Text

Annual Radioactive Effluent Release Report 2009
	ML101240921
Person / Time
Site:	San Onofre
Issue date:	04/28/2010
From:	Onge R; Southern California Edison Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML101240921 (217)
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SOUTHERN CALIFORNIA Richard I. St. Onge FDI S0'NJ Director Nuclear Regulatory Affairs An EDISON INTERNATIONAL Company 10 CFR 50.36(a)

April 28, 2010 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Subject:

Docket Nos. 50-206, 50-361 and 50-362, Annual Radioactive Effluent Release Report - 2009 San Onofre Nuclear Generating Station, Units 1, 2, and 3

Dear Sir or Madam:

In accordance with 10 CFR 50.36(a), 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 - 2009 (ARERR) for San Onofre Nuclear Generating Station, Units 1, 2, and 3.

The period of the report is January 1, 2009 through December 31, 2009.

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 Manual (ODCM) for this reporting period to be submitted with the ARERR.

On February 27, 2009, S0123-ODCM, Revision 2 was issued and is included with this submittal. To comply with Technical Specification 5.5.2.1.1, change bars are included on all affected pages.

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

P.O. Box 128 San Clemente, CA 92674

Document Control Desk April 28, 2010 : Annual Radioactive Effluent Release Report - 2009 : ODCM, S0123-ODCM, Revision 2 cc: E. E. Collins, NRC Regional Administrator, Region IV J. E. Whitten, NRC Region IV, Nuclear Material Safety Branch Chief R. Hall, NRC Project Manager, SONGS Units 2 and 3 J. C. Shepherd, NRC Project Manager, SONGS Unit 1 G. G. Warnick, NRC Senior Resident Inspector, SONGS Units 2 and 3 S. Y. Hsu, California Department of Public Health

Enclosure 1:

Annual Radioactive Effluent Release Report - 2009

SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2009 January - December

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PREFACE San Onofre Nuclear Generating Station (SONGS) 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. By August 31, 2004, all fuel was transferred to the Independent Spent Fuel Storage Installation (ISFSI). As of November 29, 2006, all remaining monitored effluent pathways were permanently removed from service. Unit 1 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 (78.21%), San Diego Gas and Electric (20%), and the City of Riverside (1.79%).

Effective December 29, 2006, the City of Anaheim transferred its ownership interests in San Onofre Units 2 and 3 and the entitlement to the Units 2 and 3 output, to Southern California Edison Company, except that it retains its-ownership interests in its used nuclear fuel and Units 2 and 3's independent spent fuel storage installation located on the facility's site. In addition, the City of Anaheim retains financial responsibility for its used fuel and for a portion of the Units 2 and 3 decommissioning costs.

The City of Anaheim remains a licensee for purposes of its retained interests and liabilities.

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San Onofre Nuclear Generating Station

TABLE OF CONTENTS SECTIO N A - INTRO DUCTIO N ....................................................... 1 SECTION B - GASEOUS EFFLUENTS ................................................. 2 SECTION C - LIQUID EFFLUENTS ................................................... 11 SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM ........ 19 SECTION E -RADWASTE SHIPMENTS U NIT S 2 & 3 ................................................................ 20 DECO MMISSIO NED UNIT 1 .................................................. 25 C O MMO N ................................................................. 28 SECTION F - APPLICABLE LIM ITS ................................................... 30 SECTION G - ESTIMATION OF ERROR ..................................... I .......... 34 SECTION H - 10 CFR 50 APPENDIX I REQUIREMENTS ................................. 35 SECTION I - CHANGES TO OFFSITE DOSE CALCULATION MANUAL ..................... 39 SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS ................ 41 SECTION K - MISCELLANEOUS .............................................. ..... 41 Abnormal Releases ..................................................... 41 Effluent Monitors Out of Service Greater Than 30 days .............................. 42 Onsite Groundwater Samples ... ............. 47 40 CFR 190 Requirem ents ..................................................... 49 SECTION L - SONGS CONCLUSIONS ................................................ 50 MET EO R O LO G Y ................................................................ 51

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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION 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. It will also summarize the radwaste shipments from the decommissioning of 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 - 2009 SAN ONOFRE NUCLEAR GENERATING STATION 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-1 31, 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 1 B, "Gaseous Effluents-Elevated Release," has not been included in this report since San Onofre Nuclear Generating Station does not conduct elevated releases.

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

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

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES A. Fission and activation gases

1. Total release Ci 2.76E+1 2.27E+1

2. Average release rate for period pCi/sec 3.54E+0 2.88E+O 3.00E+1

3. Percent of applicable limit % MPC 5.83E-3 4.83E-3

4. Percent Effluent Concentration Limit % ECL 4.09E-3 3.76E-3 B. lodines

1. Total iodine-131 Ci 2.38E-5 4.82E-5

2. Average release rate for period pCi/sec 3.06E-6 6.13E-6 1.90E+1

3. Percent of applicable limit % MPC 1 ;47E-5 2.94E-5

4. Percent Effluent Concentration Limit % ECL 7.35E-6 1.47E-5 C. Particulates

1. Particulates with half-lives >8 days Ci 1.24E-5 2.44E-6

2. Average release 'rate for period pCi/sec 1.59E-6 3.1 OE-7 1.60E+1

3. Percent of applicable limit % MPC 6.21E-7 3.05E-7

4. Percent Effluent Concentration Limit % ECL 1.45E-6 8.27E-7

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

1. Total release Ci 1.37E+1 2.35E+1

2. Average release rate for period pCi/sec 1.76E+0 2.99E+0 2.50E+1

3. Percent of applicable limit % MPC 4.23E-3 7.17E-3

4. Percent Effluent Concentration Limit % ECL 8.46E-3 1.43E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1A (Continued)

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

A. Fission and activation gases

1. Total release Ci 2.83E+1 2.71E+1

2. Average release rate for period pCi/sec 3.57E+0 3.42E+0 3.00E+1

3. Percent of applicable limit % MPC 7.81E-3 5.52E-3

4. Percent Effluent Concentration Limit % ECL 1.29E-2 3.51 E-3 B. lodines

1. Total iodine-131 Ci 8.47E-5 1.41E-4

2. Average release rate for period pCi/sec 1.07E-5 1.77E-5 1.90E+1

3. Percent of applicable limit % MPC 5.11E-5 8.51E-5

4. Percent Effluent Concentration Limit % ECL 2.56E-5 4.26E-5 C. Particulates

1. Particulates with half-lives >8 days Ci 8.19E-5 1.35E-4

2. Average release rate for period pCi/sec 1.03E-5 1.70E-5 1 .60E+1

3. Percent of applicable limit % MPC 3.60E-6 1.61 E-5

4. Percent Effluent Concentration Limit % ECL 7.73E-6 8.34E-5

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

1. Total release Ci 2.37E+1 2.46E+1

2. Average____

release

___ rate

____ ___ for

___period

______ ___ __ _ pCi/sec

___ __ 2.98E+0 3.09E+0

___ __- 2.50E+1

3. Percent of applicable limit % MPC 7.16E-3 7.43E-3

4. Percent Effluent Concentration Limit % ECL 1.43E-2 1.49E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SANONOFRE NUCLEAR GENERATING STATION 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 argon-41 Ci 1.18E-1 1.66E-1 1.61E+0 3.94E-2 krypton-85 Ci <LLD <LLD <LLD <LLD krypton-85m Ci <LLD <LLD <LLD <LLD krypton-87 Ci <LLD <LLD <LLD <LLD krypton-88 Ci <LLD <LLD <LLD <LLD xenon-133 Ci 2.67E+1 2.25E+1 2.57E+1 2.71E+1 xenon-133m Ci 1.02E-2 <LLD 5.1OE-2 9.10E-3 xenon-135 Ci <LLD 4.23E-5 2.39E-3 1.09E-3 xenon-135m Ci <LLD <LLD <LLD <LLD xenon-1 38 Ci <LLD <LLD <LLD <LLD Total for period Ci 2.69E+1 2.27E+1 2.74E+1 2.71E+1

2. lodines iodine-131 Ci 2.38E-5 4.82E-5 8.47E-5 1.41E-4 iodine-132 Ci <LLD <LLD 2.23E-7 <LLD iodine-133 Ci 1.19E-5 9.48E-5 1.48E-4 6.35E-6 iodine-135 Ci <LLD <LLD <LLD <LLD Total for period Ci 3.57E-5 1.43E-4 2.33E-4 1.48E-4 LLD Lower Limit of Detection; see Table 1D.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1C (Continued)

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

3. Particulates barium-140 Ci <LLD <LLD <LLD <LLD bromine-82 Ci 2.42E-5 3.74E-5 8.44E-5 7.22E-6 cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD 3.45E-6 <LLD cesium-137 Ci 2.46E-6 2.35E-6 7.78E-6 1.31 E-5 cobalt-58 Ci 9.85E-6 <LLD 7.06E-5 5.71 E-5 cobalt-60 Ci 6.44E-8 8.98E-8 6.34E-8 6.28E-5 iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci <LLD <LLD <LLD 1.90E-6 molybdenum-99 Ci <LLD <LLD <LLD <LLD rubidium-88 Ci <LLD <LLD 2.40E-4 <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD LLD Lower Limit of Detection; see Table 1 D.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1C (Continued)

GASEOUS EFFLUENTS-G ROUND LEVEL RELEASES BATCH MODE

First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission and activation gases krypton-85 Ci 6.94E-1 ** 9.82E-1 **

krypton-85m Ci <LLD ** <LLD **

krypton-87 Ci <LLD ** <LLD **

krypton-88 Ci <LLD ** <LLD **

xenon-133 Ci <LLD ** <LLD **

xenon-1 33m Ci <LLD ** <LLD **

xenon-135 Ci <LLD ** <LLD **

xenon-1 35m Ci <LLD ** <LLD **

xenon-138 Ci <LLD ** <LLD **

Total for period Ci 6.94E-1 ** 9.82E-1 **

LLD Lower Limit of Detection; see Table 1 D.

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

- - No batch releases were conducted in the second and fourth quarters of 2009.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1 D GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION CONTINUOUS and BATCH MODE Continuous Mode Batch Mode Radionuclides LLD (pCi/cc) LLD (pCi/cc)

1. Fission and activation gases krypton-85 1.60E-5 **

krypton-85m 3.70E-8 2.30E-6 krypton-87 1.90E-7 9.80E-6 krypton-88 1.30E-7 8.1OE-6 xenon-1 33

5.1OE-6 xenon-1 33m 3.00E-7 2.OOE-5 xenon-1 35 3.90E-8 2.50E-6 xenon-135m 1.50E-6 3.OOE-5 xenon-1 38 2.60E-6 4.80E-5

2. lodines iodine- 132 1.30E-9 N/A iodine- 135 1.50E-10 N/A

3. Particulates barium-140 4.60E-13 N/A cerium-141 5.80E-14 N/A cerium- 144 2.30E-13 N/A cesium-134 1.30E-13 N/A cobalt-58 1.20E-13 N/A iron-59 2.90E-13 N/A lanthanum- 140 9.20E-13 N/A manganese-54 1.20E-13 N/A molybdenum-99 7.OOE-14 N/A rubidium-88 6.50E-9 N/A strontium-89 1.OOE-11 N/A strontium-90 1.OOE-11 N/A zinc-65 3.10E-13 N/A

4. alpha 1.OOE-11 N/A

Radionuclide was >LLD in all 4 quarters.

- Radionuclide was >LLD in all quarters where batch releases were conducted.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1E 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 1.61 E-3 1.42E-3 3.69E-3 1.51E-3

2. Percent Applicable Limit % 1.61 E-2 1.42E-2 3.69E-2 1.51 E-2

3. Beta Air Dose mrad 4.54E-3 3.67E-3 5.22E-3 4.35E-3

4. Percent Applicable Limit % 2.27E-2 1.84E-2 2.61 E-2 2.17E-2 B. Tritium, Iodine, Particulates (at the nearest receptor)

1. Organ Dose mrem 1.87E-3 3.74E-3 3.96E-3 5.31E-3

2. Percent Applicable Limit % 1.25E-2 2.50E-2 2.64E-2 3.54E-2 NOTE: Calculations performed in accordance with the ODCM utilizing the historical X/Q.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1F GASEOUS EFFLUENTS-BATCH RELEASE

SUMMARY

12 month period

1. Number of batch releases: 6 releases

2. Total time period for batch releases: 2138 minutes

3. Maximum time period for a batch release: 447 minutes

4. Average time period for a batch release: 356 minutes

5. Minimum time period for a batch release: 271 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION SECTION C. LIQUID 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.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION 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 4.37E-3 2.65E-3

2. Average diluted concentration during period pCi/ml 5.98E-12 3.50E-12 1.90E+1

3. Percent of applicable limit % MPC 6.39E-6 4.40E-6

4. Percent Effluent Concentration Limit % ECL 3.14E-5 2.06E-5 B. Tritium

1. Total release Ci 2.25E+2 1.76E+2

2. Average diluted concentration during period pCi/mI 3.08E-7 2.32E-7 1.90E+1

3. Percent of applicable limit % MPC 1.03E-2 7.74E-3

4. Percent Effluent Concentration Limit % ECL 3.08E-2 2.32E-2 C. Dissolved'and entrained gases

1. Total release Ci 3.72E-2 5.62E-2

2. Average diluted concentration during period pCi/ml 5.09E-1 1 7.42E-1 1 1 .90E+1

3. Percent of applicable limit % MPC 2.54E-5 3.71 E-5

4. Percent Effluent Concentration Limit % ECL 2.54E-5 3.71 E-5 D. Gross alpha radioactivity

1. Total release Ci <LLD <LLD 5.00E+1 E. Volume of waste released (batch & continuous, prior to dilution) liters 1.13E+7 1.55E+7, 5.OOE+0 F. Volume of dilution water used during period liters 7.31E+11 7.58E+11 I 5.OOE+0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2A (Continued)

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

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 7.24E-3 3.49E-3

2. Average diluted concentration during period pCi/ml 9.53E-12 7.90E-12 1.90E+1

3. Percent of applicable limit % MPC 1.34E-5 1.21 E-5

4. Percent Effluent Concentration Limit % ECL 6.61E-5 8.84E-5 B. Tritium

1. Total release Ci 4.35E+2 2.22E+2

2. Average diluted concentration during period pCi/ml 5.72E-7 5.02E-7 1.90E+1

3. Percent of applicable limit % MPC 1.91 E-2 1.67E-2

4. Percent Effluent Concentration Limit % ECL 5.72E-2 5.02E-2 C. Dissolved and entrained gases

1. Total release Ci 6.51 E-1 7.07E-2

2. Average diluted concentration during period pCi/ml 8.57E-10 1.60E-10 1 .90E+1

3. Percent of applicable limit % MPC 4.28E-4 8.OOE-5

4. Percent Effluent Concentration Limit % ECL 4.28E-4 8.OOE-5 D. Gross alpha radioactivity

1. Total release Ci <LLD <LLD 5.00E+1 E. Volume of waste released (batch & continuous, prior to dilution) liters 1.45E+7 9.55E+6 5.OOE+0 F. Volume of dilution water used during period liters 7.60E+1 1 4.42E+1 1 5.OOE+0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE First Second Third Fourth Radionuclides Released 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 <LLD <LLD <LLD <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 <LLD <LLD <LLD <LLD

2. Dissolved and entrained gases xenon-133 Ci <LLD <LLD <LLD <LLD xenon-1 35 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 - 2009 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2B (Continued)

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

1. Fission and activation products antimony-1 24 Ci 5.92E-6 4.82E-5 <LLD <LLD antimony-1 25 Ci 4.50E-4 3.43E-4 4.94E-4 6.24E-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 <LLD <LLD <LLD <LLD cesiu m-137 Ci 2.72E-6 <LLD 1.08E-5 4.22E-5 chromium-51 Ci 2.90E-4 <LLD 3.24E-4 <LLD cobalt-58 Ci 1.98E-3 7.19E-4 1.43E-3 7.66E-4 cobalt-60 Ci 1.22E-4 1.74E-4 9.04E-4 7.69E-4 iodine-131 Ci <LLD <LLD 9.11E-6 <LLD iron-55 Ci 7.44E-4 8.89E-4 3.1OE-3 8.13E-4 iron-59 Ci 4.39E-5 <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci 4.84E-5 2.51E-5 1.12E-4 7.31E-5 molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci 3.16E-4 2.07E-4 3.89E-4 1.95E-4 niobium-97 Ci <LLD <LLD <LLD 6.99E-6 silver-110m Ci 2.40E-4 1.30E-4 1.81E-4 5.17E-5 strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD technetium-99m Ci <LLD <LLD <LLD <LLD tin-113 ' Ci <LLD 6.58E-6 <LLD <LLD tin-117m Ci <LLD 1.27E-5 <LLD 9.85E-6 zinc-65 Ci <LLD <LLD <LLD <LLD zirconiurm-95 Ci 1.28E-4 9.90E-5 2.92E-4 1.43E-4 Total for period Ci 4.37E-3 2.65E-3 7.24E-3 3.49E-3

2. Dissolved and entrained gases krypton-85 Ci 3.57E-2 2.30E-2 8.24E-2 1.76E-2 xenon-131m Ci 9.92E-4 8.37E-4 1.59E-2 2.61E-3 xenon-133 Ci 5.06E-4 3.23E-2 5.51E-1 5.05E-2 xenon-133m Ci <LLD 1.16E-4 1.80E-3 <LLD xenon-135 Ci <LLD <LLD <LLD <LLD Total for period Ci 3.72E-2 5.62E-2 6.51 E-1 7.07E-2 LLD Lower Limit of Detection; see Table 2C.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION LLD (pCi/ml) LLD (pCi/ml)

Radionuclides Continuous Mode Batch Mode

1. Fission and activation products antimony-1 24 N/A 2.60E-7 barium-1 40 3.OOE-7 2.50E-7 cerium-141 4.60E-8 4.30E-8 cerium-144 1.90E-7 1.90E-7 cesium-134 7.90E-8 7.80E-8 cesium-137 6.70E-8 6.70E-8 chromium-51 3.50E-7 3.20E-7 cobalt-58 7.1OE-8

cobalt-60 1.1OE-7

iodine-131 6.1OE-8 4.60E-8 iron-55 1.OOE-6 iron-59 1.70E-7 1.60E-7 lanthanum-140 5.90E-7 1.90E-7 manganese-54 7.OOE-8

molybdenum-99 6.10E-8 2.80E-8 niobium-95 7.10E-8

niobium-97 N/A 1.60E-7 strontium-89 5.OOE-8 5.OOE-8 strontium-90 5.OOE-8 5.OOE-8 technetium-99m 5.80E-8 2.90E-8 tin-1 13 N/A 5.70E-8 tin-1i17m N/A 2.50E-8 zinc-65 1.80E-7 1.80E-7 zirconium-95 1.20E-7 *

2. Dissolved and entrained gases xenon-133 2.60E-7

xenon-1 33m N/A 7.30E-7 xenon-1 35 9.40E-8 9.40E-8

3. .ross alpha 1.OOE-7 1.OOE-7

Radionuclide was >LLD in all 4 quarters.

N/A - Radionuclide not detected in continuous flow paths ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION 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 4.54E-4 3.49E-4 9.16E-4 4.38E-4

2. Percent Applicable Limit % 1.51 E-2 1.16E-2 3.05E-2 1.46E-2 B.

1. Limiting organ dose mrem 1.60E-3 9.55E-4 2.03E-3 8.91E-4

2. Percent Applicable Limit % 1.60E-2 9.55E-3 2.03E-2 8.91 E-3

3. Limiting organ for period GI/LLI GI/LLI GI/LLI GI/LLI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE

SUMMARY

12 month period

1. Number of batch releases: 221 releases

2. Total time period for batch releases: 31779 minutes

3. Maximum time period for a batch release: 456 minutes

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

5. Minimum time period for a batch release: 64 minutes

6. Average saltwater flow during batch releases: 734000 gpm ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM NONE.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION SECTION E. RADWASTE SHIPMENTS TABLE 3 (Units 2 & 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 1.19E+1 Ci 1.41E+1 3.00E+1

b. Dry active waste (DAW), compactable m3 5.39E+2 and non-compactable Ci 2.55E+0 3.00E+1

c. Irradiated components m3 N/A Ci N/A N/A

d. Other: Filters m3 1.60E+0 Ci 1.37E+0 3.00E+1 Note: Total curie content estimated.

N/A No shipment made.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION

2. Estimate of Major Nuclide Composition (spent resins, filter sludges)

a. americium-241 % 6.36E-07 antimony-124 % 2.71E-04 antimony-125 % 3.66E+00 carbon-14 % 1.63E+00 cerium-144 % 2.59E-02 cesium- 134 % 7.15E-01 cesium-137 % 8.07E+00 chromium-51 % 3.13E-04 cobalt-57 % 2.42E-02 cobalt-58 % 1.85E-01 cobalt-60 % 2.80E+00 iron-55 % 9.13E+00 iron-59 % 1.04E-04 manganese-54 % 2.79E-01 nickel-59 % 5.05E-01 nickel-63 % 7.29E+01 niobium-95 % 1.25E-04 plutonium-238 % 4.26E-07 plutonium-239/240 % 5.87E-07 strontium-89 % 1.39E-05 strontium-90 % 8.21 E-02 technetium-99 % 3.62E-04 zirconium-95 % 5.90E-05 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION

2. Estimate of Major Nuclide Composition (DAW)

b. americium-241 % 2.03E-03 antimony-124 % 6.13E-09 antimony-125 % 8.55E-01 carbon-14 % 3.54E+00 cerium-144 % 9.33E-02 cesium- 134 % 1.51 E+00 cesium-137 % 5.67E+00 chromium-51 % 1.13E-01 cobalt-57 % 6.18E-02 cobalt-58 % 3.75E+00 cobalt-60 % 1.18E+01 curium-242 % 3.02E-06 curium-243/244 % 3.31 E-03 iodine- 129 % 8.13E-04 iron-55 % 3.63E+01 iron-59 % 7.84E-02 manganese-54 % 1.26E+00 nickel-59 % 5.52E-01 nickel-63 % 3.11E+01 niobium-95 % 3.67E-01 plutonium-238 % 1.87E-03 plutonium-239 % 1.71E-03 plutonium-241 % 6.55E-02 strontiurm-89 % 1.02E-01 strontium-90 % 1.86E-02 technetium-99 % 2.51 E+00 tritium % 2.38E-03 zirconium-95 % 1.66E-01

c. not applicable % N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION

2. Estimate of Major Nuclide Composition (filters)

d. americium-241 % 2.82E-03 antimony-125 % 8.93E-01 carbon-14 % 7.29E+00 cerium-144 % 1.57E&02 cesium-134 __% 9.58E-02 cesium- 137 % 1.i10OE+00 cobalt-57 % 2.34E-02 cobalt-58 % 5.67E-03 cobalt-60 % 2.30E+01 curium-242 % 2.83E-06 curium-243 % 6.28E-03 iodine-129 % 2.1OE-05 iron-55 % 2.53E+01 iron-59 % 1.40E-06 manganese-54 % 2.66E-01 nickel-63 % 4.18E+01 niobium-95 % 4.1OE-07 plutonium-238 % 1.64E-03 plutonium-239 % 1.64E-03 plutonium-241 % 5.82E-02 silver- 11Om % 1. 1OE-02 strontium-90 %_1.09E-02 tin- 1i3 % 6.73E-04 tritium % 7.68E-02 zirconium-95 % 8.41 E-05 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION A. SOLID WASTE SHIPPED OFFSITEý FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 3 Type A Cask / Trailer SONGS to EnergySolutions Clive, UT 17 Truck / Flatbed Trailer SONGS to EnergySolutions OakRidge, TN 1 Truck / Flatbed Trailer SONGS to EnergySolutions Clive, UT 1 Truck / Flatbed Trailer SONGS to PermaFix *, FL

PermaFix receives and treats waste and disposes of the residual activity from treatment as their own waste.

Note: SONGS maintains contracts with vendors Studsvik, EnergySolutions, and PermaFix that provide volume reduction services. Studsvik received waste shipments from SONGS in 2008. The processed volume was shipped from the EnergySolutions and Studsvik facilities to Clive Utah using 57 shipments., Those shipments included waste from other generators. SCE's waste volume was a 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 - 2009 SAN ONOFRE NUCLEAR GENERATING STATION SECTION E. RADWASTE SHIPMENTS TABLE 3 (Decommissioned Unit 1)

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), compactable m3 1.57E+2 and non-compactable*: Ci 3.11E-1 3.00E+1

c. Irradiated components: m3 N/A Ci N/A N/A

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

Transported in various General Design Packages; IP-1 and IP-2.

N/A No shipment made.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION Estimate of Major Nuclide Composition (DAW)

a. not applicable % N/A

b. americium-241 % 5.96E-02 carbon-14 % 9.39E-01 cerium-144 % 6.13E-04 cesium-134 % 5.75E-01 cesium-1 37 % 4.86E+01 cobalt-60 % 7.85E+00 curium-242 % 5.26E-09 curium-243/44 % 1.16E-02 iron-55 % 2.36E+00 nickel-63 % 3.83E+01 plutonium-238 % 3.64E-02 plutonium-239/40 % 1.78E-02 plutonium-241 % 7.57E-01 silver-11 Om % 5.75E-04 strontium-90 % 1.72E-01 tritium _2.29E-01 %

c. not applicable % N/A

d. not applicable % N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination SONGS to EnergySolutions, 13 Truck / Flatbed Trailerlive, UT Note: SONGS maintains a contract with EnergySolutions for volume reduction services. SONGS shipped one shipment to EnergySolutions, UT in 2008 that was subsequently processed and shipped in two shipments to Clive, UT in 2009.

These two shipments included waste from other generators. SCE's waste volume was a 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 1RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION COMMON RADWASTE SHIPMENTS TABLE 3 (COMMON)

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 sludges, m3 N/A evaporator bottoms Ci N/A N/A

b. Dry active waste (DAW), m3 N/A compactable and non-compactable Ci N/A N/A m3 N/A

c. Irradiated components Ci N/A N/A m3 N/A

d. Other (filters)

Ci N/A N/A N/A No shipment made.

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

a. not applicable % N/A

b. not applicable % N/A

c. not applicable % N/A

d. not applicable % N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

3. Solid Waste Disposition (SONGS1, 2, and 3)

Number of Shipments Mode of Transportation Destination None No shipments were made N/A 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 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.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION 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/Q) (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 4.80E-6 sec/m 3; the annual average atmospheric dispersion defined in the ODCM.

1 MPCeff n F1

= MPC where: Fi fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT.

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

% ECL = (Rel Rate) (X/Q) (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 = 4.80E-6 sec/m 3; the annual average atmospheric dispersion defined in the ODCM.

1 ECLeff n F1 i., ECL1 where: F= fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT.

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION SECTION F. APPLICABLE LIMITS (Continued)

Liquid Effluents - Applicable 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)

MPCeff 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 MPCeff n F,

° MPC where: Fj fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT.

n = total number of radionuclides identified MPCi = 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)

ECLef where: Dil Conc = total curies released in each category and each quarter divided by the t6 tal 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 ECLef -F, i-I ECL where: F, fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT.

n = total number of radionuclides identified ECLi = 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 - 2009 SAN ONOFRE NUCLEAR GENERATING STATION 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 1 E lists the air doses as calculated using the historical X/Q. The air dose due to noble gases released in gaseous effluents from SONGS (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 SONGS (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 - 2009 SAN ONOFRE NUCLEAR GENERATING STATION 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 SONGS (per reactor) to unrestricted areas shall be limited to the following values:

1. During any calendar quarter: <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.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION 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 2c - 02 + 03 + ... 2.

where: oaj Error associated with each component.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION 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, lodines 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 boundary1 , 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 residence 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 - 2009 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1 Dose * (millirems)

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

Whole Body 4.54E-4 3.49E-4 9.16E-4 4.38E-4 2.16E-3

6) 7) 8) 9) 10)

Organ 1.60E-3 9.55E-4 2.03E-3 8.91 E'4 5.48E-3 AIRBORNE EFFLUENTS 11) 12) 13) 14) 15)

Tritium, lodines, and 4.74E-3 7.94E-3 6.73E-3 8.37E-3 2.78E-2 Particulates NOBLE GASES ** 16) 17) 18) 19) 20)

Gamma 7.08E-3 2.83E-3 8.16E&3 7.81 E-3 2.59E-2

21) 22) 23) 24) 25)

Beta 1.98E-2 7.43E-3 1.15E-2 2.27E-2 6.14E-2

26) 27) 28) 29) 30)

DIRECT RADIATION 9.67E-2 8.29E-2 1.49E-1 1.04E-1 4.15E-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.

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION

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 a child's thyroid and was located in the NNW sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.

12. The maximum organ dose was toa child's thyroid and was located in the NNW sector This was calculated using the assumptions of USNRC Regulatory Guide 1.109.

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

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

15. The maximum organ dose was to a child's thyroid and was located in the NNW 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 NNE 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, andocalculated 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 NNE 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 - 2009 SAN ONOFRE NUCLEAR GENERATING STATION

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 S 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 S 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 WSW 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 S sector.

TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 1.51 E-2 1.16E-2 3.05E-2 1.46E-2 3.60E-2 Organ 1.60E-2 9.55E-3 2.03E-2 8.91E-3 2.74E-2 AIRBORNE EFFLUENTS Tritium, lodines, and 3.16E-2 5.29E-2 4.49E-2 5.58E-2 1.85E-1 Particulates 3652 2 . - 5 2 1 E NOBLE GASES Gamma 7.08E-2 2.83E-2 8.16E-2 7.81E-2 2.59E-1 Beta 9.92E-2 3.71E-2 5.75E-2 1.13E-1 3.07E-1 NOTE: Direct Radiation is not specifically addressed in the Applicable Limits.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 27, 2009, Revision 2 of the SONGS Offsite Dose Calculation Manual (ODCM) was adopted and published. This change incorporated the following:

1. Incorporated the latest updates related to the 2008 Land Use Census (LUC) from the J.W. Scott to D. Dick Memorandum for File, "2009 Dose Parameters for SONGS," dated January, 29 2009, 2, Revised/Deleted/Added "type of samples and sampling location" in table 5-4 and Table 5-5, per the Memorandum for File, "SO123 Offsite Dose Calculation Manual (SO123-ODCM) Revision 2, Table 5-4 and Table 5-5 recommended changes", dated February 20, 2009, 3, Included the Memo to File in Appendix B as the bases for the changes to section 5 of the ODCM, 4, Edited formatting errors in Appendix A.

No 50.59 or effluent ODCM evaluation reviews were required or performed for the editorial changes.

None of the changes impacted the accuracy or reliability of effluent dose or setpoint calculations. The level of radioactive effluent control required by 10CFR20, 40CFR190, 10CFR50.35a 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 Page # changes due to LUC Reason 2-29 revised Units 2&3 CLF R Ai Updated LUC references R A1-5 update Ri table R A1-8 update R, table R A1-9 update R, table, including name of pathway R Al-10 revised Ritable R A1-12 revised R, table R A1-13 revised Rtable R A1-14 revised Ri table R Al-15 revised R, table R A1-17 revised Ri table R A1-19 revised Ritable R Page # changes due to Memorandum to file dated February 20, 2009 Reason 5-15 changed distance for TLDs #2,#3,#4,#19 R 5-15 deleted TLD #17, #18 D 5-15 change title of TLD #6 R 5-16 changed distance for TLDs #33,#35,#36,#38,#46 R 5-17 deleted TLD #60 D ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION Page # changes due to Memorandum to file dated February 20, 2009 Reason 5-17 deleted Transit Control A, Transit Control B, Fader D 5-17 change distance for TLDs #49,#53,#62,#68,#77 R 5-17 changed title of TLD #78 R 5-17 changed Direction of TLDs #55i#57, R 5-18 deleted air sampler #14 D 5-18 changed distance of soil sample #1 R 5-18 deleted soil sample #6 D 5-18 added soil sample #7 A 5-19 changed distance of drinking water R 5-19 deleted Local Crops sample #1 D 5-20 changed distance of ocean bottom sediments sample E R 5-21 changed distance of PIC sample S5 and adjusted meters for samples S1, S3-S9 R 5-23 updated table 5-1, radiological environmental monitoring sample locations, 1 mile radius R 5-24 updated table 5-2, radiological environmental monitoring sample locations, 2 mile radius R 5-25 updated table 5-3, radiological environmental monitoring sample locations, 5 mile radius R 5-26 updated table 5-4, radiological environmental monitoring sample locations, Orange County R 5-27 updated table 5-5, radiological environmental monitoring sample locations, San Diego County R Bi updated table of contents for Appendix B R 13-1 thru included memorandum to file from E.S.Goldin, issued 9/10/97 as bases, to support changes to R B3-14 section 5 of the ODCM Page # changes due to editorial corrections Reason Aypendix A, corrected a format error F The Land Use Census (LUC) for 2008 did not identify a new location with a higher calculated or committed dose than those calculated for the locations evaluated in the previous revision to the ODCM.

Therefore, no new location(s) are reported per ODCM 5.2.1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS None.

SECTION K. MISCELLANEOUS Abnormal Releases None.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2009 - December 31, 2009 SONGS 2 Inoperability Monitor Period Inoperability Cause Explanation 2RT-7870 04/17/2000 - Inoperable process flow Design deficiency causes process flow instrument to be Condenser Air present measuring device inoperable while the vacuum pump is running, as high Ejector Process whenever vacuum flow values are not sensed. Flow monitor works Flow Monitor pump is running. properly during normal operations. The monitor is isokinetic during the vacuum pump operation due to the substitute flow value that is manually inserted whenever the vacuum pump is running. The issue was previously documented in ARs 000101252 and 000400960. It is currently being tracked in NN200001437.

2RT6753 & 12/26/2008 - Outage work, flow path The radiation monitors are declared inoperable by 2RT6759, 02/16/2009 not in use Operations when the monitor's alarm and automatic Steam Generator and functions are bypassed to support outage activities.

Blowdown Monitors 9/23/2009 - The radiation monitors did not malfunction, and were 03/31/2010 placed back in service when the pathway was put back to a normal operating alignment. This condition was tracked by 2LOCAR-2008-0052/2EDMR-2009-0265.

2RT-7870, 9/25/2009 - Outage work, flow path The monitor was removed from service for scheduled Condenser Air 03/31/2010 not in use maintenance on 9/25/09. Unit 2 entered the Cycle 16 Ejector Monitor outage on 9/27/2009 and remained shutdown until April 2010. The monitor's status was tracked by 2LOCAR-2009-0420 and 2EDMR-2009-0274.

2RT-7821, 11/3/2009 - Install Flush line, 2RT-7821 was declared inoperable 11/3/09 to install a Turbine Building 12/10/2009 Outage Work monitor sample flush line to improve the monitor's Sump Monitor reliability (Order 800293593). The flush line work was completed 11/17/09, however, instrument air was.not available to support the Channel Functional Test (CFT) due to other outage work. The Unit 2 Turbine Building Sump was cross-tied to Unit 3 on 11/7/09. 2RT-7821 was returned to service on 12/10/09 when the normal turbine building sump flow path was restored and the monitor CFT was completed. The monitor status was tracked by 2LOCAR-2009-0444.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS (Continued)

January 1, 2009 - December 31, 2009 SONGS 2 Inoperability Monitor Period Inoperability Cause Explanation 2RT-7828, 11/06/2009 - Flow Probe failure The Process Flow check failed on 11/6/2009 during the Containment Purge 01/05/2010 daily surveillance. On 12/10/09, the sample flow control Process Flow valve failed wide open and proper sample flow could Monitor not be established. The Kurz flow probe and processor were replaced. There was no Containment Purge from 12/10/09 to 1/5/10. This condition was tracked and documented by NN 200658775, NN200704975, and 2LOCAR-2009-0446.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER.THAN 30 DAYS (Continued)

January 1, 2009 - December 31, 2009 SONGS 3 Inoperabiiity Monitor Period Inoperability Cause Explanation 3RT-7870, 04/17/2000 - Inoperable process flow Design deficiency causes process flow instrument to be Condenser Air present measuring device inoperable while the vacuum pump is running, as high Ejector Process whenever vacuum flow values are not sensed. Flow monitor works Flow Monitor pump is running. properly during normal operations. The monitor is isokinetic during the vacuum pump operation due to the substitute flow value that is manually inserted whenever the vacuum pump is running. The issue was previously documented in ARs 000101252 and 000400960. It is currently tracked in NN 200001437.

3RT-7870, 01/08/2009 - Failed Heat Trace Heat trace 3TICJ407 failed high on 1/8/2009. Order Condenser Air 08/12/2009 800225987 was generated to troubleshoot and correct Ejector Particulate the problem. Due to work prioritization and backlog, and Iodine Sampler 3TICJ407 was not returned to service within 30 days.

NN 200835529 was written to address alignment of work prioritization with ODCM actions. This condition was tracked and documented by 3LOCAR-2009-0007 and NN 200271533.

3RT-7870, 03/21/2009 - Failed flow channel 3RT-7870 failed flow channel check on 3/28/09. The Condenser Air 05/20/2009 surveillance flow control valve was found failed open. The valve Ejector Process was reset and observed to operate satisfactory. The Flow monitor air ejector was operated intermittently, which affects the operability of the flow monitor. After restoring stable air ejector operation, the flow monitor was returned to service. This condition was tracked and documented in 3LOCAR-2009-0082 and NN 200371228.

3RT-7865, 9/2/2009 - CFT, sample pump After starting on 9/2/09, the CFT was impacted by other Plant Vent Stack / 10/6/2009 failure maintenance activities and delayed. Work was Containment Purge restarted 9/18/09 and completed SAT. Prior to the Monitor monitor being declared Operable, the monitor failed.

Required corrective maintenance included replacement of a sample probe and sample pump. The monitor was returned to service 10/6/2009. This condition was tracked and documented in 3LOCAR-2009-0372 and NN 200585721.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS (Continued)

January 1, 2009 - December 31, 2009 SONGS 3 Inoperability Monitor Period Inoperability Cause Explanation 3RT-7821, 03/27/2009 - Oily Waste Sump work, The monitor was declared inoperable because the CFT Turbine Building 05/08/2009 Flow path not in use could not be performed due to work on the Oily Waste Sump Monitor Sump inlet piping and level indication. The Unit 3 Turbine Building Sump was. cross-tied to Unit 2 from 3/29/09 to 5/7/09. When the normal lineup was restored, the CFT was completed and the monitor was returned to service 5/8/2009. This condition was tracked and documented in 3LOCAR-2009-0089 and NN 200379633.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS (Continued)

January 1, 2009 - December 31, 2009 SONGS 2/3 Inoperability Monitor Period Inoperability Cause Explanation 2/3RT2101 and 04/28/2009 - Low Sump Level, 2/3RT-2101 was removed from service on 4/28/2009 to 2/3FQ16095, 07/29/2009 Cabinet high perform repairs to the yard drains sump. 2/3FQ16095 NIA Yard Drains temperature was declared inoperable because the flow surveillance Sump Monitor and couldn't be performed due to the low level in the sump.

Process Flow A procedure revision was issued enabling successful surveillances during dry periods. On 7/19/09, high temperature in the cabinet caused repeated monitor failure alarms. The alarm was bypassed to prevent continued nuisance alarms in the control room. The high temperature issue was resolved on 7/29/09 by addition of a solar powered ventilation fan.

There were no releases from the NIA Yard Drain Sump from 6/2/2009 - 7/30/2009. This condition was tracked and documented by 2LOCAR-2009-214 and NN 200507163.

2/3FQ16095, 11/12/2009 - Electrical bus outage 2/3FQ16095 was declared inoperable on 11/12/09 NIA Yard Drains 12/24/2009 because the CFT could not be performed due to a Sump Process Flow electrical bus outage. 2/3FQ16095 did not lose power and was fully functional during the bus outage. Power was restored 12/5/09 and the Channel Functional Test completed 12/24/09. This condition was tracked and documented by 2LOCAR-2009-449 and NN 200704974.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION Onsite Groundwater Samples (Continued)

This section provides results of on-site samples of groundwater in accordance with the voluntary Industry Groundwater Protection Initiative. The sample locations and the frequency of sampling may change as Protection Initiative over time. For those few sample data that are not below the lower limit of detection, the levels are near the analytical sensitivity for the laboratory techniques.

January 1, 2009 - December 31, 2009 Sample Date Location 1Tritium Activity, pCi/ml Gamma Activity, pCi/mI 3/21/2009 GW-OCA-1 <LLD <LLD GW-OCA-2 <LLD <LLD 3/23/2009 GW-OCA-3 <LLD <LLD 3/26/2009 GW-PA-3 <LLD <LLD GW-PA-4 <LLD <LLD 3/27/2009 GW-PA-1 <LLD <LLD GW-PA-2 <LLD <LLD 6/5/2009 GW-OCA-2 <LLD <LLD 6/8/2009 GW-OCA-1 <LLD <LLD 6/10/2009 GW-NIA-1 1.06E-06 <LLD GW-NIA-2 7.77E-07 <LLD 6/11/2009 GW-OCA-3 <LLD <LLD 6/12/2009 GW-PA-1 <LLD <LLD GW-PA-2 <LLD <LLD GW-PA-3 <LLD <LLD GW-PA-4 <LLD <LLD 7/15/2009 GW-NIA-1 <LLD <LLD GW-NIA-2 5.29E-07 <LLD 7/31/2009 GW-NIA-1 <LLD <LLD GW-NIA-2 1.29E-06 <LLD 8/6/2009 GW-NIA-1 <LLD <LLD GW-NIA 2 9.50E-07 <LLD 8/14/2009 GW-NIA-1 <LLD <LLD GW-NIA-2 1.26E-06 <LLD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION Onsite Groundwater Samples (Continued)

January 1, 2009 - December 31, 2009 Sample Date Location Tritium Activity, Gamma Activity, pCi/ml pCi/ml 8/20/2009 GW-NIA-1 <LLD <LLD GW-NIA-2 1.17E-06 <LLD 8/27/2009 GW-NIA-1 <LLD <LLD GW-NIA-2 1.24E-06 <LLD 9/3/2009 GW-NIA-1 <LLD <LLD GW-NIA-2 1.21 E-06 <LLD 9/10/2009 GW-PA-1 <LLD <LLD GW-PA-2 <LLD <LLD GW-PA-3 <LLD <LLD GW-PA-4 <LLD <LLD 9/24/2009 GW-OCA-3 <LLD <LLD 9/25/2009 GW-OCA-1 <LLD <LLD GW-OCA-2 <LLD <LLD 12/3/2009 GW-NIA-1 <LLD <LLD GW-NIA-2 9.47E-07 <LLD 12/9/2009 GW-OCA-3 <LLD <LLD 12/10/2009 GW-OCA-1 <LLD <LLD GW-OCA-2 <LLD <LLD 12/14/2009 GW-PA-1 <LLD <LLD GW-PA-2 <LLD <LLD GW-PA-3 <LLD <LLD GW-PA-4 <LLD <LLD GW-PA = Wells installed in the Protected Area to implement the Groundwater Protection Initiative.

GW-OC = Wells installed in the Owner Controlled Area to implement the Groundwater Protection Initiative.

GW-NIA : Wells installed in the North Industrial Area to implement the Groundwater Protection Initiative.

a priori LLDs = H-3: 3.OE-6 pCi/ml, Cs-137: 1.8 E-8 pCi/mI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION 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 4.53E-1

b. Percent ODCM Specification Limit % 1.81 E+0

2. Limiting Organ

a. Organ Dose (GI-LLI) mrem 3.33E-2

b. Percent ODCM Specification Limit 1.33E-1

3. Thyroid

a. Thyroid Dose mrem 2.96E-2

b. Percent ODCM Specification Limit % 3.94E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 SAN ONOFRE NUCLEAR GENERATING STATION SECTION L. SONGS CONCLUSIONS Gaseous releases totaled 1.92E+2 curies of which noble gases were 1.06E+2 curies-,

iodines were 5.59E-4 curies, particulates were 6.25E-4 curies, and tritium was 8.56E+1 curies.

The radiation doses from gaseous releases were: (a) gamma air dose: 2.59E-2 mrad at the site boundary, (b) beta air dose: 6.14E-2 mrad at the site boundary, (c) organ dose:

2.78E-2 mrem at the nearest receptor.

Liquid releases totaled 1.06+3 curies of which particulates and iodines were 1.78E-2 curies, tritium was 1.06E+3 curies, and noble gases were 8.15E-1 curies.

The radiation doses from liquid releases were: (a) total body: 2.16E-3 mrem, (b) limiting organ: 5.48E-3 mrem.

Radioactive releases and resulting doses generated from SONGS were below the Applicable Limits for both gaseous and liquid effluents.

SONGS 1, 2 and 3 made 35 radwaste shipments to EnergySolutions, UT, PermaFix, FL, and Duratek/EnergySolutions, TN. The total volume of the 35 shipments was 7.10E+2 cubic meters containing 1.83E+1 curies of radioactivity.

Meteorological conditions during the year were typical for SONGS Meteorological dispersion was good 38% of the time, fair 35% of the time and poor 27% of the time.

There were no releases from groundwater or dewatering wells during 2009. Monitoring was performed in accordance with the voluntary Industry Groundwater Protection Initiative. The results of samples taken from these on-site wells are reported in Section K.

The net result from the analysis of these effluent releases indicates that the operation of has met all the requirements of the applicable regulations that ensure adequate protection of the health of members of the public.

METEOROLOGY METEOROLOGY The meteorology of the San Onofre Nuclear Generating Station for each of the four quarters, 2009 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, 2009. 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 - 2009 METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 09010100-09033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A FXTRF:MF:I Y UINSTARI F (fT4l -1 Qfl/n MF/1R5

_..._... . ... ..... .... C/1 00=M-WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.01 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS 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 1 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 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 0 1 5 0 0 0 0 0 6 S 1 0 0 0 1 3 6 24 1 0 0 0 0 35 SSW 0 0 1 2 5 11 14 1 0 0 0 0 34 SW 0 1 0 2 7 15 10 0 0 0 0 0 35 WSW 0 0 0 1 13 35 19 2 0 0 0 0 70 W 0 0 0 0 7 42 38 2 0 1 0 0 90 WNW 0 0 0 0 1 28 36 "4 5 0 0 0 74 NW 0 0 0 0 1 1 1 1 0 1 0 0 5 NNW 0 0 0 0 1 0 1 0 0 0 0 0 1 TOTALS 0 1 1 6 39 139 147 11 5 2 0 351 NUMBER OF VALID HOURS 351 ,NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 351 PASQUILL B MODERATELY UNSTABLE (-1.9< DT/DZ -1.7 C/100 METERS)

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 0 0 1 0 0 0 0 0 0 1 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 00 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 0 1 2 2 0 0 0 0 5 S 0 0 0 0 1 1 0 3 0 0 0 0 5 SSW 0 0 1 1 1 1 1 0 0 0 0 0_ 5 SW 0 0 0 0 1 1 0 0 0 0 0 0 2 WSW 0 0 0 2 1 0 2 0 0 0 0 0 5 W 0 0 0 0 2 4 0 0 1 1 0 0 8 WNW 0 0 0 0 0 1 2 0 0 0 0 0 3 NW 0 0 0 0 1 1 4 0 0 0 0 0 6 NNW 0 0 0 0 2 0 11 0 0 0 0 0 3 TOTALS 0 0 1 3 9 11 121 5 1 1 0 0 43 INUMUIM- Uf VALIU MUUKb 41 NUMUIb= U" (;ALMZ) L NUMBER OF INVALID HOURS I 0 TOTAL HOURS FOR THE PERIOD I 4, ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 09010100-09033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ -1.5 C/100 METERS WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS 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 2 0 0 0 0 2 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0, E 0 0 0 0 0 1 1 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 0 0 1 0 0 0 0 0 1 SSE 0 0 0 0 0 0 2 0 0 0 0 0 2 S 0 0 0 0 1 1 2 1 0 0 0 0 5 SSW 0 0 0 0 0 2 1 1 0_ 0 0 0 4 SW 0 0 0 1 0 2 0 0 0 0 0 0 3 WSW 0 0 0 0 1 3 1 2 0 0 0 0 7 W 0 0 0 1 3 4 0 0 0 0 00 0 8 WNW 0 0 0 0 1 2 2 ,0 1 0 0 0 6 NW 0 0 0 0 0 0 2 0 0 0 0 0 2 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 0 2 6 15 12 6 1 01 0 0 42 NUMBER OF VALID HOURS 42 NUMBER OF CALMS (0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 42 PASQUILL D NEUTRAL -1.5 < DT/DZ -0.5 C/100 METERS)

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 'TOTALS N 0 0 0 3 5 4 0 0 0 0 0 0 12 NNE 0 0 0 4 4 6 2 0 0 0 0 0 16 NE 0 0 1 1 2 3 1 0 2 0 0 0 10 ENE 1 0 0 0 1 2 0 0 0 0 0 0 0 3 E 0 0 0 1 3 1 1 1 0 0 0 0 7 ESE 0 0 0 2 2 8 5 0 1 0 0 0 18 SE 0 0 0 1 5 15 49 12 7 1 0 0 '90 SSE 0 0 0 0 2 9 19 12 4 3 0 0 49 S 0 0 1 4 3 6 7 16 2 1 1 0 41 SSW 0 0 0 2 6 5 10 5 6 0 0 0 34 SW 0 0 1 5 10 9 5 3 4 0 0 0 37 WSW 0 0 1 5 6 2 10 6 1 1 0 0 32 W 0 1 0 1 6 6 11 0 2 1 0 0 28 WNW 0 0 1 3 2 5 7 3 4 1 0 0 26 NW 0 0 0 3 5 9 7 5 1 1 0 0 31 NNW 0 0 0 1 6 5 4 0 0 0 0 0 16 TOTALS 0 1 5 37 69 93 138 63 34 9 1 0 450 NUMBER OF VALID HOURS 450 NUMBER OF CALMS C NUMBER OF INVALID HOURS 1 0 'TOTAL HOURS FOR THE PERIOD I 45C ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 09010100-09033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ 1.5 C/100 METERS)

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-30 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 4 6 8 0 0 0 0 0 0 18 NNE 0 0 1 6 9 16 5 1 0 0 0 0 38 NE 0 2 2 2 4 2 0 5 2 0 0 0 19 ENE 0 1 1 3 2 3 2 0 0 0 0 0 12 E 0 0 1 3 2 3 4 0 0 0 0 0 13 ESE 0 0 3 4 7 11 5 0 0 0 0 0 30 SE 0 0 0 3 3 9 16 0 0 0 0 0 31 SSE 0 0 0 1 5 3 4 0 0 0 0 0 13 S 0 0 0 3 2 3 0 1 0 0 0 0 9 SSW 0 0 1 1 4 0 0 0 01 0 0 0 6 SW 0 0 0 2 1 0 0 0 0 0 0 0 3 WSW 0 0 0 2 2 3 1 3 *1 0 0 0 12 W 0 0 0 2 8 3 3 1 0 0 0 0 17 WNW 0 0 0 3 7 8 7 0 0 0 0 0 25 NW 0 0 1 4 2 7 9 1 0 0 0 0 24 NNW 0 0 0 7 3 10 6 1 0 0 0 0 27 TOTALS 0 3 10 50 67 89 62 13 3 0 0 0 297 NUMBER OF VALID HOURS 1 297 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 1 97J PASQUILL F MODERATELY STABLE (1.5 < DT/DZ 4.0 C/1 00 METERS_

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 1 0 3 1 12 5 0 0 0 0 0 22 NNE 0 1 1 13 24 38 12 2 0 0 0 0 91 NE 0 0 0 15 12 4 3 0 1 0 0 0 35 ENE 0 0 3 12 8 9 2 0 0 0 0 0 34 E 0 0 1 5 2 4 0 0 0 0 0 0 12 ESE 0 0 0 2 2 1 1 0 0 0 0 0 6 SE 0 0 3 3 2 5 3 0 0 0 0 0 16 SSE 0 0 0 5 5 3 2 0 0 0 0 0 15 S 1 0 1 1 1 2 0 0 0 0 0 0 0 5 SSW 0 0 0 3 3 0 0 0 0 0 0 0 6 SW 0 0 0 o 41 0 0 0 _ 0 0 0 0 0 4 WSW 0 0 3 1 1 5 0 0 0 0 0 0 10 W 0 0 1 4 5 0 0 0 0 0 0 0 10 WNW 0 0 0 6 7 5 0 0 0 0 0 0 18 NW __0 1 1 3 5 5 5 0 0 0 0 0 20 NNW 0 0 1 3 3 41 3 0 0 0 0 0 14 TOTALS 1 0 4 15 83 82 95 36 2 1 0 0 0 318 NUMBER OF VALID HOURS 318 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS TOTAL HOURS FOR THE PERIOD 318 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 09010100-09033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE, DT/DZ > 4.0 C/100 METERS~

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 1 6 1 13 7 0 0 0 0 0 28 NNE 0 0 0 4 6 158 189 15 0 0 0 0 372 NE 0 0 2 13 19 30 14 2 0 0 0 0 80 ENE 0 0 1 9 3 9 3 0 0 0 0 0 25 E 0 0 2 3 2 7 1 0 0 0 0 0 15 ESE 0 0 1 9 2 6 1 0 0 0 0 0 19 SE 0 0 2 5 2 1 2 0 0 0 0 0 12 SSE 0 0 0 3 -2 2 2 0 0 0 0 0 9 S 0 0 1 5 2 2 3 0 0 0 0 0 13 SSW 0 1 0 3 1 1 0 0 0 0 0 0 6 SW 0 0 1 5 3 0 0 0 0 0 0 0 9 WSW 0 0 2 4 0 1 0 0 0 0 01 0 7 W 0 1 2 2 3 3 0 0 0 0 0 0 11 WNW 0 0 1 3 8 8 2 0 0 0 0 0 22 NW 0 0 1 3 6 4 31 0 0 0 0 0 17 NNW 0 0 0 5 2 3 4 0 0 0 0 0 14 TOTALS 0 2 17 82 62 248 231 17 0 0 0 0 659 NUMBER OF VALID HOURS 659 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 00 TOTAL HOURS FOR THE PERIOD 659 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED(MS) AT 10 METERLEVEL WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 1 1 16 13 38 12 0 0 0 0 0 81 NNE 0 1 2 27 43 218 208 18 0 0 0 0 517 NE 0 2 5 31 38 39 18 9 5 0 0 0 147 ENE 0 1 5 25 15 21 7 0 0 0 0 0 74 E 0 0 4 12 9 16 7 1 0 0 0 0 49 ESE 0 0 4 17 13 26 12 0 1 0 0 0 73 SE 0 0 5 12 12 30 71 12 7 1 0 0 150 SSE 0 0 0 9 14 19 36 14 4 3 0 0 99 S 0 1 3 14 14 19 36 22 2 1 1 0 113 SSW 0 1 3 12 20 20 26 7 6 0 0 0 95 SW 0 1 2 19 22 27 15 3 4 0 0 0 93 WSW 0 .0 6 15 24 49 33 13 2 1 0 0 143 W 0 2 3 10 34 62 52 3 3 3 0 0 172 WNW 0 0 2 15 26 57 56 7 10 1 0 0 174 NW 0 1 3 13 20 27 31 7 1 2 0 0 105 NNW 0 0 1 16 17 22 18 1 0 0 0 0 75 TOTALS 0 11 49 263 334 690 638 117 45 12 1 0 2160 NUMBER (OFVALID HOURS 2160 NUMBER (OFCALMS 0 NUMBER OF INVALID HOURS I 0 TOTAL HOURS FOR THE PERIOD 2160 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 09040100-09063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ7 -1 9 C/1 00 METERS~

WIND DIR .22-50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0110.1-13.0 13.1-18.01 >18 TOTALS N 0 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 01 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 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E 00 0 0 0 0 010 0 0_0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 __ 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 0 1 3 1 0 0 0 0 5 S 00 0 0 0 0 5 29 11 1 0 0 0 46 SSW 0 0 0 0 4 15 45 4 00 0 0 0 6 68 SW 0 '0 0 1 7 33 64 1 0 0 0 0 106 WSW 0 0 0 0 7 67 125 1 0 0 0 0 200 W 0 0 0 0 4 51 107 2 0 0 0 0 1064 WNW 0 0 0 1 0 34 72 9 7 0 0 0 123 NW O0 0 0 0 0 1 7 1 0 0 01 0 9 NNW 0 0 0 000 0 0 0 0 0 _0 0 0 TOTALS 0 0 0 2 22 207 452 30 8 0 0 0 721 NUMBER OF VALID HOURS 721 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS__ 0 TOTAL HOURS FOR THE PERIOD 721 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ -1.7 C/1 00 METERS)

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 -3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 01 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 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 0 1 1 0 1 0 0 0 3 S 0 0 0 0 3 5 3 1 1 0 0 0 13 SSW 0 0 0 0 1 5 5 1 _ 001 0 00 0 1 12 SW 0 0 0 0 1 6 2 0 0 0 0 0 9 WSW 0 0 0 1 5 6 1 0 0 0 0 0 13 W 0 0 0 1 2 5 2 0 0 0 0 0 10 WNW 0 0 0 0 1 5 1 0 0 0 0 0 7 NW 0 0 0 0 0 1 2 2 0 0 0 0 5 NNW 0 0 0 0 0 0 0 0 0 0 0 0 _ _ 0 TOTALS 0 0 0 2 13 34 17 4 2 0 0 0 72 NUMBER OF VALID HOURS 72 NUMBER OF CALMS C NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD I 72 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 09040100-09063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7< DT/DZ -1.5 C/100 ETERS)

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 0 0 _1 0 0 0 0 0 0 1 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 01 0 0 0 0 E 0 0 0 0 0 01 0 0 0_ 0 0 0 0 ESE 0 0 0 0 0 01 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 1 0 0 0 0 0 1 SSE 0 0 0 0 1 2 5 3 0 0 0 0 11 S 0. 0 0 0 2 4 5 3 0 0 0 0 14 SSW 0 0 0 0 1 4 4 0 0 0 0 0 9 SW 0 0 0 0 1 9 4 0 0 .0 0 0 14 WSW 0 0 0 3 1 3 1 0 0 0 0 0 8 W 00 0 0 0 3 2 1 0 0 "0 0 0 6 WNW 0 0 0 0 4 8 2 0 0 0 0 0 14 NW 0 0 0 0 0 2 6 1 0 0 0 0 9 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 0 3 13 35 29 7 0 0 0 0 87 NUMBER OF VALID HOURS 87 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 87 PASQUILL D NEUTRAL (-1.5 < DT/DZ -0.5 C/100 METERS WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 10 10 5 1 0 0 0 0 0 26 NNE 0 0 1 11 15 10 .2 0 0 0 0 0 39 NE 0 0 4 5 4 3 0 0 0 0 0 0 16 ENE 0 0 0 2 2 1 0 0 0 0 0 0 5 E 0 0 2 2 4 7 0 0 0 0 0, 0 15 ESE 0 0 0 5 4 15 13 0 0 0 0 0 37 SE 0 0 0 4 9 32 45 7 0 0 0 0 97 SSE 0 1 0 12 17 37 61 11 0 0 0 0 139 S 0 0 1 8 18 38 34 6 0 0 0 0 105 SSW 0 0 0 11 15 31 34 1 1 0 0 0 93 SW 0 0 1 11 15 20 8 2 0 .0 0 0 57 WSW 0 0 5 7 11 18 12 4 0 0 0 0 57 W 0 0 1 8 7 16 10 1 0 0 0 0 43 WNW 0 0 0 10 13 15 2 1 4 0 0 0 45 NW 0 1 4 13 10 19 23 1 0 0 0 0 71 NNW 1 0 0 2 19 6 12 3 0 0 0 0 0 42 TOTALS 0 2 21 1381 160 279 248 34 5 0 0 01887 NUMBER OF VALID HOURS 887 INUMBER OF CALMS I o NUMBER OF INVALID HOURS 1 0 ITOTAL HOURS FOR THE PERIOD I 887 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 09040100-09063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ 1.5 C/1 00 METERS)

WIND DIR .22-50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-1.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 3 2 8 4 0 0 0 0 0 0 17 NNE 0 0 2 12 11 12 1 0 0 0 0 0 38 NE 0 0 0 6 2 3 0 0 0 0 0 0 11 ENE 0 0 0 1 4 2 0 0 0 0 0 0 7 E 0 0 0 0 2 5 3 0 0 0 0 0 10 ESE 0 0 0 3 1 6 7 0 0 0 0 0 17 SE 0 0 0 0 2 3 10 1 0 0 0 0 16 SSE 0 0 0 0 0 1 3 2 0 0 0 0 6 S 0 0 0 2 1 0 0 0 0 0 0 0 3 SSW 0 0 0 0 1 1 0 0 0 0 0 0 2 SW 0 0 0 2 0' 0 0 0 0 0 0 01 2 WSW 0 0 0 0 1 .1 0 0 0 0 0 01 2 W 0 0 0 2 1 2 0 0 0 0 0 0 5 WNW 0 0 2 2 0 7 2 0 0 0 0 0 13 NW 0 0 0 3 1 0 6 0 0 0 0 0 10 NNW 0 0 0 3 4 1 2 0 0 0 0 0 10 TOTALS 0 0 7 38 39 48 34 3 0 0 0 0 169 NUMBER OF VALID HOURS 1 1691 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS I 0o TOTAL HOURS FOR THE PERIOD 169 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ 4.0 C/100 METERS)

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 1 1 2 4 0 0 0 0 0 0 8 NNE 0 0 1 6 26 22 3 0 0 0 0 0 58 NE 0 0 0 2 3 1 1 0 0 0 0 0 7 ENE 0 0 0 4 1 2 0 0 0 0 0 0 7 E 0 0 0 2 0 0 0 0 0 0 0 00 2 ESE 0 0 0 1 1 1 1 0 0 0 0 0 4 SE 0 0 0 0 0 3 1 0 0 0 0 0 4 SSE 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 O 0 SSW 0 0 .0 3 0 1 0 0 0 0 0 0 4 SW 0 0 0 2 1 1 0 0 0 0 0 0 4 WSW 0 0 0 2 1 0 0 0 0 0 0 0 3 W 0 0 0 2 0 2 0 0 0 0 0 0 4 WNW 0 0 0 0 0 1 0 0 0 0 0 0 1 NW 0 0 1 1 0 1 0 0 0 0 0 0 3 NNW 0 0 0 3 1 1 0 0 0 0 0 0 5 TOTALS 0 01. 3 29 36 40 6 01 0 0 0 114 NUMBER OF VALID HOURS 114 NUMBER OF CALMS 0 NUMBER OF INVALID HOURSw 0 TOTAL HOURS FOR THE PERIOD 1 114 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 09040100-09063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 C/1 00 METERS)

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 1 1 0 2 1 0 0 0 0 .0 5 NNE 0 0 0 2 10 47 19 3 0 0 .0 0 81 NE 0 0 1 2 2 5 2 0 0 0 0 0 12 ENE 0 1 1 1 2 1 0 0 0 0 0 0 6 E 0 0 0 0 0 2 .1 0 0 0 0 0 3 ESE 0 0 0 0 1 0 0 0 0 0 0 0 1 SE 0 0 0 1 0 0 0 0 0 0 0 0 1 SSE 0 0 0 1 0 0 0 0 0 0 0 0 1 S 0 0 1 0 1 0 0 0 0 0 0 0 2 SSW 0 0 0 0 2 0 0 0 0 0 0 0 2 SW 0 1 0 0 1 1 0 0 0 0 0 0 3 WSW 0 0 0 1 1 0 0 0 0 0 0 0 2 W 00 0 0 1 1 1 0 0 0 0 0 0 3 WNW 0 0 1 1 1 2 1 0 0 0 0 0 6 NW 0 0 0 1 0 3 0 0 0 0 0 0 4 NNW __0 0 0 1 0 1 0 0 0 0 0 0 2 TOTALS 0 2 5 13 22 65 24 3 0 0 0 0 134 NUMBER OF VALID HOURS 134 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 134 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (MS) AT 10 METERLEVEL WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 5 14 20 16 2 0 0 0 0 0 57 NNE 0 0 4 31 62 91 25 3 0 0 0 0 216 NE 0 0 5 15 11 12 3 0 0 0 0 0 46 ENE 0 11 1 8 9 6 0 0 0 0 0 0 25 E 0 0 2 4 6 14 4 0 0 0 0 0 30 ESE 0 0 0 9 7 22 21 0 0 0 0 0 59 SE 0 0 0 5 11 38 57 8 0 0 0 0 119 SSE-' 0 1 0 13 18 42 73 17 1 0 0 0 165 S 0 0 2 10 25 52 71 21 2 0 0 0 183 SSW 0 0 0 14 24 57 88 6 11 0 0 0 190 SW 0 1 1 16 26 70 78 3 0 0 0 0 195 WSW 0 0 5 14 27 95 139 5 0 0 0 0 285 W 0 0 1 14 18 79 120 3 0 0 0 0 235 WNW 0 0 3 14 19 72 80 10 11 0 0 0 209 NW 0 1 5 18 11 27 44 5 0 0 0 00 111 2 26 11 15 5 0 0 0 0 59 NNW 0 0 TOTALS 0 4 36 225 305 708 810 81 15 0 0 0 2184 NUIVItctK Ut- VALIU MUUIO Li d4 NUMbI:IK UI- LUALMb U NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2184 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 09070100-09093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNS -ABLE (DT/DZ -1.9 C/100 METERS)

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 1 0 0 0 0 0O 0 0 0 1 NNE 0 0 0 0 1 1 1 0 0 0 0 0 3 NE 0 0 0 2 1 0 0 0 0 0 0 0 3 ENE 0 0 0 1 0 0 0 0 0 0 0 0 1 E 1 0 0 0 0 0 1 0 0 0 0 0 0 1 ESE 0 0 0 0 1 0 0 0 0 0 0 0 1 SE 0 0 0 1 0 0 1 0 0 0 0 0 2 SSE 0 0 0 1 1 4 8 6 0 0 0 0 20 S 0 0 0 4 10 18 31 7 0 0 0 0 70 SSW 0 0 0 6 9 37 48 1 0 0 0 0 101 SW 0 0 0 5 22 47 43 1 0 0 0 0 118 WSW 0 0 0 7 22 80 59 0 0 0 0 0 168 W 0 0 0 6 17 100 107 0 0 0 0 0 230 WNW 0 0 0 7 10 49 118 3 0 0 0 0 187 NW 0 0 0 3 5 7 20 2 0 0 0 0 37 NNW 0 01 0 1 1 3 0 0 0 0 0 0 5 TOTALS 0 0 0 45 100 347 436 20 0 0 0 0 948 NUMBER OF VALID HOURS 948 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS__ 0 TOTAL HOURS FOR THE PERIOD 948 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ -1.7 C/100 METERS)

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 01 0 5 3 5 2 0 0 0 0 0 15 NNE 0 01 0 4 10 3 0 0 0 0 0 0 17 NE 0 01 0 2 1 2 0 0 0 0 0 0 5 ENE 0 0 0 0 1 0 0 0 0 0 0 0 1 E 1 0 0 0 0 0 0 1_ 0 0 0 0 0 1 ESE 0 0 0 0 0 11 0 0 0 0 0 0 1 SE 0 0 0 1 0 5 3 0 1 0 0 0 10 SSE 0 0 0 0 1 14 13 1 0 0 0 0 29 S 0 0 0 2 3 8 13 0 0 0 0 0 26 SSW 0 0 0 2 5 10 5 0 0 0 0 0 .22 SW 1 0 0 0 8 8 6 0 0 0 0 0 00 22 WSW 0 0 0 6 6 3 0 0 0 0 0 0 15 W 0 ,0 1 8 1 0 0 0 0 0 0 0 10 WNW 0 0 0 6 5 6 0 0 0 0 0 0 17 NW 0 0 0 9 7 3 3 0 0 0 0 0 22 NNW 0 0 0 2 5 1 1 0 0 0 0 0 9 TOTALS 0 0 1 55 56 67 41 1 1 0 0 0 222 NUMBER OF VALID HOURS 222 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 0 TOTAL HOURS FOR THE PERIOD r 222 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 09070100-09093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SIGI(HTL Y INSTARI F (-1 7 <zflT/f7 -1 5 (',/100* MFTFRS~

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 1 3 2 0 0 0 0 0 0 0 6 NNE 0 0 0 3 4 6 0 0 0 0 0 0 13 NE 0 0 0 0 3 0 0 0 0 0 0 0 3 ENE 0 0b 0 1 0 0 0 0 0 0 0 0 1 E 0 0 0 1 1 1 0 0 0 0 0 0 3 ESE 0 0 0 1 0 3 3 0 0 0 0 0 7 SE 0 0 0 4 2 10 7 0 0 0 0 0 23 SSE 0 0 1 1 6 15 12 3 0 0 0 0 38 S 0 0 0 0 7 7 1 0 0 0 0 0 15 SSW 0 0 0 5 4 5 0 0 0 0 0 0 14 SW 0 0 0 3 6 9 0 0 0 0 0 0 18 WSW 0 0 1 4 4 11 0 0 0 0 0 0 20 W 0 1 0 4 1 5 2 0 0 0 0 0 13 WNW 0 0 0 4 2 1 0 0 0 0 0 0 7 NW 0 1 1 4 4 1 2 020 0 0 0 0 13 NNW 0 0 1 3 4 1 01 0 0 0 0 0 9 TOTALS 0 2 5 41 50 75 27 3 01 0 0 203 NUMBER OF VALID HOURS 1 2031 INUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 203 PASQUILL D NEUTRAL (-1.5 < DT/DZ -0.5 C/1 00_METERS)

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0. 8 7 0 1 0 0 0 0 0 16 NNE 0 1 3 7 14 12 0 0 0 0 0 0 37 NE 0 2 2 2 1 3 0 0 0 0 0 0 10 ENE 1 1 0 3 2 0 0 0 0 0 0 0 7 E 0 0 1 3 1 1 1 '.0 0 0 0 7 ESE 0 1 0 6 4 9 7 0 0 0 0 0 27 SE 0 0 0 2 7 11 23 2 1 0 0 0 46 SSE 0 0 0 3 10 11 6 1 .0 0 0 0 31 S 0 0 1 3 5 5 10 0 0 0 0 0 24 SSW 0 0 1 5 4 2 1 0 0 0 0 0 13 SW 0 1 0 3 0 2 2 0 0 0 0 0 8 WSW 0 1 3 6 2 15 1 0 0 0 0 0 28 W 0 2 1 8 6 141 1 0 0 0 0 0 32 WNW 0 1 0 4 1 3 0 0 0 0 0 0 9 NW 0 0 1 7 9 6 1 1 0 0 0 0 25 NNW 0 1 3 10 8 8 1 0 0 0 0 0 31 TOTALS TlO r-rALI S- -

1 -1'4 11 -

16 80 81 102 55 4 1 -

0 0 0 351 INUIVID*I: UO V/-LIU riUUr¶O 1 3011 WUIVO-K UI" UALIM) U NUMBER OF INVALID HOURS 0o TOTAL HOURS FOR THE PERIOD 351 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 09070100-09093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTILY STABLF(-E, <fT/1 1 5 fl/1 00 MFTERS' WIND DIR .22-50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 1 2 10 10 4 0 0 0 0 0 0 27 NNE 0 0 1 15 22 22 6 0 0 0 0 0 66 NE 0 0 5 1 4 0 0 0 0 0 0 0 10 ENE 0 0 0 2 5 0 0 0 0 0 0 0 7 E 0 0 1 4 3 4 1 0 0 0 0 0 13 ESE 0 0 1 5 4 4 0 0 0 0 0 0 14 SE 0 0 0 5 4 1 0 0 1 0 0 0 11 SSE 0 0 1 3 6 7 0 0 1 0 0 0 18 S 0 0 1 1 0 0 0 0 0 0 0 0 2 SSW 0 0 2 1 0 1 _ 1 0 0 0 0 0 5 SW 1 0 0 4 1 1 0 0 0 0 0 0 7 WSW 0 0 1 3 6 0 0 0 0 0 0 0 10 W 0 0 0 4 1 3 0 0 00 0 0 0 8 WNW 0 0 1 3 2 3 1 0 0 0 0 0 10 NW 0 0 0 2 1 2 2 1 0 0 0 0 8 NNW 0 2 1 3 3 0 1 0 0 0 0 0 10 TOTALS 1 3 17 66 72 52 12 1 2 0 0 0 226 NUMBER OF VALID HOURS = NUMBER OF CALMS 0 NUMBER OF INVALID HOURS_ TOTAL HOURS FOR THE PERIOD 226 PASQUILL F MODERATELY STABLE 1.5 < DT/DZ 4.0 C/1 00 METERS)

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 -2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 7 6 4 0 0 0 0 0 0 17 NNE 0 0 2 9 29 30 3 0 0 .0 0 0 73 NE 0 0 0 5 6 .2 0 0 0 0 0 0 13 ENE 0 0 0 1 3 3 0 0 0 0 0 0 7 E 0 0 1 3 2 0 0 0 0 0 0 0 6 ESE 0 0 0 0 0 1 0 0 0 0 0 0 1 SE 0 0 0 0 2 3 2 0 0 0 0 0 7 SSE 0 0 0 .0 3 0 1 0 0 0 0 0 4 S 0 0 1 1 0 0 0 0 0 0 0 0 2 SSW 0 0 0 0 1 0 0 0 0 0 0 0 1 SW 0 0 0 3 1 0 0 .0 0 0 0 0 4 WSW 0 0 2 2 1 0 0 0 0 0 0 0 5 W 0 0 0 2 2 1 0 0 0 0 0 0 5 WNW 0 0 0 0 0 4 2 0 0 0 0 0 6 NW 0 0 0 0 0 1 3 0 0 0 0 0 4 NNW 0 0 0 0 1 1 0 0 0 0 0 0 2 TOTALS 0 0 6 33 57 50 11 0 0 0 0 0 157 NUMBER OF VALID HOURS 1 1571 INUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 ITOTAL HOURS FOR THE PERIOD 1 157 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 09070100-09093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DZ>4.0 C/1 00 METERS' WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 0 1 2 4 0 0 0 0 0 7 NNE 0 0 0 0 3 25 10.. 1 0 0 0 0 39 NE 0 0 0 1 1 4 0 0 0 0 0 0 6 ENE 0 0 0 2 2 1 3 1 0 . 0 0 00 9 E 0 0 0 1 2 _ 1 0 0 0. 0 _ 0 0 4 ESE 0 0 0 0 1 0 0 0 0 0 0 0 1 SE 0 0 0 1 2 2 0 0 0 0 0 0 .5 SSE 0 0 1 2 0 1 0. O 0 0 0 0 4 S 0 0 0 0 <1 0 0 0 0 0 0 0 1 SSW 0 0 0 1 0 0 1 0 0 0 0 0 2 SW 0 0 0 0 0 0 0 .0 0 0 0 0 0 WSW 0 0 0 1 0 0 1 0 0 0 0 .0 2 W 0 0 0 1 1 1 0 0 0 0 0 0 3 WNW 0 0 0 0 01 1 3 0 0 0 0 0 0 4 NW 0 0 1 0 0 "_1 3 0 0 0 0 0 5 NNW 0 0 1 2 0 .3 3 0 0 0 0 0 9 TOTALS .0 0 3 12 15 44 25 2 0 0 0 0 101 NUMBER OF VALID HOURS 101 NUMBER OF CALMS _

NUMBER OF INVALID HOURS0 TOTAL HOURS FOR THE PERIOD 101 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (MS) AT 10 METER LEVEL WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 1 3 34 29 15 7 0 0 0 0 0 89 NNE 0 1 6 38 83 99 20 1 0 0 0 0 248 NE 0 2 7 13 17 11* 0 0 0 0 0 0 50 ENE 1 1 0 10 13 4 3 1 0 0 0 0 33 E 0 01 3 12 .9 8 3 0 0 0 0 0 35 ESE 0 1 1 12 10 18 10 0 0 0 0 0 52 SE 0 0 0 14 17 32 36 2 3 0 0 0 104 SSE 0 0 3 10 27 52 40 11 1 0 0 0 144 S 0 0 3 11 26 38 55 7 0 0 0 0 140 SSW 0 0 3 20 23 55 56 1 0. 0 0 0 158 SW 1 1 . 0 26 38 65 45 .1 0 0 0 0 .177 WSW 0 1 7 29 41 109 61 '.0 0 0 0 0 248 W 0 3 2 33 29 124 110 0 0 0 0. 0 301 WNW 0 1 1 24 21 69 121 3 0 0 0 0 240 NW 0 1 3 25 26 21 34 4 0 0 0 0 114 NNW 0 3 6 21 22 17 6 0 0 0 0 0 75 TOTALS 2 16 48 332 431 737 607 31 4 0 0 0 2208 INUiViDEr- Vr VMLIjL nvUl'O I 4UOI I1%UIVlDCr-r% Ur U../'LIVIO I U NUMBER OF INVALID HOURS 0) TOTAL HOURS FOR THE PERIOD I 2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 09100100-09123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ -1.9 C/100 METERS)

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS 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 0 2 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 1 1 0 0 0 0 \0 3 SSE 0 0 0 0 1 3 8 5 0 0 0 .0 17 5 0 0 0 0 6 19 31 5 0 0 0 0 61 SSW 0 0 0 5 6 15 15 2 1 0 0 0 44 SW 0 0 0 3 10 18 29 0 2 0 0 0 62 WSW 0 0 0 4 21 32 29 0 0 0 0 0 86 W 0 0 0 2 11 71 57 5 1 0 0 0 147 WNW 0 0 0 0 5 44 46 3 4 0 0 0 102 NW 0 0 0 0 1 1 2 0 0 0 0 0 4 NNW 0 0 0_ 0 0 0 1 0 0 1 0 0 0 2 TOTALS 0 0 0 16 63 205 218 20 9 0 0 0 531 NUMBER OF VALID HOURS 531 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS0TOTAL HOURS FOR THE PERIOD 531 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ -1.7 C/1 00 METERS)

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 2 0 0 0 0 0 0 0 2 NE 0 0 0 0 0 0 00 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 0 0 0 0 0 0 0 0 SE 0 0 0 -0 1 0 2 2 0 0 0 0 5 SSE 0 0 0 0 0 2 7 1 0 0 0 00 1 0 S 0 0 0 2 1 2 2 3 0 1 0 0 11 SSW 0 0 0 0 1 1 2 1 0 0 0 0 0 5 SW 0 0 0 3 0 0 3 1 0. 0 0 0 7 WSW 0 0 0 2. 2 1 0 0 0 0 00 5 W 0 0 0 1 2 4 0 0 0 0 00 7 WNW 0 0 0 1 0 1 1 0 0 0 0 0 0 3 NW 0 0 0 3 1 1. 2 0 1 0 0 0 0 8 NNW 0 0 0 0 0 1 0 0 0 0 0 0 1 TOTALS 0 0 0 12 10 13 19 8 1 1 0 64 NUMBER OF VALID HOURS I 641 NUMBER OF CALMS C NUMBER OF INVALID HOURS I TOTAL HOURS FOR THE PERIOD 64 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 09100100-09123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C

.Il Ilr-WTI V I IMqTAPI 9: .1- 7 < flT/n7 -1 r .ll *)f PIT:TIP WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 1 0 0 0. 0 0 0 0 0 1 NNE 0 0 0 0 1 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 1 0 0 0 0 0 0 0 1 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 1 0 2 6 1 0 0 0 0 10 SSE 0 0 0 0 0 2 2 4 0 0 0 0 8 S 0 0 0 1 1 3 1 0 1 0 0 0 7 SSW 0 0 0 0 1 1 5 2 1 0 0 0 10 SW 0 0 0 0 2 2 0 2 0 1 0 0 7 WSW 0 0 0 3 0 1 1 1 0 0 0 0 6 W 0 .0 1 2 0 2 2 1 0 0 0 0 8 WNW 0 0 0 0 2 5 5 1 1 0 0 0 14 NW 0 0 0 1 0 5 2 0 1 0 0 0 9 NNW 0 0 0 1 0 1 0 0 0 0 0 0 2 TOTALS 0 0 1 11 8 25 24 12 4 1 0 0 86 NUMBER OF VALID HOURS 1 861 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS0 TOTAL HOURS FOR THE PERIOD 86 PASQUILL D NEUTRAL (.5 < DT/DZ -0.5 C/100 METERS)

WIND DIR. .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-20 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 1 6 3 1 1 1 0 0 0 0 13 NNE 0 1 0 0 5 3 4 0 0 0 0 0 13 NE 0 0 1 0 0 2 0 0 0 0 0 0 3 ENE 0 0 0 3 1 0 0 0 0 0 0 0 4 E 0 0 1 0 2 4 2 0 0 0 0 0 9 ESE 0 0 0 2 0 5 10 0 0 0 0 0 17 SE 0 0 0 2 3 16 39 19 3 0 0 0 82 SSE 0 0 0 3 6 11 16 4 3 0 0 0 43 S 0 0 0 3 3 5 10 3 6 1 0 0 31 SSW 0 0 1 3 3 6 3 6 1 0 0 0 23 SW 0 0 1 2 1 4 3 2 1 0 0 0 14 WSW 0 0 1 4 0 2 13 5 2 0 0 0 27 W 0 1 2 1 8 9 4 4 2 2 0 0 33 WNW 0 1 0 3 6 11 0 2 2 6 0 0 31 NW 0 0 2 2 2 9 1 0 1 0 0 0 17 NNW 0 0 1 6 4 9 3 1 0 0 0 0 24 TOTALS 0 3 11 40 47 97 109 471 21 9 0 0 384 NUMBER OF VALID HOURS I 3841 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 3841 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 09100100-09123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5< DT/DZ 1.5 C/100 METERS)

WIND DIR .22-50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 1 1 7 8 6 5 1 0 0 0 0 29 NNE 0 0 1 6 17 23 8 0 0 0 0 0 55 NE 0 1 2 7 2 2 0 0 0 0 0 0 14 ENE 0 0 1 5 3 3 1 0 0 0 0 0 13 E 0 1 1 4 9 .4 0 1 0l 0 0 0 20 ESE 0 0 2 3 8 4 1 0 0 0 0 0 18 SE 0 0 0 1 3 5 1 0 0 0 0 0 10 SSE 0 0 0 1 3 2 2 1 0 0 0 0 9 S 0 0 2 3 0 1 1 0 0 0 0 0 7 SSW 0 0 0 3 1 1 0 0 0 0 0 0 5 SW 0 0 0 0 1 1 1 0 0 0 0 0 3 WSW 0 0 0 5 4 0 2 1 0 0 0 0 12 W 0 0 0 3 5 2 0 0 0 0 0 0 10 WNW 0 1 1 2 5 9 2 0 0 0 0 0 20 NW 0 0 1 4 3 8 1 1 0 .0 0 0 18 NNW 0 0 2 3 5 7 6 0 0 0 0 0 23 TOTALS 0 4 14 57 77 78 31 5 0 0 0 0 266 NUMBER OF VALID HOURS 266 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2661 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ 4.0 C/I 00 METERS)

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 1 2 8 10 6 0 0 0 0 0 27 NNE 0 0 1 11 36 50 14 0 0 0 0 0 112 NE 0 2 2 17 2 6 2 0 0 0 0 0 31 ENE 1 0 3 7 8 1 1 0 0 0 0 0 21 E 0 0 3 4 2 3 0 0 0 0 0 0 12 ESE 0 1 0 2 1 0 0 0 0 0 0 0 4 SE 0 0 0 0 0 3 1 0 0 0 0 0 4 SSE 0 0 3 1 0 0 1 0 0 0 0 0 5 S 0 0 1 4 2 1 1 0 0 0 0 0 9 SSW 0 0 1 0 2 0 0 0 0 0 0 01 3 SW 0 0 1 2 1 0 0 0 0 0 0 0 4 WSW 0 0 0 0 0 0 0 0 0 0 0 0 0 W 0 0 0 2 3 2 2 0 0 0 0 0 9 WNW 0 0 1 6 1 4 0 0 0 0 0 0 12 NW 0 0 0 2 2 0 0 0 0 0_ 0 b0 4 NNW 0 1 1 3 0 2 -3 0 0 0 01 0 0 10 TOTALS-IIAD 1 4 18I 63 27l I 68 82 31 0 I-r--

0 0 -A7 0 .

0 267A IlUIVlDCr- ,.r Vur' LJ FlUn n I "glII PIUIVIDEr Ur %'",MLIVIO V*

INUMBER OF INVALID HOURS 01 TOTAL HOURS FOR THE PERIOD 267 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2009 METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 09100100-09123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G

_X__I EM:LY51AB:LE I > 4.0 0/100 MEI t_ _ _

WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 1 1 4 11 11 0 0 0 0 0 28 NNE 0 0 0 4 37 220 198 5 0 0 0 0 464 NE 0 0 1 2 18 19 6 0 0 0 0 0 46 ENE 0 0 1 2 0 6 5 0 01 0 0 0 14 E 0 0 1 1 2 2 0 0 0 0 0 0 6 ESE 0 0 0 2 2 3 0 1 0 0 0 0 8 SE 0 0 1 1 0 3 2 0 0 0 0 0 7 SSE 0 0 0 0 2 1 1 0 0 0 0 0 4 S 0 0 0 4 1 0 1 0 0 0 0 0 6 SSW 0 0 0 0 0 0 0 0 0 0 0 0 0 SW 0 0 0 0 0 2 3 0 0 0 0 0 5 WSW 0 0 0 2 0 2 1 0 0 0 0 0 5 W 0 0 0 1 2 1 0 0 0 0 0 0 4 WNW 0 0 1 0 0 1 0 0 0 0 0 0 2 NW 0 0 1 0 2 2 1 0 0 0 0 0 6 NNW 0 0 1 0 2 1 1 0 0 0 0 0 5 TOTALS 0 0 8 20 72 274 230 6 0 0 0 0 610 NUMBER OF VALID HOURS 610i NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 01 TOTAL HOURS FQR THE PERIOD 610 ALL STABILITY CLASSES; ALL DT/DZ WIND SPEED (MS) AT 10 METER LEVEL WIND DIR .22-50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 1 4 17 23 28 23 2 0 0 0 0 98 NNE 0 1 2 21 99 296 224 5 0 0 0 0 648 NE 0 3 6 27 22 29 8 0 0 0 0 0 95 ENE 1 0 5 17 13 10 7 0 0 0 0 0 53 E 0 1 6 11 15 14 2 1 0 0 0 0 50 ESE 0 1 2 9 11 12 11 1 0 0 0 0 47 SE 0 0 1 5 8 30 52 22 3 0 0 0 121 SSE 0 0 3 5 12 21 37 15 3 0 0 0 96 S 0 0 3 17 14 31 47 11 7 2 0 0 132 SSW 0 0 2 11 14 24 25 11 3 0 0 0 90 SW 0 0 2 10 15 27 39 5 3 1 0 0 102 WSW 0 0 1 20 27 38 46 7 2 0 0 0 141 W 0 1 3 12 31 91 65 10 .3 2 0 0 218 WNW 0 .2 3 12 19 75 54 6 7 6 0 0 184 NW 0 0 4 12 11 26 9 1 3 0 0 0 66 NNW 0 1 5 13 11 22 13 11 1 0 0 0 67 TOTALS 11 11 52 219 345 774 662 98 35 11 0 0 2208 ll 15ADED ('br \IAI Irl UCTI I I 'trO I Nll 15ADED t* rAAl RAC I'UIVIIUr-I JF VPLILJ rHurf I £UOI IdlUIVIlIr-r k.JI *J/tLIVIQ IJ NUMBER OF INVALID HOURS ol TOTAL HOURS FOR THE PERIOD I 220E Enclosure 2:

S0123-ODCM, Revision 2

February 27, 2009 Mr. R. T. Ridenoure

SUBJECT:

Revision 2 of the San Onofre Nuclear Generating Station (SONGS)

Offsite Dose Calculation Manual (ODCM), S0123-ODCM.

In accordance with Technical Specification 5.5.2.1, Revision 2 to the SONGS Dose Calculation Manual has been prepared and reviewed for your approval.

This revision incorporates the current changes to the Land Use Census, as well as changes to Section 5 of the Radioactive Environmental Monitoring Program (REMP).

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 revisio.n is requested.

Copies of this letter are being forwarded to the Nuclear Safety Group as required by Technical Specification 5.5.2.1.

Please contact me if there are any questions.

O.F.. Flores Manager, Chemistry Approved by:,

Site Manager Attachment cc: Sul

2/27/2009

SUBJECT:

SONGS OFFSITE DOSE CALCULATION MANUAL Revision 2 Enclosed is Revision 2 to the SONGS Offsite Dose Calculation Manual (ODCM). This revision accomplishes two objectives: 1)Incorporates the latest updates related to the 2008 Land Use Census (LUC) from the J.W. Scott to D. Dick Memorandum for File, "2009 Dose Parameters for SONGS," dated January, 29 2009 and 2) Revises/Deletes/Adds "type of samples and sampling location" in table 5-4 and Table 5-5, per the Memorandum for File, "SO123 Offsite Dose Calculation Manual (SO123-ODCM) Revision 2, Table5-4 and Table 5-5 recommended changes", dated February 20, 2009. The Memo to File will be included in Appendix B as the bases-for these changes.

Editorial corrections were made to Appendix A,Table 1-3 (pg. A1-8) to correct a formatting mistake and Appendix A,Table 1-6 (pg. Al-15), to correct the table header changed in a prior revision.

No 50.59 or EOE reviews were required or performed for the editorial changes.

None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations.

The level of radioactive effluent control required by I0CFR20, 40CFRI90, 10CFR50:35a and Appendix Ito 10CFR50 will be maintained.

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

A Addition D Deletion F Editorial/Format change R Revision Page # changes due to LUC Reason 2-29 revised Units.2&3 CLF R Ai Updated LUC references R A1-5 update Rjtable R A1-8 update R, table R A1-9 update Rjtable, including name of pathway R Al-10 revised Rjtable R Al-12 revised Rtable R AI-13 revised R~table R A1-14 revised Rjtable R Al-15 revised R,.table R Al-17 revised R~table R Al-19 revised R,table R

2/27/2009

SUBJECT:

SONGS OFFSITE DOSE CALCULATION MANUAL Revision 2 Enclosed is Revision 2 to the SONGS Offsite Dose Calculation Manual (ODCM). This revision accomplishes two objectives: 1) Incorporates the latest updates related to the 2008 Land Use Census (LUC) from the J.W.-Scott to D. Dick Memorandum for File, "2009 Dose Parameters for SONGS," dated January, 29 2009 and 2) Revises/Deletes/Adds "type of samples and sampling location" in table 5-4 and Table 5-5, per the Memorandum for File, "SO123 Offsite Dose Calculation Manual (SO123-ODCM) Revision 2, Table5-4 and Table 5-5 recommended changes", dated February 20, 2009. The Memo to File will be included in Appendix B as the bases-for these changes.

Editorial corrections were made to Appendix A, Table 1-3 (pg. A1-8) to correct a formatting mistake and Appendix A,Table 1-6 (pg. Al-15), to correct the table header changed in a prior revision.

No 50.59 or EOE reviews were required or performed for the editorial changes.

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, IOCFR50.35a and Appendix I to 10CFR50 will be maintained.

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

A Addition D Deletion F Editorial/Format change R Revision Page # changes due to LUC Reason 2-29 revised Units 2&3 CLFR A! Updated LUC references R A1-5 update Ritable R A1-8 update Rftable R A1-9 update R~table, including name of pathway R Al-10 revised Rtable R A1-12 revised Rtable R A1-13 revised Rtable R A1-14 revised R,table R A1-15 revised Rtable R A1-17 revised R~table R Al-19 revised R,table R

Page # changes due to Memorandum to file dated February 20, 2009 5-15 changed distance for TLDs #2,#3,#4,#19 5-15 deleted TLD #17, #18 i

5-15 change title of TLD #6 5-16 changed distance for TLDs #33,#35,#36,#38,#46 5-17 deleted TLD #60 5-17 deleted Transit Control A, Transit Control B, Fader 5-17 change distance for TLDs #49,#53,#62,#68,#77 5-17 changed title of TLD #78 5-17 changed Direction of TLDs #55,#57, 5-18 deleted air sampler #14 5-18 changed distance of soil sample #1 5-18 deleted soil sample #6 5-18 added soil sample #7 5-19 changed distance of drinking water 5-19 deleted Local Crops sample #1 5-20 changed distance of ocean bottom sediments sample E 5-21 changed distance of pressurized ion chamber sample S5 and adjusted meters for samples Si, S3-S9 5-23 updated table 5-1, radiological environmental monitoring sample locations, 1 mile radius 5-24 updated table 5-2, radiological environmental monitoring samiple locations, 2 mile radius 5-25 updated table 5-3, radiological environmental monitoring sample locations, 5 mile radius 5-26 updated table 5-4, radiological environmental monitoring sample locations,. Orange County 5-27 updated table 5-5, radiological environmental monitoring sample locations, San Diego County Bi updated table of contents for Appendix B B3-1 thru included memorandum to file from E.S.Goldin, Issued 9/10/97 as bases, to support 13-14 changes to section. f5 of the ODCM Page # changes due to editorial corrections Reason Appendix corrected a format error F A, A1-8 Appendix edited incorrect X/Q, DJQ and distance values from previous revision F A, Al-15 II _ I

OFFSrTE DOSE CALCULATION MANUAL NUCLEAR ORGANIZATION SAN ONOFRE NUCLEAR GENERATING STATION (SONGS)

SDI23-ODCM Revision 0 02-27-07

ODCM TABLE OF CONTENTS Page LIST OF FIGURES .......... . . . .. . . . . . . . . . . iv LIST OF TABLES. ..........

V INTRODUCTION . . .. ... . . . . .. vi 1.0 LIQUID EFFLUENTS ....... ..... 1-1 thru 1-27 1.1 Concentration ......... .....................

1-1 1.1.1 Specification ........................ 1-6 1.1:1.1,.1.1.1.2 Surveiliances .. .. .. .. ... .

1.2 Dose . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 1,2.1 Specification .................. 1 1-6 1.2.1.1 Surveillance . .. ... 1-6 1.3 Liquid Waste Treatment 1-7 1.3.1 Specification ................ ........

I-7' 1.3.1.1, 1.3.1.2, 1.3.1.3 Surveillances ............ 1-7 1.4 LiquidEffluent Monitor Methods of Setpoint Calculation 1-9 1.4.1 Batch Release Setpoint Determination ...... *1-11 1.4.2 Continuous Release Setpoint Determination . 1-15 1.5 Dose Calculations for Liquid Effluents 1-24 1.6 Representative Sampling ...... ................ 1-27 2.0 GASEOUS EFFLUENTS 2-1 thru 2-31 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 S0123-ODCM Revisi/on 0 i 02-27-07

ODCM TABLE OF CONTENTS (Continued)

Paqe 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 2.7 Gaseous Effluent Dose Rate ...... . 2-21 2.7.1 Noble Gases ........ ... 2-21 2.7.2 Radioiodines and Particuiates. 2-22 2.8 Gaseous Effluent Dose Calculation . .

2-23 2.8.1 Noble Gases....... . 2-23 2.8.1.1 Historical Meteoroiogy * . 2-23 2.8.1.2 Concurrent Meteorology

2-24 2.8.2 Radioiodines and Particulates 2-25 2.8.2.1 Historical Meteorology 2-25 2.8.2.2 Concurrent Meteorology . . 2-26 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 Do*se . . . . . . 3-5 S0123-ODCM Revision 0 ii 02-27-07

ODCM TABLE OF CONTENTS (Continued)

Paae 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 G 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-i 5.1.1 Specification . . . 5-1 5.1.1.1 Surveillance ..... ......... 5-2 5.2 Land Use Census .................... 5-1I' 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 Radio!logical Environmental Operating Report 5-13 5.5 Sample Locations ............. 5-14 6.0 ADMINISTRATIVE. . ................ 6-i 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 S0123-ODCM Revision 0 iii 02-27-07

ODCM LIST OF FIGURES Fioure Title Paae 1-2 Site Boundary for Liquid Effluents .... ..... ............. 1-8 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 I Mile Radius ....... ... ......... ........... ..... 5-23 5-2 Radiological Environmental Monitoring Sample Locations 2 Mile Radius ..... .......... ................ 5..24 5-3 Radiological Environmental Monitoring Sample Locations 10 Miles Radius ..... ...................... .. 5-25 5-4 Radiological Environmental Monitoring Sample Locations Orange County....... ... ... ... ... ... ... ... ....... 5-26 5-5 Radiological Environmental Monitoring Sample Locations San Diego County ........ ... ..... ... . . ... 5-27 S0123-ODCM iv Revision 0 02-27-07

DDCM LIST OF TABLES Table Title Pare 1-1 Radioactive Liquid Waste Sampling and Analysis Program . 1-2 1-3 Liquid Effluent Radiation Monitors Calibration Constants ....... ... ........... . 1-23 1-4 Dose Commitment Factors Ai, . . . .. . .. . . . . . . . . . . . . 1-25 2-1 Radioactive Gaseous Waste Sampling and Analysis Program . 2-2 2-3 Gaseous Effluent Radiation Monitor Calibration Constants ....... ................... 2-20 2-4 Dose Factors for Noble Gas and Daughters ........... .. 2-27 2-5 Dose Parameters Pik . .. . . . . .. .. . . . . . . . . . 2-28 2-6 Units 2 and 3 Controlling Location Factors ............ 2-29 2-7 SYF Controlling Location Factors ................. .. 2-30 2-8 NIA (Unit 1) Controlling Location Factor .... ......... 2-31 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 S0123-ODCM Revision 0 v 02-27-07

ODCM LIST OF APPENDICES T-itle ApDendix Ri TABLES . . ... .. ... ....... ..... ... ..... ..... S0123-ODCM-A Supplemental Information for the Effluent Controls Program .... S0123-ODCM-B S0123-ODCM Revision I vi 02-29-08

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL .(ODCM) is a supporting document of the RADIOLOGICA.L EFFLUENT TECHNICAL SPECIFICATIONS (NUREG 0472). The ODCM enumerates dose and concentration specifications, instrument requiremenýt, as wel Ias describes the methodology and parameters to be used in the calculation of offsite doses from radioactive liquid and airborne effluents consistent with RG 1.109 and NUREG 0133. In order to meet release limits, it additionally provides calculations for liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints. The environmental section contains the requirements 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 lwill be incorporated 'into the ODCM in order to assure that the ODCM represents current methodology.

SO123-ODCM Revision 0 vii 02-27-07

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

For dissolved or entrained noble gases, the concentration shall be limited to 2 x-10-4 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.

S0123-ODCM 1-1 Revision 0 02-27-07

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

Type Frequency. Frequency Analysis (iCi /ml)a A. Batch Waste P P Principal Gamma 5xi0"7 Released Each Batch Each Batch Emittersý 1-131 1xI"1O P M Dissolved and 1x10"5 One Batch/M Entrained Gases (Gamma emitters)

P M H-3 !x10-1 Each Batch Compositeb Gross Alpha 1xi07 P Q Sr-89, Sr-90, 5xi0O Each Batch Compositeb Fe-55 1xlO" NOTE BATCH RELEASE POINTS: Primary Pla nt Makeup Storage Tanks, Radwaste Primary Tanks, Radwaste Secondary Tanks, Miscellaneous Waste Condensate Monitor Tanks, Blowdown Processing System Neutral ization 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 Rel easese, Grab Sample Composite' Emi ttersf 5x 10-1 1-131 m M DissolVed and 1X10"5 Grab Sample Entrained Gases (Gamma emitters)

D M H-3 ix10-7 Grab Sample Compositec Gross Alpha 1ix1O07 D Q Sr-89, Sr-90 5X10 81 Grab Sample Composite' Fe-55 1X10-1 NOTE CONTINUOUS RELEASE POINTS: Turbine Plant Sump, Blowdown Processing System Neutralization Sump', S/G Blowdown Bypass Line', S/G Blowdown, Auxiliary Building Sump.*

S0123-ODCM 1-2 Revision 0 02-27-07

TABLE 1-1 RADIOACTIVE LIOIUID WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)

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

Type Frequency Frequency Analysis (pCi/ml)-

C. Continuous 3 xW W Principal Gamma 5x10 7 Releasee Grab Sample Compositeb'* Emittersý North 3 x W M- H-3 1xlO" Industrial Area Grab Sample Compositeb' Gross Alpha lx10" Yard Drain Sump GrossAlpha

-3 W w Q Sr-89, Sr-90 5xIO 8 Grab Sample Composite, Fe-55 ix10"6 S0123-ODCM 1-3 Revision 0 02-27-07

TABLE 1-i (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 50prdbabiiity of falsely concluding that a blank observation represents a "real" signal.

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

4.66 ýsb LLD E , V 2.22 x 10' Y exp (-2t) 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 101 is the number of transformations per minute per microcurie, Y is the fractional fadiochemical 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 pori (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).

SO123-ODCM 1-4 Revision 0 02-27-07

TABLE 1-1 (Continued)

TABLE NOTATION

b. A composite sample is one in which the quantity of liquid sampled is prop orti onal to the quant'ty of. liquidWaste 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 proportionto 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 ODCMD. to assure representative sampling.

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

f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, 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, and those isotopes listed in Reg. Guide 1.21, shall also be identified and reported.

g. 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.

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.

S* 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 2EO88, S21301MU618 for Steam Generator 2Eo89, S31301MU619 for Steam Generator 3EO88 and S31301MU618 for Steam Generator 3E089) is verified locked shut.

S0123-ODCM 1-5 Revision 0 02-27-07

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"'1O0 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 REOUIREMENTS

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

S0123-ODCM 1-6 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.3 LIQUID WASTE TREATMENT SRECIFICATION 1.3.1 The, liquid radwaste treatment system shall be OPERABLE. The appropriate p6rtions of the system shall be used t.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 l.)iqu'id waste -being discharged ,without treatment and in excess of the aboVelimits":iIn lieu ofany 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.i04.2, a Special Report which incltudes the following informatfon:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of the inope rable 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 REOUIREMENTS

.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 (ether, unit in Mode 4), thet 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 daysi

.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 S0123-ODCM 1-7 Revision 0 02-27-07

SITE BOUNDARY FOR LIQUID EFFLUENTS FIGURE 1-2 SAWC ON109RE KUJ..EAl SENERATJH; .STATMO NIAUNIT-2& UNIT 3 C) 0O LW" I afflAZ us?? t.

sta&ru Pz

/

S0123-ODCM 1-8 Revision 0 02-27-07

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 IOCFR20, 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:

(*) <MPCeff where:

C. = setpoint, representative of a radionuclide concentration for the radiation monitor measuring the radioactivity in the waste effluent line prior to dilution and subsequent release, yCi/ml R permissible waste effluent flow rate at the radfation 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 factorsL such as frictiohal losses, pump ineffici ncy, 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.

S0123-ODCM 1-9 Revision 0 02-27-07

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

MPCeff effecti ve effluent maximum concentration permissible limit

(#Ci/ml) at the-release point to the unrestricted area for the radionuclide mixture being released:

(1-2) wE where:

n number of radionuclides identified in sample analysis F1 fractional concentration of the ith radionuclide as obtained by sample analysis MPC1 = MPC of the ith radionuclide (IOCFR20, 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:

RW 7813 = Radwaste Effluent discharge SG88 _2 = Unit 2 Steam Generator E-088 SG8 9 - 2 = Unit 2 Steam Generator E-089 SGes_3 = Unit 3 Steam Generator E-098 SG89-. 3 = 'Unit 3 Steam Generator E-089 B2 Unit 2 Blowdown Processing System Neutralization Sump B3 = Unit 3 Blowdown Processing System Neutralizati'on, Smp .,*

T2 = Unit 2 Turbine Plant Sump.

= Unit 3 Turbine Plant Sump Y = NIA Yard Drain 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 IOCFR20, Appendix B, Table II,Column 2. The administrative values shall be assigned such that:

(RW7813 + SG8_ 2 + SG8.-2 + SG8B.3 + SGB.. 3 + B2 + B3 + T2 + T3 + Y) . 1.'0.

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

SO123-ODCM 1-10 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.1 BATCH RELEASE SETPOINT DETERMINATION The waste flo0w (R) and monitor-setpoint (Cj are set to meet the condition of equation (1-1) for the MPCeff limit. The method by which this is'accomplished is as follows:

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

(1-3)

C i C'yi) + ( (Cs) + (Ct) + (CF.) + (CX C.) 8) where:

C *total concentration in each batch. tank, PCi/ml.

jC', = sum of the measured concentrations for each radionuclide, i, in the gamma spectrum, excluding Xe-133, #Ci/ml CO : gross alpha concentration determined in the previous monthly composite sample, uCi/ml C5 = Sr-89 and Sr-90 concentrations as determined in the previous quarterly composite sample, pCi/ml Ct = H-3 concentration as determined in the previous monthly composite sample, or as measured in the sample taken prior to release, pCi/ml CFe Fe-55 concentration as determined in the previous quarterly composite sample,, pCi/ml isotopic analysis, yCi /ml S0123-ODCM Revision 0 02-27-07

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

STEP 2: The effective MPC (MPCCff) for each batch tank (or sump)

.s determined using:

. 1. (1-4)

Murueff =

( Cy/C' CC') (Cr C (C/C +~ CFe/C

+ k MPC) MPC 1 I\-'mm~I MPC) where:

MPCw, MPCS ) = the limiting concentrations of the appropriate MPC*,

MPCt, radionuclide from IOCFR20, Appendix B, Table II, MPCFeS Column 2 MPCU NOTE: For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-4 uCi/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, ZiC'Yi F, MPCjf, and R to provide compliance with the Iimits 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., #Ci/ml.

(1-5) 9 yCi/ml)

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

S0123-ODCM 1-12 Revision 0 02-27-07

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

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

(Rw78 3 (F) c)(1)

C 1

(R)(

Where:

RW7813 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 zfcly = total gamma isotopic concentration, excluding Xe-133, gCi/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)

MPC ff = from equation (1-4)

NOTE: If C,:S z1C'w 1 , then no release is possible, To increase C., increase the administrative value RW7,8 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 C. using the new RW7813, F, R as applicable and equation (1-6).

S0123-ODCM 1-13 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.1.2 BLOWDOWN PROCESSING SYSTEM NEUTRALIZATION SUMP/FULL FLOW CONDENSATE POLISHER DEMINERALIZER. IFFCPD) SUMP DISCHARGE LINE MONITOR (BATCH)

.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:

(1-7)

C2 (12) (F)(;C'Yj)

(R)(C/VPCff)

(R)(C/MPCe.ff) where:

C2 = instantaneous concentration at detector 2RT-7817 in uCi/cc C3 = instantaneous concentration at detector 3RT-7817 in yCi/cc B2 = Unit 2 BPS Neutralization Sump administrative value B3 = Unit 3 BPS Neutralization Sump admi'nistrative 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 gamma isotopic concentration,

i excluding Xe-133, MCi/ml, (STEP i)

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, yCi/ml MPCeff = value of MPCff from equation (1-4) for the sample analysis NOTE: If C2 or C3 : F1C'Y, then no release is possible. To increase C, 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).

S0123-ODCM 1-14 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2 CONTINUOUS RELEASE SETPOINT DETERMINATION The waste flow (R) an dmonitor tetpon.nt (C,,) are. set to meet the condition of equation (1-1) for the effective MPC (MPCefI) 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, turbine plant sump, and yard drain sump) from the sum of the respective measured concentrations as determined by analysis:

(+c + + )~+(ce) t+c-~( +(Cxe) (1-3) where:

C = total concentration (YCi/ml)

TIC', = total gamma activity associated with each radionuclide, i, in the weekly composite analysis for the release stream, excluding Xe-133, yCi/ml Ca = total measured gross alpha concentration determined from the previous- monthly composite analysis for the release stream, YCi/ml CS = total measured concentration of Sr-B9 and Sr-90 as determined from the previous quarterly composite analysis for the release ýstream, pCi/ml.

Ct = total measured H-3 concentration determined from the previous weekly or monthly composite analysis for the release stream, yCi/mJ CF, = total Fe-55 concentration as determined in the previous quarterly composite sample for the release stream, pCi/ml CXe = Xe-133 concentration as determined byisotopic analysis, YCi/ml S0123-ODCM 1-15 Revision 0 02-27-07

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

STEP2: The effective MPC (MPCef)i for each release stream (steam generator blowdown, blowdown processin.g system neutralization sump, -turbine plant sump, or NIA yard drain sump) is determined using:

MPCeff I . (1.-4) zi /( ÷ (~c'ý/ + CJ/C +j CF/1C SMPCj lt MPC)a MPCFe where:

MPC5 ,

MPC*. the limiting concentrations.:of the. appropriate MPCt, radionuclide from IOCFR20, Appendix B, Table II, MPCFe' Column 2 MPCa_

STEP 3: The setpoint, C, (pCi/ml) for each continuous release radioactivity monitor may now be specified based on the respective values of C, EiC'y 1 . F, MPCff, and R to provide compliance with the limits of 10CFR2O, 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 COIpCi/ml.

(C., UCi/ml) (1-5) x (Cal. Const., uCi/cc/cpm)

S0123-ODCM 1-16 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.1 BLOWDOWN.PROCESSING SYSTEM NEUTRALIZATION SUMP DISCHARGE LINE MONiTORS :ý(2RT-17817., 3RT-7817). .

The value for Cz (Unit 2) or C3 (Unit 3). the concentration Iimi't at the Unit 2 or Unit 3 detector, is determined by using; C (1B) (F)(z, C') (1-7) 2 (R)(/P"Ceff)

('3) (F)(Zi C1,).(-

C3 * ( (C/MPCeff) where:

C2 instantaneous concentration at detector 2RT-7817 in, pCi/cc C3 instantaneous concentration at detector 3RT-7817 in yCi/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)

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

Z.C'Y = total gamma isotopic concentration, excluding Xe-133, pCi/ml, (STEP I)

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

C total concentration, pCi/ml MPceff = value of MPCff from equation (1-4) for the sample analysis NOTE: If C2 or C3 < C', then no release is possible. To increase C2 or C3, increase the administrative value B, or B3 , and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate C, or C3 using the new B, or B3, F, R as applicable and equation (1-7) or (1-8).

S0123-ODCM 1-17 Revision 0 02-27-07

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

The value for C c,. 2, C59ý3 or C53.3, the concentration limit at the Unit 2 or Unit 3 detectors, is determined by using:

C(sG88_2 (F)¢.;c'Y) (1-9)

(R)(C/MPceff)

C53-2 (sG89-2) (F)(-ricIY) (110 (R)(C/MPCe-f)

C (sG*883) (F)(Ec'y) (1-11)

(R)(c/MPCeif)

C53-3 (sG89 3) (F).(FCY) Y (1-12)

(R)(C/MPCeff) where:

C59 .2 = instantaneous concentration at detector 2RT-6759 in pCi/ml C53 2 = instantaneous concentration at detector 2RT-6753 inpCi/ml C59-3 instantaneous concentration at detector 3RT-6759 in pCi/mI C 3-3 instantaneous concentration at detector 3RT-6753 in pCi/ml SG88.2 = Unit 2 E088 Steam Generator Blowdown administrative value SGB. 2 = Unit 2 E085 Steam Generator Blowdown administrative value SG 8 .- 3 = Unit 3 E088 Steam Generator Blowdown administrative value SG9-3 = 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)

S0123-ODCM 1-18 Revision 0 02-27 -07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT-,6753..< 2RT-6759i. 3RT-6753. 3RT-6759) (Continued).

z*C' ý= 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 MPCeff value of MPCeft from equation (1-4) for the sample analysis NOTE: If C59- 2, C53_ 20 C,9.3 , or C,.3 _<i*.C', (for the respective steam generator),

then no release is possible. To increase C 9 , C53-2 CC5 -, or C*_ 3, increase the administrative \alUe .SGB*,v sG6~, SGr*

88 rSG 3 , 'and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate R and recalculate C,9 2,, C53 2, CO-, or CS-3 using the new values of SGB.. 2, SG,.. 2, SG,8 . 3 or SG._ 3 , F, R as applicable and equation (1-9), (1-10), (1-11) or (1-12).

50123-ODCM 1-19 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.3 TURBINE PLANT SUMP MONITORS (2RT-7821, 3RT-782i)

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:

< t (F) ('(1-13)

(R)(C/MPC0 ff)

C<(T 3) N(F)( yc') (1-14)

(R)(C/MPCff) where:

C2 = instantaneous concentration at detector 2RT-7821 in jiCi/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)

C'= total gamma isotopic concentration, excluding Xe-133, gCi/ml, (STEP 1)

R effluent 'flow rateP gpm, (STEP 1), typically fIlow rate:

- 100 gpm (per pump)

C total concentration, yCi/ml MPCeff value of MPCeff from equation (1-4) for the sample analysis NOTE: If C2 or C3 _<F.1C'y, then no release is possible. To increase C2 or C3 1, increase the administrative value T, or T3 , and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate C, or C3 using the new T2 or T3 , F, R as applicable and equation (2-13) or (1-14).

S0123-ODCM 1-20 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.3 TURBINE PLANT SUMP MONITORS 12RT-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 J into account' the entire discharge flow through both the normal and temporary paths.

t. P-rocedures shall require the immediate--termination; of the-discharge via the temporary path if the monitor on -the normal path alarms.

S0123-ODCM 1-21 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.4 NIA YARD DRAIN SUMP MONITOR (RT-2101)

There is one Yard Drain Sump on site, located in the North,.

industrial Area. It can be,released through either the Unit .2 or Unit 3 outfall, The same radiation monitor is used for either outfall.

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

(Y)(F) 1 '~)(-15) (I (R)(c/MPCeff) where:

CyDs instantaneous concentration at detector RT-2101 in #Ci/ml Y = NIA Yard Drain 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)

.ICryi = total gamma isotopic concentration, /Ci/ml, (STEP 1)

R = effluent flow rate, gpm, typical flow rates:

= 2300 gpm or 4100 gpm C = total concentration, pCi/ml MPCefI = value of MPCeff from equation (1-4) for the saniple analysis NOTE: If CYas < ziC'0 then no release is possible. To increase, Cy~s, increase the administrative value Y, and/or increase dilution flow F.(by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate C,,, using the new Y, F, R as applicable and equation (1-15).

SO123 -ODCM 1-22 Revision 0 02-27-07

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.

S0123-ODCM 1-23 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.5 DOSE CALCULATION FOR LIOUID EFFLUENTS The liquid releases considered in the folIowing 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 = T'j[Aj, zjt C F~ (1216) where:

Aj, Site-related adult ingestion dose commitment factor to the total body or an organ,. -c, for each identified.principal gamma and beta emitter, i, from Table 1-4 in mrem/hr per yCi/ml.

C1j average concentration of radionuclide, i, in the undiluted liquid effluent during time period, At, in YCi/ml.

DT = dose commitment to the total body or an organ, T, from the liquid effluent for the time period, Atp, in mrem.

Snear field average dilution factor (actually mixing ratio) for C~j during the time period, &tj. This factor is the ratio of the maximum undiluted liquid waste flow during time period, Ltj, to the average flow from the site discharge structure to unrestricted receiving waters, (maximum liquid radioactive waste flow or: discharge structure exit flow) length of the jth time period over which Cij and Fj are averaged for all liquid releases, in hours.

S0123-ODCM 1-24 Revision 0' 02-27-07

TABLE 1-4 DOSE COMMITMENT FACTORS*, Ajir (mrer/hrt per-uCi/ml RadiO- Total.

nuclide Bone Liver Body". Thyroid lkidney. Lung " Gl-LLI H-3 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-I 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+0 1.23E+O 7.40E+O 1.40E+3 Mn-54 7.06E+3 1.35E+3 2.1OE+3 2.16E+4 Mn-56 ,1 .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. 190E+5 7.27E+4' . ,..____* 5,30E44 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 .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.O.E+2 Sr-90 1.23E+5 3.01E+4 3.55E+3 Sr-91 9.18E+1 . _ _ 3.71E+D 4.37E+2 Sr-92 3.48E+1 1..51E+0 6.90E+2 Y-90 6.06E+0 1.63E-1 6.42E+4 Y-91m 5.73E-2 2.22E-3 1.68E-1 Y-92 5.32E-1 . 1.56E-2 9.32E+3 Zr-95, 1.59E+I 5.11E+0 3.46E+0 8.02E+0 1.62E+4 Zr-97 8.81E-i 1.78E-1 8..13E"2 2.68E-1 5.51E+4 Nb-95 1i 8E0 1.03E+0 5.51E-1.i _.. _',' 1.0 EtO ......... 6.,22E,3 Nb-95m 1.84E+0 1.03E+0 5.51E-I 1,IE+O

'10 6.22E+3 Nb-97 1.55E-2 3.,91E-3 1.43E-3 4.56E-3 1.44E+i Mo-99 1.28E+2 2.43E+1 2.89E+2 2.96E+2 Tc-99m 1i.I30E-2 3.66E-2 4.66E-E-...... 5.56E-I 1.79E-2 2.17E+I NOTE: where no value is given, no data are available.

Source: Reg. Guide 1.109, Table E-11, Table A-i USNRC NUREG-0172, Table 4 ICRP-30, Part 3, Supplement A Methodology: USNRC NUREG-0133, Section 4.3.1 S0123-ODCM 1-25 Revision 0 02-27-07

TABLE 1-4 (Conti nued)

DOSE COMMITMENT FACTORS*, Ak.

(mrelm/hr per PCi'/Mi)

Radio-nuclide B Bone Liver Total Body Thyroid Kidney Lung GI-LLI Ru-103 11.07E+2 4.60E+1 4.07E+2 1.25E+4 Ru-106 1.59E+3 2.01E+2 3.06E+3 I..03E+5 L

Ag-110m 1.42E+3 1.32E+3 7.82E+2 2.59E+3 5.37E+5 Sn-.113 . 2.26E+5 Sn-117m_ 2.26E+5 Sb-124:' 2.76E+2 . 5.22E+-0 1.09E+2 6.70E.I ..- .2.15E+2 7.84E+3 Sb-.125 1.77E+2 1.97E+0 4..20E+ 1.,79E-1 1.36E+2 -. ,94E+3 Te-129m 9.31E+2 3.47E+2 1.47-E+2 3.20E+2 3.89E+3 .... 4.69.E+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 1.779E+2 L12E+5 ' 5.35E+2"' 8.23E+1 1-132 1.06E+1 2.85E+1 9.96E+0 . 9.96E+2 4.54E+1 5.35E+0 1-133 7.45E+l 1.30E+2 3.95E+1 1.90E+4 2.26E+2 1.16E+2 1-134 5.56E+0 1.51E+1 5.40E+O 2.62E+2 2.40E+1 1.t32E-2 1-135 2.32E+1 6.08E+1 2.24E+1 4.01E+3 9.75E+1 6.87E+1 Cs-134 6.84E+3 1.63E+4 1.33E+4 5.27E+3 1.75E+3 2.85E+2 Cs-136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21E+2 Cs-137 8.77E+3 1.20E+4 7.85E+3 4.07E+3 1.35E+3 2.32E+2 Cs-138 6.07E+0 1.20E+1 5.94E+0 8.81E+O 8.70E-1 "5.12E-5 Ba-139 7.85E+0 5.59E-3 2.30E-1 5.23E-3 3.17E-3 1.39E+1 Ba-140 1.64E+3 2.06E+O 1.08E+2 7.02E-1 1.18E+O 3.38E+3 La-140 1.57E+0 7.94E-1 2.1DE-1 5.83E+4 Ce-141 3.43E+0 2.32E+0 2.63E-1 "1.08E+0 8.86Et3

,Ce-143 6.04E,1 4.46E+2 4.94E-2 1.97E7-1 _:. 167E+4 Ce-144 1.79E+2 7.47E+1 9.59E+0 4.43E+1 6.04E+4 Nd-147 3.96E+0 4.'58E+O 2.74E-1 2,68E+0 ....... 2.20E+4 W-187 9.16E+0 7.66E+0 2.68E+0 2.51E+3 Np-239 3.53E-2 3.47E-3: .1.91E-3 ':_1. 08E-2 7.11E+2 NOTE: where no value is given, no data are available.

Source: Reg. Guide 1.109, Table E-11, Table A-I USNRC NUREG-0172, Table 4 ICRP-30, Part 3, Supplement A Methodology: USNRC NUREG-0133, Section 4.3.1 S0123-ODCM 1-26 Revision 0 02-27-07

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 t.h..

requirements of Regulatory Guide 1.21 and NUREG-0800, Section 11.5. The methodology for mixing and sampling is described in S0123-111-5.23, "Generating Effluent ReleasePermits Using The Vax Computer" and S0123-III-5.2.23, "Units 2/3 Liquid Effluents".

S0123-ODCM 1-27 Revision 0 02-27-07 '

2.0 GASEOUS EFFLUENTS 2.1 DOSE RATE SPECIFICATION 2.1.1 The dose rate inl 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 REQUIREMENTS

.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 bewithin 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.

S0123-ODCM 2-1 Revision 0 02-27-07

.TABLE 2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Minimum Type of Lower imit Release Sampling Analysis Activity of Demtection Type Frequency Frequency Analysis (pCi/ml)a Batch P P Principal Gamma Emitterso 1x10"4 Waste Gas Each Tank Each Tank Decay Tank Grab Sample Continuous Principal Gamma EmittersO ix10 4 Tritium 1x10"6 Wd 1-131 1x10' 2 Continuousf Charcoal Sampler Sample 1-133 1x101 Wd Continuousf Particulate Principal Gamma EmittersO. Ixi0-"

Sampler Sample (I1-131 and Others)

M Continuousf Composite Gross Alpha ix1O' 2 Sampler Particulate Sample Q

Continuousf Composite Sr-89 and Sr-90 1x"101' Sampler Particulate Sample Continuousf Noble Gas Noble Gases ix10"6 Monitor Monitor Gross Beta or Gamma

Sampling.frequencies for noble gases and tritium are:

CONTINUOUS PATHWAYS:. Containment Purge - 42" Each Purgeb,'

Containment Purge - 8" Monthly Grabb, Condenser Air Ejector Monthly Grabb Plant Vent Stack Weekly Grabb" South Yard Facility Particulate and Iodine sampling only' S0123-ODCM 2-2 Revision 0 02-27-07

TABLE 2-1 (Continued)

TABLE NOTATION

a. The LLD is. the smallest concentration of radioactive material in a sample that will be deitcted'ith 95% probabjlity With only 5% probabiIity of.

falsely conclud ing that a bl ank ýobervation represents' a real'! signai For a particular measurement system (which may include radiochemical separation):

LLD = 4.66 sb E ,V - 2.22 x 106 - Y ' ekp (-MLt) 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 voluume),

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 i-sthe elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

The value of s, used in the calculation of the LLD 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 oriori (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).

S0123-ODCM 2-3 Revision 0 02-27-07

TABLE 2-1 (Continued)

TABLE NOTATION b Analyses. shal I, also b6 performed .on: the affected unit and plhan,: vent :stack.

foll owi ng.'shutdown,Istartup, or a THERMAL POWER change" exceeding.15 ,.percent of the RATED THERMALPOWER within a 1-h eriod. This requi.emen_ does not apply ffi (1)analysis shows that the DOSE EQUIVALENT 1-131 concentr~ation 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 compieted within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months afterchanging (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- exceedjng: 15 percent. of RATED THERMAL POWER in I hour 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 emissi'ons and Mn-54, Fe;59, Co-58, Co-60O 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. Ot'her' 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.

S0123-ODCM 2-4 Revision 0 02-27-07

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 withiR 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.

S0123-ODCM 2-5 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.;3 DOSE. - RADIOIODINES. RADIOACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM,'

SPECIFICATION 2.3.1 The dose to an itndividual 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 followi.ng:

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 actiohs to be taken to assure that subsequent releases will be in compliance with Specification 2.3.1.

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.

S0123-ODCM 2-6 Revision 0 02-27-07

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 the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to thei rdischarge.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.

7hese doses are per reactor unit.

S0123-ODCM 2-7 Revision 0 02-27-07

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

SURVEILLANCE REOUIREMENTS (Contiinued) 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 shal .be demonstrated OPERABLE by operating the GASEOUS RADWASTE. TREATMENT SYSTEM equipment,'.and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15-minutesprior 'to processing gases unless the appropriate gaseous radwaste system has been utilized to process radioactive gaseous effluents during the previous 92 days.

S0123-ODCM 2-8 Revision 0 02-27-07

I.'At 22311 11111-1 JOSE H CA M

/I

/

ISK SAN: ONOFRE NUCLEAR GENERATING.STATION SITE BOUNDARY FOR GASEOUS.'- EFFLUENTS Figure 2-2 SOI23-ODCM 2-9 Re Vision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6. Methods of Calculation for Gaseous Effluent Monitor Setpoints

AdiinihistratJ veý vial ues .are used to reduce each setpoint to. .account-for

pbental th ctiityreleased-simult, edusly fo h olvrn re-least "points:

PVS = Plant Vent Stack' CAE = Condenser Air Ejector CP = Containment Purge SY = South Yard WG = Waste Gas 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 .arelease exceeding the limitsof Specification.2.1.1. -The. sum total of all these administrative values for ýthe site shall1 be lessý .'than':or- e~q'ual'. ýto 1.0-.

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

2:.6.1 PLANTNVENTý STACK -2/3RT-7808, 2RT-7865-1-,-3RT77865-1 For the purpose of implementation of Specification 21.1k, 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:

(PVS) (21.2 M/se (500 Mrem/yr)(1e)6MI/cc)

C (let rae=$ Cf sec/ [ mrem/yr) CIj.

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

(PV)2120 cfm (3000 nmrem/yr)(1V%-3/Cc) (2-2)

Cdet k m'/sec (flow rate, cfm)(X/Q, sec/m'j) . L.+ 1.1lmi mreni/yr~ .

yCi/rn 3 )Ctat~

S0123-ODCM 2-10 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.1 PLANT VENT STACK -. 2/3RT-TB8, 2RT-7865-I, 3RT-7865-1 (Continued) where:

Cdet the instantaneous concentration at the detector, yCi/cc PVS an-administrative value used to account for potential activity from other gaseous release pathways, typically 0.38.

Ki = total body dose conversion factor from Table 2-4 for the i t gamma emitting noble gas, mrem/yr per pCi/m 3 Li .=skin Dose Conversion Factor from-Table 2-4,for the ith noble gas, mrem/yr per pCi/mi MH air Dose Conversion.Factor from Table 2-4 for the ith noble gas,ý mrem/yr per pCi/mr -

1.1 = conversion factor to convert gamma air dose to skin dose C= concentration of the ith noble gas as determined by sample analysis, yCi/cc Ctot total concentration of noble gases as determined by sample analysis, pCi/cc = zCj flow rate = total plant vent stack flow rate, cfm,

= typically 164,000 cfm 2120 = conversion constant, cfm per m3/sec 500 mrem/yr = total 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 3dispersion factor for any landward sector, sec/mi

= 4.8E-6 sec/m3 S0123-ODCM 2-11 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.2.1 Maximum Permissible Alarm Setpoint for 2/3RT-7808, 2RT-7865-1 and 3RT-7865-1 The smaller of the values of Cdt from equatibns (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, Cdt (jiCi/cc) to an equiValent release rate in pCi/sec, as follows:

(Cet, uCi/cc) (flow rate, cfm) (28320) (2-3)

(s) (60) where:

kAX maximum permissible release rate, pCi/sec Cdet = smaller of the values of C,t 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 to compensate for the split flow between Unit 2 and Unit 3 Plant Vent Stacks, typically.2 for split stack monitoring and I 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.

SOI23-ODCM 2-12 Revision 0 02-27-07

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 E.ieciorMonitors For the purpose of implemeintation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the.

gaseous effluent flow rate and the meteorological dispersion factor.

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

Total Body (2-4)

(CAE) (0.5) 2120 m,/secl cf_ J (500 mrem/yr) (10-6 m3/cc)

Cdet (Flow rate; cfm) (X/Q, sec/me)

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

Skin where: (CAE) = an administrative value used to account *for potential activity fromother gaseous releate pathways, typically 0.1.

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 and/or 2.6.2.2.

(CAE) (0 .5s2120 --- r '( 3000 mrem/yr) (10- m'/cc)

Cdet (Flow rate, cf*m) (x/Q, sec/m3) [i (L, + I.lMi' mrem/yr S0123-ODCM 2-13 Revision 0 02 07

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

The sniallI of the val'ues .Cdt from equt i ons (2-4) or (?2-5),i s to be used in determi"ing themaximum pertmsible monitor alarm setpoi-nt (cpm), as follows:

The maximum permissible alarm setting (cpm) is determined by using the calibration constant for the corresponding Condenser Evacuation System Monitor given in Table 2-3. The maximum permissible alarm setpoint is the cpm Value corresponding to the concentration, Cdet, [smaller value from equation (2-4) or (2-5)].

The calibration constant used is based on Kr-85 or on Xe-133, whichever yields a lower.:detection efficiency (higher value in terms of uCi/cc/cpm).. The alarm" setpoint will not beset 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 detbctor, C,,t (yCi/cc), to an equivalent release rate in pCi/sec.

Amax (Cde.s uCi/cc) (flow rate, cc/sec) (2-6) where:

A.eX = maximum permissible release rate, pCi/sec caet smaller value of Cdet, as obtained from equations (2-4) and (2-5) flow rate = flow rate of the condenser air ejector, cc/sec 4.719E5 cc/sec (conservatively assumed as design ,flow rate)

S0123-ODCM 2-14 Revision 0 02-27-07

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 alarmn setpoint, Ievel fo-r noble gas monitors Jis based on the gaseous effluent flow rate and the meteorological' dispersio.n, factor.

NOTE: 2(3)RT-7865 is not designed to nmonitormain 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 (2-7)

(CP) (P2) 2120 (10-' ms/cc) m SeC) 500 rem/yr) n Cdet2 (2-8)

Cdet3 The concentration at the detector corresponding to a 3000 mrem/yr skin dose rate at the exclusion area boundary is determined by using: :

Skin (2-9)

(CP) (P2)(2120 m3 sec 3000 mreyr) (10-6 M3/CC)

Cdet2 (FNow rate, cfm) (X/Q, sec/m 3) z ~L + 1.1Jv1. mrem/yr J S0123-ODCM 2-15 Revision 0 02-27-07

2.0 GASEMUS EFFLUENTS (Continued) 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865-1, 3RT-7865-1 (Continued)

(CP)(P3){2120 Cf ( 3000 mrem/yr) (I0-6 m/cc)

J M3/sec________________

(L, IMj, mrem/yr C1 (Flow rate, cfm) (X/Q, sec/m3). +

pCi/M 3 ) o) where:

Cd~t = instantaneous concentration of the Unit 2 detector, pCi/cc. i Cdet3 = instantaneous concentration of the Unit 3 detector, pCi/cc.

CP administrative Value used to. account for potential activity from other gaseous release pathways, typically 0.38.

P, 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 Pz + 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 above. The smaller of the values of maximum permissible Cd,2. from equation (2-7) or (2-9) and Cdet 3 from equations (2-8) or (2-10) is to be used in determining the maximum permissible monitor alarm setpoints.

S0123-ODCM 2-16 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865-1, 3RT-7865-1 (Conti nued) 2.6.3.1 Maximum Permissible Alarm Setting 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.

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

= (Cdet, pCi/cc) (flow rate, cc/sec) (2-6) where:

AM = maximum permissible release rate, pCi/sec Cdet = smaller, value of Cqet, as. obtained from equation (2-4, 2-9) for Unit 2 or (2-8, 2-10) for Unit 3.

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

.2 Maximum Permissible Alarm SettinQ (RT-7628)

The maximum permissible alarm setting for RT-7828- is in uCi/cc and is. the smaller of *the values of Cdft (.UCi/cc) from equations (2-7) and (2-9) for Unit 2 or equations (2-B) and (2-10) for Unit 3.

S0123,-ODCM 2-17 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.4 WASTE GAS HEADER - 3RT-7865-1, 2/3RT-7808 For the purpose of Specification 2.1o"1, the alarm'setpoint level fbr noble gas monitors prhe is basedpj 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 mrem/yr or a skin dose rate of 3000 mrem/yr at the exclusion area boundary is determined by using equations (2-1) or (2-2) with sample concentration (Cj ) and (Ctoj) being obtained from the waste gas decay tank to be released.

2.6.4.1 Maximum Permissible AlarmýSetpoint'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 moni-tor alarm setpoi nt. -

The maximum release rate (#Ci/sec) for Plant Vent Stack Monitors is determined by converting the concentration at the detector, Cdt (pCi/cc) to an equivalent release rate in yCi/sec, as follows:

Amax (Cdet, pCi/cc) (flow rate, cfm) (28320) (2-3)

(S)(60) where:

Am = maximum permissible release rate, yCi/sec C6.t= 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 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 I for 2/3RT-7808.

SO123-ODCM 2-18 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.4 WASTE GAS HEADER - 3RT-7865-., 2/3RT-7808 (Continued) 2.6.4.2 A release from the waste gas header is not possible if-:

~(2-.1z) where:

Ci = total gamma activity (iuCi/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 fl6wrate (cfm)' used in equations (2-1) and (2-2)

Cdet " = smaller of the values of Cdet determined in '

equations, (24-) and. (2-2),with C. 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:

.(WG) (Cdet) (F) where: z i Ci f = waste gas header effluent flow rate (cfm)

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

Coet, = smaller of th e value of Cdt from equation (2-1) or (2-2) z.C. = total gamma activity (uCi/cc) of the waste gas holdup tank to be released, as determined from the pre-release sample analysis.

WG = an administrative value to account for the potential activity from other releases in the same release pathway, typically 0.9.

S0123-ODCM 2-19 Revision 0 02-27-07

Table 2-3 Gaseous Effluent Radiation Monitor Calibration Constants(a)

(YC'i/cd/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.

S0123-ODCM 2-20 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.7 Gaseous Effluent Dose Rate The *n'ekthdol'6gýgy used for the purpose pf. implementation of Specification 2.1.1 f*r the dose rate above background. to an individual i unrestricted area is calculated by using' the folloWing expressions:

2.7.1 FOR NOBLE GASES:

(2-13)

DTB 1,(/Q 1 .(2-14)

DS z L + 1. 1M1) (X/)O where:

D = total. body dose rate in unrestricted areas due to radioactive materials .released in gaseous effluents, mrem/yr 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 3 gas radionuclide, i, in mrem/yr per pCi/m Li = / skin dose factor due to the beta emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrem/yr per yCi/mr Mi air dose factor due to gamma emissions.from Table 2-4 for each identified .noble gas rad'tonucl de, iA;. in mrad/yr perjjCi/m ..

(conversion constant of .1, mrem/mrad converts air dose to skin dose.)

= measured or calculated release rate of radionuclide, i, for either continuous or batch gaseous effluents, in gCi/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/mr for Units 2 and 3 B.OE-5 sec/m3 for South Yard Facility S0123-ODCM 2-21 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.7.2 FOR ALL RADIOIODINES. TRITIUM AND FOR ALL RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES. GREATER.

THAN EIGHT 'DAYS:.

(2-i5)

0 i ý ýi]

Wk)Pký where:

organ dose rate in unrestricted areas due to radioactiv.e materials released in gaseous effluents, mrem/yr measured or calculated release rate of radionuclide, i ,

for either continuous or batch gaseous effluents,

[Ci/sec Pik dose parameter for radionuclide, i, for pathway, k, from Table 2-5 for the inhalation pathway in mrem/yr per pCi/m 3 . The dose factors are based on the critical individual organ and the child age group.

= highest calculated annual average dispersion (X/Q) or deposition (D7() factor for estimating the dose to an individual at or beyond the unrestricted area boundary for pathway k.

(X7*), 4.8E-6 sec/m3 for Units 2/3 for the inhalation pathway. The location is the unrestricted area in the NW sector.

= ()-Q), 8.0E-5 sec/mn for South Yard. Facility for the inhalation pathway. The location is the unrestricted*

area in the E sector.

S(X-), 1.3E-5 sec/mr3 for the NIA (Unit 1) for-the inhalation pathway. The location is the unrestricted area in the NW sector. (Historical value)

'(fl7-)04.3E-8 mt.for Units 2/3 for the food and ground plane pathways. The location is the unrestricted area in the E sector.

(D'-), 8.OE-7 m-' for South Yard Facility for the food and ground plane pathways. The location is the unrestricted area in the E sector.

7.2E-8 sec/M 3 for NIA (Unit 1) for the food and ground pathways. The location is the unrestricted area in the NW sector. (Historical value)

SOI23-ODCM 2-22 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.8 Gaseous Effluent Dose Calculation 2.8.,1 DOSE FROM NOBLE GASES: IN GASEOUS EFFLUENTS The gaseous releasesý 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 meteoroloQy:

0 NQj]

[ (2- .6)

D 3.1

= 3.17xi0- ,i N (217) where:

D= total gamma air dose from gaseous effluents, mrad D= total beta air dose from gaseous effluents, mrad 3.17xi0" = inverse seconds per year.

Mi air dose -factor due to gamma emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrad/yr per uCi/m' N: air dose due to beta emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrad/yr per

(,X/Q) = Maximum 'annual average atmospheric dispersion factor for"any landward sector or di stance at, or beyond the unrestricted area boundary.

.4.8E-6 sec/m3 for Units 2 and 3

= 8.0E-5 sec/m3 for South Yard Facility Q= amount of noble gas radionuclide, i, released in gaseous effluents, yCi.

S0123-ODCM 2-23 Revision 0 02-27 -07

2.0 GASEOUS EFFLUENTS. (Continued) 2.8.1.2 For meteorologv concurrent with release:

NOTE: Consistentwith .the methodology provided in Regulatory Guide 1.109!'and the following equations, quallity affecting comput-er, software is used to perform the actual calculations.

(2-18)

= 2.14xI20 4 Z: i M (2-19)

Doe = 1.14X10 z. Ni E A,(X/Q)e where:

Dye total gamma air dose from gaseous effluents in sector e, mrad Doe total beta air dose from gaseous effluents in sector e, mrad 1.14x104 - inverse hours/year air dose factor due to gamma emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrad/yr per yCi/m 3 air dose factor due to beta emissions from Table 2-4 for each identified noble gas 3 radionuclide, i, in mrad/yr per PCi/m Atj length of the ji, time period over which (X/Q)* 8 and ýi, are averaged .for gaseous rel eases in. hours (X/Q)je atmospheric dispersion factor for time period At, at exclusion boundary location in landward sector e 3determined by concurrent meteorology, sec/M 0Ij average release rate of radionuclide, i, in gaseous effluents during time period, Lt j ,

piCi/sec S0123-ODCM 2-24 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.8.2 DOSE FROM TRITIUM. RADIOIODINES AND RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN 8 DAYS.IN GASEOUS EFFLUENTS.

The dose to an i ndi vi dual' friomntriti umi radiiotodi nes and, radioactive matefaIals in particulate form with 'half iives greater than' eight days in gaseous effluents released to unrestricted areas is calculated using the following expressions:

2.8.2.1 For historical meteorology:

(2-20)

Do : 3.17x1D-8 z. [F-k (RkWk)Q1]

where:

DO total projected dose from gaseous effluents to an individual, mrem 3..17xI0-8 .= year/second .

amount of each radionuclide, i, (tritium, radioiodine, radioactive material in particulate fdrm with half lives greater than eight days),

released in gaseous effluents, yCi ZR~kWk sum of all-pathways, k, for radionuclide, i, of the R1 W product, in mrem/yr per yCi/sec. The EkRikWk value for each radionuclide, i, is given in Table 2-6 for Units 2/3, Table 2-7 for South Yard Facility, and Table 2-8 forthe North Industrial Area (Unit I historical value). The value given is the maximum zkRikWk 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 in mrmm/yr' per uCi/mr and for the food and-ground plane pathways in m'-mrem/yr per pCi/sec), at the controlling location. The Rik's for each controlling location for each age group are given in Appendix A. Data in these tables are derived using the NRC code;ý PARTS... (See the annual. update of revised R1 parameters based on changes in the Land Use Census provided by Corporate Health Physics and Environmental.)

S0123-ODCM 2-25 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.8.2.1 For historical meteorology: (Continued)

Wk annual average dospersion (X/Q) or deposition (D/Q) factor'for estimatingthe ,dose to an individual at the control Ii ng locati-o.n o'for pathway. k.

= (X/Q~iorthe inhalation pathway in sec/m3.

The (X/Q) for each controlling location isgiven in Appendix A.

= (D-ZL)for the food and ground plane pathways. in m- 2.

The (D/Q) for each controlling location is given in Appendix A.

2.8.2.2 For meteorologv concurrent With releases:

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

Imn r *l(2-21) where: De I.14 x 0-' i ik (t) (RIke) (jke) i Do total annual dose from gaseous effluents to an individual in sector e, .mrem.

At = length of the jth period over which Wk, and Qýj are averaged for gaseous released, hours i Q = average release rate of radionuclide, i, in gaseous 'effluents during time period Atj, #Ci/sec Rike dose factor for each identified radionuclide i, for pathway k.for sector e (for the inhalation pathway in mrem,/yr per yCi/mr. 'and for the food- and ground pl~ane pathways in m2 mrem/yr p'er iisey at thcon'trlling location. A listing of Rik for the controlling locations in each landward sector for each group is given in Appendix A. The 'e is determined by the concurrent meteorology.

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

= (__!_Q=)for the inhalation pathway, sec/m3

= .(D/Q) for the food and ground plane pathways, m-2 S0123-ODCM 2-26 Revision 0 02-27-07

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

i otaBpdy .Dose , Skin Doe., Gamm".Ai. Dose Beta Air Dose Fac~tor Ki Fact'r L1 Fto M1 F~t~rý Radio- (mrmyem/yr rm/yr (mrad/yr * (Irt /y.

Nucli de per pCi /m3) per pCi/mrn) pe rpCi/nm') per pCi/m 3)

Kr-85m 1.17E+3 1.46E+3 1.23E+3 I .97E+3 Kr-85 1.61E+1 .1.34E+3 1.72E+1 1.95E+3 Kr-87 5.92E+3 9.73E+3 6.17E+3 1. 03E+4 Kr-88 1..47E+4 2.37E+3 1.52E+4 2.93E+3 Xe-131m 9.15E+i 4.76E+2 1.56E+2 1.11E+3 Xe-133m 2'..251E+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-'135rn 3.12E+3.. 7. 1E+? 3.36E+3 7.39E+2 Xe-135 1.81E+3 1.86E,+3 1.92E+3 ' 2.-46E+3 2,

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-i S0123-ODCM 2-27 Revision 0 02-27-07

TABLE .2-5 DOSE PARAMETER Pik*

CHILD AGEAGROUP CRITICAL ,ORGAN Inhalation Pathway Inhal ation Pathway Radionuclide (mnrem/yr per pCi/me) Radionuclide (mrem/yr per pCi/mr3 )

- 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.iE+5 I -134 5.1E+4 C1-58 *.IE+6. I,-135 7.9E+5 Co-60 7.1E+6 Cs-134 1.OE+6 S*r8., 2:.2E+6 Cs.136 . 17JE5.

Sr-90 "1.OE+8 Cs-137: 9.E+5 Zr-95 2.2E+6 Ba-140 1.7.E+6 Nb-95 6.lE+5 Ce-141 5.4E+5 Ru-103 6.6E+5 Ce-144 1.2E+7 Te-129m 1.8E+6

Source: USNRC NUREG-0133, Section 5.2.1.1 S0123-ODCM 2-28 Revision 0 02-27-07

TABLE 2-6 UNITS 2&3 CONTROLLING LOCATION FACTORS' zkRikWkf Radionuclide mrem/yr per, uCi/sec Use:

H -3 4'.81E-3 R: Camp Mesa Cr-5i 1.95E-I R: Camp Mesa Mn-54 4.24E÷1 R: Camp Mesa.

Co-57 8.61E+O Ri Camp Mesa.

Co-58 1.43E+1 R: Camp Mesa Co-60 5.82E+2 R: Camp Mesa Sr-89 1.68E+i1 Q: SC Res. with Garden Sr-90. 6.60E-I2 Q: SC Res. with Garden Zr-95 1.62E+I R: Camp Mesa Nb-95 I..05E+1 E: Deer ConSume'r/Hunter Ru-103 1.69E+1 E: Deer Consumer/Hunter Te-129m 7.90E+0 R: Camp Mesa Cs-134 1.71E+2 R: Camp Mesa Cs-136 3,82E+0 R Camp Mesa Cs-137 2.50E+2 R: Camp Mesa Ba-140 7.93E'0 R: Camp Mesa Ce-141 2.61E+O R: Camp Mesa Ce-144 4.98E+1 R: Camp.Mesa I -131 5.96E+1 R: Camp Mesa I -132 7.33E-1 R: Camp Mesa I -133 1.41E+l R: CampMesa I -134 2.O0E-1 R: Camp.Mesa I -135 2.99E+0 R: Camp Mesa UN-ID 2.32E+1 R: Camp Mesa These values to be used in manual calculations are the maximum ZkRlkWk for all locations based on the most restrictive age group.

S0123-ODCM 2-29 Revision 2 02-27-09

TABLE 2-7 SOUTH YARD FACILITY CONTROLLING LOCATION FACTORS' i'iRadionuclide,, I mrem/yr

, ... per pCi/sec:

m.yr.RikWk I 'u . J . , ' ,use*.,,,,i,.*:,

U H -"3 " 1.31E-3 G: San Oribfre Bch Campgd Cr-51 4.15E-2 F: SO St, Pk,./Guard Shack Mn-54 9.70E+O F: SO St. Pk.Gu'ard Shack Co-57 2.41E+0 F: SO St. Pk./Guard Shack Co-58 3.14E+0 F: SO St. Pk./Guard Shack Co-60 1.35E+2 F: SO St. Pk./Guard Shac.k Sr-89 1.71E+O F: Deer Consumer/Hunter Sr-90 1.04E+2 G: San Onofre Bch Campgd Zr-95 7.26E+0 F: Deer Consumer/Hunter Nb-95 2.88E+I1 F: Deer Consumer/Hunter Ru--103 4 56E+1 F: Deer Consumer/Hunter Te- 129m 2.26E+1 F: Deer Consumer/Hunter Cs-134 4.28E+1 F: SO St. Pk./Guard Shack Cs-136 1.04E+0 F: SO St. Pk./Guard Shack Cs-137- 6.36E+1 F: SO St. Pk,./Guard Shack Ba-140 1.39E+0 G: San Onofre Bch Campgd Ce- 141 4.29E-1 G: San Onofre Bch Campgd

,Ce-144 8.39E+0 G: SanOnofre Bch Campgd I -131 2.28E+1 F: Deer Consumer/Hunter I -132 1.22E-1 G: San Onofre Bch Campgd 1 -133 2.22E+0 G: San Onofre Bch Campgd I -134 3.24E-2 G: San OnofreBch Campgd 1 -135 4,60E-1 G: San Onofre Bch Campgd UN-ID 5.36E+0 F: SO St Pk./Guard Shack I L These values to be used in manual calculations are the maximum ERlkW, for all locations based on the most restrictive age group.

S0123-ODCM 2-30 Revision 0 02-27-07

TABLE 2-8 NORTH INDUSTRIAL AREA (UNIT 1) CONTROLLING LOCATION FACTORS' Radionuclide k I mrem/yrLper yWCi/sec t'

A: Camp Mesa Use:

H -38 5.46E.-3 Cr-51 Z.242E-1 B: Camp Mesa Mn-54 5.54E+1÷ B: Camp Mesa Co-57 1.. 17E+1 B: CampMesa Co-58 1.80E+1 B: CampMesa Co-60 .7. 82E+2 B: Camp Mesa 1.82E+1 Q, SC Res. with Garden Sr-89 Sr-90 7.16E+2 Q: SCRes. with Garden Zr-95 1. 93 E+1 A: Camp Mesa Nb-95 7.68E+0 CampMesa 6Ru-103 1.09E+1 Dee r,,.Consumer/Hunter 9,.04E+0 Te-129m B. Camp Mesa Cs-134 2.32E+2 Camp .Mesa Cs-136 5.17E+0 B: Camp Mesa.

Cs-137 3.40E+2 B: 'Camp Mesa Ba-.140 9.07E+0 A: Camp:Mesa Ce-141 3.01E+0 A: Camp Mesa Ce-.144 5.68E+1 A: Camp Mesa I -131 6.77E+! A: CampMesa I -132 8.36E-1 A: Camp Mesa I -133 1.60E+1 A: Camp Mesa I -134 2.29E-1 A: Camp Mesa I -135 3.40E+0 Camp Mesa A: Camp Mesa UN-ID 3.02E+1 B:

These values to be used in manual calculations are the maximum Y*kRikWk for all locations based on the most restrictive age group.

S0123-ODCM 2-31 Revision 0 02-27-07

3.0 PROJECTED DOSES 3.1 Liquid Dose Projection The methodology used for projecting a liquid dose over 31 days for.

Specification I.3.1 is, as, follows:

1. Determine the monthly total body and organ doses resulting from releases duringthe, 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.

S0123-ODCM 3-1 Revision 0 02-27-07

3.0 PROJECTED DOSES (Continued) 3.3 TOTAL DOSE SPECIFICATION

.3.3.1 The6doQse' or dose'cimtfett aymme f'h publ ic 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 thy.roid, 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' effluenits'-',exceeding. twice 'the; limits of Specifications 1.2.1.a, 1.2.1.b, 2.2.i.a, 2.2.1.b, 2.3.1.a, or 2.'3..i.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.ý Nuclea.r.

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 whichestimatesthe radiation exposure (dose) to a member of thepublic 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. Saff. action on the request is complete. The variance only .relates to the l1imi ts of 40CFR 190, and does, ndto, apply in any way to the requirements for dose limitation'of 10CFR Part 20, as addressed elsewhere.in this ODCM.

SURVEILLANCE REOQUIREMENTS

.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.

S0123-ODCM 3-2 -Revision 0 02-27-07

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS 3.4,1. ,Total, Dose.. to Most Likely..Member, of:the Public The, total!: a~nndial dose or total;. doseý. c~ommi tment' to ýAny member of the publ i c,: due to rel eases ýof ir'do 6acti vi ty and top radiation,..from uraniumfuel cycle sources within ý5 miles of the Site is .calculated using. the following expressions. This, methodologyis 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 is less than or equal: to 25 mrem, 25 mrem, and 75 mrem respectively. D

.1 Annual'Total Organ Dose (D TOTfL)1

((3--)

12 2/3 .

DTOT (0). : ." ID. 1(OG)+ D(OL)+ D

.1

( 4 1=1 j=.

where:

NOTE: DN'OG) = 0 for bone

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

n Djj (OG)= K z Ci R: Wk (3-Z) i=l i = each isotope in specific organ category j = NIA, Unit 2 and Unit 3 1 = months 1 - 12"*

year-pCi K = 3.1688E-2 sec-Ci

.S0123-ODCM 3-3 Revision 0 02-27-07

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 Total Dose to Most Likely Member of the Publ i c (ContirP-'d) n = number' of isotopes-in the soecified organ category Ci total particulate gas curies released for the month Er, kWk SONGS controlling location factors (Tables 2-6, k 2-7 or 2-8).

DdI(OL) = liquid organ dose for the specified organ in mrem for the month., [equation (1-16)]

.DHil0G)*. las organ dose from tritium in mrem. for the month.

"equation (2-15)] " .

.2 Annual Total Whole Body Dose DToT(WB)

D'TE, TOT(WB) j=1 fDj(WB+L)+ D 3(OGO+ 0.)9 ÷D(DIRECT),

where:

. = NIA, Unit 2 and Unit 3

= months 1- 12, to be summed over the most recent 12 months DjI(WBL) liquid whole body organ dose in mrem for the whole month. [equation (1-16)]

Dj- 3 (OG) as organ dose from tritium in mrem for the month.

Lequation (2-15)]

Dj1(y) gamma air dose in mrad for the month.

0.9 converts mrad to mrem,

[equation (2-16)]

n (3-4)

FD(bkgd),~

4

_ p.1 .0342 D (Direct) = n q=1 p for all TLDs per quarter q for Quarters 1-4 S0123-ODCM 3-4 Revision 0 02-27 -07

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4,-.1. Annual Total Whole Body. Dose DTOT ) (Conti nued)

Di rect 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 Iot..1 (top,*of bluff).

Reference:

E. M. Goldin Memorandum for File, "Occupancy Factors at San Onofre Owner Controlled Area Boundaries," dated October 1,1 991.

.3 Annual Total Thyroid Dose DT0T(T) 12 2/3 DTr(T) = E E [o1S (OG) + DjI (OL) (3-5) 1=1 j=l where:

j = NIA, Unit 2 and Unit 3 S= months I - 12, to be summed over the most recent

.12 months 1 (OG).

Di thyroid organ dose from gaseous iodine for the.-

month in mrem. [equation (2-20)]

D) (OL) liquid thyroid organ dose for the month in mrem.

[equation.(1-16)]

S0123-ODCM 3-5 Revision 0 02-27-07

4.0 EQUIPMENT 4.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SPECIFICATION 4.1.1 The.radioacti~ve liquid effluent'monitoring instrumentation channels shown in Table 4-1 shall beOPERABLEwith their alarm/tripo-setpoi:nts set to ensure that the1limits of Specif.icatiph; 1.1.1 are not exceeded. The alarm/trip setpoints of'these chanriels 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. ess conservative, than Arequ~iredUby the above speci fi cati on, immmediately sUspend the release of radioacti veliquid effluents monitored. by the affected channel or declare the channel inoperable.

b. With less than the minimum number-of radi oactive liquid effluuent monitoring, instrumentati on channel s *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 inoperabl e 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, channel s 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 Act.ion Program.

SURVEILLANCE REOUIREMENTS,.

.1 Each radioactive liquid effluent monitoring instrumentationchannel 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 I hour 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.

S0123-ODCM 4-1 Revision 0 02-27-07

TABLE 4-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNEL S 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 Effl.uent Line - 2(3)RT-7817

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

d. Steam Generator (E088) Blowdown Effluent Line - 2(3)RT-6759 29

e. Steam Generator (E089) Blowdown Effluent 1 Line - 2(3)RT-6753 29.

f. Yard Drain Sump.- RT-2101 I 44

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 Component Cooling Water Sumps, Storage Tank Area Sumps Effluent Line 1 31

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

e. Steam Generator (E089) Blowdown Bypass Effluent Line 1 31

f. Yard Drain Sump EffluentLine 1 31 S0123-ODCM 4-2 Revision 0-02-27-07

TABLE 4-I RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT* OPERABLE ACTION

3. DATA ACQUISITION SYSTEM (CONTROL ROOM ALARM ANNUNCIATION) 1 32

4. UNIT 2 PLANT COMPUTERSYSTEM (CONTROL ROOM ALARM ANNUNCIATION) 32 5'. CONTINUOUS COMPOSITE SAMPLERS

a. Turbine Plant Sump, Auxiliary Building Sumps - 2(3) APC 5887 1 33

b. Blowdown Processing System Neutralization Sump - 2(3) APC 3772 1 33 C. Steam Generator (E088) Blowdown to By pass, Steam Generator .(E088) Blowdown - 2(3) APC 4077 33

d. Steam Generator. E089) Blowdown to Bypass, Steam Generator (E089) Blowdown - 2(3) APC 4076 33 SO1.23 -ODCM 4I-3 Revisi*on O

02-27-.07

TABLE 4-I (Continued)

TABLE NOTATION

'Mni.tor Recorders, are.not required for .'the Operability of.the monitor.,

provi.ding the ihoperable recorder does not: cause the, montor. tobecome..n inoperable, (i.ei, feedback signal).. As .4long as the"lm:onitoiri has Indi cation, alarm capa+bility (if aopiicabl.e),, proper response (based on. .surveillaice requirements) and isolation fuhctioIn (if. applicable),. the loss of the-recorder does not render the monitor inoperable.

ACTION 28 - With the number of channels OPERABLE. less than required by the Minimum Channels OPERABLE requirements, effluent releases may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Specification 1.1.1 and

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

ACTION 29 - With the number of channels OPERABLE less. than required by the Minimum CharinelS 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-' microcuries/gram:

a. At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcuries/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 $2(3)1318MU577 and divert flow to T-064 for processing as liquid radwaste, ACTION 30 - With the number of channels OPERABLE less than requi red 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 Wlimit of detection of at least 10-7 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.

S0123-ODCM 4-4 Revision 0 02-27-07

TABLE 4-1 (Continued)

TABLE NOTATION ACTION 31 . Wit h t he n'umber

'Mini.'mum - .' of-achnne.s RB , OPERABLE 'less thhan ,required by the,.

MinmumCha'eI OPERABE I~ur~et efuent .,reeases.ývial ti s pathway.may-continue provitded, the process fb'w rate is es**mated' at

!east once per '12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months duri ng'actia'* releases. in addition',:'a new flow estimate shall bemad'e within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after' a hange Pump curves may that.

be. used affects process flow has been completed.

to estimate process flow.

Loss of process'flow instrument(s) results in the associated g.ross activity monitor becoming INOPERABLE, Perform the compensatory action for the inoperable gross 'activity monitor in addition to this' compensatory action:. [2(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.requilrement,"'efflueht releases vialthis pathway' may continue provided tthe 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.the Minimum"channels OPERABLE requirement, effluentreleases via -this pathway may continue provided'grab samples are collected. daily, and comrposited and analyzed weekly:.

a. at least once per 24'hours, 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.

ACTION 44 - 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 lower limit of detection of at least'lb-' microcurie/ml).

S0123-ODCM 4-5 Revision 0 02-27-07

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

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) Q(1)

b. Steam Generator Blowdown Processing System (Neutralization Sump), Full'Flow Condensate Polisher Effluent- Line - 2(3)RT-7;817 D M R(2) Q(1)

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

d. Steam Generator (EO8B) Biowdown 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)

f. Yar.d Drain Sump Effluent"Line - RT-2101 0 M R(2) Q0()

2. PROCESS FLOW RATE MEASUREMENT DEVICES

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

b. Steam Generator.Blowdown Processing System (Neutralization Sump), Full Flow Condensate Polisher Effluent Line D(3) N/A R Q

c. Turbine Plant Sump, Auxiliary Building Sump, Component Cooling Water Sumps, Storage Tank Area Sumps Effluent Line D(3) N/A R

d. Steam Generator (E088) .Blowdown Bypass Effluent Line D(3) N/A RQ

e. Steam Generator (E089) Blowdown Bypass Effluent Line D(3) N/A R Q

f. Yard Drain Sump..Effluent Line D(3) N/A R Q S0123-ODCM 4-6 Revision 0 02-27-07

TABLE 4-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL, SOURCE. CHANNELS FUNCTIONAL INSTRUMENT" CHECK ' CHECKý CALIBRATION TEST

3. DATA ACQUISITION SYSTEM (CONTROLROOM ALARM D N/A N/A(4) Qi ANNUNCIATION)

4. -UNIT 2 PLANT COMPUTER SYSTEM. (CONTROL ROOM ANNUNCIATION) N/A N/A Q

5. 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 -

D(5) N/A R Q.

2(3) APC 3772

c. Steam Generator, (E088) Blowdown to Bypass, Steam Generator (E088) Blowdown - 2(3) APC 4077 D(5) N/A R

d. Steam Generator (E089) Blowdown to By pass, N/A Steam Generator;(EO89) Blowdown - 2(3) APC 4076 D(5) R S0123-ODCM 4-7 Rev i s-ion 0 02-27,-07

TABLE 4-.2 .(Continued)

TABLE NOTATION

- Monito" Recorders are- fnot reqUi~red fo. Z,th Optrab0i oiy the, moniitor .

providing the'inoperable recorder does not' cause theýoni t*or to "become.

inoperable (i-e., feedback signal). As long as the monitor' has indication, alarm ca'pability (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 period.

Down scale failure testing is bounded by administrative limitation on monitor setpoint whi.ch~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 doqnot require Channel Calibration. The DAS software is quali.ty:affecting and controlled by the site Software Modification Request process under procedure: SQJ123-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 orS0123-XXIV-1O.1, 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.

SO123-ODCM 4-8 Revision 0 02-27-07

4.0 EQUIPMENT 4.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SPECIFICATION 4.2.1. The radioactive gaseous effluent monitoring.

instrumentation channels shown in Table 4-3 shall be OPERABLE with theiralarmi/trip setpoints set to' ensure that the limits of Specification M2J.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-,radioact ive gaseous effluent monitoring instrumentation channel. ala6rm/trtp, 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 inoperabl e.. .

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 3.0 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 REQUIREMENTS "

.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.

S0123-ODCM 4-9 Revision 0 02-27-07

TABLE 4-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT*** OPERABLE APPLICABILITY .-ACuwION

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 MOni toring Device 1

36a

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 1I 36b

e. Process Flow Rate Monitoring Device ** 36a

3. PLANT VENT STACK

a. Noble Gas Activity Monitor- 2/3RT-7808, or 2RT-7865-1 and 3RT-7865-. 1(2)

37

b. Iodine Sampler 1(2)

40

c. Particulate Sampler "(2)

40

d. Associated P&I Sample Flow *Measuring Device 1(2) *3.6b.

e. Process Flow Rate Monitoring Device - 2/3RT-7808, or 2RT-7865-1 and 3RT-7865-1 *36a

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 *I

40

c. Particulate Sampler . 1

40

d. Associated P&I Sample Flow Measuring Device 1

36b

e. Process. Flow Rate Monitoring Device 1 .

36a

5. DATA ACQUISITION SYSTEM (CONTROL ROOM.ALARM ANNUNCIATION) <1

42 SO123-ODCM 4-10 Revisilonr 0 02-27-07

TABLE,4-3 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT'** OPERABLE. APPLICABILITY ACTION

6. SOUTH YARD FACILITY (SYF) WORK-AREA SYFRU-7904

a. Iodine Sampler 1 *. 40

b. Particulate Sampler 1 40 Associated P&I Sample Flow.Measuring Device 1 *A 41b C.

1 41a

d. Process Flow-Rate Monitoring Device

7. SOUTH YARD FACILITY (SYF) DECONTAMINATION UNIT SYFRU-7905

a. Iodine Sampler 1 40 1

40

b. Particulate Sampler 1

C. Associated P&I Sample Flow Measuring Device 4.1b 1

41 a.

d. Process Flow Rate Monitoring Device S012.3-0D-CM 4-11 Rev*sion 0

,0227-07

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 monitors 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) 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 thenumberI of channels OPERABLE less than required.by .the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and b.. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend releases of radioactive effluents via this pathway.

S0123-0DCM 4-12 Revision 0 02-27-07

TABLE 4-3 (Continued)

TABLE NOTATION ACTION 36 - With the number of channels 'OPERABLE. I ess than requi red by the Minlimuml Channels OPERABLE requirement, effluent releases. via, thi s 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 I hour-after a. change that affects process flow has beencompleted. 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 requilred by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12.hours 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 requiredin 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..hours 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'.

S0123-ODCM 4-13 Revision 0 02-27-07

TABLE 4-4 RADIOACTIVE GASEOUS EFFLUENT: MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE -FOR- WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL

.TEST SURVEILLANCE INSTRUMENT*** CHECK CHECK CALIBRATION 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 Gas Activity 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 Sample Flow D NA R Q. **

Measuring Device

e. Process Flow Rate Monitoring 0 **

Device (2(3)RT-7870-l) NA R Q S0123-ODCM, 4-14 Revision 0 02-27-07

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- D M R(3) Q(2)

2/3RT-7808, 2RT-7865-1, 3RT-7865-1

b. Iodine Sampler W NA NA NA

c. Particulate Sampler 4W NA NA NA

d.' Associated Sampl*e Flow Measuriing Device D NA RQ Q

e. Process Flow. Rate Monitori-ng Device 0 NA R Q

4. CONTAINMENT PURGE SYSTEM

a. Noble Gas Activity Monitor -

Providing Al.arm, and Automatic Termination of Release --

2(3)RT-7828, 2(3)RT-7865-1 D 1?(4) R(3) Q(M). *

b. Iodine Sampl~er 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 *

/i S0123-ODCM 4-15 Revisioan 0

02-27-07

TABLE 4-4 (Continued)

RADIOACTIVE GASEOUS;EFFLUENT.MONITORING INSTRUMENTATION SURVEIL _LLANCE REQUIREMENTS CHANNEL MODE FOTRWHICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE INSTRUMENT*** CHECK CHECK CALIBRATION TEST

.IS REQUIRED

5. SOUTH YARD FACILITY (SYF). WORK AREA

a. Iodine Sampler W NA NA NA i*

b. Particulate Sampler .W NA NA NA

c. Process Flow Rate Monitoring Devi c.e D(5) NA R Q

d. Associated Sample Flow Measuring Device D(5) NA R Q* *

6. SOUTH YARD FACILITY (SYF) DECONTAMINATION UNIT NA

a. Iodine Sampler W NA NA *

b. Particulate Sampler W NA NA NA *

c. Process Flow Rate Monitoring Device D(6) NA R Q *

d. Associated Sample Flow:Measuring Device D(6) NA R

NOTE: For 5 and 6, ECP 030100131 abandons the-MGP radiation monitors and install]s flow meters. This section applies to the flow meters and will, take effect when ECP turnover is coimpl.ete.

SO123-ODCM 4-16 Revision O

ý02-27-07

TABLE 4-4 (Continued)

TABLE NOTATION

- .At al~l. times.

- Modes 1-4 with any main steam isolation valve and/o&r anhy 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*. i solation actuation signal., automatic pathway isol ati ont ,- and Control.

Room alarm annunciation if any 'of. the following.conditionSr exist:

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

2. Circuit failure.

t Automatic pathway isolation is tested on a" once. pe.r;efueli.ng 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.. Iinstrument, indicates measured, 1 evel s above the alarm setpoi.nt.

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.

S0123-0DCM 4-17 Revision 0 02-27-07

TABLE. 4-4. (Continued)

TABLE NOTATION (Continued)

(3) The, hiniti al. CHANNEL CALIBRATION. shal .l be.' perfo6ýmed' usi ng Oneý Dr.more of" the, reference standards certified by: the National Institute' of: Standards" and i that,.

Technology or using.standards that have been obtained from .supplie rs standards participate in meaIsurement assurance activities with NIST. I These 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 CO2 Decontamination Unit is used.

S0123-ODCM 4-18 Revision 0 02-27-07

WASTE EQUIPMENT 4.3 OPERABILITY OF RADIOACTIVE of the treatment paths and the components are.

The flow diagrams defining 'Waste management, systems gaseous a6id.sol-id the radioa'ctiVe liqu'id, 4'-7..

shown,An; Figur'es4- thru S0123-ODCM Revision 0 4-19 02-27-07

FIGURE 4-5 SONGS RADIOACTIVE LIQUID WASTE TREATMENT SYSTEMS IRadwaste Puimary Tanks Radwaste Secondary Tanks.

PuimaryMakeup Tanks Condensate Monitor Tank, (Batt~)

MAY08 (Gontinuous)

Radiation Monitor S0123-ODCM 4-20 Revision 1 02-29-08

FIGURE 4-6 SONGS RADIOACTIVE GASEOUS WASTE TREATMENT SYSTEMS ATMOSPilERE -

2(3)RT-7865-1 can be aligned to either contalnmentipurge or the plant vent stack S0123-00CM 4-21 i 7Revi0 on -0 02-27-07

FIGURE 4-7 SOLID WASTE HANDLING Spent Resin Resn luiedSpent

,,.,,,,,,,+,

,,,,,,,o,,,

Resin accumulated Resin_.sluiced foSRto disposal

- Transferred tooae

(.Loaded., ,to, it MPHFfor .shipplng cask in SAT container-and interim-stagingtobra sie dewatered Filter evaluated for Particulate FIterremoved Filter stored InctnerabilItyli Paroic later - - from in-line in accumulation ../ incenerable, Waste shipped if incinerable innpckaged position area.on site -shipped for drum:liner-:for osburia-lsite.

offa-site dIsposol inceneration Wastes Waste placed In. Waste shipped Resuilting disposable Low Level Activ.,e Dry Waste reepticles.

cl cro'container to processor: wastepackaged ai'6- for shipment to for volume Active Wasteloca ted aroundfrm and shipped the plant ' processor.. Ireductio, fromprocessor I t n processor, to burial. site Waste sorted for packaging Wastes packaged Waste shipped onsite or end transferred 1 z to bril site vendor to ?PIJF processing vlothing packed Cohn Clothing bags in boxes'.and laundered, Protective collected from - shipped to

returned-to Clothing polnts around off-site re and plant laundry site and facilityrestocked LEGEND:

SlT: Spent Resin Tank MPHF. Multi Purpose Handling Facility IXMIon Exchanger S0123-ODCM.

4-22 Revisioon 0

.02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 Monitoring Program SPECIFICATIONý 5.1 .1.The- radiological envfronmental .monitoringI program shall be conducted as specified in Table '5-i. 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.O.104,, prepare" and'submitq.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 prevent~ing a recurrence..,,

b. Should the level of radi'oactivity in anenvironmental sampl i ng medium exceed the' reporting Ievel s of Table '5-2 when averaged over any 6alendar quarter, in lieu of any other report,-required by Technical. Specification Section 5.7.4 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 10CFR 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 (1) + 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 thepotential annual dose to an individual; isr equal to,' or greater than the" calendar.

year limits of Specification(s) .21.2.1 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).

S0123-ODCM 5-1 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued)

ACTION: (Continlued) d, Wi th f resh' l eafy Vegetae .samp1~ or fl eshyvgtbl sampie's, upavaiyl abl' 1from one or* mor* of ýthe

.".sample lo1cationsr.required by. Table' 5 . identi fy speci fI C .

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 Repor.t documentation for a change in the 0DCM including a revised figure(s) and table for the ODCM reflecting. the new location(s) with

I s.upporting

. .information identifying the cause of the unavailability. of. samples: and.: justi*fying -the' selection of.

the. new location(s) for'obtaini ng sampl es.'

SURVEILLANCE REQUIREMENTS

.1 The 'radiological environmental monitoring. samples 'shall be collected pursuant toTable 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-i and 3.

S0123-ODCM 5-2 Revision 0 02-27-07

TABLE 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway, Number of Samples,". Samplingqand a and/or Sample and Samile 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 dnce per .7 days fo'or and 3 samples from offsite.locations Collection.as required 1-1311. 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.' radi oacti vi ty >124 hours ground Tevel D/Q - fol1 owi ng fi l ter change.

Perform Igamma* i sotopifcb ana-lysis onneach sample when -gross beta I sample, from the-vicinity of a community having the highest activity is.-> 10 times the ýý calculated annual, average ground- yearly mean. of-contrtol samples.

level D/Q. Perform-.gamman isotopic 'analys'is on composi~te (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' At least 30l-ocations.including At least once per , Gamma dose. At least once per

2. DIRECT RADIATIONe an inner ring of,-` sta-tioins in the 92 days. '92 days.

general.-area, of the site boundary, and an-outer ri ng <.z-approxi matel y in the: 4 to 5 mil.e range -from the site with a stationhin each sector of each. ring, The:balance of the'stations 1is in special interest areas such as population centersi nearby..;residences, schools, and in:Z or 3 areas to serve as. control. :stations.

S0123-ODCM 5-3 Revision 0 02-27-07

TABLE 5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL-MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Sample and Samole Locationsa Collection Frequency Type and Frequency of AnalyVses

3. WATERBORNE

a. Ocean 4 locations At I east once. per. GammaI sotopic analysis .of each ,

monthand composited' monthly sample. Tritium anal~ys-is 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

184 least once per Gamma *sotopic analysis. of each.

Bottom days. sample.

Sediments 50123-ODCM 5-4 :Revision O

ý02-27-07

TABLE 5-i (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Sample and Sample Locationsa -Col 1ection Frequency -Type and Frequency of Analyses

4. INGESTION

a. Nonmigratory 3 locations One samplein season, ;,Gamma isotopic analysits on Marine or-at l~east once per edible portions.

Animals 184 days if not. --

seasonal. Onesample of each of the follow-ing species:

I.. Fish-2".adult species such as-:perch or sheephead. . a

2. Crustaceae-such'as crab or lobster.

3. Mollusks-such as-limpets,.seahares or clams.

Representative iGamma isotopic .analysis .inedibl on e

b. Local Crops 2 locations vegetables,,.normally portions semiannually and 1-131 1 leafy and-l fleshy analysis for leafy cýro#ps,.*

collected at harvest time. At l-east.2 ,

vegetables collected semi annual I y from each location.

I*S0123-ODCM 5-5 iRevisi~on 0 02-_21-0

TABLE 5-1 (Continued)

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. establi~shl',control locations in accordance with the distance and wind direction criteria, other sites which providelvalid background data may be-substituted.

d. Canisters for the collection of--radio-iodine in air are subject, to channeling; These devices should'be.

carefully checked before operation in the field or several shoul.d 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 .usedin piace of, or in.-addition to, -integrating-Z.

dosimeters. For the purpose of this table, a thermoluminescent dosimeter maytbe considered to. be-bfone phosphor and two or more phosphors in a packet may be considered as two or-more dosimeters. Film badges Shouldmnot be used for measuring direct radiation..

f. Composite samples should be collected with equipment (or equivalent) which'is. capable of coll-ecti-ng:*an*.al iquot 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.

S0123-ODCM 5-6 :Revision 0 02727-07

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/mr3 ) (pCi/Kg, wet) (pCi/Kg,..wet)

H-3 2 x 104(a)

Mn-54 1 x 10'. 3 x 104.

Fe-59 4 x 102 1 x i04 Co-58 I x 1.03 3 x 104 Co-60 3 x 10: 1 x 10' Zn-65 3 x 102 2 x 104 Zr-95, Nb-95 4 x 102 1-131 2 (b) 0.9 1x 102 Cs-134 30. 10 1 x .103 lx 10 3 Cs-137 50 20 2 x 103, 2 x i0 Ba-140, La-140 2 x 102 (a) For drinking water samples. This is 40 CFR Part 141 value. If no..dri.nking water pathway;iiexists, a (b) value of 30!000 pCi /lI may be used.

If no drinking water pathway exists, a value of 20 pCi/l may beused.

'SO123-ODCM 5-7 ýRevision

.02,"27-07 0

TABLE 5-3 DETECTION CAPABILITIES. FOR ENVIRONMENTAL SAMPLE ANALY.SISc 8

MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)

Airborne Particulate Water or Gases Marine Animal.s Local,Crops Sediment-.

Analysis (pCi/l) (pCi/m 3) (pCi/Kg, wet) (pCi*Kg, wet) (pCi/.Kg- dry.).*

gross. beta 4 1 x I0-T H-3. 2000)b, Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95. Nb-95 15 1-131 1 (d) 7 x 10-7 60 Cs-134 15 .5 x 10.' 130 -60 150 Cs-137 18 6 x 10-2 150 80 180 Ba-140, La-140 15,:

SO123-ODCM 5-8 -Rev4si~on 0

.02-27-07

TABLE 5-3 (Continued)

TABLE NOTATION

a. The LLD ýis the :smallest concentration of radioactive materi al in a sampl e that will"bedetected wi th 95 robabilitywith 5%,probabilIIty* of f al sely concluding that a blank observation represents a "real" signal.

For a particular measuremenht system (which may include radichemical separation):

LLD= 4.66 sb E V

2.22 x 106 , Y exp (-Žmt) where:

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

is the standard deviation of' the.background counting ,rate or of the counting rate ofýýa blank'sample as appropriate. (as counts per minute),

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

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

2.22 x 206 is the number of transformations per minute per mi crocuri e, 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 st used in the calculation of the LLD for a datection system shall be based on the actual observed Variance of the background countin.g rate or of the cbunting rate of the blank samples (as. appropriate) rather than onan unverifiedý theoretica liyVpredicted 'variance.1'n:I calculating. ýthe, LLD for a radionuclide determined by.gamma-ray Spectrometry, the, background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). Typical values of E,V,Y and At shall be used ,in the calculations.

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

"'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).

S0123-ODCM 5-9 Revision 0 02-27-07

TABLE 5-3 (Continued)

TABLE NOTATION bk If.n6 d*riki ng water pathway .exists, a value. of 3000 pCi/ may e .use.d.

c. Other peaks which :are measurable and identi fiable, togetiherwith the radionuclides in Table 5-3, shall be identified and. repiorted.

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

S0123-ODCM 5-10 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.2, LAND USE CENSUS SPECIFICATION A land use .ensus shaI be conducted and shall identify the 5.2,.1 resi dence l ocati On , of :'the nearest: milk animal, the nearest:

and the nearest 'garden* of greater than 500 square feet producing fresh leafy.vegetab.les 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 yi eid .a calculateddose, or'. dose. commitment greaterý: than

ýthel values cuirrently being c~alc.ulated Spec;i.fic atii*on S:in 2.3.1, pursuantto Techni cal Specification 5.7.1,. identify the new locations in thelnext'Annual Radioactive Effluent gelease Report.

b. 'With the land use census. identifying aj locati6n ('s). 'that:

yields a ca lculated dose or dose "commi tment: (via the same exposure pathWay). 2O(.percent gr*eat6. 'than at' a location from. whi ch .sampl es, are_: currently beoing obtaihned in.;:

accordance ,with Specification 5.1, .add the" new location within 30.days, to the Radiological Environmenta:l Monitoring Program given in the ODCM. The sampling location(s),

excl uding the control station :location,_ having same the, lowest cal culated, dose or dose commitment(s) via the exposure Pathway, 'may be deleted- from this monitoring program after October 31, 'of the year in whikh 'this Land Use Census. was conducted.- Pursuant to Technical Specification 5.7.1, submit in the".next Annual Radioactive Effluent including Release Reportdocum'entation ,fr a change in "the'ODCM a revi sed ffigure(s) and table(s)ý or the ODCM reflecting the new location(s) with information supporting the change in sampling locati ons.

SURVEILLANCE REQUIREMENTS:

per 12 months

.1 The land use census shall be conducted at least once that information between the, dates of June 1 and October 1 using which will provide the best. results, such as by a door-to-.door survey, aerial survey, or by consulting local agriculture authorities.

boundary in the

Broad leaf vegetation sampling may be performed at the site census.

direction sector With the highest D/Q in lieu of the garden S0123-ODCM 5-11 Revision 0

02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONrTORING (Continued) 5.3 INTERLABORATORY COMPAR:SON PROGRAM SPEC.1FICATI Anialyses shall be: performed on radioactive miater.a.i s 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 Commissionin the Annual. Radiological, Envi.ronmental

Operating Report.

SURVEILLANCE REQUIREMENTS

.1 A.,summary' of -the. results obtained :aspart of the, above required.

Interlaboratory Comparison Program and in accordance withK Section 5.4.1 of this document shall be included in theAnnual Radiological Environmental Operating Report .(see Section 5.4).

S0123-ODCM 5-12 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued.)

5.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*"

5..1 The -1'r d'l oil eviomnlý'prati ng reports 5.. 'annuaraogc niomnaoe

'd"e I alinc sum-maries," inte*r e*r,-,preT ations,, and 'a an.

...-1 11

. is of :trenids of the' result sfof the radiol ogijcal en'vironmental.

surveillance activtti e for, the report perio'd including a.

comparison with preoperational studies, op0rational cntrols, (as appropriate), and previous, environmental survei 11 ance reports and an.assessment of. theobserved impacts of the plant, oerati6n. On.:the' envi ronment._The reports shall aiso 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 plann'ed course, f action- to, all evi ate, the%problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the Radiological Assessment Branch Technical Position, Revisions 1, Novemberý.1979"o-f all: .radiological environmental samples taken- during the' report period.; In the event' that' some results are, not available foriiclusi on with' he report the .repdrt' shall1 be 'submitted noti ng and 'explai ni ng the i'easons. for the missing results, The mimssipng, data shal.l be submitted as soon ýas possible, in a, supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; apmap of all sampling locations keyed to aitable 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.

S0123-ODCM 5-13 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.5 SAMPLE LOCATIONS The Radiological Environmental Monitor ing Sample Locations are identified in Figures 5-1 'throuigh'5-5;. These sample locations are, described in Tabl e 54,and,,in i-cate. the distance in miles' and the directIio, 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.

SO123-ODCM 5-14 Revision 0 02-27-07

Page 1 of 6 TABLE 5-4 RADiOLOGICAL ENVIRONMENTAL MONITORING. SAMPLE'. LOCATIONS DISTANCE*

TYPE OF SAMPLE AND SAMPLING -LOCATION*** (miles) DIRECTION*.

Direct Radiation I City of San Clemente (Former SDG&E Offices) 5.7 NW 2 Camp San Mateo (MCB, Camp Pendleton) 3.6 N 3 Camp San Onofre, (MCB, Camp Pendleton) 2.8 :NE 4 t.Camp- Hprno',(MCBj. Camp Pendleton),4.E.E 6 Old ElCamino Real (A ld, Ro ute 101) 3.0 ESE B. 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 Deleted 18 Deleted -

19 San Clemente Highlands 4.9 NNW 22 Former U.S. Coast Guard Station - San Mateo Point 2.7 WNW 23 SDG&E Service Center Yard 8.1 NW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

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

MCB - Marine Corps Base PIC - Pressurized Ion Chamber S0123-ODCM 5-15 Revision 2 02-27-09

Page 2 of 6 TABLE 5-4, RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLEt LOCATIOLS DISTANCE*

TYPE OF. SAMPLE AND SAMPLING LOCATION*** fmi1es) DIRECTION*,

Direct Radiation (Continued) 31 Aurora Park-Mission Viejo 18.6 NNW 33 Camp Talega (MCB, Camp Pendleton) 5.9 N 1.9 NW 34 San Onofre School (MCB, Camp Pendleton) 35 Range 312 (MCB, Camp Pendleton) 4.8 NNE

36. Range 208C. (MCB, CPamp Pendleton). 4.11: NE 38 San Onofre State Beach Park 3.4 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 1.0 SE SE 47 Camp Las Flores (MCB, Camp Pendleton) 8.6 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 S0123-ODCM 5-16 Revision 2 02-27-09

Page. 3 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE* .

TYPE SAMPLE AND SAMPLTNG LQCAT P0F TION;. .. Jmi es) DTRECTION*

Direct Radiation (Continued)

Camp Chappo..(MCB, Camp Pendl-eton) 12.9" ESE 49 50 Oceanside Fi re Station (CONTROL) 15.6 SE.

53 Sai Diego County Operations Center 44.2 SE..

54 Escondido Fire Station 31.8 ESE 55 San Onofre State Beach (Unit 1, West) 0.2** WNW 56 San Onofre State Beach (Unit 1, West) 0.2** W

57. San, Onofre State Beach (Unit 2) O.1* SW.

5.8 San Onofre State Beach (Unit 3),O1i 59 SONGS Meteorological Tower 0.3** WNW 60 -Deleted

'61 Mesa - East Boundary (Adjacent to PIC #4) 0.7 N 62 MCB - Camp Pendleton (Adjacent to PIC #5) 0.7 NNE 6.3. MCB- Camp Pendleton (Adjacent to'PC#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) 4.4 ENE 73 South Yard Facility 0.4"* ESE Del eted Deleted Del eted 75 Gate 25 MCB 4.6 SE 76 El Camino Real Mobil Station 4.6 NW 77 Area 62 Heavy lift pad 4.2 N 78 Horno Canyon (AKA 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 S0123-ODCM 5-17 Revision 2 02-27 -09

Page 4: of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS TYPE OF SAMPLE"AND SAMPLING LOCATION "i es): --

Airborne.

1 City of San Clemente (City Hall) 5.1 NW 7 AWS Roof ,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 Del eted -

15 Oceanside City Hall (CONTROL) 15.6 SE So.l . Samplest I Camp' San Onofre . 2.8 NE/"

3.0 ESE 2 Old Route 101 . (East Southeast) 3 Basilone Road/I-5 Freeway Offramp 2.0* NW 5 Former Visitor's Center 0.4** NW 6 Deleted - N -

7 Prince of Peace Abbey (CONTROL) 15 SE f, Ocean Water A Station Discharge Outfall - Unit 1 0.6 SW B Outfall - Unit 2 1.5 SW C Outfal.l Unit 3 1.2 SSW D Newport Beach (CONTROL). 30.0 NW

Distance (miles) and Direction (sector) are measured relative toUnits 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.

Soil Samples are not required by Technical Specifications.

I0123-ODCM 5-18 Revision 2 02-27-09

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

...-. , DISTANCEt TYPE OFý SAMPLE AND, SAMPLING LOCATION ýDIRECTION*.

Dri nking Water 4 "Camp Pendleton Drinking Water Reservoir 2.1 NW 15.6 SE 5 Oceanside City Hall (new CONTROL)

Shoreline Sediment (Beach Sand) 1 San Onofre State Beach (Southeast) 0.6 SE 2 San .Onofre":Surfing Beach. 0.8 WNW 4 San OnofreStateN Be chE(So CutheastR) 3..5 SE 4 Newport Beach (North End) (CONTROL) 29.2 NW Local, rCrops'

1. Delet'ed. .1p 2 Oceanside (CONTROL)** 15 to, 25 SE to ESE 4 San dClemente Resident w/Garden 4.4 NW 6 SONGSIGarden" 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, 15to 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.

S0123-ODCM 5-19 Revision 2 02-27-09

TABLE* 5-4 Page 6 of 6 I<"RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS.

DISTANCE*

TYPE, IOF SAMPLE ANDI SAMPLING LOCATION nTPPrTT0N1*

1,6s)nNfli Non-Migratory Marine Animals A _Unit I Outfall 0.9 WSW B Units 2 and 3 Outfall 1.5 SSW C Laguna Beach (CONTROL)** 15 to 150 WNW to NW Kelpl.

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 : :'ý.Sa~l t 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) 17 to 19 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.

- A location more distant from SONGS in the WNW to NW direction may be used as the CONTROL location.

t Kelp Samples are not required by Technical Specifications.

S0123-ODCM 5-20 Revision 2 02-27-09

TABLE 5-5 PIC- RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS PRE....E *- Theta D-IsTANCE*

PRESSURIZED ION CHAMBERS (Deqrees)* Meters: miles DIRECTION/SECTOR*

SI San Onofre Beach 2986 1060 0.7 WNW P S2 SONGS Former. Evap. Pnd 313' 890 0.6 NW Q S3 Japanese Mesa 3400 1200- 0.7 NNW R S4 MCB - Camp Pendleton 30 1130 0.7 N A S5 MCB- Camp Pendleton 190 1080 0.7 NNE B S6 MCB-,Camp Pendleton 460 970. 0.6 NE C S7 MCB - Camp Pendleton 70" 960 0.6 ENE D S8 MCB - Camp Pendleton 980 1130 0.7 E E

$9 San Onofre State Beach 121° 920 . 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.

S0123-ODCM 5-21 Revision 2 02-27-09

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

DEGREES TRUE. NORTH FROM, SONGS 2 AND.3 MID-POINT NOMENCLATURE::

Sector Center Sector 22.5° .

Limit Line Limit Sector* Direction 348.75 0 & 360 11.25 A N 11.25 22.5 33.75 B NNE 33.75 45.0 56.25 C NE 56.25 67.5 78.75 D ENE 78.75 90.0 101'.2" E2 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 3 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.

S0123-ODCM 5-22 Revision 0 02-27-07

Figure 5-1 Radiological Environmental Monitoring Sample Locations' 1 Mile Radius

.. ~~r-, ~ Sedtor R Sco

" S tor ..... NNW

~.' ~NW ~ ~ *4 Sector B REMP

.. o

+.........

8 i:: .

One-

S*F*:*+* ** *ii=*'.;+:-;..Se.ctor E

-;ri !::-N 'Z r-*-.' tE*i:*

Ti,::::"..!-*~*

"Af;*

!I-:*t 13 M ~ tP WX s'S .'M

-i.7 :::p * *

*** : .:*!: ;* .: -; * .: '.-: .:* :ie : :.: * *:'* '!i,!= + : '.:.:* : E**

i*,.*+!.2:.* i~

~ ~ H ~ *.=**+*

~ ......... ~~V2-.. O.b-i:¢...**-: T...:*etr or 125"-4DCM

`P-

,:.S i*.. Ak a *;:m

. l-As-1 . ..gth 5-23 ... r,41A.... ., .... . LI) :

S*R-orv,:-"

ENE-,-. ,.

. . "+F* ,,**" r:S EC- :

....... ..... A I,;-*;"**;.* :. ;,.,..;,,*,

4,:+,:*

no :::~ ;3:oC 5ro23 ,[Fri-iion:

25 oii

-Po

Figure 5-2 Radiological Environmental Monitoring Sample Locations 2 Mile Radius S01238ODCM 5-24 ReVi1siOn02 02-27-09

Figure 5-3 Radi ol ogi Cal Envi ronmental Monitori H ng Sampl 0- Locati on's 5- Mil eiRadius SSO12 3-ODCM 5-25 -Revsi*o 2

.02-271-09

Radi ologfical EnvirPonmental ~~FigureMo~itoring 5:-4 .

Sample. Locations -Orange* County .

P1 9 x .

IF,

--... .....- Sector A )):

Son O nofre RE AP - ;., ,.--,; i:. " "" .- ;

Unil2r 30 N~ortht int;

.~~

W!

~~~~~~~~~ ~~~~

2-,:;*;.:,

........ =-~~F*

M*;* p-ci * *;:* i gni... M.Ao ..... .... .... ..... .,. ......

Qpiato ýar G tfine ( iS A P;i* l 2F W IL 2I. IrD 3 ILI 26 TLD "L Re35:i n U.025X, t.0

Figure 5-5 Radiological Environmental Monitoring Sample Locations,- San Diego County S0123ODCM 5-27 -ReVis.ion. 2 02727-09

6.0 ADMINISTRATIVE 6.."1 DEFINNI TIONS-The,*eflined terms of this section appear fin,; captal ized type and are appli-dable. throug h ithespecise ficat ins.

ACTI ON 6.1.1 ACTION shall be that part of 8 specification Which prescribes remedial measures required under designated.

condi tions.

CHANNEL CALIBRATION 6.1.2, A{CHANNEL CALIBRATION shall ,be the adjustment, as

,ecessary,--of the6channel output such that "it responds with. the n.ecessary rangeand." accuracy to .known Value of the parameter which the channelimonitors. LThe CHANNEL CALIBRATION shall encompass the entirechannel, 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 oCf!f sequential, overlapping -or total channel steps such'that the entire channel is calibrated.

CHANNEL CHECK 6.1.3 AkCHANNEL CHECK shall be the qualitative assessment of channel behavior during operation, by observation. This determinati oh shall incl ude, 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 tothe sensor as .practicable 1to verifyVOpERABILITY, including alarm and/or trip functi ons.

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.

SO123-ODCM 6-1 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued)

DOSE EOUIVALENT.I.-131 6P. OSE. EQUIVALENT -131e' sh ll thýat .concentr~at~ion of 1-131

.:(ricrocuri es/gram) which al one',woud pidodulci eh(ame thyroid dose as .the quantity: and isotopic: mi xturre of -I 131',. 1-132, 1-133, I-134, and 1-135 actually preSent. The thyroid dose conversion factors used for this calculation shall be those.listed In International Commission on Radiological..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 ýspecified for the per.formance. of Survei 11 ance Requi rement§ 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 efflu6ents 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.

MEMBERS OF THE PUBLIC 6.1.8 MEMBER(S) OF THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant. This category complies with the requirements of IOCFR50Qand shall include non-employees of the licensee who are permitted to use portions of the tite for recreational, occupational, .or purposes not associated :with plant functions..

Suppl emlentali.'wor*kers and, thei rý dependents ..are included in this defini.tion while they. temporarily reside at. Camp Mesa. This category shall not include non-empioyees 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 pu.rposes ofprotection of individuals from exposure to radiation and radioactive material s.

S0123-ODCM 6-2, Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continuedd)

MODE 6.1. .. ,.I n si ve c o'mb 1.na t i on.

A ýMODEz- shalIl co r r espo nd t o any, one iclU of core, reacti~vi ty conditi6Tij powe leel aIeaeeco c01o:ant temperature', and reactor vessel head' cl osurejobpl t ten'sioni ng specified in Table: 6-1 with fuel' in the reactor vessel.

OPERABLE - OPERABRLITY 6.1.10 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified qfunction.(s),. and when al 1, necessary attendant instrumentation, controlsi, normal or emergency, el.ectri cal power, cooi] ing and: seal: water, lubri-zation Ihand `othef.:'auqki li ary.' equi pment thath ar.e required, for:thee system, subsystem, trai-a,"component or

.device" to perform its ffunctioh"(s.) are also cap'able of performing their related support function(s).>

PURGE - PURGING 6.1.11 PURGE or PURGING is the controlled process of discharging.

-air or gas from a confinement -to, maintain temperature, pressure., humidity, concentration or other operating condition, in such a manner.that. replacement air orgas is required to purify the confinement.

SITE BOUNDARY 6.1.12 The SITE BOUNDARY shall be that line beyond' whi.ch the land is not owned, leased, or otherwise controlled by the licensee.

SOLIDIFICATION 6.1.13 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly di*stributed),',.monolithii iimmobilized solid with- definite volume and.shape, bounded bya' stable surface of distinct outline on all sides (free-standing)..

S0123-ODCM 6-3 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued)

SOURCE CHECK For Victoreen and NMC analog monit'ors, a SOURCE CHECK

-6.1.14 of chan*iel response shall] bet he qualtative as~sessment a radioactive when the, channel sensor is.exposed to 2 (3,)RT-7818A]

source6 [2:(3),RT-6753, '.2 (3) RT-6759,1 a SOURCE CHECK For Sorrento Electronics digital monitors response to a Shall be the verification..ofproper computer check source request. [2(3)RT-7'B28, 2(3)RT-7865,l, 2 (3) RT-78704 ]

For, MGPI monitors a SOURCE CHECK shall be the verification internal:,

ofproper computer respo detectojr 5 monitor. calibration and electrical, checks.

[2 (3)ý RTý-.7 8117, 2(3) RT-7821, 2/3RT-ý7813`- 2/3RT-7808, RT2101]"

SURVEILLANCE REQUIREMENT: MEETING SPECIFIED FREQUENCY if the:

6.1.15,: Thespecified Frequency:for each SR is meA the interval Surveillance is perforirmed'within'1.125 times from the previous specified in the Frequency, as measured, a'specified performance or as measured from the time condit*ion of the :Frequency" ismetl.

interval For Frequencies specified as "once," the above extension does not apply.

If a Completion Time requires periodic performance on a "once per .:;." basis, the above Frequency extension performance.

applies to'each performance after the initiatl repeatedly as a This provision is not intended to be used beyond surveillance intervals convenient meabns to extend does not apply to any.

those specified. Additionall', it Action Statements.

THERMAL POWER core heat 6.1.16 THERMAL POWER shall be the total reactor transfer rate to the reactor coolant.

VENTILATION.EXHAUST TREATMENT SYSTEM any system 6.1.17 A.VENTILATION EXHAUST TREATMENT SYSTEM is or to reduce gaseous radioiodine designed and installed in effluents by radioactive material in particulate form through charcoal passing ventilatioh or vent exhaUst. gases of removing absorbers and/or HEPA filters for the purpose exhaust stream iodines or particulates from the gaseous to the environment (such,a system is prior to the release gas effluents).

not considered to have any effect on noble cleanup Engineered Safety Feature (ESF) atmospheric EXHAUST systems are not considered to be VENTILATION TREATMENT SYSTEM components.

S0123-ODCM 6-4 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued)

VEFNT ING 6.1.18Q i or VETIGis the 'Contrle processt, of, di~schar~n

,gasfron a co'nfineme'n'et' to maithain tempera.tur; .pre~ssure, hu'Mi dity conceintration or ot'her'operatingý conditio, n such a manner that repl:66eme'in air or'. gas is not provided orIrequired during'VENTING.. Vent used in system names

.does not imply a VENTING process.

SO12.3-ODCM 6-5 Revision 0 02-27-07

TABLE 56-1 OPERATIONAL.MODES ..

AV.ERAGE, COOLANT REACTIVITY 0 RATED' OF OPERATION MODE CONDITION. (Keffi THERMAL POWER(a)

TEMPERATURE" (F).

1. POWER OPERATION >0.99 > 5% NA

2. STARTUP > 0.99 < 5% NA

3. HOT STANDBY < 0.99 NA > 350°F

4. HOT SHUTDOWN < 0.99 NA 350'F> T ,q>200°F

-5. COLD. SHUTDOWN (b) < 0.99 NA < 200OF

6. REFUELING (c) NA 'NA:'.

(a) Excluding decay heat.

All reactor vessel head closure bolts fully tensioned.

(c One or more reactor vessel head closure bolts less than fully tensioned.

.S0123-ODCM 6-6 Revision 0 02-27-07

TABLE 6-2 FREQUENCY NOTATION FREO*ENCY.

NOTATION hours 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 days W At least once per 7 days M At least once per 31 days Q At least once per 92 At least once per 184'days SA months*

R At least once per 18 startup Prior to each reactor S/U release P Completed prior to each*

N.A. Not applicable Not to exceed 24 months Refueling Interval a 31-day period.

A month is defined as S0123-ODCM Revision 0 6-7 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.2 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE. EFFLUENT RELEASE REPORT*

covering the.

6 .2.1 Routine* radioactive effluent release, reportsý cal endar year, operaton -of. the unit during theprevius shall be. 'submitted before May 1 of eachyeari.

include a 6.2.2 The radioactive effluent release reports shall summary of the quantities of radioactive, liquid'and: romthe unit gaseous effluents and solid waste released, as outlined in Regulatory Guide 1.1, "Measuring, Solid Wastes Evaluating, and Reporting Radioactivity-inLiquid and and Releases of. Radioactive.Materials in Nuclear Power Gaseous Effluents from 'Light-Wa.er-Cooled data summarized. on a Plants;, ."Revi si on I*1,June 1974,,with B thre.basis following the format

.... of:.Appendix include an The radioactive effluent rel ease report shall data collected annual summary of hourly meteorological over the previous year. This annual summary may' be -either wind speed;s wind in the form of-an hour-by-hour listing of precipitation "

direction,. and atmospheric stability, and, form of.joint (if' measured) on magnetic tape;' or in the direction,ý and frequency'di.stributions of wind speed, wind shall1: iniclUde an atmospheric stability. This' same report the' radioactive-assessment of the radiation doses due. to the. unit or liquid and gaseous effluents released from This 'same station during the previous calendar year., the. radiation report shal.l also include, an assessment. of effluents to doses from radioactive, liquid and gaseous inside the MEMBERS OF THE PUBLIC due to their activities the' report SITE BOUNDARY (Figure 1-2 and 2-2)'during assessments period. .All assumptions used in making these and location)

(i.e.,. specific activity, exposure time meteorological shall be included in these reports, The of conditions concurrent with the time of release (as determined radioactive materials.in gaseous: effluents' be used' for by sampling frequency and measurement) shall pathway.-doses* i, The assessment:.of deter'nining',the* gaseous'. the radiation doses shall be performed.in"'acco'rdance'wi'th OFFSITE DOSE CALCULATION MANUAL (ODCM).

sections station. The submittal should combine those

A single submittal.may be made for a multiple.unit systems, the however, for units with separate radwaste that are common to all units at the Station; from each unit.

the releases of radioactive material submittal shall specify S0123-ODCM 6-8 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Cont inued) 6.2 ADMINISTRATIVE CONTROLS (Continued) 6.2-.2 (Contihnued)

The radioactiveofeffl luent reiease .report shall "aso i*clude an .assessment radiation doses tO" the -i:i kely most.

and

exposed MEMBER OF THE. PUBLIC from reactor releases ng doses other nearby uranium fuel cycle6,sourcesD(includi "for' diect-from primary effluent pathways, and to show conformanceradiation) the previous 12 consecutive months with 40 CFR 190, Environmental. Radiation Protection methods Standards 'for Nuclear Power Operation. from Acceptable for calculating the dose contribution liquid and Guide 1.109, gaseous effluents are, given. in Regulatory Rev. I.

the ,,,-

The ýrýdioactive effl*uents rlease shall include Wol id" .waste shipped following information forý 'each type of 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 Quaintity), and

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

include The radioactive effluent release report shall areas of.

unplanned releases from the site to unrestricted and liquid effluents made radioactive materials in gaseous during the 'reporting ,period.'

include any The radioactive effluent release reports shallmade during changes to the PROCESS CONTROL PROGRAM (PCP) the reporting period.

S0123-ODCM 6-9 Revision 0 02-27-07

6.0 ADMINISTRATIVE( (Continued)

SYSTEMS (Liquid, &

6.3 .MAJOR CHANGES TO RADIOACTIVE WASTE. TREATMENT Gaseous)

Lilcensee iJnitiated rajor changes t6 te r~adioacti vE, aste

.syste (liquid &t gaseous):'.

Radioactive

1. Shall be reported to the Commi ssion in the Annual eValuatibn Effluent-Release Report .for the period in which.the' Program, Description was performed pursuant to Quality Assurance (SCE-1-A)," Subsection 17,.2.20.3.1.i, The discussion of each change'shail contain:

A summary of. theevaluation that led to the with determination a.

that the change. could be'made in accordance applicable P .regulations;

b. Suffici~nt' detaileOd ihformnation to totally tuppoirt the" reason for' the change without benefit of additional or supplemental information; and

c. A.detailed descriptl On of the equipment, components with other' plant, processes involved-and the interfaces systems,;

d. An evaluation. of the change which shows the predicted gaseous.

releases of radioactive materials in.liquid and in effluents that differ'from those previously predicted.

the license application and amendments thereto;'

e. An evaluation of the change which shows the expected area maximum exposures to individual in the unrestricted those and *to the general popul ati on that .differ.. f rom -and previously estimated in the license application amendments thereto;

f. A comparison of the predicted releases of radioactive actual materials,. in liquid and gaseous effluents to the are to be release for the -period prior *to when the changes made;.'.

personnel.

g. An estimate of -the exposure to plant operating as a result of the change; and reviewed and

h. Documentation of the fact that the change was Program found acceptable 'pursuant to Qual.ity -Assurance Description (SCE-I-A), Subsection 17.2.20.3.1.i.

pursuant to

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

S0123-ODCM 6-10 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES LI1UTO EFFLUENTS, CONCENTRATION (-1 . 1) 6.4.1 This specification is provided to ensure that the concentration Of radioactive materials released in liquid waste effluents from the'.site will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, 'Table Il,.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 I',A design objectives of: Appendix I',1_O CFR 50, to an individual:, and (2)the limits of, 10 CFR "20.106(e)". to the populati on.The concentratfon limit for dissolved or entrained 'noble gases is basedupon 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 specificati on is provided. to implement.'the require-ments of Section II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section. II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time, implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as, is reasonably.

achievable.". The dose'calculations *in 'the ODCM. implement the requirements in Section, I,'I.A of Appendix' I that conformance with'the guides of Appendix I be shown by calculational procedures based on models and data,.such thatý. the" alctual', expos.ure of., 'an.1 nindividu al .thKrou .gh':

appropriate pathWays is' un~ik&I tbbesubstantially underestimated. The equations specified in the ODCM for-dalculating .the doses due to the actual release rates of radioactive materials in liquid effluents are consistent

'with the methodology provided' .,inRegulatoryIGuide'll.109, "Calculation of Annual Doses to Man fromRoutine. 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 Implementirg 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.

)

S0123-ODCM Revision 0 6-11 02-27-07

6.0 ADMINISTRATIVE (Continued).

.4 BASES '(Continued)!

LIOUTO WASTE.TREATMENT(13

,system 6.4.3 The "OPEABIIITY of -thezI liquid, radwaste treatment be avail ab, for.use

,ensures that ,this system.will ment* prior to whenever'] iquid ef fluents. reequire ; treat that'the' release 'to,the envi ronment-." The requirement of -this system be 'used when' specified appropri ate portions of.raditoactiv.e.

provides ass'ran e..that the -el eases

'l 6 w. as. is.

materials. in.liquid.d effl uents will be kept "as implements the reasonably achievable.1 Th.is specification, General Design:

requirements of:10'CFR Parlt 50.36a, Criterion. 60 of Appendix A to 10 C'.R Part 50 and. the.

to-'10 design objective given in Section I.D of' Appendixk.

CFR ..Part%: 50... ',. The. speci fied limi-ts *governing: the use of appropriate portions of-the'liqui dadriastetreatmentdose' system were specifi~ed as a4 Suitable fractio'.of!-the' Appendix I.,

design objectives set forth in Section 'II.A of 10 CFR Part 50, for liquid-effluents:.

GASEOUS EFFLUENTS DOSE RATE (2.1) 6.4.4 This specification is proVided from t.oensure that the dose at

'any.,time.at the site boundary 'gaseous"effluents.from dose all' units on' the sitet Will be. within the annual areas. The limits of 10 CFR Part 20 for unrestricted are the doses associated with the annual dose limits Table II, concentrations of 10 CFR Part 20, Appendix B, -that reasonable assurance Column 1. These limits provide effluents will radioactive material discharged in gaseous in an not result in the. exposure.'of.an:individual site unrestricted area, either within-Or outside'the exceeding the boundary, to annual, average concentrations B,' Table II: ofý 10CFR Part 20 limits specified.in Appendix may at times (10 CFR part 20,106(b ))'.'For, individuals who, of the. . .

be.within the site boundary, .the occupancy. any.

individual will be.sufficiently .low .to' compe.nsate:.for i hte a tmi 9sph'e c r',i diffusi~on factor: aboveL that::,

'in.cIreaIse 1' 'relead .rate limits for, the 'site'boundary',, The specifed& gamma and 'beta restrict, at all times, the corresponding at or beyond dose rates above background to an. indiVidual to 500 mrem/year thesite boundary, to less.than or equal to '3000:.

to, the total body or to less than or equal also mrem/Year to the skin`.: These release rate-limits corresponding thyroid dose restrict, at all times,.the inhalation rate above background to a' child via the pathway to less than or equal to 1500 mrem/year.

of gaseous This specification applies to the release site. For units with effluents from all reactors at the systems, the gaseous effluents shared radwaste treatment among the units from the shared system are proportioned sharing that system.

SO123-ODCM Revision 0 6-12 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES. (Continued)

DOSE - NOBLE GASES (2.2)

This, specification. is provided. tooimplement the.,

6.4.5 requirements 'of Sectiohs IIB, III.A an d. IV.A of Appendix I' 10'CFR, Part 5O'..The Limiting Condi ti onforOperation implements the guides set- fofthin. Secti~on .II.B of'.

Appendix: I The ACTION statements provide the r,;equired. the operating flexibility and at "th6e same time implement Ito assure guidesset fort'h in Section IV.A of Appendix that the .releases ofI"iadioactive material 'in gaseous effluents will be kept, "as low as is reasonably achievable."; The. Survei 1l ance Requirements, implement. the

. reui rements, iii' Sectibn" II.A" A:of Appendi - that.

conformance with'the, gudes of Appendix .I be 'Shown by calwcdiatioa'*,rpoedu r.es, based .on models and'd ta such'.

'that.the 'actuial ex posusre /of '. a n individual through appropriate, pathways.is unlikely to besubstant'ial ly The dose calculations established in the ODCM for calculating I the -doses due to theactual elease underestimated.

rates' of radioactiyve, nobl-ezg'aseS 1n gaseous,.effluents are consistent wj.th',: the meth6dology* provided.t* in Re`gulatory Gui de' i"109 *'"Cal-culation Annual Do-ses td of 'Effluents;for from, Manurposefe of oe Routinel~~et Rout in' Releases ea of Reacto'r the; Puri Eval uating' Compliance, with 10 CFR Part" 50,' Appendi x 1,1 Rev i sion', 1. October.1977T and Regulatory Guitde '1.111, "Methods. for 'Estimatin61Atmospheri c ýTranisp'ort,' and Dispersion of Gaseous Effluents in Routi ne" Releases from Light-Water Cooled' Reactors,," Revislon. 1, July.1977. For the,.site individuals :who may at tim'es be' 'Within sufficiently low 'boundary.,

th&'o'ccupancy'of the Iind ivi dual .Will, be to comp~ensate 'for any.incr ,e Iase Iin the-atmospheric diffusion factor' above that for the SITE BOUNDARY. For MEMBERS OF THE 'PUBLIC who trav~erse the SITE BOUNDARY via highway 1-5, the' residency time shall be .considered negligible and :hence the dose ,"0". The ODOM equations prov.ided for' determining.the'air doses at the' SITE BOUNDARY.are based'upon the historical" average'atmospheric conditi ons.

DOSE -RADIOIODINES.1 RADIOACTIVE MATERIALS INPARTICULATE 'FORM AND.

TRITIUM (2.3):

6.4.6 This specification is provided to implement the requirements'of Sections II..C, III.A and -. V.A. of Appendix I, 10 CFR Part 50, The"Limiting Condi:tions' for Ope ratiton are the guides set forth in Section II.C of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section .IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the SO123-ODCM 6-13 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES.(Continued),

requireents in,SectionhI I' o

Ip~n f tht confocmance with th1 gudes.opf Appendix.: Ibe:'shown bY cal~cula ti onIaiITprodedures. baed, on model,.s, nid:data,ý such that the actual `exposure of an individual thrugh ap propriate'pathways is'unlikely, tobe substantially underestimated.. The ODCN 'calculational methods for calculating the doses due to the actual re.lease rates of the subject materials are consistent with the methodol.ogy provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating':Cdmpiian'ce with .10 CFR Part 50, Appendix I,.V Revision 11, October' 1977 6nd Regulatory Guide 1.1114 n and Disp'rsi "Methods, of Gaseous Effluents- inAtmospheric foriEstimating Transport Rouitine 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

.condi'ti ons.,- The release6rate specificationsý.,for radioiodines, radioactive materialsJin particulate form and tritium are dependent on. the existing radionuclide pathways to man, in the unrestricted area. The pathways Whi ch 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 VENTILATIONVEXHAUST TREATMENT SYSTEM ensures that

'the systems will be available, for use whenever gaseous effluents require treatment' prior to release 'to the environment. The requirement that-the appropriate..

portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as 'low as is reasonably 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.

S0123-ODCM 6-14 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued) w(3.,3):

TOTAL, DOSE, 6.4.8 Thi' specifitcation is provided, to meet th dosere;qui res the limitations of 40 CER 190. The specification the preparation and'submittai of a'Special Report whenever. exceed calculated doses from ýplant radioactive effluents sites twice the design objective doses ofAppe~ndix.I, Foarthat..

containing up to 4 reactors, it is highly. unlikely. exceed.

the resultant dose to a member of the public willreactors the dose limits of .40 CFR 190 if the individual he..

remain within the reporting,*regu.irementýlevel.,T,,

Special Report will, describe a course oftaction.,-which.. .of the, should"re'sult in the limitation of dose to aimembei 190; with in t heý 40 CFRM public 'for 12 .consecutive. monthsto.. Report, it- may be limits. 'For, the purposes of 'the Special assumed that theddse 'commitment to the memberisofthe public from other:uranium fuel cycle sources,.

negligible, with the exception that dose ..contributions"' Isame site from other. nuclear-fuel 6ycle facilities '.at.the'

-or within a" radius of . of 5 'miles must be considered. 'If the dose to any member of the public is estimated, to exceed the requirements 40 CFR 1190, the Special Report with 'a request for a.

variancein accordance'with the provisions of 40 CFR, 190.11, is considered to be a timely request andfulifills is the. requirements of 40 CFR 190 until NRC staff actionin completed provided the release conditions resulting, violation of 40 CFR 190 have 'not already 'been corrected, An individual is not consi'dered a member of the publicl carrying during any period in which he/she is engaged in fuel cycle.

out any operation which i* part of the nuclear RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION (4J1) 6.4.9. The radioactive liquid effluent instrumentationis.

provided' to monitor' and control .'at,in appli'c6bl'e," the.:

releases' of radioactive materials liquideffluents during actual or potential releases of 'liquid effluents. be The alarm/trip setpoints for these instruments shall,ODCM the calculated .in accordance with the procedures, ino '

to ensure -that the alarm/trip will occur ýpiorp exceeding the limits of 10 CFR Part 20. The OPERABILITY the and use of this instrumentation is consistent with 64 of requirements of General Design Criteria 60, 63 and Appendix A to 10 CFR Part 50.

S0123-ODCM 6-15 Revision 0 02-27-07

6.0 ADMINISTRATIVE .(Continued) 6,4 . (Continued)

RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION (4,.2) 6.4.10 The raadioactiJve gaseous effluent ins'trumentation is, provided to 'moni tor and control, as appliaa6blee'the relqeases of radioactive materials in gaseous. effi1uents during actual or potential releases of. gaseous effluents.

The alarm/trip setpo'ints 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-ti on also inc'ludes. provsions for monitoring. andý,

controlling' the concentrationsof .potentiallS' explosive

,gas mixtures in {he: waste'gtas" hoIdup:.system. The,.

OPERABILITY7a'nd use ýof' this,:jinstrumentationis`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 ofradiation. and of radioactive materials in:those exposure pathways"and for those radionuclides,"whic.h:,lead to the highest potential radiation exposures of individuals 'resulti ng 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 pathwaysi 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 detectioncapabilities required byTable 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 pori (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.

S0123-ODCM 6-16 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BAE (Continued)

LAND USE CENSUS (5.2),

n 6.:4. 12" This specification i s. provi ded to ensure that changesi AREAS :are identi-fied an ifd t-hat.,

.the use of UNRESTRICTED nmodifications-to the monitoirg program are mad survey required by the results of this census. Thebest.

information from the door-to-door, aerial or consulting, used., This with local agricultural. authorities shall be census satisfies the. requirements of Section IV.B.3 of

50. Restricting the census to Appendix I to 10 CFR Part assurance

,gardens of greater than.500 square-feet, provides:

Sthat'significant exposure pathways, via .leafy.vegetables will be6 id~ntified ahd ,monitored- si~ncea,'grden, of this size i1s miniimum,,.req'uiredt-o' ,the t pro uce ý,te ýquantity (26 kg/year): of leafy vegetables aissumed ?in Regul atory:

this Guide 1.109 for c6nsumpti,on. by a child. To determine, used, following assumptions were minimum garden size, the leaf 1), ,that 20-% of the garden. was used for growing broadand vegetation (i..e. , simi lar to. Iettuce" and cabbage),

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 matrices of radioactive material in environmental sample for as part of the.quality assurance program are performed that-the environmental monitoring in order to demonstrate results are reasonably valid.

S0123-ODCM 6-17 Revision 0 02-27-07

ML101240921

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