Text

Annual Radioactive Effluent Release Report for 2003
	ML041240398
Person / Time
Site:	San Onofre
Issue date:	04/29/2004
From:	Scherer A; Southern California Edison Co
To:	; Document Control Desk, NRC/FSME
References
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	Download: ML041240398 (413)
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SOUTHERN CALIFORNIA A. Edward Schierer EDISON Manager of Nuclear Regulatory Affairs An EDISON INTERNATIONALV Company April 29, 2004 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Docket Nos. 50-206, 50-361 and 50-362 Annual Radioactive Effluent Release Report - 2003 San Onofre Nuclear Generating Station, Units 1, 2, and 3 Gentlemen:

In accordance with 10 CFR 50.36(a) and Unit 1 Permanently Defueled Technical Specification (TS) Section D6.9.1.4 and Units 2 and 3 TS Section 5.7.1.3, Southern California Edison (SCE) is providing the Annual Radioactive Effluent Release Report (ARERR) for the San Onofre Nuclear Generating Station, Units 1, 2, and 3. The period of the report is January 1, 2003 through December 31, 2003.

Unit 1 Permanently Defueled TS Section D6.14.2.3 and Units 2 and 3 TS Section 5.5.2.1.1 (c) require revisions made to the Offsite Dose Calculation Manuals (ODCMs) for this reporting period to be submitted with the ARERR. Revision 20 to Unit 1 and Revision 38 to Units 2/3 ODCMs were in effect during the 2003 ARERR reporting period. These ODCM revisions are included with this submittal.

Ifyou require additional information, please contact Mr. Clay E. Williams at (949) 368-6707.

Sincerely, Enclosures (3) cc: B. S. Mallett, NRC Regional Administrator, Region IV B. M. Pham, NRC Project Manager, San Onofre Units 2 and 3 W. C. Huffman, NRC Project Manager, San Onofre Unit 1 C. C. Osterholtz, NRC Senior Resident Inspector, San Onofre Units 2 and 3 P.O. Box 128 San Clemente, CA 92674-0128 949-368-7501 Fax 949-368-7575 jj

SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2003 January - December

F ~~ SOUIII[R\ CALIFORNIA Vt EDISON An i:insox lvXi:R\ Company PREFACE San Onofre Nuclear Generating Station is located next to San Onofre State Beach, adjoining Camp Pendleton Marine Corps Base, in San Diego County, 64 miles south of Los Angeles, California. There are two operating pressurized water reactors with a total rated capacity of 2254 net megawatts electrical.

Unit 1, rated at 410 net megawatts electrical, was supplied by Westinghouse Electric Company and began commercial operation on January 1, 1968. The unit was permanently shutdown on November 30, 1992. It is owned by Southern California Edison (80%) and San Diego Gas and Electric (20%).

Unit 2 and Unit 3 were supplied by Combustion Engineering, Inc., with turbine generators supplied by G.E.C. Turbine Generators, Ltd., of England. The units began commercial operation on August 18, 1983, and April 1, 1984, respectively and are rated at 1127 net megawatts electrical each. The twin units are owned by Southern California Edison (75.05%), San Diego Gas and Electric (20%), City of Anaheim (3.16%),

and the City of Riverside (1.79%).

P. . Box 128 San Clemnicte. CA 92674-0128 _j _

S.O.N.G.S. 1 TABLE OF CONTENTS SECTION A - INTRODUCTION . . . . . . . . . . . . ... . . . . . . . . . . . ... 1 SECTION B - GASEOUS EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . 2 SECTION C - LIQUID EFFLUENTS . . . . . . . .. . . . . . . . . . . . . . . . 8 SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM . . . . . . . 16 SECTION E - RADWASTE SHIPMENTS . . . . . . . .. . . . . . . . . . . . . . . 17 SECTION F - APPLICABLE LIMITS . . . . . . . . . . . . . . . . . . . . . . . . 20 SECTION G - ESTIMATION OF ERROR . . . . . . . . . . . . . . . . . . . . . . . 22 SECTION H - 10 CFR 50 APPENDIX I REQUIREMENTS . . . . . . . . . . . . . . . . 23 SECTION I - CHANGES TO OFFSITE DOSE CALCULATION MANU AL . . . . . . . . . . . . 27 SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS . . . . . . . . . . 28 SECTION K - MISCELLANEOUS . . . . . . . . . . . . . . . . . . . . . . . . . . . 29 SECTION L - S.O.N.G.S. 1 CONCLUSIONS . . . . . . . . . . . . . . . . . . . . . 31

-ii-

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

January - December SECTION A. INTRODUCTION This Annual Radioactive Effluent Release Report summarizes the gaseous and liquid radioactive effluent releases and radwaste shipments made from the San Onofre Nuclear Generating Station, Unit 1. This report is prepared in the general format of USNRC Regulatory Guide 1.21 and includes:

1. Quarterly Summaries of Gaseous and Liquid Effluents for "Continuous" and "Batch" Modes of Release

2. Percent of Applicable Limits

3. Estimated Total Percent Error

4. Lower Limit of Detection Concentrations

5. Batch Release Summaries

6. Previous Radioactive Effluent Release Report Addendum

7. Radwaste Shipments

8. 10 CFR 50 Appendix I Requirements

9. Changes to Offsite Dose Calculation Manual ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S.;1 SECTION B. GASEOUS EFFLUENTS Table 1A, "Gaseous Effluents-Summation of All Releases," provides a detailed listing of gaseous effluents released quarterly in four categories: fission and activation gases, iodine-131, particulates with half-lives greater than eight days, and tritium.

Listed for each of the four categories are:

(1) the total curies released (2) the average release rate (3) the percent of applicable limit (4) the estimated total' error In addition, the particulate category lists the 'gross alpha radioactivity released for each quarter.

The methodology used to calculate the percent of Applicable Limit is presented in Section F of this report. The methodology used in Table 1A to calculate the estimated total error is presented in Section G of this report.

Table 1B, "Gaseous Effluents-Elevated Release," has not been included in this report, since San Onofre Nuclear Generating Station Unit 1 does not conduct elevated releases.

Table IC, "Gaseous Effluents-Ground Level Releases," provides the systematic listing by radionuclide for the quantity of radioactivity released in three -categories:

fission gases, iodines, and particulates. The total radioactivity for each.

radionuclide is listed for each quarterly period by "co'ntinuous" mode of release.!

Plant stack releases are considered to be "continuous" releases. As of 8/4/93, "batch" mode releases are no longer conducted because of the permanent shutdown of' the reactor.

Table 1D, "Gaseous Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides-not detected in Tables-lA and IC for continuous mode releases only.

Table 1E,-- "Gaseous Effluents-Radiation Doses at the Site Boundary," provides a quarterly summary of doses at'the. site boundary for this report period.

Table iF, "Gaseous Effluents-Batch Release Summary," has been deleted. "Batch" mode releases are no longer conducted as'of'8/4/93, due-to'the permanent-shutdown of the.

reactor.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES

. , Y Estimated First Second Total Unit Quarter Quarter Error, %

A. Fission and activation gases

1. Total release Ci <LLD <LLD 3.OOE+1

2. Average release rate for period pCi/sec O.OOE+O O.OOE+O

3. Percent of applicable limit % MPC O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O B. Iodines (1)

1. Total iodine-131 Ci <LLD <LLD 1.90E+1

2. Average release rate for period YCi/sec O.OOE+O O.OOE+O

3. Percent of applicable limit % MPC O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O _

C. Particulates (1)

1. Particulates with half-lives >8 days Ci <LLD <LLD 1.60E+1

2. Average release rate for period yCi/sec O.OOE+O O.OOE+O

3. Percent of applicable limit % MPC O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O

5. Gross alpha activity Ci <LLD <LLD 5.0OE+1 D. Tritium

1. Total release Ci <LLD <LLD 2.50E+1

2. Average release rate for period uCi/sec O.OOE+O O.OOE+O

3. Percent of applicable limit % MPG O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O (1) On 3/19/03 for approximately eight hours, Plant Vent Stack particulate and iodine samples were not collected.

Prior and subsequent samples were <LLD. There were no dose consequences to a member of the public due to this event. The evaluation of this event is documented in AR 030301117.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 TABLE 1A (Continued)

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES

. -i ;' .

Estimated Third Fourth Total I Unit Quarter Quarter Error, %

A. Fission and activation gases

1. Total release - - Ci <LLD <LLD 3.OOE+1

2. Average release rate for period - Ci/sec O.OOE+O O.OOE+O

3. Percent of applicable limit.. % MPC O.OOE+O O.OOE+O

4. Percent Effluent -ConcentrationLimit % ECL O.OOE+O O.OOE+O B. Iodines

1. Total iodine-131 Ci <LLD <LLD 1.90E+1

2. Average release rate-for period qCi/sec O.OOE+O O.OOE+O

3. Percent of applicable limit % MPC O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O C. Particulates 1.- Particulates with half-lives >8 days- Ci <LLD <LLD 1.60E+1

2. Average-release rate for period' uCi/sec O.OOE+O O.OOE+O

3. Percent of applicable limit % MPC O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit: - ECL O.OOE+O O.OOE+O

5. Gross alpha activity Ci-- LLD <LLD 5.OOE+1 D. Tritium

1. Total release Ci 5.42E-1 <LLD 2.50E+1

2. Average release rate for-- period >. gCi/.sec 6.82E-2 O.OOE+O

3. Percent of applicable limit . % MPC 4.43E-4 O.OOE+O

4. Percent Effluent Concentration Limit %ECL I8.86E-4 jO.OOE+O I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 TABLE 1C GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission and activation gases krypton-85 Ci <LLD <LLD <LLD <LLD krypton-85m Ci <LLD <LLD <LD <LLD krypton-87 Ci <LLD <LLD <LLD <LLD krypton-88 Ci <LLD <LLD <LLD <LLD xenon-133 Ci <LLD <LLD <LID <LLD xenon-133m Ci <LID <LID <LLD <LLD xenon-135 Ci <LLD <LLD <LLD <LID xenon-135m Ci <LLD <LLD <LID <LLD xenon-138 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD

2. Iodines iodine-131 Ci <LLD <LLD <LLD <LLD iodine-133 Ci <LLD <LLD <LLD <LD iodine-135 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD

3. Particulates barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci <LD <LLD <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD <LLD <LLD iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci <LLD <LLD <LLD <LLD molybdenum-99 Ci <LLD <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LD <LLD <LIDLL D LLD Lower Limit of Detection; see Table iD.

NOTE: Due to the permanent shutdown of S.O.N.G.S. 1, "BATCH MODE" releases are no longer conducted.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S.' 1 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION CONTINUOUS MODE Radionuclides ---- LLD (vCi/cc)

1. Fission and activation gases krypton-85 1.50E-5 krypton-85m ,3.80E - krypton-87. -- - ,1.90E krypton-88 1.40E-7 xenon-133 8.10E-8 xenon-133m 3.10E-7 xenon-135- 4.OOE-8 xenon-135m 1.50E-6 xenon-138 2.60E-6

2. Iodines iodine-131 2.20E-13 iodine-133 2.10E-12 iodine-135 1.50E-10

3. Particulates barium-140 , 4.30E-13' cerium-141 5.50E-14 cerium-144 2.20E-13 cesium-134 1.20E-13 cesium-137 1.OOE-13 cobalt-58 1.10E-13 cobalt-60 1.80E-13 iron-59 2.80E-13 lanthanum-140 9.OOE-13 manganese-54 1.10E-13 molybdenum-99 6.50E-14 strontium-89 1.OOE-11 strontium-90 1.OOE-11 zinc-65 3.OOE-13

4. alpha 1;OOE-11

5. tritium 7.20E-8 NOTE: Due to the permanent shutdown of S.O.N.G.S. 1, "BATCH MODE" releases are no longer conducted.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 TABLE lE GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A. Noble Gas

1. Gamma Air Dose mrad O.OOE+O O.OOE+O O.OOE+O O.OOE+O

2. Percent Applicable Limit % O.OOE+O O.OOE+O O.OOE+O O.OOE+O

3. Beta Air Dose mrad O.OOE+O O.OOE+O O.OOE+O O.OOE+O

4. Percent Applicable Limit % O.OOE+O O.OOE+O O.OOE+O O.OOE+O B. Tritium, Iodine, Particulates (at the nearest receptor)

1. Organ Dose mrem O.OOE+O O.OOE+O 5.43E-5 O.OOE+O

2. Percent Applicable Limit % O.OOE+O O.OOE+O 7.24E-4 O.OOE+O NOTE: Calculations performed in accordance with the ODCM utilizing the historical X/Q.

TABLE iF GASEOUS EFFLUENTS-BATCH RELEASE

SUMMARY

NOTE: Due to the permanent shutdown of S.O.N.G.S. 1, "BATCH MODE" releases are no longer conducted.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 SECTION C. LIOUID EFFLUENTS Table 2A, "Liquid Effluents-Summation of All Releases," provides a detailed summary of liquid effluents released quarterly in three categories: fission and activation products, tritium, and dissolved and entrained gases. Listed for each of the three categories are:

(1) the total curies released

-(2) the average diluted concentration-(3) the percent of applicable limit (4) the estimated total error-In addition, Table 2A lists:

(1) the gross alpha radioactivity (2) the volume of waste released (prior to dilution)

(3) the volume of dilution water The methodology used to calculate the .percent of applicable limit is presented in Section F of this report. The methodology used to calculate the estimated total error ih Table 2A is presented in Section G of this report.

Table 2B, "Liquid Effluents," provides the. systematic listing by radionuclide for the quantity of radioactivity released in each category. The total radioactivity of each radionuclide released is listed for each quarterly period by both "continuous" and "batch" modes of release.

Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B.

Table 2D, "Liquid Effluents-Radiation Doses at the Liquid Site Boundary," presents a quarterly summary of doses at the Liquid-Site:Boundary for this report period.

Table 2E, "Liquid Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Unit 1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First Second Total Unit Quarter Quarter Error, %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 2.28E-4 1.21E-3 1.90E+1

2. Average diluted concentration during period uCi/ml 1.44E-10 6.52E-10

3. Percent of applicable limit % MPC 7.22E-4 3.89E-3

4. Percent Effluent Concentration Limit % ECL 1.44E-2 5.33E-2 B. Tritium

1. Total release Ci 5.83E-2 4.98E-2 1.90E+1

2. Average diluted concentration during period _Ci/ml 3.69E-8 2.69E-8

3. Percent of applicable limit % MPC 1.23E-3 8.97E-4

4. Percent Effluent Concentration Limit % ECL 3.69E-3 2.69E-3 C. Dissolved and entrained gases

1. Total release Ci <LLD <LLD 1.90E+1

2. Average diluted concentration during period AzCi/ml O.OOE+O O.OOE+O

3. Percent of applicable limit % MPC O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O D. Gross alpha radioactivity

1. Total release Ci <LLD 7.81E-6 5.00E+1 E. Volume of waste released (batch &

continuous, prior to dilution) liters 1.11E+7 2.65E+6 5.OOE+O F. Volume of dilution water used during period liters 1.58E+9 1.85E+9 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT:RELEASE REPORT (2003)

S.O.N.G.S.- 1 TABLE 2A (Continued)

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES I I -

Estimated Third Fourth Total-Unit Quarter Quarter Error, %

A. Fission and activation products

1. Total release-(not including tritium, gases, alpha) Ci- 2.20E-5 2.52E-5 1.90E+1

2. Average diluted concentration-during period - jqCi/ml 1.62E-11 1.42E-11

3. Percent of applicable limit %WMPC 8.09E-5 7.12E-5

4. Percent Effluent Concentration Limit % ECL 1.62E-3 1.42E-3_

B. Tritium '

1. Total release Ci 5.71E-3 3.83E-3 1.90E+1

2. Average diluted concentration during period ~uCi/ml 4.20E-9 2.16E-9

3. Percent of applicable limit -- - % MPC 1.40E-4 7.21E-5

4. Percent Effluent Concentration-Limit % ECL 4.20E-4 2.16E-4 C. Dissolved and entrained gases - -

1. Total release - -- L Ci <LLD -<LLD .1.90E+1

- -- 2. Average diluted concentration during period yCi/ml O.OOE+O O.OOE+O

3. Percent of applicable limit % MPC O.OOE+O O.OOE+O

4. Percent EffluentConcentration Limit % ECL O.OOE+O O.OOE+O D. Gross alpha radioactivity - ;

1. Total release Ci <LLD <LLD 5.00E+1 E. Volume of waste released (batch &

continuous, prior to dilution) liters 3.72E+6 1.24E+6 5.OOE+O F. Volume of dilution water used during period liters 1.36E+9 1.77E+9 5.OOE+O I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE I l First Second Third Fourth Radionuclides Released l Unit l Quarter l Quarter l Quarter Quarter

1. Fission and activation products barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci 2.28E-4 7.OOE-6 2.20E-5 2.52E-5 chromium-51 Ci <LLD <LLD <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD <LLD <LLD iodine-131 Ci <LLD <LLD <LLD <LLD iron-55 Ci <LLD <LLD <LLD <LLD iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci <LLD <LLD <LLD <LLD molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci <LLD <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD technetium-99m Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci <LLD <LLD <LLD <LLD Total for period Ci 2.28E-4 7.OOE-6 2.20E-5 2.52E-5

2. Dissolved and entrained gases xenon-133 Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD LLD Lower Limit of Detection; see Table 2C.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 TABLE 2B (Continued)

LIQUID EFFLUENTS BATCH MODE l First l Second Third l Fourth Radionuclides Released Unit l Quarter l Quarter Quarter l Quarter

1. Fission and activation products -

barium-140 Ci ;N/A <LLD N/A cerium-141 Ci N/A <LLD N/A N/A cerium-144 Ci N/A <LLD N/A N/A cesium-134 Ci N/A 2.24E-5 N/A N/A cesium-137 Ci N/A 8.40E-4 N/A N/A chromium-51 Ci ' N/A <LLD N/A N/A cobalt-58 Ci :N/A <LLD N/A N/A cobalt-60 Ci N/A 3.18E-4 N/A N/A iodine-131 Ci N/A <LLD N/A N/A iron-55 Ci N/A <LLD N/A N/A iron-59 Ci N/A <LLD N/A N/A lanthanum-140 Ci N/A <LLD N/A N/A manganese-54 Ci N/A <LLD N/A N/A molybdenum-99 Ci ;N/A <LLD N/A N/A niobium-95 Ci N/A <LLD N/A N/A strontium-89 Ci MN/A 1.46E-5 N/A N/A strontium-90 Ci N/A 3.52E-6 N/A N/A technetium-99m Ci N/A <LLD N/A N/A zinc-65 Ci ;N/A <LLD N/A N/A zirconium-95 Ci N/A <LLD N/A N/A Total for period Ci N/A 1.20E-3 N/A N/A

2. Dissolved and entrained gases xenon-133 Ci N/A l <LLD l N/A N/A xenon-135 Ci IN/A <LLD N/A N/A Total for period Ci N/A <LLD N/A N/A No releases conducted LLD Lower Limit of Detection; see Table 2C.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION CONTINUOUS MODE Radionuclides lLLD (bCi/cc)

1. Fission and activation products ba rum-140 2.70E-7 cerium-141 4.30E-8 cerium-144 1.70E-7 cesium-134 6.80E-8 chromium-51 3.30E-7 cobalt-58 6.20E-8 cobal t-60 8.90E-8 iodine-131 5.70E-8 iron-55 1.OOE-6 iron-59 1.40E-7 1anthanum-140 4.90E-7 manganese-54 6.10E-8 molybdenum-99 5.60E-8 niobium-95 6.20E-8 strontium-89 5.OOE-8 strontium-90 5.OOE-8 technetium-99m 5.70E-8 zinc-65 1.50E-7 zirconium-95 1.10E-7

2. Dissolved and entrained gases _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

xenon-133 1.90E-7 xenon-135 8.90E-8

3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 TABLE 2C (Continued)

LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE Radionuclides l LLD (pCi/cc)

1. Fission and activation products barium-140 2.30E-7 cerium-141 4.OOE-8 cerium-144 1.70E-7

- chromium-51 3.OOE-7 cobalt-58 6.OOE-8 iodine-131 - 4.30E-8 iron-55 1.OOE-6 iron-59 1.40E-7 lanthanum-140 1.60E-7 manganese-54 6.OOE-8 molybdenum-99 - 2.70E-8

-niobium-95 5.80E-8 technetium-99m 2.70E-8 zinc-65 1.50E-7 zirconium-95 1.OOE-7

2. Dissolved and entrained gases xenon-133 1.90E-7 xenon-135 8.90E-8

3. gross alpha 1.OOE-7 I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 TABLE 2D LIQUID EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOUNDARY First Second Third Fourth

_ Unit Quarter Quarter Quarter Quarter A.

1. Total body dose mrem 2.52E-3 5.74E-3 2.53E-4 2.61E-4

2. Percent Applicable Limit % 1.68E-1 3.83E-1 1.69E-2 1.74E-2 B.

1. Limiting organ dose mrem 3.84E-3 7.70E-3 3.86E-4 3.98E-4

2. Percent Applicable Limit % 7.68E-2 1.54E-1 7.71E-3 7.96E-3

3. Limiting organ for period Liver Liver Liver Liver ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE

SUMMARY

12 month period

1. Number of batch releases: 1 release

2. Total time period for batch releases: 631 minutes

3. Maximum time period for a batch release: 631 minutes,

4. Average time period for a batch release: 631 minutes

5. Minimum time period for a batch release: 631 minutes

6. . Average saltwater flow during batch releases: 6400 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 SECTION E. RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) 12 month Estimated total

1. Type of waste Unit period error (%)

a. Spent resins, filter sludges, m3 N/A evaporator bottoms Ci N/A N/A

b. Dry active waste (DAW), m3 6.39E+2 compactable and non-compactable (incl. demolition rubble)

Ci 1.06E+1 3.00E+1

c. Irradiated components, control m3 N/A rods Ci N/A N/A

d. Other: m3 N/A Ci N/A N/A NOTE: Total curie content estimated.

(*) Material packaged in Type A or strong tight containers of various sizes.

N/A No shipment made.

ANNUAL RADIOACTIVE EFFLUENT.RELEASE REPORT (2003)

S.O.N.G.S. 1

2. Estimate of major nuclide composition (by type of waste)

a. not applicable _ N/A

b. americium-241 1.13E-1 carbon-14 3.99E-1 cerium-144 1.35E-1

- cesium-134 2.39E-1 cesium-137 4.06E+O cobalt-58 - 5.60E-1 cobalt-60 2.85E+1 curium-242 5.74E-4 curium-243/244 - 5.91E-2 iron-55 %__ 3.69E+1 manganese-54 % 2.26E-1 nickel-59 % 1.64E-1 nickel-63 2.47E+1 niobium-94 1.33E-2 niobium-95 3.95E-3 plutonium-238 1.83E-1 plutonium-239/240 5.11E-2 plutonium-241 3.29E+O plutonium-242 6.20E-5 strontium-90 ; 3.26E-1 technetium-99 . 2.04E-3 tin-113 - - 3.84E-3 tritium % 6.63E-2 uranium-233/234 3.31E-8 zi rconium-95 5.75E-3

c. not applicable % N/A

d. not applicable % N/A l l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 24 MHFLogistical Solutions EnviroCare, UT Rail 11 T.A.G. Transport EnviroCare, UT Truck 6

Hittman Transport EnviroCare, UT Truck

SONGS maintains a contract with Duratek that provides volume reduction services. These shipments were made from the Duratek processing facility to Envirocare. The 6 shipments made this facility included waste from other generators. SCE's waste volume was a small fraction of the total waste volume of these shipments.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation l Destination None No shipments were made N/A C. DEWATERING Number of Containers Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S.' 1 SECTION F. APPLICABLE LIMITS Gaseous Effluents - Applicable Limits The percent of Applicable Limits, tabulated in Sections A.3, B.3, C.3, and D.3 of Table 1A, was calculated using the following equation:

% Applicable Limit = (Rel Rate) (XIO) (100)

MPCef -

where: Rel Rate = total curies released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of, Table 1A, pCi/sec.

X/Q = 1.30E-5 sec/n9; the annual average atmospheric dispersion defined in the Unit 1 ODCM.

1 o MPCett s.1 MPC where: F, = fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, C, by the sum of all the isotopic activity, CT.

n = total number of radionuclides identified MPC, = Maximum Permissible Concentration (MPC) of the ijtradionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 1.

% ECL = (Rel Rate) ;(X/0) (100)

ECLeff where: Rel Rate = total curies released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, pCi/sec.

X/Q = 1.30E-5 sec/m3 ; the annual average atmospheric dispersion defined in the Unit 1 ODCM.

1

_ n F.

o ECLff

. ECL where: F, = fractional abundance of the ith radionuclide obtained by dividing thelactivity (curies) for each radionuclide, C,, by the sum of all the isotopic activity, CT.

n = total number of radionuclides identified ECL, - Effluent Concentration Limit (ECL) of the ji" radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 Liquid Effluents - Applicable Limits The percent of Applicable Limits, tabulated in Sections A.3, B.3, and C.3 of Table 2A, were calculated using the following equations:

% Applicable Limit = (Dil Conc) (100)

MPCeff where: DiI Conc = total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A,

'iCi/ml.

1 o MPCeff = F-i-1 MPC i where: F. = fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, C,, by the sum of all the isotopic activity, CT.

n total number of radionuclides identified MPC1 = Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2.

% ECL = (Dil Conc) (100)

ECLeff where: Dil Conc = total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, pCi/ml.

1 0 ECLetf _n F.

1.1 ECL i where: F, = fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, C, by the sum of all the isotopic activity, CT.

n = total number of radionuclides identified ECL, = Effluent Concentration Limit (ECL) of the ith radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 SECTION G. ESTIMATION OF ERROR Estimations of the error in reported values of gaseous and liquid effluents releases have been made.

Sources of error for gaseous effluents - batch releases are:

(1)tank volumes (2)sampling (3)counting (4) calibration Sources of error for gaseous effluents - continuous releases are:

(1) fan flow rate (2) sampling (3) counting (4) calibration (5) differential pressure drop Sources of error for liquid effluents - batch releases are:

(1) tank volumes (2) sampling (3) counting (4) calibration Sources of error for liquid effluents -- continuous releases are:

(1) dilution flow rate (2) sampling (3) counting (4)calibration These sources of error are independent, and thus, the total error is calculated according to the following formula:

Total Error = .I2 + 2 2 2 wI wit2eac3 com'nG where: 01 Error associated with each component.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 SECTION H. 10 CFR 50 APPENDIX I REQUIREMENTS Table 1 in Section H presents the quarterly and annual maximum dose to an individual. Six different categories are presented:

(1) Liquid Effluents - Whole Body (2) Liquid Effluents - Organ (3) Airborne Effluents - Tritium, Iodines and Particulates (4) Noble Gases - Gamma (5) Noble Gases - Beta (6) Direct Radiation The doses for categories 1 and 2 were calculated using the methodology of the ODCM; this data is also presented in Table 2D. Categories 3, 4, and 5 were calculated utilizing RETDAS (Radioactive Effluent Tracking and Dose Assessment Software),

Regulatory Guide 1.109 methodology, and concurrent meteorology. Table 1E of gaseous effluents previously presented, however, lists data similar to categories 3, 4 and 5 using methods described in the ODCM and the historical meteorology (X/Q). Category 6 presents direct dose data measured by TLD dosimeters. Each portion of each category is footnoted to briefly describe each maximum individual dose presented.

For members of the public, per the ODCM, who may at times be within the site boundary', the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary.

For members of the public who traverse the site boundary via highway I-5, the residency time shall be considered negligible and hence the dose "0".

Table 2 in Section H presents the percent of Applicable Limits for each dose presented in Table 1.

ODCM Figure 6-1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 TABLE 1 Dose * (millirems)

First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS 1) 2) 3) 4) 5)

Whole Body 2.52E-3 5.74E-3 2.53E-4 2.61E-4 8.78E-3

6) 7) 8) 9) 10)

-Organ 3.84E-3 7.70E-3 3.86E-4 3.98E-4 1.23E-2 AIRBORNE EFFLUENTS 11) 12) 13) 14) 15)

Tritium, Iodines, and Particulates O.OOE+O O.OOE+O 3.60E-5 O.OOE+O 3.60E-5 NOBLE GASES ** 16) 17) 18) 19) 20)

Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O

21) 22) 23) 24) 25)

Beta O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O

26) 27) 28) 29) 30)

DIRECT RADIATION 9.41E-2 1.10E-1 7.93E-2 1.28E-1 4.12E-1

The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway(s).

- Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose.

1. This value was calculated using the methodology of the ODCM.

2. This value was calculated using the methodology of the ODCM.

3. This value was calculated using the methodology of the ODCM.

4. This value was calculated using the methodology of the ODCM.

5. This value was calculated using the methodology of the ODCM.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1

6. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.

7. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.

8. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.

9. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.

10. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.

11. There was no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem.

12. There was no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem.

13. The maximum organ dose was to a child's liver and was located in the NW sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.

14. There was no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem.

15. The maximum organ dose was to a child's liver and was located in the NW sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.

16. There was no activity detected during the release period, therefore the reported air dose for gamma radiation was O.OOE+O mrad.

17. There was no activity detected during the release period, therefore the reported air dose for gamma radiation was O.OOE+O mrad.

18. There was no activity detected during the release period, therefore the reported air dose for gamma radiation was O.OOE+O mrad.

19. There was no activity detected during the release period, therefore the reported air dose for gamma radiation was O.OOE+O mrad.

20. There was no activity detected during the release period, therefore the reported air dose for gamma radiation was O.OOE+O mrad.

21. There was no activity detected during the rel ease period, therefore the reported air dose for beta radiation was O.OOE+O mrad.

22. There was no activity detected during the rel ease period, therefore the reported air dose for beta radiation was O.OOE+O mrad.

23. There was no activity detected during the release period, therefore the reported air dose for beta radiation was O.OOE+O mrad.

24. There was no activity detected during the release period, therefore the reported air dose for beta radiation was O.OOE+O mrad.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1

25. There was no activity detected during the release period, therefore the reported air dose for beta radiation was O.OOE+0 mrad.

26. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months per year; highest dose was measured at the Site Boundary in the W sector.

27. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months per year; highest dose was measured at the Site Boundary in the W sector.

28. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months per year; highest dose was measured at the Site Boundary in the W sector.

29. Measurements were made using TLD dosimeters; values "are presented as site wide dose and are prorated to 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months per year; highest dose was measured at the Site Boundary in the W sector.

30. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months per year; highest dose was measured at the Site Boundary in the W sector.

TABLE 2

Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 1.68E-1 3.83E-1 1.69E-2 1.74E-2 2.93E-1 Organ 7.68E-2 1.54E-1 7.71E-3 7.96E-3 1.23E-1 AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates O.OOE+O O.OOE+O 4.79E-4 O.OOE+O 2.40E-4 NOBLE GASES Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O NOTE: Direct Radiation is not specifically addressed in the Applicable Limits.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 SECTION I. CHANGES TO OFFSITE DOSE CALCULATION MANUAL On February 28, 2003, Revision 20 to the Unit 1 Offsite Dose Calculation Manual (ODCM) was adopted and published. Incorporated into this revision were:

1. Updates related to the recent Land Use Census and

2. Addition of a note explaining that Soil and Kelp sample locations are not required by the Technical Specifications, and Neither change required an Effluent/ODCM Evaluation.

Minor format changes, correction of typographical errors, and removal of previously blank pages have been made and are described in the attached List of Affected Pages.

Per NRC Generic Letter 89-01, no safety reviews were required or performed for editorial changes or changes made to reflect actual plant operation.

None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations. The level of radioactive effluent control required by 10CFR20, 40CFR190, 10CFR50.36a, and Appendix I to 10CFR50 will be maintained.

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

A Addition D Deletion F Editorial/Format change R Revision The following is a complete list of the changes:

OLD NEW CHANGE REASON Table of Updated page numbers throughout document as a result of removing blank F Contents pages and adding new Ri Table.

Section 2 Update page numbers as a result of removing blankpages and adding new F Ri Table.

2-21 2-21 Updated CLF due to Land Use Census Update. R 2-24 Removed previously blank page F 2-27 Added a new page in Table 2-11 to include the Rec Bldg Staff in Sector A Q due to the Land Use Census Update.

2-31 2-31 Updated Dose Parameters in Table 2-11, Outage Workers due to the Land R Use Census Update.

5-21 5-21 Added note: "Soil Samples are not required by Technical A Specifications."

5-22 5-22 Corrected Directions for SONGS Garden from NW to NNW. F 5-23 5-23 Added note: "Kelp Samples are not required by Technical A Specifications."

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS

There were no changes to the Unit 1 Radioactive Waste Treatment Systems during the reporting period, January 1, 2003 to December 31, 2003.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 SECTION K. MISCELLANEOUS

Yard Drain Sump Overflow The Unit 1 Yard Drain sump overflowed to the PMF Catch Basin due to heavy rainfall two times in 2003. The very low resultant dose and curies were processed and reported per procedure. There were minimal dose consequences to members of the public as a result of these events. They are documented in ARs 030202021 and 030300911.

Estimated Estimated Estimated Start Stop Duration Activity Release Whole Body Organ Dose Date/Time Date/Time (min) (,4ci/ml) (Curies) Dose (mrem) (mrem) 02/25/03 @ 0428 2/25/03 @ 0545 77 4.36E-8 7.76E-5 8.51E-4 1.30E-3 03/15/03 @ 1735 03/15/30 @ 1832 57 <MDA O.OOE+O O.OOE+O O.OOE+O Late Reheater Pit Sump Dissolved and Entrained (D&E) Gas Surveillance On 7/16/03, it was determined the monthly dissolved and entrained gas sample for the Unit 1 Reheater Pit Sump (RPS) had not been obtained due to inadequate communication. A sample was collected approximately 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months late and analyzed with the results being <MDA. The RPS is an infrequently discharged sump and open to the atmosphere. Since 1994, there have been no detectable D&E gasses in this sump. There were no dose consequences to members of the public as a result of this event. This event is documented in ARs 030700854 and 030701613.

Ventilation Fan A-21 Backflow Leakage On 12/22/03 air was discovered coming out of fan A-21 inlet into the ventilation equipment room. The inlet damper to the fan was immediately closed to stop the leak. The system isolation damper was found to be only partially closed because of equipment degradation. Upon fully closing it, the leak was terminated. The air that had leaked into the fan room was the same air being exhausted up the vent stack and being monitored by monitor R-1254. The degraded damper was replaced with a back draft damper that will automatically prevent a recurrence. Any measurable activity has been accounted for and reported per procedure. There were no dose consequences to the public as a result of this event. This event is documented in AR 031201323.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2003 - December 31, 2003 S.0.N.G.S. 1 Monitor Inoperability Inoperability Explanation Period Cause FT-8/FT-10 08/12/03 - 11/04/03 Channel Initial channel calibration failed Liquid Radwaste Calibration and.required rework and retest. No Discharge Line liquid radwaste releases occurred Flow Devices during this time period. This event is documented in AR 030800657.

R-1218 12/19/02 - 05/01/03 De-energized to De-energized to support.work on a Liquid Radwaste support other work different system component that Discharge Line shares a common power supply. No Monitor liquid radwaste release occurred during this time period. This event is documented in AR 011200866.

R-1254 02/06/03 - 05/16/03 Detector spiking Investigation and testing Plant Vent Stack and tubing leakage determined the source of noise Monitor that caused the spiking to be in the detector / pre-amp connection.

An extensive overhaul was performed on the monitor, replacing degraded components. The harsh environment contributed to the degradation. An improved enclosure was constructed to protect the equipment. This event is documented in ARs 030200264 and 030200216.

R-2100 02/25/03 - 04/24/03 Low sample flow Monitor sample flow piping was Reheater Pit Sump and monitor disassembled and cleared of Monitor failure obstructions to resolve low sample flow. This event is documented in AR 030300337.

R-2101 02/11/03 - 05/02/03 Low sample flow Replaced sample piping and Yard Drain Sump degraded valve to clear Monitor obstruction. This event is documented in AR 030201015.

__ _ __ _ _ _ __ __ _ __ _ __I _ _ I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 1 SECTION L S.O.N.G.S. 1 CONCLUSIONS

Gaseous releases totaled 5.42E-1 curies of which noble gases were O.OOE+O curies, iodines were O.OOE+O curies, particulates were O.OOE+O curies, and tritium was 5.42E-1 curies.

The radiation doses from gaseous releases were: (a) gamma air dose: O.OOE+O mrad at the site boundary, (b) beta air dose: O.OOE+O mrad at the site boundary, organ dose: 3.60E-5 mrem at the nearest receptor.

Liquid releases totaled 1.19E-1 curies of which particulates and iodines were 1.48E-3 curies, tritium was 1.18E-1 curies, and noble gases were O.OOE+O curies.

The radiation doses from liquid releases were: (a) total body: 8.78E-3 mrem, (b) limiting organ: 1.23E-2 mrem.

The radioactive releases and resulting doses generated from Unit 1 were below the Applicable Limits for both gaseous and liquid effluents.

I I

I II S.O.N.G.S. 2 and 3 ' Ii

TABLE OF CONTENTS SECTION A - INTRODUCTION . . . . . . . . . . . . . 32 SECTION B - GASEOUS EFFLUENTS . . . . . . . . . . . . . . . 33 SECTION C - LIQUID EFFLUENTS . . . . . . . . . .. . . . . . . . . . . . . 43 SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM . . . . . 51 SECTION E - RADWASTE SHIPMENTS . . . . . . . . . . . . . . 52 SECTION F - APPLICABLE LIMITS . . . . . . . . . . . . . . . 55 SECTION G - ESTIMATION OF ERROR . . . . . . . . . . . . . . 57 SECTION H - 10 CFR 50 APPENDIX I REQUIREMENTS . . . . . . . . . . 58 SECTION I - CHANGES TO OFFSITE DOSE CALCULATION M} kANUAL . . . . . 62 SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS . . . . . 63 SECTION K - MISCELLANEOUS ................. . . . . . 64 SECTION L - S.O.N.G.S. 2 and 3 CONCLUSIONS . . . . .. . . . . . . . 67

-iii-

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

January - December SECTION A. INTRODUCTION This Annual Radioactive Effluent Release Report summarizes the gaseous and liquid radioactive effluent releases and radwaste shipments made from the San Onofre Nuclear Generating Station, Units 2 and 3. This report is prepared in the general format of USNRC Regulatory Guide 1.21 and includes:

1. Quarterly Summaries of Gaseous and Liquid Effluents for "Continuous" and "Batch" Modes of Release

2. Percent of Applicable Limits

3. Estimated Total Percent Error

4. Lower Limit of Detection Concentrations

5. Batch Release Summaries

6. Previous Radioactive Effluent Release Report Addendum

7. Radwaste Shipments

8. 10 CFR 50 Appendix I Requirements

9. Changes to Offsite Dose Calculation Manual ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 SECTION B. GASEOUS EFFLUENTS Table 1A, "Gaseous Effluents-Summation of All Releases," provides a detailed listing of gaseous effluents released quarterly in four categories: fission and activation gases, iodine-131, particulates with half-lives greater than eight days, and tritium.

Listed for each of the four categories are:

(1) the total curies released (2) the average release rate (3) the percent of applicable limit (4) the estimated total error In addition, the particulate category lists the gross alpha radioactivity released for each quarter.

The methodology used to calculate the percent of Applicable Limit is presented in Section F of this report. The methodology used in Table 1A to calculate the estimated total error is presented in Section G of this report.

Table lB, "Gaseous Effluents-Elevated Release," has not been included in this report since San Onofre Nuclear Generating Station Units 2 and 3 do not conduct elevated releases.

Table iC, "Gaseous Effluents-Ground Level Releases," provides the systematic listing by radionuclide for the quantity of radioactivity released in *three categories:

fission gases, iodines, and particulates. The total radioactivity for each radionuclide is listed for each quarterly period by both "continuous" and "batch" modes of release.

Waste gas decay tank releases are considered to be "batch" releases. Containment purges and plant stack releases are considered to be "continuous" releases.

Table ID, "Gaseous Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Tables 1A and IC.

Table 1E, "Gaseous Effluents-Radiation- Doses at the Site Boundary," provides a quarterly summary of-doses at the site boundary for this report period.

Table IF, "Gaseous Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Units 2 and 3. --

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES l

Estimated First Second Total Unit Quarter Quarter Error, %

A. Fission and activation gases

1. Total release Ci 4.79E+1 1.92E+1 3.OOE+1

2. Average release rate for period gCi/sec 6.16E+0 2.45E+O

3. Percent of applicable limit % MPC 1.45E-2 4.97E-3

4. Percent Effluent Concentration Limit % ECL 2.70E-2 7.03E-3 B. Iodines

1. Total iodine-131 Ci 1.69E-2 1.10E-5 1.90E+1

2. Average release rate for period pCi/sec 2.17E-3 1.40E-6

3. Percent of applicable limit % MPC 1.04E-2 6.72E-6

4. Percent Effluent Concentration Limit % ECL 5.22E-3 3.36E-6 C. Particulates

1. Particulates with half-lives >8 days Ci 5.78E-4 2.60E-5 1.60E+1

2. Average release rate for period pCi/sec 7.43E-5 3.31E-6

3. Percent of applicable limit % MPC 2.80E-5 2.20E-6

4. Percent Effluent Concentration Limit % ECL 8.86E-5 5.35E-6

5. Gross alpha activity Ci <LLD <LLD 5.OOE+1 D. Tritium

1. Total release Ci 9.35E+O 1.09E+1 2.50E+1

2. Average release rate for period uCi/sec 1.20E+O 1.39E+O

3. Percent of applicable limit % MPC 2.89E-3 3.33E-3

4. Percent Effluent Concentration Limit % ECL 5.77E-3 6.65E-3 I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE 1A (Continued)

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES l . . .

Estimated Third Fourth Total Unit Quarter Quarter Error, %

A. Fission-and activation gases - - -

1.. -Total release l Ci 2.43E+1 2.33E+1 3.OOE+1

2. Average release rate for period pCi/sec 3.06E+O 2.94E+O

3. Percent of applicable limit % MPC 4.98E-3 4.76E-3

-4. Percent-Effluent Concentration Limit' % ECL 3.28E-3 3.10E-3 B. Iodines

1. Total iodine-131 Ci 1.72E-5 1.08E-5 1.90E+1

2. Average release rate for period tzCi/sec 2.16E-6 1.36E-6

3. Percent of applicable limit - % MPC 1.04E-5 6.52E-6

4. Percent Effluent Concentration Limit % ECL 5.19E-6 3.26E-6 C. Particulates

1. Particulates with half-lives >8 days Ci 1.33E-5. 2.38E-5 1.60E+1

2. Average release rate for period pCi/sec 1.68E-6 2.99E-6

3. Percent of applicable limit % MPC 1.64E-6 2.07E-6

4. Percent Effluent Concentration Limit % ECL 6.59E-6 6.70E-6

5. Gross alpha activity Ci <LLD <LLD 5.00E+1 D. Tritium

1. Total release Ci 6.63E+O 4.62E+O 2.50E+1

2. Average release rate for period pCi/sec 8.34E-1 5.81E-1

3. Percent of applicable limit % MPC 2.OOE-3 11.39E-3

4. Percent Effluent Concentration Limit % ECL I4.OOE-3 l2.79E-3 I I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE 1C GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE I First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission and activation gases argon-41 Ci 3.47E+O 7.95E-1 6.86E-2 4.77E-2 krypton-85 Ci 1.37E-1 <LLD 1.62E+O <LLD krypton-85m Ci <LLD <LLD 6.17E-5 <LLD krypton-87 Ci <LLD <LLD <LLD <LLD krypton-88 Ci <LLD <LLD <LLD <LLD xenon-133 Ci 4.32E+1 1.62E+1 2.26E+1 2.33E+1 xenon-133m Ci 4.30E-1 <LLD 4.06E-3 <LLD xenon-135 Ci 1.18E-1 <LLD 7.36E-4 <LLD xenon-135m Ci <LLD <LLD <LLD <LLD xenon-138 Ci <LLD <LLD <LLD <LLD Total for period Ci 4.73E+1 1.70E+1 2.43E+1 2.33E+1

2. lodines iodine-131 Ci 1.69E-2 1.10E-5 1.72E-5 1.08E-5 iodine-132 Ci 1.36E-3 <LLD <LLD <LLD iodine-133 Ci 4.75E-4 2.84E-6 4.59E-5 1.55E-5 iodine-135 Ci <LLD <LLD <LLD <LLD Total for period Ci 1.87E-2 1.39E-5 6.31E-5 2.63E-5 LLD Lower Limit of Detection; see Table 1D.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE 1C (Continued)

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE I . First Second Third Fourth Radionuclides Released l Unit l Quarter Quarter Quarter Quarter 3.- Particulates barium-140 Ci <LLD <LLD <LLD <LLD bromine-82 Ci. 1.16E-4 5.93E-5 1.72E-5 1.58E-5 cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD

.cesium-134 Ci .4LD <LLD <LLD <LLD cesium-137 Ci 6.11E-5 1.54E-5 6.86E-6 1.04E-5

.cesium-138 Ci - <LLD <LLD 5.80E-7 <LLD chromium-51 Ci 6.67E-5 <LLD <LLD <LLD

-cobalt-58 Ci 3.82E-4 1.06E-5 2.87E-6 1.10E-5 cobalt-60 Ci 3.55E-5 <LLD 3.60E-6 2.40E-6 iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci 7.33E-6 <LLD <LLD <LLD molybdenum-99 Ci --<LLD <LLD <LLD <LLD niobium-95 Ci 1.72E-5 <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci 8.10E-6 <LLD <LLD <LLD LLD Lower Limit of Detection; see Table 1D.

_ _ _ _ _ _ _ _ _I _ _ _ _ _ I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE IC (Continued)

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES BATCH MODE

First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission and activation gases krypton-85 Ci 5.27E-1 2.14E+O <LLD <LLD krypton-85m Ci <LLD <LLD <LLD <LLD krypton-87 Ci <LLD <LLD <LLD <LLD krypton-88 Ci <LD <LLD <LLD <LLD xenon-131m Ci <LD <LLD <LLD <LLD xenon-133 Ci 3.79E-3 1.26E-1 <LLD <LLD xenon-133m Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD <LLD <LLD xenon-135m Ci <LLD <LLD <LLD <LLD xenon-138 Ci <LLD <LLD <LLD <LLD Total for period Ci 5.31E-1 2.26E+O <LLD <LLD LLD Lower Limit of Detection; see Table iD.

Iodines and particulates are not analyzed prior to release via batch mode.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION CONTINUOUS MODE Radionuclides LLD (pCi/cc)

1. Fission and activation gases krypton-85 1.50E-5 krypton-85m 3.80E-8 krypton -87 1.90E-7 krypton-88 1.40E-7 xenon-133m 3.10E-7 xenon-135 4.OOE-8 xenon-135m 1.50E-6 xenon-138 2.60E-6

2. lodines iodine-132 8.40E-10 iodine-135 1.OOE-10

3. Particulates barium-140 2.90E-13 cerium-141 3.60E-14 cerium-144 1.40E-13 cesium-134 8.20E-14 cesium-138 1.70E-10 chromium-51 3.20E-13 cobalt-60 1.20E-13 iron-59 1.90E-13 lanthanum-140 6.OOE-13 manganese-54 7.40E-14 molybdenum-99 4.40E-14 niobium-95 7.40E-14 strontium-89 1.OOE-11 strontium-90 1.OOE-11 zinc-65 2.OOE-13 zirconium-95 1.30E-13

4. alpha 1.OOE-11 I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE iD (Continued)

GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE Radionuclides l LLD (pCi/cc)

1. Fission and activation gases krypton-85 8.60E-4 krypton-85m 2.OOE-6 krypton-87 8.70E-6 krypton-88 7.10E-6 xenon-131m 7.30E-5 xenon-133 4.40E-6 xenon-133m 1.80E-5 xenon-135 2.20E-6 xenon-135m 2.70E-5 xenon-138 4.30E-5 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE lE GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY J First l Second l Third l Fourth Unit Quarter Quarter Quarter Quarter A. Noble Gas

1. Gamma Air Dose mrad 7.32E-3 2.05E-3 1.24E-3 1.32E-3

2. Percent Applicable Limit 7.32E-2 2.05E-2 1.24E-2 1.32E-2

3. Beta Air Dose mrad 9.07E-3 3.75E-3 3.91E-3 3.74E-3

4. Percent Applicable Limit 4.53E-2 1.88E-2 1.96E-2 1.87E-2 B. Tritium, Iodine, Particulates (at the nearest receptor)

1. Organ Dose mrem 1.46E-2 1.30E-3 5.59E-4 5.43E-4

2. Percent Applicable Limit % I 9.75E-2 8.70E-3 3.73E-3 3.62E-3 NOTE: Calculations performed in accordance with the ODCM utilizing the historical X/Q.

II L ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE 1F GASEOUS EFFLUENTS-BATCH RELEASE

SUMMARY

12 month period

1. Number of batch releases: 7 releases

2. Total time period for batch releases: 2116 minutes

3. Maximum time period for a batch release: 480 minutes

4. Average time period for a batch release: 302 minutes

5. Minimum time period for a batch release: 10 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S.-2 and 3 SECTION C. LIOUID EFFLUENTS Table 2A, "Liquid Effluents-Summation of All Releases," provides a detailed summary of liquid effluents released quarterly in three categories: fission and activation products, tritium, and dissolved and entrained gases. Listed for each of the three categories are:

(1) the total curies released (2) the average diluted concentration (3) the percent of applicable limit (4) the estimated total error In addition, Table 2A lists:

(1) the gross alpha radioactivity (2) the volume of waste released (prior to dilution)

(3) the volume of dilution water The methodology used to calculate the percent of applicable limit is presented in Section F of this report. The methodology used to calculate the estimated total error in Table 2A is presented in Section G of this-report.

Table 2B, "Liquid Effluents," provides the systematic listing by radionuclide for the quantity of radioactivity released in each category. The total radioactivity of each radionuclide released is listed for each quarterly period by both "continuous" and "batch" modes of release.

Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B.

Table 2D, "Liquid Effluents-Radiation Doses at the Liquid Site Boundary," presents a quarterly summary of doses at the Liquid Site Boundary for this report period.

Table 2E, "Liquid Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Units 2 and 3. - -

II I

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First Second Total Unit Quarter Quarter Error, %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 4.68E-3 1.45E-3 1.90E+1

2. Average diluted concentration during period yCi/ml 7.44E-12 1.92E-12

3. Percent of applicable limit % MPC 1.49E-5 4.59E-6

4. Percent Effluent Concentration Limit % ECL 1.39E-4 4.63E-5 B. Tritium

1. Total release Ci 2.OOE+2 2.17E+1 1.90E+1

2. Average diluted concentration during period pCi/ml 3.18E-7 2.86E-8

3. Percent of applicable limit % MPC 1.06E-2 9.54E-4

4. Percent Effluent Concentration Limit % ECL 3.18E-2 2.86E-3 C. Dissolved and entrained gases

1. Total release Ci 1.89E-1 <LLD 1.90E+1

2. Average diluted concentration during period pCi/ml 3.02E-10 0.00+0

3. Percent of applicable limit % MPC 1.51E-4 0.00+0

4. Percent Effluent Concentration Limit % ECL 1.51E-4 0.00+0 D. Gross alpha radioactivity

1. Total release Ci <LLD <LLD 5.OOE+1 E. Volume of waste released (batch &

continuous, prior to dilution) liters 9.68E+7 6.94E+7 5.OOE+O F. Volume of dilution water used during period liters 6.28E+11 7.58E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE 2A (Continued)

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Estimated Third Fourth Total Unit Quarter Quarter Error, %

A. Fission and activation products

1. Jotal release (not including

- tritium, gases, alpha) ; - -Ci 1.11E-2 2.78E-3 1.90E+1

- 2. Average diluted concentration during period -uCi/ml 1.45E-11 3.62E-12

3. Percent of applicable limit -%. MPC 3.55E-5 5.72E-6

4. Percent Effluent Concentration Limit % ECL 3.37E-4 5.81E-5 B. Tritium -

1. Total release Ci 3.99E+2 4.05E+1 1.90E+1

2. Average'diluted concentration during period yCi/ml 5.21E-7 5.28E-8

3. Percent of applicable limit % MPC 1.74E-2 1.76E-3

4. Percent Effluent Concentration Limit % ECL 5.21E-2 5.28E-3 C. Dissolved and entrained gases - ;: -_-_-

1: Total release - Ci 1.05E-2 9.72E-5 1.90E+1

2. Average diluted concentration during period yCi/ml 1.37E-11 1.27E-13

3. Percent of applicable limit - % MPGC 6.85E-6 6.34E-8

4. Percent Effluent Concentration Limit % ECL. 6.85E-6 6.34E-8 D. Gross alpha radioactivity

1. Total release Ci <LLD <LLD 5.OOE+1 E. Volume of waste released (batch &

continuous, prior to dilution) liters 6.83E+7 6.92E+7 5.OOE+O F. Volume of dilution water used during period liters 7.66E+11 7.67E+11 5.OOE+O

_ _ _ __ _ _ _I

_ _ _ _ _ _ _ I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE I First Second Third Fourth Radionuclides Released l Unit Quarter Quarter Quarter Quarter

1. Fission and activation products barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci 5.18E-5 3.12E-6 1.96E-5 <LLD chromium-51 Ci <LLD <LLD <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD <LLD <LLD iodine-131 Ci <LLD <LLD <LLD <LLD iron-55 Ci <LLD <LLD <LLD <LLD iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci <LLD <LLD <LLD <LLD molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci <LLD <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD technetium-99m Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci <LLD <LLD <LLD <LLD Total for period Ci 5.18E-5 3.12E-6 1.96-5 <LLD

2. Dissolved and entrained gases xenon-133 Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD LLD Lower Limit of Detection; see Table 2C.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE 2B (Continued)

LIQUID EFFLUENTS BATCH MODE l First Second Third Fourth Radionuclides Released I Unit I Quarter I Quarter I Quarter I Quarter

1. Fission and activation products antimony-124 Ci <LLD 1.25E-5 <LLD l <LLD antimony-125 Ci 1.38E-3 6.32E-4 2.03E-3 1.68E-4 barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD -- LLD cesium-134 Ci 9.49E-5 9.60E-5 3.78E-4 <LLD cesium-137 Ci 5.75E-4 1.86E-4 1.02E-3 9.18E-5 chromium-51 Ci 1.62E-3 <LLD <LLD <LLD cobalt-57 Ci <LLD <LLD 1.44E-5 <LLD cobalt-58 - Ci 6.10E-4 2.26E-4 8.97E-4 9.30E-5 cobalt-60 Ci 1.13E-4 3.98E-5 2.73E-3 9.39E-4 iodine-131 Ci 6.70E-6 <LLD 1.01E-5 <LLD iodine-133 Ci <LLD <LLD 6.98E-6 - <LLD iron-55 Ci <LLD 2.20E-4 3.36E-3 1.34E-3 iron-59 Ci 6.68E-5 <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci 8.03E-6 <LLD 1.91E-4 3.45E-5 molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci 9.18E-5 <LLD 1.64E-4 2.80E-6 niobium-97 Ci 8.12E-6 <LLD 6.06E-6 8.17E-6 silver-110m Ci 1.24E-5 3.07E-5 2.20E-4 9.17E-5 strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD strontium-92 Ci <LLD <LLD <LLD 9.07E-6 technetium-99m Ci <LLD <LLD <LLD <LLD tin-113 Ci <LLD <LLD <LLD 1.63E-6 tin-117m Ci 2.09E-6 7.87E-6 <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci 3.44E-5 <LLD 4.46E-5 <LLD Total for period Ci 4.63E-3 1.45E-3 1.11E-2 2.78E-3

2. Dissolved and entrained gases krypton-85 Ci 1.84E-1 <LLD 1.O1E-2 <LLD xenon-131m Ci 2.54E-3 <LLD <LLD <LLD xenon-133 Ci 2.87E-3 <LLD 4.47E-4 9.72E-5 xenon-135 Ci 3.OOE-6 <LLD 4.25E-6 <LLD Total for period Ci 1.89E-1 <LLD 1.05E-2 9.72E-5 LLD Lower Limit of Detection; see Table 2C.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION CONTINUOUS MODE Radionuclides l LLD (uCi/cc)

1. Fission and activation products barium-140 2.70E-7 cerium-141 4.30E-8 cerium-144 1.70E-7 cesium-134 6.80E-8 cesium-137 5.90E-8 chromium-51 3.30E-7 cobalt-58 6.20E-8 cobalt-60 8.90E-8 iodine-131 5.70E-8 iron-55 1.OOE-6 iron-59 1.40E-7 lanthanum-140 4.90E-7 manganese-54 6.10E-8 molybdenum-99 5.60E-8 niobium-95 6.20E-8 strontium-89 5.OOE-8 strontium-90 5.OOE-8 technetium-99m 5.70E-8 zinc-65 1.50E-7 zirconium-95 1.10E-7

2. Dissolved and entrained gases xenon-133 1.90E-7 xenon-135 8.90E-8

3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE 2C (Continued)

LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE Radionuclides LLD (pCi/cc)

1. Fission and activation products antimony-124 2.10E-7 barium-140 2.30E-7

.cerium-141 4.OOE-8 cerium-144 1.70E-7 cesium-134 6.80E-8 chromium-51 3.OOE-7 cobalt-57 2.20E-8 iodine-131 4.30E-8 iodine-133 1.10E-7 iron-55 1.OOE-6 iron-59 1.40E-7 lanthanum-140 1.60E-7 manganese-54 6.OOE-8 molybdenum-99 2.70E-8 niobium-95 5.80E-8 niobium-97 1.40E-7 strontium-89 5.OOE-8 strontium-90 5.OOE-8 strontium-92 5.40E-5 technetium-99m 2.70E-8 tin-113 5.30E-8 tin-117m 2.30E-8 zinc-65 1.50E-7 zirconium-95 1.OOE-7

2. Dissolved and entrained gases krypton-85 2.90E-5 xenon-131m 3.OOE-6 xenon-133 1.90E-7 xenon-135 8.90E-8

3. gross alpha 1.OOE-7 I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE 2D LIQUID EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOUNDARY First Second Third Fourth IUnit Quarter Quarter Quarter Quarter A.

1. Total body dose mrem 4.09E-4 6.67E-5 9.85E-4 1.61E-4

2. Percent Applicable Limit % 1.36E-2 2.22E-3 3.28E-2 5.35E-3 B.

1. Limiting organ dose mrem 7.34E-4 2.04E-4 2.43E-3 7.20E-4

2. Percent Applicable Limit % 7.34E-3 2.04E-3 2.43E-2 7.20E-3

3. Limiting organ for period GI-LLI GI-LLI GI-LLI GI-LLI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE

SUMMARY

12 month period

1. Number of batch releases: 177 releases

2. Total time period for batch releases: 25565 minutes

3. Maximum time period for a batch release: 485 minutes

4. Average time period-for a batch release: 144 minutes

5. Minimum time period for a batch release: 25 minutes

6. Average saltwater flow during batch releases: 738000 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 SECTION E. RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) 12 month Estimated total

1. Type of waste Unit period error (%)

a. Spent resins, filter sludges, m3 N/A evaporator bottoms Ci N/A N/A

b. Dry active waste (DAW), m3 1.33E+2 compactable and non-compactable* Ci 3.08E-1 3.00E+1

c. Irradiated components, control m3 N/A rods Ci N/A N/A

d. Other m3 N/A Ci N/A N/A Note: Total curie content estimated.

(*) Material packaged in Type A or strong tight containers of various sizes.

N/A No shipment made.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3

2. Estimate of major nuclide composition (by type of waste)

a. not applicable % N/A

b. americium-241 - 3.23E-3 antimony-124 -_-_--___-_3.45E-1 antimony-125 - 1.04E+O carbon-14 11.94E+O cerium-144 % 4.49E-2 cesium-134 - 7.70E-1 cesium-137 5.76E+O chromium-51 1.07E+1 cobalt-57 % 1.14E-1 cobalt-58 3.60E+l cobalt-60 1.09E+1 curium-242 1.12E-3 curium-243/244 2.90E-3 iron-55 1.42E+1 iron-59 9.96E-1 manganese-54 2.32E+O nickel-63 1.01E+1 niobium-95 2.70E+O plutonium-238 1.89E-3 plutonium-239/240 1.87E-3 plutonium-241 % 1.41E-1 strontium-90 % 1.77E-2 technetium-99 % 4.59E-3 tritium % 2.75E-1 uranium-233T234 - - - ___%_-_2.80E-4 zirconium-95 1.60E+O

c. not applicable - ___%_--_-N/A

d. not applicable % N/A I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

3. Solid Waste Disposition l Number of Shipments Mode of Transportation Destination 2 TAG Transport EnviroCare, UT Truck/Flatbed Trailer EnviroCare, UT 6

Hitman Trucking Company EnviroCare, UT

____ ____ ____ Truck/FlatbedTrailer

SONGS maintains a contract with Duratek that provides volume reduction services. These shipments were made from the Duratek processing facility to EnviroCare. The 6 shipments made from this facility included waste from other generators. SCE's waste volume was a small fraction of the total waste volume of these shipments.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None No shipments were made N/A C. DEWATERING Number of Containers Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 SECTION F. APPLICABLE LIMITS Gaseous Effluents - Applicable Limits The percent of Applicable Limits, tabulated in Sections A, B, C, and D of Table 1A, were calculated using the following equation:

% Applicable Limit = (Rel Rate) (X/0) (100)

MPCeff where: Rel Rate = total curies released in each category and each quarter, divided by the seconds in a quarter; the value inSections A.2, B.2, C.2 and D.2 of Table 1A, pCi/sec.

X/Q = 4.80E-6 sec/n?; the annual average atmospheric dispersion defined in the Units 2&3 ODCM.

1 o MPCeff n Fi

. MPC i where: F, = fractional abundance of the i" radionuclide obtained by dividing the'activity (curies) for each radionuclide, C,,

by the sum of all the isotopic activity, CT.

n = total number of radionuclides identified MPC, = Maximum: Permissible Concentration (MPC) of the "th radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 1.

% ECL = (Rel-Rate) (X/O) (100)

ELLeff where: Rel Rate = total' curies released in each category and each quarter, divided by'the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, pCi/sec.

X/Q = 4.80E-6 sec/mn; the annual average atmospheric dispersion defined in the Units 2&3 ODCM.

1 -

° ECLeff _ n F' 1 ECL 1 where: F, = fractional' abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, C,,

by the sum of all the isotopic activity, CT.

n = total number of radionuclides identified ECL, -= Effluent Concentration Limit (ECL) of the ith radionuclide I from"10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column'l.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 Liouid Effluents - ADolicable Limits The percent of Applicable Limits, tabulated in Sections A, B, and C of Table 2A, were calculated using the following equations:

% Applicable Limit = (Dil Conc) (100)

MPCerf where: Dil Conc = total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, uCi/ml.

1

- ~ n' F.

Fi o MPCetf i1l MPC i where: F, = fractional abundance of the i" radionuclide obtained by dividing the activity (curies) for each radionuclide, C,,

by the sum of all the isotopic activity, CT.

n = total number of radionuclides identified MPC, = Maximum Permissible Concentration (MPC) of the i" radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2.

% ECL = (Dil Conc) (100)

ECLeff where: Dil Conc = total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, pCi/ml.

1

° ECLeff = n F.

1=1 ECL ,

where: F. = fractional abundance of the i" radionuclide obtained by dividing the activity (curies) for each radionuclide, Ca, by the sum of all the isotopic activity, CT.

n = total number of radionuclides identified ECL, = Effluent Concentration Limit (ECL) of the ith radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 SECTION G. ESTIMATION OF ERROR Estimations of the error in reported values of gaseous and liquid effluents releases have been made.

Sources of error for gaseous effluents - batch releases are:

(1) tank volumes (2) sampling (3) counting (4) calibration Sources of error for gaseous effluents - continuous releases are:

(1) fan flow rate (2) sampling (3) counting (4) calibration (5) differential pressure drop Sources of error for liquid effluents - batch releases are:

(1) tank volumes (2) sampling (3) counting (4) calibration Sources of error for liquid effluents - continuous releases are:

(1) dilution flow rate (2) sampling (3) counting (4) calibration These sources of error are independent, and thus, the total error is calculated according to the following formula:

Total Error = + F2 + 02 + . 2

.2 where: 01 - Error associated with each component.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 SECTION H 10 CFR 50 APPENDIX T REQUIREMENTS Table 1 in Section H presents the quarterly and annual maximum dose to an individual.

Six different categories are presented:

(1) Liquid Effluents - Whole Body (2) Liquid Effluents - Organ (3) Airborne Effluents - Tritium, Iodines and Particulates (4) Noble Gases - Gamma (5) Noble Gases - Beta (6) Direct Radiation The doses for categories 1 and 2 were calculated using the methodology of the ODCM; these data are also presented in Table 2D. Categories 3, 4, and 5 were calculated utilizing RETDAS (Radioactive Effluent Tracking and Dose Assessment Software),

Regulatory Guide 1.109 methodology, and concurrent meteorology. Table 1E of gaseous effluents previously presented, however, lists data similar to categories 3, 4 and 5 using methods described in the ODCM and the historical meteorology (X/Q). Category 6 presents direct dose data measured by TLD dosimeters. Each portion of each category is footnoted to briefly describe each maximum individual dose presented.

For members of the public, per the ODCM, who may at times be within the site boundary', the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary.

For members of the public who traverse the site boundary via highway I-5, the residency time shall be considered negligible and hence the dose "0'.

Table 2 in Section H presents the percent of Applicable Limits for each dose presented in Table 1.

' ODCM Figures 1-2 & 2-2.

ANNUAL RADIOACTIVE EFFLUENT:RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 TABLE 1 Dose * (millirems)

First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS 1) 2) 3) 4) 5)

Whole Body 4.09E-4 6.67E-5 9.85E-4 1.61E-4 1.62E-3

6) 7) 8) 9) 10)

Organ 7.34E-4 2.04E-4 2.43E-3 7.20E-4 4.09E-3 AIRBORNE EFFLUENTS 11) 12) 13) 14) 15)

Tritium, Iodines, and Particulates 5.33E-2 4.15E-4 3.35E-4 5.46E-4 5.35E-2 NOBLE GASES ** 16) 17) 18) 19) 20)

Gamma 3.18E-2 4.20E-3 2.69E-3 6.68E-3 4.49E-2

21) 22) 23) 24) 25)

Beta 5.22E-2 9.14E-3 8.OOE-3 1.90E-2 8.83E-2

26) 27) 28) 29) 30)-

DIRECT RADIATION 9.41E-2 1.10E-1 -7.93E-2 1.28E-1 4.12E-1

The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway(s).

- Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose.

1. This value was calculated using the methodology of the ODCM.

2. This value was calculated using the methodology of the ODCM.

3. This value was calculated using the methodology of the ODCM.

4. This value was calculated using the methodology of the ODCM.

5. This value was calculated using the methodology of the ODCM.

_ _-i-I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3

6. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.

7. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.

8. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.

9. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.

10. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.

11. The maximum organ dose was to an infant's thyroid and was located in the NNE sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.

12. The maximum organ dose was to a teen's thyroid and was located in the NNE sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.

13. The maximum organ dose was to a teen's thyroid and was located in the SE sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.

14. The maximum organ dose was to an adult's thyroid and was located in the NE sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.

15. The maximum organ dose was to an infant's thyroid and was located in the NNE sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.

16. The maximum air dose for gamma radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

17. The maximum air dose for gamma radiation was located in the SSE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

18. The maximum air dose for gamma radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

19. The maximum air dose for gamma radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

20. The maximum air dose for gamma radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

21. The maximum air dose for beta radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

22. The maximum air dose for beta radiation was located in the NNW sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

23. The maximum air dose for beta radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

24. The maximum air dose for beta radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3

25. The maximum air dose for beta radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

26. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months per year; highest dose was measured at the Site Boundary in the W sector.

27. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months per year; highest dose was measured at the Site Boundary in the W sector.

28. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months per year; highest dose was measured at the Site Boundary in the W sector.

29. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months 'per year; highest dose 'was measured at the Site Boundary' in the W sector.

30. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months per year; highest dose was measured at the Site Boundary in the W sector.

TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 1.36E-2 2.22E-3 3.28E-2 5.35E-3 2.70E-2 Organ 7.34E-3 2.04E-3 2.43E-2 7.20E-3 2.04E-2 AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 3.56E-1 2.76E-3 2.23E-3 3.64E-3 1.78E-1 NOBLE GASES Gamma 3.18E-1 4.20E-2 2.69E-2 6.68E-2 2.24E-1 Beta 2.61E-1 4.57E-2 4.OE-2 9.50E-2 2.21E-1 NOTE: Direct Radiation is not specifically addressed in the Applicable Limits.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 28, 2003, Revision 38 to the Units 2/3 Offsite Dose Calculation Manual (ODCM) was adopted and published. This change incorporated the following:

1. Updates related to the recent Land Use Census

2. Addition of a note explaining that Soil and Kelp sample locations are not required by the Technical Specifications, and

3. Corrected a typographical error from a previous revision.

Neither change required an Effluent/ODCM Evaluation.

Minor format changes, correction of typographical errors, and removal of previously blank pages have been made and are described in the attached List of Affected Pages. Per NRC Generic Letter 89-01, no safety reviews were required or performed for editorial changes or changes made to reflect actual plant operation.

None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations. The level of radioactive effluent control required by 10CFR20, 40CFR190, 10CFR50.36a, and Appendix I to 10CFR50 will be maintained.

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

A Addition D Deletion F Editorial/Format change R Revision The following is a complete list of the changes:

OLD NEW CHANGE REASON Table of Updated page numbers throughout document as a result of removing blank F Contents pages and adding new Ri Table.

Section 2 Updated page numbers as a result of removing blank pages and adding new Ri F Table.

2-31 2-31 Updated CLF due to Land Use Census Update R 2-39 Added a new page in Table 2-8 to include the Rec Bldg staff in Sector Q A due to the Land Use Census Update 2-41 2-42 Updated Dose Parameters in Table 2-9, Outage Workers due to the Land Use R Census Update 5-18 5-18 Added note: "Soil Samples are not required by Technical Specifications" A 5-19 5-19 Corrected Direction for SONGS Garden from NW to NNW. F 5-20 5-20 Added note: "Kelp Samples are not required by Technical Specifications". A 6-9 Corrected a typographical error in the unplanned releases reporting F requirements.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS There were no changes to the Units 2&3 Radioactive Waste Treatment Systems during the reporting period, January 1, 2003 to December 31, 2003.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 SECTION K. MISCELLANEOUS Late Surveillance on Turbine Plant Sump (TPS) Samole Compositor. 2(3)APC5887 On 7/31/03 the daily surveillance on TPS sample compositor, 2(3)APC5887, was performed satisfactorily, but approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months late due to inadequate supervisory direction. This surveillance involved ensuring proper operability of the compositor. There were no dose consequences to a member of the public.

This event is documented in AR030701613.

Unit 3 Condenser Air Ejector (CAE) Missed Particulate and Iodine (P&I) Sample From 5/27/03 at 2000 to 5/28/03 at 0955 continuous P&I samples were not obtained via an auxiliary sampling device on the Unit 3 CAE. A failed component on the condenser caused excessively high process flow rates and water in the sample lines. This made any sample non-isokinetic and non representative.

Additionally, while attempting to clear the lines and obtain a sample, the filter was not reinstalled, causing the subsequent sample to be missed. Review of previous and subsequent sample results were <MDA. A separate noble gas monitor on this flow path was in service during this time period and also showed no activity. There were no dose consequences to the public as a result of this event. This event is documented in ARs 030600245 and 030501361.

Excessive Leakage Discovered on Wide Range Gas Monitor (WRGM) 3RT-7870 On 2/3/03, skid leakage was found on 3RT-7870, the condenser air ejector monitor. Tests showed approximately 43% inleakage for the entire sample skid, including downstream of the sample collection filters. Conservative calculations indicated that samples obtained during the period of inleakage could not have resulted in failure to meet the ODCM required LLDs for both P&I and noble gas isotopes. Additionally, a separate noble gas monitor, 3RT-7818, was in service monitoring the condenser air ejector. A periodic pressure test is now performed on all WRGMs to verify integrity. Air ejector samples taken since the repairs have been <MDA. There were no dose consequences to the public as a result of this event. This event is documented in AR 030200264.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2003 - December 31, 2003 S.0.M.G.S. 2 Monitor Inoperability Inoperability Explanation Period Cause 2RT-7870 04/17/00 - present Inoperable process Design deficiency causes process Condenser Air flow 'measuring flow instrument to be inoperable Ejector Process device whenever while the vacuum pump is running.

Flow Monitor vacuum pump is Substitute flow value is running. automatically inserted whenever the vacuum pump is running as high flow values are not sensed. Flow monitor works properly during normal operations. This event is documented in ARs 000101252 and

000400960.

2RT-7865 02/12/03 - 04/22/03 Heat trace erratic Heat trace exhibited erratic Plant Vent Stack operability behavior. For very short time (Containment periods temperature would be below Purge) limit before returning to normal Particulate and band. The cause for the erratic Iodine Sampler behavior could not be identified and has not recurred. This event is documented in AR 030201007.

2RT-7821 10/5/03 - 01/09/04 Low sample flow System required piping replacement Turbine Plant to resolve pipe blockage. During Sump Monitor this time period Unit 2 TPS was routed to Unit 3 TPS. This event is documented in AR 031101279.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2003 - December 31, 2003 S.O.N.G.S. 3 Monitor Inoperability Inoperability Explanation Period Cause 3RT-7870 04/17/00 - present Inoperable process Design deficiency causes process Condenser Air flow measuring flow instrument to be inoperable Ejector Process device whenever while the vacuum pump is running.

Flow Monitor vacuum pump is Substitute flow value is running. automatically inserted whenever the vacuum pump is running as high flow values are not sensed. Flow monitor works properly during normal operations. This event is documented in ARs 000101252 and 000400960.

3RT-7817 06/04/02 - 03/25/03 Failure due to low Monitor has had low sample flow BPS/FFCPD sample flow. problems since installation. The Discharge Monitor piping was replaced in 2000 with marginal improvement. The long lengths of pipe and low motive force were the cause of this problem. Corrective actions installed include a simplified piping design. This event is documented in ARs 010600960 and 020701020.

02/01/03 - 03/24/03 Inoperable flow Monitor inoperable due to totalizer erroneous signal from flow totalizer. Investigation revealed plugged sensor lines on the flow transmitter which were cleared.

This event is documented in AR 030200042.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

S.O.N.G.S. 2 and 3 SECTION L. S.O.N.G.S. 2 and 3 CONCLUSIONS

Gaseous releases totaled 1.46E+2 curies of which noble gases were 1.15E+2 curies, iodines were 1.88E-2 curies, particulates were 6.41E-4 curies, and tritium was 3.15E+1 curies.

The radiation doses from gaseous releases were: (a) gamma air dose: 4.49E-2 mrad at the site boundary, (b) beta air dose: 8.83E-2 mrad at the site boundary, (c) organ dose: 5.35E-2 mrem at the nearest receptor.

Liquid releases totaled 6.61E+2 curies of which particulates and iodines were 2.OOE-2 curies, tritium was 6.61E+2 curies, and noble gases were 2.OOE-1 curies.

The radiation doses from liquid releases were: (a) total body: 1.62E-3 mrem, (b) limiting organ: 4.09E-3 mrem.

The radioactive releases and resulting doses generated from Units 2 and 3 were below the Applicable Limits for both gaseous and liquid effluents.

COMMON ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

COMMON COMMON RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

Estimated

1. Type of waste Unit 12 month period total error (%)

a. Spent resins, filter m3 N/A

-sludges, evaporator bottoms Ci N/A N/A

b. Dry active waste (DAW), m3 5.68E+1 compactable and non-compactable

Ci 6.38E-2 3.OOE+1

__ _ _ N/A

c. Irradiated components -

Ci N/A N/A 3

N

d. Other (filters) Ci N/A ; N/A Note: Total curie content estimated.

(*) Material packaged in strong tight containers of various sizes.

N/A No shipment made.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

COMMON

2. Estimate of major nuclide composition (by type of waste)

a. not applicable % N/A

b. americium-241 % 7.61E-2 antimony-125 _ % 2.16E-1 carbon-14 L_3.70E-1 cerium-144 % 6.81E-2 cesium-134 % 1.51E+O cesium-137 % 4.76E+O cobalt-57 % 3.92E-2 cobalt-58 % 2.79E+O cobalt-60 _ _ _% 6.35E+l curium-242 3.39E-3 curium-243/244 % 3.OOE-2 iron-55 % 1.66E+1 manganese-54 5.83E-1 neptunium-237 % 1.35E-1 nickel-63 % 6.OlE+O niobium-95 % 2.18E-1 plutonium-238 % 9.27E-2 plutonium-239/240 % 3.19E-2 plutonium-241 __% 1.46E+O plutonium-242 __8.94E-6 ruthenium-103 __3.52E-2 silver-llOm % 8.30E-2 strontium-90 __4.72E-1 technetium-99 %_2.57E-2 tin-113 % 6.91E-2 tritium % 4.48E-2 uranium-233/234 %_ _1.97E-4 uranium-235 % 6.37E-1 uranium-238 % 6.09E-5 zinc-65 2.30E-4 zirconium-95 1.57E-1

c. not applicable % N/A

d. not applicable % N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

COMMON A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

3. Solid Waste Disposition (S.O.N.G.S. 1, 2, and 3)

Number of Shipments Mode of Transportation Destination 3 T.A.G. Transport EnviroCare, UT I Truck/Trailer B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None No shipments were made N/A C. DEWATERING Number of Containers Solidification Agent l None N/A D. CHANGES TO THE PROCESS CONTROL PROGRAM AT SAN ONOFRE UNITS 1, 2 & 3 None.

REFERENCES:

1. Unit 1 Technical Specifications, section D6.13.2.

2. Units 2 and 3 License Controlled Specifications, section 5.0.103.2.2.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

COMMON COMMON 40 CFR 190 REQUIREMENTS Table 1 below presents the annual site-wide doses and percent of ODCM Specification limits to members of the public. These values were calculated utilizing doses resulting from all effluent pathways and direct radiation. The different categories presented are: (1) Total Body, (2) Limiting Organ, and (3) Thyroid.

Dose Category Units Year

1. Total Body

a. Total Body Dose mrem 4.36E-1

b. Percent ODCM Specification Limit 1.74E+O

2. Limiting Organ

a. Organ Dose (Liver) mrem 4.99E-2

b. Percent ODCM Specification Limit 2.OOE-1

3. Thyroid

a. Thyroid Dose mrem 3.56E-2

b. Percent ODCM Specification Limit 4.75E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

COMMON COMMON CONCLUSIONS

Gaseous releases from S.O.N.G.S. 1, 2 and 3 totaled 1.47E+2 curies of which noble gases were 1.15E+2 curies, iodines were 1.88E-2 curies, particulates were 6.41E-4 curies, and tritium was 3.20E+1 curies.

Liquid releases from S.O.N.G.S. 1, 2 and 3 totaled 6.61E+2 curies of which particulates and iodines were 2.15E-2 curies, tritium was 6.61E+2 curies, and noble gases were 2.OOE-1 curies.

Radioactive releases and resulting doses generated from S.O.N.G.S. 1, 2 and 3 were below the Applicable Limits for both gaseous and liquid effluents.

S.O.N.G.S. 1, 2 and 3 made 52 radwaste shipments to Envirocare, UT. Total volume was 8.29E+2 cubic meters containing 1.10E+1 curies of radioactivity.

Meteorological conditions during the year were typical for S.O.N.G.S.

Meteorological dispersion was good 34% of the time, fair 39% of the time and poor 27% of the time.

The net result from the analysis of these effluent releases indicates that the operation of S.O.N.G.S. 1, 2 and 3 has met all the requirements of the applicable regulations and therefore has not resulted in any detrimental effects to a member of the public.

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

COMMON APPENDIX A GASEOUS EFFLUENTS - APPLICABLE LIMITS A. Table 1A lists the total curies released and the release rate. The percent of applicable limit compares the released concentrations to the concentration limits of 10 CFR 20, Appendix B, Table II, Column 1.

B. Table 1E lists the air doses as calculated using the historical X/Q. The air dose due to noble gases released in gaseous effluents from S.O.N.G.S. (per reactor) to areas at and beyond the site boundary shall be limited to the following values:

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

< 10 mrad for beta radiation.

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

< 20 mrad for beta radiation.

C. The dose to a Member of the Public from iodines, tritium, and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from S.O.N.G.S. (per reactor) to areas at and beyond the site boundary shall be limited to the following values:

1. During any calendar quarter: < 7.5 mrem to any organ.

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

COMMON APPENDIX A (Continued)

LIQUID EFFLUENTS - APPLICABLE LIMITS A. Table 2A lists the total curies released, the diluted concentration, and percent of the applicable limit. The percent of applicable limit compares the diluted concentration of radioactive material released to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained gases. For dissolved or entrained noble gases, the concentration is limited to 2.OOE-4 pCi/ml.

B. Table 2D lists doses due to liquid releases. The dose commitment to a Member of the Public from radioactive materials in liquid effluents released from S.O.N.G.S. (per reactor) to unrestricted areas shall be limited to the following values:

1. During any calendar quarter: s 1.5 mrem to the total body and

5 mrem to any organ.

2. During any calendar year:

3 mrem to the total body and

10 mrem to any organ.

METEOROLOGY METEOROLOGY The meteorology of the San Onofre Nuclear Generating Station for each of the four quarters, 2003 is described in this section. Meteorological measurements have been made according to the guidance provided in USNRC Regulatory Guide 1.23, "Onsite Meteorological Programs." A summary report of the meteorological measurements taken during each calendar quarter are presented in Table 4A as joint frequency distribution (JFD) of wind direction and wind speed by atmospheric stability class.

Hourly meteorological data for batch releases have been recorded for the periods of actual release. These data are available, as well as the hourly data for the Annual Report, but have not been included in this report because of the bulk of data records.

Table 4A lists the joint frequency distribution for each quarter, 2003. Each page of Table 4A represents the data for the individual stability classes: A, B, C, D, E, F, and G. The last page of each section is the JFD for all the stability classes.

The wind speeds have been measured at the 10-meter level, and the stability classes are defined by the temperature differential between the 10-meter and 40-meter levels.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 03010100-03033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ s -1.9 'C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 2 0 0 0 0 2 NNE 0 0 0 0 0 0 0 1 0 0 0 0 1 NE 0 0 0 2 0 1 1 3 0 0 0 0 7 ENE 0 0 0 0 0 0 0 1 0 0 0 0 1 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 1 1 0 0 0 0 0 2 SE 0 0 0 0 0 0 5 1 0 0 0 0 6 SSE 0 0 0 0 1 1 14 7 0 0 0 0 23 S 0 0 0 1 2 13 12 0 0 0 0 0 28 SSW 0 0 0 3 8 23 1 0 0 0 0 0 35 SW 0 0 0 0 18 28 7 0 0 0 0 0 53 WSW 0 0 1 1 15 46 23 0 0 0 0 0 86 W 0 0 0 0 10 57 50 3 0 0 0 0 120 WNW 0 0 0 0 2 12 29 17 7 0 0 0 67 NW 0 0 0 0 0 0 1 0 1 0 0 0 2 NNW 0 0 0 0 0 0 1 0 0 0 0 0 1 TOTALS 0 0 1 7 56 182 145 35 8 0 0 0 434 NUMBER OF VALID HOURS 434 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 434 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ s -1.7 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 1 0 0 0 0 0 1 NE 0 0 0 1 0 0 0 0 0 0 0 0 1 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 1 0 0 0 0 0 1 SE 0 0 0 0 1 1 5 0 0 0 0 0 7 SSE 0 0 0 0 0 1 3 2 0 0 0 0 6 S 0 0 0 2 2 0 0 1 0 0 0 0 5 SSW 0 0 0 1 0 1 0 0 0 0 0 0 2 SW 0 0 0 0 0 2 0 1 0 0 0 0 3 WSW 0 0 0 1 0 1 0 0 0 0 0 0 2 W 0 0 0 1 3 1 0 1 0 0 0 0 6 WNW 0 0 0 0 0 3 0 0 0 0 0 0 3 NW 0 0 0 0 0 0 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 0 6 6 10 10 5 0 0 0 0 37 NUMBER OF VALID HOURS 37 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 37 I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 03010100-03033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ s -1.5 °C/100 METERS)

WIND .22- .51- .76- 1. 1- 1.6- 2.1- 3.1- 5.1- 7. 1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 -

N 0 - 0 - 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 1 0 0 0 0 0 1 NE 0 0 0 0 0 0 1 1 0 0 0 0 2 ENE 0 0 0 0 0 0 1 2 0 0 0 0 3 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 1 0 0 0 0 0 0 1 SE 0 0 0 0 0 1 2 1 0 0 0 0 4 SSE 0 0 0 1 0 6 4 4 1 0 0 0 16 S 0 0 0 0 3 4 4 2 1 0 0 0 14 SSW 0 0 0 2 0 3 1 0 0 0 0 0 6 SW 0 0 0 2 2 0 0 0 0 0 0 0 4 WSW 0 0 0 1 3 0 1 0 0 0 0 0 5 W 0 0 0 0 2 0 0 0 0 0 0 0 2 WNW 0 0 0 0 1 2 1 1 0 0 0 0 5 NW 0 0 0 0 1 0 1 0 0 0 0 0 2 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 0 6 12 17 17 11 2 0 0 0 65 NUMBER OF VALID HOURS 65 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 65 PASQUILL B NEUTRAL (-1.5 < DT/DZ s -0.5 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 1 3 5 3 3 0 0 0 0 0 15 NNE 0 0 0 3 1 6 5 2 3 0 0 0 20 NE 0 0 0 0 1 1 1 1 0 0 1 0 5 ENE 0 0 0 2 1 1 2 0 4 2 1 0 13 E 0 0 0 1 1 5 5 1 0 0 0 0 13 ESE 0 1 1 0 4 9 12 4 0 2 0 0 33 SE 0 0 0 2 4 16 39 11 6 1 0 0 79 SSE 0 0 0 4 5 10 10 4 5 5 2 0 45 S 0 0 1 4 2 9 5 4 3 1 0 0 29 SSW 0 0 0 5 2 2 1 1 0 0 0 0 11 SW 0 0 1 4 6 0 3 4 0 0 0 0 18 WSW 0 0 0 2 6 1 5 5 3 0 0 0 22 W 0 0 0 4 4 4 7 12 3 0 0 0 34 WNW 0 0 0 4 3 12 6 1 6 0 0 0 32 NW 0 1 1 4 5 13 10 3 1 0 0 0 38 NNW 0 0 0 2 4 5 4 0 0 0 0 0 15 TOTALS 0 2 5 44 54 97 118 53 34 11 4 0 422 NUMBER OF VALID HOURS 422 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 422 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE .

PERIOD OF RECORD 03010100-03033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ s 1.5 OC/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 2 5 11 6 4 2 0 0 0 0 30 NNE 0 0 1 11 11 4 10 4 1 0 0 0 42 NE 0 0 3 2 5 2 3 4 0 0 0 0 19 ENE 0 0 2 7 2 5 4 9 2 0 0 0 31 E 0 0 0 4 4 6 1 2 1 0 0 0 18 ESE 0 0 0 2 4 5 3 1 0 0 0 0 15 SE 0 0 0 0 4 4 4 0 0 0 0 0 12 SSE 0 1 0 2 4 4 2 0 0 0 0 0 13 S 0 0 0 3 0 1 0 0 0 0 0 0 4 SSW 0 0 2 3 2 4 0 0 0 0 0 0 11 SW 0 0 0 4 2 0 2 0 0 0 0 0 8 WSW 0 0 0 1 5 0 0 0 0 0 0 0 6 W 0 0 3 8 8 7 2 1 0 0 0 0 29 WNW 0 0 1 4 1 4 8 0 0 0 0 0 18 NW 0 0 1 4 1 7 6 1 0 0 0 0 20 NNW 0 0 1 4 6 6 3 0 0 0 0 0 20 TOTALS 0 1 16 64 70 65 52 24 4 0 0 0 296 NUMBER OF VALID HOURS 296 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 296 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ s 4.0 *C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 5 14 16 13 0 0 0 0 0 48 NNE 0 0 1 23 52 45 7 1 0 0 0 0 129 NE 0 0 4 7 8 13 1 1 0 0 0 0 34 ENE 0 0 2 7 8 5 0 0 0 0 0 0 22 E 0 1 0 1 4 0 1 0 0 0 0 0 7 ESE 0 0 1 2 3 4 3 0 0 0 0 0 13 SE 0 0 2 3 5 2. 2 1- 0 0 0 0 15 SSE 0 0 1 1 3 1 1 0 0 0 0 0 7 S 0 0 1 2 4 1 3 0 0 0 0 0 11 SSW 0 1 1 0 1 0 1 0 0 0 0 0 4 SW 0 0 2 3 4 0 0 0 0 0 0 0 9 WSW 0 0 2 2 2 1, 0 0 0 0 0 0 7 W 0 0 1 2 4 1 I 0 0 0 0 0 9 WNW 0 0 2 4 7 2 5 0 0 0 0 0 20 NW 0 1 1 2 3 3 .2 .0 0.0 0 0 12 NNW 0 0 4 3 10 4 2. 0 0 0 0 0 23 TOTALS 0 3 25 67 132 98 42 3 0 0 0 0 370 NUMBER OF VALID HOURS 370 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 370 I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 03010100-03033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 °C/100 METERS)

..... nn ,. 4. r .

WIND .22- .51- .715- 1.1- 1.6- 2.1- 3.1-5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.I0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N - - 2 3 2 15 27 0 0 0 0 0 49 NNE 0 0 1 3 19 148 1~

L44 4 0 0 0 0 319 NE 0 0 1 8 9 11 6 1 0 0 0 0 36 ENE 0 0 1 10 8 4 2 0 0 0 0 0 25 E 0 0 0 4 2 2 3 0 0 0 0 0 11 ESE 0 0 3 2 1 0 0 0 0 0 0 0 3 SE 0 0 1 1 2 1 0 0 0 0 0 0 5 SSE 0 0 0 2 3 3 2 0 0 0 0 0 10 S 0 0 3 1 0 1 1 0 0 0 0 0 3 SSW 0 0 3 2 1 0 1 0 0 0 0 0 4 SW 0 0 0 2 3 2 3 0 0 0 0 0 10 WSW 0 0 0 6 1 2 1 0 0 0 0 0 10 W 0 0 0 2 3 3 1 0 0 0 0 O 9 WNW 0 0 1 1 3 6 3 0 0 0 0 0 14 NW 0 2 0 4 0 3 3 0 0 0 0 0 12 NNW 0 1 1 3 3 4 4 0 0 0 0 0 16 TOTALS 0 3 8 54 60 205 201 5 0 0 0 0 536 NUMBER OF VALID HOURS 536 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 536 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 5 16 32 40 47 4 0 0 0 0 144 NNE 0 0 3 40 83 203 168 12 4 0 0 0 513 NE 0 0 8 20 23 28 13 11 0 0 1 0 104 ENE 0 0 5 26 19 15 9 12 6 2 1 0 95 E 0 1 0 10 11 13 10 3 1 0 0 0 49' ESE 0 1 2 6 12 20 20 5 0 2 0 0 68 SE 0 0 3 6 16 25 57 14 6 1 0 0 128 SSE 0 1 1 10 16 26 36 17 6 5 2 0 120 S 0 0 2 13 13 29 25 7 4 1 0 0 94 SSW 0 1 3 16 14 33 5 1 0 0 0 0 73 SW 0 0 3 15 35 32 15 5 0 0 0 0 105 WSW 0 0 3 14 32 51 30 5 3 0 0 0 138 W 0 0 4 17 34 73 61 17 3 0 0 0 209 WNW 0 0 4 13 17 41 52 19 13 0 0 0 159 NW 0 4 3 14 10 26 23 4 2 0 0 0 86-NNW 0 1 6 12 23 19 14 0 0 0 0 0 75 TOTALS 0 9 55 248 390 674 585 136 48 11 4 0 2160 NUMBER OF VALID HOURS 2160 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2160 ANNUAL RADIOACTIVE EFFLUENT;RELEASE REPORT (2003)

METEOROLOGY April - June TABLE:4A SITE: SAN'ONOFRE PERIOD OF RECORD 03040100-03063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ s -1.9 0C/100 METERS) 4 _ e A _ _ _ . .

.7b-e A s 4 _

WIND .22- .bl- 1.1- 1.b- Z.1- .5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 -

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 - 0 0 0 0 O 0 0 0 0 0 NNE 0 0 0 1 1 0 0 0 0 0 0 0 2 NE 0 0 0 0 0 1 0 O 0 0 0 0 1 ENE 0 0 0 0 0 0 0 O 0 0 0 0 0 E 0 0 0 0 0 0 0 O 0 0 0 0 0 ESE 0 0 0 0 1 0* 0 0 0 0 0 1 SE 0 0 0 1 0 2 2 O 0 0 0 0 5 SSE 0 0 0 1 1 6 25 4 1 0 0 0 38 S 0 0 0 0 4 15 47 13 0 0 0 0 79 SSW 0 0 0 1 4 19 29 3 0 0 0 0 56 SW 0 0 0 1 17 61 53- 0 0 0 0 0 132 WSW 0 0 0 2 18 82 81 2 0 0 0 0 185 W 0 0 0 2 5 50 78 10 0 0 0 0 145 WNW 0 0 0 0 1 5.: 32 8 0 0 0 0 46 NW 0 0 0 0 0 0 1 1 0 0 0 0 2 NNW 0 -

0 0 1 0 0 0 O 0 0 0 0 1 TOTALS 0 0 - 10 52 241 348 41 1 0 0 - 693 NUMBER OF VALID HOURS 693 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 693 PASQUILL B MODERATELY UNSTABLE (-1.9 <-DT/DZ s -1.7 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1-. 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0.0 0 0 0 O O NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0. 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 1 0 0 0 0 0 0 1 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 2 1 0 0 0 0 0 3 SSE 0 0 0 0 1 2. 6 2 0 0 0 0 11 S 0 0 0 0 2 4 7 4 0 0 0 0 17 SSW 0 0 0 3 1. 2 4 1 0 0 0 0 11 SW 0 0 0. 1. 6 6 5 0 0 0 0 0 18 WSW 0 0 O 3 2 3 1 1 0 0 0 0 10 W 0 0 0 0 3 3 0 2 0 0 0 0 8 WNW 0 0 0 0 1. 5 5 0 0 0 0 0 11 NW 0 0 0 0 0 0 1 0 0 0 0 0 1 NNW 0 O O O O - 0 0 0 0 O0 0 0 TOTALS 0 0 0 7 16 28 30 10 0 0 0 0 91 NUMBER OF VALID HOURS 91 NUMBER OF CALMS 'O NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 91 I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 03040100-03063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ s -1.5 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 1 0 0 0 0 0 1 SE 0 0 0 0 0 4 1 1 1 0 0 0 7 SSE 0 0 0 0 1 6 8 2 1 2 0 0 20 S 0 0 0 2 1 7 12 1 2 0 0 0 25 SSW 0 0 0 2 2 8 9 3 0 0 0 0 24 SW 0 0 1 1 3 5 2 0 0 0 0 0 12 WSW 0 0 0 1 1 6 1 0 0 0 0 0 9 W 0 0 0 2 4 6 1 0 0 0 0 0 13 WNW 0 0 0 0 0 6 8 1 0 0 0 0 15 NW 0 0 0 3 0 2 0 1 0 0 0 0 6 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 1 11 12 50 43 9 4 2 0 0 132 NUMBER OF VALID HOURS 132 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 132 PASQUILL D NEUTRAL (-1.5 < DT/DZ < -0.5 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 1 2 5 9 4 0 0 0 0 0 0 21 NNE 0 1 2 11 12 10 2 0 0 0 0 0 38 NE 0 0 0 4 3 1 0 0 0 0 0 0 8 ENE 0 1 2 3 5 1 0 0 0 0 0 0 12 E 0 0 1 4 9 5 3 0 0 0 0 0 22 ESE 0 0 1 6 10 17 12 1 0 0 0 0 47 SE 0 0 4 10 16 43 43 14 2 0 0 0 132 SSE 0 0 2 7 16 45 43 8 1 0 0 0 122 S 0 0 3 10 15 36 25 4 0 0 0 0 93 SSW 0 1 4 8 16 23 13 2 0 0 0 0 67 SW 0 0 4 10 8 12 10 1 0 0 0 0 45 WSW 0 1 5 11 5 14 2 6 0 0 0 0 44 W 0 0 4 15 7 6 14 8 2 0 0 0 56 WNW 0 0 1 5 7 10 13 7 1 0 0 0 44 NW' 0 0 3 6 8 13 8 0 0 0 0 0 38 NNW 0 0 3 9 9 12 6 1 0 0 0 0 40 TOTALS 0 5 41 124 155 252 194 52 6 0 0 0 829 NUMBER OF VALID HOURS 829 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 829 ANNUAL RADIOACTIVE EFFLUENT'RELEASE REPORT (2003)

METEOROLOGY April - June TABLE 4A' SITE: SAN ONOFRE PERIOD OF RECORD 03040100-03063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ s 1.5 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 '5.0 7.0 .10.0 13.0 18.0 N 0 1 1 8 8 6 1 0 0 0 0 0 25 NNE 0 0 0 6 11 14 1 0 0 0 0 0 32 NE 0 1 0 4 2 2 0 0 0 0 0 0 9 ENE 0 0 0 2 1 8 0 0 0 0 0 0 11 E 0 0 0 3 4 3 0 0 0 0 0 0 10 ESE 0 0 0 2 1 2 1 0 0 0 0 0 6 SE 0 0 0 0 1 2 2 1 0 0 0 0 6 SSE 0 0 0 1 4 3 0 0 0 0 0 0 8 S 0 0 0 2 0 3 0 0 0 0 0 0 5 SSW 0 0 0 0 1 1 1 0 0 0 0 0 3 SW 0 0 0 2 0 0 0 0 0 0 0 0 2 WSW 0 0 0 0 1 1 0 0 0 0 0 0 2 W 0 0 0 2 2 1 0 0 0 0 0 0 5 WNW 0 0 0 2 1 3 0 0 0 0 0 0 6 NW 0 0 1 2 2 2 1 0 0 0 0 0 8 NNW 0 0 0 5 5 3 3 0 0 0 0 0 16 TOTALS 0 2 2 41 44 54 10 1 0 0 0 0 154 NUMBER OF VALID HOURS 154 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 154 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ s 4.0 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 3 2 5. 1 0 0 0 0 0 11 NNE 0 0 2 8 22 31 6 0 0 0 0 0 69 NE 0 0 1 3 6 1 0 0 0 0 0 0 11 ENE 0 0 0 1 1 0 0 0 0 0 0 0 2 E 0 0 0 0 0 1 0 0 0 0 0 0 1 ESE 0 0 0 0 0 1 0 0 0 0 0 0 1 SE 0 0 0 2 0 1 0 0 0 0 0 0 3 SSE 0 0 1 1 0 1 0 0 0 0 0 0 3 S 0 0 0 0 0 1 0 0 0 0 0 0 1 SSW 0 0 1 1 1 1 1 0 0 0 0 0 5 SW 0 0 0 0 1 0 0 0 0 0 0 0 1 WSW 0 0 1 0 0 2 0 0 0 0 0 0 3 W 0 0 0 4 0- 1 0 0 0 0 0 0 5 WNW 0 0 0 1 2 1 1 0 0 0 0 0 5 NW 0 0 0 0 1 0 0 0 0 0 0 0 1 NNW 0 0 0 1 5 0 1 0 0 0 0 0 7 TOTALS 0 0 6 25 41 47 10 0 .0 0 0 0 129 NUMBER OF VALID HOURS 129 NUMBER OF CALMS I0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 129

I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 03040100-03063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4 .0 °C/100 METERS)

WIND .22- .51- .7 6- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 1 0 4 5 1 0 0 0 0 11 NNE 0 0 0 1 10 71 0 0 0 0 0 111 NE 0 0 1 1 2 1 1 0 0 0 0 0 6 ENE 0 0 1 0 1 1 0 0 0 0 0 3 0

E 0 0 0 0 1 0 0 0 0 0 0 1 0

ESE 0 0 0 1 1 0 0 0 0 0 0 2 0

SE 0 0 0 0 0 3 0 0 0 0 0 3 0

SSE 0 0 0 3 0 1 1 0 0 0 0 5 0

S 0 0 0 0 0 0 0 0 0 0 0 0 1 0 SSW 0 0 0 1 1 0 0 0 0 0 0 2 0

SW 0 0 0 0 1 0 0 0 0 0 0 1 0

WSW 0 0 0 0 0 0 0 0 0 0 0 0 0

W 0 0 0 0 0 2 1 0 0 0 0 3 0

WNW 0 0 0 0 0 0 0 0 0 0 0 0 0

NW 0 1 0 0 0 2 1 0 0 0 0 4 0

NNW 0 0 0 2 0 1 1 0 0 0 0 -

4 TOTALS 0 2 10 17 86 ~1~ 0 0 0 -5 NUMBER OF VALID HOURS 156 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 156 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 2 3 17 19 19 7 1 0 0 0 0 68 NNE 0 1 4 27 56 126 38 0 0 0 0 0 252 NE 0 1 2 12 13 6 1 0 0 0 0 0 35 ENE 0 1 3 6 8 10 0 0 0 0 0 0 28 E 0 0 1 7 14 10 3 0 0 0 0 0 35 ESE 0 0 1 9 13 20 14 1 0 0 0 0 58 SE 0 0 4 13 17 57 49 16 3 0 0 0 159 SSE 0 0 3 13 23 64 83 16 3 2 0 0 207 S 0 0 3 14 22 66 91 22 2 0 0 0 220 SSW 0 1 5 16 26 54 57 9 0 0 0 0 168 SW 0 0 5 15 36 84 70 1 0 0 0 0 211 WSW 0 1 6 17 27 108 85 9 0 0 0 0 253 W0 0 4 25 21 69 94 20 2 0 0 0 235 WNW 0 0 1 8 12 30 59 16 1 0 0 0 127 NW 0 1 4 11 11 19 12 2 0 0 0 0 60 NNW 0 0 3 18 19 16 11 1 0 0 0 0 68 TOTALS 0 8 52 228 337 758 674 114 11 2 0 0 2184 NUMBER OF VALID HOURS 2184 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2184 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 03070100-03093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ s -1.9 °C/100 METERS)

WIND .22- .51-. .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 .5.0 7.0 10.0 13.0 18.0 N 0 0 0 1 0 1 0 0 0 0 0 0 2 NNE 0 0 0 1 0 0 0. 0 0 0 0 0 1 NE 0 0 0 1 0 0 0 0 0 0 0 0 1 ENE 0 0 0 0 0 0 0 0 0 0. 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 2 0 0 0 0 0 0 0 0 2 SE 0 0 0 0 1 0 0 0 0 0 0 0 1 SSE 0 0 0 0 2 6 5 0 0 0 0 0 13 S 0 0 0 0 4 9 37 14 0 0 0 0 64 SSW 0 0 0 5 7 13 20 0 0 0 0 0 45 SW 0 0 0 3 16 33 18 0 0 0 0 0 70 WSW 0 0 1 3 33 89 24 0 0 0 0 0 150 W 0 0 0 2 14 97 75 0 0 0 0 0 188 WNW 0 1 0 3 0 35 86 1 0 0 0 0 126 NW 0 0 0 2 2 2 0 2 0 0 0 0 8 NNW 0. 0 0 2 1 0 0 0 0 0 0 0 3 TOTALS 0 1 1 25 80 285 265 17 0 0 0 0 674 NUMBER OF VALID HOURS 674 NUMBER OF CALMS'. 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 674 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ s -1.7 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 1 0. 0 0 0 0 0 0 1 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 1 1 0 0. 0 0 0 0 0 0 2 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 1 0 0 0 0 0 0 0 1 SSE 0 0 0 0 1 2. 1 0 0 0 0 0 4 S 0 0 0 0 0 1, 7 0 0 0 0 0 8 SSW 0 0 0 1 1 7 4 0 0 0 0 0 13 SW 0 0 0. 3 6 3'. 3 0 0 0 0 0 15 WSW 0 0 0 1 1 1 0 0 0 0 0 0 3 W 0 0 0 0 0 - O 0 0 0 0 0 0 0 WNW 0 0 0 3 2 0 2 0 0 0 0 0 7 NW 0 0 0 0 1 2 0 0 0 0 0 0 3 NNW 0 0 0 0 0' 0 0 0 0 0 0 0 .0 TOTALS 0 0 1 9 14 16 17 0 0 0 0 0 57 NUMBER OF VALID HOURS 57 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 57 I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 03070100-03093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY ;UNSTABLE (-1.7 < DT/DZ s -1.5 °C/100 METERS)

WIND 1.1-

.22- .51- .76- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 -

N 0 0 0 0 0 1 - 0 0 0 0 3 NNE 0 0 1 1 0 0 0 0 0 0 0 2 0

NE 0 0 0 3 0 0 0 0 0 0 3 0 0 ENE 0 0 2 0 0 0 0 0 0 0 2 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 1 0 0 0 0 0 0 0 0 1 0

SE 0 0 0 0 1 1 0 0 0 0 0 2 0

SSE 0 1 1 4 7 3 0 0 0 0 0 16 0

S 0 0 0 2 3 7 7 0 2 0 0 0 21 0

SSW 0 2 1 3 9 4 0 0 0 0 0 19 0

SW 0 1 2 0 6 2 0 0 0 0 0 11 0

WSW 0 1 2 3 7 0 0 0 0 0 0 13 0

W 0 1 0 2 1 0 0 0 0 0 0 4 0

WNW 0 0 0 4 1 1 0 0 0 0 0 6 0

NW 0 0 0 0 0 0 0 0 0 0 0 0 0

NNW 0 1 0 2 0 0 0 0 0 0 0 3 TOTALS 0 0 8 13 25 39 19 0 2 0 0 0 106 NUMBER OF VALID HOURS 106 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 106 PASQUILL D NEUTRAL (-1.5 < DT/DZ s -0.5 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 2 4 1 0 0 1 0 0 0 0 8 NNE 0 0 0 3 10 2 0 0 0 0 0 0 15 NE 0 0 1 4 0 1 0 0 0 0 0 0 6 ENE 0 0 1 1 0 0 1 0 0 0 0 0 3 E 0 0 1 1 2 6 1 0 0 0 0 0 11 ESE 0 0 1 1 3 10 5 0 0 0 0 0 20 SE 0 0 1 2 6 15 17 3 1 0 0 0 45 SSE 0 0 2 5 8 18 23 9 1 0 0 0 66 S 0 0 2 9 13 22 23 3 0 0 0 0 72 SSW 0 1 0 7 9 9 13 1 0 0 0 0 40 SW. 0 0 1 9 12 14 2 0 0 0 0 0 38 WSW 0 0 1 9 12 5 0 0 0 0 0 0 27 W 0 0 0 8 7 11 1 0 0 0 0 0 27 WNW 0 0 2 5 14 20 10 0 0 0 0 0 51 NW 0 0 2 4 8 12 12 0 0 0 0 0 38 NNW 0 0 1 3 3 0 1 0 0 0 0 0 8 TOTALS 0 1 18 75 108 145 109 17 2 0 0 0 475 NUMBER OF VALID HOURS 475 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 475 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 03070100-03093023 WIND SPEED (M/S);AT'10METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZI :s1.5 -C/100 METERS)

WIND .22- .51- .76- -1.1- 1.6- 2.1--- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 1 2 14 21 5 1 0 0 0 0 0 44 NNE 0 0 2 21 19 4 1 0 0 0 0 0 47 NE 0 0 3 11 3 3 1 0 0 0 0 0 21 ENE 0 1 1 7 2 1 0 0 0 0 0 0 12 E 0 0 0 5 2 1 0 0 0 0 0 0 8 ESE 0 2 2 9 1 3 0 0 0 0 0 0 17 SE 0 0 2 5 15 22 13 0 0 0 0 0 57 SSE 0 1 5 11 18 17 11 2 0 0 0 0 65 S 0 1 0 15 9 11 3 0 0 0 0 0 39 SSW 0 3 1 12 10 4 0 0 0 0 0 0 30 SW 0 0 3 17 4 2 0 0 0 0 0 0 26 WSW 0 3 6 14 8 4 0 0 0 0 0 0 35 W 0 1 4 15 8 6 0 0 0 0 0 0 34 WNW 0 3 3 18 12 6 1 0 0 0 0 0 '43 NW 0 1 1 9 14 19 5 0 0 0 0 0 49 NNW 0 1 5 12 14 3 1 0 0 0 0 0 36 TOTALS 0 18 40 195 160 111 37 2 0 0 0 0 563 NUMBER OF VALID HOURS' 563 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 563 PASQUILL F MODERATELY STABLE (1.5r' DT/DZ s 4.0 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 1 3 3 2 0 0 0 0 0 0 9 NNE 0 0 3 21 33 24 0 0 0 0 0 0 81 NE 0 1 3 6 6 1 0 -0 0 0 0 0 17 ENE 0 0 0 4 5 2 0 0 0 0 0 0 11 E 0 0 1 3 1 1 1 0 0 0 0 0 7 ESE 0 0 2 2 1 0 0 0 0 0 0 0 5 SE 0 0 2 3 1 5 1 0 0 0 0 0 12 SSE 0 0 0 1 2 3 3 0 0 0 0 0 9 S 0 0 2 5 0 0' 1 0 0 0 0 0 8 SSW 0 0 1 1 1 0 0 0 0 0 0 0 3 SW 0 1 2 1 1 3 1 0 0 0 0 0 9 WSW 0 0 1' 0 0 0 O O O 0 0 0 0 1 W 0 1 1 4 4 0 0 0 0 0 0 0 10 WNW 0 0 0 3 1 1 0 0 0 0 0 0 5 NW 0 0 1 4 3 0 0 0 0 0 0 0 8 NNW 0 0 0 3 3 1 0 1 0 0 0 0 8 TOTALS 0 3 20 64 65 43 7 1 0 0 0 0 203 NUMBER OF VALID HOURS 203 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 203 I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 03070100-03093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4 .0 °C/100 METERS) c, 1.6- 5.1- 7.1- 10.1-WIND

.ZZ- .51- .76- 1.1- 2.1- 3..I- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5..0 7.0 10.0 13.0 18.0 N 0 - 0 2 4 4 - 0 0 0 0 11 NNE 0 0 0 7 19 52 2 0 0 0 0 0 80 NE 0 0 1 2 2 2 0 0 0 0 0 0 7 ENE 0 0 0 1 2 1 0 0 0 0 0 0 4 E 0 0 O 0 2 1 0 0 0 0 0 0 3 ESE 0 0 O 0 2 1 0 0 0 0 0 0 3 SE 0 0 0 2 1 2 0 0 0 0 0 0 5

°1 SSE 0 0 0 0 2 1 0 0 0 0 0 0 3 S 0 0 0 0 0 0 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 0 0 0 0 0 0 SW 0 0 0 2 1 0 0 0 0 0 0 0 3 WSW 0 0 0 1 0 0 0 0 0 0 0 0 1 W 0 0 0 1 1 0 0 0 0 0 0 0 2 WNW 0 0 0 1 0 3 1 0 0 0 0 0 5 NW 0 0 1 0 0 0 0 0 0 0 0 0 1 NNW 0 0 0 0 1 1 0 0 0 0 0 0 2 TOTALS 0 0 2 19 37 68 4 0 0 0 0 0 130 NUMBER OF VALID HOURS 130 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 130 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 1 5 26 29 12 3 1 0 0 0 0 77 NNE 0 0 5 54 83 82 3 0 0 0 0 0 227 NE 0 1 8 24 14 7 1 0 0 0 0 0 55 ENE 0 1 2 15 9 4 1 0 0 0 0 0 32 E 0 0 3 10 7 9 2 0 0 0 0 0 31 ESE 0 2 6 14 7 14 5 0 0 0 0 0 48 SE 0 0 5 12 25 45 32 3 1 0 0 0 123 SSE 0 1 8 18 37 54 46 11 1 0 0 0 176 S 0 1 4 31 29 50 78 17 2 0 0 0 212 SSW 0 4 4 27 31 42 41 1 0 0 0 0 150 SW 0 1 7 37 40 61 26 0 0 0 0 0 172 WSW 0 3 10 30 57 106 24 0 0 0 0 0 230 W 0 2 6 30 36 115 76 0 0 0 0 0 265 WNW 0 4 5 33 33 66 101 1 0 0 0 0 243 NW 0 1 5 19 28 35 17 2 0 0 0 0 107 NNW 0 1 7 20 24 5 2 1 0 0 0 0 60 TOTALS 0 23 90 400 489 707 458 37 4 0 0 0 2208 NUMBER OF VALID HOURS 2208 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

METEOROLOGY October --December TABLE" 4A SITE: SAN ONOFRE PERIOD OF RECORD 03100100-03123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ s -.1.9°C/100 METERS)

--- . A=s7t WIND .22- .51- .7b- 1.1- 1.b- -2.1- 3..1- 5.1- 7.1- 1u. 1-

13.1- >15 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5..0 7.0 10.0 13.0 . 18.0 N 0 0 1 0 0 0 1 1 0 I 0 0 0 3 NNE 0 0 0 0 0 0 2 0 0 0 0 0 2 NE 0 0 0 0 0' 1 0 0 0 0 0 1 0

ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 1 0 0 0 0 0 0 0 1 0 0 ESE 0 0 0 0* 0 0 0 0 0 0 0 0

SE 0 0 1 1 0 1 2 0 0 0 0 5 0

SSE 0 0 0 2 7 4 4.' 0 0 0 0 17 0

S 0 0 1 5 13 I18 2 0 0 0 0 39 00 SSW 0 0 3 9 16 '. 20 1 0 0 0 0 49 0

SW 0 0 4 12 28 9' 0' 0 0 0 0 53 0

WSW 0 0 4 22 31 ]12 3 0 0 0 0 72 0

W 0 1 2 21 70 16 1 0 0 0 0 131 0

WNW 0 0 0 13 43 . 53 4 4 0 0 0 117 0

NW 0 1 2 0 2 6 0 0 0 0 0 11 0

NNW 0 0 0 0 1. 0 0 0 0 0 0 1 TOTALS 0 0 3 17 86 211 163 18 4 0 0 0 502 NUMBER OF VALID HOURS 502 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 502 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ s -1.7 'C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- . 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 ' 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 1 1 0 0 0 0 0 0 2 NNE 0 0 0 0 1 0: 0 0 0 0 0 0 1 NE 0 0 0 0 0 0; 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 1 0 0 0 0 1 E 0 0 0 0 0 0 1 0 0 0 0 0 1 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 1 0 1 1 0 0 0 0 3 SSE 0 0 0 1 1 3 5 0 0 0 0 0 10 S 0 0 0 0 1 2 4 0 0 0 0 0 7 SSW 0 0 1 4 3 4 2 1 0 0 0 0 15 SW 0 0 0 0 1 1' 0 0 0 0 0 0 2 WSW 0 0 0 2 2 0' 0 0 0 0 0 0 4 W 0 0 0 3 3 1 1 0 0 0 0 0 8 WNW 0 0 0 0 5 5 1 0 0 0 0 0 11 NW 0 0 0 1 1 5 5 0 0 0 0 0 12 NNW 0. 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 1 11 20 22 20 3 0 0 0 0 77 NUMBER OF VALID HOURS 77 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 77

- I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 03100100-03123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ s -1.5 °C/100 METERS)

WIND .22- .51- .76- 1.1- 7.1- 10.1-

^

1.6- 2.1- 3.1- 5.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N - 0 0 2 2 0 0 - 0 0 0 0 4 NNE 0 0 0 1 1 1 0 0 0 0 0 0 3 NE 0 0 0 1 1 1 0 0 0 0 0 0 3 ENE 0 0 0 1 0 0 0 0 0 0 0 0 1 E 0 0 0 3 0 0 0 0 0 0 0 0 3 ESE 0 0 0 0 0 0 1 0 0 0 0 0 1 SE 0 0 0 1 2 1 1 2 0 0 0 0 7 SSE 0 0 0 0 1 3 9 1 0 0 0 0 14 S 0 0 0 3 1 2 7 0 0 0 0 0 13 SSW 0 0 0 3 1 0 2 1 0 0 0 0 7 SW 0 0 1 4 1 4 1 0 0 0 0 0 11 WSW 0 0 1 5 1 2 0 0 0 0 0 0 9 W 0 0 0 4 1 0 1 0 0 0 0 0 6 WNW 0 0 1 0 2 1 1 0 0 0 0 0 5 NW 0 0 1 2 3 5 0 0 0 0 0 0 11 NNW 0 0 0 3 2 1 1 0 0 0 0 0 7 TOTALS 0 0 4 33 19 21 24 4 0 0 0 0 105 NUMBER OF VALID HOURS 105 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 105 PASQUILL D NEUTRAL (-1.5 < DT/DZ S -0.5 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 1 2 2 5 6 0 0 0 0 0 0 16 NNE 0 0 2 9 5 8 8 1 0 0 0 0 33 NE 0 1 1 1 0 1 1 0 0 0 0 0 5 ENE 0 0 1 3 3 2 1 0 0 0 0 0 10 E 0 0 0 1 3 2 0 0 0 0 0 0 6 ESE 0 0 1 2 5 4 3 0 0 0 0 0 15 SE 0 0 0 2 5 12 24 4 0 0 0 0 47 SSE 0 0 0 5 7 14 18 6 0 0 0 0 50 S 0 0 2 3 4 7 8 7 4 2 1 0 38 SSW 0 1 1 3 7 5 9 7 1 1 0 0 35 SW 0 0 0 7 3 2 7 9 1 1 0 0 30 WSW 0 0 0 2 1 2 5 3 0 0 0 0 13 W 0 1 1 2 2 5 1 0 0 0 0 0 12 WNW 0 0 0 2 3 2 2 1 4 2 0 0 16 NW 0 0 3 5 9 11 8 1 2 0 0 0 39 NNW 0 0 1 8 6 6 2 0 0 0 0 0 23 TOTALS 0 4 15 57 68 89 97 39 12 6 1 0 388 NUMBER OF VALID HOURS 388 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 388 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 03100100-03123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E -

SLIGHTLY STABLE (-0.5 < DT/DZ s 1.5 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 5 16 14 3 0 0 0 0 0 38 NNE 0 0 3 12 17 16 17 0 0 0 0 0 65 NE 0 0 3 7 3 4 1 5 0 0 0 0 23 ENE 1 1 4 3 3 1 2 1 0 0 0 0 16 E 0 0 1 4 1 8 1 0 0 0 0 0 15 ESE 0 0 0 2 0 3 2 0 0 0 0 0 7 SE 0 1 1 5 2 1 4 0 0 0 0 0 14 SSE 0 0 0 0 2 1 3 1 0 0 0 0 7 S 0 1 1 3 1 0 0 0 0 0 0 0 6 SSW 0 0 2 3 4 1 0 0 0 0 0 0 10 SW 0 0 2 2 1 1 0 0 0 0 0 0 6 WSW 0 0 1 3 3 1 1 0 0 0 0 0 9 W 0 0 1 2 2 7 2 0 0 1 0 0 15 WNW 0 0 1 2 6 11: 5 0 0 1 0 0 26 NW 0 1 1 5 0 6 1 0 1 0 0 0 15 NNW 0 2 1 4 1 7 2 1 0 0 0 0 18.

TOTALS 1 6 22 62 62 82 44 8 1 2 0 0 290 NUMBER OF VALID HOURS 290 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 290 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ s 4.0 'C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- .5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 1 0 2 6 7 3 0 0 0 0 0 19 NNE 0 0 1 11 33 43 23 1 0 0 0 0 112 NE 0 0 0 11 11 7 4 2 0 0 0 0 35 ENE 0 0 2 8 8 1 0 0 0 0 0 0 19 E 0 0 0 3 4 2 0 0 0 0 0 0 9 ESE 0 0 0 2 2 1 0 0 0 0 0 0 5 SE 0 1 0 0 0 1 2 0 0 0 0 0 4 SSE 0 0 0 3 2 1 1 0 0 0 0 0 7 S 0 0 0 2 1 0 0 0 0 0 0 0 3 SSW 0 0 0 3 1 1 0 0 0 0 0 0 5 SW 0 0 0 3 0 3 0 0 0 0 0 0 6 WSW 0 0 2 3 2 2 1 0 0 0 0 0 10 W 0 0 1 0 5 2 1 0 0 0 0 0 9 WNW 0 0 0 0 3 3 1 0 0 0 0 0 7 NW 0 0 0 0 0 1 2 0 0 0 0 0 3 NNW 0 0 0 2 1 6 1 0 0 0 0 0 10 TOTALS 0 2 6 53 79 81 39 3 0 0 0 0 263 NUMBER OF VALID HOURS 263 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 263

-- I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2003)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 03100100-03123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4 .0 °C/100 METERS)

^.^.

WiNU IlTkln

.ZZ- .51- .76- 1.1- 1.6- . 2.1- 3..1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5..0 7.0 10.0 -

13.0 18.0 _

N 0 0 1 1 4 5 1 0 0 0 0 A

15 NNE 0 0 1 7 23 167 2' 6 0 0 0 0 443 NE 0 0 O 9 8 25 l3 0 0 0 0 0 55 ENE 0 0 2 5 2 7 0 0 0 0 0 17 1

E 0 0 0 4 1 2 0 0 0 0 0 8 ESE 0 0 1 1 3 0 1 1 0 0 0 0 0 6 SE 0 0 0 1 0 1 1 0 0 0 0 0 3 SSE 0 0 0 1 0 0 1 0 0 0 0 0 2 S 0 0 O 0 1 0 0 0 0 0 0 0 1 SSW 0 0 0 1 1 2 1 0 0 0 0 0 5 SW 0 O 0 0 0 01 07 0 0 0 0 0 0

WSW 0 0 1 0 0 0 0 0 0 0 0 1 0

W 0 0 2 1 0 1 0 0 0 0 0 4 0

0 WNW 0 0 1 0 5 2 0 0 0 0 0 8 0

0 NW 0 O 0 4 2 1 0 0 0 0 0 7 0

NNW 0 0 2 2 3 1 0 0 0 0 0 8 TOTALS 0 5 36 50 219 21 0 0 0 583 NUMBER OF VALID HOURS 583 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 583 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 2 4 12 34 33 10 2 0 0 0 0 97 NNE 0 0 7 40 80 235 289 8 0 0 0 0 659 NE 0 1 4 29 23 38 20 7 0 0 0 0 122 ENE 1 1 9 20 16 11 4 2 0 0 0 0 64 E 0 0 1 15 10 14 3 0 0 0 0 0 43 ESE 0 0 2 7 10 8 7 0 0 0 0 0 34 SE 0 2 1 10 11 16 34 9 0 0 0 0 83 SSE 0 0 0 10 15 29 41 12 0 0 0 0 107 S 0 1 3 12 14 24 37 9 4 2 1 0 107 SSW 0 1 4 20 26 29 34 10 1 1 0 0 126 SW 0 0 3 20 18 39 17 9 1 1 0 0 108 WSW 0 0 4 20 31 38 19 6 0 0 0 0 118 W 0 1 4 15 35 85 43 1 0 1 0 0 185 WNW 0 0 2 5 32 70 65 5 8 3 0 0 190 NW 0 1 6 15 17 32 23 1 3 0 0 0 98 NNW 0 2 2 19 12 24 7 1 0 0 0 0 67 TOTALS 1 12 56 269 384 725 653 82 17 8 1 0 2208 NUMBER OF VALID HOURS 2208 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2208 I:

February 28, 2003 Mr. J. J. Wambold

SUBJECT:

Revision 38 to Unit 2/3 Offsite Dose Calculation Manual (ODCM)

In accordance with Technical Specification 5.5.2.1, Revision 38 to the Unit 2/3 Offsite Dose Calculation Manual has been prepared and reviewed for your approval.

This change incorporates 1) Updates related to the recent Land Use Census,

2) addition of a note explaining that Soil and Kelp sample locations are not required by the Technical Specifications, and 3) Corrects a typographical error from a previous revision. :

None of the changes in this revision will 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 the Nuclear Safety Group as required by Technical Specification 5.5.2.1.

Please contact me if there are any questions.

F. Hirsch Manager, Chemistry Approved by: v d J am old Vice President Nuclear Generation Attachment cc: W. Strom CDM-SONGS RECEIVEDCM Chem File FEB 28 2003 SITEFILECOPY Site File Copy S02 3 -ODCM

I I N--

February 28, 2003

SUBJECT:

Units 2/3 OFFSITE DOSE CALCULATION MANUAL Revision 38 Enclosed is Revision 38 to the Units 2/3 Offsite Dose Calculation Manual (ODCM). This change incorporates 1) Updates related to the recent Land Use Census, 2) addition of a note explaining that Soil and Kelp sample locations are not required by the Technical Specifications and 3) Corrects a typographical error from a previous revision.

Neither change requires an Effluent/ODCM Evaluation.

Minor format changes, correction of typographical errors, and removal of previously blank pages have been made and are described in the attached List of Affected Pages. Per NRC Generic Letter 89-01, no safety reviews were required or performed for editorial changes or changes made to reflect actual plant operation.

None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations. The level of radioactive effluent control required by IOCFR20, 40CFR190, IOCFR50.36a, and Appendix I to 10CFR5O will be maintained.

Page 1 of 2 S02 3 -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 The following is a complete list of the changes:

OLD NEW CHANGE REASON Table of Updated page numbers throughout document as a result of removing blank pages F Contents and adding new RTable.

Section 2 Updated page numbers as a result of removing blank pages and adding new R. F Table.

2-31 2-31 Updated CLF due to Land Use Census Update. R 2-39 Added a new page in Table 2-8 to include the Rec Bldg Staff in Sector Q due A to the Land Use Census Update.

2-41 2-42 Updated Dose Parameters in Table 2-9, Outage Workers due to the Land Use R Census Update.

5-18 5-18 Added note: 'Soil Samples are not required by Technical Specifications'. A 5-19 5-19 Corrected Direction for SONGS Garden from NW to NNW. F 5-20 5-20 Added note: "Kelp Samples are not required by Technical Specifications". A 6-9 Corrected a typographical error in the unplanned releases reporting F requirements.

Page 2 of 2 S02 3 -ODCM

i II

-I, OFFSITE DOSE CALCULATION MANUAL NUCLEAR ORGANIZATION UNITS 2 AND 3 S023-ODCM Revision 38 02-28-03 S023-ODCM

ODCM TABLE OF CONTENTS Page LIST OF FIGURES . . . . . . . . . . . . . . iv LIST OF TABLES . . . . . . . . ... . . . . v-vi INTRODUCTION . . . . . . . . . . . . .I. . vii 1.0 LIQUID EFFLUENTS . . . . . . . . . . 1-1 thru 1-25 1.1 Concentration . . . . . . . . . . . . . . . . . . . . 1-1 1.1.1 Specification. . 1-1 1.1.1.1, 1.1.1.2 Surveillances ... . . . . .

1-1 1.2 Dose .. . .. .. .. ... . . 1-5 1.2.1 Specification . . . . . . . . . . . . 1-5 1.2.1.1 Surveillance . . . . . . . . . . . 1-5 1.3 Liquid Waste Treatment ... ... . ... Calcuatio 1-6 1.3.1 Specification . .-

. .

1-6 1.3.1.1, 1.3.1.2, 1.3.1.3 Surveillances 1-6 1.4 Liquid Effluent Monitor Methods of Setpoint 1-8 1.4.1 Batch Release Setpoint Determination . . . . . .1-10 1.4.2 Continuous Release Setpoint Determination .1-14 1.5 Dose Calculations for Liquid Effluents ... . .. .. .1-22 1.6 Representative Sampling ................ .1-25 2.0 GASEOUS EFFLUENTS .. ... ... .. .. ... . ... .. . 2-1 thru 2-64 IF 2.1 Dose Rate. . . . . ... . .. . . . . . .2-1 2.1.1 Specification . . 2-1 2.1.1.1, 2.1.1.2 Surveillances ... . ... .2-1 2.2 Dose - Noble Gas . . ... . . . . . . . . . . .2-5 2.2.1 Specification .... . ... .. .. . 2-5 2.2.1.1 Surveillance . . . . . . . . . . . . . . . . . . . 2-5 2.3 Dose - Radioiodines, Radioactive Materials in Particulate Form and Tritium . .. . . . . . . . . . . . . . 2-6 2.3.1 Specification ... .. ... . ... 2-6 2.3.1.1 Surveillance ... .. ... . ... 2-6 S023-ODCM Revision 30 i 05-28-97 S02 3 -ODCM

- I I ODCH TABLE OF CONTENTS (Continued)

Page 2.4 Gaseous Radwaste Treatment . . . . . . . . . . . . . . . . 2-7 2.4.1 Specification . . . . . . . . . . . . . . . . . . . . 2-7 2.4.1.1 Surveillance . . . . . . . . . . . . . . . . . . . 2-7 2.4.1.2, 2.4.1.3 Surveillances . . . . . . . . . . . . 2-8 2.5 Deleted, moved to Section 3 2.6 Gaseous Effluent Monitor Setpoints . . . . . . . . . . . . 2-10 2.6.1 Plant Stack . . . . . . . . . . . . . . . . . . . . 2-10 2.6.2 Condenser Evacuation System . . . . . . . .. . . . 2-13 2.6.3 Containment Purge . . . . . . . . . . . . .. . . . 2-15 2.6.4 Waste Gas Header . . . . . . . . . . . . .. . . . 2-18 2.6.5 South Yard Facility . . . . . . . . . . . .. . . . 2-20 2.7 Gaseous Effluent Dose Rate . . . . . . . . . . . . . . . . 2-23 2.7.1 Noble Gases . 2-23 2.7.2 Radioiodines and Particulates. 2-24 2.8 Gaseous Effluent Dose Calculation . . . . . . . . . . . . . 2-25 2.8.1 Noble Gases . . . . . . . . . . . . . . . . . . . . 2-25 2.8.1.1 Historical Meteorology . . . . . . . . . 2-25 2.8.1.2 Concurrent Meteorology . . . . . . . . . 2-26 2.8.2 Radioiodines and Particulates . . . . . . . . . . . 2-27 2.8.2.1 Historical Meteorology . . . . . . . . . 2-27 2.8.2.2 Concurrent Meteorology . . . . . . . . . 2-28 3.0 PROJECTED DOSES . . . . . . . . . . . . . . . . . . . . . . . . 3-1 thru 3-5 3.1 Liquid Dose Projection . . . . . . . . . . . . . . . . . . 3-1 3.2 Gaseous Dose Projection . . . . . . . . . . . . . . . . . . 3-1 3.3 Total Dose . . . . . . . . . . . . . . . . . . . . . . . . 3-2 3.3.1 Specification . . . . . . . . . . . . . . . . . . . . 3-2 3.3.1.1 Surveillance . . . . . . . . . . . . . . . . . . . 3-2 3.4 Total Dose Calculations . . . . . . . . . . . . . . . . . . 3-3 3.4.1 Total Dose to Most Likely Member of the Public 3-3 3.4.1.1 Annual Total Organ Dose . .3-3 3.4.1.2 Annual Total Whole Body Dose . .3-4 3.4.1.3 Annual Total Thyroid Dose . . . . . . . . 3-5 S023-ODCM Revision 35 02-29-00 S023-ODCM

4.,

ODCM TABLE OF CONTENTS (Continued)

Page 4.0 EQUIPMENT . . . . . . . . . ... . . . . . . . . . . . . . . . . 4-1 thru 4-22 4.1 Radioactive Liquid Effluent Monitoring Instrumentation 4-1 4.1.1 Specification .................... 4-1 4.1.1.1, 4.1.1.2 Surveillances . . . . . . . . . . . . . . 4-1 4.2 Radioactive Gaseous Effluent Monitoring Instrumentation 4-9 4.2.1 Specification. .. . . . . . . . . . . . . . . 4-9 4.2.1.1 Surveillance ................... 4-9 4.3 Operability of Radioactive Waste Equipment . . . . . . . . 4-19 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING . . . . . . . . . . . . . 5-1 thru 5-27 5.1 Monitoring Program ..... 5-1 5.1.1 Specification 5-1 5.1.1.1 Surveillance . . . . . . . . . . . . . . . . . . . 5-2 5.2 Land Use Census ...................... 5-11 5.2.1 Specification . . . . . . . . . . . . . . . . . . 5-11 5.2.1.1 Surveillance . .-. . . . . . . . . . . . . . . . . 5-11 5.3 Interlaboratory Comparison Program . . . . . . . . . . . . 5-12 5.3.1 Specification ....... . . . . . . . . . . . . . 5-12 5.3.1.1 Surveillance . . . . . . . . . . . . . . . 5-12 5.4 Annual Radiological Environmental Operating Report . . . . 5-13 5.5 Sample Locations . . . . . . . . . . . . . . . . . . . . . 5-14 6.0 ADMINISTRATIVE ......................... 6-1 thru 6-17 6.1 Definitions . . . . . . . . . . . . . . . . . . . . . 6-1 6.2 Administrative Controls . . . . . . . . . . . . . . . . .. 6-8 6.3 Major Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) ................ 6-10 6.4 Bases . . . . . . . . . . . . . . . . . . . . . . . . * .. 6-11 S023-ODCM Revision 25 iii 02-28-92 S023-ODCM

I Ie

$k ODCM LIST OF FIGURES Fiaure Title Paue 1-2 Site Boundary for Liquid Effluents . . ....... . 1-7 2-2 Site Boundary for Gaseous Effluents . . . . . . . . . . . . . . . . 2-9 4-5 SONGS 2 and 3 Radioactive Liquid Waste Treatment Systems . . . . . 4-20 4-6 SONGS 2 and 3 Radioactive Gaseous Waste Treatment Systems . . . . 4-21 4-7 Solid Waste Handling . . . . . . . . . . . . . . . . . . . . . . . 4-22 5-1 Radiological Environmental Monitoring Sample Locations 1 Mile Radius . . . . . . .. .. .... . . . . . .. . 5-23, 24 5-2 Radiological Environmental Monitoring Sample Locations 2 Mile Radius . . . . . . . . . . . . . . . . . . . . . . . . 5-25, 26 5-3 Radiological Environmental Monitoring Sample Locations 10 Miles Radius . . . . . . . . . . . . . . . . . . . . . . . 5-27, 28 5-4 Radiological Environmental Monitoring Sample Locations Orange County ...... .. . . . .. . . .. . . . .. . . . . 5-29 5-5 Radiological Environmental Monitoring Sample Locations San Diego County . . . . . 5-31 5023-ODCM iv Revision 31 02-27-98 S02 3 -ODCM

ODCM LIST OF TABLES Table Title PaUe 1-1 Radioactive Liquid Waste Sampling and Analysis Program . . 1-2 1-3 Liquid Effluent Radiation Monitors Calibration Constants ................. . . 1-21 1-4 Dose Commitment Factors AiT .............. . . 1-23 2-1 Radioactive Gaseous Waste Sampling and Analysis Program . . 2-2 2-3 Gaseous Effluent Radiation Monito r Calibration Constants . . . . . . . . . . . . . .. . 2-22 2-4 Dose Factors for Noble Gas and Daughters ..... . . . . . 2-29 2-5 Dose Parameters Pik1 * *- . . . . . . . . . . 2-30 .

2-6 Controlling Location Factors-.. . . . . . . . . . . . . . 2-31 .

2-7 Dose Parameters R,.'for.;Sector P . . . . . . . . . . . . . 2-32 .

2-8 Dose Parameters R. for Sector Q . . . . . . . . . . . . . 2-34 .

2-9 Dose Parameters R. for Sector R . . 0.

2-10 Dose Parameters R. for Sector A . . . . . . . . . . . . . 2-43 .

2-11 Dose Parameters R. for Sector B . . . . . ... . . . . . . 2-44 .

2-12 Dose Parameters RI for Sector C . . . . . . . . . . . . . 2-46 .

2-13 Dose Parameters R. for Sector D . . . . . . . . . . . . . 2-48 .

2-14 Dose Parameters R. for Sector E . . . . . . . . . . . . . 2-50 F .

2-15 Dose Parameters R. for Sector F . . . . . . . . . . . . . 2-52 .

2-16 Dose Parameters R. for Sector G . . . . . . . . . . . . . 2-53 .

2-17 SYF Controlling Location Factors . . . . . . . . . . . . . 2-54 .

2-18 SYF Dose Paramet .ers Ri for Sector D ...... . . . . . . 2-55 2-19 SYF Dose Paramet -ers Ri for Sector E ...... . . . . . . 2-56 2-20 SYF Dose Paramet ters Ri for Sector F ...... . . . . . . 2-57 2-21 SYF Dose Paramet ters Ri for Sector G ...... . . . . . . 2-61 S023-ODCM Revision 28 v 12-21-95 S02 3 -ODCM

I I ODCM LIST OF TABLES (Continued)

Table Title Page 4-1 Radioactive Liquid Effluent Monitoring Instrumentation . . 4-2 4-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements . . .:. . .. , . 4-6 4-3 Radioactive Gaseous Effluent Monitoring Instrumentation . . 4-10 4-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements . . . . . . . . . . . . . . . . . 4-14 5-1 Radiological Environmental Monitoring Program .. 5-3 5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples . . . . . . . . . . . . . . . . . . . 5-7 5-3 Maximum Values for the Lower Limits of Detection (LLD) . . 5-8 5-4 Radiological Environmental Monitoring Sample Locations . . 5-15 5-5 PIC Radiological Environmental Monitoring Locations * . 5-21 5-6 Sector and Direction Designation for Radiological Environmental Monitoring Sample Location Map . . . . . . .. 5-22 6-1 Operational Modes . . . . . . . . . . . . . . . . . . . . . 6-6 6-2 Frequency Notation ................... . . 6-7 S023-ODCM Revision 25 vi 02-28-92 S02 3 -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 from radioactive-liquid and airborneieffluents. In order to meet release limits, it additionally provides calculations for liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints. The environmental section contains a list' of the sample locations for the radiological environmental monitoring program.-

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

S023-ODCH Revision 21 vii 02-15-90 S02 3 -ODCM

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

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

APPLICABILITY: At all times ACTION:

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

SURVEILLANCE REQUIREMENTS

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

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

S023-ODCM 1-1 Revision 22 08-02-90 S02 3 -ODCM

1. -40 TABLE 1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)

Type Frequency Frequency Analysis (PCi/ml)'

A. Batch Waste P P Principal Gamma 5x10-7 Released Each Batch Each Batch Emittersf 1-131 1x10' P M Dissolved and 1x1D 51 One Batch/M Entrained Gases (Gamma-emitters)

P M H-3 1x10-0 Each Batch Compositeb Gross Alpha 1x10 7-P Q Sr-89, Sr-90 5x10 8 Each Batch Compositeb Fe-55 1x10'6 NOTE BATCH RELEASE POINTS: Primary Plant Makeup Storage Tanks, Radwaste Primary Tanks, Radwaste Secondary Tanks, Miscellaneous Waste Condensate Monitor Tanks, Blowdown Processing System Neutralization Sump, FFCPD sumps (high conductivity, low conductivity) and holdup tank, Component Cooling Water Sump, Storage Tank Area Sump, S/G Blowdown.

B. Continuous D W Principal Gamma 5x10-7 Releases', Grab Sample Composite' Emittersf T Ift-1 . -. ^-6i M M Dissolved and 1x10-5 Grab Sample -Entrained 'Gases ' '

(Gamma emitters)

H-3 1x10'5 Grab Sample,CoMpoite'-',

Gross Alpha ' ' l X10 7 D Qi M ; Sr-89, Sr-90 5x10 01 Grab Sample ID Composite' Fe-55 ; lx1 6-

. I .. .. . :

,, i- i-- ,-

NOTE CONTINUOUS'RELEASE POINTS: Turbine'Plant Sump -'Blowdown Processing System Neutralization Sump', S/G Blowdown Bypass Line' ,S/G Blowdown, Auxiliary Building Sump.

S023-ODCM 1-2 Revision 32 02-25-99 S02 3 -ODCM

TABLE 1-1 (Continued)

TABLE NOTATION

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

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

4.66 s LLD =b E

V

2.22 x 106

Y

exp (-Mt) where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie 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 midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

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

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

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

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

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

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

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

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

S023-ODCM 1-3 Revision 26 12-20-93 S023-ODCM

TABLE 1-1 (Continued)

TABLE NOTATION

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

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

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

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

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

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

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

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

Sampling of this flow is not required if at least once per 31 days blowdown bypass isolation valve (S21301MU619 for Steam Generator 2E088, S21301MU618 for Steam Generator 2E089, S31301MU619 for Steam Generator 3E088 and S31301MU618 for Steam Generator 3E089) is verified locked shut.

S023-ODCM 1-4 Revision 32 02-25-99 S02 3 -ODCM

I I 1.0 LIQUID EFFLUENTS (Continued) 1.2 DOSE SPECIFICATION 1.2.1 The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site (see Figure 1-2) shall be limited:

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

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

APPLICABILITY: At all times ACTION:

a. With calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to' the Commission within 30 days, pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special' Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions taken to reduce the'releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 1.2.1.

SURVEILLANCE REQUIREMENTS

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

S023-ODCM 1-5 Revision 30 05-28-97 S02 3 -ODCM

1.0 LIQUID EFFLUENTS (Continued) 1.3 LIQUID WASTE TREATMENT SPECIFICATION 1.3.1 The liquid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site (see Figure 1-2) when averaged over 31 days, would exceed 0.06 mrem to the total-body or 0.2 mrem to any organ.

APPLICABILITY: At all times ACTION:

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

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

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

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

SURVEILLANCE REQUIREMENTS

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

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

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

Per reactor unit S023-ODCM

-'1-6 Revision 33 05-03-99 S02 3 -ODCM

I I SITE BOUNDARY FOR LIQUID EFFLUENTS FIGURE 1-2 SANOWU MXLt A TunicTS $TAT=

WUTS .213 0 00

' Gnat way 3, WThKZ WAs rMa w a No _ _

p

/

S023-ODCM 1-7 Revision 29 07-31-96 S02 3 -ODCM

1.0 LIQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR METHODS OF SETPOINT CALCULATION 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 this specification and for the purpose of implementation of Specification 1.1.1, the alarm/trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is'satisfied:

F+sMPC -

where:

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.

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

= 17,000 gpm per saltwater pump (2 total)

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

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

S023-ODCM 1-8 Revision 30 05-28-97 S02 3 -ODCM

I I 1.0 LIQUID EFFLUENTS (Continued) 1.4 LUOUID EFFLUENT MONITOR METHODS OF SETPOINT CALCULATION (Continued)

MPCeff = effective effluent maximum concentration permissible limit (puCi/ml) at the release point to the unrestricted area for the

(

radionuclide mixture being released:

1 (1-2)

= MPC F i where:

n = number of radionuclides identified in sample analysis F. = fractional concentration of the it'radionuclide as obtained by sample analysis MPC, = MPC of the jth radionuclide (10CFR20, App B, Table II, Column 2)

Administrative values are used to reduce each setpoint to account for the potential activity released simultaneously from the following release points:

RW7813 = Radwaste Effluent discharge SGn-2 = Unit 2 Steam Generator E-088 SG89.2 = Unit 2 Steam Generator E-089 SG 88-3 = Unit 3 Steam Generator E-088 SG89.3 = Unit 3 Steam Generator E-089 B2 = Unit 2 Blowdown Processing System Neutralization Sump B3 = Unit 3 Blowdown Processing System Neutralization Sump Tz = Unit 2 Turbine Plant Sump T3 = Unit 3 Turbine Plant Sump The sum of the administrative values is limited to 1.0 to ensure that the total concentration from all release points to the plant discharge will not result in a release exceeding the limits of 10CFR20, Appendix B, Table II, Column 2 from Units 2 and 3. The administrative values shall be assigned such that:

7813 + SG88 2 (RW + SG89-2 + SG8-3 + SG89.3 + B2 + B3 + T2 + T3) C 1.0.

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

S023-ODCM 1-9 Revision 31 02-27-98 S02 3 -ODCM

16.

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

STEP 1: The isotopic concentration for each batch tank (or sump) to'be released 'isobtained from the sum of the measured concentrations in the tank (or sump) as determined by analysis.

C (El YC')

+ (C.) + (Cs) + (Ct) + (CFe) * (X1 ) (1-3) where:

C = total concentration in each batch tank, pCi/ml Ej1,'Y = sum of the measured concentrations for each radionuclide, 1, 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 CF. = Fe-55 concentration as determined in the previous quarterly Composite sample, pCi/ml CXe = Xe-133 concentration as determined by isotopic analysis, PCi/ml S023-ODCM 1-10 Revision 34 11-09-99 S02 3 -ODCM

I I

'-Is 1.0 LIQUID EFFLUENTS (Continued) 1.4.1 BATCH RELEASE SETPOINT DETERMINATION (Continued)

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

C1 (1-4)

MPCeff =

cWCY,/C CS/c i~MPCJ 4. (MPCS)

+

Ct/CA MPCt) 41.C ICjC Cre/C M

MPa tPFe}

where:

MPCYjI MPCSS = the limiting concentrations of the appropriate MPCt. radionuclide from 10CFR20, Appendix B. Table 11, MPCF,. Column 2 MPC 0 NOTE: For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-4 pCi/ml total activity.

STEP 3: The setpoint, C, (pCi/ml) for each batch release radioactivity monitor may now be specified based on the respective values of C. EiC'ky, F, MPCeff, and R to provide compliance with the limits of 10CFR20, Appendix B. Table II, Column 2.

STEP 4: If the monitor reads in CPM, the setpoint may be derived using the applicable calibration constants given in Table 1-3 to correspond to the calculated monitor limit C,, pCi/ml.

(1-5)

CPM = (Cm. pCi/ml) max (Cal. Const., uCi/cc/cpm)

S023-ODCM 1-11 Revision 34 11-09-99 S02 3 -ODCM

1.0 LIQUID EFFLUENTS (Continued) 1.4.1 BATCH RELEASE SETPOINT DETERMINATION (Continued) 1.4.1.1 RADWASTE DISCHARGE LINE MONITOR (2/3RT-7813)

The value for C., the c1oncentration limit at the detector, is determined by using:

CW 76 3)(F) (1C'A) (1-6)

(R) MPC C J where:

RW73 = Radwaste Effluent discharge administrative value F dilution water flow in volume per unit time

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

= 17,000 gpm per saltwater pump (2 total)

C = Total concentration in each batch sample iC'y1= total gamma isotopic concentration, excluding Xe-133, PCi /ml R = typical effluent release rate.

Values of-R-for each tank are as follows:

Radwaste Primary Tanks = 140 gpm (per pump)

Radwaste Secondary Tanks = 140 gpm (per pump)

Primary Plant Makeup' Tank = 160 gpm (per pump)

Condensate'Monitor Tanks = 100 gpm (per pump)

MPCeff = from equation-(1-4)

NOTE: If C_ < z1C'1,. then no release is possible. To increase Cm, increase the administrative value RW701 3, and/or increase dilution flow F (by running more 'dilution pumps in the' applicable discharge structure),

and/or decrease the effluent flow rate R and recalculate Cm using the new RW,, 3,'F,' R'as.4pplicable'and equation (1-6).

S023-ODCM 1-12 Revision 34 11-09-99 S02 3 -ODCM

1.0 LIQUID EFFLUENTS (Continued) 1.4.1.2 BLOWDOWN PROCESSING SYSTEM NEUTRALIZATION SUMP/FULL FLOW CONDENSATE POLISHER DEMINERALIZER (FFCPD) SUMP DISCHARGE LINE MONITOR (BATCH)

(2RT-7817. 3RT-7817)

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

(B2) (F) (zC'IY (1-7) 2 (R)(C/MP1 Cef )

~3) (F) (c') (1-8)

C3 (R)(C/MPC,ff) where:

C2 = instantaneous concentration at detector 2RT-7817 in pCi/cc C3 = instantaneous concentration at detector 3RT-7817 in pCi/cc B2 = Unit 2 BPS Neutralization Sump administrative value B, = Unit 3 BPS Neutralization Sump administrative value F = dilution water flow in volume per unit time

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

= 17,000 gpm per saltwater pump (2 total)

EiClyi = total gamma isotopic concentration, excluding Xe-133, yCi/ml, (STEP 1)

R = Typical release flow rates:

BPS Neutralization Sump = 500 gpm FFCPD High Conductivity Sump = 500 gpm FFCPD Low Conductivity Sump = 600 gpm FFCPD Holdup Tank = 1000 gpm C = total concentration in each batch sample, pCi/ml MPCff = value of MPCeIf from equation (1-4) for the sample analysis NOTE: If C2 or C, C E1 C' ,, then no release is possible. To increase C2 or C3, increase the administrative value B2 or B3, and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate C2 or C3 using the new B2 or B3, F. R as applicable and equation (1-7) or (1-8).

5023-ODCM 1-13 Revision 34 11-09-99 S02 3 -ODCM

1.0 LIQUID EFFLUENTS (Continued) 1.4.2 CONTINUOUS 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 (MPCef) limit.

The method by which this is accomplished is as follows:

STEP 1: The isotopic concentration for the continuous releases are obtained for each release stream (steam generator blowdown, steam generator blowdown bypass, blowdown processing system neutralization sump and turbine plant sump) from the sum of the respective measured concentrations as determined by analysis:

C= (C'y) + (C.) + (Cs) + (Ct) + (CFe) + (Cxe) (1-3) where:

,.1 C = total concentration (pCi/ml)

,C'i = total gamma activity associated with each radionuclide, i, in the weekly composite analysis for the release stream, excluding Xe-133 jpCi/ml C = total measured gross alpha concentration determined from the previous monthly composite analysis for the release stream, pCi/ml C, = total measured-concentration of Sr-89 and Sr-90 as determined from the previous quarterly composite analysis for the release stream, pCi/ml C, total measured H-3 concentration determined from the previous weekly or monthly composite analysis for the release stream, pCi/ml CF. = total Fe-55 concentration as determined in the previous quarterly composite sample for the release stream, pCi/ml Cme = Xe-133 concentration as determined by isotopic analysis, PCi/ml 5023-ODCM 1-14 Revision 34 11-09-99 S023-ODCM

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

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

1 (1-4)

MPCetf =

t MPCJ (

Cs/C MPCS

)14 Ct/C 4 C/C1 MPCt J MPC a

+ ( CFe/C MPC F) 1 where:

MPC~i, MPCS, the limiting concentrations of the appropriate MPCt, radionuclide from 10CFR20, Appendix B. Table II, MPCre, Column 2 MPC0 STEP 3: The setpoint, C, (pCi/ml) for each continuous release radioactivity monitor may now be specified based on the respective values of C, ACED F, MPCff, and R to provide compliance with the limits of 10CFR20, Appendix B, Table II, Column 2.

STEP 4: If the monitor reads in CPM, the setpoint may be derived using the applicable calibration constants given in Table 1-3 to correspond to the calculated monitor limit C., pCi/ml.

(1-5)

CPM - (C., 'PCi/ml)

Max (Cal. Const., pCi/cc/cpm)

S023-ODCM 1-15 Revision 34 11-09-99 S02 3 -ODCM

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.1 BLOWDOWN PROCESSING SYSTEM NEUTRALIZATION SUMP DISCHARGE LINE MONITORS (2RT-7817,3RT-7817)

The value for C2 (Unit 2) or C3 (Unit 3), the concentration limit at the Unit 2 or Unit-3 detector, is determined by using:

( 2) (F) (E,C'-) (1-7)

(R)(C/MPCeff)

(B3) (F) (Ec') (1-8) 3 (R) (C/MPCetf) where:

C2 = instantaneous concentration at detector 2RT-7817 in pCi/cc C3 = instantaneous concentration at detector 3RT-7817 in pCi/cc B2 = Unit 2 Blowdown Processing System Neutralization Sump administrative value B3 = Unit 3 Blowdown Processing System Neutralization Sump administrative- value F = dilution water flow in volume per unit time

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

= 17,000gpm per saltwater pump (2 total)

iC'yj = total gamma isotopic concentration, excluding Xe-133, pCi/ml, (STEP 1)

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

C = total concentration, pCi/ml MPCeff value of MPCeff from equation (1-4) for the sample analysis NOTE: If C2 or-C3 < EXC'y, then no release is possible. To increase C2 or C3, increase the. administrative value B2 or B3, and/or increase dilution flow F (by runningnmore'dilution.pumps), and/or decrease the effluent flow rate, R, and recalculate C2 or C3 using the new B2 or B3, F, R as applicable and equation (1-7) or (1-8).

S023-ODCM 1-16 Revision 34 11-09-99 S02 3 -ODCM

I I 1.0 LIQUID EFFLUENTS (Continued) 1.4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT-6753. 2RT-6759. 3RT-6753. 3RT-6759)

The value for C.9.2. C532, C59 3 or C53., the concentration limit at the Unit 2 or Unit 3 detectors, is determined by using:

C (SG8 8_2) (F) (EC I) (1-9) 59-2 (R) (/MPCeff)

C (SG89_2) (F) (EIC',) (1-10) 53-2 (R) (C/MPCeff)

(SG6 8 3) (F) (; C ) (1-11) 59 3 (R) (C/MPCeff)

C & (SGs93) (F) (cC) (1-12) 53-3 (R) (C/MPCeff) where:

C59. = instantaneous concentration at detector 2RT-6759 in pCi/ml CS3- = instantaneous concentration at detector 2RT-6753 in pCi/ml C59,3 = instantaneous concentration at detector 3RT-6759 in pCi/ml C53. 3 = instantaneous concentration at detector 3RT-6753 in pCi/ml SGu2 = Unit 2 E088 Steam Generator Blowdown administrative value SG89.2 = Unit 2 E089 Steam Generator Blowdown administrative value SGM.3 = Unit 3 E088 Steam Generator Slowdown administrative value SG89.3 = Unit 3 E089 Steam Generator Blowdown administrative value F = dilution water flow in volume per unit time

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

= 17.000 gpm per saltwater pump (2 total)

S023-O0CM 1-17 Revision 34 11-09-99 S023 -ODCM

Es.

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

EiCly1= total gamma isotopic concentration, excluding Xe-133, yCi/ml, (STEP 1)

R = maximum blowdown bypass-effluent flowrate per steam generator, 200 gpm, (STEP 1)

C = total concentration, pCi/ml MPCff = value of MPC,ff from equation (1-4) for the sample analysis NOTE: If C69-2, CS3.2, C59.3, or C.3-3 " EiC'.i (for the respective steam generator),

then no release is possible. To increase C5,. 2, CS3-2, CS3 or C53.3, 9-increase the administrative value SG,,.,, SG, 9.2, SG, 8, 3 or SG 89.3, and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate R and recalculate C59-2 , C53 -2, C59-3 or C53 43 using the new values of SG 89.3 or SGH8 3, F, R as applicable 8,.2 , SGN. 2, SG and equation (1-9), (1-10), (1-11) or (1-12).

S023-ODCM 1-18 Revision 34 11-09-99 S02 3 -ODCM

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

The value for C2 (Unit 2) or C3 (Unit 3), the concentration limit at the Unit 2 or Unit 3 detector, is determined by using:

(r2)(F) (zC') (1-13) 2 (R)(C/MPCef)

(T3)(F)( c',C) (1-14)

(R)(C/MPCff) where:

C2 = instantaneous concentration at detector 2RT-7821 in pCi/cc C3 = instantaneous concentration at detector 3RT-7821 in pCi/cc T2 = Unit 2 Turbine Plant Sump administrative value T3 = Unit 3 Turbine Plant Sump administrative value F = dilution water flow in volume per unit time

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

= 17,000 gpm per saltwater pump (2 total)

E1C1yj = total gamma isotopic concentration, excluding Xe-133, pCi/ml, (STEP 1)

R = effluent flow rate, gpm, (STEP 1), typically flow rate:

= 100 gpm (per pump)

C = total concentration, pCi/ml MPCeff = value of MPCe,, from equation (1-4) for the sample analysis NOTE: If C.or C3 < E1 C'y, then no release is possible. To increase C2 or C3, increase the administrative value T2 or T3, and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R. and recalculate C2 or C3 using the new T. or T3, F, R as applicable and equation (1-13) or (1-14).

S023-ODCM 1-19 Revision 34 11-09-99 S023-ODCM

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

Use of a temporary discharge path from the Turbine Plant Sump is allowed providing the radiation monitor, 2(3)RT-7821. is in service and the normal discharge path is used concurrently. Temporary

-pumps facilitate faster-discharge when draining the condenser to the outfall via this pathway. The following conditions shall be met:

a. The release permit shall account for the entire volume of water discharged from the Turbine Plant Sump.

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

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

S023-ODCM 20 Revision 21 02- 15-90 S023-ODCM

I I TABLE 1-3 Liquid Effluent Radiation Monitor Calibration Constants (a)

(pCi/cc/cpm)

MONITOR Co-60 Ba-133 Cs-137 2RT-6753 2.07E-8 1.90E-8 2RT-6759 1.90E-8 1.90E-8 3RT-6753 1.92E-8 1.92E-8 3RT-6759 1.98E-8 1.97E-8 (a) This table provides typical (+/- 20%) calibration constants for the liquid effluent radiation monitors.

S023-ODCM 1-21 Revision 34 11-09-99 S02 3 -ODCM

4-1.0 LIQUID EFFLUENTS (Continued)-_.-.

1.5 DOSE CALCULATION FOR LIOUID EFFLUENTS The liquid releases considered in the following dose calculations are described in Section-1.4. The dose commitment to an individual.from radioactive materials in liquid effluents released to unrestricted areas are calculated for the purpose of-implementing Specification 1.2.1 using the following expression.

D. =zI[AjEJ(Atj C13 Fj)] (1-15) where:

Ai, = Site-related adult ingestion dose-commitment factor to the total body or an organ, T,'-for each identified principal -gamma and beta emitter, i, from Table 1-4 in mrem/hr per pCi/ml.

Cl -

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

- 'Dt= dose commitment to the total body or an organ, x, from the liquid effluent for the time period, Atj. in mrem. . -

Fj - near field average dilution factor (actually mixing ratio) for Ci -during the time-period, Otj. This factor'is-the ratio of the maximum-undiluted liquid waste flow during time period,

atM to the average flow from the site discharge structure to unrestricted.receiving waters, ' -

-maximum liquid-radioactive waste flow

'or: ' - discharge~structure-exit flow .

At = length of the j'" time period over which Cj and Fj are averaged for all liquid releases, in hours.

.3. .~ .. ...

S023-ODCM 1-22 Revision 26 12-20-93 S02 3 -ODCM

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

Radio- Total nuclide Bone Liver Body Thyroid Kidney Lung GI-LLI H-3 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 Na-24 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 Cr-51 5.58E+0 3.34E+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+2 3.15E+1 2.26E+2 5.67E+3 Fe-55 5.11E+4 3.53E+4 8.23E+3 1.97E+4 2.03E+4 Fe-59 8.06E+4 1.90E+5 7.27E+4 _ _ _ 5.30E+4 6.32E+5 Co-57 1.42E+2 2.36E+2 3.59E+3 Co-58 6.03E+2 1.35E+3 1.22E+4 Co-60 1.73E+3 3.82E+3 3.25E+4 Cu-64 2.14E+2 1.01E+2 5.40E+2 1.83E+4 Zn-65 1.61E+5 5.13E+5 2.32E+5 3.43E+5 3.23E+5 Br-84 9.39E-2 7.37E-7 Rb-88 1.79E+0 9.49E-1 2.47E-11 Sr-89 4.99E+3 1.43E+2 _ 8.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+O 6.90E+2 Y-90 6.06E+0 1.63E-1 6.42E+4 Y-91m 5.73E-2 2.22E-3 1.68E-1 Y-92 5.32E-1 1.56E-2 9.32E+3 Zr-95 1.59E+1 5.11E+O 3.46E+O 8.02E+O 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 j 2.96E+2 Tc-99m 1.30E-2 3.66E-2 4.66E-1 5.56E-1 1.79E-2 2.17E+1 NOTE: where no value is given, no data are available.

Source: Reg. Guide 1.109. Table E-11, Table A-1 USNRC NUREG-0172, Table 4 ICRP-30, Part 3, Supplement A Methodology: USNRC NUREG-0133, Section 4.3.1 S023-ODCM 1-23 Revision 26 12-20-93 S02 3 -ODCM

TABLE 1-4 (Continued)

DOSE COMMITMENT FACTORS*, Ai.

(mrem/hr per pCi/ml)

Radio- Total nuclide Bone Liver Body Thyroid Kidney Lung GI-LLI Ru-103 1.07E+2 4.60E+1 . 4.07E+2 1.25E+4 Ru-106 1.59E+3 2.01E+2 3.06E+3 _ 1.03E+5 Ag-110m 1.42E+3 1.32E+3 7.82E42 2.59E+3 5.37E+5 Sn-113 2.26E+5 Sn-117m 2.26E+5 Sb-124 2.76E+2 5.22E+0 1.09E+2 6.70E-1 2.15E+2 7.84E+3 Sb-125 1.77E+2 1.97E+O 4.20E+1 1.79E-1 1.36E+2 1.94E+3 Te-129m 9.31E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 4.69E+3 Te-132 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 6.24E+3 1-131 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E+2 8.23E+1 I-132 1.06E+1 2.85E+1 9.96E+0 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 I-134 5.56E+O 1.51E+1 5.40E+0 2.62E+2 2.40E+1 1.32E-2 I-135 2.32E+1 6.08E+l 2.24E+1 4.01E+3 9.75E+1 6.87E+1 Cs-134 6.84E+3 1.63E+4 1.33E+4 5.27E+3 1.75E+3 2.85E+2 Cs-136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21E+2 Cs-137 8.77E+3 1.20E+4 7.85E+3 4.07E+3 1.35E+3 2.32E+2 Cs-138 6.07E+O 1.20E+1 5.94E+0 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+O 1.08E+2 7.02E-1 1.18E+O 3.38E+3 La-140 1.57E+O 7.94E-1 2.10E-1 5.83E+4 Ce-141 3.43E+0 2.32E+O 2.63E-1 1.08E+O 8.86E+3 Ce-143 6.04E-1 4.46E+2 4.94E-2 1.97E-1 1.67E+4 Ce-144 1.79E+2 7.47E+1 9.59E+0 4.43E+1 6.04E+4 Nd-147 3.96E+O 4.58E+O 2.74E-1 2.68E+O 2.20E+4 W-187 9.16E+0 7.66E+0 2.68E40 2.51E+3 Np-239 3.53E-2 3.47E-3 1.91E-3 1.08E-2 7.11E+2 NOTE: where no value is given, no data are available.

Source: Reg. Guide 1.109, Table E-11, Table A-1 USNRC NUREG-0172, Table 4 ICRP-30, Part 3, Supplement A Methodology: USNRC NUREG-0133, Section 4.3.1 S023-ODCM

- 1-24 Revision 26 12-20-93 S02 3 -ODCM

II 1.0 LIQUID EFFLUENTS (Continued) 1.6 Representative Sampling Prior to sampling of a batch release, each batch shall be thoroughly mixed to assure representative sampling in accordance with the requirements of Regulatory Guide 1.21 and NUREG-0800, Section 11.5. The methodology for mixing and sampling is described in S0123-III-5.23, "Generating Effluent Release Permits Using The Vax Computer" and S0123-III-5.2.23, "Units 2/3 Liquid Effluent Sample Collection".

S023-ODCM 1-25 Revision 36 02-28-01 S02 3 -ODCM

2.0 GASEOUS EFFLUENTS 2.1 DOSE RATE SPECIFICATION :

2.1.1 The dose rate in unrestricted areas due to radioactive

- materials released in gaseous effluents from the site (see.

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

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

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

APPLICABILITY: At all times ACTION:

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

SURVEILLANCE REOUIREMENTS

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

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

S023-ODCM 2-1 Revision 21 02-15-90 S02 3 -ODCM

11t TABLE 2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Minimum Type of Lower Limit Release Sampling Analysis Activity of Detection Type Frequency Frequency Analysis (1Ci /ml)

Batch P P, Principal Gamma Emitters" 1x1O*'

Waste Gas Each Tank Each Tank Decay Tank Grab Sample Continuous *

Principal Gamma Emitters9 lxlO"'

Tritium 1x10-6 Wd I-131 1x10' 2 Continuousf Charcoal Sampler Sample I-133 1x10-'

Wd Continuousf Particulate Principal Gamma Emitters9 1x10'1 Sampler Sample (1-131 and Others)

M Continuous' Composite Gross Alpha 1x10 11 Sampler Particulate Sample Q

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

Sampling frequencies for noble gases and tritium are:

CONTINUOUS PATHWAYS: Containment Purge - 42" Each Purgebwo Containment Purge - 8" Monthly Grabb.

Condenser Air Ejector Monthly Grabb.

Plant Vent Stack Weekly Grabb'e South Yard Facility Particulate and Iodine sampling onlyh S023-ODCM 2-2 Revision 32 02-25-99 S023-ODCM

TABLE 2-1 (Continued)

TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected.with 95% probability with only 5% probability of.

falsely concluding that a blank observation represents a "real' signal.

For a'particular measurement syste'tm (which may include radiochemical separation):

4.66 s L LD _ _ _ _ _ _ _ _ __ _b _ _ _ _ _ _ _

E

V

2.22 x 106

Y

exp (-AMt) where:

LLD is.the "a priori" lower limit of detection as defined above (as microcurie 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 midpoint of sample collection and time of counting' (for plant effluents, not environmental samples).

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

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

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

For a more complete discussion of..the.LLD, and other detection-limits; see the following: h D an oh d l (1) HASL Procedures Manual, HASL-300 (revised annually).

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

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

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

S023-ODCM

- 2-3 Revision 26 12-20-93 S02 3 -ODCM

I I TABLE 2-1 (Continued)

TABLE NOTATION

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

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

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

(ii)Sampling shall also be performed on the affected unit and plant vent stack at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown,' startup, or a THERMAL POWER'change exceeding 15 percent of RATED THERMAL POWER in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. This requirement does not apply if: (1)analysis shows that the DOSE EQUIVALENT 1-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a.factor of 10. This requirement is not applicable to the South Yard Facility.

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

f. 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 in accordance with Specifications 2.1, 2.2, 2.3.

g. The principal gamma emitters'for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.

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

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

S023-ODCM 2-4 Revision 33 05-03-99 S023 -ODCM

2.0 GASEOUS EFFLUENTS (Continued) 2.2 DOSE - NOBLE GASES SPECIFICATION 2.2.1 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site (see' Figure 2-2) shall be limited to the. following:

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

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

. radiation..

APPLICABILITY: At all times ACTION:

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

SURVEILLANCE REQUIREMENTS-. -

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

S023-ODCM 2-5 Revision 30 05-28-97 S02 3 -ODCM

I' 2.0 GASEOUS EFFLUENTS (Continued) 2.3 DOSE - RADIOTODINES. RADIOACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM SPECIFICATION 2.3.1 The dose to an individual from tritium, radioiodines and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the Site (see Figure 2-2) shall be limited to the following:

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

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

APPLICABILITY: At all times ACTION:

a. With the calculated dose from the release of tritium, radioiodines, and radioactive materials in particulate form, with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 2.3.1.

SURVEILLANCE REOUIREMENTS

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

S023-ODCM 2-6 Revision 32 02-25-99 S023-ODCM

S. 11 2.0 GASEOUS EFFLUENTS (Continued) 2.4 GASEOUS RADWASTE TREATMENT SPECIFICATION 2.4.1 -,The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be operable. The appropriate portions of the-GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce:radioactive materials in gaseous waste prior to their discharge when,"the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure 2-2), when averaged over.31:days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of theVENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce.radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see'Figure 2-2) when averaged over 31 days-would exceed 0.3 mrem to any'organ.*

APPLICABILITY: At all times -

ACTION:

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

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

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

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

SURVEILLANCE REQUIREMENTS

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

Ihese doses are per reactor unit.

S023-ODCM 2-7 Revision 30 05-28-97 S023-ODCM

JII 2.0 GASEOUS EFFLUENTS (Continued) 2.4 GASEOUS RADWASTE TREATMENT (Continued)

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

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

2.5 DELETED, moved to Section 3.

S023-ODCM 2-8 Revision 22 08-02-90 S02 3 -ODCM

tliii

fgit

a. (OIiXW I# T4 IAIS?

J vi atM LaI::i TI; "Mi gaAn. St CTIM~t

4. muse t*md4I iVAMoAsyN SZA,..aT ML&Ul flh KhiW iif 51 Mit§sn

/-

I I - .II

/

X I.

SAN ONOFRE

- NUCLEAR GENERATING STATION-Units 2 & 3 SITE BOUNDARY FOR GASEOUS EFFLUENTS POOR QUALITY DOCUMENT I BEST AVA;LABLE COPY gc.w^ ze.

Figure 2-2 S023-ODCM 2-9 Revision 26 12-20-93

AI 2.0 GASEOUS EFFLUENTS (Continued) 2.6 Methods of Calculation for Gaseous Effluent Monitor Setooints Administrative values are used to reduce each setpoint to account for the potential activity released simultaneously from the following release points:

PYS = Plant Vent Stack CAE = Condenser Air Ejector CP = Containment Purge SY = South Yard WG = Waste Gas Ul = Unit 1 Airborne Release The sum of the administrative values is limited to 1.0 to ensure that the total concentration from all release points on site to the environment will not result in a release exceeding the limits of Specification 2.1.1. The sum total of all these administrative values for the site shall be less than or equal to 1.0.

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

2.6.1 PLANT VENT STACK - 2/3RT-7808, 2RT-7865-1, 3RT-7865-1 For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor.

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

0.38 (2120 cf (500 mrem/yr)(106 mi/cc) (2-1)

C\ m /sec (flow rate, cfm)(/Q, sec/mi)[ ( Ki pCi/M3 ( Ctot Skin The concentration at the detector corresponding to a 3000 mrem/yr skin dose rate at the exclusion area boundary is determined by:

0.38 12120 3cfm (3000 mrem/yr)(10 6m3/cc) (2-2)

(flow ratecfm)(X/Qsec/m3)[E MO yCi/n pLi Cal S023-ODCM 2-10 Revision 31 02-27-98 S02 3 -ODCM

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

Cdet= the instantaneous concentration at the detector, pCi/cc 0.38 : an administrative value used to account for potential activity from other gaseous release pathways.

K, =.,total body dose conversion factor from Table 2'4 for the jth gamma emitting noble gas, Imrem/yr per pCi/mn L,= skin Dose Conversion Factor from Table'2-4 for the i'd noble gas, mrem/yr per pCi/m3 Mt = air Dose Conversion Factor from Table 2-4 for the it'noble gas, mrem/yr per pCi/m3 1.1 = conversion factor to convert gamma air dose to

, skin dose C, = concentration of the it'noble gas as determined by sample analysis, pCi/cc Ctot= total concentration of noble gases as rF'determined by sample analysis, uCi/cc =EC flow rate .,=:total plant vent stack flow rate, cfm,

~typically 164,000 cfm 2120 . -conversion constant, cfm per m 3/sec 500 mrem/yr = jtotal body dose rate limit, as specified by Specification 2.1.1.a 3000 mrem/yr = skin dose rate limit as specified by Specification 2.1.1.a X/Q = historical annual average dispersion factor for any landward sector, sec/m 3

= 4.8E-6 sec/m3 S023-ODCM 2-11 Revision 31 02-27-98 S023-ODCM

II 2.0 GASEOUS EFFLUENTS (Continued) 2.6.1.1 Maximum Permissible Alarm Setpoint for 2/3RT-7808, 2RT-7865-1 and 3RT-7865-1 The smaller of the values of Cdt from equations (2-1) and (2-2) shall be used to determine the maximum permissible monitor alarm setpoint.

The maximum release rate (pCi/sec) for Plant Vent Stack Monitors is determined by converting the concentration at the detector, Cdet (pCi/cc) to an equivalent release rate in pCi/sec. as follows:

(Cdet; pCi/cc)(flow rate, cfm)(28320) (2-4)

Am,- =

(S)(60) where:

A.l = maximum permissible release rate, pCi/sec Cdet = smaller of the values of Cdet determined in equations (2-1) and (2-2).

flow rate = plant vent stack flow rate (cfm) used in equations (2-1) and (2-2) 28320 = conversion from ft3 to cc 60 = conversion from minutes to seconds S = correction factor to compensate for the split flow between Unit 2 and Unit 3 Plant Vent Stacks, typically 2 for split stack monitoring and 1 for combined stack monitoring The release rate setpoint shall not be set greater than the maximum release rate determined above, when the monitor is being used to meet the requirements of Specification 2.1.1.

S023-ODCM 2-12 Revision 34 11-09-99 S02 3 -ODCM

2.0 GASEOUS EFFLUENTS (Continued) 2.6.2 CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-1, 3RT-7818 or 3RT-7870-1 2.6.2.1 2RT-7818 and 3RT-7818 Condenser Air Ejector Monitors For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous .effluent flow, rate and the meteorological dispersion factor. 7' The concentration at the detector corresponding to a total body dose rate of 500 mrem/yr at the exclusion area boundary is determined by-using:,

Total Body (0.1)(0.5)(2120 in m ) 500 mrem/yr)(r mi/cc) (2-5)

Cdet low rate, cfm) (/Q, sec/m3)Iz (Ki, mri/yr l( C1 '11 I.I~ pCi/rn 3 )I OJ.

The concentrati6onat the detector corresponding to a 3000 mrem/yr skin dose rate at the exclusion area boundary is determined by using:

Skin where: 0.1 = an administrative value used to account for potential activity from other gaseous release pathways.

0.5 = an administrative value used to account for releases from both SONGS 2 and SONGS 3 condenser air ejectors simultaneously.

Other parameters are specified in 2.6.1.1 and 2.6.2.2 above.

(2-6)

(0-1)(0.5)(2120 cfm ( 3000 mrem/yr) (10-6 M3/cc)

I. n 3/secJ Cdet =

(Flow rate, cfm) (X/Q. sec/m 3)lI (Li + 1. 1M, mrem/yr pCi/M 3

) Cit S023-ODCM

,- 2-13 Revision 26 12-20-93 S023 -ODCM

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

The smaller of the values Cde, from equations (2-5) or (2-6) is to be used in determining the maximum permissible monitor alarm setpoint (cpm), as follows:

The maximum permissible' alarm setting (cpm) is determined by using the calibration constant for the corresponding Condenser Evacuation System Monitor given in Table 2-3. The maximum permissible alarm setpoint is the cpm value corresponding to the concentration, Cd.t, [smaller value from equation (2-5) or (2-6)].

The calibration constant used is based on Kr-85 or on Xe-133, whichever yields a lower detection efficiency (higher value in terms of pCi/cc/cpm). The alarm setpoint will not be set greater than the maximum permissible alarm setting determined above.

2.6.2.2 2RT-7870-1 and 3RT-7870-1 Wide Range Gas Monitors The maximum release rate (pCi/sec) for Wide Range Gas Monitor is determined by converting the concentration at the detector, Cdt (fCi/cc), to an equivalent release rate in uCi/sec.

A.. = (Cdet, PCi/cc) (flow rate, cc/sec) (2-7) where:

=-maximum permissible release rate, uCi/sec Cdet smaller value of Cdt, as obtained from equations (2-5) and (2-6) flow rate flow rate of the condenser air ejector, cc/sec

= 4.719E5 cc/sec (conservatively assumed as design flow rate)

S023-ODCM 2-14 Revision 31 02-27-98 S02 3 -ODCM

2.0 GASEOUS EFFLUENTS (Continued) 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865-1, 3RT-7865-1 For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion

- factor. -

NOTE: 2(3)RT-7865 is not designed to monitor main purge.

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

Total Body (2-8)

(0.38)(P 2)(2120 cfm)1 (500 mrem/yr) (106 mi/cc)

)(C JI 3~~ - .

Cdetz =

mrem/yr (Flow rate, cfm) (/Q, sec/mi)[z1 (Ki, pCi /m3 (2-9)

Cdet3 The concentration at the detector corresponding to a 3000 mrem/yr skin dose rate at the exclusion area boundary is determined by using:

i- ~. ,- . . ..

.)Kn1 (2-10)

(0.38) (Pz)( 2120 cfMl (3000 mnrem/yr) (10-6 M3ICC)

Cdet2 =

(Flow rate, cfm) (X/Q, sec/m 3) + 1.1M1, mrem/yr (C)i1 E (Li pCi/M 3 Ctot 5023-ODCM I 15 Revision 34 11-09-99 S02 3 -ODCM

I I 2.0 GASEOUS EFFLUENTS (Continued) 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865-1, 3RT-7865-1 (Continued)

(0.38)(P 3)(2120 3 (3000 mrem/yr) (10-6 m3/cc) 3 ~ m 3/sec, Cdet3 =

Ct (Flow rate, cfm)(X/Q. Sec/m 3)li (Li + 1.1Mi, mrem/yr pCi/m 3 Cto where:

Cdet2 = instantaneous concentration of the Unit 2 detector, pCi/cc.

Cd.t3 = instantaneous concentration of the Unit 3 detector, pCi/cc.

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

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

Flow rate = observed maximum flowrate in cfm from the unit specific monitor 7828.

Default values will be the following conservative measured flows:

= 50,000 cfm main purge (2(3)RT-7828 only]

= 3.000 cfm mini-purge (The above values replace the smaller design flowrates.)

Other parameters are as specified in 2.6.1.1 above. The smaller of the values of maximum permissible Cdet2 from equation (2-8) or (2-10) and Cdet 3 from equations (2-9) or (2-11) is to be used in determining the maximum permissible monitor alarm setpoints.

S023-ODCM 2-16 Revision 28 12-21-95 S02 3 -ODCM

2.0 GASEOUS EFFLUENTS (Continued) 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865-1, 3RT-7865-1 (Continued)

M. a. s; er ;

2.6.3.1 'T Maximum Permi ssi bl e Al a'rm Setti nq for 2(3)RT-7865-1 The maximum permissible alarm setting for the Wide Range Gas Monitor expressed as a maximum release rate (pCi/sec) is determined by converting the concentration at the detector, Cdt, (pCi/cc),to an equivalent release rate in pCi/sec.

= (Cd,,,'pCi/cc) '(flow rate, cc/sec) (2-7) where:

A.x = maximum permissible release rate, pCi/sec Cdet = smaller value of Cd,t, as obtained from equation (2-8, 2-10) for Unit 2 or (2-9, 2-11) for Unit 3.

flow rate = flow rate, cc/sec

= 1.416E6 cc/sec for mini-purge.

= 2.360E7 cc/sec for-main purge [2(3)RT-7828 only].

.2 Maximum Permissible Alarm Setting (RT-7828)

The maximum permissible alarm setting 'for RT-7828 is in pCi/cc and is the smaller of the values of Cdet (pCi/cc) from equations (2-8) and (2-10).for Unit 2 or equations (2-9) and (2-11) for Unit 3. ' '

I! I~

I , I Ir'.

S023-ODCM 2-17 Revision 31 02-27-98 S023-ODCM

I I 2.0 GASEOUS EFFLUENTS (Continued) 2.6.4 WASTE GAS HEADER - 3RT-7865-1, 2/3RT-7808 For the purpose of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological. dispersion factor. Since the waste gas header discharges to the plant vent stack, either 3RT-7865-1 or 2/3RT-7808 may be used to monitor waste gas header releases.

The concentration at the detector corresponding to a total body dose rate of 500 mremfyr or a skin dose rate of 3000 mrem/yr at the exclusion area boundary is determined by using equations (2-1) or (2-2) with sample concentration (C1) and (C,,,) being obtained from the waste gas decay tank to be released.

2.6.4.1 Maximum Permissible Alarm SetDoint for 3RT-7865-1 and 2/3RT-7808 The smaller of the values of Cdt'from equations (2-1) and (2-2) shall be used to determine the maximum permissible monitor alarm setpoint.

The maximum release rate (pCi/sec) for Plant Vent Stack Monitors is determined by converting the concentration at the detector, Cdet (PCi/cc) to an equivalent release rate in pCi/sec, as follows:

A (Cdet, pCi/cc)(flow rate, cfm)(28320) (2-4) max (S)(60) where:

A. = maximum permissible release rate, pCi/sec Cde = smaller of the values of Cdt determined in equations (2-1) and (2-2) flow rate = plant vent stack flow rate (cfm) used in equations (2-1) and (2-2) 28320 = conversion from ft 3 to cc 60 = conversion from minutes to seconds S = correction factor for 3RT-7865-1 viewing only half the total plant vent stack flow, typically 2 for 3RT-7865-1 and 1 for 2/3RT-7808.

S023-ODCM 2-18 Revision 34 11-09-99 S02 3 -ODCM

2.0 GASEOUS EFFLUENTS (Continued) 2.6.4 WASTE GAS HEADER - 3RT-7865-1, 2/3RT-7808 (Continued) 2.6.4.2 A release from.the waste gas header is not possible if:

(EiCI)(LI)>Cdet .(2-12) where:

Ci = total gamma activity (MCi/cc) of the waste gas holdup tank to be released, as determined from the pre-release sample analysis f = waste gas header effluent flow rate, cfm F = plant vent-stack flowrate (cfm) used in equations (2-1) and (2-2)

Cdet = smaller of the values of Cdt determined in equations'(2-1) and (2-2) with C1 being obtained from the waste gas holdup tank to be released If a release is not possible, adjust the waste gas header flow by determining the maximum permissible waste gas header effluent.flow rate corresponding to the Plant Vent Stack Monitor setpoint in accordance with the following:

(0.-9) (Cde) (F) (2-13)

.. SzC where:

f = waste gas header effluent flow rate (cfm)

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

.Cdet = smallerof the value of Cdt from equation (2-1) or (2-2)

,C,= total gamma activity (pCi/cc) of the waste gas holdup' tank to-be released, as determined from the pre-release sample analysis.

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

S023-ODCM 2-19 Revision 34 11-09-99 S023 -ODCM

I I 2.0 GASEOUS EFFLUENTS (Continued) 2.6.5 SOUTH YARD FACILITY (SYF) - SYFRT7904, SYFRT7905 2.6.5.1 SYFRT7904 - South Yard Facility Work Area Monitor, SYFRT7905 - South Yard Facility Decontamination Area Monitor For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for the particulate monitor is based on the airborne effluent flow rate and the meteorological dispersion factor.

Organ Dose Rate The concentration at the detector corresponding to a 1500 mrem/yr organ dose rate at the exclusion boundary is determined by:

(RF)(0.5)(0.1) 2120 cM) (1500 mrem/yr)(10o6 m3/cc) (2-14)

(Flow rate, cfm)(/Q, sec/m 3)[ (Pik' pCr/M3 ) Ct where:

Cdet = the instantaneous concentration at the detector, pCi/cc 0.5 = an administrative value used to account for releases from both SYF pathways simultaneously 0.1 = an administrative value used to account for potential activity from other site airborne release pathways Pik = organ dose conversion factor from Table 2-5 for the 1 th gamma emitting particulate isotope, mrem/yr per pCi/mi C, = concentration of the it'particulate isotope as determined by sample analysis or source term evaluation, pCi/cc RF = an administrative value used to account for isotopes in the source term that are not detectable.

S023-ODCM 2-20 Revision 35 02-29-00 S023-ODCM

2.0 GASEOUS EFFLUENTS (Continued) 2.6.5 SOUTH YARD FACILITY (SYF) - SYFRT7904, SYFRT7905 (Continued)

Ctot

= total concentration of particulate isotopes as determined by sample analysis or source term evaluation, pCi/cc = ,C Flow Rate = SYF Work Area Vent cfm (typically 17,500 cfm)

SYF Decontamination Monitor (typically 5,700 cfm) 2120 - conversion constant, cfm per m3/sec 1500 mrem/yr = organ dose rate limit, as specified by Specification 2.1.1.b X/Q historical annual average dispersion factor for any landward sector, 8.OE-5 sec/nf

(

Reference:

Memo dated 12/11/94 from E. M.

Goldin to P. K. Chang, Subject, wSouth Yard Facility Dispersion and Deposition Factors for Potential Normal Gaseous Effluent Releases; Determination of Compliance with, IOCFR5O. Appendix I")

S023-ODCM 2-21 Revision 36 02-28-01 S02 3 -ODCM

I I I

Table 2-3(a)

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

MONITOR Kr-85 Xe-133 2RT-7818A 4.27E-8 6.86E-8 3RT-7818A 3.73E-8 5.12E-8 (a)This table provides typical (+/-20%) calibration constants for the gaseous effluent radiation monitors.

S023-ODCM 2-22 Revision 34 11-09-99 S02 3 -ODCM

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

2.7.1 FOR NOBLE GASES:

DT5 =i (

I ffm Q Q (2-19)

D5 DS

= z. l(L + IM (X/Q) Q] )

where:

DIB = total body dose rate in unrestricted areas due to radioactive materials released in gaseous weffluents, mrem/yr D = skin dose rate in unrestricted areas due to radioactive materials released in gaseous

effluents,- mrem/yr K, = the total body dose factor due to gamma emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrem/yr per pCi/m3 Li = skin dose factor due to the beta emissions from Table 2-4-for each identified noble gas radionuclide, i, in mrem/yr per pCi/o3 M; = - air'dose factor due to gamma emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrad/yr per pci/m3 (conversion constant of 1.1 mrem/mrad converts air

dose to'skin-dose.)

= measured or calculated release rate of

radjonuclide, i, for'either continuous or batch

-gaseous'effluents, in pCi/sec (X/Q) = Maximum annual average atmospheric dispersion factor for any landward sector or distance at or beyond the unrestricted area boundary.

= 4.8E-6 sec/m3 for Units 2 and 3

= 8.OE-5 sec/m3 for South Yard Facility S023-ODCM 2-23 Revision 31 02-27-98 S02 3 -ODCM

I I 2.0 GASEOUS EFFLUEHTS (Continued) 2.7.2 FOR ALL RADIOIODINES, TRITIUM AND FOR ALL RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN EIGHT DAYS:

(2-20)

Do = zi k*(Pi Wk) 4i where:

organ dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, mremi/yr Qa measured or calculated release rate of radionuclide, i, for either continuous or batch gaseous effluents, pCi/sec Pj = dose parameter for radionuclide, i, for pathway, k, from Table 2-5 for the inhalation pathway in mrem/yr per pCi/m3 . The dose factors are based on the critical individual organ and the child age group.

k = highest calculated annuailaverage dispersion (X7h) or deposition (T7M) factor for estimating the dose to an individual at or beyond the unrestricted area boundary for pathway k.

(X7M), 4.8E-6 sec/M 3 for Units 2/3 for the inhalation pathway. The location is the unrestricted area in the NW sector.

(XX7), 8.OE-5 sec/m3 for South Yard Facility for the inhalation pathway. The location is the unrestricted area in the E sector.

(I7i .4.3E-8 m- 2 for Units 2/3 for the food and ground plane pathways. The location is the unrestricted area in the E sector.

(D7Y). 8.OE-7 m-2 for South Yard Facility for the food and ground plane pathways. The location is the unrestricted area in the E sector.

S023-ODCM 2-24 Revision 31 02-27-98 S023-ODCM

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

2.8.1.1 For historical meteorology:

D = 3.17x1O- 8 En M; [(X7/)Q] (2-21)

D = 3.17x108 E1 N1 jo/Q i] (2-22) where:

Dy total gammaa air dose from gaseous effluents, mrad D= total beta air dose from gaseous effluents, mrad 3.17x108 = inverse'seconds per year M= air dose factor due to gamma emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrad/yr per -pCi/ 3 N, = air dose'due to beta emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrad/yr per

- ' pCi/r 3 .

(X7Q) = Maximum annual average atmospheric dispersion factor for any'landward sector or distance at or beyond the unrestricted area boundary.

= 4.8E-6 .sec/m 3 for Units-2and 3

8.OE-5'isec/m3 for South Yard Facility Q= amount of noble gas radionuclide, i, released in gaseous effluents, pCi.

S023-ODCM

--. 2-25 Revision 30 05-28-97 S02 3 -ODCM

II 2.0 GASEOUS EFFLUENTS (Continued) 2.8.1.2 For meteoroloy-v concurrent with release:

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

Do = 1.14x1O E1 M1 i J(tj (X/Q)jO Q )j (2-23)

. (2-24)

De = 1.14xlO' 4 E1 NJ J(Atj (X/Q)ie Q(-)

where:

De= total gamma air dose from gaseous effluents in sector e, mrad Doe = total beta air dose from gaseous effluents in sector e, mrad 1.14x10' = inverse hours/year M= air dose factor due to gamma emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrad/yr per yCi/mi3 N1 = air dose factor due to beta emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrad/yr per pCi/m3 At= length of the jth time period over which (X/O)j, and %, are averaged for gaseous releases in hours (X/Q)je = atmospheric dispersion factor for time period Ati at exclusion boundary location in landward sector 3 determined by concurrent meteorology, sec/m 3 ij= average release rate of radionuclide, i, in gaseous effluents during time period, at;,

pCi/sec S023-ODCM 2-26 Revision 26 12-21-95 S023-ODCM

2.0 GASEOUS EFFLUENTS (Continued) 2.8.2 DOSEFROM TRITIUM. RADIOIODINES AND RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN 8 DAYS IN GASEOUS EFFLUENTS The dose to-an individual from tritium, radioiodines and radioactive materials in particulate form with half lives greater than-eight days in gaseous effluents released to unrestricted areas is calculated using the following expressions:

2.8.2.1 For historical meteorology:

(2-25)

D = 3.17x10, a, [ tjkWkpi]

where:

Do = total projected dose from gaseous effluents to an individual, mrem 3.17x10 28 year/second Q = amount-of each radionuclide, i, (tritium, radioiodine, radioactive material in particulate form with half lives greater than eight days),

released in gaseous effluents, pCi

&kRikWk sum of all pathways, k, for radionuclide, i, of the RI W product, in mrem/yr per pCi/sec. The ZkRAkWk value for each radionuclide, 1, is given in Table 2-6 for Units 2/3 and Table 2-17 for South Yard Facility. The value given is the maximum EkRikWk for all locations and is based on the most

-restrictive age groups.

RI dose factor for each identified radionuclide, i, for pathway k, (for the inhalation pathway in mrem/yr per pCi/m 3 and for the food and ground plane pathways in m2-mrem/yr per pCi/sec), at the controlling location. The Rik's for each controlling location for each age group are given in Tables 2-7thru 2-16 for Units 2/3 and Tables 2-18:through 2-21 for South Yard Facility.

Data in these.tables are derived using the NRC

-7code, PARTS. (See the annual update of revised R1 parameters based on changes in the Land Use Census provided by Corporate Health Physics and Environmental.)

S023-ODCM 2-27 Revision 30 05-28-97 S023-ODCM

I I 2.0 GASEOUS EFFLUENTS (Continued) 2.8.2.1 For historical meteorologv: (Continued)

Wk = annual average dispersion (X/Q)or deposition (D7Q) factor for estimating the dose to an individual at the controlling location for pathway k.

= (X/Q)for the inhalation pathway in sec/M 3.

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

= (D/Q)for the food and ground plane pathways in mr2.

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

2.8.2.2 For meteorology concurrent with releases:

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

1mn (-6 D = 1.14 x lo- 1Z (At)(R)(W)II) (2-26) ij'k i ilkA jkekO )

where:

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

at;= length of the jth period over which Wike and Qj are averaged for gaseous released, hours Q,3 = average release rate of radionuclide, i, in gaseous effluents during time period atj, pCi/sec Rko = dose factor for each identified radionuclide i, for pathway k for sector e (for the inhalation pathway in mrem/yr per pCi/m 3 and for the food and ground plane pathways in m2 mrem/yr per pCi/sec) at the controlling location. A listing of Rik for the controlling locations in each landward sector for each group is given in Tables 2-7 thru 2-16 for Units 2/3 and Tables 2-18 through 2-21 for South Yard Facility. The e is determined by the concurrent meteorology.

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

= (X/O)for the inhalation pathway, sec/M 3

= (D/Q)for the food and ground plane pathways, m2 S023-ODCM 2-28 Revision 30 05-28-97 S023-ODCM

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

- Source: USNRC Reg. Guide 1.109. Table B-1 I . -I S023-ODCM

-.~2-29 Revision 21 02-15-90 S02 3 -ODCM

I I TABLE 2-5 DOSE PARAMETER Pk*

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

H- 3 1.1E+3 I -131 1.6E+7 Cr-51 1.7E+4 1 -132 1.9E+5 Mn-54 1.6E+6 I -133 3.8E+6 Co-57 5.1E+5 1 -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 S023-ODCM 2-30 Revision 23 02-28-91 S02 3 -ODCM

- ',TABLE 2-6 COHTROLLING LOCATION FACTORS

.k k . ..,,

-Radionuclide ' - ,1 e kRpWkrCi/s; Use:

H -3 3.OOE-3 R: Outage Workers Cr-51. '1.23E-1 R: Outage Workers Mn-54 2.71E+1 R: Outage Workers -

Co-57 6.91E+O R: -Outage Workers K Co-58 9.18E+O R: Outage Workers Co-60 3.71E+2 R: Outage Workers' Sr-89 I 4.65E+1 Q: 'SC Ranch,(No. Res.)

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

Zr-95 Nb-95 1.03E+1 R: Outage Workers' IP 1.07E+1 E: Deer Consumer/Hunter Ru-103 1.69E+1 7. E: -Deer Consumer/Hunter Te-129m 8.35E+O E: Deer Consumer/Hunter Cs-134 1.13EI2 R: -Outage Workers Cs-136 2.84E+O R: Outage Workers Cs-137 1.67E+2 R: .Outage Workers Ba-140 5.13E+O R: Outage Workers Ce-141 1.66E+O R: Outage Workers Ce-144 3.29E+1 Q: Outage Workers 1 -131 3.73E+1 Outage Workers I -132 4.64E-1 R- Outage Workers 1 -133 9.29E40 R: Outage Workers I -134 1.26E-1 R: -Outage Workers I -135 1.93E+O R: 'Outage Workers UN-ID 1.49E+1 R: Outage Workers Footnote: These values to be uied:in manual calculations are the'maximum EkRIAWk for all locations based on the most restrictive age group.

S023-ODCM 2-31 Revision 38 02-28-03 S02 3 -ODCM

V TABLE 2-7 DOSE PARAMETER R. FOR SECTOR P Page 1 of 2 Pathway - Cotton Point Estates with Garden Distance = 2.8 miles X/Q -. OE-7 seclm 3 D/Q = 3.OE-10 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 6.5E+2 1.1E+3 4.OE+3 1.3E+3 2.6E+3 1.3E+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.IE+5 5.8E+8 5.9E+5 6.6E+8 3.7E+5 6.3E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 7.5E+B 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+1O 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.IE+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.lE+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 7.0E+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 1.5E48 1.7E+5 3.7E+8 1.9E+5 3.2E+8 1.5E+5 3.2E+8 Cs-137 6.IE+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 2.0E46 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.IE+10 I -131 1.5E+7 1.7E+7 1.6E+7 4.BE+10 1.5E+7 3.1E+10 1.2E+7 3.8E+10 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E46 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 1 -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 7.0E+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/vi/rn 3 Food & Ground Pathway, units =(p)(mrem/sr)

S023-ODCM 2-32 Revision 32 02-25-99 S023-ODCM

TABLE 2-7 DOSE PARAMETER RI FOR SECTOR P Page 2 of 2 Pathway = 51 Area Beach Check-In Distance = 1.4 miles X/Q = 6.9E-07 sec/m 3 2 D/Q = 3.3E-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 -O- -O- -O- O -O- -O- 3.2E+2 -O-Cr-51 -O- -- -O- -O- 3.7E+3 1.2E+6 Mn-54 -O- -O- : -O- -O- 3.6E+5 3.6E+8 Co -O- -O- 9.5E+4 8.8E+7 Co-58 --

O- -O- -O- . -O- -O- 2.4E+5 9.8E+7 Co-60 --O- -- -- -- -O- 1.5E+6 5.5E+9 Sr-89 -O- -O- ; .-.- -O- -O- 3.6E+5 5.5E+3 Sr-90 -O- -O- -O- -O- -O- 2.5E+7 Zr-95, -O- -O- -O- -O- -O- 4.5E+5 6.5E+7 Nb-95 -O- -O- -O- 1.3E+5 3.5E+7 Ru-103 -O- - -- -O- --O -O- -O- 1.3E+5 2.8E+7

Te-129m -O - -- -O- -O- 3.OE+5 5.1E+6 Cs-134 -O- -O - -O- 2.2E+5 1.8E+9 Cs-136 -O- -O- : - 0- -O- -O- 3.8E+4 3.9E+7 Cs-137 O-- -O- -- 0- -O- 1.6E+5 2.6E+9 Ba-140 -O- -O- -O- '-O- -O- -O- 3.3E+5, 5.3E+6 Ce-141 -O- 0- -O- -O- 9.3E+4 3.5E+6 Ce-144 -O- O- -O- -O- 2.OE+6 1.8E+7 1 -131 -O- -- -o- O- -O- -O- 3.1E+6 4.4E+6 1 -132 -O- -O- -O- .- 0 -O- -O- 2.9E+4- 3.2E+5 1 -133 : -O- 5.5E+5 6.3E+5 1 -134 -O- -O- - -O- - 7.7E+3 1.2E+5 I -135 -O- -O- -0 - 1.2E+5 *6.5E+5 UN-ID -O- -O- .- -'O- -0 2.2E+5 1.9E+8 Inhalation Pathway, units = m Food & Ground Pathway, units = (nf) (mrem/vr) pCi/sec S023-ODCM 2-33 Revision 30 05-28-97 S02 3 -ODCM

I I TABLE 2-8 DOSE PARAMETER R1 FOR SECTOR Q Paqe 1 of 6 IF Pathway = San Onofre Mobile Homes Distance = 1.4 miles X/Q = 6.9E-7 sec/m 3 D/Q = 3.3E-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 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 1.4E49 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+S 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 1.8E46 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 l.OE+10 8.5E+5 1.OE+10 6.2E+5 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 7.8E+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 3.8ET6 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 = p/ r Food & Ground Pathway, units = (m)(mrem/vr)

Pathway.pCi/sec S023-ODCM 2-34 Revision 30 05-28-97 S02 3 -ODCM

,TABLE 2-8

'DOSE PARAMETER R. FOR SECTOR Q Page 2 of 6 IF Pathway = S. C. Resident With Garden Distance = 4.1 miles 2 X/D/Q1E ec/ . D/Q = 4.7E-10 Mn 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+31 4.OE+3 1.3E+3 2.6E+3 1.3E+3 2.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4, 1.E+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 7.8E+5 3.8E+8 l.lE+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+1O 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+B 1.4E+12 -1.lE+8 8.3E+11 9.9E+7 6.7E+11 Zr-95 1.8E+6 2.5E+8 -2.2E+6 Il.lE+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.lE+8 6.6E+5 5.OE+8 7.BE+5' -6.BE+8 5.OE+5 6.6E+8 Te-129m 1.7E+6 2.OE+7 1.8E+6 2.9E49 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.IE+5 1.OE+10 9.1E+5 3.5E+1O *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 :

-pC~i/rn

=( 2)16iemn/vr)

Food & Ground Pathway, units pCi/sec

+-". I S023-ODCM

'2-35 Revision 32 02-25-99 S02 3 -ODCM

II TABLE 2-8 DOSE PARAMETER RI FOR SECTOR Q Page 3 of 6 IF Pathway = San Clemente Ranch (No Residents) Distance = 2.2 miles X/Q = 3.5E-7 sec/m3 D/Q = 1.5E-9 m-2 Infant Child Teen Adult Inhala-. Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.8E+3 2.4E+3 3.6E+2 1.9E+3 Cr-51 4.8E+6 7.4E+6 4.1E+3 8.1E+6 Mn-54 6.1E+8 B.3E*8 4.OE+5 1.ZE+9 Co-57 2.2E+8 2.9E+8 1.1E+5 3.4E+8 Co-58 3.3E+8 5.1E+8 2.6E+5 5.8E+8 Co-60 2.0E+9 3.0E+9 1.7E+6 8.8E+9 Sr-89 3.IE+10 1.2E+10 4.OE+5 7.2E+9 Sr-90 1.3E+12 7.7E+11 2.8E+7 5.8E+11 Zr-95 7.8E+8 1.1E+9 5.OE+5 9.8E+8 Nb-95 2.4E+8 3.5E+8 1.4E+5 3.5E+8 Ru-103 3.3E+8 4.5E+8 1.4E+5 4.1E+8 Te-129m 2.3E+9 1.4E+9 3.3E+5 9.5E+8 Cs-134 2.4E+10 1.5E+10 2.4E+5 1.1E+10 Cs-136 9.OE+7 5.7E+7 4.2E+4 7.9E+7 Cs-137 2.3E+10 1.3E+10 1.8E+5 1.1E+10 Ba-140 1.1E+8 6.8E+7 3.6E+5 5.9E+7 Ce-141 3.3E+8 4.1E+8 1.OE+5 3.2E+8 Ce-144 9.2E+9 1.2E+10 2.2E+6 9.OE+9 1 -131 4.1E+9 2.IE+9 3.4E+6 1.4E+9 I -132 6.OE-36 2.6E-36 3.3E+4 3.5E+5 1 -133 4.0E-11 1.7E-11 6.1E+5 7.OE+5 I -134 6.1E-37 2.7E-37 8.5E+3 1.3E+5 I -135 7.OE-35 3.1E-35 1.3E+5 7.2E+5 UN-ID 2.5E-9 1.7E+9 2.5E+5 1.3E+9 Inhalation Pathway, units = irt4r VCi/rnl Food & Ground Pathway, units = l(mrCie/sec S023-ODCM 2-36 Revision 32 02-25-99 S023-ODCM

TABLE 2-8 DOSE PARAMETERIR. FOR SECTOR Q Page 4of 6 Pathway - Outage Workers Distance = 0.7 miles X/Q = 2.OE-6 sec/m 3 D/Q = 1.1E-8 m-2 Infant Child Teen Adult Inhala- Food & Inhala-" Food!& Inhala- Food &- Inhala- Food'&

Radio- tion Ground tion;I Ground tion Ground tion - Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 - -O- -- 0- -- -O- -O-Cr-51 -O- -O- -O- -O- -O- ' Mn-54 -O- -O- O-Co-57 -0O - - -O0- -O- Co-60 -O0- -O- 00 -O-Sr-89 --O- - - -O- -O- -O-Sr-90 -O- -O- - - Zr-95 -O- O- - -

Nb-95 -O- -O- . -O- -0 Ru-103 -O- -O- _ -- Te-129m -O- -- - - -O- -O-- Cs-134 -O- - -- , Cs-136 -0 r -0 -0, -0 -0 _ _-0-_OO Cs-137- -0 -O-0 ,

Ba-140 O-- -O0 -O- 0- -O- -O-Ce-141 -O0- -O- -O - -O-Ce-144 -O- 0'- I -131 - - .o.-O- ' -O- -0. -- O-Is-132 1-144 7 -O-

. -_0_

- ---O-- : -O- I-131 Ia-133 --O-

-O-

-O- -O- ' _ -E oO- O--

I -135 ; -13

-I -- -O- -- J -0 - -O- -O-UN-ID J -O- -,O- O- _O_' --O-Inhalation Pathway, units = mrem/vr uCi /ml Food & Ground Pathway, unitse=Foyunits =(n (mremlr) -

S023-ODCM

.2-37 Revision 32 02-25-99 S023 -ODCM

I I C.

TABLE 2-8 DOSE PARAMETER RI FOR SECTOR Q Page 5 of 6 IF Pathway = San Mateo Pt Homes Distance = 2.7 miles X/Q = 2.6E-7 sec/m 3 D/Q = 1.OE-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 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E44 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 I.1E+6 3.8E+B 1.3E+6 3.BE+8 9.3E+5 3.BE+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.IE+7 1.0E+8 1.1E+8 9.9E+7 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.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.IE+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.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 7.8E+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/yr pCi/rm 2

Food & Ground Pathway, units _ (m ) (mrem/vr) pCi /sec S023-ODCM 2-38 Revision 36 02-28-01 S023-ODCM

TABLE 2-8 DOSE PARAMETER RI FOR SECTOR Q Page 6 of 6 Pathway = Rec Bldg Staff Distance-- 1.2 miles X/Q = 8.9E-7 sec/m 3 , D/Q = 4.4E-9 mn2 Infant Child Teen Adult Inhala- Food b Inhala- Food &V 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 - --- 0- ' 1.3E+3 O-Cr-51 '0- -O- -O- -O- -O- 1.4E+4 4.7E+6 Mn-54 -O- -O- ' -O- -O- 1.4E+6 1.4E+9 Co-57 -O- -O- ; --

0 O -O- -O- 3.7E+5 3.'4E+8 Co-58 -O- -O- -O- -O- -O- 9.3E+5 3.8E+8 Co-60 -O- -O- ,0

-;,,,- -O- -O- -6.OE+6 2.2E+10 Sr-89 -O- -- -O- - -O- -0_- 1.4E+6 Z.2E+4 Sr-90 ;-0 - -O- -O- -O- -O- -O- 9.9E+7 O-Zr-95 -O- -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- , - '5.OE+5 1.1E+8 Te-129m -O- -O- -O- -O- -O- ' 1.2E+6 2.OE+7 Cs-134, -- -O '0- -O- _ 8.5E+5 .6.8E+9 Cs-136 , - 0- -O- 1.5E+5 1.5E+8 tr Cs-137 t -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- 0 - -O0 4' 3.6E+5 1.4E+7 Ce-144 -O- -O- -O- -O- 7.8E+6 7.OE+7 I -131 . -O- ' 0 -O- -O- 1.2E+7- 1.7E+7 I -132 -O- -O- -'0- -O- -O- 1.1E+5 1.2E+6 I -133 -O- -O- - 'O- 2.2E+6 2.4E+6 I -134 -O- -O- -0 -O- --O 3.OE+4 4.5E+5 I -135 _-O- --- -O- '0 4.5E+5r ;2.5E+6 UN-ID -O- -O- -0 -O- -'- 8.6E+5 7.5E+8 Inhalation Pathway, units =

pCi/mr Food & Ground Pathway, uis= u (m rem lvr) "

si= (in 2)pCi/sec S023-ODCM

' 2-39 Revision 38 02-28-03 S02 3 -ODCM

I I TABLE 2-9 DOSE PARAMETER RI FOR SECTOR R Page 1 of 3 Pathway = San Onofre Mobile Homes Distance = 1.3 miles X/Q = 5.2E-7 sec/m 3 D/Q = 3.OE-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 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 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 1.0E+8 1.1E+8 9.9E+7 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.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 1.0E+6 6.8E+9 1.1E+6 6.8E+9 8.5E+5 6.8E+9 Cs-136 1.3E+5 1.5E+8 1.7E+5 1.5E+8 1.9E+5 1.5E+8 1.5E+5 1.5E+8 Cs-137 6.1E+5 1.0E+10 9.1E+5 1.OE+10 8.5E+5 1.OE+10 6.2E+5 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 7.8E+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 1 -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.iE+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 N-ID 6.5E+5 7.5E+8 1.E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 Inhalation Pathway, units =mrmt FC&i/rnM /

Food & Ground Pathway, units = (in)N(remn/r) pCi/sec S023-ODCM 2-40 Revision 30 05-28-97 S02 3 -ODCM

,TABLE 2-9

- DOSE PARAMETER RI FOR SECTOR R Page 2 of 3 Pathway = SaniClemente Ranch (No Residents) Distance = 2.3 miles X/Q = 2.1E-7 sec/m 3 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 -O- -O- -O- 3.8E+3 -O- 2.4E+3 3.6E+2 1.9E+3 Cr-51 -O- 5 '4.8E46 -O- 7.4E+6 4.IE+3 8.1E+6 Mn-54 -O- -O- -- :6.1E+B' -O- 8.3E+8' 4.OE+5 1.2E+9 Co-57 -O- 2.2E+8 -O- 2.9E+B 1.1E+5 3'.4E+8 Co-58 -O- 3.3E+8 -O- 5.'1E+8 2.6E+5 5.8E+8 Co-60 -O- -O- ,0-n 2.OE+9' -O- 3.0E+9: 1.'7E+6 8.8E+9 Sr-89 -O- -O- 3.1E+10 1.2E+10' 4.OE+5 7.2E+9 Sr-90 -O- -O- 1.3E+12 -O- 7.7E+11 2.8E+7 5;8E+l1 Zr-95 -O- -O- 7.8E+8 1.1E+9 5.OE+5 9.8E+8 Nb-95 -O- -O- 2.4E+8 -O- 3.5E+8 1.4E+5 3.5E+8 Ru-103 -O- -O- ; 3.3E+8 4.5E+8'- 1.'4E+5 4.1E+8 Te-129m -O- ' 2.3E+9. -- 1.4E+9 3.3E+5 9.5E+8 Cs-134 -O- -O- - 2.4E+10 1.5E+10 2.4E+5 1.lE+10 Cs-136 -O- -O- -O- 9.OE+7; 5.7E+7 4.2E+4 7.9E+7 Cs-137 -0 0 --

O 2.3E+10 1.3E+10 1.8E+5 1.lE+10 Ba-140 -O- -O- -O- . 1.1E+8 ' 6.BE+7 3.6E+5 5.9E+7 Ce-141 -O- -O' - 3.3E+8 -O- 4.1E+8 1.0E+5 3.2E+8 Ce-144 -O- -O- 9.2E+9 -- ' 1.2E+10 2.2E+6 9.OE+9 I -131 -O- 4.1E+9 2.lE+9 3.4E+6 1.4E+9 I -132 -O- -O- -O- - 6.OE-36 07 2.6E-36 3.3E+4 3.5E+5 I -133 -O- 0 - 4.0E-11 1.7E-11 6.1E+5 7.0E+5 I -134 -O- -0 -O- 6.1E-37 -O- 2.7E-37 8.5E+3 '1.3E+5 1 -135 -O- -O- 7.OE-35 -O- 3.1E-35 1.3E+5 7.2E+5 UN-ID -O- '0- 2.5E+9 -O- 1.7E+9 2.5E+5 1.3E+9 Inhalation Pathway, units -m 14m Food & Ground Pathway, units = fm2)(iremLyr) pCi/sec S023-ODCM 2-41 Revision 32 02-25-99 S02 3 -ODCM

I I I1 TABLE 2-9 DOSE PARAMETER R1 FOR SECTOR R Page 3 of 3 Pathway = Outage Workers Distance = 0.4 miles X/Q = 3.7E-6 sec/n 3 D/Q = 2.5E-8 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 4.1E+2 7.2E+2 8.1E+2 8.1E+2 Cr-51 8.2E+3 3.OE+6 1.1E+4 3.OE+6 1.3E+4 3.OE+6 9.2E+3 3.OE+6 Mn-54 6.4E+5 8.9E+8 1.OE+6 8.9E+8 1.3E+6 8.9E+B 9.OE+5 8.9E+8 Co-57 2.4E+5 2.2E+8 3.2E+5 2.2E+8 3.8E+5 2.2E+8 2.4E+5 2.2E+8 Co-58 5.OE+5 2.4E+8 7.1E+5 2.4E+8 8.6E+5 2.4E+8 5.9E+5 2.4E+8 Co-60 2.9E+6 1.4E+10 4.5E+6 1.4E+10 5.6E+6 1.4E+10 3.8E+6 1.4E+10 Sr-89 1.3E+6 1.4E+4 1.4E+6 1.4E+4 1.5E+6 1.4E+4 9.OE+5 1.4E+4 Sr-90 2.6E+7 6.5E+7 6.9E+7 6.3E+7 Zr-95 1.1E+6 1.6E+8 1.4E+6 1.6E+8 1.7E+6 1.6E+8 1.1E+6 1.6E+8 Nb-95 3.1E+5 8.7E+7 3.9E+5 8.7E+7 4.8E+5 8.7E+7 3.2E+5 8.7E+7 Ru-103 3.5E+5 7.OE+7 4.2E+5 7.OE+7 5.OE+5 7.OE+7 3.2E+5 7.OE+7 Te-129m 1.1E+6 1.3E+7 1.1E+6 1.3E+7 1.3E+6 1.3E+7 7.4E+5 1.3E+7 Cs-134 4.5E+5 4.4E+9 6.5E+5 4.4E+9 7.2E+5 4.4E+9 5.4E+5 4.4E+9 Cs-136 8.6E+4 9.6E+7 1.1E+5 9.6E+7 1.2E+5 9.6E+7 9.4E+4 9.6E+7 Cs-137 3.9E+5 6.6E+9 5.8E+5 6.6E+9 5.4E+5 6.6E+9 4.OE+5 6.6E+9 Ba-140 1.OE+6 1.3E+7 1.1E+6 1.3E+7 1.3E+6 1.3E+7 8.1E+5 1.3E+7 Ce-141 3.3E+5 8.7E+6 3.5E+5 8.7E+6 3.9E+5 8.7E+6 2.3E+5 8.7E+6 Ce-144 6.3E+6 4.5E+7 7.6E+6 4.5E+7 8.6E+6 4.5E+7 5.OE+6 4.5E+7 I -131 9.5E+6 1.1E+7 1.OE+7 1.1E+7 9.4E+6 1.1E+7 7.6E+6 1.1E+7 I -13Z 1.1E+5 7.9E+5 1.2E+5 7.9E+5 9.7E+4 7.9E+5 7.3E+4 7.9E+5 I -133 2.3E+6 1.6E+6 2.5E+6 1.6E+6 1.9E+6 1.6E+6 1.4E+6 1.6E+6 I -134 2.8E+4 2.9E+5 3.2E+4 2.9E+5 2.5E+4 2.9E+5 1.9E+4 2.9E+5 I -135 4.5E+5 1.6E+6 5.1E+5 1.6E+6 4.OE+5 1.6E+5 2.9E+5 1.6E+6 UN-ID 4.1E+5 4.8E+8 6.4E+5 4.8E+8 7.9E+5 4.8E+8 5.5E+5 4.8E+8 Inhalation Pathway, units = mrem/yr FCici/m3_

2 Food & Ground Pathway, units = (m) (mrem/vr) pCi/sec S023-ODCM 2-42 Revision 38 02-28-03 S023 -ODCM

TABLE 2-10 DOSE PARAMETER R, FOR SECTOR A Page 1 of 1 Pathway = Camp San Mateo. Distance = 3.6 miles X/Q = 7.2E-8 sec/.n3 D/Q = 4.1E-10 -' 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- 1.3E+3 -O-Cr-51 , -- -O- -O- 1.4E+4 '4.7E+6 Mn-54 -O- -O- -O- -O-- -O- 1.4E+6 1.4E+9 Co-57 -0 3.7E+5 3.4E+8 Co-58 -O- -- -O- ' -O- 9.3E+5 3.8E+8 Co-60 , -O- -O- -- 6.0E+6 2.2E+10 Sr-89 -O- -O- -O- '-0 -0 -O- 1.4E+6 2.2E+4 Sr-90 -O- -O- -O' -O- -O- 9.9E+7 Zr-95 - - , ' , -0 1.8E+6 2.5E+8 Nb-95 -O- -0 -' 'O -0 -O- -O- 5.OE+5, 1.4E+8 Ru-103 , -- ' --0 5.OE+5 1.IE+8 Te-129m -O- -0' -O- -O- 1.2E+6 2.OE+7 Cs-134 O- -0 -- -"- 8.5E+5 6.BE+9 Cs-136 - -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- 1.3E+6 2.1E+7 Ce-141' -O- -O- -O- , -_O- 3.6E+5 1.4E+7 Ce-144 -0 -O- -O- 7.8E+6 7.OE+7 1 -131 0- - -O- ' -O- 1.2E+7 1.7E+7 1 -132 -O- , ', -O- 1.1E+5 1.2E+6 I -133 -O- -O- - 2.2E+6 2.4E+6 I -134 - -O- ' -- -O- 3.OE+4 4.5E+5 I 435 -O 4.5E+5 2.5E+6 UN-ID -O- 8.6E+5 7.5E+8 Inhalation Pathway, units = mrem/yr pCi/rn -

2 Food & Ground Pathway. units = ( ) (mrem/vr) -

pCi/sec S023-ODCM 43 Revision 30 05-28-97 S02 3 -ODCM

I I TABLE 2-11 DOSE PARAMETER RI FOR SECTOR B Page 1 of 2 Pathway = Deer Consumer/Hunter Distance = 3.8 miles X/Q = 6.8E-8 sec/m 3 D/Q = 5.1E-10 mr2 Infant Child Teen Adult Inhala- Food h 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- 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 -O- 5.0E+4 1.OE+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 4.6E+6 8.OE+6 1.OE+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 -O- -O- 4.9E+7 -O- 2.6E+7 3.8E+4 3.1E+7 Sr-90 -O- -O- 1.0E+9 8.OE+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 4.8E+4 2.OE+8 Nb-95 -O- 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 -O- 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.1E+6 4.2E+6 4.OE+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.OE+8 Ba-140 -O- 5.0E+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 -O- 3.1E+3 3.4E+4 1 -133 -O- -O- -O- 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 -O- 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = mremvr FCi/rn-T Food & Ground Pathway, units = (mi)(mr/secr)

S023-ODCM 2-44 Revision 30 05-28-97 S02 3 -ODCM

- TABLE 2-11 DOSE PARAMETER R1 FOR SECTOR B Page 2 of 2 Pathway = Sanitary Landfill: Distance = 2.1 miles X/Q = 1.3E-7 sec/m 3 D/Q = 1.1E-9 m2 ;

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

Radio- -tion , Ground tion - Ground tion Ground tion tround Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 -- -o 0 -- -- - 2.9E+2 Cr-51 -- - -0 O- -3.3E+3 1.1E+6

-Mn-54 -O- --- -O- -O- 3.2E+5, 3.2E+8 Co-57 -O- -O- -O- -O- - 8.4E+4 7.8E+7 Co-58 -O- -O- -O- -O- 2.1E+5 8.7E+7 Co-60 -O- -O- -O- -O- 1.4E+6 4.9E+9 Sr-89 -O- -O- -O- 3.2E+5 4.9E+3 Sr-90 -O- -O- -O- -O- 2.3E+7 Zr-95 -O- -O- 4.OE+5 5.7E+7 Nb-95 -O- -o- -O- 1.2E+5 3.1E+7

,Ru-103,. -O- -O- -O- 1.2E+5 2.5E+7 Te-129m -O- -O- -O- -O- 2.6E+5 -4.5E+6 Cs-134 -0 -O0- -O - -O- 1.9E+5 1.6E+9 Cs-136 -O- -O- -O- -O- -O - -3.3E+4 3.4E+7 Cs-137 -O- -- -o0- -O- 1.4E+5 2.3E+9 Ba-140 -O- O-0 -O- 2.9E+5 4.7E+6 Ce-141 -O- -O- -O- -8.3E+4 -3.1E+6 Ce-144 -O- -O- -O- 1.8E+6 1.6E+7 I -131 : -O- -O- -O- -O- 2.7E+6! -3.9E+6 1 -132 O-0 -O- -O- 2.6E+4 2.8E+5 I -133 -O- -0 -O- -O- -O- 4.9E+5 5.6E+5 I -134 -O- 6.8E+3 1.OE+5 1 -135 -O- -O- --- -O- -O- 1.OE+5 5.8E+5 UN-ID -O- -O- -O- -O- 2.OE+5 -1.7E+8 mrem/lr - .I Inhalation Pathway, units = pCi /ml 2 (mrem/Yr) -'

Food & Ground Pathway, units = (n )pCi /sec.

S023-ODCM

., i2-45 Revision 30 05-28-97 S02 3 -ODCM

I I rs ,j TABLE 2-12 DOSE PARAMETER RI FOR SECTOR C Page I of 2 Pathway = Camp San Onofre Distance = 2.6 miles X/Q = 9.7E-8 sec/r 3 D/Q = 8.9E-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.E+5 3.4E+8 Co-58 9.3E+5 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 1.8E+6 2.5E+8 Nb-95 5.OE+5 1.4E+8 Ru-103 5.OE+5 1.1E+8 Te-129m 1.2E+6 2.OE+7 Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+S 1.5E+8 Cs-137 6.2E+5 1.OE+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 1 -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.OE+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 Inhalation Pathway, units =mret Fpcirn Food & Ground Pathway, units = pci(re/sec S023-ODCM 2-46 Revision 30 05-28-97 S02 3 -ODCM

TABLE 2-12

'DOSE PARAMETER'R FOR SECTOR C Page 2 of 2 Pathway = Deer Consumer/Hunter Distance = 1.0 miles X/Q - 4.OE-7 sec/m 3 D/Q = 4.6E-9 m'2 Infant Child Teen Adult Inhala- Food & Inhala- Food b Inhala- Food & Inhala- Food &

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.OE+4 1.OE+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 4.6E+6 8.OE+6 1.OE+4 2.3E+7 Co-58 9.6E+6 1.9E+7 *2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 -O- *4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 -0O 1.OE+9 8.OE+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 '4.8E+4 2.OE+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 -O- 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4, -3.4E+8 Cs-136 5.1E+6 4.2E+6 4.OE+3 9.5E+6 Cs-137 - 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 ,5.0E+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 - 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 '1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 1 -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134, 8.2E+2 1.2E+4 I -135 - ,---O- l.lE-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = -

pCi/nm Food & Ground Pathway, units = (in) (mnrem/yr) pCi/sec S023-ODCM 2-47 Revision 30 05-28-97 S023-ODCM

I I

.7 TABLE 2-13 DOSE PARAMETER R. FOR SECTOR D Page 1 of 2 Pathway = Camp San Onofre Distance = 3.0 miles X/Q = 6.9E-8 sec/r3 D/Q = 7.2E-10 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- -O- -O- 1.3E+3 -O-Cr-51 -O- -O- -0 -O- 1.4E+4 4.7E+6 Mn-54 -O- -O- -O- 1.4E+6 1.4E+9 Co-57 -O- -O- -O- -O- -O- 3.7E+5 3.4E+8 Co-58 -O. -O- -O- -0 O- -O- 9.3E+5 3.8E+8 Co-60 -O- -O -O- -O- 6.OE+6 2.2E+10 Sr-89 -O- -O- -O- 1.4E+6 2.2E+4 Sr-90 -O- -O- -O- -O- 9.9E+7 -O-Zr-95 -O- -0 -O- -O- -O- 1.8E+6 2.5E+8 Nb-95 -O- -O- -O- -O- 5.OE+5 1.4E+8 Ru-103 -O- -O- -O- 5.0E+5 1.1E+8 Te-129m -O- -0 -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-0 -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- -O- 3.6E+5 1.4E+7 Ce-144 -O- -O- -O- -O- -O- 7.8E+6 7.OE+7 I -131 -O- -O- -O- -O- -O- 1.2E+7 1.7E+7 1 -132 -O- -O- -O- -O- -O- -O- 1.1E+5 1.2E+6 I -133 -O- -O- -O- -O- -O- -O- 2.2E+6 2.4E+6 I -134 -O- -O- -O- -O- -O- 3.OE+4 4.5E+5 I -135 -O- -O- -O- -O- -O- 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 Inhalation Pathway, units = m pCi/rn Food & Ground Pathway, units = W) (nremn/vr) pCi/sec S023-ODCM 2-48 Revision 30 05-28-97 S023 -ODCM

TABLE 2-13 DOSE PARAMETER R1 FOR SECTOR D Page 2 of 2 Pathway = Deer Consumer/Hunter Distance = 0.8 miles X/Q 5.3E-7:sec/

n ut D/Q = 7.3E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion Ground tion - Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.OE+4 1.OE+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 4.6E+6 8.OE+6 1.OE+4 2.3E+7 Co-58 ; 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 :1.2E+9 Zr-95 6.2E+7 1.1E+8 4.8E+4 2.OE+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 .5.1E+6 4.2E+6 4.OE+3 -9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 5.OE+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 .4.2E+6 Ce-144 *1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 *6.5E+8 4.3E+8 3.3E+5 5.9E+8 1 -132 3.1E+3 3.4E+4 I -133 1.6E+l 8.6E+O 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 :6.9E+4 UN-ID - 1.1E+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = mrem/yr FCiT7W Food & Ground Pathway, Fod&G)units nt )p(mrerm/yr) ci/se S023-ODCM 2-49 Revision 30 05-28-97 S02 3 -ODCM

I I

- I TABLE 2-14 DOSE PARAMETER R, FOR SECTOR E Page 1 of 2 Pathway = Camp Horno Distance = 4.1 miles X/Q = 7.5E-8 sec/m3 - 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 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 -O- 1.4E+6 1.4E+9 Co-57 3.7E+5 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.OE+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.9E+7 Zr-95 1.8E+6 2.5E+8 Nb-95 5.OE+5 1.4E+8 Ru-103 5.OE+5 1.1E+8 Te-129m 1.2E+6 2.OE+7 Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+5 .1.5E+8 Cs-137 6.2E+5 1.OE+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 I -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+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 Inhalation Pathway, units =

VC i/rn-2 Food & Ground Pathway, units = W(i) (mrem/vr) pCi/sec S023-ODCM 2-50 Revision 30 05-28-97 S02 3 -ODCM

V TABLE 2-14 DOSE PARAMETERR. FOR SECTOR E Page 2 of 2 Pathway = Deer Consumer/Hunter' Distance = 0.8 miles X/Q = 8.5E-7 sec/m 3 D/Q = 1.3E-8 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 -O- -O- -O- - 2.8E+1 2.3E+1 '3.5E+1 3.9E+1 Cr-51 -O- -O- 5.0E+4 -O- 1.0E+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 --

O -O- -O- 4.6E+6 -O- 8.OE+6 1.OE+4 2.3E+7 Co-58 -O- -O- -O- 9.6E+6 -O- 1.9E+7 2.5E+4 4.7E+7 Co-60 -O- -O- -O- 3.6E+7 -O- 7.2E+7 1.6E+5 7.2E+8 Sr-89 -O- -O- -O- 4.9E+7 -O- 2.6E+7 3.8E+4 3.1E+7 Sr-90 -O- -O- -O- l.OE+9 -O- 8.0E+8 2.7E+6 1.2E+9 Zr-95 -O- -O- -O- 6.2E+7 -O- 1.1E+8 4.8E+4 2.0E+8 Nb-95 -O- -O- -O- - 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 -O- -O- -O- 4.2E+8 -O- '7.5E+8 '1.4E+4 1.3E+9 Te-129m -O- -O- -O- 5.9E+8 -O- 4.5E+8 3.2E+4 6.4E+8 Cs-134 -O- -O- 1.4E+8 -O- 1.2E+8 2.3E+4 3.4E+8 Cs-136 -O- -O- -- -5.1E+6 4.2E+6 4.OE+3 9.5E+6 Cs-137 -O- -O- 1.3E+8 -O- 9.3E+7 1.7E+4 4.OE+8 Ba-140 -O- -O- -O- 5.OE+6 -O- 4.2E+6 3.5E+4 7.4E+6 Ce-141 -O- -O- -O- 1.5E+6 -O- 2.4E+6 9.9E+3 4.2E+6 Ce-144 -O- -O- -O- -1.BE+7 -O- 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 1-132 -O- -O- -O- -O- -O- 3.1E+3 3.4E+4 I--133 - -O- 1.6E+1 - -O- 8.6E+0 5.9E+4 6.7E+4 I -134 -O- -O- -O- -O- -O- 8.2E+2 1.2E+4 I -135 -O- -O- -O- 1.1E-15 -O- 6.3E-16 1.2E+4 6.9E+4 UN-ID -O- -O- -O- 1.1E+8 -O- 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = pCi/rn 2 (mnremn/vr Food & Ground Pathway, units = W) pCi/sec:

S023-ODCM

' 2-51 Revision 30 05-28-97 S02 3 -ODCM

II TABLE 2-15 DOSE PARAMETER RI FOR SECTOR F Page 1 of I Pathway = San Onofre State Park/Guard Shack Distance = 0.8 miles X/Q = 9.6E-7 sec/m 3 2 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 Pathway Pathway Pathway Pathway Pathway H -3 -O- -O- -O- -O- -O- 2.2E+2 -0 Cr-51 -O- -O- -O- -O- -O- 2.5E+3 8.OE+5 Mn-54 -O- -O- -O- -O- 2.4E+5 2.4E+8

-Co-57 -O- -O- -O- -O- -O- 6.3E+4 5.9E+7 Co-58 -O- -O- -O- -O- -O- 1.6E+5 6.5E+7 Co-60 -O- -O- -O- 1.OE+6 3.7E+9 Sr-89 -O- -O- -O- 2.4E+5 3.7E+3 Sr-90 -O- -O- -O- 1.7E+7 -O-Zr-95 -O- -O- -O- -O- -O- 3.OE+5 4.3E+7 Nb-95 -O- -O- -O- 8.6E+4 2.3E+7 Ru-103 -O- -O- 8.6E+4 1.9E+7 Te-129m -O- -O- -O- -O- 2.OE+5 3.4E+6 Cs-134 -O- -O- -O- I.5E+5 1.2E+9 Cs-136 -O- -O- -O- -O- -O- 2.5E+4 2.6E+7 Cs-137 -O- -O- 1.1E+5 1.8E+9 Ba-140 -O- -O- -O- 2.2E+5 3.5E+6 Ce-141 -O- -O- -O- -O 6.2E+4 2.3E+6 Ce-144 -O- -O- -O- -O- 1.3E+6 1.2E+7 I -131 -O- -O- -O- 2.OE+6 2.9E+6 I -132 -O- -O- -O- -O- -O 2.OE+4 2.1E+5 I -133 -O- -O- -O- -O- -O- 3.7E+5 4.2E+5 I -134 -O- -O- -O- -O- -O- -O- 5.1E+3 7.7E+4 I -135 -O- -O- -O- -O- -O- -O- 7.7E+4 4.3E+5 UN-ID 1.5E+5 1.3E+8 Inhalation Pathway, units = mre!Lr Food & Ground Pathway. units = ()p(ci/semc S023-ODCM 2-52 Revision 30 05-28-97 S02 3 -ODCM

-I

- TABLE 2-16 DOSE PARAMETER Ri FOR SECTOR' G Page 1 of I Pathway = San Onofre State Beach Campground Distance = 0.9 miles X/Q = 6.6E-7 sec/mr 3

- D/Q = 3.3E-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 8.OE+1 1.4E+2 1.6E+2 2.9E+2 Cr-51 1.6E+3 5.7E+5 2.IE+3 5.7E+5 2.6E+3 5.7E+5 3.3E+3 1.1E+6 Mn-54, 1.2E+5 1.7E+8 1.9E+5 1.7E+8 2.4E+5 1.7E+8 3.2E+5 3.2E+8 Co-57 4.7E+4 4.2E+7 6.3E+4 4.2E+7 7.2E+4 4.2E+7 8.4E+4 7.8E+7 Co-58 9.6E+4 4.7E+7 1.4E+5 4.7E+7 1.7E+5 4.7E+7 2.1E+5 8.7E+7 Co-60 5.6E+5 2.7E+9 8.7E+5 2.7E+9 1.1E+6 2.7E+9 1.4E+6 4.9E+9 Sr-89 2.5E+5 2.7E+3 2.7E+5 2.7E+3 3.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 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 1.3E+7 8.2E+4 1.3E+7 9.7E+4 1.3E+7 1.2E+5 2.5E+7 Te-129m 2.1E+5 2.4E+6 2.2E+5 2.4E+6 2.4E+5 .2.4E+6 2.6E+5 4.5E+6 Cs-134 8.7E+4 8.4E+8 1.3E+5 8.4E+8 1.4E+5 8.4E+8 1.9E+5 1.6E+9 Cs-136 1.7E+4 1.9E+7 2.1E+4 I.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 1 -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 2.4E44 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+S 4.9E+5 5.6E+5 1 -134 5.5E+3 5.SE+4 6.3E+3 5.5E+4 4.9E+3 S.SE+4 6.8E+3 1.OE+5 I -135 8.6E+4 3.1E+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 = mremlvr VC i/m3 2

Food & Ground Pathway, units = (m )(mrem/vr) pCi/sec S023-ODCM 2-53 Revision 31 02-27-98 S02 3 -ODCM

II TABLE 2-17 SOUTH YARD FACILITY CONTROLLING LOCATIOH FACTORS EkRIIWk Radionuclide mrein/yr' per pCi/sec" Use:

H -3 1.31E-03 G: SAN ONOFRE BCH CAMPGD Cr-51 4.15E-02 F: SO ST. PK./GUARD SHACK Mn-54 9.70E+OO F: SO ST. PK./GUARD SHACK Co-57 2.41E+OO F: SO ST. PK./GUARD SHACK Co-58 3.14E+OO F: SO ST. PK./GUARD SHACK Co-60 1.35E+02 F: SO ST. PK./GUARD SHACK Sr-89 1.71E+OO F: DEER CONSUMER/HUNTER Sr-90 1.04E+02 G: SAN ONOFRE BCH CAMPGD Zr-95 7.26E+OO F: DEER CONSUMER/HUNTER.

Nb-95 2.88E+01 F: -DEER,CONSUMER/HUNTER' Ru-103 4.56E+01 F: DEER CONSUMER/HUNTER.

Te-129m 2.26E+01 F: DEER CONSUMER/HUNTER:

Cs-134 4.28E+01 F: SO ST. PK./GUARD SHACK Cs-136 1.04E+OO F: SO ST. PK./GUARD SHACK Cs-137 6.36E+01 F: SO'ST. PK./GUARD SHACK Ba-140 1.39E+OO G: SAN ONOFRE BCH CAMPGD Ce-141 4.29E-01 G: SAN ONOFRE BCH CAMPGO Ce-144 8.39E+OO G: SAN ONOFRE BCH CAMPGD I -131 2.28E+01 F: DEER CONSUMER/HUNTER, I -132 1.22E-01 G: SAN ONOFRE BCH CAMPGD I -133 2.22E+OO G: SAN ONOFRE BCH CAMPGD I -134- 3.24E-02 G: SAN ONOFRE BCH CAMPGD I -135 4.60E-01 G: SAN ONOFRE BCH CAMPGD UN-ID 5.36E+_0 F: SO ST PK./GUARD SHACK Footnote: These values to be used in manual calculations are the maximum zxRkWk for all locations based on the most restrictive age group.

S023-ODCM 2-54 Revision 28 12-21-95 S02 3 -ODCM

TABLE 2-18

-SOUTH YARD FACILITY: DOSE PARAMETER R1 FOR SECTOR D Page 1 of 1 Pathway = Camp Horno Sewage Trmnt. Distance = 3.2 Miles X/Q = 1.2E-7 sec/m3 DAQ = 1.2E-9 mn2 Infant Child Teen Adult I-nhala- 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- 2.9E+2 Cr-51 -O- -O- -O- -O- 3.3E+3 1.1E+6 Mn-54 -O- -O- -O- --- -O- 3.2E+5 3.2E+8 Co-57 -O- -0 - -O- -O- -O- 8.4E+4 7.8E+7 Co-58 -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- 4.OE+5 5.7E+7 Nb-95 -O- -O- -o- - I.2E+5 3.1E+7 Ru-103 -O- -O- -O- -O- 1.2E+5' -2.5E+7 Te-129m -O- -O- -O- -O- 2.6E+5 4.5E+6 Cs-134 -O- -O- -O- 1.9E+5 1.6E+9 Cs-136 -O- -O- 3.3E+4 3.4E+7 Cs-137 -O- -O- -O- 1.4E+5 2.3E+9 Ba-140 -O- -O- -O- 2.9E+5 4.7E+6 Ce-141 -O- -O- -O- -O- -O- 8.3E+4 3.1E+6 Ce-144 -O- -O- -O- 1.8E+6 1.6E+7 1 -131 -O- -0 - -O- -O- 2.7E+6 3.9E+6 I -132 -O- -O- -O- 2.6E+4 2.8E+5 1 -133 -O- -O- -O- 4.9E+5 5.6E+5 1 -134 -O- -O- -O- -O- -O- 6.8E+3 1.OE+5 I -135 -O- -O- -O- 1.OE+5 5.8E+S UN-ID -O- -O- -0_ -O- 2.OE+5 1.7E+8 Inhalation Pathway, units = mrem/vr pci/m' Food & Ground Pathway, units = (ml) (mremlvr) pCi/sec S023-ODCM 2-55 Revision 28 12-21-95 S023-ODCM

II TABLE 2-19 SOUTH YARD FACILITY DOSE PARAMETER RI FOR SECTOR E Page- 1 of 1 Pathway = Camp Horno Distance = 3.7 Miles X/Q = 6.OE-7 sec/n3 - D/Q = 5.7E-9 m-r 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-Sl -O- -O- -O- -O- -O- 1.4E+4 4.7E+6 Mn-54 -O- -O- -O- 1.4E+6 1.4E+9 Co-57 -O- -O- -O- -O- -O- 3.7E+5 3.4E+8 Co-58 -O- -O- -O- -O- -O- 9.3E+5 3.8E+8 Co-60 -O- -O- -O- -O- -O- 6.OE+6 2.2E+10 Sr-89 -O- -O- -O- 1.4E+6 2.2E+4 Sr-90 -O- -O- -O- 9.9E+7 -O-Zr-95 -O- -O- O- -O- 1.8E+6 2.5E+8 Nb-95 -O- -O- -O- 5.OE+5 1.4E+8 Ru-103 -O- -O- -O- 5.OE+5 1.1E+8 Te-129m -O- -O- -O- 1.2E+6 2.OE+7 Cs-134 -O- -O- -O- 8.5E+5 6.8E+9 Cs-136 -O- -O- -O- -O- 1.5E+5 1.5E+8 Cs-137 -O- -O- -O- -O- 6.2E+5 1.OE+10 Ba-140 -O- -O- -O- 1.3E+6 2.1E+7 Ce-141 -O- -O- -O- -O- 3.6E+5 1.4E+7 Ce-144 -O- -O- -- -O- 7.8E+6 7.OE+7 I -131 -O- -O- -O- I.2E47 1.7E+7 I -132 -O- -O- -O- 1.1E+5 1.2E+6 I -133 -O- -O- -O- 2.2E+6 2.4E+6 1 -134 -O- -O- -O- 3.OE+4 4.5E+5 I -135 -O- -O- -O- 4.5E+5 2.5E+6 UN-ID -O- -O- -O- -O- -O- 8.6E+5 7.5E+8 Inhalation Pathway, units = mremlr FCi/mr 2 (mremlyr)

Food & Ground Pathway, units = (rn)pCi/sec S023-ODCM 2-56 Revision 28 12-21-95 S023 -ODCM

e_

TABLE 2-20 SOUTH YARb FACILITY DOSE PARAMETER R. FOR SECTOR F Page 1 of 4 Pathway - San Onofre State Park/Guard Shack Distance = 0.4 Miles X/Q = 5.4E-6 sec/de D/Q = 3.'5E-8 -m2 -

Infant Child .Teen Adult Inhala- Food & Inhala- Fo a- Food & Inhala- Food &

.Radio- tion Ground tion Gr Ground tion Ground Nuclide Pathway Pathway Pathway Pa ay Pathway.. Pathway Pathway H -3 . -O- -O- -O- 2.2E+2 -O-Cr-51 -O- -O- -O- -O- 2.5E+3 8.OE+5 Mn-54 . -O- -O- -O- -O- 2.4E+5 2.4E+8 Co-57 -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- -O- -O- -O- 2.4E+5 3.7E+3 Sr-90 -O- -O- -O- 1.7E+7 -O-Zr-95 -O- -O- -O- -O- 3.OE+5 4.3E+7 Nb-95 -O- -O- -O- 8.6E+4 2.3E+7 Ru-103. -O- -O- -O- -O- 8.6E+4 l.9E+7 Te-129m . -O- -O- -O- 2.OE+5 3.4E+6 Cs-134 -O- -O- -O- -O- 1.5E+5 1.2E+9 Cs-136 -O- . -O- -O- 2.5E+4 2.6E+7 Cs-137 -O- -O- -O- -O- 1.1E+5 1.8E+9 Ba-140 -O- -O- -O- - -O- 2.2E+5 3.5E+6 Ce-141 -O- -O- -O- -O- 6.2E+4 2.3E+6 Ce-144 -O- -O- -O- 1.3E+6 1.2E+7 I -131 -O- -O- -O- -O- 2.OE+6 2.9E+6 I -132 -O- -O- -O- 2.OE+4 2.1E+5 I -133 -O- -O- -O- -O- 3.7E+5 4.2E+5 1 -134 -O- -O- -O- -O- 5.1E+3 7.7E+4 I -135 -O- -O- -O- 7.7E+4 4.3E+5 UN-ID . -O- -O- -O- 1.5E+5 1.3E+8 Inhalation Pathway, units = mrem/vr pCI/mr Food & Ground Pathway, units =

(i 2 ) (mremi/yr) pCi/sec, S023-ODCM 2-57 Revision 28 12-21-95 S02 3 -ODCM

t.s o; TABLE 2-20 SOUTH YARD FACILITY DOSE PARAMETER RI FOR SECTOR F Paqe 2 of 4 Pathway = Border Patrol Checkpt. Distance = 1.4 Miles X/Q = 1.2E-6 sec/mr3 _ D/Q = 8.2E-9 m-r 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- 3.6E+2 -O-Cr-51 O- -O- -O- -O- -O- -O- 4.1E+3 1.3E+6 Mn-54 -O- -O- -O- -O- -O- -O- 4.OE+5 3.9E+8 Co-57 -O- -O- -O- -O- -O- -O- 1.1E+5 9.BE+7 Co-58 -O- -O- -O- -O- -O- -O- 2.6E+5 1.1E+8 Co-60 -O- -O- -O- -O- 1.7E+6 6.1E+9 Sr-89 -O- -O- -O- 4.OE+5 6.2E+3 Sr-90 -. 0 -O- -O- -O- -O- 2.8E+7 -O-Zr-95 -O- -O- -O- 5.OE+5 7.2E+7 Nb-95 -O- -O- -O- 1.4E+5 3.9E+7 Ru-103 -O- -O- -O- 1.4E+5 3.1E+7 Te-129m -O- -O- -O- -- 3.3E+5 5.6E+6 Cs-134 -O- -O- -O- 2.4E+5 1.9E+9 Cs-136 -O- -O- -O- 4.2E+4 4.3E+7 Cs-137 -O- -O- -O- -O- 1.8E+5 2.9E+9 Ba-140 -O- -O- -O- 3.6E+5 5.9E+6 Ce-141 -O- -O- -- -O- 1.OE+5 3.9E+6 Ce-144 -O- -O- -O- 2.2E+6 2.OE+7 I -131 -O- -O- -O- 3.4E+6 4.9E+6 I -132 -O- -O- -O- 3.3E+4 3.5E+5 I -133 -O- -O- -O- -O- -- 6.1E+5 7.OE+5 I -134 -O- -O- -O- -O- 8.5E+3 1.3E+5 I -135 -O- -O- -O- 1.3E+5 7.2E+5 UN-ID -O- -O- -O- 2.5E+5 2.1E+8 Inhalation Pathway, units = pCiremi/r

/m, 2)(mrem/vr)

Food & Ground Pathway, units = (ni pCi/sec S023-ODCM 2-58 Revision 28 12-21-95 S02 3 -ODCM

TABLE 2-20 SOUTH YARD FACILITY DOSE PARAMETER Ri FOR SECTOR F Page 3 of 4 Pathway = Sheep (Meat)/Shepherd Distance = 0.3 Miles X/Q = 7.2E-6 sec/m3, _ D/Q = 4.5E-8 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion ' Gr'ound tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway- Pathway Pathway Pathway H -3 1.5E+O 1.2E+0 7.OE+0 2.lE+O Cr-51 5.1E+1 1.OE+2 7.9E+1 2.6E+4 Mn 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 -O- 4.7E+3 8.1E+3 2.OE+3 1.9E+6 Co-58 -_O 9.7E+3 -2.OE+4 5.1E+3 2.1E+6 Co-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Sr-89 5.OE+4 2.6E+4 7.7E+3 3.1E+4 Sr-90 - 1.OE+6 8.1E+5 5.5E+5 1.3E+6 Zr-95 '_O_ 6.3E+4 1.1E+5 9.7E+3 1.6E+6 Nb-95 ' 2.4E+5 - 4.5E+5 2.8E+3 -1.6E+6 Ru-103 .-0-' '4.2E+5 7.6E+5 2.8E+3 1.9E+6 Te-129m 6.OE+5 4.5E+5 6.4E+3 7.6E+5 Cs-134 ; 1.4E+5 1.2E+5 4.7E+3 "3.BE+7 Cs-136 '5;1E+3 4.3E+3 8.1E+2, 8.3E+5 Cs-137 -1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 -5.1E+3 4.3E+3 7.OE+3 1.2E+5 Ce-141 -1.SE+3 2.4E+3 2.OE+3 7.9E+4 Ce-144 ' 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I -131 6.6E+5 4.4E+5 6.6E+4 7.OE+5 1 -132 6.3E+2 '6.8E+3 1 -133 '1.6E+2 8.7E+3 1.2E+4' 1.3E+4 I -134 -O- -1.6E+2 2.5E+3 1 -135 0--v 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units = mfrem/yr pci/in (mnrem/yr) -

Food & Ground Pathway, units = (in) ,pCi/sec S023-ODCM

1. 2-59 Revision 28 12-21-95 S023 -ODCM

iia I'

TABLE 2-20 SOUTH YARD FACILITY DOSE PARAMETER RI FOR SECTOR F

-. Page 4 of 4 Pathway = Deer-Consumer/Hunter Distance = 0.4.Miles X/Q = 5.4E-6 sec/m3 - D/Q = 3.5E-8mW2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.OE+4 1.OE+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-51 4.6E+6 8.OE+6 1.OE+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4- 3.1E+7 Sr-90 1.OE+9 8.OE+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 4.8E+4 2.OE+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4' 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.1E+6 4.2E+6 4.OE+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.OE+8 Ba-140 5.OE+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6

'Ce-144 1.8E+7 2.9E+7 2.lE+5 4.9E+7 1 -131 6.5E+B 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 mrem/vr Inhalation Pathway, units -

2 (mrem/vr)

Food & Ground Pathway, units = (m )pCi/sec S023-ODCM 2-60 Revision 28 12-21-95 S023 -ODCM

TABLE 2-21 SOUTH YARD FACILITY DOSE PARAMETER RI FOR SECTOR G Page 1 of 4 Pathway - San Onofre Bch Campgd Distance = 0.4 Miles X/Q = 4.5E-6 sec/; r D/Q = 1.8E-8 m 2 ,

'Infant Child Teen Adult

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

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway- Pathway Pathway Pathway Pathway Pathway H -3 8.OE+1 1.4E+2 1.6E+2 2.9E+2 Cr-51 1.6E+3 5.7E+5 2.1E+3 .5.7E+5 2.6E+3 5.7E+5 3.3E+3 1.1E+6 Mn-54 1.2E+5 1.7E+8 1.9E+5 1.7E+B 2.4E+5 1.7E+8 3.2E+5 3.2E+8 Co-57 '4.7E+4 4.2E+7 6.3E+4 4.2E+7 7.2E+4 4.2E+7 8.4E+4 7.8E+7 Co-58 9.6E+4 4.7E+7 1.4E+5 4.7E+7 1.7E+5 4.7E+7 2.1E+5 '8.7E+7 Co-60 5.6E+5 2.7E+9 8.7E+5 .2.7E+9 1.1E+6 2.7E+9 1.4E+6 4.9E+9 Sr-89 2.5E+5 2.7E+3 2.7E45 '2.7E+3 3.OE+5 2.7E+3 3.2E+5 4.9E+3 Sr-90 S.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 1.3E+7 8.2E+4 :1.3E+7 9.7E+4 1.3E+7 1.2E+5 2.5E+7 Te-129m 2.1E+5 2.4E+6 '2.2E+5 2.4E+6 2.4E+5 2.4E+6 2.6E+5 4.5E+6 Cs-134 -.7E+4 8.4E+B 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 2.0E+6 2.1E+6 I.8E+6 2.IE+6 2.7E+6 3.9E+6 I -132 2.IE+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 '3.1E+5 9.8E+4 3.IE+5 7.7E+4 3.IE+5 1.OE+5 5.BE+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 = mrem/vr pCi/m' Food & Ground Pathway,. units = (in) (mremlvr) pCi /sec S023-ODCM 2-61 Revision 28 12-21-95 S02 3 -ODCM

i _ _ _ - I ,a TABLE 2-21 SOUTH YARD FACILITY DOSE PARAMETER RI FOR SECTOR G Page 2 of 4 Pathway = Highway Patrol Weigh Station Distance = 1.6 Miles-X/Q = 4.2E-7. sec/m3 D/Q = 1.7E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 -O- -O- -O- -O- -O- 3.OE+2 -O-Cr-51 -O- -O- -O- -O- -O- -O- 3.4E+3 1.1E+6 Mn-54 -O- -O- -O- -O- -O- 3.3E+5 3.3E+8 Co-57 -O- -O- -O- -O- -O- -O- 8.8E+4 8.1E+7 Co-58 -O- -O- -O- -O- 2.2E+5 9.OE+7 Co-60 -O- -O- -O- -O- 1.4E+6 5.1E+9 Sr-89 -O- -O- -O- 3.3E+5 5.1E+3 Sr-90 -O- -O- -O- 2.4E+7 -O-Zr-95 -O- -O- -O- 4.2E+5 6.OE+7 Nb-95 -O- -O- -O- 1.2E+5 3.2E+7 Ru-103 -O- -O- -O- 1.2E+5 2.6E+7 Te-129m -O- -O- -O- -O- 2.8E+5 4.7E+6 Cs-134 -O- -O- -O- -O- -O- -O- 2.OE+5 1.6E+9 Cs-136 -O- -O -O- -O- 3.5E+4 3.6E+7 Cs-137 -O- -O- -O- -O- -O- 1.5E+5 2.4E+9 Ba-140 -O- -O- -O- 3.OE+5 4.9E+6 Ce-141 -O- -O- -0 -O- -O- 8.6E+4 3.2E+6 Ce-144 -O- -O- -O- -O- -O- -- 1.8E+6 1.7E+7 1 -131 -O- -O- -O- -O- -O- -O- 2.8E+6 4.1E+6 I -132 -O- -O- -O- 2.7E+4 2.9E+5 I -133 -O- -O- -O- -O- -O- -O- 5.1E+5 5.8E+5 I -134 -O- -O- -O- -O- -O- 7.1E+3 1.1E+5 I -135 -O- -O- -O- -O- -O- 1.1E+5 6.0E+5 UN-ID -O- -O- -O- -O- 2.1E+5 1.8E+8 Inhalation Pathway, units = mrem/vr VC~i/rn__

2 Food & Ground Pathway, units = (m ) (mrem/vr) pCi/sec S023-ODCM 2-62 Revision 28 12-21-95 S023-ODCM

TABLE 2-21 SOUTH YARD FACILITY DOSE PARAMETER R. FOR SECTOR G Page 3 of 4 Pathway = Sheep (Meat)lShepherd Distance = 2.3 Miles X/Q = 2.4E-7__sec/m D/Q = 9.2E-10Om-2 Infant CldTeen 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- 1.5E+0 -O- 1.2E+O -7.0E4D 2.1E+O Cr-51 -O- -O- -O- 5;1E+1 -O- 1.OE+2 7.9E+1 2.6E+4 Mn-54 -O- -O- 7.8E+2 1.4E+3 7.7E+3 -7.6E+6 Co-57 -O- -O- - 4.7E+3 -O- 8.1E+3 2.OE+3 1.9E+6 Co-58 -O- -O- 9.7E+3 -O- 2.OE+4 5.1E+3 2.1E+6 Co-60 -O- -O- -O- - 3.7E+4 -O- 7.3E+4 3.3E+4 1.2E+8 Sr-89 -O- -O- 5.0E+4 -O- 2.6E+4 7.7E+3 3.1E+4 Sr-90 -O- -O- -O- 1.OE+6 -O- B.1E+5 5.5E+5 1.3E+6 Zr-95 -O- -O- -O- .6.3E+4 -O- 1.IE+5 *9.7E+3 1.6E+6

-Nb-95 -O- -O- '; 2.4E+5 -O- 4.5E+5 2.BE+3 1.6E+6 Ru-103 -O- -O- 4.2E+5 -O- 7.6E+5 2.8E+3 1.9E+6 Te-129m -O- -O- 6.OE+5 -O- 4.5E+5 6.4E+3 7.6E+5 Cs-134 -O- -O- 1.4E+5 -O- 1.2E+5 4.7E+3 3.8E+7 Cs-136 -O -O- 5.1E+3 -O- 4.3E+3 8.1E+2 8.3E+5 Cs-137 -O- 1.3E+5 -O- 9.5E+4 3.4E+3 5.7E+7 Ba-140 -O- - -O- -O- 5.IE+3 -O- 4.3E+3 7.OE+3 1.2E+5 Ce-141 -O- -O- -O- 1.5E+3 -O- 2.4E+3 2.OE+3 7.9E+4 Ce-144 -O- -O- -O- 1.8E+4 -O- 3.OE+4 4.3E+4 4.3E+5 I -131 -O- -O- -O- 6.6E+5 -O- 4.4E+5 6.6E+4 7.OE+5 I -132 -O- -O- -O- -O- 6.3E+2 6.8E+3 I -133 -O- -O- -O- 1.6E+2 -O- 8.7E+3 1.2E+4 1.3E+4 1 -134 -O- -O- -O- 1.6E+2 2.5E+3 1 -135 -O- -O- 1.1E-18 -O- 6.4E-19 2.5E+3 1.4E+4 UN-ID -O- -O- -O- 1;1E+5 -O- 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units = mremlr VC~i/rnT Food & Ground Pathway, units = (mt)pCi/sec (mremlyr)

S023-ODCM 2-63 Revision 28 12-21-95 S02 3 -ODCM

I I

-f

.TABLE 2-21 SOUTH YARD. FACILITY DOSE PARAMETER RI FOR SECTOR G Page 4 of 4 Pathway = Deer Consumer/Hunter Distance - 2.9 Miles X/Q = 1.8E-7 sec/m 3 -_D/Q 6.4E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion: Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway 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- -O- 5.OE+4 -O- 1.OE+5 3.9E+2 3.2E+5 Mn-54 -O- -O- -O- 7.7E+5 -O- 1.4E+6 3.8E+4 4.1E+7 Co-57 -O- -O- -O- 4.6E+6 -O- 8.OE+6 1.OE+4 2.3E+7 Co-58 -O- -O- -O- 9.6E+6 -O- 1.9E+7 2.5E+4 4.7E+7 Co-60 -O- -O- -O- 3.6E+7 -O- 7.2E+7 1.6E+S 7.2E+8 Sr-89 -O- -O- -O- 4.9E+7 -O- 2.6E+7 3.8E+4 3.1E+7 Sr-90 -O- -O- -O- 1.0E+9 -O- 8.0E+8 2.7E+6 1.2E+9 Zr-95 -O- 6.2E+7 -O- 1.1E+8 4.8E+4 2.0E+8 Nb-95 -O- 2.3E+B -O- 4.5E+8 1.4E+4 8.2E+8 Ru-103 -O- -O- -O- 4.2E+8 -O- 7.5E+8 1.4E+4 1.3E+9 Te-129m -O- -O- 5.9E+8 -O- 4.5E+8 3.2E+4 6.4E+8 Cs-134 -O- -O- -o- 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 -O- 9.3E+7 1.7E+4 4.0E+8 Ba-140 -O- -O- 5.OE+6 -O- 4.2E+6 3.5E+4 7.4E+6 Ce-141 -O- -O- -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 -O- -O- -O- 6.5E+8 -O- 4.3E+8 3.3E+5 5.9E+8 I -132 -O- -O- -O- -O- -O- -O- 3.1E+3 3.4E+4 I -133 -O- -O- -O- 1.6E+1 8.6E40 5.9E+4 6.7E+4 I -134 -O- -O- -O- -O- -O- 8.2E+2 1.2E+4 I -135 -O- -O- -O- 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID -O- -O- -O- 1.1E+8 -O- 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = mrern/r

,uCi/mn 2

Food & Ground Pathway, units = (m ) (mrem/vr) pCi/sec S023-ODCM 2-64 Revision 28 12-21-95 S023-ODCM

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

1. 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 '

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

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

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

S023-ODCM 3-1 Revision 22 08-02-90 S02 3 -ODCM

II 3.0 PROJECTED DOSES (Continued) 3.3 TOTAL DOSE SPECIFICATION 3.3.1 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

APPLICABILITY: At all times ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 1.2.1.a, 1.2.1.b, 2.2.1.a, 2.2.1.b, 2.3.1.a, or 2.3.1.b in lieu of any other report required by Specification 6.9.1; prepare and submit a Special Report to the Director, Nuclear Reactor'Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.3.1. This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release(s) covered by this report. If the estimated dose(s) exceeds the limits of Specification 3.3.1, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of paragraph 190.11(b). Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed elsewhere in this O0CM.

SURVEILLANCE REQUIREMENTS

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

S023-ODCM 3-2 Revision 32 02-25-99 S02 3 -ODCM

.6 3.0 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 memberof 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.

.1 Annual Total Oroan Dose (DTOTL(°))

DTOT (0) = 12 2/3 [DJ1(OG)+ Dj1(0L)+ Do} (OG)] (3-)

where:

NOTE: Dj)(OG) = 0 for bone

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

n Djj (OG)= K C Sk RI t (3-2) i = each isotope in specific organ category j = Units 1,'2 and 3 I = months 1 - 12**

K = 3.1688E-22ear-pCi sec-Ci S023-ODCM 3-3 Revision 32 02-25-99 S023-ODCM

II 3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 Total Dose to Most Likely Member of the Public (Continued) n = number of isotopes in the specified organ category C, = total particulate gas curies released for the month zri kWIk = controlling location factors from ODCM Table 2-5, k Unit 1 and Table 2-6, Units 2/3, for all pathways k.

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

Unit 1 (1-13)]

H3 Di,(0I gas organ dose form tritium in mrem for the month.

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

.2 Annual Total Whole Body Dose DTO.(WB) 12 2/3 r31(~ 3)

DroT(WB) - 1 FDj2(WBL)+ Do] (OG) + 0.9 DJ, (y)] -D(DIRECT)

.1=1 j=1 where:

j - Units l, 2 and 3 1 = months 1 - 12, to be summed over the most recent 12 months DJ1(WBL) liquid whole body organ dose in mrem for the whole month. (Reference ODCM Units 2/3 (1-19), ODCM Unit 1 (1-13)]

H3 D,(OG) = gas organ dose from tritium in mrem for the month.

BRefer ODCM Units 2/3 (2-18). ODCM Unit 1 (2-14)]

DJI (Y) = gamma air dose in mrad for the month.

0.9 converts mrad to mrem.

tReference OCM Units 2/3 (2-14), O0CM Unit 1 n (3-4) 4 Z D(bkgd),

0 (Direct) = E max[D(beach) 1 ] _ 1 n .0342 q=1 p = for all TLDs per quarter q = for Quarters 1-4 S023-ODCM 3-4 Revision 32 02-25-99 S023-ODCM

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 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 measured by TLDs 5 to 50 miles from the site is used as background. These sites are-subject to change.

The background is subtracted from the highest reading TLD within 5 miles of the site (generally numbers 55 through 58). This value is the direct dose but must be prorated-by the occupancy factor.

Example: --

Beach time (west boundary, seawall) of 300 hrs/yr, east and north boundaries of

-20 hrs/yr, or 8 hrs/yr for the south boundary and west fence of parking lot I (top of bluff).

. .Rf.eec

Reference:

~ ; E. M. Goldin Memorandum for File, "Occupancy Factors at San Onofre Owner Controlled Area Boundaries," dated October 1, 1991.

.3 Annual Total Thvroid Dose DTOIJJI.

12 2/3 DTOT(T)= 1=1 j=1 3. + Dj1 (OL)]

(3-5) where:

i = -Units 1, 2 and 3 1 = months' I - 12, to be summed over the most recent 12 months Dj, (OG) = thyroid organ dose from gaseous iodine for the n month in'mrem. (from 2-21) i 1 .: .' -

Dj} (OL) =. liquid thyroid organ dose for the month in mrem.

1 Reference'ODCM Units 2/3 (1-19), Unit 1 ODCM 1, : . . I.

S023-ODCM 3-5 Revision 33 05-03-99 S02 3 -ODCM

K.-

4.0 EQUIPMENT 4.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SPECIFICATION 4.1.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 4-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 1.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with Section 1.4.

APPLICABILITY: At all times ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification.

immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE.

take the ACTION shown in Table 4-1. Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument(s) remain inoperable for greater than 30 days, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

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

SURVEILLANCE REQUIREMENTS

.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4-2.

.2 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after a change in pump operation that affects dilution flow has been completed, all pumps required to be providing dilution to meet the site radioactive effluent concentration limits of Specification 1.1.1 shall be determined to be operating and providing dilution to the discharge structure.

S023-ODCM 4-1 Revision 36 02-28-01 S02 3 -ODCM

TABLE 4-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT* OPERABLE ACTION

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

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

b. Steam Generator Blowdown Processing System (Neutralization Sump) 1 29 Full Flow Condensate Polisher Effluent Line - 2(3)RT-7817

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

d. Steam Generator (E088) Blowdown Effluent Line - 2(3)RT-6759 1 29

e. Steam Generator (E089) Blowdown Effluent Line - 2(3)RT-6753 1 29

2. PROCESS FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line 1 31

b. Steam Generator Blowdown Processing System (Neutralization Sump),

Full Flow Condensate Polisher Effluent Line 1 31

c. Turbine Plant Sumps, Auxiliary Building Sump Com ponent Cooling Water Sumps, Storage Tank Area Sumps Effluent Line- 1 31

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

e. Steam Generator (EO89) Blowdown Bypass Effluent Line 1 31

3. DATA ACQUISITION SYSTEM (CONTROL ROOM ALARM ANNUNCIATION) 1 32 S023-ODCM 4-2 Revision 34 11-09-99

TABLE 4-1 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT* OPERABLE ACTION

4. CONTINUOUS COMPOSITE SAMPLERS

a. Turbine Plant Sump, Auxiliary Building Sumps - 2(3) APC 5887 I 33

b. Blowdown Processing System Neutralization Sump - 2(3) APC 3772 1 33

c. Steam Generator (EO88) Blowdown to By pass, Steam Generator (E088) Blowdown - 2(3) APC 4077 1 33

d. Steam Generator (E089) Blowdown to Bypass, Steam Generator (E089) Blowdown - 2(3) APC 4076 1 33 5023-ODCM 4-3 Revision 36 02-28-01

TABLE 4-1 (Continued)

TABLE NOTATION

MonitorRecorders are not required for the Operability of the monitor, providingthe inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the-monitor has indication, alarm capability (ifapplicable),- proper response (based on surveillance requirements)-and isolation function (ifapp icable), the loss of the recorder does not render the monitor inoperable.

ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases may continue provided that:prior to initiating a release:

a. ,At least two independent samples are analyzed in accordance with Specification 1.1.1 and

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

ACTION 29 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 microcuries/gram:

a. At least once per-8 hours when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT 1-131;

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/gram DOSE EQUIVALENT 1-131; or

c. Lock closed valve SZ(3)1318MU577 and divert flow to T-064 for processing as liquid radwaste.

ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of collection time for gross radioactivity (beta or gamma) at a limit of detection of at least 10- microcuries/ml or lock closed valve S2(3)2419MU077 or S2(3)2419MU078 and divert flow to the radwaste sump for processing as liquid radwaste.

S023-ODCM 4-4 Revision 34 11-09-99 S02 3 -ODCM

I TABLE 4-1 (Continued)

TABLE NOTATION ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent-releases via this pathway may continue provided the process flowirate 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.

Loss of process flow instrument(s) results in the associated gross activity monitor becoming INOPERABLE. Perform the compensatory action for the inoperable gross activity monitor in addition to this compensatory action. L2(3)RT-7817, 2(3)RT-7821, 2/3RT-7813]

ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the monitor is verified OPERABLE 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.

ACTION 33 - With the number of channels OPERABLE less than required by Minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are collected daily, and composited and analyzed weekly:

-a. at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , not to exceed 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months

b. at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for steam generator when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT 1-131.

S023-ODCM 4-5 Revision 36 02-28-01 S023-ODCM

TABLE 4-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL CHANNEL SOURCE CHANNELS FUNCTIONAL INSTRUMENT** -CHECK CHECK CALIBRATION

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

a. Liquid Radwaste Effluents Line - 2/3RT-7813 D P R(2) 0(1)

b. Steam Generator Blowdown Processing System (Neutralization Sump), Full Flow Condensate Polisher Effluent Line - 2(3)RT-7817 D M R(2)

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

d. Steam Generator (E088) Blowdown Bypass Effluent Line - 2(3)RT-6759 D M R(2) Q(1)

e. Steam Generator (E089) Blowdown Bypass Effluent Line - 2(3)RT-6753 D M R(2) Q(1)

2. PROCESS FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line D(3) NA R

b. Steam Generator Blowdown Processing System (Neutralization Sump)', Full Flow Condensate Polisher Effluent Line D(3) NA R Q

c. Turbine'Plant Sump, Auxiliary Building Sump, Component Cooling Water Sumps, Storage Tank Area Sumps Effluent Line D(3) NA R Q

d. Stea~m Genereator (E088) Blowdown Bypass Effluent Line D(3) NA R Q

e. Steam Generator (E089) Blowdown Bypass Effluent Line D(3) NA R Q

3. DATA ACQUISITION SYSTEM (CONTROL ROOM ALARM ANNUNCIATION) D NA NA(4) Q S023-ODCM 4-6 Revision 34 11-09-99

TABLE 4-2 RADIOACTIVE -LOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNELS FUNCTIONAL INSTRUMENT"* CHECK CHECK CALIBRATION TEST

4. CONTINUOUS COMPOSITE SAMPLERS

a. Turbine Plant Sump, Auxiliary building Sumps -

2(3) APC 5887 D(5) N/A R Q

b. Blowdown Processing System Neutralization Sump -

2(3) APC 3772 D(5) N/A R Q

c. Steam Generator (EO8) Blowdown to Bypass, Steam Generator (EO88) Blowdown - 2(3) APC 4077 D(5) N/A R Q

d. Steam Generator (EO89) Blowdown to Bypass, Steam Generator (EO89) Blowdown - 2(3) APC 4076 D(5) N/A R Q S023-ODCM 4-7 Revision 36 02-28-01

i' TABLE 4-2 (Continued)

TABLE NOTATION

- Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (ifapplicabie); proper response (based on surveillance requirements) and isolation function' (ifapplicable). the loss of the recorder does not render the monitor inoperable.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation actuation signal, automatic pathway isolationt, and Control Room alarm annunciation if any of the following conditions exist:

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

2. Circuit failure.

t Automatic pathway isolation is tested on a once per refueling period.

Down scale failure testing is bounded by administrative limitation on monitor setpoint which ensure monitor alarm and release termination occur prior to reaching the level of monitor saturation.

If the instrument controls are not in the operate mode, procedures shall require that the channel be declared-inoperable.

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

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

(4) The Data Acquisition System (DAS) software and hardware do not require Channel Calibration. The DAS software is quality affecting and controlled by the site Software Modification Request process under procedure S0123-V-4.71, Software Development and;Maintenance. The DAS hardware is installed plant equipme'ntand controlled bytthe site design change process utilizing procedure S0123-XXIX-2.10; Design-Change Process or S0123-XXIV-10.21, Field Change Notice (FCN) and Field Interim Design Change Notice (FIDCN).

(5) CHANNEL CHECK shall consist of verifying compositor switch positions and installed counter setting, and comparing integrator readings to sample volume collected.

S023-ODCM 4-8 Revision 36 02-28-01 S02 3 -ODCM

I I 4.0 EOUIPMENT 4.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SPECIFICATION 4.2.1 The radioactive-gaseous effluent monitoring instrumentation channels shown in Table 4-3 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 2.1.1 are not exceeded.

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

APPLICABILITY: At all times ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table.4-3. Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally,' if the inoperable instrument(s) remain inoperable for greater than 30 days, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE and either the appropriate ACTION items in Table 4-3 not taken or the necessary surveillances not 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.

SURVEILLANCE REOUIREMENTS

.1 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4-4.

S023-ODCM 4-9 Revision 36 02-28-01 S02 3 -ODCM

TABLE 4-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT*** OPERABLE APPLICABILITY ACTION

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release - 2/3RT-7808, or 3RT-7865-1 1

35

b. Process Flow Rate Monitoring Device 1

36

2. CONDENSER EVACUATION SYSTEM

a. Noble Gas Activity Monitor - 2(3)RT-7818, or 2(3)RT-7870-1 1 ** 37

b. Iodine Sampler 1 ** 40

c. Particulate Sampler 1 ** 40

d. Associated P&I Sample Flow Measuring Device 1 ** 36

e. Process Flow Rate Monitoring Device 1(1) ** 36

3. PLANT VENT STACK

a. Noble Gas Activity Monitor - 2/3RT-7808, or 2RT-7865-1 and 3RT-7865-1 1(3

37

b. Iodine Sampler., 1(3

40 C. Particulate Sampler- 1(3

40

d. Associated P&I Sample Flow Measuring Device 1(3

36

e. Process Flow Rate Monitoring Device - 2/3RT-7808, or 2RT-7865-1 and 3RT-7865-1 1

36

4. CONTAINMENT PURGE SYSTEM

a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release - 2(3)RT-7828, or 2(3)RT-7865-1 1

38

b. Iodine Sampler 1

40

c. Particulate Sampler 1

40

d. Associated P&I Sample Flow Measuring Device 1

36

e. Process Flow Rate Monitoring Device 1

36

5. DATA-ACQUISITION SYSTEM (CONTROL ROOM ALARM ANNUNCIATION) 1

42 S023-ODCM 4-10 Revision 34 11-09-99

TABLE 4-3 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT*** OPERABLE APPLICABILITY ACTION

6. SOUTH YARD FACILITY (SYF) WORK AREA

40

a. Particulate Activity Monitor - SYFRT-7904 1

40

b. Iodine Sampler 1 C. Particulate Sampler 1 40

d. Associated P&I Sample Flow Measuring Device 1 41

41

e. Process Flow Rate Monitoring Device 1

7. SOUTH YARD FACILITY (SYF) DECONTAMINATION UNIT

a. Particulate:Activity Monitor - SYFRT-7905 I 40

b. Iodine Sampler 1 40 C. Particulate Sampler 1 40

d. Associated P&I Sample Flow Measuring Device 1 41

e. Process Flow Rate Monitoring Device 1 41

8. SOUTH YARD FACILITY DATA ACQUISITION SYSTEM OR DATALINK TO MAIN DAS 1 43 S023-OCM 4-11 Revision 35 02-29-00

TABLE 4-3 (Continued)

TABLE NOTATION

At all times.

- MODES 1-4 with any main steam isolation valve and/or any main steam isolating bypass valve not fully closed.

- - Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability,(if applicable), proper response (based on surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.

(1) 2(3)RT-7818 is not equipped to-monitor process flow. If another means of continuously monitoring process flow is not available, then comply with ACTION 36.

(2) Deleted.

(3) Due to unequal mixing in the Plant Vent Stack, both 2RT-7865-1 and 3RT-7865-1 are required to-be-operable when 2/3RT-7808 is inoperable.

ACTION 35 - With the number of channelsOPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be

.released to the environment provided that prior to initiating the release:

-a. At least two independent samples of the tank's contents are analyzed, and

b. .At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend releases of radioactive effluents via this pathway.

S023-ODCM 4-12 Revision 34 11-09-99 S02 3 -ODCM

TABLE 4-3 (Continued)

TABLE NOTATION ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:

a. The process flow rate is-estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during actual releases. In addition, a new flow estimate shall 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. System design characteristics may be used to estimate process'flow.

b. The particulate and iodine (P&I) sample flow rate 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 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.

ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the effected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 2-1.

ACTION 41 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:

a. The process flow rate is estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during times of building occupation. System design characteristics may be used to estimate flow.

b. The particulate and iodine (P&I) sample 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 times of building occupation.

ACTION 42 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the monitor is verified operable 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.

ACTION 43 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the monitor is verified OPERABLE by performing a channel check at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during times of building occupation.

S023-ODCM 4-13 Revision 35 02-29-00 S02 3 -ODCM

TABLE 4-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE FOR WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE INSTRUMENT*** CHECK CHECK CALIBRATION TEST IS REQUIRED

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor -

Providing'Alarm and Automatic Termination of Release -

2/3RT-7808, 3RT-7865-1 P P R(3) Q(1) *

b. Process Flow Rate Monitoring Device P NA R Q *

2. CONDENSER EVACUATION SYSTEM

a. Noble Gas7Activity Monitor -

2(3)RT-7818, 2(3)RT-7870-1 D M R(3) Q(2) **

b. Iodine Sampler ; - W NA NA NA **

c. Particulate Sampler - W NA NA NA **

d.' Associated Samp e Flow - -

Measuring Device D NA R Q **

e. Pr6cess'Flow Rate Monitoring Device (2(3)RT-7870-1) D NA R Q **

S023-ODCM 4-14 Revision 26 12-20-93

TABLE 4-4 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE FOR WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE INSTRUMENT*** CHECK CHECK CALIBRATION TEST IS REQUIRED

3. PLANT VENT STACK

a. Noble Gas Activity Monitor - 0 M R(3) Q(2)

2/3RT-7808, 2RT-7865-1, 3RT-7865-1

b. Iodine Sampler W NA NA NA *

c. Particulate Sampler W NA NA NA *

d. Associated Sample Flow Measuring Device D NA R Q *

e. Process Flow Rate Monitoring Device D NA R Q

4. CONTAINMENT PURGE SYSTEM

a. Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release -

2(3)RT-7828, 2(3)RT-7865-1 D P(4) R(3) Q(M) *

b. Iodine Sampler W NA NA NA *

c. Particulate Sampler W NA NA NA *

d. Process.Flow Rate Monitoring Device D NA R Q *

e. Associated Sample Flow Measuring Device D NA R Q *

5. DATA ACQUISITION SYSTEM (CONTROL ROOM ALARM ANNUNCIATION) D NA NA(8) Q

S023-ODCM 4-15 Revision 34 11-09-99

A'-

TABLE 4-4 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE FOR WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE INSTRUMENT*** CHECK CHECKX-' CALIBRATION TEST IS REQUIRED

6. SOUTH YARD FACILITY (SYF) WORK AREA

a. Particulate Activity Monitor - D M R(3) Q(7)

SYFRT-7904 :

b. Iodine Sampler W -NA NA NA

c. Particulate Sampler W NA NA NA *

d. Process Flow Rate Monitoring (

Device 3(5) NA R Q

e. Associated Sample Flow Measuring D5 N -

Device D(5) NA R Q

7. SOUTH YARD FACILITY (SYF) DECONTAMINATION UNIT'

a. Particulate-Activity Monitor - D M R(3) .Q(7)

SYFRT-7905

b. Iodine Sampler W NA NA NA *

c. Particulate'Sampl'er. W'. -NA NA NA *

d. Process Flow Rate Monitoring ' N - R Q Device ' 'D(6) -NA .R 'Q*

e. Associated Sample Flow Measuring Device D(6) NA R Q *

8. SOUTH YARD FACILITY ACQUISITION SYSTEM OR DATA LINK TO MAIN DAS 0 NA NA(8) Q

NOTE: For 6 and 7, surveillance requirements to take effect upon DCP A-7022.OOSC turnover of these instruments.

S023-ODCM 4-16 Revision 35 02-29-00

II TABLE 4-4 (Continued)

TABLE NOTATION

At all times.

- Modes 1-4 with any main steam isolation valve and/or any main steam isolating bypass valve not fully closed.

Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e.. feedback signal)., As long as the monitor has indication, alarm capability (if applicable), proper response -(based on surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation actuation signal, automatic pathway isolationt, and Control Room alarm annunciation if any of the following conditions exist:

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

2. Circuit failure.

t Automatic pathway isolation is tested on a once per refueling interval.

t The main containment purge isolation valves are required to be tested, in Mode 5 prior to performing initial core alterations. Containment purge valves are not required to be tested for automatic isolation in the event of a mid-cycle outage.

Down scale failure testing is bounded by administrative limitation on monitor setpoints which ensure monitor alarm and release termination occur prior to reaching the level of monitor saturation.

If the instrument controls are not set in the operate mode, procedures shall call for declaring the channel inoperable.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:#

1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

Down scale failure' testing is bounded by administrative limitation on monitor setpoints which'ensure monitor alarm and release termination occur prior to reaching the level:.of monitor saturation.

If the instrument controls are not set in the operate mode, procedures shall call for declaring the channel inoperable.

S023-ODCM 4-17 Revision 30 05-28-97 S023 -ODCM

TABLE 4-4 (Continued)

TABLE NOTATION (Continued)

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

(4) Prior to each release and at least once per month.

(5) Daily checks only required during times of building occupation.

(6) CHANNEL CHECK required by Health Physics daily for each day that the COz Decontamination Unit is used.

(7) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation actuation signal, if any of the following conditions exist:

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

2. Circuit failure.

Automatic pathway isolation is tested on a once per 24 month interval.

Down scale failure testing is bounded by administrative limitation on monitor setpoints which ensure monitor alarm and release termination occur prior to reaching the level of monitor saturation.

(8) The Data Acquisition System (DAS) software and hardware do not require Channel Calibration. The DAS software is quality affecting and controlled by the site Software Modification Request process under procedure S0123-V-4.71, Software Development and Maintenance. The DAS 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 Field Interim Design Change Notice (FIDCN).

S023-ODCM 4-18 Revision 34 11-09-99 S02 3 -ODCM

i~I I 4.3 OPERABILITY 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 4-5 thru 4-7.

S023-ODCM 4-19 Revision 21 02-15-90 S023 -ODCM

i FIGURE 4-5 SONGS 2 & 3 RADIOACTIVE LIQUID WASTE TREATMENT SYSTEMS S023-ODCM 4-20 Revision 28 12-21-95 S02 3 -ODCM

FIGURE 4-6 SONGS 2 & 3 RADIOACTIVE GASEOUS WASTE TREATMENT SYSTEMS q.--- ATMOSPHERE ----- >

I at on

_ Hon tor (1)2(3)RT-7865-1 can be aligned to either containment purge or the plant vent stack S023-ODCM 4-21 Revision 28 12-21-95

A'-'

FIGURE 4-7 SOLID WASTE HANDLING Spent Resin Particolate Precess filters Low Level Dry Active Waste Protective Clething LECEtR:

SIT: Spent Resin Tank 11P1IF:Muiti Purpose Handlinig Faci1ty MX:lon Exchaster S023-ODCM 4-22 Revision 28 12-21-95

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 MonitorinQ Program SPECIFICATION 5.1.1 The radiological environmental monitoring program shall be conducted as specified in Table 5-1. The requirements are applicable at all times.

APPLICABILITY: At all times ACTION:

a. Should the radiological environmental monitoring program not be conducted as specified in Table 5-1, in lieu of any other report required by Technical Specification-Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission. in the Annual Radiological Environmental Operating Report (see Section 5.4), a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. Should the level of radioactivity in an environmental sampling medium exceed the reporting levels of Table 5-2 when averaged over any calendar quarter, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission. within 30 days-from the end of the affected calendar quarter a Report pursuant to 10 CFR 50.73. When more than one of the radionuclides in Table 5-2 are detected in the sampling medium, this report shall be submitted if:

concentration I) + concentration (2) . . .> 1.0 limit level (1) limit level (2)

c. When radionuclides other than those in Table 5-2-are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specification(s) 1.2.1. 2.2.1 or 2.3.1, as appropriate. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report (see Section 5.4).

S023-ODCM 5-1 Revision 30 05-28-97 S02 3 -ODCM

-i 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued)

ACTION: (Continued)

d. With fresh' leafy vegetable samples or fleshy vegetable samples unavailable from one or more of the sample locations required by Table5-1,' identify specific locations-for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM.' -The-specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification 5.7.1, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new'location(s) with supporting information identifying the cause of the unavailability of samples and justifying 'the selection of the new location(s) for obtaining samples.

SURVEILLANCE REOUIREMENTS

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

S023-ODCM 5-2 Revision 36 02-28-01 S02 3 -ODCM

an 0

w 8IJ 0 TABLE 5-1 r)

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

1. AIRBORNE Samples from at least 5 locations Continuous operation of Radioiodine cartridge. Analyze Radioiodine sampler with sample at least once per 7 days for and 3 samples from offsite locations collection as required 1-131. Particulate sampler.

Particulates (in different sectors) of the by dust loading, but at Analyze for gross beta highest calculated annual average least once per 7 days.d radioactivity >-24 hours ground level D/Q. following filter change.

Perform gamma isotopich analysis 1 sample from the vicinity of a on each sample when gross beta community having the the highest activity is > 10 times the calculated annual average ground- yearly mean-of control samples.

level D/Q. Perform gamma isotopic analysis on composite (by location) 1 sample from a control location sample at least once per 15-30 km (10-20 miles) distant 92 days.

and in the least prevalent wind direction'

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

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 is in special interest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations.

S023-ODCM 5-3 Revision 21 02-15-90

TABLE 5-1 (Continued)

RADIOLOGrCAL ENVIRONMENTAL MONITORING PROGRAMM Exposure Pathway Number of Samples Sampling and and/or SamDle and SamDle Locations' Collection Frequencv' Type and Frequency of Analyses

3. WATERBORNE

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

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

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

Shoreline

d. Ocean 5 locations At lleast once per Gamma isotopic analysis of each Bottom ; - 184 days. sample.' I ' -

Sediments S023-ODCM 5-4 Revision 32 02-25-99

TABLE 5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Sample and Sample Locations' Colection Frequency' Tvye and Frequencv of Analyses

4. INGESTION

a. Nonmigratary 3 locations One sample in season, Gamma isotopic analysis on Marine or at least once per edible portions.

Animals 184 days if not seasonal. One sample of each of the follow-ing species:

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

2. Crustaceae-such as crab or lobster.

3. Mollusks-such as limpets, seahares or clams.

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

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

S023-ODCM 5-5 Revision 21 02-15-90

en 0

LA) 0I 0 TABLE 5-1 (Continued) 4..

.7.

TABLE NOTATION

a. Sample locations are indicated on 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. - J

e. Regulatory, Guide 4.13 provides minimum acceptable performance criteria forthermoluminescence dosimetry (TLO) systems used for environmental monitoring. One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or-more phosphors in a packet may be considered as two or more dosimeters. Film badges should not be used for measuring direct radiation.

f. Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly).

g. No drinking water pathway exists at SONGS.

S023-ODCM 5-6 Revision 32 02-25-99

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

H-3 2 x 104" Mn-54 1 x lo, 3 x 10' Fe-59 4 x 10 I x 10' Co-58 Ix 10i 3 x 10' Co-60 3x 102 1x 10' Zn-65 3 x 101 2 x 10' Zr-95, Nb-95 4 x 10?

I-131 2(b) 0.9 1 x 102 Cs-134 30 10 1x103 l X103 Cs-137 50 20 2 x 103 2 x 103 Ba-140, La-140 2 x 102 (a) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a (b) value of 30,000 pCi/l may be used.

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

I;I S023-ODCM 5-7 Revision 30 09-28-97

TABLE 5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS=

MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)'

Airborne Particulate Water or Gases Marine Animals Local Crops Sediment Analysis (pci/i) (pCi//m 3) (pCi/Kg, wet) (pCi/Kg, wet) (pCi/Kg, dry) gross beta 4 1 x 10' H-3 2000 {b Mn-54 15 130 Fe-59 260 Co-58, 60 130'.

. ~,. 1 Zn-65 . '30

~-.15 260 Zr-95, Nb-95 l(d)

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 S023-ODCM 5-8 Revision 30 09-28-97

I 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 x 106

Y

exp (-Mt) where:

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

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

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

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

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

X is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection or end of the collection period and time of counting (for environmental samples, not plant effluents ).

The value of 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 Dosteriori (after the fact) limit for a particular measurement.*

Wor 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).

S023-ODCM 5-9 Revision 30 05-28-97 S02 3 -ODCM

TABLE 5-3 (Continued)

TABLE NOTATION

b. If no drinking water pathway exists, a value of 3000 pCi/l 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/l may be used.

S023-ODCM 5-10 Revision 30 05-28-97 S023 -ODCM

II 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.2 LAND USE CENSUS SPECIFICATION 5.2.1 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden* of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.

APPLICABILITY: At all times ACTION:

a. With the land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 2.3.1, pursuant to Technical Specification 5.7.1, identify the new locations in the next Annual Radioactive Effluent Release Report.

b. With the land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 5.1, 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 5.7.1, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

SURVEILLANCE REQUIREMENTS

.1 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.

S023-ODCM 5-11 Revision 31 02-27-98 S023-ODCM

5.0 RADIOLOGICAL ENVIRONMENTALVMONITORING (Continued) 5.3 INTERLABORATORY COMPARISON PROGRAM SPECIFICATION 5.3.1 Analyses shall be performed'on radioactive materials supplied as part of an Interlaboratory Comparison Program that'complies with Regulatory Guide 4.15.

APPLICABILITY: At all times ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission'in the Annual Radiological Environmental Operating Report.

SSURVEILLANCE REOUIREMENTS

.1 A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with Section 5.4.1 of this document shall be included in the Annual Radiological Environmental.Operating Report (see Section 5.4).

S023-ODCM 5-12 Revision 32 02-25-99 S02 3 -ODCM

I ~I 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*

5.4.1 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 Section 5.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the 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 of all sampling locations keyed to a table giving distances and directions from the mid-point of reactor Units 2 and 3; and the results of licensee participation in the Interlaboratory Comparison Program, required by Section 5.3.

A single submittal may be made for a multiple unit station, combining those sections that are common to all units at the station.

S023-ODCM 5-13 Revision 32 02-25-99 S02 3 -ODCMt

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 described in Table 5-4 and indicate the distance in miles and the direction, determined from degrees true north, from the center of the Units 2 and 3 building complex. Table 5-6 gives the sector and direction designation for the Radiological Environmental Monitoring Sample Location on Map, Figures 5-1 through 5-5. -

S023-ODCM

-' 14 Revision 36 02-28-01 S02 3 -ODCM

I 11II Page 1 of 6 TABLE 5-4 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 #1) 0.7 WNW 11 Former Visitors' Center 0.4** NW 12 South Edge of Switchyard 0.2** E 13 Southeast Site boundary (Bluff) 0.4** ESE 15 Southeast Site Boundary (Office Building) 0.1** SSE 16 East Southeast Site Boundary 0.4** ESE 17 Transit Dose 18 Transit Dose -

19 San Clemente Highlands 5.0 NNW 22 Former U.S. Coast Guard Station - San Mateo Point 2.7 WNW 23 Samaritan Hospital, San Clemente 8.1 NW

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 S023-ODCM 5-15 Revision 32 02-25-99 S023-ODCM

Page 2 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE*

TYPE OF SAMPLE AND SAMPLING LOCATION*** (miles) DIRECTION*

Direct Radiation (Continued) 31 Aurora Park-Mission Viejo 18.6 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) 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 S023-ODCM 5-16 Revision 32 02-25-99 S02 3 -ODCM

i l Page 3 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE*

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) 0.2** 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) 0.1** 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.

S023-ODCM 5-17 Revision 32 02-25-99 S02 3 -ODCM

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

TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION*

Airborne 1- City of San Clemente (City Hall) 5.1 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 Oceanside City Hall (CONTROL) 15.6 SE Soil Samples' l 1 Camp San Onofre 2.6 NE 2 Old Route 101 - (East Southeast) 3.0 ESE 3 Basilone Road/1-5 Freeway Offramp 2.0 NW 5 Former Visitor's Center 0.4** NW 6 Oceanside (CONTROL) 16.0 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.

- 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. [A S023-ODCM 5-18 Revision 38 02-28-03 S02 3 -ODCM

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

TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION*

Drinking Water 4 Camp Pendleton Drinking Water Reservoir 2.2 NNW 5 Oceanside City Hall (new CONTROL) 15.6 SE Shoreline Sediment (Beach Sand)

I 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 should be in Section G or F, 15 to 25 miles from site. The control location will be selected based on sample availability. The exact location shall be noted in the Annual Radiological Environmental Operating Report.

S023-ODCM 5-19 Revision 37 02-28-02 S023-ODCM

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

TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION*

Non-Migratory MarineAnimals A Unit 1 Outfall 0.9 WSW B Units 2 and 3 Outfall 1.5 SSW C Laguna Beach (CONTROL) 18.2 NW Kel p' 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.

t Kelp Samples are not required by Technical Specifications.

JR S023-ODCM

-: 5-20 Revision 38 02-28-03 S02 3 -ODCM

I .1II TABLE 5-5 PIC - RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS Theta DISTANCE*

PRESSURIZED ION CHAMBERS (Degrees)* Meters nmiles DIRECTION/SECTOR*

S1 San Onofre Beach 2980 1070 0.7 WNW P S2 SONGS Former Evap. Pnd 313° 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 46° 940 0.6 NE C S7 MCB - Camp Pendleton 700 870 0.6 ENE D S8 MCB - Camp Pendleton 98° 1120 0.7 E E S9 San Onofre State Beach 121} 940 0.6 ESE F

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

S023-ODCM 5-21 Revision 36 02-28-01 S023-ODCM

-s-TABLE 5-6 SECTOR AND DIRECTION DESIGNATION FOR RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATION MAP DEGREES TRUE NORTH FROM SONGS 2 AND 3 MID-POINT NOMENCLATURE Sector Center Sector 22.50 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 56.25 C NE 56.25 67.5 78.75 D ENE 78.75 90.0 .101.25 E E 101.25 112.0 123.75 F ESE 123.75 135.0 146.25 G SE 146.25 157.0 168.75 H SSE 168.75 180.0 191.25 J S 191.25 202.5. 213.75 K SSW 213.75 225.0 236.25 L SW 236.25 247.5 258.75 M WSW 258.75 270.0 281.25 N W 281.25 292.5 303.75 P WNW 303.75 315.0 326.25 Q NW 326.25 337.5 348.75 R NNW

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

S023-ODCM 5-22 Revision 21 02-15-90 S023 -ODCM

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1r X 6.0 ADMINISTRATIVE 6.1 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable through these Specifications.

ACTION 6.1.1 ACTION shall be that part of a specification which prescribes remedial measures required under designated conditions.> - '

CHANNEL CALIBRATION 6.1.2 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the'channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the sensor and'alarm'and/or trip functions,' and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 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 FUNCTIONAL TEST 6.1.4 A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signal into channel as close to the sensor as practicable to verify OPERABILITY, including alarm and/or trip functions..-

b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY, including alarm and/or trip functions.

c. Digital computer channels - the exercising of the digital computer hardware using diagnostic programs and the injection of simulated process data into the channel to verify OPERABILITY.

S023-ODCM 6-1 Revision 21 02-15-90 S02 3 -ODCM

A Ii 6.0 ADMINISTRATIVE (Continued)

DOSE EQUIVALENT 1-131 6.1.5 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, I-133, 1-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in International Commission on Radiological Protection Publication 30, Tables titled Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activities.

FREQUENCY NOTATION 6.1.6 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 6.2.

GASEOUS RADWASTE TREATMENT SYSTEM 6.1.7 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

6.1.8 DELETED MEMBERS OF THE PUBLIC 6.1.9 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 shall include nonemployees of the licensee who are permitted to use portions of the site for recreational, occupational, or purposes not associated with plant functions. This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal Job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.

S023-ODCM 6-2 Revision 36 02-28-01 S023-ODCM

6.0 ADMINISTRATIVE (Continued)

MODE 6.1.10 A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant'temperature, and reactor vessel head closure bolt tensioning specified in Table 6-1 with fuel in the reactor vessel.

OPERABLE - OPERABILITY 6.1.11 A system, subsystem,' train, component or device shall be OPERABLE or. have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant-instrumentation, controls, normal or emergency electrical'power, cooling and seal water, lubrication and other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s).

PURGE - PURGING 6.1.12 PURGE or PURGING is the 'controlled process of discharging air or gas from A confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to'purify'the confinement.

SITE BOUNDARY 6.1.13 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased; or otherwise controlled by the licensee.

SOLIDIFICATION 6.1.14 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides-(free-standing).

S023 -ODCM

~6-3 Revision 31 02-27-98 S02 3 -ODCM

I 6.0 ADMINISTRATIVE (Continued)

SOURCE CHECK 6.1.15 For Victoreen and NMC analog monitors a SOURCE CHECK shall be the qualitative,assessment, of channel response when the channel sensor is exposed to a radioactive source.

[2(3)RT-6753, 2(3)RT-6759, 2(3)RT-7818A]

For Sorrento Electronics digital monitors a SOURCE CHECK shall be the verification of proper com puter response to a check source request. E2(3)RT-7828, 2(3)RT-7865-1, 2(3)RT-7870-1]

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

[2(3)RT-7817, 2(3)RT-7821, 2/3RT-7813, 2/3RT-7808, SYFRT-7904, SYFRT-79051' SURVEILLANCE REOUIREMENT: MEETING SPECIFIED FREQUENCY 6.1.16 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as-measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply.

If a Completion Time requires periodic performance on a "once per ... " basis, the above Frequency extension applies to each performance after the initial performance.

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 to any Action Statements.

THERMAL POWER 6.1.17 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

VENTILATION EXHAUST TREATMENT SYSTEM 6.1.18 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

S023-ODCM 6-4 Revision 34 11-09-99 S023-ODCM

6.0 ADMINISTRATIVE (Continued)

VENTING 6.1.19 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during YENTING. Vent used in system names does not imply a VENTING process.

S023-ODCM 6-5 Revision 33 05-03-99 S02 3 -ODCM

II TABLE 6-1 OPERATIONAL MODES REACTIVITY % OF RATED AVERAGE COOLANT OPERATION MODE CONDITION. (Kefit THERMAL POWER(a) TEMPERATURE (OF)

1. POWER OPERATION > 0.99 > 5% NA

2. STARTUP > O.99 < 5% NA

3. HOT STANDBY < 0.99 NA > 350 0F

4. HOT SHUTDOWN < 0.99 NA 350 0 F> TaT9>2000F

5. COLD SHUTDOWN (b) < 0.99 NA < 200 0 F

6. REFUELING (c) NA NA NA a Excluding decay heat.

b All reactor vessel head closure bolts fully tensioned.

c One or more reactor vessel head closure bolts less than fully tensioned.

S023-ODCM 6-6 Revision 33 05-03-99 S02 3 -ODCM

kw"- 1 TABLE 6-2 FREQUENCY NOTATION NOTATION FREQUENCY

- S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D At least once-per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months w At least once per 7 days M At least on'ce per 31 days Q At least once'per 92 days SA At least once.per 184 days.

R At least once per 18 months*

ISp Prior to each-reactor startup

. P Completedprior to each release N.A. Not applicable Refueling Not to exceed 24'months Interval

A month is'defined a'sa 31-day period.

. . . . 4 . ..

S023-ODCM 6-7 Revision 22 08-02-90 S02 3 -ODCM

z5 -W4 6.0 ADMINISTRATIVE (Continued) 6.2 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT*

6.2.1 Routine radioactive effluent release reports covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

6.2.2 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Revision 1, June 1974, 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 (ifmeasured) on magnetic tape.. or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 1-2 and 2-2) during the report 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 pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

A single submittal may be madefor a maultiple unit station. The submittal should combine those sections that are cramon to all units at the Station; however. for units with separate radvaste systems. the submittal shall specify the releases of radioactive material from each unit.

S023-ODCM 6-8 Revision 26 12-20-93 S023 -ODCM

6 A (nie ,N tTTV 6.0 ADMINISTRATIVE (Continued) 6.2 ADMINISTRATIVE CONTROLS -(Continued) 6.2.2 (Continued)

The radioactive effluent release report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12.consecutive months to show conformance with 40 CFR 190- Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev., 1.

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

a. Container volume,

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

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

d. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

e. Type of container '(e.g., LSA, Type A, Type B, Large Quantity), and

f. 'Solidification Agent (e.g., cement, urea formaldehyde).

The radioactive effluent release report shall include unplanned'releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made L during the reporting period.

The radioactive'effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

S023-ODCM 6-9 Revision 37 02-28-02 S02 3 -ODCM

6.0 ADMINISTRATIVE (Continued) 6.3 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, &

Gaseous)

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

1. Shall be reported to the Commission in the Annual Radioactive Effluent Release'Report for the period in which the evaluation was performed pursuant to Quality-Assurance Program Description (SCE-1-A), Subsection 17.2.20.3.1.i. The discussion of each change shall contain:

a. A summary of the evaluation'that led to the determination that the change could be made in accordance with 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 predicted 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 individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto;

f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents to the actual release for the period prior to when the changes are to be 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 Quality 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.

5023-ODCM 6-10 Revision 36 02-28-01 S023-ODCM

at- - -

6.0 ADMINISTRATIVE (Continued) 6.4 BASES LIQUID EFFLUENTS CONCENTRATION (1.1) 6.4.1 This spe'cification is provided to ensure that the concentration.of radioactive materials released in liquid

-waste effluents.from the site will be less than the concentrationtlevels'specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This-limitation provides additional assurance;that the levels of radioactive materials in bodies of water outside the site will result in exposures within. (1) the Section II.A design objectives of Appendix I,-10 CFR 50, to an individual, and (2) the limits of 10CFR 20.106(e) to the population. The

-concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its 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.

DOSE (1.2) 6.4.2 This specification is provided to implement the require-ments of.Section II.A, III.A and IV;A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section IIA of Appendix I`-The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents-will be kept "as low as is reasonably achievable. :The dose calculations in the ODCM implement the requirements .inSection III.A of Appendix I that conformance with :the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an'individual through appropriate'pathways is unlikely to be substantially underestimated.. The equations specified in the ODCM for

-' calculating the.doses'due 'to the actual release rates of radioactive materials In liquid effluents are consistent

with the methodology provided in Regulatory Guide 1.109, "Calculation of. Annual Doses to'Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating

-Compliance'with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing

'Appendix I",April 1977. .

This specification applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

S023-ODCM Revision 21 6-11 02-15-90 S02 3 -ODCM

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

LIQUID WASTE TREATMENT (1.3) 6.4.3 The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid eff uents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid'effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10' CFR Part 50 and the design objective given inSection II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR'Part 50, for liquid effluents.

GASEOUS EFFLUENTS DOSE RATE (2.1) 6.4.4 This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual 'dose limits are the doses' associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the

'limits,specified in Appendix B,. Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)); For individuals who may at times be within the site boundary,.the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above b'ackground to an individual at or beyond the site boundary to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to 'less than or equal to 1500 mrem/year.

This specification applies to the release of gaseous effluents from all reactors at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

S023-OOCM Revision 21 6-12 02-15-90 S02 3 -ODCM

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

DOSE - NOBLE GASES (2.2) 6.4.5. This specification is provided to implement the requirements of Sections II.B. III.A and IV.A of Appendix 1,-10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I.'The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in.Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents.will be kept "as low as is reasonably achievable.": The:Surveillance Requirements implement the requirements-in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by

'calculational procedures based on models and data such that the actual exposure of an individual through

.appropriate'pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for-calculating the doses-due to the actual release rates of radioactive noble.gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, -"Calculation of Annual Doses to Man from Routine Releases of -Reactor Effluents for the Purpose of Evaluating-Compliance with 10OCFR Part 50, Appendix I,"

Revision '1,' October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and DispersionIof Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. For MEMBERS OF THE PUBLIC who traverse the SITE BOUNDARY via highway 1-5, the residency time shall be considered negligible and hence'the dose "0". The ODCM e uations provided for. determining the air doses at the SITE BOUNDARY',are based upon the historical average atmospheric conditions.'

DOSE - RADIOIODINES. RADIOACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM (2.3) 6.4.6 This specification is provided to implement the

.requirements of, Sections II.C, III.A and IV.A of Appendix I, 10 CFR 'Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth 'inSection IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents

%will be kept -"as low as is.reasonably achievable." The ODCM calculational-methods specified in the Surveillance Requirements implement the S023-ODCM 6-13 Revision 22 08-02-90 S023 -ODCM

_!I 6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued) requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the'actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1. October 1977 and Regulatory Guide 1.111, T"Methods. for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,* Revision 1. July 1977.

These equations also~provide for determining the actual doses' based upon the historical. average atmospheric conditions. The release rate specifications for radioiodines, radioactive materials in particulate form and tritium are dependent on the existing radionuclide pathways' to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3)

'deposition onto grassy areas where milk animals and meat producing. animals graze with consumption of the milk and meat by man, and 4) deposition'on the ground with subsequent exposure of man.

GASEOUS RADWASTE TREATMENT (2.4) 6.4.7 The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that 'the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept has low as is reasonably achievable." This specification implements the requirements of' 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the' systems were specified as a suitable fraction of the dose-design objectives set forth in Sections II.B and II.C of Appendix 1, 10 CFR Part 50, for gaseous effluents.

S023-ODCM 6-14 Revision 21 02-15-90 S023-ODCM

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

TOTAL DOSE (3.3) 6.4.8 This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within-the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits. For.the purposes of the Special Report, it may be assumed that the'dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any member of the publiclis estimated to exceed the requirements of 40CFR 190, the Special Report with a request for a variance in accordance with-the provisions of 40 CFR

.190.11, is considered to beea timely request and fulfills the requirements-of:40 CFR 190 until NRC staff action is completed provided the release conditions resulting in violation of:40WCFR 190 have not already been corrected.

An individual'.is-not considered a member of the public during.any period. in which he/she is engaged in carrying out any operationiswhich is part of the nuclear fuel cycle.

RADIOACTIVE LIOQUID EFFLUENTINSTRUMENTATION (4.1) 6.4.9 The radioactive liquid effluent instrumentation is

. . provided-to monitor and control, as applicable, the

,- releases of-radioactive-materials in liquid effluents during :actual'or~potential 'releases of liquid effluents.

The alarm/trip setpoints for'these instruments shall be calculated in-accordance with the procedures in the ODCM to ensure that the-alarm/trip will occur prior to exceeding the limits of 10oCFR Part 20. The OPERABILITY and use;of this instrumentation is consistent with the requirements of General-Design Criteria 60, 63 and 64 of Appendix Ato-10 CFR-Part 50.

S023-ODCM 6-15 Revision 21 02-15-90 S023 -ODCM

II 6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION (4.2) 6.4.10 The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10.CFR Part 20. This instrumenta-tion also includes provisions for monitoring and controlling the-concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements-of General Design Criteria 60, 63 and 64 of.Appendix A to 10 CFR-Part 50.

MONITORING PROGRAM (5.1) 6.4.11 The radiological monitoring program required by this specification.provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation.exposures of individuals resulting from the station-operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable 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.

The detection capabilities required by Table 5-1 are state-of-the-art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an'a priori (before the fact) limit representing the capability of'a measurement system and not as a oosteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

S023-ODCM 6-16 Revision 22 08-02-90 S02 3 -ODCM

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

LAND USE CENSUS (5.2) 6.4.12 This specification is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the monitoring program are made if required by the results of this census. The best survey information from the door-to-door, aerial or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used,

1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and

2) a vegetation yield of 2 kg/square meter.

INTERLABORATORY COMPARISON PROGRAM (5.3) 6.4.13 The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

S023-ODCM 6-17 Revision 22 08-02-90 S023-ODCM

.; I -- -

February 28, 2003 Mr. J. J. Wambold

SUBJECT:

Revision 20 to Unit 1 Offsite Dose Calculation Manual (ODCM)

In accordance with Technical Specification D6.5.2.9 and D6.14;2, Revision 20 to the Unit 1 Offsite Dose Calculation Manual has been prepared and reviewed for your approval.

This change incorporates 1) updates related to the recent Land Use Census and

2) addition of a note explaining that Soil and-Kelp sample locations are not required by the Technical Specifications.

None of the changes in this revision-will 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 the Nuclear Safety Group as required by Technical Specification D6.5.2.9.

Please contact me if there are any questions.

F. Hirsch Manager, Chemistry Approved by:

,6. /.Wambold Vice President Nuclear Generation RECEIV0DM Attachment FEB 28 M03 cc: W. Strom 8WERILE0OPY CDM-SONGS Chem File Site File Copy SOl -ODCM

I -

. : J February 28. 2003

SUBJECT:

Unit I OFFSITE DOSE CALCULATION MANUAL Revision 20 Enclosed is Revision 20 to the Unit 1 Offsite Dose Calculation Manual (ODCM).

This change incorporates, 1) updates related to the recent Land Use Census and

2) addition of a note explaining that Soil and Kelp sample locations are not required by the Technical Specifications.

This change does not require an Effluent/ODCM Evaluation.

Minor format changes, correction of typographical errors, and removal of previously blank pages have been made and are described in the attached List of Affected Pages. Per NRC Generic Letter 89-01, no safety reviews were required or performed for editorial changes or changes made to reflect actual plant operation.

None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations. The level of radioactive effluent control required by 10CFR20, 40CFR190, IOCFR50.36a, and Appendix I to 10CFR50 will be maintained.

Page 1 of 2 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 The following is a complete list of the changes:

OLD NEW CHANGE REASON Table of Updated page numbers throughout document as a result of removing blank F Contents pages and adding new RjTable.

Section 2 Updated page numbers as a result of removing blank pages and adding new R. F Table.

2-21 2-21 Updated CLF due to Land Use Census Update. R 2-24 Removed previously blank page F 2-27 Added a new page inTable 2-11 to include the Rec Bldg Staff in Sector 0 A due to the Land Use Census>Update.

2-31 2-31 Updated Dose Parameters in Table 2-11, Outage Workers due to the Land Use R Census Update.

5-21 5-21 Added note: Soil Samples are not required by Technical Specifications'. A 5-22 5-22 Corrected Direction for SONGS Garden from NW to NNW. F 5-23 5-23 Added note: Kelp Samples are not required by Technical Specifications". A Paae 2 of 2 SO -ODCM

I I OFFSITE DOSE CALCULATION MANUAL NUCLEAR ORGANIZATION UNIT 1 SO1-ODCM Revision 20 02-28-03 SO1-ODCM

- DDCM 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 Determination 1-15 1.4.2.1 Reheater Pit Sump Effluent Line (RT-2100) 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 14 ii 02-25-99 SO1 -ODC

I I ODCM TABLE OF 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, Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form . . . . .. ..... . . . . . . . 2-8

.wwwwwwwwwwwwwwwwwwwwwwwwwwww 2.3.1 Specification . . . . . . . . 2-8 2.3.2 Surveillance . . . . . . . . 2-9 2.4 Gaseous Waste Treatment - DELETED 2.5 Gaseous Effluent Monitor Setpoints ... 2-10 2.5.1 Plant Vent Stack . ... .. 2-10 2.6 Gaseous Effluent Dose Rate ....... 2-13 2.6.1 For Noble Gases . . . . 2-13 2.6.2 For I-131, 1-133, Radioactive Materials in Particulate Form with Half Lives Greater than Eight Days and H-3 . . . . . . . . . . 2-14 2.7 Gaseous Effluent Dose Calculation ... 2-15 2.7.1 Dose From 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 1-131, I-133. Radioactive Material in Particulate Form and H-3 . . . . . . . . . 2-17 2.7.2.1 For Historical Meteorology . . 2-17 2.7.2.2 For Meteorology Concurrent with Release . . . 2-18 S01-ODCM Revision 14 iii 02-25-99 S01-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 Publ iic 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 SO1 -ODCM

'If ODCM TABLE OF CONTENTS (CContinued)

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 mReport . 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 S01-ODCM Revision 8 v 06-29-92 SO -ODCM

-31 i I ODCM LIST OF FIGURES Fintirp Title Pape 4-1 SONGS 1 Liquid Waste-Discharge Systems . . . 4-13 4-2 SONGS 1 RadioactivefGaseous-Waste Systems . . .. . . . 4-14 4-3 SONGS 1 Solid Waste Handling . . . . . . . . . . . . . 4-15 5-1 Radiological Environmental Monitoring Sample Locations 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

, yevi 02-27-98 SOl -ODC14

I I 1*t ODCM LIST OF TABLES Table Title Paap 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 PI ... .. .. .. . . . . . . . . . . . . 2-20 2-5 Controlling Location Factors .. . .. . . . . . . . . . . . 2-21 2-7 Dose Parameters R1 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 R. 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 R1 for Sector D . . . . . . . . . . . . . . . 2-34 2-14 Dose Parameters R. for Sector E . . . . . . . . . . . . . . . 2-35 2-15 Dose Parameters R. for Sector F . . . . . . . . . . . . . . . 2-37 2-16 Dose Parameters RI for Sector G . . . . . . . . . . . 2-3B SO1-ODCM Revision 14 vii 02-25-99 S01-ODCM

ODCM LIST OF TABLES (Continued)

Tahle Title ~I- Niao 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 S01-ODCM Revision 14 viii 02-25-99 SO1-ODCM

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

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

SOl-ODCM Revision 8 ix 06-29-92 SO0 -ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS 1.1 LIQUID EFFLUENTS CONCENTRATION ' '

1.1.1 SPECIFICATION ADlOicability: At all times.

Objective: Maintain the concentration of radioactive liquid material released from the site below 10 CFR 20 1 imits.<

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 2x10' pCi/ml.

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 8 1-1 06-29-92 SO -ODCM

I I 1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued) 1.1 LIQUID 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.

Specification: 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 1-2 08-04-93 S0 -ODCM

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

Liquid Release Type Frequency Frequency Analysis (pCi/ml)'

A. Batch Waste P ' Principal 'Gamma 5 x 10-Release Tanks Each Batch' Each'Batch Emitters' (1) Holdup Tanksb I ;I ' - I-131 1 x 10o6 (2) DELETED P One Batch/M M Dissolved and 1 x lo-Entrained Gases (3) DELETED (Gamma Emitters)

P M H-3 1x 10-Each Batch Composited _

Gross Alpha 1 X lo-P Each Batch Composited Sr-89, Sr-90 5 x 10-Fe-55 1 x 10o6 B. Continuous 3x W W Principal Gamma 5 x 1O-'

Release' Grab Sample Compositef Emitters' 1-131 1 x lo5 (1) Reheater Pit Sump' M M Dissolved and 1 x 10-Grab Sample Entrained Gases (Gamma Emitters)

(2)Yard Drain Sump 3xW M' H-3 --1 x 10 5 Grab Sample Compositef Gross Alpha I x lO-,

3xW' Q Sr-89, Sr-90 5x 10-8 Grab Sample Composite' Fe-55 1 x 10o6 SO1-ODCM Revision 1B 1-3 02-21-01 SO1 -ODCM

I I 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):

4.66 sb LLD = b E *V - 2.22 x 106 - Y

exp (-Aat) 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 a blank 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 oriori (before the fact) limit representing the capability of a measurement system and not as an a Dosteriori (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.

SOL-ODCM Revision 11 1-4 12-06-95 SO0 -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 rot 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 -isthe 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.

SOI-ODCM Revision 8 1-5 06-29-92 SOI -ODCM

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

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

Specification: A. The dose 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

1.5 mrem to the total body and to s 5 mrem to any organ, and

2. During any calendar year to 5 3 mrem to the total body and to s 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 S01 -ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS* (Continued) 1.2 LIQUID EFFLUENT DOSE (Continued) 1.2.2 SURVEILLANCE AppIlicabil ity: At all times.

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

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

S01-ODCM Revision 8 11-7 06-29-92 S0l -ODCM

I' 1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued) 1.3 LIQUID WASTE TREATMENT 1.3.1 SPECIFICATION ADOl icabil ity: 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.

S01-ODCM Revision 10 1-8 04-27-94 S0l -ODCM

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

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

SDecification: Doses due to liquid releases shall be projected at leastonce per 31 days in accordance with Section 3.1.

9..

SOl-ODCM Revision 10 1-9 04-27-94 SO1 -ODCM

I I 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 (1-1)

F+R e where:

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

N Fi (1-2) i= MPCi F, = fractional concentration of the ith radionuclide as obtained by sample analysis.

N = number of radionuclides identified in sample analysis.

MPC1 = MPC of the ith radionuclide (10CFR20, App B. Table II, Column 2).

SO1-ODCM Revision 8 1-10 06-29-92 SO0 -ODCM

-*1 -e 1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR SETPOINTS (Continued)

C, = setpoint'representative of a radionuclide concentration for the radiation monitor measuring the radioactivity in the waste effluent line prior to dilution and subsequent release, pCi/ml.

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

F = dilution water flow in volume per unit time. The dilution water flow is 3,000 gpm per saltwater pump (2 total).

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.

S01-ODCM Revision 14 1-11 02-25-99 SO1-ODCM

I l 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 (Cm) are set to meet the condition of equation (1-1) for the effective MPC (MPCef) 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 =E C'o + Ca + Cs + Ct + CFe +CXe (1-3) where:

C = total concentration in each tank, pCi/ml

,jC'Y, = 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 Ct= 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 Cxe = Xe-133 concentration as determined by isotopic analysis, yCi/ml S01-ODCM Revision 17 1-12 07-20-00 SO1 -ODCM

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

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

(1-4)

= i - 4 / + 'i/ .E{ 4(~~

WIM CVi MPCi MPCt IPCHFWC MPCYI, MPCS MPCts = the limiting concentrations of the appropriate MPCFC, MPC 0 radionuclide from 10CFR20, Appendix B. Table II,

-Column 2.

NOTE: For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-4 pCi/ml total activity.

STEP 3: The radioactivity monitor setpoint C., pCi/ml, may now be specified based on the values of C, EXCy, F, MPCf, and R to provide compliance with the limits of 10CFR20, Appendix B, Table II, Column 2.

STEP 4: 'If the monitor reads in CPM, the setpoint may be derived using the applicable calibration constants given in Table 1-2 to correspond to the calculated monitor limit Cm, pCi/ml.

C-"' ., (Cgi (1-6)

,rax =(Cal. Const.,.pCi/cc/cpm)

S01-ODCM Revision 17 1-13 07-20-00 S01 -ODCM

I L 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:

(RW) (F+R) (zEC') (1-5)

(R) MPCtf) where: RW = Radwaste Effluent discharge administrative value.

F = dilution water flow in volume per unit time.

= 3000 gpm per saltwater pump (2 total).

jCy = total gamma isotopic concentration, excluding Xe-133, ,uCi/ml.

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

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

C = total gamma concentration in each batch sample.

MPCeff = from equation (1-4).

RW, S2100, and Saws1 are administrative values used for simultaneous releases from the Radwaste Effluent discharge, the Reheater Pit Sump, and the Yard Drain Sump.

The fractions RW, S2,W, and S2,0, will be assigned such that (RW + S2100 + S2101) s 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 concentr-ation 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 ZIC', then no release is possible. To increase C., 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).

S01-ODCM Revision 17 1-14 07-20-00 SO1 -ODCM

1.0 RADIOACTIVE LIQUID EFFLUENTS. Continued) 1.4.2 CONTINUOUS RELEASE SETPOINT DETERMINATION STEP 1: ;The isotopic concentration for the continuous releases are obtained for each release stream (reheater pit sump or yard sump) from the sum of the respective measured concentrations as determined by analysis:

, C -= E jCi + Ccl + Cs + Ct + CFe CXe (1-3) where:

C = total concentration, pCi/ml

,jC', = 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/mi.

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.

CFe = total Fe-55 concentration as determined in the previous quarterly composite sample for

-ithe release stream, pCi/ml.

C .- ;Xe-133 concentration as determined by isotopic analysis, yCi/ml SO1-ODCM Revision 17

~1-15 07-20-00 S01 -ODCM

II 1.0 RADIOACTIVE LIQUID EFFLUENTS. (Continued) 1.4 LIOUID EFFLUENT MONITOR SETPOINTS (Continued) 1.4.2 CONTINUOUS RELEASE SETPOINT DETERMINATION (Continued)

STEP 2: The effective MPC (MPCff) for each release stream (reheater pit sump or yard drain sump) is determined using:

IvI/I iC____ CJC )_(CF./C ( cCt_ (1c

' MPC1) (MPCE kMHPC0) MPCFe ( MPC _9)

STEP 3: The setpoint (pCi/ml). for each continuous release radioactivity monitor may now be specified based on the respective values of C.

,lC'yj, F, MPC,,,, and R to provide compliance with the limits of IOCFR20, Appendix B.

Table II, Column 2.

STEP 4: If the monitor reads in CPM, the setpoint may be derived using the applicable calibration constants given in Table 1-2 to correspond to the calculated monitor limit C., pCi/ml.

CPM = (Cm, pCi/ml) (1-6) mXl (Cal. Const.. pCi/cc/cpm)

S01-ODCM Revision 17 1-16 07-20-00 S01 -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 REHEATER PIT SUMP EFFLUENT LINE (REHEATER PIT SUMP)

(RT-2100)

The value of Cz, 21 the concentration limit at the detector, pCimil, is determined using:

(S210) (F+R) -IC' (

C2100< RC/MPCett

-11) where: C2100 ' limiting concentration at monitor RT-2100, uCi /ml.

C, EiCly. MPCf, - values of C. EIC 'i.and MPC,ff (defined in STEPS 1 and 2 above)

R - 350 gpm/pump (x no. sump pumps to be run)

RW, S21000 and S21O, are administrative values used for simultaneous releases from the Radwaste Effluent discharge, the Reheater Pit Sump, and the Yard Drain Sump.

The fractions RW, S21W, and S2101 will be assigned such that (RW + S210O + S2101) s 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 concentr-ation 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 C21,0 s'Cy then no release is possible.

To increase C2100, increase the dilution flow F (by running more pumps) and recalculate C21,>

using the new value of F and equation (1-11).

S01-ODCM Revision 17 1-17 07-20-00 CMt .. nnrM

II V

1.0 RADIOACTIVE E LIQUID EFFLUENTS (Continued) 1.4 LIQUII ) EFFLUENT MONITOR SETPOINTS (Continued) 1.4.2 CONTINUOUS RELEASE SETPOINT DETERMINATION (Conti nued) 1.4.2 .2 YARD SUMP EFFLUENT LINE (RT-2101)

The value of C2,01, the concentration limit at the detector, pCi/mil, is determined using:

C < (S210 1) (F+R) ZC' (1-12)

Z101 RC/MPCCff where:

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

C, FjCyj, MPCf = values of C, EjC'y and MPCff (defined in STEPS 1 and 2 above)

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

RW, S2, 00, and S,,10 are administrative values used for simultaneous releases from the Radwaste Effluent discharge, the Reheater Pit Sump, and the Yard Drain Sump.

The fractions RW. S2,10, and S210, will be a~ssigned such that (RW + S2,00 + S2103) s 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 concentr-ation 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 C21o,s FC'y,9 then no release is possible.

To increase C2M0,, increase the dilution flow F (by running more pumps) and recalculate C2101 using the new value of F and equation (1-12).

SO1-ODCM Revision 17 1-18 07-20-00 S01 -ODal

1.0 RADIOACTIVE LIQUID EFFLUENTS (Continued)

Table 1-2' Liquid Effluent Radiation Monitor Calibration Constants (PCi/cc/cpm)

MONITOR Co-60 Ba-133 Cs-137 RT-1218 5.24E-9 6.37E-9 9.51E-9 RT-2100 1.48E-9 2.19E-9 2.89E-9 RT-2101 1.35E-9 2.12E-9 3.OOE-9 a This table provides typical (+/-20%) calibration constants for the liquid effluent radiation monitors.-

SO1-ODCM Revision 14

.1-19 02-25-99 S0l -ODCM

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

n m DI= E A1 E(Atj Cj Fj) (1-13) ij i where:

At = site related adult ingestion dose commitment factor to the total body or an organ, -, 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.

Cj = average concentration of radionuclide, i, in the undiluted liquid effluent during time period, at;, pCi/mI.

m = number of time periods, j.

D = dose commitment to the total body or an organ, t, from the liquid effluent for the time period, atj, mrem.

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

during the time period, ate. This factor is the ratio of the maximum undiluted liquid waste flow during time period, at , to the average flow from the site discharge structure to unrestricted receiving waters, or maximum liquid radioactive waste flow discharge structure exit flow Atj= length of the jth time period over which Cal and F, are averaged for all liquid releases, hours.

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

TABLE 1-3 DOSE COMMITMENT FACTORS% Ai, (mrem/hr per vCi/ml)

Radio- -

Nuclide Bone-Liver

_ITotal Body ' Thyroid Kidney I_.. Lung GI-LLI H-3 2.82E-1 2.82E-1 2.;82E-1 2.82E-1 2.82E-1 -2.82E-1 Na-24 .4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 Cr-51 5.58E+O 3.34E+O 1.23E+0 7.40E+O 1.40E+3 Mn-54 7.06E+3 1.35E+3 2.10E+3 2.16E+4 Mn-56 1.78E+2 3.15E+1 2.26E+2 5.67E+3 Fe-55 5.11E+4 3.53E+4 8.23E+3 1.97E+4 2.03E+4 Fe-59 8.06E+4 1.90E+5 7.27E+4 5.30E+4 6.32E+5 Co-57 1.42E+2 2.36E+2 3.59E+3 Co-58 6.03E+2 1.35E+3 1.22E+4 Co-60 1.73E+3 3.82E+3 3.25E+4 Cu-64 2.14E+2 1.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+O 9.49E-1 2.47E-11 Sr-89 4.99E+3 1.43E+2 8.OOE+2 Sr-90 1.23E+5 3.-OlE+4- 3.55E+3 Sr-91 9.18E+1 3.71E+O 4.37E+2 Sr-92 3.48E+1 1.51E+O 6.90El2 Y-90 6.06E+D 1.63E-1 6.42E+4 Y-91n 5.73E-2 2.22E-3 1.68E-1 Y-92 5.32E-1 1.56E-2 9.32E+3 Zr-95 1.59E+1 5.11E+O 3.46E+O 8.02E+O 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+0 6.22E+3 Nb-95m 1.84E+O 1.03E+O 5.51E-1 1.O1E+O 6.22E+3 Nb-97 1.55E-2 3.91E-3 1.43E-3 4.56E-3 1.44E41 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 1.07 E+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-lO1m 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 Sb-125 2.15E42 7.84E+3 1.77E+2 1.97E+O 4.20E+1 1.79E-1 l1.36E+2 1.94E+3 Te-129m 9.31E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 Te-132 4.69E+3 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 6.24E+3 1 -131 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E+2 I- 132 8.23E+1 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 I -134 5.56E+O 1.51E+1 5.40E+O 2.62E-t2 2.40E+1 I -135 1.32E-2 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 S01-ODCM Revision 9 1-21 08-04-93 SO1 -ODCM

I I TABLE 1-3 DOSE COMMITMENT FACTORS', Ai, (mrem/hr per uCi/ml)

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+O 1.20E+1 5.94E+O 8.81E40 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+O 3.38E+3 La-140 1.57E+O 7.94E-1 2.10E-1 5.83E+4 Ce-141 3.43E+O 2.32E+O 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+O 4.58E+O 2.74E-1 2.68E-O 2.20E+4 W -187 9.16E+0 7.66E+O 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 SO1-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".

)

SO1-ODCM Revision 17 1-23 07-20-00 S01 -ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS 2.1 DOSE RATE 2.1.1 SPECIFICATION ADpl icabilitv: At all times.

Objective: Maintain the dose rate at the exclusion area boundary from radioactive gaseous effluents within 10 CFR 20 limits.

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

1. The dose rate limit for noble gases shall be s 500 mrem/year to the total body and s 3000 mrem/year to the skin, and

2. The dose rate limit for 1-131, 1-133, for tritium and for all 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 8 2-1 06-29-92 SO1-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.1 DOSE RATE (Continued) 2.1.2 SURVEILLANCE Applicabili ty: At all times.

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 iodine-131, iodine-133, 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.

SO1-ODCM Revision 8 2-2 06-29-92 S01 -ODCM

I I 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)"

Gaseous Release Type Frequency Frequency Analysis (pCi/ml)

Plant Stack M M Principal Gamma 1 x lo-Grab Emittersb Sample H-3c 1 x 10.6 Continuousd We 1-131 1 x 10o-2 Charcoal Sample Continuous' we Principal Gamma 1 x 10l Particulate Emittersb Sample (1-131, Others)

Continuous' M Gross Alpha 1 x 1011 Composite Particulate Sample Continuousd Q Sr-89, Sr-90 1 x 10.11 Composite Particulate Sample Continuousd Noble Gas Noble Gases 1 x 106 Monitor Gross Beta or Gamma SOl-ODCM Revision 14 2-3 02-25-99 S0l -ODCM

.. pTABLE72-1

(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.:

LLD = b E *V *2.22 x 106- Y exp (-Aat) 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 a blank sample as appropriate (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 10e 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. 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.

SOl-ODCM Revision 11 2-4 12-06-95 Sol -ODCM

I I TABLE 2-1 (Continued)

TABLE NOTATION (Continued) c, Tritium grab samples shall be taken at least once per 7 days from 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 in 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 after changing, or after removal from sampler.

SO1-ODCM Revision 9 2-5 08-04-93 SOI -OD(M

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.2 DOSE. NOBLE GASES 2.2.1 SPECIFICATION ADpp icabil ity: At all times.,

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:

5 mrad for gamma radiation and s 10 mrad for beta radiation.

2. During any calendar year: 5 10 mrad for gamma radiation and s 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 10 2-6 04-27-94 SOI -ODCM

I I 2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.2 DOSE. NOBLE GASES (Continued) 2.2.2 SURVEILLANCE Applicability: At all times.

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 calendar quarter and current calendar year shall be determined in accordance with Section 2.7.1 at least once per 31 days.

S01-ODCM Revision 8 2-7 06-29-92 SOI -ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.3 DOSE. IODINE-131. IODINE-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM 2.3.1 SPECIFICATION Applicability: At all times. .

Objective: Maintain the dose due to radioiodine, 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 1-131,

.1-133, 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: 5 7.5 mrem to any organ; and

2. During any calendar year:

15 mrem to any organ.

B. Action:

1. With the calculated dose from the release of 1-131, 1-133, 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.

SO1-00CM Revision 10 2-8 04-27-94 S01 -ODCM

I I 2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) -

2.3 DOSE. IODINE-131. IODINE-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM (Continued) 2.3.2 SURVEILLANCE ADD licability: At all times.

Objective: To verify the dose due to iodine-131, iodine-133, 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 iodine-131, iodine-133, 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 SOL-ODCM Revision 14 2-9 02-25-99 SO1-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.5 GASEOUS EFFLUENT MONITOR SETPOINTS 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 c ) (500 mrem/yr) (lo- m /cc)

Cdet =

(Flow rate, cfm) (X/Q, sec/m ) E (Ki, mC/i r )M( C1 J~tot p~i/rn (2-1)

Skin Cdet -

(Flow rate, cfm) (X/Q, sec/m') EI (Li + 1.1M, rem/yr ) (2-2)

SOl-ODCM Revision 14 2-10 02-25-99 SOI -ODCM

I I 2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.5 GASEOUS EFFLUENT MONITOR SETPOINTS (Continued) 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 i h gamma emitting noble gas, from Table 2-3. mrem/yr per pCi/n' L, = skin dose conversion factor for the ith noble gas, from Table 2-3, mrem/yr per pCi/rn M = air dose conversion factor for the ih noble gas, from Table 2-3, mrem/yr per pCi/m3 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 Ci =concentration of the it'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

=20,000 cfm/fan (x no. of fans to be run) 2120 = conversion constant, cfm to m0/sec X/Q = historical annual average dispersion factor for any landward sector

= 1.3E-5 sec/m' S01-ODCM Revision 14 2-11 02-25-99 SO1 -ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.5 GASEOUS EFFLUENT MONITOR SETPOINTS (Continued) 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, Cdt, to an equivalent release rate, pCi/sec, as follows:

A.. = (Cdt, pCi/cc) (flow rate, cc/sec) (2-3) where:

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

-Flow Rate = vent stack flow rate, cc/sec

= 9.44 x 106 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 -0DCM Revision 10 12 04-27-94 SO0 -ODCM

I I 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:

DIB = E [K,(X/Q) Q. J (2-7)

DS = E, (L + 1.1M,) (X/Q) Q1 J (2-8) where:

DTS total body dose rate in unrestricted areas due to airborne radioactive effluents, mrem/yr.

Ds 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/M3 (Unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose.)

Q = measured or calculated release rate of radionuclide, i. pCi/sec (X70) = 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 11 2-13 12-06-95 SOI -ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.6 GASEOUS EFFLUENT DOSE RATE (Continued) 2.6.2 FOR 1-131, I-133, RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN EIGHT DAYS AND H-3:

. ~ - . ' 1.

Z [ik (Pik Wd) Q(2-9) o

= organ dose rate in unrestricted areas due to airborne effluents, mrem/yr Q = measured or calculated release rate of radionuclide, i, pCi/sec Pik = dose parameter for radionuclide, i, for pathway, k, fromTiable 2-4 for the inhalation pathway, mrem/yr per pCi/m 3. The dose factors are based on the critical individual organ and the child age group.

k = 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/M 3 for the inhalation pathway.

The location is the unrestricted area in the NW sector.

(b7U). 7.2E-8 sec/m3 for the food and ground pathways. The location is the unrestricted area in the NW sector.

S01 -ODCM Revision 11 1412-06-95 SO1-ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.7 GASEOUS EFFLUENT DOSE CALCULATION 2.7.1 DOSE FROM NOBLE GASES IN GASEOUS EFFLUENT 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 HIST0RICAL METEOROLOGY:

Dv = 3.17X100 8- M1 (i/Q) Q.] (2-10) 08 = 3.17X1 8-' ( Q1I F.1 INa-) (2-11) where:

total gamma air dose from gaseous effluents, mrad total beta air dose from gaseous effluents, mrad 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 air dose due to beta emissions for each identified noble gas radionuclide, i, from Table 2-3, mrad/yr per pCi/m3 1.3E-5 sec/n9. The maximum annual average atmospheric dispersion factor for any area at or beyond the unrestricted area boundary for a landward sector.

QI amount of noble gas radionuclide. i, released in gaseous effluents, pCi.

3.17x 1O-' inverse seconds/year SOI-ODCM Revision 11 2-15 12-06-95 Sol -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) 2.7.1.2 FOR METEOROLOGY CONCURRENT WITH RELEASE:

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

DY = 1.14xIO 4EIMij ("tj (X/Q)je (2.-12)

D 1.14x10Z E (X/Q)j (2-13) where:

Dye = total gamma air dose from gaseous effluents in sector e, mrad D8 = total:beta air dose from gaseous effluents in sector e, mrad Mj = air dose factor due to gamma emissions for each identified noble gas radionuclide, i, from Table 2-3, mrad/yr per pCi/m 3 N. = air dose factor due to beta emissions for each identified noble gas radionuclide, i, from Table 2-3, mrad/yr per pCi/r 3 Atj . ength of the jh time period over which

.:. (X/Q)g8 and Q, are averaged for gaseous releases, hours (X/Q)je = - atmospheric dispersion factor for time period, at3 at exclusion boundary location in landward sector e determined by

. <concurrent meteorology, sec/m3

= average release rate of radionuclide, i,in gaseous effluents during time period, Atj, pCi/sec 1.14x10- = inverse hours/year SOI-ODCM Revision 11 2-16 12-06-95 50 -ODCM

2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.7 GASEOUS EFFLUENT-DOSE CALCULATION (Continued) 2.7.2 DOSE FROM I-131, 1-133, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND H-3 The dose to an individual from I-131, 1-133, radioactive materials in 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:

0 = 3.17xlO-1 El [Ek(RikWk) Q1] (2-14) where:

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

= amount of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases with half lives greater than eight days, i, released in gaseous effluents, pCi iRikWk = sum of all pathways k for radionuclide. i. of the R,* W product, mrem/yr per pCi/sec. The EkRikWk value for each radionuclide, i, is given in Table 2-5. The value given is the maximum EkRikWk 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/m 3 and for the food and ground plane pathways, m"-mrem/yr per pCi/sec at the controlling location. The Rk'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.)

Wk annual average dispersion parameter for estimating the dose to an individual at the controlling location for pathway k.

= (X7fl) for the inhalation pathway, sec/m 3. The (X/Q) for each controlling location is given in Tables 2-6 thru 2-16.

for the food and ground plane pathways.

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

SOI-QOCM Revision 11 2-17 12-06-95 SO1-ODCM

I 2.0 RADIOACTIVE GASEOUS EFFLUENTS (Continued) 2.7 GASEOUS EFFLUENT DOSE CALCULATION (Continued) 2.7.2 DOSE FROM 1-131,-1-133, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND H-3 (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, RRRGS (Radioactive Release Report Generating System) software is used to perform the actual calculations.

lmn D= 1.14 X 10i4 E4 [(At) (Rake) (Wike) (QJ) ] (2415) where:

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

atj = length of, the jth period over which Wj,,

and Q!j are averaged for gaseous releases, hours Q;= average release rate of radionuclide, i, in gaseous effluents during time period atj, pCi/sec Rike = dose factor for each identified radionuclide i, for pathway k for sector e (for the inhalation pathway, mrem/yr per pCi/nm, and for the food and ground plane 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 meteorol ogy.

Wake = dispersion parameters for the time period at, for each pathway k for calculating the dose to an individual at the controlling location in sector e using concurrent meteorological conditions.

= (X/Q) for the inhalation pathway, sec/r3

- (D/Q) for the food and ground plane pathways, m-'

S01-ODCM Revision 8 2-18 06-29-92 Sol -ODCM

II TABLE 2-3 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Total Body Dose Skin Dose Gamma Air Dose Beta Air Dose Factor K, Factor L, Factor M, Factor N.

Radio- (mrem/yr (mrem/yr (mrad/yr (mrad/yr Nuclide per pCi/M 3 ) per pci/m3 ) per pCi/m3 ) per pCi/m 3 )

Kr-85m 1.17E+3 1.46E+3 1.23E+3 1.97 E+3 Kr-85 1.61E+1 1.34E+3 1.72E+1 1.95E+3 Kr-87 5.92E+3 9.73E+3 6.17E+3 1.03E+4 Kr-88 1.47E+4 2.37E+3 1.52E+4 2.93E+3 Xe-131m 9.15E+1 4.76E+2 I1.56E+2 1.11E+3 Xe-133m 2.51E+2 9.94E+2 3.27E+2 1.48E+3 Xe-133 2.94E+2 3.06E+2 3.53E+2 1.05E+3 Xe-135m 3.12E+3 7.11E+2 3.36E+3 7.39E+2 Xe-135 1.81E+3 1.86E+3 1.92E+3 2.46E+3 Xe-138 8.83E+3 4.13E+3 9.21E+3 4.75E+3 Ar-41 8.84E+3 2.69E+3 9.30E+3 3.28E+3 Source: USNRC Reg. Guide 1.109, Table B-1 SO1-ODCM Revision 8 2-19 06-29-92 SO0 -ODCM

TABLE 4 DOSE PARAMETER Pik CHILD AGE GROUP CRITICAL ORGAN Inhalation Pathwa' Inhalation Pathway Radionuclide (mrem/yr per uCi/m ) -. Radionuclide (mrem/yr per pCi/m)

H - 3 1.1E+3 I -131 1.6E+7 Cr-51 1.7E+4 I -132 1.9E+5 Mn-54 1.6E+6 I -133 3.8E+6 Co-57 5.1 E+5 I -134 5.1E+4 Co-58 1.1E+6 1-135 7.9E+5 Co-60 7.1E+6 Cs-134 I.OE+6 Sr-89 2.2E+6 Cs-136 1.7E+5 Sr-90 1.OE+8 Cs-137 9.1 E+5 Zr-95 2.2E+6 Ba-140 1.7E+6 Nb-95 6.1 E+5 Ce-141 5.4E+5 Ru-103 6.6E+5 Ce-144 1.2E+7 Te-129m 1.BE+6

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

II I

TABLE 2-5 CONTROLLING LOCATION FACTORS ElRikWk l Radionucilide mrem/yr per pCi/sec jUse:

H -3 3.16E-3 B: Outage Workers Cr-51 1.53E-1 B: Outage Workers Mn-54 3.53E+1 B: Outage Workers Co-57 8.96E+O B: Outage Workers Co-58 1.15E+1 B: Outage Workers Co-60 4.98E+2 B: Outage Workers Sr-89 4.96E+1 Q: SC Ranch (No. Res.)

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

Zr-95 1.21E+1 B: Outage Workers Nb-95 6.90E+O E: Deer Consumer/Hunter Ru-103 1.09E+1 E: Deer Consumer/Hunter Te-129m 5.51E+O E: Outage Workers Cs-134 1.52E+2 B: Outage Workers Cs-136 3.73E+O B: Outage Workers Cs-137 2.27E+2 B: Outage Workers Ba-140 5.51E+O B: Outage Workers Ce-141 1.82E+O B: Outage Workers Ce-144 3.51E+1 Q: Outage Workers I -131 3.94E+1 Q: Outage Workers I -132 4.95E-1 B: Outage Workers 1 -133 9.80E+O B: Outage Workers I -134 1.35E-1 B: Outage Workers I -135 2.04E+O B: Outage Workers UN-ID 1.94E+1 B: Outage Workers Footnote: These values to be used in manual calculations are the maximum ER,,Wk for all locations based on the most restrictive age group.

SO1-ODCM Revision 20 2-21 02-28-03 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 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion Ground ti6n Ground tion Ground Nuclide Pathway Pathway Pathway- Pathway Pathway Pathway Pathway Pathway H -3 7.8E40 --O 4.2E+l 9.6E+1 Cr-51 1.2E42 3.2E+4 6.9E+2- 1.5E+5 1.1E+3 -3.5E+5 Mn-54 1.1E+4 9.5E+6' 6.'5E+4 4.5E+7 '1.IE+5 1.1E+8 Co-57 3.5E+3 2.4E+6 1.9E+4 -1.1E+7 2.BE+4 2.6E+7 Co-58 -O- 7.6E+3 2.6E+6 4.4E+4' 1.2E+7 7.1E+4, 2.9E+7 Co-60 4.9E+4 1.5E+8 2.9E+5 7.OE+8 4.5E+5 1.6E+9 Sr-89 1.5E+4 1.5'E+2 7.9E+4 7.1E+2 1.1E+5 1.6E+3 Sr-90 7.OE+5 3.5E+6 O 7.5E+6 Zr-95 1.5E+4' 1.'7E+6 8.8E+4 *8.2E+6 1.3E+5 .1.9E+7 Nb-95 4.2E+3 9.4E+5 2.5E+4 4.5E+6 3.8E+4 1.OE+7 Ru-103 4.6E+3 .7.5E+5 2.6E+4 3.6E+6 3.8E+4 8.3E+6

'Te-129m 1.2E+4 .1.4E+5 6.5E+4 *6.'4E+5 8.8E+4 1.5E+6 Cs-134 7.OE+3 4.7E+7 3.7E+4 2.2E+8 6.5E+4 5.2E+8 Cs-136 1.2E+3 1.OE+6 6.3E+3 *4.9E+6 1.1E+4 1.IE+7 Cs-137 6.3E+3 7.1E+7 2.8E+4 3.4E+8 4.7E+4, 7.BE+8 Ba-140 .. 1.2E+4 1.4E+5 6.'6E+4 6.7E+5 9.7E+4 1.6E+6 Ce-141 3.8E+3: 9.4E+4 2.OE+4 4.5E+5 2.8E+4 1.OE+6 Ce-144 B.2E+4 ;4.8E+5 4.4E+5- 2.3E+6 5.9E+5 5.3E+6 I -131 . 1.1E+5 1.2E+5 4.8E+5 5.6E+5 9.1E+5 1.3E+6 1 -132 - 1.3E+3 8.5E+3 4.9E+3' 4.1E+4 8.7E+3 9.4E+4 I -133 2.7E+4 .1.7E+4 9.5E+4 8.0E+4 1.6E+5- 1.9E+5 I -134 3.5E+2 3.1E+3 1.3E+3 1.5E+4 2.3E+3 3.4E+4 I -135 5.5E+3 2 1.7E+4 2.OE+4 8.2E+4 3.4E+4 1.9E+5 UN-ID 6.9E+3- 5.IE+6 4.1E+4 2.4E+7 '6.6E+4 5.7E+7 Inhalation Pathway, units = mrem/yr - t-Vci/rmn - - ;

2 Food & Ground Pathway, units = (i )pCi/sec (mrem/lr)

J' S01-ODCM Revision 13 2-22 02-27-98 SO -ODCI

I I TABLE 2-7 DOSE PARAMETER R, FOR SECTOR P Paae 2 of 2 Pathway = Cotton Point Estates with Garden Distance = 2.6 miles X/Q - 1.3E-7 sec/Mn D/Q = 3.9E-10 m- 2 Infant Child Teen Adult Inhala-: Food & Inhala- Food & Inhali- 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 1.3E+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 7.8E+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 Z.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. 1.0E+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.OE48 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.BE+9 1.0E+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 Z.1E+7 1.7E+6 3.OE+8 2.OE+6 2.3E+B 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 I.3E+7 I.3E+10 7.8E+6 1.1E+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 1 -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.BE+6 8.1E+8 2.9E+6 4.6E+8 2.2E+6' 5.3E+8 1 -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 1 -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 = m R i/rn~

2 Food & Ground Pathway, units = (Im) (Nrem/vr) pCi/sec S0l-ODCM Revision 14 2-23 02-25-99 SO1 -ODCM

TABLE 2-8 DOSE PARAMETER RI FOR SECTOR Q Paqe 1 of 4 IF II Pathway = Outage Workers Distance = 0.5 miles X/Q = 3.2E-6 sec/M 3 D/Q = 1.7E-8 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion - Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 -O- -O- -O- -O- -O- -O-Cr-51 -O- -O- -O- -O- -O-Mn-54 -O- -O- _ -O- -O- -O- -O- Co-57 -O- O- -O- -O- Co-58 -O- -O- -O- -O- Co-60 -O- -0 o- -O- Sr-89 -O- ' -O- -O- -O- Sr-90 -O- -O- -O- -O- Zr-95 -O- -O- -O- -O- -O- -O- Nb-95 -O- -O- -0 - -O- -O- -O- Ru-103 -O- -O- -O- -O- -O- Te-129m -O- -O- -O- -O- -O- .--

Cs-.134 ' -o- --

O- -O-- -O- 0--O-Cs-136 -O- -O -O- -O- -O- Cs-137, --

O -0 -- -0O- -O- Ba-140 -O- -O -0 - -O-Ce-141 -O- -0 - _ Ce-144 -O- -O- -O- -O- 1 -131 -O- -O- -O- -- -O- -O- 1 -132 -O- -O- -O- -O- -O- I -133 -O- -o- 0 -O- -O- -O-1 -134 -O- -O- -O- -O- 1 -135 -O- -O- -O- -O- -O- UN-ID -O- -O- -- -O- -O-Inhalation Pathway, units =

FC~i/rnT_

2 Food & Ground Pathway, units = (m ) (mrem/vr) pCi/sec S01-ODCM Revision 14

. 2-24 02-25-99 SO1 -ODCM

TABLE 2-8 DOSE PARAMETER RI FOR SECTOR Q Paqe 2 of 4 IF I-Pathway = San Onofre Mobile Homes Distance-= 1.2 miles X/Q = 9.1E-7 sec/m 3 D/Q = 4.3E-9 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 6.5E+2 l.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 3.8E+5, ,3.4E+8 5.1E+5 3.4EtB 5.9E+5 3.4E+8 3.7E+5 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1IE+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.IE+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+B 7.BE+5 1.1E+8 5.OE+5 l.lE+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.IE+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 6.1E45 1.OE+10 9.1E+5 1.OE+10 8.5E+5 1.OE+10 6.2E+5 1.OE+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.IE+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 l.lE+5 1.2E+6 I -133 3.6E+6 2.4E46 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 1 -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 2.5E46 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/yr pc~i I/m 2

Food & Ground Pathway, units = (m ) (mrem/vr) pCi /sec SQ1-ODCM Revision 12 2-25 01-29-97 S01 -ODCM

TABLE 2-8 DOSE PARAMETER RI FOR SECTOR Q Page 3 of 4 If I

Pathway = San Mateo Pt Homes Distance = 2.5 miles X/Q = 2.8E-7 sec/m'3 D/Q = 1.1E-9 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. -6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E44 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.OE46 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.lE+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 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E48 6.6E+5 I.1E+8 7.8E+5 1.1E+8 5.OE+5 1.IE+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.BE+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.OE+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.IE+7 2.OE+6 2.IE+7 1.3E+6 2.IE+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 1 -132 1.7E+5 1.2E+6 1.9E+5 l.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 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 pC i/rnT Food & Ground Pathway, units = (ml) (mnrem/vr) pCi /sec SOl-ODCM Revision 18 2-26 02-21-01 SO -ODCM

I I

. I TABLE 2-4 DOSE PARAMETER RI FOR SECTOR Q Page 4 of 4 Pathway = Rec Bldg Staff - Distance = 1.0 miles X/Q = 1.1E-6 sec/m3 D/Q = 5.4E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion Ground- tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway' Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 -O- 1.4E+6 1.4E+9 Co-57 -0 -- 3.7E+5 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.OE+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-9o 9.9E+7 .Zr-95 1.8E+6 2.5E+8 Nb-95 5.OE+5 1.4E+8 Ru-103 5.OE+5 1.1E+8 A Te-129m 1.2E+6 2.OE+7 Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+5 1.5E+8 Cs-137 -O- 6.2E+5 1,.OE+10 Ba-140 -O- 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 I -132 1.1E+5 1.2E+6 I -133 -O- -O- 2.2E+6 2.4E+6 I -134 3.OE+4 4.5E+5 1 -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 Inhalation Pathway, units = mrem/vr pCi/mr Food & Ground Pathway, units = m7)(mrem/vr) pCi/sec S01-OOCM Revision 20 2-27 02-28-03 S01 -ODCM

a TABLE 2-9 DOSE PARAMETER R1 FOR SECTOR R Page 1 of 1 Pathway = San Onofre Mobile Homes Distance = 1.2 miles X/Q = 6.OE-7 sec/m3 D/Q = 3.5E-9 m-Z Infant Child Teen Adult Inhala-: Food & Inh'ala- 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+6r 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.IE+8 9.9E+7 Zr-95 I.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+5i 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.EE+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.OE46 2.OE+7 1.2E+6 2.OE+7 Cs-134 7.OE+5 6.8E+9 1.0E+6' 6.BE+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.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.IE+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+77 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+55 4.OE+4 4.5E+5 3.OE+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 = ! :,

FC i/rnM-2 Food & Ground Pathway, units = ( ) (mrem/vr)

pCi/sec.

S01-ODCM Revision 12 2-28 01-29-97 SO1 -ODCM

I I

q TABLE 2-10 DOSE PARAMETER R1 FOR SECTOR A.

DPan I of I Pathway = Camp San Mateo Distance = 3.5 miles 3

X/Q = 7.8E-8 sec/r 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-- -O- -O- -O- 1.3E+3 -O-Cr-51 -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 . -O- -O- -O- -O - 3.7E+5 3.4E+8 Co-58 -O- -O- -O- -O- 9.3E+5 3.8E+8 Co-60 -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- -O- 9.9E+7 Zr-95 -O- -O- -O- -O- -O- 1.8E+6 2.5E+8 Nb-95 -O- -- O- -O- -O- -- 5.0E+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 2.0E+7 Cs-134 -O- -O- -O- -O- -O- 8.5E+5 6.8E+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- 1.3E+6 2.IE+7 Ce-141 -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- 1.2E+7 1.7E+7 I -132 -O- -O- -O- 1.1E+5 1.2E+6 I -133 -O- -O- -O- -O- 2.2E+6 2.4E+6 I -134 -O- -O- -O- -O- 3.OE+4 4.5E+5 1 -135 -O- -O- -O- -O- -O- 4.5E+5 2.5E+6 UN-ID -O- -O- -O- -O- -O- 8.6E+5 7.5E+8 Inhalation Pathway, units =

FCi/rnI 2

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

' TABLE 2-11 IDOSE 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 m-2 Infant Child> Teen Adult Inhala- Food & lnhala-1 Food & Inhala- Food & Inhala- Food &

Radio- tion Ground ti on Ground tion Ground tion - Ground Nuclide Pathway Pathway Pathway Pathway Pathway' Pathway Pathway Pathway H -3 -O- -O- -O- 2.9E+2 -O-Cr-51 -O- -O- -O- -O- 3.3E+3 1.1E+6 Mn-54 -O- -O- -O- -O- 3.2E+5 3.2E+8 Co-57 -O- ' -O- 8.4E+4 7.8E+7 Co-58 -O- -O- -O- 2.1E+5 8.7E+7 Co-60 -O- . -O- 1.4E+6 4.9E+9 Sr-89 -O- -O- 3.2E+5 4.9E+3 Sr-90 -O- -O- -- -O- -O- 2.3E+7 -O-Zr-95 -O- -O- -O- -O- 4.OE+5 5.7E+7 Nb-95 -O- -O- 1.2E+5 3.1E+7 Ru-103 -O- -O- ; -O0--

O-.2E+5' - 2.5E+7 Te-129m -O- -O- ; -O- 2.6E+5 4.5E+6 Cs-134 -O- -O- ' -O- -O- 1.9E+5 1.6E+9 Cs-136 -O- -O- -O- -O- 3.3E+4 3.4E+7 Cs-137 -O- -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- 8.3E+4 3.1E+6 Ce-IW4i N-O- L -'O- _ ' -O O -O- 1:8E+6' '1.6E+7 1 -131 -O- -O- - O- -O- -O- 2.7E+6 3.9E+6 1 -132 -O- -O- -O- -O- -O- -- 2.6E+4 2.8E+5 1 -133. - - '; -O- -O- 4.9E+5 5.6E+5 1 -134 - -O- -0 - - O- - O- 6.8E+3 1.'OE+5 I -135 -O- '. 70- -O- -- 1.OE+5 5.8E+5 UN-ID -O- -O- -O- -O- 2.OE+5 1.7E+8 Inhalation Pathway, units = mrem/yr aCi /m3 2

Food & Ground Pathway, units = (W) (mrem/vr) pCi/sec SO1-ODCM Revision 8

': 2-30 06-29-92 SO1-ODCM

I I TABLE 2-11 DOSE PARAMETER R. FOR SECTOR B Page 2 of 2 Pathway = Outage Workers Distance = 0.3 miles X/Q = 3.9E-6 sec/m3 2 D/Q = 3.4E-8 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 4.1E+2 7.2E+2 8.1E+2 8.1E+2 Cr-51 8.2E+3 3.OE+6 1.1E+4 3.OE+6 1.3E+4 3.OE+6 9.2E+3 3.OE+6 Mn-54 6.4E+5 8.9E+8 1.OE+6 8.9E+8 1.3E+6 8.9E+8 9.OE+5 8.9E+8 Co-57 2.4E+5 2.2E+8 3.2E+5 2.2E+8 3.8E+5 2.2E+8 2.4E+5 2.2E+8 Co-58 5.OE+5 2.4E+8 7.lE+5 2.4E+8 8.6E+5 2.4E+8 5.9E+5 2.4E+8 Co-60 2.9E+6 1.4E+10, 4.5E+6 1.4E+10 5.6E46 1.4E+10 3.8E+6 1.4E+10 Sr-89 1.3E+6 1.4E+4 1.4E+6 1.4E+4 1.5E+6 1.4E+4 9.OE+5 1.4E+4 Sr-90 2.6E+7 6.5E+7 6.9E+7 6.3E+7 Zr-95 1.IE+6 1.6E+8 1.4E+6 1.6E+8 1.7E+6 1.6E+8 1.1E+6 1.6E+8 Nb-95 3.1E+5 8.7E+7 3.9E+5 8.7E+7 4.8E+5 8.7E+7 3.2E+5 8.7E+7 Ru-103 3.5E+5 7.OE+7 4.2E+5 7.OE+7 5.OE+5 7.OE+7 3.2E+5 7.OE+7 Te-129m 1.1E+6 1.3E+7 1.IE+6 1.3E+7 1.3E+6 1.3E+7 7.4E+5 1.3E+7 g Cs-134 4.5E+5 4.4E+9 6.5E+5 4.4E+9 7.2E+5 4.4E+9 5.4E+5 4.4E+9 Cs-136 8.6E+4 9.6E+7 1.1E+5 9.6E+7 1.2E+5 9.6E+7 9.4E+4 9.6E+7 Cs-137 3.9E+5 6.6E+9 5.8E+5 6.6E+9 5.4E+5 6.6E+9 4.OE+5 6.6E+9 Ba-140 1.OE+6 1.3E+7 1.1E+6 1.3E+7 1.3E+6 1.3E+7 8.1E+5 1.3E+7 Ce-141 3.3E+5 8.7E+6 3.5E+5 8.7E+6 3.9E+5 8.7E+6 2.3E+5 8.7E+6 Ce-144 6.3E+6 4.5E+7 7.6E+6 4.5E+7 8.6E+6 4.5E+7 5.OE+6 4.5E+7 I -131 9.5E+6 1.1E+7 1.OE+7 1.1E+7 9.4E+6 1.1E+7 I -132 1.1E+5 7.9E+5 I.2E+5 7.9E+5 9.7E+4 7.9E+5 7.3E+4. 7.9E+5 I -133 2.3E+6 1.6E+6 2.5E+6 1.6E+6 1.9E+6 1.6E+6 1.4E+6. 1.6E+6 I -134 2.8E+4 2.9E+5 3.2E+4 2.9E+5 2.5E+4 2.9E+5 1.9E+4 2.9E+5 1 -135 4.5E+5 1.6E+6 5.1E+5 I.6E+6 4.OE+5 1.6E+6 2.9E+5 1.6E+6 UN-ID 4.1E+5 4.8E+8 6.4E-F5 4.8E+8 7.9E+5 4.8E+8 5.5E+5 4.8E+8 Inhalation Pathway, units = W Food & Ground Pathway, units = (mp(Cir/eml/cyr)

SO5-ODCM Revision 20 2-31 02-28-03 SO1-ODCM

TABLE 2-12 DOSE PARAMETER RI FOR SECTOR C Page 1 of 2 Pathway = Camp San Onofre Distance = 2.7 miles X/Q = 9.3E-8 sec/n 3 D/Q = 8.3E-10 m' Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 -O- -O- - -O- 1.3E+3 -O-Cr-51 -O- -O- -O- -O- 1.4E+4 4.7E+6 Mn-54 .-O- O -O- - -O- 1.4E+6 1.4E+9 Co-57 -O- -O- -O- 3.7E+5 3.4E+8 Co-58 -O- -O- _-0_ - -O- -O- 9.3E+5 3.8E+8 Co-60 -O- -O- -_O -O- -O- 6.OE+6 2.2E+10 Sr-89 -O- -O- -O- -O- 1.4E+6 2.2E+4 Sr-90 -O- -O - -O- -O- 9.9E+7 -O-Zr-95 -O- -O- -O- -O- -O- 1.8E+6 2.5E+8 Nb-95 -O- -0 -0'- -O- 5.OE+5 1.4E+8 Ru-103 -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- 8.5E+5 6.8E+9 Cs-136 -O- -O- -O- -O- 1.5E+5 1.5E+8 Cs-137 -O- -O- -O- -O- 6.2Et5 1.OE+10 Ba-140 -O- -O- ' -O- 1.3E+6 2.IE+7 Ce-141 -O- 3.6E+5 1.4E+7 Ce-144 -O- -O- - -- O- -O- 7.8E+6 7.OE+7 1 -131 -O- -O- -O- 1.2E+7 1'7E+7 1 -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- -aO- -O- -O- 3.OE+4 4.5E+5 I -135 -O- -O- -O- 4.5E+5 2.5E+6 UN-ID -o- -O- -O- O- 8.6E+5 7.5E+8 Inhalation Pathway, units = reml/r VC i-/-my 2 ) (mrem/vr)

Food & Ground Pathway, units = (

pCi/sec SOI-ODCM Revision 12 2-32 01-29-97 sol -annm

I I TABLE 2-12 POSE PARAMETER RI FOR SECTOR C Paae 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__

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

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.OE+4 1.OE+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.IE+7

-Co-57 4.6E+6 8.OE+6 1.OE+4 2.3E+7 Co-58 9.6E+6 1.9E-7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.IE+7 Sr-90 1.OE+9 8.OE+8 2.7E+6 1.2E+9

.Zr-95 6.2E+7 1.1E+8 4.8E+4 - 2.OE+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.OE+8 Ba-140 5.OE+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6

Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 1 -131 6.5E+8 4.3E+B 3.3E+5 5.9E+8 1 -132 3.1E+3 3.4E+4 1 -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = mrem/yr pCi/rn 2

Food & Ground Pathway, units = (m ) (mrem/vr) pCi/sec S01-ODCM Revision 12 2-33 01-29-97 S01 -ODCM

TABLE 2-13 DOSE PARAMETER RA FOR SECTOR D Page 1 of 1 Pathway = Camp San Onofre Distance = 3.0 miles X/Q = 7.OE-8 sec/r 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- i0 -O- -O- -- 1.3E+3 -O-Cr-51 -O- -O - -- -0O- -O- 1.4E+4 4.7E+6 Mn-54 -O- -O- -0O- 1.4E+6 1.4E+9 Co-57 -0O - O- 3.7E+5 3.4E+8 Co-58 - O-- -0O 9.3E+5 3.8E+8 Co-60 -O- -O- _0_ -O- -O- 6.OE+6 2.2E+10

Sr-89 -O- -O- -O- -O- 1.4E+6 2.2E+4 Sr-90 -O- ' -0 o -- -O- -O- 9.9E+7 -O-Zr-95 -O- -O- -O- -O- -O- 1.8E+6 2.5E+8 Nb-95 -O- -O- -O- 5.OE+5 1.4E48 Ru-103 g -O- -O- 70- -O- 5.OE+5 1.1E+8 Te-129m -O- -O- -O- 1.2E+6, 2.OE+7 Cs-134 -O- -O- -O- -O- 8.5E+5 6.8E49 Cs-136 _ O0 N -O- ' : g O- -O- -- 1.5E+5 1.5E+8 Cs-137 -O- -O- -O- -O- -O- 6.2E+5 1.OE410 Ba-140 -O- -O- -O- 1.3E+6 2.1E+7 Ce-141 - -O- -O- 3.16E+5 1.4E47 Ce-144 -O- -O- -O- '-O- -o- ' - 7.8E+6 7.OE+7 I '-131 -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- -O- 2.2E+6 2.4E46 I -134 -O- -O- -O- -O- 3.OE+4 4.5E+5 I -135 -O- -O- -O- -O- 4.'5E+5 2.5E+6 UN-ID -O- -O- -o- -O- 8.6E+5 7.5E+8 Inhalation Pathway, units mrem/vr '

pCi/rn Food & Ground Pathway, units - (m2 ) (mrem/yr) pCi/sec '

S01-ODCM Revision 12 2-34 01-29-97 S0l -ODCM

I I TABLE 2-14 DOSE PARAMETER-RI FOR SECTOR E Paaq 1 nf 2 Pathway - Deer.Cosuer Distance = 1.0 miles X/Q = 6.OE-7 sec/m3 D/Q-= 8.4E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.OE+4 1.OE+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 4.6E+6 8.OE+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.OE+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 l.lE+8 4.8E+4 2.OE+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.1E+6 4.2E+6 4.OE+3 9'5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 5.OE+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.IE+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 1 -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.lE-15 6.3E-16 1.ZE+4 6.9E+4 UN-ID 1.lE+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = mrem/vr R i /m -

2 Food & Ground Pathway, units = ( ) (mrem/vr) pCi/sec SO1-OOCM Revision 12 2-35 01-29-97 SO0 -ODCM

TABLE 2-14 DOSE PARAMETER R, FOR SECTOR E Page 2 of 2 Pathway = Camp Horno Distance = 4.2 miles X/Q = 7.3E-8 sec/m3 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 -O- 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 -- 1.4E+6 1.4E+9 Co-57 ' 0- 3.7E+5 3.4E+8 Co-58 0- 9.3E+5 3.8E+8

.Co-60 6.OE+6 2.2E+10 Sr-89 -- O- 1.4E+6 2.2E+4

-Sr-90 H 0- 9.9E+7 Zr-95 0- 1.8E+6 2.5E+8 Nb-95 5.OE+5 1.4E+8 Ru-103 5.0E+5- 1.IE+8 Te-129m 1.2E+6 2.OE+7 Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+5 1.5E+8 Cs-137 6.2E+5 1.OE+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 -0 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 1 -134 3.OE+4 4.5E+5 I -135 0- 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 Inhalation Pathway, units = em-pCi/r m Food & Ground Pathway, units = (in) (mremn/vr) pCi/sec S01-ODCM Revision 12 2-36 01-29-97 Cw;1-rncM

I I TABLE 2-15 DOSE PARAMETER RI FOR SECTOR F Page 1 of 1 Pathway = San Onofre State Park/Guard Shack Distance = 1.0 miles X/Q = 5.8E-7 sec/Mr3 D/Q = 4.8E-9 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 2.2E+2 Cr-51 2.5E+3 8.OE+5 Mn-54 -- 2.4E+5 2.4E+8 Co-57 6.3E+4 5.9E+7 Co-58 1.6E+5 6.5E+7 Co-60 1.OE+6 3.7E+9 Sr-89 2.4E+5 3.7E+3 Sr-90 1.7E+7 Zr-95 3.OE+5 4.3E+7 Nb-95 8.6E+4 2.3E+7 Ru-103 8.6E+4 1.9E+7 Te-129m 2.OE+5 3.4E+6 Cs-134 1.5E+5 1.2E+9 Cs-136 2.5E+4 2.6E+7 Cs-137 1.1E+5 1.8E+9 Ba-140 2.2E+5 3.5E+6 Ce-141 6.2E+4 2.3E+6 Ce-144 -O- -- 1.3E+6 1.2E+7 I -131 2.OE+6 2.9E+6 1 -132 2.OE+4 2.1E+5 I -133 3.7E+5 4.2E+5 I -134 5.1E+3 7.7E+4 1 -135 7.7E+4 4.3E+5 UN-ID 1.5E+5 1.3E+8 Inhalation Pathway, units = mrm/vr pCi/rm 2

Food & Ground Pathway, units = (i ) (mrem/yr) pCi/sec S01-00CM Revision 12 2-37 01-29-97 SO -ODCM

TABLE 2-16 DOSE PARAMETER R, FOR SECTOR G Paqe 1 of 1 Pathway = San Onofre State Park Beach Distance = 1.1 miles Campground X/Q = 5.2E-7 sec/m 3 D/Q = 2.4E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- -Food & Inhala- Food & Inhala- Food &

Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 B.OE+1 1.4E+2 . 1.6E+2 _-0 2.9E+2 Cr-51 1.6E+3 5.7E+5 2.1E+3 5.7E+5 2.6E+3 5.7E+5 3.3E+3 1.1E+6 Mn-54 1.2E+5 1.7E+8 1.9E+5 1.7E+8 2.4E+5 1.7E+8 3.2E+5 3.2E+8 Co-57 4.7E+4 4.2E+7 6.3E+4 4.2E+7 7.2E+4 4.2E+7 8.4E+4 7.8E+7 Co-58 9.6E+4 4.7E+7 1.4E+5 4.7E+7 1.7E+5 4.7E+7 2.1E+5 8.7E+7 Co-60 5.6E+5 2.7E+9 8.7E+5 2.7E+9 1.1E+6 2.7E+9 1.4E+6 4.9E+9 Sr-89 2.5E+5 2.7E+3 2.7E+5 2.7E+3 3.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 Zr-95 2.2E+5 3.1E+7 2.8E+5 3.iE+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 1.3E+7 8.2E+4 1.3E+7 9.7E+4 1.3E+7 1.2E+5 2.5E+7 Te-129m 2.1E+5 2.4E+6 2.2E+5 2.4E+6 2.4E+5 2.4E+6 2.6E+5 4.5E+6 Cs-134 8.7E+4 8.4E+8 1.3E+5 8.4E+8 1.4E+5 8.4E+8 I.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 1 -131 1.8E+6 2.1E+6 2.OE+6 2.1E+6 1.8E+6 2.IE+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 1 -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 1 -135 8.6E+4 3.1E+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 = mremlr pUCi/rn 2

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

II 3.0 TOTAL AND PROJECTED DOSES 3.1 LIOUID 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 SOI-ODCM Revision 9 3-1 08-04-93 SO1-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 s 25 mrem to the total body or any organ (except the thyroid which shall be limited to s 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 Report, as defined in 10CFR20.2203(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 SOI -ODCM

I I 3.0 TOTAL AND PROJECTED DOSES (Continued) 3.3 DOSE (Continued) 3.3.2 SURVEILLANCE ADglicability: At all times.

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

SDecification: 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-ODCM 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 AnnualTotal 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.

SO] -00CM Revision 8 3-4 06-29-92 SOn -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 (DTOT (0))

12 2/3- 41*

D10T (0) = l E [ DJ1(OG) + DJ,(OL) + D,1 (0G)l (3-1) 1=1 j=1 JH NOTE: Di, (OG) = 0 for bone

All to be summed over the most recent 12 months.

where: n DJ I(OG) = K £ C1 EkRjk Wk (3-2) i=1 i = each isotope in specific organ category i Units 1, 2 and 3 1 = months 1 - 12 K = 3.1688E-2 vear-uCi sec-Ci n = number of isotopes in the specified organ category C, = total particulate gas curies released for the month Z Rik Wk = controlling location factors from ODCM k Table 2-5, Unit 1 and Table 2-6. Units 2/3 Dj1(OL) = liquid organ dose for the specified organ, in mrem, for the 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)]

SO1-ODCM Revision 9 3-5 08-04-93 SOI -ODCM

3.0 TOTAL AND PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 'TOTAL DOSE'TOH*OST LIKELY MEMBER OF THE PUBLIC (Continued) 3.4.1.2 ANNUAL TOTAL WHOLE BODY DOSE (DIOT (WB))

12 2/3 D101(WB) = E E [DJ1(WBL) + ; D" (OG) + 0.9 Dj1 (y)] + D(Direct) (3-3) 1=1 j=1

'To be summed-overlthe most recent 12 months.

., . ,i where

j = 'Units 1. 2 and 3 I = months 1 - 12-DJ1 (WBL) :'liquid whole body organ dose mrem. for the whole month.' [Unit 1 (1-13), Units 2/3

.:(1-19)]

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

DJ I(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),

D (Direct) = z nmax[D(site)1] - P=1 - .0342 (3-4) 0=1 n p = .for all TLDs per 'quarter q = t (. for Quarters 1-4

.0342 =

prorated occupancy factor based on

! _300 hours/year.

site - ILD locations within 5 miles of the site.

S01-ODCM Revision 11 3-6 12-06-95 S0l -ODCM

II 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 (DTO0 (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 is subtracted from the highest reading TLD within 5 miles of the site (generally numbers 55 through 58). This value is the direct dose but must be prorated by the occupancy factor.

Example: Beach time (west boundary, seawall) of 300 hrs/yr, east and north boundaries of 20 hrs/yr, or 8 hrs/yr for the south boundary and west fence of parking lot 1 (top of bluff).

Reference:

E. M. Goldin memorandum for file, "Occupancy Factors at San Onofre Owner Controlled Area Boundaries", dated October 1, 1991.

3.4.1.3 ANNUAL TOTAL THYROID DOSE (DTOT (T))

12 2/3 DTOT(T) = E E [oDJ (OG) + Dj1 (OL) (3-5) 1=1 j=1 To be summed over the most recent 12 months.

where:

i = Units 1, 2 and 3 1 = months 1 - 12 DJ1(OG) = thyroid organ dose from gaseous iodine for the month, mrem. [from (3-2)]

DI,(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 SO0 -ODCM

4.0 EQUIPMENT 4.1 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION 4.1.1 SPECIFICATION Aovl icabilitv: 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.

SOI-ODCM Revision 17 4-1 07-20-00 S01-ODCM

II 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 Line (R-1218) (1) 16

b. DELETED

c. Turbine Building Sumps Effluent Line (1) 18 (Reheater Pit Sump) (R-2100)

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 1

c. DELETE

3. Plant Information Monitoring System (PIMS) 2 25 (1)

(Control Room Alarm Annunciation)

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

2Applies to each effluent radiation monitor that utilizes the PIMS, as they are turned over to station.

S01-OCM Revision 17 4-2 07-20-00 SO1 -ODCM

TABLE 4-1 (Continued)

T. . NO TI 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 I hour 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.

SOl-OCM Revision 17 4-3 07-20-00 S01 -ODCM

I' 4.0 EOUIPMENT (Continued) 4.1 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION (Continued) 4.1.2 SURVEILLANCE ADplicability: During releases via this pathway.

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

Specification: 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.

SO1-ODCM Revision 10 4-4 04-27-94 SO0 -ODCM

TABLE 4-2 I

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS INSTRUMENT - CHANNEL ISOURCE 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) 0(1)

Line (R-1218) --

b. DELETED `

c. Turbine Building Sump D M (6) 18M (3) Q(l)

Effluent Line (Reheater,' :

Pit sump R-2100)

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

(R-2101)

e. DELETED

2. Flow Rate Monitors

a. Liquid Radwaste Effluent - D(4) N/A i8M N/A Line (FE-16/FT-8, FE-!

18/FT-10)

3. Plant Information Monitoring D(7) N/A N/A(5) Q(1)

System (PIMS) (Control Room Alarm Annunciation)

S01-ODCM Revision 17 4-5 07-20-00 SO0 -ODCM

I I 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 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 Field Interim Design Change Notice (FIDCN).

(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.

(7) Effective upon turnover of the first MGPI monitor.

SO1-ODCM Revision 18 4-6 02-21-01 SO0 -ODCI4

4.0 EQUIPMENT (Continued) 4.2 RADIOACTIVE; GASEOUS EFFLUENT INSTRUMENTATION 4.2.1 SPECIFICATION AD0licability: During releases via this pathway.

Objective: Monitor and control radioactive gaseous releases.

Specification: A. The radioactive gaseous effluent monitoring instrumentation channels showin 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. '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 17 4-7 07-20-00 S03 -ODCM

I 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 (1) 22 C. Iodine Sampler CARTRIDGE R-1254' (1) 23

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

e. Deleted

f. Sampler Flow Rate Measuring Device (1) 24

2. Plant Information Monitoring System (PIMS)5 (1) 26 (Control Room Alarm Annunciation)

Includes the following, subsystems:

a. Spent Fuel Building ventilation and Auxiliary Building ventilation.

b. Containment Building ventilation 2 DELETED.

3 DELETED.

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)

Heat tracing is required to be functional.

-' Applies to each effluent radiation monitor that utilizes the PIMS, as they are turned over to station.

SOI-ODCM Revision 17 4-8 07-20-00 sO1-ODCM

TABLE 4-3 (Continued)

TABLE NOTATION ACTION 21 DELETED ACTION 22 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 maycontinue, 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 and iodine 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 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.

SOl-ODCM Revision 17 4-9 07-20-00 SOI -ODCM

I I 4.0 EQUIPMENT (Continued) 4.2 RADIOACTIVE GASEOUS PROCESS AND EFFLUENT INSTRUMENTATION (Continued) 4.2.2 SURVEILLANCE ADDlicability: During releases via this pathway.

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

Speci ficati on: A. 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.

SO1-ODCM Revision 10 4-10 04-27-94 SO0 -ODCM

. I 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 D M(5) 18M(2) Q(1)

c. Iodine Sampler Cartridge R-1254 N/A N/A N/A N/A

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 D N/A 18M N/A Device

2. Plant Information Monitoring System D(6) N/A N/A(4) Q(1)

(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 Field 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) Effective upon turnover to station of the R-1254/PIMS configuration.

SO1-00CM Revision 17 4-11 07-20-00 SO1 -ODCM

- - I I 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.

SO1-ODCM Revision 10 4-12 04-27-94 SOl -ODCM

U, 0

r) 0 CCW HXI Turbine Condenser Euipment. Drains

& Valve Leakage Spent nesin Drain akDeisTn Dmn a Decon Showers Aux Bldg Auxiliary floor drains l Building - -- Filter ecuip leakage& I Surnp lank drains Fuel StorageDeo Rdg DransDrain Bldg Drans Tank Decon Shower Tank sri Pacific Ocean SONGS 1 Liquid Waste Discharge System Figure 4-1 SO1-ODCM Revision 17 4-13 07-20-00

AIR SFP FAN I AIR - Auxiliary Building Rad \

Monitor To Atmosphere SONGS 1 Radioactive Gaseous-Waste System Figure 4-2 SO1-ODCM Revision 15 4-14 05-03-99

Spent Reagm pArtlewlata Pree:s Filters A. I._ _

. . 3 Low evel try Active Waste tlothin pickedlthn Clatktng, bil Iselts aid lanere 1.14111:

Irotective collected freom skhie toWnd to SIT: Spat Itile Teat Clething points arewu off-sitslte te edim recimi pWirt Ritim per"%*wawe ptlant lanry rsitocked Man!. Exchanger Ifecliltyn tet SONGS 1 Solid Waste Handling Figure 4-3 SO1-ODCM Revision 15 4-15 05-03-99

II 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 specified in Table 5-1. prepare and submit to the Commission, in the Annual Radiological 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) + ... z 1.0 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.

SO1-ODCM Revision 10 5-1 04-27-94 S01 -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 SOI-ODCM4

TABLE 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Sample and Sample Locations' Collection Frequency' Type 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 1-131.

and 3 samples from offsite sample collection as Particulate sampler. Analyze for Particulates locations (in different required by dust gross beta radioactivity a 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 Sample and Samnle Locations' Collection Frequency TyDe and Frequency 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.

I .

b. Drinking' 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.

SO1-ODCM Revision 14 5-4 02-25-99

TABLE 5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Sample and Sample Locations' Collection Frequency' 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 as crab or lobster.

3. Mollusks - such as limpets, clams or.

seahares.

b. Local Crops 2 locations Representative Gamma isotopic analysison 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.

S01-00CM Revision 8 5-5 06-29-92

9.

TABLE 5-1 (Continued)

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.

S01-ODCM Revision 14 5-6 02-25-99

En 0

0I-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/nm') (pCi/Kg. wet) (pCi/Kg. wet)

H-3 2 x 10" Mn-54 1 x lo, 3 x 10' Fe-59 4 x 10 I x 10' Co-58 1 x l0o 3 x 10' Co-60 3 x 102 1 x 10' Zn-65 3 x 102 2 x 10' Zr-Nb-95 4 x 102 1-131 2 0.9 1 X 10Z Cs-134 30 10 1 x 103 IXl Cs-137 50 20 2 x 103 2 x 103 Ba-La-140 2 x 102 a If no drinking pathway exists, a value of 30,000 pCi/i may be used.

If no drinking water pathway exists, a value of 20 pCi/ft 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 SOI -ODCM

TABLE 5-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)n'c Airborne Particulate Water or Gases Marine Animals Local Crops Sediment Analysis (pCi/i) (pCi/m 3 ) (pCi/Kg. wet) (pCi/Kg, wet) (pCi/kg, dry)

Gross beta 4 I x lo-H-3 2O000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95, Nb-95 15 I-131 id 7 x 10. 60.

Cs-134 15 5 x 102 130 60 150 Cs-137 18 6 x 10.2 150 80 180 Ba-140, La-140 15 SO1-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 x 106- 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 Driori (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 SO -ODCM

I I TABLE 5-3 (Continued)

TABLE NOTATION

b. If no drinking water pathway exists, a value of 3,000 pCi/9 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/Q 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-O0CM Revision 12 5-11 01-29-97 SO -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 SOI -ODCM

I I 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.

SO1-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)

SOI-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 Interlaboratory Comparison Program and in accordance with the ODCM shall be included in the Annual Radiological Environmental Operating Report.

(Section 5.4)

SOl-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 surveillancetactivities 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.

IA single submittal may:beimade 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 S01 -ODCM

I I 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.5 SAMPLE LOCATIONS' The Radiological Environmental Monitoring Sample Locations are identified in Figures 5-1 through 5-5. These sample locations are described in 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. Table 5-6 gives the sector and direction designation for the Radiological Environmental Monitoring Sample Location Map, Figures 5-1 through 5-5.

'If a milk producing dairy animal is discovered within the 5 mile radius of the Emergency Planning Zone (EPZ) during the annual land use census, a monthly sampling analysis of the milk will commence.

S01-ODCM Revision 18 5-17 02-21-01 SOI -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 #1)! 0.7 WNW 11 Former Visitors' Center 0.4" NW 12 South Edge of Switchyard 0.2 E 13 Southeast Site boundary (Bluff) - 0.4- ESE 15 Southeast Site Boundary (Office Building) 0.1- SSE 16 East Southeast Site Boundary 0.4" ESE 17 Transit Dose -

18 Transit Dose -

19 San Clemente Highlands 5.0 NNW 22 Former U.S. Coast Guard Station - San Mateo Point 2.7 WNW 23 Samaritan Hospital San Clemente 8.1 NW 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 PlC - Pressurized Ion Chamber SOl-ODCM Revision 14 5-18 02-25-99 SOI -ODCM

TABLE 5-4 Page 2 of 6 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DI STANCE' TYPE-OF SAM4PLE AND SAMPLING-LOCATION" (__

miles) DlRECTION 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) 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 S0l -ODCM

. - TABLE 5-4 TABL5-4Page 3 of 6 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE' 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.I WSW 58 San Onofre State Beach (Unit 3) 0.I 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 Pendletdn (Adjacent to PIC #5) 0.6 NN E 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 O.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 'milein all 'sectors) a~nd not required by Technical Specification.

MCB - Marine Corps Base PIC Pressuri-zed Ion Chamber For fading correction due to significant increase in temperature.

S01 -ODCM Revision 14 5-20 02-25-99 S01 -ODCM4

I I TABLE 5-4 Page 4 of 6 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION 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 t l 1 Camp San Onofre 2.6 NE 2 Old Route 101 - East Southeast 3.0 ESE 3 Basilone Road/I-5 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.

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.

SO1-ODCM Revision 20 5-21 02-28-03 S0l -ODCM

.TABLE 5-4 Page 5 of 6 RADIOLOGICAL ENVIRONMENTAL MONITORING'SAMPLE LOCATIONS DISTANCE

.TYPE nF SAMPI r ANI) ZAMPI TMr I nrATTlnN (mi1lar- liRrCTTnN

... , v. a-,, us ,, vn.vtt -muE .n k..w...

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 ks 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.

SOl-ODCM Revision 19

-- 5-22 02-28-02 SO -ODCM

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

TYPE OF SAMPLE AND SAMPLING LOCATION fmiles) DIRECTION*

Non-Migratory Marine Animals A Unit 1 Outfall 0.9 W'SW B Units 2 and 3 Outfall 1.5 SSW C Laguna Beach (CONTROL) 18.2 NW Kelpt IP 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.

1A SOl-ODCM Revision 20 5-23 02-28-03 So0 -ODCM

-:TABLE 5-5 PIC - RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS SONGS 1 Theta DISTANCE PRESSURIZED JON CHAMBERS (Deqrees) 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 SB MCB - Camp Pendleton 980 1120 0.7 E E S9 San Onofre State Beach 121° 940 0.6 ESE F Distance (meters/miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Theta direction is determined from degrees true north.

S01-ODCM Revision 18 5-24 02-21-01 SOl -ODCM

I I TABLE 5-6 SECTOR AND DIRECTION DESIGNATION FOR RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATION MAP DEGREES TRUE NORTH -

FROM SONGS 2 AND 3 MID-POINT. NOMENCLATURE Sect or Center Sector 22.50 Limi t Line Limit Sector Direction 348..75 0 & 360 11.25 A N

11. .25 22.5 33.75 B NNE 33..75 45.0 56.25 C NE

56. .25 67.5 78.75 D ENE 78..75 90.0 101.25 E E 101. .25 112.0 123.75 F ESE 123 .75 135.0 146.25 G SE 146 .25 157.0 168.75 H SSE 168 .75 180.0 191.25 J S 191 .25 202.5 213.75 K SSW 213 .75 225.0 236.25 L S 236 .25 247.5 258.75 M WSW 258 .75 270.0 281.25 N W 281 .25 292.5 303.75 P WNW 303 .75 315.0 326.25 Q NW 326 .25 337.5 348.75 R NNW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true North.

So1-ODCM Revision 15 5-25 05-03-99 SO1-ODCM

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

ACTION 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 to known 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.

S01-ODCM Revision 9 6-1 08-04-93 SO1 -ODCM

6.0 ADMINISTRATIVE (Continued) 6.1 DEFINITIONS (Continued)

FREQUENCY 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 maintenance practices 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 shall include nonemployees of the licensee who are permitted to use portions of the site for recreational, occupational, or purposes not associated with plant functions. This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter an area that is controlled by the licensee for purposes of: protection of individuals from exposure to radiation and radioactive materials.

SOI-ODCM Revision 17 6-2 07-20-00 S01 -ODCM

I I 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 determination by 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.

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

SOURCE CHECK 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.

SO1-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 to any Action Statements.

UNETR E A 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.

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

I I TABLE 6-2 FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months w At least once per 7 days M At least once per 31 days Q At least once per 92 days SA At least once per 184 days 18M At least once per 18 months P Completed prior to each release N.A. Not applicable SOl-ODCM Revision 9 6-5 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 IOCFR100.3 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 SOI -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 determinedby sampling frequency and measurement) 'shall be used for determining the gaseous pathway 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.

SD.-.DCM Revision 9 6-B 08-04-93 SO0 -ODCM

II 6.0 ADMINISTRATIVE (Continued) 6.3 ADMINISTRATIVE CONTROLS (Continued) 6.3.2 (Continued)

The radioactive effluent release report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 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. Container volume,

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 any changes made 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.

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 Gaseous)

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

1. Shall 'be -reported to the Commission in the Annual

-Radioactive Effluent Release Report for the period in which-the'change(s) was made effective pursuant to Technical Specification D6.5.2.9. 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 changeiwhich shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from

'those oreviously'predicted in the license application and amendments thereto;

e. Anwevaluation 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 Technical Specification D6.5.2.

2. Shall become effective upon review and acceptance pursuant to Technical Specification D6.5.2.

'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.

S01-ODCM Revision 18 6-10 02-21-01 SOI -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. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site-will result in exposures within (1)the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a 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.

LIQUID EFFLUENT DOSE (1.2.1) 6.4.2 This specification is provided to implement the requirements of Section II.A and 1V.A of Appendix I, 10 CFRPart 50. Specification A implements the guides set forth 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 I to 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 1, 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.

SOl-ODCM Revision 8 6-11 06-29-92 SOI -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 gas low 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 5O.' 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 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 s 500 mrem/year to the total body or to.; 3000 mrem/year'to the skin. These release rate limits'also restrict, at all times, the corresponding-thyroid'dose rate above background to a child via-the inhalation pathway to s 1500 mrem/year.

SOI-ODCM Revision 10 6-12 04-27-94 SO -ODCM

I' 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 time implements 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 was low as is reasonably achievable."

DOSE. NOBLE GASES (2.2.2) 6.4.7 This specification implements the requirements in Section III.A of Appendix I, 10 CFR Part 50, that conformance with the guides of Appendix 1, 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. IODINE-131. IODINE-133. 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, IODINE-131. IODINE-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM (2.3.2) 6.4.9 This specification implements the requirements in Section III.A of Appendix 1, 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 10 6-13 04-27-94 S0l -ODCM

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued) '

DOSE, IODINE-131. IODINE-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM (2.3.2) (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

- iodine-131,'iodine-133,'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 DOS (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, nu' I,,'clear-fuel cycle facilities over five miles away are not considered to contribute to the dose assessment.

S01-ODCM Revision 9 6-14 08-04-93 So1 -ODCW

I I 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 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle.

RADIOACTIVE LIOUID EFFLUENT INSTRUMENTATION (4.1.1, 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 CFR Part 20.

RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION (4.2.1. 4.2.2) 6.4.14 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 CF Part 20.

S01-ODCM Revision 8 6-15 06-29-92 S01 -ODCM

-' rI 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 in those 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 th6reby 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 'apriori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in'such a manner that the stated LLDs will be achieved under routine 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 SOI -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.

SOl-ODCM Revision 8 6-17 06-29-92 S0 -ODCM

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