ML20138F012

Rev 29 to, Offsite Dose Calculation Manual,Nuclear Organization Units 2 & 3

ML20138F012
Person / Time
Site:	San Onofre
Issue date:	07/31/1996
From:	SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML13319A864	List: ML20138E997 ML20138F012
References
SO23-ODCM, NUDOCS 9705050233
Download: ML20138F012 (193)

Text

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July 31,1996

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SUBJECT:

Units 2/3 OFFSITE DOSE CALCULATION MANUAL Revision 29 i

Enclosed is Revision 29 to the Units 2/3 Offsite Dose Calculation Manual (ODCM). In j this revision, the changes are limited to only those concerned with the issuance of the i Technical Specification improvement Program (TSIP). Mainly, Technical Specification (TS) paragraph references are changed to coincide with the new document. In one case, the reference drawing was deleted and not transferred to the new document. The drawing, showing the site boundary for liquid effluents, is still valid and remains in the ODCM.

The site wide implementation of the TSIP has already received proper review and approval. The changes in this revision will not reduce the accuracy or reliability of dose calculations or setpoint determinations. Per NRC Generic Letter 89-01, no additional safety evaluations are required.  ;

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wea 10t.8110E6  ;

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9705050233 970428 PDR ADOCK 05000206 R PDR

The following is a complete list of the changes:

All changes in this revision are to support the side wide implementation of the TSIP, PCN 299, effective August 5,1996. All TS references in the ODCM were researched to find the corresponding paragraph reference number in the new TSIP document. The ODCM will list both reference numbers in this revision.

Next revision of Unit 2/3 ODCM, which will occur after TSIP implementation, will note only the new references.

1-5 Added appropriate TSIP reference paragraph numbers.

1-6 Added appropriate TSIP reference paragraph numbers.

1-7 Deleted reference to Technical Specification figure 5.1-4 which no longer exists.

2-5 Added appropriate TSIP reference paragraph numbers.

2-6 Added appropriate TSIP reference paragraph numbers.

2-7 Added appropriate TSIP reference paragraph numbers.

5-1 Added appropriate TSIP reference paragraph numbers.

5-2 Rolled paragraph "d" from page 5-1 and added appropriate TSIP reference paragraph numbers.

5-11 Added appropriate TSIP reference paragraph numbers.

6-9 Added appropriate TSIP reference paragraph numbers.

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OFFSITE DOSE CALCULATION MANUAL NUCLEAR ORGANIZATION l

UNITS 2 AND 3 i

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l SO23-ODCM Revision 29 07-31-96 0

1 1

ODCM l TABLE OF CONTENTS  !

Paae LIST OF FIGURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . iv LIST OF TABLES . . . . . . . . . . . . . . . . . . . . . . . . . . . . v-vi l INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vii 1.0 LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . 1-1 thru )

1-30 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 Speci fication . . . . . . . . . . . . . . . . . . . 1-5 1.2.1.1 Surveillance . . . . . . . . . . . . . . . . . . . 1-5 1 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 Setpoints . . . . . . . . . . . . . 1-8 1.4.1 Batch Release Setpoint Determination . . . . . . . 1-10 1.4.2 Continuous Release Setpoint Determination . . . . . 1-16 1.5 Dose Calculations for Liquid Effluents . . . . . . . . . . 1-27 1.6 Representative Sampling . . . . . . . . . . . . . . . . . . 1-30 2.0 GASE0US EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . 2-1 thru 2-93 2.1 Dose Rate . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 2.1.1 Speci fication . . . . . . . . . . . . . . . . . . . . 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 - Radioiodines, 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 22 i 08-02-90

, ODCM TA8LE OF CONTENTS (Continued)

P_a9A 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 5pecification . . . . . . . . . . . . . . . . . . . . 2-9 2.5.1.1 Surveillance . . . . . . . . . . . . . . . . . . . 2-9 2.6 Gaseous Effluent Monitor Setpoints . . . . . . . . . . . . 2-11 l 2.6.1 Pl ant Stac k . . . . . . . . . . . . . . . . . . . . 2- 11 l 2.6.2 Condenser Evacuation System . . . . . . . . . . . . 2-15 l 2.6.3 Containment Purge . . . . . . . . . . . . . . . . . 2-18 2.6.4 Waste Gas Header . . . . . . . . . . . . . . . . . 2-21 2.7 Gaseous Effluent Dose Rate . . . . . . . . . . . . . . . . 2-26 l 2.7.1 Nobl e Gases . . . . . . . . . . . . . . . . . . . . 2-26 i 2.7.2 Radioiodines and Particulates . . . . . . . . . . . 2-27 l 2.8 Gaseous Effluent Dose Calculation . . . . . . . . . . . . . 2-29 I 2.8.1 Nobl e Gases . . . . . . . . . . . . . . . . . . . . 2-29 l p 2.8.1.1 Historical Meteorology . . . . . . . . . 2-29 Q 2.8.1.2 Concurrent Meteorology . . . . . . . . . 2-30  ;

2.8.2 Radiciodines and Particulates . . . . . . . . . . . 2-32 2.8.2.1 Historical Meteorology . . . . . . . . . 2-32 i 2.8.2.2 Concurrent Meteorology . . . . . . . . . 2-33 2.9 Total Dose Calculations . . . . . . . . . . . . . . . . . . 2-80 2.9.1 Total Dose to Most Likely Member of the Public . . 2-80 2.9.1.1 Annual Total Organ Dose . . . . . . . . . 2-80 2.9.1.2 Annual Total Whole Body Dose . . . . . . 2-81 2.9.1.3 Annual Total Thyroid Dose . . . . . . . . 2-82 3.0 PROJECTED DOSES . . . . . . . . . . . . . . . . . . . . . . . . 3-1 thru 3-1 3.1 Liquid Dose Projection . . . . . . . . . . . . . . . . . . 3-1 3.2 Gaseous Dose Projection . . . . . . . . . . . . . . . . . . 3-1 4.0 EQUIPMENT . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 thw 4-18 4.1 Radioactive Liquid Effluent Monitoring Instrumentation . . 4-1 4.1.1 Speci fication . . . . . . . . . . . . . . . . . . . . 4-1 4.1.1.1, 4.1.1.2 Surveillances . . . . . . . . . . . . . . 4-1 S023-0DCM  ;

Revision 25 ii 02-28-92

ODCM TABLE OF CONTENTS (Continued)

Pace 4.2 Radioactive Gaseous Effluent Monitoring Instrumentation . . 4-6 4.2.1 Specification . . . . . . . . . . . . . . . . . . . . 4-6 4.2.1.1 Surveillance . . . . . . . . . . . . . . . . . . . 4-6 4.3 Operability of Radioactive Waste Equipment . . . . . . . . 4-15 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING . . . . . . . . . . . . . 5-1 thru 5-26 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 5.4 Annual Radiological Environmental Operating Report . . . . 5-13 5.5 Sample Locations . . . . . . . . . . . . . . . . . . . . . 5-14 6.0 ADMINISTRATIVE . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 thru 6-16 6.1 Definitions . . . . . . . . . . . . . . . . . . . . . . . . 6-1 6.2 Administrative Controls . . . . . . . . . . . . . . . . . . 6-7 6.3 Md or Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) . . . . . . . . . . . . . . . . . . . 6-9 6.4 Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-10 S023-0DCM Revision 25 iii 02-28-90

ODCM

LIST OF FIGURES p i V Fiaure Title Paae 1-2 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 . . . . . 4-16 4

4-6 SONGS 2 and 3 Radioactive Gaseous Waste Treatment Systems .... 4-17 4-7 Solid Waste Handling . . . . . . . . . . . . . . . . . . . . . . . 4-18 5-1 Radiological Environmental Monitoring Sample Locations l 4

2 Mile Radius .......................... 5-23 l

)

5-2 Radiological Environmental Monitoring Sample Locations 10 Miles Radius ......................... 5-24

5-3 Radiological Environmental Monitoring Sample Locations

( Orange County .......................... 5-25

5-4 Radiological Environmental Monitoring Sample Locations San Diego County . . . . . . . . . . . . . . . . . . . . . . . . . 5-26 i

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

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ODCM LIST OF TABLES Table Title Paae 1-1 Radioactive Liquid Waste Sampling and Analysis Program . . 1-2 1-3 Liquid Effluent Radiation Monitors Calibration Constants . . . . . . . . . . . . . . . . . . 1-26 1-4 Dose Commitment Factors A ir . . . . . . . . . . . . . . . 1-28 2-1 Radioactive Gaseous Waste Sampling and Analysis Program . 2-2 2-3 Gaseous Effluent Radiation Monitor Calibration Constants . . . . . . . . . . . . . . . . . . 2-25 2-4 Dose Factors for Noble Gas and Daughters . . . . . . . . . 2-35 2-5 Dose Parameters P ig . . . . . . . . . . . . . . . . . . . 2-36 2-6 Controlling Location Factors . . . . . . . . . . . . . . . 2-37  ;

2-7 Dose Parameters $R for Sector P . . . . . . . . . . . . . 2-38 l

2-8 Dose Parameters $R for Sector Q . . . . . . . . . . . . . 2-40 l 2-9 Dose Parameters $R for Sector R , . . . . . . . . . . . . 2-50 2-10 Dose Parameters iR for Sector A . . . . . . . . . . . . . 2-55 2-11 Dose Parameters $R for Sector B . . . . . . . . . . . . . 2-58 2-12 Dose Parameters $R for Sector C . . . . . . . . . . . . . 2-61 2-13 Dose Parameters R, for Sector D . . . . . . . . . . . . . 2-66 2-14 Dose Parameters $R for Sector E . . . . . . . . . . . . . 2-69 2-15 Dose Parameters $R for Sector F . . . . . . . . . . . . . 2-72 2-16 Dose Parameters R $

for Sector G . . . . . . . . . . . . . 2-76 2-17 SYF Controlling Location Factors . . . . . . . . . . . . . 2-83 2-18 SYF Dose Parameters Ri for Sector D . . . . . . . . . . . 2-84 2-19 SYF Dose Parameters Ri for Sector E . . . . . . . . . . . 2-85 2-20 SYF Dose Parameters Ri for Sector F . . . . . . . . . . . 2-86 2-21 SYF Dose Parameters Ri for Sector G . . . . . . . . . . . 2-90 0

S023-0DCM Revision 28 v 12-21-95

ODCM LIST OF TABLES (Continued)

Table Title Paae 4-1 Radioactive Liquid Effluent Monitoring Instrumentation . . 4-2 4-2 Radioactive Liquid Effluent Monitoring Instrumentation l Surveillance Requirements . . . . . . . . . . . . . . . . 4-4 l 4-3 Radioactive Gaseous Effluent Monitoring Instrumentation . 4-7 4-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements . . . . . . . . . . . . . . . . 4-11 l

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 O

V 6-1 Operational Modes . . . . . . . . . . . . . . . . . . . . 6-5 6-2 Frequency Notation . . . . . . . . . . . . . . . . . . . . 6-6 1

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

l INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the '

RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (NUREG 0472). The ODCM enumerates dose and concentration specifications, instrument requirements, as well as describes the methodology and parameters to be used in the calculation l l

of offsite doses from radioactive liquid and airborne effluents. In order to meet release limits, it additionally provides calculations for liquid and ,

l gaseous effluent monitoring instrumentation alarm / trip setpoints. The environmental section contains a list of the sample locations for the radiological environmental monitoring program.

The ODCM 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.

O S023-0DCM Revision 21 vii 02-15-90

1.0 LIQUID EFFLUENTS 1.1 CONCENTRATION l

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 entr I be limited to 2 x 10~ pined noble gases,total microcuries/ml the concentration activity. shall l

APPLICABILITY: At all times i ACTION:

4 a. With the concentration of radioactive material released from

the site exceeding the above limits, immediately restore the concentration to within the above limits. l SURVEILLANCE RE0UIREMENTS l .1 Radioactive liquid wastes shall be sampled and analyzed according j to the sampling and analysis program of Table 1-1.

.2 The results of the radioactivity analyses shall be used in acenrdance with the methodology and parameters in Section 1.4 to assure that the concentrations at the point of release are maintained within the limits of Specification 1.1.1.

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i S023-0DCM 1-1 Revision 22 08-02-90

TABLE 1-1 RADI0 ACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM

)

Liquid Release Sampling Minimum Analysis Type of Activity Lower Limit of Detection h (LLD)

Type Frequency Frequency Analysis ( Ci/ml)*

A.BatchWgste P P Principa) Gama 5x10-7 Release Each Batch Each Batch Emitters I-131 1x10-6 P M Dissolved and 1x10-5 One Batch /M Entrained Gases (Gama emitters)

P M H-3 1x10'5 b

Each Batch Composite Gross Alpha 1x10-7 P Q Sr-89, Sr-90 5x10-8 Each Batch Composite b Fe-55 1x10-6 O

ROIE BATCH RELEASE POINTS: Primary Plant tiakeup Storage Tanks, Radwaste Primary Taiiks, Radwaste Secondary Tanks, Miscellaneous Waste Condensate Monitor Tank;,

Blowdown Processing Sump, FFCPD sumps (high conductivity, low conductivity) and holdup tank, Component Cooling Water Sump, Storage Tank Area Sump, S/G Blowdown B. Continuous D W Principa) Gama 5x10-7 Releases", Grab Sample Composite

• Emitters I-131 1x10-6 M M Dissolved and 1x10-5 Grab Sample Entrained Gases (Gama emitters)

D M C

H-3 1x10-5 Grab Sample Composite ,

Gross Alpha 1x10-7 l

D Q Sr-89, Sr-90 5x10-8 Grab Sample Composite

• Fe-55 1x10-6 NOTE CONTINU0US RELEASE PQJflTS: Turbine Plant Sump *, Blowdown Proce.ssing Sump ,S/G l Blowdown Bypass Line , S/G Blowdown, Auxiliary Building Sump.

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

l TABLE 1-1 (Continued) i TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that j ), will be detected with 95% probability with only 5% probability of falsely l concluding that a blank observation represents a "real" signal.

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

LLD =

l E V . 2.22 x 106

• Y

• exp (-let) l where: l j

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

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

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

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

f- 2.22 x lo sis the number of transformations per minute per microcurie,

, Y is the fractional radiochemical yield (when applicable),

i 1 is the radioactive decay constant for the particular radionuclide, and 1 At is the elapsed time between midpoint of sample collection and time of  :

i counting (for plant effluents, not environmental samples). .

1 The value of sb used in the calculation of the LLD for a particular measurement j 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

an unverified theoretically predicted variance.

1

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 oriori (before the fact)

~

iimit representing the capability of the measurement system and i

) oosteriori (after the fact) limit for a particular measurement.,not as A '

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

. I (1)

(2) HASL Currie,Procedures L. A., " Limits Manual, HASL-300Detection for Qualitative (revised annually)d an 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 1-3 Revision 26 12-20-93

TABLE 1-1 (Continued)

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 liquids 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 LLO specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-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 i 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 for Steam Generator 2E089, S31301MU618 for Steam Generator 3E088 and S31301MU619 for Steam Generator 3E089) is verified locked shut.

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

1.0 LIQUID EFFLUENTS (Centinutd) 1.2 DQSE SPECIFICATION O 1.2.1 The dose or dose commitment 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 arem to any organ.

APPLICABILITY: At all times ACTION:

a. With calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification 6.9.1,

[Section 5.7.1 and LCS 5.0.104 upon TSIP implementation],

prepare and submit to the Commission within 30 days, pursuant o to Technical Specification 6.9.2, [Section 5.7.2 and LCS B 5.0.104.2 upon TSIP implementation], a Special Report which identifies the 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.

O S023-0DCM d

1-5 Revision 29

07-31-96 1

1.0 LIQUID EFFLUENTS (Continued) l 1.3 LIOUID WASTE TREATMENT l

! 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 (seeFigure1-2)whenaveragedover31 days,wouldexceed 0.06 mrem to the total body or 0.2 mrem to any organ 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 Specification 6.9.1,

[Section 5.7.1 and LCS 5.0.104 upon TSIP implementation],

prepare and submit to the Commission within 30 days pursuant to R Technical Specification 6.9.2, [Section 5.7.2 and LCS 5.0.104.2 upon TSIP implementation], 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 g

3. Summary description of action (s) taken to prevent a  !

recurrence.

1 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 treatment 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 liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.

'Per reactor unit S023-0DCM 1-6 Revision 29 07-31-96

4 i a -

,,. l i e0 ERAfts8 STATION UIETS L 2 63 .

l l'  :& O 00 _ ___

f  % l i

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! m

\3 we j ..

l _ .= e _a=_ (/,f,- ,

( wr

. / )

/

f n-

\. s' SITE BOUNDARY FOR LIOUID EFFLUENTS FIGURE 1-2 D

O S023-0DCM 1-7 Revision 29 07-31-96

1.0 LIQUID EFFLUENTS (Continued) 1.4 Liquid Effluent Monitor Methods of Setpoint Calculation Liquid Radwaste Effluent Line Monitors provide alarm and automatic O

termination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B, Table II, Column 2 at the release l

point to the unrestricted area. To meet this specification and for the purpose of implementation of Specification 1.1.1, the alarm / trip setpoints for liquid effluent monitors and flow measurement devices are l set to assure that the following equation is satisfied:

1 (1 3)

C,R I 5 MPC,ff F4 where:

MPC,ff = effective effluent maximum concentration permissible limit (pci/ml) at the release point to the unrestricted area for the radionuclide mixture being released, I (1-2)

=

N r ,

p i

E i =1 , MPC,,

S023-0DCM 1-8 Revision 21 02-15-90

1.0 LIQUID EFFLUENTS (Continued) 1.4 Liquid Effluent Monitor Methods of setpoint calculation (Continued)

Q

(/

where:

F, = fractional concentration of the i th radionuclide as obtained by sample analysis.

N = number of radionuclides identified in sample analysis.

MPC; = MPC of the i th radionuclide (10CFR20, App B,' Table II, Column 2).

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, pCi/ml.

R = permissible waste effluent flow rate at the radiation monitor location, in volume per unit time in the same units as for F.

F = dilution water flow in volume per unit time. The dilution water flow (F) is 185,000 gpm per circ pump (4 total) and 17,000 gpm per saltwater pump (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.

O l

l S023-0DCM 1-9 Revision 21  !

02-15-90

l 1.0 LIQUID EFFLUENTS (Continued) 1.4 Liquid Effluent Monitor Methods of Setpoint Calculation (Continued)

Administrative values are used to reduce each setpoint to account for the potential activity in other releases. These administrative values  ;

shall be periodically reviewed based on actual release data (including, for example, any saltwater discharge of the component cooling water heat exchanger) and revised as necessary.

1 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 effective MPC (MPC,ff) 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 measured concentrations in the tank (or sump) as g determined by analysis.

= E; C

(~

C y + C, + C, + Cs+C, y where:

C - total concentration in each batch tank, pCi/ml ECg jy - sum of the measured concentrations for each radionuclide, i, in the gamma spectrum, pCi/ml C Fe = Fe-55 concentration as determined in the previous quarterly composite sample, pCi/ml C, = gross alpha concentration determined in the previous monthly composite sample, pCi/ml C5 = Sr-89 and Sr-90 concentrations as determined in the previous quarterly composite sample, pCi/ml Ct - H-3 concentration as determined in the previous monthly composite sample, or as measured in the sample taken prior to release, pCi/ml.

S023-0DCM 1-10 Revision 27 12-21-94

1.0 LIQUID EFFLUENTS (Continutd) 1.4.1 Batch Release Setpoint Determination (Continued)

STEP 2: The effective MPC (MPC,ff) for each batch tank (or sump) is determined using:

3 (1-4)

MFC,f' =

' Cy ,/C' 'C,/C' 'Ct/C' 'C,/C' 'Cp ,/C' HPC MPC yj, MPC,, t, ,

MPC,, MPCp ,,

MPC y MPC t the limiting concentrations of the appropriate MPC p, ,g , MPC,s, MPC ,-

radionuclide from 10CFR20, Appendix B, Table II, Column 2.

NOTE: For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 pCi/ml total activity.

STEP 3: The radioactivity monitor setpoint C,, pCi/ml, may now be specified based on the values of C, E Cyj j , F, MPC,ff and R to provide compliance with the limits of 10CFR20, Appendix B, Table II, Column 2. The monitor setpoint, cpm, is taken from the applicable calibration constants given in Table 1-3 to correspond to the calculated monitor concentration limit C,, pCi/ml.

m S023-0DCM 1-11 Revi:: ion 21 02-15-90

l 1.0 LIQUID EFFLUENTS (Continu:d) 1.4.1 Batch Release Setpoint Determination (Continued) 1 1.4.1.1 RADWASTE DISCHARGE LINE MONITOR (2/3-7813)

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

i (C,ff) (1-5)

(RW) (F) m- e ,

j (R3 +. . +n R MPC ) eff1

• MPC effn, where: l n = number of tanks to be released. I C,ff = effective gamma isotopic concentration at the monitor for the tank combination to be released (equal to Eiyc , for single tank releases).

l (1-6) l R3 (Ej C yg ) + R2 (E iCyj) + . . . + R n(E iyC ,)

R1+R2+...+Rn O

(EjCy4)3, (EjCy g)2, etc. = total gamma isotopic concentration of first l tank, second tank, etc. (pCi/ml). l l

R 1 , R2 , etc. = typical effluent flow rate from first tank, l second tank, etc. Values of R for each tank are as follows: ,

Radwaste Primary Tanks R = 140 gpm/ pump (x no. of pumps to be run)

Radwaste Secondary Tanks R = 140 gpm/ pump (x no. of pumps to be run)

Primary Plant Makeup Tank R = 160 gpm/ pump (x no. of pumps to be run)

Condensate nonitor Tanks R = 100 gpm/ pump (x no. of pumps to be run) 5023-0DCM 1-12 Revision 26 12-20-93

1.0 LIQUID EFFLUENTS (Continu:d) 1.4.1.1 RADWASTE DISCHARGE LINE MONITOR (2/3-7813) (Continued)

OJ Ns NOTE: Since the values of R are much smaller than F, the term (F + R) in equation (1-1) may be replaced by F. l MPC,ff3, MPCeff2, etc. = values of MPC,ff from equation (1-4) for first tank, second tank, etc.

C 1 , C 2, etc. =

values of C, total concentration, from equation (1-3) for the first tank, second tank, etc., in pCi/ml.

RW 7313 and SGm-2

• SG89-2' bO88-3' bO89-3' 0 ' 03 ' I 2' I3 are 2

administrative values used for simultaneous releases from the Radwaste Effluent discharge and any or all of the four Steam Generators as well as continuous discharges from the two Blowdown Processing Systems and the two Turbine Plant Sumps. The fractions RW7813 and SGm-2* SG89-2' SG88-3' bG89-3' 02 ' 0 3' I , 2T3 will be assigned such that (RW7813 +

SGM-2 + bO89-2 + bO88-3 + bO89-3 + O2+03 + I2 + I 3) 5 1.0.

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S023-0DCM 1-13 Revision 21 02-15-90

1.0 LIQUID EFFLUENTS (Continusd) 1.4.1.1 RADWASTE DISCHARGE LINE MONITOR (2/3-7813) (Continued)

The 1.0 is an administrative value used to account for the potential l

activity released simultaneously from other release points. This I assures that the total concentration from all release points to the plant discharge will not result in a release of concentrations l

exceeding the limits of 10 CFR 20, Appendix B, Table II, Column 2 from the Site. '

NOTE: If C, s C,ff, then no release is possible. To increase C,, increase dilution flow F (by running more circulating water pumps in the applicable discharge structure), and/or decrease the effluent flow rates R3 , R2 , etc., (by throttling the combined flow as measured on 2/3FI-7643, 2FIC-4055, 2FIC-4056, 3FIC-4055 or 3FIC-4056 as appropriate) and recalculate C, using the new F, R and equation (1-5).

S023-0DCM 1-14 Revision 26 12-20-93

1.0 LIQUID EFFLUENTS (Centinued) 1.4.1.2 NEUTRALIZATION SUMP / FULL FLOW CONDENSATE POLISHER DEMINERALIZER IFJ_G.PD) SUMP DISCHARGE LINE MONITOR (batch) (2RT-7817. 3RT-7817)

The value for C2 or C 3 , the concentration limit at the Unit 2 or Unit 3 detector, is determined by using: )

I (B)(F)E,C 2

(I-7)

C5 2

73  !

(R)(C/MPC,ff) 1 l

(B3 )(F)I;C yj ( -8) i C5 3 l (R)(C/MPC,ff) where:

C, E jCyg , MPC,ff =

values of C, EjC and MPC,ff as defined in STEPS 1) and for the Neutralization Sump /FFCPD Sumps.

R = Typical release flow rates 500 gpm Neutralization Sump 500 gpm FFCPD High Conductivity Sump 600 gpm FFCPD Low Conductivity Sump j 1000 gpm FFCPD Holdup Tank C2 =

instantaneous concentration at the detector (2RT-7817) in pCi/cc C3 =

instantaneous concentration at the detector (3RT-7817) in pCi/cc B2 and B3 are administrative values used to account for simultaneous releases from both SONGS 2 and SONGS 3 neutralization sumps. The fractions B 2and B3 (each normally set to 0.05) will be assigned such that (RW7333 + SG88-2 + b689-2 + b088-3 + 3089-3 + O 2+0+I+T}i 3 2 3 1.0.

S023-0DCM 1-15 Revision 27 12-21-94

1.0 LIQUID EFFLUENTS (Continued) 1.4.1.2 NEUTRALIZATION SUMP / FULL FLOW CONDENSATE POLISHER DEMINERALIZER (FFCPD) SUMP DISCHARGE LINE MONITOR (batch) (2RT-7817, 3RT-7817)

(Continued)

NOTE: If C 2or C $3 E Cj yg, then no release is possible. To increase C2 or C 3, increase dilution flow F (by running more pumps),

and/or decrease the effluent flow rate R, (by throttling the flow as measured on 2FI-3722 and 3FI-3772), and recalculate C 2 or C3 using the new F, R and equation (1-7) or (1-8).

1.4.2 Continuous Release Setpoint Determination The waste flow (R) and monitor setpoint (C,) are set to meet the condition of equation (1-1) for the effective MPC (MPC,ff) 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=ECjyj+C,+Ce+C,+C, p S023-0DCM 1-16 Revision 26 12-20-93

1.0 LIQUID EFFLUENTS (Continu:d) 1.4.2 Continuous Release Setpoint Determination (Continued) where:

C = total concentration (pCi/ml)

EC$yj

= total gamma activity associated with each radionuclide, i, in the weekly composite analysis for the relcase stream, l pC1/ml C, = total measured gross alpha concentration determined from the previous monthly composite analysis for the release stream,pC1/ml

C,p

= total Fe-55 concentration as determined in the previous quarterly composite sample for the release stream, pCi/ml l Ct = total measured H-3 concentration determined from the

previous monthly composite analysis for the release i stream,pCi/ml i Cs = total measured concentration of Sr-89 and Sr-90 as i determined from the previous quarterly composite analysis i for the release stream, pCi/ml i

i l STEP 2: The effective MPC (MPC,ff) for each release stream (steam generator blowdown, blowdown neutralization sump, or i turbine plant sump) is determined using:

) (1-10)

MPC'## =

'Cyg/C' ' C,/C' 'CgC' 'Cp ,/C' 'C/C' j

g + + + +

t MPC, MPC, (MPC, MPCp , MPC t,

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O j S023-0DCM l-17 Revision 22 08-02-90

1.0 LIQUID EFFLUENTS (Centinued) 1.4.2 Continuous Release Setpoint Determination (Continued)

STEP 3: The setpoint, C, (pCi/ml), for each continuous release radioactivity monitor may now be specified based on the respective values of C, I,Cg, F, MPC,ff, and R to provide compliance with the limits of 10CFR20, Appendix B, Table II, Column 2. The monitor setpoint, cpm, is taken from the applicable calibration constants given in Table 1-3 to correspond to the calculated monitor limit C,,

pCi/ml.

O S023-0DCM 1-18 Revision 21 02-15-90

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.1 NEUTRALIZATION SUMP DISCHARGE LINE MONITORS (2RT-7817. 3RT-7817)

The value for C2 or 3C , the concentration limit at the Unit 2 or Unit

3 detector is determined by using:

(B2 )(F)4Cy, II~II) 2 - (R)(C/MPC,ff)

(B3 )(F)4Cyj

(~ )

3~

(R)(C/MPC,ff)

where:

C, EgCy g, MPC,ff =

values of C, I,C i and MPC ff as defined in

.. STEPS 1and2foftheStea,mGenerator

! blowdown / BPS neutralization sump.

R = effluent flow rate at the radiation monitor as ,

defined in STEP 2 (maximum of 500 gpm). '

C2 = instantaneous concentration at the Unit 2 detector (2RT-7817) in pCi/cc f'

( C3 - instantaneous concentration at the Unit 3 detector (3RT-7817) in pCi/cc B2 and B3 are administrative values used to account for simultaneous releases from both SONGS 2 and SONGS 3 neutralization sumps. The fractions B2 and B will 3 be assigned such that (RW7813 + SG88-2 + SG89-2

+ SG3g.3 + SG39 3 + B2 + B3 + T2 + T3} $ 1.0 I i

O 1-19 S023-0DCM Revision 22 08-02-90

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.1 NEUTRALIZATION SUMP DISCHARGE LINE MONITOR (2RT-7817. 3RT-7817) (Continued)

NOTE: If C2 or C3 1 I,C g, y then no release is possible. To increase C2 or C 3, increase dilution flow f (by running more circulating water pumps), and/or decrease the effluent flow rate R, (by throttling the flow as measured on 2FI-3722 and 3FI-3772), and recalculate C2 or C3 using the new F, R and equation (1-11) or (1-12).

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S023 0DCM l 1-20 Revision 26 12-20-g3 f

1.0 LIQUID EFFLUENTS (Continu::d) 1.4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT-6753. 2RT-6759, 3RT-6753, 3RT-6759)

The value for C59-2' C53-2' C59-3 or C53-3, the concentration limit at the Unit 2 or Unit 3 detectors, is determined by using:

(SG88-2)(F) ACyj (I-I3) 59 (R)(C/MPC,ff)

II~I4)

(SG89-2)(F)4 C yj 53 (R)(C/MPC,ff)

(1-15)

(SGag_3)(F)4Cyi 59 (R)(C/MPC,ff)

(SG89-3)(F) ACy ,

(1-16) 53 (R)(C/MPC,ff)

1. where:

C, I,C yj, MPC,ff = values of C, EjC y, and MPC ff as defined in l STEPS 1and2above) fort %es(teamgenerator '

blowdown bypass.

R = maximum blowdown bypass effluent flowrate per steam generator, 200 gpm.

C 59-2 = instantaneous concentration at the Unit 2 detector (2RT-6759) in pCi/ml C

53-2

" instantaneous concentration at the Unit 2 detector (2RT-6753) in pCi/ml i

C 59 3 = instantaneous concentration at the Unit 3 detector (3RT-6759) in pCi/ml C 53-3 = instantaneous concentration at the Unit 3 detector (3RT-6753) in pCi/ml l l

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l O S023-00CM 1-21 Revision 21 02-15-90

1.0 LIQUID EFFLUENTS (Continu3d) ,

1.4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT-6753. 2RT-6759. 3RT-6753, 3RT-6759) (Continued)

RW 7313 and SG88-2' SG89-2, SG33 3, SG 39 3, B2 ' B3 , T2, T3 are administrative values used for simultaneous releases from the Radwaste 1 l

Effluent discharge and any or all of the four Steam Generators as well l l

as continuous discharges from the two Blowdown Processing Systems and the two Turbine Plant Sumps. The fractions RW7313 and SG88-2' S089-2' SG88-3' SG 89-3' 02 ' 03 ' I 2, T3 will be assigned such that {RW7313 +

SG88-2 + SG89-2 + S088-3 + S089-3 02+03+T2 + I3 ) s 1.0.

The 1.0 is an administrative value used to account for the potential activity released simultaneously from other release points. This

, assures that the total concentration from all release points to the plant discharge will not result in a release of concentrations exceeding the limits of 10 CFR 20, Appendix B, Table II, Column 2 from the site.

NOTE: If C59-2, C53-2, C59 3, or C53 3 1 I,C y g (for the respective steam generator), then no release is possible. To increase C 59-2' C53-2, C59 3 or C53 3, increase dilution flow F (by running more circulating water pumps), and/or decrease the effluent flow 1 rate R (by throttling the flow as measured on 2FIC-4055, 2FIC-4056, 3FIC-4055, 3FIC-4056 or 2/3FI-7643, as aopropriate) and recalculate C59-2' C53-2' C59-3 or C 53-3 using the new values of F, R and equation (1-13), (1-14), (1-15) or (1-16).

S023-0DCM 1-22 Revision 21 02-15-90

.,._.-_u.- - . - - - -.-----a~> -

1 l 1.0 LIQUID EFFLUENTS (Centinutd) 1.4.2.3 TURBINE PLANT SUMP MONITORS (2RT-7821, 3RT-7821) i The value for C2 or C3 (the concentration limit at the Unit 2 or Unit i

3 detector) is determined by using:

4 (T)(F)AC, (1-17)

, 2 y j

2 - (R)(C/MPC,ff) i (1-18)

, , (T3 )(F)hC yg

~

3~

(R)(C/MPC,ff) where:

=

3 C, E Cg yi, MPC,ff values of C, Z C4 yg and MPC ff (as defined in

STEPS I and 2 above) for the turbine plant sump

?

l R = Typical waste stream release flow rates:

100 gpm/ pump (x no. sump pumps to be run) Unit 2 i 100 gpm/ pump (x no. sump pumps to be run) Unit 3 C2 =

instantaneous concentration at the Unit 2

,. detector (2RT-7821), pCi/ml.

~

j C3 =

instantaneous concentration at the Unit 3

detector (3RT-7821),pC1/ml.

l

?

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O' S023-0DCM l-23 Revision 27 12-21-94 I

l 1.0 LIQUID EFFLUENTS (Continued) 1.4.2.3 TURBINE PLANT SUMP MONITORS (2RT-7821. 3RT-7821) (Continued)

T2 and T3 are administrative values used to account for simultaneous releases from both SONGS 2 and SONGS 3 turbine plant sumps. The fractions T2 and T3 will be assigned such that {RW7813 + SG88-2 + SG89-2

+ SG88-3 + SG89-3 02+03+I 2 + I3) 5 1.0.

NOTE: If C2 or C3 5ECi g (for the respective sump), then no release is possible. To increase C2 or C3 , increase the dilution flow F (by running more circulating water pumps) and recalculate C 2 or C3 using the new value of F and equation (1-17) or (1-18).

I I

Use of a temporary discharge path from the Turbine Plant Sump is l

allowed providing the radiation monitor, 7821, in service and the l 1

normal discharge path is used concurrently. Temporary pumps facilitate faster discharge when draining the condenser to the outfal I via this pathway. The following conditions shall be met:

a. The release permit shall account for the entire volume of water discharged from the Turbine Plant 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 .mporary path if the monitor on the normal path al arms.

S023-0DCM 1-24 Revision 21 02-15-90

1.0 LIQUID EFFLUENTS (Continued)

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S023-0DCM 1-25 Revision 26 12-20-93 i

Tablo 1-3 Liquid Effluent Radiation Monitor Calibration constants (pCi/cc/ cpm)

MONITOR Co-60 Ba-133 Cs-137 2RT-6753 1.93E-8 1.94E-8 2RT-6759 2.18E-8 2.15E-8 3RT-6753 1.63E-8 1.91E-8 3RT-6759 2.02E-8 1.99E-8 2/3RT-7813 2.15E-9 3.77E-9 5.48E-9 2RT-7817 2.33E-9 3.27E-9 4.85E-9  ;

2RT-7821 2.30E-9 3.18E-9 4.85E-9 1

3RT-7817 2.34E-9 3.22E-9 4.95E-9 1

3RT-7821 2.32E-9 3.18E-9 4.72E-9 I O l l

l l

1 (a) This table provides typical ( 20%) calibration constants for the liquid effluent radiation monitors.

S023-0DCM 1-26 Revision 28 12-21-95

1.0 LIQUID EFFLUENTS (Continu:d) 1.5 Dose Calculation for Liquid Effluents g)

( The liquid releases considered in the following dose calculations are described in Section 1.4. The dose comitment to an individual from l radioactive materials in liquid effluents released to unrestricted areas are calculated for the purpose of implementing Specification 1.2.1 using the follwing expression.

(1-19) '

Dr"Ei A 47 E(At 3 3 Cg3 F{3 where:

A ir - Site-related adult ingestion dose comitment factor to the total body or an organ, t, for each identified principal gama and beta emitter, i, from Table 1-4 in mrem /hr per pCi/ml.

C g3 -

average concentration of radionuclide, i, in the undiluted liquid effluent during time period, At3 , in pCi/ml.

Dr = dose comitment to the total body or an organ, t, from the liquid effluent for the time period, At 3, in mrem.

O)

( F 3

=

near field average dilution factor (actually mixing ratio) for C g3 during the time period, At3 . This factor is the ratio of the maximum undiluted liquid waste flow during time period, At , to '

the average flow from the site discharge structure to unrestricted receiving waters, or maximum liauid radioactive waste flow discharge structure exit flow At 3 =

length of the jth time period over which Cg3 and FJ are averaged for all liquid releases, in hours.

S023-0DCM 1-27 Revision 26 12-20-93

TABLE 1-4 DOSE COMMITMENT FACTORS *, Ag )

(mrem /hr per pCi/ml)

Radio- Total 4 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 I 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 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 l 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 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 i 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 1 Y-92 5.32E-1 1.56E-2 9.32E+3 1 Zr-95 1.59E+1 5.11E+0 3.46E+0 8.02E+0 1.62E+4 l Zr-97 8.81E-1 1.78E-1 8.13E-2 2.68E-1 5.51E+4 l Nb-95 1.84E+0 1.03E+0 5.51E-1 1.01E+0 6.22E+3 l Nb-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 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 I-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 NOTE: where no value is given, no data are available.

• Source: Reg. Guide 1.109, Table E-11, Table A-1 Table 4 USNRC ICRP-30,NUREG-0172, Part 3, Supplement A Methodology: USNRC NUREG-0133, Section 4.3.1 5023-0DCM 1-28 Revision 26 l 12-20-93 1

.. - - _ _ - - - _ . . _ ~ . - - _- .- -- - . _ -

TABLE 1-4 DOSE COMMITMENT FACTORS *, Ag (mrem /hr per pCi/ml)

'O

,v Radio- Total Nuclide Bone 893e, Body Thyroid Kidney Lung GI-LLI Cs-134 6.84E+3 1.63b+4 3!!!!h9' 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 l 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

,Np-239 3.53E-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 Or, l

l I

S023-0DCM l 1-29 Revision 26 l 12-20-93

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 methodology for mixing and sampling is described in S0123-III-5.11.23,

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

O S023-0DCM 1-30 Revision 21 02-15-90

2.0 GASE0US EFFLUENTS 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 radiciodines, tritium and for all radioactive materials 1 in particulate form with half lives greater than 8 days: Less than or equal to 1500 arem/yr to any organ.

APPLICABILITY: At all times ACTION:

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

SURVEILLANCE REOUIREMENTS

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

.2 The dose rate due to radiciodines, 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.

O S023-0DCM  ;

2-1 Revision 21 i 02-15-90 l

TABLE 2-1 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM aseous Minimum Type of Lower Limit Release Sampling Analysis Activity of Detection Type Frequency Frequency Analysis (pCi/ml)*

Batch P P Principal Gamma Emitters 9 1x10-4 Waste Gas Each Tank Each Tank Decay Tank Grab Sample Each Batch i Each Batch i Principal Gamma Emitters 9 5x10-7 Incfnerated Oil Grab Sample Continuous *

• Principal Gamma Emitters 9 1x10-4

• Tritium 1x10-6 d

W 1-131 1x10-12 f

Continuous Charcoal Sampler Sample I-133 1x10-10 d

W f

Continuous Particulate Principal Gamma Emitters 9 1x10-Il Sampler Sample (I-131 and Others)

M Continuous f Composite Gross Alpha 1x10-Il Sampler Particulate Sample f

Continuous Composite Sr-89 and Sr-90 1x10-Il Sampler Particulate l Sample Continuous f Noble Gas Noble Gases 1x10-6 Monitor Monitor Gross Beta or Gamma

• Sampling frequencies for noble l gases and tritium are:

1 CONTINUOUS PATHWAYS: Containment Purge - 42" : b Each Purge ,e j Monthly Grab b Containment Purge - 8"  :

b Condenser Air Ejector  : Monthly Grag

Plant Vent Stack  : Weekly Grab I South Yard Facility  : Particulate and Iodine sampling onlyJ S023-0DCM 2-2 Revision 27 12-21-94

TABLE 2-1 (Continued) '

TABLE NOTATION I l

a. The LLD is the smallest concentration of radioactive material in a sample  !

2 f that 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 sb

E

• V . 2.22 x 106

• Y . exp (-Mt)

where

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

s ,

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

E is the counting efficiency (as counts per transformation), l V is the sample size (in units of mass or volume),

{ 2.22 x 106 is the number of transformations per minute per microcurie,

, f j Y is the fractional radiochemical yield (when applicable),

j 1 is the radioactive decay constant for the particular radionuclide, and l At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

i l The value of sb used in the calculation of the LLD for a particular

measurement system shall be based on the actual observed variance of the 4 backgr6und counting rate or of the counting rate of the blank samples (as '

j appropriate) rather than on an unverified theoretically predicted variance.

t l 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 oriori (before the i fact) limit representing the capability of the measurement system and not as a nosteriori (after the fact) limit for a particular measurement.*

4

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

(1) HASL Procedures Manual, HASL-300 (revised annually). l (2) Currie, L. A., " Limits for Qualitative Detection and Quantitative

' Determination - Application to Radiochemistry" Anal . Chem. 40, 586-93 (1968).

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

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

j

O S023-0DCM 2-3 Revision 26 I 12-20-93 i

TABLE 2-1 (Continued)

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.

l

c. Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the '

refueling canal is flooded.

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

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

, days following each shutdown, startup, or a THERMAL POWER change exceeding 15  !

percent of RATED THERMAL POWER in I hour and analyses shall be completed l within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. 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. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10.

3

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

f. The ratio of the sample flow rate to the sampled si. ream flow rate shall be known for the 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,  !

Zn-65, Mo-99, Cs-134, Ce-141 and Ce-144 for particulate emissions. This list i

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. Incinerated oil may be discharged at points other than the plant vent stack.

Release shall be accounted for based on pre-release grab sample data. '

1. Samples for incinerated oil releases shall be collected from representative samples of filtered oil in liquid form.

j. Radioactive airborne effluents only expected to be particulate and iodine.

S023-0DCM 2-4 Revision 27 12-21-94

l 2.0 GASE0US EFFLUENTS (Centinued) 2.2 DOSE - NOBLE GASES

! SPECIFICATION

2.2.1 The air dose due to noble gases released in gaseous effluents, 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 gamma 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 l gamma radiation and less than or equal to 20 mrad for beta l radiation.

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 6.9.1,

[Section 5.7.1 and LCS 5.0.104 upon TSIP implemer.tation),

prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, [Section 5.7.2 and LCS b 5.0.104.2 upon TSIP implementation], 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 Specifica-tion 2.2.1.

i SURVEILLANCE REQUIREMENTS I

.1 Dose 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.

O S023-0DCM 2-5 Revision 29 07-31-96

2.0 GASE0US EFFLUENTS (Continued) 2.3 DOSE - RADIOI0 DINES. RADI0 ACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM SPECIFICATION 2.3.1 The dose to an individual from tritium, radioiodines 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:

I

a. During any calendar quarter: Less than or equal to 7.5 mrem to  !

any organ and, l

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

c. Less than 0.1% of the limits of 2.3.1 (a) and (b) as a result of burning contaminated oil.

1 APPLICABILITY: At all times l l

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 6.9.1, [Section 5.7.1 and LCS 5.0.104 upon TSIP implementation], prepare and submit to the Commission within 30 days pursuant to Technical Specification 6.9.2, (Section 5.7.2 and LCS 5.0.104.2 upon TSIP implementation), 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 RE0VIREMENTS

.1 Dose 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.

S023-0DCM 2-6 Revision 29 07-31-96

2.0 GASE005 EFFLUENTS (Centinued) 2.4 GASEOUS RADWASTE TREATMENT SPECIFICATION

2.4.1 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION

EXHAUST TREATMENT SYSTEM shall be operable. The appropriate

! portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be.used j to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to

! gaseous affluent releases from the site (see Figure 2-2), when  ;

averaged over 31 days, would exceed 0.2 mrad for gamma j radiation and 0.4 mrad.for beta radiation. The appropriate a

portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be

used to reduce radioactive materials in gaseous waste prior to i their discharge when the projected doses due to gaseous i effluent releases from the site (see Figure 2-2) when averaged q over 31 days would exceed 0.3 mrem to any organ.*

t j APPLICABILITY: At all times 4

l ACTION:

a. With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report i i required by Technical Specification 6.9.1, (Section 5.7.1 and )

i LCS 5.0.104 upon TSIP implementation], prepare and submit to

the Commission within 30 days, pursuant to Technical Specifica. R

! tion 6.9.2, (Section 5.7.2 and LCS 5.0.104.2 upon TSIP i implementation], a Special Report which includes the following i information:

1. Explanation of why gaseous radwaste was being discharged

{ without treatment, identification of the inoperable j equipment or subsystems and the reason for inoperability,

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

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

SURVEILLANCE REQUIREMENTS

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

l s

2 *These doses are per reactor unit.

i O S023-0DCM i

2-7 Revision 29 07-31-96 J

2.0 GASEOUS EFFLUENTS (Continued) 2.4 .QASE0VS RADWASTE TREATMENT (Continued)

SURVEILLANCE RE0VIREMENTS (Continued) 2.4.1.2 During plant operation (Modes 1-4), the applicable portions of the GASE0US RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASE0US 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 S, 6), the applicable portions of the GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASE0US 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.

I l

9 l

l S023-0DCM 2-8 Revision 22 08-02-90

2.0 GASEOUS EFFLUENTS (Continued)

)

2.5 TOTAL DOSE SPECIFICATION 2.5.1 The dose or dose commitment to any member of the public, due to i 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. j 1

APPLICABILITY: At all times  !

ACTION:

1

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 j Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory i 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 A consecutive month period that includes the release (s) covered by this report. If the estimated dose (c) exceeds the limits of Specification 2.5.1, and if the release condition resulting in 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 RE0VIREMENTS

.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

a - . _ _ - - -o.u a I

I i

i

1i;jilbli t '-t f E as 4,

s 5 2;:

a

- 1111111 tii!"il 111 !. p-

" e!

Eli" b8 5

- *e

~

}y * ' ' " f n!!.5 u

e f

u P' - = = =

• • H  %  !!

N = .

, ,/ f*

s .

/ \ N i /

i \

)[

i N

E n/ E I ,l N

=

E ,%,% ll' .

? * %i, h f

s . a64.L- \

5 I

=p i = .. . ,

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• j . 4huse. N-4 --

% g,. ,

t,=4j *

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3 i

)j: b

=.

~

/

/

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. D

~

/

./f

!b.  : -

h\, ism e

__ _ . - s i-

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% h  ! /

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. ,_ . - - -- . - - - -.-. .. - . - _ - . - . - - - - - - . . _._ _ ~ .

2.0 GASE0US EFFLUENTS (Continu:d) 2.6 Methods of Calculation for Gaseous Effluent Monitor Setnoints Administrative values are used to reduce each setpoint to account for j the potential activity in other releases. These administrative values i

shall be periodically reviewed based on actual release data and revised t

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

2.6.1 PtANT VENT STACK - 2/3RT-7808, 2RT-7865-1, 3RT-7865-1 2.6.1.1 2/3RT-7808 - Plant Vent Stack Monitor j

For the purpose of implementation of Specification 2.1.1, the

!j alarm setpoint level for noble gas monitors is based on the

) gaseous effluent flow rate and the meteorological dispersion i, factor.

I 4

] Total Body The concentration at the detector corresponding to a j 500 mrem /yr total body dose rate at the exclusion area boundary i is determined by: (2-1) d b , ,

where: (0.38) 2120 ( 500 mrem /yr) (104 3 m /cc)

! ' m /sec, l

Cdet =

, ,e s (Flow rate, cfm) (X/Q, sec/m ) E4 3 K , "I'"!##

3 C j ,

pCi/m , , tot,,

i C det = the instantaneous concentration at the detector,

} pCi/cc i

j 0.38 =

an administrative value used to account for

! potential activity from other gaseous release

{ pathways i

S023-0DCM 2-11 Revision 26 4

12-20-93

2.0 GASEOUS EFFLUENTS (C:ntinued) 1 2.6.1 PLANT VENT STACK - 2/3RT-7808, 2RT-7865-1, 3RT-7865-1 (Continued)  ;

Kj = total body dose con ersion factor from Table 2-4 for the i gamma emitting noble gas, mrem /yr per pCi/m C, - concentration of the i th noble gas as determined by sample analysis, pCi/cc  ;

C tot - total concentration of noble gases as determined by sample analysis, pC1/cc = I gC, Flow Rate = plant vent flow rate, cfm

= 82,000 cfm/ fan (x no. of fans to be run) 2120 - conversion constant, cfm per m3 /sec l 500 mrem /yr - total body dose rate limit, as specified by i Specification 2.1.1.a '

X/Q =

historical annual average dispgrsion factor for any landwgrd sector, sec/m i

=

4.8E-6 sec/m Skin The concentration at the detector corresponding to a 3000 mrem /yr skin dose rate at the exclusion area boundary is determined by:

(2-2) l 1

r 4

"" ( 3000 mrem /yr) (104 3 (0.38) 2120 m/cc) l m /sec, Cdet =

C l 3 3 (Flow rate, cfm)(X/Q, sec/m ) E3 L3 + 1.1Mg , mrem /yr 3

pCi/m , ,

C:ot j i

l S023-0DCM 9 !

2-12 Revision 24 08-31-91

2.0 GASE0US EFFLUENTS (Continued) 2.6.1 PLANT VENT STACK - 2/3RT-7808, 2RT-7865-1,.3RT-7865-1 l

(Continued) where: l 1

l L, =

sgn Dose Conversion Factor frog Table 2-4 for the I i noble gas, mrem /yr per pCi/m

=

M, ag Dose Conversion Factor from3 Table 2-4 for the l 1 noble gas, mrem /yr per pC1/m 1.1 = conversion factor to convert gamma air dose to l skin dose l 3000 mrem /yr - skin dose rate limit as specified by Specification 2.1.1.a l

I Other values in equation (2-2) are defined in equation (2-1).

I The smaller of the values of C det from equations (2-1) or (2-2) is to be used in the determination of the maximum permissible monitor alarm setpoint (cpm), as follcws:

The maximum permissible alarm setpoint (cpm) is determined using the calibration constant for 2/3RT-7808 given in Table 2-3. The maximum permissible alarm setpoint is the value " cpm" corresponding to the concentration, Cdet(the 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 pCi/cc/ cpm).

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

l

!O V S023-0DCM 2-13 Revision 21 02 15-90

2.0 GASEOUS EFFLURffi (Continud) 2.6.1.2 2RT-7865-1 and 3RT-7865-1 Wide Panae Gas Monitors O I l

The maximum release rate (pC1/sec) for Wide Range Gas Monitors is determined by converting the concentration at the detector, C det (pC1/cc) to an equivalent release rate in pCi/sec, as follows:

(Cdet, pCi/cc)(flowrate, cc/sec) bax" 2 i where:

A ,x = maximum permissible release rate, pCi/sec C det = smaller of the values of C obtained from equations (2-1) or (2-2). det Flow Rate -

flow rate,7cc/sec

= (3.87 x 10 cc/sec per fan) (number of fans) 2- a factor to compensate for the split flow between Unit 2 and Unit 3 plant vent stacks The release rate setpoint will not be set greater than the maximum release rate determined above, when this monitor is being used to meet the requirements of Specification 2.1.1.

5023-0DCM 2-14 Revision 26 12-20-93

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 Eiector Monitors l 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 1 1

dose rate of 500 mrem /yr at the exclusion area boundary is determined by using:

Total Body (2-4)

< 3 (0.1)(0.5) 2120 ( 500 mrem /yr) (104 3 m /cc) ,

Cdet =

' *3l'

(F1ow rate, cfm)(X/Q, sec/m3) Eg K , "I'"I##

g pCi/m 3 ,

[, tot,,

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

Skin (2-4a) r ,

(0.1)(0,5) 2120 ( 3000 mrem /yr) (104 3 m/cc) 3 m /sec, Cdet =

C, '

(Flow rate, cfm) (X/Q, sec/m3) E j L, + 1.lM g, mrem /yr 3

pC1/m , , Ctot,,

!h')

l S023-0DCM 2-15 Revision 26 12-20-93

2.0 GASE0US EFFLUENTS 2.6.2 CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-1, 3RT-7818 l or 3RT-7870-1 (Continued) 0.1 is an administrative value used to account for potential 1 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.

The smaller of the values C det 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 alarm setting (cpm) is determined by using the calibration constant for the corresponding Condenser Evacuation System Monitor given in Table 2-3. The maximum permissible alarm setpoint is the cpm value corresponding to the concentration, Cdet, [ smaller value from 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 in terms of pCi/cc/ cpm). The alarm setpoint will not be set greater than the maximum permissible alarm setting determined above.

S023-0DCM 2-16 Revision 21 02-15-90

l 2.0 GASEOUS EFFLUENTS (Continu:d) i 2.6.2.2 2RT-7870-1 and 3RT-7870-1 Wide Ranae Gas Monitors The maximum release rate (pCi/sec) for Wide Range Gas Monitor is

]

determined by converting the concentration at the detector, C det

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

J i A.,x =

(Cdet, pCi/cc) (flow rate, cc/sec) 1 where:

A,,x = maximum permissible release rate, pCi/sec C det = smaller value of C as obtained from j equations (2-4) r...$,*(,2-4a) j flow rate = flow rate of the condenser air ejector, cc/sec

= 4.719ES cc/sec (conservatively assumed as design flow rate) i i

l I,

i 1

4 1

I s i O S023-0DCM i 2-17 Revision 26 12-20-93

2.0 GASEOUS EFFLUENTS (Centinued) 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865, 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)

'" ( 500 mrem /yr) (104 3 (0.38)(P2 ) 2120 3

m /cc) m/sec' Cdetz "

mre#yr C3 (Flow rate, cfm) (X/Q, sec/m3) E j K ,,

pCi/m, , , Ctot , ,

, , (2-7)

C" 4 3 (0.38)(P3) 2120 ( 500 mrem /yr) (10 m/cc) 3

' m /sec '

Cdet3 "

I (Flow rate, cfm) (X/Q, sec/m3) E 3 Kj , "#**!##

3 pCi/m , s tot,,

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

Skin ,

(2-6a) cfm 4 3 (0.38)(P2) 2120 ( 3000 mrem /yr) (10 m/cc) m /sec, Cdet2 =

I (Flow rate, cfm) (X/Q, sec/m3) E g L 3 + 1.1M j , "#*"!#[

pCi/m , , Ctog,,

5023-0DCM 2-18 Revision 22 08-02-90

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

(2-7a)

• • 4 3 (0.38)(P2) 2120 ( 3000 mrem /yr) (10 m/cc) m /sec, Cdet3 =

3 C, '

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

pC1/m , , Ctot,,

where:

C detz =

instantaneous concentration of the Unit 2 detector,pCi/cc.

C det3 =

instantaneous concentration of the Unit 3 detector,pCi/cc.

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

! P2 and P3 are administrative values used to account for simultaneous purges of both SONGS 2 and SONGS 3. The fractions P2 and P3 will be assigned such that P 2 + P3 5 1.0.

l 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 ,

l

= 3,000 cfm mini-purge (The above values replace the smaller design flowrates.) ,

i Other parameters are as specified in 2.6.1.1 above. The smaller of the values of maximum permissible Cdetz from equation (2-6) or (2-6a) and Cdet3 from equations (2-7) or (2-7a) is to be used in )

determining the maximum permissible monitor alarm setpoints. l l

S023-0DCM 2-19 Revision 28 12-21-95 4

2.0 GASEOUS EFFLUENTS (Continued) 2.6.3 f0NTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865, 3RT-7865 (Continued) 2.6.3.1 Maximum Permissible Alarm Settina (RT-7865)

The maximum permissible alarm setting for the Wide Range Gas Monitor expressed as a maximum release rate (pCi/sec) is determined by converting the concentration at the detector, Cdet (pCi/cc),to an equivalent release rate in pC1/sec.

A,,x = (Cdet, pCi/cc) (flow rate, cc/sec) where:

A ,x = maximum permissible release rate, pCi/cc C

det

= smaller value of C 4 as obtained from equation (2-6, 2-6a) for Unilt,2 or (2-7, 2-7a) for Unit 3.

flow rate = flow rate, cc/sec

= 1.416E6 cc/sec for mini-purge.

= 2.360E7 cc/sec for main purge.

.2 Maximum Permissible Alarm Settina (RT-7828)

The maximum permissible alarm setting for RT-7828 is in pCi/cc and is the smaller of the values of Cdet (pci/cc) from equations (2-6) and (2-6a) for Unit 2 or equations (2-7, 2-7a) for Unit 3.

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

- . _ - - . - . - - . . _ . . . . . - . . - . - . - . - - . - - . . . - . - - - . - - . - - . . ~ .

2.0 GASE0US EFFLUENTS (Centinuid) i 2.6.4 WASTE GAS HEADER - 3RT-7865, 2/3RT-7808  !

-g For the purpose of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the. gaseous effluent l flow rate.and the meteorological dispersion factor. Since the i waste gas header discharges to the plant vent stack, either j 3RT-7865 or 2/3RT-7808 may be used to monitor waste gas header I

releases. '

The concentration at the detector corresponding to a total body l dose rate of 500 mres/yr or a skin dose rate of 3000 mrem /yr at j the exclusion area boundary is determined by using equations ]

(2-1) or (2-2) with sample concentration (C4) and (Ctot) being obtained from the waste gas decay tank to be released.

The smaller of the values of maximum permissible concentration (Cdet) from equation (2-1) or (2-2) is to be used in l determining the maximum permissible monitor alarm setpoint.

h i 2/3RT-7808 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 det, (smaller value from equation (2-1) or (2-2)). ,

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

I 2.0 GASEOUS EFFLUENTS (ContinuId) 1 2.6.4 WASTE GAS HEADER ~3RT-7865, 2/3RT-7808 (Continued) 3RT-7865 The maximum permissible alarm setting is expressed as a maximum release rate (pCi/sec) and is determined by converting the concentration at the detector, Cdet, to an equivalent release rate in pCi/sec by equation (2-8).

pC1/cc) (flowrate, cc/sec) (2-8)

(C det, A,,x =

2 where:

Adet = the maximum permissible release rate, pCi/sec C

det

= the smaller value of C d as obtained from l equation (2-1) or (2-2)et, .

l flowrate = flowrate, cc/sec i

= 7.74E7 cc/sec for 2 fan operation or '

= 3.87E7 cc/sec for 1 fan operation 2 = correction for 3-7865 viewing only 1/2 the total Plant Vent Stack Flow.

.1 A release from the waste gas header is not possible if:

,, (2-9)

(EjjC ) >cdet where:

EjC, = total concentration in waste gas holdup tank to be released f = waste gas header effluent flow rate, cfm F = plant vent stack flowrate in cfm (164,000 cfm for 2 fan operation; 82,000 for 1 fan operation)

C det = smaller of the values of C det from equation (2-1) or (2-2) with C, being obtained from the waste gas holdup tank to be released S023-0DCM 2-22 Revision 24 08-31-91 .

l l

i

2.0 GASE0US EFFLUENTS (Continued) 2.6.4 WASTE GAS HEADER - 3RT-7865, 2/3RT-7808 (Continued) p 2.6.4.1 (Continued)

O If a release is not possible, adjust the waste gas header flow by determining the maximum permissible waste gas header effluent flow rate corresponding to the Vent Stack Monitor I setpoint in accordance with the following:

(' )

(0.9)(Cdet)(F)

ECt 4 j where:

f= waste gas header effluent flow rate (cfm)

F= plant vent stack flow rate (cfm) used in equation (2-1) or (2-2) l Cdet = smaller of the value of C det from equation (2-1) or (2-2)

A IgCi = total gamma activity (pCi/cc) of the waste gas holdup V 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.

l l

I o S023-0DCM 2-23 Revision 24 08-31-91

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S023-0DCM 2-24 Revision 26 12-20-93

1 4

) Table 2-3(a) i Gaseous Effluent Radiation Monitor i

Calibration constants (pCi/cc/ cpm) 1 4

MONITOR Kr-85 Xe-133 l 2/3RT-7808C 4.43E-8 4.81E-8 2RT-7818A 4.27E-8 6.86E-8 i 2RT-7818B 7.31E-5 1.47E-4 i

! 3RT-7818A 3.73E-8 5.12E-8 i' 3RT-7818B 9.31E-5 1.23E-4 1

a i

i 7

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I \

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1 4

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

i gaseous effluent radiation monitors.

1 l

LO S023-0DCM j 2-25 Revision 28

12-21-95 i

2.0 GASE0US EFFLUENTS (Continu:d) 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:

l (2-11)

DTB " Ei K(IIQ)Qi i

1 (2-12)

D, " Ei (l i + I IH i) (I74) Qi 4

where:

D TB = 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 Kg = the total body dose factor due to gamma emissions from Table 2-4 for each identified nogle gas radionuclide, i, in mrem /yr per pC1/m S023-0DCM 2-26 Revision 21 02-15-90

2.0 GASE0US EFFLUENTS (Continued) 2.7.1 FOR NOBLE GASES: (Continued)

'p Lg =

skin dose factor due to the beta emissions from V Table 2-4 for each identified noble ggs radionuclide,1, in mrem /yr per pCi/m M, = air dose factor due to gamma emissions from Table 2-4 for each identified noble ggs radionuclide, i, in mrad /yr per pCi/m (conversion constant of 1.1 mrem / mrad converts air dose to skin dose.)

Q, =

measured or calculated release rate of  !

radionuclide, i, for either continuous or batch j gaseous effluents, in pC1/sec (X/Q) -

Maximum annual average atmospheric dispersion factor for any landward sector or distance at or beyondtheungestrictedareaboundary.

=

4.8E-6 sec/m 2.7.2 FOR ALL RADIOI0 DINES. TRITIUM AND FOR ALL RADI0 ACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN EIGHT DAYS:

(2-13)

Do = Ej 4(PigWg)Qi where:

Do - organ dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, mrem /yr S023-0DCM 2-27 Revision 28 12-21-95 J

2.0 GASEOUS EFFLUENTS (Continu d) 2.7.2 FOR ALL RADIOI0 DINES. TRITIUM AND FOR ALL RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATF_R THAN EIGHT DAYS: (Continued)

Qi

= measured or calculated release rate of radionuclide, i, for either continuous or batch gaseous effluents, pCi/sec P 4g = dose parameter for radionuclide, i, for pathway, k, from Tablg 2-5 for the inhalation pathway in mrem /yr per pCi/m . The dose factors are based on the critical individual organ and the child age group.

Wk = highest calculated annual average dispersion (X/Q) or deposition (D7Q)factorforestimatingthedosetoan individual at or beyond the unrestricted area boundary for pathway k.

3

= (X/Q), 4.8E-6 sec/m for the inhalation pathway. The location is the unrestricted area in the NW sector.

- (D/Q), 4.3E-8 m-2 for the food and ground plane pathways. The location is the unrestricted area in the E sector.

O 2-28 S023-0DCM Revision 27 Ol I 12-21-94

)

2.0 GASEOUS EFFLUENTS (Ccntinued) 2.8 Gaseous Effluent Dose Calculation 2.8.1 DOSE FROM NOBLE GASES IN GASE0US EFFLUENTS The gaseous releases considered in the following dose calculations are described in Section 2.6. The air dose in j unrestricted areas due to noble gases released in gaseous l effluents is calculated using the following expressions:

2.8.1.1 For historical meteoroloav:

D7 = 3.17x10 4 EM j 4 '(K7Q)Q, Dp = 3.17x10-8 Ej N, '(I7Q)Q, where:

Dy = total gamma air dcse from gaseous effluents, mrad Dg- total beta air dose from gaseous effluents, mrad 3.17x10-8 = inverse seconds per year M3= air dose factor due to gamma emissions from Table 2-4 for each identifigd noble gas radionuclide, i, in mrad /yr per pCi/m l

N, = air dose due to beta emissions from Table 2-4 for each identjfied noble gas radionuclide, i, in mrad /yr per pCi/m (X/Q) = 4.8E-6 sec/m3 . The maximum annual average atmospheric dispersion factor for any landward sector or distance at or beyond the unrestricted area boundary.

Q, = amount of noble gas radionuclide, i, released in gaseous effluents, pC1.

O S023-0DCM 2-29 Revision 28 12-21-95

2.0 SASE0US EFFLUENTS (Continu;d) 2.8.1.2 For meteoroloav concurrent with release:

NOTE: Consistent with the methodology provided in Regulatory O

Guide 1.109 and the following equations, RRRGS (Radioactive Release Report Generating System) software is used to perform the actual calculations.

(2-16) 4 D yg = 1.14x10 EM g 3 E(&3 3 (X/Q)je )

(2-17)

Dg = 1.14x10 EN j g E3 ( At3(X/Q)39 )

where:

Dgy

= total gamma air dose from gaseous effluents in sector e, mrad D, = total beta air dose from gaseous effluents in sector 8, mrad 4

1.14x10 = inverse hours / year M, = air dose factor due to gamma emissions from i Table 2-4 for each identified noble ggs radionuclide, i, in mrad /yr per pCi/m N, = air dose factor due to beta errissions from Table 2-4 for each identified noble ggs radionuclide, i, in mrad /yr per pCi/m  !

At 3 =

length of the jth time period over which (X/Q)3, and033 are averaged for gaseous releases in hours i (X/Q)3, = atmospheric dispersion factor for time period At 3 I at exclusion boundary location in landward sectop e determined by concurrent meteorology, sec/m Q,3 = average release rate of radionuclide, i, in l

gaseous effluents during time period, At3 , pCi/sec l

O S023-0DCM 2-30 Revision 28 12-21-95

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I O S023-0DCM 2-31 Revision 26 12-20-93

1 2.0 GASE0US EFFLUENTS (C:ntinued) 2.8.2 DOSE FROM TRITIUM. RADIOI0 DINES AND RADI0 ACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN 8 DAYS IN GASEOUS EFFLUENTS The dose to an individual from tritium, radioiodines and radioactive materials in particulate form with half lives l l

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

l l

2.8.2.1 For historical meteoroloov:

(2-18)

D, = 3.17x10'8 Eg 4 (RikWk hi, where:

D, = total projected dose from gaseous effluents to an individual, mrem 4

3.17x10 = year /second Q, - amount of each radionuclide,1, (tritium, radioiodine, radioactive material in particulate form with half lives greater than eight days),

released in gaseous effluents, pCi ERW kng = sum of all pathways, k, for radionuclide, i, of the R W product, in mrem /yr per pCi/sec. The EgRu value for each radionuclide, i, is given in Ta e 2-6. The value given is the maximum ERgy ki W for all locations and is based on the most restrictive age groups.

Rg

= dose factor for each identified radionuclide, i, for pathway k, (fgr the inhalation pathway in mrem /yr per pCi/m nd for the food and ground plane pathways in m -mrem /yr per pCi/sec), at the controlling location. The Rik's for each controlling location for each age group are given in Tables 2-7 thru 2-16. Data in these tables are derived using the NRC code, PARTS. (See the annual update of revised R changes in the Land Use Cen$ parameters sus provided by based on Corporate Health Physics and Environmental.)

S023-0DCM 2-32 Revision 27 12-21-94

1 2.0 GASEOUS EFFLUENTS (Continued) 2.8.2.1 For historical meteoroloav: (Continued)

Wg -

annual average dispersion (X/Q) or deposition v

j (D7Q) factor for estimating the dose to an individual at the controlling location for pathway k.

(X/Q) for the inhalation pathway in sec/m3 .

The (X7Q) for each controlling location is given in Tables 2-7 thru 2-16.

=

(D/Q) in m-2.f r The the lp.pd (D/Q)andforground plane pathways each controlling

location is given in Tables 2-7 thru 2-16.

2.8.2.2 For meteoroloav concurrent with releases:

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.

i

' , ,. (2-19) 1mn 4

D, = 1.14 x 10 EEE ( At )(Rike)(Wjke) t 3 Q,ds.

ijk <

A where:

4

. U D, = total annual dose from gaseous effluents to an individual in sector e, mrem.

At 3 = length of the j th period over which W3g i Qj

< are averaged for gaseous released, hour, sand Q,3 = average release rate of radionuclide, i, in J

gaseous effluents during time period At3 , pCi/sec i

S023-0DCM 2-33 Revision 28 12-21-95

l 1

2.0 GASE0US EFFLUENTS (Continu;d) 2.8.2.2 For meteoroloav concurrent with releases: (Continued)

Rike = dose factor for each identified radionuclide i, for pathway k for sec mrem /yr per p{i/m}or e (for and for the foodthe andinhalation ground planepathway in pathways in m mrem /yr per pCi/sec) at the controlling location. A listing of R ig for the controlling locations in each landward sector for each group is given in Tables 2-7 thru 2-16. The e is determined by the concurrent meteorology.

Wjke = dispersion (X/Q) or deposition (D/Q) factor for the time period At4 for each pathway k for calculating the dose to an individual at the controlling location in sector e using concurrent meteorological conditions.

- (X/Q) for the inhalation pathway, sec/m 3

= (D/Q) for the food and ground plane pathways, m-2 0

1 l

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S023-0DCM 2-34 Revision 27 12-21-94

1 i

TABLE 2-4 DOSE FACTORS FOR NOBLE GASES Af5 DAUGHTERS **

Total Body Dose Skin Dose Gamma Air Dose Beta Air Dose Factor K Factor L 3 Factor M, Factor N, Radio- (mrem /yr$ (mrem /yr (mrad /yr (mrad /yr 3

Nuclide perpC1/m) per pC1/m3 ) per pCi/m3 ) per pC1/m3 )

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 l 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 9.15E+1 4.76E+2 1.56E+2 1.11E+3 Xe-133m 2.51E+2 9.94E+2 3.27E+2 1.48E+3 l Xe-133 2.94E+2 3.06E+2 3.53E+2 1.05E+3 1 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

)

(G

• • Source: USNRC Reg. Guide 1.109, Table B-1 I

O d S023-0DCM 2-35 Revision 21 02-15-90 l

TABLE 2-5 DOSE PARAMETER a P*

CHILD AGE GROUP CRITICAL ORGAN Inhalation Pathwag Inhalation Pathway Radionuclide (mrent/yr per pCi/m ) Radionuclide (mrem /yr per pCi/m )

H-3 1.1E+3 I -131 1.6E+7 Cr-51 1.7E+4 I -132 1.9E+5 Mn-54 1.6E+6 I -133 3.8E+6 Co-57 5.1E+5 I -134 5.1E+4 Co-58 1.lE+6 I -135 7.9E+5 Co-60 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.lE+5 Ce-141 5.4E+5 Ru-103 6.6E+5 Ce-144 1.2E+7 Te-129m 1.8E+6 O

• Source: USNRC NUREG-0133, Section 5.2.1.1 S023-0DCM 2-36 Revision 23 02-28-91

TABLE 2-6 CONTROLLING LOCATION FACTORS

(

ERW k ik k Radionuclide mrem /yr per pCi/sec Use: ,

H -3 9.62E-4 Q: San Onofre Mobil. Homes Cr-51 3.25E-2 Q: San Onofre Mobil. Homes Mn-54 6.52E+0 Q: San Onofre Mobil. Homes Co-57 1.66E+0 Q: San Onofre Mobil. Homes Co-58 2.33E+0 Q: San Onofre Mobil. Homes Co-60 8.56E+1 Q: San Onofre Mobil. Homes Sr-89 4.34E+1 Q: SC Ranch (No. Res.)

Sr-90 1.82E+3 Q: SC Ranch (No. Res.)

Zr-95 2.90E+0 Q: San Onofre Mobil. Homes Nb-95 6.81E+0 E: Deer Consumer / Hunter Ru-103 1.08E+1 E: Deer Consumer / Hunter Te-129m 5.32E+0 E: Deer Consumer / Hunter Cs-134 3.36E+1 Q: SC Ranch (No. Res.)

Cs-136 6.81E-1 Q: San Onofre Mobil. Homes Cs-137 3.67E+1 Q: San Onofre Mobil. Homes Ba-140 1.56E+0 Q: San Onofre Mobil. Homes Ce-141 5.74E-1 Q: SC Ranch (No. Res.)

Ce-144 1.68E+1 Q: SC Ranch (No. Res.)

I -131 1.19E+1 Q: San Onofre Mobil. Homes I -132 1.45E-1 Q: San Onofre Mobil. Homes I -133 2.82E+0 Q: San Onofre Mobil. Homes

O' I -134 3.94E-2 Q

San Onofre Mobil. Homes I -135 5.94E-1 Q: San Onofre Mobil. Homes UN-ID 3.59E+0 Q: San Onofre Mobil. Homes Footnote: These values to be used in manual calculations are the maximum IRW k ig for k all locations based on the most restrictive age group.

/O S023-00CM 2-37 Revision 25 02-28-92 l

l

TABLE 2-7 DOSE PARAMETER R i FOR SECTOR P Page 1 of 2 Pathway-SurfBeach/LjfeGuard Distance = 0.4 miles X/Q - 1.8E-6 sec/m D/Q - 8.2E-9 m-2 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 1.2E+1 5.1E+1 9.6E+1 '

Cr-51 1.8E+2 3.2E+4 8.4E+2 1.5E+5 1.1E+3 3.5E+5 Mn-54 1.6E+4 9.5E+6 8.0E+4 4.5E+7 1.1E+5 1.1E+8 Co-57 5.3E+3 2.4E+6 2.4E+4 1.1E+7 2.8E+4 2.6E+7 Co-58 1.2E+4 2.6E+6 5.4E+4 1.2E+7 7.1E+4 2.9E+7 Co-60 7.3E+4 1.5E+8 3.5E+5 7.0E+8 4.5E+5 1.6E+9 Sr-89 2.2E+4 1.5E+2 9.7E+4 7.1E+2 1.1E+5 1.6E+3 Sr-90 1.1E+6 4.4E+6 7.5E+6 Zr-95 2.3E+4 1.7E+6 1.1E+5 8.2E+6 1.3E+5 1.9E+7 Nb-95 6.4E+3 9.4E+5 3.0E+4 4.5E+6 3.8E+4 1.0E+7 Ru-103 6.9E+3 7.5E+5 3.2E+4 3.6E+6 3.8E+4 8.3E+6 Te-129m 1.8E+4 1.4E+5 8.0E+4 6.4E+5 8.8E+4 1.5E+6 Cs-134 1.1E+4 4.7E+7 4.5E+4 2.2E+8 6.5E+4 5.2E+8 Cs-136 1.8E+3 1.0E+6 7.8E+3 4.9E+6 1.1E+4 1.1E+7 Cs-137 9.4E+3 7.1E+7 3.4E+4 3.4E+8 4.7E+4 7.8E+8 Ba-140 1.8E+4 1.4E+5 8.2E+4 6.7E+5 9.7E+4 1.6E+6 Ce-141 5.7E+3 9.4E+4 2.5E+4 4.5E+5 2.8E+4 1.0E+6 Ce-144 1.2E+5 4.8E+5 5.4E+5 2.3E+6 5.9E+5 5.3E+6 I -131 1.7E+5 1.2E+5 5.9E+5 5.6E+5 9.1E+5 1.3E+6 I -132 2.0E+3 8.5E+3 6.1E+3 4.1E+4 8.7E+3 9.4E+4 I -133 4.0E+4 1.7E+4 1.2E+5 8.0E+4 1.6E+5 1.9E+5 I -134 5.3E+2 3.1E+3 1.6E+3 1.5E+4 2.3E+3 3.4E+4 I -135 <0- 8.2E+3 1.7E+4 2.5E+4 8.2E+4 3.4E+4 1.9E+5 UN-ID 1.0E+4 5.1E+6 5.0E+4 2.4E+7 6.6E+4 5.7E+7 l

l Inhalation Pathway, units ""**(!"

Food & Ground Pathway, units I* I" "

C /sec S023-0DCH 2-38 Revision 26 12-20-93

TABLE 2-7 DOSE PARAMETER Rg FOR SECTOR P '

p Page 2 of 2

'd ' Pathway = Cotton Point Estates with Garden Distance = 2.8 miles I

3 X/Q = 1.2E-7 sec/m D/Q = 3.4E-10 m-2 Infant Child Teen Adult 1 Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion Greund 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 3.8E+5 3.4E+8 5.1E+5 5.8E+8 5.9E+5 6.6E+8 3.7E+5 6.2E+8

)

Co-58 7.8E+5 3.8E+8 1.1E+6 7.4E+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  !

Sr-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 Sr-90 4.'E+7 1.0E+8 1.4E+12 1.1E+8 8.2E+11 9.9E+7 6.6E+11 1 Zr-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 7.5E+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-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 5.3E+8 3.6E+5 4.9E+8 b} 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 1 -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 3.6E+6 2.4E+6 3.8E+6 6.9E+8 2.9E+6 3.9E+8 2.2E+6 4.5E+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 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 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 mre r Inhalation Pathway, units 3

/m Food & Ground Pathway, units = I" jse i

O S023-0DCM i 2-39 Revision 28 12-21-95

TABLE 2-8 DOSE PARAMETER R $ FOR SECTOR Q Page 1 of 10 Pathway =51AreaBeacgTrailers Distance = 1.1 miles X/Q = 9.3E-7 sec/m D/Q = 4.6E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tien Ground tion Ground tion Ground tion Ground i 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 Co-57 1.8E+5 1.7E+8 Co-58 4.6E+5 1.9E+8 Co-60 3.0E+6 1.1E+10 Sr-89 7.0E+5 1.1E+4 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 Cs-136 7.3E+4 7.5E+7 Cs-137 3.1E+5 5.1E+9 Ba-140 6.4E+5 1.0E+7 Ce-141 1.8E+5 6.8E+6 Ce-144 3.9E+6 3.5E+7 1 -131 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 i UN-ID 4.3E+5 3.7E+8 Inhalation Pathway, units = [j"(!"

I* II*"'*#yr)

Food & Ground Pathway, units p j ec S023-0DCM 2-40 Revision 27 12-21-94

_ ._ .____- _ ___ --- ~ __

TABLE 2-8 DOSE PARAMETER R $ FOR SECTOR Q

]

Page 2 of 10  ;

f Pathway-SanOnofreMgbileHomes Distance - 1.3 miles I X/Q = 7.4E-7 sec/m D/Q = 3.6E-9 m-2 Infant Child Teen Adult 1

Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & i 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 1.4E49 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-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 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 l Sr-90 4.lE+7 -G- 1.0E+8 1.1E+8 9.9E+7 1 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 I 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 l

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 l Cs-136 1.3E+5 1.5E+8 1.7E+5 1.5E+6 1.9E+5 1.5E+8 1.5E+5 1.5E+8 l 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 2.1E+7 1.7E46 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.lE+7 p Ce-141 Ce-144 5.2E+5 9.8E+6 1.4E+7 7.0E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 v I -131 1.5E+7 1.7E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+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 1.5E45 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 i

i i i

Inhalation Pathway, units - 5" Food & Ground Pathway, units - (m ifmrem/vr) p S023-0DCM 2-41 Revision 27 12-21-94

TABLE 2-8 DOSE PARAMETER R$ FOR SECTOR Q Page 3 of 10 Pathway =StatePark0{ficeTrailer Distance = 0.6 miles X/Q = 2.2E-6 sec/m D/Q = 1.2E-8 m-2 ,

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 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 l Co-60 2.7E+5 9.8E+8 Sr-89 6.4E+4 9.9E+2 Sr-90 4.5E+6 l 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 Cs-136 6.7E+3 6.9E+6 i 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 4 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' I -134 1.4E+3 2.1E+4 j I -135 2.GE+4 1.2E+5 I UN-ID -G- 3.9E+4 3.4E+7

]

l l " "

Inhalation Pathway, units = "C /  !

1 Food & Ground Pathway, units = I" "

C se i S023-0DCM 2-42 Revision 27 12-21-94 l l

l

- - - - _ ____ - _______ ___________________________- ___________________________________ __________________ _ ______________ - _ - L

l TABLE 2-8 DOSE PARAMETER R, FOR SECTOR Q 4

Page 4 of 10 2

Pathway-Surf. Beach /GyardShack' Distance = 0.7 miles 3 X/Q = 1.8E-06 sec/m D/Q = 9.9E-09 m-2 l Infant Child Teen Adult Inhala- Food & Inhala- l Food & Inhala- Food & Inhala- Food &

l Radio- tion Ground tion Ground tion Ground tion Ground

Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.2E+1 5.1E+1 2.2E+2 1 i Cr-51 1.8E+2 3.2E+4 8.4E+2 1.5E+5 2.5E+3 8.0E+5 Mn-54 1.6E+4 9.5E+6 8.0E+4 4.5E+7 2.4E+5 2.4E+8 li Co-57 5.3E+3 2.4E+6 2.4E+4 1.1E+7 6.3E+4 5.9E+7 Co-58 1.2E+4 2.6E+6 5.4E+4 1.2E+7 1.6E+5 6.5E+7 i Co-60 7.3E+4 1.5E+8 3.5E+5 7.0E+8 1.0E+6 3.7E+9 Sr-89 2.2E+4 1.5E+2 9.7E+4 7.1E+2 2.4E+5 3.7E+3 Sr-90 1.1E+6 4.4E+6 1.7E+7 Zr-95 2.3E+4 1.7E+6 1.1E+5 8.2E+6 3.0E+5 4.3E+7 Nb-95 6.4E+3 9.4E+5 3.0E+4 4.5E+6 8.6E+4 2.3E+7 Ru-103 6.9E+3 7.5E+5 3.2E+4 3.6E+6 8.6E+4 1.9E+7 Te-129m 1.8E+4 1.4E+5 8.0E+4 6.4E+5 2.0E+5 3.4E+6 Cs-134 1.1E+4 4.7E+7 4.5E+4 2.2E+8 1.5E+5 1.2E+9 Cs-136 1.8E+3 1.0E+6 7.8E+3 4.9E+6 2.5E+4 2.6E+7 Cs-137 9.4E+3 7.1E+7 3.4E+4 3.4E+8 1.1E+5 1.8E+9 Ba-140 1.8E+4 1.4E+5 8.2E+4 6.7E+5 2.2E+5 3.5E+6 s Ce-141 5.7E+3 9.4E+4 2.5E+4 4.5E+5 6.2E+4 2.3E+6 Co-144 1.2E+5 4.8E+5 5.4E+5 2.3E+6 1.3E+6 1.2E+7 I -131 1.7E+5 1.2E+5- 5.9E+5 5.6E+5 2.0E+6 2.9E+6 I -132 2.0E+3 8.5E+3 6.1E+3 4.1E+4 2.0E+4 2.1E+5 I -133 4.0E+4 1.7E+4 1.2E+5 8.0E+4 3.7E+5 4.2E+5 I -134 5.3E+2 3.1E+3 1.6E+3 1.5E+4 5.1E+3 7.7E+4 I -135 8.2E+3 1.7E+4 2.5E+4 8.2E+4 7.7E+4 4.3E+5 UN-ID 1.0E+4 5.1E+6 5.0E+4 2.4E+7 1.5E+5 1.3E+8 I

l Inhalation Pathway, units = 5" 1

Food & Ground PatFway, units = I" C se O 2-43 S023-0DCM Revision 26 l

i 12-20-93

TABLE 2-8 DOSE PARAMETER R i FOR SECTOR Q Page 5 of 10 Pathway-51AreaBeachfCampground Distance = 1.1 miles X/Q = 9.3E-07 sec/m D/Q = 4.6E-09 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhal a- Food & Inhala- l Food &

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway 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 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 '..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 Sr-89 2.5E+05 2.7E+03 2.7E+0b 2.7E+03 3.0E+05 2.7E+03 1.7E+05 2.7E+03 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.lE+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 1 -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 Inhalation Pathway, units = "C Food & Ground Pathway, units = I* I "'m/vr) fs S023-0DCM 2-44 Revision 27 12-21-94

TABLE 2-8 DOSE PARAMETER R, FOR SECTOR Q Page 6 of 10 Q

U Pathway =51AreaBeacgCheck-In X/Q = 6.8E-7 sec/m Distance = 1.4 miles D/Q = 3.2E-9 m-2 Infant Child Teen Adult l l

Inhala- Food & Inhal a- 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 3.2E+2 l Cr-51 3.7E+3 1.2E+6 '

Mn-54 3.6E+5 3.6E+8 Co-57 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 l Zr-95 4.5E+5 6.5E+7  ;

Nb-95 1.3E+5 3.5E+7 l Ru-103 1.3E+5 2.8E+7  :

Te-129m 3.0E+5 5.lE+6 l Cs-134 2.2E+5 1.8E+9  !

Cs-136 3.8E+4 3.9E+7 Cs-137 1.6E+5 2.6E+9

)

Ba-140 3.3E+5 5.3E+6 Ce-141 9.3E+4 3.5E+6

') Ce-144 I -131 2.0E+6 3.lE+6 1.8E+7 4.4E+6  ;

I -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-ID 2.2E+5 1.9E+8 Inhalation Pathway, units = "C Food & Ground Pathway, units = I* II" **#yr) p ec O_ S023-0DCM 2-45 Revision 27 12-21-94

TABLE 2-8 DOSE PARAMETER R $ FOR SECTOR Q Page 7 of 10 Pathway-Sheep (Meat)fShepherd Distance = 1.6 miles X/Q = 5.6E-7 sec/m D/Q = 2.6E-9 m-2 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 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 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 Sr-89 5.0E+4 2.6E+4 7.7E+3 3.1E+4 Sr-90 1.0E+6 8.lE+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.lE+5 9.7E+3 1.6E+6 Hb-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.lE+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 1.5E+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 I -132 6.3E+2 6.8E+3 I -133 1.6E-2 8.7E-3 1-?f+4 1.3E+4 I -134 ]&: :, 2.5E+3 I -135 1.1E-18 6.4E-19 74 4 ) 1.4E+4 UN-ID 1.1E+5 9.5E+4  ?,0t +3

}4.2E+6 i

Inhalation Pathway, units = *C I* II""*m/vr)

Food & Ground Pathway, units p s S023-0DCM 2-46 Revision 26 12-20-93

TABLE 2-8 D0SE PARAMETER R, FOR SECTOR Q l Page 8 of 10 Pathway-S.C.ResWgarden Distance - 4.4 miles j X/Q = 1.lE-7 sec/m D/Q = 3.5E-10 m-2 j Infant Child Teen Adult Inhal a- Food & Inhala- Food & Inhala- Food & Inhala- Food &

. Radio- tion Ground tion Ground tion Ground tion Ground 4

Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway

H -3 6.5E+2 1.lE+3 4.0E+3 1.3E+3 2.6E+3 1.3E+3 2.2E+3 i 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 3

Co-57 3.8E+5 3.4E+8 5.1E+5 5.8E+8 5.9E+5 6.6E+8 3.7E+5 6.2E+8

{ Co-58 7.8E+5 3.8E+8 1.1E+6 7.4E+8 1.3E+6 9.5E+8 9.3E+5 9.6E+8 i 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 I 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 l Sr-90 4.lE+7 1.0E+8 1.4E+12 1.lE+8 8.2E+11 9.9E+7 6.6E+11 I Zr-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 7.5E+5 5.7E+8 5.0E+5 5.8E+8 l Ru-103 5.5E+5 1.lE+8 6.6E+5 4.9E+8 7.8E+5 6.6E+8 5.0E+5 6.3E+8 j 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 i 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.lE+5 3.5E+10 8.5E+5 2.4E+10 6.2E+5 1.9E+10 i 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 i 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 l 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 l

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  !

l 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 j- 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 ,

UN-ID 6.5E+5 7.5E+8 1.0E+6 3.4E+9 1.2E+6 2.6E+9 8.SE+5 2.0E+9 l Inhalation Pathway, units - 5" Food & Ground Pathway, units I" ' "

se O

S023-0DCM 2-47 Revision 28 12-21-95

l TABLE 2-8 DOSE PARAMETER Ri FOR SECTOR Q Page 9 of 10 Pathway - San Clemente Ranch (No Residents) Distance = 2.2 miles 3

X/Q = 3.3E-7 sec/m D/Q = 1.4E-9 m'2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathw.;y 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 Co-57 -Oi 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 i Sr-89 3.1E+10 1.2E+10 7.2E+9 I Sr-90 1.3E+12 7.7E+11 5.8E+11 1 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 l

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 i Ba-140 1.1E+8 6.8E+7 5.3E+7  !

Ce-141 3.3E+8 4.1E+8 3.2E+8 l Ce-144 9.2E+9 1.2E+10 9.0E+9 l I -131 4.1E+9 2.1E+9 1.4E+9 l I -132 6.0E-36 2.6E-36 1.7E-36 l 1 -133 4.0E-11 1.7E-11 1.1E-11 1 -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 l

l Inhalation Pathway, units "C Food & Ground Pathway, units I* " "

C /sec O

S023-0DCM 2-48 Revision 23 02-28-91

TABLE 2-8 D0SE PARAMETER Ri FOR SECTOR Q Page 10 of 10 0- Pathway - San Clemente Ranch Adm. Offices X/Q = 2.7E-7 sec/m 3

Distance = 2.5 miles D/Q = 1.1E-9 m'2 Infant Child Teen Adult l

Inhala- Food & Inhal a- - 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 4.3E+02 1.9E+03 Cr-51 4.9E+03 8.3E+06  :

Mn-54 4.8E+05 1.3E+09 J Co-57 1.3E+05 3.6E+08 Co-58 3.2E+05 6.0E+08 i Co-60 2.0E+06 1.0E+10 Sr-89 - 4.8E+05 7.2E+09 i Sr-90 3.4E+07 5.8E+11 Zr-95 -1 6.1E+05 9.9E+08 Nb-95 1.7E+05 3.6E+08  ;

Ru-103 1.7E+05 4.2E+08 Te-129m 4.0E+05 9.6E+08 Cs-134 2.9E+05 1.2E+10 Cs-136 5.0E+04 8.7E+07 Cs-137 2.lE+05 1.1E+10  ;

Ba-140 4.4E+05 6.0E+07 Ce-141 1.2E+05. 3.2E+08 Ce-144 2.7E+06 9.0E+09 I -131 4.1E+06 1.4E+09 1 I -132 3.9E+04 4.2E+05 i I -133 7.4E+05 8.4E+05 I -134 1.0E+04 1.5E+05 1 -135 1.5E+05 8.6E+05 ,

UN-ID 3.0E+05 1.3E+09 l i

i

)

Inhalation Pathway, units = ,5#

I*

Food & Ground Pathway, units p sec l

S023-0DCM  ;

2-49 Revision 26 )

12-20-93 1

l TABLE 2-9 l DOSE PARAMETER R$ FOR SECTOR R Page 1 of 5 Pathway-SanOnofreNgbileHomes X/Q = 5.3E-7 sec/m Distance - 1.2 miles D/Q = 3.2E-9 m-2 g

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 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 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-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 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 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 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 2.1E+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 g 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 y 1 -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 Inhalation Pathway, units = j!"

l

"'*/yr)

Food & Ground Pathway, units = I* I j ec l

S023-0DCM 2-50 Revision 23 02-28-91

TABLE 2-9 DOSE PARAMETER R, FOR SECTOR R Page 2 of 5 I'l Pathway = San Clemente3 Ranch (No Residents) Distance = 2.3 miles l

\- /

X/Q = 2.0E-7 sec/m D/Q = 1.0E-9 m-2 Infant Child Teen Adult i 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 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 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.SE+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  !

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.lE+8 6.8E+7 5.3E+7  !

Ce-141 3.3E+8 4.lE+8 3.2E+8 l O- Ce-144 I -131 9.2E+9 4.lE+9 1.2E+10 9.0E+9  ;

2.1E+9 1.4E+9 I -132 6.0E-36 2.6E-36 1.7E-36 i I -133 4.0E-11 1.7E-11 1.1E-11 I -134 6.lE-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.lE+9 i Inhalation Pathway, units = "**(5" I" I " "/yr)

Food & Ground Pathway, units C /sec S023-0DCM 2-51 Revision 23 02-28-91 i

TABLE 2-9 DOSE PARAMETER Rg FOR SECTOR R Page 3 of 5 Pathway-SCRanchPackjngwithResidents Distance - 2.6 miles X/Q - 1.7E-07 sec/m D/Q = 8.2E-10 m-2 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 4.6E+2 1.9E+3 Cr-51 5.3E+3 0.5E+6 Mn-54 5.1E+5 1.3E+9 Co-57 1.4E+5 3.7E+8 Co-58 3.4E+5 6.1E+8 Co-60 2.2E+6 1.1E+10 Sr-89 5.1E+5 7.2E+9 Sr-90 3.6E+7 5.8E+11 Zr-95 6.5E+5 1.0E+9 Nb-95 1.9E+5 3.6E+8 Ru-103 1.9E+5 4.2E+8 Te-129m 4.3E+5 9.6E+8 Cs-134 3.1E+5 1.2E+10 Cs-136 5.4E+4 9.1E+7 Cs-137 2.3E+5 1.2E+10 Ba-140 4.7E+5 6.1E+7 i Ce-141 1.3E+5 3.2E+8 '

Ce-144 2.9E+6 9.0E+9 l 1 -131 4.4E+6 1.4E+9 l I -132 4.2E+4 4.6E+5 l I -133 7.9E+5 9.0E+5 I -134 1.1E+4 1.7E+5 I -135 1.6E+5 9.3E+5 UN-ID 3.2E+5 1.3E+9 l

l l

Inhalation Pathway, units = "C I* I **#yr)

Food & Ground Pathway, units ec S023-0DCM 2-52 Revision 27 12-21-94

TABLE 2-9 l DOSE PARAMETER R i FOR SECTOR R Page 4 of 5 '

I' Distance = 0.9 miles Pathway =SheepHeat/Sgepherd X/Q = 8.3E-7 sec/m D/Q = 5.2E-9 m-2 Infant Child Teen Adult i

Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & l 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 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 l 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 ;

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 5.1E+3 4.3E+3 7.0E+3 1.2E+5 r% Ce-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 y) 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 I -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 = 5" Food & Ground Pathway, units I" * "

sec  !

l 4

) S023-0DCM 2-53 Revision 26 12-20-93

TABLE 2-9 DOSE PARAMETER R, FOR SECTOR R Page 5 of 5 Pathway =DeerConsumep/ Hunter X/Q = 1.8E-7 sec/m Distance = 2.2 miles &

y D/Q = 8.8E-10 m-2 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 l 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 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 l Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 i 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 l 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 = "C Food & Ground Pathway, units = I" * "}

sec S023-0DCM 2-54 Revision 26 12-20-93

TABLE 2-10 l DOSE PARAMETER R i FOR SECTOR A Page 1 of 3 O Pathway =CampSanMatgo Distance = 3.6 miles X/Q = 7.1E-8 sec/m D/Q = 4.1E-10 m-2 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 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 ,

C0-57 3.7E+5 3.4E+8 l i Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 l

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 Cs-136 1.5E+5 1.5E+8 l Cs-137 6.2E+5 1.0E+10 l

, 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 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 a

1

)

InhalationPathway, units =}{## ,5 Food & Ground Pathway, units = I"

/sec c)

\ 5023-0DCM 2-55 Revision 23 02-28-91

TABLE 2-10 DOSE PARAMETER R, FOR SECTOR A Page 2 of 3 Pathway = Sheep (Meat)fShepherd Distance = 0.2 miles X/Q = 6.7E-6 sec/m D/Q = 5.2E-8 m-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 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 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 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 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 I -132 6.3E+2 6.8E+3 I -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 I -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 InhalationPathway, units =""*j"(5" Food & Ground Pathway, units p ym/vr)

I* IIj"*s S023-0DCM 2-56 Revision 26 12-20-93

1

. TABLE 2-10 i

i DOSE PARAMETER R, FOR SECTOR A j Page 3 of 3 i( ) Pathway =DeerConsumep/ Hunter X/Q = 1.9E-7 sec/m Distance = 2.2 miles D/Q = 1.4E-9 m-2 f Infant Child Teen Adult I Inhala- Food & Inhala- Food & 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 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 j 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 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 i 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 4.0t+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 i Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 l~ 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 1 -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 i UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 '

I.

i i

Inhalation Pathway, units ""'*(5" I" I"" "

Food & Ground Pathway, units C /sec i -

S023-0DCM 2-57 Revision 26 12-20-93 i

d r - - - , - --

TABLE 2-11 DOSE PARAMETER R i FOR SECTOR B Page 1 of 3 Pathway-Sheep (Meat)fShepherd X/Q = 6.1E-6 sec/m Distance = 0.2 miles D/Q = 5.3E-8 m-2 g

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 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 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 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 8.3E45 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 I -132 6.3E+2 6.8E+3 I -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 I -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 = j(5" Food & Ground Pathway, units I* I "'m/vr) js S023-0DCM 2-58 Revision 26 12-20-93

_ . - . . - . . - . . - . - - . - - - . - . - - ~ - . - . _ - _ _ . - . . _-

TA8LE 2-11 i DOSE PARAMETER R i FOR SECTOR 8

).

Page 2 of 3 3

Pathway - Deer Consumep/ Hunter Distance - 1.1 miles

] X/Q = 3.4E-7 sec/m D/Q = 2.4E-9 m-2 ,

l Infant Child Teen Adult

'l i 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 i

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 i 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 i 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 l Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 ,

i 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 i 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 ,

8a-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 i Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 i

( 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 l UN-ID =0- 1.1E+8 9.4E+7 2.4E+4 1.4E+8 i

I t

i i

l Inhalation Pathway, units = ""'"(5" 4 Food & Ground Pathway, units = I" I *"

C /sec j

S023-0DCM 2-59 Revision 26

12-20-93 8

l TABLE 2-11 ,

1 l DOSE PARAMETER R, FOR SECTOR B Page 3 of 3 Pathway-SanitaryLangfill Distance = 2.1 miles X/Q = 1.4E-7 sec/m D/Q = 1.2E-9 m-2 Infant Child Teen Adult 1

Inhala- Inhala- Inhala-Food & Food & Food & Inhala- Food &

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway i 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 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 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 l Ce-141 8.3E+4 3.1E+6 Ce-144 1.8E+6 1.6E+7 l I -131 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 1.0E+5 5.8E+5 UN-ID 2.0E+5 1.7E+8 Inhalation Pathway, units = "C /

Food & Ground Pathway, units = I" #' "

fsec S023-0DCM 2-60 Revision 23 02-28-91

} TABLE 2-12 4

j DOSE PARAMETER R i FOR SECTOR C Page 1 of 5 I

! Pathway =CampSanOno{re Distance = 2.6 miles  !

X/Q = 9.2E-8 sec/m D/Q = 8.4E-10 m-2 Infant Child Teen Adult i

Inhala-i 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 e

i H -3 1.3E+3 -

Cr-51 1.4E+4 4.7E+6 l Mn-54 1.4E+6 1.4E+9 i

Co-57 3.7E+5 3.4E+8 t l Co-58 9.3E+5 3.8E+8 i

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 l Cs-134 8.5E+5 6.8E+9 i Cs-136 1.5E+5 1.5E+8

! Cs-137 6.2E+5 1.0E+10 i Ba-140 1.3E+6 2.1E+7

Ce-141 3.6E+5 1.4E+7

!s Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 j I -132 1.lE+5 1.2E+6 4

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 i

t' J

i Inhalation Pathway, units = "C 2

Food & Ground Pathway, units - (m )(mrem /vri

pCi/sec S023-0DCM 2-61 Revision 23 02-28-91

1 TABLE 2-12 DOSE PARAMETER R$ FOR SECTOR C Page 2 of 5 Pathway-CampSanOno{reFr.Stn X/Q = 1.1E-7 sec/m Distance - 2.3 miles D/Q = 1.1E-9 m-2 gI 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 5.2E+2 Cr-51 5.9E+3 1.9E+6 Hn-54 5.8E+5 5.7E+8 l Co-57 1.5E+5 1.4E+8 Co-58 3.8E+5 1.6E+8 Co-60 2.5E+6 8.8E+9 Sr-89 5.8E+5 8.9E+3 Sr-90 4.1E+7 Zr-95 -G- 7.3E+5 1.0E+8 Nb-95 2.1E+5 5.6E+7 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 6.0E+4 6.2E+7 Cs-137 2.6E+5 4.2E+9 Ba-140 5.2E+5 8.4E+6 Ce-141 1.5E+5 5.6E+6 Ce-144 3.2E+6 2.9E+7 I -131 4.9E+6 7.1E+6 I -132 4.7E+4 5.1E+5 1 -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 l

1 1

Inhalation Pathway, units mrem yr Food & Ground Pathway, units I* I" "}

C /sec S023-0DCM 2-62 Revision 23 02-28-91

- - _ _ _ _ _ _ _ _ _ _ - _ - _ _ - _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _l

. . . . - . . - . - - . . - . . - _ . . - . . . _ _ _ . . = - . . . _ _ . - - . - . - . - - . _ - -

l l

1 TABLE 2-12 i

DOSE PARAMETER Ri FOR SECTOR C 1

Page 3 of 5 lO

'V Pathway-SewageFaciljty X/Q = 1.2E-7 sec/m

-Distance = 2.2 miles D/Q = 1.2E-9 m-2 l l

Infant Child Teen Adult I

. 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 i 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 1 Co-58 2.1 E+5 8.7E+7 i Co-60 1.4E+6 4.9E+9 i Sr-89 3.2E+5 4.9E+3 Sr-90 2.3E+7 i Zr-95 4.0E+5 5.7E+7 Nb-95 1.2E+5 3.1E+7

{ Ru-103 1.2E+5 2.5E+7

, Te-129m 2.6E+5 4.5E+6 i 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 i Ce-141 8.3E+4 3.1E+6 i 4 Ce-144 1.8E+6 1.6E+7 I -131 -

l 2.7E+6 3.9E+6 i

I -132 2.6E+4 2.8E+5 I -133 4.9E+5 5.6E+5 i I -134 6.8E+3 1.0E+5 l 1 -135 1.0E+5 5.8E+5

, UN-ID 2.0E+5 1.7E+8 1

i l InhalationPathway, units =[f,5#

I" "

Food & Ground Pathway, units C sec a

i S023-0DCM 2-63 Revision 23 02-28-91

i TABLE 2-12 DOSE PARAMETER R i FOR SECTOR C Page 4 of 5 Pathway = Sheep (Meat)fShepherd X/Q = 6.5E-6 sec/m Distance = 0.2 miles D/Q = 6.1E-8 m-2 g

Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & l Radio- tion tion Ground 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 l 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 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 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 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 I -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-10 1.1E+5 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units = 5' I* "

Food & Ground Pathway, units C se S023-0DCM 2-64 Revision 26 12-20-93

TABLE 2-12 DOSE PARAMETER R$ FOR SECTOR C f~'

x Pathway-DeerConsumep/ Hunter Distance = 1.0 miles 4

X/Q = 3.4E-7 sec/m D/Q = 5.lE-9 m-2 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 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 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 s' 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 = 5" Food & Ground Pathway, units = I" C /sec S023-0DCM 2-65 Revision 26 12-20-93

TABLE 2-13 DOSE PARAMETER R $

FOR SECTOR D Page 1 of 3 Pathway-CampSanOnofre Distance = 2.8 miles X/Q = 6.6E-8 sec/m D/Q = 6.4E-10 m-2 l

Infant Child Teen Adult i 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 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 i 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 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 i Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I 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 I

UN-ID <0- 8.6E+5 7.5E+8 l l

I m

Inhalation Pathway, units = j(yr I" ' "

Food & Ground Pathway, units sec S023-00CM 2-66 Revision 23 02-28-91

TABLE 2-13 DOSE PARAMETER R, FOR SECTOR D Page 2 of 3 Pathway-Sheep (Meat)fShepherd Distance - 0.2 miles X/Q = 6.3E-6 sec/m D/Q = 6.6E-8 m-2 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 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 Co-57 4.7E+3 8.1E+3 2.0E+3 1.9E+6 Co-58 9.7FA' 2.0E+4 5.1E+3 2.1E+6 Co-60 ..ic+4 7.3E+4 3.3E+4 1.2E+8 Sr-89 5.0E+4 2.6E+4 7.7E+3 3.lE+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 7.6t+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 5.1E+3 4.3E+3 7.0E+3 1.2E+5 T 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 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 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 = "I'"# ,5 "

Food &GroundPathway, units =I"IyI*"'m/vr) p js O S023-0DCM 2-67 Revision 20 12-20-93

TABLE 2-13 DOSE PARAMETER Rg FOR SECTOR D Page 3 of 3 Distance = 1.0 miles Pathway-DeerConsumep/ Hunter X/Q = 3.3E-7 sec/m D/Q = 3.3E-9 m-2 llll 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 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 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.lE+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 Cs-134 1.4E+8 1.2F+8 2.3E+4 3.4E+8 Cs-136 5.1E+6 4.EE+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.lE+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.lE-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.lE+8 9.4E+7 2.4E+4 1.4E+8 l

l Inhalation Pathway, units = *C l

I Food & Ground Pathway, units I* II*Ff;*#vr) p y j ec l

S023-0DCM Ol 1 2-68 Revision 26 12-20-93 l

l

TABLE 2-14 DOSE PARAMETER R, FOR SECTOR E Page 1 of 3 f') Pathway - Camp Horno l

V 3 Distance - 4.0 miles X/Q - 6.6E-8 sec/m D/Q - 6.4E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala-Radio- tion Food &

Ground tion Ground tion Ground tiou 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 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.lE+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 1.3E+6 2.lE+7 Ce-141 O Ce-144 I -131 3.6E+5 7.8E+6 1.2E+7 1.4E+7 7.0E+7 1.7E+7 I -132 1.lE+5 1.2E+6 1 -133 2.2E+6 2.4E+6 1 -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 1

1 I

Inhalation Pathway, units - 5" 2

Food & Ground Pathway, units = (m H mrem /vri >

pC1/sec I i

S023-0DCM 2-69 Revision 23

! 02-28-91

TABLE 2-14 DOSE PARAMETER R, FOR SECTOR E Page 2 of 3 l Pathway = Sheep (Meat)fshepherd Distance = ).3 miles  !

X/Q = 4.5E-6 sec/m D/Q = J .9E-8 m-2 l l

Infant Child Teen Adult

- \

Inhala- Food & Inhala- Food & Inhala- Food & :nhala- Food &

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pati.w , 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 Co-57 4.7E+3 8.lE+3 2.0E+3 1.9E+6 Co-58 9.7E+3 2.0E+4 5.lE+3 2.lE+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.lE+4 Sr-90 1.0E+6 8.lE+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.lE+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 6.0Et5 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.lE+3 4.3E+3 8.lE+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.lE+3 4.3E+3 7.0E+3 1.2E+5 Ce-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 4.3E+5 W

Ce-144 1.8E+4 3.0E+4 4.3E+4 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 I -134 1.6E+2 2.5E+3 I -135 1.lE-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 = ]j*#5" I* II*"'"/yr)

Food & Ground Pathway, units j ec S023-0DCH 2-70 Revision 26 12-20-93

I .

TABLE 2-14 j l

DOSE PARAMETER R, FOR SECTOR E '

Page 3 of 3 O- Pathway-DeerConsumep/ Hunter X/Q - 3.7E-7 sec/m Distance - 1.2 miles D/Q - 8.3E-9 m-2 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 ,

l 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.lE+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 l 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 l Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 l Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.lE+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 C Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6

( Ce-144 1.8E+7 2.9E+7 2.lE+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.lE+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 = j(5" Food & Ground Pathway, units = I" * "

se i

A I I

I S023-0DCM 2-71 Revision 26 j 12-20-93

TABLE 2-15 DOSE PARAMETER R i FOR SECTOR F Page 1 of 4 Pathway = San Onofre S} ate Park / Guard Shack Distance - 0.8 miles X/Q - 8.6E-7 sec/m D/Q = 7.5E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Fooc & Inhala- Food & Inhal a- Food &

Radio- tion Ground tion Grouad tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathuay Pathway Pathway Pathway Pathway H -3 - fe - 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 C0-58 -G- 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 3.0E+5 Zr-95 4.3E+7 Nb-95 8.6E+4 2.3E+7 Ru-103 8.6E+4 1.9E+7 Te-129m -C- 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.lE+5 I -133 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 l

1 l

1 Inhalation Pathway, units = "C m

Food & Ground Pathway, units = I" pyIIjs j /vr)

S023-0DCM 2-72 Revision 25 02-28-92 1

l

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

( Pathway =BorderPatro}Checkpt. Distance = 1.8 miles X/Q = 2.4E-7 sec/m D/Q = 1.8E-9 m-2 Infant Child Teen Adul t l

l Inhala- Food & Inhala- Food & 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 Cr-51 4.1E+3 1.3E+6 Ma 54 4.0E+5 3.9E+8 Co-57 1.lE+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.lE+7 Te-129m 3.3E45 5.6E+6 Cs-134 2.4E+5 1.9E+9 Cs-136 4.2E+4 4.3E+7 Cs-137 1.8E+5 2.9E+9 Ba-140 3.6E+5 5.9E+6

'p Ce-141 1.0E+5 3.9E+6 y Ce-144 I -131 2.2E+6 3.4E+6 2.0E+7 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-ID 2.5E+5 2.lE+8 InhalationPathway, units =]j"(5" food & Ground Pathway, units = I" "**#VII f3,c

's S023-0DCM 2-73 Revision 23 02-28-91

l l

TABLE 2-15 DOSE PARAMETER R$ FOR SECTOR F Page 3 of 4 Pathway-Sheep (Meat)fShepherd Distance - 0.5 miles X/Q = 1.9E-6 sec/m D/Q = 1.7E-8 m'2 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 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.lE+3 2.0E+3 1.9E+6 Co-58 9.7E+3 2.0E+4 5.lE+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.lE+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.lE+5 9.7E+3 1.6E+6 l 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.lE+3 4.3E+3 8.lE+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.lE+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 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 -

I -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 = ]f(5" Food & Ground Pathway, units = I* I #'m/vr)

( fs S023-0DCM 2-74 Revision 26 l 12-20-93 1

I TABLE 2-15 l DOSE PARAMETER R $ FOR SECTOR F Page 4 of 4 f) v Pathway-DeerConsumep/ Hunter Distance - 1.4 miles X/Q - 3.0E-7 sec/m D/Q = 2.3E-9 m-2 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.lE+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 Hb-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.lE+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 8a-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6

/.m Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 d Ce-144 I -131 1.8E+7 6.5E+8 2.9E+7 4.3E+8 2.1E+5 3.3E+5 4.9E+7 5.9E+8 I -132 3.1E+3 3.4E+4 l 1 -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 1 -134 l 8.2E+2 1.2E+4  !

I -135 1.lE-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4

)

1.4E+8 l

Inhalation Pathway, units - 5" I* II*"**/yr)

Food & Ground Pathway, units f3ec O-

\~-

S023-0DCM 2-75 Revision 26 12-20-93

TABLE 2-16 DOSE PARAMETER Rj FOR SECTOR G Page 1 of 4 Pathway =SanOnofreS}ateBeachCampground Distance = 0.8 miles &

y X/Q = 7.7E-7 sec/m D/Q = 3.9E-9 m-2 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 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 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 2.7E+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 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-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 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 1.5E+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. 7E44 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 l 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 6.8E+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 l

l Inhalation Pathway, units = "C$/

Food & Ground Pathway, units = I* II{**e#yr) c S023-0DCM 2-76 Revision 25 02-28-92 1

r TABLE 2-16 DOSE PARAMETER R, FOR SECTOR G I

N Pathway =HwyPatrolWgighStation X/Q = 2.0E-7 sec/m Distance - 2.0 miles D/Q = 8.5E-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 Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway i H -3 3.0E+2 l Cr-51 3.4E+3 1.lE+6 Mn-54 3.3E+5 3.3E+8 Co-57 8.8E+4 8.1E+7 Co-58 2.2E+5 9.0E+7 Co-60 1.4E+6 5.lE+9 Sr-89 3.3E+5 5.lE+3 Sr-90 2.4E+7 Zr-95 4.2E+5 6.0E+7 Nb-95 1.2E+5 3.2E+7 Ru-103 1.2E+5 2.6E+7 i Te-129m 2.8E+5 4.7E+6 I Cs-134 2.0E+5 1.6E+9 Cs-136 3.5E+4 3.6E+7 Cs-137 1.5E+5 2.4E+9 Ba-140 3.0E+5 4.9E+6 Ce-141 8.6E+4 3.2E+6

( Ce-144 1.8E+6 1.7E+6 l I -131 2.8E+6 4.lE+6 I -132 2.7E+4 2.9E+5 I -133 5.1E+5 5.8E+5 I -134 7.1E+3 1.lE+5 I -135 1.1E+5 6.0E+5 UN-ID 2.1E+5 1.8E+8 Inhalation Pathway, units = %j"f!"

Food & Ground Pathway, units = I*

C /sec f

V)

S023-0DCM 2-77 Revision 28 12-21-95

TABLE 2-16 DOSE PARAMETER R, FOR SECTOR G 1 Page 3 c/ 4 Pathway = Sheep (Meat)fShepherd X/Q = 1.2E-7 sec/m Distance - 2.7 miles D/Q = 4.8E-10 m-2 g

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 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 i 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 l Co-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 i 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 Hb-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 I 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 i Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 I 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 i Ba-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5 I Ce-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 &l Ce-144 I -131 1.8E+4 6.6E+5 3.0E+4 4.4E+5 4.3E+4 6.6E+4 4.3E+5 W l 7.0E+5 I I -132 6.3E+2 6.8E+3 I I -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 l 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 l

l l

I Inhalation Pathway, units = "C Food & Ground Pathway, units I* I l

"';*/yr) j ec S023-0DCM O' l 2-78 Revision 26 12-20-93 l

_ . . . _ . . _ _ _ - - _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ . . _ _ _ _ _ _ _ _ _ _ ~

TABLE 2-16 D0SE PARAMETER Ri FOR SECTOR 6

' Pathway-DeerConsumep/ Hunter Distance - 3.3 miles X/Q - 8.8E-8 sec/m D/Q - 3.2E-10 m-2 Infant Child Teen Adult J

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 i 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 i 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 i Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 i 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.lE+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 O Ce-144 I -131 1.5E+6 1.8E+7 6.5E+8 2.4E+6 2.9E+7 4.3E+8 9.9E+3 2.1E+5 3.3E+5 4.2E+6 4.9E+7 5.9E+8 i

I -132 3.1E+3 3.4E+4 l 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 - yr I* "

Food & Ground Pathway, units C sec CD 5023 000, 2-79 Revision 26 ,

12-20-93 i i

I

2.9 TOTAL DOSE CALCULATIONS 2.9.1 Total Dose to Most Likely Member of the Public l The total annual dose or total dose commitment to any member of the l public, due to releases of radioactivity and to radiation, from uranium fuel cycle sources within 5 miles of the Site is calculated using the following expressions. This methodology is used to meet the dose limitations of 40 CFR 190 per twelve consecutive months.

The transportation of radioactive material is excluded from the dose calculations.

The Annual Total Dose is determined monthly for maximum organ (gas

& liquid), whole body (gas & liquid) and thyroid (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 mram respectively. l

.1 Annual Total Oroan Dose (D TOT (01) 12 2/3 ,

(~ }

DTOT (0) = E I D )(0G)+ D3 )(0L)+ D j(OG) l=1 j =1 3 where: ,

3

• NOTE:

Dfi(OG) = 0 for bone

• • All to be summed over the most recent 12 months.

n (2-21)

D,$3 (0G) = K EC 3 ER k ik Wk i =1 i = each isotope in specific organ category j - Units 1, 2 and 3 1 - months 1 - 12**

K = 3.1688 E-2 #**#

, sec-Ci O

S023-0DCM 2-80 Revision 21 02-15-90

1 2.9 TOTAL DOSE CALCULATIONS (Continu;d) 2.9.1 Total Dose to Most Likely Member of the Public (Continued) p n =

number of isotopes in the specified organ category V C, = total particulate gas curies released for the month IRik Wk -

controlling location factors from ODCM Table 2-5, k Unit I and Table 2-6, Units 2/3, for all pathways k.

D)(0L) 3

=

liquid organ dose for the specified organ in mrem for the month. [ Reference ODCM Units 2/3 (1-19), Unit 1 -

(1-13)]

g3 D3 ;(OG)* = gas organ dose form tritium in mrem for the month.

[ Reference ODCM Unit 1 (2-14), ODCM Units 2/3 (2-18)]

.2 Annual Total Whole Body Dose DTOT lW3-}-

12 2/3 (' }

DioT(WB) = I E D )(WBL)+ Dfj(0G) + 0.9 D31(y) 4(DIRECT) l=1 j =1 3 where:

j= Units 1, 2 and 3 1= months 1 - 12, to be summed over the most recent 12 months

( D3j(WBL) = liquid whole body organ dose in mrem for the whole month. [ Reference ODCM Units 2/3 (1-19), ODCM Unit 1 (1-13)]

3 H

D33(0G) = gas organ dose from tritium in mrem for the month.

[ Refer ODCM Units 2/3 (2-18), ODCM Unit 1 (2-14)]

Dj )(y) = gamma air dose in mrad for the month. ,

0.9 converts mrad to mrem. l

[ Reference ODCM Units 2/3 (2-14), ODCM Unit 1 (2-10)]

(2-23) n 1 4 I D(bkgd),

p=1 D (Direct) = E max [D(beach)j]

- .0342 q =1 p = for all TLDs per quarter q = for Quarters 1-4 I

O S023-0DCM 2-81 Revision 26 12-20-93 i

2.9 TOTAL DOSE CALCULATIONS (Ccntinued) 2.9.1.2 Annual Total Whole Body Dose D totLWB1 (Continued)

• Direct Radiation h 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. 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 58). This value is the direct dose but must be prorated by the occupancy factor.

Example: Beach time (west boundary, seawall) of 300 hrs /yr, east and north boundaries of 20 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 W October 1, 1991.

.3 Annual Total Thyroid Dose DToT (T)

(' }

12 2/3 E

DToT(T) = E l=1 j =1 .D 31 (0G) + D31(OL).

where:

j= Units 1, 2 and 3 1- months 1 - 12, to be summed over the most recent 12 months D)3 (0G)

= thyroid organ dose from gaseous iodine for the month in mrem. (from 2-21)

D)3 (0L)

- liquid thyroid organ dose for the month in mrem.

[ Reference ODCM Units 2/3 (1-19), Unit 1 ODCM (1-13)]

O S023-0DCM 2-82 Revision 26 12-20-93

TABLE 2-17 SOUTH YARD FACILITY CONTROLLING LOCATION FACTORS O Radionuclide H-3 E ki R gWg mrem /yr per pCi/sec 1.31E-03 Use:

G: SAN ONOFRE BCH CAMPGD Cr-51 4.15E-02 F: SO ST. PK./ GUARD SHACK Mn-54 9.70E+00 F: SO ST. PK./ GUARD SHACK Co-57 2.41E+00 F: SO ST. PK./ GUARD SHACK Co-58 3.14E+00 F: SO ST. PK./ GUARD SHACK Co-60 1.35E+02 F: SO ST. PK./ GUARD SHACK Sr-89 1.71E+00 F: DEER CONSUMER / HUNTER Sr-90 1.04E+02 G: SAN ONOFRE BCH CAMPGD Zr-95 7.26E+00 F: DEER CONSUMER / HUNTER Nb-95 2.88E+01 F:-DEER CONSUMER / HUNTER Ru-103 4.56E+01 F: DEER CONSUMER / HUNTER Te-129m 2.26E+01 F: DEER CONSUMER / HUNTER Cs-134 4.28E+01 F: SO ST. PK./ GUARD SHACK Cs-136 1.04E+00 F: SO ST. PK./ GUARD SHACK Cs-137 6.36E+01 F: SO ST. PK./ GUARD SHACK 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 l I-131 2.28E+01 F: DEER CONSUMER / HUNTER  !

I-132 1.22E-01 G: SAN ONOFRE BCH CAMPGD I-133 2.22E+00 G: SAN ON0FRE BCH CAMPGD I-134 3.24E-02 G: SAN ON0FRE BCH CAMPGD

(- I-135 4.60E-01 G: SAN ON0FRE BCH CAMPGD i UN-ID 5.36E+00 F: SO ST PK./ GUARD SHACK Footnote: These values to be used in manual calculations are the maximum IRWk ig g for all locations based on the most restrictive age group.

O S023-0DCM 2-83 Revision 28 12-21-95

TABLE 2-18 SOUTH YARD FACILITY DOSE PARAMETER R, FOR SECTOR D Page 1 of 1 Pathway-CampHornoSgwageTrmnt. Distance = 3.2 Miles I g X/Q = 1.2E-7 sec/m D/0 - 1.2E-9/m-2 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 2.9E+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 2.lE+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 RU-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 I-131 1.8E+6 2.7E+6 1.6E+7 3.9E+6 g

I-132 2.GE+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 5.8Es 5 UN-ID 2.0E+5 1.7E+8

"'*/ r Inhalation Pathway, units "Ci/mY p

Food & Ground Pathway, units Im )(mrem /vr) pCi/sec O

S023-0DCM 2-84 Revision 28 12-21-95

TABLE 2-19 SOUTH YARD FACILITY DOSE PARAMETER R$ FOR SECTOR E Page 1 of 1 Pathway = Camp Horno Distance = 3.7 Miles 3

(O) _. X/Q = 6.0E-7 sec/m D/0 - 5.7E-9 /m-2 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 1.3E+3 CR-51 1.4E+4 4.7E+6 MN-54 1.4E+6 1.4E+9 C0-57 3.7E+5 3.4E+8 C0-58 9.3E+5 3.8E+8 C0-60 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 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 f CE-144 7.8E+6

( I-131 1.2E+7 7.0E+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 = "Ci/mY p

Food & Ground Pathway, units = I" II""'*/Y"I pCi/sec l

O S023-0DCM 2-85 Revision 28 12-21-95

TABLE 2-20 S0lfTH YARD FACILITY DOSE PARAMETER Ri FOR SECTOR F Page 1 of 4 Pathway - San Onofre S} ate Park / Guard Shack Distance - 0.4 Miles X/Q = 5.4E-6 sec/m D/0 = 3.5E-8 /m-2 I )

Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhal a- 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 C0-57 6.3E+4 5.9E+7 C0-58 1.6E+5 6.5E+7 C0-60 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 2.0E+5 3.4E+6 CS-134 1.5E+5 1.2E+9 CS-136 2.5E+4 2.6E+7 C5-137 1.1E+5 1.8E+9 BA-140 2.2E+5 3.5E+6 CE-141 6.2E+4 2.3E+6 CE-144 I-131 1.3 E+6 2.0E+6 1.2E+7 2.9E+6 g

I-132 2.0E+4 2.1E+5 1-133 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 Pathway, units = 5" Food & Ground Pathway, units - (m rem /vr) p 9e O

S023-0DCM 2-86 Revision 28 12-21-95

TABLE 2-20 SOUTH YARD FACILITY DOSE PARAMETER R$ FOR SECTOR F Page 2 of 4 (3 Pathway =BorderPatro}Checkpt. Distance - 1.4 Miles

, Q X/Q = 1.2E-6 sec/m D/Q = 8.2E-9 /m-2 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 3.6E+2 CR-51 4.lE+3 1.3E+6 MN-54 4.0E+5 3.9E+8 C0-57 1.1E+5 9.8E+7 C0-58 2.6E+5 1.lE+8 C0-60 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 l

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 l CS-136 4.2E+4 4.3E+7 CS-137 1.8E+5 2.9E+9 I BA-140 3.6E+5 5.9E+6 i CE-141 1.0E+5 3.9E+6 I (N

CE-144 2.2E+6 2.0E+7 I-131 3.4E+6 4.9E+6 l I-132 3.3E+4 3.5E+5 I-133 6.lE+5 7.0E+5

I-134 8.5E+3 1.3E+5 I-135 1.3E+5 7.2E+5 UN-ID 2.5E+5 2.1E+8 I

Inhalation Pathway, units =  !"

4 I" **/yr) l Food & Ground Pathway, units ec 4

i O

S023-0DCM 2-87 Revision 28 12-21-95

TABLE 2-20 SolTTH YARD FACILITY DOSE PARAMETER R$ FOR SECTOR F Page 3 of 4 Pathway = Sheep (Meat)fShepherd Distance = 0.3 Miles X/Q = 7.2E-6 sec/m D/Q = 4.5E-8 /m-2 { l 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 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./E+3 8.1E+3 2.0E+3 1.9E+6 C0-58 9.7E+3 2.0E+4 5.1E+3 2.1E+6 C0-60 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 P.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 i CS-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 I BA-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5 CE-141 1.5E43 2.4E+3 2.0E+3 7.9E+4 I CE-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 q g!

I-131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 l I-132 6.3E+2 6.8E+3 I-133 1.6E+2 8.7E+3 1.2E+4 1.3E+4 I-134 1.6E+2 2.5E+3 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 Inhalation Pathway, units = 5" I"

Food & Ground Pathway, units C / ec S023-0DCM e

2-88 Revision 28 12-21-95

1 i

TABLE 2-20

\

SOUTH YARD FACILITY DOSE PARAMETER R$ FOR SECTOR F l Page 4 of 4 l

Pathway =DeerConsumep/ Hunter Distance = 0.4 Miles O- X/Q = 5.4E-6 sec/m D/Q = 3.5E-8 /m-2 .

Infant Child Teen Adult i 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 C0-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 C0-58 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 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 9.3 E+7 1.7E+4 4.0E+8 BA-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 CE-141 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 O- I-131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I-132 3.1E+3 3.4E+4 j 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 = "C Food & Ground Pathway, units =

C /sec O S023-0DCM 2-89 Revision 28 ,

12-21-95

E T J.E 2-21 SOUTH YARD FACILITY DOSE PARAMETER Ri FOR SECTOR G Page 1 of 4 Pathway-SanOnofreBghCampgd Distance - 0.4 Miles X/Q = 4.5E-6 sec/m D/0 = 1.8E-8 /m-2 l 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 8.0E+1 1.4E+2 1.6E+2 -u- 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.lE+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 C0-57 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.lE+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.lE+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-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 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 l 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 1.7E+6 8.3E+4 3.lE+6 CE-144 I-131 1.2E+6 1.8E+6 8.6E+6 2.lE+6 1.5E+6 2.0E+6 8.6E+6 2.1E+6 1.6E+6 1.8E+6 8.6E+6 2.lE+6 1.8E+6 2.7E+6 1.6E+7 3.9E+6 g

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 6.8E+3 1.0E+5 I-135 8.6E+4 3.lE+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 = 5" I" II*"'m/vr)

Food & Ground Pathway, units p js O

S023-0DCM 2-90 Revision 28 12-21-95

i TABLE 2-21 ,

l SOUTH YARD FACILITY DOSE PARAMETER R, FOR SECTOR G i

\ Pathway =HighwayPatrglWeighStation Distance = 1.6 Miles X/Q = 4.2E-7 sec/m D/Q = 1.7E-9 /m-2 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 3.0E+2 CR-51 3.4E+3 1.1E+6 MN-54 3.3E+5 3.3E+8 C0-57 -

8.8E+4 8.1E+7 C0-58 2.2E+5 9.0E+7 C0-60 1.4E+6 5.1E+9 SR-89 3.3E+5 5.1E+3 SR-90 2.4E+7 ZR-95 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 BA-140 3.6E+5 4.9E+6 CE-141 8.6E+4 3.2E+6 CE-144 1.8E+6 1.7E+7

- I-131 2.8E+6 4.1E+6 I-132 2.7E+4 2.9E+5 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-ID 2.1E+5 1.8E+8 Inhalation Pathway, units = 5" Food & Ground Pathway, units I* I 'm/vr) s O

S023-0DCM 2-91 Revision 28 12-21-95

TABLE 2-21 SOUTH YARD FACILITY DOSE PARAMETER Ri FOR SECTOR G Page 3 of 4 Pathway-Sheep (Meat)fShepherd Distance = 2.3 Miles X/Q = 2.4E-7 sec/m D/0 = 9.2E-10 /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 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 HN-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 9.7E+3 2.0E+4 5.1E+3 2.1E+6 C0-60 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 I 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 1.3E4 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  ;

1-132 6.3E+2 6.8E+3 I I-133 1.6E+2 8.7E+3 1.2E+4 1.3E+4 i 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 l l

l Inhalation Pathway, units -  !"

I* II""'"#yr)

Food & Ground Pathway, units p j ec O

S023-0DCM 2-92 Revision 28 12-21-95

TABLE 2-21 SOUTH YARD FACILITY DOSE PARAMETER R, FOR SECTOR G Page 4 of 4 q

g Pathway =DeerConsumep/ Hunter X/Q = 1.8E-7 sec/m Distance = 2.9 Miles -

i D/0 = 6.4E-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 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 HN-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 C0-58 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 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 8A-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

{v} 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.lE-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 = 5" Food & Ground Pathway, units = I* "'

jsec O S023-0DCM 2-93 Revision 28 12-21-95

3.0 PROJECTED DOSES 3.1 Liquid Dose Projection The methodology used for projecting a liquid dose over 31 days for Specification 1.3.1 is as follows:

1. Detemine 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.

l l

3.2 Gaseous Dose Projection 1

The methodology used for projecting a gaseous dose over 31 days for l Specification 2.4.1 is as follows:

1

1. Determine the monthly gamma, beta and organ dose resulting from releases during the previous twelve months.

~

2. Projected dose - Previous 12 months' dose divideo by 12 for the gamma, beta and organ doses.

S023-0DCM 3-1 Revision 22 08-02-90

4.0 E0UIPMENT 4.1 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION n SPECIFICATION V 4.1.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 4-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 1.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with Section 1.4. r 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 approprute 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 RE0VIREMENTS

.1 Each radioactive liquid 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 4-2.

.2 At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, all pumps required to be providing 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.

C)

(_/ S023-0DCM 4-1 Revision 26 12-20-93

i. mE 4-1 RADI0ACT.IVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT

• OPERABLE ACTION

1. GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line - 2/3 RT-7813 1 28

b. Steam Generator Blowdown (Neutralization Sump),

Full Flow Condensate Polisher Effluent Line - 2(3)RT-7817 1 29

c. Turbine Plant Sumps, Auxiliary Building Sump, Component Cooling Water Sumps, Storage Tank Area Sumps Effluent Line- 2(3)RT-7821 1 30

d. Steam Generator (E088) Blowdown Effluent Line - 2(3)RT6759 1 29

e. Steam Generator (E089) Blowdown Effluent Line - 2(3)RT6753 1 29

2. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line 1 31

b. Steam Generator Blowdown (Neutralization Sump),

Full Flow Condensate Polisher Effluent Line 1 31

c. Steam Generator (E088) Blowdown Bypass Effluent Line 1 31

d. Steam Generator (E089) Blowdown Bypass Effluent Line 1 31 S023-0DCM 4-2 Revision 25 8-92

TABLE 4-1 (Continued) j TABLE NOTATION i

• Monitor Recorders are not required for the Operability of the monitor, q providing the inoperable recorder does not cause the monitor to become jQ inoperable (i.e., feedback signal). As long as the monitor has indication, e

alarm capability (if applicable), proper response (based upon surveillance i

requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.

4 ACTION 28 - With the number of channels OPERABLE less than required by the

! Minimum Channels OPERABLE requirements, effluent releases may j j

continue provided that prior to initiating a release: i a.

At least two independent samples are analyzed in

}

accordance with Specification 1.1.1 and l

l l b. At least two technically qualified members of the Facility i Staff independently verify the release rate calculation j and discharge line valving; Otherwise, suspend release of radioactive effluents via this j pathway.

ACTION 29 - With the number of channels OPERABLE less than required by the i Minimum Channels OPERABLE requirement, effluent releases via this i pathway may continue provided grab samples are analyzed for gross i rad)oactivity (beta or gamma) at a limit of detection of at least

j. 10- microcuries/ gram:

a. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of O the secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT I-131;

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT I-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 '

pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of collection time for gross ra of detection of at least 10 pioactivity (beta or gamma) at a limit, microcuries/ml or lock closed valve S2(3)2419MUO77 or S2(3)2419MUO78 and divert flow to the radwaste sump for processing as liquid radwaste.

ACTION 31 - With the number of channels OPERABLE less than required by the i Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flow.

O S023-0DCM 4-3 Revision 22 08-02-90

.ABLE 4-2 BADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNELS FUNCTIONAL INSTRUMENT ** CHECK CHECK CALIBRATION TEST

1. GROSS BETA OR GAMMA RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluents line -

2/3 RT-7813 D P R(2) Q(I)

b. Steam Generator Blowdown (Neutralization Sump),

Full Flow Condensate Polisher Effluent Line - 2(3)RT-78I7 D M R(2) Q(1)

c. Turbine Plant Sump, Auxiliary Building Sump, Component Cooling Water Sumps, Storage Tank Area Sumps Effluent Line - 2(3)RT-7821 D M R(2) Q(1)

d. Steam Generator (E088) Blowdown Bypass Effluent Line - 2(3)RT-6759 D M R(2) Q(I)

e. Steam Generator (E089) Blowdown Bypass Line - 2(3)RT6753 D M R(2) Q(1)

2. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line D(3) N.A R Q

b. Steam Generator Blowdown (Neutralization Sump),

Full Flow Condensate Polisher Effluent Line D(3) N.A R Q

c. Steam Generator (E088) Blowdown Bypass Effluent Line D(3) N.A R Q

d. Steam Generator (E089) Blowdown Bypass Effluent Line D(3) N.A R Q S023-0DCM 4-4 Revision 22 08-02-90 0 -- -- -

0 - - -

0 - -

j TABLE 4-2 (Continued) 4

- TABLE NOTATION 1

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 j recorder does not render the monitor inoperable.

I 1

1 (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent

! -path isolation closure and Control Room alarm annunciation if any of the

following conditions exist

*

i i 1. Instrument indicates measured levels above the alarm / trip setpoint.

2. Circuit failure.

j 3. Instrument indicates a downscale failure.

i

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the 4 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 l shall permit calibrating the system over its intended range of energy and i measurement range. For subsequent CHANNEL CALIBRATION, sources that have i been related to the initial calibration shall be used.

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of l release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on j which continuous, periodic, or batch releases are made.

i i

I L *If the instrument controls are not in the operate mode, procedures shall require

that the channel be declared inoperable.

i

i. )

i l i;

l j  !

! S023-0DCM  ;

4-5 Revision 22  !

08-02-90 ,

I l

-,m- , - .-- ~ , , . _ . _ , _ - , , ,

4.0 E0UIPMENT 4.2 RADI0 ACTIVE 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 alarW trip setpoints set to ensure I that the limits of Specification 2.1.1 are not exceeded.

The alarm / trip setpoints of these channels shall be i determined in accordance with ODCM.

APPLICABILIH: At all times ACTION:

a. With a radioactive gaseous effluent monitoring l instrumentation channel alarm / trip setpoint less ,

conservative than required by the above specification, I immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation 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 r.s not corrected in a timely manner.

c. With less than the minimum number of radioactive gaseous effluent inordtoring instrumentation channels OPERABLE and either the appropriate ACTION items in Table 4-3 not taken or the necessary surveillances not performed 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 RE0UIREMENTS

.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.

5023-0DCM 4-6 Revision 26 12-20-93

BLE 4-3 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l MINIMUM CHANNELS INSTRUMENT *** OPERABLE APPLICABILITY ACTION  !

i

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor ,

Providing Alarm and Automatic Termination of Release - 1

• 35 2/3 RT-7808, or 3 RT-7865-1 i

b. Process Flow Rate Monitoring Device 1

• 36 i

2. CONDENSER EVACUATION SYSTEM i

a. Noble Gas Activity Monitor - 2(3)RT-7818 or 2(3)RT-7870-1 1- ** 37

b. Iodine Sampler ** 40 1(4)

c. Particulate Sampler 1(4) ** 40 i

d. Associated Sample Flow Measuring Device 1

• • 36  :

e. Process Flow Rate Monitoring Device ** 36 1(1)

3. PLANT VENT STACK j

a. Noble Gas Activity Monitor - 2/3 RT-7808, or 2RT-7865-1 1(3)

• 37 Aqd 3RT-7865-1

b. Iodine Sampler

• 1(3)(4) 40

c. Particulate Sampler 1(3)(4)

• 40

d. Associated Sample Flow Measuring Device .* 36 1(3)

e. Process Flow Rate Monitoring Device 2(2)

• 36 i

4. CONTAINMENT PURGE SYSTEM

a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release - 2(3)RT-7828, or 2(3)RT-7865-1 1

• 38

b. Iodine Sampler 1

• 40  ;

c. Particulate Sampler 1

• 40 '

d. Process Flow Rate Monitoring Device 1

• 36

e. Associated Sample Flow Measuring Device 1

• 36 S023-0DCM 4-7 Revision 27 12-21-94

IABL -3 (continued)

RADI0 ACTIVE SASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT *** OPERABLE APPLICABILITY ACTION

5. 500Tli YARD FACILITY (SYF) WORK AREA

a. Particulate Activity Monitor (RU-7904) 1 40

b. Iodine Sampler 1 40

c. Particulate Sampler I

• 40 Associated Sample Flow Measuring Device

• 36

d. 1 Process Flow Rate Monitoring Device

• 36

e. 1

6. SYF DECONTAMINATION AREA Particulate Activity Monitor (RU-7905)

• 40

a. 1 t

b. Iodine Sampler 1 40

c. Particulate Sampler I

• 40

' Associated Sample Flow Measuring Device

• 36

d. 1 Process Flow Rate Monitoring Device

• 36

e. 1 S023-0DCM 4-8 Revision 27 12-21-94 O -

O - -- - .

O

~ . - -. .- -._. - ._- - - ...-.... - - - - - -. - .- - -

i

~

TABLE 4-3 (Continued)

TABLE NOTATION

O

• At all times.

l MODES 1-4 with any main steam isolation valve and/or any main steam isolating l 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 l- continuously monitoring process flow is not available, then comply with i 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 l with ACTION 36.

I

(3) Due to unequal mixing in the Plant Vent Stack, both 2RT-7865 and 3RT-7865 are i required to be operable when 2/3RT-7808 is inoperable.

. (4) With only one channel operable, channel may be sampled so long as the time i that the channel is shut down is one hour or less. Ref: Memorandum for '

} File, " Units 2/3 - Clarification No. 14", by G. T. Gibson, dated June 30, 1983.

d ACTION 35 - With the number of channels OPERABLE _less than required by the l Minimum Channels OPERABLE requirement, the contents of the tank (s) <

j may be released to the environment provided that prior to *

initiating the release

j a. At least two independent samples of the tank's contents

are analyzed, and

b. At least two technically qualified members of the Facility 3 Staff independently verify the release rate calculations j and discharge valve lineup; i Otherwise, suspend releases of radioactive effluents via this pathway.

i ACTION 36 - With the number of channels OPERABLE less than required by the i Minimum Channels OPERABLE requirement, effluent releases via this i pathway may continue provided the flow rate is estimated at least 1 once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. System design characteristics may be used to j estimate flow.

s O 4-9 S023-0DCM Revision 27 12-21-94

TABLE 4-3 (Continued)

JM LE NOTATION 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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.

O S023-0DCM 4-10 Revision 26 12-20-93

O O O TABLE 4-4

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS t CHANNEL . MODE FOR WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL. SURVEILLANCE INSTRUMENT *** CHECK CHECK CALIBRATION TEST IS REQUIRED

1. WASTE GAS HOLDUP SYSTEM -

a. Noble Gas Activity Monitor -

l Providing Alarm and Automatic Termination of Release -

2/3 RT-7808, 3RT-7865-1 P P R(3) Q(1) *  !

b. Process Flow Rate Monitoring Device P N.A R Q

2. CONDENSER EVACUATION SYSTEM

a. Noble Gas Activity Monitor -

2(3)RT-7818,2(3)RT-7870-1 D M R(3) Q(2) **

b. Iodine Sampler W N.A N.A N.A **

c. Particulate Sampler W N.A N.A N.A ** t'

d. Associated Sample Flow Measuring Device D N.A R Q **

e. Process Flow Rate Monitoring Device (2(3)RT-7870-1) D N.A R Q **

S023-0DCN 4-11 Revision 26 12-20-93

TABLE 4 (Ccntinued)

RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE FOR WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE INSTRUMENT *** CHECIL CHECK CALIBRATION TEST IS REQUIRED

3. PLANT VENT STACK

a. Noble Gas Activity Monitor - D M R(3) Q(2) 2/3 RT-7808, 2RT-7865-1, 3RT-7865-1 N.A N.A *

b. Iodine Sampler W N.A N.A *

c. Particulate Sampler W N.A N.A

d. Associated Sample Flow N.A

• Measuring Device D R Q

e. Process Flow Rate Monitoring N.A

• Device D R Q

4. CONTAINMENT PURGE SYSTEM

a. Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release -

2(3)RT-7828,2(3)RT-7865-1 D P(4) R(3) Q(1)

N.A *

b. Iodine Sampler W N.A N.A

c. Particulate Sampler W N.A N.A N.A

d. Process Flow Rate Monitoring N.A

• Device D R Q

e. Associated Sample Flow Measuring Device D N.A R Q S023-0DCM 4-12 Revision 22 08-02-90

_ -. - . _ . _ _ _ . . _ . _ . . . _ _ _ _ . - . _ - . _ - . _ . . _ . . _ . _ . _ _ . - . . . _ . _ . . - . . . . _ . _ _ . _ . . _ _ _ . . _ . ~ . . _ . . _ . _ _ . - . . .

TABL 4 (Continued)

RADI0 ACTIVE'GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE FOR WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE [

INSTRUMENT *** CHECK CHECK CALIBRATION TEST IS REQUIRED ,

5. SOUTH YARD FACILITY (SYF) WORK AREA

a. Particulate Activity Monitor (RU-7904) Exact instrumentation and requirements will be added subsequent to  ;

final DCP A-7022.00SC turnover. a

b. Iodine Sampler W N.A. N.A. N.A. *

c. Particulate Sampler W N.A. N.A. N.A. *

d. Process Flow Rate Moritoring Device D(5) N.A. R Q *

e. Associated Sample Flow Measuring Device D(5) N.A. R Q *

6. SYF DECONTAMINATION AREA

a. Particulate Activity Monitor (RU-7905) Exact instrumentation and requirements will be added subsequent to  !

final DCP A-7022.00SC turnover.

b. Iodine Sampler W N.A. N.A. N.A. *

c. Particulate Sampler W N.A. N.A. N.A.

• t

d. Process Flow Rate Monitoring Device D(5) N.A. R Q i

e. Associated Sample Flow Measuring Device D(5) N.A. R Q l

NOTE: For 5 and 6, surveillance requirements to take effect upon DCP A-7022.005C turnover of these instruments.

i

5023-00CM 4-13 Revision 27 ;

12-21-94 l I

TABLE 4-4 (Continued) 1 TABLE NOTATION i

• 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, 1 providing the inoperable recorder does not cause the monitor to become j 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) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent ,

path isolation closure 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. l

3. Instrument indicates a downscale failure.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exinh#

1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure. '

(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 CHANNFL CALIBRATION, sources that have been r' elated to the initial calibration shall be used.

(4) Prior to each release and at least once per month.

(5) Daily checks only required during times of building occupation.

1. If the instrument controls are not set in the operate mode, procedures shall call for declaring the channel inoperable.

S023-0DCM 4-14 Revision 27 12-21-94

1 4

4.3 OPERABILITY 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 1

j in Figures 4-5 thru 4-7.

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S023-0DCM 4-15 Revision 21 i 02-15-90 f

FIGURE 4-5 SONGS 2 & 3 RADI0 ACTIVE LIQUID WASTE TREATMENT SYSTEMS O

5torage Tank Area Suso CCW Sump Main (latch) (Batch) , Condenser l

Aux tullding l Turbine Plant samp Sump RT.7821 3

(Continuous)

-l '

l (Continuous)

I Laundey heutralization Faci 1ity Sump l [ Batch / Cont)

---l RT 7817 l I

895 -

1 I I I

NCS LC5 NUT (Batch) (Batch) _l (Batch) l FFCPD 5tese Generator '

E.089 -- l RT-6753 '

Steam Generator RT.6759 I C 088 -l '

Radmaste Primary Tanks Radweste Secondary Tanks Primary Makeup Tanks Condensate Monitor Tanks -l2/3RT7813 l (Satch) Intake Outfall l

l l.RadiationMonitor NOTEt Monitee pathways are unit specific unless indicated to be common to Units 2 and 3.

S023-0DCH 4-16 Revision 28 12-21-95 F

O FIGURE 4-6 SONGS 2 & 3 RA L . IIVE GASE0US WASTE TREATMENT SYSTEMS O Atmosphere Atmosphere Atmosphere Atmosphere 4 b 2RT-7870 3RT-7870

-G b 2RT-7828 h 4 3RT-7828 3RT-7818 4 RU-79 Unit 2 . _ . _ . _ __ .

Unit 3 Containment @ @ Containment i Purge , Purge  !*

2RT 7865 C 3RT-7865 (1) $_ (1)

E 2/3RT-7808 Unit 2 Building - m Unit 3 Building

+

Ventilation Exhausts Ventilation Exhausts -

I Unit 2 Condenser Unit 3 Condenser South Yard Evacuation System Evacuation System Facility i

Waste Gas Decay Tanks (6)  ;

--@ Radioactivity Monitor t (1) RT-7865 can be aligned to either containment purge or the plant vent stack  :

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S023-0DCM i' 4-17 Revision 28 12-21-95

FIGURE 4-7 .sLIO WASTE HANDLING Resh slu!ced Loaded into Transfe:Ted Spent Resin from SRT IO N shipping cast Resin sfulced  : to disposal  :  :

Spent Resin  : Accumulated forWeh fortransport Imm TXto SRT hSRT container and staoina to burial slie dewatered FRter evaluated forhelnerabttryl If not

. Waste Fitterstoredin hcinerable, Filter remoM Ifincinerable  : shipped Particulate from in-line r accumulation  :- Packatredin shipped for to burial Process Filters area on sRe drum liner foi JOSEIO" off-sRe disposal sRe hcIneration_ .

Resulting

1. aste placed in disposable Wastes collected cargo container Waste shlpped to in receptacles waste packaged Low Level Dry r for shipment processor for r located around and shipped Active Waste to off-ste mjume reduction pant i Imm processor processor y to burlet sRe Waste sorted for Wastes packaging onste packaged _

Waste shipped orvendor and transferred to burialsRe processino I to MHF "tothhg packed Clothing bags in boes and Protective collected frort  :  ;-

' shipped to points around retumed to sRe ClothinD off-site laundry plant and restocked racggy Legend SRT: Spent Resin Tank MPHF: Mulit Purpose Handling Facility IX: Ion Exchanger S023-0DCM 4-18 Revision 28 12-21-95

5.0 RADIOLOGICAL EMIR 0MDITAL NONITORIM l 5.1 Monitorina Proaram SPECIFICATION 5.1.1 The radiological environmental monitoring program shall be j conducted as specified in Table 5-1. The requirements are ,

applicable at all times. t I

APPLICABILITY: At all times ACTION:

. a. Should the radiological environmental monitoring program l 1

not be conducted as specified in Table 5-1, in lieu of any other report required by Technical Specification (s) l 6.9.1, [Section 5.7.1 and LCS 5.0.104 upon TSIP R 1

t implementation], prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report f (see Section 5.4), a description of the reasons for not t conducting the program as required and the plans for preventing a recurrence. ,

i

! b. Should the level of radioactivity in an environmental i sampling medium exceed the reporting levels of Table 5-2 '

j when averaged over any calendar quarter, in lieu of any >

l other report required by Technical Specification (s) 6.9.1, i [Section 5.7.1 and LCS 5.0.104 upon TSIP implementation],

l prepare and submit to the Commission, within 30 days from g

the end of tha affected calendar quarter a Report pursuant i to Technical _ Specification (s) 6.9.1.13,[10CFR50.73],

i When more than one of the radionuclides in Table 5-2 are '

i detected in the sampling medium, this repert shall be j sub;nitted if:

I concentration (1) + concentration (2) + . . 1 1.0

!- limit level (1) limit level (2) f .i

> c. When radionuclides other than those in Table 5-2 are i

detected and are the result of plant effluents, this

j. report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specification (s) 1.2.1, 2.2.1 or 2.3.1, as j appropriate. This report is not required if the measured 1 level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the .innual Radiological Environmental Operating Report (see Section 5.4).

i O S023-0DCM 5-1 Revision 29 07-31-96

5.0 RADIOLOGICAL ENVIRONNENTAL MONITORING (Continued)

ACTION: (Continued)

d. With fresh leafy vegetable samples or fleshy vegetable samples unavailable from one or more of the sample locations required by Table 5-1, in lieu of any other report required by Technical Specification 6.9.1, [Section 5.7.1 and LCS 5.0.104 upon TSIP implementation], prepare and submit to the commission within 30 days, pursuant to R Technical Specifications 6.9.2, [Section 5.7.2 and LCS 5.0.104.2 upon TSIP implementation], a Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples. The locations from which samples were unavailable may then be deleted from those required by Table 5-1, provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations.

SURVEILLANCE RE0VIREMENTS

.1 The radiological environmental monitoring samples shall be i collected pursuant to Table 5-1 from the locations given in  !

Tables 5-4 and 5-5 and Figure 5-1 and shall be analyzed pursuant to the requirements of Tables 5-1 and 5-3.

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l 5-2 S023-0DCM Revision 29 9lI 07-31-96

~ . - . . . - . - - - - . . - - -

.4BLE 5-1 RADIOLOGICAL ENVIROINtENTAL NONITORING PROGRAN .

Exposure Pathway Number of Samples Sampling and i and/or Sample and Sample locations

• Collection Freauency* Type and Freauency of Analyses i

1. AIRBORNE Samples from at least Continuous operation Radiotodine cartridge. Analyze Radioiodine 5 locations i of sampler at least once per 7 days for I-131.

and 3 samples from offsite with sample collection Particulate sampler. Analyze for Particulates locations (in different as required by dust gross beta radioactivity 2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> sectors) of the highest loading, but at followingfiltgrchange. Perform calculated annual average onceper7 days.jeast gamma isotopic analysis on each t ground level D/Q. sample when gross beta activity is i

> 10 times the yearly mean of control t 1 sample from the vicinity samples. Perform gamma isotopic of a community having the analysis on composite (by location)  ;

the highest calculated sample at least once per 92 days.

annual average ground- ,

level D/Q.

I sample from a control loca-tion 15-30 km (10-20 miles) ,

distant and in the least pre-valent wind direction' i

2. DIRECT At least 30 locations includ- At least once per Gamma dose. At least once per 92 days.

RADIATION

• ing an inner ring of stations 92 days.

in the general area of the site boundary and an outer ring approximately in the 4 i to 5 mile range from the site '

with a station in each sector  !'

of each ring. The balance of the stations is in special  ;

interest areas such as popula-

• tion centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations.

i S023-0DCM  ;

5-3 Revision 21 02-15-90 I

TABLE . 1 (Continusd)

RADIOLOGICAL ENVIRONMENTAL N0NITORING PROGRAN Exposure Pathway Number of Samples Sampling and and/or Sample and Samole locations' Collection Frecuency* Tvoe and Freauency of Analyses

3. WATERBORNE

a. Ocean 4 locations At least once per Gamma isotopic analysis of each month and composited i monthly sample. Tritium analysis quarterly of composite sample at least once per 92 days.

b. Drinking 2 locations Monthly at each Gamma isotopic and tritium location. analyses of each sample.

c. Sediment 4 locations At least once per Gamma isotopic analysis of each from 184 days. sample.

Shoreline

d. Ocean 5 locations At least once per Gamma isotopic analysis of each Bottom 184 days, sample.

Sediments i

I S023-0DCM

.... . . .-. - ._ - ..=. . . . . - . . . . - . _ -.. -- - - . . .. . ..- - - -

TABL -1 (Continued)

RADIOLOGICAL ENVIRONMENTAL NOMITORING PROGRAN Exposura Pathway Number of Samples Sampling and and/or Sample and Sample locations

• Collection Freouencv* Tyne and Freouency of Analyses i

4. INGESTION

a. Nonmigratory 3 locations One sample in season, Gamma isotopic analysis on Marine or at least once per edible portions.

Animals 184 days if not seasonal. One sample of each of the follow-ing species:

1. Fish-2 adult species such as perch or .

sheephead.

2. Crustaceae-such as crab or lobster.

3. Mollusks-such as ,

limpets, seahares or clams.

b. Local Crops 2 locations Representative Gamma isotopic analysis on edible vegetables, normally portions semiannually and I-131 1 leafy and I fleshy analysis for leafy crops, collected at harvest time. At least 2 vegetables collected semiannually from each location.

S023-0DCM 5-5 Revision 21 02-15-90

TABLE _ 1 (C:ntinued)

TABLE NOTATION

a. Sample locations are indicated on Figure 5-1.

b. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility,

c. The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be sub:tituted.

d. Canisters for the collection of radiciodine in air are subject to channeling. These devices should be carefully checked before operation in the field or several should be mounted in series to prevent loss of iodine.

e. Regulatory Guide 4.13 provides minimum acceptable performance criteria for thermoluminescence dosimetry (TLD) systems used for environmental monitoring. One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a packet may be considered as two or more dosimeters. Film badges should not be used for measuring direct radiation.

f. Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly).

S023-0DCM 5-6 evision 22 90

p V

s

.ABLE 5-2 REPORTING LEVELS FOR RADI9 ACTIVITY CONCENTRATIONS IN ENVIR0fMENTAL SANPLES Reporting Levels Airborne Particulate Water Marine Animals Local Crops Analysis (pCi/1) or Gasg)s (pCi/m (pC1/Kg, wet) (pCi/Kg, wet)

H-3 2 x 10"I*)

3 Mn-54 1 x 10 3 x 10' Fe-59 4 x 10 2 1 x 10" Co-58 1 x 10 3 3 x 10'  !

Co-60 3 x 10 2 1 x 10' Zn-65 3 x 10 2 2 x 10" 2

Zr Nb-95 4 x 10 ,

I-131 2 0.9 1 x 10 2 Cs-134 30 10 1 x 10 3 1 x 10 3 Cs-137 50 20 2 x 10 3 2 x 10 3 r Ba La-140 2 x 10 2

(*) For drinking water samples. This is 40 CFR Part 141 value.

l S023-0DCM ,

5-7 Revision 21 .,

02-15-90 7 i

$BLE 5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS

• MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)*

Airborne Particulate Water Marine Animals Local Crops Sediment Analysis (pCi/1) or Gasg)s (pCi/m (pCi/Kg, wet) (pCi/Kg, wet) (pCi/Kg, dry) gross beta 4 1 x 10-2 b

H-3 2000 Mn-54 15 130 Fe-59 30 260 00-58, 60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 lb 7 x 10-2 60 Cs-134 15 5 x 10-2 130 60 150 Cs-137 18 6 x 10-2 150 80 180 Ba-140 60 La-140 15 (b) For drinking water samples. This is 40 CFR Part 141 value.

S023-0DCM 5-8 Revision 28 12-21-95 O O - -- --

O --

e TABLE 5-3 (Continued) i

TABLE NOTATION ip a. The LLD is the smallest concentration of radioactive material in a sample '

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

For.a particular measurement system (which may include radiochemical

separation)

LLD =

4.66 sb '

s

E.V 2.22 x lo . Y exp (-AAt)

I where:

i LLD is the "a priori" lower limit of detection as defined above (as -

i microcurie per unit mass or volume),

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

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

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

1 j 6 2.22 x 10 is the number of transformations per minute per i microcurie, Y is the fractional radiochemical yield (when applicable),

i 1 is the radioactive decay constant for the particular i radionuclide, and i

At is the elapsed time between midpoint of sample collection or end i

of the collection period and time of counting (for environmental samples, not plant effluents ). -

i 4

The value of sb used in the calculation of the LLD for a detection 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 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  !

i present in the samples (e.g., potassium-40 in milk samples). Typical values l j of E,V,Y and At shall be used in the calculations. l

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i j S023-0DCM 5-9 Revision 22

08-02-90 e

i _ _ _ _ _ .._ _-

TABLE 5-3 (Continued)

TABLE NOTATION 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 posteriori (after the fact) limit for a particular measurement.*

b. LLD for drinking water.

c. Other peaks which are measurable and identifiable, together with the radionuclides in Table 5-3, shall be identified and reported.

• 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).

O S023-0DCM O.!

5-10 Revision 21 l 02-15-90 )

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5.0 RADIOLOGICAL ENVIR0fttENTAL N0NITORING (Continued) 5.2 LAND USE CENSUS SPECIFICATION O 5.2.1 A land use census shall be conducted and shall identify the i () location of the nearest milk animal, the nearest residence and the nearest garden

• of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.

, APPLICABILITY: At all times ACTION:

a. With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 2.3.1, in lieu of any other report required by Technical Specification 6.9.1, [Section 5.7.1 and LCS 5.0.104 upon TSIP implementation], prepare and submit to the Commission g within 30 days, pursuant to Technical Specification 6.9.2,

[Section 5.7.2 and LCS 5.0.104.2 upon TSIP implementation],

a Special Report which identifies the new location (s).

Identify the new locations in the next Annual Radioactive Effluent Release Report.

a

b. With a land use census identifying a location (s) which yields a calculated dose or dose commitment via the same exposure pathway 20 percent greater than at a location from i which samples are currently being obtained in accordance with Section 5.1, in lieu of any other report required by

,O Technical Specification 6.9.1, [Section 5.7.1 and LCS 5.0.104 upon TSIP implementation], prepare and submit to the Commission within 30 days, pursuant to Technical R

Specification 6.9.2, [Section 5.7.2 and LCS 5.0.104.2 upon i

TSIP implementation], a Special Report which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days. The sampling location, excluding the control station location, having the lowest calculated dose or dose commitment 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.

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 be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.

S023-0DCM 5-11 Revision 29 07-31-96

5.0 RADIOLOGICAL ENVIRONNENTAL MONITORING (Continu:d) 5.3 INTERLABORATORY COMPARISON PROGRAM SfECIFICATION 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 1

ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

SURVEILLANCE REOUIREMENTS

.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 Environmental Operating Report (see Section 5.4),

O i

i S023-0DCM 5-12 Revision 22 08-02-90

5.0 RADIOLOGICAL ENVIR0 MENTAL N0NITORING (Continu:d) 5.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

• 5.4.1 The annual radiological environmental operating reports O shall include summaries, 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 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 summarized and tabulated results in the format 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 samnling locations keyed to a table L

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.

S023-0DCM 5-13 Revision 21 02-15-90

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.5 SAMPLE LOCATIONS The Radiological Environmental Monitoring Sample Locations are identified in Figure 5-1. These sample locations are described in Tables 5-4 and 5-5 and indicate the distance in miles and the direction, detarmined 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, Figure 5-1.

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l S023-0DCM 5-14 Revision 21 02-15-90

Page 1 of 6 i

l TABLE 5-4 j RADIOLOGICAL ENVIRONNENTAL NONITORING SANPLE LOCATIONS DISTANCE *-

TYPE OF SAMPLE AND SAMPLING LOCATION *** (miles) DIRECTION

• s Direct Radiation 1 City of San Clemente (Former SDG&E Offices) 5.6 NW l 2 Camp San Mateo (MCB, Camp Pendleton) 3.5 N

! 3 Camp San Onofre (MCB, Camp Pendleton) 2.6 NE

! 4 Camp Horno (MCB, Camp Pendleton) 4.5 E j 6 Old Route 101 (East-Southeast) 3.0 ESE 8 Noncommissioned Officers' Beach Club 1.5 NW l 10 Bluff (Adjacent to PIC #1) 0.7 WNW l 11 Former Visitors' Center 0.3** NW

! 12 South Edge of Switchyard 0.2** E  ;

j 13 Southeast Site boundary (Bluff) 0.4** SE j 14 Huntington Beach Generating Station 37.0 NW 15 Southeast Site boundary (Office Building) 0.2** SE j 16 East Southeast Site Boundary 0.4** ESE i

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 San Clemente General Hospital 8.2 NW 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.

S023-00CM 5-15 Revision 28 12-21-95

Page 2 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE

• TYPE OF SAMPLE AND SAMPLING LOCATION *** (miles) DIRECTION

• Direct Radiation (Continued) 31 Aurora Park-Mission Viejo 18.7 NNW 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, Camp Pendleton) 4.2 NE 38 San Onofre State Beach Park 3.3 SE 40 SCE Training Center - Mesa (Ar iacent to PIC #3) i 0.7 NNW 41 Old Route 101 - East 0.4** E 44 Fallbrook Fire Station 18.0 E 46 San Onofre State Beach Park 1.0 SE 47 Camp Las Flores (MCB, Camp Pendleton) 8.6 SE O

1 1

Distance (miles) and Direction (sector) are measured relative to Units 2 and l 3 midpoint. Direction is determined from degrees true north, i

• • 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 5-16 Revision 28 12-21-95

Page 3 of 6

] TABLE 5-4  ;

r3 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS U DISTANCE

• TYPE OF SAMPLE AND SAMPLING LOCATION *** (miles) DIRECTION

• i l Direct Radiation (Continued) 49 Camp Chappo (MCB, Camp Pendleton) 12.8 ESE

! 50 15.5 Oceanside Fire Station (CONTROL) SE 53 San Diego County Operations Center 45.0 SE 54 Escondido Fire Station 32.0 ESE 55 San Onofre State Beach (Unit 1, West Southwest) 0.2** WSW 56 San Onofre State Beach (Unit 1, Southwest) 0.l** SW 57 San Onofre State Beach (Unit 2) 0.l** SSW )

58 San Onofre State Beach (Unit 3) 0.l** S 59 SONGS Meteorological Tower 0.3** WNW 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) 0.5 ENE 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 #2) 0.6 NW 68 Range 210C (MCB, Camp Pendleton) 4.3 ENE 73 South Jard Facility 0.05** NE Transit Control A - -

Transit control B - -

Fader (Co-Located with TLD # 54)**** 32.0 ESE 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.

O S023-0DCM 5-17 Revision 28 12-21-95

l Page 4 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE

• TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION

• 1 Airborne i 1 City of San Clemente (City Hall) 5.5 NW l 2 Camp San Onofre (Camp Pendleton) 1.8 NE 3 Huntington Beach Generating Station (CONTROL) 37.0 NW 5 Units 2 and 3 Switchyard 0.13** NNE 7 AWS Roof 0.18** NW 9 State Beach Park 0.6 ESE 10 Bluff 0.7 WNW 11 Mesa E0F 0.7 NNW 12 Former SONGS Evaporation Pond 0.6 NW 13 Marine Corps Base (Camp Pendleton East) 0.7 E Soil Samples 1 Camp San Onofre 2.5 NE 2 Old Route 101 - East Southeast 3.0 ESE 3 Basilone Road /I-5 Freeway Offramp 2.0 NW 4 Huntington Beach Generating Station (CONTROL) 37.0 NW 5 Former Visitor's Center 0.2** NNW Ocean Water A Station Discharge Outfall - Unit 1 0.5 SSW B Outfall - Unit 2 0.7 SW C Outfall - Unit 3 0. SW D Newport Beach (CONTROL) 30.0 NW 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 a' .

sectors) and not required by Technical Specification.

S023-0DCM 5-18 Revision 26 12-20-93

Page 5 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE

• TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION

• Drinking Water 1 Tri-Cities Municipal Water District Reservoir 8.7 NW 2 San Clemente Golf Course Well 3.5 NNW 3 Huntington Beach (CONTROL) 37.0 NW Shoreline Sediment (Beach Sand) 1 San Onofre State Beach (0.6 mile Southeast) 0.6 SE 2 San Onofre . Surfing Beach 0.9 NW  ;

3 San Onofre State Beach (3.1 miles Southeast) 3.1 SE 4 Newport Beach (North End) (CONTROL) 30.0 NW Local Crops 1 San Mateo Canyon (San Clemente Ranch) 2.6 NW 2 Southeast of Oceanside (CONTROL) 22.0 SE

3. Cotton Point Estates Gardens (Casa Pacifica) 2.8 WNW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

O S023-0DCM 5-19 Revision 28 12-21-95

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 1.7 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 D

E Unit 3 Outfall Laguna Beach (CONTROL) 1.2 18.2 SSW NW h

Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

S023-0DCM 5-20 Revision 26 12-20-93

. ~ . _ ._ - . .. . . -- - . . .

TABLE 5-5 PIC - RADIOLOGICAL ENVIRONMENTAL NONITORING LOCATIONS Theta f]m PRESSVRIZED ION CHAMBERS (Decrees)* Meters DISTANCE

• miles DIRECTION / SECTOR

• S1 San Onofre Beach 298* 1070 0.7 WNW P S2 SONGS Former 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 S5 MCB - Camp Pendleton 19* 1050 0.6 NNE B S6 MCB - Camp Pendleton 46* 940 0.6 NE C S7 MCB - Camp Pendleton 70* 870 0.5 ENE D S8 MCB - Camp Pendleton 98* 1120 0.7 E E S9 San Onofre State Beach 121' 940 0.6 ESE F i

O

• Distance (meters / miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Theta direction is determined from degrees true north.

b

\ S023-0DCM 5-21 Revision 21 02-15-90

l 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 E

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 l

303.75 315.0 326.25 Q NW 326.25 337.5 348.75 R NNW l

I 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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4

6.0 ADMINISTRATIVE

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 that part of a specification which prescribes remedial measures required under designated conditions.

4 CHANNEL CALIBRATION 6.1.2 A CHANNEL CALIBRATION shall be the adjustment, as necessary, l of the channel output such that it responds with the necessary i i range and accuracy to known values of the parameter which the

' channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the

, entire channel is calibrated.

CHANNEL CHECK t

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 indications and/or status  !

derived from independent instrument channels measuring the j same parameter. I CHANNEL FUNCTIONAL TEST l

6.1.4 A CHANNEL FUNCTIONAL TEST shall be: I I

a. Analog channels - the injection of a simulated signal into channel as close to the sensor as practicable to verify OPERABILITY, including alarm and/or trip functions.

b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY, including alarm i

and/or trip functions,

c. Digital computer channels - the exercising of the digital .

computer hardware using diagnostic programs and the I injection of simulated process data into the channel to verify OPERABILITY.

A E

S023-0DCM  !

6-1 Revision 21 02-15-90

6.0 ADMINISTRATIVE (Continued) l DOSE E0UIVALENT I-131 6.1.5 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."

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 root cause(s),

corrective action, and recommendations to preclude rec 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 purposes not associated with plant functions. This category shall not include non-employees such as vending 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.

S023-0DCM 6-2 Revision 23 02-28-91

a 6.0 ADMINISTRATIVE (Continued)

OPERABLE - OPERABILITY 6.1.10 A system, subsystem, train, component or device shall be d OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or 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 6.1.11 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 B0UNDARY 6.1.12 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.

SOLIDIFICATION 6.1.13 SOLIDIFICATION shall be the conversion of radioactive wastes

,n from liquid systems to a homogeneous (uniformly distributed),

e monolithic, immobilized solid with definite volume and shape, s bounded by a stable surface of distinct outline on all sides (free-standing).

SOURCE CHECK 6.1.14 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

THERMAL POWER  !

6.1.15 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

l (s S023-0DCM 6-3 Revision 23 02-28-91

6.0 ADMINISTRATIVE (Continued)

VENTILATION EXHAUST TREATMENT SYSTEM 6.1.16 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines 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 6.1.17 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.

O 6-4 S023-0DCM Revision 25h 02-28-92

I TABLE 6-1 4  :

OPERATIONAL MODES l

REACTIVITY  % OF RATED AVERAGE COOLANT '

CONDITION. K_ff THERMAL POWER

• TEMPERATURE j

1. POWER OPERATION 2 0.99 > 5% 2 350*F

2. STARTUP 1.0.99 s 5% 1 350*F

3. HOT STANDBY < 0.99 0 2 350*F

4. HOT SHUTDOWN < 0.99 0 350* F> T,yg>200* F

5. COLD SHUTDOWN < 0.99 0 1 200*F

6. REFUELING ** 1 0.95 0 s 140*F l 4

1 l

• Excluding decay heat.  ;

• • Fuel in the reactor vessel with the vessel head closure bolts less than fully 1 tensioned or with the head removed.

l l

l 1

1 l

l i

I l

l O 6-5 S023-0DCM Revision 21 02-15-90 l

TABLE 6-2 FRE0VENCY NOTATION

.0TATION FRE0VENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 l R At least once per 18 months

• l S/U Prior to each reactor startup j l

P Completed prior to each release N.A. Not applicable Refueling Not to exceed 24 months l Interval j l

OA month is defined as a 31-day period.

I 1

l 5023-0DCM ,

6-6 Revision 22 08-02-90 1

6.0 ADMINISTRATIVE (Continued) 6.2 ' ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

• I lL 6.2.1 Routine radioactive effluent release reports covering the i

operation of the unit during the previous calendar year shall l be submitted before May 1 of each year.

! 6.2.2 The radioactive effluent release reports shall include a

. summary of the quantities of radioactive liquid and gaseous

! effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " 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,withdatasummarizedonaquarterlybasisfollowingthe 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 summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. i 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 l report period. All assumptions used in making these j assessments (i.e., specific activity, exposure time and i location shall be included in these reports. The meteorolo)gical conditions concurrent with the time of release of radioactive materials in gaseous effluents (as deteruined by sampling frequency and measurement) shall be used for  ;

determining the gaseous pathway doses. The assessment of

{

radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

• A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the Station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

/G S023-0DCM d 6-7 Revision 26 12-20-93 i

6.0 ADMINISTRATIVE (Continu:d) 6.2 ADMINISTRATIVE CONTROLS (Continued) 6.2.2 (Continued)

The radioactive effluent release report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and 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,

b. Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (s ecify whether determined by measurement or estimate ,

d. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), 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 reinse reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

5023-0DCM 6-8 Revision 26 12-20-93

6.0 ADMINISTRATIVE (Continued) 6.3 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liquid, & Gaseous) f9 Licensee initiated major changes to the radioactive waste systems (liquid

& gaseous):

V

1. Shall be reported to the Commission in the Annual Radioactive 1 Effluent Release Report for the period in which the evaluation was performed pursuant to Technical Specification 6.5.2, [ Quality S Assurance Program Description (SCE-1-A), Subsection 17.2.20.3.1.1 l upon TSIP implementation]. The discussion of each change shall '

contain:

a. A summary of the evaluation that led to the determination that i the change could be made in accordance with 10 CFR 50.59; 1

b. Sufficient detailed information to totally support the reason  ;

for the change without benefit of additional or supplemental l information;

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant 1 systems;

d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that I differ from those previously predicted in the license application and amendments thereto; O 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 liquid and gaseous effluents to the actual '

release for the period prior to when the changes are to be l made;

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 l found acceptable pursuant to Technical Specification 6.5.2,

[ Quality Assurance Program Description (SCE-1-A), Subsection p, l 17.2.20.3.1.1 upon TSIP implementation). '

2. Shall become effective upon review and acceptance pursuant to )

Technical Specification 6.5.2, [ Quality Assurance Program Description g  ;

(SCE-1-A), Subsection 17.2.20.3.1.1 upon TSIP implementation].

l t> l O S023-0DCM 6-9 Revision 29 l 07-31-96

l 6.0 ADMINISTRATIVE (Continu:d) 6.4 SASES LIOUID EFFLUENTS l 1

CONCENTRATION (1.1) l 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 B, i 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) l the Section II.A design objectives of Appendix I,10 CFR 50, i to an individual, and (2) the limits of 10 CFR 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its HPC in air

(submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

0 R0_S1 (1.2) 6.4.2 This specification is provided to implement the require-ments of Section II.A, 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 statenents 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 materia 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 I," 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.

S023-0DCM 6-10 Revision 21 02-15-90

6.0- ADMINISTRATIVE '(Continued) j 6.4 BASES (Continued)

} LIOUID WASTE TREATMENT (1.3) 6.4.3 The OPERABILITY of the liquid rad w e treatment system- )

ensures that this system will be avai.4 ale for use whenever i

j liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of

'this system be used when specified provides assurance that the i i

releases of radioactive materials in liquid effluents will be  :

I j

kept "as low as is reasonably achievable." This specification '

i 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 L

j DOSE RATE (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  :

I units on the site will be within the annual dose limits of 10

! CFR Part 20 for unrestricted areas. The annual dose limits i

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 4

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 i 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 backgrouni to an

! individual at or beyond the site boundary to less than or l

!. equal to 500 mrem / year to the total body or to less than or '

l equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid i dose rate above background to a child via the inhalation

! pathway to less than or equal to 1500 mrem / year.

l This specification applies to the release of gaseous effluents i from all reactors at the site. For units with shared radwaste i treatment systems, the gaseous effluents from the shared j system are proportioned among the units sharing that system.

j S023-0DCM

6-11 Revision 21 1

02-15-90 i

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6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

DOSE - N0BLE GASES (2.2) 6.4.5 This specification is provided to implement the requirements l of Sections II.B III.A and IV.A of Appendix I,10 CFR l Part 50. The Limiting Condition for Operation implements the j guides set forth in Section II.B of Appendix I. The ACTION  :

statements provide the required operating flexibility and at i 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 B0UNDARY. For MEMBERS OF THE PUBLIC who traverse the SITE BOUNDARY via highway I-5, the residency time shall be considered negligible and heace the dose "0". The ODCM equations provided for determiring the air doses at the SITE B0UNDARY are based upon the historical average atmospheric conditions.

DOSE - RADI0 IODINES RADI0 ACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM (2.3) 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 S023-0DCM 6-12 Revision 22 08-02-90

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i j -6.0 ADMINISTRATIVE (Continued) l l 6.4 BASES (Continued) 5

requirements in Section III.A of Appendix I that conformance

!j with the guides of Appendix I be shown by calculational i procedures based on models and data, such that the actual j exposure of an individual through appropriate pathways is a 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, l

" 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 i 1977. These equations also provide for determining the actual doses based upon the historica! average atmospheric conditions. The release rate specifications for radioiodines,

radioactive materials in particulate form and tritium are dependent on the existing radionuclide pathways to man, in the i unrestricted area. The pathways which were examined in the

! development of these calculations were: 1) individual

, inhalation of airborne radionuclides, 2) deposition of l radionuclides onto green leafy vegetation with subsequent

consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of l the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

l GASEOUS RADWASTE TREATMENT (2.4) 4 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 i

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 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 j design objectives given in Section II.D of Appendix I to 10

! CFR Part 50. The specified limits governing the use of l appropriate portions of the systems were specified as a

< suitable fraction of the dose design objectives set forth in

! Sections II.B and II.C of Appendix I,10 CFR Part 50, for gaseous effluents.

i i

i S023-0DCM 6-13 Revision 21 li 02-15-90 t

a

1 6.0 ADMINISTRATIVE (Continu:d) 6.4 BASES (Continued) l TOTAL DOSE (2.5) 6.4.8 This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the 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 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 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 I 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 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 during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle.

RADIOACTIVE 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 actual 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

t 6.0 ADMINISTRATIVE (Continued) )

6.4 BMfl (Continued) i .

?

RADI0 ACTIVE GASEOUS EFFLUENT INSTRUMENTATION (4.2) i 6.4.10 The radioactive gaseous effluent instrumentation is provided i

to monitor and control, as applicable, the releases of ,

radioactive materials in gaseous effluents during actual or i potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated in I

accordance with the procedures in the ODCM to ensure that the i alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for i monitoring and controlling the concentrations of potentially  !

i explosive gas mixtures in the waste gas holdup system. The i

OPERABILITY and use of this instrumentation is consistent with i

! the requirements of General Design Criteria 60, 63 and 64 of

Appendix A to ,

10 CFR Part 50.

1 MONITORING PROGRAM (5.1)

[ 6.4.11 The radiological monitoring program required by this specification provides measurements of radiation and of i radioactive materials in those exposure pathways and for those t j radionuclides, which lead to the highest potential radiation ,

i exposures of individuals resulting from the station operation. i This monitoring program thereby supplements the radiological '

effluent monitoring program by verifying that the measurable

! concentrations of radioactive materials and levels of

' radiation are not higher than expected on the basis of the -

effluent measurements and modeling of the environmental i exposure pathways. The initially specified monitoring program i

! will be effective for at least the first three years of j commercial operation. Following this period, program changes

! may be initiated based on operational experience.

I The detection capabilities required by Table 5-1 are state-of-

the-art for routine environmental measurements in industrial j laboratories. It should be recognized that the LLD is defined as an A oriori (before the fact) limit representing the capability of a measurement system and not as 1 posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine 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

l 6.0 ADMINISTRATIVE (Ccntinued) 6.4 BASES (Continued) I 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 pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 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 vegetation (i.e., similar to lettuce and cabbage),

and 2) a vegetation yield of 2 kg/ square meter.

INTERLABORATORY COMPARISON PROGRAM (5.3) 6.4.13 The requirement 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.

l S023-0DCM l 6-16 Revision 22 l 08-02-90