ML18018B757

Offsite Dose Calculation Manual. W/840831 Ltr

ML18018B757
Person / Time
Site:	Harris
Issue date:	08/31/1984
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NLS-84-391, PROC-840831, NUDOCS 8409100070
Download: ML18018B757 (176)

Text

REGULATORY INFORMATION DISTRIBUTION S STEM (BIDS)

ACCESSION NBR: 8009100070 DOC ~ DATE: 80/08/31 NOTARIZED:; NO DOCKET FACIL:50"400 Shearon Harris. Nuclear Power Plant~ Unit ir Carolina 05000<l00 AUTH ~ NAME . AUTHOR AFFILIATION ZIMMERMANiS,R. Carolina Power 8 Light Co.

RECIP,NAME.. < RECIPIENT AFFILIATION DENTONgH ~ Ro Office of Nuclear Reactor Regulationr Director Manuals SUBJECT; "Shearon Harris Nuclear Power Plant Offsite Dose Calcu,lation ," 8/840831 ltr.

DISTRIBUTION CODE: A009D COPIES RECEIVED:LTR ENCL SIZE; TITLE! OR/Licensing Submittal: Appendix I NOTESi RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR LB3 BC 01 7 7 INTERNAL: ADM/LFMB 1 0 ELD/HDSl 19 1 , 0 NRR/DL/DRAB 1 0 NRR/Dl /TAPMG 1 1 NRR/DSI/AEB 1 0 NR METB 08 1 1 NRR/DSI'/RAB 10 1 1 0$ 1-RGN2 1 1 RGN2/DRSS/EPRPB 1 1 EXTERNAL: ACRS 11 b LPDR 03 1 1 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1 TOTAL NUMBER OF COPIES REQUJRED: L'TTR 27 ENCL 23 t

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CSEE Carolina Power & Light Company SERIAL: NLS-84-391 AUG 81 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 DOCKET NO. 50-400 OFFSITE DOSE CALCULATION MANUAL

REFERENCE:

Letter Dated July 30, 1984 (Serial: NLS-84-338)

From Mr. A. B. Cutter (CP&L) to Mr. H. R. Denton (NRC)

Dear Mr. Denton:

In accordance with a commitment in the referenced letter, Carolina Power &

Light Company hereby submits a copy of the Offsite Dose Calculation Manual (ODCM) for the Shearon Harris Nuclear Power Plant. The enclosed ODCM is submitted for your review and approval.

If you please contact Mr. Gregg A. Sinders at I

have any questions, (919) 836-8168.

Yours very truly, S. . 'mmerman Manager Nuclear Licensing Section GAS/mf (544GAS)

Enclosure

'cc w/

Enclosure:

Mr. B. C. Buckley (NRC) Mr. Wells Eddleman Mr. G. F. Maxwell (NRC-SHNPP) Mr. John D. Runkle Mr. J. P OtReilly (NRC RII Dr. Richard D. Wilson Mr. Travis Payne (KUDZU) Mr. G. 0. Bright (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Dr. J. H. Carpenter (ASLB)

Chapel Hill Public Library Mr. J. L. Kelley (ASLB)

Wake County Public Library Mr. S. Block 411 Fayettevilte Street + P. O. Box 1551 ~ Raleigh, N. C. 27602

/

I

SHEARON HARRIS QlCLEAR POWER PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCM)

DOCKET NO. STN 50-400 CAROLINA POWER 8 LIGHT COMPANY 0 S<Qe 409gQOO'700>QQQ<QQ

@DR pgoCW , poR

TABLE OF CONTENTS Section Title Page TABLE OF CONTENTS..............................................

LIST OF TABLES................................................. ill

~ ~ ~

LIST OF FIGURES................................................ v 1.0 I NTRODUCTION................................................... 1-1 2.0 LI(UID EFFLUENTS 2.1 Compliance with 10CFR20 (Liquids)........................ 2-1 2.2 Compliance with 10CFR50 (Liquids)..................... " ~ 2-8 3.0 GASEOUS EFFLUENTS 3.1 Monitor Alarm Setpoint Determination..................... 3-1 3.2 Compliance with 10CFR20 (Gaseous)........................ 3-12 3.3 Compliance with 10CFR50 (Gaseous)........................ 3-21 4.0'ADIOLOGICAL ENVIRONENTAL MONITORING PROGRAM.................. 4-1 5.0 I NTERLABORATORY COMPARISON STUDIES 5 .1 ObJective................................................

AL 5-1 5 ~2 Program o ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5-1 6.0 TOTAL DOSE (40CFR190 COMFORMANCE) 6.1 Compliance with 40CFR190..............................". 6-1 6.2 Calculations Evaluating Conformance with 40CFR190........ 6-1 6-3 Calculations of Total Body, Dose.......................... 6-2 6.4 T byroad Dose............................................. 6-3 6.5 Dose Projections......................................... 6-3

TABLE OF CONTENTS (cont.)

Section Title Page APPENDIX A - Meteorological Dispersion Factor Computations...........................;.......... A-1 APPENDIX B - Dose Parameters for Radioiodines, Particulates, and Tritium................................ 8-1 APPENDIX C - Lower Limit of Detection.......................... C-1 APPENDIX D - Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation Numbers....................... D-1

LIST OF TABLES Title Page 2.1-1 Liquid Effluent Release Tanks and Pumps.................... 2-13 2.2-1 A. values for the Adult for the Shearon Harris Nuclear 1%

Power Plant (SHNPP)........................................ 2-14 2.2-2 D ecay Factors.............................................. 2-16 3.1-1 Gaseous Source Terms....................................... 3-10 Constants.................................

Dose Factors and 3-11 Releases from SHNPP, Normal Operation...................... 3-17 3' 2 Distance to the Nearest Special Locations for SHNPP kli1 I'l (Ml 1 les) o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 3 18 3.2-3 Dose Factors for Noble Gases and Daughters................. 3-19 3.2-4 P; Values for an Infant for SHNPP......... ~ ................ 3-20 3.3-1 thru R Values for the Shearon Harris Nuclear Power Plant........ 3-29 3-19 4.1 SHNPP Radiological Environmental Monitoring Program........ 4-2

LIST OF TABLES (cont.)

Title Page A-1 thru Relative undepleted concentration, relative depleted A-4 concentration and relative deposition flux estimates for ground level releases for special locations for long-term releases......................................... A-3 A-5 thru Relative undepleted concentration, relative depleted A-12 concentration and relative deposition flux estimates for ground level releases for standard and segmented distance locations for long-term releases.................. A-8 A-13 thru SHNPP on-site joint wind frequency distributions for A-14 1976-1982.................................................. A-15 A-15 SHNPP site information to be used for ground level calculations with NRC "XO(DOg" Program..................... A-31 B-1 Par ameters 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

LIST OF FIGURES Title Page 2.1-1 Liquid Waste Process Flow Diagram.......................... 2-17 2.1-2 Liquid Effluent Flow Stream Diagram............."......... 2-18 3.1 SHNPP Gaseous Waste Streams Unit l......................... 3-47 3.2 Plant Airborne Effluent Release Points..................... 3-48 3.3 SHNPP Condenser Off-Gas System............................. 3-49 4.1-1 SHNPP Exclusion Boundary Plan.............................. 4-15 4.1-2 thru Shearon Harris Nuclear Power Plant Environmental 4.1-5 Radiological Sampling Points............................... 4-16

The Off-Site Dose Calculation Manual (ODCM) provides the information and meth-odologies to be used by Shearon Harris Nuclear Power Plant (SHNPP) to assure compliance with Specifications 3.11.1, 3.11.2, 3.11.3, and 3.11.4 of the SHNPP Technical Specifications. These portions are those related to liquid and gaseous radiological effluents. They are intended to show compliance with 10CFR20, 10CFR50.36a, Appendix I of 10CFR50, and 40CFR190.

The ODCM is based on "Westinghouse Standard Technical Specifications" (NUREG 0452), "Preparation of Radiological Effluent Technical Specifications for Nu-clear 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 and other con-trolled documents. These procedures will be utilized by the operating staff of SHNPP to assure compliance with technical specifications.

I 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'e properly reviewed and approved as indi-cated in the Administration Control Section Specification 6.14.2 of the SHNPP Technical Specifications.

1-1

LI()UID EFFLUENT 2.1 COMPLIANCE WITH 10CFR PART 20 (LI(UIDS) 2.1.1 Batch Releases A batch release is the discharge of liquid waste of a discrete volume. Batch releases from the SHNPP liquid radwaste system may occur from treated laundry and hot shower tanks, secondary waste treatment tank, waste monitor tanks, and waste evaporator condensate tanks. The principal sources of waste for these tanks are shown in Figure 2.1-1.

The liquid radwaste effluent streams are shown in Figure 2.1-2. A batch release represents the emptying of one tank only. No concurrent liquid batch releases (i.e., more than one tank at a time) are made from SHNPP. The liquid radwaste system discharges to the cooling tower blowdown line. Dilution flow depends primarily on the blowdown flow. If liquid effluent is diverted to the

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waste neutralization basin, some additional dilution may also occur at this

~

point. The blowdown flow rate, "B" is determined by the cooling tower basin

~

water .level. This water level is adjusted depending on the conductivity of the basin water. For the purpose of calculation, the assumed value of B is 16.5 cfs (7.4E3 GPM) as presented in the SHNPP FSAR Section 11.2.3. This value is presently interpreted as the average blowdown flow rate, but may be variable. If B is less than 16.5 cfs, then the measured flow rate should be used~

The sampling and analysis frequency and the type of analyses required by the SHNPP Technical Specifications are given in Table 4.11-1 of the specifica-tions. All applicable radiation monitoring instrument numbers are listed in Appendix D.

2.1.1.1 Prerel ease

- The radioactive content of each batch release will be determined prior to

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release in accordance with Table 4.11-1 of the SHNPP Technical Specifica-

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tions. Compliance with 10CFR20 will be shown in the following manner:

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2-1

a. thinimum acceptable dilution factor:

C.

1 DFo = Z NPC.

1 where:

DFo Mi nimum acceptabl e di 1 uti on factor determi ned from a gamma i sotopic analysi s of 1 i qui d effluent to be released C; = Concentration of radionuclide "i" in the batch to be released, pCi/ml MPCi = Maximum permissible concentration of radionuclide "i" from Appendix B, Table II, Column 2 of 10CFR20, pCi/ml DFB ( 10) (DFo)

E DFB = Conservative dilution factor used by SHNPP to calculate maximum release rate prior to release in order to assure compliance with 10CFR20 10 = A factor of 10 less than 10CFR20 limits as specified in Appendix B, Table II, Column 2. This factor represents one layer of conservatism for all releases at SHNPP DFo Hi nimum acceptabl e di 1 uti on factor per Equati on 2 . 1-1 2-2

b. Maximum release rate:

MRR =

2 (DFB)

MRR = Maximum release rate of the batch to be released, GPM B = Cooling tower blowdown flow rate, GPM 7.4 E3 GPM 2 = Engineering factor to prevent spurious alarms caused by deviations in the mixtures of radionuclides which affect the monitor response OF> = Minimum acceptable dilution factor (OFo) made conserva-tive by a factor of 10 per Equation 2.1-2

c. Monitor Alarm/Trip Setpoint:

Monitor alarm/trip setpoints are determined to ensure that the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas does not exceed the limits specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. An MPC of 2 E-4 pCi/ml has been established for noble gases dissolved or entrained in liquid effluents, based on the assumption that Xenon-135 is the controlling radionuclide.

Z C E CR = i i m 2-3

CR = Calculated monitor count rate above background, cps Ci = Concentration of radionuclide "i" in the batch to be released, pCi/ml Em

= The monitor efficiency for the mixture of radionuclides in the liquid effluent prior to dilution, cps/pCi/ml SP = 2 CR+ Bkg. (2.1-5)

CAUTION: This setpoint must be evaluated as conforming to the test of Section "e" below.

SP = Monitor alarm/trip setpoint, cps 2 = Engineering factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response (see determination of Equation 2.1-3)

CR = Calculated monitor count rate per Equation 2.1-4, cps Bkg. = Background count rate due to internal contamination and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with an uncontaminated fluid, cps

d. Calculated concentration at unrestricted area:

(C;) (MRR) (2.1-6)

Conci B

where:

Conc; Calculated concentration of radionuclide "i" at the unrestricted area, pCi/ml C; = Concentration of radionuclide "i" in the batch to be released, pCi/ml MRR = Maximum release rate of the batch to be released (see Equation 2.1-3), GPM B = Cooling tower blowdown flow rate, GPM 7.4 E3 GPM

e. 10CFR20 Prerelease Compliance Check:

Before initiating the batch release, perform one final check for compliance with 10CFR20. If the sum of the ratio of liquid con-centration to MPC for all radionuclides at the unrestricted area is less than or equal to 1, then 10CFR Part 20 limits have been met. The following equation must be true:

Z Conci/MPC; < 1 (2.1-7) 1 where:

Conc; Calculated concentration of radionuclide "i" at the unrestricted area per Equation 2.1-6, pCi/ml MPC 1~ = Maximum permissible concentration of radionuclide "i" from Appendix 8, Table II, Column 2, of 10CFR20, pCi/ml 2-5

2.1.1.2

~ ~ ~ Postrel ease The actual concentration of each radionuclide following a batch release from a tank will be calculated to show final compliance with 10CFR20 as follows:

a. Actual concentration at unrestricted area:

Conc k = 1 k) (2.1-8)

Vd where:

Concik = The actual concentration of radionuclide "i" at the unrestricted area during release "k," pCi/ml C; = Concentration of radionuclide "i" in the batch re-leased, pCi/ml yk

= Actual volume of liquid effluent released, during release "k," gal (see Table 2.1-1 for waste tank volumes and pump capacities).

Vd

= Actual volume of dilution water during release "k," gal (B) (tk) where:

8 = Cooling tower blowdown flow rate, GPN tk =, Duration of release "k," min 2-6

b. 10CFR20 Postrelease Compliance Check:

To show final compliance with 10CFR20, the followi'ng relation-ship must hold:

E (Conc.k ik /MPCi) < 1 where:

Conc;k = The actual concentration of radionuclide "i" during release "k" (from Equation 2.1-8), pCi/ml MPCi Maximum permissible concentration of radionuclide "i" from Appendix B, Table II, Column 2, of 10CFR20, pCi/ml 2.1.2 Continuous Releases A continuous release is the discharge of liquid wastes of a nondiscrete vol-ume; e.g., from a volume or system that has an input flow during the contin-uous release. Planned continuous releases do not presently occur at SHNPP, although the potential does exist in the Normal Service Water ( NSW) System and Emergency Service Water (ESW) System. The returns from the NSW System to the Circulating Water System are monitored by installed radiation monitors which are covered by Technical Specification 3.3.3.10. In addition, a monthly grab sample is taken in accordance with Technical Specification Table 4.11-1. If radioactivity is detected in either system, it will be eventually diluted by flow from the Circulating'Water System. Thus, diluted effluent concentrations can be either computed with knowledge of the circulating water flow and/or monitored by periodic sampling of the Cooling Tower Basin. In the event radioactivity is detected in the Emergency Service Water System, then ESW flow, the Cooling Tower Basin, and the return flow to the auxilliary reservoir will be periodically sampled. To show compliance with 10CFR20, the sum of the concentration of radionuclide "i" in the unrestricted area due to both continuous and batch releases divided by tHat isotope's MPC must again be less than l.

2-7

2.2 COMPLIANCE WITH 10CFR50 2.2.1 Cumulation of Doses The dose contribution from the release of liquid effluents will be calculated at least once every 31 days (monthly), and a cumulative summation of these total body and any organ doses will be maintained for each calendar quarter.

The dose contribution for all batch releases will be calculated using the following equation:

-x,.t

'E (Z (A tk -k Fk C

D k

(2.2-I) where:

D = The cumulative dose commitment to the total body or any organ z, from the liquid effluents releases, mrem; tk = The length of time of release "k" over which C;k and Fk are averaged for all liquid releases, hours; C The concentration of radionucl ide "i" in the undiluted liquid effluent during release "k" from any liquid release "k, " i/ml pC A.

lv The site related ingestion dose commi tment factor to the l1 total body or any organ z for each identi fied principal gamma and beta emitter, "i" mrem-ml per hr-pCi; Radiological decay constant of radionuclide "i", hr 0.693/ (tl/2) 1/2i Radi ol ogi cal hal f-1 i fe of radi onucl i de "i ", hr; tp average transport time to reach the poi nt of exposure, hr; 2-8

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the potable water pathway (see Appendix A, 2.a.

of Regulatory Guide 1.109, Rev. 1).

The near-field average dilution factor for C;k during any liquid effluent release "k." Defined as the ratio of the volume of undiluted liquid waste released to the product of the dilution volume from the site discharge structure to unrestricted teceiving waters times AF. (AF is the site-specific applicable factor for the mixing effect of the SHNPP discharge structure as defined in NUREG 0133.

According to NUREG 0133, Section 4.3 for plants with cooling towers, the factor AF shall be a number such that the product of the average blowdown flow to the receiving water body, in cfs and applicable factor AF, is 1000 cfs or less, i.e.,

(Avg. Blowdown) (AF) < 1000 cfs Thus:

V k

~~x (2. 2-2)

Where AF c 60 and Vk and Vd are as defined in Equation 2.1-8. In the case of a continuous release, cik = cooling tower basin concentration and/or measured concentration in the emergency service water return to the auxil1 iary reservoir; and Yk = Vd.

The dose factor Ai (see NJREG 0133, Section 4.3.1) was calculated for an adult for each isotope "i" using the following equation:

A.

1%

= 1.14 x 10 (

730 0

+ 21 Bf-1 ) DFiw (2.3-2) 2-9

where:

1.14 x 105 10 6

pCi pCi x 10 3

x ml 1

1 8760 yr hr 21 Adult fish consumption rate (from Table E-5 of Regulatory Guide 1.109, Rev. 1,) kg/yr; A.

1%

Dose factor A.

lw for an adult for each isotope "i" corresponding to dilution by the Cape Fear River and uptake at the Lillington Mater Facility with Dw = 13.95. (Values are given in Table 2.2-1).

730 = Adult water consumption rate (from Table E-5 of Regulatory Guide 1.109) Rev. 1, liters/yr.

Dw Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake for the adult water consumption.

13.95 for uptake at the municipal water facility at Lillington BF ~

Bioaccumulation factor for radionuclide "i" in fish (from Table A-1 of Regulatory Guide 1.109, Rev. 1,) pCi/kg per pCi/1.

DF ~

lg Dose conversion factor for radionuclide "i" for adults for a particular organ w (from Table E-ll of Regulatory Guide 1.109, Rev. 1,) mrem/pCi.

Table 2.2-1 present the A. values for an adult at SHNPP. Values of 1%

exp (-Kit ) are presented in Table 2.2-2 for each radionuclide "i". The sum i p of the cumulative dose from all batch releases for a quarter are compared to one-half the design objectives for total body and any organ. The sum of the cumulative doses from all batch releases for a calendar year are compared to the design objective doses. The following relationships should hold for the 2-10

SHNPP to show compl i ance wi th Technical Speci ficati on 3.11.1.2 of the Techni cal Speci fi cati ons for SHNPP t Uni 1.

For the calendar quarter, D < 1.5 mrem total body (2.2-4)

D < 5 mrem any organ (2.2-5)

For the calendar year, D < 3 mrem total body (2.2-6)

D < 10 mrem any organ (2.2-7) where:

D = Cumulative total dose to any organ ~ or the total body from batch releases, mrem; The quarterly limits given above represent one-half the annual design objec-tive of 10CFR50, Appendix I, Section II.A. If any of the limits in Expres-sions 2.2-4 through 2.2-7 are exceeded, a special report pursuant to SHNPP Technical Specification 6 .9.2 must be filed with the NRC. This report complies 10CFR 50, Appendix I, with Section IV.A of Appendix I of 10CRF50.

2.2.2 Projection of Doses Dose projections for this section are required at least once. per 31 days (monthly) in Technical Specification 4.11.1.3.

The doses will be projected using Equation 2.2-1. When the operational conditions for the projected month're to be the same as for the current month, the source term inputs into the equation for the projection can be taken directly from the current month' data. klhere possible, credit for expected operational evolutions (i.e., outages, increased power levels, major 2-11

planned liquid releases, etc.), should be taken in the dose projections. This may be accomplished by using the source-term data from similar historical operating experiences where practical.

2-12

TABLE 2.1-1 LIQUID EFFLUENT RELEASE TANKS AND PUMPS(l)

Radiation Effluent No. of PUMP CAPACITY ( m) Tank Volume Monitor Tank Tanks Process Recircul ation Identification Sec.

Waste Sample tank 35 100 25,000 REM-3542 Waste Evap-orator Cond-ensate tank 35 100 10,000 REM-3541 Waste Monitor Tank 35 100 25,000 REM-3541 Laundry 5 Hot shower tank 200 25,000 REM-3540 1

Reference SHNPP FSAR Tables 11.5.1-1 and 11.2.1-7 2-13

TABLE 2.2-1 YALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT 1.14 x 10 ( + 21 BFi) DFi D~= 1395 (MREM/HR PER MICRO-Ci/ML)

Nuclide Bone Liver T.Body Thyr oid Kidney Lung GI-LLI H-3 O.OOE 0 8.50E-01 8.50E-01 8.50E-Ol 8.50E-01 8.50E-Ol 8.50E-01 C-14 3.13E 04 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 Na-24 4.17E 02 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 P-32 4.62E 07 2.87E 06 1.79E 06 O.OOE 00 0.00E 00 0.00E 00 5.20E 06 Cr-51 O.OOE 00 O.OOE 00 1.29E 00 7.71E-01 2.84E-01 1.71E 00 3.23E 02 Mn-54 O.OOE 00 4.40E 03 8.40E 02 O.OOE 00 1.31E 03 0.00E 00 1.35E 04 Mn-56 O.OOE 00 1.11E 02 1.97E 01 O.OOE 00 1.41E 02 O.OOE 00 3.54E 03 Fe-55 6.75E 02 4.66E 02 1.09E 02 0.00E 00 0.00E '00 2.60E 02 2.67E 02 Fe-59 1.06E 03 2.50E 03 9.59E 02 O.OOE 00 O.OOE 00 6.99E 02 8.34E 03 Co-58 O.OOE 00 9.36E 01 2.10E 02 O.OOE 00 O.OOE 00 O.OOE 00 1.90E 03 o-60 O.OOE 00 2.69E 02 5.93E 02 O.OOE 00 O.OOE 00 O.OOE 00 5.05E 03 i-63 3.19E 04 2.21E 03 1.07E 03 O.OOE 00 0.00E 00 O.OOE 00 4.61E 02.

i-65 1.30E 02 1.68E 01 7.68E 00 O.OOE 00 O.OOE 00 O.OOE 00 4.27E 02 Cu-64 0.00E 00 1.05E 01 4.91E 00 0.00E 00 2.64E 01 0.00E 00 8.92E 02 Zn-65 2.32E 04 7.38E 04 3.34E 04 O.OOE. 00 4.94E 04 O.OOE 00 4.65E 04 Zn-69 4.94E 01 9.44E Ol 6.57E 00 O.OOE 00 6.14E 01 O.OOE 00 1.42E 01 Br-83 O.OOE 00 O.OOE 00 4.07E 01 O.OOE 00 O.OOE 00 O.OOE 00 5.86E 01 Br-84 O.OOE 00 O.OOE 00 5.27E 01 0.00E 00 O.OOE 00 O.OOE 00 4.14E-04 Br-85 O.OOE 00 O.OOE 00 2.16E 00 O.OOE 00 O.OOE 00 O.OOE 00 1.00E-15 Rb-86 O.OOE 00 1.01E 05 4.71E 04 O.OOE 00 O.OOE 00 O.OOE 00 1.99E 04 Rb-88 O.OOE 00 2.90E 02 1.54E 02 O.OOE 00 O.OOE 00 O.OOE 00 4.01E-09 Rb-89 O.OOE 00 1.92E 02 1.35E 02 O.OOE 00 O.OOE 00 O.OOE 00 1.12E-ll Sr-89 2.40E 04 O.OOE 00 6.87E 02 O.OOE 00 O.OOE 00 O.OOE 00 3.84E 03 Sr-90 5.89E 05 O.OOE 00 1.45E 05 0.00E 00 O.OOE 00. O.OOE 00 1.70E 04 Sr-91 4.41E 02 O.OOE 00 1.78E 01 O.OOE 00 O.OOE 00 O.OOE 00 2.10E 03 Sr-92 1.67E 02 O.OOE 00 7.23E 00 0.00E 00 O.OOE 00 O.OOE 00 3.31E 03 Y-90 6.33E-01 O.OOE 00 1.70E-02 O.OOE 00 O.OOE 00 O.OOE 00 6.71E 03 Y-91M 5.98E-03 O.OOE 00 2.32E-04 O.OOE 00 O.OOE 00 O.OOE 00 1.76E-02 Y-91 9.28E 00 O.OOE 00 2.48E-Ol O.OOE 00 O.OOE 00 O.OOE 00 5.11E 03 Y-92 5.56E-02 O.OOE 00 1.63E-03 O.OOE 00 O.OOE 00 0.00E 00 9-74E 02 Y-93 1.76E-01 O.OOE 00 2.48E 00 O.OOE 00 O.OOE 00 O.OOE 00 5.05E 02 Zr-95 4. 21E-01 1.35E-01 9.14E-02 O.OOE 00 2.12E-01 O.OOE 00 4.28E 02 Zr-97 2.33E-02 4.69E-03 2.15E-03 O.OOE 00 7.09E-03 O.OOE 00 1.45E 03 Nb-95 4.47E 02 2.49E 02 1.34E 02 O.OOE 00 2.46E 02 O.OOE 00 1.51E 06 Mo-99 O.OOE 00 1.29E 02 2.45E 01 O.OOE 00 2.92E 02 O.OOE 00 2.99E 02 Tc-99m 1.03E-02 2.92E-02 3.72E-01 0.00E 00 4.44E-01 1.43E-02 1.73E 01 c-101 1.06E-02 1.53E-02 1.50E-01 O.OOE 00 2.76E-01 7.83E-03 4.60E-14 u-103 5.53E 00 0.00E 00 2.38E 00 O.OOE 00 2.11E 01 0.00E 00 6.46E 02 RU-105 4.60E-01 O.OOE 00 1.82E-01 O.OOE 00 5.95E 00 O.OOE 00 2.48E 00 RU-106 1.63E 01 O.OOE 00 2.07E 00 0.00E 00 3.16E 01 0.00E 00 1.06E 03 Ag-110M 4.78E 00 4.42E 00 2.63E 00 O.OOE 00 8.70E 00 O.OOE 00 1.81E 03 2-14

elide Bone Liver T.Body Thyroid Kidney ~Lun GI-LLI Te-125M 2.58E 03 9.36E 02 3.81E 02 7.77E 02 1.05E 04 O.OOE 00 1.03E 04 Te-127M 6.52E 03 2.33E 03 7.95E 02 1.67E 03 2.65E 04 0.00E 00 2.19E 04 Te-127 1.06E 02 3.81E 01 2.29E 01 7.85E 01 4.32E 02 O.OOE 00 8.36E 03 Te-129M 2.48E 00 2.55E 01 1.08E Ol 2.35E 01 2.85E 02 0.00E 00 3.44E 02 Te-129 1.87E-01 7.01E-01 4.55E-OO 1.43E-Ol 7.85E-02 O.OOE 00 1.41E-01 Te-131M 1.67E 03 8.15E 02 6.79E 02 1.29E 03 8.26E 03 O.OOE 00 8.09E 04 Te-131 1.90E 01 7.93E 00 5.99E 00 1.56E 01 8.32E 01 O.OOE 00 2.69E 00 Te-132 2.43E 03 1.57E 03 1.47E 03 1.73E 03 1.51E 04 O.OOE 00 7.43f 04 I-130 3.16E 01 9.33E 01 3.68E 01 7.91E 03 1.46E 02 O.OOE 00 8.04E 01 I-131 1.74E 02 2.49E 02 1.43E 02 8.16E 04 4.27E 02 O.OOE 00 6.57E 01 I-132 8.50E 00 2.27E 01 7.95E 00 7.95E 02 3.62E Ol O.OOE 00 4.27E 00 I-133 5.94E 01 1.03E 02 3.15E 01 1.52E 04 1.80E 02 O.OOE 00 9.29E 01 I-134 4.44E 00 1.21E 01 4.31E 00 2.09E 02 1.92E 01 O.OOE 00 1.05E I-135 1.85E 01 4.86E 01 1.79E 01 3.20E 03 7.78E Ol 0.00E 00 5.48E 01 Cs-134 2.98E 05 7.10E 05 5.80E 05 O.OOE 00 2.30E 05 7.62E 04 1.24E 04 Cs-136 3.12E 04 1.24E 05 8.87E 04 0.00E 00 6.86E 04 9.40E 03 1.40E 04 Cs-137 3.82E 05 5.23E 05 .3.42E 05 O.OOE 00 1.77E 05 5.90E 04 1.01E 04 Cs-138 2.65E 02 5.23E 02 2.59E 02 0.00E 00 3.84E 02 3.79E 01 2.23E-03 Ba-139 1.51E 00 1.07E-03 4.41E-02 O.OOE 00 1.00E-'03 6.08E-04 2.67E 00

. Ba-140 3.15E 02 3.96E-01 2.06E 01 0.00E 00 1.35E-01 2.27E-01 6.49E 02 Ba-141 7.31E-01 5.53E-04 2.47E-02 O.OOE 00 5.14E-04 3.14E-04 3.45E-10 a-142 3.31E-01 3.40E-04 2.08E-02 0.00E 00 2.87E-04 1.92E-04 4.66E-19 a-140 1.64E-01 8.29E-02 2.19E-02 O.OOE 00 O.OOE 00 O.OOE 00 6.09E 03 a-142 8.42E-03 3.83E-03 9.54E-04 0.00E 00 O.OOE 00 O.OOE 00 2.80E 01 Ce-141 7.80E-02 5.28E-02 5.99E-03 O.OOE 00 2.45E-02 O.OOE 00 2.02E 02 Ce-143 1.38E-02 1.02E 01 1.13E-03 0.00E 00 4.48E-03 O.OOE 00 3.80E 02 Ce-144 4.07E 00 1.70E-OO 2.18E-01 O.OOE-OO 1.01E 00 O.OOE 00 1.38E 03 Pr-143 6.05E-01 2. 43E-01 3.00E-02 O.OOE 00 1. 40E-Ol 0.00E 00 2.65E 03 Pr-144 1.98E-03 8.22E-04 1.01E-04 O.OOE 00 4.64E-04 O.OOE 00 2.85E-10 Nd-147 4.14E-01 4.78E-01 2.86E-02 O.OOE 00 2.80E-01 0.00E 00 2.30E 03 W-187 2.97E 02 2.48E 02 8.67E 01 O.OOE 00 O.OOE 00 0.00f 00 8.12E 04 Np-239 3.56E-02 3.50E-03 1.93E-03 O.OOE 00 1.09E-02 0.00E 00 7.17E 02 2-15

Tabl e 2.2-2 DECAY FACTORS

'Pt* -x.t *

"'h Radionuclide i(hr ) e Radionuclide i(hr )

> P H-3 6.40E-6 1.00 Zr-95 4.51E-4 9.99E-01 C-14 1.38E-8 1.00 Zr-97 4.10E-2 6.11E-01 F-18 3.79E-l 1.06E-02 Nb-95 8.21E-4 9.90E-Ol Na-24 4.62E-2 5.74E-1 No-99 1.05E-2 8.92E-1 P-32 2.02E-3 9.76E-1 Tc-99m 1.15E-1 2.52E-1 Cr-51 1.04E-3 9.88E-1 Tc-101 2.93 5.37 E-16 Mn-54 9.24E-S 9.99E-1 Ru-103 7.34E-4 9.91E-1 Nn-56 2.69E-1 3.96E-2 RU-105 1.56E-1 1.54E-1 Fe-55 2.93E-5 1.00 Ru-106 7.84E-5 9.99E-1 Fe-59 6.47 E-4 9.92E-1 Ag-110m 1.14E-4 9.99E-1 Co-58 4.08E-4 9.95E-1 Sb-124 4.79E-4 9.94E-1 Co-60 1.50E-5 1.00 Te-125m 4.98E-4 9.94E-1 Ni-63 8.24E-7 1.00 Te-127m 2.65E-4 9.97E-1 Ni-65 2.75E-l 3.69E-2 Te-127 7.37E-2 4.13 E-1 CU-64 5.46E 5.19E-1 Te-129m 8.59E-4 9.90E-1 Zn-65 1.18E-4 9.99E-1 Te-129 5.97E-l 7.74E-1 Zn-69 7.29E-1 1.59E-4 Te-131m 2.31E-2 7.58E-1

-83 2.90E-1 3.08E-2 Te-131 1.66 2.23E-9

-84 1.31 1.49E-7 Te-132 8.86E-3 8.99E-1 r-85 1.4E-1 0.00 I-130 5.60E-2 5.11 E-1 Rb-86 1.55E-3 9.82E-1 I-131 3.59E-3 9.58E-1 Rb-88 2.35E-O 5.66 E-13 I-132 3.01E-1 2.70E-2 Rb-89 2.74 5.25E-15 I-133 3.33E-2 6.71E-l Sr-89 5.71E-4 9.93 E-1 I-134 7.90E-l 7.64E-5 Sr-90 2.78E-6 1.00 I-135 1.05E-1 2.84E-1 Sr-91 7.29E-2 4.17E-1 Cs-134 3.84E-5 1.00 Sr-92 2.56E-1 4.63E-2 Cs-136 2.20E-3 9.74E-1 Y-90 1.08E-2 8.78E-1 Cs-137 2.62E-6 1.00 Y-91m 8.36E-1 4.40E-5 Cs-138 1.29 1.89E-7 Y-91 4.94E-4 9.94E-1 Ba-139 4.99E-,1 2.51E-3 Y-92 1.96E-1 9.52E-2 Ba-140 2.26E-3 9.73E-1 Y-93 6.80E-2 4.42E-1 Ba-141 2.28 1.31E-12 Ba-142 3.88 6.02E-21 Pr-143 2.12E-3 9.75E-1 La-140 1.58E-2 8.27E-l P r-144 2.41 2.76E-13 La-142 4.50E-l 4.52E-3 Nd-147 2.61E-3 9.69E-1 Ce-141 8.89E-4 9.89E-1 W-187 2.90E-2 7.06 E-1 Ce-143 2.09E-2 7.78E-1 Np-239 1.23E-2 8.63E-1 Ce-144 1.02E-4 9.99E-1

• Note: All values less than lE-25 are reported as 0.

2-16

Figure 2.1-1 LIQUID WASTE PRO FLOW DIAGRAM WPB LABORATORY STORAGE TANKS SAMPLE SINKS DRAINS FLOOR DRAIN STORAGE F ILTRATION REVERSE DEMINERALIZER WASTE MONITOR SUMP TANKS OSMOSIS TANKS R EV EBS E OS MOB IS CONCENTRATES DISTILLATE EVAPORATOR TREATED

. DETERGENT STORAGE FILTRATION REVERSE DEMINERALIZER LAUNDRY'OT DRAIN SUMPS TANKS OSMOSIS SHOWER TANKS PRIMARY SAMPLE SINKS DRAIN SUMPS'TORAGE EQUIPMENT TANKS FILTRATION WASTE EVAPORATOR D EMINERALIZER FILTRATION EVAPORATOR CONDENSATE TANK LOW TURB INE CONDUCTIVITY FILTRATION DEMINERALIZER SECONDARY BUILDING STORAGE TANKS WASTE SUMPS SAMPLE TANK 0 I ST ILLATE HIGH CONDUCTIVITY EVAPORATOR STORAGETANKS NOTE: SOLID WASTE STREAMS RESULTING FROM LIQUIDWASTE PROCESSING ARE NOT SHOWN

Figure 2.1-2 LIQUID EFFLUENT FLOW STREAM DIAGRAM TREATED LAUNDRY& TREATED LAUNDRY&

HOT SHOWER TANK HOT SHOWER TANK REM R EM-1WL-3640 z

0 SECONDARY WASTE 0 SAMPLE TANK 0

K 0I-z REM 0

00 REM-21WS-3642 WASTE NEUTRALIZATION WASTE MONITOR WASTE MONITOR BASIN TANK TANK REM REM-2 I WL-3641 LEGEND: TANK OR BASIN . HARRIS LAKE WASTE EVAPORATOR CONDENSATE TANK WASTE EVAPORATOR CONDENSATE TANK O RADIATIONEFFLUENT MONITOR PUMP

GASEOUS EFFLUENTS In accordance with Carolina Power 5 Light's corporate ALARA policy, batch gaseous released from SHNPP will be performed considering meteorological parameters as well as operational concerns in order to minimize radiation doses to off-site populations.

Radioactivity releases through the steam generator flash tank can only occur when significant primary-to-secondary leakage exists within the steam gener-ators. At SHNPP, steam from the flash tank can be routed to either the feed-water heaters or to the main condenser. Detection of primary-to-secondary leakage is accomplished most effectively by continuously monitoring the con-denser air vacuum line. Liquid steam generator blowdown is continuously monitored. The liquid blowdown is routed to the main condenser or, if required, can be diverted to the Secondary Waste Treatment System.

3.1 MONITOR ALARM SETPOINT DETERMINATION This procedure determines the monitor alarm setpoint that indicates if the dose rate in the unrestricted areas due to noble gas radionuclides in the gaseous effluent released from the site to areas at and beyond the site boun-dary exceeds 500 mrem/year to the whole body or exceeds 3000 mrem/year to the skin.

Gaseous effluent release points at SHNPP are shown in Figures 3.1, 3.2, and 3.3. The radioactivity monitors for each vent stack and for specific effluent streams are shown in Figures 3.1 and 3.2.

If two simultaneous releases out of one vent stack occur, calculate the set-point for each type of release and use the lowest setpoint obtained.

The methodology described in Section 3.1.2 provides an alternative means to determine monitor alarm setpoints that may be used when an analysis of batch

~ ~

releases is performed prior to release.

3-1

3.1.1

~ ~ Set oint Based on Conservative .Radionuclide Mix (Ground-level Releases)

The following setpoint calculation applies to a gaseous release via the Plant Vent Stack I, Waste Processing Building Vent Stack 5, and the Turbine Building Vent Stack 3A (condenser air vacuum) when determining:

~ Continuous release yia Plant 'Vent Stack I.

~ Continuous release via the condenser air vacuum through Vent Stack 3A.

~ Continuous mode release for containment purge via Vent Stack 1.

~ Batch mode, release of containment purge or pressure relief via Plant Vent Stack 1.

~ Batch release of waste gas decay tanks via Vent Stack 5.

3.1.1.1 Determine the "mix" (noble gas radionuclide composition) of the gaseous effluent.

a. Determine the gaseous source terms that are representative of the "mix" of the gaseous effluent. Gaseous source terms are the noble gas activities in the effluent.

Gaseous source terms were obtained from the FSAR Table 11.3.3-1 and given in Table 3.1-1 or gaseous source terms can be obtained from analysis of the gaseous effluent.

b. Determine Si (the fraction of the total noble gas radioactivity in the gaseous effluent comprised by noble gas radionuclide "i")

for 'each individu'al noble gas radionuclide in the gaseous efflu-ent.

3-2

The radioactivity of noble gas radionuclide "i" 'in the gaseous ef f1 uent fr om Tabl e 3.1-1 or from analysis of gaseous effluent to be released.

3.1.1.2 Determine () (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent [pCi/sec]) based upon the whole body exposure limit of 500 mrem/year by:

500 where:

(7xq) The highest calculated annual average relative dispersion factor for any area at or beyond the site boundary for all sectors (sec/m ).

2.0E-6 sec/m 3 from Table A-1, Appendix A.

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

3.1.1.3 Oetermine 0 (the maximum acceptable release rate of all gas radio-nuclides in the gaseous effluent [pCi/sec]) based upon the skin expo-sure limit of 3000 mrem/yr by:

3000 Li+1.1M; = The total skin dose factor due to emissions from noble gas radionuclide "i" (mrem/yr/pCi/m ) from Table 3.1-2.

3-3

3.1.1.4

~ ~ ~

~

Determine C, the maximum acceptabl e total radioactivity concentra-

~

tion of all noble gas radionuclides in'he gaseous effluent [pCi/cc].

~ ~ ~ ~

(2.12 E-3) q (3.1-4)

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

where:

The maximum effluent flow rate at the point of release (cfm) based on design flow rates.

22,650 cfm (Turbine Bldg. Vent Stack 3A).

207,000 cfm (Waste Processing Bldg. Vent Stack 5).

103,500 cim (Waste Processing Bldg. Vent Stack 5A).

390,000 cfm (Plant Vent Stack 1).

2.12 E-3 .Unit conversion factor to convert pCi/sec/cfm to pCi/cc.

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

CR (C ) (E,)

Obtained from the appl icable ef fluent monitor efficiency (cpm/pCi/cc).

3.1.1.6 s ~ ~ Determine the HSP, the monitor high alarm setpoint including back-ground I:cpmj by:

HSP TmCR + Bkg where:

m Fraction of the radioactivity from the site that may be released via the monitored pathway to en-sure that the site boundary limit is not exceeded due to simultaneous releases from several path-ways.

0.03 for Turbine Bldg. Vent Stack 3A.

0.29 for Waste Processing Bl dg. Vent Stack 5.

0.14 for Waste Processing Bldg. Vent Stack 5A.

0.54 for Plant Vent Stack l.

Bkg The background count rate (cpm) due to internal contamination and the radiation levels in the area in which the monitor is installed when the detec-tor sample chamber is filled with uncontaminated air.

3.1.2 Alternative Set oint Determination Method Based on Gaseous Effluent Anal sis Prior to Release The following method applies to setpoint determinations from plant vent stacks during the operational conditions listed below and when the gaseous effluent is sampled prior to release:

~ Batch mode release of containment pressure relief.

~ Batch release of waste gas decay tanks.

3-5

3.1.2.1

~ ~ ~ Determine the maximum allowable dischar ge flow rate prior to dilu-tion.

~

~

a. Determine f, the maximum acceptable gaseous flow rate from containment or from the Waste Gas Decay Tanks (cfm), based upon the whole body exposure limit by:

0.848 T m

(3. 1-6)

(77q) f Ki Ci where:

m Fraction of the radioactivity from the site that may be r el eased vi a the moni tored pathway to ensure that the si te boundary 1 imi t i s not exceeded due to simultaneous releases from several pathways (see Section 3.1.1.6 earlier).

(Txcc')

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

2.0E-6 sec/m from Table A-l, Appendix A.

Ki The total whole body dose factor due to gamma emissions from noble gas radionuclide (mrem/year/pCi/m ) from Table 3.1-2.

Ci The radioactivity concentration of nobl e gas radionuclide "i" in the gaseous effluent (pCi/cc) from the analysis of the gaseous effluent to be released.

3-6

0.848 A combined numerical conversion factor consisting of the whole body dose limit of 500 mrem/y'r times a conversion constant of 2.12 E-3 to convert cc/sec to cfm, times 0.80, an engineering correc-tion factor to prevent spurious alarms.

b. Determine f based upon the 'skin exposure limit by:

5.09 T (3.1-7)

(M) 3 I.(L,. + 1..1 M.) C,.j where:

The total skin dose factor due to emissions from noble gas radionuclide "i" (mrem/year/pCi/m ) from Table 3.1-2.

5.09 A combined conversion factor consisting of the skin dose limit of 3000 mrem/yr, times a conver-sion constant of 2.12 E-3 to convert cc/sec to cfm, times 0.80, an engineering factor to prevent spurious alarms.

c. The rate at which the noble gas activity is released from the containment during purging or pressure relief or from the Waste Gas Decay Tanks shall not exceed the smaller of the two "f" val-ues calculated in Steps a and b above.

3.1.2.2 Determine the monitor setpoint equivalent to the maximum allowable discharge flow rate:

a. Determine Cm, the maximum radioactivity concentration of all noble gas radionuclides to be released during containment purge or pressure relief via Plant Vent Stack 1 or Waste Gas Decay Tanks discharge via the Waste Processing Bldg Vent Stack 5 after dilution by other discharges in the respective stacks (pCi/cc):

3-7

ct The total radioactivity concentration of all noble gas radionuclides in the gas to be discharged from the containment or Waste Gas Decay Tanks prior to dilution (pCi/cc).

The maximum acceptable gaseous flow rate from containment or from the Waste Gas Decay Tanks (cfm).

The maximum desi gn vent stack flow rate ( see Section 3.1.1.4 earlier) .

b. Determine CR, the calculated monitor count rate above background attributed to the radionuclides [cpmj.

CR is obtained by using the applicable effluent monitor efficiency "Em" (cpm/pCi/cc):

CR (C ) (E )

c. Determine HSP, the monitor high alarm setpoint including background [cpm] by:

HSP CR + Bkg (3. 1-10 )

Bkg Monitor background (cpm).

d. The monitor HSP shall be set at or below the calculated value during containment purges or releases from the Waste Gas Decay Tanks. If containment purges or pressure relief or Waste Gas Decay Tanks releases are made while other sources of noble gas activity are being released from their respective stacks, the monitor HSP shall not exceed the calculated value determined in Section 3.1.1.

3-8

TABLE 3.1-1 GASEOUS SOURCE TERMS Condenser Air Containn nt Purge Plant Vent Release via Vacuun via or Presure Relief via Gas Decay Tanks via Vent Stack 1 Vent Stack 3A Vent Stack 1 Vent Stack 5 Rad(onucl (de ((( (C(~/) S( ()( (~C(/ r) S( ((( (C(/yr) S) ()( (Ci/yr)

Kr-83m 0.00E 00 O.OX 00 O.KE 00 O.OX 00 1.X N 3.78E-04 0.0X 00 0.0X 00 Kr-89n 3.X 00 2.16E-02 2.CE 00 2A4E-02 1.2E 01 4.53E-03 0.00E 00 O.KE 00 Kr-85 O.OX 00 O.KE 00 O.KE 00 O.KE 00 4.0E 00 1.51E-03 2.1E 02 9.81E-01 Kr-87 1JX N 7.19'.60E-02 O.KE N 0.0X 00 2.X 00 7.56E-04 0.00E 00 0.0X 00 Kr-88 5.X 00 3.X 00 3.66E-02 1.6E 01 6.05E-03 0.00E 00 0.00E 00 Kr49 O.OX N O.OX N 0.0X 00 O.KE 00 0.5K N O.KE N 0.5K 00 0.0X 00 Xe-131m 0.00E 00 0.0X 00 0.5K 00 O.KE 00 1.X 01 3.78E-03 3.X 00 1.4X-02 Xe-133m 2.X 00 lA4E-02 1;X N 1.22E-02 4.X 01 1.62E-02 0.5K 00 0.0X 00 Xe-133 1.2E 02 8.63E-01 7.2E 01 8.78E-01 2.5E 03 9 44E 01 1.0E 00 4.67E-03 Xe-139n O.OX 00 O.OX 00 O.OX N 0 OX 00 O.X 00 0;00E1 O.KE 00 0.5K 00 Xe-135 7.0E 00 5.04E-02 4.X 00 4.88E-02 5.9E Ol 2.2X 02 0.00E 00 O.KE 00 Xe-137 0.5K N O.OX 00 O.OX 00 O.OX 00 O.OX N 0.0X 01 O.KE 00 0.5K 00 1.CE 00 7.19E43 O.OX 00 O.OX 00 O.OX 00 O.OX 01 0.00E 00 0.0X 00 8.20E 01 2.64E 03 2.14E 02 Source terms are based upon GALE Code (see SHNPP FSAR Table 11.3.3-1) and not actual releases. These values only apply to routine releases and should not be taken as a complete inventory of noble gases in an emergency situation.

3-9

TABLE 3.1-2 DOSE FACTORS AND CONSTANTS Total Whole Body Total Skin Dose Factor Dose Factor (Ki ) (L; + 1.1 Mi)

Radionuclide (mrem/yr/ Ci/m ) mrem/yr/ Ci/m )

Kr-83m 7.56E-P 2.12E1 Kr-85m 1.17E3 2.81E3 Kr-85 1.61E1 1.36E3 Kr-87 5.92E3 1.65E4 Kr-88 1.47E4 1.91E4 Kr-89 1.66E4 2.91E4 Kr-90 1.56E4 2.52E4 Xe-131m 9.15E1 6.48E2 Xe-133m 2. 51E2 1.35E3 Xe-133 2.94E2 6.94E2 Xe-135m 3.12E3 4.41E3 Xe-135 1.81E3 3.97E3 Xe-137 1.42E3 1.39E4 Xe-138 8.83E3 1.43E4 Ar-41 8.84E3 1. 29E4

• Regulatory Guide 1.109, Rev. 1, Table 8-1 multiplied by (1.0 E6 pCi/pCi).

• 7.56E-2 = 7.56 x 10 2 3-10

COMPLIANCE WITH 10CFR20 (GASEOUS) 3.2.1 Noble Gases The gaseous effluent monitors setpoints are utilized to show compliance with 10CFR20 for noble gases. However, because they are based upon a conservative mix of radionuclides, when using Table 3.1-1, the possibility exists that the setpoints could be exceeded and yet 10CFR20 limits may actually be met.

Ther efore, the following methodology has been provided in the event that if the alarm trip setpoints are exceeded, a determination may be made as to whether the actual releases have exceeded 10CFR20.

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 with 10CFR20.

(3.2-1) 500 mrem/yr (Li + 1.1 Mi) (770) qi < 3000 mrem/yr (3.2-2) 1 v iv where:

(~X g) = The highest annual average relative dilution for all vent stack releases for areas at or beyond the site boundary sec/m .

2.0E-6 sec/m from Table A-l, Appendix A for ground level releases in the NNE sector at the site boundary.

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

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

3-11

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

The ratio of the tissue to air absorption coeffi-cients over the energy range of the photon of interest, mrem/mrad (reference, NUREG 0133).

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

The determination of limiting location for implementation of 10CFR20 for noble gases is a function of the radionuclide mix, isotopic release rate, and the meteorology.

The 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/g values utilized in the equations for implementation of 10CFR20 is based upon the maximum long-tenn annual average (~X 9) in the unrestricted area. Table 3.2-2 presents the distances from SHNPP to the nearest area for each of the 16 sectors as well as to the nearest residence, vegetable garden, cow, goat, and meat animal. Long-term annual average (~X g) values for the SHNPP release points to the special locations 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, the highest annual average 779 value for ground level releases is the controlling factor. Long-term annual average (77/)

values were calculated assuming no decay, undeplet'ed transport to the site boundary, and are given in Table A-1, Appendix A . The maximum site boundary X/g for ground level releases occurs at the NNE and SSW sectors. However, the limiting location for implementation of 10CFR20 for noble gases is considered to be the site boundary (1.33 miles) in the NNE sector due to the generally greater population density in this direction.

3-12

Values for K;, L;, and M; which are to be used by SHNPP in Equations 3.2-1 and 3.2-2 to show compliance with 10CFR20, are presented in Table 3.2-3. These values were taken from Table 8-1 of NRC Regulatory Guide 1.109, Revision 1.

The values have been multiplied by 1.0E 6 to convert picocuries to microcuries for use in Equations 3.2-1 and 3.2-2.

Radioiodines and Particulates

'.2.2 The dose rate in unrestricted area resulting from the release of radioiodines, tritium, and particulates with half-lives > 8 days is limited to 1500 mrem/yr to any organ. Based upon NUREG 0133, the following is used to show compliance with 10CFR20.

P; L (Xm) Qi3 + (Pi + P; ) I (r/q) Q,3 +

(p + p ) $ (X/Q) Q ] < 1500 mrem/yr (3.2-3)

I N v where:

The highest annual average relative dilution: 2.0 E-6 sec/m for the inhalation pathway. The loca-tion is the site boundary at 1.33 miles in the NNE sector (from Table A-l, Appendix A, for ground level releases).

(D/Q) The highest annual average relative deposition:

3.5 E-9 m for the milk and ground plane path-ways. The location is the site boundary at 1.33 miles in the NNE sector (from Table A-4, Appendix A, for ground level releases).

P. Dose parameter for radionuclide "i" for the inha-1I 3 lation pathway, mrem/year per pCi/m .

~

3-13

p- Dose parameter for radionuclide "i" for the ground lG -2 plane pathway, mrem/year per pCi/sec per m p Dose parameter for radionuclide "i" for either the M

cow milk or goat milk pathway, mrem/year per pCi/sec per m 2.

PT Dose parameter for tritium for the inhalation I pathway, mrem/year per pCu/m .

3 Release rate of radionuclide "i" from all vent stacks pCi/sec.

Release rate for tritium from all vent stacks v

pCi/sec.

In the calculation to show compliance with 10CFR20, only tHe inhalation, ground plane, cow milk, and goat milk pathways are considered. To show compliance with 10CFR20, Equation 3.2-3 is evaluated first at the limiting site boundary. If the 1500 mrem/yr limit is exceeded at the limiting site boundary when all pathways are considered present at this site boundary but the inhalation pathway contributed < 1500 mrem/yr, then Equation 3.2-3 is evaluated at the limiting real pathway location, which is the cow milk pathway at 2.2 miles in the N sector (see Tables 3.2-2 and A-4, Appendix A).

The determination of limiting location for implementation of 10CFR20 for radioiodines and particulates is a function of the same parameters as for noble gases plus a fourth, actual receptor pathway. The radionuclide mix was again based upon the source terms calculated using the GALE Code. The mix and the source terms are presented in Table 3.2-1 as a function of release point.

The determination of the controlling site boundary location was based upon the highest site boundary D/g value. The determination of actual receptor lim-iting location was based upon the milk pathway D/g value and the P; value for the respective milk pathway. Values for P; were calculated for an infant for 3-14

various radionuclides for the inhalation, ground plane, cow milk, and goat milk pathways using the methodology of NUREG 0133. The P; values are pre-sented in Table 3.2-4. A description of the methodology used in calculating the Pi values is presented in Appendix B. The values of Pi reflect, for each radionuclide, the maximum Pi value for any organ for each individual pathway of exposure. The goat milk pathway is present near SHNPP, as is the cow milk pathway. However, the cow milk pathway P; values were utilized in the deter-mination of the controlling location because the product of the maximum cow milk pathway D/Q and P; were greater than those for the goat. For the case of an infant being present at the site at the site boundary or at the real path-G, way location, the ground plane pathway is not considered as a reasonable expo-

'G sure pathway (i.e., Pi = 0). However, P for completeness.

values are presented in Table 3.2-4 The annual average [D/Qj values at the special locations, which will be uti-lized in Equation 3.2-3, are obtained from the tables presented in Appen-dix A. The [X/Qj values which will be utilized in Equation 3.2-3 are also obtained from the tables presented in Appendix A. A description of the derivation of the X/Q and D/Q values is provided in Appendix A.

3-15

TAB -1 RELEASES FROM SHEARON HARRIS NUCLEAR POWER PLANT(1)

- NORMAL OPERATION (Curies/year)

WASTE GAS DECAY TANKS( CONDENSER VIA VENT STACK 5 BUILDING VENTILATION VIA VENT STACK 1 VACUUM PUMP TOTAL EXHAUST VIA VENT STACK 3A loble Gases

.R-83M 0 0 1.0E+00 0. 0. 0. 1.0E+00

.R-85M 0 0 1.2E+01 3.0E+00 0. 2.0E+00 1.7E+01

.R-85 3.0E+00 2.1E+02 4.0E+00 0. 0. 0. 2.2E+02

.R-87 0. ~

0. 2.0E+00 1.0E+00 0. 0. 3.0E+00

,R-88 0. 0. 1.6E+01 5.0E+00 0. 3.0E+00 2.4E+01

.R-89 0. 0. 0. 0. 0. 0. 0.

E-131M 0. 3.0E+00 1.0E+01 0. 0. 0. 1.3E+01 E-133M 0. 0. 4.3E+01 2.0E+00 0. 1.0E+00 4;6E+01 E-133 0.- 1.0E+00 2.5E+03 1.2E+02 0. 7.2E+01 2.7E+03

'E-135M 0. 0. 0. 0. 0. 0. 0.

.E-135 0. 0. 5.9E+01 7.0E+00 0 4.0E+00 7.0E+01 E-137 0. 0. 0. 0. 0. 0. 0.

E-138 0. 0. 0. 1.0E+00 0. 0. 1.0E+00(3)

R-41 2.5E+01

'articulates

-131 0. 0. 1.3E-02 4.5E-03 3.0E-04 2.8E-02 4.6E-02

-133 0. 0. 1.1E-02 6.7E-03 4.2E-04 4.2E-02 6.0E-02 1-3 5.8E+02 3

-14 3 lN-54 0. 4.5E-03 2.2E-04 1.8E-04 0. 0..

E-59 0. 1.5E-03 7.3E-05 6.0E-05 0. 0. 1.6E-03 0-58 0. 1.5E-02 7.3E-04 6.0E-04 0. 0. 1.6E-02 0-60 0. 7.0E-03 3.3E-04 2.7E-04 0. 0. 7.6E-03 R-89 0. 3.3E-04 1.7E-05 1.3E-05 0. 0. 3.6E-04 R-90 0. 6.0E-05 2.9E-06 2.4E-06 0. 0. 6.5E-05 S-134 0. 4.5E-03 2.2E-04 1.8E-04 0. 0. 4.9E-03

.S-137 0. 7.5E-03 3.7E-04 3.0E-04 0. 0. 8.2E-03 SHNPP FSAR Table 11.3.3-1. Calculations based upon GALE Code and do not reflect actual release lata. These values are only for routine releases and not for a complete inventory of gases in an emergency.

)Waste gas decay tank releases assumed after a 90 day decay period.

Calculated using guidance of NUREG-0017, "Calculation of Releases of Radioactive Materials in gaseous and Liquid Effluents from PWRs."

TABLE 3.2-2 DISTANCE TO THE NEAREST SPECIAL LOCATIONS FOR THE SHEARON HARRIS NUCLEAR POWER PLANT (MILES)*

Exclusion Milk Milk Meat Sector Boundary Residence Cow Goat Garden Animal N 1.32 2.2 2.2 4.1 2.2 2.2 NNE 1.33 1.7 4.7 3.6 1.8 1.8 NE 1.33 2.3 2.3 2.3 ENE 1.33 2.0 2.0 2.0 1.33 1.9 1.9 4.6 ESE 1.33 2.7 2.8 2.8 SE 1.33 4.2 4.3 4.3 SSE 1.33 S 1.36 SSW 1.33 4.0 4.0 4.2 1.33 2.7 2.7 2.7 WSW 1.33 W 1.33 2.7 2.7 4.3 WNW 1.33 2.2 2.2 2.2 NW 1.26 1.7 1.7 1.7 1.7 NNW 1.26 1.6 1.6 1.8

• As of November 17, 1983.

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

3-17

TABLE 3.2-3 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Total Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor Ki Li t'ai Ni (mrem/yr (mrem/yr (mrad/yr (mrad/yr Radionuclide er pCi/m3) er pCi/m3) er pCi/m3) er pCi/m3)

Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1. 72E+Ol 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9. 15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+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 factors are for radionuclides that dose may be detected in gaseous effluents.

3-18

TABLE 3.2-4 Pi VALUES FOR AN INFANT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT

~Ieoto e Inhalation Ground Plane Cow Milk Goat Milk H-3 6.47E2 0.00 2.38E3 4.86E3 P-32 2.03E6 0.00 1.60E11 1.93E11 Cr-51 1.28E4 6.67E6 4.79E6 5.65E5 Mn-54 1.00E6 1.09E9 3.89E7 4.68E6 Fe-59 1.02E6 3.92E8 3.93E8 5. 11E6 Co-58 7.77E5 5.29E8 6.06E7 7.28E6 Co-60 4.51E6 4.40E9 2.10E8 2.52E7 Zn-65 6.47E5 6.89E8 1. 90E10 2.29E9 Rb-86 1.90E5 1.28E7 2. 22E10 2.67E9 Sr-89 2.03E6 3.16E4 1.27E10 2.66E10 Sr-90 4.09E7 0.00 1.21E11 2.55E11 Y-91 2.45E6 1.52E6 5.26E6 6.32ES Zr-95 1.75E6 3.48E8 8.28E5 9.95E4 Nb-95 4.79E5 1.95E8 2.06E8 2.48E7 Ru-103 5.52E5 1.55E8 1.05E5 1.27E4 RU-106 1. 16E7 2.99E8 1.44E6 1.73E5 Ag-110m 3.67E6 3.14E9 1.46E10 1.75E9 Te-127m 1.31E6 1.18E5 1.04E9 1.24E8 Te-129m 1.68E6 2.86E7 1.40E9 1.68E8 Cs-134 7.03E5 2.81E9 6.79E10 2.04E11 Cs-136 1.35E5 2.13E8 5.76E9 1.73E10 Cs-137 6. 12E5 1.15E9 6.02E10 1.81E11 Ba-140 1.60E6 2.94E7 2.41E8 2.89E7 Ce-141 5. 17E5 1.98E7 1.37E7 1.65E6 Ce-144 9.84E6 5.84E7 1.33E8 1.60E7 I-131 1. 48E7 2.46E7 1.06E12 1.27E12 I-132 1. 69E5 1.78E6 1.39E2 1.64E2 I-133 3.56E6 3.54E6 9.80E9 1.18E10 I-135 6.96E5 3.67E6 2.27E7 2.68E7 Units are mrem/yr per pCi/m for H-3 and the inhalation pathway and mrem/yr per pCi/sec per m for the food and ground plane pathways.

3-19

ss COMPLIANCE WITH 10CFR50 (GASEOUS) 3.3.1 Noble Gases 3.3.1.1 Cumulation of Doses Based upon NUREG 0133, the air dose in the unrestricted area due to noble gases released in gaseous effluents can be determined by the following equations:

D =3 17x10

~

7 Mi E (~Q) Qi +(VZ) q 3 D = 3.17 x 10 g Ni f (TX Q)v Qi + (XTq) q. 3 (3.3-2) v where:

D The air dose from gamma radiation, mrad.

Dp The air dose from beta radiation, mrad.

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

The air dose factor due to beta emissions for each identified .noble gas radionuclide "i," mrad/year per pCi/m3.

The highest annual average dilution for areas at or beyond the site area boundary for all long-term vent stack releases (> 500 hrs/year), sec/m .

2.0E-6 sec/m from Table A-l, Appendix A for ground level releases in the NNE sector at the site boundary.

3-20

(7Xq) The dilution for areas at or beyond the unre-stricted area boundary for short-term, ground level, vent stack releases (< 500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />s/year),

sec/m . See Section 3.0 earlier or use 2.0E-6 sec/m from Table A-l, Appendix A.

qiv The average release of noble gas radionuclide "i" in gaseous releases for short-term releases from all vent stacks (< 500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />s/year ), pCi.

The average release of noble gas radionuclide "i" in gaseous effluents for long-term releases from all vent stacks (> 500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />s/year), pCi.

3.17 x 10 The inverse of the number of seconds in a year (sec/year)-1 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 site boundary at 1.33 miles in the NNE sector based upon the tables presented in Appendix A (see Section 3.2.1 ear-lier). For this document, long-term annual average g values can be used in

~X 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 releas'e, and meteo-rology. The radionuclide mix was based upon source terms calculated using the NRC GALE Code and is presented in Table 3.2-1 as a function of release point.

The only source of short-term releases from the plant vent are containment pur ges, containment pressure relief, and waste gas decay tank release. To select the limiting location, the highest annual average X/g value for ground level releases is controlling.

3-21

0 0

V alues for N; and N;, 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-l of the NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 1.0E 6 to convert from picocuries to microcuries.

The following relationships should hold for SHNPP to show compliance with Technical Specification 3.11.2.2.

For the calendar quarter:

D < 5 mrad (3.3-3)

Y D~

< 10 mrad (3.3-e)

For the calendar year:

D < 10 mrad (3.3-5)

Y D~

< 20 mrad (3.3-6)

The quarterly limits given above represent one-half of the annual design ob-jectives of Section II.B.1 of Appendix I of 10CFR50. If any of the limits of Equations 3.3-3 through 3.3-6 are exceeded, a special report pursuant to Tech-nical Specification 6.9.2 must be filed with the NRC. This report complies with Section IV.A of Appendix I of 10CFR50.

3.3.1.2 Projection of Doses Doses resulting from the release of gaseous effluents will be projected once every 31 days (monthly). The doses will be projected utilizing Equations 3.3-1 and 3.3-2. When the operational conditions are expected to be the same as for toricall the current month, the source term inputs into the equation for the projection can be taken directly from the current month's data. Where possible, credit for expected operational evolutions (i.e., outages, increased power levels, major planned liquid releases, etc.) should be taken in the dose projec-,

tions. This may be accomplished by using source term data from similar his-operating experiences where practical.

3-22

~ ~

3.3.2

~ ~

~

Radioiodine and Particulates 3.3.2.1 Cumulation of DosesSection II.C of Appendix I of 10CFR50 limits the release of radioiodines and radioactive material in particulate form from each reactor such that 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 par-ticulates with half-lives greater than 8 days in gaseous effluents released to unrestricted areas can be determined by the following equation:

= 3.17 x 10 D g (Ri t(XWV Qi + ~qv qi ~ +

i I. v v (R. + Ri + Ri + Ri ) [(~D Q) v Qii

+ (~D q) V q.1 I) +

(3.3-7)

M V G B (R + R + R + R ) L(XTQ) Q + (~X q) v q ]

I v M V B Tv Tv where:

Dose to any organ z from tritium, radioiodines, and particulates, mrem.

3.17 x 10-8 The inverse of the number of seconds in a year, (sec/year) 1.

(VU) The highest annual average dilution: 9.3 E-7 sec/m for the inhalation pathway in the controlling location which is 2.2 miles in the N sector (from Table A-l, Appendix A, for long-term ground level vent stack releases).

(~Xq) The dilution for areas at or beyond the site boundary for short-term, ground level, vent stack releases (< 500 hrs/yr) sec/m . See Section 3.0 earlier if using "real" meteorology or use 9.3 E-7 sec/m3 from Table A-l, Appendix A, for the inhalation pathway at the controlling location.

3-23

The highest long-term (> 500 hr/yr) annual average relative deposition: 1.1 E-9 m 2 for the food and ground plane pathways at the controlling location which is 2.2 miles in the N sector (from Table A-4, Appendix A, for ground level vent stack releases).

The rel ative deposition factor for short-term, ground level vent releases (< 500 hrs/yr), m 2.

See Section 3.0 earlier if using "real" meteorol-ogy or use 1.1 E-9 m 2 from Table A-4, Appendix A, for the food and ground plane pathways at the controlling location.

Release of radionuclide "i" in gaseous effluents for long-term releases (> 500 hr s/yr) from all vent stacks, pCi.

qiv Release of radionuclide "i" in gaseous effluents for short-term releases (< 500 hrs/yr) from all vent stacks, pCi .

iM Dose factor for an organ for radionuclide "i" for either the cow milk or goat milk pathway, mrem/yr per pCi/sec per m 2.

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

Ri Dose factor for an organ for radionuclide "i" for I

the inhalation pathway, mrem/yr per pCi/m .

Ri Dose factor for an organ for radionuclide "i" for V

the v'egetable pathway, mrem/yr per pCi/sec per m

3-24

Ri Dose factor for an organ for radionuclide "i" rfor B

the vegetable pathway, mrem/yr per pCi/sec per m

~.'T Dose factor for an organ for tritium for the milk pathway mrem/yr per pCi/m .

RT Dose factor for an organ for tritium for the vege-V table pathway, mrem/yr per pCi/m .

RT Dose factor for an organ for tritium for the inha-I lation pathway, mrem/yr per p,Ci/m .

RT Dose factor for an organ for tritium for the meat B

pathway, mrem/yr per pCi/m .

QTv Release of tritium in gaseous effluents for long-term vent stack releases (> 500 hrs/yr), p,Ci.

qTv Release of tritium in gaseous effluents for short-term vent stack releases (< 500 hrs/yr), pCi.

To show compliance with 10CFR50, Equation 3.3-7 is evaluated at the limiting real pathway location. At SHNPP this location is 2.2 miles in the N sector.

The critical receptor is an infant. Appropriate X/Q and D/Q values from tables in Appendix A are used. For this document, long-term annual average X/Q and D/Q values may be used in lieu of short-term values (see Section 3.0 earlier).

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 3-25

In the determination of the limiting location, the radionuclide mix of radio-iodines and particulates may be based upon the source terms calculated using the GALE Code. This mix is presented in Table 3.2-1 as a function of release point.

In the determination of the limiting location, all of the exposure pathways, as presented in Table 3.2-2 are initially evaluated. These include cow milk, goat milk, beef and .vegetable ingestion, inhalation, and ground plane expo-sure. For conservatism, an infant was assumed to be present at all milk pathway locations, and a child was assumed to be present at all vegetable garden and beef animal locations. The ground plane exposure pathway was not considered a viable pathway for an infant. Naturally, the inhalation pathway was present everywhere an individual was present.

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 loca-tions are also determined during this survey. Thus, depending on the results of the survey, a new limiting location and receptor age group can result. The survey ultimately determines the applicable real exposure pathways and, there-fore, the appropriate R factors for inclusion in Equation 3.3-7.

For the actual determination of the limiting location, the highest D/Q loca-tions with existing vegetable garden, cow milk, and goat milk pathways were selected from Table 3.2-2. The I-131 thyroid dose was computed at each of these locations. Based upon these calculations, it was determined that the limiting receptor pathway is the grass-cow-milk pathway.

Long-term X/Q and D/Q 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.

3-26

Tables 3.3-1 through 3.3-19 present R;i values for the total body, GI-tract, bone, liver,, kidney, thyroid, and lung organs for the ground plane, inhala-tion, 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 (3.3-8)

For the calendar year:

D < 15 mrem (3.3-9)

The quarterly limits given above represent one-half the annual design objec-tives of Section II.C of Appendix I of 10CFR50. If any of the limits of Equations 3.3-8 or 3.3-9 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.

3.3.2.2 Projection of Doses Doses resulting from release of radioiodines and particulates will be pro-jected once every 31 days (monthly) utilizing Equation 3.3-7. When the oper-ational conditions for the projected month are expected to be the same as for the current month, the source term inputs into the equation for the projection can be taken dire'ctly from the current month's data. Where possible, credit for expected operational evolutions (i.e., outages, increased power levels, major planned liquid releases, etc.) should be taken in the dose projec-tions. This may be accomplished by using source term data from similar his-torical operating experiences where practical, 3-27

TABLE 3-3-1 R VALUES FOR THE SHEARON HARRIS NUCLEAR PSlER PUSP'ATHWAY

= Ground lhclide GI-Tract Liver Kidney Thyroid ~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 C.

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 u-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-llOM 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 4.06E 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-131 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 2.09E 07 I-132 1.24E 06 1.24E 06 1.24E 06 1.24E 06 1.24E 06 1.24E 06 1.24E 06 1.46E 06 I-133 2.47E 06 2.47E 2.47E 06 2.47E 06 2.47E 06 2.47E 06 2.47E 06 3.00E 06 06'.56E I-135 2.56E 06 06 2.56E 06 2.56E 06 2.56E 06 2.56E 06 2.56E 06 2.99E 06 Cs-134 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 7.96E 09 Cs-136 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.69E 08 Cs-137 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.20E 10 Ba-140 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.34E 07 Ce-141 1.36E 07 1.36E 07 1.36E 07 1.36E 07 1.36E 07 1.36E 07 1.36E 07 1.53E 07 Ce-144 6.95E 07 6.95E 07 6.95E 07 6.95E 07 6.95E 07 6.95E 07 6.95E 07 8.03E 07

• R Values in units of mrem/yr per micro-Ci/m for inhalation and tritium, and in units of mrem/yr per micro-Ci/sec per m-2 for all others.

TABLE 3.3-2 R VALUES FOR THE SHEARGN HARRIS NUCLEAR POMER PLAMI PATHWAY = Veget AGE GROUP = Adult Nuclide T.Body Liver Kidney TtLYrold 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 0.00E 01 Cr-51 4.60E 04 1.16E 07 O.OOE 01 O.OOE Ol 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 0.00E 01 O.OOE 01 0.00E Ol 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 0.00E 01 O.OOE Ol 0.00E 01 0.00E 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 Ol 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 11 1.93E 10 6.70E 11 O.OOE 01 O.OOE 01 O.OOE 01 O.OOE Ol O.OOE 01 Y-91 1.34E 05 2.76E 09 5.01E 06 O.OOE 01 O.OOE 01 O.OOE 01 O.OOE 01 0.00E 01 r-95 2.51E 05 1.17E 09 1.16E 06 3.71E 05 5.82E 05 O.OOE 01 O.OOE 01 0.00E Ol Nb-95 4.19E 04 4.73E 08 1.40E 05 7.79E 04 7.70E 04 0.00E Ol O.OOE 01 O.OOE 01 RQ-103 2.04E 06 5.53E 08 4.74E 06 O.OOE 01 1.81E 07 0.00E 01 O.OOE 01 O.OOE 01 Ru-106 2.46E 07 1.26E 10 1.94E 08 O.OOE Ol 3.75E 08 O.OOE 01 O.OOE 01 O.OOE 01 Ag-11ON 6.23E 06 4.28E 09 1.13E 07 1.05E 07 2.06E 07 O.OOE 01 O.OQE 01 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 0.00E 01 I-131 6.61E 07 3.04E 07 8.07E 07 1.15E 08 1.98E 08 3.78E 10 O.OOE 01 O.OOE 01 I-132 5.21E 01 2.80E 01 5.57E 01 1.49E 02 2.37E 02 5.21E 03 O.OOE 01 O.OOE Ol 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 Ol ea-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 1A8E 04 4.99E 08 1.93E 05 1.31E 05 6.07E 04 O.OOE 01 O.OOE Ol O.OOE Ol 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

• R Values in units of mrem/yr per micro-Ci/m for inhalation and tritium, and in units of mrem/yr per micro-Ci/sec per m 2 for all others.

3-29

TABLE 3.3-3 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT PATHWAY = Veget AGE GROUP = Teen Nuclide GI-Tract Liver Kidney Ttproid 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 0.00E 01 O.OOE 01 O.OOE 01 0.00E 01 Cr-51 6.11E 04 1.03E 07 O.OOE 01 0.00E 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 OeOOE Ol O.OOE 01 Fe-59 1.60E 08 9.78E 08 1.77E 08 4.14E 08 O.OOE 01 0.00E 01 1.30E 08 O.OOE 01 Co-58 9.79E 07 5.85E 08 O.OOE 01 4.25E 07 0.00E 01 0.00E 01 O.OOE 01 0.00E 01 Co-60 5.57E 08 3.22E 09 O.OOE 01 2.47E 08 O.OOE 01 0.00E 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 0.00E 01 O.OOE Ol O.OOE Ol O.OOE 01 Sr-89 4.36E 08 1.81E 09 1.52E 10 O.OOE 01 O.OOE 01 O.OOE 01 0.00E 01 0.00E 01 Sr-90 2.05E ll 2.33E 10 8.32E 11'.68E O.OOE Ol O.OOE 01 O.OOE 01 O.OOE 01 O.OOE 01 Y-91 2.06E 05 3.15E 09 06 O.OOE 01 O.OOE 01 O.OOE 01 0.00E 01 O.OOE 01 Zr-95 3.68E 05 1.23E 09 1.69E 06 5.35E 05 7.86E 05 O.OOE Ol O.OOE 01 0.00E 01 Nb-95 5.77E 04 4.48E 08 1.89E 05 1.05E 05 1.02E 05 O.OOE 01 0.00E 01 O.OOE 01 RU-103 2.90E 06 5.66E 08 6.78E 06 0.00E 01 2.39E 07 0.00E Ol O.OOE 01 O.OOE Ol RU-106 3.93E 07 1.50E 10 3.12E 08 0.00E 01 6.02E 08 O.OOE 01 O.OOE 01 O.OOE 01 Ag-116M 9.39E 06 4.34E 09 1.63E 07 1.54E 07 2.95E 07 O.OOE 01 0.00E 01 O.OOE 01'.OOE Te-127t1 9.44E 07 1.98E 09 7.93E 08 2.81E 08 3.22E 09 1.89E 08 O.OOE 01 Ol 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 Ol 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 0.00E 01 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 01 I-135 3.49E 04 1.04E 05 3.66E 04 9.42E 04 1.49E 05 6.06E 06 O.OOE 01 O.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 Ol Cs-136 1.13E 08 1.35E 07 4.28E 07 1.68E 08 9.16E 07 O.OOE 01 1.44E 07 0.00E 01 Cs-137 4.90E 09 2.00E 08 1.06E 10 1.41E 10 4.78E 09 O.OOE 01 1.86E 09 O.OOE 01 Ba-140 8.88E 06 2.12E 08 1.38E 08 1.69E 05 5.72E 04 0.00E 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 0.00E 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

• R Values in units of mrem/yr per micro-Ci/m for inhalation and tritium, and in units of mrem/yr per micro-Ci/sec per m-2 for all others.

3-30

TABLE 3.3-4 R VALUES FOR THE SHEAROM HARRIS NUCLEAR POMER PLANT" PATHNY = Veget AGE GROUP = Child Ihclide GI-Tract Liver Kidney Ttproid Lung Skin H-3 4.04E 03 4.04E 03 O.OOE 01 4.04E 03 4.04E 03 4.04E 03 4.04E 03 4.04E 03 P-32 1.42E 08 1.01E 08 3.67E 09 1.72E 08 O.OOE 01 O.OOE 01 O.OOE 01 0.00E 01 Cr-51 1.16E 05 6.15E 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 0.00E 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 0.00E 01 0.00E 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 0.00E Ol 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 0.00E 01 O.OOE 01 O.OOE 01 O.OOE 01 O.OOE 01 Y-91 4.89E 05 2.44E 09 1.83E 07 O.OOE Ol O.OOE 01 O.OOE 01 O.OOE 01 O.OOE 01 Zr-95 7.44E 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 0.00E Ol O.OOE 01 O.OOE 01 Ru-106 9.38E 07 1.17E 10 7.52E 08 0.00E 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 0.00E 01 O.OOE 01 O.OOE 01 Te-127M 2.26E 08 1.54E 09 1.90E 09 5.12E 08 5.42E 09 4.55E 08 0.00E 01 0.00E Ol 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 I-131 8.16E 07 1.23E 07 1.43E 08 1.44E 08 2.36E 08 4.75E 10 O.OOE 01 O.OOE 01 I-132 7.53E 01 1.93E 02 8.91E 01 1.64E 02 2.51E 02 7.60E 03 O.OOE 01 O.OOE 01 I-133 1.67E 06 1.78E 06 3.57E 06 4.42E 06 7.36E 06 8.21E 08 0.00E 01 O.OOE 01 I-135 5.54E 04 8.92E 04 6.50E 04 1.17E 05 1.79E 05 1.04E 07 O.OOE 01 O.OOE 01 Cs-134 5.40E 09 1.38E 08 1.56E 10 2.56E 10 7.93E 09 0.00E 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 Ba-140 1.61E 07 1.40E 08 2.76E 08 2.42E 05 7.87E 04 O.OOE 01 1.44E 05 O.OOE 01 Ce-141 4.75E 04 3.99E 08 6.42E 05 3.20E 05 1.40E 05 O.OOE 01 0.00E 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

• R Values in .units of mrem/yr per micro-Ci/m for inhalation and tritium, and in units of mrem/yr per micro-Ci/sec per m-2 for all others.

TABLE 3.3-5 R VALUES FOR %E SHEARON HARRIS NUCLEAR POWER PLANP'ATHWAY

= Meat AGE GROUP = Adult Nuclide 6I-Tract Liver Kidney Thyroid Skin H-3 3.27E 02 3.27E 02 0.00E 01 3.27E 02 3.27E 02 3.27E 02 3.27E 02 3.27E 02 P-32 1.18E 08 3.43E 08 3.05E 09 1.89E 08 O.OOE 01 O.OOE 01 0.00E 01 O.OOE Ol Cr-51 4.27E 03 1.08E 06 O.OOE 01 0.00f Ol 9.42E 02 2.56E 03 5.67E 03 O.OOE 01 Mn-54 1.06E 06 1.71E 07 O.OOE 01 5.57E 06 1.66E 06 O.OOE 01 O.OOE 01 0.00f Ol Fe-59 1.43E 08 1.25E 09 1.59E 08 3.74E 08 0.00E 01 0.00E 01 1.04E 08 O.OOE 01 Co-58 . 2.43E 07 2.20E 08 0.00E 01 1.08E 07 O.OOE 01 O.OOE 01 O.OOE 01 0.00E Ol Co-60 1.03E 08 8.76E 08 O.OOE 01 4.66E 07 O.OOE 01 O.OOE 01 O.OOE 01 O.OOE 01 Zn-65 3.58E 08 4.98E 08 2.49E 08 7.91E 08 5.29E 08 0.00E Ol 0.00E 01 0.00E 01 Rb-86 1.42E 08 6.00E 07 0.00E Ol 3.04E 08 O.OOE 01 O.OOE Ol O.OOE 01 O.OOE 01 Sr-89 5.23E 06 2.92E 07 1.82E 08 O.OOE 01 0.00E 01 O.OOE 01 O.OOE 01 0.00E 01 Sr-90 2.02E 09 2.38E 08 8.22E 09 0.00E 01 O.OOE 01 0.00E 01 O.OOE 01 O.OOE Ol Y-91 1.80E 04 3.71E 08 6.75E 05 0.00E 01 0.00E 01 O.OOE 01 O.OOE 01 O.OOE Ol

+r-95 2.43E 05 1.14E 09 1.12f 06 3.59E 05 5.64E 05 O.OOE 01 O.OOE Ol 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 2.34E 06 1.61E 09 4.27E 06 3.95E 06 7.76E 06 O.OOE 01 O.OOE 01 O.OOE 01 Te-127M 1.00E 08 2.76E 09 8.22E 08 2.94E 08 3.34E 09 2.10E 08 0.00E 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 Ol I-131 5.77E 06 2.66E 06 7.04E 06 1.01E 07 1.73E 07 3.30E 09 0.00E 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 Ol O.OOE 01 I-135 6.07E-17 1.86E-16 6.28E-17 1.64E-16 2.64E-16 1.08E-14 O.OOE 01 O.OOE 01 Cs-134 7.81E 08 1.67E 07 4.01E 08 9.55E 08 3.09E 08 O.OOE 01 1.03E 08 O.OOE 01 Cs-136 2.14E 07 3.33E 06 7.53E 06 2.97E 07 1.65E 07 0.00E Ol 2.27E 06 0.00E 01 Cs-137 4.99E 08 1.47E 07 5.57f 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 0.00E Ol 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 0.00E Ol O.OOE 01 O.OOE 01

' *R Values in units of mrem/yr per micro-Ci/m for inhalation and tritium, and in units of mrem/yr per micr o-Ci/sec per m-2 for all others.

3-32

TABLE 3.3-6 R VALUES FOR THE SHEARON HARRIS NUCLEAR POMER PLANP'ATHWAY

= Meat AGE GROUP = Teen Nuclide GI-Tract Liver Kidney Thyroid ~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 0.00E 01 0.00E 01 O.OOE 01 Cr-51 3.42E 03 5.75E 05 0.00E Ol 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 0.00E 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 Ol O.OOE 01 O.OOE 01 Co-60 8.16E 07 4.71E 08 O.OOE 01 3.62E 07 O.OOE 01 O.OOE 01 0.00E 01 O.OOE 01 Zn-65 2.83E 08 2.57E 08 1.75E 08 6.07E 08 3.89E 08 O.OOE 01 0.00E 01 O.OOE 01 Rb-86 1.19E 08 3.76E 07 0.00E 01 2.54E 08 O.OOE 01 0.00E 01 O.OOE 01 O.OOE 01 Sr-89 4.40E 06 1.83E 07 1.54E 08 0.00E 01 0.00E 01 0.00E 01 O.OOE 01 0.00E 01 Sr-90 1.31E 09 1.49E 08 5.32E 09 0.00E 01 O.OOE 01 0.00E 01 0.00E 01 O.OOE 01 Y-91 1.52E 04 2.33E 08 5.68E 05 0.00E 01 O.OOE Ol 0.00E Ol O.OOE 01 0.00E 01 Zr-95 1.95E 05 6.63E 08 8.97E 05 2.83E 05 4.16E 05 O.OOE 01 O.OOE 01 O.OOE 01 Nb-95 3.29E 05 2.65E 09 1.08E 06 5.97E 05 5.79E 05 0.00E Ol 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 Ol Ru-106 1.84E 08 7.00E 10 1.46E 09 O.OOE 01 2.81E 09 O.OOE 01 0.00E 01 O.OOE 01 Ag-110M 1.86E 06 8.59E 08 3.23E 06 3.06E 06 5.83E 06 0-OOE 01 O.OOE 01 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 01 I-131 4.40E 06 1.62E 06 5.85E 06 8.20E 06 1.41E 07 2.39E 09 O.OOE 01 0.00E 01 I-133 1.23E-01 3.06E-Ol 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 0.00E 01 0.00E 01 Cs-134 3.48E 08 9.34E 06 3.19E 08 7.51E 08 2.39E 08 0-OOE 01 9.11E 07 O.OOE 01 Cs-136 1.55E 07 1.86E 06 6.87E 06 2.31E 07 1.26E 07 0.00E 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 0.00E 01 O.OOE 01 O.OOE 01 "R Values in units of mrem/yr per micro-Ci/m for inhalation and tritium, and in units of mrem/yr per micro-Ci/sec per m 2 for all others.

3-33

TABLE 3.3-7 R VALUES FOR THE SHEARON HARRIS NXLEAR POMER PLANY PATHWAY = Meat AGE GROUP = Child Nuclide 6I-Tract Liver Kidney Thyroid Skin H-3 2.36E 02 2.36E 02 O.OOE 01 2.36E 02 2.36E 02 2.36E 02 2.36E 02 2.36E 02 P-32 1.87E 08 1.34E 08 4.86E 09 2.27E 08 0.00E 01 O.OOE 01 O.OOE 01 0.00E Ol Cr-51 5.33E 03 2.83E 05 O.OOE 01 O.OOE 01 8.09E 02 2.96E 03 5.40E 03 O.OOE 01 Mn-54 1.30E 06 4.08E 06 O.OOE 01 4.86E 06 1.36E 06 O.OOE 01 O.OOE 01 O.OOE 01 Fe-59 1.82E 08 3.80E 08 2.25E 08 3.65E 08 O.OOE 01 O.OOE 01 1.06E 08 O.OOE'1 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 0.00E Ol 4.30E 07 O.OOE Ol O.OOE 01 O.OOE 01 O.OQE 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 0.00E 01 0.00E Ol O.OOE 01 O.OOE 01 0.00E 01 Sr-90 1.74E 09 9.26E 07 6.87E 09 . O.OOE 01 0.00E 01 O.OOE Ol O.OOE 01 O.OOE 01 Y-91 2.87E 04 1.43E 08 1.07E 06 O.OOE Ol O.OOE 01 O.OOE Ol O.OOE 01 0.00E 01 Zr-95 3.12E 05 3.65E 08 1.59E 06 3.50E 05 5.01E 05 0.00E 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 0.00E Ol 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 01 O.OOE 01 0.00E 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 Te-127M 1.55E 08 1.06E 09 1.31E 09 3.52E 08 3.73E 09 3.13E 08 0.00E 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 1-133 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 Ol Cs-134 1.95E 08 4.93E 06 5.63E 08 9.23E 08 2.86E 08 O.OOE 01 1.03E 08 O.OOE Ol 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 Ol Ba-140 1.63E 06 1.42E 07 2.80E 07 2.45E 04 7.97E 03 O.OOE 01 1.46E 04 O.OOE 01 Ce-141 9.86E 02 8.28E 06 1.33E 04 6.64E 03 2.91E 03 O.OOE 01 O.OOE 01 O.OOE 01 Ce-144 7.42E 04 1.14E 08 1.39E 06 4.36E 05 2.41E 05 O.OOE 01 O.OOE 01 0.00E 01

• R Values in units of mrem/yr per micro-Ci/m for inhalation and tritium, and in units of mrem/yr per micro-Ci/sec per m-2 for all others.

TABLE 3.3-8 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT PATHWAY = Cow Milk AGE GROUP = Adult Nuclide GI-Tract Liver Kidney Thyroid Lung Skin H-3 7.69E 02 7.69E 02 O.OOE-Ol 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-Ol 0.00E-01 O.OOE-01 O.OOE-Ol Cr-51 1.73E 04 4.36E 06 O.OOE-01 O.OOE-Ol 3.82E 03 1.04E 04 2.30E 04 0.00E-Ol Mn-54 9.76E 05 1.57E 07 O.OOE-01 5.11E 06 1.52E 06 O.OOE-01 0.00E-01 O.OOE-Ol Fe-59 1.60E 07 1.39E 08 1.77E 07 4.17E 07 0.00E-01 0.00E-01 1.17E 07 O.OOE-01 Co-58 6.28E 06 5.68E 07 O.OOE-01 2.80E 06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Co-60 2.24E 07 1.91E 08 O.OOE-01 1.02E 07 O.OOE-Ol O.OOE-01 O.OOE-01 0.00E-01 Zn-65 1.38E 09 1.92E 09 9.59E 08 3.05E 09 2.04E 09 O.OOE-01 O.OOE-01 0.00E-01 Rb-86 7.54E 08 3.19E 08 0.00E-01 1.62E 09 0.00E-01 O.OOE-01 0.00E-01 0.00E-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 0.00E-01 O.OOE-01 0.00E-01 0.00E-01 O.OOE-01 Y-91 1.37E 02 2.81E 06 5.11E 03 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 Zr-95 1.22E 02 5.71E 05 5.62E 02 1.80E 02 2.83E 02 0.00E-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-Ol O.OOE-01 O.OOE-01 RU-103 2.63E 02 7.14E 04 6.11E 02 0.00E-01 2.33E 03 0.00E-01 O.OOE-Ol O.OOE-01 RU-106 1.60E 03 8.17E 05 1.26E 04 O.OOE-01 2.44E 04 O.OOE-01 O.OOE-01 O.OOE-01 Ag-110M 2.04E 07 1.40E 10 3.71E 07 3.44E 07 6-76E 07 0.00E-01 O.OOE-01 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 0.00E-01 Te-129M 6.19E 06 1.97E 08 3.91E 07 1.46E 07 1.63E 08 1.34E 07 O.OOE-01 0.00E-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 I-133 1.40E 06 4.13E 06 2.64E 06 4.59E 06 8.01E 06 6.75E 08 O.OOE-01 O.OOE-01 I-135 9.03E 03 2.76E 04 9.34E 03 2.45E 04 3.92E 04 1.61E 06 O.OOE-01 O.OOE-Ol Cs-134 6.71E 09 1.44E 08 3.45E 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 0.00E-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 0.00E-01 Ba-140 1.12E 06 3.53E 07 1.71E 07 2.15E 04 7.32E 03 O.OOE-01 1.23E 04 0.00E-01 Ce-141 2.23E 02 7.52E 06 2.91E 03 1.97E 03 9.14E 02 O.OOE-01 O.OOE-01 0.00E-01 Ce-144 1.15E 04 7.26E 07 2.15E 05 8.97E 04 5.32E 04 0.00E-01 O.OOE-01 0.00E-Ol

• R Values in units of mrem/yr per micro-Ci/m for inhalation and tritium, and in units of mrem/yr per micro-Ci/sec per m for all others.

3-35

TABLE 3.3<<9 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLAN7 PATHWAY = Cow flilk AGE GROUP = Teen Nuclide T.Bogy GI-Tract Liver Kidney Thyroid 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 0.00E-Ol 0.00E-01 O.OOE-01 0.00E-01 Cr-51 3.02E 04 5.08E 06 0.00E-Ol 0.00E-Ol 6.63E 03 1.68E 04 4.32E O.OOE-01 Mn-54 1.69E 06 1.75E 07 8.52E 06 2.54E 06 04'.OOE-01 O.OOE-01 , O.OOE-01 O.OOE-01 Fe-59 2.79E 07 1.71E 08 3.10E 07 7.23E 07 0.00E-01 0.00E-01 2.28E 07 0.00E-01 Co-58 1.09E 07 6.50E 07 O.OOE-Ol 4.72E 06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Co-60 3.88E 07 2.25E 08 0.00E-01 1.72E 07 O.OOE-01 O.OOE-01 0.00E-Ol 0.00E-01 Zn-65 2.38E 09 2.16E 09 1.47E 09 5.11E 09 3.27E 09 O.OOE-01 O.OOE-01 0.00E-01 Rb-86 1.39E 09 4.37E 08 0.00E-01 2.95E 09 0.00E-01 0.00E-Ol 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 0.00E-Ol 0.00E-Ol 0.00E-01 0.00E-01 0.00E-01 Y-91 2.52E 02 3.85E 06 9.40E 03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 Zr-95 2.13E 02 7.16E 06 9.83E 02 3.10E 02 4.56E 02 0.00E-01 O.OOE-01 0.00E-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 0.00E-01 3.83E 03 0.00E-01 O.OOE-Ol 0.00E-01 Ru-106 2.93E 03 1.11E 06 2.32E 04 O.OOE-01 4.48E 04 O.OOE-01 O.OOE-Ol O.OOE-01 Ag-110M 3.53E 07 1.63E 10 6.14E 07 5.81E 07 1.11E 08 O.OOE-Ol 0.00E-01 0.00E-01 Te-127M 7.39E 06 1.55E 08 6.22E 07 2.21E 07 2.52E 08 1.48E 07 0.00E-Ol O.OOE-Ol Te-129M 1.13E 07 2.69E 08 7.15E 07 2.65E 07 2.99E 08 2.31E 07 0.00E-01 0.00E-01 I-131 2.65E 08 9.75E 07 3.52E 08 4.93E 08 8.48E 08 1.44E 11 O.OOE-01 O.OOE-O1 I-132 1.83E-01 2.22E-01 1.94E-01 5.09E-01 8.02E-01 1.71E 01 O.OOE-01 O.OOE-01 I-133 2.49E 06 6.19E 06 4.82E 06 8.18E 06 1.43E 07 1.14E 09 O.OOE-01 O.OOE-01 I-135 1.58E 04 4.74E 04 1.66E 04 4.27E 04 6.75E 04 2.75E 06 O.OOE-Ol 0.00E-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 7ABE 08 8.97E 07 2.83E 08 1.11E 09 6.07E 08 0.00E-01 9.56E 07 0.00E-Ol 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 0.00E-01 2.55E 04 0.00E-01 Ce-141 4.09E 02 1.02E 07 6.33E 03 3.56E 03 1.68E 03 0.00E-01 O.OOE-Ol 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

• R Values in units of mrem/yr per micro-Ci/m for inhalation and tritium, and in units of mrem/yr per micro-Ci/sec per m for all others.

3-36

TABLE 3.3-10 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT+

PATHWAY = Cow Milk AGE GROUP = Child Nuclide GI-Tract Liver Kidney Thyroid 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-Ol O.OOE-01 O.OOE-01 0.00E-01 Cr-51 6.17E 04 3.27E 06 0.00E-01 0.00E-Ol 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-Ol O.OOE-01 Fe-59 5.79E 07 1.21E 08 7.18E 07 1.16E 08 0.00E-01 0.00E-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.OUE-01 O.OOE-01 O.OQE-01 Co-60 7.90E 07 1.48E 08 O.OOE-01 2.68E 07 0.00E-01 0.00E-Ol O.OOE-01 0.00E-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 0.00E-01 5.47E 09 0.00E-01 0.00E-01 0.00E-01 O.OOE-Ol Sr-89 1.13f 08 1.54E 08 3.97f 09 O.OOE-Ol O.OOE-01 O.OOE-01 O.OOE-Ol O.OOE-01 Sr-90 1.87E 10 9.95E 08 7.38E 10 O.OOE-01 O.OOE-Ol O.OOE-01 0.00E-01 O.OOE-01 Y-91 6.21E 02 3.09E 06 2.32E 04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Zr-95 4.47E 02 5.23E 05 2.28E 03 5.02E 02 7.18E 02 O.OOE-01 0.00E-01 0.00E-01 Nb-95 5.31E 04 1.37E 08 1.91E 05 7.42E 04 6.98E 04 O.OOE-01 0.00E-Ol O.OOE-Ol Ru-103 9.88E 02 6.65E 04 2.57E 03 0.00E-Ol 6.47E 03 0.00E-01 O.OOE-01 0.00E-01 RU-106 7.14E 03 8.90E 05 5.72f 04 O.OOE-Ol 7.72E 04 O.OOE-01 0.00E-Ol O.OOE-01 Ag-110M 7.19E 07 1.07E 10 1.33E 08 9.00E 07 1.68E 08 0.00E-01 0.00E-Ol 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 0.00E-01 I-131 4.88E 08 7.64E 07 8.54E 08 8.59E 08 1.41E 09 2.84E 11 0.00E-01 0.00E-01 I-132 3.89E-01 9.95E-Ol 4.60E-01 8.45E-01 1 29E 00 3.92E 01 O.OOE-01 O.OOE-01 I-133 5.48E 06 5.84E 06 1.17E 07 1.45E 07 2.41E 07 2.69E 09 0.00E-Ol 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 0.00E-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 0.00E-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-Ol 2.31E 09 O.OOE-01 Ba-140 4.36E 06 3.78E 07 7A7E 07 6.54E 04 2.13E 04 O.OOE-01 3.90E 04 O.OOE-01 Ce-141 9.73E 02 8.17E 06 1.3lf 04 6.55E 03 2.87E 03 0.00E-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 0.00E-01

• R Values in units of mrem/yr per micro-Ci/m for inhalation and tritium, and in units of mrem/yr per micro-Ci/sec per m-2 f<< all others

TABLE 3.3-11 R VALUES FOR THE SHEARON HARRIS NUCLEAR POMER PLANT>>

PATHWAY = Cow Nilk AGE GROUP = Infant Nuclide GI-Tract Liver Kidney Thyroid Skin H-3 2.40E 03 2.40E 03 0.00E-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 O.OOE-01 O.OOE-01 O.OOE-01 Cr-51 9.77E 04 2.85E 06 0.00E-01 0.00E-01 1.39E 04 6.38E 04 1.24E 05 O.OOE-01 Nn-54 5.37E 06 8.71E 06 O.OOE-01 2.37E 07 5.25E 06 O.OOE-01 O.OOE-01 0.00E-01 Fe-59 9.23E 07 1.12E 08 1.34E 08 2.34E 08 0.00E-01 O.OOE-01 6.92E 07 0.00E-Ol Co-58 3.60E 07 3.59E 07 O.OOE-01 1.44E 07 O.OOE-01 O.OOE-Ol 0.00E-Ol O.OOE-01 Co-60 1.29E 08 1.30E 08 O.OOE-01 5.47E 07 0.00E-01 0.00E-01 0.00E-01 0.00E-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 0.00E-01 1.39E 10 O.OOE-01 O.OOE-01 0.00E-01 0.00E-01 Sr-89 2.17E 08 1.55E 08 7.55E 09 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 0.00E-Ol Sr-90 2.05E 10 1.00E 09 8.04E 10 0.00E-01 0.00E-01 O.OOE-Ol 0.00E-01 O.OOE-Ol Y-91 1.16E 08 3.12E 06 4.36E 04 O.OOE-01 0.00E-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.GOE-01 O.OOE-01 O.OOE-01 Ru-103 1.74E 03 6.33E 04 5.21E 03 0.00E-01 1.08E 04 O.OOE-01 O.OOE-01 0.00E-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-llN 1.19E 08 9.32E 09 2.46E 08 1.80E 08 2.57E 08 0.00E-01 0.00E-01 0.00E-01 Te-127M 3.75E 07 1.25E 08 3.10E 08 1.03E 08 7.64E 08 8.96E 07 0.00E-01 O.OOE-01 Te-12% 5.57E 07 2.16E 08 3.62E 08 1.24E 08 9.05E 08 1.39E 08 0.00E-01 0.00E-01 I-131 9.23E 08 7.49E 07 1.78E 09 2.10E 09 2.45E 09 6.90E 11 O.OOE-01 O.OOE-01 I-132 6.90E-01 1.57E-OO 9.55E-01 1.94E 00 2.16E 00 9.09E 01 O.OOE-01 0.00E-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 5.83E 04 8.17E 04 1.63E 05 1.81E 05 1.46E 07 O.OOE-01 0.00E-Ol Cs-134 4.19E 09 1.13E 08 2.23E 10 4.15E 10 1.07E 10 O.OOE-01 4.38E 09 0.00E-01 Cs-136 1.37E 09 5.58E 07 1.25E 09 3.67E 09 1.46E 09 0.00E-01 2.99E 08 0.00E-01 Cs-137 2.72E 09 1.20E 08 3.28E 10 3.84E 10 1.03E 10 O.OOE-Ol 4.18E 09 O.OOE-01 Ba-140 7.91E 06 3.77E 07 1.54E 08 1.54E 05 3.65E 04 0.00E-01 9.43E 04 O.OOE-01 Ce-141 1.87E 03 3.21E 06 2.60E 04 1.59E 04 4.90E 03 0.00E-01 O.OOE-01 O.OOE-01 Ce-144 7.82E 04 8.01E 07 1.40E 06 5.71E 05 2.31E 05 O.OOE-01 0.00E-01 0.00E-01

• R Values in units of mrem/yr per micro-Ci/m for inhalation and tri tium, and in units of mrem/yr per micro-Ci/sec per m-2 for all others.

TABLE 3.3-12 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT>>

PATHWAY = Goat Milk AGE GROUP = Adult Nuclide GI-Tract Liver Kidney Thyroid 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-Ol O.OOE-01 O.OOE-01 O.OOE-G1 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 0.00E-Ol O.OOE-Ol Fe-59 2.08E 05 1.81E 06 2.31E 05 5.42E 05 0.00E-01 O.OOE-01 1.51E 05 0.00E-01 Co-58 7.54E 05 6.82E 06 O.OOE-01 3.36E 05 O.OOE-Ol O.OOE-01 O.OOE-Ol O.OOE-01 Co-60 2.69E 06 2.29E 07 O.OOE-01 1.22E 06 0.00E-Ol 0.00E-01 O.OOE-01 O.OOE-Ol Zn-65 1.65E 08 2.31E 08 1.15E 08 3.66E 08 2.45E 08 O.OOE-01 O.OOE-01 O.OOE-01 Rb-86 9.05E 07 3.83E 07 0.00E-01 1.94E 08 0.00E-Ol 0.00E-01 O.OOE-Ol 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 0.00E-01 0.00E-Ol O.OOE-01 0.00E-01 O.OOE-01 Y-91 1.64E Ol 3.37f 05 6.13E 02 O.OOE-01 0.00f-01 O.OOE-01 0.00E-Ol O.OOE-01 Zr-95 1.46E 01 6.85E 04 6.74E 01 2.16E 01 3.39E 01 0.00f-01 O.OOE-01 O.OOE-01 Nb-95 1.78E 03 2.01E 07 5.94E 03 3.31E 03 3.27E 03 O.OOE-01 O.OOE-Ol 0.00f-01 Ru-103 3.16E 01 8.56E 03 7.33E 01 0.00E-01 2.80E 02 0.00E-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-1194 2.45E 06 1.68E 09 4.46E 06 4.12E 06 8.11E 06 0.00E-01 O.OGE-01 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 0.00E-01 Te-129M 05 '.43E 2.36E 07 4.69E 06 1.75E 06 1.96E 07 1.61E 06 O.OOE-01 0.00E-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 0.00E-01 0.00E-01 I-133 1.68E 06 4.95E 06 3.17E 06 5.51E 06 9.61E U6 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-Ol O.OOE-01 Cs-134 2.01E 10 4.31E 08 1.03E 10 2.46E 10 7.97E 09 O.OOE-01 2.65E 09 O.OOE-01 Cs-136 1.42E 09 2.24E 08 4.99E 08 1.97E 09 1.10E 09 0.00E-Ol 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 0.00E-01 Ce-141 2.68E 01 9.03E 05 3.49E 02 2.36E 02 1.10E 02 O.OOE-01 O.OOE-01 0.00E-Ol Ce-144 1.38E 03 8.71E 06 2.58E 04 1.08E 04 6.39E 03 0.00E-01 0.00E-01 0.00E-01

• R Values in units of mrem/yr per micro-Ci/m for inhalation and tritium, and in units of mrem/yr per micro-Ci/sec per m-2 for all others.

TABLE 3-3-13 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANY" PATHWAY = Goat Milk AGE GROUP = Teen Nuclide 6I-Tract Liver Kidney Thyroid Skin 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 0.00E-01 O.OOE-01 Cr -51 3.63E 03 6.10E 05 O.OOE-01 0.00E-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 0.00E-01 2.96E 05 O.OOE-01 Co-58 1.30E 06 7.80E 06 O.OOE-01 5.66E 05 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 Co-60 4.66E 06 2.69E 07 O.OOE-01 2.07E 06 0.00E-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 0.00E-01 O.OOE-01 O.OOE-Ol I

Rb-86 1.66E 08 5.24E 07 O.OOE-01 3.54E 08 0.00E-01 0.00E-Ol O.OOE-01 O.OOE-Ol 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 3.02E 01 4.62E 05 1.13E 03 O.OOE-01 O.OOE-Ol O.OOE-01 O.OOE-01 O.OOE-01 Zr-95 2.56E Ol 8.59E 04 1.18E 02 3.72E 01 5.47E 01 O.OOE-01 0.00E-01 0.00E-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 Ol 1.09E 04 1.30E 02 0.00E-01 4.60E 02 0.00E-01 O.OOE-01 0.00E-01 Ru-106 3.51E 02 1.34E 05 2.79E 03 O.OOE-01 5.38E 03 O.OOE-01 0.00E-01 O.OOE-01 Ag-ll(N. 4.24E 06 1.96E 09 7.37E 06 6.97E 06 1.33E 07 0.00E-01 0.00E-01 0.00E-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 0.00E-01 O.OOE-01 I-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 I-132 2.19E-01 2.66E-01 2.33E-01 6.11E-01 9.62E-01 2.06E 01 O.OOE-01 O.OOE-01 I-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 0.00E-01 Cs-134 1.96E 10 5.26E 08 1.80E 10 4.23E 10 1.34E 10 0.00E-01 5.13E 09 0.00E-01 Cs-136 2.25E 09 2.69E 07 8.50E 08 3.34E 09 1.82E 09 O.OOE-01 2.87E 08 0.00E-01 Cs-137 1.19E 10 4.85E 08 2.56E 10 3.41E 10 1.16E 10 0.00E-Ol 4.51E 09 0.00E-01 Ba-140 2.39E 05 5.72E 06 3.71E 06 4.55E 03 1.54E 03 O.OOE-Ol 3.06E 03 0.00E-Ol Ce-141 4.91E 01 1.22E 06 6.40E 02 4.27E 02 2.01E 02 O.OOE-01 0.00E-01 , O.OOE-01 Ce-144 2.55E 03 1.19E 07 4.74E 04 1.96E 04 1.17E 04 O.OOE-Ol 0.00E-01 O.OOE-01

• R Values in units of mrem/yr per micro-Ci/m3 for inhalation tritium, and in units of mrem/yr per micro-Ci/sec per m-2 for all others.

TABLE 3.3-14 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT~

PATHWAY = Goat blilk AGE GROUP = Child Nuclide 61-Tract Liver Kidney Thyroid 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-01 O.UOE-01 O.OQE-01 O.OOE-01 Cr-51 7.40E 03 3.93E 05 O.OOE-01 0.00E-Ol 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-Ol O.OOE-01 Fe-59 7.52E 05 1.57E 06 9.34E 05 1.51E 06 0.00E-01 O.OOE-01 4.38E 05 O.OOE-01 Co-58 2.65E 06 5.05E 06 O.OOE-01 8.65E 05 0.00E-Ol O.OOE-01 O.OOE-01 O.OOE-01 Co-60 9.48E 06 1.78E 07 0.00E-01 3.21E 06 0.00E-Ol 0.00E-01 0.00E-01 O.OOE-01 Zn-65 5.74E 08 1.62E 08 3.47E 08 9.24E 08 5.82E 08 O.OOE-01 0.00E-Ol O.OOE-01 Rb-86 4.04E 08 4.22E 07 0.00E-01 6.57E 08 0.00E-Ol O.OOE-01 0.00E-01 O.OOE-01 Sr-89 2.38E 08 3.23E 08 8.34E 09 O.OOE-01 O.OOE-01 O.OOE-Ol O.OOE-01 O.OOE-01 Sr-90 3.93E 10 2.09E 09 1.55E 11 0.00E-01 0.00E-Ol 0.00E-01 0.00E-01 O.OOE-Ol Y-91 7.45E 01 3.71E 05 2.79E 03 0.00E-Ol 0.00E-Ol O.OOE-01 O.OOE-Ol O.OOE-01 Zr-95 5.36E 01 6.28E 04 2.74E 02 6.02E 01 8.62E 01 0.00E-01 O.OOE-01 0.00E-01 Nb-95 6.37E 03 1.65E 07 2.29E 04 8.91E 03 8.37E 03 O.OOE-01 O.OOE-01 0.00E-01 Ru-103 1.19E 02 7.98E 03 3.09E 02 O.OOE-01 7.77E 02 O.OOE-01 O.OOE-Ol O.OOE-01 RU-106 8.56E 02 1.07E 05 6.86E 03 0.00E-01 9.27E 03 O.OOE-01 O.OOE-01 O.OOE-Ol Ag-11(N 8.63E 06 1.28E 09 1.60E 07 1.08E 07 2.01E 07 0.00E-01 0.00E-01 O.OOE-Ol Te-127M 2.18E 06 1.49E 07 1.84E 07 4.95E 06 5.24E 07 4.40E 06 0.00E-01 0.00E-01 Te-129N 3.28E 06 2.58E 07 2.12E 07 5.91E 06 6.21E 07 6.82E 06 0.00E-01 O.OOE-01 I-131 5.85E 08 9.17E 07 1.02E 09 1.03E 09 1.69E 09 3.41E 11 O.OOE-Ol 0.00E-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 V.OOE-Ol O.OOE-01 I-135 4.01E 04 6.47E 04 4.72E 04 8.49E 04 1.30E 05 7.52E 06 0.00E-01 0.00E-01 Cs-134 1.43E 10 3.67E 08 4.14E 10 6.80E 10 2.11E 10 O.OOE-01 7.56E 09 0.00E-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 3.702 08 6.17E 10 5.91E 10 1.93E 10 O.OOE-Ol 6.93E 09 0.00E-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-Ol 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

• R Values in units of mrem/yr per micro-Ci/m for inhalation and tritium, and in units of mrem/yr per micro-Ci/sec per m-2 for all others.

TABLE 3.3-15 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT~

PATHWAY = Goat Milk AGE GROUP = Infant Nuclide T.Body GI-Tract Liver Kidney Thyroid Skin H-3 4.90E 03 4.90E 03 0.00E-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 0.00E-Ol 0.00E-01 1.67E 03 7.65E 03 1.49E 04 O.OOE-Ol Mn-54 6.45E 05 1.04E 06 0.00E-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 0.00E-Ol 0.00E-01 9.00E 05 0.00E-01 Co-58 4.31E 06 4.31E 06 O.OOE-01 1.73E 06 O.OOE-01 0.00E-Ol O.OOE-01 O.OOE-01 Co-60 1.55E 07 1.56E 07 0.00E-01 6.56E 06 O.OOE-01 0.00E-01 0.00E-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 0.00E-01 1.67E 09 O.OOE-01 0.00E-Ol O.OOE-01 0.00E-01 Sr-89 4.55E 08 3.26E 08 1.59E 10 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-Ol O.OOE-01 Sr-90 4.30E 10 2.11E 09 1.69E 11 O.OOE-Ol 0.00E-Ol 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 0.00E-Ol Zr-95 8.41E 01 5.90E 04 4.85E 02 1.19E 02 1.28E 02 0.00E-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 0.00E-01 O.OOE-01 Ru-103 2.09E 02 7.60E 03 6.25E 02 0.00E-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 0.00E-01 O.OOE-01 Ag-11Q1 1.43E 07 1.12E 09 2.95E 07 2.16E 07 3.08E 07 0.00E-01 O.OOE-01 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-Ol Te-129M 6.69E 06 2.59E 07 4.34E 07 1.49E 07 1.09E 08 1.67E 07 O.OOE-01 0.00E-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 I-132 8.28E-01 1.88E 00 1.15E 00 2.33E 00 2.59E 00 1.09E 02 0.00E-01 0.00E-01 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 0.00E-01 O.OOE-Ol Cs-134 1.26E 10 3.38E 08 6.68E 10 1.25E 11 3.21E 10 O.OOE-01 1.31E 10 O.OOE-01 Cs-136 4.11E 09 1.67E 08 3.75E 09 1.10E 10 4.39E 09 O.OOE-01 8.98E 08 0.00E-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 O.OOE-01 Ce-141 2.24E 02 9.85E 05 3.13E 03 1.91E 03 5.88E 02 O.OOE-01 O.OOE-01 O.OOE-01 Ce-144 9.39E 03 9.61E 06 1.67E 05 6.86E 04 2.77E 04 O.OOE-01 0.00E-01 O.OOE-01

• R Values in units of mrem/yr per micro-Ci/m3 for inhalation tritium, and in units of mrem/yr per micro-Ci/sec per m-2 for all others.

0 TABLE 3.3-16 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Inhal AGE GROUP = Adult Nuclide Bone Liver Kidney Thyroid H-3 1.26E 03 1.26E 03 0.00E-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 0.00E-01 O.OOE-01 O.OOE-01 0.00E-01 Cr-51 9.99E 01 3.32E 03 0.00E-Ol 0.00E-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 0.00E-01 Fe-59 1.05E 04 1.88E 05 1.17E 04 2.77E 04 0.00E-01 O.OOE-01 1.01E 06 0.00E-01 Co-58 2.07E 03 1.06E 05 O.OOE-01 1.58E 03 O.OOE-01 O.OOE-01 9.27E 05 0.00E-01 Co-60 1.48E 04 2.84E 05 0.00E-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-Ol O.OOE-01 1.40E 06 O.OOE-01 Sr-90 6.09E 06 7.21E 05 9.91E 07 0.00E-01 O.OOE-Ol O.OOE-01 9.59E 06 O.OOE-01 Y-91 1.24E 04 3.84E 05 4.62E 05 O.OOE-Ol 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 0.00E-01 5.82E 03 0.00E-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-11(N 5.94E 03 3.02E 05 1.08E 04 9.99E 03 1.97E 04 O.OOE-01 4.63E 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-12% 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-132 1.16E 03 4.06E 02 1.16E 03 3.25E 03 5.18E 03 1.14E 05 O.OOE-01 O.OOE-01 I-133 4.51E 03 8.87E 03 8.63E 03 1.48E 04 2.58E 04 2.15E 06 O.OOE-01 O.OOE-01 I-135 2.56E 03 5.24E 03 2.68E 03 6.97E 03 1.11E 04 4.47E 05 O.OOE-01 O.OOE-01 Cs-134 7.27E 05 1.04E 04 3.72E 05 8.47E 05 2.87E 05 0-OOE-01 9.75E 04 O.OOE-01 Cs-136 1.10E 05 1.17E 04 3.90E 04 1.46E 05 8.55E 04 O.OOE-01 1.20E 04 0.00E-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 01 1.67E 01 O.OOE-Ol 1.27E 06 0.00E-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

• R Values in units of mrem/yr per micro-Ci/m for inhalation and tri tium, and in units of mrem/yr per micro-Ci/sec per m-2 for all others.

TABLE 3.3-17 R VALUES FOR THE SHEARON HARRIS NUCLfAR POWER PLANT~

PATHWAY = Inhal AGE GROUP = Teen Nuc1ide GI-Tract Liver Kidney Term d Skin H-3 1.27E 03 1.27E 03 0.00E-Ol 1.27f 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-01 Cr-51 1.35E 02 3.00f 03 0.00E-01 O.OOE-Ol 3.07E 01 7.49E 01 2.09E 04 O.OOE-01 Nn-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 0.00E-01 2.07E 03 O.OOE-01 O.OOE-01 1.34E 06 O.OOE-01 Co-60 1.98E 04 2.59E 05 0.00E-01 1.51E 04 O.OOE-01 O.OOE-01 8.71E 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 0.00E-Ol 1.90E 05 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 Sr-89 1.25E 04 3.71E 05 4.34E 05 O.OOE-01 0.00E-01 O.OOE-01 2.41E 06 O.OOE-01 6.67E 06 7.64E 05 1.08E 08 0.00E-01 O.OOE-01 O.OOE-01 1.65E 07 0.00E-01 1.77E 04 4.08E 05 6.60E 05 O.OOE-01 O.OOE-01 O.OOE-01 2.93E 06 O.OOE-01 3.15E 04 1A9E 05 1.45E 05 4.58E 04 6.73E 04 O.OOE-01 2.68E 06 O.OOE-Ol Nb-95 5.66E 03 9.67E 04 1.85E 04 1.03E 04 9.99E 03 O.OOE-01 7.50E 05 0.00E-01 Ru-103 8.95E 02 1.09E 05 2.10E 03 O.OOE-01 7.42E 03 O.OOE-01 7.82E 05 0.00E-01 Ru-106 1.24f 04 9.59E 05 9.83E 04 O.OOE-01 1.90E 05 O.OOE-01 1.61E 07 O.OOE-01 Ag-110l 7.98E 03 2.72E 05 1.38E 04 1.31E 04 2.50E 04 O.OOE-01 6.74E 06 O.OOE-01 Te-127th 2.18E 03 1.59E 05 1.80E 04 8.15E 03 6.53E 04 4.38E 03 1.65E 06 O.OOE-Ol Te-12% 2.24E 03 4.04E 06 1.39E 04 6.57E 03 5.18E 04 4.57E 03 1.97E 06 0.00E-01 I-131 2.64E 04 6.48E 03 3.54E 04 4.90E 04 8.39E 04 1.46E 07 O.OOE-01 0.00E-01 I-132 1.57E 03 1.27E 03 1.59E 03 4.37E 03 6.91E 03 1.51E OS O.OOE-01 O.OOE-01 I-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-Ol 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 0.00E-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 0.00E-01 Ce-144 2.62E 05 8.63E 05 4.88E 06 2.02E 06 1.21E 06 O.OOE-01 1.33E 07 0.00E-01

• R Values in units of mrem/yr per micro-Ci/m for inhalation and tritium, and in units of mrem/yr per micro-Ci/sec per m-2 for all others.

TABLE 3-3-18 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Inhal AGE GROUP = Child Nuclide T.Body GI-Tract Liver Kidney Thyroid 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 0.00E-01 Fe-59 1.67E 04 7.06E 04 2.07E 04 3.34E 04 0.00E-01 0.00E-01 1.27E 06 O.OOE-01 Co-58 3.16E 03 3.43E 04 O.OOE-Ol 1.77E 03 0.00E-01 O.OOE-Ol 1.10E 06 O.OOE-01 Co-60 2.26E 04 9.61E 04 O.OOE-01 1.31E 04 0.00E-01 O.OOE-01 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 0.00E-Ol Rb-86 1.14E 05 7.98E 03 0.00E-01 1.98E 05 O.OOE-01 0.00E-01 0.00E-Ol O.OQE-01 Sr-89 1.72E 04 1.67E 05 5.99E 05 O.OOE-01 O.OOE-Ol O.OOE-01 2.15E 06 0.00E-01 Sr-90 6.43E 06 3.43E 05 1.01E 08 O.OOE-01 0.00E-01 O.OOE-01 1.47E 07 O.OOE-01 2.43E 04 1.84E 05 9.13E 05 0.00E-01 0.00E-01

,"-",, 3.69E 04 6.10E 04 1.90E 05 4.17E 04 O.OOE-01 5.95E 04 O.OOE-01 O.OOE-01 2.62E 06 2.23E 06 O.OOE-01 Nb-95 6.54E 03 3.69E 04 2.35E 04 9.16E 03 8.61E 03 O.OOE-01 6.13E 05 O.OOE-01 RU-103 1.07E 03 4.47E 04 2.79E 03 O.OOE-01 7.02E 03 0.00E-01 6.61E 05 O.OOE-01 Ru-106 1.69E 04 4.29E 05 1.36E 05 O.OOE-01 1.84E 05 O.OOE-01 1.43E 07 O.OOE-01 Ag-1101 9.13E 03 1.00E 05 1.68E 04 1.14E 04 2.12E 04 O.OOE-01 5.47E 06 O.OOE-01 Te-127M 3.01E 03 7.13E 04 2.48E 04 8.53E 03 6.35E 04 6.06E 03 1.48E 06 O.OOE-01 Te-12% 3.04E 03 1.81E 05 1.92E 04 6.84E 03 5.02E 04 6.32E 03 1.76E 06 O.OOE-01 I-131 2.72E 04 2.84E 03 4.80E 04 4.80E 04 7.87E 04 1.62E 07 O.OOE-Ol O.OOE-01 I-132 1.87E 03 3.20E 03 2.11E 03 4.06E 03 6.24E 03 1.93E 05 O.OOE-01 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 0.00E-01 Cs-134 2.24E 05 3.84E 03 6.50E 05 1.01E 06 3.30E 05 O.OOE-01 1.21E 05 0.00E-Ol Cs-136 1.16E 05 4.17E 03 6.50E 04 1.71E 05 9.53E 04 O.OOE-01 1.45E 04 0.00E-01 Cs-137 1.28E 05 3.61E 03 9.05E 05 8.24E 05 2.82E 05 O.OOE-01 1.04E 05 0.00E-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 5.43E 05 O.OOE-Ol 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

• R Values in units of mrem/yr per micro-Ci/m for inhalation and tritium, and in units of mrem/yr per micro-Ci/sec per m-2 for all others.

TABLE 3.3-19 R VALUES FOR THE SHEARON HARRIS NUCLEAR POMER PLANT~

PATHWAY = Inhal AGE GROUP = Infant Nuclide GI-Tract Liver Kidney Thyroi d 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-01 O.OOE-01 O.OOE-01 O.OOE-01 Cr-51 8.93E 01 3.56E 02 O.OOE-01 0.00f-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-Ol 1.01E 06 O.OOE-01 Co-58 1.82E 03 1.11E 04 O.OOE-01 1.22E 03 O.OOE-Ol O.OOE-Ol 7.76E 05 O.OOE-01 Co-60 1.18E 04 3.19E 04 0.00E-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 3.24f 04 O.OOE-01 6.46E 05 O.OOE-Ol Rb-86 8.81E 04 3.03E 03 0.00f-01 1.90E 05 O.OOE-01 O.OOE-Ol O.OOE-01 O.OOE-01 Sr-89 1.14E 04 6.39E 04 3.97E 05 0.00E-01 O.OOE-01 O.OOE-01 2.03E 06 0 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 0.00E-01'.OOE-01 Y-91 1.57E 04 7.02E 04 5.87E 05 O.OOE-Ol O.OOE-01 O.OOE-01 2.45E 06 Zr-95 2.03E 04 2.17E 04 1.15E 05 2.78E 04 3.10E 04 0.00E-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 RQ-103 6.78E 02 1.61E 04 2.01E 03 0.00E-01 4.24E 03 O.OOE-01 5.51E 05 O.OOE-01 RU-106 1.09E 04 1.64E 05 8.67E 04 0.00E-Ol 1.06E 05 O.OOE-01 1.15E 07 O.OOE-01 Ag-11(M 4.99E 03 3.30E 04 9.97E 03 7.21E 03 1.09E 04 O.OOE-01 3.66E 06 O.OOE-01 Te-127M 2.07E 03 2.73E 04 1.66E 04 6.89E 03 3.75E 04 4.86E 03 1.31E 06 O.OOE-01 Te-1291 2.22E 03 6.89E 04 1.41E 04 6.08E 03 3.17E 04 5.47E 03 1.68E 06 0.00E-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 I-132 1.26E 03 1.90E 03 1.69E 03 3.54E 03 3.94E 03 1.69E 05 0.00E-01 O.OOE-01 I-133 5.59E 03 2.15E 03 1.32E 04 1.92E 04 2.24E 04 3.55f 06 O.OOE-01 O.OOE-01 I-135 2.77E 03 1.83E 03 3.86E 03 7.59E 03 8.46E 03 6.95E 05 O.OOE-01 O.OOE-Ol 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 0.00E-01 1.17E 04 O.OOE-01 Cs-137 4.54f 04 1.33E 03 5.48E 05 6.11E OS 1.72E 05 O.OOE-Ol 7.12E 04 O.OOE-01 Ba-140 2.89E 03 3.83E 04 5.59f 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 0.00E-01 Ce-144 1.76E 05 1.48E 05 3.19E 06 1.21E 06 5.37E 05 O.OOE-Ol 9.83E 06 O.OOE-01

• R Values in units of mrem/yr per micro-Ci/m for inhalation and tritium, and in units of mrem/yr per micro-Ci/sec per m-2 for all others.

REM - RADIATION EFFLUENT MONITOR Figure 3.1 SHNPP GASEOUS W . TE STREAMS UNIT 1 WPB - WASTE PROCESS BLDG RAB - REACTOR AU BLDG FHB - FUEL HANDLI G TURBINE BLDG VENT STACK 3A RE REM ITV-2424 CONDENSER VACUUMPUMP WASTE PROCESSING BLDG VENT STACK 5 REM RKM IWV Sddd WPB HOT & COLD LAUNDRY WPB OFFICE AREA EXHAUST WPB COLD LAUNDRY DRYERS WPB OFFICE AREA WPB CONTROL ROOM SMOKE EXHAUST WPB CHILLER ROOM EXHAUST WPB GENERAL AREA EXHAUST WASTE PROCESSING AREAS FILTERED EXHAUST WASTE GAS DECAY TANKS WASTE PROCESSING BLDG VENT STACK 5A REM RCM IWV-$447 WPB SWITCHG EAR ROOM EXHAUST WPB HVAC EQUIP. ROOM EXHAUST WPB PERSONNEL HANDLING FACILITYEXHAUST WPB HOT & LOW ACTIVITYEXHAUST WPB LAB AREA EXHAUST PLANT VENT STACK 1 REM RKM RCM IAV S$ 045A CONTAINMENTPRE ENTRY PURGE R E M- I A V-S 4 S I RKM FHB NORMAL EXHAUST NORTH RAB NORMAL EXHAUST REM.I AV $ $ $ 2A REM FHB NORMAL EXHAUST SOUTH RAB EMERGENCY EXHAUST REM RKM-Iel:S$ 0$

FHB NORMAL EXHAUST (OPER. FL) SOUTH RAB VENTILATIONSYSTEM RCM REM IFL-S$ 01 FHB NORMAL EXHAUST (OPER. FL) SOUTH HYDROGEN PURGE REM RKM IFL S404A 5A RAB SMOKE PURGE REM FHB EMERGENCY EXHAUST REM-I FL-Sdodn-sa RAB PURGE

RWST REFUELING WATER STORAGE TANK RMWST ~ REACTOR MAKEUP WATER STORAGE TANK DIESEL FUEL OIL STORAGETANKS CST ~ CONDENSATE STORAGE TANK PLANT MAGNETIC NORTH NORTH Q

z 0 HVAC EQUIPMENT D ROOM CL PLANT VENT U K z VENT ST ACK 3A DIESEL 0

z PERATION MACHINE GEN BLDG x OFFICE SHOP CONTAIN ENT 8UILDIN 0

TURBINE BUILDING Cl WASTE Cl PROCESSING BLDG WST CST

~+ EA RMWST BA VENTSTACK

~use GAS WATER STORAGE TREATMENT SERVICE BUILDING SECURITY PARKING AREA.

BUILDING SHEARON HARRIS NUCLEAR POWER PLANT AUX CAROLINA POWER & LIGHT COMPANY BOILER AREA SCHEMATIC OF PLANT AIRBORNE EFFLUENT REI.EASE POINTS REF DWG: CAR-2165-G-002 {REV 8, OPENI FIGURE 3.2

Figure 3.3 SHNPP CONDENSER OFF-GAS SYSTEM ATMOSPHERE TURBINE BLDG VENT STACK

=8 CVPETS REM R EM.1 TV-3534 MAIN CONDENSER HOGGING VALVE ATMOSPHERE GLAND STEAM REM ATMOSPHEREa ~

COND, aCONDENSER VACUUM PUMP EFFLUENT TREATMENT SYSTEM

'adiation monitoring at these points is tentative.

3-49

4.0

~

~

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table 4.1 contains the sample point description, sampling and collection frequency analysis, and analysis frequency for various exposure pathways in the vicinity of the SHNPP for the radiological monitoring program. Figure 4.1-1 shows the exclusion boundary surrounding SHNPP. Figures 4.1-2, 4.1-3, and 4.1-4 show the locations of the various sampling points and TLD locations.

Figure 4.1-5 provides a legend for Figures 4.1-2 through 4.1-4.

4.1 Deviations from the Shearon Harris Nuclear Power Plant (SHNPP)

Environmental Report Operating License Stage (EROL) are noted below:

4.1.1 Shoreline sediment sampling will occur at Location 41 and at Location 26 (Harris Lake Spillway). A bottom sediment is collected at location 52. .

4.1.2 Locations 48, 49, 50, and 53 have been added to increase the monitoring coverage of the pr ogram.

4.1.3 Sample Location 47 has been deleted since produce is no longer available at that location.

4.1.4 Location 51 (water treatment facility at SHNPP) has been added to monitor the drinking water pathway to the plant personnel.

I 4.1.5 Location 42 has been changed. A milk cow no longer resides at the previous location.

4.1.6 Location 19 has been moved across the road to Olive's Dairy.

Triple H Dairy has ceased operation.

4.1.7 Location 43 is Goodwin's Farm. It was incorrectly listed in the EROL as Goodman's Farm.

4.1.8 Location 22, Ragan's Dairy Farm has been deleted as a milk sampling location.

4.1.9 The sample location descriptions for Stations 1, 2, 3, 4, 7, 8, 9, 15, 19, 22, 24, 25, 26, 27, 29, 30, 31, 32, 33, 39, 43, 46 have been revised to more accurately reflect their location.

4.1.10 Air sampling Location 26 has been added to increase the monitoring coverage of the program.

4.1.11 TLD locations 10, 11, 12, and 13 have been changed.

4.1.12 SW and DW location 40 has been moved to a facility that provides electricity for the sampling apparatus.

4-1

TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MON ITORING 'ROGRAM Sample Exposure Pathway Point Sample Point, Description Sampling and Analysis and/or Sam le ID No. Distance, and Direction Collection Fre uenc ~Fee uency Analysis

l. Airborne O.l mi. S. on SR. 81134 Continuous operating Gross Beta Particulates from SR. 81011 intersection. sampler with sample I-131 and Radio- N. sector, 2.5 mi. from collection as required (charcoal iodine site. by dust loading, but at canisters )

least once per 7 days. (}uarterly Gamma Isotopic Composite by Location 1.4 mi. S. on SR. 81134 Continuous operating Weekly Gross Beta from SR. 81011 inter- sampler with sample Weekly I-131 section. NNE sector, 1.5 collection as required (charcoal mi. from site. by dust loading, but at canisters3) least once per 7 days. quarterly Gamma Isotopic Composite by Location Oe9 mi. S. on SR. f1135 Continuous operating Weekly Gross Beta ti from U.S. 81 intersec on. sampler with sample Meekly I-131 HENDEC. NE sector, 2e6 mi. collection as required (cnarcoa from site. by dust loading, but at canister )

least once per 7 days. quarterly Gamma Isotopic Composite by Location 4-2

TABLE 4.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description Sampling and Analysis and/or Sam le ID No. Distance, and Direction Collection Fre uency ~Fre uency Analysis 0.7 mi. N on SR ¹1135 from Continuous operating Weekly Gross Beta U.S. ¹ 1 intersection, at sampler with sample Weekly I-131 New Hill NNE sector, 3.5 mi. collection as required (charcoal3 from site. by dust loading but at canisters )

least once per 7 days. quarterly Gamma Isotopic5 Composite by Location Pittsboro. Continuous operating Meekly Gross Beta

> 12 mi. WNW sampler with sample Meekly I-131 sector from site collection as required (charcoal (Control Station)4 by dust loading but at canisters3) least once per 7 days. t}uarter ly Gamma Isotopic Composite by Location 26 Harris Lake Spillway. Continuous operating Weekly Gross Beta S. sector. 4.7 mi. from sampler with sample Weekly I-131 site. collection as required (charcoal by dust loading but at canisters3) least once per 7 days. quarterly Gamma Isotopic Composite by Location

2. Direct 0.1 mi. S on SR. ¹1134 Continuous measurement (}uarterly Gamma Dose Radiation from SR. ¹ 1011 inter- with an integrated section.'. sector, 2.5 readout at least mi. from site. once per quarter.

TABLE 4.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description Sampling and Analysis and/or Sam le ID No. Distance, and Direction Collection Fre uenc ~Fre uency Analysis

2. Direct 1.4 mi. S. on SR. $ 1134 Continuous measurement (}uarterly Gamma Dose Radiation from SR. 0 1011 inter- with an integrated (continued) section. NNE sector, readout at least 1.5 mi. from site. once per quarter.

0.9 mi. S. on SR. 81135 Continuous measurement (}uarterly Gamma Dose from U.S. kl inter- with an integrated section HE&EC. NE sector, readout at least 2.2 mi. from site. once per quarter.

0.5 mi. S on SR 0 1135 Continuous measurement quarterly Gamma Dose from intersection with SR with an integrated 1011. NNE sector, 3.2 readout at least mi. from site. once per quarter.

Pittsboro. WNW sector, Continuous measurement quarterly Gamma Dose

> 12 mi. from sit~ with an integrated Tcontrol station) readout at least once per quarter Intersection of Continuous measurement .quarterly Gamma Dose SR. 81134 & SR. 81135. with an integrated ENE sector, 0.9 mi. readout at least from site. once per quarter.

Extension of SR. Continuous measurement l}uarterly Gamma Dose

$ 1134. E. sector, with an integrated 0.8 mi from site. readout at least once per quarter.

4-4

TNLE 4.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description Sampling and Analysis and/or Sam le ID No. Distance, and Direction Collection Fre uency ~Fre uency Analysis

2. Direct Dead end of road. Continuous measurement quarterly Gamma Dose Radiation Extension of SR with an integrated (continued) 81134. ESE sector, readout at least 0.7 mi. from site. once per quarter.

1 mi. S on SR. 8 1130 from Continuous measurement (}uarterly Gamma Dose intersection of SR k'127, with an integrated 1115, and 1130. Holleman's readout at least Crossroads. SE sector, 2.3 once per quarter.

mi. from site.

10 SR. 8 1130 S of inter- Continuous measurement guar terly Gamma Dose section of SR 0 1127, 1115, with an integrated and 1130. SSE section, readout at least 2.2 mi. from site. once per quarter.

SHNPP site. S. sector, Continuous measurement t}uarterly Gamma Dose 0.7 mi. of site. with an integrated readout at least once per quarter.

12 SHNPP site. SSW sector, Continuous measurement (}uarterly Gamma Dose 0.8 mi. of site. with an integrated readout at least once per quarter 13 SHNPP site. SW sector, Continuous measurement quarterly Gamma Dose 0.7 mi. of site. with an integrated readout at least once per quarter.

4-5

TABLE 4.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description Sampling and Analysis and/or Sam le ID No. Distance, and Direction Collection Fre uenc ~Fre uency Analysis

2. Direct 14 SHNPP site. Dead end of Continuous measurement quarterly Gamma Dose Radiation ~

SR 1191. W sector, 1.1 with an integrated (continued) mi. from site. readout at least once per quarter.

15 SR. 0 1191. W. sector, Continuous measurement quarterly Gamma Dose 1.8 mi. from site. with an integrated readout at least once per quarter.

16 1.2 mi. E. of intersection Continuous measurement (}uarterly Gamma Dose of U.S. 81 and SR 1011. with an integrated WNW sector. 1.7 mi. from readout at least site. once per quarter.

17 Intersection of U.S. rrr1 and Continuous measurement t}uarterly Gamma Dose Aux. Res. NW sector, 1.4 with an integrated mi. from site. readout at least once per quarter.

18 0.6 mi. N. on U.S. rrrrl from Continuous measurement quarterly Gamma Dose Station 17. NNW sector, with an integrated 1.3 mi. from site. readout at least once per quarter.

19 0.6 mi. E. on SR 8 1142 Continuous measurement quarterly Garrmra Dose from intersection of SR with an integrated 81141. NNE sector 4.9 mi readout at least from site. once per quarter.

4-6

TABLE 4.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description Sampling and Analysis and/or Sam le ID No. Distance, and Direction Collection Fre uenc ~Fre uency Analysis

2. Direct 20 U.S. 81 at intersection Continuous measurement quarterly Gamma Dose Radiation SR. 1149. NE sector 4.7 with an integrated (continued) mi. from site. readout at least once per quarter.

21 1.2 mi. W. on SR. 0 1152 Continuous measurement t}uarterly Gamma Dose from intersection SR. 0 with an integrated 1153. ENE sector, 4.8 mi. readout at least from site. once per quarter.

22 Formerly Ragan's Dairy on Continuous measurement quarterly Gamma Dose SR. 0 1115. E. sector, with an integrated 4.6 mi. from site. readout at least once per quarter .

23 Holloman Cemetary on Continuous measurement (}uarterly Gamma Dose SR. 8 1116. ESE sector, with an integrated 5.0 mi. from site. readout at least once per quarter 24 Sweet Springs Church on Continuous measurement quarterly Gamma Dose SR 8 1116. SE sector, with an integrated 4.7 mi. from site. readout at least once per quarter.

25 0.2 mi. W. on SR 0 1402 Continuous measurement t}uarterly Gamma Dose from intersection of SR with an integrated 8 1400. SSE sector, 4.8 readout at least once mi. from site. per quarter.

4-7

TABLE 4.1 (continued)

RADIOLOGICAL ENVIRONMENTAL NON ITORING PROGRAH Sample Exposure Pathway Point Sample Point, Description Sampling and Analysis and/or Sam le ID No. Distance, and Direction Collection Fre uency ~Fre uency Analysis

2. Direct 26 Harris Lake Spillway. Continuous measurement quarterly Gamma Dose Radiation S. sector, 4.6 mi. from with an integrated (continued) site. readout at least once per quarter 27 NC 42 9 Buckhorn United Continuous measurement quarter ly Gamma Dose Methodist Church SSW sector, with an integrated 4.8 mi. from site. readout at least once per quarter.

28 0.6 mi. on SR 0 1924 from Continuous measurement (}uar ter ly Gamma Dose intersection of SR 0 1916. with an integrated SW sector, 4.8 mi. from readout at least site. once per quarter.

29 Chemibond Corporation on Continuous measurement (}uarter ly Gamma Dose SR 8 1916. WSW sector, with an integrated 5.6 mi. from site. readout at least once per quarter.

30 Exit intersection of SR Continuous measurement quarterly Gamma Dose 8 1972 and U.S. 81. W. with an integrated sector, 5.1 mi. from site. readout at least once per quarter.

31 SR 8 1910 from intersec- Continuous measurement quarterly Gamma Dose tion of SR 8 1908 and SR with an integrated 0 1909. WNW sector, 4.5 readout at least mi. from site. once per quarter.

4-8

TABLE 4.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description Sampling and Analysis and/or Sam le ID No. Distance, and Direction Collection Fre uency ~Fee uency Analysis

2. Direct 32 SR 0 1008. NW sector, Continuous measurement (}uarterly Gamma Dose Radiation 4.8 mi. from site. with an integrated (continued) readout at least once per quarter .

33 SR 8 1142. 1.7 mi. from Continuous measurement l}uarterly Gamma Dose intersection of SR 1141. with an integrated NNW sector, 4.4 mi. from readout at least site. once per quarter.

34 Apex (Population Center). Continuous measurement (}uarterly Gaoma Dose NE sector, 8.6 mi. from with an integrated site. readout at least once per quarter.

35 Holly Springs. Continuous measurement (}uarterly Gamma Dose E. sector, 6.9 mi. from with an integrated site. readout at least once per quarter.

36 SR 8 1393 at intersection Continuous measurement (}uarterly Gamma Dose of SR 8 1421. E. sector, with an integrated 11.2 mi from site readout at least (Control Station) once per quarter.

37 U.S. 401 at CPBL office, Continuous measurement (}uarterly Gamma Dose Fuquay-Varina (Population with an integrated Center). ESE sector, 9.7 readout at least mi. from site. once per quarter.

TABLE 4.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description Sampling and Analysis and/or Sam le ID Ho. Distance, and Direction Collection Fre uency ~Fre uency Analysis SR 0 1142. 1.5 mi. from Continuous measurement Quarterly Gamma Dose intersection of SR 8 1141. with an integrated N. sector, 4.5 mi. from readout at least site. once per quar ter.

49 0.4 mi. S on SR 0 1127 from Continuous measurement Quarterly Gamma Dose US 1 intersection. NE sec- with an integrated tor, 2.6 mi. from site. readout at least once per quarter.

50 SR 0 1127 W. from inter- Continuous measurement Quarterly Gamma Dose section SR 8 1115 and 1130. with an integrated ESE sector, 2.8 mi. from readout at least site. once per quarter.

53 SR 0 1972 N from inter- Continuous measurement Quarterly Gamma Dose section of SR 8 1910 and with an integrated SR 0 1972. NW sector, 5.5 readout at least miles from site. once per quarter

3. Waterborne

a. Surface 26 Spillway on Main Res. Composite sample Monthly Gross Beta Water S. sector, 4.6 mi. from collected over a Monthly Gamma Isotopic" site. period of < 31 days. Quarterly Tritium 38 Cape Fear Steam Electric Composite sampl e5 Monthly Gross Beta Plant Intake Structure collected over a Monthly Gamma Isotopic (Control Station) period of < 31 days. Quarterly Tritium WSW sector, 6.1 mi. from site.

4-10

TABLE 4.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description 'ampl.ing and Analysis

~dl S 1 III II . Distance, and Direction Collection Fre uency ~Fre uency Analysis 40 US Geological Survey gauging Composite samplers Monthly I-131 station. Lillington, at collected over a Monthly Gamma Isotopic intersection of NC 210 and period of < 31 days. quarterly Tritium the Cape Fear River. SSE sector - 17 mi from site.

b. Groundwater 39 On site deep well Grab sample (}uarterly Gamma Isotopic in the proximity of quarterly (}uarterly Tr i tium the diabase dikes. SSW sector, 0.7 mi. of site.

c. Drinking 38 Cape Fear Steam Composite sample I-131 On I-131 Electric Plant Intake over two-week period each compo-Structurt, (Control Station)~. WSW sector, if I-131 analysis is site the whep performed, monthly 6.1 mi. from site. composite otherwise dose'alculated for the consumption of the water is greater than 1 mrem per yr.

Monthly Gross Beta Monthly Gamma Isotopic quarterly Tritium 40 US Geological Survey gauging See Sample Point 38 See Sample See Sample station. Lillington, at Point 38 Point 38 intersection of NC 210 and the Cape Fear River. SSE sector, - 17 mi from site.

4-11

TABLE 4.1 (continued)

RADIOLOGICAL ENVIRONMENTAL NNITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description Sampling and Analysis and/or Sam le ID No. Distance, and Direction Collection Fre uenc ~Fee nancy Analysi s 51 SHNPP Water Treatment See Sample Point 38 See Sample See Sample Building, on site. Point 38 Point 38

d. Sediment 26 Harris Lake Spillway. Surface sediment sample Semiannually Gamma Isotopic" from S. sector, 4.6 mi. from semiannually Shoreline site.

41 Shoreline of mixing zone Surface sediment sample Semiannually Gamma Isotopic" of cooling tower blowdown Semiannually line. S. sector, 3.8 mi.

from site.

e. Bottom 52 Harri s Lake in the vi cini ty Bottom sediment sample Semiannually Gamma Isotopic Sediment of the mixing zone of the Semiannually cooling tower S. sector, 3.8 mi. from site.

4. Ingestion 42 Maple Knoll on SR 8 1403. Grab samples semi- Each sample I-131 &

a. Milk SSE sector, 7.5 mi. from monthly when animals Gamma Isotopic site. are on pasture, monthly 9 other times 19 Olive's Dairy on SR 0 1178. Grab samples semi- Each sample I-131 8 NNE sector, 5.0 mi. from monthly when animals Gamma Isotopic site. are on pasture, monthly 9 other times.

43 Goodwin's Farm on'SR 8 1134. Grab samples semi- Each sample I-131 5 N. sector, 2.5 mi. from monthly when animals Gamma Isotopic" site ~ are on pasture, monthly 9 other times 4-12

TABLE 4.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description Sampling and Analysis

~d/ S I IDN Dtt 'dili Collection Fre uency ~Fre nency Analysis 5 Pittsbor~ (Control Grab samples semi- Each sample I-131 &

Station) > 12 mi. WNW monthly when animals Gamma Isotopic" sector of site are on pasture, monthly 9 other times.

b. Fish 44 Site varies within One sample of each Semiannually Gamma Isotopic the Harris impoundment. of the following: on edible

1. Free swimmers portion

2. Bottom feeders for each semianually Site varies above One sample of each Semiannually Gamma Isotopic" Buckhorn Dam on of the following: on edible Cape Fear River 1. Free swimmers por tion (Unaffected by si)e) 2. Bottom feeders for each (Control Station) semianually

c. Food 46 SR 8 1182. (nursing home) Broad leaf vegetation At time Gamma Isotopic Products NE sector, 2.3 mi. from at time of each of each site. harvest harvest 43 Goodwin's Farm on SR 0 1134. Broad leaf vegetation At time Gamma Isotopic N. sector, 2.3 mi from at time of each of each site. harvest harvest Pi ttsbor~. (Control Broad leaf vegetation At time Gamma Isotopic Station) . WNW sector, at time of each of each

> 12 mi. from site. harvest harvest 4-13

NOTES TO TABLE 4.1 SHNPP Radiolo ical Environmental Monitoring Pro ram

1. 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.

2. Particulate samples will be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more following filter change to allow for radon and thorium daughter decay. If gross beta activity is greater than ten times the yearly mean of the control sample station activity, a gamma isotopic analysis will be performed on the individual samples.

3. Control sample stations (or background stations) are located in areas that are unaffected by plant operations. All other sample stations 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.

5. Composite samples will be collected with equipment (or equivalent) 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).

6. The dose will be calculated for the maximum organ and age group, using the methodology contained in Regulatory Guide 1.109, Rev. 1 and the actual parameters par ticular to the site.

4-14

DIXIE PIPE LINE SHEARON HARRIS NUCLEAR POWER PLANT yI' CAROLINAPOWER dc LIGHT COMPANY gO EXCLUSION BOUNDARY gS XCLUSION BOUNDARY SHNPP EXCLUSION BOUNDARY FIGURE 4.1-1 gS O~

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FIGURE 4.1-5 LEGEND STAT lo N STATION NUMBER SYMBOL NUMBER SYMBOL AP,AC, TL 0 ~ 26 AP, AC, SW, SO, TL 0 AP, AC, TL O 27 TL 0 AP. AC, TL O TL AP, AC, TL TL AP, AC, MK, FC, TL 8 30 TL TL 31 TL 0 TL 0>> 32 TL TL ~ . 33 TL 0 9 TL TL 0 10 TL 35 TL 0 TL 36 TL 0 12 TL 37 TL 13 TL SW, DW 0 14 TL 0 39 GW 0 15 TL SW, OW 0 16 TL 41 SD 0

17 TL 42 16 TL 0 MK, FC 19 MK, TL 0 FH 0 ~ 20 TL 45 FH 21 TL 0 FC TL TL 23 TL 0 49 TL 24 TL TL 0 ~ 25 TL 0 51 OW 0 52 SO FIGURE 4.1-2 53 TL F I GUR E 4.1-3 FIGURE 4.1P AC Air Cartridge AP Air Particulate SD Sediment FC Food Crop FH Fish GW Groundwater MK Milk SW Surface Water

' OW TL Drinking Water TLD 4-19

so INTERLASORATORY COMPARISON STUD I ES 5.1 OBJ ECTI VE The objective of this program is to evaluate the total laboratory analysis process by comparing results with results obtained by a separate laboratory or laboratories for an equivalent sample.

5.2 PROGRAM 5.2.1 Environmental Sam le Anal ses Com arison Pro ram Environmental samples from the SHNPP environs are to be analyzed by the Harri s Energy & Environmental Center or by a qual i fied contracting laboratory. These laboratories will participate at least annually in a nationally recognized interl aboratory comparison study. The results of the laboratories'erformances in the study will be provided to SHNPP Environmental & Radiation Control (E8RC).

The results will be included in the Annual Radiological Environmental Operating Repor t (see SHNPP Technical Specification 4.12.3) . The results will also be provided to the NRC upon request.

5.2.2 Effluent Release Anal ses Pro ram 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. The results of these studies will be provided to the NRC upon request.

5.2 .3 Abnormal Results If the CP&L laboratory or vendor laboratory results lie at greater than three 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.

TOTAL DOSE (40CFR190 CONFORMANCE) 6.1 COMPLIANCE WITH 40CFR190 Compliance with 40CFR190 as prescribed by Technical Specification 3.11 is to be demonstrated only when one or more of Technical Specifications 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, and 3.11.2.3.b is exceeded by a factor of 2. Once this occurs the Company has 30 days to submit this report pursuant to Technical Specification 6.9.2.

6.2 CALCULATIONS EVALUATING CONFORMANCE WITH 40CFR190 To perform the calculations to evaluate conformance with 40CFR190, an effort is made to develop doses that are realistic by removing assumptions that lead to overestimates o'f dose to a MEMBER OF THE PUBLIC (i.e., calculations for compliance with 10CFR50, App. I). To accomplish this the following calculational rules are used:

(1) Doses to a MEMBER OF THE PUBLIC via the liquid release pathway are considered to be <1 mrem/yr. (Reference, NUREG 0543).

(2) Doses to a MEMBER OF THE PUBLIC due to a milk pathway will be evaluated only as can be shown to exist. Otherwise, doses via this pathway will be estimated as <1 mrem/yr.

(3) Environmental sampling data which demonstrate that no pathway exists may be used to delete a pathway to man from a calculation.

(4) To sum numbers represented as "less than" (<), use the value of the largest number in the group.

(i.e., <5 + <1 + <1 + <3 = 5) 6-1

(5) When doses via direct radiation are added to doses via inhalation pathway, they will be calculated for the same distance in the same sector.

(6) The calculational locations for a MEMBER OF THE PUBLIC will only be at residences or places of employment.

NOTE: Additional assumptions may be used to provide situation-specific parameters, provided they are documented along with their concomitant bases.

6.3 CALCULATIONS OF TOTAL BODY DOSE Estimates will be made for each of the following exposure pathways to the same location by age class. Only those age classes known to exist at a location are considered.

6.3.l Direct Radiation The component of dose to a MEMBER OF THE PUBLIC due to direct radiation will be determined by:

(I) Determining the dir ect radia.ion dose at the plant boundary in each sector, DB 8-(2) Extrapolate that dose to the calculational location as follows:

DL t

=

DB (4.49 E+6)

DL 8 = dose at calculational location in sector e.

4.49E+6 = square of mean distance to the site boundary (- 2120 m).

XL p = Di stance to cal cul ational 1 ocations in sector 0 in meters.

6-2

6.3.2

~ ~ Inhalation Dose The inhalation dose will be determined at the calculational locations for each age class at risk according to the methods outlined in Section 3.3 of this manual.

6.3.3 Ingestion Pathway The dose via the ingestion pathway will be calculated at the consumer locations for the consumers at risk. If no milk pathway exists in a sector, the dose via this pathway will be treated as <I mrem/yr.

6.3.4 Other Uranium Fuel Cycle Sources The dose from other fuel cycle sources will be treated as 76-82 STAB~A LDWNDSPD LOWNDDEG AVERAGE CALM .75-3.5 3.5-7.5 7.5-12.5 12.5-18.5 18.5-25 )4 25 TOTAL LOWNDSPD O. 1/ O.OO 7/ 0.01 225/ 0.39 172/ 0.30 7/ 0.01 411.1/ 0.71 7.43898 NNE 0.0/ 0.00 1/ 0.00 156/ 0.27 142/ 0.24 299. 0/ 0. 51 7. 50180

0. 1/ 0.00 5/ 0.01 124/ 0.21 92/ 0.16 2/ 0.00 223. 1/ 0.38 7. 15193 ENE O.O/ O.OO 3/ 0.01 97/ 0. 17 32/ 0.06 132.0/ 0.23 6.45781

0. 1/ 0.00 5/ 0.01 Sn/ O.O9 12/ 0.02 71. 1/ 0. 12 5.97841 ESE O.1/ O.OO 6/ 0.01 45/ 0.08 10/ 0.02 1/ 0.00 62. 1/ 0. 11 5.85942 SE O.1/ O.OO 10/ 0.02 34/ 0.06 8/ 0.01 52. 1/ 0.09 5.35978 SSE O.O/ O.OO 4/ 0.01 62/ 0. 11 8/ 0.01 1/ O.OO 75.0/ 0. 13 5.66358

0. 1/ 0.00 6/ o.o1 92/ 0.16 34/ 0.06 4/ 0.01 136. 1/ 0.23 6.69527 SSW O.1/ O.OO 8/ 0.01 151/ 0.26 159/ 0.27 7/ 0.01 1/ 0.00 326. 1/ 0.56 7.66362 SW 0. 1/ 0.00 9/ 0. 02 167/ 0. 29 238/ 0. 4 1 49/ O.OB 463. 1/ 0.80 8.61974 WSW O.1/ O.OO 10/ 0.02 167/ 0.29 207/ 0.36 56/ 0.10 4/ 0.01 444. 1/ 0.76 8.76059

0. 1/ 0.00 8/ 0.01 100/ 0. 17 75/ 0. 13 23/ O.On 4/ 0.01 210. 1/ 0.36 8. 16850 WNW 0. 1/ 0.00 e/ O.O1 82/ 0. 14 162/ 0.28 4S/ O.OB 9/ 0.02 304. 1/ 0.52 9. 56912 0.0/ 0.00 4/ 0.01 148/ 0.25 198/ 0.34 34/ 0.06 / 384.o/ o.ee 8.40938 NNW O.O/ O.OO 3/ 0.01 162/ 0.28 191/ 0.33 38/ 0.07 1/ O.OO 395.0/ 0.68 8.39392 TOTAL 1.0/ 0.00 95/ 0. 16 1866/ 3.21 1740/ 2.99 267/ 0.46 19/ 0.03 3988/ 6.86 7 95048 NUMBER OF BAD RECORDS: 84

TABLE A-13 con't)

Joint Mind Frequency Distribution By Pasquill Stability Classes At SHNPP Period of Record: 1/1/76 12/31/82 Lower Monitoring Level SITE~SHNP PERIOD 76-82 STAB*B LOWttDSPD LDWNDDEG AVERAGE CALM .75-3.5 3.5-7.5 7.5-12.5 12. 5-18. 5 18.5-25 >s 25 TOTAL LOWNDSPD 7/ 0.01 165/ 0.28 74/ 0.13 6/ O.O1 252.0/ 0.43 6.91414 NNE 6/ 0.01 122/ 0.21 52/ 0.09 180.0/ 0.31 6.62402 NE 8/ o.ot to4/ o. $ 8 34/ 0.06 1/ 0.00 $ 47.0/ 0.25 6. 16130 ENE 8/ 0.01 102/ 0. 18 13/ 0.02 123.0/ 0.21 5.85951 7/ O.O1 72/ 0. 12 13/ 0.02 92.0/ 0.16 5.63753 ESE 9/ 0.02 65/ 0. 11 4/ o.o$ 78.0/ 0. 13 5.24909 SE 7/ O.O$ 30/ 0.05 13/ 0.02 50.0/ 0.09 5.87852 SSE 6/ 0.01 65/ 0. 11 10/ 0.02 1/ O.OO 82.0/ 0 14 5.88498

$ 0/ 0.02 $ 01/ 0. 17 37/ O.OG 4/ 0.01 152.0/ 0.26 6.55821 SSW 7/ 0.01 132/ 0.23 59/ 0. 10 4/ 0.01 202.0/ 0.35 6. 71605 SW $ 3/ 0.02 $ 74/ 0.30 1$ 0/ 0.$ 9 22/ 0.04 2/ 0.00 321.0/ 0.55 7.5668G WSW 12/ 0.02 139/ 0.24 120/ 0.21 19/ 0.03 2/ O.OO 1/ 0.00 293.0/ 0.50 7.83773 12/ 0.02 51/ 0.09 51/ O.O9 22/ 0.04 1/ 0.00 137.0/ 0.24 8. 34 160 WNW 7/ 0.01 72/ 0. 12 94/ 0.16 37/ 0.06 3/ 0.0$ 2$ 3.0/ 0.37 9. $ 19GB t4W 12/ 0.02 $ 06/ 0.18 122/ 0.21 20/ 0.03 1/ O.OO 261.0/ 0.45 8.0402 1 NNW 8/ 0.01 1 16/ 0. 20 105/ 0. 18 16/ 0.03 1/ O.OO 246.0/ 0.42 7.73903 TOTAL 139/ 0. 2 1 16 '$6/ 2. 78 91 1/ 1. 57 152/ 0 26 10/ 0.02 1/ 0.00 2829/ 4.8G 7.22241 NUMBER OF BAD RECORDS: 87

TABLE A-13 con')

Joint Wind Prequency Distribution By Pasquill Stability Classes At SHNPP

.Period of Record: 1/1/76 12/31/82 Lower Honitoring Level SITE ~ SHNP PERIDD876-82 STAB~C LDWNDSPD LOWNDDEG AVERAGE CALM .75-3.5 3.5-7.5 7. 5-12. 5 12. 5-18. 5 18.5"25 >> 25 TOTAL LOWNDSPD 17/ 0.03 208/ 0.36 98/ 0. 17 5/ O.OI 328.0/ 0.56 6.57922 NNE 11/ 0.02 146/ 0.25 47/ 0.08 204.0/ 0.35 6. 17697 NE 13/ 0.02 126/ 0.22 21/ 0.04 160.0/ 0.28 5.80545 ENE 14/ 0.02 128/ 0.22 25/ 0.04 167.0/ 0.29 5. 58311 13/ 0.02 87/ 0. 15 3/ O.OI 103.0/ 0. 18 5.08083 ESE 17/ 0.03 63/ 0. 11 5/ O.OI 85.0/ 0. 15 4.9054 I SE 9/ 0.02 66/ 0. 11 6/ 0.01 81.0/ 0. 14 5. 17538 SSE 18/ 0.03 92/ 0. 16 15/ 0.03 125.0/ 0.21 5. 46216 22/ 0.04 122/ 0.2 I 23/ 0.04 I/ 0.00 168.0/ 0.29 5.50245 SSW 27/ 0.05 180/ 0.3 I 76/ 0. 13 7/ 0.01 290.0/ 0.50 6. 28916 SW 27/ 0.05 204/ 0.35 102/ 0. 18 14/ 0.02 2/ 0.00 349.0/ 0.60 6.89606 WSW 18/ 0.03 184/ 0.32 111/ 0. 19 18/ 0.03 3/ 0.01 334.0/ 0.57 7.42295 18/ 0.03 109/ 0. 19 67/ 0. 12 11/ 0.02 2/ 0.00 207.0/ 0.36 7. 16838 WNW 11/ 0.02 IO4/ O. 18 64/ 0. 11 32/ 0.06 2/ 0.00 213.0/ 0.37 8.23387 NW 15/ 0. 03 134/ 0. 23 I 19/ 0. 20 11/ 0.02 282.0/ 0.48 7.47358 NNW 12/ 0.02 158/ 0.27 101/ 0. 17 13/ 0.02 284.0/ 0.49 7.26539 TOTAL 262/ 0.45 2111/ 3.63 883/ 1.52 115/ 0.20 9/ 0.02 3380/ 5.81 6.61670 NUMBER OF BAD RECORDS: 100

TABLE A-13 on't)

Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP Period of Record: 1/1/76 12/31/82 Lower Monitoring Level 5 ITE~SHNP PERIOD%76-82 STABRD LOWNOSr O LOWNOOEG AVERAGE CALM 75-3.5 3.5-7.5 7. 5- 12. 5 12. 5- 18. 5 18.5-25 > ~ 25 TOTAL LOWNOSIO 1.5/ 0.00 221/ 0.38 1019/ 1.75 367/ 0.63 36/ O.OG 1645/ 2.83 6.03657 NNE 1.9/ 0.00 273/ 0.47 1138/ 1.96 273/ 0.47 12/ 0.02 1698/ 2.92 5.56478 NE 1.6/ 0.00 230/ 0.40 743/ 1.28 154/ 0.26 2/ 0.00 1131/ 1.94 5.33269 ENE 1.4/ 0.00 202/ 0.35 595/ 1.02 71/ 0. 12 1/ O.OO 870.4/ 1.50 4.94590 1.3/ 0.00 185/ 0.32 410/ 0.70 29/ 0.05 3/ 0.01 628.3/ 1.08 4.52470 ESE 1.0/ 0.00 153/ 0.26 310/ 0.53 25/ 0.04 2/ 0.00 491.0/ 0.84 4. 47621 SE 1.0/ 0.00 147/ 0.25 358/ 0.62 58/ O.1O 2/ 0.00 566.0/ 0.97 4.84089 SSE 1. 1/ 0.00 167/ 0.29 478/ 0.82 134/ 0.23 17/ 0.03 797. 1/ 1.37 5.56007 1.3/ 0.00 186/ 0.32 577/ 0.99 154/ 0.26 31/ 0.05 1/ O.OO 950.3/ 1.63 5.76856

~ SSW 1.9/ 0.00 273/ 0.47 767/ 1.32 269/ 0.46 42/ 0.07 1/ O.OO 1354/ 2.33 5.87528 Sw 1.8/ 0.00 259/ 0.45 776/ 1.33 381/ 0.6G 56/ 0.10 8/ 0.01 1482/ 2.55 6.34633 WSW 1.2/ 0.00 180/ 0.31 681/ 1. 17 265/ 0.46 48/ 0.08 17/ 0.03 1192/ 2.05 6.49G99 1.0/ 0.00 149/ 0.26 373/ 0.6 1 165/ 0.28 29/ 0.05 717.0/ 1.23 6.02672 WNW 0.9/ 0.00 135/ 0.23 352/ 0.61 236/ 0.41 72/ 0. 12 4/ O.O1 799.9/ 1.38 6.99022 NW 0.9/ 0.00 132/ 0.23 477/ 0.82 3 18/ 0.55 36/ 0.06 963.9/ 1.66 6.68711 NNW 1.2/ 0.00 180/ 0.31 617/ 1.06 380/ 0.65 48/ O.OB 1226/ 2. 11 6.54420

'10TAL 21.0/ 0.04 3072/ 5.28 9671/16.63 3279/ 5.64 437/ 0.75 31/ 0.05 165 1 1/28 . 39 5.86828 NUMBER OF BAO RECORDS: 585

TABLE A-13 (con't)

Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP Period of Record: 1/1/76 12/31/82 Lower Monitoring Level S1 TE~SHNP PERIODi76-82 STABLE LOWNDSPD LOWNDDEG AVERAGE CALM .75"3.5 3.5-7.5 7. 5-12. 5 12. 5- 18. 5 18.5-25 )~ 25 TOTAL LOWNDSPD 2.7/ 0.00 376/ 0.65 616/ 1.06 87/ 0.15 7/ 0.01 1089/ 1.87 4.57494 NNE 3.6/ 0.01 500/ 0.86 533/ 0.92 19/ 0.03 3/ O.OI 1059/ 1.82 3.77374 NE 3.0/ 0.01 428/ 0.74 335/ 0.58 29/ 0.05 795.0/ 1.37 3. 7 1377 ENE 2.6/ 0.00 368/ 0.63 214/ 0.37 24/ 0.04 I/ 0.00 609.6/ 1.05 3. 56109 2.3/ 0.00 322/ 0.55 198/ 0.34 15/ 0.03 2/ 0.00 539.3/ 0.93 3. 44014 ESE 2. I/ 0.00 291/ 0.50 155/ 0.27 16/ 0.03 464. I/ 0.80 3.36560 2.4/ 0.00 339/ 0.58 229/ 0.39 18/ 0.03 4/ O.OI 592.4/ 1.02 3.53311 SSE 3.7/ 0.01 518/ 0.89 368/ 0.63 55/ O.O9 5/ 0.01 949.7/ 1.63 3.82129

'.5/ 0.01 779/ 1.34 647/ 1. 11 98/ 0. 17 12/ 0.02 1542/ 2.65 3. 97819 SSW 5.2/ 0.01 733/ 1.26 899/ 1.55 113/ 0. 19 10/ 0.02 1760/ 3.03 4.20919 SW 2.9/ 0.00 402/ O.G9 619/ 1.06 165/ 0.28 12/ 0.02 3/ O.OI 1204/ 2.07 4.90957 WSW I . 8/ 0. 00 257/ 0. 4 I 407/ O. 70 105/ 0. 18 24/ 0.04 4/ O.OI 798.8/ 1.37 5. 15121 1.5/ 0.00 206/ 0.35 302/ 0.52 50/ 0.09 10/ 0.02 569.5/ 0.98 4.65715 WNW 1.4/ 0.00 195/ 0.34 282/ 0.48 76/ 0.13 2/ 0.00 I/ O.OO 557.4/ 0.96 4.77983 1.6/ 0.00 222/ 0.38 407/ 0.70 57/ 0. 10 3/ 0.01 690.6/ 1. 19 4 . 56185 NNW 1.8/ 0.00 259/ 0.45 385/ 0.66 95/ 0. 16 8/ 0.01 748.8/ 1.29 4.70378 TOTAL 44.0/ 0.08 G195/ IO.G5 6596/11.34 1022/ 1.76 103/ 0. 18 8/ 0.01 13968/24.02 4. 20921 NDMBER OF BAD RECORDS: 325

TABLE A-13 con't)

Joint Wind Frequency Distribution By Pasquill Stability Classes't SHNPP Period of Record: 1/1/76 12/31/82 Lower Monitoring Level 51TE~SHNP PER10DR76-82 STAFF LOWNDSPD LDWNDDEG AVERAGE CALM .75-3.5 3.5-7.5 7.5-12.5 12.5-18.5 18.5-25 >~ 25 TOTAL LOWNDSPD 8.2/ 0.01 429/ 0.74 211/ 0.36 2/ 0.00 650.2/ 1. 12 3.02325 NNE 8. 9/ 0. 02 463/ 0. 80 1 13/ 0. 19 1/ 0.00 585.9/ 1.01 2.68731 NE 8.5/ 0.01 443/ 0.76 45/ O.OB 496.5/ O.85 -2.42985 ENE 7.1/ 0.01 371/ 0.64 5O/ O.O9 428. 1/ 0.74 2.40978 5.8/ 0.01 300/ 0.52 30/ 0.05 335.8/ 0.58 2. 18794 ESE 5.5/ 0.01 286/ 0.49 25/ 0.04 316.5/ 0.54 2. 15184 SE 6. 1/ 0.01 318/ 0.55 28/ 0.05 352. 1/ 0.61 2. 21 132 SSE 8.6/ 0.01 447/ 0.77 28/ 0.05 483.6/ 0.83 2. 12694 10.5/ 0.02 548/ 0.94 99/ 0. 17 657.5/ 1. 13 2. 40714 SSW 11.3/ 0.02 58G/ 1.01 138/ 0.24 1/ O.OO 736.3/ 1.27 2. 57199 SW 6.3/ 0.01 328/ 0.56 114/ 0.20 5/ O.O1 1/ O.OO 454.3/ 0.78 2.79062 WSW 4.2/ 0.01 220/ 0.38 85/ 0. 15 1/ O.OO 310.2/ 0.53 2. 823 13 3.3/ 0.01 172/ 0.30 63/ O.11 238.3/ 0.41 2.76382 WNW 3.0/ 0.01 157/ 0.27 69/ 0. 12 229.0/ 0.39 2. 77612 3.2/ 0.01 1GB/ 0.29 65/ 0. 11 236.2/ 0.41 2.71450 NNW 5.4/ 0.01 281/ 0.48 109/ 0. 19 1/ O.OO 396.4/ 0.68 2.7930G TOTAL 106.0/ 0. 18 5517/ 9. 49 1272/ 2. 19 11/ 0.02 1/ 0.00 6907/11. 88 2.55740 NUMBER OF BAD RECORDS: 193

TABLE A-13 (con't)

Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP Period of Record: 1/1/76 12/31/82 Lower Monitoring Level SI TERSHNP PERIOD%76-82 STABRG LDWNDSPD LDWNDDEG AVFRAGE CALM .75"3.5 3.5-7.5 7.5-12.5 12. 5-18. 5 18.5-25 25 TOTAL LOWNDSPD 184. 9/ 0. 32 1010/ I . 74 86/ 0. 15 1281/ 2.20 1. 72431 169.7/ 0.29 927/ 1.59 20/ 0.03 1117/ 1.92 I . 46930 NE 171.4/ 0.29 936/ 1.61 15/ 0.03 1122/ 1.93 1.49948 ENE 151.8/ 0.26 829/ 1.43 16/ 0.03 996.8/ 1.71 1.47772 130. 9/ 0. 23 715/ 1. 23 6/ O.OI 851. 9/ I . 46 1.34463 ESE 99. 8/ 0. 17 545/ 0. 94 11/ 0.02 655.8/ 1.13 1.32153 SE 79.3/ 0.14 433/ 0.74 8/ 0.01 520.3/ 0.89 1. 35172 SSE 72. 3/ 0. 12 395/ 0. 68 5/ 0.01 472.3/ 0.81 1.35393 92.8/ 0. 16 507/ 0.87 5/ 0.01 604.8/ 1.04 1.35748 SSW 87.7/ 0.15 479/ 0.82 5/ 0.01 571.7/ 0.98 1.45870 SW 70.5/ 0. 12 385/ 0.66 19/ 0.03- I/ 0.00 475.5/ 0.82 1.63642 WSW 54.2/ 0.09 296/ 0.51 17/ 0.03 367.2/ 0.63 1.55063 46.9/ 0.08 256/ 0.44 10/ 0.02 312.9/ 0.54 1. 50179 WNW 44.3/ 0.08 242/ 0.42 9/ 0.02 295.3/ 0.51 1. 52162 NW 47.8/ 0.08 26 1/ 0.45 11/ 0.02 I/ 0.00 320.8/ 0.55 I . 56182 NNW 91.6/ O. 16 500/ 0.86 23/ 0.04 614.6/ I.O6 1.55537 TOTAL 1596/ 2. 74 8716/14. 99 266/ 0. 46 2/ 0.00 10580/ 18 . 19 1.48762 NUMBER OF BAD RECORDS: 590

TABLE A-1 con't)

Joint Mind Frequency Distribution By Pasquill Stability Classes At SHNPP Period of Record: 1/1/76 12/31/82 Lower Monitoring Level SITE~SHNP PERIOD>76-82

SUMMARY

OVER ALL STAB LDWNDSPD LDWNDDEG AVERAGE CALM .75-3.5 3.5-7.5 7.5-12.5 12.5-18.5 18.5-25 > ~ 25 TOTAL LDWNDSPD

~ 152.3/ 0.26 2067/ 3.55 2530/ 4.35 800/ 1.38 61/ 0. 10 5610/ 9.65 4.65481 NNE 160.7/ 0.28 2181/ 3.75 2228/ 3.83 534/ 0.92 15/ 0.03 5119/ 8.80 4. 19043 NE 152.0/ 0.26 2063/ 3.55 1492/ 2.57 330/ 0.57 5/ O.OI 4042/ 6.95 3.80728 ENE 132.3/ 0.23 1795/ 3.09 1202/ 2.07 165/ 0.28 2/ 0.00 3296/ 5.67 3.50671 114.0/ 0.20 1547/ 2.66 857/ 1.47 72/ 0. 12 5/ 0.01 2595/ 4.46 3. 12460 ESE 96.3/ 0. 17 1307/ 2.25 674/ 1. 16 60/ 0. 10 3/ 0.01 2140/ 3.68 3.06463 SE 93. I/ 0. 16 1263/ 2. 17 753/ 1.29 103/ 0. 18 6/ 0.01 2218/ 3.81 3. 32610 SSE 114.6/ 0.20 151.6/ 0.26 1555/ 2.67 2058/ 3.54 1098/ 1.89 1643/ 2.82 222/ 0.38 346/ 0.59 '2/ 24/ 0.04 0.09 I/ O.OO 3014/ 5. 18 4252/ 7.31 3.79054 4.00940 SSW 155.7/ 0.27 2113/ 3.63 2272/ 3.91 677/ 1. 16 70/ 0. 12 2/ 0.00 5290/ 9.09 4. 53197 SW 104.8/ 0. 18 1423/ 2.45 2073/ 3.56 1002/ 1.72 154/ 0.26 15/ 0.03 4772/ 8.20 5.50878 WSW 73.2/ 0. 13 993/ 1.71 1680/ 2.89 809/ 1.39 165/ 0.28 30/ 0.05 1/ 0.00 3751/ 6.45 5.88759 60.5/ 0. 10 821/ 1.41 1008/ 1.73 408/ 0.70 95/ 0. 16 7/ 0.01 2400/ 4. 13 5. 21635 WNW 55.5/ 0. 10 753/ 1.29 970/ 1.67 632/ 1.09 188/ 0.32 19/ 0.03 2618/ 4.50 6. 11697 60.0/ 0. 10 811/ 1.40 1348/ 2.32 815/ 1.40 107/ 0. 18 I/ O.OO 3145/ 5. 41 5.79527 NNW 91.G/ 0. 16 1243/ 2. 11 1570/ 2.70 873/ 1.50 123/ 0.21 2/ 0.00 3903/ 6.7 I 5. 37719 TOTAL 1768/ 3.04 23996/4 I . 26 23398/40. 23 7848/13. 49 1075/ 1. 85 77/ 0. 13 I/ 0.00 58163/ 100 4.55808 NUMBER OF BAD RECORDS: 3205

TABLE A-14 Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP Period of Record: 1/1/76 12/31/82 Upper Monitoring Level S ITE~SPINP PERIOD~76-82 STAB%A UPWNDSPD UPWNDDEG AVERAGE CALM .75-3.5 3.5-7.5 7.5-12.5 12. 5-18. 5 18.5-25 >~ 25 TOTAL UPWNDSPD 0.1/ 0.00 3/ 0.01 97/ 0.16 193/ 0.33 79/ 0.13 2/ 0.00 3V4.1/ O.64 9. 79160 NNE 0.2/ 0.00 4/ 0.01 97/ 0. 16 174/ 0. 30 87/ 0. 15 I/ 0.00 363.2/ 0.62 9.90464 O. I/ O.OO 3/ O.OI 48/ 0.08 123/ 0.21 35/ 0.06 4/ 0.01 2 13. I/ 0. 36 9.87411 ENE 0.2/ 0.00 5/ 0.01 4o/ o.ov 68/ 0. 12 7/ 0.01 120.2/ 0.20 8.30030 O. I/ O.OO 3/ O.OI 39/ 0.07 32/ 0.05 4/ O.OI 78. I/ 0. 13 7. 29610 ESE 0.3/ 0.00 7/ 0.01 4o/ o.ov 21/ 0.04 4/ O.OI 72.3/ 0. 12 6.59426 SE 0. I/ 0.00 3/ 0.01 22/ 0.04 10/ 0.02 4/ 0.01 I/ 0.00 40. I/ 0.07 7.29408 SSE 0.3/ 0.00 7/ 0.01 48/ 0.08 22/ 0.04 S/ O.OI 82.3/ 0. 14 7.07660 0.2/ 0.00 5/ 0.01 SS/ O.O9 62/ 0. 11 28/ 0.05 4/ 0.01 I/ 0.00 155.2/ 0.26 9. 31049 SSW 0. I/ 0.00 3/ 0.01 73/ 0. 12 153/ 0.26 118/ 0.20 15/ 0.03 I/ 0.00 363. I/ 0.62 11.21632 SW 0.2/ 0.00 6/ 0.01 88/ O. 15 198/ 0. 34 154/ 0. 26 44/ 0.07 9/ 0.02 499.2/ 0.85 11.96250 WSW 0.2/ 0.00 6/ 0.01 61/ 0. 10 176/ 0.30 87/ 0.15 38/ 0.06 12/ 0.02 380.2/ 0.65 11.97532

0. 2/ O. 00 4/ 0. 01 S4/ O.O9 74/ 0.13 42/ 0.07 11/ 0.02 5/ 0.01 190.2/ 0.32 10.82260 WNW 0.3/ 0.00 7/ 0.01 4S/ O.O8 126/ 0.21 115/ 0.20 28/ 0.05 12/ 0.02 333.3/ 0.57 12.78223 NW 0.2/ 0.00 5/ 0.01 70/ 0. 12 148/ 0.25 132/ 0.22 17/ 0.03 I/ 0.00 373.2/ 0.63 11.44957 NNW 0. I/ 0.00 2/ 0.00 84/ 0. 14 148/ 0. 25 9S/ O.16 13/ 0.02 342. I/ 0. 58 10. 7 1436 TOTAL 3.0/ 0.01 73/ 0. 12 961/ 1.63 1728/ 2.94 996/ 1.69 178/ 0.30 41/ 0.07 3980/ 6.77 10.70202 NUMBER OF BAD RECORDS: 92

TABLE A-1 on't)

Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP Period of Record: 1/1/76 12/31/82 Upper Monitoring Level SITE~SHNP PERIOD%76-82 STAB-B UPWNDSPD UPWNDDEG AVERAGE CALM .75-3.5 3.5-7.5 7.5-12.5 12.5-18.5 18.5-25 > ~ 25 TOTAL UPWNDSPD 10/ 0.02 82/ 0.14 108/ 0.18 aa/ O.O6 4/ 0.01 242.0/ 0.41 9.03918 NNE 4/ O.OI 61/ 0. 10 101/ 0. 17 38/ 0.06 204.0/ 0.35 9.23074 6/ 0.01 62/ 0. 11 87/ 0. 15 21/ 0.04 I/ O.OO 177.0/ 0.30 8.56576 ENE 5/ 0.01 57/ 0; 10 54/ o.oe 4/ 0.01 120.0/ 0.20 7.63224 5/ 0.01 51/ 0.09 39/ 0.07 I/ O.OO 96.o/ o. 16 7.09442 ESE 9/ 0.02 42/ 0.07 18/ 0.03 2/ 0.00 71.0/ 0. 12 6.44798 SE 5/ O.OI 28/ 0.05 18/ 0.03 I/ O.OO 52.0/ 0.09 6.82994 SSE 8/ 0.01 42/ 0.07 34/ 0.06 3/ O.OI I/ O.OO 88.0/ 0.15 7.32428 2/ 0.00 53/ o.oe 72/ 0. 12 25/ 0.04 3/ 0.01 155.0/ 0.26 9. 32091 SSW 6/ O.OI 74/ 0. 13 102/ 0. 17 44/ 0.07 11/ 0,02 2/ 0.00 239.0/ 0.4 I 10.01 121 SW 8/ 0.01 91/ 0. 15 128/ 0. 22 62/ 0. 11 18/ 0.03 2/ 0.00 309.0/ 0.53 10. 19455 WSW 9/ 0.02 60/ 0.10 138/ 0.23 56/ 0. 10 14/ 0.02 6/ 0.01 283.0/ 0.48 10.65406 2/ 0.00 40/ 0.07 44/ 0.07 32/ 0.05 20/ 0.03 2/ 0.00 140.0/ 0.24 11.57018 WNW 6/ 0.01 51/ o.oe 83/ 0. 14 63/ 0. 11 26/ 0.04 5/ 0.01 234.0/ 0.40 11.92320 NW 7/ 0. 01 51/ 0.09 109/ 0. 19 67/ 0. 11 10/ 0.02 I/ 0.00 245.0/ 0.42 10.67025 NNW 7/ 0.01 62/ 0. 11 91/ 0. 15 ~ 49/ 0.08 12/ 0.02 221.0/ 0.38 Io. 17149 TOTAL 99/ 0. 17 907/ 1.54 1226/ 2.08 506/ 0.86 120/ 0.20 18/ 0.03 2876/ 4.89 9.70669 NUMBER OF BAD RECORDS: 40

TABLE A-1 on't)

Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP Period of Record: 1/1/76 12/31/82 Upper Monitoring Level SITE$ SHNP PERIOD%76-82 STAB$ C UPWNDSPD UPWNODEG AVERAGE CALM .75-3.5 3.5-7.5 7. 5-12. 5 12. 5-18. 5 18 '-25 >$ 25 TOTAL UPWNOSPD

/ i 15/ 0.03 121/ 0.21 116/ 0.20 49/ O.O8 10/ 0.02 31 I . 0/ 0. 53 8. 86140 NNE 6/ 0.01 97/ 0. 16 110/ 0.19 34/ 0.06 2/ 0.00 249.0/ 0.42 8.63621 NE 11/ 0.02 79/ 0. 13 88/ 0. 15 18/ 0.03 1/ 0.00 197.0/ 0.33 8.06577 ENE I/ 0.01 82/ 0. 14 64/ 0. 11 6/ 0.01 I/ 0.00 160.0/ 0.27 7.65579 6/ 0.01 66/ 0. 11 38/ 0.06 110.0/ 0. 19 6.62648 ESE 12/ 0. 02 S4/ O.O9 19/ 0.03 2/ 0.00 87.0/ 0. 15 G. 10751 SE 5/ 0.01 51/ 0.09 21/ 0.04 77.0/ 0. 13 6.23600 SSE 10/ 0.02 S8/ O. IO 44/ 0.07 5/ 0.01 I/ O.OO 118.0/ 0.20 7. 17349 13/ 0.02 91/ 0. 15 76/ 0. 13 15/ 0.03 3/ 0.01 198.0/ 0.34 7.76472 SSW 16/ 0.03 se/ o. 16 99/ 0. 17 62/ 0. f1 12/ 0.02 2/ 0.00 287.0/ 0.49 9.GG680 SW 19/ 0.03 112/ 0. 19 126/ 0.21 67/ 0. 11 19/ 0.03 4/ 0.01 347.0/ 0.59 9.83956 WSW 19/ 0. 03 109/ 0. 19 136/ 0. 23 51/ 0.09 14/ 0.02 3/ 0.01 332.0/ 0.5G 9.34572 7/ 0.01 70/ 0. 12 80/ 0. 14 32/ 0.05 14/ 0.02 3/ 0.01 206.0/ 0.35 9.93621 WNW 12/ 0.02 58/ 0. 10 76/ 0. 13 44/ 0.07 22/ 0.04 4/ 0.01 216.0/ 0.37 10.92737 NW 13/ 0.02 82/ 0. 14 118/ 0.20 69/ 0. 12 6/ o.oI 2/ 0.00 290.0/ 0.49 9.85923 NNW 8/ 0.01 86/ 0. 15 99/ 0. 17 52/ 0.09 10/ 0.02 255.0/ 0.43 9.56059 TOTAL 179/ 0.30 1312/ 2.23 1310/ 2.23 506/ 0.86 114/ 0. 19 19/ 0.03 3440/ 5.85 8.96520 NUM8ER OF BAD RECORDS: 40

TABLF. A-1 on't)

Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP Period of Record: 1/1/76 12/31/82 Upper Monitoring Level S I TE ~ SIINP PER IOD076-82 STAB=0 UPWNDSPD UPWNDDEG AVERAGE CALM 75-3.5 3.5-7.5 7.5" 12.5 12.5-18.5 18.5-25 > ~ 25 TOTAL UPWNDSPD o.4/ o.oo 83/ 0. 14 446/ 0.76 634/ 1.08 249/ 0.42 we/ o.os 5/ 0.01 1466/ 2.49 9.40292 NNE o.4/ o.oo 84/ 0. 14 458/ 0.78 845/ 1.44 335/ 0.57 43/ 0.07 3/ 0.01 1768/ 3.01 9.64191 NE o.4/ o.oo 86/ 0. 15 367/ 0.62 540/ 0.92 187/ 0.32 5/ O.OI 1185/ 2.01 8.78455 ENE o.4/ o.oo 84/ 0. 14 339/ 0.58 422/ 0.72 79/ 0. 13 5/ 0.01 929.4/ 1.58 7.96378 0.4/ 0.00 83/ 0. 14 342/ 0.58 252/ 0.43 31/ 0.05 2/ 0.00 I/ 0.00 711.4/ 1.21 7.06800 ESE o.4/ o.oo 89/ 0. 15 289/ 0.49 158/ 0.27 24/ 0.04 I/ 0.00 I/ 0.00 562.4/ 0.96 6.53816 SE O.3/ O.OO 64/ 0. 11 277/ 0.47 171/ 0.29 37/ 0.06 7/ 0.01 556.3/ 0.95 7.20827 SSE 0.3/ 0.00 59/ 0. 10 301/ 0.51 246/ 0.42 142/ 0.24 27/ 0.05 9/ 0.02 784.3/ 1.33 9.07411.

o.4/ o.oo 77/ 0. 13 325/ 0.55 389/ 0.66 158/ 0.27 43/ 0.07 5/ 0.01 997.4/ 1.70 9.26032 SSW o.4/ o.oo 91/ 0. 15 384/ 0.65 440/ 0.75 286/ 0.49 96/ o.16 10/ 0.02 1307/ 2.22 10. 12253 SW o.5/ o.oo 107/ 0. 18 483/ 0.82 503/ 0.85 263/ 0.45 s5/ 0.<< 25/ 0.04 1467/ 2.49 9.82418 WSW o.4/ o.oo 86/ 0. IS 404/ 0.69 452/ 0.77 164/ 0.28 35/ 0.06 19/ 0.03 1160/ 1.97 9. 12122 o.4/ o.oo 90/ 0. 15 264/ 0.45 253/ 0.43 111/ 0. 19 35/ 0.06 2/ 0.00 755.4/ 1.28 8.65063 WNW O.3/ O.OO 64/ 0. 11 224/ 0.38 258/ 0.44 180/ 0.3'I 82/ 0.14 9/ 0.02 817.3/ 1.39 10 50333 NW 0.3/ 0.00 62/ 0. 11 262/ 0.45 361/ 0.61 263/ 0.45 30/ 0.05 3/ 0.01 981.3/ 1.67 10.04301 NNW 0.3/ 0.00 74/ 0. 13 348/ 0.59 411/ 0.70 227/ 0.39 41/ 0.07 1101/ 1.87 9.41321 TOTAL 6.0/ 0.01 1283/ 2. 18 5513/ 9.37 6335/10.77 2736/ 4.65 586/ 1.00 92/ 0. 16 16551/28. 13 9. 14077 NUMBER OF BAD RECORDS: 545

TABLE A-1 con't)

Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP Period of Record: 1/1/76 12/31/82 Upper Monitoring Level SITE%SHNP PERIOD%76-82 STAB%E UPWNOSPO UPWNDDEG AVERAGE CALM .75-3.5 3.5-7.5 7. 5-12.5 12.5-18.5 18.5-25 >% 25 TOTAL UPWNOSPO 0.9/ 0.00 34/ 0.06 162/ 0.28 517/ 0.88 188/ 0.32 16/ 0.03 2/ 0.00 919.9/ 1.56 10.08484 NNE O.B/ O.OO 31/ 0.05 179/ 0.30 562/ 0.96 144/ 0.24 5/ O.O1 921.8/ 1.57 9.66397 NE O.s/ O.OO 37/ 0.06 189/ 0.32 470/ 0.80 100/ 0. 17 796.9/ 1.35 9.02405 ENE 0.8/ 0.00 31/ 0.05 193/ 0.33 311( 0.53 39/ 0.07 5/ O.O1 579.8/ 0.99 8.42588 O.s/ O.OO 37/ 0.06 247/ 0.42 274/ 0.47 43/ 0.07 601.9/ 1.02 7.87046 ESE 0.9/ 0.00 34/ 0.06 226/ 0.38 229/ 0.39 20/ 0.03 1/ O.OO 5 10. 9/ 0. 87 7.59238 SE O.s/ O.OO 37/ 0.06 179/ 0.30 240/ 0.41 34/ 0.06 7/ 0.01 497.9/ 0.85 8.24473 SSE 0.9/ 0.00 34/ 0.06 257/ 0.44 455/ 0.77 113/ 0. 19 11/ 0.02 4/ 0.01 874.9/ 1.49 9. 12464

1. 1/ 0.00 42/ 0.07 316/ 0.54 765/ 1 ~ 30 256/ 0.44 19/ 0.03 5/ 0.01 1404/ 2.39 9.75685 SSW 1.0/ 0.00 39/ 0.07 339/ 0.58 1116/ 1.90 396/ 0.67 36/ 0.06 4/ 0.01 1931/ 3.28 10.236G3 SW 1.4/ 0.00 54/ 0.09 358/ 0.61 675/ 1. 15 264/ 0.45 29/ 0.05 10/ 0.02 1391/ 2.37 9.77155 WSW 1.3/ 0.00 52/ 0.09 269/ 0.46 421/ 0.72 153/ 0.26 30/ 0.05 6/ 0.01 932.3/ 1.58 9. 44024 1.2/ 0.00 47/ 0. 08 156/ 0. 27 282/ 0. 48 1 17/ 0. 20 10/ 0.02 613.2/ 1.04 9.26029 WNW O.s/ O.OO 34/ 0.06 136/ 0.23 283/ 0.48 136/ 0.23 8/ 0.01 597.9/ 1.02 9.69007 NW 1. 1/ 0.00 42/ 0.07 147/ 0.25 396/ 0.67 104/ 0. 18 5/ 0.01 1/ 0.00 696. 1/ 1. 18 9.34272 NNW 1.2/ 0.00 46/ 0.08 168/ 0.29 383/ 0.65 121/ 0.21 10/ 0.02 729.2/ 1.24 9.34068 TOTAL 16.0/ 0.03 631/ 1.07 3521/ 5.98 7379/12.54 2228/ 3.79 192/ 0.33 32/ 0 05

~ 13999/23.79 9. 40187 NUMBER OF BAO RECORDS: 294

TABLE A-1 on't)

Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP Period of Record: 1/1/76 12/31/82 Upper Monitoring Level SITEKSHNP PER IODi76-82 STABiF UPWNOSPO UPWNDDEG AVERAGE CALM .75-3.5 3.5-7.5 7.5-12.5 12.5-18.5 18.5-25 >I 25 TOTAL UPWNDSPD 0.3/ 0.00 23/ 0.04 97/ 0. 16 244/ 0.41 106/ 0. 18 470.3/ 0.80 9.73708 NNE 0.2/ 0.00 20/ 0.03 102/ 0. 17 275/ 0.47 6O/ O. 1O 457.2/ 0.78 9.25777 NE 0.3/ 0.00 26/ 0.04 90/ 0.15 238/ 0.40 44/ 0.07 398.3/ O.68 8.88562 ENE 0. 1/ 0.00 11/ 0.02 87/ 0. 15 197/ 0.33 38/ O.O6 333. 1/ 0.57 9. 15721 E 0.3/ 0.00 27/ 0.05 110/ 0.19 222/ 0.38 28/ 0.05 387.3/ 0.66 8.40405 ESE 0.2/ 0.00 18/ 0.03 117/ 0.20 164/ 0.28 13/ 0.02 3 12. 2/ 0. 53 7.85143 SE 0.2/ 0.00 17/ 0.03 91/ 0.15 129/ 0.22 10/ 0.02 247.2/ 0.42 7.80228 SSE 0.2/ 0.00 19/ 0.03 122/ 0.21 250/ 0.42 16/ 0.03 407.2/ 0.69 8. 47781 0.3/ 0.00 23/ 0.04 162/ 0.28 364/ 0.62 BO/ O.14 629.3/ 1.07 9.09853 SSW 0.3/ 0.00 23/ 0.04 183/ 0.31 542/ 0.92 136/ 0.23 1/ 0.00 885.3/ 1.50 9 56335 SW 0.4/ 0.00 30/ 0.05 162/ 0.28 475/ 0.81 77/ 0. 13 1/ 0.00 745.4/ 1.27 8.96657 WSW 0.2/ 0.00 18/ 0.03 152/ 0.26 263/ 0.45 56/ 0. 10 489.2/ 0.83 8.67930 0.3/ 0.00 23/ 0.04 98/ 0. 17 169/ 0.29 47/ 0.08 337.3/ 0.57 8.73815 WNW 0.2/ 0.00 13/ 0.02 . 88/ 0. 15 135/ 0.23 38/ O.O6 274.2/ 0.47 8. 82143 NW o.3/ o.oo as/ o.o4 93/ 0. 16 122/ 0.21 23/ 0.04 261.3/ 0.44 7. 93131 NNW 0.3/ 0.00 28/ 0.05 87/ 0. 15 198/ 0.34 51/ 0.09 364.3/ 0.62 8.87930 TOTAL 4.0/ 0.01 342/ 0.58 1841/ 3. 13 3987/ 6.78 823/ 1.40 2/ 0.00 . / 6999/ 1 1 . 90 8.89892 NUMBER OF BAO RECORDS: 101

TABLE A- con't)

Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP Period of Record: 1/1/76 12/31/82 Upper Monitoring Level SITE ~ SHNP PERIOD%76-82 STAGING UPWNDSPD UPWNDDEG AVERAGE CALM .75-3.5 3.5-7.5 7.5-12.5 12. 5-18. 5 18.5-25 25 TOTAL UPWNDSPD N 1.6/ 0.00 64/ 0.11 215/ 0.37 255/ 0.43 40/ 0.07 575.6/ 0.98 7.60577 NNE 1.6/ O.OO 64/ 0. II 204/ 0. 35 261/ 0. 44 38/ 0.06 568.6/ 0.97 7.63306 NE '1.7/ 0.00 68/ 0. 12 205/ 0.35 269/ 0.46 35/ 0.06 578.7/ 0.98 7. 52196 ENE I.S/ O.OO 71/ 0. 12 186/ 0.32 194/ 0.33 50/ 0.08 502.8/ 0.85 7.59674 1.4/ O.OO 55/ 0.09 158/ 0.27 222/ 0.38 33/ 0.06 4G9.4/ 0.80 7.69111 E SF. 8/ O.nn 71/ n. 12 i71/ 0.29 i90/ 0.32 12/ 0.02 445.8! 0.76 7.01274 SE 2.0/ 0.00 81/ 0. 14 197/ 0.33 205/ 0.35 14/ 0.02 499.O/ O.BS 7 0321rs SSE 1.5/ 0.00 60/ 0. 10 239/ 0.4 I 279/ 0.47 I I/ 0.02 590.5/ 1.00 7.35847 1.7/ 0.00 68/ 0. 12 278/ 0.47 342/ 0.58 41/ 0.07 730.7/ 1.24 7.75476 SSW 2.2/ 0.00 87/ 0. 15 360/ 0.61 623/ 1.06 63/ 0. 11 1135/ 1.93 8. 11301 SW 2.3/ 0.00 90/ 0. 15 397/ 0.67 582/ 0.99 32/ 0.05 1103/ I . 88 7. 75107 WSW 2. I/ 0.00 94/ 0. 16 490/ 0.83 594/ 1.01 72/ 0. 12 1252/ 2. 13 7.80968 2.3/ O.OO 91/ o. is 323/ n.ss 303/ 0.52 26/ 0.04 745.3/ 1.27 6. 99721 WNW 2.4/ 0.00 97/ 0. 16 263/ 0.45 202/ 0.34 22/ 0.04 S86.4/ I.OO 6.705 IS NW 2.2/ 0.00 88/ O.iS 324/ 0.55 160/ 0.27 . 6/ 0.01 580.2/ 0.99 6.16247 NNW 2. I/ 0.00 84/ 0. 11 259/ 0.44 247/ 0.42 31/ 0.05 623. I/ 1.06 7 15439 TOTAL 31.0/ 0.05 1233/ 2. 10 4269/ 7.26 4928/ 8.38 526/ 0.89 10987/18. 68 7.45160 NUMBER OF BAD RECORDS: 183

TABLE A-14 on't)

Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP Period of Record: 1/1/76 - 12/31/82 Upper Monitoring Level SI TE~SFINP PER lDD>76-82

SUMMARY

OVER ALL STAB UPWNDSPD UPWNDDEG AVERAGE CALM .75-3.5 3.5-7.5 7.5-12.5 12. 5-18. 5 18.5-25 )~ 25 TOTAL UPWNDSPD 3.6/ 0.01 232/ 0.39 1220/ 2.07 2067/ 3.51 749/ 1.27 81/ 0. 14 7/ 0.01 43eo/ 7.41 9. 31995 NNE 3.3/ 0.01 213/ 0.36 1198/ 2.04 2328/ 3.96 736/ 1.25 51/ 0.09 3/ 0.01 4532/ 7.70 9. 30314 NE 3.7/ 0.01 237/ 0.40 1040/ 1.77 1815/ 3.09 440/ 0.75 11/ 0.02 3547/ 6.03 8.65805 ENE 3.3/ 0.01 214/ 0.36 984/ 1.67 1310/ 2.23 223/ 0.38 10/ 0.02 I/ 0.00 2745/ 4.67 8. 12592 3.4/ 0.01 216/ 0.37 1013/ 1.72 1079/ 1.83 140/ 0.24 2/ 0.00 I/ 0.00 2454/ 4. 17 7.58352 ESE 3.8/ 0.01, 240/ 0.41 939/ 1.60 799/ 1.36 77/ 0. 13 2/ 0.00 I/ 0.00 2062/ 3.50 7.08213 SE 3.3/ 0.01 212/ 0.36 845/ 1.44 794/ 1.35 100/ 0.17 15/ O.O3 1969/ 3.35 7.45496 SSE 3. I/ 0.01 197/ 0.33 1067/ 1.81 1330/ 2.26 295/ 0.50 40/ 0.07 13/ 0.02 2945/ 5.01 8.47917 3.6/ 0.01 230/ 0.39 1280/ 2.18 2070/ 3.52 603/ 1.02 72/ 0. 12 11/ 0.02 4270/ 7.26 9.07728 SSW 4. I/ 0.01 265/ 0.45 1509/ 2.56 3075/ 5.23 1105/ 1.88 171/ 0.29 19/ 0. 03 6148/10. 45 9. 74608 SW 4.9/ 0.01 314/ 0.53 1691/ 2.87 2687/ 4.57 919/ 1.56 196/ 0.33 50/ 0.08 5862/ 9.96 9. 51517 WSW 4.4/ O.OI 284/ 0.48 1545/ 2.63 2180/ 3.71 639/ 1.09 131/ 0.22 46/ 0.08 4829/ 8.21 9. 12842

4. I/ 0.01 264/ 0.45 1005/ 1.71 1205/ 2.05 407/ 0.69 90/ 0. 15 12/ 0.02 2987/ 5.08 8.73836 WNW 3.6/ 0.01 233/ 0.40 865/ 1.47 1163/ 1.98 598/ 1.02 166/ 0.28 30/ 0.05 3059/ 5.20 9.85444 NW 3.8/ 0.01 240/ 0.41 1029/ 1.75 1414/ 2.40 664/ 1. 13 68/ 0. 12 8/ 0.01 3427/ 5.82 9.26642 NNW 3.9/ 0.01 249/ 0.42 1094/ 1.86 1577/ 2.68 626/ 1.06 86/ 0. 15 3636/ 6.18 9. 13737 TOTAL 60.0/ 0. 10 3840/ 6.53 18324/31. 15 26893/45.71 8321/14. 14 1192/ 2.03 202/ 0.34 58832/ 100 8.98214 NUMBER OF BAD RECORDS: 2536

TABLE A-15 SHEARON HARRIS PLANT SITE INFORMATION TO BF. USFD FOR GROUND LFVEL CALCULATIONS WITH NRC "XOODOO" PROGRAM Value to be Used

~Card T e Columns Descri tion in X DOO 1 Print Input Data 38 Calculate Annual X/Os for Points of interest 39 Calculate Annual X/0 Averages for Site Radial Segments 41 Print Out Set Distance X/Os and D/Os 55 Calculate Annual D/0 Averages for the Set Radial Segments 56 Allow Depleted X/Os (If Decays (1), (2), or (3) is Negative) 58 Calculate Annual D/Os for Points of Interest 1-80 Title Card N/A 1-5 Number of Wind Velocity Categories 7 6-10 Number of Stability Categories 7 11-15 Number of Distances within Terrain Data for Each Sector 5 16-20 Total Number of Hours in Joint Wind Frequency Distribution (1) 21-25 Increment in % for which Plotted Results are to be Plotted 5 26-30 Number of Titles of Receptor Types 5 31-35 Number of Release Exit Locations 3 1-5 Height of the Measured Wind 11 6-20 Half-Life (days) Used in the X/O Calculations 101.00 226

-8.00 N/A N/A 1-80 Joint Wind Frequency Distribution

TABLE A- ntinued)

Value to be Used Columns Descri tion in X D 1-5 Wind Velocity Units Correction 200.

6-75 Maximim Wind Speed in Each Wind Class (m/sec) 0.75 3.50 7.50 12.50 18.50 25.00 26.00 1-80 Distance in Meters at which Teerain Heights are Givin (2) 1-80 Terrain Heights (In Meters, Above Plant Grade) Corresponding (2) to Distances on Card Type 8 1-25 Number of Receptor Locations for a Particular Receptor Type Site Boundary 16 Dairy 1 Meat 14 Residence 16 Garden 16 1-16 Title Of Receptor Type for Receptor Locations Site Boundary Dairy Meat Residence Garden 1-80 Receptor Direction and Distance (See Table 1) 1-80 Title for Release Point whose Characteristics are Described on Card Type 14 1-5 Vent Average Velocity (m/sec) 20. 1 6-10 Vent Inside Diameter (m) 1.0 11-15 Height of Vent Release Point (m) 0.000 16-20 Height of the Vent's Building (m) 59.0 21-25 Minimum Cross-Sectional Area for the Vent's Buiding (m ) 1370.0 31-35 Vent Heat Emission Rate (cal/sec) 11.

0.

- TABLE A- ontinued)

Value to be Used

~Card T a Columns Descri tion in XOOD 15 1 Identification for Release Point A 2-5 Intermittent Releases 1 6-10 Number of Intermittent Releases Per Year for the Release Point 100 11-15 Average Number of Hours Per Intermittent Release 1 (1) Appropriate Data to be Supplied II (2) Obtained from Cross-Sectional Topographic Maps

APPENDIX B 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 10CFR20 and Appendix I of 10CFR50 for gaseous effluents. These dose parame-ters, 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 P; and Ri values for the various exposure pathways.

Calculation of Pi The dose parameter, Pi, contained in the radioiodine and particulates portion of Section 3.2 includes pathway transport parameters of the "i" radionuclide, the receptor's usage of the pathway media, and the dosimetry of the expo-sure. Pathway usage rates and the internal dosimetry are functions of the receptor's age; however, the youngest age group, the infant, will always receive the maximum dose under the exposure conditions for Technical Specifi-cation 3.11.2 .lb. For the infant exposure, separate values of P; may be calculated for the inhalation pathway whi'ch is combined with a W parameter based on (X/g) and the food (milk) and ground pathway which is combined with a W parameter normally based on (D/g) except for tritium. The following sec-tions provide in detail the methodology which was used in calculating the Pi values for inclusion into this ODCM.

B.l.l Inhal ation Pathwa The evaluation of this pathway consists of estimating the maximum dose to the most critical organ received by an infant through inhalation by:

pi K'(BR) DFAi I

where:

pi Dose parameter for radionuclide "i" for the inhalation path-I way, mrem/yr per pCi/m; K' constant of unit conversion; 10 pCi/pCi BR The breathing rate of the infant age group, m /yr; DFAi = The maximum organ inhalation dose factor for the infant age group for radionuclide "i," mrem/pCi.

The age group considered is the infant group. The infant's breathing rate is taken as 1400 m /yr from Table E-5 of Regulatory Guide 1.109, Revision 1. The inhalation dose factors for the infant, DFA;, are presented in Table E-10 of Regulatory Guide 1.109 in units of mrem/pCi. The total body is considered as an organ in the selection of DFA;.

The incorporation of breathing rate of an infant and the unit conversion factor results in the following equation:

pi 1.4 x 10 DFAi I

B.1.2 Ground Pl ane Pathwa The dose factor from ground plane pathway is calculated by:

-x.t K'K"DFGi (1-e )/X,.

1G where:

Dose parameter for radionuclide "i" for the ground plane path-way, mrem/yr per 'pCi/sec per m 2; A constant of unit conversion; 10 6 pCi/pCi; B-2

0 K' = A constant of unit conversion; 8760 hr/yr; The radiological decay constant for radionuclide "i," sec The exposure period; 3.15 x 10 sec (1 year);

DFG; = The ground plane dose conversion factor for radionuclide "i,"

mrem/hr per pCi/m .

The deposition rate onto the ground plane results in a ground plane concentra-tion that is assumed to persist over a year with radiological decay the only operating removal mechanism for each radionuclide. The ground plane dose conversion factors for radionuclide "i," DFG;, are presented in Table E-6 of Regulatory Guide 1.109, Revision 1.

Resolution of the units yields:

-X,it

= 8.76 x 10 OFG. (1-e )/X (B.1-4)

Pi 1 G

B.1.3 Milk The dose factor from the cow/goat-milk-man pathway is calculated by:

K'r qF (u ) F P ~

'M y (B.1-6) p 1 where:

Dose parameter for radionuclide "i" for the cow milk or goat milk pathway, mrem/yr per pCi/sec per m K' constant of unit conversion; 10 pCi/pCi; QF The cow's or goat's consumption rate of feed, kg/day (wet weight).

B-3

Ua

= The infant's milk consumption rate, liters/yr; Yp The agricultural productivity by unit area, kg/m; The stabl e el ement tr ansfer coefficient, pCi/liter per pCi/day; Fraction of deposited activity retained on cow's or goat's feed grass; DFLi = The maximum organ ingestion dose factor for radionuclide "i,"

mrem/pCi; The radiological decay constant for radionuclide "i," sec The decay constant for removal of activity on leaf and plant surfaces by weathering, sec 5.73 x 10 sec (corresponding to a 14-day half-life);

The transport time from pasture cow or goat to milk to infant, sec.

A fraction of the airborne deposition is captured by the ground plane vegeta-tion cover. The captured material is removed from the vegetation (grass) by both radiological decay and weathering processes.

Various parameters which were utilized to determine the P; values for the cow and goat milk pathways are provided in Table 8-1. Table E-1 of Regulatory Guide 1.109, Revision 1, provides the stable element transfer coefficients, Fm., and Table E-14 of the same regulatory guide provides the ingestion dose factors, DFLi, for the infant's organs. The organ with the maximum value of DFLi was used in the determination of PE for this pathway. The incorporation of the various constants of Table 8-1 into Equation 8.1-5 results in the following:

8-4

For radioiodines and particulates from cow's milk:

rF -xi t f P 2~1010 m DFL i e (B.1-6)

M ki+Q For radioiodines and particulates from goat's milk pathway:

rF -X. tf iM 2.8 x 10 DFLi e (B.1-7)

The concentration of tritium in milk is based on its airborne concentration rather than the depostion rate and is calculated by:

P TN K K FmQFUa DFLT 0 ~ 75 (0 o5/H ) (B.1-8) where:

P TM Dose parameter for tritium for the cow milk and goat milk pathways, mrem/yr per pCi/m; Kl I I A constant of unit conversion; 10 gm/kg; 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; DFLT = Maximum organ ingestion dose factor for tritium, mrem/pCi.

B-5

Calculation of R ~

The radioiodine and particulate Technical Specification 3.11.2.3 is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates that the maximum potential exposure occurs. The inhalation and ground plane exposure pathways shall be considered to exist at all locations. The grass-goat-milk, the grass-cow-milk, gr ass-cow-meat, and vegetation pathways are considered based on their existence at the various locations. R; values have been calculated for the adult, teen, child, and infant age groups for the ground plane, cow milk, goat milk, vege-table, and beef ingestion pathways. The methodology which was utilized to calculate these values is presented below.

B.2.1 Inhalation Pathway The dose factor from the inhalation pathway is calculated by:

Ri K'BR)a (DFAi)a I

where:

Ri Dose factor for each identified radionuclide "i" of the organ I

of inter est, mrem/yr per pCi/m ;

A constant of unit conversion; 106 pCi/pCi; (BR)a = Br eathing rate of the receptor of age group a, m /yr; (DFA;) a = Organ inhal ation dose factor for radionucl ide "i" for the receptor of age group a, mrem/pCi.

The breathing rates (BR)a for the various age groups are tabulated below, as given in Table E-5 of Regulatory Guide 1.109, Revision l.

8-6

A e Grou (a) Breathing Rate (m / r)

Infant 1400 Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFAi)a for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109, Revision l.

B.2.2 Ground Plane Pathwa The ground plane pathway dose factor is calculated by:

-sit Ri G

Ii K K SF DFGi 1 (B.2-2) where:

R Dose factor for the ground plane pathway for each identified G

radi onucl i de "i" for the organ of interest, mrem/yr per pCi/sec per m 2; K' constant of unit conversion; 10 pCi/pCi; K(I A constant of unit conversion; 8760 hr/year; The radiological decay constant I

for radionuclide "i," sec The exposure time, sec; 4.73 x 10 sec (1S years);

~

DFG; i = . The ground plane dose conversion factor for radionuclide "i;"

mrem/hr per pCi/m2; B-7

A tabulation of DFG; values is presented in Table E-6 of Regulatory Guide

~

1.109, Revision 1.

~ ~

SF The shiel ding factor (dimensionl ess);

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

Factor to account for fractional deposition of radionuclide II i 11 For radionuclides other than iodine, the factor I; is equal to one. For radioiodines, the value of I; may vary. However, a value of 1.0 was used in calculating the R values in Table 3.3-2. (Reference NUREG 0133) 8.2.3 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:

IK'$U

-gtf r(1-e Ki e) Biv (lw t b)

= F DFL; e )*

s t

Ei

+

Bi "v

)e (1-e

-),i t

) -zi th (8.2-3) where:

Dose factor for the cow milk or goat milk pathway, for each identified radionuclide "i" for the organ of interest, mrem/yr per pCi/sec per m 2.

8-8

A constant of unit conversion; 10 pCi/pCi.

QF The cow's or goat's feed consumption rate, kg/day (wet weight);

Uap

= The receptor' mil k consumption rate for age group a,

. liters/yr; Yp The agricul tural productivity by unit area of pasture feed grass, kg/m2; Ys The agricultural productivity by unit area of stored feed, kg/m

'he stable element tr ansfer coefficients, pCi/liter per pCi/day; Fraction of deposited activity retained on cow's feed grass; (DFLi)a = .The organ ingestion dose for radionuclide "i" for the receptor in age group a, mrem/pCi; The radiological decay constant for radionuclide "i," sec ~;

The decay constant for removal of activity on leaf and plant surfaces by weathering, sec 5.73 x 10 sec (corresponding to a 14 day half-life);

The transport time from feed to cow, or goat to milk, to receptor, sec; 8-9

The transport time for harvest, to cow or goat, to consump-tion, sec; tb Period of time that sediment is exposed to gaseous effluents, sec; Biv = Concentrati on factor for uptake of radi onucl i de "i" from tHe soil by the edible parts of crops, pCi/Kg (wet weight) per pCi/Kg (dry soil);

Effective surface density for soil, Kg (dry soil)/m  ;

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; te Period of pasture grass and crop exposure during the growing season, sec; Factor to account for fractional deposition of radi onucl i de "i "

For radionuclides other than iodine, the factor I; is equal to one. For radioiodines, the value of Ii may vary. however, a value of 1.0 was used in calcuating the R values in Tables 3.3-9 through 3.3-16. (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 fs was considered unity in lieu of site-specific information. The value of fp was 0.667 based upon an 8-month grazing period.

B-10

Table B-1 contains the appropriate parameter values and their source in Regu-latory Guide 1.109, Revision 1.

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the Ri is based on X/Q:

T

= K K'FmQFUap(DFLj)a 0 '5(0 '/H) where:

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

K' ' A constant of unit conversion; 103 gm/kg; 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.

B.2,4 Grass-Cow-Meat Pathway The integrated concentration in meat follows in a similar manner to the devel-opment for the milk pathway, therefore:

-gt r(1-e ~i ) iv (1-e ~~)

IiK'(Pa Ff Li e a p s Y g Pk.

P r(1~ ~i e) Blv (1~ )

(1 fp fs ) (B.2-5)

where:

Ri Dose factor for the meat ingestion pathway for radionuclide B "i" for any organ of interest, mrem/yr per pCi/sec per m Ff The stable element transfer coefficients, pCi/Kg per pCi/day; Ua

= The receptor's meat consumption rate for age group a, kg/yr; ts The transport time from slaughter to consumption, sec; h The 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 II i II For radionuclides other than iodine, I; is equal to one. For radioiodines, the value of I; may vary. However, a value of 1.0 was used in calculating the R values in Tables 3 .3-6 through 3 .3-8.

All other terms remain the same as defined in Equation B.2-3. Table B-2 contains the values which were used in calculating R; for the meat pathway.

The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the Ri is based on X/Q.

RT K K FmQFUa ( DFLi ) a 0 o75( 0 o5/H) (B.2-6)

B where:

RT Dose factor. for the meat ingestion pathway for tritium for any B

organ of interest, mrem/yr per pCi/m .

B-12

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

The integrated concentration in vegetation consumed by man follows the expres-sion 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:

i R;

= IiK'DFL,.) (U fL e r(1-e )

~k; iv (1-e )

-~ t -x.t usf e ih r(le i ) iv(1e ' (B.2-7)

YXE pz,.

where:

Ri Dose factor for vegetable pathway for radionuclide "i" for the V

organ of interest, mrem/yr per pCi/sec per m 2; K' constant of unit conversion; 106pCi/pCi; UL The consumption rate of fresh leafy vegetation by the receptor in age group a, kg/yr; us 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; fg The fraction of the annual intake of stored vegetation grown locally; 8-13

The average time between harvest of leafy vegetation and its consumption, sec; th The average time between harvest of stored vegetation and its consumption, sec; Yv The vegetation areal density, kg/m  ;

te period of leafy vegetable exposure during growing season, sec; Factor to account for fractional deposition of radionuclide II i II All other factors as defined before.

For radionuclides other than iodine, the factor Ii is equal to one. For radioiodines, the value of Ii may vary. However, a value of 1.0 was used in Tables 3.3-3 through 3.3-5.

Table B-3 presents the appropriate parameter values and their source in Regu-latory Guide 1.109, Revision 1.

In lieu of site-specific data default values for fL and fg, 1.0 and 0.76, respectively, were used in the calculations on Ri. These values were obtained from Table E-15 of Regulatory Guide 1.109, Revision 1.

The concentration of tritium in vegetation is based on the airborne concentra-tion rather than the deposition. Therefore, the R; is based on X/0:

RT V

K K Ua fL + Ua f (DFLi ) a 0 o75(0 o5/H) (B.2-S) where:

RT V

Dose factor for, the vegetabl e pathway for tri tium for any organ of interest, m'rem/yr per 'pCi/m .

All other terms remain the same as those in Equations 8.2-4 and B.2-7.

B-14

TABLE B-1 Parameters For Cow and Goat Milk Pathways Reference Parameter Value (Re . Guide 1.109 Rev. 1 OF (kg/day) 50 (cow) Table E-3 6 (goat) Table E-3 Yp (kg/m2) 0.7 Table E-15 Tf (seconds) 1.73 x 10 (2 days) Table E-15 1.0 ( radioiodines) Table E-'l5 0.2 (particulates) Table E-15 i a (mrem/pCi) Each radionuclide Tables E-11 to E-14 F (pCi/day per pCi/liter) Each stable element Table E-1 (cow)

Table E-2 (goat)

Tb (seconds) 4.73 x 108 (15 yr) Table E-15 Ys kg m 2.0 Table E-15 Y (kg/m2) 0.7 Table E-15 th (seconds) 7.78 x 10 (90 days) Table E-15 Uap (liters/yr) 330 infant Table E-5 330 child Table E-5 400 teen Tabl e E-5 310 adult Table E-5 te ( seconds) 2.59 x 10 (pasture) Table E-15 5.18 x 10 (stored feed)

Bi(pCi/kg [wet weight] Each stable element Table E-1 per pCi/kg [dry soil])

P kg (dry soil/m2) 240 Table E-15

TABLE B-2 Parameters For The Meat Pathway Reference Parameter Value (Reg. Guide 1.109, Rev. 1 1.0 ( radioiodines) Table E-15 0.2 (particulates) Table E-15 Ff (pCi/kg 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 Yp ( kg/m ) 0.7 Table E-15 Ys (kg/m ) 2.0 Table E-15 Tb (seconds) 4.73 x 108 (15 yr ) Table E-15 Ts (seconds) 1.73 x 10 (20 days) Table E-15 th (seconds) 7.78 x 10 (90 days) Table E-15 te (seconds) 2.59 x 10 (pasture) Table E-15 5.18 x 10 (stored feed) gF (kg/day) 50 Table E-3 Biz (pCi/kg Lwet weight] Each stable element Table E-1 per pCi/kg [dry soil])

P (kg fdry soil/m21) 240 Table E-15

TABLE B-3 Parameters for The Vegetable Pathway Reference Parameter Val ue (Re . Guide 1.109 Rev. 1 r (dimensionless) 1.0 ( radioiodines) Table E-1 0.2 (particulates) Table E-1 (DFLi)a (mrem/Ci) Each radionuclide Tables E-11 to E-14

()F (kg/day) 50 (cow) Table (goat) E-3 E-3'able 6

Ua (kg/yr) - Infant 0 Table E-5

- Child 26 Table E-5

- Teen 42 Table E-5

- Adult 64 Table E-5 Ua (kg/yr) - Infant 0 Table E-5

- Child 520 Table E-5

- Teen 630 Table E-5

- Adult 520 Table E-5 TL (seconds) 8.6 x 104 (1 day) Table E-15 th (seconds) 5.18 x 10 (60 days) Table E-15 Yv ( kg/m ) 2.0 Table E-15

'e (seconds) 5.18 x 10 (60 days) Table E-15 Tb (seconds) 4.73 x 108 (15 yr) Table E-15 P (kg I.dry soil/m2~) 240 Table E-15 Biy ( pCi/kg Lwet wei ght7 Each stable element Table E-1 per pCi/kg t:dry soil j)

APPENDIX C LOMER LIMIT OF DETECTION (LLD) FOR PLANT EFFLUENTS AND ENVIRONMENTAL SAMPLES The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probabil-ity of falsely concluding that a blank observation represents a "real" signal.

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

4.66 sb LLD E

' '.22 x 10 Y 'xp (-),at) where:

LLD the "a priori" lower limit of detection (as microcuries per unit mass or volume),

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

the counting efficiency (as counts per transformation),

the sample size (in units of mass or volume),

2.22 x 10 = the number of disintegrations per minute per microcurie (for environmental samples the LLD should be expressed in picocuries),

the fractional radiochemical yield, when applicable, the radioactive decay constant for the particular radionuclide (sec ) and,

the elapsed time between midpoint of sample collection and time of counting (sec) for plant samples, the elapsed time between environmental collection, or end of the sampl e coll ection period, and time of counting (sec) for environmental samples.

Typical values of E, V, Y, and iht should be used in the calculation.'t should be recognized that the LLD is defined as an a ~riori (before the fact) limit representing the capability of a measurement t i l(ft h f oils I'p ti system and not as For environmental samples, analyses shall be performed in such a manner that the LLDs stated in Technical Specification 4.12.1 will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radi ol ogi cal Environmental Operating Repor t pursuant to Technical Speci ficati on 6.9.1.6.

C-2

( APPENDIX D RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS I. Li uid Effluent Monitorin Instruments Monitor Identi fication A. Treated Laundry and Hot Shower Tank REM-3540 B. Waste Monitor Tank'.

REM-3541 Waste Evaporator Condensate Tank REM-3541 D. Secondary Waste Sample Tank REM-3542 II. Gaseous Effluent Monitorin Instruments A. Plant Vent Stack 1

1. Plant Vent Stack 1 REM-1AV-3509-SA

2. Reactor Auxiliary Building Normal Exhaust REM-1AV-3531

3. Reactor Auxiliary Building Emergency Exhaust 'EM-1A-3532A

4. Fuel Handling Building Normal Exhaust (South) REM-1FL-3506

5. Fuel Handling Building Normal Exhaust (South) REM-1FL-3507

6. Fuel Handling Building Emergency Exhaust REM-1FL-3508A-SA

7. Fuel Handling Building Emergency Exhaust REM-1FL-3508B- SB B. Turbine Building Vent Stack 3A REM-1TV-3534 C. Waste Processing Building Vent Stack 5 REM-1WV-3546 D. Waste Processing Building Vent Stack 5A REM-1WV-3547