ML20209B978

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Rev 2 to Offsite Dose Calculation Manual
ML20209B978
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 03/06/1986
From: Morgan R
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML14176B061 List:
References
PROC-860306, NUDOCS 8609080366
Download: ML20209B978 (164)


Text

-

Enclosure 3 to Serial: RNPD/86-3790 Page 1 of 164 -

H 8. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 0FF-SITE DOSE CALCULATIONAL MANUAL (00CM)

Revision 2

. DOCKET NO. 50-261 PNSC Review _>.s, W)it).[fOATE I

YY'7-- 6 -#L PNSC ChaMitan CAROLINA POWER & LIGHT COMPANY

, March 5, 1986 CONTROL _ED COPY 8609030366 860630 PDR R ADOCK 05000261 PD,R

Page 2 of 164 1

TABLE OF CONTENTS Section Tjtle t Page TABLE OF CONTENTS........................................... i LIST OF TA8LES.............................................. ii LIST OF FIGURES............................................. iv 1.0 INTR 000CTION................................................ 1-1 2.0 LIQUID EFFLUENTS.............. ............................. 2-1 2.1 Monitor Alarm Setpoint Suti mination................. 2-1 2.2 Compliance with 10CFR20 (Liquids).................... 2-11 2.3 Compliance with 10CFR50 (Liquids).................... 2-16 3.0 GASE0US EFFLUENTS........................................... 3-1 3.1 Moni tor Al arm Setpoint Determination. . . . . . . . . . . . . . . . . 3-1 3.2 Compliance with 10CFR20 (Gase'ous).................... 3-15 3.3 Compliance with 10CFR50 (Gaseous).................... 3-23 3.4 Methodology for RMS-11 Setpoint (Air Particulate).... 3-63 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM............... 4-1 5.0 INTERLABORATORY COMPARISON STUDIES. . . . . . . . . . . . . . . . . . . . . . . . . . 54 1 5.1 0bjective............................................ 5-1 5.2 Program.............................................. 5-1 6.0 TOTAL DOSE (40CFR190 CONFORMANCE)........................... 6-1 6.1 Compliance with 40CFR190............................. 6-1 6.2 Calculations Evaluating Conformance with 40CFR190.... 6-1 6.3 Calculations of Total Body 00se...................... 6-2 6.4 Thyroid 0ose......................................... 6-3 6.5 Dose Projects........................................ 6-3 APPENDIX A - Meteorological Dispersion Factor Computations......................................... A-1 APPENDIX B - Dose Parameters for Radioiadines, Particulates, and Tritium............................ B-1 APPENDIX C - Lower Limit of 0etectability................... C-1 s

i Rev. 2

Page 3 of 164 i

LIST OF TABLES No. Title Page 2.3-1 Aj , Values for the Adult for the H.B. Robinson Steam Electric Plant....................... 2-22 3.1-1 Gaseous Source Terms..................................... 3-13 3.1-2 Dose Factors and Constants............................... 3-14 3.2-1 Releases from H.B. Robinson Unit No. 2................... 3-19 3.2-2 Distance to Special Locations for the H.B. Robinson Plant (Mi.)................................ 3-20 3.2-3 Dose Factors for Noble Gases and Daughters............... 3-21 3.2-4 Pg Values for an Infant for the H.B. Robinson Unit No. 2............................................... 3-22 3.3-1 thru R Values for the H.B. Robinson Steam Electric Plant...... 3-34 3.3-19 thru 3-52 3.4-1 th u Ingesti on Dose R Factors. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-53 3.4-10 thru 3-62 4.0-1 H.B. Robinson Radiological Environmental Monitoring Program....................................... 4-2 A-1 X/QValuesforLong-TermGrgundLevelReleases at Special Locations (sec/m )............................ A-4 A-2 DepletedX/QValuesforLong-TermGrgundLevel Releases at Special Locations (sec/m )................... A-5 l

A-3 0/Q Values for Long-Term Gr und Level Releases at Special Locations (m'2)............................... A-6 A-4 X/QValuesforLong-TermGrogndLevelReleases

, at Standard Distances (sec/m )........................... A-7 A-5 DepletedX/QValuesforLong-TermGrogndLevel i

l Releases at Standard Distances (sec/m ).................. A-8 A-6 0/QValuesforLong-TermgroundLevelReleases at Standard Distances (m- ).............................. A-9 A-7 X/QValueforShort-TermGrgundLevelReleases at Special Locations (sec/m )............................ A-10 A-8 Depleted X/Q Values for Short-Term G ound Level l

i ReleasesatSpecialLocations(sec/m$)................... A-11 11 Rev. 2 i

Paga 4 of 164 LIST OF TABLES (continued)

No. Title Page A-9 D/Q Values at Special for Short-Terg)Groun<1 Locaticns Level Releases (m- ............................... A-12 A-10 X/QValuesforLong-TermMigedModeReleases at Special Locations (sec/m )............................ A-13 A-11 Depleted X/Q Values for Long-Term Miged Mode

)...................

~

Releases at Special Locations (sec/m A-14 A-12 0/Q Values for Long-Term Mixed Mode Releases .

at Special Locations (m~2)............................... A-15 A-13 X/Q Values for Long-Term Mixgd Mode Releases at Standa rd D i stances ( sec/ln ) . . . . . . . . . . . . . . . . . . . . . . . . . . . A-16 A-14 Depleted X/Q Values for Long-Term Mixgd Mode Releases at Standard Distances (sec/m ).................. A-17 A-15 D/Q Values for Long-Term Mixed Mode Releases at Standard Distances (m"-).............................. A-18 A-16 X/QValuesforShort-TermMjxedModeReleases at Special Locations (sec/m )............................ A-19 A-17 DepletedX/QValuesforShort-TermMjxedMode Releases at Special Locations (sec/m )................... A-20 A-18 0/QValuesforShort-Terg)MixedMoceReleases at Special Locations (m- ............................... A-21 A-19 Robinson Plant Site Information to be Used for Ground Level Calculations with NRC "X00000" Program......................................... A-22 A-20 Robinson Plant Site Information to be Used for Mixed Mode Release Calculations with NRC "X0000Q" Program......................................... A-25 B-1 Parameters for Cow and Goat Milk Pathways.. . . .. . .. ..... .. B-15 B-2 P a ramete rs fo r the Meat P athway . . . . . . . . . . . . . . . . . . . . . . . . . . B-16 B-3 Pa rameters fo r the Vegetabl e Pathway. . . . . . . . . . . . . . . . . . . . . B-17 0-1 L i qu i d P ro c e s s Mo n i t o rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 0-1 0-2 Gasecus Process Monitors................................. 0-2 iii

Page 5 of 164 LIST OF FIGURES ,

No. Title Page 4-1 Radiological Sample locations Near Site.................. 4-9 4-2 Radiological Sample Distant Locations.................... 4-10 0-1 H.B. Robinson Liquid Radweste Effluent System............ 0-3 0-2 H.B. Robinson Gaseous Radwaste Effluent System........... 0-4 l

I I

  • I iv Rev. l'

Page 6 of 164 -

1.0' INTRODUCTION The Off-Site Dose Calculation Manual (00CM) provides the information and methodologies to be used by H. B. Robinson Steam Electric Plant Unit 2, (HBR) to assure compliance with Specifications 3.9.1, 3.9.2, 3.9. 3, 3.9.4, 3.9.5, and 3.9.6 of the H. B. Robinson Technical Specification. 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 00CM is based on " Radiological Effluent Technical Specifications for PWRs (NUREG 0472. Rev. 3, Draft 7), " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREG 0133), and guidance from the United States Nuclear Regulatory Commission (NRC). Specific plant procedures for implementation of this manual are presented in H. B. Robinson Unit 2 Plant Operating Manual. These procedures will be utilized by the operating staff of HBR to assure compliance with technical specifications.

The 00CM has been prepared as generically as possible in order to minimize the need for future revisions. However, some changes to the 00CM will be expected in the future. Any such changes will be properly reviewed and approved as indicated in the Administrative Control Section, Specification 6.16.2, of the HBR Technical Specifications.

i 11 Rev. 1 i

Page 7 of 164 2.0 LIQUID EFFLUENTS 2.1 MONITOR ALARM SETPOINT DETERMINATICN This methodology determines the monitor alarm setpoint that indicates I if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds the concentrations spect-fled in 10CFR20, Appendix 8. Table II, Column 2. for radionuclides other than dissolved or entrained noble gases or exceeds a concentra-tion 2 x 10-4 uC1/mi for dissolved or entrained noble gases. Two methodclogies may be utilized to calculate monitor alarm setpoints.

Section 2.1.1 determines a fixed setpoint based on the worst case assumptions that I-131 is the only nuclide being discharged. This is consistent with the limit of 10CFR20, Appendix 8 Footnote 3.a.

Section 2.1.2 methodology determines the setpoint based on the radionuclide mix via analysis prior to release to demonstrate compliance with 10CFR20, Appendix 8 limits and may also be used as an alternative method for calculating setpoints.

2.1.1 Setpoint Based on Iodine-131 The following method applies to liquid releases via the discharge canal when determining the alarm / trip setpoint for the Waste Disposal System Effluent Monitor (RMS-18) and the Steam Generator Blowdown Monitor (RMS-19) during all operational conditions when the radwaste l discharge flow rate is maintained constant. This methodology com-plies with Specification 3.9.1.1 of the RETS by satisfying the fol-lowing equation:

h1C where:

C = The affluent concentration limit (Specification 3.9.1.1) imple-menting 10CFR20 fo* the site in uC1/ml.

2-1 Rev. I

Page 8 of 164 c = The setpoint, in uCi/ml, of the radioactivity ' monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint represents a value which, if exceeded, would result in concentrations exceeding the limits of 10CFR20 in the unrestricted area.

f = The waste effluent flow rate in gpm.

F = The <tilution water flow rate in gpe.

2.1.1.1 Determine c (the effluent monitor setpoint) in uC1/mi for each of the dilution water flow rates.

where: c=h C=3 x 10~I uC1/ml, the effluent concentration limit based on 10CFR20, Appendix B, for I-131.

F = Dilution water flow rate (gpm).

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

= 250,000 gpm from two circulating water pumps l

, Unit 2.

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

or 2

= 50,000 gpa from one circulating water pump , Unit 1.

2

= 80,000 gpa from two circulating water pumos , Unit 1.

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

= 60 gpm for the Waste Disposal System Liquid Effluent Monitor3 .

2-2 Rev. 1 l

Page 9 of 164

= 750 gpm for the Steam Generator 810wdown Monitor.

= 450 gpm for the Steam Generator 810wdown Monitor while draining a steam generator.

= 390 gpm for the Condensate Polisher Liquid Waste Monitor, i

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

CR = (c) (E)

E = The applicable effluent monitor efficiency located in the Plant Operating Manual, Volume 15, Curve Book. Use the radioactivity concentration "c" to find CR.

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

SP = (T,CR + Background) 1 where: T, = Fraction of the radioactivity from the site that may be re-leased via the monitored pathway to ensure that tne site bouno-

! ary limit is not exceeded due to simultaneous releases from several pathways.

! = .05 for the Waste Disposal System Liquid Effluent Monitor

! (RMS-18).

= .70 for the Steam Generator Blowdown Monitor (RMS-19).

= .25 for the Condensate Polisher Liquid Waste (RMC-37).

1 2-3 Rev. 1

Page 10 of 164 2.1.2 Setooint Based on an Analysis of liquid Prior to Oischarge The following method applies to liquid releases via the discharge canal when determining tne alarm set;:oint for the Waste Discosal System Liquid Effluent Monitor (RMS-18), the Steam Generator Slowdcwn Monitor (RMS-19), and the Condensate Polisher Liquid Waste Monitor (RMS-37) when an analysis of the activity of the principal gamma emitters has been made prior to each batch released.

2.1.2.1 Determine 0 (the minimum acceptable dilution factor):

Ci 0 =S[j g i

C 3 =[Cg + (C, + C3+Ct*CFe-55I Radioactivity concentration of radionuclide "i" in the liquid effluent prior to dilution (uCf/ml) from analysis of the liquid effluent to be released.

[Cg = The sum of the concentrations of each mecsured gama-emitting radionuclide observed by gamma spectroscopy.

C a = The measured concentration of alpha-emitting radionuclides observed by gross alpha analysis of the monthly composite sample.

C = The measured concentration of Sr-89 and Sr 90 in liquid waste 3

as determined by analysis of the quarterly composite sample.

C = The measured concentrations of H-3 in liquid waste as deter-t mined by analysis of the monthly composite sample.

CFe-55 = The measured concentration of Fe-55 in liquid waste as deter-mined by analysis of the quarterly composite sample.

2-4 Rev. 1

Page 11 of 164 MPC j = The liquid effluent radioactivity limit for radionuclide *i" (uC1/ml) from 10CFR20, Appendix B.

S = 2, A safety factor used as a conservatism to assure that the radionuclide concentrations are less than the limits specif fed in 10CFR20, Appendix B, at the point of discharge.

2.1.2.3 Determine c (the monitor setpoint concentration [uCl/ mil attributed to the radionuclides for the dilution water flow rate available during the release.

c =([g C)(h)(Tm) g where:

C g c The total radioactivity concentration of gama-emitting radio-nuclides in liquid effluent prior to dilution (uC1/ml).

f = The maximum approved discharged flow rate prior to dilution (gpm).

= 60 gpm for the Waste Disposal System Liquid Effluent Monitor3 .

= 750 gpm for the Steam Generator Blowdown Monitor.

= 450 gpm for the Steam Generator Blowdown Monitor while draining j a steam generator.

l

= 390 gpa for the Condensate Polisher Liquid Waste Monitor.

F = Dilution water flow rate (gpm).

= 160,000 gpm from one circulating water pump l

, Unit 2.

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

= 400,000 gpm from three circulating water pumps l

, Unit 2.

t or i 2-5 Rev. 1 i

Page 12 of 164 2

= 50,000 gpm from one circulating water pump , Unit 1.

= 80,000 gpm from two circulating water pumps 2 , Unit 1.

T, = Fraction of the radioactivity frcm the site that may be re-leased via the monitored pathway to ensure that the site boundary limit is not' excteded due to simultaneous releases from more than one pathway.

= .05 for the Waste Disposal System Liquid Effluent Monitor (RMS-18).

= .70 for the Steam Generator Blowdown Monitor (RMS-19).

= .25 for the Condensate Polisher Liquid Waste.

If it is determined that h < 1 , the release cannot be made.

Reevaluate the discharge flow rate prior to dilution and/or the dilution flow rates.

If 0 f > 1 , the release may be made.

2.1.2.4 Determine SP (the monitor alarm setpoint (ccpml.

SP = (c) (E,) + background.

where: ,

E, = The applicable effluent monitor efficiency based on "c," from the efficiency curves located in the Plant Operating Manual, Volume 15, Curve Book.

s - 2-6 Rev. I t

Paga 13 of 164 (left blank intentionally for future reyf 5f ons)

J 4

e I

2-7

Pagn 14 of 164 (Left blank intentionally for future revisions)

I i

l

\

2-8

Page 15 of 164 (Left blank intentionally for future revisions) 2-9

Page 16 of 164 SECTION

2.1 REFERENCES

1. Carolina Power & Light Company Drawing Number G-190825. Using the System Q-H Curve for Emergency Low Water Level.
2. Carolina Power & Light Company, Darlington County S.E. Plant. 1960-182 MW Installation, Unit 1. SYSTEM HEAD CURVES Unit 1 Circulating Water System Draining Quosig.
3. H.B. Robinson Electric Plant Unit 2 Updated Final Safety Analysis Re-port.

e 9

2-10

,---,-,,-e , , , - - -

Page 17 of 164 2.2 COMPLIANCE WITH 10CFR20 (LIQUIDS)

Liquid effluents from H.B. Robinson Unit 2 (H8R) will occur both continuously and on a batch basis. The following sections discuss the methodology which will be utilized by the H8R to show compliance with 10CFR20.

2.2.1 Continuous Releases Steam generator blowdown is continuously released from HBR. Each operational working day grab samples will be taken of steam generator blowdown. These samples are composited at the rate of 100 ml/sgr.  :

An aliquot of the SG composite is analyzed each week for I-131 and various other fission, activation, and corrosion products, as out-lined in Table 4.10-1 of the technical specification for H8R. Sam- ,

ples are to be maintained until the end of the quarter and analyzed for strontium. Steam generator volumes are based on blowdown rates.

In addition, a monthly analysis will be performed to determine the activity levels of tritium and dissolved and entrained gases. ,

Compliance with 10CFR20 during actual release is established through the steam generator blowdown effluent monitor alarm setpoint. This setpoint is based upon I-131 as noted in Section 2.1. However, if a continuous release should occur in which the effluent monitor alarm setpoint is exceeded, then actual compliance with 10CFR20 may be determined utilizing the actual radionucilde mix and the following equation:

C V c

Concj = (2.2-1) l dc where:

1 Conci = Concentration of radionuclide "i" at the unrestricted i area,uC1/ml; i

~

2 11 Rev. 1

P:g2 18 of 164 C

ic

= Concentration of radionuclide "i " in the continuous re-lease, Ci/ml;

'/c

= Volume of continuous effluent released, gal; V

dc

= Volume of dilution flow during release, gal.

2.2.2 Batch Releases Batch releases will occur during normal operation. When this does occur at HBR, a continuous release will usually be occurring at the same time. However, during certain shutdown conditions, only batch releases may occur at HBR. Therefore, both situations are treated here to provide the methodology to show compliance with 10CFR20.

2.2.2.1 Prerelease The radioactivity content of each batch release will be determined prior to release in accordance with Table 4.10-1. of the technical specifications for HBR. HBR will show compliance with 10CFR20 in the following manner:

For the case where only a batch release is to occur, the concentra-tion of' the various radionuclides in the batch release, determined in accordance with Table 4.10-1 of the technical specifications for HBR, is multiplied by the ratio of the maximum release rate of the poten-tial batch release to the dilution flow rate to obtain the concentra-tion at the enrestricted area. This calculation is shown in the following equation:

C R D

Concj = (2.2-2) i$r f

where: .

2-12

P gs 19 of 164 Concj = Concentration of radionuclide "i" at the unrestricted area, wCi/ml; C

ib = Concer.tration of radionuclide "1 " in the potential batch release, pCi/ml; R

b

= Release rate of the potential batch release, gpm; D yp = The dilution flow rate based upon the number of circulating water pumps in service during the release, gpm.

The concentration in the unrestricted area is compared to the con-centrations in Appendix B, Table II, Column 2, of 10CFR20. Before release may occur, the mixture of radionuclides released must be of such concentration that Equ'ation 2.2-3 is met.

[j (Concj /MpC j )I1 (2.2-3) where:

MpC j = Maximum permissible concentration of radionuclide "i" from Appendix B, Table II, Column 2 of 10CFR20, Ci/ml.

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

C ib b*Cic Nc (2.24)

Conc 3 = u fr where:

R e

= Maximum continuous liquid effluent release rate, gpm.

2-13

Page 20 fo 164 The mixture of radionuclides released must be of such concentrations that Equation 2.2-3 must be met.

For H8R, the liquid radwaste effluent line discharges to the circu-lating water system. Therefore, the dilution flow rate (Of7) is a function of the number of circulating water pumps operating. Unit 2 of the H.8. Robinson Steam Electric Plant has three circulating water pumps. Pump curves show that with three pumps operating, the circu-lating water flow is 400,000 gpe, with two pumps--250,000 gpm, and with one pump--160,000 gpm. Unit 1 of the H.8. Robinson Steam Elec-tric Plant has two circulating water pumps. The circulating water flow is 50,000 gpm with one pump and 80,000 gpm with two pumps. At least one circulating water pump must be operating during any liquid waste discharge.

Batch releases from the HBR liquid radwaste system may occur from the waste condensate tanks, the monitor tanks, the steam generators, and the Condensate Polisher Liquid Waste. The maximum release rate (Rb )

is 750 gpa for the steam generators, 60 gpm from the monitor and waste condensate tanks, and 390 gpm for the Condensate Po11 sher Liquid Wastes.

2.2.2.2 Postreleasa The Steam Generation Slowdown Monitor (RMS-19), the Waste Disposal System Liquid Monitor (RMS-18), and the Condensate Polisher Liquid Waste Monitor (RMS-37) setpoint will each be limited to 50 percent of the 10CFR20 limits. These setpoints will ensure that 10CFR20 limits are met. However, because they are based upon a given mix, the possibility exists that the alarm trip setpoints may be exceeded, while 10CFR20 limits are not exceeded. The following methodology is provided to determine whether actual releases exceeded 10CFR20 limits.

The concentration of each radionuclide in the unrestricted area ,

following release from a batch tank will be calculated in the follow-ing manner:

2-14 Rev. 1

- , - . _ - _ _ - - . , - . , , . . , . , _ , - . - . . , . - . - , , . . , _ - , , , _ , . , - - - . _ , - , . , - - . - - - , - - . ,,.n,.-_,

Pegs 21 of 164 For the case where only batch releases are occurring, the total activity of radionuclide "1" released is divided by the actual dilu-tion flow to obtain the concentration in the unrestricted area. This calculation is shown in the following equation:

C ikb Ykb (2.2-5)

Concik

  • Vkd where:

Concik = The concentration of radionuclide "i" at the unrestricted area during release k, pCi/ml; C

ikb = Concentration of radionuclide "i" in the batch release k, Ci/ml; V

kb

= Volume of batch release k, gal; V

kd

= Actual volume of dilution flow during release k, gal.

To show compliance with 10CFR20, the following relationship must hold:

(Conc ik /MPC3 ) < 1 (2.2-6)

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

V kd = 60 [k (Ofp)tk (2.2-7) where:

60 = Conversion factor, min /hr;

= Ouration of release k, hr; tk 2-15

Page 22 of 164 Ofr = Oilution flow rate from circulating water pumps during release k, gps.

The circulating water pump flow rates were given in Section 2.2.2.1 ,

above.

For the case where a batch release is occurring at the same time that a continuous release is occurring, the compliance with 10CFR20 limits may be determined by the following equation:

t C V +C V i Concik

= ikb kb ike kc (2.2-8)

V kd where:

C ike = Concentration of radionuclide "1" in continuous releases during release period k, uC1/ml; Vke = Volume of continuous release during period k, gal.

Calculated concentrations are to be compared to the concentration in Appendix 8. Table'II, Column 2, of 10CFR20.

2.3 COMPLIANCE WITH 10CFR50 2.3.1 Cumulation of 00ses The dose contribution from the release of liquid effluents will be calculated once per month, and a cumulative sunniation of these total body and any organ doses should be maintained for each calendar quarter. The dose contribution for all batch releases will be calcu-lated using the following equation:

A, t C F Deb *[k bi 9 kb ikb kb (2.3-1) l 2-16 Rev. l

Page 23 of 164 where:

0.b = The cumulative dose commitment to the total body or any organ e, from batch liquid effluents, mrem; tkb = The length of time of batch release k over which Cikb and Fkb are averaged for each batch liquid release, hours; Cikb = The average concentration of radionuclide "i" in undiluted batch liquid effluent during batch release k, uCi/ml; Ag , = The site-related ingestion dose comitment factor to the total body or any organ t for each identified principal gamma and i

beta emitter, erem-al per hr-uC1; Fkb = The near-field average dilution factor for Cikb during any baten liquid effluent release k. Defined as the ratio of the volume of undiluted liquid wasta released to the product of the dilution volume from the site discharge structure to unrestricted receiving waters times 1.0. (1.0 is the site-specific applicable f actor for the mixing effect of the HBR discharge structure as defined in NUREG-0133, October 1978).

V kb

=

V x 1.0 Where Vkb and Vkd are as defined in Equation 2.2-5.

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

Ag, = 1.14 x 105(218Fj)0Fj, (2.3-2) 4 where:

1.14 x 105 106 hx 10 3

hx g hr 1

2-17 Rev. 1

Page 24 of 164 21 Adult fish consumptien rate from Table E-5 of Regulatory Guide 1.109. Revision I, kg/yr; BF9 = Bicaccumulation factor for radionuclide "1" in fish from Table A-1 of Regulatory Guide 1.109. Revision 1, pC1/kg per pC1/1; 0Ft , = Dose conversion factor for radionuclide "i" for adults for a particular organ t from Table E-11 of Regulatory Guide 1.109 Revision 1, mres/pC1.

?

The potable water pathway does not exist either witnin Lake Robinson 5 or downstream of the Lake Robinson dam. Therefore, the potable water term was excluded from the calculation of Ag, values. Table 2.3-1 presents Ag , values for an adult at H8R.

I As noted in Section 2.2.2, steam generator blowdown is continuously released from H8R. The dose from continuous release: will be calcu-lated using the following equation:

0,g={ {4,g ke ike ge C F RM where:

0,c = The cumulative dose conuittment to the total bcdy or any organ t, from liquid effluents for continuous releases, mrem; i

the = The length of time of continuous release period k over which Cgge and Fke are averaged for all continuous liquid releases, hours; i

Cgge = The average concentration of radionuclide "i" in undiluted liquid effluent during continuous release period k from any continuous liquid release, uC1/ml; j

2-18 Rev. 1

Pags 25 of 164 l l

F ke = The near-field average dilution factor for Cike during contin-uous liquid effluent release k. Cefined as the ratio of the volume of undiluted liquid wasta released to the product of the .

dilution volume from the site discharge structure to unrestricted receiving water times 1.0. (1.0 is the site-specific applicable factor for the mixing effect of the HBR discharge structure as defined in NUREG-0133, October 1978).

V i kc ke V x 1.C kd l Where V ke and Vkd are, as defined in Equation 2.2-5, only now distin-guished for continuous releases.

The sum of the cumulative dose from all batch and continuous releases ,

for a quarter are compared to one half the design objectives for total body and any organ. The su;n of the cumulative doses from all batch and continuous releases for a calendar year are compared to the design objective doses. The following relationships should hold for H8R to show compliance with Technical Specification 3.9.2.1 of the technical specifications for H.8. Robinson Unit 2.

For the e.alendar quarter.

O,1 1.5 mrem total body (2.3-4)

O. 1 5 mrem any organ (2.3-5)

For the calendar year.

O, 5 3 mrem total body (2.3-6) 0, 310 mrem any organ (2.3-7) where:

2-19 Rev. 1

Pcg2 26 of 164 Or = Cumulative total dose to any organ r or the total body from continuous and batch releases, mres;

=O rb + O rc ,

The quarterly limits given above represent one half the annual design objective of Section II.A of Appendix ! of 10CFR50. If any of the limits, in Expressions 2.3-4 through 2.3-7 are exceeded, a special report pursuant to Technical Specification 6.9.3.2 must be filed with the NRC. This report complies with Scction IV.A. of Appendix I of i 10CRF50.

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

) Projected dose will be calculated as follows:

31 (DA) + (08)

PO = +M (2.3-8)

(TE) where:

PO = projected doses in mrem.

0A = dose accumulated during current quarter in mrem.

08 = projected dose from this release.

I TE = time elapsed in quarter in days.

TA = time in quarter in days.

M = safety margin in mrom.

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

2-20 Rev. 2

Pagm 27 of 164 8

(left blank intentionally).

2-21 cev, I

Pag 2 28 c' 164 TABLE 2.3-1 A,

j VALUES FOR THE ADULT FOR THE H.B. ROBINSON STEAM ELECTRIC PLANT i (MREM /HR PER MICRO-C1/ML)

Nuclide Bone Liver T.Bady Thyroid Kidney jgygg GI-LLI H-3 0.00E-01 2.26E 01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.25E-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 4.07E+02 4.07E 02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E +02 P-32 4.62E+07 2.87E 06 1.79E 06 0.00E-01 0.00E-01 0.00E-01 5.19E 06 Cr-51 0.00E-01 0.00E+01 1.27E 00 7.61E-01 2.81E-01 1.69E 00 3.20E 02 Mn-54 0.00E-01 4.38E 03 8.35E 02 0.00E-01 1.30E 03 0.00E-01 1.34E 04 Mn-56 0.00E+01 1.10E 02 1.95E 01 0.~00E-01 1.40E 02 0.00E-01 3.51E 03 Fe-55 6.58E 02 4.55E 02 1.06E 02 0.00E-01 0.00E-01 2.54E 02 2.61E 02 Fe-59 1.04E 03 2.44E 03 9.36E 02 0.00E-01 0.00E-01 6.82E 02 8.14E 03 Co-58 0.00E-01 8.92E 01 2.00E 02 0.00E-01 0.00E-01 0.00E-01 1.81E 03 Co-60 0.00E-01 2.56E 02 5.65E 02 0.00E-01 0.00E-01 0.00E-01 4.81E 03 Ni-63 3.11E 04 2.16E 03 1.04E 03 0.00E-01 0.00E-01 0.00E-01 4.50E 02 Ni-65 1.26E 02 1.64E 01 7.49E 00 0.00E-01 0.00E-01 0.00E-01 4.17E 02 Cu-64 0.00E-01 9.97E 00 4.68E 00 0.00E-01 2.51E 01 0.00E-01' 8.50E 02 Zn-65 2.32E 04 7.37E 04 3.33E 04 0.00E-01 4.93E 04 0.00E-01 4.64E 04 Zn-69 4.93E 01 9.43E 01 6.56E 00 0.00E-01 6.13 01 0.00E-01 1.42E 01 B r-83 0.00E-01 0.00E-01 4.04E 01 0.00E-01 0.00E-01 0.00E-01 5.8?E 01 B r-84 0.00E-01 0.00E-01 5.24E.01 0.00E-01 0.00E-01 0.00E-01 4.11E-04 i B r-85 0.00E-01 0.00E-01 2.15E 00 0.00E-01 0,00E-01, 0.00E-01 1.01E-15 Rb-86 0.00E-01 1.01E 05 4.71E 04 0.00E-01 0.00E-01 0.00E-01 1.99E 04 Rb-88 0.00E-01 2.90E 02 1.54E 02 0.00E-01 0.00E-01 0.00E-01 4.00E-09 Rb-89 0.00E-01 1.92E 02 1.35E 02 0.00E-01 0.00E-01 0.00E-01 1.12E-11 6

Sr-89 2.21E 04 0.00E-01 6.35E 02 0.00E-01 0.00E-01 0.00E-01 3.55E 03 Sr-90 5.44E 05 0.00E-01 1.'34E 05 0.00E-01 0.00E-01 0.00E-01 1.57E 04 Sr-91 4.07E 02 0.00E-01 1.64E 01 0.00E-01 0.00E-01 0.00E-01 1.94E 03 Sr-92 1.54E 02 0.00E-01 6.68E 00 0.00E-01 0.00E-01 0.00E-01 3.06E 03 Y-90 5.76E-01 0.00E-01 1.54E-02 0.00E-01 0.00E-01 0.00E-01 6.10E 03 Y-91M 5.44E-03 0.00E-01 2.11E-04 0.00E-01 0.00E-01 0.00E-01 1.60E-02 Y-91 8.44E 00 0.00E-01 2.26E-01 0.00E-01 0.00E-01 0.00E-01 4.64E 03

'Y-92 5.06E-02 0.00E-01 1.48E-03 0.00E-01 0.00E-01 0.00E-01 8.86E 02 j

Y-93 1.60E-01 0.00E-01 4.43E-03 0.00E-01 0.00E-01 0.00E-01 5.09E 03 l 3 Zr-95 2.40E-01 7.70E-02 5.21E-02 0.00E-01 1.21E-01 0.00E-01 2.44E 02 Zr-97 1.33E-02 2.68E-03 1.22E-03 0.00E-01 4.04E-03 0.00E-01 8.30E 02 Nb-95 4.47E 02 2.48E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06 Mo-99 0.00E-01 1.03E 02 1.96E 01 0.00E-01 2.34E 02 0.00E-01 2.39E 02 4

l 2-22

Pagn 29 fo 164 TABLE 2.3-1 (continued)

Bone Liver T. Body Thyroid Kidney Lung GI-LLI Nuclide 2.51E-02 3.19E-01 0.00E-01 3.31E-01 1.23E-02 1.48E+01 Tc-99M 8.87E-03 1.31E-02 1.29E-01 0.00E-01 2.37E-01 6.72E-03 3.95E-14 Tc-101 9.12E-03 0.00E-01 1.91E+00 0.00E-01 1.69E+01 0.00E-01 5.17E+02 Ru-103 4.43E+00 3.69E-01 0.00E-01 .1.46E-01 0.00E-01 4.76E+00 0.00E-01 2.26E+02 Ru-105 6.58E+01 0.00E-01 3.33E+00 0.00E-01 1.27E+02 0.00E-01 4.26E+03 Ru-106 8.81E-01 8.15E-01 4.84E-01 0.00E-01 1.60E 00 0.00E-01 3.33E 02 Ag-110M Te-125M 2.57E 03 9.30E 02 3.44E 0-4 7.72E 02 1.04E 04 0.00E-01 1.02E 04 Te-127M 6.48E 03 2.32E 03 7.90E 02 1.66E 03 2.63E 04 0.00E-01 2.17E 04 Te-127 1.05E 02 3.78E*01 2.28E 01 7.80E 01 4.29E 02 0.00E-01 8.31E 03 Te-129M 1.10E 04 4.11E 03 1.74E 03 3.78E 03 4.60E 04 0.00E-01 5.54E 04 Te-129 3.01E 01 1.13E 01 7.33E 00 2.31E 01 1.26E 02 0.00E-01 2.27E 01 Te-131M 1.66E 03 8.10E 02 6.75E 02 1.28E 03 8.21E 03 0.00E-01 8.04E 04 Te-131 1.89E 01 7.88E 00 5.96E 00 1.55E 01 8.26E 01 0.00E-01 2.67E 00 Te-132 2.41E 03 1."SE 03 1.47E 03 1.72E 03 1.50E 04 0.0CE-01 7.38E 04 I-130 2.71E 01 8.01E 01 3.16E 01 6.79E 03 1.25E 02 0.00E-01 6.89E 01 I-131 1.49E 02 2.14E 02 1.22E 02 7.00E 04 3.66E 02 0.00E-01 5.64E 01 1-132 7.29E 00 1.95E 01 6.82E 00 6.82E 02 3.11E 01 0.00E-01 3.66E 00 I-133 5.10E 01 8.87E 01 2.70E 01 1.30E 04 1.55E 02 0.00E-01 7.97E 01 1-134 3.81E 00 1.03E 01 3.70E 00 1.79E 02 1.64E 01 0.00E-01 9.01E-03 I-135 1.59E 01 4.17E 01 1.54E 01 2.75E 03 6.68E 01 0.00E-01 4.70E 01 Cs-134 2.98E 05 7.09E.05 5.79E 05 0.00E-01 2.29E 05 7.61E 04 1.24E 04 Cs-136 3.12E 04 1.23E 05 8.86E 04 0.00E-01 6.855 04 9.38E 03 1.40E 04 Cs-137 3.82E 05 5.22E 05 3.42E 05 0.00E-01 1.77E 05 5.89E 04 1.01E 04 Cs-138 2.64E 02 5.22E 02 2.59E 02 0.00E-01 3.84E 02 3.79E+01 2.23E-03 Ba-139 9.29E-01 6.62E-04 2.72E-02 0.00E-01 6.19E-04 3.75E-04 1.65E 00 Ba-140 1.94E 02 2.44E-01 1.27E 01 0.00E-01 8.30E-02 1.40E-01 4.00E 02 Ba-141 4.51E-01 3.41E-04 1.52E-02 0.00E-01 3.17E-04 1.93E-04 2.13E-10 Ba-142 2.04E-01 2.10E 1.28E-02 0.00E-01 1.77E-04 1.19E-04 2.87E-19 La-140 1.50E-01 7.54E-02 1.99E-02 0.00E-01 0.00E-01 0.00E-01 5.54E 03 7.66E-03 3.48E-03 8.68E-04 0.00E-01 0.00E-01 0.00E-01 2.54E 01 La-142 Ce-141 2.24E-02 1.52E-02 1.72E-03 0.00E-01 7.04E-03 0.00E-01 5.79E 01 3.955-03 2.92E 00 3.23E-04 0.00E-01 1.29E-03 0.00E-01 1.09E 02 Ce-143 Ce-144 1.17E 00 4.88E-01 6.27E-02 0.00E-01 2.90E-01 0.00E-01 3.95E 02 Pr-143 5.51E-01 2.21E-01 2.73E-02 0.00E-01 1.27E-01 0.00E-01 2.41E 03 Pr-144 1.80E-03 7.48E-04 9.16E-05 0.00E-01 4.22E-04 0.00E-01 2.59E-10 Nd-147 3.76E-01 4.35E-01 2.60E-02 0.00E-01 2.54E-01 0.00E-01 2.09E 03 W-187 2.96E 02 2.47E 02 8.65E 01 0.00E-01 0.00E-01 0.00E-01 8.10E 04 Np-239 2.85E-02 2.80E-03 1.54E-03 0.00E-01 8.74E-03 0.00E-01 5.75E 02 2-23

Pcg: 30 of 165 (Left blank intentionally).

I i

I l

t .

e I

2-24 Rev. l

Page 31 of 164 l

3.0 GASEQUS EFFLUENTS 3.1~ MONITOR ALARM SETPOINT DETERMINATION This methodology 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 bound-ary exceeds 500 mres/ year to the whole body or exceeds 3000 mrem / year to the skin.

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

3.1.1 SetDoint Based on Conservative Radionuclide Mix (Ground and Mixed Mode Releases Releases through the steam. generator flash tank vent can only occur through this vent when significant primary-to-secondary leakage exists within the steam generators and the plant is operating below 30 percent power and the blowdown is not going through heat recovery. Detection of primary-to-secondary leakage is accomplished most effectively by continuously monitoring the condenser vacuum pump vent (RMS-15). Steam generator blowdown is con-tinuously monitored by RMS-19 as a liquid pathway.

The following method applies to gaseous releases via the plant vent and con-denser vacuum pump vent when determining the high-alarm setpoint for the plant vent gas aonitor (RMS-14) and condenser vacuum pump vent gas monitor (RMS-15),

and the Fuel Handling Basement Exhaust Monitor (RMS-20), using the GALE code during the following operational conditions:

  • Continuous release via the plant vent.
  • Continuous release via the condenser vacuum puma vent.

3-1 Rev. 2

Pcgs 32 of 164 3.1.1.1 Determine the " mix" (noble gas radionuclides and composition) of the gaseous effluent.

Deter, wine Sj, the fraction of the total noble gas radioactivity in the gaseous effluent comprised by noble gas radionuclide "i." for each individual noble gas radionuclide in the gaseous effluent.

Ag Sj ,= , (3.1-1)

Ag bi Aj = The radioactivity of noble gas radionuclide "i" in the gaseous effluent from Table 3.1-1. -

3.1.1.2 Determine the Om, the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent luCi/secl, based upon the whole body exposure limit of 500 mrem / year by:

=

' (3.1-2)

Om (T/7) [j KgS; (X/Q) = The highest calculated annual average relative dis-persion factor for any area at or beyond the unre-stricted area boundary for all sectors (sec/m3 ).

= 8.1 E-5 sec/m3 (Continuous Ground Release) from Table A-1 Appendix A.

r

= 9.9 E-7 sec/m 3 (Continuous Mixed Mode Release) from Table A-10, Appendix A, only with upper wind speed 3 9 mph.

Kj = ' The total whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem /yr/ uC1/m3 ) from Table 3.1-2.

3-2 Rev. 2 l l

[

Prgs 33 of 164 3.1.1.3 Determine 0,, the maximum acceptable release rate of all gas radio-nuclides in the gaseous effluent [uCi/secl, based upon the skin ex-posure limit of 3000 mrem /yr by: .

000 0*

=

(3.1-3)

(T/4)[9[(Lg + 1.1 Mg ) Sy l Lj + 1.1Mg

  • The total skin dcse factor due to emissions from noble gas radionuclide "1" (mres/yr/uC1/m3 ) from Table 3.1-2.

3.1.1.4 Determine Cm , the maximum acceptable total radioactivity concentra-tion of all noble gas radionuclides.In the gaseous effluent [uC1/ccl.

2.12 E-3 0

- Cm

  • F (T,) (SF) (3.1-4)

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

where:

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

= 0.91 for Plant Vent Gas Monitor (RMS-14).

= 0.01 for the Condenser Vacuum Pump Vent Monitor (RMS-15).

= '0.06 for the Fuel Handling Basement Exhaust Monitor (RMS-20).

= 0.01 for the E&RC Building Hood Exhaust Monitor (RMS-22).

3-3 Rev. 2

Pega 34 of 164 F = The maximum acceptable effluent flow rate at the point of release (cfm).

= 60,000 cfm for plant vent.

= 45 cfm for the condenser vacuum pump vent.

= 10,200 cfm for the fuel-handling building.

2.12 E-3 = Unit conversion

"~I"gonstant to convert uCi/sec/cfm to uCi/cc. [min - cc -l SF = An engineering factor used to provide a margin of safety for cumulated measurement uncertainties. = 0. 5 3.1.1.5 Determine CR, the calculated monitor count rate above background at.

tributed to the noble gas radionuclides [cpml, by: l G =

(C,)(E,) (3.1-5) where: l.

E, = Obtained from the applicable effluent monitor efficiency curve located in the Plant Operating Manual, Volume 15 Curve Book. Use the radioactivity concentration "C," to find CR.

3.1.1.6 Determine the hSP, the monitor high-alarm setpoint including back-ground (cpol,by: -

s HSP = CR + background + 3.3 (3.1-6) i 3-4 Rev. 2

Pcg3 35 of 166 where:

3.3 = Statistical variance on the background (Bkg) counting rate quoted at the 99.951 confidence level at a RC time j constant t (minutes). This term is included to prevent inadvertent high alarm trips due to random fluctuations in the monitor background.

3.1.2 Setcoint Based on Sample Analysis Prior to Release, e

The following method applies to gaseous releases when determining tne high.

alarm setpoint with prior sample analysis and using the maximum acceptable effluent flow rate at the point of release. The method applies to the fol-lowing conditions.

  • Batch release of containment purge.

- Batch release of containment pressure relief.

  • Batch release of waste gas decay tanks.
  • Plant vent release.
  • Condenser vacuum pump vent.
  • Fuel handling basement exhaust.

l

  • Environmental and Radiation Control Building Hood Exhaust. l 3.1.2.1 Determine Rt . the noble gas release rate luc 1/secl for radionuclide "i":

Rg = 472 (Cg) (F). (3.1-7) wheret 35 Rev. 2

pcg3 36 of 164 472 = A conversion factor to convert cfm to cc/sec.

C, = The radioactivity concentration of noble gas radio-nuclide "1" from analysis

  • of gaseous effluent (uC1/cc) from the Condenser Vacuum Pump Vent, Plant Vent (stack).

Fuel Hindling Basement Exhaust, and the Environmental &

Radiation Control (E&RC) Building Hood Exhaust.

Containment Purge- **

(uC1/ccj from analysis of Containment Vent) (0.0368) +

(LC1/cci from analysis of Plant Vent) (0.632)

Containment Pressure Relief- **

(uC1/ccj from analysis of Containment Vent) (0.040) +

(uC1/ccj from analysis of Plant Vent) (0.960)

Waste Gas Decay Tanks--

(u'C1/cci from analysis of WGOT) (0.0017) +

(uC1/ccj from analysis of Plant Vent) (0.9983)

Waste Gas Decay Tanks during Containment Purge--

(uCf/cci from analysis of WGDT) (0.0011) + ,

(uC1/cci from analysis of Plant Vent) (0.631) + [

(uC1/cci from analysis of C.V.) (0.368)

NOTES:

  • !f there are no isotopes identified in the sample, the LLO's for Xe-133 and Kr-85 may be used as actual values for the purpose of the setpoint calculation.
    • uct/ccjfrom analysis for CV when RMS-12 is lined up on the CV.

3-6 Rev. 2

Pega 37 of 164 35.000 CFM 0.368 =

Dilution correction factor = (60,000 + 35,000) CFM for C.V. Purge 0.632 =

Oilution correction factor = (60,0 5 0) CFM for Plant Vent during C.V. Purge 2500* CFM 0.040 =

Dilution correction factor = (60,000 + 2500*) CFM for C.V. Pressure Relief 0.960 =

Dilution correction factor = (60,0 + 5 ) CFM for Plant Vent during C.V. Pressure Relief 0.0017 = Dilution correction factor = (60,0 + 0) CFM" for Waste Gas Decay Tank 0.9983 = Oilutioncorrectionfactor=(60,0b+1 CFM for Plant Vent during WGOT Release O.0011 = Dilution correction factor for Waste Gas Decay Tank = lei 0,000 + 0 + 100) CFR during a Continuous C.V. .

Purge and Plant Vent Release I

l 0.631 = 011ution correction factor 60.000 CFM l

for Plant Vent during a = (60,000 + 35,000 + 100) CFM Continuous C.V. Purge

'and Plant Vent Release 0.368 =

Dilution correction fac = (60,000 $5 0 100) CFM tor for Continuous C.V.

Purge during WGOT Release i

3-7 Rev. 2

Pcg3 38 of 164 F = The maximum acceptable effluent flow rate at the point of release (CFM)

= 45 CFM for the condenser

= 60,000 CFM for the plant vent

= 10,200 CFM for the fuel handling basement exhaust

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

'1

= 95.000 CFM for the containment vessel purge plus plant vent ,

I I

= 62,500 CFM for the containment vessel pressure relief I l

= 60,100 CFM for the waste gas decay tank

= 95,100 CFM for the waste gas decay tank during a con- - .

tinuous containment vessel purge I = 35,000 CFM for containment vessel purge or continuous release

  • 2500 CFM.-Refer to Appendix B.4 for additional information i 3.1.2.2 Determine the monitor alarm setpoint based on total body and skin dose rate:
a. Determine dose rate for total body (mrem /yr).

OR T8 * (T/4) gg Kg R g I

  • bO) 38 Rev. 2

Page 39 of 164 where:

X/Q = The highest calculated annual average relative dis-persion factor for any area at or beyond the unre-stricted area boundary for all sectors (sec/m,3) from Appendix A.

= 8.1 E-5 sec/m 3 (continuous ground release) from Table A-1, Appendix A.

=

9.9 E-7 sec/m3 (continuous mixed mcde release) from Table A-10, Appendix A, only with upper wind speeds of 3 9 mph.

= 5.1 E-5 sec/m3 (Batch Ground Release) from Table A-7, Appendix A.

= 2.9 E-6 sac /m 3 (Batch Mixed Mode Release) from Table A-16, Appendix A, only with upper wind speeds of 3 9 mph.

Kj = The total whole body dose factor due to gamma emis-sions from noble gas radionuclide "i" 3

(mrem /yr/uCi/m ) from Table 3.1-2.

b. Determine dose rate for skin (mrem /yr).

OR 3g = X/Q It (li+1'1M)Rg i (3.1-9) where:

L + f.1 M = The total skin dose factor for goble gas emission "i" radionuclide (mrem /yr/uCi/m ) from Table _3.1-2 l

l l

l 3-9 Rev. 2 l

Page 40 of 164

c. Determine the noble gas emission Projected Dose Rate Ratio (PORR) for Total Body and Skin.

OR T8 PORR TB

  • 500 (3.1-10)

OR SKIN PORRSKIN

  • 3000 (3.1-11) 500 = The allowable total body dose rate dua to noble gas gamma emissions in mrem /yr.

3000 = The allowable skin dose rate due to noble gas beta emissions in mrem /yr.

d. Determine the maximum monitor setpoint concentration (uCi/cc) for total body and skin.

(I 9Ci)

Maximum Monitor Total Body Setpoint = (PORRTB) *

(3.1-12)

(I,C1)

Maximum Monitor Skin Setpoint *

= (FORRSKIN)

(3.1-13) j where:

l

! SF = An engineering factor used to provide a margin of safety for cumulative uncertainties of measurements.

s

= .5 3-10 Rev. 2

Pegs 41,of 164 T, = Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the, site boundary limit is not exceeded due to si-multaneous releases from several pathways.

= 0.91 for the Plant Vent Gas Monitor (RMS-14).

= 0.01 for the Condenser Vacuum Pump Vent Monitor (RMS-15).

= 0.06 for the Fuel Handling Basement Exhaust Monitor (RMS-20).

= 0.01 for the E&RC Building Hood Exhaust Monitor (RMS-22).

= 0.81 for C.V. releases via R-11 and R-12 IThis indicates 0.81 of 10CFR20 limits for Containment releases and is also monitored by R-14.

0.91 = 0.81 + 0.'10 (Normal Plant Releases)]

e. Determine the maximum monitor setpoint (CPM) for total body (St ) and skin (53 ).

(Maximum total body setpoint in uCi/cc) (monitor efficiency) +

Skg + 3.3 (3.1-14)

(Maximum skin setpoint in uC1/cc) (monitor efficiency) + 8kg +

3.3\ 2r % (3.1-15)

P 3-11 Rev. 2

Page 42 of 164 Monitor efficiency = Obtained from the applicable effluent monitor efficiency curve located in the Plant Operating Manual, Volume 15, Curve ,

Book. Use the radioactivity concentra- I tion (uCl/cc) to find (CPM).

Bkg = The monitor background.

3.3 Bkg = Statistical variance on the background 2r (8kg) count rate (CPM) at a 9S.95% con-fidence ' level at a RC time constant t (minutes). This factor is included to prevent inadvertent high/ trip alarms due to random counts on the monitor,

f. Determine the actual gaseous monitor setpoint:

The setpoints that were determined based on the dose rate limits to the total body (S ) tand to the skin (S ) are 3

com-pared and the lesser value is used as the actual setpoint.

3-12 Rev. 2

Page 43 of 164 TABLE 3.1-1 i GASECUS SOURCE TERMS

  • condenser vacuum contain nr purge plant vent Aelease I puma vent 2 or Pressure Relief Gas Cecay ?snus 3 Radionuclide A; (Ci/yr) s; A. (Ci/yr) S; A. (Ci/yr) 5 A. (Ci/yr) S.

<r-85e 2.0E0 5.26E-2 I .0E0 4.35E-2 0.00 0.00 0.00 0.00

<r-85 0.00 O.00 0.00 0.00 0.00 0.00 1.6E2 8.00E-l

<r-87 1.0E0 2.63E-2 0.00 0.00 0.00 0.00 0.00 0.00

<r-88 3.0E0 7.89E-2 2.0E0 8.70E-2 1.0E0 2.90E-3 0.00 0.00 xe-131e 0.00 0.00 0.00 0.00 1.0E0 2.90E-3 0.0E0 4.5CE-2 xe-133e 0.00 0.00 0.00 0.00 4.0E0 1.16E-2 0.00 0.00 Xe-133 2.8El 7.37E-1 1.8E+1 7.83E-l 3.1E2 8.99E-I 3.IE1 1.55E-l re-135 4.0E0 1.05E-I 2.0E0 8.70E-2 4.0E0 t.i6E-2 0.00 0.00 l

Ar-41 0.00 0.00 0.00 0.00 2.5El 7.25E-2 0.00 0.00 TOTAL 3.SE I 2.3E1 3.45E2 2.0E2

  • Source terms are based upon GALE Code and not actual releases from the evaluation of H.B. Robinson Unit 2 to demonstrate conformance to the design objectives of 10CFR50, Appendix I, Table 2-4. These values are only for rou-tine releases and not for a complete inventory of gases in an emergency.

I These values are used to determine the monitor alarm setpoints for the Plant Vent Gas Monitor (RMS-14).

2These values are used to determine the monitor alarm setpoint for the Condenser Vacuus Pump Vent Monitor (RMS-15).

3These values are used to determine the monitor alarm setcoint for the Fuel Handling Basement Exhaust Monitor (RMS-20).

s 3-13 Rev. 2

Page 44 of 164 TA8LE 3.1-2 DOSE FACTORS AND CONSTANTS

  • Total Whole Body Total Skin Dose Factor Dose Factor (Kg) (Lj + 1.1 Mj)3 Radionuclide (mrem /yr/uCi/m3 ) mrem /yr/uC1/m )

Kr-83m ,

7.56E-2 2.12E1 Kr-85m 1.17E3 2.81E3 Kr-85 1,61El 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 9.15El 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 Xe-139 0.00 0.00 Ar-41 8.84E3 1.29E4

3-14 Rev. 2

Page 45 of 166 3.2 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, the possibility exists that the setpoints could be ex-ceeded and yet,10CFR20 limits may actually be met. Therefore, the following methodology has been .provided in the event that if the alarm trip setpoints are exceeded, a determination may be made as to whether the actual releases have exceeded 10CFR20.

The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mrem / year to the total body and 3000 mres/ year to the skin.

Based upon NUREG 0133, the following are used to show compliance witn 10CFR20.

[4 Kj [ (X/Q), h jy + (X/Q), h9,1 1 500 mrem /yr (3.2-1)

(3.2-2)

[9(Lj+1.1M)[(X/Q)hgy+(X/Q)h,]$3000 j g mrem /yr where:

(X/Q), = Annual average relativa dilution for plant vent releases at the site boundary, sec/m 3.

= From Table A-1 for ground level releases.

= From Table A-10 for mixed mode releases only with upper wind speed of > 9 mph.

(T[6), = Annual average relative dilution for condenser vacuum pump vent releases at the site boundary, sec/m3 .

= From Table A-1 for ground level releases.

3-15 .

Rev. 2

Page 46 of 164 K j = The total body dose factor due to gamma emissions

> for noble gas radionuclide "1," mrem / year per uCi/m3 ,

L9 = The skin dose factor due to beta emissions for noble gas radionuclide "1," mrem / year per uCt/m3 ,

Mj ,

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

1.1 = The ratio of the tissue to air absorption coeffi-cients over the energy range of the photon of in-terest, mrem /arad (reference NUREG 0133, October 1978).

hj, = The release rate of noble gas radionuclide "i" in gaseous effluents from the condenser vacuum pump vent uC1/sec.

hjy = The release rate of noble gas radionuclide "i" in gaseous effluents from the plant vent uCi/sec.

The determination of limiting location for implementation of 10CFR20 for noble i gases is a function of the radionuclide mix, release rate, and the meteoro-logy. For the most limiting location, the radionuclide mix will be based on j sample analysis of the effluent gases.

The X/Q value utilized in the equations for implementation of 10CFR20 is based upon the maximum long-term annual average (X/Q) in the unrestricted area.

Table 3.2-2 presents the distances from HBR to the nearest area for each of l the 16 sectors as well as to the nearest residence, vegetable garden, cow, goat, and beef animal. Long-term annual average (X/Q) values for the HBR l

release points to the special locations in Table 3.2-2 are presented in Appen-dix A. A description of their derivation is also provided in this appendix.

i 3-16 Rev. 2

Page 47 of 164 To select the limiting location, the highest annual average X/Q value for the ground level releases and the mixed mode releases was used. Since mixed made releases may not necessarily- decrease with distance (i.e., the site boundary may not have the highest X/Q value), long-term annual average (X/Q) values, calculated at the midpoint of 10 standard distances as given in Appendix A were also considered. For HBR, mixed mode release X/Q values decrease with distance for all directions except the WNW, NW, and NNW so that the maximum site boundary X/Q is usually greater at ths: site boundary than at distances greater than the site boundary. In addition, the maximum site boundary X/Q for both the ground level and mixed mode releases occurs at the SSE site boun-dary. Therefore, the limiting location for implementation of 10CFR20 for noble gases is the SSE site boundary.

Values for Kj, Lj, and Mj, which were used in the determination of the limit-ing location and which are to be used by HBR in Expressions 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 B-1 of NRC Regulatory Guide 1.109, Revision 1. The values have been' multiplied by 1.0 E6 to convert picocuries to microcuries for use in Expressions 3.2-1 and 3.2-2.

3.2.2 Radioiodines, Particulates, and Tritium The dose rate in an unrestricted area resulting from the release of radio-iodines, 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.

[j P j [(X[6),Q,y+(X/Q),Qj,1 1 M00 mrem /yr (3.2-3) l 3-17 Rev. 2

Page 48 of 164 Qy = Release rate of radionuclide "i" from the plant vent, 9

uC1/sec.

Qci.

= Release rate of radionuclide "i" from the condenser vacuum pump vent..aCi/sec.

(X/Q)y = Annual average relative dilution for plant vent releases at the site boundary, sec/m 3, (X/Q), = Annual average relative dilution for condenser vacuum pump vent releases at the site boundary, sec/m3 ,

1 P

j

= The dose parameter for Iodine-131, Iodine-133, tritium, I and all radionuclides in particulate form with half-lives greater than 8 days for the inhalation pathway only in the most restrictive sector in mrem /yr per l

uCi/m3 . The dose factor is based on the most~restric-tive group (child) and most restrictive organ (thyroid) at the SITE BOUNDARY (see Table 3.3-18).

where:

In the calculation to show compliance with 10CFR20, only the inhalation is considered. A description of the methodology used in calculating the Pi values is presented in Appendix 8. Compliance with 10CFR20 is achieved if the dose rate via inhalation pathway to a child is 5 1500 mrem / year.

l l

s l

l 3-18 Rev. 2 l

Page 49 of 164 TABLE 3.2-1 RELEASES FROM H.8. R081NSON UNIT NO. 2*

(Ci/yr)

Condenser Vacuum Plant Vent Pump Vent Isotope (Qv) (0.) Total Kr-85m 2.0E0 1.0E0 3.0E0 Kr-85 1.6E2 0.00 1.6E2 Kr-87 1.0E0 0.00 1.0E0 Kr-88 4.0E0 2.0E0 6.0E0 Xe-131m 1.0E1 0.00 1.0E1 Xe-133m 4.0E0 0.00 4.0E0 Xe-133 3.7E2 1.8E1 3.9E2 Xe-135 8.0E0 2.0E0 1.0E1 I-131 3.6E-2 2.3E-2 5.9E-2 I-133 5.4E-2 3.4E-2 9.8E-2 Mn-54 4.7E-3 0.00 4.7E-3 Fe-59. 1.6E-3 0.00 1.6E-3 Co-58 1.6E-2 0.00 1.6E-2 Co-60 7.3E-3 0.00 7.3E-3 Sr-89 3.4E-4 0.00 3.4E-4 Sr-90 6.3E-5 D.00 6.3E-5 Cs-134 4.7E-3 0.00 4.7E-3 Cs-137 7.8E-3 0.00 7.8E-3

  • Calculations based upon GALE Code and do not reflect actual release data from the Evaluation Comformance to the Design Objectives of 10CFR50, Appen-dix !. These values are only for routine releases and not for a complete in-ventory of gases in ah emergency.

l 3-19 Rev. 2 l

Page 50 of 164 TABLE 3.2-2 DISTANCE TO SPECIAL LOCATIONS FOR THE H.B. ROBINSON PLANT (MILES)

Site Milk Milk Meat Nearest Nearest Sector Boundary Cow Goat Animal Resident Garden _

NNE 1.26 - -

1.65 1.3 1.4 NE - 1.01 - -

1.16 1.2 1.3 ENE 0.86 - -

2.41 0.9 2.2 E 0.61 4.2 -

3.12 0.8 2.8 ESE 0.50 - -

1.99 0.6 0.6 SE 0.29 - - -

0.3 0.3 SSE 0.26 - - -

0.3 0.3 S 0.28 - -

2.32 0.3 0.4 SSW 0.29 - -

2.08 0.3 0.5 SW 0.36 -

2.5* 2.27 0.4 0.5 WSW 0.36 - -

2.69 0.4 0.6 W 0.50 - -

3.97 0.6 0.6 l

WNW 0.55 - -

4.07 0.7 0.9 i NW l.23 - -

1.60 1.3 1.3 NNW l.89 - -

2.84 2.9 3.0 N 1.94 - -

2.93 2.9 2.9

  • Milk is not presently used for human consumption.

i 3-20 Rev. 2

Page 51 of 164

. TABLE 3.2-3 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS

  • Total Body Skin Gamma Air Beta Air Dose Factor Oose Factor

~

Dose Factor Oose Factor Kj Lj Mg Ng (mrem /yr (mrem /yr (mrad /yr (mrad /yr Radionuclide , per uCi/m3 ) per uC1/m3 ) per uCi/m3 ) per uCi/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+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+33 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

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

3-21 Rev. 2

Page 52 of 164 TABLE 3.2-4 -

I Pj VALUES FOR AN INFANT FOR THE H.B. ROBINSON UNIT NO. 2*  ;

Isotope 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 6.32E5 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 1.16E5 1.04E9 1.24E8 Te-129m 1.68E6 2.86E7 1.40E9 1.68E8 l

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 1-135 6.96E5 3.67E6 2.27E7 2.68E7

!

  • Units are arem/yr 3 for H-3 and the inhalation pathway and mrem /yr per uC1/sec per for myrthe uCi/m food and ground plane pathways.

l I

(

i l

3-22 Rev. 2

,- . -- .---,..-..-------O - -- - _

Page 53 of 164 3.3 COMPT.IANCE WITH 10CRF50 (GASE0US) 3.3.1 Noble Gases 3.3.1.1 Cumulation of Dose:

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 equa-tions:

D y =3.17x10-0[z Mj ( (X/Q)y 44, + (X/q), q ,q + (X/Q), Qje l (3.3-1)

D g =3.17x10~0[g N g [ (X/Q),, 49y + (X/q)y igy + (X/Q), 49 ,] (3.3-2) where:

D y

= The air dose from gamma radiation, mrad.

D = The air dose from beta radiation, mrad.

a Mg = The air dose factor due to gamma emissions for each identified noble gas radionuclide "i," mrad / year per 3

uC1/m .

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

(X76), = The annual average dilution for areas at or beyond the unrestricted area boundary for long-term plant vent

, releases (> 500 hrs / year), sec/m3 ,

= From Table A-1 for ground level releases.

j

! 3-23 Rev. 2

Page 56 of 164

= From Table A-10 for mixed mode releases to be used only with upper wind speeds > 9 mph.

(X/q)y = The dilution for areas at or beyond the unrestricted area boundary for short-term vent releases ($ 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year), sec/m3 .

, = From Table A-7 for ground level releases.

= From Table A-16 for mixed mode releases.

(X/Q), = Annual average relative dilution for condenser vacuum pump vent releases at the site boundary, (> 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year), sec/m3 .

= From Table A-1 for ground level releases; gjy = The average release of noble gas radionuclide "i" in gaseous releases for short-term plant releases (5 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year),uCi; l

Q,4

= The average release of noble gas radionuclide "i" in gaseous releases for long-term condenser vacuum pump vent releases (> 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />'/ year), act; i

Q 4y = The average release of noble gas radionuclide "i" in l

gaseous effluents for long-term vent releases (> 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year),uCi; 3.17 x id-8 = The inverse of the number of seconds in a year l (sec/ year)-I.

1 At HBR the limiting location is 0.26 miles SSE. Based upon the tables pre-sented in Appendix A, substitution of the short-term X/Q value into Equation 3.3-1 yields lower dose value than the long-term X/Q values been used. In order to be conservative, for purposes of this document only, long-term annual 3-24 Rev. 2

Page 55 of 1%

average (X/Q) values will be used. Should the calculated doses exceed 10CFR50 limits, recalculation of doses may be performed using short-term X/Q values for batch releases.

To select the limiting location, the highest annual average X/Q value for ground level and mixed mode releases and the highest short-term X/Q value for ground level and mixed mode releases were considered. Since mixed mode re-leases may increase and then decrease with distance' (i.e., the site boundary may not have the highest X/Q value), long-term X/Q values were calculated at the midpoint of 10 standard distances as given in Appendix A. The calculated values decreased with the distance for all but the WNW, NW, and NNW sectors.

The values for these sectors were not found to be limiting such that the maxi- .

mun site boundary X/Q for both long-term and short-term ground level and mixed mode releases occurred at the SSE site boundary. The limiting location for l

implementation of 10CFR20 for noble gases is the SSE site boundary.

Values for Mj and Nj which are utilized in the calculation of the gama air

and beta air doses in Equation 3.3-1 to show compliance with 10CFR50 were pre-sented in Table 3.2-3. These values originate from NUREG 0472, Revision 0, and were taken from Table B-1 of the NRC Regulatory Guide 1.109, Revision 1.

The values have been multiplied by 1.0 E6 to convert from picacuries to micro-curies.

The following relationship should hold for HBR to show compliance with HBR's Technical Specification 3.9.4.1.

For the calendar quarter:

l 0, 5 5 mrad (3.3-3)

Og 1 10 mrad (3.3-4) l i

l l

3-25 Rev. 2

- - _ _ . -- 1 __ _ _ _ - _ _ _ _

Page 56 of 164 For the calendar year:

0, 1 10 mrad (3.3-5) 035 20 mrad (3.3-6)

The quarterly limits given abova represent one-half of the annual design ob-jectives of Section I1.8.1 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 6.9.4.a 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 per 31 days. These projections will include a safety margin based upon expec-ted operational conditions which will take into consideration both planned and unplanned releases.

Projected dose will be calculated as follows:

PO = + (08) +M (3.3-7) 31(DA}E)

(

where:

l PO = Projected doses in mrem.

l 1

OA = Dose accumulated during current quarter in mrem.

~

08 = Projected dose from this release.

TE = Time elapsed in quarter in days.

TA = Time in quarter in days.

M = Safety margin in mrem.

3-26 Rev. 2

Page 57 of 164 If the projected doses exceed 0.6 mrad for gama radiation or 1.3 mrad for beta radiation when averaged over a calendar quarter, the ventilation exhaust treatment system will be operated to reduce releases of radioactive materials.

3.3.2 Radiciodine and Particulates 3.3.2.1 Cumulation of DosesSection II.C of Appendix I of 10CFR50 limits the release of radiciodines and radioactive material in particulate form from each reactor such that estimated dose or dose comitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. Based upon NUREG 0133, the dose to an organ of an individual from radioiodines, ' tritium, and particulates with half-lives > 8 days in gaseous effluents released to unrestricted areas.can be determined by the following equation:

0, = 3.17 x 10-8 [g R [ (x/Q)y Q,y + (x/Q), Q,,] +

(R 9 + R+R9 $ +R$) ((DM),Qjy + (0/q)y q,y + (0/Q), Q4 ,] + (3.3-8)

B M V G s

+R +R (R T g T B

T g

+RT) y I(*/0)v OTV + (*/9)v 4TV + IX/0)e OTe!

t where:

Or ,= Dose to any organ t from radioiodines and particulates, mrem. ,

s 3-27 Rev. 2

,~

-,,--,,g-- , n-- --

y, m - - m .-,nu ,n -

Page 58 of 164 3.17 x 10-8 = The inverse of the number of seconds in a year, (sec/ year)-1

= Annual average relative concentration for plant vent (X/Q),

releases (> 500 hrs /yr) sec/m3 .

From Table A-l for ground level releases.

~

=

= From Table A-10 for mixed mode releases only to be used, with wind speeds > 9 mph.

(X[6), = Annual average dilution for condenser vacuum pump vent releases (> 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> /yr) sec/m3 .

4

= From Table A-1 for ground level releases.

(576)y = Annual average deposition factor for plant vont releases

(> 500 hrs /yr) m-2,

= From Table A-3 for ground level releases.

t

= From Table A-12 for mixed mode releases only to be used l

with upper wir.d speeds > 9 mph.

(0/q)y = Relative depcIttion factor for short-term plant vent l releases ($ 500 hrs /yr), m-2 l = From Table A-9 for ground level releases.

= From Table A-18 for mixed mode releases only to 6e used s

with upper wind speeds > 9 mph.

l t

(0/Q), = Annual average relative deposition factor for condenser vacuum pump vent releases (> 500 hrs / yr), m-2,

= From Table A-3 for ground level releases.

~

3-28 Rev. 2 i

Page 59 of 164 Q,9

= Release of radionuclide "i" in gaseous effluents for long-term condenser vacuum pump vent releases (> 500 hrs /yr),uCi.

Q'9y

= Release of radionuclide "i" in gaseous effluents for long-term plant vent releases (> 500 hrs /yr), uCi.

qgy = Release of radionuclide "i" in gaseous effluents for short-term plant vent releases (< 500 hrs /yr), uCi.

R 9

= 00se factor for an organ for radionuclide "i" for the G

ground plane exposure pathway, mrem /yr per uCi/sec per m -2 R

9

= Dose factor for an organ for radionuclide "i" for the inhalation pathway, mrem /yr per uC1/m3 .

Ri = Dose factor for an organ for radionuclida "i" for the vegetable pathway, mrem /yr per uCi/m-2, R

Ty

= Dose factor for an organ for tritium for the vegetable pathway, mrem /yr per uCi/m,.

RT

= Dose factor for an organ for tritium for the inhalation pathway, mrem /yr per uCi/m3 ,

QTV

= Release of tritium in gaseous effluents for long-term vent releases (> 500 hrs /yr), uC1.

l R, = ,0ose factor for an organ for radionuclide "i" for the milk exposure pathway, mrem /yruCi/sec/m2 ,

R = Dose factor for an organ for tritium for the milk path-T M way, mrem /yr/uCi/m3 ,

3-29 Rev. 2 !

Page 60 of .164 R

T

= Oose factor for an organ for tritium for the meat path-B way, mrem /yr/uC1/m3 . -

R- = Dose factor for an organ for radionuclide "i" for the 9

8 meat exposure pathway, mrem /yr/uCi/sec/m2 ,

= Release of tritium in gaseous effluents for long-term Qe T condenser vacuum pump releases (> 500 hrs / yr), uCi.

qq = Release of tritium in gaseous effluents for short-term plant vent releases (< 500 hrs /yr), uC1.

To show compliance with 10CFR50, Equation 3.3-8 is evaluated at the limiting pathway location. At HBR this location is the vegetable garden 0.3 miles in the SSE sector. The critical receptor is a child. Substitution of the appro-priate X/Q and 0/Q values from tables in Appendix A into Equation 3.3 8 would yield an equation with the short-term X/Q and 0/Q values being less than the long-term values. Therefore, for this document, only long-term annual X/Q and 0/Q values (i.e., more conservative values) are used. ,

The determination of a limiting location for implementation of 10CFR50 for radioiodines and particulates is a function of:

1. Radionuclide mix and isotopic release
2. Meteorology
3. Exposure pathway
4. Receptor's age In the determination of the limiting location, the radionuclide mix of radio-1 iodines and particulates was based upon the source terms calculated using the GALE Code. This mig is presented in Table 3.2-1 as a function of release point. The only source of short-term releases from the plant vent is contain-ment purges.

In the determination of the limiting location, all of the exposure pathways, as presented in Table 3.2-2, were evaluated. These include cow milk, goat i

3-30 Rev. 2

Page 61 of 164 milk, beef and vegetable ingestion, and inhalation and ground plane expo-sure. An infant was assumed to be present at all milk pathway locations. A

' child was assumed to be present at all vegetable garden and beef animal locations. The ground plane exposure pathway was r.ot considered a viable pathway for an infant. Naturally, the inhalation pathway was present everywhere an individual was present. HBR Technical Specification 4.20.2.1 requires that a land-use census survey be conducted on an annual basis. The age groupings 'at the various receptor locations are also determined during this survey; a new limiting location and receptor age group can result.

For the determination of the limiting location, the highest 0/Q values for the ,

vegetable garden, cow milk, and goat milk pathways were selected. The thyroid dose was calculated at each of these locations using the radionuclide mix and releases of Table 3.2-1. Based upon these calculations, it was determined that the limiting receptor pathway is the vegetable / child pathway.

In the determination of the limiting location, annual average 0/Q and X/Q values are used. A description of the derivation of the various X/Q and 0/Q values is presented in Appendix A.

Short-term and long-term X/Q and 0/Q values for ground level releases and for long-term mixed made releases are provided in tables in Appendix A. They may i be utilized if an additional special location arises different from those presented in the special locations of Table 3.2-2.

Tables 3.3-1 through 3.3-19 present Rj values for the total body, GI-tract, bone, liver , kidney, thyroid, and lung organs for the ground plane, inhala-l 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 using a grazing period of eight months. A description of the methodology is presented in Appendix B.

[

The following relationship should hold for HBR to shew compliance with H8R l Technical Specification 3.9.5.1.

1 l

3-31 Rev. 2 l

Page 62 of 164 ,

For the calendar quarter:

O,1 7.5 mrem (3.3-9) 9 For the calendar year:

0, 1 15 mrem (3.3-10)

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 3.3-9 or 3.3-10 are exceeded, a special report pursuant to Technical Specification 6.9.4.a 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 radioiadines and particulate effluents will be projected once per 31 days. These projections will include a safety margin based upon expected operational conditions which will~ take into consideration both planned and unplanned releases.

Projected dose will be calculated as follows:

PO =

31(DAp~E)p (08) + M (3.3-11)

(

where:

PD = Projected doses in mrem.

DA = Dose accumulated during current quarter in mrem.

08 = Projected dose from this release.

TE = Time elapsed in quarter in days.

TA = Time in quarter in days.

M = Safety margin in mrem.

3-32 Rev. 2

Page 63 of 164 If the projected doses exceed 1.0 mrem to any organ when averaged over a calendar quarter, the ventilation exhaust treatment system will be operated to reduce releases of radioactive materials.

1 L

i i

i 3-33 Rev. 2

Pega 64 of 164 TAati 3.3-1 R VALIES FOR T)E H.8. ROBINSGI STEA14 ELECTRIC PLANTe (Reference Regulatory Guide 1.1091 RADMAY a Ground Nuclide T. Body Gl-Trect Bone Liver Kidney Thyroid Lg Sicin Cc-51 4.66E 06 4.66E 06 4.66E 06 4.66E 06 4.66E 06 4.66E 06 4.66E Cd 5.5tE 06 Mn-54 1.34E 09 l.34E 09 1.34E 09 1.34E 09 f.34E 09 1.34E 09 l.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 4.44 09 Co-60 2.15E 10 2.15E to 2.15E 10 2.15E 10 2.15E 10 2.15E to 2.15E to 2.52E 10 Zn-65 7.49E 06 7.49E 08 7.49E 08 7.49E 08 7.49E 08 7.49E 08 7.49E 08 8.61E 08 db-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 f-91 1.08E 06 1.08E 06, 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.22E 06 Zr-95 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.89E 08 NO-95 1.36E 08 f.36E 08 I.36E 08 1.36E 08 f.36E 08 1.36E 08 1.36E 08 1.60E 08 Ru-103 f.09E 08 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.27E 08 Ru-IO6 4.19E 08 4.19E 08 4.19E 08 4.19E 08 4.19E 08 4.19E 08 4.19E 38 5.03E 08 Ag-110M 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 4.06E 09 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 l-l31 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 f.72E 07 1.72E 07 2.09E 07 l-132 1.24E 06 1.24E 06 1.24E 06 1.24E 06 t.24E 06 1.24E 06 f.24E 06 1.46E 06 l-133 2.47E 06 2.47E 06 2.47E 06 2.47E 06 2.47E 06 2.47E 06 2.47E 06 3.00E 06 1-135 2.56E 06 2.56E 06 2.56E 06 2.56E 06 2.56E 06 2.56E 06 2.56E 06 2.99E 06 Cs-134 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E,09 6.82E 09 6.82E 09 7.96E 09, Cs-136 1.49E 08 1.49E 08 1.49E 08 I.49E 08 I.49E 08 f.49E 08 I.49E 08 1.69E 08 Cs-137 1.03E to 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E to 1.03E to I .20E to Ba-140 2.0$E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.0$E 07 2.05E 07 2.34E 07 Co-141 1.36E 07 f.36E 07 1.36E 07 1.36E 07 I.36E 07 1.36E 07 1.36E 07 1.53E 07 Co-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 s

2

'81 values in units of scom/yr per micro-Cl/m' for innalation and tritium, and in units of S mree/yr per micro-CI/sec for all others. Reference Regulatory Guide 1.109 ,

6 3-34 Rev. 2

Page 65 of 164 TABLE 3.3-2 R VALES FOR Tif H.8. ROBINSON STEAM ELECTRIC PUNT

  • l (Ref erence Regulatory Guide I .109) parwwAy a veget AGE Grot;P = Adutt Muclide T. Body GI-Tract g Liver Kidney Thyroid g Skin H-3 2.28F 03 2.28E 03 0.00E 01 2.2SE 03 2.2SE 03 2.28E 03 2.2SE 03 ;2.28E 03 P-32 5.91E 07 f.72E 08 1.53E 09 9.51E 07 0.00E 01 0.00F 01 0.00E 01 0.00E 01 Cr-51 4.60E 04 1.I6E 07 0.00E 01 0.00E 01 1.01E 04 2.75E 04 6.10E 04 0.00E 01 Mn-54 5.83E 07 9.36E 08 0.00E 01 3.05E 08 9.09E 07 0.00E 01 0.00E 01 0.00E 01 Fe-59 1.12E 08 9.75E 08 1.24E 08 2.93E 08 0.00E 01 0.00E 01 8.17E 07 0.00E 01 Co-58 6.71E 07 6.07E 08 0.00E 01 2.99E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Co-60 3.67E 08 3.12E 09 0.00E 01 1.66E 08 0.00E 01 0.00E 01 0.0M 01 0.00E 01 in-65 5.77E 08 8.04E 08 4.01E 08 1.28E 09 8.54E 08 0.00E 01 0.00E 01 0.00E 01 Rb-86 1.03E 08 4.36E 07 0.00E 01 2.2tE 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Se-89 2.87E 08 f.60E 09 1.0M 10 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01

$r-90 1.64E 11 1.93E 10 6.70E 11 0.00E 01 0.00E 01 0.0(mi 01 0.00E 01 0.00E 01 y-91 1.34E 05 2.76E 09 5.01E 06 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Zr-95 2.51E 05 1.17E 09 1.16E 06 3.71E 05 5.82E 05 0.00E 01 0.00E 01 0.00E of Nb-95 4.I9E 04 4.73E 08 1.40E 05 7.79E 04 7.70E 04 0.00E 01 0.00E 01 0.00E 01 Ru-103 2.04E 06 }.53E 08 4.74E 06 0.00E 01 1.8IE of 0.00E 01 0.00E 01 0.00E 01 Ru-106 2.46E 07 1.26E 10 t.94E 08 0.00E 01 3.75E 08 0.00E 01 0.00E 01 0.00E 01 A9-110M 6.23E 06 4.28E 09 1.13E 07 1.05E 07 2.06E 07 0.00E 01 0.00E 01 0.00E 01 Te-127M 6.12E 07 1.68E 09 5.02E 08 1.80E 08 2.04E 09 1.20E 08 0.00E 01 0.00E 01 Te-129N 4.71E 07 1.50E 09 '2.98E 08 1.11E 08 1.24E 09 1.02E 08 0.00E 01 0.00E 01 1-131 6.61E 07 3.04E 07 8.07E 07 1.15E 08 1.98E 08 3.78E 10 0.00E 01 0.00E 01 1-132 5.21E 01 2.80E 01 5.57E 01 1.49E 02 2.37E 02 5.21E 03 0.00E 01 0.00E 01 i-133 1.12E 06 3.30E 06 2.llE 06 3.67E 06 6.40E 06 5.39E 08 0.00E 01 0.00E 01 6-135 3.9tE 04 1.20E 05 4.05E 04 1.06E 05 I.70E 05 7.00E C6 0.00E 01 0.00E 01 Cs-134 8.83E 09 1.89E 08 4.54E 09 1.00E 10 3.49E 09 0.00E 01 1.16E 09 0.00E 01 Cs-136 1.19E 06 1.88E 07 4.19E 07 f.66E 08 9.2tE 07 0.00E 01 f.26E 07 0.00E of Cs-137 5.94E 09 1.76E 08 6.63E 09 9.07E 09 3.08E 09 0.00E 01 1.02E 09 0.00E 0I Be-140 8.40E 06 2.64E 08 1.28E 08 1.61E 05 5.47E 04 0.00E 01 9.22E 04 0.00E 01 Ce-141 1.48E 04 4.99E 08 1.93E 05 1.3tE 05 6.07E 04 0.00C 01 0.00E 01 0.00E 01 Co-144 1.69E 06 I.06510 3.15E 07 1.32E 07 7.80E 06 0.00E 01 0.00E 01 0.00E 01 2

'9 values in units of meee/yr per micro-Ci/m for innalation and tritium, and in units of 5 l 1

mree/yr per micro-C3 /sec f or all otners. Reference Regulatory Guide 1.109 3-35 Sev. 2 l

1 Pagn 66 of 164 TABLE 3.3-3 R VAUKS FOR TE H.B. ROBINSON STEAM ELECTRIC Pt#fT*

(Ref erenca Regulatory Guide 1.109)

PATl4Ay a veget AGE GROUP e Teen Nucilde T. Body GI-Trect Bone Liver Kidney Thyroid g Skin H-3 2.61E 03 2.6tE 03 0.00E 01 2.61E 03 2.61E 03 2.6tE 03 2.61E 03 2.6 tE C3 P-32 6.80E 07 I.47E 08 1.75E 09 1.09E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Cc-51 6.11E 04 1.03E 07 0.00E 01 0.00E 01 1.34E 04 3.39E 04 8.72E 04 0.00E 01 wn-54 8.19E 07 9.09E 08 0.00E 01 4.43E 08 1.32E 08 0.00E 01 0.00E 01 0.00E 01 Fe-59 I 60E 08 9.79E 08 1.77E 08 4.14E 08 0.00E 01 0.00E 01 1.30E 08 0.00E Of Co-58 9.79E 07 5.85E 08 0.00E 01 4.25E 07 0.00E GI 0.00E 01 0.00E 01 0.00E 01 Co-60 5.57E 08 3.22E 09 0.00E 01 2.47E 08 0.00C 01 0.00E 01 0.00E 01 0.00E 01 Zn-65 8.68E 08 7.88E 08 5.36E 08 1.86E 09 1.19E 09 0.00E 01 0.00E 01 0.00E 01 Rb-86 1.30E 08 4.09E 07 0.00E 01 2.76E 08 0.00E 01 0.00E 01 0.00E 0'l 0.00E 01

$r-89 4.36E 08 1.81E 09 f.52E 10 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Sr-90 2.05E 11 2.33E 10 8.32E 11 0.ME 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Y-91 2.06E 05 3.15E 09 7.68E 06 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E Of Zr-95 3.68E 05 1.23E 09 1.69E 06 5.35E 05 7.86E 05 0.00E 01 0.00E 01 0.00E 01 NO-95 5.77E 04 4.48E 08 1.89E 05 1.05E 05 I.02E 05 0.00E 01 0.00E 01 0.00E 01 Au-103 2.90E 06 5.66E 08 6.78E 06 0.00E 01 2.39E 07 0.00E 01 0.00E 01 0.00E 01 Ru-106 3.93E 07 1.50E 10 3.12E 08 0.00E 01 6.02E 08 0.00E 01 0.00E 01 0.00E 01 ag-110M 9.39E 06 4.34E 09 1.63E 07 1.54E 07 2.95E 07 0.00E 01 0.00E 01 0.00E 01 Te-127M 9.44E 07 1.98E 09 7.93E 08 2.81E 08 3.22E 09 1.89E 08 0.00E 01 0.00E 01 Te-129M 6.79E 07 1.61E 09 4.29E 08 1.59E 08 I.79E 08 1.38E 08 0.00E 01 0.00E 01 1-131 5.77E 07 2.13E 07 7.64E 07 1.07E 08 1.85E 08 3.14E 10 0.00E 01 0.00E 01 1-132 4.72E 01 5.72E 01 5.02E 01 1.31E 02 2.07E 02 4.43E 03 0.00E 01 0.00E 01 1-133 t. ole 06 2.51E 06 1.96E 06 3.32E 06 5.83E 06 4.64E 08 0.00E 01 0.00E of t-135 3.49E 04 1.04E 05 3.66E 04 9.42E 04 1.49E 05 6.06E 06 0.00E 01 0.00E 01 Cs-134 7.54E 09 2.02E 04 6.90E 09 f.62E 10 5.16E 09 0.00E 01 1.97E 09 0.00E 01 Cs-136 1.13E 08 1.35E 07 4.28C 07 1.68E 08 9.16E 07 0.00E 01 1.44E 07 0.00E 01 Cs-137 4.90E 09 2.00E 08 1.06E 10 1.41E 10 4.78E 09 0.00E 01 1.56E 09 0.00E 01 Ba P to 8.'88E 06 2.12E 08 1.JPE 08 1.69E 05 5.72E 04 0.00E 01 1.14E 05 0.00E 01 Co-141 2.12E 04 5.29E 08 2.77E 05 1.85E 05 8.70E 04 0.00E 01 0.00E 01 0.00E 01 Co-144 2.71E 06 1.27't to 5.04E 07 2.09E 07 1.25E 07 0.00E 01 0.00E 01 0.00E 01 2

'R values in un6 ts et erem/ve per siero-CI M for innaiation and tritium, and in units of m

.rea/yr oer eiero-ci/sec tor n i etners. Re,erence Re9uiatery cuice i.t09 j 3 .s aev. 2 l

Page 67 of 164 Tant.E 3.3-4 R VALIES FOR TE H.B. ROBINSON STEAM ELECTRIC PtANT' (Ref erence Regulatory Guide 1.109)

PA7HWAY a veget AGE GROUP = ChIid Nuclide T. Body GI-Trect Sone Liver Kidney Thyroid g Skin H-3 4.04E 03 4.04E 03 0.00E 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 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Cc-51 1.16E 05 6.15E 06 0.00E 01 0.00E 01 1.76E 04 6.44E 04 1.18E 05 0.00E 09 Mn-54 1.73E 08 5.44E 08 <0.00E Of 6.49E 08 1.82E 08 0.00E 01 0.00E 01 0.00E 01 Fe-59 3.17E 08 6.62E 08 3.93E 08 6.36E 08 0.00E 01 0.00E 01 1.84E 08 0.00E 01 Co-58 1.92E 08 3.66E 08 0.00E 01 6.27E 07 0.00E 01 0.00E 01 0.00E 01 0.00E of Co-60 1.11E 09 2.056 09 0.00E 01 3.76E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 2n-65 1.70E 09 4.81E 08 1.03E 09 2.74E 09 1.73E 09 0.00E 01 0.00E 01 0.00E 01 Ab-86 2.81E 08 2.94E 07 0.00E 01 4.56E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Sr-89 1.03E 09 1.40E 09 3.62E to 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Sr-90 .3.49E 11 1.86E 10 1.38E 12 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Y-91 4.89E 05 2.44E 09 1.83E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Zr-95 7.44E 05 8.71E 08 3.80E 06 8.35E 05 I.20E 06 0.UJE 01 0.00E 01 0.00E 01 Nb-95 1.12E 05 2.91E G8 4.04E 05 1.57E 05 1.48E 05 0.00E 01 0.00E 01 0.00E 01 Ru-103 5.86E 06 3.94E 08 1.52E 07 0.00E 01 3.84E 07 0.00E 01 0.00E 01 0.00E 01 Ru-106 9.38t! 07 1.17E 10 7.52E 08 0.00E 01 1.02E 09 0.002 01 0.00E 01 0.00E 01 Ag-110M 1.87E 07 2.78E 09 3.46E 07 2.34E 07 4.35E 07 0.00E 01 0.00E 01 0.00E 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 0'1

( Te-129M 1.55E 08 1.22E 09 9.90E 08 2.79E 08 2.93E 09 3.22E 08 0.'44 01 0.00E 01 1-131 8.16E 0) 1.23E 07 1.43E 08 I .44E 08 2.36E 08 4.75E 10 0.00E 01 0.00E 01 1-132 7.53E 01 1.93E 02 8.91E 01 I.64E 02 2.5tE 02 7.60E 03 0.00E 01 0.00E 01 l-133 I.67E 06 't .78E 06 3.57E 06 4.42E 06 7.36E 06 8.21E 08 0.00E 01 0.00E 31 i-135 5.54E 04 8.92E 04 6.50E 04 1.17E 05 1.79E 05 1.04E 07 0.00E 01 0.00E 01 Cs-134 5.40E 09 1.38E 08 1.56E 10 2.56E 10 7.93E 09 0.00E 01 2.84E 09 0.00E 01 l Cs-136 1.43E 08 7.77E 06 8.04E 07 2.21E 08 1.ISE 08 0.00E 01 1.76E 07 0.00E 01 Cs-137 3.52E 09 1.50E 08 '2.49E 10 2.39E 10 7.78E 09 0.00E 01 2.80E 09 0.00E 01

~

Be-140: 1.'61E 07 1.40E 08 2.76E 08 2.42E 05 7.87E 04 0.00E 01 1.44E 05 0.00E 01 Ce-141 4.75E 04 3.99E 08 d.42E 05 3.20E 05 1.40E 0$ 0.00E Of 0.00E 01 0.00E 01 Co-144 6.49E 06 9.94'E 09 1.22E OS 3.81E 07 2.11E 07 0.00E 01 0.00E 01 0.00E 01

'R Values in units of meem/yr mer micro-Ci/m 3 for innalation and +ritium, and in units of M meem/yr per micro-Cl/sec for all otners. Reference Regulatory Guide 1.109 3-37 3ev. 2

Page 68 of 164 TABLE 3.3-5 R VAL 1K5 FOR T1E H.8. RGBINSON STEAN ELECTRIC Pt. ANT *

(Reference Regulatory Guide 1.109)

PATHWAY s uset AGE G807 = 4dus t MucIide T. Body GI-Tract Bone Liver Kidaey Thyroid M 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 1.39E 08 0.00E 01 0.00E 01 0.00E 01 0.00E Of Cr-51 4.27E 03 1.08E 06 0.00E 01 0.00E 03 9.42E 02 2.56E 03 5.67E 03 0.00E 01 Mn-54 1.06E 06 t.71E 07 0.00E 01 5.57E 06 1.66E 06 0.00E 01 0.00E 01 0.00E 01 Fe-59 1.43E 08 1.25E 09 1.596 08 3.7tE 08 0.00E 01 0.00E 01 1.04E 08 0.00E 01 Co-58 2.43E 07 2.20E 08 0.00E 0: 1.08E 07 .0.00E 01 0.00E 01 0.00E 01 0.00E 01 Co-60 1.03E 08 8.76E 08 0.00E 01 4.56E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Zn-65 3.58E 08 4.98E 08 2.49E 08 7.91E 08 5.29E 08 0.00E 01 0.00E 01 0.00E 01 RD-86 1.42E 08 6.00E 07 0.00E 01 3.04E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Sr-89 5.23E 06 2.92E 07 1.82E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Sr-90 2.02E 09 2.38E 08 8.22E 09 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Y-91 1.80E 04 3.71E 08 6.75E 05 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Zr-95 2.43E 05 1.14E 09 1.12E 06 3.59E 05 5.64E 05 0.00E 01 0.00E 01 0.00E 01 Nb-95 4.12E 05 4.65E 09 1.38E 06 7.66E 05 7.58E 05 0.00E 01 0.00E 01 0.00E 01 Re-103 2.72E 07 7.38E 09 6.32E 07 0.00C 01 2.41E 08 0.00E 01 0.00E 01 0.00E 01 Ru-106 2.19E 08 1.12E 11 1.73E 09 0.00E 01 3.35E 09 0.00E 01 0.00E 01 0.00E Of Ag 110M 2.34E 06 1.61E 09 4.27E 06 3.95E 06 7.76E 06 0.00E 01 0.00E 01 0.00E 01 Te-127M 1.00E 08 2.76E 09 8.22E 08 2.94E 08 3.34E 09 2.10E 08 0.00E 01 0.00E 01 Te-129M l.17E 08 3.73E 09 7.40E 08 2.76E 08 3.09E*09 2.54E 08 0.00E 01 0.00E 01 1-131 5.77E 06 2.66E 06 7.04E 06 1.01E 07 1.73E 07 3.30E 09 0.00E 01 0.M 01 1-133 1.51E-01 4.46E-01 2.85E-01 4.96E-01 8.66E-01 7.29E 01 0.00E 01 0.00E 01 1-135 6.07E-17 1.86E-16 6.28E-17 1.64E -16 2.64E-16 1.08E-14 0.00E 01 0.00E 01 Cs-134 7.81E 08 1.67E 07 4.01E 08 9.55E 08 3.09E 08 0.00E 01 1.03E 08 0.00E 01 Cs-136 2.14E 07 3.33E 06 7.53E 06 2.97E 07 I .65E 07 0.00E 01 2.27E 06 0.00E 01 Cs-137 4.99E 08 1.47E 07 5.57E 08 7.6iE 08 2.58E 08 0.00E 01 8.59E 07 0.00E 01 Ba-140 3.77E 07 1.83E 07 2.30E 04 7.82E 03 0.00E 01 1.32E 04 0.00E 01 1.70E 06 2.18E 07 8.42E 03 5.69E 03 2.65E 03 0.00E 01 0.00E 01 0.00E 01 Co-141 6.46E 02 Co-144 4.70E 04 8.75E 05 3.66E 05 2.17E 05 0.00E 01 0.00E 01 0.00E 01 2.96E,08 2

ect Values in units of crea/yr per micro-Ci/m for inhalation and tritium, and in units of ii mese/yr per micro-Cl/sec for all others. Reference Regulatory Guide 1.109 3-38 Rev. 2

Page 69 of 164 TABLE 3.3-4 R VAllES FGt TE H.S. ROSINSON STEAN ELECTRIC PLANT' (Reference Regulatory Guide 1.109)

P4TMfAY s Meet AGE GROUP = Teen Nuclide T.Sody G 8-Trect Bone Liver Kidney Thyroid Lug Skin

. H-3 i .95E 02 1.95E 02 0.00E 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 0.00E 01 0.00E 01 0.00E 01 0.00E Of Cr-51 3.42E 03 5.75E 05 0.00E 01 0.,00E 01 7.49E 02 '1.90E 03 4.88E 03 0.00E 01 Mn-54 8.43E 05 8.72E 06 0.00E 01 4.25E 06 1.27E 06 0.00E 01 0.00E 01 0.00C 01 Fe-59 1.15E 08 7.02E 08 1.27E 08 2.97E 08 0.00E 01 0.0CE 01 9.36E 07 0.00E 01 Co-58 1.93E 07 1.15E 08 0.0~.;E 01 8.36E 06 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Co-60 8.15E 07 4.71E 08 0.00E 01 3.62E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Zn-65 2.83E 08 2.57E 08 1.75E 08 6.07E 08 3.S9E 08 0.00E 01 0.00E 01 0.00E 01 Rb-86 3.19E 08 3.76E 07 0.00E 01 2.54E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01

$r-89 4.40E 06 1.83E 07 1.54E 08 0.00E 01 ,0.00E 01 0.00E 01 0.00E 01 0.00E 01 Sr-90 1.31E 09 1.49E 08 5.32E 09 0.00E 01 0.00E 01 0.0'0E 01 0.00E 01 0.00E 01 f-91 1.52E 04 2.33E 08 5.68E 05 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Zr-95 1.95E 05 6.53E 08 8.97E 05 2.83E 05 4.16E 05 0.00E 01 0.00E 01 0.00E Of NO-95 3.29E 05 2.55E 09 1.08E 06 5.97E 05 5.79E 05 0.00E 01 0.00E 01 0.00E 01 Ru-IO3 2.20E 07 4.30E 09 5.15E 07 0.00E 01 1.82E 08 0.00E 01 0.00E 01 0.00E 01 Ru-106 1.84E 08 7.00E 10 1.46E 09 0.00E 01 2.81E 09 ' O.00E 01 0.00E 01 0.00E 01 Ag-110M I.86E 06 8.59E 08 3.23E 06 3.06E 06 5.83E 06 0.00E 01 0.00E 01 0.00E 01 Te-127M 8.25E C7 1.73E 09 6.94E 08 2.46E 08 2.81E 09 1.65E 09 0.00E 01, 0.00E 01 Te-129M 9.81E 07 2.33E 09 6.20E 08 2.30E 08 2.59E 09 2.00E 08 0.00E 01 0.00E 01 1-131 4.40E 06 1.62E 06 5.85E 06 8.20E 06 1.41E 07 2.39E 09 0.00E 01 0.00E 01 1-133 1.23E-01 3.06E-01 2.39E-01 4.05E-01 7.10E-01 5.65E 01 0.00E 01 0.00E of I-135 4.88E-17 1.46E-16 1.11E-17 1.32E-16 2.08E-t 6 S.46E-15 0.00E 01 0.00E 01 Cs-134 3.4eE 08 9.34E 06 3.19E 08 7.51E 06 2.39E 08 0.00E 01 9.11E 07 0.00E 01 Cs-136 1.55E 07 1.86E 06 5.87E 06 2.31E 07 1.26E 07 0.00E 01 1.98E 06 0.00E 01 Cs-137 .?.14E 08 8.75E 06 4.62E 03 6.15E 08 2.09E 08 0.00E 01 8.13E 07 0.00E 01 Ba-140 9.76E 05 2.34E 07 1.51E 07 1.86E 04 6.296 03 0.00E 01 1.25E 04 0.00E 01 Ce-141 5.42E 02 1.35E 07 7.07E 03 4.72E 03 2.22E 03 0.00E 01 0.00E 01 0.00E 01 Ce-144 3.96E 04 I.85E 04 7.37E 05 3.05E 05 1.82E 05 0.00E 01 0.00E 01 0.00E 01 s

3 2 l

'9 values in units of erem/yr per micro-CI/m for innalation and tritium, and in units of m mrem /yr ser micro-Ci/sec for all others. Reference Regulatory Guide 1.109 3-39 Rev. 2

Page 70 of 164 TABLE 3.5-7 R VALLES FOR T)E H.B. RGBINSON STEAM ELECTRIC PLANT' (Ref erence Regula'ory Guide 1.109)

PATMfAy e West AGE GROUP e ChiId NucIIde T.Sody GI-Teect Bone Liver Kidney Thyroid L3 Skin H-3 2.36E 02 2.36E 02 0.00E 01 2.36E 02 2.36E 02 2.36E 02 2.36E 02 2.36E 02 P-32 l.87E 08 1.34E 08 4.86E 09 2.27E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Cr-51 5.33E 03 2.83E 05 0.00E 01 0.00E 01 8.09E 02 2.96E 03 5.40E 03 0.00E 01 Mn-54 1.30E 06 4.08E 06 0.00E 01 4.36E 06 3.36E 06 0.00E 01 0.00E 01 0.00E 01 Fe-59 1.82E 08 3.80E 08 2.25E 08 3.55E 08 0.00E 01 0.00E 01 1.06E 08 0.00E 01 Co-53 2.99E 07 5.70E 07 0.00E 01 9.76E 06 0.00E 01 0.00E 01 0.00E 01 0.00E Of Co-60 I.27E 08 2.38E 08 0.00E 01 4.30E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Zn-65 4.35E 08 1.23E 08 2.62E 08 6.99E 08 4.40E 08 0.00E 31 0.00E 01 0.00E 01 Re-86 2.21E 08 2.32E 07 0.00E 01 3.60E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Sr-89 8.31E 06 1.13E 07 2.91E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Sr-90 1.74E 09 9.26E 07 6.87E 09 0.00E 01 0.00E 01 0.00E 01 0.00C Oi 0.00E 01 Y-91 2.87E 04 1.43E 08 1.07E 06 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Zr-95 3.12E 05 3.65E 08 1.59E 06 3.50E 05 5.01E 05 0.00E 01 0.00E 01 0.00E 01 Nb-95 5.17E 05 1.34E 09 1.86E 06 7.23E 05 6.SOE 05 0.00E 01 0.00E 01 0.00E 01 Ru-103 3.58E 07 >2.41E 09 9.31E 07 0.00E 01 2.34E 08 0.00E 01 0.00E 01 0.00E 01 Ru-106 3.43E 08 4.27E 10 2.75E 09 0.00E 01 3.71E 09 0.00E 01 0.00E 01 0.00E 01 Ag-110M 2.*9E 06 4.30E 08 5.36E 06 3.62E 06 6.74E 06 0.00E 01 0.00E 01 0.00E 01 T,-127M 1.55E 08 1.06E 09 1.31E 09 3.52E C8 3.73E 09 3.13E 08 0.00E 01 0.'00E 01 Te-129M 1.81E 08 1.42E 09 1.17E 09 3.26E 08 3.43E 09 3.77E 08 0.00E 01 0.00E 01 1-131 ' 6.20E 06 9.72E 05 1.09E 07 1.09E 07 1.79E 07 3.61E 09 0.00E 01 0.00E 01 l

1-133 2.07E-01 2.21E-01 4.43E-01 5.48E-01 9.13E-01 1.02E 02 0.00E 01 0.00E 01 l

l-135 7.8.E-17 1 27E-16 9.25E-17 1.66E-16 2.55E-16 1.47E-14 0.00E 01 0.00E 01 l

Cs-134 1.95E 08 4.93E 06 5.63E 08 9.23E 08 2.86E 08 0.00E 01 1.03E 08 0.00E 01 i Cs-136 1.80E 07 9.78E 05 1.01E 07 2.78E OF 1.48E 07- 0.00E 01 2.21E 06 0.00E 01 Cs-137 1.20E Co 5.10E 06 8.51E 08 8.15E 08 2.65E 08 0.00E 01 9.55E 07 0.00E 01 Ba-140 1.63E 06 1.42E 07 2.80E 07 2.45E 04 ,7.97E 03 0.00E 01 1.46E 04 0.00E 01 Co-141 9.'86E 02 8.28E 06 1.33E 04 6.64E 03 2.91E 03 0.00E 01 0.00E 01 0.00E 01 Co-144 7.42E 04 1.14E 08 1.39E 06 4.36E 05 2.41E 05 0.00E 01 0.00E 01 0.00E 01 I

2

'9 Values in units of meee/yr per micro-Cl/m for innalation and tritium, and in units of m meem/yr per micro-Cl/sec for all others. Reference Regulatory Guide 1.109 3-40 lev. 2 l

Paga 71 of 164 TAsu 3.3-a R VALtKS FOR TIE H.S. RIBIN50N STEAM ELECTRIC PLANT *

(Reference Regulatory Guide 1.109) .

PATMsAY = Cow WIIk AGE GROUP a A'utt d

MucfIde T. Body GI-Tract Bone LIwer Kidaey Thyroid g Skin H-3 7.69E p2 7.69E 02 0.00E-01 7.69E 02 7.69E 02 7.69E 02 7.69E 02 7.69E 02

P-32 4.32E 08 1.26E 09 1.12E 10 6.95E 08 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Cr-51 1.73E 04 4.36E 06 0.00E-01 0.00E-Of 3.82E 03 1.04E 04 2.30E 04 0.00E -O n Mn-54 9.76E 05 1.57E 07 0.00E-01 5.11E 06 *1.52E 06 0.00E-01 0.00E-01 0.00E -O f Fe-59 1.60E 07 1.39C 08 f.77E 07 4.17E 07 0.00E-01 0.00E-01 1.17E 07 0.00E-01 Co-58 6.28E 06 5.68E 07 0.00E-01 2.80E 06 0.00E-CI 0.00E-01 0.00E-01 0.00E-01 Co-60 2.24E 07 I.9tE 08 0.00E-Cl 1.02E 07 0.00E-01 0.002-01 0.00E-01 0.00E-01 2n-65 1.38E 09 1.92E 09 9.59E 08 3.05E 09 2.04E 09 0.00E-01 0.00E-01 0.00E-01 Re-86 7.54E 08 3.19E 08 0.00E-01 1.62E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Sr-89 2.50E 07 1.40E 08 S.70E 08 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

$r-90 7.59E 09 8.94E 08 3.09E to 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y-91 1.37E 02 2.81E 06 5.11E 03 0.00E-01 d.00E-01 0.00E-01 0.00E-01 0.00E-01 Zr-95 1.22E 02 5.71E 05 5.62E 02 1.80E 02 2.83E 02 0.00E-01 0.00E-01 0.00E-01 Nb-95 1.48E 04 1.67E 08 4.95E 04 2.75E 04 2.72E 04 0.00E-01 0.00E-01 0.00E-01 Ru-103 2.63E 02 7.14E 04 6.11E 02 0.00E-01 2,33E 03 0.00E-01 0.00E-01 0.00E-01 Ru-106 1.60E 03 8.17E 05 1.26E 04 0.00E-01 2.44E 04 0.00E-01 0.00E-01 0.00E-01 Ag-110M 2.04E 07 1.40E to 3.71E 07 3.44E 07 6.76E 07 0.00E-01 0.00E-01 0.00E-OI Te-127M 4.11E 06 1.13E 06 3.37E 07 1.21E 07 1.37E 08 8.62E 06 0.00E-01 0.00E-01 Te-129M 6.19E 06 1.97E 08 3.91E 07 f.46E 07 1.63E 08 1.34E 07 0.00E-01 0.00E <1 1-131 1.59E 08 7.32E 07 I.94E 08 2.77E 08 4.76E 08 9.09E 10 0.00E-01 0.00E-01 1-132 1.03E-01 5.51E-02 1.10E-01 2.9M-01 4.67E-01 1.03E 01 0.00E-01 0.00E-01

! -133 1.40E 06 4.13E 06 2.64E 06 4.59E 06 8.01E 06 6.75E 08 0.00E-01 0.00E-Ot 5-135 9.03E 03 2.76E 04 9.34E 03 2.45E 04 3.92E 04 1.61E 06 0.00E-01 0.00E-01 l Cs-134 6.71E 09 1.44E 08 3.45E 09 3.21E 09 2.66E 09 0.00E-01 8.82E 08 0.00E-01 Cs-136 4.73E OS 7.46E 07 1.66E 08 6.57E 08 3.6 % 08 0.00E-01 5.0IE 07 0.00E-01 l Cs-137 4 22E 09 1.25E 08 4.71E 09 6.44E 09 2.19E 09 0.00E-01 7.27E 08 0.00E-01 l Be-140 1.12E 06 3.53E 07 1.71E 07 2.15E 04 7.32E 03 0.00E-01 1.23E 04 0.00E-01 Ce-141 2.23E 02 7.52E 06 2.91E 03 1.97E 03 9.14E 02 0.00E-01 0.00E-01 0.00E-01 Ce-144 1.15E 04 7.2".,E 07 2.15E 05 8.97E 04 5.32E 04 0.00E-01 0.00E-01 0.00E-01

'R values in units of meee/yr per micro-Ci/n 3 for innalation and tritium, and in units of M meem/yr oer micro-Ci/sec for all others. Reference Regulatory Guide 1.109 3-41 4ev. 2 l

Pagn 72 of 164 TABLE 3.3-9 R VALUES FGt TE H.S. RIMilC38 STEAM ELECTRIC PLANTS (Reference Regulatory Guide 1.1091 PA7HWAY a Cow Milk ACE GROUP = Teen Nuclide T.Sady GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1.00E 03 1.00E 03 0.00E-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-0I 0.00E-01 0.00E-01 0.00E-01 Cc-51 3.02E 04 5.08E 06 0.00E-01 0.00E-01 6.63E 03 1.68E 04 4.32E 04 0.00E-01 un-54 1.69E 06 1.75E 07 0.00E-01 8.52E 06 2.54E 06 0.00E-01 0.00E-01 0.00E-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 0.00E-01 4.72E 06 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Co-60 3.88E 07 2.25E 08 0.00E-01 1.72E 07 0.00E-01 0.00E-0I 0.00E-01 0.00E-01 Zn-65 2.38E 09 2.16E 09 1.47E 09 5.11E 09 3.27E 09 0.00E-01 0.00E-01 0.00E-01 Ab-86 1.39E 09 4.37E 08 0.00E-01 2.95E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Sr-89 4.59E 07 1.91E 08 1.60E 09 0.00E-01 0.00E-01 0.00E-Os 0.00E-01 0.00E-01 5r-90 1.08E 10 1.23E 09 4.37E 10 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y-91 2.52E 02 3.85E 06 9.40E 03 0.00E-41 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Zr-95 2.13E 02 7.16E 06 9.83E 02 3.10E 02 4.56E 02 0.00E-01 0.00E-01 0.00E-01 Nb-95 2.58E 04 2.00E 08 9.45E 04 4.68E 04 4.54E 04 0.00E-01 0.00E-01 0.00E-01 Ru-103 4.65E 02 9.08E 04 1.09E 03 0.00E-01 3.83E 03 0.00E-01 0.00E-01 0.00E-01 Ru-306 2.93E 03 1.11E 06 2.32E 04 0.00E-01 4.48E 04 0.00E-01 0.00E-01 0.00E-01 Ag-180M 3.53E 07 1.63E 10 6.14E 07 5.81E 07 1.11E 08 0.00E-01 0.00E-01 0.00E-01 Te-127M 7.39E 06 1.55E 08 6.22E 07 2'.2tE 07 2.52E 08 1.48E 07 0.00E-01 0.00E-01 Te-129M 1.13E 07 2.69E 06 7.15E 07 2.65E 07 2.99E 08 2.31E 07 0.00E-01 0.00E-01 1-131 2.65E 08 9.75E 07 3.52E 08 4.93E 08 8.48E 08 1.44E 11 0.00E-01 0.00E-01 1-132 1.83E-01 2.22E-01 1.94E-01 5.09E-01 8.02E-01 1.71E 01 0.00E-01 0.00E-01 1-133 2.49E 06 6.19E 06 4.82E 06 8.18E 06 f.43E 07 1.14E 09 0.00E-01 0.00E-01 1-135 1.58E 04 4.74E 04 1.66E 04 4.27E 04 6.75E CC 2.75E 06 0.00E-01 0.00E-01 Cs-134 6.54E 09 1.75E 08 5.99E 09 -1.41E 10 4.48E 09 0.00E-01 1.71E 09 0.00E-01 Cs-136 7.48E 08 8.97E 07 2.83E 08 1.11E 09 6.07E 08 0.00E-01 9.56E 07 0.00E-01 Cs-137 3.96E 09 1.62E 08 8.54E 09 1.14E 10 3.87E 09 0.00E-01 1.50E 09 0.00E-01 Ba-140 1499E 06 4.77E 07 3.09E 07 3.79E 04 1.28E 04 0.00E-01 2.55E 04 0.00E-01 Co-141 4.09E 02 1.02E 07 6.33E 03 3.56E 03 1.68E 03 0.00E-01 0.00E-01 0.00E-01 Co-144 2.12E 04 9.93E 07 3.95E 05 1.63E 05 9.76E 04 0.00E-01 0.00E-01 0.00E-01 2

'R values in units of meem/yr per micro-Ci/m for innalation ano tritium, and in units of m seem/yr per micro-Cl/sec for all otrers. Reference Regulatory Guide 1.109, 3-42 ae v. 2

Page 73 of 164 TA8tf 3.3-10 R VAllES FOR TIE H.B. ROBIN 50N STEAM ELECTRIC PLANT' l (Reference Regulatory Guide 1.109)

P4 TMIAY = Cow Mi l k AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid g Skin H-3 1.58E 03 1.58E 03 0.00E-01 1.58E 03 1.58E 03 f.58E 03 f.58E 03 1.58E 03 P-32 1.96E 09 1.4tE 09 5.09E 10 2.38E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Cr-5I 6.17E 04 3.27E 06 0.00E-01 0.00E-01 9.36E 03 3.42E 04 6.25E 04 0.00E-01 wn-54 3.39E 06 1.07E 07 0.00E-01 1.27E 07 3.57E 06 0.00E-01 0.00E-01 0.00E-Ot Fe-59 5.79E 07 1.21E 08 7.18E 07 1.16E 08 0.00E-01 0.00E-01 3.37E 07 0.00E-01 Co-58 2.21E 07 4.20E 07 0.00E-01 7.21E 06 0.00E-01 0.00E-01 0.00E-CI 0.00E-01 Co-60 7.90E 07 1.48E 08 0.00E-01 2.68E 07 0.00E-01 0.00E-01 0.00E-01 0.00E 41 Zn-45 4.79E 09 1.35E 09 2.89E 09 7.70E 09 4.85E 09 0.00E-01 0.00E-01 0.00E-01 Ab-86 3.36E 09 3.52E 08 0.00E-01 5.47E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Sr-89 1.13E 08 1.54E 08 3.97E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

$r-90 1.87E 10 9.95E 04 7.38E 10 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y-91 6.21E 02 3.09E 06 2.32E 04 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Zr-95 4.47E 02 5.23E 05 2.28E 03 5.02E 02 7.18E 02 0.00E-01 0.00E-01 0.00E-01 NO-95 5.31E 04 1.37E 08 1.91E 05 7.42E 04 6.98E 04 0.00E-01 0.00E-01 0.00E-01 Au-103 9.88E 02 6.65E 04 2.57E 03 0.00E-01 6.47E 03 0.00E-01 0.00E-01 0.00E -01 Ru-106 7.14E 03 8.90E 05 5.72E 04 0.00E-01 7.72E 04 0.00E-01 0.00E-01 0.00E -01 Ag-I IOM 7.19E 07 1.07E 10 1.33E 08 9.00E 07 1.68E 08 0.00E-0I 0.00E-01 0.00E-01 Te-127M l.82E 07 1.24E 08 1.53E 08 4.13E 07 4.37E 08 3.66E 07 0.00E-01 0.00E-01 l

Te-129M 2.74E 07 2.15E 08 1.76E 08 4.92E 07 5.18E C3 5.68E 07 0.00E-01 0.00E-01 1-131 4.88E 08 7.64E 07 8.54E 08 8.59E 08 1.41E 09 2.84E 11 0.00E-01 0.00E-01 1-132 3.89E-01 9.95E-01 4.60E-01 8.45E-01 1.29E 00 3.92E 01 0.00E-01 0.00E-01 1-133 5.48E 06 5.84E 06 1.17E 07 1.45E 07 2.41E 07 2.69E 09 0.00E-01 0.00E -01 1-135 3.35E 04 5.39E 04 3.93E 04 7.07E 04 1.08E 05 6.26E 06 0.00E-01 0.00E-01 Cs-134 4.78E 09 1.22E 08 1.38E 10 2.27E 10 7.03E 09 0.00E-01 2.52E 09 0.00E-01 l

Cs-136 1.IAE 09 6.17E 07 6.39E 08 1.76E 09 9.36E 08 0.00E-01 1.40E 08 0.00E-01 Cs-137 2.91E 09 1.23E 08 2.06E 10 1.97E 10 6.42E 09 0.00E-01 2.31E 09 0.00E-01 Be-140 4.36E 06 3.78E 07 7.47E 07 6.54E 04 - 2.13E 04 0.00E-Ol 3.90E 04 0.00E-01 9.73E 02 1.31E 04 6.55E 03 2.87E 03 0.00E-01 0.00E-01 0.00E-01 Ce-141 8.1,7E 06 5.20E 04 7.96E 07 9.74E O! 3.05E 05 1.69E 05 0.00E-01 0.00E-01 0.00E-01 Co-144 2

'R ulues in units of mees /yr oer micro-Ci/m for innelation and teitium, and in units of n f meee/yr per sicro-Ci/see for all otners. Reference Regulatory Guide 1.109 1

3-43 4ev. 2

Page 74 of 164 TAeLE 3.3-11 R VALES FOR TIE H.S. ROBINSON STEAM ELICTRIC PLANT *

(Reference Regulatory Guide 1.109)

PATMfAY = Cow Milk AGE GR01.lP s l'fant n

NuciIde T. Body GI-Tract Bone Liver Kidaey ThyrolJ g 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.*7E 09 0.00E-01 0.00E-01 0.00E-01 0.00E -01 Cr-51 9.77E 04 2.85E 06 0.00E-01 0.00E-0I 1.39E 04 6.38E 04 f.24E 05 0.00E-01 Mn-54 5.37E 06 8.71E 06 0.00E-01 2.37E 07 5.25E 06 0.00E-01 0.00E-01 0.00E -01 Fe-59 9.23E 07 1.12E 08 1.34E 08 2.34E 08 0.00E-01 0.00E-01 6.92E 07 0.00E-01 Co-58  ?.60E 07 3.59E 07 0.00E-01 1.4AE 07 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Co-40 1.29E 08 1.30E 08 0.00E-Of 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 1.3X 10 6.45E 09 0.00E-01 0.00E-01 0.00E-On RD-86 5.86E 09 3.55E 08 0.00E-01 1.39E 10 0.00E-01 0.00E-0I 0.00E-01 0.00E-01 Sr-89 2.17E 08 1.55E 08 7.55E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

$r-90 2.05E 10 1.00E 09 8.04E 10 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y-91 I.16E 08 3.12E 06 4.36E 04 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Zr-95 7.01E 02 4.92E 05 4.05E 03 9.88E 02 1.06E 03 0.00E-01 0.00E-01 0.00E-Of ND-95 8.48E 04 1.24E 08 3.56E 05 1.47E 05 1.0$E 05 0.00E-01 0.00E-01 0.00E-01 Ru-103 1.74E 03 6.33E 04 5.21E 03 0.00E-01 1.08E 04 0.00E-01 0.00E-01 0.00E-01 Ru-106 1.47E 04 8.95E 05 1.18E 05 0.00E-01 1.39E 05 0.00E-01 0.00E-01 0.00E-01 Ag-110M l.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 I.25E 08 3.10E 08 1.03E 08 7.64E 08 8.96E 07 0.00E-01 0.00E-01 Te-129M 5.57E 07 2.16E 08 3.62E 08 1.24E 08 9.0$E 08 f.39E 08 0.00E-01 0.00E-01

'l-I31 9.23E 08 7.49E 07 1.78E 09 2.10E 09 2.45E 09 6.90E II 0.00E-01 0.00E-01 1-132 6.90E-01 1.57E-00 9.55E-01 1.94E 00 2.16E 00 9.09E 01 0.00E-01 0.00E-01 1-133 1.05E 07 6.04 06 2.47E 07 3.60E 07 4.23E 07 6.55E 09 0.00E-01 0.00E-01 1-135 5.9X 04 5.8X 04 8.17E 04 1.63E 05 1.81E 05 1.46E 07 0.00E-01 0.00E-01 Cs-134 4.19E 09 1.1X 08 2.2X 10 4.15E 10 1.07E 10 0.00E-01 4.38E 09 0.00E-01 Cs-136 1.37E 09 5.58E 07 f.25E 09 3.67E 09 f.46E 09 0.00E-01 2.99E 08 0.00E-01 Cs-137 2472E 09 1.20E 08 3.28E 10 3.84E 10 1.0X 10 0.00E-01 4.18E 09 0.00E-01 Da-140 7.91E 06 3.77E 07 l.!4E 08 1.54E 05 3.65E 04 0.00E-01 9.43E 04 0.00E-01 Ce-let 1.87E 03 3.21E 06 2.60E 04 1.59E 04 4.90E 03 0.00E-01 0.00E-01 0.00E-01 Ce-144 7.82E 04 8.01E 07 1.40E 06 5.71E 05 2.31E 05 0.00E-01 0.00E-01 0.00E-01

'R values in units of mees /yr per micro-Cl/m 3 for innalation and tritium, and in units of ,2 mese/yr per micro-CI/foc for all others. Reference Regulatory Guide 1.109 l

- - - -. . u 1

Page 75 of 164 TAaLE 3.3-12 R VAtlES FOR T1E H.B. ROBINSON $1EAN ELECTRIC PLANT *

(Reference Regulatory Guide 1.109)

P4TMcAY = Goat Milk AGE GROUP = Adult Muclide T. Body GI-Tract Bone Liver Kidney Thyroid Skin L3 H-3 f.57E 03 1.57E 03 0.00E-01 1.57E 03 1.57E 03 1.57E 03 1.57E 03 1.57E 03 P-32 5.19E '08 1.5fE 09 1.34C 10 8.34E 08 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Cr-51 2.08E 03 5.23E 05 0.00E-01 0.00E-01 4.58E 02 1.24E 03 2.76E 03 0.00E-01 un-54 1.17E 05 1.88E 06 0.00E-01 6.14E 05 1.83E 05 0.00E-01 0.0CE-01 0.00E-01 Fe-59 2.08E 05 1.8tE 06 2.3tE 05 5.42E 05 0.00E-01 0.00E-01 1.51E 05 0.00E -01 Co-58 7.54E 05 6.82E 06 0.00E-01 3.36E 05 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Co-60 2.69E 06 2.29E 07 0.00E-01 1.22E 04 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Zn-65 1.65E 08 2.31E 04 1.15E 08 3.66E 08 2.45E 08 0.00E-01 0.00E-01 0.00E-01 Re-86 9.05E 07 3.83E 07 0.00E-01 't.94E 08 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Sr-89 5.24E 07 2.93E 08 1.83E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Sr-90 1.59E 10 1.88E 09 6.49E 10 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 f-91 1.64E 01 3.37E 05 6.1X 02 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Zr-95 1.46E 01 6.85E 04 6.74E 01 2.16E 01 3.39E 01 0.00E-01 0.00E-01 0.00E-Of Nb-95 1.78E 03 2.01E 07 5.94E 03 3.31E 03 3.27E 03 0.00E-01 0.00E-01 0.00E -C' Ru-103 3.16E 01 8.56E 03 7.33E 01 0.00E-01 2.80E 02 0.00E-01 0.00E-01 0.00E-01 Ru-106 1.92E 02 9.81E 04 1.52E 03 0.00E-01 2.93E 03 0.00E-01 0.00E-01 0.00E-01 Ag-Il0M 2.45E 06 1.68E 09 4.46E 06 4.12E 06 8.IIE 06 0.00E-OI 0.00E-01 0.00E-01 Te-127M 4.9h 05 1.36E 07 4.05E 06 1.45E 06 1.64E 07 1.03E 06 0.00E-01 0.00E-01 Te-129M 7.4X 05 2.36E 07 4.69E 06 1.75E 06 1.96E 07 1.6fE 06 0.00E-01 0.00E-01 1-131 1.91E 08 8.78E 07 2.3 X 08 3.3 X 08 5.71E 08 1.09E 11 0.00E-01 0.00E-01 1-132 1.23E-CI 6.6fE-02 1.32E-01 1.52E-01 5.61E-01 1.23E 01' O.00E-01 0.00E-01 1-133 1.682 06 4.95E 06 3.17E 06 5.51E 06 9.61E 06 8.10E 08 0.00E-01 0.00E-01 1-135 1.08E 04 3.32E 04 1.12E 04 2.94E 04 ,4.71E 04 1.94E 06 0.00E-Ol 0.00E-01 Cs-134 2.01E 10 4.31E 08 1.03E 10 2.46E 10 7.97E 09 0.00E-01 2.65E 09 0.00E-01 Cs-136 1.42E 09 2.24E 08 4.99E 08 1.97E 09 1.10E 09 0.00E-01 1.50E 08 0.00E-01

Cs-137 1.27E 10 3.74E 08 1.41E 10 1.93E 10 6.56E 09 0.00E-01 2.18E 09 0.00E-01

! Be-140 1.35E 05 4.23E 06 2.06E 06 2.58E 03 8.78E 02 0.00E-01 1.48E 03 0.00E-01 Co-I4l 2.68E 01 9.03E 05 3.49E 02 2.36E 02 1.10E 02 0.00E-01 0.00E-Ol 0.00E-01 Ce-144 1.38E 03 8.711 06 2.58E 04 1.08E 04 6.39E 03 0.00E-01 0.00E-01 0.00E-01 3

'R values in units of meee/yr per micro-Ci/m for innatation and tritium, and in units of m2 area /yr ser siero-Cl/sec for all others. Reference Regulatory Guide 1.109

'#' I

. . - _ _ - . _ _ . _ - - . _ _ **T*

Page 76 of 164 TA8LE 3.3-13 R V4LIKS FGt TE H.S. fMINSON STEAM ELECTRIC Pl.AhT*

I (Reference Regulatory Guide 1.109)

PATHWAY = Goat Milk AGE GROUP = Teen Nuclide T. Body GI-Tract Bons Liver Kidney Inyroid g Skin H-3 2.04E 03 2.04E 03 0.00E-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 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Cr-51 3.63E 03 6.10E 05 0.00E-01 0.00E-01 7.95E 02 2.02E 03 5.18E 03 0.00E-01 Mn-54 2.03E 05 2.10E 06 0.00E-01 1.02E 06 3.0!E 05 0.00E-01 0.00E-Ol 0.00E-01 Fe-59 3.63E 05 2.22E 06 4.03E 05 9.40E 05 0.00E-01 0.00E-01 2.96E 05 0.00E-01 Co-58 1.30E 06 7.80E 06 0.00E-01 5.66E 05 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Co-60 4.66E 06 2.69E 07 0.00E-01 2.07E 06 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Zn-65 2.86E 08 2.60E 08 1.77E 08 6.13E 08 3.93E 08 0.00E-01 0.00E-01 0.00E-01 Rb-86 1.66E 08 5.24E 07 0.00E-Oi 3.54E 08 0.00E-01 0.00E-01 0.00E-01 0.00E-01

$r-89 9.65E 07 4.01E 08 3.37E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Sr-90 2.27E 10 2.58E 09 9.18E 10 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 f-91 3.02E 01 4.62E 05 I.13E 03 0.00E-01 0.00E-01 0.00E-01 0.00E-41 0.00E-01 Zr-95 2.56E 01 8.59E 04 1.18E 02 3.72E 01 5.47E 01 0.00E-01 0.00E-01 0.00E-01 NO-95 3.09E 03 2.40E 07 I.01E 04 5.62E 03 5.45E 03 0.00E-01 0.00E-01 0.00E-01 Ru-103 5.58E 01 I.09E 04 1.30E 02 0.00E-01 4.60E 02 0.00E-01 0.00E-01 0.00E-01 Ru-106 3.51E 02 1.34E 0: 2.79E 03 0.00E-08 5.38E 03 0.00E-01 0.00E-01 0.00E-01 Ag-110M 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-127W 8.87E 05 1.S6E 07 7.46E 06 2.65E 06 3.02E 07 1.77E 06 0.00E-01 0.00E-01 Te-629M l.36E 06 3.22E 07 8.58E 06 3.19E 06 3.59E 07 2.77E 06 0.00E-01 0.00E-01 1-131 3.18E 08 1.17E 08 4.22E 08 5.91E 08 1.02E 09 1.73E 11 0.00E-01 0.00E-01 1-132 2.19E-01 2.66E-01 2.33E-01 6.11E-01 9.62E-01 2.06E 01 0.00E-01 0.00E-01 1-133 2.99E 06 7.43E 06 5.79E 06 9.8tE 06 1.72E 07 1.37E 09 0.00E-01 0.00E-01 1-135 1.90E 04 5.63E 04 1.99E 04 5.13E 04 8.10E 04 3.30E 06 0.00E-01 0.00E-01 Cs-134 1.96E 10 5.26E 08 1.80E 10 4.23E to 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 0.00E-01 2.87E 08 0.00E-01 l '

Cs-137 1.19E 10 4.85E 08 2.56E 10 3.41E to 1.16E IG 0.00E-01 4.51E 09 0.00E-01 l

Be-140 F.39E 05 5.72E 06 3.71E 06 4.55E 03 1.54E 03 0.00E-01 3.06E 0'3 0.00E-01 Co-141 4.91E 01 I.22E 06 6.40E 02 4.27E 02 2.01E 02 0.00E-01 0.00E-01 0.00E-01 Co-144 2.55E 03 1.19E 07 4.74E 04 1.96E 04 1.17E 04 0.00E-01 0.00E-01 0.00E-01

'5t Values in units of mese/yr per micro-Cl/M for inhalation and teitium, and in units of M eremiyr per micro-Cl/sec for all ottiers. Reference Regulatory Guide 1.109 I 3-46 4ev. 2 l

~ - . _ _. _ .-

Pagu 77 of 164 TABLE 3.3-14 R VALLES FOR DE H.B. ROBINSON STEAN ELECTRIC PtANT*

(Ref erence Regulatory Guide 1.109) go , . Coet un =

AGE GROUP = Child Nuclide T.Sody GI-Tract Bone liver Kidney Thyroid Lung Skin H-3 3.23E 03 3.23E 03 0.00E-01 3.23E 03 3.23E 03 3.23E 03 3.23E 03 3.23E 03 g-32 2.35E 09 1.69E 09 6.11E 10 2.86E 09 0.~0E-01 0.00E-01 0.00E-01 0.00E-01 Cr-51 7.40E 03 3.93E 05 0.00E-01 0.00E-01 1.12E 03 4.11E 03 7.30E 03 0.00E-01 un-54 4.07E 05 1.28E 06 0.00E-01 1.53E 06 4.29E 05 0.00E-01 0.00E-01 0.00E-01 Fe-59 7.52E 05 1.57E 06 9.34E 05 1.5tE 06 0.00E-01 0.00E-07 4.38E 05 0.00E-01

.Co-58 2.65E 06 5.05E 06 0.00E-01 8.65E 05 0.00C -01 0.00E-01 0.00E-01 0.00E-01 Co-60 9.48E 06 1.78E 07 0.00E-01 3.21E 06 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Zn-65 5.74E 08 1.62E 08 3.47E 08 9.24E 08 5.82E 08 0.00E-01 0.00E-01 0.00E-01 Rb-86 4.04E 08 4.22E 07 0.00E-CI 6.57E 08 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Sr-o9 2.38E 08 3.23E 08 8.34E 09 0.00E-Of 0.00E-01 0.00E-01 0.00E-Of 0.0CE-01 Sr-90 3.93E 10 2.09E 09 1.55E 11 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y-91 7.45E 01 3.71E 05 2.79E 03 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Zr-95 5.36E 01 6.28E 04 2.74E 02 6.02E 01 8.62E 01 0.00E-01 0.00E-01 0.00E-01 Nb-95 6.37E 03 1.65E 07 2.29E 04 8.91E 03 8.37E 03 0.00E-01 0.00E-01 0.00E-01 Ru-103 1.19E 02 7.98E 03 3.09E 02 0.00E-01 7.77E 02 0.00E-01 0.00E-01 0.00E-01 Ru-106 8.56E 02 I.07E 05 6.86E 03 0.00E-01 9.27E 03 0.00E-01 0.00E-01 0.00E -01 Ag-110M 8.63E 06 1.28E 09, 1.60E 07 1.08E 07 2.01E 07 0.00E-01 0.00E-01 0.00E-01 Te-127M 2.I8E 06 1.49E 07 1.84E 01 4.95E 06 5.24E 07 4.40E 06 0.00E-01 0.00E -01 Te-129M 3.28E 06 2.58E 07 2.12E 07 5.91E 06 6.21E 07 6.82E 06 0.00E-01 0.00E-01 1-131 5.85E 08 9.17E 07 1.02E 09 1.03E 09 1.69E 09 3.41E 11 0.00E-01 0.00E-01 1-132 4.67E-01 1.19E 00 5.52E-01 1.01E 00 1.55E 00 4.71E 01 0.00E-01 0.00E-01 1-133 6.58E 06 7.00E 06 1.41E 07 1.74E 07 2.90E 07 3.23E 09 0.00E-01 0.00E-01 1-135 4.01E 04 6.47E 04 4.72E 04 8.49E 04 1.30E 05 1.52E 06 0.00E-01 0.00E-01 Cs-134 1.43E 10 3.67E 08 4.14E 10 6.80E 10 2.11E 10 0.00E-01 7.56E'09 0.00E-01 Cs-136 3.41E 09 1.85E 08 1.92E 09 5.27E 09 2.81E 09 0.00E-01 4.19E 08 0.00E-01 Cs-137 8.72E 09 3.70E 08 6.17E 10 5.91E 10 1.93E 10 0.00E-01 6.93E 09 0.00E-01 Ga-140 1.23E 05 4.54E 05 8.96E 06 7.85E 03 2.56E 03 0.00E-01 4.68E 03 0.00E-01 Ce-141 1.17E 02 9.81E 05 1.53E 03 7.36E 02 3.45E 02 0.00E-01 0.00E-01 0.00E-01 Co-144 6.24E 03 9.55E 06 1.17E 05 3.66E 04 2.03E 04 0.00E-01 0.00E-01 0.00E-01

'A values in units of meem/yr per micro-CI/m 3 for inhalation and tritium, and in units of M ,

I meem/yr per micro-Cl/sec for all others. Reference Regulatory Guide 1.109 3-47 4ev. 2 l

Pagn 78 of 164 TABM 3.3-15 R VALLES FOR T)E H.B. RORINSON SWAN ELECTRIC PLANT

  • l (Reference Regulatory Guice 1.105)

P4T}MAY = Goat Milk AGE GROUP = lhf ant Nucilde g GI-Trect Bone Liver Kidney Thyroid g Skin H-1 4.90E 03 4.91E 03 0.00E-01 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 0.00E-01 0.00E-01 0.00E-Of 0.00E -01 Cr-Si 1.17E 04 3.42E 05 0.00E-01 0.00E-01 1.67E 03 7.65E 03 1.49E 04 0.00E-01 un-54 6.45E 05 1.04E 06 0.00E-01 2.54E 06 6.30E 05 0.00E-01 0.00E-01 0.00E-01 Fe-59 1.20E 06 1.45E 06 f.74E 06 3.04E 06 0.00E-01 0.00E-Of 9.00E 05 0.COE-01 Co-58 4.31E 06 4.3tE 06 0.00E-01 1.73E 06 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Co-60 f .!'E 07 1.56E 07 0.00E-01 6.56E 06 0.00E-01 0.00E-01 0.00E-01 0.00E-01 2n-65 7.36E 08 1.35E 09 4.66E 08 1.60E 09 7.74E 08 0.00E-01 0.00E-01 0.00E-01 Re-86 8.23E 08 4.26E 07 0.00E-01 1.67E 09 0.001 -01 0.00E-01 0.00E-01 0.00E-01 Sr-89 4.55E 08 3.26E 08 1.59E 10 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

$r-90 4.30E to 2.11E 09 1.69E II 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

?-91 1.39E 02 3.75E 05 5.23E 03 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00C-01 Zr-95 8.41E 01 5.90E 04 4.85E 02 1.19E 02 1.2SE 02 0.00E-01 0.00E-01 0.00E-01 NO-95 1.02E 04 1.48E 07 4.27E 04 1.76E 04 1.26E 04 0.00E-01 0.00E-01 0.00E-On Ru-103 2.09E 02 7.60E 03 6.25E 02 0.00E-01 1.30E 03 0.00E-01 0.00E-01 0.00E-01 Ru-106 1.77E 03 1.07E 05 1.41E 04 0.00E-01 1.67E 04 0.00E-01 0.00E-01 0.00E-01 Ag-110M t .43E 07 1.12E 09 2.95E 07 2.16E 07 3.08E 07 0.00E-01 0.00E-01 0.00E-01 Te-127M 4.51E 06 1.50E 07 3.72E 07 1.23E 07 9.16E 07 1.08E 07 0.00E-01 0.00E-01 Te-129M 6.69E 06 2.59E 07 4.34E 07 1.49E 07 1.09E 08 f.67E 07 0.00E-Of 0.00E-01 l

l-131 1.11E 09 8.99E 07 2.14E 09 2.52E 09 2.94E 09 8.28E 11 0.00E-01 0.00E-01 1-132 8.28E-01 1.88E 00 1.15E 00 2.33E 00 2.59E 00 1.09E 02 0.00E-01 0.00E-01 1-133  ? .27E 07 7.31E 06 2.97E 07 4.32E 07 5.08E 07 7.86E 09 0.00E-0I 0.00E-01 1-135 7.llE 04 7.06E 04 9.81E 04 1.95E 05 2.17E 05 1.75E 07 0.00E-01 0.00E-01 Cs-134 1.26E 10 3.38E 08 6.68E 10 I.25E 11 3.2tE 10 0.002-01 1.31E 10 0.00E-Ol_

Cs-136 4.11E 09 1.67E 08 3.75E 09 1.10E 10 4.39E 09 0.00E-01 8.98E 08 0.00E-01 Cs-137 8.17E 09 3.61E 08 9.85E 10 1.15E 11 3.10E 10 0.00E-01 1.25E 10 0.00E-01 Ba-140 9450E 05 4.53E 06 1.84E of 1.84E 04 4.38E 03 0.00E-01 1.13E 04 0.00E-01 Co-let 2.24E 02 9.SSE 05 3.13E 03 1.91E 03 5.88E 02 0.00E-01 0.00E-01 0.00E-01 Co-144 9.39E 03 9.61E 06 1.67E 05 6.86E 04 2.77E 04 0.00E-Ot 0.00E-01 0.00E-01 3 2

'A values in units of mese/yr oer micro-Ci/m for innalation and tritium, and in units of S meee/yr oer micro-Cl/sec for all etners. Reference Regulatory Guide 1.109, 3-48 Jew. 2

Page 79 of 164 TABLE 3.3-16 R VALLES FGt Tlf H.S. ROBINSON STEAN ELECTRIC PUNT' l (Reterence Regulatory Guide 1.109)

P4TMt4Y s inMas AGE GROUP = eduet Nucilde T. Body GI-Tract Gone Liver Kidney Thyroid L3 Skin 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 0.00E-01 0.00E-01 0.00E-01 Cc-51 9.99E 01 3.32E 03 0.00E-01 0.00E-01 2.28E 01 5.94E 01 1.44E 04 0.00E-01 wn-54 6.29E 03 7.12E 04 0.00E-01 3.95E 04 9.83E 03 0.00E-01 1.40E 06 0.0CE -01 Fe-59 1.05E 04 1.88E 05 1.17E 04 2.77E 04 0.00E-01 0.00E-01 1.01E 06 0.00E-01 Co-58 2.07E 03 1.06E 05 0.00E-01 1.58E 03 0.00E-01 0.00E-01 9.27E 05 0.00E-01 Co-60 1.48E 04 2.84E 05 0.00E-01 f.15E 04 0.00E 01 0.00E-01 5.96E 06 0.00E-01 Zn-65 4.65E 04 5.34E 04 3.24E 04 1.0X 05 6.89E 04 0.00E-01 8.63E 05 0.00E-01 Rb-86 5.89E 04 1.66E 04 0.00E-01 1.35E 05 0.00E-01 0.00E-01 0.00E-01 0.00E-01

$r-89 8.71E 03 3.49E 05 3.04E 05 0.00E-01 0.00E-01 0.00E-01 1.40E 06 0.00E-01

$r-90 6.09E 06 7.2tE 05 9.91E 07 0.00E-Of 0.00E-01 0.00E-01 9.59E 06 0.00E-CI Y-91 1.24E 04 3.84E 05 4.62E 05 0.00E-01 0.00E-0I 0.00E-01 f.70E 06 0.00E-01 Zr-95 2.32E 04 1.50E 05 1.07E 05 3.44E 04 5.41E 04 0.00E-01 1.77E 06 0.00E-01 NO-95 4.20E 03 1.04E 05 I .4tE 04 7.80E 03 7.72E 03 0.00E-08 5.04E 05 0.00E-01 Ru-103 6.57E 02 1.10E 05 1.53E 03 0.00E-01 5.82E 03 0.00E-01 5.04E 05 0.00E-ot Ru-106 8.71E 03 9.11E 05 6.90E 04 0.00E-01 1.33E 05 0.00E-01 9.35E 06 0.00E-01 Ag-110M 5.94E 03 3.02E 05 I.08E 04 9.99E 03 1.97E 04 0.00E-01 4.63E 06 0.00E-01 Te-12/M 1.57E 03 1.49E 05 1.26E 04 5.76E 03 4.57E 04 3.28E 03 9.59E 05 0.00E-01 Te-129M I.58E 03 3.83E 05 9.75E 03 4.67E 03 3.65E 04 3.44E 03 1.16E 06 0.00E-01 1-131 2.0M 04 6.27E 03 2.52E 04 3.57E 04 6.12E 04 1.19E 07 0.00E-01 0.00E-01 1-132 1.16E 03 4.06E 02 1.16E 03 3.25E 03 5.18E 03 1.14E 05 0.00E-01 0.00E-01 1-133 4.5'E 03 8.87E 03 8.6X 03 1.48E 04 2.58E 04 2.15E 06 0.00E-01 0.00E-01 1-135 2.56E 03 5.24E 03 2.68E 03 6.97E 03 1.11E 04 4.47E 05 0.00E-01 0.00E-01 Cs-134 7.27E 05 1.04E 04 3.72E 05 8.47E 05 2.87E 05 0.00E-01 9.75E 04 0.0C2-01 Cs-136 1.10E 05 1.17E 04 3.90E 04 1.46E 05 8.55E 04 0.00E-01 1.20E 04 0.00E-01 Cs-137 4.27E 05 8.39E 03 4.78E 05 6.20E 05 2.22E 05 0.00E-01 7.5tE 04 0.00E-01 Ba-140 2.SeE 03 2.18E 05 3.7X 04 4.90E 01 f.67E 01 0.00E-01 1.27E 06 0.00E-01 Ce-let 1. 5X 03 1.20E 05 1.99E 04 1.35E 04 6.25E 03 0.00E-01 3.61E 05 0.00E-01 Ce-l44 1.84E 05 8.15E 05 3.4X 06 1.4X 06 8.47E 05 0.00E-OI 7.76E 06 0.00E-01 2

'9 Values in un6ts of meem/yr per eiero-Cl/m for inhalation and tritium, and in units of m seem/yr per micro-Cl/sec for all others. Reference Regulatory Guide 1.109 3-49 4ev. 2

_ _ _ _ _ _____ _ _ . _ _ ~ _ _ _ _ _ _ _ _ _

Page 80 of 164 TASLE 3.3-17 R VALIES FOR T)E H.8. ROBINSON STEAN ELECTRIC PLANT' l (Reference Ro b .4 tory Guide 1.149)

P4THWAf n innal AGE group = Teen Nuclide T. Body' GI-Tract Bone Liver ICidney Thyroid g skin H-3 1.27E 03 1.27E 03 0.00E-01 1.27E 03 1.27E 03 1.27E 03 f.27E 03 1.27E 03 P-32 7.15E 04 9.27E 04 1.89E 06 1.09E 05 0.00E-01 0.00E-01 0.00E-01 0.00E-0I Cc-Si 1.35E 02 3.00E 03 0.0M-01 0.00E-01 3.07E 01 7.49E 01 2.09E 04 0.00E-01 Mn-54 8.39E 03 6.67E 04 0.00E-01 5.10E 04 1.27E 04 0.00E-01 l.98E 06 0.00E-01 Fe-59 f.43E 04 f.78E 05 1.59E 04 3.69E 04 0.00E-01 0.00E-01 1.53E 06 0.00E-01 Co-58 2.77E 03 9.5IE 04 0.00E-01 2.07E 03 0.00E-01 0.00E-01 1.34E 06 0.00E-01 Co-60 1.98E 04 2.59E 05 0.00E-01 1.51E 04 0.00E-01 0.00E-01 8.71E 06 0.00E-01 Zn-65 6.2 M 04 4.66E 04 3.85E 04 1.3 M 05 8.63E 04 0.00E-01 I.24E 06 0.00E-01 Rb-86 8.39E 04 1.77E 04 0.00E-01 f.90E 05 0.00E-01 0.00E-01 0.00E-01 0.00E-01

$r-89 1.25E 04 3.71E 05 4.34E 05 0.00E-01 0.00E-01 0.00E-01 2.4tE 06 0.00E-01 Sr-90 6.67E 06 7.64E 05 1.08E 06 0.00E-01 0.00E-01 0.00E-01 1.65E 07 0.00E-01 y-91 1.77E 04 4.08E 05 6.60E 05 0.00E-Of 0.00E-01 0.00E-01 2.93E 06 0.00E-01 Zr-95 3.15E 04 1.49E 05 f.45E 05 4.58E 04 6.73E 04 0.00E-01 2.68E 06 0.00E-01 No-95 5.66E 03 9.67E 04 1.85E 04 1.0M 04 9.99E 03 0.00E-01 1.50E 05 0.00E-01 Ru-103 8.95E 02 1.09E 05 2.10E 03 0.00E-01 7.42E 03 0.00E-01 7.82E 05 0.00E-01 Ru-106 1.24E 04 9.59E 05 9.83E 04 0.00E-01 1.90E 05 0.00E-01 1.61E 07 0.00E-01 Ag-110M 7.98E 03 2.72E 05 1.38E 04 1.31E 04 2.50E 04 0.00E-01 6.74E 06 0.00E-01 Te-127N 2.ISE 03 1.59E 05 1.80E 04 8.15E 03 6.5M 04 4.38E 03 1.65E 06 0.00E-01 Te-129M 2.24E 03 4.04E 05 I.39E 04 6.57E 03 5.18E 04 4.57E 03 1.97E Or 0.00E-01 1-131 2.64E 04 6.48E 03 3.54E 04 4.90E 04 8.39E 04 1.46E 07 0.00E-01 0.00E-01 1-132 1.57E 03 1.27E 03 1.59E 03 4.37E 03 6.91E 03 1.51E 05 0.00E-01 0.00E-01 1-133 6.21E 03 1.0X 04 1.2tE 04 2.05E 04 3.59E 04 2.92E 06 0.00E-Of 0.00E-Of I-135 3.48E 03 6.94E 03 3.69E 03 9.43E 03 1.49E 04 6.20E 05 0.00E-01 0.00E -01 Cs-134 5.48E 05 9.75E 03 5,02E 05 1.1M 06 3.75E 05 0.00E-01 1.46E 05 0.00E-OI Cs-136 1.37E 05 I.09E 04 5.14E 04 1.93E 05 1.10E 05 0.00E-01 I.77E 04 0.00E -01 Cs-137 1.IIE 05 8.48E 03 6.69E 05 8.47E 05 3.14E 05 0.00E-01 1.21E 05 0.00E-01 Ba-140 3.51E 03 2.28E 05 5.46E 04 6.69E 01 2.28E 01 0.00E-01 2.03E 06 0.00E-01 Co.let 2.16E 03 1.2% 05 2.84E 04 f.89E 04 8.87E 03 0.00E-01 6.13E 05 0.XE-01 Ce-144 2.62E 05 8.6M 05 4.88E 06 2.02E 06 1.21E 06 0.00E-01 1.33E of 0.00E-01 i

3 2

'51 values in units of meee/yr oor e6cro-Cl/m for inMala* ion and treflue and in units of 3 aree/yr oer m6cro-Ci/sec for Ali oteers. Reference Regulatory Guide 1.109. l 3-50 4ev. 2

Pagt 81 of 164 TAeLE 3.3-18 R VAllES FGt TIE H,8. RW!!NSGI STEAM ELECTRIC Pt. ANT

  • l (Ref erence Re991 story Guide 1.109)

PATHWAY e innel AM GROUP a Child .

Nuclide g GI-Trect Bone Liver Kloney Thyroid g Skin H-3 1.12E 03 1.12E 03 0.00E-Ol 1.12E 03 1.12E 03 1.12E 03 1.12E 03 I.12E 03 P-32 9.86E 04 4.21E 04 2.60E 06 1.14E 05 0.00E-01 0.00E-01 0.00E -01 0.00E -01 Cr-51 1.54E 02 1.08E 03 0.00E-01 0.00E-Of 2.43E 01 8.53E 01 1.70E 04 0.coc-01 Mn-54 9.5M 03 2.29E 04 0.00E-01 4.29E G4 ,1.0M 04 0.00E-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 0.00E-01 Co-58 3.16E 03 3.43E 04 0.00E-01 f.77E 03 0.00E-01 0.00E-01 1.10E 06 0.00E -01 Co-60 2.26E 04 9.61E 04 0.00E-01 1.31E 04 0.00E-01 0.00E-01 7.06E 06 0.00E-01 Zn-65 7.02E 04 1.63E 04 4.25E 04 f.13E 05 7.13E 04 0.00E-Of 9.94E 05 0.00E-01 RD-86 1.14E 05 7.98E 03 0.00E-01 1.98E 05 0.00E-01 0.00E-01 0.0 M -01 0.00E-01 Sr-89 1.72E 04 1.67E 05 5.99E 05 0.00E-01 0.00E-01 0.00E-01 2.l!E 06 0.00E-01 Sr-90 6.4 X 06 3.43E 05 1.01E 08 0.00E-01 0.00E-Ol 0.00E-01 1.47E 07 0.00E-01 t-91 2.4M 04 f .84E 05 9.1X 05 0.00E-01 0.00E-01 0.00E-01 2.62E 06 0.00E-01 fr-95 3.69E 04 6.10E 04 1.9 % 05 4.17E 04 5.95E 04 0.00E-01 2.23E 06 0.00E-01 ND-95 6.54E 03 3.69E 04 2.35E 04 9.16E 03 8.StE 03 0.0 M -01 6.13E 05 0.00E-01 Ru-103 1.07E 03 4.47E 04 2.79E 03 0.00E-01 7.02E 03 0.00E-01 6.6fE 05 0.00E -01 Ru-106 1.69E 04 4.29E 05 1.36E 05 0.00E-01 1.84E 05 0.0M-01 1.43E 07 0.00E-01 Ag-110M 9.lX 03 1.00E 05 1.64E 04 1.14E 04 2.12E 04 0.00E-01 5.47E 06 0.00E-Of 7e-127M 3.0lE 03 7.1X 04 2.48E 04 8.53E 03 6.35E 04 6.06E 03 1.48E 06 0.00E-Of 7e-129M 3.04E 03 1.8tE 05 1.9X 04 6.84E 03 5.02E 04 6.32E 03 f.76E 06 0.00E -01 1-131 2.7N 04 2.84E 03 4.80E 04 4.80E 04 7.87E 04 1.62E 07 0.00E-01 0.00E-01 6-132 1.87E 03 3.20E 03 2.llE 03 4.06E 03 6.24E 03 1.9M 05 0.00E-01 0.00E-01 1 133 7.68E 03 5.47E 03 1.66E 04 2.03E 04 3.37E 04 3.84E 06 0.00E-01 0.00E-01 1-135 4.14E 03 4.4M 03 4.91E 03 8.72E 03 1.34E 04 7.91E 05 0.00E-01 0.00E-Oi Cs-134 2.24E 05 3.84E 03 6.50E 05 1.01E 06 3.30E 05 0.00E-01 1.21E 05 0.00E -01 Cs-136 1.16E 05 4.17E 03 6.50E 04 f.7tE OS 9.53E 04 0.00E-01 1.45E 04 0.00E -01 Cs-137 1.28E 05 3.61E 03 9.05E 05 8.24E 05 2.82E 05 0.00E-01 1.04E 05 0.00E 01 Be-140 4'.3X 03 1.0M 05 7.39E 04 6.47E 01 2.11E 01 0.00E-01 1.74E 06 0.00E-01 Co-141 2.89E 03 5.65E 04 3.9 N 04 1.95E 04 8.5M 03 0.00E-01 5.4M 05 0.00E -01 Ce-144 3.61E 05 3.88E 05 6.76E 06 2.11E 06 1.17E 06 0.00E-Ol I.19E 07 0.00E-01

'81 values in units of eres/yr per elcro-CI/m 3 ter inneistion .snd telflum, s6o in units of *

  • rea/yr per micro-C1/sec for all others. Reference Re99tatory Guide 1.109.

3-56 Rev. 2

P4:gn 82 of 164 TASLE 3.3-19 R VAltKS FOR T}E H.S. ROBINSON STEAN ELECTRIC PLANT

PATHt4f s inhel 4GE GROUP s Infant NucIlde T. Body GI-Tract sono Liver Eldney Thyroid M Skin H-3 6.46E 02 6.46E 02 0.00E-Of 6.46E 02 6.46E 02 6.46E 02 6.46E 02 6.46E 02 P-32 7.73E 04 1.61E 04 2.0% 06 1.12E 05 0.00E-01 0.00E-Ol 0.00E-01 0.00E-01 Cr-51 8.93E 01 3.56E 02 0.00E-01 0.00E-01 1.32E 01 5.75E Of 1.28E 04 0.00E-01 wn-54 4.98E 03 7.05E 03 0.00E-01 2.53E 04 4.98E 03 0.00E-01 9.98E 05 0.00E-01 Fe-59 9.46E 03 2.47E 04 1.35E 04 2.35E 04 0.00E-01 0.00E-01 1.01E 06 0.00E-01 Co-58 f.82E 03 1.11E 04 0.00E-01 1.22E 03 0.00E-01 0.00E-01 7.76E 05 0.00E-01 Co-60 1.18E 04 3.1 % 04 0.00E-01 8.01E 03 0.00E-01 0.00E-01 4.50E 06 0.00E-01 Zn-65 3.10E 04 5.13E 04 1.93E 04 6.25E 04 3.24E 04 0.00E-01 6.46E 05 0.00E-01 40-86 8.81E 04 3.03E 03 0.00E-01 1.90E 05 0.00E-01 0.00E-01 0.00E-ol 0.00E -01

$r-69 1.14E 04 6.39E 04 3.97E 05 0.00E-01 0.00E-01 0.00E-01 2.0!E 06 0.00E-01

$r-90 2.59E 06 1.31E 05 4.08E 07 0.00E-01 0.00E-01 0.00E-01 1.12E 07 0.00E-01 y-91 1.57E 04 7.02E 04 5.87E 05 0.00E-01 0.00E-01 0.00E-01 2.45E 06 0.00E-01 Zr-95 2.03E 04 2.17E 04 1.15E 05  ?.78E 04 3.10E 04 0.00E -01 I.75E 06 0.00E-01 NO-95 3.77E 03 1.27E 04 1.57E 04 6.42E 03 4.7tE 03 0.00E-01 4.78E 05 0.00E -01 Ru-103 6.78E 02 1.6tE 04 2.01E 03 0.00E-01 4.24C 03 0.00E-01 5.51E 05 0.00E -01 Ru-106 1.09E 04 1.64E 05 8.67E 04 0.00E-01 1.06E 05 0.00E-01 1.15E 07 0.00E-01 ag-110M 4.99E 03 3.30E 04 9.97E 03 7.2tE 03 1.09E 04 0.00E-01 3.66E 06 0.00E-01 re-127N 2.07E 03 2.7M 04 1.66E 04 6.89E 03 3.75E 04 4.86E 03 1.31E 06 0.00E-01 Te-I29M 2.2M 03 6.89E 04 1.41E 04 6.08E 03 3.17E 04 5.47E 03 1.68E 06 0.00E-01 1-131 1.96E 04 1.06E 03 3.79E 04 4.4M 04 5.17E 04 1.48E 07 0.00E-01 0.00E-01 1-132 1.26E 03 1.90E 03 t.69E 03 3.54E 03 3.94E 03 1.69E 05 0.00E-01 0.00E-01 1-133 5.59' 03 2.15E 03 1.3M 04 1.92E 04 2.24E 04 3.55E of 0.00E-01 0.00E-Of I-135 2.77E 03 1.8M 03 3.86E 03 7.59E 03 8.46E 03 6.95E 05 0.00E-01 0.00E-01 Cs-134 7.44E 04 1.3M 03 3.96E 05 7.0M 05 1.90E 05 0.00E-01 7.95E 04 0.00E 01 Cs-136 5.28E 04 1.4M 03 4.8X 04 1.34E 05 5.63E 04 0.00E-01 1.17E 04 0.00E-01 Cs-137 4,54E 04 1.3M 03 5.48E 05 6.11E 05 f.72E 05 0.00E-01 7.12E 04 0.00E-01 9e-140 2.89E 03 3.8X 04 5.59E 04 5.59E 01 1.34E of 0.00E-01 1.5M 06 0.00E-01 Co-let 1.99E 03 2.15E 04 2.77E 04 1.36E 04 5.24E 03 0.00E-01 5.16E 05 0.00E-01 C4-144 1.76E 05 1.48E 05 3.19E 06 1.21E 06 5.37E 05 0.00E-01 9.8K 06 0.00E-01 2

'A values in units of area /yr ser ocro-Ci/* for innelation and telflue, and in un6 ts of m mees /yr per micro-Ci/sec for all others. Reference Regulatory Guide 1.109. l 1-52 Rev. 2

l Pagm 83 of 164

- \

l TABLE 3.4-I IfG STl0N'008E R FACTORS GIASS-COW-WILK PATNWAY (IPFANT)

(Reference NUREG 0133)

Nuclide Gone , Liver T. Gody Thyroid Kidney u L,ung GI-LLI H-3 NO 2.38E3 2.38E 3 2.38E3 2.38E 3 2.38E 3 2.38E 3 Cc-51 NO NO I.6tE5 1.05E 5 2.30E4 2.05E5 4.7tE6 un-54 NO. 3.89E7 8.83E6 NO 8.63E6 NO t .43E 7 Fe-55 1.35Es 8.72E7 2.33E7 NO NO 4.26E7 f.ItE7 Fe-59 2.26E8 3.94E 8 1.55E8 NO NO 1.17E8 f.88E9 Co-58 NO 2.43E7 6.06E7 NO NO NO 6.05E7 Co-60 ND 8.81E7 2.08E8 NO NO NO 2.10E8 Ni-63 3.49E10 2.16E9 1.21E9 NO NO NO l.07E8 I Zn-65 5.55E9 1.90EIO 8.78E9 NO 9.24E9 NO l.61E10 Ab-86 NO 2.23E10 1.1X 10 NO NO NO 5. 70E 8 i Sr-89 NO 1.45E6 9.98E5 NO NO NO 2.93E 5 i

$r-90 1.22E11 NO 3.10E10 NO NO NO 1.52E9 Y-91 7.33E 4 NO 1.95E3 NO NO NO 5.26E6 Zr-95 6.84E 3 1.67E3 1.18E3 NO 1.8M3 NO 8.30E5 Nb-95 5.93E 5 2.44E 5 1.4tES NO 1.75E5 NO 2.06ES Ru-103 8.68E3 NO 2.90E3 NO 1.8tE4 NO 't.06E5 Ru-306 1.90E 5 NO 2.38E 4 NO 2.25E5 NO I.44E6 Ag-110M 3.86E3 2.82E8 1.87E8 NO 4.03E8 NO 1.46E10 Te-125N l.51E8 5.04E 7 2.04E7 5.07E7 NO NO 7.18E 7 Te-127M 4.2tE8 1.40E8 5.10E7 1.22E8 1.04E9 NO 1.70E8 Te '29M 5.60E8 1.92E8 8.6N7 2.15E8 -

1.40E9 NO 3.34E8 l-I31 2.72E9 3.21E9 1.41E9 1.05E12 3.75E9 NO l.15E8 l-133 3.09E7 4.51E7 I .3M7 8.21E9 5.31E7 NO 7.64E6 Cs-134 3.65E!0 6.80E10 6.87E9 NO 1.75E10 7.18E9 1.85E8 Cs-136 2.03E9 5.9629 2.22E9 NO 2.37E9 4.85E8 9.05E7 Cs-137 5.15E10 6.02E10 4.27E9 NO 1.62E10 6.55E9 1.88E 8 Ba-140 2.4tE8 2.4 t E 5 1.24E 7 NO 5.73E4 1.48E5 5.92E7 Co-141 ,. 4.34E 4 2.64E 4 3.llE3 NO 8.16E3 NO 1.37E7 Ce-144 2.33E6 9.52E 5 1.30E5 NO 3.85E 5 NO 1.33E8 .

Pr-143 1.49E3 5.56E2 7.37El NO 2.07E2 No 7.85E5 Nd-147 8.86E2 9.10E2 5.57El NO 3.5122 No 5.77E5 l

l l

3 2

t valuas in units of meee/yr ser siero-Cl/m ter innatation and tritium and in unets of 3 l mese/yr per eiero-Ci/see for sti otners. Reference NOREG 0133.

Sev. 2 I - -- _

. _- _ _3-53___.___. __ , _

Pags 84 of 164 inaLE 3.4-2 INEESTION DOSE R FACTGt5 GtASS-CIIII-MILK PATHIIAY (CHILD) i (Reference NUREG 0133) i I

Nuclide Bone Liver T. Gody Thyroid Kidney b GI-LLI H-3 NO I.57E3 f.57E3 1.57E3 1.57E3 1.57E3 I.57E3 Cr-51 NO NO 1.02E5 5.66E4 1.55E 4 I .03E 5 5.41E6 Mn-54 NO, 2.09E 7 5.58E6 NO 5.37E6 NO t.76E7 Fe-55 1.12E8 5.93E7 1.84E7 NO NO 3.35E7 I.10E7 Fe-59 1.21E8 1.96E8 9.75E7 NO NO 5.67E7 2.04E8 Co-58 NO 1.21E7 3.72E7 NO NO NO 7.08E7 Co-60 NO 4.32E7 1.27E8 NO NO NO 2.39E8 Ni-63 2.96E10 1.59E9 1.01E9 NO NO NO 1.07ES Zn-65 4.13E9 1.10E10 6.85E9 ND 6.94E9 NO I.93E9 Rb-86 NO 8.77E9 5.39E9 NO NO NO 5.64E8

$r-89 6.69E9 NO 1.91E8 NO NO NO 2.59E8

$r-90 1.12E11 NO 2.83EIO NO NO NO 1.50E9 Y-91 3.91E 4 NO I .04E3 NO NO NO 5.21E6 l Zr-95 3.85E3 8.46E2 7.53E2 NO l.2tE3 NO 8.83E5

  • Nb-95 3.18E5 I .24E 5 8.84E4 NO l.16E5 NO 2.29E8 Ru-103 4.29E 3 NO 1.65E3 NO 1.08E4 NO 1.11E5 Ru-106 9.24E 4 NO 1.15E4 NO 1.2SE5 NO 1.44E6 Pg-llc 9I 2.09ES 1.41L 8 I .13E8 NO 2.63E8 NO 1.68E10 Te-125M 7.38E7 2.00E7 9.84E6 2.07E 7 NO NO 7.12E7 Te-127M 2.08E8 5.60E7 2.47E7 4.97E7 5.93E8 ND 1.68E8 Te-129M 3.17E8 8.85E7 4.92E7 1.CX8 9.31E8 NO 3.87E8 l l-131 1.30E9 1.31E9 7.46E8 4.34E l l 2.15E9 NO 1.17E8
  • i-133 1.47E7 1.82E7 6.87E6 3.37E9 3.03E7 ND 7.32E6 Cs-134 2.26E10 3.71E10 7.84E9 NO 1.15E10 4.13E9 2.00E8 Cs-136 1.04E 9 2.85E9 1.84E9 NO 1.52E9 2.26E8 1.00E8 l

Cs-137 3.2N10 3.09E10 4.55E9 NO 1.01E10 3.62E9 l .93E 8 l

Ba-I40 1.17E8 1.03E5 6.84E6 NO 3.34E 4 6.12E 4 5.94E7 I

Co-141 ,2.19E4 I.09E4 1.6M3 NO 4.78E3 NO 1.36E7 Co-144 't.62E6 5.09E5 8.66E 4 NO 2.8M5 NO l.33E8 Pr-143 7.19E2 2.16E2 3.57El NO 1.17E2 NO 7.76E5 Nd-147 4.47E2 3.62E2 2.00E1 NO 1.99E2 NO 5.73E5 l

3 2

'81 values in units of eree/yr per micro-Ci/m ter innalation and tritium, and in units of m aree/yr per e6cro-Ci/sec for all otners. Reference NUREG 0133.

3-54 Rev. 2

Page 85 of 164 TABLE 3.4-3 INESTION DOSE R FACTORS GIASS-COW-MILX PATHWAY (TEEN)

(Retyrence NUREG 0133)

Nuclide Bone Liver T. Body Thyroid Kidney @ GI-LLI H-3 NO 9.94E2 9.94E2 9.94E2 9.94E2 9.94E2 9.94E2 Cr-51 NO NO 5.00E4 2.78E 4 1.09E4 7.13E4 8.40E6 Mn-54 NO, l.40E7 2.78CS NO 4.18E6 NO 2.8 7E 7 Fe-55 4.45E7 3.16E7 7.36E6 NO NO 2.00E 7 1.37E7 Fe-59 5.21E7 1.22E8 4.70E7- NO ND 3.87E7 2.86E8

- Co-58 NO 7.95E6 1.83E7 NO NO NO 1.10E8 Co-60 NO I .64E6 3.70E6 NO NO NO 3.I4E7 Ni-63 1.82E10 8.35E8 4.01E8 NO NO NO 1.33E8 Zn-65 2.11E9 7.32E9 3.41E9 NO 4.68E 9 NO 3.10E 9 Rb-86 NO 4.73E9 2.22E9 NO NO NO 6.99E8 Sr-89 2.70E9 NO 7.73E7 NO NO NO 3.22E8 Sr-90 6.61E10 NO 1.63EIO NO NO NO 1.86E9 Y-91 1.58E4 NO 4.24E2 NO NO NO 6.48E6 Zr-95 1.66E3 5.22E2 3.59E2 NO 7.68E2 NO 1.21E6 NO-95 1.41E5 7.80E4 4.29E 4 NO 7.56E4 NO 3.34E8 Ru-103 f.SIE3 NO 7.74E2 NO 6.39E3 NO 1.5tE5 Ru-iO6 3.75E4 NO 4.73E3 NO 7.24E4 NO 1.80E6 Ag-110M 9.64E7 9.12E7 5.55E7 NO l.74E8 NO 2.56E10 Te-125M 3.00E7 1.08E7 4.02E6 8.39E6 NO NO 8.36E7 Te-127M 8.44E 7 2.99E7 1.00E7 2.0147 3.42E8 NO 2.10E8 Te-129M 1.11E8 4.11E7 I.75E7 3.57E7 4.63E8 NO 4.16E8 l

l-131 5.38E8 7.53E8 4.05E 8 2.20E11 1.30E9 NO 1.49E8 l-133 6.05E6 l .03E7 3.13E6 1.43E9 1.80E7 NO 7.77E6 Cs-134 9.81E9 2.31E10 1.07E10 NO 7.34E9 2.80E9 2,87E8 Cs-136 4.59E8 1.8CE9 1.21E9 NO 9.82E8 1.55E S 1.45E8 Cs-137 1.34E10 1.78E10 6.20E9 NO 6.06E9 2.35E9 2.5328 S4-140 4.87E7 5.96E4 3.14E6 NO 2.02E 4 4.01E 4 7.5 t E 7 Ce-141 8.89E3 5.93E3 6.8tE2 NO 2.79E3 NO 1.70E7 Ce-144 '6.5aES 2.72E5 3.54E 4 Pd) 1.63E 5 NO l .65E 8 Pr-143 2.89E2 1.15E2 1.44El NO 6.73El NO 9.53E5 Nd-147 1.82E2 l'.98E2 1.19El NO 1.16E2 NO 7.15E5 3 2

'A values in units of mese/yr per micro-Ci/m for innalation and tritium, and in una ts at $

meee/yr ser micro-Ci/see for all otners. Reference NUREG 0133.

3-55 Rev. 2

Page 86 of 164 TABLE 3.4-4 INGESTICM 00SE R FACTORS GtASS-COW-MILX PATHWAY (ADULT)

(Reference NUREG 0133)

Nuclide sone Liver T. Gody Thyroid , Kidney L3 GI-LLI H] ND 7.63E2 7.63E2 7.63E2 7.63E2 7.63E2 7.53E2 Cr-5i NO NO 2.86E4 1.7tE4 6.27E 3 3.80E4 7.20E6 Mn-54 NU, 8.40E6 f.60E6 NO 2.50E 6 NO 2.57E 7 Fe-55 2.51E7 1.73E7 4.04E6 NO NO 9.67E6 9.95E6 Fe-59 2.99E7 7.02E7 2.69E 7 NO NO I.96E7 2.34E8 Co *8 NO 4.72E6 1.06E7 NO NO NO 9.5tE7 Co-60 NO I.64E7 3.62E7 NO NO NO 3.08E8 Ni-63 6.73E9 4.66E8 2.27E8 NO NO NO 9.73E7 Zn-65 1.37E9 4.37E9 1.97E9 NO 2.92E9 NO 2.75E9 Rb-86 NO 2.59C9 1.21E9 NO NO NO 5.11ES Sr-89 1.47E9 NO 4.21E7 NO NO NO 2.35E8 Sr-90 4.69E10 NO 1.15Eto NO NO NO 1.35E9 Y-91 8.6CE3 NO 2.29E2 NO NO NO 4.73E6 Zr-95 1.06E3 3.04E2 2.06E2 NO 4.77E2 NO 9.63E 5 NO-95 5.65E5 2.44E 5 9.59E3 NO 2.43E5 NO 1.95E9 Ru-103 1.02E 3 NO 4.39E2 NO 3.89E 3 No t .19E 5 Ru-106 2.04E4 NO 2.58E3 NO 3.94E 4 NO t.32E6 ag-110M 5.83E7 5.39E 7 3,20E7 NO 1.06E8 NO 2.20EIO Te-125M 1.63E7 5.90E6 2.18E6 4.90E6 6.63E7 NO 6.50E7 Te-127M 4.58E7 1.64E7 5.58E6 1.17E 7 1.8628 NO 1.54E8 Te-129M 6.05E7 2.26E7 9.58E6 2.08E7 2.53E8 NO 3.0$ES t-131 2.97E8 4.24E8 2.'43Ei8 1.39 Elf 7.27E8 NO 1.12E8 l-133 3.31E6 5.76E7 1.75E6 8.46E8 ' .00E 7 NO 5.17E6 Cs-134 5.65E9 1.34E10 1.10E10 NO 4.33E9 f.44E9 2.35E8 Cs-136 2.69E8 1.06E9 7.65E8 NO 5.92E 8 8.11E7 1.21E8 Cs-137 7.38E9 1.01E10 6.61E9 NO 3.43E9 1.14E9 f.95ES Ba-140 2.70E7 3.39E4 1.77E6 NO I.15E4 1.94E4 5.55E7 Co-141 4.85E3 3.28E3 3.72E2 NO l.52E3 NO 1.25E7 Co-led '3.58E5 I .50E 5 1.92E 4 NO 8.87E 4 NO 1.21E8 Pr-143 1.94E2 7.79El 9.62E0 NO 4.49El NO 8.50E5 Nd-147 9.49El P.10E2 6.56E0 NO 6.41El NO 5.26E5 2

'9 Values in units of meem/yr per micro-Ci/=' for innalation and tritium. and in anits of m ores /yr per siero-Cl/see for all otners. Reference NOREG 0133.

3-56 4ev. 2

Peg 2 87 of 164 TAetE 3.4-5

~

'IPESTION DOSE R FACTORS GIASS-GN-4 EAT PATHIAY (OllLD)

(Reference NUREG 0133)

Nuclide Bone Liver" T. Gody Thyroid Kidney un L,u,ng Gl-LLI H-3 NO 2.34E2 2.34E2 2.34E2 2.34E2 2.34E2 2.34E2 Cr-51 NO NO 8.82E 3 4.89E3 1.34E3 8.93E3 4.68E 5 un-54 NO, 7.99E6 2.13E6 NO 2.24E6 NO 6.70E6 Fe-55 4.57E8 2.42E8 7.50E7 NO NO 1.37ES 4.49E7 Fe-59 3.81E8 6.16E8 3.07E8 NO NO 1.79E 8 6.42E8 Co-58 NO 1.65E7 5.04E 7 NO NO NO 9.60E 7 Co-60 NO 6.93E7 2.04E8 NO NO NO 3.84E8 Ni-63 2.91E10 1.56E9 9.91ES NO NC NO 1.05ES Zn-65 3.76E 8 1.00E9 6.22E8 NO 6.30E 8 NO 1.76E8 Rb-86 NO 5.77E8 3.55ES NO NO NO 3.71E7 Sr-89 4.92E8 NO l .40E 7 NO NO NO l .90E 7 Sr-90 1.04E 10 NO 2.64E9 NO NO NO l.20E8 Y-91 1.81E6 NO 4.83E 4 NO NO NO 2.41 E 8 2r-95 2.69E6 5.9 t E 5 5.26E 5 NO 8.46E5 NO 6.16E8 NO-95 3.09E6 1.20E6 8.61E5 NO 1.13E6 NO 2.23E9 Ru-103 1.55E8 NO 5.97E7 NO 3.9tE8 NO 4.02E 9 Ru-106 4.44E9 NO 5.54E8 NO 5.99E9 NO 6.90E10 Ag-IlON 8.41E6 5.68E6 4.54E6 NO 1.06E7 NO 6.76E8 Te-125M 5.69E8 1.54E 8 7.59E 7 1.60E8 NO NO 5.49E8 Te-127M l.77E9 4.78E 8 2.llE8 4.24E8 5.06E9 NO 1.44E9 Te-129M 4;78E9 5.05E8 2.81E8 5.83E8 5.3tE9 NO 2.2tE9 l-131 1.66E7 1.67E7 9.49E6 5.52E9 2.74E7 NO I.49E6 1-133 1.99E-1 2.46E-1 9.31E-2 4.57El 4.10E-1 NO 9.91E-2 Cs-134 9.2208 1.51E9 3.19E8 NO 4.69E8 1.68E 8 5.16E6 Cs-136 1.73E7 4.74E7 3.07E7 NO 2.53E7 3.77E6 f.67ES Cs-137 1.3M9 1.28E9 1.88E8 NO 4.16E8 1.50E8 7.99E 6

, Ba-140 4.39E7 3.85E4 2.56E6 NO I.25E4 2.29E4 2.22E7 l

Ce-let 2.22E4 I.11E4 1.64E3 NO 4.86E3 NO l.38E7 l

Co-144 2.32E6 7'.26ES 1.24E 5 NO 4.02E5 NO I.89E8 Pe-143 3.35E 4 1.01E4 1.66E3 ND 5.45E3 NO 3.61E 7 Nd-147 1.18E 4 9.60E3 7.43E2 NO 5.27E3 NO l .52E 7

'9 values in units of meee/yr oer micro-Cl/m 3 for innalation ano triflue, and in units of E sree/yr oer s6ero-Cl/sec eer all otr'ers, me terence NuREG 0133.

3-57 cow. 2

1 Page 88 of 164 TAetE 3.5-4 IPESTION 00$E R FACTORS GIASS-03W-4 EAT PATNIIAY (TEEN)

(Reference NUREG 0133)

Mucilde Bone Liver T. Body Thyroid Kidney L 3 GI-LLI H-3 NO I .94E 2 1.94E 2 8 .94E 2 I .94E 2 f .94E 2 I .94E 2 Cr-Si NO NO 5.65E 3 3.14E3 1.24E 3 8.07E3 9.49E5 Mn-54 NO, 6.98E6 1.39E6 NO 2.08E6 NO 1.4 3E 7 Fe-55 2.38E 8 1.69ES 3.93E7 NO NO 1.07E 8 7.30E7 Fe-59 2.15E8 5.01E8 1.94E 8 NO NO l.58E8 1.19E9 Co-58 NO I.4tE7 3.25E7 NO NO NO 1.94E8

~

Co-60 NO 5.83E7 1.3tE8 NO NO NO 7.60E8 Ni-63 1.52E10 1.07E9 5.15E8 NO NO NO 1.7tE8 Zn-65 2.50E8 8.69E8 4.06E 8 ND 5.56E8 NO 3.68E 8 Rb-86 NO 4.06E8 1.9tE8 NO NO NO 6.01 E 7 Sr-89 2.60E8 NO 7.44E6 NO NO NO 3.09E 7

$r-90 8.0$E9 NO I.99E9 NO NO NO 2.26E8 Y-91 9.56E5 NO 2.56E 4 NO NO NO 3.92E8 Zr-95 I.51E6 4.78E 5 3.2SE5 NO 7.02E5 NO l .10E 9 Ne-95 1.19E6 9.93E5 5.47E 5 ND 9.63E5 NO 4.25E9 Ru-IO3 8.58E7 NO 3.67E 7 NO 3.03E8 ND 7.17E9 Ru-106 2.36E9 NO 2.97ES NO 4.55E9 NO 1.13E11 Ag-110M 5.07E6 4.80E6 2.92E6 NO 9.15E6 NO 1.35E9 Te-125m 3.03E8 f.09E6 4.0$E7 8.47E7 NO NO 8.94E8 Te-127N 9.42E 8 3.34E8 1.12E 8 2.24E8 3.82E9 NO 2.35E9 7e-129M 9.61E8 3.57E8 1.52E8 3.10E8 , 4.02E9 NO 3.61E9 t-131 8.97E6 1.26E7 6.75E6 3.66E9 2.16E 7 NO 2.48E6 l-133 1.07E-l I.82E-l 5.54E-2 2.54El 3.19E-1 NO 1.38E -l Cs-134 5.23E8 1.2X9 5.71E8 NO 3.91E8 1.49E8 1.53E7 Cs-136 9.96E6 3.92E7 2.63E 7 NO 2.13E7 3.36E6 3.15E6 Cs-137 7.24E8 9.6M8 3.36E8 4 3.28E 8 1.27E 8 f.37E7 Be-140 2.39E7 2.9 N 4 1.54E6 NO 9.94E3 f .97E 4 3.69E 7 Ce-141 ,

1.18E4 7.88E3 9.05E2 NO 3.7tE3 NO 2.25E 7 Ce-144 "1.23E6 5.08E5 6.60E4 No 3.04E5 NO 3.09E 8 Pr-I43 1.76E4 7.03E 3 8.76E2 NO 4.09E 3 NO 5.79E 7 Nd-147 6.32E3 6'.87E 3 4.12E2 N0 4.04E 3 NO - 2.48E7 3 2

'9 values in units of eree/yr per stero-C1/m for innalation end triflun, and in units of 5 mrom/yr per micro-Cl/see for sti others. Reference NORE0 0133.

3-58 Rev. 2

P:gn 89 of 164 TABLE 3.4-7 IleESTION 008E R FACTORS GIASS-COW-4 EAT PATHIIAY (Acut.T) tReference NUREG 0133)

Nuclide Bone Liver T. Gody Thyroid Kidney Lung GI-LLI H-3 NO 3.25E2 3.2SE2 3.25E2 3.25E2 3.25E2 3.25E2 Cr-51 NO NO 7.06E3 4.22E3 1.56E 3 9.37E3 1.78E6 Mn-54 NO, 9.16E6 1.75E6 NO 2.72E6 NO 2.80E7 Fe-55 2.93E8 2.02E8 4.72E7 NO NO 1.13E8 1.t6E8 Fe-59 2.69E8 6.32E8 2.42E 8 NO NO l.76ES 2.11E9 Co-58 NO l.83E7 4.10E7 NO NO NO 3.70E8 Co-60 NO 7.52E7 1.66E8 NO NO NO l.41E9 Ni-63 1.89EIO .l.31E9 6.33E8 NO NO NO 2.73E8 Zn-65 3.56E8 1.13E9 5.12E8 NO 7.58E8 NO 7.13E8 Re-86 NO 4.86E8 2.27E8 NO NO NO 9.59E 7 Se-89 3.08E8 NO 8.83E6 No NO NO 4.93E7 Sr-90 1.24EIO NO 3.05E9 NO NO NO 3.59E8 Y-W I.13E6 NO 3.03E4 NO NO NO 6.24E8 Zr-95 f.89E6 6.06E5 4.10E 5 NO 9.51E5 NO 4 .92E 9 NO-95 2.29E6 1.28E6 6.86E5 NO l.26E6 NO 7.74E9 Ru-103 1.05E8 NO 4.54E 7 NO 4.02E8 NO 1.23Elo Ru-106 2.80E9 No 3.54E8 NO 5.40E9 NO 1.8IEli Ag-110M 6.70E6 6.19E 6 3.69E6 NO 1.22E7 NO 2.53E9 Te-125M 3.59E8 1.30E8 4.81E7 1.08E 8 f.46E9 NO 1.43E9 Te-127M 1.12E9 3.99E8 f.36E8 2.85E8 4.53E9 NO 3.74E9 fe-129M I .15E9 4.28E8 1.82E8 3.94E8 4.79E9 ND 5.78E9 l-131 1.08E7 1.547 8.85E6 5.06E9 2.65E7 NO 4.07E6 l-133 1.28E-I 2.23E-l 6.78E-2 3.27El 3.88E-I NO 2.00E -l Cs-l?# 6.57E8 1.56E9 1.29E9 NO 5.06E8 1.68E8 2.74E 7 Cs-136 1.28E 7 5.04E7 3.63E7 NO 2.80E 7 3.84E6 5.73E6 Cs-137 8.72E8 1.19E9 7.81E8 NO 4.05ES 1.35E8 2.31E7 Ba-140 2.90E7 3.64E4 1.90E6 NO l .24E 4 2.08E 4 5.96E7 Ce-141 1.41E4 9.51E3 1.08E3 No 4.4tE3 NO 3.63E 7

. Co-144 ,. l .46E6 6.09ES 7.82E4 NO 3.61E S NO 4.93E8 Pr-143 2.09E4 8.39E3 1.04E3 NO 4.85E3 NO 9.17E7 Nd-147 7.17E3 8,.29E 3 4.96E2 No 4.85E3 NO 3.99E7

'54 values in units of meee/yr oor micro-CI/m 3 for innalation and tritium, and in units of *2 mee*/yr ser encro-Cl/see for all others. Ref erence NUREG 0133.

3-59 8ev. 2

Pags 90 of 164 TABLE 3.4-8 IMESTION DOSE R FAc! ORS VE4ETATIG8 PATMIAY (041LD) tAsferonce NUREG 0133)

Nuclide Bone Liver T. Gody Thyroid Kidney L 3 G I -L t.

H-3 ND 4.0lE3 4.01E 3 4.0lE3 4.01E3 4.01E3 4.01E3 Cr-51 W NO l.18E5 6.54E 4 1.79E 4 1.19E5 6.25E6 Mn-54 NO 6.61ES 1.76E8 NO l.85E8 NO 5.55ES Fe-55 8.00E 8 4.24E8 1.31E8 NO NO 2.40E 8 7.36E7 Fe-59 4.07E8 6.58E8 3.28E8 NO NO I.91ES 6.95ES

, Co-58 NO 6.47E7 f.98E8 NO NO NO 3.77ES Co-60 ND 3.78E8 1.12E9 NO NO NO 2.10E 9 Ni-63 3.95E10 2.llE9 1.34E9 NO NO NO 1.42E8 2n-65 8.13E8 2.17E9 1.35E9 NO 1.36E A NO 3.SOES Ab-86 ND 4.5?E8 2.78E8 NO NO NO 2.91E7 Se-89 3.74E 10 NO 1.07E9 NO NO NO 1.45E9 Sr-90 1.24E12 NO 3.15 Ell NC NO NO ' 67E10 Y-91 f.87E7 NO 5.01E5 NO NO NO 2.49E9 2r-95 3.92E6 8.63E 5 7.68E 5 NO I.23E6 NO 9.00E8 Ne-95 4.10E 5 1.60E5 1.14E 5 40 1.50E5 NO 2.95E8 Ru-103 1.54E 7 NO 5.92E6 NO 3.88E7 NO 3.98E8 Ru-106 7.45E8 NO 9.30E 7 NO l.01E9 NO 1.I6EIO Ag-110M 3.23E7 2.18E7 f .74E 7 NO 4.06E7 NO 2.59E9 Te-125M 3.5IES 9.50E7, 4.67E7 9.84E 7 NO NO 3.38E8 fe-127M 1.32E9 3.56E8 1.57E8 3.16E8 f .94E9 NO l.07E9 Te-129M 8.58E8 2.40E8 1.33E8 2.77E8 2.52E9 NO 1.0$E9 l-131 1.43E8 1.44E8 8.18E7 4.76E10 2.36E8 NO 1.28E 7 l-133 3.19E6 3.95E6 1.49E6 7.33E8 6.58E6 NO 1.59E6 Cs-134 1.60E10 2.63E10 5.55E9 NO 8.15E9 2.92E9 f.42E8 Cs-136 4.44E8 1.22E9 7.90E8 NO 6.50E8 9.69E 7 4.29E 7 Cs-137 2.39EIO 2.29E10 3.38E9 NO 7.46E 9 2.68E9 1.43E8 l Ba-140 2.77E8 2.43E5 1.62E7 NO 7.9 t E 4 1.45E 5 1.40E8

. Ce-141 6.56E5 3.27ES 4.86E 4 NO l .43E5 NO 4.08E 8 Co-144 't.27ES 3.98E7 6.78E6 NO 2.2tE7 NO l.04E10 Pr-143 1.4eE S 4.39E 4 7.26E3 NO 2.38E 4 NO 1.58E 8 i Nd-147 7.23E4 E.86E4 4.54E3 NO 5.47El NO 9.28E 7 i

2

'9 Values in units of mrom/yr per micro-Ci/m for lensleflon and tritium, and in units of m meem/yr per micro-Cl/see for sit others. Aeterence NUREO 0133.

I I

3-60 Jew. 2

Pags 91 of 164 I

TAALE 3.4-9 lesESTION 00SE R FACTORS VEGETATION PATHWAY (TEEN)

(Reference NLREG 0133)

Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 ND 4.10E 3 4.10E3 4.10E 3 4.10E 3 4.10E 3 4.10E3 P-32 f.60E9 9.91E7 6.20E7 NO NO NO 1.34E 8 Cr-51  % NO 6.19E4 3.44E 4 1.36E4 8.84E4 1.04E7 Mn-54 NO 4.52E8 8.97E7 NO 1.35E S NO 9.27E8 Fe-55 3.25E8 2.31E8 5.38E7 NO NO 1.46E 8 9.98E 7 Fe-59 f.83E8 4.28E 8 1.65E8 ' NO NO 1.35E8 1.0lE9 Co-58 NO 4.38E7 1.01E 8 NO NO NO 6.04E8 Co-60 NO 2.49E8 5.60E8 NO NO NO 3.24E9 Ni -63 1.61E10 I.13E9 5.44E8 NO NO NO l.81ES Zn-65 4.24E8 f.47E9 6.87E8 NO 9.43E8 NO 6.24E8 Ab-86 NO 2.73E8 1.28E8 NO NO NO 4.04E 7

$r-89 1.57EIO NO 4.50E8 NO NO NO l.87E9

$r-90 7.5tEll NO 1.85 Ell NO NO NO 2.IIE10 Y-98 7.87E6 NO 2.llE5 NO NO NO 3.23E9 Zr-95 1.75E6 5.52E5 3.80E 5 NO 8.12E 5 NO 1.27E9 Ne-95 1.92E5 1.06E5 5.85E4 NO 1.03E 5 NO 4.54E8 Ru-103 6.85E6 NO 2.93E6 NO 2.41E 7 NO 5.72E8

, Ru-106 3.09E8 NO 3.90E7 NO 5.97E 8 NO 1.48E10 Ag-110M 1.52E7 1.44E 7 S.76E6 NO 2.75E7 NO 4.04E9 Te-125M 1.48E8 5.34E7 f.98E7 4.14E7 NO NO 4.37E8 Te-127M 5.52E8 1.96ES 6.56E7 1.31E8 2.24E9 NO l.37E9 Te-129M 3.69E8 1.37E8 5.84E7 1.19E8 1.54E9 NO 1.39E9 l-131 7.70E7 1.08E 8 5.79E7 3.15E10 1.86E8 NO 2.13E 7 l-133 1.75E6 2.97E6 9.06E5 4.15E 8 5.21E6 '.0 2.iSE6 Cs-134 7.10E9 1.67E10 7.75E9 NO 5.31E9 2.03E9 2.08E 8 Cs-136 4.65E7 1.83E0 1.23E8 NO 9.96E 7 1.57E7 f.47E7 Cs-137 1.01E10 I.35E10 4.69E9 NO 4.59E9 1.78E9 1.92E8 Se-140 1.39E8 1.71ES 8.97E6 NO 5.78E 4 1.15ES 2.15E8 Co-let 2.83E5 1.89E5 2.17E 4 NO 8.90E 4 NO 5.4tE8 Oe-144 5.27E7 2.18E7 2.82E6 NO l.30E7 NO 1.33E10 Pr-143 6.99E4 2.79E 4 3.48E3 NO 1.62E4 NO 2.30E8 Nd-147 3.66E 4 3.98E4 2.39E3 NO 2.34E4 to i.44E8 l

3 2

'81 values in units of mese/yr per micro-C1/m ter innalation and tritium, and in units of m mee*/yr per micro-Cl/see for all others. Ref erence NUREG 0133.

3-61 Rev. 2 l

I l

P g2 92 of 164 TABLE 3.4-10 ll8ESTi(BI 005 R FACTGIS VEETATION PATHIAY (ADULT)

(Reference NUREG O!33) tenellde anne Liver T. Gody Thyroid Kidney 3 L GI-LLI H-3 NO 5.IIE3 5.llE3 5.llE3 5.IIE3 5.IIE3 5.l t E 3 Cr-SI NO NO 4.6M 4 2.79E 4 1.03E4 6.18E 4 1.17E 7 Mn-54 NO, 3.llE8 5.94E 7 NO 9.27E 7 NO 9.54E8 Fe-55 2.09E8 I .45E 8 3.37E7 NO NO 8.C6E7 8.29E7 Fe-59 1.29E8 3.02E8 1.16E 8 NO NO 8.45E7 1.01E9 Co-58 NO 3.09E 7 6.92E 7 No NO NO 6.26ES Co-60 NO 1.67E8 3.69E8 NO NO NO 3.14E9 Ni-63 1.04E10 7.21E8 3.49E8 NO NO NO l .50E 8 Zn-65 3.18E8 1.01E9 4.57E8 NO 6.76E8 NO 6.37E8 Re-86 NO 2.19E8 1.02E8 NO NO NO 4.32E 7

$r-89 1.03E10 NO 2.96E8 NO NO NO 1.65E9

$r-90 6.0$ Ell NO 1.48 Ell NO NO NO l.75E10 fa91 5.13E6 No 1.37ES No No No 2.32E9 2r-95 1.19E6 3.83E5 2.59E5 ND 6.00E5 NO 1.2tE9 Ne-95 1.42E5 7.90E4 4.24E 4 NO 7.8IE4 NO 4.79E 8 Rw-103 4.79E6 NO 2.06E6 NO 1.83E7 NO 5.59E 8 Ru-106 I .93E8 NO 2.44E 7 No 3.7228 NO 1.25E10 og-110M 1.0M 7 9.78E6 5.81ES NO 1.92E 7 NO 3.99E9 Te-125M 9.6M 7 3.50E7 1.29E 7 2.90E7 3.93E8 NO 3.8M8 Te-127M 3.49E8 1.25E8 4.26ET 8.93E 7 1.42E 9 NO 1.17E9 Te-129M 2.5M8 9.5M7 4.05E7 8.79E 7 1.07E 9 NO l .29E9 l-131 8.09E7 1.16E8 6.6X7 3.79(10 1.98E8 NO 3.05E 7 l-133 1.89E6 3.29E6 1.00E6 4.83E8 5.73E6 NO 2.95E6 Cs-134 4.66E9 1.IlE10 9.07E9 NO 3.59E9 1.19E9 f .94E 8 Cs-136 4.47E7 1.77E8 1.27E8 NO 9.82E 7 1.35E7 2.01E 7 Cs-137 6.36E9 8.70E9 5.70E9 NO 2.95E9 9.81E S 1.6828 8e-140 1.29E8 f.62E5 8.47E6 No 5.52E4 9.29E4 2.66E8 Co-14l 1.97E S I .3MS l.51E4 NO 6.20E4 NO 5.10E 8 Co 144 3.29E7 f.37E7 1.77E6 NO 8.I SE6 NO l.11E10 Pe-143 '6.2M4 2.5 t E 4 3.10E3 NO I .4M 4 NO 2.14E 8 Nd-147 3.39E4 3.89E 4 2.3X3 NO 2".27E 4 N0 l .87E 8 s

'9 velwes in un6ts of *ree/yr per micro-Cl/m for innslation and trittwo, and in units of *2 aree/yr per micro-Cl/see for sti otners. Ref erence NUREO 0133.

3-62 Sev. 2

Paga 93 of 164-9 a

3.4 MCTH000 LOGY FOR RMS-11 SETPOINT (Air Particulate)

Determine the Monitor Alarm Setpoint based on the inhalation pathway to the child. The most restrictive organ "j" upon which the setpoint is based will be determined from the following methodology.

3.4.1 Determine dose rate for organ "j" (mres/yr).

R9 ) Qq (3.4-1)

OR) = X/Q r g where:

T/6 = the highest calculated annual average relative dispersion factor for any area at or beyond the unrestricted area boundary for all sectors (sec/m )3 from Appendix A.

= 8.1E-3 sec/m3 (continuous ground release) from Table A-1, Appendix A.

Rj j = the organ "j" dose factor due to gamma emissions from particulates greater than or equal to 8 day half-life, '

1-133, I-131, H-3.

  • Qg

= the particulate release rate (uC1/sec) for radionuclide

.ja,

= 472 (C1 )(F)

. t t

wheret 472 = c'onversion factor to convert CFM to cc/sec. l l

Cj = (uC1/cci from analysis of containment vessel) (0.368) for CV flow of 35,000 cfm when RMS-11 sampling the Plant Vent.

3 63 Rev. 2

-- -- - --. ,..--.--.;,._7 .-..-.c.

. ,-,-c._-----__...__-.,_ - . - . , . - - - - - , - . - - -

Pcgm 94 of 164

= (uC1/ccq from analysis of CV) (0.04) for CV pressure relief when CV flow is 2500 cfm, when RMS-11 is sampling the Plant Vent.

= (uCi/ccg) from analysis of CV for CV flow of 2500 cfm or 35,000 cfm when RMS-11 is sampling the CV F = 95,000 cfm for CV purge.

= 62,500 cfm for CV pressure relief.

3.4.2 Determine the particulate emission Projected Dose Rate Ratio (PORR) for the most critical organ "j".

PORRj = ORj/1500 (3.4-2) 1500 = the allowable organ dose rate due to particulates with >

8dayhalf-life,I-131,I-133,H-3(mrem / year).

3.4.3 Determine the maximum monitor setpoint concentration (uC1/cc) for most critical organ "j".

Maximum Monitor Setpoint for Organ "j" =

(2 9 C)/(PORR))

g (SF) (T,) (R) -

l where:

l SF = an engineering factor used to provide a margin of safety

! for cumulative measurement uncertainties = 0.50.

l 3 64 Rev. 2

t Pagn 95 of 164

= fraction of the radioactivity from the site that may be T,

released via the monitored pathway to ensure that the site boundary limit is not exceeded dus to simultaneous releasts from several pathways.

= 0.81 for RMS-11 particulate monitor.

TL = total activity / Ij C where the total activity is the 4

sum of particulates of > 8 day half-lives and particu-lates of < 8 day half-lives. If this ratio is not known, use 1.0.

3.4.4 Determine the maximum monitor setpoint (cpm) for the most critical organ "j".

Setpoint = (Maximum total body setpoint in uCi/cc) (monitor eff) + 8kg + 3.3 (3.4-3)

Setpoint = (Maximum skin setpoint in uCi/cc) (monitor eff) +

9 Skg + 3.3 (3.4-4)

Monitor = obtained from the applicable effluent monitor efficiency e iciency curve located in the POM, Volume 15, Curve Book. Use the radioactivity concentration (uCi/cc) to find cpm. -

Bkg . = the monitor background (cpm) 3.3 09= statistical variance en the background (Bkg) count rate ',

(cpm) at a 99.95% confidence level at a time , constant  :

(minutes). -This factor is included to prevented i inadvertent high/ trip alarms due to random counts on the monitor.

3-65 Rev. 2

Page 96 of 164 4.0 RADIOLOGICAL ENVIROW4 ENTAL MONITORING PROGRAM TABLE 4.0-1 contains the sample point description, sampling and collec-tion frequency, analysis, and analysis frequency for various exposure pathways in the vicinity of HBR for the Radiological Monitoring Program. Figures 4.0- l La and 4.0-lb show the location of the various sampling points.

At the time of initial preparation of this manual, the limiting cow milk location was 1.3 miles in the NE sector. As of the time of submittal of this manual, there is no longer a cow present at this location. The radiological environmental monitoring program has been ' altered to reflect this change.

However, the X/Q, and 0/Q values associated with this location have been retained for future reference.

m O

N 4-1 Rev. 2

m m

oo o

8 o

. m TAalE 4.0-8 5 s~

H. 8. 20811850N RADIOLOGICAL ENWilnetNIAL 4G88HNilIG PN013We Esposure Patheey Sagle Sagle 1% Int Description, Sagling and Amelysis I and/or Sample Polet Distance, and Direction Collection frequency frequency Analysis I 1 Airborne I. Florence, S. C. (Control Stadion)2 Continuous operating tleekly 1-131 for Air Particulates and 26 alles ESE a II9' sampler with sample Cartridg.s Radiolodine collection at least Iseekly Cross theta I seekIy Querier 8y Gamma Scan of composite (by locallon) 2 Information Center 0.2 elle S 8 180*

3 Microwave 6ower ja 0.7 alle N 8 5*

ru 4 Spillway 0.4 alle ESE e 110* f 5 East Shore of lake across from plant latake Johnson's Landing 0.9 alle E n a 73*

6 Information Center 0.3 mile SW # 214' 7 CPSL Hartswille substellon, 6.3 miles ESE e 109*

2 Direct 1 Florence, S.C. (Control Station) Continuous measurement Quarterly Comma thna Radiation 26 miles. ESE e li'J* mith readout at least once per quarter (ItDs)

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m Esposiase Patiusey Sample Sample iblat Description. Sampling and Analysis I g and/or Sample f% Int Distance, and Direction Collection fregissocy Fregenency Analysis'

  • S 2 Direct fiadiation 13 Corner pine tree where dirt road Continuous measurement Quarterly Comma Dose Icontinued) spiits 3.0 mile W. with readout at least once per querier IILDs) 14 Power pole by Highway ISI on front of Pine Ridge Church 0.9 elle WNW.

IS. Pine tree down dirt road ott Highway ISI directly adjacent to ash pond on CPAL property l.0 miles NW.

16 Southeast tence at Darlington County I.C. Turbine Plant 1.0 site NhW.

17 Small pine tree, right side of road, 1.0 mile down Discharge Canal road #

at Old lJnit One Weir 1.8 miles N.

47 s~

18 Left side of train trestle over Black Creek O.7 mile St.

19 Third power pole on Hoad #S~l6-23 from intersection with I.6 mile E.

20 Power Polo del at right side of Hoad

  1. S-16-39 going north I.3 elles Elt.

21 Power pole in the yard OL A. Atkinson at Atkinson's boat landing.

22 Shady Hest at light pole near the dock 1.9 miles hME.

23 Power Pole #41E-S on Road setE-S on Hoad #S-16-39 l.2 ma les ESE.

W 24 ISl north past peach term, fir st pa.ed Road JS-l3-711 left. fifth pole left side of road. Yellow markeng S.0

~

miles NW.

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O Esposure Pathsay Sample Sample 1% Int Descriptica. Sampling and Analysis I m and/or Sample 5% Int D! stance, aat Direction Collection frequency frequency Analysis' y ,

  • ~

2 Direct Radiation 35 Power pole at corner of Road Continuous measurement Quarterly Gamma Dose (con t inued ) #$-31-58 off Hoad AS-16-12 with readout at least 4.4 alles $$W. once per quarter (TLDs) 36 Po or pole i 3/4 alle do n paved road off Road AS-16-85

! Pole is in front of old house 4.7 alles SW.

37 Transelssion tomer closest to Clay Road 5.0 miles WSW.

36 Transmission pole right side of Road 5-16-23l next to union Church 4.9 alles W.

39 Power pole, right side of road -

4(

m in middle of field. Yellow paint 5.0 :al les WNW.

Composite sample6 4

3 Waterborne 40 Black Creek at Poad 1623 Benthly Gamma Scan

a. Surface Water 0.6 mile ESE (Indicator). o.or one-month period H-3 2

41 Black Creek (Control Station 7.2 elles NNW.

b. Groundwater 40 Artesian well Grab Sample Monthly Gamma Stan 0.6 alle E SE . H-3 42 Unit I deep mell l

43 Unit 2 deep mall

c. Drinking teos required #.

Water y d. Shoreline 44 East Shore of Lake, Shady Hest Semiaanually Semiannually Gamma Scan

< Sediment Club l.9 miles NNE.

Ca table 4.0-1 (coal inued ) oo (D

O N

Analysis I Espesure Pathsay Sampla Sample 5% Int Description. Sampling and S and/or Sample Ibint Distance, and Direction Collectica frequency frequency Analysis I ~

o P

4 4 Ingestion 53 Lyndale Fare 9.3 elles SW Sealmonthly when Sealmonthly Gamma Scan and

a. Milk (control station) anlaats are on pasture; when animals 8-138 analysis seal-monthly 8 other tiens are on pasture; monthly when animals monthly 4 are on pGiure; monthly other times e other times 54 Aurburndale Plantation
  • 10.1 miles E.
b. Fish 45 Site varias within Lake Robinson. Sealannually (collect Each sample . Gamma Scan" comparable species at Edible portion

, all three locations) 46 Prestwood Lake 4.9 alles ESE.

47 See Lake (Control Station) 13 sg alles telW or May Lake 12.5 miles Nif.

y

c. Food Products 58 One location within 3 miles of site Annual at Harvast Each sample Gamma scan" leafy vege- In the sector with the highest de-tables postilon rate based on the latest information or historical data (location may vary).

49 One location greater than 5 alles from plant site with the least position rate (Control Station)ge- .

54 Auburndale Plantation 0 10.1 elles E.

d. tiroad-leat 50, 0.25 mile SSE CP&L property'. Monthly when avalleble Each sample Gamma Scan" vegetation (3 different kinds of I-131 broad-leat wegetation)

St. 0.25 NNE CP&L property'.

o m

4 52 10 miles W Bethune (Control Station)2, ,

Page 103 of 164 .

F00TM0TES:

1. The LLO for each analysis is specified in Table 3.17-3 of the HBR Tech-nical Specifications.
2. Control stations are locations outside the influence of plant effluents.
3. Airborne particulate sample filter shall be analyzed for gross beta radio-activity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

4 Gassia scan means the identification and quantification of gama-emitting radionuclides that may be attributable to the effluents from the facility.

5. Thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.
6. Composite sample aliquots shall be collected at time intervals that are short (5 or 6 times daily) relative to the compositing period (monthly in order to assure obtaining & representative sample).
7. Collection of drinking water samples is not required since there are no known reservoirs on Black Creek used for drinking purposes.
8. Wate.r from Black Creek is used to irrigate feed and fodder for Arburndale Plantation's Dairy operation. This dairy is located / 11 miles east 9 90*

from plant.

9. Sample Points 50 and 51 are the highest and the second highest 0/Q values, respectively. These locations are more restrictive than site boundary locations.

l A

48 Rev. 1

Page 104 of 164

~

- PIGURE 41

RAOICL.OGICAL SAMPt.E _

gj LOCATION 3 tJEAR SITE .I m

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Page 105 of 164 ,A

( j', .

\ -/ /

4)1 17

\, FIGURE 4-2 I

RADIOLOGICAL SAMPLE

" 'g% ((,e DISTANT LOCATIONS i N I j k l

! /)

'(

i

) i

\ lf D);

i ,

h jf@i -

s

/ 5 R,, , \s \:\

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Page 106 of 164 5.0 INTERLA80RATORY COMPARISON STUDIES 5.1 OBJECTIVE .

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 Sample Analyses Comparison Program J

Environmental samples from the HBR environs are to be analyzed by the Harris Energy & Environmental Center or by a qualified contracting laboratory. These laboratories will participate at least annually in a nationally recognized interlaboratory comparison study. The results of the laboratories' perfor-mances in the study will be provided to HBR E&RC and will be included in the Annual Radiological Environmental Operating Report.

5.2.2 Effluent Release Analyses Program HBR E&RC will perform sample analyses for gamma-emitting radionuclides in effluent releases. The E&RC radiochemistry laboratory will participate annu-ally 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 sigma from the " recognized value," an evaluation will be performed to identify any recommended remedial actions ,to reduce anomalous errors. Complete docu-mentation on the evaluation will be available to HBR and will be provided to q the NRC upon request.

5-1 Rev. 2

Page 107 of 166 6.0 TOTAL DOSE (40CFR190 CONFORMANCE) 6.1 COMPLIANCE WITH 40CFR190 Compliance with 40CFR190 as prescribed by Specification 3.9.6 is to be demonstrated only when one or more of Specifications 3.9.2.1.a. 3.9.2.1.b, 3.9.4.la, 3.9.4.1.b. 3.9.5.1.a. and 3.9.5.1.b is exceeded by a f actor of 2.

Once this occurs the Company has 30 days to submit this report in accordance

- with Specification 6.9.4(d).

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 of 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) Ooses to a MEMBER OF THE PUBLIC via the liquid release pathway will be calculated. .

(2) 00ses 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)

(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.

6-1 Rev. 1

Page 108 of 164 (6) The calculational locations for a MEMBER OF THE PUtiLIC will only be at residences or places of employment.

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

6.3 CALCULATIONS OF TOTAL 800Y OOSE 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.

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

(1) Determining the direct radiation dose at the plant boundary in each sector. 0 8 ,e-(2) Extrapolate that dose to the calculational location as follows:

O g,, =08.e (1.49 E4)

! (*L,e)

DL ,e = dose at calculational location in sector e.

l 1.49E4 = square of mean distance to the site boundary (1220 m).

Xt ,, = Distance to calculational locations in sector e in meters.

6-2 Rev. I

Page 109 of 164 6.3.2 Inhalation Oose 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 <1 mres/yr.

6.3.4 Other Uranium Fuel Cycle Sources The dose from other fuel cycle sources will be treated as <1 mrem /yr.

6.4 THYROIO DOSE The dose to the thyroid will be calculated for each sector as the sum of inhalation dose and milk ingestion dose (if existing). The calculational methods will be those identified in Section 3.3 of this manual.

6.5 OOSE PROJECTIONS Oose projections are to incorporate planned plant operations such as power

~

reduction or outages for the projected period.

6-3 8ev. 1

Page 110 of 164 APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS Carolina Power & Light Company (CP&L) engaged the services of Dames & Moore to assess the transport and dispersion of the effluent in the atmospnere as outlined in Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG 0133 (USNRC 1978). The methodology for - this assessment was based on guidelines F. resented in Regulatory Guide (RG) 1.111, Revision 1 (USNRC 1977). The results of the assessment were to provide the relative deposition flux and relative concentrations (undepleted and depleted)

' based on numercial models acceptable for use in Appendix I evaluations.

Regulatory Guide 1.111 presented three acceptable diffusion models for use in estimating deposition flux and concentrations. These were (1) particl e-i n-cell model (a variable trajectory model based on the gradient-transport theory) , (2) puff-advection model (a variable trajectory model based on the statistical approach to diffusion), and (3) the custant mean wind direction model referred to here as the straight-line trajectory Gaussian diffusion model (the most widely used model based on a statistical approach). It was l

resolved that for operational efficiency, the straight-line described in X00000 Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Fower Stations (Draft), NUREG 0324 (USNRC September 1977) would be used for generating the required analyses of Appendix I. To provide a more realistic accounting of the variability of wind around the plant site, ter-rain / recirculation correction factors (TCF) were to be determined from a i combined puf f-advection/ straight-line scheme for a one-year meteorological data base.

~

Dames & Moore was provided a one-year reconi of meteorological data from the on-site meteorological program at the H. B. Robinson Steam Electric Plant.

These data consisted of all collecteri parameters at both the 11.03-meter and 62.39-meter tower levels for the year 1977. Dames & Moore computed disper-sions and depositions using the model described in the reference. The follos-ing tables from the reference provide the basis for the meteorological dilu-l tion factor development of the technical specifications for Appendix I and were the source of the X/Q aad D/Q values used to show compliance with 10CFR20 and 10CFR50 for noble gases and radiof odines and particulates.

A-1 l

l - - -

Page 111 of 164 Taoles A-1 through A-6 Relative undepleted concentration, relative -

d epleted concentration, and relative depo- ,

sition flux estimates for ground level releases for both stand arti distances and special locations for long-term releases.

Tables A-7 through A-9 Relative undepleted concentration, relative depleted concentration, and relative depo-sition flux estimates 'for ground level releases for special locations for short-term releases.

The X/Q and D/Q values which are used in Appendix B for showing compliance with 10CFR20 and 10CFR50 when the HBR Plant vent has been modified such that it qualifies as a mixed mode release were based upon the following tables:

Tables A-10 through A-15 Relative undepleted concentration, relative depleted concentration, and relative depo-sition flux estimates for elevated release for both standard distances and special locations for long-tenn releases.

Tables A-16 through A-18 Relative undepleted concentration, relative depleted concentration, arti relative depo-sition flux estimates for mixed mode releases for special locations for short-l term releases. ,

l It should be noted that the short-term releases were based upon 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per year of containment purges.

Future Operation Computations The NRC "X0000Q" Program (Revision 1) was obtained and installed on the CP&L computer system. In general, Dames & Moore concluded that the straighc-line i model is as reasonable a projection of concentrations as the puff-advection A-2

Page 112 of 164 mod el . By inclusion of the terrain correction factors developed by a combina- ,

tion of the puff-advection/ straight-line scheme with the results of the X0000Q Program, ready evaluation of on-site meteorological data may oe made.

For routine meteorological dispersion evaluations, the "X0QD0Q" Program will be run with the appropriate physical plant data, appropriate meteorological information for the stand arti distances, and special locations of interest without a terrain / recirculation factor. The resulting computations will have applied the TCFs to produce a final atmospheric diffusion estimate for the site. The input to "X0000Q" for ground level releases at HBR are presented in Table A-19 and for mixed mode releases at HBR in Table A-20.

Reference Chandler, Martin W. and George Hoopes, Revised Radiological Effluent Technical Specifications. Gaseous Effluent Dilution Factors, Prepared for Carolina Power & Light Company, Robinson Facility, Dames & Moore, January 18, 1979.

5 A-3 1

, - - - - y--. --

Page 113 of 164 TABLE A-1 3

X/Q Values for Long-Term Ground Level Reletases at Special Locations (sec/m )*

\

Carolina Power & Lignt Company - Robinson Release Type: Annual Release Nde: Ground level Variable: Relative Concentration (Sec./ Cubic Meter)

Calculation Points: Special Model: Straight Line (ANNXOQ9) .

Application of Terrain Correction Factors: Yes i

Nuriber of Observations: 8703 Affected Site Sector Boundary Meat Dairy Resident Garden NNE 6.67E-06 4.13E-06 0.00 6.26E-06 5.56E-06 NE 3.02E-06 2.56E-06 2.13E-06 2.44E-06 2.13E-06 ENE 4.41E-06 4.93E-07 0.00 4.18E-06 7.36E-07 E 6.39E-06 3.02E-07 1.44E-07 3.51E-06 3.68E-07 ESE 1.12E-05 1.18E-06 0.00 7.90E-06 7.90E-06 SE 3.28E-05 0.00 0.00 3.27E-05 3.27E-05 SSE 8.08E-05 0.00 0.00 6.01E-05 6.01E-05 S 3.29E-05 4.22E-07 0.00 2.78E-05 1.65E-05 SSW 2.10E-05 5.61E-07 0.00 2.04E-05 8.07E-06 SW 8.91E-06 2.61E-07 2.14E-07** 6.90E-06 5.38E-06 WSW 3.97E-06 1.16E-07 0.00 3.22E-06 1.83E-06 W 2.11E-06 3.89E-08 0.00 1.38E-06 1.38E-06 wtW 1.62E-06 5.32E-08 0.00 1.03E-06 6.06E-07 tW 7.93E-07 5.06E-07 0.00 7.39E-07 7.39E-07 NtW 1.31E-06 4.78E-07 0.00 4.42E-07 3.82E-07 N 1.45E-06 6.44E-07 0.00 6.67E-07 6.67E-07

  • Zeroes indicate that this point was not calculated
    • A milk goat is located here A_4 Rev. 1

Page 114 of 164 TABLE A 2 3

Depleted X/Q Values for Long-Ters Ground Level Releases at Special Locations (sec/m )*

Carolina Powr & Light Company - Robinson Release Type: Annual Release Mode: Ground Level Variable: Relative Depleted Concentration (Sec./ Cubic Meter)

Calculation Points: Special Model: Straight Line (ANNX009)

Application of Terrain Cor ection Factors: Yes Number of Observations: 8703 I

Afiacted Site Sector Boundary Meat Dairy Resident Garden NNE 5.84E-06 3.38E-06 0.00 5.25E-06 4.77E-06 NE 2.68E-06 2.21E-06 1.79E-06 2.09E-06 1.79E-06

, ENE 3.95E-06 3.99E-07 0.00 3.72E-06 5.93E-07 E 5.79E-06 2.42E-07 1.0aE-07 3.12E-06 2.86E-07 ESE 1.01E-05 9.72E-07 0.00 7.11E-06 7.11E-06 SE 3.08E-05 0.00 0.00 3.05E-05 3.05E-05 SSE 7.46E-05 0.00 0.00 5.61E-05 5.61E-05 S 3.11E-05 3.42E-07 0.00 2.61E-05 1.53E-05 SSW 1.91E-05 4.55E-07 0.00 1.96E-05 7.35E-06 SW S.25E-06 2.14E-07 2.44E-07** 6.44E-06 4.38E-06 WSW 3.68E-06 8.92E-08 0.00 2.94E-06 1.68E-06 W 1.98E-06 2.96E-08 0.00 1.26E-06 1.26E-06 WW 1.47E-06 4.07E-08 0.00 9.26E-07 5.42E-07
  • 6.71E-07 4.19E-07 0.00 6.31E-07 6.31E-07 NW 1.09E-06 3.80E-07 0.00 3.48E-07 2.98E-07 N 1.24E-06 5.11E-07 0.00 5.24E-07 5.24E-07
  • Zeroes indicate that this point was not calculated
    • A milk goat is located here A-5 Rev. 1

Page 115 of 164 TABLE A-3 D/Q Values for Long-Tera Ground Level Releases at Special Locations {m-2)*

Carolina Power & Light Company - Robinson Release Type: Annual Release Mode: Grourd Level Variable: Relative Deposition Rate (Meter-2)

Calculation Poirts: Special ,

Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes Ntaber of Observations: 8703 Affected Site Sector Bourdary Meat Dairy Resident Garden NNE 9.80E-09 5.63E-09 0.00 9.09E-09 7.74E-09 NE 5.59E-09 4.65E-09 3.70E-09 4.42E-09 3.7CE-09 ENE 8.06E-09 6.96E-10 0.00 7.59E-09 1.05E-09 E 1.24E-08 4.13E-10 1.80E-10 6.43E-09 5.11E-10 ESE 1.71E-08 1.46E-09 0.00 1.20E-08 1.20E-08 SE 4.23E-08 0.00 0.00 4.14E-08 4.14E-08 SSE 8.08E-08 0.00 0.00 6.21E-08 6.21E-08 S 4.39E-08 4.77E-10 0.00 3.82E-08 2.33E-08 SSW 5.92E-08 1.38E-09 0.00 6.12E-08 2.33E-08 SW 2.80E-08 6.49E-10 5.17E-10** 2.15E-08 1.65E-08 WSW 1.91E-08 4.37E-10 0.00 1.54E-08 8.84E-09 W 8.84E-09 1.09E-10 0.00 5.75E-09 5.75E-09 WNW 8.10E-09 1.88E-10 0.00 5.08E-09 2.97E-09 NW 2.44E-09 1.45E-09 0.00 2.16E-09 2.16E-09 NNW 2.44E-09 7.45E-10 0.00 6.83E-10 5.73E-10 N 1.76E-09 6.44E-10 0.00 6.67E-10 6.67E-10

  • Zeroes indicate that this point was not calculated
    • A milk goat is located here l

A-6

Page 116 of 164 TABLE A-4 X/Q Values for Long-Tern Ground Level Releases at Standard Distances (sec/m3)

Carolina Powe & Light Company - Robinson Release Type: Annual Release Mode: Ground Level Variable: Relative Concentration (Sec./ Cubic Meter)

Calculation Points: Standard Model: Straight Line (ANNX0Q9)

Application of Terrain Correction Factors: Yes Number of Observations: 8703 BASE DISTAICE IN MILES /KILDETERS Mtd Desigi Sect Dist .25 .75 1.25 , 1.75 2.25 2.75 3.25 3.75 4.25 4.75 MI 40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64

.YE 0. 8.E-05 1.E-05 6.E-06 3.E-06 2.I-06 1.E-06 1.1E-06 8.T-07 5.E-07 3. E-07 PE 0. 3.9E-05 4.E-06 2.T-06 1.1E-06 6.E-07 4.E-07 3.E-07 2.E-07 2.3-07 1.E-07 E?E 0. 3.E-05 5.2E-06 1.E-06 9.E-07 5.I-07 3.E-07 2.E-07 2 E-07 1.7E-07 1. 5-07 E 0. 2.9E-05 4.E-06 1.E-06 8.I-07 6.2E-07 3.I-07 2.E-07 1.E-07 1.I-07 9.E-08 ESE 0. 3.E-05 5.4-06 2.I-06 1.I-06 9.E-07 6.2E-07 5.1E-07 3.E-07 2.E-07 1.9E-07 SE 0. 4.T-05 5.E-06 2.E-06 1.I-06 8.E-07 4.E-07 3.E-07 2.1E-07 1.9E-07 1.E-07 SSE 0. 8.E-05 1.2E-05 5.T-06 2.E-06 1.5E-06 9.2E-07 6.E-07 5.5E-07 4.E-07 4.T-07 5 0. 3.E-05 4.E-06 1.E-06 9.E-07 4.2E-07 3.I-07 2.E-07 2.1E-07 1.E-07 1.E-07 59 0. 2.E-05 4.E-06 1.9E-06 7.9E-07 4.E-07 3.T-07 2.1E-07 1.E-07 1.E-07 9.E-08 SW 0. 1.5E-05 2.E-06 8.I-07 3.E-07 2.I-07 1.E-07 1.E-07 8.E-08 7.E-08 5.9E-08 WW 0. 6.E-06 1.T-06 3.E-07 2.T-07 1.E-07 1.T-07 6.9E-08 5.E-08 4.E 08 3.E-08 W 0. 6.E-06 8.I-07 3.2E 07 1.E-07 1.I-07 8.E-08 6.E-08 4.I-08 3.T-08 2.4-08 WrW 0. 6.1E-06 7.E-07 3.T 07 1.E-07 1.I-07 9.E-08 7.1E-08 5.4-08 4.T-08 3.T-08

'M 0. 1.1E-05 1.E-06 7.4-07 4.Z-07 2.E-07 1.I-07 8.T-08 6.E-08 5.I-08 1.4-08 NPW 0. 2.I-05 3.E-06 1.9E-06 1.E-06 9.E-07 5.E-07 2.E-07 1.E-07 1.E-07 9.E-08 N 0. 5.E-05 8.&-06 3.I-06 1.E-06 1.T-06 7.1E-07 4.9E-07 3. E-07 2.9E-07 2.E -07 Nuteer of Valid Observations = 8703

= 57 4reer of Invalid Observations

= 398 Mreer of Calrrs Lowc Level 4reer of Calrrs Upper Limit = 0 A-7 Rev. 1

Page 117 of 164 TMLE A-5 Ogleted X/Q Values for ' lag-Term Gmed Level Releases at Standard Distances (sec/m3)

Carolina Poer & Lihtt Catpany - Robinen Release Type: Mrual Releaserede: Ground Lewi Variable: Relative Con:entration (Sec./Cbuic ftter)

Calculation Points: Stanard

!tdel: Straignt Line (40E03)

Application of Terrain Correction Factors: Yes rescer of Observations: 8703 BASE DISTNG IN ElfS/KILDETBtS Mtd Desigi Sect Dist .25 15 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 E 40 1.21 2.01 2.E 3.62 4.42 5.23 6.03 6.86 7.64 NIE 0. 8.I-05 1.I45 5.4E 06 3.T-06 2.T-06 1.I-07 8.I06 6.Z-07 4.1E-07 2.7E-07 PE 0. 3.E-05 4.1E 06 1.7E-06 9.2E-07 5.E-07 3.E-07 2.7E-07 2.1E-07 1.E-07 1. I -07 EIE 0, 3.1E-05 4.E-06 1.E-06 8.I 07 4.I-07 3.T-07 2.T-07 1.E-07 1. I 07 1.1E-07 E 0. 2.7E-05 4.1E-06 1.I-06 6.9E-07 5.T-07 2.7E-07 2.1E-07 1.E-07 9.4E-08 7.2E-08 ESE 0. 3.4E-05 4.9E-06 2.T-06 1.1E-06 7.4E 07 5.T-07 4.T 07 2.9E-07 2.1E-07 1.E-07 SE 0. 3.E-05 4.9E-06 2.2E-06 1.1E-06 7,T-07 3.E-07 2.E-07 1.7E-07 1.4E-07 1.E-07 SSE 0. 7.E-05 1.1E 05 4.4E-06 2.E-06 1.I 06 7.E-07 5.1E-07 4.I-07 3.I 07 2.9E-07 5 0. 3.5E-05 3.9E-06 1.4E-06 7.E-07 3.E-07 2.E-07 2.T-07 1.E-07 1. I -07 1.E-07 59 0. 2.I-05 4.1E-06 1.E-06 6.E-07 3.7E-07 2.4E-07 1.7E-07 1.E-07 3.9E-08 6.9E-08 SW 0. 1.4E 05 1.9E-06 7.1E-07 3.1E-07 1.9E-07 1.2-07 9.E-08 6.E-08 S.I-08 4.I-08 WW 0. 6.2E 06 9.I-07 3.2E-07 1.7E-07 1.I-07 8.T-08 5.4E-08 4.4E-08 3.E 08 2.7E-08 W 0. 6.1E-06 7.E-07 2.E-07 1.4E-07 1.1E-07 6.E-08 5.2E-08 3.I-08 2.I-08 1.E-08 WNd O. 5.E-06 7.T-07 2.E-07 1.E-07 1.lE 07 7.E-08 5.E-08 4.E-08 3.T-08 2.E 08 PW 0. 1.1E-05 1.4E-06 6.4E-07 1.4E-07 2.T-07 1.T-07 6.1E-08 5.T 08 4.T-08 3.I 06 NrW 0. 1.9E 05 3.1E-06 1.E-06 1.lE-06 7.E-07 4,2E-07 2.T-07 1.I-07 8.E-08 7.1E-08

~

N 0. 4.9E-05 7.2E-06 2.E-06 1.4E-06 8.1E-07 5.E-07 3.E-07 2.9E-07 2.E-07 1.E-07 Number of Valid Observations = 8703 Number of Invalid Observations = 57

= 398 Number of Calms Lower Level Number of Calms Upper Limit = 0 A-8 Rev. 1

Page 118 of 164 TABLE A-6 D/Q Values for Long-Tera Ground Level Releases at Standard Distances (m-2}

Carolina Power & Light Company - Robinson Release Type: Annual Release Mode: Grourd Level Variable: Relative Concentration (Meter 2)

Calculation Points: Standard Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes Number of Observations: 8703 BASE DISTAICE IN MILES /KILDETERS Afid Design Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Sect Mt .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.54 tee 0. 1.3E 07 2.4E-08 9.3E-09 4.E-09 3.E-09 2.E-09 1.2E-09 8.2E-10 5.4E-10 3.4E NE 0. 7.1E-08 8.9E-09 3.4E-09 1.E-09 1.T-09 6.5E-10 4.6E-10 3.4E-10 2.E-10 2.E-10 E?E 0. 5.5E-08 9.E-09 3.1E-09 1.5E-09 7.9E-10 5.1E-10 3.3E-10 2.6E-10 1.9E-10 1.6E-10 E 0. 5.1E-08 8.7E-09 2.7E-09 1.4E-09 9.4E-10 4.7E-10 3.6E-10 2.4E-10 1.5E-10 1.1E-10 ESE 0. 5.E.OB 8.2E-09 3.2E-09 1.6E-09 1.1E-09 6.9E-10 5.1E-10 3.6E-10 2.5E-10 1.8E-10 SE 0. 4.E-08 7.E-09 3.1E-09 1.5E-09 8.6E-10 4.5E-10 3.1E-10 1.E-10 1.5E-10 1.2E-10 SSE 0. 8.2E-08 1.3E-08 5.2E-09 2.6E-09 1.4E-09 7.7E-10 4.9E-10 3.9E-10 3.E-10 2.5E-10 S 0. 4.E-08 6.I-09 2.2E-09 1.2E-09 4.E-10 3.5E-10 2.6E-10 1.9E-10 1.6E-10 1.2E-10 SSW 0. 7.2E-08 1.4E-08 5.1E-09 2.E-09 1.1E-09 6.8E-10 4.5E-10 3.2E-10 2.3E-10 1.8E-10

~

SW 0. 4.2E-08 6.E-09 2.I-09 1.E-09 5.7E-10 3.7E-10 2.7E-10 1.E-10 1.4E-10 1.1E-10 WSW 0. 3.T-08 4.9E-09 1.7E-09 8.5E-10 6.3E-10 3.8E-10 2.5E-10 1.9E-10 1.6E-10 1.2E-10 W 0. 2.7E-08 3.4E-09 1.2E-09 6.1E-10 4.4E-10 2.7E-10 2.E-10 1.3E-10 8.5E-11 6.7E-11 W 0. 3.E 08 3.9E-09 1.4E-09 7.4E-10 5.4E-10 3.7E-10 2.6E-10 2.T-10 1.4E-10 1.E-10 NW 0. 3.4E-08 5.2E-09 2.2E-09 1.2E-09 6.3E-10 3.2E-10 1.E-10 1.5E-10 1.1E-10 9.E-11 NW 0. 4.1E-08 7.4E-09 3.6E-09 2.5E-09 1.6E-09 8.E-10 3.9E-10 2.4E-10 1.5E-10 1.2E-10 N 0. 6.7E-08 1.1E-08 4.1E-09 2.E-09 1.1E-09 7.2E-10 4.7E-10 3.3E-10 2.5E-10 2.E-10

= 8703 Number of Valid Observations

= 57 Number of Invalid Observations

= 398 Nunt>er of Calms Lower Level Number of Calms Upper Limit = 0 A-9

Page 119 of 164 TABLE A-7 3

X/Q Values for Short-Tern Ground Level Releases at Special Locations (sec/m )*

Carolina Power & Light Company - Robinson Release Type: Purge Release Mode: Grourd Level Variable: Pelative Concentration (Sec./ Cubic deter)

Calculation Points: Special Model: Purge (ACNPURG2)

Application of Terrain Correction Factors: No Nunber of Observations: 8703 Purge Time: 100 Hours Affected Site Sector Bouniary Meat Dairy Resident Garden NNE 7.20E-06 5.00E-06 0.00 6.80E-06 6.20E-06 NE 5.3E-06 4.60E-06 4.00E-06 4.40E-06 4.00E-06 ENE 6.90E-06 1.50E-06 0.00 6.70E-06 1.90E-06 E 1.00E-05 1.10E-06 6.40E-07 6.20E-06 1.20E-06 ESE 1.50E-05 2.60E-06 0.00 1.10E-05 1.10E-05 SE 3.40E-05 0.00 0.00 3.30E-05 3.30E-05 SSE 5.10E-05 0.00 0.00 4.10E-05 4.10E-05 S 3.00E-05 1.20E-06 0.00 2.60E-05 1.80E-05 SSW 2.10E-OS 1.30E-06 0.00 2.00E-05 9.80E-06 SW 1.10E-05 7.80E-07 6.70E-07** 9.10E-06 7.20E-06 WSW 8.10E-06 5.50E-07 0.00 6.90E-06 4.20E-06 W 5.50E-06 3.00E-07 0.00 4.20E-06 4.20E-06 WNW 5.30E-06 3.90E-07 0.00 3.70E-06 2.50E-06 NW 2.30E-06 1.70E-06 0.00 2.20E-06 2.20E-06 NNW 2.40E-06 1.20E-06 0.00 1.20E-06 1.10E-06 2.70E-06 1.50E-06 0.00 1.50E-06 1.50E-06 N

  • Zeroes irdicate that this point was not calculated
    • A milk goat is locataf here A-10

Page 120 of 164 TABLE H 3

Depleted X/Q Values for Short-Ters Ground Level' Releases at Special Locations (sec/m )*

Carolina Power & Light Company - Robinson Release Type: Purge Release Mode: Grourd Level Variable: Relative Depleted Concentration (Sec./ Cubic Meter)

Calculation Points: Special Model: Purge (ACNPURG2)

Application of Terrain Correction Factors: No Nunber of Observations: 8703 Purge Time: 100 Hours Affected Site Sector Bourdary Meat Dairy Resident Garden NNE 6.30E-06 4.09E-06 0.00 5.71E-06 5.31E-06 NE 4.71E-06 3.97E-06 3.37E-06 3.77E-06 3.37E-06 ENE 6.19E-06 1.21E-06 0.00 5.96E-06 1.53E-06 E 9.06E-06 8.80E-07 4.80E-07 5.51E-06 9.34E-07 ESE 1.36E-05 2.14E-06 0.00 9.90E-06 9.90E-06 SE 3.19E-05 0.00 0.00 3.08E-05 3.08E-05 SSE 4.71E-05 0.00 0.00 3.83E-05 3.83E-05 S 2.83E-05 9.74E-07 0.00 2.44E-05 1.67E-05 SSW 1.91E-05 1.05E-06 0.00 1.92E-05 8.93E-06 i SW 1.02E-05 6.38E-07 7.64E-07** 8.49E-06 6.52E-06 WSW 7.50E-06 4.23E-07 0.00 6.30E-06 3.85E-06 5.16E-06 2.28E-07 0.00 3.85E-06 3.85E-06

! W WNW 4.82E-06 2.98E-07 0.00 3.33E-06 2.23E-06 ,

NW 1.95E-06 1.41E-06 0.00 1.88E-06 1.88E-06 NNW 1.99E-06 9,53E-07 0.00 9.46E-07 8.59E-07 N 2.31E-06 1.19E-06 0.00 1.18E-06 1.18E-06

  • Zeroes irdicate that this point was not calculated
    • A milk goat is locatai here A-11

Page 121 of 164 TABLE k 9 D/Q Values for Short-Tern Ground Level Releases at Special Locations (m-2)*

Carolina Power & Light Company - Robinson Release Type: Purge Release Mode: Grourd Level Variable: Relative Deposition Rate (Meter-2)

Calculation Points: Special Model: Purge (ACNPURG2)

Application of Terrain Correction Factors: No Number of Observations: 8703 Purge Time: 100 Hours Affected Site Sector Boundary Meat Dairy Resident Garden NNE 1.06E-08 6.80E-09 0.00 9.86E-09 8.62E-09 NE 9.80E-09 8.37E-09 6.96E-09 7.96E-09 6.96E-09

'INE 1.26E-08 2.12E-09 0.00 1.21E-08 2.72E-09 E 1.94E-08 1.51E-09 8.00E-10 1.13E-08 1.67E-09 ESE 2.29E-08~ 3.22E-09 0.00 1.68E-08 1.68E-08 SE 4.25E-08 0.00 0.00 4.19E-08 4.19E-08 SSE 5.10E-08 0.00 0.00 4.22E-08 4.22E-08 S 3.99E-08 1.36E-09 0.00 3.59E-08 2.54E-08 SSW 5.92E-08 3.18E-09 0.00 6.00E-08 2.83E-08 SW 3.46E-08 1.93E-09 1.61E-09** 2.83E-08 2.20E-08 WSW 3.90E-08 2.07E-09 0.00 3.30E-08 2.03E-08 W 2.30E-08 8.40E-10 0.00 1.75E-08 1.75E-08 WNW 2.65E-08 1.38E-09 0.00 1.82E-08 1.22E-08 NW 7.08E-09 4.86E-09 0.00 6.42E-09 6.42E-09 NNW 4.46E-09 1.87E-09 0.00 1.86E-09 1.65E-09 N 3.27E-09 1.50E-09 0.00 1.50E-09 1.50E-09

  • Zeroes irdicate that this point was not calculated
    • A milk goat is located here

\

A-12

Page 122 of 164 TABLE A-10 X/Q Values for '.ong-Tern Mixed Male Releases at Special Locations (sec/2)*

Carolina Power & Light Company - Robinson Release Type: Annual Release Mode: Mixed Mcde Variable: Relative Concentration (Sec./ Cubic Meter)

Calculation Points: Special Model: Straight Line (APNX0Q9)

Application of Terrain Correction Factors: Yes Number of Observations: 8703 Affectal Site Sector Boundary Meat Dairy Resident Garden NNE 3.33E-07 2.82E-07 0.00 3.23E-07 3.18E-07 NE 1.34E-07 1.40E-07 1.23E-07 1.39E-07 1.23E-07 ENE 2.74E-07 1.23E-07 0.00 2.79E-07 8.51E-08 E 2.40E-07 1.11E-07 5.39E-08 2.53E-07 1.33E-07 ESE 2.75E-07 1.25E-07 0.00 2.17E-07 2.17E-07 SE 5.13E-07 0.00 0.00 5.23E-07 5.23E-07 SSE 9.94E-07 0.00 0.00 7.61E-07 7.61E-07 S 4.57E-07 3.61E-08 0.00 4.00E-07 2.50E-07 SSW 5.54E-07 1.27E-07 0.00 5.71E-07 2.69E-07 SW 2.31E-07 5.38E-08 4.72E-08** 1.84E-07 1.51E-07 WSW 2.06E-07 4.64E-08 0.00 1.68E-07 1.02E-07 W 9.36E-08 1.87E-08 0.00 7.13E-08 7.13E-08 WNW 1.02E-07 4.28E-08 0.00 9.55E-08 9.80E-08 NW 1.52E-07 1.30E-07 0.00 1.54E-07 1.54E-07 NNW 1.71E-07 8.86E-08 0.00 8.30E-08 7.28E-08 N 9.32E-08 5.66E-08 0.00 5.80E-08 5.80E-08

  • Zeroes irdicate that this point was not calculated
    • A milk goat is located here A-13

Page 123 of 164 TABLE A-11 3

Depleted X/Q Values for Long Tern Mixed Pede Releases at Special Locations (sec/m )*

Carolina Power & Light Company - Robinson Release Type: Annual Release Mode: Mixa1 Mode Variable: Relative Concentration (Sec./ Cubic Meter)

Calculation Points: Special Model: Straight Line (ANNXOQ9),

A; plication of Terrain Correction Factors: Yes Number of Observations: 8703 Affectai Site Sector Boundary Meat Dairy Residerst Gartien NNE 3.33E-07 2.82E-07 0.00 3.23E-07 2.98E-07 NE 1.23E-07 1.28E-07 1.23E-07 1.28E-07 1.23E-07 ENE 2.59E-07 1.23E-07 0.00 2.63E-07 8.12E-08 E 2.40E-07 1.11E-07 4.39E-08 2.53E-07 1.23E-07 ESE 2.54E-07 1.18E-07 0.00 1.96E-07 1.96E-07 SE 4.93E-07 0.00 0.00 5.02E-07 5.02E-07 SSE 9.32E-07 0.00 0.00 7.21E-07 7.21E-07 S 4.39E-07 3.42E-08 . 0.00 3.82E-07 2.33E-07 SSW 5.35E-07 1.27E-07 0.00 5.51E-07 2.51E-07 SW 2.31E-07 5.14E-08 5.31E-08** 1.84E-07 1.45E-07 i

WSW 2.06E-07 4.46E-08 0.00 1.68E-07 9.91E-08 W 9.10E-08 1.82E-08 0.00 6.90E-08 6.90E-08 j

WNW 9.88E-08 4.07E-08 0.00 9.26E-08 9.54E-08 NW 1.51E-07 1.27E-07 0.00 1.54E-07 1.54E-07 NNW 1.64EJ)7 8.44E-08 0.00 8.04E-08 6.92E-08 N 8.91E-08 5.42E-08 0.00 5.56E-08 5.56E-08

  • Zeroes irdicate that this point was not calculated
    • A milk goat is locatal here A-14 l

Page 124 of 164 TABLE A-12 D/Q Values for long-Tern Mixed Made Reletses at Special Locations (m-2)*

Carolina Power & Light Company - Robinson Release Type: Annual Release itxie: Mixed Mode Variable: Relative Deposition Rate (Meter-2)

Calculation Points: Special Model: Straight Line (ANNX0Q9)

Application of Terrain Correction Factors: Yes Number of Observations: 8703 Affected Site Sector Boundary Mitat Dairy Resident Garden NNE 2.29E-09 1.39E-09 0.00 2.22E-09 1.89E-09 NE 1.79E-09 1.51E-09 1.23E-09 1.39E-09 1.23E-09 ENE 3.19E-09 3.41E-10 0.00 3.10E-09 4.78E-10 E 4.99E-09 2.31E-10 1.15E-10 2.92E-09 2.76E-10 ESE 4.86E-09 5.90E-10 0.00 3.75E-09 3.75E-09 SE 6.98E-09 0.00 0.00 7.20E-09 .7.20E-09 SSE 6.22E-09 0.00 0.00 5.21E-09 5.21E-09 S 7.31E-09 1.77E-10 0.00 6.60E-09 5.17E-09 SSW 1.01E-08 7.41E-10 0.00 1.06E-08 6.81E-09 SW 4.62E-09 3.32E-10 2.66E-10** 4.14E-09 3.87E-09 WSW 4.85E-09 2.59E-10 0.00 4.34E-09 3.35E-09 W 2.64E-09 6.74E-11 0.00 1.95E-09 1.95E-09 WNW 2.59E-09 1.25E-10 0.00 1.94E-09 1.29E-09 NW 1.20E-09 7.66E-10 0.00 1.12E-09 1.12E-09 NNW 7.77E-10 2.53E-10 0.00 - 2.41E-10 2.03E-10 N 3.62E-10 1.41E-10 0.00 1.51E-10 1.51E-10

  • Zeroes irtlicate that this point was not i:alculated
    • A milk goat is locatal here A-15

Page 125 of 164 l

l TABLE A-13 3

X/Q Values for Long-Ters Mixei Mode Releases at Stardard Distances (sec/m )

Carolina Power & Light Company - Robinson Release Type: Annual Release Mode: Mixei Mode Variable: Relative Concentration (Sec./ Cubic Meter)

Calculation Points: Standard Model: Straight Line (ANNXUQ9)

Application of Terrain Correction Factors: Yes Nunber of Observations: 8703 BASE DISTAICE IN MILES /KILM.TERS Atti Desigi Sect Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 M[ .40 1.21 2.01 2.82 3.62 -4.42 5.23 6.03 6.84 7.64 s

ME 0. 1.5E-06 3.9E-07 3.1E-07 2.7E-07 2.3E-07 2.E-07 1.6E 07 1.4E 07 L8E-08 6.5E-08 NE 0. 1.E-06 1.5E-07 1.1E-07 9.E-08 6.7E-08 5.2E-08 7.E-08 3.E-08 5.4E-08 3.4E-08 DE 0. 8.6E-07 2.6E-07 1.9E-07 1.7E-0/ 1.2E-07 1.1E-07 7.4E-08 '6.2E-08 4.8E-08 4.2E-08 E 0. 7.2E-07 2.6E-07 2.2E-07 2.T-07 2.1E-07 1.2E-07 9.4E-08 7.E-08 4.7E-08 3.6E-08 ESE 0. 7.8E-07 1.9E-07 1.7E-07 1.3E-07 1.E-07 7.E-08 6.6E-08 4.9E-08 3.8E-08 2.9E-08 SE 0. 5.9E-07 1.E-07 7.5E-08 5.1E-08 3.8E-08 2.4E-08 1.E-08 1.2E-08 1.2E-08 1.1E-08 SSE 0. 1.E-06 1.8E-07 1.2E 07 8.2-08 5.4E-08 3.6E-08 2.6E-08 2.3E-08 1.9E-08 1.8E-03 S 0. 5.T-07 9.4E-08 7.E-08 5.9E-08 3.5E-08 3.2E-08 2.9E-08 2.E-08 2.2E-08 1.9E-OS

! SSW 0. 6.3E-07 2.7E-07 2.4E-07 1.5E-07 1.2E-07 8.4E-08 6.3E-08 4.7E-08 3.6E-08 3.1E-08 SW 0. 3.E-07 9.9E-08 8.E-08 6.1E-08 4.6E-08 3.7E-08 3.2E-08 2.I-08. 2.E-08 1.7E-08 l WSW 0. 3.E-07 6.5E-08 6.2E-08 5.4E-08 5.4E-08 4.1E-08 3.E-08 2.7E-08 2.4E-08 1.9E-08 l W 0. 2.4E-07 6.2E-08 6.E-08 4.9E-08 4.9E-08 3.5E-08 3.E-08 2.E-08 1.E-08 1.2E-08 l W 0. 2.E-07 8.4E-08 8.6E-08 6.E-08 6.3E 08 5.2E-08 4.2E-08 3.6E-08 3.6E-08 3.4E-08 SI 0. 3.E-07 1.2E-07 1.5E-07 1.2E-07 9.2E-08 6.E-08 4.7E-08 4.1E-08 3.E-08 2.9E-08 M 0. 4.2E-07 1.E-07 1.4E-07 1.6E-07 1.4E-07 9.2E-08 5.4E-08 3.7E-08 2.5E-08 2.1E-08 N 0. 7.8E-07 1.7E-07 1.I-07 9.3E-08 7.2E-08 5.9E-08 4.5E-08 3.E-08 3.3E-08 2.9E-08

= 8703 Nunber of Valid Observations

= 57

, Number of Invalid Observations l Ntaber of Calms Lower Level = 60 Ntsnber of Calms Upper Limit = 5 l

l l

i A-16

Page 126 of 164 TABLE Ar-14 3

Depletsi X/Q Values for Long-Ters Mixed lede Releases at Starulani Distances (sec/m )

Carolina Power & Light Compary - Robinson Release Type: Annual Release Mode: Mixed Mode Variable: Relative Depeleted Concentration (Sec./ Cubic Meter)

Calculati n Points: Standard Model: Straight Line (ANNX0Q9)

Application of Terrain Correction Factors: Yes Nunber of Observations: 8703 BASE DISTANCE IN MILES /KILGETERS Arti Desigt Sect Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 MI .40 1.21 2.01 2.82 3.fi2 4.42 5 23 6.03 6.84 7.64 ME 0. 1.5E-06 3.7E-07 3.1E-07 2.5E-07 2.2E-07 1.E-07 1.5E-07 1.3E-07 8.9E-08 6.1E-08 NE 0. 9.E-07 1.4E-07 1.1E 47 8.5E-08 6.4E-08 4.9E-08 7.E-08 3.E-08 5.2E-08 3.1E-08 DE 0. 8.3E-07 2.SE 07 1.E-07 1.6E-07 1.E-07 1.T-07 6.9E-08 ~5.7E-08 4.5E-08 4.T-08 E 0. 7.E-07 2.4E-07 2.E-07 1.9E-07 2.1E-07 1.1E-07 9.4E-08 6.E-08 4.5E-08 3.4E-08 ESE 0. 7.3E-07 1.E-07 1.6E-07 1.2E-07 9.6E-08 7.2E-08 6.1E-08 4.E-08 3.6E-08 2.7E-08 SE 0. 5.7E-07 9.6E-08 6.9E-08 4.7E-08 3.6E-08 2.3E-08 1.E-08 1.2E-08 1.T-OS 9.SE-09 SSE 0. 9.6E-07 1.7E-07 1.1E-07 7.4E-08 4.9E-08 3.3E-08 2.4E-08 2.1E-08 1.7E-08 1.6E-08 5 0. 4.8E-07 8.9E-08 6.7E-08 5.E-08 3.E-08 3.1E-08 2.7E-08 2.4E-08 2.1E-08 1.E-08 SSW 0. 6.1E-07 2.5E-07 2.4E-07 1.5E-J7 1.1E 07 8.T-08 6.T-08 4.5E-08 3.4E-08 2.9E-08 l SW 0. 3.4E-07 9.5E-08 8.5E-08 5.E-08 4.4E-08 3.6E-08 3.1E-08 2.2E-N 1.9E-08 1.6E-08 WSW 0. 2.9E-07 6.I-08 6.1E-08 5.2E-08 5.E-08 4.E-08 2.9E-08 2.6E-08 2.2E-08 1.E-08 W 0. 2.4E-07 6.E-08 5.9E-08 4.E-08 4.7E-08 3.4E-08 2.9E-08 1.9E-08 1.4E-08 1.2E-08 W 0. 2.6E-07 8.3E-08 8.4E 08 6.6E-08 6.2E-08 5.E-08 4.E-08 3.4E-08 3.4E-08 3.2E-08 i NW 0. 3.E-07 1.1E-07 1.5E-07 1.1E-07 9.T-08 6.3E-08 4.5E-08 3.9E-08 3.E-08 2.4E-08 NW 0. 4.1E-07 1.2E-07 1.4E 07 1.6E-07 1.4E-07 8.E-08 5.2E-03 3.5E-08 2.4E-08 2.E-08 l N 0. 7.5E-07 1.5E-07 1.2E-07 8.E-08 6.9E-08 5.7E-08 4.3E-08 3.6E-08 3.1E-08 2.7E-08 1

= 8703 Pumber of Valid Obsenations

= 57 humber of Invalid Obsenations Number of Calms Lower Level = 60 Number of Calms Upper Limit = 5 A-17

Page 127 of 164 TABLE A-15 D/Q Values for Long-Ters Mixed itxle Releases at Standard Distances (m~2)

Carolina Power & Light Company - Robinson Release Type: Annual Release Mode: Mixed Made Variable: Relative Deposition Rate (Meter-2)

Calculation Points: Standard Model: Straight Line (ANNX0Q9)

Application of Terrain Correction Factors: Yes Nunber of Observations: 8703 BASE DISTANCE IN ttILES/KILGETERS Arti Desfy:

Sect Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 MI .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 ME 0, 1.E-08 5.T-09 2.1E-09 1.2E 09 7.5E-10 5.2E-10 3.4E-10 2.7E-10 2.T-10 1.4E-10 NE 0. 1.1E-08 2.E-09 1.2E-09 6.2E-10 3.E-10 2.3E-10 1.E-10 1.EE-10 1.2E-10 1.T-10 EE 0. 1.1E-08 3.E-09 1.4E-09 7.6E-10 3.7E-10 2.7E-10 1.E-10 ~ 1.4E-10 1.2E-10 1.1E-10 E 0. 1.1E-08 3.7E-09 1.4E-09 7.2E-10 5.T-10 2.E-10 2.1E-10 1.4E-10 1.T-10 7.E-11 ESE 0. 8.6E-09 2.7E-09 1.2E-09 6.7E-10 4.3E-10 2.8E-10 2.1E-10 1.5E-10 1.T-10 7.3E-11 SE 0. 7.T-09 1.9E-09 9.5E-10 4.7E-10 2.E-10 1.E-10 1.1E-10 5.9E-11 5.T-11 4.2E-11 SSE 0. 6.2E-09 1.8E-09 8.6E-10 4.6E-10 2.6E-10 1.E-10 9.5E-11 7.7E-11 5.9E-11 5.T-11 S 0. 7.1E-09 1.E-09 7.E-10 4.2E-10 1.E-10 1.I-10 9.9E-11 7.3E-11 6.1E-11 4.E-11 SSW 0. 1.T-08 5.T-09 2.6E-09 1.1E-09 f).1E-10 3.9E-10 2.6E-10 1.8E-10 1.3E-10 1.T-10 SW 0. 5.T-09 2.T-09 9.E-10 4.7E-10 2.9E-10 1.9E-10 1.E-10 9.E-11 7.6E-11 6.4E-11 WSi 0. 4.9E-09 1.9E-09 8.4E-10 4.E-10 3.7E-10 2.3E-10 1.5E-10 1.2E-10 1.T-10 7.1E-11 W 0. 4.T-09 1.4E-09 6.I-10 3.4E-10 2.6E-10 1.E-10 1.I-10 7.9E-11 5.4E-11 4.1E-11 W 0. 4.6E-09 1.5E-09 7.1E-10 4.2E-10 3.2E-10 2.2E-10 1.6E-10 1.2E-10 9.9E-11 7.4E-11 FM 0. 5.6E 49 2.2E-09 1.1E-09 6.4E-10 3.E-10 1.9E-10 1.2E-10 1.T-10 1.1E-10 9.6E-11 N 0. 4.5E-09 1.9E-09 1.1E-09 8.1E-10 5.2E-10 2.7E-10 1.4E-10 8.E-11 5.7E-11 4.5E-11 N 0. 5.9E-09 1.E-09 8.2E-10 4.T-10 2.4E-10 1.6E-10 1.T -10 7.4E-11 5.E -11 4.7E-11

= 8703 Nunt>er of Valid Observations

= 57 Number of Invalid Observations

= 60 Number of Calms Lcwer Level Number of Calms Upper Limit = 5 A-18

Page 128 of 164 TABLE A-16 3

X/Q Values for Short-Tern Mixei Male Aeleases at Special Locations (sec/m )*

Carolina Power & Light Company - Robinson Release Type: Purge Release Mode: Mixd Mode Variable: Relative Concentration (Sec./ Cubic Meter)

Calculation Points: Special Model: Purge (ACNPURG2)

Application of Terrain Correction Factors: No Nunber of Observations: 8703 Purge Time: 100 Hours

. Affected Site Sector Bourdary Meat Dairy Resident Garden NNE 8.40E-07 7.00E-07 0.00 8.30E-07 7.90E-07 NE 5.40E-07 5.30E-07 4.70E-07 5.20E-07 4.70E-07 ENE 8.90E-07 4.20E-07 0.00 8.80E-07 3.10E-07 E 1.00E-06 4.00E-07 2.50E-07 9.20E-07 4.50E-07 ESE 1.24E-06 4.70E-07 0.00 1.00E-06 1.00E-06 SE 2.20E-06 0.00 0.00 2.10E-06 2.10E-06 SSE 2.90E-06 0.00 0.00 2.40E-06 2.40E-06 S 1.90E-06 2.00E-07 0.00 1.70E-06 1.20E-06 SSW 2.00E-06 4.00E-07 0.00 2.00E-06 1.10E-06 SW 1.10E-06 2.40E-07 2.10E-07** 9.50E-07 7.70E-07 WSW 1.20E-06 2.20E-07 0.00 9.90E-07 6.30E-07 W 7.40E-07 1.30E-07 0.00 5.90E-07 5.90E-07 WNW 7.90E-07 2.20E-07 0.00 6.80E-07 6 20E-07 NW 6.30E-07 5.10E-07 0.00 6.20E-07 6.20E-07 NNW 5.10E-07 3.20E-07 0.00 3.10E-07 2.90E-07 N 3.50E-07 2..'0E-07 0.00 2.40E-07 2.40E-07

  • Zeroes indicate that this point was not calculated
    • A milk goat is locatai here A-19

s Page 129 of l'66 TABLE A-17 3

Depleted X/Q Values for Short-Tern Mixed Male Releases at Special Locations (sec/m )*

Carolina Power & Light Company - Robinson Release Type: Purge Release Mode: Mixed Mcde Variable: Re,lative Depleted Concentration (Sec./ Cubic Meter)

Calculation Points: Special Madel: Purga (ACNPURG2)

Application of Terrain Correction Factors: No Number of Observations: 8703 Purge Time: 100 Hours Affected Site Sector Bourulary Meat Dairy Resident Gartien

!N2 8.40E-07 7.00E-07 0.00 8.30E-07 7.41E-07 NE 4.95E-07 4.86E-07 4.70E-07 4.77E-07 4.70E-07 ENE 8.40E-07 4.20E-07 0.00 8.31E-07 2.96E-07 E 1.00E-06 4.00E-07 2.03E-07 9.20E-07 4.15E-07 ESE 1.11E-06 4.44E-07 0.00 9.00E-07 9.00E-07 SE 2.11E-06 0.00 0.00 2.01E-06 2.01E-06 SSE 2.72E-07 0.00 0.00 2.27E-06 2.27E-06 S 1.82E-06 1.90E-07 0.00 1.63E-06 1.12E-06 l SSW 1.93E-06 4.00E-07 0.00 1.93E-06 1.03E-06 SW 1.10E-06 2.29E-07 2.35E-07** 9.50E-07 7.36E-07 WSW 1.20E-06 2.12E-07 0.00 9.90E-07 6.11E-07 W 7.19E-07 1.26E-07 0.00 5.71E-07 5.71E-07 WNW 7.65E-37 2.09E-07 0.00 6.59E-07 6.04E-07 NW 6.24E-07 4.99E-07 0.00 6.20E-07 6.20E-07 NNW 4.90E-07 3.05E-07 0.00 3.00E-07 2.76E-07 N 3.35E-07 2.20E-07 0.00 2.30E-07 2.30E-07 l

  • Zeroes irdicate that this point was not calculated
    • A milk goat is located here A-20

Page 130 of 164 TABLE A-18 0/Q Values for Short-Tern Mtxed Mode Releases at Special Locations (m-2)*

Carolina Powe & Lignt Conpany - Robinson Release Type: Purge Release Mode: Mixed Mode Variable: Relative Deposition Rate (Meter *2)

Calculation Points: Special Model: Purge (ACNPURG2)

Application of Terrain Correction Factors: No Number of Observations: 8703 Purge Time: 100 Hours Affacted Site Sector Boundary Meat Dairy Resident Garden NNE 5.77E-09 3.45E-09 0.00 5.70E-09 4.68E-09 NE 7.18E-09 5.72E-09 4.70E-09 5.20E-09 4.70E-09 CNE 1.04E-08 1.16E-09 0.00 9.77E-09 1.74E-09 E 2.08E-08 8.36E-10 5.32E-10 1.06E-08 9.36E-10 ESE 2.12E-08 2.22E-09 0.00 1.73E-08 1.73E-08 SE 2.99E-08 0.00 0.00 2.88E-08 2.88E-08 SSE 1.81E-08 0.00 0.00 1.64E-08 1.64E-08 5 3.04E-08 9.84E-10 0.00 2.80E-08 2.48E-08 SSW 3.66E-08 2.33E-09 0.00 3.72E-08 2.78E-08 SW 2.20E-08 1.48E-09 1.18E-09** 2.14E-08 1.97E-08 WSW 2.83E-08 1.23E-09 O.00 2.55E-08 2.07E-08 W 2.09E-08 4.69E-10 0.00 1.62E-08 1.62E-08 WW 2.01E-08 ,6.45E-10 0.00 1.38E-C8 8.18E-09 NW 4.98E-09 3.00E-09 0.00 4.53E-09 4.53E-09 NW 2.32E-09 9.15E-10 0.00 8.99E-10 8.09E-10 N 1.36E-09 5.75E-10 0.00 6.24E-10 6.24E-10

  • Zeroes indicate that this point as not calculated
    • A milk goat is located here A-21 Rev. 1

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a t s) t aet l ntC ne 2 n t rl u o51 i t e(i af u c i n i sh d s ) l sa t h o f sQt ,f nnrs d e rc a t i o / ) o s e n 9 mi t rD r1 e ii e o p so o( s awd ps t Q 1

- ro w i tf df s n t

i r r eyn e/

mX i

t A f r n n os rt t t o u

n s

(

n c i sas yi geent i e

E I o s oe pgs gcp eao eit i ort dh b

L e t r aonjpt c ol oa nt i

r B e i D aQae po i t t t rr/rD r c gi A

T i a oeX e o eh nh el wn i s

S lu f v vff yt t i cc i d

aeai t ai i et d t lc s c ( s i cwsh ri rw ed r e y n a - //QQnQ a/s/

Q c oys u f e x

us c aC XX t DQD l t eoro s u a

n e

l P s / eich o f s s e e) u l X l vl n n e al l i l t aad a a i af ea msy q e

o e v a uu ud u db t o%l e r d nnt nen nas t l ea sL n anent n i t i rnie hd t(

f i t aas aea wsd eit r d b dn u peet epe l d r f f f mt f f b

f e n o ooounoo of Rou i

nt t ct et a w i aaoad a c ne i G

r l l l l rrr mrr t l t

t uut uwu e eeel eee h -

gf n r nccncoc i l l il l l l

t bmmmt bb arbb c n m il A i

. o raaral a i u uu onu u ea / o f PCCPCAC T NNNTI NN Hh N J s 50505 0 n 0 01 2233 0 m 8 51 - - - - - 52 A 8

- - 1 61 61 - - / -

u 891 568 1 61 1 223 1 6 N 1 l 1 334555 1 o

' C e

p y

T 4 5 6 1 2 3 d

r a

C

,l l' ji; I!!  ! 1 i  ! i !li >

l l '

m i t; w.

O i TABLE A-19 (continued) ]

Value To Be Used .

f Card Type Columns -

Description in X0QD0Q

! 7 1-5 Wind velocity units correction 200.00 6-75 Maximum wind speed in each wind class (m/sec) 0.75 3.50 7.50 ,

' 12.50 18.50 i 25.00 26.00 I

i 8 1-80 Distance in meters at which terrain heights are given (2) l [ 9 1-80 Terrain heights (in meters, above plant grade) correspond (2) u to distances in Card Type 8 1

i 10 1-25 Number of receptor locations for a particular receptor type Site boundary = 16 i Dairy = 1 l

Meat = 14 Residence = 16

) Garden = 16 1

11 1-16 Title of receptor type for receptor locations Site 8oundary Dairy

- Heat l Residence Garden 12 1-80 Receptor direction and distance (See Table 1) l i

! 13 1-80 Title for release point whose characteristics are described (1) i on Card Type 14

1 2

E t;

w S,

TABLE A-19 (continued) -

. S'-

Value To Be used ,

Card Type Columns Gescription in X0000Q

, 14 1-5 Vent average velocity (m/sec) 20.1 6-10 Vent inside diameter (m) 1.0 d

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 building (m2) 1370.0 26-30 Wind height used for vent elevated Telease 11.0

< 31-35 Vent heat emission rate (cal /sec) 0.0 i

15 1 Identification for release point A 2-5 Intermittent releases- 1 6-10 Number of intermittent releases per year for this release point 100 11-15 Average number of hours per intermittent release 1 7

(1) Appropriate data to be supplied (2) Obtained from cross-sectional topographic maps l

g% >Y R ._ o "

s ,

d e

s u 0 0 Q 0 0

' e0 A ) )

BD / 7 7 51 553 1 1 68 1

Q 1 1 1 1 1 1 1 N ( 1 02 - _

(

o0 1 2 TX en ui l

a V

)

e -

v m i nd a st oe r t a i t g ng rt n o s ee oui P

r t mn t b r n g cip e ee er m s r st e "Q g a sb d 0 e hi eD s l

a) cd o Us 0Q l i 3 d(

a ey t

s eX t a a t ce n _

B" si rrs rnr o ed oe r oea i Te oCt ra er t

e , e f u qs t

a l t s) t aet l ne 2 n t rl u nh o t i t e(i af u c i

i n

o f sQt i sh

,f d

d e s )l sa ta w i o / ) o s nnrs e rc n

0 m t rD r1 e ii e 2 r s p so o( s i awd ps t Q o

- o n i t fdf t r r eyn e/ i A f io r n n sn os rt t t o mX t n t c i sasyi geent i ( u E I s oe eao eiti ort e b L a e pgs gcp t r ol oa dh i r

B el D aQae aonjpt c nt t u rr/rD r c gi po i t A

T i c oeX e o eh nh el wn i s

S la f v vf f yt ti cc i aeai t ai i et d d t C s' c ( s i c

cwsh ri r w x ed r e y n e QQnQ Q c a s // a/s/ oysu f e us n X X t DQD l t eoro s u l

Pa e s / eich o e a e al l i l Xl vl n f ss e) u l t a ad a a i af ea msy q

_ nR o e auu ud u dbt o%l e nas tl ea e

r s d nnt nen hd f n e nnent n i ti rnie t(

i t a as aea wsd eit r d b d u l d b n

oo peet epe r fff mt f f ooounoo f e R M nt t ut et a of i

_ i aaoad al c ne i w d l l l rrr mrr tl e t uut uwu e eeel eee h - t n

x nccncoc l bbb arbb gf i

il l i l l l t mmmt c mm il A i M raaral a i uuuonu u ea / o PCCPCAC T NNNTI NN l l l l N J r

f o

s 50505 0 n 0 01 2233 0 m 8 51 - - - - - 52 A 8 u 891 568 - - 1 61 61 - - / -

1 6 N 1

_ l o

1 334555 1 1 61 1 223

_ C ep y _

T 4 5 6 1 2 3 d

r a

C r0

E C.

v P,,

TABLE A-20 (continued) _.

Value To Be Used Card Type Columns Description in XOQD0Q 7 1-5 Wind velocity units correction 200.00 6-75 Maximum wind speed in each wind class (m/sec) 0.75 3.50 7.50 I 12.50 i 18.50 25.00 26.00 8 1-80 Distance in meters at which terrain heights are given (2)

! $ 9 l-80 Terrain heights (in meters, above plant grade) corresponding (2)

  • to distances in Card Type 8 10 1-25 Number of receptor locations for a particular receptor type Site boundary = 16 Dairy = 1 Meat = 14 Residence = 16
Garden = 16 11 1-16 Title of receptor type for receptor locations Site Boundary l

Dairy Meat Residence Garden 12 1-80 Receptor direction and distance (See lable 1) 13 1-80 Title for release point whose characteristics are described (1) on Card Type 14

E C

e TABLE A-20 (continued)

E Value To Be Used Card Type Columns Description in X0QD0Q 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) 60.7 16-20 Height of the vent's building (m) 59.0 21-25 Minimum cross-sectional area for the vent's building (m2) 1370.0 26-30 Wind height used for vent elevated release 11.

31 35 Vent heat emission rate (cal /sec) 0.

15 1 Identification for release point A 2-5 Intermittent releases 1 6-10 Number of intermittent releases per year for this release point 100 11-15 Average number of hours per intermittent release 1 O

(1) Appropriate data to be supplied (2) Obtained from cross-sectional topographic maps W

Page 137 of 164 APPEleIX B OOSE PARAMETERS FOR ~ RADI0 IODINES, PARTICULATES, AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for radiof odines, particulates, and tritium to show compliance with 10CFR20 and Appendix I of 10CFR50 for gaseous effluents. These dose parame-ters, P 4 and R9 , 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 Pj and R$

values for the various exposure pathways.

B.1 Calculation of Pg The dose parameter, 4P , contained in the radiotodine and particulates portion of Section 3.2 includes pathway transport parameters of the "i" radicnuclide, 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 dosc under the exposure conditions for Technict.1 Speciff-cation 3.9.3.1.b. For the infant exposure, separate values of P9 may be calculated for the inhalation pathway which is combined with a W parameter based on (X/Q) and the food (milk) and ground pathway which is combined with a

'W parameter normally based on (D/0) except for tritfum. The following sec-tions provide in detail the methodology which was used in calculating the Pg values for inclusion into this ODCM.

i .

B.1.1 Inhalation Pathway, l

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

l P4

=

K'(BR) DFA9 (B.1-1)

B-1 l

t

~

Pagn 138 of 164 where:

Pg = Dose parameter for radionuclide "i" for the innalation patn-3 way, mrem /yr per Ci/m ; ,

K' = A constant of unit conversion;

= 106 pCi/pCi; BR = The breathing rate of the infant age group, m3 fyp; DFAj = The maximum organ inhalation dose factor for the infant age group for radionuclide "1," mrem /pC1.

The age group considered is the infant group. The infant's breathing rate is 3

taken as 1400 m /yr from Table E-S of Regulatory GJide 1.109, Revision 1. The inhalation dose factors for the infant, DFA j, are presented in Taole E-10 of Regulatory Guide 1.109 in ur.its of mrem / pct . The total body is considered as an organ in the selection of DFAg .

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

l

= 9 (B .1-2 )

, P 9 1.4 x 10 0FA9 B.1.2 -Ground Plane Pathway The dose factor from ground plane pathway is calculated by:

P j = K'K"DFGj (1-e )/A 4 (B .1-3 )

i where:

i P

9

= Dose parameter for radionuclide "i" for the ground plane path-

- way, mrem /yr per pCi/sec per m*2;

K' = A constant of unit conversion; i = 106 pC1/pCi;

! B-2 l

Pcg2 139 of 164 K = A constant of unit conversion;

= 8760 hr/yr; A

g

= Tne radiological decay constant for radionucli'ce "i," sec~l; t = The exposure period;

= 3.15 x 107 sec (1 year);

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

mrem /hr per pC1/m2 .

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--tne only operating removal mecnanism for each radionuclide. The ground plane dose conversion factors for radionuclide "1," DFG j , are presented in Table E-6 of Regulatory Guide 1.109, Revision 1.

Resolution of the units yields:

Pg = 8.76 x 109 0FGj (1-e )/A g (B.1-4)

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

K'r Qp (U,P) F* -A gf t

P IM

= DFLI e (B.1-5)

Y p (Aj + \)

where:

P j = Dose parameter for radionuclide "1" for the cow milk or goat milk pathway, mrem /yr per C1/sec per m*2; K' = A constant of unit conversion;

= 106 pC1/pCi; Qp

= The cow's or goat's consumption rate of feed, kg/ day (wet wei ght );

B-3 k

Ptgs 140 of 164 V = The infant's milk consumption rate, liters /yr; ap Y

p

= The agricultural productivity by unit area, kg/M; F

m

= The stable element transter coefficient, pC1/ liter per pCi/ day; e = Fraction of deposited activity retained on co# 5 or goat's feed grass; 0FLj = The maximum organ ingestion dose factor for radionuclide "i,"

mrem /pCi; A

j

= The radiological decay constant for radionuclide "i," sec-I-A,

= The decay constant for removal of activity on leaf and plant surfaces by waathering, sec-1;

= 5.73 x 10~7 sec -I (corresponding to a 14-day half-life);

tf = 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.

3 Various parameters which were utilized to determine the Pj values for the cow and goat milk pathways are provided in Table B-1. Table E-1 of Regulatory Guide 1.109, Revision 1, provides the stable element transfer coefficients, F,; and Table E-14 of the same regulatory guide provides the ingestion dose ,

factors, OFLj, for the infant's organs. The organ with the maximum value of 0FLj was used in the determination of Pj for this pathway. The incorporation of the various constants of Table B-1 into Equation B.1-6 results in the following:

84 i

Pags 141 of 164 For radioiodines and particulates from cow's milk:

rF -A t II m (5.1-6)-

P9

= 2.4 x 10 10 DFL9 e -

For radiofodines and particulates from goat's milk pathway:

rF -AtII Pg

= 2.8 x 109 DFL, 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:

P7

=

K'KF,QpU,pDFLT 0.76(0.5/H) (8.1-8) where:

PTM

= 0 se parameter for tritium for the cow milk and goat milk pathways, mrem /yr per Ci/m3 ;

K = A constant of unit conversion;

= 103 gm/kg; H = Absolute humidity of the atmosphere, gm/m3 ;

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; 0FL7

= Maximum organ ingestion dose factor for tritium, mrem /pCf.

B-5

Page 142 of 164 8.2 Calculation of R, Following Regulatory Guide 1.109 Methodology The radiciodine and particulate Technical Specification 3.9.5.1 is applicable to the location in the unrestricted area where the combination of exist.ing pathways and receptor age groups indicates that the maximum potential exposure l

occurs. The inhalation and ground plane exposure pathways shall be considered to exist at all locations. The grass-goat-milk, the grass-cow-milk, grass-l cow-meat, and vegetation pathways are considered based on their existence at the various locations. Rj 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 (see Tables 3.3-1 through 3.3-19) is presented below and follows the guidance given in Regulatory Guide 1.109. .

8.2.1 Inhalation Pathway The dose factor from the inhalation pathway is calculated by:

Rj = K' (BR), (DFAj), (B.2.-1) where:

R, a Dose factor for each identified radionuclide "i" of the organ I of interest, mres/yr per uC1/m3 ;

1 K' = A constant of unit conversion;

= 106 pC1/uCi; (BR)a

= Breathing rate of the receptor of age group a, m3 /yr;

! (OFA j )a = Organ inhalation dose factor for radionuclide "i" for the i

recep' tor of age group a, mrem /pC1.

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 1.

B-6 Rev. 2

Pcga 143 of 164 Age Group (a) Breathing Rate (m3 /yr)

Infant 1400 Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFAj )a for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109, Revision 1.

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

R 9

=

19 K'K"(SF)0FG 9 (1-e I )/A 9 (B .2-2 )

where:

R = Dose factor for the ground plane pathway for each identified 9 ,

radionuclide "i" for the organ of interest, mrem /yr per uCi/sec per m-2; K' = A constant of unit conversion;

= 106 pCi/nCi; K" = A constant of unit conversion;

= 8760 hr/ year; Aj = The radiological decay constant for radionuclide "i," sec"l; t - = The exposure time, sec;

= 4.73 x 108 sec (15 years);

0FG 9 = The ground plane dose conversion factor for radionuclide "i;"

mrem /hr per pct /m2 ;

8-7

Peg 2 144 of'164 A tabulation of DFGj values is presented in Table E-6 of Regulatory Guide 1.109, Revision 1.

SF = The snielding factor (dimensionless);

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

Ij = Factor to account for fractional deposition of radionuclide j,

For radionuclides other than iodine, the factor I t is equal to one. For radioiodines, the value of Ij may vary. However, a value of 1.0 was used in calculating the R values in Table 3.3-2.

B.2.3 Grass Cow or Goat Milk Pathway The dose factor for the cow milk or goat milk pathway for each radionuclide '

for each organ is calculated by:

s .

I.

R, =

I gK'Op U ,F ,(DFLg ) ,e "htf ff die y

Tt) ie +

B iv (1-e b b) p

+

p 4E

-A I-E,te) B (1-e 1 b) -' -At f ) L ru-e Y A iv jh (1-fP5 ,

PA g

, (B.2-3) s Ej ,

j where:

R j = 00se factor for the cow milk or goat milk pathway, for each M

identified radionuclide "i" for the organ of interest, mrem /yr per pC1/see per m-2; B-8 t

.v_ . . . , - _ _ _ - . _ _ . . - _ . . , _ . _ . . _ _ _ _ , _ _ _ .._,,, - _. . , _ - , , _ _ . ,. , _..

Pagt 145 of 164-K' = A constant of unit conversion;

= 106 pCi/pCi; Op

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

~

U ap = The receptor's milk consumption rate for age group a, liters /yr; Y

p

= The agricultural productivity by unit area of pasture feed grass, kg/m2 ;

Y 3

= The agricultural productivity by unit area of stored feed, kg/m2 ;

F, ,= The stable element transfer coefficients, pCf/ liter per pCi/ day; r = Fraction of deposited activity retained on cow's feed grass; (DFL 9

)a = The organ ingestion dose for radionuclide "i" for the receptor in age group a, mrem /pCi; A'

E j Ai*AI w

= The radiological decay constant for radionuclide "1," sec-1; Ag x, = The decay constant for removal of activity on leaf and plant surfaces by weathering, sec"I-

= 5.73 x 10*7 sec ~1 (corresponding to a 14 day half-life);

tg = .The transport time from feed to cow, or goat to milk, to receptor, sec; B-9

Pegs 146 of 164 t

h

= The transport time for harvest, to cow or goat, to consump-tion, sec; t = Period of time that sediment is exposed to gaseous effluents, b

sec; Bjy = Concentration factor for uptake of radionuclide "i" from the soil by the edible parts of crops, pCi/Kg (wet weignt) per pCi/Kg (dry soil);

/

P = Effective surface density for soil, Kg (dry so11)/m2; f

p

= Fraction of the year that the cow or goat is on pasture; f = Fraction of the cow feed that is c3sture grass while the cow s

is on pasture; t,

= Period of pasture grass and crop exposure during the growing season, sec; , ,

= Factor to account for fractional deposition of radionuclide 14

. j , ..

For radionuclides other than iodine, the factor 19 is equal to one. For radiciodines, the value of It may vary. However, a value of 1.0 was use.d in I

calcuating the R values tii Tables 3.3-9 through 3.3-16.

i Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Fcilowing the development in Regulatory Guide l

1.109, Revision 1, the value of f 3 was considered unity in 'ieu of site-specific information. The value of f was p 0.667 based upon an 8-month grazing period.

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

B-10 l

l P

l - _ - _ . ,_ _._, _ _ __

Page 147 of 164 The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the Rj is based on X/Q:

RTg

= K'KF 0 Um F ap(DFLj)a 0.75(0.5/H) (B.2-:)

where:

R T

= Dose factor for the cow or' goat milk pathway for tritium for the organ of interest, mres/yr per uC1/m3 ;

K = A constant of unit conversion;

= 103 gs/kg; H = Absolute humidity of the atmosphere, ge/m3 ;

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 infomation.

3

- 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:

-A t -A t s

Eh .

8,y iy .

I Rj g = I jK'QpU ,pF f (OFLj ), e fp f, _r _

1

~k t ~

"r(1-e

-A t Ej e)

B jy (1-e ih)- 'gh-A t (1-ff) ps . yy 1 Pq .

(8.2-5) -

i wher'e:

Rj = Dose factor for the meat ingestion patnway for radionuclide 0 "i" for any organ of interest, mrem /yr per uCi/sec per m-2; 8-11 Rev. 1

Page 148 of 164 Fg = The stable element transfer coefficients, pCi/Kg per pCf/ day; U ap = The receptor's meat consumption rate for age group a, kg/yr; t = The transport time frem slaughter to consumption, sec; s

i t

n

= The transport time from harvest to animal consumption, see; t, = Period of pasture grass and crop exposure during the growing season, sec; 1

9

= Factor to account for fractional deposition of radionuclide ,

"1.*

For radionuclides other than iodine, It is equal to one. For radiciodines, the value of Ij 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 R4 for the meat pathway.

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

f Ry = K'KF Qpu f ap (OFLj)a 0.75(0.5/H) (B.2-6)

I where: .

RT

= Oose factor for the meat ingestion pathway for tritium for any organ of interest, arem/yr per uC1/m3 .

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

8-12 Rev. 1

Page 149 of 164 B.2.5 Vegetation Pathway 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 I time period between harvest and consumption, therefore:

-A -t t Rj = I jK' (DFLg ),

U, fg e

("TI-* t'I +

,,gg i b) y

. 1 I

e i h [ r(1-e E,t,}

g tv (l-e yb)

+ U, f 9 Y A y PA g

7) .

E, i

where:

R 9

= Dose factor for vegetable pathway for radionuclide "i" for the organ of interest, sres/yr per uC1/sec per m*2; K' = A constant of unit conversion;

= 106pC1/uC1; Uk = The consumption rate of fresh leafy vegetation by the receptor in age group a, kg/yr; l

U{ = The consumption rate of stored vegetation by the receptor in age group a, kg/yr; l ft = The fraction of the annual intake of fresh leafy vegetation grown locally; fg = The fraction of the annual intake of stored vegetation grown locally; t

t

= The average time between harvest of leafy vegetation and its consumption, sec; 8-13 Rev. 1

Pcga 150 of 164 t

h

= The average time between harvest of stored vegetation and its consumption, sec; Yy = The vegetation areal density, kg/m2 ;

t,

= Period of leafy vegetable exposure during growing season, sec; Ij = Factor to account for fractional deposition of radionuclide j,

All other factors as defined before.

For radionuclides other than iodire, the factor 1 4 is equal to one. For radiotodines, the value of I4 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 ft and f.g 1.0 and 0.76, respectively, were used in the calculations on Rj. These values were obtained from Table E-15 of Regulatory Guide 1.109, Revistor.1.

The concentration of tritium in vegetation is based on the airborne concentra- -

tion rather than the deposition. Therefore, the Rj is based on X/Q:

U fL + 0.75(0.5/H) (B.2-8)

R y,

= K'K

Uff g (OFLj )a L J where:

R = Dose factor for the vegetable pathway for tritium for any 7V 3

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

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

B-14

Paga 151 of 164 TABLE B-1 Parameters For Cow and Goat Milk Pathways Reference Parameter Value (Reg. Guide 1.109, Rev.1 Op (kg/ day) 50 (cow) Table E-3 6 (goat) Table E-3 2 0.7 Table E-15 Yp (kg/m )

1.73 x 105 (2 days) Table E-15 Tf (seconds) r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 (OFLj )a (mrem /pCi) Each radionuclide Tables E-11 to E-14 Fm (pCi/ day per pCi/ liter) Each stable element Table E-1 (ccw)

Table E-2 (goat) 4.73 x 108 (15 yr) Table E-15 Tb (seconds)

Y (kg/m 2) 2.0 Table E-15 3

0.7 Table E-15 Yp (kg/m ) ,

7.78 x 106 (90 days) Table E-15 th (seconds) 330 infant Table E-5 Vap (liters /yr) 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 2.59 x 106 (pasture) Table E-15 te (seconds) ~

5.18 x 10 (stored feed)

Table E-1 Bjy (pC1/kg [ wet weig ht]- Each stable element i

per pCi/kg (dry soil.l}

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

{

9 l

r 3-15 ,

.P

^

Paga 152 of 164 TABLE B-2 ,

Parameters For The Meat Pathway Reference Parameter Value (Reg. Guide 1.109, Rev. I r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 Ff (pCi/kg per pC1/ day) Each stable element Table E-1 Uap (kg/yr) 0 infant Table E-5 41 child Table E-6 65 teen Table E-5 110 adult Table E-5 (DFLj ), (mrem /pC1) Each radicnuclide Tables E-11 to E-14 2 .0. 7 Table E-15 Yp (kg/m )

Y3 (kg/m 2) 2.0 Table E-15 4.73 x 108 (15 yr) Table E-15 Tb (seconds) 1.73 x 106 (20 days) Table E-15 Ts (seconds) 7.78 x 106 (90 days) Table E-15 tn (seconds) t,(seconds) 2.59 x 106 (pasture) Table E-15 5.18 x 10 (stored feed)

Op (kg/ day) 50 Table E-3 8 9y (pC1/kg [ wet weight] Each stable element Table E-1 per pCi/kg [ dry soil])

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

3-16

Page 153 of 164 TABLE B-3 Parameters for The Veget,able Pathway Reference Parameter Value (Reg. Guide 1.109, Rev. I r (dimensionless) 1.0 (radiciodines) Table E-1 0.2 (particulates) Table E-1 (DFLj)a (mrem /C1) Each radionuclide Tables E-11 to E-14 Op (kg/ day) 50 (cow) Table E-3 6 (goat) Table E-3 Uk (kg/yr) - Infant 0 Table 'E-5

- Child 26 Table E-5

- Teen 42 Table E-5

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

- Child 520 Table E-5

- Teen 630 Table E-5

- Adult 520 Table E-5 8.6 x 104 (1 day) Table E-15 Tt (seconds)

5. 18 x 106 (60 days) Table E-15 th (seconds)

Yy (kg/m2) 2.0 Table E-15 5.18 x 106 (60 days) Table E-15 te (seconds) 4.73 x 108 (15 yr) Table E-15 Tb (seconds)

P (kg [ dry soil /m2 ]) 240 Table E-15 89y (pCi/kg (wet weicht Each stable element Table E-1 per pCi/kg [ dry soil.$) )

O B-17 i

_ _ _ . __ . - _ . _ _ . , - - , - , , . . . _ , ,. ___-..,__,y

Page 154 of 164 B.3 Calculation of R, Following NUREG 0133 Methodology The Grass-Cow-Milk pathway. Grass-Cow-Meat Pathway and the Vegetation Pathway can also be evaluated using the simpler methodology of NUREG 0133.

The following sections describe this simpler approach and provide the basis for Tables 3.4-1 through 3.4-10.

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l B-18 Rev. 2

Page 155 of 164 0.3.1: Grass-Cow-Milm C

Pathway (R1 [0/Ql) -A t-t h (U )' ff (1 - f f )e i h F ao ps p -s -A t Rc [0/Q] = K' F + e i r i A + A m (r) (OFLi )a Y Y

_i W. .p 5 -

=nere: Units = m2

  • mrem /yr per aci/sec o.forence taoi., R,c. i.,0 K' = A constant of unit conversion, 106 pCi/uCI.

QF = The cow's consumption rate, 50 kg/ day (=et E-3 weight)

  • U,, = The receptor's milk consumotion rate for E-5 age (a), in liters /yr 330 infant and child 400 feen 310 adult Y, = The agricultural productivity by unit area of E-15 pasture feed grass 0.7 kg/m 2 Y = The agricultural productivity by unit area of E-15 s

stored feed 2.0 kg/m 2 F, = The stante element transfer coefficients, in E-1 i

days / liter.

e = Fraction of deposited activity retained on cow's f eed grass 1.0 radiciodine E-15 0.2 particulates E-15 (OFL; ?a = The maximum organ ingestion dose f actor for the E-11 to E-14 ith radionuclide for the receptor in age group (a), in eres/pCI Ag = rhe decay constant for the ith radionuclide, in

-I sec A = The decay constant for removal of activity on leaf and plant surfeccs by weathering 5.73 m 10"I sec'I (corresponding to a I4 day half-life).

= The transport time from pasture to cow, to milk, E-15 t,

to receptor 1.73 a 10-5 see (2 days) t = The transport time from pasture, to harvest, to E-15 n

cow, to milk, to receptor 7.78 m 100 sec (90 days) f, = Fraction of the year that the cow is on pasture (dimensionless) = 18 f,

= Fraction of the cow feed that is pasture grass while the cow is on pasture (dimensionless) = 18

= Milk cattle are considered to be fed from two potential sources, p3sture grass and stoced feeds. Following the development in Regulatory Guide 1.109 (Ref. 6), the values in of f, and f, will be considered unity, in li.eu of site-specific information provided the annual land census report by the licensee.

Note: The aDove equction does not apply to the concentration of tritium in stilk. A separate equation is provided in NUREG 0133, Section 5.3.1.3 to determine tri+1um values.

Referance: The equation deriving Ry (0/0) was taken f rom NUREG 0133 Section 5.3.1.3 B-19 Rev. 2

Page 156 of 164 8.3.2: Grass-Cow-*eest Patn=ay (R* (0/Q])

-A t~

1 F(Uap )~ ~f f (1 - f f )e i h ps p s -A t Rm + e i f

[D/Ql = K' F f (r) (OFL i)a i a +A Y Y

_I W. .P 5 _

.nore: Units = m2

  • rr. rem /yr per uci/sec me terence raaie, e.o. i.iG K' = A constant of un6 t conversion 100 pCl/uci.

QF = The cow's consumption rate, 50 kg/ day (wet E-3

-eight) .

U s The receptor's milk consumption rate for E-5 age (a), in liters /yr infant--O

% 3d--41 Teen--65 Adult--II0 t,

a The agricultural productivity Dy unit area of. E-15 pasture feed grass 0.7 kg/m 2 t,

a the agricultural productivity by unit area of E-15 stored feed 2.0 kg/m2 F, a The stacle element transfer coefficients, in E-1 days / liter, c = Fraction of deposited activity retained on cow's feed grass-1.0 radiciodine E-15 0.2 particulates E-15 t,

= Transport time from pasture to receptor, in sec. E-15 0

1.73 x 10 sec (20 days)

= Transport time from crop field to receptor, in sec. E-15 t,

0 7.78 x 10 sec.

(90 days)

(DFL,)a = The maximum organ ingestion dose f actor for the E-II to E-14 l ith radionuclide for tne receptor in age group l

(al, in aree/pCI i A, a The decay constant for two Ith racionuclide, in sec'I f A, = The decay constant for removal of activity on leaf and plant surfaces by weathering 5.73 x 10"I'sec-3 (corresponding to a 14 day half-life).

f, -s Fraction of the year that the con is on pasture (dlaensionless) = 18 f, a Fraction of the cow feed that is pasture grass while the cow is on pasture (dimensionless) = I'.

    • d i l k cattle are considered to be fed from two potential sources, pasture grass and stored feeds. Following the dovetooment in Regulatory Guide 1.109 (r.of. 6), the values of f, and f, will be considered unity, in lieu of site-specific inrcreation provided in the annual land census report ey the licensee.

Note: The aeove equation does g apply to the concentration of tritium in milk. A separare i

equation is provided in NUREG 0133, Section 5.3.I.3 to determine tritium values.

l

Reference:

The equation deriving (0/0) was taken f rom NUREG 0133, Section 5.3.1.4 l

B-20 Rev. 2

Page 157 of 164 I

B.3.3: vegetation Pata=ay (R{ [0/Ql)

(r) -A t Uf e i L+Ufe i h S -A t Rv [0/Q] ='K' (OFL )

i i [Y (A .+ A aL ag v i w -

=nere: Units = m mrem /yr per uci/sec Reference raoie, a.s. i.to 6 pCi/uCI.

A constant of unit conversion, 10 E-5 K{

U

== The consumotion rate et fresn leafy vegetation ey ene a receptor in age group (a), in kg/yr, infant--O Child--26 Teen-a2 Adult--64 U ,$= The consumotion rate of stored vegetation ey the recentor E-5 in age , group (a), in kg/yr infant--O Child--520 Teen--630 Adult--520 (DFL;)a = The maximum organ ingestion dose f actor for the E-11 to E-la ith radionuclide for the receptor in age group (a), in aree/DCI f = The fraction of the ann 6al intake of fresn leafy vegetation gro=n locally (Default 1.0) the cow is on pasture f = The fraction of the annual intane of s'ored vegetation gro=n locally (Default 0.76)

= The average time between harvest of leafy vegetation t(

and its consumption, 8.6 x !O 4, seconds (I day) to receptor 1.73 x 10-5 sec (2 days) t = The average time between harvest of stored vegetation and E-15 h

its consumption, 5.18 x 106seconds (60 days) 7.78 x 106 sec (90 days) y

= The vegetation areal density, 2.0 kg/m2 l r = Fraction of deposited activity retained on the vegetation E-15 A, = The decay constant for removal of activity on leaf 1.0 radioiodine 0.2 particulates A, = The: decay constaat for the ith radionuclide in sec'I 1, = The decay constcnt for removal of activity on leaf and olant surfaces by weathering, 5.73 x 10*7 sec"' (corresponding to a 14 day half-life).

Note: The above equation doeso n,ot apply to the concentration of tritium in milk. A separate equation is provided in NUREG 0133, Section 5.3.1.3 to determine tritium values.

Referenes: The equation deriving R[ (0/0) =as taken f rom NUREG 0133. Section 5.3.1.5.

1 8-21 Rev. 2

Page 138 of 164 B.4 The calculations that suoport the 2500 CFM maximum instantaneous flow rate for a C.V. pressure relief as calculated by CP&L Nuclear Fuels Section, Project 85-0015, are found in File 2486-0015 and were performed by Mr. Talmage Clements, 10 February 1986.

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l 1 -

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i B-22 Rev. 2

Page -159 of 164 APPENDIX C LOWER LIMIT OF DETECTABILITY The LLD 1 ,2 is defined , for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal .

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

4.66 s b LLD =

E . V . 2.22 . Y . exp (-Aat) where:

LLD = "A priori" lower limit of detection as defined above, as picacuries per unit mass or volume; sb

= Standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate, as counts per minute; E = Counting efficiency, as counts per disintegration; V = Sample size in units 'of mass or volume; 2.22 = Number of disintegrations per minute per picocurie; Y = Fractional radiochemical yield, when applicable; A = Radioactive decay constant for the particular radionuclide; and at = The elapsed time between sample collection or end of the sample collection period and time of counting; C-1

Page 160 of 164 Typical values of efficiency, volume / mass, chemical yield, and radionuclid e decay corrections are to be used in the calculation.

It should be racognized that the LLD is defined as an a_ priori (before the fact) limit representing the capability of a measurement system and not as an a_ posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conoitions. Occasionally background fluctuations, unadvoidable small sample sizes, the presence of interfering nuclides, or other uncontroll-able circumstances may render these LLDs unachievable. In 'such cases, the contributing factors shall be identified and described in the Annual Rad io-logical Environmental Operating Report pursuant to Specification 6.9.1.E.3 References

1. HASL-300 (Suppl. 4), HASL Procedures Manual, (1972).
2. NBS SP456 "The Minimum Detectable Activity Concept," J. C. Lockamy (1976).
3. Technical Specifications for H. B. Robinson Unit 2.

I .

C-2

Page 161 of 164 TA8LE 0-1 Liquid Process Monitors l Name RMS # 10 # Orawing #

Containment Vessel 16 R-16 C997261 Fan Cooling Water Component Cooling 17 R-17 C997246 Water Liquid Waste Disposal 18 PI 871109 NRC Industries 4PI Liquid Sample Manual Condensate Polisher 37 R-37 s Plant Mod.-723 Liquid Waste H.B.R.-2-9065 i

Steam Generator 19 R-19 997261 Blowdown Liquid Radweste Flow Measurement Devices Liquid Radwaste Flow N/A FT 1064 l (ITT Barton Flow Integrator) l l

l 0-1 Rev. 1 l

Pagn 162 of 164 TABLE 0-2 Gaseous Process Monitors Sample Flow System Flow Rate Measurement Rate Name RMS # ID # Drawing # Device Measurement Device Containment Vessel 11 11 0997556 F&P Co. Flow Tube UGC Microflow 3000 Particulate FP-3/4-27-G 10/80 (if sampling stack)

Containment Vessel 12 12 0997556 F&P Co. Flow Tube UGC Microflow 3000 Gaseous FP-3/4-27-G 10/80 (if sampling stack)

Plant Vent low 14 R-14 0997704 UGC Microflow 3000 UGC Microflow 3000 Range Condenser Vacuum 15 R-15 0997299 Condenser Vacuum Pump Condenser Vacuum Pump Vent Flowmeter (on pump) Flowmeter (en pump)

Fuel Handling 20 R-20 C998233 Fisher Porter Flowmeter None (Use fan Building Basement Mod. 10A35755Z ratings)

Exhaust Serial 6908A0837Al Fuel Handling 21 R-21 C998233 Fisher Porter Flowmeter None (Use fan Building Upper Mod. 1043565 ratings)

Level Exhaust Mod. 6908A0837Al PING 2A Effluent 34 R-34 Eberline Dwyer Flowmeter VRFA27 UGC Microflow 3000 Monitoring System Pins 2-A Manual Plant Vent 36 R-36 Harshaw None UGC Microflow 3000 High Range Manual NR-75 0-2

r Page 163 of 164 ,

N. 9. RC91NSCN LICulO R A0 WASTE ccCCESS / EFFLUENT SYSTEM i+

STEAM STEAM STEAM 7 GENERATOR GENERATOR GENERATCR SUMP l \'

A B C OESCRATING SLOWDCWN BLOWOOWN BLOWOOWN '/

^

X [ qu3 CHEMICAQ

, K 39

. 0 RAIN t i ~$ / Tn.

l ,_ a_L___J CV

, h 4 SUMP LAUNDRY STEAM ,

/

  • GENERATOR BLOWOOWN SUMP FLASH TANK T M. (

A '\

- l RCS CRAiN -

lI TK.

SPENT RESIN M. g*

l

-r + ,

WASTE HOLOUP l TANK

, 4 LIQUl0 RA0 WASTE  % CVCS TREATMENT SYSTEM V ~ ~ ! - ~ ~,*)

I l I ORUM I EVAPORATOR 1 ROOM BORIC I i PACKAGE I I ACIO I I EVAP L. _ _ q _ _ _ .2 WASTE CONDENSATE TANKS VONITOR FLOW INTEGRATOR ANKS l RMS-18 l 1->d RCV 018

  • SIMPLIFIED BLOCK FLOW OI AGRAM h

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