18.5 6 3 8 0 3 5 0 0 0 4 3 3 29 17 4 6 91 18.5-24 0 1 1 0 0 0 1 0 1 4 3 2 17 18 9 4 61

          >24        0       5    0  0  0   0     0   0    3      3    0  0  6   19  8    0   44 TOTAL       10      20   14  3  7   9     1   0    5     13    6 10 62   62 25   11  258 mph        N     NNE   NE ENE E  ESE  SE   SSE   s    SSW  SW WSW  w  WNW NW  NNW TOTAL Calm-0.95      0       0    0  0  0   0     0   0     0     0    0  0  0    0  0    0    0 0.95-3.5      0       0    0  0  0   0     0   0     0     0    0  0  0    0  0    0    0 3.5-7.5      0       0    0  0  1   1     0   0     0     0    1  0  0    0  0    0    3 7.5-12.5       1       1   0  0  0   2     1   0     3     6    0 6   3    0  2    1   26 12.5-18.5       5      3    3  0  0   2     2   0     1     2   11 4  10    6  2    1   52 18.5-24       0       2   0  0  0   0     1   0     1     4    1  0  2   12  0    3   26
           >24        1       1   0  0  0   0     0   0     0     0    0  0   1   3  3    0    9 TOTAL         7      7    3  0  1   5     4   0     5    12   13 10 16   21  7    5  116 mph        N     NNE   NE ENE E  ESE   SE  SSE   s    SSW  SW WSW  w  WNW NW  NNW TOTAL Calm-0.95       0       0   0  0  0   0     0   0     0     0    0  0   0   0  0    0    0 0.95-3.5       0       0   1  0  0   1     0   0     0     0    1  0   0   0  0    0    3 3.5-7.5       0       1   1  0  0   0     0   3     1      1   0  0   1   1  2    0   11 7.5-12.5       2       1   3  0  0   2     1   0     5     2    2  2  4    1  1    0   26 12.5-18.5      3      11   2  0   1  3     1   0     2     9    9  7 22    8  2    2   82 18.5-24       1       7   1  2  0   0     2   4     0     5    3  0  10  16  1    4   56
           >24        1       2   0  2  0   0     0   0     1     0    0  0   3   5  4    1   19 TOTAL         7      22   8  4   1  6     4   7     9     17  15  9 40   31 10    7  197 Class D     Freq: 0.482 mph         N    NNE   NE ENE E  ESE   SE  SSE   s    SSW  SW WSW  w  WNW NW  NNW TOTAL Calm-0.95       0       0   0  0   0  0     0    0    0      0   0  0   0   0   0   0    0 0.95-3.5      3       2   3  2   1  1     0    1    0     2    3  0   0   1   0   2   21 3.5-7.5      2       6   7  3  4   4     5   6     5      3   5  6   7   3  7    8   81 7.5-12.5     13      13   9  6  7   8    21   18   14    22   17 30  20  24  19  18  259 12.5-18.5      8       8   8  15  3  13   34   20   14    60   61 45  74  34 22   15  434 18.5-24       9       5   6  7  13  2     8   20    7     23  18  8  23  21 21   26  217
           >24        7       1   1  3   0  6     1    0    0      0   0  0   2  12  2   17   52 TOTAL        42      35  34  36 28  34   69   65   40    110 104 89 126  95 71   86  1064 Page 65 65

Table A-2 (continued) Oct-Dec 2017 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 3 2 1 1 4 0 1 1 0 1 1 2 2 4 1 25

3.5-7.5 4 1 1 4 3 8 6 4 0 3 7 6 8 8 6 4 73 7.5-12.5 0 1 0 0 2 2 16 14 9 8 6 9 6 15 9 2 99 12.5-18.5 1 0 0 1 2 0 15 27 16 21 32 40 11 8 3 0 177 18.5-24 0 0 0 0 1 0 0 6 0 4 21 5 2 3 2 2 46

          >24       0       0    0  0   0    1    0    1    0     0    0  0    0    1   2    2     7 TOTAL       6       5    3  6   9   15   37   53   26    36  67  61  29   37  26    11  427 mph       N      NNE  NE ENE  E  ESE  SE   SSE   s    SSW  SW WSW   w  WNW NW   NNW  TOTAL Calm-0.95     0       0    0   0  0    0    0    0    0      0   0  0    0    0   0    0     0 0.95-3.5     3       0    1   1  0    0    0    0    0     2    0  0    0    1   0    2    10 3.5-7.5     0       0    0   1  2    1    1    1    3      1   1  2    2    1  4     0    20 7.5-12.5     0       0    0   0  4    2    6    0    3      1   1  0    1    5   4    1    28 12.5-18.5     0       0    0   0  0    0    0    1    2     2   12  8    1    6   6    1   39 18.5-24     0       0    0   0  0    0    0    0    0      0  13  4    0    0   0    0    17
          >24       0       0    0   0  0    0    0    0    0      0   0  0    0    0   0    0     0 TOTAL       3       0    1  2 , 6    3    7    2    8     6   27 14    4   13  14   4   114 mph       N      NNE  NE ENE  E  ESE   SE  SSE   s    SSW  SW WSW   w  WNW NW   NNW  TOTAL Calm-0.95      0      0    0   0  0    0    0    0    0      0   0  0    0    0   0    0     0 0.95-3.5      0      0    0   0   1   0    0    0    0      0   0  0    0    0   0    0     1 3.5-7.5      1      0    0   0  2    0    1    0    0      0   1  2    2    0   1    1    11 7.5-12.5      0      0    0   0  0    0    0    0    0      0   1  0    3    1   4    1    10 12.5-18.5     0       0   0   0  0    0    0    0    0      0   1  3    0    3   2    0     9 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   0   0  3    0    1    0    0      0   3   5   5    4   7    2    31 Class All  Fre_g: 1.000 moh       N      NNE  NE ENE  E  ESE   SE  SSE    s   SSW  SW WSW   w  WNW NW   NNW  TOTAL Calm-0.95      0       0   0   0  0    0    0    0    0      0   0   0   0    0   0    0     0 0.95-3.5     7       5   7   4  3    6    0    2    1      4   5   1   2    4   4    5    60 3.5-7.5     8      13  12   8  14  14   13   14    9      8  15  16  20   13  20   13  210 7.5-12.5    19      22  14   9  15  20   45   32   35    41   27  52  47   54  43   24  499 12.5-18.5    23      25  21  16   9  23   52   48   35     98 129 110 147   82  41   25  884 18.5-24     10      15   8   9  14   2   12   30    9    40   59  19  54   70  33   39  423
           >24       9       9   1   5   0   7    1    1    4      3   0   0  12   40  19   20   131 TOTAL       76      89  63  51  55  72  123  127   93    194 235 198 282  263 160  126  2207 Page 66 66

Table A-2 (continued) Jan-Dec 2017 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 1 0 o* 0 0 0 0 0 0 0 0 0 d 0 1 3.5-7.5 16 18 24 15 20 4 2 0 0 2 1 0 2 3 12 7 126 7.5-12.5 30 24 31 9 16 38 10 2 3 9 2 5 30 31 15 16 271 12.5-18.5 35 20 16 13 17 9 12 3 7 11 11 16 50 56 18 22 316 18.5-24 15 9 3 2 1 0 4 0 1 14 5 2 28 56 20 18 178

    >24      6       7  0. 5   0    1    0    0    3      3    0   0   11   55 33    0   124 TOTAL      102     78 75   44  54   52   28    5    14    39   19  23  121  201 98   63   1016 Class B    Freg: 0.054 mph        N    NNE NE  ENE   E  ESE  SE   SSE    s    SSW  SW  WSW   w  WNW  NW  NNW  TOTAL Calm-0.95      0      0  0    0   0    0    0    0     0     0    0   0    0    0  0    0      0 0.95-3.5     0      1  1    0   0    0    0    0     0     0    0   0    0    0  0    0      2 3.5-7.5     6      3  4    7  10    3    1    0     0      1   1   2    6    5  5    5    59 7.5-12.5     6      2  4    2   2   14    9    2     7    22   14  16   16    6  6    3    131 12.5-18.5     6      4  5    3   2    5    4    1     9    46   22  14   20   13  3    5    162 18.5-24      0      4  0    1   0    0    1    0     1    12    5   2    4   19  0    4    53
    >24       3      6  3    6   3    0    0    0     0     0    0   0    4    5 17    5    52 TOTAL       21     20 17   19  17   22   15    3    17    81   42  34   50   48 31   22   459 Class C    Freq: 0.068 mph       N    NNE NE  ENE   E  ESE  SE   SSE    s    SSW  SW  WSW   w  WNW  NW  NNW  TOTAL Calm-0.95     0      0  0    0   0    0    0    0     0      0   0    0   0    0  0    0      0 0.95-3.5     0      1  3    0   0    1    0    0     0      0   1    0   0    0  0    0      6 3.5-7.5     2      7  4    3   8    7    1    4     2      3   2   5    2    7  5     1    63 7.5-12.5     5      2  4    5   2    9   11    4    19     12  18  18   13    2   1    1   126 12.5-18.5     7     14  6    2   6    8    4    3     8    46   23  15   34   13  5    4    198 18.5-24      6     11  3   10   2    1    2    5     0     17   6   3   13   24  6    7    116
    >24       5      3  3   14   2*   1    0    0     1      0   0    0   4   11 22    5     71 TOTAL      25     38 23   34  20   27   18    16   30     78  50  41   66   57 39    18   580 Class D    Freg: 0.442 mph       N    NNE NE  ENE   E  ESE  SE   SSE     s   SSW  SW  WSW   w  WNW  NW  NNW  TOTAL Calm-0.95     0      0  0    0   0    0    0     0    0      0   0    0   0    0   0    0     0 0.95-3.5     6     10 16    10 12    4    2     1    2      4   6    3   0    1   2    4    83 3.5-7.5    24     18 26   27  30   39   41   29    23     29  20   20  12   12  10  20    380 7.5-12.5    28     43 47   46  24   45   61   67    93    148  87   67  55   41  43   38   933 12.5-18.5    44     26 32   33  44   41   61   51    61    304 185  117 175   63  57  41   1335 18.5-24     30     29 17   30  59   29   24   24     9    110  83   19  56   79  58  56    712
    >24      55     58  9   27  24   16    2     0    1      3   2    0   4   54  45  45    345 TOTAL     187    184 147  173 193 174  191   172  189    598 383  226 302  250 215  204  3788 Page 67 67

Table A-2 (continued) Jan-Dec 2017 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 6 6 4 6 11 8 4 4 5 4 4 3 4 5 6 2 82 3.5-7.5 14 *10 6 12 9 37 29 19 7 21 19 12 14 14 19 14 256 7.5-12.5 12 10 10 6 7 14 40 31 38 51 29 24 34 58 35 31 430 12.5-18.5 6 7 5 6 12 7 36 48 43 109 175 110 81 49 32 24 750 18.5-24 9 12 3 6 4 0 5 14 1 48 105 14 23 24 15 20 303

      >24     10       7  1    2   5    2     0    2    0    16  24     0   1   4    7   7    88 TOTAL      57      52 29   38  48   68   114  118   94   249 356   163 157  154 114  98   1909 Class F      F     0.075 mph       N    NNE  NE  ENE   E  ESE   SE   SSE    s  SSW  SW   WSW   w  WNW  NW  NNW  TOTAL Calm-0.95    0       0  0    0   0    0     0    0    0     0   0     0   0    0   0    0     0 0.95-3.5    5       2  2    5   0    0     5    0    2     4   4     0   0    1   1   4     35 3.5-7.5   10       2  1    3   4    7     3    5    9     8   3     6   5   4   11   6     87 7.5-12.5    2       1  0    1   6    5     8    4    9    11  12    10  14   17 40   19    159 12.5-18.5    0       3  0    0   0    0     5   12   12    22  39    56 38   48   17    8  260 18.5-24     0       0  0    0   0    0     0    0    0     6  62    14   6    0   1   2     91
      >24      0       0  0    0   0    0     0    0    0     1   9     0   0    1   0    0    11 TOTAL      17       8  3    9  10   12    21   21   32    52 129    86 63   71  70   39   643 Class G      F     0.020 mph      N    NNE  NE  ENE   E  ESE   SE   SSE    s  SSW  SW   WSW   w  WNW  NW  NNW  TOTAL Calm-0.95     0      0   0   0   0    0     0    0    0     0   0     0   0    0   0    0     0 0.95-3.5    2       0   1   0   3    1     1    1    0     0   1     0   0    0   0    1    11 3.5-7.5    4       2  4    3   3    0     1    1    2     3   8     5   2    1   2    5    46 7.5-12.5    2       1   0   0   0    0     0    1    1     5  14     6   8   10   9   4     61 12.5-18.5    0       0  1    0   0    0     0    0    0     2   6     9  11   10   3    0    42 18.5-24     0       1   0   0   0    0     0    0    0     0   8     4   0    0   0    0    13
      >24      0       0   0   0   0    0     0    0    0     0   0     1   0    0   0    0     1 TOTAL       8      4   6   3   6    1     2    3    3    10  37    25  21   21  14   10   174 Class All    F     1.000 mph       N   NNE  NE  ENE   E  ESE   SE   SSE    s  SSW  SW   WSW   w  WNW  NW  NNW  TOTAL Calm-0.95     0      0   0   0   0    0     0    0    0     0   0     0   0    0   0    0     0 0.95-3.5    19     20 28   21  26   14    12    6    9    12  16     6   4    7   9   11   220 3.5-7.5    76     60 69   70  84   97    78   58   43    67  54    50  43   46  64   58  1017 7.5-12.5   85      83  96  69  57  125   139  111  170   258 176   146 170  165 149  112  2111 12.5-18.5   98      74 65   57  81   70   122  118  140   540 461   337 409  252 135  104  3063 18.5-24    60      66 26   49  66   30    36   43   12   207 274    58 130  202 100  107  1466
      >24      79     81  16  54   34  20     2    2    5    23  35     1  24  130 124   62   692 TOTAL     417    384 300  320 348 356   389  338  379  1107 1016  598 780  802 581  454  8569 Page 68 68

APPENDIX B Results of Onsite Groundwater Monitoring Program In response to the Nuclear Energy Institute (NEI) Groundwater Protection Initiative, Pilgrim Station instituted a groundwater monitoring program during 2007. Four monitoring wells were installed inside the protected area fence during the fourth quarter of 2007. The first samples were collected in November 2007. Since these are onsite wells, they are not considered part of the Radiological Environmental Monitoring Program (REMP), and data from these wells are being reported in the annual Radiological Effluent Release Report. Two pre-existing wells were incorporated into the groundwater monitoring program in early 2008. Additional wells were added to the program in 201 O (12 wells), 2011 (2 wells), 2012 (1 well), 2013 (3 wells), and 2014 (1 well). A total of 23 wells are being sampled on a routine basis. In addition to sampling the onsite monitoring wells, samples of surface water are collected from a location in the PNPS Intake Canal. These locations are along the shoreline in the same direction as the groundwater flow gradient. All samples collected are analyzed for tritium, a radioactive isotope of hydrogen, and also for gamma emitting radionuclides. In accordance with industry practice established under the NEI initiative, lower limits of detection (LLDs) used for analysis of REMP samples were used when assessing these samples for the presence of radioactivity. Low levels of tritium were detected in many of the onsite wells. Although gamma spectroscopy indicated the presence of naturally-occurring radioactivity, such as Potassium-40 and radon daughters from the uranium/thorium decay chains, there was no indication of any plant-related radioactivity in the groundwater samples, other than tritium. Such levels of natural radioactivity are expected as these radionuclides are dissolved into the groundwater from the rocks and soil. The fact that these low levels of naturally-occurring radioactivity can be detected demonstrates the ability of the gamma spectroscopy analyses to detect radioactivity in groundwater. Analyses are also performed for hard-to-detect radionuclides, including lron-55, Nickel-63, Strontium-89, and Strontium-90 on a less frequent basis. These hard-to-detect radionuclides were also non-detectable in all of the wells sampled and analyzed during 2017. A summary of the results of the tritium analyses conducted in 2017 are presented in the following table. In this table, a value of "NOA < xx" in the columns. indicates that no activity was detected in the sample when analyzed to the minimum-detectable level following the "<" sign. For example, the sample collected from MW201 on 6-Feb-2017 contained no detectable tritium, and a minimum detectable concentration of 281 pCi/L was achieved on that sample. The achieved sensitivity of 281 pCi/L is well below the required REMP LLD of 3000 pCi/L, and no tritium was detected even when counted to this more sensitive level of detection. No plant-related radioactivity (other than tritium) was detected in any of the monitoring wells, and no tritium or plant-related radioactivity was detected in surface water samples collected from the intake canal. Page 69 69

Number of Minimum Maximum Installation Number of Monitoring Well ID Positive Concentration Concentration Date Samples Results pCi/L pCi/L MW201 Nov-2007 4 2 NDA < 281 331 MW202 Nov-2007 4 4 432 839 MW202-I Apr-2010 4 0 NDA < 277 NDA<290 MW203 Nov-2007 Well decommissioned in 2013 during construction of ISFSI pad MW204 Nov-2007 4 4 318 433 MW205 Apr-2010 4 3 NDA<306 793 MW206 Apr-2010 16 5 NDA < 259 750 MW207 Apr-2010 4 1 NDA < 277 339 MW208-S Apr-2010 4 0 NDA < 275 NDA < 307 MW208-I Apr-2010 4 0 NDA < 278 NDA < 309 MW209 Aug-2010 4 4 528 731 MW210 Aug-2010 12 12 549 1190 MW211 Aug-2010 5 5 1230 1740 MW212 Aug-2010 4 4 435 688 MW213 Aug-2010 4 3 NDA < 311 389 MW214 Aug-2010 4 0 NDA < 278 NDA < 330 MW215 Dec-2011 18 17 781 1410 MW216 Sep-2012 17 17 659 3860 MW217 Dec-2011 4 4 359 959 MW218 Nov-2013 18 17 1640 3770 MW219 Dec-2013 7 7 909 6030 MW220 Dec-2014 4 4 331 1040 MW3 Jul-1987 4 0 NDA < 275 NDA < 307 MW4 Jul-1997 Well decommissioned in 2013 during installation of MW4R MW4-R Nov-2013 4 0 NDA < 259 NDA < 330 All Wells -- 157 113 NDA < 259 6030 Intake Canal West -- 50 0 NDA < 229 NDA < 346 Intake Canal East -- Discontinued sampling in 2016 for sampling safety concerns Concentrations of tritium detected in the onsite wells ranged from non-detectable at less than 229 pCi/L, up to a maximum concentration of 6030 pCi/L. The average concentrations from these onsite wells are well below the voluntary communication reporting level of 20,000 pCi/L as established by the EPA Drinking Water Standard. Although the EPA Standard provides a baseline for comparison, no drinking water sources are affected by this tritium. All of the affected wells are onsite, and the general groundwater flow pathway is under Pilgrim Station and out into the salt water of Cape Cod Bay. As such, there is no potential to influence any off-site drinking water wells. Even if worst-case assumptions were made and the water from monitoring well MW218 (average concentration= 3545 pCi/L) was consumed as drinking water for an entire year, the maximum dose consequence would be less than 0.31 mrem/yr. In actuality, any dose consequence would be much less than this, as any tritium-laden water potentially leaving the site would be diluted into the seawater of Cape Cod Bay before being incorporated into any ingestion pathways. No drinking water ingestion pathway exists at the Pilgrim Station site. Page 70 70

Although there are no indications that the groundwater containing detectable tritium is actually migrating offsite, a bounding calculation was performed to assess the potential dose impact of such a scenario. Based on the tritium concentrations detected during 2017, the annual average concentrations of tritium in groundwater in the four monitoring wells most closely adjacent to the shoreline (MW204, MW205, MW202, and MW201) were used to estimate potential tritium migration into the intake bay. Hydrological characteristics of the compacted backfill in the vicinity of these wells. were measured in 201 O and indicate the hydraulic conductivity ranges from 0.002 cm/sec to approximately 0.006 cm/sec. When coupled with the hydraulic slope of 0.014 and average porosity of 0.3, the flow velocity was calculated as being between 0.08 and 0.23 meters per day. Using an assumed horizontal shoreline interface area 236 meters long by 3 meters deep that could potentially transmit groundwater into the intake bay, the annual discharge of groundwater would be approximately 12.5 million Liters of water per year. Assuming this volume of 12.5 million liters contained the segment-weighted average concentration of 468 pCi/L, the annual discharge of tritium , into the intake bay under this hypothetical scenario would be 0.00585 Curies. This activity represents less than 0.009% of the annual airborne effluent of tritium released frc;,m the reactor building vent (see Table 2.2-C). Such airborne effluents can be washed down to the ground surface during precipitation events and infiltrate into the ground, thereby introducing tritium into the groundwater. In the hypothetical scenario described above, the 0.00585 Curies of tritium entering the intake bay would be further diluted into the circulating water flow of the plant. As documented in Table 2.3-A, the total volume of circulating water flow during 2017 was 563 billion Liters, yielding an effective concentration of tritium in the intake bay of approximately 0.0068 pCi/L. Such a concentration would be well below the detection sensitivity of approximately 450 pCi/L used to analyze water collected from the discharge canal as part of the radiological environmental monitoring program (REMP). The calculated dose to the maximum-exposed member of the public from such a hypothetical release would be 0.0000000039 millirem, resulting from ingestion of tritium incorporated into fish and shellfish. Since the tritium would be incorporated into seawater, there is no drinking water ingestion pathway in the described scenario. The following table lists the hydrological characteristics in the vicinity of each of the monitoring wells used to estimate tritium migration. Predicted flow velocities, annual discharge volumes, average tritium concentrations, and hypothetical tritium discharges are listed for each shoreline segment represented by each monitoring well. Page 71 71

Shoreline Segment Number 1 2 3 4 Monitoring Well Number MW204 MW205 MW202 MW201 Hydraulic Conductivity - cm/sec 1.99E-03 4.27E-03 3.13E-03 5.64E-03 Hydraulic Slope 0.014 0.014 0.014 0.014 Porosity 0.300 0.300 0.300 0.300 Flow Velocity - m/day 8.02E-02 1.72E-01 1.26E-01 2.27E-01 Flow Velocity - ft/yr 9.61E+01 2.06E+02 1.51E+02 2.72E+02 Length of Shoreline Segment - m 61.0 38.1 45.7 91.4 [Thickness of Water Layer - m 3.0 3.0 3.0 3.0 3

  !Volumetric Discharge - m /day                    4.40E+OO   5.90E+OO      5.19E+OO  1.87E+01
  !Volumetric Discharge - Liter/yr                  1.61E+06   2.16E+06      1.90E+06  6.84E+06
  !Annual Average H-3 Concentration - pCi/L         3.73E+02   4.86E+02      5.58E+02  1.62E+02
  !Annual Segment Tritium Discharge - Ci/yr         6.00E-04   1.05E-03      1.06E-03  1.11 E-03

[Total Volumetric Discharge - L/vr 1.25E+07 [Total H-3 Discharge - Ci/yr 3.81E-03

  !Annual Circulating Water Flow - Liter/yr                            5.63E+11 Discharge Canal H-3 Concentration - Ci/L                            6.77E-15 Discharge Canal H-3 Concentration - pCi/L                           6.77E-03 Max. lndiv. Dose Factor - mrem/yr per Ci/L                          5.73E+05 Maximum Individual Dose - mrem/yr                                   3.88E-09 In conclusion, the only radionuclide detected in groundwater during the 2017 monitoring effort that is attributable to Pilgrim Station operations is tritium. Although some soil samples near the separation in the underground discharge line from the neutralizing sump indicated the presence of low-level gamma radioactivity, such activity has not been detected in the groundwater and indicates the radioactivity is immobile and confined to the soil. Even in the case of the three reportable events that occurred in 2013 and subsequent sample results in 2016, the total dose impact to a maximally-exposed member of the public would have been much less than 1 mrem/yr.

Page 72 72

APPENDIX C CORRECTIONS TO PREVIOUS EFFLUENT REPORTS There were no corrections made to previous effluent reports during calendar-year 2017. Page 73 73

APPENDIX D CHANGES TO PNPS OFFSITE DOSE CALCULATION MANUAL A revision was made to the PNPS Offsite Dose Calculation Manual (ODCM) during calendar year 2017. ODCM changes were approved on 06-JUN-2017 and affect page iii; page 3/4-18; pages 3/4-30, 3/4-34 through 3/4-36 and page 11-1. Changes include:

Modify Page iii to denote new revision number
Modify Table 4.3-1 to indicate Turbine Building and Feed Pump GEMS utilize beta-sensitive detectors for gross noble gas measurement
Modify Table 3.5-2, Figure 3.5-1, and Figure 3.5-2 to indicate location of ISFSI Pad and addition of three TLDs for ISFSI direct radiation monitoring
Clarify wording in section 11.0 regarding laboratory analysis of REMP samples and REMP TLDs Page 74 74

PNPS-ODCM Rev. 11 PILGRIM NUCLEAR POWER STATION OFFSITE DOSE CALCULATION MANUAL APPROVED BY:

                   ~~1y~~-- ~~~~ -/7 DEP                  T'1NT M         GER       ff(Pi'h)

APPROVED BY: L. ~. 121t 1~ ~: L_ l~ l, rz-/17 RADIATIQ(\! Date PROTECTION MANAGER REVIEWED BY: uf). ~ \

                       *:l,,o"l,e.;>.;;.!SP""',;
                  -{Fl~==*                      ~**=~-.-------((1---1.j'---1_2jt--1__,_7_
                                                   ~                  fo,,,~

Rev. 0 was originally reviewed by ORC on June 10, 1983. OSRC REVIEW REQUIRED SAFETY REVIEW REQUIRED 75

PNPS-ODCM Rev. 11 RECORD OF DOCUMENT CHANGES DOCUMENT REV. DATE SECTION NO. IDENTIFICATION OF CHANGE APPROVED AND PAGE 0 Original Submittal 06/10/1983 All Sections 5 Add Steam Jet Air Ejector Monitor to section 10/30/1991 Pages i, ii, iii, v, addressing monitor setpoints. 34a 6 Update revision Log; renumber pages ii through viii; 08/11/1994 Pages i through clarify definition of dilution flow used for liquid viii; 14, 17, 33, effluent discharges; clarify assumptions used in 34a, A-35 gaseous effluent dose calculations and SJAE monitor setpoints. 7 Reference NRC Safety Evaluation and 11/22/1995 Pages i through vi, 10CFR20.302 permit for onsite disposal of slightly Appendix C, page contaminated construction soil; repaginate C-1 preliminary pages. 8 Relocate Effluent Controls from PNPS Technical 08/27/1998 Entire document Specifications to the ODCM in accordance with Generic Letter 89-01; Repaginate and sectionalize entire ODCM; update distance and direction information for environmental sampling locations. 9 Relocate Effluent Control Bases within Control; 06/19/2003 Pages i through v, align Definitions with NUREG-1302; align gaseous vii, viii; page 1-1; sampling requirements with NUREG-1302; revise section 2; section REMP sampling program for samples and locations 3/4; page 7-5; no longer required; align REMP LLDs and reporting section 8; page 9-levels with NUREG-1302; enhance discussion of 1, section 11, page alarm setpoint methodologies. 13-2 10 Add turbine building and reactor feed pump 05/20/2009 Pages i through v, gaseous effluent monitors (GEMS) for gaseous vii, viii; pages 3/4-effluent monitoring; revise action statements for 7 through 3/4-12; steam jet air ejector monitors inoperable; revise 3/4-17 through liquid effluent concentration limits to conform with 3/4-19; 3/4-24; STS requirements; clarify total dose limit at or 3/4-28; 3/4-31; beyond site boundary; revise REMP sampling table 3/4-40 through to address availability of various sample types; 3/4-43; 7-2; 7-4; change title of annual report; correct typographical 12-1; A-28 through error on ingestion dose tables A-42; 11 Modify Page iii to denote new revision number; 06/14/2017 Page iii; modify Table 4.3-1 to indicate Turbine Building and page 3/4-18; Feed Pump GEMS utilize beta-sensitive detectors pages 3/4-30, for gross noble gas measurement; modify Table 3/4-34 through 3.5-2, Figure 3.5-1, and Figure 3.5-2 to indicate 3/4-36; location of ISFSI Pad and addition of three TLDs for page 11-1 ISFSI direct radiation monitoring; clarify wording in section 11.0 regarding laboratory analysis of REMP samples and REMP TLDs A"'* ii 76

PNPS-ODCM Rev. 11 LIST OF EFFECTIVE PAGE REVISIONS Page Rev. Page Rev. Page Rev. Page ' Rev. Page Rev. Page ; Rev. i 11 3/4-16 11 5-1 11 9-1 11 A-1 11 B-1 11 ii 11 3/4-17 11 5-2 11 9-2 11 A-2 11 B-2 11 iii 11 3/4-18 11 9-3 11 A-3 11 B-3 11 iv 11 3/4-19 11 9-4 11 A-4 11 V 11 3/4-20 11 9-5 11 A-5 11 vi 11 3/4-21 11 9-6 11 A-6 11 vii 11 3/4-22 11 9-7 11 A-7 11 viii 11 3/4-23 11 9-8 11 A-8 11 ix 11 3/4-24 11 6-1 ' 11 9-9 11 A-9 11 C-1 11 3/4-25 11 6-2 11 9-10 11 A-10 11 3/4-26 11 9-11 11 A-11 11 3/4-27 11 9-12 11 A-12 11 3/4-28 11 9-13 11 A-13 11 3/4-29 11 . 9-14 11 A-14 11 1-1 11 3/4-30 11 9-15 11 A-15 11 1-2 11 3/4-31 11 A-16 11 1-3 11 3/4-32 11 7-1 11 A-17 11 3/4-33 11 7-2 11 A-18 11 3/4-34 11 7-3 11 A-19 11 3/4-35 11 7-4 11 A-20 11 3/4-36 11 7-5 11 A-21 11 3/4-37 11 7-6 11 10-1 11 A-22 11 3/4-38 11 10-2 11 A-23 11 2-1 11 3/4-39 11 A-24 11 2-2 11 3/4-40 11 A-25 11 3/4-41 11 A-26 11 3/4-42 11 A-27 11 3/4-43 11 A-28 11 3/4-44 11 8-1 11 A-29 11 3/4-45 11 8-2 11 11-1 11 A-30 11 3/4-1 11 3/4-46 11 8-3 11 11-2 11 A-31 11 3/4-2 11 3/4-47 11 8-4 11 A-32 11 3/4-3 11 8-5 11 A-33 11 3/4-4 11 A-34 11 3/4-5 11 A-35 11 3/4-6 11 A-36 11 3/4-7 11 12-1 11 A-37 11 3/4-8 11 A-38 11 3/4-9 11 A-39 11 3/4-10 . 11 A-40 11 3/4-11 11 A-41 11 3/4-12 11 13-1 11 A-42 11 3/4-13 11 13-2 11 A-43 11 3/4-14 11 3/4-15 11 ' iii 77

PNPS-ODCM Rev. 11 TABLE OF CONTENTS SECTION TITLE PAGE RECORD OF DOCUMENT CHANGES ii LIST OF EFFECTIVE PAGE REVISIONS iii TABLE OF CONTENTS Iv LIST OF FIGURES Vii LIST OF TABLES Viii

1.0 INTRODUCTION

1-1 2.0 DEFINITIONS 2-1 3/4.0 EFFLUENT AND ENVIRONMENTAL CONTROLS 3/4-1 3/4.1 INSTRUMENTATION 3/4-2 3/4.1.1 Radioactive Liquid Effluent Instrumentation 3/4-3 3/4.1.2 Radioactive Gaseous Effluent Instrumentation 3/4-6 3/4.2 RADIOACTIVE LIQUID EFFLUENTS 3/4-12 3/4.2.1 Liquid Effluents Concentration 3/4-12 3/4.2.2 Dose - Liquids 3/4-14 3/4.2.3 Liquid Radwaste Treatment 3/4-15 3/4.3 RADIOACTIVE GASEOUS EFFLUENTS 3/4-17 3/4.3.1 Gaseous Effluents Dose Rate 3/4-17 3/4.3.2 Dose - Noble Gases 3/4-20 3/4.3.3 Dose - lodine-131, lodine-133, Radioactive Material in Particulate 3/4-21 Form, and Tritium 3/4.3.4 Gaseous Effluent Treatment 3/4-22 3/4.4 TOTAL DOSE 3/4-24 3/4.4.1 Total Dose 3/4-24 3/4.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4-25 3/4.5.1 Environmental Monitoring Program 3/4-25 3/4.5.2 Land Use Census 3/4-47

iv 78

PNPS-ODCM Rev. 11 TABLE OF CONTENTS (continued) SECTION TITLE PAGE 5.0 RADIOLOGICAL EFFLUENT CONTROLS AND METHODOLOGY 5-1 CROSS REFERENCE

6.0 DESCRIPTION

OF RADWASTE SYSTEMS 6-1 6.1 Liquid Radwaste System 6-1 6.2 Treated Gaseous Radwaste System 6-1 7.0 RELEASE POINT AND MONITOR DESCRIPTION 7-1 7.1 Radioactive Effluent Release Point Description 7-1 7.1.1 Liquid Radioactive Waste Effluent Release 7-1 7.1.2 Main Stack Gas Release 7-1 7.1.3 Reactor Building Exhaust Vent Release 7-2 7.1.4 Turbine Building and Reactor Feed Pump Ventilation Releases 7-2 7.2 Radioactive Effluent Monitoring System Description 7-3 7.2.1 Liquid Radioactive Waste Effluent Monitoring System 7-3 7.2.2 Main Stack Gas Monitoring System 7-3 7.2.3 Reactor Building Exhaust Vent Monitoring System 7-4 7.2.4 Turbine Building and Feed Pump Gaseous Effluent Monitoring 7-4 System (GEMS) 7.3 Measurement Method During Release 7-7 7.3.1 Liquid Effluent 7-7 7.3.2 Gaseous Effluent 7-7 7.3.3 Limitations 7-7 8.0 MONITOR SETPOINTS 8-1 8.1 Liquid Effluent Monitor 8-1 8.2 Gaseous Effluent Monitors 8-2 8.3 Steam Jet Air Ejector Monitor 8-3 8.4 Post-Treatment Radiation Monitor 8-4 9.0 CALCULATIONAL METHODS 9-1 9.1 Concentrations of Liquid Effluents 9-1 9.2 Liquid Effluents Dose Assessment Methodology 9-2 9.2.1 Liquid Pathways Annual Dose Rates 9-2 9.2.1.1 Aquatic Foods Ingestion (Fish, shellfish) 9-2 9.2.1.2 Shoreline Deposits (Discharge Canal and Recreational Area) 9-3 9.2.1.3 Swimming (White Horse Beach) 9-3 9.2.1.4 Yachting/Boating (Cape Cod Bay) 9-3 9.2.2 Definitions 9-4 V 79

PNPS-ODCM Rev. 11 TABLE OF CONTENTS (continued) SECTION TITLE PAGE 9.3 Gaseous Effluents Dose Assessment Methodology 9-6 9.3.1 Gaseous Pathways Annual Dose Rates from Noble Gases 9-6 9.3.1.1 Gamma Air Dose 9-6 9.3.1.2 Beta Air Dose 9-7 9.3.1.3 Total Body Dose 9-7 9.3.1.4 Skin Dose 9-7 9.3.2 Gaseous Pathways Annual Dose Rates from Iodine 131 and 133, 9-8 Particulates with a Half-Life Greater Than 8 Days, and Tritium 9.3.2.1 Ground Plane Deposition 9-8 9.3.2.2 Breathing/Inhalation 9-8 9.3.2.3 Leafy Vegetation Ingestion 9-9 9.3.2.4 Root Crop/Non-Leafy Vegetation Ingestion 9-10 9.3.2.5 Milk Ingestion 9-10 9.3.2.6 Meat Ingestion 9-10 9.3.3 Definitions 9-11 9.4 Total Dose to a Member of the Public 9-15 10.0 RECEPTOR LOCATIONS, HYDROLOGY, AND METEOROLOGY 10-1 11.0 RADIOLOGICAL ENVIRONMENTAL SAMPLING AND 11-1 MEASUREMENT LOCATIONS 12.0 ANNUAL REPORT PREPARATION 12-1 12.1 Radioactive Effluent Release Report 12-1 12.2 Annual Radiological Environmental Operating Report 12-1

13.0 REFERENCES

13:..1 Appendix A DATA REQUIRED FOR EFFLUENT CALCULATIONS A-1 Appendix B DEFINITION OF THE LOWER LIMIT OF DETECTION B-1 Appendix C NRC SAFETY EVALUATION FOR ONSITE DISPOSAL OF C-1 SLIGHTLY CONTAMINATED CONSTRUCTION SOIL vi 80

PNPS-ODCM Rev. 11 LIST OF FIGURES FIGURE PAGE NUMBER FIGURE TITLE NUMBER 4.2-1 Liquid Radwaste Treatment System Schematic 3/4-16 . 4.3-1 Gaseous Effluent Treatment System Schematic 3/4-23 3.5-1 Environmental TLD Locations Within the PNPS Protected Area 3/4-33 3.5-2 TLD and Air Sampling Locations: Within 1 Kilometer 3/4-35 3.5-3 TLD and Air Sampling Locations: 1 to 5 Kilometers 3/4-37 3.5-4 TLD and Air Sampling Locations: Greater Than 5 Kilometers 3/4-39 3.5-5 Terrestrial and Marine/Aquatic Sampling Locations 3/4-41 3.5-6 Environmental Sampling and Measurement Control Locations 3/4-43 vii 81

PNPS-ODCM Rev. 11 LIST OF TABLES TABLE PAGE NUMBER TABLE TITLE NUMBER 1.1 Effluent Controls Cross-Reference 1-2 3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation 3/4-4 4.1-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance 3/4-5 Requirements 3.1-2 Radioactive Gaseous Effluent Monitoring Instrumentation 3/4-7 4.1-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance 3/4-9 Requirements 4.2-1 Radioactive Liquid Waste Sampling and Analysis Program 3/4-13 4.3-1 Radioactive Gaseous Waste Sampling and Analysis Program 3/4-18 3.5-1 Operational Radiological Environmental Monitoring Program 3/4-27 3.5-2 Environmental TLD Locations 3/4-30 3.5-3 Routine Radiological Environmental Sampling Locations 3/4-31 3.5-4 Reporting Levels for Radioactivity Concentrations in Environmental 3/4-45 Samples 4.5-1 Detection Capabilities for Environmental Sample Analysis 3/4-46 5-1 PNPS Effluent Controls And Methodology Cross-Reference 5-2 7-1 Radioactive Effluent Monitor Data 7-6 10-1 Critical Receptor Locations and Atmospheric Dispersion Factors 10-2 A-1 Bioaccumulation Factors To Be Used In The Absence Of Site-Specific A-1 Data A-2 Dose Factors For Immersion In Water A-2 A-3 Recommended Values For Liquid Effluents A-3 A-4 Dose Factors For Exposure To A Semi-Infinite Cloud Of Noble Gases A-4 A-5 Stable Element Transfer Data A-5 A-6 Nuclide Transfer Parameters For Goat's Milk A-6 A-7 Animal Consumption Rates A-6 A-8 Recommended Use Factors To Be Applied For The Average Individual A-7 A-9 Recommended Use Factors To Be Applied For The Maximum Exposed A-8 Individual A-10 External Dose Factors For Standing On Contaminated Ground A-9 A-11 Inhalation Dose Factors For Adult A-11 A-12 Inhalation Dose Factors For Teen A-15 A-13 Inhalation Dose Factors For Child A-19 A-14 Inhalation Dose Factors For Infant A-23 viii 82

PNPS-ODCM Rev. 11 LIST OF TABLES (continued) TABLE PAGE NUMBER TABLE TITLE NUMBER A-15 Ingestion Dose Factors For Adult A-27 A-16 Ingestion Dose Factors For Teen A-31 A-17 Ingestion Dose Factors For Child A-35 A-18 Ingestion Dose Factors For Infant A-39 A-19 Recommended Values For Gaseous Effluents A-43 ix 83

PNPS-ODCM Rev. 11

1.0 INTRODUCTION

This manual contains the current methodology, parameters, data, and information used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitor alarm/trip setpoints, and in the conduct of the radiological environmental monitoring program. All effluent controls contained in the Offsite Dose Calculation Manual (ODCM) were originally part of the PNPS Technical Specifications (Reference 1). In response to Generic Letter 89-01 (Reference 2) from the Nuclear Regulatory Commission, these Radiological Effluent Technical Specifications (RETS) were removed from the main body of the Technical Specifications and relocated to the ODCM. The effluent controls previously existed as parts of Section 3/4.8 and Section 7/8 of the PNPS Technical Specifications. In conjunction with the transfer of the effluent controls from the RETS to the ODCM, the numbering scheme for the individual effluent controls were changed to agree with the numbering scheme present in NUREG-1302, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors" (reference 27). The original Technical Specification 3/4.8.F, "Gaseous Effluent Treatment", addressed both offgas treatment and explosive gas monitoring. In accordance with the guidance in Generic Letter 89-01, monitoring of explosive gas concentrations was to be retained in the main body of the Technical Specifications. Subsequent to GL89-01, the improved standard technical specifications removed the requirement for explosive gas monitoring, in accordance with NED0-31466. Therefore, the original Technical Specification 3/4.8.F was partitioned and the portion addressing offgas treatment was relocated to the ODCM Effluent Controls (Control 3/4.3.4). The portion of the original Specification 3/4.8.F addressing explosive gas monitoring was relocated to the FSAR (Reference 3). A cross-reference of the original Technical Specification Section to the revised ODCM Effluent Control Section is included in Table 1.1. In conjunction with the GL89-01 change, the ODCM was restructured from that which previously existed. None of the requirements or methodologies were changed. Rather, the various sections were reorganized to facilitate support of the effluent controls relocated from the Technical Specifications. Descriptions of effluent monitoring systems and setpoint calculations were moved to the sections immediately following the controls, followed by dose calculation methodologies, and finally by the environmental monitoring program section. Supporting information is listed in the appendices at the rear of the manual. 1-1 84

PNPS-ODCM Rev. 11 TABLE 1.1 EFFLUENT CONTROLS CROSS-REFERENCE Original Technical Revised ODCM Effluent Control Topic Specification Section Control Section Liquid Effluents Concentration 3.8.A.1 3.2.1 4.8.A.1 4.2.1.a 4.8.A.2 4.2.1.b Table 4.8-1 Table 4.2-1 Radioactive Liquid Effluent Instrumentation 3.8.B.1 3.1.1

                                                                                                                                                                                         - 4.8.B.1                                                          4.1.1.a 4.8.B.2                                                          4.1.1.b Table 3.8-1                                                      Table 3.1-1 Table 4.8-2                                                      Table 4.1-1 Liquid Radwaste Treatment                                                                                                                                                               3.8.C.1                                                           3.2.3 4.8.C.1                                                          4.2.3.a 4.8.C.2                                                          4.2.3.b

.........................................................................................................................................................................................Fig.ure. 4 .8-1..................................................Fig ure ..4.2-.1........................... Gaseous Effluents Dose Rate 3.8.D.1 3.3.1 4.8.D.1 4.3.1.a 4.8.D.2 4.3.1.b Table 4.8-3 Table 4.3-1 Radioactive Gaseous Effluent 3.8.E.1 3.1.2 Instrumentation 4.8.E.1 4.1.2.a 4.8.E.2 4.1.2.b Table 3.8-2 (partial) Table 3.1-2 ............................................................................................................................................................................Table.. 4 ..8-4 . (partialt...................................Table.4.1.-2........................... Gaseous Effluent Treatment 3.8.F.a 3.3.4 3.8.F.1 Relocated to FSAR 4.8.F.1 4.3.4 4.8.F.2 Relocated to FSAR .........................................................................................................................................................................................Figure.4.8-2 ................................................Fig.ure.4.3-.1........................... Environmental Monitoring 7.1.A 3.5.1 8.1.A 4.5.1 Table 7.1-1 Table 3.5-4 Table 8.1-1 Table 3.5-1 Table 8.1-2 Table 3.5-3 Table 8.1-3 Table 3.5-2 Table 8.1-4 Table 4.5-1 Land Use Census 7.1.B 3.5.2 8.1.B 4.5.2 1-2 85

PNPS-ODCM Rev. 11 TABLE 1.1 (continued) EFFLUENT CONTROLS CROSS-REFERENCE Original Technical Revised ODCM Effluent Control Topic Specification Section Control Section Dose - Liquids 7.2.A 3.2.2 8.2.A 4.2.2 Dose - Noble Gases 7.3.A 3.3.2 8.3.A 4.3.2 Dose- lodine-131, lodine-133, Radioactive 7.4.A 3.3.3 ........ Material ..in ..Particu_late .. Form, .. and .. Tritium ................-...................................~.:.4..:A. . . . . . . . . . . . . . . . . . _

                                                                                                                                                                 . . . . . . . . . . . . . . . . . ..4..:.~.:.~......................................

Total Dose 7.5.A 3.4.1 8.5.A 4.4.1 1-3 86

PNPS-ODCM Rev. 11 2.0 DEFINITIONS This section lists definitions which are unique to the ODCM. Other definitions pertaining to actions and surveillance requirements for the various controls can be found in the Technical Specifications (Reference 1). 2.1 ACTION - ACTION shall be that part of a Control that prescribes remedial measures required under designated conditions. 2.2 CHANNEL CALIBRATION - A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm, interlock and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated. 2.3 CHANNEL CHECK - A CHANNEL CHECK shall be the 'qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent channels measuring the same parameter. 2.4 CHANNEL FUNCTIONAL TEST -A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions and channel failure trips.

b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is tested. 2.5 DOSE EQUIVALENT 1-131 - DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in ICRP 30, Supplement to Part 1, page 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity". 2.6 MEMBER(S) OF THE PUBLIC - MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the site. 2.7 NOMINAL STEADY STATE LEVEL - NOMINAL STEADY STATE LEVEL shall be the baseline level of radionuclide concentrations and/or radiation monitor readings resulting from at least 72 hours of operation at a given reactor power level and hydrogen injection rate. 2-1 87

PNPS-ODCM Rev. 11 2.8 OFFSITE DOSE CALCULATION MANUAL (ODCM) - The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain: (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specifications Administrative Controls 5.5.1 and 5.5.4; and, (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Technical Specifications Administrative Controls 5.6.2 and 5.6.3. 2.9 OPERABLE - OPERABILITY - A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication, or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s). 2.10 RADWASTE TREATMENT SYSTEM

a. Gaseous Radwaste Treatment System - The gaseous radwaste treatment system is that system identified in Figure 4.3-1.

b. Liquid Radwaste Treatment System - The liquid radwaste treatment system is that system identified in Figure 4.2-1.

2.11 RATED THERMAL POWER - RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2028 MWt. 2.12 REPORTABLE EVENT - A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10CFR Part 50. 2.13 SITE BOUNDARY - The SITE BOUNDARY is shown in Figure 1.6-1 in the FSAR (Reference 3). 2.14 SOURCE CHECK - A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity. 2.15 THERMAL POWER -THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. 2.16 UNRESTRICTED AREA -An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for the purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. 2-2 88

PNPS-ODCM Rev. 11 3/4.0 EFFLUENT AND ENVIRONMENTAL CONTROLS This section includes the effluent and environmental controls that were originally part of the PNPS Technical Specifications. With the exception of the environmental monitoring program previously listed in the Technical Specifications (Reference 1), these controls were relocated into the ODCM without any substantial changes, in accordance with Generic Letter 89-01 (Reference 2). Text and tables were reformatted to.the style of the ODCM. The various controls were renumbered from the original numbering scheme of the Technical Specifications. A cross-reference of the old Technical Specifications section to the new ODCM section is presented in Table 1.1. Prior to the Generic Letter 89-01 change to the ODCM (Revision 8), the ODCM contained an enhanced radiological environmental monitoring program (REMP), above that required by the Technical Specifications. To prevent confusion and capture the more inclusive monitoring program that existed in the ODCM, the original Technical Specification REMP was replaced with the REMP described in the ODCM. Therefore, the monitoring program listed in section 3/4.5 contains more samples and monitoring locations than existed in the Technical Specifications REMP prior to the Generic Letter 89-01 change. , In addition to the changes in the REMP program described above, all of the tables were revised with the latest distance and direction information available. The global positioning system (GPS) was used to verify the locations of the various sampling and monitoring stations, and the tables were updated accordingly. In keeping with governmental efforts to adopt the metric system of measurement, all distances have been listed in metric units (meters and/or kilometers) in the various tables and figures. Any changes in distances and directions to the various monitoring locations from those originally listed in the Technical Specifications REMP are corrections based on new information. None of the locations of the sampling stations were actually changed. Some of the verbal descriptions, especially those for near-plant TLDs, have been updated to reflect current names of buildings and other areas near Pilgrim Station. Again, none of the physical locations were altered, and the change merely reflects up-to-date place names adopted by station management. In 1977, Boston Edison Company was pursuing construction of a second unit on the PNPS site. As part of the preliminary licensing efforts for this second unit, Pilgrim Station committed to a special marine sampling program under the REMP. This program was much more aggressive than that outlined in standard NRC guidance for an environmental monitoring program, and included collecting many more samples, duplicate/split sampling, analysis of special radionuclides, and analysis to detection limits lower than those recommended by the NRC. This specialized sampling program was agreed to by Boston Edison Company for a period not to exceed 1O years. Due to the inclusion of the REMP in the Technical Specifications at that time, the program was carried forward beyond the 10-year period. Following an evaluation of results obtained from this specialized marine sampling program over the past 25 years, it has been determined that the analyses have shown that the impact of radioactivity in liquid discharges on the general public and environment is negligible. In light of the fact that the terms of the sampling program have expired, the specialized program is no longer warranted. Furthermore, replacement of the specialized program with a marine sampling program such as that prescribed by the NRC in NUREG-1302 (reference 27) and the Branch Technical Position on Environmental Monitoring (reference 28) will still allow PNPS personnel to evaluate the impact of its operations on the environment and general public. Therefore, PNPS has dropped most of the specialized requirements and has adopted the standard model for marine sampling recommended by the NRC. In order to streamline the flow of information for each of the applicable effluent controls, the technical bases for the controls were relocated from the end of Section 3/4 to within the applicable 3/4-1 89

PNPS-ODCM Rev. 11 control. As is the case with Technical Specifications, the bases are not considered to be part of the control or its requirements. Rather, the bases provide the technical rationale behind the applicable control, and are listed to provide additional clarification regarding the specific control. 3/4-2 90

PNPS-ODCM Rev. 11 3/4.1 INSTRUMENTATION 3/4.1.1 Radioactive Liquid Effluent Instrumentation CONTROLS 3.1.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.1-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Controls 3.2.1 are not exceeded during periods when liquid wastes are being discharged via the radwaste discharge header. For releases other than the radwaste discharge header, the above specification does not apply, these releases shall be made in accordance with Action 1 of Table 3.1-1. APPLICABILITY: As shown in Table 3.1-1. ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of Control 3.2.1 are met, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or change the setpoint so that it is acceptably conservative or declare the channel inoperable.

b. With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the action shown in Table 3.1-1.

SURVEILLANCE REQUIREMENTS 4.1.1.a The setpoints for monitoring instrumentation shall be determined in accordance with the ODCM. 4.1.1.b Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE at the frequencies shown in Table 4.1-1. BASES 3/4.1.1 Radioactive Liquid Effluent Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the Offsite Dose Calculation Manual (ODCM) to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10CFR50. 3/4-3 91

PNPS-ODCM Rev. 11 TABLE 3.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument 0 erable A licabilit Action<1>

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste During actual discharge of 1 Effluent Line Ji uid wastes

2. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste During actual discharge of 2 Effluent Line liquid wastes

b. Discharge Canal N/A During actual discharge of 3 liquid wastes

3. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Reactor Building Closed 1 During operation of the reactor building 4 Cooling Water Loop "A" closed cooling system During operation of the reactor building 1 closed coolin s stem 4

<1> Actions Required -- ACTION 1: With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirement, effluent releases may be resumed provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Control 4.2.1.a; and,

b. An independent verification of the release rate calculations is performed; and,

c. An independent verification of the discharge line valving is performed.

ACTION 2: With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided that the flow rate is verified at least once per 4 hours during actual releases. Flow will be estimated based on design flow rate of the operating circulating water pumps and/or operating salt service water pumps. ACTION 3: Flow will be estimated based on the sum of the operating waste discharge pumps, operating circulating water pumps, and/or operating salt service water pumps. ACTION 4: With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided that at least once per day grab samples are collected and analyzed for radioactivity at a lower limit of detection of no more than 5E-07 uCi/mL. 3/4-4 92

PNPS-ODCM Rev. 11 TABLE 4.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Source Channel Channel Instrument Check Check Calibration Functional Test

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE (1)

a. Liquid Radwaste N/A Once per Quarterly Effluents Line 24 months<2l

2. FLOW RATE MEASUREMENT DEVICES (1)

a. Liquid Radwaste N/A Once per Quarterly Effluents Line 24 months

3. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE (3)

a. Reactor Building Closed N/A Once per Quarterly Cooling Water Loop "A" 24 months<2l (3)

b. Reactor Building Closed N/A Once per Quarterly CoolinQ Water Loop "8" 24 months<2 >

1 <> During or prior to release via this pathway. 2 <) Previously established calibration procedures will be used for these requirements. 3 <J During operation of the reactor building closed cooling water system. 3/4-5 93

PNPS-ODCM Rev. 11 3/4.1 INSTRUMENTATION 3/4.1.2 Radioactive Gaseous Effluent Instrumentation CONTROLS 3.1.2 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.1-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 3.3.1 are not exceeded. APPLICABILITY: As shown in Table 3.1-2 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of Control 3.3.1 are met, change the setpoint so that it is acceptably conservative or declare the channel inoperable.

b. With one or more radioactive gaseous effluent monitoring instrumentation channels inoperable, take the action shown in Table 3.1-2.

SURVEILLANCE REQUIREMENTS 4.1.2.a The setpoints shall be determined in accordance with ODCM. 4.1.2.b Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE at the frequencies shown in Table 4.1-2. BASES 3/4.1.2 Radioactive Gaseous Effluent Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General design Criteria 60, 63, and 64 of Appendix A to 10CFR50. 3/4-6 94

PNPS-ODCM Rev. 11 TABLE 3.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument Operable Aoolicabilitv Parameter Action( 1)

1. MAIN STACK EFFLUENT MONITORING SYSTEM (2)

a. Noble Gas Activity 1 Radioactivity Rate 1 Monitor Providing Alarm Measurement (2)

b. Iodine Sampler 1 Collect Halogen 2 Cartridge Sample (2)

C. Particulate Sampler 1 Collect Particulate 2 Filter Sample (2)

d. Effluent System Flow 1 System Flow Rate 3 Rate Measuring Device Measurement (2)

e. Sampler Flow Rate 1 Sampler Flow Rate 3 Measuring Device Measurement

2. REACTOR BUILDING VENTILATION EFFLUENT MONITORING SYSTEM (2)

a. Noble Gas Activity 1 Radioactivity Rate 1 Monitor Providing Alarm Measurement (2)

b. Iodine Sampler 1 Collect Halogen 2 Cartridge Sample (2)

C. Particulate Sampler 1 Collect Particulate 2 Filter Sample (2)

d. Effluent System Flow 1 System Flow Rate 3 Rate Measuring Device Measurement (2)

e. Sampler Flow Rate 1 Sampler Flow Rate 3 MeasurinQ Device Measurement

3. STEAM JET AIR EJECTOR RADIOACTIVITY MONITOR (3)

a. Noble Gas Activity Monitor 1 Noble Gas Radioactivity 4 (Providing Alarm and Rate Measurement Auto-isolation of Stack)

4. POST-TREATMENT RADIATION MONITOR (4)

a. Noble Gas Activity Monitor 1 Noble Gas Radioactivity 5 (Providing Alarm and Rate Measurement Auto-isolation of Stack) 3/4-7 95

PNPS-ODCM Rev. 11 TABLE 3.1-2 (continued) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument Operable Aoolicabilitv Parameter Action( 1>

5. TURBINE BUILDING GASEOUS EFFLUENT MONITORING SYSTEM (GEMS)

(2)

a. Noble Gas Activity 1 Radioactivity Rate 5 Monitor Providing Alarm Measurement (2)

b. Iodine Sampler 1 Collect Halogen 2 Cartridge Sample (2)

c. Particulate Sampler 1 Collect Particulate 2 Filter Sample (2)

d. Sampler Flow Rate 1 Sampler Flow Rate 3 Measurinq Device Measurement

6. FEED PUMP GASEOUS EFFLUENT MONITORING SYSTEM (GEMS)

(2)

a. Noble Gas Activity 1 Radioactivity Rate 5 Monitor Providing Alarm Measurement (2)

b. Iodine Sampler 1 Collect Halogen 2 Cartridge Sample (2)

C. Particulate Sampler 1 Collect Particulate 2 Filter Sample (2)

d. Sampler Flow Rate 1 Sampler Flow Rate 3 Measuring Device Measurement 1

<> Actions Required -- ACTION 1*: With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed for activity within 24 hours. ACTION 2*: With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.3-1. ACTION 3*: With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours. r 3/4-8 96

PNPS-ODCM Rev. 11 ACTION 4: With the number of operable channels less than required, gases from the steam jet air ejector may continue to be released to the offgas system provided the following is met: a.1 The augmented offgas (AOG) treatment system is not bypassed, AND a.2 Two channels of the post-treatment radiation monitors are OPERABLE or tripped and capable of alarm and auto-isolation of the main stack. AND a.3 The AOG charcoal vault area radiation monitor (ARM) and control room alarm are FUNCTIONAL. AND a.4 Technical Specification Surveillance Requirement 4.8.1.1 is performed at least once every 24 hours. OR b.1 Technical Specification Surveillance Requirement 4.8.1.1 is performed at least every four hours. Otherwise, be in Hot Standby within 12 hours. I ACTION 5*: With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per week and these samples are analyzed for activity within 24 hours.

Note: (For Actions 1, 2, 3, and 5) If the instruments are not returned to OPERABLE status within 30 days, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

2 <> During releases via this pathway. 3 <> During operation of steam jet air ejector. f 4 <> During operation of augmented offgas treatment system. 3/4-9 97

PNPS-ODCM Rev. 11 TABLE 4.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Source Channel Channel Instrument Check Check Calibration Functional Test

1. MAIN STACK EFFLUENT MONITORING SYSTEM

a. Noble Gas Activity Daily< 1l Monthly Once per Quarterly Monitor (2 channels) 24 months <2>

b. Iodine Sampler NIA NIA NIA NIA Cartridge

c. Particulate Sampler NIA NIA NIA NIA Filter

d. Effluent System Flow Daily< 1l NIA Once per Quarterly Rate Measuring Device 24 months

e. Sampler Flow Rate Daily< 1l NIA Once per Quarterly Measuring Device 24 months

2. REACTOR BUILDING VENTILATION EFFLUENT MONITORING SYSTEM

a. Noble Gas Activity Daily<1l Monthly Once per Quarterly Monitor (2 channels) 24 months <2>

b. Iodine Sampler NIA NIA N/A N/A Cartridge

c. Particulate Sampler N/A N/A N/A N/A Filter

d. Effluent System Flow Daily< 1l N/A Once per Quarterly Rate Measuring Device 24 months

e. Sampler Flow Rate Daily<1l N/A Once per Quarterly Measuring Device 24 months

3. STEAM JET AIR EJECTOR RADIOACTIVITY MONITOR

a. Noble Gas Activity Dailyl3 > N/A Once per Quarterly Monitor (2 channels) 24 months<2 >

4. POST-TREATMENT RADIATION MONITOR

a. Noble Gas Activity Daily<4> N/A Once per Quarterly Monitor (2 channels) 24 months<2>

3/4-10 98

PNPS-ODCM Rev. 11 TABLE 4.1-2 (continued) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Source Channel Channel lnstrum'ent Check Check Calibration Functional Test

5. TURBINE BUILDING GASEOUS EFFLUENT MONITORING SYSTEM (GEMS}

a. Noble Gas Activity Daily<1l Monthly Once per Quarterly Monitor (1 channels) 24 months <2l

b. Iodine Sampler N/A N/A N/A N/A Cartridge C. Particulate Sampler N/A N/A N/A N/A Filter

d. Sampler Flow Rate Dail/1l N/A Once per Quarterly Measuring Device 24 months

6. FEED PUMP GASEOUS EFFLUENT MONITORING SYSTEM (GEMS)

a. Noble Gas Activity Daily<1l Monthly Once per Quarterly 2

Monitor (1 channels) 24 months <)

b. Iodine Sampler N/A N/A N/A N/A Cartridge C. Particulate Sampler N/A N/A N/A N/A Filter

d. Sampler Flow Rate Dail/ 1l N/A Once per Quarterly Measuring Device 24 months 1

<) During releases via this pathway. 2 <) Previously established calibration procedures will be used for these requirements. 3 <) During operation of the steam jet air ejector. 4 <l During operation of the augmented offgas treatment system. 3/4-11 99

PNPS-ODCM Rev. 11 3/4.2 RADIOACTIVE LIQUID EFFLUENTS 3/4.2.1 Liquid Effluents Concentration CONTROLS 3.2.1 The concentration of radioactive materic1I released in liquid effluents to areas at and beyond the SITE BOUNDARY shall be limited to ten times the concentration values specified in Appendix B, Table 2, Column 2, to 10 CFR 20.1001-20.2402, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration of individual isotopes shall be limited to 2E-04 µCi/ml. APPLICABILITY: At all times. ACTION: With the concentration of radioactive material released from the site to areas at and beyond the SITE BOUNDARY exceeding the above limits, without delay restore concentration within the above limits. SURVEILLANCE.REQUIREMENTS 4.2.1.a The radioactivity content of each batch of radioactive liquid waste to be discharged shall be determined prior to release by sampling and analysis in accordance with Table 4.2-1. 4.2.1.b The results of pre-release analyses shall be used with calculational methods in the Offsite Dose Calculation Manual (ODCM) to assure that the concentration at the point of release is limited to the values in Control 3.2.1. BASES 3/4.2.1 Liquid Effluents Concentration This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to areas at and beyond the SITE BOUNDARY will be less than ten times the concentration values specified in Appendix B, Table 2, Column 2, to 10 CFR 20.1001-20.2402. This limitation provides additional assurance that the levels of radioactive materials in bodies of water at and beyond the SITE BOUNDARY will result in exposures within (1) the Section II.A design objectives of Appendix I, 10CFR50, to a MEMBER OF THE PUBLIC and (2) restrictions authorized by 10 CFR 20.1301(e). 3/4-12 100

PNPS-ODCM Rev. 11 TABLE 4.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Sampling Analysis Type of Activity Detection( 1) Liquid Release Type Frequency Frequency Analysis µCi/ml

1. Batch Waste Release Tanks\LJ Principal Each Prior to Gamma 5E-07

a. Non-treatable Releases Batch Each Emitters(3 >

(e.g., Neutralizer Sumps), Batch 1-131 1E-06 AND Release Dissolved and

b. Treatable Releases Entrained 1E-05 (e.g., Radwaste Tanks) Gases Composite Monthly H-3 1E-05 from Each Composite(4 > Gross Alpha 1E-07 Batch Quarterly Sr-89, Sr-90 5E-08 Composite(4J Fe-55 1E-06

2. Continuous Releases Weekly Principal Grab Weekly Gamma 5E-07

a. Salt Service Water Sample Emitters(3 l 1

( J Refer to Appendix B of the ODCM for definition of lower limit of detection (LLD). (Z) A batch release is the discharge of liquid wastes of a discrete volume. 3 ( l The principal gamma emitters for which the LLD control applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall be analyzed and reported in the Annual Radioactive Effluent Release Report. 4 ( J A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released. 3/4-13 101

PNPS-ODCM Rev. 11 3/4.2 RADIOACTIVE LIQUID EFFLUENTS 3/4.2.2 Dose - Liquids CONTROLS 3.2.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released at and beyond the SITE BOUNDARY shall be limited:

a. During any calendar quarter to ~ 1.5 mrem to the total body and to ~ 5 mrem to any organ; and,

b. During any calendar year to ~ 3 mrem to the total body and to ~ 10 mrem to any organ.

APPLICABILITY: At all times ACTION: With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a special report that identifies the cause(s), corrective actions taken, and corrective actions to be taken. SURVEILLANCE REQUIREMENTS 4.2.2 Dose Calculations - Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM for each calendar month during which releases occurred. BASES 3/4.2.2 Dose - Liquids This section is provided to implement the requirements of Sections II.A, III.A, and IV.A of 10CFR50, Appendix I, to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Because Pilgrim is not a site where plant operations can conceivably affect drinking water, none of these requirements are intended to assure compliance with 40CFR141. The dose calculations in the ODCM implement the requirements of 10CFR50, Appendix I, Section Ill.A to ensure that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113. 3/4-14 102

PNPS-ODCM Rev. 11 3/4.2 RADIOACTIVE LIQUID EFFLUENTS 3/4.2.3 Liquid Radwaste Treatment CONTROLS 3.2.3 The liquid radwaste treatment system shall be maintained and used to reduce th.e radioactive materials in liquid wastes prior to their discharge when the dose due to liquid effluent releases to areas at and beyond the SITE BOUNDARY averaged over a 31-day period would exceed 0.06 mrem to the total body or 0.20 mrem to any organ. APPLICABILITY: At all times. ACTION: With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days a special report which includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability; and,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status; and,

3. Summary description of action(s) taken to prevent a recyrrence.

SURVEILLANCE REQUIREMENTS 4.2.3.a Doses due to liquid releases at and beyond the SITE BOUNDARY shall be calculated at least once per 31-day period in accordance with the ODCM, only if releases in that period have occurred. 4.2.3.b The liquid radwaste treatment system schematic is shown in Figure 4.2-1. BASES 3/4.2.3 Liquid Radwaste Treatment The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10CFR50.36a, General Design Criteria 60 of Appendix A to 10CFR50 and design objective Section 11.D of Appendix I to 10CFR50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I, 10CFR50, for liquid effluents. 3/4-15 103

PNPS-ODCM Rev. 11 HIGH PURITY WASTE SYSTEM Clean Waste Mixed Bed Treated Water Discharge or Tanks Ion Exchange Tanks Recycle LOW PURITY WASTE SYSTEM I Chemical Waste I Tanks

                                                                      ~ ~I__D_is_c_h_a_rg_e_ __.

DETERGENT WASTE SYSTEM (Decon Areas) Miscellaneous Waste Tanks or Non-treatable Releases 1------------------ Discharge (e.g., Neutralizer Sumps) Figure 4.2-1 Liquid Radwaste Treatment System Schematic 3/4-16 104

PNPS-ODCM Rev. 11 3/4.3 RADIOACTIVE GASEOUS EFFLUENTS 3/4.3.1 Gaseous Effluents Dose Rate CONTROLS 3.3.1 The instantaneous dose rate due to radioactive materials rel.eased in gaseous effluents from the site boundary to areas at and beyond the SITE BOUNDARY (see FSAR Figure 1.6-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin; and,

b. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.

APPLICABILITY: At all times. ACTION: With the instantaneous dose rate(s) exceeding the above limits, without delay restore the release rate to within the above limit(s). SURVEILLANCE REQUIREMENTS 4.3.1.a The instantaneous dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of Control 3.3.1.a on a continuous basis using the noble gas activity monitors with appropriate setpoints and in accordance with the ODCM. 4.3.1.b The instantaneous dose rate due to iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the limits of Control 3.3.1.b in accordance with the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.3-1. BASES 3/4.3.1 Gaseous Effluents Dose Rate This control is provided to ensure that the dose rate at anytime at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR20. The annual dose limits are the doses associated with the concentration of 10CFR20, Appendix B, Table 2. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC outside the SITE BOUNDARY to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10CFR20.1001-20.2402. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the individual will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBERS OF THE PUBLIC at or beyond the SITE BOUNDARY to :s; 500 mrem/year to the total body or to :s; 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to :s; 1500 mrem/year for the nearest cow to the plant. 3/4-17 105

PNPS-ODCM Rev. 11 TABLE 4.3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Type of Activity Lower Limit of Sampling Analysis Analysis Detection< 1> Gaseous Release Type Frequency Frequency µCi/ml Main Stack Principal 2 and Monthly Monthl/ l Gamma 1E-04 Reactor Building Vent Grab Emitters(3 J Sample H-3 1E-06 Weekll'J Continuous(4 l Charcoal 1-131 1E-12 Sample Weekll'J Principal Continuous(4 J Particulate Gamma 1E-11 Sample Emitters(3 J Monthly Continuous(4 J Composite Gross Alpha 1E-11 Particulate Sample Quarterly Continuous(4 J Composite Sr-89, Sr-90 1E-11 Particulate Sample Continuous Noble Gas Continuous(4 J Noble Gas Gross 1E-06 Monitor Gamma Post-Treatment Radiation Monthly Monthly Principal Monitor Grab Gamma 1E-04 Sample Emitters(3 J Turbine Building GEMS Principal 2 and Monthly Monthl/ l Gamma 1E-04 Feed Pump GEMS Grab Emitters(3 l Sample H-3 1E-06 Weeklyl"1 Continuous(4J Charcoal 1-131 1E-12 Sample Weeklyl"1 Principal Continuous(4J Particulate Gamma 1E-11 Sample Emitters(3 > Monthly Continuous(4J Composite Gross Alpha 1E-11 Particulate Sample Quarterly Continuous(4 J Composite Sr-89, Sr-90 1E-11 Particulate Sample Continuous Noble Gas Continuous(4 J Noble Gas Gross 1E-06 Monitor Beta 3/4-18 106

PNPS-ODCM Rev. 11 TABLE 4.3-1 (continued) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 1 <l Refer to Appendix B of the ODCM for definition of lower limit of detection (LLD). 2 <l A noble gas sample shall be collected and analyzed as soon as practicable following any 15-minute or longer sustained increase in noble gas release rates more than a factor of 3 above NOMINAL STEADY STA TE LEVEL. 3 <l The principal gamma emitters,for which the LLD control applies are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases; and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Cs-134, Cs-137, Ce-141, and Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall be analyzed and reported in the Annual Radioactive Effluent Release Report. 4 <l The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Controls 3.3.1, 3.3.2, and 3.3.3. 5 <l Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from the sampler. Sampling of the affected release point shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement applies ONLY IF: (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in reactor coolant has increased more than a factor of 3 above NOMINAL STEADY STATE LEVEL; OR (2) the noble gas monitor shows that effluent activity has increased by more than a factor of 3 above NOMINAL STEADY STATE LEVEL Increased 24 hour sampling can be terminated when BOTH: (1) DOSE EQUIVALENT 1-131 concentration in reactor coolant, AND (2) noble gas effluent release rate are less than a factor of 3 times above NOMINAL STEADY STATE LEVEL. When comparison is made using levels under which 72-hour steady state operation has not been achieved, DOSE EQUIVALENT 1-131 concentrations and noble gas release rates should be adjusted for expected changes in response to changes in reactor power level and/or hydrogen injection rate. 3/4-19 107

PNPS-ODCM Rev. 11 3/4.3 RADIOACTIVE GASEOUS EFFLUENTS 3/4.3.2 Dose - Noble Gases CONTROLS 3.3.2 The air dose in areas at and beyono the SITE BOUNDARY due to noble gases released in gaseous effluents shall be limited to the following:

a. During any calendar quarter, to ~ 5 mrad for gamma radiation and.~ 10 mrad for beta radiation; and,

b. During any calendar year, to ~ 10 mrad for gamma radiation and ~ 20 mrad for beta radiation.

APPLICABILITY: At all times ACTION: With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a special report which identifies the cause(s), the corrective actions taken, and corrective actions to be taken. SURVEILLANCE REQUIREMENTS 4.3.2 Dose Calculations - Cumulative dose contributions for the total time period shall be determined in accordance with the ODCM for each calendar month during which releases occurred. BASES 3/4.3.2 Dose - Noble Gases This section is provided to implement the requirements of 10CFR50, Appendix I, Sections 11.B, 111.A, and IV.A to ensure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The surveillance requirements implement the requirements of 10CFR50, Appendix I, Section Ill.A to ensure that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY will be based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. 3/4-20 108

PNPS-ODCM Rev. 11 3/4.3 RADIOACTIVE GASEOUS EFFLUENTS 3/4.3.3 Dose - lodine-131, lodine-133, Radioactive Material in Particulate Form, and Tritium CONTROLS 3.3.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, radioactive materials in particulate form with half-lives greater than 8 days, and tritium in gaseous effluents released to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter to ~ 7.5 mrem to any organ; and,

b. During any calendar year to~ 15 mrem to any organ.

APPLICABILITY: At all times ACTION: With the calculated dose from the release of iodine-131, iodine-133, radioactive materials in particulate form, and tritium in gaseous effluents exceeding any of the above limits; prepare and submit to the Commission within 30 days, a special report which identifies the cause(s), corrective actions taken, and the corrective actions to be taken. SURVEILLANCE REQUIREMENTS 4.3.3 Dose Calculations - Cumulative dose contributions for the total time period shall be determined for iodine-131, iodine-133, radioactive material in particulate form with half-lives greater than 8 days, and tritium in accordance with the ODCM for each calendar month during which releases occurred. BASES 3/4.3.3 Dose - lodine-131, lodine-133, Radioactive Material In Particulate Form, And Tritium This section is provided to implement the requirements of Sections 11.C, Ill.A and IV.A of 10CFR50, Appendix I, to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements of 10CFR50, Appendix I, Section Ill.A to ensure that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods approved by the NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guides 1.109 and 1.111. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for iodine-131, radioactive material in particulate form with half-lives greater than 8 days, and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways which are examined in the development of these calculations are:

1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and

4) deposition on the ground with subsequent exposure of man.

3/4-21 109

PNPS-ODCM Rev. 11 3/4.3 RADIOACTIVE GASEOUS EFFLUENTS 3/4.3.4 Gaseous Effluent Treatment CONTROLS 3.3.4 The augmented offg.as system shall be put into service prior to reaching 50 p~rcent reactor power during startup. APPLICABILITY: Whenever the plant is operating at or above 50 percent reactor power. ACTION: With gaseous effluents being discharged for more than 14 days without treatment, prepare and submit to the Commission within 30 days, a special report which includes the following information:

1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability; and,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status; and,

3. Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS 4.3.4.a Augmented offgas (post-treatment radiation monitor) annunciator OPERABILITY shall be verified once per 12 hours when the augmented offgas system is in use. 4.3.4.b The gaseous effluent treatment system schematic is shown in Figure 4.3:.1. BASES 3/4.3.4 Gaseous Effluent Treatment The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10CFR50.36a, General Design Criterion 60 of Appendix A to 10CFR50, and design objective Section 11.D of Appendix I to 10CFR50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections 11.B and 11.C of Appendix I, 10CFR50, for gaseous effluents. 3/4-22 110

PNPS-ODCM Rev. 11 L SJAE from Main Condenser

               --    Recombiner++       Condenser -+ ~D_r_ie_r_ _~

I t I Charcoal I* Discharge

                                                                                          ~k_ot_~_c~_in_ _,

GLAND SEALS 1.7 Minute Discharge to from Turbine Gland Seals Holdu 1 Main Stack MECHANICAL VACUUM PUMP Discharge to from Main Condenser Main Stack I DRYWELL Discharge to from Drywell Main Stack REACTOR BUILDING Discharge to from Reactor Building Reactor Building Vent RADWASTE BUILDING Discharge to from Radwaste Building Reactor Building Vent TURBINE BUILDING Discharge to from Turbine Building Reactor Building Vent 1

 '  l No significant effect in reducing offsite doses when compared to transit time required for releases to reach SITE BOUNDARY.

Figure 4.3-1 Gaseous Effluent Treatment System Schematic 3/4-23 111

PNPS-ODCM Rev. 11 3/4.4 TOTAL DOSE 3/4.4.1 Total Dose CONTROLS 3.4.1 The dose or dose commitment to any MEMBER OF THE PUBLIC beyo,nd the SITE BOUNDARY from Pilgrim Station sources is limited to ~ 25 mrem to the total body or any organ (except the thyroid, which is limited to :::_75 mrem) over a period of any calendar year. APPLICABILITY: At all times ACTION: With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 3.2.2, 3.3.2 or 3.3.3; prepare and submit a special report to the Commission and limit the subsequent releases such that the dose or dose commitment to any MEMBER OF THE PUBLIC beyond the SITE BOUNDARY from all uranium fuel cycle sources is limited to~ 25 mrem to the total body or any organ (except thyroid, which is limited to ~ 75 mrem) over any calendar year. This special report shall include an analysis which demonstrates that radiation exposures to all members of the public from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40CFR190 standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40CFR190 standard. SURVEILLANCE REQUIREMENTS 4.4.1 Dose Calculations - Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 3.2.2, 3.3.2, and 3.3.3; and in accordance with the ODCM. BASES 3/4.4.1 Total Dose This section is provided to meet the dose limitations of 40CFR190 that have now been incorporated into 10CFR20 by 46FR 18525. The control requires the preparation and submittal of a special report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of 10CFR50, Appendix I. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC beyond the SITE BOUNDARY will exceed the dose limits of 40CFR190 if the individual reactors remain within the reporting requirement level. The special report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC beyond the SITE BOUNDARY to within the 40CFR190 limits. For the purposes of the special report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC beyond the SITE BOUNDARY from other uranium fuel cycle sources is negligible, except dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC beyond the SITE BOUNDARY is estimated to exceed the limits of 40CFR190, a request for a variance in a special report in accordance with 40CFR190.11 and 10CFR20.2203(a)(4) is considered to be a timely request and fulfills the requirements of 40CFR190 until NRG staff action is completed. This is provided that the release conditions resulting in violation of 40CFR 190 have not already been corrected. The variance only relates to the limits of 40CFR190, and does not apply in any way to the other requirements for dose limitation of 10CFR20. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in any operation that is part of the nuclear fuel cycle. 3/4-24 112

PNPS-ODCM Rev. 11 3/4.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.5.1 Environmental Monitoring Program CONTROLS 3.5.1 An environmental monitoring program shall be conducted to evaluate the effects of station operation on the environs and to verify the effectiveness of the source controls on radioactive materials The radiological environmental monitoring program shall be conducted as specified in Tables 3.5-1 through 3.5-3. APPLICABILITY: At all times. ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in Tables 3.5-1 through 3.5-3, prepare and submit to the Commission, in the Annual Radiological Environmental Monitoring Report required by Technical Specifications Administrative Control 5.6.2, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.5-4 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, a special report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Controls 3.2.2, 3.3.2, or 3.3.3.

When more than one of the radionuclides in Table 3.5-4 are detected in the sampling medium, this report shall be submitted if: Concentration (1) + Concentration (2) + ;;:: 1.0 Reporting Level (1) Reporting Level (2) When radionuclides other than those in Table 3.5-4 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Controls 3.2.2, 3.3.2, or 3.3.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Monitoring Report. 3/4-25 113

PNPS-ODCM Rev. 11 3/4.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.5.1 Environmental Monitoring Program (Continued) CONTROLS ACTION: (continued)

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.5-1, identify locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specifications Administrative Control 5.6.2, identify the cause of the unavailability of samples and identify the new location(s) obtaining replacement samples in the next Annual Radiological Environmental Monitoring Report and also include in the report the table for the ODCM reflecting the new location(s).

SURVEILLANCE REQUIREMENTS 4.5.1 The radiological environmental monitoring samples shall be collected pursuant to Tables 3.5-1 through 3.5-3 in the Offsite Dose Calculation Manual (ODCM) and shall be analyzed pursuant to the requirements of Table 3.5-1 and the detection capabilities required by Table 4.5-1.

1. Cumulative dose contributions from the current calendar year from radionuclides detected in environmental samples shall be determined in accordance with the methodology and parameters in the ODCM. These results will be reported in the Annual Radiological Environmental Monitoring Report.

BASES 3/4.5.1 Environmental Monitoring Program An environmental radiological monitoring program is conducted to verify the adequacy of in-plant controls on the release of radioactive materials. The program is designed to detect radioactivity concentrations to ensure that radiation doses to individuals do not exceed the levels set forth in 10CFR50, Appendix I. Groundwater -flow at the plant site is into Cape Cod Bay; therefore, terrestrial monitoring of groundwater is not included in this program. Detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLD). The LLD in Table 4.5-1 is considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually); Currie, L.A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry", Anal. Chem. 40, 586-93 (1968); and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). 3/4-26 114

PNPS-ODCM Rev. 11 TABLE 3.5-1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway, Sampling, Sampling, Sample, or Measurement, Measurement, Type and Frequency Measurement and/or Collection and/or Collection of Analysis or Type Locations( 1l Frequency Measurement DIRECT RADIATION Environmental TLD 110 Locations, Quarterly Collection Gamma exposure <2l; See Table 3.5-2 Quarterly AIRBORNE Particulates 11 Locations, Continuous sampling with Gross beta radioactivity See Table 3.5-3 particulate filter; analysis 24 hours or Weekly Collection more after weekly filter change (3l; Weekly AND Gamma isotopic (4l of composite by location; Quarterly Radioiodines 11 Locations, Continuous sampling with 1-131 analysis; Weekly See Table 3.5-3 charcoal cartridge; Weekly Collection TERRESTRIAL Green Leafy Vegetables Plymouth County Farm(5 J, At time of harvest Gamma isotopic Bridgewater Farm analysis (4> on edible Control <5> portions Cranberries Manomet Point Bog, At time of harvest Gamma isotopic Bartlett Rd. Bog, analysis <4l on edible Pine St. Bog Control (5> portions 3/4-27 115

PNPS-ODCM Rev. 11 TABLE 3.5-1 (continued) OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway, Sampling, Sampling, Sample, or Measurement, Measurement, Type and Frequency Measurement and/or Collection and/or Collection of Analysis or Type Locations<1> Freauency Measurement MARINE/AQUATIC Surface Water <7> Discharge Canal, Continuous Composite Gamma isotopic <4 >, Sample analysis of monthly

                     ---------------------------------- ----------------------------------    composite samples; Bartlett Pond,                      Weekly grab sample                   AND Powder Point Control <5>                                                 H-3 analysis of quarterly composite samples Sediment              Discharge Canal Outfall,            Semiannual Collection                Gamma isotopic Manomet Point,                                                           analysis <4 >

Plymouth Beach, Plymouth Harbor, Duxbury Bay Control <5> 5 Green Harbor Control < > Irish Moss (Algae) Discharge Canal Outfall, Semiannual Collection Gamma isotopic Manomet Point, analysis <4> Ellisville, 5 Brant Rock Control < > Mussels Discharge Canal Outfall, Semiannual Collection Gamma isotopic Plymouth Harbor, analysis <4> on edible Green Harbor Control <5> portions Soft-shelled clams Plymouth Harbor, Semiannual Collection Gamma isotopic Duxbury Bay Control <5> analysis <4> on edible portions Lobster Discharge Canal Outfall Four times per season, Gamma isotopic from May through analysis <4> on edible October portions 5 Offshore Control < > Once per season 8 Fishes Discharge Canal Outfall Semiannual for Group 1< >; Gamma isotopic annually in season for analysis <5> on edible Groups II, Ill, and IV 18> portions

                     ----------------------------------  Annuallr for each Offshore Control <3>                group 18 ;

3/4-28 116

PNPS-ODCM Rev. 11 TABLE 3.5-1 (continued) NOTES (1) Specific parameters of distance and direction sector from centerline of the reactor, and additional description where pertinent, are provided for each sample location in Table 3.5-1 in a subsequent tables and figures in the ODCM. Deviation are permitted from the required sampling schedule if samples are unobtainable due to circumstances such as hazardous conditions, extreme inclement weather, seasonable unavailability, and malfunction of automatic sampling equipment. If samples are unobtainable due to sampling equipment malfunction, efforts shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to PNPS Technical Specification Administrative Control 5.6.2. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program outlined in ODCM Table 3.5-1 and subsequent tables. Pursuant to PNPS Technical Specification Administrative Control 5.5.1, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including revised figure(s) and table(s) for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for the pathway and justifying the selection of the new location(s) for obtaining samples. (2) Minimum sensitivity for TLD exposure measurements is 1 µR/hr, or 2.19 mR/standard quarter. (3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow of radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. (4) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. (5) These locations may be altered in accordance with results of land use census surveys discussed in Effluent Control 4.5.2. (6) Indicates control location. (7) Groundwater flow at the plant site is into Cape Cod Bay; therefore, terrestrial monitoring of groundwater and/or drinking water is not included in this program. (8) Fish analyses will be performed on samples from each of the following groups: I. Bottom Oriented II. Near Bottom Ill. Anadromous IV. Coastal Migrato!Y Distribution Winter Flounder Tautog Alewife Bluefish Yellowtail Flounder Gunner Rainbow Smelt Atlantic Herring Atlantic Cod Striped Bass Atlantic Menhaden Pollock Atlantic Mackerel Hakes 3/4-29 117

PNPS-ODCM Rev. 11 TABLE 3.5-2 ENVIRONMENTAL TLD LOCATIONS TLD Station Location 1 TLD Station LocationP> Descriotion Code Distance/Direction Descriotion Code Distance/Direction TLDs Within Protected Area Zone 1 TLDs: 0-3 km O&M/RXB. BREEZEWAY P21 50 m SE EMERSON ROAD EM 1.53 km SSE EXEC.BUILDING P24 57 m w EMERSON/PRISCILLA EP 1.55 km SE FENCE-R SCREENHOUSE P04 66 m N ACCESS ROAD AR 1.59 km SSE O&M - 2ND W WALL P20 67 m SE BAYSHORE BS 1.76 km w EXEC.BUILDING LAWN P25 76 m WNW STATION E E 1.86 km s FENCE-WATER TANK P05 81 m NNE JOHN GAULEY JG 1.99 km w FENCE-OIL STORAGE P06 85 m NE STATION J J 2.04 km SSE O&M - 2ND SW CORNER P19 86 m s WHITEHORSE ROAD WH 2.09 km SSE O&M -1ST SW CORNER P18 90 m s PLYMOUTH YMCA RC 2.09 km WSW COMPRESSED GAS STOR P08 92 m E STATION K K 2.17 km s FENCE-L SCREENHOUSE P03 100 m NW TAYLOR/THOMAS TT 2.26 km SE FENCE-EXEC.BUILDING P17 107 m w YANKEE VILLAGE YV 2.28 km WSW O&M - 2ND S WALL P23 121 m ENE GOODWIN PROPERTY GN 2.38 km SW FENCE-INTAKE BAY P07 121 m SSE RIGHT OF WAY RW 2.83 km s FENCE-WAREHOUSE

P26 134 m ESE TAYLOR/PEARL TP 2.98 km SE FENCE-SHOREFRONT P02 135 m NW FENCE-W BOAT RAMP P09 136 m E Zone 2 TLDs: 3-8 km O&M - 2ND N WALL P22 137 m SE VALLEY ROAD VR 3.26 km SSW FENCE-W SWITCHYARD P16 172 m SW MANOMET ELEM ME 3.29 km SE FENCE-TCF GATE P11 183 m ESE WARREN/CLIFFORD WC 3.31 km w FENCE-TCF/BOAT RAMP P27 185 m ESE RT.3A/BARTLETT RD BB 3.33 km SSE FENCE-ACCESS GATE P12 202 m SE MANOMET POINT MP 3.57 km SE FENCE-E SWITCHYARD P15 220 m s MANOMET SUBSTATION MS 3.60 km SSE FENCE-TCF/INTAKE BAY P10 223 m E BEACHWOOD ROAD BW 3.93 km SE FENCE-MEDICAL BLDG. P13 224 m SSE PINES ESTATE PT 4.44 km SSW FENCE-BUTLER BLDG P14 228 m s EARL ROAD EA 4.60 km SSE FENCE-TCF/PRKNG LOT P28 259 m ESE S PLYMOUTH SUBST SP 4.62 km w ROUTE 3 OVERPASS RP 4.81 km SW Zone 1 TLDs: 0-3 km RUSSELL MILLS RD RM 4.85 km WSW BOAT LAUNCH WEST 'l BLW 0.11 km E HILLDALE ROAD HD 5.18 km w OVERLOOK AREA OA 0.15 km w MANOMET BEACH MB 5.43 km SSE HEALTH CLUB TC 0.15 km WSW BEAVERDAM ROAD BR 5.52 km s BOAT LAUNCH EAST BLE 0.16 km ESE PLYMOUTH CENTER PC 6.69 km w PEDESTRIAN BRIDGE PB 0.21 km N LONG POND/DREW RD LO 6.97 km WSW ISFSI DOSE #3 ISF-3 0.21 km w HYANNIS ROAD HR 7.33 km SSE SHOREFRONT SECURITY P01 0.22 km NNW MEMORIAL HALL MH 7.58 km WNW MEDICAL BUILDING ws 0.23 km SSE SAQUISH NECK SN 7.58 km NNW ISFSI DOSE #2 ISF-2 0.29 km w COLLEGE POND CP 7.59 km SW PARKING LOT CT 0.31 km SE '

ISFSI DOSE #1 ISF-1 0.35 km SW ! SHOREFRONT PARKING PA 0.35 km NNW Zone 3 TLDs: 8-15 km STATION A A 0.37 km WSW DEEP WATER POND ow 8.59 km w STATION F F 0.43 km NW LONG POND ROAD LP 8.88 km SSW STATION B B 0.44 km s NORTH PLYMOUTH NP 9.38 km WNW EAST BREAKWATER EB 0.44 km ESE STANDISH SHORES ss 10.39 km NW PNPS MET TOWER PMT 0.44 km WNW ELLISVILLE ROAD EL 11.52 km SSE STATION H H 0.47 km SW UP COLLEGE POND RD UC 11.78 km SW STATION I I 0.48 km WNW SACRED HEART SH 12.92 km w STATION L L 0.50 km ESE KING CAESAR ROAD KC 13.11 km NNW STATION G G 0.53 km w BOURNE ROAD BE 13.37 km s STATION D D 0.54 km NW SHERMAN AIRPORT SA 13.43 km WSW PROPERTY LINE PL 0.54 km NNW STATION C C 0.57 km ESE HALL'S BOG HB 0.63 km SE GREENWOOD HOUSE GH 0.65 km ESE Zone 4 TLDs: >15 km(iJ W ROCKY HILL ROAD WR 0.83 km WNW CEDARVILLE SUBST cs 15.93 km s E ROCKY HILL ROAD ER 0.89 km SE KINGSTON SUBST KS 16.15 km WNW MICROWAVE TOWER MT 1.03 km SSW LANDING ROAD LR 16.46 km NNW CLEFT ROCK CR 1.27 km SSW CHURCH/WEST cw 16.56 km NW BAYSHORE/GATE RD BO 1.34 km WNW MAIN/MEADOW MM 17.02 km WSW MANOMET ROAD MR 1.38 km s DIV MARINE FISH DMF 20.97 km SSE DIRT ROAD DR 1.48 km SW EAST WEYMOUTH SUBST EW 39.69 km NW 1 ( ) Distance and direction are measured from the centerline of the Reactor Building to the monitoring location. (Z) Indicates control locations. 3/4-30 118

PNPS-ODCM Rev. 11 TABLE 3.5-3 ROUTINE RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Description No. Code Distance Direction Air Particulate Filters; Charcoal Cartridges Overlook Area 08 OA 0.1 km w Pedestrian Bridge 07 PB 0.2 km N Medical Building 00 ws 0.2 km SSE East Breakwater 09 EB 0.5 km ESE Property Line 06 PL 0.5 km NNW West Rocky Hill Road 03 WR 0.8 km WNW East Rocky Hill Road 01 ER 0.9 km SE Cleft Rock 10 CR 1.3 km SSW Manomet Substation 17 MS 3.6 km SSE Plymouth Center 15 PC 6.7 km w East Weymouth Control 21 EW 40 km NW Vegetation (1> Plymouth County Farm 11 CF 5.6 km w Bridgewater Farm Control 27 BF 31 km w Cranberries Manomet Point Bog 13 MR 3.9 km SE Bartlett Road Bog 14 BT 4.3 km SSE Pine Street Bog Control 23 PS 26 km WNW 1 ( l Additional samples of vegetables/vegetation will be collected each year at or near selected gardens identified during the most recent land use census. The locations of these selected gardens are listed in the station procedure describing crop sampling. 3/4-31 119

PNPS-ODCM Rev. 11 TABLE 3.5-3 (CONTINUED) ROUTINE RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Description No. Code Distance Direction Surface Water Discharge Canal 11 DIS 0.2 km N Bartlett Pond 17 BP 2.7 km SE Powder Point Control 23 pp 13 km NNW Sediment Discharge Canal Outfall 11 DIS 0.8 km NE Manomet Point 15 MP 3.3 km ESE Plymouth Beach 14 PLB 4.0 km WNW Plymouth Harbor 12 Ply-H 4.1 km w Duxbury Bay Control 13 Dux-Bay 14 km NNW Green Harbor Control 24 GH 16 km NNW Irish Moss Discharge Canal Outfall 11 DIS 0.7 km NNE Manomet Point 15 MP 4.0 km ESE Ellisville 22 EL 12 km SSE Brant Rock Control 34 BR 18 km NNW Mussels Discharge Canal Outfall 11 DIS 0.7 km NNE Plymouth Harbor 12 Ply-H 4.1 km w Green Harbor Control 24 GH 16 km NNW Soft-shelled Clams Plymouth Harbor 12 Ply-H 4.1 km w Duxbury Bay Control 13 Dux-Bay 13 km NNW Lobster Discharge Canal Outfall 11 DIS 0.5 km N Duxbury Bay Control 13 Dux-Bay 11 km NNW Fishes Discharge Canal Outfall 11 DIS 0.5 km N Jones River Control 30 JR 13 km WNW Cape Cod Bay Control 98 CC-Bay 24 km ESE Buzzard's Bay Control 90 BB 40 km SSW Priest Cove Control 29 PC 48 km SW Vineyard Sound Control 92 MV 64 km SSW 1 <l Additional samples of vegetables/vegetation will be collected each year at or near selected gardens identified during the most recent land use census. The locations of these selected gardens are listed in the station procedure describing crop sampling. 3/4-32 120

PNPS-ODCM Rev. 11 Figure 3.5-1 Environmental TLD Locations Within the PNPS Protected Area

                                       .        TLD Station                   Location*

Description i Code Distance/Direction TLDs Within Protected Area O&M/RXB. BREEZEWAY EXEC.BUILDING I P21 P24 50 57 m m SE w FENCE-R SCREENHOUSE P04 66 m N O&M - 2ND W WALL P20 67 m SE EXEC.BUILDING LAWN P25 76 m WNW FENCE-WATER TANK P05 81 m NNE FENCE-OIL STORAGE P06 85 m NE O&M - 2ND SW CORNER P19 86 m s O&M - 1ST SW CORNER P18 90 m s COMPRESSED GAS STOR P08 92 m E FENCE-L SCREENHOUSE

P03 100 m NW FENCE-EXEC.BUILDING P17 107 m w O&M - 2ND S WALL P23 121 m ENE FENCE-INTAKE BAY P07 121 m SSE FENCE-WAREHOUSE P26 134 m ESE FENCE-SHOREFRONT P02 135 m NW FENCE-W BOAT RAMP P09 136 m E O&M - 2ND N WALL P22 137 m SE FENCE-W SWITCHYARD P16 172 m SW FENCE-TCF GATE P11 183 m ESE FENCE-TCF/BOAT RAMP P27 185 m ESE FENCE-ACCESS GATE P12 202 m SE FENCE-E SWITCHYARD P15 220 m s FENCE-TCF/INTAKE BAY P10 223 m E FENCE-MEDICAL BLDG. P13 224 m SSE FENCE-BUTLER BLDG i P14 228 m s FENCE-TCF/PRKNG LOT t P28 259 m ESE
Distance and direction are measured from the centerline of the Reactor Building to the monitoring location.

3/4-33 121

PNPS-ODCM Rev. 11 Figure 3.5-1 (continued) Environmental TLD Locations Within the PNPS Protected Area 3/4-34 122

PNPS-ODC M Rev. 11 Figure 3.5-2 TLD and Air Sampling Locations: Within 1 Kilometer TLD Station ................~IJ.C::<3.t.i_<l_~.: ....................................... Air..Sampling.Station .........................................~IJ.C::<3.t.i_<l_~.: .............. Descriotion ! Code Distance/Direction Description ! Code Distance/Direction Zone 1 TLDs : 0-3 km BOAT LAUNCH WEST BLW 0.11 km E OVERLOOK AREA OA 0.15 km w OVERLOOK AREA OA 0.15 km w PEDESTRIAN BRIDGE PB 0.21 km N HEALTH CLUB TC 0.15 km WSW MEDICAL BUILDING ws 0.23 km SSE BOAT LAUNCH EAST BLE 0.16 km ESE EAST BREAKWATER EB 0.44 km ESE PEDESTRIAN BRIDGE PB 0.21 km N PROPERTY LINE PL 0.54 km NNW ISFSI DOSE #3 ISF-3 0.21 km w W ROCKY HILL ROAD WR 0.83 km WNW SHOREFRONT SECURITY P01 0.22 km NNW E ROCKY HILL ROAD ER 0.89 km SE MEDICAL BUILDING ws 0.23 km SSE ISFSI DOSE #2 ISF-2 0.29 km w PARKING LOT CT 0.31 km SE ISFSI DOSE #1 ISF-1 0.35 km SW SHOREFRONT PARKING PA 0.35 km NNW STATION A A 0.37 km WSW STATION F F 0.43 km NW STATION B B 0.44 km s EAST BREAKWATER EB 0.44 km ESE PNPS MET TOWER PMT 0.44 km WNW STATION H H 0.47 km SW STATION I I 0.48 km WNW STATION L L 0.50 km ESE STATION G G 0.53 km w STATION D D 0.54 km NW PROPERTY LINE PL 0.54 km NNW STATION C C 0.57 km ESE HALL'S BOG HB 0.63 km SE GREENWOOD HOUSE GH 0.65 km ESE W ROCKY HILL ROAD WR 0.83 km WNW E ROCKY HILL ROAD ER 0.89 km SE

Distance and direction are measured from the centerline of the Reactor Building to the monitoring location .

3/4-35 123

PNPS-ODCM Rev. 11 Figure 3.5-2 (continued) TLD and Air Sampling Locations: Within 1 Kilometer 3/4-36 124

PNPS-ODCM Rev. 11 Figure 3.5-3 TLD and Air Sampling Locations: 1 to 5 Kilometers TLD Station Location* Location*

                                                               ....................... Air.Samplin9... Station .......................... *****************************************************

Description ! Code Distance/Direction Description ' Code Distance/Direction Zone 1 TLDs: 0-3 km MICROWAVE TOWER MT 1.03 km SSW CLEFT ROCK ' CR 1.27 km SSW CLEFT ROCK CR 1.27 km SSW MANOMET SUBSTATION 1 MS 3.60 km SSE BAYSHORE/GATE RD BO 1.34 km WNW MANOMET ROAD MR 1.38 km s DIRT ROAD DR 1.48 km SW EMERSON ROAD EM 1.53 km SSE EMERSON/PRISCILLA EP 1.55 km SE ACCESS ROAD AR 1.59 km SSE BAYSHORE BS 1.76 km w STATION E E 1.86 km s JOHN GAULEY JG 1.99 km w STATION J J 2.04 km SSE WHITEHORSE ROAD WH 209 km SSE PLYMOUTH YMCA RC 2.09 km WSW STATION K K 2.17 km s TAYLOR/THOMAS TT 2.26 km SE YANKEE VILLAGE YV 2.28 km WSW GOODWIN PROPERTY GN 2.38 km SW RIGHT OF WAY RW 2.83 km s TAYLOR/PEARL TP 2.98 km SE Zone 2 TLDs : 3-8 km VALLEY ROAD VR 3.26 km SSW MANOMET ELEM ME 3.29 km SE WARREN/CLIFFORD WC 3.31 km w RT.3A/BARTLETT RD BB 3.33 km SSE MANOMET POINT MP 3.57 km SE MANOMET SUBSTATION MS 3.60 km SSE BEACHWOOD ROAD BW 3.93 km SE PINES ESTATE PT 4.44 km SSW EARL ROAD EA 4.60 km SSE S PLYMOUTH SUBST SP 4.62 km w ROUTE 3 OVERPASS RP 4.81 km SW RUSSELL MILLS RD RM 4.85 km WSW

Distance and direction are measured from the centerline of the Reactor Building to the monitoring location .

3/4-37 125

PNPS-ODCM Rev. 11 Figure 3.5-3 (continued) TLD and Air Sampling Locations: 1 to 5 Kilometers 3/4-38 126

PNPS-ODCM Rev. 11 Figure 3.5-4 TLD and Air Sampling Locations: Greater Than 5 Kilometers TLD Station Location* Location*

                                        ***************************************************** ............. Air.Sampling .Station ..............*....................... .....................................................

Description ! Code Distance/Direction Description ! Code Distance/Direction Zone 2 TLDs : 3-8 km ' HILLDALE ROAD HD 5.18 km w PLYMOUTH CENTER PC 6.69 km w MANOMET BEACH MB 5.43 km SSE EAST WEYMOUTH SUBST EW 39.69 km NW BEAVERDAM ROAD BR 5.52 km s PLYMOUTH CENTER PC 6.69 km w LONG POND/DREW RD LO 6.97 km WSW HYANNIS ROAD HR 7.33 km SSE MEMORIAL HALL MH 7.58 km WNW SAQUISH NECK SN 7.58 km NNW COLLEGE POND CP 7.59 km SW Zone 3 TLDs : 8-15 km DEEP WATER POND ow 8.59 km w LONG POND ROAD LP 8.88 km SSW NORTH PLYMOUTH NP 9.38 km WNW STANDISH SHORES ss 10.39 km NW ELLISVILLE ROAD EL 11.52 km SSE UP COLLEGE POND RD UC 11 .78 km SW SACRED HEART SH 12.92 km w KING CAESAR ROAD KC 13.11 km NNW BOURNE ROAD BE 13.37 km s SHERMAN AIRPORT SA 13.43 km WSW Zone 4 TLDs : >15 km CEDARVILLE SUBST cs 15.93 km s KINGSTON SUBST KS 16.15 km WNW LANDING ROAD LR 16.46 km NNW CHURCH/WEST cw 16.56 km NW MAIN/MEADOW MM 17.02 km WSW DIV MARINE FISH DMF 20 .97 km SSE EAST WEYMOUTH SUBST EW 39 .69 km NW

Distance and direction are measured from the centerline of the Reactor Building to the monitoring location .

3/4-39 127

PNPS-ODCM Rev. 11 Figure 3.5-4 (continued) TLD and Air Sampling Locations: Greater Than 5 Kilometers 3/4-40 128

PNPS-ODCM Rev. 11 Figure 3.5-5 Terrestrial and Marine/Aq uatic Sampling Locations Description Cod Distance/Direction* Description Code Distance/Direction* e FORAGE SURFACE WATER Whipple Farm WH 2.9 km SW Discharg e Canal DIS 0.2 km N Plymouth County Farm CF 5.6 km w Bartlett Pond BP 2.7 km SE Whitman Farm Control WF 34 km WNW Powder Point Control pp 13 km NNW VEGETABLESNEGETATION SEDIMENT Plymouth County Farm CF 5.6 km w Discharge Canal Outfall DIS 0.8 km NE Bridgewater Farm Control BF 31 km w Manomet Point MP 3.3 km ESE Plymouth Beach PLB 4.0 km WNW CRANBERR IES Plymouth Harbor PLY-H 4.1 km w Manomet Point Bog MR 3.9 km SE Duxbury Bay Control DUX-BAY 14 km NNW Bartlett Road Bog BT 4.3 km SSE Green Harbor Control GH 16 km NNW Pine Street Bog Control PS 26 km WNW IRISH MOSS Discharge Canal Outfall DIS 0.7 km NNE Manomet Point MP 4.0 km ESE Ellisville EL 12 km SSE Brant Rock Contro l BK 18 km NNW MUSSELS Discharge Canal Outfall DIS 0.7 km NNE Plymouth Harbor PLY-H 4.1 km w Green Harbor Control GH 16 km NNW SOFT-SHELLED CLAM S Plymouth Harbor PLY-H 4.1 km w Duxbury Bay Control DUX-BAY 13 km NNW LOBSTER Discharge Canal Outfall DIS 0.5 km N Duxbury Bay Control DUX-BAY 11 km NNW FISHES Discharge Canal Outfall DIS 0.5 km N Plymouth Beach PLB 4.0 km w Jones River Control JR 13 km WNW Cape Cod Bay Control CC-BAY 24 km ESE N River-Hanover Control NR 24 km NNW Cataumet Control CA 32 km SSW Provincetown Control PT 32 km NE Buzzards Bay Control BB 40 km SSW Priest Cove Control PC 48 km SW Nantucket Sound Control NS 48 km SSE Atlantic Ocean Control AO 48 km E Vineyard Sound Control MV 64 km SSW

Distance and direction are measured from the centerline of the Reactor Building to the sampling/monitoring location.

3/4-41 129

PNPS-ODCM Rev. 11 Figure 3.5-5 (continued) Terrestrial and Marine/Aquatic Sampling Locations 24KIL0METERS

                                                                          \ NORTH-NORTHWEST SYMBOL KEY 0        ~iE~tUi~USSEL)

(S SOFT-SHELL) (H HARD-SHELL) Q IRISH MOSS c:::::r LOBSTER 0 FISHES

                                                                                                      '[) SURFACE WATER
        ' A E_j ~

{.3i 34 KILOMETERS WEST-NORTHWEST D O D SEDIMENT cRANBERRY VEGETATION '-.4 26KILOMETERS

      '{}" WEST -NORTHWEST 0        MILK 0,-----~MIL =r=E= S ---;2 SCALE

-a-@ CAPE COD BAY 31 KILOMETERS WEST

32 KILOMETERS NORTHEAST EAST

~-

48 Ktl..OME.TERS P WHITEHORSE BEACH

                                                                                                                                 @;:-BAY 24 KUDMETERS CARVER                                                                                                  EAST.SOUTHEAST
                                       \
                                          \
                                            \
                                              \                    PLYMOUTH
                                                \       #,f,
                                                  \~
                                                 ~
             ~ 48 KILOMETERS            /
    /             SOUTHWEST
<<l KILOMETERS               64 KILOMETERS          32 KILOMETERS r

SOUTH-SOUTHWESr SOUTH-SOUTHWEST SOUTH-SOUTHWEST

                                  ~                       ~

I I 3/4-42 130

PNPS-ODCM Rev. 11 Figure 3.5-6 Enviro nmental Sampl ing And Measu rement Control Locations Description Code Distance/Direction* Description Code Distance/Direction* TLD SURFACE WATER Cedarville Substation cs 16 km s Powder Point Control pp 13 km NNW Kingston Substation KS 16 km WNW Landing Road LR 16 km NNW SEDIMENT Church & West Street cw 17 km NW Duxbury Bay Control DU X-BAY 14 km NNW Main & Meadow Street MM 17 km WSW Green Harbor Control GH 16 km NNW Div. Marine Fisheries DMF 21 km SSE East Weym outh EW 40 km NW IRISH MOSS Substation Brant Rock Control BK 18 km NNW A IR SAM PLI NG East Weymouth EW 40 km NW MUSSELS Substation Green Harbor Control GH 16 km NNW SOFT-SHELLED CLAMS Duxbury Bay Control DUX- BAY 13 km NNW LOBSTER Duxbury Bay Control DUX-BAY 11 km NNW FISHES VEGETABLESNEGETATION Jones River Control JR 13 km W NW Bridgewater Farm Control BF 31 km w Cape Cod Bay Control CC-BAY 24 km ESE N River-Hanover Control NR 24 km NNW CRANBERR IES Cataumet Control CA 32 km SSW Pine Street Bog Control PS 26 km WNW Provin cetown Control PT 32 km NE Buzzards Bay Control BB 40 km SSW Priest Cove Control PC 48 km SW Nantucket Sound Control NS 48 km SSE Atlantic Ocean Control AO 48 km E Vineyard Sound Control MV 64 km SSW

Distance and direction are measured from the cente rline of the Reactor Build ing to the sampling/monitori ng location.

3/4-43 131

PNPS-ODCM Rev. 11 Figure 3.5-6 (continued) Environmental Sampling And Measurement Control Locations SYMBOL KEY LJ SHELLFISH (M BLUE MUSSEL) (S SOFT-SHELL CLAM) (H HARD-SHELL CLAM) 0 IRlSHMOSS D LOBSTER MASSACHUSETTS BAY a FISHES 0 SURFACE WATER D SEDIMENT 0 CRANBERRY EJ VEGETATION/FORAGE

                                            ,/             0 0

MILK TID D AIR SAMPLER 0 MILES 10 SCALE CAPE COD BAY

                                                                ~     BAY BUZZARD'S BAY NANTUCKET SOUND 3/4-44 132

PNPS-ODCM Rev. 11 TABLE 3.5-4 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate Water or Gases Fish Milk Food Products Analysis pCi/L pCi/m 3 pCi/kg, wet pCi/L pCi/kg, wet H-3 30,000 (1) -- -- -- -- Mn-54 1,000 -- 30,000 -- -- Fe-59 400 -- 10,000 -- -- Co-58 1,000 -- 30,000 -- -- Co-60 300 -- 10,000 -- -- Zn-65 300 -- 20,000 -- -- Zr-95 400 -- -- -- -- Nb-95 400 -- -- -- -- 1-131 20 (1) 0.9 -- 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-140 200 -- -- 300 -- La-140 200 -- -- 300 -- 1 ' l Value adjusted for fact that no drinking water pathway exists at Pilgrim Station. 3/4-45 133

PNPS-ODCM Rev. 11 TABLE 4.5-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)( 1l Airborne Marine and Surface Particulate Aquatic Food Water or Gases Foods Milk Products Sediment 3 Analysis pCi/L pCi/m pCi/kQ,wet pCi/L pCi/kQ,wet

pCi/kQ,dry Gross Beta -- 0.01 -- -- -- --

H-3 3000 (2) -- -- -- -- -- Mn-54 15 -- 130 -- -- -- Fe-59 30 -- 260 -- -- -- Co-58 15 -- 130 -- -- -- Co-60 15 -- 130 -- -- -- Zn-65 30 -- 260 -- -- -- Zr-95 30 -- -- -- -- -- Nb-95 15 -- -- -- -- -- 1-131 15 (2) 0.07 -- 1 60 -- Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 -- -- 60 -- -- La-140 15 -- -- 15 -- -- 1 ( l Refer to Appendix B of the ODCM for definition of lower limit of detection (LLD). 2 ( l Value adjusted for fact that no drinking water pathway exists at Pilgrim Station. 3/4-46 134

PNPS-ODCM Rev. 11 3/4.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.5.2 Land Use Census CONTROLS 3.5.2 A land use census shall be conducted and shall identify, within a distance of 8 km (5 miles), the location in each of the 16 meteorological sectors of the nearest milk 2 animal, the nearest residence and the nearest garden of greater than 50 m 2 (500 ft ) producing broad leaf vegetation. For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify, within a distance of 5 km (3 miles), the locations in each of the 16 2 meteorological sectors of fill milk animals and fill gardens of greater than 50 m producing broad leaf vegetation. APPLICABILITY: At all times. ACTION:

a. With a land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Control 4.3.3, identify the new location(s) in the next Annual Radiological Environmental Monitoring Report.

b. With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Control 3.5.1, add the new location(s) to the Radiological Environmental Monitoring Program within 30 days. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted: Identify the new location(s) in the next Annual Radiological Environmental Monitoring Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

SURVEILLANCE REQUIREMENTS 4.5.2 The land use census shall be conducted during the growing season, at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Monitoring Report. Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of the two different direction sectors with the highest predicted D/Qs, in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.5-1 shall be followed, including analysis of control samples. BASES 3/4.5.2 Land Use Census This section is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-3/4-47 135

PNPS-ODCM Rev. 11 door survey, from aerial survey, or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of 10CFR50, Appendix I, Section IV.B.3. Restricting the 2 census to gardens of greater than 50 m provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored, since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: 1) 20% of the garden was used for growing broad leaf vegetation (i.e., 2 similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m . 3/4-48 136

PNPS-ODCM Rev. 11 5.0 RADIOLOGICAL EFFLUENT CONTROLS CROSS REFERENCE Table 5-1 presents a summary of the limits contained in the PNPS Effluent Controls, Sections 3/4.2.1, 3/4.2.2, 3/4.2.3, 3/4.3.1, 3/4.3.2, 3/4.3.3, and 3/4.4.1. This table also presents cross-references to applicable portions of Methodology Section 9.0. This table is intended to serve as a summary of the PNPS Effluent Controls and does not, in itself, establish limits. The specific effluent controls presented in Section 3/4 should be consulted for exact wording and specifics. 5-1 137

PNPS-ODCM Rev. 11 TABLE 5-1 PNPS EFFLUENT CONTROLS AND METHODOLOGY CROSS-REFERENCE Effluent Control Methodology Applicable Limit Exposure Section. Section ' or Objective Period . i Required Action 3/4.2.1 l 10CFR20, App. B, Table 2 Liquid Effluent 9.1 Column 2, and Instantaneous Restore concentration to 4 Concentration 2x10- µCi/ml for dissolved within limits noble gases 3/4.2.2 1.5 mrem T.B. Calendar Dose- Liquids 9.2 5 mrem Organ Quarter 30-day report if exceeded 3 mrem T.B. Calendar Year 10 mrem Organ 3/4.2.3 0.06 mrem T.B. Projected for Operate Liquid Waste Liquid Radwaste 9.2 0.2 mrem Organ 31 days Treatment System Treatment 3/4.3.1 9.3.1.3 500 mrem/yr T.B. from Gaseous Noble Gases Instantaneous Restore release rates to Effluents ------------------- ****************************************** within specifications Dose Rate 9.3.1.4 3000 mrem/yr Skin from Noble Gases

                        9.3.2            1500 mrem/yr Organ from
                  ~

l particulates with T% > 8d., 1-131, 1-133 and tritium 3/4.3.2 5 mrad gamma air Calendar Dose- 9.3.1.1 and 10 mrad beta air Quarter 30-day report if exceeded Noble Gases 9.3.1.2 ****************************************** ********************** 10 mrad gamma air Calendar Year 20 mrad beta air 3/4.3.3 7.5 mrem Organ Calendar Dose-1-131, 9.3.2 Quarter 30-day report if exceeded 1-133 ****************************************** ********************** Particulates, H-3 15 mrem Organ Calendar Year 3/4.4.1 9.2, 9.3.1, 25 mrem T.B. Calendar Year 30-day report if controls Total Dose 9.3.2, and 9.4 25 mrem Organ 3/4.2.2, 3/4.3.2, or 3/4.3.3 75 mrem Thyroid are exceeded by a factor of

2. Restore dose to public to within the applicable EPA limit(s) or obtain a

                  !                                                                                                        variance.

NOTE: T.B. means total body. 5-2 138

PNPS-ODCM Rev. 11

6.0 DESCRIPTION

OF RADWASTE SYSTEMS 6.1 Liquid Radwaste System Liquid wastes from Pilgrim Station originates from a variety of sources which have a considerable disparity in chemical and radio-chemical composition and concentration (see section 9.2 of Reference 3). Normally these wastes are collected and treated separately. The liquid wastes fall into the following categories:

1) High Purity

2) Low Purity

3) Detergent High purity clean wastes are typically characterized by having variable solids content, low conductivity, and variable radioactivity. They come from equipment drain sumps, ultrasonic resin cleaner (URC) operation, and the backwash and resin transfer water used to change out the condensate demineralizers. Reuse of processed high-purity waste is highly desirable.

Low purity chemical wastes have moderate conductivity and solids. content. They come from building floor sumps and are generally high-purity wastes which have been contaminated by dirt, oil, etc. When processed, this stream may or may not be reused depending on the water balance in the plant and the quality of the product. Detergent wastes are low radioactivity concentration wastes that have the potential to contain detergents. This waste is generated from washing and decontamination of equipment, the plant, and personnel. This detergent waste is collected in the miscellaneous waste tank and is not treatable. The waste is passed through strainers, prior to discharge through the radwaste discharge header and into the circulating water discharge canal. A schematic of the system as determined in Reference 4 is shown in Figure 4.2-1, in Section 3/4.2. In the system, the high purity waste is collected in one of two 15,000-gal clean waste tanks. Low purity waste is collected in one of two 15,000 gallon chemical waste tanks. This low purity waste is batched to the clean waste tanks where both types of waste are processed through a mixed bed ion exchange demineralizer. The processed liquid is collected in one of four 18,000 gal treated water holdup tanks. It is reused to the greatest extent possible. 6.2 Treated Gaseous Radwaste System The air ejector and augmented offgas system (see Section 9.4 of Reference 3) includes the subsystems that process and/or dispose of the gases from the main condenser air ejectors, the startup mechanical vacuum pump, and the gland seal condensers. All such gases from the unit are routed to the main stack for dilution and elevated release to the atmosphere. Discharges from the air ejector, the charcoal vault, and the stack are continuously monitored by radiation monitors. Gases routed to the main stack include air ejector and gland seal offgases, and gases from the standby gas treatment system (SGTS). Dilution air input to the stack is supplied by one of two fans located in the filter building at the base of the main stack. The stack is designed such that prompt mixing of all gas inlet streams occurs in the base to allow location of sample points as near the base as possible. 6-1 139

PNPS-ODCM Rev. 11 The augmented offgas system uses a high temperature catalytic recombiner to recombine radiolytically dissociated hydrogen and oxygen from the air ejector system. Noncondensable radioactive offgas is continuously removed from the main condenser by the air ejector during plant operation. The air ejector offgas normally contains activation gases, principally N-16, 0-19, and N-13. The N-16 and 0-19 have short half-lives and quickly decay. The 10 min half-life N-13 is present in small amounts which is further reduced by decay. The air ejector offgas also contains Sr-90, Ba-140, and Cs-137. After hydrogen/oxygen recombination and chilling to strip the condensable to reduce the volume, the remaining noncondensables, principally the kryptons, xenons, and air, are delayed in a 30 minute holdup system before reaching the adsorption bed. Radioactive particulate daughters of the noble gases are retained on the HEPA filters and on the charcoal. The charcoal adsorption bed, operating in a constant temperature vault, selectively adsorbs and delays the xenons and kryptons from the bulk carrier gas, principally air. This delay on the charcoal permits the xenons and kryptons to decay in place. The offgas is discharged to the environs via the main stack. The activity of the gas leaving the offgas treatment system is continuously monitored as described in Section 7.2.2. This system results in a reduction of the offgas activity (Curies) released by factor of approximately 185 relative to a 30 minute holdup system. The system as determined in Reference 4 for handling gaseous waste is shown in Figure 4.3-1, in Section 3/4.3. 6-2 140

PNPS-ODCM Rev. 11 7.0 RELEASE POINT AND MONITOR DESCRIPTION 7.1 Radioactive Effluent Release Point Description (Reference 3) 7.1.1 Liquid Radioactive Waste Effluent Release The liquid radwaste discharge header receives discharge from the chemical radwaste monitor tank pumps, the clean radwaste treated water transfer pumps, and the miscellaneous waste drain tank pump (see Figure 4.2-1). The header provides controlled discharge through either a low flow discharge path or a high flow discharge path. The high flow path is normally used with a variable liquid radwaste effluent flow from 1-200 gpm. The common discharge header extends from both the low and high flow-paths and is monitored for radiation prior to discharge (see Section 7.2.1 ). The monitor trips the discharge pumps, closes the flow control valves, and provides an alarm on high radiation. The liquid radwaste effluent is finally discharged through an outlet diffuser to the circulating water discharge canal. Liquid effluent releases enter the Cape Cod Bay at the outfall of the discharge canal which is located about 1100 feet north from the center of the reactor building. In addition, batch releases from sources other than the radwaste tanks are permitted provided at least two independent samples are analyzed in accordance with PNPS Effluent Control Section 4.1.1.a, an independent verification of the release rate calculations is performed, and an independent verification of the discharge valving is performed. Concentrations released to unrestricted areas must be limited to the values specified in 10CFR20. All batch releases which are not processed through the liquid radwaste treatment system are also discharged through an outlet to the circulating water discharge canal. These untreated liquid effluent releases also enter the Cape Cod Bay at the outfall of the discharge canal. 7.1.2 Main Stack Gas Release The processed gases from the unit are routed to the main stack for dilution and elevated release to the atmosphere (see Figure 4.3-1). The main stack is continuously monitored by a radiation monitor (see Section 7.2.2). Dilution air input to the stack is provided to reduce the hydrogen in the air ejector offgases to a concentration of less than 4 percent by volume. Dilution air is supplied by one of two fans located in the filter building at the base of the main stack. The stack is designed such that prompt mixing of all gas inlet streams occurs in the base to provide prompt dilution of hydrogen and to allow location of sample points as near to the base as possible. The main stack is a pipe with a top elevation of about 400 feet mean sea level (MSL). The main stack is supported by the filter building. The filter building is a reinforced concrete structure which houses the dilution fans (16,860 cfm each fan), offgas filters, and heaters. The main stack is located about 700 feet west northwest of the reactor building. 7-1 141

PNPS-ODCM Rev. 11 7.1.3 Reactor Building Exhaust Vent Release Air from areas containing potential sources of radioactive contamination such as the reactor building, radwaste building basement, and turbine building basement are discharged through the reactor building exhaust vent (see Figure 4.3-1). Normal airflow is routed from lesser to progressively greater areas of radioactive contamination potential prior to final exhaust. The reactor building exhaust vent is continuously monitored by a radiation monitor (see Section 7.2.3). The operating floor ventilation is normally supplied with 40,000 cfm of filtered and tempered outside air which enters the reactor building through louvers in the east wall. Air is exhausted from the operating floor through ducts located in the roof truss area and the south wall; adjacent to the floor (54,000 cfm per fan). Additional exhaust ducts are located above the water level in the fuel pool, steam dryer/separator storage pool, and the reactor cavity. Two contaminated area exhaust fans (25,000 cfm per fan), each rated at design capacity, are located in the reactor building. The fans discharge to the main exhaust plenum at the base of the reactor building. An additional smaller exhaust fan (5,000 cfm), located in the reactor building, exhausts only from the control rod drive maintenance shop and discharges to the main exhaust plenum. Constant volume control is maintained by inlet vanes which are automatically positioned. The reactor building exhaust vent is a square plenum extending from the top of the west corner of the reactor building. The exhaust plenum releases to the atmosphere at an elevation of 182 feet MSL. 7.1.4 Turbine Building and Reactor Feed Pump Ventilation Releases Air from areas above the main turbine and reactor feed pumps containing potential sources of radioactive contamination are discharged via roof exhausters above each of these plant components. The air exhausted from these roof exhausters is continuously monitored by a radiation monitor (see Section 7.2.4). Six roof exhausters are located in the overhead above the main turbine. Each exhauster is rated at 35,000 scfm. Although these exhausters can be operated individually, the typical configuration is to only have one or two fans running to maintain proper ventilation balance in the building. lsokinetic sample probes are located under the two roof fans (VREX-102A, VREX-102B) nearest the west end of the building. These fans are operated preferentially to ensure sampling of air exhausted from the building. Three roof exhausters are located above the reactor feed pumps, each rated at 28,000 scfm. These three fans exhaust into a common horizontal exhaust plenum located on the roof of the building. A single isokinetic probe is located in the plenum to collect a representative sample of air being exhausted. 7-2 142

PNPS-ODCM Rev. 11 7.2 Radioactive Effluent Monitoring System Description (References 3, 5, and 6) 7.2.1 Liquid Radioactive Waste Effluent Monitoring System The liquid radiation waste effluent monitoring system consists of a single channel (see Section 7.12 of Reference 3). This channel, includes a scintillation detector, a seven decade logarithmic radiation monitor, and a strip chart recorder. The detector is located in a shielded sampler that is located in a section of the radwaste liquid discharge header to minimize background radiation. The meter and recorder are located in the main control room. This channel is connected to the 24 volt DC power bus. The channel has an upscale trip to indicate high radiation level and a downscale trip to indicate instrument trouble. The upscale trip alarms in the main control room (see Section 8.1 for liquid effluent monitor setpoints), trips the monitor tank pumps, and terminates the discharge. The downscale trip alarms in the main control room. The waste discharge valve is the isolation control device for the liquid radwaste effluent stream and it is automatically closed when the alarm is tripped. There are two waste discharge valves, one is situated on a two inch line and the other is situated on a one inch line. Both valves are located prior to the radiation waste effluent monitor and prior to the discharge canal. The valves are air operated valves. The waste discharge valves are: A07216A and SV7216A, which are on the 2 inch line; and A07216B and SV7216B, on the 1 inch line. The power source is the 24 volt DC power bus. Alarm trip circuits can be tested using test signals. The channel is calibrated by laboratory analysis of a grab sample from the liquid radwaste system. 7.2.2 Main Stack Gas Monitoring System The main stack gas monitoring system consists of two individual channels (see Section 7.12 of Reference 3) to monitor the release of noble gases. Each channel consists of a gamma-sensitive scintillation detector and a seven decade logarithmic count rate monitor that includes a power supply and a meter. Both channels are recorded on a two-pen recorder located in the main control room. Both channels are connected to the 24 volt DC power bus and to the AC radiation protection system via a transfer switch to the emergency diesel generators. Each monitor has two upscale alarms and one downscale alarm. Exceeding a setpoint initiates an alarm in the main control room, but no control action is provided. The upscale alarms indicate high radiation (see Section 8-2 for gaseous effluent monitor setpoint), and the downscale alarm indicates instrument trouble. To monitor noble gases in the gaseous effluent from the main stack, a sample is drawn through an isokinetic probe which is located in the stream to assure representative sampling. The sample passes through a particulate filter and charcoal cartridge. The filtered gas then flows to two shielded chambers where the radiation level of the noble gases is measured by two scintillation detectors, one located in each shielded chamber. The system also provides for sampling of particulates and iodines by the use of a filter and charcoal cartridge located upstream of the gas being monitored in the shielded chambers. The filter and cartridge are routinely analyzed in a chemistry laboratory in accordance with PNPS Effluent Controls. Each individual channel includes a built-in check source and a purge line to purge the stack gas from the sampling chamber. Both the purge valve and the check source are operated from the main control room. Each channel is calibrated by laboratory analysis of a grab sample in the offgas line. Alarm trip circuits can be tested using a test source. 7-3 143

PNPS-ODCM Rev. 11 7.2.3 Reactor Building Exhaust Vent Monitoring System The reactor building exhaust vent monitoring system consists of two channels (see Section 7.12 of Reference 3). Each channel consists of a gamma-sensitive detector and a seven decade logarithmic count rate monitor that includes a power supply and a meter. Both channels are recorded on a two-pen recorder located in the main control room. Both channels are. connected to the 24 volt DC power bus and the AC radiation protection system via a transfer switch to the emergency diesel generators. Each monitor has two upscale alarms and one downscale alarm. Exceeding a setpoint initiates an alarm in the main control room, but no control action is provided. The upscale alarms indicate high radiation and the downscale alarm indicates instrument trouble. To monitor noble gases from the gaseous effluent in the reactor building exhaust vent, a sample is drawn through an isokinetic probe which is located to assure representative sampling. The sample passes through a particulate filter and iodine cartridge. The filtered gas then flows to two shielded chambers where the radiation level of the gas is measured by two scintillation detectors, one located in each shielded chamber. The system also provides for sampling of particulates and iodines by the use of a filter and charcoal cartridge located upstream of the gas being monitored in the shielded chamber. The filter and cartridge are routinely analyzed in a chemistry laboratory in accordance with PNPS Effluent Controls. Each individual channel includes a built-in check source and a purge line to purge the gas from the sampling chamber. Both the purge valve and the check source are operable from the main control room. Each channel is calibrated by laboratory analysis of a grab sample from the reactor building ventilation system. Alarm trip circuits are tested using test signals. 7.2.4 Turbine Building and Feed Pump Gaseous Effluent Monitoring System (GEMS) The turbine building and reactor feed pump gaseous effluent monitoring systems (GEMS) each contain a single-channel radiation detector. Each detector consists of a beta-sensitive plastic scintillation detector coupled to a photomultiplier tube. Power is supplied locally to each unit from local 120 VAC power. Each monitor has two upscale alarms and one instrument failure (downscale) alarm. Exceeding a setpoint initiates an a local alarm, with no control action provided. The upscale alarm indicates high radiation and the downscale alarm indicates instrument trouble. To monitor noble *gases from the gaseous effluent in the air exhausted over the turbine deck or reactor feed pumps, a sample is drawn through an isokinetic probe which is located to assure representative sampling. The sample passes through a particulate filter and iodine cartridge. The filtered gas then flows to a shielded chamber where the radiation level of the gas is measured by a scintillation detector. The system also provides for sampling of particulates and iodines by the use of a filter and charcoal cartridge located upstream of the gas being monitored in the shielded chamber. The filter and cartridge are routinely analyzed in a chemistry laboratory in accordance with PNPS Effluent Controls. Each GEMS system noble gas detector channel includes a built-in check source, operated via local control. Each channel is calibrated by laboratory analysis of a grab sample from the monitored effluent stream. Alarm trip circuits are tested using test signals. 7-4 144

PNPS-ODCM Rev. 11 One radiological air sampling (RAS) pump is situated with intakes in the vicinity of each of the GEMS intakes to provide for continuous collection of particulate and iodine samples in the event of failure of either of the GEMS units. 7-5 145

PNPS-ODCM Rev. 11 TABLE 7-1 RADIOACTIVE EFFLUENT MONITOR DATA Stack Gas Reactor Buildinq Vent Item Channel 1 Channel 2 Channel A ChannelB Liquid Effluent Manufacturer GE GE GE GE I GE Model Number 194X900G9 194X900G11 194X900G11 194X900G11 194X900G9 Serial Number 6,343,901 PPA 6,550,PA6,343 6,550,733 6,550,789 6,342,995 PPA 6,342,790 PRM 907 ! 6,342,788 PRM Scale cps cps cps cps cps Range 1E-1 to 1E+6 1E-1to1E+6 1E-1 to 1E+6 1E-1 to 1E+6 1E-1 to 1E+6 Power 24VDC 24VDC 24VDC i 24VDC 24VDC Location Panel C910 PanelC910 Panel C910 Panel C910 Panel C910 I Installation Date 8/20/71 8/20/71 8/20/71 8/20/71 9/13/71 I Surveillance Test

a. Daily Channel Check Channel Check Channel Check

b. Monthly Source Check Source Check ---

C. Quarterly Channel Functional Test Channel Functional Test Channel Functional Test Calibration )

a. Quarterly Check Source Check Source Check Source

b. 24-month Known radiation source Known radiation source Known radiation source Alarm Set Points

- - - - See Section 8.2 See Section 8.2 See Section 8.1

a. Hi Alarm

b. Hi-Hi Alarm Isolation Control None None Waste Device Discharge Valve 7-6 146

PNPS-ODCM Rev. 11 7.3 Measurement Method During Release (References 3 and 7) 7.3.1 Liquid Effluent Prior to the release of any liquid waste, a sample of the release is collected and the specific activity is determined by isotopic analysis. The waste discharge tank is recirculated at least 60 minutes prior to the collection of a sample. The release of any liquid waste is controlled on a mixed effluent concentration limit (ECL) basis, where the sum of the ratios between the isotopic concentration and the ECL is less than one. The specified waste discharge flow rate must be at least 10% less than the maximum waste discharge flow rate which shall not exceed 200 gpm. The discharge of the liquid effluent is made from the liquid radwaste discharge header. 7.3.2 Gaseous Efflu-ent The gaseous effluent radiation level is continuously monitored as it is being vented to the atmosphere. Periodic samples are collected from the turbine building, reactor building vent and the main stack. The particulate filters, charcoal cartridges, gas samples, and condensed water samples are analyzed for isotopic identification and quantification, in accordance with the PNPS Effluent Controls. 7.3.3 Limitations

a. Gaseous Effluent

1) PNPS Effluent Controls for gaseous release values.

b. Liquid Effluent

1) PNPS Effluent Controls for liquid release values.

2) If one pump is used to discharge the liquid waste and fails, the release is immediately discontinued.

3) If the discharge flow rate recorder fails, the release is immediately discontinued.

7-7 147- _J

PNPS-ODCM Rev. 11 8.0 MONITOR SET POINTS Radiation monitors are typically used to measure levels of radioactivity in given process and effluent streams. In the case of effluent monitors, various setpoints can be established to cause an annunciator alarm to sound to warn an operator to take a specific action, or in other cases to cause an automated system to isolate the system to curtail the release of radioactivity from that system. In most cases, two levels of alarm are established. Typically, the highest level, or 'Hi-Hi' alarm, is established at or below the level that would correspond to exceeding one of the effluent controls in Section 3/4. In the cases of the liquid radwaste effluent monitor, steam jet air ejector monitor, and post-treatment radiation monitor, such a high level alarm would cause the system to automatically isolate to prevent additional release. A second level of alert, or 'Hi' alarm, is often set at a lower level to provide early warning of

unanticipated elevated levels of radioactivity in the system. This level of alarm is meant to alert the operators of the level of radioactivity, so that evaluations can be performed or additional samples collected to characterize the effluent or process stream. This 'Hi' alarm is typically set at some level that is a fraction of the limit, and is often administratively controlled through procedure guidance.

8.1 Liquid Effluent Monitor The setpoint for the liquid effluent monitor (see Section 7.2.1) is established as follows:

1) Prior to a liquid batch release, the waste discharge tank is recirculated for at least 60 minutes and a sample is taken.

2) The liquid effluent sample is analyzed (see Section 7.3) to determine the concentrations of each detectable isotope in µCi/ml. (See Appendix B for the definitions of lower limit of detection.)

3) The efficiency (in counts/sec per µCi/ml) of the liquid discharge monitor is calculated based on prior release experience.

4) The setpoint for the liquid effluent monitor is calculated as follows:

a) Monitor setpoint based on activity concentration C(F+ J) C = f where: c = the setpoint of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is proportional to the volumetric flow of the effluent line and inversely proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value, which if exceeded, would result in concentrations exceeding the limits of 10CFR20 in the unrestricted area, (µCi/ml); C = the effluent concentration limit implementing10CFR20 for the site (µCi/ml); F = the dilution water flow setpoint as measured at the release point, (gpm); 8-1 148

PNPS-ODCM Rev. 11 f = the effluent flow setpoint as measured at the radiation monitor location, (gpm); where: C = L Cw;

            ,* EGL-I Cw;      = concentration of nuclide i in the liquid waste discharge volume prior to any dilution as determined by current isotopic analysis for gamma emitting nuclides and most recent results from pure beta emitters as specified in Table 4.2-1 of PNPS Effluent Controls,

(µCi/ml); EGL; = Effluent Concentration Limit of each nuclide i from 10CFR20 Appendix B, Table 2, Column 2, (µCi/ml); b) Monitor setpoint based on monitor count rate C8 = (c*x)+z where: c8 = the setpoint of the radioactivity monitor measuring the radionuclide concentration in the effluent line prior to dilution, (counts/sec); c = the liquid effluent monitor setpoint based on activity concentration as calculated in step 4.a above, (µCi/ml); x = the liquid effluent monitor efficiency/conversion factor for activity concentration to count rate, (counts-mL/µCi-sec); z = the liquid effluent monitor background count rate, (counts/sec). The setpoint will ensure that the concentration of liquid effluents discharged does not increase above the value for which the maximum permissible discharge flow rate was established (see Section 9.1 of this manual). 8.2 Gaseous Effluent Monitors The only components of the station's gaseous effluent and discharge which are continuously monitored are the noble gases. The method of determining the main stack gas monitor (see Section 7.2.2) and reactor building exhaust vent monitor (see Section 7.2.3) Hi and Hi-Hi alarms is as follows:

1) At the time a gas grab sample is taken at the discharge point, the gross monitor reading is recorded (in counts/sec).

2) The results of the isotopic analyses on this sample in terms of µCi/cc of each isotope detected are used along with estimates of gaseous discharge flow rate (SCFM) to determine the current release rate of each detected isotope in µCi/sec.

8-2 149

PNPS-ODCM Rev. 11

3) These calculated release rates (µCi/sec) are used along with the equations given in Sections 9.3.1.3 and 9.3.1.4 of this manual to calculate the maximum offsite dose rate due to noble gases.

4) The ratio of this calculated dose rate to the PNPS Effluent Control instantaneous dose rate limit (500 mrem/yr for the total body and 3000 mrem/yr for the skin, or some fraction thereof) is used to scale the observed monitor reading at the time at which the grab sample was obtained as follows:

where: SG = gaseous monitor setpoint corresponding to 500 mrem/yr to the total body or 3000 mrem/yr to the skin, whichever is more limiting (in counts/sec) C8 = observed monitor reading at the time of the grab sample (in counts/sec) Bg = measured background count rate at the sampler with no sample present (in counts/sec) DRumit = the applicable dose rate limit, 500 mrem/yr for the total body or 3000 mrem/yr for the skin or some fraction thereof DRca/c = the calculated dose rate for the maximum individual from the methods of Section 9.3.1.3 and 9.3.1.4 of this manual using the release rates determined from the grab sample, mrem/yr The resulting setpoint will be valid until the next grab sample is taken from the release point. This method will be used to establish the Hi-Hi alarm at 500 mrem/yr to the total body or 3000 mrem/yr to the skin, whichever is more restrictive. Since two release points exist for noble gas effluents, the setpoints may be varied to allow greater release rates from one point than the other, provided the total limit is below 500 mrem/yr for the total body or 3000 mrem/yr for the skin, whichever is more restrictive. The Hi-Hi alarm setpoint for the gaseous monitors will be based on the equation in this section. The Hi alarm setpoint may be set at or below, but in no case above, the Hi-Hi alarm setpoint. 8.3 Steam Jet Air: Ejector Monitor The steam jet air ejector (SJAE) monitor is used to measure the release rate of noble gases in main condenser offgas prior to its further treatment and release from the main stack. This monitor's primary function is to provide alarm and isolation of this process flow stream in the event of excessively high release rates of noble gases from the condenser and recombiner. The maximum allowable release rate of noble gases in the SJAE offgas is 500,000 µCi/sec, as established in Technical Specification 3.8.1. For conservatism, the Hi~Hi alarm is set at 75% of this limit, or 375,000 µCi/sec. In association with changing to a 24-month refueling cycle, the frequency of equipment calibrations has also been extended from the typical 18-month cycle. In order to accommodate for any drift which may occur in SJAE monitor response during the 8-3 150

PNPS-ODCM Rev. 11 additional 6-months in the calibration interval, the Hi-Hi alarm has been further derated to a release rate of 300,000 µCi/sec. In response to guidance from the Institute of Nuclear Power Operations outlined in SOER 90-02, Pilgrim Station has chosen to administratively control the SJAE noble gas rate to a lower value to determine the desirability of a plant derate. Since this gaseous stream undergoes further processing downstream of the SJAE monitor and is ultimately released via the main stack and monitored by the main stack gaseous effluent monitor, the SJAE monitor does not strictly qualify as a primary effluent monitor. Therefore, it is not normally recognized as such. However, the methodology for establishment of alarm setpoints is included in this section for completeness. These setpoints are established as follows:

1) A grab sample of the SJAE offgas is collected. The SJAE monitor reading (mR/hr) is recorded in conjunction with this sample.

2) Isotopic analyses are performed on the offgas sample and the total noble gas concentration

(µCi/cc) is coupled with the flow rate (CFM) to calculate the SJAE release rate (µCi/sec).

3) The release rate (µCi/sec) is divided by the monitor reading (mR/hr) to determine the SJAE monitor conversion factor (µCi/sec/mR/hr).

4) The Hi-Hi alarm setpoint (mR/hr) is determined by dividing the administratively-determined maximum tolerable release rate by the SJAE monitor conversion factor (µCi/sec/mR/hr).

5) The Hi alarm setpoint is set at a maximum of 50% of the corresponding Hi-Hi alarm setpoint, or at other levels procedurally controlled to initiate evaluation of the system (e.g., sampling to determine noble gas mix and/or evaluate conversion factors).

Grab samples of the SJAE offgas are collected: 1) at least once every 31 days; or, 2) if the gross radioactivity release rate increases by 50% or more over the nominal steady state fission gas release after factoring out increases due to changes in thermal power level and hydrogen injection. Upon collection of these grab samples, new values are established for the total noble gas concentration, SJAE monitor conversion factor, and alarm setpoints. Typically, existing setpoints will be used unless the newly calculated setpoints yield lower values. In this case, the setpoints will be lowered to the newer, more conservative values. 8.4 Post-Treatment Radiation Monitor The post-treatment radiation monitoring system takes a continuous sample from the outlet of the augmented offgas treatment system. This system has two instrumentation channels, each of which is equipped with a gamma-sensitive scintillation detector, a pulse preamplifier, a logarithmic radiation monitor, and an electroluminescent display. Both channels are recorded on a two-pen recorder located in the main control room. The two scintillation detectors are mounted in two shielded sample chambers. The sample is drawn from the offgas line through the sample line by the sample pump. Each monitor has two upscale trips and a downscale trip. Any one upscale high radiatiqn trip of the augmented offgas monitor closes the carbon bed filter bypass valve, if open, and opens the offgas line to the carbon bed, if closed, in the augmented offgas system. This upscale high radiation trip also provides an annunciator alarm in the control room. Any combination of two high-high upscale radiation trips, one high-high upscale trip and one downscale trip, or two downscale trips of each monitor will actuate a time delay switch through a 8-4 151

PNPS-ODCM Rev. 11 keylock selector switch. This is the same 0-15 minute time delay switch located in the SJAE radiation monitor which closes the drain valve and the outlet valve in the offgas discharge line. Since the gaseous stream from the augmented offgas treatment system undergoes further processing (delay decay) downstream of the post-treatment radiation monitor and is ultimately released via the main stack and monitored by the main stack gaseous effluent monitor, the post-treatment radiation monitor does not strictly qualify as a primary effluent monitor. Therefore, it is not normally recognized as such. The methodology for establishing alarm setpoints for the post-treatment radiation monitor is similar to that described in Section 8.3 for the SJAE monitors. 8-5 152

PNPS-ODCM Rev. 11 9.0 CAlCUlATIONAl METHODS This section presents the calculational specifics required to demonstrate compliance with each of the Effluent Controls identified in Section 3/4 of this document. The equations in this section are based on the equations and calculational methods described in Reference 8, unless otherwise specified. These equations have, in some cases, been presented in a slightly different form in an effort to simplify their use. The subscripts used are "a" for age group, "j" for organ, "i" for radionuclide, "p" for pathway and "I" for location. Capital letters have been used on the dose/dose rate, use factor, concentration, and dose conversion factor abbreviations to designate pathways. "A" is for aquatic foods, "S" for shoreline deposits, "W" for swimming, "Y" for yachting/boating, "N" for noble gas, "G" for ground plane deposition, "B" for breathing/inhalation, "l" for leafy vegetation, "R" for root crops/non-leafy vegetation, "M" for milk, and "C" for meat. The descriptions of constants, variables, and parameters in this section are also based on those described in Reference 8, unless otherwise specified. The descriptions have, in some cases, been modified to describe the constant, variable, and parameter specific application in the corresponding equation. In addition, some of the constant and variable values have been revised to include more site specific values, to include more technically correct information, or to provide uniformity (e.g., Ai values always presented in hr1). Values for parameters which only have a single value will appear along with the definition. For those parameters which can take on different values for different conditions, the appropriate value will appear in the referenced tables. All numerical constants have been derived from the indicated base conversion factors and are represented in scientific notation to the third significant digit. 9.1 Concentrations of Liquid Effluents The following equation shall be used to determine the discharge flow rate such that concentrations of radioactive effluents released to unrestricted areas do not exceed the concentration limits specified in 10CFR20 Appendix B, Table 2, Column 2: DFR = cw L Cw;

                ; EGL; where:

DFR = Maximum discharge release rate of liquid effluent, (gal/min). CW = Flow rate of dilution water, (sum of waste discharge pumps, circulating water pumps, and/or salt service water pumps), (gal/min). Cw; = Concentration of nuclide i in the liquid waste discharge volume prior to any dilution as determined by current isotopic analysis for gamma emitting nuclides and most recent results from pure beta and alpha emitters, (µCi/ml). EGL; = Effluent Concentration Limit of each nuclide ifrom 10CFR20 Appendix B, Table 2, Column 2, (µCi/ml). 9-1 153

PNPS-ODCM Rev. 11 9.2 Liquid Effluents Dose Assessment Methodology The following equations shall be used to estimate the annual dose rates due to a release of radioactive liquid effluents. All input parameters (i.e., activity and volume) must be normalized to a 1 year release period. Modification of the final results is necessary for comparison to dose rate limits for periods different than one year. For comparison to monthly limits and quarterly limits, results would be scaled by 1/12 and 1/4, respectively. To determine the dose or dose commitment for a desired period, multiply the annual dose rate by the fraction of the year for the dose period desired. For purposes of projecting resulting dose estimates for the subsequent month, the release rates and concentrations are assumed to be equal to the previous month's release. Pathways assuming internal deposition of radionuclides (i.e., ingestion) involve the use of a 50-year committed dose conversion factor. This entire prospective dose will be assigned to the individual for the year of intake (Reference 8). In the original version of the ODCM, values from Regulatory Guide 1.109 (Reference 8) were used for calculating doses. Upon incorporation of the Generic Letter 89-01 change (Revision 8), and conversion to an electronic document, dose conversion factors were obtained from updated tables used by the NRC in the computer program GASPAR-II (Reference 9). For pathways involving external radiation to the total body (i.e., shoreline activity, swimming, boating), the dose to all other organs is assumed equal to that for the total body (Reference 8, Appendix E). Summation of the dose rates from the equations below should be performed for all significant pathways. 9.2.1 Liquid Pathways Annual Dose Rates 9.2.1.1 Aquatic Food Ingestion {Fish, Shellfish) DAajp = UAap ~ [CA;p OF/aij] I where: CA;p = CW;1 B;p e-A/h

                                 -kt, CW-     = 1.OOE12 Q; M 1 e          '
     ,1                V Above equations derived from Reference 8, equations 2 and A-3.

9-2 154

PNPS-ODCM Rev. 11 9.2.1.2 Shoreline Deposits (Discharge Canal and Recreational Area) DSajt = US81 W, ~ [ CSil DFGij] I . where: (1-e-A;tb) csil = 2.89 CW;, ~----'--

                           ;i,.

I CWif = same as indicated in Equation 9.2.1.1 Above equation derived from Reference 8, equations A-4 through A-7. 9.2.1.3 Swimming (White Horse Beach) DWajt = UW81 ~ [ Cv1f;1 DFWij] I where: CWif = same as indicated in Equation 9.2.1.1 Above equations derived from Reference 10, equation 41 on page 151. 9.2.1.4 Yachting/Boating (Cape Cod Bay) DYajt = 0.5 UYat ~[ CW;1 DFW;j] I where: CWif = same as indicated in Equation 9.2.1.1 Above equations derived from Reference 10, equation 41 on page 151. 9-3 155

PNPS-ODCM Rev. 11

9.2.2 Definitions

B;p = equilibrium bioaccumulation factor for radionuclide i, in aquatic foods pathway p, expressed as the concentration in biota (pCi/kg), divided by the concentration in water (pCi/liter) from Table A-1, (liters/kg); Ca;p = concentration of radionuclide i in pathway p of aquatic foods, (pCi/kg); CSif = effective surface concentration of radionuclide i in sediments at location I, (pCi/m2); CW;J = concentration of radionuclide i in seawater at location I, (pCi/liter); DAajp = total annual dose rate from ingestion of aquatic foods to organ j, of individuals of age group a, from pathway p, (mrem/yr); DFGij = open field ground plane dose conversion factor for organ j, from radionuclide i, from 2 Table A-10, (mrem-m /pCi-hr); DF1aij = ingestion 50-year committed dose conversion factor for organ j, of individuals in age group a, from radionuclide i, from Table A-15 through A-18 (mrem/pCi ingested); DFWij = submersion dose conversion factor in water, for organ j, of individuals in age group a, from radionuclide i, from Table A-2, (mrem-liter/pCi-hr); DSajl = total annual dose rate from exposure received during shoreline activities, to organ j, of individuals of age group a, at location I, (mrem/yr); DWajl = total annual dose rate from exposure received during swimming, to organ j, of individuals of age group a, at location I, (mrem/yr); DYajl = total annual dose rate from exposure received during yachting/boating, to organ j, of individuals in age group a, at location I, (mrem/yr); MJ = mixing ratio (reciprocal of dilution factor) at location I of exposure or harvest of aquatic food, from Table A-3, (dimensionless); Q; = annual release rate of radionuclide i in liquid effluents, (Ci/yr); tb = period of time for which sediment is exposed to radionuclides in seawater, including buildup, (hr, assumed to be 1.31 E5 hr= 15y); th = time between exposure of aquatic foods to radionuclides in sea water and their consumption by an individual, from Table A-3, (hr); ti = transit time required for radionuclides to reach location I, (hr, assumed to be 0.0 hr from the liquid waste tank to the discharge canal); UAap = use factor of aquatic foods from pathway p, by individuals in age group a, from Table A-9 for maximum individual, Table A-8 for average individual, (kg/yr); 9-4 156

PNPS-ODCM Rev. 11 USaJ = use factor (amount of time) an individual in age group a, engages in shoreline activities at location I, from Table A-9 for maximum individual, Table A-8 for average individual, (hr/yr); UWaJ = use factor (amount of time) an individual in age group a, engages in swimming at location I, from Table A-9 for maximum individual, Table A-8 for average individual, (hr/yr); UYaJ = use factor (amount of time) an individual in age group a, engages in yachting/boating at location I, from Table A-9 for maximum individual, Table A-8 for average individual, (hr/yr); V = total annual discharge rate of liquids, represented by the sum of liquid effluents, circulating water pumps, and/or salt service water pumps, (liters/yr); w, = shoreline width factor for location I, from Table A-3, (dimensionless);

                                                            -1 Aj    = radioactive decay constant of radionuclide i, (hr );

0.50 = scaling factor for yachting/boating assuming that doses received while on the surface of the water are 1/2 of doses received while immersed in water from Reference 10, (dimensionless); 2.89 = factor to convert for transfer of nuclides from water to sediment, equal to 2 100 liters/m -day from Reference 11 multiplied by 1 day/24 hr and by natural log of 2 (to convert reciprocal Ai to half-life), as calculated in Reference 8, equation A-5, 2 (liter/m -hr); 1.00E12 = factor to convert from Ci to pCi, (pCi/Ci); 9-5 157

PNPS-ODCM Rev. 11 9.3 Gaseous Effluents Dose Assessment Methodology The following equations shall be used to estimate the annual dose rates due to release of radioactive gaseous effluents. All input parameters (i.e., activity and volume) must be normalized to a 1 year release period. Modification of final results is necessary for comparison to dose rate limits for periods different than one year. For comparison to monthly limits and quarterly limits, results would be scaled by 1/12 and 1/4, respectively. To determine the dose or dose commitment for a desired period multiply the annual dose rate by the fraction of the year for the dose period desired. For conservatism, the shielding factor (S) used for calculating total body dose and skin dose from noble gases is normally assumed to be unity (1.0), as specified in NUREG-0133 (Reference 12). Also, although iodine deposition on vegetation is assumed to be 50% (Reference 8), 100% of airborne iodine is assumed to be deposited on the ground surface when calculating direct radiation (ground plane) exposure. Pathways assuming internal deposition of radionuclides (i.e., inhalation, ingestion) involve the use of a SO-year committed dose conversion factor. This entire prospective dose will be assigned to the individual for the year of intake (Reference 8). In the original version of the ODCM, values from Regulatory Guide 1.109 (Reference 8) were used for calculating doses. Upon incorporation of the Generic Letter 89-01 change (Revision 8), and conversion to an electronic document, dose conversion factors were obtained from updated tables used by the NRC in the computer program GASPAR-II (Reference 9). For pathways involving external radiation to the total body (i.e., noble gas total body dose, ground plane deposition), the dose to all other organs is assumed equal to that for the total body (Reference 8, Appendix E). Summation of the doses rates from the equations below should be performed for all significant pathways and all release points from which significant radioactive effluent releases have occurred (i.e., Main Stack and Reactor Building Exhaust Vent). 9.3.1 Gaseous Pathways Annual Dose Rates from Noble Gases 9.3.1.1 Gamma Air Dose DNr = ~[c;r DFN;r] I where: C;r = 3.17E4 [Yot O; Above equations derived from Reference 8, equations 6, 7, B-1, B-2, B-4, and B-5, as well as References 13 and 14. 9-6 158

PNPS-ODCM Rev. 11 9.3.1.2 Beta Air Dose ON/3 = ~ [C;p DFN;p] I where: Above equations derived from Reference 8, equations 7, B-4, and B-5. 9.3.1.3 Total Body Dose DNTa = S ~[c;r DFN;Ta] I where: C;y = Same as indicated in Equation 9.3.1.1. Above equations derived from Reference 8, equations 8, 10, B-1, B-2, B-4, B-5, B-6, and B-8, as well as References 13 and 14. 9.3.1.4 Skin Dose DNs = (1.11 S DNr) + ~[c;p DFN;s] I where: DNr,C;p = same as indicated in Equations 9.3.1.1 and 9.3.1.2, respectively. Above equations derived from Reference 8, equations 6, 7, 9, 11, B-1, B-2, B-4, B-7, and B-9, as well as References 13 and 14. 9-7 159

PNPS-ODCM Rev. 11 9.3.2 Gaseous Pathways Annual Dose Rates from Iodine 131 and 133, Particulates with a Half-life Greater than 8 Days, and Tritium. PNPS Effluent Controls do not consider doses from C-14 and 1-135 for compliance. However, equations for these radionuclides are included in this section for completeness. 9.3.2.1 Ground Plane Deposition DGj = S ~[CG; DFGij] I where: (1 -)Ab) 1 CG; = 1.00E12 [%] O; - e A; Above equations derived from Reference 8 equations 12, C-1, and C-2. 9.3.2.2 Breathing/Inhalation DBaj = UB 8 ~[ CB; DFBaij] I where: CB; = 3.17 E4 [%L O; for H-3, C-14 CB; = 3.17 E4 [%]d O; for particulates with TYz >8d, 1-131, 1-133, and 1-135 Above equations derived from Reference 8, equations 13, C-3, and C-4. 9-8 160

PNPS-ODCM Rev. 11 9.3.2.3 Leafy Vegetation Ingestion DLaj = ULa t, ~[ CL; DF/aij] I where: CL;= leafy vegetation concentration as calculated below. Above equation derived from Reference 8, equations 14 and C-13. where: for H-3 for C-14

                                . [D/_o]

l" (1-CH-,, CL-,, GP,, CR-I = 5.71E7 *o.I /G 1 e-AE;te) y A . +

a. IV (1 _e-A;tb )]

e-A;th p A*

V E, I for 1-131, 1-133, and 1-135 (1 - (1 l

r. e-AE;te) B e-A;tb )]

CH-,, CL-,, GP,, CR-=I 1.14E8 Q.I [01_]

/Q

P y A .

                                                                  . + iv p- A*

e-A;th V E, I for particulates with T ~ >8 days, Above equations derived from Reference 8, equations C-5 through C-9.

9-9 161

PNPS-ODCM Rev. 11 9.3.2.4 Root Crop Non-Leafy Vegetation Ingestion DRaj = URa fr ~ [CR; DF/aij] I where: CR;= root crop concentration as calculated in Equation 9.3.2.3. Above equations derived from Reference 8, equations 14 and C-13. 9.3.2.5 Milk Ingestion DMaj = UMa ~ [ CM; DF!aij] I where: CM-, -- FIm CFI Or e-A;tr GP;, CH; = concentration in pasture grass and harvested/stored feed as calculated in Equation 9.3.2.3. Above equations derived from Reference 8, equations 14, C-10, C-11, and C-13 9.3.2.6 Meat Ingestion DCaj = UCa ~[ CC; DF!aij] I where: CC; = F;, CF; Q, e-A;fs CF;= concentration in forage as calculated in Equation 9.3.2.5 Above equations derived from Reference 8, equations 14, C-12, and C-13 9-10 162

PNPS-ODCM Rev. 11 9.3.3 Definitions B;v = concentration factor for uptake of radionuclide i, from soil in the edible portions of crops, in pCi/kg (wet weight) per pCi/kg dry soil, from Table A-5, (kg/kg); C;p = effective semi-infinite cloud concentration of noble gas i, for the purpose of calculating beta air dose, (pCi/m3); C;y = effective finite cloud concentration of noble gas i for the purpose of calculating gamma air dose, (pCi/m3); CB; = ground-level airborne concentration of radionuclide i, (pCi/m3); CC; = concentration of radionuclide i in meat, (pCi/kg); CF; = concentration of radionuclide ion forage, (pCi/kg); 2 CG; = ground plane concentration of radionuclide i, (pCi-hr/m -yr); CH; = concentration of radionuclide ion harvested/stored feed, (pCi/kg); CM; = concentration of radionuclide i in milk, (pCi/liter); CL; = concentration of radionuclide i in leafy vegetables, (pCi/kg); CP; = concentration of radionuclide i on pasture grass, (pCi/kg); CR; = concentration of radionuclide i in root crops/non-leafy vegetables, (pCi/kg); DBaj = total annual dose rate from breathing/ inhalation to organ j, of an individual in age group a, (mrem/yr); DCaj = total annual dose rate from ingestion of meat to organ j; of an individual in age group a, (mrem/yr); DFBaij = inhalation 50-year committed dose conversion factor for organ j, of individuals in age group a, from radionuclide i, from Tables A-11 through A-14, (mrem/pCi); DFGij = open field ground plane dose conversion factor for organ j, from radionuclide i, from 2 Table A-10, (mrem -m /pCi-hr); DF1aij = ingestion 50-year committed dose conversion factor for organ j, for individuals in age group a, from radionuclide i, from Tables A-15 through A-18, (mrem/pCi); DFN;s = beta skin dose conversion factor for a semi-infinite cloud of noble gas i, which includes the attenuation by the outer "dead" layer of skin, from Table A-4, (mrem-m 3/pCi-yr); DFN;ra = total body dose conversion factor for a semi-infinite cloud of noble gas i, which includes 3 the attenuation of 5 g/cm2 of tissue, from Table A-4, (mrem-m /pCi-yr); DFN;p = beta air dose conversion factor from a semi-infinite cloud of noble gas i, from Table A-4, 3 (mrad-m /pCi-yr); 9-11 163

PNPS-ODCM Rev. 11 DFN;y = gamma air dose conversion factor from a semi-infinite cloud of noble gas i, from 3 Table A-4, (mrad-m /pCi-yr); DGj = total annual dose rate to organ j from direct exposure to the contaminated ground plane from all radionuclides, (mrem/yr); DLaj = total annual dose rate from ingestion of leafy vegetables to organ j, of an individual in age group a, (mrem/yr); DMaj = total annual dose rate from ingestion of milk to organ j, of an individual in age group a, (mrem/yr); DNs = total annual skin dose rate due to immersion in a finite cloud of noble gases, (mrem/yr); DNra = annual total body dose rate due to immersion in a finite cloud of noble gases, (mrem/yr); DNp = annual beta air dose rate to a semi-infinite cloud of noble gases, (mrad/yr); DNy = annual gamma air dose rate due to a finite cloud of noble gases, (mrad/yr); DRaj = total annual dose rate from ingestion of root crop or non-leafy vegetables to organ j, of an individual in age group a, (mrem/yr); [DIQJ = deposition rate considering depletion at the receptor location in question, from Table 10-1, (m-2); f/ = fraction of the ingestion rate of a leafy vegetable that is produced in the garden of interest, (dimensionless; assumed to be 1.0); fp = fraction of the year the animals graze on pasture, (dimensionless; assumed to be 1.0); fr = fraction of root crops/non-leafy vegetable that are produced in the garden of interest, (dimensionless; assumed to be 0.76); f5 = fraction of daily feed that is pasture grass when the animal grazes on pasture, (dimensionless; assumed to be 1.0); F;f = average fraction of the animal's daily intake of radionuclide i which appears in each kilogram of meat, from Table A-5, (days/kg); F;m = average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk, from Table A-5 for cows, Table A-6 for goats, (days/liter); 3 H = absolute humidity of the atmosphere from Reference 15, (g/m ; assumed to be 5.6 g/m3); p = fractional equilibrium ratio, (dimensionless; assumed to be 1.0 for continuous release); p = effective surface density for dry soil, (kg/m 2 ; assumed to be 240 kg/m2); Qf = amount of feed consumed by the animal per day from Table A-7, (kg/day); Q; = annual release rate of radionuclide i in gaseous effluents (Ci/yr); 9-12 164

PNPS-ODCM Rev. 11

      = fraction of deposited radioiodine retained on crops, (dimensionless; assumed to be 1.0 from References 16-19);
      =   fraction of deposited particulates retained on crops, (dimensionless; assumed to be 0.2 from References 20 and 21);

s = attenuation factor that accounts for the dose reduction due to shielding provided by residential structures from Table A-19, (dimensionless);

      =    time period over which the radionuclide buildup is evaluated, (hr; assumed to be 1.31E5 hr= 15 yr);

te = time period that crops are exposed to radionuclide deposition during the growing season, from Table A-19, (hr); tr = average transport time of the activity from the feed into the milk and to the receptor from Table A-19, (hr); th = holdup time that represents the time interval between harvest and consumption of the food, from Table A-19, (hr); ts = average time for radionuclides to pass from feed through meat to the consuming individual, (hr; assumed to be 480 hr= 20 days); UBa = annual breathing rate, for individuals in the a~e group a, from Table A-9 for maximum individual, Table A-8 for average individual, (m /yr); UCa = annual intake of meat, for individuals in age group a, from Table A-9 for maximum individual, Table A-8 for average individual, (kg/yr); ULa = annual intake of leafy vegetables, for individuals in the age group a, from Table A-9 for maximum individual, Table A-8 for average individual, (kg/yr); UMa = annual intake of milk, for individuals in the age group a, from Table A-9 for maximum individual, Table A-8 for average individual, (liter/yr); URa = annual intake of root crops/non-leafy vegetables, for individuals in the age group a, from Table A-9 for maximum individual, Table A-8 for average individual, (kg/yr); 2 Yv = agricultural productivity/yield, from Table A-19, (kg/m , wet weight); [Z/QJc = appropriate value of undepleted atmospheric dispersion factor used to estimate ground level airborne concentration of gaseous, (i.e., non-particulate) radionuclides, from Table 10-1, (sec/m3); [X/Q]d = appropriate value of the average gaseous dispersion factor corrected for depletion of particulates and radioiodines, from Table 10-1, (sec/m3); [X/Q]y = appropriate value of gamma atmospheric dispersion factor used to estimate ground level gamma dose rate from an elevated or ground level plume as calculated in References 13 and 14, from Table 10-1, (sec/m3); 9-13 165

PNPS-ODCM Rev. 11

\ = radioactive decay constant of radionuclide i, (hr -1);

     =    effective removal rate constant for radionuclide i from crops, in hr1, where AEi = Ai + Aw*        Ai is the radioactive decay constant, and Aw is the removal rate constant for physical loss by weathering. Aw= 0.0021 hr1, (hr1);

1.11 = average ratio of the tissue to air energy absorption coefficients, (mrem/mrad); 3.17E4 = 1.00E12 pCi/Ci divided by 3.15E7 sec/yr, (pCi-yr/Ci-Sec) 1.19E7 = 1.00E12 pCi/Ci divided by 3.15E7 sec/yr and multiplied by 1.00E3 g/kg and by 0.5 g H-3 in plant water per g H-3 in atmospheric water from Reference 22 (dimensionless) and by 0.75 g water per g plant (dimensionless), as calculated in Reference 8 equation C-9, (pCi-yr-g/Ci-sec-kg); 2.1BE7 = 1.00E12 pCi/Ci divided by 3.15E7 sec/yr and multiplied by 1.00E3 g/kg and by 0.11 g Carbon/g plant mass from References 23 and 24 divided by 0.16 g Carbon/m3 of air, as calculated in Reference 8 equation C-8, (pCi-yr-m 3/Ci-sec-kg): 5.71E7 = conversion factor to correct for activity, time units, and elemental forms of radioiodines, equal to the particulate radionuclide conversion factor 1.14E8 multiplied by an elemental iodine fraction of 0.5 from Reference 25, (pCi-yr/Ci-hr); 1.14EB = conversion factor to correct activity units and time units for particulate radionuclides, equal to 1.00E12 pCi/Ci multiplied by 1 yr/8760 hr, (pCi-yr/Ci-hr); 1.00E12 = conversion factor to correct for activity units, (pCi/Ci); 9-14 166

PNPS-ODCM Rev. 11 9.4 Total Dose to a Member of the Public The purpose of this section is to describe the method used to calculate the cumulative dose contributions from liquid and gaseous effluents in accordance with PNPS Effluent Controls for total dose. This method can also be used to demonstrate compliance with the Environmental Protection Agency (EPA) 40CFR190, "Environmental Standards for the Uranium Fuel Cycle". Compliance with the PNPS Effluent Controls dose objectives for the maximum individual demonstrates compliance with the EPA limits to any member of the public, since the design dose objectives from 10CFR50 Appendix I are much lower than the 40CFR190 dose limits to the general public. With the operational objectives in PNPS Effluent Controls Sections 3.2.2, 3.3.2, and/or 3.3.3 being exceeded by a factor of two, a special analysis must be performed. The purpose of this special analysis is to demonstrate if the total dose to any member of the public (real individual) from all uranium fuel cycle sources (including all real pathways and direct radiation) is limited to less than or equal to 25 mrem per year to the total body or any organ except for the thyroid which is limited to 75 mrem per year. If required, the total dose to a member of the public will be calculated for all significant effluent release points for all real pathways including direct radiation. Only effluent releases from PNPS (Pilgrim Station) need to be considered since no other nuclear fuel cycle facilities exist within a 50 mile radius. The calculations will be based on the equations contained in this section, with the exception that the usage factors and other site specific parameters will be modified using more realistic assumptions, where appropriate. The direct radiation component from the facility can be determined by using environmental TLD results. These results will be corrected for natural background and for actual occupancy time of the recreational areas accessible to the general public at the location of maximum direct radiation. It is recognized that by including the results from the environmental TLDs into the sum of total dose component, the direct radiation dose may be overestimated. The TLD measurements may include the exposure from noble gases, ground plane deposition, and shoreline deposition, which have already been included in the summation of the significant dose pathways to the general public. However, this conservative method can be used, if required, as well as any other method for estimating the direct radiation dose from contained radioactive sources within the facility. The methodology used to incorporate the direct radiation component into total dose estimates will be outlined whenever total doses are reported. Therefore, the total dose will be determined based on the most realistic site specific data and parameters to assess the real dose to any member of the general public. 9-15 167

PNPS-ODCM Rev. 11 10.0 RECEPTOR LOCATIONS, HYDROLOGY, AND METEOROLOGY The purpose of this section is to identify those receptor locations which represent critical pathway locations and the methods used to estimate dilution and dispersion factors for these locations. For the dose calculations from liquid effluents, the maximum individual is assumed to: 1) ingest fish and shellfish from the discharge canal, 2) receive direct radiation from shoreline deposits at both the discharge canal and PNPS shoreline recreational area, and 3) receive external radiation while swimming at White Horse Beach as well as while boating on the Cape Cod Bay. The doses are calculated for the various age groups (i.e., infant, child, teenager and adult), as well as for the various organs, (i.e., bone, liver, thyroid, kidney, lung, gastrointestinal tract/lower large intestine, skin, and total body). The maximum total body and organ doses are selected from the totals of the various age groups and organ doses calculated as described above. For liquid effluent pathways, Table A-3 lists the conservative values for the mixing ratio and shore width factor for the various aquatic receptor locations. For the dose calculations for gaseous effluents, the maximum individual is assumed to reside at the receptor location that provides the highest dose from the dose contributions from all gaseous release points where significant releases have occurred. The locations selected in Table 10-1 are the site boundary, a garden at the site boundary, and the nearest milk animal at the Plimoth Plantation. The dose calculations are performed for each release point and totaled for the following dose pathways; 1) noble gas immersion, 2) ground plane deposition, 3) inhalation, and

4) ingestion of leafy vegetable, root crops/non-leafy vegetables, milk, and meat. The doses are also calculated for the various age groups and for the various organs as described for liquid effluents. The maximum total body, skin, and organ doses are selected from the totals of the various age groups and organ doses calculated as described above.

In order to estimate atmospheric dispersion and deposition factors for each of these locations, a computer code supplied by the Yankee Atomic Electric Company was used. The code, AEOLUS (Reference 13), was used to calculate quarterly average values of dispersion and deposition factors. Meteorological data for a three year period, January 1, 1977 to December 31, 1979, were used for these analyses. The most conservative quarterly average values of ground level average atmospheric dispersion factor before depletion [X/O]c, ground level average atmospheric dispersion factor after depletion [X/Q]d, average gamma dilution factor [X/O]y, and average deposition rate [D/Q] for the three year period were chosen for each of the critical receptor locations. The technique used to estimate ground level gamma doses from an elevated or ground level plume is based on the sector average finite cloud model of Regulatory Guide 1.109 (Reference 8). The equation has been rearranged into a form similar to the standard semi-infinite cloud equation thereby allowing the use of a "gamma Chi/Q" which includes the effects of plume dimensions, gamma energy mix, atmospheric and geometric attenuation, etc. (See References 13 and 14 for a detailed discussion.) For gaseous effluent pathways, Table10-1 lists the critical locations for receptors and conservative atmospheric dispersion factors for each atmospheric receptor location. 10-1 168

PNPS-ODCM Rev. 11 TABLE 10-1 CRITICAL RECEPTOR LOCATIONS AND ATMOSPHERIC DISPERSION FACTORS [X/O]c [X/Q]d [X/Q]y [D/Q] 3 3 3 2

.Effluent Control Section                     (sec/m )         (sec/m )          (sec/m )           (1/m )

GROUND-LEVEL RELEASES: Reactor Building Vent, Turbine Building, etc. 3/4.3.1: Gaseous Effluent Dose Rate Site Boundary <1> 7.40E-06 7.04E-06 4.69E-06 5.22E-08 Nearest Garden <2> 7.40E-06 7.04E-06 4.69E-06 5.22E-08 Nearest Milk Animal <3> 4.29E-07 4.21E-07 1.70E-07 7.93E-10 3/4.3.2: Dose - Noble Gases Site Boundary <1> 7.40E-06 N/A 4.69E-06 N/A 3/4.3.3: Dose - lodine-131, lodine-133, Radioactive Materials in Particulate Form, and Tritium Site Boundary <1> 7.40E-06 7.04E-06 N/A 5.22E-08 Nearest Garden <2> 7.40E-06 7.04E-06 N/A 5.22E-08 Nearest Milk Animal <3 > 4.29E-07 4.21E-07 N/A 7.93E-10 3/4.4.1: Total Dose Site Boundary <1> 7.40E-06 7.04E-06 4.69E-06 5.22E-08 Nearest Garden <2> 7.40E-06 7.04E-06 4.69E-06 5.22E-08 Nearest Milk Animal <3> 4.29E-07 4.21E-07 1.70E-07 7.93E-10 ELEVATED RELEASES: Main Stack 3/4.3.1: Gaseous Effluent Dose Rate Site Boundary <1> 4.69E-07 4.69E-07 1.68E-06 2.92E-09 Nearest Garden <2> 4.69E-07 4.69E-07 1.68E-06 2.92E-09 Nearest Milk Animal <3> 3.73E-08 3.70E-08 3.22E-08 2.46E-10 3/4.3.2: Dose - Noble Gases Site Boundary <1> 4.69E-07 N/A 1.68E-06 N/A 3/4.3.3: Dose - lodine-131, lodine-133, Radioactive Materials in Particulate Form, and Tritium Site Boundary <1> 4.69E-07 4.69E-07 N/A 2.92E-09 Nearest Garden <2> 4.69E-07 4.69E-07 N/A 2.92E-09 Nearest Milk Animal <3> 3.73E-08 3.?0E-08 N/A 2.46E-10 3/4.4.1: Total Dose Site Boundary <1> 4.69E-07 4.69E-07 1.68E-06 2.92E-09 Nearest Garden <2 > 4.69E-07 4.69E-07 1.68E-06 2.92E-09 Nearest Milk Animal <3 > 3.73E-08 3.70E-08 3.22E-08 2.46E-10 1 <> "Site Boundary" means the location at or beyond the boundary of the restricted area with the highest calculated dispersion and/or deposition factor. 2 <> "Nearest Garden" is considered to be the same as the site boundary due to the abundance of small gardens near Pilgrim Station. 3 <> "Nearest Milk Animal" is presently considered to be at the Plimoth Plantation, 3.7 km (2.3 mi) west of Pilgrim Station. 10-2 169

PNPS-ODCM Rev. 11 11.0 RADIOLOGICAL ENVIRONMENTAL SAMPLING AND MEASUREMENT LOCATIONS Sampling and measurement locations have been established for Pilgrim Station considering meteorology, population distribution, hydrology, and land use characteristics of the Plymouth area. The sampling locations are divided into two classes: indicator and control. Indicator locations are those which are expected to show effects from .PNPS operations, if any exist. These locations were selected primarily on the basis of where the highest predicted environmental concentrations were calculated to occur. While the indicator locations are typically within a few kilometers of the plant, the control stations are generally located so as to be outside the influence of Pilgrim Station. They provide a basis on which to evaluate fluctuations at indicator locations relative to natural background radiation, natural radioactivity, and fallout from prior nuclear weapons tests. The environmental sampling media collected in the vicinity of Pilgrim Station include air particulate filters, charcoal cartridges, seawater, shellfish, Irish moss, American lobster, fishes, sediment, cranberries, vegetation, and animal forage. The media, sample designation location, description, distance, and direction for indicator and control samples are listed in Tables 3.5-1 and 3.5-3 under Control 3/4.5.1. These sampling locations are also displayed on the maps shown in Figures 3.5-1 through 3.5-5. The frequency of collection and types of radioactivity analysis are described in the PNPS Effluent Control 3/4.5.1, Table 3.5-1. The maximum lower limits of detection (LLD) for the analytical measurements are specified in the PNPS Effluent Controls Table 4.5-1 (see Appendix B for the definitions of the lower limit of detection). The environmental TLD location designations, distance, and direction from the reactor are listed in Table 3.5-2. The radiation measurement locations for the environmental TLDs are shown in Figures 3.5-1 through 3.5-5. The frequency and type of radiation measurement is described in the PNPS Effluent Control 3/4.5.1, Table 3.5-1. The pressurized ion chamber measurement locations, distance, and direction from the reactor are listed in Table 3.5-3. These radiation measurement locations for the surveys performed on local beaches. The frequency and type of radiation measurement is described in PNPS Effluent Control 3/4.5.1, Table 3.5-1. The atmospheric and land-based samples are collected by Entergy personnel. The aquatic samples are collected by an external contractor experienced with diving and marine sampling. The radioactivity analyses of samples and the processing of the environmental TLDs are performed by external laboratories certified to perform these types of analyses. The PNPS staff reviews the radioactivity analysis results from the contractor laboratory. Reporting levels for radioactivity concentrations in environmental samples are listed in PNPS Effluent Controls Table 3.5-4. If the radioactivity concentrations are above the reporting levels, the NRC is notified in writing within 30 days. A determination of the cumulative dose contribution for the current year will be performed for radioactivity which is detected that is attributable to PNPS operation. Depending upon the circumstances, a special study may also be conducted. If radioactivity levels in the environment become elevated as a result of the station's operation, an investigation is performed, and corrective actions are recommended to reduce the amount of radioactivity to as far below the legal limits as is reasonably achievable. The radiological environmental sampling and measurement locations are reviewed annually, and modified if necessary. A garden and milk animal census is performed every year to identify changes in the use of the environment in the vicinity of the station to permit modification of the sampling and measurement locations. 11-1 170

PNPS-ODCM Rev. 11 The original radiological monitoring program was modeled after guidance from the NRC presented in Regulatory Guide 4.8 (reference 29). Shortly after the inception of Regulatory Guide 4.8 in 1975, the NRC began to solicit comments on the environmental monitoring guidelines. The NRC working group modified the environmental monitoring guidelines, and issued the revised guidance in the form of Revision 1 to the Branch Technical Position on an acceptable radiological environmental monitoring program (reference 28). In turn, the Branch Technical Position became the model for environmental monitoring put forth in NUREG-1302. Notable changes in the Branch Technical Position were the elimination of soil sampling, and increased reliance on direct radiation monitoring using environmental thermoluminescent dosimeters (TLDs). Upon review of the PNPS radiological environmental monitoring program in 2002, several departures from the model program outlined in NUREG-1302 were noted .. PNPS was still using the soil sampling program of once per three years outlined in Regulatory Guide 4.8. Also, PNPS was using an annual assessment of direct radiation at six locations using a pressurized ion chamber, in addition to the 11 O TLDs posted around the plant. Based on the extensive monitoring of airborne particulates and iodines above and beyond that prescribed by NUREG-1302, any buildup of plant-related activity in soil would be first indicated in airborne monitoring. Due to the extent and sensitivity of the airborne monitoring efforts, soil sampling and analysis was dropped from the sampling program. In a similar fashion, the integrating nature of TLDs makes this approach to monitoring direct radiation the preferred method, and industry standard. Again, since the PNPS TLD placement far exceeds that prescribed by NUREG-1302, assessment of direct radiation through use of pressurized ion chamber measurements was dropped in lieu of the extensive TLD monitoring effort. In 1977, Boston Edison Company was pursuing construction of a second unit on the PNPS site. As part of the preliminary licensing efforts for this second unit, Pilgrim Station committed to an special marine sampling program under the REMP. This program was much more aggressive than that outlined in standard NRC guidance for an environmental monitoring program, and included collecting many more samples, duplicate/split sampling, analysis of special radionuclides, and analysis to detection limits lower than those recommended by the NRC. This specialized sampling program was agreed to by Boston Edison Company for a period not to exceed 1O years. Due to the inclusion of the REMP in the Technical Specifications at that time, the program was carried forward beyond the 10-year period. Following an evaluation of results obtained by this specialized marine sampling program over the past 25 years, it has been determined that the results have shown that the impact of radioactivity in liquid discharges on the general public and environment is negligible. In light of the fact that the terms of the sampling program have expired, the specialized program is no longer warranted. Furthermore, replacement of the specialized program with a marine sampling program such as that prescribed by the NRC in NUREG-1302 and the Branch Technical Position on Environmental Monitoring will still allow PNPS personnel to evaluate the impact of its operations on the environment and general public. Therefore, PNPS has dropped most of the specialized requirements and has adopted the standard model for marine sampling prescribed by the NRC. 11-2 171

PNPS-ODCM Rev. 11 12.0 ANNUAL REPORT PREPARATION 12.1 Radioactive Effluent Release Report The annual Radioactive Effluent Release Report covering the operation of Pilgrim Nuclear Power Station during the previous calendar year shall be submitted by May 15 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid wastes released from the facility. This report shall be submitted in accordance with 10CFR50.36a. General guidance for the preparation of this report can be found in Regulatory Guide 1.21 (Reference 26). In addition to effluent and disposal data, this report should also include summaries of meteorological data in the form of joint frequency distribution tables. This report should present an evaluation of the doses received by members of the public resulting from operation of Pilgrim Station. Liquid and airborne effluent pathways, as discussed in ODCM Section 9, should be used to assess the doses, as well as ambient (direc;t) radiation exposure resulting from plant operation. In addition to summarizing effluents and their resulting doses, the annual Radioactive Effluent Release Report serves as the vehicle to notify the NRC of any changes in the ODCM. Changes to the ODCM during the previous calendar year shall be submitted in the annual Radioactive Effluent Release Report. 12.2 Annual Radiological Environmer:ital Operating Report The Annual Radiological Environmental Operating Report covering the operation of Pilgrim Nuclear Power Station during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in other sections of the ODCM, as well as 10CFR50 Appendix I, Sections IV.8.2, IV.8.3, and IV.C. The Annual Radiological Environmental Operating Report shall include tables summarizing the results of analyses of radiological environmental samples and environmental radiation measurements taken during the period, pursuant to the locations specified in Section 3/4.5 of the ~ ODCM. Summarized and tabulated results of these analyses and measurements shall be similar in format to guidance provided in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion in the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible. 12-1 172

PNPS-ODCM Rev. 11

13.0 REFERENCES

1) PNPS Technical Specifications.

2) U. S. Nuclear Regulatory Commission, Generic Letter 89-01, "Implementation of Programmatic Controls for R~dioactive Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program", January 1989.

3) Updated Final Safety Analysis Report for Pilgrim Nuclear Power Station, Volumes 1 through 7.

4) Boston Edison Company, Pilgrim Station Unit 1 Appendix I Evaluation, April, 1977.

5) General Electric Company, GEK-32445A, Pilgrim Process Radiation Monitoring System Manual.

6) PNPS Maintenance Department Recalibration and Malfunction Records.

7) PNPS Operations Manual, Volume 7, Book 2: Chemical and Radiochemical Procedures.

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

9) D.L. Strenge, T.J. Bander, and J.K. Soldat, NUREG/CR-4653, "GASPAR II Technical Reference and User Guide", March 1987.

10) "HERMES", A Digital Computer Code for Estimating Regional Radiological Effects from the Nuclear Power Industry, HEDL-TME-N1-168, December 1971.

11) G. L. Toombs and P. B. Culter, "Comprehensive Final Report for the Lower Columbia River Environmental Survey in Oregon June 5, 1961 - July 31, 1967," Oregon State Board of Health, Division of Sanitation and Engineering, 1968.

12) U.S. Nuclear Regulatory Commission, NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", Revision 2, May, 1982.

13) J.N. Hamawi, "AEOLUS", Yankee Atomic Electric Company YAEC-1120, 1977.

14) J. N. Hamawi, "SKIRON", Yankee Atomic Electric Company YAEC-1138, 1977.

15) U.S. Nuclear Regulatory Commission, NUREG/CR-3332, "Radiological Assessment",

December 1983.

16) D. F. Bunck (ed.), USAEC Report 100-12063, "Controlled Environmental Radioiodine Test, Progress Report Number Two", January 1968.

17) J. D. Zimbrick and P. G. Voilleque, USAEC Report 100-12065, "Controlled Environmental Radioiodine Tests at the National Reactor Testing Station, Progress Report Number Four,"

December 1968. 13-1 173

PNPS-ODCM Rev. 11

13.0 REFERENCES

(continued)

18) F. 0. Hoffman, IRS-W-6, "Environmental Variables Involved with the Estimation of the Amount of 1311 in Milk and the Subsequent Dose to the Thyroid," Institute fur Reaktorsicherheit, June 1973.

19) F. 0. Hoffman, IRS-W-13, "A Reassessment of the Parameters Used To Predict the Environmental Transport of 1311 from Air to Milk," Institute fur Reaktorsicherheit, April 1975.

20) C. A. Pelletier and P. G. Voilleque, Health Physics, Vol. 21, p. 777, "The Behavior of 137cs and Other Fallout Radionuclides on a Michigan Dairy Farm," 1971.

21) P. G. Voilleque and C. A. Pelletier, Health Physics, Vol. 27, p. 189, "Comparison of External Irradiation and Consumption of Cow's Milk as Critical Pathways for 137Cs, 54Mn, and 144ce-144pr Released to the Atmosphere", 1974.

22) L. R. Anspaugh et al., USAEC Report UCRL-73195, Rev. 1, "The Dose to Man via the Food-Chain Transfer Resulting from Exposure to Tritiated Water Vapor", 1972.

23) Y. C. Ng et al., USAEC Report UCRL-50163, Part IV, "Prediction of the Maximum Dosage to Man from the Fallout of Nuclear Devices, IV Handbook for Estimating the Maximum Internal Dose from Radionuclides Released to the Biosphere," 1968.

24) R. C. Weast (ed.), "Handbook of Chemistry and Physics," CRC Press, 1970.

25) U.S. Nuclear Regulatory Commission, NUREG-75/021, "Detailed Measurement of 1-131 in Air, Vegetation and Milk Around Three Operating Reactor Sites," March 1975.

26) U.S. Nuclear Regulatory Commission, Regulatory Guide 1.21, "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", Revision 1, June 1974.

27) U.S. Nuclear Regulatory Commission, NUREG-1302, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors", April 1991.

28) U.S. Nuclear Regulatory Commission, Radiological Assessment Branch Technical Position, Revision 1, November 1979.

29) U.S. Nuclear Regulatory Commission, Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants", December 1975.

13-2 174

PNPS-ODCM Rev. 11 APPENDIX A DATA REQUIRED FOR EFFLUENT CALCULATIONS TABLE A-1 BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPECIFIC DATA pCi/kg per pCi/liter< 1l FRESHWATER SALTWATER ELEMENT FISH INVERTEBRATE FISH INVERTEBRATE H 9.0E-01 9.0E-01 9.0E-01 9.3E-01 C 4.6E+03 9.1E+03 1.8E+03 1.4E+03 Na 1.0E+02 2.0E+02 6.7E-02 1.9E-01 p 1.0E+05 2.0E+04 2.9E+04 3.0E+04 Cr 2.0E+02 2.0E+03 4.0E+02 2.0E+03 Mn 4.0E+02 ! 9.0E+04 5.5E+02 4.0E+02 Fe 1.0E+02 ' 3.2E+03 3.0E+03 2.0E+04 Co 5.0E+01 2.0E+02 1.0E+02 1.0E+03

                                        'i Ni               1.0E+02                1.0E+02               1.0E+02           2.5E+02 Cu               5.0E+01                4.0E+02               6.7E+02           1.7E+03 Zn               2.0E+03                1.0E+04               2.0E+03           5.0E+04 Br               4.2E+02                3.3E+02               1.5E-02           3.1E+OO Rb               2.0E+03                1.0E+03               8.3E+OO           1.7E+01 Sr               3.0E+01                1.0E+02               2.0E+OO           2.0E+01 y               2.5E+01                1.0E+03               2.5E+01            1.0E+03 Zr               3.3E+OO                6.7E+OO               2.0E+02           8.0E+01 Nb               3.0E+04                1.0E+02               3.0E+04            1.0E+02 Mo               1.0E+01                1.0E+01               1.0E+01            1.0E+01 Tc               1.5E+01                5.0E+OO               1.0E+01           5.0E+01 Ru               1.0E+01                3.0E+02               3.0E+OO            1.0E+03 Rh               1.0E+01                3.0E+02               1.0E+01           2.0E+03 Te               4.0E+02                6.1E+03               1.0E+01            1.0E+02 I               1.5E+01                5.0E+OO               1.0E+01            5.0E+01 Cs               2.0E+03                1.0E+03               4.0E+01           2.5E+01 Ba               4.0E+OO                2.0E+02               1.0E+01            1.0E+02 La               2.5E+01                1.0E+03               2.5E+01            1.0E+03 Ce               1.0E+OO                1.0E+03               1.0E+01            6.0E+02 Pr               2.5E+01                1.0E+03               2.5E+01            1.0E+03 Nd               2.5E+01                1.0E+03               2.5E+01            1.0E+03 w                1.2E+03                1.0E+01               3.0E+01      !     3.0E+01 Np               1.0E+01                4.0E+02               1.0E+01      !     1.0E+01 1

<l Data presented in this table are from Reference 8. A-1 175

PNPS-ODCM Rev. 11 TABLE A-2 DOSE FACTORS FOR IMMERSION IN WATER< 1l mrem/hr per pCi/Liter<2> NUCLIDE SKIN TOTAL BODYl~J H-3l4 ! O.OE+OO O.OE+OO N-13 2.6E-06 1.9E-06 C-14t4 ! 3.8E-06 O.OE+OO Na-22 4.8E-06 4.0E-06 Na-24 9.3E-06 7.8E-06 Cr-51 6.4E-08 5.2E-08 Mn-54 1.8E-06 1.SE-06 Fe-55l"! 3.6E-10 6.4E-11 Fe-59 2.6E-06 2.2E-06 Co-58 2.3E-06 1.8E-06 Co-60 5.4E-06 4.6E-06 Ni-63 O.OE+OO O.OE+OO Cu-64 5.2E-07 3.?E-07 Zn--65 1.2E-06 1.1 E-06 Sr-89l"! 5.4E-07 4.6E-09 Sr-90l"! 1.SE-07 5.4E-10 Y-9Ql"I 9.6E-07 1.3E-08 Sr+ Y-90t"1-t 01 1.1 E-06 1.3E-08 Zr-95 1.8E-06 1.SE-06 Nb-95 1.6E-06 1.4E-06 Mo-99 9.1 E-07 4.?E-07 Ru-103 1.1 E-06 8.9E-07 Ru-106 1.9E-06 3.8E-07 Te-132 4.8E-07 4.0E-07 1-129 6.1E-09 2.1E-09 1-131 9.SE-07 6.8E-07 1-132 5.SE-06 4.4E-06 1-133 1.SE-06 9.6E-07 1-135 4.0E-06 3.3E-06 Cs-134 3.SE-06 2.9E-06 Cs-137 1.4E-06 1.0E-06 Ba-140 7.6E-07 4.6E-07 La-140 5.3E-06 4.1E-06 Ce-141 2.4E-07 ~ 1.3E-07 Ce-144 6.2E-08 i 3.0E-08 Pr-144 1.3E-06 j 5.6E-08 Ce+Pr-144u 1 1.4E-06 'i 8.6E-08 1

 <> Data presented in this table are from Reference 10.

2

 <> The same factors apply to adult, teenager, and child.

3

 <> Total body factors also apply to other internal organs.

4

 <l Not including penetration of oxide into skin.

5

 <l Includes bremsstrahlung.

5

 <l Use these factors for Sr-90 unless Y-90 concentration is given separately.

7

 <l Use these factors for Ce-144 unless Pr-144 concentration is given separately.

A-2 176

PNPS-ODCM Rev. 11 TABLE A-3 RECOMMENDED VALUES FOR LIQUID EFFLUENTS(1> Parameter Symbol Parameter Description Values Mixing ratio at location I of exposure 0.2 (Aquatic foods taken from Discharge or harvest of aquatic foods** Canal Outfall) (2 > 0.05 (Shoreline, Pilgrim Station Recreational Area) (3> 1.0 (Shoreline, Discharge Canal) 0.03 (Swimming, White Horse Beach) 0.03 (Boating, Cape Cod Bay) Period of time between exposure of 24 hr for maximum individual aquatic foods to radionuclides in water and their consumption 168 hr for average individual, sport fish doses 240 hr for average individual, commercial fish doses Shoreline width factor for location I 0.5 (Recreational Area) (4> 0.1 (Discharge Canal) (4> 1 ( > Data presented in this table are from Reference 8 unless otherwise noted. 2 ( > Collection of aquatic foods from within the Discharge Canal is prohibited. 3 ( > Swimming is prohibited at Pilgrim Station Recreational Area. 4 ( > From Reference 4. A-3 177

PNPS-ODCM Rev. 11 TABLE A-4 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES(1l p-air (DFNiP) p-skin (DFNis) y-air (DFNjy) y-body (DFNiTB) Nuclide mrad-m3/pCi-yr mrem-m~/pCi-yr mrad-m3/pCi-yr mrem-m3/pCi-yr Kr-83m 2.88E-04 --- 1.93E-05 7.56E-08 Kr-85m 1.97E-03 1.46E-03 1.23E-03 1.17E-03 Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61 E-05 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 Kr-89 1.06E-02 1.01 E-02 1.73E-02 1.66E-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 Xe-131m 1.11 E-03 4.76E-04 1.56E-04 9.15E-05 Xe-133m 1.48E-03 9.94E-04 3.27E-04 2.51E-04 Xe-133 1.05E-03 3.06E-04 3.53E-04 2.94E-04 Xe-135m 7.39E-04 7.11E-04 3.36E-03 3.12E-03 Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81 E-03 Xe-137 1.27E-02 1.22E-02 1.51 E-03 1.42E-03 Xe-138 4.75E-03 4.13E-03 9.21E-03 8.83E-03 Ar-41 3.28E-03 2.69E-03 9.30E-03 8.84E-03 1 ( ) Data presented in this table are from Reference 8. A-4 178

PNPS-ODCM Rev. 11 TABLE A-5 STABLE ELEMENT TRANSFER DATA( 1J Biv Fm(Cow) Ft Element Veg/Soil Milk (day/liter) Meat (day/kg) H 4.8E+OO 1.0E-02 1.2E-02 C 5.5E+OO 1.2E-02 3.1 E-02 Na 5.2E-02 4.0E-02 3.0E-02 p 1.1 E+OO 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 1.2E-03 4.0E-02 Co 9.4E-03 1.0E-03 1.3E-02 Ni 1.9E-02 6.?E-03 5.3E-02 Cu 1.2E-01 1.4E-02 8.0E-03 Zn 4.0E-01 3.9E-02 3.0E-02 Rb 1.3E-01 3.0E-02 3.1E-02 Sr 1.?E-02 8.0E-04 6.0E-04 y 2.6E-03 1.0E-05 4.6E-03 Zr 1.?E-04 5.0E-06 3.4E-02 Nb 9.4E-03 2.5E-03 2.SE-01 Mo 1.2E-01 7.5E-03 8.0E-03 Tc 2.5E-01 2.5E-02 4.0E-01 Ru 5.0E-02 1.0E-06 4.0E-01 Rh 1.3E+01 1.0E-02 1.5E-03 Ag 1.5E-01 5.0E-02 1.?E-02 Te 1.3E+OO 1.0E-03 7.?E-02 I 2.0E-02 6.0E-03 2.9E-03 Cs 1.0E-02 1.2E-02 4.0E-03 Ba 5.0E-03 4.0E-04 3.2E-03 La 2.5E-03 5.0E-06 2.0E-04 Ce 2.5E-03 1.0E-04 1.2E-03 Pr 2.5E-03 5.0E-06 4.?E-03 Nd 2.4E-03 5.0E-06 3.3E-03 w 1.SE-02 5.0E-04 1.3E-03 Np 2.5E-03 5.0E-06 2.0E-04 1 ( ) Data presented in this table are from Reference 8. A-5 179

PNPS-ODCM Rev. 11 TABLE A-6 NUCLIDE TRANSFER PARAMETERS FOR GOAT'S MILK<1> Element Fm (day/liter) H 1.?0E-01 C 1.00E-01 p 2.50E-01 Fe 1.30E-04 Cu 1.30E-02 Sr 1.40E-02 6.00E-02 Cs 3.00E-01 TABLE A-7 ANIMAL CONSUMPTION RATES< 1> QF QAW Feed or Forage Water Animal (kg/day [wet weight]) (liter/day) Milk Cow 50 60 Beef Cattle 50 50 Goats 6 8 1 < l Data presented in these tables are from Reference 8. A-6 180

PNPS-ODCM Rev. 11 TABLE A-8 RECOMMENDED USE FACTORS TO BE APPLIED FOR THE AVERAGE INDIVIDUAL<1J,<2l Pathway Adult Teen Child Infant Fruits, vegetables, & grain (kg/yr) 190 240 200 Milk (liter/yr) 110 200 170 330 Meat & poultry (kg/yr) 95 59 37 Fish (kg/yr) 6.9 5.2 2.2 Seafood (kg/yr) 1.0 0.75 0.33 Drinking Water (liter/yr) 370 260 260 330 3 Shoreline recreation (hr/yr) < l Discharge Canal 8.3 47 9.5 Pilgrim Station Recreational Area 8.3 47 9.5 Swimming (hr/yr) <3l 52 52 29 White Horse Beach Boating - Cape Cod Bay (hr/yr) <3l 52 52 29 Inhalation (m 3/yr) 8000 8000 3700 1400 (1) Data presented in this table are from Reference 8, unless otherwise indicated. (2) Usage factors for the average individual are used to determine the annual dose to the total body and thyroid of an average individual and the annual integrated dose to the population within a 50 mile radius. (3) From Reference 4. A-7 181

PNPS-ODCM Rev. 11 TABLE A-9 RECOMMENDED USE FACTORS TO BE APPLIED FOR THE MAXIMUM EXPOSED INDIVIDUAL(1> Pathway Fruits, vegetables, & grain (kg/yr) 520 630 520 Leafy Vegetables (kg/yr)) 64 42 26 Milk (liter/yr) 310 400 330 330 Meat & poultry (kg/yr) 110 65 41 Fish (fresh or salt) (kg/yr) 21 16 6.9 Shellfish (kg/yr) (2> 9 6 3 Drinking Water (liter/yr) 730 510 510 330 Shoreline recreation (hr/yr) (2> Discharge Canal 12 67 14 Pilgrim Station Recreational Area 12 67 14 Swimming (hr/yr) (2> 52 52 29 White Horse Beach Boating-Cape Cod Bay (hr/yr) (2> 52 52 29 3 Inhalation (m /yr) 8000 8000 3700 1400 1 ( > Data presented in this table are from Reference 8, unless otherwise indicated. 2 ( > From Reference 4. A-8 182

PNPS-ODCM Rev. 11 TABLE A-10 1 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND < l mrem/hr per pCi/m2 Nuclide I Total Body Skin Nuclide I Total Body Skin H-3 O.OOE+OO O.OOE+OO Zr-93 O.OOE+OO O.OOE+OO Be-10 j O.OOE+OO j O.OOE+OO Zr-95 j 5.00E-09 j 5.80E-09

  *****************c-14******************j* ***o.OOE+oo"***********i"""** *o.OOE+OO ..... .......                                          Zr-9i""                            i". . . . . 5.50E-09                 j        ... 6.40E-09****

N-13 j 7.60E-09 j 8.80E-09 Nb-93m j 8.20E-13 j 1.00E-10 F-18 j 6.80E-09 j 8.00E-09 Nb-95 j 5.1 OE-09 j 6.00E-09 Na-22 j 1.60E-08 j 1.80E-08 Nb-97 j 4.60E-09 j 5.40E-09 Na-24 j 2.50E-08 j 2.90E-08 Mo-93 j 2.29E-11 ! 9.32E-10 P-32 j O.OOE+OO j O.OOE+OO Mo-99 j 1.90E-09 j 2.20E-09 Ca-41 j 3.41E-09 j 4.01E-09 Tc-99m j 9.60E-10 j 1.10E-09 Sc-46 j 1.30E-08 j 1.50E-08 Tc-99 j O.OOE+OO ! O.OOE+OO Cr-51 ! 2.20E-10 j 2.60E-10 Tc-101 j 2.70E-09 j 3.00E-09 Mn-54 ! 5.80E-09 j 6.80E-09 Ru-103 j 3.60E-09 j 4.20E-09 Mn-56 j 1.1 OE-08 j 1.30E-08 Ru-105 j 4.50E-09 j 5.1 OE-09 Fe-55 j O.OOE+OO ! O.OOE+OO Ru-106 j 1.50E-09 j 1.80E-09 Fe-59 j 8.00E-09 j 9.40E-09 Rh-105 j 6.60E-10 j 7.70E-10

               ***co-57 .......... \                        9.'foE-10 ...... ('                   1.00E-09             ........ Pd-107                                         j            O.OOE+OO                 j            O.OOE+OO Co-58                     j             7.00E-09                j             8.20E-09                                Pd-109                                j             3.50E-11                j             4.00E-11
................. Co-6 0................. !.............1 .7 0E-08 ...........    .L. . . . . 2_. 00 E-08 ........... ........... Ag-1.1 _0m .......... ...! .............1 .80 E-08 ............ !............ 2 ..1. 0 E-08 ............
.................. Ni-59 .................. :........... O.OOE+oo............ t............o.. ooE+oo........... ............. A.9-1.1.1 ........... *.J . . . . . . .1.. 80E-1.o............. t............ 2.1.0E-1 o.............

Ni-63 i O.OOE+OO i O.OOE+OO Cd-113m i 2.30E-12 i 2.60E-12

.................. Ni-65 .................. j............ 3. 70E-09 ............ j'" .......... 4.30E-09 .................... *cd-fr5m ... j............O.OOE+OO                                                     j ... O.OOE+OO .
    .............. Cu-64 ................. j .........1.50E-09 ............ j........1.70E-09........... ....... Sn-123                                                        j"........O.OOE+OO j                                6.46E-08 Zn-65                     j             4.00E-09                 j            4.60E-09                                Sn-125                                j             5.70E-10                j             6.60E-10 Zn-69m                        j            2.90E-09                 j            3.40E-09                                Sn-126                                j             9.00E-09                j             1.00E-08
            ...... Zn-69. .. ......... j                  *o.*ooE+Oo"........... j....           O.OOE+OO ....... .......                Sb-124                                !         ... 1.30E-08                j             1.50E-08
=     =::r1i=: =! =H~rH =! = mHf ===!~=1i~ =!= iig;:gi _: !=rn11i: _

Br-84 j 1.20E-08 j 1.40E-08 Te-125m j 3.50E-11 j 4.80E-11 Br-85 j O.OOE+OO j O.OOE+OO Te-127m j 1.10E-12 j 1.30E-12

 ................. Rb-86 ................. j............ 6.30E-1*o*........... j...........'i.20E-10 ......................... Te-127 ........ ( ....... 1.00E-1*1*                                                   j             1.1 OE-11

=: ~r:i =: =! =H~r~f: =! ==; ~~i~~r == ==::~;!!£_:_=t==-rnrn- -!- -rnrn---

 ..................~~:~~---**..*********.. i*******..   **-i.*ig::b~*-..* * . **1********..**i.*ig::b~........... .. . . . . . i:: ~ ~~. . . . . . . . 1............ ~*:~~~:~~ ............ 1............ ~-:~~~:~~ ............

Sr-91 j 7.10E-09 \ 8.30E-09 Te-133m j 1.50E-08 j 1.70E-08

 .................. S r-92 .................. j.............9. 0 0E-09 ............ j.............1 .00 E-08 ........... .............. T e-1.34................               i. . . . . . .1: 00 E-0 9 ............ j.............1.: 2 0E-0 9 ............

Y-90 i 2.20E-12 i 2.60E-12 i i

=:::_:Yt::::::!==:;*~gi:!!=!==1*igrn====:::: ::::: ::::::! =: : : : : : =i=--=: ====

Y-93 j 5.70E-10 j 7.80E-10 ....................................................i j 1 ( l Data presented in this table are from Reference 9. A-9 183

PNPS-ODCM Rev. 11 TABLE A-10 (continued) 1 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND <> mrem/hr per pCi/m2 Nuclide I Total Body Skin Nuclide I Total Body Skin 1-129 4.50E-10 i 7.50E-10 Pb-210 1.30E-11 1.?0E-11 ...................l-130"""""""*".. i"". . . . .1.40E-08 ............ ('..""""1. ?OE-08 ........... ............... Bi-21* o*.. .. (""".."o.ooE+OO ........... j"..........O. OOE+oo"""...... 1-131 i 2.80E-09 i 3.40E-09 Po-210 i 5.40E-14 i 6.20E-14 1-132 ! 1.?0E-08 i 2.00E-08 Ra-223 ! 1.50E-09 i 1.80E-09 1-133 i 3.?0E-09 i 4.50E-09 Ra-224 i 8.90E-09 i 1.00E-08 1-134 i 1.60E-08 ! 1.90E-08 Ra-225 ! 8.40E-11 i 1.20E-10 1-135 i 1.20E-08 ! 1.40E-08 Ra-226 ! 6.40E-09 ! 7.40E-09 Cs-134m ! 6.20E-10 ! 7.30E-10 Ra-228 ! 1.20E-08 i 1.40E-08 Cs-134 \ 1.20E-08 ! 1.40E-08 Ac-225 ! 1.60E-09 \ 1.80E-09 Cs-135 i O.OOE+OO ! O.OOE+OO Ac-227 i 2.00E-09 ! 2.40E-09 Cs-136 i 1.50E-08 ! 1.?0E-08 Th-227 ! 5.10E-10 ! 6.30E-10 Cs-137 i 4.20E-09 ! 4.90E-09 Th-228 i 8.90E-09 ! 1.00E-08 Cs-138 i 2.10E-08 ! 2.40E-08 Th-229 i 2.20E-09 ! 2.?0E-09 Cs-139 i 6.30E-09 ! 7 .20E-09 Th-230 ! 6.50E-09 ! 7 .50E-09 Ba-139 i 2.40E-09 i 2.?0E-09 Th-232 i

............... Ba-1.40 ............... ("........ 2.1.0E-09 ............ ("........ i.40E-09 ......................... Th-234.............. i. . . . . . .1.1.0E-10 ...

3.00E-09 i f ...... 4.00E-09 1.. 30E-10 ..... .. Ba-141 i 4.30E-09 i 4.90E-09 Pa-231 ! 2.20E-09 i 2.?0E-09 Ba-142 i 7.90E-09 ! 9.00E-09 Pa-233 ! 1.30E-09 i 1.50E-09 La-140 ! 1.50E-08 i 1.?0E-08 U-232 i 2.59E-12 i 2.69E-11 La-141 ! 2.50E-10 i 2.80E-10 U-233 i 2.30E-09 ! 2.80E-09 La-142 ! 1.50E-08 i 1.80E-08 U-234 i 6.32E-13 ! 1.59E-10 Ce-141 ! 5.50E-10 i 6.20E-10 U-235 i 3.20E-09 ! 4.00E-09 Ce-143 ! 2.20E-09 ! 2.50E-09 U-236 i 2.10E-14 i 1.80E-11 Ce-144 i 3.20E-10 ! 3.?0E-10 U-237

................ Pr-143 ................ i"". . . . o.'ooE+oo ........... ( .........o.ooE+oo .......................... U-238 ..........

i

i. . . . . . 1.00E-09

{*1*0E-1 o ii . . . . .1.30E-09 1.50E-1 o

................ Pr-1. 44 ...............J.. . . . . 2. 0 0E-1.0 ............ i... . . . . 2. 30 E-1 0 ........... .............. Np-237 ...............i.............1.40 E-09 ............ i. . . . . . .1... 60 E-09 ............
............... Nd-1. 47...............!.............1.0 0E-09 ............!.............1.. 20E-09 ........... .............. Np-2 38 ............... !............ 2_. 80 E-09 ............ L........... 3_. 20 E-09 ............

Pm-147 : O.OOE+OO : O.OOE+OO Np-239 : 9.50E-10 i 1.10E-09 Pm-148m i 1.41E-08 i 8.16E-08 Pu-238 i 1.30E-12 i 1.80E-11 Pm-148 \ 4.60E-09 \ 5.30E-09 Pu-239 \ 7.90E-13 \ 7.?0E-12

.............. Pm-149 ............. ( ......... 2.SOE-1.f........... i. . . 2.90E-1.f.......                                  ..Pu-240.                       i 1.30E-12 i 1.80E-11 Pm-151                    i 2.20E-09                          i            2.30E-09                               Pu-241                      i            4.60E-12            i             6.80E-12 Sm-151                    i          4.80E-11                 i            2.10E-10                               Pu-242                      ! 1.10E-12                       !             1.60E-11 Sm-153                     !          2.?0E-10                 i 3.00E-10                                          Pu-244                      !            8.95E-10            !             9.62E-10 Eu-152                   !          7.37E-09                 i 8.53E-09                                        Am-241                        !            1.80E-10            !             2.60E-10 Eu-154                   !          7.80E-09                 !            9.00E-09                          Am-242m                          i 2.60E-11                       !              1.80E-10 Eu-155                   ! 3.81E-10 i 4.33E-10                                                                 Am-243                        i 1.30E-09                       !              1.50E-09 Eu-156                   !          7.60E-09                 !            8.?0E-09                             Cm-242                        i 5.50E-12
 ............... Tb-160 ............... ("........ 8.60E-09 ............ j"...........1.00E-08 ........... ............. Cm-243 ....... .... ( ........ i.30E-09 ii ..         2.30E-11

2. 90E-09 Ho-166m i 8.90E-09 i 1.00E-08 Cm-244 i 2.90E-12 i 1.80E-11

 . . . . . . . .::~-~;. . . . . . . . i. . . . . . ~_-6gi~6~"""*""*l. . . . . . ~_-ig:~6~"""'". . . . . . . .g~:~:~ . . . . . . . j............ ;:~~~:~*~ ............ j.............~ *:;~~:~; ............

W-187 i 3.1 OE-09 i 3.60E-09 Cm-247 i 2.20E-09 i 2.60E-09 i i Cm-248 ! 6.81 E-09 ! 5.23E-09 i i . . . . . . . .ff.:.??..?..................i 6.60E-08 i 7.20E-08 1 < > Data presented in this table are from Reference 9. A-10 184

PNPS-ODCM Rev. 11 TABLE A-11 INHALATION DOSE FACTORS FOR ADULT< 1) mrem/pCi Inhaled 1 : j Total 1 i : Nuclide ! Bone I Liver 1 Body I Thyroid I Kidney ! Lung l GI-LLI H-3 I No Data I 8.98E-08 I 8.98E-08 i 8.98E-08 I 8.98E-08 i 8.98E-08 i 8.98E-08 Be-10 ! 1.98E-04 ! 3.06E-05 i 4.96E-06 i No Data i No Data i 2.22E-04 i 1.67E-05 C-14 ! 2.27E-06 ! 4.26E-07 i 4.26E-07 i 4.26E-07 i 4.26E-07 i 4.26E-07 i 4.26E-07 N-13 i 6.27E-09 i 6.27E-09 i 6.27E-09 i 6.27E-09 i 6.27E-09 i 6.27E-09 i 6.27E-09 F-18 i 4. 71 E-07 i No Data i 5.19E-08 i No Data i No Data i No Data i 9.24E-09 Na-22 i 1.30E-05 ! 1.30E-05 i 1.30E-05 i 1.30E-05 i 1.30E-05 i 1.30E-05 ! 1.30E-05 Na-24 i 1.28E-06 i 1.28E-06 i 1.28E-06 ! 1.28E-06 i 1.28E-06 i 1.28E-06 ! 1.28E-06 P-32 i 1.65E-04 i 9.64E-06 i 6.26E-06 ! No Data ! No Data ! No Data ! 1.08E-05 Ca-41 i 3.83E-05 i No Data i 4.13E-06 / No Data i No Data ! 3.83E-06 ! 2.86E-07 Sc-46 ! 5.51 E-05 ! 1.07E-04 ! 3.11 E-05 ! No Data ! 9.99E-05 i No Data ! 3.23E-05 Cr-51 ! No Data ! No Data ! 1.25E-08 ! 7.44E-09 ! 2.85E-09 ! 1.80E-06 ! 4.15E-07 Mn-54 ! No Data ! 4.95E-06 ! 7.87E-07 ! No Data ! 1.23E-06 ! 1.75E-04 i 9.67E-06

--~;:~i~---*-**--***---*---l---~-~-f:_~5-*-------l---~:;;~:ci~--****--*l-*-!:~;~:ci}-*****--l***~~--g:~:-----------l---~~tE;tlO***----**l---~:-~~~:~~----****-l**~:~!~:~~--------

Fe-59 ! 1.47E-06 i 3.47E-06 ! 1.32E-06 i No Data i No Data i 1.27E-04 ! 2.35E-05 Co-57 ! No Data i 8.65E-08 ! 8_39E-08 i No Data i No Data ! 4.62E-05 i 3.93E-06 Co-58 ! No Data ! 1.98E-07 ! 2.59E-07 i No Data i No Data ! 1.16E-04 ! 1.33E-05 Co-60 ! No Data i 1.44E-06 ! 1.85E-06 i No Data i No Data i 7.46E-04 ! 3.56E-05 Ni-59 \ 4.06E-06 i 1.46E-06 \ 6.77E-07 i No Data i No Data i 8.20E-06 i 6_ 11 E-07 Ni-63 ! 5.40E-05 i 3.93E-06 ! 1.81 E-06 i No Data i No Data i 2.23E-05 i 1.67E-06 Ni-65 ! 1.92E-10 ! 2.62E-11 ! 1.14E-11 ! No Data \ No Data i 7.00E-07 ! 1.54E-06 Cu-64 ! No Data ! 1.83E-10 \ 7.69E-11 ! No Data ! 5.78E-10 ! 8.48E-07 ! 6.12E-06 Zn-65 i 4.05E-06 i 1.29E-05 i 5.82E-06 i No Data ! 8.62E-06 i 1.08E-04 i 6.68E-06 Zn-69m i 1.02E-09 i 2.45E-09 i 2.24E-10 ! No Data ! 1.48E-09 i 2.38E-06 ! 1.71 E-05 Zn-69 ! 4.23E-12 ! 8.14E-12 ! 5.65E-13 ! No Data i 5.27E-12 ! 1.15E-07 ! 2.04E-09 Se-79 ! No Data ! 3.83E-07 ! 6_09E-08 i No Data ! 5.69E-07 ! 4.47E-05 ! 3.33E-06

*--~~:~~---------------*-*--*i---~~--g:!:------------i---~~--g:!:-*-********-i*-*~:~~~:~~----*---i*--~~--g:!:***-***--**i***~~-g:!:---***----**i---~~--g:!:-****--*-**-i--~:~~~:~:*******-

Br-84 i No Data i No Data i 3.91E-08 i No Data i No Data i No Data i 2.05E-13 Br-85 i No Data i No Data ! 1.60E-09 i No Data i No Data i No Data ( l'-i"o -Data Rb-86 i No Data i 1.69E-05 i 7.37E-06 i No Data i No Data i No Data i 2.08E-06

*--~~:~~ . . . ._. _,,_ _ _ i*--~~-g:!:--..- . ,-. J-- !:~:~:~:-*-. *---!-* ~:!*~*~:~:--*-*--*l---~~ . g:!:--***--**-*i"*~~. g:!:-*---*--*---i"-~~ --g:!:**"'"""'"i" !:~~~:~;-----..-

Rb-89 i No Data i 3.20E-08 i 2.12E-08 i No Data i No Data i No Data i 1.16E-21 Sr-89 i 3.80E-05 i No Data ! 1.09E-06 i No Data i No Data i 1.75E-04 i 4.37E-05 Sr-90 ! 3.59E-03 ! No Data ! 7.21 E-05 ! No Data ! No Data ! 1.20E-03 ! 9.02E-05 Sr-91 ! 7.74E-09 ! No Data \ 3.13E-10 ! No Data ! No Data ! 4.56E-06 ! 2.39E-05 Sr-92 ! 8.43E-10 ! No Data ! 3.64E-11 ! No Data ! No Data ! 2.06E-06 ! 5.38E-06 Y-90 ! 2.61 E-07 ! No Data ! 7.01 E-09 ! No Data ! No Data ! 2.12E-05 ! 6.32E-05 Y-91m ! 3.26E-11 i No Data \ 1.27E-12 \ No Data \ No Data \ 2.40E-07 \ 1.66E-10

---~::~** * * * * * * -----*-* i . *;:;~~:~~-----***-i---~~--g:!:************l***~:~~~:~~***-*---i--*~~--g:!:********"'i"*~~-g:!:*----*--*-**l--~:;~~:~:-********l**i:-~;~~~~ . . . .

Y-93 j 1.18E-08 j No Data j 3.26E-10 j No Data j No Data j 6.06E-06 j 5.27E-05 1 <) Data presented in this Table are from Reference 9. A-11 185

PNPS-ODCM Rev. 11 TABLE A-11 (continued) INHALATION DOSE FACTORS FOR ADULT( 1> mrem/pCi Inhaled

i I Total ' i : ,

Nuclide : Bone I Liver j Body : Thyroid j Kidney : LunQ j GI-LU Zr-93 i 5.22E-05 i 2.92E-06 i 1.37E-06 i No Data i 1.11 E-05 i 2.13E-05 i 1.51 E-06

. ~~:~~-----**-----*-*--*---*l---~*:;~~:~~ --**-----!---~:!~~:~~----*--**!-* ~:~~~:~~-----***l*--~~-g:!:---*-------!---~: ;~~:~~-****-*-*l*-~:~1~:~:---------!---~:~~~:~;-*---**-

Nb-93m i 3.1 OE-05 -j {o"1*E-05--*-*--°T2.49E-06**--**--(No--Data ___________ (1*."16E-05-****-**(3."1*1-E-05-*----*r2.38E-06---*-**- Nb-95 i 1.76E-06 j 9.77E-07 i 5.26E-07 i No Data i 9.67E-07 ! 6.31 E-05 j 1 _30E-05 Nb-97 ! 2.78E-11 ! 7.03E-12 j 2.56E-12 ! No Data ! 8.18E-12 ! 3.00E-07 j 3_02E-08 ___ Mo-93_**--*---***-* __j _ _ No_ Data ________ __j ___ 1_._17E-06 _____ _...i ___ 3._1_ 7E-08 ________ :___No __Data ___________ :___3.55E-07 _____ _...: ___5._11. E-05 _______ _.: ___ 3. 79E-06 _______ _ Mo-99 i No Data i 1.51 E-08 i 2.87E-09 i No Data i 3.64E-08 i 1.14E-05 i 3.10E-05

*-*~ ~:~~m--*----------*-i---~: ~;~:6~ *******--!*- !:~:~:6~*-*-**-**J-- ~:~;~:6~ -*---**-!---~~ -.g:!:**-***-****!-**;: ~;~:6~ -** *-*-*!---~ :-~~~:~~-----**--[---~:;~~:~~ - -* *

5

. ;~--~~}---*---*-**-*--l---~:~~~:6~ -* * -* *! ---~-~~E;t: ***------l**-;:;~~:6: -*-----*!---~~ ..g:!:**---*---**i--*; :;~~:6; -* * -*-*!*- ::*;~~:~~***---*--!---~ -:;~~:;~ *----*--

Ru-105 i9.88E-11 !NoData !3.89E-11 !NoData !1.27E-10 !1.37E-06 !6.02E-06 Ru-106 ! 8.64E-06 ! No Data ! 1.09E-06 j No Data j 1.67E-05 ! 1.17E-03 ! 1.14E-04 Rh-105 ! 9.24E-10 ! 6.73E-10 j 4.43E-10 ! No Data ! 2.86E-09 j 2.41E-06 j 1.09E-05

...Pd-107 ________________ :___No. Data***-****_...: ___ 8.27E-08 ________ _i ___ 5._87E-09 ____ _...i ___No __Data ___________ :___6. 57E-07 ... _._...: ___9 .47E-06 .........:...7. 06E-07 _______ _

Pd-109 i No Data i 4.63E-10 i 1.16E-10 i No Data i 2.35E-09 i 1.85E-06 i 1.52E-05 __ Ag-11_ Om *---***--*: ...1: 35E-06 _____ _...i ___ 1_.25E-06 _____ _...i J .43E-07 ____ _...i ___ No __Data_____ ......i . 2.46E-06 _____ _...i ___5. 79E-04 _____ _...i ___ 3. 78E-05 -******* Ag-111 i 4.25E-08 i 1.78E-08 i 8.87E-09 i No Data i 5.74E-08 i 2.33E-05 i 2.79E-05

...Cd-1_1_3m ______ _j _ _No. Data............i .. _1_._54E-04 _____ _...i __ 4.97E-06 ____ _j _ _No __Data.... _......J ... 1: 71_ E-04 _____ _...i __ 2.08E-04 ______ __j ___ 1_.59E-05_.......

Cd-115m i No Data i 2.46E-05 i 7.95E-07 i No Data i 1.98E-05 i 1.76E-04 i 4.80E-05 Sn-123 .... "( 3."02E-05*******-t6.67E-07*-*****-*(g_82E-07**-****-(5.67E-07*-*****-(No ..Data*--*******r 2.88E-04*-******t3.92E-05-******* Sn-125 i 1.16E-06 ! 3.12E-08 ! 7.03E-08 ! 2.59E-08 i No Data j 7.37E-05 i 6.81E-05 Sn-126 ! 1.58E-04 j 4.18E-06 ! 6.00E-06 i 1.23E-06 i No Data j 1.17E-03 i 1.59E-05 Sb-124 j 3.90E-06 ! 7.36E-08 ! 1.55E-06 i 9.44E-09 i No Data j 3.10E-04 i 5.08E-05 Sb-125 ! 6.67E-06 ! 7.44E-08 j 1.58E-06 i 6.75E-09 i No Data j 2.18E-04 i 1.26E-05 Sb-126 j 4.50E-07 i 9.13E-09 ! 1.62E-07 i 2.75E-09 i No Data ! 9.57E-05 i 6.01 E-05 Sb-127 ! 3.30E-08 ! 7.22E-10 ! 1.27E-08 i 3.97E-10 i No Data ! 2.05E-05 i 3.77E-05 Te-125m j 4.27E-07 ! 1.98E-07 j 5.84E-08 i 1.31E-07 i 1.55E-06 i 3.92E-05 i 8.83E-06 Te-127m ! 1.58E-06 i 7.21E-07 ! 1.96E-07 i 4.11E-07 ! 5.72E-06 i 1.20E-04 ! 1.87E-05 Te-127 ! 1.75E-10 i 8.03E-11 ! 3.87E-11 i 1.32E-10 i 6.37E-10 i 8.14E-07 ! 7.17E-06 Te-129m j 1.22E-06 ! 5.84E-07 j 1.98E-07 i 4.30E-07 j 4.57E-06 j 1.45E-04 j 4.79E-05 Te-129 ! 6.22E-12 i 2.99E-12 j 1.55E-12 i 4.87E-12 j 2.34E-11 j 2.42E-07 j 1.96E-08 Te-131m i 8.74E-09 j 5.45E-09 i 3.63E-09 j 6.88E-09 j 3.86E-08 j 1.82E-05 j 6.95E-05 Te-131 i 1.39E-12 ! 7.44E-13 i 4.49E-13 j 1.17E-12 j 5.46E-12 j 1.74E-07 i 2.30E-09 Te-132 i 3.25E-08 j 2.69E-08 i 2.02E-08 j 2.37E-08 j 1.82E-07 j 3.60E-05 i 6.37E-05 Te-133m i 7.24E-12 j 5.40E-12 ! 4.17E-12 ! 6.27E-12 j 3.74E-11 ! 5.51E-07 ! 7.65E-09 Te-134 i 3.84E-12 ! 3.22E-12 i 1.57E-12 j 3.44E-12 ! 2.18E-11 j 4.34E-07 i 2.97E-11

*-*:: ~-~~ --** * -* * * * * ---*!* ;:;~~:~~-*-* * * !* *~:~~~:~~*-*******!**-~:~6~:~~**-*****!*-*~ :!~~:~!*-*-****!** ~: ~~~:~~ -****----J---~~ ..g:::---*-*******!-* ~:~~~:~;---*****

1-131 ! 3.15E-06 i 4.47E-06 ! 2.56E-06 ! 1.49E-03 ! 7.66E-06 i No Data i 7.85E-07 1-132 j 1.45E-07 ! 4.07E-07 ! 1.45E-07 ! 1.43E-05 ! 6.48E-07 i No Data i 5.08E-08 1-133 ! 1.08E-06 j 1.85E-06 j 5.65E-07 ! 2.69E-04 ! 3.23E-06 ! No Data i 1.11 E-06 1-134 ! 8.05E-08 ! 2.16E-07 ! 7.69E-08 j 3.73E-06 ! 3.44E-07 j No Data j 1.26E-10 1-135 : 3.35E-07 : 8.73E-07 : 3.21E-07 : 5.60E-05 : 1.39E-06 i No Data : 6.56E-07 (ll Data presented in this Table are from Reference 9. A-12 186

PNPS-ODCM Rev. 11 TABLE A-11 (continued) INHALATION DOSE FACTORS FOR ADUL T< 1l mrem/pCi Inhaled

: ! Total ' ' : :

Nuclide ! Bone i Liver j Body ! Thyroid ! Kidney i Lung i GI-LLI Cs-134m I 1.59E-08 I 3.20E-08 I 1.72E-08 I No Data I 1.83E-08 : 2.93E-09 I 7.92E-09 Cs-134 ! 4.66E-05 j 1.06E-04 j 9.1 OE-05 j No Data j 3.59E-05 j 1.22E-05 ! 1.30E-06 Cs-135 j 1.46E-05 j 1.29E-05 ! 5.99E-06 ! No Data ! 5.11 E-06 ! 1.57E-06 j 2.11 E-07 Cs-136 j 4.88E-06 j 1.83E-05 j 1.38E-05 j No Data j 1.0?E-05 j 1.SOE-06 j 1.46E-06 Cs-137 j 5.98E-05 ! 7.76E-05 j 5.35E-05 j No Data j 2.78E-05 j 9.40E-06 ! 1.0SE-06

 . g:: ~ ~~** * * * * * * *;* ~:*;:~:~~. . J. .;:~~~:~~********:i***~:~~~:~~* * * *!:* *~~.g:!:***********i** ~: ~~~:~~ * * * * *:* ~: ~:~:~~** * * * ;* *;:*!~~:}~ . . . ..

Ba-139 j 1.17E-10 j 8.32E-14 j 3.42E-12 No Data i 7.78E-14 i 4.?0E-07 j 1.12E-07 Ba-140 j 4. 88E-06 j 6.13E-09 j 3.21 E-07 j No Data j 2. 09E-09 ! 1.59E-04 j 2. 73E-05 Ba-141 i 1.25E-11 j 9.41E-15 j 4.20E-13 j No Data i 8.75E-15 j 2.42E-07 j 1.45E-17 Ba-142 j 3.29E-12 j 3.38E-15 j 2.0?E-13 j No Data j 2.86E-15 j 1.49E-07 ! 1.96E-26 La-140 i 4.30E-08 j 2.17E-08 i 5.73E-09 j No Data j No Data j 1.?0E-05 j 5.73E-05 La-141 i5.34E-10 !1.66E-10 i2.71E-11 iNoData iNoData !1.35E-06 !7.31E-06 La-142 j 8.54E-11 j 3.88E-11 j 9.65E-12 j No Data j No Data j 7.91E-07 j 2.64E-07 Ce-141 j 2.49E-06 j 1.69E-06 j 1.91E-07 j No Data j 7.83E-07 j 4.52E-05 j 1.SOE-05 Ce-143 j 2.33E-08 j 1.72E-08 j 1.91E-09 j No Data j 7.60E-09 j 9.97E-06 j 2.83E-05 Ce-144 j 4.29E-04 j 1.79E-04 j 2.30E-05 j No Data j 1.06E-04 j 9.72E-04 j 1.02E-04 Pr-143 j 1.17E-06 j 4.69E-07 j 5.80E-08 j No Data j 2.?0E-07 j 3.51E-05 j 2.SOE-05 Pr-144 j 3.76E-12 j 1.56E-12 j 1.91E-13 j No Data j 8.81E-13 j 1.27E-07 j 2.69E-18 Nd-147 j 6.59E-07 j 7.62E-07 j 4.56E-08 j No Data j 4.45E-07 j 2.76E-05 j 2.16E-05 Pm-147 j 8.37E-05 j 7.87E-06 j 3.19E-06 j No Data j 1.49E-05 j 6.60E-05 ! 5.54E-06 Pm-148m j 9.82E-06 j 2.54E-06 j 1.94E-06 j No Data j 3.85E-06 j 2.14E-04 j 4.18E-05 Pm-148 i 3.84E-07 ! 6.37E-08 ! 3.20E-08 j No Data j 1.20E-07 i 3.91 E-05 j 5.80E-05 Pm-149 j 3.44E-08 j 4.87E-09 j 1.99E-09 j No Data j 9.19E-09 ! 7.21E-06 \ 2.SOE-05 Pm-151 j 8.SOE-09 j 1.42E-09 j 7.21E-10 j No Data j 2.55E-09 ! 3.94E-06 ! 2.00E-05 Sm-151 j 8.59E-05 i 1.48E-05 j 3.55E-06 j No Data j 1.66E-05 j 4.45E-05 j 3.25E-06 Sm-153 j 1.?0E-08 j 1.42E-08 j 1.04E-09 ! No Data ! 4.59E-09 j 4.14E-06 ! 1.58E-05 Eu-152 ! 2.38E-04 ! 5.41E-05 ! 4.76E-05 j No Data j 3.35E-04 j 3.43E-04 i 1.59E-05 Eu-154 j 7.40E-04 j 9.10E-05 j 6.48E-05 j No Data j 4.36E-04 j 5.84E-04 j 3.40E-05 Eu-155 ! 1.01E-04 ! 1.43E-05 ! 9.21E-06 j No Data ! 6.59E-05 j 9.46E-05 ! 5.95E-06 Eu-156 j 1.93E-06 j 1.48E-06 j 2.40E-07 j No Data j 9.95E-07 j 8.56E-05 j 4.SOE-05 Tb-160 j 2.21E-05 j No Data j 2.75E-06 j No Data j 9.10E-06 j 1.92E-04 j 2.68E-05 Ho-166m ! 3.37E-04 j 1.0SE-04 j 8.00E-05 j No Data j 1.57E-04 j 3.94E-04 i 1.59E-05 W-181 i 6.23E-09 ! 2.03E-09 ! 2.17E-10 j No Data j No Data j 1.71E-06 j 2.53E-07 W-185 j 1.95E-07 j 6.47E-08 ! 6.81 E-09 j No Data ! No Data ! 5.57E-05 j 1.0?E-05 W-187 i 1.06E-09 i 8.85E-10 i 3.1OE-10 ! No Data j No Data ! 3.63E-06 j 1.94E-05 Pb-210 j 2.64E-02 j 6.73E-03 j 8.37E-04 ! No Data j 2.12E-02 j 2.62E-02 j 1.51E-06 Bi-210 j 2.31 E-07 ! 1.59E-06 j 1.32E-07 j No Data j 1.92E-05 ! 1.11 E-03 ! 2.95E-05 Po-210 ! 3.97E-04 ! 8.60E-04 ! 9.58E-05 ! No Data j 2.95E-03 i 3.14E-02 i 4.19E-05 Ra-223 j 1.80E-04 j 2.77E-07 j 3.60E-05 j No Data j 7.85E-06 \ 2.55E-02 j 2.84E-04 Ra-224 j 1.98E-05 j 4.78E-08 j 3.96E-06 j No Data j 1.35E-06 j 8.77E-03 j 3.01 E-04 Ra-225 i 3.00E-04 j 3.56E-07 j 5.99E-05 j No Data j 1.01 E-05 j 2.92E-02 j 2.71 E-04 Ra-226 i 1.25E-01 j 2.39E-06 j 9.14E-02 j No Data j 6.77E-05 j 1.17E-01 j 2.94E-04 Ra-228 j 4.41E-02 j 1.23E-06 j 4.78E-02 ! No Data ! 3.48E-05 j 1.61E-01 j 5.00E-05 1 ' l Data presented in this Table are from Reference 9. A-13 187

PNPS-ODCM Rev. 11 TABLE A-11 (continued) INHALATION DOSE FACTORS FOR ADULT< 1l mrem/pCi Inhaled

!

i Total : ' : '

Nuclide 1 Bone ! Liver ! Body j Thyroid ! Kidney j Lung ! GI-LLI Ac-225 : 4.23E-04 : 5.82E-04 i 2.84E-05 : No Data i 6.63E-05 1 2.21 E-02 : 2.52E-04 Ac-227 ! 2.30E+OO ! 3.05E-01 ! 1.36E-01 ! No Data ! 9.82E-02 ! 2.41E-01 ! 5.08E-05 Th-227 ! 2.17E-04 "°i" 3.92E-06 ! j *6.25E-06********i""°No ..Data******** 2.22E-05 *******t3.77E-oi*******t3.34E-04******** Th-228 i 2.00E-01 \ 3.39E-03 i **6.77E-o3********i""°No ..Data***********i***f a9E-Oi********i***f o"1*E+oo"******t3.49E-04******** Th-229. i 1 .5*1 E+o1 ******y 4.34E-01 . (2.51* E-of******tNo ..Data **********t2.13E+OO .......(3.62E+OO ....... :°..4 ..83E-05******** Th-230 j 2.29E+OO ""j" 1.31 E-01 i *6.36E-oi*******tNo ..Data***********i***6.40E-01*********t6.i1.E-of""""**t3.73E-o5******** Th-232 j 2.56E+OO "\ 1.12E-01 j *9.04E-04********i***No ..Data***********i***5.47E-01*********t5 ..96E-of*******i***3 ..1.7E-o5******** Th-234 j 1.63E-06 j 9.56E-08 j 4.70E-08 i No Data i 5.41E-07 i 1.89E-04 ! 7.03E-05 Pa-231. j 5 ..08E+OO .......j 1.91.E-01 j .{98E-01*********tNo.Data******** (1*.07E+OO *****r5.75E-oi********: 4.44E-05 ..... Pa-233 i 1.21 E-06 i 2.42E-07 i 2.09E-07 j No Data j 9.15E-07 j 3.52E-05 i 1.02E-05 U-232 j 5.14E-02 j No Data j 3.66E-03 j No Data j 5.56E-03 i 2.22E-01 j 4.21 E-05 U-233 j 1.09E-02 ! No Data ! 6.60E-04 j No Data \ 2.54E-03 j 5.32E-02 j 3.89E-05 U-234 j 1.04E-02 j No Data j 6.46E-04 i No Data j 2.49E-03 j 5.22E-02 i 3.81E-05 U-235 i 1.00E-02 i No Data i 6.07E-04 j No Data j 2.34E-03 i 4.90E-02 j 4.84E-05 U-236 i 1.00E-02 i No Data i 6.20E-04 j No Data i 2.39E-03 i 5.00E-02 j 3.57E-05 U-237 ! 3.67E-08 j No Data j 9. 77E-09 ! No Data j 1.51 E-07 ! 1.02E-05 i 1.20E-05 U-238 j 9.58E-03 ! No Data i 5.67E-04 i No Data j 2.18E-03 j 4.58E-02 i 3.41E-05

i. .

... Np-237 ............... 1.. 56E+OO .......i ... 1.-.00E+OO .......i ...6.87E-02 ........i ...No__Data...........i ...5 ..1OE-01 ...... ...J ...5.22E-02 .........i .. 4 ..92E-05 ........

Np-238 : 2.96E-07 1 7.20E-08 \ 4.61E-09 \ No Data \ 2.72E-08 : 1.02E-05 \ 2.13E-05

... Np-239 ............... i. 2.87E-08 ..... ....i ...2.54E-08 .........i ... 1.-55E-09 ........i ...No._Data........... i. .8. 75E-09 .........i .. 4. 70E-06 .........! ... 1_.49E-05 ........

Pu-238 1 1.43E+OO i 9.71 E-01 i 6.90E-02 i No Data i 2.96E-01 i 1.82E-01 i 4.52E-05 Pu-239. i. {66E+OO .......j 1.07E+OO **t7.75E-oi*******i""°No ..Data***********i"**3.30E-01**********i***f 72E-of*******j 4."13E-05******** Pu-240. j* {65E+OO ....... j 1.07E+OO ***:***7.73E-oi*******tNo ..Data******* *:***3.29E-01**********t1*.72E-of*******j 4.i1.E-05 ...... Pu-241 i 3.42E-02 i 8.69E-03 i 1.29E-03 j No Data j 5.93E-03 j 1.52E-04 i 8.65E-07 Pu-242 j 1.53E+OO j 1.03E+OO i 7.46E-02 j No Data i 3.17E-01 j 1.65E-01 ! 4.05E-05 Pu-244. ({79E+OO .......! f 18E+OO . (8.54E-oi*******tNo ..Data ......... (3.64E-01*********y--{89E-O{*******j 6.03E-05 .....

* ~~:~:~m** * * *i* *~*:~~~:~~* *----i* *~*:6~~:~~

Am-243 j 1.68E+OO j 1.10E+OO

                                                                 *******I**::

i

                                                                                ;~~:~~********i***~~-*~:!:***********i***;:~~~:~~**********i** ~:~~~:~~*-* * * *i* : ~~~:~;-* * *

6.57E-02 j No Data j 4.95E-01 j 5.75E-02 f 5.40E-05 Cm-242 ! 2.22E-02 ! 1.77E-02 j 9.84E-04 ! No Data j 4.48E-03 j 3.92E-02 j 4.91 E-05 Cm-243 j 1.10E+OO j 7.61E-01 j 4.61E-02 i No Data ! 2.15E-01 i 6.31E-02 j 4.84E-05 Cm-244 i 8.37E-01 i 5.88E-01 ! 3.51 E-02 i No Data ! 1.64E-01 i 6.06E-02 j 4.68E-05 J.

...cm-245..............i ...1_.74E+oo..... 1.-.1.4E+oo........i .. 7 .1.4E-02 ........i...N.o_ Data...........i...3_.33E-D1 ..........i ...5 ..85E-D2 .........i.. 4.36E-05 ........
...Cm-246 ...........J.. 1.-73E+OO .....J. 1.-.14E+OO .....           JJ .      13E-02 ...... J. No ._Data...........! ...3.33E-01 ........J. 5 ..96E-02 .........! . 4.29E-05 ........
...Cm-247 ......... ....! ... 1.. 68E+OO .......! ...1.-.12 E+OO ......J...7. 03E-02 ........! ...No ._Data........... i...3.28E-01 ..........! ...5 ..85E-02 .........! ...5.63E-05 ........

Cm-248 1 1.40E+01 1 9.26E+OO 1 5.79E-01 i No Data 1 2.70E+OO 1 4.82E-01 1 9.09E-04 Cf-252 j 5.43E-01 j No Data j 2.33E-02 j No Data j No Data j 1.99E-01 j 1.78E-04 1 <l Data presented in this Table are from Reference 9. A-14 188

PNPS-ODCM Rev. 11 TABLE A-12 INHALATION DOSE FACTORS FOR TEEN< 1l mrem/pCi Inhaled

                             '                        '                          I Total               !                         ,                     '                          '

Nuclide l Bone l Liver ! Body ! Thyroid l Kidney I Lung I GI-LU H-3 ! No Data ! 9.06E-08 ! 9.06E-08 i 9.06E-08 i 9.06E-08 ! 9.06E-08 i 9.06E-08 Be-10 j 2.78E-04 i 4.33E-05 i 7.09E-06 i No Data i No Data i 3.84E-04 i 1.77E-05 C-14 j 3.25E-06 j 6.09E-07 j 6.09E-07 j 6.09E-07 j 6.09E-07 i 6.09E-07 j 6.09E-07 N-13 i 8.65E-09 j 8.65E-09 i 8.65E-09 j 8.65E-09 i 8.65E-09 i 8.65E-09 j 8.65E-09 F-18 i 6.52E-07 i No Data i 7.10E-08 j No Data i No Data j No Data i 3.89E-08 Na-22 j 1. 76E-05 i 1. 76E-05 j 1. 76E-05 i 1. 76E-05 j 1. 76E-05 i 1. 76E-05 i 1. 76E-05 Na-24 j 1. 72E-06 i 1. 72E-06 j 1. 72E-06 j 1. 72E-06 j 1. 72E-06 j 1. 72E-06 i 1. 72E-06 P-32 j 2.36E-04 j 1.37E-05 j 8.95E-06 i No Data j No Data j No Data j 1.16E-05 Ca-41 j 4.05E-05 j No Data j 4.38E-06 j No Data j No Data j 1.01 E-01 j 3.03E-07 Sc-46 i 7.24E-05 i 1.41E-04 j 4.18E-05 i No Data j 1.35E-04 i No Data j 2.98E-05 Cr-51 j No Data j No Data j 1.69E-08 j 9.37E-09 j 3.84E-09 j 2.62E-06 j 3.75E-07 Mn-54 j No Data j 6.39E-06 j 1.05E-06 j No Data j 1.59E-06 j 2.48E-04 j 8.35E-06 Mn-56 j No Data i 2.12E-10 i 3.15E-11 j No Data i 2.24E-10 j 1.90E-06 j 7.18E-06 Fe-55 j 4.18E-06 j 2.98E-06 j 6.93E-07 j No Data j No Data j 1.55E-05 j 7.99E-07 Fe-59 j 1.99E-06 j 4.62E-06 j 1.79E-06 j No Data j No Data j 1.91 E-04 j 2.23E-05 Co-57 i No Data j 1.18E-07 j 1.15E-07 j No Data j No Data j 7.33E-05 j 3.93E-06 Co-58 j No Data j 2.59E-07 j 3.47E-07 j No Data j No Data j 1.68E-04 j 1.19E-05 Co-60 j No Data j 1.89E-06 j 2.48E-06 i No Data j No Data i 1.09E-03 i 3.24E-05 Ni-59 i 5.44E-06 i 2.02E-06 j 9.24E-07 j No Data j No Data j 1.41 E-05 j 6.48E-07 Ni-63 j 7.25E-05 j 5.43E-06 j 2.47E-06 j No Data j No Data j 3.84E-05 i 1.77E-06 Ni-65 i 2.73E-10 i 3.66E-11 i 1.59E-11 j No Data i No Data j 1.17E-06 i 4.59E-06 Cu-64 i No Data j 2.54E-10 j 1.06E-10 j No Data j 8.01E-10 j 1.39E-06 f 7.68E-06 Zn-65 j 4.82E-06 j 1.67E-05 i 7.80E-06 i No Data i 1.08E-05 i 1.55E-04 i 5.83E-06 Zn-69m j 1.44E-09 j 3.39E-09 j 3.11E-10 j No Data j 2.06E-09 j 3.92E-06 j 2.14E-05 Zn-69 j 6.04E-12 j 1.15E-11 j 8.07E-13 j No Data j 7.53E-12 j 1.98E-07 f 3.56E-08 7 7 5

*--~~t:********************l***~~* g:!:************l***~*:tE;t~ *********l** ~:~;~:~~********l***~~*-g:!:***********l***~-~ tE;t~ *********l** ~-;.1E;t~ *********l***~*~t~t~6-.........

Br-83 i No Data i No Data i 4.30E-08 i No Data i No Data i No Data i No Data Br-84 i No Data i No Data i 5.41 E-08 i No Data i No Data i No Data i No Data Br-85 i No Data i No Data i 2.29E-09 i No Data i No Data i No Data i No Data

...Rb-86 ...................i ...No. Data ........ ....\ .. 2.38E-05 .........i ...1_.05E-05 ........\ ...No. Data...........i ...No.. Data ............i ...N.o. Data............\ .. 2_.21.E-06 ........

Rb-87 i No Data i 1.40E-05 i 4.58E-06 i No Data i No Data i No Data i 3.05E-07

~~::~: : : : : : : : : :l: :~~: g:!:::::::::::::1::*~:~~~:~::::::::::l:::;::~~:~:::::::::l:::~~::g:!:.::::::::::i:::~~:*g:!:::::::::::::l:::~~:*g:!:.:::::::::::l::*!:~;~:~:~: : : :

Sr-89 i 5.43E-05 1 No Data i 1.56E-06 i No Data i No Data i 3.02E-04 i 4.64E-05 Sr-90 j 4.14E-03 j No Data j 8.33E-05 j No Data j No Data j 2.06E-03 j 9.56E-05

***~~:~~ *********************i***~ *:*~ ~~:~~ *********!***~~ . g:!:************i** :: ~~~: ~*~ ********!***~~ . g:!:***********l***~~. g:!:************l***~:!;~:~~*********!***~ :~:~:~~ ........

Y-90 j 3.73E-07 j No Data i 1.00E-08 i No Data j No Data j 3.66E-05 j 6.99E-05

* ~:~~ m******************i** ::~~~:~~*********i***~~*-g:!:************l***~:~~~:~~********i***~~..g:!:***********l***~~-g:!:************i** ~:~~~:~;** * * * !* *;: ~~~:~;** * *

Y-92 j 1.84E-09 i No Data i 5.36E-11 j No Data i No Data i 3.35E-06 i 2.06E-05 Y-93 j 1.69E-08 j No Data j 4.65E-10 j No Data j No Data j 1.04E-05 j 7.24E-05 1

<l Data presented in this Table are from Reference 9. A-15 189

PNPS-ODCM Rev. 11 TABLE A-12 (continued) INHALATION DOSE FACTORS FOR TEEN< 1l mrem/pCi Inhaled

                                !                     !                       ! Total                :                  '                        '

Nuclide ! Bone I Liver ! Body ! Thyroid ! Kidney ! Lung i GI-LU Zr-93 ! 6.83E-05 ! 3.38E-06 : 1.84E-06 : No Data : 1.16E-05 : 3.67E-05 ! 1.60E-06 Zr-95 i 1.82E-05 i 5.73E-06 i 3.94E-06 i No Data i 8.42E-06 i 3.36E-04 i 1.86E-05 Zr-97 i 1.72E-08 i 3.40E-09 i 1.57E-09 i No Data i 5.15E-09 i 1.62E-05 i 7.88E-05 Nb-93m i 4.14E-05 i 1.36E-05 i 3.41 E-06 i No Data i 1.59E-05 i 5.36E-05 i 2.52E-06 Nb-95 i 2.32E-06 i 1.29E-06 \ 7.08E-07 i No Data i 1.25E-06 i 9.39E-05 i 1.21 E-05 Nb-97 i 3.92E-11 i 9.72E-12 i 3.55E-12 i No Data i 1.14E-11 i 4.91E-07 i 2.71E-07 Mo-93 i No Data i 1.66E-06 i 4.52E-08 i No Data i 5.06E-07 i 8.81 E-05 i 3.99E-06 Mo-99 i No Data i 2.11 E-08 i 4.03E-09 i No Data i 5.14E-08 i 1.92E-05 i 3.36E-05 Tc-99m i 1.73E-13 i 4.83E-13 i 6.24E-12 i No Data i 7.20E-12 i 1.44E-07 i 7.66E-07 Tc-99 i 4.48E-08 \ 6.58E-08 i 1.79E-08 i No Data i 8.35E-07 i 1.74E-04 i 7.99E-06

. ;~--~~1 * * * * . *****l***;::~~:6~*********l***~~1E;t~ * * * * *l* *~*: ~;~:6~*-******l***~~. g:!:********. *l***~:;~~:6~*********l***::~:~:~~*********!***~*:~~~:6~********

4 Ru-105 i 1.40E-10 i No Data \ 5.42E-11 i No Data i 1.76E-10 j 2.27E-06 i 1.13E-05 Ru-106 i 1.23E-05 j No Data i 1.55E-06 j No Data i 2.38E-05 j 2.01 E-03 j 1.20E-04

...Rh-1.05................ ({32E-09*********(g.48E-1*o*******r*6.24E-1*o********j*..No Data********* j 4.04E-09                                  \ 4.09E-06            i 1.23E-05 Pd-107                      i   No Data            i 1.17E-07 i 8.39E-09 i No Data                                   i 9.39E-07 i 1.63E-05                         i 7.49E-07 Pd-109                      i   No Data            i 6.56E-10 i 1.66E-10 i No Data                                   i 3.36E-09 i 3.19E-06                         i 1.96E-05
.. Ag-1 _1_0m ..........i...1_. 73E-06 ......       J. 1.-64E-06.......J. 9.99E-07 ........! ...No _pata...........L.3._13E-06 .........i ...8.44E-04.........i...3.41_ E-05 ........

Ag-111 ! 6.07E-08 ! 2.52E-08 ! 1.26E-08 ! No Data ! 8.17E-08 ! 4.00E-05 ! 3.00E-05 Cd-113m i No Data i 2.17E-04 i 7.10E-06 i No Data i 2.43E-04 i 3.59E-04 i 1.68E-05 Cd-115m i No Data i 3.48E-05 i 1.14E-06 i No Data i 2.82E-05 i 3.03E-04 i 5.1 OE-05 Sn-123 i 4.31E-05 i 9.44E-07 i 1.40E-06 i 7.55E-07 i No Data i 4.96E-04 i 4.16E-05 Sn-125 i 1.66E-06 i 4.42E-08 i 9.99E-08 i 3.45E-08 i No Data i 1.26E-04 i 7.29E-05 Sn-126 i 2.18E-04 i 5.39E-06 i 8.24E-06 i 1.42E-06 i No Data i 1. 72E-03 i 1.68E-05 Sb-124 i 5.38E-06 i 9.92E-08 i 2.1 OE-06 i 1.22E-08 i No Data i 4.81 E-04 i 4.98E-05

~~:~ ~~:: : : : : : :: :4.64E-08

Sb-127 l: :~:~~~:~~::::::::L~i 9.92E-10

~;~:~~:: : : : l:: ;:~;~:~~::::::::l :::~:-~~~:~~: : : : l: :~~::g:::::::::::::::l: 3.31E-05 1.75E-08 : 5.21E-10 ! No Data

}::;~:~::::::::::i. .;.:~~t~t::::::

                                                                                                                                                                       ! 3.94E-05 Te-125m                      i 6.10E-07 i 2.80E-07 i 8.34E-08 i 1.75E-07 i No Data                                                           i 6.70E-05 i 9.38E-06

i ::~-;;m * * * *
l* *;: ~~~:~~ . . . . .i. ~-:*~~~:~~. . . . . 1...~: ;;~:~; ........ i. ~:;~~:~b****.
l*. ::-~ b~:~~ . . . . .i. ~ :~b~:~:*********l***~*: ~~~:~; . . . ..

Te-129m i 1.74E-06 i 8.23E-07 i 2.81E-07 i 5.72E-07 i 6.49E-06 i 2.47E-04 i 5.06E-05

***Te-1.29 ................ (8.87E-1.i.......f4.22E-1*2*********(2.20E-1i ....... (6.48E-1*i****                         i 3.32E-11 i 4.12E-07                          i 2.02E-07 Te-131m                      i  1.23E-08           i    7.51E-09           ! 5.03E-09 i 9.06E-09 i 5.49E-08 j 2.97E-05                                              j 7.76E-05 Te-131                       j 1.97E-12            i    1.04E-12           i 6.30E-13 j 1.55E-12 i 7.72E-12 i 2.92E-07                                              j 1.89E-09 Te-132                       i  4.50E-08           i    3.63E-08            j 2.74E-08 i 3.07E-08 j 2.44E-07 i 5.61E-05                                             i  5.79E-05 Te-133m                      i  1.01E-11           i    7.33E-12            j 5.71E-12 j 8.18E-12 j 5.07E-11 i 8.71E-07                                             i  1.23E-07 Te-134                       i  5.31E-12           i    4.35E-12           i 3.64E-12 i 4.46E-12 i 2.91E-11 i 6.75E-07                                              i  1.37E-09
 ... 1-1*29***.................. (3.53E-06********(2.94E-06                  . i"4.90E-06 ....... i".3.66E-03***** i 5.26E-06 j No Data                                 i  2.29E-07
 . .::~-~~** * * * * * * * *. * *!* :::~~:~~*********:**~:~!~:~~*********l***~:;~~:~~***. ***i***~ *:~~~:~~** * * *!* ~:~:~:~~** * * * !* *~~. g:!:************l***~: ~ ~~:~~********

1-132 i 1.99E-07 i 5.47E-07 i 1.97E-07 j 1.89E-05 i 8.65E-07 i No Data i 1.59E-07 1-133 i 1.52E-06 i 2.56E-06 i 7.78E-07 i 3.65E-04 i 4.49E-06 i No Data i 1.29E-06 1-134 i 1.11 E-07 i 2.90E-07 i 1.05E-07 i 4.94E-06 i 4.58E-07 i No Data i 2.55E-09 1-135 i 4.62E-07 i 1.18E-06 i 4.36E-07 i 7.76E-05 i 1.86E-06 i No Data i 8.69E-07 1 < l Data presented in this Table are from Reference 9. A-16 190

PNPS-ODCM Rev. 11 TABLE A-12 (continued) INHALATION DOSE FACTORS FOR TEEN<1l mrem/pCi Inhaled

! I Total , ' , :

Nuclide ! Bone I Liver ! Body ! Thyroid i Kidney ! Lung ! GI-LU ...Cs-134m ........J. 2.20E-08 .........!.. 4 ..35E-08 .........!.. 2.35E-08 ...... J. No._Data...........! . 2.54E-08 ..... ....! .. 4 ..56E-09 ....... J. 2.02E-08 ........ Cs-134 : 6.28E-05 1 1.41 E-04 : 6.86E-05 : No Data i 4.69E-05 : 1.83E-05 : 1.22E-06 Cs-135 i 2.08E-05 ! 1.82E-05 i 4.47E-06 i No Data ! 7.30E-06 i 2.70E-06 ! 2.23E-07 Cs-136 i 6.44E-06 ! 2.42E-05 ! 1.71 E-05 ! No Data i 1.38E-05 i 2.22E-06 ! 1.36E-06 Cs-137 ! 8.38E-05 ! 1.06E-04 i 3.89E-05 i No Data i 3.80E-05 i 1.51 E-05 i 1.06E-06

i. . i. .

...cs-138 ................i . .5..82E-08 .........i ... 1...o?E-07 .........i ...5. 58E-08 ........ No ..Oata........... 8. 28E-08 .........i ...9 ..84E-09 .........i ...3. 38E-1.1 .........

Cs-139 : 3.65E-08 1 5.12E-08 : 1.97E-08 : No Data : 4.34E-08 : 4.86E-09 : 1.66E-23 Ba-139 ! 1.67E-10 ! 1.18E-13 i 4.87E-12 i No Data i 1.11E-13 ! 8.08E-07 ! 8.06E-07 Ba-140 ! 6.84E-06 ! 8.38E-09 ! 4.40E-07 ! No Data j 2.85E-09 j 2.54E-04 j 2.86E-05 Ba-141 ! 1.78E-11 i 1.32E-14 j 5.93E-13 i No Data i 1.23E-14 i 4.11E-07 i 9.33E-14 Ba-142 ! 4.62E-12 i 4.63E-15 i 2.84E-13 i No Data ! 3.92E-15 i 2.39E-07 i 5.99E-20 La-140 ! 5.99E-08 i 2.95E-08 ! 7.82E-09 ! No Data i No Data i 2.68E-05 i 6.09E-05 La-141 !7.63E-10 i2.35E-10 !3.87E-11 !NoData iNoData i2.31E-06 !1.54E-05 La-142 ! 1.20E-10 i 5.31E-11 ! 1.32E-11 i No Data ! No Data ! 1.27E-06 i 1.50E-06 Ce-141 ! 3.55E-06 i 2.37E-06 i 2.71E-07 ! No Data i 1.11E-06 ! 7.67E-05 i 1.58E-05 Ce-143 ! 3.32E-08 i 2.42E-08 ! 2.70E-09 i No Data ! 1.08E-08 ! 1.63E-05 i 3.19E-05 Ce-144 ! 6.11 E-04 i 2.53E-04 ! 3.28E-05 i No Data i 1.51 E-04 i 1.67E-03 i 1.08E-04 Pr-143 i 1.67E-06 i 6.64E-07 ! 8.28E-08 j No Data i 3.86E-07 i 6.04E-05 i 2.67E-05 Pr-144 \ 5.37E-12 ! 2.20E-12 \ 2.72E-13 j No Data \ 1.26E-12 \ 2.19E-07 \ 2.94E-14 Nd-147 i 9.83E-07 i 1.07E-06 ! 6.41 E-08 i No Data i 6.28E-07 i 4.65E-05 i 2.28E-05 Pm-147 ! 1.15E-04 i 1.10E-05 ! 4.50E-06 ! No Data i 2.10E-05 ! 1.14E-04 i 5.87E-06 Pm-148m ! 1.32E-05 i 3.35E-06 i 2.62E-06 ! No Data i 5.07E-06 ! 3.20E-04 ! 4.10E-05 Pm-148 i 5.44E-07 i 8.88E-08 ! 4.48E-08 i No Data i 1.60E-07 ! 6.52E-05 i 6.14E-05 Pm-149 i 4.91E-08 i 6.89E-09 ! 2.84E-09 ! No Data ! 1.31E-08 i 1.24E-05 i 2.79E-05 Pm-151 j 1.20E-08 i 1.99E-09 ! 1.01E-09 ! No Data j 3.57E-09 ! 6.56E-06 i 2.27E-05 Sm-151 ! 1.07E-04 i 2.10E-05 ! 4.86E-06 \ No Data ! 2.27E-05 ! 7.68E-05 i 3.53E-06 Sm-153 ! 2.43E-08 i 2.01 E-08 j 1.47E-09 i No Data ! 6.56E-09 ! 7.11 E-06 i 1.77E-05 Eu-152 i 2.96E-04 i 7.19E-05 i 6.30E-05 ! No Data ! 3.34E-04 ! 5.01 E-04 j 1.35E-05 Eu-154 ! 9.43E-04 i 1.23E-04 ! 8.60E-05 i No Data j 5.44E-04 ! 9.12E-04 i 3.34E-05 Eu-155 l 2.00E-04 j 1.96E-05 l 1.21E-05 j No Data l 7.65E-05 l 1.51E-03 j 5.97E-05 Eu-156 ! 2.70E-06 i 2.03E-06 i 3.30E-07 ! No Data ! 1.36E-06 i 1.37E-04 i 4.56E-05 Tb-160 i 3.04E-05 i No Data ! 3.79E-06 i No Data ! 1.20E-05 i 2.97E-04 i 2.60E-05 Ho-166m j 4.40E-04 j 1.36E-04 i 9.87E-05 ! No Data j 2.00E-04 j 6.24E-04 i 1.68E-05 W-181 i 8.90E-09 i 2.88E-09 i 3.01E-10 i No Data i No Data i 2.95E-06 i 2.69E-07 W-185 i 2.78E-07 i 9.17E-08 ! 9.73E-09 i No Data i No Data i 9.60E-05 i 1.14E-05 W-187 ! 1.50E-09 ! 1.22E-09 j 4.29E-10 i No Data j No Data j 5.92E-06 i 2.21E-05 Pb-210 ! 3.09E-02 j 8.28E-03 ! 1.07E-03 ! No Data ! 2.95E-02 ! 4.52E-02 i 1.60E-06 Bi-210 j 3.30E-07 ! 2.26E-06 i 1.89E-07 ! No Data j 2.74E-05 ! 1.91 E-03 i 3.19E-05 Po-210 ! 5.68E-04 j 1.22E-03 ! 1.37E-04 ! No Data ! 4.21E-03 ! 5.41E-02 i 4.45E-05 Ra-223 i 2.57E-04 ! 3.93E-07 ! 5.14E-05 i No Data \ 1.12E-05 ! 4.39E-02 \ 3.04E-04 Ra-224 i 2.83E-05 ! 6.77E-08 ! 5.65E-06 ! No Data i 1.93E-06 ! 1.51 E-02 ! 3.29E-04 Ra-225 i 4.28E-04 i 5.04E-07 i 8.56E-05 ! No Data i 1.44E-05 i 5.04E-02 ! 2.89E-04

i. . i. .

 ...Ra-226 ............... 1.-33E-01..........i ...3 ..38E-06 .........i ...9.87E-02 ........ No._Data...........i ...9.67E-05 ....... ..i .. 2.02E-01 ..........i . .3..1.1.E-04 ........

Ra-228 ! 5.34E-02 / 1.74E-06 / 5.88E-02 j No Data ! 4.97E-05 / 2.78E-01 \ 5.30E-05 1 <) Data presented in this Table are from Reference 9. A-17 191

PNPS-ODCM Rev. 11 TABLE A-12 (continued) INHALATION DOSE FACTORS FOR TEEN<1J mrem/pCi Inhaled

                           '                       !                      j Total                '                        !                       '                        '

Nuclide ! Bone ! Liver j Body ! Thyroid ! Kidney ! Lung ! GI-LU

                       ..J . .                                                                                        ..J . .
.. Ac-225 ............ 6. 04E-04 ........J ...8.25E-04 .........! . 4. 06E-05 ........! ...No ._Data....... 9.4 7E-05 .........1 ...3. 81. E-02 .........1 ...2. 70E-04 ........
                                                                                                                      ..J . .
.. Ac-227 ............ ....! .. 2.49E+OO ......J ...3.69E-01 .........J ... 1_.48E-01 .........! ...No ._Data....... 1.- 07E-01 .........J .. 4 ..16E-01.........J ...5.38E-05 ........

Th-227 i 3.09E-04 I 5.56E-06 1 8.93E-06 1 No Data 1 3.18E-05 1 6.50E-02 l 3.57E-04 01 02

. .;~:;;:****************!** ~::~~~ * * * * !* ::1:~:~~*********!** ~:~~~:~~********l***~~**~:!:***********!** ;:~~~~

01 0 0 .......f ***~:~:~:~~********!***;: ~~~:~:******** Th-230 i 2.34E+OO i 1.34E-01 i 6.49E-02 i No Data i 6.55E-01 i 8.98E-01 i 3.95E-05 Th-232 i 2.61 E+OO i 1.14E-01 i 9.21 E-04 i No Data i 5.60E-01 i 8.60E-01 i 3.36E-05 Th-234 i 2.32E-06 i 1.35E-07 i 6.71E-08 i No Data i 7.73E-07 i 3.26E-04 i 7.49E-05 Pa-231 i 5.32E+OO i 2.00E-01 j 2.07E-01 j No Data j 1.12E+OO j 9.91 E-02 j 4.71 E-05 Pa-233 i 1.68E-06 i 3.24E-07 i 2.89E-07 i No Data i 1.22E-06 i 5.39E-05 i 1.00E-05 U-232 i 7.31 E-02 i No Data i 5.23E-03 i No Data i 7.94E-03 i 3.84E-01 i 4.46E-05 U-233 i 1.55E-02 i No Data i 9.42E-04 i No Data i 3.63E-03 i 9.18E-02 i 4.12E-05 U-234 i 1.48E-02 i No Data i 9.23E-04 i No Data i 3.55E-03 i 8.99E-02 i 4.04E-05 U-235 i 1.42E-02 i No Data i 8.67E-04 i No Data i 3.34E-03 i 8.44E-02 i 5.13E-05 U-236 i 1.42E-02 i No Data i 8.86E-04 i No Data i 3.41E-03 i 8.62E-02 i 3.79E-05 U-237 i 5.25E-08 i No Data i 1.40E-08 i No Data i 2.16E-07 i 1. 76E-05 i 1.29E-05 U-238 i 1.36E-02 i No Data i 8.10E-04 i No Data i 3.12E-03 i 7.89E-02 i 3.62E-05

i. . i. . i. .

... Np-237 ............... 1: 64E+OO .......i ... 1.-.06E+OO .......i...7 .2.1. E-02 ........ No ..Data........... 5. 35E-01 ..........i ...8 ..99E-02 ..... ....i ...5.22E-05 ........
 ...Np-238................ \.. 4.23E-07 .........l ... 1_.02E-07 .........\ .. 6_.59E-09 ........ \...No ..Data........... \...3.88E-08 ........ \... 1.- 75E-05 ........J ...2.38E-05 ........
... Np-239................ \.. 4.23E-08 .........! ...3.60E-08 ......... \...2.2.1.E-09 ........l . .No ..Data...........l . .1_.25E-08 ...... ..J ...8 ..1.1.E-06 ........J ... 1.-65E-05 ........

Pu-238 1 1.50E+OO 1 1.03E+OO 1 7.22E-02 I No Data 1 3.10E-01 I 3.12E-01 I 4.79E-05 Pu-239 i 1. 73E+OO i. f12E+OO i 8.05E-oi* ( No ..Data........ *(3.44E-01*********t2.93E-01********r 4.37E-os********

i. . i. .

...Pu-240 ................i . . 1.. 72E+OO ... ....i ...1.-.12E+oo........i ...8. 04E-02 ........ No ._Data........... 3.43E-O 1..........i .. 2 ..93E-O 1..........i .. 4.46E-05 ........

Pu-241 1 3.74E-02 1 9.56E-03 1 1.40E-03 1 No Data 1 6.47E-03 \ 2.60E-04 \ 9.17E-07 Pu-242 i 1.60E+OO i 1.08E+OO i 7. 75E-02 i No Data i 3.31 E-01 i 2.82E-01 i 4.29E-05 Pu-244 i 1.87E+OO i 1.24E+OO i 8.88E-02 i No Data i 3.79E-01 i 3.23E-01 i 6.39E-05 Am-241 i 1.77E+OO i 1.20E+OO i 7.10E-02 i No Data j 5.32E-01 i 1.05E-01 i 4.88E-05 Am-242m i 1.79E+OO i 1.13E+OO i 7.15E-02 i No Data i 5.30E-01 i 4.21E-02 i 6.14E-05 Am-243 i 1.77E+OO i 1.17E+OO i 6.95E-02 i No Data i 5.21 E-01 i 9.91 E-02 i 5.72E-05 Cm-242 j 3.17E-02 j 2.51E-02 j 1.41E-03 j No Data j 6.40E-03 i 6.76E-02 j 5.21E-05 Cm-243 i 1.19E+OO i 8.30E-01 i 5.00E-02 i No Data i 2.34E-01 i 1.09E-01 i 5.13E-05 Cm-244 i 9.19E-01 j 6.53E-01 i 3.88E-02 j No Data i 1.81E-01 i 1.05E-01 i 4.96E-05 Cm-245 i 1.83E+OO j 1.22E+OO i 7.53E-02 i No Data i 3.52E-01 i 1.01 E-01 i 4.63E-05 Cm-246 i 1.81 E+OO i 1.22E+OO i 7.52E-02 i No Data i 3.51 E-01 i 1.03E-01 j 4.54E-05 Cm-247 \ 1.77E+OO i 1.19E+OO \ 7.41E-02 i No Data i 3.46E-01 i 1.01E-01 j 5.97E-05 Cm-248 i 1.47E+01 i 9.83E+OO j 6.11 E-01 i No Data i 2.85E+OO i 8.32E-01 i 9.63E-04 Cf-252 j 7.16E-01 j No Data j 3.07E-02 j No Data j No Data j 3.43E-01 j 1.89E-04 1 <J Data presented in this Table are from Reference 9. A-18 192

PNPS-ODCM Rev. 11 TABLE A-13 1 INHALATION DOSE FACTORS FOR CHILD< l mrem/pCi Inhaled iT~al

Nuclide i Bone i Liver I Body i Thyroid i Kidney i Lung I GI-LU

... H-3 .........................J. No. Data..........J.1_. 73E-07 ...... .J. 1: 73E-07 .......J. 1: 73E-07 ......J. 1: 73E-07 ........J ...1.-73E-07 .........l...1.-73E-07........ Be-10 1 8.43E-04 1 9.83E-05 1 2.12E-05 1 No Data 1 No Data i 7.41E-04 i 1.72E-05

~:~

~: :::::::::::::::::::::::1:: ;:;~~:~~:::::::::l:::;: ~;~:~~:::::::::l:: ;:

F-18 i 1.88E-06 i No Data 1

                                                                                            ~;~:~~ :::::::::!:: ;:.~;~:~~: : :i: !: .;:~;~:~~:::::::::l:: ;: ~;~:~~ :::::::::l:: ;:~;~:~~::::::::

1.85E-07 : No Data No Data 1 No Data : 3.37E-07 -~;J! - -!; Ei];-!-iiii:~i-!rn;:~; :!ti~a!~ -!-ti ~a!~ :~tii;.~~=:!:rnt~i =

...ca-41 .................... i...7 ..06E-05 .........i ...No ..Oata........ ....i...7. 70E-06 ........J ... No ..Oata...........i ...No ..Oata............i .. 7 .2.1. E-02 ........J...2. 94E-07 ........

Sc-46 1 1.97E-04 i 2.70E-04 i 1.04E-04 1 No Data 1 2.39E-04 1 No Data i 2.45E-05

...cr-5.1.. ................ ....i ...No. Data............i ...No .,Oata............i . 4 ..1.7E-08 .........i . .2 .3.1. E-08 ........i ...6. 57E-09 .........i.. 4.59E-06 .........i ...2. 93E-07 ........

Mn-54 1 No Data i 1.16E-05 i 2.57E-06 i No Data i 2.71E-06 i 4.26E-04 i 6.19E-06 Mn-56 i No Data i 4.48E-10 i 8.43E-11 i No Data i 4.52E-10 i 3.55E-06 i 3.33E-05 Fe-55 i 1.28E-05 i 6.80E-06 i 2.10E-06 i No Data i No Data i 3.00E-05 i 7.75E-07 Fe-59 i 5.59E-06 i 9.04E-06 i 4.51 E-06 i No Data i No Data i 3.43E-04 i 1.91 E-05

. g~:;~ . . . . . . . . . . ~~ g:!:. . . . . .

j... .. j.. ~:~:~:~; ......... j.. ~:~~~:~; .........j...~~ ..g:!:. . . . . . j...~~. g:!:. . . . . . j.. ;:~;~:~:......... *~:~~~:~~ J.. ...... ..

... co-60 ...................i ...No._Data............i ...3 ..55E-06 .........i ...6 ..12E-06 .........i ... No ..Oata........... i. .No. Data............i ...1.. 91.E-03 ........J.. 2.60E-05 ........

Ni-59 1 1.66E-05 \ 4.67E-06 1 2.83E-06 1 No Data \ No Data 1 2.73E-05 \ 6.29E-07 Ni-63 i 2.22E-04 i 1.25E-05 i 7.56E-06 i No Data i No Data i 7.43E-05 [ 1.71E-06 Ni-65 i 8.08E-10 i 7.99E-11 i 4.44E-11 i No Data i No Data i 2.21E-06 i 2.27E-05 Cu-64 i No Data ! 5.39E-10 i 2.90E-10 i No Data i 1.63E-09 i 2.59E-06 i 9.92E-06 Zn-65 i 1.15E-05 i 3.06E-05 i 1.90E-05 i No Data i 1.93E-05 i 2.69E-04 i 4.41 E-06 Zn-69m i 4.26E-09 i 7.28E-09 i 8.59E-10 i No Data i 4.22E-09 i 7.36E-06 i 2.71E-05 Zn-69 i 1.81E-11 i 2.61E-11 i 2.41E-12 i No Data i 1.58E-11 i 3.84E-07 i 2.75E-06

***~~i;********************i***~~**g:!:************i***~*~~E;t~6* * * * *l* ~:~~~:~;. . . . . ~~**g:!:***********i***~*;.1E;t~6 ......... ~*~~E;t~4 .........f...~*~tE;t~6 ********

J ... J ...

***:~::1. . . . . . . . . . .1. .~~**g:!:*. *********l***~~**g:!:************l***~*:!~~:~;. . . . . ~~**g:!:***********i***~~*g:!:*********. *l***~~**g:!:*. . . . . . ~~**g:!:***********

J... J... Br-85 i No Data i No Data i 6.84E-09 i No Data i No Data i No Data i No Data

                                                                                                                                                                                   .J.
...Rb-86 ...................i ...No. Data............i ...5.36E-05 .........i ...3.09E-05 .........i ...No .,Oata...........i ...No. Data............i ...No._Data......... 2.,1, 6E-06 ........

Rb-87 1 No Data 1 3.16E-05 1 1.37E-05 1 No Data : No Data 1 No Data 1 2.96E-07 Rb-88 i No Data i 1.52E-07 i 9.90E-08 i No Data i No Data i No Data i 4.66E-09 Rb-89 i No Data i 9.33E-08 i 7.83E-08 i No Data i No Data i No Data i 5.11E-10 Sr-89 i 1.62E-04 i No Data i 4.66E-06 i No Data i No Data i 5.83E-04 i 4.52E-05 Sr-90 i 1.04E-02 i No Data i 2.07E-04 i No Data i No Data i 3.99E-03 i 9.28E-05 Sr-91 i 3.28E-08 i No Data i 1.24E-09 i No Data i No Data ! 1.44E-05 i 4. 70E-05 Sr-92 i 3.54E-09 i No Data i 1.42E-10 i No Data i No Data i 6.49E-06 [ 6.55E-05

i. . i. .

.. Y-9D........................ 1.-.1.1.E-06 .........i ... No ..Oata............i .. 2 ..99E-08 .........i ...No ..Oata........... No ..Oata............i...7-.07E-05 .........i...7.24E-05 ........

Y-91m 1 1.37E-10 1 No Data 1 4.98E-12 1 No Data 1 No Data \ 7.60E-07 \ 4.64E-07 Y-91 i 2.47E-04 ! No Data j 6.59E-06 ! No Data ! No Data j 7.10E-04 j 4.97E-05

i. . i. . i.

.. Y-92 ........................ s .50E-09 .........i ... No _pata ........... .i ...1_.57E-1.0 .........i . .No ..Oata........... No ..Oata............ 6.46E-06 .........i ...6.46E-05 ........

Y-93 i 5.04E-08 i No Data i 1.38E-09 i No Data i No Data i 2.01 E-05 i 1.05E-04 1 <l Data presented in this Table are from Reference 9. A-19 193

PNPS-ODCM Rev. 11 TABLE A-13 (continued) 1 INHALATION DOSE FACTORS FOR CHILD< > mrem/pCi Inhaled

                                          '                                         *                                          [ Total'                                  :                                        ,                                        :                                         :

Nuclide i Bone i *Liver i Body i Thyroid ! Kidney i Lung i GI-LLI Zr-93 1 2.07E-04 i 7.80E-06 1 5.55E-06 1 No Data : 3.00E-05 1 7.1 OE-05 : 1.47E-06 Zr-95 j 5.13E-05 j 1.13E-05 j 1.00E-05 ! No Data ! 1.61 E-05 ! 6.03E-04 [ 1.65E-05 Zr-97 ! 5.07E-08 j 7.34E-09 ! 4.32E-09 ! No Data j 1.05E-08 j 3.06E-05 ! 9.49E-05 Nb-93m ! 1.27E-04 j 3.17E-05 ! 1.04E-05 j No Data j 3.44E-05 j 1.04E-04 j 2.45E-06 Nb-95 \ 6.35E-06 \ 2.48E-06 \ 1.77E-06 j No Data j 2.33E-06 j 1.66E-04 j 1.00E-05 Nb-97 ! 1.16E-10 \ 2.08E-11 j 9.74E-12 \ No Data ! 2.31E-11 \ 9.23E-07 j 7.52E-06 Mo-93 j No Data ! 3.76E-06 j 1.35E-07 j No Data j 1.06E-06 j 1.70E-04 j 3.78E-06 Mo-99 j No Data ! 4.66E-08 j 1.15E-08 ! No Data j 1.06E-07 j 3.66E-05 [ 3.42E-05 Tc-99m j 4.81E-13 j 9.41E-13 j 1.56E-11 j No Data j 1.37E-11 ! 2.57E-07 j 1.30E-06 Tc-99 j 1.34E-07 j 1.49E-07 ! 5.35E-08 j No Data j 1.75E-06 ! 3.37E-04 \ 7.75E-06 Tc-101 ! 2.19E-14 j 2.30E-14 j 2.91E-13 \ No Data ! 3.92E-13 j 1.58E-07 j 4.41E-09 Ru-103 \ 7.55E-07 \ No Data j 2.90E-07 j No Data j 1.90E-06 j 1.79E-04 j 1.21E-05 Ru-105 ! 4.13E-10 ! No Data \ 1.50E-10 ! No Data \ 3.63E-10 j 4.30E-06 j 2.69E-05 Ru-106 j 3.68E-05 ! No Data ! 4.57E-06 \ No Data ! 4.97E-05 \ 3.87E-03 \ 1.16E-04 Rh-105 \ 3.91E-09 \ 2.10E-09 ! 1.79E-09 j No Data ! 8.39E-09 ! 7.82E-06 ! 1.33E-05 Pd-107 j No Data j 2.65E-07 j 2.51 E-08 j No Data j 1.97E-06 j 3.16E-05 j 7.26E-07 Pd-109 j No Data j 1.48E-09 j 4.95E-10 j No Data j 7.06E-09 j 6.16E-06 \ 2.59E-05

i. .i . .

.. Ag-1 _1_0m .......... 4.56E-06 .........i ...3. 08E-06 .........i . 2.4 7E-06 ........ No ..Oata........... 5. 7 4E-06 .........i . .1..48E-03 .........i ...2. 71_ E-05 ........                              i. .
.. Ag-1_1.1 ................. \...1__.8_1_E-07 .........\ ...5.68E-08 ........J ...3.75E-08 .........L..No ..Data........... L..1_.7.1.E-07 ........ L.7.73E-05 ........L2.98E-05 ........

Cd-113m 1 No Data : 4.93E-04 : 2.12E-05 1 No Data i 5.13E-04 1 6.94E-04 1 1.63E-05 Cd-115m

.........................................      No Data
                                          *j........................................ j 7.88E-05                                 ! 3.39E-06 j No Data j 5.93E-05 \ 5.86E-04 j 4.97E-05 Sn-123                                1 1.29E-04 : 2.14E-06 1 4.19E-06 : 2.27E-06 1 No Data                                                                                                                                                            1 9.59E-04 1 4.05E-05 Sn-125                                 j 4.95E-06                                j 9.94E-08 j 2.95E-07 j 1.03E-07 j No Data ! 2.43E-04                                                                                                                                                           !   7.17E-05 Sn-126                                 j 6.23E-04                                j 1.04E-05                                 j 2.36E-05                               \ 2.84E-06                               !    No Data                             j 3.02E-03                                f 1.63E-05 Sb-124                                 j 1.55E-05                                j 2.00E-07                                 !   5.41E-06                             j 3.41E-08 j No Data                                                              \ 8.76E-04 \ 4.43E-05 Sb-125                                 j 2.66E-05 j 2.05E-07 j 5.59E-06 j 2.46E-08 j No Data                                                                                                                                                           j 6.27E-04                                i    1.09E-05
... ~~: ~ ~~                                   ~ ~~~:~~
                         ................ 1... *:                          ......... j... ~:~~~:~~ .........j.. !:;~~:~;. . . . ./. ~ *: ~~~:~~ . . . . /* *~~ **~:!:***. * * * *:" ~:-~~~:~:""""'i "*~: :;~:~;. . .

Te-125m j 1.82E-06 j 6.29E-07 \ 2.47E-07 j 5.20E-07 ! No Data j 1.29E-04 f 9.13E-06

**i::~*~;m. . . . . . ~:;~~:~~            1...                             .........:.. ~:-;;~:~~ .........1...                     ~:J~~:~b. . . . .J** ~:~ci~:~~. . . . J** ~*:~~~:~~** * *

J* ~:~~~:~:* * *. **l ..*~*:;;~:~; ........

Te-129m ! 5.19E-06 \ 1.85E-06 j 8.22E-07 ! 1.71E-06 j 1.36E-05 j 4.76E-04 ! 4.91E-05

                                                                                                                              .L
 .. Te-1_29 .............. ..\.. 2.64E-1.1 ..........i...9A5E-12 ........ 6_.44E-12 .........i...1 _.93E-1.1 ........ 6_.94E-1.1 .........                                                                      .L                                        .i.J.       93E-07 ........J...6.89E-06 ........

J ..

 ,,,T e-.1.31.m .......... 1...3 .63E-08 ..... 1_.60E-08 .........! ...1_. 37E-08 .........1 .. 2 .64E-08 ........: ...1_. 08E-07 ..... 5. 56E-05 ..... 8. 32E-05 ........                                                                             J ..                                      J ..
.. Te-1.31 .................L. 5._87E-1.2 ........J...2.28E-1_2 ........L1_. 78E-1.2 .........L. 4.59E-1.2 ........ L..1_.59E-1_1 .........J...5.55E-07 ....... J..3.60E-07 ........

Te-132 : 1.30E-07 : 7.36E-08 1 7.12E-08 : 8.58E-08 i 4.79E-07 1 1.02E-04 i 3.72E-05 Te-133m j 2.93E-11 j 1.51E-11 \ 1.50E-11 j 2.32E-11 j 1.01E-10 j 1.60E-06 j 4.77E-06 Te-134 j 1.53E-11 j 8.81E-12 j 9.40E-12 ! 1.24E-11 ! 5.71E-11 ! 1.23E-06 ! 4.87E-07 1-129 j 1.05E-05 j 6.40E-06 ! 5.71E-06 j 4.28E-03 ! 1.08E-05 j No Data ! 2.15E-07 1-130 j 2.21 E-06 j 4.43E-06 \ 2.28E-06 j 4.99E-04 ! 6.61 E-06 j No Data j 1.38E-06 1-131 ! 1.30E-05 j 1.30E-05 ! 7.37E-06 j 4.39E-03 j 2.13E-05 \ No Data j 7.68E-07 1-132 j 5.72E-07 j 1.1 OE-06 j 5.07E-07 j 5.23E-05 j 1.69E-06 ! No Data j 8.65E-07 1-133 j 4.48E-06 ! 5.49E-06 j 2.08E-06 ! 1.04E-03 j 9.13E-06 ! No Data ! 1.48E-06 1-134 j 3.17E-07 j 5.84E-07 j 2.69E-07 j 1.37E-05 j 8.92E-07 j No Data j 2.58E-07 1-135 i 1.33E-06 ! 2.36E-06 ! 1.12E-06 i 2.14E-04 i 3.62E-06 ! No Data ! 1.20E-06 1 < > Data presented in this Table are from Reference 9. A-20 194

PNPS-ODCM Rev. 11 TABLE A-13 (continued) INHALATION DOSE FACTORS FOR CHILD( 1l mrem/pCi Inhaled

                                                   !                         )    Total              '                         '                          '

Nuclide j Bone i Liver i Body j Thyroid i Kidney j Lung i GI-LU Cs-134m i 6.33E-08 ! 8.92E-08 i 6.12E-08 ! No Data i 4.94E-08 ! 8.35E-09 i 7.92E-08 Cs-134 j 1.76E-04 j 2.74E-04 j 6.07E-05 j No Data j 8.93E-05 j 3.27E-05 j 1.04E-06 Cs-135 j 6.23E-05 j 4.13E-05 j 4.45E-06 j No Data j 1.53E-05 j 5.22E-06 j 2.17E-07 Cs-136 j 1.76E-05 j 4.62E-05 j 3.14E-05 j No Data j 2.58E-05 j 3.93E-06 j 1.13E-06 Cs-137 j 2.45E-04 j 2.23E-04 j 3.47E-05 j No Data j 7.63E-05 j 2.81 E-05 j 9.78E-07 Cs-138 j 1.71 E-07 j 2.27E-07 j 1.50E-07 j No Data j 1.68E-07 j 1.84E-08 i 7.29E-08 Cs-139 j 1.09E-07 j 1.15E-07 j 5.80E-08 j No Data j 9.08E-08 j 9.36E-09 j 7.23E-12 Ba-139 j 4.98E-10 j 2.66E-13 j 1.45E-11 j No Data j 2.33E-13 j 1.56E-06 j 1.56E-05 Ba-140 j 2.00E-05 j 1.75E-08 j 1.17E-06 j No Data j 5.71E-09 j 4.71E-04 j 2.75E-05 Ba-141 j 5.29E-11 j 2.95E-14 j 1.72E-12 j No Data j 2.56E-14 j 7.89E-07 j 7.44E-08 Ba-142 j 1.35E-11 j 9.73E-15 j 7.54E-13 j No Data i*7.87E-15 j 4.44E-07 j 7.41E-10 La-140 j 1.74E-07 j 6.08E-08 j 2.04E-08 j No Data j No Data j 4.94E-05 j 6.10E-05 La-141 j 2.28E-09 j 5.31E-10 j 1.15E-10 j No Data j No Data j 4.48E-06 i 4.37E-05 La-142 i3.50E-10 i1.11E-10 \3.49E-11 \NoData \NoData \2.35E-06 \2.05E-05 Ce-141 j 1.06E-05 j 5.28E-06 j 7.83E-07 j No Data j 2.31E-06 j 1.47E-04 j 1.53E-05 Ce-143 j 9.89E-08 j 5.37E-08 j 7.77E-09 j No Data j 2.26E-08 j 3.12E-05 j 3.44E-05 Ce-144 j 1.83E-03 j 5.72E-04 j 9.77E-05 j No Data j 3.17E-04 j 3.23E-03 j 1.05E-04 Pr-143 j 4.99E-06 j 1.50E-06 j 2.47E-07 j No Data j 8.11E-07 j 1.17E-04 j 2.63E-05 Pr-144 j 1.61E-11 j 4.99E-12 j 8.10E-13 j No Data j 2.64E-12 j 4.23E-07 j 5.32E-08 Nd-147 j 2.92E-06 j 2.36E-06 j 1.84E-07 j No Data j 1.30E-06 j 8.87E-05 i 2.22E-05 Pm-147 j 3.52E-04 j 2.52E-05 j 1.36E-05 j No Data j 4.45E-05 j 2.20E-04 i 5.70E-06 Pm-148m j 3.31E-05 j 6.55E-06 j 6.55E-06 j No Data j 9.74E-06 j 5.72E-04 j 3.58E-05 Pm-148 j 1.61 E-06 j 1.94E-07 j 1.25E-07 j No Data j 3.30E-07 j 1.24E-04 j 6.01 E-05 Pm-149 j 1.47E-07 j 1.56E-08 j 8.45E-09 j No Data j 2.75E-08 j 2.40E-05 j 2.92E-05 i

E~~}=:::j:~j~i:~: :J:~ m:~=! ~:iJi=~: =!:~~ g:::: =!:!m~: !H~i:~;: :I H!!:~t Pm-151 j 3.57E-08 j 4.33E-09 j 2.82E-09 j No Data j 7.35E-09 j 1.24E-05 2.50E-05 Eu-154 j 2.74E-03 j 2.49E-04 j 2.27E-04 j No Data j 1.09E-03 j 1.66E-03 j 2.98E-05 Eu-155 j 5.60E-04 j 4.05E-05 j 3.18E-05 j No Data j 1.51E-04 j 2.79E-04 j 5.39E-05 Eu-156 j 7.89E-06 j 4.23E-06 j 8.75E-07 j No Data j 2.72E-06 j 2.54E-04 j 4.24E-05 Tb-160 j 7.79E-05 j No Data j 9.67E-06 j No Data j 2.32E-05 j 5.34E-04 i 2.28E-05 Ho-166m j 1.34E-03 j 2.81E-04 j 2.37E-04 j No Data j 4.01E-04 j 1.13E-03 ! 1.63E-05 W-181 j 2.66E-08 j 6.52E-09 j 8.99E-10 j No Data j No Data j 5.71 E-06 j 2.61 E-07 W-185 j 8.31E-07 j 2.08E-07 j 2.91E-08 j No Data j No Data j 1.86E-04 j 1.11E-05

...W-1_87 .................i . 4.41_E-09 .........i ...2.6_1_E-09 .........i ... 1,..17E-09 .........i ...No ..Data ...........i ...No.. Data ............i ...1....1.1.E-05 .........i .. 2.46E-05 ........

Pb-210 ! 8.03E-02 i 1.85E-02 i 3.18E-03 ! No Data i 6.31 E-02 i 8.74E-02 i 1.55E-06

i. . i. .

...Bi-21_0 .................. 9. 85E-07 .........i ... 5._1 _1_ E-06 .........i . .5.65E-07 .........i ...No ,,Oata........... s. 76E-05 .........i ...3. 70E-03 .........i ...3.2.1. E-05 ........

Po-210 i 1.70E-03 I 2.76E-03 I 4.09E-04 i No Data I 8.85E-03 i 1.05E-01 i 4.32E-05 Ra-223 j 7.69E-04 j 8.89E-07 j 1.54E-04 j No Data j 2.36E-05 j 8.48E-02 j 3.00E-04

                                                       ~ ~!~:~~ . . . . .
...~::~~: ............... /..*~:~:~:~; ......... j... *:                      1.. 1:~~~:~!. . . . . ~~ .g:!:. . . . . .

j... j.. ~: ~~~:~~ .........j.. ~: ;~~:~~ .........j..*;: ~:~:~: ........

... Ra-226 ........... ....i ...2._34E-01 ...... ....iJ.66E-06.........i . .1.. 92E-01 ..........i ...No_Data...........i . 2,.03E-04 .........i .. 3.90E-01 ..........i ...3,.02E-04 ........

Ra-228 ! 1.49E-01 i 3.94E-06 i 1.68E-01 i No Data i 1.04E-04 i 5.37E-01 i 5.14E-05 1 <l Data presented in this Table are from Reference 9. A-21 195

PNPS-ODCM Rev. 11 TABLE A-13 (continued) INHALATION DOSE FACTORS FOR CHILD( 1> mrem/pCi Inhaled

                           '                      !                      i Total                    :                         ,                         '                       ,

Nuclide I Bone i Liver i Body i Thyroid i Kidney i Lung i GI-LLI Ac-225 ! 1.81 E-03 ! 1.87E-03 ! 1.21 E-04 ! No Data ! 1.99E-04 ! 7.37E-02 ! 2.67E-04 Ac-227 i 4.96E+OO i 8.05E-01 i 3.07E-01 i No Data i 1.77E-01 i 8.04E-01 i 5.22E-05 Th-227 i 9.24E-04 i 1.26E-05 i 2.67E-05 i No Data i 6.67E-05 \ 1.26E-01 i 3.49E-04 Th-228 i 8.06E-01 i 1.04E-02 i 2.72E-02 i No Data i 5.41E-02 i 3.34E+OO i 3.59E-04 Th-229 i 2.18E+01 i 5.74E-01 i 3.63E-01 i No Data i 2.83E+OO i 1.08E+01 i 4.99E-05 Th-230 i 3.30E+OO i 1. 73E-01 i 9.20E-02 i No Data i 8.52E-01 i 1.85E+OO i 3.84E-05 Th-232 i 3.68E+OO i 1.47E-01 i 1.28E-03 i No Data i 7.28E-01 i 1.77E+OO i 3.27E-05 Th-234 i 6.94E-06 i 3.07E-07 i 2.00E-07 i No Data i 1.62E-06 i 6.31 E-04 i 7.32E-05 Pa-231 i 8.62E+OO i 2.86E-01 i 3.43E-01 i No Data i 1.56E+OO i 1.92E-01 i 4.57E-05 Pa-233 i 4.14E-06 i 6.48E-07 i 7.25E-07 i No Data i 2.38E-06 i 9.77E-05 i 8.95E-06 U-232 i 2.19E-01 i No Data i 1.56E-02 i No Data i 1.67E-02 i 7.42E-01 i 4.33E-05 U-233 i 4.64E-02 i No Data i 2.82E-03 i No Data i 7.62E-03 i 1.77E-01 i 4.00E-05

*--~:;;:. . . . . . .1--:i :~~~:~;* "* *+i -~~. g:!:""""'*i\**;:~~~:~}""'i(~~. g:!:"""""'il'{~;~:~;---.. ...ji.. }~~~:~~---.......ii-{-~~~:~;"""

U-236 4.27E-02 No Data 2.65E-03 No Data 7. 16E-03 1.67E-01 3.67E-05 U-237 i 1.57E-07 i No Data i 4.17E-08 i No Data i 4.53E-07 i 3.40E-05 i 1.29E-05 U-238 i 4.09E-02 i No Data i 2.42E-03 i No Data i 6.55E-03 i 1.53E-01 i 3.51 E-05 i.

...Np-237 ............... 2. 72E+OO .......i...1_.62E+OO ...... .i...1 _._1_ 9E-01 ..........i ... No,.Oata.........        ..i.J   .41_ E-01 ..........i...1_.74E-01 ..........i ...5.06E-05 ........
...N p-238................ \...1_.26E-06 .........\ .. 2._30E-07 .........\ ...1_. 97E-08 .........\ ...No ..Data...........!. .8._1_ 6E-08 .........\ ...3 ._39E-05 .........\ ...2.50E-05 ........
.. _Np-239................ i...1_.26E-07 .........i...8._14E-08 ........J.. 6.35E-09 ........J ...No_ Data........... !.. 2.63E-08 ........J... 1_.57E-05 .........\ ... 1_. 73E-05 ........
... P.u-238................! . 2 ._55E+OO .......i ... 1_.60E+OO........i ... 1_.2_1_ E-01 .........J ... No ..Data...........! .. 4.4 7E-O 1..........! ...6. 08E-O 1..........i . 4.65E-05 ........

Pu-239 ! 2.79E+OO ! 1.68E+OO ! 1.28E-01 ! No Data ! 4.78E-01 ! 5.72E-01 ! 4.24E-05 Pu-240 i 2.79E+OO i 1.68E+OO i 1.27E-01 i No Data i 4.77E-01 i 5.71 E-01 i 4.33E-05 Pu-241 i 7 .94E-02 i 1.75E-02 i 2.93E-03 i No Data i 1.1 OE-02 \ 5.06E-04 ! 8.90E-07 Pu-242 i 2.59E+OO i 1.62E+OO i 1.23E-01 i No Data i 4.60E-01 i 5.50E-01 i 4.16E-05 Pu-244 i 3.02E+OO i 1.85E+OO i 1.41 E-01 i No Data i 5.27E-01 i 6.30E-01 i 6.20E-05

. ~~:~:;m. . .

Am-243 1...~: ~;~:~~ ~ i 2.94E+OO

                                          ........1... *:~:~:~~........1.. -~ -:~;~:~~ ..........1...

i 1.78E+OO i 1.20E-01

                                                                                                          ~~ ..

i No Data

                                                                                                                ~=~=. . . . i :~~~:~~

1...; 7.42E-01

                                                                                                                                              ..........1.. ~: ~~~:~;  .........1.. ::

i 1.92E-01 i 5.55E-05

                                                                                                                                                                                       ;~~:~~  ...... ..

Cm-242 i 9.48E-02 i 5.68E-02 i 4.20E-03 i No Data i 1.34E-02 \ 1.31 E-01 \ 5.06E-05 Cm-243 i 2.32E+OO i 1.42E+OO i 9.95E-02 j No Data i 3.74E-01 i 2.10E-01 i 4.98E-05 Cm-244 i 1.94E+OO j 1.18E+OO i 8.31 E-02 i No Data i 3.06E-01 i 2.02E-01 i 4.82E-05 Cm-245 i 3.05E+OO i 1.84E+OO i 1.28E-01 i No Data ! 5.03E-01 ! 1.95E-01 \ 4.49E-05 Cm-246 i 3.02E+OO i 1.84E+OO i 1.28E-01 i No Data i 5.03E-01 i 1.99E-01 i 4.41 E-05 Cm-247 i 2.94E+OO i 1.82E+OO i 1.26E-01 i No Data i 4.95E-01 i 1.95E-01 i 5.80E-05 Cm-248 i 2.45E+01 i 1.50E+01 i 1.04E+OO i No Data i 4.08E+OO i 1.61 E+OO i 9.35E-04 Cf-252 j 2.18E+OO j No Data j 9.33E-02 j No Data j No Data j 6.62E-01 j 1.84E-04 1 ( > Data presented in this Table are from Reference 9. A-22 196

PNPS-ODCM Rev. 11 TABLE A-14 INHALATION DOSE FACTORS FOR INFANT(1l mrem/pCi Inhaled

                                 ,                         '                         I Total                  '                         !                         '                        '

Nuclide ! Bone i Liver I Body j Thyroid ! Kidney j Lung ! GI-LLI H-3 i No Data i 2.63E-07 i 2.63E-07 i 2.63E-07 i 2.63E-07 i 2.63E-07 i 2.63E-07

rr : !:~*ii ~~=:!:gi;.;: !:!*ii ~~,d* n~~I~: :i* nr~I~ J:nt;iid:!*~ii~~!==

Na-22 P-32

= i 7.37E-05 i 7.37E-05 i 7.37E-05 i 7.37E-05 i 7.37E-05 i 7.37E-05 i 7.37E-05

... Na-24 ................... L7.54E-06 .........i..?.54E-06 .........iJ.54E-06 .........i..7._54E-06 ........i .. 7.54E-06 .........i..7._54E-06_.... ....iJ.54E-06 ........

i 1.45E-03 i 8.03E-05 i 5.53E-05 i No Data j No Data i No Data i 1.15E-05

i;Ji:= =!Il~a!~: :!:~:1~!*=1 Hii:~:=:!:~; fl~a=!:nffii Mn-54 j No Data j 1.81 E-05 i 3.56E-06 j No Data 3.56E-06

                                                                                                                                                                  !  H~:;:=!:Ii i:~~=

j 7.14E-04 j 5.04E-06 Itlf==:=II~E!~:). t*i;i]~ =l. j*fi :~~=I=~~.~~~=!** ~~lI ). 1*! i~~=:i=i*~~;:~i= : Co-60 Ni-59 f No Data

                                 \ 1.81 E-05 f    5. 73E-06
                                                           \ 5.44E-06 f    8.41 E-06
                                                                                      \ 3.1 OE-06 j No Data
                                                                                                              \ No Data f    No Data
                                                                                                                                        \ No Data j 3.22E-03
                                                                                                                                                                  \ 5.48E-05 f   2.28E-05
                                                                                                                                                                                           \ 6.34E-07
-. ~~:~~m
    ~~;1-....... *~:~~~:~~     -!    ri1;E-!rnrn-!1m=!!-!-~;-g:::-~!-~~iE;9-!i i~i]i~!-~ii :~~-
                                 !.               . . . . .:. ~:::~:~~ . . . . .!.         ~:~~~:~~ ~~
                                                                                                     . . . . .:. . .g:!:. . . . . .:.        ~:~~~:~~ ~:~~~:~:
                                                                                                                                                         . . . . .!.              . . . . .!. ;:~;~:~;. . . .

1

~~~~~::::::::::::::::::::l:::~-~~E;t~ : : : : : l: ~:;~~:6~ :::::::::!:: ~:1~~:6~ :::::::::! :::~~ ::g:!::::::::::::l:: ;::;~:6~: : : : :1: 1: ~~~:~: : : : : !: :;: :~:~~ : : : :

Br-82 1 No Data j No Data 1 9.49E-06 i No Data 1 No Data i No Data j No Data

~ :~~ :::::::::::::::::::::!:::~~::g:!:::::::::::::!:::~~:-g:!:::::::::::::!::*;:;~~:~;: : : : :!: :~~:g:!::::::::::::l:::~~:g:!::::::::::::-l:::~~:*g:!:::::::::::::1:::~~:*g:!::::::::::::

Br-85 : No Data : No Data : 1.46E-08 : No Data : No Data : No Data : No Data

i. .

 ...Rb-86 ................... No __Data............i ...1_.36E-04 .........i ...6. 30E-05 ...... ...! ...No __Data ...........i ...No ..Data............i ...No __Data............i .. 2._1 ?E-06 ........

Rb-87 i No Data i 7.11 E-05 1 2.64E-05 i No Data : No Data : No Data : 2.99E-07 Rb-88 i No Data i 3.98E-07 i 2.05E-07 i No Data i No Data i No Data i 2.42E-07

i. .

 ...Rb-89 ................... No __Data .......... ..i ...2.29E-07 .........i ... 1_.47E-07 .........i ...No ..Data...........i ... No ..Data............i ...No__Data............i .. 4.87E-08 ...... ..
 ...sr-89 ..................... i. 2._84E-04 ........J ... No ..Data............: ...8._15E-06 .........: ... No__Data........... i. _No. Data............i...1_.45E-03 .........i.. 4.57E-05 ........

Sr-90 i 1.11 E-02 i No Data i 2.23E-04 j No Data i No Data i 8.03E-03 i 9.36E-05

i. i. .

 ...s_r-91 ...................... 6.83E-08 .........! ... No ..Data............i .. 2.47E-09 .........i ...No__Data........... No. Data............i ...3. 76E-05 .........! ...5.24E-05 ........

Sr-92 i 7.50E-09 i No Data i 2.79E-10 j No Data i No Data i 1.?0E-05 i 1.00E-04

~:~~ m::::::::::::::::::l:: ;:~~~:~~ : : : :i:!: :~~:.g:!:::::::::::::i::*~:~~~:~~

Y-91 j 4.20E-04 No Data i

l:::~.~ :*g:!:_::::::::::i:::~~: g:!:::::::::::::i : :~ ::~~~:~::::::::::!::*~::~~:~~::::::::

1.12E-05 j No Data i No Data i 1.75E-03 i 5.02E-05

 .. Y-92.................... ....i ...1_._1 ?E-08 .........! ... No __Data............i ...3.29E-1_o .........i ... No __Data...........i . .No_ Data............i ... 1.-75E-05 .........i ...9.04E-05 ........

Y-93 i 1.0?E-07 i No Data i 2.91 E-09 l No Data i No Data i 5.46E-05 j 1.19E-04 1 ( > Data presented in this Table are from Reference 9. A-23 197

PNPS-ODCM Rev. 11 TABLE A-14 (continued) INHALATION DOSE FACTORS FOR INFANT(1> mrem/pCi Inhaled

                                  '                     !                        i Total                 1 Nuclide                       i Bone                 i    Liver               i    Body               !    Thyroid            i Kidney                  i Lung                 I GI-LLI Zr-93                          i 2.24E-04 i 9.51 E-06 i 6.18E-06 i No Data                                                    i    3.19E-05 i 1.37E-04 i 1.48E-06 Zr-95                          ! 8.24E-05 ! 1.99E-05 ! 1.45E-05 ! No Data                                                     !    2.22E-05 ! 1.25E-03 j 1.55E-05 Zr-97                          j 1.07E-07 j 1.83E-08 j 8.36E-09 j No Data                                                      j   1.85E-08 \ 7.88E-05 \ 1.00E-04 Nb-93m                         i 1.38E-04 i 3.59E-05 i 1.15E-05 i No Data                                                      i   3.68E-05 i 2.09E-04 i 2.47E-06
...Nb-95 ................... i...1.-.12E-05 .........i .. 4. 59E-06 .........i .. 2. 70E-06 .........i ... No __Data........... i. . 3. 37E-06 .........i ...3 .42E-04 .........\ ... 9. 05E-06 ........

Nb-97 i 2.44E-10 i 5.21E-11 i 1.88E-11 i No Data i 4.07E-11 i 2.37E-06 i 1.92E-05

***~*;:~*~*******************i***~~-*g:!:************i***~:~~~:~~*********i**~:;~~:~~-********i***~~**g:!:***********l***~*:~:~:~~*********l***~::~~:~:*********i***;:~~~:~~********

Tc-99m j 9.98E-13 j 2.06E-12 j 2.66E-11 j No Data j 2.22E-11 j 5.79E-07 ! 1.45E-06 Tc-99 ! 2.09E-07 ! 2.68E-07 j 8.85E-08 ! No Data j 2.49E-06 j 6.77E-04 ! 7.82E-06 Tc-101 ! 4.65E-14 j 5.88E-14 ! 5.80E-13 ! No Data ! 6.99E-13 j 4.17E-07 j 6.03E-07 Ru-103 ! 1.44E-06 ! No Data ! 4.85E-07 ! No Data ! 3.03E-06 j 3.94E-04 j 1.15E-05 Ru-105 ! 8.74E-10 ! No Data ! 2.93E-10 ! No Data ! 6.42E-10 ! 1.12E-05 j 3.46E-05 Ru-106 j 6.20E-05 j No Data j 7.77E-06 j No Data j 7.61E-05 j 8.26E-03 j 1.17E-04 Rh-105 j 8.26E-09 j 5.41 E-09 j 3.63E-09 ! No Data ! 1.50E-08 ! 2.08E-05 j 1.37E-05 Pd-107 ! No Data ! 4.92E-07 ! 4.11E-08 ! No Data ! 2.75E-06 ! 6.34E-05 j 7.33E-07 Pd-109 ! No Data j 3.92E-09 ! 1.05E-09 ! No Data ! 1.28E-08 ! 1.68E-05 ! 2.85E-05 i.

.. Ag-1_1.0m .......... 7 ..13E-06 .........i ...5._16E-06 .........\ ...3.57E-06_........i ...No __Data........... iJ.80E-06_ ........i ...2.62E-03 .........\ ...2.36E-05 ........
.. Ag-11.1 ................. \. ..3.75E-07 .......J. 1_.45E-07 .........\.J.75E-08 ......... \. ..No __Data...........i. .3.05E-07_ .......J.. 2 ..06E-04 ........J ...3.02E-05 ........

Cd-113m i No Data i 6.67E-04 i 2.64E-05 i No Data i 5.80E-04 i 1.40E-03 i 1.65E-05 Cd-115m j No Data ! 1.73E-04 ! 6.19E-06 ! No Data ! 9.41 E-05 j 1.47E-03 ! 5.02E-05 Sn-123 j 2.09E-04 ! 4.21 E-06 ! 7.28E-06 ! 4.27E-06 ! No Data ! 2.22E-03 ! 4.08E-05

...s.n-125 ................\ ...1.-.0.1. E-05 .........i ...2._51. E-07 .........i ...6. OOE-07 .........\ .. 2 .4 7E-07 ........ i...No ._Data............\ .. 6.43E-04 .........iJ     .26E-05 ........

Sn-126 i 8.30E-04 i 1.44E-05 i 3.52E-05 ! 3.84E-06 ! No Data ! 4.93E-03 ! 1.65E-05 Sb-124 ! 2.71 E-05 ! 3.97E-07 ! 8.56E-06 j 7.18E-08 j No Data ! 1.89E-03 ! 4.22E-05 Sb-125 j 3.69E-05 ! 3.41E-07 ! 7.78E-06 j 4.45E-08 j No Data ! 1.17E-03 ! 1.05E-05

~~: ~-~~::::::::::::::::i:: ;:~~~:~~ :::::::::i:} ~~~:~~ :::::::::i:::;: ;~~:~~ : : : : :!: :~:~~~:~~: : : : !: :~~: ~:!:::::::::::::!:::~: ~:~:~::::::::::!:::~: ~~~:~~ : : : :

Te-125m i 3.40E-06 i 1.42E-06 ! 4.70E-07 i 1.16E-06 ! No Data i 3.19E-04 i 9.22E-06 Te-127m j 1.19E-05 j 4.93E-06 ! 1.48E-06 j 3.48E-06 j 2.68E-05 j 9.37E-04 j 1.95E-05 Je-1.27 ................i . .1_.59E-09 .........i ...6.8_1.E-1.o ........ .i...3.49E-1.o .........i...1_.32E-09 ........i ...3.47E-09_........i..7.39E-06 .........i...1_.74E-05 ....... . Te-129m i 1.01E-05 i 4.35E-06 i 1.59E-06 i 3.91E-06 i 2.27E-05 i 1.20E-03 i 4.93E-05

i. .

Je-1.29 ................ 5.63E-1.1 ..........i ...2.48E-1_ 1..........i...1_.34E-1.1 ..........i .. 4.82E-1.1 ......... i...1 _.25E-1.o .........i.. 2 ..14E-06 .........i...1_.88E-05 ........ Te-131 m i 7.62E-08 i 3.93E-08 i 2.59E-08 i 6.38E-08 i 1.89E-07 i 1.42E-04 i 8.51 E-05 Te-131 j 1.24E-11 j 5.87E-12 j 3.57E-12 j 1.13E-11 ! 2.85E-11 j 1.47E-06 j 5.87E-06 i.

 .. Te-.1.32 ................ 2.66E-07 .........i ...1_.69E-07.........! ...1_.26E-07 .........i . .1_._99E-07 ......)J .39E-07 .........! .. 2.43E-04 .........i ...3 ..15E-05 ........

Te-133m 1 6.13E-11 1 3.59E-11 1 2.74E-11 1 5.52E-11 1 1.72E-10 1 3.92E-06 1 1.59E-05 Te-134 !3.18E-11 i2.04E-11 !1.68E-11 !2.91E-11 !9.59E-11 !2.93E-06 !2.53E-06

 .J-1.29 ......................\.. 2 ..16E-05 .........i...1_._59E-05 .........i...1_..16E-05 .........i ...1_._04E-02 ........ i...1.-88E-05 .........i...No._Data...........L2 ..12E-07 ........

1-130 ! 4.54E-06 ! 9.91 E-06 ! 3.98E-06 ! 1.14E-03 i 1.09E-05 \ No Data ! 1.42E-06

 * *: ~*;~ * * * * * * * * * * * :* *~ :~-~* ~:~~ *********!***;:~;~:~~*********i***~::~~:~~-********i***~ *:~~t~~ * * *

i* ;: ~~~:~~ *********l***~~. g:!:************l ***~: ~~~:~;. . . ..

1-133 i 9.46E-06 i 1.37E-05 ! 4.00E-06 ! 2.54E-03 i 1.60E-05 ! No Data i 1.54E-06

 ... 1-1.34 ...................... i...6.58E-07 .........i ... 1.-34E-06 ......... i.. 4.75E-07 .........\ ...3 ..18E-05 ........ i...1.-49E-06 .........\ ...No._Data.......... ..i ...9.21_E-07 ........

1-135 ! 2.76E-06 ! 5.43E-06 ! 1.98E-06 i 4.97E-04 ! 6.05E-06 i No Data i 1.31E-06 1 ( > Data presented in this Table are from Reference 9. A-24 198

PNPS-ODCM Rev. 11 TABLE A-14 (continued) INHALATION DOSE FACTORS FOR INFANT(1l mrem/pCi Inhaled i 1 ( Total i i = : Nuclide I Bone l Liver ! Body l Thyroid l Kidney ! Lung ! GI-LLI Cs-134m i 1.32E-07 i 2.10E-07 i 1.11E-07 i No Data i 8.50E-08 i 2.00E-08 i 1.16E-07

...Cs-134................ i.                                               i. .                                           i. .

2 ..83E-04 .........i ...5 ..02E-04 ......... 5.32E-05 .........i ...No. Data........... 1_.36E-04 .........i ...5.69E-05 .........i ...9.53E-07 ........ Cs-135 i 1.00E-04 i 8.66E-05 i 4.73E-06 i No Data i 2.58E-05 i 1.01E-05 i 2.18E-07

. g:: ~ ;~* * * * * * *i * :* *;:~;~:~:* * * * *i:* !:~~~:~!*********!***;:;~~:~~*********:***~~

Cs-138 3.61E-07 5.58E-07 i 2.84E-07 i

                                                                                                            **~:!:***********: . ~:~;~:~: *********:***~ :~~~:~~ *********:***;: ~~~:~~********

No Data i 2.93E-07 i 4.67E-08 i 6.26E-07

***~:: ~ ;~****************:***~:~~~:~~* * * * *:* *~: ~;~:~~ *********!***1:~;~:~~* * * * *!* *~~ .g:!:***********i** ~:~~~:~~ * * * * *i* !:;;~:~~*********i***1::!~:~~. . . ..

Ba-140 i 4.00E-05 i 4.00E-08 i 2.07E-06 i No Data i 9.59E-09 i 1.14E-03 ! 2.74E-05 Ba-141 i 1.12E-10 i 7.70E-14 i 3.55E-12 i No Data i 4.64E-14 i 2.12E-06 i 3.39E-06

. ~~i~f==i**i*Ei~~~ =:!=!*~!!~~~= :]. ~*!Ii~~i =i=~~:~;E =i=~i1I=i=I*~i~~i: i*iii~~i :

i. . i. .

J .

...Ce-141 ................ 1.- 98E-05 ....... ..i ... 1.-.19E-05 ....... ..i ...1_.42E-06 .........i ...No __Data ........... 3. 75E-06 .........i ...3.69E-04 .........i ...1_.54E-05 ........

Ce-143 i 2.09E-07 i 1.38E-07 i 1.58E-08 : No Data i 4.03E-08 i 8.30E-05 : 3.55E-05

        ~~                        ~:~~~:~; *********i***~:~!~:~:*********i**~:~~~:~i*********i***~~.g:!:***********i***~:~~~:~:* * * * *:* *~: ~~~:~!*********:***~:~~~:~:********

4

***~~~        ***************:**

Pr-144 i 3.42E-11 i 1.32E-11 \ 1.72E-12 i No Data \ 4.80E-12 \ 1.15E-06 \ 3.06E-06 Nd-147 i 5.67E-06 i 5.81 E-06 i 3.57E-07 i No Data i 2.25E-06 i 2.30E-04 i 2.23E-05

i. .

...Pm-14 7.............. 3.91 E-04 .........i ...3. 07E-05 .........i... 1_.56E-05 .........i...No__Data...........i.. 4.93E-05 .........i.. 4.55E-04 ..... ....i ...5. 75E-06 ........

Pm-148m i 5.00E-05 i 1.24E-05 i 9.94E-06 j No Data i 1.45E-05 : 1.22E-03 i 3.37E-05 Pm-148 i 3.34E-06 i 4.82E-07 i 2.44E-07 i No Data i 5.76E-07 i 3.20E-04 i 6.04E-05

i. .

...Pm-149.............. 3 ..1OE-07 ....... ..i .. 4. OSE-08 .........i ...1_. 78E-08 .........i ...No._Data...........i . 4.96E-08 .........i ...6.50E-05 .........i ...3.01. E-05 ....... .
                                                                          ..J . .                                                                ..J . .
... Pm-151............... 1.. 7 ..52E-08 .........1 ... 1.-.1 OE-08 ..... 5.55E-09 .........l ... No._Data...........! ...1_.30E-08 ..... 3.25E-05 ..... ....1 ...2.58E-05 ........
                                                                          ..J . .                                                                ..J .
...sm-15.1-. ............. 1...3. 38E-04 .........! ...6.45 E-05 ..... 1_.63E-05 .........! ... No ._Data...........! ...5.24E-05 ..... 2 ..98E-04 ........J ...3.46E-06 ........

Sm-153 i 1.53E-07 i 1.18E-07 i 9.06E-09 i No Data i 2.47E-08 i 3.70E-05 i 1.93E-05 Eu-152 i 7.83E-04 i 1.77E-04 1.72E-04 i No Data i i 5.94E-04 i 1.48E-03 i 9.88E-06 Eu-154 i 2.96E-03 i 3.46E-04 i 2.45E-04 i No Data i 1.14E-03 i 3.05E-03 i 2.84E-05 Eu-155 ! 5.97E-04 \ 5.72E-05 i 3.46E-05 ! No Data j 1.58E-04 j 5.20E-04 j 5.19E-05 Eu-156 j 1.56E-05 i 9.59E-06 i 1.54E-06 j No Data i 4.48E-06 i 6.12E-04 i 4.14E-05 Tb-160 i 1.12E-04 i No Data i 1.40E-05 i No Data i 3.20E-05 i 1.11 E-03 i 2.14E-05 Ho-166m i 1.45E-03 i 3.07E-04 i 2.51E-04 i No Data i 4.22E-04 i 2.05E-03 i 1.65E-05 W-181 j 4.86E-08 i 1.46E-08 i 1.67E-09 i No Data i No Data i 1.33E-05 i 2.63E-07 W-185 i 1.57E-06 i 4.83E-07 i 5.58E-08 i No Data i No Data i 4.48E-04 i 1.12E-05 W-187 i 9.26E-09 i 6.44E-09 i 2.23E-09 i No Data i No Data i 2.83E-05 i 2.54E-05

i. .

... Pb-2.1. o................i ...8.62E-02 .........i . 2. 02E-02 .........i ...3.43E-03 .........i ...No ..Data........... 6. 85E-02 .........i ...1_. 76E-O 1..........i ... 1_. 57E-06 ........

Bi-210 i 2.06E-06 i 1.33E-05 : 1.18E-06 i No Data i 1.03E-04 : 9.96E-03 I 3.27E-05 i.

... Po-2.1.0 ................ 2 ..98E-03 .........i ... 5.63E-03 ........ .i .. 7 ..12E-04 .........i ...No._Data.......... .i . .1_.30E-02 .........i ...2.40E-01 ..........i .. 4.36E-05 ........

Ra-223 ! 1.56E-03 ! 2.26E-06 ! 3.12E-04 ! No Data ! 4.16E-05 j 2.25E-01 ! 3.04E-04 Ra-224 i 1.77E-04 i 4.00E-07 i 3.54E-05 i No Data i 7.30E-06 i 7.91 E-02 i 3.42E-04 Ra-225 i 2.57E-03 i 2.88E-06 i 5.13E-04 i No Data i 5.31E-05 i 2.57E-01 i 2.87E-04 Ra-226 i 2.48E-01 i 1.46E-05 i 2.05E-01 i No Data i 2.94E-04 i 7.83E-01 i 3.05E-04 Ra-228 j 1.60E-01 j 7.61 E-06 j 1.80E-01 j No Data j 1.53E-04 j 1.09E+OO j 5.19E-05 1 ( > Data presented in this Table are from Reference 9. A-25 199

PNPS-ODCM Rev. 11 TABLE A-14 (continued) 1 INHALATION DOSE FACTORS FOR INFANT< > mrem/pCi Inhaled

                                            ,                                         ;                                        ! Total                                  ;                                         i                                          :                                          '

Nuclide ! Bone i Liver i Body i Thyroid ! Kidney ! Lung l GI-LLI Ac-225 ! 3.69E-03 ! 4.72E-03 ! 2.48E-04 ! No Data ! 3.49E-04 ! 1.96E-01 ! 2.71 E-04 Ac-227 i 5.29E+OO i 8.76E-01 i 3.28E-01 i No Data i 1.86E-01 i 1.62E+OO i 5.27E-05 Th-227 i 1.82E-03 i 3.03E-05 i 5.24E-05 i No Data i 1.13E-04 i 3.27E-01 i 3.53E-04 Th-228 i 8.46E-01 i 1.1 OE-02 j 2.86E-02 j No Data j 5.61 E-02 j 4.65E+OO j 3.62E-04

...Th-229****************t2.28E+o1********t5.94E-O{ ******t3 ..81 E-of*******tNo ..Data........ 9."32E-01 *********t1*.27E+o1********j                                                                            i                                                                                         5.02E-05 Th-230                                  i     3.46E+OO                            i 1.79E-01                                j 9.65E-02                               j No Data                                i 8.82E-01                                 i 2.18E+OO                                 i 3.87E-05 Th-232                                  i    3.86E+OO j                                1.53E-01                            i 2.29E-03 i No Data i 7.54E-01                                                                                               i 2.09E+OO                                 i 3.29E-05 Th-234                                  i     1.33E-05                            i    7.17E-07                            i 3.84E-07 i No Data i 2.70E-06                                                                                               j 1.62E-03                                 i 7.40E-05
. *Pa-23f ........°i".9."1 OE+OO .... \                                                    3.00E-01.                           i 3.62E-of*******:***No Data******** i 1.62E+OO                                                                               i 3.85E-01                                 j 4.61 E-05 Pa-233                                  j 6.84E-06                               i    1.32E-06                            i 1.19E-06 i No Data j 3.68E-06                                                                                               i 2.19E-04                                 j 9.04E-06 U-232                                   j 2.57E-01                                j No Data                               i 2.13E-02 j No Data j 2.40E-02                                                                                               i 1.49E+OO                                 i   4.36E-05 U-233                                  i     5.44E-02 j No Data                                                            \ 3.83E-03 \ No Data                                                              i 1.09E-02                                 i 3.56E-01                                 i   4.03E-05 U-234                                   j 5.22E-02                               i    No Data                              j 3.75E-03                               j No Data                                 j 1.07E-02                                i 3.49E-01                                 i   3.95E-05 U-235                                  i     5.01 E-02 j No Data                                                          i    3.52E-03                             i    No Data                             i     1.01 E-02                            i 3.28E-01                                 i   5.02E-05 U-236                                  i     5.01 E-02                           i    No Data                             i    3.60E-03                             i    No Data                             j 1.03E-02 j 3.35E-01                                                                 j 3.71 E-05 U-237                                   j 3.25E-07                                i   No Data                              i   8.65E-08                             i    No Data                              j 8.08E-07 j 9.13E-05                                                                i   1.31 E-05 U-238                                   i    4.79E-02                             i   No Data                              i   3.29E-03                             i    No Data                              j 9.40E-03                                i     3.06E-01                             i   3.54E-05
 ... Np-237 ............... i.. 2.88E+OO .......i ... 1.-71 E+OO .......i ...1.-26E-01 ..........i ...No__Data........... iJ.69E-01 ..........i ...3.49E-01 ..........i ...5 ..1OE-05 ........

Np-238 ! 2.67E-06 ! 6.05E-07 ! 4.16E-08 ! No Data ! 1.47E-07 ! 9.19E-05 ! 2.58E-05 Nn-239 j 2.65E-07 j 2.13E-07 j 1.34E-08 i No Data j 4.73E-08 j 4.25E-05 j 1.78E-05

 **.**... t'.:.............................. * ..........................................................................................................................* ....................................... * ........................................ * ................................................................................

Pu-238 ! 2.69E+OO ! 1.68E+OO ! 1.27E-01 ! No Data ! 4.64E-01 ! 9.03E-01 ! 4.69E-05

 ... Pu-239**** .......... 1***2:93E+Oo .... ""i" f76E+OO .. (f34E-of*..****:***No Data******** 4.95E-01                                                                                                          i                                          i     8.47E-01                             i   4.28E-05 Pu-240                                  j 2.93E+OO                                i    1.75E+OO                            i   1.34E-01                             j No Data                                 j 4.94E-01                                 j 8.47E-01                                i 4.36E-05 Pu-241                                  i    8.43E-02                             i    1.85E-02                            i   3.11 E-03                            i    No Data                              i 1.15E-02 i 7.62E-04                                                                i 8.97E-07 Pu-242                                  j 2.72E+OO                                i   1.69E+OO                             i   1.29E-01                             i    No Data                              i 4.77E-01 i 8.15E-01                                                                i 4.20E-05 Pu-244                                  j 3.17E+OO \ 1.94E+OO \ 1.48E-01 j No Data                                                                                                                            \ 5.46E-01                                 j 9.33E-01                                j 6.26E-05
 . Am-241......... (3 ..15E+00 .......({95E+OO *y*{3*1*E-of******tNo Data.......                                                                                                                                   i 7.94E-01                                 i 4.06E-01                                i 4.78E-05 Am-242m j 3.25E+OO j 1.86E+OO j 1.35E-01                                                                                                                             j No Data                                 j 8.03E-01                                 j 1.64E-01                                [ 6.01 E-05....

~:~~!~:: : : : : : !: ;:~~~~it: : : !: :~:~~~~it: : : i: :!:~~~:~~:::::::::!:::~~: g:~::::::::::::l::

 ...cm-243 ............. /.. 2.47E+oo........i ... 1_. 52E+oo.......J ... 1_. 06E-01 ..........l ...No ..Oata.......J . .3. 9.1. E-01 ..........l .. 4.24E-O 1.........J ...5._02E-05 ........
                                                                                                                                                                                                                        ~ :~~~:~~                   :::::::J:: ;:        ~~~:~~:: : : : :!: :;:~~~:~;: : : :

Cm-244 ! 2.07E+OO ! 1.27E+OO ! 8.89E-02 ! No Data ! 3.21E-01 ! 4.08E-01 ! 4.86E-05 Cm-245 ....... (3.22E+OO ..... \ {96E+OO j .. {36E-01.......:""No Data...... 5.23E-01 i \ 3.92E-01 \ 4.53E-05

i. .

  ...Cm-246 ............. :***3.20E+OO ....... 1.. 96E+OO ....... :***1 *.36E-01 .......... j***No ..Data........... 5.23E-01**********i ...3."99E-01 .........j 4.45E-05                                          i. .
 ***cm-247 ............°i"".3."1*1*E+OO ....... j...1.."93E+00 .......(1*.33E-Of******tNo**Data........... (5."1*5E-01********(3."92E-01 ******j 5.85E-05
  . .g~;~~s . . . . . . . ,. ;:;~~:~6*******l***~~~Ea~~ 1*****...l..*~*:*6~~~gt..****l***~~-g:~=*****..****\ .. ~~~Ea~~o********\**;:~;~:~~ ..*****\***~*::;~:~!***. * *

<1> Data presented in this Table are from Reference 9. A-26 200

PNPS-ODCM Rev. 11 TABLEA-15 INGESTION DOSE FACTORS FOR ADUL T( 1> mrem/pCi Ingested Nuclide I Bone I Liver I ~~~~ 1*Thyroid I Kidney I Lung l GI-LLI H-3 : No Data i 5.99E-08 : 5.99E-08 i 5.99E-08 : 5.99E-08 i 5.99E-08 : 5.99E-08 Be-10 j 3.18E-06 i 4.91E-07 j 7.94E-08 i No Data j 3.71E-07 i No Data j 2.68E-05 C-14 ! 2.84E-06 i 5.68E-07 ! 5.68E-07 i 5.68E-07 ! 5.68E-07 i 5.68E-07 j 5.68E-07 N-13 i 8.36E-09 ! 8.36E-09 j 8.36E-09 i 8.36E-09 i 8.36E-09 i 8.36E-09 j 8.36E-09 F-18 i 6.24E-07 i No Data i 6.92E-08 i No Data i No Data j No Data i 1.85E-08 Na-22 ! 1.74E-05 i 1.74E-05 j 1.74E-05 i 1.74E-05 ! 1.74E-05 i 1.74E-05 ! 1.74E-05 Na-24 i 1.70E-06 j 1.70E-06 j 1.70E-06 i 1.70E-06 i 1.70E-06 i 1.70E-06 i 1.70E-06 P-32 i 1.93E-04 i 1.20E-05 i 7.46E-06 i No Data i No Data i No Data j 2.17E-05 Ca-41 i 1.85E-04 j No Data j 2.00E-05 j No Data j No Data j No Data j 1.84E-07 Sc-46 j 5.51 E-09 ! 1.07E-08 ! 3.11 E-09 ! No Data j 9.99E-09 i No Data j 5.21 E-05 Cr-51 i No Data i No Data ! 2.66E-09 i 1.59E-09 i 5.86E-10 j 3.53E-09 i 6.69E-07 Mn-54 j No Data ! 4.57E-06 i 8.72E-07 i No Data i 1.36E-06 i No Data j 1.40E-05 Mn-56 i No Data i 1.15E-07 ! 2.04E-08 i No Data i 1.46E-07 i No Data j 3.67E-06 Fe-55 i 2.75E-06 ! 1.90E-06 ! 4.43E-07 i No Data i No Data i 1.06E-06 j 1.09E-06 Fe-59 j 4.34E-06 ! 1.02E-05 ! 3.91 E-06 j No Data ! No Data j 2.85E-06 j 3.40E-05 Co-57 j No Data i 1.75E-07 i 2.91 E-07 j No Data i No Data j No Data i 4.44E-06 Co-58 j No Data i 7.45E-07 i 1.67E-06 j No Data i No Data j No Data i 1.51 E-05 Co-60 i No Data i 2.14E-06 i 4.72E-06 i No Data i No Data i No Data i 4.02E-05 Ni-59 \ 9.76E-06 \ 3.35E-06 \ 1.63E-06 \ No Data \ No Data \ No Data \ 6.90E-07 Ni-63 ! 1.30E-04 i 9.01 E-06 i 4.36E-06 j No Data i No Data i No Data j 1.88E-06 Ni-65 i 5.28E-07 i 6.86E-08 i 3.13E-08 j No Data i No Data ! No Data j 1.74E-06 Cu-64 ! No Data i 8.33E-08 i 3.91 E-08 i No Data i 2.1 OE-07 i No Data j 7 .1 OE-06 Zn-65 i 4.84E-06 i 1.54E-05 i 6.96E-06 i No Data i 1.03E-05 i No Data ! 9.70E-06

 *--~~:~~m **************li***~ *: ~~~:~;...*****l**i ~: ~~~:~; ********l***~:

Se-79 No Data 2.63E-06 i

                                                                                   ;~~:~~ ********!***~~.g:::***********l** ~:~;~:~;********l***~~.g:::***********l** ~:~~~:~~ ********

4.39E-07 i No Data i 4.55E-06 i No Data i 5.38E-07 Br-82 i No Data i No Data i 2.26E-06 No Data i No Data i No Data l l 2.59E-06 Br-83 i No Data i No Data i 4.02E-08 i No Data i No Data i No Data i 5.79E-08 Br-84 i No Data i No Data i 5.21E-08 i No Data j No Data i No Data i 4.09E-13 Br-85 j No Data j No Data j 2.14E-09 j No Data j No Data j No Data i No Data Rb-86 i No Data i 2.11 E-05 i 9.83E-06 i No Data i No Data i No Data i 4.16E-06 Rb-87 i No Data i 1.23E-05 j 4.28E-06 i No Data j No Data i No Data i 5.76E-07 Rb-88 i No Data j 6.05E-08 i 3.21E-08 i No Data j No Data i No Data i 8.36E-19 Rb-89 i No Data i 4.01 E-08 i 2.82E-08 i No Data i No Data i No Data i 2.33E-21 Sr-89 i 3.08E-04 i No Data j 8.84E-06 i No Data i No Data j No Data i 4.94E-05 Sr-90 i 8.71E-03 i No Data i 1.75E-04 i No Data i No Data i No Data i 2.19E-04 Sr-91 : 5.67E-06 : No Data : 2.29E-07 i No Data : No Data i No Data : 2.70E-05 Sr-92 i 2.15E-06 j No Data i 9.30E-08 i No Data i No Data i No Data i 4.26E-05 Y-90 i 9.62E-09 i No Data i 2.58E-10 i No Data j No Data j No Data j 1.02E-04 Y-91m i 9.09E-11 i No Data i 3.52E-12 i No Data i No Data i No Data i 2.67E-10 Y-91 i 1.41E-07 j No Data i 3.77E-09 No Data l i No Data i No Data j 7.76E-05

i. . i. . i. . i. .

  .. Y-92........................ 8.45E-1.o ........i ...No. Data........... 2.4 7E-1_ 1.........i ...No __Data........... No __Data ........... No __Data...........L.1 _.48E-05 ........

Y-93 ( 2.68E-09 j No Data ( 7.40E-11 i No Data I No Data ( No Data ( 8.50E-05 1 ( > Data presented in this Table are from Reference 9. A-27 201

PNPS-ODCM Rev. 11 TABLE A-15 (continued) INGESTION DOSE FACTORS FOR ADULT( 1l mrem/pCi Ingested

                                    '                      1                        1   Total              *                          ,                       1                          1 Nuclide                        I Bone                 I Liver                  i Body                 I Thyroid                  i Kidney                I Lung                     I GI-LLI Zr-93                          i 4.18E-08             i 2.34E-09               i 1.09E-09             i No Data                  i 8.87E-09              i No Data                  i 2.43E-06
 --~~:~~------------------**-i** ~:~:~:~~--------i-*-;:~~~:~~--------i---~:~~~:~~-*-*---*i-*-~~-g:!:---*-*---**i* *~:-~;~:~~--------i--*~~*g:!:** *-------i---~:-~;~:~~*-* * --

~mm:: ::! mi:~;::!:mi:~;::!rni:~i: !~~:g::: :::!:;m:~;::! ~~:g::::: Jrni=~i :

Mo-93 i No Data i 7.51E-06 i 2.03E-07 i No Data j 2.13E-06 i No Data j 1.22E-06 Mo-99 i No Data i 4.31E-06 i 8.20E-07 i No Data i 9.76E-06 j No Data j 9.99E-06 Tc-99m j 2.47E-10 j 6.98E-10 i 8.89E-09 i No Data j 1.06E-08 j 3.42E-10 j 4.13E-07

  -* Tc-99 _.. _____________ _...i __.1 _.25E-07 ____ _...i ___ 1_._86E-07 *--***--i .. _5. 02E-08 -*-----*j __.No ._Data___________ j___2 ..34E-06 ..... ___ j___ 1_. 58E-08 ____ _...i __ .6 ..08E-06 _______ _

Tc-101 j 2.54E-10 i 3.66E-10 i 3.59E-09 j No Data i 6.59E-09 i 1.87E-10 j 1.10E-21

  -*-~~:~*~~----------------i---t~~~:~~--------i---~~*-g:!:*-* -* *---i*{~~~:~~-*---*-*i*-*~~*g:::-*---------i-*-;:*~~~:~;** * ---i---~~-g:::-----*--*-*i-{~~~:~~--------

Ru-106 j 2.75E-06 i No Data i 3.48E-07 j No Data i 5.31 E-06 i No Data i 1.78E-04 ___ Rh-1.05__.... ______ _...i ___ 1_.2_1. E-07 ____ _...i ___ 8.85E-08 *--**--*i .. _5. 83E-08 _______.j __.No ..Oata.. _.. __ _...i ___ 3. 76E-07 **--_...i __.No __Data _______ _...i __ .1 _.41_ E-05 _______ _ Pd-107 i No Data i 1.47E-07 j 9.40E-09 j No Data i 1.32E-06 i No Data i 9.11 E-07

:~:

Ag-111

            ~ ~~m ::::::::::i:::~-~~E~~7::::::::!:::~::~~~:~;: : : : i: :~: ~~~:~~ ::::::::i:::~~::g::::::::::::::i:: ~::~~: ~:~~ ::::::::ii :::~~::g::::::::::::::i:::~: ~~~:~~ : : : :

j 5.81 E-08 \ 2.43E-08 \ 1.21 E-08 j No Data j 7.84E-08 No Data \ 4.46E-05 Cd-113m i No Data i 3.18E-06 j 1.02E-07 ! No Data i 3.50E-06 ! No Data j 2.56E-05 ___Cd-1_15m ________ j _ .No._Data..___._____ j___ 1_.84E-06 ...... __ j__.5.87E-08 ___.___.i _ _No__Data. ______...-i _ _1_.46E-06 ___.....i ...No __Data _______..__ j...7.74E-05 __._..__ Sn-123 i 3.11E-05 i 5.15E-07 j 7.59E-07 i 4.38E-07 i No Data i No Data i 6.33E-05 Sn-125 j 8.33E-06 j 1.68E-07 i 3.78E-07 j 1.39E-07 ! No Data j No Data j 1.04E-04 Sn-126 ! 8.45E-05 j 1.67E-06 i 2.40E-06 ! 4.92E-07 ! No Data j No Data j 2.43E-05 Sb-124 i 2.80E-06 ! 5.29E-08 j 1.11E-06 i 6.79E-09 ! No Data j 2.18E-06 j 7.95E-05

  ---~~:~;~----------------:--*~*:;~~:~~--------i--;:~~~:~~-** *--*l--::~~~:~;---*---*i---;:~~~:~~--------i---~~*-g:::*---*-* * -l** ;:~~~:~~--**----l---~:!b~:~~--** -*

Sb-127 i 2.58E-07 j- 5.65E-09 j 9.90E-08---*-*-*i""°3."1 OE-09 _______ ! No--Data*---*-****{\.53E-Oi______ "j"" 5.90E-05*-***-*- Te-125m i 2.68E-06 j 9.71E-07 j 3.59E-07 ! 8.06E-07 i 1.09E-05 j No Data j 1.07E-05 Te-127m j 6.77E-06 j 2.42E-06 j 8.25E-07 j 1.73E-06 j 2_75E-05 j No Data j 2.27E-05 Te-127 i 1.10E-07 i 3.95E-08 i 2.38E-08 ! 8.15E-08 i 4.48E-07 ! No Data j 8.68E-06 Te-129m j 1.15E-05 i 4.29E-06 j 1.82E-06 j 3.95E-06 j 4.80E-05 j No Data j 5.79E-05 Te-129 ! 3.14E-08 i 1.18E-08 i 7.65E-09 ! 2.41E-08 ! 1.32E-07 ! No Data j 2.37E-08 Te-131m j 1.73E-06 j 8.46E-07 j 7.05E-07 i 1.34E-06 j 8.57E-06 i No Data j 8.40E-05

  -* Te-1_31. ________________ j_._1 _. 97E-08 _____...i ___8 .23E-09 .... _. __ j___6.22E-09 -**--*..i .. _1 _.62E-08 ________ j___ 8.63E-08 ---**-*-i ... No __Data_. _____ _...i ___2. 79E-09 _______ _
  -* Te-1_32**---*-*-****--.L_ 2.52E-06*-***-J._1 _.63E-06_*-*-*J .. 1_.53E-06 _____.J__ 1.-.80E-06 _____...! ___ 1_.57E-05 ______ J._No __Data ___.. ____ 7. 71. E-05*---***-         J_

Te-133m i 4.62E-08 i 2.70E-08 i 2.60E-08 i 3.91E-08 i 2.67E-07 i No Data i 9.26E-09 Te-134 j 3.24E-08 j 2.12E-08 j 1.30E-08 j 2.83E-08 j 2.05E-07 j No Data j 3.59E-11 1-129 j 3.27E-06 j 2.81E-06 j 9.21E-06 j 7.23E-03 j 6.04E-06 j No Data j 4.44E-07 ___ 1-1.30_*-****--**-*******-***L 7 .56E-07 ***-****L 2.23E-06 **-****.:.__8_.80E-07 **-****_i.._1 _.89E-04 --*****.\.. 3_.48E-06 _.......i...No. Data_......-... L.1_.92E-06 *-****** 1-131 i 4.16E-06 i 5.95E-06 j 3.41E-06 i 1.95E-03 i 1.02E-05 i No Data i 1.57E-06 i. _._1-1_32***---****-***--*****_j __.2.03E-07 __.__...i ...5.43E-07_.... _..i. __ 1_.90E-07 ____ .. _.j __.1_.90E-05 __ ... _.. _8.65E-07 ........i .. _No__Data_ .... ___ .__i __ .1_..02E-07_.. __ ... _.. 1-1_33 ____ *-****-***-*-***--!_.. 1_.42E-06_.......!._2.47E-06_.... ___ !J.53E-07 .. _.....!._.3.63E-04._......!._4.3_1_E-06 ..... ___ l. . No __Data****--*....l ...2.22E-06 ...-.... 1-134 l 1.06E-07 l 2.88E-07 i 1.03E-07 i 4.99E-06 l 4.58E-07 l No Data i 2.51E-10 1-135 j 4.43E-07 j 1.16E-06 j 4.28E-07 j 7.65E-05 j 1.86E-06 j No Data j 1.31E-06 1 ( ) Data presented in this Table are from Reference 9. A-28 202

PNPS-ODCM Rev. 11 TABLE A-15 (continued) INGESTION DOSE FACTORS FOR ADULT' 1 ) mrem/pCi Ingested

                            '                       :                      ( Total                 i                     :                  :                        .

Nuclide i Bone i Liver i Body i Thyroid i Kidney ) Lung ! GI-LLI Cs-134m : 2.13E-08 i 4.48E-08 : 2.29E-08 : No Data : 2.43E-08 i 3.83E-09 i 1.58E-08

 ...Cs-134................ l. .                    l. .                   i. .                                          l.

6.22E-05 ........ 1.-48E-04 ........ 1.-2.1. E-04 ........l ... No._Data........... 4. 79E-05 ...... ..i ...1.-59E-05 ........l .. 2.59E-06 ........ Cs-135 ! 1.95E-05 ! 1.80E-05 ! 7.99E-06 i No Data ! 6.81 E-06 ! 2.04E-06 i 4.21 E-07 Cs-136 j 6.51 E-06 j 2.57E-05 j 1.85E-05 j No Data j 1.43E-05 j 1.96E-06 j 2.92E-06 Cs-137 j 7.97E-05 j 1.09E-04 j 7.14E-05 i No Data i 3.70E-05 i 1.23E-05 j 2.11E-06 Cs-138 i 5.52E-08 j 1.09E-07 i 5.40E-08 i No Data i 8.01 E-08 i 7.91 E-09 i 4.65E-13

 ***~=: ~ ;:****************i***~:i6~:~~ ********l** ~ :*~~~:~~ ********i** ~: ~!~:~~ ********l***~~ ..g:!:***********l** ::~~~:~~ ********l***;:;~~:~~********l***~*:;~:~~~********

Ba-140 i 2.03E-05 j 2.55E-08 i 1.33E-06 j No Data i 8.67E-09 j 1.46E-08 j 4.18E-05 Ba-141 i 4.71E-08 j 3.56E-11 i 1.59E-09 j No Data i 3.31E-11 i 2.02E-11 i 2.22E-17

  * *~=:~:~* * * * * * * * :* ~: ~~~:~~       ********1***~:~~~:6; ********i***1: ;~~:~~ ********!***~~..g:::***********l***~*~1E;t~1*********i***~*;6~t~1*********i***~:~~:~~~********

La-141 j 3.19E-10 j 9.90E-11 j 1.62E-11 i No Data i No Data ! No Data ! 1.18E-05

  * *~:--~!~    ****************l***;:;~~:6~********i** ~:*~;~:6;********l**;    :~~~: ~*6********l***~~*.g:::***********l** ~.~i:~9 ********l***~~ ..g:::***********l***~:~;~:~~********

Ce-143 i 1.65E-09 j 1.22E-06 i 1.35E-10 j No Data j 5.37E-10 i No Data i 4.56E-05 Ce-144 j 4.88E-07 j 2.04E-07 i 2.62E-08 ! No Data j 1.21 E-07 i No Data ! 1.65E-04 Pr-143 i 9.20E-09 j 3.69E-09 ! 4.56E-10 i No Data ! 2.13E-09 ! No Data ! 4.03E-05 Pr-144 i 3.01E-11 \ 1.25E-11 j 1.53E-12 j No Data j 7.05E-12 j No Data j 4.33E-18 Nd-147 ! 6.29E-09 ! 7.27E-09 ! 4.35E-10 ! No Data ! 4.25E-09 j No Data ! 3.49E-05

  ***~~:~:;m********!***;:*~i~:~~********l***~:~;~:~:********l***~:~;~:~:********i***~~**g:::***********l***~*:~~~:~~********l***~~*.g:::***********l***~:~!~:~~********

Pm-148 j 7.17E-09 i 1.19E-09 j 5.99E-10 \ No Data j 2.25E-09 ! No Data ! 9.35E-05 Pm-151 J.

  ...Pm-1.49 ..............\...1 _.52E-09 ........\.. 2.-.1.5E-1.0 ........\...8. 78E-1.1 .........L.No. Data...........L 4 ..06E-1.0 ...... No ._Data...........\.. 4.03E-05 ........

6.97E-10 ! 1.17E-10 : 5.91E-11 i No Data i 2.09E-10 ! No Data i 3.22E-05 Sm-151 ! 6.90E-08 j 1.19E-08 j 2.85E-09 j No Data j 1.33E-08 No Data j 5.25E-06 i Sm-153 ! 8.57E-10 ! 7.15E-10 i 5.22E-11 ! No Data ! 2.31E-10 i No Data i 2.SSE-05 Eu-152 i 1.95E-07 i 4.44E-08 i 3.90E-08 i No Data i 2.75E-07 i No Data i 2.56E-05 Eu-154 j 6.15E-07 ! 7.56E-08 j 5.38E-08 j No Data ! 3.62E-07 j No Data ! 5.48E-05 Eu-155 j 8.60E-08 j 1.22E-08 i 7.87E-09 i No Data j 5.63E-08 j No Data j 9.60E-06 8

  ***~~:~~~****************l**1:~~~:~~********i***~*~~E;t~ ********l***~:;~~:~:********l***~~*.g:!:***********i**~:~~~:~~********l***~~**g:::***********l**~:;~~:~~********

Ho-166m i 2.70E-07 j 8.43E-08 j 6.40E-08 j No Data i 1.26E-07 ! No Data j 2.56E-05 W-181 j 9.91E-09 j 3.23E-09 j 3.46E-10 j No Data j No Data j No Data j 3.68E-07 W-185 j 4.05E-07 j 1.35E-07 j 1.42E-08 j No Data j No Data j No Data j 1.56E-05 W-187 ! 1.03E-07 j 8.61E-08 j 3.01E-08 i No Data i No Data j No Data j 2.82E-05 Pb-210 j 1.53E-02 i 4.37E-03 j 5.44E-04 j No Data j 1.23E-02 j No Data j 2.24E-06 Bi-210 j 4.61 E-07 j 3.18E-06 i 2.64E-07 j No Data j 3.83E-05 j No Data j 4.75E-05 Po-210 j 3.56E-04 j 7 .56E-04 j 8.59E-05 j No Data j 2.52E-03 j No Data j 6.36E-05 Ra-223 i 4.97E-03 ! 7.65E-06 j 9.94E-04 j No Data j 2.17E-04 j No Data ! 3.21E-04 Ra-224 j 1.61 E-03 j 3.90E-06 j 3.23E-04 j No Data j 1.1 OE-04 j No Data j 3.40E-04 Ra-225 j 6.56E-03 i 7.78E-06 j 1.31 E-03 j No Data j 2.21 E-04 j No Data j 3.06E-04 Ra-226 \ 3.02E-01 j 5.74E-06 j 2.20E-01 ! No Data j 1.63E-04 j No Data j 3.32E-04 Ra-228 j 1.12E-01 l 3.12E-06 j 1.21E-01 j No Data j 8.83E-05 j No Data j 5.64E-05 1 ( ) Data presented in this Table are from Reference 9. A-29 203

PNPS-ODCM Rev. 11 TABLE A-15 (continued) INGESTION DOSE FACTORS FOR ADULT< 1> mrem/pCi Ingested

                            !                       !                     I Total                :                     :                      '                      !

Nuclide ! Bone l Liver l Body / Thyroid l Kidney ! Lung i GI-LLI Ac-225 ! 4.40E-06 ! 6.06E-06 ! 2.96E-07 ! No Data ! 6.90E-07 ! No Data ! 4.07E-04

**~~:~~; ................ j...   ~-:~;~:~~ ........ j.. ~:::~:~i . . . . j...1:~;~:~i** . ***i***~~--g:!:********. *[ . *~:~~~:~~ . . . ,.[***~~--g:!:***********!**-~::~~:~!*****. .

Th-228 j 4.96E-04 j 8.40E-06 j 1.68E-05 j No Data j 4.67E-05 j No Data j 5.63E-04 Th-229 j 1.36E-02 j 3.89E-04 j 2.25E-04 j No Data j 1.88E-03 j No Data j 7.81 E-05 Th-230 j 2.06E-03 j 1.17E-04 j 5.70E-05 j No Data j 5.65E-04 j No Data j 6.02E-05 Th-232 j 2.30E-03 j 1.00E-04 j 1.50E-06 j No Data j 4.82E-04 j No Data j 5.12E-05 Th-234 j 8.01E-08 j 4.71E-09 j 2.31E-09 j No Data j 2.67E-08 j No Data j 1.13E-04

 ...Pa-231............. ....i .. 4 ..1OE-03 ........i ...1.-54E-04 ...... J.                     i. .

1_.59E-04 ........ No __Data ...........f...8.64E-04 ........i ...No ..Data...........iJ._17E-05 ........ Pa-233 ! 5.26E-09 ! 1.06E-09 ! 9.12E-10 ! No Data ! 3.99E-09 ! No Data ! 1.64E-05 U-232 j 4.13E-03 j No Data j 2.95E-04 j No Data j 4.47E-04 j No Data j 6.78E-05 U-233 j 8.71 E-04 j No Data j 5.28E-05 j No Data j 2.03E-04 j No Data j 6.27E-05 U-234 j 8.36E-04 j No Data j 5.17E-05 j No Data j 1.99E-04 j No Data j 6.14E-05 U-235 j 8.01 E-04 j No Data j 4.86E-05 j No Data j 1.87E-04 i No Data j 7.81 E-05 U-236 j 8.01 E-04 j No Data j 4.96E-05 j No Data j 1.91 E-04 j No Data j 5.76E-05 U-237 j 5.52E-08 j No Data j 1.47E-08 j No Data j 2.27E-07 j No Data j 1.94E-05 U-238 j 7.67E-04 j No Data j 4.54E-05 j No Data j 1.75E-04 j No Data j 5.50E-05

~~:~;~_:::::::::::::::l:::~::;~~:~~::::::::l::*~:~~~:~~::::::::l:::;:~~~:~~::::::::l:::~~:-g:~:.::::::::::l::~:~;~:~:::::::::l:::~~:*g:~::::::::::::I::*~:~~~:~~::::::::

Np-239 ! 1.19E-09 ! 1.17E-10 ! 6.45E-11 ! No Data ! 3.65E-10 ! No Data ! 2.40E-05

 ... Pu-238................i...6._30E-04 ........iJ. 98E-05 ........ i...1: 71. E-05 ........i ...No ,,Oata........... i..-7 ._32E-05 ........i...No __Data ...........iJ .30E-05 ........

Pu-239 ! 7.25E-04 ! 8.71 E-05 ! 1.91 E-05 ! No Data ! 8.11 E-05 ! No Data ! 6.66E-05 Pu-240 j 7.24E-04 j 8.70E-05 j 1.91E-05 j No Data j 8.10E-05 j No Data j 6.78E-05 Pu-241 j 1.57E-05 j 7.45E-07 j 3.32E-07 j No Data j 1.53E-06 j No Data j 1.40E-06 Pu-242 j 6.72E-04 j 8.39E-05 j 1.84E-05 j No Data j 7.81 E-05 j No Data j 6.53E-05 Pu-244 j 7.84E-04 j 9.61 E-05 j 2.11 E-05 j No Data j 8.95E-05 j No Data j 9. 73E-05 Am-241 j 7.55E-04 j 7 .05E-04 j 5.41 E-05 j No Data j 4.07E-04 j No Data j 7.42E-05 Am-242m j 7.61 E-04 j 6.63E-04 j 5.43E-05 j No Data j 4.05E-04 j No Data j 9.34E-05 Am-243 j 7.54E-04 j 6.90E-04 j 5.30E-05 j No Data j 3.99E-04 j No Data j 8.70E-05 Cm-242 j 2.06E-05 j 2.19E-05 j 1.37E-06 j No Data j 6.22E-06 j No Data j 7.92E-05 Cm-243 j 5.99E-04 j 5.49E-04 j 3.75E-05 j No Data j 1.75E-04 j No Data j 7.81 E-05 Cm-244 j 4.56E-04 j 4.27E-04 j 2.87E-05 j No Data j 1.34E-04 j No Data j 7.55E-05 Cm-245 j 9.38E-04 j 8.17E-04 j 5.76E-05 i No Data j 2.69E-04 j No Data j 7.04E-05 Cm-246 j 9.30E-04 j 8.16E-04 j 5.75E-05 j No Data j 2.68E-04 j No Data j 6.91 E-05

i. . i. . !.

 ...cm-24 7 ............. 9 ._07E-04 ........i ...8 ..04E-04 ........ 5.67E-05 ........ _No ..Data...........! .. 2. 64E-04 ........i ...No __Data ...........i ...9. 09E-05 ........

Cm-248 ! 7.54E-03 ! 6.63E-03 ! 4.67E-04 ! No Data ! 2.18E-03 ! No Data ! 1.47E-03 Cf-252 i 2.61 E-04 i No Data i 6.29E-06 i No Data i No Data i No Data i 2.88E-04 1 <> Data presented in this Table are from Reference 9. A-30 204

PNPS-ODCM Rev. 11 TABLE A-16 INGESTION DOSE FACTORS FOR TEEN( 1l mrem/pCi Ingested

                             ! *                    ,                      I   Total             !                     :                    !                     1 Nuclide                  I    Bone              l Liver                 l Body               l Thyroid             l Kidney              / Lung                i GI-LLI H-3                       i No Data : 6.04E-08                          i 6.04E-08           : 6.04E-08            i 6.04E-08            : 6.04E-08            : 6.04E-08 Be-10                     j 4.48E-06            i    6.94E-07           i   1.13E-07          i   No Data           j 5.30E-07           i   No Data           i   2.84E-05 C-14                      j 4.06E-06 j 8.12E-07                         i 8.12E-07            j 8.12E-07            j 8.12E-07           j 8.12E-07            j 8.12E-07 N-13                      j 1.15E-08            i    1.15E-08           j 1.15E-08            j 1.15E-08            j 1.15E-08           i   1.15E-08          j 1.15E-08 F-18                      i   8.64E-07          i    No Data            i   9.47E-08         i    No Data          i No Data i               No Data           i   7.78E-08 Na-22                     j 2.34E-05             !   2.34E-05           j 2.34E-05            j 2.34E-05            i 2.34E-05 i             2.34E-05          i   2.34E-05 4
 *--~~;~ ................... 1.. -~:~~~:~~ ........ j.. ~:~~~:~~  ........ 1.. ~:~~~:~~ ........ j.. ~-i~E;t~B........ j.. ~-i~E;t~6........1...~-i~E;t~B ........1.. ~:-~~~:~~ ........

Ca-41 i 1.97E-04 i No Data i 2.13E-05 i No Data i No Data i No Data i 1.95E-07 Sc-46 i 7.24E-09 i 1.41E-08 j 4.18E-09 j No Data i 1.35E-08 j No Data i 4.80E-05 Cr-51 j No Data j No Data i 3.60E-09 j 2.00E-09 i 7.89E-10 i 5.14E-09 j 6.05E-07 Mn-54 j No Data j 5.90E-06 j 1.17E-06 j No Data j 1. 76E-06 j No Data j 1.21 E-05 Mn-56 j No Data j 1.58E-07 j 2.81 E-08 j No Data j 2.00E-07 j No Data j 1.04E-05 Fe-55 i 3.78E-06 j 2.68E-06 i 6.25E-07 i No Data i No Data j 1.70E-06 i 1.16E-06 Fe-59 j 5.87E-06 i 1.37E-05 j 5.29E-06 i No Data j No Data i 4.32E-06 i 3.24E-05 Co-57 j No Data i 2.38E-07 i 3.99E-07 i No Data j No Data i No Data i 4.44E-06 Co-58 i No Data i 9.72E-07 i 2.24E-06 i No Data i No Data i No Data i 1.34E-05 Co-60 i No Data i 2.81E-06 i 6.33E-06 i No Data i No Data i No Data i 3.66E-05 Ni-59 ! 1.32E-05 \ 4.66E-06 \ 2.24E-06 \ No Data \ No Data i No Data \ 7.31 E-07 Ni-63 ! 1.77E-04 j 1.25E-05 i 6.00E-06 j No Data i No Data j No Data i 1.99E-06 Ni-65 j 7.49E-07 j 9.57E-08 j 4.36E-08 j No Data i No Data i No Data j 5.19E-06 Cu-64 j No Data i 1.15E-07 j 5.41 E-08 j No Data j 2.91 E-07 j No Data j 8.92E-06 Zn-65 i 5.76E-06 j 2.00E~05 i 9.33E-06 i No Data i 1.28E-05 j No Data i 8.47E-06 Zn-69m i 2.40E-07 j 5.66E-07 i 5.19E-08 i No Data i 3.44E-07 i No Data j 3.11 E-05 Zn-69 i 1.47E-08 j 2.80E-08 j 1.96E-09 j No Data j 1.83E-08 j No Data i 5.16E-08 Se-79 ! No Data ! 3.73E-06 ! 6.27E-07 \ No Data j 6.50E-06 ! No Data ! 5.70E-07 Br-82 i No Data i No Data i 3.04E-06 i No Data i No Data i No Data i No Data Br-83 i No Data i No Data i 5.74E-08 i No Data i No Data i No Data i No Data Br-84 i No Data i No Data i 7.22E-08 i No Data i No Data i No Data i No Data Br-85 j No Data i No Data j 3.05E-09 j No Data j No Data i No Data i No Data Rb-86 i No Data i 2.98E-05 i 1.40E-05 i No Data i No Data i No Data i 4.41 E-06 Rb-87 i No Data i 1. 75E-05 i 6.11 E-06 i No Data i No Data i No Data i 6.11 E-07 Rb-88 i No Data i 8.52E-08 i 4.54E-08 i No Data i No Data i No Data i 7.30E-15 Rb-89 i No Data i 5.50E-08 i 3.89E-08 i No Data i No Data i No Data i 8.43E-17 Sr-89 i 4.40E-04 i No Data i 1.26E-05 i No Data i No Data j No Data i 5.24E-05 Sr-90 i 1.02E-02 i No Data i 2.04E-04 i No Data i No Data j No Data i 2.33E-04 Sr-91 j 8.07E-06 i No Data i 3.21E-07 ! No Data ! No Data ! No Data i 3.66E-05 Sr-92 ! 3.05E-06 i No Data i 1.30E-07 i No Data i No Data j No Data j 7.77E-05 Y-90 i 1.37E-08 i No Data i 3.69E-10 i No Data j No Data i No Data i 1.13E-04 Y-91m i 1.29E-10 i No Data i 4.93E-12 i No Data i No Data i No Data i 6.09E-09 Y-91 j 2.01 E-07 i No Data i 5.39E-09 i No Data i No Data i No Data i 8.24E-05 Y-92 i 1.21 E-09 i No Data i 3.50E-11 i No Data i No Data i No Data i 3.32E-05 Y-93 i 3.83E-09 i No Data i 1.05E-10 i No Data i No Data i No Data i 1.17E-04 1 ( l Data presented in this Table are from Reference 9. A-31 205

PNPS-ODCM Rev. 11 TABLE A-16 (continued) INGESTION DOSE FACTORS FOR TEEN< 1> mrem/pCi Ingested

i ! Total ! ! =

I l Nuclide i Bone i Liver i Body i Thyroid i Kidney i Lung GI-LLI Zr-93 1 5.53E-08 1 2.73E-09 1 1.49E-09 1 No Data : 9.65E-09 1 No Data : 2.58E-06 Zr-95 i 4.12E-08 i 1.30E-08 i 8.94E-09 i No Data i 1.91 E-08 ! No Data i 3.00E-05 Zr-97 ! 2.37E-09 ! 4.69E-10 2.16E-10 ! No Data i i 7.11E-10 i No Data i 1.27E-04 Nb-93m ! 3.44E-08 ! 1.13E-08 ! 2.83E-09 ! No Data i 1.32E-08 i No Data i 4.0?E-06 Nb-95 j 8.22E-09 j 4.56E-09 j 2.51 E-09 j No Data j 4.42E-09 j No Data i 1.95E-05 Nb-97 ! 7.37E-11 ! 1.83E-11 ! 6.68E-12 No Data i i 2.14E-11 i No Data i 4.37E-07 Mo-93 ! No Data i 1.06E-05 ! 2.90E-07 i No Data ! 3.04E-06 ! No Data i 1.29E-06 Mo-99 i No Data i 6.03E-06 i 1.15E-06 i No Data i 1.38E-05 i No Data i 1.08E-05 Tc-99m i 3.32E-10 i 9.26E-10 i 1.20E-08 i No Data i 1.38E-08 i 5.14E-10 i 6.08E-07 Tc-99 i 1.79E-07 i 2.63E-07 i 7.17E-08 ! No Data i 3.34E-06 i 2.72E-08 i 6.44E-06 Tc-101 i 3.60E-10 i 5.12E-10 i 5.03E-09 i No Data i 9.26E-09 i 3.12E-10 i 8.75E-17 Ru-103 j 2.55E-07 \ No Data i 1.09E-07 i No Data i 8.99E-07 i No Data \ 2.13E-05 Ru-105 ! 2.18E-08 i No Data ! 8.46E-09 ! No Data ! 2.75E-07 ! No Data ! 1.76E-05 Ru-106 ! 3.92E-06 No Data i i 4.94E-07 i No Data i 7.56E-06 \ No Data ! 1.88E-04 Rh-105 i 1.73E-07 ! 1.25E-07 i 8.20E-08 i No Data i 5.31 E-07 i No Data i 1.59E-05 Pd-107 i No Data i 2.08E-07 ! 1.34E-08 i No Data i 1.88E-06 ! No Data i 9.66E-07 Pd-109 i No Data i 2.51E-07 i 5.?0E-08 ! No Data i 1.45E-06 i No Data ! 2.53E-05

i. . i. . l. . i. . l. .

.. Ag-1 _1_ Om .......... 2._05E-07 ........i ...1: 94E-07 ........ 1_._18E-07 ........ No __Data........... 3. ?OE-07 ........i ... No __Data ........... 5.45E-05 ........

Ag-111 1 8.29E-08 \ 3.44E-08 : 1.73E-08 \ No Data l 1.12E-07 l No Data l 4.80E-05 Cd-113m i No Data i 4.51 E-06 i 1.45E-07 i No Data i 4.99E-06 i No Data i 2.71 E-05 Cd-11 Sm i No Data i 2.60E-06 i 8.39E-08 i No Data i 2.08E-06 i No Data i 8.23E-05 Sn-123 ! 4.44E-05 i 7.29E-07 ! 1.08E-06 ! 5.84E-07 ! No Data ! No Data i 6.71E-05 Sn-125 i 1.19E-05 i 2.37E-07 i 5.37E-07 ! 1.86E-07 ! No Data i No Data ! 1.12E-04 Sn-126 i 1.16E-04 ! 2.16E-06 ! 3.30E-06 i 5.69E-07 i No Data i No Data i 2.58E-05 Sb-124 i 3.87E-06 i 7.13E-08 ! 1.51E-06 ! 8.78E-09 i No Data i 3.38E-06 ! 7.80E-05 Sb-125 i 2.48E-06 i 2.71E-08 \ 5.80E-07 j 2.37E-09 i No Data i 2.18E-06 \ 1.93E-05 Sb-126 i

                         ! 1.59E-06 3.25E-08 ! 5.71E-07 ! 8.99E-09 ! No Data ! 1.14E-06 9.41E-05                                                          i Sb-127                i    3.63E-07      !    7.76E-09 i 1.37E-07                   !   4.08E-09         !    No Data       !     2.47E-07             i    6.16E-05 Te-125m               i    3.83E-06 ! 1.38E-06 ! 5.12E-07                           i    1.0?E-06        i    No Data       ! No Data ! 1.13E-05 Te-127m               \ 9.67E-06         i    3.43E-06          i    1.15E-06       i    2.30E-06         i   3.92E-05      !     No Data              !    2.41E-05 Te-127                i    1.58E-07 ! 5.60E-08 ! 3.40E-08                           i    1.09E-07         i   6.40E-07 ! No Data                       ! 1.22E-05 Te-129m               !    1.63E-05      i    6.05E-06          i    2.58E-06       i    5.26E-06         i   6.82E-05      i     No Data              i    6.12E-05 Te-129                !    4.48E-08 \ 1.67E-08 \ 1.09E-08                           !    3.20E-08 \ 1.88E-07 \ No Data                                 \ 2.45E-07 Te-131m               i    2.44E-06      i    1.17E-06          i    9.76E-07       i    1.76E-06         i   1.22E-05      i     No Data              i    9.39E-05 Te-131                i    2.79E-08      i    1.15E-08          i    8.72E-09       i    2.15E-08         i   1.22E-07      i     No Data              i    2.29E-09 Te-132                i    3.49E-06      i    2.21E-06          i    2.08E-06       i    2.33E-06         i                 !

2.12E-05 . No Data i 7.00E-05 Te-133m i 6.44E-08 i 3.66E-08 i 3.56E-08 \ 5.11E-08 i 3.62E-07 i No Data i 1.48E-07 Te-134 i 4.47E-08 i 2.87E-08 i 3.00E-08 i 3.67E-08 i 2.74E-07 i No Data i 1.66E-09 1-129 ! 4.66E-06 i 3.92E-06 ! 6.54E-06 ! 4.77E-03 i 7.01 E-06 i No Data ! 4.57E-07 1-130 i 1.03E-06 i 2.98E-06 i 1.19E-06 i 2.43E-04 j 4.59E-06 i No Data i 2.29E-06 1-131 i 5.85E-06 ! 8.19E-06 i 4.40E-06 i 2.39E-03 ! 1.41E-05 i No Data i 1.62E-06 1-132 ! 2.79E-07 ! 7.30E-07 j 2.62E-07 i 2.46E-05 i 1.15E-06 i No Data i 3.18E-07 1-133 i 2.01E-06 ! 3.41E-06 i 1.04E-06 i 4.76E-04 i 5.98E-06 i No Data i 2.58E-06 1-134 i 1.46E-07 i 3.87E-07 \ 1.39E-07 i 6.45E-06 \ 6.1 OE-07 i No Data i 5.1 OE-09 1-135 l 6.10E-07 j 1.57E-06 j 5.82E-07 j 1.01E-04 j 2.48E-06 j No Data j 1.74E-06 1 <> Data presented in this Table are from Reference 9. A-32 206

PNPS-ODCM Rev. 11 TABLE A-16 (continued) INGESTION DOSE FACTORS FOR TEEN( 1> mrem/pCi Ingested

' i Total : : i

Nuclide i Bone i Liver i Body i Thyroid i Kidney i Lung ! GI-LU Cs-134m i 2.94E-08 i 6.09E-08 i 3.13E-08 1 No Data 1 3.39E-08 i 5.95E-09 1 4.05E-08 Cs-134 j 8.37E-05 i 1.97E-04 i 9.14E-05 j No Data j 6.26E-05 j 2.39E-05 i 2.45E-06 Cs-135 \ 2.78E-05 \ 2.55E-05 \ 5.96E-06 j No Data j 9.73E-06 j 3.52E-06 j 4.46E-07 Cs-136 ! 8.59E-06 i 3.38E-05 j 2.27E-05 j No Data j 1.84E-05 j 2.90E-06 j 2.72E-06 Cs-137 j 1.12E-04 i 1.49E-04 i 5.19E-05 j No Data j 5.07E-05 \ 1.97E-05 j 2.12E-06 Cs-138 ! 7. 76E-08 i 1.49E-07 i 7.45E-08 j No Data j 1.1 OE-07 j 1.28E-08 j 6. 76E-11 Cs-139 j 4.87E-08 j 7.17E-08 j 2.63E-08 j No Data j 5.79E-08 j 6.34E-09 j 3.33E-23 Ba-139 j 1.39E-07 j 9.78E-11 i 4.05E-09 j No Data j 9.22E-11 j 6.74E-11 j 1.24E-06 Ba-140 j 2.84E-05 j 3.48E-08 j 1.83E-06 j No Data j 1.18E-08 j 2.34E-08 j 4.38E-05 i.

 ... Ba-141.................L.6. 71. E-08 ........L.s ..o.1. E-1.1 ......... 2.24E-09 ........i.. No ..Oata........... i.. 4.65E-1.1 ..... ....i ...3.43E-1.1 ......... i...1_.43E-1.3 ........

Ba-142 i 2.99E-08 i 2.99E-11 i 1.84E-09 i No Data i 2.53E-11 : 1.99E-11 : 9.18E-20 La-140 i 3.48E-09 j 1.71E-09 j 4.55E-10 j No Data j No Data j No Data j 9.82E-05 La-141 j 4.55E-10 j 1.40E-10 j 2.31E-11 j No Data j No Data j No Data j 2.48E-05 La-142 \1.79E-10 \7.95E-11 i1.98E-11 iNoData iNoData \NoData i2.42E-06 Ce-141 j 1.33E-08 i 8.88E-09 j 1.02E-09 i No Data j 4.18E-09 i No Data j 2.54E-05 Ce-143 i 2.35E-09 i 1.71E-06 j 1.91E-10 ! No Data j 7.67E-10 j No Data j 5.14E-05 Ce-144 ! 6.96E-07 j 2.88E-07 j 3.74E-08 ! No Data \ 1.72E-07 j No Data j 1.75E-04 Pr-143 ! 1.31E-08 j 5.23E-09 j 6.52E-10 j No Data j 3.04E-09 j No Data j 4.31E-05 Pr-144 i 4.30E-11 i 1.76E-11 \ 2.18E-12 j No Data j 1.01E-11 j No Data j 4.74E-14 Nd-147 ! 9.38E-09 i 1.02E-08 i 6.11E-10 ! No Data i 5.99E-09 j No Data j 3.68E-05 Pm-147 j 1.05E-07 j 9.96E-09 j 4.06E-09 j No Data j 1.90E-08 j No Data j 9.47E-06 Pm-148m j 4.14E-08 j 1.05E-08 j 8.21E-09 i No Data i 1.59E-08 ! No Data j 6.61E-05 Pm-148 j 1.02E-08 j 1.66E-09 j 8.36E-10 j No Data j 3.00E-09 j No Data j 9.90E-05 Pm-149 j 2.17E-09 j 3.05E-10 j 1.25E-10 j No Data j 5.81E-10 \ No Data \ 4.49E-05 Pm-151 j 9.87E-10 j 1.63E-10 j 8.25E-11 j No Data j 2.93E-10 i No Data j 3.66E-05 Sm-151 i 8.73E-08 j 1.68E-08 j 3.94E-09 j No Data j 1.84E-08 i No Data j 5.70E-06 Sm-153 i 1.22E-09 j 1.01 E-09 j 7.43E-11 i No Data j 3.30E-10 i No Data i 2.85E-05 Eu-152 j 2.45E-07 j 5.90E-08 j 5.20E-08 j No Data j 2.74E-07 j No Data j 2.17E-05 Eu-154 j 7.91 E-07 j 1.02E-07 i 7.19E-08 j No Data j 4.56E-07 j No Data j 5.39E-05 Eu-155 j 1.74E-07 j 1.68E-08 j 1.04E-08 j No Data j 6.57E-08 j No Data j 9.63E-05 Eu-156 j 1.92E-08 j 1.44E-08 j 2.35E-09 j No Data j 9.69E-09 j No Data j 7.36E-05 Tb-160 j 6.47E-08 i No Data i 8.07E-09 j No Data j 2.56E-08 j No Data i 4.19E-05 Ho-166m j 3.57E-07 j 1.10E-07 j 7.96E-08 j No Data j 1.61E-07 j No Data i 2.71E-05 W-181 j 1.42E-08 j 4.58E-09 j 4.79E-10 j No Data i No Data j No Data i 3.90E-07 W-185 j 5.79E-07 j 1.91 E-07 j 2.02E-08 j No Data j No Data j No Data j 1.65E-05 W-187 i 1.46E-07 i 1.19E-07 j 4.17E-08 i No Data i No Data j No Data ! 3.22E-05 Pb-210 j 1.81E-02 ! 5.44E-03 j 7.01E-04 ! No Data j 1.72E-02 j No Data ! 2.37E-06 Bi-210 j 6.59E-07 j 4.51 E-06 j 3. 77E-07 j No Data j 5.48E-05 j No Data j 5.15E-05 Po-210 j 5.09E-04 j 1.07E-03 j 1.23E-04 j No Data j 3.60E-03 j No Data j 6.75E-05 Ra-223 j 7.11 E-03 j 1.08E-05 j 1.42E-03 j No Data j 3.1 OE-04 j No Data j 3.43E-04 Ra-224 j 2.31 E-03 i 5.52E-06 i 4.61 E-04 j No Data j 1.58E-04 j No Data j 3.71 E-04 Ra-225 j 9.37E-03 j 1.1 OE-05 j 1.87E-03 ! No Data j 3.15E-04 ! No Data j 3.27E-04 Ra-226 j 3.22E-01 j 8.13E-06 j 2.39E-01 j No Data j 2.32E-04 j No Data j 3.51 E-04 Ra-228 j 1.37E-01 j 4.41 E-06 j 1.51 E-01 j No Data j 1.26E-04 j No Data j 5.98E-05 1 ( > Data presented in this Table are from Reference 9. A-33 207

PNPS-ODCM Rev. 11 TABLE A-16 (continued) INGESTION DOSE FACTORS FOR TEEN <1l mrem/pCi Ingested

' : Total i ' : :

Nuclide : Bone j Liver J Body I Thyroid I Kidney : Lung : GI-LLI Ac-225 I 6.29E-06 1 8.59E-06 14.22E-07 I No Data I 9.85E-07 1 No Data I 4.36E-04 Ac-227 i 2.05E-03 i 3.03E-04 i 1.22E-04 i No Data i 8.81 E-05 i No Data i 8.68E-05 Th-227 i 1.96E-05 i 3.52E-07 i 5.65E-07 i No Data \ 2.01 E-06 i No Data \ 5.75E-04 Th-228 i 6.80E-04 i 1.14E-05 i 2.30E-05 i No Data i 6.41E-05 i No Data i 5.97E-04 Th-229 i 1.43E-02 i 4.11 E-04 i 2.37E-04 \ No Data i 1.99E-03 i No Data i 8.28E-05 Th-230 i 2.16E-03 i 1.23E-04 i 6.00E-05 \ No Data \ 5.99E-04 \ No Data \ 6.38E-05 Th-232 \ 2.42E-03 i 1.05E-04 i 1.63E-06 i No Data i 5.11 E-04 i No Data i 5.43E-05 Th-234 i 1.14E-07 i 6.68E-09 i 3.31E-09 i No Data i 3.81E-08 i No Data i 1.21E-04 Pa-231 i 4.31 E-03 i 1.62E-04 i 1.68E-04 i No Data i 9.10E-04 \ No Data \ 7.60E-05 Pa-233 i 7.33E-09 i 1.41E-09 i 1.26E-09 i No Data i 5.32E-09 i No Data i 1.61E-05 U-232 i 5.89E-03 i No Data i 4.21E-04 i No Data i 6.38E-04 i No Data i 7.19E-05 U-233 i 1.24E-03 i No Data i 7.54E-05 i No Data i 2.90E-04 i No Data i 6.65E-05 U-234 i 1.19E-03 i No Data i 7.39E-05 i No Data i 2.85E-04 i No Data i 6.51E-05 U-235 i 1.14E-03 i No Data i 6.94E-05 j No Data i 2.67E-04 ! No Data \ 8.28E-05 U-236 i 1.14E-03 i No Data i 7.09E-05 i No Data i 2.73E-04 f No Data i 6.11E-05

 *--~~~;~ *******************;***~: ~~~~~~ ********;***~~ . g:~:-**********i** ~:~~~~~~ ********;***~~ . g:~:-**********i** ;:;6~~~~********t***~~ . g:~:-**********l** ;:-~;~~~;. . . ..

i. .

 ...Np-237 ............... 1_._33E-03 ........i ...9 .55E-05 ........       i. .5. 85E-05 ........i ...No ..Oata...........i . 4. 33E-04 ........i. .No ..Oata...........i ...8.4_1. E-05 ........

Np-238 : 1.95E-08 : 5.22E-10 : 3.04E-10 : No Data : 1.79E-09 : No Data : 3.83E-05

 ...Np-239................i ... 1.-76E-09 ........i ... 1_.66E-1.o ........ i. .9.22E-1.1 .........i. .No __Data...........i . .5.2.1.E-1.o ........i ...No__Data...........i ...2.67E-05 ........

Pu-238 I 6.70E-04 I 8.58E-05 I 1.82E-05 i No Data 17.80E-05 I No Data I 7.73E-05 Pu-239 i 7.65E-04 i 9.29E-05 i 2.01 E-05 i No Data i 8.57E-05 i No Data i 7.06E-05 Pu-240 i 7.64E-04 i 9.27E-05 j 2.01E-05 j No Data j 8.56E-05 i No Data i 7.19E-05 Pu-241 \ 1.75E-05 i 8.40E-07 \ 3.69E-07 \ No Data \ 1.71 E-06 i No Data \ 1.48E-06 Pu-242 i 7.09E-04 j 8.94E-05 j 1.94E-05 i No Data i 8.25E-05 j No Data i 6.92E-05 Pu-244 i 8.28E-04 i 1.02E-04 \ 2.22E-05 i No Data i 9.45E-05 i No Data i 1.03E-04 Am-241 \ 7.98E-04 i 7.53E-04 j 5.75E-05 ! No Data ! 4.31E-04 ! No Data ! 7.87E-05 Am-242m ! 8.07E-04 j 7.11 E-04 ! 5.80E-05 ! No Data ! 4.30E-04 j No Data j 9.90E-05 Am-243 i 7.96E-04 ! 7.35E-04 ! 5.62E-05 i No Data \ 4.22E-04 i No Data i 9.23E-05 Cm-242 j 2.94E-05 ! 3.1 OE-05 j 1.95E-06 j No Data j 8.89E-06 j No Data \ 8.40E-05 Cm-243 i 6.50E-04 i 6.03E-04 i 4.09E-05 i No Data \ 1.91 E-04 \ No Data i 8.28E-05 Cm-244 i 5.04E-04 i 4.77E-04 i 3.19E-05 i No Data i 1.49E-04 i No Data i 8.00E-05 Cm-245 j 9.90E-04 ! 8.71 E-04 ! 6.1 OE-05 ! No Data i 2.85E-04 j No Data j 7.46E-05 Cm-246 i 9.82E-04 \ 8.70E-04 j 6.09E-05 \ No Data j 2.84E-04 i No Data i 7.33E-05 Cm-247 j 9.57E-04 j 8.57E-04 j 6.00E-05 j No Data j 2.80E-04 j No Data j 9.63E-05 Cm-248 i 7.95E-03 j 7.06E-03 i 4.95E-04 j No Data j 2.31 E-03 i No Data i 1.55E-03 Cf-252 i 3.47E-04 i No Data i 8.37E-06 i No Data i No Data i No Data i 3.05E-04 1 <l Data presented in this Table are from Reference 9. A-34 208

PNPS-ODCM Rev. 11 TABLE A-17 INGESTION DOSE FACTORS FOR CHILD <1 ) mrem/pCi Ingested

                                      '                         i

i Total i : , :

Nuclide I Bone I Liver ! Body I Thyroid ! Kidney ! LunQ J GI-LLI

... t:!.~.~***************-*-***---....l_._No ..Oata_. ___.__...: ___ 1_._16E-07 ____ J_._1_._16E-07 ____ ....J ... 1_._16E-07_...J _ _ 1_._16E-07 ____ .... l. _ 1_._16E-07 ____ _...: ___ 1_._1_6E-07 _______ _

Be-10 : 1.35E-05 1 1.57E-06 1 3.39E-07 1 No Data 1 1.11 E-06 1 No Data I 2.75E-05 C-14 i 1.21 E-05 i 2.42E-06 i 2.42E-06 i 2.42E-06 i 2.42E-06 i 2.42E-06 i 2.42E-06 N-13 i 3.1 OE-08 j 3.1 OE-08 i 3.1 OE-08 i 3.1 OE-08 j 3.1 OE-08 i 3.1 OE-08 i 3.1 OE-08

---~~-~2*---****---*-------:--;::~~:~~--------:---~.~~E~~s--*---**i***;::~~:~;-----*--:*-*~.~~E~~s--------:---~.~~:~s*-*-**-*i--*~.~~;~5--------:--*~:~:~:~;----*---

Na-24 i 5.80E-06 i 5.80E-06 i 5.80E-06 i 5.80E-06 i 5.80E-06 i 5.80E-06 i 5.80E-06 P-32 i 8.25E-04 i 3.86E-05 i 3.18E-05 i No Data i No Data i No Data i 2.28E-05 Ca-41 i 3.47E-04 i No Data i 3.79E-05 i No Data i No Data i No Data i 1.90E-07 Sc-46 i 1.97E-08 i 2.70E-08 i 1.04E-08 i No Data i 2.39E-08 i No Data i 3.95E-05 Cr-51 i No Data j No Data i 8.90E-09 i 4.94E-09 i 1.35E-09 i 9.02E-09 i 4.72E-07 Mn-54 i No Data i 1.07E-05 i 2.85E-06 i No Data i 3.00E-06 i No Data i 8.98E-06 Mn-56 i No Data i 3.34E-07 i 7.54E-08 i No Data i 4.04E-07 i No Data i 4.84E-05 Fe-55 i 1.15E-05 i 6.1 OE-06 i 1.89E-06 i No Data i No Data i 3.45E-06 i 1.13E-06 Fe-59 i 1.65E-05 i 2.67E-05 i 1.33E-05 i No Data i No Data i 7.74E-06 i 2.78E-05 Co-57 i No Data i 4.93E-07 i 9.98E-07 i No Data i No Data i No Data i 4.04E-06 Co-58 i No Data i 1.80E-06 i 5.51 E-06 i No Data i No Data i No Data i 1.05E-05 Co-60 i No Data i 5.29E-06 i 1.56E-05 i No Data i No Data i No Data i 2.93E-05 Ni-59 i 4.02E-05 i 1.07E-05 i 6_82E-06 i No Data i No Data i No Data i 7.10E-07 Ni-63 i 5.38E-04 i 2.88E-05 i 1.83E-05 i No Data i No Data i No Data i 1.94E-06 Ni-65 i 2.22E-06 i 2.09E-07 i 1.22E-07 i No Data i No Data i No Data j 2.56E-05 Cu-64 i No Data i 2.45E-07 i 1.48E-07 i No Data i 5. 92E-07 i No Data i 1.15E-05 Zn-65 i 1.37E-05 i 3.65E-05 i 2.27E-05 i No Data i 2.30E-05 i No Data j 6.41 E-06 Zn-69m i 7.10E-07 i 1.21E-06 i 1.43E-07 i No Data i 7.03E-07 i No Data i 3.94E-05 Zn-69 i 4.38E-08 i 6.33E-08 i 5.85E-09 i No Data i 3.84E-08 i No Data i 3_99E-06 Se-79 i No Data i 8.43E-06 i 1.87E-06 i No Data i 1.37E-05 i No Data i 5.53E-07 ___ Br-82**-**-*--*-*------*-*i ___ No __Data ____ ... ___ _i ___ No __Data ..--**-****iJ.55E-06 ________ i.. _No__Data ..... _.....i._.No_Data .. _____ .___ i_._No __Data_*****-**J ..No __Data ___ .. _____ _ Br-83 : No Data : No Data I 1.71 E-07 : No Data : No Data I No Data : No Data Br-84 i No Data i No Data i 1.98E-07 i No Data i No Data i No Data i No Data ___ B_r-85 ...... _______________ j___No __Data ___________ j___No __Data******--***i ...9 ..12E-09 *-***-*-i ._.No __Data_ ..... _._._i __.No _Data*----*-***-i .._No __Data_****---***j___No __Data_. ________ _ Rb-86 I No Data I 6.70E-05 I 4.12E-05 I No Data I No Data I No Data 1 4.31E-06 Rb-87 i No Data i 3.95E-05 i 1.83E-05 i No Data i No Data i No Data i 5.92E-07 Rb-88 i No Data i 1 _90E-07 i 1.32E-07 i No Data i No Data i No Data i 9.32E-09 Rb-89 i No Data i 1.17E-07 i 1.04E-07 i No Data i No Data i No Data i 1.02E-09 Sr-89 i 1:32E-03 i No Data i 3.77E-05 i No Data i No Data i No Data i 5.11E-05 ___Sr-90 -***---***--******-**i._ 2.56E-02**--**..i_..No ..Oata__________ .! ___5._15E-04 .......-! ...No __Data _________) ___No __Data_****---***i ...No. Data*-******-**!_._2_29E-04_.. ____ _ Sr-91 : 2.40E-05 : No Data : 9.06E-07 : No Data : No Data i No Data : 5.30E-05 Sr-92 i 9.03E-06 i No Data i 3.62E-07 i No Data i No Data i No Data i 1.71 E-04 Y-90 j 4.11 E-08 l No Data i 1.1 OE-09 i No Data l No Data j No Data i 1.17E-04 Y-91m i 3.82E-10 i No Data \ 1.39E-11 i No Data i No Data i No Data i 7.48E-07 Y-91 i 6.02E-07 i No Data i 1.61 E-08 i No Data i No Data i No Data i 8.02E-05 Y-92 i 3.60E-09 i No Data i 1.03E-10 i No Data i No Data i No Data i 1.04E-04 Y-93 i 1.14E-08 i No Data j 3.13E-10 i No Data j No Data j No Data j 1.70E-04 1 <) Data presented in this Table are from Reference 9. A-35 209

PNPS-ODCM Rev. 11 TABLE A-17 (continued) 1 INGESTION DOSE FACTORS FOR CHILD ' > mrem/pCi Ingested

; ! Total 1 i :

Nuclide I Bone ! Liver ! Body ! Thyroid I Kidney ! Lung ! GI-LLI Zr-93 l 1.67E-07 l 6.25E-09 l 4.45E-09 l No Data l 2.42E-08 l No Data l 2.37E-06

 * ~~f:~m= !*ii ~~~=iJ*~ii~~i
                           =i *

~~~;~:::::::::::::::::::!:: ~*~ ~E;t~O: : : : !: ;:!~~:~~

=i:i*~!i~~~ j:~i:~;f =i:i*i i~~i:=!:~i:~; :=:lJ*!ii~i =

l:::~::;~:~;::::::::I:::~~: g:!: : : : : : I: :: ;~~:~~ ::::::::!:::~~ : g:!: : : : : : I: :~::;~~:~~: : : :

Mo-99 l No Data l 1.33E-05 l 3.29E-06 l No Data l 2.84E-05 l No Data l 1.1 OE-05 Tc-99m j 9.23E-10 j 1.81 E-09 j 3.00E-08 i No Data j 2.63E-08 i 9.19E-10 i 1.03E-06

~~:~~ 1: : : : : : : : :I: :~: ~~~:~~::::::::I:::~::~~~:~~ ~:1~~:~;::::::::I:::~~::g:!::::::::::::I::;: ~~~:~~::::::::I:::~:~;~:~~::::::::!:::~:~~~:~~: : : :

Ru-103 l 7.31E-07 l No Data

1::

l 2.81E-07 l No Data l 1.84E-06 l No Data l 1.89E-05 Ru-105 j 6.45E-08 i No Data i 2.34E-08 i No Data j 5.67E-07 j No Data i 4.21E-05

  ... Ru-1.06 ............... i. . 1.-.1 ?E-05 ........i ... No ..Oata...........i ... 1_.46E-06 ........ i. . No ..Oata...........i ...1_. 58E-05 ........i ... No ..Oata.......... .i . .1_. 82E-04........

Rh-105 l 5.14E-07 l 2. 76E-07 l 2.36E-07 l No Data l 1.1 OE-06 l No Data l 1. 71 E-05 Pd-107 j No Data ! 4.72E-07 i 4.01E-08 i No Data i 3.95E-06 i No Data i 9.37E-07

~~: ~ ~~m : : : : : i: :~.~~E~~7:: : : :I: :~:~~~:~;::::::::!:::~:~~~:~;: : : : !: :~~ : g:~: : : : : : I: .~: ~:~:~~ : : : :i!: :~~::g:!::::::::::::i::.~::;~~:~~: : : :

Ag-111 \ 2.48E-07 \ 7.76E-08 l 5.12E-08 l No Data \ 2.34E-07 No Data l 4.75E-05

i. . i. . i. .

  ...Cd-1.1.3m.......... No ._Data...........i ... 1.-.02E-05 ........ 4.34E-07 ........i ...No __Data ........... 1_.05E-05 ........i ...No ..Oata...........i .. 2.63E-05 ....... .

Cd-115m l No Data l 5.89E-06 l 2.51E-07 l No Data l 4.38E-06 l No Data l 8.01E-05 Sn-123 j 1.33E-04 i 1.65E-06 i 3.24E-06 i 1.75E-06 i No Data i No Data i 6.52E-05 Sn-125 j 3.55E-05 j 5.35E-07 j 1.59E-06 i 5.55E-07 i No Data i No Data j 1.1 OE-04

i. . i. . .i . . i. .

  ...sn-126................ 3.33E-04 ........i . 4 ..1.5E-06 ........ 9.46E-06 ....... 1.-.14E-06 ........ No. Data...........i ... No ..Oata........... 2.50E-05 ........             i.
  ...Sb-124................! ... 1.-.11.E-05 ........! ... 1_.44E-07 ........ !. .3.89E-06 .... ....! .. 2.45E-08 ........! ...No. Data...........i ...6 ..16E-06 ........! ...6 ..94E-05 ........

Sb-125 l 7.16E-06 l 5.52E-08 l 1.50E-06 l 6.63E-09 l No Data l 3.99E-06 l 1.71E-05

:~~:~~~:: : : : : : : :i: ~:~~~:~~:: : : :i: :~:~!~:~: : :l: :i: :;:~:~:~~:: : : :i: ~:*~:~:~: : : : :i: :~~:~:!: : : : : : li: ~:~~~:~~:: : : :li: :~: ~;~:~;: : : :

Te-125m l 1.14E-05 l 3.09E-06 1.52E-06 l 3.20E-06 l No Data No Data 1.10E-05

  ...Te-1.27m .......... i...2 ..89E-05 ........ i.. 7. 78E-06 ........ i...3.43E-06 ........ i.. 6 ..9.1. E-06 ........ L.8.24E-05 ........L.No ._Data...........i.. 2 ..34E-05 ....... .

Te-127 ! 4.71E-07 l 1.27E-07 l 1.01E-07 l 3.26E-07 l 1.34E-06 l No Data l 1.84E-05 Te-129m i 4.87E-05 i 1.36E-05 i 7.56E-06 ! 1.57E-05 i 1.43E-04 i No Data i 5.94E-05 Te-129 i 1.34E-07 i 3.74E-08 j 3.18E-08 j 9.56E-08 j 3.92E-07 j No Data j 8.34E-06 Te-131m i 7.20E-06 i 2.49E-06 i 2.65E-06 i 5.12E-06 j 2.41E-05 j No Data j 1.01E-04

i. .

___T e-1.31 .................i...s . 30E-08 ........i.. 2.53E-08 ........!.. 2.47E-08 ........ i.. 6.35E-08 ........ i.. 2 ..51. E-07 ........ No ._Data...........i.. 4 ..36E-07 ....... . Te-132 l 1.01E-05 l 4.47E-06 l 5.40E-06 l 6.51E-06 l 4.15E-05 l No Data l 4.50E-05

                                                       .i.J                       i. .                                              i.                      i. .

___Te-1.33m ..........i ... 1_.87E-07 ....... .56E-08 ........ 9.37E-08 ........i ...1_.45E-07 ........ 7 ..18E-07 ........ No __Data ...........i ...5. 77E-06 ....... . Te-134 l 1.29E-07 l 5.80E-08 j 7.74E-08 j 1.02E-07 l 5.37E-07 j No Data j 5.89E-07 1-129 i 1.39E-05 i 8.53E-06 i 7.62E-06 j 5.58E-03 j 1.44E-05 j No Data i 4.29E-07 1-130 i 2.92E-06 j 5.90E-06 j 3.04E-06 j 6.50E-04 j 8.82E-06 j No Data j 2.76E-06 1-131 j 1.72E-05 j 1.73E-05 i 9.83E-06 i 5.72E-03 i 2.84E-05 j No Data j 1.54E-06 1-132

j 8.00E-07 j 1.47E-06 i 6.76E-07 i 6.82E-05 i 2.25E-06 i No Data j 1.73E-06 1-133 i 5.92E-06 i 7.32E-06 i 2.77E-06 i 1.36E-03 i 1.22E-05 i No Data ! 2.95E-06 1-134 ! 4.19E-07 ! 7. 78E-07 ! 3.58E-07 ! 1. 79E-05 i 1.19E-06 ! No Data i 5.16E-07 1-135 j 1.75E-06 j 3.15E-06 j 1.49E-06 j 2.79E-04 j 4.83E-06 j No Data j 2.40E-06 1

' > Data presented in this Table are from Reference 9. A-36 210

PNPS-ODCM Rev. 11 TABLE A-17 (continued) INGESTION DOSE FACTORS FOR CHILD (1> mrem/pCi Ingested

: j Total ' : : :

Nuclide ! Bone j Liver ! Body ! Thyroid i Kidney i Lung ! GI-LLI Cs-134m I 8.44E-08 : 1.25E-07 I 8.16E-08 i No Data I 6.59E-08 : 1.09E-08 : 1.58E-07 Cs-134 \ 2.34E-04 j 3.84E-04 \ 8.10E-05 j No Data \ 1.19E-04 j 4.27E-05 j 2.07E-06 Cs-135 \ 8.30E-05 j 5.78E-05 \ 5.93E-06 j No Data \ 2.04E-05 j 6.81E-06 j 4.33E-07 Cs-136 j 2.35E-05 j 6.46E-05 j 4.18E-05 j No Data j 3.44E-05 j 5.13E-06 j 2.27E-06 Cs-137 j 3.27E-04 j 3.13E-04 j 4.62E-05 j No Data j 1.02E-04 j 3.67E-05 j 1.96E-06 Cs-138 j 2.28E-07 j 3.17E-07 j 2.01E-07 j No Data j 2.23E-07 \ 2.40E-08 j 1.46E-07 Cs-139 \ 1.45E-07 \ 1.61E-07 j 7.74E-08 j No Data \ 1.21E-07 j 1.22E-08 j 1.45E-11 Ba-139 \ 4.14E-07 \ 2.21E-10 j 1.20E-08 j No Data \ 1.93E-10 j 1.30E-10 j 2.39E-05 Ba-140 j 8.31 E-05 j 7.28E-08 j 4.85E-06 j No Data j 2.37E-08 j 4.34E-08 j 4.21 E-05 Ba-141 j 2.00E-07 j 1.12E-10 j 6.51E-09 j No Data \ 9.69E-11 \ 6.58E-10 j 1.14E-07 Ba-142 j 8.74E-08 j 6.29E-11 j 4.88E-09 j No Data \ 5.09E-11 j 3.70E-11 \ 1.14E-09 La-140 \ 1.01 E-08 j 3.53E-09 j 1.19E-09 j No Data j No Data j No Data \ 9.84E-05 La-141 j 1.36E-09 j 3.17E-10 j 6.88E-11 j No Data j No Data j No Data j 7.0SE-05 La-142 j 5.24E-10 j 1.67E-10 j 5.23E-11 j No Data j No Data j No Data j 3.31E-05 Ce-141 j 3.97E-08 j 1.98E-08 j 2.94E-09 j No Data j 8.68E-09 j No Data j 2.47E-05 Ce-143 j 6.99E-09 j 3.79E-06 j 5.49E-10 j No Data j 1.59E-09 j No Data j 5.55E-05 Ce-144 j 2.08E-06 j 6.52E-07 j 1.11E-07 j No Data j 3.61E-07 j No Data j 1.70E-04 Pr-143 j 3.93E-08 j 1.18E-08 j 1.95E-09 j No Data j 6.39E-09 j No Data j 4.24E-05 Pr-144 j 1.29E-10 j 3.99E-11 j 6.49E-12 \ No Data j 2.11E-11 j No Data \ 8.59E-08 Nd-147 \ 2.79E-08 j 2.26E-08 j 1.75E-09 j No Data \ 1.24E-08 j No Data j 3.58E-05 Pm-147 j 3.18E-07 j 2.27E-08 j 1.22E-08 j No Data \ 4.01 E-08 \ No Data j 9.19E-06 Pm-148m j 1.03E-07 j 2.0SE-08 \ 2.0SE-08 \ No Data \ 3.04E-08 j No Data j 5.78E-05 Pm-148 j 3.02E-08 j 3.63E-09 j 2.35E-09 j No Data j 6.17E-09 j No Data j 9.70E-05 Pm-149 \ 6.49E-09 \ 6.90E-10 j 3.74E-10 \ No Data j 1.22E-09 j No Data j 4.71E-05 Pm-151 j 2.92E-09 j 3.55E-10 \ 2.31E-10 j No Data j 6.02E-10 \ No Data j 4.03E-05 Sm-151 j 2.56E-07 \ 3.81E-08 \ 1.20E-08 \ No Data j 3.94E-08 \ No Data j 5.53E-06 Sm-153 j 3.65E-09 \ 2.27E-09 \ 2.19E-10 \ No Data j 6.91E-10 \ No Data j 3.02E-05 Eu-152 j 6.15E-07 \ 1.12E-07 j 1.33E-07 j No Data j 4.73E-07 \ No Data j 1.84E-05 Eu-154 j 2.30E-06 \ 2.07E-07 \ 1.89E-07 j No Data \ 9.09E-07 j No Data j 4.81 E-05 Eu-155 j 4.82E-07 j 3.47E-08 j 2.72E-08 j No Data j 1.30E-07 j No Data j 8.69E-05 Eu-156 j 5.62E-08 \ 3.01 E-08 \ 6.23E-09 \ No Data \ 1.94E-08 j No Data \ 6.83E-05 Tb-160 j 1.66E-07 \ No Data \ 2.06E-08 j No Data \ 4.94E-08 j No Data \ 3.68E-05 Ho-166m j 1.08E-06 \ 2.26E-07 j 1.91 E-07 j No Data \ 3.22E-07 j No Data j 2.63E-05 W-181 j 4.23E-08 j 1.04E-08 j 1.43E-09 j No Data \ No Data j No Data \ 3.79E-07 W-185 j 1.73E-06 \ 4.32E-07 j 6.0SE-08 \ No Data \ No Data j No Data \ 1.61E-05 W-187 j 4.29E-07 j 2.54E-07 j 1.14E-07 j No Data \ No Data j No Data \ 3.57E-05 Pb-210 \ 4.75E-02 j 1.22E-02 j 2.09E-03 j No Data j 3.67E-02 j No Data j 2.30E-06 Bi-210 j 1.97E-06 j 1.02E-05 j 1.13E-06 j No Data j 1.15E-04 j No Data j 5.17E-05 Po-210 j 1.52E-03 \ 2.43E-03 j 3.67E-04 j No Data \ 7.56E-03 \ No Data j 6.55E-05 Ra-223 ( 2.12E-02 \ 2.45E-05 j 4.24E-03 j No Data \ 6.SOE-04 ( No Data \ 3.38E-04 Ra-224 \ 6.89E-03 \ 1.25E-05 j 1.38E-03 j No Data j 3.31 E-04 \ No Data \ 3.78E-04 Ra-225 \ 2.80E-02 \ 2.SOE-05 j 5.59E-03 j No Data \ 6.62E-04 j No Data \ 3.21 E-04 Ra-226 j 5.75E-01 \ 1.84E-05 \ 4.72E-01 j No Data \ 4.88E-04 j No Data \ 3.41E-04 Ra-228 j 3.85E-01 j 9.99E-06 j 4.32E-01 j No Data j 2.65E-04 j No Data j 5.81 E-05 1 ( > Data presented in this Table are from Reference 9. A-37 211

PNPS-ODCM Rev. 11 TABLE A-17 (continued) INGESTION DOSE FACTORS FOR CHILD <1> mrem/pCi Ingested i ' i Total , : : i Nuclide I Bone l Liver I Body I Thyroid i Kidney j Lung i GI-LLI Ac-225 i 1.88E-05 l 1.94E-05 i 1.26E-06 l No Data l 2.07E-06 1 No Data j 4.31 E-04

  -i~:i ~ -!-Hii:~i-!-rn;:~~-! Hii:~: =!:~~:g: : =:!:~ ~[~::=!:~~ g:E:=:!:rn;:~:=

~: ;;~::::::::::::::::!:::;:;;~:~;: : : : !: :~: ~~~:~: ::::::::!:{ :~~:~:::::::::!:::~~ ::g:!::::':::::::!:: ~: :~~:~!::::::::!:::~~ ::g:!::::::::::::!::t~:~:~;::::::::

Th-232 i 3.96E-03 j 1.52E-04 i 3.01 E-06 j No Data j 7.41 E-04 i No Data 1 5.27E-05 Th-234 i 3.42E-07 i 1.51 E-08 i 9.88E-09 i No Data i 8.01 E-08 i No Data i 1.18E-04 3 Pa-231 j 7.07E-03 j 2.34E-04 j 2.81 E-04 j No Data j 1.28E-03 j No Data i 7.37E-05

~~~ii ::=:!:i*~ii~~i =i:~i~E::r=i ~i,1~~~=:i:~i ~~i:l* i!~!~~=l:~i ~g=!J*~;:~!==

U-235 l 3.42E-03 l No Data

i. .

i 2.07E-04 i No Data i 5.61 E-04 j No Data l 8.03E-05

i. . i. .

  ... U-236 ................... 3.42E-03 ........i ...No ..Data........... 2 ..1. 2E-04 .... ....i ...No. Data...........i ...5. 73E-04 ........ No __Data ...........i ...5._92E-05 ........

U-237 l 2.36E-07 j No Data l 6.27E-08 l No Data l 6.81 E-07 l No Data l 2.08E-05 U-238 i 3.27E-03 j No Data i 1.94E-04 i No Data i 5.24E-04 i No Data i 5.66E-05

i. i. . i. .

  ... Np-237 ............... 2.23E-03 ........i ... 1_.47E-04 ........i . .9. 79E-05 ........ No ._Data...........! ...6. 05E-04 ........ No ._Data...........! ...8._16E-05 ........

Np-238 l 5.83E-08 l 1.18E-09 l 9.08E-10 l No Data l 3.76E-09 l No Data l 4.04E-05 Np-239 i 5.25E-09 j 3.77E-10 j 2.65E-10 i No Data i 1.09E-09 i No Data i 2.79E-05 Pu-238 j 1.19E-03 i 1.38E-04 i 3.16E-05 j No Data j 1.15E-04 j No Data j 7.50E-05 Pu-239 j 1.29E-03 i 1.38E-04 j 3.31 E-05 j No Data i 1.22E-04 j No Data j 6.85E-05 Pu-240 j 1.28E-03 i 1.43E-04 i 3.31 E-05 j No Data i 1.22E-04 i No Data i 6.98E-05 Pu-241 j 3.87E-05 j 1.58E-06 ! 8.04E-07 j No Data ! 2.96E-06 i No Data j 1.44E-06 Pu,242 i 1.19E-03 j 1.38E-04 j 3.19E-05 i No Data i 1.17E-04 i No Data i 6.71 E-05 Pu-244 i 1.39E-03 i 1.58E-03 i 3.65E-05 i No Data i 1.35E-04 i No Data i 1.00E-04 Am-241 j 1.36E-03 i 1.17E-03 j 1.02E-04 j No Data j 6.23E-04 j No Data j 7.64E-05 Am-242m j 1.40E-03 j 1.12E-03 j 1.04E-04 j No Data j 6.30E-04 j No Data j 9.61E-05

i. . i. .

  .. Am-243 .............. 1.-34E-03 ........ 1.-_13E-03 ........ i...9.83E-05 .... ....i ...No ..Data ...........i .. 6.06E-04 ........i ...No. Data ...........i ...8.95E-05 ....... .

Cm-242 l 8.78E-05 l 7.01E-05 l 5.84E-06 l No Data l 1.87E-05 l No Data i 8.16E-05

i. . i. . i. . i. .

  ...cm-243 ............. 1_.28E-03 ........ 1.-.04E-03 ........ 8.24E-05 ........i ...No __Data ...........i ...3._08E-04 ........ No __Data ...........i ...8. 03E-05 ........

Cm-244 i 1.08E-03 1 8.74E-04 j 6.93E-05 l No Data i 2.54E-04 j No Data 1 7.77E-05

i. . i. . i. . i

  ...cm-245 ............. 1_.67E-03 ........ 1_.34E-03 ........i ...1_. 05E-04 ........i ...No __Data...........i . 4 ..1_1_ E-04 ........ No __Data........... J .24E-05 ........

Cm-246 1 1.65E-03 l 1.34E-03 1 1.05E-04 1 No Data 1 4.1 OE-04 1 No Data 1 7.11 E-05 Cm-247 i 1.61 E-03 i 1.32E-03 i 1.03E-04 i No Data i 4.04E-04 i No Data i 9.35E-05

i. . i. . i. . i. .

  ...cm-248 .............i ... 1_._34E-02 ........ 1_. 09E-02 ........ 8.52E-04 ........i ...No __Data ...........i ...3._33E-03 ........ No __Data ........... 1_._5_1_ E-03 ........

Cf-252 i 1.05E-03 i No Data i 2.54E-05 i No Data i No Data i No Data i 2.96E-04 1 < > Data presented in this Table are from Reference 9. A-38 212

PNPS-ODCM Rev. 11 TABLE A-18 INGESTION DOSE FACTORS FOR INFANT <1) mrem/pCi Ingested Nuclide . , Bone ; Liver I~~~~ ! Thyroid j Kidney ! Lung j GI-LLI H-3 I No Data i 1.76E-07 11.76E-07 11.76E-07 1 1.76E-07 1 1.76E-07 i 1.76E-07 Be-10 j 1. 71 E-05 j 2.49E-06 j 5.16E-07 j No Data j 1.64E-06 j No Data i 2. 78E-05 C-14 i 2.37E-05 i 5.06E-06 i 5.06E-06 j 5.06E-06 i 5.06E-06 j 5.06E-06 j 5.06E-06 N-13 i 5.85E-08 i 5.85E-08 i 5.85E-08 i 5.85E-08 j 5.85E-08 j 5.85E-08 j 5.85E-08 F-18 i 5.19E-06 i No Data j 4.43E-07 i No Data i No Data j No Data i 1.22E-06 Na-22 j 9.83E-05 j 9.83E-05 j 9.83E-05 j 9.83E-05 j 9.83E-05 j 9.83E-05 j 9.83E-05 Na-24 i 1.01 E-05 j 1.01 E-05 j 1.01 E-05 j 1.01 E-05 i 1.01 E-05 i 1.01 E-05 i 1.01 E-05 P-32 j 1.70E-03 j 1.00E-04 i 6.59E-05 j No Data i No Data j No Data j 2.30E-05 Ca-41 i 3.74E-04 i No Data i 4.08E-05 i No Data j No Data i No Data i 1.91E-07 Sc-46 i 3.75E-08 i 5.41 E-08 j 1.69E-08 i No Data i 3.56E-08 i No Data j 3.53E-05 Cr-51 i No Data i No Data j 1.41E-08 j 9.20E-09 j 2.01E-09 j 1.79E-08 i 4.11E-07 Mn-54 j No Data i 1.99E-05 j 4.51E-06 j No Data j 4.41E-06 j No Data j 7.31E-06 Mn-56 j No Data i 8.18E-07 i 1.41E-07 j No Data i 7.03E-07 i No Data i 7.43E-05 Fe-55 i 1.39E-05 j 8.98E-06 i 2.40E-06 j No Data j No Data i 4.39E-06 j 1.14E-06 Fe-59 j 3.08E-05 j 5.38E-05 i 2.12E-05 i No Data j No Data j 1.59E-05 j 2.57E-05 Co-57 j No Data i 1.15E-06 j 1.87E-06 j No Data i No Data j No Data j 3.92E-06 Co-58 i No Data i 3.60E-06 i 8.98E-06 i No Data i No Data i No Data i 8.97E-06 Co-60 i No Data i 1.08E-05 i 2.55E-05 i No Data i No Data i No Data i 2.57E-05 Ni-59 i 4.73E-05 i 1.45E-05 i 8.17E-06 j No Data j No Data j No Data j 7.16E-07 Ni-63 i 6.34E-04 j 3.92E-05 j 2.20E-05 j No Data j No Data j No Data j 1.95E-06 Ni-65 j 4.70E-06 i 5.32E-07 i 2.42E-07 i No Data i No Data j No Data i 4.05E-05 Cu-64 j No Data j 6.09E-07 i 2.82E-07 j No Data i 1.03E-06 j No Data j 1.25E-05 Zn-65 j 1.84E-05 i 6.31 E-05 i 2.91 E-05 i No Data i 3.06E-05 i No Data i 5.33E-05 Zn-69m i 1.50E-06 i 3.06E-06 j 2.79E-07 j No Data j 1.24E-06 i No Data j 4.24E-05 Zn-69 j 9.33E-08 j 1.68E-07 j 1.25E-08 j No Data i 6.98E-08 j No Data j 1.37E-05 Se-79 j No Data i 2.10E-05 j 3.90E-06 j No Data i 2.43E-05 i No Data j 5.58E-07 Br-82 i No Data i No Data i 1.27E-05 i No Data i No Data i No Data / No Data Br-83 i No Data i No Data i 3.63E-07 i No Data i No Data i No Data i No Data Br-84 i No Data i No Data i 3.82E-07 i No Data i No Data i No Data i No Data Br-85 i No Data j No Data i 1.94E-08 j No Data j No Data j No Data j No Data Rb-86 i No Data i 1.70E-04 i 8.40E-05 i No Data j No Data i No Data i 4.35E-06 Rb-87 i No Data i 8.88E-05 i 3.52E-05 i No Data i No Data i No Data i 5.98E-07 Rb-88 i No Data i 4.98E-07 i 2.73E-07 i No Data i No Data i No Data i 4.85E-07 Rb-89 i No Data i 2.86E-07 i 1.97E-07 i No Data i No Data i No Data i 9.74E-08 Sr-89 i 2.51E-03 i No Data i 7.20E-05 i No Data i No Data i No Data i 5.16E-05 Sr-90 i 2.83E-02 i No Data i 5. 74E-04 i No Data i No Data i No Data i 2.31 E-04 Sr-91 i 5.00E-05 i No Data i 1.81 E-06 i No Data i No Data j No Data j 5.92E-05 Sr-92 j 1.92E-05 i No Data i 7.13E-07 i No Data i No Data i No Data i 2.07E-04 Y-90 i 8.69E-08 i No Data i 2.33E-09 i No Data i No Data i No Data i 1.20E-04 Y-91m i 8.10E-10 i No Data i 2.76E-11 i No Data i No Data i No Data i 2.70E-06 Y-91 j 1.13E-06 j No Data j 3.01 E-08 j No Data j No Data j No Data j 8.1 OE-05 Y-92 i 7.65E-09 i No Data i 2.15E-10 i No Data i No Data i No Data i 1.46E-04 Y-93 i 2.43E-08 i No Data i 6.62E-10 i No Data i No Data i No Data i 1.92E-04 1 <) Data presented in this Table are from Reference 9. A-39 213

PNPS-ODCM Rev. 11 TABLE A-18 (continued) INGESTION DOSE FACTORS FOR INFANT<1J mrem/pCi Ingested

                             '                     :                 I   Total              1                       :                       1                       '

Nuclide ! Bone ! Liver ! Body i Thyroid i Kidney i Lung i GI-LLI Zr-93 1 1.93E-07 1 9.19E-09 1 5.54E-09 ! No Data 1 2.71 E-08 1 No Data 1 2.39E-06 Zr-95 i 2.06E-07 i 5.02E-08 i 3.56E-08 j No Data j 5.41 E-08 j No Data j 2.50E-05 Zr-97 ! 1.48E-08 ! 2.54E-09 i 1.16E-09 j No Data j 2.56E-09 j No Data j 1.62E-04 Nb-93m i 1.23E-07 i 3.33E-08 j 1.04E-08 j No Data j 3.25E-08 i No Data j 3.98E-06 Nb-95 i 4.20E-08 i 1.73E-08 j 1.00E-08 j No Data i 1.24E-08 i No Data i 1.46E-05 Nb-97 i 4.59E-10 i 9.79E-11 i 3.53E-11 i No Data i 7.65E-11 i No Data i 3.09E-05 Mo-93 i No Data i 5.65E-05 j 1.82E-06 i No Data i 1.13E-05 i No Data i 1.21 E-06 Mo-99 i No Data i 3.40E-05 j 6.63E-06 j No Data i 5.08E-05 j No Data i 1.12E-05

. .;~:~~m***************l***~*:~~~:~~********l***~:!~~:~~********l***!:*J~~:~~********l***~~*g:!:***********l**~:~~~:~:********l***~:~;~:~~********l***~*:*~~~:~~********

Tc-101 j 2.27E-09 i 2.86E-09 j 2.83E-08 i No Data i 3.40E-08 i 1.56E-09 j 4.86E-07 Ru-103 j 1.48E-06 i No Data j 4.95E-07 i No Data i 3.08E-06 j No Data j 1.80E-05 Ru-105 j 1.36E-07 i No Data j 4.58E-08 i No Data j 1.00E-06 j No Data j 5.41 E-05 Ru-106 j 2.41 E-05 j No Data j 3.01 E-06 j No Data j 2.85E-05 j No Data j 1.83E-04 Rh-105 j 1.09E-06 j 7.13E-07 j 4.79E-07 i No Data j 1.98E-06 j No Data j 1.77E-05 Pd-107 j No Data i 1.19E-06 j 8.45E-08 i No Data j 6.79E-06 j No Data j 9.46E-07 Pd-109 j No Data i 1.50E-06 j 3.62E-07 i No Data j 5.51 E-06 j No Data j 3.68E-05 i.

.. Ag-11. Om .......... i...9 ..96E-07 ........i.. 7 .27E-07 ........i . 4.8.1.E-07 ........i...No ._Data...........i...1 .-.04E-06 ........i...No ._Data........... ..3. 77E-05 ........
.. Ag-1.1.1 ................. \.. 5.20E-07 ........\.. 2_.02E-07 i...1_.07E-07 ........\...N.o. Data........... l.. 4.22E-07 ........\. .. No. Data...........\.. 4.82E-05 ........

Cd-113m 1 No Data 1 1.77E-05 6.52E-07 1 No Data 1 1.34E-05 1 No Data 1 2.66E-05 Cd-115m j No Data j 1.42E-05 ! 4.93E-07 j No Data j 7.41 E-06 j No Data j 8.09E-05 Sn-123 j 2.49E-04 j 3.89E-06 j 6.50E-06 j 3.91 E-06 i No Data j No Data j 6.58E-05 Sn-125 j 7.41E-05 j 1.38E-06 j 3.29E-06 j 1.36E-06 j No Data j No Data j 1.11E-04 Sn-126 i 5.53E-04 j 7.26E-06 i 1.80E-05 j 1.91E-06 j No Data j No Data j 2.52E-05 Sb-124 j 2.14E-05 j 3.15E-07 i 6.63E-06 j 5.68E-08 j No Data j 1.34E-05 j 6.60E-05 Sb-125 i 1.23E~05 j 1.19E-07 i 2.53E-06 i 1.54E-08 i No Data j 7.12E-06 j 1.64E-05 Sb-126 i 8.06E-06 i 1.58E-07 i 2.91E-06 i 6.19E-08 i No Data i 5.07E-06 j 8.35E-05 Sb-127 i 2.23E-06 i 3.98E-08 i 6.90E-07 i 2.84E-08 i No Data i 1.15E-06 i 5.91E-05 Te-125m i 2.33E-05 i 7.79E-06 i 3.15E-06 j 7.84E-06 i No Data i No Data j 1.11E-05 Te-127m j 5.85E-05 j 1.94E-05 j 7.08E-06 j 1.69E-05 j 1.44E-04 j No Data j 2.36E-05 Te-127 i 1.00E-06 i 3.35E-07 j 2.15E-07 i 8.14E-07 i 2.44E-06 j No Data j 2.10E-05 Te-129m j 1.00E-04 j 3.43E-05 j 1.54E-05 i 3.84E-05 i 2.50E-04 j No Data j 5.97E-05 Te-129 i 2.84E-07 i 9.79E-08 j 6.63E-08 i 2.38E-07 i 7.07E-07 j No Data i 2.27E-05 Te-131m i 1.52E-05 i 6.12E-06 j 5.05E-06 i 1.24E-05 i 4.21E-05 i No Data j 1.03E-04 Te-131 j 1.76E-07 j 6.50E-08 j 4.94E-08 j 1.57E-07 j 4.50E-07 j No Data j 7.11 E-06 Te-132 j 2.08E-05 i 1.03E-05 i 9.61 E-06 i 1.52E-05 i 6.44E-05 i No Data i 3.81 E-05 Te-133m j 3.91 E-07 i 1.79E-07 i 1.71 E-07 i 3.45E-07 i 1.22E-06 j No Data i 1.93E-05 Te-134 j 2.67E-07 i 1.34E-07 i 1.38E-07 j 2.39E-07 i 9.03E-07 i No Data i 3.06E-06 1-129 i 2.86E-05 j 2.12E-05 i 1.55E-05 j 1.36E-02 i 2.51E-05 j No Data i 4.24E-07 1-130 j 6.00E-06 j 1.32E-05 j 5.30E-06 j 1.48E-03 j 1.45E-05 j No Data j 2.83E-06 1-131 i 3.59E-05 j 4.23E-05 i 1.86E-05 j 1.39E-02 j 4.94E-05 i No Data i 1.51 E-06 1-132 i 1.66E-06 i 3.37E-06 i 1.20E-06 j 1.58E-04 i 3.76E-06 i No Data i 2.73E-06 1-133 i 1.25E-05 i 1.82E-05 i 5.33E-06 j 3.31 E-03 i 2.14E-05 j No Data j 3.08E-06 1-134 i 8.69E-07 j 1.78E-06 i 6.33E-07 i 4.15E-05 .99E-06 j No Data j 1.84E-06 1-135 j 3.64E-06 j 7.24E-06 j 2.64E-06 j 6.49E-04 , 8.07E-06 i No Data j 2.62E-06 1 <J Data presented in this Table are from Reference 9. A-40 214

PNPS-ODCM Rev. 11 TABLE A-18 (continued) INGESTION DOSE FACTORS FOR INFANT <1J mrem/pCi Ingested

                             !                      :                      1 Total               !

i , i Nuclide i Bone i Liver i Body J Thyroid i Kidney j Lung i GI-LLI Cs-134m i 1.76E-07 I 2.93E-07 i 1.48E-07 i No Data i 1.13E-07 i 2.60E-08 i 2.32E-07 Cs-134 i 3.77E-04 i 7.03E-04 i 7.10E-05 i No Data i 1.81E-04 i 7.42E-05 i 1.91E-06 Cs-135 i 1.33E-04 ! 1.21E-04 ! 6.30E-06 ! No Data i 3.44E-05 i 1.31E-05 i 4.37E-07 Cs-136 i 4.59E-05 i 1.35E-04 i 5.04E-05 i No Data i 5.38E-05 i 1.1 OE-05 i 2.05E-06 Cs-137 i 5.22E-04 i 6.11E-04 i 4.33E-05 i No Data i 1.64E-04 i 6.64E-05 i 1.91E-06 Cs-138 i 4.81E-07 i 7.82E-07 i 3.79E-07 i No Data i 3.90E-07 ! 6.09E-08 i 1.25E-06

i. .

 ...Cs-139................ :...3 ..1. OE-07 ........! .. 4.24E-07 ........ :...1_.62E-07 ........i ...No ..Data...........i .. 2 ..19E-07 ........ 3.30E-08 ........i .. 2.66E-08 ........

Ba-139 i 8.81E-07 i 5.84E-10 i 2.55E-08 i No Data i 3.51E-10 i 3.54E-10 i 5.58E-05 Ba-140 j 1.71E-04 j 1.71E-07 i 8.81E-06 j No Data j 4.06E-08 j 1.05E-07 j 4.20E-05 Ba-141 i 4.25E-07 i 2.91E-10 ! 1.34E-08 i No Data i 1.75E-10 i 1.77E-10 i 5.19E-06 Ba-142 i 1.84E-07 i 1.53E-10 ! 9.06E-09 ! No Data ! 8.81E-11 ! 9.26E-11 i 7.59E-07 La-140 i 2.11E-08 i 8.32E-09 i 2.14E-09 ! No Data ! No Data ! No Data i 9.77E-05

                                                                           !. .                  !. .                                             i. .
 ... La-141................) ...2 ..89E-09 ........i ...B.38E-1.o ........ 1_.46E-1.o ........ No ..Data.........) ...No. Data........... No ..Oata.........) ...9.6.1. E-05 ........

La-142 l 1.10E-09 : 4.04E-10 i 9.67E-11 : No Data i No Data i No Data i 6.86E-05 Ce-141 i 7.87E-08 ! 4.BOE-08 i 5.65E-09 ! No Data ! 1.48E-08 ! No Data i 2.48E-05 Ce-143 i 1.48E-08 ! 9.82E-06 ! 1.12E-09 ! No Data ! 2.86E-09 ! No Data ! 5.73E-05 Ce-144 i 2.98E-06 i 1.22E-06 i 1.67E-07 ! No Data ! 4.93E-07 i No Data i 1.71E-04 Pr-143 i 8.13E-08 i 3.04E-08 i 4.03E-09 ! No Data i i 1.13E-08 No Data 4.29E-05 i Pr-144 i 2.74E-10 \ 1.06E-10 j 1.38E-11 i No Data \ 3.84E-11 \ No Data \ 4.93E-06 Nd-147 i i 5.53E-08 5.68E-08 i SE-09 i No Data \ 2.19E-08 i No Data i 3.60E-05 Pm-147 i 3.88E-07 i 3.27E-08 1.59E-08 i No Data i 4.88E-08 i No Data i 9.27E-06 Pm-148m i 1.65E-07 i 4.1 SE-08 i 3.28E-08 i No Data i 4.SOE-08 i No Data i 5.44E-05 Pm-148 i 6.32E-08 i 9.13E-09 i 4.60E-09 i No Data i 1.09E-08 i No Data i 9.74E-05 Pm-149 i i 1.38E-08 1.81E-09 i 7.90E-10 \ No Data \ 2.20E-09 i No Data i 4.86E-05 Pm-151 i 6.18E-09 i 9.01E-10 \ 4.56E-10 \ No Data \ 1.07E-09 i No Data i 4.17E-05

~~~ ~ ~~::::::::::::::!::*~: ;~~~~~ : : : : i: :~:~;~~~~ : : :

Eu-152 : 6.74E-07 : 1.79E-07 : 1.51 E-07 : No Data l1:: ~~~~::::::::!:::~~: g:~: : : : : : i: ~:;~~~~~ : : : : i: :~~::g:~::::::::::::i:::;:~~~~~~: : : :

l 5.02E-07 : No Data l 1.59E-05 Eu-154 \ 2.64E-06 i 3.67E-07 i 2.20E-07 \ No Data i 9.95E-07 \ No Data \ 4.58E-05 Eu-155 j 5.42E-07 i 6.25E-08 j 3.23E-08 j No Data j 1.40E-07 i No Data j 8.37E-05 Eu-156 i 1.14E-07 i 7.06E-08 i 1.12E-08 \ No Data i 3.26E-08 \ No Data \ 6.67E-05 Tb-160 i 2.59E-07 i No Data \ 3.24E-08 \ No Data i 7.37E-08 \ No Data \ 3.45E-05 Ho-166m \ 1.25E-06 i 2.69E-07 i 2.13E-07 \ No Data i 3.57E-07 \ No Data \ 2.66E-05

  .. w-1.s1 ................) ...s ..85E-08 ......) .. 2.72E-08 ......) ...3.04E-09 ........ !...No ..Data...........i ...No ..Oata........... !... No ..Data........... !. .3.82E-07 ........

W-185 l 3.62E-06 l 1.13E-06 i 1.29E-07 : No Data : No Data i No Data i 1.62E-05 W-187 \ 9.03E-07 i 6.28E-07 \ 2.17E-07 \ No Data i No Data \ No Data \ 3.69E-05 Pb-210 i 5.28E-02 i 1.42E-02 i 2.38E-03 i No Data i 4.33E-02 i No Data \ 2.32E-06 Bi-210 i 4.16E-06 i 2.68E-05 i 2.39E-06 i No Data i 2.0BE-04 i No Data i 5.27E-05 Po-210 i 3.1 OE-03 i 5.93E-03 i 7.41 E-04 \ No Data i 1.26E-02 i No Data \ 6.61 E-05 Ra-223 i 4.41 E-02 i 6.42E-05 i 8.82E-03 \ No Data i 1.17E-03 \ No Data \ 3.43E-04 Ra-224 i 1.46E-02 i 3.29E-05 i 2.91 E-03 \ No Data i 6.00E-04 i No Data \ 3.86E-04 Ra-225 \ 5.78E-02 i 6.52E-05 i 1.15E-02 \ No Data i 1.19E-03 i No Data \ 3.24E-04 Ra-226 i 6.20E-01 i 4.76E-05 i 5.14E-01 \ No Data i 8.71E-04 \ No Data i 3.44E-04 Ra-228 j 4.32E-01 i 2.58E-05 j 4.86E-01 j No Data i 4.73E-04 j No Data i 5.86E-05 1 < J Data presented in this Table are from Reference 9. A-41 215

PNPS-ODCM Rev. 11 TABLE A-18 (continued) INGESTION DOSE FACTORS FOR INFANT <1> mrem/pCi Ingested

Total 1 ' * :

Nuclide i Bone I Liver 1 I Body i Thyroid i Kidney j Lung j GI-LLI Ac-225 I 3.92E-05 i 5.03E-05 i 2.63E-06 i No Data i 3.69E-06 1 No Data i 4.36E-04

 ..  ~~:~~; .............,,,!** ~:~~~:~! . . . . j.. ~ :~~~:~: ........ 1...~:~;~:~: ........ 1... ~~ g:!:. . . .
                                                                                                     ..           1...; :!~~:~:********!***~~*g:!:. ,. . . . 1... ~: ~~~:~! . . . ..

Th-228 j 2.47E-03 i 3.38E-05 j 8.36E-05 j No Data i 1.58E-04 i No Data j 5.84E-04

i. i. .

 .. Th-229 ................i .. 2.52E-02 ........ 6 .,33E-04 ........i .. 4.20E-04 ........ No _pata........... i.)._03E-03 ........i . . No __Data.......... i...8._1 OE-05 ........

Th-230 i 3.80E-03 1 1.90E-04 i 1.06E-04 1 No Data 1 9.12E-04 i No Data i 6.24E-05 Th-232 i 4.24E-03 j 1.63E-04 j 1.65E-06 j No Data j 7.79E-04 j No Data j 5.31 E-05 Th-234 j 6.92E-07 j 3.77E-08 j 2.00E-08 j No Data j 1.39E-07 j No Data i 1.19E-04 Pa-231 j 7.57E-03 j 2.50E-04 j 3.02E-04 j No Data i 1.34E-03 i No Data j 7.44E-05 Pa-233 j 3.11 E-08 j 6.09E-09 j 5.43E-09 i No Data i 1.67E-08 i No Data i 1.46E-05 U-232 i 2.42E-02 j No Data i 2.16E-03 i No Data i 2.37E-03 j No Data j 7.04E-05 U-233 i 5.08E-03 j No Data i 3.87E-04 i No Data j 1.08E-03 i No Data i 6.51 E-05 U-234 i 4.88E-03 i No Data j 3.80E-04 j No Data j 1.06E-03 j No Data j 6.37E-05 U-235 j 4.67E-03 j No Data i 3.56E-04 j No Data j 9.93E-04 j No Data j 8.10E-05 U-236 j 4.67E-03 j No Data j 3.64E-04 j No Data j 1.01 E-03 j No Data j 5.98E-05 U-237 j 4.95E-07 j No Data i 1.32E-07 i No Data i 1.23E-06 j No Data j 2.11 E-05 U-238 j 4.47E-03 i No Data j 3.33E-04 i No Data i 9.28E-04 j No Data i 5.71 E-05

i. . i. i. . i. . .i . .

  ... Np-237 ............... 2.40E-03 ........ _1_._59E-04 ........ 1_.05E-04........i ...No,.Oata........... 6.34E-04 ........i . . No,.Oata.......... 8.23E-05 ....... .

Np-238 i1.24E-07 \3.12E-09 :1.92E-09 :NoData :6.81E-09 :NoData :4.17E-05 Np-239 j 1.11E-08 j 9.93E-10 i 5.61E-10 i No Data i 1.98E-09 i No Data i 2.87E-05 Pu-238 j 1.28E-03 j 1.50E-04 i 3.40E-05 j No Data j 1.21 E-04 j No Data i 7.57E-05 Pu-239 j 1.38E-03 j 1.55E-04 j 3.54E-05 j No Data j 1.28E-04 j No Data j 6.91 E-05 Pu-240 j 1.38E-03 j 1.55E-04 j 3.54E-05 j No Data j 1.28E-04 j No Data j 7.04E-05 Pu-241 j 4.25E-05 j 1.76E-06 j 8.82E-07 j No Data j 3.17E-06 j No Data j 1.45E-06 Pu-242 j 1.28E-03 j 1.49E-04 j 3.41 E-05 j No Data j 1.23E-04 j No Data j 6. 77E-05 Pu-244 j 1.49E-03 j 1.71 E-04 j 3.91 E-05 i No Data i 1.41 E-04 j No Data i 1.01 E-04 Am-241 j 1.46E-03 i 1.27E-03 i 1.09E-04 j No Data j 6.55E-04 j No Data j 7.70E-05 Am-242m j 1.51 E-03 j 1.22E-03 i 1.13E-04 i No Data i 6.64E-04 i No Data j 9.69E-05 Am-243 i 1.44E-03 j 1.23E-03 i 1.06E-04 j No Data j 6.36E-04 j No Data i 9.03E-05 Cm-242 j 1.37E-04 j 1.27E-04 j 9.1 OE-06 j No Data j 2.62E-05 j No Data j 8.23E-05 Cm-243 i 1.40E-03 j 1.15E-03 j 8.98E-05 j No Data j 3.27E-04 j No Data j 8.1 OE-05 Cm-244 i 1.18E-03 j 9. 70E-04 j 7.59E-05 j No Data j 2. 71 E-04 j No Data / 7.84E-05 Cm-245 i i i 1.79E-03 1.45E-03 i 1.13E-04 No Data 4.32E-04 i No Data i 7.30E-05 i Cm-246 i 1.77E-03 i 1.45E-03 i 1.13E-04 i No Data j 4.31 E-04 j No Data j 7.17E-05 Cm-247 j 1.73E-03 \ 1.43E-03 j 1.11 E-04 \ No Data \ 4.24E-04 j No Data i 9.43E-05 Cm-248 j 1.43E-02 i 1.18E-02 j 9.16E-04 j No Data j 3.50E-03 j No Data j 1.52E-03 Cf-252 i 1.22E-03 i No Data i 2.95E-05 i No Data i No Data i No Data j 2.99E-04 1 < > Data presented in this Table are from Reference 9. A-42 216

PNPS-ODCM Rev. 11 TABLE A-19 RECOMMENDED VALUES FOR GASEOUS EFFLUENTS <1l Parameter Symbol Parameter Description Values S Attenuation factor that accounts for 0.7 (maximum individual) the shielding provided by residential 0.5 (average individual.) structures 1.0 (noble gas-gamma instantaneous dose) <2l Time period that crops are exposed to contamination during growing season i) for forage ingested by animals 720 hrs (30 days, for pasture grass) 3 1440 hr (60 days for stored feed) < > ii) for crops ingested by man 1440 hrs (60 days) Average transport time of activity 48 hr (2 days, maximum individual) from the feed into the milk and to the 96 hr ( 4 days, average individual) receptor Time delay between harvest of vegetation or crops and ingestion i) for forage ingested by animals Zero (for pasture grass) 2160 hr (90 days for stored feed) ii) for crops ingested by man 24 hr (1 day, for leafy vegetables & max. individual) 1440 hr (60 days, for produce & max. individual) 336 hr (14 days, for average individual) Agricultural productivity by unit area (measured in wet weight) i) for forage ingested by animals 0.42 kg/m 2 (for pasture grass) 3 2.5 kg/m 2 (for stored feed) <3> 2 ii) for crops ingested by man 2.0 kg/m 1 <> All data presented in this table are from Reference 8, unless otherwise indicated. 2 <> From Reference 12. 3 < l From Reference 4. A-43 217

PNPS-ODCM Rev. 11 APPENDIX B DEFINITION OF THE LOWER LIMIT OF DETECTION For purposes of analyzing effluents and environmental samples for radioactivity, t,he lower limit of detection (LLD) is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability, with only 5% probability of falsely concluding that a blank observation represents a "real" signal. It should be recognized that the listed LLD is defined as an a priori (before the fact) limit representing the capability of the measurement system or analytical process, and not as an a posteriori (after the fact) limit for a particular measurement. Analyses should be performed in such a manner that the stated LLDs will be achieved under routine conditions. Usually, samples are counted for a period of time sufficient to ensure that the listed LLDs, based on normal analytical and counting parameters, are achieved. Printouts of analytical results typically list the a posteriori minimum detectable concentration (MDC) which was actually achieved on a particular measurement. In those cases where a given sample MDC is less than or equal to the listed a priori LLD, the required LLD has been achieved. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering radionuclides, or other uncontrollable circumstances may result in the MDC for a particular measurement not meeting the listed LLD. In such cases, the contributing factors shall be identified and described in the Semiannual Radioactive Effluent and Waste Disposal Report (for effluents) or the Annual Radiological Environmental Monitoring Report (for environmental samples). The value of the counting standard deviation (sb) used in the calculation of the LLD for a particular measurement system should be based on the actual observed standard deviation of the background counting rate or of the counting rate of an appropriate blank sample, rather than on an unverified, theoretically-predicted variance. One acceptable method for deriving Sb is as follows: Sb= Jalr where: Sb = standard deviation of the background counting rate or of the counting rate of an appropriate blank sample (counts/minute); B = background counting rate or counting rate of an appropriate blank sample (counts/minute); T = counting time interval for sample analysis (minutes). B-1

PNPS-ODCM Rev. 11 Lower Limit of Detection For Effluent Samples For a particular measurement system or analytical process which may include radiochemical separation used to analyze effluent samples, the lower limit of detection is calculated as follows: LLD* = 4.66 sb

            ' EV 2.22E6 Y           e- 2 ;t where:

LLD; = a priori lower limit of detection for radionuclide i, (µCi/ml or µCi/g); 4.66 = combined numerical constant corresponding to 95% probability of detection, with 5% probability of falsely identifying background as a "real" signal; Sb = standard deviation of the background counting rate or of the counting rate of an appropriate blank sample, (counts/minute); E = counting efficiency, (counts/disintegration); V = sample size, (milliliters or grams); 2.22E6 = conversion factor for disintegrations/minute per µCi; Y = fractional radiochemical yield, when applicable;

       ).,;     = radioactive decay constant for radionuclide i, (hr-1);

t = elapsed time between the midpoint of sample collection and time of counting, (hr). Typical values of E, V, Y, and t used for normal effluent sample analyses should be used in this calculation. B-2 219

PNPS-ODCM Rev. 11 Lower Limit of Detection For Environmental Samples For a particular measurement system or analytical process which may include radiochemical separation used to analyze effluent samples, the lower limit of detection is calculated as follows: LLD- = 4.66 sb 1 EV 2.22 Y e-l;t where: LLDj = a priori lower limit of detection for radionuclide i, (pCi/liter, pCi/m 3 , or pCi/kg); 4.66 = combined numerical constant corresponding to 95% probability of detection, with 5% probability of falsely identifying background as a "real" signal; Sb = standard deviation of the background counting rate or of the counting rate of an appropriate blank sample, (counts/minute); E = counting efficiency, (counts/disintegration); V = sample size, (liters, cubic meters, or kilograms); 2.22 = conversion factor for disintegrations/minute per pCi; Y = fractional radiochemical yield, when applicable; Ai = radioactive decay constant for radionuclide i, (hr-1 ); t = elapsed time between environmental sample collection or end of the sample collection period, and time of counting, (hr). Typical values of E, V, Y, and t used for normal effluent sample analyses should be used in this calculation. 8-3 220 J

PNPS-ODCM Rev. 11 APPENDIXC NRC SAFETY EVALUATION FOR ONSITE DISPOSAL OF SLIGHTLY CONTAMINATED CONSTRUCTION SOIL In May 1993, the NRC approved a permit under 10CFR20.302 to allow Pilgrim Station to dispose of construction soil containing small amounts of cobalt-60 and cesium-137. This soil was disposed of via onsite burial at a location on company property adjacent to the Pilgrim Station meteorological tower. Dose calculations performed as part of the permit application and within the NRC Safety Evaluation concluded that the maximum dose from the disposal area would be less than 0.1 mrem/year during the year of disposal. Doses during subsequent years through the time of site decommissioning would be less than 0.01 mrem/year. Such exposure levels are considered insignificant relative to radiation dose arising from naturally-occurring sources of radiation and radioactivity, and other exposure pathways arising from operation of Pilgrim Nuclear Power Station. Complete details regarding the NRC permit for disposal, and the accompanying NRC Safety Evaluation, can be found in NRC Docket No. 50-293, "APPROVAL UNDER 10CFR20.302(a) RELOCATION AND PLACEMENT OF CONSTRUCTION SOIL WITH TRACES OF RESIDUAL RADIOACTIVITY ON SITE AT PILGRIM NUCLEAR POWER STATION (TAC NO. M85501)", dated May 4, 1993. C-1 221}}

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