Text

Annual Radioactive Effluent Release Report, Table of Contents, Enclosure 1 Through Table 3.5-19
	ML031220199
Person / Time
Site:	Robinson
Issue date:	04/29/2003
From:	Baucom C; Progress Energy Co
To:	; Office of Nuclear Reactor Regulation
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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 1 of 44 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT January 1, 2002 - December 31, 2002 PROGRESS ENERGY CAROLINAS H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 2 of 44 TABLE OF CONTENTS Description...................................................

Page I.

EXECUTIVE

SUMMARY

4 A.

Discussion..................................................

4 B.

Significant Variances..................................................

7 C.

Regulatory Compliance..................................................

8 II.

SUPPLEMENTAL I NFORMATION..................................................

9 A.

Regulatory Limits..................................................

9 B.

Measurements and Approximations of Total Radioactivity.................................. 10 C.

Estimated Total Errors..................................................

11

m.

GASEOUS EFFLUENTS................................................

12 A.

Batch Releases................................................

12 B.

Abnormal Releases................................................

12 C.

Data Tables................................................

12 IV.

LIQUID EFFLUENTS................................................

18 A.

Batch Releases................................................

18 B.

Abnormal Releases................................................

18 C.

Data Tables................................................

18 V.

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS.

24 A.

Waste Class A................................................

24 B.

Waste Class B................................................

26 C.

Waste Class C................................................

28 D.

Irradiated Fuel Shipments.................................................

29 VI.

40 CFR 190 DOSE CONFORMANCE................................................

30 VII.

METEOROLOGICAL DATA................................................

30 A.

Continuous Release Diffusion Analysis................................................

30 B.

Mixed Mode Batch Release Diffusion Analysis................................................

33 C.

Ground Level Batch Release Diffusion Analysis..................................

36

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 3 of 44 LIST OF TABLES Enclosure I Table Description.........

Page Table En-A Table 11-B Table mH-C Table IV-A Table IV-B Table IV-C Table VII-A Table VII-B Table VII-C Gaseous Effluents - Summation of All Releases....................................... 13 Gaseous Effluents - Ground Level and Mixed Mode Releases................. 15 Typical Lower Limits of Detection for Gaseous Effluents........................ 17 Liquid Effluents - Summation of All Releases.......................................... 19 Liquid Effluents - Continuous Mode and Batch Mode Releases............... 21 Typical Lower Limits of Detection for Liquid Effluents........................... 23 Joint Occurrence Frequencies for LOWNDDEG and LOWNDSPD -

Continuous Releases..................................................

31 Joint Occurrence Frequencies for LOWNDDEG and LOWNDSPD Mixed Mode Batch Releases..................................................

34 Joint Occurrence Frequencies for LOWNDDEG and LOWNDSPD Ground Level Batch Releases..................................................

37

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 4 of 44 I.

EXECUTIVE

SUMMARY

A.

Discussion

1.

Protection Standards The main objective in the control of radiation is to ensure that any exposure is kept not only within regulatory limits, but As Low As Reasonably Achievable (ALARA). The ALARA concept applies to reducing radiation exposure both to workers at H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2 and to the general public. "Reasonably achievable" means that radiation exposure reduction is based on sound environmental practices, economic decisions, and operating practices. By practicing ALARA, HBRSEP and Progress Energy Carolinas, Inc.

minimizes health risk and environmental detriment, and ensures that exposures are maintained well below regulatory limits.

2.

Sources of Radioactivity Released During normal operations of a nuclear power station, most of the fission products are retained within the fuel and fuel cladding. However, small quantities of radioactive fission and activation products are present in the reactor coolant water.

The types of radioactive material released are noble gases, iodines and particulates, and tritium.

The noble gas fission products in the reactor coolant water are released as a gas when the coolant is depressurized. These gases are collected by a system designed for collection and storage for radioactive decay prior to release to the environment.

Small releases of radioactivity in liquids may occur from equipment associated with the reactor coolant system. These liquids are collected, processed for radioactivity removal, prior to and during release.

3.

Noble Gas Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as krypton, argon, and xenon. Noble gases are by nature inert and do not concentrate in humans or other organisms. Noble gases contribute to human radiation exposure as external exposure. The major isotopes released are Argon-41, Xenon-133, and Xenon-135 with half-lives of approximately two hours, five days, and nine hours, respectively. Half-life is defined as the time required for a radioactive isotope to lose 50 percent of its radioactivity by decay.

Noble gases are readily dispersed in the atmosphere.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 5 of 44

4.

lodines and Particulates Annual releases of iodines, and those particulates with half-lives greater than eight days are small. Factors such as chemical reactivity and solubility in water, combined with high processing efficiencies, minimize their discharge. The main contribution of radioactive iodine to human exposure is to the thyroid gland, where the body concentrates iodine. The particulates contribute to internal exposure of tissues such as the muscle, liver, and intestines. These particulates can also be a source of exposure if deposited on the ground.

5.

Tritium Tritium, a radioactive isotope of hydrogen, is the predominate radionuclide in liquid and gaseous effluents. Tritium is produced in the reactor coolant as a result of neutron interaction with deuterium (also a hydrogen isotope) and boron, both of which are present in the reactor coolant. Tritium is a weak beta particle emitter and contributes very little radiation exposure to the human body, and when tritium is inhaled or ingested it is dispersed throughout the body until eliminated.

6.

Processing and Monitoring Effluents are strictly controlled and monitored to ensure that radioactivity released to the environment is minimal and within regulatory limits. Effluent controls include the operation of radiation monitoring systems, in-plant and environmental sampling and analyses, quality assurance programs for both in-plant and environmental sampling and analyses, and procedures that address effluent and environmental monitoring.

The plant radiation monitoring system provides monitors that are designed to ensure that all releases are below regulatory limits. Each instrument provides indication of the amount of radioactivity present and is equipped with alarms and indicators in the control room. The alarm setpoints are set below the regulatory limits, i.e., typically at less than 50 percent of the regulatory limit, to ensure that the limits are not exceeded. If a monitor alarms, a release to the environment from a tank is automatically suspended. Additionally, releases are sampled and analyzed in the laboratory prior to discharge to the environment. The sampling and analysis done in the laboratory provides a more sensitive and precise method of determining pre-effluent composition than in-plant monitoring instruments.

The plant has a meteorological tower, which is linked to computers that record the meteorological data. The meteorological data and the release data are used to calculate dose to the public.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 6 of 44 In addition to in-plant equipment the company maintains a Radiological Environmental Monitoring Program, which consists of devices used to sample the air and water in the environment. The samples collected from the surrounding environment are analyzed to determine the presence of radioactive material in the environment.

7.

Exposure Pathways Radiological exposure pathways are the methods by which people may become exposed to radioactive material. The major pathways of concern are those, which could cause the highest calculated radiation dose. The projected pathways are determined from the type and amount of radioactive material that may have been released, the environmental transport mechanism, and the use of the environment.

Environmental transport mechanisms include, but are not limited to, hydrological (i.e., water) and meteorological (i.e., weather) characteristics of the area.

Information on water flow, wind speed and direction, dietary intake of residents, recreational use of the area and location of homes and farms in the area are some of the many factors used to calculate the potential exposure to offsite personnel.

The release of radioactive gaseous effluents includes pathways such as external whole body exposure, deposition on plants and soils, and human inhalation. The release of radioactive material in liquid effluents includes pathways such as fish consumption and direct exposure from the lake at the shoreline and while swimming.

Even though radionuclides can reach humans by many different pathways, some radionuclides result in more exposure than others. The critical pathway is the exposure which will provide, for a specific radionuclide, the greatest exposure to a population, or a specific group of the population, called the critical group. The critical group may vary depending on the radionuclides involved, the age and diet of the group, and other cultural factors. The exposure may be received by the whole body or to a specific organ, with the organ receiving the largest fraction of the exposure called the critical organ.

The exposures to the general public in the area surrounding HBRSEP, Unit No. 2 are calculated for gaseous and liquid releases. The exposure due to radioactive material released in gaseous effluents is calculated using factors such as the amount of radioactive material released, the concentration beyond the site boundary, weather conditions at the time of release, locations of exposure pathways, and usage factors. The exposures calculated due to radioactive materials released in liquid effluents are calculated using factors such as the total volume of liquid, the total volume of dilution water, field irrigation, and usage factors.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 7 of 44

8.

Results The Radioactive Effluent Release Report is a detailed listing of the radioactivity released from the HBRSEP, Unit No. 2 during the period from January 1, 2002, through December 31, 2002.

During the period of January 1, 2002, through December 31, 2002, the estimated maximum individual offsite dose due to radioactivity released in effluents was:

Liquid Effluents:

Total Body Dose 0.000174 millirem Critical Organ Dose 0.000221 millirem, liver Gaseous Effluents:

Beta Air Dose 0.00673 millirad Gamma Air Dose 0.01720 millirad Critical Organ Dose 0.09390 millirem, lung B.

Significant Variances The following are explanations of significant variances in this Annual Report:

1.

The 10 CFR 50, Appendix I, doses were calculated from the last posted release for the period indicated using the Canberra (Offsite Dose Calculation Manual (ODCM) meteorology) Effluent Management System (EMS). The ODCM (EMS' Software) provides day-by-day dose estimates that are conservative because all releases are assigned to the limiting receptor, using the continuous ground level dispersion factors calculated from 1978 meteorology.

2.

After 517 days of continuous operation, HBRSEP Unit No. 2 was removed from service on October 12, 2002 for a refueling outage. Power operation was resumed on November 13, 2002. Continuous operation along with continued good fuel and reactor coolant system integrity kept gaseous and liquid effluent totals relatively low in 2002. Some of the gaseous release parameters for this reporting period are summarized below:

EMS, Effluent Management Software, A product of Canberra Nuclear Industries used for determining curies and dose released from routine radioactive effluent releases

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 8 of 44 GASEOUS EFFLUENTS Units 1st Qtr 2nd Qtr 3rd Qtr 4th Otr Fission & Act. Gas Ci 3.99E-02 5.45E-02 1.30E-01 6.86E-01 1-131 Ci

<LLD

<LLD 9.14E-07 Part. >8 Day Half-Lives Ci 1.15E-06 7.16E-06 4.34E-08 3.36E-06 Tritium Ci 1.86E+00 1.34E+00 1.03E+00 2.56E+00

3.

Virtually all parameters associated with liquid effluents were stable for the year except for the differences caused by the refueling outage in the fourth quarter.

Some of the liquid release parameters for this reporting period are shown below:

LIQUID EFFLUENTS Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Fission & Act. Products Ci 8.26E-04 6.89E-04 6.36E-04 2.12E-02 Tritium Ci 2.20E+02 1.33E+02 1.49E+02 2.25E+01 Dilution Volume Liters 2.79E+11 2.85E+11 2.91E+11 1.29E+11 Waste Volume Liters 1.98E+06 4.75E+05 1.26E+06 4.78E+06 C.

Regulatory Compliance

1.

When projected on a day-by-day basis utilizing conservative meteorological conditions, the dose commitment from gaseous and liquid effluents is a small fraction of the 10 CER 50, Appendix I limits. The direct radiation assessment to the most likely exposed member of the public is reported in the Annual Radiological Environmental Operating Report. During 2002 the results of the direct radiation assessment demonstrated no measurable effect above background for plant operations.

2.

There was a change to the waste solidification Process Control Program (PCP) during this reporting period. See page 42.

3.

There were no changes to the Radioactive Waste Systems (i.e., liquid, gaseous, or solid) during this reporting period. See page 41

4.

There were no reportable instrumentation inoperability events during this reporting period. See page 42

5.

There were no outside liquid holdup tanks that exceeded the 10 curie limit during this reporting period. See page 42

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 9 of 44

6.

There were no Waste Gas Decay Tanks that exceeded the 1.9E+04 curie limit during this reporting period. See page 42

7.

There were revisions to the ODCM during this reporting period. See page 40.

II.

SUPPLEMENTAL INFORMATION A.

Regulatory Limits

1.

Fission and Activation Gases:

10 CFR 20 Limits (Instantaneous Release Rate)

Total Body Dose <500 mrem/yr Skin Dose <3000 mrem/yr 10 CFR 50, Appendix I For Calendar Quarter Gamma Dose <5 mrad Beta Dose <10 mrad For Calendar Year Gamma Dose <10 mrad Beta Dose <20 mrad

2.

Iodine - 131 and 133, Tritium, and Particulates >8 day half-lives:

10 CFR 20 Limits (Instantaneous Release Rate)

Dose from Inhalation (only) to a child to any organ <1500 mrem/yr 10 CFR 50, Appendix I (Organ Doses)

For Calendar Quarter <7.5 mrem For Calendar Year <15 mrem

3.

Liquids:

Concentrations are specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.OOE-04 yuCi/ml total activity.

10 CFR 50, Appendix I For Calendar Quarter Total Body Dose <1.5 mrem Any Organ Dose <5 mrem For Calendar Year Total Body Dose <3 mrem Any Organ Dose <10 mrem

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 10 of 44 B.

Measurements and Approximations of Total Radioactivity

1.

Continuous Gaseous Releases a)

Fission and Activation Gases - The total activity released is determined from the net count rate of the gaseous monitor, its calibration factor, and the total exhaust flow. The activity of radioactive gas is determined by the fraction of that radioactive gas in the isotopic analysis for that period.

b) lodines - The activity released as Iodine-131, 133, and 135 is based on isotopic analysis of the charcoal cartridge and particulate filter and the total exhaust flow.

c)

Particulates - The activity released via particulates with half-lives greater than eight days is determined by isotopic analysis of particulate filters and the total exhaust flow.

d)

Tritium - The activity released as tritium is based on weekly grab sample analysis and total exhaust flow.

2.

Batch Gaseous Releases a)

Fission and Activation Gases - The activity released is based on the volume released and the activity of the individual nuclides obtained from an isotopic analysis of the grab sample taken prior to the release.

b)

Iodines - The iodines from mixed mode batch releases are included in the iodine determination from the mixed mode continuous Reactor Auxiliary Building release.

c)

Particulates - The particulates from mixed mode batch releases are included in the particulate determination from the mixed mode continuous Reactor Auxiliary Building release.

d)

Tritium - The activity released as tritium is based on the grab sample analysis of each batch and the batch volume.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 11 of 44

3.

Liquid Releases a)

Fission and Activation Products - The total release values (not including tritium, strontium, Iron-55, and alpha) are comprised of the sum of the individual radionuclide activities in each release to the discharge canal for the respective quarter. These values represent the activity known to be present in the liquid radwaste effluent.

b)

Tritium & Alpha - The measured tritium and alpha concentrations in a monthly composite sample are used to calculate the total release and average diluted concentration during each period.

c)

Strontium-89, 90, and Iron The total release values are measured quarterly from composite samples.

C.

Estimated Total Errors

1.

Estimated total errors for gaseous effluents are based on uncertainties in counting equipment calibration, counting statistics, exhaust flow rates, exhaust sample flow rates, non-steady release rates, chemical yield factors, and sample losses for such items as charcoal cartridges.

2.

Estimated total errors for liquid effluents are based on uncertainties in counting equipment calibration, counting statistics, non-steady release flow rate, sampling and mixing losses, and volume determinations.

3.

Estimated total errors for solid waste are based on uncertainties in equipment calibration, dose rate measurements, geometry, and volume determinations.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 12 of 44 III.

GASEOUS EFFLUENTS A.

Batch Releases Jan - June 2002 July - Dec 2002 Number of batch releases 7.70E+01 8.50E+01 Total time period for batch releases 4.29E+04 min 8.93E+04 min Maximum time period for a batch release 1.01E+04 min 1.03E+04 min Average time period for a batch release 5.57E+02 min 1.05E+03 min Minimum time period for a batch release 1.OOE+00 min 1.00E+00 min B.

Abnormal Releases Jan - June 2002 July - Dec 2002 Number of releases 0.OOE+00 0.OOE+00 Total activity released 0.OOE+00 Ci O.OOE+00 Ci C.

Data Tables The following tables provide the details of gaseous releases:

Table 1-A Table M-B Table m-C Summation of all Releases Ground Level and Mixed Mode Releases Typical Lower Limits of Detection for Gaseous Effluents

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 13 of 44 TABLE HI-A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2002 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES I Unit Quarter J Quarter Est. Total A.

Fission and Activation Gases

1. Total release Ci 3.99E-02 l_5.45E-02 3.63E+01

2. Average release rate for period lCi/sec 5.13E-03 lJ6.93E-03 B.

lodines

1. Total Iodine-131 Ci

<LLD

<LLD l 1.74E+01

2. Average release rate for period lICi/sec l

_<LLD

<LLD C.

Particulates

1. Particulates with half-lives >8days Ci l1.15E-06 7.16E-06 1.05E+01

2. Average release rate for period ds pCi/sec 1.47E-07 9.1 lE-07 1

3. Gross alpha radioactivity Ci

<LLD T <LLD D.

Tritium

1. Total release I

Ci I 1.86E+00_l 1.34E+00 2.31E+01 l

2. Average release rate for period I pCi/sec I 2.39E-01 I 1.70E-01 I

E.

Percent of 10 CFR 50, Appendix I

1. Quarterly limit Gamma air 1.84E-02 2.16E-02 Beta air 3.27E-03 4.05E-03 Organ: Total Body 3.43E-01 NA Organ: Lung NA 2.52E-01

2. Annual limit Gamma air 9.19E-03*

2.00E-02*

Beta air 1.64E-03*

3.66E-03*

Organ: Total Body 1.71E-01*

NA Organ: Lung NA 2.97E-01*

Cumulative total for the year-to-date using the methodology in the ODCM.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 14 of 44 TABLE I-A (Continued)

EFFLUENT ANT WASTE DISPOSAL ANNUAL REPORT - 2002 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Quarter Quarter t otal Unitr4 A.

Fission and Activation Gases

1. Total release Ci 1.30E-01 6.86E-01 3.63E+01

2. Average release rate for period

[LCi/sec l 1.63E-02 8.64E-02 B.

Iodines

1. Total Iodine-131 Ci

<LLD 9.14E-07 1.74E+01

2. Average release rate for period liCi/sec

<LLD 1.15E-07 C.

Particulates

1. Particulates with half-lives >8 days Ci 4.34E-08 3.36E-06 1.05E+01

2. Average release rate for period

,uCi/sec 5.46E-09 4.22E-07

3. Gross alpha radioactivity Ci

<LLD

<LLD D.

Tritium

1. Total release Ci l_1.03E+00 2.56E+00 2.31E+01 II

2. Average release rate for period I pCi/sec I 1.30E-01 I 3.22E-01 I

E.

Percent of 10 CFR 50, Appendix I

1. Quarterly limit Gamma air 2.32E-02 2.82E-01 Beta air 7.63E-03 5.24E-02 Organ: Total Body 1.89E-01 NA Organ: Thyroid NA 4.71E-01

2. Annual limit Gamma air 3.16E-02*

1.73E-01*

Beta air 7.48E-03*

3.37E-02*

Organ: Lung 3.92E-01*

6.27E-01*

Cumulative total for the year-to-date using the methodology in the ODCM.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 15 of 44 TABLE Il-B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2002 GASEOUS EFFLUENTS - GROUND LEVEL AND MIXED MODE RELEASES Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 I Quarter 2

1.

Fission Gases Ar-41 Ci

<LLD

<LLD 3.85E-02 4.47E-02 Kr-85m Ci

<LLD

<LLD 8.7 1E-06 Xe-133 Ci

<LLD

<LLD 1.36E-03 8.89E-03 Xe-133m Ci

<LLD

<LLD 5.51E-05 Xe-135 Ci

<LLD

<LLD 8.03E-04 Total for Period Ci

<LLD

<LLD 3.99E-02 5.45E-02

2.

lodines' I-131 Ci

<LLD

<LD

<LLD

<LLD 1-133 Ci

<LLD

<LLD 4.12E-08 Total for Period Ci

<LLD

<LLD 4.12E-08

3.

Particulates_

Co-60 Ci

<LLD

<LLD 1.11E-06 7.16E-06 Br-82 Ci

<LLD

<LLD 3.17E-07 Cs-137 Ci

<LLD

<LLD 3.79E-08

<LLD Total for Period Ci

<LLD

<LLD 1.14E-06 7.48E-06 1Mixed mode continuous accountability includes mixed mode batch accountability (excludes tritium).

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 16 of 44 TABLE Ill-B (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2002 GASEOUS EFFLUENTS - GROUND LEVEL AND MIXED MODE RELEASES Continuous Mode Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4

1.

Fission Gases Ar-41 Ci

<LLD

<LLD 4.76E-02 5.85E-01 Kr-85 Ci

<LLD

<LLD 6.1 lE-02

<LLD Kr-85m Ci

<LLD

<LLD 3.48E-04 Xe-131m Ci

<LLD

<LLD 1.32E-04 1.17E-04 Xe-133 Ci

<LLD 3.12E-02 2.02E-02 5.49E-02 Xe-133m Ci

<LLD

<LLD 1.16E-04 1.11E-03 Xe-135 Ci

<LLD

<LLD 4.38E-04 1.34E-02 Total for Period Ci

<LLD 3.12E-02 1.30E-01 6.55E-01

2.

Iodines'11-131 Ci

<LLD 9.14E-07

<LLD

<LLD 1I-133 Ci

<LLD

<LLD Total for Period Ci

<LLD 9.14E-07

<LLD

3.

Particulates' Co-58 Ci

<LLD 2.31E-06

<LLD 8.13E-07 Co-60 Ci

<LLD

<LLD 4.34E-08 4.36E-08 Nb-95 Ci

<LLD

<LLD 1.90E-08 Cs-137 Ci

<LLD

<LLD 1.72E-07 Total for Period Ci

<LLD 2.31E-06 4.34E-08 1.05E-06

'Mixed mode continuous accountability includes mixed mode batch accountability (excludes tritium).

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 17 of 44 TABLE 11-C TYPICAL LOWER LIMITS OF DETECTION FOR GASEOUS EFFLUENTS Nuclide LLD (,uCi/cc)

H-3 l.OOE-06 Ar-41 5.06E-08 Mn-54 l.OOE-11 Co-58 l.OOE-Il Fe-59 l.OOE-Il Co-60 l.OOE-Il Zn-65 1.OOE-Il Br-82 8.13E-14 Kr-85 4.44E-06 Kr-85m 1.56E-08 Kr-87 l.OOE-04 Kr-88 l.OOE-04 Sr-89 l.OOE-ll Sr-90 l.OOE-l1 Mo-99 l.OOE-1 1 1-131 l.OOE-12 Xe-131m 3.99E-07 I-133 1.OOE-10 Xe-133 l.OOE-04 Xe-133m 1.OOE-04 Cs-134 l.OOE-11 I-135 3.60E-10 Xe-135 1.OOE-04 Xe-135m 5.95E-07 Cs-137 l.OOE-11 Xe-138 l.OOE-04 Ba-140 5.42E-14 La-140 1.70E-13 Ce-141 I.OOE-11 Ce-144 l.OOE-11 Gross Alpha 1.OOE-11

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 18 of 44 IV.

LIQUID EFFLUENTS A.

Batch Releases Jan - June 2002 July - Dec 2002 Number of batch releases 3.40E+01 8.80E+01 Total time period for batch releases 6.47E+03 min 1.51E+04 min Maximum time period for a batch release 3.34E+02 min 2.68E+02 min Average time period for a batch release 1.90E+02 min 1.71E+02 min Minimum time period for a batch release 1.28E+02 min 2.07E+01 min Average stream flow during release periods 5.72E+05 gpm 5.14E+05 gpm B.

Abnormal Releases Jan - June 2002 July - Dec 2002 Number of releases

.OOE+00 0

1.OOE+00 Total activity released O.OOE+00 Ci O.OOE+00 Ci C.

Data Tables The following tables provide the details of gaseous releases:

Table IV-A Table IV-B Table IV-C Summation of all Releases Continuous and Batch Mode Releases Typical Lower Limits of Detection for Liquid Effluents

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 19 of 44 TABLE IV-A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2002 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Quarter Quarter Est. Total I

1 2

Error %

A.

Fission and Activation Products

1. Total release (not including tritium, gases, alpha)

Ci 8.26E-04 6.89E-04 1.07E+01

2. Average diluted concentration during period lICi/ml 2.96E-12 2.42E-12 B.

Tritium

1. Total release Ci 2.20E+02 1.33E+02 9.20E+00

2. Average diluted concentration during period pCi/ml 7.87E-07 4.66E-07 C.

Dissolved and entrained gases

1. Total release Ci 5.1 1E-04 2.99E-04 9.60E+00

2.

Average diluted concentration during period pICi/ml 1.83E-12 1.05E-12

3. Percent of applicable limit 9.16E-07 5.25E-07 D.

Gross alpha radioactivity

1. Total release Ci

<LLD

<LLD 1.83E+01 E.

Volume of waste released prior to Liters 1l.98E06 4.75E+05 dilution F.

Volume of dilution water used during L

E J E period lLiters l2.79E+11 I 2.85E+1 1l G.

Percent of 10CFR50, Appendix I

1. Quarterly Limit Organ: Liver 8.82E-04 6.26E-04 Total body l

2.77E-03 1.54E-03

2. Annual Limit Organ: Liver 4.41E-04*

7.54E-04*

Total body l

1.39E-03*

2.16E-03*

Cumulative total for the year-to-date using the methodology in the ODCM.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 20 of 44 TABLE IV-A (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2002 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Quarter Quarter Est. Total Unit 4

1Er-ror A.

Fission and Activation Products

1. Total release (not including tritium, gases, alpha)

Ci 6.36E-04 2.12E-02 1.07E+01

2. Average diluted concentration during period iCi/ml 2.19E-12 1.65E-10 B.

Tritium D 1.

Total release Ci 1.49E+02 2.25E+01 9.20E+00

2. Average diluted concentration 0

during period IlCi/ml 5.1 1E-07 1.74E-07 C.

Dissolved and entrained gases

1. Total release Ci 2.42E-02 4.43E-03 9.60E+00

2. Average diluted concentration during period ICi/_l 8.33E-11 3.44E-I1

3. Percent of applicable limit 4.17E-05 1.72E-05 D.

Gross alpha radioactivity

1. Total release Ci

<LLD

<LLD 1.83E+01 E.

Volume of waste released prior to Liters 1.26E+06 4.78E+06 dilution lF.

Volume of dilution water used during period Liters 2.91E+11 1.29E+11 G.

Percent of 10CFR50, Appendix I

1. Quarterly Limit Organ: Liver 3.62E-04 2.56E-03 Total body 1.13E-03 6.19E-03

2. Annual Limit Organ: Liver 9.35E-04*

2.22E-03 Total body 2.72E-03*

5.82E-03*

Cumulative total for the year-to-date using the methodology in the ODCM.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 21 of 44 TABLE IV-B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2002 LIQUID FFL

.NT. - CONTINUOUS MODE AND BATCH MODE RELEASES Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 1

1 2

H-3 l

Ci 1.48E-03 l

<LLD 2.20E+02 1.33E+02 Fe-55 Ci

<LLD

<LLD 6.53E-05 2.57E-05 Co-58 Ci

<LLD

<LLD 4.24E-06 7.72E-06 Co-60 Ci

<LLD

<LLD 6.03E-04 6.27E-05 Te-123m Ci

<LLD

<LLD 1.71E-05 2.3lE-06 Sb-124 Ci

<LLD

<LLD 1.33E-05 3.27E-05 Sb-125 Ci

<LLD

<LLD 1.1 lE-04 3.1OE-04 Cs-134 Ci

<LLD

<LLD 1.17E-05 Cs-137 Ci

<LLD

<LLD 1.23E-05 2.36E-04 Total for Period Ci

<LLD

<LLD 8.26E-04 6.89E-04 D

Xe-133

[

Ci

<LLD

<LLD l_5.11E-04 2.99E-04 Total for Period

[

Ci

<LLD

<LLD l_5.11E-04 2.99E-04

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 22 of 44 TABLE IV-B (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2002 LIOUID EFFLUENTS - CONTINUOUS MODE AND BATCH MODE RELEASES Continuous Mode Batch Mode I

Qartr uarer Quarter Quarter l Nuclides Released Unit Quarter Quarter 3

4 lH-3 Ci

<LLD

<LLD l

1.49E+02 2.24E+01 Cr-51 Ci

<LLD

<lLD

<LLD 2.65E-03 Mn-54 Ci

<LLD

<LLD 4.71E-07

<LLD Fe-55 Ci

<LLD

<LLD 5.22E-05 2.45E-05 Co-57 Ci

<LLD

<LLD 6.18E-08

<LLD Co-58 Ci

<LLD

<LLD 4.17E-07 4.09E-03 Fe-59 Ci

<LLD

<L-D

<LILD 9.52E-05 Co-60 Ci

<LLD

<LLD 5.10E-04 1.55E-03 Zn-65 Ci

<LLD

<LLD 9.87E-06 Nb-95 Ci

<LLD

<LLD 1.95E-06 Ag-110m Ci

<LLD

<LLD 5.18E-06 1.96E-04 Sn-113 Ci

<LLD

<LLD 5.72E-05 Sb-122 Ci

<LLD

<LID

<LLD 2.98E-06 Te-123m Ci

<LLD

<LLD 3.62E-06 1.03E-04 Sb-124 Ci

<LLD

<LLD 1.62E-03 Sb-125 Ci

<LLD

<LLD 4.94E-05 1.06E-02 Te-132 Ci

<LLD

<LLD 5.38E-06 Cs-137 Ci

<LLD

<LLD 1.49E-05 7.25E-05 La-140 Ci

<LLD

<LLD 4.81E-05 Total for Period Ci

<LLD

<LLD 6.36E-04 2.12E-02 Xe-127 Ci

<LLD

<LLD 1.75E-05 Xe-131m Ci

<LLD

<LLD 1.51E-04

<LLD Xe-133 Ci

<LLD

<LLD 2.39E-02 4.40E-03 Xe-133m Ci

<LLD

<LLD 1.85E-04 2.83E-05 Xe-135 Ci

<LID

<LLD 6.27E-06

<LLD Total for Period Ci

<LLD

<LLI) 2.42E-02 4.44E-03

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 23 of 44 TABLE TV-C TYPICAL LOWER LIBITS OF DETECTION FOR LIQUID EFFLUENTS Nuclide LLD (,Ci/ml)

H-3 l.OOE-05 Cr-51 1.30E-07 Mn-54 5.OOE-07 Fe-55 1.OOE-06 Co-57 2.45E-08 Co-58 5.OOE-07 Fe-59 5.OOE-07 Co-60 5.OOE-07 Zn-65 5.OOE-07 Sr-89 5.00E-08 Sr-90 5.OOE-08 Nb-95 1.86E-08 Zr-95 3.34E-08 Mo-99 5.OOE-07 Tc-99m 2.87E-07 Ag-I lOmn 1.71E-08 Sn-113 2.34E-08 Sb-122 3.48E-08 Te-123m 1.76E-08 Sb-124 7.63E-08 Sb-125 5.38E-08 Xe-127 l.OOE-05 1-131 1.OOE-06 Xe-13 lm l.OOE-05 Te-132 2.49E-08 Xe-133 1.OOE-05 Xe-133m l.OOE-05 Cs-134 5.OOE-07 Xe-135 l.OOE-05 Cs-137 5.00E-07 Ba-140 1.14E-07 La-140 4.23E-08 Ce-141 5.OOE-07 Ce-144 5.OOE-07 Gross Alpha I.OOE-07

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 24 of 44 V.

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Report Time Period January 1, 2002, Through December 31, 2002 A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel)

Waste Class A

1 Period Est. Total Solid.

Cont.

F

[No.

1.

Type of Waste Unit Total Error (%)

Agent Type F

l Ship.

a)

Spent resins, filter sludges, m3 7.69E+00 1.OOE+00 N

evaporator bottoms, etc.

Ci 7.62E+00 2.29E+01 None IC Normal 2

b)

Dry compressible waste, m3 1.59E+02 1.00E+00 contaminated equipment, etc.

Ci 1.96E+00 2.29E+01 None STP Normal 3

c)

Irradiated components, control m3 NA NANA NANA NA rods, etc.

Ci d)

Other: Steam Generator sludge /

I3 8.03E+01 1.2OE+00 None STP Normal 3

liquid Ci 4.78E-01 2.29E3+01 Noe SPora3 STP = Strong Tight Package HIC = High Integrity Container

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 25 of 44

2.

Estimate of major nuclide composition (by type of waste)

Ci

a.

C-14 3.93E+00 3.OOE-01 Fe-55 5.22E+00 3.98E-01 Co-58 5.08E+00 3.87E-01 Co-60 1.68E+01 1.28E+00 Ni-63 6.12E+01 4.67E+00 Sb-125 1.53E+00 1.17E-01 Cs-137 2.89E+00 2.20E-01 Others*

3.32E+00 2.53E-01

b.

C-14 1.32E+00 2.58E-02 Fe-55 1.30E+01 2.54E-01 Co-58 1.57E+01 3.07E-01 Co-60 7.29E+00 1.43E-01 Ni-63 5.76E+00 1.13E-01 Nb-95 4.99E+01 9.78E-01 Zr-95 4.40E+00 8.63E-02 Sb-124 1.24E+00 2.44E-02 Others**

1.5 lE+00 2.96E-02

c.

NA

[

NA l

NA

d.

H-3 1.40E+00 6.69E-03 Ni-63 9.39E+01 4.49E-01 l

Ce-144 3.1OE+00 1.48E-02 Others***

1.57E+00 7.51E-03

3.

Solid Waste Disposition Number of Shipments:

Mode of Transportation:

Destination:

8 Exclusive use - Highway Barnwell, GTS Duratek, Race LLC, Envirocare Others include:

Others include:

H-3, Mn-54, Co-57, Zn-65, Sr-89, Sr-90, Ag-1 10m, Te-123m, Sb-124, Cs-134, Ce-144, Pu-238, Pu-239, Pu-241, Cm-242, Cm-243.

H-3, Cr-51, Mn-54, Co-57, Sr-89, Sr-90, Cd-109, Ag-1 10m, Sn-i 13, Te-123m, Sb-125, Cs-137, Ce-144, Pu-238, Pu-239, Am-241, Pu-241, Cm-242, Cm-243.

C-14, Co-60, Cs-137, Pu-238, Pu-239.

Total Curie Quantity and Principle Radionuclides were determined by Estimate.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 26 of 44 V.

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Report Time Period January 1, 2002, Through December 31, 2002 B.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel)

Waste Class B

1 e of Waste Unit Period Est. Total 1 Solid. 1 Cont.

F l

No.

ll Total Error (%)

Agent Type Ship.

a)

Spent resins, filter sludges, m3 3.85E+00 1.OOE+00 N

evaporator bottoms, etc.

Ci 2.64E+01 2.29E+01 None MC Normal I

b)

Dry compressible waste, m3 N

N contaminated equipment, etc.

Ci NA NANA NANA NA c)

Irradiated components, control 3

rods, etc.

Ci NA NA NA NA NA NA d)

Other: Wax stripper sludge, mixed m3 waste shipment of refrigerant still Ci NA NA NA NA NA NA bottoms, parts washer sludge.

HIC = High Integrity Container

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 27 of 44

2.

Estimate of major nuclide composition (by type of waste)

3.

Solid Waste Disposition Number of Shipments:

Mode of Transportation:

Destination:

1 Exclusive use Barnwell Ci

a.

C-14 8.90E-02 2.35E-02 Mn-54 8.48E-01 2.24E-01 Fe-55 1.31E+01 3.45E+00 Co-57 1.90E-01 5.02E-02 Co-60 2.34E+01 6.18E+00 Ni-63 5.53E+01 1.46E+01 Ag-110m 9.39E-02 2.48E-02 Sb-125 4.73E+00 1.25E+00 Cs-134 1.26E-01 3.33E-02 Cs-137 1.83E+00 4.82E-01 Ce-144 1.55E-01 4.09E-02 Others*

1.56E-01 4.13E-02

b.

NA NA NA

c.

NA NA NA

d.

NA NA NA Others include: H-3, Sr-89, Sr-90, Pu-238, Pu-239, Am-241, Pu-241, Cm-242, Cm-243.

Total Curie Quantity and Principle Radionuclides were determined by Estimate.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 28 of 44 V.

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Report Time Period January 1, 2002, Through December 31, 2002 C.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel)

Waste Class C

e of Waste Unit Period Est. Total Solid.

Cont.

o F

No.

ype J Total Error (%)

Agent Type For Ship.

a)

Spent resins, filter sludges, m3 3.85E+00 1.OOE+00 evaporator bottoms, etc.

Ci 6.43E+00 2.29E+01 None MC Normal I

b)

Dry compressible waste, m

NA NANA NANA NA contaminated equipment, etc.

Ci c)

Irradiated components, control m3 NA NANA NANA NA rods, etc.

Ci d)

Other: Wax stripper sludge, mixed m3 waste shipment of refrigerant still Ci NA NA NA NA NA NA bottoms, parts washer sludge.

HIC = High Integrity Container

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 29 of 44

2.

Estimate of major nuclide composition (by type of waste)

3.

Solid Waste Disposition Number of Shipments:

Mode of Transportation:

1 Exclusive use - Highway Barnwell Destination:

Ci

a.

C-14 5.05E+00 3.25E-01 Mn-54 3.70E-01 2.38E-02 Fe-55 2.41E+01 1.55E+00 Co-58 2.33E+00 1.50E-01 Co-60 4.46E+01 2.87E+00 Ni-63 2.02E+01 1.30E+00 Nb-95 2.72E-01 1.75E-02 Cd-109 2.71E-01 1.74E-02 Ag-110m 8.65E-01 5.56E-02 Sb-124 1.70E-01 1.09E-02 Sb-125 8.96E-01 5.76E-02

Others 8.12E-01 5.22E-02

b.

NA NA NA

c.

NA NA NA

d.

NA NA F-NA Others include: H-3, Cr-51, Cm-242, Am-243, Cm-243.

Co-57, Ni-59, Sr-89, Sr-90, Zr-95, Sn-113, Te-123m, Cs-137, Ce-144, Pu-238, Pu-239, Am-241, Pu-241, Total Curie Quantity and Principle Radionuclides were determined by Estimate.

D.

IRRADIATED FUEL SHIPMENTS Number of Shipments 5

Mode of Transportation Exclusive Use - Rail Destination Shearon Harris Nuclear Power Plant

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 30 of 44 VI.

40 CFR 190 DOSE CONFORMANCE The direct radiation assessment to the most likely exposed member of the public is reported in the Annual Radiological Environmental Operating Report. The results of the assessment demonstrate no measurable affect above background from plant operations. Since no 10 CFR 50, Appendix I, limits have been exceeded and the evaluation of the Independent Spent Fuel Storage Installation indicates only a small fraction of the total dose to the environs, this demonstrates conformance with 40 CFR 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."

VII.

METEOROLOGICAL DATA A.

Continuous Release Diffusion Analysis Table VII-A presents the number and frequency of wind direction occurrences by wind speed class as recorded at the onsite meteorological system during continuous release for the period January 1, 2002, through December 31, 2002.

The frequencies are presented as a percent of total occurrences for each stability class as well as a summary for all classes for the lower (11 meter) sensor elevation.

Pertinent information available from the tables is as follows:

1.

Stability Percent occurrence Pasquill Stability categories based on lower level (1 Im) wind distribution:

A B

C D

E F

G 18.84 4.19 3.74 31.16 22.38 9.55 10.14

2.

Wind Speed 11 Meter Average Speed (mph) 4.27 Percent Calm 9.39 Percent Less than 3.5 mph 46.26

3.

Wind Direction 11 Meter Prevailing S

Percent Occurrence 13.10

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 31 of 44 TABLE VIT-A JOINT OCCURRENCE FREOUENCIES FOR LOWNDDEG AND LOWNDSPD - CONTINUOUS RELEASES JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS A UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.001 0.157 0.980 0.290 0.000 0.000 0.000 1.43 NNE 0.001 0.351 1.271 0.097 0.000 0.000 0.000 1.72 NE 0.002 0.472 1.004 0.000 0.000 0.000 0.000 1.48 ENE 0.002 0.557 0.569 0.000 0.000

0. 000 0.000 1.13 E

0.004 0.617 0.496 0.000 0.000 0.000 0.000 1.12 ESE 0.002 0.520 0.424 0.000 0.000 0.000 0.000 0.95 SE

0. 002 0.557 0.617 0.024 0.000 0.000 0.000 1.20 SSE 0.001 0.145 0.835 0.121

0. 000

0. 000 1.10 S

0.001 0.157 0.557 0.315 0.048 0.000 0.000 1.08 SSW 0.001 0.157 1.077 0.424 0.012 0.000 0.000 1.67 SW 0.001 0.242 1.113 0.315 0.000 0.000 0.000 1.67 WSW 0.002 0.448 0.811 0.097 0.012 0.000 0.000 1.37 W

0.001 0.182 0.738 0.061 0.000 0.000 0.000 0.98 WNW 0.001 0.133 0.424 0.290 0.012 0.000 0.000 0.86 NW 0.000 0.073 0.303 0.206 0.012 0.000 0.000 0.59 NNW TOTAL 0.000 0.025 0.121 4.889 0.254 11.471 0.121 2.360 0.000 0.097 0.000 0.000 0.000 0.000 0.50 18.84 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS B UMAX (MIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0. 001 0.073 0.254 0.073 0.000 0.000 0.000 0.40 NNE 0.001 0.073 0.206 0.024

0. 000 0.000 0.000 0.30 NE 0.001 0.097 0.133 0.000 0.000 0.000 0.000 0.23 ENE 0.001 0.073 0.085 0.000 0.000 0.000 0.000 0.16 E

0.001 0.061 0.048

0. 000

0. 000 0.000 0.000 0.11 ESE 0.001 0.048 0.036 0.012 0.000 0.000 0.000 0.10 SE

0. 001 0.085 0.061 0.000 0.000 0.000 0.000 0.15 SSE 0.001 0.048 0.206 0.024 0.000 0.000 0.000 0.28 S

0.000 0.024 0.218 0.182 0.048 0.000 0.000 0.47 SSW 0.000 0.012 0.278 0.097 0.012 0.000 0.000 0.40 SW 0.001 0.073 0.194 0.036 0.000 0.000 0.000 0.30 WSW 0.001 0.061 0.169 0.000 0.000 0.000 0.000 0.23 W

0.001 0.073 0.085 0.024 0.012 0.000 0.000 0.19 WNW 0.000 0.024 0.133 0.061 0.012 0.000 0.000 0.23 NW 0.000

0. 000 0.145 0.097 0.061

0. 000 0.000 0.30 NNW 0.001 0.048 0.182 0.097 0.000 0.000 0.000 0.33 TOTAL 0.015 0.871 2.432 0.726 0.145 0.000 0.000 4.19 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS C UMAX (MIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.000 0.024 0.182 0.036 0.000 0.000 0.000 0.24 NNE 0.000 0.085 0.242 0.012 0.000 0.000 0.000 0.34 NE 0.000 0.097 0.121 0.000 0.000 0.000 0.000 0.22 ENE 0.000 0.036 0.097 0.000 0.000

0. 000 0.000 0.13 E

0.000 0.085 0.133 0.012 0.000 0.000 0.000 0.23 ESE 0.000 0.024 0.073 0.000 0.000 0.000 0.000 0.10 SE

0. 000 0.061 0.024 0.000

0. 000

0. 000 0.08 SSE 0.000 0.061 0.254 0.097

0. 000

0. 000 0.41 S

0.000

0. 000 0.194 0.157 0.000 0.000 0.000 0.35 SSW 0.000 0.012 0.230 0.121 0.012

0. 000 0.000 0.38 SW 0.000 0.024 0.182 0.048 0.000 0.000 0.000 0.25 WSW 0.000 0.061 0.145 0.036 0.000 0.000 0.000 0.24 W

0.000 0.012 0.121 0.000 0.000 0.000 0.000 0.13 WNW 0.000 0.024 0.145 0.048 0.000 0.000 0.000 0.22 NW 0.000 0.024 0.145 0.073 0.024 0.000 0.000 0.27 NNW 0.000 O.000 0.085 0.048 0.012 0.000 0.000 0.15 TOTAL 0.000 0.629 2.372 0.690 0.048 0.000 0.000 3.74 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS D UMAX (MIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.007 0.206 3.255 0.714 0.024

0. 000 0.000 4.21 NNE 0.030 0.835 2.819 0.085 0.000 0.000 0.000 3.77 NE 0.030 0.847 0.908 0.000

0. 000 0.000 0.000 1.78 ENE 0.038 1.053 0.895 0.000 0.000 0.000 0.000 1.99 E

0.031 0.883 0.714 0.024 0.000 0.000 0.000 1.65 ESE 0.021 0.593 0.387 0.061 0.000 0.000 0.000 1.06 SE 0.019 0.532 0.363 0.121 0.000 0.000 0.000 1.04 SSE 0.024 0.678 1.658 0.484 0.000 0.000 0.000 2.84 S

0.016 0.448 2.251 1.162 0.097 0.000 0.000 3.97 SSW 0.019 0.532 0.859 0.242 0.000 0.000 0.000 1.65 SW 0.015 0.399 0.653 0.109 0.000 0.000 0.000 1.18 WSW 0.018 0.496 0.424 0.048 0.000 0.000 0.000 0.99 W

0.012 0.327 0.460 0.073 0.012 0.000 0.000 0.88 WNW 0.012 0.327 0.496 0.133 0.024 0.000 0.000 0.99 NW 0.008 0.254 0.859 0.303 0.085 0.024

0. 000 1.53 NNW TOTAL 0.002 0.304 0.085 8.494 0.799 17.800 0.666 4.223 0.061 0.303 0.012 0.036 0.000 0.000 1.62 31.16

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 32 of 44 TABLE VI-A JOINT OCCURRFNCE FRFOUFNCIFS FOR LOWNDDFG AND lOWNDSPD - CONTINUOUS RFLEASES JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS E UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.067 0.581 0.520 0.024 0.000 0.000 0.000 1.19 NNE 0.063 0.557 0.230

0. 000

0. 000 0.000 0.000 0.85 NE 0.067 0.581 0.097 0.000 0.000 0.000 0.000 0.74 ENE 0.052 0.460 0.073 0.000 0.000 0.000 0.000 0.58 E

0.041 0.363 0.036 0.000 0.000 0.000 0.000 0.44 ESE 0.033 0.290 0.036 0.000 0.000 0.000 0.000 0.36 SE 0.3034

0. 303 0.097 0.012 0.000 0.000 0.000 0.45 SSE 0.139 1.222 0.956 0.036 0.000 0.000 0.000 2.35 S

0.236 2.081 1.682 0.278 0.036 0.000 0.000 4.31 SSW 0.185 1.634 1.186 0.157 0.000 0.000 0.000 3.16 SW 0.160 1.404 0.702 0.036 0.000 0.000 0.000 2.30 WSW 0.088 0.774 0.206 0.012 0.000 0.000 0.000 1.08 W

0.063 0.557 0.133 0.000 0.000 0.000 0.000 0.75 WNW 0.054 0.484 0.254 0.024 0.000 0.000 0.000 0.82 NW 0.048 0.424 0.629 0.157 0.024 0.000 0.000 1.28 NNW TOTAL 0.024 1.354 0.218 11.931 0.944 7.781 0.520 1.258 0.000 0.061 0.000 0.000 0.000 0.000 1.71 22.38 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS F UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.076 0.206 0.024 0.000 0.000 0.000 0.000 0.31 NNE 0.031 0.085 0.000 0.000 0.000 0.000 0.000 0.12 NE 0.050 0.133 0.000 0.000 0.000 0.000 0.000 0.18 ENE 0.018 0.048 0.000 0.000 0.000 0.000 0.000 0.07 E

0.008 0.024 0.000 0.000 0.000

0. 000

0. 000 0.03 ESE 0.041 0.109 0.000 0.000 0.000 0.000 0.000 0.15 SE

0. 031 0.085 0.000 0.000 0.000 0.000 0.000 0.12 SSE 0.235 0.629 0.109 0.000 0.000 0.000 0.000 0.97 S

0.416 1.113 0.073 0.000 0.000 0.000 0.000 1.60 SSW 0.362 0 968 0.061 0.000

0. 000 0.000 0.000 1.39 SW 0.180 0.484 0.133 0.000 0.000 0.000 0.000 0.80 WSW 0.185 0.496 0.000 0.000 0.000 0.000 0.000 0.68 W

0.149 0.399 0.000 0.000 0.000 0.000 0.000 0.55 WNW 0.086 0.230 0.024 0.000 0.000 0.000 0.000 0.34 NW 0.195 0.520 0.448 0.024

0. 000

0. 000 0.000 1.19 NNW 0.113 0.303 0.605 0.036 0.000 0.000 O. 000 1.06 TOTAL 2.177 5.832 1.476 0.061 0.000 0.000 0.000 9.55 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS G UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.047 0.036 0.000 0.000 0.000 0.000 0.000 0.08 NNE 0.031 0.024 0.000 0.000 0.000 0.000 0.000 0.06 NE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 E

0.016

0. 012

0. 000

0. 000 0.000

0. 03 ESE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 SE

0. 174 0.133 0.000 0.000 0.000 0.000 0.000 0.31 SSE 0.790 0.605 0.012 0.000 0.000 0.000 0.000 1.41 S

0.759 0.581 0.000 0.000 0.000 0.000 0.000 1.34 SSW 0.490 0.375 0.012 0.000 0.000 0.000 0.000 0.88 SW 0.411 0.315 0.024 0.000 0.000 0.000 0.000 0.75 WSW 0.347 0.266 0.000 0.000 0.000 0.000 0.000 0.61 W

0.284 0.218 0.000 0.000 0.000 0.000 0.000 0.50 WNW 0.396 0.303 0.012 0.000 0.000 0.000 0.000 0.71 NW 1.154 0.883 0.085 0.000 0.000 0.000 0.000 2.12 NNW TOTAL 0.617 5.518 0.472 4.223 0.242 0.387 0.012 0.012 0.000 0.000 0.000 0.000 0.000 0.000 1.34 10.14 TOTAL HOURS CONSIDERED ARE 8264.

WIND MEASURED AT 11.0 METERS.

OVERALL WIND DIRECTION FREQUENCY WIND DIRECTION:

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTAL FREQUENCY:

7.9 7.2 4.6 4.1 3.6 2.7 3.3 9.4 13.1 9.5 7.3 5.2 4.0 4.2 7.3 6.7 100.0

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 33 of 44 VII.

METEOROLOGICAL DATA B.

Mixed Mode Batch Release Diffusion Analysis Table VII-B presents the number and frequency of wind direction occurrences by wind speed class as recorded at the onsite meteorological system during mixed mode batch releases for the period January 1, 2002, through December 31, 2002.

The frequencies are presented as a percent of total occurrences for each stability class as well as a summary for all classes for the lower (11 meter) sensor elevation.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 34 of 44 nt o1ss n wAn t

Arw tnnnvsr rintwAsttelsC rAn

^s-lXlT\\er xvver woree n A>rrvz vel eA cec IAULEVII-B JUNI UOjtURRNtEFREIUEN1iIFtUK WWNDDFJGAINDU)WIDW-MIAW MUL'r.llA JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS A UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0. 000 0.106 1.056 0.211 0.000 0.000 0.000 1.37 NNE 0.000 0.000 0.739 0.106 0.000 0.000 0.000 0.85 NE 0.021 0.739 0.423 0.000 0.000 0.000 0.000 1.18 ENE 0.011 0.211 0.423 0.000 0.000 0.000 0.000 0.64 E

0.021 0.634 0.423 0.000 0.000 0.000 0.000 1.08 ESE 0.021 0.739 0.317 0.000 0.000 0.000 0.000 1.08 SE 0.011 0.528 0.845 0.000 0.000 0.000 0.000 1.38 SSE 0.000 0.106 0.528 0.000 0.000 0.000 0.000 0.63 S

0.000

0. 000 0.423 0.528 0.211 0.000 0.000 1.16 SSW 0.000 0.106 1.268 0.528 0.000 0.000 0.000 1.90 SW 0.000 0.106 1.373 0.423 0.000 0.000 0.000 1.90 WSW 0.011 0.423 0.845 0.000 0.000 0.000 0.000 1.28 W

0.011 0.211 1.162 0.000 0.000 0.000 0.000 1.38 WNW 0.000 0.106 0.845 0.000 0.000 0.000 0.000 0.95 NW 0.000 0.000 0.211 0.000 0.000 0.000 0.000 0.21 NNW TOTAL 0.000 0.106 0.000 4.014 0.211 11.091 0.106 1.901 0.000 0.211 0.000 0.000 0.000 0.000 0.32 17.32 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS B UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0. 000

0. 000 0.211 0.106 0.000 0.000 0.000 0.32 NNE 0.000 0.106 0.000 0.000 0.000 0.000 0.000 0.11 NE 0.000 0.317 0.106 0.000 0.000 0.000 0.000 0.42 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 E

0.000 0.106 0.211 0.000 0.000 0.000 0.000 0.32 ESE 0.000 0.106 0.106 0.000 0.000 0.000 0.000 0.21 SE 0.000 0.106 0.000 0.000 0.000 0.000 0.000 0.11 SSE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 S

0. 000 0.106 0.211 0.211 0.106

0. 000

0. 000 0.63 SSW 0.000 0.000 0.106 0.317 0.000 0.000 0.000 0.42 SW 0.000 0.211 0.000 0.000 0.000 0.000 0.000 0.21 WSW 0.000 0.000 0.317 0.000 0.000

0. 000 0.000 0.32 W

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 WNW 0.000 O.000 0.106 0.000 0.000 0.000 0.000 0.11 NW 0.000 0.000 0.211 0.000 0.000 0.000 0.000 0.21 NNW 0.000 0.000 0.000 0.106 0.000 0.000 0.000 0.11 TOTAL 0.000 1.056 1.584 0.739 0.106 0.000 0.000 3.49 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS C UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.000 0.000

0. 000 0.106 0.000 0.000 0.000 0.11 NNE 0.000 O.000 0.106 0.000

0. 000 0.000 0.000 0.11 NE 0.000 0.211 0.106 0.000 0.000 0.000 0.000 0.32 ENE 0.000 0.106 0.211 0.000 0.000 0.000 0.000 0.32 E

0.000 0.000 0.106 0.000 0.000 0.000 0.000 0.11 ESE 0.000 0.000 0.211 0.000 0.000 0.000 0.000 0.21 SE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 SSE 0.000 0.000 0.106 0.106 0.000 0.000 0.000 0.21 S

0.000

0. 000 0.211 0.106

0. 000 0.000 0.000 0.32 SSW 0.000 0.000 0.317 0.106 0.000 0.000 0.000 0.42 SW 0.000 0.000 0.000 0.106 0.000 0.000 0.000 0.11 WSW

0. 000 0.106 0.106 0.000 0.000 0.000 0.000 0.21 W

0.000 0.106 0.000 0.106 0.000 0.000 0.000 0.21 WNW 0.000 O.000 0.211 0.000 0.000 0.000 0.000 0.21 NW 0.000 0.000 0.317 0.000 0.000 0.000 0.000 0.32 NNW 0.000 O.000 0.211 0.106 0.000 0.000 0.000 0.32 TOTAL 0.000 0.528 2.218 0.739 0.000 0.000 0.000 3.49 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS D UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.000

0. 000 2.218 0.845 0.106 0.000 0.000 3.17 NNE 0.053 0.528 1.901 0.000 0.000 0.000 0.000 2.48 NE 0.106 1.056 0.951 0.000

0. 000 0.000 0.000 2.11 ENE 0.190 1.901 0.317 0.000 0.000 0.000 0.000 2.41 E

0.106 1.056 1.056 0.000 0.000 0.000 0.000 2.22 ESE 0.042 0.423 0.317 0.000 0.000 0.000 0.000 0.78 SE 0.032 0.317 0.211 0.317 0.000 0.000 0.000 0.88 SSE 0.063 0.634 2.852 0.845 0.000 0.000 0.000 4.39 S

0.042

0. 423 3.486 1.056 0.106 0.000 0.000 5.11 SSW 0.032 0.317 1.056 0.634 0.000 0.000 0.000 2.04 SW 0.032 0.317 0.739 0.106

0. 000 0.000

0. 000 1.19 WSW 0.042 0.423 0.423 0.000 0.000 0.000 0.000 0.89 W

0.074 0.739 1.056 0.106 0.000

0. 000 0.000 1.98 WNW 0.032 0.317 0.317 0.000 0.000 0.000 0.000 0.67 NW 0.000 0.000 0.528 0.106 0.000 0.000 0.000 0.63 NNW TOTAL 0.011 0.856 0.106 8.556 0.423 17.851 0.634 4.648 0.000 0.211 0.000 0.000 0.000 0.000 1.17 32.12

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RAi/03-0053 Page 35 of 44 TABLE VII-B JOINT OCCURRENCE FREOUENCIES FOR LOWNDDEG AND LOWNDSPD - MIXED MODE BATCII RELEASFS JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS E UMAX (MIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

NNE NE ENE E

ESE SE SSE 0.106 0.951 0.634 0.000 0.000 0.000 0.000 1.69 0.074 0.634 0.317 0.000 0.000 0.000 0.000 1.02 0.053 0.423 0.000 0.000 0.000 0.000 0.000 0.48 0.085 0.739 0.106 0.000 0.000

0. 000 0.000 0.93 0.148 1.268 0.000 0.000 0.000 0.000 0.000 1.42 0O.011 0.106 0.106 0.000 0.000 0.000 0.000 0.22 0.074 0.634 0.000 0.000 0.000 0.000 0.000 0.71 0.190 1.690 1.373 0.106 0.000 0.000 0.000 3.36 S

SSW SW 0.317 0.180 0.201 2.746 1.584 1.796 2.641 2.218 1.584 0.317 0.317 0.211 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 6.02 4.30 3.79 WSW 0.106 0.951 0.634 0.000 0.000 0.000 0.000 1.69 W

0.032 0.317 0.317 0.000 0.000 0.000 0.000 0.67 WNW 0.063 0.528 0.106 0.000 0.000 0.000 0.000 0.70 NW 0.032 0.317 0.211 0.106 0.000 0.000 0.000 0.67 NNW TOTAL 0.011 1.680 0.106 14.788 0.423 10.669 0.845 1.901 0.000 0.000 0.000 0.000 0.000 0.000 1.38 29.04 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS F UMAX (MIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0. 095 0.211 0.106 0.000 0.000 0.000 0.000 0.41 NNE 0.053 0.106 0.000 0.000 0.000 0.000 0.000 0.16 NE 0.053 0.106 0.000 0.000 0.000 0.000 0.000 0.16 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 E

0.053 0.106 0.000 0.000 0.000 0.000 0.000 0.16 ESE 0.053 0.106 0.000 0.000 0.000 0.000 0.000 0.16 SE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 SSE 0.095 0.211 0.317 0.000 0.000 0.000 0.000 0.62 S

0.391 0.845 0.106 0.000 0.000 0.000 0.000 1.34 SSW 0.349 0.739 0.106 0.000 0.000 0.000 0.000 1.19 SW 0.148 0.317 0.528

0. 000 0.000 0.000 0.000 0.99 WSW 0.243 0.528 0.000 0.000 0.000 0.000 0.000 0.77 W

0.148 0.317 0.000 0.000 0.000 0.000 0.000 0.46 WNW 0.148 0.317 0.106 0.000 0.000 0.000 0.000 0.57 NW 0.095 0.211 0.317 0.106 0.000 0.000 0.000 0.73 NNW 0.201 0.423 0.317 0.000 0.000 0.000 0.000 0.94 TOTAL 2.123 4.542 1.901 0.106 0.000 0.000 0.000 8.67 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS G UMAX (MIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.137 0.106 0.000 0.000 0.000 0.000 0.000 0.24 NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000

0. 00 NE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 ENE 0.000 0.000 0.000

0. 000 0.000 0.000 0.000 0.00 E

0.137 0.106 0.000 0.000 0.000 0.000 0.000 0.24 ESE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 SE 0.137 0.106 0.000 0.000 0.000 0.000 0.000 0.24 SSE 0.285 0.211 0.000 0.000 0.000 0.000 0.000 0.50 S

0. 137 0.106 0.000 0.000 0.000 0.000 0.000 0.24 SSW 0.570 0.423 0.106

0. 000

0. 000 0.000 0.000 1.10 SW 0.423 0.317 0.106 0.000 0.000 0.000 0.000 0.85 WSW 0.423 0.317 0.000 0.000 0.000 0.000 0.000 0.74 W

0.137 0.106

0. 000 0.000

0. 000

0. 000 0.24 WNW 0.423 0.317

0. 000 0.000

0. 000

0. 000 0.000 0.74 NW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NNW 0.423 0.317 0.000 0.000 0.000 0.000 0.000 0.74 TOTAL 3.232 2.429 0.211 0.000 0.000 0.000 0.000 5.87 TOTAL HOURS CONSIDERED ARE 947.

WIND MEASURED AT 11.0 METERS.

OVERALL WIND DIRECTION FREQUENCY WIND DIRECTION:

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTAL FREQUENCY:

7.3 4.7 4.7 4.3 5.5 2.7 3.3 9.7 14.8 11.4 9.0 5.9 4.9 3.9 2.8 5.0 100.0

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 36 of 44 VII.

METEOROLOGICAL DATA C.

Ground Level Batch Release Diffusion Analysis Table VII-C presents the number and frequency of wind direction occurrences by wind speed class as recorded at the onsite meteorological system during ground level batch releases for the period January 1, 2002, through December 31, 2002.

The frequencies are presented as a percent of total occurrences for each stability class as well as a summary for all classes for the lower (11 meter) sensor elevation.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 37 of 44 TABLE VI1-C JOINT OCCURRENCE FREQUENCIES FOR LOWNDDEG AND LOWNDSPD - GROUND LEVEL BATCH RELEASFS JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS A UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.000 0.119 1.189 0.238

0. 000 0.000

0. 000 1.55 NNE 0.000 0.000 0.357 0.000 0.000 0.000 0.000 0.36 NE 0.024 0.595 0.357

0. 000 0.000 0.000 0.000 0.98 ENE 0.012 0.238 0.476

0. 000 0.000 0.000 0.000 0.73 E

0.024 0.714 0.476 0.000 0.000 0.000 0.000 1.21 ESE 0.024 0.714 0.357 0.000 0.000 0.000 0.000 1.09 SE

0. 012 0.476 0.951 0.000 0.000 0.000 0.000 1.44 SSE 0.000 0.119 0.476 0.000 0.000 0.000 0.000 0.59 S

0.000 0.000 0.357 0.476 0.238 0.000 0.000 1.07 SSW 0.000 0.119 1.427 0.595 0.000 0.000 0.000 2.14 SW 0.000 0.000 1.546 0.476 0.000 0.000 0.000 2.02 WSW 0.012 0.238 0.951 0.000 0.000 0.000 0.000 1.20 W

0.000 0.119 1.189 0.000 0.000 0.000 0.000 1.31 WNW 0.000 0.476 0.000 0.000 0.000 0.48 NW 0.000 0.000 0.238 0.000

0. 000

0. 000 0.24 NNW TOTAL 0.000 0.107 0.000 3.449 0.238 11.061 0.119 1.903 0.000 0.238 0.000 0.000 0.000 0.000 0.36 16.76 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS B UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.000 0.000 0.238 0.119 0.000 0.000 0.000 0.36 NNE 0.000 0.119 0.000 0.000 0.000 0.000 0.000 0.12 NE 0.000 0.357 0.119

0. 000 0.000 0.000 0.000 0.48 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 E

0.000 0.000 0.238 0.000 0.000 0.000 0.000 0.24 ESE 0.000 0.000 0.119 0.000 0.000 0.000 0.000 0.12 SE 0.000 0.119 0.000 0.000 0.000 0.000 0.000 0.12 SSE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 S

0.000 0.119 0.238 0.119 0.119 0.000 0.000 0.59 SSW 0.000 0.000 0.119 0.357 0.000 0.000 0.000 0.48 SW 0.000 0.238 0.000 0.000 0.000 0.000 0.000 0.24 WSW 0.000 0.000 0.357 0.000 0.000 0.000 0.000 0.36 W

0.000 0.000 0.000 0.000 0.000 0.000 0.000

0. 00 WNW 0.000 0.000 0.119 0.000 0.000 0.000 0.000 0.12 NW 0.000 0.000 0.119 0.000

0. 000 0.000 0.000 0.12 NNW 0.000 0.000 O.000 0.119 0.000 0.000 0.000 0.12 TOTAL 0.000 0.951 1.665 0.714 0.119

0. 000 0.000 3.45 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS C UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.000 0.000 0.000 0.119 0.000 0.000 0.000 0.12 NNE 0.000 0.000 0.119 0.000 0.000 0.000 0.000 0.12 NE 0.000 0.238 0.119 0.000

0. 000 0.000 0.000 0.36 ENE 0.000 0.119 0.238 0.000 0.000 0.000 0.000 0.36 E

0.000 0.000 0.119 0.000 0.000 0.000 0.000 0.12 ESE 0.000 0.000 0.238 0.000 0.000 0.000 0.000 0.24 SE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 SSE 0.000 0.000 0.119 0.119 0.000 0.000 0.000 0.24 S

0.000 0.000 0.238 0.000 0.000 0.000 0.000 0.24 SSW 0.000 0 000 0.357 0.119 0.000 0.000 0.000 0.48 SW 0.000 0.000 0.000 0.119 0.000 0.000 0.000 0.12 WSW 0.000 0.119 0.119 0.000 0.000 0.000 0.000 0.24 W

0. 000 0.119 0.000 0.119 0.000 0.000 0.000 0.24 WNW 0.000 0.238 0.000 0.000 0.000 0.000 0.24 NW 0.000 0.000 0.357 0.000 0.000

0. 000

0. 000 0.36 NNW 0.000 O.000 0.238 0.119 0.000 0.000 0.000 0.36 TOTAL 0.000 0.595 2.498 0.714 0.000 0.000 0.000 3.81 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS D UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.000 0.000 1.903 0.951 0.119 0.000 0.000 2.97 NNE 0.059 0.595 2.022 0.000 0.000 0.000 0.000 2.68 NE 0.131 1.189 1.070 0.000 0.000 0.000

0. 000 2.39 ENE 0.214 2.022 0.357 0.000

0. 000 0.000 0.000 2.59 E

0.131 1.189 1.189 0.000 0.000 0.000 0.000 2.51 ESE 0.048 0.476 0.357 0.000 0.000 0.000 0.000 0.88 SE 0.036 0.357 0.238 0.357 0.000 0.000

0. 000 0.99 SSE 0.059 0.595 3.092 0.951 0.000 0.000 0.000 4.70 S

0.024 0.238 2.617 1.070 0.119 0.000 0.000 4.07 SSW 0.036 0.357 1.070 0.714 0.000 0.000 0.000 2.18 SW 0.036 0.357 0.833 0.119 0.000 0.000 0.000 1.34 WSW 0.036 0.357 0.476 0.000 0.000 0.000 0.000 0.87 W

0.071 0.714 1.189 0.119 0.000 0.000 0.000 2.09 WNW 0.024 0.238 0.238 0.000 0.000 0.000 0.000 0.50 NW 0.000

0. 000 0.595 0.119 0.000 0.000 0.000 0.71 NNW TOTAL 0.012 0.916 0.119 8.801 0.476 17.721 0.714 5.114 0.000 0.238 0.000 0.000 0.000 0.000 1.32 32.79

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 38 of 44 TABLE Vn-C JOINT OCCURRENCE FREOUENCTFS FOR LOWNDDFG AND LOWNDSPD. GROUND LEVEL BATCH RELEASES JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS E UMAX (MIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.107 0.833 0.714 0.000 0.000 0.000 0.000 1.65 NNE 0.095 0.714 0.357 0.000 0.000 0.000 0.000 1.17 NE 0.048 0.357 0.000 0.000 0.000 0.000 0.000 0.40 ENE 0.107 0.833 0.119 0.000 0.000 0.000 0.000 1.06 E

0.178 1.427 0.000

0. 000 0.000

0. 000 0.000 1.61 ESE 0.012 0.119 0.119 0.000 0.000 0.000 0.000 0.25 SE 0.095 0.714 0.000 0.000 0.000 0.000 0.000 0.81 SSE 0.190 1.546 1.546 0.119 0.000 0.000 0.000 3.40 S

0. 309 2.498 2.617 0.357 0.000 0.000 0.000 5.78 SSW 0.214 1.665 2.498 0.357 0.000 0.000 0.000 4.73 SW 0.250 2.022 1.784 0.238 0.000 0.000 0.000 4.29 WSW 0.131 1.070 0.714 0.000 0.000 0.000 0.000 1.91 W

0.048 0.357 0.357 0.000 0.000 0.000 0.000 0.76 WNW 0.071 0.595 0.119 0.000 0.000 0.000 0.000 0.78 NW 0.048 0.357 0.119 0.119 0.000 0.000 0.000 0.64 NNW TOTAL 0.012 1.915 0.119 15.224 0.357 11.418 0.833 2.022 0.000 0.000 0.000 0.000 0.000 0.000 1.32 30.58 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS F UMAX (MIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.059 0.119 0.119 0.000 0.000 0.000 0.000 0.30 NNE 0.059 0.119 0.000 0.000 0.000 0.000 0.000 0.18 NE 0.059 0.119 0.000 0.000 0.000 0.000 0.000 0.18 ENE 0.000 0.000

0. 000 0.000 0.000 0.000 0.000 0.00 E

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 ESE 0.059 0.119 0.000 0.000 0.000 0.000 0.000 0.18 SE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 SSE 0.059 0.119 0.357 0.000 0.000 0.000 0.000 0.54 S

0.404 0.833 0.000 0.000 0.000 0.000 0.000 1.24 SSW 0.404 0.833 0.119 0.000 0.000 0.000 0.000 1.36 SW 0.178 0.357 0.476 0.000 0.000 0.000 0.000 1.01 WSW 0.226 0.476 0.000 0.000 0.000 0.000 0.000 0.70 W

0.178 0.357 0.000 0.000 0.000 0.000 0.000 0.54 WNW 0.059 0.119 0.119

0. 000

0. 000 0.000 0.30 NW 0.059 0.119 0.238 0.119 0.000 0.000 0.000 0.54 NNW 0.119 0.238 0.238 0.000 0.000 0.000 0.000 0.59 TOTAL 1.927 3.925 1.665 0.119 0.000 0.000 0.000 7.64 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS G UMAX (MIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N

0.107 0.119 0.000 0.000 0.000 0.000 0.000 0.23 NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000

0. 00 NE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 ENE 0.000 0.000

0. 000 0.000 0.000 0.000 0.000 0.00 E

0.107 0.119 0.000 0.000 0.000 0.000 0.000 0.23 ESE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 SE 0.107 0.119 0.000 0.000 0.000 0.000 0.000 0.23 SSE 0.214 0.238 0.000 0.000 0.000 0.000 0.000 0.45 S

0. 107 0.119 0.000 0.000 0.000 0.000 0.000 0.23 SSW 0.428 0.476 0.119 0.000 0.000 0.000 0.000 1.02 SW 0.321 0.357 0.119 0.000 0.000 0.000 0.000 0.80 WSW 0.214 0.238 0.000 0.000 0.000 0.000 0.000 0.45 W

0.107 0.119 0.000 0.000 0.000 0.000 0.000 0.23 WSNW 0.214 0.238 0.000 0.000 0.000 0.000 0.000 0.45 NW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NNW 0.321 0.357 0.000 0.000 0.000 0.000 0.000 0.68 TOTAL 2.248 2.498 0.238 0.000 0.000 0.000 0.000 4.98 TOTAL HOURS CONSIDERED ARE 841.

WIND MEASURED AT 11.0 METERS.

OVERALL WIND DIRECTION FREQUENCY WIND DIRECTION:

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTAL FREQUENCY:

7.2 4.6 4.8 4.7 5.9 2.8 3.6 9.9 13.2 12.4 9.8 5.7 5.2 2.9 2.6 4.7 100.0

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 39 of 44 CHANGES TO ODCM, PCP, AND RADIOACTIVE WASTE SYSTEMS TABLE OF CONTENTS Description.........

Page I.

Changes to the Offsite Dose Calculation Manual.40 II.

Changes to the Radioactive Waste Systems.41 111.

Changes to the Process Control Program.42 IV.

Changes to the Land Use Census.42 V.

Instrument Inoperability.42 VI.

Liquid Holdup Tank Curie Limit.42 VII.

Waste Gas Decay Tank Curie Limit.42

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 40 of 44 I.

CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

There were changes to the ODCM during this reporting period. A summary of the changes are shown below. A complete copy of the updated ODCM is being forwarded under separate letter.

ODCM REVISION 20 DESCRIPTION OF CHANGE There was only one change to the ODCM in revision 20. Table 2.6-1, Item 2.b was revised to clarify the applicability of the specification and the associated compensatory measures.

Specifically, the change clarifies the required actions for estimating Steam Generator blowdown flow when at least a portion of the flow is to the blowdown flash tank.

ODCM REVISION 21 DESCRIPTION OF CHANGE There were several programmatic changes to the ODCM made in revision 21. A brief statement of each is included below.

1. Requirements for particulate and iodine sampling of the new Outage Contaminated Storage Building Exhaust were added to the appropriate tables in Section 3 since the exhaust is a potential release point for gaseous effluents. No sampling requirement for tritium or noble gas is necessary because no tritium or noble gas source term exists in the warehouse. This is consistent with the surveillance requirements in effect for the Radwaste Building Exhaust where a similar type of effluent is possible.

2. Tables 3.10-1 and 3.12-1 specify the requirements for Radioactive Gaseous Effluent Monitoring Instrumentation and the Radioactive Gaseous Waste Sampling and Analysis Program, respectively. A note was added to each of these tables to clarify the requirements for continuous particulate and iodine sampling. Specifically, the note states "no auxiliary sampling is required for periods when normal sampling is off < 45 minutes." The purpose of this note is to allow time for routine activities such as sample filter changes and sample pump maintenance without initiating compensatory actions.

3. Table 4.1-3 specifies the lower limits of detection that are required for the analysis of various environmental sample media.

a. The LLD requirement for I-13 1 in water was changed from 1 picocurie per liter to 15 picocuries per liter. The requirement to meet the 1 picocurie per liter sensitivity applies only to drinking water pathways. RNP liquid effluents do not supply any drinking water pathways. (Reference NUREG-1301).

b. Note (b.) to this table was added to clarify the LLD requirement for Ba-La-140 and Zr-Nb-95 transient equilibrium mixtures. The note explains that the LLD applies to the daughter nuclide. By meeting the LLD for the daughter nuclide it can be derived that the parent LLD has also been met.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 41 of 44

4. Table 4.5-1, H.B. Robinson Radiological Environmental Monitoring Program, has several changes in Revision 21:

a. The sample point descriptions were changed to make their formats more consistent and to reflect more accurate distance and direction data obtained by new GPS equipment.

b. Two new air sampling stations and one broad leaf sample point were added based on the review of the 10-year average meteorological data.

c. The control sample for fish was changed to 'any lake not influenced by plant discharge' to avoid specifying a lake which may be inaccessible.

5. The acceptance criteria for the Interlaboratory Comparison Studies, required by the ODCM Section 5, were changed from the present 3-sigma criteria to the criteria set forth in NRC Inspection Procedure 84750 for confirmatory measurements. The use of the present 3-sigma criteria for acceptability of interlaboratory QC results dates back to when the EPA Crosscheck program existed. At that time there were enough participants in the program to provide for good statistical analysis. Since the end of the EPA Crosscheck program, the nuclear utilities have participated in other equivalent programs. However, the number of participants in a particular program typically is not sufficient to provide a good statistical sampling. Such is the case with the Analytics Crosscheck Program with which the HEEC Laboratories participate.

ODCM REVISION 22 DESCRIPTION OF CHANGE Revision 22 to the ODCM added Note 2 to Table 3.10-1, Radioactive Gaseous Effluent Monitoring Instrumentation, which changed the monitoring requirements for Containment Vessel releases. The containment atmosphere radiation monitors, R-1 1 and R-12, are now "... required during Modes 1, 2, 3, 4, and during the movement of recently irradiated fuel assemblies within the containment." This change brings the ODCM into closer alignment with the requirements of the recently changed plant Technical Specifications.

II.

CHANGES TO THE RADIOACTIVE WASTE SYSTEMS There were no changes to the Radioactive Waste System during this reporting period.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 42 of 44

m.

CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

There was a change to the PCP during this reporting period. Revision 5 to the PCP was largely administrative in nature and was effective on April 19, 2002. A brief description of the change follows:

1. The responsibilities for the Manager - E&RC were replaced by the Superintendent - RC in sections 3.1.2, 3.1.3, 3.2.3, 3.2.4, and 4.1.

2. The responsibilities for the Superintendent - RC were replaced by the RC Supervisor with accountability for radioactive waste processing in Section 3.1.3.

3. The references to HBR Technical Specifications were deleted because the PCP references have been relocated to the Technical Requirements Manual.

4. A note and a step have been added concerning the requirements to be met if the initial test specimen from a batch of waste fails to verify solidification.

5. Minor editorial and clerical corrections were made throughout the PCP.

IV.

CHANGES TO THE LAND USE CENSUS The results of the 2002 Land Use Census, closest residents, gardens, milk producing animals, or meat/egg laying animals, noted no changes that require an ODCM change, additional dose calculations, or procedure changes. A review of the 10-year average meteorological data found that three new sample stations needed to be added to the ODCM. Air particulate/air charcoal (APAC) units were placed in the southeast and west-southwest sectors and an additional broadleaf sample location was added in the southeast sector.

V.

INSTRUMENT INOPERABILITY There were no reportable instrumentation inoperability events during this reporting period.

VI.

LIQUID HOLDUP TANK CURIE LIMIT There were no outside liquid holdup tanks that exceeded the ten curie limit during this reporting period.

VII.

WASTE GAS DECAY TANK CURIE LIMIT There were no waste gas decay tanks with a curie content that exceeded the 1.90E+04 curie limit during this reporting period.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 43 of 44 SUPPLEMENTS TO PREVIOUS REPORTS TABLE OF CONTENTS Description Page I.

DISCUSSION.44

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0053 Page 44 of 44 I.

DISCUSSION There are no corrections to previous reports.

TS 5.5.1 Progress Energy Serial: RNP-RA/03-0054 APR 2 9 2003 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 ANNUAL OFF-SITE DOSE CALCULATION MANUAL SUBMITTAL Ladies and Gentlemen:

Enclosed is a copy of the Off-Site Dose Calculation Manual (ODCM), which includes changes made during the period of January 1, 2002, through December 31, 2002, for H. B. Robinson Steam Electric Plant (IIBRSEP), Unit No. 2. This report is submitted in accordance with HBRSEP, Unit No. 2, Technical Specifications (TS), Section 5.5.1(c)(3). This is a supplement to the 2002 Annual Radioactive Effluent Release Report provided in the HBRSEP, Unit No. 2, letter dated April 29, 2003 (Serial: RNP-RA/03-0053).

If you have any questions concerning this report, please contact me.

Sincerely, C. T. Baucom Supervisor - Licensing/Regulatory Programs RAC/rac Enclosure C:

Mr. L. A. Reyes, NRC, Region II Mr. C. P. Patel, NRR, NRC (w/o enclosure)

NRC Resident Inspector, HBRSEP Progress Energy Carolinas, Inc 3581 West Entrance Road Hartsville, SC 29550

United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/03-0054 252 Pages Including Cover Page H. B. Robinson Steam Electric Plant, Unit No. 2 OFF-SITE DOSE CALCULATION MANUAL (Including changes made from January 1 to December 31, 2002)

CAROLINA POWER & LIGHT COMPANY H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 OFF-SITE DOSE CALCULATION MANUAL (ODCM)

Revision 22 DOCKET NO. 50-261 EFFECTIVE DATE:

hlD oD2 REVIEWED BY:

APPROVED BY:

PNSi Chairmaf' P4NT MANAGER DATE:

l oC o r0Z DATE:

Ic ocroc

LIST OF EFFECTIVE PAGES EFFECTIVE PAGES REVISION Cover Sheet............

22 LEP.22 Table of Contents...........

19 List of Tables.19 List of Figures.21 1-1.......................

19 2-1 through 2-24.19 2-25 through 2-26.20 2-27 through 2-38.19 3-1 through 3-84.............

19 3-85.21 3-86 through 3-87.22 3-88 through 3-91.21 3-92.22 3-93.19 3-94.21 3-95 through 3-96.19 3-97.21 3-98.19 3-99.21 3-100 through 3-102.19 4-1 through 4-5.19 4-6.21 4-7 through 4-8.1 9

4-.9.21 4-10.19 4-11.21 4-12 through 4-14.19 4-15 through 4-22.21 4-23.21 4-24 through 4-25.21 5-1.19 5-2 through 5-3.21 6-1 through 6-5.19 7-1 through 7-3.19 7-4.19 7-5.1 9

8-1 through 8-4.19 9-1 through 9-6.19 A-i through A-26.19 B-i through B-16.19 C-i through C-4.19 D-1 through 0-4.19 HBRODCM i

Rev. 22

TABLE OF CONTENTS Section Title Pagqe LIST OF EFFECTIVE PAGES...........................................................

i TABLE OF CONTENTS...........................................................

ii LIST OF TABLES...........................................................

iv LIST OF FIGURES...........................................................

vii

1.0 INTRODUCTION

1-1 2.0 LIQUID EFFLUENTS.........................................................

2-1 2.1 Monitor Alarm Setpoint Determination.......................................

2-1 2.2 Requirements for Compliance with 10 CFR 20 (Liquids).......................................

2-8 2.3 Compliance with 10 CFR 20 (Liquids).......................................

2-10 2.4 Requirements for Compliance with 10 CFR 50 (Liquids).......................................

2-15 2.5 Compliance with 10 CFR 50 (Liquids).......................................

2-17 2.6 Radioactive Liquid Monitoring Instrumentation.

2-23 2.7 Radioactive Liquid Monitoring Instrumentation Surveillance Requirements.

2-30 2.8 Radioactive Liquid Effluents Sampling and Analysis Requirements.

2-33 2.9 Liquid Radwaste Treatment System...............................

2-37 3.0 GASEOUS EFFLUENTS...............................

3-1 3.1 Monitor Alarm Setpoint Determination..............................

3-1 3.2 Requirements for Compliance with 10 CFR 20 (Gaseous).........................................

3-13 3.3 Compliance with 10 CFR 20 (Gaseous).........................................

3-14 3.4 Requirements for Compliance with 10 CFR 50 (Gaseous).........................................

3-23 3.5 Compliance with 10 CFR 50 (Gaseous).........................................

3-25 3.6 Methodology for R-1 1 Setpoint (Air Particulate).........................................

3-75 3.7 Methodology for R-14A Setpoint (Particulate Monitor).........................................

3-77 3.8 Methodology for R-14B Setpoint (Iodine Monitor).........................................

3-79 3.9 Methodology for R-22 Setpoint Determination for the Iodine and Particulate Monitors.........................................

3-80 3.10 Radioactive Gaseous Effluent Monitoring Instrumentation..

3-83 3.11 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements..

3-93 3.12 Radioactive Gaseous Effluents Sampling and Analysis Requirements..

3-96 3.13 Radionoble Gases - Cumulative Doses..

3-99 3.14 Radioiodines, Radioactive Materials in Particulate Form, and Radionuclides Other Than Radionoble Gases - Cumulative Doses..

3-100 3.15 Gaseous Radwaste and Ventilation Exhaust Treatment Systems 3-101 HBRODCM 1i Rev. 1 9

TABLE OF CONTENTS (Continued)

Section Title Page 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

............................. 4-1 4.1 Monitoring Program - Implementation................................................

4-1 4.2 Land Use Census - Implementation................................................

4-12 4.3 Monitoring Program - Sampling Requirements..................................... 4-13 4.4 Land Use Census - Surveillance Requirements.....................................

4-14 4.5 Analysis and Sample Point Description.....................................

4-14 5.0 INTERLABORATORY COMPARISON PROGRAM 5-1 5.1 through 5.4 Specifications.

5-1 5.5 Interlaboratory Comparison Studies - Program Requirements.5-2 5.5.1 Objective.

5-2 5.6 Program................................

5-2 6.0 COMPLIANCE WITH 40 CFR 190................................

6-1 6.1 Requirements for Compliance With 40 CFR Part 190 - Radioactive Effluents From Uranium Fuel Cycle Sources................................

6-1 6.2 Total Dose (40 CFR 190) Conformance................................

6-3 6.3 Calculations of Total Body Dose................................

6-4 6.4 Thyroid Dose................................

6-5 6.5 Dose Projections................................

6-5 6.6 Radioactive Effluents From Uranium Fuel Cycle Sources - Cumulative Doses............... 6-5 7.0 DEFINITIONS..............................................................

7-1 8.0 CONTROLS AND SURVEILLANCE REQUIREMENTS............................................................ 8-1 8.1 Controls............................................................

8-1 8.2 Surveillance Requirements............................................................

8-2 9.0 REPORTING REQUIREMENTS............................................................ 9-1 9.1 Annual Radioactive Effluent Release Report......................................................

...... 9-1 9.2 Annual Radiological Environmental Operating Report......................................................

9-4 9.3 Special Radiological Effluent Reports............................................................

9-5 APPENDIX A - Meteorological Dispersion Factor Computations.

A-1 APPENDIX B - Dose Parameters for Radioiodines, Particulates, and Tritium.B-1 APPENDIX C - Lower Limit of Detectability.C-1 HBRODCM Has.

Rev.1 9

No.

2.5-1 2.6-1 2.7-1 2.8-1 3.1-1 3.1-2 3.3-1 3.3-2 3.3-3 3.3-4 3.5-1 thru 3.5-19 3.10-1 3.11-1 3.12-1 4.1-1 4.1-2 4.1-3 4.5-1 8.2-1 LIST OF TABLES Title Page Air Values for the Adult for the H.B. Robinson Steam Electric Plant.......................... 2-21 Radioactive Liquid Effluent Monitoring Instrumentation.............................................. 2-24 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements........................................................

2-31 Radioactive Liquid Waste Sampling and Analysis Program........................................ 2-34 Gaseous Source Terms........................................................

3-11 Dose Factors and Constants........................................................

3-12 Releases from H.B. Robinson Unit No. 2........................................................

3-18 Distance to Special Locations for the H.B. Robinson Plant (Mi.)................................ 3-19 Dose Factors for Noble Gases and Daughters........................................................

3-20 P, Values for a Child for the H.B. Robinson Unit No. 2................................................ 3-21 R Values for the H.B. Robinson Steam Electric Plant................................................. 3-37 thru 3-73 Radioactive Gaseous Effluent Monitoring Instrumentation......................................... 3-84 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements........................................................

3-94 Radioactive Gaseous Waste Sampling and Analysis Program................................... 3-97 Radiological Environmental Monitoring Program........................................................

4-5 Reporting Levels For Radioactivity Concentrations in Environmental Samples........... 4-8 Lower Limits of Detection (LLD's)........................................................

4-9 H. B. Robinson Radiological Environmental Monitoring Program............................... 4-15 Surveillance Requirements........................................................

8-4 HBRODCM iv Rev. 19

LIST OF TABLES No.

Title Pace A-1 X/Q Values for Long-Term Ground Level Releases at Special Locations (sec/rn3)..................................

A-3 A-2 Depleted X/Q Values for Long-Term Ground Level Releases at Special Locations (sec/r 3)

A-4 A-3 D/Q Values for Long-Term Ground Level Releases at Special Locations (m-2)....................................

A-5 A-4 X/Q Values for Long-Term Ground Level Releases at Standard Distances (sec/M 3)......

A-6 A-5 Depleted X/Q Values for Long-Term Ground Level Releases at Standard Distances (sec/rn3)...........

A-7 A-6 D/Q Values for Long-Term Ground Level Releases at Standard Distances (m 2)..................................

A-8 A-7 X/Q Value for Short-Term Ground Level Releases at Special Locations (sec/rn3).....

A-9 A-8 Depleted XIQ Values for Short-Term Ground Level Releases at Special Locations (sec/M 3)...........

A-10 A-9 D/Q Values for Short-Term Ground Level Releases at Special Locations (m-2).................................

A-l A-10 X/Q Values for Long-Term Mixed Mode Releases at Special Locations (sec/M 3)......

A-1 2 A-1 1 Depleted X/Q Values for Long-Term Mixed Mode Releases at Special Locations (sec/rn3)...........

A-1 3 A-12 D/Q Values for Long-Term Mixed Mode Releases at Special Locations (m-2)..................................

A-14 A-13 X/Q Values for Long-Term Mixed Mode Releases at Standard Distances (sec/rn3).....

A-1 5 A-1 4 Depleted X/Q Values for Long-Term Mixed Mode Releases at Standard Distances (sec/M 3).............

A-1 6 A-15 D/Q Values for Long-Term Mixed Mode Releases at Standard Distances (m 2)................................

A-17 A-16 X/Q Values for Short-Term Mixed Mode Releases at Special Locations (sec/M 3)...

A-1 8 A-17 Depleted X/Q Values for Short-Term Mixed Mode Releases at Special Locations (sec/M 3)...........

A-1 9 HBRODCM v

Rev. 1 9

LIST OF TABLES (continued)

No.

Title Pagqe A-18 D/Q Values for Short-Term Mixed Mode Releases at Special Locations (m-2).................................

A-20 A-1 9 Robinson Plant Site Information to be Used for Ground Level Calculations with NRC "XOQDOQ" Program.....................

A-21 A-20 Robinson Plant Site Information to be Used for Mixed Mode Release Calculations with NRC HXOQDOQ" Program.A-24 B-1 Parameters for Cow and Goat Milk Pathways.

B-13 B-2 Parameters for the Meat Pathway.B-1 4

B-3 Parameters for the Vegetable Pathway.B-1 5

D-1 Liquid Process Monitors.

D-1 D-2 Gaseous Process Monitors.

D-2 HBRODCM vi Rev. 1 9

LIST OF FIGURES No.

Title Paqe 4-1 Radiological Sample Locations Near Site.....................................

4-24 4-2 Radiological Sample Distant Locations.....................................

4-25 7-1 Plant Site Boundary and Exclusion Zone.....................................

7-5 D-1 H.B. Robinson Liquid Radwaste Effluent System.....................................

D-3 D-2 H.B. Robinson Gaseous Radwaste Effluent System.....................................

D-4 HBRODCM vii Rev. 21

1.0 INTRODUCTION

The Off-Site Dose Calculation Manual (ODCM) provides the information and methodologies to be used by H. B. Robinson Steam Electric Plant Unit 2 (HBR) to assure compliance with 10 CFR 20, Appendix I of 10 CFR 50, and 40 CFR 190.

The ODCM is based on "Radiological Effluent Technical Specifications for PWRs (NUREG 0472, Rev.

3, Draft 7), "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREG 0133), and guidance from the United States Nuclear Regulatory Commission (NRC). Specific plant procedures for implementation of this manual are presented in H. B. Robinson Unit 2 Plant Operating Manual. These procedures will be utilized by the operating staff of HBR to assure compliance with technical specifications.

Changes to the ODCM which affect the methodologies showing compliance with 10 CFR 20, Appendix I of 10 CFR 50, and 40 CFR 190 will be properly reviewed and approved as indicated in the Administrative Control Section of Plant Technical Specifications. Site specific parameters such as vent fractions, dilution water flow rates (gpm), and liquid/gaseous discharge flow rates are listed in this document as typical system values. Actual values derived from actual operating Plant conditions should be used in lieu of these typical values. Specific Plant procedures control the values of the above parameters; therefore, minimizing the need for frequent revisions to the ODCM.

The Annual Radioactive Effluent Release Report will be prepared as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Waste and Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" (Revision 1, June 1974) with data summarized on a quarterly basis following the format of Appendix B thereof. This report will be inclusive of the requirements as outlined in the HBR Technical Specifications.

ODCM revisions that change items relocated from the Technical Specifications will have an Unreviewed Safety Question Determination evaluation performed for the change. Relocated requirements are identified in the Technical Requirements Manual, Appendix B.

HBRODCM 1 -1 Rev. 19

2.0 LIQUID EFFLUENTS 2.1 MONITOR ALARM SETPOINT DETERMINATION This methodology determines the monitor alarm setpoint that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds 10 times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases or exceeds a concentration 2 x 1 04 pCVml for dissolved or entrained noble gases. Two methodologies may be utilized to calculate monitor alarm setpoints. Section 2.1.1 determines a fixed setpoint based on the worst case assumptions that Cs-1 34 is the only nuclide being discharged. This is consistent with the limit of 10 CFR 20, Appendix B, Note 2. Section 2.1.2 methodology determines the setpoint based on the radionuclide mix via analysis prior to release to demonstrate compliance with 10 CFR 20, Appendix B, limits and may also be used as an alternative method for calculating setpoints.

2.1.1 Setpoint Based on Cs-134 The following method applies to liquid releases via the discharge canal when determining the alarm/trip setpoint for the Condensate Polisher Liquid Waste Monitor (R-37) and the Steam Generator Blowdown Monitor (R-1 9A, R-19B, and R-1 9C) during operational conditions when there is no primary to secondary leaks. The Condensate Polisher Sump discharge (monitored by R-37) discharges to the Settling Ponds prior to release via the discharge canal. Even though the Settling Ponds provide additional dilution prior to discharge, no dilution from the Settling Ponds is used in calculating setpoints for R-37. The setpoint for R-37 is calculated using only circulating water for dilution. This methodology complies with Specification 2.2.1 of the ODCM by satisfying the following equation:

cf <C f + F where:

C

=

The effluent concentration limit (Specification 2.2.1) implementing 10 CFR 20 for the site in pCi/ml.

c

=

The setpoint, in pCVml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint represents a value which, if exceeded, would result in concentrations exceeding 10 times the limits of 10 CFR 20 in the unrestricted area.

HBRODCM 2-1 Rev. 1 9

f f

The waste effluent flow rate in gpm.

F

=

The dilution water flow rate in gpm.

2.1.1.1 Determine c (the effluent monitor setpoint) in [pCi/ml] for each of the dilution water flow rates.

where: c=

(-

(S) where:

C

=

9 x 10- pCi/ml, the effluent concentration limit based on 10 CFR 20, Appendix B, for Cs-1 34.

F

=

Dilution water flow rate (gpm).

=

160,000 gpm from one circulating water pump', Unit 2.

=

250,000 gpm from two circulating water pumps', Unit 2.

=

400,000 gpm from three circulating water pumps', Unit 2.

or

=

50,000 gpm from one circulating water pump2, Unit 1.

=

80,000 gpm from two circulating water pumps2, Unit 1.

f

=

The maximum acceptable discharge flow rate prior to dilution (gpm).

=

60 gpm for the Waste Disposal System Liquid Effluent Monitor3.

=

160 gpm for each Steam Generator Blowdown Monitor.

=

130 gpm for each Steam Generator Blowdown Monitor while draining a steam generator.

=

300 gpm for the Condensate Polisher Liquid Waste Monitor.

S

=

0.5, safety factor used as a conservatism to assure that the radionuclide concentrations are less than the limits specified in 10 CFR 20, Appendix B, at the point of discharge.

HBRODCM 2-2 Rev. 19

2.1.1.2 Determine CR (calculated monitor count rate in corrected counts per minute [ccpm]) attributed to the radionuclides for each of the dilution water flow rates.

CR = (c)(E)

E

=

The applicable effluent monitor efficiency located in the Station Curve Book.

Use the radioactivity concentration "c" to find CR.

2.1.1.3 Determine SP (the monitor alarm/trip setpoint including background [cpm] for each of the dilution water flow rates.

SP = (T )(CR)+Bkg where:

Tm

=

Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from several pathways.

=

0.16 for each Steam Generator Blowdown Monitor (R-19A, R-19B, and R-1 9C).

=

0.25 for the Condensate Polisher Liquid Waste (R-37).

Bkg

=

the monitor background.

HBRODCM2R 2-3 Rev. 19

2.1.2 Setpoint Based on an Analysis of Liquid Prior to Discharge The following method applies to liquid releases via the discharge canal when determining the alarm setpoint for the Waste Disposal System liquid Effluent Monitor (R-1 8), the Steam Generator Blowdown Monitors (R-1 9A, R-19B, and R-1 9C), and the Condensate Polisher Liquid Waste Monitor (R-37) when an analysis of the activity pf the principal gamma emitters has been made prior to or during the release. The Condensate Polisher Sump discharge (monitored by R-37) discharges to the Settling Ponds prior to release via the discharge canal.

Even though the Settling Ponds provide additional dilution prior to discharge, no dilution from the Settling Ponds is used in calculating setpoints for R-37. The setpoint for R-37 is calculated using only circulating water for dilution.

2.1.2.1 Determine Dreq (the minimum acceptable dilution factor):

Dre = Deqg + Dreqng I

C, D e

= ig ECL, reN.

(S)(R.

)

C, D reg

-ECL, (S)(R.)

where:

Dreqg

=

required dilution factor for gamma-emitters.

Dreq,g

=

required dilution factor for non-gamma-emitters (Gross Alpha, H-3, Sr-89, Sr-90, and Fe-55).

ECL,

=

effluent concentration limit of nuclide i in pCi/ml C,

the concentration of nuclide i in pCi/ml S

=

0.5, a safety factor used for conservatism to assure that the radionuclide concentrations are less than the limits specified in 10 CFR Part 20 Appendix B, at the point of discharge.

Rma

=

The maximum ECL ratio limit.

HBRODCM 2-4 Rev. 1 9

2.1.2.2 Determine the maximum waste flow, Remix:

R r = (Favaml)(Faiioc)

(Dreq 0)

RCx =

Maximum allowable release flowrate from the waste source.

Favalj

=

Available dilution flow in gpm.

=

160,000 gpm from one circulating water pump', Unit 2.

=

250,000 gpm from two circulating water pumps', Unit 2.

=

400,000 gpm from three circulating water pumps', Unit 2.

or

=

50,000 gpm from one circulating water pump2, Unit 1.

=

80,000 gpm from two circulating water pumps2, Unit 1.

Fao

=

Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from more than one pathway.

=

0.25 for the Waste Disposal System Liquid Effluent Monitor (R-1 8).

=

0.16 for each of the Steam Generator Blowdown Monitor (R-1 9A, R-1 9B or R-1 9C).

=

0.25 for the Condensate Polisher Liquid Waste (R-37)

If it is determined that Favail + Fwaste <1, the release cannot be made.

(Dreq )(Fwaste)

Reevaluate the discharge flowrate prior to dilution and/or dilution flow rates If Favail + Fwaste > 1, the release can be made.

(Dreq )(Fwas.e)

HBRODCM 2-5 Rev. 1 9

2.1.2.3 Determine the setpoint adjustment factor, Sadi:

[(Faiioc)(Favaji) + Fwastel] Dreq ng Sadj Fwaste Dreq g Fwaste

=

Waste flow anticipated for this release (gpm).

=

60 gpm for the Waste Disposal System Liquid Effluent Monitor3.

=

160 gpm for each Steam Generator Blowdown Monitor.

=

130 gpm for each Steam Generator Blowdown Monitor while draining a steam generator.

=

300 gpm for the Condensate Polisher Liquid Waste Monitor.

2.1.2.4 Determine Smax monitor alarm setpoint in pCi/ml:

S.= jtCi/m1) = (SadjX)(C)

C,

=

All gamma-emitting nuclides (pCi/ml).

2.1.2.5 Determine the monitor alarm setpoint (Smacpm) in CPM:

Smxxcpm = (SmaxXEm)+ Bkg Em

=

The applicable effluent monitor efficiency based on Smax from the efficiency curves located in the Station Curve Book.

Bkg

=

The monitor background in CPM.

HBRODCM 2-6 Rev. 19

SECTION

2.1 REFERENCES

1.

Carolina Power & Light Company Drawing Number G-1 90825. Using the System 0-H Curve for Emergency Low Water Level.

2.

Carolina Power & Light Company, Darlington County S.E. Plant. 1960-182 MW Installation, Unit 1. SYSTEM HEAD CURVES Unit 1 Circulating Water System Draining Quosig.

3.

H.B. Robinson Electric Plant Unit 2, Updated Final Safety Analysis Report.

HBRODCM 2-7 Rev. 1 9

2.2 Requirements for Compliance with 10 CFR Part 20 - Radioactive Materials in Liquid Effluents Applicability Applies to radioactive material in liquid effluents released from the site to unrestricted areas.

Obiective To define the concentration limits of 10 CFR 20 for radioactive material in liquid effluents released to unrestricted areas.

Specification CONTROLS 2.2.1 The concentration of radioactive material in liquid effluents released at any time from the site to unrestricted areas (see Figure 7-1) shall be limited to 10 times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 104 tLCi/ml total activity.

ACTIONS 2.2.2 With the concentration of radioactive material in liquid effluents released from the site to unrestricted areas exceeding the above limits, without delay restore the concentration to within the above limits. In addition, notification must be made to the Commission in accordance with 10 CFR 50.72 and 10 CFR 50.73.

2.2.3 The provisions of Specification 8.1 are not applicable.

HBRODCM 2-8 Rev. 1 9

Bases Compliance With 10 CFR Part 20 - Radioactive Materials in Liquid Effluents This specification is provided to ensure that the concentration of radioactive materials in liquid effluents released from the site to unrestricted areas will be less than 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides the additional assurance that the concentrations of radioactive materials in bodies of water outside the site will result in exposures within the limits of 10 CFR Part 20.1302 to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radionuclide and its EC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). 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).

HBRODCM 2-9 Rev. 19

2.3 COMPLIANCE WITH 10 CFR 20 (LIQUIDS)

Liquid effluents from H.B. Robinson Unit 2 (HBR) will occur both continuously and on a batch basis.

The following sections discuss the methodology which will be utilized by the HBR to show compliance with 10 CFR 20.

2.3.1 Continuous Releases Steam generator blowdown may be a continuous release from HBR. During release periods grab samples will be taken of steam generator blowdown and analyzed for 1-131, fission, activation, and corrosion products as outlined in Table 2.8-1 of the ODCM for HBR. These samples are then composited at a rate using the following equation:

Vup = Vcp(va/v,)

where:

VUP

=

Volume to be replaced/updated (milliliters)

Vcp

=

Volume of the composite (milliliters)

Va

=

Actual volume released from grab sample (gallons)

Vt

=

Total waste volume (gallons) released to date, including volume Va, within the compositing period.

Compliance with 10 CFR 20 during actual release is established through the steam generator blowdown effluent monitor alarm setpoint. This setpoint is based upon Cs-134 as noted in Section 2.1. However, if a continuous release should occur in which the effluent monitor alarm setpoint is exceeded, then actual compliance with 10 CFR 20 may be determined utilizing the actual radionuclide mix and the following equation:

Conc,,=

CVC (2.3-1)

Vdc where:

Conc,

=

Concentration of radionuclide 'i" at the unrestricted area,.LCVml C

=

Concentration of radionuclide "i" in the continuous release, 1ICi/ml VC

=

Volume of continuous effluent released, gal Vd

=

Volume of dilution flow during release, gal.

HBRODCM 2-10 Rev. 19

2.3.2 Batch Releases Batch releases will occur during normal operation. When this does occur at HBR, a continuous release will usually be occurring at the same time. However, during certain shutdown conditions, only batch releases may occur at HBR. Therefore, both situations are treated here to provide the methodology to show compliance with 10 CFR 20.

2.3.2.1 Prerelease The radioactivity content of each batch release will be determined prior to release in accordance with Table 2.8-1 of the ODCM for HBR. HBR will show compliance with 10 CFR 20 in the following manner:

For the case where only a batch release is to occur, the concentration of the various radionuclides in the batch release, determined in accordance with Table 2.8-1 of the ODCM for HBR, is multiplied by the ratio of the maximum release rate of the potential batch release to the dilution flow rate to obtain the concentration at the unrestricted area. This calculation is shown in the following equation:

Con"c-CbRb (2.3-2)

DJr~

where:

Conc,

=

Concentration of radionuclide "i" at the unrestricted area, gCiml; Cib

=

Concentration of radionuclide Si" in the potential batch release, pCi/ml; Rb

=

Release rate of the potential batch release, gpm; Dfr

=

The dilution flow rate based upon the number of circulating water pumps in service during the release, gpm.

Tm

=

Fraction of dilution flow allocated to this release.

The concentration in the unrestricted area is compared to 10 times the concentrations in Appendix B, Table 2, Column 2, of 10 CFR 20. Before release may occur, the mixture of radionuclides released must be of such concentration that Equation 2.3-3 is met.

X, [Conc, /(1O)EC,]< 1 (2.3 - 3) where:

EC,

=

Effluent Concentration Limit of radionuclide 'i' from Appendix B, Table 2, Column 2 of 10 CFR 20, pCVml.

HBRODCM 2-11 Rev. 19

For those cases where batch releases may be occurring at the same time that continuous releases are occurring, the concentration in the unrestricted area will be calculated by the following equation:

C

= Cb Rb + CC Rc (2.3 -4)

DfrTm.

where:

ir Maximum continuous liquid effluent release rate, gpm.

ITm

=

Summation of allocation fractions for those concurrent releases The mixture of radionuclides released must be of such concentrations that Equation 2.3-3 must be met.

For HBR, the liquid radwaste effluent line discharges to the circulating water system. Therefore, the dilution flow rate (Dfr) is a function of the number of circulating water pumps operating. Unit 2 of the H.B. Robinson Steam Electric Plant has three circulating water pumps. Pump curves show that with three pumps operating, the circulating water flow is 400,000 gpm, with two pumps-250,000 gpm, and with one pump--1 60,000 gpm. Unit 1 of the H.B. Robinson Steam Electric Plant has two circulating water pumps. The circulating water flow is 50,000 gpm with one pump and 80,000 gpm with two pumps. At least one circulating water pump must be operating during any liquid waste discharge.

Batch releases from the HBR liquid radwaste system may occur from the waste condensate tanks, the monitor tanks, and the steam generators (during drainage). Continuous release may occur from Steam Generator Blowdown and the Condensate Polisher Liquid Waste. The maximum administrative release rate (Rb) is 160 gpm for each of the steam generators, 60 gpm from the monitor and waste condensate tanks, and 300 gpm for the Condensate Polisher Liquid Wastes, and 130 for each of the steam generators during drainage.

HBRODCM 2-12 Rev. 19

2.3.2.2 Postrelease The Steam Generation Blowdown Monitor (R-1 9A, R-1 9B, and R-1 9C), the Waste Disposal System Liquid Monitor (R-18), and the Condensate Polisher Liquid Waste Monitor (R-37) setpoint will each be limited to 50 percent of 10 times the 10 CFR 20 limits. These setpoints will ensure that 10 times the 10 CFR 20 limits are met. However, because they are based upon a given mix, the possibility exists that the alarm trip setpoints may be exceeded, while 10 times the 10 CFR 20 limits are not exceeded. The following methodology is provided to determine whether actual releases exceeded 10 times the 10 CFR 20 limits.

The concentration of each radionuclide in the unrestricted area following release from a batch tank will be calculated in the following manner:

For the case where only batch releases are occurring, the total activity of radionuclide Wi" released is divided by the actual dilution flow to obtain the concentration in the unrestricted area. This calculation is shown in the following equation:

ConC~k C~kb Vkb (2.3 -5)

Vkd where:

Conck =

The concentration of radionuclide '"I at the unrestricted area during release k, tiCvml CW

=

Concentration of radionuclide "i" in the batch release k,.Ci/mI Vkb

=

Volume of batch release k, gal; Vkd

=

Actual volume of dilution flow during release k, gal.

To show compliance with 10 CFR 20, the following relationship must hold:

Ex [Conck /(l0) EC.] < 1 (2.3-6)

HBRODCM 2-13 Rev. 19

The actual dilution volume during release k (Vkd) is calculated by the following equation:

Vkd = 60-k(Dfr)tk (2.3-7) where:

60

= Conversion factor, min/hr; tk

= Duration of release k, hr, Dfr

= Dilution flow rate from circulating water pumps during release k, gpm.

The circulating water pump flow rates were given in Section 2.3.2.1 above.

For the case where a batch release is occurring at the same time that a continuous release is occurring, the compliance with 10 CFR 20 limits may be determined by the following equation:

Conck -= ClkbVkb+kcVkc (2.3-8)

Vkd where:

Ckc

=

Concentration of radionuclide 'T' in continuous releases during release period k, 4.Ciml; VkC

=

Volume of continuous release during period k, gal.

Calculated concentrations are to be compared to 10 times the concentrations in Appendix B, Table 2, Column 2, of 10 CFR 20.

HBRODCM 2-14 Rev. 19

2.4 Requirements for Compliance With 10 CFR Part 50 - Radioactive Materials in Liquid Effluents Applicability Applies to radioactive materials in liquid effluents released from the site to unrestricted areas.

Obiective To define the calculated dose limits of 10 CFR 50 for radioactive materials in liquid effluents released to unrestricted areas.

Specification CONTROLS 2.4.1 The dose commitment at all times to a member of the public from radioactive material in liquid effluents released to unrestricted areas (See Figure 7-1) shall be limited:

a.

During any calendar quarter to 51.5 mrem to the total body and to 55 mrem to any organ, and

b.

During any calendar year to 53 mrem to the total body and to *10 mrem to any organ.

ACTIONS 2.4.2 With the calculated dose commitment from the release of radioactive materials in liquid effluents exceeding any of the limits prescribed by ODCM Specification 2.4.1 above, prepare and submit a report to the Commission in accordance with the ODCM Specification 9.3.

HBRODCM 2-15 Rev. 19

BASES Compliance With 10 CFR Part 50 - Radioactive Materials in Liquid Effluents This specification is provided to implement the requirements of Sections lI.A, and II.A and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section II.A of Appendix I.

The action statement provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I of 10 CFR Part 50 to assure that the release of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." The dose calculations in the ODCM implement the requirements in Section IIL.A of Appendix I that conformance with the guides of Appendix I be shown by calculative procedures based on models and data, such that the actual exposure of an individual 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 are consistent with the methodology provided in the Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, 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.

HBRODCM 2-16 Rev. 19

2.5 COMPLIANCE WITH 10 CFR 50 2.5.1 Cumulation of Doses i

The dose contribution from the release of liquid effluents will be calculated once per month, and a cumulative summation of these total body and any organ doses should be maintained for each calendar quarter. The dose contribution for all batch releases will be calculated using the following equation:

Dtb X

Ek Xi A,. tkb Ckb Fkb (2.5-1) where:

Db

=

The cumulative dose commitment to the total body or any organ T, from batch liquid effluents, mrem; b

=

The length of time of batch release k over which Ckb and Fkb are averaged for each batch liquid release, hours; Gkb The average concentration of radionuclide "is in undiluted batch liquid effluent during batch release k, IiCi/ml; r =

The site-related ingestion dose commitment factor to the total body or any organ X for each identified principal gamma and beta emitter, mrem/hr per

[+/-CVml; Fkb

=

The near-field average dilution factor for Cw during any batch liquid effluent release k. Defined as the ratio of the volume of undiluted liquid waste released to the product of the dilution volume from the site discharge structure to unrestricted receiving waters times 1.0.

(1.0 is the site-specific applicable factor for the mixing effect of the HBR discharge structure as defined in NUREG-0133, October 1978).

Vkb VkdXl.O Where Vkb and Vkd are as defined in Equation 2.3-5.

HBRODCM 2-17 Rev. 19

The dose factor A, was calculated for an adult for each isotope using the following equation:

AT= 1.14x1lo(21BO)DF,,

(2.5-2) where:

1.14XOr5 = 106 pCi x 103 rmlx lyr

[iCi I

8760hr 21

=

Adult fish consumption rate from Table E-5 of Regulatory Guide 1.109, Revision 1, kg/yr; BF,

=

Bioaccumulation factor for radionuclide li" in fish from Table A-1 of Regulatory Guide 1.109, Revision 1, pCVkg per pCi/A; DF,

=

Dose conversion factor for radionuclide 'i" for adults for a particular organ X from Table E-1 1 of Regulatory Guide 1.109, Revision 1, mrem/pCi.

The potable water pathway does not exist either within Lake Robinson or downstream of the Lake Robinson dam. Therefore, the potable water term was excluded from the calculation of A, values.

Table 2.5-1 presents A, values for an adult at HBR.

As noted in Section 2.3.1, steam generator blowdown is continuously released from HBR. The dose from continuous releases will be calculated using the following equation:

DTc = Sk En Alr tkc Cikc Fkc (2.5 - 3) where:

Dc

=

The cumulative dose commitment to the total body or any organ r, from liquid effluents for continuous releases, mrem; tkc

=

The length of time of continuous release period k over which Ckc and Fkc are averaged for all continuous liquid releases, hours; 0ikc The average concentration of radionuclide ni" in undiluted liquid effluent during continuous release period k from any continuous liquid release, p.CVml; HBRODCM 2-18 Rev. 1 9

FkC

=

The near-field average dilution factor for Cikc during continuous liquid effluent release k. Defined as the ratio of the volume of undiluted liquid waste released to the product of the dilution volume from the site discharge structure to unrestricted receiving water times 1.0. (1.0 is the site-specific applicable factor for the mixing effect of the HBR discharge structure as defined in NUREG-0133, October 1978).

Fkc =

Vkc VkdXl-O Where Vkc and Vkd are, as defined in Equation 2.3-8 and 2.3-5, respectively, only now distinguished for continuous releases.

The sum of the cumulative dose from all batch and continuous releases for a quarter are compared to one half the design objectives for total body and any organ. The sum of the cumulative doses from all batch and continuous releases for a calendar year are compared to the design objective doses. The following relationships should hold for HBR to show compliance with Specification 2.4.1 of the ODCM for H.B. Robinson Unit 2.

For the calendar quarter, DT

1.5 mrem total body (2.5-4)

D,

5 mrem any organ (2.5 -5)

For the calendar year, D,

3 mrem total body (2.5 - 6)

D, S 10 mrem any organ (2.5-7) where:

D

=

Cumulative total dose to any organ T or the total body from continuous and batch releases, mrem;

=

DRb+Dtc HBRODCM 2-19 Rev. 19

The quarterly limits given above represent one half the annual design objective of Section IL.A of Appendix I of 10 CFR 50. If any of the limits in Expressions 2.5-4 through 2.5-7 are exceeded, a special report pursuant to ODCM Specification 9.3 must be filed with the NRC. This report complies with Section IV.A, of Appendix I of 10 CFR 50.

2.5.2 Proiection of Doses Doses resulting from the release of liquid effluents will be projected once per 31 days. These projections will include a safety margin, based upon expected operational conditions, which will take into consideration both planned and unplanned releases.

Projected dose will be calculated as follows:

PD 31(DA+DB)+M (2.5-8)

TE where:

PD

= projected doses in mrem.

DA

= dose accumulated during current quarter in mrem.

DB

= projected dose from this release.

TE

= time elapsed in quarter in days.

M

= safety margin in mrem.

If the projected doses exceed 0.2 mrem to the whole body or 0.6 mrem to any organ when averaged over a calendar quarter, the liquid radwaste equipment will be operated to reduce the radioactive materials in the liquid effluent.

HBRODCM 2-20 Rev. 19

TABLE 2.5-1 A, VALUES FOR THE ADULT FOR THE H.B. ROBINSON STEAM ELECTRIC PLANT (mrem/hr per pC/ml)

Nuclide Bone Liver T.Bodv Thyroid Kidnev Lung GI-LLI Skin H-3 0.OOE+00 2.27E-01 2.27E-01 2.27E-01 2.27E-01 2.27E-01 2.27E-01 2.27E-01 F-18 2.30E-02 2.13E-02 2.15E-02 2.13E-02 2.13E-02 213E-02 2.13E-02 2.51E-02 NA-24 1.35E+02 1.35E+02 1.35E+02 1.35E+02 1.35E+02 1.35E+02 1.35E+02 7.45E-01 CR-51 2.51E-01 2.51E-01 1.49E+00 9.94E-01 5.25E-01 1.90E+00 3.13E+02 2.96E-01 MN-54 7.45E+01 4.45E+03 9.09E+02 7.45E+01 1.38E+03 7.45E+01 1.35E+04 8.74E+01 MN-56 4.86E-02 2.23E-01 7.94E-02 4.86E-02 2.69E-01 4.86E-02 5.60E+00 5.74E-02 FE-55 6.59E+02 4.55E+02 1.06E+02 0.OOE+00 O.00E+00 2.54E+02 2.61 E+02 0.OOE+00 FE-59 1.04E+03 2.42E+03 9.38E+02 1.47E+01 1.47E+01 6.88E+02 8.04E+03 1.72E+01 C0-57 1.01E+01 2.89E+01 4.49E+01 1.01E+01 1.01E+01 1.01E+01 5.41E+02 1.11E+01 C0-58 2.04E+01 1.09E+02 2.19E+02 2.04E+01 2.04E+01 2.04E+01 1.81E+03 2.39E+01 C0-60 1.16E+03 1.41E+03 1.72E+03 1.16E+03 1.16E+03 1.16E+03 5.98E+03 1.36E+03 NI-65 1.88E-01 3.83E-02 2.62E-02 1.60E-02 1.60E-02 1.60E-02 5.83E-01 1.86E-02 CU-64 3.26E-02 2.73E+00 1.30E+00 3.26E-02 6.83E+00 3.26E-02 2.30E+02 3.70E-02 ZN-65 2.32E+04 7.37E+04 3.33E+04 4.02E+01 4.93E+04 4.02E+01 4.64E+04 4.62E+01 BR-82 1.15E+00 1.15E+00 1.42E+03 1.15E+00 1.15E+00 1.15E+00 1.63E+03 1.33E+00 BR-83 2.62E-04 2.62E-04 3.87E-02 2.62E-04 2.62E-04 2.62E-04 5.56E-02 3.81 E-04 BR-84 1.09E-02 1.09E-02 1.09E-02 1.09E-02 1.09E-02 1.09E-02 1.09E-02 1.27E-02 RB-86 4.83E-01 9.75E+04 4.54E+04 4.83E-01 4.83E-01 4.83E-01 1.92E+04 5.52E-01 RB-88 1.78E-03 1.78E-03 1.78E-03 1.78E-03 1.78E-03 1.78E-03 1.78E-03 2.03E-03 RB-89 6.61 E-03 6.61 E-03 6.61 E-03 6.61 E-03 6.61 E-03 6.61 E-03 6.61 E-03 7.93E-03 SR-89 2.19E+04 1.16E-03 6.27E+02 1.16E-03 1.16E-03 1.16E-03 3.51E+03 1.35E-03 SR-90 5.45E+05 O.OOE+00 1.34E+05 0.OOE+00 0.OOE+00 0.OOE+00 1.58E+04 O.OOE+00 SR-91 7.09E+01 1.16E-01 2.98E+00 1.16E-01 1.16E-01 1.16E-01 3.37E+02 1.35E-01 SR-92 3.76E-01 4.18E-02 5.62E-02 4.18E-02 4.18E-02 4.18E-02 6.66E+00 4.64E-02 Y-91M 5.39E-03 5.39E-03 5.39E-03 5.39E-03 5.39E-03 5.39E-03 5.39E-03 6.24E-03 Y-91 8.41 E+00 5.77E-02 2.81 E-01 5.77E-02 5.77E-02 5.77E-02 4.60E+03 6.49E-02 Y-92 1.02E-02 9.70E-03 9.72E-03 9.70E-03 9.70E-03 9.70E-03 8.09E+00 1.1 5E-02 Y-93 4.08E-02 9.86E-03 1.07E-02 9.86E-03 9.86E-03 9.86E-03 9.82E+02 1.35E-02 ZR-95 1.34E+01 1.32E+01 1.32E+01 1.32E+01 1.33E+01 1.32E+01 2.55E+02 1.53E+01 ZR-97 1.64E-01 1.60E-01 1.60E-01 1.59E-01 1.61E-01 1.59E-01 3.11E+02 1.85E-01 NB-95 4.46E+02 2.51 E+02 1.39E+02 7.35E+00 2.49E+02 7.35E+00 1.48E+06 8.65E+00 NB-97 9.47E-03 9.47E-03 9.47E-03 9.47E-03 9.47E-03 9.47E-03 1.29E-02 1.11 E-02 MO-99 2.15E-01 8.06E+01 1.55E+01 2.15E-01 1.82E+02 2.15E-01 1.86E+02 2.49E-01 TC-99M 1.05E-02 1.15E-02 3.01E-02 9.90E-03 3.40E-02 1.07E-02 9.47E-01 1.13E-02 TC-1 01 1.09E-03 1.09E-03 1.09E-03 1.09E-03 1.09E-03 1.09E-03 1.09E-03 1.22E-03 HBRODCM 2-21 Rev. 19

TABLE 2.5-1 (continued)

Nuclide RU-103 RU-105 RU-106 AG-ilOM SN-113 SB-1 24 SB-1 25 TE-129M TE-1 29 TE-131 M TE-132 1-131 1-132 1-133 1-134 1-135 CS-1 34 CS-136 CS-137 CS-138 BA-1 39 BA-140 BA-1 42 LA-140 LA-142 CE-141 CE-143 CE-144 PR-144 HF-181 W-187 NP-239 Bone 1.02E+01 4.29E-02 8.85E+01 1.86E+02 2.00E+03 3.88E+01 1.30E+02 1.08E+04 1.43E-03 9.54E+02 1.95E+03 1.38E+02 7.23E-02 2.31 E+01 2.40E-02 1.42E+00 2.98E+05 2.96E+04 3.83E+05 1.93E-02 5.70E-03 1.86E+02 2.41 E-03 1.13E+00 4.09E-02 7.57E-01 1.27E-01 4.91 E+00 9.87E-05 1.33E+01 1.48E+02 1.13E-01 Liver 5.82E+00 3.42E-02 2.27E+01 1.86E+02 7.80E+01 3.23E+01 1.26E+02 4.03E+03 1.42E-03 4.67E+02 1.26E+03 1.97E+02

8. 1 E-02 4.01 E+01 2.40E-02 3.50E+00 7.1 OE+05 1.17E+05 5.23E+05 1.93E-02 5.69E-03 1.34E+00 2.41 E-03 1.08E+00 4.09E-02 7.50E-01 1.89E+00 4.23E+00 9.87E-05 1.06E+01 1.23E+02 9.41 E-02 T.Bodv 7.70E+00 3.77E-02 3.1 OE+01 1.85E+02 1.90E+03 3.48E+01 1.27E+02 1.71 E+03 1.42E-03 3.89E+02 1.19E+03 1.13E+02 7.19E-02 1.23E+01 2.40E-02 1.38E+00 5.80E+05 8.42E+04 3.43E+05 1.93E-02 5.69E-03 1.32E+01 2.41 E-03 1.05E+00 4.09E-02 7.37E-01 1.25E-01 3.80E+00 9.87E-05 1.09E+01 4.32E+01 9.31 E-02 Thyroid 5.82E+00 3.42E-02 2.27E+01 1.85E+02 2.80E+01 3.22E+01 1.26E+02 3.71 E+03 1.42E-03 7.39E+02 1.40E+03 6.44E+04 5.61 E-01 5.87E+03 2.40E-02 2.22E+02 3.69E+02 8.12E+00 5.55E+02 1.93E-02 5.69E-03 1.10E+00 2.41 E-03 1.03E+00 4.09E-02 7.35E-01 1.24E-01 3.74E+00 9.87E-05 1.06E+01 1.26E-01 9.20E-02 Kidney 2.25E+01 1.47E-01 1.50E+02 1.86E+02 5.75E+01 3.22E+01 1.26E+02 4.51 E+04 1.49E-03 4.72E+03 1.22E+04 3.38E+02 8.95E-02 6.98E+01 2.40E-02 5.54E+00 2.30E+05 6.51 E+04 1.78E+05 1.93E-02 5.69E-03 1.18E+OO 2.41 E-03 1.03E+00 4.09E-02 7.42E-01 1.25E-01 4.03E+00 9.87E-05 1.06E+01 1.26E-01 9.85E-02 Lung 5.82E+00 3.42E-02 2.27E+01 1.85E+02 7.66E-01 3.73E+01 1.29E+02 1.06E+00 1.41 E-03 4.32E-01 2.28E-01 9.25E-01 6.70E-02 1.32E-01 2.40E-02 1.36E-01 7.66E+04 8.93E+03 5.95E+04 1.93E-02 5.69E-03 1.24E+00 2.41 E-03 1.03E+00 4.09E-02 7.35E-01 1.24E-01 3.74E+00 9.87E-05 1.06E+01 1.26E-01 9.20E-02 GI-LLI 5.15E+02 5.36E+00 4.28E+03 5.17E+02 3.50E+04 2.21 E+02 1.73E+02 5.44E+04 1.42E-03 4.63E+04 5.98E+04 5.27E+01 6.96E-02 3.60E+01 2.40E-02 3.94E+00 1.28E+04 1.33E+04 1.07E+04 1.93E-02 5.70E-03 3.81 E+02 2.41 E-03 3.67E+03 4.16E-02 5.75E+01 6.62E+01 3.98E+02 9.87E-05 2.12E+02 4.04E+04 4.29E+02 Skin 6.79E+00 3.88E-02 2.72E+01 2.16E+02 2.19E+00 3.71 E+01 1.42E+02 1.24E+00 1.67E-03 5.09E-01 2.68E-01 1.12E+00 7.88E-02 1.60E-01 2.85E-02 1.59E-01 4.30E+02 9.20E+00 6.47E+02 2.21 E-02 6.41 E-03 1.26E+00 2.75E-03 1.17E+00 4.90E-02 8.28E-01 1.41 E-01 4.32E+00 1.13E-04 1.50E+01 1.47E-01 1.06E-01 HBRODCM 2-22 Rev. 19

2.6 Radioactive Liquid Effluent Monitonng Instrumentation Applicability Applies to the radioactive liquid effluent instrumentation system.

Obiective To define the operating requirements for the radioactive liquid effluent instrumentation system.

Specification CONTROLS 2.6.1 ACTIONS 2.6.2 2.6.3 2.6.4 The radioactive liquid effluent monitoring instrumentation channels shown in Table 2.6-1 shall be operable with their alarm/trip setpoint set to ensure that the limits of ODCM Specification 2.2.1 are not exceeded. The alarm/trip setpoints shall be determined in accordance with the ODCM.

With a radioactive liquid monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluent monitored by the affected channel, change the setpoint so it is acceptably conservative, or declare the channel not operable.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation operable, take the action shown in Table 2.6-1.

The provisions of Specification 8.1 are not applicable.

BASES Radioactive Liquid Effluent Instrumentation The radioactive liquid effluent monitoring 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 the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding 10 times the limits of 10 CFR Part 20, Appendix B, Table 2, Column 2. The operability and use of this instrumentation are consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

HBRODCM 2-23 Rev. 19

~ JL KJ TABLE 2.6-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Release Pathway / Instrumentation MCO*

Compensatory Measures

1.

Liquid Radwaste Effluent Discharge Line 1

With the number of channels operable less than the MCO requirements:

a.

Exert best efforts to return the instruments to operable status within

a.

Monitor (R-18) 30 days and, if unsuccessful, explain in the next Annual Radioactive provides automatic Effluent Release Report why the inoperability was not corrected in a termination of timely manner in accordance with Technical Specification 5.6.3 and, release upon exceeding alarm/trip setpoint.

b.

Effluent releases via this pathway may continue provided that prior to initiating a release:

1.

Two independent samples are analyzed in accordance with the Surveillance Requirements of ODCM Specification 2.2.1 and;

2.

Two members of the facility staff independently verify the release rate calculations and the discharge line valving.

b.

Flow rate measurement device 1

With the number of channels operable less than the MCO requirement:

a.

Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner in accordance with Technical Specification 5.6.3 and,

b.

Effluent releases via this pathway may be continued, provided that the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves generated "in situ" and tank volumes may be used to estimate flow.

MCO - Minimum Channels Operable 2-24 Rev.19 HBRODCM

K)o TABLE 2.6-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Release Pathway / Instrumentation MCO*

Compensatory Measures

2.

Steam Generator Blowdown Effluent 1 per With the number of channels operable less than the MCO requirement:

Line S/G

a.

Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent

a.

Monitor (R-1 9A,B, and C)

Release Report why the inoperability was not corrected in a timely provides automatic termination of manner in accordance with Technical Specification 5.6.3 and, blowdown from the affected Steam Generators upon

b.

Effluent releases via this pathway may continue provided that grab exceeding alarm/trip setpoint.

samples are analyzed for gross radioactivity (beta or gamma) with a lower limit of detection of at least 1.OE-07pCi/ml or are analyzed for principle gamma emitters consistent with Table 2.8-1;

1.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is S0.01 pCi/ml Dose Equivalent 1-131, or;

2.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is >0.01 pCi/ml dose Equivalent 1-131.

b.

Flow rate measurement devices 1 per With the number of channels operable less than the MCO requirement due to inoperable

- each Steam Generator has its S/G equipment:

own blowdown flow rate

a. Exert best efforts to return the instruments to operable status within 30 days measuring device. These and, if unsuccessful, explain in the next Annual Radioactive Effluent Release devices only measure flow Report why the inoperability was not corrected in a timely manner in directed through the heat accordance with Technical Specification 5.6.3 AND, recovery system, and will not measure flow which bypasses With the number of channels operable less than the MCO requirement due to inoperable the heat recovery system.

equipment, OR if the steam generator blowdown system is aligned such that any flow bypasses the flow measurement device(s) (i.e. heat recovery is not in service):

b. Effluent releases via this pathway may continue provided that the flow rate for the affected blowdown line(s) is estimated at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

MCO - Minimum Channels Operable 2-25 Rev.20 HBRODCM

I K)

TABLE 2.6-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Release Pathway/instrumentation MCO*

Compensatory Measures 1

Steam Generator Blowdown Effluent 1 per With the number of channels operable less than the MCO requirement due to Line (continued)

S/G inoperable equipment:

c.

R-1 9A, B and C flow

a.

Exert best efforts to return the instruments to operable status within measurement device - each 30 days and, if unsuccessful, explain in the next Annual Radioactive monitor has its own flow rate Effluent Release Report why the inoperability was not corrected in a measurement device timely manner in accordance with Technical Specification 5.6.3 and,

b.

Effluent releases via this pathway may continue provided that the flow rate for the affected monitor line(s) is estimated at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.

Discharge Canal Flow Note 1 With the number of channels operable less than the MCO requirement suspend effluent release via this pathway.

1 4.

Tank Level Indicating Devices

a.

Refueling Water Storage Tank

b.

Monitor Tanks Tank A Tank B

c.

Waste Condensate Tanks Tank C Tank D Tank E

d.

Temporary Tanks (Note 2) 1 1

1 1

1 per Tank With the number of channels operable less than the MCO requirement:

a.

Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner in accordance with Technical Specification 5.6.3 and,

b.

Liquid additions to the affected tank(s) may continue provided that the liquid level for the affected tanks is estimated during all liquid additions to the affected tank(s).

IJ___

MCO - Minimum Channels Operable 2-26 Rev.20 HBRODCM

t TABLE 2.6-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Release Pathway/Instrumentation MCO*

Compensatory Measures

5.

Containment Fan Cooling Water 1

With the number of channels operable less than the MCO requirement:

Monitor

a.

Exert best efforts to return the instruments to operable status (Service Water Effluent Line) within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not

a.

Monitor (R-16) does not provide corrected in a timely manner in accordance with Technical automatic termination of release Specification 5.6.3 and, upon exceeding alarm setpoint.

b.

Effluent releases via this pathway may continue provided that, once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , grab samples are collected and analyzed for gross radioactivity (beta or gamma) with a lower limit of detection of at least 1.OE-07 pCi/ml or are analyzed for principal gamma emitters consistent with Table 2.8-1.

6.

Composite Sampler for Settling Ponds 1

With the number of channels operable less than the MCO requirement:

a.

Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner in accordance with Technical Specification 5.6.3 and,

b.

Effluent releases via this pathway may continue provided that, once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , grab samples are collected and analyzed for gross radioactivity (beta or gamma) with lower limit of detection of at least 1.OE-07 pCi/ml or are analyzed for principal gamma emitters consistent with Table 2.8-1.

MCO - Minimum Channels Operable 2-27 Rev.19 HBRODCM

2' J

)J TABLE 2.6-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Release Pathway/instrumentation MCOO Compensatory Measures

7.

Condensate Polisher Liquid Waste 1

With the number of channels operable less than the MCO requirement:

Monitor

a.

Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Annual

a.

Monitor (R-37) provides Radioactive Effluent Release Report why the inoperability was not automatic termination of release corrected in a timely manner in accordance with Technical upon exceeding alarm/trip Specification 5.6.3 and, setpointb.

Effluent releases via this pathway may continue provided that, once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , grab samples are collected and analyzed for gross radioactivity (beta or gamma) with a lower limit of detection of at least 1.OE-07 pCi/ml or are analyzed for principal gamma emitters consistent with Table 2.8-1.

MCO - Minimum Channels Operable 2-28 Rev.19 HBRODCM

NOTES TO TABLE 2.6-1 Note 1 Pump curves for Unit 2 operating circulating water pumps may be used to satisfy this MCO.

If no Unit 2 circulating water pumps are operating the pump curves for circulating water pumps operating in Unit 1 may be used to satisfy this MCO.

Note 2 A temporary tank is defined as any tank having a capacity of 2100 gallons used for the receipt or transfer of radioactive liquids.

HBRODCM 2-29 Rev. 19

2.7 Radioactive Liquid Effluent Monitoring Instrumentation - Surveillance Requirements Applicability Applies to the radioactive liquid effluent instrumentation system.

Obiective To ascertain that the radioactive liquid effluent instrumentation system is functioning properly in order to accurately monitor radioactive liquid effluent releases.

Specification SURVEILLANCE REQUIREMENTS 2.7.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated operable by performance of the channel check, source check, channel calibration, and Channel Operational Test operations at the frequencies shown in Table 2.7-1.

HBRODCM 2-30 Rev. 19

t.

TABLE 2.7-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pathway/Instruments Channel Source Channel Channel Check Check Calibration Operational Test

1.

Liquid Radwaste Effluent Line

a.

Monitor (R-18)

D P

R (Note 3)

Q (Note 4)

b.

Flow rate measurement device (Note 1)

N.A.

R N.A.

2.

Steam Generator Blowdown Effluent Line

a.

Monitor (R-19A)

D M

R (Note 3)

Q (Note 4)

(R-1 9B)

D M

R (Note 3)

Q (Note 4)

(R-1 9C)

D M

R (Note 3)

Q (Note 4)

b.

Flow rate measurement devices for measuring flow of sample to R-1 9 (Note 2)

N.A.

c.

Flow rate measuring devices for each steam generator blowdown line (Note 2)

N.A.

R N.A.

3.

Containment Fan Cooling Water Monitor (Service Water Effluent Line)

a.

Monitor (R-16)

D M

R (Note 3)

Q (Note 5)

4.

Tank Level Indicating Devices

a.

Refueling Water Storage Tank D

N.A.

R Q

b.

Monitor Tanks A & B D*

N.A.

R Q

c.

Waste Condensate Tanks C D & E D*

N.A.

R Q

5.

Condensate Polisher Waste Monitor (R-37)

D M

R Q

During liquid additions to the tank L-nnR A

2-31 Rev. 19 I

It51 UtbM

NOTES TO TABLE 2.7-1 Note 1 The channel check shall consist of verifying indication of flow at least once during each batch type release or shall consist of verifying indication of flow at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for continuous type releases.

Note 2 The channel check shall consist of verifying indication of flow at least once during each batch type release or shall consist of verifying indication of flow at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for continuous releases, except during steam generator drain at cold shutdown.

Note 3 The channel calibration shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities or otherwise NIST traceable.

Note 4 The Channel Operational Test shall also demonstrate that automatic isolation of this pathway and Control Room alarm annunciation occur if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm/trip setpoint.

2.

Power failure.

3.

Instrument controls not set in operate mode.

Note 5 The Channel Operational Test shall also demonstrate that Control Room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm setpoint.

2.

Power failure.

3.

Instrument indicates a downscale failure.

4.

Instrument controls not set in operate mode.

NOTATION P

Completed prior to making a radioactive materials release D

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W

At least once per 7 days N.A.

Not applicable M

At least once per 31 days R

At least once per 18 months a

At least once per 92 days HBRODCM 2-32 Rev. 19

2.8 Radioactive Liquid Effluents Sampling and Analysis Requirements A~plicability Applies to the monitoring of radioactive liquid effluents.

Obiective To ascertain that radioactive liquid effluent releases are being maintained as low as reasonably achievable and within allowable limits.

Specification SURVEILLANCE REQUIRMENTS 2.8.1 The radioactivity content of each batch of radioactive liquid waste to be discharge shall be determined prior to release by sampling and analysis in accordance with Table 2.8-1. The results of pre-release analyses shall be used with the calculative methods in the ODCM to assure that the concentration at the point of release to the unrestricted area is maintained within the limits of Specification 2.2.1.

2.8.2 Analyses of samples composited from batch releases shall be performed in accordance with Table 2.8-1. The results of the post-release analyses shall be used with the calculative methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Specification 2.2.1.

2.8.3 The concentration of radioactive materials in liquid effluents discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 2.8-1. The results of the analyses shall be used with the calculative methods in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 2.2.1.

2.8.4 Dose Calculations: Cumulative dose commitments for the current calendar quarter and calendar year from liquid effluents shall be determined in accordance with the ODCM once per 31 days.

HBRODCM 2-33 Rev. 19

TABLE 2.8-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Sampling Minimum Analysis Required Required Type of Release Frequency Frequency Activity LLDa Analysis pCi/ml Batch Waste P

P Principal Gamma 5E-07 Releasesb Grab Sample on Grab Sample Emittersc 1-131 1 E-06

1.

Monitor Tanks P

M Dissolved and 1 E-05 Grab Sample on Grab Entrained Gases One Batch/M (gamma emitters)

Sample P

M Grab Sample on Composite Tritium 1 E-05

2. Waste Condensate Tanks Each Batch and Compositedd Gross Alpha 1E-07 P

0

3.

Drainage of Grab Sample on Composite Sr-8g, Sr-90 5E-08 Systems Each Batch and Compositedd Fe-55 1 E-06 Continuous D

W Principal Gamma 5E-07 Releasese Grab Sample on Grab Sample EmittersC 1-131 1 E-06

1. Steam Generator Dissolved and 1 E-05 Blowdown M

M Entrained Gases Grab Sample on Grab Sample (gamma emitters)

M M

Grab Sample and on Composite Tritium 1E-05 Composited d,f Gross Alpha 1E-07 D

0 Grab Sample on Composite Sr-89, Sr-90 5E-08 and Composited Fe-55 1 E-06 HBRODCM 2-34 Rev. 19

TABLE 2.8-1 (Continued)

TABLE NOTATION

a.

The LLD is defined, for purposes of these specifications, 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.

For a particular measurement system, which may include radiochemical separation:

LLD=46S ExVx2.22xlO6xYxexp(

)

Where:

LLD is the 'a priori' lower limit of detection as defined above, as microcuries per unit mass or

volume, Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, I is the radioactive decay constant for the particular radionuclide, and At for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V, Y, and At should be used in the calculation.

HBRODCM 2-35 Rev. 19

TABLE 2.8-1 (Continued)

TABLE NOTATION 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.

b.

A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses each batch shall be isolated and thoroughly mixed whenever possible, to assure representative sampling. Residual liquids in systems such as feedwater heaters and lines cannot be thoroughly mixed for representative samples of their respective system. Grab samples from these systems will be accepted as representative of their respective system.

c.

The principal gamma emitters for which the LLD specification 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-1 44.

This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

d.

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.

e.

A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a system that has an input flow during the continuous release.

f.

Grab sample of continuous flows taken for compositing purposes will be taken in volumes proportional to the existing flow rate of the system in a manner described in the ODCM.

HBRODCM 2-36 Rev. 19

2.9 Liquid Radwaste Treatment System Applicability Applies to the liquid radwaste treatment system.

Obiective To define the operating requirements for the liquid radwaste treatment system and to ascertain that the concentration of radioactive materials in the liquid waste treatment system is maintained as low as reasonably achievable and within allowable limits.

Specification CON' TROLS 2.9.1 The appropriate portions of the Liquid Radwaste Treatment System shall be maintained and used to reduce the concentrations of radioactive materials in liquid wastes prior to their discharge when the projected dose commitments, due to the release of radioactive liquid effluents to unrestricted areas (See Figure 7-1) when averaged over a calendar quarter, would exceed 0.2 mrem to the total body or 0.6 mrem to any organ.

ACTIIDNS 2.9.2 With radioactive liquid wastes being discharged without treatment while in excess of the limits of ODCM Specification 2.9.1 above, prepare and submit a report to the Commission in accordance with ODCM Specification 9.3.b.

SURVEILLANCE REQUIREMENTS 2.9.3 Dose commitments from liquid releases shall be projected at least once per 31 days, in accordance with the ODCM to ensure the provisions of ODCM Specification 2.9.1 are satisfied when the Liquid Radwaste Treatment System is not in use.

HBRODCM 2-37 Rev. 19

Bases Liquid Radwaste Treatment System The requirements that the appropriate portions of this system be maintained and used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonably achievable".

This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.0 of Appendix I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as the dose design objective set forth in Section I.A of Appendix 1, 10 CFR Part 50, for liquid effluents.

HBRODCM 2-38 Rev. 1 9

3.0 GASEOUS EFFLUENTS 3.1 MONITOR ALARM SETPOINT DETERMINATION This methodology determines the monitor alarm setpoint if the dose rate in the unrestricted areas due to radionoble gases in the gaseous effluent released from the site to areas at and beyond the site boundary exceeds 500 mrem/year to the whole body or exceeds 3000 mrem/year to the skin using a conservative mix (GALE Code).

The methodology described in Section 3.1.2 provides an alternative means to determine monitor alarm setpoints when an analysis is performed prior to release.

3.1.1 Setpoint Based on Conservative Radionuclide Mix (Ground and Mixed Mode Releases Releases through the steam generator flash tank vent can only occur through this vent when significant primary-to-secondary leakage exists within the steam generators and the blowdown is not going through heat recovery. Detection of primary-to-secondary leakage is accomplished most effectively by continuously monitoring the condenser vacuum pump vent (R-1 5). Steam generator blowdown is continuously monitored by R-1 9A, R-1 9B, and R-1 9C as a liquid pathway. The condenser vacuum pump vent discharges via plant vent which is monitored by R-14.

The following method applies to gaseous releases via the plant vent when determining the high-alarm setpoint for the plant vent gas monitor (R-14C) and the Fuel Handling Basement Exhaust Monitor (R-20), using the GALE code during the following operational conditions:

Continuous release via the plant vent (R-14C).

Continuous release via the Fuel Handling Basement Exhaust (R-20).

HBRODCM 3-1 Rev. 19

3.1.1.1 Determine the 'mix" (noble gas radionuclides and composition) of the gaseous effluent.

Determine S., the fraction of the total noble gas radioactivity in the gaseous effluent comprised by noble gas radionuclide "i," for each individual noble gas radionucihde in the gaseous effluent or use the S, from Table 3.1-1 when using GALE Code.

A,

=

The radioactivity of noble gas radionuclide "iin the gaseous effluent from Table 3.1-1.

Al Si-(3.1-1) 3.1.1.2 Determine the Qm, the maximum acceptable total release rate [CXi/sec] of all noble gas radionuclides in the gaseous effluent based upon the whole body exposure limit of 500 mrem/year by:

Qm 500 (3.1-2)

(X/QgS,

( (

) =

The highest calculated annual average relative dispersion factor for any area at or beyond the unrestricted area boundary for all sectors (sec/in3).

=

8.1 E-5 sec/M 3 (Continuous Ground Release) from Table A-1, Appendix A.

9.9 E-7 sec/M3 (Mixed Mode Release) from Table A-1 0, Appendix A.

K,

=

The total whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem/yr / iCi/i 3) from Table 3.1-2.

HBRODCM 3-2 Rev. 19

3.1.1.3 Determine Om, the maximum acceptable release rate [IlCi/sec] of all gas radionuclides in the gaseous effluent based upon the skin exposure limit of 3000 mrem/yr by:

Q 3000 (3.1-3)

Qm (X/Q)

[(L. +1.1M1 M) S.]-

L1+1.1 M, =

The total skin dose factor due to emissions from noble gas radionuclide "i" (mrem/yr I liClm3) from Table 3.1-2.

3.1.1.4 Determine Cm,-the maximum acceptable total radioactivity concentration [l.Ci/cc] of all noble gas radionuclides in the gaseous effluent.

Cm (2.12E - 3)Q m (Tm)(SF)

(3.1-4)

NOTE:

Use the lower of the Om values obtained in Sections 3.1.1.2 and 3.1.1.3. This will protect both the skin and total body from being exposed to the limit.

where:

Tm

=

Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from several pathways.

=

0.92 for Plant Vent Gas Monitor (R-14C).

=

0.05 for the Fuel Handling Basement Exhaust Monitor (R-20).

F

=

The maximum acceptable effluent flow rate at the point of release (cfm).

=

60,600 cfm for plant vent.

=

10,200 cfm for the fuel-handling building.

HBRODCM 3-3 Rev. 19

2.12E-3=

Unit conversion constant to convert ILCi/sec/cfm to LCi/cc.

- sec-ft3 min-ccj SF

-=

An engineering factor used to provide a margin of safety for cumulated measurement uncertainties.

0.5 3.1.1.5 Determine CR, the calculated monitor count rate above background attributed to the noble gas radionuclides [cpm], by:

CR = (Cm)(E.)

(3.1-5) where:

Em

=

Obtained from the applicable effluent monitor efficiency curve located in the Station Curve Book. Use the radioactivity concentration C,," to find CR.

3.1.1.6 Determine the HSP, the monitor high-alarm setpoint including background [cpm], by:

HSP = CR +background (3.1-6) 3.1.2 Setpoint Based on Sample Analysis Prior to Release The following method applies to gaseous releases when determining the high-alarm setpoint with prior sample analysis and using the maximum acceptable effluent flow rate at the point of release. The method applies to the following conditions.

Batch Releases Containment purge.*

Containment pressure relief.

Waste gas decay tanks.

HBRODCM 3-4 Rev. 19

Continuous Releases Plant vent.

Fuel handling basement exhaust.

Environmental and Radiation Control Building Hood Exhaust.

Containment purge.

Radwaste Building exhaust vent.

Batch containment purge is considered as 1 volume of containment air removed.

3.1.2.1 Determine R., the noble gas release rate [LCi/sec] for radionuclide "i":

R. =472(C)(F)

(3.1-7) where:

472

=

A conversion factor to convert cfm to cc/sec.

C,

=

The radioactivity concentration of noble gas radionuclide "i" from analysis of gaseous effluent ([iCi/cc) from the Plant Vent (stack),

Fuel Handling Basement Exhaust, Environmental & Radiation Control (E&RC) Building Hood Exhaust, Radwaste Building Exhaust Vent and the Containment Vessel when R-12 is sampling from the Containment. If there are no isotopes identified in the sample, the EC for Xe-133 may be used as an actual value for the purpose of the setpoint calculation.

Containment Purge

[(Ci/cc. from analysis of Containment VentXO.366)]+

[([iCi/cc. from analysis of Plant VentXO.634)]

Containment Pressure Relief

[(iCi/cc. from analysis of Containment VentXO.040)]+

[(pCi/ccfrom analysis of Plant VentXO.960)]

HBRODCM 3-5 Rev. 1 9

Waste Gas Decay Tanks--

[VCi/ccfrom analysis of WGDTXO.0016)]+

[(jCi/cc. from analysis of Plant VentXO.9984)]

Waste Gas Decay Tanks during Containment Purge--

[(jCi/cc1 from analysis of WGDTX0.001)]+.

[(jCi/cc, from analysis of Plant VentXo.633)]+

[&Ci/cc, from analysis of C.V.XO.366)]

0.366 =

Dilution correction factor for C.V.

Purge 35,000 CFM (60,600 + 35,000) CFM 60,600 CFM 0.634=

Dilution correction factor for Plant Vent during C.V. Purge Dilution correction factor for C.V.

0.040 =Pressure Relief Dilution correction factor for Plant 0.960 Vent during C.V. Pressure Relief Dilution correction factor for Waste 0.0016 =Gas Decay Tank Dilution correction factor for Plant 0.9984 =Vent during WGDT Release Dilution correction factor for Waste 0.0010 = Gas Decay Tank during a Continuous C.V. Purge and Plant Vent Release (60,600 + 35,000) CFM 2,500 CFM (60,600+2,500) CFM 60,600 CFM (60,600+2,500) CFM 100 CFM (60,600+100)CFM 60,600 CFM (60,600+100) CFM 100 CFM (60,600+35,000+100) CFM Dilution correction factor for Plant 0.633 =

Vent during a Continuous C.V.

Purge and Plant Vent Release Dilution correction factor for 0.366 = Continuous C.V. Purge during WGDT Release 60,600 CFM (60,600 + 35,000 + 100) CFM 35,000 CFM (60,600+35,000+100) CFM HBRODCM 3-6 Rev. 19

F

=

The maximum acceptable effluent flow rate at the point of release (CFM)

=

60,600 CFM for the plant vent

=

10,200 CFM for the fuel handling basement exhaust

=

11,500 CFM for the E&RC building hood exhaust

=

15,000 CFM for the Radwaste Building exhaust vent

=

95,600 CFM for the containment vessel purge plus plant vent

=

63,100 CFM for the containment vessel pressure relief 60,700 CFM for the waste gas decay tank

=

95,700 CFM for the waste gas decay tank during a continuous containment vessel purge

=

35,000 CFM for containment vessel purge or continuous release

=

2,500 CFM for containment vessel pressure relief releases

2,500 CFM--Refer to Appendix B.3 for additional information HBRODCM 3-7 Rev. 19

3.1.2.2 Determine the monitor alarm setpoint based on total body and skin dose rate:

a.

Determine dose rate for total body (mrem/yr).

DRTB= (X/Q) Ei K. R.

(3.1-8) where:

(X/Q) =

The highest calculated annual average relative dispersion factor for any area at or beyond the unrestricted area boundary for all sectors (sec/M 3) from Appendix A.

=

8.1 E-5 sec/M3 (continuous ground release) from Table A-1, Appendix A. To be conservative this can be used for all releases.

=

9.9 E-7 sec/M 3 (continuous mixed mode release) from Table A-1 0, Appendix A, only with upper wind speeds of < 9 mph.

=

5.1 E-5 sec/M 3 (batch ground release) from Table A-7, Appendix A.

=

2.9 E-6 sec/M3 (batch mixed mode release) from Table A-1 6, Appendix A.

K,

=

The total whole body dose factor due to gamma emissions from noble gas radionuclide 'i" (mrem/yr I pCi/m3) from Table 3.1-2.

HBRODCM 3-8 Rev. 19

b.

Determine dose rate for skin (mrem/yr).

DRsK= (X/Q) A (L, + 1-1 M) R.

(3.1-9) where:

L, + 1.1 M,

=

The total skin dose factor for noble gas emission i radionuclide (mrem / yr / pCi/M3) from Table 3.1-2

c.

Determine the noble gas emission Projected Dose Rate Ratio (PDRR) for Total Body and Skin.

PDRR DRTB (3.1-10)

PDRRS__ = DRSKIN (3.1-11) 3000 where:

500

=

The allowable total body dose rate due to noble gas gamma emissions in mrem/yr.

3000

=

The allowable skin dose rate due to noble gas beta emissions in mrem/yr.

d.

Determine the maximum monitor setpoint concentration (pCVcc) for total body and skin.

Maximum Monitor Total Body Setpoint =

1 i) -(SF)(Tm)

(3.1-12)

(PDRR TB)

Maximum Monitor Skin Setpoint =(PDCR

-(SF)(Tm)

(3.1-13)

(PDRRSKIN)~~m 3

3 where:

SF

=

An engineering factor used to provide a margin of safety for cumulative uncertainties of measurements.

=

0.5 HBRODCM 3-9 Rev. 19

Tm

=

Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from several pathways.

=

0.92 for the Plant Vent Gas Monitor (R-14C).

=

0.05 for the Fuel Handling Basement Exhaust Monitor (R-20).

=

0.01 for other potential release points.

=

0.01 for the E&RC Building Hood Exhaust Monitor (R-22).

=

0.01 for the Radwaste Building exhaust vent Monitor (R-23).

=

0.81 for C.V. releases via R-1 1 and R-1 2 [This indicates 0.81 of 10 CFR 20 limits for Containment releases and is also monitored by R-14C. 0.92 = 0.81 + 0.11 (Normal Plant Releases)]

e.

Determine the maximum monitor setpoint (CPM) for total body (St) and skin (Ss).

S= (Maximum Total Body Setpoint in [lCi/cc)] + Bkg (Monitor Efficiency)

S

[(Maximum Skin Setpoint in,ICiicc)1 Bk (Monitor Efficiency)

(3.1-14)

(3.1-15)

Monitor efficiency Bkg

=

T

=

Obtained from the applicable effluent monitor efficiency curve located in the Station Curve Book.

Use the radioactivity concentration ([iCicc) to find (CPM).

he monitor background.

f.

Determine the actual gaseous monitor setpoint:

The setpoints that were determined based on the dose rate limits to the total body (St) and to the skin (Ss) are compared and the lesser value is used as the actual setpoint.

HBRODCM 3-10 Rev. 19

TABLE 3.1-1 GASEOUS SOURCE TERMS Condenser Vacuum Containment Purge or Plant Vent Release' Cnes Vacuu or Gas Decay Tanks3 Pump, Vent`

Pressure Relief Radionuclide S(Ci.

I r)

_(Ci/v a(Ci/

V(Ci

/ vr)

Kr-85m 2.0E0 5.26E-2 1.0E0 4.35E-2 0.00 0.00 0.00 0.00 Kr-85 0.00 0.00 0.00 0.00 0.00 0.00 1.6E2 8.00E-1 Kr-87 1.OE0 2.63E-2 0.00 0.00 0.00 0.00 0.00 0.00 Kr-88 3.0E0 7.89E-2 2.0E0 8.70E-2 1.0E0 2.90E-3 0.00 0.00 Xe-131 m 0.00 0.00 0.00 0.00 1.oE0 2.90E-3 9.0E0 4.50E-2 Xe-133m 0.00 0.00 0.00 0.00 4.OEO 1.16E-2 0.00 0.00 Xe-133 2.8E1 7.37E-1 1.8E+1 7.83E-1 3.1 E2 8.99E-1 3.1 E1 1.55E-1 Xe-135 4.OEO 1.05E-1 2.OEO 8.70E-2 4.OEO 1.16E-2 0.00 0.00 Ar-41 0.00 0.00 0.00 0.00 2.5E1 7.25E-2 0.00 0.00 TOTAL 3.8E1 2.3E1 3.45E2 2.0E2 Source terms are based upon GALE Code (not actual releases) from the evaluation of H.B. Robinson Unit 2 to demonstrate conformance to the design objectives of 10 CFR 50, Appendix I, Table 2-4. These values are only for routine releases and not for a complete inventory of gases in an eme rgency.

'These values are used to determine the monitor alarm setpoints for the Plant Vent Gas Monitor (R-14C).

2These values are used to determine the monitor alarm setpoint for the Condenser Vacuum Pump Vent Monitor (R-15). R-15 is a process monitor and its effluents are monitored by R-14A, R-14B and R-14C. This column is intentionally left for reference.

3These values are used to determine the monitor alarm setpoint for the Fuel Handling Basement Exhaust Monitor (R-20).

HBRODCM 3-11 Rev. 19

TABLE 3.1-2 DOSE FACTORS AND CONSTANTS Radionuclide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-i 31 m Xe-i 33m Xe-i 33 Xe-i 35m Xe-135 Xe-137 Xe-138 Xe-139 Ar-41 Total Whole Body Dose Factor (1(4 (mrem / yr / uCi/m3) 7.56E-2 1.17E3 1.61 El 5.92E3 1.47E4 1.66E4 1.56E4 9.15E1 2.51 E2

\\

2.94E2

\\ 3.12E3 1.81 E3 1.42E3 8.83E3 0.00 8.84E3 Total Skin Dose Factor L+1.1 MI (mrem / yr J I/Ci/m 3) 2.12E1 2.81 E3 1.36E3 1.65E4 1.91 E4 2.91 E4 2.52E4 6.48E2 1.35E3 6.94E2 4.41 E3 3.97E3 1.39E4 1.43E4 0.00 1.29E4 Regulatory Guide 1.109, October 1977, Table B-1, times (1.0E6 pCi/[LCi).

HBRODCM 3-12 Rev. 19

3.2 Requirements for Compliance With 10 CFR Part 20 - Radioactive Materials in Gaseous Effluents Applicability Applies to radioactive materials in gaseous effluents released from the site to unrestricted areas.

Obiective To define the dose rate limits for radioactive materials in gaseous effluents released to unrestricted areas.

Specification CONTROLS 3.2.1 The dose rate due to radioactive materials in gaseous effluents released from the site boundary (see Figure 7-1) shall be limited to the following:

a.

For radionoble gases: *500 mrem/yr to the total body, *3000 mrem/yr to the skin, and

b.

For 1-131, 1-133, and tritium, and for all radioactive materials in particulate form, inhalation pathway only, with half lives greater than 8 days: *1500 mrem/yr to any organ.

ACTIONS 3.2.2 With the dose rate(s) exceeding the above limits, without delay decrease the release rate to within the above limits. In addition, a notification must be made to the Commission in accordance with 10 CFR 50.72 and 10 CFR 50.73.

BASES Compliance With 10 CFR Part 20 - Radioactive Materials in Gaseous Effluents This specification is provided to ensure that the dose rate at any time at the site boundary from gaseous effluents from H. B. Robinson Unit No. 2 will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20 Appendix B, Table 2, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will result in the exposure of individuals outside the site boundary, to annual average concentrations within the limits specified in Appendix B Table 2 of 10 CFR Part 20, (10 CFR Part 20.1302). For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary unrestricted area. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rate equivalents above background to an individual in unrestricted areas to *500 mrem / year to the total body or to *3000 mrem / year to the skin HBRODCM 3-13 Rev. 19

3.3 COMPLIANCE WITH 10 CFR 20 (GASEOUS) 3.3.1 Noble Gases The gaseous effluent monitors setpoints are utilized to show compliance with 10 CFR 20 for noble gases. However, because they are based upon a conservative mix of radionuclides, the possibility exists that the setpoints could be exceeded and yet 10 CFR 20 limits may actually be met. Therefore, the following methodology has been provided in the event that if the alarm trip setpoints are exceeded, a determination may be made as to whether the actual releases have exceeded 10 CFR 20.

The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mrem I year to the total body and 3000 mrem / year to the skin. Based upon NUREG 0133, the following are used to show compliance with 10 CFR 20.

Y, K,[(X/Q)vQv + (X/Q )eQe < 500 mremnyr (3.3-1)

Y, (Li + 1.1 M.)[(X/Q ),Q1v + (X/Q )¢Q] < 3000 mrem/yr (3.3-2) where:

(X/Q)

=

Annual average relative dilution for plant vent releases at the site boundary, sec/m 3.

=

From Table A-1 for ground level releases used for additional conservatism.

=

From Table A-10 for mixed mode releases.

Q)e =

Annual average relative dilution for the Fuel Handling Basement Exhaust, the Environmental and Radiation Control Building Exhaust, and Radwaste Building Exhaust releases at the site boundary, sec/M3.

=

From Table A-1 for ground level releases.

K,

=

The total body dose factor due to gamma emissions for noble gas radionuclide "i," mrem / year per pCi/CM 3.

HBRODCM 3-14 Rev. 19

, =

The skin dose factor due to beta emissions for noble gas radionuclide 'i," mrem / year per [ICVM3.

M,

=

The air dose factor due to gamma emissions for noble gas radionuclide "i," mrad / year per [LCiVM3.

1.1

=

The ratio of the tissue to air absorption coefficients over the energy range of the photon of interest, mrem / mrad (reference NUREG 0133, October 1978).

Qe

=

The release rate of noble gas radionuclide "i" in gaseous effluents from the radwaste building exhaust vent, fuel handling basement exhaust, and the environmental and radiation control building hood exhaust, pCi/sec.

.V =

The release rate of noble gas radionuclide Ni in gaseous effluents from the plant vent pCi/sec.

The determination of limiting location for implementation of 10 CFR 20 for noble gases is a function of the radionuclide mix, release rate, and the meteorology. For the most limiting location, the radionuclide mix will be based on sample analysis of the effluent gases.

The X/Q value utilized in the equations for implementation of 10 CFR 20 is based upon the maximum long-term annual average (X/Q) in the unrestricted area. Table 3.3-2 presents the distances from HBR to the nearest area for each of the 16 sectors as well as to the nearest residence, vegetable garden, cow, goat, and beef animal. Long-term annual average (XIQ) values for the HBR release points to the special locations in Table 3.3-2 are presented in Appendix A. A description of their derivation is also provided in this appendix.

HBRODCM 3-15 Rev. 19

To select the limiting location, the highest annual average (xIQ) value for the ground level releases and the mixed mode releases was used. Since mixed mode releases may not necessarily decrease with distance (i.e., the site boundary may not have the highest I) value), long-term annual average IQ) values, calculated at the midpoint of 10 standard distances as given in Appendix A were also considered. For HBR, mixed mode release X/Q values decrease with distance for all directions except the WNW, NW, and NNW so that the maximum site boundary X/Q is usually greater at the site boundary than at distances greater than the site boundary. In addition, the maximum site boundary X/Q for both the ground level and mixed mode releases occurs at the SSE site boundary. Therefore, the limiting location for implementation of 10 CFR 20 for noble gases is the SSE site boundary.

Values for K, L, and M,, which were used in the determination of the limiting location and which are to be used by HBR in Expressions 3.3-1 and 3.3-2 to show compliance with 10 CFR 20, are presented in Table 3.3-3. These values were taken from Table B-1 of NRC Regulatory Guide 1.109, Revision 1.

The values have been multiplied by 1.0E6 to convert picocuries to microcuries for use in expressions 3.3-1 and 3.3-2.

HBRODCM 3-16 Rev. 19

3.3.2 Radioiodines, Particulates, and Tritium The dose rate in an unrestricted area resulting from the release of radioiodines, tritium, and particulates with half-lives > 8 days is limited to 1500 mrem /yr to any organ. Based upon NUREG 0133, the following is used to show compliance with 10 CFR 20:

t P,,[(X/Q )v~v + (X/Q ) e]

1500 mrem/yr (3.3 -3) where:

v =

Release rate of radionuclide '"i from the plant vent, iLCi / sec.

Qie

=

Release rate of radionuclide gin from the radwaste building exhaust vent, fuel handling building basement exhaust, and environmental and radiation control building exhaust, iLCi / sec.

(X/Q ), =

Annual average relative dilution for plant vent releases at the site boundary, sec / M3.

(X/Q)e=

Annual average relative dilution for fuel handling building basement exhaust, environmental and radiation control building exhaust, and radwaste building exhaust vent releases at the site boundary, sec / M3.

pi]

=

The dose parameter for lodine-1 31, lodine-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days for the inhalation pathway only in the most restrictive sector in mrem / yr per I+/-Ci/m3. The dose factor is based on the most restrictive group (child) and most restrictive organ at the SITE BOUNDARY (see Table 3.3-4).

where:

In the calculation to show compliance with 10 CFR 20, only the inhalation is considered. A description of the methodology used in calculating the P, values is presented in Appendix B.

Compliance with 10 CFR 20 is achieved if the dose rate via inhalation pathway to a child is

< 1500 mrem / year.

HBRODCM 3-17 Rev. 1 9

TABLE 3.3-1 RELEASES FROM H.B. ROBINSON UNIT NO. 2 (CVyr)

Condenser Vacuum Plant Vent Isotope

(,)

Pump Vent Total MQe Kr-85m 2.0E0 1.0E0 3.OEO Kr-85 1.6E2 0.00 1.6E2 Kr-87 1.OEO 0.00 1.OEO Kr-88 4.OEO 2.OEO 6.OEO Xe-131 m 1.OE1 0.00 1.OE1 Xe-1 33m 4.0E0 0.00 4.OEO Xe-133 3.7E2 1.8E1 3.9E2 Xe-1 35 8.0E0 2.0E0 1.OE1 1-131 3.6E-2 2.3E-2 5.9E-2 1-133 5.4E-2 3.4E-2 9.8E-2 Mn-54 4.7E-3 0.00 4.7E-3 Fe-59 1.6E-3 0.00 1.6E-3 Co-58 1.6E-2 0.00 1.6E-2 Co-60 7.3E-3 0.00 7.3E-3 Sr-89 3.4E-4 0.00 3.4E-4 Sr-90 6.3E-5 0.00 6.3E-5 Cs-1 34 4.7E-3 0.00 4.7E-3 Cs-137 7.8E-3 0.00 7.8E-3

Calculations based upon GALE Code and do not reflect actual release data from the Evaluation Conformance to the Design Objectives of 10 CFR 50, Appendix I. These values are only for routine releases and not for a complete inventory of gases in an emergency. Condenser vacuum pump vent is intentionally left in for reference.

HBRODCM 3-18 Rev. 19

TABLE 3.3-2 DISTANCE TO SPECIAL LOCATIONS FOR THE H.B. ROBINSON PLANT (MILES)

Sector NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW N

Site Boundary 1.26 1.01 0.86 0.61 0.50 0.29 0.26 0.28 0.29 0.36 0.36 0.50 0.55 1.23 1.89 1.94 Milk Cow 4.2 Milk Goat Meat Anim2 1.65 1.16 2.41 3.12 1.99 Nearest Resident 1.3 1.2 0.9 0.8 I

0.6 0.3 0.3 0.3 0.3 0.4 0.4 0.6 0.7 1.3 2.9 2.9 Nearest Garden

- 1.4 1.3 2.2 2.8 0.6 0.3 0.3 0.4 0.5 0.5 0.6 0.6 0.9 1.3 3.0 2.9 2.5*

2.32 2.08 2.27 2.69 3.97 4.07 1.60 2.84 2.93 Milk is not presently used for human consumption.

HBRODCM 3-19 Rev. 19

TABLE 3.3-3 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Radionuclide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-1 33m Xe-1 33 Xe-1 35m Xe-1 35 Xe-1 37 Xe-138 Ar-41 Total Body Dose

- Factor K (mrem/yr Per uCi/m3) 7.56E-02 1.17E+03 1.61 E+01 5.92E+03 1.47E+04 1.66E+04 1.56E+04 9.15E+01 2.51 E+02 2.94E+02 3.12E+03 1.81 E+03 1.42E+03 8.83E+03 8.84E+03 Skin Dose Factor l (mrem/vr Per uiCVm3) 1.46E+03 1.34E+03 9.73E+03 2.37E+03 1.01 E+04 7.29E+03 4.76E+02 9.94E+02 3.06E+02 7.11 E+02 1.86E+03 1.22E+04 4.13E+03 2.69E+03 Gamma Air

-Dose Factor M, (mrad/yr per IuCi/m 3) 1.93E+01 1.23E+03 1.72E+01 6.17E+03 1.52E+04 1.73E+04 1.63E+04 1.56E+02 3.27E+02 3.53E+02 3.36E+03 1.92E+03 1.51 E+03 9.21 E+03 9.30E+03 Beta Air Dose

- Factor N (mrad/yr per

[iCVm3) 2.88E+02 1.97E+03 1.95E+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.i1E+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03 The listed dose factors are for radionuclides that may be detected in gaseous effluents.

HBRODCM 3-20 Rev. 19

TABLE 3.3-4 Pi VALUES FOR A CHILD FOR H.B. ROBINSON UNIT NO. 21 Nucide Pi Bone P. Liver P. T Body P. Thyroid P, Kidney P, Lung P. GI-Tract P. Skin H-3 0 OOE+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 F-1 8 6 96E+03 O.OOE+00 6 85E+02 O.OOE+00 0 00E+00 0 OOE+O0 1.25E+03 O.OOE+00 NA-24 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04

- 1.61E+04 1.61E+04 O.OOE+00 CR-51 O.OOE+00 O.OOE+00 1.54E+02 8 55E+01 2.43E+01 1.70E+04 1.08E+03 O.OOE+00 MN-54 OOE+00 4 29E+04 9 51E+03 0 OOE+00 1.00E+04 1.58E+06 2.29E+04 O.OOE+00 MN-56 0 OOE+00 1.66E+00 3 12E-01 O.OOE+00 1.67E+00 1.31 E+04 1.23E+05 0 OOE+00 FE-55 4 74E+04 2.52E+04 7.77E+03 O.OOE+00 0 OOE+00 1.11E+05 2.87E+03 O.OOE+00 FE-59 2.07E+04 3.34E+04 1.67E+04 O.OOE+00 0 OOE+00 1.27E+06 7.07E+04 0 OOE+00 CO-57 O.OOE+00 9.03E+02 1.07E+03 0 OOE+00 O.OOE+00 5.07E+05 1.32E+04 O.OOE+00 CO-58 0 OOE+00 1.77E+03 3 16E+03 0 OOE+00 O.OOE+00 1.11 E+06 3 44E+04 O.OOE+00 CO-60 O.OOE+00 1.31 E+04 2.26E+04 0 OOE+00 O.OOE+00 7.07E+06 9 62E+04 0 OOE+0O NI-65 2.99E+00 2.96E-01 1.64E-01 0 OOE+00 0 OOE+00 8 18E+03 8.40E+04 0 OOE+00 CU-64 0 OOE+00 1.99E+00 1.07E+OO O.OOE+00 6 03E+00 9.58E+03 3 67E+04 0 OOE+00 ZN-65 4.26E+04 1.13E+05 7.03E+04 0 OOE+00 7.14E+04 9 95E+05 1.63E+04 O.OOE+00 BR-82 0 OOE+00 O.OOE+00 2.09E+04 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 BR-83 0 OOE+00 0 OOE+00 4.74E+02 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 BR-84 O.OOE+00 0 OOE+00 5 48E+02 0 OOE+00 O OOE+00 O.OOE+00 O OOE+00 0 OOE+00 RB-86 0 OOE+00 1.98E+05 1.14E+05 O.OOE+00 O.OOE+00 O.OOE+00 7.99E+03 O.OOE+00 RB-88 0 OOE+00 5.62E+02 3 66E+02 O.OOE+00 0 OOE+00 0 0OE+00 1.72E+01 0 OOE+00 RB-89 0 OOE+00 3 45E+02 2 90E+02 O.OOE+00 0 OOE+00 0 OOE+00 1.89E+00 0 OOE+00 SR-89 5.99E+05 0 OOE+00 1.72E+04 0 OOE+00 O.OOE+00 2 16E+06 1.67E+05 O.OOE+00 SR-90 1 01 E+08 0 OOE+00 6 44E+06 0 OOE+00 0 OOE+0O 1 48E+07 3 43E+05 0 OOE+00 SR-91 1.21 E+02 O.OOE+00 4.59E+00 0 OOE+O0 0 OOE+00 5 33E+04 1.74E+05 0 OOE+00 SR-92 1 31E+01 0 OOE+00 5.25E-01 O.OOE+00 O OOE+00 2.40E+04 2.422+05 0 OOE+00 Y-91 M 5 07E-01 0 00E+00 1.84E-02 0 OOE+00 O.OOE+00 2 81 E+03 1.72E+03 0 OOE+00 Y-91 9 14E+05 0 OOE+00 2 44E+04 0 OOE+00 O OOE+00 2.63E+06 1.84E+05 0 OOE+00 Y-92 2 04E+01 O.OOE+00 5 81E-01 O.OOE+00 O OOE+00 2.39E+04 2.39E+05 0 OOE+00 Y-93 1.86E+02 0 OOE+00 5 11E+00 0 OOE+00 0 OOE+00 7.44E+04 3 89E+05 O.OOE+00 ZR-95 1.90E+05 4 18E+04 3.70E+04 0 OOE+00 5.96E+04 2.23E+06 6 11E+04 0 OOE+00 ZR-97 1.88E+02 2.72E+01 1.60E+01 0 OOE+00 3 88E+01 1.13E+05 3 51E+05 0 OOE+00 (a)

NUREG 0133, Section 5.2.1.1 (Calculation of P, (Inhalation)).

(b)

Regulatory Guide 1.109 Table E-5, Table E-9 (Breathing Rate Constant and Inhalation dose factors).

(c)

Units are mrem t yr per pCi/M 3 HBRODCM 3-21 Rev. 1 9

TABLE 3.3-4 (continued)

Nuclide Pi Bone P. Liver P T Body P. Thyroid P. Kidney P. Lung P. GI-Tract P. Skin NB-95 2.35E+04 9 18E+03 6 55E+03 O.OOE+00 8.62E+03 6.14E+05 3.70E+04 O.OOE+00 NB-97 4 29E-01 7.70E-02 3 50E-02 O.OOE+00 8 55E-02

-3.42E+03 2.78E+16 0 OOE+00 MO-99 0 OOE+00 1.72E+02 4.25E+01 O.OOE+00 3.92E+02 1.35E+05 1.27E+05 0 OOE+00 TC-99M 1.78E-03 348E-03 5.77E-02 O.OOE+00 5.07E-02 9.51E+02 4.81E+03 0 OOE+00 TC-101 810E-05 8.51E-05 1.08E-03 O.OOE+00 1.45E-03 585E+02 1.63E+01 OOE+00 RU-103 2.79E+03 OOE+00 1.07E+03 O.OOE+00 7.03E+03 6 62E+05 4.48E+04 OOOE+00 RU-105 1.53E+00 0 OOE+00 5 55E-01 O.OOE+00 1.34E+00 1.59E+04 9.95E+04 0 OOE+00 RU-106 1.36E+05 0 OOE+00 1.69E+04 O.OOE+00 1.84E+05 1.43E+07

-4.29E+05 0 OOE+00 AG-110M 1.69E+04 1.14E+04 914E+03 OOE+00 2.12E+04 5.48E+06 1.00E+05 OOE+00 SN-113 8 99E+03 2 90E+02 9.81E+03 1.19E+02 2.03E+02 3.40E+05 7.44E+03 O.OOE+00 SB-124 5.74E+04 7.40E+02 2 OOE+04 1.26E+02 0 OOE+00 3 24E+06 1.64E+05 0 OOE+00 SB-125 9 84E+04 7.59E+02 2.07E+04 9 10E+01 O.OOE+00 2.32E+06 4 03E+04 0 OOE+00 TE-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 0 OOE+00 TE-129 9 77E-02 3.50E-02 2 38E-02 7.14E-02 2.57E-01 2.93E+03 2.55E+04 O.OOE+00 TE-131M 1 34E+02 5 92E+01 5 07E+01 9 77E+01 4 00E+02 2.06E+05 3.08E+05 0 OOE+00 TE-132 4.81 E+02 2.72E+02 2.63E+02 3.17E+02 1.77E+03 3 77E+05 1.38E+05 O.OOE+00 1-131 4.81E+04 4.81 E+04 2.73E+04 1.62E+07 7.88E+04 0 OOE+00 2.84E+03 OOE+00 1-132 2.12E+03 4.07E+03 1.88E+03 1.94E+05 6 25E+03 0 OOE+00 3.20E+03 0 OOE+00 1-133 1.66E+04 2 03E+04 7.70E+03 3 85E+06 3 38E+04 O.OOE+00 5 48E+03 0 OOE+00 1-134 1.17E+03 2.16E+03 9.95E+02 5 07E+04 3.30E+03 0 OOE+00 9.55E+02 0 OOE+00 1-135 492E+03 873E+03 4.14E+03 7.92E+05 1.34E+04 OOE+00 4.44E+03 O.OOE+00 CS-134 6 51 E+05 1 01E+06 2 25E+05 O.OOE+00 3 30E+05 1 21E+05 3 85E+03 0 OOE+00 CS-136 6 51E+04 1.71E+05 1.16E+05 O.OOE+00 9 55E+04 1.45E+04 4 18E+03 O.OOE+00 CS-1 37 9.07E+05 8.25E+05 1.28E+05 0 OOE+00 2.82E+05 1.04E+05 3 62E+03 O.OOE+00 CS-138 6 33E+02 8 40E+02 5.55E+02 O.OOE+00 6.22E+02 6 81E+01 2.70E+02 0 OOE+00 BA-139 1.84E+00 9 84E-04 5.36E-02 0 OOE+00 8.62E-04 5.77E+03 5.77E+04 0 ooE+00 BA-140 7.40E+04 648E+01 433E+03 OOE+00 2.11E+01 1.74E+06 1.02E+05 O.0OE+00 BA-142 4 99E-02 3 60E-05 2.79E-03 0 OOE+00 2.91 E-05 1.64E+03 2.74E+00 0 OOE+00 LA-140 6 44E+02 2 25E+02 7.55E+01 O.OOE+00 0 OOE+00 1.83E+05 2.26E+05 0 OOE+00 LA-142 1.29E+00 4.11 E-01 1.29E-01 0 OOE+00 0 OOE+00 8 70E+03 7.59E+04 0 OOE+00 CE-141 3 92E+04 1.95E+04 2.90E+03 0 OOE+00 8 55E+03 5 44E+05 5 66E+04 0 OOE+00 CE-143 3 66E+02 1.99E+02 2 87E+01 O.OOE+00 8.36E+01 1.15E+05 1.27E+05 O.OOE+00 CE-144 6.77E+06 2 12E+06 3 61E+05 O.OOE+00 1.17E+06 1.20E+07 3 89E+05 O.OOE+00 PR-144 5 96E-02 1.85E-02 3.00E-03 O.OOE+00 9.77E-03 1.57E+03 1.97E+02 0 OOE+00 HF-181 8 33E+04 3 28E+02 8.47E+03 2.76E+02 2.63E+02 7.96E+05 5.29E+04 O.OOE+00 W-187 1.63E+01 9.66E+00 433E+00 O.OOE+00 OOE+00 4.11E+04 9.10E+04 OOE+00 NP-239 4 66E+02 3 34E+01 2 35E+01 0 OOE+00 9 73E+01 5 81 E+04 6.40E+04 0 OOE+00 HBRODCM 3-22 Rev. 19

3.4 Requirements for Compliance With 10 CFR Part 50 - Radionoble Gases Applicability Applies to radionoble gases released in gaseous effluents to unrestricted areas.

Objective To define the air dose limits of 10 CFR 50 for radionoble gases released in gaseous effluents to unrestricted areas.

Specification CON TROLS 3.4.1 The air dose commitment due to radionoble gases released in gaseous effluents to areas at and beyond the site boundary (See Figure 7-1) shall be limited, at all times, to the following:

a.

During any calendar quarter, to s5 mrad for gamma radiation and s10 mrad for beta radiation;

b.

During any calendar year, to s10 mrad for gamma radiation and s20 mrad for beta radiation.

ONS ACTI 3.4.2 With the calculated air dose commitment from radioactive noble gases in gaseous effluents exceeding any of the limits, prescribed by ODCM Specification 3.4.1 above, prepare and submit a report to the Commission in accordance with the ODCM Specification 9.3.

HBRODCM 3-23 Rev. 19

Bases Compliance With 10 CFR part 50 - Radionoble Gases This specification is provided to implement the requirements of Section ll.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Control implementing the guides set forth in Section IV.A.of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept 'as low as reasonable achievable". The Surveillance Requirements implement the requirements in Section II.A of Appendix I that conformance with the guides of Appendix I be shown by calculative procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The methods 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 the Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.1 11, "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 dose commitments at the site boundary are based upon historical average atmospheric conditions.

HBRODCM 3-24 Rev. 1 9

3.5 COMPLIANCE WITH 10 CFR 50 (GASEOUS) 3.5.1 Noble Gases 3.5.1.1 Cumulation of Doses Based upon NUREG 0133, the air dose in the unrestricted area due to noble gases released in gaseous effluents can be determined by the following equations:

Dj=3.17X1j0 8 8Mj[(X/Q)VQ3 +(X/q)V qV, +(X/Q)cQIe (3.5-1)

Do = 3.17x1O8 L Na[(X/Q)yQ, +(X/q)yq1v+(X/Q)eQjI (3.5-2) where:

Dy The air dose from gamma radiation, mrad.

D

=

The air dose from beta radiation, mrad.

M

=

The air dose factor due to gamma emissions for each identified noble gas radionuclide "i," mrad / year per LiCVM3.

N,

=

The air dose factor due to beta emissions for each identified noble gas radionuclide Hin@ mrad / year per pCi/M3.

(XIQ )V =

The annual average dilution for areas at or beyond the unrestricted area boundary for long-term plant vent releases (> 500 hrs / year), sec / M3.

=

From Table A-1 for ground level releases used for conservatism.

=

From Table A-10 for mixed mode releases.

HBRODCMRv 3-25 Rev. 19

(X/q)y =

The dilution for areas at or beyond the unrestricted area boundary for short-term plant vent releases (a 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months / year), sec / M3.

=

From Table A-1 for ground level continuous release for conservatism.

=

From Table A-7 for ground level releases.

=

From Table A-16 for mixed mode releases.

(X/Q )e =

Annual average relative dilution for fuel handling basement exhaust, the environmental and radiation control building exhaust, and radwaste building exhaust vent releases at the site boundary, (> 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months / year), sec / M3.

=

From Table A-1 for ground level releases;

- =

The average release of noble gas radionuclide "i" in gaseous releases for short-term plant releases (a 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), [pCi; Qte

=

The average release of noble gas radionuclide "if in gaseous releases for long-term fuel handling basement exhaust, the environmental and radiation control building exhaust, and radwaste building exhaust (> 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months / year),

pci; Q

=

The average release of noble gas radionuclide I in gaseous effluents for long-term vent releases (> 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months / year), [LCi; 3.17x10-8 The inverse of the number of seconds in a year (sec/ year)-'.

At HBR the limiting location is 0.26 miles SSE. Based upon the tables presented in Appendix A, substitution of the short-term X/Q value into Equation 3.5-1 yields lower dose value than the long-term X/Q values used. In order to be conservative, for purposes of this document only, long-term annual average P) values will be used. Should the calculated doses exceed 10 CFR 50 limits, recalculation of doses may be performed using short-term X/Q values for batch releases.

HBRODCM 3-26 Rev. 19

To select the limiting location, the highest annual average X/Q value for ground level and mixed mode releases and the highest short-term X/Q value for ground level and mixed mode releases were considered. Since mixed mode releases may increase and then decrease with distance (i.e.,

the site boundary may not have the highest X/Q value), long-term X/Q values were calculated at the midpoint of 10 standard distances as given in Appendix A. The calculated values decreased with the distance for all but the WNW, NW, and NNW sectors. The values for these sectors were not found to be limiting such that the maximum site boundary X/Q for both long-term and short-term ground level and mixed mode releases occurred at the SSE site boundary. The limiting location for implementation of 10 CFR 20 for noble gases is the SSE site boundary.

Values for M, and N, which are utilized in the calculation of the gamma air and beta air doses in Equation 3.5-1 to show compliance with 10 CFR 50 were presented in Table 3.3-3. These values originate from NUREG 0472, Revision 0, and were taken from Table B-1 of the NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 1.OE6 to convert from picocuries to microcuries.

The following relationship should hold for HBR to show compliance with HBR's ODCM Specification 3.4.1.

For the calendar quarter:

D < 5 mrad (3.5 -3)

Do < 10 mrad (3.5-4)

For the calendar year:

DY < 10 mrad (3.5-5)

Do < 20 mrad (3.5-6)

The quarterly limits given above represent one-half of the annual design objectives of Section II.B.1 of Appendix I of 10 CFR 50. If any of the limits of Equations 3.5-3 through 3.5-6 are exceeded, a special report pursuant to ODCM Specification 9.3 must be filed with the NRC. This report complies with Section IV.A of Appendix I of 10 CFR 50.

HBRODCM 3-27 Rev. 19

3.5.1.2 Projection of Doses Doses resulting from the release of gaseous effluents will be projected once per 31 days. These projections will include a safety margin based upon expected operational conditions which will take into consideration both planned and unplanned releases.

Projected dose will be calculated as follows:

PD 31(DA + DB) +M (TE)

(3.5 -7) where:

PD DA

=

Projected doses in mrem.

=

Dose accumulated during current quarter in mrem.

DB

=

Projected dose from this release.

TE

=

Time elapsed in quarter in days.

M

=

Safety margin in mrem.

If the projected4doses &ceed 0.6 mrad for gamma radiation or 1.3 mrad for beta radiation when averaged over a calendar quarter, the ventilation exhaust treatment system will be operated to reduce releases of radioactive materials.

HBRODCM 3-28 Rev. 1 9

3.5.2 Compliance With 10 CFR Part 50- Radioiodines. Radioactive Materials in Particulate Form, and Radionuclides Other Than Radionoble Gases Applicability Applies to radioiodines, radioactive materials in particulate form, and radionuclides other than radionoble gases released from the site to unrestricted areas.

Obiective To define the dose limits of 10 CFR 50 for radioiodines, radioactive materials in particulate form, and radionuclides other than radionoble gases released from the site to unrestricted areas.

Specification CONTROLS 3.5.2.1 The dose to a member of the public from 1-131, 1-133, tritium and radioactive materials in particulate form, with half-lives greater than 8 days in gaseous effluents released to unrestricted areas (See Figure 7-1), shall be limited, at all times, to the following:

a.

During any calendar quarter, *7.5 mrem to an organ and, b.

During any calendar year, *15 mrem to any organ.

ACTIONS 3.5.2.2 With the calculated dose commitment from the release of 1-131, 1-133, tritium and radioactive materials in particulate form, with half lives greater than 8 days, in gaseous effluents exceeding any of the limits prescribed by ODCM Specification 3.5.2.1 above, prepare and submit a report to the Commission in accordance with ODCM Specfication 9.3.

HBRODCM 3-29 Rev. 19

BASES Compliance With 10 CFR Part 50- Radioiodines, Radioactive Materials in Particulate Form, and Radionuclides Other Than Radionoble Gases This specification is provided to implement the requirements of Section I.C, lll.A, and IV.A of Appendix 1, 10 CFR Part 50. The Control implements the guides set forth in Section I1.C of Appendix I. The action statement provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials as gaseous effluents will be kept "as low as reasonably achievable." The surveillance requirements implement the requirements in Section II.A of Appendix I that conformance with the guides of Appendix I be shown by calculative procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The methods established in the ODCM for calculating the doses due to the actual release rates of the subject materials are 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 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.1 11, "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 commitment are based upon historical average atmospheric conditions.

HBRODCM 3-30 Rev. 19

3.5.3 Radioiodine, Particulates and Tritium 3.5.3.1 Cumulation of Doses Section I1.C of Appendix I of 10 CFR 50 limits the release of radioiodines and radioactive material in particulate form from each reactor such that estimated annual dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. Based upon NUREG 0133, the dose to an organ of an individual from radioiodines, tritium, and particulates with half-lives 28 days in gaseous effluents released to unrestricted areas can be determined by the following equation:

DT = 3.17x10-8 Zi Ri, [(X/Q),Q1, + (XQ)eQie+ (X/q), q1 ] +

(RIB + RIM + Ri, + Ri,)[(D/Q), Q 1 + (D/q ),q,, + (D/Q )e Qje] +

(RTM + RT1 + RT. + RTV)[(X/Q ), QTV + (X/q ) qTV + (X/Q)e QTE]

(3.5 -8) where:

D

=

Dose to any organ Xr from 1-131, 1-133, particulates with 28 day half-lives, and Tritium in mrem.

8 3.17 x 10

=

The inverse of the number of seconds in a year, (sec/year)'.

(X/Q) =

Annual average relative concentration for plant vent releases (> 500 hrs / yr),

sec/m 3.

=

From Table A-1 for ground level releases for conservatism.

=

From Table A-10 for mixed mode releases.

(X/Q)C=

Annual average dilution for radwaste building vent, fuel handling basement exhaust, and the environmental and radiation control building hood exhaust releases (> 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months / yr), sec / m3.

=

From Table A-1 for ground level releases.

HBRODCM 3-31 Rev. 19

(X/q )v =

Annual average relative concentration for plant vent releases (s500 hrs / yr),

sec / M3.

=

From Table A-7 for ground release.

=

From Table A-1 6 for mixed mode releases.

(D/Q), =

Annual average deposition factor for plant vent releases (>500 hrs / yr), m 2.

=

From Table A-3 for ground level releases for conservatism.

=

From Table A-12 for mixed mode releases.

(D/q), =

Relative deposition factor for short-term plant vent releases ( 500 hrs / yr),

m-2.

=

From Table A-3 for ground level continuous releases for conservatism.

=

From Table A-9 for ground level releases.

=

From Table A-18 for mixed mode releases.

(D/Q)e=

Annual average relative deposition factor for radwaste building vent, fuel handling basement exhaust, and the environmental and radiation control building hood exhaust releases (> 500 hrs / yr), m-2.

=

From Table A-3 for ground level releases.

Qie Release of radionuclide '"i in gaseous effluents for long-term radwaste building vent, fuel handling basement exhaust, and the environmental and radiation control building hood exhaust releases (> 500 hrs /yr),.ICi.

Qv

=

Release of radionuclide "i" in gaseous effluents for long-term plant vent releases (> 500 hrs / yr), [+/-Ci.

qv

=

Release of radionuclide Ni" in gaseous effluents for short-term plant vent releases ( 500 hrs / yr), pCi.

HBRODCM 3-32 Rev. 19

RIG

=

Dose factor for an organ for radionuclide "i" for the ground plane exposure pathway, mrem I yr per pCi I sec per m-2.

RI

=

Dose factor for an organ for radionuclide "i" for the inhalation pathway, mrem / yr per lICi / m3.

RIV

=

Dose factor for an organ for radionuclide "Y" for the vegetable pathway, mrem I yr per tLCi I m-2.

RTv

=

Dose factor for an organ for tritium for the vegetable pathway, mrem I yr per tICi/M3.

RTi

=

Dose factor for an organ for tritium for the inhalation pathway, mrem I yr per pCVm3.

QTV Release of tritium in gaseous effluents for long-term plant vent releases

(> 500 hrs /yr), plCi.

Rim

=

Dose factor for an organ for radionuclide "i" for the milk exposure pathway, mrem / yr per pCi I sec per m2.

RTM

=

Dose factor for an organ for tritium for the milk pathway, mrem I yr per pCi / m3.

RTB.

Dose factor for an organ for tritium for the meat pathway, mrem / yr per tLCi/rM3 RIB

=

Dose factor for an organ for radionuclide i" for the meat exposure pathway, mrem / yr per pCi / sec I m2.

QTE

=

Release of tritium in gaseous effluents for long-term radwaste building vent, fuel handling basement exhaust, and the environmental and radiation control building hood exhaust (>500 hrs I yr), pCi.

QTV

=

Release of tritium in gaseous effluents for short-term plant vent releases (L500 hrs / yr), plCi.

HBRODCM 3-33 Rev. 1 9

To show compliance with 10 CFR 50, Equation 3.5-8 is evaluated at the limiting pathway location. At HBR this location is the vegetable garden 0.3 miles in the SSE sector. The critical receptor is a child.

Substitution of the appropriate X/Q and D/Q values from tables in Appendix A into Equation 3.5-8 would yield an equation with the short-term X/Q and D/Q values being less than the long-term values. Therefore, for this document, only long-term annual X/Q and D/Q values (i.e., more conservative values) are used.

The determination of a limiting location for implementation of 10 CFR 50 for radioiodines and particulates is a function of:

1.

Radionuclide mix and isotopic release

2.

Meteorology

3.

Exposure pathway

4.

Receptor's age In the determination of the limiting location, the radionuclide mix of radioiodines and particulates was based upon the source terms calculated using the GALE Code. This mix is presented in Table 3.3-1 as a function of release point. The only source of short-term releases from the plant vent is containment purges. In the determination of the limiting location, all of the exposure pathways, as presented in Table 3.3-2, were evaluated. These include cow milk, goat milk, beef and vegetable ingestion, and inhalation and ground plane exposure.

An infant was assumed to be present at all milk pathway locations. A child was assumed to be present at all vegetable garden and beef animal locations. The ground plane exposure pathway was not considered a viable pathway for an infant. Naturally, the inhalation pathway was present everywhere an individual was present. HBR ODCM Specification 4.4.1 requires that a land-use census survey be conducted on an biennial basis. The age groupings at the various receptor locations are also determined during this survey; a new limiting location and receptor age group can result.

For the determination of the limiting location, the highest D/Q values for the vegetable garden, cow milk, and goat milk pathways were selected. The thyroid dose was calculated at each of these locations using the radionuclide mix and releases of Table 3.3-1. Based upon these calculations, it was determined that the limiting receptor pathway is the vegetable/child pathway.

In the determination of the limiting location, annual average X/Q and D/Q values are used. A description of the derivation of the various X/Q and D/Q values is presented in Appendix A.

HBRODCM 3-34 Rev. 19

Short-term and long-term X/Q and D/Q values for ground level releases and for long-term mixed mode releases are provided in tables in Appendix A. They may be utilized if an additional special location arises different from those presented in the special locations of Table 3.3-2.

Tables 3.5-1 through 3.5-19 present R, values for the total body, GI-tract, bone, liver, kidney, thyroid, skin, and lung organs for the ground plane, inhalation, cow milk, goat milk, vegetable, and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the pathways.

These values were calculated using the methodology described in NUREG 0133 using a grazing period of eight months. A description of the methodology is presented in Appendix B.

The following relationship should hold for HBR to show compliance with HBR ODCM Specification 3.5.2.1.

For the calendar quarter:

DI < 7.5 mrem (3.5-9)

For the calendar year:

D* < 15 mrem (3.5-10)

The quarterly limit given above represent one-half the annual design objectives of Section I.C of Appendix I of 10 CFR 50. If any of the limits of Equations 3.5-9 or 3.5-10 are exceeded, a special report pursuant ODCM Specification 9.3 must be filed with the NRC. This report complies with Section IV.A of Appendix I of 10 CFR 50.

3.5.2.2 Projection of Doses Doses resulting from release of radioiodines and particulate effluents will be projected once per 31 days. These projections will include a safety margin based upon expected operational conditions which will take into consideration both planned and unplanned releases.

HBRODCM 3-35 Rev. 19

Projected dose will be calculated as follows:

PD 3 1(DA+DB)+M (3.5-11)

(TE) where:

PD

=

Projected doses in mrem.

DA

=

Dose accumulated during current quarter in mrem.

DB

=

Projected dose from this release.

TE

=

Time elapsed in quarter in days.

M

=

Safety margin in mrem.

If the projected doses exceed 1.0 mrem to any organ when averaged over a calendar quarter, the ventilation exhaust treatment system will be operated to reduce releases of radioactive materials.

HBRODCM 3-36 Rev. 19

TABLE 3.5-1 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT' (Reference Regulatory Guide 1.109)

PATHWAY = Ground Nucide Bone Liver T.Bodv Thyroid Kidney Lun GI-Tract Skin F-1 8 3.96E+05 3 96E+05 3 96E+05 3.96E+05 3.96E+05 3.96E+05 3 96E+05 4 66E+05 NA-24 1.19E+07 1.19E+07 1.19E+07 1.19E+07 1.19E+07 1.19E+07 1.19E+07 1.39E+07 CR-51 4.66E+06 4.66E+06 4.66E+06 4.66E+06 4.66E+06 4 66E+06 4.66E+06 5.51 E+06 MN-54 1.39E+09 1.39E+09 1.39E+09 1.39E+09 1.39E+09 1.39E+09 1.39E+09 1.62E+09 MN-56 9 03E+05 9.03E+05 9 03E+05 9 03E+05 9.03E+05 9.03E+05 9 03E+05 1.07E+06 FE-59 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 3.21 E+08 CO-57 1.88E+08 1.88E+08 1.88E+08 1.88E+08 1.88E+08 1.88E+08 1.88E+08 2.07E+08 CO-58 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3 79E+08 3.79E+08 3.79E+08 4.44E+08 CO-60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.53E+10 NI-65 2.97E+05 2.97E+05 2 97E+05 2.97E+05 2.97E+05 2.97E+05 2.97E+05 3.45E+05 CU-64 6.07E+05 6.07E+05 6.07E+05 6.07E+05 6.07E+05 6.07E+05 6 07E+05 6 88E+05 ZN-65 7.47E+08 7.47E+08 7.47E+08 7.47E+08 7.47E+08 7.47E+08 7.47E+08 8 59E+08 BR-82 2.14E+07 2.14E+07 2.14E+07 2.14E+07 2.14E+07 2.14E+07 2.14E+07 2 47E+07 BR-83 4.87E+03 4 87E+03 4.87E+03 4.87E+03 4 87E+03 4 87E+03 4.87E+03 7.08E+03 BR-84 2.03E+05 2 03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.36E+05 RB-86 8.99E+06 8.99E+06 8.99E+06 8 99E+06 8 99E+06 8.99E+06 8 99E+06 1.03E+07 RB-88 3 31 E+04 3.31 E+04 3.31 E+04 3.31 E+04 3 31 E+04 3 31 E+04 3 31 E+04 3.78E+04 RB-89 1 23E+05 1.23E+05 1 23E+05 1.23E+05 1.23E+05 1.23E+05 1.23E+05 1.48E+05 SR-89 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2 51E+04 SR-91 2.15E+06 2.15E+06 2.15E+06 2.15E+06 2.15E+06 2.15E+06 2.15E+06 2.51E+06 SR-92 7.77E+05 7.77E+05 7.77E+05 7.77E+05 7.77E+05 7.77E+05 7.77E+05 8.63E+05 Y-91M 1.OOE+05 1.00E+05 1.00E+05 1 OOE+05 1.00E+05 1.00E+05 1.OOE+05 1.16E+05 Y-91 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.21 E+06 Y-92 1.80E+05 1.80E+05 1.80E+05 1.80E+05 1.80E+05 1.80E+05 1.80E+05 2 14E+05 Y-93 1.83E+05 1.83E+05 1.83E+05 1.83E+05 1.83E+05 1.83E+05 1.83E+05 2.51 E+05 ZR-95 2.45E+08 2.45E+08 2.45E+08 2A5E+08 2.45E+08 2.45E+08 2 45E+08 2 84E+08 ZR-97 2.96E+06 2 96E+06 2.96E+06 2.96E+06 2.96E+06 2 96E+06 2.96E+06 3 44E+06 NB-95 1.37E+08 1.37E+08 1.37E+08 1.37E+08 1.37E+08 1.37E+08 1.37E+08 1.61 E+08 NB-97 1.76E+05 1.76E+05 1.76E+05 1.76E+05 1.76E+05 1.76E+05 1.76E+05 2.07E+05 MO-99 3.99E+06 3.99E+06 3 99E+06 3 99E+06 3 99E+06 3 99E+06 3.99E+06 4 63E+06 TC-99M 1.84E+05 1.84E+05 1.84E+05 1.84E+05 1.84E+05 1.84E+05 1.84E+05 2.11 E+05 TC-101 2.04E+04 2.04E+04 2.04E+04 2 04E+04 2.04E+04 2.04E+04 2.04E+04 2 26E+04

'R Values in units of mrem/yr per micro-CVm3 for inhalation and tritium, and in units of m2 mrem/yr per micro-Ci/sec for all others.

HBRODCM 3-37 Rev. 19

TABLE 3.5-1 (continued)

Nuclide RU-103 RU-105 RU-106 AG-11OM SN-i13 SB-124 SB-125 TE-129M TE-129 TE-131 M TE-1 32 1-131 1-132 1-133 1-134 1-135 CS-134 CS-136 CS-1 37 CS-138 BA-139 BA-140 BA-1 42 LA-140 LA-142 CE-141 CE-143 CE-144 PR-144 HF-181 W-1 87 NP-239 Bone 1.08E+08 6.36E+05 4.22E+08 3.44E+09 1.42E+07 5.98E+08 2.34E+09 1.98E+07 2.62E+04 8.03E+06 4 23E+06 1.72E+07 1.25E+06 2.45E+06 4.47E+05 2.53E+06 6 86E+09 1.51 E+08 1.03E+10 3.59E+05 1.06E+05 2.05E+07 4 49E+04 Liver 1.08E+08 6.36E+05 4.22E+08 3 44E+09 1.42E+07 5.98E+08 2.34E+09 1.98E+07 2.62E+04 8 03E+06 4.23E+06 1.72E+07 1.25E+06 2.45E+06 4.47E+05 2.53E+06 6.86E+09 1.51 E+08 1.03E+10 3.59E+05 1.06E+05 2.05E+07 4 49E+04 T Body 1.08E+08 6 36E+05 4.22E+08 3 44E+09 1.42E+07 5.98E+08 2.34E+09 1.98E+07 2.62E+04 8.03E+06 4 23E+06 1.72E+07 1.25E+06 2.45E+06 4.47E+05 2.53E+06 6.86E+09 1.51E+08 1.03E+10 3 59E+05 1.06E+05 2.05E+07 4.49E+04 1.92E+07 7.60E+05 1.37E+07 2.31 E+06 6 95E+07 1.83E+03 1.96E+08 2 35E+06 1.71 E+06 Thyroid 1.08E+08 6 36E+05 4 22E+08 3.44E+09 1.42E+07 5 98E+08 2.34E+09 1.98E+07 2 62E+04 8 03E+06 4.23E+06 1.72E+07 1.25E+06 2.45E+06 4.47E+05 2.53E+06 6.86E+09 1.51 E+08 1.03E+10 3.59E+05 1.06E+05 2.05E+07 4.49E+04 1.92E+07 7.60E+05 1.37E+07 2.31 E+06 6 95E+07 1.83E+03 1.96E+08 2.35E+06 1.71 E+06 Kidney 1.08E+08 6 36E+05 4 22E+08 3.44E+09 1.42E+07 5.98E+08 2.34E+09 1.98E+07 2.62E+04 8 03E+06 4.23E+06 1.72E+07 1.25E+06 2 45E+06 4.47E+05 2.53E+06 6 86E+09 1.51 E+08 1.03E+10 3 59E+05 1.06E+05 2.05E+07 4 49E+04 1.92E+07 7.60E+05 1.37E+07 2.31 E+06 6 95E+07 1.83E+03 1.96E+08 2.35E+06 1.71 E+06 Lung GI-Tract 1.08E+08 1.08E+08 6 36E+05 6.36E+05 4 2E+08 4.22E+08 3 44E+09 1.42E+07 5.98E+08 2.34E+09 1.98E+07 2 62E+04 8 03E+06 4.23E+06 1.72E+07 1.25E+06 2.45E+06 4.47E+05 2.53E+06 6.86E+09 1.51 E+08 1.03E+10 3 59E+05 1.06E+05 2 05E+07 4.49E+04 1.92E+07 7.60E+05 1.37E+07 2 31 E+06 6.95E+07 1.83E+03 1.96E+08 2.35E+06 1.71 E+06 3.44E+09 1.42E+07 5.98E+08 2.34E+09 1.98E+07 2.62E+04 8.03E+06 4.23E+06 1.72E+07 1.25E+06 2.45E+06 4.47E+05 2.53E+06 6 86E+09 1.51E+08 1.03E+10 3.59E+05 1.06E+05 2.05E+07 4.49E+04 1.92E+07 7.60E+05 1.37E+07 2 31 E+06 6.95E+07 1.83E+03 1.96E+08 2.35E+06 1.71 E+06 Skin 1.26E+08 7.21 E+05 5.07E+08 4.01 E+09 4.08E+07 6.90E+08 2.64E+09 2.31 E+07 3.1 OE+04 9.46E+06 4 98E+06 2.09E+07 1 A6E+06 2.98E+06 5.30E+05 2.95E+06 8 OOE+09 1.71E+08 1.20E+10 4.10E+05 1.19E+05 2.35E+07 5.t 1 E+04 2 18E+07 9.11E+05 1.54E+07 2 63E+06 8.04E+07 2.11 E+03 2.80E+08 2.73E+06 1.98E+06 1.92E+07 1.92E+07 7.60E+0(

7.60E+05 1.37E+07 1.37E+07 2.31 E+06 2.31 E+06 6.95E+07 6 95E+07 1.83E+03 1.83E+03 1.96E+08 1.96E+08 2.35E+06 2.35E+06 1.71 E+06 1.71 E+06 HBRODCM 3-38 Rev. 19

TABLE 3.5-2 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT2 (Reference Regulatory Guide 1.109)

PATHWAY = Vegetation AGE GROUP = Adult Nuclide H-3 F-1 8 NA-24 CR-51 MN-54 MN-56 FE-55 FE-59 CO-57 CO-58 C0-60 NI-65 CU-64 ZN-65 BR-82 BR-83 BR-84 RB-86 RB-88 RB-89 SR-89 SR-90 SR-91 SR-92 Y-91 M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 NB-97 MO-99 Bone O.00E+00 4.22E+00 2.68E+05 0.OOE+00 o 00E+00 0.00E+00 2.00E+08 1.24E+08 0.OOE+00 O.00E+00 0.00E+00 5.97E+01 0 00E+00 4.01 E+08 0.OOE+00 O.OOE+00 0.00E+00 0.00E+00 o 00E+00 O OOE+00 9.77E+09 671E+11 3.02E+05 4.15E+02 4.76E-09 4.98E+06 8.96E-01 1.68E+02 1.14E+06 3 36E+02 1.40E+05 2.02E-06 0 OOE+00 Liver 2.26E+03 0.00E+00 2.68E+05 0.00E+00 3.08E+08 1.54E+01 1.38E+08 2.90E+08 1.01 E+07 2.99E+07 1.67E+08 7.75E+00 9.19E+03 1.28E+09 o 00E+00 o 00E+00 0 O0E+00 2 21E+08 2.66E-22 2.90E-26 0.00E+00 0 OOE+00 o 00E+00 O.O0E+00 0 OOE+00 0 O0E+00 0 00E+00 0 00E+00 3 66E+05 6.78E+01 7.80E+04 5.11E-07 6.18E+06 T.Bodv 2.26E+03 4.68E-01 2.68E+05 4.59E+04 5.87E+07 2.74E+00 3.22E+07 1.11 E+08 1.88E+07 6.70E+07 3 67E+08 3.54E+00 4 31 E+03 5 77E+08 1.55E+06 3.1 0E+00 2.21 E-11 1.03E+08 1.41 E-22 2 04E-26 2.80E+08 1.65E+11 1.22E+04 1.79E+01 1.84E-10 1.33E+05 2.62E-02 4 65E+00 2.48E+05 3.10E+01 4.19E+04 1.87E-07 1.18E+06 Thyroid 2.26E+03 0 OOE+00 2.68E+05 2.74E+04 0 00E+00 0.00E+00 0 00E+00 O00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.002+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 O.00E+00 0.00E+00 0.00E+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0 OOE+00 Ktdney 2.26E+03 0.00E+00 2.68E+05 1.01 E+04 9.15E+07 1.96E+01 O00E+00 0 00E+00 0.00E+00 0 O0E+00 0 O0E+00 0.00E+00 2.32E+04 8 54E+08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 OOE+00 0.00E+00 0 00E+00 0.00E+00 0 OOE+00 0.00E+00 0 00E+00 0.00E+00 5.75E+05 1.02E+02 7.71 E+04 5.96E-07 1 AOE+07 Lung 2.26E+03 0 00E+00 2 68E+05 6 09E+04 0.00E+00 0.00E+00 7.70E+07 8 11E+07 0 O0E+00 0 OOE+00 0 O0E+00 0 00E+00 0.00E+00 0.00E+00 O.OOE+00 0 O0E+00 0 O0E+00 0 00E+00 0.00E+00 0.00E+00 0 OOE+00 0.00E+00 0 OOE+00 0 00E+00 0 OOE+00 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 O.O0E+00 O.O0E+00 GI-Tract 2.26E+03 1.25E-01 2.68E+05 1.15E+07 9.42E+08 4.93E+02 7.91E+07 9.68E+08 2.86E+08 6.06E+01 3.13E+09 1.97E+02 7.83E+05 8 04E+08 1.78E+06 4 47E+00 1.73E-16 4.35E+07 3 67E-33 0 OOE+00 1.57E+09 1.94E+10 1.44E+06 8.22E+03 1.40E-08 2.74E+09 1.57E+04 5.34E+06 1.16E+09 2.1 OE+07 4.73E+08 1.89E-03 1.43E+07 Skin 2.26E+03 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0 OOE+00 O.O0E+00 0.00E+00 0 00E+00 O.00E+00 O.OOE+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0 OOE+00 0 O0E+00 0 00E+00 0 00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 2R Values in units of mrem / yr per micro-Ci/m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-Ci / sec for all others.

HBRODCM 3-39 Rev. 19

TABLE 3.5-2 (continued)

Nucdde Bone Liver T Body Thvroid Kidney Luna GI-Tract Skin TC-99M 3.10E+00 8.75E+00 1.11E+02 O.OOE+00 1.33E+02 429E+00 5.18E+03 O.OOE+00 TC-101 6.00E-31 8 64E-31 8.47E-30 O.OOE+00 1.56E-29 4.41 E-31 O.OOE+00 0 OOE+00 RU-103 4.72E+06 O.OOE+00 2.03E+06 0 OOE+00 1.80E+07 O.OOE+00 5.51E+08 O.OOE+00 RU-105 5.30E+01 0 OOE+00 2.09E+01 O.OOE+00 6 85E+02 O.0OE+00 3.24E+04 O.OOE+00 RU-1 06 1.95E+08 O.OOE+00 2.47E+07 O.OOE+00 3.76E+08 0 OOE+00 1.26E+10 O.OOE+00 AG-110M 1.13E+07 1.05E+07 6 22E+06 0OOE+00 2.06E+07 O.OOE+00 4.27E+09 O.OOE+00 SN-113 1.43E+07 550E+05 1.35E+07 1.94E+05 4.04E+05 O.OOE+00 2.49E+08 O.OOE+00 SB-124 1.01E+08 1.91E+06 4.01E+07 2.45E+05 O.OOE+00 7.88E+07 2.87E+09 O.OOE+00 SB-125 1.34E+08 1.50E+06 3.20E+07 1.37E+05 0 OOE+00 1.04E+08 1.48E+09 O.OOE+00 TE-129M 2.94E+08 1.1OE+08 4.65E+07 1.01 E+08 1.23E+09 O.OOE+00 1.48E+09 O.OOE+00 TE-129 7.52E-04 2.83E-04 1.83E-04 5 77E-04 3.16E-03 O.OOE+00 5.68E-04 0 OOE+00 TE-131M 9.63E+05 4.71 E+05 3.93E+05 7.46E+05 4.77E+06 O.0OE+00 4.68E+07 0 OOE+00 TE-132 4 58E+06 2.96E+06 2.78E+06 3 27E+06 2.85E+07 O.OOE+00 1.40E+08 O.OOE+00 1-131 8.07E+07 1.15E+08 6.61E+07 3.78E+10 1.98E+08 0 OOE+00 3 04E+07 O.OOE+00 1-132 5.57E+01 1.49E+02 5.21 E+01 5 21E+03 2.37E+02 O.OOE+00 2.80E+01 O.OOE+00 1-133 2.08E+06 361E+06 1.10E+06 5.31E+08 6 31E+06 0 OOE+00 325E+06 0 OOE+00 1-134 8 84E-05 2.40E-04 8 59E-05 4.16E-03 3.82E-04 O.OOE+00 2.09E-07 0 OOE+00 1-135 3.85E+04 1.01E+05 3.72E+04 6.65E+06 1.62E+05 O.0OE+00 1.14E+05 0 OOE+00 CS-134 4 55E+09 1.08E+10 8 84E+09 O.OOE+00 3.50E+09 1.16E+09 1.89E+08 O.OOE+00 CS-136 426E+07 1.68E+08 1.21E+08 OOE+00 9.36E+07 1.28E+07 1.91E+07 O.OOE+00 CS-137 6 64E+09 9.08E+09 5.95E+09 O.OOE+00 3 08E+09 1.03E+09 1.76E+08 0 OOE+00 CS-138 339E-11 6.70E-11 332E-11 O.OOE+00 4.92E-11 4.86E-12 2.86E-16 0OE+00 BA-139 2.70E-02 1.93E-05 7.91E-04 0 OOE+00 1.80E-05 1.09E-05 4.79E-02 0 OOE+00 BA-140 1.28E+08 1.61 E+05 8.40E+06 O.OOE+00 5.47E+04 9 22E+04 2.64E+08 O.OOE+00 LA-140 1.97E+03 9.95E+02 2 63E+02 0 OOE+00 O.OOE+00 O.OOE+00 7.30E+07 O.OOE+00 LA-142 1.92E-04 8.75E-05 2.18E-05 0 OOE+00 0 OOE+00 0 OE+00 639E-01 O.OOE+00 CE-141 1.94E+05 1.31 E+05 1A9E+04 O.OOE+00 6 10E+04 O.OOE+00 5.02E+08 O.OOE+00 CE-143 9.96E+02 7.36E+05 8.15E+01 O.OOE+00 3 24E+02 O.OOE+00 2.75E+07 O.OOE+00 CE-144 3.15E+07 1.32E+07 1.69E+06 0 OOE+00 7.81E+06 O.OOE+00 1.07E+10 0 OOE+00 PR-144 2.36E-26 9.81 E-27 1.20E-27 O.OOE+00 5.53E-27 O.OOE+00 3.40E-33 OOE+00 HF-181 9.50E+06 5.36E+04 1.08E+06 3.40E+04 4.47E+04 O.OOE+00 7.05E+08 O.OOE+00 W-187 3.79E+04 3.17E+04 1.11E+04 O.OOE+00 O.OOE+00 0 OOE+00 1.04E+07 O.OOE+00 NP-239 1.43E+03 1.40E+02 7.73E+01 0 OOE+00 4.37E+02 0 OOE+00 2 88E+07 O.OOE+00 HBRODCM 3-40 Rev. 19

TABLE 3.5-3 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT3 (Reference Regulatory Guide 1.109)

PATHWAY = Vegetation AGE GROUP = Teen Nuclide H-3 F-1 8 NA-24 CR-51 MN-54 MN-56 FE-55 FE-59 CO-57 CO-58 c0-60 NI-65 CU-64 ZN-65 BR-82 BR-83 BR-84 RB-86 RB-88 RB-89 SR-89 SR-90 SR-91 SR-92 Y-91 M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 NB-97 Bone O.OOE+00 3 83E+00 2.38E+05 O.OOE+00 O.OOE+00 O.OOE+00 3.10E+08 1.76E+08 O.OOE+00 0 OOE+00 O.OOE+00 5.56E+01 O.OOE+00 5.36E+08 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 1.48E+10 8 33E+1 1 2.83E+05 3 86E+02 4 43E-09 7.64E+06 8 42E-01 1.58E+02 1 67E+06 3 11E+02 1.89E+05 1.87E-06 Liver 2.59E+03 O.OOE+00 2.38E+05 O.OOE+00 4.47E+08 1.39E+01 2 20E+08 4 10E+08 1.72E+07 4.24E+07 2.48E+08 7.10E+00 8 33E+03 1.86E+09 O.OOE+00 O.OOE+00 O.OOE+00 2.75E+08 2 46E-22 2.61 E-26 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O OOE+00 O.OOE+00 5 28E+05 6.15E+01 1.05E+05 4 65E-07 T.Bodv 2.59E+03 4.20E-01 2.38E+05 6 09E+04 8.86E+07 2.48E+00 5.13E+07 1.58E+08 2.89E+07 9.78E+07 5 58E+08 3 23E+00 3 92E+03 8.68E+08 1.37E+06 2.91 E+00 2 01 E-t 1 1.29E+08 1.31 E2-22 1.84E-26 4 25E+08 2.06E+11 1.12E+04 1.65E+01 1.69E-10 2.05E+05 2.43E-02 4 33E+00 3 63E+05 2.83E+01 5.78E+04 1.70E-07 Thyroid 2.59E+03 0 OOE+00 2.38E+05 3 38E+04 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 Kidney 2.59E+03 O.OOE+00 2.38E+05 1.34E+04 1.33E+08 1.76E+01 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 2.11 E+04 1.19E+09 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 7.76E+05 9.33E+01 1.02E+05 5 44E-07

-Lung GI-Tract 2.59E+03 2.59E+03 Skin 2.59E+03 O.OOE+00 2.38E+05 8.70E+04 O.OOE+00 O.OOE+00 1.40E+08 1.29E+08 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 00E+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 3.45E-01

^0.00E+00 2 38E+05 1.02E+07 9.16E+08 9.17E+02 9.53E+07 9.70E+08 3 21 E+08 5.85E+08 3.23E+09 3.85E+02 6.46E+05 7.88E+08 0 O0E+00 0 OOE+00 O.OOE+00 4.07E+07 2.11E-29 4 OOE-35 1.77E+09 2.34E+10 1.28E+06 9.84E+03

.2.09E-07 3.13E+09 2.31 E+04 4.82E+06 1.22E+09 1.67E+07 4 49E+08 1.11E-02 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 MO-99 O.OOE+00 5.67E+06 1.08E+06 0 OOE+00 1.30E+07 0 OOE+00 1.02E+07 O.OOE+00 3R Values in units of mrem/yr per micro-Ci/m3 for inhalation and tritium, and in units of m2 mrem/yr per micro-Ci/sec for all others.

HBRODCM 3-41 Rev. 19

TABLE 3.5-3 (continued)

Nuclide TC-99M TG-101 RU-103 RU-105 RU-106 AG-110M SN-113 SB-124 SB-125 TE-129M TE-129 TE-131 M TE-132 1-131 1-132 1-133 1-134 I-135 CS-134 CS-136 CS-137 CS-138 BA-139 BA-140 LA-140 LA-142 CE-141 CE-143 CE-144 PR-144 HF-181 W-187 NP-239 Bone Liver T Bodv Thyroid Kidney Luna 2.73E+00 7.62E+00, 9 87E+01 0 OOE+00 1.13E+02 4.23E+00 5 58E-31 7.93E-31 7.79E-30 0 OOE+00 1.43E-29 4.83E-31 6.75E+06 O.OOE+0O 2.88E+06 0 OOE+0O 2.38E+07 O.OOE+00 4 93E+01 O.OOE+00 1.91E+01 O.OOE+00 6 22E+02 O.OOE+00 3 13E+08 O.OOE+OO 3.94E+07 O.OOE+00 6 03E+08 0 OOE+00 1.63E+07 1.54E+07 9.37E+06 O.OOE+00 2.94E+07 O.OOE+00 1.88E+07 7.89E+05 2.OOE+07 2.60E+05 5.58E+05 10 OOE+00 1.51 E+08 2.78E+06 5 88E+07 3 42E+05 O.OOE+00 1.32E+08 2.1i E+08 2 30E+06 4.92E+07 2 01 E+05 O.OOE+00 1.85E+08 4.23E+08 1.57E+08 6.69E+07 1.36E+08 1.77E+09 O.OOE+00 7.04E-04 2.63E-04 1.71 E-04 5.03E-04 2.96E-03 0 OOE+00 8 92E+05 4.2BE+05 3 57E+05 6.43E+05 4 46E+06 0 OOE+00 4.16E+06 2.64E+06 2 48E+06 2.78E+06 2.53E+07 0 OOE+00 7.67E+07 1.07E+08 5 77E+07 3.14E+10 1.85E+08 0 OOE+00 5.02E+01 1.31 E+02 4.72E+01 4.43E+03 2.07E+02 O.OOE+00 1.93E+06 3 27E+06 9.99E+05 4.57E+08 5 74E+06 0 OOE+O0 7.99E-05 2.12E-04 7.61 E-05 3 53E-03 3 34E-OA 0 OOE+00 3 48E+04 8.96E+04 3 32E+04 5.77E+06 1 42E+05 0 OOE+00 6 92E+09 1.63E+10 7.55E+09 O.OOE+00 5.17E+09 1.97E+09 4 36E+07 1.72E+08 1.15E+08 0 OOE+00 9.35E+07 1.47E+07 1.06E+10 1.41E+10 490E+09 OOOE+00 479E+09 1.86E+09 3.13E-11 601E-11 301E-11 OOOE+00 4.44E-11 5 16E-12 2 54E-02 1.79E-05 7.41 E-04 0 OOE+0O 1.69E-05 1 23E-05 1.38E+08 1.69E+05 8.87E+06 0 OOE+00 5 72E+04 1.13E+05 1.80E+03 8 66E+02 2.36E+02 O.OOE+00 0 OOE+00 0 OOE+00 1.77E-04 7.85E-05 1.95E-05 O.OOE+00 0 OOE+00 0 OOE+00 2.79E+05 1.86E+05 2.14E+04 O.OOE+00 8 76E+04 0 OOE+00 9.31 E+02 6.77E+05 7.56E+01 0 OOE+00 3 04E+02 0 OOE+00 5 05E+07 2.09E+07 2 71 E+06 0 OOE+00 1.25E+07 O.OOE+00 2.22E-26 9 07E-27 1.12E-27 O.OOE+00 5.20E-27 O.OOE+00 1.38E+07 7.58E+04 1.54E+06 4.62E+04 6.30E+04 O.OOE+00 3.53E+04 2.87E+04 1.01 E+04 0 OOE+00 O.OOE+00 0 OOE+00 1.38E+03 1.31 E+02 7.25E+01 O.OOE+00 4 1 OE+02 0 OOE+00 GI-Tract Skin 5.OOE+03 O.OOE+00 1.36E-37 O.OOE+00 5.64E+08 O.OOE+0O 3.98E+04 O.OOE+00 1.50E+10 O.OOE+00 4.33E+09 0 OOE+00 2.26E+08 0 OOE+00 3 04E+09 0 OOE+00 1.64E+09 O.OOE+00 1.59E+09 O.OOE+00 3 85E-03 O.OOE+00 3 43E+07 0 OOE+OO 8 35E+07 0 OOE+00 2.13E+07 0 OOE+00 5.73E+01 0 OOE+OO 2.48E+06 O.OOE+OO 2.79E-06 0 OOE+00 9 93E+04 0 OOE+00 2.02E+0 0 OOE+00 1.38E+07 0 OOE+00 2.OOE+08 0 OOE+00 2.73E-14 0 OOE+00 2.27E-01 O.OOE+00 2.12E+08 0 OOE+00 5 09E+07 0 OOE+00 2.39E+00 0 OOE+00 5.32E+08 0 OOE+00 2.04E+07 0 OOE+00 1.27E+1 0 O.OOE+0O 2.44E-29 O.OOE+00 6.89E+OB 0 OOE+00 7.78E+06 0 OOE+00 2.1OE+07 O.OOE+00 HBRODCM 3-42 Rev. 19

TABLE 3.5-4 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT4 (Reference Regulatory Guide 1.109)

PATHWAY = Vegetation AGE GROUP = Child Nuclide H-3 F-18 NA-24 CR-51 MN-54 MN-56 FE-55 FE-59 C0-57 C0-58 CO-60 NI-65 CU-64 ZN-65 BR-82 BR-83 BR-84 RB-86 RB-88 RB-89 SR-89 SR-90 SR-91 SR-92 Y-91M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 NB-97 SR-91 SR-92 Y-91M Y-91 Y-92 Bone 0.00E+00 6 84E+00 3.72E+05 O.OOE+00 O OOE+00 O.OOE+00 7.63E+08 3.89E+08 O.OOE+00 O.OOE+00 0.OOE+0O 1.02E+02 O.OOE+00 1.03E+09 O OOE+00 O OOE+00 O.OOE+00 O.OOE+O0 O OOE+00 0.00E+00 3.52E+10 1.38E+12 5 20E+q5 7.08E+02 8.12E-09 1.82E+07 1.55E+00 2.91 E+02 3 75E+06 5 68E+02 4.04E+05 3 41 E-06 5 20E+05 7.08E+02 8.12E-09 1.82E+07 1.55E+00 Liver 4 01 E+03 O.OOE+00 3.72E+05 O.OOE+00 6.54E+08 1.82E+01 4.05E+08 6 30E+08 2.88E+07 6.27E+07 3.77E+08 9.60E+00 1.10E+04 2.74E+09 O.OOE+00 O.OOE+00 O.OOE+00 4.55E+08 3 39E-22 3 43E-26 O OOE+00 O.OOE+00 O.60E+00 O OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O OOE+00 8 25E+05 8.20E+01 1.57E+05 6.16E-07 O OOE+00 O.OOE+00 O OOE+00 O OOE+00 0.00E+00 T Body 4.01 E+03 6 78E-01 3.72E+05 1.16E+05 1.74E+08 4.t 1 E+00 1.25E+08 3.14E+08 5.83E+07 1.92E+08 1.11 E+09 5.60E+00 6 63E+03 1.70E+09 2.1 OE+06 5.36E+00 341E-1I 2.80E+08 2.36E-22 3.05E-26 1.01 E+09 3 50E+11 1.96E+04 2.84E+01 2 95E-10 4.86E+05 4.44E-02 7.98E+00 7.34E+05 4 84E+01 1.12E+05 2.88E-07 1.96E+04 2.84E+01 2.95E-10 4.86E+05 4.44E-02 Thyroid 4.01 E+03 O.OOE+00 3.72E+05 6.42E+04 0.00E+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O OOE+00 0 OOE+00 O OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0 OOE+00 Kidney 4.01 E+03 O.OOE+00 3.72E+05 1.75E+04 1.83E+08 2.20E+01 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0.00E+00 O.OOE+00 2 65E+04 1.72E+09 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 1.18E+06 1.18E+02 1.48E+05 6 84E-07 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00

. LunA 4.01 E+03 O.OOE+00 3.72E+05 1.17E+05 0 OOE+00 O.OOE+00 2.29E+08 1.83E+08 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 GI-Tract 4.01 E+03 1.85E+00 3.72E+05 6.14E+06 5 49E+08 2.64E+03 7.50E+07 6.56E+08 2.36E+08 3.65E+08 2.09E+09 1.1 8E+03 5.15E+05 4.81 E+08 O.OOE+00 O.OOE+00 0 OOE+00 2 93E+07 1.66E-23 2.99E-28 1.36E+09 1.86E+10 1.1 5E+06 1.34E+04 1.59E-05 2.42E+09 4.48E+04 4.34E+06 8.60E+08 1.24E+07 2.91 E+08 1.90E-01 1.15E+06 1.34E+04 1.59E-05 2.42E+09 4.48E+04 Skin 4.01 E+03 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 4R Values in units of mrem / yr per micro-Ci / m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-Ci I sec for all others.

HBRODCM 3-43 Rev. 1 9

TABLE 3.5-4 (continued)

Nuclide Y-93 ZR-95 ZR-97 NB-95 NB-97 MO-99 TC-99M TC-101 RU-103 RU-105 RU-1 06 AG-110M SN-113 SB-124 SB-125 TE-129M TE-129 TE-131M TE-132 1-131 1-132 1-133 1-134 1-135 CS-134 CS-136 CS-137 CS-138 BA-139 BA-140 LA-140 LA-142 CE-141 CE-143 CE-144 PR-144 HF-181 W-187 NP-239 Bone '

2.91 E+02 3.75E+06 5.68E+02 4 04E+05 3 41E-06 0 OOE+00 4.70E+00 1.03E-30 1.52E+07 9.02E+01 7.54E+08 3.45E+07 3 60E+07 3 43E+08 4 91E+08 9.83E+08 1.30E-03 1.63E+06 7.46E+06 1.43E+08 8 92E+01 3 52E+06 1.42E-04 6.18E+04 1.56E+10 8.22E+07 2.50E+10 5.69E-l l 4 69E-02 2.76E+08 3.24E+03 3 20E-04 6 46E+05 1.71 E+03 1.22E+08 4.11E-26 3.12E+07 6 41 E+04 2.56E+03 Liver 0 OOE+00 8 25E+05 8.20E+01 1.57E+05 6 16E-07 7.75E+06 9 21 E+00 1.07E-30 O.OOE+00 O.OOE+00 O.OOE+00 2.33E+07 1.16E+06 4.46E+06 3.79E+06 2.74E+08 3 64E-04 5 63E+05 3 30E+06 1.44E+08 1.64E+02 4.35E+06 2.64E-04 1.11 E+05 2.56E+10 2.26E+08 2 39E+10 7.92E-l l 2.50E-05 2 42E+05 1.13E+03 1.02E-04 3 22E+05 9 29E+05 3 82E+07 1.27E-26 1.22E+05 3.80E+04 1.84E+02 T Body 7.98E+00 7.34E+05 4.84E+01 1.12E+05 2.88E-07 1.92E+06 1.53E+02 1.36E-29 5.83E+06 3.27E+01 9.40E+07 1.86E+07 3.93E+07 1.20E+08 1.03E+08 1.53E+08 3.09E-04 5.99E+05 3 99E+06 8.16E+07 7.53E+01 1.65E+06 1.21 E-04 5.27E+04 5 41 E+09 1.46E+08 3.53E+09 5.02E-1 1 1.36E-03 1.61 E+07 3.82E+02 3.20E-05 4.79E+04 1.35E+02 6 50E+06 2.07E-27 3.14E+06 1.70E+04 1.29E+02 Thyroid 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 4.75E+05 7.58E+05 4 55E+05 3.17E+08 9.30E-04 1.16E+06 4 81 E+06 4.75E+10 7.60E+03 8 08E+08 6 07E-03 9 86E+06 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 1.03E+05 O.OOE+00 O.OOE+00 Kidney O.OOE+00 1.18E+06 1.18E+02 1.48E+05 6.84E-07 1.65E+07 1.34E+02 1.83E-29 3 82E+07 7.93E+02 1.02E+09 4.34E+07 7.96E+05 O.OOE+00 0 OOE+00 2 89E+09 3.81 E-03 5.45E+06 3.07E+07 2 36E+08 2.51 E+02 7.25E+06 4.03E-04 1.71 E+05 7.94E+09 1.20E+08 7.79E+09 5.57E-11 2.18E-05 7.87E+04 O.OOE+00 O.OOE+00 1.41 E+05 3.90E+02 2.11 E+07 6.73E-27 9.80E+04 0 OOE+00 5.31 E+02 Lunq O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 4.68E+00 5.68E-31 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.91 E+08 2.74E+08 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OC O.OOE+00 O.OOE+00 O.OOE+00 0 0OE+00 2 85E+09 1.79E+07 2.80E+09 5.99E-12 1.47E-05 1.44E+05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 GI-Tract 4 34E+06 8 60E+08 1.24E+07 2.91 E+08 1.90E-01 6.41 E+06 5.24E+03 3 41 E-30 3.92E+08 5.89E+04 1.17E+10 2.77E+09 1.44E+08 2.15E*09 1.17E+09 1.20E+09 8.12E-02 2.28E+07 3.32E+07 1.28E+07 1.93E+02 1.75E+06 1.75E-04 8 48E+04 1.38E+08 7.94E+06 1.50E+08 3 65E-11 2.71 E+00 1.40E+08 3.16E+07 2.02E+01 4.02E+08 1.36E+07 9 95E+09 2.74E-23 5.18E+08 5 34E+06 1.36E+07 Skin O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.0OE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 HBRODCM 3-44 Rev. 19

TABLE 3.5-5 r-R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT'

?Nj f(Reference Regulatory Guide 1.109)

PATHWAY = Meat AGE GROUP =Adult Nuclide Bone Uver T.Body Thyroid Kidney Lung GI-Tract Skin H-3 O.OOE+00 3 24E+02 3 24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 NA-24 1.39E 1.39E-03 1.39E-03 1.39E-03 1.39E-03 1.39E-03 1.39E-03 O.OOE+00 CR-51 O.OOE+00 0.00E+O0 6.30E+03 3.76E+03 1.39E+03 8.36E+03 1.58E+06 O.OOE+00 MN-54 O.OOE+00 7.33E+06 1AOE+06 O.OOE+00 2.18E+06 O.OOE+00 2.24E+07 O.OOE+00 FE-55 2.28E+08 1.58E+08 3.68E+07 O.OOE+00 O.OOE+00 8.81 E+07 9.06E+07 0.00E+00 FE-59 2.28E+08 5.36E+08 2.05E+08 0 OOE+00 O.OOE+00 1.50E+08 1.79E+09 O.OOE+00 C0-57 O.OOE+00 4.01 E+06 7.43E+06 O.OOE+00 O.OOE+00 O.OOE+00 1.13E+08 O.OOE+00 C0-58 O.OOE+00 1.52E+07 3.40E+07 O.OOE+00 O.OOE+00 O.OOE+00 3.07E+08 O.OOE+00 C0-60 O.OOE+00 5.96E+07 1.31E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.12E+09 O.OOE+00 CU-64 O.OOE+00 2.80E-07 1.31 E-07 O.OOE+00 7.05E-07 O.OOE+00 2.38E-05 O.OOE+00 ZN-65 3.20E+08 1.02E+09 4.60E+08 O.OOE+00 6 81 E+08 O.OOE+00 6.42E+08 0 OOE+00 BR-82 O.OOE+00 O.OOE+00 1.25E+03 O.OOE+00 O.OOE+00 O.OOE+00 1.43E+03 0.00E+00 RB-86 0.00E+00 4 53E+08 2.11E+08 O.OOE+00 0 OOE+00 0.00E+00 8.94E+07 0 OOE+00 SR-89 2.57E+08 0 OOE+00 7.37E+06 0 OOE+0O 0 OOE+00 0 OOE+00 4.12E+07 O.OOE+00 SR-90 1.03E+10 O.OOE+00 2.53E+09 O.OOE+00 0 OOE+00 O.OOE+00 2.98E+08 O.OOE+00 SR-91 1.58E-10 O.OOE+00 6 39E-12 O.oOE+00 O.OOE+00 0 OOE+O0 7.53E-10 O.OOE+00 Y-91 9.53E+05 O.OOE+00 2.55E+04 O.OOE+00 0 OOE+00 O.OOE+00 5 24E+08 0 OOE+00 Y-93 4.87E-12 0 OOE+00 1.35E-13 0 OOE+00 O OOE+00 O.OOE+00 1.55E-07 0 OOE0O0 ZR-95 1.57E+06 5 02E+05 3.40E+05 O.OOE+00 7.88E+05 0.00E+00 1.59E+09 0 OOE+O0 ZR-97 2.11 E-05 4.27E-06 1.95E-06 O.OOE+00 6 44E-06 O.OOE+00 1.32E+00 O.OOE+00 NB-95 2.01E+06 1.12E+06 6.02E+05 O.OOE+00 1.11E+06 O.OOE+00 6.79E+09 O.OOE+00 MO-99 O.OOE+00 1.01 E+05 1.92E+04 O.OOE+00 2.28E+05 O.OOE+00 2.33E+05 0 OOE+00 TC-99M 4.76E-21 1.35E-20 1.71E-19 O.OOE+00 2.04E-19 6.59E-21 7.96E-18 O.OOE+00 RU-103 9.15E+07 O.OOE+00 3.94E+07 O.OOE+00 3.49E+08 O.OOE+00 1.07E+10 O.OOE+00 RU-105 6 30E-28 O.OOE+00 2.49E-28 O.OOE+00 8.15E-27 O.OOE+00 3.86E-25 O.OOE+00 RU-106 2.26E+09 O.OOE+00 2.85E+08 O.OOE+00 4.36E+09 O.oOE+00 1.46E+11 O.OOE+00 AG-110M 5.57E+06 5.15E+06 3.06E+06 O.OOE+00 1.01E+07 0OOE+00 2.10E+09 0.00E+00 SN-1 13 3.94E+07 1.52E+06 3.73E+07 5.36E+05 1.12E+06 O.OOE+00 6.89E+08 O.OOE+00 SB-124 1.66E+07 3.14E+05 6.60E+06 4.03E+04 O.OOE+00 1.30E+07 4.72E+08 O.OOE+00 SB-125 1.51E+07 1.69E+05 3.59E+06 1.53E+04 O.OOE+00 1.16E+07 1.66E+08 0O0E+00 TE-129M 1.07E+09 3 99E+08 1.69E+08 3 67E+08 4A6E+09 0 OOE+00 5.38E+09 0.00E+00 5R Values in units of mrem/yr per micro-Ci/mr3 for inhalation and tritium, and in units of m2 mrem/yr per micro-Ci/sec for all others.

HBRODCM 3-45 Rev. 19

TABLE 3.5-5 (continued)

Nuclide TE-131M TE-132 1-131 1-133 1-135 CS-134 CS-136 CS-137 BA-140 LA-140 CE-141 CE-143 CE-144 HF-181 W-187 NP-239 Bone 4.66E+02 1.46E+06 1.06E+07 3.72E-01 4.69E-17 5.18E+08 1.15E+07 7.04E+08 2.75E+07 3.74E-02 1.24E+04 2.03E-02 1.15E+06 1.79E+08 2.08E-02 2.61 E-01 Liver 2.28E+02 9.44E+05 1.51 E+07 6.47E-01 1.23E-16 1.23E+09 4.54E+07 9.63E+08 3.45E+04 1.89E-02 8.37E+03 1.50E+01 4.82E+05 1.01 E+06 1.74E-02 2.56E-02 T Bodv 1.90E+02 8.86E+05 8.66E+06 1.97E-01 4.53E-17 1.01 E+09 3.27E+07 6.31 E+08 1.80E+06 4.99E-03 9 49E+02 1.66E-03 6.19E+04 2.03E+07 6.09E-03 1.41 E-02 Thyroid 3.61 E+02 1.04E+06 4.95E+09 9.51 E+01 8.10E-15 O.OOE+00 O.OOE+00 O.OOE+OO 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.41 E+05 O OOE+00 O.OOE+00 Kidney 2.31 E+03 9 09E+06 2.59E+07 1.13E+00 1.97E-16 3.99E+08 2.53E+07 3 27E+08 1.17E+04 O.OOE+00 3 89E+03 6 61E-03 2 86E+05 8 41E+05 O.OOE+00 8 OOE-02 Lunq O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 1.32E+08 3.46E+06 1.09E+08 1.98E+04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 GI-Tract 2.26E+04 4.46E+07 3 99E+06 5.82E-01 1.39E-16 2.16E+07 5.16E+06 1.86E+07 5.66E+07 1.38E+03 3 20E+07 5.61 E+02 3.90E+08 1.33E+10 5.71 E+00 5.26E+03 Skin O.OOE+00 O OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 0OE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 HBRODCM 3-46 Rev. 19

TABLE 3.5-6 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT6 (Reference Regulatory Guide 1.109)

PATHWAY = Meat AGE GROUP =Teen Nucdide H-3 NA-24 CR-51 MN-54 FE-55 FE-59 CO-57 CO-58 CO-60 CU-64 ZN-65 BR-82 RB-86 SR-89 SR-90 SR-91 Y-91 Y-93 ZR-95 ZR-97 NB-95 MO-99 TC-99M RU-103 RU-1 05 RU-106 AG-11OM SN-113 SB-124 SB-125 TE-129M TE-131M Bone 0 OOE+00 1.11E-03 O.OOE+00 O.OOE+O0 t.86E+08 1.82E+08 O.OOE+OO O OOE+00 O.OOE+O0 0.OOE+OO 2.25E+08 0 OOE+00 0 OOE+00 2.17E+08 6 68E+09 1.33E-10 8 03E+05 4.11E-12 1.25E+06 1.76E-05 1.57E+06 0 OOE+00 3.78E-21 7.45E+07 5 27E-28 1.90E+09 4 21E+06 2.78E+07 1.36E+07 1.24E+07 8 96E+08 3 89E+02 Liver 1.93E+02 1.11E-03 0 OOE+00 5.59E+06 1.32E+08 4.25E+08 3 59E+06 1.17E+07 4.62E+07 2.28E-07 7.82E+08 0 OOE+00 3.78E+08 O.OOE+O0 O.OOE+O0 0 OOE+00 0 OOE+00 0 OOE+00 3.96E+05 3 49E-06 8.72E+05 8.33E+04 1.05E-20 O.OOE+O0 O.OOE+00 O.OOE+OO 3.99E+06 1.16E+06 2.50E+05 1.35E+05 3.32E+08 1.86E+02 T.Bodv 1.93E+02 1.11E-03 5.04E+03 1.11E+06 3 07E+07 1.64E+08 6 02E+06 2.69E+07 1.04E+08 1.07E-07 3 65E+08 9.94E+02 1.78E+08 6 21E+06 1.65E+09 5.29E-12 2.15E+04 1.13E-13 2.72E+05 1.61E-06 4.80E+05 1.59E+04 1.37E-19 3.18E+07 2.05E-28 2.39E+08 2.43E+06 2.95E+07 5.30E+06 2.89E+06 1.42E+08 1.55E+02 Thyroid 1.93E+02 1.11E-03 2.80E+03 OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+OO O.OOE+OO O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O OOE+00 O.OOE+O0 O.O0E+O0 O.OOE+OO O.O0E+O0 O.OOE+00 O.OOE+O0 0 OOE+00 O.OOE+OO 0 OOE+00 0 OOE+00 O.OOE+OO O.OOE+O0 0.OOE+O0 O.OOE+OO 3.84E+05 3.08E+04 1.1 8E+04 2.89E+08 Kidney 1.93E+02 1.1 1 E-03 1.1OE+03 1.67E+06 OOOE+00 0.OOE+O0 0.OOE+OO 0.OOE+00 OOOE+00 5.77E-07 5.00E+08 O.OOE+OO O.O0E+OO 0OOE+00 0 OOE+OO O OOE+00 O.OOE+00 0 OOE+00 5.82E+05 5.29E-06 845E+05 1.91 E+05 1.57E-19 263E+08 6.65E-27 3 66E+09 7.60E+06 8.23E+05 0 OOE+0O O.OOE+OO 3 75E+09 Lung 1.93E+02 1.11E-03 7.19E+03 O.OOE+O0 8.35E+07 1.34E+08 0 OOE+00 O OOE+00 O.OOE+OO 0 OOE+OO 0OOE+00 0 00E+0 OOE+00 O.OOE+OO O.OOE+O0 00WE+00 0 OOE+00 00WE+00 O.O0E+OO 0 OOE+00 O.OOE+00 002E+00 5.85E-21 O.OOE+OO O.oOE+O0 O.00E+00 O.W0E+OO O.W0E+O0 1.1 9E+07 1.09E+07 0 OOE+00 Gi-Tract 1.93E+02 1.11E-03 8.46E+05 1.15E+07 5.69E+07 1.01E+09 6.70E+07 1.61E+08 6 02E+08 1.77E-05 331E+08 O.OOE+O0 5.60E+07 2.58E+07 1.88E+08 6.04E-1 0 3.29E+08 1.26E-07 9.13E+08 9.44E-01 3.73E+09 1.49E+05 6 92E-18 6.22E+09 4.26E-25 9.11E+10 1.12E+09 3 33E+08 2.74E+08 9.61E+07 3.36E+09 Skin 1.93E+02 O.OOE+OO O.OOE+O0 O.OOE+W0 0 OOE+00 O.OOE+OO O.OOE+O0 O.OOE+OO O.OOE+O0 O.OOE+OO O.00E+00 0 00E+O0 O.W0E+0O 0.OOE+OO O.OOE+OO O.OOE+00 0 W0E+00 0 OOE+OO O.OOE+00 0 OOE+00 O.00E+W0 002E+OO 0 OOE+00 O.OOE+O0 OOE+00 0o0E+00 OOE+00 O.OOE+O0 O.OOE+00 OOE+00 OOE+00 2.80E+02 1.94E+03 O.OOE+00 1.50E+04 0 OOE+00 6R Values in units of mrem / yr per micro-Ci / m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-Ci / sec for all others.

HBRODCM 3-47 Rev. 19

TABLE 3.5-6 (continued)

Nucihde Bone Liver T Body Thyroid Kidney Luna GI-Tract Skin TE-132 1.1 9E+06 7.56E+05 7.12E+05 7.97E+05 7.25E+06 O.OOE+OO 2AOE+07 O.OOE+O0 1-131 8.78E+06 1.23E+07 6.60E+06 3 59E+09 2.12E+07 O.OOE+OO 2.43E+06 0 OOE+O0 1-133 3.11E-01 5.28E-01 1.61E-01 7.37E+01 9.26E-01 O.OOE+OO 3.99E-01 O.OOE+0O 1-135 3.82E-17 9.83E-17 3.64E-17 6.32E-15 1.55E-16 O.OOE+0O 1.09E-16 0 OOE+0O CS-134 4.12E+08 9.69E+08 4.50E+08 O.OOE+00 3 08E+08 1.1 8E+08 1.21 E+07 O.OOE+0O CS-136 8.97E+06 3 53E+07 2 37E+07 O.OOE+0O 1.92E+07 3.03E+06 2.84E+06 O.OOE+0O CS-137 5 85E+08 7.78E+08 2.71E+08 O.OOE+00 2.65E+08 1.03E+08 1.11E+07 O.OOE+00 BA-140 2.27E+07 2.78E+04 1.46E+06 O.OOE+00 9.44E+03 1.87E+04 3 50E+07 O.OOE+O0 LA-140 3 08E-02 1.51 E-02 4.02E-03 O.OOE+OO 0 OOE+00 O.OOE+0O 8.69E+02 0 OOE+00 CE-141 1.04E+04 6.94E+03 7.97E+02 O.OOE+00 3.27E+03 O.OOE+00 1.98E+07 0 OOE+00 CE-143 1.71 E-02 1.24E+01 1.39E-03 O.OOE+0O 5.58E-03 O.OOE+00 3.74E+02 0 OOE+00 CE-144 9.71E+05 4 02E+05 5 22E+04 0 OOE+00 2.40E+05 O.OOE+00 2 44E+08 0 OOE+OO HF-181 1.47E+08 8.06E+05 1.64E+07 4 91 E+05 6.70E+05 O.OOE+00 7.33E+09 O.OOE+0O W-1 87 1.75E-02 1.42E-02 4.99E-03 O.OOE+0O 0 OOE+00 O.OOE+0O 3 85E+0O O.OOE+O0 NP-239 2.28E-01 2 15E-02 1.19E-02 O.OOE+00 6.75E-02 O.OOE+00 3.46E+03 O.OOE+00 C _.r HBRODCM 3-48 Rev. 19

TABLE 3.5-7 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT7 (Reference Regulatory Guide 1.109)

PATHWAY = Meat AGE GROUP = Child Nucdde H-3 NA-24 CR-51 MN-54 FE-55 FE-59 CO-57 CO-58 CO-60 CU-64 ZN-65 BR-82 RB-86 SR-89 SR-90 SR-91 Y-91 Y-93 ZR-95 ZR-97 NB-95 MO-99 TC-99M RU-103 RU-105 RU-106 AG-11 OM SN-113 SB-124 SB-125 TE-129M Bone O.OOE+00 1.77E-03 O.OOE+00 O.OOE+00 3.56E+08 3.23E+08 O.OOE+00 O.OOE+00 O OOE+00 O.OOE+00 3.38E+08 O OOE+O0 O OOE+00 4.10E+08 8 64E+09 2.50E-10 1.52E+06 7.73E-12 2.23E+06 3 28E-05 2.71 E+06 O OOE+00 6.63E-21 1.35E+08 9 84E-28 3 58E+09 6.99E+06 4.17E+07 2.46E+07 2.25E+07 1.69E+09 Liver 2.33E+02 1.77E-03 O OOE+00 6.39E+06 1.89E+08 5.23E+08 4.69E+06 1.37E+07 5.49E+07 3.06E-07 9.OOE+08 0.00E+00 5 37E+08 O.OOE+00 O.OOE+00 O.OOE+00 O OOE+00 O.OOE+00 4.90E+05 4.74E-06 1.06E+06 1.16E+05 1.30E-20 O OOE+00 O.OOE+00 O.OOE+00 4.72E+06 1.34E+06 3.19E+05 1.73E+05 4.71 E+08 T Body 2.33E+02 1.77E-03 7.85E+03 1.70E+06 5 85E+07 2.60E+08 9.50E+06 4.18E+07 1.62E+08 1.85E-07 5.60E+08 1.56E+03 3 30E+08 1.17E+07 2.19E+09 9.42E-12 4 06E+04 2.12E-13 4 36E+05 2 80E-06 7.55E+05 2.87E+04 2.15E-19 5.18E+07 3.57E-28 4.46E+08 3.77E+06 4.56E+07 8.62E+06 4.71 E+06 2 62E+08 Thyroid 2.33E+02 1.77E-03 4.36E+03 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.51 E+05 5.43E+04 2.08E+04 5.44E+08 Kidney 2.33E+02 1.77E-03 1.19E+03 1.79E+06 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 7.41 E-07 5.67E+08 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 00E+00 0 OOE+00 7.01 E+05 6 80E-06 9.92E+05 2.47E+05 1.89E-19 3 39E+08 8 65E-27 4.83E+09 8.79E+06 9 23E+05 O.OOE+00 0.00E+00 4 96E+09 Lun 2.33E+02 1.77E-03 7.96E+03 O.OOE+00 1.07E+08 1.51 E+08 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 6.60E-21 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 1.36E+07 1.25E+07 O.OOE+00 GI-Tract 2.33E+02 1.77E-03 4.16E+05 5.37E+06 3.50E+07 5.44E+08 3 85E+07 7.97E+07 3.04E+08 1.44E-25 1.58E+08 O.OOE+00 3 45E+07 1.59E+07 1.16E+08 5.51 E-10 2.02E+08 1.15E-07 5 11E+08 7.18E-01 1.95E+09 9.58E+04 7.40E-18 3 48E+09 6.42E-25 5.56E+10 5 61 E+08 1.67E+08 1.54E+08 5.37E+07 2.06E+09 Skin 2.33E+02 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 00E+O0 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 TE-131M 7.23E+02 2.50E+02 266E+02 5.14E+02 2.42E+03 OOE+00 1.01 E+04 O.OOE+00 7R Values in units of mrem I yr per micro-Ci / m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-Ci / sec for all others.

HBRODCM 3-49 Rev. 19

TABLE 3.5-7 (continued)

Nuclide TE-132 1-131 1-133 1-135 CS-134 CS-136 CS-137 BA-140 LA-140 CE-141 CE-143 CE-144 HF-181 W-187 NP-239 Bone 2.18E+06 1.63E+07 5.78E-01 6 91E-17 7.26E+08 1.55E+07 1.08E+09 4.19E+07 5.64E-02 1.96E+04 3.21 E-02 1.83E+06 2.66E+08 3.24E-02 4.29E-01 Liver 9.65E+05 1.64E+07 7.15E-01 1.24E-16 1.19E+09 4.26E+07 1.03E+09 3.67E+04 1.97E-02 9.76E+03 1.74E+01 5 74E+05 1.04E+06 1.92E-02 3 08E-02 T.Bodv 1.17E+06 9.30E+06 2.71 E-01 5.88E-17 2.51 E+08 2.75E+07 1.52E+08 2 45E+06 6.64E-03 1.45E+03 2.52E-03 9.77E+04 2 68E+07 8 60E-03 2.16E-02 Thyroid 1.41 E+06 5.41 E+09 1.33E+02 1.10E-14 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 8.75E+05 0 OOE+00 O.OOE+00 Kidney Lung GI-Tract 8 96E+06 O.OOE+00 9.71 E+06 2.69E+07 O.OOE+00 1.46E+06 1.19E+00 O.OOE+00 2.88E-01 1.91E-16 0 OOE+00 9.47E-17 3.69E+08 1.33E+08 6.43E+06 2 27E+07 3.38E+06 1.50E+06 3 36E+08 1.21 E+08 6 45E+06 1.20E+04 2.19E+04 2.12E+07 O.OOE+00 O.OOE+00 5 49E+02 4.28E+03 O.OOE+00 1.22E+07 7.29E-03 0 OOE+00 2.55E+02 3 1 BE+05 0 OOE+00 1.50E+08 8 35E+05 0 OOE+00 4.42E+09 0 OOE+00 0 OOE+00 2 69E+00 8.90E-02 O.OOE+00 2.28E+03 Skin O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 HBRODCM 3-50 Rev. 19

TABLE 3.5-8 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT8 (Reference Regulatory Guide 1.109)

PATHWAY = Cow Milk AGE GROUP = Adult Nuclide H-3 F-18 NA-24 CR-51 MN-54 MN-56 FE-55 FE-59 C0-57 CO-58 CO-60 NI-65 CU-64 ZN-65 BR-82 BR-83 BR-84 RB-86 SR-89 SR-90 SR-91 SR-92 Y-91M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 NB-97 MO-99 Bone O.OOE+00 4.57E-03 2.45E+06 O.OOE+00 O.OOE+00 O.OOE+00 1.96E+07 2.55E+07 O OOE+00 0 OOE+00 O OOE+00 3.76E-01 O.OOE+00 1.23E+09 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 1.23E+09 3 89E+10 2.91 E+04 4.95E-01 6 27E-20 7.23E+03 5 64E-05 2.24E-01 7.89E+02 4.34E-01 7.23E+04 3 40E-12 O.OOE+00 Liver 7.63E+02 0 OOE+00 2.45E+06 O.OOE+00 6.71 E+06 4.21 E-03 1.35E+07 5.99E+07 9.10E+05 3 92E+06 1.30E+07 4.88E-02 2 39E+04 3.93E+09 0.00E+00 O.OOE+00 0 OOE+00 2 41 E+09 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 00E+00 O.OOE+00 2.53E+02 8.76E-02 4.02E+04 8.59E-13 2.48E+07 T Body 7.63E+02 5.07E-04 2.45E+06 2.55E+04 1.28E+06 7.47E-04 3 15E+06 2.30E+07 1.69E+06 8.79E+06 2.87E+07 2.23E-02 1.12E+04 1.78E+09 3 27E+07 9.98E-02 1.75E-23 1.12E+09 3.54E+07 9.54E+09 1.17E+03 2.14E-02 2.43E-21 1.93E+02 1.65E-06 6.19E-03 1.71 E+02 4.01 E-02 2.16E+04 3.14E-13 4 72E+06 Thyroid 7.63E+02 0 OOE+00 2.45E+06 1.53E+04 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Kidney 7.63E+02 0 OOE+00 2 45E+06 5.62E+03 2 OOE+06 5.35E-03 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.04E+04 2.63E+09 O.OOE -00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 3 97E+02 1.32E-01 3.97E+04 1.OOE-12 5.62E+07 Lung 7.63E+02 O.OOE+00 2.45E+06 3 39E+04 O.OOE+00 0 OOE+00 7.54E+06 1.67E+07 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 GI-Tract 7.63E+02 1.35E-04 2.45E+06 6 42E+06 2.06E+07 1.34E-01 7.75E+06 2.00E+08 2 57E+07 7.95E+07 2.44E+08 1.24E+00 2.04E+06 2.47E+09 3 75E+07 1.44E-01 1.37E-28 4 76E+08 1.98E+08 1.12E+09 1.38E+05 9 82E+00 1.84E-19 3 98E+06 9.88E-01 7.11 E+03 8.02E+05 2.71 E+04 2.44E+08 3.17E-09 5.76E+07 Skin 7.63E+02 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3R Values in units of mrem / yr per micro-Ci / m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-Ci / sec for all others.

HBRODCM 3-51 Rev. 19

TABLE 3.5-8 (continued)

Nuclide Bone Liver T.Body Thvroid Kidney Lunq GI-Tract Skin TC-99M 3 35E+00 9 48E+00 1.21 E+02 O.OOE+00 1.44E+02 4 64E+00 5.61 E+03 O.OOE+00 RU-103 8 85E+02 O.OOE+OO 381E+02 O.OOE+00 3.38E+03 0 OOE+00 1.03E+05 0 OOE+00 RU-1 05 8.65E-04 O.OOE+00 3 41E-04 O.OOE+00 1.12E-02 O.OOE+00 5.29E-01 0 OOE+00 RU-106 1.64E+04 O.OOE+00 2.08E+03 0 OOE+00 3.17E+04 0 OOE+00 1.06E+06 0 OOE+00 AG-110M 4.85E+07 4.49E+07 2.66E+07 O.OOE+00 8 82E+07 0 OOE+00 1.83E+10 O.OOE+00 SN-113 3.87E+06 1.49E+05 3.66E+06 5.26E+04 1.10E+05 O.OOE+00 6.77E+07 O.OOE+00 SB-124 2.16E+07 4.09E+05 8.58E+06 5.25E+04 0 OOE+00 1.68E+07 6.14E+08 O.OOE+00 SB-125 1.61 E+07 1.80E+05 3 84E+06 1.64E+04 0 OOE+00 1.24E+07 1.78E+08 0 OOE+00 TE-129M 5.67E+07 2.12E+07 8.98E+06 1.95E+07 2.37E+08 O.OOE+00 2.86E+08 O.OOE+00 TE-129 2.97E-10 1.12E-10 7.25E-11 2 28E-10 1.25E-09 0 OOE+00 2.25E-10 O.OOE+00 TE-131M 3 69E+05 1.80E+05 1.50E+05 2.86E+05 1.83E+06 O.OOE+00 1.79E+07 0 OOE+00 TE-1 32 2.46E+06 1.59E+06 1.49E+06 1.76E+06 1.53E+07 O.OOE+00 7.52E+07 O.OOE+00 1-131 2 91E+08 4.16E+08 2.38E+08 1.36E+11 7.13E+08 O.OOE+00 1.10E+08 0 OOE+00 1-132 1.67E-01 4.47E-01 1.56E-01 1.56E+01 7.12E-01 0 OOE+00 8.39E-02 0 OOE+00 1-133 3.88E+06 6.74E+06 2.06E+06 9.91E+08 1.18E+07 O.OOE+00 6.06E+06 0 OOE+00 1-134 2.11E-12 5.72E-12 2.05E-12 9.92E-11 9.10E-12 O.OOE+00 4.99E-15 O.OOE+00 1-135 1.29E+04 3 38E+04 1.25E+04 2.23E+06 5 42E+04 O.OOE+00 3 82E+04 O.OOE+00 CS-134 4.45E+09 1.06E+10 8.66E+09 0 OOE+00 3.43E+09 1.14E+09 1.85E+08 0 OOE+00 CS-136 2.51E+08 9.91E+08 7.14E+08 0 OOE+00 5.52E+08 7.56E+07 1.13E+08 0 OOE+00 CS-137 5.96E+09 8.15E+09 534E+09 0 OOE+00 2.77E+09 9 20E+08 1 58E+08 0 OE+00 CS-138 972E-24 1.92E-23 9.51E-24 O.OOE+00 1 41E-23 1.39E-24 8.19E-29 0 OOE+00 BA-1 39 4 54E-08 3 24E-11 1.33E-09 O.0OE+00 3 03E-11 1.84E-11 8 06E-08 O.OOE+00 BA-140 2.57E+07 3.23E+04 1.68E+06 O.OOE+00 1.10E+04 1.85E+04 5.29E+07 O.OOE+00 LA-140 4 52E+00 2.28E+00 6 01E-01 O.OOE+00 0 OOE+00 O.OOE+00 1.67E+05 0 OOE+00 LA-142 1.90E-11 8 66E-12 2 16E-12 OOE+00 OOE+00 0 OE+00 632E-08 0 OE+00 CE-141 4.27E+03 2 89E+03 3 27E+02 OOE+00 1.34E+03 O.OOE+00 1.10E+07 OOE+00 CE-143 4.16E+01 3 08E+04 3 40E+00 0 OOE+00 1.35E+01 O.OOE+00 1.15E+06 0 OOE+00 CE-144 2.83E+05 1.18E+05 1.52E+04 OOE+00 7.01 E+04 OOE+00 9.56E+07 O.OOE+00 HF-181 8 46E+03 4.77E+01 9 57E+02 3.03E+01 3 97E+01 0 OOE+00 6 28E+05 O.0OE+00 W-187 6 52E+03 5.45E+03 1.90E+03 O.OOE+00 0 OOE+00 0 OOE+00 1.78E+06 0 OOE+00 NP-239 3 67E+00 3 61E-01 1.99E-01 0 OOE+00 1.13E+00 O.OOE+00 7.41 E+04 O.OOE+00 HBRODCM 3-52 Rev. 1 9

TABLE 3.5-9 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT9 (Reference Regulatory Guide 1.109)

PATHWAY = Cow Milk AGE GROUP = Teen Nuclide Bone Liver T Body Thyroid Kidney Luna GI-Tract Skin H-3 O.OOE+00 9.93E+02 9 93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 F-1 8 8.16E-03 0 OOE+00 8.94E-04 O.OOE+00 O.OOE+00 O.OOE+00 7.35E-04 O.OOE+00 A-24 4.27E+06 4.27E+06 4.27E+06 4.27E+06 4.27E+06 4.27E+06 4.27E+06 O.OOE+00 CR-51 O.OOE+00 0 OOE+00 4.46E+04 2.48E+04 9.77E+03 6.36E+04 7.49E+06 O.OOE+00 MN-54 O.OOE+00 1.12E+07 2.22E+06 0 OOE+00 3 34E+06 O.OOE+00 2.29E+07 O.OOE+00 MN-56 0 OOE+00 7.47E-03 1.33E-03 O.OOE+0O 9 45E-03 O.OOE+00 4.91 E-01 0.00E+00 FE-55 3 47E+07 2.46E+07 5.74E+06 O.OOE+00 0.00E+00 1.56E+07 1.06E+07 O.OOE+00 FE-59 4 45E+07 1.04E+08 4.01 E+07 O.OOE+00 O.OOE+00 3 27E+07 2.45E+08 O.OOE+00 CO-57 0 00E+00 1.78E+06 2.99E+06 O.OOE+00 O.OOE+00 O.OOE+00 3.32E+07 O.OOE+00 CO-58 O.OOE+00 6 60E+06 1.52E+07 0.OOE+00 0.OOE+00 O.OOE+00 9.1 OE+07 0 OOE+00 CO-60 O.OOE+00 2 20E+07 4.96E+07 O.OOE+00 O.OOE+00 O.OOE+00 2.87E+08 O.OOE+00 NI-65 6.88E-01 8.79E-02 4.00E-02 O.OOE+00 O.OOE+00 0 OOE+00 4.76E+00 O.OOE+00 CU-64 O.OOE+00 4.27E+04 2.01 E+04 O.OOE+00 1.08E+05 O.OOE+00 3 31E+06 O.OOE+00 ZN-65 1.90E+09 6.58E+09 3.07E+09 O.OOE+00 4.21 E+09 O.OOE+00 2.79E+09 0 OOE+00 BR-82 0 OOE+00 O OOE+00 5 68E+07 O.OOE+00 O.OOE+00 0.00E+O0 O.OOE+00 0 OOE+00 BR-83 O.OOE+00 O OOE+0O 1.84E-01 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O OOE+00 BR-B4 O.OOE+00 O OOE+00 3.13E-23 O.OOE+00 O OOE+00 0 OOE+00 0.00E+00 O.OOE+00 RB-86 0 OOE+00 4 40E+09 2 07E+09 0 OOE+00 O OOE+00 O OOE+00 6 51 E+08 O.OOE+00 SR-89 2.28E+09 0 OOE+00 6 52E+07 0 OOE+00 O OOE+00 O OOE+00 2.71E+08 0 OOE+00 SR-90 5 49E2.O1

-'. 0fE+00 1.36E+10 O.OOE+00 OOE+00 O.OOE+00 1.54E+09 0 OOE+00 SR-91 5 34E+04 0 OOE+00 2.12E+03 0 OOE+00 O.OOE+00 O.OOE+00 2.42E+05 0.00E+00 SR-92 9.07E-01 0 OOE+00 3 87E-02 0 OOE+00 O.OOE+00 0.00E+00 2.31 E+01 O.OOE+00 Y-91M 1.15E-19 0002+00 439E-21 OOE+00 O.OOE+00 0.00E+00 5.42E-18 O.OOE+00 Y-91 1.33E+04 O.OOE+00 3 56E+02 0 OOE+00 O OOE+00 O OOE+00 5.45E+06 O.OOE+00 Y-92 1.04E-04 O.OOE+00 3 01E-06 0 OOE+00 O.OOE+00 O.OOE+00 2.86E+00 O.OOE+00 Y-93 4.14E-01 O.OOE+00 1.13E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.26E+04 0 OOE+00 ZR-95 1.38E+03 4.35E+02 2.99E+02 O.OOE+00 6.40E+02 O.OOE+00 1.OOE+06 0 OOE+00 ZR-97 7.90E-01 1 56E-01 7.20E-02 O.OOE+00 237E-01 O.0OE+00 4.23E+04 OOE+00 NB-95 1.23E+05 6 84E+04 3.76E+04 O.OOE+00 6 63E+04 0.00E+00 2.92E+08 O.OOE+00 NB-97 6.19E-12 1.54E-12 5.61E-13 O.OOE+00 1.80E-12 O.OOE+00 3.67E-08 O.OOE+00 MO-99 O.OOE+00 4.48E+07 8 55E+06 0 OOE+00 1.03E+08 0 OOE+00 8.03E+07 0 OOE+00 9R Values in units of mrem / yr per micro-Ci / m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-Ci / sec for all others.

HBRODCM 3-53 Rev. 19

TABLE 3.5-9 (continued)

Nuclide Bone Liver TC-99M 5.82E+00 1.62E+01 RU-103 1.57E+03 O.OOE+00 RU-105 1.58E-03 O.OOE+00 RU-106 3.02E+04

- O.OOE+00 AG-11iM 8.02E+07 7.59E+07 SN-113 5.95E+06

-2.49E+05 SB-124 3 86E+07 7.11E+05 SB-125 TE-129M TE-129 TE-131M TE-132 1-131 1-132 1-133 1-134 1-135 CS-134 CS-136 CS-137 CS-138 BA-139 BA-140 LA-140 LA-142 CE-141 CE-143 CE-144 HF-181 W-187 NP-239 2 89E+07 1.04E+08 5.48E-10 6.71 E+05 4 39E+06 5.28E+08 2.96E-01 7.08E+06 3.74E-12 2.29E+04 7.73E+09 4.27E+08 1.08E+10 1.76E-23 8.40E-08 4.64E+07 8.11E+00 3.44E-1 1 7.82E+03 7.65E+01 5.20E+05 1.51 E+04 1.19E+04 7.01 E+00 3.15E+05 3.85E+07 2.04E-10 3.22E+05 2.78E+06 7.39E+08 7.75E-01 1.20E+07 9 93E-12 5.91 E+04 1.82E+10 1.68E+09 1.44E+10 3 38E-23 5.91 E-11 5 68E+04 3.99E+00 1.53E-l l 5 22E+03 5.56E+04 2.15E+05 8.32E+01 9.72E+03 6 61E-Ol T Body 2.10E+02 6.73E+02 6.13E-04 3.81 E+03 4.61 E+07 6.33E+06 1.51 E+07 6.75E+06 1.64E+07 1.33E-10 2.69E+05 2.62E+06 3 97E+08 2.78E-01 3 66E+06 3 5612-12 2.19E+04 8.44E+O9 1.13E+09 5 01 E+09 1.69E-23 2.45E-09 2.99E+06 1.06E+00 3 80E-12 6 OOE+02 6.22E+00 2 80E+04 1.69E+03 3.40E+03 3 67E-01 Thyroid 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 8.23E+04 8.75E+04 2.76E+04 3.35E+07 3.91 E-10 4.84E+05 2.93E+06 2.16E+11 2.61E+01 1.68E+09 1.65E-10 3 80E+06 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.06E+01 0 OOE+00 0 OOE+00 Kidney Lung GI-Tract 2.42E+02 9.01 E+00 1.07E+04 5.55E+03 O.OOE+00 1.31 E+05 1.99E-02 O.OOE+00 1.28E+00 5.83E+04 O.OOE+00 1.A5E+06 1.45E+08 O.OOE+00 2.13E+10 1.76E+05 0.0OE+00 7.14E+07 O.OOE+00 3 37E+07 7.78E+08 O.OOE+00 2.54E+07 2.25E+08 4.34E+08 O.OOE+00 3.90E+08 2.30E-09 0.00E+00 2.99E-09 3.36E+06 O.OOE+00 2.58E+07 2.67E+07 O.OOE+00 8.81 E+07 1.27E+09 0 OOE+00 1.46E+08 1.22E+00 0 OOE+00 3 38E-9.1 2.11E+07 O.OOE+00 9.09E+06 1.56E-1I 0 OOE+00 1.31 E-13 9.33E+04 O.OOE+00 6.54E+04 5.78E+09 2.21 E+09 2.26E+08 9.16E+08 1.44E+08 1.35E+08 4.89E+09 1.90E+09 2.05E+08 2.50E-23 2.91 E-24 1.54E-26 5 57E-11 4.07E-11 7.50E-07 1.93E+04 3.82E+04 7.15E+07 0 OOE+00 O.OOE+00 2.29E+05 OOE+00 O.OOE+00 4 64E-07 2.46E+03 O.OOE+00 1.49E+07 2.50E+01 0 OOE+00 1.67E+06 1.29E+05 O.OOE+00 1.31 E+08 6.91 E+01 0 OOE+00 7.57E+05 O.OOE+00 O.OOE+00 2.63E+06 2.08E+00 O.OOE+00 1.06E+05 Skin O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 HBRODCM 3-54 Rev. 19

TABLE 3.5-1 0 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT10 (Reference Regulatory Guide 1.109)

PATHWAY = Cow Milk AGE GROUP = Child Nuclide H-3 F-18 NA-24 CR-51 MN-54 MN-56 FE-55 FE-59 CO-57 CO-58 C0-60 NI-65 CU-64 ZN-65 BR-82 BR-83 BR-84 RB-86 SR-89 SR-90 SR-91 SR-92 Y-91M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 NB-97 MO-99 Bone O.OOE+OO 1.94E-02 8.88E+06 O.OOE+00 O.OOE+00 O.OOE+00 8.71 E+07 1.03E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.68E+00 O.OOE+00 3.72E+09 O.OOE+00 O OOE+00 O.OOE+00 O.OOE+00 5 63E+09 9 28E+10 1.31 E+05 2.21 E+00 2 80E-19 3 28E+04 2.56E-04 1.02E+00 3.20E+03 1.92E+00 2.78E+05 1.50E-11 O.OOE+00 Liver 1.57E+03 O OOE+00 8 88E+06 O.OOE+00 1.67E+07 1.30E-02 4.62E+07 1.67E+08 3.04E+06 1.01 E+07 3 42E+07 1.58E-01 7.50E+04 9.91 E+09 O.OOE+00 O.OOE+00 0 OOE+00 8.16E+09 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 7.04E+02 2.78E-01 1.08E+05 2.72E-12 8.16E+07 T.Bodv 1.57E+03 1.92E-03 8.88E+06 9.09E+04 4.46E+06 2.94E-03 1.43E+07 8.31 E+07 6.16E+06 3.09E+07 1.01 E+08 9.24E-02 4.53E+04 6.16E+09 1.16E+08 4 52E-01 7.08E-23 5.02E+09 1.61 E+08 2.35E+10 4.94E+03 8 88E-02 1.02E-20 8.78E+02 7.32E-06 2.79E-02 6.27E+02 1.64E-01 7.74E+04 1.27E-12 2.02E+07 Thyroid 1.57E+03 O.OOE+00 8.88E+06 5.05E+04 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 Kidney 1.57E+03 0 OOE+00 8.88E+06 1.38E+04 4.69E+06 1.57E-02 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 1.81 E+05 6 24E+09 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 1.01 E+03 3 99E-01 1.02E+05 3.01E-12 1.74E+08 Lunq 1.57E+03 0 OOE+00 8.88E+06 9 21 E+04 0 OOE+00 O.OOE+00 2.61 E+07 4.84E+07 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 GI-Tract 1.57E+03 5.25E-03 8.88E+06 4.82E+06 1.40E+07 1.89E+00 8.56E+06 1.74E+08 2 49E+07 5.88E+07 1.89E+08 1.94E+01 3.52E+06 1.74E+09 O.OOE+00 O.OOE+00 O.OOE+00 5.25E+08 2.18E+08 1.25E+09 2.89E+05 4.19E+01 5.49E-16 4.38E+06 7.39E+00 1.51 E+04 7.35E+05 4.21 E+04 2.00E+08 8.38E-07 6.75E+07 Skin 1.57E+03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00

'°R Values in units of mrem / yr per micro-Ci / m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-Ci / sec for all others.

HBRODCM 3-55 Rev. 19

TABLE 3.5-10 (continued)

Nuclide TC-99M RU-103 RU-105 RU-106 AG-11OM SN-113 SB-124 SB-125 TE-129M TE-129 TE-131M TE-132 1-131 1-132 1-133 1-134 1-135 CS-134 CS-136 CS-137 CS-138 BA-139 BA-140 LA-140 LA-142 CE-141 CE-143 CE-144 HF-181 W-187 NP-239 Bone 1.33E+01 3.72E+03 3 86E-03 7.45E+04 1.74E+08 1.17E+07 9 13E+07 6.87E+07 2.56E+08 1.35E-09 1.63E+06 1.05E+07 1.28E+09 7.01E-01 1.72E+07 8.87E-12 5.43E+04 1.78E+10 9.65E+08 2.60E+10 4.27E-23 2.06E-07 1.12E+08 1.94E+01 8.30E-1I 1 93E+04 1.88E+02 1.28E+06 3 59E+04 2 89E+04 1.73E+Ol Liver T Bodv Thyroid 2 62E+01 4.34E+02 0 OOE+00 O.OOE+00 1.43E+03 O.OOE+00 O.OOE+00 1.40E-03 O.OOE+00 O.OOE+00 9.29E+03 O.OOE+00 1.17E+08 9.39E+07 O.OOE+00 3.76E+05 1.28E+07 1.54E+05 1.18E+06 3 20E+07 2.01iE+05 5.30E+05 1.44E+07 6 36E+04 7.14E+07 3.97E+07 8.25E+07 3.77E-10 3.21 E-10 9.64E-10 5.65E+05 6.02E+05 1.16E+06 4.64E+06 5.61 E+06 6.76E+06 1.29E+09 7.32E+08 4.26E+11 1.29E+00 5.92E-01 5 97E+01 2.13E+07 8 05E+06 3.95E+09 1.65E-11 7.57E-12 3.79E-10 9.77E+04 4.62E+04 8 66E+06 2.93E+10 6.17E+09 0 OOE+00 2.65E+09 1.72E+09 O.OOE+00 2.49E+10 3.68E+09 O.OOE+00 5 94E-23 3 77E-23 0 OOE+00 1.10E-10 5.98E-09 O.OOE+00 9.80E+04 6 53E+06 0 OOE+00 6 79E+00 2 29E+00 0 OOE+00 2.64E-11 8 28E-12 O.OOE+00 9.61 E+03 1.43E+03 O.OOE+00 1.02E+05 1 A7E+01 O.OOE+00 4.02E+05 6.85E+04 O.OOE+00 1.40E+02 3.61E+03 1.18E+02 1.71 E+04 7.68E+03 0 OOE+00 1.24E+00 8 71 E-01 O.OOE+00 Kidnev 3.80E+02 9.37E+03 3 39E-02 1.01 E+05 2.19E+08 2.59E+05 O OOE+00 O.OOE+00 7.51 E+08 3.95E-09 5.47E+06 4.31 E+07 2.11 E+09 1.97E+00 3.55E+07 2.52E-1 1 1.50E+05 9.07E+09 1.41E+09 8.12E+09 4.18E-23 9.62E-11 3.19E+04 0 OOE+00 O OOE+00 4 21 E+03 4.27E+01 2.23E+05 1.13E+02 0 OOE+00 3 58E+00 Luna 1.33E+01 0 0OE+00 O.OOE+00 O.OOE+00 O OOE+00 O OOE+00 5 07E+07 3.83E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 0OE+00 3 25E+09

2. 1 E+08 2.92E+09 4 50E-24 6 4BE-1I 5.85E+04 0 OOE+00 O OOE+00 O OOE+00 O.OOE+00 0 OOE+00 GI-Tract 1.49E+04 9.62E+04 2.52E+0O 1.16E+06 1.40E+10 4 67E+07 5.71 E+08 1.64E+08 3.12E+08 8.41 E-08 2.29E+07 4.67E+07 1.15E+08 1.52E+00 8 57E+06 1.09E-11 7.45E+04 1.58E+08 9.32E+07 1.56E+08 2.74E-23 1.19E-05 5 67E+07 1.89E+05 5.24E-06 1.20E+07 1.49E+06 1.05E+08 Skin 0 OOE+00 O.OOE+00 0 002+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 5 96E+05 O.OOE+00 0 OOE+00 2.40E+06 o.OOE+00 0 OOE+00 9.17E+04 o.oOE+00 HBRODCM 3-56 Rev. 19

TABLE 3.5-11 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT" (Reference Regulatory Guide 1.109)

PATHWAY = Cow Milk AGE GROUP = Infant Nuclide H-3 F-18 NA-24 CR-51 MN-54 MN-56 FE-55 FE-59 C0-57 C0-58 C0-60 NI-65 CU-64 ZN-65 BR-82 BR-83 BR-84 RB-86 SR-89 SR-90 SR-91 SR-92 Y-91M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 NB-97 MO-99 TC-99M Bone O.OOE+00 4.04E-02 1.55E+07 O.OOE+00 O.OOE+O0 O.OOE+00 1.05E+08 1.93E+08 O OOE+00 O.OOE+00 0.00E+00 3 56E+OO 0 OOE+00 5 OOE+09 O.OOE+00 0.00E+00 O.OOE+00 O OOE+00 1.07E+10 1.01 E+11 2.73E+05 4.71 E+00 5.94E-19 6 16E+04 5.44E-04 2.16E+00 5.69E+03 4.07E+00 5.19E+05 3.18E-1 1 0.00E+00 2.78E+01 Liver 2.38E+03 O.OOE+00 1 55E+07 O.OOE+00 3.11 E+07 3.19E-02 6 80E+07 3.36E+08 7.1 OE+06 2.02E+07 6.98E+07 4 03E-01 1 86E+05 1.71E+10 O.OOE+00 0 0OE+00 O.OOE+00 2 07E+10 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 1.39E+03 6.99E-01 2.14E+05 6.78E-12 2 09E+08 5.73E+01 T.Bodv 2.38E+03 3 45E-03 1.55E+07 1.44E+05 7.05E+06 5.50E-03 1.82E+07 1.33E+08 1.15E+07 5.03E+07 1.65E+08 1.83E-01 8.63E+04 7.90E+09 1.96E+08 9 60E-01 1.37E-22 1 02E+10 3 07E+08 2.57E+10 9.87E+03 1.75E-01 2.03E-20 1.64E+03 1.53E-05 5.90E-02 9.83E+02 3.19E-01 1.24E+05 2.45E-12 4.07E+07 7.37E+02 Thyroid 2.38E+03 0 00E+00 1.55E+07 9.40E+04 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0 00E+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 Kidney 2.38E+03 O.OOE+00 1.55E+07 2.05E+04 6.90E+06 2.74E-02 O.OOE+00 0 OOE+00 O.OOE+00 0 00E+00 0 OOE+00 O.OOE+00 3.15E+05 8.31 E+09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0.00E+00 O.OOE+00 1.49E+03 7.04E-01 1.53E+05 5 30E-12 3.12E+08 6.16E+02 Luna 2.38E+03 O.OOE+00 1.55E+07 1.83E+05 0 OOE+00 O.OOE+00 3 32E+07 9.94E+07 O.OOE+00 0 OOE+00 0.00E+00 0.00E+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 2.99E+01 GI-Tract 2.38E+03 9.51 E-03 1.55E+07 4.20E+06 1.14E+07 2.90E+00 8.63E+06 1.61 E+08 2.42E+07 5.03E+07 1.66E+08 3.07E+01 3.83E+06 1.45E+10 0 OOE+00 0 OOE+00 O.OOE+00 5.30E+08 2.20E+08 1.26E+09 3 23E+05 5.08E+01 1.98E-15 4 42E+06 1.04E+01 1.71 E+04 6.91 E+05 4.46E+04 1.81 E+08 2.14E-06 6.87E+07 1.66E+04 Skin 2.38E+03 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 00+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 00E+00 O.OOE+00 0 00E+00 O.OOE+00 0 OOE+00 0 002+00 0 OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 00E+00 11R Values in units of mrem /yr per micro-Ci/ m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-Ci / sec for all others.

HBRODCM 3-57 Rev. 19

TABLE 3.5-11 (continued)

Nuclide RU-103 RU-105 RU-106 AG-i1 OM SN-113 SB-124 SB-125 TE-129M TE-129 TE-131 M TE-132 1-131 I-132 1-133 1-134 1-135 CS-134 CS-136 CS-137 CS-138 BA-139 BA-140 LA-140 LA-142 CE-141 CE-143 CE-144 HF-181 W-187 NP-239 Bone 7.54E+03 8.13E-03 1.53E+05 3.21 E+08 1.78E+07 1.76E+08 1.18E+08 5 25E+08 2.86E-09 3 45E+06 2.16E+07 2.67E+09 1.45E+00 3.63E+07 1.84E-11 1.13E+05 2.87E+i 0 1.88E+09 4.16E+10 9.01 E-23 4.39E-07 2.30E+08 4.06E+01 Liver O.OOE+00 O.OOE+00 O.OOE+00 2.35E+08 6.79E+05 2.59E+06 1.14E+06 1.80E+08 9 87E-10 1.39E+06 1.07E+07 3.15E+09 2.95E+00 5.29E+07 3.77E-11 2 25E+05 5.36E+10 5.54E+09 4.86E+10 1.47E-22 2.91 E-1 0 2 30E+05 1.60E+01 T.Bodv 2.52E+03 2.74E-03 1.92E+04 1.55E+08 1.84E+07 5.45E+07 2.43E+07 8 09E+07 6 69E-10 1.15E+06 9 98E+06 1.38E+09 1.05E+00 1.55E+07 1.34E-1I 8.19E+04 5 41 E+09 2.07E+09 3 45E+09 7.10E-23 1.27E-08 1.19E+07 4 11E+00 1.53E-1I 2.74E+03 3 01 E+01 1.03E+05 6 06E+03 1.46E+04 1.84E+00 Thyroid O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 2.59E+05 4.67E+05 1.48E+05 2.02E+08 2.40E-09 2.82E+06 1.58E+07 1.03E+12 1.38E+02 9.62E+09 8.78E-10 2.01 E+07 O.OOE+O0 Kidney 1.57E+04 5.98E-02 1.81 E+05 3.36E+08 3.65E+05 O.OOE+OO 0 OOE+00 1.31 E+09 7.13E-09 9.56E+06 6 69E+07 3.68E+09 3.29E+00 6.22E+07 4 21E-11 2.50E+05 1.38E+10 Lung O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+O0 1.1OE+08 6 83E+07 O.OOE+O0 O.OOE+OO O.OOE+O0 O.OOE+OO O.OOE+O0 0 OOE+00 O.OOE+OO 0 OOE+00 O.OOE+O0 5 65E+09 4.52E+08 5.29E+09 1.14E-23 1.77E-10 1.41 E+05 O.OOE+OO 0 O0E+O0 O.OOE+OO O.OOE+O0 O.OOE+O0 0 OOE+00 O OOE+OO O.O0E+O0 GI-Tract 9.17E+04 3.23E+00 1.16E+06 1.22E+10 3.79E+07 5.43E+08 1.57E+08 3.14E+08 2.29E-07 2.34E+07 3 96E+07 1.12E+08 2.39E+00 8 95E+06 3.89E-11 8 13E+04 1.46E+08 8 42E+07 1.52E+08 2 34E-22 2.78E-05 5 66E+07 1.88E+05 1.09E-05 1.20E+07 1.54E+06 1.05E+08 5.62E+05 2.49E+06 9.44E+04 Skin O.OOE+O0 O.OOE+00 O.OOE+OO O.OOE+O0 O.OOE+O0 O.OOE+OO O.O0E+O0 O.OOE+O0 O.OOE+OO O.OOE+O0 O.OOE+O0 O.OOE+O0 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+O0 O.OOE+OO O.OOE+O0 O.OOE+OO 0 OOE+00 O.OOE+OO 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+O0 0 OOE+00 0 O0E+OO 0 OOE+O0 O.OOE+O0 O.OOE+OO 1.74E-10 6.40E-11 3 82E+06 2.33E+04 3.97E+02 2.64E+05 1.84E+06 7.52E+05 6 86E+04 3 22E+02 6 08E+04 4.23E+04 3 65E+01 3 26E+00 O.OOE+00 2.21 E+09 0 OOE+00 1.31 E+10 0 OOE+00 7.31 E-23 0 OOE+OO 1.75E-10 0 OOE+00 5 47E+04 0 O0E+OO 0 OOE+00 O.OOE+O0 0 OOE+00 O.OOE+O0 7.18E+03 O.OOE+OO 7.68E+01 0 OOE+00 3.04E+05 2.73E+02 1.89E+02 0 OOE+00 O.OOE+O0 0 OOE+OO 6 51 E+00 HBRODCM 3-58 Rev. 19

TABLE 3.5-12 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT12 (Reference Regulatory Guide 1.109)

PATHWAY = Goat Milk AGE GROUP = Adult Nuclide H-3 F-1 8 NA-24 CR-51 MN-54 MN-56 FE-55 FE-59 C0-57 CO-58 CO-60 Nl-65 CU-64 ZN-65 BR-82 BR-83 BR-84 RB-86 SR-89 SR-90 SR-91 SR-92 Y-91M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 NB-97 MO-99 Bone O.OOE+00 5.48E-04 2.93E+05 0.00E+00 O.OOE+00 0.OOE+00 2.54E+05 3 31E+05 O.OOE+00 O.OOE+00 O.OOE+00 4.51 E-02 O.OOE+00 1.48E+08 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 2.59E+09 816E+10 6.1OE+04 1.04E+00 7.52E-21 8.67E+02 6.77E-06 2.69E-02 9.47E+01 5.21E-02 8 67E+03 4.08E-13 O.OOE+00 Liver 1.56E+03 O.OOE+00 2 93E+05 OOE+00 8 06E+05 5.05E-04 1.76E+05 7.79E+05 1.09E+05 4.71E+05 1.56E+06 5.86E-03 2.67E+03 4.71E+08 0 OOE+00 OOOE+00 OOE+00 2 90E+08 O.OOE+00 0 OOE+00 0OOE+00 OOE+00 0 OOE+00 OOE+00 O.OOE+00 O.OOE+00 3.04E+01 1.05E-02 4.82E+03 1.03E-13 2.98E+06 T.Bodv 1.56E+03 6.08E-05 2 93E+05 3.06E+03 1.54E+05 8.96E-05 4.1OE+04 2.98E+05 2.02E+05 1.05E+06 3 44E+06 267E-03 1.25E+03 2.13E+08 3.93E+06 1.20E-02 2.10E-24 1.35E+08 7.44E+07 2.00E+10 2 46E+03 4 50E-02 2.91E-22 2.32E+01 1.98E-07 7.43E-04 2 06E+01 4.81E-03 259E+03 3 76E-14 5.67E+05 Thyroid 1.56E+03 0 OOE+00 2.93E+05 1.83E+03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 OOE2400 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 Kidney 1.56E+03 0 OOE+O0 2.93E+05 6.75E+02 2.40E+05 6 42E-04 OOE+00 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0OE+00 673E+03 3.15E+08 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 4.76E+01 1.59E-02 4.77E+03 1.20E-13 6 75E+06 Lung 1.56E+03 O.OOE+00 2.93E+05 406E+03 0 OOE+00 O.OOE+00 9 80E+04 2 18E+05 OOE+00 O.OOE+00 0.00E+00 O.OOE+00 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 OOE+00 OOE+00 0 0OE+00 0.00E+00 OOE+00 0 OOE+00 OOE+00 0 OOE+00 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 Gl-Tract 1.56E+03 1.63E-05 2.93E+05 7.70E+05 2 47E+06 1.61 E-02 1.01 E+05 2.60E+06 3 09E+06 9.54E+06 2.93E+07 1.49E-01 2.27E+05 2.97E+08 4.50E*06 1.73E-02 1.65E-29 5.71E+07 4.16E+08 2.36E+09 2.91E+05 2 06E+01 2.21E-20 4.77E+05 1.19E-01 8.53E+02 9 62E+04 3 26E+03 2 93E+07 3.80E-10 6 91E+06 Skin 1.56E+03 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 12R Values in units of mrem / yr per micro-Ci / m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-Ci / sec for all others.

HBRODCM 3-59 Rev. 19

TABLE 3.5-12 (continued)

Nuclide Bone Liver T.Bodv Thyroid Kidney Lung GI-Tract Skin TC-99M 4.03E-01 1.14E+00 1.A5E+01 0OOE+00 1.73E+01 5.57E-01 6.73E+02 0 OOE+00 RU-103 1.06E+02 O.OOE+00 4.58E+01 0 OOE+00 4 05E+02 O.OOE+00 1.24E+04 O.OOE+00 RU-105 1.04E-04 0 OOE+00 4.10E-05 O.OOE+00 1.34E-03 O.OOE+00 6.35E-02 O.OOE+00 RU-106 1.97E+03 O.OOE+00 2.50E+02 O.OOE+00 381E+03 O.OOE+00 1.28E+05 0 OOE+00 AG-110M 5.82E+06 5.38E+06 3.20E+06 0 OOE+00 1.06E+07 0 OOE+00 2.20E+09 O.OOE+00 SN-113 4 64E+05 1.79E+04 4.39E+05 6 31E+03 1.32E+04 O.OOE+00 8.12E+06 O.OOE+00 SB-124 2.60E+06 4.90E+04 1.03E+06 6 29E+03 0 OOE+00 2.02E+06 7.37E+07 O.OOE+00 SB-125 1.94E+06 2.16E+04 4 61E+05 1.97E+03 O.OOE+00 1.49E+06 2.13E+07 O.OOE+00 TE-129M 6.81E+06 2.54E+06 1.08E+06 2.34E+06 2.84E+07 0 OOE+00 3.43E+07 0 OOE+00 TE-129 3.57E-11 1.34E-1I 8.70E-12 2.74E-11 1.50E-10 O.OOE+00 2.69E-1I O.OOE+00 TE-131M 4 43E+04 2.17E+04 1.80E+04 3 43E+04 2.19E+05 O.OOE+00 2.15E+06 OOE+00 TE-132 2.95E+05 1.91E+05 1.79E+05

2. 1E+05 1 84E+06 0OOE+00 9.02E+06 0OOE+00 1-131 3 49E+08 4 99E+08 2 86E+08 1.64E+11 8 56E+08 O.OOE+00 1.32E+08 O.OOE+00 1-132 2.00E-01 5.36E-01 1.88E-01 1.88E+01 8 54E-01 O.OOE+00 1.01E-01 O.OOE+00 1-133 4.65E+06 8 09E+06 2.47E+06 1.19E+09 1.41E+07 O.OOE+00 7.27E+06 OOE+00 1-134 2.53E-12 6 87E-12 2.46E-12 1.19E-10 1.09E-1I O.OOE+00 5.99E-15 0OOE+00 1-135 1.55E+04 4.06E+04 1.50E+04 2.68E+06 6.51E+04 O.OOE+00 4.58E+04 OOE+00 CS-134 1.34E+10 3.18E+10 2.60E+10 O.OOE+00 1.03E+10 3 41E+09 5.56E+08 O.OOE+00 CS-136 7.53E+08 2.97E+09 2.14E+09 0OOE+00 1.65E+09 2.27E+08 3.38E+08 0 OOE+00 CS-137 1.79E+10 2 45E+10 1.60E+10 O.OOE+00 8.30E+09 2.76E+09 4.73E+08 O.OOE+00 CS-138 2.91 E-23 5.76E-23 2.85E-23 O.OOE+00 4 23E-23 4.18E-24 2A6E-28 0OOE+00 BA-139 5.45E-09 3 88E-12 1.60E-10 0 OOE+00 3 63E-12 2 20E-12 9.67E-09 OOE+00 BA-140 3 08E+06 3 87E+03 2 02E+05 O.OOE+00 1.32E+03 2 22E+03 6 35E+06 OOE+00 LA-140 542E-01 2 73E-01 7.22E-02 0 OOE+00 0OOE+00 0OOE+00 2.00E+04 0 OOE+00 LA-142 2.28E-12 1.04E-12 2.59E-13 0OOE+00 0OOE+00 OOE+00 7.58E-09 O.OOE+00 CE-141 5.12E+02 3 46E+02 3.93E+01 O.OOE+00 1.61E+02 O.OOE+00 1.32E+06 O.OOE+00 CE-143 4.99E+00 369E+03 4 09E-01 O.OOE+00 1.63E+00 O.OOE+00 1.38E+05 0OOE+00 CE-144 3.39E+04 1.42E+04 1.82E+03 O.OOE+00 8.41E+03 O.OOE+00 1.15E+07 OOE+00 HF-181 1.01 E+03 5.73E+00 1.15E+02 3.63E+00 4 77E+00 O.OOE+00 7.53E+04 OOE+00 W-187 7.82E+02 6.54E+02 2.29E+02 O.OOE+00 OOE+00 0OOE+00 2.14E+05 O.OOE+00 NP-239 441E-01 4 34E-02 239E-02 O.OOE+00 1.35E-01 OOE+00 8 89E+03 O.OOE+00 HBRODCM 3-60 Rev. 1 9

TABLE 3.5-13 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT13 (Reference Regulatory Guide 1.109)

PATHWAY = Goat Milk AGE GROUP = Teen Nuclide H-3 F-18 NA-24 CR-51 MN-54 MN-56 FE-55 FE-59 CO-57 CO-58 CO-60 NI-65 CU-64 ZN-65 BR-82 BR-83 BR-84 RB-86 SR-89 SR-90 SR-91 SR-92 Y-91 M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 NB-97 MO-99 Bone O.OOE+00 9.79E-04 5 12E+05 0 OOE+00 0 OOE+00 0 OOE+00 4.51 E+05 5.78E+05 O.OOE+00 0 OOE+00 O OOE+00 8.25E-02 O OOE+00 2.27E+08 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 4.78E+09 1.15E+11 1.12E+05 1.90E+00 1.38E-20 1.59E+03 1.25E-05 4.96E-02 1.66E+02 9.48E-02 1.48E+04 7.43E-13 0 OOE+00 Liver 2.03E+03 O.OOE+00 5.12E+05 O.OOE+00 1.34E+06 8.96E-04 3 20E+05 1.35E+06 2.14E+05 7.92E+05 2.64E+06 1.05E-02 4.75E+03 7.90E+08 O.OOE+00 O.OOE+00 O.OOE+00 5.28E+08 0 OOE+00 O.OOE+00 0 OOE+00 O OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 5.22E+01 1.88E-02 8.20E+03 1.84E-13 5.38E+06 T.Bodv 2.03E+03 1.07E-04 5 12E+05 5.35E+03 2.66E+05 1.59E-04 7.46E+04 5.21 E+05 3 58E+05 1.83E+06 5.95E+06 4.80E-03 2.24E+03 3 68E+08 6 82E+06 2.21 E-02 3 75E-24 2.48E+08 1.37E+08 2 85E+10 4 46E+03 8.12E-02 5.26E-22 4 28E+01 3.62E-07 1.36E-03 3.59E+01 8.64E-03 4.52E+03 6.73E-14 1.03E+06 Thyroid 2.03E+03 O.OOE+00 5.12E+05 2.97E+03 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE400 O OOE+00 O.OOE+00 0.00E+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O OOE+00 O.OOE+00 Kidney 2.03E+03 O.OOE+00 5.12E+05 1.17E+03 4.OOE+05 1.13E-03 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 1.20E+04 5.05E+08 0 OOE+00 O.OOE+00 0.00E+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 7.68E+01 2.84E-02 7.95E+03 2.16E-13 1.23E+07 Luna 2.03E+03 O.OOE+00 5.12E+05 7.64E+03 O.OOE+00 0 OOE+00 2 03E+05 4 25E+05 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 GI-Tract 2.03E+03 8.82E-05 5.12E+05 8 99E+05 2.75E+06 5.90E-02 1.38E+05 3.19E+06 3.99E+06 1.09E+07 3.44E+07 5.72E-01 3.69E+05 3.34E+08 O.OOE+00 O.OOE+00 0.00E+00 7.81 E+07 5.69E+08 3 24E+09 5.08E+05 4.85E+01 6.50E-19 6.54E+05 Skin 2.03E+03 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 00E+00 O.OOE+00 0 OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00

- 3 43E-01 0 OOE+00 1.52E+03 0 OOE+00 1.21 E+05 O.OOE+00 5.08E+03 O.OOE+00 3.51 E+07 0 OOE+00 4.40E-09 O.OOE+00 9 63E+06 13R Values in units of mrem / yr per micro-Ci / m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-Ci / sec for all others.

HBRODCM 3-61 Rev. 19

TABLE 3.5-13 (continued)

Nuclide Bone Liver T Body Thyroid Kidney Lung GI-Tract Skin TC-99M 6 98E-01 1.95E+00 2.52E+01 0 OOE+00 2.90E+01 1.08E+00 1.28E+03 0 OOE+00 RU-1 03 1.89E+02 O.OOE+00 8.07E+01 0 OOE+00 6.66E+02 O.OOE+00 1.58E+04 O.OOE+00 RU-105 1.90E-04 0 OOE+00 7.36E-05 O.OOE+00 2.39E-03 0 OOE+00 1.53E-01 O.OOE+00 RU-106 3 63E+03 O.OOE+00 4.57E+02 O.OOE+00 7.00E+03 O.OOE+00 1.74E+05 O.OOE+00 AG-110M 9.62E+06 9.10E+06 5.54E+06 O.OOE+00 1.74E+07 OOE+00 2.56E+09 O.OOE+00 SN-113 7.14E+05 2.99E+04 7.59E+05 9.88E+03 2.12E+04 O.OOE+00 8 57E+06 O.OOE+00 SB-124 4.63E+06 8.53E+04 1.81E+06 1.05E+04 O.OOE+00 4.04E+06 9.33E+07 O.OOE+00 SB-125 3.46E+06 3.78E+04 8.10E+05 3.31E+03 O.OOE+00 3.04E+06 269E+07 0 OOE+00 TE-129M 1.25E+07 4.62E+06 1.97E+06 4.02E+06 5.21E+07 O.OOE+00 4.68E+07 O.OOE+00 TE-129 6 57E-11 2.45E-11 1.60E-11 4.69E-11 2.76E-10 O.OOE+00 3 59E-10 O.OOE+00 TE-131M 8.06E+04 386E+04 3.22E+04 581E+04 4.03E+05 OOE+00 3.10E+06 O.OOE+00 TE-132 5 27E+05 3 34E+05 3.14E+05 3 52E+05 3.20E+06 O.OOE+00 1.06E+07 O.OOE+00 1-131 6 34E+08 8.87E+08 4.76E+08 2.59E+11 1.53E+09 O.OOE+00 1.75E+08 OOE+00 1-132 3.55E-01 9 30E-01 3.34E-01 3 13E+01 1.47E+00 O.OOE+00 4 05E-01 0 OOE+00 1-133 8 50E+06 1.44E+07 4.40E+06 2.01 E+09 2.53E+07 O.OOE+00 1.09E+07 0 OOE+00 1-134 4.49E-12 1.19E-11 428E-12 1.99E-10 1.88E-11 0 OOE+00 1 57E-13 0 OOE+00 1-135 2.75E+04 7.09E+04 2.63E+04 4 56E+06 1.12E+05 0 OOE+00 7.85E+04 O.OOE+00 CS-134 2.32E+10 5.46E+10 2.53E+10 \\ O.OOE+00 1.73E+10 6 62E+09 6 79E+08 O.OOE+00 CS-136 1.28E+09 5.05E+09 3 39E+09 O.OOE+00 2.75E+09 4.33E+08 4.06E+08 0 OOE+00 CS-137 3.24E+10 4.31E+10 1.50E+10 O.OOE+00 1.47E+10 5.70E209 6 14E+08 OOE+00 CS-138 529E-23 1.02E-22 5 08E-23 OOE+00 7.50E-23 8.72E-24 4.61E-26 0 OOE+00 BA-139 1.01 E-08 7.09E-12 2.94E-10 O.OOE+00 6 69E-12 4 89E-12 8 99E-08 O.OOE+00 BA-140 5.56E+06 6.82E+03 3 58E+05 0 OOE+00 2 31 E+03 4.58E+03 8 58E+06 O.OOE+00 LA-140 9 73E-01 4.78E-01 1.27E-01 O.OOE+00 0 OOE+00 0 OOE+00 2 75E+04 0 OOE+00 LA-142 4.12E-12 1.83E-12 4.56E-13 O.OOE+00 O.OOE+00 O.OOE+00 5 57E-08 0 OOE+00 CE-141 9 39E+02 6.27E+02 7.20E+01 O.OOE+00 2.95E+02 O.OOE+00 1.79E+06 0 OOE+00 CE-143 9.18E+00 6.68E+03 7.46E-01 O.OOE+00 3 OOE+00 0 OOE+00 2.01 E+05 O.OOE+00 CE-144 6.24E+04 2.58E+04 3.35E+03 O.OOE+00 1.54E+04 0 OOE+00 1.57E+07 O.OOE+00 HF-181 1.82E+03 9.98E+00 2.03E+02 6 08E+00 8.29E+00 0 OOE+00 9.08E+04 0 OOE+00 W-187 1 43E+03 1.17E+03 409E+02 O.OOE+00 OOE+00 OOE+00 3.16E+05 O.OOE+00 NP-239 8 42E-01 7.94E-02 4.41 E-02 O.OOE+00 2.49E-01 O.OOE+00 1.28E+04 OOE+00 HBRODCM 3-62 Rev. 19

TABLE 3.5-14 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT14 (Reference Regulatory Guide 1.109)

PATHWAY = Goat Milk AGE GROUP = Child Nuclide H-3 F-18 NA-24 CR-51 MN-54 MN-56 FE-55 FE-59 C0-57 C0-58 CO-60 Nl-65 CU-64 ZN-65 BR-82 BR-83 BR-84 RB-86 SR-89 SR-90 SR-91 SR-92 Y-91 M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 NB-97 Bone O.OOE+00 2.33E-03 1.07E+06 O.OOE+00 O.OOE+00 O.OOE+00 1.13E+06 1.34E+06 O.OOE+00 0 OOE+00 O.OOE+00 2.02E-01 O.OOE+00 4.46E+08 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 1.18E+10 1.95E+.I1-2.75E+05 4.65E+00 3.36E-20 3 94E+03 3.07E-05 1.22E-01 3 85E+02 2.31 E-01 3.34E+04 1.80E-12 Liver 3 20E+03 0 OOE+00 1.07E+06 O.OOE+00 2.01 E+06 1.56E-03 6.OOE+05 2.17E+06 3 65E+05 1 21E+06 4.11 E+06 1.90E-02 8.35E+03 1.19E+09 O.OOE+00 O.OOE+00 0 OOE+00 9.79E+08 0 OOE+00 0.0E+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 8 45E+01 3.33E-02 1.30E+04 3.26E-13 T.Body 3.20E+03 2.31 E-04 1.07E+06 1.09E+04 5 35E+05 3.53E-04 1.86E+05 1.08E+06 7.39E+05 3.71 E+06 1.21 E+07 1.1IE-02 5.05E+03 7.40E+08 1.40E+07 5 42E-02 8 49E-24 6.02E+08 3.38E+08 4 94E+10 1.04E+04 1.86E-01 1.22E-21 1.05E+02 8.78E-07 3 35E-03 7.53E+01 1.97E-02 9 29E+03 1.52E-13 Thyroid 3 20E+03 0 OOE+00 1.07E+06 6.05E+03 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Kidney 3.20E+03 O.OOE+00 1.07E+06 1.65E+03 5 63E+05 1.89E-03 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 2.02E+04 7.49E+08 O.OOE+00 O.OOE+0O 0.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 1.21 E+02 4.79E-02 1.22E+04 3.62E-13 Lung 3 20E+03 O.OOE+00 1.07E+06 1.11 E+04 0 OOE+00 O.OOE+00 3 40E+05 6.29E+05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 GI-Tract 3.20E+03 6.30E-04 1.07E+06 5.79E+05 1.69E+06 2.26E-01 1.11 E+05 2.26E+06 2.99E+06 7.06E+06 2.27E+07 2.33E+00 3 92E+05 2.09E+08 O.OOE+00 O.OOE+00 0 OOE4 00 6.30E+07 4 58E+08 2.62E+09 6.07E+05 8.81 E+01 6.59E-17 5 25E+05 8.87E-01 1.82E+03 8 82E+04 5.05E+03 2.40E+07 1.01 E-07 Skin 3.20E+03 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 MO-99 O.OOE+00 9.79E+06 2 42E+06 0 OOE+00 2.09E+07 0 OOE+00 8.10E+06 O.OOE+00 14R Values in units of mrem / yr per micro-Ci/ m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-Ci / sec for all others.

HBRODCM 3-63 Rev. 1 9

TABLE 3.5-14 (continued)

Nuclide Bone Liver T.Body Thyroid Kidney Lunq GI-Tract Skin TC-99M 1.60E+00 3.14E+00 5.20E+01 0 OOE+O0 4.56E+01 1.59E+00 1.79E+03 0 OOE+00 RU-103 4.47E+02 0 OOE+00 1.72E+02 O.OOE+00 1.12E+03 O.OOE+OO 1.15E+04 0 OOE+00 RU-105 4.63E-04 O.OOE+00 1.68E-04 O.OOE+00 4.07E-03 0 OOE+00 3.02E-01 O.OOE+00 RU-106 8.93E+03 O.OOE+00 1.11E+03 O.OOE+00 1.21E+04 O.OOE+00 1.39E+05 O.OOE+00 AG-l10M 2 09E+07 1.41 E+07 1.13E+07 O.OOE+00 2.62E+07 O.OOE+00 1.68E+09 O.OOE+00 SN-113 1.40E+06 4.52E+04 1.53E+06 1.85E+04 3.10E+04 0 OOE+00 5.61E+06 O.OOE+00 SB-124 1.10E+07 1.42E+05 3.84E+06 2.42E+04 O.2OE+00 6.08E+06 6 85E+07 OOOE+00 SB-125 8 25E+06 6.36E+04 1.73E+06 7.64E+03 0 OOE+00 4.60E+06 1.97E+07 0 OOE+00 TE-129M 3 07E+07 8.57E+06 4.76E+06 9.90E+06 9 01E+07 O.OOE+00 3.74E+07 O.OOE+00 TE-129 1.62E-10 4.53E-11 3.85E-11 1.16E-10 4.74E-10 OOE+00 1.01E-08 O.OOE+00 TE-131M 1.96E+05 6 78E+04 7.22E+04 1.39E+05 6.57E+05 O.OOE+00 2.75E+06 O.0OE+00 TE-132 1.26E+06 5 57E+05 6 73E+05 8.11E+05 5.17E+06 0.00E+00 5.61 E+06 O.OOE+00 1-131 1.54E+09 1.55E+09 878E+08 5.11E+11 2.54E+09 OOE+00 1.38E+08 OOE+00 1-132 8.41E-01 1.55E+00 7.11E-01 7.17E+01 2.36E+00 0 OE+00 1.82E+OO O.OOE+00 1-133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 O.OOE+00 1.03E+07 O.OOE+00 1-134 1.06E-11 1.98E-11 9.09E-12 4.54E-10 3 02E-11 0.00E+00 1.31 E-11 O.OOE+00 1-135 6 52E+04 1.17E+05 5 55E+04 1.04E+07 1.80E+05 0 OOE+00 8.94E+04 0 OOE+00 CS-134 5.35E+10 8.78E+10 1.85E+10 0 OOE+00 2.72E+10 9.76E+09 4.73E+08 0 OOE+00 CS-136 2 89E+09 7.96E+09 5.15E+09 0 OOE+00 4 24E+09 6.32E+08 2.80E+08 O.OOE+00 CS-137 7.81E+10 7.48E+10 1.10E+10 0 OOE+00 2 44E+10 8.77E+09 4.68E+08 0 OOE+00 CS-138 1.28E-22 1.78E-22 1.13E-22 O.OOE+00 1.25E-22 1.35E-23 8.21E-23 0 OOE+00 BA-139 2.48E-08 1.32E-11 7.18E-10 OOE+00 1.15E-11 7.78E-12 1.43E-06 OOE+00 BA-140 1.34E+07 1.18E+04 7.84E+05 OOE+00 3.83E+03 7.01 E+03 680E+06 O.OOE+00 LA-140 2.33E+00 8.14E-01 2.75E-01 O.OOE400 0 OOE+00 0 OOE+00 2 27E+04 O.OOE+00 LA-142 9.95E-12 3 17E-12 9 94E-13 O.OOE+00 0 OOE+00 O.OOE+00 6.29E-07 O.OOE+00 CE-141 231E+03 1.15E+03 1.71 E+02 O.OOE+00 505E+02 O.OOE+00 1.44E+06 O.OOE+00 CE-143 2 25E+01 1.22E+04 1.77E+00 0 OOE+00 5.12E+00 0 OOE+00 1.79E+05 O.OOE+00 CE-144 1.54E+05 4 82E+04 8.21E+03 OOE+00 2.67E+04 OOE+00 1.26E+07 O.OOE+00 HF-181 4.30E+03 1.68E+01 4 33E+02 1.42E+01 1.35E+01 O.OOE+00 7.15E+04 O.OOE+00 W-187 3 47E+03 2.05E+03 9.22E+02 O.OOE+00 O.OOE+00 O.OOE+00 2.89E+05 O.OOE+00 NP-239 2 07E+00 1.49E-01 1.05E-01 O.OOE+00 4.30E-01 O.OOE+00 1.10E+04 O.OOE+00 HBRODCM 3-64 Rev. 19

TABLE 3.5-15 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT'5 (Reference Regulatory Guide 1.109)

PATHWAY = Goat Milk AGE GROUP = Infant Nuclide H-3 F-18 NA-24 CR-51 MN-54 MN-56 FE-55 FE-59 CO-57 co-58 C0-60 NI-65 CU-64 ZN-65 BR-82 BR-83 BR-84 RB-86 SR-89 SR-90 SR-91 SR-92 Y-91M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 NB-97 MO-99 Bone 0 OOE+00 4.85E-03 1.86E+06 0 OOE+00 0.00E+00 O.OOE+00 1.37E+06 2.50E+06 O OOE+00 0.00E+00 0.00E+00 4.27E-01 0.00E+00 5.99E+08 0.00E+00 0 OOE+00 O O0E+00 0.00E+00 2.25E+10 2.12E+11 5.73E+05 9 89E+00 7.13E-20 7.40E+03 6.52E-05 2.60E-01 6.83E+02 4 89E-01 6.23E+04 3 82E-12 Liver 4.86E+03 0 OOE+00 1.86E+06 0.00E+00 3 73E+06 3.83E-03 8 84E+05 4.37E+06 8.52E+05 2.42E+06 8 38E+06 4.84E-02 2.08E+04 2.06E+09 O.OOE+00 0 00E+00 O.W0E+00 2 48E+09 0 00E+00 o 00E+00 0.00E+00 O.00E+00 0.00E+00 0 00E+00 O OOE+00 O.OOE+00 1.66E+02 8.38E-02 2.57E+04 8.14E-13 T Bodv 4.86E+03 4.14E-04 1 86E+06 1.73E+04 8.46E+05 6.60E-04 2.36E+05 1.72E+06 1.39E+06 6 04E+06 1.98E+07 2.20E-02 9.62E+03 9.48E+08 2.35E+07 1.15E-01 1.64E-23 1.23E+09 6 45E+08 5.40E+10 2.07E+04 3 67E-01 2.43E-21 1.97E+02 1.83E-06 7.08E-03 1.18E+02 3 83E-02 1.48E+04 2.93E-13 Thyroid 4 86E+03 0.00E+00 1.86E+06 1.13E+04 0 00E+00 0 O0E+00 O.O0E+00 0 00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0 O0E+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 OOE+00 O.OOE+00 0 00E+00 0.00E+00 O.OOE+00 Kidney 4.86E+03 O.OOE+00 1.86E+06 2.46E+03 8 28E+05 3 29E-03 O.OOE+00 0 00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 3.51 E+04 9.97E+08 0 00E+00 O.OOE+00 O OOE+00 0.00E+00 0.00E+00 0.00E+00 0 OOE+00 0.00E+00 0 00E+00 0.00E+00 O.OOE+00 O.OOE+00 1.79E+02 8 45E-02 1.84E+04 6 36E-13 Lung 4.86E+03 O.OOE+00 1.86E+06 2.19E+04 O.OOE+00 O.OOE+00 4.32E+05 1.29E+06 O OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O OOE+00 O.OOE+00 0.00E+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 GI-Tract 4.86E+03 1.14E-03 1.86E+06 5.04E+05 1.37E+06 3 48E-01 1.12E+05 2 09E+06 2.90E+06 6.03E+06 1.99E+07 3 68E+00 4.26E+05 1.74E+09 O.OOE+00 0 OOE+00 0 OOE+00 6 36E407 4 62E+08 2.65E+09 6.78E+05 1.07E+02 2.38E-16 5.30E+05 1 24E+00 2.05E+03 8 29E+04 5.35E+03 2.17E+07 2.57E-07 Skin 4.86E+03 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 2.50E+07 4.88E+06 0.00E+00 3.74E+07 0 OOE+00 8 24E+06 O.OOE+00

'5R Values in units of mrem / yr per micro-Ci / m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-Ci / sec for all others.

HBRODCM 3-65 Rev. 1 9

TABLE 3.5-15 (continued)

Nuclide TC-99M RU-103 RU-105 RU-1 06 AG-i1 OM SN-113 SB-124 SB-125 TE-129M TE-129 TE-131M TE-132 1-131 1-132 1-133 1-134 1-135 CS-134 CS-136 CS-137 CS-138 BA-139 BA-140 LA-140 LA-142 CE-141 CE-143 CE-144 HF-181 W-187 Bone 3.33E+00 9.04E+02 9.76E-04 1.84E+04 3.86E+07 2.13E+06 2.11 E+07 1.42E+07 6.30E+07 3.44E-10 4.14E+05 2.59E+06 3 21 E+09 1.74E+00 4 36E+07 2.21 E-11 1.36E+05 8.62E+10 5 65E+09 1.25E+11 2.70E-22 5.27E-08 2.76E+07 4.87E+00 2.09E-1 1 4.58E+03 4.77E+01 2.21 E+05 8.23E+03 7.30E+03 Liver 6 87E+00 0 OOE+00 O OOE+00 0.OOE+O0 2.81 E+07 8.15E+04 3.11 E+05 1.37E+05 2.16E+07 1.18E-10 1.67E+05 1.28E+06 3.78E+09 3 54E+OO 6 35E+07 4.52E-11 2.70E+05 1.61 E+11 1.66E+10 1.46E+11 4.40E-22 3.49E-11 2.76E+04 1.92E+00 7.68E-12 2 80E+03 3 16E+04 9 03E+04 3 87E+01 5.08E+03 T.Body Thyroid Kidney 8.85E+01 0 OOE+00 7.39E+01 3 02E+02 O.OOE+OO 1.88E+03 3.29E-04 0 OOE+00 7.17E-03 2.30E+03 O.OOE+O0 2.18E+04 1.86E+07 O.OOE+O0 4.03E+07 2.20E+06 3.IOE+04 4.37E+04 6.54E+06 5.61 E+04 O.OOE+OO 2.91 E+06 1.77E+04 O.OOE+O0 9.71 E+06 2.42E+07 1.58E+08 8.02E-1I 2.88E-10 8.56E-10 1.38E+05 3.38E+05 1.15E+06 1.20E+06 1.89E+06 8.02E+06 1.66E+09 1.24E+12 4.41E+09 1.26E+00 1.66E+02 3.95E+00 1.86E+07 1.15E+10 7.46E+07 1.61E-11 i.05E-09 5 05E-11 9.83E+04 2.42E+07 3.00E+05 1.62E+10 O.OOE+OO 4.14E+10 6 21E+09 O.OOE+OO 6 63E+09 1.03E+10 O.OOE+QO 3 92E+10 2.13E-22 0 OOE+00 2.19E-22 1.53E-09 O.OOE+00 2.IOE-11 1.42E+06 0 OOE+00 6.56E+03 4.94E-01 O.OOE+OO O.OOE+OO 1.84E-12 0 OOE+00 0 OOE+OO 3 29E+02 0 OOE+00 8 62E+02 3 61E+00 O.OOE+O0 9 21E+00 1.24E+04 O.OOE+O0 3 65E+04 7.27E+02 3 28E+01 2.27E+01 1.75E+03 0 OOE+OO O.OOE+O0 Lung 3 59E+00 O.OOE+OO O.OOE+OO O.OOE+OO 0 OOE+00 O.OOE+OO 1.32E+07 8 20E+06 O.OOE+OO 0 OOE+OO 0 OOE+00 O.OOE+OO O.OOE+00 O.OOE+O0 O.O0E+OO 0 OOE+00 0 OOE+00 1.70E+10 1.35E+09 1.59E+10 3.42E-23 2.12E-1I 1.70E+04 O.OOE+OO O.OOE+00 0 OOE+00 0 O0E+OO 0 OOE+00 GI-Tract 2.00E+03 1.1OE+04 3.88E-01 1.40E+05 1.46E+09 4.55E+06 6.52E+07 1.89E+07 3.76E+07 2.75E-08 2.81 E+06 4.75E+06 1.35E+08 2.87E+00 1.07E+07 4.67E-1I 9.76E+04 4.37E+08 2.52E+08 4.56E+08 7.03E-22 3 34E-06 6.79E+06 2.25E+04 1.30E-06 1.44E+06 1.85E+05 1.27E+07 Skin O.OOE+00 0.OOE+O0 O.OOE+OO O.OOE+OO O.OOE+OO 0 OOE+00 O.OOE+O0 0 OOE+OO O.OOE+OO, 0.OOE+O0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0 OOE+00 0 OOE+O0 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.O0E+OO O.OOE+O0 O.OOE+OO 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 6.75E+04 O.00E+OO O.OOE+00 2 98E+05 O.OOE+00 O.OOE+00 NP-239 4.38E+00 392E-01 2.21E-01 OOE+00 7.81E-01 O.OOE+00 1.13E+04 HBRODCM 3-66 Rtev. 19

TABLE 3.5-16 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT"6 (Reference Regulatory Guide 1.109)

PATHWAY = Inhalation AGE GROUP = Adult Nuclide H-3 F-1 8 NA-24 CR-51 MN-54 MN-56 FE-55 FE-59 CO-57 CO-58 CO-60 Nl-65 CU-64 ZN-65 BR-82 BR-83 BR-84 RB-86 RB-88 RB-89 SR-89 SR-90 SR-91 SR-92 Y-91M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 Bone O.OOE+00 4 99E+03 1.02E+04 O OOE+00 O.OOE+00 O OOE+00 2.46E+04 1.1 8E+04 O.OOE+00 O.OOE+00 O OOE+00 1.54E+00 O.OOE+00 3 24E+04 O.OOE+00 O.OOE+00 O.OOE+00 O OOE+00 O.OOE+00 O OOE+00 3.04E+05 9.92E+07 6.19E+01 6.74E+00 2.61E-01 4.62E+05 1.03E+01 9.44E+01 1.07E+05 9.68E+01 1.41 E+04 Liver 1.26E+03 0 00E+00 1.02E+04 0 OOE+00 3 96E+04 1.24E+00 1.70E+04 2.78E+04 6.92E+02 1.58E+03 1.15E+04 2.1 OE-01 1.46E+00 1.03E+05 O.OOE+00 O.OOE+00 O.OOE+00 1.35E+05 3 87E+02 2 56E+02 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 3 44E+04 1.96E+01 7.82E+03 T.Bodv 1.26E+03 5.54E+02 1.02E+04 1.OOE+02 6.30E+03 1.83E-01 3 94E+03 1.06E+04 6.71 E+02 2.07E+03 1.48E+04 9 12E-02 6.15E-01 4 66E+04 1.35E+04 2 41 E+02 3.13E+02 5.90E+04 1.93E+02 1.70E+02 8.72E+03 6 10E+06 2.50E+00 2.91E-01 1.02E-02 1.24E+04 3.02E-01 2.61 E+00 2.33E+04 9.04E+00 4.21 E+03 Thyroid 1.26E+03 0 OOE+00 1.02E+04 5.95E+01 O.OOE+00 O.OOE+00 0.00E+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 Kidney 1.26E+03 0.00E+00 1.02E+04 2.28E+01 9 84E+03 1 30E+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4 62E+00 6 90E+04 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 5.42E+04 2.97E+01 7.74E+03 Lung 1.26E+03 O.OOE+00 1.02E+04 1.44E+04 1.40E+06 9.44E+03 7.21 E+04 1.02E+06 3.70E+05 9.28E+05 5.97E+06 5.60E+03 6.78E+03 8.64E+05 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 1.40E+06 9.60E+06 3.65E+04 1.65E+04 1.92E+03 1.70E+06 1.57E+04 4.85E+04 1.77E+06 7.87E+04 5 05E+05 GI-Tract 1.26E+03 1 A8E+02 1.02E+04 3.32E+03 7.74E+04 2.02E+04 6.03E+03 1.88E+05 3.14E+04 1.06E+05 2.85E+05 1.23E+04 4.90E+04 5.34E+04 1.04E+04 2.32E+02 1.64E-03 1.66E+04 3.34E-09 9.28E-12 3 50E+05 7.22E+05 1.91E+05 4.30E+04 1.33E+00 3 85E+05 7.35E+04 4.22E+05 1.50E+05 5.23E+05 1.04E+05 Skin 1.26E+03 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 16R Values in units of mrem / yr per micro-Ci/ m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-G / sec for all others.

HBRODCM 3-67 Rev. 19

TABLE 3.5-16 (continued)

Nuclide Bone Liver T Body Thyroid Kidney Lung GI-Tract Skin NB-97 2.22E-01 5.62E-02 2.05E-02 0 OOE+00 6 54E-02 2.40E+03 2.42E+02 0 OOE+00 MO-99 O.OOE+00 1.21E+02 2.30E+01 OOOE+00 2.91E+02 9.12E+04 2.48E+05 O.OOE+00 TCG99M 1.03E-03 2.91E-03 3.70E-02 0 OOE+00 4 42E-02 7.64E+02 4.16E+03 O.OOE+00 TC-1 01 4.1 BE-05 6.02E-05 5.90E-04 0 OOE+00 1.08E-03 3.99E+02 1.09E-1 1 O.OOE+00 RU-1 03 1.53E+03 O.OOE+00 6.58E+02 O.OOE+00 5.83E+03 5 05E+05 1.10E+05 0 OOE+00 RU-1 05 7.90E-01 0 OOE+00 3.11E-01 O.OOE+00 1.02E+00 1.10E+04 4.82E+04 OOE+00 RU-106 6 91E+04 O.OOE+00 8.72E+03 O.OOE+00 1.34E+05 9.36E+06 9.12E+05 O.0OE+00 AG-110M 1.08E+04 1.00E+04 5.94E+03 0 OOE+00 1.97E+04 4.63E+06 302E+05 OOE+00 SN-113 6.86E+03 266E+02 6.48E+03 9.28E+01 1.97E+02 2.99E+05 2.48E+04 O.OOE+00 SB-124 3.12E+04 5.89E+02 1.24E+04 7.55E+01 O.OOE+00 2.48E+06 4.06E+05 0 OOE+00 SB-125 5.34E+04 5.95E+02 1.26E+04 5.40E+01 O.OOE+00 1.74E+06 1.01E+05 0 OOE+00 TE-129M 9.76E+03 4.67E+03 1.58E+03 3 44E+03 3.66E+04 1.16E+06 3 83E+05 0 OOE+00 TE-1 29 4.98E-02 2 39E-02 1.24E-02 3.90E-02 1.87E-01 1.94E+03 1.57E+02 O.OOE+00 TE-131M 6 99E+01 4.36E+01 2.90E+01 5.50E+01 3.09E+02 1.46E+05 5 56E+05 O.OOE+00 TE-132 2.60E+02 2.15E+02 1.62E+02 1.90E+02 1.46E+03 2.88E+05 5.10E+05 O.OOE+00 1-131 2 52E+04 3 58E+04 2 05E+04 1.19E+07 6.13E+04 0.002+00 6 28E+03 0 OOE+00 1-132 1.16E+03 3.26E+03 1.16E+03 1.14E+05 5.18E+03 0 OOE+00 4 06E+02 0 OOE+00 1-133 8 64E+03 1.48E+04 4.52E+03 2.15E+06 2 58E+04 0 OOE+00 8.88E+03 O.OOE+00 1-134 644E+02 1.73E+03 6.15E+02 2.98E+04 2.75E+03 0 OOE+00 1.01E+00 OOE+00 1-135 2.68E+03 698E+03 2.57E+03 4.48E+05 1.11E+04 O.OOE+00 525E+03 O.OOE+00 CS-134 3.73E+05 8.48E+05 7.28E+05 O.OOE+00 2.87E+05 9.76E+04 1.04E+04 O.OOE+00 CS-136 3.90E+04 1.46E+05 1.10E+05 0 OOE+00 8.56E+04 1.20E+04 1.17E+04 0 OOE+00 CS-137 4.78E+05 6.21 E+05 4.28E+05 OOE+00 2 22E+05 7.52E+04 8.40E+03 O.OOE+00 CS-138 3.31 E+02 6.21 E+02 324E+02 O.OOE+00 480E+02 486E+01 1.86E-03 OOE+00 BA-139 9 36&-i 6.66E-04 2.74E-02 O.OOE+00 6.22E-04 3 76E+03 8 96E+02 0 OOE+00 BA-140 3.90E+04 4 90E+01 2.57E+03 0 OOE+00 1.67E+01 1.27E+06 2 18E+05 0.002+00 BA-142 2 63E-02 2.70E-05 1.66E-03 OOE+00 229E-05 1.19E+03 1.57E-16 OOE+00 LA-140 3 44E+02 1.74E+02 4.58E+01 0 OOE+00 O.OOE+00 1.36E+05 4 58E+05 0 OOE+00 LA-142 6 83E-01 3 10E-01 7.72E-02 0 OOE+00 OOE+00 633E+03 2.11E+03 O.OOE+00 CE-141 1.99E+04 1.35E+04 1.53E+03 O.OOE+00 6 26E+03 3 62E+05 1.20E+05 O.OOE+00 CE-143 1.86E+02 1 38E+02 1.53E+01 O.OOE+00 608E+01 7.98E+04 2.26E+05 O.OOE+00 CE-144 3.43E+06 1.43E+06 1.84E+05 O.OOE+00 8.48E+05 7.78E+06 8.16E+05 O.OOE+00 PR-144 301E-02 1.25E-02 1.53E-03 OOE+00 7.05E-03 1.02E+03 2.15E-08 OOE+00 HF-181 4 56E+04 2.57E+02 5.15E+03 1.63E+03 2.14E+02 5.98E+05 1.29E+05 O.OOE+00 W-187 8 48E+00 7.08E+00 2.48E+00 0 OOE+00 O.OOE+00 2.90E+04 1.55E+05 O.OOE+00 NP-239 2.30E+02 2.26E+01 1.24E+01 0 OOE+00 7.00E+01 3.76E+04 1.19E+05 0 OOE+00 HBRODCM 3-68 Rev. 1 9

TABLE 3.5-17 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT"T (Reference Regulatory Guide 1.109)

PATHWAY = Inhalation AGE GROUP = Teen NuCide H-3 F-18 NA-24 CR-51 MN-54 MN-56 FE-55 FE-59 CO-57 CO-58 CO-60 NI-65 CU-64 ZN-65 BR-82 BR-83 BR-84 RB-86 RB-88 RB-89 SR-89 SR-90 SR-91 SR-92 Y-91M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 Bone O.OOE+00 5.22E+03 1.38E+04 O.OOE+00 O OOE+00 0.00E+00 3.34E+04 1.59E+04 0.00E+00 O.OOE+00 O.OOE+00 2.18E+00 O.OOE+00 3 86E+04 O OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 4.34E+05 I 08E+08 8 80E+01 9.52E+00 3.70E-01 6.61 E+05 1.47E+01 1.35E+02 1.46E+05 1.38E+02 1.86E+04 Liver 1.27E+03 O.OOE+00 1.38E+04 0 OOE+00 5.11E+04 1.70E+00 2.38E+04 3 70E+04 9.44E+02 2.07E+03 1.51 E+04 2.93E-01 2.03E+00 1.34E+05 0 00E+00 O.OOE+00 O OOE+00 1.90E+05 5.46E+02 3 52E+02 O.OOE+00 O OOE+00 0 OOE+00 O OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 4.58E+04 2.72E+01 1.03E+04 T.Body 1.27E+03 5.68E+02 1.38E+04 1.35E+02 8.40E+03 2 52E-01 5.54E+03 1.43E+04 9.20E+02 2.78E+03 1.98E+04 1.27E-01 8.48E-01 6 24E+04 1.82E+04 3 44E+02 4.33E+02 8.40E+04 2 72E+02 2.33E+02 1.25E+04 6 68E+06 3 51 E+00 4.06E-01 1.42E-02 1.77E+04 4 29E-01 3 72E+00 3.15E+04 1.26E+01 5.66E+03 Thyroid 1.27E+03 0 OOE+00 1.38E+04 7.50E+01 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Kidney 1.27E+03 O.OOE+00 1.38E+04 3 07E+01 1.27E+04 1.79E+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0.00E+00 6.41 E+00 8 64E+04 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0.00E+00 6 74E+04 4 12E+01 1.OOE+04 Luna 1.27E+03 0 OOE+00 1.38E+04 2.1 0E+04 1.98E+06 1.52E+04 1.24E+05 1.53E+06 5.86E+05 1.34E+06 8 72E+06 9.36E+03 1.11 E+04 1.24E+06 0.00E+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.42E+06 1.65E+07 6.07E+04 2.74E+04 3.20E+03 2.94E+06 2.68E+04 8.32E+04 2.69E+06 1.30E+05 7.51 E+05 GI-Tract 1.27E+03 3 11 E+02 1.38E+04 3.00E+03 6.68E+04 5.74E+04 6 39E+03 1.78E+05 3.14E+04 9.52E+0T 2.59E+05 3.67E+04 6.14E+04 4.66E+04 O.OOE+00 0 OOE+00 0.00E+00 1.77E+OA 2.92E-05 3.38E-07 3.71 E+05 7.65E+05 2.59E+05 1.19E+05 3 02E+01 4.09E+05 1.65E+05 5 79E+05 1.49E+05 6 30E+05 9.68E+04 Skin 1.27E+03 0.00E+00 O.OOE+00 0.00E+00 0 00E+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 00E+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 002+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 17R Values in units of mrem t yr per micro-Ci / m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-Ci / sec for all others.

HBRODCM 3-69 Rev. 1 9

TABLE 3.5-17 (continued)

Nuclhde NB-97 MO-99 TC-99M TC-101 RU-103 RU-105 RU-106 AG-11OM SN-113 SB-124 SB-125 TE-129M TE-129 TE-131M TE-132 1-131 1-132 1-133 1-134 1-135 CS-134 CS-136 CS-137 CS-138 BA-139 BA-140 BA-142 LA-140 LA-142 CE-141 CE-143 CE-144 PR-144 HF-181 W-187 NP-239 Bone 3.14E-01 O.OOE+00 1.38E-03 5.92E-05 2.10E+03 1.12E+00 9.84E+04 1.38E+04 8.1 6E+03 4.30E+04 7.38E+04 1.39E+04 7.10E-02 9.84E+01 3 69E+02 3.54E+04 1.59E+03 1.22E+04 8.88E+02 3 70E+03 5.02E+05 5 15E+04 6.70E+05 4.66E+02 1.34E+00 5 47E+04 3.70E-02 4.79E+02 9 60E-01 2.84E+04 2 66E+02 4 89E+06 4.30E-02 6 31 E+04 1.20E+01 3 38E+02 Liver 7.78E-02 1.69E+02 3.86E-03 8.40E-05 O.OOE+00 O.OOE+00 O OOE+00 1.31 E+04 3 44E+02 7.94E+02 8 08E+02 6.58E+03 3.38E-02 6 01 E+01 2.90E+02 4 91 E+04 4.38E+03 2.05E+04 2.32E+03 9.44E+03 1.13E+06 1.94E+05 8.48E+05 8.56E+02 9.44E-04 6 70E+01 3.70E-05 2 36E+02 4.25E-01 1.90E+04 1.94E+02 2 02E+06 1.76E-02 3 47E+02 9.76E+00 3.19E+01 T Body 2 84E-02 3.22E+01 4 99E-02 8.24E-04 8.96E+02 4.34E-01 1.24E+04 7.99E+03 8.64E+03 1.68E+04 1.72E+04 2 25E+03 1.76E-02 4.02E+01 2.19E+02 2.64E+04 Thyroid 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 1.13E+02 9.76E+01 7.04E+01 4.58E+03 5.18E-02 7.25E+01 2.46E+02 1.46E+07 1.58E+03 1.51E+05 6.22E+03 2.92E+06 8.40E+02 3 95E+04 3.49E+03 6 21 E+05 5.49E+05 O.OOE+00 1.37E+05 O.OOE+o0 3 11E+05 O.OOE+00 4A6E+02 0 OOE+00 3 90E-02 O.OOE+00 3 52E+03 O.OOE+00 2 27E-03 0 OOE+00 6.26E+01 O.OOE+00 1.06E-01 O.OOE+00 2.17E+03 O.OOE+00 2.16E+01 0 OOE+00 2.62E+05 O.OOE+00 2 18E-03 0 OOE+00 7.04E+03 2.12E+02 3 43E+00 O.OOE+00 1.77E+01 0 OOE+00 Kidney 9.12E-02 4.11 E+02 5.76E-02 1.52E-03 7.43E+03 1.A1 E+00 1.90E+05 2.50E+04 2.46E+02 0 OOE+00 O.OOE+00 5.19E+04 2.66E-01 4.39E+02 1.95E+03 8 40E+04 6 92E+03 3 59E+04 3.66E+03 1.49E+04 3.75E+05 1.10E+05 3 04E+05 6 62E+02 8.88E-04 2.28E+01 3.14E-05 O.OOE+00 0 OOE+00 8.88E+03 8.64E+01 1.21 E+06 1.01 E-02 2.90E+02 O.OOE+00 1.OOE+02 Lung 3.93E+03 1.54E+05 1.15E+03 6.67E+02 7.83E+05 1.82E+04 1.61 E+07 6.75E+06 4.26E+05 3.85E+06 2.74E+06 1.98E+06 3.30E+03 2.38E+05 4.49E+05 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 1.46E+05 1.78E+04 1.21E+05 7.87E+01 6.46E+03 2.03E+06 1.91 E+03 2.14E+05 1.02E+04 6.14E+05 1.30E+05 1.34E+07 1.75E+03 9 36E+05 4.74E+04 6.49E+04 GI-Tract 2.17E+03 2.69E+05 6.13E+03 8.72E-07 1.09E+05 9.04E+04 9 60E+05 2.73E+05 2.03E+04 3.98E+05 9.92E+04 4 05E+05 1.62E+03 6.21 E+05 4.63E+05 6 49E+03 1.27E+03 1.03E+04 2.04E+01 6.95E+03 9.76E+03 1 09E+04 8.48E+03 2.70E-01 6.45E+03 2.29E+05 4.79E-10 4.87E+05 1.20E+04 1.26E+05 2.55E+05 8.64E+05 2.35E-04 1.20E+05 1.77E+05 1.32E+05 Skin O.OOE+00 O.ooE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.ooE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.ooE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 HRRODCM 3-70 Rev. 19

TABLE 3.5-18 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT"8 (Reference Regulatory Guide 1.109)

PATHWAY = Inhalation AGE GROUP = Child Nuclide H-3 F-1 8 NA-24 CR-51 MN-54 MN-56 FE-55 FE-59 CO-57 C0-58 CO-60 Nl-65 CU-64 ZN-65 BR-82 BR-83 BR-84 RB-86 RB-88 RB-89 SR-89 SR-90 SR-91 SR-92 Y-91M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 Bone O.OOE+00 6.96E+03 1.61 E+04 0 OOE+00 O.OOE+00 O.OOE+00 4.74E+04 2.07E+04 O.OOE+00 0 OOE+00 0 OOE+00 2.99E+00 O.OOE+00 4 26E+04 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 5.99E+05 1.01 E+08 1.21 E+02 1.31 E+01 5 07E-01 9.14E+05 2.04E+01 1.86E+02 1.90E+05 1.88E+02 2.35E+04 Liver 1.12E+03 O.OOE+00 1.61 E+04 O.OOE+00 4.29E+04 1.66E+00 2.52E+04 3 34E+04 9 03E+02 1.77E+03 1.31 E+04 2.96E-01 1.99E+00 1.13E+05 O.OOE+00 O.OOE+00 O.OOE+00 1.98E+05 5.62E+02 3 45E+02 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 4.18E+04 2 72E+01 9.18E+03 T.Bodv 1.12E+03 6.85E+02 1.61 E+04 1.54E+02 9 51 E+03 3.12E-01 7.77E+03 1.67E+04 1.07E+03 3.16E+03 2.26E+04 1.64E-01 1.07E+00 7.03E+04 2 09E+04 4.74E+02 5.48E+02 1.14E+05 3.66E+02 2.90E+02 1.72E+04 6.44E+06 4.59E+00 5 25E-01 1.84E-02 2.44E+04 5.81 E-01 5.11 E+00 3.70E+04 1.60E+01 6.55E+03 Thyroid 1.12E+03 O.OOE+00 1.61 E+04 8.55E+01 O.OOE+00 0.002+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0.002+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0.002+00 O.OOE+00 Kidney 1.12E+03 0 OOE+00 1.61 E+04 2.43E+01 1.OOE+04 1.67E+00 O.OOE+00 0 00E+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 6.03E+00 7.14E+04 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0.00E+00 O.OOE+00 O.OOE+00 5.96E+04 3.88E+01

8.62E+03 Lunq 1.12E+03 O.OOE+00 1.61 E+04 1 70E+04 1.58E+06 1.31 E+04 1.11 E+05 1.27E+06 5 07E+05 1.11 E+06 7.07E+06 8.18E+03 9 58E+03 9.95E+05 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 2.16E+06 1.48E+07 5 33E+04 2 40E+04 2.81 E+03 2.63E+06 2.39E+04 7.44E+04 2 23E+06 1.13E+05 6.14E+05 GI-Tract 1.12E+03 1.25E+03 1.61 E+04 1.08E+03 2.29E+04 1.23E+05 2.87E+03 7.07E+04 1.32E+04 3 44E+04 9.62E+04 8.40E+04 3.67E+04 1.63E+04 O.OOE+00 O.OOE+00 0 OOE+00 7.99E+03 1.72E+01 1.89E+00 1.67E+05 3.43E+05 1.74E+05 2.42E+05 1.72E+03 1.84E+05 2 39E+05 3.89E+05 6.11 E+04 3.51 E+05 3.70E+04 Skin 1.12E+03 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 00E+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00

'8R Values in units of mrem / yr per micro-Ci / m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-Ci / sec for all others.

HBRODCM 3-71 Rev. 19

TABLE 3.5-18 (continued)

Nuclide Bone Liver T Body Thyroid Kidney Lunq GI-Tract Skin NB-97 4.29E-01 7.70E-02 3.50E-02 O.0OE+OO 8 55E-02 3.42E+03 2.78E+16 0 OOE+00 MO-99 O.OOE+OO 1.72E+02 4.25E+01 0 OOE+00 3 92E+02 1.35E+05 1.27E+05 0 OOE+O0 TC-99M 1.78E-03 3.48E-03 5.77E-02 O.OOE+OO 5.07E-02 9.51 E+02 4 81 E+03 O.0OE+OO TC-101 8.10E-05 8.51E-05 1.08E-03 O.O0E+00 1.45E-03 5 85E+02 1.63E+01 0 OOE+O0 RU-103 2.79E+03 O.OOE+OO 1.07E+03 O.OOE+OO 7.03E+03 6 62E+05 4.48E+04 0 OOE+00 RU-105 1.53E+00 O.OOE+OO 5.55E-01 O.0OE+OO 1.34E+00 1.59E+04 9.95E+04 0 O0E+00 RU-106 1.36E+05 O.OOE+OO 1.69E+04 0 OOE+00 1.84E+05 1.43E+07 4.29E+05 O.OOE+OO AG-10M 1.69E+04 1.14E+04 9.14E+03 O.OOE+OO 2.12E+04 5.48E+06 1.00E+05 O.OOE+OO SN-113 8.99E+03 2.90E+02 9.81E+03 1.19E+02 2.03E+02 3.40E+05 7.44E+03 O.0OE+00 SB-124 5 74E+04 7.40E+02 2.OOE+04 1.26E+02 O.OOE+OO 3.24E+06 1.64E+05 O.OOE+OO SB-125 9.84E+04 7.59E+02 2.07E+04 9.10E+01 0 OOE+00 2.32E+06 4.03E+04 O.OOE+OO TE-129M 1.92E+04 6.85E+03 3.04E+03 6 33E+03 5.03E+04 1.76E+06 1.82E+05 0 OOE+00 TE-129 9.77E-02 3.50E-02 2.38E-02 7.14E-02 2.57E-01 2 93E+03 2.55E+04 O.0OE+OO TE-131M 1.34E+02 5 92E+01 5.07E+01 9.77E+01 4.00E+02 2 06E+05 3 08E+05 0 OOE+00 TE-132 4.81E+02 2.72E+02 2.63E+02 3.17E+02 1.77E+03 3.77E+05 1.38E+05 O.OOE+OO 1-131 4 81 E+04 4.81 E+04 2.73E+04 1.62E+07 7.88E+04 0 OOE+OO 2.84E+03 0 OOE+00 1-132 2 12E+03 4.07E+03 1.88E+03 1.94E+05 6 25E+03 0 OOE+00 3 20E+03 O.O0E+OO 1-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3 38E+04 O.OOE+O0 5.48E+03 O.OOE+O0 1-134 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3 30E+03 O.OOE+00 9 55E+02 0 OOE+00 1-135 4 92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 0 0OE+00 4.44E+03 0 OOE+OO CS-134 6 51 E+05 1.01 E+06 2 25E+05 0 OOE+00 3 30E+05 1.21 E+05 3.85E+03 0 OOE+OO CS-136 6 51E+04 1.71E+05 1.16E+05 O.O0E+OO 9.55E+04 1.45E+04 4.18E+03 O.OOE+00 CS-137 9 07E+05 8 25E+05 1.28E+05 O.OE+OO 2.82E+05 1.04E+05 3 62E+03 O.OOE+OO CS-138 6.33E+02 8 40E+02 5.55E+02 O.O0E+O0 6 22E+02 6.81E+01 2.70E+02 0 OOE+00 BA-139 1.84E+00 9 84E-04 5.36E-02 O.OOE+OO 8 62E-04 5.77E+03 5 77E+04 0 OOE+00 BA-140 7.40E+04 6.48E+01 4.33E+03 O.OOE+OO 2.11E+01 1.74E+06 1.02E+05 002E+O0 BA-142 4.99E-02 3.60E-05 2.79E-03 0 OOE+00 2.91 E-05 1.64E+03 2.74E+00 0 OOE+00 LA-140 6 44E+02 2.25E+02 7.55E+01 O.0OE+OO O.O0E+OO 1.83E+05 2.26E+05 O.OOE+00 LA-142 1.29E+00 4.11E-01 1.29E-01 0 OOE+00 O OOE+00 8.70E+03 7.59E+04 o.OOE+00 CE-141 3.92E+04 1.95E+04 2.90E+03 O.0OE+OO 8 55E+03 5.44E+05 5.66E+04 0 OOE+00 CE-143 3.66E+02 1.99E+02 2 87E+01 O.O0E+OO 8 36E+01 1.15E+05 1.27E+05 O.OOE+00 CE-144 6 77E+06 2.12E+06 3.61E+05 O.OOE+OO 1.17E+06 1.20E+07 3.89E+05 O.0OE+OO PR-144 5.96E-02 1.85E-02 3 OOE-03 O.OOE+OO 9.77E-03 1.57E+03 1.97E+02 0 OOE+00 HF-181 8.33E+04 3 28E+02 8.47E+03 2.76E+02 2.63E+02 7.96E+05 5 29E+04 O.OOE+00 W-187 1.63E+01 9.66E+00 4.33E+00 O.0OE+OO O.O0E+OO 4.11E+04 9.10E+04 002E+O0 NP-239 466E+02 3.34E+01 2.35E+01 O.OOE+00 9.73E+01 5.81E+04 6 40E+04 O.OOE+OO HBRODCM 3-72 Rev. 19

TABLE 3.5-19 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT19 (Reference Regulatory Guide 1.109)

PATHWAY = Inhalation AGE GROUP = Infant Nuclide H-3 F-1 8 NA-24 CR-51 MN-54 MN-56 FE-55 FE-59 CO-57 CO-58 CO-60 NI-65 CU-64 ZN-65 BR-82 BR-83 BR-84 RB-86 RB-88 RB-89 SR-89 SR-90 SR-91 SR-92 Y-91M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 Bone O OOE+00 5.49E+03 1.06E+04 O.OOE+00 0 OOE+00 0 OOE+00 1.97E+04 1.36E+04 0 OOE+00 O.OOE+00 0 OOE+00 2.39E+00 O.OOE+00 1.93E+04 O.OOE+OO 0.00E+O0 O OOE+00 O.OOE+00 O.OOE+00 O OOE+?0' 3.98E+05 4.09E+07 9.56E+01 1.05E+01 4.07E-01 5.88E+05 1.64E+01 1.50E+02 1.15E+05 1.50E+02 1.57E+04 Liver 6.47E+02 O.OOE+00 1.06E+04 O.OOE+00 2.53E+04 1.54E+00 1.17E+04 2.35E+04 6.51 E+02 1.22E+03 8.02E+03 2.84E-01 1.88E+00 6.26E+04 O.OOE+00 0 OOE+00 0 0OE+00 1.90E+05 5.57E+02 3 2IE+02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 2.79E+04 2.56E+01 6 43E+03 T.Bodv 6 47E+02 4.66E+02 1.06E+04 8.95E+01 4.98E+03 2.21 E-01 3.33E+03 9.48E+03 6 41 E+02 1.82E+03 1.18E+04 1.23E-01 7.74E-01 3.11E+04 1.33E+04 3 81 E+02 4 00202 8.82E+04 2.87E+02 2 06E+02 1.14E+04 2.59E+06 3 46E+00 3 91 E-01 1.39E-02 1.57E+04 4.61 E-01 4.07E+00 2.03E+04 1.17E+01 3.78E+03 Thyroid 6.47E+02 O.OOE+00 1.06E+04 5.75E+01 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Kidney 6.47E+02 0 OOE+00 1.06E+04 1.32E+01 4.98E+03 1.1 OE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 3.98E+00 3.25E+04 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 00E+00 0 OOE+00 O.OOE+00 3 11 E+04 2.59E+01 Luna 6.47E+02 O.OOE+00 1.06E+04 1.28E+04 1.00E+06 1.25E+04 8 69E+04 1.02E+06 3.79E+05 7.77E+05 4.51 E+06 8.12E+03 9 30E+03 6.47E+05 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 2.03E+06 1.12E+07 5.26E+04 2.38E+04 2.79E+03 2.45E+06 2 45E+04 7.64E+04 1.75E+06 1.10E+05 GI-Tract 6.47E+02 8 54E+02 1.06E+04 3 57E+02 7.06E+03 7.17E+04 1.09E+03 2.48E+04 4.86E+03 1.11 E+04 3.19E+04 5.01 E+04 1.50E+04 5.14E+04 0 OOE+00 0 OOE+O 0 OOE+00 3.04E+03 3 39E+02 6 82E+01 6 40E+04 1.31 E+05 7.34E+04 1.40E+05 2.35E+03 7.03E+04 1.27E+05 1.67E+05 2.17E+04 1.40E+05 Skin 6 47E+02 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 00E+00 4.72E+03 4.79E+05 1.27E+04 0 OOE+00 19R Values in units of mrem / yr per micro-Ci / m3 for inhalation and tritium, and in units of m2 mrem / yr per micro-Ci / sec for all others.

HBRODCM 3-73 Rev. 19

TABLE 3.5-19 (continued)

Nuclide Bone Liver T Body Thyroid Kidney Lung GI-Tract Skin NB-97 3 42E-01 7.29E-02 2.63E-02 O.OOE+O0 5.70E-02 3 32E+03 2.69E+04 O.OOE+OO MO-99 O.OOE+OO 1.65E+02 3 23E+01 O.OOE+O0 2.65E+02 1.35E+05 4.87E+04 O.OOE+O0 TC-99M 1.40E-03 2.88E-03 3.72E-02 0 OOE+00 3.11 E-02 8.11E+02 2.03E+03 O.OOE+O0 TC-101 6.51E-05 8.23E-05 8.12E-04 O.OOE+O0 9.79E-04 5.84E+02 8.44E+02 O.OOE+O0 RU-1 03 2.02E+03 O.OOE+O0 6.79E+02 O.OOE+OO 4.24E+03 5.52E+05 1.61 E+04 O.OOE+O0 RU-105 1.22E+00 O.OOE+O0 4.10E-01 O.OOE+O0 8.99E-01 1.57E+04 4 84E+04 O.O0E+O0 RU-106 8.68E+04 O.OOE+OO 1.09E+04 O.OOE+00 1.07E+05 1.16E+07 1.64E+05 O.OOE+OO AG-11 OM 9.98E+03 7.22E+03 5.00E+03 O.OOE+00 1.09E+04 3.67E+06 3.30E+04 0 OOE+00 SN-113 4.68E+03 1.74E+02 4.89E+03 6.72E+01 9.94E+01 2.30E+05 2.28E+03 O.OOE+O0 SB-124 3 04E+04 5.56E+02 1.20E+04 1.01 E+02 O.O0E+OO 2.65E+06 3.42E+04 O.OOE+O0 SB-125 5.17E+04 4.77E+02 1.09E+04 6.23E+00 5.70E-02 3 32E+03 2.69E+04 O.O0E+O0 TE-129M 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 O.OOE+O0 TE-129 7.88E-02 3 47E-02 1.88E-02 6.75E-02 1.75E-01 3.OOE+03 2.63E+04 0 OOE+00 TE-131M 1.07E+02 5.50E+01 3.63E+01 8.93E+01 2.65E+02 1.99E+05 1.19E+05.

0 OOE+00 TE-132 3.72E+02 2.37E+02 1.76E+02 2.79E+02 1.03E+03 3 40E+05 4.41 E+04 0 OOE+OO 1-131 3 79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0 OOE+00 1.06E+03 O.OOE+00 1-132 1.69E+03 3.54E+03 1.26E+03 1.69E+05 3.95E+03 O.OOE+O0 1.90E+03 O.OOE+00 1-133 1.32E+04 1.92E+04 5 60E+03 3.56E+06 2.24E+04 O.OOE+OO 2.16E+03 0 OOE+00 1-134 9.21 E+02 1.88E+03 6.65E+02 4.45E+04 2.09E+03 O.OOE+00 1.29E+03 0 O0E+OO 1-135 3.86E+03 7.60E+03 2.77E+03 6 96E+05 8 47E+03 O.OOE+00 1.83E+03 0 OOE+O0 CS-134 3.96E+05 7.03E+05 7.45E+04 O.OOE+O0 1.90E+05 7.97E+04 1.33E+03 O.OOE+OO CS-136 4 83E+04 1.35E+05 5.29E+04 O.OOE+O0 5 64E+04 1.18E+04 1.43E+03 O.OOE+O0 CS-137 5 49E+05 6.12E+05 4.55E+04 O.OOE+O0 1.72E+05 7.13E+04 1.33E+03 0 OOE+00 CS-138 505E+02 7.81 E+02 3 98E+02 0 OOE+00 4.10E+02 6 54E+01 8.76E+02 O.OOE+O0 BA-139 1 48E+00 9.84E-04 4.30E-02 0 OOE+00 5.92E-04 5 95E+03 5.10E+04 O.O0E+O0 BA-140 5.60E+04 5.60E+01 2.90E+03 O.OOE+O0 1.34E+01 1.60E+06 3 84E+04 O.OOE+O0 BA-142 3 98E-02 3.30E-05 1.96E-03 O.OOE+O0 1.90E-05 1.55E+03 6 93E+02 O.OOE+O0 LA-1 40 5 05E+02 2.00E+02 5.15E+01 O.OOE+OO O.O0E+OO 1.68E+05 8.48E+04 O.OOE+O0 LA-t42 1.03E+00 3.77E-01 9.04E-02 0 OOE+00 O.OOE+OO 8 22E+03 5.95E+04 O.OOE+OO CE-141 2.77E+04 1.67E+04 1.99E+03 O.OOE+00 5.25E+03 5.17E+05 2.16E+04 O.OOE+00 CE-143 2.93E+02 1.93E+02 2.21E+01 O.OOE+O0 5 64E+01 1.16E+05 4.97E+04 O.OOE+O0 CE-144 3.19E+06 1.21E+06 1.76E+05 O.OOE+OO 5.38E+05 9.84E+06 1.48E+05 O.OOE+OO PR-144 4.79E-02 1.85E-02 2.41E-03 O.OOE+O0 6.72E-03 1.61E+03 4.28E+03 O.OOE+O0 HF-181 5.64E+04 2.66E+02 5 05E+03 2.25E+02 1.58E+02 6.72E+05 1.90E+04 O.OOE+O0 W-187 1.30E+01 9.02E+00 3.12E+00 O.OOE+O0 0 OOE+00 3 96E+04 3 56E+04 0 O0E+O0 NP-239 3.71 E+02 3.32E+01 1.88E+01 O.OOE+OO 6.62E+01 5.95E+04 2.49E+04 O.OOE+O0 HBRODCM 3-74 Rev. 19

ML031220199

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SUMMARY

SUMMARY

1.0 INTRODUCTION

1.0 INTRODUCTION

2.1 REFERENCES

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