Text

Rev 4 to Odcm.
	ML18011A563
Person / Time
Site:	Harris
Issue date:	07/01/1994
From:	; CAROLINA POWER & LIGHT CO.
To:	;
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ML18011A558	List: ML18011A557; ML18011A562; ML18011A563;
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	PROC-940701, NUDOCS 9408300115
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SHEARON HARRIS NUCLEAR POWER PLANT OFF-SITE DOSE CALCULATIONMANUAL (ODCM)

Revision 4 Docket No. STN-50-400 CAROLINA POWER 6 LIGHT COMPANY PNSC Chairman's Approval Effective Date RECElVED JUP 01 1994 nial'f QQl 94083003.i5 940822 PDR ADDCK 05000400 R PDR

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) ~ Rev. 4 TABLE OF CONTENTS Section Title ~Pa e TABLE OF CONTENTS i LIST OF TABLES LIST OF FIGURES iv

1.0 INTRODUCTION

2.0 LIQUID EFFLUENTS 2-1 2.1 Compliance With 10CFR20 2-2 2.2 Compliance With 10CFR50 Appendix I 2-13 3.0 GASEOUS EFFLUENTS 3-1 3.1 Monitor Alarm Set Point Determination . 3-1 3.2 Postrelease Compliance With 10CFR20-Based Technical Specification 3.11.2 3-10 3.3 Compliance With 10CFR50 3-17 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4-1 5.0 INTERLABORATORY COMPARISON STUDIES 5-1 6.0 TOTAL DOSE (COMPLIANCE WITH 40 CFR 190) 6-1 6.1 Dose to the Likely Most Exposed Member of the Public 6-1 6.2 Dose to a Member of the Public Due to Activities Within the Site Boundary ~ . 6-2 7.0 LICENSEE-INITIATED CHANGES TO THE ODCM 0 . 7-1 APPENDIX A - METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS A-1 APPENDIX B - DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B-1 APPENDIX C - RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS C-l

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 LIST OF TABLES No. Title ~Pa e 2.1-1 Liquid Effluent, Release Tanks and Pumps 2-19 2.1-2 SetPoints for Cooling Tower Blowdown Dilution Flow Rates (Fg~gjz) o ~ ~ ~ ~ ~ ~ ~ ~ 2-20 2.1-3 Signal Processor Time Constants (r) for GA Technologies RD-53 Liquid Effluent Monitors 2-20 2.1-4 Nuclide Parameters 2-21 2.2-1 A~, Values for the Adult for the Shearon Harris Nuclear Power Plant ~ ~ ~ ~ 0 ~ 0 ~ 2-24 3.1-1 Gaseous Source Terms 3-8 F 1-2 Dose Factors and Constants 3-9 3.2-1 Releases from Shearon Harris Nuclear Power Plant (1)

Normal Operation (Curies/year) 3-13 3.2-2 Distance to the Nearest Special Locations for the Shearon Harris Nuclear Power Plant (Miles) 3-14 3.2-3 Dose Factors for Noble Gases . . . . . ~ . , ~ . . . ~ . . . 3-15 3.2-4 Pzz Values (Inhalation) for a Child 3-16 3.3-1 through 3.3-19 R Values for the Shearon Harris Nuclear Power Plant 3-29 4.1 Radiological Environmental Monitoring Program 4-2 A-1 through A-4 X/Q and D/Q values for long-term ground-level releases at special locations . . . . . . . . . . . . . . . . . . . . A-4

0 b

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 LIST OF TABLES (continued) e Ne. Tit1e ~Pa e A-5 through AS Undepleted, No Decay, X/Q Values For Long Term Ground Level Releases At Standard Distances (Sec/M~) A-5 A9 through A10 Depleted, 8.0 Day Decay, X/Q Values For Long Term Ground Level Releases At Standard Distances (Sec/M3) A-9 All through A12 Deposition Values (D/Q) For Long Term Releases At Standard Distances (m 2) . . . . . . . . . . . . . . . . . . . . . . . A-ll A-13 Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP A-13 A-14 Shearon Harris Plant. Site Input Information for Continuous Groundlevel Release Calculations With the NRC XOQDOQ Program A-16 Parameters for Cow and Goat Milk Pathways B-16 B-2 Parameters for the Meat Pathway B-17 B-3 Parameters for the Vegetable Pathway B-18

i 0

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 LIST OF FIGURES Ne. Title ~Pa e 2.1-1 Liquid Waste Processing Flow Diagram 2-26 2.1-2 Liquid Effluent Flow Stream Diagram 2-27 2.1-3 Normal Service Water Flow Diagram 2-28 2.1-4 Other Liquid Effluent Pathways 2-29 3.1 SHNPP Gaseous Waste Streams 3-48 3.2 Schematic of Airborne Effluent Release Points 3-49 3.3 SHNPP Condenser Off-Gas System 3-50 4.1-1 SHNPP Exclusion Boundary Plan 4.1-2 through 4.1-5 I

Environmental'Radiological .Sampling Points 4-19

0 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 List of Effective Pa es

~Pa e Revision Cover Page 1 - v ~ ~ ~

2 2-29 ~ ~ ~

3-1 3-50 ~ 4 4 4-22 ~ ~ ~ 0 ~ 0 ~ ~ 0 5-1 6 6-2 ~ ~ ~ ~ ~ ~ 4 7-1 ~ ~ ~ ~ ~ 4 A A-21 ~ ~ ~ ~, 4 B B-18 ~ ~ ~

C-1 ~ ~ ~ ~

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4

1.0 INTRODUCTION

The Off-Site Dose Calculation Manual (ODCM) provides the information and methodologies to be used by Shearon Harris Nuclear Power Plant (SHNPP) to ensure compliance with Technical Specifications 3.3.3.10, 3.3.3.11, 3/4.11.1, 3/4.11.2, 3/4.11.4, 4.12.1, 4.12.2, 4.12.3, and 6.9.1 of the SHNPP Operating License. These specifications are those related to normal liquid and gaseous radiological effluents, environmental monitoring, and reporting. They are intended to show compliance with 10CFR20-based requirements and 10CFR50.36a, Appendix I of 10CFR50, and 40CFR190 in terms of appropriate moni.toring instrumentation and set points, dose rate, and cumulative dose limitations. Off-site dose estimates from non-routine releases will also be included in the cumulative dose estimates for the plant to comply wi,th Appendix I of 10CFR50.

The ODCM is based on "Westinghouse Standard Technical Specifications" (NUREG 0452), "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 the SHNPP Plant Operating Manual. These procedures are utilized by the operating staff of SHNPP to ensure compliance with technical specifications.

The ODCM has been prepared as generically as possible in order to minimize the need for future revisions. However, some changes to the ODCM are expected in the future. Any such changes will be properly reviewed and approved as indicated in Administrative Controls Section 6.14 of the SHNPP Technical Specifications.

The assessment of annual radiation doses to members of the public from radioactive liquid and gaseous effluents from the plant is estimated using the NRC codes LADTAP II and CASPAR using concurrent meteorology for the report period. These off-site dose estimates for each calendar year are reported in the Radioactive Effluent Release Report required by Technical Specification 6.9.1.4.

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.0 LI UID EFFLUENTS Radioactive materials released in liquid effluents from SHNPP to unrestricted areas are required to demonstrate compliance with 10 CFR 50 Appendix I (Technical Specification 3.11.1.2) and, on an annual average )

basis, be limited to the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases I the concentration shall be limited to 2E-4 pCi/ml total activity. On an individual release basis, the release concentration for liquid effluents will be limited to ten times (10x) the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 (Technical Specification 3.11.1.1). The liquid effluent release point is at the point of discharge from the Cooling Tower Blowdown Line into Harris Lake (see Figure 2.1-3 and T/S Figure 5.1-3).

Figure 2.1-1, Liquid Waste Processing Flow Diagram, and Figure 2.1-2 Liquid Effluent Flow Stream Diagram, show how effluents are processed and where they are released.

Effluent monitor identification numbers 'are provid'ed in Appendix C.

Liquid effluent dilution prior to release to Harris Lake is provided by the Cooling Tower Blowdown Line. Concurrent batch releases shall not occur at SHNPP.

The SWST and the Normal Service Water (NSW) system have a low potential for radioactive effluent releases. These releases are checked by effluent monitors on the SWST (Figure 2.1-2) and the NSW lines (Figure 2.1-3).

The Turbine Building floor drains and the outside tank area drains (Figure 2.1-4) are monitored effluent lines with low probability of radioactive contamination.

The radioactive liquid waste sampling and analysis required for batch and continuous releases are found in Table 4.11-1 of the Technical Specifications.

The SHNPP ODCM uses the Canberra, Inc., Effluent Management System (EMS) software for automating the necessary calculations and record keeping.

As such, the ODCM is written with the following parameters set in the EMS:

The SET OPT option is set to NO WASTE The SETP EQN option is set to STD 2-1

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.1 Com lienee with 10 CFR 20 10, CFR 20.1301 requires that the total effective dose equivalent to individual members of the public will not exceed 0.1 rem (100 mrem) in a year.

10 CFR 20.1302 states that a licensee can show compliance with the annual dose limit of 20.1301 by demonstrating that the annual average concentration of radioactive material released in liquid effluents at the boundary of the unrestricted area does not exceed the values specified in 10 CFR 20, Appendix B, Table 2, Column 2.

Technical Specification 3.11.1.1 says that, on an individual release basis, the concentration of radioactive material released in liquid effluents to unrestricted area shall be limited to 10 times the values specified in 10 CFR 20, Appendix B, Table 2, Column 2.

Technical Specification 3.3 '0 requires that radioactive effluent instrumentation have alarm/trip setpoints that will ensure that an alarm/trip will occur prior to exceeding {10 times) the limits of Technical Specification 3.11.1.1". for principal gamma emitters.

effluent monitors have two setpoints, the high alarm and the

'iquid alert alarm. The high alarm setpoint, S~~, provides alarm and isolation if the radionuclide concentrations, when diluted, would approach the Technical Specification limits for concentrations in unrestricted areas. Alert alarm setpoints, S,>~, are set at a fraction of the S~~ to provide an early warning of the approach to Technical Specification limits.

2-2

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.1.1 Batch Releases Radioactive liquids are routinely released as batches from the Waste Evaporator Condensate Tank (WECT) and Treated Laundry and Hot Shower Tank (TL&HST). Batch releases may also originate from the Secondary Waste Sample Tank (SWST) and Waste Monitor Tank (WMT). These tanks are shown in Figures 2.1-1 and 2.1-2. Based on analysis of the tank contents, the tank release rate is adjusted, based on the Cooling Tower Blowdown Line flow rate, to dilute the tank activities to 50 percent of the allowable concentrations at the release point to Harris Lake.

The ODCM software calculates a nuclide specific response setpoint which is based on the sum of responses for each nuclide. The nuclide specific response setpoint equates all gamma-emitting nuclides to Cs-137, to which the monitor is calibrated.

If analysis of the batch sample indicates all gamma-emitting nuclides are ( LLD, (as defined in Technical Specification Table 4.11-1), the tank gamma activity, Cz, may be assumed to consist only of Cs-134. This nuclide has the lowest Effluent Concentration Limit (ECL) of any to be fou'nd in liquid effluents and provides a conservative basis for a

'onitor setpoint.

2-3

i Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.1.1 Batch Releases (continued)

1. Minimum Tank Mixing Time Footnote 2 to Technical Specification Table 4.11-1 requires that the method used to mix an isolated effluent tank prior to sampling and analysis be described.

Equation 2.1-1 below provides an acceptable method for ensuring a well mixed tank so that a representative sample can be taken for radioactivity or other appropriate analyses.

R (V) (E) (n) (2.1-1)

(RR) (60) where:

Minimum allowable mixing time, hr Actual tank liquid volume, gal E Eductor factor RR - Pump design recirculation flow rate, gpm Number of tank volumes for turnover; this will be typically two or more.

60 - 60 min/hr Table 2.1-1 lists the tank capacities, eductor factors, and pump design recirculation flow rates for individual liquid effluent release tanks.

2-4

pi Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.1.1'atch Releases (continued)

2. Required Dilution Factor Technical Specification 3.11.1.1 requires that the sum of concentrations divided by ECL values must not exceed 10 for an individual release. Therefore:

E~ Cg ECLAT s zo (2.1-2) where:

Cz the concentration of nuclide i to be released ECL< the Effluent Concentration Limit for nuclide i from 10CFR20, Appendix B, Table 2, Column 2.

If the summation is greater than 10; dilution is required. The total required dilution factor, Dzeq, is the minimum acceptable dilution factor required to meet the limits of Technical Specification 3.11.1.1, based on pre-release and composite analysis.'zeq Dzeq,g + Dzeq,ng (2.1-3) where:

Dzeq s Required dilution factor for gamma-emitters Cg ECL~

(2.1-4) 2-5

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Hanual (ODCM) Rev. 4 2.1.1 Batch Releases (continued)

Dred,ag Required dilution factor for non-gamma-emitters c,

and f ~ R f ~

~

f - 0.5 A safety factor to assure that the nuclide concentrations are 50% of the Technical Specification limit at the point of discharge.

a value to take into account that tritium is potentially being released via the settling basin discharge to the cooling tower discharge line. This value is normally'et.'t'o 1E-03, which is the H-3 ECL.

The maximum ECL ratio for the release point (normally set to 10).

The sums include gamma-emitters (g) and non-gamma-emitters (ng),

respectively.

The measured concentration of each gamma-emitting nuclide, including noble gases, is reported in pCi/ml. If no gamma activity is detectable then an activity of 9E-07 pCi/ml of Cs-134 is assumed for setpoint calculations. The measured concentration of non-gamma emitters is determined by analysis of the liquid effluent or previous composite sample, and is reported in pCi/ml.

2-6

0 Et 0

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.1.1 Batch Releases (continued)

3. Maximum Waste Flow For liquid releases, the maximum permissible waste flow rate for this release, W is the minimum of R, ~ and R where Rcwmax Favail fel lee (2.1-6)

Liquid effluent tank maximum waste flow rate, as specified in Table 2.1-1. This value is the same as Fwaste and Favai1 The available dilution flow is the minimum dilution stream flow (Cooling Tower Blowdown) that can be ensured for the period of the release. Since only one batch release occurs at a time out of a single discharge point, the flow is not corrected for other releases in progress, for any activity in the dilution stream, or reduced by a safety factor. The minimum dilution flow rate for each setting is shown in Table 2.1-2.

falloc Fraction of the available dilution volume which may be assigned to a particular release to ensure discharge point limits are not exceeded by simultaneous radioactive liquid releases. The value of F,lice is based on assumed operational considerations for simultaneous releases but normally will be 0.8 for a batch release and 0.2 for a continuous release.

Minimum Dilution Flow Rate The Minimum Dilution Flow Rate (min dflow) is the minimum Cooling Tower discharge flow necessary to dilute the release to less than Technical Specification Limits.

If Dse S 1, the minimum dilution flow rate is set to 0.0. If

> 1, t%e minimum dilution flow rate is determined as follows: D<

F D min dflow L (2.1-7) falice.,

where F<<s<< - waste flow anticipated for this release 2-7

Cl Shearon Harris Nuclear power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.1.1 Batch Releases (continued)

5. Setpoint Calculations The ODCM software calculates a nuclide specific response setpoint, which is based on the sum of responses for each nuclide. The setpoint equates all gamma-emitting nuclides to Cs-137, to which the monitor is calibrated. The setpoint is listed in terms of Cs-equiv and the units are pCi/ml.

If analysis of the batch sample indicates all gamma-emitting nuclides are ( LLD, (as defined in Technical Specification Table 4.11-1), the tank gamma activity, Cz, may be assumed to consist only of Cs-134. This nuclide has the lowest ECL of any to be found in liquid effluents and provides a conservative basis for a monitor setpoint, (1) Maximum setpoint value, based on Nuclide Specific Response S ~ (Cs-equiv)- <Sad) 'on>' B (2.1-8) where S,~ Setpoint adjustment factor.

falloc Favai1 (2.1-9)

F~see 'z~

S,~ should always be greater than 1 to ensure that adequate dilution flow is available for the release.

B - monitor background (pCi/ml) 2-8

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.1.1 Batch Releases (continued)

R Z slope<

C<

where the sum extends over all nuclides which have response factors stored in the database for the monitor of interest and slope< the Liquid Effluent Monitor Gamma Sensitivities (from Table 2.1-4) for nuclide i, relative to Cs-137. To make nuclide i relative to Cs-137, the nuclide sensitivity is divided by the Cs-137 sensitivity.

Sensitivit nuclide i Cs-137 Sensitivity (2) Monitor alert alarm setpoint, S,le<< (Cs-equiv)

An Alert Alarm setpoint is calculated to provide an operator with adequate warning that the high alarm setpoint is being approached. S,lt is calculated from the nuclide specific response setpoint.

Sale<< [ (s~- B) x) where:

F A value <1.0 designed to provide an operator with adequate warning that the high alarm setpoint is being approached.

2-9

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.1.1 Batch Releases (continued)

(3) Check for Excessive Monitor Background In order to differentiate between the S,z< and the statistical fluctuations associated with a high monitor background, a check for excessive monitor background is made. As a check, verify that the minimum detectable concentration (MDC) for the monitor is less than 0.1 of the net S ~, ~'therefore, background is acceptable if:

MDC O.X((S - S) ~

F) (2.1-11) where:

(2.1-12) where:

Signal Processor Time constant, minutes.

(Table 2.1-3)

Bkg Background Count" Rate, in cpm B / E E Monitor efficiency for the Cs-137 gamma energy, cpm/pCi/ml determined by primary calibration.

If not, postpone the release and decontaminate or replace the sample chamber to reduce the background, then recalculate S and S,z~ using the new, lower background.

Post-Release Compliance After the release is made, actual concentrations are used to check 10 CFR 20 limits, and the actual dilution flow and waste flow are used instead of the anticipated dilution flow and waste flow.

For batch releases, the duration is determined from the start and end dates and times of the release. This is used with the actual release volume input to calculate the release rate.

2-10

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.1.2 Continuous Releases The continuous releases from the SWST and the NSW return lines are monitored as shown in Figures 2.1-2 and 2.1-3. The function of these monitors, in contrast to the isolation function of batch release tank monitors, is to provide an indication of low levels of radioactivity in the effluent. The continuous effluent monitor setpoint is based on an assumed FSAR nuclide mix for the SWST (from Table 11.2.1-5 of the FSAR).

The EMS software does not calculate continuous release monitor setpoints.

1. Monitor High Alarm Setpoint, S~~ (pCi/ml).

0.1 (ECL,fz Sens,zf

~

) + B (2.1-13)

Sam where:

ECL'e ff Weighted EC for'the SWST nuclides listed in Table 11.2.1-5 of the FSAR.

Sens,~z g~ (Sens i x 0 abundance) for the SWST nuclide mix, cpm/pCi/ml.

2. Monitor Alert Alarm Setpoint, S,z~ (Cs-equiv)

[ (S B) ~

F) B Sale?t When the monitor is operable and not in alarm, analysis of weekly composite samples is not required by Technical Specification Table 4.11-1.

If the monitor is in alarm or t'e presence of non-naturally occurring radioactivity > effluent LLD is confirmed, the releases I may continue provided the sampling and analysis required by Technical Specification Table 4.11-1 are performed. The results of the sample analysis wi.ll be evaluated for compliance with Technical Specification 3.11.1.1.

The monitor alarm setpoints may be recalculated using the methodology is Section 2.1.1 with the results of the gamma

, analysis and analyses of the composite sample.

3. Check for Excessive Monitor Background Monitor background is considered excessive when the minimum detectable concentration (MDC) for the monitor is >0.01 ECL,ff.

Therefore, background is acceptable if:

MDC 0 '1 ( ECLetf 'ENSetf ) (2.1-15) 2-11

Shearon Harris Nuclear Power Plant (SHNPP) i June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.1.3 Other Li uid Releases

1. Outdoor Tank Area Drain Effluent Line The outdoor tank area drain effluent line routes rain water collected in the outdoor tank area to the storm drain system and from there directly to the lake. The line is monitored for radioactivity and is capable of automatic termination of effluent release. Because no radioactivity is normally expected in this line, the monitor high alarm and alert alarm setpoints are determined using the methodology is Section 2.1.2. If the setpoint is exceeded, the release to the storm drains is terminated. Effluent can then be diverted to the floor drain system for processing and eventual release (see Figures 2.1-1 and 2.1-2).

2. Turbine Building Floor Drains Effluent Line Water collected in the turbine building floor drains is normally routed to the yard oil separator for'elease to the environment via the waste neutralization system and then to the cooling tower discharge line. Tritium is expected to be detected in this pathway from sources such as background from the lake. Tritium I activity will be administratively controlled to limit the activity at the release point. Because no other radioactivity is normally expected in this path, the setpoints for the turbine building drain monitor are determined using the methodology is Section 2.1.2. Should the setpoint be exceeded, the release is automatically terminated. Effluent can then be diverted to the secondary waste treatment system for processing and eventual release (see Figures 2.1-1 and 2.1-2).

2-12

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.2 Com liance with 10 CFR 50 A endix I 2.2.1 Cumulation of Doses The dose contribution from each release of liquid effluents will be calculated and a cumulative summation of the total body and each organ dose will be maintained for each 31 days (monthly), each calendar quarter, and the year.

The EMS software calculates and stores the dose for the critical receptor (site boundary), for each nuclide, and for each organ. The dose is the total over all pathways which apply to that receptor. A receptor is defined by receptor ID, age group (infant, child, teen, or adult), sector, and distance from the plant.

The dose contribution for batch releases and all defined periods of continuous release received by receptor "r" from a released nuclide "i" will be calculated using the following equation'.

Dirr AirrAts <is Frs (2.2-1) where:

Dirr the cumulative dose or dose commitment to the total body or an organ "r" by nuclide "i" for receptor "r" from the liquid effluents for the total time period of the release, in mrem.

Airr site-related ingestion dose or dose commitment factor for receptor "r" to the total body or organ "r" for nuclide "i",

in mrem/hr per pCi/ml.

hts length of time period 's', over which the concentration and F value are averaged, for all liquid releases, in hours.

Cis the average concentration of nuclide "i" in undiluted liquid effluent during time period ~t, from any liquid release, in pCi/ml.

Frs the near field average dilution factor for receptor "r" during any liquid effluent release.

2-13

ll,l I

k 1

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.2.1 Cumulation of Doses (continued)

Where:

Fvaste Fss 'mix (2.2-2)

Fvaste + Fayat1 and mixing ratio fraction of the release that reaches the receptor. At the SHNPP, this value is set to l.

Also, the sum extends over all time periods 's'.

In the case of a continuous secondary waste sample tank radioactive release, Cz the concentration of nuclide "i" in the SWST composite sample. For the NSW, Cz - concentration'f nuclide "i" in the cooling tower basin and F<<ste - discharge from the cooling tower basin while Faa~1 the flow from t'e makeup water cross-tie. For a release through the Turbine Building Floor Drain Line to the waste neutralization system, C< - the Turbine Building floor drain sample activity, Fv<< discharge from the Turbine Building floor drain line, and Faye f ] the average f1 ow during the period of the total Coo 1 ing Tower discharge. The total Cooling Tower discharge is the sum of the Cooling Tower Blowdown flow and the Cooling Tower Bypass Line flow.

When there is a primary-to-secondary leak, the change in concentration of tritium in the steam generators times the secondary loses (balance of plant), will be used for effluent accountability. The secondary loss rate will also be used for volume accountability.

The dose factor A~r (see NUREG-0133, Section 4.3.1) was calculated for an adult for each isotope'"i" using the following equation:

Agr 1 ~ 4E+05 (

Dv

+ 21BF<) DF (2.2-3) where:

Air The ingestion dose commitment factor to the whole body or any organ vrv for an adult for each nuclide "i".

Corresponding to fish consumption from the Harris Lake (dilution - 1) and drinking water from Lillington (dilution - 13.95).

Values for the adult total body and organs in mrem/hr per pCi/ml are given in Table 2.2-1.

2-14

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.2.1 Cumulation of Doses (continued) 1.14E+05 - Units Conversion Factor 10'Ci 1 pCi

. 1000 1

ml liest

. ~1t 8760 hzs (2.2-4) 21 - Adult fish consumption rate (from Table E-5 of Regulatory Guide 1.109, Rev. 1), kg/yr; 730 - Adult water consumption rate (from Table E-5 of Regulatory, Guide 1.109, Rev. 1), liters/yr.

Dilution factor for the drinking water pathway 13.95 BFq Bioaccumulation factor for nuclide "i" in fish (from Table A-1 of Regulatory Guide.'1.109, Rev. 1), pCi/kg per pCi/1 DFig Dose conversion factor for nuc 1 ide "i" for adul ts for a particular organ r (from Table E-ll of Regulatory Guide 1.109, Rev. 1), mrem/pCi Ai - Radiological decay constant of nuclide "i," hr 0.693 (tN)g (th)< - ~ Radiological half-life of nuclide "i," hr; t - Average transport time to reach point of exposure, hr; 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The more limiting decay time for the drinking water and fish exposure pathways (Reg. Guide 1.109, Appendix A, Rev. 1).

Ta/le 2.2-1 presents the A~, values for an adult receptor. Values of e ~ > are presented in Table 2.1-4 for each nuclide i.

2.2.2 Com arison A ainst Limits The sum'f the cumulative dose from all batch and any continuous releases for a quarter is compared to one-half the design objectives for total body and any organ. The sum of the cumulative doses from all releases for a calendar year is compared to the design objective doses.

The following relationships should hold for the SHNPP to show compliance with Technical Specification 3.11.1.2.

2-15

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev.

2.2.2 Com arison A ainst Limits (continued)

For the calendar quarter:

Di<< ~ 1.5 mrem total body (2.2-5) 5 mrem any organ (2.2-6)

For the calendar year:

Dier 3 mrem total body (2.2-7)

Disr 10 mrem any organ (2.2-8) where:

/zan Cumul ative tota 1 dose to any organ t or the to ta 1 body from all D

releases, mrem:

The quarterly .limits given above represent one-half the annual design os'ective of 10 CFR 50, Appendix I, Section II.A. If any of the limits in equations (2.2-5) through, (2.2-8) are exceeded, a special report pursuant to SHNPP Technical Specification 6.9.2 must be filed with the NRC. This report complies with Section IV.A of Appendix I, 10 CFR 50.

The calculations described in Section 2.2.1 will be used to ensure compliance with the limits in 10 CFR 50 Appendix I on a "per-release" basis. The NRC approved program LADTAP II will be used to demonstrate compliance on an annual basis. While there are substantial differences between the ODCM methodology and the methodology in LADTAP, conservative factors have been chosen for the ODCM methodology which will ensure compliance with the limits of 10 CFR 50 Appendix I.

The SHNPP ODCM uses a "modified" NUREG 0133 equation with conservative assumptions. It calculates the dose to a single maximum (ALARA) individual. It does not calculate doses in a steady-state environment, nor does it calculate reconcentration factors. The ALARA individual is an individual that consumes fish caught in the Harris Lake (dilution of 1.0) and receives their drinking water from Lillington, North Carolina (dilution 13.95).

The SHNPP LADTAP II program uses the guidance of Reg Guide 1.109 and Reg Guide 1.113 to calculate the dose to a maximum individual in all age groups, downstream receptors, and integrated populations. It will calculate doses based on a steady-state environment using the completely-mixed model and reconcentration factors, as per Reg Guide 1.113, and will use average, rather than minimum values for the Cape Fear River flow.

2-16

S t

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.2.2 Com arison A ainst Limits (continued)

LADTAP Parameters are maintained in the Laboratory and Facility Services Section Instruction RC-ER-36, Operating Instruction for XOQDOQ, GASPARS, and LADTAP Computer Programs. Parameters subject to change on a periodic basis (flows, source terms, etc.) are not listed, but will be defined and described in the Radioactive Effluent Release Report for the period of interest.

2.2.3 Post-release Com liance With 10 CFR 50 - Based Technical S ecification After the release is made, actual concentrations are used to check 10CFR50 limits, and the actual dilution flow and waste flow are used instead of the anticipated dilution flow and waste flow.

For batch releases, the duration is determined from the actual start and end dates and times of the release. This is used with the actual volume input to calculate the release rate.

2:2.4 Pro ection of Doses Dose projections for this section are required at least once per 31 days (monthly) in Technical Specification 4.11.1.3.1 whenever the liquid radwaste treatment systems are not being fully utilized.

The doses will be calculated using Equation 2.2-1, and projected using the following expression:

Dpr ~ (D

p) + Dar where:

D~ - the 31 Day Projected Dose by organ r D, sum of all open release points in mrem/day by organ r.

p - the Projection Factor which is the result of 31 divided by the number of days from start of the quarter to the end of the release.

D - Additional Anticipated Dose for liquid releases by organ r and quarter of release.

NOTE: The 31 Day Projected Dose values appear on the Standard and Special Permit Reports. The 31 day dose projections on the Approval/Results screen include any additional dose.

Where possible, expected operational evolutions (i.e., outages, increased power levels, major planned liquid releases, etc.) should be accounted for in the dose projections. This may be accomplished by using the source-term data from similar historical operating experiences where practical, and adding t'e dose as Additional Anticipated Dose.

2-17

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.2.4 Pro ection of Doses (continued)

To show compliance with Technical Specification 3.11.1 ~ 3> the proj ected month's dose should be compared as in the following:

Dpz S 0 . 06 mrem for total body (2.3-2) and Dz, S 0.2 mrem for any organ (2.3-3)

If the projections exceed either Expressions 2.3-2 or 2.3-3, then the appropriate portions of the liquid radwaste treatment system shall be used to reduce releases of radioactivity.

2-18

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 2.1-1 LIQUID EFFLUENT RELEASE TANKS AND PUMPS '"

Tank

"'o. Tanks of PUMP DESIGN CAPACITY (gpm)

Discharge Recirculation Eductor Factor Tank Capacity Igall Radiation Effluent Monitor ID SWST ,1 00 100 0.2 25,000 REM-3542 WECT 35 100 1.0 10,000 REM-3541 100 100 0.25 25,000 REM-3542 WMT'3'L8(HS 35 100 0.25 25,000 REM-3540 The settling basin has two pumps. When one pump is running, the design flow rate is 500 gpm. When both pumps are running, the design flow rate is 800 gpm.

Reference SHNPP FSAR Tables 11.5.1-1 and 11.2.1-7 SWST: Secondary Waste Sample Tank WECT: Waste Evaporator Condensate Tank WMT: Waste Monitor Tank TL&HS: Treated Laundry and Hot Shower Tank Waste Monitor Tank are used to batch release secondary waste effluent when activity is suspected in this pathway.

2-19

~ ~

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 2.1-2 Setpoints for Cooling Tower Blowdown Dilution Flow Rates (F,)

Setting Trip Flow Rate (gpm) Minimum Dilution Flow Rate (gpm) 4ppp 2 5 3,800 7,000 a 5% 6,650 11 000 ~ 5% 10,450 15 000 ~ 5% 14,250 TABLE 2.1-3 Signal Processor Time Constants (r) for GA Technologies RD-53 Liquid Effluent Monitors

. Detector Background (cpm) r (min) 10' 10 10 10' 103 10s/cpm bkg 10s - 104 10'/cpm bkg 10' 10s 10'/cpm bkg 10s 10e 0.01 10e - 107 0.01 2-20

1 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 2.1-4 Page 1 of 3 Nuclide Parameters Half-Life Sensitivity Nuclide ~hour e ~hr 1- e-At ~cm ~Ci~ml ~Slo e H-3 6.46E+06 1.07E-07 1.00E+00 O.OOE+00 O.OOE+00 C-14 3.01E+09 2.30E-10 1.00E+00 O.OOE+00 O.OOE+00 F-18 1.10E+02 6.32E-03 9 '7E-Ol O.OOE+00 O.OOE+00 Na-24 9.00E+02 7.70E-04 9. 91E-01 9.36E+07 9.00E-01 P-32 2.06E+04 3.36E-05 1.00E+00 O.OOE+00 O.OOE+00 Cr-51 3.99E+04 1.74E-05 1.00E+00 1.61E+07 1.55E-01 Mn-54 4.50E+05 1.54E-06 1.00E+00 1.03E+08 9.90E-01 Mn-56 1.55E+02 4.47E-03 9.48E-01 1.01E+08 9.71E-01 Fe-55 1.42E+06 4.88E-07 1.00E+00 O.OOE+00 O.OOE+00 Fe-59 6.43E+04 1.08E-05 1.00E+00 1.26E+08 1.21E+00 Co-57 3.90E+05 1.78E-06 1,00E+00 0.00E+00 0.00E+00

'o-58 1.02E+05 6.80E-06 1.00E+00 1.46E+08 1.40E+00 Co-60 2,.77E+06 2.50E-07 1.00E+00 1.89E+08 1.82E+00 Ni-63 5.27E+07 1.32E-08. 1.00E+00 O.OOE+00 O.OOE+00 Ni-65 1.51E+02 4.59E-03 9.46E-Ol 2 '4E+07 2.15E-01 C0-64 7.62E+02 9.10E-04 9.89E-01 5.16E+07 4.96E-01 Zn-65 3.52E+05 1.97E-06 1.00E+00 5.24E+07 5.04E-01 Zn-69 5.56E+01 1.25E-02 8.61E-01 2.22E+03 2.13E-05 Zn-69m 8.26E+02 8 '9E-04 9.90E-01 0 OOE+00

~ O.OOE+00 Br-82 2.12E+03 3.27E-04 9.96E-01 O.OOE+00 O.OOE+00 Br-83 1.43E+02 4.85E-03 9.43E-01 1.95E+06 1.88E-02 Br-84 3.18E+01 2.18E-02 7 '0E-01 6.50E+07 6.25E-01 Br-85 2.87E+00 2.42E-01 5.51E-02 6.76E+06 6.50E-02 Rb-86 2.69E+04 2.58E-05 1.00E+00 8.39E+06 8.07E-02 Rb-88 1.78E+01 3.89E-02 6.27E-01 1.45E+07 1.39E-01 Rb-89 1.54E+01 4.50E-02 5.83E-01 1.22E+08 1.17E+00 Sr-89 7.28E+04 9.52E-06 1.00E+00 1.46E+04 1.40E-04 Sr-90 1.50E+07 4.62E-OS 1.00E+00 O.OOE+00 O.OOE+00 Sr-91 5.70E+02 1.22E-03 9.86E-01 8.16E+07 7.85E-01 Sr-92 1.63E+02 4.25E-03 9.50E-01 1.01E+08 9.71E-01 Y-90 3.85E+03 1.80E-04 9.98E-01 O.OOE+00 O.OOE+00 Y-91 8.43E+Q4 8.22E-06 1.00E+00 2.83E+05 2.72E-03 Y-91m 4.97E+01 1.39E-02 8.46E-01 1.28E+08 1.23E+00 Y-92 2.12E+02 3.27E-03 9.62E-01 2.76E+07 2.65E-01 Y-93 6.06E+02 1.14E-03 9.86E-01 1.37E+07 1.32E-01 Zr-95 9.22E+04 7.52E-06 1.00E+00 1.07E+08 1.03E+00 Zr-97 1.01E+03 6.86E-04 9.92E-01 2,68E+07 2.58E-01 Nb-95 5.05E+04 1.37E-05 1.00E+00 1,06E+08 1.02E+00 Nb-97 7.21E+01 9.61E-03 8.91E-01 O,OOE+00 O.OOE+00 Mo-99 3.96E+03 1.75E-04 9.98E-01 3.47E+07 3.34E-01 Tc-99m 3.61E+02 1.92E-03 9.77E-01 1,11E+08 1 ~ 07E+00 2-21

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 2.1-4 Page 2 of 3 Nuclide Parameters (continued)

Half-Life At Sensitivity Nuclide ~hours ~hr-1 e-At ~c)~m~sC i ~ml ~Slo e Tc-101 1.42E+01 4.88E-02 5.57E-01 1.66E+08 1.60E+00 RQ-103 5.67E+04 1.22E-05 1.00E+00 1.38E+08 1.33E+00 RU-105 2.66E+02 2.61E-03 9.69E-Ol 1.71E+08 1.64E+00 Ru-106 5.30E+05 1.31E-06 1.00E+00 4.52E+07 4.35E-01 Ag-110m 3.60E+05 1.93E-06 1.00E+00 3.22E+08 3.10E+00 Sn-113 2.76E+03 2.51E-04 9.97E-01 3.08E+06 2.96E-02 Sb-124 8.67E+04 7.99E-06 1.00E+00 1.59E+08 1.53E+00 Sb-125 1.46E+06 4.75E-07 1.00E+00 1.21E+08 1.16E+00 Te-125m 8.35E+04 8.30E-06 1.00E+00 3.00E+05 2.88E-03 Te-127m 1.57E+05 4.41E-06 1.00E+00 1.33E+04 1.28E-04 Te-127 5.61E+02 1.24E-03 9.85E-01 1.97E+06 1.89E-02

'Te-129m 4.84E+04 1.43E-05 ~ 1".OOE+00 5.17E+06 4.97E-02 Te-129 6, 96E+01 9.96E-03 8.87E-01 1.58E+07 1.52E-01 Te-131m 1.80E+03 3.85E-04, 9.95E-01 2.17E+08 2.09E+00 Te-131 2.50E+01 2.77E-02 7.17E-01 1.50E+08 1.44E+00 Te-132 4.69E+03 1.48E-04 9.98E-01 1.39E+08 1.34E+00 I-130 7.42E+02 9.34E-04 9.89E-01 4.13E+08 3.97E+00 I-131 1.16E+04 5.98E-05 9.99E-01 1.55E+08 1.49E+00 I-132 1.38E+02 5.02E-03 9,42E-01 3.31E+08 3.18E+00 I-133 1.25E+03 5.55E-04 9.93E-01 1.39E+08 1.34E+00 I-134 5.26E+01 1.32E-02 8.54E-01 3.08E+08 2.96E+00 I-135 3.97E+02 1.75E-03 9.79E-01 1.03E+08 9.90E-01 Cs-134 1.08E+06 6.42E-07 1.00E+00 2.60E+08 2.50E+00 Cs-136 1.90E+04 3.65E-05 1 OOE+00

~ 3.37E+08 3.24E+00 Cs-137 1.59E+07 4.36E-08 1.00E+00 1.04E+08 1.00E+00 Cs-138 3.22E+01 2.15E-02 7.72E-01 1.15E+08 1.11E+00 Ba-139 8.31E+Ol 8.34E-03 9.05E-01 2.34E+07 2.25E-01 Ba-140 1.84E+04 3.77E-05 1.00E+00 6.01E+07 5.78E-01 Ba-141 1.83E+01 3,.79E-02 6.35E-01 2.53E+08 2.43E+00 Ba-142 1.07E+Ol 6.48E-02 4.60E-01 1.47E+08 1.41E+00 La-140 2.41E+03 2.88E-04 9.97E-01 1.53E+08 1.47E+00 La-142 9.54E+01 7.27E-03 9.17E-01 9.59E+07 9.22E-01 Ce-141 4.68E+04 1.48E-05 1.00E+00 6.11E+07 5.88E-01 Ce-143 1.98E+03 3.50E-04 9.96E-01 9.60E+07 9.23E-01 Ce-144 4 '9E+05 1.69E-06 1.00E+00 1.30E+07 1.25E-01 Pr-143 1.95E+04 3.55E-05 1.00E+00 1.08E+02 1.04E-06 Pr-144 1 ~ 73E+01 4.01E-02 6.18E-01 1.68E+06 1.62E-02 Nd-147 1 ~ 58E+04 4.39E-05 9.99E-01 2.86E+07 2.75E-01 Hf-181 1.02E+03 6.81E-04 '.92E-01 2.08E+08 2.00E+00 W-187 1.4SE+03 4.85E-04 9.94E-01 1.04E+08 1.00E+00 Np-239 3.39E+03 2.04E-04 9.98E-01 1.13E+08 1.09E+00 2-22

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 2.1-4 page 3 of 3 Nuclide Parameters (continued)

Half-Life Sensitivity Nuclide ~hours e-At ~cm sCi ~ml ~Slo e Ar-41 1.10E+02 6.30E-03 9.27E-01 9.28E+07 8.92E-01 Kr-83m 1.10E+02 6.30E-03 9.27E-01 O.OOE+00 O.OOE+00 Kr-85 5.64E+06 1.23E-07 1.00E+00 6.20E+05 5.96E-03 Kr-85m 2.69E+02 2.58E-03 9.70E-01 1.20E+08 1.15E+00 Kr-87 7.63E+01 9.08E-03 8.97E-01 9.19E+07 8.84E-Ol Kr-88 1.70E+02 4.08E-03 9.52E-01 7.49E+07 7.20E-01 Kr-89 3.16E+00 2.19E-01 7.19E-02 1.39E+08 1.34E+00 Kr-90 5.39E-01 1.29E+00 1 ~ 99E-07 1.59E+08 1.53E+00 Xe-131m 1.70E+04 4.08E-05 1.00E+00 2.62E+06 2.52E-02 Xe-133 7.55E+03 9.18E-05 9.99E-01 9.90E+04 9.52E-04 Xe-133m 3.15E+03 2.20E-04 9.97E-01 1.59E+07 1.53E-01 Xe-135 5.47E+02 1.27E-03 . 9;85E-'01 1.47E+08 1.41E+00 Xe-135m 1,54E+01 4.50E-02 5.83E-01 1.14E+08 1.10E+00 Xe-137 3.83E+00 1.81E-01. 1.14E-01 4.85E+07 4.66E-01 Xe-138 1.41E+Ol 4.92E-02 5.54E-01 1.20E+08 1.15E+00 G-ALPHA 1.00E+05 6.93E-06 1.00E+00 O.OOE+00 O.OOE+00 G-BETA 1.00E+09 6.93E-10 1.00E+00, O.OOE+00 O.OOE+00 OTHER 1.00E+09 6.93E-10 1.00E+00 0 '0E+00 O.OOE+00 Notes to Table 2.1-4 SENSITIVITY 80% of weighted response to 100 - 1400 keV gammas for GA RD-53 offline sodium iodide (NaI) detector (reference GA Manual E-115-904, June 1980).

Abundances for each gamma from "Radioactive Decay Tables" by David C. Kocher (Report DOE/TIC-11026, Washington, D.C., 1981)

SLOPE The Liquid Effluent Monitor Gamma Sensitivities for nuclide i, relative to Cs-137. To make nuclide relative to Cs-137, the nuclide sensitivity is i

divided by the Cs-137 sensitivity.

2-23

Cl Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Sheet 1 of 2 TABLE 2.2-1 AgT UALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT AlT,K,P 1'148+05 ( + 21BFZ) DFg '

V (mrem/hr per pCi/ml)

Nuclide Bone Liver ~T. Bod ~Th roid ~Kidne ~Lnn Gl-LLI H-3 O.OOE+00 8.54E-01 8.54E-01 8. 54E-01 8. 54E-01 8.54E-01 8.54E-01 C-14 3. 13E+04 6.27E+03 6.27E+03 6.27K+03 6.27Et03 6.27E+03 6.27E+03 NA-24 2.40E+02 2.40E+02 2.40K+02 2.40K+02 2.40E+02 2.40K+02 2.40K+02 P-32 4.52E+07 2.81E+06 1.75Et06 O.OOE+00 O.OOE+00 O.OOE+00 5.08E+06 CR-51 O.OOE+00 O.OOE+00 1.28E+00 7. 63E-01 2.81E-01 1.69E+00 3.21K+02 HN-54 O.OOE+00 4. 41Et03 8.41Et02 O.OOE+00 l. 31Et03 O.OOE+00 1.35E+04 HN"56 O.OOE+00 4.44E+00 7.87E-01 O.OOE+00 5.63K+00 O.OOE+00 1.42E+02

. FE-55 6.76E+02 4.67Et02 1.09E+02 O,OOEt00 O.OOE+00 2.60K+02 2.68E+02 FE-59 . 1.06E+03 2.49E+03 9.54E+02 O.OOE+00 O.OOE+00 6.95K+02 8.29E+03 CO-57 O.OOE+00 2.20E+01 3.66E+01 O.OOE+00 O.OOE+00 O.OOE+00 5.58E+02 CD58 O.OOEt00 9.33K+01 2.09Et'02 O.OOE+00 O.OOE+00 O.OOE+00 1.89E+03 CO-60 O.OOE+00 2.69K+02 5.94E+02 O.OOE+00 O.OOE+00 O.OOE+00 5.06E+03 I

NI-63 3.20K+04 2.21E+03 1.07E+03 O.OOE+00 O.OOE+00 O.OOE+00 4.62E+02 NI-65 4.76K+00 6. 19E-01 2.82E-01 O.OOE+00 O.OOE+00 O.OOE+00 1. 57K+01 CU-64 O.OOE+00 5.45E+00 2.56K+00 O.OOE+00 1.37E+01 O.OOE+00 4.64E+02 ZN-65 2.32E+04 7.39E+04 3.34K+04 O.OOE+00 4.94E+04 O.OOE+00 4.65E+04 ZN-69 6.25E-03 1.20E-02 8.32E-04 O.OOE+00 7.77E-03 O.OOE+00 1.80E-03 ZN-69H 4.46E+02 1.07K+03 9.79E+01 O.OOE+00 6.48E+02 O.OOE+00 6.54K+04 BR-82 O.OOE+00 O.OOE+00 1.81E+03 O.OOE+00 O.OOE+00 O.OOE+00 2.07K+03 BR-83 O.OOE+00 O.OOE+00 1.24K+00 O.OOE+00 O.OOE+00 O.OOE+00 1.79E+00 BR-84 O.OOE+00, O.OOE+00 8.07E-06 O.OOE+00 O.OOE+00 O.OOE+00 6.33E-11 BR-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 RB-86 O.OOE+00 9.95E+04 4.63E+04 O.OOE+00 O.OOE+00 O.OOE+00 1.96E+04 RB-88 O.OOE+00 1.94E-10 1.03E-10 O.OOE+00 O.OOE+00 O.OOE+00 2. 67E-21 RB"89 O.OOE+00 1.62E-12 1. 14E-12 O.OOE+00 O.OOE+00 O.OOE+00 9.43E-26 SR-89 2.3SE+04 O.OOE+00 r6.84Et02 O.OOE+00 O.OOE+00 O.OOEt00 3.82E+03 SR-90 5.91E+05 O.OOE+00 1.45E+05 O.OOE+00 O.OOE+00 O.OOE+00 1.71E+04 SR-91 1.S4E+02 O.OOE+00 7.43K+00 O.OOE+00 O.OOE+00 O.OOE+00 8.77E+02 SR-92 7.84E+00 O.OOE+00 3. 39E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.55E+02 Y-90 5. 57E-01 O.OOE+00 1.49E-02 O.OOE+00 O.OOE+00 O.OOE+00 5.91E+03 Y-91H 2.61E-07 O.OOE+00 1.01E-OS O.OOE+00 O.OOE+00 O.OOE+00 7.67E-07 Y-91 9.24E+00 O.OOE+00 2. 47E-01 O.OOE+00 O.OOE+00 O.OOE+00 5.09E+03 Y-92 5.29E-03 O.OOE+00 1.55E-04 O.OOE+00 O.OOE+00 O.OOE+00 9.27K+01 Y-93 7.75E-02 O.OOE+00 2.14E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.46E+03 ZR-95 4.20E-Ol 1. 35E-01 9.12E-02 O.OOE+00 2. 11E-01 O.OOE+00 4.27Et02 ZR-97 1.42E-02 2.87E-03 1.31E-03 O.OOE+00 4.34E-03 O.OOE+00 8.90K+02 NB-95 4.43E+02 2.47K+02 1.33E+02 - O.OOE+00 2.44K+02 O.OOE+00 1.50E+06 NB-97 3.70E 9.36E-04 3.42E-04 O.OOE+00 1.09E-03 O.OOEt00 3.45Et00 HO-99 O.OOE+00 1. 14K+02 2.17K+01 O.OOE+00 2.58E+02 O.OOE+00 2.64E+02 TC-99H 2.60E-03 7.35E-03 9.36E-02 O.OOE+00 l. 12E-01 3.60E-03 4.35E+00 2-24

0 r

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Sheet 2 of 2 TABLE 2.2-1 (Continued)

Ag~ UALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT (mrem/hr per pCi/ml)

Nuclide Bone Liver ~T. Bod Typhoid ~Kid ne GI-LLI TC-101 5.81E-18 8.37E-18 8. 21E-17 O.OOE+00 1. 51E-16 4.28E-18 2.52E-29 RV-103 S.49E+00 O.OOE+00 2.37K+00 O.OOE+00 2.10K+01 O.OOE+00 6. 41E+02 RV-105 7.07E-02 O.OOE+00 2.79E-02 O.OOE+00 9. 13E-01 O.OOE+00 4.32E+01 RV-106 8.23E+01 O.OOE+00 1. 04Et01 O.OOE+00 1.59E+02 O.OOEt00 5.33E+03 hG-110M 9.55E-01 8. 83E-01 5. 25E-01 O.OOE+00 1.74E+00 O.OOE+00 3.60E+02 SB-124 2.33E+01 4. 40K-01 9.24E+00 5.65E-02 O.OOE+00 l. 82Et01 6.62E+02 SB-125 1.50K+01 1. 67E-01 3.57K+00 1.52E-OR O.OOE+00 1. 16E+01 1.6SE+02 TE-125H 2.57E+03 9. 32K+02 3.44K+02 7.73E+02 1.05E+04 O.OOE+00 1.03E+04 TE-127M 6.51K+03 R.33K+03 7.94K+02 1.66K+03 2.65E+04 O.OOE+00 2. 18K+04 TE-127 4.36E+0'1 1. 57E+01 9.44K+00 3.23Etol 1.78E+02 O.OOE+00 3.44E+03 TE-129M 1.10E+04 4. 10E+03 1.74Et03 3.77E+03 4.SSE+04 O.OOEt00 5.53K+04 TE-129 2.33E-02 8.76E-03 5.68E-03 1.79E-02 9.80E-02 O.OOE+00 1.76E-02 TE-131H 1.27K+03 6. 18E+02 5.16E+02 9.80K+02 6.27K+03 O.OOE+00 6. 14Et04 TE-131 4.07E-08 1.70E-08 1.28E-08 3.35E-08 1.78E-07 O.OOE+00 5.76E-09 TE-132 2. 19E+03 1.41Et03 1.33E+03 1.56E+03 1.36E+04 O.OOE+00 6.69K+04 Z-130 l. 62K+01 4.77K+01 l. 88E+01 4.05E+03 7.45K+01 O.OOE+00 4. 11Et01 Z-131 1.67E+02 2.39E+02 1.37E+02 7.84K+04 4.10E+02 O.OOE+00 6.31E+01 T-132 2.29E-01 6.12E-01 2.14E-01 2. 14Et01 9.75E-01 O.OOE+00 1.15E-01 Z-133 4. OOE+01 6.SSE+01 2.12K+01 1.02K+04 1.21K+02 O.OOE+00 6.25E+01 1-134 3.37E-04 9. 15E-04 3.27E-04 1.59E-02 1.46E-03 O.OOE+00 7.98E-07 T-135 5.29E+00 1.38E+01 5. 11E+00 9.13Et02 2.22K+01 O.OOE+00 1.56Et01 CS-134 2.SSE+05 7.10E+05 5.81E+05 O.OOE+00 2.30E+OS 7.63Et04 1.24E+04 CS-136 3.05K+04 1.20EtOS 8.6SE+04 O.OOE+00 6.69E+04 9.17K+03 1.37E+04 CS-137 3.8aE+Os 5.23E+05 a.43K+Os O.OOE+00 1.78E+05 5.S1E+04 1.01Et04 CS-138 4.82E 05 9.72E-OS 4.82E 05 O.OOE+00 7.14E-05 7.06E-06 4. 15E-10 Bh-139 3.72E 03 2.65E-06 1.09E 04 O.OOE+00 2.48E-06 1.50E-06 6.60E-03 Bh 140 3.08K+02 3.86E-01 2. 02E+01 O.OOE+00 1.31E-01 2. 21E-01 6.33E+02 Bh-141 1. OSE-12 7.94E-16 3.55E-14 O.OOE+00 7.38E-16 4. 51E-16 4.95E-22 Bh-142 1.84E 21 1.89E-24 1.16E 22 O.OOE+00 1.60E 24 1.07E-24 O.OOE+00 Lh-140 1.34E-01 6.75E-02 1.78E-02 O.OOE+00 O.OOE+00 O.OOE+00 4.96E+03 Lh-142 4.51E-05 2.05E-05 5. 11E-06 O.OOE+00 O.OOEt00 O.OOE+00 1. SOE-01 CE-141 7.76E-02 S.24E-02 5.95E-03 O.OOE+00 2.44E-02 O.OOE+00 2. 01K+02 CE-143 1.07E-02 7.94E+00 8.79E-04 O.OOE+00 3.50E-03 O.OOE+00 2.97E+02 CE-144 4.08K+00 1.71K+00 2. 19E-01 O.SOB+00 1.01Et00 O.OOE+00 1.38Et03 PR-143 5. 91E-01 2. 37E-01 2.93E-02 O.OOE+00 1. 37E-01 O.OOE+00 2.59E+03 PR-144 5.88E-16 2. 44E-16 2.99E-17 O.OOE+00 1. 38K-16 O.OOE+00 8.46E 23 ND 147 4.02E-01 4.64E-01 2.78E-OR O.OOE+00 2.71E-01 O.OOE+00 2.23E+03 H-187 2.10K+02 1.75E+02 6.12K+01 O.OOE+00 O.OOE+00 O.OOE+00 5.74K+04 NP-239 3.08E-02 3.03E-03 1.67E-03 O.OOE+00 9.44E-03 O.OQE+00 6. R1E+02 2-25

0HI crt 0'te IS rft o0 N Q)

IS ax 0

N IS O In 0I 0 g 0

Figure 2.1-$ VV Uquld Waste Processing Flow Diagram rt I

r0 8

F4 0 eeccerday Was'carce X OC Tecec ISIISTI 8

Iai a It O

Oaaeeey Seeece l laniyl Hce Shaeer H

oA M Terece 8

lasatyl 8'N Iee haer Teeke I rIUHstI F

g Tat QO flfKCI)

O cA tt) 0 Ol s>

Treated Laundry 8 Tank or Basin rt 0 Trealed Laundry tt Hot Shower Tank Hot Shower Tank Radiation Effluent Monitor C

0 Pump 0 I

n REM g

REM-1 WL4540 T Secondary Waste 0 Sample Tank W e

r B

I 0

W d

REM-21 WS 3542 0

W n

Waste Neutralization Basin Waste Monitor Waste Monitor Tank Tank Settling Basin Wasle Evaporator Waste Evaporator Condensate Tank Condensate Tank 'quids containing radioactive material other than tritium are not ~

permitted by procedure to REM-21 WL-3541 be sent to the Waste Harris Neutralization Basin. Lake REM r

ps r0 C C'

~ ~

I~ ~ S

>>Q I

~ ~ .~ ~ c g)

~ ' ~ ~ ~

i Q CO V'

rt 0 IS 0 0)

TUhS INE SUILOINO 5 LOOh DhAINS EF 5 LUSH f LINE Vg 0 g t 0 WASTE VV TURSIHE SLDO YARD OIL FLOOR DRAINS SUMFS NEUlhALITA'TION SEFAhATOR

~ ASIN 0 8 A

RF.M SETTLINQ SATIN OUTSIDE TANK AREA OhAIN EF F LUEN F LINE OUT SIO E TANK STOhM ORAIH 6 AREA DRAIN SYSTEM IEM i CAN SF. DIVERTED TO SECONDARY WASTE

'TREATMENT SYSTEM

'AN 4'5 QIVFRTEO TO LIQUID RAOWAS t \

'TREATMENT SYSTEM HAhhIS EKE

Shearon Harris Nuclear Power Plan't (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.0 GASEOUS EFFLUENTS At SHNPP there are four gaseous effluent release points: Plant Vent Stack 1, Turbine Building Vent Stack 3A, and the Waste Processing Building Vent Stacks 5 and 5A. These are shown in Figures 3.1, 3.2, and 3.3 along with their tributaries. All gaseous effluent releases at the plant are considered ground releases.

3.1 Monitor Alarm Set Point Determination (Technical Specification 3.3.3.11)

This section provides the methodology for stack effluent monitor set points to ensure that the dose rates from noble gases at the site boundary do not exceed the limits of 500 mrem/year to the whole body or 3000 mrems/year to the skin as specified in Technical Specification 3.11.2.1. I The radioactivity effluent monitors for each stack and for specific effluent streams are shown in Figures 3.1 and 3.3 and are listed in Appendix C.

In Stacks 1 and 5, the potential exists for batch releases concurrent with the normal continuous ventilation flow of effluents. The sources of batch releases for the Plant Vent Stack 1 include containment normal and preentry purge and pressure relief. Batch release sources for Vent Stack 5 include releases from the waste gas decay tanks (WGDT). In these cases, the monitor set point must reflect the contribution of both the continuous and batch sources.

The following set point calculation is applicable to the 4 vent stack monitors for all conditions, e.g.

Continuous release via Plant Vent Stack 1.

Batch mode release of containment normal purge, preentry purge, or pressure relief via Plant Vent Stack 1 concurrent with the continuous release.

Continuous release through Vent Stack 3A.

Continuous release via Vent Stack 5.

Batch release of a waste gas decay tank .via Stack 5 concurrent with the continuous release.

Continuous release via Vent Stack 5A.

3-1

0 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.1.1 Effluent Monitor Set Point Based On Known Or Assumed Stack Effluent The general approach to gas monitor set point determination begins with the Technical Specification limits on noble gas dose rates (mrem/year) to the whole body and skin at the site boundary. These site limits are apportioned to each of the four stacks on the basis of respective design flow rate. Individual stack release rates (pCi/sec) are calculated which are functions of the known or assumed (GALE code) noble gas composition of the effluent. Based on stack flow rate (acfm) the release rate can be converted to an allowable noble gas concentration (pCi/cc). The monitor high alarm set point is then established to provide alarm when the concentration reaches 50 percent of the allowable level.

Determine the noble gas radionuclide composition of the gaseous effluent.

a. Gamma spectroscopy analysis of the gas sample should provide

'he nuclide identification and activity. However, in the case where the noble gas activities are ( LLD the relative nuclide composition can be assumed from the GALE code activities for pro]ected normal operating releases (Table 3.1-1).

A Activity (pCi/cc) of noble gas nuclide "i" at the stack monitor weighted for dilution by other sources Ab( F+ff ) +AiP ( F )

F+f (3. 1-1) where:

ib Activity of nuclide "i" in an undiluted batch sample, pCi/cc A

ip Activity of nuclide "i" in the ventilation flow sample, pCi/cc .

Use the measured effluent flow rate or the maximum effluent design flow rate at the point of release (acfm) as follows:

28,320 acfm (Turbine Buildings Vent Stack 3A) 232,050 acfm (Waste Processing Building Vent Stack 5) 103,500 acfm (Waste Processing Building Vent Stack 5A) 3-2

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.1.1 Effluent Monitor Set Point Based on Known or Assumed Stack Effluent 390,000 acfm (Plant Vent Stack 1)

Release flow rate for batch releases (acfm) 1,500 acfm for containment normal purge 37,000 acfm for containment preentry purge 2 26 E+06 (

~

14 7 ~

) (

273 Tc

)

for a containment pressure release 600 (

14.7 t

) (

273 Tc

)

for a Waste Gas Decay Tank release where:

2.26E+06 and 600 are the volumes in ft3 of the containment and decay tank, respectively, and T Tc, DP and BPc are the estimated, respective temperature and change in pressure (psig) following the release of the containment and decay tank; and, 14.7 lb/in~, i.e., 1 atmosphere pressure Length of release, min 273'K - O'C Tt~Tc 273 K + C b., Determine Sz (the fraction of the total noble gas radioactivity in the gaseous effluent comprised by noble gas radionuclide'"i") for each individual noble gas radionuclide in the gaseous effluent.

Ai (3.1-1a)

Sg g Aq 3-3.

8 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.1.1 Effluent Monitor Set Point Based On Known Or Assumed Stack Effluent

2. . Determine the maximum allowable noble gas release rate from the stack, Q (pCi/sec), based upon the whole body exposure limit of 500 nrem)year and the particular vent stack allocation for releases 4-wb where:

(R75)Z K Si (Tm),

m '3.1-2) pCi/sec C7U) The highest calculated annual average relative concentration for any sector at or beyond the exclusion boundary (sec/m3) 6.1E-06 sec/m~ from Table A-l, Appendix A Ki The whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem/yr/pCi/m3) from Table 3.1-2 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 by simultaneous releases 0.52 for Plant Vent Stack 1 0.03 for Turbine Building Vent Stack 3A 0.31 for Waste Processing Building Vent Stack 5 0.14 for Waste Processing Building Vent Stack 5A Using the gaseous source terms for continuous ventilation flow from Table 3.1-1 and the dose factors from Table 3.1-2, the Q values for the vent stacks are:

Stack 1 4.22E+04 pCi/sec Stack 3A 2.68E+03 pCi/sec Stack 5 1.38E+06 pCi/sec Stack 5A 1. 14E+04 pCi/sec 3-4,

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.1.1 Effluent Monitor Set Point Based on Known or Assumed Stack Effluent

3. - Determine the maximum allowable noble gas release rate from the stack, Q , (pCi/sec), based upon the skin exposure limit of 3000 mrem/year by 3000 (T (3.1-3)

)

(775) Z f(Li + 1.1 M )S ]

~

where:

Lg The skin dose factor due to beta emissions for each identified noble gas radionuclide (mrem/yr/pCi/m )

Mg air dose factor due to gamma emissions for each identified noble gas radionuclide (mrad/yr/pCi/m~). A unit conversion constant of 1.1 mrad/mrem converts air dose to skin dose Lg+1.1M'he Skin dose li factor (mrem/yr/pCi/m~) from Table 3.1-2 Using the gaseous source terms (Table 3.1-1) for continuous flow and the dose factors (Table 3.1-2) the 0 values are:

m-s Stack 1 - 1.43E+05 pCi/sec Stack 3A 9.30E+03 pCi/sec Stack 5 - 1.13E+05 pCi/sec Stack 5A - 3.85E+04 pCi/sec 4, Determine the maximum allowable total noble gas concentration in the stack effluent (pCi/cc) 472 (F + f) (3.1-4) where:

Q The more restrictive release rate between 0w-wb and 0 m-s 472 Conversion factor for cfm to cc/sec 3-3

8 n 1 1

Shearon Harris Nuclear power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.1,3. Effluent Monitor Set Point Based On Known Or Assumed Stack Effluent

5. . Determine the gas channel high alarm set point, HSP~ (pCi/cc)

HPS m O.S (C ) + ~ (3.1-5) where:

0.5 Safety factor Bkg - Monitor background, cpm E Monitor efficiency, cpm/pCi/cc f'r Xe-133

6. Determine the effluent channel high alarm set point, HSP, (pCi/sec)

HSPi - HSP~ (472)'(F+f)'3.1-6)

Determine the gas and effluent channel alert alarm set points, ASP~ (pCi/cc) or ASP~ (pCi/sec) .

a. ASP~ [(HSP~ - Bkg ) F] + Bkg (3.1-7) where:

F A value ( 1.0 designed to alert the operator that the high alarm set point is being approached

b. ASPr ASPm (472) (F + f) (3.1-8) 3.1.2 Alternative Set Point Method Based On Conservative Noble Gas Radionuclide Mixture And Monitor Efficienc (Set Point Calculation Method : CONG)

1. Substitute the Kr-89 dose factors for nuclide-specific K~ and Lg + 1.1M< values in Equations 3.1-2 and 3.1-3, respectively.

3.1.3 Effluent Monitorin Durin Ho in 0 erations If the reactor has been shut down for greater than 30 days, the condenser vacuum pump discharge during initial hogging operations at plant start-up and prior to turbine operation may be routed as dual exhaust to (1) the Turbine Vent Stack 3A and (2) the atmosphere directly. In this instance, the blind flange on the latter exhaust route will be removed (see Figure 3.3).

3-6

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.1.3 Effluent Monitorin Durin Ho in 0 erations (continued)

A conservative effluent channel set point (2.68E+03 pCi/sec; see 3.1.-1.2) has been established for Vent Stack 3A. The monitor set point should be reduced proportionately to the estimated fraction of the main condenser effluent flowing directly to the atmosphere.

3-1

Table 3.1-1 O tn GASEOUS SOVRCE TERMS H) m m m Containment rt 0 m

WPB Plant Vent Condenser Vacuum Pump Purge or HPB NGDT Ventilation Flow Ventilation Flow Ventilation Flow Pressure Relief Ventilation Flow Release << 0 D) via via via via via via m Stack Sh Stack 1 Stack 3h Stack 1 Stack 5 'tack 5 tD C) M Nucllda h~icC~lcc Si h~lC~icc S i ~hi %~ice Sl A~k<~l 81 h~lCl I

Kr-83m 1.82E-Q 3.78E-4 0 C 0 0 0 0 0 C 0 Kr-85m 1.95E-9 2.16E-2 5.17E-10 2.16E-2 4.74E-Q 2.43E-2 2.18E-8 4.53E-4 01 m rt 0)

Kr-85 0 0 0 0 0 7.26E-Q 1.51E-3 6.08E-8 9.81E-1 7.05E-S 9.81E-1 0 0

Kr-87 6. 49K-10 7. 19E-3 l. 72E-10 7. 19E-3 0 3.63E-9 7.56E-4 X s.')

m Kr-88 3.25E-Q 3.60E-2 8.61E-10 3.60E-2 7.12E-Q 3.66E-2 2.91E-8 6.05E-3 Kr-89 0 0 0 0 0 0 D>

Xe-131m 0 0 0 0 0 1. 82E-8 3:78E-3 8. 69E-10 l. 40E-2 1.01E-6 1.40E-2 O rt Xe-133m 1.30E-Q 1.44E-2 3.45E-10 1.44E-2 2.37E-Q 1.22E-2 7.81E-8 1.62E-2 O~

Xe-133 7.79E-8 '.63E-l 2.07E-8 8.63E-1 1.71E-7 8. 78E-1 4.54E-6 9:44E-1 2.90E-10 4.67E-3 3.36E-7 4.67E-3 Xe-135m 0 0 0 0 0 '0 Xe-135 4.54E-9 5.06E-2 1.21E-9 5.04E-2 9.49E-9 4.87E-2 1.07E-7 2.23E-2 0 Xe-137 0 0 0 0 0 0 ,- 0 Xe-138 6.49E-10 7.19E-3 1.72E-10 7.19E-3 0 (a) Source terms are based upon GALE code (SHHPP FSAR Table 11.3.3-1) and not actual releases. Values apply only to routine releases and not emergency situations.

(b) Source term for this effluent stream not presented witb FSAR. RAB mix assumed.

(c) hi()Ci/cc) ~ Ci r r min Ci Ci ft3 cc For f (d) Based on an assumed f 200 CF)i for HGDT.

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.1-2 DOSE FACTORS AND CONSTANTS Whole Body Dose Skin Dose Factor Factor (K~) (L~ + 1. 1 Mg)

Radionuclide (mrem/yr/pCi/m~) (mrem/yr/pCi/m~)

Kr-83m 7.56E-02 2.12E+01 Kr-85m 1.17E+03 2.81E+03 Kr-85 1.61E+Ol 1.36E+03 Kr-87 5.92E+03 1.65E+04 Kr-88 1.47E+04 1.91E+04 Kr-89 1.66E+04 2.91E+04 Kr-90 1.56E+04 2.52E+04 Xe-131m 9.15E+Ol 6.48E+02 Xe-133m 2.51E+02 1.35E+03 Xe-133 2.94E+02 6.94E+02 Xe-135m 3.12E+03 ~

4.41E+03 Xe-135'e-137 1.81E+03 3.97E+03 1.42E+03 1.39E+04 Xe-138 8 '3E+03 1.43E+04 Ar-41 8.84E+03 1.29E+04

Regulatory Guide 1.109, Rev. 1, Table B-l, multiplied by (1.0+E6 pCi/pCi).

3-9.

0 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.2 Postrelease Com liance with 10CFR20-Based Technical S ecification 3.11.2 3.2.1 Noble Gases The gaseous effluent monitors set points are utilized to show prerelease compliance with Technical Specification 3.11.2.1. However, because they may be based upon a conservative (GALE code) mix of radionuclides, when using Table 3.1-1, the possibility exists that the set points could be exceeded and yet 10CFR20-based limits may actually be met. Therefore, the following methodology has been provided in the event that high alarm set points are exceeded, a determination may be made as to if the whether the actual releases have exceeded the dose rate limits of Technical Specification 3.11.2.1.

The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mrem/year to the total body and 3000 mrem/year to the skin. Based upon NUREG-0133, the following equations are used to show compliance:

g K (R75)0

.s 500 mrem/yr (3. 2-1)

Zl. ( i ')(~ v ()iv s 3000 mrem/yr (3.2-2) where:

(VU) The highest calculated annual average relative concentration for long-term vent stack releases for areas at or beyond the exclusion boundary sec/m~.

I 6.1E-06 sec/m~ from Table A-l, Appendix A, for ground-level releases in the S sector at the exclusion boundary.

Kz - The total body dose factor due to gamma emissions for noble gas radionuclide "i," mrem/year per pCi/m~.

Table 3.2-3.

Lz The skin dose factor due to beta emissions for noble gas radionuclide "i," mrem/year per pCi/m~.

Table 3.2-3.

Mg The air dose factor due to gamma emissions for noble gas radionuclide "i," mrad/year per pCi/m .

Table 3.2-3.

3-10

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.2.1 Noble Gases (continued)

The ratio of the tissue to air absorption coefficients over the energy range of the photon of interest.

Converts mrad to mrem (Reference NUREG-0133). The factors (Lz + 1.1 M<) are tabulated in Table 3.1-2.

Qiv The release rate of radionuclide "i" in gaseous effluents from all plant vent stacks (pCi/sec).

The determination of the controlling location for implementation of dose rate limits for noble gas exposure is a function of the historical annual average meteorology.

The radionuclide mix is based on the sampling and analysis required by Technical Specification 4.11.2.2.1. If the analysis is < LLD, then the GALE code, historical data for the mix, or a 'Xe-133 that analysis will be used to demonstrate compliance.

/ Kr-85 LLD mix for The release rate is derived from either 'the actual flow rate or the default. flow rate and the known or assumed mix.

Release Rate (pCi/sec) - Flow (cc/sec)

Concentration (pCi/cc)

The noble gas radionuclide mix was based upon source terms calculated using the NRC GALE Code and presented in the SHNPP FSAR Table 11.3.3-1.

They are reproduced in Table 3.2-1 as a function of release point.

The X/Q value utilized in the equations is the highest long-term annual average relative concentration (275)v in the unrestricted area for the period 1976 - 1987. Long-term annual average (Fjg) v values at other locations shown in Table 3.2-2 are presented in Appendix A. A description of their derivation is also provided in this appendix.

To select the limiting location for ground-level releases, long-term annual average (X75) values were calculated assuming no decay, undepleted transport to the exclusion boundary. These values are given in Table A-l, Appendix A . The maximum exclusion boundary (X7Q) v for ground-level releases occurs in the S sector. Therefore, the limiting location for implementation of the dose rate limits for noble gases is considered to be the exclusion boundary (1.36 miles) in the S sector.

Values for Kz, Lz, and M~ which are to be used by SHNPP in Equations 3.2-1 and 3.2-2 to show compliance with Technical Spe'cification 3.11.2 are presented in Table 3.2-3. These values were taken from Table B-1 of NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 1.0E+06 to convert mrad/pCi to mrad/pCi for use in Equations 3.2-1 and 3.2-2.

3-11

'h Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.2.2.'Radioiodines and Particulates The bases for, Technical Specification 3/4.11.2.1 states that the dose rate -to the thyroid of a child in an unrestricted area resulting from the inhalation of radioiodines, tritium, and particulates with half-lives h 8 days is limited to 1500 mrem/yr to any organ. Based upon NUREG-0133, the following is used to show compliance:

z, l (X7U) Qi] s 1500 mrem/yr (3.2-3) where:

Pi - The dose parameter for radionuclides other than noble gases for the inhalation pathway, mrem/yr per pCi/m .

In the calculation to show compliance with Technical Specification 3.11.2.1.b, only the inhalation pathway is considered.

The radionuclide mix is based on the sampling and analysis required by Technical Specification 4.11.2.1.2. If the analysis is < LLD, then no activity is assumed to have been released during the sampling period.

The release rate is derived from the flow (actual or default) "and the mix.

Release Rate (pCi/sec) Flow (cc/sec)

Concentration (pCi/cc)

The determination of the controlling exclusion boundary location was based upon the highest exclusion boundary (Z7g) v value. Values for Pi in Eq. 3.2-3 were calculated for a child for various radionuclides fob the inhalation pathway using the methodology of NUREG-0133. The Pi values are presented in Table 3.2-4. A description of the methodology used in calculating the Pi values is presented in Appendix B. The values of Pi reflect, for each radionuclide, the maximum Pi value for any organ.

The (X7Q)v value utilized in Equation 3.2-3 is obtained from the tables presented in Appendix A. A description of the derivation of the X/Q values is provided in Appendix A.

Table 3.2-1 Q M H) W tt) (D Releases from the Shearon Harris Nuclear Power Plant (1) Ol VI gIl tt Normal Operation (Curies/year) rt 0 Q

Waste Processing Bldg Waste Processing Bldg Condenser Vacuum Pump 0 Exhaust and/or Waste Gas Decay Tanks (2)

Exhaust via VENT STACK 5A or RAB/FHB and Containment and Turbine Building Exhaust I lO via VENT STACK 5 Exhaust via VENT STACK I via VENT STACK 3A O N NOBLE NORMAL GASES SHUTDOWN OPERATIONS CONTAINMENT RAB/FHB TURBINE "

STACK 3A TOTAL n t=

g O Kr-83m 0 0 I.QE+00 0 0 0 1.0E+00 Qs rt I

Ol Kr45m 0 0 ICE+01 3.E+00 0 2.0E+00 1.7E+01 Kr-85 3.0E+00 2.1E+02 4.0E+00 0 0 0 2.2E+02 o Kr-87 0 0 2.0E+00 I.QE+00 0 0 3.0E+00 0 Kr-88 0 0 1.6E+01 5.0E+00 0 3.0E+00 2.4E+01 fO tD Kr-89 0 0 0 0 0 0 0 Xe-131m 0 3.0E+00 I.QE+00 0 0 0 1.3E+01 Xe-133m 0 0 4.3E+01 2.0E+00 0 1.0E+00 4.6E+01 Xe-133 0 1.0E+00 2.5E+03 1.2E+02 0 7.2E+01 2.7E+03 Xe-135m 0 0 0 0 0 0 0 O rt Xe-135 0 0 5.9E+01 7.0E+00 0 4.0E+00 7.0E+01 aO~

Xe-137 0 0 0 0 0 0 0 +M Xe-138 0 0 1.0E+00 0 . 0 I.QE+00 Ardl 2.5E+o1t>>

PARTICULATES 1-131 0 0 1.3E42 4.5E-03 3.0E44 2.8E42 4.6E42 I-133 0 0 I.IE42 6.7E43 4.2E44 4.2E42 6.0E42 H-3 5.8E+02 t>>

C-14 8.OE+OO t>>

Mn-54 0 4.5E43 2.2E44 1.8E44 0 0 4.9E43 Fe-59 0 1.5E43 7.3E45 6.0E45 0 0 1.6E43 Co-58 0 1.5E42 7.3E44 6.0E44 0 0 1.6E42 Co60 0 7.0E43 3.3E44 2.7E44 0 0 7.6E43 Sr-89 0 3.3E44 1.7E45 1.3E45 0 0 3.6E44 Sr-90 0 6.0E45 2.9E46 2.4E46 0 0 6.5E45 Cs-134 0 4.5E43 2.2E44 1.8E44 0 0 4.9E43 Cs-137 0 7.5E45 3.7E44 3.OE44 0 0 8.2E43 (I) Adapted from SHNPP FSAR Table 11.3.3-1. Calculations are based upon the GALE code, and do not refiect actual release data. These values are only for routine releases and not for a complete inventory of gases in an emergency.

(2) Waste Gas Decay Tank releases assumed alter a 904ay decay period.

O (3) Calculated using the guidance of NUREG4017, "Calculation of Releases of Radioactive Material in Gaseous and Liquid Effiuents from PWR's.

c c

W I P1 1 4 11 I

~

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Table 3.2-2 Distance to the Nearest Special Locations for the Shearon Harris Nuclear Power Plant (miles)*

(Comparison of 1992/1993 Data)

Residence Milk Animal Garden Meat Animal Exclusion Sector Bounda 1992 1993 1992 1993 1992 1993 1992 1993 N 1.32 2.2 2 ' 2.2 2.2 2.2 2.8 2.2 2.2 NNE 1.33 1.8 1 9

~ 1.7 1.7 3..1 2.2 NE 1.33 2.3 2.3 2.3 2.3 2.3 2.3 ENE 1.33 3.6 1.8 3.8 3.6 1.33 1.9 1.8 4.7 2.0 2.2 2.0 ESE .1 33 2.7 2.6 4.7 4.4 4.2 SE 1.33 4.3 2.6 4.4 4.1 4.3 4.1 1.33 4.4 4.2 4.6 4.3 SSE'SM

l. 36 5.3 5.3 5.3 1.33 3.9 3.9 3.9 3.9 SW 1.33 2.8 2.9 2.8 2.9 VSQ 1.33 4' 4.5 4.3 4' 1.33 2.8 3.0 2.9 3.1 2.9 3.1 1.33 2.1 2.3 2.1 2.3 2.6 1.26 2' 2.4 3.8 2.7 3.8 3.7 1.26 1.5 1.6 1.7 2.0 1.7 2.0 As of June, 1993.

Distance estimates are + 0.1 miles except at the exclusion boundary.

Distances and sectors determined by Global Positioning System.

3-L4

~ 4.

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.2-3 DOSE FACTORS FOR NOBLE GASES

Total Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor Radionuclide K< k M, N; (mrem/yr per (mrem/yr per (mrad/yr per (mrad/yr per yCi/m') yCi/ms) yCi/ms) yCi/ms)

Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+ 03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90, 1.56E+04 7.29E+ 03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+ 02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1 A2E+03 1.22E+04 1.51E+03 1.27E+04 Xe-1 38 8.83E+03 4.13E+03 9.21 E+03 4.75E+03 Ar<1 8.84E+03 2.69E+03 9.30E+03 3.28E+03

The listed dose factors are for radionuclides that may be detected in gaseous effluents.

3-l5

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.2-4 Pi I VALUES (INHALATION) FOR A CHILD PiI.z Value ISOTOPE mrem r er Ci m H-3 1.12E+03 P-32 2.60E+06 Cr-51 1.70E+04 Mn-54 1.57E+06 Fe-59 1.27E+06 Co'-58 1.10E+06 Co-60 7.06E+06 Zn-65 9.94E+05 Rb-86 1.98E+05 Sr-89 *.2.15E+06 Sr-90 1.01E+08 Y-91 2.62E+06 Zr-95 2.23E+06 Nb-95 6.13E+05 Ru-103 6.61E+05 Ru-106 1.43E+07 Ag-110m 5.47E+06 Sn-113 3.40E+05 Sb-124 3.24E+06 Te-127m 1.48E+06 Te-129m 1 76E+06

~

I-131 1.62E+07 I-132 1.93E+05 I-133 3.84E+06 I-135 7.91E+05 Cs-134 1.01E+06 Cs-136 1.71E+05 Cs-137 9.05E+05 Ba-140 1.74E+06 Ce-141 5.43E+05 Ce-144 1.19E+07 Hf-181 7.95E+05 3-16

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3,.3 COMPLIANCE WITH 10CFR50 The calculations described in Section 3.2 will be used to ensure compliance with the limits in 10 CFR 50 Appendix I on a "per-release" basis. The NRC approved program GASPAR will be used to demonstrate compliance on an annual basis. While there are differences between the ODCM methodology and the methodology in GASPAR, conservative factors have been chosen for the ODCM methodology which will ensure compliance with the limits of 10 CFR 50 Appendix I.

The SHNPP ODCM calculates the dose to a single maximum (ALARA) individual. The ALARA individual is an individual that "lives" at the site boundary in the sector that has the most limiting long-term average X/Q value.

The SHNPP GASPAR program calculates the dose to a maximum individual in all age groups, down wind receptors, and integrated populations. It t'e will calculate doses based on the actual average meteorology for period of interest.

GASPAR Parameters are maintained in the Laboratory and Facility Services Section Instruction RC-ER-36, Operating Instruction for XOQDOQ, GASPARS, and LADTAP Computer Programs. Parameters subject to change on a periodic basis (receptor locations, source terms, etc.) are not listed, but will be defined and described in the Radioactive Effluent Release Report 'for the period of interest.

0 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.3.1 Noble Gases

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:

3.17 E-<

500 hrs/yr) from all vent stacks (pCi). q w The total release of radionuclide "i" in gaseous releases for short-term releases (5500 hour0.0637 days 1.528 hours 0.00909 weeks 0.00209 months s/year) from all vent stacks, (pCi). 'inverse of the number of seconds in -1 3.17 E-0& The a year (sec/year) Mg The air dose factor due to gamma emissions for each identified noble gas radionuclide (mrad/yr/pCi/m~). A unit conversion constant of 1.1 mrad/mrem converts air dose to skin dose 0 P Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.3.1 Noble Gases (continued) To show compliance with 10CFR50, Expressions 3.3-1 and 3.3-2 are evaluated at the controlling location where the air doses are at a maximum. At SHNPP the limiting location is the exclusion boundary at 1.36 miles in the S sector based upon the tables presented in Appendix A (see Section 3.2.1 earlier). For this document, long-tenn annual average (F79)v values can be used in lieu of short-term values (see Section 3.0 earlier). The determination of the limiting location for implementation of 10CFR50 is a function of parameters such as radionuclide'ix, isotopic release, and meteorology. To select the limiting location, the highest annual average27gv value for ground-level releases is controlling. The only source of short-term releases from the plant vent are containment purges, containment pressure relief, and waste gas decay tank release. Determination of source terms is described in 3.3.1.2. Values for Mz and Nq, which are utilized in the calculation of the gamma .air and beta air doses in Equation 3.3-1 to show compliance with 10CFR50, are presented in Table 3.2-3. These values originate from Table B-1 of the NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 1.0E+06 to convert from mrad/pCi to mrad/pCi. The following relationships should hold for SHNPP to show compliance with Technical Specification 3.11.2.2. For the calendar quarter: Dy 8 5 mrad (3.3-6) DP S 10 mrad (3.3-7) For the calendar year: Dy s 10 mrad (3.3-8) DP s 20 mrad (3.3-9) The quarterly limits given above represent one-half of the annual design objectives of Section II.B.1 of Appendix I of 10CFR50. If any of the limits of Equations 3.3-3 through 3.3-6 are exceeded, a Special Report pursuant to Technical Specification 6.9.2 must be filed with the NRC. This report complies with Section .IV.A of Appendix I of 10CFR50. 3-19 0 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.3.1 Noble Gases (continued)

2. Source Term Determination Containment Batch Purge A purge of containment may be started as a Batch purge and continued as a normal purge. The containment Batch Purge volume is considered to be two air containment volumes (RCB vol - 2.26E+06 ft ). The containment air is sampled and analyzed for noble gases and tritium prior to release.

Stack 1 has a continuous particulate filter and iodine cartridge sampler that is analyzed weekly (minimum) and used for total particulate and iodine effluent accountability for continuous releases. The noble gases and tritium analysis are used for containment effluent accountability as follows; (3 '-3) Where; qz Activity of. nuclide "i" released (pCi). Cq Concentration of radionuclide "i" (pCi/cc) vb - Containment volume (cc). Waste Gas Decay Tank Batch Releases Waste Gas Decay Tanks (WGDT) are sampled and analyzed for tritium and noble gases prior to each release. Stack 5 has a continuous particulate filter and iodine cartridge sampler that is analyzed weekly (minimum) and used for total particulate and iodine effluent accountability for continuous releases. The activity (pCi) for nuclide "i" for Waste Gas Decay Tank effluent accountability is calculated as follows; (Cg 'Pq '00 '8320 '98) (3.3-3a) (14 7 '83) qg ~ 3-20 0 8 1 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.3.1 Noble Gases (continued) Where; Activity of nuclide "i" released (pCi). Cg Concentration of nuclide "i" (pCi/cc). Change in pressure (psia) of the WGDT (psia psig + 14.7) 600 WGDT volume, (ft~) . 28320 Conversion factor for converting from ft~ to cc. 298 Sample temperature at time of analysis, ( k). 14.7 Sample pressure at time of measurement, (psia). 283 WGDT Temperature,'. k (see Note below) NOTE: The FSAR assumes WGDT temperature to be in the 50-140 F range. Since there is no indicator for the actual WGDT temperature, 50 F (10 C) is conservatively assumed as an acceptable substitute. Also assumed is a sample analysis temperature of 77' (25'). NOTE: Containment Pressure Releases (ILRT) are calculated using the same methodology. Containment Pressure Releases are released via Stack 1. The volume to use is 2.26E+06 ft~. Continuous Releases Each of the four effluent stacks at the HNP have noble gas monitors. Using the net concentration (pCi/cc) from these monitors times the volume released (determined from the flow monitors) the total activity (pCi) of noble gases released are calculated as follows: Qx Cx ~ Vx (3.3-4) Where; Q - Total activity (pCi) released from Stack "x". C Net concentration (pCi/cc) from Stack "x" noble gas monitor. V - Volume (cc) released from Stack "x" using the flow monitor and, if out of service use the compensatory measurements for volume determination. 3-21 Cl Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation manual (ODCM) Rev. 4 3.3.1 Noble Gases (continued) The activity (pCi) released for radionuclide "i" equals the radionuclide "i" fraction of the radionuclide mix times the total activity released from Stack "x". Q~ Qx ~ Si (3.3-4a) Where; Cg Sg (3.3-4b) and; Sz The radionuclide "i" fraction of the radionuclide mix C< - The concentration of nuclide "i" in the grab sample (pCi/cc). ZCz Total activity in grab sample (pCi/cc). The radionuclide mix is based on the sampling and analysis required by Technical Specification 4.11.2.2.1. sample activity is If the grab < LLD, then a mix based on historical data or a mix based on the Xe-133 sample may be used. / Kr-85 LLD mix of that When a monitor is out of service, the" results of the compensatory sampling for each nuclide times the volume released for that time interval will be used for effluent accountability. During this situation detectable activity if the sample shows no then there is no activity released. Corrections for Double Accounting For the two stacks that may have batch releases during the same time interval as continuous releases, the above calculations are corrected for double accounting as follows; Qic-Qi - qi (3 '-5) Where; Qq, Total corrected activity of nuclide "i" (pCi) from Stack "x" when batch releases are being made during that time period. 3-22 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.3.1 Noble Gases (continued) For short term (batch) releases, the effluent stream is sampled and analyzed. The results of the sampling and analysis is used as the source term for the batch release. Release rate is derived from the source term and the release flow rate. Projection of Doses Doses resulting from the release of gaseous effluents will be projected once every 31 days (monthly). The doses will be projected utilizing Equations 3.3-1 and 3.3-2. When the operational conditions are expected to be the same as for the current month, the source-term inputs into the equation for the projection can be taken directly from the current month's data. Where possible, credit for expected operational evolutions (i.e., outages, increased power levels, major planned batch gas releases, etc.) should be integrated into the dose projections by using source-term data from histori'cal operating experiences. This may also be accomplished by using the projected Percent Power-Reactor Days for the unit as in the following expression: Dq Pq D~ Pq i.e., D~ = Dx P P~ (3.3 10) I To show compliance with Technical Specification 3.11.2.4, the projected month's dose should be compared as in the following: Dy 5'.2 mrad to air for gamma radiation (3. 3-11) I and DP 8 0.4 mrad to air for beta radiation (3.3-12) I If the projections exceed either Equations 3.3-11 or 3.3-12, then the appropriate portions of the gaseous radwaste treatment system shall be used to reduce releases of radioactivity. 3-23 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.3.2 Radioiodine and Particulates

1. Cumulation of DosesSection II.C of Appendix I of 10CFR50 limits the release of radioiodines and radioactive material in particulate form from a reactor such that the estimated 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 and particulates with half-lives greater than 8 days in gaseous effluents released to unrestricted areas can be determined by the following equation:

- g D, 3.X'7E-Oa (Ri I [(Vg) Oiv + (XR) ai v ] + iy iG+ iB ) f(ma) 'Qj v + (mdiv Qiv ))+ +RT +RZ +RT) ((~Q + Wq) q ) (3 3-13) ~ where: D 7 Dose to any organ r from tritium, radioiodines, and particulates, mrem. (575) The highest long-term () 500 hr/yr) annual average relative deposition: 8.8 E-09 m -2 for the food and ground plane pathways at the controlling location which is the exclusion boundary in the S sector (from Table A-4, Appendix A, for ground-level vent stack releases). Wa) The relative deposition factor for short term ground-level vent releases (s 500 hrs/yr), m See Section 3.0 earlier meteorology or use 8.8 E-09 m if usiyg "real" from Table A-4, Appendix A, for the food and ground plane pathways at the controlling location. Ri Dose factor for an organ for radionuclide "i" for either the cow milk or2goat milk pathway, mrem/yr per pCi/sec per m 3-2A Shearon Harris Nuclear Power Plant (SHNPP) .June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.3.2 Radioiodine and Particulates (continued) Ri Dose factor for an organ for radionuclide "i" for the ground plage exposure pathway, mrem/yr per pCi/sec per m Ri Dose factor for an organ for radionuclide "i" for the inhalation pathway, mrem/yr per pCi/m . R iq Dose factor for an organ for radionuclide "i" for th~ vegetable pathway, mrem/yr per pCi/sec per m R. is Dose factor for an organ for radionuclide "i" fog the meat pathway, mrem/yr per pCi/sec per m R Dose factor for an organ for tritium for the milk pathway mrem/yr per pCi/m . R Dose factor for an organ for tritium for the vegetable pathway, mrem/yr per pCi/m~. r, Dose factor for an organ for tritium for the inhalation pathway, mrem/yr per pCi/m . R Dose factor for an organ for tritium for the meat pathway, mrem/yr per pCi/m~. Release of tritium in gaseous effluents for long-term vent stack releases (> 500 hrs/yr), pCi. Release of tritium in gaseous effluents for short-term vent stack releases (5 500 hrs/yr), pCi. To show compliance with 10CFR50, Equation 3.3-10 is evaluated for a hypothetical individual at the limiting location. At SHNPP this location is the exclusion boundary in the S sector which has the highest annual average (Xjg)v and (575)v values. This assures that the actual exposure of a member of the public will not be substantially underestimated. The critical receptor is a child. Appropriate (X75)v and (~)v values from tables in Appendix A are used. For this document, long-term annual average (X7Q)v and (575)v values may be used in lieu of short-term values (see Section 3.0 earlier). 3- 25 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.3.2 Radioiodine and Particulates 'n (continued) The determination of a limiting location for implementation of 10CFR50 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 limi.ting location, the radionuclide mix of radioiodines and particulates is based on the sampling and analysis required by Technical Specification 4.11.2.1.2.

analysis is < LLD, then no activity is assumed to have been If the released during the sampling period. The release rate is derived from the flow (actual or default) and the mix. In the determination of the limiting sector, all age groups and all of the exposure pathways are initially evaluated using the GASPAR code. These include cow milk, beef and vegetable ingestion, inhalation, and ground plane exposure. Goat milk is not currently an exposure pathway at SHNPP. SHNPP Technical Specification 3.12.2 requires that a land-use census survey be conducted on an annual basis. The age groupings at the various receptor locations are also determined during this survey. Thus, depending on the results of the survey, a new limiting location and receptor age group could result. To avoid possible annual revisions to the ODCM software which evaluates effluent releases for compliance with 10CFR50, the limiting sector location has been fixed at the exclusion boundary 'in the S sector where the highest historical annual average (275)v and (575)v values occur (Appendix A). With all of the exposure pathways identified in the land use census (Table 3.2-2) available to a hypothetical receptor, the critical organ is a child's bone. This approach avoids a substantial underestimate of the dose to a real member of the public. Long-term (275)v releases are provided 'nd (575)v values for ground-level 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 3.2-2. A description of the derivation of the various X/Q and D/Q values is presented in Appendix A. 3-26 N Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Hanual (ODCH) Rev. 4 3.3.2 Radioiodine and Particulates (continued) Tables 3.3-1 through 3.3-19 present Rz values for the total body, GI-tract, bone, liver, kidney, thyroid, 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 assuming a grazing period of eight months. A description of the methodology is presented in Appendix B. The following relationship should hold for SHNPP to show compliance with SHNPP Technical Specification 3.11.2.3. For the calendar quarter: Dr 8 7.5 mrem (3.3-14) For the calendar year: Dr S 15 mrem (3.3-15) The quarterly limits given above represent one-half the annual design objectives of Section II.C of Appendix I of 10CFR50. If any of the limits of Equations 3.3-14 or 3.3-15 are exceeded, a Special Report pursuant to Technical Specification 6.9.2 must be filed with the NRC. This report complies with Section IV.A of Appendix I of 10CFR50.

2. Projection of Doses Doses resulting from release of radioiodines and particulates will be projected once every 31 days (monthly) utilizing Equation 3.3-10. When the operational conditions for the projected month are expected to be the same as for the current month, the source-term inputs into the equation for the projection can be taken directly from the current month's data. Where possible, credit for expected operational evolutions (i.e.,

outages, increased power levels, major batch gas releases, etc.) should be integrated into the dose projections by using source term data from historical operating experiences. This may also be accomplished by the using projected Percent Power-Reactor Days for the unit as in the following expression: Dg Pg Dp Pg i.e., Q m Dg Pg Pi (3.3-16) To show compliance with Technical Specification 3.11.2.4, the projected month's dose should be compared as in the following: D S 0.3 mrem to any organ (3. 3-17) I 3-27 Shearon Harris Nuclear Power Plant (SHNpp) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 3.3.2 Radioiodine and Particulates (continued) If the projections exceed Expression 3.3-14, then the appropriate portions of the gaseous radwaste treatment system shall be used to reduce releases of radioactivity. 3-28 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.3.1 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT PATHWAY ~ Ground AGE GROUP ~ ALL Nuclide ~T. Bod ~GI-Trac Bone Liver ~Kidne ~Th old ~Lun Skin Cr-51 4.66E+06 4.66E+06 4.66E+06 4.66E+06 4.66E+06 4.66E+06 4.66E+06 5.51E+06 Mn.54 1.34E+09 1.34E+09 1.34E+09 1.34E+09 1.34E+09 1.34E+09 1.34E+09 1.57E+09 Fe-59 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 3.23E+08 Co.58 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 4A4E+09 Co-60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.52E+10 Zn 65 7.49E+08 7.49E+08 7.49E+08 7.49E+08 7.49E+08 7.49E+08 7A9E+08 8.61E+08 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 Sr-89 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.58E+04 Y-91 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 '.08E+06 1.22E+06 Zr 95 2.49E+08 2.49E+08 2.49E+08 2.49E+08 2:49E+08 2.49E+08 2.49E+08 2.89E+08 Nb-95 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.60E+08 Ru-103 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.27E+08 Ru-106 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 5.03E+08 Ag-110M 3.48E+09 3.48E+09 3.48E+09 3.48E+09 3.48E+09 3.48E+09 3.48E+09 4.06E+09 Sn-113 1A4E+07 6,28E+06 1.22E+07 6.21E+06 1.00E+07 1.33E+07 8.14E+06 4.09E+07 Sb-124 8.76E+08 7.53E+08 8.99E+08 7.76E+08 8.17E+08 1.01E+09 8.23E+08 1.24E+09 Te-127M 9.15E+04 9.15E+04 9.'I 5E+04 9.15E+04 9.15E+04 9.15E+04 9.15E+04 1.08E+05 Te-129M 2.00E+07 2.00E+07 2.00E+07 2.00E+01 2.00E+01 2.00E+07 2.00E+01 2.34E+07 I-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+01 1.72E+07 2.09E+07 I-132 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.46E+06 I-133 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 3.00E+06 I-135 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.99E+06 Cs-134 6.82E+09 6.82E+09 6.82E+09 6.82E+09 6.82E+09 6.82E+09 6.82E+09 7.96E+09 Cs-136 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.69E+08 Cs-137 1.03E+ 10 1.03E+10 1.03E+10 1.03E+ 10 1.03E+ 10 1.03E+ 10 1.03E+ 10 1.20E+ 10 Ba-140 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.34E+07 Ce-141 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.53E+07 Ce-144 6.95E+07 6.9SE+07 6.95E+07 6.95E+07 6.95E+07 6.95E+07 6.95E+07 8.03E+07 Hf-181 1.97E+08 1.63E+08 2.30E+08 1.70E+08 1.77E+08 2.33E+08 1.82E+08 2.82E+08 'R Values in units of mrem/yr per yCI/m~ for Inhalation and tritium snd in units of mrem/yr per /rCI/sec per m'or all others. 3-29 I )II I I) Pf Shearon Harris Nuclear Po<<r Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.3-2 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANTi PATHWAY ~ Veget AGE GROUP ~ Adult Nuclide ~T. Bod Gl-Tract Bone Liver ~Kidne ~Th aid ~Lun H-3 2.28E+03 2.28E+03 O.OOE+Ol 2.28E+03 2.28E+03 2.28E+03 2.28E+03 2.28E+03 P-32 5.91E+07 1.72E+08 1.53E+09 9.61E+07 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+Ol Cr-51 4.60E+04 1.16E+07 O.OOE+01 O.OOE+01 1.01E+04 2.75E+04 6.10E+04 O.OOE+01 Mn-54 5.83E+07 9.36E+08 O.OOE+01 3.05E+08 9.09E+07 O.OOE+01 O.OOE+01 O.OOE+01 Fe.59 1.12E+08 9.75E+08 1.24E+08 2.93E+08 O.OOE+01 O.OOE+01 8.17E+07 O.OOE+01 Co.58 6.71E+07 6.07E+08 O.OOE+01 2.99E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Co.60 3.67E+08 3.12E+09 O.OOE+01 1.66E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn.65 " 5.77E+08 8.04E+08 4.01E+08 1.28E+09 8.54E+08 O.OOE+01 O.OOE+Ol O.OOE+01 Rb.86 1.03E+08 4.36E+07 O.OOE+01 2.21E+08 O.OOE+Ol O.OOE+01 Q.OOE+Ol O.OOE+ 01 'Sr-89 2.87E+08 1.60E+09 1.00E+10'.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Ii O.OOE+01 Sr-90 1.64E+ 11 1.93E+ 10 6.70E+11 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Y-91 1.34E+05 2.76E+09 5.01E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 2.51E+05 1.17E+09 1.16E+06 3.71E+05 5.82E+05 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 4.19E+04 4.73E+08 1.40E+05 7.79E+04 7.70E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 2.04E+06 5.53E+QB 4.74E+06 O.OOE+Ql 1.81E+07 O.OOE+01 O.OOE+01 O.OOE+Ol Ru.106 2.46E+07 1.26E+10 1.94E+08 O.OOE+ 01 3.75E+ 08 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Ag-110M 6.23E+06 4.28E+09 1.13E+07 1.05E+07 2.06E+07 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 -1.36E+07 2.52E+08 1.44E+07 5.66E+05 4.09E+05 1.96E+05 O.OOE+01 O.OOE+01 Sb-124 4.02E+07 2.88E+09 1.01E+08 1.92E+06 O.OOE+00 2.46E+05 7.90E+07 O.OOE+01 Te-127M 6.12E+07 1.68E+09 5.02E+08 1.80E+08 2.04E+09 1.28E+08 O.OOE+01 O.OOE+01 Te-129M 4.71E+Q?, 1.50E+09 2.98E+08 1.11E+08 1.24E+09 1.02E+08 O.OOE+01 O.OOE+01 l-131 6.61E+07 3.04E+07 8.07E+07 1.15E+08 1.98E+08 3.78E+10 O.OOE+01 O.OOE+01 I-132 5.21E+01 2.80E+Ol 5.57E+01 1.49E+02 2.37E+02 5.21E+03 O.OOE+01 O.OOE+01 I-133 1.12E+06 3.30E+06 2.11E+06 3.67E+06 6.40E+06 5.39E+08 O.OOE+01 O.OOE+01 l.135 3.91E+04 1.20E+05 4.05E+04 1.06E+05 1.70E+05 7.00E+06 O.OOE+01 O.OOE+01 Cs-134, 8.83E+09 1.89E+08 4.54E+09 1.08E+10 3.49E+09 O.OOE+01 1.16E+09 O.OOE+01 Cs-136 1.19E+08 1.88E+07 4.19E+07 1.66E+08 9.21E+07 O.OOE+01 1.26E+07 O.OOE+01 Cs-137 5.94E+09 1.76E+08 6.63E+09 9,07E+09 3.08E+09 O.OOE+01 1.02E+09 O.OOE+Ol Ba-140 8.40E+06 2.64E+08 1.28E+08 1.61E+05 5.47E+04 O.OOE+01 9.22E+04 O.OOE+01 Ce-141 1.48E+04 4.99E+08 1.93E+05 1.31E+05 6.07E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ce-144 1.69E+06 1.06E+10 3.15E+07 1.32E+07 7.80E+06 O.OOE+Ol O.OOE+01 O.OOE+01 Hf-181 1.07E+06 7.06E+08 9.51E+06 5.36E+04 4.48E+04 3.41E+04 O.OOE+01 O.OOE+01 'R Values in units of mrem/yr per /rCI/m~ for inhalation and tritium and in units of mrem/yr per yCI/sec per m'or all others. 0 I Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.3-3 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT PATHWAY ~ Veget AGE GROUP ~ Teen Nuclide ~T. Bod Gl-Tract Bone Liver ~Kidne ~Th oid ~Lun Skin H-3 2.61E+03 2.61E+03 O.OOE+Ol 2.61E+03 2.61E+03 2.61E+03 2.61E+03 2.61E+03 P-32 6.80E+07 1.47E+08 1.75E+09 1.09E+08 O.OQE+01 O.OOE+01 O.OQE+01 O.OOE+Ol Cr-51 6.11E+04 1.03E+07 O.OOE+01 O.OOE+01 1.34E+04 3.39E+04 8.72E+04 O.OOE+01 Mn-54 8.79E+07 9.09E+08 O.OOE+01 4.43E+08 1.32E+08 O.OOE+01 O.OQE+01 O.OOE+01 Fe-59 1.60E+08 9.78E+08 1.77E+08 4.14E+08 O.OOE+01 O.OOE+01 1.30E+08 O.OOE+01 Co-58 9.79E+07 5.85E+08 O.OOE+01 4.25E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Co.60 5.57E+08 3.22E+09 O.OQE+01 2.47E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn.65 8.68E+08 7.88E+08 5.36E+08 1.86E+09 1.19E+09 O.OOE+01 O.OOE+01 O.OOE+01 Rb-86 1.30E+08 4.09E+07 O.OQE+Ol 2.76E+08 O.OOE+Ol O.OOE+01 O.OOE+01 O.OOE+Ol Sr<9 4.36E+08 1.81E+09 1.52E+10 O.OOE+Ol 0.005+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 2.0SE+11 2.33E+10 8.32E+11 O.OOE+01 O.OOE+01 O.OQE+01 O.OOE+01 O.OOE+01 Y-91 2.06E+05 3.15E+09 7.68E+06 O.OOE+Ol O.OOE+01 O.OQE+01 O.QOE+01 O.OOE+01 Zr-95 3.68E+05 1.23E+09 1.69E+06 5.35E+05 7.86E+05 O.OOE+01 O.OOE+01 O.OOE+01 Nb.95 5.77E+04 4.48E+08 1.89E+05 1.05E+05 1.02E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 2.90E+06 5.66E+08 6.78E+06 Q,QOE+Ol 2.39E+0? O.OQE+01 O,QQE+Ol O.OQE+01 Ru-106 3.93E+07 1.50E+10 3.12E+08 O.OOE+01 6.02E+08 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 9.39E+06 4.34E+09 1.63E+07 1.54E+07 2.95E+07 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 2.02E+07 2.29E+08 1.91E+07 8.03E+05 5.65E+05 2.63E+05 O.OOE+Ol O.OOE+Ol Sb-124 5.89E+07 3.04E+09 1.51E+08 2.78E+06 O.OOE+01 3.43E+05 1.32E+08 O.OOE+01 Te-127M 9.44E+07 1.98E+09 7.93E+08 2.81E+08 3.22E+09 1.89E+08 O.OOE+01 O.OQE+01 Te-129M 6.79E+07 1.61E+09 4.29E+08 1.59E+08 1.79E+08 1.38E+08 O.OOE+01 O.OOE+01 1-131 5.77E+07 2.13E+07 7.68E+07 1.07E+08 1.85E+08 3.14E+10 O.OOE+01 O.OOE+01 I.132 4.72E+0'l 5.72E+01 5.02E+01 1.31E+02 2.07E+02 4.43E+03 O.OOE+01 O.OQE+01 I-133 1.01E+06 2.51E+06 1.96E+06 3.32E+06 5.83E+06 4.64E+08 O.OOE+01 O.OOE+01 I-135 3.49E+04 1.04E+05 3.66E+04 9.42E+04 1.49E+05 6.06E+06 O.OOE+01 O.OQE+01 Cs-134 7.54E+09 2.02E+08 6.90E+09 1.62E+10 5.16E+09 O.OOE+01 1.97E+09 O.OOE+01 Cs-136 1.13E+08 1.35E+07 4.28E+07 1.68E+08 9.16E+07 O.OQE+Ol 1A4E+07 O.OOE+01 Cs-137 4.90E+09 2.00E+08 1.06E+10 1.41E+10 4.78E+09 O.OOE+01 1.86E+09 O.OOE+01 Ba-140 8.88E+06 2.12E+08 1.38E+08 1.69E+05 5.72E+04 O.OOE+01 1.14E+05 O.OOE+01 Ce-141 2.12E+04 5.29E+08 2.77E+05 1.85E+05 8.70E+04 O.OOE+01 O.OOE+01 O.OQE+01 Ce-144 2.71E+06'.27E+10 5.04E+07 2.09E+07 1.25E+07 O.OOE+01 O.OOE+01 O.OOE+01 Hf-181 1.54E+06 6.90E+0& 1.38E+07 7.58E+04 6.32E+04 4.63E+04 O.OOE+01 O.OQE+01 'R Values in units of mremlyr per yCI/m~ for inhalation and tritium and in units of rnremlyr per IrCI/sec per m'~ for all others. 3-31 Shearon Harris Nuclear Power Plane (SHNPP) June l994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.3c4 R VALUES FOR THE SHEARQN HARRIS NUCLEAR POWER PLANT'GE PATHWAY ~ Veget GROUP ~ Child Nuclide ~T. Bcd Gi.Truce B e U er ~Kidce ~Th cid ~L Skin H.3 4.04E+03 4.04E+03 O.OOE+01 4.04E+03 4.04E+03 4.04E+03 4.04E+03 4.04E+03 P-32 1.42E+08 1.01E+08 3.67E+09 1.72E+08 O.OOE+Ol Q.OOE+01 O.OOE+01 Q.OOE+01 Cre51 1.16E+05 6.15E+06 O.OOE+Ol O.OOE+Ol 1.76E+04 6.44E+04 1.18E+05 O.OOE+01 Mn-54 1.73E+08 5.44E+08 O.OOE+01 6.49E+08 1.82E+08 O.OOE+01 O.OOE+01 O.OOE+01 Fe.59 3.17E+08 6.62E+08 3.93E+08 6.36E+08 O.OOE+01 O.OOE+01 1.84E+08 O.OOE+01 Co-58 1.92E+08 3.66E+08 O.OOE+01 6.27E+07 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+Ol Co.60 1.11E+09 2.08E+09 O.OOE+01 3.76E+08 O.OOE+01 O.OOE+01 O.QOE+01 O.OOE+01 Zn.65 1.70E+09 4.81E+08 1.03E+09 2.74E+09 1.73E+09 O.OOE+01 O.OOE+01 O.OOE+01 Rb.86 2.81E+08 2.94E+07 O.OOE+01 4.56E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-89 1.03E+09 1.40E+09 3.62E+10 O.OOE+01 0;OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 3.49E+11 1.86E+10 1.38E+12 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+Ol O.OOE+01 Y-91 4.89E+05 2.44E+09 1.83E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 7A4E+05 8.71E+08 3.80E+06 8.35E+05 1.20E+06 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 1.12E+05 2.91E+08 4.04E+05 1.57E+05 1.48E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 5.86E+06 3.94E+08 1.52E+0? Q,OOE+Ol 3.84E+Q7 Q.OOE+Ol O.OOE+Ol O.OOE+01 Ru-106 9.38E+07 1.17E+ 10 7.52EPOB O.OOE+01 1.02E+09 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 1.87E+07 2.78E+09 3.46E+07 2.34E+07 4.35E+07 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 3.97E+07 1.45E+08 3.64E+07 1.18E+06 8.09E+05 4.82E+05 O.OOE+01 O.OOE+Ol Sb-124 1.21E+08 2.16E+09 3.44E+08 4.47E+06 O.OOE+01 7.61E+05 1.91E+08 O.OOE+01 Te-127M 2.26E+08 1.54E+09 1.90E+09 5.12E+08 5.42E+09 4.55E+08 O.OOE+01 O.OOE+01 Te-129M 1.5SE+08 1.22E+09 9.98E+08 2.79E+08 2.93E+09 3.22E+08 O.OOE+01 O.OOE+01 I-131 8.16E+07 1.23E+07 1.43E+08 1.44E+08 2.36E+08 4.75E+10 O.OOE+01 O.OOE+01 I-132 7.53E+01 1.93E+02 8.91E+01 1.64E+02 2.51E+02 7.60E+03 O.OOE+01 O.OOE+01 I-133 1.67E+06 1.78E+06 3.57E+06 4.42E+06 7.36E+06 8.21E+08 O.OOE+01 O.OOE+01 I-135 5.54E+04 8.92E+04 6.50E+04 1.17E+05 1.79E+05 1.04E+07 O.OOE+01 O.OOE+01 Cs-134 5.40E+09 1.38E+08 1.56E+10 2.56E+10 7.93E+09 O.OOE+01 2.84E+09 O.OOE+01 Cse136 1.43E+08 7.77E+06 8.04E+07 2.21E+08 1.18E+08 O.OOE+01 1.76E+07 O.OOE+01 Cs-137 3.52E+09 1.50E+08 2.49E+10 2.39E+10 7.78E+09 O.OOE+01 2.80E+09 O.OOE+01 Ba-140 1.61E+07 1.40E+08 2.76E+08 2.42E+05 7.87E+04 O.OOE+01 1.44E+05 O.OOE+01 Ce-141 4.?SE+04 3.99E+08 6.42E+05 3.20E+05 1.40E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ce-144 6.49E+06 9.94E+09 1.22E+08 3.81E+07 2.11E+07 O.OOE+01 O.OOE+01 O.OOE+01 Hf-181 3.15E+06 5.17E+08 3.13E+07 1.22E+05 9.78E+04 1.03E+05 O.OOE+01 O.OOE+01 'R Values in units of mrern/yr per /rCI/m for inhalation and tritium and in units of mrem/yr per yCI/sec per m'or aII others. 3-32 ,), b h Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.3-6 R VALUES FOR THE SHEARON HARRIS NUCLFAR POWER PLANT PATHWAY ~ Meat AGE GROUP ~ Adult Nuclide ~Kidne ~Th roid ~Lun Skin H-3 3.27E+02 3.27E+02 O.OOE+01 3.27E+02 3.27E+02 3.27E+02 3.27E+02 3.27E+02 P-32 1.18E+08 3.43E+08 3,05E+09 1.89E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 4.27E+03 1.08E+06 O.OOE+01 O.OOE+01 9.42E+02 2.56E+03 5.67E+03 O.OOE+01 Mn-54 1.06E+06 1.71E+07 O.OOE+01 5.57E+06 1.66E+06 O.OOE+01 O.OOE+01 O.OOE+01 Fe-59 1.43E+08 1.25E+09 1.59E+08 3.74E+08 O.OOE+01 O.OOE+01 1.04E+08 O.OOE+01 Co-58 2.43E+07 2.20E+08 O.OOE+01 1.08E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Co-60 1.03E+08 8.76E+08 O.OOE+01 4.66E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn-65 3.58E+08 4.98E+08 2.49E+08 7.91E+08 5.29E+08 O.OOE+01 O.OOE+01 O.OOE+01 Rb-86 1 A2E+08 B.OOE+ 07 O.OOE+ 01 3.04E+ 08 O.OOE+ 01 O.OOE+01 O.OOE+01 O.OOE+ 01 Sr-89 5.23E+06 2.92E+07 . 1.82E t08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE t 01 O.OOE+01 Sr-90 2.02E+09 2.38E+08 8.22E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Y-91 1.8OE+04 3.71E+08 6.75E+05 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 2.43E+05 1.14E+09 1.12E+06 3.59E+05 5.64E+05 O.OOE+01 O.OOE+01 O.OOE+01 Nb.95 4.12E+05 4.65E+09 1.38E+06 7.66E+05 7.68E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 2.72E+07 7.38E+09 6.32E+07 O.OOE+01 2A1E+08 O.OOE+01 O.OOE+01 O.OOE+01 Ru-106 2.19E+08 1.12E+11 1.73E+09 O.OOE+01 3.35E+09 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 2.34E+06 1.61E+09 4.27E+06 3.95E+06 7.76E+06 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 2.80E+07 5.19E+0& 2.9?E+07 1.15E+06 SAOE+05 4.03E+05 O.OOE+01 O.OOE+01 Sb-124 4.72E+06 3.38E+08 1.19E+07 2.25E+05 O.OOE+01 2.88E+04 9.27E+06 O.OOE+01 Te-127M 1.00E+08 2.76E+09 8.22E+08 2.94E+08 3.34E+09 2.10E+08 O.OOE+01 O.OOE+01 Te-129M 1.17E+08 3.73E+09 7AOE+08 2.76E+08 3.09E+09 2.54E+08 O.OOE+01 O.OOE+01 I-131 5.77E+06 2.66E+06 7.04E+06 1.01E+07 1.73E+07 3.30E+09 O.OOE+01 O.OOE+01 I-133 1.51E-01 4.46E-01 2.85E-01 4.96E-01 8.66E-01 7.29E+01 O.OOE+01 O.OOE+01 I-135 6.07E-17 1.86E-16 6.28E-17 1.64E-16 2.64E-16 1.08E-14 O.OOE+01 O.OOE+01 Cs-134 7.81E+08 1.67E+07 4.01E+08 9.55E+08 3.09E+08 O.OOE+01 1.03E+08 O.OOE+01 Cs-136 2.14E+07 3.33E+06 7.53E+06 2.97E+07, 1.65E+07 O.OOE+01 2.27E+06 O.OOE+01 Cs-137 4.99E+08 1.47E+07 6.57E+08 7.61E+08 2.58E+08 O.OOE+01 8.59E+07 O.OOE+01 Ba-140 1.20E+06 3.77E+07 1.83E+07 2.30E+04 7.82E+03 O.OOE+01 1.32E+04 O.OOE+01 Ce-141 6.46E+02 2.18E+07 8.42E+03 5.69E+03 2.65E+03 O.OOE+01 O.OOE+01 O.OOE+01 Ce-144 4.70E+04 2.96E+08 8.75E+05 3.6BE+05 2.17E+05 O.OOE+0'I O.OOE+01 O.OOE+01 Hf-181 1.525+06 9.97E+08 1.34E+07 7.57E+04 6.33E+04 4.81E+04 O.OOE+01 O.OOE+01 'R Values in units of mrem/yr per /rCI/ms for inhalation and tritium and in units of mrem/yr per /rCI/sec per mr for all others. 3-33 8 ~ j Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.3W R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'ATHWAY ~ Meat AGE GROUP ~ Teen Nuclide ~T. Bod Gl-Tract Bone Liver ~Kidne ~Th oid ~Lun Skin H-3 1.95E+02 1.95E+02 O.OOE+01 1.95E+02 1.95E+02 1.95E+02 1.95E+02 1.95E+02 P-32 9.98E+07 2.16E+08 2.58E+09 1.60E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 3.42E+03 5.75E+05 O.OQE+01 O.OOE+01 7.49E+02 1.90E+03 4.88E+03 O.OOE+01 Mn.54 8.43E+05 8.72E+06 O.OOE+01 4.25E+06 1.27E+06 O,OOE+01 O.OOE+01 O.OOE+01 Fe.59 1.15E+08 7.02E+08 1.27E+08 2.97E+08 O.OOE+01 O.OOE+01 9.36E+07 O.OQE+01 Co-58 1.93E+07 1.15E+08 O.OOE+01 8.36E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Co-60 8.15E+07 4.71E+08 O.OOE+01 3.62E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn 65 2.83E+08 2.57E+08 1.75E+08 6.07E+08 3.89E+08 O.OOE+01 O.OOE+01 O.OOE+01 Rb-86 1.19E+08 3.76E+07 O.OOE+01 2.54E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 'r.89 4.40E+06 1.83E+07, 1.54E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 1.31E'+09 1.49E+08 5.32E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Y-91 1.52E+04 2.33E+OB 5.68E+05 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 1.95E+05 6.53E+08 8.97E+05 2.83E+05 4.16E+05 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 3.29E+05 2.55E+09 1.08E+06 5.97E+05 5.79Et05 O.OQE+01 O.OOE+01 O.OOE+01 RU-103 2.20E+0? 4.30E+09 5.15E+Q7 Q.OOE+Ql 1.82E+08 O.OOE+01 O.OQE+Ol O.OOE+Ol Ru-106 1.84E+08 7.00E+10 1.46E+09 O.OOE+01 2.81E+09 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 1.86E+06 B.SBE+08 3.23E+06 3.06E+06 5.83E+06 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 2.22E+07 2.51E+08 2.09E+07 B.BOE+05 6.19E+05 2.88E+05 O.OOE+01 O.OOE+Q1 Sb-124 3.80E+06 1.96E+08 9.73E+06 1.79E+05 O.OOE+01 2.21E+04 8.50E+06 O.OOE+01 Te-127M 8.25E+07 1.73E+09 6.94E+08 2.46E+08 2.81E+09 1.65E+08 O.OOE+01 O.OQE+01 Te-129M 9.81E+07 2.33E+09 6.20E+08 2.30E+08 2.59E t 09 2.00E+08 O.OOE+01 O.OOE+01 I-131 4.40E+06 1.62E+06 5,85E+06 8.20E+06 1.41E+07 2.39E+09 O.OOE+01 O.OOE+01 I-133 1.23E-01 3.06E-01 2.39E-01 4.05E-01 7.10E-01 5.65E+01 O.OOE+01 O.OOE+01 l-135 4.88E-17 1.46E-16 5.11E-17 1.32E-16 2.08E-16 8.46E-15 O.OOE+01 O.OOE+01 Cs-134 3.48E+08 9.34E+06 3.19E+08 7.51E+08 2.39E+08 O.OOE+01 9.11E+07 O.OOE+01 Cs-136 1.55E+07 1.86E+06 5.87E+06 2.31E+07 1.26E+07 O.OOE+Ol 1.98E+06 O.OOE+01 Cs-137 2.14E+08 8.75E+06 4.62E+08 6.15E+08 2.09E+08 O.OOE+01 8.13E+07 O.OOE+01 Ba-140 9.76E+05 '.34E+07 1.51E+07 1.86E+04 6.29E+03 O.OOE+01 1.25E+04 O.OOE+01 Ce-141 5.42E+02 1.35E+07 7.07E+03 4.72E+03 2.22E+03 O.OOE+01 O.OOE+01 O.OOE+01 Ce-144 3.96E+04 1.85E+08 7.37E+05 3.05E+05 1.82E+05 O.OOE+01 O.OOE+01 O.OOE+01 Hf-181 1.22E+06 5.50E+08 1.10E+07 6.05E+04 5.04E+04 3.69E+04 O.OQE+01 O.OOE+01 'R Values in units of mrem/yr per /rCI/ms for inhalation and tritium and in units of rnrem/yr per /rCI/sec per m'~ for all others. 3-34 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.3-7 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT PATHWAY ~ Meat AGE GROUP ~ Child Nuclide ~Kidne ~Th o id ~Lun Skin H-3 2.36E+02 2.36E+02 O.OOE+01 2.36E+02 2.36E+02 2.36E+02 2.36E+02 2.36E+02 P-32 1.87E+08 1.34E+08 4.86E+09 2,27E+08 O,OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 5.33E+03 2.83E+05 O.OOE+01 O.OOE+01 8.09E+02 2.96E+03 5.40E+03 O.OOE+01 Mn.54 1.30E+06 4.08E+06 O.OOE+01 4.86E+06 1.36E+06 O.OOE+01 O.OOE+01 O.OOE+01 Fe-59 1.82E+08 3.80E+08 2.25E+08 3.65E+08 O.OOE+01 O.OOE+01 1.06E+08 O.OOE+01 Co-58 2.99E+07 5.70E+07 O.OOE+01 9.76E+06 O.OOE+Ol O.OOE+01 O.OOE+01 O.OOE+01 Co-60 1.27E+08 2.38E+08 O.OOE+01 4.30E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn-65 4.35E+08 1.23E+08 2.62E+08 6.99E+08 4.40E+08 O.OOE+01 O.OOE+01 O.OOE+01 Rb.86 2.21E+08 2.32E+07 O.OOE+01 3.60E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-89 8.31E+06 1.13E+07 2.91E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 1.74E+09 9.26E+07 6.87E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Y-91 2.87E+04 1.43E+08 1.07E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 3.12E+05 3.65E+08 1.59E+06 3.50E+05 5.01E+05 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 5.17E+05 1.34E+09 1.86E+06 7.23E+05 6.80E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 3.58E+07 2.41E+09 9.31E+07 O.OOE+01 2.34E+08 O.OOE+Ol O.OOE+01 O.OOE+01 Ru-106 3A3E+08 4.27E+10 2.75E+09 O.OOE+01 3.71E+09 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 2.89E+06 4.30E+08 5.36E+06 3.62E+06 6.74E+06 O.OOE+01 O.005+ 01 O.OOE+01 Sn-113 3.42E+07 1.25E+08 3.14E+07 1.01E+06 6.97E+05 4.15E+05 O.OOE+01 O.OOE+01 Sb-124 6.17E+06 1.10E+08 1.76E+07 2.28E+05 O.OOE+01 3.88E+04 9.77E+06 O.OOE+01 Te-127M 1.55E+08 1.06E+09 1.31E+09 3.52E+08 3.73E+09 3.13E+08 O.OOE+01 O.OOE+0'I Te-129M 1.81E+08 1.42E+09 1.17E+09 3.26E+08 3.43E+09 3.77E+08 O.OOE+01 O.OOE+01 1-131 6.20E+06 9.72E+05 1.09E+07 1.09E+07 1.79E+07 3.61E+09 O.OOE+01 O.OOE+01 I-133 2.07E-01 2.21E-01 4.43E-01 5.48E-01 9.13E-01 1.02E+02 O.OOE+01 O.OOE+01 l-135 7.87E-17 1.27E-16 9.25E-17 1.66E-16 2.55E-16 1.47E-14 O.OOE+01 O.OOE+01 Cs-134 1.95E+08 4.93E+06 5.63E+08 9.23E+08 2.86E+08 O.OOE+01 1.03E+08 O.OOE+01 Cs-136 1.80E+07 9.78E+05 1.01E+07 2.78E+07 1.48E+07 O.OOE+01 2.21E+06 O.OOE+01 Cs-137 1.20E+08 5.10E+06 8.51E+08 8.15E+08 2.65E+08 O.OOE+01 9.55E+07 O.OOE+01 Ba-140 1.63E+06 1.42E+07 2.80E+07 2.45E+04 7.97E+03 O.OOE+01 1.46E+04 O.OOE+01 Ce-141 9.86E+02 8.28E+06 1.33E+04 6.64E+03 2.91E+03 O.OOE+01 O.OOE+01 O.OOE+01 Ce-144 7.42E+04 1.14E+08 1.39E+06 4.36E+05 2.4'IE+05 O.OOE+01 O.OOE+01 O.OOE+01 HM81 2.02E+06 3.31E+08 2.00E+07 7.79E+04 6.26E+04 6.56E+04 O.OOE+01 O.OOE+01 'R Values inunits of mrem/yr per pCi/ms for inhalation and tritium and in units of mrem/yr per/rCI/sec per m'~ for all others. 3-35 S li Shearon Harris Huclear power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.3-8 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANTi PATHWAY ~ Cow Milk AGE GROUP ~ Adult Nuclide ~T. Bod Gl-Tract Bone Li er ~Kine ~Th old H-3 7.69E+02 7.69E+02 O.OOE+01 7.69E+02 7.69E+02 7.69E+02 7.69E+02 /.69E+02 P-32 4.32E+08 1.26E+09 1.12E+10 6.95E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 1.73E+04 4.36E+06 O.OOE+01 O.OOE+01 3.82E+03 1.04E+04 2.30E+04 O.OOE+01 Mn-54 9.76E+05 1.57E+07 O.OOE+01 5.11E+06 1.52E+06 O.OOE+01 O.OOE-01 O.OOE+01 Fe.59 1.60E+07 1.39E+08 1.77E+07 4.17E+07 O.OOE+01 O.OOE+01 1.17E+07 O.OOE+01 Co-58 6.28E+06 5.68E+07 O.OOE+01 2.8OE+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Co 60 2.24E+07 1.91E+08 O.OOE+01 1.02E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn-65 1.38E+09 1.92E+09 9.59E+08 3.05E+09 2.04E+09 O.OOE+01 O.OOE+01 O.OOE+01 Rb-86 7.54E+08 3.19E+08 O.OOE+01 1.62E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 'r-89 2.50E+07 1.40E+08 8.70E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 7.59E'+09 8.94E+08 3.09E+10 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+01 O.OOE+01 Y-91 1.37E+02 2.81E+06 5.11E+03 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+Ol Zr-95 1.22E+02 5.71E+05 5.62E+02 1.80E+02 2.83E+02 O.OOE+01 O.OOE+01 O.OOE+Ol Nb-95 1.48E+04 1.67E+08 4.95E+04 2.75E+04 2.72E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 2.63E+02 7.14E+04 6,11E+02 O.QOE+Ol 2,33E+03 O.OOE+Ol O.OOE+Ol O.OOE+01 Ru-106 1.60E+03 8.17E+05 1.26E+04 O.OOE+01 2.44E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 2.04E+07 1.40E+10 3.71E+07 3A4E+07 6.76E+07 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 1.32E+06 2.44E+07 1.40E+06 5.41E+04 3.95E+04 1.90E+04 O.OOE+Ol O.OOE+Ol Sb-124 6.14E+06 4.39E+08 1.55E+07 2.92E+05 O.OOE+01 3.75E+04 1.20E+07 O.OOE+01 Te-127M 4.11E+06 1.13E+08 3.37E+07 1.21E+07 1.37E+08 8.62E+06 O.OOE+01 O.OOE+01 Te.129M 6.19E+06 1.97E+08 3.91E+07 1.46E+07 1.63E+08 1.34E+07 O.OOE+01 O.OOE+01 1-131 1.59E+08 7.32E+07 1.94E+08 2.77E+08 4.76E+08 9.09E+10 O.OOE+01 O.OOE+01 I-132 'I.03E+01 5.51E-02 1.10E+01 2.93E+01 4.67E+01 1.03E+01 O.OOE+01 O.OOE+01 I-133 1.40E+06 4.13E+06 2.64E+06 4.59E+06 8.01E+06 6.75E+08 O.OOE+01 O.OOE+01 I-135 9.03E+03 2.76E+04 9.34E+03 2.45E+04 3.92E+04 1.61E+06 O.OOE+01 O.OOE+01 Cs-134 6.7'IE+09 1A4E+08 3.45E+09 3.21E+09 2.66E+09 O.OOE+0'I 8.82E+08 O.OOE+Ol Cs-136 4.73E+08 7.46E+07 1.66E+08 6.57E+08 3.65E+08 O.OOE+01 5.01E+07 O.OOE+01 Cs-137 4.22E+09 1.25E+08 4.71E+09 6A4E+09 2.19E+09 O.OOE+01 7.27E+08 O.OOE+01 Ba-140 1.12E+06 3.53E+07 1.71E+07 2.15E+04 7.32E+03 O.OOE+01 1.23E+04 O.OOE+01 Ce-141 2.23E+02 7.52E+06 2.91E+03 1.97E+03 9.14E+02 O.OOE+01 O.OOE+01 O.OOE+01 Ce-144 1.15E+04 1.265+07 2.15E+05 8.97E+04 5.32E+04 O.OOE+01 O.OOE+01 O.OOE+01 Hf-181 6.68E+02 4.38E+05 3.33E+Ol 2.?9E+01 2.12E+Ol O.OOE+01 O.OOE+01 /rCI/m'.91E+03 'R Values in units of mrern/yr per for inhalation and tritium and in units of mrem/yr per yCI/sec per m for all others. 3- 36 4< Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3,3.9 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT PATHWAY ~ Cow Milk AGE GROUP I Teen Nuclide Li er ~Kid e ~Th aid H-3 1.00E+03 1.00E+03 O.OOE+01 1.00E+03 1.00E+03 1.00E+03 1.00E+03 1.00E+03 P-32 B.OOE+08 1.73E+09 2.06E+10 1.28E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr.51 3.02E+04 5.08E+06 O.OOE+01 O.OOE+01 6.63E+03 1.68E+04 4.32E+04 O.OOE+01 Mn-54 1.69E+06 1.75E+07 O.OOE+01 8.52E+06 2.54E+06 O.OOE+01 O.OOE+01 O.OOE+01 U Fe.59 2.79E+07 1.71E+08 3.10E+07 7.23E+07 O.OOE+01 O.OOE+01 2.28E+07 O.OOE+01 Co-58 1.09E+07 6.50E+07 O.OOE+01 4.72E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Co-60 3.88E+07 2.25E+08 O.OOE+01 1.72E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn-65 2.38E+09 2.16E+09 1.47E+09 5.11E+09 3.27E+09 O.OOE+01 O.OOE+01 O.OOE+01 Rb.86 1.39E+09 4.37E+08 O.OOE+01 2.95E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-89 4.59E+07 1.91E+08 1.60E+09 O.OOE+01 0;OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 1.08E'+10 1.23E+09 4.37E+10 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Y-91 2.52E+02 3.85E+06 9.40E+03 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 2.13E+02 7.16E+05 9.83E+02 3.10E+02 4.56E+02 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 2.58E+04 2.00E+08 8.45E+04 4.68E+04 4.54E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 4.65E+02 9.08E+04 1.09E+03 O.OOE+01 3.83E+03 O.OOE+01 O.OOE+01 O.OOE+01 Ru-106 2.93E+03 1.11E+06 2.32E+04 O.OOE+01 4.48E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ag.110M 3.53E+07 1.63E+10 6.14E+07 5.81E+07 1.11E+08 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 2.28E+06 2.58E+07 2.15E+06 9.06E+04 6.37E+04 2.97E+04 O.OOE+Ol O.OOE+01 Sb-124 1.08E+07 5.56E+08 2.76E+07 5.08E+05 O.OOE+01 6.26E+04 2A1E+07 O.OOE+01 Te-127M 7.39E+06 'l.55E+08 6.22E+07 2.21E+07 2.52E+08 1.48E+07 O.OOE+01 O.OOE+01 Te-129M 1.13E+07 2.69E+08 7.15E+07 2.65E+07 2.99E+08 2.31E+07 O.OOE+01 O.OOE+01 I-131 2.65E+08 9.75E+07 3.52E+08 4.93E+08 8.48E+08 1.44E+11 O.OOE+01 O.OOE+01 I-132 1.83E+01 2.22E+01 1.94E+01 5.09E+01 8.02E+01 1.71E+01 O.OOE+01 O.OOE+01 I-133 2.49E+06 6.19E+06 4.82E+06 8.18E+06 1.43E+07 1.14E+09 O.OOE+01 O.OOE+01 I-135 1.58E+04 4.74E+04 1.66E+04 4.27E+04 6.75E+04 2.75E+06 O.OOE+01 O.OOE+01 Cs-134 6.54E+09 1.75E+08 5.99E+09 1.41E+10 4.48E+09 O.OOE+01 1.71E+09 O.OOE+01 Cs-136 7.48E+08 8.97E+07 2.83E+08 1.11E+09 6.07E+08 O.OOE+01 9.56E+07 O.OOE+01 Cs-137 3.96E+09 1.62E+08 8.54E+09 1.14E+10 3.87E+09 O.OOE+01 1.50E+09 O.OOE+01 Ba-140 1.99E+06 4.77E+07 3.09E+07 3.79E+04 1.28E+04 O.OOE+01 2.55E+04 O.OOE+01 Ce-141 4.09E+02 1.02E+07 5.33E+03 3.56E+03 1.68E+03 O.OOE+01 O.OOE+01 O.OOE+01 ~ ~ Ce-144 2.12E+04 9.93E+07 3.95E+05 1.63E+05 9.76E+04 O.OOE+01 O.OOE+01 O.OOE+01 Hf-181 1.18E+03 5.28E+05 1.06E+04 5.82E+01 4.84E+01 3.55E+01 O.OOE+01 O.OOE+01 'R Values in units of mrem/yr per /rCI/m~ for Inhalation and tritium and in units of mrem/yr per /rCI/sec per m s for all others. 3-37 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.3.10 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT~ PATHWAY I Cow Milk AGE GROUP I Child Nuclide ~T. Bod Gl-Tract Bone Liver ~Kidne T~hraid ~Lun Skin H-3 1.58E+03 1.58E+03 O.OOE+01 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 P-32 1.96E+09 1.41E+09 5.09E+10 2.38E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 6.17E+04 3.27E+06 O.OOE+01 O.OOE+01 9.36E+03 3.42E+04 6.25E+04 O.OOE+01 Mn.54 3.39E+06 1.07E+07 O.OOE+01 1.27E+07 3.57E+06 O.OOE+01 O.OOE+01 O.OOE+01 Fe-59 5.79E+07 1.21E+08 7.18E+07 1.16E+08 O.OOE+Ol O.OOE+01 3.37E+07 O.OOE+01 Co.58 2.21E+07 4.20E+07 O.OOE+Ol 7.21E+06 O.OOE+Ol O.OOE+01 O.OOE+01 O.OOE+01 Co-60 7.90E+07 1.48E+08 O.OOE+01 2.68E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn.65 4.79E+09 1.35E+09 2.89E+09 7.70E+09 4.85E+09 O.OOE+01 O.OOE+01 O.OOE+01 Rb-86 3.36E+09 3.52E+08 '.OOE+01 5.47E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-89 1.13E+08 1.54E+08 3.97E+09 O.OOE+01 0.005+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 1.87B+10 9.95E+08 7.38E+10 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Y-91 6.21E+02 3.09E+06 2.32E+04 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 4.47E+02 5.23E+05 2.28E+03 5.02E+02 7.18E+02 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 5.31E+04 1.37E+08 1.91E+05 7.42E+04 6.98E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 9.88E+02 6.65E+04 2.57E+03 O.OOE+01 6.47E+03 O.OOE+01 O.OOE+Ol O.OOE+01 Ru-106 7.14E+03 8.90E+05 5.72E+04 O.OOE+01 7.72E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 7.19E+07 1.07E+10 1.33E+08 9.00E+07 1.68E+08 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 4.61E+05 1.69E+06 4.22E+05 1.36E+04 9.37E+03 5.58E+03 O.OOE+01 O.OOE+01 Sb-124 2.29E+07 4.09E+08 6.53E+07 8.47E+05 O.OOE+01 1A4E+05 3.62E+07 O.OOE+01 Te-127M 1.82E+07 1.24E+08 1.53E+08 4.13E+07 4.37E+08 3.66E+07 O.OOE+01 O.OOE+01 Te-129M 2.74E+07 2.15E+08 1.76E+08 4.92E+07 5.18E+08 5.68E+07 O.OOE+01 O.OOE+01 I ~ 131 4.88E+08 7.64E+07 8.54E+08 8.59E+08 1.41E+09 2.84E+11 O.OOE+01 O.OOE+01 I-132 3.89E+Ol 9.95E+01 4.60E+01 8.45E+01 1.29E+00 3.92E+01 O.OOE+01 O.OOE+01 1-133 5.48E+06 5.84E+06 1.17E+07 1.45E+07 2.41E+07 2.69E+09 O.OOE+01 O.OOE+01 I-135 3.35E+04 5.39E+04 3.93E+04 7.07E+04 1.08E+05 6.26E+06 O.OOE+01 O.OOE+01 Cs-134 4.78E+09 1.22E+08 1.38E+10 2.27E+10 7.03E+09 O.OOE+01 2.52E+09 O.OOE+01 Cs-136 1.14E+09 6.17E+07 6.39E+08 1.76E+09 9.36E+08 O.OOE+01 1.40E+08 O.OOE+01 Cs-137 2.91E+09 1.23E+08 2.06E+10 1.97E+10 6.42E+09 O.OOE+01 2.31E+09 O.OOE+01 Ba-140 4.36E+06 3.78E+07 7.47E+07 6.54E+04 2.13E+04 O.OOE+Ol 3.90E+04 O.OOE+01 Ce-141 9.73E+02 8.17E+06 1.31E+04 6.55E+03 2.87E+03 O.OOE+01 O.OOE+01 O.OOE+01 Ce-144 5.20E+04 7,.96E+07 9.74E+05 3.05E+05 1.69E+05 O.OOE+01 O.OOE+01 O.OOE+01 Hf-181 2.53E+03 4.16E+05 9.79E+01 7.86E+01 8.24E+01 O.OOE+01 O.OOE+01 /rCI/m'.51E+04 'R Values in units of mrem/yr per for inhalation and tritium and in units of mrem/yr per yCI/sec per m'~ for all others. 3-3B Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. TABLE 3.3-11 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT~ PATHWAY ~ Cow Milk AGE GROUP ~ Intent l.iver ~Kidne Typhoid H-3 2.40E+03 2.40E+03 O.OOE+01 2.40E+03 2.40E+03 2.40E+03 2.40E+03 2.40E+03 P-32 4.06E+09 1.42E+09 1.05E+ 11 6.1 7E+09 O.005+ 01 O.OOE+01 O.OOE+01 O.OOE+ 01 Cr-51 9.77E+04 2.85E+06 O.OOE+01 O.OOE+01 1.39E+04 6.38E+04 1.24E+05 O.OOE+01 Mn-54 5.3?E+06 8.?1E+06 O.OOE+Q1 2.37E+07 5.25E+06 O.OQE+01 O.OOE+Qt O.OQE+01 Fe-59 9.23E+07 1.12E+08 1.34E+08 2.34E+08 O.OOE+01 O.OOE+01 6.92E+07 O.OOE+01 e Co.58 3.60E+07 3.59E+07 O.OOE+01 1A4E+07 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+01 Co-60 1.29E+08 1.30E+08 O.OQE+0'I 5.47E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn-65 6.14E+09 1.12E+10 3.88E+09 1.33E+10 6.45E+09 O.OOE+01 O.OOE+01 O.OOE+01 Rb.86 6.86E+09 3.55E+08 O.OOE+01 1.39E+10 O.OOE+01 O.OQE+01 O.OOE+01 O.OOE+01 'r-89 2.17E+08 1.55E+08 7.55E+09 O.OOE+01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+01 e Sr-90 2.05E+ 10 1.00E+09 8.04E+ 10 O.OOE+01 O.OOE+01 O.OOE+01 O.OOF+01 O.OOE+01 Y-91 1.16E+08 3.12E+06 4.36E+04 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 7.01E+02 4.92E+05 4.05E+03 9.88E+02 1.06E+03 O.OOE+01 O.OOE+01 O.OOE+01 Nb.95 8.48E+04 1.24E+08 3.56E+05 1.47E+05 'l.05E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 1.?4E+Q3 6,33E+04 5.21E+03 O.OOE+01 1.0BE+04 O.QQE+01 O.OOE+01 O.OQE+01 Ru-106 1.47E+04 8.95E+05 1.18E+05 O.OOE+01 1.39E+05 O.OQE+01 O.005+ 01 O.OOE+01 Ag-110M 1.19E+08 9.32E+09 2.46E+08 1.80E+08 2.57E+08 O.OQE+01 O.OOE+01 O.OOE+01 Sn-113 6.65E+06 1.37E+07 6.45E+06 2.45E+05 1.31E+05 9.34E+04 O.OOE+01 O.OOE+01 Sb-124 3.90E+07 3.88E+08 1.26E+08 1.85E+06 O.OOE+01 3.34E+Q5 7.88E+0? O.OOE+01 Te-127M 3.75E+07 1.25E+08 3.10E+08 1.03E+08 7.64E+08 8.96E+07 O.OOE+01 O.OOE+Ol Te-129M 5.575+07 . 2.16E+08 3.62E+08 1.24E+08 9.05E+08 1.39E+08 O.OQE+01 O.OOE+01 I-131 9.23E+08 7.49E+07 1.78E+09 2.10E+09 2.45E+09 6.90E+11 O.OOE+01 O.OOE+01 I-132 6.90E+01 1.5?E-OO 9.55E+01 1.94Et00 2.16E+00 9.09E+01 O.OOE+01 O.OOE+01 I-133 1.05E+07 6.09E+06 2.47E+07 3.60E+07 4.23E+07 6.55E+09 O.OOE+01 O.OOE+01 l-135 5.93E+04 5.88E+04 8.17E+04 1.63E+05 1.81E+05 1.46E+07 O.OOE+01 O.OOE+01 Cs-134 4.19E+Q9 1.13E+0& 2.23E+10 4.15E+10 1.07E+10 O.OQE+01 4.3BE+09 O.OQE+01 Cs-136 ~ 1.37E+09 5.58E+07 1.25E+09 3.67E+09 1.46E+09 O.OOE+01 2.99E+08 O.OOE+01 Cs-137 2.72E+ 09 1.20E+ 08 3.28E+ 10 3.84E+ 10 1.03E+ 10 O.OQE+ 01 4.1 BE+ 09 O.OOE+ 01 Ba-140 7.91E+06 3.77E+07 1.54E+08 1.54E+05 3.65E+04 O.OOE+01 9.43E+04 O.OOE+01 Ce-141 1.87E+03 8.21E+06 2.60E+04 1.59E+04 4.90E+03 O.OOE+Ol O.OQE+Ol O.OOE+01 Ce-144 7.82E+04'.01E+07 1.40E+06 5.71E+05 2.31E+05 O.OOE+01 O.OOE+01 O.OOE+01 Hf-181 4.23E+03 3.93E+05 4.78E+04 2.26E+02 1.32E+02 1.91E+02 O.OOE+01 O.OOE+01 'R Values in units of mrem/yr per yCI/ms for inhalation snd tritium snd in units of mrem/yr per yCI/sec per m't for ell others. 3-39 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.3-12 R VALUES PQR THE SHEARON HARRIS NUCLEAR POWER PLANT PATHWAY ~ Goat Milk AGE GROUP ~ Adult Nuclide ~Kidoe ~Th roid ~Lo Skin H-3 1.57E+03 1.57E+03 O.OOE+01 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 P-32 5.19E+08 1.51E+09 1.34E+10 8.34E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 2.08E+03 5.23E+05 O.005+ 01 O.OOE+01 4.58E+02 1.24E+03 2.76E+03 O.OOE+01 Mn.54 1.17E+05 1.88E+06 O.OOE+01 6.14E+05 1.83E+05 O.OOE+01 O.OOE+01 O.OOE+01 Fe-59 2.08E+05 1.81E+06 2.31E+05 5.42E+05 O.OOE+01 O.OOE+01 1.51E+05 O.OOE+01 Co-58 7.54E+05 6.82E+06 O.OOE+01 3.36E+05 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+Ol Co-60 2.69E+06 2.29E+07 O.OOE+01 1.22E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+Ol Zn-65 1.65E+08 2.31E+08 1.15E+08 3.66E+08 2.45E+08 O.OOE+01 O.OOE+01 O.OOE+01 Rb-86 9.05E+07 3.83E+07 O.OOE+Ol 1.94E+08 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+01 'r-89 5.24E+07 2.93E+08 1.83E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 1.59E+10 1.88E+09 6.49E+10 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Y-91" 1.64E+01 3.37E+05 6.13E+02 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 1.46E+01 6.85E+04 6.74E+Ol 2.16E+01 3.39E+01 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 1.78E+03 2.01E+07 5.94E+03 3.31E+03 3.27E+03 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 3.16E+01 8.56E+03 7.33E+01 O.OOE+01 2.80E+02 O.OOE+01 O.OOE+Ol O.OOE+01 Ru-106 1.92E+02 9.81E+04 1.52E+03 O.OOE+01 2.93E+03 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 2.45E+06 1.68E+09 4.46E+06 4.12E+06 8.11E+06 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 1.32E+05 2.44E+06 1.40E+05 5.41E+03 3.96E+03 1.9OE+03 O.OOE+01 O.OOE+01 Sb-124 7.36E+05 5.27E+07 1.86E+06 3.51E+04 O.OOE+01 4.50E+03 1.44E+06 O.OOE+01 Te-127M 4.93E+05 1.36E+07 4.05E+06 1.45E+06 1.64E+07 1.03E+06 O.OOE+01 O.OOE+01 Te-129M 7.43E+05 2.36E+07 4.69E+06 1.75E+06 1.965+07 1.61E+06 O.OOE+01 O.OOE+01 I-131 1.91E+08 8.78E+07 2.33E+08 3.33E+08 5.71E+08 1.09E+11 O.OOE+01 O.OOE+01 I-132 1.23E+01 6.61E-02 1.32E+01 3.52E+01 5.61E+01 1.23E+Ol O.OOE+01 O.OOE+01 I-133 1.68E+06 4.95E+06 3.17E+06 5.51E+06 9.61E+06 8.10E+08 O.OOE+01 O.OOE+01 1-135 1.08E+04 3.32E+04 1.12E+04 2.94E+04 4.71E+04 1.94E+06 O.OOE+Ol O.OOE+01 Cs-134 2.01E+10 4.31E+08 1.03E+10 2.46E+10 7.97E+09 O.OOE+01 2.65E+09 O.OOE+01 Cs-136 1.42E+09 2.24E+08 4.99E+08 1.97E+09 1.10E+09 O.OOE+01 1.50E+08 O.OOE+01 Cs-137 1.27E+ 10 3.74E+08 1.41E+10 1.93E+ 10 6.56E+09 O.OOE+01 2.18E+09 O.OOE+01 Ba-140 1.35E+05 4.23E+06 2.06E+06 2.58E+03 8.78E+02 O.OOE+01 1 e48E+03 O.OOE+0'I Ce-141 2.68E+01 9.03E+05 3.49E+02 2.36E+02 1.10E+02 O.OOE+01 O.OOE+01 O.OOE+01 Ce-144 1.38E+03 8.71E+06 2.58E+04 1.08E+04 6.39E+03 O.OOE+01 O.OOE+01 O.OOE+01 Hf-181 8.02E+01 5.26E+04 7.09E+02 3.99E+00 3.34E+00 2.54E+00 O.OOE+01 O.OOE+01 'R Values in units of mrem/yr per /rCI/m~ for inhalation and tritium and in units of mrem/yr per /rCI/sec m'or all others. per 3-40 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.3-13 R VALUES FOR THE SHEARQN HARRIS NUCLEAR POWER PLAI4T PATHWAY ~ Goat Milk AGE GROUP ~ Teen Nuclide ~Kidne ~Th aid ~Lun H-3 2.04E+03 2.04E+03 O.OOE+01 2.04E+03 2.04E+03 2,04E+03 2.04E+03 2.04E+03 P-32 9.60E+08 2.08E+09 2.48E+10 1.53E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.005+ 01 Cr-51 3.63E+03 6.10E+05 O.OOE+01 O.OOE+01 7.95E+02 2.02E+03 5.18E+03 O.OOE+01 Mn-54 2.03E+05 2.10E+06 O.OOE+01 1.02E+06 3.05E+05 O.OOE+01 O.OOE+01 O.OOE+01 Fe.59 3.63E+05 2.22E+06 4.03E+05 9.40E+05 O.OOE+01 O.OOE+01 2.96E+05 O.OOE+Ol Co-58 1.30E+06 7.80E+06 O.OQE+Ol 5.66E+05 O.OOE+01 O.OQE+01 O.OOE+01 O.OOE+01 Co.60 4.66E+06 2.69E+07 O.OOE+01 2.07E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn.65 2.86E+08 2.60E+08 1.77E+08 6.13E+08 3.93E+08 O.OOE+01 O.OOE+Ol O.OOE+01 Rb-86 1.66E+08 5.24E+07 O.OOE+01 3.54E+08 O.OOE+01 O.OQE+Ol O.OOE+01 O.OOE+01 Sr-89 9.65E+07 4.01E+08 3.37E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+01 Sr-90 2.27E'+10 2.58E+09 9.18E+10 O.OOE+01 O.OOE+01 O.OOE+01 O.OQE+01 O.OOE+01 Y-91 3.02E+01 4.62E+05 1.13E+03 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 2.56E+01 8.59E+04 1.18E+02 3.72E+01 S.47E+01 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 3.09E+03 2.40E+07 1.01E+04 5.62E+03 S.45E+03 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 5.58E+01 1.09E+04 1.30E+02 Q.OOE+01 4.60E+02 O.OOE+Ol O.OQE+01 O.OOE+01 Ru-106 3.51E+Q2 1.34E+05 2.?BE+03 O.OOE+01 5.38E+03 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 4.24E+06 1.96E+09 7.37E+06 6.9?E+Q6 1.33E+07 O.OOE+01 O.OOE+01 O.OQE+01 Sn-113 2.28E+05 2.58E+06 2.15E+05 9.06E+03 6.3?E+03 2.9?E+Q3 O.OOE+01 O.OOE+01 Sb-124 1.29E+06 6.67E+07 3.31E+06 6.10E+04 O.OOE+01 7.51E+03 2.89E+06 O.QOE+01 Te-127M 8.8?E+05 1.86E+07 7.46E+06 2.65E+06 3.02E+07 1.77E+06 O.005+ 01 O.OOE+01 Te-129M 1.36E+06 3.22E+07 8.58E+06 3.19E+06 3.59E+07 2.77E+ 06 O.OOE+ 01 O.OOE+ 01 I-131 3.18E+08 1.17E+08 4.22E+08 5.91E+08 1.02E+09 1.73E+1'I O.OOE+01 O.OOE+01 I-132 2.19E+01 2.66E+01 2.33E+01 6.11E+01 9.62E+01 2.06E+O'I O.OOE+01 O.OOE+01 I-133 2.99E+06 7.43E+06 5.79E+06 9.81E+06 1.72E+07 1.3?E+09 O.OOE+01 O.OOE+01 I-135 1.90E+04 5.63E+04 1.99E+04 5.13E+04 8.10E+04 3.30E+06 O.OOE+01 O.OOE+01 Cs-134 1.96E+10 S.26E+08 1.80E+10 4.23E+10 1.34E+10 O.OOE+01 5.13E+09 O,OOE+01 Cs-136 2.25E+09 2.69E+07 8.50E+08 3.34E+09 1.82E+09 O.OOE+01 2.87E+08 O.OOE+Ol Cs-137 1.19E+10 4.85E+08 2.56E+10 3.41E+ 10 1 ~ 16E+10 O.OOE+01 4.515+09 O.OOE+01 Ba-140 2.39E+05 5.72E+06 3.71E+06 4.55E+03 1.54E+03 O.OOE+01 3.06E+03 O.OOE+01 Ce-141 4.91E+01 1.22E+06 6.40E+02 4.27E+02 2.01E+02 O.OOE+01 O.OOE+01 O.OOE+01 Ce-144 2.55E+03 'I.19E+07 4.74E+04 1.96E+04 1 ~ 17E+04 O.OOE+01 O.OOE+01 O.OOE+01 Hf-181 1.41E+02 6.34E+04 '1.27E+03 6.97E+00 S.BOE+00 4.26E+00 O.OOE+01 O.OOE+01 'R ~ Values in units of mremlyr per yCI/m~ for inhalation and tritium and in units of mremlyr per pCI/sec per mo for ail others. 3-41 Shearon Harris Nuclear Power Plant (SHNPP) TJune 1994 Offsite Dose Calculation Manual (ODCM) Rev, 4 TABLE 3.3-14 / R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT~ PATHWAY ~ Goat Milk AGE GROUP ~ Child Nuciide T. Bod GI-Tract Bone Liver ~Kidne ~Th eid H-3 3.23E+03 3.23E+03 O.OOE+Ol 3.23E+03 3.23E+03 3,23E+03 3.23E+03 3.23E+03 P-32 2.35E+09 1.69E+09 6.11E+10 2.86E+09 O.OQE+01 O.OQE+01 O.OOE+01 O.OOE+01 Cr-51 7.40E+03 3.93E+05 O.OQE+01 O.OOE+01 1.12E+03 4.11E+03 7.50E+03 O.OOE+01 Mn.54 4.07E+05 1.28E+06 O.OOE+01 1.53E+06 4.29E+05 O.OOE+01 O.OOE+01 O.OOE+01 Fe-59 7.52E+05 1.57E+06 9.34E+05 1.51E+06 O.OQE+01 O.OOE+01 4.38E+05 O.OOE+Ol Co-58 2.65E+06 5.0SE+06 O.OQE+01 8.65E+05 O.OOE+01 O.OOE+01 O.OQE+0\ O.QQE+01 Co-60 9.48E+06 1.78E+07 O.OOE+01 3.21E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.QOE+Ol Zn-65 ~ 5.74E+08 1.62E+08 3.47E+08 9.24E+08 5.82E+08 O.OOE+01 O.OQE+01 O.OOE+01 Rb-86 4.04E+08 4,22E+07 O.OOE+01 6.57E+08 O.OOE+01 O.OOE+01 O.OQE+01 O.OQE+01 'r<9 2.38E+08 3.23E+08 8.34E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 3.93E'+10 2.09E+09 1.5SE+11 O.OOE+01 O.OOE+01 O.OQE+01 O.OOE+01 O.OOE+01 Y-91 7.45E+01 3.71E+05 2.79E+03 O.OOE+Ol O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 5.36E+01 6.28E+04 2.74E+02 6.02E+01 8.62E+01 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 6.37E+03 1.65E+07 2.29E+04 8.91E+03 8.37E+03 O.OOE+01 Q.OOE+01 O.OOE+01 Ru-103 1.19E+02 7,98E+03 3.QSE+02 Q.QOE+01 7.77E+02 O.OOE+Ol O.OOE+01 O.OOE+01 Ru-106 8.56E+02 1.07E+05 6.86E+03 O.OOE+01 9.27E+03 O.OOE+01 O.OOE+Ol O.OOE+Ol Ag-110M 8.63E+06 1.28E+09 1.60E+07 1.08E+07 2.01E+07 O.OOE+Ol O.OOE+Ol O.OOE+01 Sn-113 4.61E+05 1.69E+06 4.22E+05 1.36E+04 9.38E+03 5.59E+03 O.OOE+01 O.OOE+01 Sb-124 2.75E+06 4.91E+07 7.84E+06 1.02E+05 O.OOE+01 1.73E+04 4.35E+06 O.OOE+01 Te-127M 2.18E+06 1.49E+07 1.84E+07 4.95E+06 5.24E+07 4.40E+06 O.OOE+01 O.OOE+01 Te-129M ., 3.28E+06 2.58E+07 2.12E+07 5.91E+06 6.21E+07 6.82E+06 O.OOE+01 O.OQE+01 1-131 5.85E+08 9.17E+07 1.02E+09 1.03E+09 1.69E+09 3.41E+11 O.OOE+01 O.OQE+01 I-132 4.67E+01 1.19E+00 5.52E+01 -1.01E+00 1.55E+00 4.71E+01 O.OQE+01 O.OOE+01 I-133 6.58E+06 7.00E+06 1.41E+07 1.74E+07 2.90E+07 3.23E+09 O.QQE+Ol O.OOE+01 I-135 4.01E+04 6.47E+04 4.72E+04 8.49E+04 1.30E+05 7.52E+06 O.OOE+01 O.OOE+01 Cs-134 1.43E+10 3.67E+08 4.14E+10 6.80E+10 2.11E+10 O.OOE+Ol 7.56E+09 O.OOE+01 Cs-136 3.41E+09 1.85E+08 1.92E+09 5.27E+09 2.81E+09 O.OQE+01 4.19E+08 O.OOE+01 Cs-137 8.72E+09 3.70E+08 6.17E+10 5.91E+10 1.93E+10 O.OOE+01 6.93E+09 O.OOE+01 Be-140 5.23E+05 4.54E+05 8.96E+06 7.85E+03 2.56E+03 O.OOE+01 4.68E+03 O.OOE+01 Ce-141 1.17E.+02 9.81E+05 1.53E+03 7.36E+02 3.45E+02 O.OOE+01 O.OOE+01 O.OOE+01 Ce-144 6.24E+Q3'.SSE+06 1.17E+05 3.66E+04 2.03E+04 O.QQE+01 O.OQE+01 O.OOE+01 Hf-181 . 3.04E+02 4.99E+04 3.02E+03 1.17E+01 9.43E+00 9.88E+OQ Q.QQE+01 O.QOE+Ol 'R Values in units of mrem/yr per /ICI/m~ for inhalation end tritium end in units of mrem/yr per /ICI/sec per m'~ for eli others. 3-42 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODOM) Rev. 4 TABLE 3.3-1 5 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT~ PATHWAY ~ Goat Milk AGE GROUP ~ Infant Nuclide LlVBf ~Kidne ~Th eid H-3 4.90E+03 4.90E+03 O.OOE+01 4.90E+03 4.90E+03 4.90E+03 4.9OE+03 4.90E+03 P-32 4.88E+09 1.70E+09 1.26E+11 7.40E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 1.17E+04 3.42E+05 O.OOE+01 O.OOE+01 .1.67E+03 7.65E+03 1.49E+04 O.OOE+01 Mn-54 6.45E+05 1.04E+06 O.OOE+01 2.84E+06 6.30E+05 O.OOE+01 O.OOE+Ol O.OOE+Ol Fe-59 1.20E+06 1.45E+06 1.74E+06 3.04E+06 O.OOE+01 O.OOE+01 9.00E+05 O.OOE+01 Co-58 4.31E+06 4.31E+06 O.OOE+01 1.73E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+Ol Co-60 1.55E+07 1.56E+07 O.OOE+01 6.56E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn.65 7.36E+08 1.35E+09 4.66E+08 1.60E+09 7.74E+08 O.OOE+01 O.OOE+01 O.OOE+Ol Rb.86 8.23E+08 4.26E+07 O.OOE+01 1.67E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-89 4.55E+GS 3.26E+08 1.59E+10 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 4.30E+10 2.11E+09 1.69E+11 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+01 Y-91 1.39E+02 3.75E+05 5.23E+03 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 8.41E+01 5.9OE+04 4.85E+02 1.19E+02 1.28E+02 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 1.02E+04 1.48E+07 4.2?E+04 1.76E+04 1.26E+04 O.OQE+Ol O.OOE+01 O.OOE+Ol Ru-103 2.09E+02 7.605+03 6,25E+02 O.QOE+Ql 1.30E+Q3 O.QOE+01 O.OOE+Ol O.OOE+01 Ru-106 1.77E+03 1.07E+05 1.41E+04 O.OOE+01 1.67E+04 O.OOE+Ol O.OOE+01 O.OOE+01 Ag.110M 1.43E+07 1.12E+09 2.95E+07 2.16E+07 3.08E+07 O.OOE+Ol O.OOE+Ol O.OOE+01 Sn-113 6.66E+05 1.37E+06 6.46E+05 2.45E+04 1.32E+04 9.34E+03 O.OOE+01 O.OOE+01 Sb-124 4.68E+06 4.66E+07 1.51E+07 2.22E+05 O.OOE+01 4.01E+04 9.46E+06 O.OOE+01 Te-127M 4.51E+06 1.50E+07 3.72E+07 1.23E+07 9.16E+07 1.08E+07 O.OOE+0'I O.OOE+01 Te-129M 6.69E+06 2.S9E+07 4.34E+07 1.49E+07 1.09E+08 1.67E+07 O.OOE+01 O.OOE+01 1-131 1.11E+09 8.99E+0? 2.14E+09 2.52E+09 2,94E+09 8.28E+11 O.OOE+01 O.OOE+01 I-132 8.28E+01 1.88E+00 1.15E+00 2.33E+00 2.59E+00 1.09E+02 O.OOE+01 O.OOE+01 I-133 1.27E+07 7.31E+06 2.97E+07 4.32E+07 S.OSE+07 7.86E+09 O.OOE+01 O.OOE+01 l-135 7.11E+04 7.06E+04 9.81E+04 1.95E+05 2.17E+05 1.75E+07 O.OOE+01 O.OOE+01 Cs-134 1.26E+10 3.38E+08 6.68E+10 1.25E+11 3.21E+10 O.OOE+01 1.31E+10 O.OOE+01 Cs-136 4.11E+09 1.67E+08 3.75E+09 1 ~ 10E+10 4.39E+09 O.OOE+Ol 8.98E+08 O.OOE+01 Cs-137 8.1?E+09 3.61E+08 9.85E+10 1.15E+11 3.10E+10 O.005+ 01 1.25E+10 O.OOE+01 Ba-140 9.50E+05 4.53E+QS 1.84E+07 1.84E+04 4.38E+03 O.OOE+01 1.\3E+04 O.OOE+01 Ce-141 2.24E+02 9.85E+05 3.13E+03 1.91E+03 5.88E+02 O.OOE+01 O.OOE+Ql O.OOE+Ol Ce-144 9.39E+03 9.61E+06 1.67E+05 6.86E+04 2.7?E+04 O.OOE+01 O.OOE+01 O.OOE+01 Hf-181 S.OSE+02 4.72E+04 5.74E+03 2.71E+01 1.S8E+01 2.30E+01 O.OOE+01 O.OOE+01 'R ~ Values in units of mremlyr per pCIlms for inhalation and tritium and in units of mremlyr per pCIlsec per mt for all others. 3-Q Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.3-16 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY ~ Inhal GROUP ~ Adult Nuclide ~Kidne 7~hold ~Lun H-3 1.26E+03 1.26E+03 O.OOE+01 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 P-32 5.00E+04 8.63E+04 1.32E+06 7.70E+04 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 9.99E+Ol 3.32E+03 O.OOE+01 O.OOE+01 2.28E+01 5.94E+01 1A4E+04 O.OOE+Ol Mn.54 6.29E+03 7.72E+04 O.OOE+01 3.95E+04 9.83E+03 O.OOE+01 1.40E+06 O.OOE+01 Fe.59 1.05E+04 1.88E+05 1.17E+04 2.77E+04 O.OOE+01 O.OOE+01 1.01E+06 O.OQE+01 Co-58 2.07E+03 1.06E+05 O.OOE+Ol 1.58E+03 O.OOE+01 O.OOE+01 9.27E+05 O.OOE+01 Co.60 1.48E+04 2.84E+05 O.OQE+01 1.1SE+04 O.OOE+01 O.OQE+Ol 5.96E+06 O.QQE+01 Zn-65 4.65E+04 5.34E+04 3.24E+04 1.03E+05 6.89E+04 O.OOE+01 8.63E+05 O.OOE+Ol Rb.86 5.89E+04 1.66E+04 O.OOE+01 1.35E+05 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 'r-89 8.71E+03 3.49E+05 3.04E+05 O.OOE+01 O.OOE+ 01 O.OOE+ 01 1.40E+ 06 O.OOE+ 01 Sr-90 6.09E+06 7.21E+05 9.91E+07 O.OOE+01 O.OQE+01 O.OOE+01 9.59E+06 O.OOE+01 Y-91 1.24E+04 3.84E+05 4.62E+05 O,OOE+01 O,OOE+01 O.OOE+01 1.70E+06 O.OOE+01 Zr-95 2.32E+04 1.50E+05 1.07E+05 3.44E+04 5.41E+04 O.OOE+O'I 1.77E+06 O.OOE+01 Nb-95 4.20E+03 1.04E+05 1.41E+04 7.80E+03 7.72E+03 O.OOE+01 5.04E+05 O.OOE+01 Ru-103 6.57E+02 1.1OE+05 1.53E+03 O.OOE+01 5.82E+03 O.OOE+01 5.04E+05 O.OQE+01 Ru-106 8.71E+03 9.11E+05 6.90E+04 O.OOE+01 1.33E+05 O.OOE+Ol 9.35F+06 O.OOE+01 Ag-110M 5.94E+03 3.02E+05 1.08E+04 9.99E+03 1.97E+04 O.OOE+01 4.63E+06 O.OOE+01 Sn-113 6.48E+03 2.48E+04 6.86E+03 2.69E+02 1.97E+02 9.33E+01 2.99E+05 O.OOE+Ol Sb-124 1.24E+04 4.06E+05 3.12E+04 S.BBE+02 O.OOE+01 7.55E+01 2.48E+06 O.OOE+01 Te-127M 1.57E+03 1.49E+OS 1.26E+04 5.76E+03 4.57E+04 3.28E+03 9.59E+05 O.OOE+01 Te-129M 1.58E+03 3.83E+05 9.75E+03 4.67E+03 3.65E+04 3A4E+03 1.16E+06 O.OOE+01 1-131 2.05E+04 6.27E+03 2.52E+04 3.57E+04 6.12E+04 1.19E+07 O.OOE+01 O.OOE+01 1.132 1.16E+Q3 4.06E+Q2 1.16E+03 3.25E+03 5.18E+03 1.14E+05 O.OQE+01 O.OOE+01 l-133 4.51E+03 8.87E+03 8.63E+03 1.48E+04 2.58E+04 2.15E+06 O.OOE+01 O.OOE+01 I-135 2.56E+03 5.24E+03 2.68E+03 6.97E+03 1.11E+04 4.47E+05 O.OOE+01 O.OOE+01 Cs-134 7.27E+05 1.04E+04 3.72E+05 8.47E+05 2.87E+05 O.OOE+01 9.75E+04 O.OOE+01 Cs-136 1.10E+Q5 1.17E+04 3.90E+04 1.46E+05 8.55E+04 O.OOE+01 1.20E+04 O.OQE+01 Cs-137 4.27E+05 8.39E+03 4.78E+05 6.20E+05 2.22E+05 O.OOE+01 7.51E+04 O.OOE+01 Be-140 2.56E+03 2.18E+05 3.90E+04 4.90E+01 1.67E+01 O.OOE+01 1.27E+06 O.OOE t 01 Ce-141 1.53E+03 1.20E+05 1.99E+04 1.35E+04 6.25E+03 O.OOE+01 3.61E+05 O.OOE+01 Ce-144 1.84E+05 L15E+05 3.43E+06 1.43E+Q6 8.47E+05 O.QOE+01 7.76E+06 O.OQE+01 Hf-1 81 S.16E+03 1.29E+05 4.56E+04 2.S7E+02 2.1 BE+02 1.63E+02 5.99E+05 O.OOE+01 'R Values in units of mremlyr per yCI le for inhalation and tritium and in u~its of mremlyr per yCI/sec per m'~ for all others. Shearon Harris Nuclear power plant (SHNpp) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.3-17 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANTB PATHWAY BB Inhal AGE GROUP BB Teen Nuchds ~T. Bod ~GI-Tra Boor Liver ~IGdaa ~Th ord H-3 1.27E+03 1.27E+03 O.OOE+01 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 P.32 7.15E+04 9.27E+04 1.89E+06 1.09E+05 O.OQE+01 O.OOE+01 O.OQE+01 O.OOE+01 Cr-51 1.35E+02 3.00E+03 O.OOE+01 O.OOE+01 3.07E+01 7.49E+01 2.09E+04 O.OOE+01 Mn-54 8.39E+03 6.67E+04 O.OOE+01 5.10E+04 1.27E+04 O.OOE+01 1.98E+06 O.OOE+01 Fe.59 1.43E+04 1.78E+05 1.59E+04 3.69E+04 O.OOE+01 O.OOE+01 1.53E+06 O.OOE+01 Co.58 2.77E+03 9.51E+04 O.OOE+01 2.07E+03 O.OOE+01 O.OOE+01 1.34E+06 O.OOE+01 Co.60 1.98E+04 2.59E+05 O.OQE+01 1.51E+04 O.OOE+01 O.OQE+Ol 8.71E+08 O.OOE+01 Zn.65 6.23E+04 4.66E+04 3.85E+04 1.33E+05 8.63E+04 O.OOE+01 1.24E+06 O.OQE+Ol Rb 86 8.39E+04 1.77E+04 O.OOE+01 1.90E+05 O.OOE+01 O.OQE+01 O.OOE+01 O.OOE+01 Sr.89 1.25E+04 3.71E+05 4.34E+05 O.OQE+01 O.OOE+01 O.OOE+Ol 2.41E+06 O.OOE+01 Sr-90 6.67E+06 7.64E+05 1.08E+08 O.OOE+01 O.OOE+01 O.OOE+01 1.65E+07 O.OOE+01 Y-91 1.77E+04 4.08E+05 6.60E+05 O.OOE+01 O.OQE+O'I O.OOE+01 2.93E+06 O.OOE+01 Zr-95 3.15E+04 1.49E+05 1.45E+05 4.58E+04 6.73E+04 O.OOE+01 2.68E+06 O.OOE+Ol Nb-95 5.66E+03 9.67E+04 1.85E+04 1.03E+04 9.99E+03 O.OOE+01 7.50E+05 O.OOE+01 Ru-1Q3 8.S5E+02 1.QSE+05 2.10E+03 O.OOE+01 7.42E+03 O.OQE+01 7.82E+05 O.OOE+01 Ru-106 1.24E+04 9.59E+05 9.83E+04 O.OOE+01 1.90E+05 O.OQE+01 1.61E+07 O.QOE+Ql Ag-110M 7.98E+03 2.72E+05 1.38E+04 1.31E+04 2.50E+04 O.OQE+01 6.74E+06 O.OOE+01 Sn-113 8.68E+03 2.03E+04 8.19E+03 3A4E+02 2.45E+02 1.13E+02 4.27E+05 O.OOE+01 Sb-124 1.68E+04 3.98E+05 4.30E+04 7.94E+02 O.OQE+01 9.76E+01 3.85E+06 O.OQE+01 Te-127M 2.18E+03 1.59E+05 1.80E+04 8.15E+03 6.53E+04 4.38E+03 1.65E+06 O.OOE+01 Te-129M 2.24E+03 4.04E+05 1.39E+04 6.57E+03 5.18E+04 4.57E+03 1.97E+06 O.OOE+01 I-131 2.64E+ Q4 6.48E+03 3.54E+04 4.90E+04 8.39E+04 1.46E+07 O.OOE+01 O.OOE+01 I-132 1.57E+03 1.27E+03 1.59E+03 4.37E+03 6.91E+03 1.51E+05 O.OOE+01, O.QOE+Ol I-133 6.21E+03 1.03E+04 1.21E+04 2.05E+04 3.59E+04 2.92E+06 O.OQE+01 O.OOE+01 l-135 3.48E+03 6.94E+03 3.69E+03 9.43E+03 1.49E+04 6.20E+05 O.OOE+01 O.OOE+01 Cs-134 5.48E+05 9.75E+03 5.02E+05 1.13E+06 3.75E+05 O.OOE+01 1.46E+05 O.OOE+01 Cs-136 1.37E+05 1.09E+04 5.14E+04 1.93E+05 1.10E+05 O.OOE+01 1.77E+04 O.OOE+01 Cs-137 3.11E+05 8.48E+03 6.69E+05 8.47E+05 3.04E+05 O.OOE+01 1.21E+05 O.OOE+OI Ba-140 3.51E+03 2.28E+05 5.46E+04 6.6SE+01 2.28E+01 O.OQE+01 2.03E+06 O.OOE+01 Ce-141 2.16E+03 1.26E+05 2.84E+04 1.89E+04 8.87E+03 O.OOE+01 6.13E+05 O.OQE+01 Ce-144 2.62E+05'.63E+05 4.88E+06 2.02E+06 1.21E+06 O.OOE+01 1.33E+07 O.OOE+01 Hf-181 7.04E+03 1.20E+05 3.48E+02 2.90E+02 2.12E+02 9.39E+05 O.OOE+01 pCI/m'.32E+04 'R ~ Values in units of mrem/yr per for inhalation and tritium and in units of mremlyr per yCI/sec per m's for all others. 3-Q Shearon Harris Nuclear Power plant (SHNpp) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.3-18 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANTG PATHWAY BB Inhal AGE GROUP ~ Child Nuclide ~T. Bod ~GI-Tra Bone Liver ~Kidne ~Th oid ~Lun H-3 1.12E+03 1.12E+03 O.OOE+01 1.12E+03 1.12E+03 1.12E+03 1 ~ 12E+03 1.12E+03 P-32 9.86E+04 4.21E+04 2.60E+06 1.14E+05 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 1.54E+02 1.08E+03 O.OOE+01 O.OOE+01 2.43E+Ol 8.53E+01 1.70E+04 O.OOE+01 Mn-54 9.50E+03 2.29E+04 O.OOE+01 4.29E+04 1.00E+04 O.OOE+01 1.57E+06 O.OOE+01 Fe.59 1.67E+04 7.06E+04 2.07E+04 3.34E+04 O.OOE+01 O.OOE+01 1.27E+06 O.OOE+Ol Co-58 3.16E+03 3.43E+04 O.OOE+01 1.77E+03 O.OOE+01 O.OOE+01 1.10E+06 O.OOE+01 Co.60 2.26E+04 9.61E+04 O.OOE+01 1.31E+04 O.OQE+01 O.OOE+01 7.06E+06 Q.OOE+01 Zn.65 7.02E+04 1.63E+04 4.25E+04 1.13E+05 7.13E+04 O.OQE+01 9.94E+05 O.OOE+01 Rb-86 1.14E+05 7.98E+03 O.OOE+01 1.98E+05 O.OOE+01 O.OOE+01 O.OQE+01 O.OQE+01 'r.89 1.72E+04 1.67E+05 5.99E+05 O.OOE+01 0.005+01 O.OOE+01 2.'l 5E+06 O.OOE+01 Sr-90 6.43E+06 3.43E+05 1.01E+08 O.OOE+01 O.OOE+Ol O.OOE+Ol 1.4/E+07 O.OOE+01 Y-91 2.43E+04 1.84E+05 9.13E+05 O.OOE+Ol O.OOE+01 O.OOE+01 2.62E+06 O.OOE+01 Zr-95 3.69E+04 6.10E+04 1.90E+05 4.17E+04 5.95E+04 O.OOE+01 2.23E+06 O.OOE+01 Nb-95 6.54E+03 3.69E+04 2.35E+04 9.16E+03 8.61E+03 O.OOE+01 6.13E+05 O.OOE+01 Ru-103 1.07E+03 4.47E+04 2.79E+03 O.OOE+01 7.02E+03 O.OQE+01 6.61E+05 O.OQE+01 Ru-106 1.69E+04 4.29E+05 1.36E+05 O.OOE+01 1.84E+05 O,OOE+01 1.43E+07 O.OOE+Ol Ag-110M 9.13E+03 1.00E+05 1.68E+04 1.14E+04 2.12E+04 O.OOE+01 5.47E+06 O.OOE+01 Sn-113 9.83E+03 7.45E+03 9.00E+03 2.91E+02 2.02E+02 1.19E+02 3.40E+05 O.OOE+01 Sb-124 2.00E+04 1.64E+05 5.73E+04 7.40E+02 O.OOE+01 1.26E+02 3.24E+06 O.OOE+01 Te-127M 3.01E+03 7.13E+04 2.48E+04 8.53E+03 6.35E+04 6.06E+03 1.48E+06 O.OOE+01 Te-129M 3.04E+03 -1.81E+05 1.92E+04 6.84E+03 5.02E+04 6.32E+03 1.76E+06 O.OOE+01 I-131 2.72E+04 2.84E+03 4.80E+04 4.80E+04 7.87E+04 1.62E+07 O.OOE+Ol O.OOE+01 I-132 1.87E+03 3.20E+03 2.11E+03 4.06E+03 6.24E+03 1.93E+05 O.QOE+Ol O.OOE+01 l-133 7.68E+03 5.47E+03 1.66E+04 2.03E+04 3.37E+04 3.84E+06 O.OOE+01 O.OOE+01 I-135 4.14E+03 4.43E+03 4.91E+03 8.72E+03 1.34E+04 7.91E+05 O.OOE+01 O.OOE+01 Cs-134 2.24E+05 3.84E+03 6.50E+05 '1.01E+06 3.30E+05 O.OOE+01 1.21E+05 O.OOE+01 Cs-136 1.16E+05 4.17E+03 6.50E+04 1.71E+05 9.53E+04 O.OOE+01 1.45E+04 O.OOE+01 Cs-137 1.28E+05 3.61E+03 9.05E+05 8.24E+05 2.82E+05 O.OOE+01 1.04E+05 O.OOE+01 8a-140 4.32E+03 1.02E+05 ~ 7.39E+04 6.47E+01 2,11E+Ol O.OOE+Ol 1.745+06 O.OOE+01 Ce-141 2.89E+03 5.65E+04 3.92E+04 1.95E+04 8.53E+Q3 O.QOE+Ql 5.43E+05 O.OQE+01 Ce-144 3.61E+05 3.88E+05 6.76E+06 2.11E+06 1,17E+06 O.OOE+01 1.19E+07 O.OOE+01 Hf-181 8.50E+03 5.31E+04 8A4E+04 3.28E+02 2.64E+02 2.76E+02 7.95E+05 O.OOE+01 'R Values in units of mrem/yr per pCI/m~ for inhalation and tritium and in units of mrem/yr per /rCI/sec per m'3 for ail others. 3-46 I' Shearon Harris Huclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 3.3-19 R VALUES FOR THE SHEARQN HARRIS NUCLEAR POWER PLANT~ PATHWAY ~ Inhal AGE GROUP ~ Infant Nuclide ~T. Bod ~GI-Tra Bone Liver ~Kidns ~Th aid H-3 6.46E+02 6.46E+02 O.OOE+01 6.46E+02 6.46E+02 6.46E+02 6.46E+02 6.46E+02 P-32 7.73E+04 1.61E+04 2.03E+06 1.12E+05 '.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 8.93E+01 3.56E+02 O.OQE+01 O.OOE+01 1.32E+01 5.75E+01 1.28E+04 O.OOE+01 Mn-54 4.98E+03 7.05E+03 O.QOE+01 2.53E+04 4.98E+03 O.OOEt01 9.98E+05 O.OOE+01 Fe-59 9.46E+03 2.47E+04 1.35E+04 2.35E+04 O.OQE+01 O.OQE+01 1.01E+06 O.OOE+01 Co.58 1.82E+03 1.11E+04 O.OOE+01 1.22E+03 O.OOE+0'I O.OOE+01 7.76E+05 O.OOE+01 Co.60 1.18E+04 3.19E+04 O.OOE+Ol 8.0'IE+03 O.OOE+01 O.OOE+01 4.50E+06 O.OOE+01 Zn.65 3.10E+04 5.13E+04 1.93E+04 6.25E+04 3.24E+04 O.OOE+0'I 6.46E+05 O.OOE+01 Rb-86 8.81E+04 3.03E+03 O.OOE+01 1.90E+05 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 'r-89 1.14E+04 6.39E+04 3.97E+05 O.OOE+01 O.QOE+01 O.OOE+01 2.03E+06 O.OOE+01 Sr-90 2.59E+05 1.31E+05 4.08E+07 O.OOE+01 O.OOE+01 O.OOE+01 1.12E+07 O.OOE+01 Y-91 1.57E+04 7.02E+04 5.87E+05 O.OOE+01 O.OOE+01 O.OOE+01 2.45E+06 O.OOE+01 2r-95 2.03E+04 2.17E+04 1.15E+05 2.78E+04 3.10E+04 O.OOE+01 1.75E+06 O.OOE+01 Nb-95 3.77E+03 1.27E+04 1.57E+04 6.42E+03 4.71E+03 O.OOE+01 4.78E+05 O.OOE+Ol Ru-103 6.78E+02 1.61E+04 2.01E+03 O.OOE+01 4.24E+03 O.OOE+01 5.51E+05 O.OOE+01 Ru-106 1.09E+04 1.64E+QS &.67E+04 Q.OOE+Q1 1.06E+05 O.OOE+01 1.'I 5E+07 O.OOE+ 01 Ag-110M 4.99E+03 3.30E+04 9.97E+03 7.21E+03 1.09E+04 O.OOE+01 3.66E+06 O.OOE+01 Sn-113 4.89E+03 2.29E+03 4.67E+03 1.74E+02 9.94E+01 6.73E+01 2.30E+05 O.OOE+01 Sb-124 1.20E+04 5.91E+04 3.79E+04 5.56E+02 O.OOE+01 1.00E+02 2.64E+06 O.OOE+01 Te-127M 2.07E+03 2.73E+04 1.66E+04 6.89E+03 3.75E+04 4.86E+03 1.31E+06 O.OOE+01 'Te-129M 2.22E+03 6.89E+04 1.41E+04 6.08E+03 3.17E+04 5.47E+03 1.68E+06 O.OOE+01 l-131 1.96E+04 1.06E+03 3.79E+04 4.43E+04 5.17E+04 1.48E+07 O.OOE+01 O.OOE+01 I-132 1.26E+03 1.90E+03 '1.69E+03 3.54E+03 3.94E+03 1.69E+05 O.OOE+01 O.OOE+01 l-133 5.59E+03 2.15E+03 1.32E+04 1.92E+04 2.24E+04 3.55E+06 O.OOE+01 O.OOE+01 I-135 2.77E+03 1.&3E+03 3.86E+03 7.59E+03 8,46E+03 6,95E+05 O.OOE+01 O.OOE+01 Cs-134 7A4E+04 1.33E+03 3.96E+05 7.02E+05 1.90E+Q5 Q.OQE+Ol 7.95E+04 O.OOE+01 Cs-136 5.28E+04 1.43E+03 4.82E+04 1.34E+05 5.63E+04 O.OOE+01 1.17E+04 O.OOE+01 Cs-137 4.54E+04 1.33E+03 5.48E+05 6.11E+05 1.72E+05 O.OOE+01 7.12E+04 O.OOE+Ol Ba-140 2.89E+03 3.83E+04 5.59E+04 5.59E+01 1.34E+01 O.OOE+01 1.59E+06 O.OOE+01 Ce-141 1.99E+03 2.1SE+04 2.77E+04 1.66E+04 5.24E+03 O.OOE+Ol 5.16E+05 O.OOE+01 Ce-144 1.76E+05'.48E+05 3.19E+06 1.21E+06 5.37E+05 O.OOE+01 9.83E+06 O.OOE+Ol Hf-181 5.05E+03 1.90E+04 5.65E+04 2.66E+02 1.59E+02 2.25E+02 6.73E+05 O.OOE+01 'R Values ~ in units of mrem/yr per pCI/ms for inhalation and tritium and in units of mrem/yr per /rCI/sec per m s for all others. 3-Q Shearon Harris Nuclear Power plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Figure 3.1 SHNPP Gaseous Waste Streams REH RAOIAIIOH EFTLIIQII MOHIIOR HHR WASTE RROCESSIHC RIOC RAO REACTOR ACTUARY OIOC Ittd IVEL HAHOIIHC BLOC VIICH WIDE RANCE CAS QOHIIOR TURBINE BLDG VENT STACK 3A RH IIV 5$ 5d I (Mtdtt) ItEH IIV 5$ 51 RGI CONDENSER POL AREA CONDENSER VACUUM PUMP WASTE PROCESSING BLDG VENT STACK 5 REM It(M IVV 5$ ld IUlt WV 5$ ld I ('NCM) WPB HOT lt COLD LAUNDRY WPB OFhCE AREA EXHAUST WPB COLD LAUNDRY DRTERS WPB CONTROL ROOM SMOKE EXIIAVST WPB OFhCE AREA WPB CENERAL AREA EXHAVST WPB CHILLER ROOM EXHAUST WASTE CAS DECAY TANKS WASTE PROCESSNC AREAS ALTERED EXHAUS'T WASTE PROCESSING BLDG VENT STACK 5A Rtt IVV SSIT I (VIICtt) RM REM RTH IVV 55IT WPB SWITCHCEAR ROOM EXHAUST WPB HVAC EORP, ROOM EXHAUST WPB PERSONNEL HANDUNC FATTY EXHAUST WPB HOT It LOW ACTlVlTY EXHAUST W'PB LAB AREA EXHAUST PLANT VENT STACK 1 RH SIAV SSOI 1$ A HRCli) REM ILT 55010 RM REM REM IAV 5$ 0SA RGI CONTHHMENT PRE EHTRY PURCE REII-ILT-5551 REM FHB NORMAL EXHAUS'T NORTH RAB NORMAI. EXHAUST FHB NORMAL EXHAVST SOUTH RIM IAV SSSIA RE RGI REM ML 5$ 0d RAB GIERCENCY EXHAUST ISI IAV 55520 REM FHB NORMAL EXHAUST (OPER. FL) SOUlH REM II(M ML SSOT RAB VENTILATION SYSTEM AIB NORMAL EXHAVST (OPEL FL) SOUTH HYDROCOI PVRCE REM ROI-IIL-5$0dh-SA RAB SMOKE PVRCE REM REll ML 5$ 0$ $ $$ FHB GIERCOICY EXHAUST RAB PVRCE ~ ~ I ~ ~ l i' ~ ' ~ % g ~8 ~ aq h3 G+E 5%HI g$ > + ~ F+ll ~ ~ 5%8 ~a 8 lg3 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Figure 3.3 SHNPP Condenser Off-Gas System OM SVOEIHE ~ LOG IlM I SV.SS 06 I tWAGIQ VEHI SlACK i ja CLANG Sl EAM CONG. CVFESSi hEM KEIR I lv )'ll~ MAIN CONOENSEh ~,/ 1100 lilh0 VALVE WOGM WIOE OAHGE QAS MONIIOh SLING F LANGE hEM hAOIASIOH ESFLIIEN'I LIONIIOh ASMOSI'I IEQE Calldellaer Vatuuu Puup Effluent Treatuent Spateu Adapted Frau PSSure 9.4.0i2 SNNPP PSAR Auellduallt Na. 15 3-50 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table 4 ' contains the sample point description, sampling and collection frequency, analysis type, and frequency for various exposure pathways in the vicinity of the SHNPP for the radiological monitoring program. Figure 4.1-1 shows the exclusion boundary surrounding SHNPP. Figures 4.1-2, 4.1-3, and 4.1-4 show the locations of the various sampling points and TLD locations. Figure 4.1-5 provides a legend for Figures 4.1-2 through 4.1-4. 4-1 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE A.l RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Pathway and/or Sample: Airborne Particulates and Radioiodine Sampling and Collection Frequency: Continuous operating sampler with sample collection as required by dust loading but at least once per 7 days. Analysis Frequency and Weekly Gross Beta~ Required Analysis: Weekly I-131 (charcoal canisters) Quarterly Gamma Isotopic~ ~ (Composited by location), Sample Point ID No. Sample Point, Description~, Distance, and Direction 0.1 mi. S on SR 1134 from SR 1011 intersection. N sector, 2.6 mi. from site. 1.4 mi. S on SR 1134 from SR 1011 intersection. NNE sector, 1.4 mi. from site. 0.7 mi. N on SR 1127 from intersection with US 1'. NNE sector, 3.1 mi. from site. Pittsboro (Control Station)3 NW sector from site, > 12 mi. from site 26 Harris Lake Spillway S sector, 4.7 mi. from site 1.3 mi. N on SR 1912 from intersection of NC 42 SSW sector, 3.4 miles from site 4-2. WA k Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODM) Rev. 4 TABLE 4.1 RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Pathway and/or Sample: Direct Radiation (TLD) Sampling and Collection Frequency: Continuous measurement with an integrated readout at least once per quarter. Analysis Frequency and Required Analysis; Quarterly Gamma Dose Sample Point ID No. Sample Point, Description, Distance, and Direction 0.1 mi. S on SR 1'134 from SR '1011 intersection. N sector, 2.6 mi. from site. 1.4 mi. S on SR 1134 from SR 1011 intersection. NNE sector, 1.4 mi. from site. HE&EC ENE sector, 2.6 mi. from site. 0.7 mi. N on SR 1127 from intersection with US 1 NNE sector, 3.1 mi. from site. Pittsboro (Control Station) NW sector from, site, ) 12 mi. from site Intersection of SR 1134 & SR 1135. NE sector, 0.8 mi. from site. Extension of SR 1134. E sector 0.7 mi. from site. Dead end of road. Extension of SR 1134. ESE sector, 0.6 mi. from site. 1 mi. S on SR 1130 from intersection of SR 1127, 1115, and 1130. SE sector, 2.2 mi. from site. 10 SR- 1130 S of intersection of SR 1127, 1115, and 1130. SSE sector, 2.2 mi. from site. 4-3 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE A.L RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Path~ay and/or Sample: Direct Radiation (TLD) Sampling and Collection Frequency: Continuous measurement with an integrated readout at least once per quarter. Analysis Frequency and Required Analysis: Quarterly Gamma Dose Sample Point ZD No. Sample Point, Description~, Distance, and Direction 'HNPP site. S sector, 0.6 rnidmi. from site 12 SHNPP site. SSW sector, 0.9 mi. from site. 13 SHNPP site. WSW sector 0.7 mi. from site. 14 SHNPP site. Access road to aux. reservoir. W sector, 1.5 from site. 15 SR 1911. W sector, 2.0 mi. from site. 16 1.2 mi. E of intersection of US 1 and SR 1011. WNW sector 1.9 mi. from site. 17 Intersection of US 1 and Aux. Res. NW sector, 1.5 mi. from site. 18 0.2 mi. N on US 1 from Station 17. NNW sector, 1.4 mi. from site. 19 0.6 mi. E on SR 1142 from intersection of SR 1141. NNE sector 5.0 mi. from site. 20 US 1 at intersection SR 1149. NE.sector 4.5 mi. from site. 21 1.2 mi. W on SR 1152 from intersection SR 1153. ENE sector, 4.8 mi. from site. 'l! )f ~ I E Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4.1 RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Pathway and/or Sample: Direct Radiation (TLD) Sampling and Collection Frequency: Continuous measurement with an integrated readout at least once per quarter. Analysis Frequency and Required Analysis: Quarterly Gamma Dose Sample Point ID No. Sample Point, Description~, Distance, and Direction 22 'ormerly Ragan's Dairy on SR 1115. E sector, 4.3 mi. from site. 23 Intersection of SR 1127 and SR 1116. ESE sector, 4.8 mi. from site. 24 Sweet Springs Church on SR 1116. SE sector 4.0 mi. from site. 25 0.2 mi. W on SR 1402 from intersection of SR 1400 SSE sector, 4.7 mi. from site 26 Harris Lake Spillway S sector, 4.7 mi. from site 27 NC 42 I Buckhorn United Methodist Church SW sector, 4.8 mi. from site. 28 0.6 mi. on SR 1924 from intersection of SR 1916. SSW sector, 4.8 mi. from site. 29 Parking lot of Neste Resins Corporation on SR 1916. WSW sector, 5.7 mi. from site. 30 Exit intersection of SR 1972 and US 1. W sector, 5.6 mi. from site. 31 At intersection of SR 1908, 1909, 1910. WNW sector, 4.7 mi. from site. 32 SR 1008. NNW sector 6.4 mi. from site. 4-5. II 1 -I Shearon Harris Nuclear Power Plant: (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4.1 RADIOLOGICALENVIRONMENTAL-MONITORING PROGRAM Exposure Pathway and/or Sample: Direct Radiation (TLD) Sampling and Collection Frequency: Continuous measurement with an integrated readout at least once per quarter. Analysis Frequency and Required Analysis: Quarterly Gamma Dose Sample Point ID No. Sample Point, Description~, Distance, and Direction 33 'R 1142. 1.7 mi.from intersect'ion of SR 1141. NNW sector, 4.5 mi. from site, 34 Apex (Population Center). NE sector, 8.7 mi. from site. 35 Holly Springs (Populat:ion Center). E sector, 6.9 mi. from site. 36 SR 1393 at intersection of SR 1421. E sector, 10.9 mi. from site. 37 US 401 at old CP&L office, Fuquay-Varina (Population Center). ESE sector, 9.2 mi. from site. 48 SR 1142. 1.5 mi. from intersection of SR 1141. N sector, 4.5 mi. from site. 49 SR 1127 NNE '.3 sector, mi. S from intersection with 2.5 mi. from site. US l. 50 SR 1127 W from intersection SR 1115 and 1130. ESE sector, 2.6 mi. from site. 53 SR 1972 N from intersection of SR 1910 and SR 1972. NW sector, 5.8 mi. from site. 56 SR-1912 at intersection of SR 1912 and SR 1924. WSW sector, 3.0 mi. from site. 4-6. 40 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 msLE <.1 RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Pathway and/or Sample: Direct Radiation (TLD) Sampling and Collection Frequency: Continuous measurement with an integrated readout at least once per quarter. Analysis Frequency and Required Analysis: Quarterly Gamma Dose Sample Point ID No. Sample Point, Description~, Distance, and Direction 63 SHNPP Site. SV sector, 0.6 mi. from site. 4-L Shearon Harris Nuclear Po~er Plan't (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 - TABLE 4.1 RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Pathway and/or Sample: Waterborne, Surface Water Sampling and Collection Frequency: Composite sample5 collected over a period of less than or equal to 31 days. Analysis Frequency and Required Analysis: Monthly Gross Beta4 and Quarterly Gamma Isotopic Sample Point ID No. Sample point, Descriptionsp, Distance, and Direction 26 Harris Lake Spillway S sector, 4.7 mi. from site 38 Cape Fear Steam Electric Plant Intake Structure (Control Station)~ WSW sector, 6.'2 miles from site 40 NE Harnett Metro Water Treatment Plant Intake Building Duncan Street, Lillington, N.C. SSE sector, -17 mi. from site. ') Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4.1 RADIOLOGICALENVIRONMENTALMONITORING PROGRAM I Exposure Pathway and/or Sample: Waterborne, Groundwater Sampling and Collection Frequency: Grab sample collected quarterly Analysis Frequency and Required Analysis: Each Sample Gamma Isotopic4 and Tritium Sample Point ID No, Sample Point, Description~, Distance, and Direction 39 On-site deep well in the vicinity of the diabase dike SSW sector, 0.7 mi. from site'7 SHNPP Site N. bank of Emergency Service Water (ESW) intake channel, S. of Water Treatment Building. SSW sector, 0.4 mi. from site 58 SHNPP Site N. bank of Emergency Service Water (ESW) intake channel, S. of Water Treatment Building. WSW sector, 0.5 mi. from site 59 SHNPP Site N. side of Old Construction Road. NNE sector, 0.5 mi. from site 60 SHNPP Site W. bank of Thomas Creek N of Cooling Tower. ESE sector, 0:5 mi. from site Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE k. 1 ,RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Pathway and/or Sample: Waterborne, Drinking Water Sampling and Collection Frequency: Composite sample~ collected over a two-week period if I-131 analysis is performed; monthly composite otherwise. Analysis Frequency and Required Analysis: I-131 on each composite when the dose calculated for the consumption of the water is greater; than 1 mrem per yr. Monthly Gross Beta Monthly Gamma Isotopic4 Quarterly Tritium Sample Point XD No. Sample Point, Description~, Distance, and Direction 38 Cape Fear Steam Electric Plant Intake Structure (Control Station)3 WSW sector, 6.2 miles from site 40 NE Harnett Metro Water Treatment Plant Intake Building Duncan Street, Lillington, N.C. SSE sector, -17 mi'. from site. 51 SHNPP Water Treatment Building On Site NOTE: I-131 analysis is normally performed weekly on these samples. H-3 analysis is normally performed monthly. 4-10 8 '8 i ~ 'hl a Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4.1 RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Pathway and/or Sample: Waterborne, Sediment from Shoreline Sampling and Collection Frequency: Shoreline Sediment sample collected semiannually. Analysis Frequency and Required Analysis: Each Sample Gamma Isotopic~ Sample Point ID No. Sample Point, Description~, Distance, and Direction 26 'arris Lake Spill'way S sector, 4.6 mi. from site 41 Shoreline of Mixing Zone of Cooling Tower Blowdown Line S sector, 3.8 miles from site. f' Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation manual (ODCM) Rev. 4 TABLE 4.1 RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Pathway and/or Sample: Waterborne, Bottom Sediment Sampling and Collection Frequency: Bottom Sediment sample collected semiannually. Analysis Frequency and Required Analysis: Each Sample Gamma Isotopic~ Sample Point ID No. Sample Point, Description~, Distance, and Direction 52 Harris Lake in the vicinity of the mixing zone of the cooling tower S sector, 3.8 miles from site. Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE A > U .RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Pathway and/or Sample: Ingestion - Milk Sampling and Collection Frequency: Grab samples semi-monthly when animals are on pasture; monthly at ~ other times. Analysis Frequency and Required Analysis: Each Sample I-131 Each Sample Gamma Isotopic~ Sample Point 1 TD No. Sampl'e Point, Description~, Distance, and Direction 42 Maple Knoll Dairy on SR 1403 SSE sector, 7.0 mi. from site. 43 Goodwin's Dairy on SR 1403 N sector, 2.2 mi. from site Stroud's Dairy, Pittsboro (Control Station)3 NW sector from site, ) 12 mi. from site P>> &4lA Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE A.> RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Pathway and/or Sample: Ingestion - Fish Sampling and Collection Frequency: One sample of each of the following semiannually: Catfish (bottom feeders)

2. Sunfish & Largemouth Bass (free swimmers)

Analysis Frequency and Required. Analysis: Each sample - Gamma Isotopic4 on edible portion for each Sample Point ID No. Sample Point, Descriptioni, Distance, and Direction 44 Site varies within the Harris Lake. 45 Site varies above Buckhorn Dam on Cape Fear River (Control Station)3 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4.1 RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Pathway and/or Sample: Ingestion - Food Products Sampling and Collection Frequency: Samples of 3 different kinds of broadleaf vegetation monthly during the growing season Analysis Frequency and Required Analysis: Each sample - Gamma Isotopic~ on edible portion for each Sample Point ID No. Sample Point, Description~, Distance, and Direction ~ 5 Pittsboro (Control Station)3 NNW sector, ) 12 mi. from site 54 SR 1189. Gunter-Morris Rd. NNE sector, 1.7 mi. from site. 55 SR 1167, Bonsai NNW sector, 2.0 mi. from site 62 SR 1127, 0.4 m. W of SR 1134 NE sector, 2.3 mi. from site 4-15 Cl $ 4ly i ~ ~ ~ ~ II ~ II ~ ~ ~ ~ ~ ~ II ~ ~ ~ ~ II ~ ' I ~ II ~ ~ ~ ~ ~ II ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ II ~ II ~ ~ ~ ~ ~ ~ ~ ~ II Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 NOTES TO TABLE 4.1 SHNPP Radiolo ical Environmental Monitorin Pro ram Sample locations are shown on Figures 4.1-2, 4.1-3, and 4.1-4. Figure 4.1-5 provides a legend for Figures 4.1-2 through 4.1-4. Particulate samples will be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more following filter change to allow for radon and thorium daughter decay. If gross beta activity is greater than ten times the yearly mean of the control sample station activity, a gamma isotopic analysis will be performed on the individual samples.

3. Control sample stations (or background stations) are located in areas that are unaffected by plant operations:; All other sample stations th'at have the potential to be affected by radioactive emissions from plant operations are considered indicator stations.

Gamma isotopic analysis means the identification and quantitation of gamma-emitting radionuclides that may be attributable to effluents from plant operations. Composite samples will be collected with equipment which is capable of collecting an aliquot at time intervals which are very short (e.g., every 2 hours) relative to the compositing period (e.g., monthly). The dose will be calculated for the maximum organ and age group, using the methodology contained in ODCM Equation 2.2-1.

7. Based on historical meteorology (1976-1987), food product Locations 54 and 55 were added in the summer of 1988 as the off-site locations with the highest predicted D/Q values. Food product locations 43 and 46 were deleted after the 1988 growing season.

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Figure 4.1-1 SHNPP Exclusion Boundary Plan DIXIE I'll'E LINE EXCLUSION OOIftfohflY XCLUSION OOUNDAflY a pMETEOIIOLO CAL STATION O A. V~ cQ AUX. IlE EI voffl Eh1 AGENCY CI NNEL ~ SEI VICE 0~Sf WAIEg G QIIANNEL SEP DIKE 0 AUX llESEIIVOIfl AUX D M COOLING T OWEII MAKEUP CIIANNEL EhlF IIGENCY SEIIVICF. WAI EII INIAKECNANtlEL ZO 4 gg Z ug EXCLUSION OOUNDAIIY SCAI.E IN FEET 4-1B June 1994 Shearon Harris Nuclear Power Plant (SHNPP) Rev. 4 Offsite Dose Calculation Manual (ODCM) Figure 4.1-2 Environmental Radiological Sampling Points ~ ll>C V >'s vvrrCS IC i>> ~ IS I ~ I 00 / '5 II Ins I Is t SOS >>><< 04> ~ 44 >I 4 4 I 4 4 >ttt> >0>l ITTSBORO n>c / "-= ~ 44 rhlile 5 ' kl C ~ 53 >>IC mt '/ . 9/ I~ /~u p I >r n I I lt<< ~>>I IIII 4 / "! cr0>4> ~ l 4>> I~ I 31 Otlssl Iciily 4 II 'lll 4 ~ III 4 4 <<>I JJ 30 Oc / I ><l 4 4 ~ >to >> I>> C 38 ~ II~ 440445 C ~ >JJ ~ ~ 'I t ~ >I> ~ Bute ~ <tl 0>>l elle scen ~ >It ~ >l ~ JI tt ~C>0027 ~ . > ~ I ~ I>01 ~ I~ ~ I ! I II <<Il ,r Il 4 ~0 IC ~ t >0 ~ g utt 45 ~ >I ~> ~ ~ Jlt Colon 0 ~ Ilt ~ ~ 0>CS ~ C>v VJ 0> 05 I I Isn 4~ >r J I ~ 0< It -: Ies ~ 4 v oo~' 00> ~ I ~ 4 I ~ I ~ l ll I ~ e ~ ~ ~ ' ~ ll ~ I' I eea4= ~<~ e Q) ~$ ~ :I 0 I e~ Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Figure 4.1-4 Environmental Radiological Sampling Points l A2$ 22Q$ 22$ 2 I 12BV IISL I I I 2 I I 20 4 I 1 I 222$ 43 49 - / I 2 O 3 IIjKAYOAKS %59 15 16 slr I I \ 14 63 60 0 I ~ ttS i57 KXC$uSCII SOONOAS1 39 I I I I et I Ie' I 9 I I I 10 II N 112$ IAK$ ~ ~ tI 47 I I I 28 \ \ I 5 1 I 2 lg I I I I '11$ '25 r ~$ SOAL$ %22tt I 4-21 ,U 4 AF ) Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCH) Rev. 4 Figure 4.1-5 Environmental Radiological Sampling Points Legend STATION REFER TO STATION REFER TO NUMBER SAMPLE TYPE FIGURE NUMBER SAMPLE TYPE FIGURE AP, AC, TL 4.1-4 34 TL 4.1-3 AP, AC, TL 4.1% 35 TL 4.1-3 TL 4.1A 36 TL 4.1-3 AP, AC, TL 4.1A 37 TL 4.1-3 AP, AC, MK, FC, TL 4.1-2 38 SW, DW 4.1-2 TL 4.1% 39 GW 4.1-4 TL 4.1& 40 SW, DW 4.1-3 TL 4.1% 41 SS, AV 4.1% TL 4.1% 42 MK 4.1-3 10 TL 43 4.1% TL 4.1A FH 4.1% 12 TL 4.1% 45 4.1-2 13 TL 4.1K 47 AP, AC 4.1% 14 TL 48 TL 4.1-3 15 TL 4.1% 49 TL 16 TL 4.1% 50 TL 4.1% 17 TL 4.1A 51 DW 18 TL 4.1% 52 SD 4.1% 19 TL 4.1-3 53 TL 4.1-2 20 TL 4.1-3, 4.14 4.1W 21 TL 4.1-3 55 FC 4.1% 22 TL 4.1-3 56 TL 4.1% 23 TL 4.1-3 57 GW 4.1< 24 TL 4.1-3 58 GW 4.1% 25 TL 4,1-3, 4.14 59 GW 4.1A 26 AP, AC, AV, SS, SW, TL 4.1-3, 4.14 60 GW 4.1-4 27 TL 4.1-2, 4.14 61 AV 4.1-3 28 TL 4.1-2, 4.14 62 FC 4.1& 29 TL 4.1-2 63 TL 4.1 A 30 4.1-2 31 4.1-2 32 TL 4.1-2 33 TL 4.1-3 AC Air Cartridge FC Food Crop SD Bottom Sediment AP Air Particulate FH Fish SS Shoreline Sediment AV Aquatic Vegetation GW Groundwater SW Surface Water DW Drinking Water MK Milk TL TLD Approximate location 4-22 I )' Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4

5. 0 INTERLABORATORY COMPARISON STUDIES The objective of this program is to evaluate the total laboratory analysis process by comparing results for an equivalent sample with those obtained by an independent laboratory or laboratories.

Environmental samples from the SHNPP environs are to be analyzed by the Harris Energy & Environmental Center (HE&EC) or by a qualified contracting laboratory. These laboratories will participate at least annually in a nationally recognized interlaboratory comparison study. The results of the laboratories'erformances in the study will be included in the Annual Radiological Environmental Operating Report (see SHNPP Technical Specification 4.12.3). SHNPP E&RC will perform sample analyses for gamma-emitting radionuclides in effluent releases. The E&RC radiochemistry laboratory will participate annually in a corporate interlaboratory comparison study or an equivalent study. Radiochemical analyses of composite samples required by Technical Specifications Tables 4.11-1 and 4.11-2 will be performed by the HE&EC. If the CPSL than three laboratory or vendor laboratory results lie at greater standard deviations from the "recognized value," an evaluation will be performed to identify any recommended remedial actions to reduce anomalous errors. Complete documentation on the evaluation will be available to SHNPP and will be provided to the NRC upon request. 5-1 l 'L Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite .Dose Calculation Manual (ODCM) Rev. 4 6.0 TOTAL DOSE COMPLIANCE WITH 40 CFR 190 Technical Specification 3.11.4 requires that the annual dose or dose commitment to a member of the public from uranium fuel cycle sources be limited to 25 mrem for the whole body and any organ except the thyroid which is limited to 75 mrem. In addition, assessment of radiation doses to the likely most exposed member of the public from primary effluent pathways, direct radiation, and any other nearby uranium fuel cycle sources are required by Technical Specifications 6.9.1 to show conformance with 40 CFR 190 limits. The results of the dose assessments are submitted with the Radioactive Effluent Release Report. If a dose assessment is made as a requirement of Technical Specification 3.11.4, the calculation will include a complete statement of the assumptions and parameters used in calculating the dose for the report. 6.1 Dose to the Likel Most Ex osed Member of the Public 6.1.1 Effluent Pathwa s The ODCM dose equations for noble gases, iodines, particulates, and tritium provide conservative estimates because the X/Q and D/Q are historical values for the exclusion boundary distances. Because these distances are fixed and represents the closest points in the unrestricted areas to the plant, it assures that 10 CFR 50 Appendix I doses to a member of the public are unlikely to be substantially underestimated. More realistic estimates of the actual doses from the gas and liquid effluent pathways to the likely most exposed member of the public can be obtained by using the Regulatory Guide 1.109- and WASH 1258-based NRC codes LADTAP II and GASPAR. These permit use of current annual average meteorology X/Q and D/Q values derived from the NRC XOQDOQ (NUREG/CR-2919) Code appropriate for the specific location of the receptor and the applicable exposure pathways. 6.1.2 Direct Radiation Radiation exposures of members of the public from direct radiation sources (the reactor unit and other primary system components, radwaste, radioactivity in auxiliary systems such as storage tanks, transportation of radioactive material, etc.) will be determined from TLD measurements. Quarterly TLD measurements at locations within three miles of the plant center (inner ring) will be compared with the four-year, pre-operational TLD measurements using methods contained in NBS Handbook 91, "Experimental Statistics," to determine any significant contribution from direct radiation associated with plant operation. If there location is a significant direct radiation component at the TLD in the sector containing the likely most exposed member of the public then this dose will be added to the doses from effluent pathways derived from IADTAP II and GASPAR. 6-1. Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 6.2 Dose to a Member of the public Due to Activities Within the Site Boundarar The.Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include assessments of the radiation doses to members of the public due to activities within the site boundary. The Harris Lake is generally available for public recreational purposes year-round, and certain areas are within the site boundary (Figure 4.1-4). 1 LADTAP II and GASPAR allow the calculation of doses for special cases. The assumptions used in the calculations, e.g., exposure time, location, and activity, will be included in the Radioactive Effluent Release Report. 6-2. Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 - LICENSEE-INITIATED CHANGES TO THE ODCM Pursuant to Technical Specification 6,14.2, licensee to .the Offsite Dose Calculation Manual: initiated changes Shall be submitted to the Commission in the Radioactive Effluent Release Report for the period in which the change(s) was made effective. The submittal shall contain: a) Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information. Information submitted should consist of a package of those pages of the ODCM changed with each page numbered, dated, and containing the revision number together with the appropriate analyses or evaluations justifying the change(s). b) A determination that the change will not reduce the accuracy or reliability of dose calculations or set point determination. c) Documentation of the fact that the change has been reviewed and found acceptable by the PNSC. 2 ~ Shall become effective upon review and acceptance by the PNSC. 7-1 J' Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Sheet 1 of 3 APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS Carolina Power 6 Light Company (CP&L) has performed the assessment of the transport and dispersion of the effluent in the atmosphere as outlined in Pre aration of Radiolo ical Effluent Technical S ecifications for Nuclear Power Plants, NUREG 0133 (USNRC, 1978). The methodology for this assessment was based on guidelines presented in Regulatory Guide 1.111, Revision 1 (USNRC, 1977) The results of ~ the assessment were to provide the relative depositions flux and relative concentrations (undepleted and depleted) based on numerical models acceptable for use in Appendix I evaluations. Regulatory Guide l.ill presented three acceptable diffusion models for use in estimating deposition flux and concentrations. These are (1) particle-in-cell model (a variable trajectory model based on the gradient-transport theory), (2) puff-advection model (a variable trajectory model based on the statistical approach to diffusion), and (3) the constant mean wind direction model referred to here as the straight-line trajectory Gaussian diffusion model (the most widely used model based on a statistical approach). It was resolved that for operational efficiency, the straight-line method described in X~O DO/ Com uter Pro ram for the Meteorolo ical Evaluation of Routine Effluent Releases at Nuclear Power Stations, NUREG/CRC-2919 (USNRC, September 1982) would be used for generating the required analyses of Appendix I. To provide a more realistic accounting of the variability of wind around the plant site, standard terrain/recirculation correction factors (TCF) were used. Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Sheet 2 of 3 APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS A twelve-year record of meteorological data was used from the on-site meteorological program at the Shearon Harris Plant. These data consisted of all collected parameters from the normal 10.0 meter tower level for the years 1976-1987. The description of the model used and the computations are presented in NUREG/CRC-2919. The following tables provide the meteorological dilution factors (i.e., the X/Q and D/Q values) utilized to show compliance with Technical Specifications 3/4.11.2 for noble gases and radioiodines and particulates. Tables A-1 through A-4 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for ground level releases for special locations for long-term releases. Tables A-5 through A-12 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for ground level releases for standard and segmented distance locations for long-term releases. Table A-13 SHNPP on-site joint wind frequency distributions for 1976-1987. The X/Q and D/Q values which are utilized in the appendices are all assumed to be ground level releases. A-2 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Sheet 3 of 3 APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS The NRC "XOQDOQ" Program (Version 2.0) was obtained and installed on the CP&L computer system. For routine meteorological dispersion evaluations, the "XOQDOQ" Program will be run with the appropriate physical plant data, appropriate meteorological information for the standard distances, and special locations of interest with a terrain/recirculation factor. The input to "XOQDOQ" for ground level releases are presented in Table A-14. The resulting computations will have the TCFs applied to produce a final atmospheric diffusion estimate for the site. 'V Shearon Harris NLlclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE A-1 THROUGH A-4 USNRC COMPUTER CODE XOQOOQ, VERSIOH 2.8 RUN DATE: 06/23/94 RUH TIME: ob:46:27 XOQOOQ -- SHHPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 EXIT ONE GROUND-LEVEL HISTORICAL DATA, 1976-1987 CORRECTEO US STANDARD OPEN TERR AIK FACTORS Table Table Table Table SPKCIFZC POI HTS OF INTEREST 'A-2 A-3 A-4 RELEASE TYPE OF . DZRECTZOH DISTANCE X/Q X/Q X/Q D/Q ZD LOCATION FROH SITE (HZLES) (METERS) (SEC/CUB.HET ER) (SEC/CUS.HETER) (SEC/CUB.HETER) (PER SQ.METER) KO 2.300 OAY DECAY S.OOG DAY DECAY DEPLETED DEPLETED DEPLETED A SITE BOUNDARY S 1.36 2189. 6.1E 86 5.9E-06 5.2E-06 8.SE-09 A SITE BOUNDARY SSN 1.33 2140 ~ 6.eE-06 5.bf G6 5. lf-06 8,7E-09 A SITE BOUHOARY SII 1.33 2148. 5.5E-06 5.4E-86 4.7E-O6 7.0E-09 A SITE BOUNDARY IISW 1.33 2140. 4.SE-06 4.7E-06 4. lf-06 5.4E-O9 A SITE BOUNDARY )I 1.33 2140. 3.6E 06 3.6E-86 3. 1E-06 4, 1E-09 A SITE BOUNDARY )IHII 1.33 2140. 2.8E-06 2.7E-G6 2.4E-G6 3,3E-09 A SITE BOUNDARY NII 1.26 2028. 2.9E-86 2.SE-G6 2.5E-86 3.9E-09 A SITE BOUKDARY NNM 1.26 2828. 3.3E"06 3.2E-06 2.SE-G6 5. 1E-G9 A SITE BOUNDARY N 1.32 2124. 3.SE-86 3.SE-06 3.3E-06 6.6E-09 A SITE BOUNDARY NNE 1.33 2140 ~ 4. 1E-86 4.OE-06 3 ~ 5E-06 7.9E-09 A SITE BOUNDARY HE 1.33 2140. 3.2E 06 3.2E"06 2.7E-06 7.3E-O9 A SITE BOUNDARY ENE 1.33 2140. 2.4E"06 2.4E 06 2. 1E-06 6.3E-09 A. SITE BOUKDARY E .1.33 2140. ,2.0f"06 lo9E-G6 1.7E 06 3.SE 09 A . SZTE BOUHOARY ESE ~ 1.33 2140 ~ l.bf 86 1.7E 06 1.5E-06 4.0E-89 A SITE BOUNDARY SE 1.33 2140. 2. 1E-06 2. 1E"06 1.SE-06 5. 1E-G9 A SITE BOUNDARY SSE 1.33 2140, 3.5E-06 3.4E-06 2.9E-06 6.2E-G9 A NEAREST RESIDENT SSH 3.90 6275 ~ 7.8E-07 7.3E-07 5 'E-G7 6. SE-10 A KEAREST RESIDENT SII 2.80 4506. 1.3E-06 1.2E-06 1.0K-06 1.2E-09 A NEAREST RESIOEKT IISH 4.30 6920. 5.4E-07. 5.0E-07 4.0E-07 3.4E 10 A HEAREST RKSIDENT H 2.78 4345. 9.2E-07 B.BE"07 7.3E-07 7.3E 10 A KEAREST RESIDENT IIKN 2.10 3380. 1 lE 06 ~ 1.1E-06 9. lf"07 1. lf-09 A NEAREST RESIDENT HI( 1.80 2897. 1.4E"06 1.3E-06 11E06 1.6E-09 A NEAREST RESZDf HT HIAI 1.50 2414. 2.2E 06 2.2E-06 1.9E-06 3.3E 09 A NEAREST RESZOEKT N 2.28 3540. 1.4f-06 1.3E-06 1.1E-86 1.9E-09 A NEAREST RESIDENT NKE 1.70 2736. 2.4E 06 2.4E 06 2.OE>>06 4.3E-09 A NEAREST RESIDENT HE 2.30 3781, I.OE 06 1.OE-06 8.5E-07 1.9E-09 A NEAREST RESIDENT ENE 2.00 3219 1.0E-06 1,OE-06 8.5E-07 2.3E-09 A HEAREST RESIDENT E 1.90 3857. 9.3E-07 9.1E 07 7.7E-G7 1 6E 09 A NEAREST RESZOENT ESE 2.7G 4345. 4.3E-07 4.1E-07 3.4E-GT 7. 3E-10 A KEAREST RESZDEKT SE 4.70 7562. 1 9E-07 ~ 1.8E-07 1.4E-07 2. 6E-10 A NEAREST RESIDENT SSE 4.4G 70S1. 3.6E 07 3.4E-07 2.7E 07 3.7E-10 A GARDEN SSH 3.98 6276. 7.SE"07 7.3E"07'.2E-O6 5,9E 07 6.SE-10 A CARDEH SW 2.80 uses.'920. 1.3E 06 1.GE-06 1 ~ 2E 09 A GARDEN IISH 4.30 5.4E-07 5.0E-07 4.OE-O7 3. 4E-10 A GARDEN H 3 +00 4828. 7.6E-07 7.2E-07 6.0E 07 5.7E 10 A GARDEN IIHII 2. 10 3380. 1. 1E" 06 1. 1E-06 9. 1E-07 1. 1E 09 A CAADEH HII 3.80 6116. 3. 5E-07 3.3E 07 2 'E-07 2.SE-10 A GARDEN NNII 1.90 3658. 1.4E 06 1.4E 06 1. lf-06 1. SE-09 A GARDEN N 2.2G 3540. l. uf-06 1.3E-O6 l. 1E-06 1.9E-09 A GARDEN NHE 1.70 2736. 2.4f 06 2.4E-06 2.0E-06 4.3E-09 A GARDEN Nf 2.30 3701. 1.0E-06 1.0E-86 8.5E-O7 1.9E-09 A GARDEN E 4.70 7564. 'I.SE-07 1.7E-07 1.3E 07 2.0E 10 A GARDEN ESE 2.80 uses. 4.0E-07 3.9E-07 3.2E 07 6.7E 10 A GARDEN SE 4.7G 7562. 1.9E 87 1. bE-07 1.4E-07 2. 6E-1G A CORI MILK H 2.20 3540. 1.4E 06 1.3K-G6 1. 1E 06 1.9E-09 A COII HZLK NNE 2.92 4703. 8.5E-07 8.2E-07 6.7E-07 1.2E'-09 A MEAT k POULTRY SSH 4.40 7081. 6.3E-87 5.9E-07 4.7E-07 5.2E 10 A MEAT 8 I'OULTRY S'lI 2.80 4506. 1.3E-06 1.2E 06 1.OE-e6 1.2E-09 A HEAT 8 POULTRY HSII 4.30 6928. 5.4E-07 5.0E-07 4.0E-07 HEAT a POULTRY 3. 10 3. 4E-10 A W 4989. 7 2f-07 6.SE-OT 5.6E"07 5.3E-lG A HEAT 8 POULTRY llNH 2.50 4823. d. 1E-07 7.7E-07 A HEAT 8 POULTRY 6.4E 07 7 ~ 2E 10 NII 3.80 6116. 3.5E"07 3.3E-GT 2.6E"07 2. SE-1G A MEAT 8 POULTRY NIOI 1.90 3058. 1.4E-86 1.4E-G6 1 1E 06 1.SE-09 A A HEAT k POULTRY RELEASES'NC HEAT a POULTRY HNE H 2.20 1.80 3540. 2897 1.4E-06 2.2E-06 1.3E-06

2. 1E-06 1

~ ~ lf G6 1.9E-09 A MEAT 8 poULTRY 1.SE 06 3.8E-G9 KE 2.30 '701 ~ 1.0E 06 1. 0E-06 8.5E"07 1.9E"G9 A MEAT k POULTRY EHE 2.ee 3219. 1.OE-06 1. GE-G6 A HEAT 8 POULTRY 8.5E 07 2.3E-09 ESE E 4.6G 7483. 1.8E 07 1.7E 07 1.4E 07 2. 1E" 18 A HEAT 8 poULTRY 4.40 7081. 1.SE G7 1.7E-OT I 1.3E 07 2. 4E-18 VEHT AKD BUILDIKC PARAMETERS REL EASE HKICHT (METERS ). G.ee DIAMETER (METERS ) -e.ee REP. IIIKD HEIGHT (METERS) lb.0 EXZT VELOCITY BUILDIKC HEIGHT (HETERS) ss'.e (HETERS ) G.ee BLOC.MIN.CRS.SKC.AREA (SQ.METERS) 2161.0 HEAT EHZSSZOH RATE (CAL/SEC) 0.0 ALL GROUND LEVEL A-4. TABLE A-5 O CA H) O Ol Undepleted, No Decay, X/Q Values For Long Term Ground Level Releases At Standard Distances (Sec/ms) tt O t0 t7 0 X USNRC COMPU1'KR CODE XOQDOQ, VERSIOH 2.0 RUN DATE: 06/23/94 RUN TIHE: 08:46:27 th tf O XoqDOq SHNPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 O I)) EXIT ONE GROUND-LEVEI. HISTORICAL DATA) 1976-1987 NO DECAY, I UNDEPLETED CORRECTEO USINO STANDARD OPEN TERRAIN FACTORS ANNUAL AVKRAGK CHI/q (SEC/METER CUBED) DISTAHCE IN MILKS FR OM THE SITE rrI o g C ct l5 0 SECTOR e.ase e.see e.vse i.eee i.see a.eeo "2.500 3.000 3.500 4.000 4.500 o 1.72BE 04 5.121E-05 2.531E-05 1. 246E" 05 4.943E-06 2.814E-06 1.851E-06 1.330E-06 1. 015E-06 8.077E-07 6.637E-07 0 SS'W SM S

1. 571E-64 4.715E-B5 2.346E-05 1.15BE 05 4.596E-06 2.6G7E-06 1:711E-06
1. 481E-04 4.412K-e5 2.182E-05 1.074E-05 4.263K-06 2.428E-06 1.597K-06 1.227E-06 1.14BE-06
9. 341E-07 8.757E-01 7.424E-07 6.911E-B7 6.093E-07 5.728E-07 X

jl C I WSM MNM 'M 1.295E-04 3.842K-05 1.893E-05 9.308K"06 3.693E-06 2. 1GSE-06 1.389E-06 9.839K"05 2.921E"05 1.440E-05 7.087E-06 V.43eE-eS 2.216E-05 1.098E-05 5.420E-B6 2.S14E-06 1.605E-06

2. 154E-06 1.225E-06 1.057E-06 8.053E-07 9.995E-07 7.60SE-07 5.784E-07 7.632E-07 5.808E-07 4.409E-07 6.080K-O7 4.626K-07 3.508E-07 4.999E-GT 3.803E-07 2.881E-07 rr S~

Dl NW 6.636E-85 1.996E-05 9.994E-06 4.967E-O6

7. 179E-05 2. 185K-05 1. 111E-05 5.57BE B6 1.9S2E-06 1.121F-06 2.234E-06 1.254E-06 7.339E-07
8. 166K-07 5.254E-07 5.820E-07 3.995K-B7 4.409E-07 3.111E-07 3.489E-07 2.599E-07 2.853E-07 0

Cf rt NHM N 9.224E-05 2.824K-05 1.448E-05 7.277E-B6 2.919E-06 1.633E-G6 1.060E-06 7.539E-07 5.701E"07 4.505K-07 3.678E-07 O~ NNE 9.847E-05 3.034E-B5 1.560E-05 7.846E-06 3. 145K-06 1.754E-06 1.137E-06 8.870E-87 6.094E-07 4.810E-07 3.923K-07 NE 7.892E"05 2.430K-05 1.24GE-05 6. 194E" 06 2.467K-06 1.376E"06 8.91SK-01 6.333E-Ol 4.784E-07 3.771E-B1 3.081K"07 ENE 5.998E-05 1.845E-05 9.388K-86 4.679E-06 1.860E-06 1.036E-06 6.711E-07 4.764E-07 3.597E-07 2.839E-G7 2.316K.-O7 E 4.983E-05 1.498E-05 7.585E-06 3.vvgE-e6 1.506E-06 8.439E-G7 5.4SBE-07 3.90SE-07 2.959K-07 2.341E-07 1.913E-07 ESE u'.usSE-es 1.361E-05 6.e72E-e6 3.uivE-e6 1.359E-06 7.616E-07 4.952E-07 3.527E-07 2. 67BE-G7 2. 112E-07 1.726E-07 SE 5.351E-05 1.632E-05 S.255E-06 u.ieaE-e6 1.629E-06 9. 123E-07 5.929E-87 4.221E-B7 3.'l95E-07 2.526E-OT 2.064E-07 SSE 9. 101K-05 2.734E-05 1.361K-G5 6.718E-06 2.666E-06 1.509E-06 9.8S5E-07 7.081E"07 5.387E-07 4.278E-O7 3.509E-07 ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTAHCE IN MILES FROM THE SITE SECTOR s.eoe l.see ie.eee is.eoe ae.oee as.eoe 30.0ee 3s.ooo 48.060 4S.eee Se.oee S 5.589E-07 3.064E-07 2.075E-07 1.263K-e7 8.984K-GB 6.799E-0S 5.459E-GS 4.537E-OS 3.867E-GS 3.360K-GB 2 964E"08 ~ SSM 5. 126E-07 2.198E-GT 1.890E-BT 1. 147E 87 8.066K-GB 6. 149E"08 4.930E-GB 4.093E-GB 3.485K-OS 3.026E-OS 2.667K-GS SM 4.824E-ev 2.645E-07 1.791E-07 1.090E" 07 7.686E"08 5.869E"GS 4.712K-GB 3.916E-OS 3.338E-BB 2.900K-GB 2.55BE"08 'MSM 4.213E-07 2.315E-07 1.570E-07 9.574E-BB 6.758K-ee 5. 165E-oe 4.150K-GB 3.451E-OS 2.943E-OS 2.558E-GB 2.257E"08 W 3.205E-07 1. 760E-07 1.193E 07 7.275E-GB 5 133E-08 3.922E-GB 3 151E-08 ~ 2.620E-OB 2.234E-GB 1.941E-OB 1.713K 08 WHM 2.426E-07 1.328K-G? 8.985E-68 5.463E-GB 3.849E-BB 2.937E-BB 2.357E-GB 1.958E-BB 1.668E-GS 1.449E-OB 1.278E-GB NW 2. 185K-87 1, 18SE-07 B.e85E-ee 4.839E-GB 3.396K-ee a.seuE-oe 2.069K-ee 1.716E-GB 1.460E-GB 1.266K-OB 1. 115E"08 NNM 2.392E-G7 1.290E-07 8.639E-GS 5. 181E" GS 3.617K-GB 2.741E" 08 2.187E-GB 1.809E-GB 1.535E-GB 1.329E-GB 1. 16SE-08 N 3.081E-87 1.654'E-07 1. 105K-07 6.603E-GB 4.597E-GB 3.478E-GB 2.771E-BB 2.289K-GS 1.940E-OB 1.678E-GB 1.474E-GB NNE 3.283E-07 1.758E-ev 1. 171E-07 6.980E-GB 4.8'52E-08 3.665E"88 2.918E-GB 2.408E-OB 2.040E-OB 1.763E-OB 1.548E-OB NE 2.579E-07 1.383K-ol 9.230E-GB 5.512E-BB 3.839E-ee 2.904E-ee 2.315E-GB 1.912K-GB 1.622E-OB 1.403K-OB 1.232K-OB ENK 1.938E-07 1.039E-07 6.935K-GB 4. 142E-08 2.8S6E-GB 2. 184E-GB 1.741E-GS 1.439E-GS 1.220E-GS 1.056E"08 9.278E"G9 E 1.684E-GT 8.645E-OS 5 '89E-08 3.473E"08 2.426K-GB 1.840E"GS 1.469E-GB 1.215E-OS 1.032E-OB 8.935E-O9 7.858E-09 ESE 1. 441E-07 7.804E-GS 5.228K-GB 3. 139K-GB 2. 193K-08 1.664E-BB 1. 329E-08 1. 100K-08 9. 34 lE-09 8.091E-09 7. 117E-09 C SE 1.730E-07 9.328E-GB 6.248E-OS 3.750E-GS 2.620E"08 1.9SSE-GB 1.588E-08 1.314E-GB 1. 116E" 08 9.665E-09 8.501E-O9 SSK 2.950E-07 1.6eBE-ev i:eesE-ev 6.575E-BB 4.622E-GS 3.522E-GS 2.823E-GB 2.343E-OS 1.995K"08 1.732E-GB 1.526K 08 VENT AND BUILDING PARAMETERS: 4 r RELEASE HEIGHT (METERS) e.oe REP. MIND HEIGHT (METERS) 10.0 C DIAMETER (METERS) e.oe BUILDING HEIGHT (METERS) 55.0 C EXIT VELOCITY (METERS) 8.00 BLDG.MIN.CRS.SEC.AREA (SQ.METERS) 2161.0 HEAT EMISSION RATE (CAL/SEC) 0.0 ALL GRDUND LEVEL RELEASKS. TABLE A-6 O CA H) 0 I tA Un d epleted, No Decay, I/Q Values For Long Term Ground Level Releases At Standard Distances (Sec/ms) I rt 0 tO J O l5 (h USNRC COMPUTER CODE - XOQDOQ, VERSION 2.0 RUN DATE: 06/23/94 RUN TIHE: 08:46:27 0 XOQDOQ SHNPP GROUND-LEVEL HISTORICAL DATA, 1976" 1987 n rn I EXIT -- GROUND-LEVEL HISTORICAL DA1'A, 1976-1987 n ONE g n NO DECAY, UNDEPLKTKD V V tD CHI/q tSKC/HETER CUSKD) FOR EACH SECHENT rt V' SECHENT BOUNDARIES IN HILES FROH THE SITE o DIRECTIOH .5-1 1 2 2-3 3-4 4 5 5-10 10-20 20-30 30-40 40-50 0 FROH SITE X C p) 0 S 2.535E-05 5.661E-86 1.910E-06 1.026E-66 6.616E-07 3. 1s5E-e7 1 . 278K- G7 6.S24E-GS 4.545E-GS 3.363E-88 SSW 2.344E-05 5.264E-06 1.756E"86 9.447E" 07 6.129K-07 2.912E-07 1. 161K-07 6. 172K-Gs 4. 101E-08 3.029E-GS SM 2. 185E-05 4.881E-06 1.639K-86 S.855E-07 5.761K-07 2.749E-07 1. 103 E-G7 5. 891E-98 3.923K-OS 2.903E"08 WSW 1.899E" 05 4.236E-16 1.425E-06 7.715E" 07 5.02SE"07 2.405E-01 9.683E-08 5. 184E-GS 3.457E-08 2.560E-GS M 1.444E-05 3.226K 06 1.085K-66 5.872E-07 3 . 826 E-01 1, 829E-07 7'.35SE-es 3.937E-GS 2.624E-OS 1.943E-GS Hthl 1.G99E"05 2.467E-06 8.265E-07 4.459E-07 2.S9SE-07 1. 381E-07 5. 528E-18 2.948K-08 1.962E-GS 1.451K-08 O rt NM 9.915E-06 2.263E-06 7.538E"07 4.041E-GT 2.615E-07 1.237K-07 4.902E"08 2.595E-GS 1.719E-08 1. 267K-GS NIAI 1 103 E-05 ~ 2.540E-06 8.395E 07 4. 462E-07 2. 871E-07 1. 345E-07 5.254E-08 2.753E-08 1. 813E-es 1,339E-08 Q~ N 1.43'4E-85 3.316E-66 1.891E 86 5.771E 07 3 .712E-07 1.727E-07 6'.16eE-es 3.494E-GS 2.294K-08 1.680E-GS NNE 1.543 E-05 3.572E-16 1. 169E-86 6. 1 69E-07 3.949E-87 1.836E-07 T.es6E-es 3.682E-08 2.413E-GS 1.765E-es NE 1.229E-65 2. 8 \ 1E-06 9.116E-67 4.843E-07 3. 102E-07 1.445E-07 5.595E"08 2.918K-08 1.917E-GS 1.404E-GS ENE 9.309E-06 2. 121E-16 6.966E 07 3.642E-07 2.331E-07 l.es5E-e7 4.'2e4E-es 2. 194K-GS 1.442E-GS 1.G57E-GS E 7.536E-06 1.711E-16 5.6'43E-01 2.995E-GT 1.925K-97 9.019E-GS 3.523E-08 1.84SE-08 1.218E-08 8.946E-69 ESE 6.833E-86 1.551E-06 5.092K"07 2.782E-07 1.737E-87 8. 141E-08 3. 183E" G8 1.671E-GS 1. 102E-08 S. le 1E-09 SE &.202E-86 1.866E-66 6.097 E-GT 3.233E-GT 2.078E-GT 9.732E-GS'.674E-07'. 3 . 803K-08 1.996E-08 1.311E-GS 9.676E-09 SSE 1.360E"85 3.052K-06 1.015E 06 5.449E-07 3.530E-07 6.651E-G8 3.536E-08 2.34SE-GS 1.733K-08 Table A-7 O co W tD Ol Undepleted, No Decay, X/Q Values for Long-Term Ground Level Releases at Standard Distances (Sec/ms) V' tt 0 - 0 USNRC COHPUTER CODE XOQOOQ, VERSION 2.0 RUN DATE: 06/23/94 RUH TZME: Gs:46:27 XOQDOQ SHNPP GROUND LEVEL HISTORICAL DATA, 1976-1987 0 g) 0 EXIT ONE -" GROUND-LEVEL HISTORICAL DATA 1976-1987 O t5 2.380 DAY DECAY, UNDEPLETED 0> CORRECTED )SING STANDARD OPEN TERRAIN FACTOR o g ANNUAL AVERAGE SECTOR CHI/O (SEC/HETER CUBED) e.25e e.50e e.75e l.ooe DISTANCE 1.500 IH MILES 2.000 FROM THE II 2.500 SITE 3.000 3.500 u.eee 4'5GO vv g 0 ft V't S 1.712E-04 5.078E-05 2.5GGE-G5 1.226E-05 4.824E-06 2.7P3E-06 1.776E-06 1.266E-06 9. 57 1E-07 7.553E"07 6. 153K-07 0 SSH 1.564E-04 4.675K-e5 2.318E-e5 1. 139E-85 4.489E-06 2.525E-06 1.643E" 06 l. 16SE-e6 8.820E-G7 6.951E-GV 5.657E-07 0 SM 1.474E-04 4.374E-05 2. 15'4E-85 1.056E-05 4. 15BE-06 2.3'47E-06 1.531K"86 1. 091E-06 8.247E-07 6.50SE-GV 5.301E-07 X 0C NSH 1.2S9E-04 3.BOSE-G5 1.869E-05 9. 149E-06 3.6oeE-e6 2.036K-06 1.33eE-e6 9.4S4E-07 7. 177K-07 5.667K-e7 4.619E-eT H 9.794E-05 2 '95E-05 1.422E-05 6.966E-06 2.743E-06 1.551E-06 1. 013E" G6 7.221E-07 5.464E-GV 4.314E-GV 3.515E-07 WNW 7.39SE-05 2. 197E-05 1.085E-G5 5. 33 1E-,06 2. 102E-06 1. 185E-86 7.723E-B7 5.499E-B7 4. 156E-07 3.2'18E-07 2.669K-OT NU 6.609K-05 1.980E-05 9.879E-B6 4.892E-06 1.938E-06 1.'es7E-e6 T.e6eE-e7 5.014E-07 3.782E-GV 2.97SE-e7 2.421E-07 NW 7. 152E-05 2. 170E-05 1.099K"05 5.495E-06 2. 189E-06 1.22GE-06 7.887E-07 5.5S1E-07 4. 197E-07 3.297E-07 2.676E-07 N 9. 191E-G5 2.805E-05 1.434E-05 7. 184E-06 2.864E-06 1.591E-06 1:e26E-e6 7.247E"07 5.442E-87 4.2TBE-B7 3.463E-GV O rt HNE 9.814E-05 3.014E-05 1.546E 05 7. 751E-86 3.0SSE-G6 1.712E-B6 1, 1G2E-06 7.710E-G7 5.829E-GV 4.570E-07 3.703E-GT t7 NE 7.865E-05 2.414E-05 1.22BE-85 6. 117E-06 2.422K-06 1.342E-06 8.635E-07 6. 091E-07 4.569E-GV 3.582E-B7 2.902E-OT Om ENE 5.97BE-05 1.833E-05 9.300E-06 4. 621E-06 1.82SE-e6 l.ellE-e6 6.499E-07 4.582E-07 3.436E-B7 2.693K 07 2.182K-07 E 4.BS5E-05 1.487E-05 7.507E-G6 3.729E-06 1 ~ 476E"G6 S.212E-GV 5.301K-07 3.74BE"07 2.817E-G7 2.212E-GT 1.794K"07 ESE 4.441E-05 1 351E-05 ~ 6.801E 06 3.372K-06 1.332K-06 T.411E-GT 4-783E-BT 3.3B2E-B7 2. 541K-07 1.996K-07 1.619E-07 SE 5.331E-05 1. 621E-05 8. 172E-06 4.047E-06 1.597E-06 8.879E-07 5.72BE"07 u.eusE-eT 3.042E-GV 2.38BE-07 1.937E-GT SSE 9.063K-05 2.712K-B5 1.345E-05 6.616K-06 2.606E-06 1.463E-06 9.505K-07 6.753E-ev 5.095E-GV 4.014K-07 3.265E-G7 ANNUAL AVERAGE CHI/O (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE SECTOR 5.000 7.500 10.808 15.000 28.000 25.880 30,0GG 35.000 45.000 50.eeo S 5. 13BE-07 2.700E-07 1.755K-G7 9. 871E-08 6.459E-GB 4.597E-GB 3.454E-OS 2.697E-es 2. 167E-08 1.781E-GB 1.490E-OS SSH 4.719E-GT 2.472E-GT 1.603E-GV 8.990E-GB 5.871E-GS 4.172K-GB 3.131K-BB 2.442E"08 1 ~ 960E-08 1.609K-OB 1.345E-GB SU 4.426E-07 2.324E"07 1.509E-07 S.u72E-es 5.532E"08 3.929E-BS 2.946E-GB 2.296E-es 1. 841K-08 1 510E-GS ~ 1.261E OS HSH 3.85BE-07 2.029K-B7 1.31BE-B7 7.405E-GB 4.835E-es 3.433E-es 2.574E-es 2.ee5E-GS 1.607E-OS 1'.317F.-es 1'. 100E-es H 2.936E-GV 1.544E-07 l.ee3E-eV 5.633E-GB 3.678E-OB 2.612E-GB 1.95BE-GB 1.525E-BS 1.223E-GB 1.003K-OS 8.370E-B9 'MSt 2.228E-07 1. 169E-07 7.589E-GB 4.259E"08 2.782K-GB 1.976E-BS 1.482E-GB 1. 155E-08 9.267K-09 7.602E-09 6.350E-09 Ol 2.019E-GV 1.055E-07 6.837E-.GB 3.834E-OB 2.505E-GB 1.782E-GB 1.339E-OB 1.045E-BB 8.394E-09 6.896'E-09 5.76BE-09 NSI 2.22BE-07 1.159E-07 7.490E-OS 4. 194E-08 2.742E-OS 1.953E-GB 1.470K-GB 1. 150E-08 9.252E-09 7.614E-09 6.378E-09 N 2.BBGE-07 1.495E-OV 9.650K-OB 5. 401E-08 3.534E-OS 2.520E-OS 1.89BE-OS 1.486E-GB 1. 19SE-Gs 9.86BE-09 8.276E-G9 NNE 3.07SE-BV 1.594E-07 1.828E-G7 5.753K-GB 3.766E-OS 2.687E-GB 2.026K-GB 1.5BBE"08 1.281E-BB 1.057E-GS 8.812E-09 NE 2.413E-GT 1,25BE-07 8.065K-OS 4.512E-GB 2.953E-OB 2. 106E-08 1.588E-OS 1.244E-GB 1.003E-GB 8.276K-O9 6.949E-e9 ENE 1.814E-07 9.395E-OB 6.060E-OB 3.391E GB 2.220E-GB 1.585E-GB 1. 195E-08 9.369E-09 7. 561E-09 6.239E-G9 5.241E G9 E 1.493E-GT 7.761K-GB 5.'eluE-es 2 ~ SGVE-08 1.836E-GS 1.30SE-GS 9.S47E-09 7.7G5E-09 6.205E-09 5. 11GE-09 4.284E-09 ESE 1.347K-eT T.eo5E-OB 4.527E-GB 2 '35K-08 1.659E-OS 1. 183E-08 S.908E-09 6.974E-09 5.619E"09 4.630E-09 3.884E-09 SE 1.612K-07 8.37BE"08 5. 414E-08 3.033K-GB 1.985E-G& 1.416K-GB 1.067E-GB 8.353E-09 6.732E-09 5.549E-09 4.657E-09 SSE 2.723E-G7 1.425E-07 9.243E-OS 5 189E"GB 3.394E-OS 2.416K-GS ~ 1.816E-es 1.419E-OB 1. 140E-08 9.37BE-09 7.851E G9 VEHT AND BUILDING PARAHETERS: RELEASE HEIGHT (METERS) 0.00 REP. MIND HEIGHT (HETERS) 1O.G DIAHETER (HETERS) e.ee BUILDING HEIGHT (METERS) 55.0 EXIT VELOCITY (HETERS) e.'oe BLOC.HZH.CRS.SEC.AREA (SQ.METERS) 2161.0 HEAT EHZSSIOH RATE (CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES. Table A-8 O CA H) I Undepleted, No Decay, X/Q Values for Long-Term Ground Level Releases at Standard Distances (Sec/ms) rct N e 0 fD a0 N N O Ql " 2.0 06/23/94 TIME: 08:46:27 USNRC COHRUTER CODE ~ xoqooq sHNpp XOQDOQ, VERSION ORDUND-LEYEL HIsToRIGAL DATA, RUN DATE: 1976-1987 I RUN rr o g Pl tt O 0 EXIT ONE -" GROUND-LEVEL HISTORICAL DATA> 1976-1987 2.308 DAY DECAY, UNDEPLETED o CHI/Q (SEC/HETER CUBED) FOR EACH SECHENT A C8 SECHENT BOUNDARIES IN HILES FROH THE SITE DIRECTION .5-1 1 2 2 3 3"4 4-5 5" 10 10" 20 20-3G 30-40 40-50 FROH SITE S 2.506E-05 5.542E-B6 1.825E"06 9.6s3E-e7 6. 192E-07 2.822E-07 1.006E-BT 4.636E-08 2.711E-08 1.787E-08 SSM 2.31SE-05 5. 151E-06 1:688K-e6 8.926E-OT 5.693K-BT 2.585E-07 9. 168E-08 4.289E-BS 2.455E-BS 1.615E-08 SH MSH

2. 159E-05 1.876E-05 4.776E-06
4. 138 E-06 1.572E 86 1.366E-06 8.345E-07 7 261E-87 5.334E-BT 4.647K-BT 2.429E-07
2. 119E-BT s.636E-es 7.5'47E-Bs 3.964E-OS 3.463K-OS 2.309E-GS 2.016E-08 1.516E-GG
1. 323 E-08 a0O~rt H 1.427E" 05 3. 152E" 06 l.e4eE-e6 5.528K-BT 3.537K-07 1. 613E-07 5.741E-08 2.635E-OS 1.534E" 08 l.e06E-es NW 1 . 087E-05 2.412E-e6 7.934K-GT 4.205E-BT 2.686E-ev 1.222E 07 4.343E-BB 1.994E-GS 1. 162E-08 7.632E-09 NM 9.867K-06 2.216E-06 7.259E-B7 3;827E-07 2.437K"07 1.184E-B7 3.911E-08 1.798E-08 1. 051E" 08 6.922E-G9 NNH 1.093 E-05 2.493E-06 8. 116E-87 4.25BE-BT 2.694E-07 1.214E-07 4.281E-08 1.970E-08 1. 156E-08 7.641E-09 N 1.421K-05 3.25SE-06 1.056E-06 5.511K-07 3.486E-07 1.567E-07 5.515E-08 2.541E-BS 1.494E-08 9.903E-G9 NNE 1.530E-05 3.513E-06 1.134E 86 5.984E-07 3.728K-07 1.672E-07 5.svvE-es 2.710K-08 1.596E-OS 1.060E-08 NE 1.21SE 05 2.763K-06 8.893E-07 4.628E-07 2.923K-07 1. 311E-07 4.6G8E-08 2. 125E-08 1.251E" 08 8.305E-09 ENE 9.227E-B6 2.884E 06 6.694E-B7 3.4seE-ev 2. 197E-07 9.855E-BS 3.464E-BS 1.59SE-BS 9.418K-09 6.261E-09 E 7.464E-06 1.685E"06 5.456E-07 2.852E-BT l.ee6E-ev 8. 134E-08. 2.866K-GS 1.319K-BS 7.746E-09 5. 129E-09 ESE 6.76SE-06 1.523E-06 4.923E-BT 2.574E-07 1.630K-07 7.341E-es 2.58SE-OS 1. 193K-08 7. G10E-09 4.647E-09 SE s.124K-e6 1.826K-86 5.897E" 07 3.080K-GT 1.950E"07 8. 781E-08 3.096K-08 1.428E"08 8.396E-09 5 '69E-09 SSE 1.345E-05 2.989K 06 9.771E-BT 5. 157K-07 3.286K-07 1.491E 07 5.292E-GS 2.437K-GS 1.426E-08 9. 4 13 E-09

k I 0 Table A-9 M W tD I N m Depleted, 8.0 Day Decay, X/Q Values for Long-Term Ground Level Releases at Standard Distances (Sec/ms) VI tt 0 USNRC COMPUTER CODE - XOQDOQ, VERSION 2.6 RUN DATE: 66/23/94 RUN TIHE: OS:46:27 (D XOQDOQ - SHNPP CROUNO-LEVEL HISTORICAL DATA, 1976-1987 0 l5 tO EXIT ONE ->> GROUND-LKVEL HISTORICAL DATA, 1976-1987 0 lf 8.068 OAY DECAY, DEPLETED O lO CORRECTED USING STANDARD OPEN TERRAIH FACTORS SECTOR I ANNUAL AVERAGE CHZ/q (SEC/HETER CUBED) e.a5e e.50e e.756 1.eoe OISTAHCE 1.566 IN HILKS 2.66G FROH THE 2.566 SITK 3.6GG 3.506 4.886 4.590 rr 0 g g 0 rt 8 1.625E-84 4.665E-65 2.247E-B5 1.685K-05 4. 169E>>66 2.368E-66 1.482K-B6 1.642E-06 7.784E-67 6.0SGE-67 4.99SE-BT 0 SSW 1.485E-64 4.295E-65 2.683E-65 1.609E-05 3.S77E-86 2. 139E-G6 1.369E-66 9.666E-67 7. 168E-67 5.599E-B7 4.507E-B7 S'M 1:4eeE-e4 4.G19E-65 1.937E-65 9.357E-66 3.594E-66 1.991K-66 1.278K-66 S.984E-67 6. 715E-67 5.244E-07 4.233E-87 0 MSM 1.224E-64 3.499E-65 1.681E-85 8.107K-B6 3.113K-66 1.728E-66 1.111E-66 7.818E<<87 5.849E-67 4.572E-67 3.693E-e7 0 'M 9.360E-65 2.666E-65 1.279K-85 6.173K-66 2.372E"66 1.316E-66 8.458E-87 5.952E-G7 4.452E-67 3.479E-67 R.816K-OT n WNW 7.623E-65 2.e18f-e5 9.753E-e6 4.721E-66 1.816E-66 1.665K-G6 6.444K-67 4.527K-67 3.382E-BT 2.646E-OT 2. 136E-07 g~ NW 6.273E"65 1.819K-65 B.BT6E-86 4.329K-B6 1.672E-66 9.262E-67 5.878E-G7 4.117K-67 3.668E-67 2.390E-67 1.925E-67 NNW 6.787K-85 '1.991K-65 9.871E-66 4.857E-66 1.886K"66 1.636E-66 6.548E-87 4.567E-67 3. 391E-07 2.635E-67 2. 117E<<67 m N S.721E-65 2.574E-e5 1.287K-65 6.346K-66 2.465E-66 1.342E-66 8.585E-67 5.926E-87 4.389E-67 3.464E-67 2.732E-OT O rt NNE 9. 311E-85 2.765K-B5 1.387E-05 6.844f-66 2.657E-06 1.'442K-66 9. 123E-67 6.339E-07 4.694E-67 3.637E-OT 2.916E-OT Nf 7.462E-65 2.215E-65 1. 182E" 65 5.463K-86 2 '84K-66 1. 131E-86 7. 156E-67 4.974E-07 3.683E-OT 2.855E-B7 2.289E-B7 ENE 5. 671E-65 1.6SRE-B5 8.343K-66 4.681E-66 1.571E-G6 8.519E-67 5.3S5E-67 3.741E-67 2.776E"07 2.146E-67 1.721E-67 E 4.635E-B5 1.365K-05 6.739E 06 3.295E 86 1.271K-06 6 933E-67 ~ 4.481K-67 3.667K-87 2.276E-OT 1.767E-B7 1.419E-67 ESE 4. 214 E-65 1.246E-65 6. 105E-66 2.986K-66 1.147E-66 6.256K-67 3.971K-BT 2.767E-67 2.054E-B7 1.595E-87 1.281K-07 SE 5.85SE 65 1.487K-65 7.335E-66 3.576K-66 1.376E-G6 7.495K-87 4.755E-G7 3.312E-67 2.457E-07 1.968E-67 1.532E-87 SSE 8.683E-05 2.491E-65 1.289K>>65 5.855K-66 2.249E-66 1.238K-66 7.917E" 67 5.547E-87 4 ~ 136E-67 3.223K-87 2.597E-67 ANNUAL AVERAGE CHZ/Q (SEC/HETER CUBED) DISTANCE IN HILES FROH THE SITE SECTOR 5.686 7.580 16.666 15.eee ae.eee a5.eoe 3e;eee 35.eee 4e.eee 45.eee 5e.eoe S 4.664K-87 R.esef-e7 1.325E"87 7.286E-OS 4.760E-OS 3.317E-OS 2.477E-OB 1 '24E-OS 1.538E-OB 1.257K-OB 1.845E-OS SSM 3.729K-67 1.901K-67 1.268E-67 6.616E-68 4.263E-OB 3.664E-OS 2.246E-GB 1.73SE-OB 1.388E-OS 1. 134E-68 9.424E-69 SW 3.5e6E-e7 1,794E-67 1. 143E-G7 6.274K-BS 4.649E-BB R.S56E-OB 2. 131E-88 1.654E-BB 1.322E-BB 1.079E-OB 8.973E-09 MSM 3.e6eE-e7 1.569E-67 1. 66 1 f-67 5.562E-OB 3.554E-GB 2.508E-OB 1.S72E-OS 1.453E-OB 1. 161E-68 9.487E-69 7.887E-e9 'M 2.328K-67 1. 193E-67 7.609K-OB 4. 182K-68 2.7G1E-OS 1.966E-OS 1.422E-68 1. 164E-68 8.823E-69 7.267E-89 5.991E-69 WNW 1.764K-67 9.614E-GS 5.738E-OB 3. 147E-68 2.030E-OS 1.431E-BB 1.86BE-OB 8.289E-69 6.622E-09 5.469E-69 4.496E-09 NW 1.591K" 67 S.es6f-es 5. 129E-68 2.881E"OS 1.803E-OS 1.269E-eS 9.462E-G9 7.339E-89 5. 861E-09 4.787E-69 3.979E-69 NNW 1. 746E-67 8.80SE-OB 5.560E-OB 3.619E-OS 1.936E-OS 1.366E-OS 1.613K-BB 7.848E-G9 6.264E-69 5.115E"69 4.251K-69 N 2.251K-OT 1. 132E-67 7. 127E-68 3.859E-OB 2.471E-OS 1.735E-BS 1.291E-OB 1.600E-BB 7.981E-69 6.516E-09 5.417E-O9 NNE 2.461E-67 1.204K-67 7.567E-OS 4.089E-OS 2.616E-OS 1.835E-OB 1.365E-OB 1.657E-OB 8.437E-69 6.888E"69 5.726E-69 NE 1:885K-67 9.461E-OB 5.954E-OS 3.222E-OB R.G63E-OS 1.449E-OS 1.678E-GS 8.353K-69 6.66SE-09 5.445E-69 4.527E-09 ENE 1.417E-67 7. 169E-68 4.473E"68 2.421E-OB 1.551E-OB 1.889E-OB 8.189E-B9 6.285E-69 5.018E-69 4 '99E-69 3.409K-69 E 1. 171E-67 5.962E-OS 3.724E-OS 2.623K-OB 1.29SE-GS 9.120E-69 6.791E-69 5.264E-09 4.263K-G9 3.432E-09 2.853E-69 ESE 1.656K-67 5.327E-OB 3.363K-OB 1.827E-OB 1. 173E-OB 8.246K-.69 6. 143E-09 4.763E-69 3.803E-O9 3. 197E-69 2.5S3E-69 SE 1.263K-67 6 '69E-08 4.626E-GB 2. 184E-OS 1.462K-OB 9.856E-69 7.343E-69 5.694E-69 4.5'47E-09 3.714E-69 3.0S9K-69 SSE 2. 148 E-67 1.694K-67 6.946E-GB 3.801K-OB 2.449E-OS 1.726E-OB 1.2SSE-GS .9.994E-69 7.985E-G9 6.524E-69 5.425E-09 VENT AND BUILDING PARAHETERS: RELEASE HEIGHT (HETERS) O.oe REP. WIND HEIGHT (HETERS) 16.6 DIAHETKR (HKTKRS) O.ee BUILDING HEIGHT (HETERS) 55.0 EXIT VELOCITY (HETERS) e.ee Bl OG.HIN.CRS.SEC.AREA (SQ.HETERS) 2161.0 HEAT EHZSSION RATE (CAL/SEC) 0.6 ALL GROUND LEVEL RELEASES. Table A-10 Depleted, 8.0 Day Decay, I/Q Values for Long-Term Ground .Level Releases at Standard Distances (Sec/m ) USNRC COHPUTER CODE - XOQOOQ, VERSION 2.0 RUH DATE: 06/23/94 RUN TIHE: 08:46:27 XOQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 EXIl'NE -" CROUKD-LEVEL HISTORICAL DATA, 1976-1987 s.eee o~v oEOAv, oERLETEo I CHI/Q (SEC/HETER CUBED) FOR EACH SECH ENT SECHENT SOVNDARIES IH HILES FRDH THE SITE DIRECTION .5-1 1-2 2-3 3"4 4 5 5" 10 10-20 2G 30 30-40 FROH SITE S 2.26SE-05 1.526E-06 7.887E-07 4. 943 E-07 2. 186 E-07 7.461E-OS 3 . 350E-OS 1.935E-OS 1.262E-OS ssH 2.097E-05 1.411E-06 7.263E-07 4.540E-07 1.999E" G7 6.785E-OS 3 .034E-OS 1;74SE-Os 1. 138E-08 SM 1.955E-05 1.316E-06 6.803E"07 4.264E-G7 1. 885E-'07 6.43eE-es 2.8S4E-OS 1.664E-OS 1. Gs4E-os MSH 1.69SE-e5 1. 144E-06 5.925E"07 3.719E-07 1.648E"07 5,637E-OS 2 .532E-08 1.462E-08 9.524E-09 M 1.292E-05 S.v1eE-ev 4.518E-07 2.830E-07 1.253E-07 4.285E-OS 1.924E-GS 1. 111E-08 7.236E-09 MNH 9.S35E-06 6.638E-87 3'.426E-ev 2. 145E-07 9.474E-08 3.226E-es 1.446E-08 8.338E-G9 5.430E-69 W 8.924E-06 6.060E-B7 3. 109E-07 1.939E-07 s'.51eE-es 2.sv5E-es 1.282E-GS 7.383E-09 4.806E-09 NNH 9. S74E-06 6.757E"87 3.439E-07 2. 133 E-07 9.287E"08 3 . 102 E-08 1.375E-08 7.896E-69 5. 136E-09 N 1.283E-05 8.782E-07 4.451E-07 2.753E" 07 1 . 394E-Bv 3.969E-08 1.75'4E-08 1.006E-88 6.543E-09 NNE 1;381E-05 9.423E-07 4.761E-07 2.939E-G7 1.271E-07 4.207E-BS 1.855E-08 1.064E-es 6.917E-69 NE 1. 100E-05 7.392E-07 3.736E-07 2.3evE-ev 9.990E"08 3.314E-08 1.464E-es 8.4G4E-G9 5.467E-09 ENE 8.332E-e6 5.563E"07 2.81eE-ev 1.734E-07 7.5e6E-es 2. 491E-08 1. 101E-08 6.323E-09 4. 115E-G9 E 6.744E-06 4.542E-07 2.308E-07 1.430E-07 6.224E-es 2.'ev9E-es 9.217E-09 5.296E-09 3 '46E-09 ESE 6. 115E-06 4.099E-07 2.GS3E-07 1. 291E-07 5. 618E-08 1.87SE-es 8.333E-09 4.791E-09 3. 119E-09 SE 7.340E-06 4.98SE-07 2.492E-07 1.544E-07 6.v1vE-es 2.244E-es 9.960E-09 5.72SE-09 3.730E-09 SSE 1.217E-85 8. 168E-07 4. 191E" 07 2.616E-07 1. 151E" G7 3.899E-GS 1.743E-es 1.ee5E-GS 6.550E-89 < v C ~, TABLE A-11 0 M Deposition Values (D/Q) For Long Term Releases At Standard Distances l kf) N I 0') P) (m ) rt 0 O USNRC COHPUTER CODE XOQDOQ, VERSION 2.0 RUN DATE: 06/23/94 RUN TINE: 08:46:27 ax 0 0) XOQDOQ - SHNPP GROUND LEVEL HISTORICAL DATA, 1976 1987 Ir Ol EXIT ONE GROUND-LEVEL HISTORICAL DATA, nm ~ 1976-1987 CORRECTEO USING STANDARD OPEN TERRAIN FACTORS RELATIVE DEPOSITION PER UHIT AREA (H++-2) AT FIXED POINTS BY DOWWIHD SECTORS DIRECTION DISTANCES IN HILES VV FROH SITE 0.25 0.50 0.75 l.ee 0 2.324E 07 7.857E-GB 4.034E GS 1.5e 2.0G 2.50 3.00 3.50 4.ee 4.5e tt r ttQ S 1.91SE-OS 6.889E-09 3.417E-09 2.012E-09 1.317E-09 9.269E-10 6.869E-10 5 '94E-10 SS'K 2.171E-07 7.343E-OS 3.770E-OB 1.792E-GB 6.43SE-09 3.193E-09 1.BSGE-09 1.231E-G9 8.662E-10 6.420E-10 0 1.74GE-07 4.947E-10 SM 5.885E"08 3.022E-GS 1.437E-GB 5. 160E-09 2.559E-09 1..507E-09 9.866E-10 6.942E-10 5. 145E-10 3.965E-10 0 HSH 1.355E-07 4.5S2E-OB 2.353E-GS 1.119E-OB 4.01BE-09 1.993E-09 1.173E-09 7.682E-10 5.406E-10 4.006E-10 3.087E-10 X C 'M 1.013E-07 3.427E"OS 1.759E-OS 8.365E-B9 3.005E-09 1 ~ 490E-09 8.774E-10 5.745E-10 4.042E-10 0 2.996E-10 2.309E-10 WKM S.296E-GB 2.805E"OS 1.440E-GS 6.84SE-09 2.460E-B9 1.220E-09 7. 183E-10 4.703E-10 3.309E-10 2.453E-1G 1. 890E" 10 KN 8.46SE-OS 2.864E-GS 1.470E-OB 6.996E-09 2.511E-09 1.245E-09 7.332E-le 4.801E-10 3.37SE-10 2.5G3E-1G 1 929E-10 NNN 1.105E-07 3.736E-GB 1.91SE-GS 9.120E-09 3.276E-09 1.625E-09 9.566E-1G 6.264E" 1G 4.40SE-18 ~ 3.266E-le 2 517E-10 VV ~ N 1.626E-07 5.499E-GB 2.823E-GB 1.342E-OS 4.821E-09 2.391E-09 1.4BBE-09 9.21SE-10 6.487E-10 4. 807E-18 3.705E-10 NNE 1.985E"07 6.713E OS 3.447E-GS 1.639E-GS 5.886E-89 2.919E"'G9 1.719E 09 1.125E-89 7.919E-10 5.869E-10 4.522E"10 O rt ENE NE 1.815E-07 1.56SE"07 6.137E-GB 3.151E-OS 5.302E-GB 2.723E-GS 1.49SE-OS 1.294E-GB 5.381E"G9 4.649E-09 2.669E-09 1.571E-09 1.029E-09 2.306E-09 1.35SE-09 8.890E-10 7.240E-10 5.366E-10 4. 135E-10 nm W M '.595E-OS 6.255E-10 4.636E-le 3. 572E-10 E 3.245E"OB 1 ~ 666E-eB 7.920E-09 2.S45E-09 1.411E-09 8.307E-10 5.439E-10 3.827E-10 2.837E-10 2. 186E-10 ESE 1.003E-07 3.393E-OS 1.742E-OS S.281E-09 2.975E-09 1.475E-09 8.6S6E"1G 5.6BSE"10 4.002E"10 2.966E-lG 2. 286E-10 SE 1.27GE-07 4.294E-OB 2.2G5E-OS 1.04BE-OB 3.765E"09 1.867E-09 1.099E-09 7.199E-18 5.066E-10 3.754E-18 2.893E-le SSE 1.54BE-87 5.236E-OB 2.6BBE-OS 1.27BE-OS 4.591E-09 2.277E-09 1.341E-09 8.77SE-10 6. 177E-10 4.57BE-10 3 . 52BE-10 DIRECTION DISTANCES IN HILES FROH SITE 5.ee 7.50 le.ee 15.ee ae.ee 25.ee ,30.00 35.ee 4e.ee 45.ee 5e.ee S 4. 265E-10 1.86BE-le 1 . 132E-18 5.720E-11 3. 462E-11 2.321E-11 1.663E-11 1.249E-11 9.711E-12 7.757E-12 6. 332E-12 SSH 3 . 930 E-10 1.746E-10 1. 05BE-10 5.346E"11 3.235E-11 2.169E" 11 1.554E-11 1.167E-11 9.075E-12 7.249E-12 5. 917E- l2 SM 3. 150E" 10 1. 399E-10 8 '76E-11 4.284E-11 2.593E-11 1.739E-11 1.246E" 11 9.354E-12 7.273E-12.5.810E 12 4. 742E-12 HSM 2.453E-10 1. 090E-10 6.6GOE-11 3.336E-11 2. 019E-11 1.354E-11 9.700E-12 7.2S4E-12 5.663E-12 4,524E"12 3. 692E-12 H 1.834E-10 B. 14SE-11 4.935E-ll 2.495E-11 1.510E" 11 1.012E-11 7.254E-12 5.447E-12 4.235E-12 3.383E-12 2. 761E-12 NNM 1. 501E-10 6.670E-1 1 4.040E-11 2.042E-11 1.236E" 11 8.287E-12 5.93SE-12 4.459E-12 3.467E-12 2.769E-12 2. 261E-12 NM 1.533E-10 6.BOSE-11 4. 124E-11 2.0S5E-11 1.262E-11 8.459E-12 6.062E-12 4.552E-12 3.539E-12 2.827E 12 2. 307E-12 NNM 2.0GOE-10 8.884E-11 5. 38 1E-11 2.720E-11 1. 646E-11 1. 104E-11 7. 909E-12 5. 939E-12 4.61SE-12 3.689E-12 3.011E-12 M 2. 943E-10 1.307E" 10 7.920E-11 4.003E-11 2.423E-11 1.624E-11 1.164E-11 8.740E-12 6.796E-12 5.42BE-12 4.431E-12 NKE 3. 593E-10 1.596E-10 9.66SE-11 4. 887E-11 2.95BE-11 1.983E-11 1.421E-11 1.067E-11 8.296E-12 6.627E-12 5. 409E-12 HE 3.2S5E-10 1.459E-10 8.839E-ll 4.46SE-11 2.704E-11 1.813E-11 1.299E-11 9.755E-12 7.585E-12 6.059E-12 4. 946E-12 ENE a.'83BE-le 1.261E-10 7.637E-11 3.860E-11 2.336E-11 1.566E-11 1.122E-11 8.42BE-12 6.553E-12 5.235E-12 4.273E-12 E 1.737E-10 7.714E-11 4.673E-1 1 2.362E"11 1 430E-11 ~ 9.585E-12 6.86SE-12 5.157E-12 4.010E-12 3.203E-12 2. 614E-12 ESE 1. 816E-10 8.066E-11 4.886E-11 2.470E-11 1.495E-11 1.002E"11 7.181E-12 5.393E-12 4.193E-12 3.349E-12 2. 734E-12 SE 2. 29SE-10 1.021E-10 6 185E-11 3. 126E-11 ~ 1.892E 11 1.269E-11 9.090E-12 6.826E-12 5.307E-12 4.240E-12 3. 46OE- la SSE 2.802E 10 1.245E-10 7. 541E-11 3. 812E-11 2.307E-11 1.547E-11 1.10BE-ll 8.323E-12 6.471E-12 5. 169E-12 4.219E- l2 Jl TABLE A-12 0 tn W S Deposition Values (D/Q) For Long Term Releases At Standard Distances (m ) Ol k rt 0 lD USNRC COHPUTER CODE - XOQDOQ, VERSION 2.0 RUN DATE: 06/23/94 RUN TIHE: GS:46:27 0 lh O XOQDOQ "- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976" 1987 oP rn EXIT QNE -- GROUND-LEVEL HISTORICAL DATA, 1976-19S7 V4 o c 1%%$ 101111%1%11%11%1%1%% RELATIVE DKPOSZTION PER UNIT AREA (H11-2) BY OOMNIIIND SECTORS 111111111111111111111111 g 0 SEGHENT BOUNDARIES IN HILES 0 DIRECTION .5-1 2-3 3-4 4-5 5-10 18-2G 20-30 3e-ue 40"50 rr p FROH SITK 0 S 3.943E-BS 8.077E-09 2. 109E-09 9.470K"10 5. 357E-10 2. e6e E- le 5.96ef-l 1 2.362K-ll 1.261K- 1 1 7.BOSK-12 0 SSH 3.6S5E"08 7.54SE-09 1. 971E-09 8.85ef-le 5.0GTE-10 1. 925K-10 5 '70E-11 2.20SE-11 1. 179K-11 7.297K-12 SW wsw 2.953E-GS 2.'3eeE-es 6.050E"89 4.710K-09 1.579K-09 1.230E-09 7.093K-le

5. 523K-10
4. 013E-10 3.'124 E-le
1. 543 E-10 1.201E-18 4.464E-11 3 '76E-11 1.769E-11 1.37SE-11 9.44SE-12
7. 357E-12 5.84SE-12 4.554E-12 I5 I ll 1.720E-GB 3.523E"09 9. 196E-10 4. 130K-10 2.337E-10 8.985E-11 2.599E-11 1.03GE-11 5. 502E-12 3.405K"12

'MNM 1.408'E-08 2.884K-09 7. 52 8E-10 3. 381K-10 1.913E-10 7.356E-11 2. 12SE-11 8. 434E" 12 4.504E-12 2.78SE-12 VV NH 1.437K-ee 2.944K-09 7. 685E-1G 3.451E" 10 1. 952K-10 7.50SE-11 2. 172E-11 8.609E-12 4.597E-12 2.S46E-12 MNN 1.875K-BS 3. 841K-09 1 ~ 003E-09 4.503E-10 2.5uSE"le 9.797E-11 2.834E-11 1. 123K-1 1 5.99SE-12 3.713E-12 O rr N 2.760K"08 5.652E-09 1.476E-B9 6.627E-10 3.749E-10 1.442K-le 4. 171E-11 1.653K-l 1 8.82SE-12 5. 464K-12 er NNE 3.369K-GS 6.981K-09 1.801E-09 8. 091E-1G 4.577E"18 1.760E-10 5.892E-11 2.01SE 11 1.07SE-11 6. 671K- 12 O~ NE 3.esef-es 6.309E"09 1.647E-89 7.397K"18 4. 185E-10 1.6e9f-le 4 '55E-11 1. 845E-11 9. 853E-12 6. 099E-12 ENE 2.661K-ee 5. 451K-09 1.423E-09 6. 391E-10 3.615E-1G 1.39GE-10 4.022E-ll 1.594E-11 8. 513E-12 5.269K-12 E 1.62SE"GS 3.335K-09 8.787E-18 3.911E-10 2.212E-10 8.507K-11 2.461E-11 9.754E-12 5.209E-12 3.224E-12 ESE 1.703E-BB 3.487E-09 9. 104E-10 4. 0S9E-10 2.313E-10 8. 895K-11 2.573E-11 1.020E-11 5.447E-12 3 371K-12 ~ SE 2. 155E-GS 4.414E"89 1. 152E-09 5. 176E-10 2. 92SE" 10 1. 126E" 10 3.257E-ll 1. 291E-1 1 6.894E-12 4.267K-12 SSE 2.62SE-GS 5 '83K-89 1. 405E-09 6.311K 10 3.570E-10 1. 373 K-10 3. 972E-11 1. 574 E-1 1 8.406E 12 5.203E-12 VENT AND BUILDING PARAHETERS: RELEASE HEIGHT (HETERS) 0.00 REP. IIZND HEIGHT HETERS) 10.0 DIAHETER (HETERS) B.ee BUILDING HEICHT HETERS) 55.0 EXIT VELOCITY (HETERS) 8.00 BLDG.HIN.CRS.SEC,AREA SQ.HETERS) 2161.0 HEAT EHZSSION RATE CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES. t) TABLE A-13 O Ph co P'l (O Joint Rind Frequency Distribution By Pasquill Stability Classes At SHNPP 1 ct K 0 0 Period of Record: 1/1/76 - 12/31/82 . t$ X 0 Lower Monitoring Level N l0 USNRC COHPUTER CODE - XOQDOQ, VERSZOH 2.0 RUN DATE: 06/23/94 RUH TINE: BS:46:27 O PIe Ol XOQDOQ SHKPP GROUND-LEVEL HISTORICAL DATA, 1976 1967 k q o o I p 0 VP 0 JOINl'REQUEKCY DISTRIBUTION OF MIND SPEED AND DIRECTION ATHOSPHERIC STABILITY CLASS A ft $ 0 UHAX (H/S) N NKE NE ENE E ESE SE SSE S SSM SM MSM M MKM NM NNM TOTAL 0.34 e.eeo B.BBB e.eoo B.eoe B.eeo O.eee e.eee e.oee e.eoo e.eoe O.eoo e.eeo D.eoo e.oee B.eoe B.eoo O.BG1 1.56 0.014 e.'oe9 0.'e16 0.012 e.cia e.ee9 0.021 e.'Bos B.eae e.'e16 e.'oao B.eis 0.015 0.010 0.011 8.609 0.219 3.35 e.u25 0 ~ 354 0.3G7 8.219 0.162 0. 123 0. 116 0.177 8.357 0.329 0:33S 0.416 G. 163 0. 165 0.317 8.334 4.303 5.59 e.'3e7 0. 296 0. 173 e.'e6e 0.017 0.029 e.eae 8.021 B.BS3 8.257 0.361 8.'450 0.145 0.234 0.367 0.356 3.176 6.27 e'.ees e.eoe e.eoa e.ooe e.eee e.'eei o.eee e.eel 0'.e05 e'.0>> e.e57 e.esu 0.033 0. 071 0.059 e.'Duu 0.374

11. 16

>>.62 TOTAL B.BSB 8.088 e.'eeo 0.75 e.'eee e.'66 8.800 e.'eoe e.'5e 0.000 e.eee 0.29 0.080 e.eee

0. 19 B.eeo e'.eee
0. 16 0.'eoo e.eoo 0.16 e'.eoe e.'eee e.al e'.eee e.eee 0.47 e'.eei e.eoe 0.61 e'.eee e.eee 0.7S e'.eeu e'.eeo 0.97 e'.eeu e.eeo 0.36 0'.eos 0'.860 0.49 e.eoo B.eoe 0.75 e.eei 0.600 0.74 e.els B.OOO 6.09 vr O rt JOINT FREQUENCY DISTRIBUTION OF MZKD SPEED AHD DIRECTION ATHOSPHERZC STABILITY CLASS B UHAX (H/S) N NKE HE ENE E ESE SE SSE S SSM .SM MSM M MHM NM HKM TOTAL 0.34 e.eee e.eee G.OGO e,ooe e.eoe e.oeo 0.806 e.oee 8.060 0.688 e.oeo 8.808 e.eoe B.eoo B.eee e.oee e.eoo 1.56 e'.eiu e.ei5 0.023 0.022 0.017 e.eal e.ei7 0.016 0.022 0.020 8.032 0.821 e.025 0.013 e.ois 8.017 G. 314 3.35 8.38S 8.269 0.264 8, 161 8. 151 0. 121 0.067 0. 133 0.234 0.262 8.323 0.314 0. 1>> 0. 142 0.221 0.217 3.29S 5.59 0.189 O.GS7 0.061 0.022 0.021 e.eos e.eae e.'eaa 0.847 0.099 e.i6e 0. 196 e.iea 0. 151 0.216 0. 15S 1.47S 6.27 e'.ee6 e.eee e'.eei e.eeo e'.eee e'.eee e'.eoe e.oel e.eeu e.ee5 0.031 G.826 0.032 0.053 e.eas 0.019 0.285
11. 16 e.'eee e.'oee 0.'eeo e.'eee e.ooe e.ooe 0.060 e.'eee 6.060 0.068 8.062 8.082 e.eel 8.803 0'.eel e.esl e.eie
11. 62 e.'eee e.oee e.eee e.ooe e'.eoe e.eeo e'.eoe e.oee e'.eeo e.'eee e'.eBe 0.001 e'.eeo e'.eoe B.eee e.'eoe e.eel TOTAL 0.44 8.37 8.29 8.23 8.19 B. 15 0.12 0.17 0 ~ 31 8.41 8.55 e.56 8.27 8.36 e.us 0.41 5.31 JOINT FREQUENCY DISTRIBUTION OF MIND SPEED AKD DIRECTION ATHOSPHERZC STABILITY CLASS C UHAX (H/S) H NNE NE EHE E ESE SE SSE S SSM S'M MSM M MNM NM HHM TOTAL 0.34 e.eee e.eee e.oee e.ooo B.eoo e.ooB e.eeo e.eee e.eoe e.ooe 0 BOG

~ e.ooo O.OOG e.eoe e.eoe G.OOO G.eoo 1.56 0.031 0.031 0.035 0.G26 B.e23 0.631 G.041 0.037 0'.e50 e'.e57 e'.e69 e'.eu5 8.035 0.029 0.033 e'.e36 0.610 3.35 0. 347 0.2S7 0.245 0. 228 0. 152 0.131 .0.121 0. 156 B.a61 e.332 0.375 0.369 0. 175 B. 192 8.246 8.261 3.674 5.59 0. 139 e.esl e'.e39 e.036 0'.Bes 0'.ee9 '0'.014 e.ea7 0.029 0. 112 0. 16G G. 192 0. 117 G. >>5 0. 199 0. 145 1.423 6.27 B.ee7 e.ooo B.eee e'.eoe e'.060 8.608 8.060 8.081 e.eol e'.eos 0.019 0.023 e.eia e'.055 0.024 8.015 8. 164

11. 16 e.'eee e.'eee 0.'oeo e.eoe e.'Bee 0.'eeo e.'oeo e.eee e.eee e.eeo e.eoa O.G03 O.G02 0.002 G.OOO e.'000 e.e09
11. 62 B.eeo 8.000 O.GGO e.ooo B.eee e'.eoo e.ooo B.eoo e.eeo e'.000 e'.Oee 0.000 0.08G 0.000 O.OGO 0'.Goe e'.eoo TOTAL e.'52 e'.ue e.'32 0.2S 0.1S e.'i7 e.is 0.22 0.34 0.51 e.63 0.63 0.34 8.39 0 50

~ 0.46 6.06 JOINT FREQUENCY DISTRIOUTIOH OF MIND SPEED AND DIRECTION ATHOSPHERIC STABILITY CLASS D UHAX (H/S) H NKE NE ENE E ESE SE SSE S SSM SM MSM MKM HM NNM TOTAL e.34 e.eea 8.002 O.OG2 e.eea e.eel e.eel e.eoi B.OG1 e.eea e.eoa e.oea O.GG1 0.001 0.001 0.001 G.001 0.025 1.56 0.434 e.5e6 e.uuu 0.370 0.329 0.266 0.276 e.'30e 0.362 0.461 0.'465 0. 346 0.267 0.25S 0.269 0.346 5.739 3.35 1.759 2.054 1.350 e.964 e.'624 0.523 0.556 0.742 1.05S 1.346 1.316 1. 177 0.647 0.5S3 G.746 1.025 16.471 5.59 8.556 0.491 8.330 0.114 O.G66 e.076 e.loe e.'i9e 0.220 e.376 e.55e e.u62 0.260 0.402 0.523 e.556 5.271 6.27 e.e55 0.023 e.eeu e.eil e.oou e.eo6 e'.005 0.023 0.032 0.847 0 069 ~ 0.075 0.042 0.092 D.e6a 0.063 0.610 11.16 e.eee e'.00e O.ooe e'.eoe e.eoe e'.eoo e.eol B.eee e.oel 8.001 O.GGS 0.017 e.ooo O.OG4 G.OOO e.ooo G.032

11. 62 e.eee e.'oee e.'eee e.'eee e.'eei e.'eoe e'.eoo e.eee e.oee 0.800 8.000 0.688 0.000 0.680 0.000 0.000 0.001 TOTAL 2.61 3.0S 2.13 1,46 l.e2 B.S7 0.94 1.26 1.66 2.25 2.41 2.0S 1.24 1.34 1.60 1.99 26.15

TABLE A-13 (continued) O CA H) H) O ~ I Ql Q) Joint Rind PrBquency Distribution By Pesquill Stability Classes At SHNPP V' O tb USHRC COHPUTER CODE - XOQDOQ, VERSION 2.6 Ct XOQOOQ SHNPP CROUHO-LEVEL HISTORICAL DATA, 4~+><-P<~> th JOINT FREQUENCY DISTRIBUTION OF ltIND SPKKO ANO DIRECTION ATHOSPHERIC STABILITY CLASS E O Ql UHAX (H/S) I H HHE NE KHK E ESE SE SSE S SS'M SM MSM lt 'ltNM NM NNM TOTAL 0 I 0.34 0.007 0.806 e.oos e.eeu e.ee3 e.eou e.oo6 0.009 8 ~ 089 0.665 8 ~ 00'4 0.083 e.eoz e.oe3 0.863 0 079 I O 1.56 B.G85 8.747 0.962 0.624 0.692 0.51s e.'use 0'.536 e.'Sls 1.244 1. 183 0.723 0.492 0.415 e.'312 e.uos ~ 0.466 le.'616 VV Ctt 3.35 1.026 8.655 8.549 8.329 8.309 0.266 0.356 0.577 1.05S 1.547 1.029 0.744 e.uss 0'.us9 e.66e 0.667 10.92G rt Rt 5.59 0. 124 0.032 e.'e46 0.029 0.019 0.02S 8.032 e.'es0 0. 136 0. 148 0.216 0. 145 e.'06v o'.lel e'.ess 0. 131 1.421 Sszv e.'eev 0.603 e.eee e.eoz 0'.eez e.eeu e.ee6 e.ee6 0.016 e.ele e.els e.e26 e.ele e.003 B.ee3 e.eos 0. 128 0 e'.eee e.'eoe e.eeo G.008 8.880 0.000 8.668 8.060 e'.Boe B.e63 e.esu e'.Doe e.eel e.eoo e.eoe e'.eos K 0C

11. 16 B.G08 11.62 B.oee e.eoe e.eee e.eoe e,eoe e.eee e.oee e.eoe e.eoe 0.'eoe e.'ooe 0.'eoe G.ooe B.eoo e.eoo e'.eoo 0.060 TOTAL 1.91 1.66 1.42 1. 06 8.65 B.vs 0.93 1.49 2.47 2.90 1.99 1.41 0.96 B.SS 1.16 1.2S 23.36 Ot JOINT FREQUENCY DISTRIBUTION OF MIND SPEED AHD DIRECTION ATHOSPHERIC STABILITY CLASS F g

V~ I UHAX tH/S) H NHE NE Ett E E ESE SE SSE S SSM SM MSM M MNM NM HHM TOTAL O rt e.34 e.e1a e.ela 0.017 8.814 8.011 8.889 e.ell 0.815 e.els 0. 019 8. 812 e.ee9 B.ees e.eev e.oev 0.011 e.ze3 O~ 1.56 8.777 G.vss 0.735 8. 621 e.see 0.414 0.4s9 0.667 B.s03 0.657 0.553 0.395 0.341 0.291 0.321 8.467 9.017 + 3.35 5.59 S. 27 11.16 0.349 e,'oe3 e'.oee e.'eee

0. 159 0.001 e'.eoo 8.060 e.evz e.eoe e'.ooe 0.'eoe
0. 071
0. 081 e.eee G.oee e'.es6 e.'eee e'.eee e.eee 0.033 e.eoe 8.000 e.eee 0.843 0.008 e.oee e.'ooe e.'eu6 e'.060 e.'ooe e'.eoe
0. 12S 0.000 e.'eee e.eee
0. 192 e'.eel e.'ceo e'.eee
0. 176 e'.ee6 e.'eel e'.eee
0. 144 e.601 e.'eee e.eee G.09S e.ooo e.'eee e.eoe e.'1e6 e.ooo e.'Goe e.'oee e.e96 e.eoo e.eoo e.eeo
0. 154 0.062 e.'eoe e.'eoe 1.925 B.G15 e.'eel e.eee ICO
11. 62 0.'oee e.oee e.eoe e.eee e.'eee e.eee e.'eoo e.'eoe e.'eee e'.eee e'.eee e'.eee 8.880 8.008 B.GBB e.eoe 8.868 TOTAL 1. 15 0.97 8.62 0.71 e'.sv e'.46 e'.su 0.73 8.95 1.87 8.75 e.'ss e.us e.ue e.'43 0.63 11.16 JOINT FREQUENCY DISTRIBUTION OF MIND SPEED AHD DIRECTION ATHOSP HERIC STABILZ1'Y CLASS O I

UHAX tM/S) N NNE NE ENE E ESE SE SSE S 'SM SM MS'M 'M MNM NM NNM TOTAL 8.34 8.368 0.317 0.316 0.264 0.214 0. 154 0. 121 0. 1GS 0. 12S 0. 12S G. 112 G.OS5 0.077 0.071 0.065 0.176 2.737 1.56 1.932 1.699 1.692 1.522 1.146 0.623 0.649 e.'Sae e.664 e.sas e'.6ee 0.45T 8.414 8.361 8.455 8.945 14.666 3.35 e'.162 e.e32 e.ezu 0.'ezl e'.e09 e.elz 0.012 0.0G7 e.eev e.ees 0'.ez6 0.023 e.'elu 0. G15 0. 021 e.'euv 0.439 5.59 e.eoe 0.808 8.060 0.008 8.008 0.000 e.ese 0.068 e.eoe e.eee e'.e01 0'.eee e'.eoe B.G00 G.eel e'.eel e'.e03 S.zv e.eee e.eoe e.'eeo e.'eoe e.'eoe B.eee e.eoe G.00G e.eeo e.'eee e.eee B.eeo e.'eoo e.eoo B.eoo 0.860 0.000 11.16 e'.oee G.OG6 0.800 e.eoo 0'.eee 0.080 e.eoe e'.Goe B.ooo e'.eee e'.oee 0.000 0.000 0.0GB 0 000 0.000 G.GGG 11.62 e.eoe B.eoe e.eoe e.eoo 0'.eoe 0.000 8.000 8.800 B.eoe e'.eeo 0'.eoe e.eee e.ooe e.ooe =B.ooo e.oeo 0.000 TOTAL 2.45 2.05 2.03 1.63 1.37 0.99 8.76 0.70 e.sz 0'.Sz e'.vu 0.57 0.51 e.uv e'.s6 1. 17 17.85 TOTAL HOURS CONSIDERED ARE +++I+ TABLE A-13 (continued) . 0 H) 0 Ut tt) O Ql Joint Wind frequency Distribution By Pasquill Stability Classes At SHNPP V'h ft 0 O Period of Record: 1/1/76 - 12/31/82 0 I>> Lower Monitoring Level IA IY O Vl V4 0 g I 0 O ft 0 0 X Rl 0 C OVERALL WINO DIAECT IOH FAFOUENCY WINO DIRECT IUNt N NNE. HE ENE E f Sf. Sf. SSE 5 SSW Sw wSw W WNW HW NNW IOTA!. VI FAEOUENCVt 10 0 9 4 7 5 5 9 4 4 3 6 3 7 4 8 ~ 7 0 8.6 7.8 6.8 4. I 4.3 5.5 6. 7 100.0 O rt OVERALL WIND SPEED FREOUFHCY MAx WIND sPEED TM/s):-'.335 1.565 3.353 5.588 8.270 11. 176 11.623 Q~

vf. wlND SPEFD (MIS)t 0.168 0 950 2.459 4.470 6.919 F 9.723 11.400 WINO SPEED FAEQUEHCYt 3.05 41.38 4 1.23 11.79 1.48 0.08 0.00

'IIIE COHVEASION FACTOR APPLIEO TO THE WINO SPEED CLASSES IS 0.447 8 l. 1. 1. 1. 'I. I I. 1 I, 1. I. I. l. I.i I. I. 9 1.000 1.000 1.000 1.000 1.000 1,000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 I. 000 IO 2189. 2140. 1140. 2140. 1140. 1140. 2018. '2028. 1124. 2'140. 2140. '2140. 2140. 2140. 2140. 1'I 40. II 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0~ 0. D. DISTANCES AND TERRAIN HEIOHTS IH METERS AS FUHCT IONS OF DIRECTION FROll THf. SITE DIAEC'IIOH > S SSw Sw WSw w WNw Nw NHw N HHF. HE i EHF. E ESE SE SSE OI STAHCE 2189. 21 ~ 0. 2140. 2140. 2140. 2140. 2028. 2028. 2124. 2140. 2140. 1140. '2140. 2140. 2140. 1140. ELEVAIIUH 0. 0. 0. 0. 0. 0. 0 ~ 0 ~ 0 ~ 0. 0. 0. 0.. 0. U. U. 12 16 15 13 2 0 11 TABLE A-14 I Shearon Harris Plant Site Input Information for Continuous Groundlevel Release Calculations With the NRC XOQDOI) Program Card lype I Is an array (r0pt) of options, such that I do, 0 bypass. Ihes ~ options rooaln ln effect or all release points run. lhus, all release points wst Law the sane assunp(tons. Card Varlabt ~ Value Used ln X Jm. M I I ropl(t) tlon to dlstrlbute cetus as lhe first utnd-speed c ass (lf coins are already dlstrlbuted by dlrectlon In Card lype C, 10PI(l) ~ 0, and'Card lype 5 ls bien'k). If r0pl(I) ), the cain values of Card lype 6 are dlstrlbuted by dlrectlon ln tbe sane pro-portion as. the dlrectlon frequency of triad-speed class tuo. rOPI(i) Option to Input joint freqwncy dlstrlbutlon data ~ s percent frequency. 3 IIP1(3) Option to coopute a sector spread" for coeparlson ultb centerline valw ln purie calculation (Noraal ly ~ I). rOPI(t) tlon to plot short-tera X/4 va'lues versus prob-a ll(ty of occurrence (Norually ~ 0) ~ 6 rDpI (6) Option to use cubic spline In lieu of least sqwre fwcilon for flttlne Interulttent releas ~ dl s tr lbut ton (Norw I ly ~ I ) . c ropl (c) Option to punch radial seyoent I/4 and 0/4 valves (Nornally ~ I). 1 ropl (7) tlon to punch output of r/4 and D/4 values of I points of Interest (Noraally I). e rOpt(e) Option to correct I/O aed D/4 valws for open terrain roc lrcul all on. rorl(s) Option to correct I/O and D/4 values uslny site speci flc terrain reclrcul ~ t Ion dat ~ . TABLE A-14 (continued) Shearon Harris Plant Site Input Information for Continuous Groundlevel Release Calculations With the NRC XOQDOQ Program Card Ter table I 'Lb I Value Used ln X ~ 1 10 yOP I (10) Optloo to use desert stpaa curves (Nor+ally ~ 0). 0 I .1'I LDtl (11) Optloo to calcul ~ te sexual 2/II avarapes <<1th 30 0 dasrae sectors far oorth, ~ att, south aad <<est ~ a4 20 *Iree sectors fer all ottkrs (NorvLally 0, and the code <<lll usa 22-1/2 dayrae sectors). 2 1-40 'I I I III )Nt 1he +ala title prloted at the hefloolo9 ~f ILe output. 3 1-S NT[L IS 1he ouober of velocity cateiorlas (oaxl~ of It). C- IO NSIA IS 1he ouadkr of slahlllty catatorlel (aaxluuo of 7) ('I alwys equals pasqulll stablllty class N, 2 0, ~ ~ ~ ~ 7 ~ C). 11-1$ NP IS IS 1Le ouober ~ f ~ Istaacas ulth tecrato data for each sector. 1he oLxxbar ~ I 4lstaaces ~tt he ILe saoe for aacL teeter (Carl 1ype 10)(oaxI~ of 10). 3 1 S-20 INC IS 'Ihe lacreueot lo percaal for <<Lich plotta4 results )5 are prlatel wt (Noroally ~ IS). ' 21-2S I NP IPC IS 1Le auabar of titles of receptor types (co<<, Oardao, ~ tc.) (Card Iype I))(aaxloue ~ I eIOLI) 2S ~ )0 NCII1 IS lhe ouotkr ~ f release exit polets (oaxl~ of five). )I-)S NCON Ilk auvtkr of ~ I staac ~ s of alt ~ spectflc correct leo factors fer roc lrculat leo (uaxl ~I 10). I-S ptIT ES.O )tk Le laht ( Io utters ~ above crowd level ) ~ I tlk I 2.0 ~ assured <<Iod pretext ~ 4 Ia the J ~ Iot f~ueecy ~ ata (Card Iype )).. (Eor elevated/}roual-level alud release. usa the 10-aeter level <<lads). TABLE A-14 (continued) O cn H) H) ~ ca Shearon Harris Plant Site Input Information for Continuous Groundlevel'elease th Calculations With the NRC XOQDOQ Program rt 0 tD t7 0 X 0) Ql e n~ War I able ro Card I e ~yL Col~s Nave Lorw l lor eoc'h ls lhe 'half.life (days) vsed ln the I/O Value Used In X rr I 0 e 4-10 DICKS{I) I ~ I, 5 SIS.O r ~ Icvl ~ lions t If OCCAYS o 100, na decay vlII 101. 00 r0rt v te occur; Il OCCAYS <<0, d<<ptcttw lector vill be deflect used I>> the 5/0 ca'Icvlatlonsl tt OICATS ~ 0, 5/0 2.30 will >>ot le colcul ~ ted. (Nor>>ally, O(Cly5{l) ~ 101, X C (I) 2.N, {)) -0.00.) -8.00 8 ? I-ZS tLNO IS.O Pl ~ >>I Ore* ~ Icvallo<< ftCAAO 0.0, DI5l o>>d above sea level), Hl dol ~ Card lyre 10 and Il 0.00 rr g~ ll wst he l<<>>cters. It- PLOAAO <<0.0, blSI In O rt alias and Nl data I>> feel abave plant trode. If ' PLCAAO s ~ .0 abave DISI I<<<<Iles ond III dal ~ ln cn Icet above sea I ~ vel. S- I-3$ CAI H( I ) lf$.4 Ihe>>uuber ol hours, or pcrce>>t, ol cola lor l-l, NSIA each stabl Illy cateyoryt ll LOpI(I) ~ 0, BLANK I>>sert blent card. {Notes I~l Is stohlllty class A~ l0 ~ ~ .. I 0). ~ I-OO tatq(X,I.J) lhe jol>>t fregv'ncy dlslrlbutlaa I>> hours (er N-I, Il ~ ercenl). Ihc values ter IC {N) sectors are I I~ NVIL Ilt- L'DPI{I) read on each card lar each cabal<<otto<< of vl>>d-

0) spccd cl ~ ss {I) and stablllly class (J). Ihe I i, NIIL (It y0pl(I) loop to read these valve cycles first o>> dlrec-

~ I) tlon conllnvl>>O I>> a ctoc'kvlsc tosh!on) ~ II <<>> w J I ~ NSIA wind class and ll>>ally o<<stahlllly cl ~ ss. I-S fS. ~ A correction factor applied to vl>>d-speed classes. Il UCOA <<0: wo correcllons vill be 200. >>ode. If UCON o 100: the vl>>d-speed classes vill bc converted troa <<Iles/hour to eaters/second. I 0 TABLE A-14 (continued) O ca H) 0 lh jx Shearon Harris Plant Site Input Information for Continuous Groundlevel Release V 0 Calculations With the NRC XOQDOQ Program t0 ts 0 xta Ol O r Ql la Card Variable A ~a~ Le~i Oescrl tlon Volvo Used In T '-7$ tax(t) Nane ~ Ttfs.o The wxtnun utnd speed ln each utnd-speed X V 0V 0 class ~ In either nl les/hour or naters/ second. (lf given ln atlas/hour, set 0 75 3 50 7 50 12 50 rrt0 to tjCOa a lO0;) 18.50,25.00,26.00 Card Types 4 and g are read ln for each correction factor and distance given, 1 ~ t,KOtt 1-40 V401ST(X,T) 16f$ .0 The distance ln eaters at uhtch correction All Distances 1.0 6 1,16 factors arq given. These values are read ln VV bagtnnlng utth soulh and proceeding ln a cloctutse dlrecl ion (naxlaua of 10). 0 rt Om 1-40 vxcg(x.l) P 1,16 16fS.O Correction factor to be applied to X/4 and 0/4 valws corresponds to distances speclf led ln VADIS l. All Factors ).000 IM Car4 Types 4 and 4 are repeated for the reualnlng distances and correction factors. Card Types 10 an4 11 are read ln lor each terrain ~ lstance and hetght gtven, 1 ~ l,sm1$ . 10 1-40 DTST(x,t) 16f $ .0 1be distance ln neters at uhtch terrain Distances Site Bounder) li1,16 heights are given. These values are read ln beglnnlng utth south and proceeding ln Distances a cloclutse dlrectlon (naxlnua ol ten distances). The terrain heights (ln neters, above plant 1-40 HT(K 1) y, ~ I,16 16TS.O grade level) corresponding to the distances All Heights 0.0 spectf ted ln lhe D1$ 1 array (Card Type 10). These values are read ln the sane order as the DISI array. for ~ given direct ton and distance, the terrain hetght should bc lhe highest elevation bet~en thr source and that 4lstancc anprtere utthtn the dlrcctlon sector. Card Types 10 and ll are repeated for the renalntng distances and heights. + PD C TABLE A-14 (continued) Q Ch ttl W vi lo Shearon Harris Plant Site Input Information for Continuous Croundlevel'elease v~ rt 0 8 Calculations Vith the NRC XOQDOQ Program 0 ac 0 In VJ 0 W tn Card Ilkk Ckl~< Varlabl ~ Qmsk rs 12 i 1-2$ NPOINT (I ) I I ~ KPITFE SIS . Tha nunber tions for a (oaxl~ of 30) of receptor loca-particular~captor type (such lhe nunber of caus, Sar*as, or alto as 16,15713,2,0,11 rr n I 0 rt I, Io I boundaries). I I 0 I Card Types 13 aad It are read la for eac'h receptor type, thus I I, NFTTFE X s: I-IS I ITLPT(I,J) title tc.) of !he Site Boundary rr '13 1M The {coopt, yardcns ~ ~ 16 receptor type for lhe receptor locatloas (Card Type tt) {~ wxl~ ~ f IS spaces). Nearest Resident 15 Garden 13 0 rt 1-00 XDIX{I II) 1(IS The receptor dlrectlon aad distance. XDIN Milk'a Milk CoM ER Cl PTDIST(I.N) FS.Oj Is the dlrectlon of laterest, such that Qm N-'I KPOINT { I) I South, 2 ~ SSM,..., IS SSE, pTDIST ls Goat 0 the distance, Ia eaters ~ lo lhe receptor Meat T Poultry 11 See Table A-l. Card Types 13 and I< are repealed for the renalnlny receptor types. Card lypcs IS, IS, and IT read la for each pleat release point, thus I I, NEXIT IS 1-80 I TILE{l,d) 20At The till~ for the re'lease polat Vise characlarlstlcs aro described on Card Types IS and ll-1-5 EXIT(1) FS.O 1hc vent avcraie wloclty (actors/second). {Note: If ~ IDOX Sround-level release Is 0 ~ sauced, sei EXIT ~ 0. DIANIN 0, and SLEV ~ 10 enters). S-IO D IAHIN . FS.O Ihc vent Inside dlaactar (actcrs). I I -IS NSIACr(1) FS.O Thc height of the vent release potnt {actors ~ plant Sradc level). If rel ~ ase ls IDOX ~ I ~- 0.0 vated, Input negative of hcI9ht. I& IS-20 IIbLDG(I) FS.D 'Ihc hcl9ht of Ihe vent's bulldlny (eaters ~ ~ bove plant abrade level). 55. 0 TABLE A-1/s (continued) c3 cB I rn ra N Shearon Harris Plant Site Input Information for Continuous Groundlevel Release V Calculations 57ith the NRC XOQDOQ Program I0 ts o a Ol tf ra n~ 0 C C o Card be. C~o~s Variable kana Value Usod In X rt I ta 0 16 21-25 CRSEC(I) fS.O Tha <<tnt~ cross-sectional area for Lhe 216l . 0 0 vent's bulldlnI (sguar~ters). X <<l ja ta 16 26-30 SLEV(l) fS.O The ulnd hel9ht used for Lhe vent ~ levated release (<<ctcrs ~ above planL Srade level). 10. 0 S~I P 16 31-35 ItEAI R( I) f$ .0 Tha vent heat e<<lsslon rat ~ (cal/sec) (Nor<<ally 0). 0.0 O rt 17 RLSIO(1) Al 'A ona letter ldcntlflcatlon for the release Q~ point. h 2-5 IPURGE(l) IPURGE ~ I, 2 or 3 If the vent has later- <<lttaat rclcascs. The I, 2 or 3 corres-ponds Io OECATS(1), OECATS(2), or MCATS(3) (Card Type l), respect tvely, uhlchever Is used as tke bast for Inter<<lt tent release calculations (nor<<ally no decay/no dcpl ale 3/4, such that IPURGE(l) 'I)t lf ~ vent has na Inter<<lt tent rcleascs, IPURGE 0. 17 6-10 KPURGE(l ) 15 . Tke nucber of Inter<<lttcnt releases per year for Lhls release point. 0 17 11-15 KPRGtR(I ) 15 Tha average outer of hours pcr later<<lttent release. 0 Card Types IS, 16 and 17 ara repeated for the rc<<alnlni release points. Card lypcs 1-17 nay bc repeated for the next case. 4 1 Shearon Harris Nuclear Power Plant,(SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 1 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICUIATES, AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for radioiodines, particulates, and tritium to show compliance with Technical Specification 3.11.2.1.b and Appendix I of 10CFR50 for gaseous effluents. These dose parameters, P< and R~, were calculated using the methodology outlined in NUREG 0133 along with Regulatory Guide 1.109, Revision 1. The following sections provide the specific methodology which was utilized in calculating the Pz and Rz values for the various exposure pathways (Tables 3.2-4 and 3.3-1 through 3.3-19, respectively). 2.1 Calculation of P The dose parameter, P~, contained in the radioiodine and particulates portion of Section 3.2 includes only the inhalation pathway transport parameter of the "i" radionuclide, the receptor's usage of the pathway media, and the dosimetry of the exposure. Inhalation rates and the internal dosimetry are functions of the receptor's age; however, under the exposure conditions for Technical Specification 3.11.2.lb, the child is considered to receive the highest, dose. The values for Pi presents the highest dose to any organ including the whole I body resulting from inhalation of radionuclide "i" by a child. The following sections provide in detail the methodology which was used in calculating the Pz values for inclusion into this ODCM. The age group considered is the child because the bases for the Technical Specification 3.11.2.1.b is to restrict the dose to the child's thyroid via inhalation to 8 1500 mrem/yr. The child's breathing rate is taken as 3700 m~/yr from Table E-5 of Regulatory Guide 1.109, Revision 1. The inhalation dose factors for the child, DFAq, are presented in Table E-9 of Regulatory Guide 1.109 in units of mrem/pCi. The total body is considered as an organ in the selection of DFAq, Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 AppENDIX B Sheet 2 of 15 DOSE PARAtKTERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM 2.1 Calculation of P (continued) The evaluation of this pathway consists of estimating the maximum dose to the most critical organ received by a child through inhalation by: P. K'BR) DFAz (B.l-l) iz where: P. iz Dose parameter for radionuclide "i" for the inhalation pathway, mrem/yr per pCi/m3; K'. A constant of unit conversion; 106 pCi/pCi; BR The breathing rate of the children's age group, m3/yr; DFAz The maximum organ inhalation dose factor for the children's age group for radionuclide "i," mrem/pCi. I The incorporation of breathing rate of a child (3700 m3/yr) and the unit conversion factor results in the following equation: Pi z 3.7 E+09 DFAz (B. 1-2) B ~' Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 3 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2 Calculation of R The bases for Technical Specification 3.11.2.3 state that conformance with the guidance in Appendix I should be shown by calculational procedures based on models and data such that the actual exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated. Underestimation of the dose can be avoided by assigning a theoretical individual to the exclusion boundary in the sector with the highest X/Q and D/Q values and employing all of the likely exposure pathways, e.g., inhalation, cow milk, meat; vegetation, and ground plane. Rz values have been P calculated for the adult,.teen, child, and infant age groups for the inhalation, ground plane, cow milk, goat milk, vegetable, and beef ingestion pathways. The methodology which was utilized to calculate these values is presented below. B-3 Shearon Harris Nuclear Power Plant (SHNpp) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. APPENDIX B Sheet 4 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.1 Inhalation Pathwa The dose factor from the inhalation pathway is calculated by: Ri K (BR)a (DFAL)a (B. 2-1) where: K'ose Ri factor for each identified radionuclide "i" of the organ of interest, mrem/yr per 5 pCi/m~; A constant of unit conversion; 106 pCi/pCi; (BR) ~ Breathing rate of the receptor of age group "a," m~/yr; (DFAg) ~ Organ inhalation dose factor for radionuclide "i" for the receptor of age group "a", mrem/pCi. The breathing rates (BR), for the various age groups are tabulated below, as given in Table E-5 of Regulatory Guide 1.109, Revision 1. A e Grou a Breathin Rate m~ r Infant 1400 Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFAz) ~ for the various age groups are given in Tables E-7 through E<<10 of Regulatory Guide 1.109, Revision l. Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 - APPENDIX B DOSE PARAMETERS FOR RADIOIODINES> PARTICULATES, AND h Sheet TRITIUM 5 of 15 B.2.2 Ground Plane Pathwa The ground plane pathway dose factor is calculated by: -A t Ri I K'K"(SF)DFG. (1-e )/A< (B.2-2) where: R. Dose factor for the ground plane pathway for each is identified radionuclide "i" for the organ of interest, -2 mrem/yr per pCi/sec per m K', A constant of unit conversion; 10'Ci/pCi;. A constant of unit conversion; 8760 hr/year; The radiological decay constant for radionuclide "i," sec -l. The exposure time, sec; 4.73 E+08 sec (15 years); DFGg The ground plane dose conversion factor for radionuclide "i," mrem/hr per pCi/m~; A tabulation of DFG~ values is presented in Table E-6 of Regulatory Guide 1.109, Revision l. The shielding factor (dimensionless); (A shielding factor of 0.7 is suggested in Table E-15 of Regulatory Guide 1.109, Revision 1.) Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) . Rev. 4 APPENDIX B Sheet 6 of 15 DOSE PETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.2 Ground Plane Pathwa '(continued) Factor to account for fractional deposition of radionuclide "i." For radionuclides other than iodine, the factor I< is equal to one. For radioiodines, the value of I< may vary. However, a value of 1.0 was used in calculating the R values in Table 3.3-2. (Reference NUREG 0133) B-6. Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 7 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTI@HATES, AND TRITIUM B.2.3 Grass Cow or Goat Milk Pathwa The dose factor for the cow milk or goat milk pathway for each radionuclide for each organ is calculated by: i'E te Biv (1-e "itb) 1'M i F ap m ia g Y + PAi ) + Ei (" (>e -Aitb) -A th ) (BE 2-3) (1-f f ) ) e s E where: R Dose factor for the cow milk or goat milk pathway, for 4 each identified radionuclide "i" for the organ of interest, mrem/yr per pCi/sec per m -2. K' constant of unit conversion; 106 pCi/pCi; The cow's or goat's feed consumption rate, kg/day (wet weight); U ap The receptor's milk consumption rate for age group "a," liters/yr; Yp The agricultural productivity by unit area of pasture feed grass, kg/m~; Ys The agricultural productivity by unit area of stored feed, kg/m~ Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX E Sheet 8 of 15 DOSE PARAMETERS FOR RADIOIODINESl PARTICULATES> AND TRITIUM B.2.3 Grass Cow or Goat Milk Pathwa (continued) The stable element transfer coefficients, pCi/liter per pCi/day; Fraction of deposited activity retained on cow's feed grass; (DFL<)a The organ ingestion dose for radionuclide hih for the receptor in age group "a,h mrem/pCi; AE I Xi+i g The radiological decay constant for radionuclide hi h -1 sec o w The decay constant for removal of activity on leaf and plant surfaces by weathering, sec -1 5.73 E-07 sec (14 day half-life); The transport time from feed to cow, or goat to milk, to receptor, sec; The transport time from pasture, to cow or goat, to milk to receptor, sec; Period of time that sediment is exposed to gaseous effluents, sec; Bi Concentration factor for uptake of radionuclide "i" from the soil by the edible parts of crops, pCi/Kg (wet weight) per pCi/Kg (dry soil); B Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 9 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.3 Grass Cow or Goat Milk Pathwa (continued) Effective surface density for soil, Kg (dry soil)/mz; fP Fraction of the year that the cow or goat is on pasture; Fraction of the cow feed that is pasture grass while the cow is on pasture; (dimensionless). te Period of pasture grass and crop exposure during the growing season, sec; Factor to account for fractional deposition of radionuclide "i." For radionuclides other than iodine, the factor I is equal to one. For i radioiodines, the value of Ii may vary. However, a value of 1.0 was used in calculating the R values in Tables 3.3-8 through 3.3-15. .(Reference NUREG 0133) Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following the development in Regulatory Guide 1.109, Revision 1, the value of f, was considered unity in lieu of site-specific information. The value of fz was 0.667 based upon an 8-month grazing period. Table B-1 contains the appropriate parameter values and their source in Regulatory Guide 1.109, Revision l. 4 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 - APPENDIX B DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND Sheet TRITIUM 10 of 15 B.2.3 Grass Cow or Goat Milk Pathwa (continued) The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the Rq is based on X/Q: K K FeQzU (DFLj)a 0.75(0 5/H) (B.2-4) ap where: Dose factor for the cow or goat milk pathway for tritium for the organ of interest, mrem/yr per pCi/m~; KI I ~ A constant of unit conversion; 10~ gm/kg; H Absolute humidity of the atmosphere, gm/m~; 0.75 The fraction of total feed that is water; 0.5 The ratio of the specific activity of the feed grass water to the atmospheric water. and other parameters and values are given above. A value of H 8 grams/ meter,3 was used in lieu of site-specific information. Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDXX > DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.4 Grass-Cow-Meat Pathwa The integrated concentration in meat follows in a similar manner to the development for the milk pathway; therefore: is z(1e i e iv( e ib) Ri3.B -"XiK X QF Ua ap Ff (DFLi) a ( p ss( + PAi ) + p Ei -Xitb r(1-e Ei t e) iv ) -1 th (s.2-s) ~s XE where: Ri Dose factor for the meat ingestion pathway for radionuclide "i" for any organ of interest, mrem/yr per pCi/sec per m -2. Fg The stable element transfer coefficients, pCi/Kg per pCi/day; U The receptor's meat consumption rate for age group "a," ap kg/yr; ts Transport time from slaughter to consumption, sec; Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 - APPENDIX B DOSE PARAMETERS FOR RADIOIODINES, PARTI CUIATES, AND Sheet 12 TRITIUM of 15 ,B.2.4 Grass-Cow-Meat Pathwa (continued) Transport time from harvest to animal consumption, sec; te Period of pasture grass and crop exposure during the growing season, sec; Factor to account for fractional deposition of radionuclide "i." For radionuclides other than iodine, I~ is equal to one. For radioiodines, the value of Iz may vary. However,. a value of 1.0 was used in calculating the R values in Tables 3.3-5 through 3.3-7. All other terms remain the same as defined in Equation B.2-3. Table B-2 contains the values which were used in calculating Rz for the meat pathway. The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the R~ is based on X/Q. K'KFggpU (DFLg)g Oe75(0 5/H) (B.2-6) ap where: Dose factor for the meat ingestion pathway for tritium for any organ of interest, mrem/yr per pCi/m3. All other terms are defined in Equations B.2-4 and B.2-5. Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 13 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.5 Ue etation Pathwa The integrated concentration in vegetation consumed by man follows the expression developed in the derivation of the milk factor. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption; therefore: -XE te B (1 e -Xitb) iv i ia aL Yv Ei i PX. ) + -Xitb S Uaf@e" -X t ih ( r(1-e Ei e) + iv ) ) (B. 2-7) pk,i Yv XE i where: RiV Dose factor for vegetable pathway for radionuclide "i" for the organ of interest, mrem/yr per pCi/sec per m K' constant of unit conversion; 106pCi/pCi; Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX E Sheet 14 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES AND TRITIUM B.2.5 Ve etation Pathwa (continued) UL The consumption rate of fresh leafy vegetation by the a receptor in age group "a," kg/yr; U' The consumption rate of stored vegetation by the receptor in age group "a," kg/yr; The fraction of the annual intake of fresh leafy vegetation grown locally; 1.0* The fraction of annual intake of stored vegetation grown locally; 0.76 The average time between harvest of leafy vegetation and its consumption, sec; The average time between harvest of stored vegetation and its consumption, sec; Yv The vegetation a real density, kg/m~; Period of leafy vegetable exposure during growing season, sec; Factor to account for fractional deposition of radionuclide "i." All other factors as defined before. Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX 5 Sheet 15 o f 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.5 Ue etation Pathwa (continued) For radionuclides other than iodine, the factor I< is equal to one. For radioiodines, the value of I< may vary. However, a value of 1.0 was used in Tables 3.3-2 through 3.3-4. Table B-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109, Revision l. In lieu of site-specific data default values for f> and fs, 1.0 and 0.76, 1 respectively, were used in the calculations on R<. These values were obtained from Table E-15 of Regulatory Guide 1.109, Revision l. The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the R~ is based on X/g: )Lf = K'K '[UAEI + UA f5] (DFLI)0 [ 0.75(0.5/H)] (B.2.8) V where: Dose factor for the vegetable pathway for tritium for any organ of interest, mrem/yr per pCi/m3. All other terms remain the same as those in Equations B.2-4 and B.2-7. Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE B-1 Parameters For Cow and Goat Milk Pathways Reference Parameter Value Re . Guide 1.109 Rev. 1 Q (kg/day) 50 (cow) Table E-3 6 (goat Table E-3 2 Y (kg/m ) 0.7 Table E-15 P tf (seconds) 1.73 E+05 (2 days) Table E-15 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 (DFLi) (mr em/pCig Each radionuclide Table E-11 to E-14 F (pCi/liter-per pCi/day) Each stable element Table E-1 (cow) Table E-2 (goat) Tb (seconds) 4.75 E+08 (15 yr) Table E-15 2 Y (kr/m ) 2.0 Table E-15 (seconds) 7.78 E+06 (90 days) Table E-15 U ap (liters/yr) 330 infant Table E-5 330 child Table E-5 400 teen Table E-5 - 310 adult Table E-5 te (seconds) 2.59 E+06 (pasture) Table E-15 5.18 E+06 (stored feed) B. (pCi/kg [wet weight] Each stable element Table E-1 per pCi/kg [dry soil]) 2 P (kg dry soil/m ) 240 Table E-15 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE'-2 Parameters For The Meat Pathway Reference Parameter Value Re . Guide 1.109 Rev. 1 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 Ff gpCi/ke per (pCi/Day) Each stable element Table E-1 U (kg/yr) 0 infant Table E-5 41 child Table E-5 65 teen Table E-5 110 adult Table E-5 'DFLi) (mrem/pCi) Each radionuclide Tables E-11 to E-14 2 Y (kg/m ) 0.7 Table E-15 P 2 Y (kr/m ) 2.0 Table E-15 Tb (seconds) 4.73 E+08 (15 yr) Table E-15 T s (seconds) 1.73 E+06 (20 days) Table E-15 t (seconds) 7.78 E+06 (90 days) Table E-15 te (seconds) 2.59 E+06 (pasture) Table E-15 5.18 E+06 (stored feed) QF (1g/day) 50 Table E-3 Bi (pCi/kg [wet weight] Each stable element Table E-1 per pCi/kg [dry soil]) P (kg dry soil/m 2 240 Table E>>15 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 - Parameters for TABLE B-3 The Vegetable Pathway Reference Parameter Value Re . Guide 1.109 Rev. 1 r (dimensionless) 1.0 (radioiodines) Table E-1 0.2 (particulates) Table E-1 (DFL. ) (mrem/pCi) Each radionuclide Tables E-11 to E-14 Q (kg/day) 50 (cow) Table E-3 6 (goat) Table E-3 U" (kg/yr} Infant 0 Table E-5 Child 26 Table E-5 h Teen ~ 42 Table E-5 Adult 64 Table E-5 Us a (kr/hr) Infant 0 Table E-5 Child 520 Table E-5 Teen 630 Table E-5 Adult 520 Table E-5 TL (seconds) 8.6 E+04 (1 day) Table E-15 t (seconds) 5.18 E+06 (60 day) Table E-15 2 Y (kg/m ) 2.0 Table E-15 te (seconds) 5.18 E+06 (60 day) Table E-15 t (seconds) 4.73 E+08 (15 yr) Table E-15 2 P (kg dry soil/m 240 Table E-15 Bi (pCi/kg [wet weight] Each stable element Table E-1 per pCi/kg [dry soil]) B-X8 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 0- APPENDIX C RADIOACTIVE LIQUID AND GASEOUS EFFLUENT Sheet 1 of 1 MONITORING INSTRUMENTATION NUMBERS Monitor Li uid Effluent Monitorin Instruments Identification Treated Laundry and Hot Shower Tank . . . . . . . REM-1WL-3540 B. Waste Monitor Tank . . . . . . . . . . . . . . . REM-21WL-3541 C. Waste Evaporator Condensate Tank REM-21WL-3541 D. Secondary Waste Sample Tank . . . . . . . . . . REM-21WS-3542 NSW Returns to Circulating Water 'System from Waste Processing Building . . . . . REM-1SW-3500A from Reactor. Auxiliary Building . . . . REM-1SW-3500B Outdoor Tank Area Drain Transfer Pump Monitor REM-1MD-3530 G. Turbine Building Floor Drains Effluent REM-1MD-3528 II. Gaseous Effluent Monitorin Instruments A. Plant Vent Stack 1 REM-1AV-3509- SA

RM-21AV-3509-1SA B. Turbine Building Vent Stack 3A . . . . . . . .
RM-1TV-3536-1 C. Waste Processing Building Vent Stack 5 . . . . . . REM-lWV-3546
RM-1WV-3546-1 D. Waste Processing Building Vent Stack 5A REM-1WV-3547
RM-1WV-3547-1 Wide-Range Gas Monitor (WRGM)

'0 ODCM C-3 f l, ~ 0

ML18011A563

Text

1.0 INTRODUCTION

1.0 INTRODUCTION

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