Text

Annual Radioactive Effluent Release Report - 2004 January - December
	ML051220222
Person / Time
Site:	San Onofre ; (DPR-013, NPF-010, NPF-015)
Issue date:	12/31/2004
From:	Scherer A; Southern California Edison Co
To:	; Document Control Desk, NRC/FSME
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SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2004 January - December

SOUTHERN CALIFORNIA EDISON~

An EDISON INTER.VATIONAL.4 Company PREFACE San Onofre Nuclear Generating Station is located next to San Onofre State Beach, adjoining Camp Pendleton Marine Corps Base, in San Diego County, 64 miles south of Los Angeles, California. There are two operating pressurized water reactors with a total rated capacity of 2254 net megawatts electrical.

Unit 1, rated at 410 net megawatts electrical, was supplied by Westinghouse Electric Company and began commercial operation on January 1, 1968. The unit was permanently shutdown on November 30, 1992.

By August 31, 2004, all fuel was transferred to the Independent Spent Fuel Storage Installation (ISFSI).

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 (75.05%), San Diego Gas and Electric (20%), City of Anaheim (3.16%),

and the City of Riverside (1.79%).

P.O. Box 128 San Clemente. CA 92674-0128 S.O.N.G.S. 1

An.

TABLE OF CONTENTS SECTION A SECTION B SECTION C SECTION D SECTION E SECTION F SECTION G SECTION H

- INTRODUCTION............

- GASEOUS EFFLUENTS..........

- LIQUID EFFLUENTS..........

- PREVIOUS RADIOACTIVE EFFLUENT RELEASE

- RADWASTE SHIPMENTS.........

- APPLICABLE LIMITS..........

- ESTIMATION OF ERROR.........

- 10 CFR 50 APPENDIX I REQUIREMENTS..

RE 1

2 8

PORT ADDENDUM....... 17

.............. 18

.............. 24

.............. 26

.............. 27 AL............ 31 YSTEMS.......... 36

.............. 39

.............. 41 SECTION I - CHANGES TO OFFSITE DOSE CALCULATION MANU SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT S SECTION K - MISCELLANEOUS.............

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

-ii-

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

1.

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

2.

Percent of Applicable Limits

3.

Estimated Total Percent Error

4.

Lower Limit of Detection Concentrations

5.

Batch Release Summaries

6.

Previous Radioactive Effluent Release Report Addendum

7.

Radwaste Shipments

8.

10 CFR 50 Appendix I Requirements

9.

Changes to Offsite Dose Calculation Manual ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

Listed for each of the four categories are:

(1) the total curies released (2) the average release rate (3) the percent of applicable limit (4) the estimated total error As of the fourth quarter of 2004, the noble-gas and iodine source terms no longer exist, and therefore are no longer measured. All the fuel is stored in the ISFSI and the plant is being demolished.

In addition, the particulate category lists the gross alpha radioactivity released for each quarter.

The methodology used to Section F of this report.

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

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

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

fission gases, iodines, and particulates.,

The total radioactivity for each radionuclide is listed for each quarterly period by continuous" 'mode of release.

Plant stack releases are considered to be "continuous" releases.

-As of 8/4/93, "batch" mode releases are no longer conducted because of the permanent shutdown of the reactor. As of the fourth quarter of.2004, the noble gas'and iodine source terms no longer exist, and therefore are no longer measured. All the fuel is stored in the ISFSI and the plant is beingdemolished.

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

Table 1E, "Gaseous Effluents-Radiation Doses at the Site Boundary,-"--provides a quarterly summary of doses at the site boundary for this rep6rt period.-'

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

A. Fission and activation gases

1. Total release Ci

<LLD 2.75E+0 3.00E+1

2. Average release rate for period uCi/sec O.OOE+O 3.50E-1

3. Percent of applicable limit

% MPC O.OOE+O 1.52E-3

4. Percent Effluent Concentration Limit

% ECL O.OOE+O 6.50E-4 B. lodines

1. Total iodine-131 Ci

<LLD

<LLD 1.90E+1

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

3. Percent of applicable limit

% MPC O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit

% ECL O.OOE+O O.OOE+O I C. Particulates

1. Particulates with half-lives >8 days Ci

<LLD

<LLD 1.60E+1

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

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

4. Percent Effluent Concentration Limit

% ECL O.OOE+O O.OOE+O

5. Gross alpha activity Ci

<LLD

<LLD 5.00E+1 D. Tritium

1. Total release Ci

<LLD 2.27E-1 2.50E+1

2. Average release rate for period pCi/sec O.OOE+O 2.89E-2

3. Percent of applicable limit

% MPC O.OOE+O 1.88E-4

4. Percent Effluent Concentration Limit

% ECL O.OOE+O 3.75E-4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

GASEOUS EFFLUENTS-SUMMATIONOF ALL RELEASES Third

Quarter, Fourth Quarter Estimated Total

-Error, %

I Unit A. -Fission and activation gases

1. Total-release

-Ci 1.62E+Q N/A 3.OOE+1

2. Average release rate for period uCi/sec 2.04E-1 N/A

3. Percent of applicable limit MPC 8'.83E-4 N/A

4. Percent Effluent Concentration Limit

% ECL 3.78E-4 N/A B. Iodines

1. Total iodine-131 Ci

<LLD N/A l.90E+1

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

N/A

3..-Percent of applicable limit

% MPC O.OOE+O N/A

4. Percent Effluent Concentration Limit, % ECL O.OOE+O N/A C. Particulates 1.- Particulates with half-lives >8-days Ci 8.O1E-6 1.91E-6 1.60E+1

2. Average release-rate for period-,

-Ci/sec 1.01E-6 2.40E-7

3. Percent of applicable limit

% MPC 2.62E-6 6.25E-7

4. Percent-Effluent Concentration Limit

% ECL 6'.55E-6 1.56E-6

5. Gross alpha activity Ci

<LLD

<LLD 5.00E+1 D. Tritium

1. Total release Ci.

<LLD

-2.50E+1 2.' Average release rate for peri6d

,Ci/sec O.OOE+O O.OOE+O

3. Percent:of applicable limit

% MPC O.OOE+O-O.OOE+O

4. Percent Effluent Concentration Limit

% ECL O.OOE+O O.OOE+O it ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

1. Fission and activation gases krypton-85 Ci

<LLD 2.75E+O 1.62E+O N/A krypton-85m Ci

<LLD

<LLD N/A krypton-87 Ci

<LLD

<LLD N/A krypton-88 Ci

<LLD

<LLD N/A xenon-133 Ci

<LLD

<LLD N/A xenon-133m Ci

<LLD

<LLD N/A xenon-135 Ci

<LLD

<LLD N/A xenon-135m Ci

<LLD

<LLD N/A xenon-138 Ci

<LLD

<LLD N/A Total for period Ci

<LLD 2.75E+O 1.62E+O N/A

2. Iodines.

iodine-131 l

Ci

<LLD

<LLD N/A iodine-133 Ci

<LLD

<LLD N/A iodine-135 l

Ci

<LLD

<LLD N/A Total for period l

Ci

<LLD

<LLD N/A

3. Particulates barium-140 Ci

<LLD

<LLD cerium-141 Ci

<LLD

<LLD cerium-144 Ci

<LLD LLD

<LLD

<LLD cesium-134 Ci

<LLD

<LLD cesium-137 Ci

<LLD

<LLD 8.01E-6 1.91E-6 cobalt-58 Ci

<LLD

<LLD cobalt-60 Ci

<LLD

<LLD iron-59 Ci LLD

<LLD

<LLD lanthanum-140 Ci

<LLD

<LLD manganese-54 Ci

<LLD

<LLD molybdenum-99 Ci

<LLD

<LLD strontium-89 Ci

<LLD

<LLD strontium-90 Ci

<LLD

<LLD zinc-65 Ci

<LLD

<LLD LLD Lower Limit of Detection; see Table 1D.

NOTE:

Due to the permanent shutdown of longer conducted.

S.O.N.G.S. 1, "BATCH MODE" releases are no ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G'.S. 1 TABLE 1D GASEOUS EFFLUENTS-LOWER'LIMIT OF DETECTION CONTINUOUS MODE Radionuclides--l

-LLD (uCi /cc)- ---

1. Fission and activation gases krypton-85 1.50E-5

krypton-85m 3.80E-8 krypton-87.-.

9OE-7-- --

krypton-88 1.40E-7 xenon-133 8.10E-8 xenon-133m 3.10E-7 xenon-135 4.OOE-8 xenon-135m 1.50E-6--

xenon-138 2.60E-6.

2. Iodines iodine-131 220E-13';.

iodine-133 2.10E-12 iodine-135 1.50E-10

3. Particulates

'barium-140

-4.30E-13 cerium-141 5.50E-14 cerium-144 2.20E-13 cesium-134 1.20E-13 cesium-137 1.00E-13 cobalt-58 1.10E-13 cobalt-60 1.80E-13 iron-59 2.80E-13 lanthanum-140 9.OOE-13 manganese-54 1.10E-13 molybdenum-99 6.50E-14 strontium-89

->*;1.OOE-11 strontium-90 1.OOE-11 zinc-65 3.OOE-13

4. alpha 1.'OOE-1i

5. tritium 7.20E-8 NOTE:

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY l

First Quarter Second Quarter I Third Quarter Unit Fourth Quarter A. Noble Gas

1. Gamma Air Dose mrad O.OOE+O 7.19E-6 4.24E-6 O.OOE+O

2. Percent Applicable Limit O.OOE+O 1.44E-4 8.48E-5 O.OOE+O

3. Beta Air Dose mrad O.OOE+O 8.15E-4 4.81E-4 O.OOE+O

4. Percent Applicable Limit a

O.OOE+O 8.15E-3 4.81E-3 O.OOE+O B. Tritium, Iodine, Particulates (at the nearest receptor)

1. Organ Dose mrem O.OOE+O 1.55E-5 3.88E-5 9.24E-6

2. Percent Applicable Limit O.OOE+O 2.06E-4 5.18E-4 1.23E-4 NOTE:

Calculations performed in accordance with the ODCM utilizing the historical X/Q.

TABLE iF GASEOUS EFFLUENTS-BATCH RELEASE

SUMMARY

NOTE:

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 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 t (4) the estimated total error In addition, Table 2A lists:

(1) the gross alpha radioactivity (2) the volume of waste released (prior;todilution)

(3) -the -volume of-dilution water As of--the fourth quarter of 2004, the-noble gas and iodine source -terms no-longer exist, and therefore are no longer measured.

All the fuel is stored in the ISFSI and the plant is being demolished.

The methodology usedto calculate the percentof 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 radioadctivity of each radionuclide released is listed for each quarterly period by both "continuous" and "batch" modes of release. As of the fourth quarter of 2004, the noble gas and iodine source terms no longer exist, and therefore are no longer measured.. All-the fuel is stored in the ISFSI and-the plant is being demolished.

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 dosesat 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:Unitl. i K'

A.-

, i~

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

Unit A. Fission and activation products

1. Total release (not including tritium, gases, alpha)

Ci 1.08E-4 1.91E-5 1.90E+1

2. Average diluted concentration during period yCi/ml 6.52E-11 1.18E-11

3. Percent of applicable limit

% MPC 3.33E-4 5.90E-5

4. Percent Effluent Concentration Limit % ECL 6.53E-3 1.18E-3 B. Tritium

1. Total release Ci 6.50E-3 3.10E-4 1.90E+1

2. Average diluted concentration during period MCi/ml 3.92E-9 1.92E-10

3. Percent of applicable limit

% MPC 1.31E-4 6.38E-6

4. Percent Effluent Concentration Limit % ECL 3.92E-4 1.92E-5 C. Dissolved and entrained gases

1. Total release Ci

<LLD

<LLD 1.90E+1

2. Average diluted concentration during period yCi/ml 0.00+0 0.00+0

3. Percent of applicable limit

% MPC 0.00+0 0.00+0

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

1. Total release Ci

<LD

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

continuous, prior to dilution) liters 4.67E+6 2.18E+5 5.OOE+O F. Volume of dilution water used during period liters 1.66E+9 1.62E+9 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES I

Third -

Quarter Fourth

Quarter, Estimated Total Error, %

Unit A. Fission and activation products

1. Total release (not including tritium, gases, alpha)

Ci 6.10E-6 5.32E-3 1.90E+1

2. Average diluted concentration during period

-- Ci/ml 3.69E-12 1.88E 3. Percent of applicable limit-

% MPC 1.85E-5 8.59E-3

4. Percent Effluent Concentration Limit % ECL 3.69E-4 1.04E-1 B. Tritium

1. Total release Ci 8.17E-5 5.29E-1 1.90E+1

2. Average diluted concentration during period guCi/ml 4.95E-11 1.87E-7

3. Percent of applicable limit

%' MPC 1.65E-6 6.22E-3

4. Percent Effluent ConcentrationLimit

%-ECL 4.95E-6 1.87E-2 C.- Dissolved and entrained gases

1. Total release Ci

<LLD N/A-1.90E+1

2. Average-diluted concentration during period pCi/ml

<LLD N/A

3. Percent of applicable limit -%

MPC-LLD N/A

4. Percent-Effluent Concentration Limit % ECL

<LLD -

N/A -

D. Gross alpha radioactivity

1. Total release Ci

<LLD 1.53E-5 5.OOE+1 E. Volume of waste released (batch &

continuous, prior to dilution) liters 1.10E+5 8.91E+6 5.OOE+O F. Volume of dilution water used during period liters 1.65E+9 2.83E+9 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

1. Fission and activation products barium-140 Ci

<LLD

<LLD cerium-141 Ci

<LLD

<LLD cerium-144 Ci

<LLD

<LLD cesium-134 Ci 1.99E-6

<LLD

<LLD cesium-137 Ci 1.06E-4 1.91E-5 6.10E-6 5.23E-7 chromium-51 Ci

<LLD

<LLD cobalt-58 Ci

<LLD

<LLD cobalt-60 Ci

<LLD

<LLD iodine-131 Ci

<LLD

<LLD N/A iron-55 Ci

<LLD

<LLD iron-59 Ci

<LLD

<LLD lanthanum-140 Ci

<LLD

<LLD manganese-54 Ci

<LLD

<LLD molybdenum-99 Ci

<LLD

<LLD niobium-95 Ci

<LLD

<LLD strontium-89 Ci

<LLD

<LLD strontium-90 Ci

<LLD

<LLD technetium-99m Ci

<LLD

<LLD zinc-65 Ci

<LLD

<LLD zirconium-95 Ci

<LLD

<LLD Total for period Ci 1.08E-4 1.91E-5 6.10E-6 5.23E-7

2.

Dissolved and entrained gases xenon-133 Ci

<LLD

<LLD N/A xenon-135 Ci

<LLD

<LLD N/A Total for period Ci

<LLD

<LD LLD N/A LLD Lower Limit of Detection; see Table 2C.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

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

1. Fission and activation products barium-140 Ci

-N/A N/A N/A

<LLD cerium-141 Ci N/A N/A N/A

<LLD cerium-144 Ci N/A N/A N/A

<LLD cesium-134 Ci N/A N/A N/A 4.14E-5 cesium-137 Ci MN/A N/A N/A,,2.61E-3 chromium-51 Ci N/A N/A N/A

-, LLD.

cobalt-58 Ci

'N/A N/A N/A

'<LLD cobalt-60 Ci N/A N/A N/A 7.10E-4 iodine-131 Ci N/A N/A N/A N/A iron-55 Ci N/A N/A N/A

'1.90E-3 iron-59 Ci N/A N/A N/A

<LLD lanthanum-140 Ci N/A N/A N/A

<LLD manganese-54 Ci

-N/A N/A N/A

<LLD molybdenum-99 Ci N/A N/A N/A

<LLD niobium-95 Ci N/A N/A N/A

<LLD strontium-89 Ci N/A N/A N/A

,3.49E-5 strontium-90 Ci N/A N/A N/A 2.12E-5 technetium-99m Ci N/A N/A N/A

<LLD zinc-65 Ci N/A N/A N/A'.

<LLD zirconium-95 Ci N/A N/A N/A

<LLD Total for period Ci N/A

' N/A N/A-5.32E-3

2. Dissolved and'entrained gases xenon-133 Ci N/A N/A N/A N/A xenon-135 Ci-

_.N/A N/A.

N/A

-:N/A Total for period Ci N/A N/A N/A N/A N/A No releases conducted LLD Lower Limit of Detection; see Table 2C.

l ffi ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides l

LLD (pCi/cc)

1. Fission and activation products barium-140 2.70E-7 cerium-141 4.30E-8 cerium-144 1.70E-7 cesium-134 6.80E-8 chromium-51 3.30E-7 cobalt-58 6.20E-8 cobalt-60 8.90E-8 iodine-131 5.70E-8 iron-55 1.00E-6 iron-59 1.40E-7 lanthanum-140 4.90E-7 manganese-54 6.10E-8 molybdenum-99 5.60E-8 niobium-95 6.20E-8 strontium-89 5.OOE-8 strontium-90 5.OOE-8 technetium-99m 5.70E-8 zinc-65 1.50E-7 zirconium-95 1.10E-7

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

3. gross alpha 1.00E-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

LIQUID EFFLUENTS-LOWER LIMIT BATCH MODE OF DETECTION Radionuclides lLLD

(_Ci/cc)

1. Fission and activation products barium-140 2.30E-7 cerium-141

_-_4.OOE-8 cerium-144 1.70E-7 chromium-51 3.OOE cobalt-58 6.OOE-8 iodine-131 4.30E-8 iron-59 1.40E-7 lanthanum-140 1.60E-7 manganese-54 6.OOE-8 molybdenum-99 2.70E-8 niobium-95..

5.80E-8 technetium-99m--

2.70E zinc-65 1.50E-7 zirconium-95 1.ODE-7

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

3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

1. Total body dose mrem 1.16E-3 2.04E-4 6.50E-5 1.31E-2

2. Percent Applicable Limit 7.72E-2 1.36E-2 4.33E-3 I 8.74E-1 B.

1. Limiting organ dose mrem 1.76E-3 3.12E-4 9.94E-5 4.02E-2

2. Percent Applicable Limit 3.52E-2 6.24E-3 1.99E-3 8.04E-1

3. Limiting organ for period Liver Liver Liver Bone ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

SUMMARY

12 month period

1. Number of batch releases:

1 release

2. Total time period for batch releases:

1127 minutes

3. Maximum time period for a batch release:

1127 minutes

4. Average time period for a batch release:

1127 minutes

5. Minimum time period for a batch release:

1127 minutes

6. Average saltwater flow during batch releases:

13500 gpm ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (2003)

A review of shipping data showed an error in the Unit 1 DAW shipments of reported isotopes. The corrected isotopes and % composition from Table 3 are:

TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

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

b. silver-1O1m lrn 3.84E-3 tin-113 l

<LLD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004):

S.O.N.G.S. -1 SECTION E. RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL-OR DISPOSAL (NotIrradiated Fuel) _

'12'month-Estimated--total

1. -Type of waste

-Unit

-period --

error (%)

a-.

Spent-resins, filter-sludges,-

n--m 3

I.25E-i

'evaporator bottoms

8.75E-2 3.OOE+1

b. Dry active waste (DAW),

i 1.02E+3 compactable'and non-compact'ble (incl.-demolition rubble)-**-

Ci 8.45E+O 3.OOE+1

c. Irradiated components (Reactor m'

3 '

1.09E+1-

'insulation)

Ci 1.82E+2 3.OOE+1

d. Other: (Mechanical filters) #

inm 3.54E+O-

'Ci 6.28E+1 3.OOE+1 NOTE: Total *curie content estimated.

Material packaged in Type A or Type.B casks.

Material packaged in Type A or Type B casks or strong tight containers of various sizes.

I Material packaged in Type B casks.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1

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

a. americium-241 1.39E-4 carbon-14 4.04E-2 cerium-144 5.45E-3 cesium-134 2.59E-3 cesium-137 1.38E-1 cobalt-58 2.18E-6 cobalt-60 6.03E+1 curium-242 2.14E-8 curium-243/244 5.10E-5 iron-55 1.79E+1 manganese-54 4.75E-3 nickel-59 1.58E-1 nickel-63 2.15E+1 niobium-94 5.06E-4 plutonium-238 8.OOE-7 plutonium-239/240 2.16E-7 plutonium-241 1.50E-5 strontium-90 5.02E-4 technetium-99 1.16E-4 tritium 2.OlE-3 ANNUAL RADIOACTIVE EFFLUENT-RELEASE REPORT (2004)

S.O.N.G.S. 1

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

b. americium-241

--4.06E-2--

ant'imony-125 2.21E-3

.carbon-14 3.59E-1 cerium-144 6.96E-2

'-cesium-134 3.74E-1 cesium-137 8.64E+O '

-'cobalt-57 2.20E-6 cobalt;58 5.99E-2 cobalt-60 4.66E+1-curium-242 2.35E-4

,;.uium-~*243/244 1.14E-2 europium-155%

1.-68E-4

- iron-55 2.39E+1

.' manganese-54 1.46E-2 nickel -59 i

,1.37E-1 nickel-63 1.83E+1

iniobium-94 1.04E-2 niobium-95 2.86E-2

' plutonium-238..

,5.OOE-2 p utonium-239/240 1.45E-2 plutonium-241 9.45E-1 plutonium-242 4.04E-5 ruthenium-106 3.14E-4 silver-llOm 4.95E-3 strontium-89 1.46E-5 strontium-90 3.09E-1 technetium-99 1.41E-3 thorium-228 1.69E-5 thorium-230 1.68E-5 tritium 7.63E-2 uranium-233 1.47E-5 zirconium-95 3.90E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1

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

c. americium-241 6.51E-5 carbon-14 3.55E-2 cerium-144 1.08E-3 cesium-134 5.17E-4 cesium-137 2.79E-2 cobalt-60 5.57E+1 curium-242 3.62E-9 curium-243/244 2.60E-5 iron-55 9.23E+O manganese-54 1.17E-4 nickel-59 2.10E-1 nickel-63 2.63E+1 niobium-94 8.46E-4 plutonium-238 5.49E-5 plutonium-239/240 2.09E-5 plutonium-241 1.21E-3 silver-108m 8.29E+O strontium-90

__1.47E-4 technetium-99 1.94E-4 tritium 1.70E-1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1

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

d. americium-241 2.11E-6 carbon-14 '

3.41E-2' cerium-144

-3.69E-6 cesium-137 3.97E-6 cobalt-58 4.99E-5 cobalt-60 5.25E+1 curium-242

%3.15E-8 curium-243/244 1.24E-6 iron-55 2.32E+1 manganese-54%

6.83E-3 nickel-59 1.72E-1 nickel-63 2.41E+1 niobium-94 5.06E-4 plutonium-238 3.52E-6 plutonium-239/240 9.51E-7 plutonium-241 6.71E-5 strontium-90 6.88E-6 technetium-99 1.07E-4 tritium 3.37E-7'

1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 3

RSB and TAG Transport Barnwell, SC Truck 16 TAG Transport EnviroCare, UT Truck 42 MHF Logistical Solutions EnviroCare, UT Rail 2 *TAG Transport Duratek/EnviroCare UT Truck

SONGS maintains a contract with Duratek that provides volume reduction services. The processed volume was shipped from the Duratek facility to EnviroCare using 13 shipments. Those 13 shipments included waste from other generators. SCE's waste volume was a small fraction of the total waste volume of these shipments.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation l Destination None No shipments were made N/A C. DEWATERING Number of Containers Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

% Applicable Limit where:

Rel Rate X/Q o

MPCeff (Rel Rate) (XIQ) (100)

MPCeff 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 IA, MCi/sec.

=

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

=

n 1I 11 MPC i

=

fractional abundance of the it' radionuclide obtained by dividing the activity (curies) for each radionuclide, C,, by the sum of all the isotopic activity, C T.

=

total number of radionuclides identified

=

Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602),

Appendix B, Table II, Column 1.

=

(Rel Rate) (X/0) (100)

ECLeff where:

F, n

MPCj

% ECL where:

Rel Rate X/Q

° ECLeff

=

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 IA, pCi/sec.

=

1.30E-5 sec/m 3; the annual average atmospheric dispersion defined in the Unit 1 ODCM.

1 ECL i fractional abundance of the it' radionuclide obtained by dividing.the activity (curies) for each radionuclide, C,, by the sum of all the isotopic activity, C T.

=

total number of radionuclides identified

=

Effluent Concentration Limit (ECL) of the ijh radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1.

where:

F, n

ECL, ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

% Applicable Limit

=

(Dil Conc) (100)

MPCeff where:

DiI Conc

=

total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, jUCi/ml.

1 a

MPCeff

=

FE

j. MPC i where:

F, n

MPC1

% ECL

=

fractional abundance of the it' radionuclide obtained by dividing the activity (curies) for each radionuclide, C1, by the sum of all the isotopic activity, C T.

=

total number of radionuclides identified

=

Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2.

=

(Dil Conc) (100)

ECLeff where:

Dil Conc 0

ECLe,,

=

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

=

n F.

.1 ECL,

=

fractional abundance of the it' radionuclide obtained by dividing the activity (curies) for each radionuclide, Ct, by the sum of all the isotopic activity, C T.

=

total number of radionuclides identified

=

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

where:

F, n

ECL1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

Sources of error for gaseous effluents -

batch releases'are:-

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

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

batch releases are:

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

continuous releases are:

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

Total Error

=

+ 02

+

63

+

... a2 where:

a

=

Error associated with each component.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

Six different categories are presented:

(1)

(2)

(3)

(4)

(5)

(6)

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

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

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

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

Table 2 in Section H presents the percent presented in Table 1.

of Applicable Limits for each dose 1 ODCM Figure 6-1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 TABLE 1

'Dose * (millirems)

First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS

1)

2)

3)

4) 5)

Whole Body 1.16E-3 2.04E-4 6.50E-5 1.31E-2 1.45E-2

6)

7)

8) 9),

10)

Organ 1.76E-3 3.12E-4 9.94E-5 4.02E-2 4.18E-2 AIRBORNE EFFLUENTS

11)

12)

13)

14) 15)

Tritium, Iodines, and Particulates O.OOE+O 9.80E-5 3.37E-4 1.50E-4 5.24E-4 NOBLE GASES **

16)

17)

18)

19) 20)

Gamma O.OOE+O 2.09E-5 1.61E-5 O.OOE+O 3.48E-5

21)

22)

23)

24) 25)

Beta O.OOE+O 2.37E-3 1.83E-3 O.OOE+O 3.94E-3

26)

27)

28)

29) 30)

DIRECT RADIATION 1.07E-1 8.21E-2 1.18E-1 9.45E-2 3.68E-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.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1

6.

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

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

8.

This value was calculated using the methodology of the 0DCM; the liver received the maximum dose primarily by the saltwater fish pathway.

9.

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

10.

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

11.

There was no activity detected during the release period, therefore the reported organ dose was 0.OOE+0 mrem.

12.

The maximum organ dose was to a teen's liver and was located in the NNE sector.

This was calculated using the assumptions of USNRC Regulatory Guide 1.109.

13.

The maximum organ dose was to the skin (all age groups) and was located in the NNE sector.

This was calculated using the assumptions of USNRC Regulatory Guide 1.109.

14.

The maximum organ dose was to the skin (all age groups) and was located in the NNE sector.

This was calculated using the assumptions of USNRC Regulatory Guide 1.109.

15.

The maximum organ dose was to a teen's liver and was located in the NNE sector.

This was calculated using the assumptions of USNRC Regulatory Guide 1.109.

16.

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

17.

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 W sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

19.

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

20.

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

21.

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

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 W sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

24.

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1

25.

The maximum air dose for beta radiation was located in 'the W sector,;Vat 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 anid 'are prdrated 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 tare 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.

1 Jo I

29.

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

30.

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

TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter_

Quarter

-Quarter Year -

LIQUID EFFLUENTS Whole Body-7.72E-2 1.36E-2 4.33E-3

--8.74E-1 4.85E-1 Organ 3.52E-2 6.24E-3 1.99E-3 8.04E-1 4.18E-1 AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates-O.OOE+O 1.31E-3 4.49E-3 2.00E-3 3.49E-3 NOBLE GASES Gamma O.OOE+O 4.17E-4 3.22E-4 O.OOE+O 3.48E-4 Beta O.OOE+O 2.37E-2

-1.83E-2 '

O.OOE+O 1.97E-2 NOTE:Direct Radiation is not specifically addressed in the Applicable Limits.

i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 SECTION I. CHANGES TO OFFSITE DOSE CALCULATION MANUAL On February 26, 2004, Revision 21 to the Unit 1 Offsite Dose Calculation Manual (ODCM) was adopted and published. This change incorporated 1) Removal of the reference to the specific software used to calculate off-site airborne doses using concurrent meteorology, 2) Updated two sections to reflect the completed installation of MGPI radiation monitors, 3) Incorporated updates related to the recent Land Use Census (LUC), 4) Identified members of the public staying at Camp Mesa, and 5) Corrected a reference in section 6.

Per NRC Generic Letter 89-01, no Effluent/ODCM Evaluation or 50.59 reviews were required or performed for editorial changes made to reflect actual plant operation.

None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations. The level of radioactive effluent control required by 10CFR20, 40CFR190, 10CFR50.36a, and Appendix I to 10CFR5O will be maintained.

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

A Addition F

Editorial/Format change D Deletion R

Revision Page Change Reason 1-19 Deleted Table 1-2 as MGPI monitors don't have calibration constants D

2-16 Removed reference to type of software used to calculate offsite dose using R

concurrent meteorology.

This item is controlled by site programs and procedures.

2-18 Removed reference to type of software used to calculate offsite dose using R

concurrent meteorology.

This item is controlled by site programs and procedures.

2-21 Changed Controlling Location Factors per LUC and corrected footnote format R

2-24 Per LUC, outage workers are no longer at this location 0

2-25 Renumbered pages for sector Q F

2-26 Renumbered pages for sector Q F

2-27 Per LUC, this location is renamed Beach Complex and renumbered pages for sector Q R

2-31 Per LUC, this location renamed Camp Mesa R

4-2 Removed note 2 as all MGPI radiation monitors are turned over to station R

4-5 Removed note (7) as the MGPI radiation monitors are turned over to station R

4-6 Clarified wording accounting for installation of MGPI monitors and removed note (7)

R 5-18 Changed name of TLD # 23 to better reflect location R

6-2 Added Camp Mesa residents to the category of Member of the Public R

6-10 Changed reference to Quality Assurance Program from deleted Tech Spec section R

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 On September'3, 2004, Revision 22 to the Unit 1 Offsite Dose Calculation Manual (ODCM) was adopted and published.

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

1) Removed the reheater pit sump (RPS) system as a credited release point',and the associated requirements for continuous monitoring (R-2100) and periodic sampling and analysis. This supports ECP 040500364 that physically removed the system and all components from the plant as part of-decommissioning. The-deletion was -

evaluated in action 1 of the AR.

2) Removed the Plant Vent Stack Monitor (R-1254) gas channels and the-associated surveillance and planned maintenance once all fuel was transferred to the ISFSI.

As discussed in detail in action 2 of the AR, the transfer of the--spent'fuel-removed the last potential source of noble gas.-

3) Deleted requirements for iodine sampling for the airborne release point, the Plant Vent Stack, to reflect the absence of anjiodine source term due to radioactive decay since 'the plant was shutdown in November 1992'. The deletion was evaluated-fin-action 14 of the AR.

4) Removed requirement-for sampling andanalysis of dissolved and entrained gases for liquid releases once the transfer of spent fuel to the ISFSI was completed.

Once the last potential -source of noble'gas'was removed, the requirement-to perform sampling and analysis of liquid effluents for dissolved and entrained gases no longer appl ied.' This was "evalu'afted 'in'a'ction 13 of the AR.'.

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

6) Added note allowing for the use of additional-dilution to-support decommissioning efforts, particularly during final draindown of the spent fuel pool and decommiissioning of the-liquidra'dwa'stie processi n g-sstem. This change was screened in action 4 of the AR.

7) Modified compensatory action for an'out of'service sample flow measuring device on the Plant Vent Stack to reflect the removal of noble gas channel from R-1254.

This was evaluated in action 15 of the AR, -and

8) Updated PVS fan flow rate per AR 030600106.

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

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

A Addition D Deletion F Editorial/Format change R Revision ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 Page Change Reason ii Removed the RPS system name from section 1.4.2.1.

to reflect ECP 040500364 D

iii Revised Titles for 2.3 and 2.6.2 to remove iodine.

R 1-1 Added note stating the noble gas source term will no longer exist once fuel is A

transferred to the ISFSI so the dissolved and entrained gas limit will become not applicable.

1-3 Removed the RPS from Table 1-1. Added footnote (g) to the sampling requirement of D & R dissolved and entrained gases.

1-5 Added footnote (g) stating the requirement for dissolved and entrained gases A

becomes not applicable once transfer of all of the spent fuel to the ISFSI has been completed and AR 040501435-16 is closed.

1-11 Added note to allow increased dilution flow A

1-13 Deleted obsolete step 4 for cpm monitors and added to the note that once transfer D & A of spent fuel to the ISFSI is completed, dissolved and entrained gas limit will not be applicable.

1-14 Removed the RPS and deleted line about the previously removed radwaste system D,A & R monitor tanks.

Added note to allow increased dilution flow 1-15 Removed the RPS R

1-16 Removed the RPS and removed obsolete step 4 for cpm monitors D & R 1-17 Removed the RPS D

1-18 Removed the RPS D

2-1 Noted that once all fuel is transferred to the ISFSI, Specification A.1 is not A & D required. Removed i-131/I-133 requirement as the iodine source no longer exists.

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

2-3 Added note "f" to Table 2-1 deleting sampling requirements for noble gas and A & 0 continuous monitoring once transfer of all of the spent fuel to the ISFSI has been completed. Removed 1-131/1-133 sampling requirement as the iodine source no longer exists.

2-5 Added note "f" to Table 2-1 deleting requirements for noble gas monitoring and A

noble gas sampling once transfer of all of the spent fuel to the ISFSI has been completed.

2-6 Changed applicability for specification 2.2.1 from "at all times" to "not required A

once transfer of all of the spent fuel to the ISFSI has been completed".

2-7 Changed applicability for specification 2.2.2 from "at all times" to "not required A

once transfer of all of the spent fuel to the ISFSI has been completed".

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

0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 2-9 Removed 1-131/I-133 requirement as the iodine source no longer exists.

D 2-10 Noted the section on calculating setpoints for R-1254 is not applicable once A

transfer of all of the spent fuel to the ISFSI has been completed.

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

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

2-13 Changed applicability for specification 2.6.1 from "at all times" to 'not required A

once transfer of all of the spent fuel-to the ISFSI-has been completed".

2-14 Removed 1-131/1-133 requirement as the iodine source no longer exists.

D 2-15 Changed applicability for specification 2.7.1 from "at all times" to "not required A

once transfer of all of the spent fuel to the ISFSI has been completed".

2-16 Changed applicability for specification 2.7.1 from "at all times" to "not required A

once transfer of all of the spent fuel to the ISFSI has been completed".

2-17 Removed 1-131/1-133 requirement as the iodine source no longer exists.

D D

2-18 Removed 1-131/1-133 requirement as the iodine source no longer exists.

D 4-2 Removed the RPS D

4-5 Removed the RPS D

4-7 Changed applicability for specification 4.2.1.B.1 from "at all times" to "not A

required once transfer of all of the spent fuel to the ISFSI has been completed".

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

Deleted the charcoal sampler as the iodine source tern no longer exists.

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

4-9 Changed action 22 of Table 4-4 to "not required once transfer of all of the spent A & D fuel to the ISFSI has been completed". Also, removed the iodine reference in Action 24.

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

4-10 Changed applicability for specification 4.2.2.A from "at all times" to "not A

required once transfer of all of the spent fuel to the ISFSI has been completed".

l

^

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 4-11 Added footnote (7) to Table 4-4 to state that wonce transfer of the spent fuel to A & D the ISFSI is completed, the noble gas monitor is not required." Removed surveillance requirements for the iodine sampler.

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

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

D & R 4-14 Modified figure 4-2 to reflect configuration of reactor building ventilation per R

ECP 030600106-1.

5-26 Replaced Figures with newer versions.

F thru 5-30 6-12 Modified Basis 6.4.5 to reflect that once transfer of the spent fuel to the ISFSI A

is completed, the noble gas source term no longer exists and therefore the limitations of gamma and beta dose rates due to noble gas are not applicable.

6-13 Modified Basis 6.4.7 to reflect that once transfer of the spent fuel to the ISFSI A & D is completed, the noble gas source term no longer exists and therefore this basis is not applicable.

Also removed reference to 1-131 & 1-133 from bases 6.4.8 and 6.4.9.

6-14 Removed reference to 1-131 and 1-133 from base 6.4.9.

D 6-15 Modified Basis 6.4.14 to reflect that once transfer of the spent fuel to the ISFSI A

is completed, the noble gas source term no longer exists and therefore this basis is not applicable.

ANNUAL RADIOACTIVE EFFLUENT'RELEASE REPORT (2004)

S.O.N.G.S. 1 SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS Change 1 Demolition of Reheater Pit Sump On August"30, 2004, the Reheater Pit Sump (RPS) system was permanently'removed from service. The reheater-sump,'sump pumpstand radiation monitoring-system skid (RE-2100) were all removed to facilitate turbine building removal.

These systems are no longer-functionally necessary, and encumber demolition activities in the-area.

Unit 1 has reached the point in its decommissioning where systems are being physically removed. To support future demolition of the-turbine'building, the RPS system components, including the radiation monitoring system, were removed. All of the piped-sources of wastewater to the RPSowere permanently cut-.and filled or routed to the Yard Drain Sump (YDS), the single remaining Unit-1 ODCM-credited continuous liquid release point.

The RPS was-designed to collect area drainage from the turbine building-and secondary side equipment leaks. A radiation monitoring system was installed because of the potential for contamination from primary-to-secondary leaks, and the discharge was routed through an oil-water-separator to ensure compliance with the NPDES'permit. As part of decommissioning, secondary side systems have been removed and the majority of the-turbine-building itself has been decontaminated and free-released by Health Physics.

The issue of rainwater accumulation and run-off from contaminated areas is addressed in AR 040500364-48.

Run-off from those areas that continue to have low levels of detectable contamination, such as the north extension, crane deck, and feedwater pump pedestals, are being routed to the YDS. The water management plan requires sampling of any water that may accumulate from free-released areas to confirm <MDA. In the unlikely event that,!a sample has measurable activity, the water will be routed to the YDS.

The water accumulation in the RPS sump area is expected to be much less than historically collected due to the plugging and routing of existing drains to the yard drain sump. There will be no unmonitored release of radioactive liquid effluents and no resultant increase in radioactive liquid effluents from Unit 1.

There will be no expected change in exposure to plant personnel or to a member of the public due to this change.

This change was reviewed and approved acceptable pursuant to Quality Assurance Program Description (SCE-1-A), subsection 17.2.20.3.1.i per ECP 040500364.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 Change 2 R-1254 changes to delete noble gas and iodine sampling and monitoring On November 8, 2004, certain portions of the Plant Vent Stack radmonitoring system were modified and are no longer used. On August 31, 2004, the last of the fuel from the Unit 1 spent fuel pool was transferred to the Independent Spent Fuel Storage Installation (ISFSI).

Additionally, any iodine source term has decayed away since Unit 1 was permanently shut down in 1992.

The noble gas and iodine source terms no longer exist at Unit 1, as detailed in AR 040501435. Accordingly, with no gas or iodine source term remaining, the need to sample for those species no longer exists. Therefore, the monitoring and sampling requirements for noble gas and iodine were removed from the Unit 1 ODCM and chemistry procedures.

A similar change was made to the Unit 1 DSAR.

This change included deletion of the requirement for compensatory actions for an inoperable gas monitor as well as maintenance requirements for the gas channel.

The requirement to sample for particulates remain unchanged.

The only potential source of noble gas remaining at Unit 1 was the spent fuel.

The spent fuel has now been transferred from the spent fuel pool to the ISFSI.

There has been no noble gas released from Unit 1 since the end of 1993 except for Kr-85 from damaged assemblies during vacuum drying operations as part of the transfer of the spent fuel to the ISFSI.

As described more fully in AR 040501435, once the transfer was completed, there no longer remains a source of noble gases.

The ISFSI itself is designed to prevent airborne and/or liquid releases.

The ISFSI design precludes any release of radioactive materials, so no release is expected. The iodine source term has decayed away. Since the noble gas and iodine source terms no longer exist, there is no dose increase to plant personnel or to a member of the public from this change.

This change to the ODCM and the effluent program was reviewed and found acceptable pursuant to Quality Assurance Program Description (SCE-1-A), subsection 17.2.20.3.1.i.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 Change 3 Modification of Plant Vent Stack flow Daths at Unit 1 by addition of fan A-21.

In April 2004. the plant ventilation system was modified by adding fan A-21. ':The sole function of A-21 is to take suction on the-containment building and exhaust into the existing Plant Vent Stack (PVS),,system. Previously, the-containment building was just one of many loads offan A-22 or A-24. -With fan A-21 now-:

dedicated to the containment building, better air flow williresult, creating a system enhancement.

Either fan A-22 or A-24 is required to be on. The containment ventilation system contains'filtering'capability.

Fan A-21 exhausts into the existing Plant' Vent Stack system, and will therefore be sampled by existing radiation monitor R-1254. This design change creates no new' source term or release path, does notremove any sampling or monitoring_

requirements.' As such, no increase in airborne activity is expected as a result of this change. -No dose to a plant personnel or a member of the public will result from this change..

This change was reviewed and approved acceptable pursuant to Quality Assurance Program Description (SCE-1-A), subsection. 17.2.20.3.1.i per ECP 030600106. -

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 SECTION K. MISCELLANEOUS Yard Drain Sump Overflow The Unit 1 Yard Drain sump overflowed to the PMF Catch Basin due to heavy rainfall on three different days in 2004. Since there was no detectable activity samples taken the public as documented in during the overflows, there were no dose consequences to a result of these unplanned, unmonitored releases.

These ARs 040202013, 041001767, and 041002348.

in the grab a member of events are Estimated Estimated Estimated Start Stop Duration Activity Release Whole Body Organ Dose Date/Time Date/Time (min)

(pCi/ml)

(Curies)

Dose (mrem)

(mrem) 02/23/04 @ 0145 2/23/04 @ 0205 20 cMDA O.OOE+0 O.OOE+O O.OOE+0 10/20/04 @ 0757 10/20/04 @ 0910 73

'MDA O.OOE+O O.OOE+O O.OOE+0 10/20/04 @ 0953 10/20/04 @ 1028 35

'MDA O.OOE+0 O.OOE+0 O.OOE+O 10/27/04 @ 0155 10/27/02 @ 0410 135

'MDA O.OOE+0 O.OOE+0 O.00E+0 10/27/04 @ 0610 10/27/04 @ 0705 55

'MDA O.OOE+0 O.OOE+O O.OOE+0 10/27/04 @ 2030 10/27/04 @ 2143 73

'MDA O.OOE+0 O.OOE+0 O.OOE+O Sample Line Hose Leak on Plant Vent Stack (PVS) Monitor R-1254 On 9/3/04, a stainless steel braided hose on the R-1254 sample line was found to be leaking. This resulted in slight dilution of the air sample upstream of the sample media and detector. The hose was replaced and the skid verified to be leak tight.

The leak was discovered during the channel function test (CFT). The previous successfully conducted leak check was in May, marking that point as the earliest failure date. Evaluation of sample results from the monitor during this time period revealed there was minimal or no in-leakage during normal operation. Therefore there were no dose consequences to members of the public as a result of this event. This event is documented in AR 040900118.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2004 - December 31, 2004 S.O.N.G.S. 1 Monitor Inoperability Period Inoperability Cause Explanation R-2100 12/15/03 - 02/24/04 Sample flowpath Demolition debris clogged sample Reheater Pit Sump plugged &

lines and degraded electronic Monitor electronic monitor components. Sample lines were failure cleared and the the local processing unit (LPU) and cable were replaced. Monitor was calibrated.

03/27/04 - 06/09/04 Monitor failure Concrete 'dust blanketed monitor and electrical components. Mechanical

- vibrations from demolition activities degraded instrumentation. Electrical components were cleaned'and ahigh voltage adjustment-corrected calibration drift.

06/24/04 - 09/03/04 Monitor failure LPU failed again due to'demolition alarm won't reset activities and debris. Replaced LPU and cleaned components. Reheater pit sump system removed from service prior to work being completed.

1it ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 1 SFCTION LI S.O.N.CS. 1 CONICLUSIONS Gaseous releases totaled 4.60E+O curies of which noble gases were 4.37E+O curies, iodines were O.OOE+O curies, particulates were 9.92E-6 curies, and tritium was 2.27E-1 curies.

The radiation doses from gaseous releases were: (a) gamma air dose: 3.48E-5 mrad at the site boundary, (b) beta air dose: 3.94E-3 mrad at the site boundary, organ dose: 5.24E-4 mrem at the nearest receptor.

Liquid releases totaled 5.41E-1 curies of which particulates and iodines were 5.45E-3 curies, tritium was 5.36E-1 curies, and noble gases were O.OOE+O curies.

The radiation doses from liquid releases were: (a) total body: 1.45E-2 mrem, (b) limiting organ: 4.18E-2 mrem.

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

Ii '

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

TABLE OF CONTENTS SECTION A - INTRODUCTION.................

SECTION B - GASEOUS EFFLUENTS...............

SECTION C - LIQUID EFFLUENTS...............

SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADI SECTION E - RADWASTE SHIPMENTS..............

SECTION F - APPLICABLE LIMITS...............

SECTION G - ESTIMATION OF ERROR..............

SECTION H - 10 CFR 50 APPENDIX I REQUIREMENTS.......

SECTION I - CHANGES TO OFFSITE DOSE CALCULATION MANUAL..

SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS SECTION K - MISCELLANEOUS.................

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

.......... 42

.......... 43

.......... 53 DENDUM....... 61 62

.......... 66

...........68

...........69

...........73 74

........... 75

...........78

-iii-

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

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

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 (2004)

S.O.N.G.S. 2 and 3 SECTION B. 'GASEOUS EFFLUENTS Table 1A, "Gaseous Effluents-Summation of All Releases," provides a detailed listing of gaseous effluents released quarterly in four categories:

fission and activation gases, iodine-131, particulates with half-lives greater than eight days, and tritium.

Listed for each of the four categories are:

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

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

Table 1B, "Gaseous Effluents-Elevated Release," has not been included in this report since San Onofre Nuclear Generating Station Units 2 and 3 do not conduct-elevated releases.

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

fission gases,

iodines, and particulates.

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

Waste gas decay tank releases are considered to be "batch" releases.

Containment purges and plant stack releases are considered to be "continuous" releases.

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

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

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

Unit First Quarter Second Quarter Estimated Total Error, %

A. Fission and activation gases

1. Total release Ci 3.86E+1 2.26E+1 3.OOE+1

2. Average release rate for period pCi/sec 4.90E+O 2.87E+O

3. Percent of applicable limit

% MPC 1.28E-2 6.78E-3

4. Percent Effluent Concentration Limit

% ECL 2.68E-2 1.26E-2 B. Iodines

1. Total iodine-131 Ci 2.55E-4 3.88E-5 1.90E+1

2. Average release rate for period pCi/sec 3.24E-5 4.93E-6

3. Percent of applicable limit

% MPC 1.56E-4 2.37E-5

4. Percent Effluent Concentration Limit

% ECL 7.78E-5 1.18E-5 C. Particulates

1. Particulates with half-lives >8 days Ci 2.15E-4 3.14E-5 1.60E+1

2. Average release rate for period pCi/sec 2.74E-5 4.OOE-6

3. Percent of applicable limit

% MPC 9.35E-6 1.29E-6

4. Percent Effluent Concentration Limit

% ECL 2.73E-5 2.76E-6

5. Gross alpha activity Ci

<LLD

<LLD 5.OOE+1 D. Tritium

1. Total release Ci 1.62E+1 1.36E+1 2.50E+1

2. Average release rate for period pCi/sec 2.06E+O 1.73E+O

3. Percent of applicable limit

% MPC 4.95E-3 4.15E-3

4. Percent Effluent Concentration Limit

% ECL 9.89E-3 8.30E-3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Third Quarter,'

Fourth Quarter Estimated Total

--Error, -'-%

Unit A. -Fission and activation gases

.1. Total release Ci 2.14E+1 3.99E+1-' '3.OOE+1

2. Average' release rate for period-:

/Ci/sec 2.69E+O 5.02E+O

,3. Percent 6f applicable limit

-%-MPC 9.62E 8.07E-3.'

4. Percent Effluent Concentration Limit

% ECL 2.66E-2 4.84E-3.,,;.'__,_'

B. Iodines 1.' Total iodine-131 C i 3.26E 5.45E-,3 1.90E+1

2. Average release rate for period pCi/sec 4.10E-5 6.86E-4

'3., Percent of-applicable limit

% MPC 1.97E-4 3.'29E-3 I 4.' Percent Effluent Concentration Limit

% ECL 9.84E-5 1.65E3 C. Particulates '

1. Particulates with half-lives >8 days 7Ci 1.53E-5 2.OOE-4 1.60E+1

2. Average release rate for period uCi/sec 1.92E-6 2.52E-5

3. Percent of applicable limit

% MPC 1.56E-6 1.05E-5

4. Percent Effluent Concentration Limit

% ECL 7.24E-6 3.90E-5

5. Gross alpha activity Ci

<LLD

<LLD 5.OOE+1 D. Tritium

1. Total release Ci 1.36E+1 1.78E+1 2.50E+1

2. Average release rate for period.

pCi/sec 1.71E+0 2.24E+O

3. Percent of applicable limit

% MPC 4.11E-3 5.37E-3

4. Percent Effluent Concentration Limit

% ECL 8.21E-3 1.07E-2 I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 2 and 3 TABLE IC GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE I

l First Second Third Fourth Radionuclides Released l Unit Quarter l Quarter l Quarter l Quarter

1. Fission and activation gases argon-41 Ci 3.72E+O 1.65E+O 4.06E+O 2.64E-2 krypton-85 Ci 4.26E-1

<LLD

<LLD 1.69E+O krypton-85m Ci

<LLD

<LLD krypton-87 Ci

<LLD

<LLD krypton-88 Ci

<LLD

<LLD xenon-133 Ci 3.07E+1 1.97E+1 1.68E+1 3.57E+1 xenon-133m Ci 9.75E-2

<LLD

<LLD 1.61E-1 xenon-135 Ci 6.31E-3

<LLD

<LLD 1.24E-2 xenon-135m Ci

<LLD

<LLD xenon-138 Ci

<LLD

<LLD Total for period Ci 3.50E+1 2.13E+1 2.08E+1 3.75E+1

2. Iodines iodine-131 Ci 2.55E-4 3.88E-5 3.26E-4 5.45E-3 iodine-132 Ci 1.22E-6

<LLD 6.59E-5 1.28E-4 iodine-133 Ci 5.91E-5 2.70E-5 4.47E-5 1.96E-5 iodine-135 Ci

<LLD

<LLD Total for period Ci 3.16E-4 6.58E-5 4.36E-4 5.60E-3 LLD Lower Limit of Detection; see Table 1D.

ANNUAL RADIOACTIVE EFFLUENT'RELEASE REPORT (2004)

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

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE

_1, l-First I

Second Third l Fourth Radionuclides Released Unit

'Qurter Quarter Quarter Quarter

3. Particulates barium-140>

Ci

.<LLD

<LLD

<LLD bromine-8Z Ci 2.23E-4 6.04E-5 4.81E-5 8.87E-6 cerium-141 Ci

- <LLD

<LLD

<LLD.

LLD

- ceri um-144; Ci

<LLD

-<LLD cesium-134 Ci 1.27E-6 6.82E-7

<LD 8.54E-8 cesium-137 Ci 2.09E-5 2.75E-6 2.92E-6 7.81E-6

','cesium-138.

Ci

<LD 3.28E-6

<LLD

<LLD chromium Ci 3.08E-5

<LLD

<LLD-

-1.84E-6 cobalt Ci,

1.20E-7

<LLD

<LLD cobalt-58 Ci

-1.45E-4 2.80E-5 7,.47E-6 1.56E-4 cobalt-60 Ci 8.95E-6

<LLD 4.89E-6 2.21E-5 iron-59 Ci 7.52E-7,

.<LLD

<.'LLD

'<LLD lanthanum-140 Ci

<LLD

<LLD manganese-54

'Ci 1.;58E-6

<LLD LD 2.88E-6 molybdenum-99 Ci

<LLD

<LLD niobium-95 Ci 3.68E-6

<LLD

<LLD 9.28E-6 niobium-95m Ci

<LLD

<LLD 6.29E-6 sodium-24 Ci

<LLD

<LLD 3.99E-7

<LLD strontium-89 Ci

<LLD

<LLD strontium-90 Ci

<LLD

<LLD zinc-65 Ci

<LLD

<LLD LLD

<LLD zirconium-95 Ci 2.31E-6

<LLD

<LLD 1.30E-7 LLD Lower Limit of Detection; see Table 1D.

-l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES BATCH MODE

First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission and activation gases krypton-85 Ci 3.57E+O 1.24E+O 5.02E-1 2.31E+O krypton-85m Ci

<LLD

<LLD krypton-87 Ci

<LLD

<LLD krypton-88 Ci

<LLD

<LLD 1.49E-3

<LLD xenon-131m Ci

<LLD

<LLD xenon-133 Ci 4.69E-3 6.38E-3

<LLD 1.82E-2 xenon-133m Ci

<LLD

<LLD xenon-135 Ci

<LLD

<LLD xenon-135m Ci

<LLD

<LLD xenon-138 Ci

<LLD

<LLD Total for period Ci 3.57E+O 1.25E+O 5.03E-1 2.33E+O LLD Lower Limit of Detection; see Table iD.

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

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

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

3. Particulates barium-140 2.90E-13 cerium-141 3.60E-14 cerium-144 1.40E-13 cesium-134 8.20E-14 cesium-138 1.70E-10 chromium-51 3.20E-13 cobalt-57 1.80E-14 cobalt-60 1.20E-13 iron-59 1.90E-13 lanthanum-140 6.OOE-13 manganese-54 7.40E-14 molybdenum-99 4.40E-14 niobium-95 7.40E-14 niobium-95m 1.70E-13 sodium-24 1.00E-12 strontium-89 1.OOE-11 strontium-90 1.OOE-11 zinc-65 2.OOE-13 zirconium-95 1.30E-13

4. alpha 1.OOE-11 l.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE Radionuclides l

LLD (juCi/cc)

1. Fission and activation gases krypton-85m 2.OOE-6 krypton-87 8.70E-6 krypton-88 7.10E-6 xenon-131m 7.30E-5 xenon-133 4.40E-6 xenon-133m 1.80E-5 xenon-135 2.20E-6 xenon-135m 2.70E-5 xenon-138 4.30E-5 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 2 and 3 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY r

F F

F First Quarter Second Quarter Third Quarter I Unit Fourth Quarter A. Noble Gas

1. Gamma Air Dose mrad 6.94E-3 3.39E-3 6.65E-3

1.

98E-3

2. Percent Applicable Limit 6.94E-2 3.39E-2 6.65E-2 1.98E-2i

3. Beta Air Dose mrad 7.98E-3 4.33E-3 4.86E-3 l6.94E-3,

4. Percent Applicable Limit 3.99E-2 2.17E-2 2.43E-2 3.47E-2 B. Tritium, Iodine, Particulates (at the nearest receptor)

1. Organ Dose mrem 1.78E-3 9.28E-4 1.21E-3 5.97E-3

2. Percent Applicable Limit 1.19E-2 6.19E-3 8.04E-3 3.98E-2 NOTE:

Calculations performed in accordance with the ODCM utilizing the historical X/Q.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

SUMMARY

12 month period

1. Number of batch releases:

8 releases

2. Total time period for batch releases:

3506 minutes

3. Maximum time period for a batch release:

598 minutes

4. Average time period for a batch release:

438 minutes

5. Minimum time period for a batch release:

306 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 2Land 3 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 Ainformation regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Units 2 and 3.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

A. Fission and activation products C')

1. Total release (not including tritium, gases, alpha)

Ci 3.47E-2 2.44E-3 1.90E+1

2. Average diluted concentration during period pCi/ml 5.63E-11 3.21E-12

3. Percent of applicable limit

% MPC 1.20E-4 3.77E-6

4. Percent Effluent Concentration Limit

% ECL 1.27E-3 2.10E-5 B. Tritium

1. Total release Ci 1.12E+3 7.63E+1 1.90E+1

2. Average diluted concentration during period yCi/ml 1.82E-6 1.OOE-7

3. Percent of applicable limit

% MPC 6.06E-2 3.35E-3

4. Percent Effluent Concentration Limit % ECL 1.82E-1 1.OOE-2 C. Dissolved and entrained gases

1. Total release Ci 2.69E-1 1.62E-2 1.90E+1

2. Average diluted concentration during period uCi/ml 4.37E-10 2.13E-11

3. Percent of applicable limit

% MPC 2.19E-4 1.07E-5

4.

Percent Effluent Concentration Limit % ECL 2.19E-4 1.07E-5 D. Gross alpha radioactivity (1)

1. Total release Ci

<LLD

<LLD 5.0OE+1 E. Volume of waste released (batch &

continuous, prior to dilution) liters 5.47E+7 7.OOE+7 5.OOE+O F. Volume of dilution water used during period liters 6.16E+11 7.60E+11 5.OOE+O (1) The sample for T076 released on 3/24/04 was discarded prior to use in the monthly composite for offsite analysis for alpha, Fe-55 and Sr-89/90. The March radwaste composite was comprised of 3 other tanks released that month. The missing sample had been analyzed and used to generate permit # 4L-85-0. This event is documented in AR 040400853.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

LIQUID EFFLUENTS-SUMMATIONOF ALL RELEASES F

i Unit Third --

Quarter Fourth Quarter.

Estimated Total Error, %

A. Fission and activation products(',

1. Total release (not including tritium, gases, alpha)

Ci

-1.75E-2 7.96E-3 1.90E+1--

2. Average diluted concentration during period jCi/ml 2.37E-11 1.49E-11

3.

Percent of applicable limit

%.MPC 3.12E 2.34E-5,

4. Percent Effluent Concentration Limit

% ECL 2.39E-.4 1.66E-4

-_l B. Tritium

1. Total release Ci 4.54E+2 2.38E+2 1.90E+1

2. Average diluted concentration during period

Ci/ml 6.17E-7 4.46E-7

3. -Percent of applicable limit

% MPC 2.06E-2 1.49E-2

4. Percent Effluent Concentration Limit % ECL 6.-17E-2 4.46E-2 C. Dissolved and-entrained gases

1. Total release Ci 2.26E-1 2.02E-4 1.90E+1

2. Average diluted concentration during period yCi/ml 3.08E-10, 3.78E-13

3. Percent of applicable limit MPC

-1.54E-4 1.89E-7

4. Percent Effluent Concentration Limit

% ECL 1.54E-4

-1.89E-7' D. Gross alpha radioactivity

1. Total release Ci

<LLD

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

continuous, prior to dilution) liters 7.66E+7 7.78E+7 5.OOE+O F. Volume of dilution water used during period liters 7.36E+11 5.34E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 2 and 3 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 cerium-141 Ci

<LLD

<LLD cerium-144 Ci

<LLD

<LLD cesium-134 Ci

<LLD

<LLD cesium-137 Ci

<LLD

<LLD chromium-51 Ci

<LLD

<LLD cobalt-58 Ci

<LLD

<LLD cobalt-60 Ci

<LLD

<LLD iodine-131 Ci

<LLD

<LLD iron-55 Ci

<LLD

<LLD iron-59 Ci

<LLD

<LLD lanthanum-140 Ci

<LLD

<LLD manganese-54 Ci

<LLD

<LLD molybdenum-99 Ci

<LLD

<LLD niobium-95 Ci

<LLD

<LLD strontium-89 Ci

<LLD

<LLD strontium-90 Ci

<LLD

<LLD technetium-99m Ci

<LLD

<LLD zinc-65 Ci

<LLD

<LLD zirconium-95 Ci

<LLD

<LLD Total for period Ci

<LLD

2. Dissolved and entrained gases

<LLD

<LLD_-<LLD xenon-133 Ci

<LLD

'LLD xenon-135 Ci

<LLD

'LLD

'LLD Total for period Ci

<LLD

<LLD LLD Lower Limit of Detection; see Table 2C.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

LIQUID EFFLUENTS BATCH MODE I

First Second Third Fourth Radionuclides Releasedi Unit Quarter Quarter Quarter l Quar'ter

1. Fission and activation products,_'-_','__

antimony-124 Ci

<LLD

<LLD : 2.20E-5 antimony-125 Ci 3.81E-3 1.40E-4 1.77E-3

-1.15E-3 barium-140 Ci

<LLD

<LLD cerium-141 Ci

<LLD

'LLD cerium-144 Ci

<LLD

<LLD cesium-134 Ci 5.58E-4

LLD 5.42E 1.04E-5 cesium-137 Ci 2.52E-3 4.60E-6 3.01E-4

-3.47E-4 chromium-51 Ci 8.65E-4 6.43E-4 4.22E-4

-4.17E-4 cobalt-57 Ci 6.12E-5

<LLD 7.59E-6' -LLD cobalt-58 Ci 5.36E-3 8.OOE-4 2.78E-3 2.03E-3.

cobalt-60 Ci 1.20E-2 2.44E-4 2.65E-3 7.41E-4 iodine-131 Ci

<LLD LD

<LLD i6.14E-6 iron-55 Ci 7.38E-3

<LLD 5.71E-3 2.08E-3 iron-59 Ci 1.93E-4 6.91E-5 8.33E-5

'7.76E-4 lanthanum-140 Ci

<LLD

.::<LLD manganese-54 Ci 6.85E-4 9.60E-5 7.59E-4-' ;'1.05E-4 molybdenum-99 Ci

<LLD

<LLD -- !, _LLD niobium-95 Ci 2.76E-4 2.82E-4 1.37E-3 -9.83E-5 niobium-97 Ci

<LLD

<LLD 2.08E-5 (8.11E-6-,

silver-llOm Ci 8.21E-4 4.28E-6 8.56E 1.67E-4 strontium-89 Ci

<LLD

<LLD strontium-90 Ci

'5LLD..

<LLD

-. <LLD

_.-'LLD technetium-99m Ci

_<LLD

<LLD d

LLD-

-'<LLD tin-117m Ci 6.21E-6 5.43E-6

_<LLD

- <LLD zinc-65 Ci

<LLD

<LLD zirconium-95 Ci

- 1.33E-4

-.1.52E

-6.64E-4

--.<LLD-zirconium-97 Ci

<LLD

<LLD 2.88E-5

<LLD Total for period Ci 3.47E-2 2.44E-3 1.75E-2 7.96E-3

2. Dissolved and entrained gases krypton-85 Ci 1.06E-1 1.59E-2 5.51E-2

<LLD xenon-131m Ci 4.96E-3

<LLD 4.57E-3

<LLD xenon-133 Ci 1.58E-1 3.64E-4 1.66E-1 2.02E-4 xenon-133m Ci 2.65E-4

<LLD 7.70E-4

<LLD xenon-135 Ci 2.33E-5

<LLD

<LLD Total for period Ci 2.69E-1 1.62E-2 2.26E-1 2.02E-4 LLD Lower Limit of Detection; see Table 2C. ' -

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

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

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

3. gross alpha I.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

LIQUID EFFLUENTS-LOWER LIMIT BATCH MODE OF DETECTION-Ra'di onucl ides

'lLLD (kCi/cc)

1. Fission and activation products antimony-124 2.10E-7 barium-140 2.30E-7 cerium-141 4.OOE-8 cerium-144

-1.70E cesium-134 6.80E-8 cobalt-57 2.20E-8 iodine-131 4.30E-8 iron-55 1.00E-6 lanthanum-140

_--_-_--_--_,__-__---_-_-_-1_._60E-__7 molybdenum-99 2.70E-8 niobium-97 1.40E-7 strontium-89 5.00E-8

--strontium-90

-5.00E-8 technetium-99m 2.70E-8

.tin-117m 2.30E-8 zinc-65 1.50E-7 zirconium-95 1.OOE-7 zirconium-97 1.50E-7

2. Dissolved and entrained gases krypton-85 2.90E-5 xenon-131m 3.OOE-6 xenon-133m 6.90E-7 xenon-135 8.90E-8

3. gross alpha 1.OOE-7 II ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 2 and 3 TABLE 2D LIQUID EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOLINDARY F

Unit First Quarter.I Second Quarter Third Quarter Fourth Quarter A.

1. Total body dose mrem 2.82E-3 1.71E-4 1.20E-3 8.90E-4

2. Percent Applicable Limit 9.39E-2 5.70E-3 3.99E-2 2.97E-2 B.

1. Limiting organ dose mrem 9.01E-3 5.58E-4 5.49E-3 4.43E-3

2.

Percent Applicable Limit 9.01E-2 5.58E-3 5.49E-2 4.43E-2

3. Limiting organ for period

=

GI/LLI GI/LLI GI/LLI GI/LLI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

SUMMARY

12 month period-

1. Number of batch releases:

117 releases

2. Total time period for batch releases:

19995 minutes

3. Maximum time period for a batch release:

1475 minutes

4. Average time period for a batch release:

171 minutes

5. Minimum time period for a batch release:

45 minutes

6. Average saltwater flow during batch releases:

735256 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None.

-U ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

1. Type of waste Unit period error (%)

a. Spent resins, filter sludges

m3 1.84E+O Ci 5.09E+1 3.00E+1

b. Dry active waste (DAW),

in 3

4.23E+1 compactable and non-compactable **

Ci 9.63E-1 3.00E+1

c. Irradiated components, control m

3 N/A rods Ci N/A N/A

d. Other: Filters **

m3 1.80E-1 Ci 1.00E-3 3.00E+1 Note: Total curie content estimated.

Material packaged in Type A containers.

Material packaged in strong tight containers of various sizes.

N/A No shipment made.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

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

a. americium-241 7.OOE-4

-antimony-125

. 2.17E+O carbon-14 1.65E+O cerium-144 3.35E-2 cesium-134 1.65E+O cesium-137 1.98E+1 chromium-51 8.10E-3 cobalt-57 7.31E-2 cobalt-58 3.60E-3 cobalt-60 7.74E+O curium-243/244 7.OOE-4 iodine-129

%7.20E3 iron-55 8.24E+O manganese-54 4.07E-2 nickel-63 5.85E+1 plutonium-238 7.OOE-4 plutonium-239/240 3.OOE-4

_plutonium-241 1.67E-2 strontium-89 7.OOE-4 strontium-90 1.06E-1 technetium-99

%1.60E-3 tritium 4.38E-2

'I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

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

b. americium-241 1.70E-3 antimony-124 1.73E-1 antimony-125 1.36E+O carbon-14 1.98E+O cerium-144 1.71E-1 cesium-134 2.04E+O cesium-137 8.09E+O chromium-51 6.05E+O cobalt-57 1.37E-1 cobalt-58 2.03E+1 cobalt-60 8.48E+O curium-242 1.OOE-3 curium-243/244 2.30E-3 iodine-129 1.OOE-4 iron-55

__2.25E+1 iron-59 1.18E+O manganese-54 1.50E+O nickel-59 1.42E-1 nickel-63 2.12E+1 niobium-95 2.74E+O plutonium-238 1.20E-3 plutonium-239/240 1.OOE-3 plutonium-241 9.36E-2 strontium-89 4.10E-3 strontium-90 3.32E-2 technetium-99 2.20E-3 tritium 1.39E-1 uranium-233/234 1.OOE-4 zirconium-95 1.64E+O

c.

not applicable N/A

d.

antimony-125 3.59E-1 carbon-14 2.65E+O cesium-134 9.07E-1 cesium-137 5.60E+1 cobalt-60 6.19E+O iron-55 1.36E+1 manganese-54 1.OOE-2 nickel-63

__2.O1E+1 plutonium-241

__1.79E-1 strontium-90

__1.OOE-2 tritium 3.98E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

3.

Solid Waste Disposition l

Number of Shipments Mode of:Transportation Destination 9

TAG Transport 2**

TAG Transport Studsvik/EnviroCare, UT 2Truck/Flatbed Trailer Studsvik/Barnwell, SC 1

TAG Transport Truck/Flatbed Trailer EnviroCare, UT SONGS maintains a contract with Duratek that provides volume reduction services. The processed volume was shipped from the Duratek facility to EnviroCare using 61 shipments.

Those 61 shipments included waste from other generators. SCE's waste volume was a small fraction of the total waste volume of these shipments.

SONGS maintains a contract with Studsvik that provides volume reduction services. The processed volume was shipped from the Studsvik facility to EnviroCare and Barnwell using 1 and 6 shipments, respectively. Those, 7 shipments included waste from other generators.

SCE's waste volume was a small fraction of the total waste volume of these shipments.

A.

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 (2004)

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

% Applicable Limit where:

Rel Rate X/Q o

MPCeff

=

(Rel Rate)

(X/Q)

(100)

MPCeff

=

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.

4.80E-6 sec/m3; the annual average atmospheric dispersion defined in the Units 2&3 ODCM.

l n

Fi 1

i i-MPC i where:

Fj

=

fractional abundance dividing the activity by the sum of all the of the ith radionuclide obtained by (curies) for each radionuclide, C1, isotopic activity, C T-n

=

total number of radionuclides identified MPC1

=

Maximum Permissible Concentration (MPC) radionuclide from 10 CFR 20 (20.1-20.602),

Table II, Column 1.

of the i "

Appendix B, a ECL

=

(Rel Rate) (X/0)

(100)

ECLeff where:

Rel Rate X/Q

° ECLeff where:

F,

=

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.

=

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

1 n

F.

i-ECL i

=

fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, C1, by the sum of all the isotopic activity, C T.

n

ECL,

=

total number of radionuclides identified

=

Effluent Concentration Limit (ECL) of the it" radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

Dii Conc o

MPCeff

=

(DiI Conc) (100)

MPCeff 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.

.1 MPC i

=

fractional abundance of the it' radionuclide obtained by dividing the activity (curies) for each radionuclide, C,,

by the sum of all the isotopic activity, C T.

=

total number of radionuclides identified where:

F, n

MPC,

=

Maximum. Permissible Concentration (MPC). of. the radionuclide from 10 CFR 20 (20.1-20.602), Appendix Table II, Column 2.

B th B,

% ECL

=

(Dil Conc) (100)

ECL,ff where:

Dil Conc

° ECLeff

=

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

=n Fi ih

=

fractional abundance of theith radionuclide obtained by dividing the activity (curies) for each radionuclide, C1, by the sum of all the isotopic activity, C a.

=

total number of radionuclides identified

-=

Effluent Concentration Limit (ECL) of the ith'radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 2.

where:

F, n

ECL, ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

Sources of error for gaseous effluents -

batch releases are:

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

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

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

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

12 2

22 Total Error

=

+

C2

+ C3

+

where:

G1

=

Error associated with each component.

ANNUAL RADIOACTIVE EFFLUENT'RELEASE REPORT (2004)

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

Six different categories are presented:

(1) Liquid Effluents - Whole Body (2) Liquid Effluents - Organ (3) Airborne Effluents - Tritium, Iodines and Particulates (4) Noble Gases -Gamma (5) Noble Gases -

Beta (6) Direct Radiation The doses for categories 1 and,2 were calculated using, the methodology of the. ODCM; 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, *and 5 using methods described in the ODCM and -the historical meteorol'ogy (X/Q)., Category 6 presents direct dose data measured by TLD dosimeters. Each portion of each category is footnoted to briefly describe each maximum individual dose presented.-

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

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

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 (2004)

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

First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS

1)

2)

3)

4) 5)

Whole Body 2.82E-3 1.71E-4 1.20E-3 8.90E-4 5.07E-3

6)

7)

8)

9) 10)

Organ 9.01E-3 5.58E-4 5.49E-3 4.43E-3 1.95E-2 AIRBORNE EFFLUENTS

11)

12)

13)

14) 15)

Tritium, lodines, and Particulates 1.56E-3 5.89E-4 1.07E-3 1.11E-2 1.29E-2 NOBLE GASES

16)

17)

18)

19) 20)

Gamma 3.57E-2 7.46E-3 2.76E-2 1.04E-2 8.11E-2

21)

22)

23)

24) 25)

Beta 3.76E-2 9.39E-3 1.76E-2 3.57E-2 1.OOE-1

26)

27)

28)

29) 30)

DIRECT RADIATION 1.07E-1 8.21E-2 1.18E-1 9.45E-2 3.68E-1 The numbered footnotes below briefly explain how each organ and the predominant pathway(s).

Noble gas doses due to airborne effluent are in units

1. This value was calculated using the methodology of the

2. This value was calculated using the methodology of the

3. This value was calculated using the methodology of the

4. This value was calculated using the methodology of the

5. This value was calculated using the methodology of the maximum dose was calculated, including the of mrad, reflecting the air dose.

ODCM.

e ODCM.

ODCM.

ANNUAL RADIOACTIVE'EFFLUENT RELEASE REPORT (2004)

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

6.

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

7.

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

8.

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

9.

This value was calculated using the methodology of -the ODCM; the GI-LLI received the maximum dose

primarily by the saltwater fish pathway.

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

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

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

15. The-maximum organ dose was to an infant's thyroid and was located in the NNE sector. This was calculated using the assumptions of USNRC Regulat6ry 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. i

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 radiatio'nwas located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

20. The-maximum air dose for gamma radiation wvas-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 locatedi 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.

g ffi ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

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

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

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

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

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

TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 9.39E-2 5.70E-3 3.99E-2 2.97E-2 8.46E-2 Organ 9.01E-2 5.58E-3 5.49E-2 4.43E-2 9.75E-2 AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 1.04E-2 3.93E-3 7.10E-3 7.41E-2 4.29E-2 NOBLE GASES Gamma 3.57E-1 7.46E-2 2.76E-1 1.04E-1 4.06E-1 Beta 1.88E-1 4.69E-2 8.78E-2 1.79E-1 2.51E-1 specifically addressed in the NOTE: Di rect Radi ati on i s not Applicable Limits.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

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

CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 26, 2004, Revision 39 to the Units 2/3 Offsite Dose Calculation Manual (ODCM) was adopted and published. This change incorporated 1) Removing the reference to the specific software used to calculate off-site doses using concurrent meteorology ;

2) Updates related to the recent Land Use Census (LUC),

and 3) Identified members of the public staying at Camp Mesa.

Per NRC Generic Letter 89-01, no Effluent/ODCM Evaluation or 50.59 reviews were required or performed for editorial changes made to reflect actual plant operation.

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

The level of radioactive effluent control required by 10CFR2O, 40CFR190, 10CFR50.36a, and Appendix I to 10CFR50 will be maintained.

Throughout A

D F

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

Addition Deletion Editorial/Format change Revision Page Change Reason 2-26 Removed reference to type of software used to calculate offsite dose R

using concurrent meteorology. This item is controlled by site programs and procedures.

2-28 Removed reference to type of software used to calculate offsite dose R

using concurrent meteorology. This item is controlled by site programs and procedures.

2-31 Changed Controlling Location Factors per LUC and corrected footnote R

format 2-34 to Renumbered sector Q page numbers due to deletion of a table F

2-39 2-37 Per LUC, outage worker is no longer at this location so this page is D

deleted 2-3.

Per LUC, this location is renamed Beach Complex R

2-42 Per LUC, this location is renamed Camp Mesa R

2-54 Clarified footnote format on Table 2-17 F

5-15 Changed name of TLD # 23 to better reflect location R

6-2 Added Camp Mesa residents to category of Members of the Public R

'I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 2 and 3 SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS There were no changes to the Units 2&3 Radioactive Waste Treatment Systems during the reporting period, January 1, 2004 to December 31, 2004.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 2 and 3 SECTION K. MISCELLANEOUS Unplanned leakage from the Waste Gas System At approximately 0630 on 6/28/04, the'oncoming radwaste operator noted that the in service decay tank pressure was decreasing. The valve lineup was immediately verified and then a more extensive walkdowhn of the waste gas system performed.

At 1205, the leaking valve was identified and closed.

A vent path for a clearancein the PASS lab was established at 0343 on 6/28/04 and allowed a previously unidentified leaking isolation' valve to vent the in-service waste gas decay tank.

A PVS gas grab sample taken at 1012 during the release identified Xe-133 at 2.14E-7 uCi/cc. The curies and dose inadvertently released during this event were accounted for in permit # 4G-102-0; gamma dose of 8.17E-5 mrad, beta dose of 2.43E-4 mrad.

The release was' below'the assumed continuous release rates' via the PVS and the monitor did not alarm at any point during the release. In addition, the release would not have exceeded any of the setpoints that would have been calculated in a release permit.

This event is documented in AR 040601883.

^

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2004 - December 31, 2004 S.O.N.G.S. 2 Monitor Inoperability Period Inoperability Cause Explanation 2RT-7870 04/17/00 - present Inoperable process Design deficiency causes process Condenser Air flow measuring flow instrument to be inoperable Ejector Process device whenever while the vacuum pump is running.

Flow Monitor vacuum pump is Substitute flow value is running.

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

2RT-7817 02/18/04 - 4/23/04 Detector components Floor plug above monitor removed BPS/FFCPD damaged from for unrelated maintenance allowed Discharge Monitor rainwater.

rain water to damage monitor.

Individual electrical components checked for operability. Found flow meter also required corrective action. Protective shelters are being fabricated. This event is documented in ARs 040201606, 040301998 and 040202006.

05/01/04 - 06/10/04 Flow meter Cleaned debris from sensing lines.

inoperable Performed calibration. This event is documented in AR 040500018.

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 2--and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2004 - December 31, 2004 S.O.N.G.S. 3 Monitor Inoperability Period Inoperability Cause Explanation 3RT-7870 04/17/00 -

present In6perable process Design deficiency causes process Condenser Air flow measuring flow instrument to be inoperable Ejector Process device whenever while the vacuum pump is running.

Flow Monitor vacuum pump is Substitute flow value is running.'

automatically inserted whenever the vacuum pump is.

running as high flow values are not sensed. Flow monitor works properly during normal operations. This event is documented inmARs'000101252 and 000400960.

3RT-7817 10/20/04 -

12/28/04 Inoperable process Flow integrator records flow with BPS/FFCPD flow measuring none in progress. Repairs were made Discharge Monitor device :

but required a release'to verify instrument calibration.'Due to the outage, no releases were made for several weeks. This event is documented in ARs 041001845 and 041002248.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

S.O.N.G.S. 2 and 3 SECTION L. S.O.N.G.S. 2 and 3 CONCLUSIONS Gaseous releases totaled 1.83E+2 curies of which noble gases were 1.22E+2 curies, iodines were 6.42E-3 curies, particulates were 4.62E-4 curies, and tritium was 6.12E+1 curies.

The radiation doses from gaseous releases were: (a) gamma air dose: 8.11E-2 mrad at the site boundary, (b) beta air dose: 1.OOE-1 mrad at the site boundary, (c) organ dose: 1.29E-2 mrem at the nearest receptor.

Liquid releases totaled 1.89E+3 curies of which particulates and iodines were 6.25E-2 curies, tritium was 1.89E+3 curies, and noble gases were 5.12E-1 curies.

The radiation doses from liquid releases were: (a) total body: 5.07E-3 mrem, (b) limiting organ: 1.95E-2 mrem.

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

COMMON

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

COMMON COMMON RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A.

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

Estimated

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

a. Spent resins, filter m

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

b. Dry active waste (DAW),

m3 N/A compactable and non-Ci compactable eN/AN/A m3 N/A

c. Irradiated components Ci N/A N/A in 3

N/A

d. Other (filters)

Ci N/A N

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 I

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

COMMON A.

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

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

Number of Shipments Mode of Transportation Destination None N/A N/A IRRADIATED FUEL SHIPMENTS (Disposition)

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

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 (2004)

COMMON COMMON RADWASTE SHIPMENTS ADDENDUM 2003 A review of 2003 shipping data showed that a shipment of common DAW should have been characterized as "Other: filters". The entire, corrected common shipment section is reproduced:

TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) 12 month Estimated total

1.

Type of waste Unit period error (%)

a. Spent-resins, filter sludges,.

m3 N/A evaporator bottoms Ci N/A N/A

b. Dry active waste (DAW), -

-M 3

4.79E+1 compactable and non-compactable

Ci 4.18E-2 3.00E+1

c. Irradiated components (Reactor m3 N/A insulation)

Ci N/A N/A

'd. Other: (Filters) #

m3 8.92E+O Ci 2.20E-2 3.00E+1 NOTE: Total curie content estimated.

Material packaged in Type A casks or strong tight containers of various sizes.

I Material packaged in strong tight-containers.

N/A No shipment made.

-IL ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

COMMON COMMON RADWASTE SHIPMENTS ADDENDUM 2003 (Cont'd)

2. Estimate of major nuclide composition (by type of waste) 2003 Common

a. not applicable N/A

b. americium-241 6.92E-2 carbon-14 2.89E-2 cerium-144 5.79E-2 cesium-134

__1.35E-2 cesium-137 6.82E-2 cobalt-58 5.07E-1 cobalt-60

__8.20E+1 curium-242 2.97E-4 curium-243/244 2.20E-2 iron-55 9.OOE+O manganese-54 9.52E-2 neptunium-237 1.78E-1 nickel-59

__2.92E-2 nickel-63 6.36E+O plutonium-238 1.08E-1 plutonium-239/240 3.81E-2 plutonium-241 1.31E+O plutonium-242 2.85E-4 strontium-90 1.56E-1 technetium-99 3.64E-2 tritium 2.85E-3

c. not applicable N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

COMMON COMMON RADWASTE SHIPMENTS ADDENDUM 2003 (Cont'd)

2. Estimate of major nuclide composition (by type 'of waste) 2003 Common

d. americium-241

-'8.95E-2 antimony-125 6.27E-1 carbon-14 -%

---1.02E+O cerium-144-8.77E-2 cesium-134 4.37E+O cesium-137 1.37E+1 cobalt-57

1.14E-1 cobalt-58

-7.14E+O cobalt-60 ^,

2.84E+1 curium-242 9.27E-3 curium-243/244 4.55E-2 iron-55 3.11E+1 0

manganese-54 I

1.51E+O nickel-63 5.36E+O niobium-95 6.32E-1 plutonium-238 6.45E-2 plutonium-239/240 2.OOE-2 plutonium-241 1.75E+O plutonium-242 1.27E-4 ruthenium-106 1.02E-1 silver-llOm 2.41E-1 strontium-90 1.07E+O tin-113 2.OOE-1 tritium 1.30E-1 uranium-233/234 5.73E-4 uranium-235 2.60E-5 uranium-238 1.77E-4 zinc-65 1.85E+O zirconium-95 4.55E-1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

COMMON COMMON RADWASTE SHIPMENTS ADDENDUM A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Cont'd)

(Not Irradiated Fuel)

3. Solid Waste Disposition (2003 Common)

Number of Shipments Mode of Transportation Destination 3

TAG Transport EnviroCare, UT TruckI 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 I

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

COMMON COMMON 40 CFR 190 REQUIREMENTS Table 1 below presents the annual site-wide doses and percent of ODCM Specification limits to members of the public.

These values were calculated utilizing doses resulting from all effluent pathways and direct radiation.

The different categories presented are: (1) Total Body, (2) Limiting-Organ, and (3) Thyroid.

Dose Category' Units Year

1.

Total Body

a. Total Body Dose mrem 4.09E-1

b. Percent ODCM Specification Limit 1.64E+O

2. Limiting Organ ;_,'-,__',,_;',,_

a. Organ Dose (Bone) mrem 5.71E-2

b. Percent ODCM Specification Limit 2.28E-1

3. Thyroid

a. Thyroid Dose mrem 1.32E-2

b.

Percent ODCM'Specification Limit 1.76E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

COMMON COMMON CONCLUSIONS Gaseous releases from S.O.N.G.S. 1, 2 and 3 totaled 1.88E+2 curies of which noble gases were 1.26E+2 curies, iodines were 6.42E-3 curies, particulates were 4.72E-4 curies, and tritium was 6.14E+1 curies.

Liquid releases from S.O.N.G.S. 1, 2 and 3 totaled 1.89E+3 curies of which particulates and iodines were 6.80E-2 curies, tritium was 1.89E+3 curies, and noble gases were 5.12E-1 curies.

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

S.O.N.G.S. 1, 2 and 3 made 71 radwaste shipments to Envirocare, UT and 4 shipments to Barnwell, SC.

Total volume was 1.08E+3 cubic meters containing 3.05E+2 curies of radioactivity.

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

Meteorological dispersion was good 36% of the time, fair 40% of the time and poor 24% of the time.

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

COMMON APPENDIX`'A GASEOUS EFFLUENTS -

APPLICABLE LIMITS A. Table IA lists the total curies relea'sed and the release 'rate. The percent of applicable'limit compares the relesed 'conrcentrations to'the concelntration limits of 1O'CFR 20', Appendix B, 'Table II, Column-1. -

B. Table 1E lists the dose due to noble reactor) to areas following values:

air doses as calculated using the historical" X/Q.

The air gases released in gaseous effluents from S.O.N.G.S.

(per at and beyond the site boundary shall be limited to the

~

1.

During any calendar quarter:

~5

10

'_10

20 mrad mrad for gamma radiation and for beta radiation.

2. During any calendar year:

mrad for gamma radiation and mrad for beta radiation.

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

1. During any calendar quarter:

2. During any calendar year:

7.5 mrem to any organ.

15 mrem to any organ. -.1

1L ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

COMMON APPENDIX A (Continued)

LIQUID EFFLUENTS - APPLICABLE LIMITS A. Table 2A lists the total curies released, the diluted concentration, and percent of the applicable' limit.

The percent of applicable limit 'compares the diluted concentration of radioactive material released to the' concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for 'radionuclides other than dissolved or entrained gases.

For dissolved or entrained noble gases, the concentration is limited to 2.OOE-4 yCi/ml.

I B. Table 2D lists doses due to liquid releases. The d6se commitment to a Member of the Public from radioactive materials in liquid effluents released from S.O.N.G.S. (per reactor) to unrestricted areas shall be limited to the following values:

1. During any calendar quarter:

2. During any calendar year:

1.5 mrem to the total body and

5 mrem to any organ.

3 mrem to the total body and

10 mrem to any organ.

METEOROLOGY

METEOROLOGY The meteorology of the San Onofre Nuclear Generating Station for each of the four quarters, 2004 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, 2004.

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 (2004)

METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 04010100-04033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A

.EXTREMELY UNSTABLE (DT/DZ s -1.9 °C/100 METERS)

WIND

.22-51-.76--.

1.1-

-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50 r75 1.0 1.5 2.0 '

'3.0

. 5.0 7.0 10.0 13.0 18.0 N

0' 0

1 0

2 0

0 0

3 NNE 0

0 0

0' 0

0 0

NE 0

1 0

0 1

0' 1

1 0

0 0

0 4

ENE 0

0 0

E 0

0 0

0 0'

0 0

ESE 0

0 0

1 0:

0 0

0 1

SE 0

0 0

1 0

2 3

0 0

0 6

SSE 0

0 0

0 2

4 8

2 0

0 0'

0 16 S '

0 0

2 13 12 1

0 0

28 SSW 0

0 0

3 2'

10 12 0

0 0

27 SW 0

0 0

1 9

48 10 0

0 0

68 WSW 0

0 0

4 14 48 8

0 0

0 74 W

0 0

13 83 57 4

0 0

157 WNW 0

0 0

0 5

25 39 10 0

0 0

0 79 NW 0

0 0

0 3

2 4

0 0-0 0

0 9

NNW 0

0 0

0 1

0' 0

0 0

0 1

TOTALS 0

1 1

9 54 236 154 18 0

0 0

0 473 NUMBER OF VALID HOURS 473 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 473 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ s -1.7 °C/100lMETERS)

WIND

.22-..51-

'.76-1.1-1.6-

.:2.1-3.1-

-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0

.3.0 5.0

'7.0 10.0 13.0 : 18.0 N

0 0

2.

0 0

0 2

NNE 0

0 0

2 0

1 0

0 0

0 3

NE 0

0 0

0' 0 0

0 0

0 ENE 0

0 0

0 1

0 0

0 1

E 0

0 0

1:

0 0

0 1

ESE 0

0 0

0 0'

0 0

SE 0

0 0

0 0'

0' 2

0 0

0 2

SSE 0

0' 0 0

0 0

5 0

0 0

5 S

0 0

1 1

0 4

1 0

0 0'

0 7

SSW 0

0 0

1 0

4 4

0 0

0 9

SW 0

0 0

2 2'

1 5

1' 0

0 0

0 11 WSW 0

0 0

1 2

0 1

0 0'

0 0

0

'4 W

0 0

1 0

0 0

0 0'

0 0

1 WNW 0

O 0

0 1

.3' 0

1 0

0 0

0 5

NW

0.

O 0

0.

0 1

1 0

0 0

2 NNW 0

0 0

1 0

0' O

0 0

0 1

TOTALS 0

0 1

9 9

10 22 3

0 0

54 NUMBER OF VALID HOURS 54:t NUMBER OF INVALID HOURS 0

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD I 0o 54

-9o0-

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 04010100-04033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ s -1.5 'C/100 METERS)

WIND

.22-

.51-

.76-

.1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

1 2

0 0

3 NNE 0

0 0

2 0

0 0

0 2

NE 0

0 0

1 0

0 0

0 1

ENE 0

0 0

E 0

0 0

ESE 0

0 0

1 1

1 0

0 0

0 3

SE 0

0 0

1 1

0 1

0 0

0 3

SSE 0

0 0

0 1

7 6

2 0

0 0

0 16 S

0 0

0 1

3 1

10 3

0 0

18 SSW 0

0 0

1 2

4 1

0 0

0 8

SW 0

0 0

1 1

0 2

0 0

0 4

WSW 0

0 0

5 3

0 0

0 8

W 0

0 1

1 3

5 0

0 0

0 10 WNW 0

0 0

2 1

7 0

0 0

0 10 NW 0

0 0

1 1

1 3

0 0

0 6

NNW 0

0 1

1 1

1 0

0 0

0 4

TOTALS 0

0 2

15 18 32 23 5

1 0

0 0

96 NUMBER OF VALID HOURS 96 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 96 PASQUILL D NEUTRAL (-1.5 < DT/DZ s -0.5 °C/100 METERS)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

0 7

8 10 6

0 0

0 31 NNE 0

0 1

5 6

16 14 4

0 0

46 NE 0

0 0

2 2

5 1

1 0

0 0

0 11 ENE 0

0 0

1 1

0 0

0 4

E 0

0 1

3 3

7 1

1 0

0 0

0 16 ESE 0

0 2

4 2

10 8

5 2

0 0

0 33 SE 0

0 1

5 7

15 44 14 7

0 0

0 93 SSE 0

0 0

2 1

19 37 21 6

1 0

0 87 S

0 0

0 1

3 13 13 6

4 1

0 0

41 SSW 0

0 0

1 3

5 6

1 2

0 0

0 18 SW 0

0 3

5 4

2 1

0 0

1 0

0 16 WSW 0

0 1

6 3

1 6

0 0

0 17 W

0 0

1 1

3 7

7 2

0 0

21 WNW 0

0 0

5 8

7 19 6

2 0

0 0

47 NW 0

0 1

6 1

17 15 2

0 0

42 NNW 1

0 0

10 7

13 1

0 0

0 32 TOTALS 1

0 11 64 62 148 180 63 23 3

0 0

555 NUMBER OF VALID HOURS 555 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 555 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

METEOROLOGY January -March TABLE 4A SITE: SAN;ONOFRE PERIOD OF.RECORD 04010100-04033123 WINDSPEED (M/S) AT lO'METER LEVEL '

PASQUILL E' SLIGHTLY STABLE. (-0.5 < DT/DZ;s 1.5 °C/100METERS)

WINDU DIR N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W.

WNW 22-1

.50 0

0 0 '1 0

0.

0 0

0

.51-

'.75 0

1 0

0 0

0 1

0

..76-

', 1.0 2

0 0

1 0

0 0

1

.1.1-.

1.5 5

8 7

3 5

2 4

2 0

1 3

1 2

1 1.6-2.0 5

22 4

4 4

1 4

0 3

2 2

2 3

6 2.1-3.0 10 36 2

2 7

5 0

0 1

1 1

3 2

6

.3.1-

, 5.0 6

-12

1.

1 2

4 9

1 0

0 0

2 5.1-7.0 0

1 1

0 0

1 0

0 0

1 7.1-10.0 0

0 1

0 0

1 0

0 0

0 lO.l1-

13. 1-.>1

-13.0 0

0 0

0 18.0 0

'0 0

0 0

0

.0 0

.8 TOTAL' O

28 O

80 O

16 0

11' 0

18 0

13-0 17 O

4 0

5 O

6 O

6 0

8 0

17

I NW 0

2 0

3 5

5 3

3 2

O U

U 23 NNW 0

0 2

2 1

6 4

0 0

0 -

0 0

15 TOTALS 0

4 6

49 68 87 46 7

4 0 : 0 0

'271 NUMBER OF VALID HOURS 271 NUMBER OF CALMS' 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 271 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ s 4.0 °C/100 METERS)

WIND

.22-

.51-

.76--

1.1-1.6-'.2.1-3.1-5.1-7.1-- 10.1-13.1-

>18 TOTAL DIR

.50

.75 1.;0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 1

1..

4 5

6 2:

0 0

0 19 NNE 0

0 3

10 33

.65

-13 1

0 0

125 NE 0

0 1

7.

7 6.1 1

0 0

23 ENE 0

0 0

4 6

3 1

0 0

0 14 E

0 0

0 5

4 5

0 0

14 ESE 0

0 1

0 2

2.r 0 0

0 0

5 SE 0

0 1

1 1

2 0

0

'0 0

0 0

5 SSE.

0 0

1 3

1 0

0 O ;

0 0

5 S

0 0

0 4

0 0

0 O.0 0

0 0

0 4

SSW 0

0 0

1,

1 1

0 0

0 3

SW 0

0 0

2 3

I 0

0 0

0:0 0

6

WSW, 0

0 0

1 1 -

1 0

0 0

0

., 0 0

3:

W 0

O 0

2 4

2 0

0

.0 0

0 0

8 WNW 0

0 0

2.

11 5 0

0 0

O 0

0 0

8 NW 0

0 0

2 3 ;

4 4

0 0

0 0 : 0 13 NNW 0

1 2

5 2

2

. 0 0

0 0

12 TOTALS

'0 2

9 50 73 108 23 2

0 O

O 0

267 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 267!

0 NUMBER OF CALMS.

0 O

TOTAL HOURS FOR THE PERIOD.267

-92.-.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 04010100-04033123 WIND SPEED (M/S) AT 10 METER LEVEL P

WIND DIR N

NNE NE ENE E

ESE SE SSE S.

SSW SW WSW W

WNW NW NNW

.22-

.50 10 0

0 0

0 1

0

.51-

.75 0

0 0

2 1

0 0

1 0

2 0

0 0

0

.7 1.

EXTREMELY STABLE (

6-1.1-1.6-0 1.5 2.0 3

5 2

1 8

26 1

5 13 2

6 2

2 1

0 6

1 1

0 0

1 1

1 2

2 1

1 0

0 1

2 0

0 4

2 1

0 1

1 2

1 O

0 1

ASQUILL G DT/DZ > 4 2.1-3 3.0 5

7 135 1

19 2

1 2

4 1

0 2

0 0

3 2

0 3

.1-

.0 5

31 8

1 2

0 2

0 0

2 0

2 1

1 0

1 5.1-7.0 0

8 0

0 0

0

.0 °C/100 METERS) 7.1-10.0 0

0 0

0 10.1-13.0 0

0 0

0 13.1-18.0 0

0 0

0

>18 TOTAL 0

23 0

309 0

46.

0 15 0

9 0

8 0

3 0

5 0

7 0

3 0

6 0

10 0

5 0

5 TOTALS 2

6 15 39 61 181 156 8

0 0

468 NUMBER OF VALID HOURS 468 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 468 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

1 1

7 21 25 35 19 0

0 0

109 NNE 0

1 5

33 87 255 170 14 0

0 0

0 565 NE 0

1 2

22 27 32 12 4

1 0

0 0

101 ENE 0

2 3

14 14 8

4 0

0 0

45 E

0 1

3 15 13 20 5

1 0

0 0

0 58 ESE 0

0 4

7 12 21 12 5

3 0

0 0

64 SE 0

0 3

12 12 24 61 14 8

0 0

0 134 SSE 0

0 0

5 6

34 58 26 6

1 0

0 136 S

0 0

1 9

14 28 39 11 4

1 0

0 107 SSW 0

1 1

9 9

27 27 1

2 0

0 0

77 SW 0

0 3

15 23 53 18 1

0 1

0 0

114 WSW 0

2 1

20 25 53 17 0

0 0

118 W

0 1

3 10 28 102 65 6

0 0

215 WNW 0

0 2

10 23 55 61 18 2

0 0

0 171 NW 1

2 2

14 14 30 30 5

2 0

0 0

100 NNW.

1 1

5 19 13 25 6

0 0

0 70 TOTALS 3

13 45 235 345 802 604 106 28 3

0 0

2184 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2184 0

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0

2184 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

METEOROLOGY April - June TABLE 4A SITE:-'SAN ONOFRE PERIOD OF RECORD 04040100-04063023 WIND SPEED (M/S)'ATfIO METER LEVEL fPASQUILL A

... _.... EXTREMELY UNSTABLE (DT/DZ s -1.9 °C/IOO METERS)

WIND

.22-

.51- :,.76-

.1.1-1.6-.

2.1-.r.

3.1-5.1-7.1-10.1-. 13.1-

>18 TOTAL DIR

.50

.75-:- -1.0

1.5 2.0-' 3.0

-5.0 7.0- -10.0 13.0 -'18.0-N 0

O 0

2 0

O-O' 0

0

0.

Or 0

2 NNE 0

0, 0

0 0-1 0

0 0

0 O'

0 1

NE 0

0 0

07 0

0 0

ENE 0

0 0

0 O

0 0

0' 0

0 0

E 0

0' 0

0 0

3 0

0 0

0

.3 ESE 0

0 0

SE 0

0 0

0.

0 1

0 0

1 SSE 0

0 0

1 0

1.

4, 7

4 0

0.

0 17 S0 0

0 0

3 10 45 22 1

0' 0

0 81 SSW 0

0 1

0 5

11' 62 11 0

0 0

0 90 SW 0

0 0

2 7

35.

69 3

0 0

116 WSW 0

0 0

1 8

76, 72 0

1 0

0 0

158 W0 0

0 0

7; 47 92 0

0 0

146 WNW 0

0 0

0 1

11 40 3

0 0

Or 0

55 NW 0

0 0

1 0'

3:

4 2

0 0

10 NNW O

_.0 O _.. 0 0

0

.0

- 0 0

0 TOTALS--

. 0: --

O --

'-.1 -

7 --

--31:- -198-- -388 49 6

0 0 -

0 680 NUMBER OF VALID HOURS

' 680 NUMBER'OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 680

-..PASQUILL B MODERATELY UNSTABLE (-1.9 <'-DT/DZ s -1.7 °C/100 METERS) '

WIND

-.22-

.51-

.76-1.1- -

1.6---: 2.1- --

3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0' 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

0 O'

0 0

0.

0 0

NNE 0O O

0 0

O 0'

0 0

0 NE 0

0'-

0 0

ENE 0

0' 0

1 ;

O-0 0

0 0

1 E

0 0

0 I

0 0

1 ESE 0

0' 0

0 0'-

O '

0 0

0 SE 0

O O

0 1

2 0,

0 0

0 3

SSE 0

0' 0

1 0',

4 3

2 3

0 0O 0

13.

S' 0

0 0

0 1-4 7

7 1

0 0

0 20 SSW 0

0 0

2 2

3 12 2

0 0

21.

SW 0

O 0

0 3

6 0

0

0.

0 0

0 9

WSW 0

0 0'

0 4

4, 1,

0 1

0 0

0 10 W

0 0'

0 0

0' 4

0 O

O '

O 0

0 4

WNW 0

0 0

0 2'-

2 2

0 0

0 6.

NW 0..

0...

0 1

1 1

1 O.

0 0.O

-O.--

4 NNW 0

O o.. o O.

0 0

-0 TOTALS 0

0 0

4 13 29 27 14 5

0 0

0

.92 NUMBER OF-VALID HOURS NUMBER OF INVALID HOURS 92 0

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0

92 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 04040100-04063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ s -1.5 °C/100 METERS)

WIND DIR N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW

.22-

.50 0

0 0

0

.51-

.75 0

0 0

0

.76-1.0 0

0 0

1.1--

1.5 0

0 0

1 0

2 2

0 0

0 1.6-2.0 0

0 0

3 1

5 0

0 1

0 2.1-3.0 1

1 0

0 0

0 5

6 8

3 4

2 3

1 0

3.1-5.0 0

0 0

0 5

9 11 11 8

3 0

1 7

0 5.1-7.0 0

0 0

0 1

5 7

6 1

0 0

1 0

0 7.1-10.0 0

0 0

3 0

0 0

0 10.1-13.0-0 0

0 0

13.1-18.0 0

0 0

0

>18 TOTAL O*

1 0

0 O

0 0

6 0

22 0

24 0

29 0

13 O

14 O

4 0

5 O

9 O

0 TOTALS 0

0 0

5 10 34 55 21 3

0 0

0 128 NUMBER OF VALID HOURS 128 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 128 PASQUILL D NEUTRAL (-1.5 < DT/DZ s -0.5 °C/100 METERS)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 1

4 9

4 5

0 0

23 NNE 0

0 2

8 4

13 2

0 0

0 29 NE 0

0 0

2 7

4 0

0 0

0 13 ENE 0

0 1

3 3

1 0

0 0

0 8

E 0

1 0

0 6

19 5

0 0

0 31 ESE 0

0 1

2 7

35 15 0

0 0

60 SE 0

0 2

3 7

33 52 12 0

0 0

0 109 SSE 0

0 1

2 4

28 50 24 1

0 0

0 110 S

0 0

3 7

8 26 56 15 1

0 0

0 116 SSW 0

0 1

4 14 23 34 16 0

0 0

0 92 SW 0

2 1

10 11 24 12 0

0 0

60 WSW 1

1 4

9 5

6 7

0 0

0 33 W

0

0.

4 9

7 5

8 1

0 0

.0 0

34 WNW 0

0 2

11 7

2 7

4 0

0 0

0 33 NW 0

1 1

5 5

7 16 2

0 0

37 NNW 0

0 4

6 5

2 3

0 0

0 20 TOTALS 1

6 31 90 104 233 267 74 2

0 0

0 808 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 808 0

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0

808 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

METEOROLOGY April - June TABLE 4A SITE:'SAN ONOFRE PERIOD OF RECORD 04040100-04063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ s 1.5 °C/100 METERS)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

'.75 1.0' 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

1 3

7 2

0 0

13 NNE 0

0 1

9 11 10 1

0 0

0 32 NE 0

1 0

5 0

5 1

0 0

0 12 ENE 0

0 0

4 3

2' 0

0 0

0 9

E 0

0.

0 3

6 15 4

0 0

0 28 ESE 0

1 0

0 1

6 1

0 0

0 9

SE 0

0 0

1 2

1 7

0 0

0 11 SSE 0

0 0

1 3

0 2

0 0

0 6

S 0

0 0

3 1

2 0

0 0

0 6

SSW 0

0 0

0 1

1 0

0 0

0 2

SW 0

0 0

2 0

0 0

0 4

WSW 0

0 1

2 0

1 0

0 0

0 4

W 0

0 0

2 2

0 1

0 0

0 5

WNW 0

0 0

3 0

4 8

0 0

0 15 NW 0

0 1

3 1

2 1

0 0

0 8

NNW 0

1 0

4 2'

3 1

0 0

0 11 TOTALS 0

3 4

45 40 56 27 0

0 0

175 NUMBER OF VALID HOURS 175 NUMBER OF CALMS 0

NUMBER OF 'INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 175 PASQUILL F MODERATELY STABLE (1.5 ' DT/DZ's 4.0 !C/100 METERS)

WIND

.22-

.51-

.76-1.1-1.6--

2.1-3.1-5.1-7.1-10.1-

.13.1-

>18 TOTAL DIR

.50

'.75 1.0 1.5 2.0

' 3.0 5.0 7.0 10.0

13.0 18.0-N 0

0 0

4 2

2.

O 0

0 0

8 NNE 1

0 1

5 27' 20 3

0 0'

0 O'

0 57 NE 0

0 1

7 4

2; 0

0 0

0 14 ENE 0'

0 1

1 1

4.

0 0

7 E

0 0

1 0

2 0

0 0

3 ESE 0

0 0

1 0'

1' O

0-0 0

0 0

2 SE 0

0 0

0 2'

1 0

0 0!

0 0

0 3

SSE 0

0 0

2 1

0.

O 0

0

0.

0 0

0 3

S 0

0 1

2 0

o' 0

0 0

3 SSW 0

0 0

2 1-3' 0

0 O'

O' 0

0 6

SW 0

0 0

1 1

0 0

0 0'

0 0

0 2

WSW 0

0 1

1 0

0

.0 0

O' 0

0 0

2 W

0 1

2

1.

0 0

0-0 5

WNW 0

0 0

2 1

4' 0

1 0

0 0

0 8

NW 0

0 1

1

1.

2 3

O 0

0 0

0 8

NNW 0

O'.

0 00 0

01 0

0 0

-1 TOTALS 1

1 7

30 46 40 6

1 0

0 0

0 132 NUMBER OF VALID HOURS

'132 NUMBER OF CALMS O'

NUMBER OF INVALID HOURS'- 0 TOTAL HOURS FOR THE PERIOD 132' ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 04040100-04063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 °C/100 METERS)

WIND DIR NNE NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW

.22-

.50 0

0 0

0

.51-

.75 0

0 0

0 1

0

.76-1.0 0

1 2

1 0

2 1

0 0

1 1

0 0

1.1-1.5 2

4 4

0 4

0 2

1 1

2 2

1 0

0 1.6-2.0 1

6 5

3 1

1 1

0 0

1 3

0 1

2 2.1-3.0 1

65 2

0 1

1 0

1 2

0 0

1 0

3 0

0 3.1-5.0 25 0

0 0

1 0

0 0

0 2

1 5.1-7.0 0

1 0

0 0

0 7.1-10.0 0

0 0

0 10.1-13.0 0

0 0

0 13.1-18.0 0

0 0

0

>18 TOTAL 0

5 0

101 0

12 0

5 0

7 0

2 0

5 0

4 0

2 0

3 0

4 0

3 0

4 0

3 TOTALS 0

0 9

24 27 77 30 1

0 0

169 NUMBER OF VALID HOURS 169 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 169 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 1

5 20 14 11 1

0 0

0 52 NNE 1

0 4

26 48 110 31 1

0 0

221 NE 0

1 2

18 16 13 1

0 0

0 51 ENE 0

0 4

9 10 7

0 0

30 E

0 1

2 7

15 39 9

0 0

0 73 ESE 0

1 1

3 9

43 16 0

0 0

73 SE 0

0 4

6 12 35 65 16 0

0 0

0 138 SSE 0

0 2

8 9

39 69 38 11 0

0 0

176 S

0 0

4 13 14 50 119 51 3

0 0

0 254 SSW 0

0 2

11 26 49 119 35 0

0 0

0 242 SW 0

2 2

17 23 70 89 4

0 0

207 WSW 1

1 7

16 23 92 83 0

2 0

0 0

225 W

0 1

4 14 21 59 101 1

0 0

201 WNW 0

0 2

17 11 29 58 9

0 0

126 NW 0

2 3

10 10 16 34 5

0 0

80 NNW 0

1 4

10 10 5

5 0

0 0

35 TOTALS 2

11 52 205 271 667 800 160 16 0

0 0

2184 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2184 01 NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0

2184 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

METEOROLOGY July -

September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 04070100-04093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A

' EXTREMELY UNSTABLE (DT/DZ s -l.9 °C/100 METERS)

WIND

.22-

.51-

.76-1.1-1.6-2.1- -

3.1-5.1-7.1-10.1-

'13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0

'5.0 7.0 10.0 13.0 18.0 N

0 0

0 NNE 0

0 0

NE 0

0 0

0 1

0 0

0 1

ENE 0

0 0

E 0

0 0

ESE 0

0 0

1 0

0" 0

0 0

0 1

SE 0

0 0

0 2

0 0

0 2

SSE 0

0 0

0 2

4 7

1 1

0 0

0 15 S

0 0

0 1

3 9

27 9

1 0

0 0

50 SSW 0

0 0

1 11 17 32 0

0 0

61 SW 0

0 0

5 17 48 49 0

0 0

119 WSW 0

0 0

5 17 104 74 0

0 0

200 W

0 0

0 4

19 104 149 0

0 0

276 WNW 0

0 0

2 6

19 28 5

0 0

60 NW 0

0 0

0 2

1 0

0 1

0 0

0 4

NNW 0

0 0

0 1

0 0

0 1

TOTALS 0

0 0

19 79 306 368 15 3

0 0

0 790 NUMBER OF VALID HOURS 790 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 790 PASQUILL8B MODERATELY UNSTABLE (-1.9 < DT/DZ s -1.7 °C/100 METERS)

WIND

.22-

.51--

.76-1.1-1.6-2.1- -3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

0 NNE 0

0 0

1 1

0 0

0 2

NE 0

0 0

ENE 0

0 0

E 0

0 0

0' 0

0 0

ESE 0

0 0

0 0'

O';

0 0

0 SE 0

0 0

0' 0

0 0

SSE 0

0 0

0 1

1 3

1 1

0 0

0 7

S 0

0 0

0 1

4 3

0 0

0 8

SSW 0

0 0

0 2

4 5

1 0

0 0

0 12 SW 0

0 0

1 3

8 3

0 0

0 15 WSW 0'

0 0

3 2

5 1

0

.0 0

0 0

11 W

0 0

0 3

1 6

1 0

0 0

11 WNW 0

0.

0 2

3 3

2 0

0 0

10 NW0 0

0 1

0 2

1 0

0 0

4 NNW.

0 0

0o O

O O

O 0

0 TOTALS 0

0 0

11 14 33 19 2

1 0

0 0

80 NUMBER OF VALID HOURS':

80 NUMBER OF INVALID HOURS 0

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD

0 80 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 04070100-04093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ s -1.5 °C/100 METERS)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

0 1

2 2

0 0

5 NNE 0

0 0

0 1

1 0

0 0

0 2

NE 0

0 0

0 1

1 0

0 0

0 2

ENE 0

0 0

E 0

0 0

ESE 0

0 0

0 1

0 0

0 1

SE 0

0 0

0 1

1 0

0 0

0 2

SSE 0

0 0

0 1

6 5

2 0

0 0

0 14 S

0 0

0 1

1 2

3 2

2 0

0 0

11 SSW 0

0 0

1 4

6 4

0 0

0 15 SW 0

0 0

5 8

5 2

1 0

0 0

0 21 WSW 0

0 0

2 5

11 2

0 0

0 20 W

0 0

0 4

11 3

0 0

18 WNW 0

0 1

2 6

2 1

1 0

0 0

0 13 NW 0

0 0

2 5

0 0

0 7

NNW 0

0 0

2 0

0 0

0 2

TOTALS 0

0 1

16 41 43 23 7

2 0

0 0

133 NUMBER OF VALID HOURS 133 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 133 PASQUILL D NEUTRAL (-1.5 < DT/DZ 5 -0.5 °C/100 METERS)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 2

3 7

8 1

0 0

21 NNE 1

0 3

13 24 15 0

0 0

0 56 NE 0

0 0

7 8

1 0

0 0

0 16 ENE 0

0 2

3 1

0 0

0 6

E 0

1 2

6 4

6 1

0 0

0 20 ESE 0

0 4

6 2

16 10 0

0 0

38 SE 0

0 0

9 7

47 19 8

2 0

0 0

92 SSE 0

0 1

11 15 36 23 6

3 0

0 0

95 S

0 0

2 8

19 25 10 0

0 0

64 SSW 0

0 3

16 16 16 4

0 0

0 55 SW 0

5 2

17 10 12 6

0 0

0 52 WSW 0

3 3

17 14 15 4

0 0

0 56 W

1 2

8 16 11 3

6 0

0 0

47 WNW 0

1 4

14 13 6

2 0

0 0

40 NW 0

0 3

7 5

4 6

0 1

0 0

0 26 NNW 0

2 1

9 8

4 3

0 0

0 27 TOTALS 2

16 41 166 165 207 94 14 6

0 0

0 711 NUMBER OF VALID HOURS 711 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 711 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

METEOROLOGY July - September TABLE 4A SITE:-SAN ONOFRE PERIOD OF RECORD 04070100-04093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-O.5 < DT/DZ s 1.5 °C/100 METERS)

WIND

.22-

..51-

'.76-1.1-1.6-2.1-.3.1-5.1-7.1- <10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0

.3.0 5.0 7.0 10.0 13.0 18.0 N

1 1

4 10 6

0 0

0 22 NNE 0

0 3

25 28 27 1

0 0

0 84 NE 0

0 5

7 6

2 0

0 0

0 20 ENE 0

0 2

6 1

3 0

0 0

0 12 E

0 0

0 3

1 3

0 0

7 ESE 0

0 1

0 0

2 0

0 0

0 3

SE 1

1 1

2 2

1 1

0 0

0 9

SSE 0

1 2

1 1

6 0

0 0

0 11 S

0 1

0 3

2 1

0 0

0.

0 0

0 7

SSW 1

0 1

0 0

1 0

0 0

0 3

SW 0

2 1

2 0

1 0

0 0

0 6

WSW 0

0 0

0 1

1 0

0 0

0 2

W 0

0 2

1 0

0 0

0 4

WNW 0

0 1

2 1

1 0

0 0

0 5

NW 0

0 3

1 1

0, 0 0

0 0

5 NNW 0

0 1

4 1

1 3

0 0

O 0

0 10 TOTALS 3

6 27 67 51 51 5

0 0

0 0,

0 210 NUMBER OF VALID HOURS 210 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 210 PASQUILL.F-'

MODERATELY STABLE (1.5 < DT/DZ s 4.0 °C/100 METERS)

WIND

.22-

.51-

.76-1.1-1.6-2.1-

.3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0

.5.0 7.0

10.0 q13.0 18.0 N

0 0

1 3

4 1

1 0 :0 0

0 0

10 NNE 0

0 0

10 36 46 4

0 0

0 96 NE 0

0 1

3 2

2 0

0

-O 0

08 ENE 0

0 2

1 1

2 0

0 0

0 6

E 0

0 0

3 0

1 0

0 0

0 4

ESE 0

0 0

2 0

1 0

0 1

0 0

0 4

SE 0

0 0

1 O

0 0

0 1

SSE 0

0 0

0 1

1 0

0 0

0' 0

0 2

S 0

0 2

2 2

1;0 0

0 0

7 SSW 0

0 0

0 1

0 0

0i0

0.

0 0

1 SW 0

0 0

0

1.

0 O O

O0 0

0 0

0 1

WSW 0

1 1

0 1 i 0

0 0

3 W

0 0

0 O'

O 1

'1 O

O O0 0O 0

2 WNW 0

0 0

1 3

0 0

0 4

NW 0

0 0

O 1

3 o0 0

0 0

4 NNW OKi 0

0 0

0' O

0 0

0O 0.0 0

0 TOTALS 0

1 7

24 50

'61 l 9 0

1 0

0 0

153 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS' 153 0

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 153

-100-' -

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 04070100-04093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 °C/100 METERS)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

0 3

2 0

0 0

5 NNE 0

0 0

0 5

67 30 0

0 0

102 NE 0

0 0

3 1

0 0

0 4

ENE 0

0 0

1 2

0 0

0 3

E 0

0 0

0 1

0 0

0 1

ESE 0

0 0

1 1

0 0

0 2

SE 0

0 0

SSE 0

0 0

2 0

0 0

0 2

S 0

0 1

1 2

0 0

0 4

SSW 0

0 0

1 0

0 0

0 2

SW 0

1 0

0 1

0 0

0 3

WSW 0

0 0

1 0

0 0

0 1

W 0

0 0

1 0

0 0

0 1

WNW 0

0 0

NW 0

0 0

NNW 0

0 0

1 0

0 0

0 1

TOTALS 0

1 1

8 11 76 34 0

0 0

131 NUMBER OF VALID HOURS 131 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 131 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

1 3

8 21 20 7

3 0

0 0

63 NNE 1

0 6

49 95 156 35 0

0 0

342 NE 0

0 6

17 18 9

1 0

0 0

51 ENE 0

0 6

11 5

5 0

0 0

0 27 E

0 1

2 12 6

10 1

0 0

0 32 ESE 0

0 5

10 4

19 10 0

1 0

0 0

49 SE 1

1 1

11 9

49 23 9

2 0

0 0

106 SSE 0

1 3

12 21 56 38 10 5

0 0

0 146 S

0 1

5 16 30 42 43 11 3

0 0

0 151 SSW 1

0 4

19 34 45 45 1

00 0

0 149 SW 0

8 3

31 39 74 61 1

0 0

217 WSW 0

4 4

28 40 136 81 0

0 0

293 W

1 2

10 29 42 118 157 0

0 0

359 WNW 0

1 6

22 29 32 36 6

0 0

132 NW 0

0 6

9 9

12 12 0

2 0

0 0

50 NNW 0

2 2

14 10 7

6 0

0 0

41 TOTALS 5

24 77 311 411 777 552 38 13 0

0 0

2208 NUMBER OF VALID HOURS 2208 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 2208

-101-

ANNUAL'RADIOACTIVE'EFFLUENT RELEASE'REPORT'(2004)

METEOROLOGY October -

December TABLE-4A SITE; SAN ONOFRE PERIOD OF RECORD -04100100-04123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ s -1.9 °C/100 METERS)

WIND

.22-

.51-

.76-1.1-1.6-2.1-..3.1--

5.1-7.1-- 10.1--

13.1- - >18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0

-18.0 N

0 0

0 1

1 0

0 0

2 NNE 0

0 0

1 0

0 0

2 0

0 0

0 3

NE 0

0 0

0 1

1 0

0 0

0 2

ENE 0

0 0

0 1

2 0

0 0

0 3

E 0

0 0

ESE 0

0 0

0 1

0 0

0 1

SE 0

0 0

0 1

0 0

0 1

SSE 0

0 0

0 0-2 12 4

0 0

18 S

0 0

1 2

8 12 17 5

0 0

1 0

46 SSW 0

0 0

2 9

20 12 0

0 0

43 SW 0

0' 0

6 11 33 10 2

0 0

62 WSW 0

0 1

3 19 60-20 3

0 0

106 W

0 0

1 2

12 61 40 0

0 0

116 WNW 0'

0 0

1 4

18 46 5

0 0

74 NW 0

0 0

1 1

2 3

0 0

0 7

NNW 0

0 0

0 1

0 2

0 0

0 3

TOTALS 0

0 3

19 66

-208 r165 24 1

0 1

0 487-NUMBER OF VALID HOURS 487 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE-PERIOD 487 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ s

.-1.7 -C/100 METERS)

WIND

.22-

.51-

.76-1.1-1.6-

-2.1--

3.1-5.1-7.1-10.1-13.1--

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0

-5.0 7.0 :10.0 13.0 18.0 :

I n

n n

1 n

n n

n

.E NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTALS 0

0 0

~0 0

0 0

0 1

0 0

0 1

0 0

3 0

0 1

1 0

0 0

0 1

0 0

0 3

0 0

1 I0 0

-0 i

0 0

. 0 2

f 1

.I 1 0

0 0

1

1.

1 2

1 0

'7 2

3 0

1 0

2 2

0 1

0 0

0 3

1 0

0 0

1 1

0 0

0 1

0 0

3'-

0 1'

0 3-0 1

0 0

0 1'

0 14 0-4-

0 5'-

0 3

0 6

0 0

0 4

-0 3

0 1

0

- 50 u

u u

I u

u u

i 0'

1 I

6 5

' 6i;

&21 7

-2 1'

0 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 50 0

NUMBER OF CALMS-

-0 TOTAL HOURS FOR THE PERIOD 50

-102-'

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 04100100-04123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ s -1.5 °C/100 METERS)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

0 1

0 0

1 NNE 0

0 0

2 0

0 1

0 0

0 3

NE 0

0 0

1 0

0 0

0 1

ENE 0

0 0

1 0

0 0

0 2

E 0

0 0

ESE 0

0 0

SE 0

0 0

2 4

5 1

0 0

0 12 SSE 0

0 1

0 0

0 8

6 4

0 2

0 21 S

0 0

0 1

1 3

4 0

1 2

1 0

13 SSW 0

0 0

2 1

1 2

1 0

0 0

0 7

SW 0

0 0

1 0

0 0

0 3

WSW 0

0 0

6 0

1 2

0 0

0 9

W 0

0 0

3 2

1 0

0 0

0 6

WNW 0

0 0

0 1

1 0

0 0

0 2

NW 0

0 0

0 1

1 2

0 0

0 4

NNW 0

0 0

0 1

0 0

0 1

TOTALS 0

0 1

14 6

15 23 14 7

2 3

0 85 NUMBER OF VALID HOURS 85 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 85 PASQUILL D NEUTRAL (-1.5 < DT/DZ s -0.5 °C/100 METERS)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

1 8

7 3

0 0

19 NNE 0

0 3

14 13 12 6

1 2

0 0

0 51 NE 0

1 0

0 5

5 5

3 1

0 0

0 20 ENE 1

0 1

1 2

0 2

1 1

0 0

0 9

E 0

0 1

1 2

6 1

2 5

0 0

0 18 ESE 0

0 0

1 1

9 18 12 4

1 0

0 46 SE 0

0 1

4 6

10 37 24 10 1

0 0

93 SSE 0

0 1

3 8

18 20 10 3

11 4

0 78 S

0 2

1 4

3 6

12 5

4 2

5 0

44 SSW 0

0 0

5 4

5 11 9

11 2

0 0

47 SW 0

1 1

5 1

3 7

7 2

1 0

0 28 WSW 0

0 0

2 3

2 6

4 0

0 0

0 17 W

0 0

0 4

9 3

2 1

0 0

19 WNW 0

0 0

3 2

1 0

0 0

0 6

NW 0

0 1

6 4

6 6

1 0

0 0

0 24 NNW 0

1 1

5 3

12 3

0 0

0 25 TOTALS 1

5 12 66 73 101 136 80 43 18 9

0 544 NUMBER OF VALID HOURS 544 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 544

-103-

ANNUAL RADIOACTIVE EFFLUENT.RELEASE REPORT (2004)

METEOROLOGY October.-. December TABLE-4AA SITE: SANONOFRE PERIOD OF RECORD 04100100-04123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E`

SLIGHTLY STABLE 1 -0.~5 '< DT/DZ i 1'.5.0C/100 METERS)

WIND

.22-

.51-.

.76-1.1-1.6-2.1--

3.1-5.1-7.1-10.1- -13.1--.>18 TOTAL'.

DIR

.50

.75

.1.0 1l.5 2.0

-3.0

5. 0 7.0 10.0 113.0-18.0 N

1.0 4'S 9

6(2' 0

0 0

0' 0

27 NNE

~

0 0

1 11 15 14~ 6 4

1 0

0.0 52 NE 0

1 1

2 0

3 5

6 3

0 0

0 21 ENE 0'

2 2

6 r 2

2~

2 2.0 0

0 0

18:

E'0 0

0 3

0 5

3.0 0

0 0

0 11 ESE 0

1 2

1 4'

8 1

0 1

0 0

0 18 SE 0

1 0

1 5

1' 1

1 0

0 0'

0 10' SSE 0

0 0

1 1

1 3

0 0

0 6

5' 0'

0 1

2 0

0 0

0

.0.0 4

SSW 0

0 0

0 1

0 0

0.0 0

1 SW 0

O0 1

0 4

0 0

5 WSW 0

0 0

0 2

1 0

0 0

.0 0

0 3

W 1-0 0

0 5'

2 0

1.0 0

0 0

9 WNW 0

0 0

3 1

2 1

1 0

0 0

0 8

NW 0

0 0

4 2

2 0

0 0

0 8'

NNW*

0 1

1 6

5 3

3.0 o0 0

0 0

19 TOTALS 2

6 12 44

.53 56 227 15 5

0 0

.0

'.220' NUMBER OF VALID HOURS'

.220 NUMBER OF CALMS I.1 NUMBER OF INVALID HOURS 0O TOTAL HOURS FOR THE PERIOD 221 PASQUILL F MODERATELY STABLE (1.5:< DT/DZ :5 4.0 OC/100 METERS)

WIND

.22-

..51--

.76--

1.1-

. 1.6-

-2.1-- 3.1-- 5.1-7.1-10.1-.13.'1-

>18 TOTAL; DR.50

.75 1.0

.1.5

.0 3.0

, 5.0 73.0 10.0 13.0

18.0 N

0 1

3 5

3':2 7

0 0

0 0.0 21 NNE 2

0 1

6

'38

i55

'!22 5

'0 0

0 0

139 NE 0

0 3

5 6

'6 12 9

0 0

41 ENE 0

0 1

1.6

'3 1

0 0

0 12 E

0 0

3 3

1 1

0' 0

0

0.

0 0

8 ESE 0

0 0

1 ~1 0

0 0

2 SE.

0 0

0 1

0

.1 0

.0 0

0 i0 0

2 SSE 0

0

'.0 2

I 0

0

.0 0

0 0

0 3

S 0

0.0 0

1 0

0 0

2 SSW 0

0 0

2 0

0

.0 0

0 0

0.0 2

SW 0

0-0 3

0

.0 1

.0 z

0:0 0

4 WSW-0 0

1 4

0 I

0 0

6.

0 2 O

1 2

1 0

0' 0

0 6

WNW' 0

0 0

1 1

4 1

0 0.0 0

0 7..

NW 0

0 3

0 1

.0

~0 0

0 0

4 NNW 0 0 0

0 2

3 1

0 0

0 0

6 TOTALS.

2 3

15 46

-.63

.76.'46 14 0~

0.-0

.0 265 NUMBER OF VALID HOURS.-

NUMBER OF INVALID HOURS-265 0

NUMBER OF CALMS K ~:

~ 0:"

TOTAL HOURS FOR THE PERIOD - :265s

-104- -

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2004)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 04100100-04123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 °C/100 METERS)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- ->18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

0 3

0 6

4 0

0 0

13 NNE 1

0 0

6 14 200 239 3

0 0

463 NE 0

0 0

4 6

9 9

0 0

0 28 ENE 0

0 2

0 3

1 2

0 0

0 8

E 0

0 2

1 3

2 0

0 0

0 8

ESE 0

0 0

0 1

0 2

0 0

0 3

SE 0

0 0

1 0

0 0

0 1

SSE 0

1 0

0 2

0 0

0 3

S 0

0 0

1 0

0 0

0 1

SSW 0

1 0

0 0

1 0

0 0

0 2

SW 1

0 0

2 0

0 0

0 3

WSW 0

0 0

1 1

1 0

0 0

0 3

W 0

1 0

2 0

0 0

0 5

WNW 0

0 0

0 3

2 1

0 0

0 6

NW 1

0 0

1 1

0 0

0 3

NNW 1

0 0

1 1

1 2

0 0

0 6

TOTALS 4

3 4

21 34 227 260 3

0 0

556 NUMBER OF VALID HOURS 556 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 556 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

1 1

8 22 20 19 13 0

0 0

84 NNE 3

0 5

48 80 283 274 17 4

0 0

0 714 NE 0

2 4

11 17 23 33 20 4

0 0

0 114 ENE 1

2 6

9 13 7

10 6

1 0

0 0

55 E

0 0

6 8

6 14 5

2 5

0 0

0 46 ESE 0

1 2

2 6

18 23 12 5

1 0

0 70 SE 0

1 1

7 11 14 42 30 13 1

0 0

120 SSE 0

1 2

6 13 23 50 23 8

11 6

0 143 S

0 2

3 7

14 25 36 11 5

4 7

0 114 SSW 0

1 0

11 15 28 28 10 11 3

0 0

107 SW 1

1 1

21 12 41 18 10 2

1 0

0 108 WSW 0

1 2

16 28 67 29 7

0 0

150 W

1 3

1 12 30 70 42 2

0 0

161 WNW 0

0 1

9 12 28 51 6

0 0

107 NW 1

0 4

12 10 12 13 1

0 0

53 NNW 1

2 2

15 13 17 11 0

0 0

61' TOTALS 9

18 48 216 300 689 678 157 58 21 13 0

2207 NUMBER OF VALID HOURS 2207 NUMBER OF CALMS 1

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 2208

-105-

ML051220222

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ML051220222
Site:	San Onofre (DPR-013, NPF-010, NPF-015)
Issue date:	12/31/2004
From:	Scherer A Southern California Edison Co
To:	Document Control Desk, NRC/FSME
References
+sispmjr200601
Download: ML051220222 (113)
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ML051220222

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