Text

Revision 22 to Unit 1 Offsite Dose Calculation Manual (ODCM)
	ML051220226
Person / Time
Site:	San Onofre
Issue date:	09/03/2004
From:	Hirsch J, Wambold J; Southern California Edison Co
To:	; Document Control Desk, NRC/FSME
References
	+sispmjr200601
	Download: ML051220226 (145)
	v • d • e

September 3, 2004 Mr. J. J. Wambold

SUBJECT:

Revision 22 to Unit 1 Offsite Dose Calculation Manual (ODCM) '

Inaccordanrce with Technical Specification D6.14.2, Revision 21 to the Unit 1 Offsite Dose Calculation Manual has been prepared and reviewed for your approval.

This'change incorporates several changes: 1)deletion of the reheater pit sump (RPS) from Unit 1 as part of ECP 040500364 and the Unit 1 demolition process, 2) removes the Plant Vent Stack monitor gas channels, including surveillance and sampling requirements, once fuel is transferred to the ISFSI, 3) deletes requirement for iodine sampling in gaseous effluents, 4) removes requirements for dissolved and entrained gases for liquid releases once fuel is transferred to the ISFSI, 5) noted extra dilution flow may be used for liquid releases, and 6) updated PVS fan flow.

This change will not adversely affect the accuracy or reliability of effluent dose calculations or set point determinations. Your approval for this revision is requested.

Copies of this letter are being forwarded to the Vice President, Nuclear Generation and Nuclear Safety Group as required by Technical Specification D6.14.2.

Please contact me if there'6re any questions.

'J.F. Hirsch Manager, Chemistry' Approved by: Aj J,/ fambold- l Vice President:

Nuclear Generation' ' -

- r -RECEIVEDO0M Attachment cc: NSG SEP 03 2004 CDM-SONGS - -

Chem File SITEFILECOPY Site File Copy SOI -ODCM

- l -

September 3, 2004

SUBJECT:

Unit 1 OFFSITE DOSE CALCULATION MANUAL Revision 22 Enclosed is Revision 22 to the Unit 1 Offsite Dose Calculation Manual (ODCM).

Per NRC Generic Letter 89-01, no Effluent/ODCM Evaluation or 50.59 reviews were required or performed for editorial changes. Effluent ODCM Evaluations (EOE) or screens have been performed as separate actions under AR 040501435.

This revision to the ODCM:

1. Removes the reheater pit sump (RPS) system as a credited release point and the associated requirements for continuous monitoring (R-2100) and periodic sampling and analysis. This supports ECP 040500364 that physically removed the system and all components from the plant as part of the ongoing decommissioning. The deletion is evaluated in action 1 of the AR.

2. Removes the Plant Vent Stack Monitor (R-1254) gas channels and the associated surveillance and planned maintenance once all fuel has been transferred to the ISFSI. As discussed in detail in action 2 of the AR, the transfer of the spent fuel removes the last potential source of noble gas.

3. Deletes requirements for iodine sampling for the airborne release point, the Plant Vent Stack, to reflect the absence of an iodine source term due to radioactive decay since the plant was shutdown in November 1992.

The deletion is evaluated in action 14 of the AR

4. Removes requirement for sampling and analysis of dissolved and entrained gases for liquid releases once the transfer of spent fuel to the ISFSI has been completed. Once the last potential source of noble gas is removed, the requirement to perform sampling and analysis of liquid effluents for dissolved and entrained gases will no longer apply. This is evaluated in action 13 of the AR.

5. Removes a missed reference to the radwaste system monitor tanks, editorial change

6. Adds note allowing for the use of additional dilution to support decommissioning efforts, particularly during final draindown of the spent fuel pool and decommissioning of the liquid radwaste processing system. This change was screened in action 4 of the AR.

7. Modifies compensatory action for an out of service sample flow measuring device on the Plant Vent Stack to reflect the removal of noble gas channel from R-1254. This is evaluated in action 15 of the AR. And

8. Updated PVS fan flow rate per AR 030600106.

None of the changes, impact the accuracy or reliability of effluent dose or setpoint calculations. The level of radioactive effluent control required by 10CFR120, 40CFR190, 10CFR50.36a and Appendix I to 10CFR50 will be maintained.

SO1-ODCM

Throughout'the document, change bars'are marked in one of four ways as follows:

A Addition D Deletion F

.. Editorial/Format change.,

.R-; Revision-Page Change lReason ii Removed the RPS system name from section 1.4.2.1. to. D

. -. reflect-ECP 040500364 iii Revised Titles for 2.3 and 2.6.2,to remove iodine. R 1-1 Added note.stating 'the noble ga's source term will .no A longerexist once fuel -is,-transferred to the ISFSI so the dissolved and entrained gas.limit will become not applicable. - ,. , , ,_

1-3 Removed the RPS from Table 1-1. Added footnote (g)toethe D & R-.

sampling requirement of, dissolved and entrained gases.

1-5 Added footnote.(g) statintg'the.requirement for dissolved A

,and entrained gases becomes.not applicable once transfer-,

of all of the spent fuel to the ISFSI has been completed and AR 040501435-16 is closed - -

1-11 Added note to allow increased dilution flow -- A 1-13 Deleted obsolete step 4 for cpm monitors and added to the . D &'A note that once transfer of,>spent-fuel.to the ISFSI is -

completed, dissolved and entrained gas limit will'not.be applicable. -- -

1-14 'Removed the RPS and deleted line about the previously :DA & R removed radwaste.system monitor tanks. Added'note to allow increased dilution flow 1-15 Removedthe RPS R '-

1-16 Removed the',RPS and removed ob'soIete step '4,for cpm D& R monitors - --.-

1-17 Removed the RPS

., . .D 1-18 Removed the'RPS D 2-1 Noted that once all fuel-is-transferred-to-the ISFSI, A-& D Specification'A..1 is not'require'd. Removed 1-131/1-133 requirement as the iodine source no longer exists.

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1L-2-2 Noted Specification 2.1.2.A is not applicable once all of A& D the spent fuel has been transferred to the ISFSI. Removed 1-131/1-133 requirement as the iodine source no longer exists.

2-3 Added note "f" to Table 2-1 deleting sampling requirements A &D for noble gas and continuous monitoring once transfer of all of the spent fuel to the ISFSI has been completed.

Removed I-131/I-133 sampling requirement as the iodine source no longer'exists.

2-5 Added note "f" to Table 2-1 deleting-requirements for A noble gas monitoring and noble gas- sampling'once transfer of all of the spent fuel to the ISFSI has been completed.

2-6 Changed applicability for specification 2.2.11from "at all A times" to "not required once transfer of all of the spent fuel to the ISFSI has been completed".

2-7 Changed applicability for specification 2.2.2 from "at all A times" to "not required once transfer of all of the spent fuel to the ISFSI has been completed".

2-8 Removed I-131/1-133 requirement as the iodine source no D longer exists.

2-9 Removed 1-131/1-133 requirement as the iodine source no D longer exists.

2-10 Noted the section on calculating setpoints for R-1254 is A not applicable once transfer of all of the spent fuel to the ISFSI has been completed.

2-11 Changed applicability for specification 2.5.1 from "at all A &R times" to "not required once transfer of all of'the spent fuel to the ISFSI has been completed". Changed PVS flow rate based on AR 030600106.

2-12 Changed applicability for specification 2.5.1 from "at all A&R times" to "not required once transfer of all of the spent fuel to the ISFSI has been completed". Changed PVS flow rate based on AR 030600106.

2-13 Changed applicability for specification 2.6.1 from "at all A times" to "not required once transfer of all of the spent fuel to the ISFSI has been completed". '

2-14 Removed! I-131/1-133 requirement as the iodine source no -

longer exists.

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2-15 Changed applicability for specification 2.7.1 from "at all A times" to "not required'once transfer'of all of'the spent fuel to the ISFSI.has been completed".

2-16 Changed applicability for specification 2.7.1 from "at all A times" to not required once transfer of all of the spent fuel to the ISFSI has been completed".

2-17 Removed I-131/I-133 requirement~asthe iodine source no D longer exists.

2-18 Removed I-131/I-133 requirement as the iodine source no D longer exists.

4-2 Removed the RPS , . ,, D 4-5 Removed the RPS D 4-7 Changed applicability for specification 4.2A..B.1 from "at 'A all times" to "not required once transfer of all of the spent'fuel to'the ISFSI has been completed".

4-8 Added footnote (7)to Table 4-3:to state that "once A&D transfer of the spent fuel to the ISFSI is completed, the noble gas monitor is not-required." Added Action 24 to item 2 to be consistent with the Action definitions.-

Deleted the charcoal sampler as the iodine source termno longer exists.

Deleted footnote (6),that discussed the installation of monitors and PIMS as no longer relevant.

4-9 'Changed action 22 of Table 4-4 to "Pnot required once A&D

transfer of all of the spent fuel to the ISFSI has been completed". Also, removed the iodine reference in Action

24. -

Modified action 26 to reflect the'fact that the PIMS R-1254 alarm window will have only the sample flow measuring device input once fuel has been completely transferred to the ISFSI and should therefore have the same 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months time interval as Action 24.

4-10 Changed applicability for specification 4.2.2.A from "at A all times" to "not required once transfer of all of the spent fuel to the ISFSI has been completed".

4 of 5 SOI -ODCM

IL 4-11 Added footnote (7)to Table 4-4 to state that 'once. A &D transfer of-the spent fuel to the ISFSI is completed, the noble gas monitor is not required." Removed surveillance requirements-for the iodine sampler.

Deleted footnote 6 that discussed station turnover of PIMS as no longer relevant. '

4-13 Removed the RPS from figure 4-1 and corrected the flow D &R path and other typos.

4-14 Modified figure 4-2 to reflect configuration of reactor R building ventilation per ECP 030600106-1.

5-26 Replaced Figures with newer versions. F thru 5-30 6-12 Modified Basis,6.4.5 to reflect that once transfer of the A spent fuel to the ISFSI is completed, the noble gas source term no longer exists and therefore the limitations of gamma and beta dose rates due to noble gas are not applicable.

6-13 Modified Basis 6.4.7 to reflect that once transfer of the A &D spent fuel to the ISFSI is completed, the noble gas source term no longer exists and therefore this basis is not applicable. Also removed reference to I-131 & I-133 from bases 6.4.8 and 6.4.9.

6-14 Removed reference to 1-131 and I-133 from base'6.4.9. D 6-15 Modified Basis 6.4.14 to reflect that once transfer of the A spent fuel' to the ISFSI is completed, the noble gas'source term no longer exists and therefore this basis is not applicable. '_'_'

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. - . .f :l OFFSITE DOSE CALCULATION MANUAL NUCLEAR ORGANIZATION UNIT 1 .

, . , . L SOI-ODCM Revision 22 09-03-04 SO1-ODCM

lL ODCM TABLE OF CONTENTS Page LIST OF FIGURES . . . . . . . . . . . . . vi LIST OF TABLES . .. .. ... ... . . vii INTRODUCTION .. .. .. ... ... . . ix 1.0 RADIOACTIVE LIQUID EFFLUENTS .. . 1-1 thru 1-23 1.1 Liquid Effluents Concentration . . . . . . . . 1-1 1.1.1 Specification . . . 1-1 1.1.2 Surveillance . . . . . . . . . . .

1-2 1.2 Liquid Effluent Dose . . . . . 1-6 1.2.1 Specification . 1-6 1.2.2 Surveillance . 1-7 1.3 Liquid Waste Treatment . . .. . . . . . . . . 1-8 1.3.1 Specification 1-8 1.3.2 Surveillance . . . 1-9 1.4 Liquid Effluent Monitor Setpoints 1-10 1.4.1 Batch Release Setpoint Determination 1-12 1.4.1.1 Liquid Radwaste Effluent Line (RT-1218) 1-14 1.4.2 Continuous Release Setpoint Determinati on 1-15 1.4.2.1 DELETED . . 1-17 1.4.2.2 Yard Sump Effluent Line (RT-2101) 1-18 1.5 Dose Calculation for Liquid Effluents ... .. . 1-20 1.6 Representative Sampling .. .. ... ... .. . 1-23 2.0 RADIOACTIVE GASEOUS EFFLUENTS .. .. ... .... . . 2-1 thru 2-38 2.1 Dose Rate . . . . . . . . . . . . 2-1 2.1.1 Specification 2-1 2.1.2 Surveillance 2-2 S01-ODCM Revision 22 ii 09-03-04 SO1-ODCM

- ODCM TABLEOF-CONTENTS (Continued)

Page 2.2 Dose, Noble Gases .. .. .. .. .. 2-6 2.2.1' Specification. 2-6 2.2.2 Surveillance .. 2-7 2.3 Dose, Tritium and Radionuclides' IR in Particulate Form . ... . . .'. . 2-8 2.3.1 Specification .. . . . . . . . ... 2-8

-2.3.2' Surveillance .'. . . . . . . . . . . . . . . 2-9 2.4 Gaseous Waste'Treatment - DELETED 2.5 Gaseous Effluent MonitorSetpoints 2-10 2.5.1 Plant Vent StackK'. 2-10 2.6 Gaseous Effluent Dose Rate . . . . . . 13 2.6.1 For Noble Gases . . . . . . 2-13 2.6.2 For Radioactive-Materials It.

in Particulate Form with Hal than Eight Days and H-3 2-14 2.7 Gaseous Effluent Dose Calculation . .. . .. .. .. 2-15 2.7.1' Dose Frorm'Noble Gases in Gaseous Effluent 2-15 2.7.1.1 For Historical Meteorology-. 2-15 2.7.1.2 For Meteorology Concurrent with Release 2-16 2.7.2 Dose From Radioactive Material in Particulate Form and H-3 . . . . . . . . 2-17 2.7.2.1 For Historical Meteorology.. . 2-17

'2.7.2.2 Foir Meteorology Concurrent with Release 2-18 SO1-ODCM Revision 22 iii 09-03-04 '

SOI-ODCM

ODCM TABLE OF CONTENTS (Continued)

Page 3.0 TOTAL AND PROJECTED DOSES . .. .. .. ... ... ... . . 3-1 thru 3-7 3.1 Liquid Dose Projection ........... . 3-1 3.2 Gaseous Dose Projection - DELETED 3.3 Dose . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-2 3.3.1 Specification .. 3-2 3.3.2 Surveillance . . . . . . . . . . . . . . . . . 3-3 3.4 Total Dose Calculations . . . . . . . . .; . . . . . . . 3-4 3.4.1 Total Dose to Most Likely Member of the Public 3-4 3.4.1.1 Annual Total Organ-Dose .. . . . . . . . . 3-5 3.4.1.2 Annual Total Whole Body Dose . . . . . 3-6 3.4.1.3 Annual Total Thyroid Dose . ... . . . . 3-7 4.0 EQUIPMENT .. 4-1 thru 4-15 4.1 Radioactive Liquid Effluent Instrumentation ... .. . . 4-1 4.1.1 Specification . . . . . . . . . . . . . . . . . 4-1 4.1.2 Surveillance . . . . . . . . . . . . . . . . . 4-4 4.2 Radioactive Gaseous Effluent Instrumentation .. ... . . 4-7 4.2.1 Specification.... . 4-7 4.2.2 Surveillance .4-10 4.3 Functionality of Radioactive Waste Equipment .. .. ... 4-12 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING . . . . ... . . . . . . . 5-1 thru 5-30 5.1 Monitoring Program .5-1 5.1.1 Specification . . . . . . . . . . . . . . . . . 5-1 5.1.2 Surveillance . . . . . . . . . . . . . . . . . 5-8 5.2 Land Use Census .. 5-12 5.2.1 Specification . . . . . . . . . . 5-12 5.2.2 Surveillance. ..... . 5-13 S01-ODCM Revision 14 iv 02-25-99 SOI-ODCM

.ODCM TABLE OF CONTENTS (Continued)

Page 5.3 Interlaboratory Comparison Program .. ... . .. . . . 5-14 5.3.1 Specification. 5-14 5.3.2 Surveillance ... ... . . . . .. . . . ..

5-15 5.4 Annual Radiological Environmental Operating Report * . .. 5-16 5.5 Sample Locations .. ............ * . .. 5-17 6.0 Administrative . . . . . . . . . . . . . . . . . . . . . 6-1 thru 6-17 6.1 Definitions . . . . . . . 6-1 6.2 Site Description . . .. . . * . .. 6-6 6.3 Administrative Controls . . . . . . . . . . . . 6-8 -;

6.4 Bases . . . . . . . . . . . . . . . . . . . . . . . 6-11 SOI-ODCM Revision 8 06-29-92 SO1-ODCM

IL ODCM LIST OF FIGURES Fioure Title Paae 4-1 SONGS 1 Liquid Waste-Discharge Systems . . . 4-13 4-2 SONGS 1 Radioactive Gaseous-Waste Systems 4-14 4-3 SONGS 1 Solid Waste Handling . . . . . . . . 4-15 5-1 Radiological Environmental Monitoring Sample Locations 1 Mile Radius . . . . . . . . . . . . . . . . . . . . . . 5-26 5-2 Radiological Environmental Monitoring Sample Locations 2 Mile Radius . . . . . . . . . . . . . . . . . . . . . . 5-27 5-3 Radiological Environmental Monitoring Sample Locations 5 Mile Radius . . . . . . . . . . . . . . . . . . . . . . 5-28 5-4 Radiological Environmental Monitoring Sample Locations Orange County . . . . . . . . . . . . . . . . . . . . . . 5-29 5-5 Radiological Environmental Monitoring Sample Locations San Diego County . . . . . ... . . . . . . . . . . . . . . 5-30 6-1 Exclusion Area .. .. .. .. ... .. . 6-7 S01-ODCM Revision 13 vi 02-27-98 SO1-ODCM

ODCM

- LIST OF TABLES Tnhlci Titlp Pane 1-1 Radioactive Liquid Waste Sampling and Analysis Program -.. . . . 1-3 1-2 Liquid Effluent Radioactive Radiation Monitor Calibration Constants .. . . . . . . . . . . . . . . . . . .... 1-19 1-3 Dose Commitment Factors, A,. ... . .. ... . . . . . . . 1-21 2-1 Radioactive Gaseous Waste Sampling and Analysis Program . . . . 2-3 2-2 Gaseous Effluent Radiation Monitor Calibration Constants - DELETED 2-3 Dose Factors For Noble Gases and Daughters ..........

. . . . . . . . . 2-19 2-4 Dose Parameters Pik . . . . 2-20 2-5 Controlling Location Factors 2-21 2-7 Dose Parameters R, for Sector P 2-22 2-8 Dose Parameters RI for Sector Q 2-24 2-9 Dose Parameters R. for Sector R 2-28 2-10 Dose Parameters RI for Sector A . .. . . . . . . . . * *. . 2-29 2-11 Dose Parameters R. for Sector B 2-30 2-12 Dose Parameters R. for Sector C 2-32 2-13 Dose Parameters RI for Sector D . . .. . . . . . 2-34 2-14 Dose Parameters R. for Sector E * . .. . . . . . . . . .* 2-35 2-15 Dose Parameters RI for Sector F 2-37 2-16 Dose Parameters R1 for Sector G :: 2-38 S01-ODCM Revision 14

vii 02-25-99 SO1-ODCM

ODCM LIST OF TABLES (Continued)

Table Title Pane 4-1 Radioactive Liquid Effluent Monitoring Instrumentation .. . . 4-2 4-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements . . . . . . . . . . . . . . . . . . . 4-5 4-3 Radioactive Gaseous Effluent Monitoring Instrumentation . . . . 4-8 4-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements . . . . . . . . . . . . . . . . . . 4-11 5-1 Radiological Environmental Monitoring Program . . . . . . . . 5-3 thru 5-6 5-2 Reporting Levels For Radioactivity Concentrations Environmental Samples ................. . . . . 5-7 5-3 Maximum Values for the Lower Limits of Detection (LLD) . . . . 5-9 5-4 Radiological Environmental Monitoring Sample Locations .. . . 5-18 thru 5-23 5-5 PIC - Radiological Environmental Monitoring Locations SONGS 1 . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-24 5-6 Sector and Direction Designation For Radiological Environmental Monitoring Sample Location Map . . . . . . . . . . . . . . . . 5-25 6-2 Frequency Notation ... ............ . 6-5 SO1-ODCM Revision 14 .

viii 02-25-99 SO1-ODCM

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

SO1-ODCM Revision 8

> ix 06-29-92 SO1-ODCM

it 1.0 RADIOACTIVE LIQUID EFFLUENTS 1.1 LIQUID EFFLUENTS CONCENTRATION 1.1.1 SPECIFICATION ApDlicabilitY: At all times.

Objective: Maintain the concentration of radioactive liquid material released from the site below 10 CFR 20 limits.

Specification: A. The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 6-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B. Table II, Column 2 for radionuclides other than dissolved-or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited to 2x104 pCi/ml until transfer of spent fuel to the ISFSI is completed. See AR 040501435-16. At that time there will be no noble gas source term.

B. Action:

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, without delay restore the concentration to within the above limits.

S01-ODCM Revision 22 1-1 09-03-04 SO1-ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued) 1.1 LIOUID EFFLUENTS CONCENTRATION (Continued).'

1.1.2 SURVEILLANCE '

Applicability: At all times'.

.Ob.iective:' To.verify that discharge of radioactive liquid material to UNRESTRICTED AREAS is maintained below 10 CFR,20 limits.

Speci fication: A. Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 1-1 B. The results of the radioactivity analyses shall be used in accordance with Section 1.4 to'assure that the concentrations at the point of release are maintained within the limits of

-Specification 1.1.1.

SO1-ODCM Revision 9 T1-2 08-04-93 SO1-ODCM

it TABLE 1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Sampling Analysis Type of Activity (LLD)

Liquid Release Type Frequency Frequency Analysis (PCi/ml)a A. Batch Waste P P Principal Gamma 5 x 10-'

Release Tanks Each Batch Each Batch Emittersc (1)Holdup Tanksb 1-131 1 x 1o-,

(2) DELETED P One Batch/M M Dissolved and 1 x l0o Entrained Gasesg (3) DELETED (Gamma Emitters)

P M H-3 1x 1lo 5 Each Batch Composited _

Gross Alpha 1 x 10-P Q Each Batch Composited Sr-89, Sr-90 5 x 10-8 Fe-55 i x 10-B. Continuous 3 x W W Principal Gamma 5 x 10'7 Release' Grab Sample Compositef Emittersc I-131 1 x 10-6 (1) DELETED M M Dissolved and 1 x lo-Grab Sample Entrained Gasesg IR (2) Yard Drain Sump (Gamma Emitters) 3x W M H-3 1x 10-5 Grab Sample Composite' Gross Alpha 1X 10-7 3 x W Q Sr-89, Sr-90 5 x 10" Grab Sample Compositef Fe-55 1 x lo-,

S01-ODCM Revision 22 1-3 09-03-04 SOI-ODCM

TABLE .1-1 (Continued)

TABLE NOTATION

a. The LLD.is defined, for.purposes of these.specifications, as the smallest.concentration of radioactive material:in a sample that will

-yield a net count (above'system background) that will;be detected with

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

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

-4.66s-LLD=

E

V 2.22 x 106 :Y* exp (-X at) where, -

LLD is "a priori" lower limitiof detection as defined above (as microcuries per-unit mass or volume).

Sb is-the standard deviation of-the background counting rate or of the counting rate of a blank sample as appropriatej(as counts'per minute).

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

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

2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, at for plant effluents is the elapsed time between.the midpoint of sample collection and time of counting, Typical values of E, V, Y and at should be used in the calculation.

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

b. 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 to assure representative sampling.

S01-ODCM Revision 11 1-4 12-06-95 SO1-ODCM

TABLE 1-1 (Continued)

TABLE NOTATION (Continued)

c. The principal,-gamma emitters for which the LLD'specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60,;Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides-are to be detected and reported. Other peaks that are measurable and'identifiable, together with the above nuclides, shall also be identified and reported.

d. A composite sample is one which results in a specimen that is representative of the liquids released.

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

f. 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.- -:

g. Once transfer of spent fuel to the ISFSI is completed, dissolved and entrained gases sampling requirement is not applicable. See AR 040501435-16.

A SOl-ODCM Revision 22 1-5 09-03-04 SOI-ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS .(Continued) 1.2 LIQUID EFFLUENT DOSE 1.2.1 SPECIFICATION ApglicabilitV: At all times.

Objective: Maintain~the release of radioactive liquid effluents from'the~site'as low as is reasonably achievable.

Specification: A. The-dos'e or'-'dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (see Figure-6-1) shall be limited:

1. During any calendar quarter to s 1.5 mrem to the total body and to *5 mrem to any organ, and

2. During any calendar year to

3 mrem to the total body and to

10 mrem to any organ.

B. Action:

1. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification D6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

S01-ODCM Revision 10 1-6 04-27-94 S0l -ODCM

It 1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued) 1.2 LIOUID EFFLUENT DOSE (Continued) 1.2.2 SURVEILLANCE Applicability: At all times.

Objective: To verify that doses due to the release of radioactive liquid effluents are as low as is reasonably achievable.

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

SO1-ODCM Revision 8 1-7 06-29-92 SO1-ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued) 1.3 LIQUID WASTE TREATMENT 1.3.1 SPECIFICATION AplPicability: At all times.

ObJective: Maintain!radioactive releases from the site as low as is reasonably achievable by use of the liquid radwaste treatment system.

Specification: A. The:liquid radwaste treatment system shall be used to.reduce the-radioactive materials in liquid wastes prior to their discharge when the projected dose due to the liquid effluent from San Onofre Unit 1, to UNRESTRICTED AREAS (see Figure 6-1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period.

B. Action

1. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification D6.9.2, a Special Report that includes the following information:

a. Explanation of why liquid radwaste was being discharged without treatment, identification of any nonfunctional equipment or subsystems and the reason for nonfunctional status.

b. Action(s) taken to restore the nonfunctional equipment to FUNCTIONAL status.

c. Summary description of action(s) taken to prevent a recurrence.

SO1-ODCM Revision 10 1-8 04-27-94 SO1-ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued) 1.3 LIQUID WASTE TREATMENT (Continued) 1.3.2 SURVEILLANCE AnDlicability: At all times.

ObJective: To verify the functionality and potential use of the liquid radwaste treatment system.

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

S01-ODCM Revision 10 1-9 04-27-94 SO -ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR SETPOINTS. '

Liquid Radwaste Effluent Line Monitors provide alarm and automatic termination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B, Table II, Column 2 at the release point to the unrestricted area. .To meet Specification 1.1.2 and for the purpose of implementation of Specification 1.1.1, the alarm/trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied:

m < MPC~f (1-1)

F+R ef where:

MPCC,, = effective'effluent maximum concentration permissible limit (pCi/ml) at the release point to the unrestricted area for the radionuclide mixture being released, 1

N ( F. (1-2) i=l t MPCJ F1 = fractional concentration of the i'h radionuclide as obtained by sample analysis.

N = number of radionuclides identified in sample analysis.

MPC, = MPC of the ith radionuclide (10CFR20, App B, Table II, Column 2).

SO1-ODCM Revision 8

1-10 06-29-92 SO1-ODCM

I.

1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR SETPOINTS (Continued)

Cm = 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 is 3,000 gpm per saltwater pump (2 total). Up to 2 pumps may be used for additional dilution as needed at approximately 6,000 gpm per A pump.

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.

SOt-ODCM Revision 22 1-11 09-03-04 SO -ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR SETPOINTS. (Continued) 1.4.1 BATCH RELEASE SETPOINT DETERMINATION The waste flow (R) and monitor setpoint (Cj)are set to meet the condition of equation (1-1) for the effective MPC

'(MPCeff) 'limit. The method by which this is accomplished is as follows:

STEP'1: The'isotopic concentration for each batch tank to be released is obtained from the sum of the measured concentrations in the tank as determined by'analysis.

C = 1 Cs +C + C + Ct + CFe CXe (1-3) where:

C '= total concentration in each tank, pCi/ml

,C' = sum of the measured concentrations for each

.,radionuclide, i, in the gamma spectrum.

'excluding Xe-133, pCi/ml Ca ' gross alpha concentration determined in the previous monthly composite sample, pCi/ml Cs = Sr-89 and Sr-90 concentrations as determined in the previous quarterly

composite sample, pCi/ml C= H-3 concentration as determined in the previous monthly composite sample, or as measured in the sample taken prior to release, pCi/ml CFe '= Fe-55 concentration as determined in the previous quarterly composite sample,

. pCi/ml CX, = Xe-133 concentration as determined by isotopic analysis, uCi/ml S01-ODCM Revision 17 1-12 07-20-00 SO1-ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR SETPOINTS (Continued) 1.4.1 BATCH RELEASE SETPOINT DETERMINATION (Continued)

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

1 MPC,,, = (1-4)

CYI/C] . VCSC Ct/C] , C,/C1 , CF./C]

Elt MPC) MPCs MPCt MPCq) MPCF@

MPCYR. MPCS, MPCt. = the limiting concentrations of the appropriate MPCF,. MPCQ radionuclide from 10CFR2O, Appendix B, Table II, Column 2.

NOTE: Once transfer of spent fuel to the ISFSI is completed, the noble gas source term no longer 1A exists and this note is not applicable. For dissolved or entrained noble gases, the concentration shall be limited to 2.ME-4 pCi/ml total activity.

STEP 3: The radioactivity monitor setpoint C., pCi/ml, may now be specified based on the values of C.

CIY F. MPCef and R to provide compliance with the limits of 10CFR20, Appendix B, Table II, Column 2.

1)

DELETED (1-6)

SOL-ODCM Revision 22 1-13 09-03-04 SO1-ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR SETPOINTS (Continued) 1.4.1 BATCH RELEASE SETPOINT DETERMINATION (Continued) 1.4.1.1 LIQUID RADWASTE EFFLUENT LINE (RT-1218)

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

r (RW) (F+R) ( C')

US k X-JJ (R) t MPC l where: RW = Radwaste Effluent discharge

-,administrative value.

F = dilution water flow in volume per unit time.

=- 3000 gpm per saltwater pump (2 total).

Additional flow, up to 2 pumps of approximately 6,000 gpm per pump, may be used on a case by case basis.

.il , I $:.

x-c -,

-=!

total gamma isotopic concentration, excluding Xe-133, yCi/ml.

-Radwaste holdup tanks R - -. 50 gpm/pump (x no. of pumps to be run)

C = total gamma concentration in each ID batch sample.

It

I, fo e MPCe,,-.-1= - -from equation (1-4) .

RW and S21,1 are administrative values used for simultaneous releases from the Radwaste Effluent discharge and the Yard Drain Sump. The fractions RW and S2101 will 1 be assigned such that (RW + S2101)

1.0. The 1.0 is an administrative value used to account for the potential activity for all release pathways. 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 10CFR20, Appendix B, Table II, Column 2 from the site.

NOTE: If C. s EiC'yi, then no release is possible. To increase Cm, increase dilution flow F (by running more pumps in the applicable discharge structure), and/or decrease the effluent flow rates R (by throttling the combined flow as measured on CV11O) and recalculate C. using the new F, R and equation (1-5).

SO1-ODCM Revision 22 1-14 09-03-04 SO1-ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued) 1.4.2 CONTINUOUS RELEASE SETPOINT DETERMINATION STEP 1: The isotopic concentration for the continuous release is obtained for the yard sump from the sum of the measured concentrations as determined by analysis:

C i 1 Y1 + C(+S+ C t + CFe + CXe (1-3) where:

C = total concentration, pCi/ml ElC' = total gamma activity associated with each radionuclide, i, in the weekly composite analysis for the release stream, excluding Xe-133, pCi/ml.

C= total measured gross alpha concentration determined from the previous monthly composite analysis for the release stream, pCi/ml.

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

Ct= total measured H-3 concentration determined from the previous monthly composite analysis for the release stream, pCi/ml.

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

Cxe- = Xe-133 concentration as determined by isotopic analysis, ACi/ml S01-ODCM Revision 22 1-15 09-03-04 SO1-ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS -(Continued) I 1.4 LIQUID EFFLUENT MONITOR SETPOINTS -(Continued) 1.4.2 CONTINUOUS RELEASE SETPOINT DETERMINATION (Continued)

STEP 2: The effective MPC (MPCff) for the yard drain sump isdetermined using:

1 MFLeffr =

I CI/C] + CS/C] +( C/C + ( CFe/ C + _) (1-9)

MPCI MPCsJ MPCa MPC FeJ MPCt (

STEP 3: The setpoint (pCi/ml), for the yard drain sump Iy radioactivity monitor may now be specified based on the values of C, E1CIV, F, MPCff, and R to IQ provide compliance with the limits of 10CFR20, Appendix B. Table II, Column 2.

DELETED (1-6)

S01-ODCM Revision 22 1-16 09-03-04 SO1-ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR SETPOINTS" (Continued) 1.4.2 CONTINUOUS RELEASE SETPOINT-DETERMINATION (Continued) 1.4.2.1 DELETED (1-11) ID This page intentionally left blank.

S01-ODCM Revision 22 1-17 09-03-04 SO1-ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR SETPOINTS (Continued) 1.4.2 CONTINUOUS RELEASE SETPOINT DETERMINATION (Continued) 1.4.2.2 YARD SUMP EFFLUENT LINE (RT-2101)

The value of C2101, the concentration limit at the detector, pCi/ml, is determined using:

C1 S (S 2101) (F R) ERCe (1-12) where:

C2101 = limiting concentration at monitor RT-2101, pCi/ml.

C, ' i MPCefS= values of C, FiC' 1 and MPCeff (defined in STEPS 1 and 2 above)

R= 1000 gpm/pump (x no. sump pumps to be run)

RW and S2,1, are administrative values used for Io simultaneous releases from the Radwaste Effluent discharge ID and the Yard Drain Sump. The fractions RW and Scan will ID be assigned such that (RW + S2101) s 1.0. The 1.0 is an 1 administrative value used to account for the potential activity for all release pathways. 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 10CFR20, Appendix B, Table II, Column 2 from the site.

NOTE: If C2101

LC'lI, then no release is possible.

To increase C2101, increase the dilution flow F (by running more pumps) and recalculate C210 1 using the new value of F and equation (1-12).

S01-ODCM Revision 22 1-18 09-03-04 SO1-ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued)

Table 1-2 This page intentionally left blank.

SO1-ODCM Revision 21 1-19 02-26-04 SO1-ODCM

1.5 DOSE CALCULATION FOR LIQUID EFFLUENTS The liquid releases considered'in the following.dose calculations are described in Section 1.4. The dose commitment.to an individual from radioactive materials in liquid effluents released to unrestricted -

areasare calculated for:the purpose of implementing Specification

.. 1.2.1 using the following expression.

D = l C F (1-13)

'-' where:

j. .

Ai, = site related adult ingestion dose commitment factor to the total body or an organ, l, for each identified principal gamma and beta emitter, i, from Table 1-3, mrem/hr per pCi/ml.

n number of principal gamma and beta emitters,.i.

., CIJ = average concentration-of radionuclide, i,-in the undiluted liquid effluent during time period, atj, -pCi/ml.

m = number of time periods,' j.

DI - dose commitment to the total body or an organ, x, from the liquid'effluent for the-time period, At1,,mrem.'

= average dilution factor (actually mixing ratio) for C,'

during the time period, Lte. This factor is the ratio of the maiimum-'ndiluted,-Iiquid waste flow during time period, at- to'the average flow from the'site discharge structure unrestricted receiving waters, or . .I

.maximum liquid radioactive waste flow -

discharge'structure exit flow Atj = length of the j'th. time period over which Cj and FJare averaged for'all liquid releases, hours.

S01-ODCM Revision 9 1-20 08-04-93 SO1-ODCM

ii_

TABLE 1-3 DOSE COMMITMENT FACTORS%, Al, (mrem/hr Der uCi/ml)-

Radio- Total . 1 Nuclide _ Bone Liver I Body IThyroid 4Kidney Lung GI-LLI H-3 2.82E-I 2.82E-1 2'.82E-1 2.82E-1 2.82E-1 2.82E-1 Na-24 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 Cr-51 5.58E+O 3.34E+O 1.23E+O -7.40E+O 1.40E+3 Mn-54 7.06E+3 1.35E+3 2.10E+3 2.16E+4 Mn-56 1.78E+Z 3.15E+1 2.26E+2 5.67E+3 Fe-55 5.11 E+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.O1E+2 5.40E+2 1.83E+4 Zn-65 1.61E+5 5.13E+5 2.32E+5 3.43E+5 3.23E+5 Br-84 9.39E-2 7.37E-7 Rb-88 1.79E+0 9.49E-1 2.47E-l1 Sr-89 4.99E+3 1.43 E+2 8.OOE+2 Sr-90 1.23E+5 3.01E+4 3.55E+3 Sr-91 9.18E+1 3.71E+O 4.37E+2 Sr-92 3.48E+1 1.51E+0 6.90E+2 Y-90 6.06E+O 1.63E-1 6.42E+4 Y-9lm 5.73E-2 2.22E-3 1.68E-1 Y-9z 5.32E-1 1.56E-2 9.32E+3 Zr-95 1.59E+1 5.11E+O 3.46E+0 8.02E+0 1.62E+4 Zr-97 8.81E-1 1.78E-1 8.13E-2 2.68E-1 5.51E+4 Nb-95 1.84E+O 1.03E+O 5.51E-1 1.01E+O 6.22E+3 Nb-95m 1.84E+O 1.03E+O 5.51E-1 1.01E+O 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 2.01 E+2 3.06E+3 1.03E+5 Ag-lOrm 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+O 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 I- 132 1.06E+1 2.85E+1 9.96E+O 9.96E+2 4.54E+1 5.35E+O I -133 7.45E+1- 1.30E+2 3.95E+1 1.90E+4 *2.26E+2 1.16E+2 1 -134 5.56E+O 1.51E+1 5.40E+O 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

Sources: 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 SO1-ODCM Revision 9 1-21 08-04-93 SO1-ODCM

TABLE 1 DOSE COMMITMENT FACTORS, A, (mrem/hr per pCi/mi)

Radio- Total Nuclide Bone Liver Body Thyroid Kidney .-

Lung GI-LLI Cs-134 6.84E+3 1.63E+4 1.33E+4,' 5.27E+3 1.75E+3 2.85E+2 Cs-136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21E+2 Cs-137 8.77E+3 1.20E+4 7.85E+3 -4.07E+3 1.35E+3 2.32E+2 Cs-138 6.07E+0 1.20E+1 5.94E+O 8.81E+O 8.70E-1 5.12E-5 Ba-139 7.85E+O 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+O 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+O 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

Sources: 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 S01-ODCM Revision 9 1-22 08-04-93 SO1 -ODCM

1.0 RADIOACTIVE 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-5.23, "Generating Effluent Releases Permits Using The VAX Computer" and S0123-III-5.2.1 "Unit 1 Radioactive Liquid Radwaste Sampling and Analysis".

S01-ODCM Revision 17 1-23 07-20-00 S01.-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS ,

2.1 DOSE RATE 2.1.1 SPECIFICATION App1 icabiliitv: -At all times.- Once transfer of spent fuel to the ISFSI is,completed, the noble gas source term no

- longer exists and specification A.1 is not A

-applicable.- See:AR 040501435-16.

Objective: 'Maintain thedoseirate at the exclusion area boundary from radioactivegaseous effluents within 10 CFR 20 limits. .

I Snecificatiion: :A.: The~dose.rate due to radioactive materials released,.in-gaseous effluejnts from the site to areas at and beyond the SITE BOUNDARY (see Figure 6-1),shall be limited to the following values:

1. LiThe dose-rate limit for noble gases shall

-be s,.500 mrem/year to the total body and

.-3000imrem/year to the skin, and 2.:,.The dose rate limit for tritium and for all ID

-radionuclides in particulate form with half lives greater than 8 days shall be

1500 mrem/year to any organ.

B. Action With the dose rate(s) exceeding the above limits, without delay restore the release rate to within the above limit(s).

S01-ODCM Revision 22 2-1 09-03-04 SO1-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.1 DOSE RATE (Continued) 2.1.2 SURVEILLANCE Applicability: At all times. Once transfer of spent fuel to the ISFSI is completed, the noble gas source term no longer exists and specification "A" is not A applicable. See AR 040501435-16.

ObJective: To verify the dose rate due to the discharge of radioactive gaseous effluents is maintained within 10 CFR 20 limits.

Specification: A. The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of Specification 2.1.1 in accordance with Section 2.5.1.

B. The dose rate due to tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the limits of Specification 2.1.1 in accordance with Section 2.5.2 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 2-1.

SOI-ODCM Revision 22 2-2 09-03-04 SO1-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS- (Continued)

TABLE 2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit

-Minimum of Detection Sampling .Analysis, Type of Activity (LLD)a Gaseous Release Type Frequency Frequency' . Analysis (pCi/ml)

Plant Stack M M Principal Gamma 1 x lo-,

Grab : Emittersb Sample'f__ IA

- H-3 1 x lo0 DELETED ___' ID Continuousd We Principal Gamma 1 x 10o-,

Particulate Emittersb Sample Continuousd M Gross Alpha 1 x lo-,

Composite Particulate Sample Continuousd Q Sr-89, Sr-90 1 x 101-1 Composite Particulate Sample Continuousdf Noble Gas Noble Gases 1 x lo-, IA

-Monitor- Gross'Beta'or Gamma

. . . I .

S01-ODCM Revision 22 2-3 09-03-04 SO -ODCM

TABLE 2-1 (Continued)

TABLE NOTATION

a. The LLD is defined, for purposes of these specifications as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with a 95%

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

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

4.66 sb LLD = b E V 2.22 x 106

Y* exp (-X At) where, LLD is 'a priori" lower limit of detection as defined above (as microcuries per unit mass or volume).

Sb is the standard deviation of the background counting rate or of the counting rate of atblank sample as appropriate (as counts per minute).

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

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

2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, At for plant effluents is the elapsed time between the midpoint of sample collection and time of counting, 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 Driori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

b. The principal gamma emitters for which the LLD specification applies are exclusively 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, Cs-137, Ce-141, and Ce-144 for particulate emissions.

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

S01-ODCM Revision 11 2-4 12-06-95 SO1-ODCM

,TABLE 2-1 (Continued)

TABLE NOTATION (Continued) c..Tritium grab samples shall be taken.at least once per,7 daysfrom the ventilation exhaust from the spent fuel area. whenever spent fuel is in the spent fuel pool.

d. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the,.time period covered by each dose or dose rate.calculation made An accordance with Specifications 2.1.1, 2.2.1, and 2.3.1.

e. Samples-shall-be changed at least.once per 7 days and-analyses;shall be

-completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months afterchanging, or after removal from sampler.

f. *Onc'e transfer of spent fuel to the ISFSI is completed, continuous noble gas monitoring and grab sampling are no longer required. See AR 040501435-16.

S01-ODCM

. I Revision 22 2-5 09-03-04.

S0l -ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.2 DOSE. NOBLE GASES 2.2.1 SPECIFICATION Applicability: At all times. Once transfer of spent fuel to the ISFSI is completed.-the noble-gas source term no longer exists and this specification is not A applicable. See AR 040501435-16.

Objective: Maintain the dose;due to noble'gases in gaseous effluents as low as is reasonably achievable.

Specification: A. The air dose'due to'noble gases released in gaseous'effluents from San Onofre Unit 1 to areas at and beyond the SITE BOUNDARY (see Figure 6-1) shall be limited to the following:

1. During any calendar quarter: s 5 mrad for gamma radiation and

10 mrad for beta radiation.

2. During any calendar year: s 10 mrad for gamma radiation and

20 mrad for beta radiation.

B. Action:

1. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification D6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and.the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

S01-ODCM Revision 22 2-6 09-03-04 SO1-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS. (Continued) 2.2 DOSE. NOBLE GASES (Continued) 2.2.2 SURVEILLANCE Applicability: At all times. Once transfer of spent fuel to the ISFSI is completed, the noble gas source term no longer exists and this specification is not A applicable. -See AR 040501435-16.

Objective: To verify the dose due to noble gases in radioactive gaseous effluent is maintained as low as is

,reasonably achievable.

Specification: Cumulative-dose contributions for noble gases for the current-calendarquarter and current calendar year shall be determined in accordance with Section 2.7.1

.at least once per 31 days.

S01-0DCM 7 Revision 22 2-7 09-03-04 SO1-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.3 DOSE. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM ID 2.3.1 SPECIFICATION Appl icability: At all times.

Objective: Maintain the dose due to radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents as low as is reasonably achievable.

Specification: A. The dose to a MEMBER OF THE PUBLIC from tritium and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from San Onofre Unit 1 to areas at and beyond the SITE BOUNDARY (see Figure 6-1) shall be limited to the following:

1. During any calendar quarter:

7.5 mrem to any organ; and

2. During any calendar year: s 15 mrem to any organ.

B. Action:

1. With the calculated dose from the release of tritium and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification D6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

S01-ODCM Revision 22 2-8 09-03-04 SOI-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS. (Continued) 2.3 DOSE. TRITIUM AND RADIONUCLIDES IN 'PARTICULATE FORM (Continued) It 2.3.2 SURVEILLANCE Applicability: At all times.

Objective: To verify the dose due to tritium and radionuclides in particulate form with half-lives greater than 8 days is maintained'as low as is reasonably achievable.-:

Specification: Cumulative-dose contributions for the current calendar quarter and current calendar year for tritium and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with Section 2.7.2 at least once per 31 days.

2.4 GASEOUS RADWASTE TREATMENT 2.4.1 DELETED S01-ODCM Revision 22 2-9 09-03-04 SO1-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.5 GASEOUS EFFLUENT MONITOR SETPOINTS Once transfer of spent fuel to the ISFSI is completed, the noble gas source term no longer exists and this specification is not applicable. A See AR 040501435-16.

2.5.1 PLANT VENT STACK 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 meteorological dispersion factor.

Total Body (0.03) (2120 'm) ( 500 mrem/yr)(10-6 mi/cc)

Cdtcf)(xQ se 3m),(K mrem/yr j~C '

(Flow rate, cfm)(X/Q sec/m C ) (2-1)

Skin (0.03) 12120 /

cfM 3000 mrem/yr) (106 M3/cc)

Cdet m /sec 3)mem/yr C1 22 (Flow rate, cfm) (X/Q, sec/m) L (L+ 11 mr 3 Cto (2-2)

+1.M 1 pCi/in S01-00CM Revision 22 2-10 09-03-04 SO1-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) .

2.5 GASEOUS EFFLUENT MONITOR SETPOINTS (Continued)

- Once transfer of spent fuel to the ISFSI is completed, the noble gas source term no longer exists and this specification is not applicable. A See AR 040501435-16.

2.5.1 PLANT VENT STACK (Continued) where:.

Cdet = instantaneous concentration at the detector, pCi/cc 0.03 = an administrative factor used to account for potential activity from other airborne release pathways on Site, .

K- total body dose conversion factor for the ijh gamma emitting noble gas, from Table 2-3, mrem/yr per pCi/n3 L, = skin dose conversion factor for the ijh noble gas, from Table 2-3, mrem/yr per pCi/M 3 M, air dose conversion factor for the ith

-.noble3 gas, from Table 2-3, mrem/yr per pCi/Mn 1.1 - = conversion factor to convert gamma air dose to skin dose.

3000 mrem/yr =.skin dose rate limit, as specified by Specification 2.1.1 500 mrem/yr = total body dose rate limit, as specified by Specification 2.1.1 C, = concentration of the ith noble gas, as determined by sample analysis, pCi/cc

.Ctot ..=,total concentration of noble gases, as determined by sample analysis, pCi/cc Flow Rate = plant vent flow rate, cfm

= 25,000 cfm/fan (x no. of fans to be run) IP 2120 = conversion constant, cfm to m3/sec X/Q = historical annual average dispersion factor for any landward sector

= 1.3E-5 sec/r3 SO1-ODCM Revision 22

.2-11 09-03-04 SO1-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.5 GASEOUS EFFLUENT MONITOR SETPOINTS (Continued)

Once transfer of spent fuel to the ISFSI is completed, the noble gas IN source term no longer exists and this specification is not applicable.

See AR 040501435-16. IA 2.5.1 PLANT VENT STACK (Continued)

RT-1254. Wide Range Gas Monitor The maximum release rate, pCi/sec, is determined by converting the concentration at the detector, Cdet, to an equivalent release rate, pCi/sec, as follows:

Amx = (Cd~t, pCi/cc) (flow rate, cc/sec) (2-3) where:

A.. = maximum permissible release rate Cdet = smaller of the values of Cdt obtained from equations (2-1) and (2-2).

Flow Rate = vent stack flow rate, cc/sec

= 1.18 x 107 cc/sec x (number of fans)

The release rate setpoint shall 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.

S01-ODCM Revision 22 2-12 09-03-04 SO1-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS .(Continued) 2.6 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:

2.6.1 FOR NOBLE GASES:

Once transfer of-spent fuel to the ISFSI is completed, the noble gas source term no longer exists and this specificationis not applicable. See AR 040501435-16.

DIB = E1 lK 1(x/Q) Q1 l (2-7)

. . .1

= I[C(LI + 1.1M1) (X7Q) Q. l (2-8) where:

DT 8 = total bodydose rate in unrestricted areas due to airborne radioactive effluents, mrem/yr.

D = skin dose rate in unrestricted areas due to airborne radioactive effluents, mrem/yr.

Ki = total body dose factor due to gamma emissions for-each identified noble gas radionuclide, i, from Table 2-3, mrem/yr per pCi/r3.

L = skin dose factor due to the beta emissions for each identified noble gas radionuclide, i, from Table 2-3, mrem/yr per pCi/m 3 M = air dose factor due to gamma emissions for each identified noble gas radionuclide, i, from Table 2-3, mrad/yr per pCi/M 3 (Unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose.)

I = measured or calculated release rate of radionuclide, i, pCi/sec (X7U) = 1.3E-5 sec/m 3 . The maximum annual average atmospheric dispersion factor for any area at or beyond the unrestricted area boundary for a landward sector.

S01-ODCM Revision 22 13 09-03-04 SO1-ODCM

1.

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.6 GASEOUS EFFLUENT DOSE RATE (Continued) 2.6.2 FOR RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN EIGHT DAYS AND H-3:

Do= I Q1] (2-9) o = organ dose rate in unrestricted areas due to airborne effluents, mrem/yr

= measured or calculated release rate of radionuclide, i, pCi/sec Pik = dose parameter for radionuclide, i, for pathway, k, from Table 2-4 for the inhalation pathway, mrem/yr per pCi/m3 . The dose factors are based on the critical individual organ and the child age group.

Wk = highest calculated annual average dispersion parameter for estimating the dose to an individual at or beyond the unrestricted area boundary for pathway k.

= (X/Q), 1.3E-5 sec/r3 for the inhalation pathway.

The location is the unrestricted area in the NW sector.

= (p7IQ), 7.2E-8 sec/r3 for the food and ground pathways. The location is the unrestricted area in the NW sector.

SO1-ODCM Revision 22 2-14 09-03-04 SO1-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.7 GASEOUS EFFLUENT DOSE CALCULATION 2.7.1 DOSE FROM NOBLE GASES IN GASEOUS EFFLUENT Once transfer of spent fuel to the ISFSI is completed, the noble gas source term no longer exists and this A specification is.not applicable.. See AR 040501435-16.

The gaseous-releases:considered in the following dose calculations are described in Section 2.5.1. The air dose in unrestricted areas due to noble gases released in

-gaseous effluents is calculated using the following expressions: .

2.7.1.1 FOR HISTORICAL METEOROLOGY:

D = 3.17x10-8 z1 [Mi :(X/Q) Qu] (2-10)

D= 3.17x10 B Ej [N' (X/Q) Qu] (2-11) where:

DY = total gamma air dose from gaseous

- effluents, mrad Da = total beta air dose from gaseous effluents, mrad MN = -air dose factor due to gamma emissions for each identified noble gas radionuclide, i,

-from Table 2-3, mrad/yr per pCi/mr 3 N. = !air dose due to beta emissions for each identified noble gas radionuclide, i, from Table 2-3. mrad/yr per pCi/r 3

-d) - : 1.3E-5 sec/mr 3. The maximum annual average atmospheric dispersion factor for any area

- at or beyond the unrestricted area boundary

e.for a landward sector.

.. . -, (.

.-amount of noble gas radionuclide, i.

released in gaseous effluents, pCi.

.3.17x 108.,= -inverse seconds/year S01-ODCM Revision 22 2-15 09-03-04 SO1-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.7 GASEOUS EFFLUENT DOSE CALCULATION (Continued) 2.7.1 DOSE FROM NOBLE GASES IN GASEOUS EFFLUENT (Continued)

Once transfer of spent fuel to the ISFSI is completed, the noble gas source term no longer exists and this specification is not applicable. See AR 040501435-16.

2.7.1.2 FOR METEOROLOGY CONCURRENT WITH RELEASE:

NOTE: Consistent with the methodology provided in Regulatory Guide 1.109 and the following equations, quality affecting computer software is used to perform the actual calculations.

Doe = 1.14x0l4 z1 [MlEi (Atjt(X/Q)Jo Qi14 (2-12)

Do= 1.14xlo 4 1[Nz (6ti (X/Q)io Q;4) (2-13) where:

Dy= total gamma air dose from gaseous effluents in sector e, mrad DON = total beta air dose from gaseous effluents in sector e, mrad M= air dose factor due to gamma emissions for each identified noble gas radionuclide, i, from Table 2-3. mrad/yr per pCi/m3 N, = air dose factor due to beta emissions for each identified noble gas radionuclide, i, from Table 2-3. mrad/yr per pCi/M3 at= length of the jth time period over which (X/Q)je and k are averaged for gaseous releases, hours (X/Q)j, = atmospheric dispersion factor for time period, at at exclusion boundary location in landwarA sector e determined by concurrent meteorology, sec/m3 QI= average-release rate of radionuclide, i,in gaseous effluents during time period, Ati, pCi/sec 1.14 x10' = inverse hours/year S01-ODCM Revision 22 2-16 09-03-04 S01-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) -

2.7 GASEOUS EFFLUENT DOSE CALCULATION (Continued)-

-27.2 DOSE FROM RADIOACTIVE MATERIAL IN PARTICULATE FORM AND N-3 lb The dose to an individual from radioactive materials in ID particulate-form with'half lives .greater.than:eight days and H-3 in gaseous effluents released to unrestricted areas is-calculated using the following expressions:

2.7.2.1 FOR HISTORICAL-METEOROLOGY:

SD0 = 3.17x10i .z[1 i(RlkW) Qu] (2-14) where:

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

= amount of radioactive materials in particulate form and radionuclides other than noble gases

-with half lives greater.than eight days, i,

- released in gaseous effluents, pCi

-kRIAWk = sum of all pathways k for radionuclide, i, of the R1*

W product,-nmrem/yr per pCi/sec. The EkRjkWk value for each radionuclide, i, is given in Table 2-5. The value given is the maximum XkRikWk for all locations and is based 'on the most restrictive age groups.

Rik = dose factor for each identified radionuclide, i, for, pathway k (for the inhalation pathway, mrem/yr. per pCi/m3 and for the food and ground

iplane pathways, m2-mrem/yr per pCi/sec at the controlling location. The R. 's for each age group are;given in Tables 2-6 thru 2-16. Data

. in these tables are derived using the NRC code, PARTS. (See the annual update of revised R.

parameters based on changes in the Land Use

-Census;provided by Corporate Health Physics and Environmental.)

~ 'annual a:Verage dispersion parameter for

'estimatingthe dose to an individual at the

-coitrolling location for pathway k.

.'(XZ)for'the .inhalation pathway, sec/m3. The

- (X/Q) f6ir each controlling location is given in

'-Tables'2-6 thru 2-16.

-= (P ) for the food and ground plane pathways,

.:m. The (D/Q) for each controlling location are given in Tables 2-6 thru 2-16.

S01-ODCM Revision 22

2-17 09-03-04 SO1-ODCM

1I 2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued)'

2.7 GASEOUS EFFLUENT DOSE CALCULATION (Continued) 2.7.2 DOSE FROM RADIOACTIVE MATERIAL IN PARTICULATE FORM AND H-3 1D (Continued) 2.7.2.2 FOR METEOROLOGY CONCURRENT WITH RELEASES:

NOTE: Consistent with the methodology provided in Regulatory Guide 1.109 and the following equations, quality affecting computer software is used to perform the actual calculations.

lImn D= 1.14 x 10-' EE [(Att) (RIke) (Wjke) (Q1) J (2-15) where:

De = total annual dose from gaseous effluents to an individual in sector 9, mrem.

length of the jth period over which Wjke and'Qj are-averaged for gaseous releases, hours Q, = average release rate of radionuclide, i, in gaseous effluents during time period atp, pCi/sec Rike = dose factor for each identified radionuclide i, for pathway k for sector 9 (for the inhalation pathway, mrem/yr per pCi/n 3 , and for the food and ground p1ane pathways, m2 mrem/yr per pCi/sec) at the controlling location.

The dose factor is based on the maximum dose to the most restrictive age group. A listing of Rik for the controlling locations in each landward sector for each group is given in Tables 2-6 thru 2-16.

The e is determined by the concurrent meteorology.

Wake = dispersion parameters for the time period At for each'pathway k for calculating the dose io 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 S01-ODCM Revision 22 2-18 09-03-04 SO1-ODCM

. TABLE 2-3 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Total Body Dose- --SkinDose Gamma Air Dose Beta-Air-Dose Factor K, Factor L1 Factor M, Factor N:

Radio- (mrem/yr I (mrem/yr (mrad/yr' (mrad/yr Nuclide per pCi 3 ) )p per p per pCi/m 3 ) per pCi/m3)

Kr-85m 1.17E+3 1.46E+3 1.23E+3I 1.97E+3 Kr-85 1.61E+1 1.34E+3 1.72E+1 1.95E+3 Kr-87 5.92E+3 9.73E+3 6.17E+3 1. 03E+4 Kr-88 1.47 E+4 2.37E+3 1.52E+4 2.93E+3 Xe-131m 9.15E+1 4i76E+2 1.56E+2 1.11 E+3 I' i ,

Xe-133m 2.51E+2 9.94E+2 3.27E+2 1.48E+3 Xe-133 2.94E+2 3.06E+2 3.53E+2 1. 05E+3 Xe-135r 3.12E+3 7.11 E+2 3.36E+3 7.39E+2 Xe-135 1.81 E+3 1.-86E+3 1.92E+3 2.46E+3 Xe-138 8.83E+3 4.13E+3 9.21E+3; 4.75 E+3 Ar-41 8.84E+3 2.69E+3 9.30E+3; 3.28E+3 t

i

., .... - .-j .- ..-

I a a "Source: USNRC Reg. Guide 1.109, Table B-1 SO1-ODCM Revision 8

'2-19 06-29-92 SO0 -ODCM

TABLE 2-4

DOSE PARAMETER Pj1 CHILD AGE GROUP CRITICAL ORGAN Iinhalation Radionuclde I(mrem/yr Inhalation Pathwa perPCi/m) I Radionuclide Pathway (mrem/yr per KCi/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 1.1E+6 I -135 7.9E+5 Co-60 7.1E+6 Cs-134 1.OE+6 Sr-89 2.2E+6 Cs-136 1.7E+5 Sr-90 1.OE+8 Cs-137 9.1E+5 Zr-95 2.2E+6 Ba-140 1.7E+6 Nb-95 6.1E+5 Ce-141 5.4E+5 Ru-103 6.6E+5 Ce-144 1.2E+7 Te-129m 1.8E+6

Source: USNRC NUREG-0133, Section 5.2.1.1 S01-ODCM Revision 8 2-20 06-29-92 SO1-ODCM

.TABLE 2-5 CONTROLLING LOCATION FACTORS'

-kRikWk Radionuclide I mrem/yr per PCi/sec- Use:

H -3 2.15E-3 ; B: Camp Mesa

' Cr-51 1.03E-1 ' B: Camp Mesa Mn-54 2.38E+1t B:. Camp. Mesa I'; Co-57 .5.15E+O B: Camp .Mesa Co-58 t 8.04E+O B: Camp Mesa

-Co-60 3.34E+2 i B:' Camp Mesa Sr-89-, 4.96E+1-^-' Q: SC Ra'n'ch (No. Res';.)

Sr-90 2.08E+3 Q: SC Ranch (No.Res.)

Zr-95 8.42E+O B:. Camp'Mesa

- Nb-95 6.90E+O E: Deer Consumer/Hunter Ru-103 1.09E+1< E: Deer Consumer/Hunter Te-129m 4.96E+O E: Deer Con'sumer/Hunter

'Cs-134 1'.02E+2 B:. Camnp Mesa

'Cs-136 2.24E+ ' B:: Camp Mesa Cs-137 1.53E+2 B: Camp Mesa Ba-140 3.73E+D B: Camp'Mesa Ce-141 1.25E+O B: Camp Mesa Ce-144 2.36E+1 Q: Camp Mesa

- -131 2.79E+1 Q:; Camp Mesa 1 -132 3.46E-1 B:', Camp Mesa 1-133 6.67E+O, B: Camp Mesa I'-134 9.26E-2 B: Camp Mesa

'I -135 1.36E+O B: Camp Mesa

'UN-ID 1.30E+1 : B:' Camp' Mesa

.. I .

I

___________________________________________________ -I These values to be used in manual calculations are the maximum

£kRkWk for all locations based on the most restrictive age group.

SO1-ODCM Revision 21

'2-21 02-26-04 SO1- ODCM

TABLE 2-7 DOSE PARAMETER R. FOR SECTOR P Page 1 of 2 Pathway = Surf Beach/Life Guard Distance = 0.4 miles X/Q = 2.7E-6 sec/m 3 D/Q 1.2E-8 mn2 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 -O- -O- 7.8E+0 -O- 4.2E+1 -O- 9.6E+1 -O-Cr-51 -O- -O- 1.2E+2 3.2E+4 6.9E+2 1.5E+5 1.1E+3 3.5E+5 Mn-54 -O- -O- 1.1E+4 9.5E+6 6.5E+4 4.5E+7 1.1E+5 1.1E+8 Co-57 -O- -O- 3.5E+3 2.4E+6 1.9E+4 1.1E+7 2.8E+4 2.6E+7 Co-58 -O- -O- 7.6E+3 2.6E+6 4.4E+4 1.2E+7 7.1E+4 2.9E+7 Co-60 -O- -O- 4.9E+4 1.5E+8 2.9E+5 7.OE+8 4.5E+5 1.6E+9 Sr-89 -O- -O- 1.5E+4 1.5E+2 7.9E+4 7.1E+2 1.1E+5 1.6E+3 Sr-90 -O- -O- .7.OE+5 -O- 3.5E+6 -O- 7.5E+6 -O-Zr-95 -O- -O- 1.5E+4 1.7E+6 8.8E+4 8.2E+6 1.3E+5 1.9E+7 Nb-95 -O- -O- 4.2E+3 9.4E+5 2.5E+4 4.5E+6 3.8E+4 1.OE+7 Ru-103 -O- -O- 4.6E+3 7.5E+5 2.6E+4 3.6E+6 3.8E+4 8.3E+6 Te-129m -O- -O- 1.2E+4 1.4E+5 6.5E+4 6.4E+5 8.8E+4 1.5E+6 Cs-134 -O- 7.OE+3 4.7E+7 3.7E+4 2.2E+8 6.5E+4 5.2E+8 Cs-136 -O- -O- 1.2E+3 1.OE+6 6.3E+3 4.9E+6 1.1E+4 1.1E+7 Cs-137 -O- -O- 6.3E+3 7.1E+7 2.8E+4 3.4E+8 4.7E+4 7.8E+8 Ba-140 -O- -O- 1.2E+4 1.4E+5 6.6E+4 6.7E+5 9.7E+4 1.6E+6 Ce-141 -O- -O- 3.8E+3 9.4E+4 2.OE+4 4.5E+5 2.8E+4 1.OE+6 Ce-144 -O- -O- 8.2E+4 4.8E+5 4.4E+5 2.3E+6 5.9E+5 5.3E+6 I -131 -O- -O- 1.1E+5 1.2E+5 4.8E+5 5.6E+5 9.1E+5 1.3E+6 I -132 -O- -O- 1.3E+3 8.5E+3 4.9E+3 4.1E+4 8.7E+3 9.4E+4 I -133 -O- -O- 2.7E+4 1.7E+4 9.5E+4 8.OE+4 1.6E+5 1.9E+5 I -134 -O- -O- 3.5E+2 3.1E+3 1.3E+3 1.5E+4 2.3E+3 3.4E+4 I -135 -O- -O- 5.5E+3 1.7E+4 2.OE+4 8.2E+4 3.4E+4 1.9E+5 UN-ID -O- -O- 6.9E+3 5.1E+6 4.1E+4 2.4E+7 6.6E+4 5.7E+7 mrem/vr Inhalation Pathway, units = YCi/m-'

Food & Ground Food&Pathway, units = (ml) (mrem/vr)

GrundPathaypCi/sec SO1-ODCM Revision 13 2-22 02-27-98 SO1-ODCM

-TABLE 2-7 DOSE PARAMETER RI FOR SECTOR P Page 2 of 2 Pathway = Cotton Point Estates with Garden Distance = 2.6 miles X/Q = 1.3E-7 sec/mr3. D/Q = 3.9E-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 6.5E+2 1.1E+3 4.OE+3 1.3E+3 2.6E+3 I.3E+3 2.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 1.1E+7 2.1E+4 1.5E+7 1.4E+4 1.6E+7 Mn-54 1.OE+6 1.4E+9 1.6E+6 2.OE+9 2.OE+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 6.3E+8 Co-58 7.BE+5 3.8E+8 1.1E+6 7.5E+8 1.3E+6 9.7E+8 9.3E+5 9.9E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.4E+10 8.7E+6 2.5E+10 6.OE+6 2.5E+10 Sr-89 2.OE+6 2.2E+4 2.2E+6 3.5E+10 2.4E+6 1.5E+10 1.4E+6 9.8E+9 Sr-90 4.1E+7 1.OE+8 1.4E+12 1.1E+8 8.3E+11 9.9E+7 6.7E+11 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 4.3E+8 7.5E+5 5.9E+8 5.OE+5 6.1E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 5.OE+8 7.8E+5 6.8E+8 5.OE+5 6.6E+8 Te-129m 1.7E+6 2.OE+7 1.8E+6 2.9E+9 2.OE+6 1.8E+9 1.2E+6 1.5E+9 Cs-134 7.OE+5 6.8E+9 1.OE+6 3.2E+10 1.1E+6 2.3E+10 8.5E+5 1.8E+10 Cs-136 1.3E+5 1.5E+8 1.7E+5 3.7E+8 1.9E+5 3.2E+8 1.5E+5 3.2E+8 Cs-137 6.1E+5 1.OE+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 3.OE+8 2.OE+6 2.3E+8 1.3E+6 2.8E+8 Ce-141 5.2E+5 1.4E+7 5.4E+5 4.2E+8 6.1E+5 5.5E+8 3.6E+5 5.2E+8 Ce-144 9.8E+6 7.OE+7 1.2E+7 1.OE+10 1.3E+7 1.3E+10 7.8E+6 1.lE+10 I -131 1.5E+7 1.7E+7 1.6E+7 4.8E+10 1.5E+7 3.1E+10 1.2E+7 3.8E+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 8.1E+8 2.9E+6 4.6E+8 2.2E+6 5.3E+8 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.OE+4 4.5E+5 3.OE+4 4.5E+5 I -135 7.OE+5 2.5E+6 7.9E+5 1.2E+7 6.2E+5 8.2E+6 4.5E+5 9.1E+6 UN-ID 6.5E+5 7.5E+8 1.OE+6 3.5E+9 1.2E+6 2.6E+9 8.6E+5 2.OE+9 Inhalation Pathway, units = mrem/yr (M2) (mremlvr)

Food & Ground Pathway, units = pCi/sec S01-ODCM Revision 14

'2-23 02-25-99 SO1-ODCM

TABLE 2-8 DOSE PARAMETER R1 FOR SECTOR Q This page intentionally left blank.

SO1-ODCM Revision 21 2-24 02-26-04 SO1-ODCM

,,TABLE 2-8 DOSE PARAMETER R. FOR SECTOR Q Page 1 of 3 Pathway = San Onofre.Mobile Homes Distance = 1.2 miles X/Q = 9.1E-7.sec/m3 D/Q = 4.3E-9 m2 -

'Infant Child Teen 'Adult Inhala- Food & Inhala- Food & Inhala- Food & -Inhala- Food &

Radio- tion .Gr6und tion Ground tion Ground tion Ground Nuclide Pathway 'Pathway Pathway; Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 , -1.1E+3 -,0- 1.3E+3 -O- 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.OE+6 1.4E+9 1.6E+6 '14E+'9 2.OE+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+66 *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.OE+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 0- -1.OE+8 ;1.1E+8 ' 9.9E+7 0-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+51 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.E+5 : 1.1E+8 Te-'129m 1.7E+6 2.OE+7 1.8E+6 2.OE+7 2.OE+6 2.OE+7 1.2E+6 2.OE+7 Cs-134 :7.OE+5 - 6.8E+9 1.OE+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.OE+10 9.1E+5, 1.OE+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.OE+6 2.1E+7 '-1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 -5.'4E+5 1.4E+7 6.1E+5 1.4E+7 3'.6E+5 1.4E+7 Ce-144 9.8E+6 7.OE+7 1.2E+7 7.OE+7 1.3E+7 7.OE+7 , 7.8E+6 7.OE+7 I -131 1'.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 -1.7E+5 1.2E+6 1.-9E+5 1.2E+6 1.5E+5 '1.2E+6 -1.1E+5 1.2E+6 I -133 3.6E+56 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.OE+4 4.5E+5 :3;0E+4 4.5E+5 1-135 '7.OE+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.OE+6 7.5E+8 1.2E+6, 7.5E+8 ,8.6E+5 7.5E+8 Inhalation Pathway, units = mrem/pr pCi/m3 -

2 Food & Ground Pathway, units = (m )pCi/sec (mrerm/vr)

S01-ODCM Revision 12

, 2-25 01-29-97 S01-ODCM

TABLE'2-8 DOSE PARAMETER RI FOR'SECTOR Q

, Page 2 of 3 Pathway = San Mateo Pt Homes Distance 2.5miles X/Q = 2.8E-7 sec/m3 D/Q = 1.1E-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 6.5E+2 i.1E+3 _0_- '1I.3E+3 -O- 1.3E+3 -0' 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.OE+6 1.4E+9 1.6E+6 1.4E+9 '2.OE+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.OE+6 2.2E+10 Sr-89 2.OE+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.OE+8 1.1E+8 9.9E+7 _0-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.OE+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.OE+5 1.1E+8 Te-129m 1.7E+6 2.OE+7 1.8E+6 '2.OE+7 2.OE+6 '2.OE+7 1.2E+6 2.OE+7 Cs-134 7.OE+5 6.8E+9 1.OE+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.OE+10 '9.1E+5 1.OE+10 ~8.5E+5 1.OE+10 6.2E+5 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 '2.OE+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.OE+7 1.2E+7 7.OE+7 1.3E+7 7.OE+7 7.8E+6 7.OE+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 '1.9E+5 1.2E+6 1.5E+5 '1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.OE+4 4.5E+5 3.OE+4 4.5E+5 I -135 7.OE+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.OE+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 Inhalation Pathway, units = mrem/4r VC i/rn Food & Ground Pathway, units = (m) (Nrem/yr) pCi/sec S01-ODCM Revision 18 2-26 02-21-01 SO1-ODCM

, TABLE 2-8 DOSE PARAMETER -R 1 FOR SECTOR Q Page 3 of 3 Pathway = Beach Complex - Distance 0.8 miles X/Q = 1.2E-6 sec/m3 D/Q = 6.1E-9 mnf

,Infant ,Child - Teen Adult Inhala-' Food A& 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.OE+6- 1.4E+9 1.6E+6 -1.4E+9 2.OE+6 ;1.4E+9 1.4E+6 1.4E+9 Co-57 , -:4.9E+3 3.4E+8 -1.3E+4> 3.4E+8 3.1E+4, 3.4E+8 3.1E+4 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.OE+6 2.2E+10 Sr-89 2.OE+6 2.2E+4 ;2.2E+6, 2.2E+4- 2.4E+6 2.2E+4 -1.4E+6 2.2E+4 Sr-90 1.1E+7 ;, -. 5E+7 _0 . 1.6E+7 .-

0' - 9.6E+6 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.OE+5, 1.1E+8 Te-129m `1.7E+6 2.OE+7 1.8E+6 2.OE+7, 2.OE+6 2.OE+7. 1.2E+6-, 2.OE+7 Cs-134, 8.OE+4 6.8E+9 1.2E+5, 6.8E+9 1.5E+5 6.8E+9 9.8E+4 6.8E+9 Cs-136 -1.2E+4 -1.5E+8 1.5E+4, -1.5E+8 1.8E+4 1.5E+8 :1.2E+4;4 1.5E+8 Cs-137- 7.1E+4, 1.OE+10 -I.OE+5, 1 1-.OE+10 1.2E+5 1.OE+10 7.5E+4 1.OE+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 ,:, 2.1E+7 2.OE+6 2.1E+7, 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7, 5.4E+5 1.4E+7 6.1E+5 1.4E+7- 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.OE+7 '-1.2E+7 -7.OE+7 1.3E+7 7.OE+7 7.8EK-6 7.OE+7 I.-131 1.5E+7 -1.7E+7 -1.6E+7 1.7E+7- 1.5E+7 1.7E+7, 1.2E+7 1.7E+7 I -132 1.7E+5-, 1.2E+6 .1.9E+5 - 1.2E+6- 1.5E+5. 1.2E+6 1.1E+5 1.2E+6 I;'-133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6- -:2.2E+6 2.4E+6

,I.-134 4.5E+4 4.5E+5 5.1E+4; 4.5E+5- 4.OE+4 4.5E+5, -3.OE+4 4.5E+5 I -135 7.OE+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.OE+6 -7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 I .U -: .5 8 +

Inhalation Pathway, units = mrem/vr V VF1

/m 2

Food & Ground Pathway, units = (m )pCi/sec(mrem/vr)

S01-ODCM Revision 21 27 02-26-04 S01 -ODCM

TABLE 2-9 DOSE PARAMETER R. FOR SECTOR R Page 1 of 1 Pathway = San Onofre'Mobile Homes Distance = 1.2 miles 2

X/Q = 6.OE-7 sec/m 3 D/Q = 3.5E-9 m-Infant Child Teen Adult Inhala- Food & Inhala-- Food & Inhala- Food &- Inhala- Food &

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 -O- 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.OE+6 1.4E+9 1.6E+6 1.4E+9 '2.OE+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.OE+6 2.2E+10 Sr-89 2.OE+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.OE+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.OE+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.OE+5 1.1E+8 Te-129m 1.7E+6 2.OE+7 1.8E+6 2.OE+7 2.0E+6 2.OE+7 1.2E+6- 2.OE+7 Cs-134 7.OE+5' 6.8E+9 1.OE+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.OE+10 9.1E+5 1.OE+10 8.5E+5 1.OE+10 6.2E+5 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.OE+6 2.1E+7' 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.OE+7 1.2E+7 7.OE+7 1.3E+7 7.OE+7 7.8E+6 :7.OE+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132. 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.OE+4' 4.5E+5 3.OE+4 4.5E+5 I -135 7.OE+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.OE+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 Inhalation Pathway, units = mrem/r

'UCi/m.

2 (mrem/vr)

Food & Ground Pathway, units = ( )pCi/sec SO1-ODCM Revision 12 2-28 01-29-97 SO1-ODCM

TABLE 2-10 XDOSE PARAMETER R FOR SECTOR A Page 1 of I Pathway = Camp-San Mateo Distance,= 3.5 miles X/Q = 7.8E-8 sec/m3 D/Q =-4.4E-10 m-2 Infant Child Teen Adult

. -Inhala-: Food & 'Inhala-.- Food &- Inhala- Food-'& Inhala- Food &

Radio- tion Ground tion Ground tion' Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway. Pathway Pathway Pathway H -3 - - -O- -O- '1.3E+3 -O-Cr-51 -0 0- -- - -- -O- 1.4E+4 4.7E+6 Mn-54 ' -0' 1.4E+6 1.4E+9

-Co-57i -O -O- -0t -O- 3.7E+5 3.4E+8 Co-58 - O-

- -O- -O- -O- 9.3E+5 3.8E+8 Co-60 -O- -O- -0 ,0-O- '6.OE+6 2.2E+10 Sr-89 ~°-O- ---

-O- 1.4E+6 2.2E+4

.Sr-90 -O- *.- -0i '9.9E+7 Zr-95 i -O- 1.8E+6 2.5E+8 I Nb-95 ..,0- -0 -O- 5.OE+5 1.4E+8 Ru-103 --0-, -0 -O- -07 5.0E+5. 1.1E+8

-Te-129m ,- -O- -O- -O- & - '1.2E+6 2.OE+7

,Cs-134.- -0 S8.5E+5' 6.8E+9 Cs-136 -0

-O -O- 1.5E+5k 1.5E+8 Cs-137 - O -O.; ,-O_o O_ -O- -O- -6.2E+5' 1.OE+~10 Ba-140 -- 0-, -1.3E+6' 2.1E+7 Ce-141 -0O-!_0 3.6E+5 14+

---.- ,_0 Ce-144 -O-O - '. -O- '7.8E+6; 7.OE+7 I -131 -O- -- -0'

_1.2E+7 -0 1.7E+7

-I-132 - .- 0- -O - 1.1E+5 1.2E+6 I *-133 ; -- -- O - -0' ,2.2E+56 2.4E+6 1 -134 - c-O.- -- '3.OE+4' 4.5E+5 I -135 ' -O0., -O- 4.5E+5' 2.5E+6 UN-ID -O-' -O- -O- - _0 -O- -O- '8.6E+5 7.5E+8 Inhalation Pathway, units = mrem/vrVC i/-m-2 (mrem/vr)

Food & Ground Pathway, units = ( )pCi/sec: -

S01-ODCM Revision 12 29 01-29-97 SO1-ODCM

- lt TABLE 2-11 DOSE PARAMETER RI FOR SECTOR B Page 1 of 2 Pathway = Sanitary Landfill Distance = 2.1 miles X/Q = 1.4E-7 sec/M 3 D/Q = 1.2E-9 m2 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 -O- -O- -O- -O- -O- -O- 2.9E+2 -O-Cr-51 -O- -O- -O- -O- -O- -O- 3.3E+3 1.1E+6 Mn-54 -O- -O- -O- -O- -O- 3.2E+5 3.2E+8 Co-57 -O- -O- -O- -O- -O- -O- 8.4E+4 7.8E+7 Co-58 -O- -O- -O- -O- -O- -O- 2.1E+5 8.7E+7 Co-60 -O- -O- -O- -O- . -O- 1.4E+6 4.9E+9

-Sr-89 -O- -O- -O- -O- -O- 3.2E+5 4.9E+3 Sr-90 -O- -O- -O- -O- -O- 2.3E+7 -O-

-Zr-95 -O- -O- -O- -O- -O- 4.0E+5 5.7E+7 Nb-95 -O- -O- -O- -O- -O- -O- 1.2E+5 3.1E+7 Ru-103 -O- -O- -O- -O- -O- -O- 1.2E+5 2.5E+7 Te-129m -O- -O- -O- -O- -O- -O- 2.6E+5 4.5E+6 Cs-134 -O- -O- -O- -O- -O- 1.9E+5 1.6E+9 Cs-136 -O- -O- -O- -O- -O- -O- 3.3E+4 3.4E+7

'Cs-137 -O- -O- -O- -O- 1.4E+5 2.3E+9 Ba-140 -O- -O- -O- -O- ; -O- 2.9E+5 4.7E+6 Ce-141 -O- -O- -O- -O- -O- -O- 8.3E+4 3.1E+6 Ce-144 -O- -O- -O- -O- -O- -O- 1.8E+6 1.6E+7 I -131 -O- -O- -O- -O- -O- -O- 2.7E+6 3.9E+6 1 -132 -O- -O- -O- -O- -O- -O- 2.6E+4 2.8E+5 I -133 -O- -O- -O- -O- -O- -O- 4.9E+5 5.6E+5 I -134 -O- -O- -O- -O- -O- -O- 6.8E+3 1.OE+5

-I -135 -O- -O- -O- -O- -O- -O- 1.OE+5 5.8E+5 UN-ID -O- -O- -O- -O- , -O- 2.0E+5 1.7E+8 Inhalation Pathway, units = mrem/r VCi-/-m-Food & Ground Pathway, units = n) (mrem/vr) pCi/sec SO1-ODCM Revision 8 2-30 06-29-92 S01- ODCM

, TABLE 11 DOSE PARAMETER,-RI FOR SECTOR B Paqe 2 of 2 Pathway = CampMesa Distance = 0.3 miles X/Q = 3.9E-6 sec/r 3 , D/Q = 3.4E-8 m 2 ,

Infan Child ,;

t Teen Adult

-Inhala-, Food & Inhala-. Food-& Inha& Inhala& Inhala- Food&

Radio- '.tion Ground 'tion 'Ground tion Ground 'tiont Ground Nuclide Pathway' Pathway Pathway 'Pathway Pathway' Pathway 'Pathway, Pathway H -3 2.8E+2 4.9E+2 5.5E+2 5.5E+2 ---

O--

Cr-51i 5.6E+3 2.OE+6 -7.4E+3 :2.OE+6 9.1E+3 2.OE+6 -6.3E+3 2.OE+6 Mn-54 '-4.3E+5 ;6.OE+8 6.9E+5 6.OE+8 8.6E+5 6.OE+8 :6.1E+5 '6.OE+8 Co-57 '2.1E+3 1.5E+B ;c5.8E+3 -1.5E+8 1.4E+4 '1.5E+8 1.4E+4 I1.5E+8 Co-58 3.4E+5 1.7E+8 4.8E+5 '1.7E+8 5.8E+5 1.7E+8 4.OE+5 -1.7E+8 Co-60 '2.OE+6 9.4E+9 3.1E+6 .9.4E+9 '3.8E+6 9.4E+9 2.6E+6 9.4E+9 Sr-89 18.8E+5 9.4E+3 9.4E+5 9.4E+3 1.1E+6 :9.4E+3 6.1E+5 9.4E+3 Sr-90 '4.9E+6 .6.4E+6 : ,,7.2E+6 , 4.2E+6 Zr-95 -7.6E+5 1.1E+8 9.7E+5 ,1.1E+8 1.2E+6 1.1E+8 7.7E+5 ,1.1E+8 Nb-95 2.1E+5 5.9E+7 '2.7E+5 *5.9E+7 3.3E+5 5.9E+7 2.2E+5 5.9E+7 Ru-103 ,.2.4E+5 ;4.7E+7 2.9E+5 4.7E+7 3.4E+5 4.7E+7 2.2E+5~ 4.7E+7 Te-129m -7.3E+5 8.6E+6 -7.7E+5 ;8.6E+6 .8.6E+5 8.6E+6 ;5.4E+5', 8.6E+6 Cs-134 3.5E+4 '3.OE+9 5.3E+4 ,3.OE+9 6.4E+4 3.OE+9 '4.2E+4 3.OE+9 Cs-136, 5.1E+3 6.5E+7 .6.3E+3 ,6.5E+7 7.7E+3 6.5E+7 -,5.2E+3 '6.5E+7 Cs-137 '3.1E+4 4.5E+9 ,'4.5E+4 ,4.5E+9 5.3E+4 4.5E+9 3.3E+4 4.5E+9 Ba-140 , 6.9E+5 8.9E+6 ;.7.6E+5 ;8.9E+6 ',8.8E+5 8.9E+6 S.5E+5;' 8.9E+6 Ce-141 '2.2E+5 5.9E+6 '2.4E+5 ,5.9E+6 2.7E+5 5.9E+6 ,'1.6E+5 '5.9E+6 Ce-144 '4.3E+6 3.OE+7 :5.2E+6 i3.OE+7 5.8E+6 3.OE+7 3.4E+6, 3.OE+7 I -131 6.5E+6 7.5E+6 '7.1E+6 7.5E+6 6.4E+6 7.5E+6 5.2E+6 7.5E+6 I'-132 7.4E+4 5.4E+5 '8.4E+4 5.4E+5 6.6E+4 5.4E+5 5.OE+4'. 5.4E+5 I -,133 1.5E+6 1.1E+6 '1.7E+6 1.1E+6 1.3E+6 1.1E+6 '9.4E+5: 1.1E+6 I -134 1.9E+4 2.OE+5 2.2E+4 2.OE+5 1.7E+4 2.OE+5 1.3E+4 2.OE+5 I -135 -3.OE+5 1;1E+6 ' 3.4E+5 '1.1E+6 2.7E+5 -1.1E+6 1.9E+5 1.1E+6 UN-ID 2.8E+5 3.2E+8 '4.3E+5 3.2E+8 5.4E+5 3.2E+8 3.8E+5 3.2E+8 Inhalation Pathway, units = mrem/vr VC i/m-M

2) (mrem/vr) .

Food & Ground Pathway, units = (m pCi/sec -

S01-ODCM Revision 21 2-31 02-26-04 SO1-ODCM

TABLE 2-12 DOSE PARAMETER R. FOR SECTOR C Paae 1 of 2 Pathway = Camp San Onofre Distance = 2.7 miles X/Q = 9.3E-8 sec/m3 D/Q = 8.3E-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 -O- -O- -O- -O- -O- 1.3E+3 -O-Cr-51 -O- -O- -O- -O- -O-. 1.4E+4 4.7E+6 Mn-54 -O- -O- -O- -O- -- -O- 1.4E+6 1.4E+9 Co-57 3.7E+5 3.4E+8 Co-58 -O- -O- -O- -O- -O- -O- 9.3E+5 3.8E+8 Co-60 -O- -O- -O- -O- -O- -O- 6.OE+6 2.2E+10 Sr-89 -O- -O- -O- -O- -O- 1.4E+6 2.2E+4 Sr-90 -O- -O- -O- -O- _-O- 9.9E+7 -O-Zr-95 -O- -O- -O- -O- 1.8E+6 2.5E+8 Nb-95 -O- -O- -O- . -O- -O- 5.OE+5 1.4E+8 Ru-103 -O- -O- -O- -O- -O- -O- 5.OE+5 1.1E+8 Te-129m -O- -O- -O- -O- -O- 1.2E+6 2.OE+7 Cs-134 -O- -O- -O- -O- 8.5E+5 6.BE+9 Cs-136 -O- -O- -O- -O- 1.5E+5 1.5E+8 Cs-137 -O- -O- -O- -O- -O- 6.2E+5 1.OE+10 Ba-140 -O- -O- -O- -O- 1.3E+6 2.1E+7 Ce-141 -O- -O- -O- -O- -O- 3.6E+5 1.4E+7 Ce-144 -O- -O- -O- -O- 7.8E+6 7.OE+7 I -131 -O- -O- -O- -O- -O- 1.2E+7 1.7E+7 I -132 -O- -O- -O- -O- -O- 1.1E+5 1.2E+6' 1 -133 -O- -O- -O- -O- -O- 2.2E+6 2.4E+6 1 -134 -O- -O- -O- -O- -O- 3.OE+4 4.5E+5 I -135 -O- -O- -O- -O- -O- -O- 4.5E+5 .2.5E+6 UN-ID -O- -O- -O- -O- -0. 8.6E+5 7.5E+8 Inhalation Pathway, units = mrevr PCi/rn 2

Food & Ground Pathway, units = (m) (mrem/vr) pCi/sec S01-ODCM Revision 12 2-32 01-29-97 SO1-ODCM

TABLE 2-12 DOSE- PARAMETER R, FOR SECTOR C Page 2 of 2 Pathway = Deer Consumer/Hunter Distance = 1.1 miles X/Q = 3.7E-7 sec/m 3 D/Q = 4.6E-9,m 2 Infant Child Teen Adult

-Inhala- Food-& Inhala-. Food &V Inhala- Food & Inhala- Food &

Radio- tion ' Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway, Pathw'ay Pathway Pathway Pathway Pathway Pathway H -3 0-

-- -O- 2.8E+1 -O-' 2.3E+1 3.5E+1 3.9E+1 Cr-51 , -0 ' 5.OE+4 -O- 1.0E+5 '3.9E+2 3.2E+5

-Mn-54 ' -O- 7.7E+5 ' 1.4E+6 3.8E+4 4.1E+7 Co-57, -O- : 4.6E+6 8.OE+6 ,1.OE+4 2.3E+7 Co-58 -O- -O- 9.6E+6 -O- 1.9E+7 2.5E+4 4.7E+7 Co-60 -O- 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 ' -O- ' 4.9E+7 -O- 2.6E+7 .3.8E+4 3.1E+7 Sr-90 -O- -O- ; 1.OE+9 ' 8.OE+8 2.7E+6 1.2E+9 Zr-95 ' 6.2E+7 -O- 1.1E+8 4.8E+4 2.OE+8 Nb-95 -0 - ' 2.3E+8 -O- 4.5E+8 1.4E+4 8.2E+8 Ru 103 0 ,,0- 4.2E+8 -O- 7.5E+8 1.4E+4 1.3E+9 Te-129m -' ' - .5.9E+8 -O-' 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 :-'O- ' 5.1E+6 -O- 4.2E+6 4.OE+3 9.5E+6 Cs-137 0-' '- ' 1.3E+8 --

-O- 9.3E+7 1.7E+4 4.0E+8 Ba-140 -O- ' 5.0E+6 -O- 4.2E+6 .,3.5E+4 7.4E+6 Ce-141 -O- 1.5E+6 -O- 2.4E+6 *9.9E+3 4.2E+6 Ce-144 -O- '-O- -O- 1.8E+7 -O- 2.9E+7 2.1E+5 4.9E+7 I -131 ^ 6.5E+8 -O- 4.3E+8 3.3E+5 5.9E+8 I -132 --'0 _O-- ' 3.1E+3 3.4E+4 I'-133 -O- -O- I.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 -0O- .,-O- !O 8.2E+2 1.2E+4 I,-135 ' - 1.1E-15 -O- 6.3E-16 1.2E+4 6.9E+4 UN-ID -O- -O- 1.1E+8 -O- 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = 'mrem/vr-FCi/rm Food & Ground Pathway, units = tm2)pCi/sec (mrem/vr)

SO1-ODCM Revision 12

(,2-33 01-29-97 SO1-ODCM

TABLE 2-13 DOSE PARAMETER RI FOR SECTOR D Page 1 of 1 Pathway = Camp San Onofre Distance = 3.0 miles X/Q = 7.OE-8 sec/M 3 D/Q = 7.2E-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 -O- -O- -O- -O- -O- -O- 1.3E+3 Cr-51 -O- -O- -O- -O- -O- -O- 1.4E+4 4.7E+6 Mn-54 -O- -O- -O- -O- -O- -O- 1.4E+6 1.4E+9 Co-57 -O- -O- -O- -O- -O- -O- 3.7E+5 3.4E+8 Co-58 -O- -O- -O- -O- -O- -O- 9.3E+5 3.8E+8 Co-60 -O- -O- -O- -O- -O- -O- 6.0E+6 2.2E+10 Sr-89 -O- -O- -O- -O- -O- -O- 1.4E+6 2.2E+4 Sr-90 -O- -O- -O- -O- -O- 9.9E+7 -O-Zr-95 -O- -O- -O- -O- -O- -O- 1.8E+6 2.5E+8 Nb-95 -O- -O- -O- -O- -O- -O- 5.OE+5 1.4E+8 Ru-103 -O- _0_' -O- -O- -O- -O- 5.OE+5 1.1E+8 Te-129m -O- -O- -O- -O- -O- 1.2E+6 2.OE+7 Cs-134 -O- -O- -O- -O- -O- 8.5E+5 6.8E+9 Cs-136 -O- -O- -O- -O- -O- -:O- 1.5E+5 1.5E+8 Cs-137 -O- -O- -O- -O- -O- -O- 6.2E+5 1.OE+10 Ba-140 -O- -O- -O-' -O- -O- -O-

_ 1.3E+6 2.1E+7 Ce-141 -O- -O- -O- -O- -O- -O- 3.6E+5 1.4E+7 Ce-144 -O- -O- -O- -O- -O- -O- 7.8E+6 7.OE+7 I -131 -O- -O- -O- ' -O- -O- 1.2E+7 1.7E+7 I -132 -O- -O- -O- -O- -O- -O- 1.1E+5 1.2E+6 I -133 -O- -O- -O- 2.2E+6 2.4E+6 r -134 -O- -O- -O- -O- -O- -O- 3.OE+4 4.5E+5 I -135 -O- -O- -O- -O- -O- -O- 4.5E+5 2.5E+6 UN-ID -O- -O- -O- -O- -O- -O- 8.6E+5 7.5E+8 Inhalation Pathway, units =

Food & Ground Pathway, units = CM 2) (mrem/yr) pCi/sec S01-ODCM Revision 12 2-34 01-29-97 SO1-ODCM

TABLE 2-14 DOSE PARAMETER RI FOR SECTOR E Page 1 of 2 Pathway = Deer Consumer/Hunter Distance = 1.0 miles 2

X/Q = 6.OE-7 sec/m 3 D/Q 8.4E-9 m-Infant Child Teen ,Adult Inhala- Food-& ;Inhala- Food & Inhala-. Food & Inhala- Food &

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathw'ay Pathway Pathway Pathway: Pathway H -3 -O- -O- -O- 2.8E+1 -O- 2.3E+1 3.5E+1 3.9E+1 Cr-51 -O- -O- ' 5.OE+4 -O- 1.OE+5 3.9E+2 3.2E+5 Mn.-54 -O- -O- 7.7E+5 -O- 1.4E+6 3.8E+4 4.1E+7 Co-57 -, - 4.6E+-0 8.OE+6 ,1.OE+4 ;2.3E+7 Co -O- 9.6E+6 -O- 1.9E+7 2.5E+4 4.7E+7 Co-60 -O- -O- . 3.6E+7 -O- 7.2E+7 .1.6E+5 7.2E+8 Sr-89 - ' .4.9E+7 -O -2.6E+7 3.8E+4 3.1E+7 Sr-90 . -O- -O- 1.OE+9 -O- 8.OE+8 2.7E+6 1.2E+9 Zr-95 -O- -O- 6.2E+7 -O- 1.1E+8 4.8E+4 2.OE+8 Nb-95 .- O- 2.3E+8 -O- 4.5E+8 1.4E+4 8.2E+8

.Ru-103 - -O- .4.2E+8 -O 7.5E+8 1.4E+4 , 1.3E+9 Te-129m - -O- . 5.9E+8 -O- 4.5E+8 3.2E+4 6.4E+8 Cs-134 -0 .- 0- - 1.4E+8 -O- 1.2E+8 2.3E+4 3.4E+8 Cs-136 , . -O- -O- 5.1E+6 -O- 4.2E+6 :4.OE+3 ,9.5E+6

-Cs-137 -O- -O- 1.3E+8 , 9.3E+7 1.7E+4 4.0E+8 Ba 140 . : 5.OE+6 -O- 4.2E+6 3.5E+4 7..4E+6 Ce-141 - -- '-O- -O- .1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 -O- -O-, 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 -O- -O- 6.5E+8 -O- 4.3E+8 3.3E+5 5.9E+8 I -132 -O- -O- 3.1E+3 3.4E+4 1 -133 -O- -O- ' 1.6E+1 -O- 8.6E+0 5.9E+4 6.7E+4 I1-134, -O- , *--:_O -O- -_O_ 8.2E+2 1.2E+4

-135 -O- -O- ; .1.1E-15 -O- 6.3E-16 1.2E+4 6.9E+4 UN-ID - , 1.1E+8 -O- 9.4E+7 2.4E+4 -1.4E+8 Inhalation Pathway, units = mrem/Yr-pCi/rn, 2 (mremr/vr)

Food & Ground Pathway, units = (m)pCi/sec, -

S01-ODCM Revision 12 2-35 01-29-97 SO1-ODCM

TABLE 2-14 DOSE PARAMETER R. FOR SECTOR E Paae 2 of 2 Pathway = Camp Horno Distance = 4.2 miles X/Q = 7.3E-8 sec/m 3 D/Q = 6.9E-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 Co-57 3.7E+S 3.4E+8 Co-58 -O- -a- 9.3E+S 3.8E+8 Co-60 6.OE+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.9E+7 Zr-95 -O- 1.8E+6 2.5E+8 Nb-95 -_0_ 5.OE+S 1.4E+8 Ru-103 -O- 5.OE+5 1.1E+8 Te-129m -O- 1.2E+6 2.0E+7 Cs-134 8.5E+5 6.8E+9 Cs-136 -_O_ 1.SE+S 1.5E+8 Cs-137 6.2E+5 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.OE+7 I -131 1.2E+7 1.7E+7 1 -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.OE+4 4.5E+5 I -135 4.5E+S 2.SE+6 UN-ID 8.6E+5 7.5E+8 mrem/vr Inhalation Pathway, units = pC i/mr (m2 ) (mrem/vr)

Food & Ground Pathway, units = yCi/sec S01-ODCM Revision 12 2-36 01-29-97 SO1-ODCM

TABLE 2-15 DOSE PARAMETER RIl FOR SECTOR F Page 1 of 1 Pathway = San Onofre State Park/Guard Shack, Distance= 1.0 miles X/Q = 5.8E-7 sec/m3 D/Q = 4.8E-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 Pathiay4 Pathway -Pathway Pathway Pathway- Pathway H -3 -O- -0 -- -O0- 2.2E+2 Cr-51 -O- -O- -O- 2.5E+3 ,8.OE+5 Mn-54 -O- -0O- 2.4E+5 2.4E+8 Co-57 70- -O- -O- ; -O- '6.3E+4 5.9E+7 Co-58 -O- -O- % -O - 1.6E+5 :6.5E+7 Co-60 -O- -O- -O- -O- 1.OE+6 , 3.7E+9 Sr-89 -O- -- -- -, - 2.4E+5 3.7E+3 Sr-90 -O -O- -O- -0_ -O- -1.7E+7 Zr-95 -O- -0 -O- -O- -- 3.OE+5 :4.3E+7 Nb-95 -- .8.6E+4 2.3E+7 Ru-103 + -0 O- -O- -O- i8.6E+4 1.9E+7 Te-129m :-O- -O- -O- -O- 2.OE+5 3.4E+6 Cs-134 -O--- -O- 1.5E+5. 1.2E+9 Cs-136 -O- -- -0, -O- 2.5E+4t 2.6E+7 Cs-137 -O- - O-- 1.1E+5 1.8E+9 Ba-140 -O- -O- -O- , - -O- 2.2E+5 3.5E+6 Ce-141 -0O- 6.2E+4, 2.3E+5 Ce-144 -- O--- -O- 1.3E+65 :1.2E+7 I -131 -O- . 2.0E+6 :2.9E+6 I -132 -0 o- 0- -0 2.OE+44 2.1E+5 1 -133 .-

0- -0 -O- -O- 3.7E+5 4.2E+5 I -134 -O- -- -0O -O0 5.1E+3 :7.7E+4 I -135 -O- 0-O - 0--0 -0 7.7E+4 4.3E+5 UN-ID -O- -o- -O- -O- 1.5E+5- 1.3E+8 Inhalation Pathway, units = /

Food & Ground Pathway, units = (m2 )(mrem/vr) puCi/sec_

S01-ODCM Revision 12 2-37 01-29-97 SO1-ODCM

TABLE 2-16 DOSE PARAMETER R. FOR SECTOR G Page 1 of 1 Pathway = San Onofre State Park Beach Distance = 1.1 miles Campground D/Q = 2.4E-9 m-'

X/Q = 5.2E-7 sec/m3 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 -0 1.4E+2 1.6E+2 -O- 2.9E+2 -O-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-5B 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.OE+5 2.7E+3 3.2E+5 4.9E+3 Sr-90 5.OE+6 1.2E+7 1.3E+7 2.3E+7 -O-Zr-95 2.2E+5 3.1E+7 2.8E+5 3.1E+7 3.3E+5 3.1E+7 4.OE+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 13E+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.OE+5 1.3E+9 1.4E+5 2.3E+9 Ba-140 2.OE+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 3.1E+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.OE+6 2.1E+6 1.8E+6 2.1E+6 2.7E+6 3.9E+6 I -132 2.1E+4 1.5E+5 2.4E+4 1.5E+5 1.9E+4 1.5E+5 2.6E+4 2.8E+5 I -133 4.4E+5 3.OE+5 4.7E+5 3.OE+5 3.6E+5 3.OE+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.OE+5 I -135 8.6E+4 3.IE+5 9.8E+4 3.1E+5 7.7E+4 3.1E+5 1.OE+5 5.8E+5 UN-ID 8.OE+4 9.2E+7 1.2E+5 9.2E+7 1.5E+5 9.2E+7 2.OE+5 1.7E+8 Inhalation Pathway, units = PCt i/mn 2

Food & Ground Pathway, units = (m ) (mrem/vr) pCi/sec S01-ODCM Revision 13 2-38 02-27-98 SO1-ODCM

3.0 TOTAL AND PROJECTED DOSES 3.1 LIQUID DOSE PROJECTION The methodology used for projecting a liquid dose for Specification 1.3.2 is as follows:

1. Determine the monthly' total body and organ doses resulting from releases during the' previous twelve months.

2. 'Projected Dose'= Previous,12 months' dose divided by 12 for the total-body and each'organ.

3.2 GASEOUS DOSE PROJECTION DELETED

.a.

1..

SO1-ODCM.

Revision 9 3-1 .08-04-93 SOI-ODCM

3.0 TOTAL AND PROJECTED DOSES (Continued) 3.3 DOSE 3.3.1 SPECIFICATION Applicability: At all times.

Objective: Maintain the dose due to the release of radioactive materials within specified limits.

Specification: A. The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation, from uranium fuel cycle sources shall be limited to 5 25 mrem to the total body or any organ (except the thyroid which shall be limited to

75 mrem).

B. Action:

1. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of-Specifications 1.2.1.A, 2.2.1.A or 2.3.1.A, calculations should be made to determine whether the above limits of Specification 3.3.1.A have been exceeded.

If such is the case, prepare and submit to the Commission within 30 days pursuant to Technical Specification D6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases, to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. The Special Re ort, as defined in IOCFR20.2203(a)(4), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with .the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

S01-ODCM Revision 12 3-2 01-29-97 SO1-ODCM

3.0 TOTAL AND PROJECTED DOSES (Continued)-

3.3 DOSE (Continued) 3.3.2, ..

', SURVEILLANCE .

ADDlicability: At all times.

.- Objective , -To verify.the doses due.to liquid and gaseous effluents are maintained as-low as is reasonably achievable.

I , :.Secifica tion: . Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 1.2.1.A, 2.2.1.A, and 2.3.1.A and in

-accordance with.Sections 1.5. 2.7.1, and 2.7.2.

S01-0DCM Revision 8 3-3 06-29-92 SO1-ODCM

3.0 TOTAL AND PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS 3.4.1 TOTAL DOSE TO MOST LIKELY MEMBER OF THE PUBLIC The total annual dose or total dose commitment to any member of the 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 mrem respectively.

S01-ODCM Revision 8 3-4 06-29-92 SOI -ODCM

3.0 TOTAL AND PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 TOTAL DOSE TO MOST LIKELY MEMBER OF THE PUBLIC (Continued) 3.4.1.1 ANNUAL TOTAL ORGAN DOSE (DroT (0))

12 2/3 DTOT (0) = E ! z [ Dil(OG) + Di,(OL) + Dj1 (OG)] (3-1) 1=1 j=1 3H - ! "

NOTE: Dij(OG) = 0 for bone

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

where:

DJ1 (OG) K E C1 EkRik Wk (3-2)

'-; i=1 i = each isotope in specific organ category

.. f j -= Units 1, 2 and 3 I = amonths 1 - 12'*

K ='

er-MCi 3.1688E-2 vsecrC n = number of isotopes in the specified organ category Ci = - total particulate gas curies' released for the month Z Rik Wk = controlling location factors from ODCM Table 2-5, Unit 1 and Table 2-6, Units'2/3 Dj,(OL) - = ;;liquid organ dose for the specified organ, in mrem, for the month. [Unit 1 (1-13),

Units 2/3 (1-19)]

DJ1 (OG) -=

gas organ dose from tritium, mrem, for

the'month. [Unit'1 (2-14), Units 2/3 (2-18)]

S01-ODCM Revision 9

3-5 08-04-93 S0l - ODCM

3.0 TOTAL AND PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 TOTAL DOSE TO MOST LIKELY MEMBER OF THE PUBLIC (Continued) 3.4.1.2 ANNUAL TOTAL WHOLE BODY DOSE (DyOT (WB))

12 2/3 ++

DTOT (WB) = E z [D,, (WBL) + D~i' (OG) + 0.9 Djl(y)JI+ D(Direct) (3-3)

To be summed over the most recent 12 months.

where:

j = Units 1, 2 and 3

= months 1 - 12*

D31 (WBL) = liquid whole body organ dose mrem, for the whole month. [Unit 1 (1-13), Units 2/3

(1-19)]

D;H (OG) = gas organ dose from tritium, mrem, for the month. [Unit 1 (2-14), Units 2/3 (2-18)]

DiI(y) = gamma air dose, mrad, for the month. 0.9 converts mrad to mrem. [Unit 1 (2-10),

Units 2/3 (2-14)]

n

.4 l D(bkgd)1 D (Direct) = z max[D(site)1 ] - p=1 n .0342 (3-4) n=1

-I -

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

.0342 = prorated occupancy factor based on 300 hour0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months s/year.

site = TLD locations within 5 miles of the site.

SO1-ODCM Revision 11 3-6 12-06-95 SO1-ODCM

3.0 TOTAL AND PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 TOTAL DOSE TO MOST LIKELY MEMBER OF THE PUBLIC (Continued) 3.4.1.2 ANNUAL TOTAL WHOLE BODY DOSE (DTOT (WB)) (Continued)

Direct Radiation The direct radiation levels are evaluated most recently using thulium doped TLDs. The TLDs are placed at a minimum of,30 locations around the site- The average dose from TLDs 5 to 50 miles from the site is used as background. *.These sites are subject to change.

The background issubtracted 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

..-,October 1, 1991.

3.4.1.3 ANNUAL TOTAL THYROID DOSE (DIOT (T))

12 2/3 DTOT(T) E - E [DJI (OG) + DJ 1 (OL)] (3-5) 1=1 j=1

.To be summed over the most recent 12 months.

where:

- Units 1, 2 and 3 1 = months 1 - 12'

, Dj1(OG) = -thyroid organ dose from gaseous iodine for the month, mrem. [from (3-2)]

Dj1(OL) ..liquid thyroid organ-dose for the month,

. mrem. [Unit 1 (1-13), Units 2/3 (1-19)]

S01-ODCM Revision 15

.3-7 05-03-99 SO1-ODCM

4.0 EQUIPMENT 4.1 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION 4.1.1 SPECIFICATION AIpRlicabilitv: During releases via this pathway.

Objective: Monitor and control radioactive liquid effluent releases.

Specification: A. The radioactive liquid effluent monitoring instrumentation channels shown in Table 4-1 shall be FUNCTIONAL with their alarm/trip setpoints set to ensure that the limits of Specification 1.1.1 are not exceeded.

B. Action:

1. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of Specification 1.1.1 are met, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel nonfunctional, or change the setpoint so it is acceptably conservative.

2. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels FUNCTIONAL, take the ACTION shown in Table 4-1. If the nonfunctional instruments remain nonfunctional for greater than 30 days, explain in the next Annual Radioactive Effluent Release Report why the nonfunctional status was not corrected in a timely manner.

3. With less than the minimum number of radioactive liquid effluent monitoring instrumentation' channels FUNCTIONAL and either the appropriate ACTION items in Table 4-1 not taken or the necessary surveillances not performed at the specified frequency prescribed in Table 4-2, perform an evaluation based on the significance of the event in accordance with the site Corrective Action Program.

S01-ODCM Revision 17 4-1 07-20-00 SO1-ODCM'

TABLE.4-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT ' ' FUNCTIONAL ACTION

1. Gross Radioactive Monitors Providing'Automatic Termination of 'Release

a. Liquid Radwaste Effluent Line2(R-1218) (1) 16

b. DELETED C. DELETED Ib

d. Yard Sump Effluent Line (R-2101) (1) 18

e. 'DELETED

2. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent'Line (1) 20 (FE-16/FT-8, FE-18/FT-10)

b. Circulating Water Outfall ,

c. DELETE

3. Plant Information Monitoring System (PIMS) (1) 25

-(Control Room'Alarm Annunciation),,

I .. .. . -

. , .7 .;; .

'Pump status, valve turns or calculations are utilized to estimate flow.

S01-ODCM I Revision 22 2 09-03-04 SO1-ODCM

TABLE 4-1 (Continued)

TABLE NOTATION ACTION 16 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided that prior to initiating a release:

1. At least two separate samples which can be taken by a single person are analyzed in accordance with Specification 1.1.2, and;

2. At least two technically qualified persons verify the release rate calculations and discharge valving.

ACTION 17 DELETED ACTION 18 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of collection time for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10- microcurie/ml.

ACTION 19 DELETED ACTION 20 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided the process flow rate is estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during actual releases. In addition, a new flow estimate shall be made within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after a change that affects process flow has been completed. Pump curves may be used to estimate process flow.

ACTION 25 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided the monitor is verified FUNCTIONAL by performing a CHANNEL CHECK at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases, otherwise, declare the affected monitor non-functional.

SO1-ODCM Revision 17 4-3 07-20-00 SO1-ODCM

4.0 EQUIPMENT (Continued) 4.1 RADIOACTIVE LIOUID EFFLUENT INSTRUMENTATION (Continued) 4.1.2 SURVEILLANCE Applicabilitv:. During releases via this pathway.

Ob.iective: To specify the minimum frequency and type of surveillance to be applied to the radioactive liquid instrumentation.

SDecification: A. The setpoints shall be determined'in accordance with Section 1.4.

B. Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL TEST operations at the frequencies shown'in

.Table 4-2.

S01-ODCM Revision 10 4 04-27-94 SO1-ODCM

TABLE 4-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT CHANNEL SOURCE CHANNEL CHANNEL CHECK CHECK CALIBRATION TEST

1. Gross Beta or Gamma Radio-activity Monitoring Providing Alarm and Automatic Isolation

a. Liquid Radwaste Effluent D P(6) 18M(3) Q(1)

Line (R-1218)

b. DELETED

c. DELETED ID

d. Yard Sump Effluent Line D M(6) 18M(3) Q(1)

(R-2101)

e. DELETED

2. Flow Rate Monitors

a. Liquid Radwaste Effluent D(4) N/A 18M N/A Line (FE-16/FT-8, FE-18/FT-10)

3. Plant Information Monitoring D N/A N/A(5) Q(1)

System (PIMS) (Control Room Alarm Annunciation)

SO1-ODCM Revision 22 4-5. 09-03-04 SO1-ODCM

TABLE 4-2 (Continued)

TABLE NOTATION (1) The CHANNEL TEST'.also demonstrates-the following:..

1. Automatic isolation of this'pathway and control room alarm annunciation occurs when the instrument indicates measured levels above the alarm/trip setpoint..

2.. Control Room alarm annunciation when the instrument controls are not

.set in the operate-mode. .,

(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 the suppliers

'that'participate in measurement assurance activities with NIST. These standards shall permit-calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources

. that have been'related.to.the initial calibration shall be used.

-. (Operating.plants may substitute-previously established calibration procedures for this requirement.)

(4) CHANNEL.CHECK shall consist of verifying indication of flow during periods of release.-CHANNEL.CHECK shall be made at least once daily on any day in which continuous, periodic, or batch releases are made.

(5) The Plant.Information Monitoring-System (PIMS) software and hardware do not

,-require CHANNEL CALIBRATION.-' The PIMS software is quality affecting and controlled by the site programs. The PIMS hardware is installed plant equipment and-controlled by the site design change process.

(6) MGPI monitors 'perform a periodic'automatic detector response verification.

No manual operator action is.'required as the monitor will report a failure if the source check does not pass.

S01-ODCM Revision 21 4-6 02-26-04 SO1-ODCM

4.0 EQUIPMENT (Continued) 4.2 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION 4.2.1 SPECIFICATION Applicability: During releases via this pathway.

Objective: Monitor and control radioactive gaseous releases.

Specification: A. The radioactive gaseous effluent monitoring instrumentation channels show in Table 4-3 shall be FUNCTIONAL with their alarm/trip setpoints set to ensure that the limits of Specification 2.1.1 are not exceeded.

B. ACTION

1. Once transfer of spent fuel to the ISFSI is completed, the noble gas source term no A longer exists and this action is not applicable. See AR 040501435-16. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of 2.1.1 are met, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel nonfunctional, or change the setpoint so it is acceptably conservative.

2. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels FUNCTIONAL. take the ACTION shown in Table 4-3. If the nonfunctional instruments remain nonfunctional for greater than 30 days, explain in the next Annual Radioactive Effluent Release Report why the nonfunctional status was not corrected in a timely manner.

3. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels FUNCTIONAL 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, perform an evaluation based on the significance of the event in accordance with the site Corrective Action Program.

So1-ODCM Revision 22 4-7 09-03-04 SO1-ODCM

I

-TABLE 4-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS -.

INSTRUMENT FUNCTIONAL' ACTION

1. Stack Monitoring System' .

a. DELETED..

b., Noble Gas Activity MONITOR R-12544 7' (1) 22 1I

c. DELETED

d. 'Particulate Sample FILTER R-1254 5 - .(1), 23 '

e. DELETED

f. Sampler Flow Rate Measuring Device *(i) 24

2. Plant Information Monitor-ing System',(PIMS)

(Control Room Alarm Annunciation)

(1) . . 26' (24)- 1Ar I' q' '-; O-- . ' I.

Includes the following subsystems:

a. Spent Fuel Building ventilation and Auxiliary Building ventilation.

-b. -Containment Building ventilation ' -

2

. DELETED.

.3 DELETED.

4 High range not required. Mid range shall be maintained functional during evolutions in which an FHA is possible. This includes fuel handling and movement of heavy loads over the fuel in the pool. Low range required in service at all times. (Ref. design calculation DC-3782)

S Heat tracing is required to be functional.

6 DELETED ID Once transfer of spent fuel to the ISFSI is completed, the noble gas source term no longer exists and the noble gas monitor is not required. See AR 040501435-16.

SO1-ODCM Revision 22 4-8 09-03-04 SO1-ODCM

l TABLE 4-3 (Continued)

TABLE NOTATION ACTION 21 DELETED ACTION 22 Once transfer of spent fuel to the ISFSI is completed, the noble gas channel is no longer required and this Action becomes not applicable. See AR 040501435-16. With the number of channels FUNCTIONAL less than the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway-may continue, provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 23 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via the affected pathway may continue, provided samples are continuously collected with auxiliary sampling equipment as required in Table 2-1.

ACTION 24 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided the particulate sample flowrate is estimated or verified at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during actual releases.

ACTION 26 Once transfer of spent fuel to the ISFSI is completed, Action 26 becomes not applicable and Action 24 applies. With the number of 1A channels FUNCTIONAL less than required- by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided the monitor is verified FUNCTIONAL by performing a CHANNEL CHECK at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases, otherwise, declare the affected monitor non-functional.

So1-ODCM.

Revision 22 4-9 09-03-04 SO1-ODCM

4.0 EQUIPMENT (Continued) 4.2 RADIOACTIVE GASEOUS PROCESS-AND EFFLUENT.INSTRUMENTATION (Continued)

. , ., JI 4.2.2 SURVEILLANCE Applicability: During releases via this pathway.

Objective: To specify the minimum frequency and type of surveillance to be applied to the radioactive gaseous monitoring instrumentation.

Specification: A. Once transfer of spent fuel to the ISFSI is completed, the noble gas source term no longer exists and'this specification is not applicable.

See AR 040501435-16. The setpoints shall be determined in accordance with Section 2.5.

B. Each radioactive gaseous process or effluent.

monitoring instrumentation channel 'shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL TEST operations at the frequencies shown in Table 4-4.

- ,- . -. I

. . 'I

. , . v .

. x . )

, . : . -1 I

@'~~" I , -_

'~~~ ;10 -'S; S01-ODCM Revision 22 09-03-04 SO1-ODCM

TABLE 4-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING-INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Stack Monitoring System

a. DELETED

b. Noble Gas Activity Monitor R-1254 (7) D M(5) 18M(2) Q(1)

c. DELETED ID

d. Particulate Sampler Filter R-1254 N/A N/A N/A N/A

e. Stack Fan Flow See Note (3)

f. Sampler Flow Rate Measuring Device D N/A 18M N/A

2. Plant Information Monitoring System 0 N/A N/A(4) Q(1) lb (PIMS) (Control Room Alarm Annunciation)

TABLE NOTATION (1) The CHANNEL TEST also demonstrates the following:

1. Control room alarm annunciation occurs when the instrument indicates measured levels above the alarm/trip setpoint.

2. Control room alarm annunciation when the instrument controls are not set in the operate mode.

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of.

the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(Operating plants may substitute previously established calibration procedures for this requirement.)

(3) Perform stack fan flow measurement once every 60 months.

(4) The Plant Information Monitoring System (PIMS) software and hardware do not require CHANNEL CALIBRATION. The PIMS software is quality affecting and controlled by the site Software Modification Request Process under procedure S0123-V-4.71, Software Development and Maintenance. The PIMS hardware is installed plant equipment and controlled by the site design change process utilizing procedure S0123-XXIX-2.10, Design Change Process, or S0123-XXIV-10.21, Field Change Notice (FCN) and Fie1d Interim Design Change Notice (FIDCN).

(5) The monitor performs an automatic check source test each 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . No manual operator action is required.

(6) DELETED ID (7) Once transfer of spent fuel to the ISFSI is completed, the noble gas source term no longer exists and the noble gas monitor is not required.

See AR 040501435-16.

S01-ODCM Revision 22 4-11 09-03-04 SOI-ODCM

4.0 EQUIPMENT (Continued) 4.3 FUNCTIONALITY OF RADIOACTIVE WASTE EQUIPMENT The flow diagrams defining the treatment paths and the components-of the radioactive liquid, gaseous and solid waste management systems are shown.

in Figures 4-1 thru 4-3.

I

. I L, ::

" k e..

.1. .

S01-ODCM Revision 10 4-12 04-27-94 SOI -ODCM

cn 0

EO 0

CCWHX I D Equipment, Drains_

&Valve Leakago Spent Resin Holdup Radwaste Drains Tank T IR it Decon Showers Aux Bldg aay Iloor drains Building _ Fitr _* Filter Monitor equip leakage & Sump lank drains R-1218 Fuel Storage Doron Bldg Drains Tank Decon Shower --- Y Tank upR210 Pacifi SONGS 1 Liquid Waste Discharge System Figure 4-1 SO1-ODCM Revision 22 4-13 09-03-04

Air Filter Fan Air -4p A Ir _{

Air ~A ux iliarya Building SONGS 1 Radioactive Gaseous-Waste System-,

Figure 4-2 SO1-ODCM Revision 22 4-14 09-03-04

Spent lRasm Particulate Process filters Low Level try Active Waste ClothingpClothing packed Clet bas to boxes am lmmndered 1 LICE"I' Protective culiectud from shipped, to SITs Spat Ni lo. Tank Clething points arould off-site raetrsed to PIP11 Multi Purpose NIelng facilit plant lam1dry site and luon Excheager facility restocked SONGS 1 Solid Waste Handling Figure 4-3 SO1-ODCM Revision 15 4-15 05-03-99

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 MONITORING PROGRAM 5.1.1 SPECIFICATION APPLICABILITY: At all times..

OBJECTIVE: Monitor exposure pathways for radiation and radioactive material.

SPECIFICATION: A. The radiological environmental monitoring program shall be conducted as specified in Table 5-1.

B. ACTION:

-1. With the radiological environmental monitoring program not being conducted as

-specifiedin Table 5-1, prepare and submit to the Commission, in the Annual

- iRadiological Environmental Operating Report (see Section 5.4), a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

2. With the level of radioactivity as the result of plant effluents in an

---environmental sampling medium exceeding the reporting levels of Table 5-1 when averaged over any calendar quarter, prepare and-submit to the Commission within 30 days from the end of the affected calendar quarter a Special Report pursuant to Technical Specification D6.9.2. When more than one of the radionuclides in Table 5-1 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) + ... 2 reporting level (1) reporting level (2)

When radionuclides other than those in Table 5-1 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Specifications 1.2.1, 2.2.1, and 2.3.1.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

S01-ODCM Revision 10 5-1 04-27-94 SO1-ODCM

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.1 MONITORING PROGRAM (Continued) 5.1.1 SPECIFICATION (Continued)

SPECIFICATION: B. ACTION: (Continued)

3. With fresh leafy vegetable samples or fleshy vegetable samples unavailable from one or more of the sample locations required by Table 5-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification D6.9.1, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples.

S01-ODCM Revision 13 5-2 02-27-98 SOl-ODCM

TABLE 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or SamDle and Sample Locations" Collection Freguency' TyDe and Freauencv of Analyses

1. AIRBORNE Samples from at least Continuous operation Radioiodine cartridge. Analyze at Radioiodine 5 locations of sampler with least once per 7 days for I-131.

and 3 samples from offsite sample collection as Particulate sampler. Analyze for Particulates locations (indifferent required by dust gross beta radioactivity 2 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sectors) of the highest loading, but at least following filter change. Perform calculated annual average once per 7 days.d gamma isotopicb analysis on each ground level D/Q. sample when gross beta activity is 2 10 times the yearly mean of 1 sample from the vicinity of a control samples. Perform gamma community having the highest isotopic analysis on composite (by calculated annual average location) sample at least once per ground level D/Q. 92 days.

1 sample from a control location'15-30 km (10-20 miles) distant and in the least prevalent wind direction'.

2. DIRECT RADIATION' At least 30 locations including At least once per Gamma dose. At least once per an inner ring of stations in 92 days. 92 days.

the general area of the SITE BOUNDARY and an outer ring approximately in the 4 to 5 mile range from the Site with a station in each sector of each ring. The balance of the stations are in special interest areas such as population centers, nearby residences, schools, and 2 or 3 areas to serve as control stations.

S01-ODCM Revision 8 5-3 06-29-92

TABLE 5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or SamDle and Sample Locations" Collection FreQuencv' Type and Freauencv of Analyses

3. WATERBORNE a.. Ocean 4 locations At least once per Gamma isotopic analysis of each month and composited monthly sample. Tritium analysis of quarterly composite sample at least once per 92 days.

b. Drinkingf 2 locations Monthly at each Gamma isotopic and tritium analyses location. of each sample.

c. Sediment 4 locations At least once per Gamma isotopic analysis of each from Shoreline 184 days. sample.

d. Ocean 5 locations At least once per Gamma isotopic analysis of each Bottom Sediments 184 days. sample.

S01-ODCM Revision 14 5-4 02-25-99

cn 0

TABLE 5-1 (Continued) t:

0)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Sample and Sample Locations' Collection Freauencvy Type and Frequency of Analyses

4. INGESTION

a. Nonmigratory 3 locations One sample from each Gamma isotopic analysis of an edible Marine Animals group (listed below) portion.

will be collected in season, or at least once per 184 days if not seasonal. Groups to be sampled:

1. Fish - 2 adult species such as flatfish, bass, perch, or sheephead.

2. Crustacea - such

.. . ... . .. . . . 1.. ...

as. crab or.

.I ..

. I .

.I .. .

. 1.

lobster., .

... . , I- ;1 ' ! I

3. Mollusks such as limpets, clams or seahares.

b. Local Crops 2 locations Representative, Gamma isotopic analysis on edible vegetables, normally portions semiannually and I-131 1 leafy and 1 fleshy analysis for leafy crops.

collected at harvest time. At least 2 vegetables collected semiannually from each .location.

S01-ODCM Revision 8 5-5 06-29-92

En 0

0P-8 TABLE 5-1 (Continued) 3 TABLE NOTATION

a. Sample locations are indicated in Figures 5-1 through 5-5.

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 substituted.

d. Canisters for the collection of radioiodine 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. No drinking water pathway exists at SONGS.

SO1-ODCM Revision 14 5-6 02-25-99

TABLE 5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Analysis Water Airborne (pCi/1) Particulate or Gases Marine Animals Local Crops (pCi/m 3 ) (pCi/Kg, wet) (pCi/Kg, wet)

H-3 2 x 104' Mn-54 1 x lo, 3 x 10' Fe-59 4 x1 2 I Xlo, Co-58 1 x 10i 3 x 10.

Co-60 3 x102 1 x 10o Zn-65 3 x 101 2 x 10' Zr-Nb-95 4 x 10-1-131 2b 0.9 1 x 10 2 Cs-134 30 10 I X10 3 1 X 103 3

Cs-137 50 20 2 x 103 2 x 10 Ba-La-140 2 x 102 If no drinking pathway exists, a value of 30,000 pCi/t may be used.

If no drinking water pathway exists, a value of 20 pCi/I may be used.

S01-ODCM Revision 12 5-7 01-29-97

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.1 MONITORING PROGRAM (Continued) 5.1.2 SURVEILLANCE APPLICABILITY: At all times.

OBJECTIVE: Ensure required actions of the radiological monitoring program are being performed.

SPECIFICATION: The radiological environmental monitoring samples shall be collected pursuant to Table 5-1 from the locations given in Tables 5-4 and 5-5 and Figures 5-1 through 5-5, and shall be analyzed pursuant to the requirements of Tables 5-1 and 5-3.

S01-ODCM Revision 13 5-8 02-27-98 SO1-ODCM

En 0

0 TABLE 5-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)-,

.- Airborne Particulate Water or Gases Marine Animals Local Crops Sediment Analysis (pCi/1)' (pCi/m 3 ) (pCi/Kg, wet) (pCi/Kg, wet) (pCi/kg, dry)

Gross beta 4 1 x 10.2 H-3 20 00 b Mn-54 15 130 Fe-59 30 260 Co-58, 60 15' 130 Zn-65 - 30 260 Zr-95, Nb-95 15 -

I-131' 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, La-140 15 S01-ODCM Revision 12 5-9 01-29-97

! TABLE 5-3 (Continued)

TABLE NOTATION

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

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

4.66 sb LLD =

E *V *2.22 x106 Y exp (-Mt) where:

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

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

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

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

2.22 x 106 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between sample collection (or end of the sample collection period) and time of counting.

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 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 present in the samples (e.g., potassium-40 in milk samples). Typical values of E, V. Y and At shall be used in the calculations.

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.'

S01-ODCM Revision 11 5-10 12-06-95 SO1-ODCM

TABLE 5-3 '(Continued)

TABLE NOTATION

b. If no drinking water pathway exists, a value of 3,000 pCi/f may be used.

c. Other peaks'which are measurable and identifiable, together with the radionuclides' in Table 5-3, shall' be identified and reported.

d. If no drinking water pathway exists, a value of 15 pCi/f may be used.

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). -;

SO1-ODCM Revision 12 5-11 01-29-97 SOI -ODCM

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.2 LAND USE CENSUS 5.2.1 SPECIFICATION APPLICABILITY: At all times.

OBJECTIVE: Monitor the UNRESTRICTED AREAS surrounding the site for potential changes to the radiological monitoring program as necessary.

SPECIFICATION: A. A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden* of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sections within a distance of five miles.

B. ACTION:

1. With the 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, pursuant to Technical Specification D6.9.1, identify the new locations in the next Annual Radioactive Effluent Release Report.

2. With the land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 5.1.1. add the new location within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location(s),

excluding the control station location, having the lowest calculated dose or dose commitment(s) via the same exposure pathway,. may be deleted from this monitoring program after October 31, of the year in which this Land Use Census was conducted. Pursuant to Technical Specification D6.9.1, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

Broad leaf vegetation sampling may be performed at the SITE BOUNDARY in the direction section with the highest D/Q in lieu of the garden census.

S01-ODCM Revision 13 5-12 02-27-98 SO1-ODCM

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING: (Continued) 5.2 LAND USE CENSUS (Continued) 5.2.2 SURVEILLANCE APPLICABILITY: At all times..

OBJECTIVE: Perform the land use census to ensure the monitoring program is appropriate for the surrounding areas.

SPECIFICATION: The land use census shall be conducted at least once per 12 months between the date 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 agricultural authorities.

SOI -ODCM Revision 8 5-13 06-29-92 SO1-ODCM

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.3 INTERLABORATORY COMPARISON PROGRAM 5.3.1 SPECIFICATION APPLICABILITY: At all times.

OBJECTIVE: To ensure laboratory analysis of radiological environmental monitoring samples is correct and accurate.

SPECIFICATION: A. Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that complies with Regulatory Guide 4.15.

B. ACTION:

1. 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.

(Section 5.4)

S01-ODCM Revision 14 5-14 02-25-99 SO1-ODCM

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) -

5.3 INTERLABORATORY COMPARISON PROGRAM (Continued) 5.3.2 SURVEILLANCE APPLICABILITY: At all times.,

OBJECTIVE: To ensure laboratory analysis of radiological environmental monitoring samples is correct and accurate.

SPECIFICATION: A summary-.of-the results.,obtained as part of the InterlaboratoryComparison Program and in accordance with the ODCM shall be included in the Annual Radiological Environmental Operating Report.

(Section 5.4)

S01-ODCM Revision 8 5-15 06-29-92 SOI -ODCM

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT' 5.4.1 Routine radiological environmental operating reports for the unit during the previous calendar year shall be submitted prior to May 1 of each year.

5.4.2 The annual radiological environmental operating reports 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 Specification 5.2.1. 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 the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979, 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 for all sampling locations keyed to a table giving distances and directions from the site reference point; and the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 5.3.1.

(Note: Information which may be required by Specifications 5.1.1, 5.1.2, 5.3.2 and Section 6.4.18 should be included.

1A 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.

SOl-ODCM Revision 14 5-16 02-25-99 SO1-ODCM

5.0. RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.5 SAMPLE LOCATIONS' The Radiological Environmental Monitoring Sample Locations are identified in Figures 5-1 through 5-5. These sample locations are describedin Table 5-4 and indicates the distance in miles and the direction,.determined from degrees true.north,-from the center of the Units 2 and'3-building-'complex.-'7Table 5-6 gives-the sector-and '

direction designation for the Radiological Environmental:Monitoring Sample Location Map, Figuress5-1.through,5-5. ,

'Ifa milk producing dairy animal is discovered within the 5 mile radius of the Emergency Planning Zone (EPZ) during the annual land use census, *amonthly sampling analysis of the milk will comm~ence.

S01-ODCM Revision 18 5-17 02-21-01 SO1-ODCM

TABLE 5-4 Page 1 of 6 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE' TYPE OF SAMPLE AND SAMPLING LOCATION... (miles) DIRECTION' Direct Radiation 1 City of San Clemente (Former SDG&E Offices) 5.7 NW 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 6 Old Route 101 (East-Southeast) 3.0 ESE 8 Noncommissioned Officers' Beach Club 1.4 NW 10 Bluff (Adjacent to PIC 11) 0.7 WNW 11 Former Visitors' Center 0.4" NW 12 South Edge of Switchyard 0.2 E 13 Southeast Site boundary (Bluff) 0.4" ESE 15 Southeast Site Boundary (Office Building) 0.1" SSE 16 East Southeast Site Boundary 0.4* ESE 17 Transit Dose 18 Transit Dose -

19 San Clemente Highlands 5.0 NNW 22 Former U.S. Coast Guard Station - San Mateo Point 2.7 WNW 23 SDG&E Service Center Yard 8.1 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 S01-ODCM Revision 21 5-18 02-26-04 SO -ODCM

. .TABLE 5-4 Page 2 of 6

. ADIOLOI L. .A M OI I . .

.ATN . .

RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE TYPE OF SAMPLE AND SAMPLING LOCATION'" (miles)

\ _

DIRErTTON*

Direct Radiation (Continued) 31 Aurora Park-Mission Viejo (CONTROL) 18.6 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)i 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 (Adjacent to PIC #3) 0.7 NNW 41 Old Route 101 - East 0.3 E 44 Fallbrook Fire Station 17.7 E 46 San Onofre State Beach Park 0.9 SE 47 Camp Las Flores (MCB, Camp Pendleton) 8.6 SE Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint.

Direction is determined from degrees true north.

Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.

MCB - Marine Corps Base PIC - Pressurized Ion Chamber S01-ODCM Revision 14 5-19 02-25-99 SO1-ODCM

TABLE 5-4 Page 3 of 6 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE7 TYPE OF SAMPLE AND SAMPLING LOCATION... (miles) DIRECTION*

Direct Radiation (Continued) 49 Camp Chappo (MCB, Camp Pendleton) 12.8 ESE 50 Oceanside Fire Station (CONTROL) 15.6 SE 53 San Diego County Operations Center 44.3 SE 54 Escondido Fire Station 31.8 ESE 55 San Onofre State Beach (Unit 1, West) O.2* W 56 San Onofre State Beach (Unit 1. West) 0.2 W 57 San Onofre State Beach (Unit 2) 0.1 WSW 58 San Onofre State Beach (Unit 3) O.1* 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) 0.6 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 Yard Facility 0.4^ ESE Transit Control A Transit Control B Fader (Co-located with TLD #54) 31.8 ESE 74 Oceanside City Hall (Backup CONTROL) 15.6 SE 75 Gate 25 MCB 4.6 SE 76 El Camino Real Mobil Station 4.6 NW 77 Area 62 Heavy lift pad 4.3 N 78 Sheep Valley 4.4 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.

S01-ODCM Revision 14 5-20 02-25-99 SO1-ODCM

- ~ TABLE 5-4 Page 4 of 6 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE TYPE OF SAMPLE AND SAMPLING LOCATION (fmiles)

~__ DIRFCTION Airborne 1 City of San Clemente (City Hall) 5.1. NW 7 AWS ROOF 0.18^ NW 9 State Beach Park 0.6 ESE 10 Bluff 0.7 - WNW 11 Mesa EOF .- 0.7 NNW 12 Former SONGS Evaporation Pond -0.6 NW 13 Marine Corps Base (Camp Pendleton East) -0.7 E 14 Mesa Medical Facility ! : ;, 0.7 NNW 15 City Hall Oceanside (CONTROL) 15.6 SE Soil Samples' 1 Camp San Onofre 2.6 NE 2 Old Route 101 - East Southeast 3.0 ESE 3 Basilone Road/I-S Freeway Offramp . 2.0 :! NW 5 Former Visitor's Center 0.4 NW 6 Oceanside (CONTROL) 16 SE Ocean Water A Station Discharge Outfall - Unit 1 0.6 SW B Outfall - Unit 2 1.5 SW C Outfall - Unit 3 1.2. SSW. . -

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.- -

z . i, f ' :..

Distances are within the Units 2 and 3 Site boundary (0.4 mile in all sectors) and not required by Technical Specification.

t Soil Samples *are not required by Technical Specifications.

S01 -ODCM Revision 20 5-21 02-28-03 S01-ODCM

TABLE 5-4 Page 5 of 6 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE' TYPF OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION Drinking Water 4 Camp Pendleton Drinking Water Reservoir 2.2 NNW 5 Oceanside (CONTROL) 15.6 SE Shoreline Sediment (Beach Sand) 1 San Onofre State Beach (Southeast) 0.6 SE 2 San Onofre Surfing Beach 0.8 WNW 3 San Onofre State Beach (Southeast) 3.5 SE 4 Newport Beach (North End) (CONTROL) 29.2 NW Local Crops 1 San Clemente Ranch (San Mateo Canyon) 2.6 NW 2 Oceanside (CONTROL)" 15 to 25 SE to ESE 4 San Clemente Resident w/Garden 4.4 NW 6 SONGS Garden 0.4 NNW

Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

Control location shall, be in sector G or F, 15 to 25 miles from the site.

The control location will be selected based on sample availability. The exact location will be noted in the Annual Radiological Environmental Operating Report.

S01-ODCM Revision 19 5-22 02-28-02 SO1-ODCM

r- TABLE 5-4 Page 6 of 6 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE*

TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION' Non-Migratory Marine Animals A Unit 1 Outfall 0.9 WSW B Units 2 and 3 Outfall 1.5 SSW C Laguna Beach (CONTROL) 18.2 NW Kelpt-A San Onofre Kelp Bed 1.5 S B San Mateo Kelp Bed 3.8 WNW C Barn Kelp Bed 6.3 SSE D Deleted E Salt Creek (CONTROL) . 11 to 13 WNW to NW Ocean Bottom Sediments A Deleted B Unit 1 Outfall 0.8 SSW C Unit 2 Outfall 1.6 SW D Unit 3 Outfall 1.2 SSW E Laguna Beach (CONTROL) 18.2 NW F SONGS Upcoast 0.9 WSW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

Kelp Samples are not required by Technical Specifications.

SO1-ODCM Revision 20 5-23 02-28-03 SO1-ODCM

TABLE 5-5 PIC - RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS SONGS 1 Thieta DISTANCE PRESSURIZED ION CHAMBERS (De !qrees) Meters miles DIRECTION/SECTOR' S1 San Onofre Beach 2980 1070 0.7 WNW P S2 SONGS Former Evap. Pnd 3130 890 0.6 NW Q S3 Japanese Mesa 3400 1150 0.7 NNW R S4 MCB - Camp Pendleton 30 1120 0.7 N A S5 MCB - Camp Pendleton 190 1050 0.6 NNE B S6 MCB - Camp Pendleton 460 940 0.6 NE C S7 MCB - Camp Pendleton 700 870 0.6 ENE D S8 MCB - Camp Pendleton 980 1120 0.7 E E S9 San Onofre State Beach 1210 940 0.6 ESE F

Distance (meters/miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Theta direction is determined from degrees true north. -

SO1-ODCM Revision 18 5-24 02-21-01 SO1-ODCM

TABLE 5-6 SECTOR AND DIRECTION DESIGNATION FOR RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATION MAP

- DEGREESTRUE NORTH FROM

.....SONGS 2 AND, 3 MlI-POINT

_ NOMENCLATURE Sector Center Sector 22.50 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 56.25zs- C NE 56.25 67.5 78.75 D ENE 78.75 90.0 101.25 E E.

101.25 112.0 123.75-- F ESE 123.75 135.0 146.25 G SE 146.25 157.0 168.75, H SSE 168.75 - 180.0 191-.25 J I S.

191.25 202.5 .213.75 K SSW 213.75 - 225.0 236.25 L S 236.25 247.5 258.75- M WSW 258.75 270.0 281.25 IN W 281.25 292.5 303.75 P WNW 303.75 3i5.0 326.25 Q NW 326.25 337.5 348.75 R NNW.

I..

Distance (miles) and Direction, (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true'North.

SO1-ODCM Revision 15 5-25 05-03-99 SO1 -ODCM

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6.0 ADMINISTRATIVE 6.1 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout the ODCM.

I. .

ACTION I .

6.1.1 ACTION shall be that part of a specification which

prescribes remedial measures required under designated conditions.

'CHANNEL CALIBRATION 6.1.2 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of-the channel such that it responds with the required range and accuracy toknown values of input.

The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions, and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK . ...

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 same parameter.

CHANNEL TEST 6.1.4 A CHANNEL TEST shall be the injection of a simulated signal into!the channel to verify its proper response including, where applicable, alarm and/or trip initiating action. The CHANNEL-TEST shall include adjustments, as necessary, of the alarm, interlock and/or trip setpoints, such that the setpoints are within the required range and accuracy.

SO1-ODCM Revision 9 6-1 08-04-93 SO -ODCM

6.0 ADMINISTRATIVE (Continued) 6.1 DEFINITIONS (Continued)

FRE0UENCY NOTATION 6.1.5 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 6-2.

FUNCTIONAL 6.1.6 A functional system, subsystem, train, component, or device is capable of performing its specified function(s) and is maintained in accordance with good engineering and maintenancepractices for commercial grade equipment. Surveillances required within this document are required to maintain instrumentation as FUNCTIONAL.

6.1.7 DELETED MEMBER(S) OF THE PUBLIC 6.1.8 MEMBER(S) OF THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant. This category complies with the requirements of 10CFR5O and shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or purposes not associated with plant functions. Supplemental workers and their dependents are included in this definition while they temporarily reside at Camp Mesa. 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.

S01-ODCM Revision 21 6-2 02-26-04 SO1-ODCM

6.0 ADMINISTRATIVE (Continued) 6.1 DEFINITIONS (Continued)

PROCESS CONTROL PROGRAM;]-

6.1.9 The PROCESS :CONTROL PROGRAM shall contain the current

- formula,- sampling, analysis, and formulation determinationwby which SOLIDIFICATION of radioactive wastes from liquid systems is assured.

SITE BOUNDARY 6.1.10 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.

SOLIDIFICIATION

. r-6.1.11 SOLIDIFICATION shall be the conversion of wet wastes into-a form that meets shipping and burial ground requirements. :

SOURCE CHIECK 6.1.12 For REM RAD analog monitors a SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

For Sorrento Electronics digital Monitors a SOURCE CHECK shall be verification of proper computer response to a check source request.

For MGPI monitors a SOURCE CHECK shall be the verification of proper computer response to the continuous internal detector, monitor calibration and electrical checks.

S01-ODCM Revision 17 6-3 07-20-00 SO -ODCM

6.0 ADMINISTRATIVE (Continued) 6.1 DEFINITIONS (Continued)

SURVEILLANCE REQUIREMENT: MEETING SPECIFIED FREQUENCY 6.1.13 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

This provision is not intended to be used repeatedly as a convenient means to extend Surveillance intervals beyond those specified. Additionally, it does not apply toany Action Statements.

UNRESTRICTED AREA 6.1.14 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials of any area within the site boundary used for residential quarters or industrial. commercial, institutional and/or recreational purposes.

S01-ODCM Revision 15 6-4 05-03-99 SO1-ODCM

TABLE 6-2 FREQUENCY NOTATION NOTATION FREOUENCY-S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D At least once ,per 24.hours 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 18M At least once per 18 months P Completed prior to each release N.A. Not applicable SO1-ODCM Revision 9 08-04-93 S0l -ODCM

6.0 ADMINISTRATIVE (Continued) 6.2 SITE DESCRIPTION The San Onofre Nuclear Generating Station is located on the West Coast of Southern California in San Diego County, about 62 miles southeast of Los Angeles and about 51 miles northwest of San Diego.

The site is located within the U.S. Marine Corps Base, Camp Pendleton, California. The minimum distance to the boundary of the exclusion area as defined in 10CFR100.3 shall be 283.5 meters from the outer edge of the Unit 1 containment sphere. For the purpose of dose assessment, a slightly reduced distance of 282 meters defined by the discontinuous line in Figure 6-1 is assumed.

Basis: Leasing arrangements with the U.S. Marine Corps provide that a minimum distance to the exclusion boundary will be 283.5 meters. All dose assessments are calculated assuming 282 meters.

SOl-ODCM Revision 8 6-6 06-29-92 SO1-ODCM

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6.0 ADMINISTRATIVE (Continued) 6.3 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT' 6.3.1 Routine radioactive effluent release reports for the unit during the previous calendar year shall be submitted before May 1 of each year.

6.3.2 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, with data summarized on a quarterly basis following the format of Appendix B thereof.

The radioactive effluent release report shall include an annual summary of hourly meteorological' data collected over the previous year. This annual 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.2 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 during the report period. All assumptions used in making these'assessments (i.e., specific activity, exposure time'and location) shall'be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents-(as determined by sampling frequency and measurement)'shall be used for determining the gaseous athway doses'. The assessment of radiation doses shall be performed in accordance with Sections 1.5 and 2.6.

'A single submittal may be made for 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.

2In lieu of submission with the Annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request. '

S01-ODCM Revision 9 6-8 08-04-93 SO1-ODCM

6.0 ADMINISTRATIVE (Continued) 6.3 ADMINISTRATIVE CONTROLS (Continued) 6.3.2: (Continued).'..

The radioactive effluent release report shall also

-include an assessmentof radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses fr&m'primary effluent pathways and direct radiation)'for the.previous calendar year 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 Sections

. : . 1.5 and 2.6.' '

The radioactive:effluent release reports shall include the following information for each type of'solid waste shipped offsite during the report period:

a.- -Containervolume,

b. Total curie-quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate),

d. Type of waste.(e.g., dewatered spent resin, compacted='dry.waste, evaporator bottom),

e. Type-of~container (e.g., LSA, Type A, Type B, Large Quantity), and*-

f. Solidification agent (e.g., cement, urea formaldehyde)..

The.radioactive release reports shall include unplanned releases from the site to UNRESTRICTED AREAS of radioactive material in gaseous and liquid effluents made during the'reporting period.

The Annual'Radioactive Effluent Release Reports shall include'anytchangesniade to the PROCESS CONTROL PROGRAM (PCP),'to the'OFFSITE'DOSE CALCULATION MANUAL (ODCM); or major changes to radioactive waste treatment systems

. .during the reporting period. .

.: C S01-ODCM Revision 19 6-9 02-28-02 SO1-ODCM

6.0 ADMINISTRATIVE (Continued) 6.3 ADMINISTRATIVE CONTROLS (Continued) '

6.3.3 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS' (Liquid and baseous)

Licensee initiated. major changes to the radioactive waste systems (liquid and gaseous):

1. Shall be reported to the Commission in the Annua1 Radioactive Effluent Release Report for the period in which the change(s),was made effective ursuant to Quality Assurance Program Description (SCE-1-A),

Subsection 17.2.20.3.1.i. The discussion of each change shall contain:-

a. A summary of the evaluation that led to the determination that the change could be made in accordance with applicable regulations;

b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

c. A detailed description of the equipment components and processes involved and the interfaces with other plant systems;

d. An evaluation of the change which shows the redicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the license application and amendments thereto;

e. An evaluation of the change which shows the expected maximum exposures to an 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 releases for the period prior to when the changes are to be 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 found acceptable pursuant to uality Assurance Program Description

?SCE-1-A). Subsection 17.2.20.3.1.i.

2. Shall become effective upon review and acceptance pursuant to Quality Assurance Program Description (SCE-1-A), Subsection 17.2.20.3.1.i.

'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.

SO1-ODCM Revision 21 6-10 02-26-04 SO1-ODCM

6.0 ADMINISTRATIVE (Continued) 6.4 BASES LIQUID EFFLUENT CONCENTRATION (1.1.1, 1.1.2)

. 6.4.1 These specifications are provided to ensure that the

..concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less :than the concentration levels specified in 10 CFR Part 20, Appendix B. Table II, Column 2. Ihis-limitation provides additional assurance that thelevels of radioactive materials in bodies of water outside the site will result in exposures within (1),the SectionzII.A-design objectives of Appendix I,

-10 CFRPart 50, toa.MEMBER OF. THE PUBLIC, and (2)the limits of 10 CFR Part 20.106(e) .to the population. The concentration limit for noble gases is based upon the assumption.that Xe-135 is the controlling radioisotope

.and its MPC in air. (submersion) was converted to an equivalent concentration in water using .the methods described in International Commission on Radiological Protection '(ICRP)..Publication 2.

-LIOUID EFFLUENT DOSE (1.2.1) 6.4.2. This specificationis provided to implement the requirements of'Section II.A and IV.A of Appendix I,

10 CFR Part 50 .. Specification A implements the guides

-setforth in Section II.A of Appendix I. Specification B provides the required operating flexibility and at the same time implements the guides set forth in Section

. IV.A of Appendix.Ito assure that the-releases of radioactive material in liquid effluents will be kept

,"as low as is'.reasonably achievable."

LIQUID EFFLUENT DOSE (1.2.2)- .--

.6.4.3 . This specification is provided to implement the requirements of Section III.A of Appendix I, 10 CFR Part

50. 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-a MEMBER OF THE PUBLIC through appropriate pathways is.unlikely to be substantially underestimated.

-6 .0.*6.: ; . ;

6-11 06-29-92 SO1-ODCM

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

LIQUID WASTE TREATMENT (1.3.1, 1.3.2) 6.4.4 The FUNCTIONALITY of the liquid radwaste treatment system ensures that this system will be available for use'whenever liquid effluents require treatment prior to release to the environment. The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "asilow as is reasonable achievable." This specification implements the requirements of 10 CFR Part 50.36a 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 guide set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

GASEOUS EFFLUENTS DOSE RATE (2.1.1, 2.1.2) 6.4.5 Once transfer of spent fuel to the ISFSI is completed.

the noble gas source term no longer exists and there is no source of gamma and beta dose. See AR 040501435-16.

Therefore, the limitations pertaining to gamma and beta dose will not be applicable at this time. This specification is'provided to ensure that.the dose rate at and beyond the SITE BOUNDARY from gaseous effluents will be within the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the exclusion area 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'MEMBERS OF THE PUBLIC who may at times be within the exclusion area boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the exclusion area boundary to

500 mrem/year to the total body or to S 3000 mrem/year to the skin.

These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to

1500 mrem/year.

S01-ODCM Revision 22 6-12 09-03-04 S01-ODCM

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

DOSE. NOBLE GASES (2.2.1)-

6.4.6 This specification is provided to implement the requirements of Section II.B-and IV.A of Appendix I, 10 CFR Part 50. Specification A implements the guides set forth in Section II.B of;Appendix I. Specification B provides the-required'operating'flexibility and at the

-same -timevimplements 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 asis reasonably achievable."

DOSE. NOBLE GASES (2.2.2),-,

6.4.7 Once transfer of spent fuel to the ISFSI is completed, the noble gas:source term no longer exists and this A basis is not applicable. See AR 040501435-16. This specification implements the requirements in Section III.A of Appendix I,10 CFR Part 50, that conformance with the guides of-Appendix I, be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE'PUBLIC through.the appropriate pathways is unlikely to be substantially underestimated. The ODCM equations provided for determining the air doses at the SITE BOUNDARY will be based upon the historical average atmospheric conditions.

DOSE. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM (2.3.1) 6.4.8 This specification is provided to implement the requirements of Sections II.C and IV.A of Appendix I, 10 CFR Part 50. Specification A is the guide set forth in Section II.C of Appendix I. Specification B provides the required operating flexibility and at'the'same time implements 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."

DOSE. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM (2.3.2) 6.4.9 This specification implements the requirements in Section III.A of Appendix I, 10 CFR Part 50, that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

S01-ODCM Revision 22 6-13 09-03-04 SO1-ODCM

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

DOSE. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM (2.3.2) IDb (Continued) 6.4.9 (Continued)

The ODCM equations provided for determining the actual doses are based upon the historical average atmospheric conditions. The release rate specifications for tritium and radionuclides in particulate form with half-lives greater than 8 days are dependent on the existing radionuclides pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways which are examined in the development of these calculations are:

(1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation and subsequent consumption by man, (3)deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure to man.

6.4.10 DELETED DOSE (3.3.1) 6.4.11 This specification is provided to meet the reporting requirements of 40 CFR 190. In complying with 40 CFR 190, nuclear fuel cycle facilities over five miles away are not considered to contribute to the dose assessment.

SO1-ODCM Revision 22 6-14 09-03-04 SO1-ODCM

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

DOSE (3.3.2).

6.4.12 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 four 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 the 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 fuel cycle facilities at the same site or within a

.radius of five 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- 40CFR,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 OFTHE.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 (4.1.1, 4.1.2) 6.4.13 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. The alarm/trip

setpoints for these instruments are calculated in accordance with methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFRNPart 20.

RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION (4.2.1, 4.2.2)

'6.4.14 Once transfer'of spent fuel toithe ISFSI is completed, the noble gas source'term~no longer exists and this basis is not applicable. See AR 040501435-16. The

' radioactive gaseous effluent instrumentation is provided

-to monitor and control,.as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The-alarm/trip setpoints for

these instruments are calculated in accordance with methods in this ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

S01-ODCM Revision 22

6-15 09-03-04 SO1-ODCM

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING (5.1.1) 6.4.15 The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials .inthose exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of a MEMBER OF THE PUBLIC resulting from the station operation'. ..

This monitoring program thereby supplements the radiological effluents 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 exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial operation.

Following this period, program changes may be initiated based on operational experience.

RADIOLOGICAL ENVIRONMENTAL MONITORING (5.1.2) 6.4.16 The radiological environmental monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling for the environmental exposure pathways.

The detection capabilities required by Table 5-3 are state-of-the-art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not'as a Dosteriori (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.

SOI-ODCM Revision 8 6-16 06-29-92 SO1-ODCM

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

LAND USE CENSUS (5.2.1) 6.4.17 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 (25 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.

LAND USE CENSUS (5.2.2) 6.4.18 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.

INTERLABORATORY COMPARISON PROGRAM (5.3.1, 5.3.2) 6.4.19 The requirements 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.

S01-ODCM Revision 8 6-17 06-29-92 SO1-ODCM

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