Text

Rev 5 to Odcm.
	ML18011A803
Person / Time
Site:	Harris
Issue date:	08/31/1994
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML18011A800	List: ML18011A799; ML18011A802; ML18011A803;
References
	PROC-940831, NUDOCS 9503060123
	Download: ML18011A803 (253)
	v • d • e

SHEARON HARRIS NUCLEAR POWER PLANT OFF-SITE DOSE CALCULATiON'ANUAL (ODCM)

Revision 5 Docket No. STN-50-400 CAROLINA POWER & LIGHT COMPANY PNSC Chairman's Approval EEEective Date RECEDED SEP 0 2 1994 HNP DOCUMENT CONTROL 9503060123 950226 PDR ADOCK 05000400 R PDR

4 Shearon Ha"r's Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE OF CONTENTS Section Title ~Pa e TABLE OF CONTENTS LIST OF TABLES LIST OF FIGURES iv

1.0 INTRODUCTION

2.0 LIQUID EFFLUENTS 2-1 2.1 Compliance With 10 CFR 20 2-2 2.2 Compliance With 10 CFR 50 Appendix I 2-13 3.0 GASEOUS EFFLUENTS 3-1 3.1 Monitor Alarm Setpoint Determination 3-1 3.2 Postrelease Compliance With 10CFR20-Based Technical Specification 3.11.2 3-15 3.3 Compliance With 10 CFR 50 3-22 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4-1 INTERLABORATORY COMPARISON STUDIES 5-1 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 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

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Shearon Harris Nuclear Power Plant (SHNPP) Auaus t Offsite Dose Calculation Manual (ODCM) Rev.

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 (Favaxx) 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 Az, Values for the Adult for the Shearon Harris Nuclear Power Plant 2-24 3.1-1 Gaseous Source Terms 3-12 3.1-2 Dose Factors and Constants 3-13 3.1-3 Gaseous Monitor Parameters 3-14 3.2-1 Releases from Shearon Harris Nuclear Power Plant (1)

Normal Operation (Curies/year) 3-18 3.2-2 Distance to the Nearest Special Locations for t'e Shearon Harris Nuclear Power Plant (Miles) 3-19 3.2-3 Dose Factors for Noble Gases 3-20 3.2-4 Pzz Values (Inhalation) for a Child 3-21 3.3-1 through 3.3-19 R Values for the Shearon Harris Nuclear Power Plant 3-34 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

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Shearon Harris Nuclear Power Plant (SHNPP) QuguD %

1 Qo Offsite Dose Calculation Manual (ODCM) 5e I LIST OF TABLES (continued)

No. Title ~Pa e A-5 through A-6 Undepleted, No Decay, X/Q Values For Long Term Ground Level Releases At Standard Distances (Sec/M3) A-5 A-7 through A-8 Undepleted, 2.26 Day Decay, X/Q Values For Long Term Ground Level Releases At Standard Distances (Sec/M ) A-7 A-9 through A-10 Depleted, 8.0 Day Decay, X/Q Values For Long Term Ground Level Releases At Standard Distances (Sec/M3) A-9 A-11 through A-12 Deposition Values (D/Q) For Long Term Releases At Standard Distances (m 2) A-11 A-13 Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP A-13 Shearon Harris Plant Site Input Information for Continuous Ground-level Release Calculations With the NRC XOQDOQ Program A-16 B-1 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

Shearon Harris Nuclear Power Plant (SHN?P) August 1994 fi Of s te Dose Ca 1cula cion ~fanual (ODCN) Rev. 5 LIST OF FIGURES No. 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 Mater Flow Diagram . 2-2&

2.1-4 Other Liquid Effluent Pathways 2-29 3.1 SHNPP Gaseous Waste Streams 3-53 3.2 Schematic of Airborne Effluent Release Points 3-54 3.3 SHNPP Condenser Off-Gas System 3-55 4.1-1 SHNPP Exclusion Boundary Plan 4-18 4.1-2 through 4.1-5 Environmental Radiological Sampling Points 4-19

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offs'te Dose Calculation Manual (ODCM) Rev. 5 List of Effective Pa es

~Pa e Revision Cover Page 1 - 11 iv 2-1 2 2-7 \ ~ ~

2-8 ~ ~ 5 2 2-10 2-11 ~ 0 ~ 0 ~ ~ ~ 5 2 2-29 ~ ~ ~ 4 3-1 55 4-1 22 5-1 ~ ~ ~ ~ ~ 0 ~

6-1 2 7-1 ~ \ 4 A-1 - A-4 A-5 - A-8 A-9 - A-21 ~ ~

B-1 - B-2 ~ ~ ~

B-3 B-4 ~ ~ ~ ~ ~ ~

B B-18 ~ ~ ~ ~ 4 C-l 4

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 monitoring 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 with Appendix I of 10CFR50.

The ODCM is based on "Vestinghouse 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 GASPAR 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.

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-"'e--'rc"" Harr's Nuclear Power Plant (SHNPP) Augus" 199-

o. e Calculation Manual (ODCM) Rev. 5 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 l (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 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 provided 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 uges 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 LOW ACT 2-1

L P

Shearon Harris Nuclear Power Plant (SHNPP) 0 fsite Dose Calculation Manual (ODCM) 2.1 Com liance with 10 CFR 20 10 CFR 20.1301 requires that the total effective dose equivalent to individual members of the public will not, exceed O.l 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 3.3.10 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.

Liquid effluent monitors have two setpoints, the high alarm and the 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 Hucles" P". ~'" June 1 QqQ Offsite Dose Calcu a""-": an' 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 found in liquid effluents and'provides a conservative basis for a monitor setpoint.

2-3

S ea on flarr ' %nuclear Power Plant (SUPP) June 1994

~:-=site Dcse Calculation Manual (ODCM) Rev, 4 2.1.1 Batch Releases (continued)

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)

(Ra.) (60) where:

R - Minimum allowable mix ng time, hr

'h V 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

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Shearon Harris Nuclear Power Plant (SHNPP)

Offsite Dose Calculation Hanual (ODCM) 2.1.1 Batch 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 ind.vidual release. Therefore:

Z, Cg ECLAT s Xo (2.1-2) where:

C~ - 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, Dq, 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.

Dreq Dreq,y Dreq,ng (2.1-3) where:

Dzeq, s Required dilution factor for gamma-emitters i

ECLAT (2.1-4) 2-5

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0 i,

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Shearon Harris Nuclear Power Plant !Si8:"-.'j June 1994 Offsite Dose Calculation <an Wev 2.1.1 Batch Releases (continued)

Drsq,ng Required dilution factor for non-gamma-emitters f ~ R f ~ R and 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 set'to 1E-03, which is the H-3 ECL.

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

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

respectively.

oi The measured concentration of each gamma-emitting nuclide, including noble gases, is reported in pCi/ml. If no gamma activity is d'etectable 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

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~ tris Huc Lea owe P lant (SR~P ) June 1994

".cse "=.'--cu'tion M -.; aj (QDCM) Rev.

2. j. 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 Rc~~ and R where Rcenaax Favail falloc (2.1-6)

Liquid effluent tank maximum waste flow rate, as specified in Table 2.1-1. This value is the same as FMaaoa

'nd Favaf). 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,~z 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 s 1, the minimum dilution flow rate is set to 0.0. If

) 1,D<<qthe minimum dilution flow rate is determined as follows: Dzaq min dflow ~F, D, (2.1-7) falloc where F~, = waste flow anticipated for this release 2-7

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

2.1.1 Batch Releases (continued)

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, C 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)

' ) + B where Setpoint adjustment factor.

alice Favell P vasce zeg 'ag (2.1-9)

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

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Shearon Harris Nuclear Power Plant Dose Calculation Manual (ODCM)

(SHNPP'ffsite 2.1.1 Batch Releases (continued)

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, Ci, 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) (S<<i ~

R ) + g (2.1-8) where Sad/ Setpoint adjustment factor.

falloe Favai1 (2.1-9)

F~aee 'x~

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 riarris 'nuclear Powe= P'a.".= (S:"2iPP) June 1994 Cr:s =e Dose Ce'ula" 'n Ha-.,ua'QDCK~~ Rev. E:

2.1.1 Batch Releases (continued)

Z slope<

Cl where the sum extends over all nuclides which have response factors stored in the database for the monitor of interest and slopel 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.

Sensit'vit nuclide i Cs-137 Sensitivity (2) Monitor alert alarm setpoint, Salezt (Cs-equiv)

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

Salezt [(S -B) F] +B where:

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

2-9

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Shearon Harris Nuclear Power Plant (SHNPP) June 199<

Offs'e Dose Calculation Manual (ODCM) Rev.

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,z~, therefore, background is acceptable if:

0.1[(S "B) 'F]

where:

MDC (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,~~ 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)

Offsite Dose Calculation Manual (ODCM) 2.1.2 Continuous Releases The continuous rele ases from the SWST and the NSW return lines are monrtored 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,g~ ~

Sensejf ) + Bkg (2.1-13) where:

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

Sens,z Q (Sens i x % abundance) for the SWST nuclide mix, cpm/pCi/ml.

Monitor Alert Alarm Setpoint, S, (Cs-equiv)

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 the presence of non-naturally occurring radioactivity > effluent LLD is confirmed, the releases may continue provided the sampling and analysis required by Technical Specification Table 4.11-1 are performed. The results of the sample analysis wj.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.

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

Therefore, background is acceptable if:

0'01 (ECLoEE 'ENSeff)

MDC (2.1-15) 2-11

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Shearon Harris nuclear .owe- Plan" {S~i;"->> June 1994 Offsite Dose Calculaciop <a "a'OD<<i Rev.

2.1.3 Other Li uid Releases

l. 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. Xf 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).

Turbine Building Floor Drains Effluent Line Mater collected in the turbine building floor drains is normally routed to the yard oil separator for release 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 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

8 S<<aaron Harris Nuclear Power Plant (SHNPP) June 1994 C=fsita Dose Calculation Manual (ODCH) Rev.

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:

Aicr' 'Ate Cia Fzs (2.2-1) where:

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.

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.

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

Cg, the average concentration of nuclide "i" in undiluted liquid effluent during time period at, from a'y liquid release, in pCi/ml.

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

2-13

8 I

4 14

Shearon Harris Nuclear Power Plant (SHNPP) e Offsite Dose Calculation Manual (ODCM) ~ T 2.2.1 Cumulation of Doses (continued)

Where:

Fzs vasse vaste avail

'Mx (2.2-2) and

%ix mixing ratio fraction of the release that reaches the receptor. At the SHNPP, this value is set to 1.

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

In the case of a continuous secondary waste sample tank radioactive release, Ci the concentration of nuclide "i" in the SWST composite sample. For the NSW, Ci - concentration'f nuclide "i" in the cooling tower basin and F<<s~e - discharge from the cooling tower basin while Favaii f the 1 ow from the makeup water cross - tie . For a re 1 ease through the Turbine Building Floor Drain Line to the waste neutralization system, Ci the Turbine Building floor drain sample activity, F~, discharge from the Turbine Building floor drain line, and Favai1 the average flow during the period of the total Cooling Tower discharge. The total Cooling Tower discharge is the sum of the Cooling Tower Slowdown 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 Ai~ (see NUREG-0133, Section 4.3.1) was calculated for an adult for each isotope "i" using the following equation:

Air 1 14E+05 (

~ Dv

+ 21BFi) i DFi e (2.2-3) where:

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

Corresponding to fish consumption from the Harris Lake (dilution - 1) and drinking water fr'om 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

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Shearon Harris iouclear 'Powe"= 331.ant June 1994 Dose Calculation Aanua. {ODC.".) Rev. 4 (SK1PP'ffsite 2.2.1 Cumulation of Doses (continued) 1.14E+05 - Units Conversion Factor

~XO'i . 3000 m3 . 3 yz (2 2-4) 1 pCi 1 liter 8760 hrs 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 BFz - Bioaccumulation factor for nuclide "i" in fish (from

'able A-1 of Regulatory Guide.,'1.109, Rev. 1), pCi/kg per pCi/1 DFz, - Dose conversion factor for nuclide "i" for adults for a particular organ ~ (from Table E-ll of Regulatory Guide 1.109, Rev. 1}, mrem/pCi Radiological decay constant of nuclide "i," hr ~;

0. 693 (ok),

(t4)~ - 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 pr'esents the Aq, 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 of 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 fr'om 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 ~

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Shearon Harris Nuclear Power Plant (SHNPP) June 1996 Offs' Dose Calculation Manual (ODCM) Rev.

2.2.2 Com arison A ainst Limits (continued)

For the calendar quarter:

Dj < 1.5 mrem total body (2.2-5)

Dz < 5 mrem any organ (2.2-6)

For the calendar year:

Dq,~ 6 3 mrem total body (2.2-7)

Dz,~ < 10 mrem any organ (2.2-8) where:

Dier Cumulative total dose to any organ t or the total body from all releases, mrem:

The quarterly limits given above .represent one-half the annual design objective 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.

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Offsite Dose Calculation Manual (ODCM)

Limits' 2.2.2 Com arison A ainst (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) + Der (2.3-1) where:

D~ the 31 Day Projected Dose by organ ~

D,- - sum of all open release points in mrem/day by organ 7.

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 the dose as Additional Anticipated Dose.

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Shearon Harris Vi clear Pwer Plant (Sgipp) June '994 Offsite Dose Calcu at'on >anua (0DC;g Rev. 4 2.2.4 Pro ection of Doses (continued)

To show compliance with Technical Specification 3.11.1.3, the projected month's dose should be compared as in the following:

D>, 0.06 mrem for total body (2.3-2) and D~, ( 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.

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Snearon riaxtis Nuclear Power Plant (SHNPP) June 1994 0"=site Dose Calculation Manual (ODCM) Rev.

TABLE 2.1-1 LIQUID EFFLUENT RELEASE TANKS AND PUMPS u'o. of Tanks PUMP DESIGN CAPACITY Igpm)

Discharge Recirculation Eductor Factor

"'ank Tank Capacity (gall Radiation Effluent Monitor ID SWST 100 100 0.2 25.000 REM-3542 WECT 35 100 1.0 10,000 REM-3541 100 100 0.25 25,000 REM-3542 WM7'3'LSHS 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.

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Offsite Dose Calculation Manual (ODCM)

TABLE 2.1-2 Setpoints for Cooling Tower Blowdown Dilution Flow Rates (F,)

Setting Trip Flow Rate (gpm) Minimum Dilution Flow Rate (gpm) 4 ppp 3,800 7 ppp 6,650 11 000 g 10,450 a 5%

5'5,000 14,250 TABLE 2.1-3 Signal Processor Time Constants (r) for GA Technologies RD-53 Liquid Effluent Monitors Detector Background (cpm) (min) 10> 10> 10 10~ - 103 103/cpm bkg 103 - 103/cpm bkg 10'0'-

105 103/cpm bkg 105 - 106 0.01 10'-10' 0.01 2-20

0'

'I I ~

f'

~

Shearon Harris Nuclear Por~er 'Plant June 1994 Offsite Dose Calculation Manua (OQCM) Rev. 4 TABLE 2.1-4 Page 1 of 3 Nuclide Parameters Half-Life At 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 0.00E+00 O.OOE+00 F-18 1.10E+02 6.32E-03 9.27E-01 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 O.OOE+00 O.OOE+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-01 2.24E+07 2.15E-Ol Cu-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 8.39E-04 9.90E-01 O.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 7.70E-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 '3E-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-08 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 ~

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+04 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

4f S'nearon 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 Sensitivity Nuclide ~hours e-At i

~c)~ms C ~ml ~Slo e Tc-101 1.42E+01 4.88E-02 5.57E-01 1.66E+08 1.60E+00 Ru-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-01 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 2.8&E-03 Te-127m 1.57E+05 4.41E-06 1.00E+00 1.33E+04 1.2&E-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+Ol 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 5.9&E-05 9.99E-01 1.55E+08 1.49E+00 I-132 1.3&E+02 5.02E-03 9.42E-01 3.31E+08 3.1&E+00 I-133 1.25E+03 5.55E-04 9.93E-01 1.39E+08 1.34E+00 I-134 5.26E+Ol 1.32E-02 8.54E-01 3.08E+08 2.96E+00 I-135 3.97E+02 1.75E-03 9 '9E-01 1.03E+08 9.90E-01 Cs-134 1.0&E+06 6.42E-07 1.00E+00 2.60E+08 2.50E+00 Cs-136 1.90E+04 3.65E-05 1.00E+00 3.37E+08 3.24E+00 Cs-137 1.59E+07 4.36E-OS 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+01 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 5.7&E-Ol Ba-141 1.83E+Ol 3.79E-02. 6.35E-01 2.53E+08 2.43E+00 Ba-142 1.07E+01 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+0& 1.47K+00 La-142 9.54E+01 7.27E-03 9.17E-01 9.59E+07 9.22E-Ol Ce-141 4.68E+04 1.4&E-05 1.00E+00 6.11E+07 5.88E-01 Ce-143 1.9&E+03 3.50E-04 9.96E-01 9.60E+07 9.23E-01 Ce-144 4.09E+05 1.69E-06 1.00E+00 1.30E+07 1.25E-01 Pr-143 1.95E+04 3.55E-05 1.00E+00 1.0SE+02 1.04E-06 Pr-144 1.73E+01 4.01E-02 6.18E-Ol 1.68E+06 1.62E-02 Nd-147 1.5&E+04 4.39E-05 9.99E-01 2.86E+07 2.75E-01 Hf-181 1.02E+03 6.81E-04 9.92E-01 2.0&E+08 2.00E+00 W-187 1.4SR+03 4.85E-04 9.94E-01 1.04E+08 1.00E+00 Hp-239 3.39E+03 2.04E-04 9.98E-01 1.13E+08 1.09E+00 2~22

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Shearon Harris Nuclear Power Plant (SHNPP)

Offsite Dose Calculation Manual (ODCM}

TABLE 2.1-4 page 3 of 3 Nuclide Parameters (continued)

Half-Life Sensitivity Nuclide ~houre e-At ~cm pCi~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 9.2?E-01 O.OOE+00 O.OOE+00 Kr-85 5.64E+06 1.23E-O? 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-01 Kr-88 1.70E+02 4.08E-03 9.52E-01 ?.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-O? 1.59E+08 1.53E+00 Xe-131m 1.70E+04 4.08E-05 1.00E+00 2 '2E+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 9.9?E-01 1.59E+07 1.53E-01

'Xe-135 5.47E+02 1.2?E-03 9.85E-'Ol 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+01 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 O.OOE+00 O.OOE+00 Notes to Table 2 '-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 Davi'd 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 i relative to Cs-137, the nuclide sensitivity is divided by the Cs-137 sensitivity.

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Shearon Harris Nuclear rower Plant (SHNPP) June 1994 Offsite Dose Calculation Hanual (ODCH) Rev.

Sheet 1 of 2 TABLE 2.2-1 Air UALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT AZ,, 9 = 1.14EtOS ( V

+ 21BF>) DF~, e (mrem/hr per pCi/ml)

Nuclide Bone Liver ~T. Bod ~rh roid ~Kidne ~Lnn GI-LLI H-3 O.OOE+00 8. 54E-01 8.54E-01 8.54E-01 8.54E-01 S. 54E-01 8.54E-01 C-14 3. 13E+04 6.27E+03 6.27E+03 6.27Et03 6.27E+03 6.27K+03 6.27K+03 Nh 24 2.40K+02 2.40K+02 2.40Et02 2.40K+02 2.40K+02 2.40E+02 2.40K+02 P-32 4.52E+07 2.81E+06 1.75E+06 O.OOE+00 O.OOE+00 O.OOE+00 5.08K+06 CR-51 O.OOE+00 O.OOE+00 1.28E+00 7. 63E-01 2. 81E-01 1.69E+00 3.21E+02 MN-54 O.OOE+00 4.41E+03 8.41E+02 O.OOE+00 1.31E+03 O.OOE+00 1.35K+04 MN-56 O.OOE+00 4.44E+00 7. 87E-01 O.OOE+00 5.63E+00 O.OOE+00 1.42E+02

, FE-55 6.76E+02 4.67E+02 1.09K+02 O.OOE+00 ~

O.OOE+00 2.60E+02 2.68E+02 FE-59 . 1.06E+03 2.49E+03 9.54E+02 O.OOE+00 O.OOE+00 6.95K+02 8.29K+03 CO-57 O.OOE+00 2. 20K+01 3.66K+01 O.OOE+00 O.OOE+00 O.OOE+00 5.58E+02 CD58 O.OOE+00 9.33K+01 2.09E+02 O.OOE+00 O.OOE+00 O.OOE+00 1.89K+03 CO-60 O.SOB+00 2.69E+02 5.94E+02 O.OOE+00 O.OOE+00 O.OOE+00 5.06E+03 Nj-63 3.20E+04 2.21Et03 1.07E+03 O.OOE+00 O.OOE+00 O.OOE+00 4.62K+02 NI-65 4.76E+00 6. 19E-01 2.82E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.57E+01 CU-64 O.OOE+00 5.45K+00 2.56K+00 O.OOE+00 1. 37K+01 O.OOE+00 4.64K+02 ZN-65 2.32K+04 7.39Et04 3.34K+04 O.OOE+00 4.94E+04 O.OOE+00 4.65K+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-69M 4.46E+02 1.07K+03 9. 79E+01 O.OOE+00 6.48E+02 O.OOE+00 6.54E+04 BR-82 O.OOE+00 O.OOE+00 1. 81K+03 O.OOE+00 O.OOE+00 O.OOE+00 2.07K+03 BR-83 O.OOE+00 O.OOE+00 1.24E+00 O.OOE+00 O.OOE+00 O.OOE+00 1.79K+00 BR-84 O.OOE+00 O.OOE+00 8.07E-06 O.OOE+00 O.OOEt00 O.OOE+00 6.33E-11 BR-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.SOB+00 O.OOE+00 O.OOEt00 RB-86 O.OOE+00 9.95E+04 4.63E+04 O.OOE+00 O.OOE+00 O.SOB+00 1.96K+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 2.38Et04 O.OOE+00 6.84Et02 O.OOE+00 O.OOE+00 O.OOE+00 3.82E+03 SR-90 5. 91E+05 O.OOE+00 1.45K+05 O.OOE+00 O.OOE+00 O.OOE+00 1.71E+04 SR-91 1.84K+02 O.OOE+00 7.43E+00 O.OOE+00 O.OOE+00 O.OOE+00 8.77Et02 SR-92 7.84K+00 O.OOE+00 3. 39E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.55Et02 Y-90 5. 57E-01 O.OOE+00 1.49E-02 O.SOB+00 O.OOE+00 O.OOE+00 5.91K+03 Y-91M 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 9.27E+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-01 1.35E-01 9.12E-02 O.OOE+00 2. 11E-01 O.OOE+00 4.27E+02 ZR-97 1.42E-02 2.87E-03 1.31E-03 O.OOE+00 4.34E-03 O.OOE+00 8.90E+02 NB-95 4.43K+02 2.47K+02 1.33K+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.OOE+00 3.45E+00 M3-99 O.OOE+00 1.14K+02 2. 17E+01 O.OOE+00 2.58K+02 O.OOE+00 2.64K+02 TC-99M 2.60E-03 7.35E-03 9.36E-02 O.OOE+00 1. 12E-01 3.60E-03 4.35E+00 2-24

Shearon harris Nuclear Pover Plant (SHNPP) June l994 Of site Dose Calculation Manual (ODCM) Rev. 4 Sheet 2 of 2 TABLE 2.2-1 (Continued)

AgT VALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT (mrem/hr per pCi/ml)

Nuclide Bone Liver ~T. Bod ~Th old ~Kidne ~Lnn GI-LLI TC-101 5. 81E-18 8. 37E-18 8.21E-17 O.DOE+00 1. 51E-16 4.28E-18 2.52E-29 RU-103 5.49K+00 O.DOE+00 2.37K+00 O.OOE+00 2.10E+01 O.DOE+00 6. 41Et02 RU-105 7.07E-02 O.DOE+00 2.79E-02 O.DOE+00 9. 13E-01 D.DOE+00 4.32K+01 RU-106 8.23K+01 O.OOE+00 1.04K+01 O.OOE+00 1.59K+02 O.DOE+00 5.33E+Q3 AG-110H 9.55E-01 S.83E-01 5.25E-01 O.DOE+00 1.74K+00 O.DOE+00 3.60K+02 SB-124 2.33K+01 I0.40E 01 9.24K+00 5.65E-02 O.DOE+00 1.82E+01 6.62K+02 SB"125 1.50K+01 1. 67E-01 3.57E+00 1.52E-02 O.DOE+00 l. 16K+01 1.65K+02 TE-125H 2.57E+03 9.32K+02 3.44E+02 7.73E+02 1.05E+04 O.OOE+00 1.03Et04 TE-127H 6. 51K+03 2.33K+03 7.94E+02 1.68E+03 2.65K+04 O.DOE+00 2. 18E+04 TE-127 4.36K+0'1 l. 57K+01 9.44Etoo 3. 23Etol 1.78Et02 O.DOE+00 3.44K+03 TE-129H 1.10E+Q4 4.10K+03 1.74Et03 3.77E+03 4.59K+04 O.DOE+00 5.53K+04 TE-129 2.33E-02 8.76E-03 5.68E-03 1.79E-02 9.80E 02 O.DOE+00 1.76E-02 TE-131H 1.27E+03 6. 19E+02 5. 16K+02 9.80Et02 6.27Et03 O.DOE+00 6.14E+04 TE-131 4.07E-OS 1.70E 08 1.28E-08 3.35E-OS 1.78E-07 O.DOE+00 5.76E-OS TE-132 2.19K+03 1,41EtQ3 1.33E+03 1.56K+03 1.36E+04 O.DOE+00 6.69K+04 I-130 1.62K+01 4. 77Eto1 1.88E+01 4.05E+03 7. 45K+01 O.DOE+00 4. 11E+01 I-131 1.67E+02 2.39E+02 1.37E+02 7.84K+04 4.10E+02 O.DOE+00 6.31E+01 I-132 2.29E 01 6.12E 01 2.14E-01 2. 14E+01 9.75E 01 O.DOE+00 1.15E 01 I-133 4. OOE+01 6.95K+01 2. 12Eto 1 1.02Et04 1. 21Et02 O.DOE+00 6.25K+01 I-134 3.37E-04 9.15E 04 3.27E-04 1.59E-02 1.46E 03 O.DOE+00 7.9SE-07 I-135 5.29K+00 1.38E+01 S. 11K+00 9.13K+02 2. 22K+01 O.DOE+00 1.58E+01 CS-134 2.99E+05 7.10E+05 5.81E+05 O.DOE+00 2.30K+05 7.63K+04 1.24K+04 CS-136 3.05K+04 1.20K+05 8.65E+04 O.OQE+00 6.69Et04 9.17K+03 1.37E+04 CS-137 3.83E+05 5.23E+05 3.43E+05 O.DOE+00 1.78E+05 5.91K+04 1. 01Et04 CS-138 4.92E-05 9.72E-05 4.S2E-05 O.OOE+00 7. 14EW5 7.06E-06 4.15E-10 Bh-139 3.72E-03 2.65E-QS 1.09E-04 O.ODE+00 2.48E-OS 1.50E-06 6.6OE-03 BA 140 3.08E+02 3. 86E-01 2. 02K+01 O.OOE+00 l. 31E-01 2.21E-01 6.33K+02 BA-141 1.05E-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 l. 16E-22 O.DOE+00 1.60E-24 1.07E-24 O.OOE+00 LA-140 1.34E-Q1 6.75E-02 1.78E-02 O.OOE+00 O.DOE+00 O.DOE+00 4.96E+03 Lh-142 4.51E-05 2.05E-05 5. 11E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.5QE-01 CE-141 7.76E-02 5.24E-02 5.95E-03 O.DOE+00 2.44E-02 O.OOE+00 2 01K+02 CE-143 1.07E-02 7.94K+00 8.79E-OI0 O.OOE+00 3.50E-03 O.OOE+00 2.97E+02 CE-144 4.08K+00 1. 71E+Q0 2. 19E-01 O.OOEtao l. 01E+00 O.DOE+00 1.38K+03 PR-143 5. 91E-01 2. 37E-01 2.93E-02 O.OOE+00 1.37E-01 O.DOE+00 2.59K+03 PR-144 5. 88E-16 2;44E-16 2.99E-17 O.DOE+00 1.38E-16 O.DOE+00 8.46E-23 ND-147 4.02E-01 4.64K-01 2.78E-02 O.DOE+00 2.71E-01 O.DOE+00 2.23K+03 M-187 2.10K+02 1.75K+02 6. 12K+01 o.aoK+ao O.DOE+00 O.OOEtoo 5.74K+04 NP-239 3.08E-02 3.03E-03 1.67E-03 O.DOE+00 9.44E-03 O.DOE+00 6.21K+02 2-25

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Shearon Harris Nuclear Power Plant (SHNPP)

Offsite Dose Calculation Manual (ODCM)

- Figure 2.1-1 Liquid Waste Processing Flow Diagram I

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Shearon Harris Nuclear Power Plant (SHNPP) August 199~

Offsite Dose Calculation Manual (ODCM) Rev. 5 3.0 GASEOUS EFFLUENTS At SHNPP there a re four gaseous effluent discharge 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 oint Determination (Technical Specification 3.3.3.11)

This section provides the methodology for stack effluent monitor setpoints 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 mrem/year to the skin as specified in Technical Specification 3.11.2.1.

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 CD Gamma spectroscopy analysis of the gas sample should provide the nuclide identification and activity. However, in the case where the noble activities are ( LLD the relative nuclide composition can be assumedgas from the GALE code activities for projected normal operating releases (Table 3.1-1). The GALE code is used to establish a default setpoint for each vent stack. This setpoint will be used as a "fixed" setpoint until a more conservative setpoint is calculated, either using a different assumed mix or actual sample results.

3-1

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Shearon Harris Nuclear Power Plant (SHNPP) Augus- 199<

Offsite Dose Calculation Manual (ODCM) Rev.'

3.1.1 Default Continuous Release Monitor Set pints Usin a Conservative mix

2. Determine the maximum whole body and skin dose rate (mrem/year) during the release.

~XQ [ Zg Kg Qg ] (3.1-2a) and Q-s YxXQ [ Ef (Lf + 1.1Mf) Qf ) (3.1-2b) where:

index over all nuclides the total body dose factor due to gamma emissions for noble gas radionuclide i (in mrem/yr per pCi/m3), from Table 3.1-2.

The skin dose factor due to beta emissions for noble gas radionuclide i (mrem/yr per pCi/m~)

The air dose factor due to gamma emissions for noble gas radionuclide i (mrad/yr per pCi/m~). A unit conversion constant of 1.1 mrad/mrem converts air dose to skin dose Lg+1. 1M'kin dose Table 3.1-2 factor (mrem/yr per pCi/m~), from The highest calculated annual average relative concentration for any sector at or beyond the exclusion boundary (sec/m~)

6.1E-06 sec/m~ from Table A-l, Appendix A 3-3

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Shearon Harr's "nuclear Power Plant (SHiNPP) August 1991<

Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.1 Default Continuous Release Monitor Set pints Usin a Conservative mix Using the GALE code activities from Table 3.1-1 and the maximum effluent design flow rate, continuous release stack maximum setpoints in pCi/cc and pCi/sec are determined. These values will be used as default values for the stack monitors. Based on sampling and analysis, the setpoint will be recalculated.

sample analysis setpoint is higher than the default setpoint, the If the setpoint will not be changed. If the sample analysis setpoint is lower than the default, the setpoint will be changed to reflect the more conservative setpoint. When the setpoint changes again, the more conservative setpoint, comparing the default (GALE code) and sample analysis, will be used.

Determine S lt, the gas channel alert alarm setpoint in pCi/cc, and RR,lt the gas channel alert alarm release rate setpoint in pCi/sec.

S alert [ (S~~ - Bkg) Ag j + Bkg (3.1-5a) and RRalert [(RR ag

- Bkg,z) Af) + Bkg,g (3.1-5b) where:

Ag A value < 1.0 designed to alert the operator that the high alarm setpoint is being approached.

Bkgrr- Bkg ~ Fv ~ 28316.85 / 60 3-5

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Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.2 Monitor Set pints Usin Sam le Results 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 pre-entry 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 setpoint must reflect the contribution of both the continuous and batch sources.

The following methodology will calculate a setpoint for the continuous release vent stacks based on actual sample results and for batch releases occurring concurrently with continuous releases.

Determine the noble gas.radionuclide activity (Q<) in pCi, and the activity release rate (Q<) in pCi/sec for each nuclide i. Q~ is the average release rate of nuclide i in gaseous effluent from discharge point v, in pCi/sec. Noble gases may be averaged over a period of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Q( m Z Cz ~ F ~ duration ~ 28316.85 (3.2-1a) and Qz Z Cg ~ F ~ 28316.85 / 60 (3.2-1b) where:

index over all vent stacks Cg concentration of nuclide, in pCi/cc the measured concentration from a stack effluent sample or pre-release sample. If there is no activity in the sample, then the GALE code activities from Table 3.1-1 will be used.

Fv effluent release rate or vent flow rate in CFM for continuous releases, the measured effluent flow rate or the maximum effluent design flow rate at the point of release (acfm) from Table 3.1-3.

3-6

Shearon Harris Nuclear Power Plant (SHNPP)

Offsite Dose Calculation Manual (ODCM) 3.1.2 Monitor Set pints Usin Sam le Results (continued) for batch releases, the release flow rate, in acfm',500 acfm for containment normal purge 37,000 acfm for containment preentry purge 2.26 E+06 (

hPc 14.7 ) (

273 Tc

)

for a containment pressure release for a Waste Gas Decay Tank release where:

2.26E+06 and 600 are the volumes in ft~ of the containment and decay tank, respectively, and Tc, T~, QPc, and hP~ are the estimated, respective temperature and change in pressure (psig) following the release of the containment and decay tank; and, 14.7 - 1b/in~, i.e., 1 atmosphere pressure Length of release, min 273'K O'C Tg,T, . 273'K +

duration of release, in minutes C'uration 28316.S5 conversion factor for cc/ft>

3-7

Shearon Harris Muc ea" Po~er Plant (SHiNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.2 Monitor Set pints Usin Sam le Results (continued)

2. Determine the maximum whole body and skin dose rate (mrem/year) during the release by summing together the dose rates for this release with all concurrent releases for the time of the release.

7xXgj Z f Zg Kq gq ] (3.2-2a) and Mj~ Z, [ Zf (Lf + 1.1M') Qf ] (3.2-2b) where:

index over all radionuclides Kg the total body dose factor due to gamma emissions for noble gas radionuclide i (mrem/yr per pCi/m3), from Table 3.1-2.

The skin dose factor due to beta emissions for noble gas radionuclide i (mrem/yr per pCi/m )

The air dose factor due to gamma emissions for noble gas radionuclide i (mrad/yr per pCi/m~). A unit conversion constant of 1.1 mrad/mrem converts air dose to skin dose L~+1. 1M'kin dose factor (mrem/yr per pCi/m~) from Table 3.1-2 XXXi The highest calculated annual average relative concentration for any sector at or beyond the exclusion boundary (sec/m~)

6.1E-06 sec/m~ from Table A-l, Appendix A 3-8

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.2 Monitor Set pints Usin Sam le Results (continued)

3. Determine the ratio of dose rate limit to dose rate.

nratio - lesser of the ratios Whole Body ratio 500 (3.2-3a)

Q-b and Skin ratio 3000 (3.2-3b) where:

500 site dose rate limit for whole body in mrem/year.

3000 site dose rate limit for skin in mrem/year.

Determine S~~, the maximum concentration setpoint in pCi/cc, and RR ~ the maximum release rate setpoint in pCi/sec for the monitor.

(f, ~ f,ll ~ nratio ~ ZCz ) + Bkg (3.2-4a) and RR ~ - S~~ ~ F>> ~ 28316.852 / 60 (3.2-4b) where safety factor for the discharge point 0.5 fallo c dose rate allocation factor for the discharge point 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. These values are based on the percentage of an individual stack flow to the total stack flow and are in Table 3.1-3 ~

Bkg Monitor background, in pCi/cc measured background at time of release or 0.

3-9

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Shearon Harris Nuclear Power Plant (SHNPP) c Qgus Offsite Dose Calculation Manual (ODCM) Rev.

3.1.2 Monitor Set pints Usin Sam le Results (continued)

5. Determine S,l,<<, the gas channel alert alarm setpoint in pCi/cc, and RRal<<t the gas channel alert alarm release rate setpoint in pCi/sec.

[(S~~ - Bkg) Af] + Bkg (3.2-5a) and RRalert [( ~ax Bkgrr ) Af] + Bkgrr (3.2-5b) where:

Af A value ( 1.0 designed to alert the operator that the high alarm setpoint is being approached.

P Bkg Bkg ~ Fv ~ 28316'85 / 60 3-10

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Shearon Harris Nuclear Power Plant (SHNPP) Augus" 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.3 Effluent Monitorin Durin Ho in 0 erations If the reactor has been shut down for g rea ter 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).

A conservative effluent channel setpoint has been established for Vent Stack 3A. The monitor setpoint should be reduced proportionately to the estimated fraction of the main condenser effluent flowing directly to the atmosphere.

3-11

l II

Table 3.1-1 C) tn GASEOUS SOURCE TERHS tii O m Qi ti rt 0 Condenser Vacuum Containment (D Plant Vent Pump WPB WPB Purge or WGDT (d) O 0:

Ventilation Flow Ventilation Flow Ventilation Flow Ventilation Flow Pressure Relief Release 0 via via via via via via N Stack 1 Stack 3A Stack 5 Stack 5A Stack 1 Stack 5 (c) nsi ta I Rel. I Rel. I Rel. I Rel. I Rel. I Nuclide Ci

~Ci~cc Hix Ci Qi~Ci cc Hix Ci cHix gHCCiccc Ci Qi~Ci cc Mix Ci Qi~Ci cc Hix ~Cl Ci Rel.

Hl* 0 C 0

k Kr-83m 1.82E-B 3.78E-4 O fl Kr-85m 5.17E-10 2.16E-2 4.74E-9 2.43E-2 1. 95E-9 2. 16E-2 2. 18E-8 4. 53E-I0 0 Kr-85 6.08E-B 9.81E-1 7.26E-9 1.51E-3 7.05E-5 9.81E"1 0

Ã 8 m

Kr-87 1. 72E-10 7. 19E-3 6.49E-10 7.19E-3 3.63E-9 7.56E-4 C

Kr-88 8.61E-10 3.60E-2 7. 12E-9 3.66E-2 3.25E-B 3.60E-2 2.91E-B 6.05E-3 Kr-89 0 .

0 n Xe-131m 8.69E-10 1.40E-2 1.82E-B 3.78E-3 1.01E-6 1.40E-2 M

Xe-133m 3.45E-10 1.44E-2 2.37E-9 1.22E-2 1.30E-9 1.44E-2 7.81E-B 1.62E-2 'R Xe-133 2.07E-B 8.63E-1 1.71E-7 8.78E-1 2.90E-10 4.67E-3 7.79E-B 8.63E-1 4.54E-6 9.44E-1 3.36E-7 4.67E-3 Xe-135m Xe-135 1.21E-9 5.04E-2 9.49E-9 4.87E-2 4.54E-9 5.06E-2 1.07E-7 2.23E-2 Xe-137 0 .0 Xe-138 1.72E-10 7.19E-3 0 6. 49E-10 7. 19E-3 (a) Source terms are based upon GALE code (SHNPP FSAR Table 11.3.3-1) and not actual re).eases.

Values apply only to routine releases,and not emergency situations.

I (b) Souzcs term for this effluent stream not presented with FSAR. RAB mix assumed.

(c) Ci (uCi/cc) ~ Ci r r min Ci Ci ft3 cc F, C 0c C

(d) Based on an asstzsed flow of 200 CFH for WGDT.

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Shearon Harris Nuclear Power Plant (SHNPP) August Offsite 199>>'ev.

Dose Calculation Manual (ODCM) 5 TABLE 3.1-2 DOSE FACTORS AND CONSTANTS" Whole Body Dose Skin Dose Factor Factor (K~) (Lg + 1.1 Mg)

Radionuclide (mrem/yr/pCi/m~) (mr em/yr/pC i/m~)

Kr-83m 7.56E-02 2.12E+01 Kr-85m 1.17E+03 2.81E+03 Kr-85 1.61E+01 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+01 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 1.81E+03 3.97E+03 Xe-137 1.42E+03 1.39E+04.

Xe-138 8.83E+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).

3-13

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Shearon Harris Nuclear Power Plant (SHNPP} August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.1-3 GASEOUS MONITOR PARAMETERS PVS-1 TBVS-3A WPBVS-5 WPBVS-5A Maximum effluent design 390,000 28,620 232,500 103,050 flow rate, (acfm)

Flow Allocation Factor 0. 517 0.038 0.308 0. 137 l f.u.c j 3-14

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N 4

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.2 Postrelease Com liance with 10CFR20-Based Technical S ecification 3.11.2 3.2.1 Noble Gases The gaseous effluent monitors setpoints 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 setpoints could be exceeded and yet 10CFR20-based limits may actually be met. Therefore, the following methodology has been provided in the event that if the high alarm setpoints are exceeded, a determination may be made as to 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:

P K (X75) g s 500 mzem/yr (3. 2-1)

( i + ')(xXQ)v ~iv s / (3.2-2) i where:

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

6.1E-06 sec/m from Table A-l, Appendix A, for ground-level releases in the S sector at the exclusion Ki'he

'boundary.

total body dose factor due to gamma emissions for noble gas radionuclide "i," mrem/year per pCi/m3.

Table 3.2-3.

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

Table 3.2-3.

Mi - The air dose factor due to gamma emissions for noble gas radionuclide "i," mrad/year per pCi/m3.

Table 3.2-3.

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~ l" Shearon Harris Nuclear Power Plant (SHNPP) August 199~

Offsite Dose Calculation Manual (ODCM) Rev. 5

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 Mz) are tabulated in Table 3.1-2.

Q.iv - 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 4.11.2.1.2. 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

/ Kr-85 LLD mix for compliance'he 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 {Zjg) in the unrestricted area for the period 1976 - 1987. Long-term annual. average {Xjg)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 {Z7Q) values were calculated assumin'g no decay, undepleted transport to the exclusion bo'undary. These values are given in Table A-l, Appendix A . The maximum exclusion boundary {279)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 K~, Lz, and M~ which are to be used by SHNPP in Equations 3.2-1 and 3.2-2 to show compliance with Technical Specification 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.

3-16

0 fq "I<'

Shearon Harris Nuclear Power Plant (SHNPP) Augus- 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.2.2 Radioiodines and Particulates The bases for Technical Specrfication 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 > 8 days is limited to 1500 mrem/yr to any organ. Based upon NUREG-0133, the following is used to show compliance:

(~Q) Qf ] s 1SOO mrem/yr (3.2-3) 1 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 excl'usion boundary (Z7$ ) value. Values for Pi I in Eq. 3.2-3 were calculated for a child for various radionuclides for the inhalation pathway using the methodology of NUREG-0133. The Pi11 values are presented in Table 3.2-4. A description of the=

methodology used in calculating the Pz values is presented in B. The values of Pz reflect, for each radionuclide, the'ppendix maximum Pz value for any organ.

. The (X7g)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'rovided in Appendix A.

3-17

K t

fj~i d

Table 3.2-1 Releases from the Shearon Harris Nuclear Power Plant (1)

Normal Operation (Curies/year)

Waste Processing Bldg Waste Processing Bldg Condenser Vacuum Pump Exhaust and/or Exhaust via VENT STACK 5A and Turbine Building Waste Gas Decity Tanks (2) or RAB/FHB and Containment Exhaust via VENT STACK 5 Exhaust via VENT STACK I via VENT,STACK 3A NOBLE NORMAL GASES SHUTDOWN OPERATIONS i CONTAINMENT RAB/FHB TURBINE STACK 3A TOTAL Kr-83m 0 0 I.QE+00 0 0 0 I.OE+00 Kr-85m 0 0 1.2E+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 Kr-87 0 0 2.0E+00 I.QE+00 Q 0 3.0E+00 Kr-88 0 0 1.6E+01 5.0E+00 0 3.0E+00 2.4E+01 Kr-89 0 0 0 0 0 0 0 Xe-131m 0 3.0E+00 I.OE+00 0 0 0 1.3E+01 Xe-133m 0 0 4.3E+01 2.0E+00 0 I.OE+00 4.6E+01 Xe-133 0 I.QE+00 2.5E+03 1.2E+02 0 7.2E+01 2.7E+03 Xe-135m Q s 0 0 0 0 0 0 Xe-135 0 0 5.9E+01 7.0E+00 0 4.0E+00 7.0E+01 Xe-137 0 0 0 0 0 0 0 Xe-138 0 0 0 I.QE+00 0 0 I.OE+00 Ar41 2.5E+O le'ARTICULATES I-131 0 0 1.3E42 4.5E43 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 '"

C-14 8.0E+00 Mn-54 0 4.5E43 2.2E44 1.8E44 0 0 "'.9E43 Fe-59 0 I 1.5E43 7,3E45 6.0E45 0 0 1.6E43 Co-58 0 1.5E42 7.3E44 6.0E44 0 0 1.6E42 Co%0 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 3.0E44 0 0 8.2E43 Adapted from SHNPP FSAR Table 11.3.3-1. Calculations are based upon the GALE code, and do not reflect 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 after a 90-day decay period.

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

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Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 Table 3.2-2 Distance to the Nearest Special Locations for the Shearon Harris Nuclear Power Plant (miles)*

(Comparison of 1993/1994 Data)

Residence Milk Animal Garden Meat Animal Exclusion Sector Boundary 1993 1994 1993 1994 1993 1994 1993 1994 N 1.32 2.2 2.2 2.2 2.2 2.8 2.2 2.2 2.2 NNE 1.33 1.9 1.9 1.7 1.9 2.2 2.2 NE 1.33 2.3 2.3 2.3 2.3 2.3 2.3 ENE 1.33 1.8 1.8 3.6 1.8 1.8 1.33 1.8 1.8 2.0 2.0 2.0 ESE 1.33 2.6 2' 4.7 4,7 4.2 4.2 SE 1.33 2.6 2.6 4.1 2.6 4.1 2.6 SSE 1.33 4.2 4.2 4.3 1.36 5.3 5.3 5.3 5.3 5.3 SSW 1.33 3.9 3.9 3.9 SW 1.33 2.9 2.9 2.9 2.9 WSW 1.33 4.5 4.5 4.5 4.5 4' 1.33 3.0 3.0 3.1 3.1 3.1 3.1 1.33 2.3 2.3 2.3 2.3 2.6 1.26 2.4 2.4 2.7 2.7 3,.7 3 7-NNW 1.26 1.6 1.6 , .2.0 2.0 2.0 2.0 As of August, 1994.

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

Distances and sectors determined by Global Positioning System.

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Shearon Harris Nuclear Power Plant (SHNPP) August to9r; Offsite Dose Calculation Manual (ODCM) Rev. 5 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; L. M) Ni (mrem/yr per (mrem/yr per (mrad/yr per (mrad/yr per yCi/m~) yCi/ms) yCi/m') yCi/m')

Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.1 7E+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 9.1 5E+ 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 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 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.

3-20

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.'2-4 Pi11 VALUES (INHALATION) FOR A CHILD PE

'I 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 '1E+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 HZ-181 7.95E+05 3-21

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Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.3 COMPLIANCE WITH 10CFR50 The calculatrons 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.'he 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 will calculate doses based on the actual average meteorology for the period of interest.

GASPAR Parameters are maintained in the Laboratory and Facility Services Section Instruction RC-ER-36, Operating Instruction for XOQDOQ, GASPAR, 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..

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Shearon Harris Nuclear Power Plant (SHNPP) Augus Offsite Dose Calculation Manual (ODCM) Rev. 5 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:

D 3.17 E-08 Q M [ (xXX)) () + (~xz) a ) (3.3-1) v v D~ - 3.17 E-08 P N [ ('XXQ) g +,(XR)v ai v ] (3.3-2) i v where:

D The air dose from gamma radiation, mrad.

7 Dp The air dose from beta radiation, mrad.

Ng The air dose factor due to beta emissions for each-identified noble gas radionuclide "i," mrad/year. per pCi/m~.

Table 3.2-3 ~

Z7g The relative concentration for areas at or beyond the exclusion boundary for short-term ground-level vent stack releases (8 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), sec/m~. See Section 3.0 earlier or use 6.1E-06 sec/m~ from Table A-l, Appendix. A.

Qiv The total release of noble gas radionuclide "i" in gaseous effluents for long term releases (>500 hrs/yr) from all vent stacks (pCi).

q;.."

i . . The total release of radionuclide "i" in gaseous releases for short-term releases (<500 hours/year) from all vent stacks, (pCi).

3.17 E-08 The inverse of the number of seconds in 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 retrad/mrem converts air dose to skin dose 3-23

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 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

(-2.19 kilometers) in the S sector based upon the tables presented in Appendix A (see Section 3.2.1 earlier). For this document, long-term annual average Zjgv 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 mix, isotopic release, and meteorology. To select the limiting location, the highest annual average 77Qv 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 Nz, 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 (3.3-3)

DP S 10 mrad (3.3-4)

For the calendar year:

Dy S. 10 mrad (3.3-5)

DP 8 20 mrad (3; 3-6)

The quarterly limits given above represent one-half of the annual design objectives of Section II.B.l 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.

3-24

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Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.3.1 Noble Gases (continued)

2. Source Term Determination Y

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 - 2.26K+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; Ci

vh (3.3-7)

Where; qq Activity of nuclide "i" released (pCi).

Cz Concentration of radionuclide "i" (pCi/cc) vh 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; (Ci 'Pe '00 '8316.85 '98) (3.3-7a)

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283) 3-25

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Shearon Harris Nuclear Power Plant (SHNPP) August \,994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.3.1 Noble Gases (continued)

Where; Activity of nuclide "i" released (pCi).

Cg Concentration of nuclide "i" (pCi/cc) ~

AP, Change in pressure (psia) of the WGDT (psia psig + 14.7) 600 WGDT volume, (ft~) .

28316.85 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'or 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 time's .the volume released (determined from the flow monitors) the total activity (pCi) of noble gases released are calculated as follows:

Qx Cx 'x (3.3-8)

Where; Q - Total activity (pCi) released from Stack "x".

Cx- 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.

3-26

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.3.1 Noble Gases (continued)

The active.ty (pCi) released for radionuclide "i" equals the radionuclide "i" fraction of the radionuclide mix times the total activity released from Stack "x".

Qx (3.3-8a)

Where; s, (3.3 8b) I and; Sz - The radionuclide "i" fraction of the radionuclide mix Cg The concentration of nuclide "i" in the grab sample (pCi/cc).

ZC< Total activity in grab sample (pCi/cc).

The radionuclide mix is based on the sampling and analysis required by Technical Specification 4.11.2 '.1. If the grab sample activity is ( 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 if the sample shows no detectable activity 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; Q~c "Qi - q~ (3.3-9)

Where; Qz, Total corrected activity of nuclide "i" (pCi) from Stack "x" when batch releases are being made during that time period.

3-27

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Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 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.

3. 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, and projected using the following expression:

Dp~ (Dr ~

p) + D~~ (3.3-10) where:

Dpp the 3 1 Day Proj ected Dose by organ 7 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 batch gas 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 the dose as Additional Anticipated Dose.

To show compliance with Technical Specification 3.11.2.4, the projected month's dose should be compared as in the following:

Dy ~ 0.2 mrad to air for gamma radiation and DP ~ 0.4 mrad to ai'r for beta radiation (3.3-12)

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.

3-28

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Shearon Harris Nuclear Power Plant (SHNPP) August 199<

OfEsite Dose Calculation Manual (ODCM) Rev. 5 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 Eorm 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:

D> = 3.17E-OS Z (Ri [{Mq)v ()i I V

+ (MXq) v qiv )

iM iv iG+R ) [(575) 9 + Wq q j)+

B (3.3-13)

(R M

+ R I + RTV + RTB ) [ (275< QT v

+ (Z7g)v qT ]

v where:

D 7

Dose to any organ r from trit'ium, radioiodines, and particulates, mrem.

(57U) The highest long-term () 500 hr/yr) annual average relative deposition:- 8.8 E-09 m ~ Eor 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).

(57g) The relative deposition factor Eor short term, ground-level vent releases (8 500 hrs/yr), m 2.

See Section 3.0 earlier if using "real" meteorology or use 8.8 E-09 m ~ from Table A-4, Appendix A, for the food and ground plane pathways at the controlling location.

Dose factor for an organ for radionuclide "i" for either the cow milk or goat milk pathway, mrem/yr per pCi/sec per m ~.

3-29

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Shearon Harris Nuclear Power Plant (SHNPP) August 199<

Offsite Dose Calculation Manual (ODCM) Rev. 5 3 .3.2 Radioiodine and Particulates (continued)

R. - Dose factor for an organ for radionuclide "i" for the ground plane exposure pathway, mrem/yr per pCi/sec per m 2.

R. - Dose factor for an organ for radionuclide "i" for the inhalation pathway, mrem/yr per pCi/m~.

iv Dose factor for an organ for radionuclide "i" for the vegetable pathway, mrem/yr per pCi/sec per m ~.

R.

is

- Dose factor for an organ for radionuclide "i" for 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~.

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~.

QT 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 (8 500 -hrs/yr),

@Cia To show compliance with 10CFR50, Equation 3.3-13 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 77Qv and 575v 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 Xjgv and 57gv values from tables in Appendix A are used. For this document,, long-term annual average Xjg and 575 values may be used in lieu of short-term values (see Section 3.0 earlier).

3-30

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.3.2 Radioiodine'and Particulates (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 limiting location, the radionuclide mix of radioiodines and particulates 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.

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 Xjgv and 57@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 X7{} and 57g values for ground-level releases are provided in tables in Appendix A. They may be utilized if an additional special location arises different from those presented in the special locations of Table 3.2-2. A description of the derivation of the'various X/Q and D/Q values is presented in Appendix A.

3-31

Shearon Harris Nuclear Power Plant (SHNPP) Augus- 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.3.2 Radioiodine and Particulates (continued)

Tables 3.3 1 through 3.3 19 present R~ 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:

D~ < 7.5 mrem (3.3-14)

For the calendar year:

Dr < 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.

Projection of Doses Doses resulting from release of radioiodines and particulates will be projected once every 31 days (monthly). The doses will be projected utilizing Equation 3.3-13, and projected using the following expression:

Dpr (Dr p) + Dz~ (3.3-16) where:

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

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.

Der Additional Anticipated Dose for gaseous releases by organ r and quarter of release.

3-32

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.3.2 Radioiodine and Particulates (continued)

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 batch gas 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 the dose as Additional Anticipated Dose.

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)

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.

3-33

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-1 R VALUES FOR THE SHEARON HARRiS NUCLEAR POWER PLANT'GE PATHWAY ~ Ground GROUP M ALL Nuclide ~T. Bod Gl-Tract Bone Liver ~UdBB ~Th raid ~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 4.44E+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 7.49E+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 1.08E+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 3B48E+09 3.48E+09 4.06E+09 Sn-113 1.44E+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 9.15E+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+07 2.00E+07 2.00E+07 2.00E+07 2.34E+07 I-1 31 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 2.09E+07 1-132 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 2.0SE+07 2.05E+07 2.05E+07 2.05E+07 2.0SE+07 2.05E+07 2.05E+07 2.34E+07 Ba-140'e-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 6.95E+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 /JCi/m~ for inhalation and tritium and in units of mrem/yr per /rCi/sec per rn'or all others.

3-34

Shearon Harris Nuclear Power Plant (SHNPP) August 199/d Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-2 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY ~ Veget GROUP ~ Adult Nuclide ~T. Bod Gl-Tract Bone Liver ~Kidllo ~Th roid ~Lun Skin H.3 2.28E+03 2.28E+03 O.OOE+01 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 9.51E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 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+01 O.OOE+01 Rb-86 1.03E+ 08 4.36E+ 07 O.OOE+01 2.21E+ 08 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Sr.89 2.87E+08 1.60E+09 1.00E+10 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE %01 Sr-90 1.64E+1 1 1.93E+10 6.70E+11 O.OOE+01 O.OOE+01 O.OOE+01 O.005+ 01 O.OOE+ 01 Y-91 1.34E+05 2.76E+09 5.01E+06 O.OOE+01 O.OOE+Ol 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+08 4.74E+06 O.OOE+01 1.81E+07 O.OOE+01 O.OOE+01 O.OOE+01 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+Ol 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+07 1.50E+09 2.98E+08 1.11E+08 1.24E+09 1.02E+08 O.OOE+01 O.OOE+01 l-l 31 6.61E+07 3.04E+07 8.07E+07 1.15E+08 1.98E+08 3.785+ 10 O.OOE+01 O.OOE+01 I-132 5.21E+01 2.80E+01 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 I-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+01 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+01 O.OOE+01 O.OOE+01 Hf-181 1.07E+06 7.06E+08 9.51 E+06 5.36E+04 4.48E+04 3.41E+04 O.OOE+01 O.OOE+01

'R Values in units of mrem/yr per yCI/me for inhalation and tritium and in units of mrem/yr per yCI/sec per m'or all others.

3-35

1%

f 4r l

1

'x II

Shearon Harris Nuclear Power Plant (SHNPP) Augus t 199<

Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-3 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'ATHWAY

~ Veget AGE GROUP ~ Teen Nuclide Bod Gl-Tract Bone Liver ~Kidne ~Th roid ~Lun Skin

~T.

H-3 2.61E+03 2.61E+03 O.OOE+ 01 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.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 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.OOE+ 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.OOE+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.OOE+01 2.76E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-89 4.36E+08 1.81E+09 1.52E+10 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 2.05E+11 2.33E+10 8.32E+11 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Y-91 2.06E+05 3.15E+09 7.68E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+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 O.OOE+01 2.39E+07 O.OOE+01 O.OOE+01 O.OOE+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+01 O.OOE+01 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.OOE+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 I-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+01 5.72E+01 5.02E+01 1.31E+02 2.07E+02 4.43E+03 O.OOE+Ol O.OOE+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+Ol I-135 3.49E+04 1.04E+ 05 3.66E+04 9.42E+04 1.49E+05 6.06E+06 O.OOE+01 O.OOE+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.OOE+01 1.44E+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 B.BBE+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.OOE+01 Ce-144 2.71E+06 1.27E+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+08 1.38E+07 7.58E+04 6.32E+04 4.63E+04 O.OOE+01 O.OOE+01 R Vaiues in units of mrem/yr per yCI/m~ for inhalation and tritium and in units of mrem/yr per yCi/sec per m'or all others.

3-36

<r r1 h

~w

Shearon Harris Nuclear Power Plant (SHNPP) August 199/r Offsite Dose Calculation Manual (QDCM) Rev. 5 TABLE 3.3-4 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'ATHWAY Veget AGE GROUP ~ Child ta adda ~T. Bad Gi.T ant B na Liver ~Kidna ~Th raid ~LU Skin H-3 4.04E+03 4.04E+03 O.OOE+Ol 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+01 O.OOE+ 01 O.OOE+ 01 O.OOE+01 Cr-51 1.1 6E+ 05 6.1 5E+ 06 O.OOE+ 01 O.OOE+ 01 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+01 O.OOE+01 O.OOE+01 Co-60 1.11E+09 2.08E+ 09 O.OOE+01 3.76E+08 O.OOE+01 O.OOE+01 O.OOE+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 O.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+01 O.OOE+01 O.OOE+01 O.OOE+Ol 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+07 O.OOE+01 3.84E+07 O.OOE+01 O.OOE+01 O.OOE+01 Ru-106 9.38E+07 1.17E+10 7.52E+08 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+01 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 1.55E+ 08 1.22E+ 09 9.98E+08 2.79E+08 2.93E+ 09 3.22E+08 O.OOE+ 01 O.OOE+ 01 1-131 8.16E+07 1.23E+07 1.43E+08 1A4E+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 l-135 5.54E+04 8.92E+04 6.50E+04 1.17E+05 1.79E+05 1.04E+07 O.OOE+Ol 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 Cs-136 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 8a.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 4.75E+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 mrem/yr per /TCI/m~ for inhalation and tritium and in units of mrem/yr per /rCI/sec per m'or all others.

3-37

Shearon Harris Nuclear Po~er Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-5 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY Meat GROUP ~ Adult GI.T at Bone Liver ~Kidne ~Th roid ~Lun Skin Nuclide ~T. Bod 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 3.43E+08 3.05E+09 1.89E+08 O.OOE+01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 P-32 1.18E+08 Cr-51 4.27E+03 1.08E+ 06 O.OOE+ 01 O.OOE+ 01 9a42E+ 02 2.56E+03 5.67E+03 O.OOE+ 01 1.71E+07 O.OOE+01 5.57E+06 1.66E+06 O.OOE+01 O.OOE+01 O.OOE+01 Mn.54 1.06E+ 06 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 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.58 1.03E+08 8.76E+08 O.OOE+01 4.66E+07 O.OOE+01 O.OOE+01 O.OOE+ 01 O.OOE+01 Co 60 3.58E+08 4.98E+08 2.49E+08 7.91E+08 5.29E+08 O.OOE+01 O.OOE+01 O.OOE+01 Zn 65 Rb-86 1.42E+ 08 6.00E+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+08 O.OOE+01 O.OOE+01 O.OOE+ 01 O.OOE+ 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 1.80E+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 7.58E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 2.72E+07 7.38E+09 6.32E+07 O.OOE+01 2.41E+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 a 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+08 2.97E+07 1.15E+06 8.40E+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+Ol 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 7.40E+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 1-135 6.07E-17 1.86E-16 6.28E-17 1.64E-16 2.64E-16 1.08E-14 O.OOE+01 "O.OOE j01 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 j08 1.47E+07 5.57E+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 3.66E+05 2.17E+ 05 O.OOE+01 O.OOE+01 O.OOE+01 Hf-181 1.52E+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 yCi/m'or inhalation and tritium and in units of mrem/yr per yCi/sec per m'~ for all others.

3-38

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-6 R VALUES FOR THE SHEARON HARRlS NUCLEAR POWER PLANT'GE PATHWAY ~ Meat GROUP ~ Teen Nuclide ~T. Bod GI.Traat Bone Liver ~Kidne ~Th roid ~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.OOE+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.OOE+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+Ol 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 Sr-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+08 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 5.79E+05 O.OOE+01 O.OOE+01 O.OOE+ 01 Ru-103 2.20E+07 4.30E+09 5.15E+07 O.OOE+01 1.82E+08 O.OOE+01 O.OOE+01 O.OOE+01 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 a 1.86E+06 8.59E+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 8.80E+05 6.19E+05 2.88E+05 O.OOE+01 O.OOE+01 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.OOE+01 Te-129M 9.81E+07 2.33E+09 6.20E+08 2.30E+08 2.59E+09 2.00E+08 O.OOE+01 O.OOE+Ol I-1 31 4.40E+06 1.62E+06 5.85E+06 8.20E+06 1.41E+07 2.39E+09 O.OOE+01 O.OOE+01 1-133 1.23E-01 3.06E-01 2.39E-01 4.05E-01 7.10E-01 5.65E+01 O.OOE+01 O.OOE+01 I-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+01 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 2.34E+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.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 mt for all others.

3-39

t Lt

~w

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3.7 R VALUES FOR THE SHEARON HARRiS NUCLEAR POWER PLANT PATHWAY ~ Meat AGE GROUP ~ Child Gl-Treot Bone Liver ~Kidne ~Th roid ~Lun Skin Nuclide ~T. Bod 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 1.87E+08 1.34E+08 4.86E+09 2.27E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 P-32 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 1.30E+06 4.08E+06 O.OOE+01 4.86E+06 1.36E+06 O.OOE+01 O.OOE+01 O.OOE+01 Mn 54 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+01 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 3.125+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+01 O.OOE+01 O.OOE+01 Ru-106 3.43E+08 4.27E+10 2.75E+09 O.OOE+01 3.71E+09 O.OOE+Ol 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.OOE+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+Ol 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+01 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 I-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 l-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 I-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 t 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 2.80Ee07 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+Ol O.OOE+01 O.OOE+01 Ce-144 7.42E+04 1.14E+08 1.39E+06 4.36E+05 2.41E+05 O.OOE+01 O.OOE+01 O.OOE+01 Hf-181 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 in units of mrem/yr per /rCi/m'or inhalation and tritium end in units of mrem/yr per /rCi/sec per m't for all others.

3-40

V '

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-8 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY ~ Cow Milk GROUP ~ Adult Nuclide ~T. Bod Gl-Tract Bone Liver ~IGd e ~Th aid ~Lun Skin H-3 7.69E+02 7.69E+02 O.OOE+01 7.69E+02 7.69E+02 7.69E+02 7.69E+02 7.69E+02 P-32 4.32E+08 1.26E+09 1.12E+10 6.95E+08 O.OOE+01 O.OOE+Ol O.OOE+Ol O.OOE+01 Cr-51 1.73E+04 4.36E+06 O.OOE+01 O.OOE+Ol 3.82E+03 1.04E+04 2.30E+04 O.OOE+01 Mn.54 9.76E+ 05 1.57E+ 07 O.OOE+ 01 5.1 1E+ 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 2.80E+06 O.OOE+01 0.00E+Ol 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 Sr-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+01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Y-91 1.37E+ 02 2.81 E+ 06 5.1 1E+ 03 O.OOE+ 01 O.OOE+01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 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+01 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.OOE+Ol 2.33E+03 O.OOE+01 O.OOE+01 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 3.44E+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+01 O.OOE+01 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 I-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 1.03E+01 5.51E.02 1.10E+01 2.93E+01 4.67E+01 1.03E+01 O.OOE+01 O.OOE+01 1-133 1.40E+06 4.13E+06 2.64E+06 4.59E+06 8.01E+06 6.75E+08 O.OOE+01 O.OOE+01 l-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 6.71E+09 1A4E+08 3A5E+09 3.21E+09 2.66E+09 O.OOE+01 8.82E+08 O.OOE+01 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 6.44E+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 7.26E+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 5.91 E+ 03 3.33E+ 01 2.79E+ 01 2.12E+01 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 /ICI/sec per m'~ for all others.

3-41

Shearon Harris Nuclear Power Plant (SHNPP) august 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-9 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER

~ Cow Milk AGE GROUP I Teen PLANT'ATHWAY Nuclide ~T. Bod Gl-Tract Bone Liver ~Kid e ~Th old ~Lun Skin 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 8.00E+08 1.73E+09 2.06E+10 1.28E+09 O.OOE+01 O.OOE+01 O.OOE+Ol 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 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.005+ 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 O.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+01 O.OOE+01 Sb-124 1.08E+07 5.56E+08 2.76E+07 5.08E+05 O.OOE+01 6.26E+04 2.41E+07 O.OOE+01 Te.127M 7.39E+06 1.55E+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 1-131 2.65E+08 9.75E+07 3.52E+08 4.93E+08 8.485+08 1.44E+11 O.OOE+01 O.OOE+01 1-132 1.83E+01 2.22E+01 1.94E+01 5.09E+01 8.02E+01 1.71E+Ol O.OOE+01 O.OOE+01 I ~ 133 2.49E+06 6.19E+06 4.82E+06 8.185+06 1.43E+07 1.14E+09 O.OOE+01 O.OOE+01 l-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 yCi/ms for inhalation and tritium and in units of mrem/yr per yCi/sec per m'or all others.

3-42

~I Fl

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-10 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT PATHWAY ~ Cow Milk AGE GROUP ~ Child Nuclide ~T. Bod GI-Tract Bone Liver ~rddhe ~Th rdd ~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+ 01 O.OOE+01 3.37E+07 O.OOE+01 Co-58 2.21E+07 4.20E+07 O.OOE+01 7.21E+06 O.OOE+01 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 O.OOE+01 5.47E+09 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ Ol Sr-89 1.13E+08 1.54E+08 3.97E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 1.87E+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+Ol 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 1.44E+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 1-132 3.89E+01 9.95E+01 4.60E+01 8.45E+01 1.29E+00 3.92E+01 O.OOE+01 O.OOE+01 l-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+01 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 2.51E+04 9.79E+01 7.86E+01 8.24E+01 O.OOE+01 O.OOE+01

'R Values in units of mrem/yr per /rCi/m3 for inhalation and tritium and in units of mrem/yr per /ICi/sec per m'~ for all others.

3-43

4i Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3.11 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY ~ Cow Milk GROUP ~ Infant Nuclide ~T. Bod GI.Tract Bone Liver ~tdd a ~Th crd Lunco Skin 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 6.17E+09 O.OOE+01 0 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 5.37E+06 8.71E+06 O.OOE+01 2.37E+07 5.25E+06 O.OOE+01 O.OOE+01 O.OOE+Ol 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 Co-58 3.60E+07 3.59E+07 O.OOE+01 1.44E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Co-60 1.29E+08 1.30E+08 O.OOE+01 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.OOE+ 01 O.OOE+ 01 O.OOE+01 Sr.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 Sr-90 2.05E+ 10 1.00E+09 8.04E+10 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+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 1.05E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 1.74E+03 6.33E+04 5.21E+03 O.OOE+01 1.08E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ru-106 1.47E+04 8.95E+05 1.18E+05 O.OOE+01 1.39E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 1.19E+08 9.32E+09 2.46E+08 1.80E+08 2.57E+08 O.OOE+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+05 7.88E+07 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+01 Te-129M 5.57E+07 2.16E+08 3.62E+08 1.24E+08 9.05E+08 1.39E+08 O.OOE+01 O.OOE+01 I-1 31 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 1.57E-OO 9.55E+ 01 1.94E+ 00 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 I-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+09 1.13E+08 2.23E+10 4.15E+10 1.07E+10 O.OOE+01 4.38E+09 O.OOE+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.OOE+01 4.18E+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+01 O.OOE+01 O.OOE+01 Ce-'l44 7.82E+ 04 8.01E+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 pCI/m~ for inhalation and tritium and in units of mrern/yr per /rCI/sec per m'or all others.

3-44

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-12 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT PATHWAY ~ Goat Milk AGE GROUP ~ Adult Nuclide ~T. Bod Gl-Tract Bone Liver ~Kidhe T~htdd ~Lun 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.OOE+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+ 01 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+ 01 1.94E+08 O.OOE+01 O.OOE+01 O.OOE+ 01 O.OOE+01 Sr.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+Ol O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 1.46E+01 6.85E+04 6.74E+ 01 2.16E+01 3.39E+01 0.00E+01 O.OOE+01 O.OOE+Ol 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+ 01 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 1.90E+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 1.96E+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+01 O.OOE+01 O.OOE+01 I-133 1.68E+06 4.95E+06 3.17Et06 5.51E+06 9.61E+06 8.10E+ 08 O.OOE+01 O.OOE+01 I-135 1.08E+04 3.32E+04 1.12E+04 2.94E+04 4.71E+04 1.94E+06 O.OOE+01 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 1.48E+03 O.OOE+01 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 yCi/m3 for inhalation and tritium and in units of mrem/yr per yCi/sec per m'or all others.

3-45

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3.13 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'ATHWAY

~ Goat Milk AGE GROUP ~ Teen Nuclide Bod Gl-Tract Bone Liver ~Kidne ~Th roid ~Lun Skin

~T.

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.OOE+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+01 Co-58 1.30E+ 06 7.80E+06 O.OOE+01 5.66E+05 O.OOE+Ol O.OOE+01 O.OOE+01 O.OOE+Ol 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+01 O.OOE+01 Rb-86 1.66E+08 5.24E+07 O.OOE+Ol 3.54E+08 O.OOE+01 O.OOE+01 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+01 O.OOE+01 Sr-90 2.27E+10 2.58E+09 9.18E+ 10 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Y-91 3.02E+01 4.62E+05 1.13E+03 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 2.56E+01 8.59E+04 1.18E+02 3.72E+01 5.47E+01 O.OOE+01 O.OOE+01 O.OOE+01 Nb.95 3.09E+03 2.40E+07 1.01E+04 5.62E+03 5.45E+03 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 5.58E+01 1.09E+04 1.30E+02 O.OOE+01 4.60E+02 O.OOE+01 O.OOE+01 O.OOE+01 Ru-106 3.51E+02 1.34E+05 2.79E+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 6.97E+06 1.33E+07 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 2.28E+05 2.58E+06 2.15E+05 9.06E+03 6.37E+03 2.97E+03 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.OOE+01 Te-127M 8.87E+05 1.86E+07 7.46E+06 2.65E+06 3.02E+07 1.77E+06 O.OOE+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 1-131 3.18E+08 1.17E+08 4.22E+08 5.91E+08 1.02E+09 1.73E+11 O.OOE+01 O.OOE+01 l-132 2.19E+01 2.66E+01 2.33E+01 6.1 1E+ 01 9.62E+ 01 2.06E+ 01 O.OOE+ 01 O.OOE+01 l-133 2.99E+06 7.43E+06 5.79E+06 9.81E+06 1.72E+07 1.37E+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 5.26E+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+01 Cs-137 1.19E+10 4.85E+08 2.56E+10 3.41E+10 1.16E+10 O.OOE+01 4.51E+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.005+ 01 O.OOE+01 O.OOE+01 Ce-144 2.55E+03 1.19E+07 4.74E+04 1.96E+04 1.17E+04 O.OOE+Ol O.OOE+01 O.OOE+01 Hf-181 1.41E+02 6.34E+04 1.27E+03 6.97E+00 5.80E+00 4.26E+00 O.OOE+01 O.OOE+01

'R Values in units of mrem/yr per /rCI/m~ for inhalation and tritium end in units of mrem/yr per yCI/sec per m't for all others.

3-46

yf

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-14 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'ATHWAY

~ Goat Milk AGE GROUP ~ Child Nuclide ~T. Bod Gl-Tract Bone Liver ~Kd o ~Th roid ~Lun Skin H-3 3.23E+03 3.23E+ 03 O.OOE+01 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.OOE+Ol O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 7.40E+03 3.93E+05 O.OOE+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.OOE+01 O.OOE+01 4.38E+05 O.OOE+01 Co-58 2.65E+06 5.05E+06 O.OOE+01 8.65E+05 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+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.OOE+01 Zn 65 5.74E+08 1.62E+08 3.47E+08 9.24E+08 5.82E+08 O.OOE+01 O.OOE+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.OOE+01 O.OOE+01 Sr-89 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.OOE+01 O.OOE+Ol O.OOE+01 Y-91 7.45E+01 3.71E+05 2.79E+03 O.OOE+01 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+Ol 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 O.OOE+01 O.OOE+01 Ru-103 1.19E+02 7.98E+03 3.09E+02 O.OOE+01 7.77E+02 O.OOE+01 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+01 O.OOE+01 Ag-110M 8.63E+06 1.28E+09 1.60E+07 1.08E+07 2.01E+07 O.OOE+01 O.OOE+01 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.OOE+01 I-l 31 5.85E+08 9.17E+07 1.02E+09 1.03E+09 1.69E+09 3.41E+11 O.OOE+01 O.OOE+01 I-132 4.67E+01 1.19E+00 5.52E+01 1.01E+00 1.55E+00 4.71E+01 O.OOE+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.OOE+Ol O.OOE+01 I-1 35 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 2.1,],E+ 10 O.OOE'+ 01 7.56E+09 O.OOE+01 Cs-136 3.41E+09 1.85E+08 1.92E+09 5.27E+09 2.81E+09 O.OOE+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 Ba-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+03 9.55E+06 1.17E+05 3.66E+04 2.03E+04 O.OOE+01 O.OOE+01 O.OOE+01 Hf-181 3.04E+02 4.99E+04 3.02E+03 1.17E+01 9.43E+00 9.88E+00 O.OOE+01 O.OOE+01 R Values in units of mrem/yr per yCi/ms for inhalation and tritium and in units of mrem/yr per yCi/sec per m'or all others.

3-47

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-15 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'ATHWAY

~ Goat Milk AGE GROUP ~ Infant Nuclide ~T. Bod Gl-Tract Bone Liver ~Kid o ~Th roid luncu Skin H-3 4.90E+03 4.90E+03 O.OOE+Ol 4.90E+03 4.90E+03 4.90E+03 4.90E+ 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+01 O.OOE+01 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+01 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+01 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+08 3.26E+08 1.59E+10 O.OOE+01 O.OOE+Ol 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+01 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+Ol 5.90E+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 4.27E+04 1.76E+04 1.26E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 2.09E+02 7.60E+03 6.25E+02 O.OOE+01 1.30E+03 O.OOE+01 O.OOE+01 O.OOE+01 Ru-106 1.77E+03 1.07E+05 1.41E+04 O.OOE+01 1.67E+04 O.OOE+01 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+01 O.OOE+01 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+01 O.OOE+01 Te-129M 6.69E+ 06 2.59E+07 4.34E+07 1.49E+07 1.09E+08 1.67E+07 O.OOE+01 O.OOE+01 I-131 1.11E+09 8.99E+07 2.14E+ 09 2.52E+ 09 2.94E+09 8.28E+ 11 O.OOE+ 01 O.OOE+ 01 l-132 8.28E+01 1.88E+00 1.15E+00 2.33E+00 2.59E+ 00 1.09E+02 O.OOE+01 O.OOE+Ol I-133 1.27E+07 7.31E+06 2.97E+07 4.32E+07 5.08E+07 7.86E+ 09 O.OOE+ 01 O.OOE+ 01 I-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 '.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 3r75E+09 1.10E+10 4.39E+09 O.OOE+01 h 8.98E+08 O.OOE+01 Cs-137 8.17E+09 3.61E+08 9.85E+ 10 1.15E+11 3.10E+10 O.OOE+01 1.25E+ 10 O.OOE+01 Ba-140 9.50E+05 4.53E+06 1.84E+07 1.84E+04 4.38E+03 O.OOE+01 1.13E+04 0.00E+01 Ce-141 2.24E+02 9.85E+05 3.13E+03 1.91E+03 5.88E+02 O.OOE+01 O.OOE+01 O.OOE+01 Ce-144 9.39E+03 9.61E+06 1.67E+05 6.86E+04 2.77E+04 O.OOE+01 O.OOE+01 O.OOE+Ol Hf-181 5.08E+02 4.72E+04 5.74E+03 2.71E+01 1.58E+01 2.30E+ 01 O.OOE+ 01 O.OOE+ 01 R Values in units of mrem/yr per /rCI/m3 for inhalation and tritium and in units of mrem/yr per /rCI/sec per m't for all others.

3-48

t Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-16 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'ATHWAY

~ Inhal AGE GROUP ~ Adult Nuclide ~T. Bod Gl-Tract Bone Liver ~Kidne ~Th old ~Lun Skin 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+01 3.32E+03 O.OOE+01 O.OOE+01 2.28E+01 5.94E+01 1.44E+04 O.OOE+01 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.OOE+01 Co-58 2.07E+03 1.06E+05 O.OOE+01 1.58E+03 O.OOE+01 O.OOE+01 9.27E+05 O.OOE+01 Co.60 1.48E+04 2.84E+05 O.OOE+01 1.15E+04 O.OOE+01 O.OOE+01 5.96E+06 O.OOE+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+01 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 Sr-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.OOE+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+01 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 1.10E+05 1.53E+03 O.OOE+01 5.82E+03 O.OOE+01 5.04E+05 O.OOE+01 Ru-106 8.71E+03 9.11E+05 6.90E+04 O.OOE+01 1.33E+05 O.OOE+01 9.35E+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+01 Sb-124 1.24E+04 4.06E+05 3.12E+04 5.88E+02 O.OOE+01 7.55E+01 2.48E+06 O.OOE+01 Te-127M 1.57E+03 1.49E+05 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 3.44E+03 1.16E+06 O.OOE+01 I-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 I-1 32 1.16E+03 4.06E+02 1.16E+03 3.25E+03 5.18E+03 1.14E+05 O.OOE+01 O.OOE+01 l-1 33 4.51E+03 8.87E+03 8.63E+03 1.48E+04 2.58E+04 2.15E+06 O.OOE+01 O.OOE+01 l-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+Ol Cs-136 1.10E+05 1.17E+04 3.90E+04 1.46E+05 8.55E+04 O.OOE+01 1.20E+04 O.OOE+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 Ba-140 2.56E+03 2.18E+05 3.90E+04 4.90E+Ol 1.67E+01 O.OOE+01 1.27E+06 O.OOE+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 8.15E+05 3.43E+06 1.43E+06 8.47E+05 O.OOE+01 7.76E+06 O.OOE+01 Hf-181 5.16E+03 1.29E+05 4.56E+04 2.57E+02 2.15E+02 1.63E+02 5.99E+05 O.OOE+01

'R Values in units of mrem/yr per /rCI/m'or inhalation and tritium and in units of mrem/yr per /rCI/sec per m'or all others.

3-49

t%

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-17 R VALUES FOR THE SHEARQN HARRIS NUCLEAR POWER PLANT PATHWAY ~ Inhai AGE GROUP ~ Teen Nuclide ~T. Bod Gl-Tract Bone Liver ~lddee T~heeld ~Lun Skin 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.OOE+01 O.OOE+01 O.OOE+01 O.OOE+Ol 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.OOE+01 1.51E+04 O.OOE+01 O.OOE+01 8.7'I E+06 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.OOE+01 Rb.86 8.39E+04 1.77E+04 O.OOE+01 1.90E+05 O.OOE+01 O,OOE+01 O.OOE+01 O.OOE+01 Sr-89 1.25E+04 3.71E+05 4.34E+05 O.OOE+01 O.OOE+01 O.OOE+01 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.OOE+ 01 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+01 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-103 8.95E+02 1.09E+05 2.10E+03 O.OOE+01 7.42E+03 O.OOE+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.OOE+01 1.61E+07 O.OOE+01 Ag-110M 7.98E+03 2.72E+05 1.38E+04 1.31E+04 2.50E+04 O.OOE+01 6.74E+06 O.OOE+01 Sn-113 8.68E+03 2.03E+04 8.19E+03 3.44E+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.OOE+01 9.76E+01 3.85E+06 O.OOE+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+04 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.OOE+01 1-133 6.21E+03 1.03E+04 1.21E+04 2.05E+04 3.59E+04 2.92E+06 O.OOE+01 O.OOE+01 I-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+01 Ba-140 3.51E+03 2.28E+05 5.46E+04 6.69E+01 2.28E+Ol O.OOE'+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.OOE+01 Ce-144 2.62E+05 8.63E+05 4.88E+06 2.02E+06 1.21E+06 O.OOE+01 1.33E+07 O.OOE+01 Hfe181 7.04E+03 1.20E+05 6.32E+04 3.48E+02 2.90E+02 2.12E+02 9.39E+05 O.OOE+01 R Values in units of mrem/yr per /rCI/m'or inhalation and tritium and in units of mrem/yr per /rCI/sec per m'or all others.

3-50

8

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Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-18 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY ~ Inhal GROUP ~ Child Nuclide ~T. Bod Gl-Tract Bone Liver ~Kid o ~Th roid ~Lun Skin 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+01 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 3.346+04 O.OOE+01 O.OOE+Ol 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+Ol 1.10E+06 O.OOE+01 Co-60 2.26E+04 9.61E+04 O.OOE+01 1.31E+04 O.OOE+01 O.OOE+Ol 7.06E+06 O.OOE+01 Zn-65 7.02E+04 1.63E+04 4.25E+04 1.13E+05 7.13E+04 O.OOE+01 9.94E+05 0.006+01 Rb-86 1.14E+05 7.98E+03 O.OOE+01 1.98E+05 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+ 01 Sr-89 1.72E+04 1.67E+05 5.996+05 O.OOE+01 O.OOE+01 O.OOE+01 2.15E+06 O.OOE+01 Sr-90 6.43E+06 3.43E+05 1.01E+08 O.OOE+01 O.OOE+01 0.006+01 1.47E+07 0.006+01 Y-91 2.43E+04 1.84E+05 9.13E+05 O.OOE+01 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+Ol Nb-95 6.54E+ 03 3.69E+04 2.356+04 9.166+03 &.61E+03 0.006+01 6.13E+05 O.OOE+Ol Ru-103 1.07E+03 4.47E+ 04 2.79E+ 03 0.006+01 7.02E+ 03 O.OOE+ 01 6.61E+05 O.OOE+01 Ru-106 1.69E+04 4.296+05 1.366+05 O.OOE+01 1.84E+05 0.006+01 1.43E+07 O.OOE+01 Ago110M 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 9.836+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 1.646+05 5.736+04 7.40E+02 O.OOE+ 01 1.266+02 3.24E+06 O.OOE+01 Te-127M 3.016+ 03 7.13E+04 2.48E+04 8.53E+03 6.35E+04 6.06E+03 1.48E+06 O.OOE+01 Te-129M 3.046+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+01 O.OOE+01 I-132 1.87E+03 3.20E+03 2.11E+03 4.06E+03 6.24E+03 1.93E+05 O.OOE+Ol O.OOE+01 I-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 Ba-140 4.32E+03 1.02E+05 7.39E+04 6.47E +01 2.11E+01 O.OOE+01 1.74E+06 O.OOE+ 01 Ce-141 2.89E+03 5.65E+04 3.92E+04 1.95E+04 8.53E+ 03 O.OOE+01 5o43E+05 O.OOE+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 8.44E+04 3.28E+02 2.64E+02 2.76E+02 7.95E+05 O.OOE+Ol R Values in units of mrem/yr per /rCI/m~ for inhalation and tritium and inunits of mrem/yr per /rCI/sec per m'~ for all others.

3-51

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4 41

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-19 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY ~ Inhal GROUP ~ Infant Nuclide ~T. Bod Gl-Tract Bone Liver ~Kidllo ~Th roid Luncu Skin 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 O.OOE+Ol O.OOE+01 O.OOE+01 O.OOE+Ol Cr-51 8.93E+01 3.56E+02 O.OOE+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.OOE+01 2.53E+04 4.98E+03 O.OOE+01 9.98E+ 05 O.OOE+ 01 Fe-59 9.46E+03 2.47E+04 1.35E+04 2.35E+04 O.OOE+01 O.OOE+01 1.01E+06 O.OOE+01 Co-58 1.82E+03 1.11E+04 O.OOE+01 1.22E+03 O.OOE+01 O.OOE+01 7.76E+05 O.OOE+01 Co.60 1.18E+04 3.19E+04 O.OOE+01 8.01E+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+01 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 Sr-89 1.14E+04 6.39E+04 3.97E+05 O.OOE+01 O.OOE+01 O.OOE+01 2.03E+06 O.OOE+01 Sr-90 2.59E+06 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 Zr-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+01 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 404 1.64E+05 8.67E+04 O.OOE+01 1.06E+05 O.OOE+01 1.15E+07 O.OOE+01 A9-110M 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+Ol 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 I-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 1-132 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 1-135 2.77E+03 1.83E+03 3.86E+03 7.59E+03 8.46E+03 6.95E+05 O.OOE+01 O.OOE+01 Cs-134 7.44E+04 1.33E+03 3.96E+05 7.02E+05 1.90E+05 O.OOE+01 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 6.1 1E+05 1.72E+05 O.OOE+01 7.12E+04 O.OOE+01 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 2.15E+04 2.77E+04 1.66E+04 5.24E+03 O.OOE+01 5.16E+05 O.OOE+01 Ce-144 1.76E+05 1.48E+05 3.19E+06 1.21E+06 5.37E+05 O.OOE+01 9.83E+06 O.OOE+01 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 /rCI/m~ for inhalation and tritium and in units of mrem/yr per /rCI/sec per m'or all others.

3-52

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Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 Figure 3.1 SHNPP Gaseous Waste Streams BKM-6JOIAnON 677LVOII MenrOB vPB IIASIK PAOCKSSIHC BLOC RAB RKACIOII AVXBIAIIYBIOC INB fVKL NACXPIO BLOC r6IQI 760K RAHCC CAS MOIOIOII TURBINE BLDG VENT STACK 3A RM RM IIV 5556 I (>ROM)

ROI IIV 5551 RKM CONDENSER POI. AREA CONDENSER VACUUM PUMP WASTE PROCESSING BLDG VENT STACK 5 RM REM REM IWV 5516 AMI WV 5516 I (1610M)

WPB HOT Ic COLO LAUNDRY WPB OfflCE AREA EXHAUST WPB COLD LAUNDRY DRYEAS WPB COHTROL ROON SMOKE EXHAUST WPB OFFICE AREA WPB GENERAL AREA EXHAUST WPB CHILLOI ROOM EXHAUST WASTE CAS DECAY TANKS WASTE PROCESSINC AREAS FILTGIEO EXHAUST WASTE, ISROCESSING BLDG VENT STACK 5A RM AEM RKN IwV 5517 RM IWJ 5567 I (r610'4)

WPB SWITQICEAR ROOM EXHAVST WPB HVAC EQUIP. ROOM EXHAVST WPB PERSONNEL HANDUNC FAQLIIY KXHAVST WPB HOf Ic LOW ACTI'41TY EXHAUST WPB LAB AREA EXHAUST PLANT VENT STACK I RJI 11AV 5506 ISA 7610M)

RN RKM REM-IAV 5506A RKM-ILT-55016 AEM CCNTABIMQIT PRE ENTRY PURCE FHB NORMAL EXHAUST NORIH ROI-ILT-SSSI REM RAB NORMAL KXNAVST fHB NORMAL EXHAUST SOUTH ROI IAV SSS1A REM RKll REM IR 5506 FHB NORMAL EXHAUST (OPER. FL) SOUTH AAB EMERCKNCY EXHAUSf IIKM IAv-5552B REM REM RIM IR 5507 f119 NORMAL EXHAUST (OPER. FL) SOUTH RAB VENTILATION SYSTEM AEM RQt IFL 55066 SA HYDAOCKN PVRCE AAB SMOKK PURGE AKM REM IFL 5506B SB flIB EMERGENCY EXHAUST RAB PVACE 3-53

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Offsite Dose Calculation Manual (ODCM) Rev. 5 Figure 3.3 SHNPP Condenser Off-Gas System IUnOINf 8LOC IIM IIV.SS Os I (WnGQ VfNl SIACK ~ SA GLANO Slfh<<

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Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table 4.1 contains the sam P le P oint ti descri p on, 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.

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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: 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 11 SHNPP site ~

S sector, 0.6 mi. 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 mi. 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.

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.

H 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: 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 Formerly 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 Q 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' mi. from site.

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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 63 SHNPP Site.

SW sector, 0.6 mi. from site.

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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, Surface Water Sampling and Collection Frequency: Composite sample~ collected over a period of less than or equal to 31 days.

Analysis Frequency and Required Analysis: Monthly Gross Beta~ and Quarterly Gamma Isotopic Sample Point ID No. Sample Point, Description~, .Distance, and Direction 26 Harris Lake Spillway S sector, 4.7 mi. from site 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.

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE A. I RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Pathway and/or Sample: Waterborne, Groundwater Sampling and Collection Frequency: Grab sample collected quarterly Analysis Frequency and Required Analysis: Each Sample Gamma Isotopic~ and Tritium Sample Point ID No. Sample Point, Description~, Distance, and Direction On-site deep well in the vicinity of the diabase dike SSW sector, 0.7 mi. from'site 57 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 ' mi. from site

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Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4.1 RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Path~ay 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 doses calculated for the consumption of the water is greater;than 1 mrem per yr.

Monthly Gross Beta Monthly Gamma Isotopic~

Quarterly Tritium Sample Point ID No. Sample Point, Description~, Distance, and Direction 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.

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

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 Harris Lake Spillway S sector, 4.6 mi. from site 41 Shoreline of Mixing Zone of Cooling Tower Blowdown Line S sector, 3.8 miles from site.

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.

TABLE A.l 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 ID NQ. Sampl'e Point, Description~, Distance, and Direction 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

Pie his 1

1'

Shearon Harris nuclear Power Plan" (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE A.L RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Pathway and/or Sample: Ingestion - Fish Sampling and Collection Frequency: One sample of each of the following semiannually:

Catfish (bottom feeders)

Sunfish & Largemouth Bass (free swimmers)

Analysis Frequency and Required. Analysis: Each sample - Gamma Isotopic~ on edible portion for each Sample Point ID No. Sample Point, Description~, Distance, and Direction Site varies within the Harris Lake.

45 Site varies above Buckhorn Dam on Cape Fear River (Control Station)

g;s 2I

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

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 4

5 Pittsboro (Control Station)

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

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Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 NOTES TO TABLE 4.1 SHNPP Ra'diplo 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. Xf 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.

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

4, 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 19&& 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 OIX IE I'ICE LINE I

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zo 4 (g

% gp EXCLUSION BOUNOAIIY SCALE IN FEET

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

Figure 4.1-2 Environmental Radiological Sampling Points I ~ Its Vs'0

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Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Figure 4.1-4 Environmental Radiological Sampling Points t

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Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) 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 4.1A 34 TL 4.1-3 AP, AC, TL TL 4.1-3 TL 4.1-4 36 TL 4.1-3 AP, AC, TL 4.1% 37 TL 4.1-3 AP, AC, MK, FC, TL 38 SW, DW 4.1-2 TL GW 4.1<

TL 4.1-4 40 SW, DW 4.1-3 TL SS, AV

'.1-3 9 TL 42 MK 10 TL 4.1% 43 MK 4.1 A TL 4.1-4 FH TL 4.1 A 45 FH 4.1-2 13 TL 4.1A 47 AP, AC 4.1<

TL 4.1-4 48 TL 4.1-3 15 TL 4.1A 49 TL 4.1<

16 TL 4.1-4 50 TL 4.1A TL 4.1A 51 DW 18 TL 4.1A 52 SD 4.1%

19 TL 4.1-3 53 TL 4.1-2 20 TL 4.1-3, 4.14 54 FC 4.1-4 21 TL 4.1-3 55 FC 4.1 A 22 TL 4.1-3 56 TL TL 4.1-3 GW 24 TL 4.1-3 58 GW 25 TL 4.1-3, 4.14 59 GW 4.1-4 26 Ap, Ac, Av, ss. Sw, TL 4.1-3, 4.1% 60 GW 27 TL 4.1-2, 4.14 61 AV 4.1-3 28 TL 4.1-2, 4.1-4 62 FC 4.1%

29 TL 4.1-2 TL 4.1%

30 TL 4.1-2 31 TL 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

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 5.0 INTERIABORATORY COMPARISON STUDIES The ob]ective 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 CP&L laboratory than three 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

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

- 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 is a significant direct radiation component at the TLD location Xn the sector containing the likely most exposed member the public then this dose will be added to the doses from effluent of pathways derived from LADTAP II and GASPAR.

6-1

ytl f

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 Boundaror The.Radzoactive Effluent Release Report to be submitted wx.than 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).

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.

4' f

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 7.0 LICENSEE-INITIATED CHANGES TO THE ODCM Pursuant to Technical Specification 6.14.2, licensee initiated changes to the Offsite Dose Calculation Manual:

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) Doc'umentation of the fact that the change has been reviewed and found acceptable by the PNSC.

Shall become effective upon review and acceptance by the PNSC.

7-1

4 P'P k

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~

Shearon Harris Nuclear Power Plant (SHNPP) 1994 'une Offsite Dose Calculation Manual (ODCM) Rev. 4 Sheet 1 of 3 APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS 4

Carolina Power & 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 1.111 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 ~XO ~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.

4

t ll

~

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

0 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.

A-3.

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE A-l THROUGH A-4 USNRC COMPUTER CODE XOQDOQ, VERSION 2.0 RVN DATE: 06/23/94 RUK TZHE: 08:46:27 XOQDOQ SHNPP CROUND-LEVEL HISTORICAL DATA, 1976 1987 EXIT ONE - GROUND-LEVEL HISTORZCAL DATA, 1976-1987 CORRECTED USING STANDARD OPEN TER RAZK FACTORS Table Table Table Table SPECIFIC POINTS OF INTEREST A-1 'A-2 A-3 A-4 RELEASE TYPE OF . DZRKCTZOH DISTANCE X/Q X/Q X/Q D/Q ID LOCATION FROH SZ TE (MILES) (METERS) (SEC/CVB.METER) (SEC/CUB.HETER) (SEC/CUB.HETER) (PER SQ.HETER)

No 2.300 OAY DECAY S.OOO OAY OECAY c

DEPLETED DEPLETED DEPLETED A SITE BOUNDARY S 1.36 2189. 6. 1E-06 5.9E-O6 5.2E-06 8.8E G9 A SITE BOUNDARY SSW ~

1. 33 2140. 6. GE-06 5.8E-G6 5. 1E-G6 8.7E 09 A SITE BOUNDARY SM 1.33 2140. 5.5E-06 5.4E-06 4.7E-06 7.0E-G9 A SITE BOUNDARY MSM 1. 33 2140. 4. 8E-06 4.7E>>86 4. 1E-06 5.4'E-09 A SITE BOUNDARY 1. 33 2140. 3. 6E-06 3.6E-06 3.1E G6 4. 1E-09 A SITE BOUNDARY MNM 1 ~ 33 2140. 2. BE-06 2.7E-O6 2.4E 06 3.3E 09 A SITE BOUNDARY NM 1.26 2G28. 2.9E-O6 2.8E-06 2.5E-06 3.9E-O9 A SITE BOUNDARY NNM 1.26 2028. 3.3E-06 3.2E-06 2.8E-O6 5,1E 09 A SITE BOUNDARY N 1.32 2124. 3.8E-06 3.8E-06 3.3E-06 6.6E-09 A SITE BOUNDARY NNE 1.33 2140. 4.1E-06 AGE-06 3.5E-06 7.9E-09 A SITE BOUNDARY NE 1.33 214O. 3.2E-O6 3.2E-O6 2.7E-06 7.3E-O9 A SITE BOUNDARY ENE 1. 33 2140. 2. 4E-06 2.4E-06 2. IE-06 6.3E-09 A SITE BOUKDARY E .,1.33 2140. 2.GE-06 ',. 1.9E-06 1.7E-G6 3.8E-G9 A SITK BOUNDARY ESK 1.33 2140. 1.8E-06 1.7E-06 1.5E-O6 4.0E-09 A SITE BOUNDARY SE 1.33 2140. 2. 1E-06 2. 1E-06 I.SE-06 5. 1E-G9 A SITE BOUNDARY SSE 1.33 2140. 3.5K-06 3.4E-06 2.9E-06 6.2E"09 A NEAREST RESIDENT SSM 3 ~ 90 6275 v 7 Sf 07 7.3E-GT 5.9E-07 6. Sf-10 A NEAREST RESIDENT SM 2.80 4506. 1.3E-06 1.2E-O6 1.GE-06 1.2E 09 A NCAREST RESZDCNT WSM 4.30 6920. 5.4K-07 5.0E-07 4.OE-OT 3. 4E-10 A NEAREST RESIDENT M 2.70 4345. 9.2E-07 8 Bf 07 7.3C-O7 7.3E-1G A NEAREST RESIDENT 'MNM 2.10 3380. 1.1K 06 1. 1E-06 9. 1E-07 1. IE-G9 A KCAREST RESIDENT NM 1.80 2897. 1.4C-06 1.3E-G6 I ~ 1E"06 1.6E 09 A RESIDENT 1.50 2414. 2.2E-06 2.2E-06 1.9E-06 3. 3E-09

'.4E NEAREST NNM A NEAREST RESIDENT H 2.ZO 354O. 1.4E-06 l. 3E-06 1. 1E-06 1 9E-G9

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A NEAREST RESZDEKT KNE 1.70 2736 06 2. IIE-06 2.0E-06 4.3E-09 A NEAREST RESIDf NT NE 2.30 3701. 1.0C-06 1.0E-06 8 'E-07 1.9E 09 A NEAREST RESIDENT KNE 2.00 3219. I .OE-06 1.0E-O6 8.5E-07 2.3E-09 A NEAREST RESIDENT E 1.90 3057. 9.3E-07 9. 1E-07 7.7E-O7 1,6E-09 A NEAREST RESIDENT ESE 2.70 4345. 4.3E-07 4. 1E-07 3.4E-07 7.3E-IO A NEAREST RESIDENT SE 4.70 7562. 1.9K-07 1.8C-07 1.4E-07 2.6E-10 A NEAREST RESIDENT SSE 4.4G 7081. 3.6E-07 3.4E-07 2.7E-07 3.7E-10 A GARDEN SSW 3.9G 6276. 7.8C-07 7.3E-07 5.9E-07 6. BE-10 A CARDEN SW 2.80 4506. 1.3E-06 1.2E-O6 1.GE-O6 'I.2E-09 A GARDEN MSM 4.30 6920. 5.4E-07 5.0E-O7 4.0E-07 3.4E-IO A GARDEN 3,00 4S28. 7.6E-OT 7.2E-OT 6.0E-O7 5.7E 10 A GARDEN MHM 2. Io 3380. 1. 1K-06 1. IE-06 9. IE-O7 I.IE-09 A GARDEN NM 3.80 6116. 3 'E-07 3.3C-O7 2.6E-07 2.8E-IO A CARDEN NNM 1.90 3058. 1.4E-06 1.4E-O6 1. IE-06 1.8E-O9 A GARDEN N 2.20 3540. 1.4E-06 1.3E-O6 1. 1E-06 'I.9E-O9 A GARDEN NNE . 1.70 2736. 2.4E-06 2.4K-06 2.6K-06 4.3E-09 A GARDEN NE 2,3G 3701. 1.OE 06 1.GE-06 8.5E-07 1.9E-O9 A GARDEN K 4.70 7564. 1.8E-07 1.7E-07 1.3K-07 2.0E-10 A

A A

GARDEN GARDEN COM MILK ESE SE N

2.80 4.70 2 20 4506.

7562 3540.

'.9E-07 4.GE-07.

1.4E 06 3.9E 67 IsBK-07 1.3E-06 3.2E-GT 1.4E-07

1. 1E-06 6.7E-10

2. 6E-10 1.9E-O9 A COM HZLK NNE 2.92 4703. 8.5E-07 8.2E-07 6.7E-87 1.2E-O9 A HEAT a POULTRY SSM 4.40 7081. 6.3E-07 5.9E-07 4.7E-07 5.2E-10 A HEAT tc POULTRY SM 2.80 4506. 1.3E-06 1.2E 06 1.OE-06 1.2E"G9 A HEAT tc POULTRY MS'M 4.30 6920. 5.4E"07 5.0E-G7 4.GE-07 3.4E-10 A HEAT k POULTRY W 3.10 4989. 7.2E-07 6.8E-O7 5.6E-G7 5. 3E-10 A HEAT Ic POULTRY MNW 2.50 4G23. 8.1E 07 7.7E-07 6.4E-07 7.2E 10 A HEAT a poULTRY NM 3.&0 6116. 3.5E 07 3.3K-07 2.6E-G7 2.8E-10 A HEAT Ic POULTRY NNW 1.90 305S. 1.4E 06 1.4E-G6 1. I E-G6 1.8E 09 A MEAT k POULTRY N 2.20 3540. '1.4K 06 1.3E-G6 1. 'IE-G6 1.9K 09 A MEAT a poULTRY NKE 1.80 2897. 2.2E 06 2. 1E-06 1.8E-06 3.8E 09 A HEAT 8c POVI.TRY Nf 2.30 3701. 1.OE-O6 1.6E-06 S.5E"07 1.9E 09 A HEAT 8 POULTRY ENE 2.00 3219. 1.OE 06 1.GE"86 8.5C-07 2.3E 09 A HEAT 8 POULTRY 4.6G 7403. 1.8E 07 A MEAT 8 poULTRY - ESE E

4.40 7OS1. 1.8E 07 1.7E 07 1.7E-O7 1.4E-OT 1.3E 07 2.1E 10

2. 4E-10 c

VENT AKD BUILDING PARAHETER S:

RE LEASE HEIGHT (HCTERS ) 0.00 REP. WINO HEIGHT (NETERS) 1G. G DIAMETER (HETERS ) -0.00 BUILDING HEZCHT (METERS) 55.'0 EXZT VELOCITY (HKTERS ) 0.00 BLOC.NZH.CRS.SEC.AREA (SQ.HETERS) 2161.0 HEAT KHZSSZON RATE (CAL/SEC) 6.0 LL CROUHO LEVEL, RELEASKS ~

TABLE A-5 0H) V)

P't) tD Ul K

X/Q Values For Long Term Ground Level Releases At'tandard Distances V~

Undepleted, No Decay, (Sec/ms} rt 0 (D

USNRC coHpUTER coDE - XOQDOQ, vERBIoN 2.e RUN DATE: 06/23/94 RUN TIHE: OS:46:2T t7 K O

XOQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA, 19T6-1987 Ql 0

EXIT ONE -- GROUND-lEVEL HISTORICAL DATA, 1976-1987 O N NO DECAYJ UNDEPLETED r0 g0 CORRECTED USING STANDARD OPEN TERRAIN FACTORS ANNUAL AVERAGE CHZ/Q (SEC/HETER CUBED)

SECTOR 0.250 0.500 0.750 1.600 DISTANCE 1.500 IN HILfS 2.MO FROH THE 2.500 SITE 3.MO 3.500 4.000 4.500 g

rr rt lD r0 tt 0>

S 1.720E-04 5.121E-O5 2.531E-05 1.246E-05 4.943E-O6 2.814E-D6 1.851E-06 1.33GE-06 1.015E-06 8.077E-07 6 '3?E-07 SSM 1.571E-O4 4.715E-05 2.346E-G5 1.158E-05 4.596E-06 2.607E-06 1.711E-06 1.227E-06 9.341E-O7 7.424E-07 6.093E-07 0 S'M 1.481E-04 4.412E-05 2.182E-05 1.074E-05 4.263E-06 2.428E-06 1.597E-06 1. 148E-06 8.75?E-07 6. 971E-07 5.728E-07 fo (D MSM 1.295E-04 3.842E-05 1.893E"05 9.308E-O6 3.693E-06 2. 108E-e6 1.389E-06 9.995E-07 7.632E-GT 6.086E-07 4.999E-07 MNM NM NNM M 9.839E-05 2.921E-05

7. 430E-15 2. 216E-05 6.636E-05 1.996E-05

'? .

1.440E-05

1. 098E-05 9.994f-06 179E-05 2. 185E>>05 1. 111E-05 7.087E-06 5.426E-66 4.967E-06 5.570E-06 2.814E-06 1.605E-06 2 '54E-06 1.225E-O6 1.982E-06 1.121E-06 2.234E-06 1.254E-06 1.057E-06 8.053E-BT 7.339E-07 S. 166E-07 7.608E-07 5.BOSE-07 5 '84E-07 4.409E-BT 5.254E-07 3.995E-07 5.820E-O7 4.409E-07 4.626E-O7 3.508E-BT

3. 171E-07 3.489E-07 3.803E-07 2.881E"07 2.599E-BT 2.853E-B7 rr C

N 9.224E-05 2.824E-G5 1.448E-05 7.277E-06 2.919f-06 1.633E-O6 1.060E-06 7.539E-07 5.701E-07 4.505E-07 3.678E-07 O rt NNE 9.847E-05 3.034E-05 1.560E-G5 7.892E-05 2.430E-05 1.240E-05 7.846E-06 3. 145E-06 1.754E-06 2.467E-06 1.376E-O6

1. 137E-06 8.070E 07 6.094E-07 6.333E-07 4.784E-B7 4.810E-O7 3.777E-07 3.923E 07 O~

NE 6. 194E-06 8.91SE-07 3.0S1E-O7 ENE 5.998E-05 1.845E-05 9.388E-06 4.679E-06 1.860E-06 1.036E-06 6.711E-07 4.764E-B7 3.597E-07 2.839E-07 2. 316E-07 E 4.903E-05 1.498E-B5 7.585E-06 3.779E-06 1 506E-06 8.439E-GT

~ 5.488E-07 3.908E"07 2.959E-07 2.341E-O7 1. 913E-07 ESE 4.458E-05 1.361E-05 6.872E-O6 3.417E-06 1.359E-B6 7.616E-07 4.952E-07 3.527E"07 2.670E-BT 2. 112E-07 1.726E-07 SE 5.351E-05 1.632E 05 8.255E-06 4. 102E-06 1.629E-06 9. 123E-07 5.929E-07 4.221E 07 3 . 195E-07 2.526E-07 2.064E-07 SSE 9.101E-05 2 '34E-05 1.361E'"85 6.718E-06 2.666E-B6 1.509E-06 9.8S5E-07 7.081f"07 5.387E-07 4.2?BE-07 3.509E-07 ANNUAL AVERAGE CHI/Q (SEC/HETER CUBED) DISTANCE ZN HILES FROH THE SITE SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45 000 50 000 S 5.589E-07 3.064E-OT 2.075E-07 1.263E-O7 8.904E-OB 6.799E-OB 5.459E-OS 4.53?E"08 3.867E-OS 3.360E-OB 2.964E-OB SSM 5. 126E-07 2.798E-07 1.890E-07 1. 147E-07 8 '66E-08 6. 149E-08 4.930E-GS 4.093E-OB 3.485E-OS 3.026E-OB 2.667E"08 SM 4.824E-OT 2.645E-07 1.791E-07 1.090E-07 7.686E-OB 5.869E-BB 4.712E-OB 3.916E-BB 3.338E-OS 2.900E-BB 2.55SE-BB MSM 4.213E-07 2. 3 15E-07 1.570E-B? 9.574E-BB 6.758E-BB 5. 165E-08 4.150E-BB 3.451E-BB 2.943E-OS 2.558E-OB 2.257E-BB M 3.205E-07 1.760E-07 1. 193f-87 7.275E-GB 5. 133 E-08 3.922E-BB 3. 151E-08 2.620E" 08 2.234E-BS 1.941E-OB 1.713E 08 MNM 2.426E-07 1.328E-07 8.985E-OB 5.463E-OB 3.849E-BS 2.93?E-OB 2.35?E-OB 1.958E-'08 1.66SE"08 1.449E-BB 1.278E 08 NM 2. 185E-07 1. 18&E-07 8.685E-OS 4.839E-GS 3.396E-GS 2.584E-GB 2.069E-GS 1.716E"68 1.460E-BB 1.266E-BS 1. 115E-08 NNM 2.392E-07 1.290E-07 8.639E-OB 5. 1SlE-08 3.617E-Ge 2. 741E-08 2. 187E-Oe 1.809E-GB 1.535E-OB 1.329E-BB 1. 168E-08 N 3.081E-B7 1.654E-GT 1. 105f -07 6.603E-OB 4.597E-BS 3.478E-BS 2.771E-OB 2.289E-BB 1.940E-OB 1.678E-BB 1.474E-BB NNE 3.283E-07 1.758E-07 1. 171E-G7 6.9eof-oe 4.852E-BB 3.665E-GB 2.918E-BB 2.408E-OB 2.040E-OS 1.763E-OB 1.548E-BS NE 2.579E-07 1.3S3E-07 9.230E-OB 5. 512E-08 3.839E"08 2.904E-OS 2.315E-BB 1.912E-BB 1.622E-BB 1.403E-OB 1.232E-BS ENE 1.938E-07 1.039E-07 6.935E-BB 4. 142E-OS 2.886E-OB 2.184E-BB 1.741E-OB 1.439E-BB 1.22OE-BB 1.056E-OS 9.278E"09 E 1.604E-O7 8.645E-GB 5.789E-BS 3.473E-OS 2.426E-OB l.e40E-OB 1.469E-OB 1 215E-08

~ 1.032E-OB 8.935E-09 7.858E-09 ESE 1.447f-o? 7.864E-OB 5.228E-BB 3. 139E-08 2. 193E-08 1.664E-GS 1. 329E-08 1. 110E "08 9. 341E "09 8. 091E-09 7. 117E-09 C SE 1.730E-07 9.328E-BB 6.24eE-GB 3.750E-BS 2.620E"BS 1.988E"GS 1.588E-OB 1.314E"08 1.116E-BB 9.665E-B9 8.501E 09 QQ SSE 2.950E-07 1.608E-07 1 085E"07

~ 6.575E"08 4.622E-GB 3.522E-GB 2.823E-OS 2 '43E 08 1.995E-BS 1.732E-OB 1.526E-BB ft VENT AND BUILDING PARAHETERS:

RELEASE HEIGHT (HETERS) 0.00 REP. MIND HEIGHT (HETERS) 10.0 DZAHETER (HETERS) B.GO BUILDING HEIGHT (HETERS) 55.0 EXIT VELOCITY (HETERS) 0.00 BLDG.HIN.CRS.SEC.AREA (SQ.HETERS) 2161.0 LA HEAT EHZSSION RATE (CAL/SEC) 6.0 ALL GROUND LEVEL RELEASES.

I J

II p'

II I

TABLE A-6 O ti) tt) tb lO ib Undepleted, No Decay, X/Q Values For Long Term Ground Level Releases At Standard Distances (Sec/m ) r't O

Q USNRC COHPUTER CODE - XOQDOQ, VERSION 2.0 RUN DATEt 06/23/94 RUN TIME: 08: 46: 27 tt X 0

XOQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 Vl O

EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 Ah NO DECAY, UNDEPLETED 0 C CHI/Q {SEC/HETER CUBED) FOR EACH SECHENT g 0 SFGHENT BOUNDARIES IN HILES FROH THE SITE Ps (D

.5-1 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 DIRECTION FROH SITE h rft0 tt S 2.535E-05 5.667E-06 1.900E-'06 1.026E"06 6.676E-07 3.185E-07 1.278E-07 6.824E-GB 4.545E-Oe 3.363E-08 SSM 2.344E-05 5.264E-06 1.756E"06 9.447E-07 6. 129E-07 2 . 9 12E-07 1.161E-07 6. 172E-08 4 101E-08

~ 3;029E-08 0 SM 2.185E-65 4.887E-06 1.639E-66 8.855E-07 5.761E-O7 2.749E-07 1. 163E-07 5. 891E-08 3 . 923 E-08 2.903E-OB R 4lD MSM 1.899E-05 4.236E-06 1.425E-06 7.715E-07 5.02SE-07 2.405E-O7 9.683E-OB 5. 184E-08 3 . 457E-08 2.560E-OS

'M 1.444E-05 3.226E-O6 1.085E-06 5.872E-07 3.826E-O7 1.829E-07 7.358E-GB 3.937E-GS 2.624E-68 1.943E-GB C MNM NM 1.099E-05 9.975E-06 2.467E-06 2.263E-06 8.265E-07 7.538E-07 4.459E-07 4.041E" 07 2.898E-07

2. 615E-07 1.381E-07 1.237E-07 5.528E-OB 4.902E-OS 2.948E-GS 2.595E-GS 1.962E-08 1.719E 08 1.451E-08 1.267E-08 vr NNM 1. 103 E-05 2.540E-06 8.395E-07 4.462E-O7 2.871E-07 1.345E-07 5.254E-OB 2.753E-GB 1.813E-GS 1.33OE-OS N 1.434E-05 3.316E-06 1.090E-06 5.771E-B7 3 . 702 E-07 1.727E-07 6.700E-OS 3.494E-GS 2.294E-OS 1.68OE-OB 0 rt tt KNE 1.543E-05 3.572E-06 1.169E-66 6. 169 E-07 3.949E-07 1.836E-07 7.086E-OB 3.682E-GB 2.413E-O8 1.765E-O8 O~

NE 1 . 229 E-05 2.811E-06 9. 176E-07 4.843E-07 3. 102E-07 1.445E-G7 5.595E"08 2. 918E-08 1.917E-OB 1.404E-OS ENE 9 '09E-06 2. 120E-06 6.906E-07 3.642E-O7 2.331E-O7 1.085E-O7 4.204E-OB 2. 194E-08 1.442E-08 1.057E-SB E 7.536E-06 1.717E-06 5.643E-07 2.995E-07 1.925E-07 9.019E-OS 3.523E-GB 1. 848E-08 1.218E-08 8 . 946 E-09 ESE 6.e33E-e6 1.551E-06 5.092E-07 2.702E-07 1 .737E-07 8. 141E-GS 3. 183 E-08 1.671E-OB 1. 102E-08 8. 101E-09 SE 8.262E-66 1.860E-O6 6.097E-07 3.233E-07 2.078E" 07 9. 732E-08 3.803E-GS 1 . 996E-08 1.317E-GB 9.676E-09 SSE 1.360E-05 3.052E-06 1.015E-O6 5.449E-07 3.530E-07 1. 674E-07 6.657E-GS 3.536E-GS 2.348E-GS 1.733E-OS

Q M Table A-7 Ht rD Undepleted, 2.26 Day Decay, X/Q Values for Long-Term Ground Level Releases at Standard Distances (Sec/ms) rrt Iit tt 0

O USNRC CDHPUTER CODE - XOQDOQ, VERSION 2.0 RUN DATE': 06/23/94 RUN TIHEI 08:46:27 0 At M

III XOQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 Cl III EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 2.300 OAY DECAY, UNOEPI.ETED 0 C CORRECTED USING STANDARD OPEN TERRAIN FACTORS g 0 tD ANNUAL AVERAGE SECTOR CHI/Q (SEC/METER CUBED) 0.250 0.500 0.750 1.000 DISTANCE 1.500 IN HILES 2.000 FROH THE 2.500 SITE 3.000 3.500 4.000 4.500 r0 ti S 1.712E-04 5.078E-O5 2.500E-05 1.226E"05 4.824E-06 2.723E-06 1.776E-06 1.266E-06 9. 57 1E-07 ?.553E-07 6. 153 E-07 0 SSM 1.564E-O4 4.675E-05 2.318E"05 1. 139E-05 4.4S9E-06 2.525E-86 1.643E-06 1. 168E-06 8.82OE-07 6. 951E-07 5.65?E-07 0 SH 1.474E-04 4.374E-O5 2. 154E"05 1.056E-05 4. 158E-06 2.347E-06 1.531E"06 1.091E-06 8.247E-07 6.508E"07 5. 301E-07 J HSM 1.289E"04 3.808E-05 1.869E.-05 9. 149E"06 3.600E-06 2.036E-06 1.330E-06 9.484E-07 7. 177E-07 5.667E-07 4.619E-07 C M 9.794E-O5 2.895E-05 1.422E-G5 6.966E-06 2.743E-06 1.551E-06 1.013E-06 7.221E-07 5.464E-07 4. 314E-07 3.515E-07 VV HNM 7.398E-95 2 '97E-05 1.085E 05 5.331E-06 2.102E-06 1.185E-06 7.723E-07 5.499E-07 4. 156E-07 3.278E-O7 2.669E-07 NM 6.689E-05 1.980E-05 9.879E.-06 4.892E-06 1.938E-06 1.087E-06 7.060E-07 5.014E-07 3.782E-07 2.978E 07 2. 421E-07 0a rt Ntht 7. 152E-05 2. 170E-05 1. 099E.-O5 5.495E-06 2. 189E-06 1.22OE-06 7.887E-O7 5.581E-07 4.19?E-O? 3.297E-O7 2.676E-O7 N 9.191E-05 2.805E-05 1.434E-05 7. 184E-06 2.S64E-06 1.591E-06 1.026E-06 7.247E-O? 5.442E-07 4.270E-07 3.463E-07 NNE 9.814E-05 3.014E-05 1.546E-05 7.751E-06 3.0SBE-06 1.712E-86 1. 102E-06 7.7?GE-87 5.829E-07 4.570E-07 3 '03E 07 t NE 7.865E-05 2.414E-05 1.228E-05 6. 117E-06 2.422E-86 1.342E-06 8.635E-07 6.091E-87 4.569E-O7 3.582E-07 2.902E-O7 ENE 5.978E-O5 1.833E-05 9 '00E-06 4.621E-O6 1.825E-06 1.011E-O6 6.499E-07 4.582E-07 3.436E-07 2.693E"07 2. 182E 07 E 4.885E-05 1.487E-05 7.507E-06 3.729E-O6 1.476E-06 8.212E-07 5.3G1E-07 3.748E-07 2.817E-07 2.212E 07 1.794E 07 ESE 4.441E-05 1.351E-05 6.801E-06 3.372E-06 1.332E-06 7.411E-07 4.783E-07 3.382E-B7 2. 541E-07 1.996E-07 1.619E-07 SE 5.331E-05 1.621E-05 8.172E 06 4.047E-06 1.597E-06 8.879E-07 5.728E-07 4.048E-07 3.042E-07 2.388E-07 1.937E-07 SSE 9.063E-05 2.712E-05 1.345E-05 6.616E-06 2.606E-06 1.463E-06 9.505E-G? 6.753E-87 5.095E-O7 4. 014 E-07 3.265E-O?

ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN HILES FROM THE SITE SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.0OO 45.OOO 5O.OOO S 5. 138E-87 2.70OE-07 1 ~ 755E-07 9. 871E-08 6.459E-GB 4.597E-GB 3.454E-GB 2.697E-GB 2. 167E-OB 1.781E-OS 1.499E"08 SSM 4.719E-87 2.472E-07 1.603E-07 8.990E 08 5 ~ 871E-OB 4.172E-GB 3.131E-OB 2.442E-OB 1.960E-OB 1.699E-OB 1.345E-BB SH 4.426E-07 2.324E-G? 1.589E-07 8.472E-OS 5.532E-OS 3.929E-OS 2.946E-OB 2.296E-OB 1. 841E-08 1. 510E-08 1. 261E-08 MSM 3.858E-07 2.029E-07 1.318E-07 7.405E-OB 4.835E-OS 3.433E-OB 2.574E-BB 2.005E-OB 1.607E-OB 1. 31?E-08 1. 100E-08 M 2.936E-O7 1.544E-07 1.003E-O7 5.633E-OB 3.6?SE-OB 2.612E-GB 1.958'E-08 1.525E-OB 1.223E-OB 1. 003E-08 8.370E-O9 HNM 2.228E-07 1. 169E"07 7.589E-OB 4.259E"08 2.782E-OB 1.976E-OB 1.482E-OS 1. 155E-08 9.267E-09 7.602E-09 6.350E-O9 NM 2.019E-07 1.055E-O7 6.837E 08 3.834E-OB 2.505E-GB 1.782E-GB 1.339E-BB 1.0'45E-08 8.394E-09 6.896E-09 5.768E"09 NNM 2.228E-07 1. 159E-07 7.490E-OS 4. 194E-08 2.742E-GB 1.953E-GB 1.470E-BS 1. 150E-08 9.252E-O9 7. 614 E" 09 6.378E-O9 N 2 BBOE-07 1.495E-07

~ 9.65OE 08 5. 401E "08 3.534E-GB 2.520E-OS 1.898E-GB 1.486E-BB 1. 198E-08 9.868E-09 8.276E-09 NNE 3.078E-97 1.594E-07 1.028E-07 5.753E-BB 3.766E-BS 2.687E-BB 2.026E-OB 1.588E-OB 1. 281E-08 1.05?E 08 8.872E-09 NE 2.413E-O7 1.25OE-07 8.065E 08 4.512E-OB 2.953E-GB 2. 106E-08 1.588E-OS 1.244E-OS 1.003E-OB 8.276E-09 6.949E-O9 ENE 1.814E-O7 9.395E-BS 6.060E-OB 3. 391E-08 2.220E-BB 1.585E-GB 1. 195E-08 9.369E-09 7. 561E-09 6.239E-09 5. 241E-09 E 1.493E-07 7.761E-OS 5.014E-BB 2.807E-BS 1.836E-GB 1.308E-BS 9.847E'-09 7.705E-09 6.205E-09 5. 110E-09 4.284E-09 C ESE 1.347E-07 7.005E-OB 4.527E-GB 2.535E"08 1.659E-OB 1. 183E-08 8.908E-09 6.9?4E-09 5.619E-09 4.63OE-09 3.884E-O9 00 C

SE 1.612E-O? 8.37SE-GS 5.414E"08 3.033E-OB 1.985E-OB 1.416E-OS 1.06?E-OB 8.353E-09 6.732E-09 5.549E 09 4.65?E-09 SSE 2.723E-07 1.425E-07 9.243E-OB 5 189E" OS 3.394E-GB 2.416E-GB 1.816E-OS

~ 1.419E-OB 1. 14OE-08 9.378E-09 7.851E-09 ft VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (HETERS) O.OG REP. MIND HEIGHT (METERS) 10.0 C

OIAHETER (METERS) 0.00 BUILDING HEIGHT (HETERS) 55.0 EXIT VELOCITY (HETERS) G.oo BLDG. HIM.CRS. S Ec . AREA (SQ.HETERS) 2161.0 HEAT EHISSION RATE (CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES.

I,

,r I

L

Table A-8 0 M Ht (D Undepleted, 2.26 Day Decay, I/Q Values for Long-Term Ground Level Releases at Standard Distances to Il)

Pl (Sec/m3) rt 0 COHPUTER CODE - XOQDOQ, 0

USNRC VERSION 2.0 RUN DATE: 06/23/94 RUN TIHE: 08:46:27 XOQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 0 N

0 EXIT ONE -" GROUND-LEVEL HISTORICAL DATA, 1976-1987 VI 2.300 DAY DECAY, UNOEPLETED A Ol I

CHI/Q (SEC/HETER CUBED) FOR EACH SEGHENT 0 C g 0 SEGMENT BOUNDARIES IN HILES FROH THE SITE DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40"50 tD FROH SITE ft S 2.506E-05 5.542E-06 1.825E-06 9.683E-07 6. 192E-07 2.822E-07 1.006E-e7 4.636E-OS 2. 711E-08 1.787E-OB 0 SSM 2. 318E-05 5. 151E-06 1.688E-06 8.926E-07 5.693E-07 2.585E-07 9. 168 E-08 4.209E-OB 2.455E-OB 1.615E-OB 0 SM 2. 159E-05 4.776E-06 1.572E"06 8.345E-07 5.334E-07 2.429E-07 8.636E-OB 3.964E-es 2.309E-OS 1. 516E-08 MSM 1.876E-05 4. 138E-06 1.366E-06 7.261E-07 4.647E-07 2. 119E-07 7.547E-OB 3 .463E-08 2.016E-OB 1.323E-OS O M 1.427E-05 3. 152E-06 1.040E-06 5.528E-07 3.537E-07 1.613E-07 5.741E-OS 2 .635E-08 1.534E-OS 1'. 006E-08 C

MNM NM NNM 1.087E-05 9.867E-06 1.093E-05 2.412E-06 2.216E-06 2.493E-06 7 . 934 E-67 7.259E-07

8. 116E-07 4.205E-07 3.827E-07 4.250E-07 2.686E-07 2.437E-07 2.694E"07 1.222E-07

1. 104E-07 1.214E-07 4.343 E-OS 3.911E-OS 4.281E-OB 1.994E-OS 1.798E-OS 1.970E-OS

1. 162E-08 1 . 051E-08

1. 156E-08 7.632E-09 6.922E-09 7.641E"09 re N 1.421E-05 3 . 25 8 E-06 1.056E-06 5.511E" 07 3 .486 E-07 1.567E"07 5. 515E-08 2. 541E-08 1 . 494 E-08 9.903E-09 O rt NNE 1.530E-05 3.513E-06 1.134E"06 5.904E-07 3.728E-07 1.672E-07 5.877E-OS 2.710E-OB 1.596E-OB 1.060E-OB NE 1.218E-05 2.763E-06 8 .893 E-07 4.628E-07 2.923E-07 1 . 3 11E-07 4 . 608 E-08 2. 125E-08 1.251E-OS 8. 3 05E-09 M ENE 9.227E-06 2.084E-06 6.694E" 07 3.480E-07 2.197E-07 9.855E-OS 3.464E-OS 1.598E-OB 9.418E-09 6.261E-O)

E 7.464E-06 1.685E-06 5.456E-07 2.852E-07 1.806E-07 8. 134E-08 2.866E-OS 1.319E-OB 7.746E-09 5.129E-09 g ESE 6.768E-06 1.523E-06 4.923E-07 2.574E-07 1.630E-07 7. 341E-08 2.588E-OS 1. 193 E-08 7. 010E-09 4.647E-09 SE 8. 124E-06 1.826E-06 5.897E-07 3.080E-07 1.950E-07 8 -781E" 08 3.096E-OS 1.428E-OB 8. 396E-09 5.569E-09 SSE 1.345E-05 2.989E-06 9.771E-07 5. 157E-07 3.286E-07 1. 491E-07 5.292E-OS 2.437E-OB 1.426E-OS 9.413E-09

tt4 I

4g

Table A-9 Depleted, 8.0 Day Decay, X1Q Values for Long-Term Ground Level Releases at Standard Distances (Sec/ms)

USNRC COMPUTER CODE - XOQDOQ, VERSIOH 2.0 RUN DATE: 96/23/94 RUN TIME: 08:46:21 XOQDOQ -- SHNPP CROUND LEVEL HISTORICAL DATA, 1976-1987 EXIT ONE -- GROUND-l.EVEL HISTORICAL DATA 1976- 1987 8.000 DAY DECAY, DEPLETED CORRECTED USING STANDARD OPEN TERRAIH FACTOR I

ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE SECTOR 0.250 0.5GG 0.750 1. 000 1.500 2.000 2.500 3.000 3.500 4.000 S 1.625E-04 4.665E-05 2.247E-05 1.085E-05 4. 169E-06 2.308E-06 1.482E-06 1.042E-06 7.784E-07 6.080E-07 4.908E 07 SSM 1.485E-04 4.295E-05 2.G83E-05 1.OG9E-05 3.877E"06 2.139E-06 1.369E"G6 9.606E-07 7. 168E-07 5.599E-07 4.507E-07 SM 1.40BE-04 4.019E-05 1.937E-05 9.357E-06 3.594E-06 1.991E-06 1.278E-G6 8.984E-G7 6.715E-07 5.244E-07 4.233f-ev MSM 1.224E 84 3.499E-05 '1,.681E-05 8.107E-06 3.113E-06 1.728F-06 l.'lllf-06 7.818E-07 5.849E-07 4.572E-07 3.693E-07 M 9.300E 05 2.660E-B5 1.279E"05 6.173E-06 2.372E-06 1.316E-06 8.458E"07 5.952E-07 4.452E-07 3.479E-07 2.81OE-07 MNM 7.023E-05 2.018E-05 9.753E-06 4.721E-06 1.S16E-06 1.005E-06 6.444E-07 4.527E-07 3.382E-07 2.640E-07 2.130E-07 NM 6.273E"05 1.819E-05 8.876E-06 4.329E-06 1.672E-G6 9.PG2E-07 5.878E-OT 4.111E-B1 3.06SE<<07 2.390E-07 1.925E-07 HNM 6.787E-05 1.991E-05 9.871E-B6 4.857E-06 1.886E-06 l.e3eE-e6 6.54sE-ev 4.56vf-ev 3.391E-07 2.635f-ev 2. 117E-07 N 8.721E" 05 2.574E-05 1.287E-05 6.346E-06 2.465E-06 1.342E-06 8.505E-07 5.920E-87 4.389E-97 3.494E-07 2.732E-O7 NNE 9.311E-05 2.765E 05 1.387E-05 6.844E-06 2.657E-06 1.442E-G6 9. 123E-07 6.339E-07 4.694E-OT 3.637E-O7 2 916E-Ov

~

NE 7.462E"05 2.215E-05 1.102E-05 5.403E-06 2.084E-06 1. 13 lf-06 7. 156E-07 4.974E-07 3.683E-O7 2.855E-07 2.289E-07 ENE 5,671E-05 1.682E-05. 8.343E-06 4.081E-06 1.571E-G6 8.519E-07 5.385E-07 3.741E-07 2.770E-07 2. 146E-07 1.721E-07 E 4.635E-05 1.365E-05 6.739E-06 3.295E-06 1.271E-96 6.933E-07 4.4elf 07 3.067E-07 2.276E-01 1.767E-07 1 . 419E-07 ESE 4. 214E-05 1.249E-05 6. 105E-06 2.980E-06 1.147E-06 6.256E-07 3.971E-07 2.767E-07 2.054E-07 1.595E-07 1.2SlE-07 SE 5.058E 05 1.487E-05 7.335E-06 3.576E-06 1.376E-06 7.495E-G7 4.755E-07 3.312E-07 2.457E-07 1.908E-07 1.532E-07 SSE S.603E-05 2.49 IE-05 1.209E-05 5.855E-06 2.249E-06 1.238E-06 7.917f-ov 5.547E-07 4. 136E-07 3.223E-07 2.597E-O7 ANNUAL AVERAGE CMI/Q (SEC/METER CUBED) DISTANCE IH MILES FROM THf SITE SECTOR 5.eee v.5ee le.ooe 15.000 20,GGB 25.990 3G;090 35.098 4e.eoo 45.090 50.090 S 4.B64E-07 2.OBOE-07 1.325E-07 7.280E-OB 4.7BOE-ea 3.317E-GB 2.477E-ea 1.924f-eB 1.538E-GB 1.257E-BB 1.045E"OS SSM 3.729E-07 1.901E-07 1.208E-07 6.616E-OB 4.263E-GB 3.004E-GB 2.240E-BB 1.73BE-BB 1.388E-OB 1.134E-GB 9.424E"09 SM 3.506E-07 1.794E-07 1. 143 E" 07 6.274E-OB 4.049E-GB 2.856E-BB 2. 131E-08 1.654E-BB 1.322E-OB 1.079E-GS 8.973E-09 MSM 3.B60E-07 1.569E-07 1. 001E-07 5.502E-GB 3.554E-GB 2.508E-OS 1.872E-BS 1.453E-BS 1. 161E-08 9.487E-O9 7.887E-09 M 2.328E-07 1.193E-07 7.609E-GB 4. 182E-08 2.velf-es 1.906f-ea 1.422E-OS 1. 194E-es 8.823E-09 7.207E-09 5. 991E-09 MNM 1.764E-07 9.014E-GS 5'.738E-es 3. 147E-08 2.030E-GB 1.431E-OS 1.068E-BS 8.289E-09 6.622E-09 5.409E-09 4.496E-09 NM 1.591'E-07 8.086E-GB 5. 129E-08 2.801E-OS 1.803E-BB 1.269E-GB 9.462E-09 7.339E-09 5.861E-09 4.787E-09 3.979E"09 NNM 1.746E-07 B.BOSE-GB 5.560E-GB 3.019E-OS 1.936f-ea 1.360E-eB 1.G13f-os 7.848E-09 6.26'4E-09 5. 115E-09 4. 251E-09 H 2.251E-07 1. 132E-07 7. 127E-OS 3.859E-GB 2.471E-BS 1.735E-BS 1.291E-BB 1.000E-GB 7.981E-09 6.516E-09 5. 417E" 09 NNE 2. 401E-07 1. 204 E-07 7.567E-GB 4.089E-GB 2.616E-BB 1.835E-OB 1.365E-GB 1.057E-GB 8.437E-09 6.8SBE-09 5.726E-09 NE 1.885E-B7 9.461E-GB 5.954E-GB 3.222E-OS 2.063E-OB 1.449E-GS 1.018E-OB 8.353E-09 6.668E-09 5.445E-09 4.527E-09 ENE 1.417E-07 7.1G9E-OS 4.473E-OB 2.421E-GB 1.551E-OS 1.089E-OS 8.109E-09 6.2S5E-09 5.018E-O9 4.099E-09 3.409E-09 E 1. 171E>>07 5.902E-GB 3.124E-OS 2.023E-BS 1.298E-OB 9.120E-09 6.791E-G9 5.264E-09 4.203E-09 3.432E-09 2.S53E"09 ESE 1.056E-07 5.327E-OS 3.363E-GB 1.S27E-OB l. 173f"0& 8.246E-09 6. 143E-09 4.763E-09 3.803E-09 3 . 107E<<09 2.583E 09 SE 1.263E-07 6.369E-OB 4'.02eE-08 2.184E-OB 1.402E-GB 9.856f-09 7.343E-O9 5.694E-09 4.547E-09 3.714E-09 3.089E-09 SSE 2.148E-07 1.094E-07 6.946E-OB 3.801E-OB 2.449E-GB 'l.726E-OB 1.2SBE-GB 9.994E"09 7.985E-09 6.524E-09 5.425E-O9 VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS) O.oo REP. MIND HEIGHT (METERS) 10.0 DIAMETER (METERS) D.oe BUILDING HEIGHT (METERS) 55.0 EXIT VELOCITY (METERS) 0'.Ge BLDG.MIN.CRS.SEC.AREA (SQ.METERS) 2161.0 HEAT EMISSIDN RATE (CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES.

Table A-10 Q N Ph P')

iD Depleted, 8.0 Day Decay, X/Q Ualues for Long-Term Ground Level Releases at Standard Distances (Sec/m ) rt 0 USNRC COHPUTER CODE XOQDOQ, VERSION 2.0 RUN DATE: 06/23/94 RUN TIHE: 08t46127 0 0>

XOQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA) 1976-1987 tll O

+o EXIT ONE -- CROUND-LEVEL HIST ORICAL DATA, 1976-1987 n ot 8.008 O)Y DECAY, DEPLETED 0

CHI/O (SEC/HETER CUBED) FOR EACH SEGMENT g 0 SEGHENT SOIGND ARIES IN HILES FROH THE SITE 0 DIRECTION .5-1 1-2 2-3 3"4 4-5 5-10 10" 20 20-30 30-40 40-50 rt Pt FROH SITE 0 S 2.268E-05 4.827E 06 1.526E-06 7.887E-07 4.943E-07 2. 186E-07 7.461E-GS 3.359E-08 1. 935E-08 1.262E-08 SSH 2.097E"05 4.485E-06 1.411E 06 7.263E-BT 4.540E-07 1.999E-BT 6.785E-GS 3.G34E-OS 1.748E-08 1. 138E-08 SM 1.955E-05 4. 162E-96 1. 3 16E-06 6.803E-07 4.264E-07 1.885E-'07 6.430E-08 2.884E-08 1.664E-08 1.084E-OS X 0>

C WsiI 1.698E-05 3.607E-06 1. 144 E" 06 5.925E"07 3 . 719E-07 1 648 E-07

~ 5.637E-GS 2.532E-08 1 462E-08

~ 9.524E-O9 1.292E-05 2.747E"06 8.710E-07 4. 5 1eE-07 2.830E-BT 1.253E" BT 4.285E-98 1.924E-08 1.111E-08 7 .236E-09 MS(

NM 9'.835E-e6 8.924E"06

2. 101E-06 1.928E-06 6.638E-O7 6.'e60E-07 3 . 426 E-07

3. 109E-07

2. 145E-07 1.939E-07 9.474E-08 8.51eE-es 3.226E-GS 2.875E-GB 1.446E-08 1.282E-GS 8.338E-09 7.383E-09 5.430E-09 4.806E-09 Vt NW 9.874E-06 2. 166E" e6 6.757E-B7 3.439E-07 2. 133E-07 9.287E-08 3.102E-08 1.375E-GS 7.896E-09 5. 136E-09 O rt H 1.283E"85 2.828E-06 8.782E 07 4.451E-07 2.753E-07 1.194E-G7 3.969E-O8 1.754E-08 1.G96E-08 6.543E-09 NNE 1.381E 85 3'.04sE-e6 9.423E-07 4.761E-07 2.939E-OT 1.271E-07 4.207E-OS 1.855E-08 1.064E-08 6.917E-09 O~

HE 1. 100E-05 2.398E-06 7.392E-07 3.736E-07 2.307E-BT 9.990E-GB 3.314E-BS 1.464E-08 8.404E-09 5.467E-09 ENE 8.332E-06 1.809E"96 5'.563E-eT 2.810E-BT 1.734E-OT T.586E-08 2.491E-98 1. 101E-Gs 6.323E-O9 4.115E-O9 E 6.744E-06 1.464E-06 4.542E-07 2.308E-07 1.430E-BT 6.224E-GS 2.e79F.-es 9.217E-09 5.296E-09 3.446E-09 ESE 6.115E 06 1. 323 E-06 4.G99E"07 2.083E-BT 1. 291E-07 5.618 E-08 1.878E-BS 8.333E-G9 4.791E-09 3.119E-09 SE 7.340E-06 1.586E 06 4.988E-07 2.492E-07 1.544E-BT 6. 717E-08 2.244E-es 9.96GE-09 5.728E-09 3.730E-09 SSE 1,217E" 05 2.601E-06 8.160E 07 4. 191E-07 2 616 E-07

~ 1. 151E-07 3.899E-BS 1.743E-08 1.005E-O8 6.550E-09

2 22

TABLE A-ll 0 M H) O Deposition Values (D/0) For Long Term Releases At Standard Distances -2 Vl Q)

(m ) tt O O

USNRC COHPUTER CODE " XOQDOQ, VERSION 2.0 RUN DATE: 06/23/94 RUN TIHE: 08:46:27 0 lh Xoqeoq SNNPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 tD r'

0 EXIT 0 NE -- GROUND-LEVEL HISTORICAL DATA, CORRECTED USING STANDARD OPEN TERRAIN FACTORS 1976- 1987 r0 gg 4%%4%%%%%

DIRECTION RELATIVE DEPOSITION PER UHIT AREA (HII4I-2) AT FIXED POINTS BY DOMNMIHD SECTORS DISTANCES IH HILES ON%4%%%%%%%%%%%%4%%%

r r0 C

O FROH SITE S

0.25 2.324E-07 0.50 7.857E 08 0.75 4.034E-OS 1.00 1.50 1.918E-08 6.889E-09 2.00 3.417E-09 2.50 3.00 2.012E-09 1.317E-09 9.269E-1G 3.50 4.00 4.50 6.869E-lG 5.294E-10 r0ft v SSM 2.171E-07 7.343E-08 3.770E-OS 1.792E-OS 6.438E-09 3.193E-09 1.880E-09 1.231E-09 8.662E-10 6.420E-lG 4.947E-10 SM 1.740E-07 5.885E-GS 3.022E-08 1.437E-08 5. 160E-09 2.559E-09 1..5GTE-G9 9.866E-10 6.942E-10 5.145E-10 3.965E-10 0 MSM 1.355E-07 4.582E-08 2.353E-08 1.119E"08 4.018E-B9 1.993E-09 1 ~ 173E"09 7.682E-10 5.406E-10 4 '06E-10 3.0S7E-10 0 M 1.013E-07 3.427E-GS 1.759E-OS 8.365E-09 3.005E-09 1.490E-09 8.774E-10 5.745E-10 4.042E-10 2.996E-10 2.309E-10 MNM 8.296E-OS 2.805E-08 1.440E-08 6.848E-09 2.460E-09 1.226E-09 7.183E-10 4.703E-10 3.309E-10 2.453E-10 1.890E-10 NM S.468E-08 2.864E-08 1.470E-08 6.990E-09 2.511E"09 1.245E-09 7.332E-10 4.801E-10 3.378E-10 2.503E-10 1.929E-10 NNM 1 ~ 105E-07 3.736E-OS 1.918E-GS 9.120E-09 3.276E-09 1.625E-09 9.566E-10 6.264E-10 4.408E-10 3.266E-10 2.517E-10 N 1.626E-07 5.499E-OS 2.823E-OS 1.342E-GS 4.821E-09 2.391E"09 1.408E-09 9.218E-10 6.487E-10 4.807E-10 3.7B5E-10 NHE NE 1.985E-GT 1.815E-07 6.713E-08 6.137E-08 3.447E-GS 3.151E-08 1.639E-08 5.886E-09 1.498E-08 5.381E-G9 2.919E"G9 2.669E-09 1.719E-09 1.125E-G9 7.919E-10 1.571E-69 1.029E-09 7.240E-10 5.869E-1G 4.522E-10 5.366E-10 4.135E-10 aQO ~rt ENE 1.568E-07 5.302E-08 2.723E 08 1.294E-OS 4.649E-09 2.306E 09 1.358E-09 8.890E-10 6.255E-10 4.636E-10 3.572E-10 C/l E 9.595E-08 3.245E-08 1.666E-OS 7.920E-09 2.845E-09 1.411E-G9 S.307E-lB 5.439E-10 3.827E-10 2.837E-1G 2.1S6E-10 ESE 1.003E-07 3.393E-08 1.742E-OS 8.281E-09 2.975E-09 1.475E-G9 8.686E-lG 5.688E-10 4.002E-10 2.966E-10 2.286E-10 SE 1.270E-07 4.294E-08 2.205E-08 1.048E-G8 3.765E-09 1.867E-09 1.099E-09 7. 199E-10 5.066E-10 3.754E-10 2.893E-10 SSE 1.548E-07 5.236E"08 2.6S8E-OS 1.278E-GS 4.591E-09 2.277E-09 1.341E-09 8.778E-10 6. 177E-10 4.578E-10 3.528E-10 DIRECTION DISTANCES ZN HILES FROH SITE 5.60 7.50 10.00 15.ee 28.00 25.00 ,30.00 35.60 40.00 45.00 50.00 S 4. 205E-10 1.868E-10 1. 132E-1G 5,720E-11 3.462E-11 2.321E" 11 1.663E-11 1.249E-11 9.711E-12 7.757E-12 6.332E-12 SSM 3. 930E-10 1.746E-10 l. e58E- le 5.346E-11 3.235E-11 2. 169E-11 1.554E-11 1.167E-l 1 9.075E-12 7.249E-12 5.917E" 12 SM 3. 150E-10 1.399E-10 8.476E-11 4.284E-11 2.593E-ll 1.739E-11 1.246E-11 9.354E-12 7.273E-12 5.810E-12 4.742E-12

'MSM 2.453E-10 1. 090E-10 6.6GOE-11 3.336E-11 2. 019E-11 1.354E-11 9.70GE-12 7.284E-12 5.663E-12 4.524E"12 3. 692E-12 M 1. 834E-10 8. 148E-11 4.935E-11 2.495E-11 1. 510E-11 1.012E-11 7. 254E-12 5. 447E-12 4. 235E-12 3. 383E-12 2. 761E-12

'MNM 1. 501E-10 6.670E-11 4.040E-11 2.042E-11 1.236E-11 8.287E-12 5.938E-12 4.459E" 12 3.467E-12 2.769E-12 2.261E" 12 NM 1. 533 E-10 6.BOSE-11 4. 124E-11 2.085E-11 1.262E-11 8.459E-12 6. 062E-12 4 . 552E- 12 3 . 539 E- 12 2.827E-12 2. 307E-12 NNM 2. GOBE-10 8.884E-11 5.381E-11 2.720E-11 1.646E-11 1. 104E-11 7.9B9E-12 5.939E-12 4.618E-12 3.689E-12 3. 011E-12 H 2.943E-10 1. 307E-10 7.920E-11 4.003E-11 2.423E-11 1.624E-11 1.164E-ll 8.740E-12 6.796E-12 5.428E-12 4.431E-12 NNE 3.593E-10 1.596E-10 9.668E-11 4.887E'-ll 2.958E-11 1.983E" 11 1.421E-11 1.067E-11 8.296E-12 6.627E-12 5.469E-12 NE 3.285E-10 1. 459E-10 8.839E-11 4.468E-11 2.704E-11 1. 813E-11 1.299E-11 9.755E-12 7.585E-12 6.059E-12 4 ~ 946E-12 ENE 2. 838E-1G 1.261E-10 7.637E-11 3 '60E-11 2.336E-ll 1.566E-11 1.122E" 11 8.428E-12 6.553E-12 5.235E-12 4. 273E-12 E 1. 737E-10 7.714E-11 4.673E-11 2.362E-11 1.430E-11 9. 585E-12 6.868E" 12 5.157E-12 4.010E-12 3.203E-12 2.614E-12 ESE 1. 816E-10 8.066E-11 4.886E-11 2.47OE-11 1.495E-11 1.002E" 11 7.181E-12 5.393E-12 4.193E-12 3. 349E-12 2.734E-12 SE 2.298E-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 3.460E-12 SSE 2.8G2E-10 1. 245E-10 7. 541E-11 3.812E-11 2.307E-11 1.547E-11 1.108E-11 8.323E-12 6.471E-12 5. 169E-12 4.219E- l2 C

W o C

TABLE A-12 Q M H) lD Deposition Values (D/Q) For Long Term Releases At Standard Distances (m )

Ql r~ t{

ct 0 (D

USNRC COHPUTER CODE - XOQDOQ, VERSION 2.0 RUN DATE'6/23/94 RUN TIHE: 08:46:27 ax 0 0)

Ql 0

XOQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976-. 1987 O

rN EXIT QNE -- GROUND-LEVEL HISTORICAL DATAI 1976-1987 RELATIVE DEPOSITION PER UNIT AREA (H%%-2) BY DOMNMIND SECTORS SEGHENT BOUNDARIES IN HILES rr 0 C g A t%

rt P tD DIRECTION FROH SITE

. 5- '1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 r0 8 S 3.943E-08 8.077E-09 2. 109E-09 9.470E-10 5.357E-10 2.060E-10 5.960E-11 2.362E-11 1. 261E-11 7.eoeE-12 SSH 3.685E-08 7.548E-09 1. 97 lE"09 8.85OE-lo 5. 007E-10 1. 925 E- ie 5. 570E-1 2.20BE-11 1. 179E-11 7.297E-12 0 SM 2.953E 08 6.050E-09 1.579E-09 7.093E-10 4. 013E-10 1. 543 E-10 4.464E-11 1

1.769E-11 9. 448E-12 5.848E-12 X C0 NSM 2.300E 08 4. 710E-09 1.230E-09 5.523E-10 3. 124E-10 1. 201E-10 3.476E-11 1.378E-11 7.357E-12 4.554E-12 WW W

M 1.720E-08 1.408E"08 1.437E-08 3.523E-09 2.8S4E-09 2.944E-09

9. 196E-10

7. 528E-10

7. 685E-10

4. 130E-10

3. 381E-10 3.451E" 10

2. 337E-10

1. 913 E-10 1.952E" 10 8.985E 11 7.356E-ll 7.508E-11 2.599E-11

2. 128E-11

2. 172E-11

1. 030E-11

8. 434E-12

8. 609 E-12 5.502E-12 4.504E-12 4.597E-12 3.405E-12 2.788E-12 2.846E-12 rr C

MNH 1.875E"08 3.841E-09 1.003E-09 4.503E-10 2.548E-10 9.797E"11 2.834E-11 1 ~ 123E-11 5.99SE-12 3.713E-12 0 rt N 2.760E-08 5.652E-09 1.476E-09 6.627E-10 3.749E-10 1.442E-10 4. 171E-11 1.653E-11 8.828E-12 5.464E-12 NNE 3.369E"08 6.981E-09 1 . 801E-09 8. 091E-10 4.577E-10 1.760E-10 5.092E-11 2.018E-11 1.07SE-11 6. 67 1E- 12 NE 3.080E-08 6.309E-O9 1.647E-09 7. 397E-10 4. 185E-10 1.609E-10 4.655E-11 1.845E-11 9.853E-12 6.099E-12 ENE 2.661E"08 5. 451E-09 1.423E-09 6. 391E-10 3. 615E-10 1.390E-10 4. 022E-11 1.594E-11 8. 513E" 12 5.269E-12 E 1.628E-BS 3.335E-09 8.787E" 10 3. 911E-10 2. 212E-10 8.507E-11 2. 461E-11 9.754E-12 5.209E-12 3. 224E- 12 ESE 1.703E-08 3.487E-09 9. 104E-10 4. 089E-10 2. 313E-10 8.895E-11 2.573E-11 1.020E-11 5.447E-12 3.371E-12 SE 2.'155E-08 4. 414 E-09 1. 152E-09 5. 176E-10 2. 928E-10 1. 126E-18 3.257E-11 1.291E 11 6.894E-12 4. 267E-12 SSE 2.628E-08 5.383E"09 1.405E-09 6.311E-10 3. 570E-10 1. 373E-10 3.972E-11 1. 574E-1 1 8.406E-12 5.203E-12 VENT AND BUILDING PARAHETERS:

RELEASE HEIGHT (HETERS) 0.08 REP. MIND HEIGHT (HETERS) 10.0 DZAHETER (HETERS) 0.00 BUILDING HEIGHT (HETERS) 55.0 EXIT VELOCITY (HETERS) 0.00 BLDG.HIN.CRS.SEC.AREA (SQ.HETERS) 2161.0 HEAT EHISSION RATE (CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES.

k

~ ~

TABLE A-13 Q M Ul Q)

Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP rt 0 S

Period Gf Record: 1/1/76 - 12/31/82 .

0 Ol Lower Monitoring Level Qt 8

VSNRC COHPUTER CODE " XOQDOQ, VERSION 2.0 RUN DATE: 06/23/94 RUN TINE: BS:46:27 O Ol XDQDDQ, SHNPP CRDUND-LEVEL HISTORICAL DATA, 1976-1987 n g g 0 l

JOINT FREQVEHCY DISTRIBUTION OF MIND SPEED AND DIRECTION .ATHOSPHERIC STABILITY CLASS A n

UHAX (H/S) N NNE NE ENE E ESE SE SSE S SSW SM MSM W WNW NNW TOTAL r0 Q o

8.34 B.eoo O.oeo e.eoo e.eeo e.eoo D.eeo e.eoo 0.008 e.eoo B.eoe 0.000 e.eeo 0.000 0.000 0.000 0.000 0.001 1.56 e.'0 lu 0.'Oe9 0.'016 0.012 O.G12 8.009 0.021 0.008 0.020 0.816 0.020 0.01S 0.015 0.810 0.011 0.009 0.219 O 3.35 0.425 0.354 0.307 0.219 0.162 O. 123 G. 116 0.177 0.357 0.329 0;33S 0. 416 0. 163 0. 165 G.317 0.334 4.303 .X C lD 5.59 8.38T 8.296 0. 173 0.868 0.017 0.029 0.020 0. 021 0.083 o.25v e.361 e'.450 0. 145 G.234 0.367 0.356 3. 176 8.27 O.ees e.'eoo B.eo2 e.000 e.ooo O.G01 Q.008 0.881 B.Q05 0.011 0.057 G.OS4 0.033 0.071 8.059 0.044 0.374 0.009 0.000 0.000 o'.ooo e'.eoo e'.Doe o'.ooo o.oo 1 e.ooo B.OG4 B.oeu O.OGS 8.000 e.eol O.GlS 11 ~

11.62 19 B.OQG 6 F 000 0.008 0.080 8.000 G.OOG 8.800 o.000 O.eoo e.ooo B.eee B.eee e.ooe e'.eeo B.eoo 0.000 0.600 0'.Ooe 0.000 P V TOTAL e.'v5 e.'66 e'.5e 0.29 0 19

~

0.'6 e.'16 0.21 0.47 8.61 0.78 0.97 0.36 0.49 0.75 0.74 8.09 O rt Cl JOINT FREQUEHCY DISTRIBVTIDtl OF MIND SPEED AND DIRECTION ATHOSPHERIC STABILITY CLASS 8 + M UHAX (H/S) N NNE NE ENE E ESE SE SSE S SSW .SM 'WSM M MHM HW NNM TOTAL 0.34 e.eeo e.eoe o.eoB e.eoo B.eoe 8.000 8.800 e.ooo B.oeo B.eoe e.eoo O.OOG G.OOO O.OOQ e.ooo 0.600 O.OQO 1.56 0.014 0.015 G.923 0.022 O.G17 0.021 G.017 0. 018 0.022 0.020 0.032 0.021 0. 025 0. 013 0.01S e.'elv 0.314 3.35 0.30S G.269 0.204 0. 1S1 Q.151 0. 121 B.GS7 0. 133 8.234 0.282 8.323 0.314 0.111 8. 142 0.221 0.217 3.298 5.59 8.109 O.GS7 0.961 e.'022 e.'021 O.G08 0.028 0.822 e.ouv e.e99 e.16e 0. 196 e. le2 0. 151 0. 216 G. 158 1.478 8.27 e'.ee6 0'.Bee 0'.eol B.GOO 0.000 o.eee e'.e00 0.001 0.004 0.085 O.G31 0.026 0.032 0.053 e'.028 G. 019 0.205

11. 18 B.eoo e.ooo 0.000 O.OGO G.OOO 8.000 0.000 e.000 e.oee e.oeo e'.e02 e.ee2 0.081 8.803 8.801 0. 001 8.010 11.62 e'.eoe e'.eee 0'.eoo O.OOG G.BOO 0.'eeo e.eeo e.ooo e.'eeo 0.'eoo e'.OBe 0.801 0. GOB O.GGO O.GGG e'.eeo G.OG1 Tol'AL 0.44 8.37 0.29 0.23 0.19 0.15 0.12 0.17 G.31 0.41 0.55 G.56 0.27 0.36 0.4S 0.41 5.31 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATHDSPHERIC STABILITY CLASS C UHAX (H/S) N NtlE NE ENE E ESE SE SSE S SSM SM MSM M WNW HW NNW TOTAL 0.34 O.OOG B.oee B.ooo 0.600 6.000 8.000 0.088 8.000 B.eoo e.ooo B.eoo 0.000 0.000 0.090 B.eoo G.GOO 0.000 1.56 0.831 0.031 0.035 0.02S D.G23 0.031 0.041 '0.037 0.050 G.857 0.069 O.eu5 B.G35 0.029 0.033 Q.038 0.610 3.35 0. 347 0.297 0.245 0. 22G 0. 152 8.131 0.121 G. 158 0.261 0.332 0.375 0.369 0. 175 0. 192 e.2u6 0.261 3.874 5.59 0. 139 0.081 0.039 0.836 0.008 0.009 8.814 8.027 8.829 0. 11'2 0.160 0. 192 0. 117 0. 115 0. 199 G. 145 1.423 8.27 e.eov G.OOO 0.088 e.eoo e'.000 0.'Boe 0.'eoo O.OG1 e.eol o.eos e.019 0.023 0. 012 e.055 0.024 0.015 0. 164

11. 18 0.000 0.000 0.900 0.000 0.000 0.000 0.000 e'.Ooo 0.000 G.OGO O.G02 0.003 D.G02 0.602 G.OGO B.OGB 0.009

11. 62 e.ooB e.ooe e.ooo O.GOO O.GOO 0.000 6.000 e.oee 0.000 0.088 0.008 8.000 0.000 0.000 0.000 0.000 e.ooo TOTAL 0.52 0.40 0.32 0.2S 0.1S 0. 17 0 ~ 18 0.22 0.34 0.51 0.63 0.63 0.34 0.39 0.50 0.46 6.08 JOINT FREQUENCY DISTRIBVTIOH OF MIND SPEED AND DIRECTION ATHOSPHERIC STABILITY CLASS D UHAX (H/S) N NNE NE EtlE E ESE SE SSE S SSM SM MSM 'WN'W NNW TOTAL Gt 8.34 e.e02 0.002 O.OG2 G.002 8.881 G.001 0.001 0.001 O.OG2 0.002 0.002 0.001 0.001 0.001 0.001 0.001 0.025 1.56 0.434 8.506 0.444 0.370 0.329 0.266 0.278 0.300 0.362 0.481 0.465 0.346 0.287 0.258 G.269 G.346 5.739 3.35 1.759 2.054 1.350 0.964 0.624 0.523 G.556 0.742 1.058 1.346 1.316 1. 177 0.647 0.583 0.746 1.Q25 16.471 5.59 0.556 0.491 0.330 0. 114 G.066 0. G76 G. 1GO 0. 190 0.220 0.376 0.55G 0.462 0.260 0.402 0.523 0 ~ 55S 5.271 C C' 8.27 B.e55 O.G23 O.OG4 O.Q1 1 0.004 0.006 8.005 0.023 0.032 0.0'47 0.069 0.075 0.042 0.092 0.062 0.063 0.610

11. 19 O.OOG 8.000 0.000 0.000 O.OOG O.OOG O.GOl D.ooe 0 001 0 001 0 GOS G.017 0.000 0.004 0.000 0.000 0.032 11.62 e.eeo e'.Ooe 0.000 e.eoo e'.Oel o.eoe B.eoo 0.000 0.000 G.OOO 0.000 G.OGO G.OOO 0.000 O.OGO e.ooo 0.001 TOTAL 2.81 3.0S 2. 13 1.46 1.02 O.S7 0.94 1.26 1.68 2.25 2.41 2.08 1.24 1.34 1.60 1 ~ 99 28. 15

TABLE A-13 (continued) O Ch

~

Ol Gl Q>

Joint Vind Frequency Distribution By Pasquill Stability Classes At SHNPP rt 0 O

USNRC COHPUTER CODE - XOQDOQ, VERSION 2.G RUN DATE: 06/>>/o4 R"" T t GSt46:27 Period of Rect3rd:

sos<-iaa~

I/1/76 12/3l./82 0 0>

XOQDOQ SHNPP GROUND-LEVEL HISTORICAL DATA, ~

r o'vter9%onitoring Level ttt tD A

r th JOINT FREQUENCY DISTRIBUTION UHAX e.34 (H/S) I 8.005 N NNE 0.607 OF MIND SPEED AND 8.006 NE ENE 0.005 8.864 E

DIRECTION ESE 8.003

'E 0.00'4 SSE 0.006 ATHOSP HERIC 0.009 S

0.089 STABILITY CLASS SS'M 0.085 SM MSM e.004 E

0.003 M MNM 0.002 0.003 NNM TOTAL 0.003 0.079 0

C 0 C

1.56 0.747 0.962 0.824 0.692 0.518 0.480 0.536 e.sls 1.244 1. 183 0.723 0.492 0.415 0. 312 e'.405 e'.466 10.S16 f5 tD 3.35 1.028 0.855 0.549 0.309 0.266 0.356 0. 577 1.658 1.547 0.744 e.488 0.459 0.668 0.667 10.920 rl 5.59 8.124 e.'eov e'.032 e'.046 G.329 0.029 8.819 0.02S 8.032 0.080 0.13S 0.14S 1.029 0.216 0. 145 e.06v O. 1G1 0.085 0. 131 1.421 r0 $n S.2? G.003 8.008 0. 802 0.002 e.oe4 0.006 B.eo6 0.016 8.01G 0.015 O.G26 8.010 O.OG3 0.003 B.oos 8. 120 11 ~ 18 e.'Boe 0.'oee e.'Goe 0.000 0.000 O.GGO 0.000 G.BGB 0'.e00 e'.ooe e'.003 8. 68'4 0.880 0.001 0.000 e.e00 e'.eos 0

11. 62 0.008 o.'eoe e.'oeo e.'000 e'.eoo e'.Boo e.eeo O.GGG e.'o00 e'.eBe e.'Boe G.BBO e.'ooe B.e00 0.080 e.ooo 0.000 X0)

C tb TOT Al 1.91 1.86 1.42 1.06 G.s5 0.78 0.93 1.49 2,47 2.90 1.99 1.41 0.98 O.BS 1. 16 1.28 23.36 H JOINT FREQUENCY DISTRIBUTION OF MIND SPEED AND DIRECTION ATHOSPHERIC STABILITY CLASS F S~r t

UHAX (H/S) N NNE NE ENE E ESE SE SSE S SS'M S'M 'MSM M MW W NW TOTAL O rt 0.34 e.ols e.o18 e.elv 0. 014 0.011 0.009 0.0'll G.G15 8.01S O.G19 0.012 e.ee9 0.00& 0.007 O.OOT 0.011 0.203 1.56 0.777 0.7SS 0.735 0. 621 0.5GO 0. 414 0.489 e.66V e'.803 e'.85v 0.553 0.395 0.341 0.291 0.321 0.467 9.817 3.35 0.349 0.159 0.072 0.071 0.056 0.033 0.043 0.046 0.128 0.192 0. 176 8. 144 e'.e98 0. 106 8.098 8. 154 1.925 5.59 6.003 0.001 8.088 0.081 0.000 0.000 G.eeo e'.eee 0.000 8.091 e'.ee6 8.801 G.eBo 0.000 B.eoo G.002 0.015 8.27 e'.Boe 0'.Goo e.ooo e'.eoo e.o00 B.Ceo G.GOO e.ooG e.'Goo e'.ooe e.'Bel G.GOO e.'Beo 0.000 0.000 0.000 0.081 11.18 e'.000 0.'000 e'.eoo e'.ooo e'.610 0.610 e.'o00 G.OOO D.ooo B.ooe B.eoo G.eeo G.GOG O.GOO 0.080 8.000 O.GOO 11.62 0.000 e.ooe 0'.Goe 0.000 8.000 e'.000 0.880 o.oeo 0.000 0'.eoe e'.eeo e'.Gee G.008 e'.Beo B.GGO e'.eoe e.eoo TOTAL e'.9v e'.82 G.71 8.57 e.'46 e.54 G.73 0.95 1.87 0,75 0.55 8.45 0.48 8.43 0.63 11.16 JOINT FREQUENCY DISTRIBUTION OF ltIND SPEED AND DIRECTIOH ATHOSP HERIC STABILITY CLASS 0 UHAX (H/S) N NNE NE EKE E ESE SE SSE S SSM SM ltSM M MNM W NNM TOTAL 8.34 0 360

~ 0.317 0.316 0.28'4 8.214 0. 154 0. 121 e. les 0. 128 0. 128 0. 112 G.085 8.877 0.071 0.085 0. 176 2.737 1.56 1.932 1.699 1.692 1.522 1.146 G.S23 8.649 e'.5se 8.684 8.688 0.600 0.457 0.414 8.381 G.455 0.945 1tl.668 3.35 0.162 O.G32 0.024 8.021 G.009 G.012 0.012 0.007 0.007 B.GGS 0.026 0.023 8.014 0.015 0.021 0.047 8.439 5.59 8 000

~ 0.000 G.GGO 0.000 0.688 0.008 8.000 0.800 e'.Boo e.'000 e.eel G.BGG 8.000 e.'ooo 0.001 0.081 0.003

&.27 8.008 0.800 0.860 0.800 0.800 0.000 G.eeo B.eeo 0 Beo

~ e.oeo o.oeo e'.eee e.e00 0.000 e.eoo e.oeo e'.eoo

11. 1s o.'oo0 0.0eo 0.'eee e.'000 o.'000 0.088 o.'eeo 0.008 0.000 8.088 6.060 0.600 8.600 0.000 0.000 O.GOO 0.000 11 '2 T0TAL 0.000 2.45 0.000 2.05 0.010 2.e3 0.000 1.83 0.000 1.37 0.000 0.99 B.eeo e'.vs 0.0oe 0.70 0.000 0.82 e.000 O.S2 o.eoo 0.74 o.oee e'.5v e.eoo 0.51 B.ooe 0.47 o.oo0 0.680 0.56 1, 17 8.008 17.85 TOTAL HOURS CONSIDERED ARE """"~

0 i

TABLE A-13 (continued) C7 CD ttt N ttt tD tlt At Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP 1*tt rt 0 Q

Period of Record: 1/1/76 - 12/31/82 0 Lower Monitoring Level 0

r Ol r0 RC g 0 t0 rt r

0 At th 0

Ã C Q

C OVEAALL WIND DIAEC'I ION FAEOUEHCY WINO OIAECI IUHt H HNE NE EHE f. ESE SE SSE 5 SSW SW WSW W WNW Hw HNW TOTAL FAEQUENCVa 10 0 9 4 7 5 5 9 4 4 3 6 3.7 4 8 ~ 1 0 8 6 7.8 6.8 4.1 4.3 5.5 6.1 100.0 C3 rt QAx 'wlNO SPEfO TM/S)t '.335 OVfAAt.L WIND SPEED FAEOUEHCV

'1.565 3.353 5.588 8.210 11.'116 11.623 Qm AVE WIND SPEED {M/S)t

'WINO SPEED FAEQUfNCVC

0. 168 0.950 2.459 4.470 6.929 3.05 4 1.38 4 1.23 12.79 1.48 9.123 11. 400 0,08 0.00

-R THE COHVERSIOH FACTOR APPLIED TO TtlE WINO SPEFD CLASSES IS 0.441 8 I. 1. I. l. l. I. I. I. 1. I. I. I. 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 I 000 I 000 'I DOO I 000 1. 000 1. 000 10 2189. 2140. 2140. 2140. 2140. 2140. 2028. 2028. 2124. 2140. 2140. 2140. 2140. 2140. 2140. 2140.

II 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

Ol SIANCF 5 ANO 'lfRAAlt< IIEIOHTS IH METFAS AS FUNCTIONS Of DIAECTION FROM THE SITE:

DIAEC'I ION = 5 SSW SW 'WSw 'W WHW Nw NHw N NNE Hf. CHC E ESE. SE SSE DISTANCE 2189. 2140. 2140. 2140. 2140. 2140. 2028. 2028. 2124. 2140. 2140. 2140. 2140.- 2140. 2140. 214U.

ELEVAIIUH 0. 0. 0. 0. 0. 0. 0. 0. 0. D. 0. 0, 0.. 0. U. U.

12 16 15 13 2 0 I I

TABLE A-l4 O cn pn ttt to N at Shearon Harris Plant Site Input Information for Continuous Groundlevel Release V't 0

Calculations With the NRC XOQDOQ Program ta 0 at N

ta A

rN Card Type I Is an array (%OPT) of options, such that I do, 0 bypass. These options renaln ln t effect 'for all release points run. Thus, all release points oust have the sane ~ ssueptlons. 0 t t 0 Card Varlabl ~ Value Used In X V st V

K rt V>>

0 IOP1(l) tlon lo dlstrlbute caine as the first ttlnd-speed 0 c as! (If calns are ~ lready distributed by direction 0 In Card Iype C, IOPT(l) 0, and Card Type 5 ls to blank). If KOPT(I) l, the cain values of Card Type S are dlstrlbuted by dlractlon In tbe sane pro-portion as the dlractlon freqwncy of ulnd-speed VV class tuo.

O rt COP I (I) Option to Input joint freqwncy dlsirlbutlon data

~ s percent frequency.

0 3 TOPI(3) Option to coepute a sector spread for conparlson ulth centerline va'Iw In pur9a calculation ADOPT (ttoraally ~ I).

IOPT(1) tlon to plot short-ters X/4 valws wrsus prob-a Il (ty of occurrence (ltorually 0).

IOPT(S) Option to use cubic spline ln lieu of least square function for flttlne Interntttent releas ~

distr lbut Ion (tloral ly I).

(C) Option io ptetch radial seyeent I/4 and D/4 values (lto rue I ly I ).

rOPT(T) Option to punch output of I/4 and D/4 values of ihe points of Interest (ttoraally ~ I).

a rOPT(S) Option to correct I/4 and 0/4 values for open terrain recirculation.

I 9 IOPI(S) Option to correct X/Q and 0/Q values using site specific terrain reclrcul ~ lion data.

PD c c

TABLE A-14 (continued) O M re o Site Input Information for Continuous Groundlevel Release CD CD Shearon Harris Plant rs 0 Calculations With the NRC XOQDOQ Program O 0 at Dt la o r ctt Card Tartable Loeuottsc Value Used 1st X 0 C 0

.1 10 yOtl (lO) Optloa t~ uce 4>>cart alps curves (Norually ~ 0). 0 VV C

dt 1 11 yOP1(11) Optloa to calcul ~ te aaaual 2/l) averapec wltct 30 0 rrt0 rtlu 4>>9raa s ~ clorL loc'ofth ~ ast ~ south aad steat

~ ad 20 depre>> cec'tort for all others (No~lly ~ 0, 0 attd tbe co4>> util uce 22-1/2 dapree sectors). X CD

<<l CD 1-00 1l lilt 2OAL 1be asia title prlated at the beplaala9 of the output 1-9 NTft. 1be au>>ber of velocity cat>>port ~ c (oaxt~ of lt).

O rt S-10 NS1A lS 1be Dueler of stailllty cat>>perl ~ c (oaxl~ of 2) ts Om (I ~ lttays equals pasqulll stablllty class A, 2 ~ 9,

..., 2 - C).

11-1$ N(i l S 1be au>>ber of ~ lstaaces vltb terrala dat ~ for each sector. lbe amber of 4lstaaces aust be L4 saoe for ~ ach sector (fard lype 10](oaxl~ of 10).

1 s-20 IsN: IS lhe leer>>>>eat la porc>>at for tdttcli plotted results are prlal>>4 out (Normally ~ 1S). '-

3 2'I-2S NP11P( lbe au>>ster of titles of receptor typec (ceu, pard>>a, etc.) (Lard fype 13)(wxl~ of eipkt) 3 2S-30 Nf111 lS 1ae au>>bar of release exit polatc (aaxl~ of five).

3 31-3S KOA lS 1b>> a~r of dlstaacec of slt ~ speclflc c>>rrectloa factors for recirculatloa (oaxt-

~f 10).

'I-S fS.O 1he belpht lla Deters, above around level) ~ f tie 12.0

~eacured ulad prese>>ted la Lite $ >>lat f~ucacy

~ ate l(ard 1ype 2). ~ (for elevated/proust-level at>>ed release, us ~ the 10-sttter level uladc).

C I

C C

TABLE A-14 (continued) O M rtt ta p'tt Shearon Harris Plant Site Input Information for Continuous Groundlevel'elease td rt 0 Calculations With the NRC XOQDOQ Program ta 0 at M

ta O ttt rd Variable V 'g CD 0 g Type Co luvns Naoe Lor<<at Value Used In X t t nI A-20 DCCATS(1) ~

)FS;0 For each I: lhe half-Ilt>> (days) used ls thc I/O IOI.OO rt Q r

I~ I, J r ~ Icul ~ lions s It DCCAVS > 100, so decay vill 0 ts occur; ll DCCAVS c 0, deplellos tactor vill be 2.30 0" used ln lhe a/0 calcvl ~ lions; It DICAVS 0, I/O vill not be calcul ~ lod. (Nor<<ally, DICAYS(l) ~ 101, X si

-8.00 SI

{l) l-lcI (sl -0 00 )

l l-l S PCGAAD FS.D Plant grade>>lcvallos (fact above sea level). It t QI t

PttdtAD ~ 0.0 ~ DIST and Hl dat ~ Card Type 10 and ll <<ual bc ls <<>>ters. It ptGAAD c 0.0, DIST In 0. 00 O rt

, altos and Hl dale ln teat abov>> plant Vrade. It tt O~

ptCAAD v ~ .0 above DIST Is <<ll ~ a and HI dal ~ ls lect above s>> ~ level.

I - JS CAI H( I ) TF$ .4 Tbe nu<<ber ~ f hours ~ or percent ~ ~ f cal ~ tor I I ~ KSIA each slablllty catcyoryt If aOFI(t) 0, BLANK Insert blast card. (Net ~: I I Is slablllly class A, 2.0 ~ ~ .., 7 0).

I-00 I al0(K. I,J) a-l, IC The Joist trcIIII ncy dlstrlbutlao li hours {or

~ erccnl). Ihc values Ior IC (a) sectors are I I, NVTI. (It NOpl{l) read os each card for each co<<blsatlos ot vlsd-

0) specd class ( I) and stab!Illy class (J), lhe Iil, HV(t (It FOPT(1) loop to read these valve cycles first os dlrcc-

~ I) llos contlnvlna ls a cloclvlsc fashion) ~ lien os J ~ I ~ NSIA vlnd class and tidally on slablllly class.

I-S FS. ~ A correction tactor ~ pp lied to vIIId-speed classes. It UCDA < 0: oe corrections vill be 200.

<<ade. It OCON s 100: tbe vtnd-speed classes vill be converted tron <<Iles/haut lo

<<>>ters/second.

TABLE A-14 (continued) O v) pl Shearon Harris Plant Site Input Information for Continuous Groundlevel Release so rt 0 Calculations With the NRC XOQDOQ Program 0 sa so tD O tlat I

Card I Vari able n g

~oasans Nanc Lorna t Desert tlon Voluo Usod In X s. n

~T T

'-TS . IgtjtX(1) ~ ltfS.O TLe naxlwn wind speed ln each utnd-speed

.class, In either nil~ s/Lour or netars/ 0.75,3.50,7.50,12.50, V

Io 8 rt P

so second. (If given ln alias/hour, sct 18. 50, 25. 00, 26. 00 0 UCOR > 100.) 0 X <<!

Cat'd Types d and g ara read In for each correction factor and distance given, I I,NCOSt so tD s-1-00 VXDIST(r,l) ltfS.O The distance In nctars at uhlch correction All Dl.stances (.0 lil 16 laclors art given. These values arc read ln I Leglnnlng ulth soulL an4 proceeding In a cloctulsa 4lrectlon (walla of ID). O rt ts n~

1-00 VXCN(X.I)

X.l s 16 16f5.0 Correction factor to be applied to X/II an4 0/II values corresponds lo distances spcctf lcd All Factors 1.000 ln VXDIST.

Card Types d and g are repeated for ihe renalnlng dlslancas and corrcctfon factors.

~ I,NDIS.

Card Types 10 an4 11 are read In for ~ ach terrain distance and height glvcn, I 10 1-00 DIST(X,I) '!6f5.0 The distance ln wters at uhIch terrain Distances =Site IIoundar)l X-l,16 Lclghts arc glvcn. These values are rca4 ln bcglnnlng ulth soutL and proceeding ln Distances a cloct<<isa dtrcctton (nsxloua of tcn distances).

16f 5.0 'lhc lerraln heights (ln nctcrs. above plant 1-80 IIT (K, I )

X.1,16 grade level) corresponding to thc dtstanses All 1(eights ~ 0.0 specified ln thc DILl array (Card Type 10).

TLesc values are read ln thc sane order as thc DIST array. for ~ glvcn direction and distance, thc terrain height should be thc hlghcsl elevation bet~an thc source and that distance anp herc uithtn thc direction sector.

Card Types 10 and ll arc repeated for thc renalnlng distances and hclghts.

TABLE A-14 (continued) Q M rn p rn tD

0) to Shearon Harris Plant Site Input Information for Continuous Groundle~el Release ft 0 Calculations Vith the NRC XOQDOQ Program tD o fo N

Pl Card Yarlabl ~

O ill 0>

lygf., (dt)~s Volvo Used In X l o I 12 1-25 NPO IN I ( I ) The nuebar (naxlmm of 30) of receptor loca- 0 I

I 'I, NPITPE tions for a particular~captor type (such as 16,15,13,2,0,11 l0 the nueber of cous ~ gardens, or sl'te ft sa bounder les). 0 0

Card Types 13 and lt ara read ln for each receptor type, thus I I, NPTTPE X C ta 13 '1-16 T I TI.PT(I,J) LAN The tltl ~ (cars, gardens ~ ~ tc.) of the Site Boundary 16 receptor lype for the receplor locations Nearest Resident (Card Type lt) (a aaxlnuo of 16 spaces). 15 Garden 13 1-80 KOll(I N) 8(15, The receptor dlrectlon and distance. lbll Cow Hilk 2 0

Cl rt PTOIST) I,N) f5.01 Is the dlrectlon of Interest, such that Goat Mil.k ~ 0 O~

N I,NPOINI ( I ) South. 2 ~ SSII...., 16 ~ SSE, PTOIST ls lhe distance, ln notars, to the receptor Heat b Poultry 11 location. See Table A-l.

Card 1ypas )3 and It are repeated for the reaLalnlng receptor lypcs.

Card Types 15, 16, and lf read ln for each plant release point, thus I I ~ NEKIT 15 1-80 TITLE(I,J) 20At The tltl~ fol the fala ~ sa point %hose characterlstlcs are described on Card Types 16 and IT.

16 1-5 EXIT (I ) FS.O The vent average velocity (actors/second).

(Note: I f ~ 1005 gromd-level release ls 0 assuead, sct EIIT 0, OIANIN 0, and SLE'It 10 eaters).

16 6-10 0lhHTN, f5.0 The vent Inside dtauetar (neters). 0 11-15 HSTACK(I ) f5.0 The hetght of the vent rel ~ as ~ point (eaters ~ ~

J plant grade level). If release ls IOOX ~ le- 0.0 vatcd, Input ncgatlva of height.

16 16-20 llatOG(l ) f5.0 The height of the vent's bulldlng (neters ~

~ bove plant grade level). SS.O

TABLE A-14 (continued) O Ch I

rh (D Ol Harris Plant Site Input Information for Continuous Groundlevel Release D)

Shearon t rt 0 Calculations lfith the NRC XOQDOQ Program lO 0 Ia se ta A sa 0 g 0

Card Variable ra Iy~ C~o~s Nasa Volvo Used In X rt V'

0

'I6 21-25 CRSEC(I) fS.O The slnl~ cross-sectional area (or the 2161. 0 o vent's bulldlnR (sguar~ters). X 0C 26-30 'LEV(I) fS.O lhe ulnd helsht used for the vent ~ lavatory release (sctcrs. above plant Srade level). 10. 0 I6 3I-35 IIEAIR(I) f6.0 lhe vent heat eslsslon rat ~ (cal/sac)

(Norsa) I y 0) . 0.0 0 t7 rt

'A Q ~

'I RLSID(l) Al one I ~ tter Idhntlflcatlon for tbe release point.

2-S IPURGE(I) IPURGE I. 2 or 3 If the vent bas Inter-0 nlttant rclcascs. TLe I, 2 or 3 corres-ponds to DECAYS(I), DECAYS(2), or DECAYS(3)

(Card fype d), respectively, uhlthever Is used as ILe base for Interslttcnt re'lease calcul ~ lions (norsally no decay/no deplete I/4, such that IPURGE(l) ~ I); If ~ vent Las no Int ~ rslttcnt rcleascs, IPURGE 0.

6-10 NPURGE (I) IS . Tbe nucbcr of Intcrslt tent relcascs pcr year for this release point. 0 I I IS NPRQyl(l ) IS lha avera9c nusber of hours pcr lntcrslitent rclcas ~ . 0 Card Types 15, l6 and IT are repeated for the rcsalnlnR rclcas ~ points.

Card Iypcs I-IT say bc repeated for the neat case.

l e

0

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 APPENDIX B Sheet 1 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, 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.l.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 P1 and Rz values for the various exposure pathways (Tables 3.2-4 and 3.3-1 through 3.3-19, respectively).

B.l 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 P. presents the highest dose to any organ including the whole iz body resulting from inhalation of radionuclide "i" by a child. The following sections provide in detail the methodology which was used in calculating the P< values for inclusion into this ODCM.

The age group considered is the child because the bases for the Technical Specification 3.11.2.l.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 m3/yr from Table E-5 of Regulatory Guide 1.109, Revision 1. The inhalation dose factors for the child, DFA<, 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 DFA~.

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 APPENDIX B Sheet 2 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.l 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.

iz K'(BR) DFAz (B.l-l) where:

P.

iz Dose parameter for radionuclide "i" for the inhalation pathway, mrem/yr per pCi/m~;

K' constant of unit conversion; 106 pCi/pCi; BR The breathing rate of the children's age,group, m /yr; DFAz The maximum organ inhalation dose factor for the children's age group for radionuclide "i," mrem/pCi ~

The incorporation of breathing rate of a child (3700 m /yr) and the unit conversion factor results in the following equation:

P.

iz 7 E+ 9 DFA (B.1-2)

B-2

~ ~

1 V

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

~PENOXX 1 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. R< values have been 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.

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 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:

R.

iz K'BR)~ (DFAz), (B.2-1) where:

K'ose R.

iz factor for each identified radionuclide "i" of the organ of interest, mrem/yr per pti m/;s A constant of unit conversion; 106 pCi/pCi; (BR)~ Breathing rate of the receptor of age group "a,"

m3/yr; (DFAz) ~ 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.

Ae Grou a Breathin Rate m~ r Infant 1400 Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFA<)~ for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109, Revision 1.

B-4

4 Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 5 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.2 Ground Plane Pathwa The ground plane pathway dose factor is calculated by:

-A t Ri G I. K'K"(SF)DFG. (1-e )/A~ (B.2-2) where:

R.

io Dose factor for the ground plane pathway for each identified radionuclide "i" for the organ of interest, mrem/yr per pCi/sec per m

-2.

K'. A constant of unit conversion; 10'Ci/pCi;.

Klt A constant of unit conversion; 8760 hr/year; Ag The radiological decay constant for radionuclide "i,"

-1 sec 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 DFGz values is presented in Table E-6 of Regulatory Guide 1.109, Revision l.

SF The shielding factor (dimensionless);

(A shielding factor of 0.7 is suggested in Table E-15 of Regulatory Guide 1.109, Revision 1.)

0 j

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 6 of 15 DOSE PARAMETERS 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 Iz 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, PARTICULATES, 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:

-1 t E te Biv {1 e -Xitb iM i F ap m ia Y p E ~

+

pX

) +

-~itb (1-f f,) (*r (1-e Ei t e) Biv(1-e Lith (B. 2-3) pji where:

R. Dose factor for the cow milk or goat milk pathway, for identified radionuclide "i" for the organ of K',

each interest, mrem/yr per pCi/sec per m -2.

constant of unit conversion; 106 pCi/pCi; QF 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~;

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 B DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND Sheet TRITIUM 8 of 15 B.2.3 Grass Cow or Goat Milk Pathwa (continued)

Fm The stable element transfer coefficients, pCi/liter per pCi/day; Fraction of deposited activity retained on cow's feed grass',

(DFLg) ~ The organ ingestion dose for radionuclide "i" for the receptor in age group "a," mrem/pCi; E I The radiological decay constant for radionuclide ffi tf -1 sec e 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; B

iv 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);

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'.2.3 Grass Cow or Goat Milk Pathwa (continued)

Effective surface density for soil, Kg (dry soil)/m2; fP Fraction of the year that the cow or goat is on pasture; fs 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 1

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.

B-9.

l~

4'

~~

0

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 10 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM 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 Ri is based on X/Q:

K'K' 'F~QpU (DFLg)~ 0.75(0.5/H) (B.2-4) r ap where:

r Dose factor for the cow or goat milk pathway for tritium for the organ of interest, mrem/yr per pCi/m~;

Kt I 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~, was used in lieu of site-specific information.

Ii I

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDXX 8 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 r(1-e i e iv (1-e i b)

~B a F ap vp PAi E ~

itb) -i th (1-fpfs) ( r (1-e .

i e) +

iv . ) e...)

~

(B.2-S)

~

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.

Ff The stable element transfer coefficients, pCi/Kg per pCi/day; U

ap The receptor's meat consumption rate for age group "a,"

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 Sheet 12 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM

.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, Iz 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 Rq 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'K' 'FLU (DFLg) ~ 0. 75(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/m~.

All other terms are defined in Equations B.2-4 and B.2-5.

l 4

wE

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES > AND TRITIUM B.2.5 Ve 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 . (1 e litb) iv i ia aL Yv E

-l,E te B (g e

-A.

itb)

U fg e ~ih (

Y g

) +

PAi

) ) (B. 2-7)

Ei where:

Ri " Dose factor for vegetable pathway for radionuclide "i" for the organ of interest, mrem/yr per pCi/sec per m -2 K' constant of unit conversion; 10spCi/pCi; B-L3

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 14 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, B.2.5 Ve etation Pathwa (continued)

UL a

The consumption rate of fresh leafy vegetation by the receptor in age group "a," kg/yr; Us a

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'he 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/m2; Period of leafy vegetable exposure during growing season, sec; Factor to account for fractional deposition of radionuclide "i."

All other factors as defined before.

"1 2

V ei

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 15 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.5 Ve etation Pathwa (continued)

For radionuclides other than iodine, the factor Iq is equal to one. For radioiodines, the value of Iz 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 1.

In lieu of site-specific data default values for f~ and fz, 1.0 and 0.76, E

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 Rz is based on X/Q:

K'K' '[ UHEL' 00 55] (UFLL) 0.05 (0.5/H)] (B.2.8)

[

where:

Dose factor for the vegetable pathway for tritium for any organ of interest, mrem/yr per pCi/m .

All other terms remain the same as those in Equations B.2-4 and B.2-7.

~ $i 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

t (seconds) 1.73 E+05 (2 days) Table E-15 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 (DFL.) (mrem/pCi) Each radionuclide Table E-ll 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 Y (kr/m2 ) 2.0 Table E-15 t (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)

Bi (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 B-16

li Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE B-2 Parame'ters 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 (pCi/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

Y (kr/m2 ) 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)

Q (kg/day) 50 Table E-3 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 B-3 Parameters for 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 (DFCi) (mrem/pCi) Each radionuclide Tables E-ll 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 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 (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 (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-18

4.

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Sheet 1 of 1 APPENDIX C RADIOACTIVE LIQUID AND GASEOUS EFFLUENT 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 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 F. Outdoor Tank Area Drain Transfer Pump Monitor o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ REM-1MD-3530 G. Turbine Building Floor Drains Effluent . . . . . . REM-1MD-3528 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-1WV-3546

RM-1WV-3546-1 D. Waste Processing Building Vent Stack 5A REM-1WV-3547

RM-1WV-3547-1 Wide-Range Gas Monitor (WRGM)

ODCM C-3

ML18011A803

Text

1.0 INTRODUCTION

1.0 INTRODUCTION

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