Text

Rev 31 to S023-ODCM, SONGS Units 2 & 3 Odcm
	ML20206E600
Person / Time
Site:	San Onofre
Issue date:	02/27/1998
From:	; SOUTHERN CALIFORNIA EDISON CO.
To:	;
Shared Package
ML13319A872	List: ML13319A871; ML13326A231; ML20206E585; ML20206E600;
References
	S023-ODCM, S23-ODCM, NUDOCS 9905050178
	Download: ML20206E600 (180)
	v • d • e

- - ___ _ __ _ _

t OFFSITE DOSE CALCULATION MANUAL NUCLEAR ORGANIZATION UNITS 2 AND 3 l

\\

l MOENEDCDM S023-0DCM Revision 31 02-27-98 FEB 2 71998 STERLE00PY 9905050178'990429-T PDR ADOCK 05000206!

R PDR (

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00CM TABLE OF CONTENTS PEla LIST OF FIGURES........................... iv LIST OF TABLES v-vi INTRODUCTION vii 1.0 LIQUID EFFLUENTS........................ 1-1 thru l-26 lF 1.1 Concentration........................ 1-1 1.1.1 Specification................... 1-1 1.1.1.1, 1.1.1.2 Surveillances 1-1 1.2 Dose 1-5 1.2.1 Specification................... 1-5 1.2.1.1 Surveillance 1-5 1.3 Liquid Waste Treatment 1-6 1.3.1 Speci fi cation................... 1-6 1.3.1.1, 1.3.1.2, 1.3.1.3 Surveillances.......... 1-6 1.4 Liquid Effluent Monitor Methods of Setpoint Calculation.. 1-8 1.4.1 Batch Release Setpoint Determination......

1-10 1.4.2 Continuous Release Setpoint Determination....

1-15 1.5 Dose Calculations for Liquid Effluents

. 1-23 1.6 Representative Sampling.................

1-26 2.0 GASEOUS EFFLUENTS......................

2-1 thru 2-83 lF 2.1 Dose Rate........................

2-1 2.1.1 Specification...................

2-1 2.1.1.1, 2.1.1.2 Surveillances.............

2-1 2.2 Dose - Noble Gas....................

2-5 2.2.1 Specification..................

2-5 2.2.1.1 Surveillance..................

2-5 2.3 Dose - Radiciodines, Radioactive Materials in Particulate Form and Tritium....................

2-6 2.3.1 Specification..................

2-6 2.3.1.1 Surveillance..................

2-6 S023-0DCM Revision 30 1

05-28-97

l ODCM TABLEOFCONTENTS(Continued)

.P_gg.t 2.4 Gaseous Radwaste Treatment 2-7 2.4.1 Specification.................... 2-7 2.4.1.1 Surveillance

................... 2-7 2.4.1.2, 2.4.1.3 Surveillances 2-8 2.5 Total Dose

........................ 2-9 2.5.1 Specification.................... 2-9 2.5.1.1 Surveillance 2-9.

2.6 Gaseous Effluent Monitor Setpoints 2-11 2.6.1 Plant Stack.................... 2-11 2.6.2 Condenser Evacuation System............. 2-15 2.6.3 Containment Purge.................. 2-18 2.6.4 Waste Gas Header 2-21 2.7 Gaseous Effluent Dose Rate 2-25 2.7.1 Noble Gases.................... 2-25 2.7.2 Radiciodines and Particulates........... 2-26 2.8 Gaseous Effluent Dose Calculation............. 2-28 2.8.1 Noble Gases.................... 2-28 2.8.1.1 Historical Meteorology 2-28 2.8.1.2 Concurrent Meteorology 2-29

'2.8.2 Radioiodines and Particulates........... 2-30 2.8.2.1 Historical Meteorology 2-30 2.8.2.2 Concurrent Meteorology 2-31 2.9 Total Dose Calculations.................. 2-70 2.9.1 Total Dose to Most Likely Member of the Public 2-70 2.9.1.1 Annual Total Organ Dose......... 2-70 F

2.9.1.2 Annual Total Whole Body Dose 2-71 2.9.1.3 Annual Total Thyroid Dose........ 2-72 3.0.-PROJECTED DOSES

........................ 3-1 thru 3-1 3.1 Liquid Dose Projection 3-1 3.2 Gaseous Dose Projection.................. 3-1 S023-00CM Revision 25 ii 02-28-92 t

F~

00CM TABLE OF CONTENTS (Continued)

Page i

4.0 EQUIPMENT

........................... 4-1 thru 4-20 l

4.1 Radicactive Liquid Effluent Monitoring Instrumentation 4-1 4.1.1 Specification.................... 4-1 4.1.1.1, 4.1.1.2 Surveillances 4-1 I

4.2 Radioactive Gaseous Effluent Monitoring Instrumentation.. 4-7 4.2.1 Specification.................... 4-7 p.

4.2.1.1 Surveillance 4-7 4.3 Operability of Radioactive Waste Equipment 4-17 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5-1 thru 5-27 lF 5.1 Monitoring Program 5-1 5.1.1 Specification 5-1 5.1.1.1 Surveillance................... 5-2 5.2 Land Use Census...................... 5-11 5.2.1 Specification 5-11 5.2.1.1 Surveillance................... 5-11 5.3 Interlaboratory Comparison Program 5-12 5.3.1 Specification 5-12 5.3.1.1 Surveillance................... 5-12 i

i 5.4 Annual Radiological Environmental Operating Report 5-13 1

i 5.5 Sample Locations 5-14 6.0 ADMINISTRATIVE,....-.................... 6-1 thru 6-16 6.1 Definitions........................ 1 6.2 Administrative Controls.................. 6-7 6.3 Major Changes to Radioactive Waste Treatment Systems (LiquidandGaseous) 6-9 6.4 Bases........................... 6-10 S023-0DCM Revision 25 iii 02-28-92 E..

..J

1 ODCM LIST OF FIGURES Fiaure Title Pace 1 Site Boundary for Liquid Effluents................

1-7 2-2 Site Boundary for Gaseous Effluents 2-10 i

4-5 SONGS 2 and 3 Radioactive Liquid Waste Treatment Systems..... 4-18 4-6 SONGS 2 and 3 Radioactive Gaseous Waste Treatment Systems 4-19

\\

4-7 Solid Waste Handling....................... 4-20 1

5-1 Radiological Environmental Monitoring' Sampl'e Locations 1 Mile Radius 5-23 k

5-2 Radiological Environmental Monitoring Sample Locations

~

-2 Mile Radius 5-24 5-3 Radiological Environmental Monitoring Sample Locations 10 Miles Radius 5-25 5-4 Radiological Environmental Monitoring Sample Locations F

Orange County 5-26 5-5 ' Radiological Environmental Monitoring Sample Locations San Diego County.......................... 5-27 I

l S023-0DCM iv Revision 31 j

02-27-98 I

i J

r' -

~

ODCN LIST OF TABLES Table Title Pace 1-1 Radioactive Liquid Waste Sampling and Analysis Program..

1-2 1-3 Liquid Effluent Radiation Monitors Calibration Constants..................

1-22 1-4 Dose Connitment Factors A,

. 1-24 i

2-1 Radioactive Gaseous Waste Sampling and Analysis Program

. 2-2 2-3 Gaseous Effluent Radiation Monitor Calibration Constants..................

2-24 2-4 Dose Factors for Noble Gas and Daughters.........

2-33 2-5 Dose Parameters Pa 2-34 2-6 Controlling Location Factors...............

2-35 2-7 Dose Parameters R for Sector P

. 2-36 i

2-8 Dose Parameters R for Sector Q

. 2-39 i

2-9 Dose Parameters R for Sector R

. 2-48 i

2-10 Dose Parameters R for Sector A

. 2-51 i

2-11 Dose Parameters R for Sector B

. 2-53 i

2-12 Dose Parameters R for Sector C

. 2-55 i

2-13 Dose Parameters R for Sector D

. 2-59 i

2-14 Dose Parameters R for Sector E

. 2-61 i

2-15 Dose Parameters R for Sector F

. 2-64 f

i 2-16 Dose Parameters R for Sector G

. 2-68 i

2-17 SYF Controlling Location Factors.............

2-73 2-18 SYF Dose Parameters R1.for Sector D

. 2-74 2-19 SYF Dose Parameters Ri for Sector E

. 2-75 2-20 SYF Dose Parameters Ri for Sector F

. 2-76 2-21 SYF Dose Parameters Ri for Sector G

. 2-80 S023-0DCM Revision 28 y

12-21-95

E ODCM LIST OF-TABLES (Continued) 1 Table Title Pace l

4-1 Radioactive Liquid Effluent Monitoring Instrumentation..

4-2 4-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements................

4-5 4-3 Radioactive Gaseous Effluent Monitoring Instrumentation.

4-8 F

4-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements................

4-12 5-1 Radiological Environmental Monitoring Program......

5-3 5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples..................

5-7 5-3 Maximum Values for the Lower Limits of Detection (LLD)..

5-8 5-4 Radiological Environmental Monitoring Sample Locations..

5-15 5-5 PIC Radiological Environmental Monitoring Locations...

5-21 5-6 Sector and Direction Designation for Radiological Environmental Monitoring Sample Location Map.......

5-22 l

6-1 Operational Modes....................

6-5 6-2 Frequency Nota tion....................

6-6 f

f S023-0DCM Revision 25 vi 02-28-92 a

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (00CM) is a supporting document of the RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (NUREG 0472). The ODCM enumerstes dose and concentration specifications, instrument requirements, as well as describes the methodology and parameters to be used in the calculation of offsite doses from radioactive liquid and airborne effluents.

In order to l

meet release limits, it additionally provides calculations for_ liquid and gaseous effluent _ monitoring instrumentation alam/ trip setpoints. -The environmental section contains a list of the sample locations.for the radiological environmental monitoring program.

The 00CM will be maintained at the Site for use as a document of_ Specifications and acceptable methodologies and calculations.to be used in implementing the Specifications. Changes in the calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents current methodology.

5023-0DCM Revision 21 vii 02-15-90 A

1.0 LIQUID EFFLUENTS 1.1 CONCENTRATION SPECIFICATION 1.1.1 The concentration of radioactive material released from the site (see Figure 1-2) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B. Table II, column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited'to 2 x 104 microcuries/ml total activity.

APPLICABILITY: At all times ACTION:

a.

With the concentration of radioactive material released from the site exceeding the above limits, intnediately restore the concentration to within the above limits.

i SURVEILLANCE REOUIREMENTS

.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 1-1.

.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in Section 1.4 to

? esure that the concentrations at the point of release are m., ntained within the limits of Specification 1.1.1.

S023-00CM 1-1 Revision 22 08-02-90

I TABLE l-1 RADI0 ACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)

Type Frequency Frequency Analysis (4Ci/ml)*

A. Batch Waste P

P Principal Gamma 5x107 Release

Each Batch Each Batch Emitters I-131 1x104 P

M Dissolved and 1x10 -

4 OneBatch/M Entrained Gases (Gama emitters)

P M

H-3 1x104 Each Batch Composite' 4

Gross Alpha 1x10 P

Q Sr-89, Sr-90 5x104 Each Batch Composite' Fe-55 1x104 N_QTE BATCH RELEASE POINTS: Primary Plant Makeup Storage Tanks, Radwaste Primary Tanks, Radwaste Secondary Tanks, Miscellaneous Waste Condensate Monitor Tanks, BlowdownProcessingSump,FFCPDsumps(highconductivity,lowconductivity)and holduptank,ComponentCoolingWaterSump,StorageTankAreaSump,S/GBlowdown.

B. Continuous D

W Principal Gama 5x104 Releases *,

Grab Sample Composite

Emitters I-131 1x104 i

M M

Dissolved and 1x104 Grab Sample Entrained Gases (Gamma emitters)

D M

H-3 1x104 Grab Sample Composite' 4

Gross Alpha 1x10 D

Q Sr-89 Sr-90 5x104 Grab Sample Composite' Fe-55 1x104

!LOTI CONTINUOUS RELEASE POINTS: Turbine Plant Sump *, Blowdown Processing Sump **, S/G O

Blowdown Bypass Line"*, S/G Blowdown, Auxiliary Building Sump.*

S023-0DCM 1-2 Revision 28 12-21-95

7 p

TABLE 1-1 (Continued)

L TABLE NOTATION The LLD is the smallest concentration of radioactive material in a sample that

~a.

will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

I For a particular measurement system (which may include radiochemical separation):

4.66 s*

LLD =

E = V = 2.22 x 10'. Y = exp (-AAt) wherei

\\

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

s. is the standard deviation of the background counting rate or of the

. counting rate of a blank sample.as appropriate (as counts per minute),

E is the counting efficiency (as counts per transformation),

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

8 2.22 x 10 is the number of transformations per minute per microcurie.

Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

The value of s, used in the calculation of the LLD fcr a particular measurement system shall be based on the actual observed variance of the background counting i

rate or of the counting rate of the blank samples (as appropriate) rather than on i

an unverified theoretically predicted variance..

Typical values of E. V, Y and At should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of the measurement system and not as A nosteriori (after the fact) Ifmit for a particular measurement.'

'For a more complete discussion of the LLD, and other detection limits, see the following:

(1) HASL Procedures Manual, NASL-300-(revised annually).

(2). Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40,586-93(1968).

(3) Hartwell, J.

K., " Detection Limits for Radioisotopic Counting Techniques,"

Atlantic Richfield Hanford Company Report ara-2537 (June 22, 1972).

I S023-0DCM i

1-3 Revision 26 12-20-93 l-

-4

TABLE 1-l' (Continued 1 TABLE NOTATION b.

A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquid; released.

c.

To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

d.

A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sampling.

e.

A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.

. f.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean

- that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

Administrative controls shall ensure that only one continuous release point is discharging through a discharge path at any given time. The normal continuous release point via 2(3)RT-7821 is the turbine plant sump.

The first sump when transferring outlying sumps shall be treated as a batch release.

~

- - . Sampling of this flow is not required if at least once per 31 days blowdown bypass isolation valve (S21301MU618 for Steam Generator 2E088, S21301MU619 l

for Steam Generator 2E089, S31301MU618 for Steam Generator 3E088 and

- $31301MU619 for Steam Generator 3E089) is verified locked shut.

S023-0DCM 1-4 Revision 26 12-20-93 1

J

4 1.0 LIQUID EFFLUENTS (Continued) 1.2 PSji[

SPECIFICATION 1.2.1 The dose or dose comitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site (see Figure 1-2) shall be limited:

a.

During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and b.

During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times ACTION:

a.

With calculated dose from the release of radioactive materials l

in liquid effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Comission within 30 days, pursuant to Technical Specification Section j

5.7.2 and LCS 5.0.104.2, a Special Report which identifies the i

cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce the releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 1.2.1.

SURVEILLANCE REOUIREMENTS

.1 Dose Calculation. Cumulative dose contributions from liquid effluents shall be determined in accordance with Section 1.5 at least once per 31 days.

I l

I i

i S023-0DCM 1-5 Revision 30 05-28-97

r i

1.0. LIQUID EFFLUENTS (Continued) 1.3 LIOUID WASTE TREATMENT SPECIFICATION 1.3.1 The liquid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site (see Figure 1-2) when averaged over 31 days, wou O.06 mrem to the total body or 0.2 mrem to any organ.ld exceed APPLICABILITY: At all times ACTION:

a.

With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Technical coecification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Sunnary description of action (s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS

.1 Doses due to liquid releases'shall be projected at least once per 31 days, in accordance with Section 3.1.

.2 During plant operation (Mode 1-4), the appropriate portions of the liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 15-minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.

.3 In' plant shut-down (Mode 5, 6), the appropriate portions of the liquid radwaste.treatreent system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 15-minutes prior to processing liquids unless the appropriate li uid radwaste system has been utilized to process radioactive li uid effluents during the previous 92 days.

Per reactor unit S023-00CM 1-6 Revision 30 05-28-97 v.

saa enoratnac.tAs EDIERATING STATIou emisLass.

N O

OO y

h

\\

y,g p>'

wL 1

(N!

e so-e J

f,

/

j t

1

/.

Dr s-

~.

i SITE BOUNDARY FOR LIOUID EFFLUENTS FIGURE 1-2 S023-0DCM

.7 Revision 29 07-31-96 l

2

1 1.0 LIQUID EFFLUENTS (Ccntinued) 1.4 LIOUID EFFLUENT MONITOR METHODS OF SETPOINT CALCULATION Liquid Radwaste Effluent Line Monitors provide alarm and automatic temination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B, Table II, Column 2 at the release point to the unrestricted area. To meet this specification and for the purpose of implementation of Specification 1.1.1, the alam/ trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied:

C,R '

(1~1) s MPC'"

,F+Rj where:

C, setpoint, representative of a radionuclide concentration for

=

the radiation monitor measuring the radioactivity in the waste effluent line prior to dilution and subsequent release, C1/ml permissible waste' effluent flow rate at the radiation monitor R

=

location, in volume per unit time in the same units as for F dilution water flow in volume per unit time.

F

=

185,000 gpm per circulating water pump (4 total)*

=

17,000gpmpersaltwaterpump(2 total)

=

The design flowrate of each circulating water pump is 205,000 gpm. The value used in the determination of F takes into account factors such as frictional losses, pump inefficiency, and tidal flow, and provides reasonable assurance that the radioactive release concentration is not underestimated.

NOTE:

Since the values of R are much smaller than F, the term (F + R) in equation (1-1) may be replaced by F.

S023-0DCM 1-8 Revision 30 05-28-97 1

i 1.0.LIQUIDEFFLUENTS.(Continued) 1.4 LIOUID EFFLUENT MONITOR METHODS OF SETPOINT CALCULATION (Continued)

MPC,,, = effective effluent maximum concentration permissible limit

-(C1/ml)atthereleasepointtotheunrestrictedareaforthe radionuclide mixture being released:

y (1-2) 1 e

p'

E i.

MPCy, where:

4 4

number of radionuclides identified in sample analysis n

=

fractional concentration of the 1" radionuclide as obtained by F,

=

sample analysis MPC, =

MPC of the 1" radionuclide (10CFR20, App B, Table II, Column 2) 1 Administrative values are used to reduce each setpoint to account for the potential activity released simultaneously from the following release points:

RW,m3

= Radwaste Effluent discharge SG 3

= Unit 2 Steam Generator E-088 SGn.:

= Unit 2 Steam Generator E-089 56 3

= Unit 3 Steam Generator E-088 SG 3

= Unit 3 Steam Generator E-089 B

= Unit 2 Neutralization Sump i

3 B

= Unit 3 Neutralization Sump 3

T

= Unit 2 Turbine Plant Sump 3

T

= Unit 3 Turbine Plant Sump 3

The sum of the administrative values is limited to 1.0 to ensure that the total concentration from all release points to the plant discharge will not result in a release exceeding the limits of 10CFR20 Appendix B, Table II, Column 2 from Units 2 and 3.

The administrative values shall be assigned such that:

(RW,,13 + SG 3 + SGn r +. SGa.3 + SGn.3 + Br + Ba + T, + T ) 5 1.0.

3 The administrative values shall be periodically reviewed based on actual release data and revised as necessary.

S023-0DCM 1-9 Revision 31 02-27-98

i 1.0 LIQUID EFFLUENTS (Cantinued) 1.4.1 BATCH RELEASE SETPOINT DETERMINATION The waste flow (R) and monitor setpoint (C,) are set to meet the condition of equation (1-1) for the MPC,f, limit. The method by which this is accomplished is as follows:

STEP 1:

The isotopic concentration for each batch tank (or sump) to be released is obtained from the sum of the measuredconcentrationsinthetank(orsump)as determined by analysis.

C = % Cy + p,) + p,) + p,) + p,,)

(1-3) where:

totalconcentrationineachbatchtank,pCi/ml C

=

I,C,i = sum of the measured concentrations for each radionuclide, 1, in the gama spectrum, pCi/ml Cr.

Fe-55 concentration as detemined in the previous

=

quarterly composite sample, pC1/ml C,

gross alpha concentration detemined in the previous I

=

monthly composite sample, pCi/ml l

C, Sr-89 and Sr-90 concentrations as detemined in the

=

previous quarterly composite sample, C1/ml C,

H-3 concentratien as detemined in the previous monthly

=

composite sample, or as measured in the sample taken prior to release, pC1/ml 5023-00CM 1-10 Revision 27 12-21-94 i

1.0 LIQUID EFFLUENTS (Continued) 1.4.1 BATCH RELEASE SETPOINT DETERMINATION (Continued)

STEP 2:

The effective MPC (MPC,,) for each batch tank (or sump) is determined using:

MPC'" =

r g/C'

' C,/C '

'C,/C'

' C,,/C '

'C MPC MPC,,

MPC,,

MPC,,,

i g,

where:

MPC,

g MPC,,

the limiting concentrations of the appropriate

=

MPCs, radionuclide from 10CFR20, Appendix B, Table II, f

MPC,,,

Column 2

MPC, NOTE:

For dissolved or entrained noble gases, the concentration shall be f

limitedto2.0E-4yC1/mltotalactivity.

I STEP 3:

The setpoint, C, (pC1/ml) for each batch release radioactivity monitor may now be specified based on the respective values of C, E c, F, MPC,,,, and R to ip provide compliance with the limits of 10CFR20, Appendix B. Table II, Column 2.

STEP 4:

If the monitor reads in CPM, the setpoint may be 4

derived using the applicable calibration constants given in Table 1-3 to correspond to the calculated monitor limit' C,, pCi/ml.

(C,,

Ci/ml)

(1-4a)

CPM,"

(Cal. Const., pCi/cc/ cpm) p S023-0DCM 1 Revision 31 02-27-98

1.0 LIQUID EFFLUENTS (Continued) 1.4.1 BATCH RELEASE SETPOINT DETERMINATION (Continued) 1.4.1.1 RADWASTE DISCHARGE LINE MONITOR (2/3RT7813)

- The value for C, the concentration limit at the detector, is determined by using:

fW,,g) (F) f,C,,)

(1-5)

C, s 3

(R)

MPC,g where:

RWnu Radwaste Effluent discharge administrative value

=

F dilution water flow in volume per unit time

=

185,000 gpm per circulating water pump (4 total)

=

i 17,000gpmpersaltwaterpump(2 total)

Total concentration in each batch sample b

C ID E C,,

=

total ganna isotopic concentration, C1/ml A

typical effluent release rate.

l A, R

=

Yalues of R for each tank are as follows:

Radwaste Primary Tanks 140 gpm (per pump)

=

Radwaste Secondary Tanks 140 gpm (per pump)

=

Primary Plant Makeup Tank = 160 gpm (per pump)

Condensate Monitor Tanks 100 gpm (per pump)

=

IP MPC.,, =

from equation (1-4)

NOTE:

If C, s E c i, then no release is possible. To increase C., increase the iy administrative value RWau, and/or increase dilution flow F (by running more dilution pumps in the applicable discharge structure), and/or k

decrease the effluent flow rate R and recalculate C, using the new RWnu.

F, R as applicable and equation (1-S).

l l

S023-0DCM 1-12 Revision 31 02-27-98 j

t

- 1.0 LIQUID EFFLUENTS (Continued) l THIS PAGE INTENTIONALLY BLANK b

S023-0DCM 1-13 Revision 31 02-27-98

l r

i 1

1.0- LIQUID EFFLUENTS (Ccntinued) 1.4.1.2 NEUTRALIZATION SUMP / FULL FLOW CONDENSATE POLISHER DEMINERALIZER

{

(FFCPD1 SUMP DISCHARGE LINE MONITOR (BATCH) (2RT7817. 3RT7817)

The value for_C (Unit 2) or C (Unit 3), the concentration limit 3

at the Unit 2 or Unit 3 detector, is determined by using:

i

,) ( @,C,,)

(1-7)

C s- @(R) p/MPC,,f) 2 Cs U

3 (R) f/MPCerr) where:

C, instantaneousconcentrationatdetector2RT7817inpCf/cc

=

C instantaneousconcentrationatdetector3RT7817inpCi/cc

=

3 8,

Unit 2 Neutralization Sump administrative value

=

Unit 3 Neutralization Sump administrative value B

=

3 dilution water flow in volume per unit time F

=

185,000 gpmpercirculatingwaterpump(4 total)

=

17,000 gpm per saltwater pump (2 total)

=

q E C,, = total ganna isotopic concentration, Ci/ml, (STEP 1) i Typical release flow rates:

R

=

Neutralization Sump 500 gpm

=

FFCPD High Conductivity Sump 500 gpm

=

FFCPD Low Conductivity Sump 600 gpm

=

FFCPD Holdup Tank 1000 gpm

=

C total concentration in each batch sample, pCi/ml

=

MPC,,, = value of MPC,,, from equation (1-4) for the sample analysis NOTE:

If C, or C,5 I,C,i, then no release is possible. To increase C, or C,

3 increase the administrative value B, or B, and/or increase dilution 3

flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate C, or C using the new Br OF B, F R as 3

2 applicable and equation (1-7) or (1-8).

5023-0DCM 1-14 Revision 30 05-28-97 i...

1.0 LIQUID EFFLUENTS (Continued) 1.4.2 CONTINU0US RELEASE SETPOINT DETERMINATION The waste flow (R) and monitor setpoint (C,) are set to meet the conditionofequation(1-1)fortheeffectiveNPC(MPC,r) limit.

The method by which this is accomplished is as follows:

STEP 1:

The isotopic concentration for the continuous releases are obtained for each release stream (steam generator blowdown, steam generator blowdown bypass, blowdown neutralization sump and turbine plant sump) from the sum of the respective measured concentrations as determined by analysis:

C = % Cy + (C,) + (C,) + (C,) + (C,,)

(1-9) where:

C

= total concentration (pC1/ml)

D,Cg = total gamma activity associated with each radionuclide,1, in the weekly composite analysis for the release stream, pCi/ml C,

= total measured gross alpha concentration determined from the previous monthly composite analysis for the release stream, Ci/ml Cr,

= total Fe-55 concentration as determined in the previous quarterly composite sample for the release stream, pCi/ml C,

= total measured H-3 concentration determined from the '

previous weekly or monthly composite analysis for the release stream, pCi/ml C,

= total measured concentration of Sr-89 and Sr-90 as detemined from the previous quarterly composite analysis for the release stream, C1/ml S023-0DCM 1-15 Revision 30 05-28-97

r_-

1 1.0 LIQUID EFFLUENTS (Continued) 1.4.2 CONTINUOUS RELEASE SETPOINT DETERMINATION (Continued)

STEP 2:

The effective MPC (MPC,,) for each release stream (steam generator blowdown, blowdown neutralization sump,'or turbine plant sump) is determined using:

1 (1-10)

HPC'" =

' C /C'

' C,/C '

'C,/C'

' C,,/C '

g g

+

MPC MPC,,

MPC,,,

g, y

where:

MPC,

g MPC,,

the limiting concentrations of the appropriate

=

MPC,,

radionuclide from 10CFR20, Appendix B. Table II, p

MPC,,,

Column 2

MPC, STEP 3:

The setpoint, C, ( C1/ml) for each continuous release radioactivity monitor may now be specified based on the respective values of C, E c, F, MPC,,,, and R to ip provide compliance with the limits of 10CFR20, Appendix B, Table II, Column 2.

STEP..4:

If the monitor reads in CPM, the setpoint may be lL derived using the applicable calibration constants -

given in Table 1-3 to correspond to the calculated monitor limit C, pC1/ml.

(C,,pC1/ml)

(1-4a)

CPM"**

(Cal. Const., pC1/cc/ cpm)

O l

i S023-0DCM 1-16 Revision 31 02-27-98

1.0 LIQUID EFFLUENTS- (Continued) i 1.4.2.1 NEUTRALIZATION SUMP DISCHARGE LINE MONITORS (2RT7817. 3RT7817)

The vaine for C, (Unit 2) or C (Unit 3),the_concentrationlimit 3

at the 'Jnit 2 cr Unit 3 detector, is detemined by using:

Cs 2

(R) $/MPC,ff)

@3)(F)%C,,)

(1-12) 3 (R) f/MPC,,f) where:

C, instantaneousconcentrationatdetector2RT7817inpCi/cc

=

C instantaneousconcentrationatdetector3RT7817inpCi/cc

=

3 B,

Unit 2 Neutralization Sump administrative value

=

B Unit 3 Neutralization Sump administrative value

=

3

' dilution water flow in volume per unit time F

=

185,000 gpm per circulating water pump (4 total)

=

17,000gpmpersaltwaterpump(2 total)

=

E c,i = total gamma isotopic concentration, pCi/ml, (STEP 1) i R

effluent flow rate, gpm, (STEP 1), (maximum of 500 gpm)

=

C total concentration, pC1/ml

=

MPC,,, = value of MPC,,, from equation (1-4) for the sample analysis NOTE:

If C, or C $ E c,i, then no release is possible. To increase C, or C,.

3 i

3 increase the administrative value B, or B, and/or increase dilution 3

flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate C or C using the new B, or 8, F. R as 2

3 3

applicable and-equation (1-11) or (1-12).

S023-0DCM 1-17 Revision 30 05-28-97

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT6753. 2RT6759. 3RT6753. 3RT67591 The value for Cs,., Css.t. Cs,.3 or C

.3, the concentration limit at 53 the Unit 2 or Unit 3 detectors, is determined by using:

@G,,,,) (F) (E,C,)

(1-13) y C"'8 s (R) f/MPC,,,)

@G,,) (F) (E,C,)

(1-14) 7 53-2 (R) p/MPC,,,)

i (SG,.3) (F) (E,C,,)

(1-15)

""3 (R) f/MPC,,,)

I C'3-3 s (R) p/MPC,,,)

where:

C,.:

= instantaneous concentration at detector 2RT6759 in yC1/ml 3

C.

= instantaneous concentration at detector 2RT6753 in pCi/ml 33 C.,.3

= instantaneous concentration at detector 3RT6759 in C1/ml Cu.3

= instantaneous concentration at detector 3RT6753 in Ci/ml SG

= Unit 2 E088 Steam Generator Blowdown administrative value SG.: = Unit 2 E089 Steam Generator Blowdown administrative value SG, 3 = Unit 3 E088 Steam Generator Blowdown administrative value SG. 3 = Unit 3 E089 Steam Generator Blowdown administrative value F

= dilution water flow in volume per unit time

= 185,000 gpm per circulating water pump (4 total) 17,000 gpm per saltwater pump (2 total)

=

5023-0DCM 1-18 Revision 30 05-28-97

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT6753. 2RT6759. 3RT6753. 3RT6759) (Continued)

E,Cri total gamma isotopic concentration, yCi/ml, (STEP 1)

=

R maximum blowdown bypass effluent flowrate per steam

=

generator, 200 gpm, (STEP 1) 9 C

total concentration, C1/ml

=

value of MPC,,, from equation (1-4) for the sample MPC,rf

=

analysis NOTE:

If Co-a, Co., Co.2, or Cu-3 5 E,C,i (for the respective steam generator),

then no release is possible. To increase Ca.2, Co.2, Ca.: or Cu-a, increase the administrative value SG.3, SG., SG 3 or SG 3, and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate R and recalculate Cu-a, Cn., Ca.3 or Cu-3 using the new values of SGn., SG.., SGn.3 or SG 3, F, R as applicable and equation (1-13), (1-14), (1-15) or (1-16).

t i

i I;

i l

S023-0DCM i

1-19 Revision 30 05-28-97 l

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.3 TURBINE PLANT SUMP MONITORS (2RT7821. 3RT7821)

The value for C, (Unit 2) or C (Unit 3), the concentration limit 3

at the Unit 2 or Unit 3 detector, is determined by using:

,) (F) (E,C,,)

(1-17)

C, s (R) $/MPC,7f)

(T)(F)(E,C,,)

(1-18) l 3

(R) p/MPC,7,)

where:

C, instantaneous concentration at detector 2RT7821 in C1/cc

=

C3 instantaneous concentration at detector 3RT7821 in Ci/cc

=

Unit 2 Turbine Plant Sump administrative value T,

=

Unit 3 Turbine Plant Sump administrative value T

=

3 dilution water flow in volume per unit time F

=

185,000 gpm per circulating water pump (4 total)

=

17,000gpmpersaltwaterpump(2 total)

=

E C,, = total gamma isotopic concentration, yC1/ml, (STEP 1) i effluent flow rate, gpm, (STEP 1), typically flow rate:

R

=

100 gpm (per pump)

=

l total concentration, pC1/mi l

C

=

l MPC.,, = value of MPC,,, from equation (1-4) for the sample analysis If C or C 1 E C,i, then no release is possible. To increase C or C,

NOTE:

3 3

i 3

increase the administrative value T: or T, and/or increase dilution 3

flow F (by running more dilution pumps), and/or decrease the effluent

. flow rate, R, and recalculate C, or C using the new T, or T, F, R as 3

3 applicable and' equation (1-17) or (1-18).

5023-00CM 1-20 Revision 30 05-28-97 l

m

1.0' LIQUID EFFLUENTS (Continued) 1.4.2.3 TURBINE PLANT SUMP MONITORS (2RT7821. 3RT7821) (Continued)

Use of a temporary discharge path from the Turbine Plant Sump is allowed providing the radiation monitor, 2(3)RT7821, in service and the nomal discharge path is used concurrently. Temporary pumps facilitate faster discharge when draining the condenser to the outfall 'via this pathway. The following conditions shall be met:

a. The release pemit shall account for the entire volume of water discharged from the Turbine P' ant Sump,

b. The alarm setpoint for the monitor shall be adjusted to take into account the entire discharge flow through both the normal and temporary paths.

c. Procedures shall require the immediate termination of the discharge via the temporary path if the monitor on the normal path alarms.

1 5023-0DCM 1-21 Revision 21 02-15-90

l l

Table 1-3 Liquid Effluent Radiation Monitor Calibration Constants (')

(pC1/cc/ cpm) l HONITOR Co-60 Ba-133 Cs-137 l

l 2RT6753 1.92E-8 1.90E-8 2RT6759 1.96E-8 1.89E-8 3RT6753 2.12 E-8 1.91E-8 3RT6759 1.91E-8 1.97E-8 2/3RT7813 2.29E-9 3.15E-9 4.81E-9 k

2RT7817 2.36E-9 3.40E-9 4.91E-9 2RT7821 2.85E 3.56E-9 4.78E-9 3RT7817 2.38E-9 3.27E-9 4.82E-9 3RT7821 2.33E-9 3.18E-9 5.00E-9 l

l i

(*)

This table provides typical (* 20fs) calibration constants for the liquid l

effluent radiation monitors.

i S023-0DCM 1-22 Revision 31 02-27-98 h

4 1.0 LIQUID EFFLUENTS (Continued) 1.5 llQ1E CALCULATION FOR LIOUID EFFLUENTS The liquid releases considered in the following dose calculations are described in Section 1.4.

The dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas

.are calculated for the purpose of implementing Specification 1.2.1 using the following expression.

i 0,

= I fA,, E (At C,3 F)]

(1-19) 3 3

3 where:

A, Site-related adult ingestion dose comitment factor to the

=

i total body or an organ, r, for each identified principal ganrna j

and beta emitter,1, from Table 1-4 in mrem /hr per pCi/ml.

l Cu average concentration of radionuclide,1, in the undiluted

=

liquid effluent during time period At, in C1/ml.

3 dose commitment to'the total body or an organ, t, from the D,

=

liquid effluent for the time period, At, in mrem.

j j

near field average dilution factor (actually mixing ratio) for F

=

3 Cu during the time period, At. This factor is the ratio of 3

the maximum undiluted liquid waste flow during time period, At, to the average flow from the site discharge structure to 3

unrestricted receiving waters,

' maximum liquid radioactive waste flow '

0" discharge structure exit flow 3

length of the j* time period over which Cy and F are averaged At

=

3 for all liquid releases, in hours.

S023-0DCM 1-23 Revision 26 12-20-93

y TABLE 1-4 D0SE COMITMENT FACTORS *, A,

i (mrem /hrperpCi/ml)

Radio-Total nuclide Bone Liver Body Thyroid Kidney Lung GI-LLI H-3 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 Na-24 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 Cr-51 5.58E+0 3.34E+0 1.23E+0 7.40E+0 1.40E+3 i

Mn-54 7.06E+3 1.35E+3 2.10E+3 2.16E+4 Mn-56 1.78E+2 3.15E+1 2.26E+2 5.67E+3 Fe-55 5.11E+4 3.53E+4 8.23E+3 1.97E+4 2.03E+4 Fe-59 8.06E+4 1.90E+5 7.27E+4 5.30E+4 6.32E+5 l

Co-57 1.42E+2 2.36E+2 3.59E+3 Co-58 6.03E+2 1.35E+3 1.22E+4 Co-60 1.73E+3 3.82E+3 3.25E+4 Cu-64 2.14E+2 1.01E+2 5.40E+2 1.83E+4 Zn-65 1.61E+5 5.13E+5 2.32E+5 3.43E+5 3.23E+5 Br-84 9.39E-2 7.37E-7 Rb-88 1.79E+0 9.49E-1 2.47E-11 Sr-89 4.99E+3 1.43E+2 8.00E+2 Sr-90 1.23E+5 3.01E+4 3.55E+3 Sr-91 9.18E+1 3.71E+0-4.37E+2 Sr-92 3.48E+1 1.51E+0 6.90E+2 Y-90 6.06E+0 1.63E-1 6.42E+4 Y-91m 5.73E-2 2.22E-3 1.68E-1 Y-92 5.32E-1 1.56E-2 9.32E+3 Zr-95 1.59E+1 5.11E+0 3.46E+0 8.02E+0 1.62E+4 Zr-97 8.81E-1 1.78E-1 8.13E-2 2.68E-1 5.51E+4 Mb-95 1.84E+0 1.03E+0 5.51E-1 1.01E+0 6.22E+3 Mb-95m 1.84E+0 1.03E+0 5.51E-1 1.01E+0 6.22E+3 Nb-97 1.55E-2 3.91E-3 1.43E-3 4.56E-3 1.44E+1 Mo-99 1.28E+2 2.43E+1 2.89E+2 2.96E+2 Tc-99m 1.30E-2 3.66E-2 4.66E-1 5.56E-1 1.79E-2 2.17E+1 NOTE:

where no value is given, no data are available.

Source:

Reg. Guide 1.109. Table E-11, Table A-1 USNRC NUREG-0172, Table 4 ICRP-30, Part 3, Supplement A Methodology:

USNRC NUREG-0133, Section 4.3.1 S023-00CM 1-24 Revision 26 12-20-93

TABLE 1-4 (Continued)

DOSE COMITMENT FACTORS *, A,

i (mrem /hrper Ci/ml)

Radio-Total nuclide Bone Liver Body Thyroid Kidney Lung GI-LLI Ru-103 1.07E+2 4.60E+1 4.07E+2 1.25E+4 Ru-106 1.59E+3 2.01E+2 3.06E+3 1.03E+5 Ag-110m 1.42E+3 1.32E+3 7.82E+2 2.59E+3 5.37E+5 Sn-113 2.26E+5 Sn-117m 2.26E+5 Sb-124 2.76E+2 5.22E+0 1.09E+2 6.70E-1 2.15E+2 7.84E+3 Sb-125 1.77E+2 1.97E+0 4.20E+1 1.79E-1 1.36E+2 1.94E+3 Te-129m 9.31E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 4.69E+3 Te-132 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 6.24E+3 1-131 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E+2 8.23E+1 1-132 1.06E+1 2.85E+1 9.96E+0 9.96E+2 4.54E+1 5.35E+0 1-133 7.45E+1 1.30E+2 3.95E+1 1.90E+4 2.26E+2 1.16E+2 I-134 5.56E+0 1.51E+1 5.40E+0 2.62E+2 2.40E+1 1.32E-2 I-135-2.32E+1 6.08E+1 2.24E+1 4.01E+3 9.75E+1 6.87E+1 Cs-134 6.84E+3 1.63E+4 1.33E+4 5.27E+3 1.75E+3 2.85E+2 Cs-136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21E+2 Cs-137 8.77E+3 1.20E+4 7.85E+3 4.07E+3 1.35E+3 2.32E+2 Cs-138 6.07E+0 1.20E+1-5.94E+0 8.81E+0 8.70E-1 5.12E-5 Ba-139 7.85E+0 5.59E-3 2.30E-1 5.23E-3 3.17E-3 1.39E+1 Ba-140 1.64E+3 2.06E+0 1.08E+2-7.02E-1 1.18E+0 3.38E+3 La-140 1.57E+0-7.94E-1 2.10E-1 5.83E+4 Ce-141 3.43E+0 2.32E+0 2.63E-1 1.08E+0 8.86E+3 Ce-143 6.04E-1 4.46E+2 4.94E-2 1.97E-1 1.67E+4 Ce-144 1.79E+2 7.47E+1 9.59E+0 4.43E+1 6.04E+4 Nd-147 3.96E+0 4.58E+0-2.74E-1 2.68E+0 2.20E+4 W-187 9.16E+0 7.66E+0 2.68E+0 2.51E+3 j

Np-239 3.53f-2 3.47E-3 1.91E-3 1.08E-2 7.11E+2 NOTE:

where no value is given, no data are available.

Source:

Reg. Guide 1.109 Table E-11, Table A-1 USNRC NUREG-0172, Table 4 ICRP-30,- Part 3, Supplement A Methodology:

USNRC NUREG-0133, Section 4.3.1 S023-0DCM 1-25 Revision 26 12-20-93 L

p L

1.0 LIQUID EFFLUENTS (Continued) 1.6 Representative Sampling Prior to sampling of a batch release, each batch shall be thoroughly mixed to assure representative sampling in accordance with the requirements of Regulatory Guide 1.21 and NUREG-0800 Section 11.5. The i

methodology for mixing and sampling is described in 50123-III-5.11.23,

" Units 2/3 Liquid Effluent Release Permit" and S0123-III-5.2.23,

" Units 2/3 Liquid Effluent Sample Collection".

l i

1

}

\\

SO23-0DCM 1-26 Revision 21 02-15-90

2.0 GASE0US EFFLUENTS I

2.1 DOSE RATE SPECIFICATION 2.1.1 The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site (see

]

Figure 2-2) shall be limited to the following:

a.

For noble gases: Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, and b.

For all radiofodines, tritium and for all radioactive materials in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.

APPLICABILITY: At all times ACTION:

a.

With dose rate (s) exceeding the above limits, imediately decrease the release rate to within the above limit (s).

SURVEILLANCE REQUIREMENTS

.1 The dose rate due to noble gases in gaseous effluents shall be detemined to be within the above limits in accordance with Section 2.7.

.2 The dose rate due to radiofodines, tritium and radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with Section 2.7 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 2-1.

5023-0DCM 2-1 Revision 21 02-15-90

TABLE 2-1 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM

{

Gaseous Minimum Type of Lower Limit Release Sampling Analysis Activity of Detection Type Frequency Frequency Analysis (pCi/ml)'

Batch P

P Principal Gama Emitters' 1x10" Waste Gas Each Tank Each' Tank Decay Tank Grab.Sampie 1

DELETED lD Continuous Principal Gama Emitters' 1x1C '

Tritium 1x10-'

W I-131 1x1022 Continuous' Charcoal Sampler Sample I-133 1x10-"

W Continuous' Particulate Principal Gama Emitters' 1x10 "

Sampler Sample (I-131 and Others)

I M

Continuous' Composite Gross Alpha 1x10 U Sampler Particulate Sample

.q Q

Continuous' Composite St-89 and Sr-90 1x10*"

l Sampler Particulate f

Sample i

Continuous' Noble Gas Noble Gases 1x10-'

Monitor

. Monitor Gross Beta or Gama

Sampling frequencies for noble gases and' tritium are:

CONTINUOUS PATHWAYS: Containment Purge - 42" :

Each Purge

Containment Purge - 8" Monthly Grabb Condenser Air Ejector Monthly Grab' 6

Plant. Vent Stack Weekly Grab '

South Yard Facility Particulate and Iodine 8

sampling only S023-0DCM 2-2 Revision 31 02-27-98

TABLE 2-1 (Continuedl TABLE NOTATION The LLD is the smallest concentration of radioactive material in a sample a.

that will-be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

1 LLD =

E V

2.22 x 10' = Y. exp (-AAt) where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

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

i E is the counting efficiency (as counts per transformation),

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

2.22 x 10' is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

.A is the radioactive decay constant for the particular radionuclide, and-

~At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, no,t environmental samples).

The value of s, used in the calculation of the LLD for a particular measurement system shall be based on the actual observed variance of the backgrouno counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.

Typical values of E, V, Y and At should be used in the calculation.

It should be recognized.that the LLD is defined as an a priori (before the fact)limitrepresentingthecapabilityofthemeasurementsystemardnotas A posteriori (after the fact) limit for a particular measurement.*

For a more complete discussion of the LLD, and other detection limits, see the following:

1 HASL Procedures Manual, HASL-300 (revised annually).

2 Currie, L. ' A.,

" Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).

(3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques,"

Atlantic Richfield Hanford Company Report ARH-2537 (June-22,1972).

S023-0DCM 2-3 Revision 26 12-20-93 a

g TABLE 2-1 (Continuedl TABLE NOTATION b..

Analyses shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a 1-hour period. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

c.

Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

l d.

Samples shall'be changed'at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler).

'i Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7

-days following each shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and analyses shall be completed i

within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. This requirement does not apply if:

L (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the l

reactor coolant has not increased more than a factor of 3; and (2) the noble L

gas monitor shows that effluent activity has not increased more than a factor of 3.

When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding

.LLDs may be increased by a factor of 10.

e.

Tritium grab samples shall-be taken at least one per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

l f.

The ratio of the sample flow rate to the sampled stream flow rate shall be known for t h time period covered by each dose or dose rate calculation made in accordance with Specifications 2.1, 2.2, 2.3.

g.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58 Co-60, t

i.

In-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

h.

Deleted D

l-1.

Deleted J.

Radioactive airborne effluents only expected to be particulate and iodine.

l l

5023-0DCM 2-4 Revision 31 02-27-98 I

2.0 GASE0US EFFLUENTS (Continued)

-2.2 DOSE - NOBLE GASES SPECIFICATION 2.2.1 The air dose due to noble gases released in gaseous ef fluents, from each reactor unit, from the site (see Figure 2-2) shall be limited to the following:

a.

During any calendar quarter: Less than or equal to 5 mrad for gama radiation and less than or equal to 10 mrad for beta radiation and, b.

During any calendar year: Less than or equal to 10 mrad for ganna radiation and less than or equal to 20 mrad for beta radiation.

i APPLICABILITY: At all times ACTION:

a.

With calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days, pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with Specification 2.2.1.

$MRVEILLANCE REOUIREMENTS

.1-Dose Calculations Cumulative dose contributions for the current talendar quarter and current calendar year shall be determined in accordance with Section 2.8 at least once per 31 days.

~

l I

S023-0DCM 2-5 Revision'30 05-28-97 i

i i

4 2.0 GASE0US EFFLUENTS (Continued) 2.3 DOSE - RADI0 IODINES. RADI0 ACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM

)

SPECIFICATION 2.3.1 The dose to an individual from tritium, radiciodines and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the Site (see Figure 2-2) shall be limited to the following:

a.

During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, j

\\

b.

During any calendar year: Less than or equal to 15 mrem to any

{

organ, j

i c.

Deleted.

lp APPLICABILITY: At all times ACTION:

)

a.

With the calculated dose from the release of tritium, radiciodines, and radioactive materials in particulate form, with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days i

pursuant to Technical Specification Section 5.7.2 and LCS j

5.0.104.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 2.3.1.

SURVEILLANCE REOUIREMENTS

.1 pose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section 2.8 at least once per 31 days.

l S023-0DCM 2-6 Revision 31 02-27-98

2.0 GASEQUS EFFLUENTS (Continueti) 2.4 GASEOUS RADWASTE TREATMENT SPECIFICATION 2.4.1 The GASE0US PADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be operable. The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure 2-2), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to effluent relaases from the site (see Figure 2-2)gaseouswhen averaged over 31 days would exceed 0.3 mrem to any organ.*

APPLICABILITY: At all times 1

ACTION:

a.

With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days, pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special' Report which includes the following

{

information:

)

1. Explanation of why gaseous radwaste was being discharged without treatment, identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Sunnary description of action (s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS

.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with Section 3.2.

'These doses are per reactor unit.

5023-0DCM 2-7 Revision 30 05-28-97

2.0 EASE 005 EFFLUENTS (Continued) 2.4 GASEOUS RADWASTE TREATMENT (Continued)

SURVEILLANCE REOUIREMENTS (Continued) 2.4.1.2 During plant operation (Modes 1-4), the applicable portions of the GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.

.3 In plant shut-down (Mode 5, 6), the applicable portions of the GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15-minutes prior to processing gases unless the appropriate gaseous radwaste system has been utilized to process radioactive gaseous effluents during the previous 92 days.

5023-0DCM 2-8 Revision 22 08-02-90 l

I.....

2.0 GASE0US EFFLUENTS (Continued) 2.5 TOTAL DOSE SPECIFICATION 2.5.1 The dose or dose connitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to-25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

APPLICA8ILITY: At all times bC1LQ1iL a.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 1.2.1.a.1.2.1.b, 2.2.1.a, 2.2.1.b, 2.3.1.a. or 2.3.1.b in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Of rector, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 2.5.1.

This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report. If the estimated dose (s) exceeds the limits of Specification 2.5.1, and if the release condition resulting in -

l violation of 40 CFR 190 has not already been corrected, the Special Report shall. include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of paragraph 190.11(b).

Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to-the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed elsewhere in this ODCM.

SURVEILLANCE REOU:REMENTS

.1 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with surveillance 1.2.1.1, 2.2.1.1, and 2.3.1.1.

S023-0DCM 2-9 Revision 21 02-15-90

l I1lj;il i!

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,l I

2.0 GASE0US EFFLUENTS (Continued)~

2.6 Methods of Calculation for Gaseous Effluent Monitor Setnoints Administrative values are used to reduce each setpoint to account for the potential activity released simultaneously from the following E

release points:

PVS = Plant Vent Stack CAE = Condenser Air Ejector CP Containment Purge

=

SY South Yard

=

WG

' Waste Gas

=

U1 Unit 1 Airborne Release

=

The sum of the administrative values is limited to 1.0 to ensure that.

[

the total concentration from all release points on site to the environment will not result in a release exceeding -the limits of Specification 2.1.1.

The sum total of all these administrative values for the site shall be less than or equal to 1.0.

The administrative values shall be periodically reviewed based on actual i

release data and revised es necessary.

2.6.1 PLANTVENTSTACK-2/3RT7808,2RT7865-1,3RT7865-1 lp for the purpose of implementation of Specification 2.1.1, the alam setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor.

- Total Body The concentration at the detector corresponding to a 500 mrem /yr total body dose rate at the exclusion area boundary is determined by:

i C'"

(2-1)

(500 mrem /yr)(10 m /cc) 3 0.38 2120 C

=

det f

3' 3

(flow rate, cfm)(X/Q, sec/m ) E, K,, mm/yr h

3 3

pC1/m,,C,,,,

lill!

The concentration at the detector corresponding to a 3000 mrem /yrskindoserateattheexclusionareaboundaryis detemined by:-

t (2-2) m /sec, (3000 mrem /yr)(10-'m /cc) 3 0.38 2120 C

=

det f

y 3

1 (flow rate,cfm)(X/Q,sec/m ) [, L, + 1.1M,, mrem /yr 4 3

3 pCi/m C,,,,

(

5023-00CM 2-11 Revision 31 02-27-98

2.0 GASE0US EFFLUENTS (Continued) 2.6.1 PLANTVENTSTACK-2/3RT7808,2RT7865-1,3RT7865-1(Continued) where:

C.,

- = the instantaneous concentration at the detector,pCi/cc 0.38 an administrative value used to account for

=

potential activity from other gaseous release pathways.

K

= total body dose conversion factor from i

Table 2-4 for the 1** gamma emitting noble gas, mrem /yrper C1/m' L

skin Dose Conversion Factor from Table 2-4 for a

i the i'" noble gas, mrem /yr per pCi/m' 4

M tir Dose Conversion Factor from Table 2-4 for

=

i

he i'" noble gas, mrem /yr per C1/m' 1.1 conversion factor to convert gamma air dose to i

=

skin dose C

concentration of the t'" noble gas as determined'

=

i bysampleanalysis,pCi/cc C,,,

total concentration of noble gases as

=

determined by sample analysis, pC1/cc = E C ii flow rate total plant vent stack flow rate, cfm.

=

typically 164,000 cfm

=

2120 8

conversion constant, cfm per m /sec

=

' total body dose rate limit, as specified by 500 mrem /yr

=

Specification 2.1.1.a 3000 mrem /yr skin dose rate limit as specified by

=

Specification 2.1.1.a X/Q historical annual average dispersion factor for

=

3 anylandwardsector,sec/m 4.8E-6 sec/m'

=

S023-0DCM 2-12 Revision 31 02-27-98 r

c.

2.0 SASE0US EFFLUENTS (Continued) 2.6.1 PLANTVENTSTACK-2/3RT-7808,2RT-7865-1,3RT-7865-1 (Continued) 2.6.1.1 MaximumPermissibleAlarmSetpointfor2/3RT-7808 A.

The smailer of the values of C., from equations (2-1) or (2-2) is to be used in the detemination of the ' maximum pemissible monitoralarmsetpoint(cpm),asfollows:

i The maximum permissible alarm setpoint (cpm) is detemined using the calibration constant for 2/3RT-7808 given in 7

Table 2-3.

The maximum permissible alarm setpoint is the value" cpm"correspondingtotheconcentration,C.,(the s

smaller value from equation (2-1) or (2-2)). The calibration

{

constant used is based on Kr-85 or on Xe-133, whichever yields a lower detection efficiency (the largest value in terms of i

. Ci/cc/ cpm).

1 (C,, pC1/cc)

(2-5)

CPM"" ~

(Cal.Const.pC1/cc/ cpm)

A The alarm setpoint will be maintained at a value not greater than the maximum pcmissible alarm setpoint.

4 1

S023-0DCH 2-13 Revision 31 02-27-98

2.0 GASE0US EFFLUENTS (Continued) 2.6.1.2 Maximum Permissible Alarm Setpoint for 2RT-7865-1 and 3RT-7865-1 The smaller of the values of C,,, from equations (2-1) and (2-2) shall be used to determine the maximum permissible monitor alarm setpoint.

The maximum release rate (pCi Monitors is determined by con /sec) for Plant Vent Stack verting the concentration at the detector, C uCf b

pC1/sec, as fo(llow/cc) to an equivalent release rate in s:

(C,,,, pC1/cc)(flow rate, cfm)(472)

(2-3)

A, =

where:

A,,

= maximum permissible release rate, C1/sec Cut

= smaller of the values of C., determined in equations (2-1)and(2-2).

flow rate

= plant vent stack flow rate (cfm) used in equations (2-1) and (2-2) l.

472

= conversion cfm to cc/sec (28320 cc/ft' / 60 sec/ min) lA 2

= correction factor'to compensate for the split flow between Unit 2 and Unit 3 Plant Vent Stacks.

The release rate setpoint shall not be set greater than the maximum release rate determined above, when the monitor is being used to meet the requirements of Specification 2.1.1.

S023-0DCM 2-14 Revision 31 02-27-98

1 2.0 GASE0US EFFLUENTS (Continued) 2.6.2 CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-1, 3RT-7818 or 3RT-7870-1 2.6.2.1 2RT-7818 and 3RT-7818 Condenser Air E.iector Monitors For the purpose of implementation of Specification 2.1.1. the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor.

The concentration at the detector corresponding to a total body doserateof500 mrem /yrattheexclusionareaboundaryis determined by using:

Total Body (2-4)

C'"

(0.1)(0.5) 2120 m /sec,

( 500 mreni/yr) (10-' m /cc) 3 3

C,=

i f.

(Flow rate, cfm)(X/Q, sec/m ) E, K,. * **!#

3 3

pCi/m

,C,,,,

The concentration at the detector corresponding to a 3000 mrem /yr skin dose rate at.the_ exclusion area boundary is determined by using:

3. kin (2-4a) s C*

m /sec;

( 3000 mrem /yr) (10-8 m /cc)

(0.1)(0.5) 2120 3

C

=

ut (Flow rate, cfm)(X/Q, sec/m ) E, L, + 1.1M,, mrem /yr, r C,

3 3

C1/m

, C,,,,

1 where:

0.1 is an administrative value used to account for potential activity from other gaseous release pathways. 0.5 is an administrative value used to account for releases from both SONGS 2 and-SONGS 3 condenser air ejectors simultaneously.

Other parameters are specified in 2.6.1.1, and 2.6.2.2.

5023-0DCM 2-15 Revision 26 12-20-93

2.0 GASEGUS EFFLUENTS (Continued) 2.6.2 CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-1, 3RT-7818 or 3RT-7870-1 (Continued)

The smaller of the values C from equations (2-4) or (2-4a)

-is to be used in determining the maximum permissible monitor alarm setpoint (cpm), as follows:

The maximum permissible _ alam setting (cpm) is detemined by

-using the calibration constant for the corresponding Condenser Evacuation System Monitor given in Table 2-3.

The maximum permissible alam setpoint is the cpm value correspondingtotheconcentration,C,,,,[smallervaluefrom equation (2-4) or (2-4a)].

The calibration constant used is based on Kr-85 or on Xe-133, whichever yields a lower detection efficiency (higher value intermsofyC1/cc/ cpm). The alam setpoint will not be set greater than the maximum pemissible alam setting detemined above.

1 5023-0DCM 2-16 Revision 21 02-15-90

2.0 GASE0US EFFLUENTS (Continued) 2.6.2.2 2RT-7870-1 and 3RT-7870-1 Wide Ranae Gas Monitors The maximum release rate ( C1/sec) for Wide Range Gas Monitor is detemined by converting the concentration at the detector, C..,

F

( Ci/cc), to an equivalent release rate in pCi/sec.

(C... C1/cc) (flow rate, cc/sec)

(2-8)

L

(

=

where:

(

maximum pemissible release rate, Ci/sec

=

C,,,

smaller value of C.., as obtained from

=

equations (2-4) and (2-4a) flow rate flow rate of the condenser air ejector, cc 4.719E5 cc/sec (conservatively assumed as /sec

=

design flow rate) l 1

S023-0DCM 2-17 Revision 31 02-27-98 l

1

2.0 GASE0US EFFLUENTS (Continued) 2.6.3

[ANTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7855, 3RT-7865 For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor.

The concentration at the detector corresponding to a total body dose rate of 500 mrem /yr at the exclusion boundary is determined by using:

Total Body (2-6) 1 e

3 cfm (0.38)(P,)

2120 m,/sec;

( 500 mrem /yr)(10-8 m /cc) 3 Cdet2 =

3 f (Flow rate, cfm)(X/Q, sec/m ) E, K,,

mrem /yr C, 3 -

3 3

C1/m

, C,,,,

j I

(2-7) k f

3 cfm (0.38)(P )

2120 I'

( 500 mrem /yr) (10-' m /cc) 3 3

Cdet3 =

3 f

i (Flow rate, cfm)(X/Q, sec/m ) E, K,, * **!#

3 3

pCi/m

, C,,,,

The concentration at the detector corresponding to a 3000 mrem /yr skin dose rate at the exclusion area boundary is determined by using:

Sjin (2-6a)

C*

m /sec,

( 3000 mrem /yr)(10-' m'/cc)

(0.38)(P,)

2120 3

gdett,

i

/

3 C

(Flow rate, cfm)(X/Q, sec/m ) E, L, + 1.lM,, mrem /yr 3

i pC1/m,,, C,,,,

S023-0DCM 2-18 Revision 22 08-02-90

2.0 GASE0US EFFLUENTS (Continued) 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865, 3RT-7865 (Continued)

(2-7a)

(0.38)(P ) 2120

( 3000 mrem /yr) (10-6 m /cc) 8 3

"3 **#'

Cdet3 =

r 3-(Flow rate, cfm)(X/Q, sec/m ) E, L, + 1.1M,, mrem /yr

,h 3

3 Ci/m

,C,,,,,

where:

C, instantaneous concentration of the Unit 2

=

detector, C1/cc.

-Cm3 instantaneous concentration of the Unit 3

=

detector,yC1/cc.

0.38 is an administrative value used to account for potential activity from other gaseous release pathways.

P and P are administrative values used to account for 3

3 simultaneous purges of both SONGS 2 and SONGS 3.

.The fractions P3 and P will be assigned such that P + P s 1.0.

3 3

3 Flow rate observed maximum flowrate in cfm from the unit

=

specific monitor 7828.

Default values will be the following conservative measured flows:

50,000 cfm full purge F

=

3,000~cfm mini-purge

=

(The above values replace the smaller design flowrates.)

Other parameters are as specified in 2.6.1.1 above. The smaller of the values of maximum permissible C.,13 from equation (2-6) or (2-6a)andC,,,3 fromequations(2-7)or(2-7a)istobeusedin determining the maximum permissible monitor alarm setpoints.

S023-0DCM 2-19 Revision 28 12-21-95

1 l

l 2.0 GASE0US EFFLUENTS (Continued) 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865, 3RT-7865 (Continued) 2.6.3.1 Maximum Permissible Alarm Settina (RT-78651 The maximum pemissible alam setting for the Wide Range Gas Monitorexpressedasamaximumreleaserate(Ci/sec)is determined by converting the concentration at the detector, C..

( C1/cc),to an equivalent release rate in pCi/sec.

( C.,, Ci/cc) (flow rate, cc/sec)

(2-8)

A.,,

=

4 where:

9 A.,,

maximum pemissible release rate, pCi/sec

=

C.,

smaller value of C,..

as obtained from equation

=

(2-6, 2-6a) for Unit 2 or (2-7, 2-7a) for Unit 3.

flow rate = flowrate,cc/sec 1.416E6 cc sec for mini-purge.

=

2.360E7 cc sec for main purge.

=

.2 Maximum Permissible Alam Settina (RT-78281 The maximum permissible alarm setting for RT-7828 is in Ci/cc and is the smaller of the values of C.,, (pC1/cc) from equations (2-6) and (2-6a) for Unit 2 or equations (2-7, 2-7a) for i

Unit 3.

l l

j l

S023-0DCM 2-20 Revision 31 02-27-98 1

a

2.0 GASE0US EFFl.UEllTS (Continued) 2.6.4 WASTEGASHEADER-3RT-7865,2/3RT-7808 for the purpose of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor. Since the waste gas header discharges to the plant vent stack, either 3RT-7865 or 2/3RT-7808 may be used to monitor waste gas header releases.

The concentration at the detector corresponding to a total body dose rate of 500 mrem /yr or a skin dose rate of 3000 mrem /yr at the exclusion area boundary is determined by using equations (2-1) or (2-2) with sample concentration (C ) and (C..) being i

obtained from the waste gas decay tank to be released.

The smaller of the values of (C,,,) from equation (2-1) or (2-2) is to be used in determine the maximum permissible monitor alarm setpoint.

1 2.6.4.1 Maximum Permissible Alarm Setpoint 2/3 RT-7808 6

The maximum permissible alarm setting (cpm) is determined by using the calibration constant for plant vent stack monitor 7808 given in Table 2-3.

The maximum permissible setpoint is the cpm value corresponding to the concentration C.,, (smaller value from equation (2-1) or (2-2)).

L (C,,,, pCi/cc)

(2-5) g l

CPM""

(Cal.Const., C1/cc/ cpm)

I i

l-S023-0DCM 2-21 Revision 31 02-27-98 i

1 2.0 GASE005 EFFLUENTS (Continued) 2.6.4.2 Maximum Permissible Alam Setnoint 3RT-7865-1 The smaller of the values of C., from equations (2-1) and (2-2) shall be used to detemine the maximum permissible monitor alarm setpoint.

The maximum release rate (pCi/sec) for Plant Vent Stack f

Monitors is determined by converting the concentration at the 1

detector, C gCi pC1/sec, as.fo(llow/cc) to_an equivalent release rate in f

s:

t A,,,

=

(C,,,, C1/cc)(flow rate, cfm)(472)

(2-3) where:

A,,,

maximen permissible release rate, pCi/sec

=

equations (2-1) and (2-2)., determined in C.,

smaller of the values of C

=

flow rate plant vent stack flow rate (cfm) used in

=

equations (2-1) and (2-2) i 472

= conversion cfm to cc/sec (28320 cc/ft' / 60 sec/r4 p

2 correction factor for 3-7865 viewing only half

=

the total plant vent stack flow 2.6.4.3 A release from the waste gas header is not possible if:

r 3 (2-9) h10,)

f

>C,,,

r >

'where:

E c, total gamma activity ( Ci/cc) of the waste gas

=

i holdup tank to be released, as' detemined from the pre-release sample analysis f

waste gas header effluent flow rate, cfm

=

F

= plant vent stack flowrate (cfm) used in equations (2-1) and (2-2) determined in b

.C.

= smaller of the values of C*lth C being obtained equations (2-1)and(2-2) i from the waste gas holdup tank to be released 5023-0DCM 2-22 Revision 31 02-27-98 L

)

\\

2.0 GASE0US EFFLUENTS (Continued) 2.6.4 WASTEGASHEADER-3RT-7865,2/3RT-7808 (Continued) 2.6.4.3 (Continued)

)

If a release is not possible, adjust the waste gas header flow by determining the maximum permissible waste gas header i

effluent flow rate corresponding to the Plant Vent Stack

(

Monitor setpoint in accordance with the following:

)

f < (0.9)(C,,,)(F)

(2-10)'

E, C, where:

f waste gas header effluent flow rate (cfm)

=

plant vent stack flow rate (cfm) used in equation (2-1)

F

=

or(2-2)

C.,,

=

smaller of the value of C.,, from equation (2-1) or (2-2)

EC= total ganna activity ( Ci/cc) of the waste gas holdup ii tank to be released, as determined from the pre-release sample analysis.

The 0.9 is an administrative value to account for the potential activity from other releases in the same release pathway.

I 5023-0DCM 2-23 Revision 31 02-27-98 j

Table 2-3(a)

Gaseous Effluent Radiation Monitor Calibration Constants (pC1/cc/ cpm)

MONITOR Kr-85 Xe-133 2/3RT-7808C 4.43E-8 4.81E-8 2RT-7818A 4.27E-8 6.86E-8 3RT-7818A.

3.73E-8 5.12E-8 i

)

i l

(a)This table provides typical (*20%) calibration constants for the j

gaseous effluent radiation monitors.

l S023-0DCM 2-24 Revision 30 05-28-97

2.0 GASE0US EFFLUENTS (Continued) 2.7 Gaseous Effluent Dose Rate The methodology used for the purpose of implementation of Specification 2.1.1 for the dose rate above background to an individual in an unrestricted ~ area is calculated by using the following expressions:

2.7.1 FOR NOBLE GASES:

(2-11) l D

=E, K,(@) Q, u

"2 (L + 1.1M,) (@) Q, (2-12)

D, 1

t where:

Dn total body dose rate in unrestricted areas due to

=

radioactive materials released in gaseous effluents, mrem /yr D,

skin dose rate in unrestricted areas due to

=

radioactive materials released in gaseous effluents, mrem /yr K,

the total body dose factor due to ganna emissions

=

from Table 2-4 for each identified noble gas radionuclide,1, in mrem /yr per C1/m' Li skin dose factor due to the beta emissions from

=

Table 2-4 for each identified noble gas radionuclide,1,inmrem/yrper C1/m f

8 Mi air dose factor due to ganna emissions from

=

Table 2-4 for each identified noble g'as radionuclide, i, in mrad /yr per Ci (conversionconstantof1.1 mrem /mr/m ad converts air dose to skin dose.)

Q, measured or calculated release rate of

=

radionuclide, i, for either continuous or batch gaseouseffluents,inpC1/sec

(@)

Maximum annual average atmospheric dispersion

=

factor for any landward sector or distance at or beyond the unrestricted area boundary.

4.8E-6 see m' for Units 2 and 3

=

8.0E-5 sec m' for South Yard Facility

=

S023-00CM 2-25 Revision 31 02-27-98 L

n 2.0 GASE0US EFFLUENTS (Continued) 2.7.2 FOR ALL RADIOI0 DINES. TRITIUM AND FOR ALL RADI0 ACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN EIGHT DAYS:

[),

E, E,(Pu W,) Q, (2-13) 4

=

where:

D.

organ dose rate in unrestricted areas due to

=

radioactive materials released in gaseous effluents, mrem /yr i

Q, measured or calculated release rate of radionuclide,1

=

for either continuous or batch gaseous effluents, pC1/sec dose parameter for radionuclide, i, for pathway, k, P,,

=

from Table 2-5 for the inhalation pathway in mrem /yr per Ci/m'. The dose factors are based on the critical individual organ and the child age group.

9, highest calculated annual average dispers' ion (T[Q) or

=

deposition (D7Q)factorforestimatingthedosetoan f

individual at or beyond.the unrestricted area boundary for pathway k.

(X/Q), 4.8E-6 sec/m' for Units 2/3 for the inhalation

=

pathway. The location is the unrestricted area in the NW sector.

(T/Q), 8.0E-5 sec/m' for South Yard Facility for the

=

inhalation pathway. The location is the unrestricted area in the E sector.

(D7Q), 4.3E-8 m-' for Units 2/3 for the food and ground

=

plane pathways. The. location is the unrestricted area in the E sector.

(D7Q), 8.0E-7 m-8 for South Yard Facility for the food

=

and ground plane pathways. The location is the unrestricted area in the E sector.

l S023-0DCM 2-26 Revision 31 02-27-98 k

2.0 GASE0US EFFLUENTS (Continued) l f

.J l

)

THIS PAGE INTENTIONALLY BLANK F

I 1

l 1

e S023-0DCM 2-27 Revision 31 02-27-98 j

2.0 GASE0US EFFLUENTS (Continued)

.2.8 Gaseous Effluent Dose Calculation 2.8.1 DOSE FROM NOBLE GASES IN GASEOUS EFFLUENTS The gaseous releases considered in the following dose calculations are described in Section 2.6.

The air dose in unrestricted areas due to noble gases released in gaseous

. effluents is calculated using the following expressions:

2.8.1.1 For historical meteoroloav:

0, = 3.17x10 -s E, M, (Q)Q, (2-14)

D, = 3.17x10'8 E, N, (@)Q (2-15) i_

where:

D, =

total gamma air dose from gaseous effluents, mrad D, =

total beta air dose from gaseous effluents, mrad 3.17x108 inverse seconds per year

=-

Mi=

air dose factor due to ganrna emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrad /yrperpC1/m' Ni=

air dose due to beta emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrad /yr per pC1/m'

.I/Q)

(

Maximum annual average atmospheric dispersion factor

=

for any landward sector or distance at or beyond the unrestricted area boundary.

4.8E-6 sec m' for Units 2 and 3

=

8.0E-5 sec m' for South Yard Facility b

=

Qi =

amount of noble gas radionuclide, 1, released in gaseous effluents, C1.

)

S023-0DCM l

2-28 Revision 30 05-28-97 I

4 i

2.0 GASE0US EFFLUENTS (Continued) 2.8.1.2 For meteorolocy concurrent with release:

NOTE:

Consistent with the methodology provided in Regulatory Guide 1.109 and the following equations, RRRGS (Radioactive Release Report Generating System) software is used to perform the actual calculations.

D,,

= 1.14x10 E, M, E,( A t, (X/Q)), g )

D,,

= 1.14x10 E, H, E ( A t, (X/Q),, q, )

(2-17) 3 where:

D,,

total gamma air dose from gaseous effluents

=

in sector e, mrad D,,

total beta air dose from gaseous effluents in

=

sector e, mrad 1.14x10d inversehours/ year

=

M, air dose factor due to gamma emissions from

=

Table 2-4 for each identified noble gas radionuclide,1, in mrad /yr per C1/m'

'N, air dose factor dua to beta emissions from

=

Table 2-4 for each identified noble g'as radionuclide,1, in mrad /yr per C1/m At 3 length of the j* time period over which

=

(X/h)3, and Qu are averaged for gaseous releases in hours (X/Q)3, atmospheric dispersion factor for time period

=

Atj at exclusion boundary location in a

landward sector e determined by concurrent 2

meteorology, sec/m Qn average release rate of radionuclide,1, in

=

gaseous effluents during time period, At,

3 pCi/sec S023-0DCM 2-29

}

Revision 28 12-21-95

II 2.0 6ASE005 EFFLUENTS (Continued)-

2.8.2 DOSE FROM TRITIUM. RADIOIODINES AND RADIOACTIVE MATERIALS IN PAtTICULATE FORM WITH 4ALF LIVES GREATER "HAN 8

)AYS IN GASE0US EFFLJENTS The dose to an individual from tritium, radiciodines and radioactive materials in particulate form with half lives I

greater than eight days in gaseous effluents released to unrestricted areas is calculated using the following expressions:

1 l

l 2.8.2.1 For historical meteoroloav:

0,

= 3.17x10 -a 3, [3,

w,]

(2-18) where:

0, total projected dose from gaseous effluents to an

=

individual, mrem 4

3.17x10 year /second

=

Qi amount of each radionuclide,1, (tritium,

=

radioiodine, radioactive material in particulate form with half lives greater than eight days),

released in gaseous effluents, Ci E R aW, sum of all pathways, k, for radionuclide, i, of

=

i the R, W product, in mrem /yr per Ci/sec. The E R g,le 2-6 for Units 2/3 and Table 2-17 forW value for i

in Tab South Yard Facility. The value given is the maximum E R gW, for all locations and is based on i

the most restrictive age groups.

dose factor for each identified radionuclide, 1 Rg

=

i mrem /pathwayk,(fortheinhalationpathwa for yr per pCi in m -mrem /yr per C1 controlling location for eachg's for/sec), a controlling location. The R each age group are given in Tables 2-7 thru 2-16 for Units 2/3 and Tables 2-18 through 2-21 for South Yard Facility.

Data in these tables are derived using the NRC code, PARTS.

(See the annual update of revised R, parameters based on changes in the Land Use Census provided by Corporate Health Physics and Environmental.)

S023-00CH Revision 30 2-30 05-28-97 s

q 2.0 GASE005. EFFLUENT $ (Continued) 2.8.2.1 For historical meteoroloav:

(Continued) annual average dispersion (i[Q) or deposition (6[Q)

W.

=

factor for estimating the dose to an individual at the controlling location for pathway k.

(i7Q)_fgr the inhalation pathway in sec/m'.

l

=

The (X/Q) for each controlling location is given in Tables 2-7 thru 2-16 for Units 2/3 and Table 2-18 through 2-21 for South Yard Facility.-

(b7Q)_fgr the food and ground plane pathways in m.

=

The (D/Q) for each controlling location is given in Tables 2-7 thru 2-16 for Units 2/3 and Tables 2-18 through 2-21 for South Yard Facility.

2.8.2.2 For meteoroloav concurrent with releases:

1 NOTE:

Consistent with the methodology provided in Regulatory Guide 1.109 and the following equations, RRRGS (Radioactive Release Report Generating System) software is used to perform the actual calculations.-

1mn' r, s -

(2-19) 0,

= 1.14 x 10" E E E (At )(R,g)(Wg) g%

3 ijk

(

where:

total annual dose from gaseous effluents to an D,

=

individual in sector e, mrem.

3 length of the j" period over which W m and Qu At

=

3 are averaged for gaseous released, hours average release rate of radionuclide,1, in Qu

=

gaseous effluents during time period At, pC1/sec j

Ra=

dose factor.for each identified radionuclide 1 for i

pathway k for sector e (for the inhalation pathway in z /m' and for the food and ground plane mrem /yrper C1 pathways in m mrem /yr per pCi/sec) at the controlling location. A listing of R,, for the controlling locations in each landward sector for each group is i

given in Tables 2-7 thru 2-16 for Units 2/3 and Tables 2-18 through '2-21 for South Yard Facility. The e is determined by the concurrent meteorology.

W.=

dispersion (X/Q) or deposition (D/Q) factor for the p

time period At for each pathway k for calculating the 3

dose to an individual at the controlling location in seglor e using concurrent meteorological conditions.

i

(

) for the inhalation pathway, sec/m' i

=

(

) for the food and ground plane pathways, m-8

=

S023-00CM-4 Revision 30 1

2-31 05-28-97 l

1 i

1 2.0 GASE0US EFFLUENTS (Continued)

(

i THIS PAGE INTENTIONALLY BLANK l

l l

l S023-0DCM 2-32 Revision 31 02-27-98

TABLE 2-4 00$E FACTORS FOR NOBLE GASES AND DAUGHTER $**

Total Body Dose Skin Dose Gamma Air Dose Beta Air Dos'.t Factor K Factor L.

Factor M Factor N i

i i

Radio-(mrem / r (mrem /r (mrad / r (mrad /r Nuclide per Ci

')

per Ci m')

per Ci

)

per Ci m')

Kr-85m 1.17E+3 1.46E+3 1.23E+3 1.97E+3 Kr-85 1.61E+1 1.34E+3 1.72E+1 1.95E+3 Kr-87 5.92E+3 9.73E+3 6.17E+3 1.03E+4 Kr-88 1.47E+4 2.37E+3 1.52E+4 2.93E+3 Xe-131m 9.15E41 4.76E+2 1.56E+2 1.11E+3 Xe-133m 2.51E+2 9.94E+2 3.27E+2 1.48E+3 Xe-133 2.94E+2 3.06E+2 3.53E+2 1.05E+3 Xe-135m 3.12E+3 7.11E+2 3.36E+3 7.39E+2 Xe-135 1.81E+3 1.86E+3 1.92E+3 2.46E+3 Xe-138 8.83E+3 4.13E+3 9.21E+3 4.75E+3 Ar-41 8.84E+3 2.69E+3 9.30E+3 3.28E+3

- Source: USNRC Reg. Guide 1.109 Table 8-1 l

I i

l l

S023-0DCM 2-33 Revision 21 02-15-90

TABLE 2-5 D0SE PARAMETER Pa*

CHILD AGE GROUP CRITICAL ORGAN InhalationPathway Inhalation Pathway Radionuclide (mrem /yr per yC1/m )

Radionuclide (mrem /yr per pC1/m ).

H-3 1.1E+3 I -131 1.6E+7 Cr-51 1.7E+4 I -132 1.9E+5 Hn-54 1.6E+6 I -133 3.8E+6

.00-57 5.1E+5 I -134 5.1E+4 Co-58 1.1E+6 I -135 7.9E+5 Co 7.1E+6 Cs-134 1.0E+6 Sr-89 2.2E+6 Cs-136 1.7E+5 Sr-90 1.0E+8 Cs-137 9.1E+5 Zr-95 2.2E+6 Ba-140 1.7E+6

'Nb-95 6.1E+5 Ce-141 5.4E+5 Ru-103 6.6E+5 Ce-144 1.2E+7 Te-129m 1.8E+6

Source: USNRC NUREG-0133, Section 5.2.1.1 l

l S023-0DCM i

2-34 Revision 23 02-28-91

TABLE 2-6 CONTROLLING LOCATION FACTORS E

mrem /yr.RnW, Ci/sec Use:

Radionuclide per H -3 9.00E-4 Q: Outage Workers lR-Cr-51 3.00E-2 Q: San Onofre Mobil. Homes Mn-54 6.39E+0 Q: Outage Workers Co-57 1.58E+0 Q: Outage Workers Co-58 2.20E+0 Q: Outage Workers

(

Co-60 8.89E+1 Q: Outage Workers Sr-89 4.65E+1 Q: SCRanch(No.Res.)

Sr-90 1.95E+3 Q: SC Ranch (No. Res.)

Zr-95 2.69E+0 Q: San Onofre Mobil. Homes Nb-95 1.07E+1 E: Deer Consumer Hunter Ru-103 1.69E+1 E: Deer Consumer Hunter Te-129m 8.35E+0 E: Deer Consumer Hunter Cs-134 3.60E+1 Q: SC Ranch (No. Res.)

Cs-136 6.87E-1 Q: Outage Workers Cs-137 4.11E+1 Q: Outage Workers k

Ba-140 1.45E+0 Q: San Onofre Mobil. Homes Ce-141 6.15E-1 Q: SC Ranch (No. Res.)

Ce-144 1.80E+1 Q: SC Ranch (No. Res.)

1 -131 1.83E+1 Q:

SanOnofr/ Garden

[g.

SC Res. w I -132 1.35E-1 Q:

e Mobil. Homes I -133 2.63E+0 Q: San Onofre Mobil. Homes I -134 3.67E-2 Q: San Onofre Mobil. Homes I -135 5.53E-1 Q: San Onofre Mobil. Homes UN-ID 3.75E+0 Q: SC Ranch (No. Res.)

Footnote:

These values to be used in manual calculations are the maximum E RnW, for all locations based on the most restrictive age group.

S023-0DCM 2-35 Revision 31 02-27-98

TABLE 2-7 DOSE PARAMETER R FOR SECTOR P Page 1 of 3 Pathway = Surf Beach / Life Guard Distance = 0.5 miles 3

X/Q=1.3E-6sec/m D/Q=5.5E-9md Infant Child Teen Adul t Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 7.8E+0 4.2E+1 9.6E+1 Cr-51 1.2E+2 3.2E+4 6.9E+2 1.5E+5 1.1E+3 3.5E+5 Mn-54 1.1E+4 9.5E+6 6.5E+4 4.5E+7 1.1E+5 1.1E+8 Co-57 3.5E+3 2.4E+6 1.9E+4 1.1E+7 2.8E+4 2.6E+7 Co-58 7.6E+3 2.6E+6 4.4E+4 1.2E+7 7.1E+4 2.9E+7 Co-60 4.9E+4 1.5E+8 2.9E+5 7.0E+8 4.5E+5 1.6E+9 Sr-89 1.5E+4 1.5E+2 7.9E+4 7.1E+2 1.1E+5 1.6E+3 Sr-90 7.0E+5 3.5E+6 7.5E+6 Zr-95 1.5E+4 1.7E+6 8.8E+4 8.2E+6 1.3E+5 1.9E+7 Nb-95 4.2E+3 9.4E+5 2.5E+4 4.5E+6 3.8E+4 1.0E+7 Ru-103 4.6E+3 7.5E+5 2.6E+4 3.6E+6 3.8E+4 8.3E+6 Te-129m 1.2E+4 1.4E+5 6.5E+4 6.4E+5 8.8E+4 1.5E+6 g

Cs-134 7.0E+3 4.7E+7 3.7E+4 2.2E+8 6.5E+4 5.2E+8 lb Cs-136 1.2E+3 1.0E+6 6.3E+3 4.7E+6 1.1E+4 1.1E+7 Cs-137 6.3E+3 7.1E+7 2.8E+4 3.4E+8 4.7E+4 7.8E+8 Ba-140 1.2E+4 1.4E+5 6.6E+4 6.7E+5 9.7E+4 1.6E+6 Ce-141 3.8E+3 9.4E+4 2.0E+4 4.5E+5 2.8E+4 1.0E+6 Ce-144 8.2E+4 4.8E+5 4.4E+5 2.3E+6 5.9E+5 5.3E+6 1 -131 1.1E+5 1.2E+5 4.8E+5 5.6E+5 9.1E+5 1.3E+6 I -132.1.3E+3 8.5E+3 4.9E+3 4.1E+4 8.7E+3 9.4E+4 I -133 2.7E+4 1.7E+4 9.5E+4 8.0E+4 1.6E+5 1.9E+5 I -134 3.5E+2 3.1E+3 1.3E+3 1.5E+4 2.3E+3 3.4E+4 I -135 5.5E+3 1.7E+4 2.0E+4 8.2E+4 3.4E+4 1.9E+5 i

UN-ID 6.9E+3 5.1E+6 4.1E+4 2.4E+7 6.6E+4 5.7E+7 Inhalation Pathway, units = p*

7" Food & Ground Pathway, units =

C1/ c S023-0DCM 2-36 Revision 31 02-27-98

r_

TABLE 2-7 DOSE PARAMETER R FOR SECTOR P Page 2 of 3 Pathway = Cotton Point Estates with Garden Distance = 2.8 miles X/Q = 1.0E-7 sec/m' D/Q'= 3.0E-10 m"'

Infant Child Teen Adult Inhala-Food &

Inhaft-Food &

Inhala-Food &

Inhe ". 3-Food &

l Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathwty Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 4.0E+3 1.3E+3 2.6E+3 1.3E+3 2.2E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 1.1E+7 2.1E+4 1.4E+7 1.4E+4 1.5E+7 Mn-54 1.0E+6 1.4E+9 1.6E+6 2.0E+9 2.0E+6 2.3E+9 1.4E+6 2.3E+9 Co-57 3.8E+5 3.4E+8 5.1E+5 5.3E+8 5.9E+5 6.6E+8 3.7E+5 6.2E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 7.4 E+8 1.3E+6 9.5E+8 9.3E+5 9.7E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.4E+10 8.7E+6 2.5E+10 6.0E+6 2.5E+10 fr 89 2.0E+6 2.2E+4 2.2E+6 3.5E+10 2.4E+6 1.4E+10 1.4E+6 9.4E+9 S,.90 4.1E+7 1.0E+8 1.4E+12 1.1E+8 8.2E+11 9.9E+7 6.6E+11

~ r-95 1.8E+6 2.5E+8 2.2E+6 1.1E+9 2.7E+6 1.5E+9 1.8E+6 1.4E+9 Nb-95 4.8E+5 1.4E+8 6.1E+5 4.2E+8 7.5 E+ 5 5.7E+8 5.0E+5 5.9E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 4.9E+8 7.8E+5 6.6E+8 5.0E+5 6.4E+8.

Te-129m 1.7E+6 2.0E+7 1.8E+6 2.8E+9 2.0E+6 1.7E+9 1.2E+6 1.4E+9 Cs-134 7.0E+5 6.8E+9 1.0E+6 3.2E+10 1.1E+6 2.3E+10 8.5E+5 1.7E+10 Cs-135 1.3E+5 1.5E+8 1.7 Et5 3.5E+8 1.9E+5 3.0E+8 1.5E+5 3.0E+8 Cs-137 6.1E+5 1.0E+10 9.1E+5 3.5E+10 8.5E+5 2.4E+10 6.2E+5 1.9E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.7E+8 2.0E+6 2.1E+8 1.3E+6 2.5E+8 Ce-141 5.2E+5 1.4E+7 5.4 E+5 4.0E+8 6.1E+5 5.3E+8' 3.6E+5 4.9E+8 Ce-144 9.8E+6 7.0E+7 1.2E+7 9.9E+9 1.3E+7 1.3E+10 7.8E+6 1.0E+10 I -131 1.5E+7.

1.7E+7 1.6E+7 4.1E+10 1.5E+7 2.7E+10 1.2E+7 3.2E+10 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6 E+6 2.4E+6 3.8E+6 6.9E+8 2.9E+6 3.9E+8 2.2E+6 4.5E+8 1

I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 1.1E+7 6.2E+5 7.4E+6 4.5E+5 8.1E+6 IIN-ID 6.5E+5 7.5E+8 1.0E+6 3.4E+9 1.2E+6 2.6E+9 8.6E+5 2.0E+9 I

I Inhalation Pathway, units = ""

h",3 Food & Ground Pathway, units =

Ci c

S023-0DCM 2-37 Revision 30 05-28-97

r:

j.

TABLE 2-7 D0SE PARAMETER R. FOR SECTOR P H.

Page 3 of 3 Pathway = 51 Area Beach Check-In Distance = 1.4 miles 8

4 X/Q = 6.9E-7 sec/m -

D/Q=3.3E-9m Infant Child Teen Adult Inhala-Food &

Inhala-Food &-

Inhala-Food &

Radio-tion Ground-tion Ground tion c '9und tion Ground Nuclide Fhthway Pathway Pathway Pathway Pathway Pathway Pathv:3y Pathway H -3 3.2E+2 Cr-51 3.7E+3 1.2E+6 Mn-54 3.6E+5 3.6E+8 Co 9.5E+4 8.8E+7 Co-58 2.4E+5 9.8E+7 Co-60 1.5E+6 5.5E+9 Sr-89. 3.6E+5 5.5E+3 Sr-90 2.5E+7 Zr-95 -0-~ 4.5E+5 6.5E+7 Nb-95. 1.3E+5 3.5E+7 Ru-103 1.3E+5 2.8E+7 Te-129m 3.0E+5 5.1E+6 Cs-134 2.2E+5 1.8E+9 Cs-136' - 3.8E+4 3.9E+7 Cs-13? 1.6E+5 2.6E+9 Ba-140 3.3E+5 5.3E+6 Ce-141 9.3E+4 3.5E+6 Ce-144 2.0E+6 1.8E+7 I -131 3.1E+6 4.4E+6 1 -132 2.9E+4 3.2E+5 I -133 5.5E+5 6.3E+5' I -134 7.7E+3 1.2E+5 I -135. 1.2E+5 6.5E+5 UN-IO 2.2E+5 1.9E+8 e

InhalationPathway, units =p""*"7" Food & Ground Pathway, unfts =

Ci/ c S023-00CM 2-38 Revision 30 05-28-97

{

L

1 TABLE 2-8 DOSE PARAMETER R, FOR SECTOR Q Page 1 of 9 (p

Pathway = Rec. Bldg Staff Distance = 1.2 miles X/Q=8.9E-7sec/m' D/Q=4.4E-9m' Infant Child Teen Adult Inhala-Food &'

Inhala-Food &

Radio-tion Ground-tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.3E+2 Cr-51 7.2E+3 2.3E+6 Mn-54 - 7.0E+5 6.9E+8 00-57 1.8E+5 1.7E+8 Co-58

. 4.6E+5 1.9E+8 Co-60 3.0E+6 1.1E+10 j

Sr-89 7.0E+5 1.1E+4 i

Sr-90 5.0E+7 !

Zr-95 8.8E+5 1.3E+8 Nb-95 2.5E+5 6.8E+7 Ru-103 2.5E+5 5.4E+7 Te-129m 5.8E+5 9.8E+6 Cs-134

4.2E+5 3.4E+9 k

Cs-136

-r 7.3E+4 7.5E+7 Cs-137

.-t 3.1E+5 5.1E+9 Ba-140 6.4 E+5 1.0E+7 Ce-141 1.8E+5 6.8E+6 Ce-144-3.9E+6 3.5E+7

-I -131 -0-- 6.0E+6 8.6E+6 I -132 5.7E+4 6.2E+5 I -133 1.1E+6 1.2E+6 I -134 ~ 1.5E+4 2.2E+5 I -135 2.2E+5 1.3E+6 UN-ID 4.3E+5 3.7E+8 Inhalation Path'way, units =. p" 7"

Food & Ground Pathway, units =

C1/ c S023-00CM 2-39 Revision 31 02-27-98

TABLE 2-8 DOSE PARAMETER R FOR SECTOR Q Page 2 of 9 lF Pathway.= San Onofre Mobile Homes Distance = 1.4 miles 8

X/Q=6.9E-7sec/m D/Q = 3.3E-9 m-r j

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway-Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 l

Co-57 3. w '.+ 5 3.4 E+8 5.1E+5 3.4E+8 5.9E+5 3.4E+8 3.7E+5 3.4E48 Co-58

8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 i

Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90

~4.1E+7 1.0F+8 1.1E+8 0-9.9E+7 -

Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 i

Ru-103 5.5E+5 1.1E+8 6.6E+5' 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 i

Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 7.0E+5 6.8E+9 1.0E+6-6.8E+9 1.1E+6 6.8E+9 8.5E+5 6.8E+9 Cs-136 1.3E+5 1.5E+8 1.7E+5 1.5E+8 1.9E+5 1.5E+8 1.5E+5 1.5E+8 Cs-137 6.1E+5 1.0E+10 9.1E+5 1.0E+~0 8.5E+5 1.0E+10 6.2E+5 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6

_7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 1

i

'I Inhalation Pathway, units =

""(f Food & Ground Pathway, units =

gj S023-0DCM 2-40 Revision 30 05-28-97

TABLE 2-8 D0SE PARAMETER R, FOR SECTOR Q j

Pathway = Surf Beach / Guard Shack Distance = 0.7 miles 3

X/Q=2.0E-06sec/m D/Q = 1.1E-08 m-8 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

hadio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway.

Pathway Pathway Pathway Pathway Pathway Pathway l

H -3 7.8E+0 4.2E+1 2.2E+2 Cr-51 1.2E+2 3.2E+4 6.9E+2 1.5E+5 2.5E+3 8.0E+5 Mn-54 1.1E+4 9.5E+6~

6.5E+4

4. 5 E+'i 2.4E+5 2.4E+8 Co-57

. 3.5E+3 2.4E+6 1.9E+4 1.1E+7 6.3E+4 5.9E+7 Co-58

~ 0- 7.6E+3 2.6E+6 4.4E+4 1.2E+7 1.6E+5 6.5E+7 Co-60 4.9E+4 1.5E+8 2.9E+5 7.0E+8 1.0E+6 3.7E+9 Sr-89 1.5E+4 1.5E+2 7.9E+4 7.1E+2 2.4E+5 3.7E+3 Sr-90 7.0E+5 3.5E+6 1.7E+7 Zr-95 -0--

1.5E+4 1.7E+6-8.8E+4 8.2E+6 3.0E+5 4.3E+7 Nb-95 0- 4.2E+3 9.4E+5 2.5E+4 4.5E+6 8.6E+4 2.3E+7 Ru-103 4.6E+3 7.5E+5 2.6E+4 3.6E+6 8.6E+4 1.9E+7 Te-129m

. 1.2E+4 1.4E+5 6.5E+4 6.4E+5 2.0E+5 3.4E+6 Cs-134 7.0E+3 4.7E+7

'3.7E+4 2.2E+8

1. 5 E+5 1.2E+9 Cs-136 1.2E+3 1.0E+6 6.3E+3 4.9E+6 2.5E+4 2.6E+7 Cs-137 6.3E+3 7.1E+7 2.8E+4 3.4E+8 1.1E+5 1.8E+9 Ba-140 1.2E+4 1.4E+5 6.6E+4 6.7E+5 2.2E+5 3.5E+6 Ce-141 3.8E+3 9.4E+4 2.0E+4 4.5E+5 6.2E+4 2.3E+6 Ce-144 8.2E+4 4.8E+5 4.4E+5 2.3E+6 1.3E+6 1.2E+7 I -131 1.1E+5 1.2E+5 4.8E+5 5.6E+5 2.0E+6 2.9E+6 I -132 1.3E+3 8.5E+3 4.9E+3 4.1E+4 2.0E+4 2.1E+5 I -133 2.7E+4 1.7 E+4 9.5E+4 8.0E+4 3.7E+5 4.2E+5 I -134 3.5E+2 3.1E+3 1.3E+3 1.5E+4 5.1E+3 7.7E+4 I

I -135 -0-'

5.5E+3 1.IE+4 2.0E+4 8.2E+4 7.7E+4 4.3E+5 UN-ID 6.9E+3 5.1E+6 4.1E+4 2.4E+7 1.5E+5 1.3E+8 Inhalation Pathway, units = p" 7"

Food h E-ound Pathway, units =

C1/ c S023-0DCM 2-42 Revision 30 05-28-97 i

=

_ TABLE 2-8 DOSE PARAMETER R, FOR SECTOR Q Page 5 of 9 lf Pathway =51AreaBeach[ Campground Distance = 1.2 miles X/Q=9.8E-07sec/m D/0=5.0E-09m-8 Infant Child

_ Teen Adult Inhala-Food &

Inhala-Food &

)

Radio-tion Ground-tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Path.4ay Pathway Pathway Pathway Pathway H -3 8.0E+01 1.4E+02 1.6E+02 1.6E+02 '

Cr-51 1.6E+03 5.7E+05 2.1E+03 5.7E+05 2.6E+03 5.7E+05 1.8E+03 5.7E+05 4

Mn-54 1.2E+05 1.7E+08 1.9E+05 1.7E+08 2.4E+05 1.7E+08 1.7E+05 1.7E+08 Co-57 4.7E+04 4.2E+07 6.3E+04 4.2E+07 7.2E+04 4.2E+07 4.6E+04 4.2E+07 Co-58 9.6E+04 4.7E+07 1.4E+05 4.7E+07 1.7E+05 4.7E+07 1.1E+05 4.7E+07 Co-60 5.6E+05 2.7E+09 8.7E+05 2.7E+09 1.1E+06 2.7E+09 7.4E+05 2.7E+09

_3 Sr-89_

2.5E+05 2.7E+03 2.7E+05 2.7E+03 3.0E+05 2.7E+03 1.7E+05 2.7E+03 i

Sr-90 5.0E+06 1.2E+07 1.3E+07 -1.2E+07 Zr-95 2.2E+05 3.1E+07 2.8E+05 3.1E+07 3.3E+05 3.1E+07 2.2E+05 3.1E+07 Nb-95 5.9E+04 1.7E+07 7.6E+04 1.7E+07 9.3E+04 1.7E+07 6.2E+04 1.7E+07 Ru-103 6.8E+04 1.3E+07 8.2E+04 1.3E+07 9.7E+04 1.3E+07 6.2E+04 1.3E+07 Te-129m 2.1E+05 2.4E+06 2.2E+05 2.4E+06 2.4E+05 2.4E+06 1.4E+05 2.4E+06 Cs-134 8.7E+04 8.4E+08 1.3E+05 8.4E+08 1.4E+05 8.4E+08 1.0E+05 8.4E+08 Cs-136 1.7E+04 1.9E+07 2.1E+04 1.9E+07 2.4E+04 1.9E+07 1.8E+04 1.9E+07 Cs-137 7.5E+04 1.3E+09 1.1E+05 1.3E+09 1.0E+05 1.3E+09 7.7E+04 1.3E+09 Ba-140 2.0E+05 2.5E+06 2.1E+05 2.5E+06 2.5E+05 2.5E+06 1.6E+05 2.5E+06 Ce-141 6.4E+04 1.7E+06 6.7E+04 1.7E+06 7.6E+04 1.7E+06 4.5E+04 1.7E+06 Ce-144 1.2E+06 8.6E+06 1.5E+06 8.6E+06 1.6E+06 8.6E+06 9.6E+05 8.6E+06 I -131 1.8E+06 2.1E+06 2.0E+06 2.1E+06 1.8E+06 2.1E+06 1.5E+06 2.1E+06 I -132 2.1E+04 1.5E+05 2.4E+04 1.5E+05 1.9E+04 1.5E+05 1.4E+04 1.5E+05 I.-133 4.4E+05 3.0E+05 4.7E+05 3.0E+05 3.6E+05 3.0E+05 2.7E+05 3.0E+05 I -134 5.5E+03 5.5E+04 6.3E+03 5.5E+04 4.9E+03 5.5E+04 3.7E+03 5.5E+04 I -135 8.6E+04 3.1E+05 9.8E+04 3.1E+05 7.7E+04 3.1E+05 5.5E+04 3.1E+05 UN-ID 8.0E+04 9.2E+07.

1.2E+05 9.2E+07 1.5E+05 9.2E+07 1.1E+05 9.2E+07 InhalationPathway, units =p"['"7" Food & Ground Pathway, units =

C1/ c e

5023-00CM 2-43 Revision 30 05-28-97 a

n TABLE 2-8 DOSE PARAMETER R, FOR SECTOR Q Page 3 of 9 lf Pathway = State Park Office Trailer Distance = 0.6 miles X/Q = 2.5E-6 sec/m' D/Q = 1.4E-8 nr2 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 5.8E+1 Cr-51 6.6E+2 2.1E+5 Mn-54 6.4E+4 6.3E+7 Co-57 1.7E+4 1.6E+7 Co-58 4.2E+4 1.7E+7 Co-60 2.7E+5 9.8E+8 Sr-89 6.4E+4 9.9E+2 Sr-90 4.5E+6 I Zr-95 8.1E+4 1.1E+7 Nb-95 2.3E+4 6.2E+6 Ru-103 2.3E+4 5.0E+6 Te-129m 5.3E+4 9.0E+5 Cs-134 3.9E+4 3.1E+8 3

Cs-136 6.7E+3 6.9E+6 Cs-137 2.8E+4 4.7E+8 Ba-140 5.8E+4 9.4E+5 Ce-141 1.7E+4 6.2E+5 Ce-144 3.6E+5 3.2E+6 I -131 5.4E+5 7.9E+5 I -132 5.2E+3 5.7E+4 I -133 9.8E+4 1.1E+5 I -134 1.4L+3 2.1E+4 I -135 2.0E+4 1.2E+5 UN-ID 3.9E+4 3.4E+7

)

i Inhalation Pathway, units =

yr Food & Ground Pathway, units =

Ci/ c 5023-0DCM 2-41 Revision 30 05-28-97

TABLE 2-8 DOSE PARAMETER R, FOR SECTOR Q Page 5 of 9 lf Pathway = S. C. Resident With Garden Distance = 4.4 miles X/Q = 1.2E-7 sec/m D/0 a 4.1E-2 m-2 0

3 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 4.0E+3 1.3E+3 2.6E+3 1.3E+3 2.2E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 1.1E+7 2.1E+4 1.4E+7 1.4E+4 1.5E+7 Mn-54 1.0E+6 1.4E+9 1.6E+6 2.0E+9 2.0E+6 2.3E+9 1.4E+6 2.3E+9 Co-57 3.8 E+5 3.4E+8 5.1E+5 5.8E+8 5.9E+5 6.6E+8 3.7E+5 6.2 E+8 Co-58 7.8 E+5 3.8E+8.

1.1E+6 7.4E+8 1.3E+6 9.5 E+8 9.3E+5 9.6E+8

)

C0-60 4.5E+6 2.2E+10 7.1E+6 2.4E+10 8.7E+6 2.5E+10 6.0E+6 2.5E+10

)

Sr-89 2.0E+6 2.2E+4 2.2E+6 3.4E+10 2.4E+6 1.4E+10 1.4E+6 9.3E+9 i

Sr-90 4.1E+7 1.0E+8 1.4E+12 1.1E+8 8.2F+11 9.9E+7 6.6E+11 Zr-95 1.8 E+6 2.5E+8 2.2E+6 1.1E+9 2.7E+6 1.5E+9 1.8E+6 1.4E+9 Nb-95 4.8E+5 1.4E+8 6.1E+5 4.2E+8 7.5E+5 5.7E+8 5.0E+5 5.8E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5

-4.9E+8 7.8E+5 6.6E+8 5.0E+5 6.3E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.8E+9 2.0E+6 1.7E+9 1.2E+6 1.4E+9 Cs-134 7.0E+5 6.8E+9 1.0E+6 3.2E+10 1.1E+6 2.3E+10 8.5E+5 1.7E+10

(

Cs-136 1.3E+5 1.5E+8 1.7E+5 3.5E+8 1.9E+5 3.0E+8 1.5E+5 3.0E+8 Cs-137 6.1E+5 1.0E+10 9.1E+5 3.5E+10

'8.5E+5 2.4E+10 6.2E+5 1.9E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.7E+8 2.0E+6 2.1E+8 1.3E+6 2.5E+8 Ce-141 5.2E+5 1.4E+7 5.4E+5 4.0E+8 6.1E+5 5.2E+8 3.6E+5 4.8E+8 Ce-144 9.8E+6 7.0E+7 1.2E+7 9.9E+9 1.3E+7 1.3E+10 7.8E+6 1.0E+10 I -131.

1.5E+7 1.7E+7-1.6E+7 4.0E+10 1.5E+7 2.6E+10 1.2E+7 3.2E+10 I -132 1.7E+5 1.2E46 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 6.7E+8 2.9E+6 3.8E+8 2.2E+6 4.4E+8 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 1.1E+7 6.2E+5 7.3E+6 4.5E+5 8.0E+6 1

UN-ID 6.5E+5 7.5E+8 1.0E+6 3.4E+9 1.2E+6 2.6E+9 8.6E+5 2.0E+9 Inhalation Pathway, units = p" Food & Ground Pathway, units =

Ci s c S023-0DCM 2-44 Revision 31 02-27-98 M '

a TABLE 2-8 DOSE PARAMETER R, FOR SECTOR Q Page 7 of 9 p

Pathway =-SanClementeRanch(NoResidents)

Distance = 2.2 miles X/Q=3.5E-7sec/m' D/Q = 1.5E-9 m.:

Infant Child Tecn-Adult Inhala-Food &

Inhala.

Food &

Inhala-Food &

Radio-tion Ground-tion Ground tion Ground.

tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 - 3.8E+3 2.4E+3 1.9E+3 Cr-51 - 4.8E+6 7.4E+6 6.7E+6

{

Mn-54 6.1E+8 8.3E+8 8.0E+8 l

Co-57. 2.2E+8 2.9E+8 2.4E+8

)

Co 3.3E+8 5.1E+8 4.7E+8 j

Co-60 2.0E+9 3.0E+9 2.7E+9 j

Sr-89 3.1E+10 1.2E+10 7.2E+9 Sr-90 1.3E+12 7.7E+11 5.8 E+11 Zr-95 7.8E+8 1.1E+9 9.1E+8 Nb-95 2.4E+8 3.5E+8 3.1E+8 Ru-103 ' 3.3E+8 4.5E+8 3.8E+8 Te-129m 2.3E+9 1.4E+9 9.5E+8 j

Cs-134-2.4E+10 1.5E+10 9.2E+9 Cs-136 9.0E+7 5.7E+7 3.6E+7 Cs-137-2.3E+10 1.3E+10 7.8E+9 Ba-140 1.1E+8 6.8E+7 5.3E+7

-)

Ce-141 3.3E+8 4.1E+8 3.2E+8 Ce-144 9.2E+9 1;2E+10 9.0E+9 I -131 4.1E+9 2.1E+9 1.4E+9 I -132 - 6.0E-36 2.6E-36 1.7E-36 I -133 4.0E-11 1.7E-11 1.1E-11 I -134 6.1E-37 2.7E-37 1.7E-37 I -135 7.0E-35 3.1E-35 1.9E-35 UN-ID 2.5E+9 1.7E+9 1.1E+9

' Inhalation Pathway, units = p" 7"

Food & Ground Pathway, units -

Ci/ c 1

5023-0DCM 2-45 Revision 30 05-28-97

1 TABLE 2-8 D0SE PARAMETER R FOR SECTOR Q Page 8 of 9 lF Pathway = San Clemente Ranch Adm. Offices Distance = 2.6 miles X/Q=2.7E-7sec/m' D/Q = 1.1E-9 m'8 Infant Child Teen Adult 1

I Inhala-Food &

Inhala-Food &

Radio-tion-Ground tion Ground tion Ground tion Ground l

Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 4.3E+02 Cr-51. 4.9E+03 1.6E+06 Mn-54 4.8E+05 4.7E+08 Co-57 1.3E+05 1.2E+08 i

Co-58 3.2E+05 1.3E+08 Co-60 2.0E+06 7.4E+09 Sr-89 4.8E+05 7.4E+03 1

Sr-90. -0-- 3.4E+07 Zr-95 ' 0- 6.1E+05 8.6E+07 Nb-95 1.7E+05 4.7E+07 Ru-103 1.7E+05 3.7E+07 Te-129m 4.0E+05 6.7E+06 Cs-134 2.9E+05 2.3E+09 Cs-136 5.0E+04 5.1E+07 Cs-137 -C-2.1E+05 3.5E+09 Ba-140 4.4E+05 7.0E406 Ce-141 1.2E+05 4.7E+06 Ce-144 2.7E+06 2.4E+07 I -131 4.1E+06 5.9E+06 I -132 3.9E+04 4.2E+05 I -133 -0-. 7.4E+05 8.4E+05 I -134 1.0E+04 1.5E+05 I -135 1.5E+05 8.6E+05 UN-ID 3.0E+05 2.6E+08 2

InhalationPathway, units =p""'"7"

' food & Ground Pathway, units =

Ci/

i I

S023-0DCM 2-46 Revision 30 05-28-97 i

l

I I

TABLE 2-8 DOSE PARAMETER R, FOR SECTOR Q Page 9 of 9

)

Pathway = Outage Workers Distance = 0.7 miles f

X/Q=2.0E-6sec/m' D/Q = 1.1E-8 m-8 Infant Child Teen Adult Inhala-Food &

Inhala-Fc9d &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 4.5E+2 Cr-51. 5.1E+3 1,7E+6 Mn-54 5.0E+5 4.9E+8 Co-57 - 1.3E+5 1.2E+8 Co-58 3.3E+5 1.4E+8 Co-60 2.1E+6 7.7E+9 Sr-89 5.0E+5 7.7E+3 Sr-90 3.5E+7 Zr-95 6.3E+5 8.9E+7 Nb-95 1.8E+5 4.9E+7 Ru-103 1.8E+5 3.9E+7 Te-129m 4.1E+5 7.0E+6 Cs-134 3.0E+5 2.4E+9 Cs-136 5.2E+4 5.3E+7 g

Cs-137 2.2E+5 3.7E+9 Ba-140 4.5E+5 7.3E+6 Ce-141 1.3E+5 4.9E+6 Ce-144 2.8E+6 2.5E+7 I -131 4.2E+6 6.1E+6 I -132 4.1E+4 4.4E+5 I -133 7.7E+5 8.7E+5 I -134 1.1E+4 1.6E+5 I -135 1.6E+5 9.0E+5 UN-ID 3.1E+5 2.7E+8 Inhalation Pathway, units =

yr r

Food & Grour.d Pathway, units = (m Hmrem/vri pCi/sec S023-0DCM 2-47 Revision 31 02-27-98

TABLE 2-9 l

DOSE PARAMETER R, FOR SECTOR R Page 1 of 3

~

Pathway =' San Onofre Mobile Homes Distance = 1.3 miles 3

X/Q=5.2E-7sec/m D/Q = 3.0E-9 nr' Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway.

Pathway Pathway 4

H -3 6.5E+2' 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4 E+4 4.7E+6 Mn-54

-1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Co-57 3.8E+5 3.4E+8 5.1E+5 3.4E+8 5.9E+5 3.4E+8 3.7E+5 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-E0 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 4.1E+7 1.0E+8 1.1E+8 9.9E+7 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Mb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 7.0E+5 6.8E+9 1.0E+6 6.8E+9 1.1E+6 6.8E+9 8.5E+5 6.8E+9 Cs-136 1.3E+5 1.5E+8 1.7E+5 1.5E+8 1.9E+5 1.5E+8 1.5E+5 1.5E+8 Cs-137 6.1E+5 1.0E+10 9.1E+5 1.0E+10 8.5E+5 1.0E+10 6.2E+5 1.0E+10 Ba-140 1.6E+6 2.1E47 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141-5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6

1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8 E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 Ix-134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5

~I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 l

I' Inhalation Pathway, units = } h "

l Food & Ground Pathway, units =

Ct/

l' 5023-0DCM 2-48 Revision 30 05-28-97

TABLE 2-9 DOSE PARAMETER R FOR SECTOR R Page 2 of 3 Pathway = San Clemente Ranch (No Residents)

Distance = 2.3 miles 8

4 X/Q=2.1E-7sec/m D/Q = 1.4E-9 m Infant Child Teer; Adul t Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.BE+3 2.4E+3 1.9E+3 Cr-51 4.8E+6 7.4E+6 6.7E+6 Mn-54 6.1E+8 8.3E+8 8.0E+8 Co-57 2.2E+8 2.9E+8 2.4E+8 Co-58 3.3E+8 5.1E+8 4.7E+8 Co-60 2.0E+9 3.0E+9 2.7E+9 Sr-89 3.1E+10 1.2E+10 7.2E+9 Sr-90 1.3E+12 7.7E+11 5.8E+11 Zr-95 7.8E+8 1.1E+9 9.1E+8 Nb-95 2.4 E+8 3.5E+8 3.1E+8 Ru-103 3.3E+8 4.5E+8 3.8E+8 Te-129m 2.3E+9 1.4E+9 9.5E+8 Cs-134 2.4E+10 1.5E+10 9.2E+9 Cs-136 9.0E+7 5.7E+7 3.6E+7 Cs-137 2.3E+10 1.3E+10 7.8E+9 Ba-140 1.1E+8 6.8E+7 5.3E+7 Ce-141 3.3E+8 4.1E+8 3.2E+8 Ce-144 9.2E+9 1.2E+10 9.0E+9 I -131. 4.1E+9 2.1E+9 1.4E+9 I -132 6.0E-36 2.6E-36 1.7E-36 I -133 4.0E-11 1.7E-11 1.1E-11 I -134 6.1E-37 2.7E-37 1.7E-37 I -135 7.0E-35 3.1E-35 1.9E-35 UN-ID 2.5E+9 i.7E+9 1.1E+9 l

InhalationPathway, units ="['*[7" Food & Ground Pathway, units =

Ci/ c l

l S023-00CM i

2-49 Revision 30 05-28-97 a

a r

TABLE 2-9 D0SE PARAMETER R FOR SECTOR R Page 3 of 3 Pathway = SC Ranch Packing Distance = 2.6 miles l

-X/Q=1.7E-07sec/m' D/Q=8.4E-10m'8 l

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio -

tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 4.9E+2 Cr-51 5.6E+3 1.8E+6 Mn-54 5.4E+5 5.3E+8 Co-57 1.4E+5 1.3E+8 Co-58 3.6E+5 1.5E+8 i

Co-60 2.3E+6 8.3E+9

)

Sr-89 5.4E+5 8.3E+3-1 Sr-90 3.8E+7 l Zr-95 6.8E+5 9.7E+7 Nb-95 1.9E+5 5.3E+7 Ru-103 1.9E+5 4.2E+7 Te-129m 4.5E+5 7.6E+6 k

Cs-134 3.3E+5 2.6E+9 Cs-136 5.6E+4 5.8E+7 Cs-137 2.4 E+5 4.0E+9 Ba-140 4.9E+5 7.9E+6 Ce-141 1.4E+5 5.3E+6 Ce-144 3.0E+6 2.7E+7 I -131 4.6Ev6 6.6E+6 I -132' 4.4E+4 4.8E+5 J

I -133 8.3E+5 9.4E+5 d

I -134 1.2E+4 1.7E+5 1 -135 1.7E+5 9.7E+5 UN-ID 3.3E+5 2.9E+8 Inhaletion Pathway, units = p" 7"

Food & Ground Pathway, units =

Ci/sc w

5023-0DCM 2-50 Revision 31 02-27-98

TABLE 2-10 DOSE PARAMETER R, FOR SECTOR A Page 1 of 2 Pathway = camp San Mateo Distance = 3.6 miles

'X/Q=7.2E-8sec/m' D/Q=4.1E-10m.:

Infant Child Teen Adult Inhala-Food &

inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51

- 1.4E+4 4.7E+6 Mn-54. 1.4E+6 1.4E+9 Co-57 3.7E+5 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 - 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.9E+7 Zr-95 1.8E+6 2.5E+8 Mb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 8.5E+5 6.8E+9 Cs-136

' 0- 1.5E+5 1.5E+8 Cs-137 6.2E+5 1.0E+10 i

Ba-140 1.3E+6 2.1E+7 i

Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 -G-3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 Inhalation Pathway, units =

h" Food & Ground Pathway, units = (m'1(rrem/vr) pC1/sec S023-0DCM 2-51 Revision 30 05-28-97

TABLE 2-11 DOSE PARANETER R FOR SECTOR 8 Page 2 of 2 Pathway = Sanitary Landfill Distance = 2.1 miles X/Q=.1.3E-7sec/m'.

D/Q=1.1E-9m2 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground' tion Ground tion' Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.9E+2 Cr-51 -0-' 3.3E+3 1.1E+6 Mn-54 3.2E+5 3.2E+8 C0-57 8.4E+4-7.8E+7 Co-58

. 2.1E+5 8.7E+7 Co-60 1.4E+6 4.9E+9

)

Sr-89 3.2E+5 4.9E+3 Sr-90 2.3E+7 Zr-95 4.0E+5 5.7E+7 Nb-95 1.2E+5 3.1E+7 Ru-103 3-1.2E+5 2.5E+7 Te-129m 2.6E+5 4.5E+6 Cs-134 1.9E+5 1.6E+9 Cs-136 3.3E+4 3.4E+7 Cs-137 1.4E+5 2.3E+9 i

Ba-140 2.9E+5 4.7E+6 Ce-141 8.3E+4 3.1E+6 j

Ce-144

-0. ' 0- 1.8E+6 1.6E+7 I -131 2.7E+6 3.9E+6 I -132 '

~ 0- 2.6E+4 2.8E+5 I -133 4.9E+5 5.6E+5 I -134 6.8E+3 1.0E+5 I -135 1.0E+5 5.8E+5 UN-ID 2.0E+5 1.7E+8 Inhalation Pathway, units =

7" Food & Ground Pathway, units =

C1/ c S023-0DCM 2-54 Revision 30 05-28-97

r.

4 1

i TABLE 2-12 DOSE PARAMETER R. FOR SECTOR C Page 1 of 4 Pathway = Camp San Onofre Distance = 2.6 miles X/Q=9.7E-8sec/m'.

D/Q = 8.9E-10 m-2 j

Infant Child Teen Adult 1

Inhala-Food &

Radio-tion-Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 -0 ' 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54

- 1.4E+6 1.4E+9 Co-57 3.7E+5 3.4 E+8 Co-58 9.3E+5 3.8E+8 Co -0. 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.9E+7 Zr-95 - 1.8E+6 2.5E+8 Mb ' 0-

-0 ' 5.0E+5 1.4E+8 Ru-103 -0. 5.0E+5 1.1E+8 Te-129m 1.2C+6 2.0E+7 Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+5 1.5E+8 Cs-137 6.2E+5 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 1 -131~ 0- 1.2E+7 1.7E+7 I~-132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 i

! -134' - 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 Inhalation. Pathway, units = p*

VI

~ Food &' Ground Pathway, units =

pCi/ c J

S023-00CM 2-55 Revision 30 05-28-97 1

r:

TABLE 2-12.

D0SE PARAMETER R, FOR SECTOR C Page 2 of 4 l

Pathway = Camp San Onofre Fr. Stn Distance = 2.5 miles X/Q=1.0E-7sec/m

D/Q=9.4E-10m.:

Infant Child Teen Adult Inhala-Food &-

Inhala-Food &

Radio-

. tion Ground tion Ground ~

tion Ground tion Ground Nuclide~

Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 5.2E+2 Cr-51 5.9E+3 1.9E+6 Mn-54 5.8E+5 5.7E+8 Co 1.5E+5 1.4E+8 Co-58

' 0- ' 3.8E+5 1.6E+8 Co-60 -0 '

2.5E+6 8.8E+9

)

Sr-89' - 5.8 E+5 8.9E+3

)

Sr-90 -0. 4.1E+7 j Zr -0 ' 7.3E+5 1.0E+8 Nb-95 2.1E+5 5.6E+7 i

Ru-103 2.1E+5 4.5E+7 Te-129m 4.8E+5 8.1E+6 Cs-134 3.5E+5 2.8E+9 Cs-136. 6.0 E+4 6.2E+7 Cs-137 2.6E+5 4.2E+9 Ba-140 5.2E+5 8.4E+6 j

Ce-141 ' 0- 1.5E+5 5.6E+ 6 1

Ce-144 3.2 E+6 2.9E+7 I -131 4.9E+6 7.1E+6 I -132 4.7E+4 5.1E+5 I.133 ~ 8.8E+5 1.0E+6 I -134 1.2E+4 1.8E+5 I -135-1.8E+5 1.0E+6 UN-ID 3.6E+5 3.1E+8 InhalationPathway, units =p"[{"[#

Food & Ground Pathway, units =

Ci/ c S023-0DCM 2-56 Revision 30 05-28-97 s

1

l i

TABLE 2-12 DOSE PARAMETER R FOR SECTOR C Page 3 of 4 Pathway =' Sewage Facility Distance = 2.2 miles 3

X/Q = 1.3E-7 sec/m 0/Q=1.2E-9m'2 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Inhal a-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 -0 ' 2.9E+2 Cr-51

-0. 3.3E+3 1.1E+6 Mn-54 -0-- 3.2E+5 3.2E+8 Co-57

-0. 8.4E+4 7.8E+7 Co-58 2.1E+5 8.7E+7 Co-60 1.4 E+6 4.9E+9 Sr-89 3.2E+5 4.9E+3 Sr-90 2.3Et7 Zr-95 4.0E+5 5.7E+7 Nb-95 1.2E+5 3.1E+7 Ru-103 -0 ~ 1.2E+5 2.5E+7 Te-129m 2.6E+5 4.5E+6 Cs-134 1.9E+5 1.6E+9 Cs-136 3.3E+4 3.4E+7 Cs-137 1.4E+5 2.3E+9 Ba-140. 2.9E+5 4.7E+6 Ce-141 8.3E+4 3.1E+6 Ce-144 -0 = 1.8E+6 1.6E+7 I -131 -0 ' 2.7E+6 3.9E+6 I -132 2.6E+4 2.8E+5 I -133. 4.9E+5 5.6E+5 I -134 6.8E+3 1.0E+5 I -135 -0-- 1.0E+5 5.8E+5

.UN-ID - 2.0E+5 1.7E+8 Inhalation Pathway, units = p*"'"7"

~

' Food & Ground Pathway, units =

Ci/ c S023-0DCM 2-57 Revision 30 05-28-97

TABLE 2-12 DOSE PARAMETER R. FOR SECTOR C Page 4 of 4 Pathway =DeerConsumer/ Hunter Distance = 1.0 miles X/Q=4.0E-7sec/m' D/Q = 4.6E-9 nr Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 0- 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 0- 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 0- 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 0- 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 0- 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 0- 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 0- 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 0- 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 0- 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Nb-95 0- 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 0- 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 0- 5.9E+8 4.5E+8 3.2E+4 6.4E4 8 Cs-134 0- 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 0- 5.1E+6 4.2E+6 4.0E+3 9.5E+6 i

Cs-137 0- 1.3E+8 9.3 E+7 1.7E+4 4.0E+8 Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 0- 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 0- 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 0- 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132

> 3.1E+3 3.4E+4 1 -133 0- 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 0- 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 0- 1.1E+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = p*

[#

Food & Ground Pathway, units =

Ci/ c S023-00CM 2-58 Revision 30 05-28-97 i_m._..._.......

_......._..._.2m._

TABLE 2-13 DOSE PARAMETER R. FOR SECTOR D Page 1 of 2 Pathway = Camp San Onofre Distance = 3.0 miles X/Q=6.9E-8sec/m' 0/Q=7.2E-10mr Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Inhala-food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 {

Cr-51 1.4E+4 4.7E+6 i

Mn-54 1.4E+6 1.4E+9 Co-57 3.7E+5 3.4E+8 i

Co-58 9.3E+5 3.8E+8 i

Cc 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2 E+4 Sr-90 9.9E+7 Zr-95 1.8E+6 2.5E+8 Mb-95 5.0E+5 1.4E+8 Ru-103 -0-- 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+5 1.5E+8 Cs-137 6.2E+5 1.0E+10 Ba-140 -0-- 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 j

I -132 1.1E+5 1.2E+6 j

I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 Inhalation Pathway, units = p" i

Food & Ground Pathway, units = I* II""**/V"I pC1/sec

)

I l

l 1

S023-00CM 2-59 Revision 30 i

05-28-97

)

i l

TABLE 2-13 DOSE PARAMETER R FOR SECTOR D Page 2 of 2 Pathway =DeerConsumer/ Hunter Distance = 0.8 miles X/Q=5.3E-7sec/m' 0/Q=7.3E-9m'8 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 4.6E+6 8.0E+6 1.0E+4' 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7

{

Sr-90 1.0E+9 8. 0 E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 '1.3E+8 9.3E+7 1.7E+4 4.0E+8 l

Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-IO 1.1E+8 9.4E+7 2.4E+4 1.4E+8

)

i i

Inhalation Pathway, units =

7" Food & Ground Pathway, units =

C1/ c l

S023-0DCM 2-60 Revision 30 05-28-97 i

l l

I

e TABLE 2-14 DOSE PARAMETER R, FOR SECTOR E Page 1 of 3 Pathway = Camp Horno Distance = 4.1 miles X/Q=7.5E-8sec/m' D/Q=7.2E-10m'8 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 -0-- -0 1.4E+6 1.4E+9 Co-57 3.7E+5 3.4E+8 Co 9.3E+5 3.8 E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.9E+7 2r-95 1.4E+6 2.5E+8 Mb-95 - 5.dE+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 8.5E+5 6.8E+9 Cs-136 - 1.5E+5 1.5 E+8 Cs-137 6.2E+5 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131

-0. 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 ~ -4.5E+5 2.5E+6 UN-10 8.6E+5 7.5E+8 Inhalation Pathway, units = [

V" Food & Ground Pathway, units =

C1/ c S023-0DCM 2-61 Revision 30 05-28-97

3-

)

TABLE 2-14 DCSE PARAMETER R FOR SECTOR E Page 2 of 3 Pathway = Sheep (Meat)[ Shepherd Distance = 5.0 miles X/f)=5.6E-8sec/m 0/0=5.0E-10m'8 i

Infant Child Teen Adult 1

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 Cr-51 5.1E+1 1.0E+2 7.9E+1 2.6E+4 l

Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 4.7E+3 8.1E+3 2.0E+3 1.9E+6 Co-58 9.7E+3 2.0E+4 5.1E+3 2.1E+6 Co-60 -0-. 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Sr-89 5.0E+4 2.6E+4 7.7E+3 3.1E+4 Sr-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.1E+5 9.7E+3 1.6E+6 Nb-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 Te-129m 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Cs-134 1.4E+5 1.2E+5 4./E+3 3.8E+7 Cs-136 5.1E+3 4.3E+3 8.1E+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5 Ce-141 1.5Eo3 2.4E+3 2.0E+3 7.9E+4 Ce-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I -131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 I -132 6.3E+2 6.8E+3 I -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 1 -134 1.6E+2 2.5E+3 I -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units = p" Food & Ground Pathway, units =

Ci/

S023-00CM 2-62 Revision 30 05-28-97

f ii TABLE 2-14 DOSE PARAMdTER R. FOR SECTOR E Page 3 of 3 Pathway = Oeer Consumer / Hunter Distance = 0.8 miles X/Q=8.5E-7sec/m' 0/Q = 1.3E-8 nrr Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 - 2.8E+1-2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Mb-95 2.3E+8 4.5E+8 1.4 E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4 E+4 1.3 E+9 Te-129m

' 0- 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3 E+4 3.4E+8 Cs-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 -0--

1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 1 -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-10 1.1E+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units =

["

Food & Ground Pathway, units =

Ci/ c S023-0DCM 2-63 Revision 30 05-28-97

l_

TABLE 2-15 DOSE PARAMETER R FOR SECTOR F Page 1 of 4 i

Pathway =SanOnofreStatePark/GuardShack Distance = 0.8 miles 8

X/Q=9.6E-7sec/m D/Q=8.4E-9m'8 l

Infant Child Teen Adult i

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway.

Pathway Pathway Pathway H -3

-0.

' 2.2E+2 Cr-51 2.5E+3 8.0E+5 Mn-54~ 2.4E+5 2.4E+8 Co-57 -- 6. 3E+4 '

5.9E+7 Co-58 -0-- 1.6E+5 6.5E+7 Co-60 1.0E+6 3.7E+9 Sr-89 2.4E+5 3.7E+3 Sr-90' 1.7E+7 l Zr-95 3.0E+5 4.3E+7 l-Nb-95 8.6E+4 2.3E+7 l

Ru-103 -0-- 8.6E+4 1.9E+7 Te-129m

-0. 2.0E+5 3.4E+6 Cs-134.

' 0- 1.5E+5 1.2E+9 Cs-136 2.5E+4 2.6E+7 f

Cs-137. 1.1E+5 1.8E+9 Ba-140 - 2.2E+5 3.5E+6 Ce-141 6.2E+4 2.3E+6 Ce-144 1.3E+6 1.2E+7 l

I -131 - 2.0E+6 2.9E+6 l

I -132 2.0E+4 2.1E+5 L

I -133 3.7E+5 4.2E+5 l

1 -134-5.1E+3 7 7E+4 i

I -135 7.7E+4 4.3E+5 UN-ID 1.5E+5 1.3E+8 l

f

(

Inhalation Pathway, units = p" 7"

Food & Ground Pathway, units =

C1/ c I

S023-0DCM 2-64 Revision 30 05-28-97 h

E L

TABLE 2-15 DOSE PARAMETER R FOR SECTOR.F Page 2 of 4 l

Pathway = Border Patrol Checkpt.

Distance = 1.8 miles X/Q=2.8E-7sec/m' 0/0=2.1E-9m'8 i

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.6E+2 Cr-51 4.1E+3 1.3E+6 Mn-54 4.0E+5 3.9E+8 Co-57 ~1.1E+5 9.8E+7 Co-58 2.6E+5 1.1E+8 00-60 -

1.7E+6 6.1E+9 Sr-89 4.0E+5 6.2E+3 Sr-90 ' 0- 2.8E+7 -

2r-95 5.0E+5 7.2E+7 Nb-95 1.4E+5 3.9E+7 Ru-103 1.4E+5 3.1E+7 Te-129m 3.3E+5 5.6E+6 Cs-134 '2.4E+5 1.9E+9 Cs-136 y 4.2E+4 4.3E+7 Cs-137 1.8E+5 2.9E+9 Ba-140 ~ 0- 3.6E+5 5.9E+6 Ce-141 1.0E+5 3.9E+6 Ce-144 2.2E+6 2.0E+7 I -131

-0. -0-- 3.4E+6 4.9E+6 I -132 3.3E+4 3.5E+5 I -133 6.1E+5 7.0E+5 I -134 8.5E+3 1.3E+5 I -135 1.3E+5 7.2E+5 UN-IO 2.5E+5 2.1E+8 l

1 Inhalation Pathway, units = p*

Y" Food & Ground Pathway, units =

Ci/ c S023-00CM 2-65 Revision 30 05-28-97

p I

TABLE 2-15 DOSE PARAMETER R. FOR SECTOR F

[

Page 3 of 4 Pathway = Sheep (Meat)'/ Shepherd Distance = 5.0 miles X/Q=6.2E-8sec/m D/Q = 3.3E-10 m4 I'fant Child Teen Adult n

Inhala-Food &

Inhala-Food.&

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway l

H -3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 l

Cr-51 5.1E+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 - 4.7E+3 8.1E+3 2.0E+3 1.9E+6 Co-58 9.7E+3-2.0E+4 5.1E+3 2.1E+6 Co-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 l

Sr-89 5.0E+4 2.6E+4 7.7E+3 3.1E+4 Sr-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 2r-95 6.3E+4 1.1E+5 9.7E+3 1.6E+6 Nb-95' 2.4E+5 4.5E+5 2.8E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 l

Te-129m 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 l

Cs-136 5.1E+3 4.3E+3 8.1E+2 8.3E+5 i

Cs-137-1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5 Ce-141 1.5E+3-2.4E+3 2.0E+3 7.9E+4 Ce.144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I -131 6.6E+5

- 4.4E+5 6.6E+4 7.0E+5 l

1 -132-6.3E+2 6.8E+3 I -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 i

I -134 1.6E+2 2.5E+3 l

I -135 1.1E-18

-0.

6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 l

I l'

' Inhalation Pathway, units =

h" Food'&' Ground Pathway, units -

Ci/ c S023-0DCM 2-66 Revision 30 05-28-97 L

TABLE 2 DOSE PARAMETER R, FOR SECTOR F Page 4 of 4 Pathway =DeerConsumer/ Hunter Distance = 1.5 miles X/Q=3.6E-7sec/m' 0/Q = 2.8E-9 m-'

+

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Inhala- ' Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Mb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103. 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136' 5.1E+6 4.2E+6 4.0E+3 9.5E+6 Cs-137-1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 5.0E+6 4.2E+6 3.5 E+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.1E+5-4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = p*

Y" Food & Ground Pathway, units =

Ci/ c S023-0DCM 2-67 Revision 30 05-28-97

TABLE 2-16 DOSE PARAMETER R, FOR SECTOR G Page 1 of 2 Pathway = San Onofre State Beach Campground Distance = 0.9 miles I

X/Q=6.6E-7sec/m' D/Q=3.3E-9m-8 i

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 8.0E+1 1.4E+2 1.6E+2 2.9E+2 Cr-51 1.6E+3-5.7E+5 2.1E+3 5.7E+5 2.6E+3 5.7E+5 3.3E+3 1.1E+6 Mn-54 1.2E+5 1.7 E+8

- 1.9E+5 1.7E+8 2.4E+5 1.7E+8 3.2E+5 3.2E+8 Co 4.7E+4 4.2E+7-6.3E+4 4.2E+7 7.2E+4 4.2E+7 8.4E+4 7.8E+7 Co-58 9.6E+4 4.7E+7 1.4E+5 4.7E+7 1.7E+5 4.7E+7 2.1E+5 8.7E+7 Co-60 5.6E+5 2.7E+9 8.7E+5 2.7E+9 1.1E+6 2.7E+9 1.4E+6 4.9E+9 Sr-89 2.5E+5 2.7 E+3 2.7E+5 2.7E+3 3.0E+5 2.7E+3 3.2E+5 4.9E+3 i

Sr-90 5.0E+6 1.2E+7 1.3E+7 2.3E+7 'l Zr-95 2.2E+5 3.1E+7 2.8E+5 3.1E+7 3.3E+5 3.1E+7 4.0E+5 5.7E+7 Nb-95 5.9E+4 1.7E+7 7.6E+4 1.7E+7 9.3E+4 1.7E+7 1.2E+5 3.1E+7 Ru-103 6.8E+4 1.3E+7 8.2E+4 1.3E+7 9.7E+4 1.3E+7 1.2E+5 2.5E+7

)

Te-129m 2.1E+5 2.4E+6 2.2E+5 2.4E+6 2.4E+5 2.4E+6 2.6E+5 4.5E+6 Cs 534 8.7E+4 8.4E+8 1.3E+5 8.4E+8 1.4E+5 8.4E+8 1.9E+5 1.6E+9 b

Cs-136 1.7E+4 1.9E+7 2.1E+4 1.9E+7 2.4E+4' 1.9E+7 3.3E+4 3.4E+7 Cs-137

'7.5E+4 1.3E+9 1.1E+5 1.3E+9 1.0E+5 1.3E+9 1.4E+5 2.3E+9 Ba-140 2.0E+5 2.5E+6 2.1E+5 2.5 E+6 2.5E+5 2.5E+6 2.9E+5 4.7E+6 Ce-141 6.4E+4 1.7E+6 6.7E+4 1.7E+6 7.6E+4

- 1.7E+6 8.3E+4 3.1E+6 Ce-144 1.2E+6-8.6E+6 1.5E+6 8.6E+6 1.6E+6 8.6E+6 1.8E+6 1.6E+7 I -131 1.8E+6 2.1E+6 2.0E+6' 2.1E+6 1.8E+6 2.1E+6 2.7E+6 3.9E+6 I -132 2.1E+4 1.5E+5 2.4E+4 1.5E+5 1.9E+4 1.5E+5 2.6E+4 2.8E+5 1 -133 4.4E+5 3.0E+5 4.7E+5 3.0E+5 3.6E+5 3.0E+5 4.9E+5 5.6E+5 1.-134 5.5E+3 5.5E+4 6.3E+3 5.5E+4 4.9E+3-5.5E+4 6.8E+3 1.0 E+5 I -135 8.6E+4 3.1E+5 9.8E+4 3.1E+5 7.7E+4 3.1E+5 1.0E+5 5.8E+5 UN-ID 8.0E+4 9.2E+7 1.2E+5 9.2E+7 1.5E+5 9.2E+7 2.0E+5 1.7E+8 l

I I

Inhalation Pathway, units = p*

Food & Ground Pathway, units =

Ci/ c S023-0DCM 2-68 Revision 31 02-27-98

I V

TABLE 2-16 DOSE PARAMETER R, FOR SECTOR _ G j

Page 2 of 2 l

Pathway = Hwy Patrol Weigh Station Distance = 2.0 miles X/Q=1.9E-7sec/m' 0/Q = 8.0E-10 m-2 Infant Child' Teen Adult Inhala-Food &

Inhala-Food &

Inhala-Food &'

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground i

)

Muclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 - 3.0E+2 Cr-51 3.4E+3' 1.1E+6 Mn-54 3.3E+5 3.3E+8 Co-57 8.RF.+4 8.1E+7 4

Co-58 -0-- 2 %+5 9.0E+7.

Co-60 1.4E+6 5.1E+9 Sr-89 3.3E+5 5.1E+3 Sr-90 2.4E+7 Zr-95

-0 ' 4.2E+5 6.0E+7 Nb-95 1.2E+5 3.2E+7 Ru-103 1.2E+5 2.6E+7 Te-129m 2.8E+5 4.7E+6 Cs-134 2.0E+5 1.6E+9 Cs-136 3.5E+4 3.6E+7 Cs-137' 1.5E+5 2.4E+9 8a-140 3.0E+5 4.9E+6 Ce-141 8.6E+4 3.2E+6 Ce-144 1.8E+6 1.7E+6 I -131-2.8E+6 4.1E+6 I -132 -G-2.7E+4 2.9E+5 I -133 5.1E+5 5.8E+5 1 -134 7.1E+3 1.1E+5 I -135 1.1E+5 6.0E+5!

UN-10 2.1E+5 1.8E+8 Inhalation Pathway, units =

7" Food & Ground Pathway, units ='

Cf/ c S023-0DCH 2-69 Revision 30 05-28-97 L

l

q 2.0 GASEGUS EFFLUENTS (Ontinued) l' 2.9 TOTAL DOSE ( ALCULATIONS 2.9.1 Total Dose to Most Likely Member of the Public l

The total annual dose or total dose comitment to any member of the public, due to releases of radioactivity and to radiation, from uranium fuel' cy'ia sources within 5 miles of the Site is calculated using the following expresd ons.

This methodology is used to meet the dose limitations of 40 l

CFR 190 per twelve consecutive months. The transportation of j

radioactive material is excluded from the dose calculations.

l The Annual Total Dose is determined monthly for maximum i

organ (gas & liquid), whole body (gas & liquid) and thyroid j

(gas & liquid) to verify that the Site total (Units 1, 2 and

3) is less than or equal to 25 mrem, 25 mrem, and 75 mrem respectively.

.1 Annual Total Oraan Dose (Dry (0))

12 2/3 (2-20)

D (OG)+ D (0L)+ D[3 (OG)

D,, (0) = E E

g p

1=1 j=1 where:

NOTE: D (OG) = 0 for bone

- All to be sumed gver the most recent 12 months.

Dp (OG) = K E C, E, R,, W (2-21) l e

i=1

)

l 1 = each isotope in specific organ category l

j = Units 1, 2 and 3 1 = months 1 - 12**

j

'"#~#

K = 3.1688 E-2 I

sec-Ci l

S023-0DCM 2-70 Revision 21 02-15-90 i

l j

3 l

2.0' GASE0US EFFLUENT 3 (Continued) 2.9 TOTAL D0SE CALCULATIONS (Continued) 1 2.9.1 Total Dose to Most Likely Member of the Public (Continued) number of isotopes in the specified organ category n

=

C, total particulate gas curies released for the month

=

ERaW, controlling lo:ation factors from 00CM Table 2-5,

=

k Unit 1 and Table 2-6, Units 2/3, for all pathways k.

D (0L) liquid organ dose for the specified organ in mrem for

=

o the month.

[ Reference ODCM Units 2/3 (1-19), Unit 1 (1-13)]

on i

D"i(OG)* = gas organ dose form tritium in mrem for the month.

i 3

[ Reference ODCM Unit 1 (2-14), ODCM Units 2/3 (2-18)]

i

.2 Annual Total Whole Body Dose DmIW_El 12 2/3 r (2-22) j=1 (D (WBL)+ Dj,(OG) + 0.9 Df(y)

+D(DIRECT)

{

Dm(WB) = E E

p l=1 where:

i j= Units 1, 2 and 3 1=

months 1 - 12, to bt summed over the most recent i

12 months D (WBL) p liquid whole body organ dose in mrem for the whole

=

(1-13)] [ Reference ODCH Units 2/3 (1-19), ODCM Unit 1 month.

Dff(OG) as organ dose from tritium in mrem for the month, fReferODCMUnits2/3(2-18),ODCMUnit1(2-14)]

=

D (y) p gama air dose in mrad for the month.

=

0.9 converts mrad to mrem.

[ReferenceODCMUnits2/3(2-14),ODCMUnit1(2-10)]

n (2-23) 4 E 0(bkgd),

D (Direct) = E max [D(beach),]

E"

.0342 q=1 p = for all TLDs per quarter q = for Quarters 1-4 S023-0DCM 2-71 Revision 26 12-20-93

l 2.0 GASE0USEFFLUENTS-(Continued) 1 2.9 TOTAL DOSE CALCULATIONS (Continued) l 2.9.1.2 Annual Total Whole Body Dose Dror.($1 (Continued)

Direct Radiation The direct radiation levels are evaluated most recently using cadmium covered TLDs. The TLDs are placed at 47 locations around the site. The average dose measured by TLDs 5 to 50 miles from the site is used as background.

4 These sites are subject to change.

The background is subtracted from the highest reading TLD within 5 miles of the site (generally numbers 55 through j

I 58). This value is the direct dose but must be prorated by the occupancy factor.

Example:

Beach time (west boundary, seawall) of 300 L

hrs /yr,eastandnorthboundariesof20 hrs /yr, or 8 hrs /yr for the south boundary and west fence of parking lot 1 (top of bluff).

Reference:

E. M. Goldin Memorandum for File, " Occupancy Factors at San Onofre Owner Controlled Area Boundaries," dated October 1, 1991.

.3 Annual Total Thyroid Dose 0,o, (T) 12 2/3 0,,7(T) = E E

{Dp (OG) + Dp (0L)]

1-1 j =1 (2-24)

E where:

j=

Units 1, 2 and 3 1=

months 1 - 12, to be summed over the most recent 12 months Do (OG) thyroid organ dose from gaseous iodine for the month

=

4 in mrem.

(from 2-21)

Do (0L) liquid thyroid organ dose for the month in mrem.

=

[ReferenceODCMUnits2/3(1-19), Unit 1ODCM l

(1-13)]

e S023-0DCM 2-72 Revision 26 12-20-93 l

TABLE 2-17 SOUTH YARD FACILITY CONTROLLING LOCATION FACTORS EaRuWe Radionuclide mrem /yr per #C1/sec Use:

H-3 1.31E-03 G: SAN ON0FRE BCH CAMPGD Cr-51 4.15E-02 F: SOST.PK./GUARDSHACK Mn-54 9.70E+00 F: SOST.PK./GUARDSHACK Co-57 2.41E+00 F: SOST.PK./GUARDSHACK Co-58 3.14E+00 F: 50ST.PK./GUARDSHACK Co-60 1.35E+02 F: SOST.PK./GUARDSHACK Sr-89 1.71E+00 F: DEERCONSUMER/ HUNTER Sr-90 1.04E+02 G: SAN ONOFRE BCH CAMPGD Zr-95 7.26E+00 F: DEERCONSUMER/ HUNTER Nb-95 2.88E+01 F: DEERCONSUMER/ HUNTER Ru-103 4.56E+01 F: DEERCONSUMER/ HUNTER Te-129m 2.26E+01 F: DEER' CONSUMER / HUNTER Cs-134 4.28E+01 F: SOST.PK./GUARDSHACK j

Cs-136 1.04E+00 F: SOST.PK./GUARDSHACK Cs-137 6.36E+01 F: SOST.PK./GUARDSHACK Ba-140 1.39E+00 G: SAN ONOFRE BCH CAMPGD Ce-141 4.29E-01 G: SAN ONOFRE BCH CAMPGD Ce-144 8.39E+00 G: SAN ONOFRE BCH CAMPGD q

I-131 2.28E+01 F: DEERCONSUMER/ HUNTER I-132 1.22E-01 G: SAN ONOFRE BCH CAMPGD I-133 2.22E+00 G: SAN ONOFRE BCH CAMPGD I-134 3.24E-02 G: SAN ONOFRE BCH CAMPGD I-135 4.60E-01 G: SAN ONOFRE BCH CAMPG0 UN-ID 5.36E+00 F: 50STPK./GUARDSHACK Footnote:

These values to be used in manual calculations are the maximum E raw for all locations based on the most restrictive age group.

i i

i S023-0DCM 2-73 Revision 28 12-21-95

TABLE 2-18 SOUTH YARD FACILITY DOSE PARAMETER R, FOR SECTOR D Page 1 of 1 Pathway = Camp Horno Sewage Trinnt.

Distance = 3.2 Miles X/Q = 1.2E-7 sec/m' D/Q = 1.2E-9 m lF 4

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 2.9E+2 CR-51 3.3E+3 1.1E+6 MN-54 3.2E+5 3.2E+8 CO-57 8.4E+4 7.8E+7 C0-58 - 0.-

2.1E+5 8.7E+7 C0-60 1.4E+6 4.9E+9 SR-89 3.2E+5 4.9E+3 SR-90 2.3E+7 ZR-95 4.0E+5 5.7E+7 NB-95 1.2E+5 3.1E+7 PU-103 1.2E+5 2.5E+7 TE-129m 2.6E+5 4.5E+6 CS-134 1.9E+5 1.6E+9 CS-136 3.3E+4 3.4E+7 CS-137 1.4E+5 2.3E+9 BA-140 2.9E+5 4.7E+6 CE-141 8.3E+4 3.1E+6 CE-144 1.8E+6 1.6E+7.

1-131 2.7E+6 3.9E+6 I-132 0- 2.6E+4 2.8E+5 I-133 4.9E+5 5.6E+5 I-134 6.8E+3 1.0E+5 I-135 1.0E+5 5.8E+5 UN-10 2.0E+5 1.7E+8 Inhalation Pathway, units = p" 7"-

Food & Ground Pathway, units = I* ' " dc C1 5023-0DCM 2-74 Revision 28 12-21-95 I

(

l TABLE 2-19 SOUTH YARD FACILITY DOSE PARAMETER R, FOR SECTOR E Page 1 of 1 Pathway = Camp Horno Distance = 3.7 Miles X/Q = 6.0E-7 sec/m' D/Q = 5.7E-9 m-lF Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 1.3E+3 CR-51 1.4E+4 4.7E+6 MN-54 1.4E+6 1.4E+9 C0-57 3.7E+5 3.4 E+8 CO-58 9.3E+5 3.8E+8 CO-60 6.0E+6 2.2E+10 SR-89 1.4E+6 2.2E+4 SR-90 9.9E+7 ZR-95 1.8E+6 2.5E+8 NB-95 5.0E+5 1.4E+8 RU-103 5.0E+5 1.1E+8 TE-129M 1.2E+6 2.0E+7 CS-134 8.5E+5 6.8E+9 l

CS-136 1.5E+5 1.5E+8 CS-137 6.2E+5 1.0E+10 BA-140 1.3E+6 2.1E+7 CE-141 3.6E+5 1.4E+7 CE-144 7.8E+6 7.0E+7 j

I-131 1.2E+7 1.7E+7 1-132 1.1E+5 1.2E+6 I-133 2.2E+6 2.4E+6 I-134 3. 0 E*-

4.5E+5 I-135 4.fi+5 2.5E+6 UN-ID 8,6E+5 7.5E+8 Inhalation Pathway, units = p*

7" Food & Ground Pathway, units = '"

Ci c

l l

l S023-0DCM 2-75 Revision 28 12-21-95 l

l l

L

I TABLE 2-2q SOUTH YARD FACILITY DOSE PARAMETER R. FOR SECTOR F Page 1 of 4 Pathway =SanOnofreStatePark/GuardShack Distance = 0.4 Miles X/0 = 5.4E-6 sec/m' 0/0 = 3.5E-8 m-2 (p

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 2.2E+2 CR-51 2.5E+3 8.0E+5 MN-54 2.4E+5 2.4E+8 CO 6.3E+4 5.9E+7 C0-58 1.6E+5 6.5E+7 CO-60 1.0E+6 3.7E+9 SR-89 2.4E+5 3.7E+3 SR-90 1.7E+7 ZR-95 3.0E+5 4.3E+7 NB-95 8.6E+4 2.3E+7 RU-103 8.6E+4 1.9E+7 TE-129M 0- 2.0E+5 3.4E+6 CS-134 1.5E+5 1.2E+9 CS-136 2.5E+4 2.6E+7 CS-137 1.1E+5 1.8E+9 BA-140 2.2E+5 3.5E+6 CE-141 '6.2E+4 2.3E+6 CE-144 1.3E+6 1.2E+7 I-131 2.0E+6 2.9E+6 I-132 2.0E+4 2.1E+5 I-133 -0 3.7E+5 4.2E+5 I-134 5.1E+3 7.7E+4 I-135 7.7E+4 4.3E+5 UN-ID 1.5E+5 1.3E+8 Inhalation Pathe y, units = p*C Food & Ground Pathway, units =

C1/s c S023-0DCM 2-76 Revision 28 12-21-95 I

i l

L

[.

TABLE 2-20 SOUTH YARD FACILITY DOSE PARAMETER R, FOR SECTOR F Page 2 of 4 Pathway = Border Patrol Checkpt.

Distance = 1.4 Miles X/Q = 1.2E-6 sec/m

0/Q = 8.2E-9 m-'

lf' Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio--

-tion Ground tion Ground tion Ground tion Ground l

Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway

!~

H-3 3.6E+2 l CR-51. 4.1E+3

-1.3E+6 MN-54 4.0E+5 3.9E+8 C0-57 1.1E+5 9.8E+7 CO-58 2.6E+5-1.1E+8 CO-60 1.7E+6 6.1E+9 SR-89 4.0E+5 6.2E+3 SR-90 2.8E+7 ZR-95' 5.0E+5 7.2E+7 NB-95 1.4E+5 3.9E+7 RU-103 1.4E+5 3.1E+7 TE-129M 3.3E+5 5.6E+6 l

CS-134 -0--

2.4E+5 1.9E+9 I

l CS-136 - 4.2E+4 4.3E+7 l.

CS-137 -0-' 1.8E+5 2.9E+9 BA-140 3.6E+5 5.9E+6 CE-141 1.0E+5

'3.9E+6 CE-144 2.2E+6 2.0E+7 I-131 3.4E+6 4.9E+6 I-132 3.3E+4 3.5E+5 I-133 6.1E+5 7.0E+5 I-134 8.5E+3 1.3E+5 I-135 0- 1.3E+5 7.2E+5 UN-ID 2.5E+5 2.1E+8 I

\\

Inhalation Pathway, units =

7" i

Food & Ground Pathway, units = I" Iar /vr)

C

~

S023-0DCM 2-77 Revision 28 12-21-95

m TABLE 2-20 i

SOUTH YARD FACILITY DOSE PARAMETER R FOR SECTOR F Page 3 of 4 Pathway = Sheep (Neat)/ Shepherd Distance = 0.3 Miles X/Q = 7.2E-6 sec/d 0/Q = 4.5E-8 m*

lF Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion.

Ground tion Ground l

Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 0-1.0E+2 7.9E+1 2.6E+4 CR-51 5.1E+1 MN-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 CO-57 4.7E+3 8.1E+3 2.0E+3 1.9E+6 C0-58 9.7E+3 2.0E+4 5.1E+3 2.1E+6 CO-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 SR-89 5.0E+4 2.6E+4 7.7E+3 3.1E+4-SR-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 ZR-95 ' 6.3E+4 1.1E+5 9.7E+3 1.6E+6 NB-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 RU-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 TE-129M 6.0E+5 4.5E+5 6.4E+3 7.6E+5 CS-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 CS-136 5.1E+3 4.3E+3 8.1E+2 8.3E+5 L

CS-137 '1.3E+5 9.5E+4 3.4E+3 5.7E+7 BA-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5 CE-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 CE-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I-131 6.6E+5 4.4E+5 6.6E+4 7.0E45 I-132 6.3E+2 6.8E+3 1-133 1.6E+2 8.7E+3 1.2E+4 1.3E+4 I-134 1.6E+2 2.5E+3 l

1-135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 l

UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 i

Inhalation Pathway, units = pC1/mmrem/yr Food & Ground Pathway, units = II""""IV"I pCi/sec l

I i

5023-0DCM 2-78 Revision 28 12-21-95 L

1 TABLE 2-20 l

SOUTH YARD FACILITY DOSE PARAMETER R, FOR SECTOR F Page 4 of 4 Pathway =DeerConsumer/ Hunter Distance = 0.4 Miles 8

X/Q = 5.4E-6 sec/m D/Q = 3.5E-8 m'8 jf Infant Child Teen Adult inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 2.BE+1 2.3E+1 3.5E+1 3.9E+1 CR-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 MN-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 C0-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 CO-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 C0-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 SR-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 SR-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 ZR-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 NB-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 RU-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 TE-129M 5.9E+8 4.5E+8 3.2E+4 6.4E+8 i

CS-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 CS-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 CS-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 BA-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 CE-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 CE-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I-131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I-132 3.1E+3 3.4E+4 I-133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I-134 8.2E+2 1.2E+4 I-135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-10 1.1E+8 9.4E+7

2. 4 E+4 1.4E+8 Inhalation Pathway, units =

["

Food & Ground Pathway, units = '*

Ci/ c S023-0DCM 2-79 Revision 28 12-21-95

v TABLE 2-21 SOUTH YARD FACILITY D0SE PARANETER R FOR SECTOR G l

Page 1 of 4 l

Pathway = San Onofre Bch Campgd Distance = 0.4 Miles X/Q = 4.5E-6 sec/m' D/Q = 1.8E-8 m'8 lf Infant Child Teen Adult Inhala-Food &

Inhala-Food &

l Radio-tion Ground tion Ground tion Ground tion Ground l

Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway l

H-3 8.0E+1 1.4E+2 1.6E+2 2.9E+2 CR-51 1.6E+3 5.7E+5 2.1E+3 5.7E+5 2.6E+3 5.7E+5 3.3E+3 1.1E+6 MN-54 1.2E+5 1.7E+8 1.9E+5 1.7E+8 2.4E+5 1.7E+8 3.2E+5 3.2E+8 CO-57 4.7E+4 4.2E+7 6.3E+4 4.2E+7 7.2E+4 4.2E+7 8.4E+4 7.8E+7 C0-58 9.6E+4 4.7E+7 1.4E+5 4.7E+7 1.7E+5 4.7E+7 2.1E+5 8.7E+7 C0-60 5.6E+5 2.7E+9 8.7E+5 2.7E+9 1.1E+6 2.7E+9 1.4E+6 4.9E+9 SR-89 2.5E+5 2.7E+3 2.7E+5 2.7E+3 3.0E+5 2.7E+3 3.2E+5' 4.9E+3 SR-90 5.0E+6 1.2E+7 1.3E+7 2.3E+7 ZR-95 2.2E+5 3.1E+7 2.8E+5 3.1E+7 3.3E+5 3.1E+7 4.0E+5 5.7E+7 l

NB-95 5.9E+4 1.7E+7 7.6E+4 1.7E+7 9.3E+4 1.7E+7 1.2E+5 3.1E+7 l

RU-103 6.8E+4 1.3E+7 8.2E+4 1.3E+7 9.7E+4 1.3E+7 1.2E+5 2.5E+7 TE-129M 2.1E+5 2.4E+6 2.2E+5 2.4E+6 2.4E+5 2.4E+6 2.6E+5 4.5E+6 CS-134 8.7E+4 8.4E+8 1.3E+5 8.4E+8 1.4E+5 8.4E+8 1.9E+5 1.6E+9 l

CS-136 1.7E+4 1.9E+7 2.1E+4 1.9E+7 2.4E+4 1.9E+7 3.3E+4 3.4E+7 CS-137 7.5E+4 1.3E+9 1.1E+5 1.3E+9 1.0E+5 1.3E+9 1.4E+5 2.3E+9 BA-140 2.0E+5 2.5E+6 2.1E+5 2.5E+6 2.5E+5 2.5E+6-2.9E+5 4.7E+6 CE-141

.6.4E+4 1.7E+6 6.7E+4 1.7E+6 7.6E+4 1.7 E+6 8.3E+4 3.1E+6 CE-144 1.2E+6 8.6E+6 1.5E+6 8.6E+6 1.6E+6 8.6E+6 1.8E+6 1.6E+7 I-131 1.8E+6 2.1E+6 2.0E+6 2.1E+6 1.8E+6 2.1E+6 2.7E+6 3.9E+6 I-132 2.1E+4 1.5E+5 2.4E+4 1.5E+5 1.9E+4 1.5E+5 2.6E+4 2.8E+5 I-133 4.4E+5 3.0E+5 4.7E+5 3.0E+5 3.6E+5 3.0E+5 4.9E+5

~5.6E+5 I-134.

5.5E+3 5.5E+4 6.3E+3 5.5E+4 4.9E+3 5.5E+4 6.8 E+3 1.0E+5 I-135 8.6E+4 3.1E+5 9.8E+4 3.1E+5 7.7E+4 3.1E+5 1.0E+5 5.8E+5 UN-ID 8.0E+4 9.2E+7 1.2E+5 9.2E+7 1.5E+5 9.2E+7 2.0E+5 1.7E+8 Inhalation Pathway, units = p*

7" Food & Ground Pathway, units =

C1 c

9 f

i S023-0DCM 2-80 Revision 28 12-21-95 l

i t

L i

p TABLE 2-21 SOUTH YARD FACILITY D0SE PARANETER R FOR SECTOR G 7

Page 2 of 4 Pathway = Highway Patrol Weigh Station Distance = 1.6 Miles X/Q = 4.2E-7 sec/m' D/Q = 1.7E-9 m-2 lf Infant Child Teen Adult Inhala-Food &

Inhala-Food &

i l

Radio-tion Ground tion Ground tion Ground tion Ground l

Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathwal H-3. 3.0E+2 i-CR-51 3.4E+3 1.1E+6 l

MN-54 - 3.3E+5 3.3E+8 l-C0-57 -0. 8.8E+4 8.1E+7 CO-58 2.2E+5 9.0E+7 CO-60 1.4E+6 5.1E+9 l

SR-89 3.3E+5 5.1E+3 l

SR-90 2.4E+7 ZR-95 : 4.2E+5 6.0E+7 NB-95 1.2E+5 3.2E+7 j

RU-103 1.2E+5 2.6E+7 TE-129M 2.8E+5 4.7E+6 CS-134 2.0E+5 1.6E+9 CS-136 3.5E+4 3.6E+7 l

CS-137 1.5E+5 2.4E+9 BA-140 3.0E+5 4.9E+6 i

CE-141 8.6E+4 3.2E+6 l

CE-144 1.8E+6 1.7E+7 I-131 2.8E+6 4.1E+6 I-132 2.7E+4 2.9E+5 l

I-133 5.1E+5 5.8E+5 I-134. 7.1E+3 1.1E+5 I-135 1.1E+5 6.0E+5 UN-10 2.1E+5 1.8E+8 Inhalation Pathway, units = p yr m

Food & Ground Pathway, units =

C1 l

S023-0DCM 2-81 Revision 28 12-21-95

fl l-TABLE 2-21 SOUTH YARD FACILITY D0SE PARAMETER R. FOR SECTOR G Page 3 of 4 Pathway = Sheep (Meat)/ Shepherd Distance = 2.3 Miles X/Q = 2.4E-7 sec/m' '

D/Q = 9.2E-10 m-8 lf Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion-Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 CR-51 5.1E+1 1.0E+2 7.9E+1 2.6E+4 MN-54 - 7.8E+2 1.4E+3 7.7E+3 7.6E+6 C0-57~ 4.7E+3 8.1E+3 2.0E+3 1.9E+6 C0-58

- -0. 9.7 E+3 2.0E+4 5.1E+3 2.1E+6 l

CO-60 - -0--

3.7E+4 7.3E+4 3.3E+4 1.2E+8 SR-89 5.0E+4 2.6E+4 7.7E+3 3.1E+4 SR-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 ZR-95 6.3E+4 1.1E+5 9.7E+3 1.6E+6 NB-95. 2.4E+5 4.5E+5 2.8E+3 1.6E+6 RU-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 TE-129M.6.0E+5 4.5E+5 6.4E+3 7.6E+5 CS-134-1.4E+5 1.2E+5 4.7E+3 3.8E+7 CS-136 5.1E+3 4.3E+3 8.1E+2 8.3E+5 CS-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 BA-140 3.1E+3 4.3E+3 7.0E+3 1.2E+5 CE-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4

.CE-144 ~ 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I-131 6.6E+5 4.4E+5 6.6E+4 7.0 E+5 l

I-132 6.3E+2 6.8E+3 i

1-133 1.6E+2 8.7E+3 1.2E+4 1.3E+4 I-134 1.6 E+2 2.5E+3 I-135 1.1E-18 6.4E-19

2. 5 E+3 1.4E+4 UN-ID 1.1E+5.

9.5E+4 4.8E+3 4.2E+6 i

Inhalation Pathway, units = p*

V" Food & Ground Pathway, units =

Ci c

I S023-0DCM.

2-82 Revision 28 12-21-95

r

]

TABLE 2-21 SOUTH YARD FACILITY D0SE PARAMETER R. FOR SECTOR G i

Page 4 of 4 Pathway =DeerConsumer/ Hunter Distance = 2.9 Miles X/Q = 1.8E-7 sec/m' D/Q = 6.4E-10 m lf 1

4 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 CR-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 MN-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 C0-57 0- 4.6E+6 8.0E+6 1.0E+4 2.3E+7 CO-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 l

CO-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 SR-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 SR-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 2R-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 l

NB-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 l

RU-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 TE-129M 5.9E+8 4. 5 E+8 3.2E+4 6.4 E+8 CS-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 l

CS-136 5.1E+6 4.2E+6 4.0 E+3 9.5E+6 CS-137 1.3E+8 9.3E+7 1.7E+4 4.0 E+8 BA-140 5.0E+6 4.2E+6

3. 5 E+4 7.4E46 CE-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 CE-144 1.8E+7 2.9E+7 2.1E+5 4.9i+7 I-131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I-132 3.1E+3 3.4E+4 I-133 1.6E+1 8.6E+0 5.9E+4 6.7E+4-

'I-134 8.2E+2 1.2E+4 I-135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units =

7" Ci/sjc Food & Ground Pathway, units =

l 5023-0DCM I

2-83 Revision 28 12-21-95 1

p l

3.0 PROJECTED DOSES 3.1 Liquid Dose Projection j

The methodology used for projecting a Ifquid dose over 31 days for Specification 1.3.1 is as follows:

1.

Determine the monthly total body and organ doses resulting from releases during the previous twelve months.

2.

Projected dose = Previous 12 months' dose divided by 12 for the total body and each organ.

3.2 Gaseous Dose Projection i

The methodology used for projecting a gaseous dose over 31 days for Specification 2.4.1 is as follows:

1 1.

Determine the monthly gama, beta and organ dose resulting from releases during the previous twelve months.

2.

Projected dose = Previous 12 months' dose divided by 12 for the gama, beta and organ doses.

I S023-0DCM I

3-1 Revision 22 08-02-90 l

4.0 EQUIPMENT' 4.1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SPECIFICATION 4.1.1' The radioactive liquid effluent monitoring instrumentation channels shown in Table 4-1 sijall be OPERABLE with their alam/ trip setpoints set to ensure that the limits of Specification 1.1.1 are not exceeded. The alam/ trip setpoints of these channels shall be detemined in accordance with Section 1.4.

APPLICABILITY: At all times ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel alarm / trip-setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

.b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE,

take the ACTION shown in Table 4-1.

Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument (s) remain inoperable for greater than 30 days, explain in the next

' Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner, c.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE and either the appropriate ACTION items in Table 4-1 not taken or the necessary surveillances not performed at the specified frequency prescribed in Table 4-2, an INVESTIGATIVE REPORT shall be prepared which identifies the cause(s) for the event and defines the corrective actions to be taken to preclude recurrence of the event.

SURVEILLANCE REOUIREMENTS

.1 Each radioactive liquid effluent monitoring instrumentation channel siall be demonstrated OPERABLE by performance of the CHANNEL CHECK,

(

SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST-operations at the frequencies shown in Table 4-2.

.2 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or after a change in plant mode or pump lg lineup has been completed, all pumps required to be providing I

dilution to meet the site radioactive effluent concentration limits of Specification 1.1.1 shall be determined to be operating and providing dilution to the discharge structure.

S023-0DCM 4-1 Revision 31 02-27-98

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TABLE 4-l' (Continued)

TABLE NOTATION Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal. As long as the monitor has indication, alarm capability (if applicable),) prop (er response (base requirements) and isolation function if applicable), the loss of the recorder does not render the monitor inoperable.

ACTION 28 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases may continue provided that prior to initiating a release:

a.

At least two independent samples are analyzed in accordance with Specification 1.1.1 and b.

. At least two technically qualified members of the Facility Staff independently verify the release rate calculation and discharge line valving;.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 29 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, ef(luent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 microcuries/ gram:

a.

At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcuries/gramDOSEEQUIVALENTI-131; b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/gramDOSEEQUIVALENTI-131;or c.

Lock closed valve HV-3773 and divert flow to T-064 for processing as liquid radwaste.

ACTION 30 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this i

pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of collection time for gross radioactivity (beta or gamma) at a limit of detection of at least 10-' microcuries/mi or lock closed valve S2(3)2419MUO77 or S2(3)2419MUO78 and divert flow to the radwaste sump for processing as liquid radwaste.

F i

i..

S023-0DCM 4-3 Revision 31 02-27-98 1

t. -

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TABLE 4-1 (Continued)

TABLE NOTATION 7

l.

ACTION 31 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:

a.

The process flow rate is estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during actual releases. In addition, a new flow l

estimate shall be made within I hour after a change is made to an effluent pathway. This includes plant mode, pump operation, or valve lineups. Pump curves may be used toestimateflow,and/or fi l

b.

The sample flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

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l TABLE 4-2 (Continued)

TABLE NOTATION Monitor. Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e... feedback signal). As long as the monitor has indication, alarm capability (if applicable), prop (er response (based upon surveillance requirements) and isolation function if applicable), the loss of the recorder does not render the monitor inoperable.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation actuation signal, automatic pathway isolation, and Control Room alarm annunciation if any of the following conditions exist:

1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

Automatic pathway isolation is tested on a once per refueling period.

Down scale failure testing is bounded by administrative limitation on monitor setpoint which ensure monitor alarm and release termination occur prior to reaching the level of monitor saturation.

If the instrument controls are not in the operate mode, procedures shall require that the channel be declared inoperable.

(2) 'he initial CHANNEL CALIBRATION shall be performed using one or more of the

eference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measuremer.t assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATIONS, sources that have been related to the initial calibration shall be used.

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

S023-0DCM 4-6 Revision 30 05-28-97

(,..

4.0 EQUIPMENT 4.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SPECIFICATION 4.2.1 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 4-3 shall be OPERABLE with their alam/ trip setpoints set to ensure that the limits of Specification 2.1.1 are not exceeded.

determine / trip setpoints of these channels shall be The alarm d in accordance with 00CM.

APPLICABILITY: At all times ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, innediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the v.annel inoperable.

b.

With less than the minimum number of radioactive gaseous effluent monitoring nstrumentation channels OPERABLE, take the ACTION shown in Table 4-3.

Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument (s) remain inoperable for greater than 30 days, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE and either the appropriate ACTION items in Table 4-3 not taken or the necessary surveillances not perfomed at the specified frequency prescribed in Table 4-4, an INVESTIGATIVE REPORT shall be prepared which identifies the cause(s) for the event and defines the corrective actions to be taken to preclude recurrence of the event.

SURVEILLANCE REOUIREMENTS

.1 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4-4.

S023-0DCM 4-7 Revision 26 12-20-93 mr..

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TABLE 4-3 (Continued 1 TABLE NOTATION At all times.

MODES 1-4 with any main steam isolation valve and/or any main steam isolating bypass valve not fully closed.

Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based upon surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.

(1) 2(3)RT-7818 is not equipped to monitor process flow.

If another means of continuously monitoring process flow is not available, then comply with ACTION 36.

(2) 2/3RT-7808 is not equipped to monitor process flow.

If 2RT-7865 and 3RT-7865 are not available to continuously monitor plant vent stack flow, then comply with ACTION 36.

(3)

Due to unequal mixing in the Plant Vent Stack, both 2RT-7865 and 3RT-7865 arerequiredtobeoperablewhen2/3RT-7808isinoperable.

(4)

Deleted.

p ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the release:

a.

At least two independent samples of the tank's contents are analyzed, and b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend releases of radioactive effluents via this pathway.

f l

}

S023-0DCM 4-10 Revision'31 l

02-27-98

TABLE 4-3 (Continued)

TABLE NOTATION ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:

a.

The process flow rate is estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during actual releases. In addition, a new flow estimate shall o

be made within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after a change is made to an effluent F-pathway. This includes plant mode, fan operation, or valve / damper lineups. System design characteristics may be used to estimate flow.

b.

The sample flow rate is estimated at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months during actual releases.

s

- ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.

ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the effected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 2-1.

S023-0DCM 4-11 Revision 31 02-27-98

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TABLE 4-4 (Continued)

TABLE NOTATION At all times.

Modes 1-4withanymainsteamisolationvalveand/oranymainsteam isolating bypass valve not fully closed.

Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alam capability (if applicable), prop (er response (based upon surveillance requirements) and isolation function if applicable), the loss of the recorder does not render the monitor inoperable.

(1)

The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation actuation signal, automatic pathway isolation, and Control Room alarm annunciation if any of the following conditions exist:

1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

Automatic pathway isolation is tested on a once per refueling interval. The i

main containment purge isolation valves are required to be tested in Mode 5 1

prior to performing initial core alterations. Containment purge valves are not required to be tested for auton.atic isolation in the event of a mid-cycle outage.

Down scale failure testing is bounded by administrative limitation on monitor setpoints which ensure monitor alarm and release termination occur prior to reaching the level of monitor saturation.

If the instrument controls are not set in the operate mode, procedures shal.1 call for declaring the channel inoperable.

(2)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:f 1.

Instrument indicates measured levels above the alarm setpoint.

2.

Circuit failure.

Down scale failure testing is bounded by administrative limitation on monitor setpoints which ensure monitor alann and release termination occv prior to reaching the level of monitor saturation.

.If the instrument controls are not set in the operate mode, procedures shall call for declaring the channel inoperable.

S023-00CM 4-15 Revision 30 05-28-97

(.;

i I

b-TABLE 4-4 (Continued)_

TABLE NOTATION (Continued) l (3)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards. certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATIONS, sources that have been related to the initial calibration shall be used, f

(4)

Prior to each release and at.least once per month.

l (5)

Daily checks only required during times of building occupation.

(6)

CHANNEL CHECK required by Health Physics daily for each day that the CO, Decontamination Unit is used.

(7)

The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation actuation signal, if any of the following conditions exist:

l 1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

Automatic pathway isolation is tested on a once per 24 month interval.

h Down scale failure testing is bounded by administrative limitation on monitor setpoints which ensure monitor alarm and release termination occur prior to reaching the level of monitor saturation.

l (8)

The SOURCE CHECK for SYFRE7904 SYFRE7905 consists of a constant status check of the detector. Satisfactory completion of an instrument CHANNEL CHECK satisfies this requirement.

i

)

i l

l 1

S023-0DCM 4-16' Revision 31

~

02-27-98 Q

f l

i L

l 1

4.3 OPERA 8ILITY OF RADI0 ACTIVE WASTE EQUIPMENT j

]

The flow diagrams defining the treatment paths and the components of the radioactive liquid, gaseous and solid waste management systems are shown in Figures 4-5 thru 4-7.

S023-00CM 4-17 Revision 21 02-15-90 l

l FlGURE 4-5 SONGS 2 & 3 RADI0 ACTIVE LIQUID WASTE TREATMENT SYSTEMS Storage Tank Area CCW Sump Sump (latch)

Mala Condenser j

(Batd)

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+

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Radunste Primary Tasks.

/ Intake g andmaste Secondary Tasks Radiaties Primary Mekeep Tanks Moeiter Condemnate Meetter Tasks 2/3RY7813 (latch)

U Pacific Oceae l

l l

S023-00CM 4-18 Revision 28 12-21-95

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5.0 RADIOLOGICAL ENVIRONMENTAL NONITORING.

l 5.1 Monitorina Proaram SPECIFICATION 5.1.1 The radiological environmental monitoring program shall be conducted as specified in Table 5-1.

The requirements are applicable at all times.

APPLICABILITY: At all times ACTION:

a.

Should the radiological environmental monitoring program not be conducted as specified in Table 5-1, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report (see Section 5.4), a description of the l

l reasons for not conducting the program as required and the plans for preventing a recurrence, b.

Should the level of radioactivity in an environmental i

sampling medium exceed the reporting levels of Table 5-2 1

when averaged over any calendar quarter, in lieu of any other report required by Technical Specification Section l

5.7.1 and LCS 5.0.104, prepare and submit to the Connission, within 30 days from the end of the affected l

calendar quarter a Report pursuant to 10 CFR 50.73. When more than one of the radionuclides in Table 5-2 are i

detected in the sampling medium, this report shall be I

submitted if:

i concen': ration '1)

+

concentration (2)

+...t 1.0 limit ' eve' (1) limit level (2) c.

When radionuclides other than those in Table 5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or reater than the calendar year limits of Specification (g) 1.2.1, 2.2.1 or 2.3.1, as s

appropriate. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report (see Section 5.4).

S023-00CM 5-1 Revision 30 05-28-97

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued)

ACTION:

(Continued) d.

'Jith fresh. leafy vegetable samples or fleshy vegetable samples unavailable from one or more of the sample locations required by Table 5-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification 5.7.1, submit in the next Annual

[-

Radioactive Effluent Release Report documentation for_ a change in the ODCM including a revised figure (s) and table for the ODCM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples.

SURVEILLANCE RE0VIREMENTS

.1 The radiological environmental monitoring samples shall be collected pursuant to Table 5-1 from the locations given in Tables 5-4 cod 5-5 and Figures 5-1 through 5-5 and shall be p.

analyzed pursuant to the requirements of Tables 5-1 and 5-3.

}'

j 1

5023-0DCM 5-2 Revision 31 02-27-98

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TABLE 5-3 (Continued)

TABLE NOTATION The LLD is the smallest concentration of radioactive material in a sample a.

that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

l For a particular measurement system (which may include radiochemical separation):

LW =

E Y. 2.22 x 10' Y. exp (-AAt) where:

LLD is the "a priori" lower limit of detection as defined above (as microcurieperunitmassorvolume),

is the standard deviation of the background counting rate or of s

the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per transformation),

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

2.22 x 10' is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

1 is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection or end of the collection period and time of counting (for environmental samples, not plant effluents ).

The value of s used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally of E V,Y and At shall b(e used in the calculations.e.g., potassium-40 in milk samples) present in the samples

'It should be recognized that the LLD is defined as an a priori (before the fact) limit re A nosteriori (presenting the capability of the measurement system and not as, afterthefact)limitforaparticularmeasurement.*

"For a more complete discussion of the LLD, and other detection limits, see the following:

(2)1) HASL Procedures Manual, HASL-300 (revised annually).

(

Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).

S023-0DCM 5-9 Revision 30 05-28-97

TABLE 5-3 (Continued)

TABLE NOTATION b.

If no drinking water pathway exists, a value of 3000 pC1/1 may be used.

Other peaks which are measurable and identifiable, together with the c.

radionuclides in Table 5-3, shall be identified and reported.

d.

If no drinking water pathway exists, a value of 15 pC1/1 may be used.

S023-0DCM 5-10 Revision 30 05-28-97

m 15.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) j 5.2 LAND USE CENSUS.

SPECIFICATION:

5.2.1 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden

of greater than 500 square feet producin fresh leafy vegetables in each of the 16 meteorol ical sectors within a distance of five miles.

APPLICABILITY: At all times ACTION:

a.

With the land use census identifying a location (s) that yields a calculated dose or dose counitment greater-than the values currently being calculated in Specification 2.3.1, pursuant to Technical Specification 5.7.1, identify the new locations in the next Annual Radioactive-Effluent l

Release Report.

b.

With the land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in o

accordance with Specification 5.1, add the new location N

within 30 days to the Radiological Environmental Monitoring Programgiveninthe00CM.-Thesamplinglocation(s),

excluding the control station location, having the lowest calculated dose or dose commitment (s) via the same exposure pathway, may be deleted from this monitoring program after October 31, of the year in which this Land Use Census was conducted. Pursuant to Technical Specification 5.7.1, submit in the next Annual Radioactive Effluent Release Report documentation for a chan revisedfigure(s)andtable(s)geinthe00CMincludingafor the ODCM ref newlocation(s)withinformationsupportingthechangein sampling locations.

SURVEILLANCE REOUIREMENTS

.1 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which will provide the best results, such as by a door-to-door

. survey, aerial survey, or by consulting local agriculture authorities.

Broad leaf vegetation sampling may /Q in lieu of the garden census.y in the be performed at the site boundar direction sector with the highest D S023-0DCM 5-11 Revision 31 02-27-98

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.3 INTERLABORATORY COMPARISON PROGRAM SPECIFICATION 5.3.1 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

APPLICABILITY: At all times ACTION:

With analyses not being performed as required above, report a.

the corrective actions taken to prevent a recurrence to the Comission in the Annual Radiological Environmental Operating Report.

SURVEILLANCE RE0VIREMENTS

.1 A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with Section 5.4.1 of this document shall be included in the Annual Radiological EnvironmentalOperatingReport(seeSection5.4).

S023-00CM 5-12 Revision 22 08-02-90

r 1

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.4 AtS,UAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

l 5.4.1 The annual radiological environmental operating reports shall include sumaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational-studies, operational i

controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Section 5.2.

If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include sumarized and tabulated results in the l

famat of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from the mid-point of reactor Units 2 and 3; and the results of licensee participation in the Interlaboratory Comparison Program, required by Section 5.3.

A single submittal may be made for a multiple unit station, combining those sections that are common to all units at the station.

l S023-0DCM 5-13 Revision 21 02-15-90 I

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.5 SAMPLE LOCATIONS The Radiological Environmental Monitoring Sample Locations are identified in Figures 5-1 through 5-5.

These sample locations are lb described in Tables 5-4 and 5-5 and indicate the distance in miles and the direction, determined from degrees true north, from the center of the Units 2 and 3 building complex. Table 5-6 gives the sector and direction designation for the Radiological Environmental Monitoring Sample Location on Map, Figures 5-1 through 5-5.

lb t

i st S023-0DCM 5-14 Revision 31 02-27-98

4 Page 1 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE

TYPE OF SAMPLE AND SAMPLING LOCATION ***

Imiles)

DIRECTION

Direct Radiation 1

City of San Clemente (Former SDG&E Offices) 5.7 NW lL 2

CampSanMateo(MCB,CampPendleton) 3.5 N

3 CampSanOnofre(MCB,.CampPendleton) 2.6 NE 4

Camp Horno (NCB, Camp Pendleton).

4.5-E 6

OldRoute101(East-Southeast) 3.0 ESE 8

Noncommissioned Officers' Beach Club 1.4 NW l f.

10 Bluff (Adjacent to PIC #1) 0.7 WNW 11 Former Visitors' Center 0.4

NW 12 South Edge of' Switchyard 0.2**

E

13. Southeast Site boundary (Bluff) 0.4**

ESE l1 14 Deleted lD 15 Southeast Site Boundary (Office Building) 0.1**

SSE 16-East Southeast Site Boundary 0.4'*

ESE 17 Transit Dose 18 Transit Dose 19 San Clemente Highlands 5.0 NNW 22 Former U.S. Coast Guard Station - San Mateo Point 2.7 WNW 23 Samaritan Hospital, San Clemente 8.1 NW l$

Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.

MCB'- Marine Corps Base PIC - Pressurized Ion Chamber Locations previously deleted and removed: 5, 7, 9, 20, 21, 24, 25 through 30, 32,'37, 39, 42, 43, 45, 48, 51, 52.

S023-0DCM 5-15 Revision 31 02-27-98

o Page 2 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE

TYPE OF SAMPLE AND SAMPLING LOCATION ***

(milesi DIRECTION

Direct Radiation (Continued) 31 Aurora Park-Mission Viejo 18.6 NNW b

33 Camp Talega (MCB, Camp Pendleton) 5.7 N

34 San Onofre School (MCB, Camp Pendleton) 1.9 NW 35 Range 312 (MCB, Camp Pendleton) 4.7 NNE 36 Range 208C(MCB,CampPendleton) 4.2 NE 38 San Onofre State Beach Park 3.3 SE 40 SCE Training Center - Mesa (Adjacent to PIC f3) 0.7 NNW 41 Old Route 101 - East 0.3**

E j

44 Fallbrook Fire Station 17.7 E

4 46 San Onofre State Beach Park 0.9 SE 47 Camp Las Flores (MCB, Camp Pendleton) 8.6 SE Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.

MCB - Marine Corps Base PIC - Pressurized Ion Chamber Locations previously deleted and removed:

5,-7, 9, 20, 21, 24 25 through 30, 32, 37, 39, 42, 43, 45, 48, 51, 52.

5023-0DCM 5-16 Revision 31 02-27-98

l Page 3 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE *

-TYPE OF SAMPLE AND SAMPLING LOCATION ***

(mfles)

DIRECTION

Direct Radiation (Continued) 49 Camp Chappo (MCB, Camp Pendleton) 12.8 ESE 50 Oceanside Fire Station (CONTROL) 15.6 SE I

53 San Diego County Operations Center 44.3 SE 54 Escondido Fire Station 31.8 ESE 4

55 San Onofre State Beach (Unit 1 West Southwest) 0.2**

W 56 San Onofre State Beach (Unit 1, Southwest) 0.2**

W 57 SanOnofreStateBeach(Unit 2) 0.1**

WSW 58 San Onofre State Beach (Unit 3) 0.1**

S 59 SONGS Meteorological Tower 0.3**

WNW l

60 Transit Control Storage Area 61 Mesa - East Boundary (Adjacent to PIC #4) 0.7 N

62 MCB - Camp Pendleton (Adjacent to PIC #5) 0.6 NNE 63 MCB - Camp Pendleton (Adjacent to PIC #6) 0.6 NE 64 MCB - Camp Pendleton (Adjacent to PIC #7) 0.6 ENE lA l

65 MCB - Camp Pendleton (Adjacent to PIC #8) 0.7 E

)

66 San Onofre State Beach (Adjacent to PIC #9) 0.6 ESE 67 Former SONGS Evaporation Pond (Adjacent to PIC d2) 0.6 NW 68 Range 210C(MCB,CampPendleton) 4.3 ENE 73 South Yard Facility 0.4**

ESE lL Transit Control A Transit control B Fader (Co-LocatedwithTLD#54)****

31.8 ESE l$

74 Oceanside City Hall (Backup CONTROL) 15.6 SE A

Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.

MCB - Marine Corps Base PIC - Pressurized Ion Chamber

- - - For fading correction due to significant increase in temperature.

Locations previously deleted and removed:

5, 7, 9, 20, 21, 24, 25 through 30, 32, 37, 39, 42, 43, 45, 48, 51, 52.

S023-0DCM 5-17 Revision 31 02-27-98

Page 4 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE

TYPE OF SAMPLE AND SAMPLING LOCATION (miles)

DIRECTION

Airborne 1

City of San Clemente (City Hall) 5.5 NW 2

Deleted 3

Deleted D

5 Deleted 7

AWS Roof 0.18**

NW 9

. State Beach Park 0.6 ESE 10 Bluff 0.7 WNW 11 Mesa EOF.

0.7 NNW 12 Former SONGS Evaporation Pond 0.6 NW 13 Marine Corps Base (Camp Pendleton East) 0.7 E

14 Mesa Medical Facility 0.7 NNW 15 Oceanside City Hall (new CONTROL) 15.6 SE b

Soil Samples 1

Camp San Onofre 2.6 NE l$

2-Old Route 101 - East Southeast 3.0 ESE 3-BasiloneRoad/1-5FreewayOfframp 2.0 NW 4'

Deleted (D

5 Former Visitor's Center 0.4**

NW f.

6 Oceanside (new CONTROL) 16.0 SE g

Ocean Water A

Station Discharge Outfall - Unit 1 0.6 SW B

Outfall - Unit 2 1.5 SW h

C Outfall - Unit 3 1.2 SSW D

NewportBeach(CONTROL) 30.0 MW Distance (miles) and Direction (sector) are measured relative to Units 2 and

3. midpoint. Direction is determined from degrees true north.

Distances are within the Units 2 and 3 Site boundary (0.4 mile in all

. sectors) and not required by Technical Specification.

S023-0DCM 5-18 Revision 31 02-27-98

Page 5 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE

TYPE OF SAMPLE AND SAMPLING LOCATION (miles)

DIRECTION

Drinking Water 1

Deleted 2

Deleted 3

Deleted

[0 4

Camp Pendleton Drinking Water Reservoir 2.2 NNW 5

Oceanside City Hall (new CONTROL) 15.6 SE g

ShorelineSediment(BeachSand) 1-San Onofre State Beach (0.6 mile Southeast) 0.6 SE 2

San Onofre Surfing Beach 0.8 WNW 3

San Onofre State Beach (3.1 miles Southeast) 3.5 SE 4

Newport Beach (Nerth End) (CONTROL) 29.2 NW Local Crops lf 1

SanClementeRanch(SanMateoCanyon).

2.6 NW 2

Oceanside (CONTROL)**

15 to 25 SE to ESE 3

Deleted I#

4 SanClementeResidentw/ Garden 4.4 NW lA Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

Control location should be in Section G or F,15 to 25 miles from site. The control location will be selected based on sample availability. The exact location shall be noted in the Annual Radiological Environmental Operating Report.

S023-0DCM 5-19 Revision 31 02-27-98

Page 6 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE

TYPE OF SAMPLE AND SAMPLING LOCATION (miles)

DIRECTION

Non-Migratory Marine Animals A

-Unit 1 Outfall 0.9 WSW B

Units 2 and 3 Outfall 1.5 SSW C

Laguna Beach (CONTROL) 18.2 NW Kelp A

San Onofre Kelp Bed 1.5 S

B San Mateo Kelp Bed 3.8 WNW C

Barn Kelp Bed 6.3 SSE D

Laguna Beach (CONTROL) 15.6 NW Ocean Bottom Sediments A

Unit 1 Outfall (0.5 mile West) 0.6 W

B Unit 1 Outfall (0.6 mile West) 0.8 SSW C

Unit 2 Outfall 1.6 SW l

D Unit 3 Outfall 1.2 SSW E

LagunaBeach(CONTROL) 18.2 NW l

Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

S023-00CM 5-20 Revision 30 05-28-97

p

]

r TABLE 5-5 PIC - RADIOLOGIC.8L ENVIRONMENTAL MONITORING LOCATIONS Theta DISTANCE

PRESSURIZED ION CHAM 8ERS (Decrees)*

Meters miles DIRECTION / SECTOR

S1 San Onofre Beach 298*

1070 0.7 WNW F

S2' SONGS Fomer Evap. Pnd 313' 890 0.6 NW Q

S3 Japanese Mesa 340*

1150 0.7 NNW R

S4 MCB - Camp Pendleton 3*

1120 0.7 N

A 55 MC8 - Camp Pendleton 19' 1050 0.6 NNE B

S6 MCB - Camp Pendleton 46' 940 0.6 NE C

57 MCB - Camp Pendleton 70*

870 0.5 ENE D

l S8 MCB - Camp Pendleton 98*

1120 0.7 E

E S9 San Onofre State Beach 121' 940 0.6 ESE F

Distance (meters / miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Theta direction is determined from deg,ees true north.

S023-0DCM 5-21 Revision 21 02-15-90

TABLE 5-6 SECTOR AND DIRECTION DESIGNATION FOR RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATION MAP DEGREES TRUE NORTH FROM SONGS 2 AND 3 MID-POINT NOMENCLATURE Sector Center Sector 22.5*

Limit Line Limit Sector

Direction 348.75 0 & 360 11.25 A

N 11.25 22.5 33.75 B

NNE 33.75 45.0 56.25 C

NE 56.25 67.5

~78.75 D

ENE 78.75 90.0 101.25 E

E 101.25 112.0 123.75 F

ESE 123.75 135.0 146.25 G

SE 146.25 157.0 168.75 H

SSE 168.75 180.0 191.25 J

S 191.25 202.5 213.75 K

SSW 213.75 225.0 236.25 L

SW 236.25 247.5 258.75 M

WSW 258.75 270.0 281.15 N

W 281.25 292.5 303.75 P

WNW 303.75 315.0 326.25 Q

NW 326.25 337.5 348.75 R

NNW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true North.

S023-0DCM 5-22 Revision 21 02-15-90

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uom aoed 5-27 SO23-DCM Sn.et

.cW Revision 31

(

2/19/9s oocu9e_souin j 02-27-98

1 l.

. 6.0 ADMINISTRATIVE i

6.1 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable through these Specifications.

ACTION 6.1.1 ACTION shall be thh part of a specification which prescribes remedial measures required under designated conditions.

CHANNEL CALIBRATION 6.1.2 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of i

the parameter which the channel monitors. The CHANNEL l

CALIBRATION shall encomp/or trip functions, and shallass the e L

the sensor and alarm and include the CHANNEL FUNCTIONAL TEST. The CHANNEL l

CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

L CHANNEL CHECK l

L 6.1.3 A CHANNEL ~ CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other

.indicationsand/orstatusderivedfromindependent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST 6.1.4 A CHANNEL FUNCTIONAL TEST shall be:

l a.

Analog channels - the injection of a simulated signal l

into channel as close to the sensor as practicable to verify OPERABILITY, including alarm and/or trip functions.

b.

B1 stable channels - the injection of a simulated signal into the sensor to verify OPERABILITY, including alarm and/or trip functions.

c.

Digital computer channels - the exercising of the digital computer hardware using diagnostic programs and the injection of simulated process data into the l

channel to verify OPERABILITY.

S023-0DCM 6-1 Revision 21 02-15-90

E-

-l 6.0'LADMINISTRATIVE (Continued)

DOSE EOUIVALENT I-131 6.1.5 DOSE EQUIVAL' ENT I-131 shall be that concentration of I-131 (microcuries thyroid dose / gram) which alone would produce the same as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in International Commission on Radiological Protectien Publication 30. Tables titled Committed Dose Equivalent in Target Organs or Tissues per

[

Intake of Unit Activities.

~FRE00ENCY NOTATION 6.1.6 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 6.2.

GASEOUS RADWASTE TREATMENT SYSTEM 6.1.7 A GASE0US RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

INVESTIGATIVE REPORT 6.1.8 The group responsible for the missed ACTION or surveillance shall perform an evaluation which covers the rootcause(s),correctiveaction,andrecommendationsto preclude recurrence of the event. Copies of the resulting report shall be provided to Effluent Engineering and the Unit Superintendent with the original sent to CDM-SONGS for retention.

MEMBERS OF THE PUBLIC 6.1.9 MEMBER (S) 0F THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant. This category shall include nonemployees of the licensee who are permitted to use portions of the site for recreational, occupational, or j

purposes not associated.with plant functions. This j

category shall not include non-employees such as vending i

machine servicemen or postmen who, as part of their formal _

job function, occasionally enter an area that is

~

controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.

s 5023-0DCM 6-2 Revision 31 02-27-98 i

6.0 ADMINISTRATIVE (Continued)

MQM 6.1.10' A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 6-1 with fuel in the reactor g

vessel.

OPERABLE - OPERABILITY 6.1.11 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication and other auxiliary equipment that are

[

required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

PURGE - PURGING 6.1.12 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

SITE BOUNDARY 6.1.13 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.

SOLIDIFICATION 6.1.14 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic,immobilizedsolidwithdefinite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).

SOURCE CHECK 6.1.15 A SOURCE CHECK shall be the qualitative assessment of I

channel response when the channel sensor is exposed to a radioactive source.

THERMAL POWER 6.1.16 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

4 S023-0DCM 6-3 Revision 31 02-27-98

]

6.0 ADMINISTRATIVE-(Continued)~

VENTILATION EXHAUST TREATMENT SYSTEM 6.1.17 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbersand/orHEPAfiltersforthepurposeofremoving todines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING 6.1.18 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent used in system names does not imply a VENTING process, I

S023-00CM 6-4 Revision 25 02-28-92

TABLE 6-1 OPERATIONAL MODES REACTIVITY

% OF RATED.

AVERAGE COOLANT OPERATION MODE CONDITION. K:,,

THERMAL POWER

TEMPERATURE

1. POWER OPERATION 1 0.99-

> 5%

NA

.2.'STARTUP.

t 0.99 5 5%

NA

3. HOT STANDBY

< 0.99 NA t 350*F 4.. HOT SHUTDOWN

< 0.99 NA 350*F> T,,,>200*F k

5. COLD SHUTDOWN

< 0.99 NA 5 200*F

6. REFUELING **

NA NA NA

Excluding decay heat.

- Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

S023-0DCM 6-5 Revision 31 02-27-98

p i

TABLE 6-2 l

FREQUENCY NOTATION i

NOTATION FRE00ENCY l

S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W

At least once per 7 days

, M At least once per 31 days Q

At least once per 92 days SA At least once per 184 days R

At least once per 18 months

S/U Prior to each reactor startup P

Completed prior to each release N.A.

Not applicable Refueling Not to exceed 24 months Interval L

A month is defined as a 31-day period.

I' I

l l

l S023-0DCM 6-6 Revision 22 08-02-90 l

l I

L

l 6.0 'ADMfMISTRATIVE (Continued)

)

6.2 ADMINISTRATIVE CONTROLS l

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

6.2.1 Routine radioactive effluent release reports covering the operation of the unit during the previous calendar year i

shall be submitted before May 1 of each year.

6.2.2

.The radioactive effluent release reports shall include a sunenary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21e " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants " Revision 1 June 1974, with data summarized on a e

quarterly basis following the format of Appendix B thereof.

The radioactive effluent release report shall include an annual summary of hourly meteorological data collected over the previous year. This annual suninary may be either in the fom of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the fom of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same

{

report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 1-2 and 2-2) during the report i

p(eriod. All assumptions used in making these assessments i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as detemined by sampling frequency and measurement) shall be used for detemining the gaseous pathway doses. The assessment of radiation doses shall be >erfomed in accordance with the OFFSITE DOSE CALCULATION 14ANUAL (0DCM).

A slagle submittet any be made for a multiple unit station. The semittel should tambine these sectlens that are commen to all units et the Stetten heuever, for salts slth separate redweste systems, the sutetttel shall specify the releases of radioactive meterial from each unit.

i S023-0DCM 6-7 Revision 26 12-20-93

i 6.0 ADMINISTRATIVE (Continued) 6.2 ADMINISTRATIVE CONTROLS (Continued) j 6.2.2 (Continued)

The radioactive effluent release report shall also include f

an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and i

other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.

The radioactive effluents release shall include the following information for each type of solid waste shipped offsite during the report period:

a.

Container volume, 1

b.

Total curie quantity (specify whether determined by measurement or estimate),

c.

Principal radionuclides (specify whether determined by measurement or estimate),

d.

Type of waste (e.g., spent resin, compacted dry waste,evaporatorbottoms),

e.

Typeofcontainer(e.g.,LSA,TypeA,TypeB, LargeQuantity),and f.

Solidification Agent (e.g., cement, urea formaldehyde).

The radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis.

The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

l 1

l S023-0DCM 6-8 Revision 26 12-20-93 1:L

n 6.0 ADMINISTRATIVE (Continued) 6.3 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, &

Gaseous)

Licensee initiated major changes to the radioactive waste systems (liquid & gaseous):

1.

Shall be reported to the Conrufssion in the Annual Radioactive Effluent Release Report for the period in which the evaluation was performed pursuant to Quality Assurance Program Description (SCE-1-A), Subsection 17.2.20.3.1.i.

The discussion of each change shall contain:

a.

A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; b.

Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; c.

-A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; d.

An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the Itcense application and amendments thereto; e.

An evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto; f.

A comparison of the predicted releases of radioactive materials, in 11guld and gaseous effluents to the actual release for the period prior to when the changes are to be made;-

j g.

An estimate of the exposure to plant operating personnel as a result of the change; and h.

Documentation of the fact that the change was reviewed and found acceptable pursuant to Quality Assurance Program Description (SCE-1-A), Subsection 17.2.20.3.1.1.

2.

Shall become effective upon review and acceptance pursuant to Quality Assurance Program Description (SCE-1-A), Subsection

-17.2.20.3.1.1.

S023-00CM 6-9 Revision 30 05-28-97

6.0 ADMINISTRATIVE (Continued) 6.4 EMffi LIOUID EFFLUENTS CONCENTRATION (1,1) 6.4.1 This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site will be less than the concentration levels specified in 10 CFR Part 20, Appendix

8. Table II, Column 2.

This limitation provides-additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR 50 to an individual, and (2) the limits of 10 CFR 20.106( ) to the population. The concentration limit for issolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

Qgig(1.2) 6.4.2 This specification is ments of Section II.A,provided to implement the require-III.A and IV.A of Appendix I, 10-CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases'of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109,

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113 " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix 1," April 1977.

This specification applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

S023-00CM Revision 21 6-10 02-15-90

6.0: ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

LIOUIDWASTETREATMENT(1.3) 6.4.3 The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurant.e that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

GASEOUS EFFLUENTS DOSERATE(2.1) 6.4.4 This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20. Appendix B. Table II, Column 1.

These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict,'at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem / year.

This specification applies to the release of gaseous effluents from all reactors at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

S023-0DCM Revision 21 6-11 02-15-90

6.0 ADMINISTRATIVE (Continued)

6.4 BASES-(Continued)

DOSE-NOBLEGASES(2.2) 6.4.5 This specification is provided to implement the requirements of Sections II.8, III.A and IV.A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix 1.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably -

achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision 1, October 1977 and Regulatory Guide 1.111

" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. For MEMBERS OF THE PUBLIC who traverse the SITE BOUNDARY via highway I-5, the residency time shall be considered negligible and hence the dose "0".

The ODCM equations provided for determining the air doses at the SITE BOUNDARY are based upon the historical average atmospheric conditions.

00$K - RADIO 0 DINES. RADI0 ACTIVE MATERIALS IN PARTICULATE FORM AND TRI"IUM (2.3J 6.4.6 This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the 5023-0DCM 6-12 Revision 22 08-02-90

6.0 ADMINISTRATIVE'(Continued) 6.4 H.Ag), (Continued)

A requirements in Section III.A of Appendix I that confonnance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport-and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.

These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate-specifications for radiciodines, radioactive materials in particulate form and tritium are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides 'nto green o

leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man,'and 4) deposition on the ground with subsequent: exposure of man.

GASEGUSRADWASTETREATMENT(2.4)-

6.4.7 The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will'be available for use whenever gaseous effluents require treatment prior to release to the environment..The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievatie." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to-10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth

' n Sections II.B and II.C of Appendix I, 10 CFR Part 50, i

for gaseous effluents.

S023-00CM 6-13 Revision 21 02-15-90

6.0. ADMINISTRATIVE.(Continued) 6.4 38ES, (Continued).

TOTALDOSE(2.5) 6.4.8 This specification is provided to meet the dose limitations of 40 CFR 390. The specification requires the i

preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I.

For sites l

containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the j

public for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any member of the public is estimated to exceed the requirements of l

40 CFR 190, the Special Report with a request for a

{

variance in accordance with the provisions of 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected.

An individual is not considered a member of the public duringanyperiodinwhichhe/sheisengagedincarrying out any operation which is part of-the nuclear fuel cycle.

RADI0 ACTIVE LIOUID EFFLUENT INSTRUMENTATION (4.1) 6.4.9 The radioactive. liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during acteal or potential releases of liquid effluents.

The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM

.to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

S023-0DCM 6-14 Revision 21 02-15-90 s

6.0 8211NISTRATIVE (Continued) 6.4 jag 1 (Continued)

RADI0 ACTIVE GASEOUS EFFLUENT INSTRUMENTATION (4.2) 6.4.10 The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCH to ensure that the alam/ trip will occur prior to exceeding the limits of 10 CFR Part 20. This fostrumenta-tion &lso includes provisions for monitoring ana controlling the concentrations of potentially explosive gas 1xtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

MONITORINGPROGRAM(5.1) 6.4.11 The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable cuncentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The detection capabilities required by Table 5-1 are state-of-the-art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an A priori (before the fact) limit representing the capability of a measurement system and not as a nosteriori particular measuremen(after the fact) limit for a t.

Analyses shall be performed in such a manner ^that the stated LLDs will be uchieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

S023-0DCM 6-15 Revision 22 08-02-90 I

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

LAND USE CENSUS (5.2) 6.4.12

'This specification is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the monitoring program are made if

. required by the results of this census. The best survey information from the door-to-door, aerial or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of-Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathwave via leafy vegetables will be identified and monitorea ince a garden of this size is the minimum required to produce the quantity Guide./ year) of leafy vegetables assumed in Regulatory (26 kg l.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used,

1) that 20% of the garden was used for growing broad leaf 2)getation (i.e., similar to lettuce and cabbage), and ve avegetationyieldof2kg/squaremeter.

INTERLABORATORY COMPARISON PROGRAM (5.3) 6.4.13 The iequirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

S023-0DCM 6-16 Revision 22 08-02-90

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ML20206E600

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