Text

Rev 9 to Hb Robinson Steam Electric Plant,Unit 2,ODCM
	ML20091P443
Person / Time
Site:	Robinson
Issue date:	12/30/1994
From:	Young D; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML14182A408	List: ML14182A407; ML20091P443;
References
	PROC-941230, NUDOCS 9509010211
	Download: ML20091P443 (176)
	v • d • e

..

r United States Nuclear Regulatory Commission

) to Serial: RNP-RA/95-0159

- Page' ;5 of 172 CAROLINA POWER & LIGHT COMPANY H. B. ROBINSON STEAM ELECTRIC PIANT, UNIT No. 2

'0FF-SITE DOSE CALCULATIONAL MANUAL (ODCM)

Revision-9 DOCKET NO. 50-261 Y

t I

EFFECTIVE DATE

/

I 1

2d14HA Date:

/

9 Reviewed-By:

/

PNSC %ai g b

~

Accepted By:

bM Date:

/j2 8d [

PN$C pairmaff

/

HBRODCM r

9509010211 950829 PDR ADOCK 05000261

.. R.. _ _ _ _-._ _ _P DR..._ _... _..

w

. ---m

-. m.

t

.dnited' States Nuclear Regulatory Commission to Serial: RNP-RN95-0159 '

~

Page v6Tof 172 '

i TABLE OF CONTENTS'

~e O

Section Iilla Eagg

^

DTABIS OF. CONTENTS...............................................

_i LIST OF.TAhLES...a..............................................

11 i-LIST 0F FIGURES.................................................

iv-fl.0_

INTRODUCTION...........................,........................

1-1

2. 0..

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

2 2.1 Monitor'Alara Setpoint Determination................'......

2 : 2.2 - Compliance with 10CFR20.(Liquids).........................

2-11.

~2.3 Compliance with 10CFR50 (Liquids).........................

.2-16 GASEOUS EFFLUENTS...............................................

3-1 3,0 3.1 Monitor Alarm Setpoint Determination......................

3-1 3.2 Compliance with 10CFR20 (Gaseous).........................

3-15 3.3 Compliance with 10CFR50 (Gaseous)...................

3-24 3.4 Methodology for RMS ll Setpoint (Air Particulate).........

3-73

^

3.5 Methodology for R-14A Setpoint (Particulate Monitor)......

3-77 3.6 Methodology for R-14B Setpoint (Iodine Monitor)...........

3-79 3.7-Methodology for R-22 and R-23 Setpoint Determinations for.the' Iodine and Particulate Monitors...................

3-80 1

1 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM...................

4-1

.i 5.0 INTERLABORATORY COMPARI305 STUDIES..............................

5-1 F

5.1 0bjective......................

5-1 5.2 Pre 6 ram........................................

5-1

^

l l

6.0 TOTAL DOSE-(40CFR190 CONFORMANCE)...............................

6-1 6.1 Compliance with 40CFR190.....

6-1 6.2 Calculations Evaluating Conformance with 40CFa190.........

6-1 I

'6.3 Calculations of Total Body Dose...........................

6-2 L

6.4 Thyroid Dose..............................................

6-3

[

6.5 Dose Projects.............................................

6-3

~

i APPENDIX A - Meteorological Dispersion Factor Computations..............................................

A-1 APPENDIX B - Dose Parameters for Radioiodines, Particulates, and Tritium.................................

B-1 4

APPENDIX C - Lower Limit of Detectability.......................

C1 j

a

HBRODCM

-i Rev. 9

. : w: -

ta

United States Nuclear Regulatory Commission IEnclosure 2 to Serial: RNP-RA/95-0159 Page 7 of 172 LIST 0F TABLES No.

Title Egge 2.3 1~

Air Valhes for the Adult for the H.B. Robinson Steam Electric Plant.......................

2-22 L3.1-1 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 (M1.)................................

3 20 3.2-3 Dose Factors for Noble Gases and Daughters...............

3-21 3.2-4 P Values for a Child for the H.B. Robinson 3

Unic No.

2.........................................

3-22 3.3-1 thru R Values for the H.B. Robinson Steam Electric Plant......

3 3.3-19 thru 3-72 4.0-1 H.B. Robinson Radiological Environmental Monitoring Program.......................................

4-2

'A-l_

X/Q Values for Long-Term Ground Level Releases 3

at Special Locations (s ec/m )............................

A-4 i

A2 Depleted X/Q Values for Long-Term Ground Level 3

Releases at Special Locations (sec/m )...................

A-5 A-3 D/Q Values for Long-Term Ground Level Releases a t S p e c i al Lo c a t i ons ( m 2 )...............................

A-6

'A-4 X/Q Values for Long-Term Ground Level Releases 3

at S tandard Dis tances ( s ec/m )...........................

.A-7.

i A-5 Depleted X/Q Values for Long-Term Ground Level 3

Releases at Standard Distances (sec/m )..................

A-8 i

A6 D/Q Values for Long Term Ground Level Releases a t S t andar d D i s t anc e s ( m-2 )..............................

A-9 l

\\

A X/Q Valus_for Short-Term Ground Level Relenses at Special Loca tions ( s e c/m )............................

A-10 3

l A-8 Depleted X/Q Values for Short-Term Ground Level 3

Releases at' Special Locations (sec/m )..

A-11 4

p i

\\

HBRODCM 11 Rev. 9 j

l United States Nuclear Regulatory Commission

' Enclosure 2 to Serial: RNP-RA/95-0159

Page 8-of 172 LIST OF TABLES (continued)

No.

Title f.fute, A-9 D/Q Values for Short Term Ground Level Releases a t S p e c ial Loc a tions (m-2)...............................

A-12 A 10 X/Q Values for Long-Term Mixed Mode Releases 3

a t S p e c i al Lo c a t i o ns ( s e c/m )............................

A-13 A-ll Depleted X/Q Values for Long-Tern Mixed Mode 3

Releases at Special Locations (sec/m )...................

A-14 A-12 D/Q. Values for Long-Term Mixed Mode Releases a t S p e c ial Loca tions (m-2),,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,

g.15 e

j A-13 X/Q Values for Long-Term Mixed Mode Releases 3

at S tandard Dis tances (sec/m )...........................

A-16 A-14 Depleted X/Q Values for Long-Term Mixed Mode 3

Releases at Standard Distances (sec/m )..................

A-17 A-15 D/Q Values for Long-Term Mixed Mode Releases a t S tandard Dis tanc e s (m-2)..............................

A-18 A-16.X/Q Values for Short-Term Mixed Mode Releases at'Special Locations ( s e c /m )............................

A 19 3

A-17 Depleted X/Q Values for Short-Term Mixed Mode 3

Releases at Special Locations (sec/m )...............

A-20 A-18.D/Q Values for Short Term Mixed Mode Releases at Special Locations (m-2)...............................

A-21 A 19 Robinson Plant Site Information to be Used for Ground Level Calculations with NRC "XOQD0Q" Program.........................................

A-22 A-20 Robinson Plant Site Information to be Used for Mixed Mode Release Calculations with NRC "XOQD0Q" Program.........................................

A-25 B-1 Parameters for Cow and Coat Milk Par.hways................

B 15 B-2 Parameters for the Meat Pathway............

B 16 B-3 Parameters for the Vegetable Pathway.....................

B 17 D-1 Liquid Process Monitors..................................

D-1 D Caseous Process Monitors.................................

D-2 s

HBRODCM iii Rev. 9

-LUnited States Nuclear Regulatory' Commission to Serial:'RNP RA/95-0159 iPage 9. of 172 '

LTST OF FIGURES No '.

Title f.agt

'41

' Radiological Sample Locations Near Site..................

4-9 4-2 Radiological Sample' Distant Locations....................

4-10 D1

.H.B. Robinson Liquid Radwaste Effluent System............

D-3

'D-2 H.B.i Robinson Gaseous Radwaste Effluent System...........

D-4 m

1 i

1 1

i 1

1 HBRODCM iv Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 10 of 172

1.0 INTRODUCTION

The. Off Site Dose Calculation Manual (ODCM) provides the information and t

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 Specifications. These portions are those related to liquid and gaseous radiological effluents. They are intended to show compliance with 10CFR20, Appendix I of 10CFR50, and 40CFR190.

The ODCM is based on " Radiological Effluent Technical Specifications for PWRs (NUREC 0472, Rev. 3, Draft 7), " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREC 0133), and guidance from the United States Nuclear Regulatory Commission (NRC). Specific plant procedures for implementation of this manual are presented in H.

B.

Robinson Unit 2 Plant Operating Manual.

These procedures will be utilized by the operating staff of HBR to assure compliance with technical specifications.

Changes to the ODCM which affect the methodologies showing compliance with-10CFR20, Appendix I of 10 CFR 50, and 40 CFR 190 will be properly reviewed and approved as indicated in the Administrative Control Section of Plant Technical Specifications. Site specific parameters such as vent fractions, dilution water flow rates (gpm), and liquid / gaseous discharge flow rates are listed in this document as typical system values. Actual values derived from actual operating i

Plant conditions should be used in lieu of these typical values. Specific Plant procedures control the values of the above parameters; therefore, minimizing the need for frequent revisions to the 0.D.C.M.

The Semiannual Radioactive Effluent Release Report prepared af ter July 1 and January 1 of each year will be complied on the Canberra Nuclear Effluent Management System software.

This report will be prepared as outlined in Regulatory Guide 1.21. " Measuring, Evaluating, and Reporting Radioactivity in Solid Waste and Radioactive Materials in Liquid and Caseous Effluents from Light-Water-Cooled Nuclear Power Plants" (Revision 1, June 1974) with dats summarized on a quarterly basis following the format of Appendix B thereof, i

HBRODCM l-1 Rev. 9

1 United States Nuclear Regul tory Commissisn to Serial: RNP-RA/95-0159 Page 11 of 172 i

The Semitnnual Radioactive Effluent Release Report prepared after January 1 of each year will include an. assessment of the radiation doses from radioactive liquid and gaseous effluents using LADTAP and GASPAR software using concurrent meteorology obtained during the report period. This report will be inclusive of the requirements as outlined in the HER Technical Specifications.

l l

HBRODCM 12 Rev. 9

q United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 12 of 172 2.0 LIQUID EFFLUENTS 2.1 MONITOR ALARM SETPOINT DETERMINATION This methodology determines the monitor alarm setpoint that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds the concentrations specified in 10CFR20, Appendix B.

Table II, Column 2, for radionuclides other than dissolved or entrained noble gases or exceeds a

concentration 2 x 10-' pCi/ml for dissolved or entrained noble gases. Two methodologies may be utilized to calculate monitor alarm setpoints.

Section 2.1.1 determines a fixed setpoint based on the worst case assumptions that Cs-

-134 is the only nuclide being discharged.

This is consistent with the limit of 10CFR20, Appendix B,

Note 2.

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

2.1.1 Setooint Based on Cs-134 The following method applies to liquid releases via the discharge canal when determining the alarm / trip setpoint for the Condensate Polisher Liquid Waste Monitor (R-37) and the Steam Generator Blowdown Monitor (R-19A, R 19B, and R-19C) during operational conditions when there is no j

primary to secondary leaks. This methodology complies with Specification 3.9.1.1 of the RETS by satisfying the following equation:

'I sC f+F 4

where:

The effluent concentration limit (Specification 3.9.1.1)

C implementing 10 CFR 20 for the site in pCi/ml.

1 HBRODCM 2-1 Rev. 9 f

United States Nuclear Regulatory Commi::sion to Serial: RNP-RA/95-0159 Page li of 172 The setpoint, in pCi/m1, of the radioactivity monitor c

measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release:

the setpoint represents a value which, if exceeded, would result in concentrations exceeding 10 times the limits of 10CFR20 in the unrestricted area.

The waste effluent flow rate in gpm.

f The dilution water flow rate in gpm.

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

wheren c = N

f) (S) where:

9 x 10-7 pCi/m1, the effluent concentration limit based on C

10CFR20, Appendix B, for Cs-134.

Dilution water flow rate (gpm).

F 1

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

1 250,000 gpm from two circulating water pumps, Unit 2.

1 400,000 gpm from three circulating water pumps, Unit 2.

or a

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

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

The maximum acceptable discharge flow rate prior to dilution f

(gpm).

3 60 gpm for the Waste Disposal System Liquid Effluent Monitor.

i HBRODCM 2-2 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 14 of 172 160 gpm for each Steam Generator Blowdown Monitor.

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

300 gpm for the Condensate Polisher Liquid Waste Monitor.

0.5, safety factor used as a conservatism to assure that the S

radionuclide concentrations are less than the limits specified in 10CFR20, Appendix B, at the point of discharge.

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

t

}

CR (c) (E) i The applicable effluent monitor efficiency located in the E

Plant Operating Manual, Volume 15, Curve Book.

Use the radioactivity concentration "c"

to find CR.

2.1.1.3 Determine SP (the monitor alarm / trip setpoint including background

[ cpm) for each of the dilution water flow rates.

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

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 due to simultaneous releases from several pathways.

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

.25 for th:, tudensate Polisher Liquid Waste (R-37).

the monitor baakground.

Bkg HBRODCM 2-3 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 15 of 172 2.1.2 Setooint Based on an Analysis of Liould Prior to Discharge The following method applies to liquid releases via the discharge canal when determining the alarm setpoint for the Waste Disposal System Liquid Effluent Monitor (R-18), the Steam Generator Blowdown Monitors (R-19A, R-19B, and R-19C), and the Condensate Polisher Liquid Waste Monitor (R-37) when an analysis of the activity of the principal gamma emitters has been made prior to or during the release.

2.1.2.1 Determine D,,, (the minimum acceptable dilution factor):

D,g D,g,,

D,g,n

=

+

ci

,, act, D,"' '

(S) (b)

E n

g p, M'

~(S) (b) where:

D,,,,,

required dilution factor for gamma-emitters.

D,,,, n, -

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

effluent concentration limit of nuclide i in pCi/ml.

ECL i

FBRODCM 2-4 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 16 of 172 the concentration of nuclide i in pCi/al.

C i

0.5, a safety factor used for conservatism to assure that the S

radionuclide concentrations are less than the limits specified in 10 CFR Part 20 Appendix B, at the point of discharge.

The maximum ECL ratio limit.

R, 2.1.2.2 Determine the maximum vaste flow, R R'"*"

=

(D,, - 1. 0 )

F., n -

Available dilution flow in gpm.

1 160,000 gpm from one circulating water pump, Unit 2.

1 250,000 gpm from two circulating water pumps, Unit 2.

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

or 2

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

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

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

0.25 for the Waste Disposal System Liquid Effluent Monitor (R-18).

0.16 for each of the Steam Generator Blowdown Monitor (R-19A, R-19B or R-19C).

1 0.25 for the Condensate Polisher Liquid Waste (R-37).

F.,,rs + F

,e.

<1 the release cannot be If it is determined that (p,y) (F,,,)

made.

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

If

=H * #"* *

the release can be made.

>1 (Dig)(# waste)

HBRODCM 2-5 Rev. 9

United States Nuclear Regulatory Commission.

Enclosure 2 to Serial: RNP-RA/95-0159 Page 17 -of 172 2.1.2.3

' Determine the setpoint adjustment factor, S c - :

F. e,)

D,

( (Fa2,,) (F.,a2)

+

S*0

=

D,n,y Waste flow anticipated for this release (gpa).

i F.,,,s, 3

I 60 gpm for the Waste Disposal System Liquid Effluent Monitor.

1 160 gpm for each Steam Generator Blowdown Monitor.

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

300 gpm for the Condensate Polisher Liquid Waste Monitor.

2.1.2.4 Determine S, monitor alarm setpoint in pCi/ml:

(S,4) (E ci)

S, (pci/ml)

=

x 4

All gamma-emitting nuclides (pCi/ml).

C i

A 2.1.2.5 Determine the monitor alarm setpoint (S

., ) in CPM:

(S ) (E.) + Bkg S,,,

=

i 4

The applicable effluent monitor efficiency based on S, from E.

j the efficiency curves located in the Plant Operating Manual, Volume 15, Curve Book.

The monitor background in CPM.

Bkg 4

HBRODCM 2-6 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 18 of 172 (Left blank intentionally for future revisions)

HBRODCM 2-7 Rev. 9

1 United States Nuclear Regulatory Commission l Enclosure 2 to Serial: RNP-RA/95-0159

' Page 19 of 172

~

(Left blank intentionally for future. revisions) i.

1 1

4 s

1-1, I

i 4

4 4

J

)

I.

i 1.

W i

a i

i HBRODCM '

2-8 Rev. 9

United States Nuclear Regulatory Commission

Enclosure' 2 to Serial: RNP-RA/95-0159

- Page 20 'of 172 (Left blank intentionally for future revisions) 4 i

4 1

3

\\

J d

i 1

4 l

1 1

2

)

i 1

-l

\\

4 HBRCDCM 29 Rev, 9-

United States Nuclear Regulatory Commission to Serial: RNP-RA/95 0159 Page 21 of 172 SECTION

2.1 REFERENCES

1.

Carolina Power & Light Company Drawing Number C-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 Report.

4 1

HBRODCM 2-10 Rev. 9

United States Nuclear Regulatory Commission.

~

' Enclosure 2 to Serial: RNP-RA/95-0159

.Page 22 of.172 2.2 COMPLIANCE WITH 10CFR20 (LIQUIDS)

Liquid. effluents from H.B.

Robinson Unit 2 (HAR) will occur both I

continuously and on a batch basis.

The following sections discuss the methodology which will be utilized by the HBR to show compliance with 10CFR20.

2.2.1 Continuous Relegggg i

Steam generator blowdown may be a continuous release from HBR.

During l

release periods grab samples will be taken of stesa generator blowdown and analyzed for 1-131, fission, activation, and corrosion products as outlined in Table 4.10-1 of the Technical Specification for HBR.

These samples are then composited at a rate using the following equation:

j Vep (Va/Ve}

j-

.Vup i,.

where:

Volume to be replaced / updated (milliliters)

Vup Volume of the composite (milliliters) i Vcp Actual volume released from grab sample (gallons)

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

i compliance with 10CFR20 during actual release is established through the steam generator blowdown effluent monitor alarm setpoint. This setpoint l

is based upon Cs-134 as noted in Section 2.1.

However, if a continuous release should occur in which the effluent monitor alarm setpoint is exceeded, then actual compliance with 10CFR20 may be determined utilizing the actual radionuclide mix and the following equation:

Conc =

(2.2-1) s va 4

HBRODCM 2-11 Rev. 9

. United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 23 of 172 where:

Conci -

Concentration of radionuclide "i" at the unrestricted area, pCi/ml; Conecatration of radionuclide "i" in the continuous release, C,

i pCi/ml; Volume of continuous effluent released, gal; V.

Volume of dilution flow during release, gal.

V, 4

2.2.2 Batch Releases Batch releases will occur during normal operation.

When this does occur at HER, 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 concentration 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 potential batch release to the dilution flow rate to obtain the concentration at the unrestricted area. This calculation is shown in the following equation:

Conc, = f (2. 2 -2)

HBRODCM

.2-12 Rev. 9

' United States Nuclear Regulatory Commission

' Enclosure 2 to Serial: RNP-RA/95-0159 Page 24 of 172 l

where:

Conci -

Concentration of radionuclide "i" at the unrestricted area, pCi/ml; Concentration of radionuclide "i" in the potential batch C

i3 release, pCi/ml; 4

Release rate of the potential batch release, gpm; R

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

Fraction of dilution flow allocated to this release.

T, 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 Equation 2.2-3 is net.

Ej (Conc 3/ECg) s 1 (2. 2 -3 )

a where:

f Effluent Concentration Limit of radionuclide "i" from Appendix EC i

B, Table II, Column 2 of 10CFR20, pCi/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:

Conej =

(2.2-4) where:

Maximum continuous liquid effluent release rate, gpm.

R.

Su:smation of allocation fractions for these concurrent I T, releases HBRODCM 2-13 Rev. 9

l ' United States Nuclear Regulatory Commission i Enclosure 2 to Serial: RNP-RN95-0159 l Page 25 of 172 0

}

The mixture of radionuclider released must be of such concentrations that Equation 2.2-3 must be met.

1 For HBR, the liquid radwaste effluent line discharges to the circulating water system. Therefore, the dilution flow rate (Dg,) is a function of the number of circulating water pumps operating. Unit 2 of the H.B. Robinson Steam Electric Plant has three circulating water pumps. Pump curves show th t with three pumps operating, the circulating water flow is. 400,000 gpa, with two pumps--250,000 gpa, and with one pump--160,000 gpm. Unit 1 of the H.B. Robinson Steam Electric Plant has two circulating water pumps.

The circulating water flow is 50,000 gpa with one pump ard 80,000 gpm with two puana.

At least one circulating water pump must be operating during any lign d waste discharge.

Batch releases from the HBR liquid radwaste system may occur from the waste condensate tanks, the monitor tanks, and the steam generators (during drainage).

Continuous release may occur from Steam Generator Blowdown and the Condensate Polisher Liquid Waste.

The maximum administrative release rate (Rn) is 160 gpm for each of the steam gener -

. ators, 60 gpa from the monitor and waste condensate tanks, and 300 gpm for the Condensate Polisher Liquid Wastes, and 130 for each of the steam generators during drainage.

2.2.2.2 Postrelease i

The Steam Generation Blowdown Monitor (R-19A, R-19B, and R-19C), the Waste Disposal System Liquid Monitor (R-18), and the Condensate Polisher Liquid Waste Monitor (R-37) setpoint will each be limited to 50 percent of 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.

HBRODCM 2-14 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 26 of 172 The concentration of each radionuclide in the unrestricted area following release from a batch tank will be calculated in the following manne0r:

For the case where only batch releases are occurring, the total activity of radionuclide "i" released is divided by the actual dilution flow to obtain the concentration in the unrestricted area.

This calculation is shown in the following equation:

'*6 Concj,=

(2. 2 -5 )

Vs a

where:

Conc 33 -

The concentration of radionuclide "i" at the unrestricted area during release k, pCi/ml; Concentration of radionuclide "i" in the batch release k, C g3 i

pCi/ml; Volume of batch release k, gal; Vg3 4

Actual volume of dilution flow during release k, gal.

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

Es (Cone,/ECj) s.1 (2. 2 -6 )

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

Ykd = 6 0 E, (D,) e, (2. 2 -7 )

f where:

Conversion factor, min /hr; 60 Duration of release k, hr; tg HBRODCM 2-15 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 27 of 172 Dilution flow rate from circulating water pumps during release Dg, k, gpm.

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:

Concj,=

(2.2-8)

V,4 where:

4 Concentration of radionuclide "i" in continuous releases Ca, during release period k, pCi/ml; Volume of continuous release during period k, gal.

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

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

D,3 = Z, Z Aj, C,3 Cs,3 F,,,

(2. 3 -1) 3 HBRODCM 2-16 Rev. 9

United States Nuclear Regulatory Commission l-to Serial: RNP-RA/95-0159 Page 28 of 172 where:

The cumulative dose commitment to the total body or any D,'b organ r, from batch liquid effluents, mrem; The length of time of batch release k over which C mb and Fa i

ta are averaged for each batch liquid release, hours; Ca The average concentration of radionuclide "1" in undiluted i

batch liquid effluent during batch release k, pCi/ml; 4

e The site-related ingestion dose commitment factor to the total A,

i body sr any organ r for each identified principal gamma and beta emitter, mrem /hr per pCi/ml; The near-field average dilution factor for C a during any Fa i

batch liquid effluent release k.

Defined as the ratio of the volume of undiluted liquid waste released to the product of the dilution volume from the site discharge structure to unrestricted receiving waters times 1.0.

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

Vn v x 1. 0 u

Where Va and Vkd are as defined in Equation 2.2-5.

The dose factor A, was calculated for an adult for each isotope using the i

following equation:

(21BF ) DF,

(2.3-2) 1.14 x 105 A,

i i

i where:

3yx ggQ i

1.14 x 105 - 10' x 10 HBRODCM 2-17 Rev. 9 l

United States Nuclear Regulatory Commissisn to Serial: RNP-RA/95-0159 Page 29 of 172 Adult fish consumption rate from Table E-5 of Regulatory Guide 21 1.109. Revision 1, kg/yr; Bioaccumulation factor for radionuclide "i" in fish from Table BF i

A-1 of Regulatory Guide 1.109, Revision 1, pCi/kg per pCi/1; Dose conversion factor for radionuclide "i" for adults for a DF,

i particular organ r from Table E-11 of Regulatory Guide 1.109, Revision 1, mrem /pC1.

The potable water pathway does not exist either within Lake Robinson or j

downstream of the Lake Robinson dam.

Therefore, the potable water cerm was excluded from the calculation of A, values. Table 2.3-1 presents A,

i i

values for an adult at HBR.

i As noted in Section 2.2.2, steam generator blowdown is continuously released from HBR. The dose from continuous releases will be calculated using the following equation:

D,, = E, E j Aj, C,, Cj,, F,,

(2.3-3) where:

The cumulative dose commitment to the total body or any D,,

organ r, from liquid effluents for continuous releases, mrem; The length of time of continuous release period k over which tg.

Cm, and Fg, are averaged for all continuous liquid releases, i

hours; The average concentration of radionuclide "i" in undiluted C g, i

li;uid effluent during continuous release period k from any continuous liquid release, pCi/ml; 4

HBRODCM 2-18 Rev. 9

United States Nuclear Regulatory Commission to Seriai RNP-RA/95-0159 Page 30. cf 172 The near-field average dilution factor for Ca, during contin-Fm, uous liquid effluent release k.

Defined as the ratio of the volume of undiluted liquid waste released to the product of the dilution volume from the site discharge structure to unrestricted receiving water times 1.0.

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

V V x 1. 0 u

Where Va, and Vnd are, as defined in Equations 2.2-8 and 2.2-5 respectively, only now distinguished for continuous releases.

The sum of the cumulative dose from all batch and continuous releases for a quarter are compared to one half the design objectives for total body and any organ.

The sum of the cumulative doses from all batch and calendar year are compared to the design continuous releases for a objective doses. The following relationships should hold for HBR to show compliance with Technical Specification 3.9.2.1 of the technical specificatioru for H.B. Robinson Unit 2.

f For the calender quarter, D, $ 1.5 mrem total body (2.3-4) 3-

~

D, 5 5 mrem any organ (2.3-5)

For the calendar year, D, 5 3 mrem total body (2 3 6)

Dr s 10 mrea any organ (2.3-7)

HBRODCM 2 19 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159

, Page 31 of 172 where:

Cumulative total dose to any organ r or the total body from D,

continuous and batch releases, arem; i

D,s + D,,

The quarterly limits given above represent one half the annual design j

objective of Section II. A of Appendix I of 10CFR50.

If any of the limits 4

.)

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 j

report complies with Section IV.A, of Appendix I of 10CRF50.

2.3.2 Proiection of Doses Doses resulting from the release of liquid effluents will be projected 4

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.

4 I

Projected dose will be calculated as follows:

i pp. 31 (M

D8)

+M (2.3-8)

(TE)

J l

where:

projected doses in area.

PD dose accumulated during current quarter in mrem.

DA projected dose from this release.

DB time elapsed in quarter in days.

TE safety margin in arem.

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

HBRODCM~

2-20 Rev. 9 i

f. United States Nuclear Regulatory Commission

' Enclosure 2 to Serial: RNP-RA/95-0159 Page 32 ~ of 172 '-

'(Left blank intentionally).

3-n i

i i

L i

1 4

4 e

1 d

l-i

.i l

1 J'

\\

1 4

4 4

HBRODCM 2-21 Rev. 9 J

United States Nuclear Regulatory Commission

( Enclosure 2 to Serini: RNP-RN95-0159 i

, Page 33 of 172 TABLE 2.3-1 Au VALUES for the ADULT for the H.B. ROBINSON STEAM ELECTRIC PIANT (area /hr per pCi/si) i 4

)

i hclide lent Li?.ar T. Body Thyroid Kidney Luns CI-LLI 1hin H-3

.0.00E+00 2.27E-01 2.27E-01 2.27E 01 2.27E 01 2.27E-01 2.27E-01 2.27E 01 i

F-18 2.30E-02 2.13E-02 2.15E-02 2.13E 02 2.13E 02 2.13E-02 2.13E 02 2.51E 02 NA-24 1.35E+02 1.35E+02 1.35E+02 1.35E+02 1.35E+02 1.35E+02 1.35E+02 7.45E-01 l

CR-51 2.51E-01 2.51E-01 1.49E+00 9.94E 01 5.25E-01 1.90E+00 3.13E+02 2.96E-01 l

MN 7.45E+01 4.45E+03 9.09E+02' 7.45E+01 1.38E+03 7.45E+01-1.35E+04 8.74E+01 MN-96' 4.86E-02 2.23E-01 7.94E-02 4.86E 02 2.69E-01 4.86E-02 5.60E+00 5.74E 02 FE 55 6.59E+02 4.55E+02 1.06E+02 0.00E+00 0.00E+00 2.54E+02 2.61E+02 0.00E+00 l

FE 1.04E+03 2.42E+03 9.38E+02

1. ( ? ?.+01 1.47E+01-6.88E+02 8.04E+03 1.72E+01 Co-57 1.01E+01 2.89E+01 4.49E+01 1.01E+01 1.01E+01 1.01E+01 5.41E+02 1.11E+01 CO-58 2.04E+01 1.09E+02 2.19E+02 2.04E+01 2.04E+01 2.04E+01 1.81E+03 2.39E+01 CO-60 1.16E+03 1.41E+03 1.72E+03-1.16E+03 1.16E+03 1.16E+03 5.98E+03 1.36E+03 NI 65 1.88E-01 3.83E 02 2.62E-02 1.60E-02 1.60E 02 1.60E-02 5.83E-01 1.86E-02 l

CU 64 3.26E-02 2.73E+00 1.30E+00' 3.26E-02 6.83E+00 3.26E-02 2.30E+02 3.70E-02 ZN-65 2.32E+04 7.37E+04 3.33E+04 4.02E+01 4.93E+04 4.02E+01 4.64E+04 4.62E+01 BR-82 1.15E+00 1.15E+00 1.42E+03 1.15E+00 1.15E+00 1.15E+00 1.63E+03 1.33E+00 BR-83 2.62E-04 2.62E-04 3.87E 02 2.62E-04 2.62E-04 2.62E-04 5.56E-02 3.81E-04 BR-84 1.09E-02 1.09E-02 1.09E-02 1.09E-02 1.09E-02 1.09E-02 1.09E-02 1.27E-02 RB-86 4.83E 01 9.75E+04 4.54E+04 4.83E-01 4.83E-01 4.83E-01 1.92E+04 5.52E-01 RB-88 1.78E-03 1.78E-03 1.78E-03 1.78E-03 1.78E-03 1.78E-03 1.78E-03 2.03E-03 RB-89 6.61E-03 6.61E-03 6.61E-03 6.61E-03 6.61E 03 6.61E-03 6.61E-03 7.93E 03 SR-89 2.19E+04 1.16E-03 6.27E+02 1.16E-03 1.16E-03 1.16E-03 3.51E+03 1.35E 03 j

SR-90 5.45E+05 0.00E+00 1.34E+05 0.00E+00 0.00E+00 0.00E+00 1.58E+04 0.00E+00 SR-91 7.09E+01 1.16E-01 2.98E+00 1.16E-01 1.16E-01 1.16E-01 3.37E+02 1.35E-01 SR-92 3.76E 01 4.18E 02 5.62E-02 4.18E 02 4.18E-02 4.18E-02 6.66E+00 4.64E 02 4

Y-91M 5.39E-03 5.39E-03 5.39E-03 5.39E-03 5.39E-03 5.39E-03 5.39E-03 6.24E-03 Y-91 8.41E+00 5.77E-02 2.81E-01' 5.77E-02 5.77E-02 5.77E-02 4.60E+03 6.49E-02 Y-93 1.02E-02 9.70E-03 9.72E-03 9.70E 03 9.70E 03 9.70E-03 8.09E+00 1.15E-02 Y-93 4.08E-02 9.86E-03 1.07E 02 9.86E 03 9.86E-03 9.86E-03 9.82E+02 1.35E-02 ZR-95 1.34E+01 1.32E+01 1.32E+01 1.32E+01 1.33E+01 1.32E+01 2.55E+02 1.53E+01

'ZR-97

.- l. 64E- 01 1.60E-01 1.60E-01 1.59E-01 1.61E-01 1.59E-01 3.11E+02 1.85E-01

'NS-95 4.46E+02 2.51E+02 1.39E+02 7.35E+00 2.49E+02 7.35E+00 1.48E+06 8.65E+00 NB-97 9.47E-03 9.47E 03 9.47E 03 9.47E 03 9.47E-03 9.47E-03 1.29E-02 1.11E-02 MO-99 2.15E-01 8.06E+01-1.55E+01 2.15E-01 1.82E+02 2.15E-01 1.86E+02 2.49E-01 TC-99M 1.05E-02 1.15E-02 3.01E-02 9.90E-03 3.40E-02 1.07E-02 9.4.E-01 1.13E-02 TC-101

'1.09E-03 1.09E 03 1.09E 1.09E 03 1.09E 03 1.09E-03 1.09E 1.22E-03 1

q HBRODCM 2-22 Rev. 9

~ United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 34 of 172 TABLE 2.3-1 (continued)

Nuclide

long, Liv 3e1 T. Body Thyroid Kidney Luyng GI-LLI Skin RU-103 1.02E+01 5.82E+00 7.70E+00 5.82E+00 2.25E+01 5.82E+00 5.15E+02 6.79E+00 RU-105 4.29E-02 3.42E-02 3.77E-02 3.42E-02 1.47E-01 3.42E 02 5.36E+00 3.88E-02 RU 106 8.85E+01 2.27E+01 3.10E+01 2.27E+01 1.50E+02 2.27E+01 4.28E+03 2.72E+01 AC-110M 1.86E+02 1.86E+02 1.85E+02 1.85E+02 1.86E+02 1.85E+02 5.17E+02 2.16E+02 SN-113 2.00E+03 7.80FA01 1.90E+03 2.80E+01 5.75E+01 7.66E 01 3.50E+04 2.19E+00 SB-124 3.88E+01 3.23E+01 3.48E+01 3.22E+01 3.22E+01 3.73E+01 2.21E+02 3.71E+01 SB-125 1.30E+02 1.26E+02 1.27E+02 1.26E+02 1.26E+02 1.29E+02 1.73E+02 1.42E+02 TE-129M 1.08E+04 4.03E+03 1.71E+03 3.71E+03 4.51E+04 1.06E+00 5.44E+04 1.24E+00 TE-129.

1.43E 03 1.42E-03 1.42E-03 1.42E-03 1.49E-03 1.41E-03 1.42E-03 1.67E-03 TE-131M 9.54E+02 4.67E+02 3.89E+02 7.39E+02 4.72E+03 4.32E-01 4.63E+04 5.09E-01 TE-132 1.95E+03 1.26E+03 1.19E+03 1.40E+03 1.22E+04 2.28E-01 5.98E+04 2.68E-01 1-131 1.38E+02 1.97E+02 1.13E+02 6.44E+04 3.38E+02 9.25E-01 5.27E+01 1.12E+00 I-132 7.23E 02 8.11E-02 7.19E-02 5.61E-01 8.95E-02 6.70E 02 6.96E 02 7.88E-02 I-133 2.31E+01 4.01E+01

-1.23E+01 5.87E+03 6.98E+01 1.32E-01 3.60E+01 1.60E-01 I-134 2.40E 02 2.40E-02 2.40E-02 2.40E-02 2.40E-02 2.40E-02 2.40E-02 2.85E-02 I-135 1.42E+00 3.50E+00 1.38E+00 2.22E+02 5.54E+00 1.36E-01 3.94E+00 1.59E-01 CS-134 2.98E+05 7.10E+05 5.80E+05 3.69E+02 2.30E+05 7.66E+04 1.28E+04 4.30E+02 CS-136 2.96E+04 1.17E+05 8.42E+04 8.12E+00 6.51E+04 8.93E+03 1.33E+04 9.20E+00 CS-137 3.83E+05 5.23E+05 3.43E+05 5.55E+02 1.78E+05 5.95E+04 1.07E+04 6.47E+02 CS-138 1.93E-02 1.93E-02 1.93E-02 1.93E 02 1.93E-02 1.93E-02 1.93E-02 2.21E-02 BA-139 5.70E-03 5.69E-03 5.69E-03 5.69E-03 5.69E-03 5.69E 03 5.70E-03 6.41E 03 BA-140 1.86E+02 1.34E+00 1.32E+01 1.10E+00 1.18E+00 1.24E+00 3.81E+02 1.26E+00 BA-142 2.41E-03 2.41E-03 2.41E-03 2.41E-03 2.41E-03 2.41E-03 2.41E-03 2.75E-03 LA-140 1.13E+00 1.088+00 1.05E+00 1.03E+00 1.03E+00 1.03E+00 3.67E+03 1.17E+00 LA-142 4.09E-02 4.09E-02 4.09E-02 4.09E-02 4.09E-02 4.09E-02 4.16E-02 4.90E-02 CE-141 7.57E-01 7.50E-01 7.37E-01 7.35E-01 7.42E-01 7.35E-01 5.75E+01 8.28E-01 CE-143 1.27E-01 1.89E+00 1.25E-01 1.24E-01 1.25E-01 1.24E-01 6.62E+01 1.41E-01 CE 144 4.91E+00 4.23E+00 3.80E+00 3.74E+00 4.03E+00 3.74E+00 3.98E+02 4.32E+00 PR-144 9.87E-05 9.87E-05 9.87E-05 9.87E 05 9.87E 05 9.87E-05 9.87E-05 1.13E-04 HF-181 1.33E+01 1.06E+01 1.09E+01 1.06E+01 1.06E+01 1.06E+01 2.12E+02 1.50E+01 W-187 1.48E+02 1.23E+02 4.32E+01 1.26E-01 1.26E-01 1.26E-01 4.04E+04 1.47E-01 NP-239 1.13E-01 9.41E-02 9.31E-02 9.20E-02 9.85E-02 9.20E-02 4.29E+02 1.06E-01 H8RODCM 2-23 Rev. 9

United States Nuclear Regulatory Commission.

' : Enclosure 2 to Serial: RNP-RN95-0159 Page,35 of 172 (Left blank intentionally).

4 i

i; f.

i i

l 4

i l

4 4'

i-4 i

l '.

HBRODCM 2-24 Rev, 9-i.

i

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 36 - of 172

)

3.0 GASEOUS EFFLUENTS 3.1 MONITOR AIARM SETPOINT DETERMINATION 4

This methodology determines the monitor alarm setpoint if the dose rate in the unrestricted areas due to radionoble gases in the gaseous effluent released from the site to areas at and beyond the site boundary exceeds 500 mrea/ year to the whole body or exceeds 3000 mres/ year to the skin

-using a conservative mix (CALE Code).

4 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.

l 3.1.1 Setooint Based on Conservative Radionuclide Mix (Ground and Mixed Mode Releases Releases through the steam generator flash tank vent can only occur l

through this vent when significant primary-to-secondary leakage exists within the steam generators and the blowdown is not going through heat recovary. Detection of primary-to secondary leakage is accomplished most effectively by continuously monitoring the condenser vacuum pump vent (R-l 15). Steam generator blowdown is continuously monitored by R-19A, R-198, j

and R 19C as a liquid pathway. The condenser vacuum pump vent discharges via plant vent which is monitored by R 14, i.

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

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

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

i

!!BRODCM -

31 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 37. of 172 3.1.1.1 Determine the " mix" (noble gas radionuclides and composition) of the gaseous effluent.

Determine S, the fraction of the total noble gas radioactivity in the i

gaseous effluent comprised by noble ga9 radionuclide "i," for each individual noble gas radionuclide in the, gaseous effluent or use the Si from Table 3.1 1 when using CALE Code.

~

Sj =

(3.1-1)

The radioactivity of noble gas radionuclide "i" in the gaseous A

t effluent from T.tble 3.1-1.

3.1.1.2 Determine the Q,,

the maximum acceptable total release rate

[pci/sec] of all noble gas radionuclides in the gaseous effluent based upon the whole body exposure limit of 500 mrem / year by:

l 500 O, =

(3.1-2 )

(XID) Es KjSg (X/Q) -

The highest calculated annual average relative dispersion 4

factor for any area at or beyond the unrestricted area 3

boundary for all sectors (sec/m ).

8.1 E 5 sec/m (Continuous Ground Release) from Table A 1, 3

Appendix A.

9.9 E-7 sec/m (Mixed Mode Release) from Table A-10, Appendix 3

A.

The total whole body dose factor due to gamma emissions from K

i 3

noble gas radionuclide "i" (ares /yr/ pCi/m ) from Table 3.12.

HBRODCM 3-2 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RN95-0159 Page 38 of 172 3.1.1.3 Determine Q,, the maximum acceptable release rate (pCi/sec) of all I

gas radionuclides in the gaseous effluent based upon the skin ex-posure limit of 3000 aren/yr by:

3000 0" -

g3,1_3)

(77D) Is [(Ls + 1.1 Mj) Sj) i 4

i The total skin dose factor due to emissions from noble Li + 1.lHi 3

gas radionuclide "i" (arna/yr/pCi/m ) from Table 3.1-2.

3.1.1.4 Determine C., the maximum acceptable total radioactivity concentra-tion [pC1/cc) of all noble gas radionuclides in the gaseous effluent.

1 3

C, =

( T,) (SF)

( 3.1-4 )

i NOTE: Use the lower of the Q values obtained in Sections 3.1.1.2 and 3.1.1.3.

This will protect both the skin and total body from being exposed to the limit.

where:

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 due to simultaneous releases from several pathways.

0.92 for Plant Vent Cas Monitor (R-140).

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

HBRODCM 3-3 Rev. 9 4

United States Nuclear Regulatory Commission -

- Enclosure 2 to Serial: RNP-RA/95-0159 Page 39. of 172 The maximum acceptable effluent flow rate at the point of F

g release (cfa).

60.600 cfm for plant vent.

10,200 cfm for the fuel-handling building.

Unit conversion constant to convert pCi/sec/cfm to pCi/cc.

2.12 E-3 gsee - Ic3 y min - cc An engineering' factor used to provide a margin of safety for SF 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 [ cpm], by:

4 i

(C.) (E.)

(3.1 5) 4 CR where:

Obtained from the applicable effluent monitor efficiency curve E,

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 (cpm], by:

HSP = CR + background (3.1-6)

\\

HBRODCM 3-4 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159-Page 40. of 172 i

l 3.1.2 Setooint Based on s==nle Analysis Prior to Release

-)

The following method applies to gaseous releases when determining the I

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

Batch Releases Containment purge.*

j e

\\

Containment pressure relief.

e i

i Waste gas decay tanks.

e 1

i Continuous Releases Plant vent.

Fuel har.dling basement exhaust.

Environmental and Radiation Control Building Hood Exhaust.

I i

Containment purge.

e Radwaste Building exhaust vent.

4 Batch containment purge is considered as 1 volume of containment air 4

removed.

4

'i i

t e

.HBRODCM 3-5 Rev. 9

' Urdted States Nuclear Regulatory Commission Ecclosure 2 to Serial: RNP-RA/95-0159 Page: 41. of 172 3.l'.2.1-Determine R, the noble gas release rate (pCi/sec] for radionuclide i

"i":

472 (C ) (F).

(3.1-7)

R.

i t

i where:

A conversion factor to convert cfm to cc/sec.

472-The radioactivity concentration of noble _ gas radionuclide "i" C.

3 from analysis of gaseous effluent (pCi/cc) from the Plant Vent (stack). Fuel Handling Basement Exhaust, Environmental &

Radiation Control (E&RC) Building Hood Exhaust, Radwaste Building Exhaust Vent and the Contat unent Vessel when R-12 is sampling - from the Containment.

If there are no isotopes identified in the sarple, the EC for Xe-133 may be used as an actual value for the purpose of the setpoint calculation.

Containment Purge--

i (pC1/cci from analysis of Containment Vent)(0.366) + (pci/cci I

from analysis of Plant Vent) (0.634)

Contr.inment Pressure Relief--

(pci/cci from analysis of Containment Vent)(0.040) +

4 (pci/cci from analysis of Plant Vent) (0.960)

Waste Gas Decay Tanks--

[

(pCi/cci from analysis of UGDT) (0.0016) +

(pci/cci from analysis of Plant Vent) (0.9984) g HBRODCM 3-6 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 42 of 172 Waste Gas-Decay Tanks during Containment Purge--

(pci/cci from analysis of WGDT) (0.0010) +

( Ci/cci from analysis of Plant Vent) (0.633) +

( Ci/cci from analysis of C.V.) (0.366)

J 0.366 -

Dilut n correction factor for

=

(60,600 + 35,0

) Cm 60,600 cm 0.634 -

Dilution correct'.on factor for

=

(60,600 + 35,000) m Plant Vent during C.V. Purge 4

2500*Cm 0.040 -

Dilution correction factor for

=

(60,600 + 2500') Cru C.V. Pressure Relief 60,600 cm 0.960 -

Dilution correction factor for

=

(60,600 + 2500 *) N Plant Vent during C.V. Pressure Relief 0.0016 -

Dilution correction factor for

=

(60,600 + 1 ) Cm Waste Gas Decay Tank 0.9984 -

Dilution correction factor for

=

(60,600 + 1 CFM 4

Plant Vent during WGDT Release 0.0010 -

Dilution correction factor fer

=

(60,600 + 50

+ 100) Cm Waste Gas Decay Tank during a Continuous C.V. Purge and Plant Vent Release 0.633 -

Dilution correction factor for

=

(60,600 + 35,000 100) C m Plant Vent during a Continuous C.V. Purge and Plant Vent Release O.366 -

Dilution correction factor for

=

(60,600 + 35,000 100) Cm Continuous C.V. Purge during WGDT Release e

1 HBRODCM 3-7 Rev. 9

)

$ United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 43 of 172 The maximum acceptable affluent flow rate at the point of F

release (CFM) 60,600 cm for the plant vent 10,200 L*FM for the fuel handling basement exhaust 11,500 CFM for the E&RC building hood exhaust 15,000 CFM for the Radwaste Buildin5 exhaust vent 95,600 CFM for the containment vessel purge plus plant vent 63,100 cm for the containment vessel pressure relief 60,700 CFM for the waste gas decay tank 95,700 CFM for the waste gas decay tank during a continuous j

containment vessel purge 35,000 CFM for containment vessel purge or continuous release 2500 CFM for containment vessel pressure relief releases 1

2500 CFM--Refei-to Appendix B,4 for additional information i

1

{

HBRODCM 3-8 Rev. 9

United States Nuclear Regulatory Comminion

- Enclosure 2 to Serial: RNP-RA/95-0159 Page 44 of 172_

3.1. 2 -. 2 -

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

a.

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

K R (3.1-8)

(X/Q) Zi DRn t i where:

The highest calculated annual average relative dispersion X/Q factor for any area at or beyond the unrestricted area 3

i boundary for all sectors (sec/m ) from Appendix A.

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

Appendix A.

To be conservative this can be used for all releases.

9.9 E-7 sec/m (continuous mixed node release) from Table A-3 1

10, Appendix A, only with upper wind speeds of 5 9 mph.

5.1 E-5 sec/m3 (batch ground release) from Table A-7, Appendix A.

2.9 E-6 sec/m (batch mixed mode release) from Table A 16, 3

Appendix A.

The total whole body dose factor due to gamma emissions from K

i 8

noble gas radionuclide "i" (mrem /yr/ Ci/m ) from Table 3.1-2.

b.

Determine dose rate for skin (mrem /yr).

4 (3.1-9)

X/Q Et (Li + 1.1 M ) Rt DRsx i

HBRODCM 3-9 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 45 of 172 where:

1 The total skin dose factor for noble gas emission "i" L + 1.1 M t

i 8

radionuclide (area /yr/pci/m ) from Table 3.1-2 c.

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

PDRRn=

(3.1 -10 )

PDRRms "

(3al-ll)

The allowable total body dose rate due to noble gas gamma 500 emissions in mrem /yr.

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

d.

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

Maximum Monitor Total Body Setpoint =

(SF) ( T,)

(3.1-13) i pg Maximum MoniCor Skin Secpoint =

(SF) ( T,)

(3.1-13)

(PDRRmy) l 1

i MBRODCM 3-10 aev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159

.Page 46 of 172 where:

i i

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

.5 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 due to simultaneous releases from several pathways.

1 0.92 for the Plant Vent Cas Monitor (R-14C).

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

0.01 for other potential release points.

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

I 0.01 for the Radwaste Building exhaust vent Monitor (R-23).

0.01 for C.V. releases via R-11 and R-12

[This indic.ates 0.81 of 10CFR20 limits for Containment releases and is also monitored by R-14C.

0.92 - 0.81 + 0.11 (Normal Plant Releases))

Determine the maximum monitor setpoint (CPM) for total body (S ) and e.

t skin (S.).

(Maximum total body setpoint in pCi/cc) (monitor efficiency)

S t

+ Bkg (3.1-14) i HBRODCM 3-11 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 47 of 172 (Maximum skin setpoint in Ci/cc) (monitor efficiency) + Bkg S.

(3.1-15) r Obtained from the applicable effluent Monitor efficiency monitor efficiency curve located in the Plant Operating Manual, Volume 15, Curve Book. Use the radioactivity concentration (pCi/ce) to find (CPM).

The monitor background.

Bkg f.

Determine the actual gaseous monitor setpoint:

The setpoints that were determined based on the dose rate limits to the total body (S ) and to the skin (S.) are compared and the lesser t

value is used as the actual setpoint.

i 4

)

4 4

HBRODCM.

3-12 Rev. 9

United States Nuclear Regulatory Coaunhsion to Serial: RNP-RA/95-0159 Page 48 of 172 TABLs 3.1-1 GABEngs ensarv TEBS' Condenser Vacuse Conteirunent Purse Plant Vent Release' Pussp Vent' or Proespro Relief Gas Decay Tanks' Radionuclide A (C1/yr) 5, 4 (Cityr) 3, A (C1/yr) 5 A (Cf/yr) 5 Kr-8Se 2.0E0 5.26E-2 1.0E0 4.35E-2 0.00 0.00 0.00 0' ;;0 Kr-85 0.00 0.00 0.00 0.00 0.00 0.00 1.6E2 8.00E-1 Kr-87 1.0E0 2.63E-2 0.00 0.00 0.00 0.00 0.00 0.00 Kr-88 3.0E0 7.89E-2 2.0E0 8.70E-2 1.0E0 2.90E-3 0.00 0.00 Xe-131m 0.00 0.00 0.00 0.00 1.0E0 2.90E-3 9.0E0 4.50E-2 Xe-133m 0.00 0.00 0.00 0.00 4.0E0 1.16E-2 0.00 0.00 Xe-133 2.8E1 7 37E-1 1.8E+1 7.83E-1 3.1E2 8.99E-1 3.1El 1.55E-1 J

Xe-135 4.0E0 1.05E-1 2.0E0 8.70E-2 4.0E0 1.16E-2 0.00 0.00 l

1 Ar-41 0.00 0.00 0.00 0.00 2.5El 7.25E-2 0.00 0.00 TOTAL 3.8E1 2.3E1 3.45E2 2.0E2 9

Source terms are based upon GALE Code (not actual releases) from the svaluation of H.B. Robinson Unit 2 to demonstrate conformance to the design objectives of 10CFR50, Appendix I, Tabla 2-4.

These values are only for routine releases and not i

for a complete inventory of gases in an emergency.

1These values are used to determine the monitor alarm setpoints for the Plant Vent Gas Monitor (R-14C).

2These values are used to determine the monitor alarm setpoint foe the Condenser Vacuum Pump Vent Monitor (R-15). R-15 is a process monitor and its effluents cre monitored by R-14A, R-14B and R-14C.

This column is intentionally left for reference.

8These values, are used to determine the monitor alarm setpoint for the Fuel Handling Basement Exhaust Monitor (R-20).

HBRODCM 3-13 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 49 of 172 TABLE 3.1-2 4

DOSE FACTORS AND CONSTANTS

Total Whole Body Total Skin Dose Factor Dose Factor (K )

(Li + 1.1 M )

i i

8 3

Radionuclide (arem/yr/pCi/m )

(area /yr/pci/m )

i 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 i

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 j

Regulatory Guide 1.109, October 1977, Table B-1, times (1.0 E6 pCi/pci).

i HBRODCM 3-14 Rev. 9 1

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 50' of 172 3.2'

' COMPLIANCE WITH 10CFR20 (CASEOUS) 3.2.1 Noble Gases 4

The gaseous effluent monitors setpoints are utilized to show compliance with 10CFR20 for noble Bases.

However, because they are based upon a conservative mix of radionuclides, the possibility exists that the setpoints could be exceeded and yet 10CFR20 limits may actually be met.

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

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

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

Es Ks I (77D), ds, + (77D), ds,] s 500 mram/yr (3. 2 -1)

Es (Ls + 1.1 Ms) [(77D),ds, + (77D),ds,] s 3000 mrom/yr (3.2-2) i where:

Annual average relative dilution for plant vent releases (X/Q),

3 at the site boundary, sec/m.

From Table A-1 for ground level releases used for additional conservatism.

From Table A-10 for mixed mode releases.

Annual average relative dilution for the Fuel Handling (X/Q),

Basement Exhaust, the Environmental and Radiation Control Building Exhaust, and Radwaste Building Exhaust 3

releases at the site boundary, sec/m.

From Table A-1 for ground level releases.

HBRODCM 3-15 Rev 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 51 of 172 -

The total body dose factor due to gamma emissions for noble K

i 3

gas radionuclide "i," area / year per pCi/m.

The skin dose factor due to beta emissions for noble gas L

i 3

radionuclide "i," arem/ year per pCi/m.

The air dose factor due to gamma emissions for noble gas M

i 3

radionuclide "i," mrad / year per pCi/m.

The ratio of the tissue to air absorption coefficients over 1.1 the energy range of the photon of interest, mrem / mrad (reference NUREG 0133, October 1978),

J The release rate of noble gas radionuclide "i" in gaseous Qi, effluents from the radwaste building exhaust vent, tuel handling basement exhaust, and the environmental and radiation control building hood exhaust, pCi/sec.

The release rate of noble gas radionuclide "i" in gaseous Qi, effluents from the plant vent pCi/sec.

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

The X/Q value utilized in the equations for implementation of 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 the 16 sectors as well as to the nearest residence, vegetable j

garden, cow, goat, and beef animal. Long-term annual average (X/Q) values for the HBR release points to the special locations in Table 3.2-2 are presented in Appendix A.

A descriptian of their derivation is also i

provided in this appendix.

1 l

I HBRODCM 3-16 Rev. 9

- United States Nuclear Regulatory' Commission to Serial: RNP-RA/95-0159 i

Page 52 of 172 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 mode releases may not necessarily decrease with distance (i.e., the site boundary may not have the highest X/Q value), lon5-term annual l

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, i

and NNW so that the maximum site boundary X/Q is usually greater at the i

site boundary than at distances greater than the site boundary.

In addition, the maximum site boundary X/Q for both the ground level and mixed mode releases occurs at the SSE site boundary.

Therefore, the limiting location for implementation of 10CFR20 for noble gases is the SSE site boundary.

T and M, which were used in the determination of the Values for K,

L, i

i i

limiting 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 Re5ulatory Guide 1.109, Revision 1.

The values have been multiplied by 1.0 E6 to convert picoeuries to microcuries for use in Expressions 3.2-1 and 3.2-2.

i I

3.2.2 B,pdiciodines. Particulates. and Tritium The dose rate in an unrestricted area resulting from the release of radio-l iodines, tritium, and particulates with half-lives 2 8 days is limited to 1500 mrem /yr to any organ.

Based upon NUREG 0133, the following is used to show compliance with 10CFR20.

Zj Pj, [ (T/D), dj, + (T/D), dj,) s 1500 mrem /yr (3. 2 -3 )

l i

HBRODCM 3-17 Rev. 9

)

.. ~

c United States Nuclear Regulatory Commission l Enclosure 2 to Serial: RNP-RA/95-0159 Page 53 of 172 Di, Release rate of radionuclide "i" from the plant vent, pCi/sec.

j.

D[..

Release rate of radionuclide "i" from the radwaste building exhaust vent, fuel handling building basement exhaust, and environmental and radiation control building exhaust pCi/sec.

j (X/Q),-

Annual average relative dilution for plant vent releases at 8

i the site boundary, sec/m.

(X/Q) -

Annual average relative dilution for fuel handling building,

basement exhaust, environmental and radiation control building exhaust, and radwaste building exhaust vent releases at the 8

j site boundary, sec/m.

l Pil The dose parar.eter for Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days for the inhalation pathway only in the most j

restrictive sector in arem/yr per Ci/m. The dose factor is 3

s.

based on the most restrictive group (child) and most i

restrictive organ at the SITE BOUNDARY (see Table 3.2-4).

i I-where:

I In the calculation to show compliance with 10CFR20, only the inhalation is l

considered.

A description of the methodology used in calculating the P t i

values is presented in Appendix B.

Compliance with 10CFR20 is achieved if the dose rate via inhalation pathway to a child is 5 1500 arem/ year.

l-

i d

i 1

i HBRODCM 3-18 Rev. 9 4

1 t

United States Nuclear Regulatory Cornminion to Serial: RNP-RA/95-0159

; Page.'54 '. of 172 1

TABLE 3.2-1 4

RELEASES FROM H.B. ROBINSON UNIT No. 2*

(Ci/yr) i Condenser Vacuum Plant Vent Pump Vent Isotope (Q,)

(Q )

Total Kr-85m 2.0E0 1.0E0 3.0E0 Kr-85 1.6E2 0.00 1.6E2 Kr-87 1.0EO.

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 i

Xe-135 8.0E0 2.0E0 1.0El i.

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 1.6E-3 0.00-1.6E-3 Co-58 1.6E-2 0.00 1.6E-2 e

Co-60 7.3E-3 0.00 7.3E-3 i

i Sr-89 3.4E 4 0.00 3.4E-4 Sra90 6.3E-5 0.00 6.3E-5 Cs-134 4.7E-3 0.00 4.7E-3 Cs-137 7.8E-3 0.00 7.8E-3 l

Calculations based upon GALE Code and do not reflect actual release data from the Evaluation Conformance to the Design Objectives of 10CFR50, Appendix I.

These values are only for routine releases and not for a. complete inventory of j

gases in an energency. Condenser vacuum pump vent is intentionally left in for reference, i-HBRODCM

'3-19 Rev. 9 a

. United States Nuclear Regu atory Commission l to Serial: RNP-RA/95-0159 Page 55 of 172 i

TABLE 3.2-2 DISTANCE TO SPECIAL LOCATIONS FOR THE H.B. ROBINSON PIANT (MILES)

Site Milk Milk Meat Nearest Nearest Sector Boundsrv Cow Goat Animal Resident Garden 1.65 1.3 1.4 NNE 1.26 1.16 1.2 1.3 NE 1.01 2.41 0.9 2.2 ENE 0.86 3.12 0.8 2.8 E

0.61 4.2 1.99 0.6 0.6 ESE 0.50 0.3 0.3 SE 0.29 0.3 0.3 SSE 0.26 2.32 0.3 0.4 S

0.28 2.08 0.3 0.5 SSW 0.29 SW 0.36 2.5*

2.27 0.4 0.5 2.69 0.4 0.6 WSW 0.36 3.97 0.6 0.6 W

0.50 4.07 0.7 0.9 WNW 0.55 1.60 1.3 1.3 NW 1.23 2.84 2.9 3.0 NNW 1.89 1

2.93 2.9 2.9 l

N 1.94

Milk is not presently used for human consumption.

i i

HBR0DCM 3-20 Rev. 9

=

United States Nuclear Regulatory Commission to Serial: RNP-RAi95-0159 Page 56 of 172 TABLE 3.2-3 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS

Total Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor N

K L

Hi i

i i

(arem/yr (arem/yr (arad/yr (mrad /yr 8

3 3

3 Radionuclide per pCi/m )

per pCi/m )

per pC1/m )

per pCi/m )

1.93E+01 2.88E+02 Kr-83m 7.56E-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 9,3E+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 2.51Et02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E.+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

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

HBRODCM 3-21 Rev. 9

l United States Nuclear Rigulatory Commission to Serial: RNP-RA/95-0159 MMC 57 of 172 -

TaaLE 3.2-4 I

Pg val-UES for a CHILD for the 1

'H.B.

ROBINSON UNIT No. 2 l

Nuclide Zi Bone P. Liver P. T. Body P. Thyroid Z. Kidney P. Luna P. GI-Tract Pi Skin H3 0.00E+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 l

F-18 6.96E+03' O.00E+00-

6. 8 5 E+02.. 0.00E+00 0.00E+00 0.00E+00 '1.25E+03 0.00E+00 I

NA 1.61E+04 1.61' 04 -1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 0.00E+00 s

t CR-51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 0.00E+00 MN-54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 0.00E+00 i

MN-56 0.00E+00 1.66E+00 3.12E-01 0.00E+00 1.67E+00 -1.31E+04 1.23E+05 0.00E+00 i

j FE-55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03 0.00E+00 FE-59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.07E+04 0.00E+00 CO 0.00E+00 9.03E+02 1.07E+03 0.00E+00 0.00E+00 5.07E+05 1.32E+04 0.00E+00

[

CO-58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 0.00E+00 f

CO 60' O.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 0.00E+00 i

NI-65 2.99E+00 2.96E-01 1.64E-01 0.00E+00 0.00E+00 8.18E+03 8.40E+04 0.00E+00 1

CU-64 0.00E+00 1.99E+00 -1.07E+00 0.00E+00 6.03E+00 9.58E+03 3.67E+04 0.00E+00

)

~ZN-65 4.26E+04 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 0.00E+00 BR-82 0.00E+00 0.00E+00 2.09E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-83 0.00E+00 0.00E+00 4.74E+02.0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l

BR-84 0.00E+00 0.00E+00 5.48E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.99E+03 0.00E+00 I

'RB-88 0.00E+00 5.62E+02 3.66E+02 0.00E+00 0.00E+00 0.00E+00 1.72E+01 0.00E+00 f:~RB-89 0.00E+00 3.45E+02 2.90E+02 0.00E+00 0.00E+00' O.00E+00 1.P

+00 0.00E+00

'SR-89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 0.00E+00 SR-90 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07' 3.43E+05 0.00E+00 SR-91 1.21E+02 0.00E+00 4.59E+00 0.00E+00 0.00E+00 5.33E+04 1.74E+05 0.00E+00 SR-92 1.31E+01 0.00E+00 5.25E-01 0.00E+00 0.00E+00 2.40E+04 2.42E+05 0.00E+00 Y-91M 5.07E 01 0.00E+00 1.84E 0.00E+00 0.00E+00 2.81E+03 1.72E+03 0.00E+00 Y-91 9.14E+05 0.00E+00 2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84E+05 0.00E+00 Y-92 2.04E+01 0.00E+00 5.81E-01 0.00E+00 0.00E+00 2.39E+04 2.39E+05 0.00E+00 I

Y 93 1.86E+02 0.00E+00 5.11E+00 0.00E+00 0.00E+00 7.44E+04 3.89E+05 0.00E+00

]

i.

ZR-95 1.90E+05-4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 -0.00E+00 ZR-97 1.88E+02 2.72E+01 1.60E+01 0.00E+00 3.88E+01 1.13E+05 3.51E+05 0.00E+00 i

1 j

(a) NUREG 0133, Section 5.2.1.1.(Calculation of Pi (Inhalation)).

1 (b) Regulatory Guide 1.109 Table E-5, Table E-9-(Breathing Rate Constant and

. Inhalation dose factors).

3 (c) Units are aren/yr per.pCi/m.

HBRODCM 3-22 Rev. 9 p

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 58 of 172 TABLE 3.2-4 (continued)

Fuelide Z. Bone Z. Liver I. T. Body Z. Thyroid Z. Kidnev Z. lung P. CI-Tract F. Skin NB 95 2.35E+04 9.18E+03 6.55E+03 0.00E+00 8.62E+03 6.14E+05 3.70E+04 0.00E+00 l

NB-97 4.29E 01 7.70E-02 3.50E-02 0.00E+00 8.55E-02 3.42E+03 2.78E+16 0.00E+00 MO-99 0.00E+00 1.72E+02 4.25E+01 0.00E+00 3.92E+02 1.35E+05 1.27E+05 0.00E+00 TC-99M 1.78E-03 3.48E-03 5.77E-02 0.00E+00 5.07E-02 9.51E+02 4.81E+03 0.00E+00 TC-101 8.10E 05 8.51E-05 1.08E-03 0.00E+00 1.45E-03 5.85E+02 1.63E+01 0.00E+00 RU-103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 0.00E+00 RU-105 1.53E+00 0.00E+00 5.55E-01 0.00E+00 1.34E+00 1.59E+04 9.95E+04 0.00E+00 RU-106 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1.84E+05 1.43E+07 4.29E+05 0.00E+00 AC 110M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 0.00E+00 SN 113 8.99E+03 2.90E+02 9.81E+03 1.19E+02 2.03E+02 3.40E+05 7.44E+03 0.00E+00 i

SB-124 5.74E+04 7.40E+02 2.00E+04 1.26E+02 0.00E+00 3.24E+06 1.64E+05 0.00E+00 SB 125 9.84E+04 7.59E+02 2.07E+04 9.10E+01 0.00E+00 2.32E+06 4.03E+04 0.00E+00 I

TE-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 0.00E+00 TE-129 9.77E-02 3.50E-02 2.38E-02 7.14E-02 2.57E-01 2.93E+03 2.55E+04 0.00E+00 TE 131M 1.34E+02 5.92E+01 5.07E+01 9.77E+01 4.00E+02 2.06E+05 3.08E+05 0.00E+00 TE-132 4.81E+02 2.72E+02 2.63E+02 3.17E+02 1.77E+03 3.77E+05 1.38E+05 0.00E+00 l

I-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03 0.00E+00 I-132 2.12E+03 4.07E+03 1.88E+03 1.94E+05 6.25E+03 0.00E+00 3.20E+03 0.00E+00 I-133 1.66Ev04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 0.00E+00 1 134 1.17E+)3 2.16E+03 9.95E+02 5.07E+04 3.30E+03 0.00E+00 9.55E+02 0.00E+00 I-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 0.00E+00 4.44E+03 0.00E+00 CS-134 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 0.00E+00 CS-136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04 1.45E+04 4.18E+03 0.00E+00 CS-137 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 0.00E+00 1

CS-138 6.33E+02 8.40E+02 5.55E+02 0.00E+00 6.22E+02 6.81E+01 2.70E+02 0.00E+00 q

BA-139 1.84E+00 9.84E-04 5.36E-02 0.00E+00 8.62E-04 5.77E+03 5.77E+04 0.00E+00 BA-140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 0.00E+00 BA-142 4.99E-02 3.60E-05 2.79E-03 0.00E+00 2.91E-05 1.64E+03 2.74E+00 0.00E+00 LA-140 6.44E+02 2.25E+02 7.55E+01 0.00E*00 0.00E+00 1.83E+05 2.26E+05 0.00E+00 LA-142 1.29E+00 4.11E-01 1.29E-01 0.00E+00 0.00E+00 8.70E+03 7.59E+04 0.00E+00 CE-141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 0.00E+00 CE-143 3.66E+02 1.99E+02 2.87E+01 0.00E+00 8.36E+01 1.15E+05 1.27E+05 0.00E+00 CE-144 6.77E+06 2.176+06 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+05 0.00E+00 PR-144 5.96E 02 1.85E-02 3.00E 03 0.00E+00 9.77E-03 1.57E+03 1.97E+02 0.00E+00 HF-181 8.33E+04 3.28E+02 8.47E+03 2.76E+02 2.63E+02 7.96E+05 5.29E+04 0.00E+00 W-187 1.63E+01 9.66E+00 4.33E+00 0.00E+00 0.00E+00 4.11E+04 9.10E+04 0.00E+00 NP-339 4.66E+02 3.34E+01 2.35E+01 0.00E+00 9.73E+01 5.81E+04 6.40E+04 0.00E+00 HBRODCM 3-23 Rev. 9

United States Nucleak Regulatory Commienion - to Serialr RNP-RA/95-0159.

Page:59 of 172 :

3.3 COMPLIANCE WITH 10CFRSO (GASEOUS) ll i3.3.11 Noble cases t

'3.3.1.1 Cumulation of Doses 4-

Based upon NUREG 0133, the air dose in the unrestricted area due to noble gases released in gaseous effluents can be determined by the following}

~

equations:

D =. 3.17 x 10-8 E g Ng [(T/D),, Dj, + (7/Q), Gj, + (T/D), Dj,]

(3.3-1) y

D, = 3.'17 x 10-' E, Ng [ (7/D), Dj, + (7/Q), 43, + (T/D), Dj,]

(3. 3 -2) t i'

where:

The air' dose from gamma radiation, arad.

' D.,

The air dose from beta radiation, arad.

De Tha air dose factor due to gamma emissions for each identified Mi 3

noble gas radionuclide "i," mrad / year per pCi/m.

i-The air dose factor due to beta emissions for each identified 4.

N 3

3 noble gas radionuclide "i," mrad / year per pCi/m.

4

'(X/Q), --

The annual average dilution for areas at or beyond the unrestricted' area boundary for long-term plant vent releases 3

(> 500 hrs / year), sec/m.

>From Table-A-1 for ground level releases used for

. conservatism'.

I j s'

HBRODCM3 3-24' Rev. 9-

-w,-

.-e y

l JUnited States Nuclear Regulatory Commienion

: Enclosure 2 to Serial: RNP-RA/95-0159

- Page 60 ' of 172 1

From Table A-10 for mixed mode releases.

4 l

'(X/q),-

The dilution for. areas at or beyond the unrestricted ' area boundary for short-term plant vent releases

($

500 3

hours / year), sec/m.

i From Table A-1 for ground level continuous -release for

(

conservatism.

I From Table A-7 for ground level. releases.

i j[

From Table A-16 for mixed mode releases.

j

.(X/Q), -

Annual average relative dilution for fuel handling basement j_

exnaust, the environmental and radiation control building 1

exhaust, and radwaste building exhaust vent releases at the 8

site boundary, (> 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months / year), sec/m.

~

From Table A-1 for ground level releases; i

qi, The average release of noble gas radionuclide "i" in gaseous i~

releases for short-term plant releases. ($ 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months / year),

i pCi; t

The average release of noble gas radionuclide "i" in gaseous Qi, releases for long-term fuel handling basement exhaust, the 5

environmental and radiation control building exhaust, and radwaste building exhaust (> 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months / year), pCi; The average release of noble gas radionuclide "i" in gaseous j

Q3y

[

effluents for long-term vent releases (> 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months / year), pCi; i

The inverse of the number of seconds in a year (sec/ year)~1 3.17 x 10'8 At HBR the limiting location is 0.26 miles SSE.

Based upon the tables presuted in Appendix A, substitution of the short-tern X/Q value into Equation 3.3-1 yields lower dose value than the long-term X/Q values been i

used.

In order to be conservative, for purposes of this document only, long-term annual average (X/Q)

P t

i HBRODCM' 3-25

~Rev. 9 e

L United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159-

- Psge ' 61 of 172 values will be used.

Should the calculated doses exceed 10CFR50 limits, j

recalculation'of doses may be performed using short-term X/Q values for batch releases, i-To select the limiting location, the highest annual average X/Q value for ground level and mixed mode releases and the highest short-term X/Q value for ground level and mixed mode releases were considered.

Since mixed

' mode releases may increase and then decrease with distance (i.e., the site boundary may not have the highest X/Q value), long-term X/Q values were I

calculated at-the midpoint'of 10 standard distances as given in Appendix A.

The calculated values decreased with the distance for all but the WNW, NW, and NNW sectors.

The values for these sectors were not found to be limiting such that the maximum site boundary X/Q for both long-term and short-term ground level and mixed mode releases occurred at the SSE site boundary.

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

Values for Mi and N which are utilized in the calculation of the gamma air i

I and beta air doses in Equation 3.3-1 to show compliance with 10CFR50 were presented 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 multipl.ied by 1.0 E6 to convert from picoeuries to microcuries.

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

i For the calendar quarter:

j-D, s 5 mrad (3.3-3)

De s 10 mrad (3.3-4) i 1

'HBRODCM.

3-26 Rev. 9 1

i

' United States Nuclear Regulatory Commiss on O Serial: RNP-RA/95-0159 Page 62 of 172 _

For the calendar year:

D, s 10 'erad

-(3.3-5)

Da s 20 mrad (3.3-6)

'The quarterly limits given above represent one-half of the annual design objectives of Section II.B.1 of Appendix I of 10CMt50.

If any of the-limits of Equations _3.3-3 through 3.3-6 are exceeded, a special. report pursuant to Technical Specification must be filed with the NRC.

This report complies with Section IV.A of. Appendix I of 10CFR50.

< 3. 3. l'. 2 Projection of Doses Domes resulting from the release of gaseous effluents will be projected once per 31 days.

These projections will include' a safety margin based upon expected operational conditions which will take into consideration both planned and unplanned releases.

]

4 Projected dose will be calculated as follows:

pp 31 (DA + DB)

+M (3. 3 -7 )

( TE)

.5

'~

where:

Projected doses in mrem.

PD Dose accumulated during current quarter in mrem.

DA Projected dose from this release.

DB 1

Time elapsed in quarter in days.

j TE Safety margin in mrem.

M-HBRODCM 3-27 Rev. 9 1

4 i

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 63 of 172 If the projected doses exceed 0.6 mrad for gamma radiation or 1.3 mrad for beta radiation when averaged over a calendar quarter, the ventilation exhaust treatment system will be operated to reduce releases of radioactive materials.

3.3.2 Radioiodine. Particulates and Tritium 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 annual dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ.

Based upon NUREG 0133, the dose to an organ of an individual from radioiodines, tritium, and particulates with half-lives 2 8 days in gaseous effluents released to unrestricted areas can be determined by the following equation:

Rj, ( (XIQ), Og, + (XfD), Og, + (Xf~q), qg,} +

D, = 3.17 x 10'* Z j

( Rj, + Rj, + Rj, + Rj,) [ (IT[Q), Oj, + (ITq), gg, + (IT[D), Oj,] +

(Rr, + Rr, + Rr, Rr,) I(I[D) Orv + (II7) Grv + (IIU) e Oral (3 3-8)

~

where:

Dose to any organ r from I-131, I-133, particulates with a 8 D,

day half lives, and Tritium in mrem.

A HBRODCM 3-28 Rev. 9 I

i United States Nuclear Regulatory Commission

' to Serial: RNP-RA/95-0159 Page 64 of 172 The inverse of the number of seconds in a year. (sec/ year)'I 3.1 x 04 Annual average relative concentration for plant vent releases (X/Q),

3

(> 500 hrs /yr) sec/m.

From Table A-1 for ground level releases for conservatism.

From Table A-10 for mixed mode releases.

Annual average dilution for radwaste building vent, fuel (X/Q),

handling basement exhaust, and the environmental and radiation control building hood exhaust releases

(>

500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months /yr) 3 sec/m.

From Table A-1 for ground level releases.

Annual average relative concentration for plant vent releases (X/q),

3

($ 500 hrs /yr) sec/m.

i From Table A-7 for ground release.

From Table A 16 for mixed mode releases, j

Annual aveyge deposition factor for plant vent releases (>500 (N

hrs /yr) m From Table A-3 for ground level releases for conservatism.

From Table A-12 for mixed mode releases.

Relative deposition factor for short-term plant vent releases (D/q),

j

($ 500 hrs /yr), m 2, From Table A-3 for ground level continuous releases for conservatism.

From Table A-9 for ground level releases.

Fram Table A-18 for mixed mode releases.

=

Annual average relative deposition factor for radwaste (UTQ).

building vent, fuel handling basement exhaust, and the environmental and radiation control building hood exhaust releases (> 500 hrs / yr), m-2, From Table A-3 for ground level releases.

HBRODCM 3-29 Rev. 9

United States Nuclear Regulatory Commission

, to Serial: RNP-RA!95-0159 Page 65 of 172 Release of radionuclide "i" in gaseous effluents for long-term Q4.

radwaste building vent, fuel handling basement exhaust, and the environmental and radiation control building hood exhaust releases (> 500 hrs /yr), pCi.

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

qi, Release of radionuclide "i" in gaseous effluents for short-term plant vent releases ($ 500 hrs /yr), pCi.

j ig Dose factor for an organ for radionuclide "i" for the ground R

plane exposure pathway, mrem /yr per Ci/see per m-2.,

Dose factor for an organ for radionuclide "i" for the R

ig 3

inhalation pathway, mrem /yr per pCi/m.

Dose factor for an organ for radiomc ude "U

for the R

iy vegetable pathway, mram/yr per pCi/m-2, Dose factor for an organ for tritium for the veSetable R

Ty 3

pathway, mrem /yr per pCi/m.

1 Dose factor for an organ for tritium for the inhalation RTI 3

pathway, mrem /yr per pCi/m.

Release of critium in gaseous effluents for long-term plant Q2v vent releases (> 500 hrs /yr), pCi.

Dose factor for an organ for radionuclide "i" for the milk Rig 2

exposure pathway, mrem /yr per pCi/see per m,

Dose factor for an organ for trMum for the mm pathay, R

Tg 3

mrem /yr per Ci/m.

Dose factor for an organ for tritium for the meat pathway, RTB 3

mrem /yr per pCi/m Dose factor for an organ for radionucli "i" for the meat rib exposure pathway, mrem /yr per pCi/sec/m Release of tritium in gaseous effluents for long-term radwaste Qr.

building vent, fuel handling basement exhaust, and the environmental and radiation control building hood exhaust

(>500 hrs / yr), pCi.

Release of tritium in gaseous effluents for short-term plant grv vent releases ($ 500 hrs /yr), pCi.

RBRODCM 3-30 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159

-Page 66 of 172 To show compliance with 10CFR50, Equation 3.3-8 is evaluated at the i

. limiting pathway location. At HBR this location is the vegetable garden 0.3 miles in the SSE sector.

The critical receptor is a child.

l i

Substitution of the appropriate X/Q and D/Q values from tables in AppenSx i

A into Equation 3.3-8 would yield an equation with the short-term X/Q and D/Q values being less than the long-term values.

Therefore, for ttis

document, only long-term annual X/Q and D/Q values.

(i.e.,

more I

conservative values) are used.

1

)

i The determination of a limiting location for implementation of 10CFR50 for i

f radioiodines and particulates is a function of:

b-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 t

radioiodines and particulates was based upon the source terms calculated using tha GALE Code. This six 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 containment purges.

In the determination of the limiting I

[

location, all of the exposure pathways, as presented in Table 3.2-2, were 8

evaluated.

These include cow milk, goat milk, beef and vegetable l

ingestion, anc inhalation and ground plane exposure.

An infant was j'

assumed to be present at all milk pathway locations. A child wasassumed a

to be present at all vegetable garden and beef animal locations.

The ground plane exposure pathway was not considered a viable pathway for an infant.

Naturally, the inhalation pathway was present everywhere an individual was present.

HBR Technical Specification 4.20.2.1 requires j

that a land-use census survey be conductad on an annual basis.

The age groupings at the various recaptor locations are also determined during this survey; a new limiting location and receptor age group can result.

w.

HBRODCM 3-31 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 67 of 172 For the determination of the limiting location, the highest D/Q values for the vegetable garden, cow milk, and goat milk pathways were selected. The thyroid dose was calculated at each of thesa 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.

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

4 Short-term and long-term X/Q and D/Q values for ground level releases and for long-term mixed mode releases are provided in tables in Appendix A.

They may be utilized if an additional special location arises different from those presented in the spacial locations of Table 3.2-2.

Tables 3.3-1 through 3.3-19 present R values for the total body, GI-tract, i

bone, liver, kidney, thyroid, skin, and lung organs for the ground plane, inhalation, cow milk, goat milk, vegetable, and meat ingestion pathways for th6 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 i

methodology is presented in Appendix B.

l The following relationship should hold for HBR to show compliance with HBR

. Technical Specification 3.9.5.1.

i 1

HBRODCM 3-32 Rev. 9

I niend States Nuclear Regulatory Commission :

U

~

Enclosme 2 to Serial: RNP-RA/95-0159 Page 68 : of 172 For'the calendar quarter:

D,' s 7.5 mrom (3.3-9)-

s.

For the calendar-year:

D, s 15 mram (3.3-10)

The ' quarterly _ limit given above represent-'. one-h'alf the annual design objectives 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 soecial renort pursuant to Techr.ical~ Specification must be filed with the NRC. - This report complies

-with Section IV.A of Appendix I'of 10CFR50.

~

Projection of Doses 3.3.2.2 e

Doses resulting from release of radiciodines 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, i

?

Projected dose will be calculated as follows:

31 (DA + D8)

(3,3 12) pp.

( TE) l.

I where:

PD Projected doses in mrem, i

Dose accumulated during current quarter in area.

DA Projected dose from this release.

DB I

Time elapsed in quarter in days.

.TE l;

Safety margin in arem.

M 5

.a

'HBRODCM 3-33 Rev. 9 L.

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 69 of 172 If the projected doses exceed 1.0 mrea to any organ when averaged over a calendar. quarter, the tantilation exhaust treatment system will be operated to reduce releases of radioactive materials.

t l

i I

1 i

i i

7 i

l i

i 1

1 HBRODCM' 3-34 Rev. 9

.... ~ - -

2. Uniend States Nuclear Regulatory Commission

! Raciasme 2 to' Serial: RNP-RA/95-0159 '

[ Page. 70 E of 172 ~

)

TABLE 3.3-1 1

.R VALUES for the H.B. ROBINSON STEAM ELECTRIC PIANT l

(Reference Regulatory Guide 1.109)-

PATHWAY'- Ground 4

Ihaclide Akas Lizar T. Body Thyroid Kidney Lung GI-Tract Ehin F 18 3.96E+05 3.96E+05 3.96E+0S 3.96E+051 3.96E+05 3.96E+05 3.96E+05 4.66E+05 NA-24' 1.19E+07 :1.19E+07 1.19E+07 1.19E+07 1.19E+07 1.19E+07-1.19E+07 1.39E+07 CR-51

4.66E+06l 4.66E+06 4.66E+06 4.66E+06 4.66E+06 4.66E+06 4.66E+06 5.51E+06 MN-541 1.39E+09 '1.39E+09 1.39E+09 :1.39E+09 1.39E+09 1.39E+09 1.39E+09 1.62E+09 MN-56:

9.03E+05 ' 9,03E+05 9.03E+05 9.03E+05 9.03E+05 9.03E+05 9.03E+05 1.07E+06 FE-59

-2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 3.21E+08 l

'CO 57-1.88E+08 1.88E+08 1.88E+08 1.88E+08 1.88E+08 1.88E+08 1.88E+08 2.07E+08 l~

CO-58 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 -4.44E+08 CO 60 2.15E+10. 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.53E+10 f.

NI-45' 2.97E+05 2.97E+05 2.97E+05. 2.97E+05 2.97E+05 2.97E+05 2.97E+05 3.45E+05 CU-64 6.07E+05 6.07E+05 6.07E+05 6.07E+05 6.07E+05 6.07E+05 6.072+05 6.88E+05 ZN-65 7.47E+08 7.47E+08 7.47E+08 7.47E+08 7.47E+08 7.47E+08 7.47E+08 8.59E+08 BR-82 2.14E+07 2.14E+07 2.14E+07-2.14E+07 2.14E+07 2.14E+07 2.14E+07 2.47E+07

.BR-83 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 7.08E+03 BR-84 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.36E+05 I

RB-86 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99E+06 1.03E+07

~RB-88 3.31E+04 3.31E+04 3.31E+04 3.31E+04 3.31E+04 3.31E+04 3.31E+04 3.78E+04 RB-89 1.23E+05 1.23E+05 1.23E+05 1.23E+05 1.23E+05 1.23E+05 1.23E+05 1.48E+05 SR-89 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.51E+04 l-SR-91 2.15E+06 2.15E+06 2.15E+06 2.15E+06 2.15E+06 2.15E+06 2.15E+06 2.51E+06 SR-92 7.77E+05 7.77E+05 7.77E+05 7.77E+05 7.77E+05 7.77E+05 7.77E+05 8.63E+05

.Y-91M 1.00E+05 1.00E+05 1.00E+05 1.00E+05 1.00E+05 1.00E+05 1.00E+05 1.16E+05 i

Y-91 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.21E+06 l

Y-92 1.80E+05 1.80E+05 1.80E+05 1.80E+05 1.80E+05 1.80E+05 1.80E+05 2.14E+05 Y 93 1.83E+05 1.83E+05 1.83E+05 1.83E+05 1.83E+05 1.83F+05 1.83E+05 2.51E+05 4

ZR-95 2.45E+08 2.45E+08 2.45E+08 2.45E+08 2.45E+08 2.45E+08 2.45E+08 2.84E+08 l

2R 2.96E+06 2.96E+06 2.96E+06 2.96E+06 2.96E+06 2.96E+06 2.96E+06 3.44E+06 NS-951 1.37E+08 1.37Z+08 1.37E+08 1.37E+08 1.37E+08 1.37E+08 1.37E+08 1.61E+08 NB-97 1.76E+05 1.76E+05 1.76E+05 1.76E+05 1.76E+05 1.76E+05 1.76E+05 2.07E+05 MO 99 3.99E+0C 3.99E+06 3.99E+06 3.99E+06 3.99E+06 3.99E+06 3.99E+06 4.63E+06 i

l TCS99M 1.84E+05 1.84E+05 1.84E+05 '1.84E+05 1.84E+05 1.84E+05 1.84E+05 2.11E+05 i

TC-101 :2.04E+04 2.04E+04 2.04E+04 2.04E+04

'2.04E+04 2.04E+04 2.04E+04 2.26E+04 3

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

H8RODCN 3 Rev. 9

.,,m

' United States Nuclear Regulatory Comminion l Enclosure 2 to Serial: RNP-RA/95-0159 -

Page 71' of 172 TABLE 3.3-1 (continued).

l l

Nuclide Egna Lizag T. Body Thyroid Kidney Lung GI-Tract Ekin RU-103 1.08E+08 1.08E+08 1.08E+08 1.08E+08 1.08E+08. 1.08E+08.

1.08E+08' 1.26E+08 RU 105 6.36E+05. 6.36E+05 6.36E+05 -6.36E+05 6.36E+05 6.36E+05 6.36E+05 7.21E+05 l

'RU-106 4.22E+08 4.22E+08 4.22E+08 4.22E+08 4.22E+08 4.22E+08 4.22E+08 5.07E+08

~

AG-110M -3.44E+09 3.44E+09 3.44E+09 3.44E+09 3.44E+09 3.44E+09 3.44E+09 4.01E+09 SN-113

-1.42E+07 1.42E+07 1.42E+07 1.42E+07 1.42E+07 1.42E+07 1.42E+07 4.08E+07

]

SB-124

.5.98E+08 5.98E+08 5.98E+08 5.98E+08 S.98E+08 5.98E+08 5.98E+08 6.90E+08 SB-125 2.34E+09 2.34E+09 2.34E+09 2.34E+09 2.34E+09 '2.34E+09 2.34E+09 2.64E+09 TE-129M. 1.98E+07-1.98E+07 'l.98E+07 'l.98E+07 1.98E+07 1.98E+07 1.98E+07 2.31E+07 l

TE-129 2.62E+04 2.62E+04 2.62E+04 2.62E+04 2.62E+04 ~ 2.62E+04 2.62E+04 3.10E+04

-TE-131M 8.03E+06 8'03E+06 8.03E+06 8.03E+06 8.03E+06 8.03E+06 8.03E+06 9.46E+06 l'

tea 132'.

4.23E+06 4.23E+06 4.23E+06 4.23E+06 4.23E+06 4.23E+06 4.23E+06 4.98E+06

~ 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 2.09E+07 I-131 1.72E+07 i

I-132

'1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.46E+06 I-133 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.98E+06

.I-134 4.47E+05 4.47E+05 4.47E+05 4.47E+05 4.47E+05 4.47E+05 4.47E+05 5.30E+05 I-135 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.95E+06 CS-134 6.86E+09 6.86E+09 6.86E+09 6.86E+09 6.86E+09 6.86E+09 6.86E+09 8.00E+09 l

CS-136 1.51E+08 1.51E+08 1.51E+08 1.51E+08 1.51E+08 1.51E+08 1.51E+08 1.71E+08 CS 137 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.20E+10 i

CS-138 3.59E+05 3.59E+05 3.59E+05 3.59E+05 3.59E+05 3.59E+05 3.59E+05 4.10E+05 l

BA-139 1.06E+05_

l.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.19E+05

-BA 140 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.35E+07 j

--BA-142 4.49E+04 4.49E+04 4.49E+04 4.49E+04 4.49E+04 4.49E+04 4.49E+04 5.11E+04 l

1A-140 1.92E+07 1.92E+07 1.92E+07 1.92E+07 1.92E+07 1.92E+07 1.92E+07 2.18E+07 1A-142 7.60E+05 7.60E+05 7.60E+05 7.60E+05 7.60E+05 7.60E+05 7.60E+05 9.11E+05 CE-141 1.37E+07_

1.37E+07 1.37E+07 1.37E+07 1.37E+07 1 37E+07 1.37E+07 1.54E+07 CE-143 2.31E+06 2.31E+06 2.31E+06 2.31E+06 2.31E+06 2.31E+06 2.31E+06 2.63E+06 CE-144 6.95E+07 6.95E+07 6.95E+07 6.95E+07 6.95E+07 6.95E+07 6.95E+07 8.04E+07 j.

PR-144 1.83E+03 1.83E+03 1.83E+03 1.83E+03 1.83E+03 1.83E+03 1.83E+03 2.11E+03 i

HF 181 1.96E+08 1.96E+08 1.96E+08 1.96E+08 1.96E+08 1.96E+08 1.96E+08 2.80E+08 j

W-187 2.35E+06 2.35E+06 2.35E+06 2.35E+06 2.35E+06 2.35E+06 2.35E+06 2.73E+06 F

NP-239 1.71E+06 1.71E+06 1.71E+06 1.71E+06 1.71E+06 1.71E+06 1.71E+06 1.98E+06 i

j l

j[

HBRODCM:

3-36 Rev. 9 i

r

l l United States Nuclear Regulatory Commission -

' to Serial: RNP-RA/95-0159-Page' 72 of 172 TABLE 3.3-2 1

R VALUES for the H.B. ROBINSON STEAM ELECTRIC PIANT (Reference Regulatory Guide 1.109)

PATHWAY - Vegetation -

ACE GROUP Adulti 1.

Wuclide R$taf L17.tE T. Body Thyroid Kidney Lung CI-Tract ghin H 0.00E+00 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03-2.26E+03 l

l

-F-18 4.22E+00- 0.00E+00 4.68E-01 0.00E+00 0.00E+00 0.00E+00 1.25E-01 0.00E+00 NA-24 2.68E+05' 2.68E+05 2.68E+05 2.68E+05 2.68E+05 2.68E+05 2.68E+05 0.00E+00 CR 51 0.00E+00- 0(00E+00- 4.59E+04 2.74E+04 1.01E+04 6.09E+04 1.15E+07 0.00E+00

~

MN-54 0.00E+00 3-08E+08 5.87E+07' O.00E+00 9.15E+07

.0.00E+00 9.42E+08- 0.00E+00 MN-56'

. 0.00E+00 ~ ~ 1. 54E+01 2.74E+00 0.00E+00 1.96E+01 0.00E+00 4.93E+02 0.00E+00 j

FE 55~.

2.00E+08

-1.38E+08-3.22E+07 0.00E+00- 0.00E+00 7.70E+07 7.91E+07 0.00E+00

'FE 59.

1.24E+08 2.90E+08. 1.11E+08 0.00E+00 0.00E+00 8.llE+07 9.68E+08 0.00E+00 CO-57

.0.00E+00 '1.01E+07 1.88E+07 0.00E+00 0.00E+00 0.00E+00 2.86E+08 0.00E+00 CO 0.00E+00 2.99E+07 6.70E+07 0.00E+00 0.00E+00 0.00E+00 6.06E+08 0.00E+00 Co 60 0.00E+00 1.67E+08' 3.67E+08- 0.00E+00 0.00E+00 0.00E+00 3.13E+09 0.00E+00 1

NI-65 5.97E+01 7.75E+00 3.54E+00 0.00E+00 0.00E+00 0.00E+00

1. 97E+07.. 0.00E+00 CU-64

'O.00E+00 9.19E+03 4.31E+03 0.00E+00 2.32E+04 0.00E+00 7.83E+05 0.00E+00 f

l ZN-65 4.01E+08 1.28E+09 5.77E+08 0.00E+00 8.54E+08 0.00E+00 8.04E+08 0.00E+00 i

BR-82

.0.00E+00 0.00E+00 1.55E+06 0.00E+00 0.00E+00 0.00E+00 1.78E+06 0.00E+00 BR-83 0.00E+00 0.00E+00 3.10E+00 0.00E+00 0.00E+00 0.00E+00 4.47E+00 0.00E+00 BR-84 0.00E+00 0.00E+00 2.21E-11 0.00E+00 0.00E+00 0.00E+00 1.73E-16 0.00E+00 RB-86

'O.00E+00 2.2]E+08 1.03E+08 0.00E+00 0.00E+00 0.00E+00- 4.35E+07 0.00E+00

'RB-88 0.00E+00 2.66E-22 1.41E-22 0.00E+00 0.00E+00 0.00E+00 3.67E-33 0.00E+00 E

RB-89 0.00E+00- 2.90E-26 2.04E 26 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR.9.77E+09 0.00E+00 2.80E+08 0.00E+00 0.00E+00 0.00E+00 1.57E+09 0.00E+00 LSR-90 6.71E+11 0.00E+00 1.65E+11 0.00E+00 0.00E+00 0.00E+00 1.94E+10 0.00E+00 4-SR-91 3.02E+05- 0.00E+00 1.22E+04 0.00E+00 0.00E+00 0.00E+00 1.44E+06 0.00E+00 i

SR-92 4.15E+02 0.00E+00 1.79E+01 0.00E+00 0.00E+00 0.00E+00 8.22E+03 0.00E+00

'Y-91M 4.76E-09 0.00E+00 1.84E-10 0.00E+00 0.00E+00 0.00E+00 1.40E-08 0.00E+00

Y-91

.4.98E+06-0.00E+00 1.33E+05 0.00E+00 0.00E+00 0.00E+00 2.74E+09 0.00E+00 F

Y-92 8.96E-01 0.00E+00 2.62E-02 0.00E+00 0.00E+00 0.00E+00 1.57E204.0.00E+00 Y-93 1~.68E+02 '0.00E+00 4.65E+00 0.00E+00 0.00E+00 0.00E+00 5.34E.06 0.00E+00 ZRo95 1.14E+06 3.66E+05 2.48E+05 0.00E+00 5.75E+05 0.00E+00 1.16E+09 0.00E+00 ZR 97 3.36E+02 6.78E+01: 3'.10E+01 0.00E+00 1.02E+02 0.00E+00 2.10E+07 0.00E+00 i.

- 1.40E+05 7.80E+04~- 4.19E+04 0.00E+00 7.71E+04 0.00E+00 4.73E+08 0.00E+00

-NB-95=

NB-97

-2.02E-06 5.11E 07 l'. 87E-07 -- 0. 00E+00 5.96E-07 0.00E+00 1.89E-03 0.00E+00

'MO 99

'O.00E+00. 6.18E+06 1.18E+06 0.00E+00 1.40E+07 0.00E+00 1.43E+07 -0.00E+00

~

1R Values in unit's of ares /yr per micro-Ci/m for inhalation'and tritium, 8

'and in units.of ma area /yr per micro-Ci/sec for all others.

HSRODCM.

3-37 Rev. 9

~.

~ United States Nuclear Regulatory Comminaion Baclosure 2 to Serial: RNP-RA/95-0159 Page c 73 of 172 TABI.E 3.s-2 (continued)

Nuclide Agna Mv.gr T. Body Thyroid Kidney Lung GI-Tract Shin l

1 1

TC-99M 3.10E+00 8.75E+00 1.11E+02 0.00E+00 1.33E+02 4.29E+00 5.18E+03 0.00E+00 TC-101-6.00E 31 8.64E-31 8.47E-30 0.00E+00 1.56E-29 4.41E-31 0.00E+00 -. 0. 00E+00 j

RU 103 4.72E+06 0.00B+00 2.03E+06 0.00E+00 1.80E+07 0.00E+00 5.51E+08 0.00E+00

~

~RU-105 5.30E+01 0.00E+00 2.09E+01 0.00E+00- 6.85E+02 0.00E+00 3.24E+04 0.00E+00 I

RU-106

<1.95E+08 0.00E+00 2.47E+07 -0.00E+00 3.76E+08 0.00E+00 1.26E+10 0.00E+00 AG-110M l'.13E+07 1.05E+07 -6.22E+06 0.00E+00 2.06E+07 0.00E+00 4.27E+09 0.00E+00 SN-113 1.43E+07 5.50E+05 1.35E+07 1.94E+05 4.04E+05 0.00E+00 2.49E+08 0.00E+00 SB-124-1.01E+08 1.91E+06-4.01E+07 2.45E+05 0.00E+00 7.88E+07 2.87E+09 0.00E+00 SB-125-

1. 34E+08 ' 1. 50E+06 3.20E+07 1.37E+05 0.00E+00 1.04E+08=

1.48E+09 0.00Er00 i

TE-129M '2.94E+08 1.10E+08 4.65E+07 1.01E+08 1.23E+09 0.00E+00 1.48E+09 0.00E+00 TE-129 7.52E-04' 2.83E 04' 1.83E-04' 5.77E 04 3.16E-03 0.00E+00 5.68E-04 0.00E+00 l

.TE-131M E9.63E+05 4.71E+05 3.93E+05 7.46E+05 4.77E+06. 0.00E+00 4.68E+07 0.00E+00 h

TE-132 4.58E+06 2.96E+06 2.78E+06 3.27E+06 2.85E+07 0.00E+00 1.40E+08 0.00E+00 b

I-131-8.07E+07 1.15E+08 6.61E+07 3.78E+10 1.98E+08 0.00E+00 3.04E+07 0.00E+00 l

I-132 5.57E+01 1.49E+02 5.21E+01 5.21E+03 2.37E+02 0.00E+00 2.80E+01 0.00E+00 4 -

j:

I-133 2.0SE+06 3.61E+06 1.10E+06 5.31E+08 6.31E+06 0.00E+00 3.25E+06 0.00E+00 I-134 8.84E-05 2.40E-04 8.59E-05 4.16E-03 3.82E-04 0.00E+00 2.09E-07 0.00E+00 l

I-135 3.85E+04 1.01E+05 3.72E+04 6.65E+06 1.62E+05 0.00E+00 1.14E+05 0.00E+00 F

CS-134 4.55E+09 1.08E+10 8.84E+09 0.00E+00 3.50E+09 1.16E+09 1.89E+08 0.00E+00

{

CS-136 4.26E+07 1.68E+08 1.21E+08 0.00E+00 9.36E+07 1.2CE+07 1.91E+07 0.00E+00 CS-137 6.64E+09 9.08E+09 5.95E+09 0.00E+00 3.08E+09 1.03E+09 1.76E+08 0.00E+00

[

CS-138 3.39E-11 6.70E-11 3.32E-11 0.00E+00 4.92E-11 4.86E-12 2.86E-16 0.00E+00 BA-139 2.70E-02 1.93E-05 7.91E-04 0.00E+00 1.80E-05 1.09E-05 4.79E-02 0.00E+00

[

i BA-140 1.28E+08 1.61E+05 8.40E+06 0.00E+00 5.47E+04 9.22E+04 2.64E+08 0.00E&OO LA-140 1.97E+03 9.95E+02 2.63E+02 0.00E+00 0.00E+00 0.00E+00 7.30E+07 0.00E+00 I

LA-142 1.92E-04 8.75E-05 2.18E-05 0.00E+00 0.00E+00 0.00E+00 6.39E-01 0.00E+00 4

l' CE-141 1.94E+05 1.31E+05 1.49E+04 0.00E+00 6.10E+04 0.00E+00 5.02E+08 0.00E+00 CE-143 9.96E+02 7.36E+05 8.15E+01 0.00E+00 3.24E+02 0.00E+00 2.75E+07 0.00E+00 CE-144 3.15E+07 1.32E+07 1.69E+06 0.00E+00 7.81E+06 0.00E+00 1.07E+10 0.00E+00 i

PR-144 2.36E-26 9.81E 27 1.20E 27 0.00E+00 5.53E-27 0.00E+00 3.40E-33 0.00E+00 b

HF-181 9.50E+06 5.36E+04 1.08E+06 3.40E+04 4.47E+04 0.00E+00 7.05E+08 0.00E+00 W 187 3.79E+04 3.17E+04 1.11E+04 0.00E+00 0.00E+00 0.00E+00 1.04E+07 0.00E+00 NP-239 1.43E+03 1.40E+02 7.73E+01 0.00E+00 4.37E+02' O.00E+00 2.88E+07 0.00E+00 i

a f

HBRODCM-3-38 Rev. 9

4 i Uniend States Nuclear Regulatory canwninian -

; Enclosure 2 to Serial: RNP-RA/95-0159 F Page l74 of 172 TABLE 3.3 i R VALUES for the H.B. ' ROBINSON STEAM ELECTRIC PIANT 1

'(Reference Regulatory Guide 1.109) l 3

I j

PATHWAY.- Vegetation-1 ACE GROUP - Teenu l

Nuclide Bent

]dysg T. Body

'thn.e.id Kidney launa GI-Tract

_hin j

H-3o 0.00E+00 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03' 2.59E+03 i

F-18 3.83E+00 0.00E+00 4.20E-01 'O.00E+00 0.00E+00 0.00E+00 3.45E-01 0.00E+00 l

NA 24 2.38E+05 2.38E+05 :2.38E+05' 2.38E+05 2.38E+05 2.38E+05 2.38E+05 0.00E+00 f

'CR-51 0.00E+00 0.00E+00 6.09E+041 3.38E+04-1.34E+04 8.70E+04: 1.02E+07 0.00E+00 MN-54 10.00E+00 '4.47E+08 8.86E+07 0.00E+00 1.33E+08 0.00E+00 9.16E+08 0.00E+00 l

MN-56 0.00E+00 1.39E+01 2.48E+00 0.00E+00 1.76E+01 0.00E+00 9.17E+02 0.00E+00 j

FE 55: ' 3.10E+08 2.20E+08 _5.13E+07 'O.00E+00. 0.00E+00: 1.40E+08 9.53E+07 0.00E+00 i

.FE-59; 1.76E+08 4.10E+08 1.58E+08 0.00E+00 0.00E+00 1.29E+08 9.70E+08 0.00E+00 i

CO - 57 '-

0.00E+00 1.72E+07 2.89E+07 0.00E+00 0.00E+00 'O.00E+00 3.21E+08 0.00E+00

'co-58 0.00E+00 4.24E+07 9.78E+07 0.00E+00- 0.00E+00- 0.00E+00 5.85E+08 0.00E+00 CO-60 0.00E+00- 2.48E+08 5.58E+08 0.00E+00 0.00E+00 0.00E+00 3'.23E+09 0.00E+00 I

NI-65'.

'5.56E+01 7.10E+00 3.23E+00 0.00E+00 0.00E+00 0.00E+00 3.85E+02 0.00E+00 CU-64 0.00E+00 8.33E+03 3.92E+03 0.00E+00 2.11E+04 0.00E+00 6.46E+05 0.00E+00 ZN-65 5.36E+08 1.86E+09 8.68E+08 0.00E+00 1.19E+09 0.00E+00 7.88E+08 0.00E+00 BR 'O.00E+00 0.00E+00 1.37E+06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-83

.0.00E+00 0.00E+00 2.91E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j

p BR-84 0.00E+00 0.00E+00 2.01E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 2.75E+08 1.29E+08 0.00E+00- 0.00E+00 0.00E+00 4.07E+07 0.00E+00 RB-88 0.00E+00 2.46E-22 1.31E-22 0.00E+00 0.00E+00 0.00E+00 2.11E 0.00E+00 RB-89 0.00E+00 2.61E-26 1.84E-26 0.00E+00 0.00E+00 0.00E+00 4.00E-35 0.00E+00 SR-89 1.48E+10 0.00E+00 4.25E+08 0.00E+00 0.00E+00 0.00E+00 1.77E+09 0.00E+00 3

j-

.SR-90 8.33E+11 0.00E+00 2.06E+11 0.00E+00 0.00E+00 0.00Ei.0 2.34E+10 0.00E+00 SR-91 2.83E+05 0.00E+00 1.12E+04 0.00E+00 0.00E+00 0.00E+00 1.28E+06 0.00E+00 l

SR-92 3.86E+02 0.00E+00 1.65E+01 0.00E+00 0.00E+00 0.00E+00 9.84E+03 0.00E+00 I

Y-91M 4.43E 0.00E+00 1.69E-10 0.00E+00 0.00E+00 0.00E+00 2.09E-07 0.00E+00 I-Y-91 7.64E+06 0.00E+00- 2.05E+05 0.00E+00 0.00E+00 0.00E+00 3.13E+09 0.00E+00 Y-92

.8.42E-01 0.00E+00 2.43E 02 0.00E+00 0.00E+00 0.00E+00 2.31E+04 0.00E+00 Y-93 1.58E+02. 0.00E+00 4.33E+00 0.00E+00 0.00E+00 0.00E+00 4.82E+06 0.00E+00 ZR-95 1.67E+06-5.28E+05 3.63E+05 0.00E+00 7.76E+05 0.00E+00 1.22E+09 0.00E+00 i

ZR 3.11E+02 6.15E+01 2.83E+01 0.00E+00 9.33E+01 0.00E+00 1.67E+07 0.00E+00 L

NS-95 1.89E+05' 1.05E+05' 5.78E+04 0.00E+00 1.02E+05 0.00E+00 4.49E+08 0.00E+00

[

NBo97

'1.87E-06 4.65E-07 1.70E 07 0.00E+00 5.44E-07 0.00E+00 1.11E-02 0.00E+00 MO-99

.0.00E+00- 5.67E+06 1.08E+06 0.00E+00 1.30E+07 0.00E+00 1.02E+07 0.00E+00 l

3 1R Values in units of aren/yr per micro-Ci/m for inhalation and tritium, a

Land in units of.m ares /yr per micro-Ci/sec for all others.

'HBRODCM 3-39 Rev. 9 1-

~__ ;_._.

,_i.-,.,-..,e

-m

~

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 75 of 172 TABLE 3.3-3 (continued)

Ifuglide Bone Liy.g.g T. Body Thyroid Kidney Lgng GI-Tract Skin TC-99M 2.73E+00 7.62E+00 9.87E+01 0.00E+00 1.13E+02 4.23E+00 5.00E+03 0.00E+00 TC-101 5.58E-31 7.93E-31 7.79E 30 0.00E+00 1.43E-29 4.83E-31 1.36E-37 0.00E+00 KUo103 6.75E+06 0.00E+00 2.88E+06 0.00E+00 2.38E+07 0.00E+00 5.64E+08 0.00E+00 RU-105 4.93E+01 0.00E+00 1.91E+01 0.00E+00 6.22E+02 0.00E+00 3.98E+04 0.00E+00 RU-106 3.13E+08 0.00E+00 3.94E+07 0.00E+00 6.03E+08 0.00E+00 1.50E+10 0.00E+00

^

AC-110M 1.63E+07 1.54E+07 9.37E+06 0.00E+00 2.94E+07 0.00E+00 4.33E+09 0.00E+00 SN-113 1.88E+07 7.89E+05 2.00E+07 2.60E+05 5.58E+05 0.00E+00 2.26E+08 0.00E+00 SB-124 1.51E+08 2.78E+06 5.88E+07 3.42E+05 0.00E+00 1.32E+08 3.04E+09 0.00E+00 SB-125 2.11E+08 2.30E+06 4.92E+07 2.01E+05 0.00E+00 1.85E+08 1.64E+09 0.00E+00 TE-129M. 4.23E+08 1.57E+08 6.69E+07 1.36E+08 1.77E+09 0.00E+00 1.59E+09 0.00E+00 TE-129 7.04E-04 2.63E-04 1.71E-04 5.03E 04 2.96E-03 0.00E+00 3.85E-03 0.00E+00 TE-131M 8.92E+05 4.28E+05 3.57E+05 6.43E+05 4.46E+06 0.00E+00 3.43E+07 0.00E+00 TE-132 4.16E+06 2.64E+06 2.48E+06 2.78E+06 2.53E+07 0.00E+00 8.35E+07 0.00E+00 I-131 7.67E+07 1.07E+08 5.77E+07 3.14E+10 1.85E+08 0.00E+00 2.13E+07 0.00E+00 I-132 5.02E+01 1.31E+02 4.72E+01 4.43E+03 2.07E+02 0.00E+00 5.73E+01 0.00E+00 4

I-133 1.93E+06 3.27E+06 9.99E+05 4.57E+08 5.74E+06 0.00E+00 2.48E+06 0.00E+00 I-134 7.99E-05 2.12E-04 7.61E-05 3.53E-03 3.34E-04 0.00E+00 2.79E-06 0.00E+00 I-135 3.48E+04 8.96E+04 3.32E+04 5.77E+06 1.42E+05 0.00E+00 9.93E+04 0.00E+00 CS-134 6.92E+09 1.63E+10 7.55E+09 0.00E+00 5.17E+09 1.97E+09 2.02E+08 0.00E+00 CS-136 4.36E+07 1.72E+08 1.15E+08 0.00E+00 9.35E+07 1.47E+07 1.38E+07 0.00E+00 CS-137 1.06E+10 1.41E+10 4.90E+09 0.00E+00 4.79E+09 1.86E+09 2.00E+08 0.00E+00 CS-138 3.13E-11 6.01E-11 3.01E-11 0.00E+00 4.44E-11 5.16E-12 2.73E-14 0.00E+00 BA-139 2.54E-02 1.79E-05 7.41E-04 0.00E+00 1.69E-05 1.23E-05 2.27E-01 0.00E+00 BA-140 1.38E+08 1.69E+05 8.87E+06 0.00E+00 5.72E+04 1.13E+05 2.12E+08 0.00E+00 LA-140 1.80E+03 8.86E+02 2.36E+02 0.00E+00 0.00E+00 0.00E+00 5.09E+07 0.00E+00 1A-142 1.77E-04 7.85E-05 1.95E-05 0.00E+00 0.00E+00 0.00E+00 2.39E+00 0.00E+00 CE-141 2.79E+05 1.86E+05 2.14E+04 0.00E+00 8.76E+04 0.00E+00 5.32E+08 0.00E+00 CE-143 9.31E+02 6.77E+05 7.56E+01 0.00E+00 3.04E+02 0.00E+00 2.04E+07 0.00E+00 CE-144 5.05E+07 2.09E+07 2.71E+06 0.00E+00 1.25E+07 0.00E+00 1.27E+10 0.00E+00 PR-144 2.22E-26 9.07E-27 1.12E 27 0.00E+00 5.20E-27 0.00E+00 2.44E-29 0.00E+00 HF-181 1.38E+07 7.56E'04 1.54E+06 4.62E+04 6.30E+04 0.00E+00 6.89E+08 0.00E+00 W-187 3.53E+04

2. 87 E ')4 1.01E+04 0.00E+00 0.00E+00 0.00E+00 7.78E+06 0.00E+00 NP-239 1.38E+03 1.31E+02 7.25E+01 0.00E+00 4.10E+02 0.00E+00 2.10E+07 0.00E+00 l

HBRODCM 3-40 Rev. 9

t Unhed States Nuclear Regulatory Commission -

Enciname 2 to Serial: RNP-RA/95-0159 gigtg 3,3,4T 1 Page 76' of 172 R VA uEs'for the H.B.' ROBINSON STEAM EM CTRIC PIANT 1

(Reference Regulatory Guide 1.109)

PATHWAY LVegetation-1 i

ACE GROUP = Child-F I

Ihaclide Bent Liy.3I T, Body Thyroid Kidney

]dag GI-Tract J. kin k

j H-3 0.00E+00 14'.0 m 03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 F-18

,6.84E+00: 0.00E+00 6.78E 01 0.00E+00.- 0.00E+00 0.00E+00 1.85E+00 0.00E+00 4

NA-24 3.72E+05 3.72E+05 3.72E+05' 3.72E+05 3.72E+05 3.72E+05 3.72E+05' O.00E+00

CR-51

0.00E+00 0.00E+00 1.16E+05 6.42E+04 1.75E+04 1.17E+05 6.14E+06 0.00E+00 MN 54 0.00E+00 6.54E+08.1.74E+08 0.00E+00 1.83E+08 0.00E+00 5.49E+08 0.00E+00 MN-56 0.00E+00 1.82E+01 4.11E+00

'O 00E+00 2.20E+01' O.00E+00 2.64E+03 0.00E+00

-FE-55.

7.63E+08 4.05E+08 1.25E+08 0.00E+00~ 0.00E+00 2.29E+08 7.50E+07 0.00E+00 FE-59:

3.89E+08 6.30E+08 3.14E+08' O.00E+00 0.00E+00' 1.83E+08 6.56E+08 0.00E+00 j

CO-57 0._00E+00 2.88E+07 <5.83E+07 0.00E+00 0.00E+00- 0.00E+00 2.36E+08 0.00E+00 CO-58.

0.00E+00 6.27E+07 1.92E+08 0.00E+00- 0.00E+00 0.00E+00 3.65E+08 0.00E+00 CO.60 0.00E+00 3.77E+08 1.11E+09 0.00E+00 0.00E+00 0.00E+00 2.09E+09 0.00E+00 j

_NI-65

.1.02E+02 9.60E+00 5.60E+00 0.00E+00 0.00E+00 0.00E+00 1.18E+03 0.00E+00 F

l LCU-64' O.00E+00 1.10E+04. 6.63E+03 0.00E+00 2.65E+04 0.00E+00 5.15E+05 0.00E+00

.ZN-65' 1.03E+09 2.74E+09 1.70E+09 0.00E+00 1.72E+09 0.00E+00 4.81E+08 0.00E+00 I

BR-82

'O.00E+00 0.00E+00. 2.10E+06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

.BR-83

'O.00E+00 0.00E+00 5.36E+00.0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-84

'O.00E+00 0.00E+00 3.41E-11 0.00E+00 0.00E+00 0.00E+00: 0.00E+00 0.00E+00 RB-86 0.00E+00' 4.55E+08 2.80E+08 0.00E+00 0.00E+00 0.00E+00 2.93E+07 0.00E+00 RB-88 0.00E+00 3.39E-22 2.36E-22 0.00E+00 0.00E+00 0.00E+00 1.66E-23 0.00E+00 RB-89 0.00E+00- 3.43E-26 3.05E-26 0.00E+00 0.00E+00 0.00E+00 2.99E-28 0.00E+00 SR-89 3.52E+10 0.00E+00 1.01E+09 0.00E+00 0.00E+00 0.00E+00 1.36E+09 0.00E+00 SR-90 1.38E+12 0.00E+00 3.50E+11 0.00E+00 0.00E+00 0.00E+00 1.86E+10 0.00E+00 SR-91 5.20E+05 0.00E+00 1.96E+04 0.00E+00 0.00E+00 0.00E+00 1.15E+06 0.00E+00 SR-92 7,08E+02 0.00E+00 2.84E+01 0.00E+00 0.00E+00 0.00E+00 1.34E+04 0.00E+00 i

Y-91M-8.12E 09 0.00E+00 2.95E-10 0.00E+00 0.00E+00 0.00E+00 1.59E-05 0.00E+00

-Y-91 1.82E+07 0.00E+00 4.86E+05 0.00E+00 0.00E+00 0.00E+00 2.42E+09 0.00E+00 I

Y-92 1.55E+00 0.00E+00- 4.44E-02 0.00E+00 0.00E+00 0.00E+00 4.48E+04 0.00E+00

.Y-93 2.91E+02 0.00E+00 7.98E+00 0.00E+00 0.00E+00 0.00E+00 4.34E+06 0.00E+00

'ZR-95 3.75E+06 8.25E+05 7.34E+05 0.00E+00 1.18E+06 0.00E+00 8.60E+08 0.00E+00 I'

ZR-97 5.68E+02 8.20E+01 4.84E+01 0.00E+00 1.18E+02 0.00E+00 1.24E+07 0.00E+00 L

NB 4.04E+05 1.57E+05 1.12E+05 0.00E+00 1.48E+05 0.00E+00 2.91E+08 0.00E+00 I

NB-97 3.41E-06 6.16E-07 2.88E-07 0.00E+00 6.84E-07 0.00E+00 1.90E-01 0.00E+00 SR-91 5.20E+05 0.00E+00 1.96E+04 0.00E+00 0.00E+00 0.00E+00 1.15E+06 0.00E+00 SR-92 7.08E+02 0.00E+00 2.84E+01 0.00E+00 0.00E+00 0.00E+00 1.34E+04 0.00E+00

.Yo91M

8.12E-09 0.00E+00 2.95E-10 0.00E+00- 0.00E+00 0.00E+00 1.59E-05 0.00E+00

?Yo91 1.82E+07 0.00E+00 4.86E+05 0.00E+00 0.00E+00 0.00E+00 2.42E+09 0.00E+00

Yi92-l1.55E+00 0.00E+00 4.44E-02 0.00E+00 0.00E+00 0.00E+00 4.48E+04 0.00E+00 t

1 3

R Values in units of area /yr per micro-Ci/m for inhalation and tritium,

'and in units of ma area /yr per micro-Ci/sec for all others.

p.

HBRODCM' 3-41 Rev. 9 4

4,.o

United States Nuclear Regulatory Camminian to Serial: RNP-RA/95 0159 TABLE 3.3-4 (centinusd)

Page - 77 of 172 '

Buclide Igna Li!.tr T. Body Thyroid Kidney Lung GI-Tract ghin Y-93 2.91E+02 0.00E+00 7.98E+00 0.00E+00 0.00E+00 0.00E+00 4.34E&O6 0.00E+00 ZR-95 3.75E+06 8.25E+05 7.34E+05 0.00E+00 1.18E+06 0.00E+00 8.60E+08 0.00E+00 ZR-97 5.68E+02 8.20E+01 4.84E+01 0.00E+00 1.18E+02 0.00E+00 1.24E+07 0.00E+00 NB-95 4.04E+05 1.57E+05 1.12E+05 0.00E+00 1.48E+05 0.00E+00 2.91E+08 0.00E+00 NB-97 3.41E-06 6.16E-07 2.88E-07 0.00E+00 6.84E-07 0.00E+00 1.90E-01 0.00E+00 MO-99.

0.00E+00 7.75E+06 1.92E+06 0.00E+00 1.65E+07 0.00E+00 6.41E+06 0.00E+00 TC-99M 4.70E+00 9.21E+00 1.53E+02 0.00E+00 1.34E+02 4.68E+00 5.24E+03 0.00E+00 TC-101 1.03E-30 1.07E-30 1.36E-29 0.00E+00 1.83E-29 5.68E-31 3.41E-30 0.00E+00 RU-103 1.52E+07 0.00E+00 5.83E+06 0.00E+00 3.82E+07 0.00E+00 3.92E+08 0.00E+00 RU-105 9.02E+01 0.00E+00 3.27E+01 0.00E+00 7.93E+02 0.00E+00 5.89E+04 0.00E+00 RU-106 7.54E+08 0.00E+00 9.40E+07 0.00E+00 1.02E+09 0.00E+00 1.17E+10 0.00E+00 AG-110M 3.45E+07 2.33E+07 1.86E+07 0.00E+00 4.34E+07 0.00E+00 2.77E+09 0.00E+00 SN-113 3.60E+07 1.16E+06 3.93E+07 4.75E+05 7.96E+05 0.00E+00 1.44E+08 0.00E+00 SB-124 3.43E+08 4.46E+06 1.20E+08 7.58E+05 0.00E+00 1.91E+08 2.15E+09 0.00E+00 SB-125 4.91E+08 3.79E+06 1.03E+08 4.55E+05 0.00E+00 2.74E+08 1.17E+09 0.00E+00 TE-129M 9.83E+08 2.74E+08 1.53E+08 3.17E+08 2.89E+09 0.00E+00 1.20E+09 0.00E+00 TE-129 1.30E-03 3.64E-04 3.09E-04 9.30E-04 3.81E-03 0.00E+00 8.12E 02 0.00E+00 TE-131M 1.63E+06 5.63E+05 5.99E+05 1.16E+06 5.45E+06 0.00E+00 2.28E+07 0.00E+00 TE-132 7.46E+06 3.30E+06 3.99E+06 4.81E+06 3.07E+07 0.00E+00 3.32E+07 0.00E+00 I-131 1.43E+08 1.44E+08 8.16E+07 4.75E+10 2.36E+08 0.00E+00 1.28E+07 0.00E+00 1-132 8.92E+01 1.64E+02 7.53E+01 7.60E+03 2.51E+02 0.00E+00 1.93E+02 0.00E+00

-I-133 3.52E+06 4.35E+06 1.65E+06 8.08E+08 7.25E+06 0.00E+00 1.75E+06 0.00E+00 I-134 1.42E-04 2.64E-04 1.21E-04 6.07E-03 4.03E-04 0.00E+00 1.75E-04 0.00E+00 1-135 6.18E+04 1.11E+05 5.27E+04 9.86E+06 1.71E+05 0.00E+00 8.48E+04 0.00E+00 CS-134 1.56E+10 2.56E+10 5.41E+09 0.00E+00 7.94E+09 2.85E+09 1.38E+08 0.00E+00 CS-136 8.22E+07 2.26E+08 1.46E+08 0.00E+00 1.20E+08 1.79E+07 7.94E+06 0.00E+00 CS-137 2.50E+10 2.39E+10 3.53E+09 0.00E+00 7.79E+09 2.80E+09 1.50E+08 0.00E+00 CS-138 5.69E-11 7.92E 11 5.02E-11 0.00E+00 5.57E-11 5.99E-12 3.65E-11 0.00E+00 BA-139 4.69E 02 2.50E 05 1.36E-03 0.00E+00 2.18E-05 1.47E-05 2.71E+00 0.00E+00 BA-140 2.76E+08 2.42E+05. 1.61E+07 0.00E+00 7.87E+04 1.44E+05 1.40E+08 0.00E+00 LA-140 3.24E+03 1.13E+03 3.82E+02 0.00E+00 0.00E+00 0.00E+00 3.16E+07 0.00E+00 LA-142 3.20E-04 1.02E-04 3.20E-05 0.00E+00 0.00E+00 0.00E+00 2.02E+01 0.00E+00 CE-141.

6.46E+05 3.22E+05 4.79E+04 0.00E+00 1.41E+05 0.00E+00 4.02E+08 0.00E+00 CE 143 1.71E+03 9.29E+05 1.35E+02 0.00E+00 3.90E+02 0.00E+00 1.36E+07 0.00E+00 CE-144 1.22E+08 3.82E+07 6.50E+06 0.00E+00 2.11E+07 0.00E+00 9.95E+09 0.00E+00 PR-144 4.11E-26 1.27E-26 2.07E-27 0.00E+00 6.73E 27 0.00E+00 2.74E-23 0.00E+00 HF-181 3.12E+07 1.22E+05 3.14E+06 1.03E+05 9.80E+04 0.00E+00 5.18E+08 0.00E+00 1

W-187 6.41E+04 3.80E+04 1.70E+04 0.00E+00 0.00E+00 0.002+00 5.34E+06 0.00E+00 NP-239 2.56E+03 1.84E+02 1.29E+02 0.00E+00 5.31E+02 0,00E+00 1.36E+07 0.00E+00 1

L H8RODCM 3-42 Rev. 9

__________._._____________._._'______m.___,r

~

.. m-n.

...n.,

.e,-c

L Unhed States Nuclear Regulatory ( wnminian f Enclosure 2 tc Serial: RNP-RA/95-0159 '

TAsLE 3.3-5 Pagej78-of 172:

a,gtgg, for the s.n. monINsoN STEAM' ELECTRIC FLANT1 (Reference Regulatory Guide 1.109)-

I

' PATHWAY - Meat ACE" GROUP - Adult j

Nuclide jgEt LhtE.

T. Body Thyroid Eidney Lung GI-Tract ghin

)

H-3

'O 00E+00 3.24E+02. 3.24E+02 3.24E+02 3.24E+02 ~3.24E+02 3.24E+02 3.24E+02 j

NA. 24' 1.39E-03 1.39E-03 1.39E-03 1.39E 03 1.39E-03 1.39E-03 1.39E-03 0.00E+00 l'

.CR-51 0.00E+00.0.00E+00 -6.30E+03 3.76E+03 1.39E+03 8.36E+03 1.58E406 0.00E+00 1

.MN-54

0. 00E+00 ' - 7.33E+06 1.40E+06 0.00E+00 2.18E+06 0.00E+00 2.24E+07 0.00E+00 FE-55.

2.28E+08 1.58E+08 3.68E+07 ' O.00E+00 0.00E+00 8.81E+07 9.06E+07 0.00E+00

}

FE-59 2.28E+08 5'.36E+08 2.05E+08 0.00E+00 0.00E+00 1.50E+08 1.79E+09 0.00E+00 CO-57'

'O.00E+00 4.01E+06 7.43E+06 0.00E+00 0.00E+00 0.00E+00 1.13E+08 0.00E+00

~

CO-58,

'~ 0. 00E+00 ' 1.52E+07 3.40E+07 0.00E+00 0.00E+00 0.00E+00 3.07E+08 0.00E+00 CO-60

0.00E+00 5'.96E+07 1.31E+08 0.00E+00 0.00E+00 0.00E+00 1.12E+09 0.00E+00 j

CU 64

.0;00E+00 2.80E-07 =1.31E 07 0.00E+00 7.05E 07 0.00E+00 2.38E-05 :0.00E+00 ZN-65:

3.20E+08. 1.02E+09 '4.60E+08 0.00E+00 6.81E+08 0.00E+00 6.42E+08 0.00E+00

)

.BR-82

-O.00E+00 0.00E+00 1.25E+03 0.00E+00 0.00E+00 0.00E+00 1.43E+03 0.00E+00 0.00E+00 4.53E+08 2.11E+08 0.00E+00 0.00E+00 0.00E+00 8.94E+07 0.00E+00 RB-86 i

'SR-89'

2.57E+08 0.00E+00' 7.37E+06 0.00E+00 0.00E+00 0.00E+00 4.12E+07 0.00E+00 i

.SR-90 1.03E+10 0.00E+00 2.53E+09 0.00E+00 0.00E+00 0.00E+00 2.98E+08 0.00E+00 l-lSR-91 11.58E-10 0.00E+00- 6.39E-12 0.00E+00 0.00E+00 0.00E+00 7.53E-10 0.00E+00 JY 9.53E+05- 0.00E+00 2.55E+04 0.00E+00 0.00E+00 0.00E+00 5.24E+08 0.00E+00

'Y-93 4.87E-12 0.00E+00

.1.35E-13 0.00E+00 0.00E+00 0.00E+00 1.55E-07 0.00E+00 ZR-95 1.57E+06 5.02E+05 3.40E+05 0.00E+00 7.88E+05 0.00E+00 1.59E+09 0.00E+00 l.

.ZR-97 2.11E 05 4.27E 06 1.95E-06 0.00E+00 6.44E-06 0.00E+00 1.32E+00 0.00E+00 NB-95 2.01E+06 1.12E+06 6.02E+05 0.00E+00 1.11E+06 0.00E+00 6.79E+09 0.00E+00 MO-99 0.00E+00' 1.01E+05 1.92E+04 0.00E+00 2.28E+05 0.00E+00 2.33E+05 0.00E+00

[

TC-99M 4.76E-21 1.35E-20 1.71E-19 0.00E+00 2.04E-19 6.59E-21 7.96E-18 0.00E+00

[

RU-103 9.15E+07 0.00E+00 3.94E+07 0.00E+00 3.49E+08 0.00E+00 1.07E+10 0.00E+00 l'

RU-105

.6.30E 28 0.00E+00 2.49E-28 0.00E+00 8.15E-27 0.00E+00 3.86E-25 0.00E+00 RU-106

.2.26E+09 0.00E+00 2.85E+08 0.00E+00 4. 3 6 E+0'.

0.00E+00 1.46E+11 0.00E+00

[

'AG-110M' 5.57E+06 5.15E+06 3.06E+06 0.00E+00 1.01E+07 0.00E+00 2.10E+09 0.00E+00 j:

SN-113 3.94E+07 1.52E+06 3.73E+07-5.36E+05 1.12E+06 0.00E+00 6.89E+08. 0.00E+00 SB-124

'.1.66E+07 3.14E+05 6.60E+06-4.03E+04 0.00E+00 1.30E+07 4.72E+08 0.00E+00 SB-125 1.51E+07 -1.69E+05 3.59E+06 1.53E+04 0.00E+00 1.16E+07 1.66E+08 0.00E+00 TE-129M 'l 07E+09 3.99E+08 1.69E+08 3.67E+08 4.46E+09 0.00D00 5.38E+09 0.00E+00 r

i-I i-r 4.

3

'1R. Values in units of ares /yr'per micro-Ci/m for inhalation and tritium, r

a and-in units of* m ' area /yr per; micro-Ci/sec ~ for all others.

4 LHBRODCM?

3-43 Rev. 9-l L

United States Nuclear Regulatory Conunission' to Serid: RNP-RN95-0159 TABLE 3.3-5 (centinund)

Page 79 of 172 i

Nuclide 3g33 Liver T. Body Thyroid Kidney Lgng CI-Tract Skin TE-131M 4.66E+02 2.28E+02 1.90E+02 3.61E+02 2.31E+03 0.00E+00 2.26E+04 0.00E+00 TE-132 1.46E+06 9.44E+05 8.86E+05 1.04E+06 9.09E+06 0.00E+00 4.46E+07 0.00E+00 I-131 1.06E+07 1.51E+07 8.66E+06 4.95E+09 2.59E+07 0.00E+00 3.99E+06 0.00E+00 1-133 3.72E 01 6.47E-01 1.97E-01 9.51E+01 1.13E+00 0.00E+00 5.82E-01 0.00E+00 1 135 4.69E-17 1.23E-16 4.53E-17 8.10E-15 1.97E-16 0.00E+00 1.39E-16 0.00E+00 CS-134 5.18E+08 1.23E+09.

1.01E+09 0.00E+00 3.99E+08 1.32E+08 2.16E+07 0.00E+00 CS-136 1.15E+07 4.54E+07 3.27E+07 0.00E+00 2.53E+07 3.46E+06 5.16E+06 0.00E+00 CS-137 7.04E+08 9.63E+08 6.31E+08 0.00E+00 3.27E+08 1.09E+08 1.86E+07 0.00E+00 BA-140 2.75E+07 3.45E+04 1.80E+06 0.00E+00 1.17E+04 1.98E+04 5.66E+07 0.00E+00 LA 140

.3.74E-02 1.89E-02 4.99E-03 0.00E+00 0.00E+00 0.00E+00 1.38E+03 0.00E+00 CE-141 1.24E+04 8.373+03 9.49E+02 0.00E+00 3.89E+03 0.00E+00 3.20E+07 0.00E+00 CE-143 2.03E-02 1.50E+01 1.66E-03 0.00E+00 6.61E-03 0.00E+00 5.61E+02 0.00E+00 CE-144 1.15E+06 4.82E+05 6.19E+04 0.00E+00 2.86E+05 0.00E+00 3.90E+08 0.00E+00 HF-181 1.79E+08 1.01E+06 2.03E+07 6.41E+05 8.41E+05 0.00E+00 1.33E+10 0.00E+00 W-187 2.08E-02 1.74E-02 6.09E-03 0.00E+00 0.00E+00 0.00E+00 5.71E+00 0.00E+00 NP-239 2.61E 01 2.56E-02 1.41E-02 0.00E+00 8.00E-02 0.00E+00 5.26E+03 0.00E+00 i

HBRODCM 3-44 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 TABLE 3.3-6 1

Page 80 of 172 R VALUES for the H.B. ROBINSON STEAM ELECTRIC PIANT (Reference Regulatory Guide 1.109)

PATHWAY - Meat-AGE GROUP - Teen Nuclide Aqua Li7er T. Body Thyroid Kidney LHDg GT-Tract Skin H-3 0.00E+00 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 NA-24 1.11E-03 1.11E-03 1.11E-03 1.11E-03 1.11E-03 1.11E-03 1.11E 03 0.00E+00 CR-51 0.00E+00 0.00E+00 5.04E+03 2.80E+03 1.10E+03 7.19E+03 8.46E+05 0.00E+00 MNoS4 0.00E+00 5.59E+06 1.11E+06 0.00E+00 1.67E+06 0.00E+00 1.15E+07 0.00E+00 FE-55 1.86E+08 1.32E+08 3.07E+07 0.00E+00 0.00E+00 8.35E+07 5.69E+07 0.00E+00 FE-59 1.82E+08 4.2SE+08 1.64E+08 0.00E+00 0.00E+00 1.34E+08 1.01E+09 0.00E+00 CO-57 0.00E+00 3.59E+06 6.02E+06 0.00E+00 0.00E+00 0.00E+00 6.70E+07 0.00E+00 CO-58 0.00E+00 1.17E+07 2.69E+07 0.00E+00 0.00E+00 0.00E+00 1.61E+08 0.00E+00 CO-60 0.00E+00 4.62E+07 1.04E+08 0.00E+00 0.00E+00 0.00E+00 6.02E+08 0.00E+00 CU-64 0.00E+00 2.28E-07 1.07E-07 0.00E+00 5.77E-07 0.00E+00 1.77E-05 0.00E+00 ZN-65 2.25E+08 7.82E+08 3.65E+08 0.00E+00 5.00E+08 0.00E+00 3.31E+08 0.00E+00 BR-82 0.00E+00 0.00E+00 9.94E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 3.78E+08 1.78E+08 0.00E+00 0.00E400 0.00E+00 5.60E+07 0.00E+00 SR-89 2.17E+08 0.00E+00 6.21E+06 0.00E+00 0.00E+00 0.00E+00 2.58E+07 0.00E+00 SR-90 6.6SE+09 0.00E+00 1.65E+09 0.00E+00 0.00E+00 0.00E+00 1.88E+08 0.00E+00 SR 91 1.33E-10 0.00E+00 5.29E-12 0.00E+00 0.00E+00 0.00E+00 6.04E-10 0.00E+00 1

Y-91 8.03E+05 0.00E&00 2.15E+04 0.00E+00 0.00E+00 0.00E+00 3.29E+08 0.00E+00 Y 93 4.11E-12 0.00E+00 1.13E-13 0.00E+00 0.00E+00 0.00E+00 1.26E-07 0.00E+00 ZR-95 1.25E+06 3.96E+05 2.72E+05 0.00E+00 5.82E+05 0.00E+00 9.13E+08 0.00E+00 ZR-97 1.76E-05 3.49E-06 1.61E-06 0.00E+00 5.29E-06 0.00E+00 9.44E-01 0.00E+00 NB-95 1.57E+06 8.72E+05 4.80E+05 0.00E+00 8.45E+05 0.00E+00 3.73E+09 0.00E+00 MO-99 0.00E+00 8.33E+04 1.59E+04 0.00E+00 1.91E+05 0.00E+00 1.49E+05 0.00E+00 TC-99M 3.78E-21 1.05E-20 1.37E-19 0.00E+00 1.57E-19 5.85E-21 6.92E-18 0.00E+00 j

RU-103 7.45E+07 0.00E+00 3.18E+07 0.00E+00 2.63E+08 0.00E+00 6.22E+09 0.00E+00 RU-105 5.27E-28 0.00E+00 2.05E-28 0.00E+00 6.65E-27 0.00E+00 4.26E-25 0.00E+00 RU-106 1.90E+09 0.00E+00 2.39E+08 0.00E+00 3.66E+09 0.00E+00 9.11E+10 0.00E+00 AG-110M 4.21E+06 3.99E+06 2.43E+06 0.00E+00 7.60E+06 0.00E+00 1.12E+09 0.00E+00 SN-113 2.78E+07 1.16E+06 2.95E+07 3.84E+05 8.23E+05 0.00E+00 3.33E+08 0.00E+00 SB-124 1.36E+07 2.50E+05 5.30E+06 3.08E+04 0.00E+00 1.19E+07 2.74E+08 0.00E+00 SB-125 1.24E+07 1.35E+05 2.89E+06 1.13E+04 0.00E+00 1.09E+07 9.61E+07 0.00E+00 TE-129M 8.96E+08 3.32E+08 1.42E+08 2.89E+08 3.75E+09 0.00E+00 3.36E+09 0.00E+00 TE 131M 3.89E+02 1.86E+02 1.55E+02 2.80E+02 1.94E+03 0.00E+00 1.50E+04 0.00E+00 4

i i

i 1

3 R Values in units of area /yr per micro-Ci/m for inhalation and tritium, and in units of mz ares /yr per micro-Ci/sec for all others.

HBRODCM 3-45 Rev. 9

' United States Nuclear Regulatory Commission

Erelosure 2 to Serial: RNP-RA/95-0159 TABI.E 3.3-6 (centinu2d)

Fag) 81 of 172 Wuclide Best Liver T. Body Thyroid Kidney Lgng CI-Tract Skin i

TE-132 1.19E+06 7.56E+05 7.12E&05 7.97E+05 7.25E+06 0.00E+00 2.40E+07 0.00E+00 I-131 8.78E+06 1.23E+07 6.60E+06 3.59E+09 2.12E+07 0.00E+00 2.43E+06 0.00E+00 I-133 3.11E-01 5.28E-01 1.61E-01 7.37E+01 9.26E-01 0.00E+00 3.99E-01 0.00E+00 I-135 3.82E 17 9.83E-17 3.64E-17 6.32E-15 1.55E-16 0.00E+00 1.09E-16 0.00E+00 CS-134 4.12E+08 9.69E+08 4.50E+08 0.00E+00 3.08E+08 1.18E+08 1.21E+07 0.00E+00 CS-136 8.97E+06 3.53E+07.

2.37E+07 0.00E+00 1.92E+07 3.03E+06 2.84E+06 0.00E+00 CS-137 5.85E+08 7.78E+08 2.71E+08 0.00E+00 2.65E+08 1.03E+0S 1.11E+07 0.00E+00 BA'-140 2.27E+07 2.78E+04 1.46E+06 0.00E+00 9.44E+03 1.87E+04 3.50E+07 0.00E+00 1A 140 3.08E 02 1.51E-02 4.02E-03 0.00E+00 0.00E+00 0.00E+00 8.69E+02 0.00E+00 CE-141 1.04E+04 6.94E+03 7.97E+02 0.00E+00 3.27E+03 0.00E+00 1.98E+07 0.00E+00 CE-143 1.71E-02 1.24E+01 1.39E-03 0.00E+00 5.58E-03 0.00E+00 3.74E+02 0.00E+00 CE-144 9.71E+05 4.02E+05 5.22E+04 0.00E+00 2.40E+05 0.00E+00 2.44E+08 0.00E+00 HF-181 1.47E+08 8.06F.+05 1.64E+07 4.91E+05 6.70E+05 0.00E+00 7.33E+09 0.00E+00 W-187 1.75E 02 1.42E-02 4.99E-03 0.00E+00 0.00E+00 0.00E+00 3.85E+00 0.00E+00 I

NP-239 2.28E 01 2.15E-02 1.19E-02 0.00E+00 6.75E 02 0.00E+00 3.46E+03 0.00E+00 4

4

)

t i

N

,1 1

i HBRODCM 3-46 Rev. 9

Unhed States Nuclear Regulatory Commission Fwla==e 2 to Serial:-RNP-RN95-0159

,,, g 3,7 1

R VALUES for the B.S. ROBINSON STEAM' ELECTRIC FIANT

(Reforence-Regulatory Guide l'.109);

PATHWAY - Meat-

ACE GROUP = Child j

Nuclide Esna Lb.ar T.sody Thyroid E1.dnar Lunt GI-Treet-Ehin q

= H-3 0.00E+00 2.33E+02

-2.33E+02-.2.33E+0?.

2. 33E+02 2.33E+02 2.33E+02 2.33E+02 NA-24' 1.77E-03 1.77E 03 1.77E-03 1.77E-03 1.77E-03 1.77E-03 1.77E 03 0.00E+00

{

~

CR-51 0.00E+001

0. 00E+00 ' 7.85E+03 ' 4.36E+03 1.19E+03 7.96E+03 4.16E+05 0.00E+00

. NN-54 0.00E+00.6.39E+06-1.70E+C6 0.00E+00 1.79E+06 0.00E+00

5. 37E+06 '. 0.00E+00 FE-55 3.56E+08 1.89E+08 5.85E+07.- 0.00E+00 0.00E&OO 1.07E+08 3.50E+07- 0.00E+00 i

FE-59

. 3. 2 3 E+08 '. 5. 23 E+08 2.60E+08 0.00E+00 0.00E+00 1.51E+08 5.44E+08 '. 0.00E+00 CO-57 0.00E+00 4.69E+06' 9.50E+06 0.00E+00 0.00E+00 0.00E+00 3.85E+07- 0.00E+00 CO 58 0.00E+00 1.37E+07; 4'.18E+07 0.00E+00 0.00E+00 0.00E+00 7.97E+07 0.00E+00 i

CO-60" 0.00E+00 5.49E+07..

1.62E+08 0.00E+00 0.00E+00 0.00E+00 -3.04E+08 0.00E+00

. CU-64c

-0.00E+00

3.0 6E-07

1.85E 07 0.00E+00

'7.41E-07 0.00E+00 1.44E-05.0.00E+00

. ZN-65' 3.3EE+08 9.00E+08-5.60E+08 0.00E+00 5.67E+08 0.00E+00 1.58E+08

.0.00E+00 t

' BR-82 10.00E+00 0.00E+00 1.56E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB 86 0.00E+00 5.37E+08. 3.30E+08 0.00E+00 0.00E+00 0.00E+00 3.45E+07 0.00E+00

- SR-89

~4.10E+08 0.00E+00 1.17E+07 0.00E+00 0.00E+00 0.00E+00- 1.59E+07 0.00E+00 SR-90

.8.64E+09 0.00E+00 2.19E+09- 0.00E+00 0.00E+00 0.00E+00 1.16E+08 0.00E+00

< SR-91 2.50E-10. 0.00E+00 9.42E-12 0.00E+00 0.00E+00 0.00E+00 5.51E-10 0.00E&OO Y-91 1.52E+06 0.00E+00' 4.06E+04 0.00E+00 0.00E+00 0.00E+00 2.02E+08 0.00E+00 1

..Y :7.73E-12 0.00E+00- 2.12E-13 0.00E+00 0.00E+00 0.00E+00 1.15E 0.00E+00 f'

ZR-95' 2.23E+06 4.90E+05 4.36E+05 0.00E+00 7.01E+05 0.00E+00 5.11E+08 0.00E+00 i

. ZR-97 13.28E-05 4.74E-06 2.80E-06 -0.00E+00 6.80E-06 0.00E+00 7.18E-01 0.00E+00 NB 2.71E+06 1.06E+06 7.55E+05 0.00E+00 9.92E+05 0.00E+00 1.95E+09 0.00E+00 F

MO-99 0.00E+00 1.16E+05 2.87E+04 0.00E+00 2.47E+05 0.00E+00 9.58E+04 0.00E+00

-TC-99M 6.63E-21 1.30E-20 2.15E-19 0.00E+00 1.89E-19 6.60E-21 7.40E-18 0.00E+00 RU-103 1.35E+08 0.00E+00 5.18E+07. 0.00E+00 3.39E+08- 0.00E+00 3.48E+09 0.00E+00 3

l' RU-105-9.84E-28 0.00E+00 3.57E-28 0.00E+00 8.65E-27 0.00E+00- 6.42E-25 0.00E+00 I

- RU-106 3.58E+09 0.00E+00 4.46E+08 0.00E+00 4.83E+09- 0.00E+00- 5.56E+10 0.00E+00

~ AG-110M 6.99E+06 4.72E+06 3.77E+06 0.00E+00 8.79E+06 0.00E+00 5.61E+08 0.00E+00

~ SN-113 4.17E+07 1.34E+06 4.56E+07 5.51E+05 9.23E+05 0.00E+00 1.67E+08 0.00E+00 SB 124' 2.46E+07 3.19E+05 8.62E+06 5.43E+04 0.00E+00 1.36E+07 1.54E+08 0.00E+00 I

- SB-125 2 '. 25 E+07 1.73E+05 4.71E+06 2.08E+04 0.00E+00 1.25E+07 5.37E+07 0.00E+00 TE-129M-1.69E+09 4.71E+08 2.62E+08 5.44E+08 4.96E+09- 0.00E+00 2.06E+09 0.00E+00 TE-131M-7.23E+02' 2.50E+022 2.66E+02 5.14E+02 2.42E+03 0.00E+00 1.01E+04 0.00E+00 I

i i.

i.

.i 3

tR Values in units of area /yr per micro Ci/m for inhalation and tritium,

-1

'and;in units of m area /yr per micro-Ci/sec'for all others.

{

a

[

HBRODCM..

3-47

'Rev. 9 A

i

! United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 TABIZ 3.3-7 (c:ntinu:d)

Page 83 of 172 Nuclide Agna Liver T. Body Thyroid Kidney Jigng GI-Tract Skin TE-132 2.18E+06 9.65E+05 1.17E+06 1.41E+06 8.96E+06 0.00E+00 9.71E+06 0.00E+00 I 131 1.63E+07 1.64E+07 9.30E+06 5.41E+09 2.69E+07 0.00E+00 1.46E+06 0.00E+00 I 133 5.78E-01 7.15E-01 2.71E-01 1.33E+02 1.19E+00 0.00E+00 2.88E-01 0.00E+00 I-135 6.91E-17 1.24E-16 5.88E-17 1.10E-14 1.91E-16 0.00E+00 9.47E-17 0.00E+00 CS-134 7.26E+08 1.19E+09 2.51E+08 0.00E+00 3.69E+08 1.33E+08 6.43E+06 0.00E+00 CS-136 1.55E+07 4.26E+07 2.75E+07 0.00E+00 2.27E+07 3.38E+06 1.50E+06 0.00E+00 CS-137 1.08E+09 1.03E+09 1.52E+08 0.00E+00 3.36E+08 1.21E+08 6.45E+06 0.00E+00 BA-140 4.19E+07 3.67E+04 2.45E+06 0.00E+00 1.20E+04 2.19E+04 2.12E+07 0.00E+00 LA-140 5.64E-02 1.97E-02 6.64E-03 0.00E+00 0.00E+00 0.00E+00 5.49E+02 0.00E+00 CE-141 1.96E+04 9.76E+03 1.45E+03 0.00E+00 4.28E+03 0.00E+00 1.22E+07 0.00E+00 CE-143 3.21E-02 1.74E+01 2.52E-03 0.00E+00 7.29E-03 0.00E+00 2.55E+02 0.00E+00 CE-144 1.83E+06 5.74E+05 9.77E+04 0.00E+00 3.18E+05 0.00E+00 1.50E+08 0.00E+00 HF-181 2.66E+08 1.04E+06 2.68E+07 8.75E+05 8.35E+05 0.00E+00 4.42E+09 0.00E+00 W-187 3.24E-02 1.92E-02 8.60E 03 0.00E+00 0.00E+00 0.00E+00 2.69E+00 0.00E+00 NP-239 4.29E-01 3.08E-02 2.16E-02 0.00E+00 8.90E-02 0.00E+00 2.28E+03 0.00E+00 4

4 E

RBRODCM 3-48 Rev. 9

~ _. ~ _

i,

4 deiend States Nuclear Regulatory.Conunission ;

Enclosure'2 to' Serial: RNP-RA/95 0159 TAnLE 3:3-8 p 5 K of 172 -

R VALUE8' for. the B.B. ROBINSON STEAM ELECTRIC PIANT -

1 j'

(Reference Regulatory Guide.1.109) l

= PATHWAY'- Cow Milk' U

. AGE GROUP. Adult 2

)

Nuclide EgnR lit,ag T, Body Thyroid Kidney Lgag GI-Tract ghin

,H-3

'O.00E+00 7.63E+02 :7.63E+02 7.63E+02 7.63E+02 7.63E+02

.7.63E+02.7.63E+02 i

!F-18:

4.57E 03 0,00E+00 5.07E-04 0.00E+00 - 0.00E+00 0.00E+00 1.35E-04 0.00E+00

NAo24 2. 4'5 E+06 '2.45E+06 2.45E+06 2.45E+06 2.45E+06 - - 2.45E+06 2.45E+06 : 0.00E+00 CR 51' 0.00E+00' O.00E+00' 2.55E+04 '1.53E+04 5~.62E+03 3.39E+04 6.42E+06 0.00E+00 h

MN-54 0.00E+00. 6.71E+06 l'. 2 8E+06 -- 0.00E+00- 2.00E+06 0.00E+00 2.06E+07 0.00E+00 h

MN-56?

0 00E+00 14.21E-03 7.47E-04 ' : 0,00E+00 ' 5.35E 03 0.00E+00 1.34E-01 0.00E+00

+

F FE-55 1.96E+07 1.35E+07 3.15E+06 0.00E+00 0.00E+00 7.54E+06 7.75E+06 0.00E+00 1FE-59

2. 55E+07.- - 5. 99E+07 2.30E+07 0.00E+00 ~0.00E+00.1.67E+07 -2.00E+08 0.00E+00 4

CO-57t 0.00E+00 9.10E+05 1.69E+06

-0 00E+00 0.00E+00 0.00E+00 2.57E+07 0.00E+00 Co-5M 0.00E+00 3.92E+06 8.79E+06 0.00E+00 0.00E+00- 0.00E+00- 7.95E+07- 0.00E+00

)

CO-60h

-0.00E+00 -1.30E+07 2.87E+07 0.00E+00 0.00E+00- 0.00E+00 2.44E+08 0.00E+00 i-NI-65 3.76E-01 4.88E-02 2.23E-02. 0.00E+00 0.00E+00 0.00E+00 1.24E+00 0.00E+00 lI CU-64 0.00E+00 2.39E+04 1.12E+04 0.00E+00 6.04E+04 0.00E+00' 2.04E+06 0.00E+00 ZN-65

=1.23E+09 3.93E+09-1.78E+09 0.00E+00 2.63E+09 0.00E+00 2.47E+09 0.00E+00 BR-82:

0.00E+00 0.00E+00 3.27E+07' O.00E+00 0.00E+00 0.00E+00 3.75E+07 0.00E+00

[

'BR 83

.0.00E+00 0.00E+00 9.98E-02 0.00E+00 0.00E+00 0.00E+00 1.44E-01 0.00E+00

!~

BR-84

0.00E+00 0.00E+00 1.75E-23 0.00E+00 0.00E+00 0.00E+00- 1.37E-28 0.00E+00

RB-86 0.00E+00

2. 41h.+09 1.12E+09 0.00E+00 0.00E+00 0.00E+00 4.76E+08 0.00E+00 h

-SR-89

.1.23E+09 0.00E+00 3.54E+07 0.00E+00 0.00E+00 0.00E+00 1.98E+08 0.00E+00

.SR-90

-3.89E+10 0.00E+00 9.54E+09 0.00E+00 0.00E+00 0.00E+00 1.12E+09 0.00E+00 i

SR 2.91E+04 0.00E+00 1.17E+03 0.00E+00 0.00E+00 0.00E+00 1.38E+05 0.00E+00 SR-92 4.95E 01. 0.00E+00 2.14E-02 0.00E+00 0.00E+00 0.00E+00 9.82E+00 0.00E+00

[

,Y-91M 6.27Ee20 0.00E+00 2.43E-21 0.00E+00 0.00E+00 0.00E+00 1.84E-19 0.00E+00 Y '7.23E+03 0.00E+00 1.93E+02 0.00E+00 0.00E+00 0.00E+00 3.98E+06 0.00E+00 l

-Y-92 5.64E-05 0.00E+00 1.65E-06 0.00E+00 0.00E+00 0.00E+00 9.88E-01 0.00E+00

.Y 2,24E-01 0.00E+00 6.19E 03 0.00E+00 0.00E+00 0.00E+00 7.11E+03-0.00E+00

,ZR-95 7.89E+02 2.53E+02 1.71E+02 0.00E+00 3.97E+02 0.00E+00 8.02E+05 0.00E+00

[

ZR 97 4.34E-01 8.76E-02 4.01E 02 0.00E+00 1.32E-01 0.00E+00 2.71E+04 0.00E+00 NS-95' 7.23E+04 4.02E+04 2.16E+04 0.00E+00 3.97E+04 0.00E+00 2.44E+08 0.00E+00

.NB-97.-

3.40E'-12 8.59E-13 3.14E-13. 0.00E+00 1.00E-12 0.00E+00 3.17E-09 0.00E+00 MO-99.

0.00E+00- 2.48E+07.

4.72E+06 0.00E+00 5.62E+07 0.00E+00 5.76E+07 0.00E+00 1

J e

N 3

c R Valuesiin unit's~of' ares /yr per micro-Ci/m for inhalation and tritium, and:in units;of a:Tarem/yr per. micro-Ci/see for all others.

HRRODCN!

.3-49

Rev. 9 MS 1

~. ; -__, -

United States Nuclear Regulatory Comminion to Serial: RNP-RA/95-0159 TABLE 3.3-8 (cantinusd)

Page 85 of 172 Nuclide Agag.

Liver T. Body Thyroid Kidney

. Lung CI-Tract Skin TC-99M 3.35E+00 9.48E+00 1.21E+02 0.00E+00 1.44E+02 4.64E+00 5.61E+03 0.00E+00 RU-103 8.85E+02 0.00E+00 3.81E+02 0.00E+00 3.38E+03 0.00E+00 1.03E+05 0.00E+00 RU-105 8.65E-04 0.00E+00 3.41E-04 0.00E+00 1.12E-02 0.00E+00 5.29E-01 0.00E+00 RU-106 1.64E+04 0.00E+00 2.08E+03 0.00E+00 3.17E+04 0.00E+00 1.06E+06 0.00E+00 AG-110M 4.85E+07 4.49E+07 2.66E+07 0.00E+00 8.82E+07 0.00E+00 1.83E+10 0.00E+00 SN-113 3.87E+06 1.49E+05 3.66E+06 5.26E+04 1.10E+05 0.00E+00 6.77E+07 0.00E+00 SB-124 2.16E+07 4.09E+05 8.58E+06 5.25E+04 0.00E+00 1.68E+07 6.14E+08 0.00E+00 SB-125 1.61E+07 1.80E+05 3.84E+06 1.64E+04 0.00E+00 1.24E+07 1.78E+08 0.00E+00 TE-129M 5.67E+07 2.12E+07 8.98E+06 1.95E+07 2.37E+08 0.00E+00 2.86E+08 0.00E+00 TE-129 2.97E-10 1.12E-10 7.25E-11 2.28E-10 1.25E-09 0.00E+00 2.25E-10 0.00E+00 TE-131M 3.69E+05 1.80E+05 1.50E+05 2.86E+05 1.83E+06 0.00E+00 1.79E+07 0.00E+00 TE-132 2.46E+06 1.59E+06 1.49E+06 1.76E+06 1.53E+07 0.00E+00 7.52E+07 0.00E+00 I-131 2.91E+08 4.16E+08 2.38E+08 1.36E+11 7.13E+08 0.00E+00 1.10E+08 0.00E+00 I-132 1.67E-01 4.47E 01 1.56E-01 1.56E+01 7.12E-01 0.00E+00 8.39E-02 0.00E+00 I-133 3.88E+06 6.74E+06 2.06E+06 9.91E+08 1.18E+07 0.00E+00 6.06E+06 0.00E+00 I-134 2.11E-12 5.72E-12 2.05E-12 9.92E-11 9.10E-12 0.00E+00 4.99E-15 0.00E+00 I-135 1.29E+04 3.38E+04 1.25E+04 2.23E+06 5.42Es04 0.00E+00 3.82E+04 0.00E+00 CS-134 4.45E+09 1.06E+10 8.66E+09 0.00E+00 3.43E+09 1.14E+09 1.85E+08 0.00E+00 CS-136 2.51E+08 9.91E+08 7.14E+08 0.00E+00 5.32E+08 7.56E+07 1.13E+08 0.00E+00 CS 137 5.96E+09 8.15E+09 5.34E+09 0.00E+00 2.77E+09 9.20E+08 1.58E+08 0.00E+00 CS-138 9.72E-24 1.92E-23 9.51E-24 0.00E+00 1.41E-23 1.39E-24 8.19E-29 0.00E+00 BA-139 4.54E-08 3.24E-11 1.33E-09 0.00E+00 3.03E-11 1.84E-11 8.06E-08 0.00E+00 BA-140 2.57E+07 3.23E+04 1.68E+06 0.00E+00 1.10E+04 1.85E+04 5.29E+07 0.00E+00 LA-140 4.52E+00 2.28E+00 6.01E-01 0.00E+00 0.00E+00 0.00E+00 1.67E+05 0.00E+00 LA-142 1.90E-11 8.66" 12 2.16E-12 0.00E+00 0.00E+00 0.00E+00 6.32E-08 0.00E+00 CE-141 4.27E+03 2.8,a+03 3.27E+02 0.00E+00 1.34E+03 0.00E+00 1.10E+07 0.00E+00 1

CE-143 4.16E+01 3.08E+04 3.40E+00 0.00E+00 1.35E+01 0.00E+00 1.15E+06 0.00E+00 CE-144 2.83E+05 1.18E+05 1.52E+04 0.00E+00 7.01E+04 0.00E+00 9.56E+07 0.00E+00 HF-181 8.46E+03 4.77E+01 9.57E+02 3.03E+01 3.97E+01 0.00E+00 6.28E+05 0.00E+00 W-187 6.52E+03 5.45E+03 1.90E+03 0.00E+00 0.00E+00 0.00E+00 1.78E+06 0.00E+00 NP-239 3.67E+00 3.61E-01 1.99E-01 0.00E+00 1.13E+00 0.00E+00 7.41E+04 0.00E+00 HBRODCM 3-50 Rev. 9

EUnhed States Nuclear Reg % Commission Enclosme 2 to Serial: RNP-RA/95-0159 gants 3,3.,-

Page 86 " of m.

- a VALtrEs for the E.B. ROBINSON STEAM ELECTRIC FIANT I

(Reference Regulatory Guide 1.109)

PATHWAY = Cow Milk' AGE GROUP - Teen Nuclide Igna Liver

'T. Body Thyroid Kidney Lgggg GI-Tract Shin Ho3 0 00E+00 9.93E+02 9.93E+02 9.93E+02' 9.93E+02 9.93E+02 9.93E+02 9.93E+02 1F-18 8.16E 0.00E+00 8.94E-04.0.00E+00 0.00E+00 0.00E+00- 7.35E-04 0.00E+00

'NAo24 4.27E+06 4.27E+06' 4.27E+06 4.27E+06 4.27E+06 4.27E+06 4.27E+06 0.00E+00

.CR-51'^

0.00E+00 0.00EiOO 4.46E+04.2.48E+04 9.77E+03

'6.36E+04, 7.49E+06 0.00E+00

,MN-54 0.00E+00 1.12E+07 2.22E+06 0.00E+00~ 3.34E+06 0.00E+C9 2'.29E+07 0.00E+00 MN-56 0.00E+00 7.47E-03 1.33E-03 0.00E+00 9.45E 03 0.00E+00 4.91E-01 0.00E+00 FE-55:

3.47E+071 2.46E+07 5.74E+06 0.00E+00 0.00E+00 1.56E+07 1.06E+07 0.00E+00 FE 4.45E+07 1.04E+08 4.01E+07 0.00E+00 0.00E+00 3.27E+07 2.45E+08 0.00E+00 CO 5 7. - 0.00E+00 '

'1. 78E+06 2.99E+06 '0.00E+00 0.00E+00 0.00E+00 3.32E+07 0.00E+00 CO 58J 0.00E+00 6.60E+06 1.52E+07 0.00E+00 0.00E+00 0.00E+00 9.'10E+07 0.00E+00 CO-60.

~0.00E+00' 2.20E+07.4.96E+07 0.00E+00. 0.00E+00 0.00E+00 2.87E+08 0.00E+00 NI-65 6.88E-01 8.79E-02 4.00E-02 0.00E+00 0.00E+00 0.00E+00 4.76E+00 0.00E+00 CU-64

.0.00E+00 4.27E+04 2.01E+04 0.00E+00 1.08E+05 0.00E+00 3.31E+06 0.00E+00 ZN-65 1.90E+09 '6.58E+09 -3.07E+09 0.00E+00 4.21E+09 0.00E+00 2.79E+09 0.00E+00

-BR-82 0.00E+00 0.00E+00 5.68E+07- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

-BR 83 0.00E+00 0.00E+00 1.84E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-84'

. 0.00E+00 0.00E+00 3.13E 23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86.

'O.00E+00 4.40E+09 2.07E+09 0.00E+00 0.00E+00 0.00E+00 6.51E+08 0.00E+00

'SR-89

' 2.28E+09 0.00E+00 6.52E+07 0.00E+00 0.00E+00 0.00E+00 2.71E+08 0.00E+00 SR-90 5.49E+10 0.00E+00 1.36E+10- 0.00E+00 0.00E+00 0.00E+00 1.54E+09 0.00E+00

.SR-91 5.34E+04 0.00E+00 2.12E+03 0.00E+00 0.00E+00 0.00E+00 2.42E+05 0.00E+00 SR-92

.9.07E-01 0.00E+00 3.87E-02 0.00E+00 0.00E+00 0.00E+00 2.31E+01 0.00E+00

'Y-91M 1.15E-19 0.00E+00 4.39E-21 0.00E+00 0.00E+00 0.00E+00 5.42E-18 0.00E+00 L

Y-91' 1.33E+04 -0.00E+00 3.56E+02 0.00E+00 0.00E+00 0.00E+00 5.45E+06 0.00E+00 Y 92-1.04E 04 0.00E+00 ;3.01E-06 0.00E+00 0.00E+00 0.00E+00 2.86E+00 0.00E+00 l

Y 93' 4.14E 01 0.00E+00~ 1.13E-02 0.00E+00 0.00E+00 0.00E+00 1.26E+04 0.00E+00 ZR-95 1.38E+03 4.35E+02 2.99E+02 0.00E+00 6.40E+02 0.00E+00 1.00E+06 0.00E+00 ZR-97

. 7.90E 01 1.56E 01 7.20E-02 0.00E+00 2.37E-01 0.00E+00 4.23E+04 0.00E+00 I

.NB-95 1.23E+05 6.84E+04 3.76E+04 0.00E+00 6.63E+04 0.00E+00 2.92E+08 0.00E+00

.NB-97

' 6.19E-12 1.54E-12' 5.61E-13 0.00E+00 1.80E-12 0.00E+00 3.67E-08 0.00E+00

'MO-99.

0.00E+00- 4.48E+07. 8.55E+06. 0.00E+00 1.03E+08 0,00E+00 8.03E+07 0.00E+00 3

i; i'

l i

.R Values in units of area /yr per micro-Ci/m for inhalation and tritium, f

~1 3

a andjin units of m area /yr per micro-Ci/see for all others.

2HERODCM-3-51 Rev. 9

United States Nuclear Regulatory Comminion to Serial: RNP-RA/95-0159 TABLE 3.3-9 (centinuzd)

Page 87 of 172 Nuclide 32B1 Li"er T. Body lhyroid Kidney Lyng GI-Tract Skin TC-99M 5.82E+00 1.62E+01 2.10E+02 0.00E+00 2.42E+02 9.01E+00 1.07E+04 0.00E+00 RU-103 1.57E+03 0.00E+00 6.73E+02 0.00E+00 5.55E+03 0.00E+00 1.31E+05 0.00E+00 RU-105 1.58E 03 0.00E+00 6.13E-04 0.00E+00 1.99E-02 0.00E+00 1.28E+00 0.00E+00 RU-106 3.02E+04 0.00E+00 3.81E+03 0.00E+00 5.83E+04 0.00E+00 1.45E+06 0.00E+00 AG-110M 8.02E+07 7.59E+07 4.61E+07 0.00E+00 1.45E+08 0.00E+00 2.13E+10 0.00E+00 SN-113 5.95E+06 2.49E+05 6.33E+06 8.23E+04 1.76E+05 0.00E+00 7.14E+07 0.00E+00 SB-124 3.86E+07 7.11E+05 1.51E+07 8.75E+04 0.00E+00 3.37E+07 7.78E+08 0.00E+00 SB-125 2.89E+07 3.15E+05 6.75E+06 2.76E+04 0.00E+00 2.54E+07 2.25E+08 0.00E+00 TE-129M 1.04E+08 3.85E+07 1.64E+07 3.35E+07 4.34E+08 0.00E+00 3.90E+08 0.00E+00 TE-129 5.48E-10 2.04E-10 1.33E-10 3.91E-10 2.30E-09 0.00E+00 2.99E-09 0.00E+00 TE-131M 6.71E+05 3.22E+05 2.69E+05 4.84E+05 3.36E+06 0.00E+00 2.58E+07 0.00E+00 TE-132 4.39E+06 2.78E+06 2.62E+06 2.93E+06 2.67E+07 0.00E+00 8.81E+07 0.00E+00 I 131 5.28E+08 7.39E+08 3.97E+08 2.16E+11 1.27E+09 0.00E+00 1.46E+08 0.00E+00 I-132 2.96E-01 7.75E-01 2.78E-01 2.61E+0.

1.22E+00 0.00E+00 3.38E-01 0.00E+00 1 133 7.08E+06 1.20E+07 3.66E+06 1.68E+09 2.11E+07 0.00E+00 9.09E+06 0.00E+00 I-134 3.74E-12 9.93E-12 3.56E-12 1.65E-10 1.56E-11 0.00E+00 1.31E-13 0.00E+00 I-135 2.29E+04 5.91E+04 2.19E+04 3.80E+06 9.33E+04 0.00E+00 6.54E+04 0.00E+00 CS-134 7.73E+09 1.82E+10 8.44E+09 0.00E+00 5.78E+09 2.21E+09 2.26E+08 0.00E+00 CS-136 4.27E+08 1.68E+09 1.13E+09 0.00E+00 9.16E+08 1.44E+08 1.35E+08 0.00E+00 CS-137 1.08E+10 1.44E+10 5.01E+09 0.00E+00 4.89E+09 1.90E+09 2.05E+08 0.00E+00 CS 138 1.76E-23 3.38E-23 1.69E-23 0.00E+00 2.50E-23 2.91E-24 1.54E-26 0.00E+00 BA 139 8.40E-08 5.91E-11 2.45E-09 0.00E+00 5.57E-11 4.07E-11 7.50E-07 0.00E+00 BA-140 4.64E+07 5.68E+04 2.99E+06 0.00E+00 1.93E+04 3.82E+04 7.15E+07 0.00E+00 LA-140 8.11E+00 3.99E+00 1.06E+00 0.00E+00 0.00E+00 0.00E+00 2.29E+05 0.00E+00 LA-142 3.44E-11 1.53E-11 3.80E-12 0.00E+00 0.00E+00 0.00E+00 4.64E-07 0.00E+00 CE-l'41 7.82E+03 5.22E+03 6.00E+02 0.00E+00 2.46E+03 0.00E+00 1.49E+07 0.00E+00 CE-143 7.65E+01 5.56E+04 6.22E+00 0.00E+00 2.50E+01 0.00E+00 1.67E+06 0.00E+00 CE-144 5.20E+05 2.15E+05 2.80E+04 0.00E+00 1.29E+05 0.00E+00 1.31E+08 0.00E+00 j

HF-181 1.51E+04 8.32E+01 1.69E+03 5.06E+01 6.91E+01 0.00E+00 7.57E+05 0.00E+00 W-187 1.19E+04 9.72t+03 3.40E+03 0.00E+00 0.00E+00 0.00E+00 2.63E+06 0.00E+00 i

NP-239 7.01E+00 6.61E-01 3.67E-01 0.00E+00 2.08E+00 0.00E+00 1.06E+05 0.00E+00 4

HBRODCM 3-52 Rev. 9

r. _

b United States Nuclear Regulatory.Commianiaa

~ Fwla=we 2 G Serial: RNP-RA/95-0159 J

,,,g,3,3,1n.

1

'R'VALURS for the M.B.2 ROBINSON STEAM ELECTRIC'FLANT

-(Reference Regulatory Guide 1.109)-

E < PATHWAY - Cow Milk.

ACE CROUP.- Child i

Nuclide Egnt Lly.gK T. Body Thyroid

' Kidney Lunt GI-Tract Rhin 1,

.Ho3[

l0.00E+00- 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57'E+03 1.57E+03

'1.57E+03 i

F-18 1~.94E-02 0.00E+00 1.92E-03 0.00E+00 0.00E+00 0.00E+00 5.25E-03 0.00E+00

'NA 8.88E+06~

8.88E+06 8.88E+06. 8. 88EM)6 8.88E+06 8.88E+06 8.88E+06 0.00E+00 CR-51 0.00E+00 0.00E+00 9.09E+04 5.05E+04~ 1.38E+04 9.21E+04 4.82E+06 0.00E+00 MN-54 0.00E+00 1.67E+07-4.46E+06 0.00E+00 - 4.69E+06 0.00E+00- 1.40E+07 0.00E+00

'MN-56 0.00E+00: ' 1.30E-02 ' 2.94E-03 0.00E+00 1.57E-02 0.00E+00 1.89E+00 0.00E+00 j

FEoS5

.8.71E+07' 4.62E+07 1.43E+07 0.00E+00 0.00E+00 2.61E+07 8.56E+06 0.00E+00 FE-59a 1~.03E+08 1.67E+08 8.31E+07 0.00E+00 0.00E+00 4.84E+07 1.74E+08 'O.00E+00

.i

.i -

CO-57 O.00E+00 3.04E+06 6.16E+06 0.00E+00 0.00E+00 0.00E+00 2.49E+07 0.00E+00 CO-58 0.00E+00 1.01E+07 3.09E+07 0.00E+00 0.00E+00 0.00E+00 5.88E+07- 0.00E+00 CO.60' O.00E+00.3.42E+07: 1.01E+08 0.00E+00 0.00E+00 0.00E+00 1.89E+08 0.00E+00 NI-65 1.68E+00 1.58E-01 9.24E-02 0.00E+00 0.00E+00 0.00E+00 1.94E+01 0.00d+00 ICU 0.00E+00

'7.'50E+04.4.53E+04 0.00E+00 1.81E+05 0.00E+00 3.52E+06 '0.00E+00 i

'2N-65 3.72E+09-9.91E+09 6.16E+09 0.00E+00 6.24E+09 0.00E+00 1.74E+09, 0.00E+00 BR-82 0.00E+00 0.00E+00 1.16E+08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0'00E+00

BR-83 0.00E+00 0.00E+00 4.52E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

[

BR-84 0.00E+00 0.00E+00 7.08E-23 0.00E+00- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 8.16E+09 5.02E+09 0.00E+00 0.00E+00 0.00E+00 5.25E+08 0.00E+00 SR-89 5.63E+09 0.00E+00 1.61E+08 0.00E+00 0.00E+00 0.00E+00 2.18E+08 0.00E+00 t

SR-90

-9.28E+10 0.00E+00 2.35E+10 0.00E+00 0.00E+00 0.00E+00 1.25E+09 0.00E+00 SR-91

.1.31E+05 0'.00E+00 4.94E+03 0.00E+00 0.00E+00 0.00E+00 2.89E+05 0.00E+00 SR-92 2.21E+00 0.00E+00 8.88E-02 0.00E+00 0.00E+00 0.00E+00 4.19E+01 0.00E+00 Y 91M :

.2.80E-19 0.00E+00 1.02E-20 0.00E+00 0.00E+00 0.00E+00 5.49E-16 0.00E+00

'Y-91 3.28E+04- 0.00E+00 8.78E+02 =0.00E+00 0.00E+00 0.00E+00 4.38E+06 0.00E+00

-Y-92 2.56E 04 0.00E+00 7.32E-06 0.00E+00 0.00E+00 0.00E+00 7.39E+00 0.00E+00 Y-93 1.02E+00 0.00E+00 2.79E-02 0.00E+00 0.00E+00 0.00E+00 1.51E+04 0.00E+00

.ZR-95 3;20E+03 7.04E+02 6.27E+02 0.00E+00 1.01E+03 0.00E+00 7.35E+05 0.00E+00

-ZR-97 1.92E+00 2.78E-01 1.64E-01 0.00E+00 3.99E-01 0.00E+00 4.21E+04 0.00E+00 i.

NB-95 2.78E+05 1.08E+05 7.74E+04 0.00E+00 '1.02E+05 0.00E+00 2.00E+08 0.00E+00 NB-97' 1.50E-11 2.72E-12

'1.27E-12 0.00E+00 3.01E-12 0.00E+00 8.38E-07 0.00E+00 1

l

MO 99 0.00E+00 8.16E+07 2.02E+07 0.00E+00 1.74E+08 0.00E+00 6.75E+07 0.00E+00 i

3 for inhalation and tritium, R Values in-units o'f area /yr per. micro-Ci/m 1

and in units of~ m ares /yr per micro-Ci/sec for all others.

~

a 3 Rev. 9=

~HSRODCM-

~

. =.

.---a.

.~

United States Nuclear Regulatory Comminion

< to Serial RNP-RA/95-0159 TABIz 3.3-10 (centinu:d)

Page 89 of 172 Nuclide Agns.

Liver T. Body Dyroid Kidney LHER GI-Tract Skin TC-99M 1.33E+01 2.62E+01 4.34E+02 0.00E+00 3.80E+02 1.33E+01 1.49E+04 0.00E+00 RU.103 3.72E+03 0.00E+00 1.43E+03 0.00E+00 9.37E+03 0.00E+00 9.62E+04 0.00E+00 RU-105 3.86E-03 0.00E+00 1.40E-03 0.00E+00 3.39E 02 0.00E+00 2.52E+00 0.00E+00 RU-106 7.45E+04 0.00E+00 9.29E+03 0.00E+00 1.01E+05 0.00E+00 1.16E+06 0.00E+00 AG 110M 1.74E+08 1.17E+08 9.39E+07 0.00E+00 2.19E+08 0.00E+00 1.40E+10 0.00E+00 SN 113 1.17E+07 3.76E+05 1.28E+07 1.54E+05 2.59E+05 0.00E+00 4.67E+07 0.00E+00 SB-124 9.13E+07 1.18E+06 3.20E+07 2.01E+05 0.00E+00 5.07E+07 5.71E+08 0.00E+00 SB-125 6.87E+07 5.30E+05 1.44E+07 6.36E+04 0.00E+00 3.83E+07 1.64E+08 0.00E+00 4

TE-129M 2.56E+08 7.14E+07 3.97E+07 8.25E+07 7.51E+08 0.00E+00 3.12E+08 0.00E+00 TE-129 1.35E-09 3.77E-10 3.21E-10 9.64E-10 3.95E-09 0.00E+00 8.41E-08 0.00E+00 TE-131M 1.63E+06 5.65E+05 6.02E+05 1.16E+06 5.47E+06 0.00E+00 2.29E+07 0.00E+00 TE-132 1.05E+07 4.64E+06 5.61E+06 6.76E+06 4.31E+07 0.00E+00 4.67E+07 0.00E+00 1 131 1.28E+09 1.29E+09 7.32E+08 4.26E+11 2.11E+09 0.00E+00 1.15E+08 0.00E+00 I-132 7.01E-01 1.29E+00 5.92E-01 5.97E+01 1.97E+00 0.00E+00 1.52E+00 0.00E+00 I-133-1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.55E+07 0.00E+00 8.57E+06 0.00E+00 1-134 8.87E-12 1.65E-11 7.57E-12 3.79E-10 2.52E-11 0.00E+00 1.09E-11 0.00E+00 I-135 5.43E+04 9.77E+04 4.62E+04 8.66E+06 1.50E+05 0.00E+00 7.45E+04 0.00E+00 CS-134 1.78E+10 2.93E+10 6.17E+09 0.00E+00 9.07E+09 3.25E+09 1.58E+08 0.00E+00 CS-136 9.65E+08 2.65E+09 1.72E+09 0.00E+00 1.41E+09 2.11E+08 9.32E+07 0.00E+00 CS-137 2.60E+10 2.49E+10 3.68E+09 0.00E+00 8.12E+09 2.92E+09 1.56E+08 0.00E+00 CS-138 4.27E-23 5.94E-23 3.77E-23 0.00E+00 4.18E-23 4.50E-24 2.74E-23 0.00E+00 BA-139 2.06E-07 1.10E-10 5.98E-09 0.00E+00 9.62E-11 6.48E-11 1.19E-05 0.00E+00 BA-140 1.12E+08 9.80E+04 6.53E+06 0.00E+00 3.19E+04 5.85E+04 5.67E+07 0.G0E+00 LA-140 1.94E+01 6.79E+00 2.29E+00 0.00E+00 0.00E+00 0.00E+00 1.89E+05 0.00E+00 LA-142 8.30E-11 2.64E-11 8.28E 12 0.00E+00 0.00E+00 0.00E+00 5.24E-06 0.00E+00 CE-141 1.93E+04 9.61E+03 1.43E+03 0.00E+00 4.21E+03 0.00E+00 1.20E+07 0.00E+00 CE-143 1.88E+02 1.02E+05 1.47E+01 0.00E+00 4.27E+01 0.00E+00 1.49E+06 0.00E+00 CE 144 1.28E+06 4.02E+05 6.85E+04 0.00E+00 2.23E+05 0.00E+00 1.05E+08 0.00E+00 HF-181 3.59E+04 1.40E+02 3.61E+03 1.18E+02 1.13E+02 0.00E+00 5.96E+05 0.00E+00

)

W-187 2.89E+04 1.71E+04 7.68E+03 0.00E+00 0.00E+00 0.00E+00 2.40E+06 0.00E+00 NP-239 1.73E+01 1.24E+00 8.71E-01 0.00E+00 3.58E+00 0.00E+00 9.17E+04 0.00E+00 1

HBRODCM 3-54 Rev. 9

. - ~

~

Ubited States Nucleaf RWamry Commienian to Serial: RNP-RA/95-0159 TABU 3. 3-11 '

Page 90 of 172-

.R VALUES for'the B.B. ROBINSON STEAM EU CTRIC FudlT 1

(Reference Regulatory Guide 1.109)

-PATHWAY - Cow Milk

. ACE CROUP.

_ Infant t

l Nuclide Igna Liver T. Body Thyroid Kidner Lung CI-Tract Ehin H3 0.00E+00 2.38E+03 2.38E+03 '2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 l

L F618 4'. 04 E-02 0.00E+00' 3.45E-03 0.00E+00 0.00E+00 0.00E+00 9.51E-03 0.00E+00 NA : 1'. 5 5 E+07 ~1.55E+07 1.55E+07 1.55E+07 1.55E+07 ' 1.55E+07 1.55E+07 -0.00E+00 j

CR-51

-0.00E+00, 0.00E+00 1.44E+05 -9.40E+04 2.05E+04 1.83E+05 4.20E+06 0.00E+00 i

MN-54 0.00E+00 3.11E+07 7.05E+06 0.00E+00 6.90E+06 0.00E+00 1.14E+07 0.00E+00 MN-56 0.00E+00. 3.19E-02 5.-50E 03 0.00E+00 2.74E 02 0.00E+00 2.90E+00 0.00E+00 FE-55

,1,05E+08 L -- 6. 80E+07 1.82E+07 0.00E+00. 0.00E+00 3.32E+07 8.63E+06 0.00E+00

'FE 59..

1.93E+08 3.36E+08~ 1.33E+08 0.00E+00 0.00E+00 9.94E+07 1.61E+08- 0.00E+00 CO-571 0.00E+00. 7.10E+06 1.15E+07 0.00E+00 0.00E+00 0.00E+00 2.42E+07-0.00E+00 i

co-585

-0.00E+00 2.02E+07 5.03E+07 0.00E+00 0.00E+00 0.00E+00 5.03E+07 0.00E+00 CO-60

'O.00E+00 6.98E+07 1.65E+08

.0.00E+00 0.00E+00 0.00E+00 1.66E+08 0.00E+00 l-NIU65

'3.56E+00 4.03E-01 1.83E-01 0.00E+00 0.00E+00 0.00E+00 3.07E+01 0.00E+00 i

CU 0.00E+00 1.86E+05 8'.63E+04 0.00E+00 3.15E+05- 0.00E+00 3.83E+06 0.00E+00 LZN-65 5.00E+09 1.71E+10 7.90E+09 0.00E+00 8.31E+09 0.00E+00 1.45E+10 0.00E+00 3

l

-BR-82 0.00E+00 0.00E+00 1.96E+08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-83 LO.00E+00 0.00E+00 9.60E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-841 0'00E+00 0.00E+00 1.37E-22 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86

.0.00E+00 2.07E+10 1.02E+?C 0.00E+00 0.00E+00 0.00E+00 5.30E+08 0.00E+00 SR-89 1.07E+10 0.00E+00 J.07E+08 0.00E+00 0.00E+00 0.00E+00 2.20E+08 0.00E+00 SR-90 1.01E+11 0.00E+00 2.57E+10 0.00E+00 0.00E+00 0.00E+00 1.26E+09 0.00E+00 SR-91 2.73E+05 0.00E+00 9.87E+03 0.00E+00 0.00E+00 0.00E+00 3.23E+05 0.00E+00 SR 4.71E+00 0.00E+00 1.75E-01 0.00E+00 0.00E+00 0.00E+00 5.08E+01 0.00E+00 Y-91M.

5.94E-19 0.00E+00 2.03E-20 0.00E+00 0.00E+00 0.00E+00 1.98E-15 0.00E+00 4

Y-91 6.16E+04 0.00E+00 1.64E+03 0.00E+00 0.00E+00 0.00E+00 4.42E+06 0.00E+00

~

Y 5.44E-04 0.00E+00.

1.53E-05 0.00E+00 0.00E+00 0.00E+00 1.04E+01 0.00E+00

_Y-93 2.16E+00 0.00E+00 5.90E-02 0.00E+00 0.00E+00 0.00E+00 1.71E+04-0.00E+00

ZR-95 5.69E+03 1.39E+03 9.83E+02 0.00E+00 1.49E+03 0.00E+00 6.91E+05 0.00E+00 ZR-97

- 4.07E+00 6.99E-01 3.19E-01 0.00E+00 7.04E-01 0.00E+00 4.46E+04 0.00E+00 p

.NB-95 5.19E+05 2.14E+05 1.24E+05 0.00E+00 1.53E+05 0.00E+00 1.81E+08- 0.00E+00 NB-97 3.18E-11 6.78E-12 2.45E-12 0.00E+00 5.30E-12 ' O.00E+00 2.14E-06 0.00E+00 NO-99

~0.00E+00 2.09E+08 4.07E+07 0.00E+00 3.12E+08 0.00E+00 6.87E+07 0.00E+00 TC-99H

' 2.78E+015 ' 5.73E+01 7.37E+02 0.00E+00 6.16E+02 2.99E+01 1.66E+04 0.00E+00 i

1 8

i R-Valuesfin units of area /yr per micro-Ci/a for inhalation and tritium, and in units of as area /yr per micro-Ci/sec.for all others.

HERODCM 3-55' Rev. 9 c

-.__--_.--___--.____.___-----.-----__._.____--_--_------,.._---~n.-

e a--

,------e,-

+-.,m

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 TAsLE 3.3-11 (centinu-d) l Page 91 of 172 i

l Nuclide Igna Liggg T. Body Thyroid Kidney laing GI-Tract E]dB RU-103 7.54E+03 0.00E+00 2.52E+03 0.00E+00 1.57E+04 0.00E+00 9.17E+04 0.00E+00 L

RU-105 8.13E-03 0.00E+00 2.74E 03 0.00E+00 5.98E-02 0.00E+00 3.23E+00 0.00E+00 RU-106 1.53E+05 0.00E+00 1.92E+04 0.00E+00 1.81E+05 0.00E+00 1.16E+06 0.00E+00 AG-110M 3.21E+08 2.35E+08 1.55E+08 0.00E+00 3.36E+08 0.00E+00 1.22E+10 0.00E+00 SN-113 1.78E+07 6.79E+05 1.84E+07 2.59E+05 3.65E+05 0.00E+00 3.79E+07 0.00E+00 S8-124 1.76E+08 2.59E+06.

5.45E+07 4.67E+05 0.00E+00 1.10E+08 5.43E+08 0.00E+00 i

SB 125 1.18E+08 1.14E+06 2.43E+07 1.48E+05 0.00E+00 6.83E+07 1.57E+08 0.00E+00 l

TE-129M 5.25E+08 1.80C+08 8.09E+07 2.02E+08 1.31E+09 0.00E+00 3.14E+08 0.00E+00 TE-129 2.86E-09 9.87E-10 6.69E-10 2.40E-09 7.13E-09 0.00E+00 2.29E-07 0.00E+00

. 3.45E+06 1.39E+06 1.15E+06 2.82E+06 9.56E+06 0.00E+00 2.34E+07 0.00E+00 TE-131M TE-132 2.16E+07 1.07E+07 9.98E+06 1.58E+07 6.69E+07 0.00E+00 3.96E+07 0.00E+00 I-131 2.67E+09_

3.15E+09 1.38E+09 1.03E+12 3.68E+09 0.00E+00 1.12E+08 0.00E+00 i

1 132 1.45E+00 2.95E+00 1.05E+00 1.38E+02 3.29E+00 0.00E+00 2.39E+00 0.00E+00 1-133' 3.63E+07 5.29E+07 1.55E+07 9.62E+09 6.22E+07 0.00E+00 8.95E+06 0.00E+00 I-134 1.84E-11 3.77E-11 1.34E-11 8.76E-10 4.21E-11 0.00E+00 3.89E-11 0.00E+00 I

I-135 1.13E+05 2.25E+05 8.19E+04 2.01E+07 2.50E+05 0.00E+00 8.13E+04 0.00E+00 f

CS-134 2.87E+10 5.36E+10 5.41E+09 0.00E+00 1.38E+10 5.65E+09 1.46E+08 0.00E+00 CS-136 1.88E+09 5.54E+09 2.07E+09 0.00E+00 2.21E+09 4.52E+08 8.42E+07 0.00E+00 CS-137 4.16E+10 4.86E+10 3.45E+09 0.00E+00 1.31E+10 5.29E+09 1.52E+08 0.00E+'

CS-138 9.01E-23 1.47E-22 7.10E-23 0.00E+00 7.31E-23 1.14E-23 2.34E-22 0.00E+00 BA-139 4.39E 07 2.91E-10 1.27E-08 0.00E+00 1.75E-10 1.77E-10 2.78E 05 0.00E+00 BA-140 2.30E+08 2.30E+05 1.19E+07 0,00E+00 5.47E+04 1.41E+05 5.66E+07 0.00E+00 IA-140 4.06E+01 1.60E+01 4.11E+00 0.00E+00 0.00E+00 0.00E+00 1.88E+05 0.00E+00 IA-142 1.74E-10 6.40E-11 1.53E-11 0.00E+00 0.00E+00 0.00E+00 1.09E-05 0.00E+00 CE-141 3.82E+04 2.33E+04 2.74E+03 0.00E+00 7.18E+03 0.00E+00 1.20E+07 0.00E+00 I

CE 143 3.97E+02 2.64E+05 3.01E+01 0.00E+00 7.68E+01 0.00E+00 1.54E+06 0.00E+00 CE-144 1.84E+06 7.52E+05 1.03E+05 0.00E+00 3.04E+05 0.00E+00 1.05E+08 0.00E+00 j-HF-181 6.86E+04 3.22E+02 6.06E+03 2.73E+02 1.89E+02 0.00E+00 5.62E+05 0.00E+00

)

W-187 6.08E+04 4.23E+04 1.46E+04 0.00E+00 0,00E+00 0.00E+00 2.49E+06 0.00E+00 NP-239 3.65E+01 3.26E+00 1.84E+00 0.00E+00 6.51E+00 0.00E+00 9.44E+04 0.00E+00 4

4 1

i HBRODCM 3-56 Rev. 9

' United States Nuclear Regulatory Commissian

~ Enclosure 2 G Serial: RNP-RA/95-0159 TABLE 3.3-12 1

R VALUES for the E.B. ROBINSON STEAM ELECTRIC FIANT (Reference Regulatory Guide 1.109)

PATHWAY = Goat Milk

. AGE. GROUP = Adult:

Nuclide Bent LLy.3I T. Body Thyroid Kishitz Lune GI-Tract jhin 1

a N 0.00E+00 _1.56E+03,1.56E+03 -1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 F-18:

5.48E 04' O.00FFOO 6.08E 05 0.00E+00 0.00E+00 0.00E+00 1.63E-05 0.00E+00 l

E NA 24 2.93E+05 2.9aE+05 2.93E+05 2.93E+05 2.93E+05 2.93E+05' 2.93E+05 0.00E+00 l

CR-51.

0.00E+00 0.00E+00 3.06E+03 1.83E+03 6.75E+02 4.06E+03 7.70E+05 0.00E+00

MN-54 0.00E+00 8.06E+05 1.54E+05 0.00E+00 2.40E+05 0.00E+00 2.47E+06 0.00E+00 i

MN-56 0.00E+00.

5. 05 E-04' - 8.96E-05 0.00E+00 6.42E-04 0.00E+00- 1.61E-02' O.00E+00

]

FE 55.

-2.54E4 95' ~1.76E+05 4.10E+04 0.00E+00 0.00E+00 9.80E+04 1.01E+05 0.00E+00

-FE 59 3.31E+05

.7.79E+05 2.98E+05 0.00E+00 0.00E+00 2.18E+05 2.60E+06 0.00Ev00 CO-57.

0.00E+00 1.09E+05 2.02E+05 0.00E+00 0.00E+00 0.00E+00 3.09E+06 0.00E+00 C0 58

-0.00E+00 4.71E+05 1.05E+06' O.00E+00 0.00E+00 0.00E+00 9.54E+06 0.00E+00 i

' Codo 0.00E+00 l'568+06 3.44E+06 0.00E+00 0.00E+00 0.00E+00 2.93E+07 0.00E+00 3

NI 4.51E 02 5.86E-03 2.67E-03 0.00E+00 0.00E+00 0.00E+00 1.49E-01 0.00E+00 CUi64 0.00E+00 2.67E+03 1.'25E+03 0.00E+00 6.73E+03 0.00E+00 2.27E+05 0.00E+00

)

ZN-65 l'.48E+08 4.71E+08. 2.13E+08. 0.00E+00 3.15E+08 0.00E+00 2.97E+08 0.00E+00 BR-82 0.00E+00 0.00E+00 3;93E+06 0.00E+00 0.00E+00 0.00E+00 4.50E+06 0.00E+00 BR-83<

0.00E+00 0.00E+00 1.20E-02 0.00E+00 0.00E+00 0.00E+00 1.73E-02 0.00E+00 LBR-84 0.00E+00 0.00E&OO 2.10E-24 0.00E+00 0.00E+00 0.00E+00 1.65E-29 0.00E+00 i

RB 86 0.00E+00 2.90E+08 1.35E+08 0.00E+00 0.00E+00 0.00E+00 5.71E+07 0.00E+00 SR-89 2.59E+09 0.00E+00 7.44E+07 0.00E+00 0.00E+00 0.00E+00 4.16E+08 0.00E+00 SRo90 8.16E+10- 0.00E+00 2.00E+10 0.00E+00 0.00E+00 0.00E+00 2.36E+09 0.00E+00 SR-91 6.10E+04 0.00E+00 2.46E+03 0.00E+00 0.00E+00 0.00E+00 2.91E+05 0.00E+00 SR 92 1.04E+00 0.00E+00 4.50E 02 0.00E+00 0.00E+00 0.00E+00 2.06E+01 0.00E+00

.Yo91M 7.52E-21 0.00E+00 2.91E-22 0.00E+00 0.00E+00 0.00E+00 2.21E-20 0.00E+00 h.

Y-91 8.67E+02 0.00E+00 2.32E+01 0.00E+00 0.00E+00 0.00E+00 4.77E+05 0.00E+00 Y-92 6.77E 06 0.00E+00 1.98E 07 0.00E+00 0.00E+00 0.00E+00 1.19E-01 0.00E+00 i

Y-93 2.69E-02 0.00E+00 7.43E-04 0.00E+00 0.00E+00 0.00E+00 8.53E+02 0.00E+00 ZR-95 9.47E+01 3.04E+01 2,06E+01 0.00E+00 4.76E+01 0.00E+00 9.62E+04 0.00E+00 ZR-97

'5.21E-02 1.05E 02 4.81E-03 0.00E+00 1.59E-02 0.00E+00 3.26E+03 0.00E+00 NB-95 8.67E+03 4.82E+03 2.59E+03 0.00E+00 4.77E+03 0.00E+00 2.93E+07 0.00E+00 NB-97 4.08E 13-1.03E-13 3.76E-14 0.00E+00 1.20E-13 0.00E+00 3.80E-10 0.00E+00

'MO-99 0.00E+00 2.98E+06 5.67E+05 0.00E+00 6.75E+06 0.00E+00 6.91E+06 0.00E+00 3

1R Values in units of ares /yr per micro-Ci/m :for inhalation and tritium.

and in units of ma area /yr per micro-Ci/see for all others, p

1HBRODCM 3-57 Rev. 9

United States Nuclear Regulatory Comminion

Enclorure 2 to Serial: RNP-RA/95-0159 7 Ant,g 3.3 12 (centinund)

Page 93 of 172 Nuclide lent Liv 1.g T. Body Thyroid Kidney Jaglg GI-Tract Skin TC 99M 4.03E 01 1.14E+00 1.45E+01 0.00E+00 1.73E+01 5.57E 01 6.73E+02 0.00E+00 RU-103 1.06E+02 0.00E+00 4.58E+01 0.00E+00 4.05E+02 0.00E+00 1.24E+04 0.00E+00 RU-105 1.04E 04 0.00E+00 4.10E-05 0.00E+00 1.34E 03 0.00E+00 6.35E 02 0.00E+00 RU 106 1.97E+03 0.00E+00 2.50E+02 0.00E+00 3.81E+03 0.00E+00 1.28E+05 0.00E+00 AG-110M 5.82E+06 5.38E+06 3.20E+06 0.00E+00 1.06E+07 0.00E+00 2.20E+09 0.00E+00 SN-113 4.64E+05 1.79E+04 4.39E+05 6.31E+03 1.32E+04 0.00E+00 8.12E+06 0.00E+00 SB-124 2.60E+06 4.90E+04 1.03E+06 6.29E+03 0.00E+00 2.02E+06 7.37E+07 0.00E+00 SB 125 1.94E+06 2.16E+04 4.61E+05 1.97E+03 0.00E+00 1.49E+06 2.13E+07 0.00E+00 TE-129M 6.81E+06 2.54E+06 1.08E+06 2.34E+06 2.84E+07 0.00E+00 3.43E+07 0.00E+00 TE 129 3.57E-11 1.34E 11 8.70E 12 2.74E 11 1.50E-10 0.00E+00 2.69E-11 0.00E+00 TE 131M 4.43E+04 2.17E+04 1.80E+04 3.43E+04 2.19E+05 0.00E+00 2.15E+06 0.00E+00 TE 132 2.95E+05 1.91E+05 1.79E+05 2.11E+05 1.84E+06 0.00E+00 9.02E+06 0.00E+00 I-131 3.49E+08 4.99E+08 2.86E+08 1.64E+11 8.56E+08 0.00E+00 1.32E+08 0.00E+00 1-132 2.00E 01 5.36E 01 1.88E-01 1.88E+01 8 54E-01 0.00E+00 1.01E 01 0.00E+00 I-133 4.65E+06 8.09E+06 2.47E+06 1.19E+09 1.41E+07 0.00E+00 7.27E+06 0.00E+00 I-134 2.53E-12 6.87E-12 2.46E-12 1.19E-10 1.09E-11 0.00E+00 5.99E 15 0.00E+00 I-135 1.55E+04 4.06E+04 1.50E+04 2.68E+06 6.51E+04 0.00E+00 4.58E+04 0.00E+00 CS-134 1.34E+10 3.18E+10 2.60E+10 0.00E+00 1.03E+10 3.41E+09 5.56E+08 0.00E+00 CS-136 7.53E+08 2.97E+09 2.14E+09 0.00E+00 1.65E+09 2.27E+08 3.38E+08 0.00E+00 4

CS-137 1.79E+1C 2.45E+10 1.60E+10 0.00E+00 8.30E+09 2.76E+09 4.73E+08 0.00E+00 CS 138 2.91E 23 5.76E-23 2.85E-23 0.00E+00 4.23E-23 4.18E-24 2.46E-28 0.00E+00 BA-139 5.45E-09 3.88E-12 1.60E 10 0.00E+00 3.63E-12 2.20E-12 9.67E 09 0.00E+00 BA-140 3.08E+06 3.87E+03 2.02E+05 0.00E+00 1.32E+03 2.22E+03 6.35E+06 0.00E+00 LA-140 5.42E 01 2.73E 01 7.22E-02 0.00E+00 0.00E+00 0.00E+00 2.00E+04 0.00E+00 LA-142 2.28E 12 1.04E-12 2.59E-13 0.00E+00 0.00E+00 0.00E+00 7.58E-09 0.00E+00 CE-141 5.12E+02 3.46E+02 3.93E+01 0.00E+00 1.61E+02 0.00E+00 1.32E+06 0.00E+00 CE-143 4.99E+00 3.69E+03 4.09E-01 0.00E+00 1.63E+00 0.00E+00 1.38E+05 0.00E+00 CE-144 3.39E+04 1.42E+04 1.82E+03 0.00E+00 8.41E+03 0.00E+00 1.15E+07 0.00E+00 HF-181 1.01E+03 5.73E+00 1.15E+02 3.63E+00 4.77E+00 0.00E+00 7.53E+04 0.00E+00 W-187 7.82E+02 6.54E+02 2.29E+02 0.00E+00 0.00E+00 0.00E+00 2.14E+05 0.00E+00 NP-239 4.41E 01 4.34E 02 2.39E-02 0.00E+00 1.35E-01 0.00E+00 8.89E+03 0.00E+00 1

HBRODCM 3-58 Rev. 9

r

' United States Nuclear Regulatory Comminaion to Serial: RNP-RA/95-0159 TABLE 3.3-13 of M R VALUES for the H.B. ROBINSON STEAM ELECTRIC FLANT 1

(Reference Regulatory Guide 1.109)

PATHUAY - Goat Milk AGE CROUP - Teen,

leuclido Long.

Liver T. Body Thyroid

_ Kidney Ianig GI-Trast.;

skin H-3 0.00E+00 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 F-18 9.79E-04 0.00E+00 1.07E-04 0.00E+00 0.00E+00 0.00E+00 8.82E-05 0.00E+00 NA-24 5.12E+05 5.12E+05 5.12E+05 5.12E+05 5.12E+05 5.12E+05 5.12E+05 0.00E+00 CR-51 0.00E+00 0.00E+00 5.35E+03 2.97E+03 1.17E+03 7.64E+03 8.99E+05 0.00E+00 MN-54 0.00E+00 1.34E+06 2.66E+05 0.00E+00 4.00E+05 0.00E+00 2.75E+06 0.00E+00 MN-56 0.00E+00 8.96E-04 1.59E-04 0.00E+00 1.13E-03 0.00E+00 5.90E-02 0.00E+00 FE-55 4.51E+05 3.20E+05 7.46E+04 0.00E+00 0.00E+00 2.03E+05 1.38E+05 0.00E+00 FE-59 5.78E+05 1.35E+06 5.21E+05 0.00E+00 0.00E+00 4.25E+05 3.19E+06 0.00E+00 CO-57 0.00E+00 2.14E+05 3.58E+05 0.00E+00 0.00E+00 0.00E+00 3.99E+06 0.00E+00 CO 58 0.00E+00 7.92E+05 1.83E+06 0.00E+00 0.00E+00 0.00E+00 1.09E+07 0.00E+00 CO 60 0.00E+00 2.64E+06 5.95E+06 0,00E+00 0.00E+00 0.00E+00 3.44E+07 0.00E+00 NI 65 8.25E-02 1.05E-02 4.80E-03 0.00E+00 0.00E+00 0.00E+00 5.72E-01 0.00E+00 CU-64 0.00E+00 4.75E+03 2.24E+03 0.00E+00 1.20E+04 0.00E+00 3.69E+05 0.00E+00 ZN-65 2.27E+08 7.90E+08 3.68E+08 0.00E+00 5.05E+08 0.00E+00 3.34E+08 0.00E+00 BR-82 0.00E+00 0.00E+00 6.82E+06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-83 0.00E+00 0.00E+00 2.21E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-84 0.00E+00 0.00E+00 3.75E-24 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 5.28E+08 2.48E+08 0.00E+00 0.00E+00 0.00E+00 7.81E+07 0.00E+00 SR-89 4.78E+09 0.00E+00 1.37E+08 0.00E+00 0.00E+00 0.00E+00 5.69E+08 0.00E+00 SR-90 1.15E+11 0.00E+00 2.85E+10 0.00E+00 0.00E+00 0.00E+00 3.24E+09 0.00E+00 SR-91 1.12E+05 0.00E+00 4.46E+03 0.00E+00 0.00E+00 0.00E+00 5.08E+05 0.00E+00 I

SR-92 1.90E+00 0.00E+00 8.12E-02 0.00E+00 0.00E+00 0.00E+00 4.85E+01 0.00E+00 Y 91M 1.38E-20 0.00E+00 5.26E-22 0.00E+00 0.00E+00 0.00E+00 6.50E-19 0.00E+00 Y-91 1.59E+03 0.00E+00 4.28E+01 0.00E+00 0.00E+00 0.00E+00 6.54E+05 0.00E+00 Y-92 1.25E-05 0.00E+00 3.62E-07 0.00E+00 0.00E+00 0.00E+00 3.43E-01 0.00E+00 I

I Y-93 4.96E-02 0.00E+00 1.36E-03 0.00E+00 0.00E+00 0.00E+00 1.52E+03 0.00E+00 ZR-95 1.66E+02 5.22F+01 3.59E+01 0.00E+00 7.68E+01 0.00E+00 1.21E+05 0.00E+00 ZR-97 9.48E-02 1.88E-02 8.64E-03 0.00E+00 2.84E-02 0.00E+00 5.08E+03 0.00E+00 NB-95 1.48E+04 8.20E+03 4.52E+03 0.00E+00 7.95E+03 0.00E+00 3.51E+07 0.00E+00 NB 97 7.43E-13 1.84E-13 6.73E-14 0.00E+00 2.16E-13 0.00E+00 4.40E-09 0.00E+00 MD-99 0.00E+00 5.38E+06 1.03E+06 0.00E+00 1.23E+07 0.00E+00 9.63E+06 0.00E+00 2R Values in units of mres/yr per m1.cro-Ci/m for inhalation and tritium, 3

and in units of m mrea/yr per micro-Ci/sec. for all others.

8 l

HBRODCM 3-59 Rev. 9

1 United States Nuclear Regulatory Commizzion to Serial: RNP-RA/95-0159 TAsir. 3.3-13 (czneinu:d)

Page 95 of 172 Buclido lont Liver Wy Thyroid Kidney Lung GI-Tract Skin TC-99M 6.98E-01 1.95E+00 2.52E+01 0.00E+00 2.90E+01 1.08E+00 1.28E+03 0.00E+00 RU-103 1.89E+02 0.00E+00 8.07E+01 0.00E+00 6.66E+02 0.00E+00 1.58E+04 0.00E+00 RU-105 1.90E-04 0.00E+00 7.36E-05 0.00E+00 2.39E-03 0.00E+00 1.53E-01 0.00E+00 RU-106 3.63E+03 0.00E+00 4.57E+02 0.00E+00 7.00E+03 0.00E+00 1.74E+05 0.00E+00 AG-110M 9.62E+06 9.10E+06 5.54E+06 0.00E+00 1.74E+07 0.00E+00 2.56E+09 0.00E+00 SN 113 7.14E+05 2.99E+04 7.59E+05 9.88E+03 2.12E+04 0.00E+00 8.57E+06 0.00E+00 SB-124 4.63E+06 8.53E+04 1.81E+06 1.05E+04 0.00E+00 4.04E+06 9.33E+07 0.00E+00 SB-125 3.46E+06 3.78E+04 8.10E+05 3.31E+03 0.00E+00 3.04E+06 2.69E+07 0.00E+00 TE-129M 1.25E+07 4.62E+06 1.97E+06 4.02E+06 5.21E+07 0.00E+00 4.68E+07 0.00E+00 TE-129 6.57E-11 2.45E-11 1.60E-11 4.69E-11 2.76E-10 0.00E+00 3.59E-10 0.00E+00 TE-131M 8.06E+04 3.86E+04 3.22E+04 5.81E+04 4.03E+05 0.00E+00 3.10E+06 0.00E+00 TE-132 5.27E+05 3.34E+05 3.14E+05 3.52E+05 3.20E+06 0.00E+00 1.06E+07 0.00E+00 I-131 6.34E+08 8.87E+08 4.76E+08 2.59E+11 1.53E+09 0.00E+00 1.75E+08 0.00E+00 I-132 3.55E-01 9.30E-01 3.34E-01 3.13E+01 1.47E+00 0.00E+00 4.05E-01 0.00E+00 I-133 8.50E+06 1.44E+07 4.40E+06 2.01E+09 2.53E+07 0.00E+00 1.09E+07 0.00E+00 I-134 4.49E-12 1.19E-11 4.28E-12 1.99E-10 1.88E-11 0.00E+00 1.57E-13 0.00E+00 1-135 2.75E+04 7.09E+04 2.63E+04 4.56E+06 1.12E+05 0.00E+00 7.85E+04 0.00E+00 CS-134 2.32E+10 5.46E+10 2.53E+10 0.00E+00 1.73E+10 6.62E+09 6.79E+08 0.00E+00 CS-136 1.28E+09 5.05E+09 3.39E+09 0.00E+00 2.75E+09 4.33E+08 4.06E+08 0.00E+00 CS-137 3.24E+10 4.31E+10 1.50E+10 0.00E+00 1.47E+10 5.70E+09 6.14E+08 0.00E+00 CS-138 5.29E-23 1.02E-22 5.08E-23 0.00E+00 7.50E-23 8.72E-24 4.61E-26 0.00E+00 BA-139 1.01E-08 7.09E-12 2.94E-10 0.00E+00 6.69E-12 4.89E-12 8.99E-08 0.00E+00 BA-140 5.56E+06 6.82E+03 3.58E+05 0.00E+00 2.31E+03 4.58E+03 8.58E+06 0.00E+00 LA-140 9.73E-01 4.78E-01 1.27E-01 0.00E+00 0.00E+00 0.00E+00 2.75E+04 0.00E+00 1A-142 4.12E-12 1.83E-12 4.56E-13 0.00E+00 0.00E+00 0.00E+00 5.57E-08 0.00E+00 CE-141 9.39E+02 6.27E+02 7.20E+01 0.00E+00 2.95E+02 0.00E+00 1.79E+06 0.00E+00 CE-143 9.18E+00 6.68E+03 7.46E-01 0.00E+00 3.00E+00 0.00E+00 2.01E+05 0.00E+00 CE-144 6.24E+04 2.58E+04 3.35E+03 0.00E+00 1.54E+04 0.00E+00 1.57E+07 0.00E+00 HF-181 1.82E+03 9.98E+00 2.03E+02 6.08E+00 8.29E+00 0.00E+00 9.08E+04 0.00E+00 W-187 1.43E+03 1.17E+03 4.09E+02 0.00E+00 0.00E+00 0.00E+00 3.16E+05 0.00E+00 NP-239 8.42E 01 7.94E-02 4.41E-02 0.00E+00 2.49E-01 0.00E+00 1.28E+04 0.00E+00 HBRODCM 3-60 Rev. 9

United States Nuclear Regulatory Comminnion G Serial: RNP-RA/95-0159 gigtg 3,3 14 1

R VALUES for the H.B. ROBINSON STEAM ELECTRIC PLANT (Reference Regulatory Guide 1.109)

PATHWAY ' coat Milk l

AGE CROUP - Child-

]lggl{ds.

1g33 Liver T. Body Thyroid Kidney Lgng CI-Tract g]k.in H-3 0.00E+00 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 F-18 2.33E-03 0.00E+00 2.31E-04 0.00E+00 0.00E+00 0.00E+00 6.30E-04 0.00E+00 NA-24 1.07Et06 l'.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 0.00E+00 C2-51 0.00E+00 0.00E+00 1.09E+04 6.05E+03 1.65E+03 1.11E+04 5.79E+05 0.00E+00 MN 54 0.00E+00 -2.01E+06 5.35E+05 0.00E+00 5.63E+05 0.00E+00 1.69E+06 0.00E+00 MN-56' O.00E+00 1.56E-03 3.53E 04 0.00E+00 1.89E-03 0.00E+00 2.26E-01 -0.00E+00 FE-55 1.13E+06 6.00E+05 1.86E+05 0.00E+00 0.00E+00 3.40E+05 1.11E+05 0.00E+00

-FE-59 1.34E+06 2.17E+06 1.08E+06 0.00E+00 0.00E+00 6.29E+05 2.26E+06 0.00E+00 Co 57 0.00E+00 3.65E+05 7.39E+05 0.00E+00 0.00E+00 0.00E+00 2.99E+06 0.00E+00

~Co-58 0.00E+00 1.21E+06 3.71E+06 0.00E+00 0.00E+00 0.00EF00 7.06E+06 0.00E+00 CO-60 0.00E+00 4.11E+06 1.21E+07 0.00E+00 0.00E+00 0.00E+00 2.27E+07 0.00E+00 NI-65 2.02E-01 1.90E-02 1.11E 02 0.00E+00 0.00E+00 0.00E+00 2.33E+00 0.00E+00

'CU-64 0.00E+00 8.35E+03 5.05E+03 0.00E+00 2.02E+04 0.00E+00 3.92E+05 0.00E+00 ZN-65 4.46E+08 1.19E+09 7.40E+08 0.00E+00 7.49E+08 0.00E+00 2.09E+08 0.00E+00 BR-82 0.00E+00 0.00E+00 1.40E+07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-83 0.00E+00 0.00E+00 5.42E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-84 0.00E+00 0.00E+00 8.49E-24 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 9.79E+08 6.02E+08 0.00E+00 0.00E+00 0.00E+00 6.30E+07 0.00E+00 SR-89 1.18E+10 0.00E+00 3.38E+08 0.00E+00 0.00E+00 0.00E+00 4.58E+08 0.00E+00 SR-90 1.95E+11 0.00E+00 4.94E+10 0.00E+00 0.00E+00 0.00E+00 2.62E+09 0.00E+00 SR-91 2.75E+05 0.00E+00 1.04E+04 0.00E+00 0.00E+00 0.00E+00 6.07E+05 0.00E+00 SR-92 4.65E+00 0.00E+00 1.86E-01 0.00E+00 0.00E+00 0.00E+00 8.81E+01 0.00E+00 Y-91M 3.36E-20 0.00E+00 1.22E-21 0.00E+00 0.00E+00 0.00E+00 6.59E-17 0.00E,00 Y-91 3.94E+03 0.00E+00 1.05E+02 0.00E+00 0.00E+00 0.00E+00 5.25E+05 0.00E+00 Y-92 3.07E-05 0.00E+00 8.78E-07 0.00E+00 0.00E+00 0.00E+00 8.87E-01 0.00E+00 Y-93 1.22E-01' O.00E+00 3.35E-03 0.00E+00 0.00E+00 0.00E+00 1.82E+03 0.00E+00 ZR-95 3,85E+02 8.45E+01 7.53E+01 0.00E+00 1.21E+02 0.00E+00 8.82E+04 0.00E+00 ZR-97 2.31E 01 3.33E-02 1.97E-02 0.00E+00 4.79E-02 0.00E+00 5.05E+03 0.00E+00 NB-95 3.34E+04 1.30E+04 9.29E+03 0.00E+00 1.22E+04 0.00E+00 2.40E+07 0.00E+00

)

NB-97 1.80E-12 3.26E-13 1.52E-13 0.00E+00 3.62E-13 0.00E+00 1.01E-07 0.00E+00 MO-99 0.00E+00 9.79E+06 2.42E+06 0.00E+00 2.09E+07 0.00E+00 8.10E+06 0.00E+00 l

3 1R Values in units of area /yr per micro-Ci/m for inhalation and tritium, and in units of*ma area /yr per micro-Ci/see for.all others.

HBRODCM 3-61 Rev. 9

United States Nuclear Regulatory Commintion

~ Enclosure 2 to Serial: RNP-RA/95-0159 TAsts 3.3-14 (centinu.d)

Pase 97 of 172 Nuclide Agns.

Liver T. Body IbTr_g.14 Kidney Lung GI-Tract S]_in ki TC 99M 1.60E+00 3.14E+00 5.20E+01 0.00E+00 4.56E+01 1.59E+00 1.79E+03 0.00E+00 RU 103 4.47E+02 0.00E+00 1.72E+02 0.00E+00 1.12E+03 0.00E+00 1.15E+04 0.00E+00 RU-105 4,63E-04 0.00E+00 1.68E 04 0.00E+00 4.07E-03 0.00E+00 3.02E-01 0.00E+00 RU-106 8.93E+03 0.00E+00 1.11E+03 0.00E+00 1.21E+04 0.00E+00 1.39E+05 0.00E+00 AG-110M 2.09E+07 1.41E+07 1.13E+07 0.00E+00 2.62E+07 0.00E+00 1.68E+09 0.00E+00 SN-113 1.40E+06 4.52E+04 1.53E+06 1.85E+04 3.10E+04 0.00E+00 5.61E+06 0.00E+00 SB-124 1.10E+07 1.42E+05 3.84E+06 2.42E+04 0.00E+00 6.08E+06 6.85E+07 0.00E+00 SB-123 8.25E+06 6.36E+04 1.73E+06 7.64E+03 0.00E+00 4.60E+06 1.97E+07 0.00E+00 TE-129M 3.07E+07 8.57E+06 4.76E+06 9.90E+06 9.01E+07 0.00E+00 3.74E+07 0.00E+00 TE-129 1.62E-10 4.53E-11 3.85E-11 1.16E-10 4.74E-10 0.00E+00 1.01E-08 0.00E+00 TE-131M 1.96E+05 6.78E+04 7.22E+04 1.39E+05 6.57E+05 0.00E+00 2.75E+06 0.00E+00 TE 132 1.26E+06 5.57E+05 6.73E+05 8.11E+05 5.17E+06 0.00E+00 5.61E+06 0.00E+00 1-131 1.54E+09 1.55E+09 8.78E+08 5.11E+11 2.54E+09 0.00E+00 1.38E+08 0.00E+00 1-132 8.41E-01 1.55E+00 7.11E-01 7.17E+01 2.36E+00 0.00E+00 1.82E+00 0.00E+00 I-133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 0.00E+00 1.03E+07 0.00E+00 1 134 1.06E 11 1.98E-11 9.09E-12 4.54E-10 3.02E-11 0.00E+00 1.31E-11 0.00E+00 I-135 6.52E+04 1.17E+05 5.55E+04 1.04E+07 1.80E+05 0.00E+00 8.94E+04 0.00E+00 4

CS-134 5.35E+10 8.78E+10 1.85E+10 0.00E+00 2.72E+10 9.76E+09 4.73E+08 0.00E+00 CS-136 2.89E+09 7.96F+09 5.15E+09 0.00E+00 4.24E+09 6.32E+08 2.80E+08 0.00E+00 CS-137 7.81E+10 7.48E+10 1.10E+10 0.00E+00 2.44E+10 8.77E+09 4.68E+08 0.00E+00 CS 138 1.28E-22 1.78E-22 1.13E-22 0.00E+00 1.25E-22 1.35E-23 8.21E-23 0.00E+00 BA-130 2.48E-08 1.32E-11 7.18E-10 0.00E+00 1.15E-11 7.78E-12 1.43E-06 0.00E+00 BA-140 1.34E+07 1.18E+04 7.84E+05 0.00E+00 3.83E+03 7.01E+03 6.80E+06 0.00E+00 LA-140 2.33E+00 8.14E-01 2.7?E-01 0.00E+00 0.00E+00 0.00E+00 2.27E+04 0.00E+00 LA-142 9.95E-12 3.17E-12 9.94E-13 0.00E+00 0.00E+00 0.00E+00 6.29E-07 0.00E+00 CE-141 2.31E+03 1.15E+03 1.71E+02 0.00E+00 5.05E+02 0.00E+00 1.44E+06 0.00E+00 CE-143 2.25E+01 1.22E+04 1.77E+00 0.00E+00 5.12E+00 0.00E+00 1.79E+05 0.00E+00 i

CE 144 1.54E+05 4.82E+04 8.21E+03 0.00E+00 2.67E&O4 0.00E+00 1.26E+07 0.00E+00 HF-181 4.30E+03 1.68E+01 4.33E+02 1.42E+01 1.35E+01 0.00E+00 7.15E+04 0.00E+00 W 187 3.47E+03 2.05E+03 9.22E+02 0.00E+00 0.00E+00 0.00E+00 2.89E+05 0.00E+00 l

NP-239 2.07E+00 1.49E-01 1.05E-01 0.00E+00 4.30E-01 0.00E+00 1.10E+04 0.00E+00 1

HBRODCM 3-62 Rev. 9

United States Nuclear Regulatory Comminaian

. Enclosure 2 to Serial: RNP-RA/95-0159 TABLE 3.3-15

! Page 98 L of 172 R VAIsEs for the E.B. ROBINSON STEAM EII.CTRIC FIANT 1

(Reforence Regulatory Guide ~1.109) i

. PATHWAY - Coat Milk AGE GROUP - Infant 1

1.

Ituclide Agat MIRE T. Body Thyroid Kidney Lung GI-Tract Rhin 1

1 H-3 0.00E+00-

4. 86E+03 - ~ 4. 86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03

~

F 4'85E-03 0.00E+00 4.14E-04 0.00E+00 0.00E+00 0.00E&OO 1.14E-03 0.00E+00 L

NA-24 1.86E+06 1.86E+06-1.86E+06 1.86E+06 1.86E+06 1.86E+06 1.86E+06.0.00E+00 CR-51

'O.00E+00 0.00E+00 1.73E+04 1.13E+04 2.46E+03 2.19E+04 5.04E+05 '0.00E+00

.- MN 0.00E+00 3.73E+06 8.46E+05 0.00E+00 8.28E+05 0.00E+00 1.37E+06 0.00E+00 MN 56-0.00E+00 3.83E 6.60E-04 0.00E+00 3.29E-03 0.00E+00 3.48E-01 0.00E+00 FE 55

'1.37E+06 8.84:305 2.36E+05 0.00E+00 0.00E+00 4.32E+05 1.12E+05 0.00E+00 i

FE-59 2.50E+06 4.37E+06.

1.72E+06 0.00E+00 0.00E+00 1.29E+06 2.09E+06 0.00E+00 C0 57 0.00E+00' 8.52E+05 1.39E+06 0.00E+00 0.00E+00 0.00E+00 2.90E+06 0.00E+00 J

CO-58' O.00E+00 2.42E+06 6.04E+06 0.00E+00 0.00E+00 0.00E+00 6.03E+06 0.00E+00 4

CO 60-0.00E+00 8.38E+06 1.98E+07 0.00E+00 0.00E+00 0.00E+00 1.99E+07 0.00E+00

'NI-65 4.27E-01 4.84E-02 2.20002 0.00E+00 0.00E+00 0.00E+00 3.68E+00 0.00E+00 CU-64 0.00E+00 2.08E+04 9.62E+03 0.00E+00 3.51E+04 0.00E+00 4.26E+05 0.00E+00 ZN-65 5.99E+08' 2.06E+09 9.48E+08 0.00E+00 9.97E+08- 0.00E+00 1.74E+09 0.00E+00 BR-82 0.00E+00 0.00E+00 2.35E+07 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 BR 0.00E+00 0.00E+00 1.15E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

'BR-84 0.00E+00 0.00E+00 1.64E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i

RB-86 0.00E+00 2.48E+09 1.23E+09 0.00E+00 0.00E+00 0.00E+00 6.36E+07 0.00E+00 SR-89 2.25E+10 0.00E+00 6.45E+08 0.00E+00 0.00E+00 0.00E+00 4.62E+08' O.00E+00

[

SR 90 2.12E+11 0.00E+00 5.40E+10 0.00E+00 0.00E+00 0.00E+00 2.65E+09 0.00E+00

.SR-91 5.73E+05 0.00E+00 2.07E+04 0.00E+00 0.00E+00 0.00E+00 6.78E+05 0.00E+00 SR-92 9.89E+00 0.00E+00 3.67E-01 0.00E+00 0.00E+00 0.00E+00 1.07E+02 0,00E+00 Y-91M 7.13E-20 0.00E+00 2.43E-21 0.00E+00 0.00E+00 0.00E+00 2.38E 16 0.00E+00 l

Y-91' 7.40E+03 0.00E+00 1.97E+02 0.00E+00 0.00E+00 0.00E+00 5.30E+05 0.00E+00 Y-92 6.52E-05 0.00E+00 1.83E-06 0.00E+00 0.00E+00 0.00E+00 1.24E+00 0.00E+00 Y-93 2.60E.01 0.00E+00 7.08E 03 0.00E+00 0.00E+00 0.00E+00 2.05E+03 0.00E+00

)

ZR-95 6.83E+02 1.66E+02 1.18E+02 0.00E+00 1.79E+02 0.00E+00 8.29E+04 0.00E+00 l

ZR-97 4.89E-01 8.38E-02 3.83E-02 0,00E+00 8.45E-02 0.00E+00 5.35E+03 0.00E+00 f

NB 95 6.23E+04 2.57E+04 1.48E+04 ~ 0.00E+00 1.84E+04 0.00E+00 2.17E+07 0.00E+00 NS-97 3.82E 12 8.14E-13 2.93E-13 0.00E+00 -6.36E-13 0.00E+00 2.57E-07 0.00E+00 MO-99 0.00E+00 2.50E+07 4.88E+06 0.00E+00 3.74E+07 0.00E+00 8.24E+06 0.00E+00 i

1 1

3 1R Values in units'of ares /yr per micro-Ci/m for inhalation and tritium, and in units of na aren/yr per micro-Ci/sec for all others.

HERODCM 3-63

'Rev. 9-l

d United States Nuclear Regulatory Comnussion

Enclosure 2 to Serial: RNP-RA/95-0159 TABLE 3.3-15.(continusd)

Page 99 of 172 Nuclide A2B1 Liver T. Body Thyroid Kidney LEDg GI-Tract Shin TC-99M.

3.33E+00 6.87E+00 8.85E+01 0.00E+00 7.39E+01 3.59E+00 2.00E+03 0.00E+00 RU-103 9.04E+02 0.00E+00 3.02E+02 0.00E+00 1.88E+03 0.00E+00 1.10E+04 0.00E+00 RU-105 9.76E 04 0.00 +00 3.29E-04 0.00E+00 7.17E-03 0.00E+00 3.88E-01 0.00E+00 RU-106 1.84E+04 0.00E+00 2.30E+03 0.00E+00 2.18E+04 0.00E+00 1.40E+05 0.00E+00 AC-110M 3.86E+07 2.81E+07 1.86E+07 0.00E+00 4.03E+07 0.00E+00 1.46E+09 0.00E+00 i

SN-113 2.13E+06 8.15E+04 2.20E+06 3.10E+04 4.37E+04 0.00E+00 4.55E+06 0.00E+00 S5-124 2.11E+07 3.11E+05 6.54E+06 5.61E+04 0.00E+00 1.32E+07 6.52E+07 0.00E+00 SB 125 1.42E+07 1.37E+05 2.91E+06 1.77E+04 0.00E+00 8.20E+06 1.89E+07 0.00E+00 TE-129M 6.30E+07 2.16E+07 9.71E+06 2.42E+07 1.58E+08 0.00E+00 3.76E+07 0.00Et00 TE-129 3.44E-10 1.18E 10 8.02E-11 2.88E-10 8.56E-10 0.00E+00 2.75E-08 0.00E+00 TE-131M 4.14E+05 1.67E+05 1.38E+05 3.38E+05 1.15E+06 0.00E+00 2.81E+06 0.00E+00 TE-132 2.59E+06 1.28E+06 1.20E+06 1.89E+06 8.02E+06 0.00E+00 4.75E+06 0.00E+00 I-131 3.21E+09 3.78E+09 1.66E+09 1.24E+12 4.41E+09 0.00E+00 1.35E+08 0.00E+00 I-132 1.74E+00 3.54E+00 1.26E+00 1.66E+02 3.95E+00 0.00E+00 2.87E+00 0.00E+00 2

I-133 4.36E+07 6.35E+07 1.86E+07 1.15E+10 7.46E+07 0.00E+00 1.07E+07 0.00E+00 I-134 2.21E-11 4.52E-11 1.61E-11 1.05E-09 5.05E-11 0.00E+00 4.67E-11 0.00E+00 I-135 1.36E+05 2.70E+05 9.83E+04 2.42E+07 3.00E+05 0.00E+00 9.76E+04 0.00E+00 CS-134 8.62E+10 1.61E+11 1.62E+10 0.00E+00 4.14E+10 1.70E+10 4.37E+08 0.00E+00 CS 136 5.65E+09 1.66E+10 6.21E+09 0.00E+00 6.63E+09 1.35E+09 2.52E+08 0.00E+00 CS-137 1.25E+11 1.46E+11 1.03E+10 0.00E+00 3.92E+10 1.59E+10 4.56E+08 0.00E+00 CS-138 2.70E-22 4.40E-22 2.13E-22 0.00E+00 2.19E-22 3.42E-23 7.03E-22 0.00E+00 BA-139 5.27E 08 3.49E-11 1.53E-09 0.00E+00 2.10E-11 2.12E-11 3.34E-06 0.00E+00 BA-140 2.76E+07 2.76E+04 1.42E+06 0.00E+00 6.56E+03 1.70E+04 6.79E+06 0.00E+00 1A-140 4.87E+00 1.92E+00 4.94E-01 0.00E+00 0.00E+00 0.00E+00 2.25E+04 0.00E+00 LA-142 2.09E-11 7.68E-12 1.84E-12 0.00E+00 0.00E+00 0.00E+00 1.30E-06 0.00E+00 CE-141 4.58E+03 2.80E+03 3.29E+02 0.00E+00 8.62E+02 0.00E+00 1.44E+06 0.00E+00 CE 143 4.77E+01 3.16E+04 3.61E+00 0.00E+00 9.21E+00 0.00E+00 1.85E+05 0.00E+00 CE-144 2.21E+05 9.03E+04 1.24E+04 0.00E+00 3.65E+04 0.00E+00 1.27E+07 0.00E+00 HF-181 8.23E+03 3.87E+01 7.27E+02 3.28E+01 2.27E+01 0.00E+00 6.75E+04 0.00E+00 W-187 7.30E+03 5.08E+03 1.75E+03 0.00E+00 0.00E+00 0.00E+00 2.98E+05 0.00E+00 NP-239 4.38E+00 3.92E-01 2.21E-01 0.00E+00 7.81E-01 0.00E+00 1.13E+04 0.00E+00 HERODCM 3-64 Rev. 9

. United States Nuclear Regulatory Commianian to Serial: RNP-RA/95-0159

. TABU 3. 3 Pass 100 of 172 R VALUES for the E.B.' ROBINSON STEAM ELECTRIC PLANT 1 (Reference Regulatory Guide 1.109)

PATHWAY - Inhalation

~ AGE GROUP - Adult Huclids Ign1 Liver T. Body Thyroid Kidney Lung GI-Trace flin H-3 0.00E+00' 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 F-18 4.99E+03 0.00E+00

.5.54E+02 0.00E+00 0.00E+00 0.00E+00 1.48E+02 0.00E+00

.NA-24 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 0.00E+00

'CRoS1 0.00E+00 0.00E+00 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 0.00E+00 MN-54' O 00E+00 3.96E+04 6.30E+03 0.00E+00 9.84E+03 1.40E+06 7.74E+04 0.00E+00 MN-56 0.00E+00 1.24E+00 1.83E-01 0.00E+00 1.30E+00 9.443+03 2.02E+04 0.00E+00 FE-55 2.46E+04 1.70Ev04 3.94E+03 0.00E+00 0.00E+00 7.21E+04 6.03E+03 0.00E+00 FE 1.18E+04.2.78E+04 1.06E+04 0.00E+00 0.00E+00 1.02E+06 1.88E+05 0.00E+00 CO-57 0.00E+00 6.92E+02 6.71E+02 0.00E+00 0.00E+00 3.70E+05 3.14E+04 0.00E+00 4

CO 58.

0.00E+00 1.58E+03 2.07E+03 0.00E+00 0.00E+00 9.28E+05 1.06E+05 0.00E+00 CO 0.00E+00 1.15E+04 1.48E+04 0.00E400 0.00E+00 5.97E+06 2.85E+05 0.00E+00 NIe65 1.54E+00 2.10E 01 9.12E-02 0.00E+00 0.00E+00 5.60E+03 1.23E+04 0.00E+00 CU-64 0.00E+00 1.46E+00 6.15E-01 0.00E+00 4.62E+00 6.78E+03 4.90E+04 0.00E+00 ZN-65 3.24E+04 1.03E+05 4.66E+04 0.00E+00 6.90E+04 8.64E+05 5.34E+04 0.00E+00 BR-82 0.00E+00 0.00E+00 '1.35E+04 0.00E+00 0.00E+00 0.00E+00 1.04E+04 0.00E+00 BR-83 0.00E+00 0.00E+00 2.41E+02 0.00E+00 0.00E+00 0.00E+00 2.32E+02 0.00E+00 BR-84 0.00E+00- 0.00E+00 3.13E+02 0.00E+00 0.00E+00 0.00E+00 1.64E-03 0.00E+00 RB 86 0.00E+00 1.35E+05 5.90E+04 0.00E+00 0.00E+00 0.00E+00 1.66E+04 0.00E+00 RB 0.00E+00 3.87E+02 1.93E+02 0.00E+00 0.00E+00 0.00E+00 3.34E-09 0.00E+00 RB-89 0.00E+00 2.56E+02 1.70E+02 0.00E+00 0.00E+00 0.00E+00 9.28E-12 0.00E+00 SR 89

.3,04E+05 0.00E+00 8.72E+03 0.00E+00 0.00E+00 1.40E+06 3.50E+05 0.00E+00 SR-90

'9.92E+07 0.00E+00 6.10E+06 0.00E+00 0.00E+00 9.60E+06 7.22E+05 0.00E+00 SR-91 6.19E+01 0.00E+00 2.50E+00 0.00E+00 0.00E+00 3.65E+04 1.91Po 0.00E+00 SR-92 6.74E+00 0.00E+00 2.91E-01 0.00E+00 0.00E+00 1.65E+04 4.30Wt.

0.00E+00 Y-91M 2.61E-01 0.00E+00 1.02E-02 0.00E+00 0.00E+00 1.92E+03 1.33E,ru0 0.00E+00 i

Y 91 4.62E+05 0.00h.+00 1.24E+04 0.00E+00 0.00E+00 1.70E+06 3.85E+05 0.00E+00 Y-92 1.03E+01 0.00E+00 3.02E-01 0.00E+00 0.00E+00 1.57E+04 7.35E+04 0.00E+00 t.

Y-93 9.44E+01 0.00E+00 2.61E+00 0.00E+00 0.00E+00 4.85E+04 4.22E+05 0.00E+00 ZR-95 1.07E+05 3.44E+04 2.33E+04 0.00E+00 5.42E+04 1.77E+06 1.50E+05 0.00E+00 ZR-97 9.68E+01 1.96E+01 9.04E+00 0.00E+00 2.97E+01 7.87E+04 5.23E+05 0.00E+00 NB-95 1.41E+04 7.82E+03 4.21E+03 0.00E+00 7.74E+03 5.05E+05 1.04E+05 0.00E+00 l

8 for inhalation and tritium, 1R Values in' units of ares /yr per micro-Ci/m area /yr_per micro-Ci/sec for all others.

l and in units of'm2 HBRODCM 3 65 Rev. 9

]

United States Nuclear Regulatory Commission

, to Serial: RNP-RA/95-0159 TABLE 3.3-16 (continusd)

Page 101 of 172 Nuclide jgng Liver T. Body Thyroid Kidney 1,gg GI-Tract Skin NB 97 2.22E-01 5.62E-02 2.05E-02 0.00E+00 6.54E 02 2.40E+03 2.42E+02 0.00E+00 MO-99 0.00E+00 1.21d+02 2.30E+01 0.00E+00 2.91E+02 9.12E+04 2.48E+05 0.00E+00 TC-99M 1.03E-03 2.91E-03 3.70E 02 0.00E+00 4.42E-02 7.64E+02 4.16E+03 0.00E+00 TC-101 4.18E 05 6.02E-05 5.90E-04 0.00E+00 1.08E-03 3.99E+02 1.09E-11 0.00E+00 RU-103 1.53E+03 0.00E+00 6.58E+02 0.00E+00 5.83E+03 5.05E405 1.10E+05 0.00E+00 RU-105 7.90E 01 0.00E+00 3.11E 01 0.00E+00 1.02E+00 1.10E+04 4.82E+04 0.00E+00 RU-106 6.91E+04 0.00E+00 8.72E+03 0.00E+00 1.34E+05 9.36E+06 9.12E+05 0.00E+00 AG-110M 1.08E+04 1.00E+04 5.94E+03 0.00E+00 1.97E+04 4.63E+06 3.02E+05 0.00E+00 SN-113 6.86E+03 2.66E+02 6.48E+03 9.28E+01 1.97E+02 2.99E+05 2.48E+04 0.00E+00 SB-124 3.12E+04 5.89E+02 1.24E+04 7.55E+01 0.00E+00 2.48E+06 4.06E+05 0.00E+00 SB-125 5.34E+04 5.95E+02 1.26E+04 5.40E+01 0.00E+00 1.74E+06 1.01E+05 0.00E+00 TE-129M 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 0.00E+00 TE-129 4.98E-02 2.39E-02 1.24E-02 3.90E-02 1.87E-01 1.94E+03 1.57E+02 0.00E+00 TE-131H 6.99E+01 4.36E+01 2.90E+01 5.50E+01 3.09E+02 1.46E+05 5.56E+05 0.00E+00 TE-132 2.60E+02 2.15E+02 1.62E+02 1.90E+02 1.46E+03 2.88E+05 5.10E+05 0.00E+00 I-131 2.52F+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 0.00E+00 6.28E+03 0.00E+00 I-132 1.16E+03 3.26E+03 1.16E+03 1.14E+05 5.18E+03 0.00E+00 4.06E+02 0.00E+00 I-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 0.00E+00 8.88E+03 0.00E+00 1 134 6.44E+02 1.73E+03 6.15E+02 2.98E+04 2.75E+03 0.00E+00 1.01E+00 0.00E+00 I-135 2.68E+03 6.985+03 2.57E+03 4.48E+05 1.11E+04 0.00E+00 5.25E+03 0.00E+00 CS-134 3.73E+05 8.48E+05 7.28E+05 0.00E+00 2.87E+05 9.76E+04 1.04E+04 0.00E+00 CS-136 3.90E+04 1.46E+05 1.10E+05 0.00E+00 8.56E+04 1.20E+04 1.17E+04 0.00E+00 CS-137 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03 0.00E+00 CS-138 3.31E+02 6.21E+02 3.24E+02 0.00E+00 4.80E+02 4.86E+01 1.86E-03 0.00E+00 BA-139 9.36E-01 6.66E-04 2.74E-02 0.00E+00 6.22E-04 3.76E+03 8.96E+02 0.00E+00 BA-140 3.90E+04 4.90E+01 2.57E+03 0.00E+00 1.67E+01 1.27E+06 2.18E+05 0.00E+00 BA-142 2.63E-02 2.70E-05 1.66E-03 0.00E+00 2.29E-05 1.19E+03 1.57E 16 0.00E+00 LA-140 3.44E+02 1.74E+02 4.58E+01 0.00E+00 0.00E+00 1.36E+05 4.58E+05 0.00E+00 LA-142 6.83E-01 3.10E-01 7.72E-02 0.00E+00 0.00E+00 6.33E+03 2.11E+03 0.00E+00 CE-141 1.99E+04 1.35E+04 1.53E+03 0.00E+00 6.26E+03 3.62E+05 1.20E+05 0.00E+00 CE-143 1.86E+02 1.38E+02 1.53E+01 0.00E+00 6.08E+01 7.98E+04 2.26E+05 0.00E+00 CE-144 3.43E+06 1.43E+06 1.84E+05 0.00E+00 8.48E+05 7.78E+06 8.16E+05 0.00E+00 PR-144 3.01E-02 1.25E-02 1.53E-03 0.00E+00 7.05E-03 1.02E+03 2.15E-08 0.00E+00 HF-181 4.56E+04 2.57E+02 5.15E+03 1.63E+03 2.14E+02 5.98E+05 1.29E+05 0.00E+00 W-187 8.48E+00 7.08E+00 2.48E+00 0.00E+00 0.00E+00 2.90E+04 1.55E+05 0.00E+00 NP-239 2.30E+02 2.26E+01 1.24E+01 0.00E+00 7.00E+01 3.76E+04 1.19E+05 0.00E+00 HBRODCM 3-66 Rev. 9

United States Nuclear Regulatory Comminaion O Serial: RNP-RA/95-0159 TABLE 3.3 17 Page.102 of 172 R VAIUES for the H.B. ROBINSON STEAM ELECTRIC PLANT 1 (Reference Regulatory Guide 1.109)

PATHWAY.- Inhalation-

)

ACE GROUP - Teen Nuclide 12B1 Li m T. Body Thyroid Kidney LMDR

.G.l.-Tp e t 1)du H-3 0.00E+00 1.27E+03 1.27E+03 1.27E+03-1.27E+03 1.27E+03 1.27E+03 1.27E+03 F-18 5.22E+03- 0.00E+00 5.68E+02 0.00E+00 0.00E+00 0.00E+00 3.11E+02 0.00E+00 NA-24 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 0.00E+00 CR-51 0.00E+00 0.00E+00 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03 0.00E+00 MN-54 0.00E+00 5.11E+04 8.40E+03 0.00E+00 1.27E+04 1.98E+06 6.68E+04 0.00E+00 NN-56 0.00E+00 1.703+00 2.52E-01 0.00E+00 1.79E+00 1.52E+04 5.74E+04 0.00E+00 FE 55 3.34E+04 '2.38E+04 5.54E+03 0.00E+00 0.00E+00 1.24E+05 6.39E+03 0.00E+00 l

FE 59

.1.59E+04 3.70E+04 1.43E+04 0.00E+00 0.00E+00 1.53E+06 1.78E+05 0.00E+00 CO-57 0.00E+00 9.44E+02 9.20E+02 0.00E+00 0.00E+00 5.86E+05 3.14E+04 0.00E+00 CO-58' O 00E+00 2.07E+03 2.78E+03 0.00E+00 0.00E+00 1.34E+06 9.52E+04 0.00E+00 CO-60 0.00E+00 1.51E+04 1.98E+04 0.00E+00 0.00E+00 8.72E+06 2.59E+05 0.00E+00 NI-65 2.18E+00 2.93E-01 1.27E-01 0.00E+00 0.00E+00 9.36E+03 3.67E+04 0.00E+00 CU-64 0.00E+00 2.03E+00 8.48E 01 0.00E+00 6.41E+00 1.11E+04 6.14E+04 0.00E+00 ZN-65 3.86E+04 1.34E+05 6.24E+04 0.00E+00 8.64E+04 1.24E+06 4.66E+04 0.00E+00 BR-82 0.00E+00 0.00E+00 1.82E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

~

BR-83 0.00E+00 0.00E+00 3.44E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-84 0.00E+00 0.00E+00 4.33E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 1.90E+05 8.40E+04 0.00E+00 0.00E+00 0.00E+00 1.77E+04 0.00E+00 RB-88 0.00E+00 5.46E+02 2.72E+02 0.00E+00 0.00E+00 0.00E+00 2.92E-05 0.00E+00 RB-89 0.00E+00 3.52E+02 2.33E+02 0.00E+00 0.00E+00 0.00E+00 3.38E-07 0.00E+00 SR-89 4.34E+05 0.00E+00 1.25E+04 0.00E+00 0.00E+00 2.42E+36 3.71E+05 0.00E+00 SR-90 1.08E+08 0.00E+00 6.68E+06 0.00E+00 0.00E+00 1.65E+07 7.65E+05 0.00E+00 SR 91 8.80E+01 0.00E+00 3.51E+00 0.00E+00 0.00E+00 6.07E+04 2.59E+05 0.00E+00 SR 92 9.52E+00 0.00E+00 4.06E-01 0.00E+00 0.00E+00 2.74E+04 1.19E+05 0.00E+00 Y-91M 3.70E-01 0.00E+00 1.42E-02 0.00E+00 0.00E+00 3.20E+0?

3.02E+01 0.00E+00 Y-91 6.61E+05 0.00E+00 1.77E+04 0.00E+00 0.00E+00 2.94E+06

4. 09 E+05-0.00E+00 Y-92 1.47E+01 0.00E+00 4.29E-01 0.00E+00 0.00E+00 2.68E+04 1.65E+05 0.00E+00 Y-93 1.35E+02 0.00E+00 3.72E+00 0.00E+00 0.00E+00 8.32E+04 5.79E+05 0.00E+00 ZR-95 1.46E+05 4.58E+04 3.15E+04 0.00E+00 6.74E+04 2.69E+06 1.49E+05 0.00E+00 ZR-97 1.38E+02 2.72E+01 1.26E+01 0.00E+00 4.12E+01 1.30E+05 6.30E+05 0.00E+00 NB 1.86E+04 1.03E+04 5.66E+03 0.00E+00 1.00E+04 7.51E+05 9.68E+04 0.00E+00 3

IR Values in units of area /yr per micro Ci/m for inhalation and tritium, cnd in units of ma ares /yr per micro-Ci/sec for all others.

HBRODCM 3-67 Rev. 9

1 United States Nuclear Regulatory Commission

' Enclosure 2 to Serial: RNP-RA/95-0159 TABI.E 3.3-17 (centinu2d)

Page 103 of 172 Nuclide Agit Liver T. Body Thyroid Kidney Lyng GI-Tract S,hig NB-97 3.'14E 01 7.78E-02 2.84E-02 0.00E+00 9.12E-02 3.93E+03 2.17E+03 0.00E+00 MO.99 0.00E+00 1.69E+02 3.22E+01 0.00E+00 4.11E+02 1.54E+05 2.69E+05 0.00E+00 TC-99M 1.38E-03 3.86E-03 4.99E-02 0.00E+00 5.76E-02 1.15E+03 6.13E+03 0.00E+00 TC-101 5.92E 05 8.40E-05 8.24E-04 0.00E+00 1.52E-03 6.67E+02 8.72E-07 0.00E+00

-RU-103 2.10E+03 0.00E+00 8.96E+02 0.00E+00 7.43E+03 7.83E+05 1.09E+05 0.00E+00 RU 105 1.12E+00 0.00E+00 4,34E-01 0.00E+00 1.41E+00 1.82E+04 9.04E+04 0.00E+00 4

RU-106 9.84E+04 0.00E+00 1.24E+04 0.00E+00 1.90E+05 1.61E+07 9.60E+05 0.00E+00 2

AG-110M 1.38E+04 1.31E+04 7.99E+03 0.00E+00 2.50E+04 6,75E+06 2.73E+05 0.00E+00 SN-113 8.16E+03 3.44E+02 8.64E+03 1.13E+02 2.46E+02 4.26E+05 2.03E+04 0.00E+00 SB-124 4.30E+04 7.94E+02 1.68E+04 9.76E+01 0.00E+00 3.85E+06 3.98E+05 0.00E+00 SB-125 7.38E+04 8.08E+02 1.72E+04 7.04E+01 0.00E+00 2.74E+06 9.92E+04 0.00E+00 TE-129M 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 0.00E+00 TE-129 7.10E-02 3.38E-02 1.76E 02 5.18E-02 2.66E-01 3.30E+03 1.62E+03 0.00E+00 i

TE-131M 9.84E+01 6.01E+01 4.02E+01 7.25E+01 4.39E+02 2.38E+05 6.21E+05 0.00E+00 TE-132 3.60E+02 2.90E+02 2.19E+02 2.46E+02 1.95E+03 4.49E+05 4.63E+05 0.00E+00 I-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 0.00E+00 6.49E+03 0.00E+00 I-132 1.59E+03 4.38E+03 1.58E+03 1.51E+05 6.92E+03 0.00E+00 1.27E+03 0.00E+00 I-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.00E+00 1.03E+04 0.00E+00 I-134 8.88E+02 2.32E+03 8.40E+02 3.95E+04 3.66E+03 0.00E+00 2.04E+01 0.00E+00 I-135 3.70E+03 9.44E+03 3.49E+03 6.21E+05 1.49E+04 0.00E+00 6.95E+03 0.00E+00 CS-134 5.02E+05 1.13E+06 5.49E+05 0.00E+00 3.75E+05 1.46E+05 9.76E+03 0.00E+00 CS-136 5.15E+04 1.94E+05 1.37E+05 0.00E+00 1.10E+05 1.78E+04 1.09E+04 0.00E+00 CS-137 6.70E+05 8.48E+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 0.00E+00 CS-138 4.66E+02 8.56E+02 4.46E+02 0.00E+00 6.62E+02 7.87E+01 2.70E-01 0.00E+00 BA-139 1.34E+00 9.44E-04 3.90E-02 0.00E+00 8.88E-04 6.46E+03 6.45E+03 0.00E+00 BA-140 5.47E+04 6.70E+01 3.52E+03 0.00E+00 2.28E+01 2.03E+06 2.29E+05 0.00E+00 i

BA-142 3.70E 02 3.70E-05 2.27E-03 0.00E+00 3.14E-05 1.91E+03 4.79E-10 0.00E+00 LA-140 4.79E+02 2.36E+02 6.26E+01 0.00E+00 0.00E+00 2.14E+05 4.87E+05 0.00E+00 1A-142 9.60E-01 4.25E-01 1.06E-01 0.00E+00 0.00E+00 1.02E+04 1.20E+04 0.00E+00 CE-141 2.84E+04 1.90E+04 2.17E+03 0.00E+00 8.88E+03 6.14E+05 1.26E+05 0.00E+00 CE-143 2.66E+02 1.94E+02 2.16E+01 0.00E+00 8,64E+01 1.30E+05 2.55E+05 0.00E+00 CE-144 4.89E+06 2.02E+06 2.62E+05 0.00E+00 1.21E+06 1.34E+07 8.64E+05 0.00E+00 PR-144 4.30E-02 1.76E 02 2.18E-03 0.00E+00 1.01E-02 1.75E+03 2.35E-04 0.00E+00 HF-181 6.31E+04 3.47E+02 7.04E+03 2.12E+02 2.90E+02 9.36E+05 1.20E+05 0.00E+00 W-187 1.20E+01 9.76E+00 3.43E+00 0.00E+00 0.00E+00 4.74E+04 1.77E+05 0.00E+00 NP-239 3.38E+02 3.19E+01 1.77E+01 0.00E+00 1.00E+02 6.49E+04 1.32E+05 0.00E+00 HBRODCM 3-68 Rev. 9

gUnited States Nuclear Regulatory _ Con =minaina

Enciomme 2 e Serial: RNP-RA/95-0159 TABLE-3.3 18 Page104 of 172 ~ ~

E VALUEsifor the E.B. ROBINSON STEAM ELECTRIC. PLANT 1

(

(Reference Regulatory Cuide 1.109)

I PATHWAY = Inhalation :

[

AGE GROUP!- Child :

1 1

Buclide Agar LiztE T, Body Thyroid Kidney Lung GI-Tract Ehin

.j 2

i fH 3

-0.00E+00 1.12E+03' 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1 1.12E+03 1.12E+03 C

F-18) 6.96E+03: 0.00E+00 6.85E+02 0.00E+00 0.00E+00 0'.00E+00: 1.25E+03 0.00E+00 i

~

1 1NA-241 1.61d+041 1,61E+04 1.61E+04 1.61E+04 ~ 1.61E+04 1.61E+04 1.61E+04 0.00E+00

'CR-511 0.00E+00 0.00E+00.'1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 0.00E+00 3'

LMN-54 0,00E+00 4.29E+04 9.51E+03 0.00E+00- 1.00E+04 1.58E+06 2.29E+04 :0.00E+00 5

'MN-56

'O.00E+00'-

1.66E+00- 3.12E 01- 0.00E+00. 1.67E+00 1.31E+04 1.23E+05 0.00E+00 y

FE-55 4.74E+04 2.52E+04-7.77E+03 0.00E+00 0.00E+00 1.11E+05-2.87E+03 - 0.00E+00

[

FE 59:

2.07E+04 3.34E+04 1.67E+04, 0.00E+00 0.00E+00 1.27E+06 7.07E+04- 0.00E+00 i

CO-57, 0.00E+00 9.03E+02 l'.07E+03 0.00E+00. 0.00E+00 5.07E+05 1.32E+04 0.00E+00

[

LC0f58; 0.'00E+001 1.77E+03 3.16E+03- 0.00E+00 0.00E+00 1.11E+06 3.44E+04 0.00E+00 E

CO 60

-0.00E+00,1.31E+04.2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 0.00E+00 7

i-NI-65:

2.99E+00- 2.96E-01 -1.64E 01 0.00E+00 0.00E+00 8.18E+03 8.40E+04 0.00E+00 L

2CU-641

- 0. 00E+00 -- 1.99E+00 1.07E+00 0.00E+00 6.03E+00 9.58E+03 3.67E+04.0.00E+00 ZN-65I

4.26E+04 1.13E+05 7.03E+04 0'.00E+00 7.14E+04 9.95E+05 1.63E+04 0.00E+00 lT BR-82 0,00E+00' O 00E+00 2.09E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

{:

BR-83 0.00E+00 0.00E+00 4.74E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 BR-84 0.00E+00 0.00E+00 5.48E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00' O.00E+00 i

RBL86 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 -0.00E+00 7.99E+03 0.00E+00

]

RB-88 0.00E+00 5.62E+02.3.66E+02 0.00E+00 0.00E+00 0.00E+00 1.72E+01 0.00E+00

!)

RB-89 0.00E+00 3.45E+02 2.90E+02 0.00E+00 0.00E+00 0.00E+00 1.89E+00 0.00E+00 L

-SR-89'

=5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 0.00E+00 j

SR-90.

1.01E+08 0.00E+00 6.44E+06 -0.00E+00 0.00E+00 1.48E+07 3.43E+05 0.00E+00 l

~5R-91

'1.21E+02 0.00E+00 4.59E+00 0.00E+00 0.00E+00 5.33E+04 1.74E+05 0.00E+00 h

'SR-92 1.31E+01 0.00E+00 5.25E-01 0.00E+00 0.00E+00 2.40E+04 2.42E+05 0.00E+00

]

i; TY-91M 5.07E-01 0.002+00 1.84E-02 0.00E+00 0.00E+00 2.81E+03 1.72E+03 0.00E+00

' Y-9.1.

9.14E+05 0.00E+00.2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84E+05 0.00E+00 Y-92'

'2.04E+01 0.00E+00 5.81E-01 0.00E+00 0.00E+00 2.39E+04 2.39E+05 0.00E+00 i

'Y-93 1.86E+02. 0.00E+00 -5.11E+00 0.00E+00 0.00E+00- 7.44E+04 3.89E+05 0.00E+00

}

.ZR-95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 0.00E+00 ZR 1.88E+02 2.72E+01 1.60E+01 0.00E+00 3.88E+01 1.13E+05 3.51E+05 0.00E+00 I

NS-95, 2.35E+04-9.18E+03 6.55E+03 0.00E+00 8.62E+03 6.14E+05 3.70E+04 0.00E+00 i

L i

in l

G j

R Values.'in units of area /yr per micro-Ci/m - for inhalation and tritium, j

1 8'

a

'and'in units of.m aren/yr per micro-Ci/sec' for all others.

iHBRODCN-3-69 Rev. 9

United States Nuclear Regulatory Comminion

- Enclosure 2 to Serial: RNP-RA/95-0159 TABLE 3.3-18 (centinu2d) gg Muclido D.ene Liver T. Body I_hyggf.d Kidney Lgng GI-Tract S,_hin NB-97 4.29E 01 7.70E-02 3.50E-02 0.00E+00 8.55E-02 3.42E+03 2.78E+16 0.00E+00 MO 99 0.00E+00 1.72s+02 4.25E+01 0.00E+00 3.92E+02 1.35E+05 1.27E+05 0.00E+00 TC-99M 1.78E-03 3.48E-03 5.77E-02 0.00E+00 5.07E-02 9.51E+02 4.81E+03 0.00E+00 TC-101 8.10E-05 8.51E-05 1.08E-03 0.00E+00 1.45E-03 5.85E+02 1.63E+01 0.00E+00 RU-103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 0.00E+00 RU-105 1.53E+00 0.00E+00 5.55E-01 0.00E+00 1.34E+00 1.59E+04 9.95E+06 0.00E+00 RU-106 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1.84E+05 1.43E+07 4.29E+05 0.00E+00 AC-110M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 0.00E+00 SN-113 8.99E+03 2.90E+02-9.81E+03 1.19E+02 2.03E+02 3.40E+05 7.44E+03 0.00E+00 SB-124 5.74E+04 7.40E+02 2.00E+04 1.26E+02 0.00E+00 3.24E+06 1.64C+05 0.00E+00 SB-125 9.84E+04 7.59E+02 2.07E+04 9.10E+01 0.00E+00 2.32E+06 4.03E+04 0.00E+00 TE-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 0.00E+00 TE-129 9.77E 02 3.50E-02 2.38E-02 7.14E-02 2.57E-01 2.93E+03 2.55E+04 0.00E+00 TE-13LM 1.34E+02 5.92E+01 5.07E+01 9.77E+01 4.00E+02 2.06E+05 3.08E+05 0.00E+00 TE-132 4.81E+02 2.72E+02 2.63E+02 3.17E+02 1.77E+03 3.77E+05 1.38E+05 0.00E+00 I-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03 0.00E+00 I-132 2.12E+03 4.07E+03 1.88E+03 1.94E+05 6.25E+03 0.00E+00 3.20E+03 0.00E+00 I-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 0.00E+00 I-134 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 0.00E+00 9.55E+02 0.00E+00 I-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 0.00E+00 4.44E+03 0.00E+00 CS-134 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 0.00E+00 c

CS-136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04 1.45E+04 4.18E+03 0.00E+00 CS-137 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 0.00E+00 CS-138 6.33E+02 8.40E+02 5.55E+02 0.00E+00 6.22E+02 6.81E+01 2.70E+02 0.00E+00 BA-139 1.84E+00 9.84E-04 5.36E-02 0.00E+00 8.62E-04 5.77E+03 5.77E+04 0.00E+00 BA-140. 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 0.00E+00 BA-142 4.99E-02 3.60E-05 2.79E 03 0.00E+00 2.91E-05 1.64E+03 2.74E+00 0.00E+00 LA 140 6.44E+02 2.25E+02 7.55E+01 0.00E+00 0.00E+00 1.83E+05 2.26E+05 0.00E+00 1A-142 1.29E+00 4.11E-01 1.29E-01 0.00E+00 0.00E+00 8.70E+03 7.59E+04 0.00E+00 CE-141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 0.00E+00 CE-143 3.66E+02 1.99E+02 2.87E+01 0.00E+00 8.36E+01 1.15E+05 1.27E+05 0.00E+00 CE-144 6.77E+06 2.12E+06 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+05 0.00E+00 PR-144 5.96E-02 1.85E-02 3.00E-03 0.00E+00 9.77E-03 1.57E+03 1.97E+02 0.00E+00 HF-181 8.33E+04 3.28E+02 8.47E+03 2.76E+02 2.63E+02 7.96E+05 5.29E+04 0.00E+00 4

W-187 1.63E+01 9.66E+00 4.33E+00 0.00E+00 0.00E+00 4.11E+04 9.10E+04 0.00E+00 NP-239 4.66E+02 3.34E+01 2.35E+01 0.00E+00 9.73E+01 5.81E+04 6.40E+04 0.00E+00 HBRODCM.

3-70 Rev. 9

United States Nuclearle~y Commission Enclosme 2 to Serial: RNP-RA/95-0159

,, 3, 3 3, j Page 106 of 172'

,,,,,,,,,,,,L,,,,,,,,.sTEau ELECTRIC rtAmT2

)i (Reference Regulatory Guide 1.109)

PATHWAY 1 =-Inhalation-4

' AGE GROUP - Infant-V

(

Nuclida 35tna LLY1E T. Body Thyroid Eidasy Lgag GI-Tract 3]Ein j

'H 0.00E+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02-6.47E+02

[

F-18; 5.49E+03 0.00E+00 4.66E+02 0.00E+00 0.00E+00 0.00E+00 8.54E+02 0.00E+00 I'

NA 1.06E+04

.1.06E+04' 1.06E+04 1.06E+04 1.06E+04 1.06E+04-1.06E+04 0.00E+00

}

CR-51

- 0.00E+00 0.00E+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 '0.00E+00 l

f..

'MN-54 0.00E+00; 2.53E+04 4.98E+03 0.00E+00' 4.98E+03 1.00E+06 7.06E+03 '0.00E+00 MN 0.00E+00 1.54E+00 2.21E-01.0.00E+00 1.10E+00 1.25E+04 7.17E+04- 0.00E+00 j

j[;

'FE 1.97E+04 1.17E+04 3.33E+03 0.00E+00 0.00E+00 8.69E+04 1.09E+03 0.00E+00 FE 1.36E+04 2.35E+04 9.48E+03 0.00E+00 0.00E+00 1.02E+06 2.48E+04 0.00E+00

[.

Co-57'

<0.00E+00 16.51E+02 6.41E+02 -0.00E+00 0.00E+00 3.79E+05 4.86E+03 0.00E+00 j '

CO-58

.0.00E+00 1.22E+03 1.82E+03 0.00E+00 0.00E+00 7.77E+05 1.11E+04 0.00E+00 j

CO.60' O.00E+00 8.02E+03 1.18E+04- 0.00E+00 0.00E+00 4.51E+06

-3.19E+04. 0.00E+00 d

f NI-65 2.39E+00- 2.84E-01 1.23E 01 0.00E+00 0.00E+00 8.12E+03 5.01E+04 0.00E+00

{

.CU-64' O.00E+00 1.88E+00 7.74E-01 0.00E+00 3.98E+00 9.30E+03 1.50E+04 0.00E+00 i

'ZN-65 1.93E+04-6.26E+04 3.11E+04 0.00E+00 3.25E+04 6.47E+05 5.14E+04 0.00E+00 BR-82 0.00E+00 0.00E+00 1.33E+04 0.00E+00 0.00E+00 0.00E+00 -0.00E+00 0.00E+00 1

h BR-83' O.00E+00 0.00E+00 3.81E+02 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 0.00E+00

~BR-84 0.00E+00 0.00E+00 4.00E+02 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 I

RB-86 0.00E+00 1.90E+05 8.82E+04 0.00E+00 0.00E+00 0.00E+00 3.04E+03.0.00E+00

RB-88 0.00E+00 5.57E+02 2.87E+02 0.00E+00 0.00E+00 0.00E+00 3.39E+02.0.00E+00 RB-89 0.00E+00 3.21E+02 2.06E+02 0.00E+00 0.00E+00 0.00E+00 6.82E+01 0.00E+00 SR'-89 3.98E+05 0.00E+00 1.14E+04 0.00E+00 0.00E+00 2.03E+06 6.40E+04 0.00E+00 SR-90 4.09E+07 0.00E+00 2.59E+06 0.00E+00 0.00E+00 1.12E+07 1.31E+05 0.00E+00

)

-SR-91,~

- 9.56E+01. 0.00E+00 3.46E+00 0.00E+00 0.00E+00 5.26E+04 7.34E+04 0.00E+00 SR-92 l'. 05 E+01 0.00E+00 3.91E-01 0.00E+00 0.00E+00 2.38E+04 1.40E+05 0.00E+00 Y-91M 4.07E-01 0.00E+00 1.39E-02 0.00E+00 0.00E+00 2.79E+03 2.35E+03 0.00E+00 l

Y 5.88E+05 0.00E+00- 1.57E+04 0.00E+00 0.00E+00 2.45E+06 7.03E+04 0.00E+00 Y-92 1.64E+01 0.00E+00 4.61E-01 0.00E+00 0.00E+00 2.45E+04 1.27E+05 0.00E+00

-Y-93 1.50E+02 0.00E+00 4.07E+00 0.00E+00 0.00E+00 7.64E+04 1.67E+05- 0.00E+00 I'

ZR-95 l'.15E+05 2.79E+04 2.03E+04 0.00E+00 3.11E+04 1.75E+06 2.17E+04 0.00E+00 ZR-97 1.50E+02 2.56E+01 1.17E+01- 0.00E+00 -2.59E+01 1.10E+05 1.40E+05 0.00E+00

.NB-95 1.57E+04 653E+03 3.78E+03 0.00E+00 4.72E+03 4.79E+05 1.27E+04 0.00E+00

+

4 J

l 2

i-1 3

R Values'in units of ares /yr per micro-Ci/m 'for inhalation and tritium, E

'and in units'of m2 ares /yr per micro-Ci/sec for all others.

H5RODCM 3-71 Rev. 9 er9--s a

m t-A+%o s+

nv,=-

4 -. +

r 4

-m+1

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 TAs1.E 3.3-19 (centinusd)

Page 107 of 172 Nuclide Bone Liver T. Body Thyroid Kidnev

,Iggig CI-Tract Skin NB-97 3.42E-01 7.29E 02 2.63E-02 0.00E+00 5.70E-02 3.32E+03 2.69E+04 0.00E+00 MO-99 0.00E+00 1.65E+02 3.23E+01 0.00E+00 2.65E+02 1.35E+05 4.87E+04 0.00E+00 TC-99M 1.40E 03 2.88E-03 3.72E-02 0.00E+00 3.11E-02 8.11E+02 2.03E+03 0.00E+00 TC-101 6.51E-05 8.23E-05 8.12E 04 0.00E+00 9.79E-04 5.84E+02 8.44E+02 0.00E+00 RU-103 2.02E+03 0.00E+00 6.79E+02 0.00E+00 4.24E+03 5.52E+05 1.61E+04 0.00E+00 RU-105 1.22E+00 0.00E+00 4.10E-01 0.00E+00 8.99E-01 1.57E+04 4.84E+04 0.00E+00 RU-106 8.68E+04 0.00E+00 1.09E+04 0.00E+00 1.07E+05 1.16E+07 1.64E+05 0.00E+00 AC-110M 9.98E+03 7.22E+03 5.00E+03 0.00E+00 1.09E+04 3.67E+06 3.30E+04 0.00E+00 SN-113 4.68E+03 1.74E+02 4.89E+03 6.72E+01 9.94E+01 2.30E+05 2.28E+03 0.00E+00 SB-124 3.04E+04 5.56E+02 1.20E+04 1.01E+02 0.00E+00 2.65E+06 3.42E+04 0.00E+00 SB-125 5.17E+04 4.77E+02 1.09E+04 6.23E+00 5.70E-02 3.32E+03 2.69E+04 0.00E+00 TE 129M 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 0.00E+00 TE-129 7.88E-02 3.47E-02 1.88E-02 6.75E-02 1.75E-01 3.00E+03 2.63E+04 0.00E+00 TE 131M 1.07E+02 5.50E+01 3.63E+01 8.93E+01 2.65E+02 1.99E+05 1.19E+05 0.00E+00 TE-132' 3.72E+02 2.37E+02 1.76E+02 2.79E+02 1.03E+03 3.40E+05 4.41E+04 0.00E+00 I-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.00E+00 1.06E+03 0.00E+00 I-132 1.69E+03 3.54E+03 1.26E+03 1.69E+05 3.95E+03 0.00E+00 1.90E+03 0.00E+00 I-133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 0.00E+00 2.16E+03 0.00E+00 I-134 9.21E+02 1.882+03 6.65E+02 4.45E+04 2.09E+03 0.00E+00 1.29E+03 0.00E+00 1-135 3.86E+03 7.60E+03 2.77E+03 6.96E+05 8.47E+03 0.00E+00 1.83E+03 0.00E+00 CS-134 3.96E+05 7.03E+05 7.45E+04 0.00E+00 1.90E+05 7.97E+04 1.33E+03 0.00E+00 CS-136 4.83E+04 1.35E+05 5.29E+04 0.00E+00 5.64E+04 1.18E+04 1.43E+03 0.00E+00 CS-137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+05 7.13E+04 1.33E+03 0.00E+00 CS-138 5.05E+02 7.81E+02 3.98E+02 0.00E+00 4.10E+02 6.54E+01 8.76E+02 0.00E+00 BA-139 1.48E+00 9.84E-04 4.30E-02 0.00E+00 5.92E-04 5.95E+03 5.10E+04 0.00E+00 BA-140 5.60E+04 5.60E+01 2.90E+03 0.00E+00 1.34E+01 1.60E+06 3.84E+04 0.00E+00 BA-142 3.98E-02 3.30E-05 1.96E-03 0.00E+00 1.90E-05 1.55E+03 6.93E+02 0.00E+00 LA-140 5.05E+02 2.00E+02 5.15E+01 0.00E+00 0.00E+00 1.68E+05 8.48E+04 0.00E+00 LA-142 1.03E+00 3.77E-01 9.04E-02 0.00E+00 0.00E+00 8.22E+03 5.95E+04 0.00E+00 CE-141 2.77E+04 1.67E+04 1.99E+03 0.00E+00 5.25E+03 5.17E+05 2.16E+04 0.00E+00 CE-143 2.93E+02 1.93E+02 2.21E+01 0.00E+00 5.64E+01 1.16E+05 4.97E+04 0.00E+00 CE-144 3.19E+06 1.21E+06 1.76E+05 0.00E+00 5.38E+05 9.84E+06 1.48E+05 0.00E+00 PR-144 4.79E-02 1.85E-02 2.41E-03 0.00E+00 6.72E-03 1.61E+03 4.28E+03 0.00E+00 HF-181 5.64E+04 2.66E+02 5.05E+03 2.25E+02 1.58E+02 6.72E+05 1.90E+04 0.00EF00 W-l'87 1.30E+01 9.02E+00 3.12E+00 0.00E+00 0.00E+00 3.96E+04 3.56E+04 0.00E+00 NP-239 3.71E+02 3.32E+01 1.88E+01 0.00E+00 6.62E+01 5.95E+04 2.49E+04 0.00E+00 HBRODCM 3-72 Rev. 9

Unbed States Nuclear Regulatory Comminion to Serial: RNP-RA/95-0159 Page 108 of 172 3.4 METHODOLOGY FOR R-11 SETPOINT (Air Particulate)

Determine the Monitor Alarm Setpoint based on the inhalation pathway to the child.

The most restrictive organ "j" will be determined from the following methodology.

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

dry = XIQ Eg Rg, Qi (3.4-1) where:

the highest calculated annual average relative dispersion X/Q factor for any area at or beyond the unrestricted area 3

boundary for all sectors (sec/m ) from Appendix A.

8.lE-5 sec/m (continuous ground release) from Table A-1, 3

Appendix A.

the organ "j " dose factor due to gamma emissions from Rq particulates greater than or equal to 8 day half-life, I-133, I-131, and H-3.

the particulate release rate (pCi/sec) for radionuclide "i".

Qi 472 (C )(F) i where:

conversion factor to convert CFM to ec/sec. 472

( Ci/cci from analysis of containment vessel) (0.366)

C i

+ (DF) + (pCi/ce, from analysis of Plant Vent) (0.634) when R-11 is sampling the Plant Vent for CV purges.

HBRODCM 3-73 Rev. 9

United Staics Nuclear Regulatory Commission

' to Serial: RNP-RA/95-0159 Page 109 of 172 (pCi/cci from analysis of CV) (0.04) + (DF) + (pCi/ce; from analysis of Plant Vent) (0.960) when RMS-11 sampling from Plant Vent for CV pressure relief.

(pci/cci from analysis of CV) + (DF) when RMS-11 is sampling j

W.

95,600 cfm for CV purge when R 11 is sampling from Plant Vent.

j F

35,000 cfm for CV purge when R-11 is sampling from CV.

2,500 cfm for CV pressure relief when R-11 is sampling from CV.

63,100 cfm for CV pressure relief when R-11 is sampling Plant Ve't.

n 1.0 for Tritium DF 10 for Iodines when using characoal filters 100 for Particulates 2: 8 day half-lives when using HEPA Filters.

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

DR /1500 (3.4-2)

PDRR 3

3 the allowable organ dose rate due to particulates with > 8 day 1500 half-life, I-131, I-133, H-3 (area / year).

)

HBRODCM' 3-74 Rev. 9 i

United States Nuclear Regulatory Comminnion Raciasure 2 to Serial: RNP-RA/95-0159 Page 110 of 172 3.4.3 Determine the maximum monitor setpoint concentration (pCi/cc) for most critical organ "j ".

{(E C ) / (PDRR )) (SF) (T,) (TL)

Maximum Monitor Setpoint for Organ "j" -

t i 3

where:

an engineering factor used to provide a margin of safety for SF cumulative measurement uncertainties - 0.50.

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 due to simultaneous releases 3

4 from several pathways.

4 0.81 for R-11 particulate monitor.

4 i

C5 where the total activity is the sum of total activity / Ei TL all detectable particulates from analysis of particulate filter divided by the detectable particulates of 2: 8 day half-2 lives.

If this ratio is not known, use 1.0.

i 1.0 when R-11 sampling from Plant Vent.

i 4

a i

1 I

4 4

4 1

2 HBRODCM 3-75 Rev. 9

' L

United States Nuclear Regulatory Commision Frelamn 2 to Serial: RNP-RA/95-0159 Page 111 of 172 3.4.4 Determine the maximum monitor setpoint (cpm) for the most critical organ "j ".

f l

Setpoinc = (Maximum organ secpoinc in pC1/cc) (monitot eff) l

+ Ekg (3. 4 -3 )

obtained from the applicable effluent monitor efficiency j

Monitor curve efficiency located in the POM, Volume 15, Curve

.I Book. Use the radioactivity concentration (pci/cc) to find epm.

the monitor background (cpm) j Bkg

}

b a

4

\\

l HBRODCM 3-76 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 112 of 172 3.5 Methodolorv for R-14A Setooint (Particulate Monitor)

This section describes the methodology in determining high alarm setpoint for the plant vent monitor (R-14A) based on the inhalation pathway to the child.

The most restrictive organ "j " will be determined frna a conservative mix (GALE Code).

3.5.1 Determine Si, the fraction of the total radioactivity in particulate form in the gaseous effluents comprised by radionuclide "i" for each radionuclide in the gaseous effluent from Table 3.2-1.

Ai (3.5-1)

Si Ei Ai where:

The radioactivity of radioparticulate radionuclide "i" in the Ai gaseous effluent from Table 3.2-1.

3.5.2 Determine Qm, the maximum acceptable total release rate [uci/sec) of all the radioparticulate radionuclides in the gaseous effluent based upon the most restrictive organ "j" exposure limit of 1500 mrem / year by:

1500 (3.5-2)

Qar (X/Q) Ei Si Pir where:

the maximum allowable dose rate in an unrestricted area in 1500 I

gaseous effluents due to radioparticulates with half lives greater than 8 days, radioiodines and tritium via the inhalation pathway to the child.

(X/Q) -

The highest calculated annual average relative dispersion i

factor for any area at or beyond the unrestricted area boundary for all sectors (sec/m ).

3 8.lE-05 Sec/m (continuous ground release) from Table A-1, 3

Appendix A.

i RBRODCM 3-77 Rev. 9

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 113 of 172 Th. dose parameter for I-131, I-133, ib 3, and all particulates Pir in particulate form with half lives greater than 8 days for the inhalation pathway only in the most restrictive sector in mrem / year per uCi/m.

The dose factor is based on the most 3

restrictive group (child) and most restrictive organ at the SITE BOUNDARY (see Table 3.2-4).

3.5.3 Determine Qiv, fraction of plant stack release rate acquired on filter, r

by:

Qui [3.33E-05)

(3.5-3)

Qivi 4

where:

fraction of monitor sample rate to plant vent flow rate 3.33E-05 (2.02 CFM/60,600 CFM) 3.5.4 Determine HCI, maximum acceptable concentration [uci] accumulated on the filter due to all particulate radionuclides in the gaseous effluents based 1

on the most restrictive organ "j", by:

Qivt (T)

(3.5-4)

HCI where:

time in seconds T

8.64E04 for one day 6.05E05 for one week 3.5.5 Determine

HAC, high alarm concentration (uCi]

from particulate radionuclides in gaseous effluents, by:

4 (HCI) (SF) (Tm)

(3.5-5)

HAC where:

An engineering factor used to provide a margin of safe *y for SF cumulative uncertainties of measurements 0.5 HBRODCM 3-78 Rev. 9

United States Nuclear Regulatory Comminion to Serial: RNP-RA/95-0159 Page114 of 172 Fraction of the radioactivity from the site that may be Tm released to ensure the site boundary limit is not exceeded due to simultaneous releases from pathways

.92 for the Plant Vent Monitor (R-14A).

3.5.6 Determine the HSP, High Alarm Setpoint including background (cpm], by:

RSP = (RAC/ED) + BKG (3. 5 -6 )

where:

from monitor efficiency curve located in the Plant Operating Em Manual Curve Book.

3.6 Methodology for R-14B Setooint (Iodine Monitor)

This section describes the methodology in determining high alarm setpoint for the plant vent monitor (R-14B) based on the inhalation pathway to the child.

The most restrictive organ "j " will be determined from a conservative mix (GALE Code).

3.6.1 Determine Qa, the maximum acceptable release rate [uci/sec] of I-131 in r

gaseous effluents based upon the most restrictive organ "j" exposure limit of 1500 mrem / year, by:

1500 (3.6-1) i Qmg a

(X/Q) Pir

)

i where.

The dose parameter for I-131 for the inhalation pathway only Pir in the most restrictive sector in mrem / year per uCi/m.

The dose factor is based on the most restrictive group (child) and most restrictive organ at the Site Boundary (see Table 3.2-4).

3.6.2 Determine Qiv, fraction of plant stack release rate acquired on the r

cartridge, by:

Qa (3.33E-05)

(3.6-2)

Qivt r

HBRODCM 3-79 Rev. 9

l

. United States Nuclear Regulatory Commission

< to Serial: RNP-RA/95-0159 Page 115 of 172 13.6.3 Determine ~HCI, maximum acceptable con:entration [uci) accumulated on the-f ca'rtridge due to I-131 in gaseous effluents based on the most restrictive or5an "j ".

(Qivg) (T)

(3.6-3)

HCI where:

time is seconds T

8.64E04 for one day 6.05E05 for one week 3.6.4 Determine HAC, high alarm concentration [uCi] from I-131 in gaseous 2

effluents, by:

(HCI) (SF) (Tm)

(3.6-4)

HAC 3.6.5 Determine HSP, High Alarm Setpoint including background [ cpm), by:

i RSP = (NAC/an) + BKG (3.6-5) 4 3.7 Methodology for R-22 and R-23 Setooint Determination for the Iodine and 1

Particulate Monitors j

This section describes the methodology in determining high alarm setpoint for the particulate and iodine channels for the Environmental and Radiation Control Building and Radwaste Building exhaust vent (R-22 and R-23, respectively) based on the inhalation pathway to the nost restrictive organ and age gtoup (child).

3.7.1 The dose rate in an unrestricted area resulting from the release of radiciodines, tritium, and particulates with half-lives a8 days is

' limited to 1500 mrem /yr to any organ via inhalation (10CFR20). The iodine and particulate monitor setpoints for R-22 and R-23 are limited to 1.0% of 10CFR20 over one hour period.

Therefore, the iodine and particulate channels high alarm shall be set to 1.0% of 10CFR20 for any given hour.

HBRODCM 3-80 Rev. 9

-aem

- United States Nuclear Regulatcty Comminion to Serial: RNP-RA/95-0159

~

Page116 of 172 3.7.2 Determine Qt, the maximum release rate (pCi/sec) for Iodine-131 and Cobalt-60 (the most restrictive particulate 2: 8 day half-life) base on the most restrictive organ "j" via inhalation to a child.

15 O, =

g 3,7_1)

(Rj) (T/D) i

'where:

1.0% of the maximum allowable dose rate in an unrestricted 15 d

area in gaseous effluents due to radioparticulates with half-lives greater than or equal to 8 days, radioiodine, and tritium via the inhalation pathway to the child.

The dose factor based on the most-restrictive age group R

i (child) and the most restrictive organ (thyroid) for 3

Iodine-131 (1.62E7 mrem /yr/pci/m ) and lung for Co-60 (7.06E6 j

mrem /yr/pCi/m )

at the most restrictive location (SITE 3

BOUNDARY).

4 Annual average relative dilution for continuous ground level X/Q releases for the most restrictive section at the SITE BOUNDARY (8.08E-5 sec/m for the SSE sector from Table A-1).

8 Therefore:

1.15E-2 pCi/sec Qtrodin.ist 2.63E-2 pCi/sec Qic.3.ti,-so m,

1 HBRODCM 3-81 Rev. 9 1

l

United States Nuclear' Regulatory Commission -

' Enclosure 2 to Serial: RNP-RA/95 0159 :

Page 117 of 172 3.7.3 Determine, Sei, the air particulate filter and charcoal cartridge sample collection rate (pci/sec) by:

Qi

'(3.7-2)

Se,

\\

where:

sampler flow ~ rate (typically 2.5 C m for R-22 and 2 CFM for f

R-23)

Radwaste Building exhaust vent flow rate (15,000 typically)

F Environmental and Radiation Control Building exhaust vent flow rate (11,500 typically)

Therefore:

1The typical Co-60 sample collection rate is 5.72E-6 pCi/see and 4.39E-6 pCi/sec, for R-22 and R-23, respectively.

The typical I-131 sample collection rate is 2.5E-6 pCi/see and 1.91E-6 pCi/sec for R-22 and R-23, respectively.

3.7.4 Determine Qm,,

the 'setpoint activity (pci) accumulated on the air particulate filter and charcoal filter for any given hour by:

(S,) (T)

(3.7-3)

Qat c

4 where:

3600 see in an hour.

.T Therefore:

The typical setpoint activity for the air particulate filter and the charcoal cartridge is:

Monitor Particulate Iodine R-22 2.06E-02 9.00E-03

'R-23 1.58E-02 6.88E-03

'HBRODCM-3-82 Rev.' 9

United States Nuclear. Regulatory Commission blaanse 2 to Serial: RNP-RA/95-0159

. Page 118 of 172

- 3.7.5 Determine the HSP, High Alarm Setpoint including background (cpm) by:

HSP '

(Qai).(Em) + BKG (3.7 4) where:

efficiency of the detector Em the background of the detector BKG The a'oove methodology _ shall-be used for the. iodine cartridge.. and air particulate. filter setpoint determinations for the Environmental and Radiation Control Building and Radwaste Building exhaust vent.

The sampling and building vent flow rates used in the above equations are subject to change and shall be controlled by plant procedures. If or when this occurrs, the recalculations of setpoints shall be performed by approved procedures using the above methodology.

HBRODCM 3-83 Rev. 9

Unhed States Nuclear. Regulatory Comminion

, to Serial: RNP-RN95-0159

Papl119 of 172 j'-'

(Left blank intentionally) 4 t

e 4

4 i.

'O E

1 1-Y 3--

i.

4 1

e HBRODCM-B-18' Rev. 9 4

e

_~.,._

,5(

~

4 United States Nuclear Regulatory Comminion qEnclosure 2 to Serial: RNP-RA/95-0159 -

Page 120 of 172 -

(Laft blank intentionally) 4

'{'

i '

J k

e i

1 4

4 i

d i

2

(

4 i

J 4

i HBRODCM'-

=3 19 Rev. 9 o

w-a

i

! United States Nuclear Regulatory.Cammianion - to Serial: RNP-RA/95-0159 Page 121 of172 (Left blank intentionally)

A 1

l 1

i l

HBRODCM B-20 Rev. 9-

~

.1 1

.Unhed States Nuclear Regulatory Comminion klamine 2 to Serial: RNP-RA/95 0159 Page 122 of 172.

(Left blank intentionally) 4 4

e i

d.

n i

1-

)

1 i

)

1 i

J 4

4 e

l 1

l 4

l 1

l HBRODCM

.B-21

-Rev. 9~

i

United States Nuclear Regulatory Commission Z.nclosure 2 to Serial: RNP-RA/95-0159 g

Page 123 of 172 JUSTIFICATIONS AND CHANGES FOR ODCM, REVISION 10 Pace No.

' Comments / Justifications for ODCM Revision 10 i

Changed to page 11. The new page i is the List of Effective.Pages (LEP).

11'

' Renumbered to page lii.

iii Renumbered to page iv.

I iv ~

Renumbered to page v.

4-2 Was previously page 2 of.section 4.

Page was renumbered and reformatted into table form.

j

.4-3 thru 4-5 Pages were reformatted into table form.

I 4-6 thru 4-7 Were previously pages 6 and 7 of section 4.

Pages were renumbered and reformatted into table rbrm.

4-9 thru 4-10 Were previously unnumbered pages 9 and 10 of section 4.

Pages were 4

numbered and revision number was added.

A-1 thru A-3 The revision number was'added to the pages.

A-6 The revision number was added to the page.

A-9 thru A-20 The revision number was added to the pages.

A-22 thru A-27 The revision number was added to the pages and the pages were reformatted

'f into table form.

E B-2 thru B-5 The revision number was added to the pages.

~ B-7 The revision number was added to the page.

i B-8 Hand drawn brackets in equation B.2-3 were replaced with computer generated blackets for the equation and the revision number was added to the page.

B-9 thru B-10 The revision number was added to the pages.

j B-24 Hand drawn brackets in equation B.2-8 were replaced with computer generated brackets for the equation and the revision number was added to the page.

B-15 thru B-17 The revision number was added to the pages, i

i e

t-9 e

4

United States Nuclear Regulatory Comminion to Serial: RNP-RA/95-0159 Page 124 of 172 CAROLINA POWER & LICHT COMPANY j

~

i H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 0FF-SITE DOSE CALCUIATIONAL MANUAL (ODCM)

Revision 10 DOCKET NO. 50-261 4

4/CM/QS EFFECTIVE DATE CONTROLLE]

~

RECIPIENT

'D 4

I Reviewed By:

si Date:

fN#/#F irma[

PNSC C A [ C' Date:

'//7# /ff Accepted By:

PNSC aig HERODCM f

United States Nuclear Regulatory Commission - to Serial: RNP-RA/95-0159

~Page:125 of 172 LLTT OF EFFECTIVE PACES i

REVISION

= EFFECTIVE PACES 10

' Cover Sheet 10

-LEP 10

. Table of Contents 10 List of Tables 10 List of Figures 9

1-1 through 1-2 9

2-1 through 2-24 9

3-1 through 3-83 8

4-1 10

'4-2 through 4-7 5

4-8 10 4-9. through 4-10 5-1 2

4

'6-1 1

6-2 through 6-3 10 A-l' through A-3 1

A-4 through'A-5 10 A-6 1

A-7.through A-8 10 A-9 through A-20 1

'A-21 f

10

'A-22 through A-27 3

B-l' 10-B-2 ~through B-5 2

j, B-6 10 i

B-7 through B-10 1

B-11 through B-13 10 l

B-14 through B-17 9

l B-18 through B-21 2

B-22 4

j

-C-1 through C-4 7

D-1. through D-4

,~

l

~~

RBRODCM' i

Rev. 10

)

-United States Nuckar Regulatory Commission to Serial: RNP-RA/95-0159 Page 126 'of 172 -

TABLE OF CONTENTS Iltla fait incrinn

-1 LIST OF EFFECTIVE PAGES........................................

TABLE OF CONTENTS.......................'........................

11 iii LIST OF TABLES..................................................

Y LIST.OF FIGURES.................................................

1 1-1 1.0

. INTRODUCTION....................................................

1

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

2-1 2.1

-Monitor Alarm Setpoint Determination......................

2-11 2.2 Compliance with 10CFR20-(Liquids).........................

'2-16 2.3 Compliance with 10CFR50 (Liquids).........................

3-1 3.0 CASEOUS EFFLUENTS..............................

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

3-15 3.2'

' Compliance with 10CFR20 (Caseous).........................

3-24 3,3 Compliance with 10CFR50 (Caseous).........................

3-73 3.4 Methodology for RMS-11 Setpoint (Air Particulate)'.........

3-77 3.5 Methodology for R-14A Setpoint (Particulate Monitor)......

3-79 3.6 Methodology for R-148 Setpoint (Iodine Monitor)...........

3.7 Methodology for R-22 and R-23 Setpoint Determinations 3-80 for the Iodine and Particulate Monitors...................

1 1

4-1 i

4.O RADI0IDGICAL ENVIRONMENTAL MONITORING PROGRAM......,4...........

5-1 5.0 INTERIABORATORY COMPARISON STUDIES..............................

5-1 5.1 0bjective.................................................

5-1 5.2 Program...................................................

1 6-1 6.0 TOTAL DOSE (40CFR190 CONFORMANCE)...............................

6-1 6.1 Compliance with 40CFR190..................................

6.2 Calculations Evaluating Conformance with 40CFR190.........

6-1 6-2 i

6.3 ~

Calculations of Total Body Dose...........................

6-3 6.4 Thyroid Dose..............................................

6-3 6.5

. Do s e Pr oj e c ts.............................................

' APPENDIX A

' Meteorological Dispersion Factor

~l A-1

~

Computations...................'...........................

4 APPENDIX B - Dose Parameters for Radiciodines, 51 Particulates, and Tritium.................................

i C-1

. APPENDIX C - Lower Limit of Detectability.......................

Rev. 10 r.

MBRODCM 11 s

i

~

,.~

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 127 of 172-LIST OF TABLES

\\

l No.

Title

f. Age 2.3 Air Values for the Adult.for the j

2-22 H.'B. Robinson Steam Electric P1 ant.......................

3-13 3.1-1 Gaseous Source Terms.............

1 3-14

)

3.1-2.

, Dose Factors and Constants...............................

3-19 3.2-1 Releases from H.B. Robinson Unit No.

2...................

3.2-2 Distance to Special Locations for the 3-20 H.B. Robinson Plant (Mi.)................................

3.2-3 Dose Factors for Noble Cases and Daughters...............

3-21 3.2-4

i values for a Child for the H.B. Robinson 3-22 Unit No.

2.........................................

3.3-1 thru R Values for the H.B. Robinson Steam Electric Plant......

3-35 thru 3-72 3.3-19 4.0-1 H.B. Robinson Radiological Environmental 4-2 Monitoring Program.......................................

A-1 X/Q Values for Long-Term Ground Level Releases 8

A-4 at Special locations (sec/m )........................,....

A-2 Depleted X/Q Values for Long-Term Ground IAvel, Releases at Special Locations (sec/m )....... /..........

A-5 3

i l

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

A-6 l

A-4 X/Q Values for Long-Tera Ground Level Releases a t S tandard Dis tanc e s ( s e c/m )...........................

A-7 3

A-5 Depleted X/Q Values for Iong-Term Ground level Releases at Standard Distances (sec/m )..................

A-8 3

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

A-9 A X/Q Value for Short-Term Ground Level Releases 3

A-10 at Special locations (sec/m )............................

A-8 Depleted X/Q Values for Short-Term Ground Level Releases at Special Locations (sec/m )...................

A-ll 3

t

{

i i

MBRODCM' iii Rev. 10 l

United States Nuclear Regulatory Comminaion Kneinsure 2 to Serial: RNP-RN95-0159 Page 128 of 172

' LIST OF TABLES (continued) m No.

Title last

. A 9-D/Q Values for Short-Term Ground IAvel Releases A-12 at Special Locations (m-2)...............................

i A-10 X/Q Values for-long-Tern Mixed Mode Releases 8

A at Special locations (sec/m )............................

A-ll Depleted X/Q Values for Long-Term Mixed Mode 3

A-14 Releases at Special Imcations (sec/m )...................

A-12 L/Q Values for Long-Tern Mixed Mode Releases A-15 at Special Locations (m-a)...............................

A-13 X/Q. Values for Long-Tern Mixed Mode Releases 3

A-16 a t S tandard Di s tance s ( s ec/m )...........................

A-14. Depleted X/Q Values for Long-Tern Mixed Mode 3

A Releases at Standard Distances (sec/m )..................

A-15 D/Q Values for Long Term Mixed Mode Releases A-18 at Standard Distances (m-2)..............................

A-16.X/Q Values for Short-Term Mixed Mode Releases 3

A-19 at Special Locations (sec/m )............................

A-17 Depleted X/Q Values for Short-Tern Mixed Mode 3

A-20 Releases at Special locations (sec/m )...................

A-18. D/Q Values for Short-Term Mixed Mode Releases A-21

- a t S pe c i al Lo c at ions (m-2 )...............................

A-19 Robinson Plant Site Information to be Used for Ground Level Calculations with NRC A-22 "XOQD0Q" Program........................................,

i

[

A-20 Robinson Plant Site Information to be Usad i

for Mixed Mode Release Calculations with NRC A-25 l_

"XOQD0Q" Program.........................................

B-15 B-1 Parameters for Cow and Goat Milk. Pathways................

B-16 B2' Parameters for the Meat Pathway...........................

B-17 B Parameters for the Vegetable Pathway.....................

1.

D-1 D-1; Liquid Process Monitors..................................

D-2 D-2 Caseous Process Monitors.................................

4 i

MBRODCM iv Rev. 10

.e..

. United States Nuclear Regulatory Commission

) to Serial: RNP-RA/95-0159 Page 129 of 172 LIST OF FIGURES T.lE11 M

No.

4-9 4-1 Radiological Sample Locations Near Site..................

4-10. 2 Radiological Sample Distant locations....................

D-3 D l' N.B. Robinson Liquid Radwaste Effluent Sfstem............

D D2

'H.B. Robinson Caseous Radwaste Effluent System...........

4 4

l 4.

i-

/

4 1

+

b 1

m eu-s Rev. 10 y.

i -

~HBRODCM-d

United States Nuclear Regulatory Commission Enciamre 2 to Serial: RNP-RA/95-0159 Page 130 of 172 l

Table 4.0-1 H. B. ROBINSON RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i

Esposure Pathway temple semple Point Description, sempting and Analysis' I

end/or semple Point Oletence, and Ofrection Collection Frequency Frequency Anotysis' 1.

Airborne 1.

Florence, S. C. (Control Stetton)'

Continuous operating Weekly 1-131 for Air Particulates 26 miles ESE e 119*

sempler with sosple certri,dge,u collection et teest and mediolodines 2.

Information Center weekly Weekly Cross sete' O.2 miles S 8 180*

= ---.. --

3.

Microueve tower Quarterly Gemme Scan

0.7 mile N a 5*

of compoelte (by location) 4.

Spittwey 0.4 mile ESE S 110*

5.

East Shore of take across from plant intake Johnson' Landing 0.9 mile ENE a 73*

6.

Information Center 0.3 mite su a 214*

7.

CP&L Nortsvitte othetetton, 6.3 miles ESE 8 109' 55.

South of the West Settling Pond

.3 altes SSE a 159' 2.

Direct 1.

Florence, S. C. (Controt Stetten)'

Continuous measurement Guarterly Gamma Dose' Radletion 26 miles ESE G 119' \\

with reedout et least once per quarter (TL0s) 4-2 Rev. 10 HBRODCM t

' Unned States Nuclear Regulatory' Commission to Senal: RNP-RA/95-0159 Page 131 of 172 Table 4.0-1 (Continued) i H. B. ROBINSON RADIOLDGICAL ENVIRONMENTAL MONITORING PROGRAM l

~

Esposure Pethisey Seepte Seaple Point Description, Seepting and Analysis' and/or Seepte Point Olstence, and Direction Cottecttwi Fregaency Fregaency Anotysis' 2.

Direct medletion 2.

Information Center contirmaous measurement euerterly W Dose' (continued) 0.2 mite 5 a 180*

with reedout et teest

+

once per quarter 3.

Microueve tower (TLDs) f 0.7 mile N a 5*

l B

~

4.

SplILucy 0.4 mile ESE a 110*

5.

East shore of take across from plant intake Johnson's tending 0.9 mile ENE a 73*

t 6.

Information Center 0.3 mile SW 8214' 7.

CP&L Martsvltte sL4 station 6.3 miles ESE a 109*

I 8.

Trenomission tower

?

0.8 mile SSE.

5 9.

Trenomiselon tower t

1.0 mite S.

10.

The Church of God caqatory 1.0 mile WSW 11.

Old Camden aced 1.0 site SW.

12.

Tree 1.2 miles SSW.

i I

4-3 Rev. 10 HBRODCM k

- Uniied Siaies Nkisar Megularnry Oynmeccum

~ -

-- ~- -

'-~ to Serial: RNP-RA/95-0159 1

Page 132 of 172 Table 4.0-l'(Continued)

H. B. ROBINSON RADIOIDGICAL ENVIRONMENTAL MONITORINC PROGRAM

\\

l Esposure Pethisey Semple.

Semple Point Description, sempting and Anotysis' and/or Seepte Point Distence, and Direction Collection Fregaency Frequency Analysis' i

2.

Direct Radletion 13.

Tree 1.0 mile W.

. Continuous measurement euerterly Samma Dese' (continued) with reedout et toest 14.

Nighuey 151 et Pine Ridge Church once y p rt w O.9 alle WNW.

(TWs) s 15.'

Tree directly adjacent to ash pond on CP&l, proper 1y 1.0 miles W.

16.

Dertington Comty I.C. Turbine Plant I-1.0 mite NNW.

17.

1.0 mite down Ol4 charge cenet road at Old Unit one Weir 1.1 miles N.

18.

giock Creek 0.7 mite SE.

)

19.

Road 85-16-23 1.0 mite E.

}

20.

Road 85-16-39 1.3 mites ENE.

i i

i 21.

Atkinson's tending 1.4 miles NE.

22.

Shady Rest Clih 1.9 miles NNE.

23.

Road 85-16-39 1.2 mites ESE.

24.

Road es-13-711 5.0 mites w.

?'

l.

HBRODCM 4-4 Rev. 10 t

I

= - -

. United States Nuclear Regulatory Commission

- to Serial: RNP-RN95-0159 Page133 of 172 Table 4.0-1 (Continued):

H.

B. ROBINSON RADIOLOGICAL ENVIRONMENTAL MONJTORING PROGRAM Esposure Pethuey semple sempte Point Description, Seepting and Anotysis' and/or semple Point Distence, and Direction collection Frequency Fre p ncy Analysis' 2.

Direct Redletion 25.

Road es-13-346 4.6 miles muW.

Continuous measurement euerterly Gumme Dose" (continued) with reedout at least 26.

Road #S-13-346 5.0 miles M.

once per p rter 27.

Road #S-13-763 5.0 miles MNE.

28.

Road es-13-39 4.8 miles NE.

29.

Road SS-16-20 4.1 mile ENE.

30.

Road 85-16-20 4.6 mites E.

31.

Lakeshore Drive 4.6 miles ESE.

32.

Trenomission 4.5 miles SE.

33.

Road #s-16-493 4.6 miles $5E.

34.

Trenomission pote on Road

s-16-TT2 4.6 miles S.

l

'N.

I 1

I i

l

(

HBRODCM 4-5 Rev. 10 l

i

I Unimed States Nuclear Regulatory Commission to Serial: RNP-RN95-0159 Page 134 of 172 Table 4.0-1 (Continued)

H. B. ROBINSON RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM t

Emposure Pathuey Sample Sample Point Description, Seepting and Anotysis' I

an#or Sample Point Distence. and Direction Collection Frequency Frequency Analyels' l

2.

Direct Radletion 35.

Power pole on Road SS-31-51 C::,cInuous measurement euerterly ca=== Dose' l

(continued) 4.4 miles SSW.

With reedout at toest once per quarter 36.

Power pote 3/4 mile doun (TLDs) paved road off Road 85-16-85.

4.7 miles SW.

1 l

37.

Traneelselon tower 5.0 miles WSW.

38.

Road S-16-231 next to union Church 4.9 alies W.

39.

Power Pole 5.0 elles WuW.

t 55, South of the West settling Pond

.3 mites SSE 8 159' 3.

Waterborne 40.

Black Creek at Road 1623 Composite sempte*

Monthly a==== Scen*

l

e. Surface Water 0.6 elle ESE (Indicator).

over one-month period u.3 41.

Stock Creek (Control Stetton)*

7.2 mites uuW.

l

b. Grounducter 40.

Artesten well Grab Sample Monthly Gesem Scen*

i 0.6 miles ESE.

g.3 42.

Unit 1 deep wett 43.

untt 2 deep wett

c. Drinking unter not required'

d. Shoreline 44.

East Shore of Lake,\\ Shady Rest Semiennuelty Seelannuelty Gemme Scen*

Sedleent Club 1.9 elles muE. '

I l

I I

a t

t 4-6 Rev. 10 tlBRODCM t

6

[

United States Nuclear Regularnry Commission to Serial: RNP-RA/95-0159 i

Page 135 of 172 I

Table 4.0-1 (Continued)

H.

B. ROBINSON RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 5

Exposure Pathway Sample Sample Point Description, Sampling and Anotysis' and/or Sample Point Oletence. and Direction Cottection fregJency Frequency Anotysis' 4.

Ingestion 54.

Asurndete Farm. 10 miles E.

Semimonthly den Semimonthly cm=== Scan

and animals are on posture; when ontmots I-131 analysis semi-l

a. Nilk 63.

Cmningham Fars 18.4 miles ESE monthly a other times are on posture; monthly den animals (Control Stetton for allk).

monthly a are on posture; monthly other times 8 other times f

Indicator Mith Sample Location I

(There are no milk samples evaltable within 8 Km of Plant.

I The following broad-teef vegetetton are to be sampled and analyzed.)

groedtesf 50.

SSE Close to Site Soundary'.

Monthly when avaltable Each sample Gamunn Scan *

(3 different kinds of I-131 51.

SSW Close to Site soundary'.

broad-teef vegetetton) 52.

110 miles W, near Bethune (Control Stetton for Broad-teef vegetetton).

t

b. Fish 45.

Site varies within take Robinson Sealannually (cottect Each sample Gesum Scan

cosperable species at Edible. port.lon 46.

Prestwood take 4.9 miles ESE.

att three tocations)

=

I 47.

See Lake (Control station)' 13 miles W or May Lake 12.5 mites mW.

c. Food Products 54.

A 4urndate Plantation

Annual at harvest Each sample Gamusa Scan

t teefy 10.1 miles E. (One sample of each vegetables principet etess of irrigeted food prockscts).

t l

4-7 Rev. 10 HBRODCM I

o

7. United. States Nuclear Regulatory Conunission

! - Enclosure 2 to Serial: RNP-RA/95 0159 '

? Page ~136 of 172 e

i s

1 i-4 j.'

i rmune ss

'~

nAoiotooscAL sawts 8

O -! g j t.ocATsons nsAn stra r

fj

~~

l l.

.j.

Q.,r *

' =

j pc 4

s n.

I 9,}

e g

J, 4.

j v.

i

/,4 j

/..

g

/

s s

s g

s s

6

. s.-

o g

l m

s T

j-s l

@?

's N --

y r

/

1.-

.DMV@

l.,

\\

g's s

I l

v l\\

%s s

/

8,

\\

/

i g

l

%'s a

1 J

l g

l

,.'* s a

s Ig----

e f

g 1./

y% f o

r g

g'

?.

{,

%'s f %.l'

'~

\\

l

'. '%pJ i@

o' i

s 1-

[g i\\\\ s s

4 e

vT a

l OI.

1 l

l.

4 ed i

t HBRODCM 49 Rev. 10

-~'

~~ ~

's 19 t

<II

\\

/ 'i<

41 FIGURE 4 2 hg

,y RADIOLOGICAL SAMPLE j

/

DISTANT LOCATIONS I

\\

T

\\q

\\

j

,(

]

-(

%s.

i e

e N

/ei (s

s Ea

),

C'.

'(

tm 5

/

- g l

)',

\\

(k r

N w

>o g

,ia

)

n 9

N J

1 09

)

i i

\\

z 8

c ei 11 i

a3 y(

3 gaf 1

\\

s.

a' il.go i

n

-' g g*

eg.g.@

e s

p e

85E

\\

{1 l United States Nuclear Radamry Commissisn i Enclosure 2 to Serial: RNP-RA/95-0159

! Page138 of 172 I

APPENDIX A l

METEORO!ACICAL DISPERSION FACTOR COMPUTATIONS i

Carolina Power & Light tompany (CP&L) engaged the services of Dames & Moore to assess the transport and dispersion of the affluent in the atmo. sphere as outlined in Preoaration of Radiolomical Effluent Technical Soecifications for Nuclear 1

Power Plants. NUREG 0133 (USNRC 1978). The methodology for this assessment was based on guidelines presented in Regulatory Guide (RC) 1.111, Revision 1 (USNRC The results of the assessment were to provide the relative deposition-1977).

flux and relative concentrations (undepleted and depleted) based on numerical i

models acceptable for use in Appendix I evaluations.

f Regulatory Guide 1.111 presented three acceptable diffusion models for use in estimating deposition flux and concentrations. These were (1) particle-in-cell model (a variable trajectory model based on the gradient-transport theory), (2)

, puf f-advection model (a variable trajectory model based on the statistical f

approach to diffusion), and (3) the constant mean wind direction model referred i

to here as the straight-line trajectory Gaussian diffusion model (the most widely i

used model based on a statistical approach).

It was resolved that for operational efficiency, the straight-line described in XOOD00 Prorram for the Meteoroloeical Evaluation of Routine Effluent Releases at Nuclear Power Stations i

(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, terrain / recirculation correction factors (TCF) were to be determined from a combined puff-advection/ straight-line i

scheme for a one year meteorological data base.

l Dames & Moore was provided a one-year record of meteorologica?. data from the on-These

)

site meteorological program at the 11. B. Robinson Steam Electric Plant.

data consisted of all collected parameters at both the 11.03-meter and 62.39-4 i

meter tower levels for the year 1977.

Dames & Moore computed dispersions and depositions using the model described in the reference.

The following tables a

from the reference provide the basis-for the meteorological dilution factor development of the technical specifications for Appendix I and were the source of the X/Q and D/Q values used to show compliance with 10 CFR 20 and 10 CPR 50

)

for noble gases and radiciodines and particulates.

i

]

HBRODCM A-1 Rev. 10

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 139 of 172 Tables A-1 through A-6 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for ground level and releases,for both standard distances special locations for long-term rele,ases.

^

Tables A-7 through A-9 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for ground level releases for special locations for short-tern releases.

i l

The X/Q and D/Q values which are used in Appendix B for showing compliance with

~10 CFR 20 and 10 CFR 50 when the HBR Plant vent has been modified such that it i

qualifies as a mixed mode release were based upon the following tables:

1 Relative undepleted concentration, relative j

Tables A-10 through A-15 depleted concentration, and relative deposition flux estimates for elevated release for both standard distances and special locations for long term releases, f

Tables A-16 through A-18 Relative undepleted copcentration, relative depleted concentration, and relative deposition flux estimates for mixed mode releases for special locations for short-term releases. It should be noted that the short-term releases were based upon 100 h.

hours per year of containment purges.

1 Future Operation Comoutations The NRC "XOQDOQ" Program (Revision 1) was obtained and installed on the CP&L computer system.

In general, Dames & Moore concluded that the straight-line model is as reasonable a projection of concentrations as the puff-advection n

HBRODCM A Rev. 10

i United States Nuclear Regulatory Comminion to Serial: RNP-RA/95-0159 i Page?40 of 172 By inclusion of the terrain correction factors developed by a combination model.

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

For routine meteorological dispersion evaluations, the "XOQD0Q" Program will be I

l run with the appropriate physical plant data, appropriate meteorological information for the standard distances, and special locations of interest without

- a terrain / recirculation factor. The resulting computations will have applied the j

The input TCFs to prodace a final atmospheric diffusion estimate for the site.

i to "X0QDOQ" for ground level releases at HBR are presented in Table A-19 and for mixed mode releases at HBR in Table A-20.

l Reference Chandler, Martin W. and George Hoopes, Revised Radiological Effluent Technical Gaseous Effluent Dilution Factors, Prepared for Carolina Power Specifications.

18, 1979.

& Light Company, Robinson Facility, Dames & Moore, January 1

,/

1

?

1 i

A-3 Rev. 10 4

HBRODCM

=-

United, States Nuclear Regulatory Commission to Serial: RNP-RA/95 0159

Page 141 of 172 TABLE A-3

~ )* '

D/Q Values for long-Term Ground Level Releases at Special'I4 cations (m i

J Carolina Power & Light Company - Robinson Release Type: Annual

. Release Mode: Ground level Variable:. Relative Deposition Rate (Meter" )

Calculation Points:

Special l

Model:

Straight Line (ANNKOQ9)

Yes Application of Terrain Correction Factors:

Number of Observations: 8703

)

Affected Site Sector Boundary 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 3.70E-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 Zeroes indicate that this point was not calculated

- A milk goat is located here H8RODCM' A-6 Rev. 10 l

~

i l

United States Nuclear Regulatory Commissinn Encio8ure 2 to Serial: RNP-RA/95-0159

Page 142 of 172 TABLE A-6 i

D/Q Values for Long-Term Ground Level Releases at Standard Distances (m' )

1 i

Ccrolina Power & Light Company Robinson i.

Rolease Type: ~ Annual Release Mode: Ground Level

[

Variable: Relative Concentration (Meter 2) i Calculation Points:

Standard-l

~ M: del:. Straight Line (ANNX0Q9)

Yes i

Application of Terrain Correction Factors:

Number of Observations: 8703 BASE DISTANE IN NILES/KILGIETBts f

l

. Aftd ; Deslyi sect Diet

.25

.75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 NI 40 1.21 2.01 2.82 3.42 4.42 5.25 6.05 6.84 7.44 1

mut 0.

1.3E 07 2.4E-08 9.3E 09 4.8E-09 3.0E-09 2.0E 09 1.2E-09 8.2E 10 5.4E 10 3.4E 10 l

NE 0.

7.1E 08 8.9E 09 3.4E 09 1.8E 09 1.0E 09 6.5E-10 4.6E 10 3.4E 10 2.6E 10 2.0E 10

]

ENE 0.

5.5E 08 9.6E 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 D.

5.0E 08 8.2E 09 3.2E 09 1.6E 09 1.1E 09 6.9E-10 5.1E 10 3.6E 2.5E 10 1.8E 10 l

SE 0.

'4.8E 08 7.0E 09 3.1E 09 1.5E 09 8.6E 10 4.5E 10 3.1E 10 1.8E 10 1.5E 10 1.2E-10 f

Sst O.

8.2E 08 1.3E 08 5.2E 09 2.6E 09 1.4E-09 7.7E 10 4.9E10/3.9E10 3.0E 10 2.5E 10 S

0.

4.8E 08 6.3E 09 2.2E 09 1.2E 09 4.8E 10 3.5E 10 2.6E 10 1.9E 10 1.6E 10 1.2E 10 j

SSW 0.

7.2E 08 1.4E 08 5.1E 09 2.0E 09 1.1E 09 6.8E 10 4.5E 10 3.2E*10 2.3E 10 1.8E 10 SW 0.

4.2E 08 6.5E 09 2.3E 09 1.0E 09 5.7E 10 3.7E 10 2.7E 10 1.8E 10 1.4E 10 1.1E 10 WsW 0.

3.0E 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 i

W 0.

2.7E 08 3.4E 09 1.2E 09 6.1E 10 4.4E 10 2.7E 10 2.0E 10 1.3E 10 8.5E 11 6.?E 11 l

WWW 0.

3.0E 08 3.9E 09 1.4E 09 7.4E 10 5.4E 10 3.7E 10 2.6E 10 2.0E 10 1.4E 10 1.0E 10 w

0.

3.4E 08 5.2E 09 2.2E-09 1.2E 09 6.3E 10 3'.2E 10 1.8E 10 1.5E 10 1.1E 10 9.0E 11 NNW 0.

4.1E 08 7.4E 09 3.6E 09 2.5E 09 1.6E 09 8.0E 10 3.9E 10 2.4E 10 1.5E 10 1.2E 10 N

0.

0 7E 08 1.1E 08 4.1E 09 2.0E 09 1.1E 09 7.2E 10 4.7E 10 3.3E 10 2.5E-10 2.0E 10 e

8703 Number of Valid Observations Number of Invalid Observations 57 398 Number of Calms Lower Level 0

Number of Calms Upper Limit

~H8RODCM' A-9 Rev. 10

United States Nuclear Regulatory Commission

Enclosure 2 to Serial: RNP-RA/95-0159 Pass 143 of 172 TABLE A-7 8

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

l 1

i C rolina. Power & Light Company - Robinson I

};

R31 ease Type: Purge

)

R31 ease Mode: Ground lavel b

Variable:

Relative Concentration (Sec./ Cubic Meter)

)

lCc1culation Points:

Special

.Model:

Purge.(ACNPURG2) l No l

~ Application of Terrain' Correction Factors:

Number.of observations:

8703 3'

Purge Tire:

100 Hours Affected Site S:ictor Boundary Meat Dairy Resident Garden

.NNE 7.20E-06 5.00E-06 0.00 6.80E-06 6.20E-06 NE 5.30E-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 i

'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 i

SSW 2.10E-05 1,30E-06 0.00

/2.00E-05 9.80E.

~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 V'

5.50E-06 3.00E-07 0.00 4.20E-06 4.20E-06 WNW 5.30E-06 3.90E-0?

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 N

2.70E-06 1.50E 06 0.00 1.50E-06 1.50E-06 Zeroes indicate that this point was not calculated

- A tsilk goat is. located here I

i l

l A-10' Rev. 10 HERODCM:

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 144 of 172 TABLE A-8 3

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

Cerolina Power & Light Company - Robinson 1

R31 ease Type:. Purge Release Mode: Ground Level Variable: Relative Depleted Concentration (Sec./ Cubic Meter) 1 Csiculation Points:

Special M: del:

Purge (ACNPURC2)

No Application of Terrain Correction Factors:

Number of Observations:

8703 Purge Time:

100 Hours Affected Site S:ctor Boundary 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 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 W

5.16E-06 2.28E-07 0.00 3.85E-06 3.85E-06 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 NNV 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 i

i Zeroes indicate that this point was not calculated

- A milk goat is located here HBRODCM A-11 Rev. 10

i

United States Nuclear Regulatory Comminnion O Serial: RNP-RA/95-0159 I Page 145 'of 172 TABLE A-9 D/Q Values for Short-Term Ground Level Releases at Special Incations (m' )*

i

~~

Cr.rolina Power (m Light Company - Robinson Release Type:

Purge Release Mode: Ground Level

-Variable: Relative Deposition Race (Meter )

Calculation Points; Special M: deli Purge (ACNPURG2)

No Application of Terrain Correction Factors:

Number of Observations:

8703 Purge Time:

100 Hours Affected Site Sector Boundary Meat Dairy Resident Garden i

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 ENE 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 t-SE 4.25E-08 0.00 0.00 4.19E-08 4.19E-08 4'

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 j -

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 j

NNW

.4.46E-09 1.87E-09 0.00 1.86E-09 1.65E-09 i

N 3.27E-09 1.50E-09 0.00 1.50E-09 1.50E-09 Zeroes indicate that this point was not calculated

- A milk goat is located.here 4

a

~

4 A-12 Rev. 10

.HBRODCM'

LUnited States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 146 of 172 TABLE A-10 3

. X/Q Values for Long-Term Mixed Mode Releases at Special Locations (sec/m )*

C:rolina Power & Light Company - Robinson

.R31 ease Type: Annual Rolease' Mode: Mixed Mode Variable: _ Relative Concentration (Sec./ Cubic Meter)

Calculation Points:

Special M: del:

Straight Line (ANNXOQ9)

Yes Application of Terrain Correction Factors:

Number of Observations:

8703 Affected Site-

. Sector Boundary Nest 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 l

W 9.36E-08 1.87E-08 0.00 7.13E-08 7.13E-08 i

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 i

Zeroes indicate that this point was not calculated

- A milk goat is located here s

6 l

'A-13 Rev. 10 i -

HBRODCM

. ~.

7.-

dnited States Nuclear Regulatory Comminion to Serial: RNP-RA/95-0159 Page 147 of 172 TABLE A-11 Depleted X/q Values for Long-Tern Mixed Mode Releases at Special beations (sec/ab

~

Ccrolina Power & Light Company - Robinson,

Rolease Type: Annual

~

Ralease Mode: Mixed Mode Vcriable: Relative Concentration (Sec./ Cubic Meter)

Calculation Points:

Special M: del:

Straight Line (ANNXOQ9)

Yes Application of Terrain Correction Factors:

Humber of Observations:

8703 Affected Site Sector.

Boundary Heat Dairy Resident Garden 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.

WSW 2.06E-07 4.46E 08 0.00 1.68E-07 9.91E-08 W

9.10E-08 1.82E-08 0.00 6.93E-08 6.90E-08 UNW 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 1.64E-07 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 indicate that this point was not calculated

- A milk goat is located here A-14 Rev. 10 HBRODCM

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 148 of 172 TABLE A-12 D/Q Values for Long-Tern Mixed Mode Releases at Special Locations (m' )*

C rolina Power & Light Company:- Robinson Release Type: Annual Rolease Mode: Mixed Mode Vcriable:

Relative Deposition Rate (Meter' )

Calculation Points:

Special M: del:

Straight Line (ANNX0Q9)

Yes Application of Terrain Correction Factors:

Number of Observations:

8703 Affected-Site Sector Boundary Heat 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 I

N 3.62E-10 1.41E 10 0.00 1.51E-10 1.51E-10

)

Zeroes indicate that this point was not calculated

- A milk goat is located here 1

Rev. 10 A-15 HBRODCM m

7

I l

! United' States Nuclear Regulatory Commission

! Eich mars 2 to Serial: RNP-RA/954159 l Pty 149 of 172 TABLE A-13 a

I/Q Values for long-Tere Mixed Mode Releases at Standard Distances (sec/m )

l l

1 e

Ccrolina Powir & Light Company'- Robinson Ralease Type: Annual 4

i Release Mode: Mixed Mode i

Relative Concentration (Sec./ Cubic Meter)

V:riable:

4 Calculation Points:

Standard Model:

Straight Line (ANNXOQ9)

Yes Application of Terrain Correction Factors:

Number of Observations:

8703 l

SAE DISTANE IN MILES /EILGETERS

.Aftd Design l

sect slet

.25

.75 1.25 1.75 2.5 2.75 3.25 3.75 4.25 4.75 NI

.40 1.21 2.01 2.82 3.62 6.42 5.25 6.05 6.84 7.64

,i i

NME 0.

1.5E 06 3.9E 07 3.1E 07 2.7E 07 2.3E 07 2.0E 07 1.6E 07 1.4E 07 9.8E 08 6.5E 08 NE 0.

1.0E 06 1.5E 07 1.1E 07 9.0E 08 6.7E 08 5.2E 08 7.8E 08 3.8E 08 5.4E 08 3.4E 08 ENE 0.

8.6E 07 2.M 07 1.9E 07 1.7E 07 1.2E 07 1.1E 07 7.4E 08 6.2E 08 4.8E 08 4.2E-08 f

E 0.

7.2E 07 2.6E 07 2.2E 07 2.OE 07 2.1E 07 1.2E 07 9.4E 08 7.0E 05 4.7E 06 3.6E 08 i

9 Est 0.

7.8E 07 1.9E 07 1.7E 07 1.3E 07 1.0E 07 7.6E 08 6.6E 08 4.9E 06 3.8E 06 2.9E 08

' SE 0.

5.9E 07 1.0E 07 7.5E 08 5.1E 08 3.8E 08 2.4E 08 1.9E 08 1.2E 08 1.2E 08 1.1E 08 SSE 0,

1.0E 06 1.8E 07 1.2E 07 8.0E 08 5.4E-06 3.6E 08 2.6E 08 2.3E 08 1.9E 08 1.8E 08 s

O.

5.0E 07 9.4E 08 7.0E 08 5.9E 06 3.5E 08 3.2E 06 2.9E 06 2.5E 08 2.2E 08 1.9E 08 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 06 3.1E 06 3

SW 0.

3.5E 07 9.9E 08 8.8E 08 6.1E 08 4.6E 08 3.7E 08 3.2E 06 2.3E 08 2.0E 08 1.7E 06 Wsu 0.

3.0E 07 6.5E 08 6.2E 08 5.4E 08 5.4E 08 4.1E 08 3.0E 06 2.7E 08 2.4E 08 1.9E 06 f

W 0.

2.4E 07 6.2E 08 6.0E 08 4.9E 08 4.9E 08 3.5E 08 3.0E 0E 2.0E 08 1.5E 08 1.2E 08 WNW 0.

2.8E 07 8.4E 08 8.6E 08 6.8E 08 6.3E 08 5.2E 08 4.2E 08 3.6E 06 3.6E 08 3.4E 06 NW 0.

3.8E 07 1.2E 07 1.5E 07 1.2E 07 9'.2E 08 6.5E 08 4.7E 08 4.1E 08 3.5E 08 2.9E 06 NNW 0.

4.2E 07 1.8E 07 1.4E 07 1.6E 07 1.4E 07 9.2E 08 5.4E 08 3.7E 06 2.5E 08 2.1E 08 l

N 0.

7.8E 07 1.7E 07 t.3E 07 9.M 08 7.2E 08 ' 5.9E 08 4.5E 08 3.8E 08 3.M 06 2.9E 08 8703 haber of Valid observations

=

57 h e er of Invetid observetione

=

60 haber of Cates Lower Levet

=

5 haber of Calas Upper Lielt

_HBRODCM A-16 Rev. 10 i

United States Nuclear Regulatory Comminaian Enclo8ure 2 to Serial: RNP-RA/95-0159

- Page 150. of 172 I

J TABLE A-14 l

8 Depleted I/Q Values for Long-Tern Mixed Ysode Relasses' at Standard Distances (sec/m )

1 l

1 0

l'

C rolina Power & Light Company - Rob nson i

R21 ease Type: Annual' I

R21 ease Mode: Mixed Mode Variable: Relative Depleted Concentration (Sec./ Cubic Meter) i Calculation Points:

Standard N del:

Straight Line (ANNX0Q9)'

Yes Application of Terrain Correction Factors:

j.

f Number of Observations:

8703 l

BAE DISTANE IN NILES/EILWETERS Aftd Desist Sect Piet

.5

.75 1.5 1.75 2.5 2.75 3.5 3.75 4.5 4.75 j

at 40 1.21 2.01 2.82 3.62 4.42 5.5 6.85 6.84 7.64 j

MNE 0.

1.5E 06 3.7E 07 3.1E 07 2.5E 07 2.2E-07 1.8E-07 1.5E 07 1.3E 07 8.9E 08 6.1E 08 s

A NE 0.

9.8E 07 1.4E 07 1.1E 07 8.5E 08 6.4E 08 4.9E 08 7.8E 08 3.6E-08 5.2E 08 3.1E-08

[

ENE '

O.

8.3E 07 2.5E 07 1.8E 07 1.6E 07 1.2E 07 1.0E-07 6.9E 08.5.7E 06 4.5E 08 4.0E 08 l'

E 0.

7.0E 07 2.4E 07 2.0E 07 1.9E 07 2.1E 07 1.1E 07 9.4E 08 6.6E 08 4.5E 08 3.4E-08 i

ESE 0.

' 7.3E 07 1.8E 07 1.6E 07 1.2E 07 9.6E 08 7.2E 08 6.1E 08/ 4.6E 08 3.6E 06 2.7E-08 SE 0,

5.7E-07 9.6E 08 6.9E 08 4.7E-08 3.6E 06 2.3E 08 1.8E 08 1.2E 08 1.06 06 9.9E 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 S

0, 4.8E 07 8.9E 06 6.7E 08 5.8E 08 3.8E 08 3.1E 08 2.7E 06 2.4E 08 2.1E 08 1.8E 06 l

l.

SSW 0,

6.1E 07 2.5E 07 2.4E 07 1.5E 07 1.1E 07 8.0E 08 6.0E-08 4.5E-08 3.4E-06 2.9E-08 SW 0.

3.4E 07 9.5E 08 8.5E 08 5.8E 08 4.4E 06 3.6E 08 3.1E 06 2.2E 08 1.9E 08 1.6E 08 f

j

' WSU 0.

2.9E 07 6.3E 08 6.1E-08 5.2E 08 5.2E 08 4.0E 08 2.9E 06 2.6E 06 2.2E 08 1.8E 08

~

W 0.

2.4E 07 6.0E 08 5.9E 08 4.8E 08 4.7E 08 3.4E 08 2.9E-06 1.9E 08 1.4E 08 1.2E 06 1

WWW 0.

2.6E-07 8.3E 08 U.4E OS 6.6E-08 6.2E 08 5.0E 08 4.0E 08 3.4E-06 3.4E-08 3.2E 08 W

0.

3.8E-07 1.1E 07 1.5E 07 1.1E 07 9.0E 08 6.M 08 4.5E 08 3.9E 08 3.0E-06 2.4E 06 f

NNW 0.

4.1E 07 1.2E 07 1.4E 07 1.6E 07 1.4E 07 8.8E 08 5.2E 06 3.5E-06 2.4E-08 2.0E 08 N

0.

7.5E 07 1.5E 07 1.2E 07 8.8E 08 6.9E 08 5.7E 08 4.3E 08 3.6E 08 3.1E-06 2.7E 08 1

8703 leumber. of vetid cheervations

=

a 57

-leumber of Invetid cheervations a

60 lausher of Cetus Lower Lovet letadser of Cetus uppee Limit-

=

5

~~

d Rev. 10 A-17 liBRODCM

~

i A.

United States Nuclear Regulatory Commission -

Enclo8ure 2 to Serial: RNP-RA/95-0159 -

--Page 151 of 172.

TABLE A-15

-a)

D/Q. Values for lang-Tern Mixed Mode Releases at Standard Distances (m Carolina Power.& Light Company - Robinson

~

Ralease Type:. Annual E21 ease Mode: Mixed Mode

-V riable: Relative Deposition Race (Meter-2) f Csiculation Points:

Standard-M: del: Straight Line ~(ANNXOQ9)

Yes Application of Terrain Correction Factors:

Number of Observations:

8703 l

OAsE DISTANCE IN NILES/EILOIETERS Aftd Design Sect Diet

.5

.75 1.5 1.75 2.5 2.75 3.5 3.75 4.5 4.75 al 40 1.21 2.01 2.82 3.62 4.42 5.5 6.5 6.84 7.64 NME 0.

1.6E 08 5.0E 09 2.1E 09 1.2E 09 7.5E-10 5.2E 10 3.4E-10 2.7E-10 2.0E 10 1.4E-10 NE 0.

1.1E-08 2.6E 09 1.2E 09 6.2E 10 3.5E-10 2.M 10 1.8E 10 1.2E 10 1.2E-10 1.0E 10 ENE 0.

1.1E 08 3.8E 09 1.4E 09 7.6E 10 3.7E 10 2.7E-10 1.8E 10 1.4E-10 1.2E 10 1.1E 10 E

0.

1.1E CS 3.7E 09 1.4E 09 7.2E 10 5.0E-10 2,6E 10 2.1E 10 1.4E-10 1.0E 10 7.8E 11 Est O.

8.6E-09 2.7E 09 1.2E 09 6.7E 10 4.M 10 2.8E-10 2.1E 10.- 1.5E 10 1.0E 10 7.M 11 SE 0.

7.0E 09-1.9E 09 9.5E 10 4.7E 10 2.8E 10 1.5E 10 1.1E 10 5.9E 11 5.0E 11 4.2E 11 SSE 0.

6.2E 09 1.8E-09 8.6E 10 4.6E 10 2.6E 10 1.5E 10 9.5E 11 7.7E 11 5.9E 11 5.0E 11 s

0.

7.1E 09 1.8E 09 7.6E 10 4.2E-10 1.8E 10 1.M-10 9.9E 11 7.M 11 6.1E 11 4.8E 11 SSW 0.

1.0E 08 5.0E 09 2.6E 09 1.1E-09 6.1E 10 3.9E-10 2.6E 10 1.8E 10 1.M 10 1.0E 10 SW 0.

5.0E 09 2.0E 09 9.8E-10 4.7E 10 2.9E 10 1.9E-10 1.5E 10 9.8E 11 7.6E 11 6.4E 11 i

h WSW 0.

4.9E 09 1.9E 09 8.4E 10 4.8E 10 3.7E 10 2.M 10 1.5E 10 1.2E 10 1.0E-10 7.1E-11 W

0.

4.0E 09 1.4E 09 6.M 10 3.4E 10 2.6E 10 1.6E 10 1.M 10 7.9E 11 5.4E 11 4.1E 11 WNW 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 NW 0.

5.6E 09 2.2E 09 1.1E 09 6.4E 10 3.6E 10 1.9E 10 1.2E-10 1.0E 10 1.1E 10 9.6E 11 NIM 0.

4.5E-09 1.9E 09 1.1E 09 8.1E 10 5.2E-10 2.7E 10 1.4E-10 8.8E 11 5.7E-11 4.5E 11 N

0.

5.9E 09 1.8E 09 8.2E-10 4.0E 10 2.4E 10 1.6E 10 1.0E 10 7.4E-11 5.8E 11 4.7E 11 g

8703 i '

thaber of vetid observations'

=

a 57 thsher of Irwelid cheervations

=

60 thaber of Calms Lower Levet

=

5 skaber of Calms upper Lielt

g i

HERODCM A-18 Rev. 10 i

m

United States Nuclear Regu1==y Commission Rel-we 2 to Serial: RNP-RA/95-0159

' Page 152 of 172 TABLE A-16 8

1/Q Values for' Short-Teru Mixed Mode Releases at Special locations (sec/a )*

Carolina Power & Light Company - Robinson Rslease' Type:

Purge Release Mode: Mixed Mode

_Veriable: Relative Concentration (Sec./ Cubic Meter)

Calculation Points:

Special Model:

Purge, (ACNPURG2)

No Application of Terrain Correction Factors:

Number of Observations:

8703 Purge Time:

100 Hours Affected site Sector Bewudary nest Seiry Reeldent

$ sedan 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 8.00E 07 3.10E 07 E

1.00E-06 4.00E 07 2.50E 07 9.20E 07 4.50E 07 Est 1.24E 06 4.70E 07 0.00 1.00E 06 1.00E-06 f

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 f

ssW 2.00E 06 4.00E 07 0.00 ft.00E-06 1.10E 06 SW 1.10E 06 2.40E 07 2.10E 07**

' 9.50E 07 T.70E 07 l~

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 WWW 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 I

NNW 5.10E 07 3.20E 07 0.00 3.10E 07 2.90E 07 N

3.50E 07 2.30E 07 0.00 2.40E 07 2.40E 07 I

Zeroes indicate that this point was not calcuteted

- A milk goet is located here i

4 J

P HRRODCM

.A-19 Rev. 10 4

Onited States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 153 of 172 TABLE A-17 Depleted I/Q Values for Short-Term Mixed Mode Releases at Special locations (sec/m*)*

Carolina Power & Light Company - Robinson Release Type:

Purge R;1 ease Mode: Mixed Mode Variable: Relative Depleted Concentration (Sec./ Cubic Meter)

Calculation Points:

Special M: del:

Purge (ACNPURG2)

No Application of Terrain Correction Factars:

Number of Observations:

8703 Purge Time:

100 Hours Affected Site sector sawdery Most Delry Reeldent Garden NNE 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 f

5 1.82E 06 1.90E 07 0.00 1.63E 06 1.12E 06 ssW 1.93E De 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 WW 7.65E 07 2.09E 07 0.00 6.59E 07 6.04E-07 W

6.24E 07 4.99E 07 0.00 6.20E 07 6.20E-07 NW 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 2eroes indicate that this point was not calculated

- A allk goat is located here HERODCM A-20 Rev. 10

~

Eac1osure 2 to Serial: RNP-RA[95-0159

~

Page154 of 172 TABLE A-19 Robinscu Plant Site Information To Be Used for Ground Level Calculations with NRC "XOQDOQ" Program CARD TYPE COLUMNS DESCRIPTION VALUE TO BE USED IN 100D00 1

1 Print input data 1

38 Calculate annual X/Qs for points of interest 1

39 Calculate annual X/Q averages for site radial segments t

41 Print out set distance X/Qs and D/Qs 1

55 Calculate annual D/Q averages for the set radial segments 1

56 Allow depleted X/Qs (if Decays (1). (2), or (3) are negative) 1

$8 Calculate annual D/Qs for points of interest 1

2 1-80 Title card N/A 3

1-5 Number of wind velocity categories 7

6-10 Number of stability categories 7

11-15 Number of distances within terrain data for each sector 5

16-20 Total number of hours in joint wind frequency distribution (1) 21-25 Increment in % for which plotted results are to be printed 5

26-30 Number of titles of receptor types 5

31-35 Number or release exit locations 3

4 4

1-5 Height of the measured wind (meters) 11 6-20 Half-life (days) used in the X/Q calculations 101.00

'N 226

-8.00 5

N/A N/A 6

1-80 Joint wind frequency distribution (1)

HBRODCM A-22 Rev. 10 t

_.. ~.. _ _ -..

Unimed States Nuclear Regulatory Conuniction to Serial: RNP-RA/95-0159 Page 155 of 172 TABLE A-19 (Continued)

CARD TYPE COLUMitS DESCRIPTION VALUE TO BE USED IN XOOD00 7

1-5 Wind velocity units correction 200.00 6-75 Maximum wind speed in each wind class (m/sec) 0.75 3.5b 7.50 12.50 18.50 25.00 26.00 8

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

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

-1 Meat-

- 14 l

Residence

- 16 Carden

- 16 I

I

.11 1-16 Title of receptor type for receptor locations Site Boundary Dairy i

Meat Residence Carden 12 1-80 Receptor direction and distance (Ses Tsole 1) 13 1-80 Title for release point whose characteristics are described (1) on Card Type 14 A-23 Rev. 10 HBRODCM

United States Nuclear Regulatory Comminion to Serial: RNP-RA/95-0159 Page 156 of 172 TAB.LE A-19 (Continued)

CARD TYPE COLUMNS DESCRIPTION VALUE TO BE USED IN XOODOO 14 1-5 Vent average velocity (m/sec) 20.1 6-10 Vent inside diameter (m) 1.0 11-15 Height of vent release point (m) 0.dOO 16-20 Height of the vent's building (m) 59.0 2 25 Minimum cross-sectional area for the vent's building (m )

1370.0 26-30 Wind height used for vent elevated release 11.0 31-35 Vent heat emission rate (cal /sec) 0,0 15 1

Identification for release point A

2-5 Intermittent releases 1

5-10 Number of intermittent releases per year for this release point 100 11-15 Average number of hours per intermittent release 1

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

I A-24 Rev. 10 HBRODpi

m.-._. _ _ _ _ _ _ _. _. _. _ _.

United States Nuclear Regulatory enemienion Paclanne 2 to Serial: RNP-RN95-0159 Page 157_ of 172 TABIZ A-20 Robinson Plant Site Information To Be Used for Mixed Mode Release Calculations with NRC "XOQD0Q" Program CARD TYPE COLUMEIS DESCRIPTION VALUE TO BE USED IN XOQD00 1

1 Print input data 1

38 Calculate annual X/Qs for points of interest 1

39 Calcutate annual X/Q averages for site radial segments 1

1 41 Print out set distance X/Qs and D/Qs 1

55 Calculate annual D/Q averages for the set radial segments 1

56 Allow depleted X/Qs (if Decays (1), (2), or (3) are negative) 1 58 Calculate annual D/Qs for points of interest 1

2 1-80 Title card N/.A L

3 1-5 Number of wind velocity categories

.7 l

6-10 Number of stability categories 7-l 11-15 Number of distances within terrain data for each sector 5

16-20 Total number of hours i.n joint wind frequency distribution (1) l 21-25 Increment in t for which plotted results are to be printed 5

26-30 Number of titles of receptor types 5

I 31-35 Number of release exit locations 3

i N

4 1-5 Height of the measured wind (meters) 11 6-20 Half-life (days) used in the X/Q calculations 101.00 226

-8.00 5

N/A N/A 6

1-80 Joint wind frequency distribution (1) 5 A-25 Rev. 10 HBRODf t

United States Nuclear Regulatory Commision to Senal: RNP-RA/95-0159 Page 158 cf 172 TABLE A-20 (continued)

CARD TYPE COLUMNS DESCRIPTION VALUE TO BE USED IN 100D00 200.00 7

1-5 Wind velocity units correction 6-75 Maximum wind speed in each wind class (m/sec) 0.7p 3.50 7.50 12.50

.18.50 25.00 26.00 8

1-80 Distance in meters at which terrain heights are given (2) 9 1-80 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 1

Dairy Meat

- 14 Residence

- 16 Carden

- 16

.11 1-16 Title of receptor type for receptor locations Site Boundary Dairy Meat Residence Carden 12 1-80 Receptor direction and distance (See Table 1) 13 1-80 Title for release point whose characteristics are described

(1) on Card Type 14 A-26 Rev. 10 HBRODGM

-~

~ ~~ ~ "

~

~'

~^

l United States Nuciar Regulatory Commission to Serial: RNP-RA/95-0159 Page 159 of 172 i

l l

l TABLE A-20 (continued) f i

CARD TYPE COLUMNS DESCRIPTION VALUE TO BE USED IN 100D00 14 1-5 Vent average velocity (m/sec) 20.1 6-10 Vent inside diameter (m) 1.'O 11-15 Height of vent release point (m) 60.7 59.0 16-20 Height of the vent's building (m) 2 21-25 Minimum cross-sectional area for the vent's building (m )

1370.0 26-30 Wind height used for vent elevated release 11.

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

O.

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

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

'N A-27 Rev. 10 HBR0g

United States Nuclear Regulatory Commission

' to Serial: RNP-RA/95-0159

' Page 60 of 172 1

where:

Dose parameter for radionuclide "i" for the inhalation pathway, P

gI ares /yr per pCi/m ;

3 l

A constant of unit conversion; K'

=

108 pCi/pci; 3

The bredthing rate of the infant age group, m /yr, BR The maximum organ inhalation dose factor for the infant age group l

DFA i

for radionuclide "i," ares /pci.

j The age group considered is the infant group.

The infant's breathing rate is taken as 1400 m /yr from Table E 5 of Regulatory Guide 1.109 Revision 1.

The 3

inhalation dose factors for the infant, DFA, are presented in Table E-10 of i

Regulatory Guide 1.109 in units of ares /pci. The total body is considered as an organ in the selection of DFA.

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

Pj, 1.4 x 10'DFA; (R.1-2)

=

l B.1.2 Cround Plane Pathway The dose factor from ground plane pathway is calculated by:

E K'X"DFG I A }'

(B.' 1 -3 )

Pj,

=

3 where:

y Dose parameter for radionuclide "i" for the ground plane pathway, P

gC ares /yr per Ci/sec per a-2; h

K' A constant of unit conversion; e

10s pCi/ Ci; II.

5 of 5

!M

1. s3 3%

e HMRODCM B-2 Rev. 10

United States Nuclear Regulatory Comminion to Serial: RNP-RA/95-0159 Page 159 of 172 TABLE A-20 (continued)

DESCRIPTION VALUE TO BE CARD TYPE COI,UMNS USED IN 100D00 2b'.1 14 1-5 Vent average velocity (m/sec) 1.'O 6-10 Vent inside diameter (m) 11-15 Height of vent release point (m) 60.7 59.0 16-20 Height of the vent's building (m) 2 21-25 Minimum cross-sectional area for the vent's building (m )

1370.0 26-30 Wind height used for vent elevated release 11.

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

O.

15 1

Identification for release point A

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

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

'N b

S A-27 Rev. 10 HBRODjM

i United States Nuclear Regulatory Comnussion

' to Serial: RNP-RA/95-0159 Page 60 of 172 1

where:

Dose parameter for radionuclide "i" for the inhalation pathway, P

gI aren/yr per pCi/m ;

8 A constant of unit conversion; K'

8 10 pC1/ Ci; 3

The bredthing rate of the infant age group, m /yr; BR The maximum organ inhalation dose factor for the infant age group DFAg for radionuclide "i," ares /pci.

1 The age group considered is the infant group.

The infant's breathing rate is taken as 1400 m /yr from Table E-5 of Regulatory Guide 1.109, Revision 1.

The 3

inhalation dose factors for the infant, DFAg, are presented in Table E-10 of Regulatory Guide 1.109 in units of area /pci. The total body is considered as an organ in the selection of DFAg.

The incorporation of breathing rate of an infant and the unit conversion factor i

results in the following equation:

i 1

Pj, 1.4 x 10'DFAj (B.1-2)

=

B.l.2 Ground Plane Pathway The dose factor from ground plane pathway is calculated by:

}

X'X"DFG

$A~*

}

{B.1-3)

Pj,

=

3 l

1 where:

j Dose parameter for radionuclide "i" for the ground plane pathway, l

P gG arem/yr per pCi/sec per m-2; A constant of unit conversion; K'

s lo pCi/pci; l

)

i l

i WRODCM B.2 g,y, to

United States Nuclear Regulatory Comminion to Serial: RNP-RA/95-0159 Page 161 of 172 A constant of unit conversion; K

8760 hr/yr; The radiological decay constant for radinnuclide "i," sec'1; A

The exposure period; t

7 3.15 x 10 see (1 year);

The groGnd plane dose conversiop factor for radionuclide "i,"

DFG 3

8 area /hr per pCi/m.

The deposition rate onto the ground plane results in a ground plane concentration year with radiological decay--the only that is assumed to persist over a operating - removal mechanism for each radionuclida.

The ground plane dose conversion factors for radionuclide "1," DFC, are presented in Table E-6 of 3

Regulatory Guide 1.109, Revision 1.

Resolution of the units yields:

Pj, 8.76 x 10' DFGj I1]*

(B.1-4)

=

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

p. I'I Or IU ) In p g,-A,e' (B.1-5) e Y, (Aj + A,)

where:

Dose parameter for radionuclide "i" for themow milk or goat milk P

b pathway, mres/yr per pCi/sec per a-2; 4

A constant of unit conversion; K'

108 pCi/pci; The cow's or goat's consumption rate of feed, kg/ day (wet Qr weight);

i a

i 6

W d

i United States Nuclear Regulatory Commission 2 Enclosure 2 to Serial: RNP-RA/95-0159 Page 162 of 172 U,p The infant's milk consumption rate, liters /yr; The agricultural productivity by unit area, kg/m*;

i

.Y, The stable element transfer coefficient, pCi/ liter per pCi/ day; F.

i Fraction of deposited activity retained on cow's or goat's feed r

grass; The maximum organ ingestion dose factor for radionuclide =1,=

DFL i

ares /pci; The radiological decay constant fo* <adionuclide ai, =. sec-1; 1

3 The decay constant for removal of activity on leaf and plant A

surfaces by weathering, sec~1; 5.73 x 10~7 see (corresponding to a 14-day half-life);

-1 The transport time from pasture cow or goat to milk to infant, i

3 tr j

sec.

1 l

A fraction of the airborne deposition is captured by the ground plane vegetation cover.

The captured material is removed from the vegetation (grass) by both i

radiological decay and weathering processes.

l Various parameters which were utilized to determine the P values for the cow and i

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, J

DFLg, for the infant's organs. The organ with the maximum value of DFL was used i

in the determination of P for this pathway.

The incorporation of the various i

constants of Table B-1 into Equation B.1-5 results in the following:

./

i J

i i

4 a

eseD

' United States Nuclear Regulatory Commissisn to Serial: RNP-RA/95-0159 Page - 163 of 172 For radiciodines and particulates from cow's milk:

e 4 (B.1 -6 )

18 Aj + A, DFLj

2. 4 x 10 Pj*

=

For radiciodines agd particulates from goat's milk pathway:

=

( B.1 -7.,)

Pj=

2. 8 x 10' Ag + A, DFLj e

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

(B.1-8)

Pr, K'K"'F,Q,U DFL, 0.7 5 (0. 5/H)

=

y where:

Dose parameter for tritium for the cow milk and goat milk P

j; 3

T pathways, Brem/yr per #01/m ;

M i

A constant of unit conversion; K

108 gn/kg; 3

Absolute humidity of the atmosphere, gn/m ;

H

\\

The fraction of total feed that is water; l

0.75 The ratio of the specific activity of the feed grass water to the 0.5 atmospheric water; Maximum organ ingestion dose factor for trii:ium, mres/p01.

DFIE I

t t

i i United States Nuclear Regulatory Commission l Enclosure 2 to Serial: RNP-RA/95-0159 l Page 164 of 172 3

Are Group (a)

Breathine Rate (m /vr)

Infant 1400 l

Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFAs), for the various age groups are given in Tables i

E.7 through E-10 of Regulatory Guide 1.109, Revision 1.

B.2.2 Ground Plane Pathway The ground plana pathway dose factor is calculated by:

I ~'

}

(B.2-2)

Rj, Ij K'K" (SF) DFG,

=

1 f

where:

Dose factor for the ground plane pathway for each identified R

=

radionuclide "i" for the organ of interest, mres/hr per pCi/sec 10 1

per a-s; L

A constant of unit conversion; K'

10' pCi/pci; A constant of unit conversion; l

K" 8760 hr/ year; The radiological decay constant for radionuclide "i," sec-1; 1

3 The exposure time, sec; e

4.73 x los see (15 years);

The ground plane dose conversion factor for radionuclide "i;"

t DFGt 2

ares /hr per pCi/m ;

i

.I k

W

United States Nuclear Regulatory Commission

' to Serial: RNP-RA/95-0159 Page 165 of 172 values is presented in Table E-6 of Regulatory Guide 1.109, j

l A tabulation of DFUi Revision 1.

]

SF The shielding factor (dimensionless);

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

Factor to account for fractional deposition of radionuclide "i."

I t

j For radionuclides other than iodine, the factor I is equal to one.

For t

t may vary.

However, a value of 1.0 was used in radiciodines, the value of I calculating the R values in Table 3.5-2.

5.2.3 Grass Cow or Goat Milk Pathway i

The dose factor for the cow milk or goat milk pathway for each radionuclide for i

each organ is calculated by:

'(~*

}*

~

ff Rs, = Ig K' Or Um != (DFL ), 0 t

pe y

y I

l i

r (1 -e **)

Es, ( 1 - * **)

,-a,e*

(B.2-3) g3_f f,)

Y, Ay, P Ag

)

where:

i

/

i R

Dose factor for the cow milk or goat milk pathway, for each M

identified radionuclide "i" for the organ of interest, erem/yr

{

per pCi/sec per m-2; 4

}

i 1

W

\\

United States Nuclear Regulatory Comminion to Serial: RNP-RA/95-0159 Page 166 of 172 A constant of unit conversion; K'

108 pCi/pci; The cow's or goat's feed consumption rate, kg/ day (wat weight);

Qr U,p The receptor's milk consumption race for age group a, liters /yr; The agricultural productivity by unit area of pasture feed grass, Y,

z kg/a ;

I The agricultural productivity by unit area of stored feed,-kg/m ;

Y, The stable element transfer coefficients, pCi/ liter per pCi/ day; F,

Fraction of deposited activity retained on cow's feed grass; r

The organ ingestion dose for radionuclide "i" for the receptor in (DFL ).

i age group a, mres/pci; A

A

~

E3 The radiological decay constant for radionuclide "1," sec~1; A

3

.The decay constant for removal of activity on leaf and plant A.,

5.73 x 10~7 weathering, sec-1;(corresponding to a 14 day half-life);

surfaces b

-1 sec The transport time from feed to cow, or goat to milk, to c

f receptor, sec; i

i SED e

S.

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 167 of 172 The transport time for harvest, to cow or goat, to consumption, t,

see; Period of time that sediment is exposed to gaseous effluents.

e, -

sec; Concentration factor for uptake of radionuclide "i" from the soil B*

by the edible parts of crops, pCi/Kg (wet weight) per pCi/Kg (dry g

soil);

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

P Fraction of the year that the c'ow or goat is on pasture; f,

Fraction of the cow feed that is pasture grass while the cow is f,

on pasture; Period of pasture grass and crop exposure during the growing t,

season, see; Factor to account for fractional deposition of radionuclide "1."

I t

is equal to one.

For

'For radionuclides other than iodine, the factor 13 However,.a value of 1.0 was used in radiciodines, the value of It may vary.

calculating the R values in Tables 3.5-9 through 3.5-16.

Milk caccle and goats are considered to be fed from two potential sources, Following the development in Regulatory Guide pasture grass and stored feeds.

1.109, Revision 1, the value of f, was considered unity in lieu of site-specific information. The value of f, was 0.667 based upon an 8-month grazing period.

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

i a

/

4 i

i o

4 1

1

)

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 168 of 172 The average time between harvest of stored vegetation and its tn constaaption, see; z

The vegetation areal density, kg/a ;

Y, Period of leafy vegetable exposure during growing season, see; t,

Factor to account for fractional deposition of radionuclide "i."

I t

All other factors as defined before.

For radionuclides other than iodine, the factor I is equal to one.

For t

However, a value of 1.0 was used in radiciodines, the value of It may vary.

Tables 3.5-3 through 3.5-5.

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

and f,,

1.0 and 0.76, in lieu of site-specific data default values for ft These values were obtained respectively, were used in the calculations on R.

t from Table E-15 of Regulatory Guide 1.109, Revision 1.

The concentration of tritium in vegetation is based on the airborne concentration is based on X/Q:

l rather than the deposition. Therefore.the Ri U,#, ) (DFIq), 0.75 (0. 5/N)

(B.2-8)

K'K"# (U,'fg f

+

R,

=

f i

where:

Dose factor for the vegetable athway for tritium for any organ g'

4 of interest, ares /yr per pGi/m l

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

)

j

)

i 4

l a

i

~

I

United States Nuclear Regulatory Commissinn

< to Serial: RNP-RA/95-0159 I Page 169 of 172 94sg 3 1 Parametets For Cow and Goat Milk'Fathways Reference (Res. Guide 1.109. Rev. 1 i

1A131 Parameter 4

i Table E-3 50 (cow)

~

Q, (kg/ day)

Table E-3 6 (goat) 2 0.7 Table E-15 j

Y, (kg/m )

5 (2 days)

Table E-15 1.73 x 10 Tr (seconds)

Table E-15 1.0 (radiciodines) r Table E-15 0.2 (particulates) i (DFL ). (arem/pci)

Each radionuclide Tables E-11 to E-14 i

F (pci/ day per pCi/ liter)

Each stable element Table E-1 (cow) tble E-2 (goat) i 4.73 x 10s (15 yr)

Table E-15 T (seconds) 6 l

Table E-15 2

2.0 l

Y. (kg/m )

Table E-15 2

0.7 Y, (kg/m )

7.78 x 10s (90 days)

Table E-15 en (seconds) 330 infant Table E-5 ap (liters /yr)

U 330 child Table E-5 l

Table E-5 400 teen l

310 adult Table E-5 5

' Table E-15 8

c. (seconds) 2.59 x 10 (pasture) 5.18 x 10 (stored feed) 8 Each stable element Table E-1 g (pCi/kg [ wet weight)

BPer pCi/kg (dry soil])

l P kg (dry soil /m )

240 Table E-15 2

I 4

n.

Rev. 10

~ ~ ~ - " ' "

United States Nucleer Regulatory Commission 1 to Serial: RNP-RA/95-0159 j Page 770 of 172 TABM B-2 Parameters For The Meat Fachway Reference (Rem. cuide 1.109. Rev. 1 h

Farsaster Table E-15 1.0 (radiolodines)

~

Table E-15 r

0.2 (particulates)

Fg (pCi/kg per pCi/ day)

Each stable element Table E-1 Table E+5 0 infant ap (kg/yr) 41 child Table E-5 U

Table E-5 65 ceen 110 adult Table E-5

~

(DFL ), (ares /pci)

Each radionuclide Tables E-11 to E-14 3

Table E-15 2

0.7 Y, (kg/m )

Table E-15 2

2.0 l

Y (kg/m )

}

T (seconds) 4.73 x 10s (15 yr)

Table E-15 3

l 1.73 x lo (20 days)

Table E-15 s

T. (seconds)

J ca (seconds) 7.78 x 10s (90 days)

Table E-15 1

2.59 x 10s (pasture)

Table E-15 i

c, (seconds) 5.18 x 10s (stored feed) l

}

Table E-3 50 Qr (kg/ day)

Each stable element Table E-1 g (pci/kg [ wet weight) l B

Per pCi/kg [ dry soil])

P (kg [ dry soil /m ))

240 Table E-15 2

i I

i i

t aS

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 171 of 172 TA312 3-3 Parameters for The Vegetable Fathway Reference Fareasteg h

(Raa. Guide 1.109 Rav. 1 r (dimensionless) i 1.0 (radiciodines)

Table E-1 1

0.2 (particulates)

Table E-1 (DN). (area /Ci)

Each radionuclide Tables E-ll to E-14 Qr (kg/ day) 50 (cow)

Table E-3 6 (goat)

Table E-3 UL (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 Tt (seconds) 8.6 x 10' (1 day)

Table E-15 (seconds) 5.18 x 108 (60 days)

Table E-15 th Y, (kg/m )

2.0 Table E-15 2

t, (seconds) 5.18 x 10 (60 days)

Table E-15 8

T (seconds) 4.73 x 10 (15 yr)

Table E-15 8

P (kg [ dry soil /m ])

240

/ Table E-15 2

B (pci/kg [ wet weight)

Each stable element Table E-1 pkyr pCi/kg [ dry soil))

I m

D i

1 J

..n uv. 10

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 172 of 172 II, QBl{GES TO THE RADIOACTIVE WASTE SYSTEMS There were no changes to the Radioactive Waste System during this reporting period.

III.

CHANGES TO THE PROCESS CONTROL PROGRAM There were no changes to the Process Control Program (PCP) during this reporting period.

IV.

CHANGES TO THE LAND USE CENSUS There were no changes to the environmental sampling program as a result of the Land Use Census performed in the first six months of 1995.

V.

INSTRUMENT INOPERABILITY The Gas Analyzer, which monitors waste gas streams for potentially explosive mixtures of hydrogen and oxygen, was declared inoperable on November 30, 1993. The analyzer was removed from service when an Engineering Evaluation determined that it was no longer capable of performing " continuous monitoring" as required by plant Technical Specifications. The analyzer is to be upgraded by plant modification #1159 and PIR

92-295 which will replace broken components for which parts are no longer available.

The Gas Analyzer remains out-of-service as of the date of this report.

Compensatory sampling is in progress as required by Technical Specifications for the above inoperability.

VI.

LIOUID HOLDUP TANK CURIE LIMIT There were no outside Liquid Holdup Tanks that exceeded the ten curie limit during this reporting period.

VII.

WASTE GAS DECAY TANK CURIE LIMIT There were no Waste Gas Decay Tanks with a curie content that exceeded the 1.90E+04 curie limit during this reporting period.

VIII.

INDEPENDENT SPENT FUEL STORAGE INSTALLATION The onsite Independent Spent Fuel Storage Installation, Docket No. 72-3/ License No.

SNM-2502, became operational during the first six months of 1989.

See Addendum I for reporting requirements concerning this facility.

United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 1 of 2 SUPPLEMENTS TO PREVIOUS SEMIANNUAL REPORTS TABLE OF CONTENTS Description Pace I.

DISCUSSION 2

i f

i United States Nuclear Regulatory Commission to Serial: RNP-RA/95-0159 Page 2 of 2 1.

DISCUSSION

~There were no changes to previous reports during this reporting period.

~.,

i 1 United States Nublear Regulatory Commission SAddendum I'to Serial: RNP-RA/95-0159

. Page 1.of 4c

,.-s 1

.t 4

f Y

i i

3-i-

Y CAROLINA' POWER & LIGHT COMPANY

-H.

B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 INDEPENDENT SPENT-FUEL STORAGE INSTALLATION 1

h..

SEMIANNUAL ENVIRONMENTAL REPORT JANUARY 1,'1995 - JUNE 30, 1995 d

1 3

FACILITY OPERATING LICENSE NO. SNM-2502 DOCKET No. 72-3 1

f 6

.4 1

h f

= -

United States Nuclear Regulatory Commission Addendum I to Serial: RNP-RA/95-0159 Page 2 of 4 I.

HISTQ&Y OF THE FACI 1 M The Independent Spent Fuel Storage Installation (ISFSI) is located within the Protected Area of H.

B.

Robinson Steam Electric Plant, Unit No.

2.

Currently, the Installation contains eight (8) Dry Storage Canisters.

The initial canister was loaded on 3/16/89 and other canisters were Joaded on 4/11/89, 4/18/89, 4/24/89, 5/2/89, 5/8/89, 6/28/89, and 7/3/89.

II.

EFFLUENT LIMITS AND CONTROLS This Installaticn operates under effluent control limits as required by 10 CFR 72.44.

However, there are, by design of the sealed storage canisters at the ISFSI, no effluent releases.

All H.

B.

Robinson Steam Electric Plant, Unit No. 2 site cask loading and unloading operations and waste treatment will occur at the H. B. Robinson Steam Electric Plant, Unit No. 2 under the specifications of its Operating License (DPR-23).

III.

RADIOLOGICAL EFFLUENT RELEASES A review of the quarterly surveillance tests performed during this reporting period indicatet that no radioactive liquid or gaseous releases occurred during this report period.

IV.

THE ISFSI ENVIRONMENTAL PROGRAM The ISFSI Environmental Program consists of two air samplers and three TLDs about the Installation plus an unaffected air sampler and TLD site 26 miles ESE of the facility.

Two of the environmental TLDs are maintained at the air sampling sites adjacent to the plant boundary. These are located south at 0.2 miles and southwest at 0.3 miles from the ISFSI.

A third TLD site is located 0.1 miles north of the Installation.

The nearest residence is located south to south-southeast approximately 0.25 miles from the facility. Air samplers operate continuously and samples are changed weekly.

TLDs are changed quarterly.

V.

OTHER ENVIRONMENTAL PROGPAMS In addition to the ISFSI Environmental Program, the H.

B.

Robinson Steam Electric Plant, Unit No. 2 Environmental Program is described in Technical Specification 3.17 (see Carolina Power and Light Company, " Technical Specifications and Bases for H.

B.

Robinson Unit No.

2," Appendix A to Facility Operating License DPR-23, Docket No. 50-i 261, Darlington County, S.C.).

For a comprehensive summary of this program and its j

results, see also " Environmental Surveillance Report," H.

B.

Robinson Steam Electric Plant, Unit No.

2 issued in compliance with the above referenced Technical Specification for this report period.

1 1

United States Nuclear Regulatory Commission

' Addendum I to Seriali RNP-RA/95-0159.

' Page 3 of 4.

..VI.

ISFSI ENVIRONMENTAL MEASUREMENTS-A.

Environmental'TLDs.

TLD'fLocation) lat.Qtr.

2nd Qtr.

'(mrem /90 days)

(mrem /90 days) l' (26. miles ESE) -

12.5 13,8 (Control) i 2 (0.2. miles S) 14.1

.13.6

6 (0.3 miles SW)

-15.9 14.4-

56. (0.1: miles ' N) 15.7 13.2'

~B.

' Air-Sampling Gross Beta Measurements - 1st Qtr.

(picocuries;per cubic meter)

Air'Samoler (Location)-

Averace Maximum 1 (26 miles ESE) 2.47E-02 7.75E-02

-- (Cont rol) i j

2-(0.2 miles S) 2.13E-02, 3.36E-02 r

--6 (0.3 miles SW) 2.14E 2.97E-02

)

a

. Gross Beta Measurements - 2nd Qtr.

e (picocuries per cubic meter)

-Air Samoler fLocation)-

Averace li[ximum 1--(26 miles ESE) 2.11E-02 2.60E-02

-(Control) 2 '(0.2 ndles S) 2.07E-02 2.84E-02 j

1-q 6 (0.3 miles SW) 2.14E-02 2.70E-02 I

A-composite analysis of-air samples detected no radionuclides f rom man-made sources-for either quarter.

a 4

M h

oe-w w-w mv---

United States Nuclear Regulatory Commission Addendum I to Serial: RNP-RA/95-0159 Page 4 of 4 VII.

CONCLUSIONS Based on the above measurements performed during this reporting period, it is concluded that the dose issuing from the ISFSI to the most exposed member of the public did not exceed 1 mrem. This is best estimated as presented in the ISFSI FSAR.

VIII.

SUMMARY

This report is subntitted in compliance with ISFSI Specification 1.4.1 as required pursuant to 10 CFR 72.44 (d) (3).

Paragraph III specifies liquid and gaseous releases to the environment.

Paragraphs VI and VII are provided for estimation of potential radiation dose commitment to the public resulting from effluent release.

l D

3 i

l i

l l

l

.

ML20091P443

Text

1.0 INTRODUCTION

2.1 REFERENCES

3.0 6E-07

SUMMARY

Navigation menu

Search