Text

Annual Radioactive Effluent Release Report 1999 January - December
	ML003709674
Person / Time
Site:	San Onofre
Issue date:	12/31/1999
From:	; Southern California Edison Co
To:	; NRC/FSME
References
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SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 1999 January - December

I*

SOUTHERN CALIFORNIA EDISON An EDISON IN\\tFJ?\\AJ IL\\.t 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 Electr4c Company and began commercial operation on January 1, 1968.

The unit was permanently shutdown on November 30, 1992.

It is owned by Southern California Edison (80%)

and San Diego Gas and Electric (20%).

Unit 2 and Unit 3 were supplied by Combustion Engineering, Inc.,

with turbine generators supplied by G.E.C. Turbine Generators, Ltd., of England.

The units began commercial operation on August 18, 1983, and April 1, 1984, respectively and are rated at 1127 net megawatts electrical each.

The twin units are owned by Southern California Edison (75.05%),

San Diego Gas and Electric (20%),

City of Anaheim (3.16%),

and the City of Riverside (1.79%).

P. 0. Box 128 San Clemente, CA 92674-0128

-i-

O.N Som

.S.

1

TABLE OF CONTENTS SECTION A -

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

SECTION C -

LIQUID EFFLUENTS SECTION D -

PREVIOUS RADIOACTIVE EFFLUENT RELEASE REP 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 MANUA SECTION J SECTION K ORT ADD L

- CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS

- MISCELLANEOUS......

2 ENDUM.........

16 S......

17 S......

19 S.....

21 22 26 29 29 30 SECTION L - S.O.N.G.S. 1 CONCLUSIONS

-ii-

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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 (1999)

S.O.N.G.S. 1 SECTION B.

GASEOUS EFFLUENTS Table 1A, "Gaseous Effluents-Summation of All Releases,"

provides a detailed listing of gaseous effluents released quarterly in four categories:

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

Listed for each of the four categories are:

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

The methodology used to calculate the percent of Applicable Limit is presented in Section F of this report.

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

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

Table 1C, "Gaseous Effluents-Ground Level Releases," provides the systematic listing by radionuclide for the quantity of radioactivity released in three categories:

fission gases,

iodines, and particulates.

The total radioactivity for each radionuclide is listed for each quarterly period by "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.

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 for continuous mode releases only.

Table 1E, "Gaseous Effluents-Radiation Doses at the Site Boundary,"

provides a quarterly summary of doses at the site boundary for this report period.

Table 1F, "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 (1999)

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

A. Fission and activation gases

1. Total release Ci

<LLD

<LLD 3.OOE+1

2.

Average release rate for period

,ACi/sec O.OOE+O O.OOE+O

3.

Percent of applicable limit

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

4.

Percent Effluent Concentration Limit

% ECL O.OOE+O O.OOE+O B. Iodines

1. Total iodine-131 Ci

<LLD

<LLD 1.90E+1

2.

Average release rate for period gCi/sec O.OOE+O O.OOE+O

3.

Percent of applicable limit

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

4.

Percent Effluent Concentration Limit

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

1. Particulates with half-lives >8 days Ci

<LLD

<LLD 1.60E+1

2.

Average release rate for period gCi/sec O.OOE+O O.OOE+O

3.

Percent of applicable limit

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

4.

Percent Effluent Concentration Limit

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

5.

Gross alpha activity Ci 6.56E-8 6.50E-9 5.OOE+1 D. Tritium

1. Total release Ci

<LLD 1.78E-1 2.50E+1

2.

Average release rate for period ACi/sec O.OOE+O 2.26E-2

3.

Percent of applicable limit

% MPC O.OOE+O 1.47E-4

4.

Percent Effluent Concentration Limit

% ECL O.OOE+O 2.94E-4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

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

A. Fission and activation gases

1. Total release Ci

<LLD

<LLD 3.OOE+1

2.

Average release rate for period gCi/sec O.OOE+O O.OOE+O

3.

Percent of applicable limit

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

4.

Percent Effluent Concentration Limit

% ECL O.OOE+O O.OOE+O B. Iodines

1.

Total iodine-131 Ci

<LLD

<LLD 1.90E+1

2.

Average release rate for period kCi/sec O.OOE+O O.OOE+O

3.

Percent of applicable limit Y MPC O.OOE+O O.OOE+O

4.

Percent Effluent Concentration Limit

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

1. Particulates with half-lives >8 days Ci

<LLD

<LLD 1.60E+1

2.

Average release rate for period ktCi/sec O.OOE+O O.OOE+O

3.

Percent of applicable limit

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

4.

Percent Effluent Concentration Limit

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

5.

Gross alpha activity Ci 7.25E-8

<LLD 5.OOE+1 D. Tritium

1.

Total release Ci 1.35E-1 5.44E-1 2.50E+1

2.

Average release rate for period ACi/sec 1.70E-2 6.84E-2

3.

Percent of applicable limit

? MPC 1.10E-4 4.45E-4

4.

Percent Effluent Concentration Limit

% ECL.

2.21E-4 8.90E-4 I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

1. Fission and activation gases krypton-85 Ci

<LLD

<LLD krypton-85m Ci

<LLD

<LLD krypton-87 Ci

<LLD

<LLD krypton-88 Ci

<LLD

<LLD xenon-133 Ci

<LLD

<LLD xenon-133m Ci

<LLD

<LLD xenon-135 Ci

<LLD

<LLD xenon-135m Ci

<LLD

<LLD xenon-138 Ci

<LLD

<LLD Total for period Ci

<LLD

2.

Iodines iodine-131 Ci

<LLD

<LLD iodine-133 Ci

<LLD

<LLD iodine-135 Ci

<LLD

<LLD Total for period Ci

<LLD

3.

Particulates 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 cobalt-58 Ci

<LLD

<LLD cobalt-60 Ci

<LLD

<LLD iron-59 Ci

<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

<LD zinc-65 Ci

<LLD

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

NOTE:

Due to the permanent shutdown longer conducted.

of S.O.N.G.S.

1, "BATCH MODE" releases are no ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

1. Fission and activation gases krypton-85 2.50E-5 krypton-85m 6.O0E-8 krypton-87 3.10E-7 krypton-88 2.10E-7 xenon-133 1.90E-7 xenon-133m 4.80E-7 xenon-135 6.30E-8 xenon-135m 2.40E-6 xenon-138 4.10E-6

2.

Iodines iodine-131 2.70E-13 iodine-133 1.70E-12 iodine-135 4.50E-11

3.

Particulates barium-140 6.50E-13 cerium-141 7.60E-14 cerium-144 3.10E-13 cesium-134 1.90E-13 cesium-137 1.60E-13 cobalt-58 1.70E-13 cobalt-60 2.70E-13 iron-59 4.20E-13 lanthanum-140 1.10E-12 manganese-54 1.70E-13 molybdenum-99 8.OOE-14 strontium-89 1.OOE-14 strontium-90 1.OOE-15 zinc-65 4.60E-13

4.

gross alpha 1.OOE-14 NOTE:

Due to the permanent shutdown of S.O.N.G.S.

1, "BATCH MODE" longer conducted.

releases are no ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

1 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A. Noble Gas

1.

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

2.

Percent Applicable Limit 5

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

3.

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

4.

Percent Applicable Limit

?

O.OOE+O O.OOE+O O.OOE+O O.OOE+O B. Tritium, Iodine, Particulates (at the nearest receptor)

1.

Organ Dose mrem O.OOE+O 6.65E-6 5.06E-6 2.04E-5

2.

Percent Applicable Limit O.OOE+O 8.87E-5 6.74E-5 2.71E-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 (1999)

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)

(2)

(3)

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

(1)

(2)

(3) the the the gross alpha radioactivity volume of waste released (prior to dilution) volume of dilution water The methodology used to Section F of this report.

in Table 2A is presented calculate the percent of applicable limit is presented in The methodology used to calculate the estimated total error in Section G of this report.

Table 2B, "Liquid Effluents," provides the systematic quantity of radioactivity released in each category.

radionuclide released is listed for each quarterly "batch" modes of release.

listing by radionuclide for the The total radioactivity of each period by both "continuous" and Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B.

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

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

1 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES First Second A. Fission and activation products

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

Ci

<LLD 1.36E-5 1.90E+1

2.

Average diluted concentration during period gCi/ml 0.00+0 8.72E-12

3.

Percent of applicable limit

% MPC 0.00+0 4.36E-5

4.

Percent Effluent Concentration Limit

% ECL 0.00+0 8.72E-4 B. Tritium

1.

Total release Ci

<LLD

<LLD 1.90E+1

2.

Average diluted concentration during period UCi/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 C. Dissolved and entrained gases

1. Total release Ci

<LLD

<LLD 1.90E+1

2.

Average diluted concentration during period ACi/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

<LLD

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

continuous, prior to dilution) liters 6.54E+6 4.40E+5 5.OOE+O F.

Volume of dilution water used during period liters 1.68E+9 1.56E+9 5.OOE+O Estimated Total ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

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

Error, A. Fission and activation products

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

Ci 1.86E-3 1.50E-6 1.90E+1

2.

Average diluted concentration during period gCi/ml 1.25E-9 9.20E-13

3. Percent of applicable limit

% MPC 6.19E-3 4.60E-6

4.

Percent Effluent Concentration Limit

% ECL 8.45E-2 9.20E-5 B. Tritium

1. Total release Ci 5.41E-1 2.50E-5 1.90E+1

2.

Average diluted concentration during period gCi/ml 3.66E-7 1.53E-11

3.

Percent of applicable limit

% MPC 1.22E-2 5.11E-7

4.

Percent Effluent Concentration Limit

% ECL 3.66E-2 1.53E-6 C. Dissolved and entrained gases

1.

Total release Ci

<LLD

<LLD 1.90E+1

2.

Average diluted concentration during period 4Ci/ml 0.00+0 O.OOE+O

3.

Percent of applicable limit

% MPC 0.00+0 O.OOE+O

4.

Percent Effluent Concentration Limit % ECL 0.00+0 O.OOE+O I D. Gross alpha radioactivity

1.

Total release Volume of waste released (batcl continuous, prior to dilution)

Volume of dilution water us(

period E.

F.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S. 1 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE LLD Lower Limit of Detection; see Table 2C. 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 1.36E-5 3.43E-6 1.50E-6 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 1.36E-5 3.43E-6 1.50E-6

2.

Dissolved and entrained gases xenon-133 Ci

<LLD

<LLD xenon-135 Ci

<LLD

<LLD Total for period Ci

<LLD

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

LIQUID EFFLUENTS BATCH MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter I 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 5.73E-5

<LLD cesium-137 Ci

<LLD

<LLD 8.69E-4

<LLD chromium-51 Ci

<LLD

<LLD cobal t-58 Ci

<LLD

<LLD cobalt-60 Ci

<LLD

<LLD 9.22E-4

<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 3.26E-6

<LLD technetium-99m Ci

<LLD

<LLD zinc-65 Ci

<LLD

<LLD zirconium-95 Ci

<LLD

<LLD Total for period Ci

<LLD

<LLD 1.85E-3

<LLD

2. Dissolved and entrained gases xenon-133 Ci

<LLD

<LLD xenon-135 Ci

<LLD

<LLD Total for period Ci

<LLD

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

1. Fission and activation products barium-140 3.30E-7 cerium-141 5.20E-8 cerium-144 2.30E-7 cesium-134 9.90E-8 cesium-137 8.60E-8 chromium-51 4.20E-7 cobalt-58 8.70E-8 cobalt-60 1.30E-7 iodine-131 6.OOE-8 iron-55 I.OOE-6 iron-59 2.OOE-7 lanthanum-140 2.40E-7 manganese-54 8.80E-8 molybdenum-99 3.50E-8 niobium-95 8.50E-8 strontium-89 5.OOE-8 strontium-90 1.OOE-8 technetium-99m 3.50E-8 zinc-65 2.20E-7 zirconium-95 1.50E-7

2.

Dissolved and entrained gases xenon-133 3.10E-7 xenon-135 1.20E-7

3.

gross alpha 1.OOE-7

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

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

1. Fission and activation products barium-140 3.30E-7 cerium-141 5.20E-8 cerium-144 2.30E-7 cesium-134 9.90E-8 cesium-137 8.60E-8 chromium-51 4.20E-7 cobalt-58 8.70E-8 cobalt-60 1.30E-7 iodine-131 6.OOE-8 iron-55 1.OOE-6 iron-59 2.OOE-7 lanthanum-140 2.40E-7 manganese-54 8.80E-8 molybdenum-99 3.50E-8 niobium-95 8.50E-8 strontium-89 5.OOE-8 strontium-90 1.OOE-8 technetium-99m 3.50E-8 zinc-65 2.20E-7 zirconium-95 1.50E-7

2.

Dissolved and entrained gases xenon-133 3.10E-7 xenon-135 1.20E-7

3. gross alpha 1.OOE-7

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

1 TABLE 2D LIQUID EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A.

1.

Total body dose mrem O.OOE+O 1.46E-4 9.58E-3 1.62E-5

2.

Percent Applicable Limit O.OOE+O 9.70E-3 6.39E-1 1.08E-3 B.

1. Limiting organ dose mrem O.OOE+O 2.22E-4 2.55E-2 2.47E-5

2.

Percent Applicable Limit y

O.OOE+O 4.45E-3 5.09E-1 4.94E-4

3.

Limiting organ for period N/A Liver GI-LLI Liver ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

SUMMARY

12 month period

1.

Number of batch releases:

2 releases

2.

Total time period for batch releases:

5370 minutes

3.

Maximum time period for a batch release:

5353 minutes

4.

Average time period for a batch release:

2685 minutes

5.

Minimum time period for a batch release:

17 minutes

6.

Average saltwater flow during batch releases:

5125 gpm SECTION D.

PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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 Total curie content estimated.

Material packaged in High Integrity Containers No shipment made.

(Not Irradiated Fuel) and shipped in a Type B Cask (C of C 9208). Estimated 12 month total

1. Type of waste Unit period error (%)

a.

Spent resins, filter sludges, m3 7.50E+O evaporator bottoms 1

Ci 2.88E+2 3.OOE+1

b.

Dry active waste (DAW),

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

c.

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

d.

Other m3 N/A Ci N/A N/A NOTE:

(#)

N/A

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S. I

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

a.

not applicable ameri cium-241 1.13E-3 carbon-14 1.92E-2 cesium-134 1.19E+1 cesium-137 8.13E+1 cobal t-60 2.14E+O curium-242 1.43E-5 curi um-243/244 8.61E-4 nickel-59 2.60E-2 nickel-63 4.40E+O niobi um-94 2.03E-2 pl utonium-238 1.21E-3 pl utonium-239/240 4.85E-4 pl utoni um-241 3.52E-2 strontium-90 1.79E-1 tritium 4.61E-3

b.

not applicable

__N/A

c.

not applicable

__N/A

d.

not applicable

__N/A

3.

Solid Waste Disposition

-See COMMON section of this report B. IRRADIATED FUEL SHIPMENTS (Disposition)

See COMMON section of this report ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

I 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 MPCeii where:

Fj n

MPCj 8

%ECL where:

Rel Rate X/Q ECLeff where:

Fj n

EC Li (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, 4Ci/sec.

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

13.

1 i-1 MPC i fractional abundance of the it h radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT.

total number of radionuclides identified Maximum Permissible Concentration (MPC) of the it" radionuclide from 10 CFR 20 (20.1-20.602),

Appendix B, Table II, Column 1.

(Rel Rate) (X/Q)

(100)

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 1A, uCi/sec.

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

13.

1 M

ECL i fractional abundance of the it" radionuclide obtained by dividing the activity (curies) for each radionuclide, C1,

by the sum of all the isotopic activity, CT.

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 (1999)

S.O.N.G.S.

1 Liquid Effluents - Applicable Limits The percent of Applicable Limits, using the following equations:

% Applicable Limit where:

Dil Conc 0

MPCeff where:

Fj n

MPC1 S ECL where:

Dil Conc 0

EC Leff where:

Fj n

ECL, tabulated in Sections A.3, B.3, and C.3 of Table 2A, were calculated (Dil 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, pMCi/ml.

n Fi 1

1.-

MPC fractional abundance of the it' radionuclide obtained by dividing the activity (curies) for each radionuclide, C1,

by the sum of all the isotopic activity, CT.

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

1 n '

F.

M ECL 1 fractional abundance of the it' radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT.

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.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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 CF1 +

a

+

(Y where:

0i Error associated with each component.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S. I SECTION H.

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

Six different categories are presented:

(1) Liquid Effluents - Whole Body (2)

Liquid Effluents - Organ (3) Airborne Effluents - Tritium, Iodines and Particulates (4) Noble Gases -

Gamma (5)

Noble Gases -

Beta (6) Direct Radiation The doses for categories 1 and 2 were calculated using the methodology of the ODCM, this data is also presented in Table 2D.

Categories 3, 4,

and 5 were calculated utilizing RRRGS (Radioactive Release Report Generating System) 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 individuals who may, at times, be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary.

For members of the public who traverse the site boundary via highway 1-5, the residency time shall be considered negligible and hence the dose "0".

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

I TABLE I Dose * (millirems)

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

1)

2)

3)

4)

5)

Whole Body O.OOE+O 1.46E-4 9.58E-3 1.62E-5 9.74E-3

6)

7)

8)

9)

10)

Organ 0.00+0 2.22E-4 2.55E-2 2.47E-5 2.55E-2 AIRBORNE EFFLUENTS

11)

12)

13)

14)

15)

Tritium, lodines, and Particulates O.OOE+O 6.07E-5 3.40E-5 4.96E-4 5.90E-4 NOBLE GASES

16)

17)

18)

19)

20)

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

21)

22)

23)

24)

25)

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

26)

27)

28)

29)

30)

DIRECT RADIATION 9.69E-2 8.93E-2 7.24E-2 8.79E-2 3.41E-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 data was calculated using the methodology of the ODCM.

2.

This data was calculated using the methodology of the ODCM.

3.

This data was calculated using the methodology of the ODCM.

4.

This data was calculated using the methodology of the ODCM.

5.

This data was calculated using the methodology of the ODCM.

6.

7.

gamma radiation was O.OOE+O mrad.

19.

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

20.

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

21.

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

22. There was no activity detected during the release period, therefore beta radiation was O.OOE+O mrad.

23.

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

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

the reported air dose for the the the the the reported reported reported air air air dose dose dose reported air dose reported air dose for for for for for ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S. 1 This data was calculated using the methodology of the ODCM.

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

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

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

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

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

The maximum organ dose was to a child's thyroid and was located in the NW sector.

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

The maximum organ dose was to a child's thyroid and was located in the NW sector.

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

The maximum organ dose was to a child's thyroid and was located in the NW sector.

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

The maximum organ dose was to a child's thyroid and was located in the NW sector.

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

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

There was no activity detected during the release period, therefore the reported air dose for

8.

9.

10.

11.

12.

13.

14.

15.

16.

17.

18.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

1

25.

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

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

27.

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

28.

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

29.

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

30.

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

TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 0.00+0 9.70E-3 6.39E-1 1.08E-3 3.25E-1 Organ O.OOE+O 4.45E-3 5.09E-1 4.94E-4 2.55E-1 AIRBORNE EFFLUENTS Tritium, Iodines, O.OOE+O 8.09E-4 4.53E-4 6.61E-3 3.94E-3 and Particulates NOBLE GASES Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O NOTE:

Direct Radiation is not specifically addressed in the Applicable Limits.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

1 SECTION I.

CHANGES TO OFFSITE DOSE CALCULATION MANUAL On February 25, 1999, revision 14 to the Unit I Offsite Dose Calculation Manual (ODCM) was adopted and published.

Incorporated into this revision were:

1. changes due to the 1998 Land Use Census, and

2.

updated monitor calibration constants to reflect periodic maintenance activity.

The Unit 1 ODCM contains requirements for an Inter-laboratory Comparison Program.

Standard RETS uses wording that requires the program to be approved by the NRC.

In the past, the approved program was the Environmental Protection Agency (EPA) cross check program.

The EPA no longer provides a cross-check program, as stated in a letter from Wayne N. Marchant, EPA to Charles L. Miller, NRC dated 5/18/95, discussing calibration standards and performance evaluation studies.

However, Regulatory Guide 4.15 provides the guidance for this program.

As such, Specification 5.3.1.A was changed to reflect that Reg. Guide.

In accordance with the results of AR-980102040, Section 5.4 of the Unit 1 0DCM was changed to remove the reference to Regulatory Guide 4.18 and add Radiological Assessment Branch Technical Position, Revision 1, November 1979.

Section 3.4.1.2 provided a number of TLD's of 47 around the site.

This section was changed from '47' to 'at a minimum of 30' locations around the site.

Elsewhere in the document, over the years, changes have left blank pages, mixed fonts, and other administrative errors.

Additionally, equations located throughout the ODCM have been renumbered to provide a consecutive numerical sequence and to number identical equations with the same number throughout the ODCM.

This revision corrected those.

None of the changes were substantive in nature nor did they 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 was maintained.

As such, per NRC Generic Letter 89-01, no safety reviews were required or performed.

The following is a complete list of the changes:

OLD Page NEW Page CHANGE TOC Renumbered pages as necessary based on changes in the body of the ODCM.

TOC ii Removed previously deleted lines TOC iii Removed previously deleted lines, added previously deleted title as a place holder TOC iv Removed previously deleted lines, added previously deleted title as a place holder TOC vii Removed previously deleted lines, added previously deleted title as a place holder TOCv iii Removed previously deleted lines 1-11 Changed from 3 saltwater pumps to 2 1-14 Changed from 3 saltwater pumps to 2 1-15 Removed previously blank page ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

1 OLD Page NEW Page CHANGE 1-16 Removed previously deleted page 1-17 1-15 Changed equation number 1-8 to 1-3 1-19 1-17 Renumbered step due to prior deletion 1-20 1-18 Renumbered step due to prior deletion 1-21 1-19 Updated calibration constants 2-3 Removed previously deleted lines, renumbered notes 2-5 Removed previously deleted lines, renumbered notes 2-9 Added previously deleted title as a place holder 2-10 Reinserted Section 2.5.1, it was inadvertently deleted in the previous revision.

2-11 Reinserted Section 2.5.1, it was inadvertently deleted in the previous revision.

2-12 Changed will to shall 2-14 Removed previously deleted page 2-16 Removed previously deleted page 2-25 2-21 Changed CLF factors due to LUC 2-27 Removed previously deleted page, gaseous monitor calibration constants 2-28 2-23 Sector P, Cotton Point Estates, ingestion factor changed for child, teen, and adult 2-31 2-26 Sector Q, Outage Workers, occupancy factor changed 2-36 2-31 Sector Q, San Clemente Ranch, occupancy factor changed 2-38 2-33 Sector Q, S. C.

Resident with garden, ingestion factor and distance changed 2-40 2-35 Sector R, San Clemente Ranch, occupancy factor changed 2-41 2-36 Removed 'W. Res.'

2-46 2-41 Sector C, Camp San Onofre Fr.

Stn.,

X/Q, D/Q changes 2-49 2-44 Changed 'Treat.'

to 'Treatment' 2-58 2-53 Sector F, Changed name to Border Patrol Checkpoint 2-60 2-55 Sector G, Hwy Patrol Weigh Station, occupancy factor changed 3-5 Format only 3-7 Changed number of TLD locations 5-4 Added note f stating no drinking water pathway at SONGS 5-6 Added note f stating no drinking water pathway at SONGS 5-9 Combined Zr/Nb, Ba/La 5-14 Changed 'which has been approved by the Commission' to 'that complies with Regulatory Guide 4.15.'

5-16 Changed reference to Reg Guide 4.8 to Radiological Assessment Branch Technical Position.

5-17 Format only 5-18 Removed reference to previously deleted TLD locations 5-19 Removed reference to previously deleted TLD locations 5-20 Removed reference to previously deleted TLD locations, added new TLD locations 75, 76, 77, and 78, changed TLD 55 and 56 title.

5-21 Removed previously deleted lines, changed 'NEW CONTROL' to 'CONTROL' 5-22 Added SONGS Garden to Local Crops, removed previously deleted lines, re4moved reference to previously deleted TLD locations 5-26 to Updated maps 5-30 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

1 On May 3, 1999, revision 15 to the Unit 1 Offsite Dose Calculation Manual (ODCM) was adopted and published.

Incorporated into this revision were:

1. changes to Action Statements 20 and 24 for flow estimate requirements on inoperable radiation instruments,

2.

added a definition of 25% extension on Surveillance Requirements and,

3.

removal of dose parameter tables from section 2 per memo "ODCM Dose Parameter Evaluation" dated 11/13/99 from EM Goldin to D Dick.

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

Safety Evaluations were provided for the first two items.

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

None of the changes impacted 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 IOCFR50 was maintained.

The following is a complete list of the changes:

OLD Page NEW Page CHANGE TOC Renumbered pages as necessary based on changes in the body of the ODCM.

The following dose parameter location tables were removed from the ODCM since other, more dose-conservative locations exist in those sectors per memo "ODCM Dose Parameter Evaluation" dated 11/13/99 from EM Goldin to D Dick 2-24 Removed Surf Beach/Guard Shack from Sector Q 2-25 Removed State Park Office Trailer from Sector Q 2-27 Removed Rec. Building Staff from Sector Q 2-28 Removed "51 Area" Beach Campground from Sector Q 2-30 Removed "51 Area" Beach Check-in from Sector Q 2-31 Removed San Clemente Ranch (No Residents) from Sector Q 2-32 Removed S. C. Ranch Adm.

Offices from Sector Q 2-33 Removed S. C. Resident with garden from Sector Q 2-35 Removed San Clemente Ranch (No Residents) from Sector R 2-36 Removed S. C. Ranch Pac. from Sector R 2-37 Removed Deer Consumer/Hunter from Sector A 2-39 Removed Deer Consumer/Hunter from Sector B 2-41 Removed Camp San Onofre Fr. Stn from Sector C 2-44 Removed Sewage Treatment Facility from Sector C 2-45 Removed Deer Consumer/Hunter from Sector D 2-47 Removed Sheep Meat/Shepherd from Sector E 2-50 Removed Sheep Meat/Shepherd from Sector F 2-51 Removed Deer Consumer/Hunter from Sector F 2-53 Removed Border Patrol Checkpoint from Sector F 2-55 Removed Hwy Patrol Weigh Station from Sector G 3-4 Single spaced lines 3-7 Changed cadmium covered TLDs to thulium doped TLDs, single spaced lines 4-3 Changed Action 20 per Safety Evaluation 4-9 Changed Action 24 per Safety Evaluation 4-14 Updated drawing - removed aux building fan, per Unit 1 OPS request ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S. I OLD Page NEW Page CHANGE 4-15 Updated drawing -

removed redundant boxes 5-25 Changed Sector N limit from 281.15 to 281.25, per Environmental Protection request 6-4 Added definition for Surveillance Requirement Frequency Extension, Renumbered the definitions 6-5 Removed previously deleted page SECTION J.

CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS There were no changes to the Unit 1 Radioactive Waste Treatment Systems during the reporting period, January 1, 1999 to December 31, 1999.

SECTION K. MISCELLANEOUS There were no entries in Section K Miscellaneous for Unit 1.

EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 1999 - December 31, 1999 There were no effluent radiation monitors out of service greater than 30 days in 1999 at Unit 1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

S.O.N.G.S.

I CONCLUSIONS Gaseous releases totaled 8.57E-1 curies of which noble gases were O.OOE+O curies, iodines were O.OOE+O curies, particulates were O.OOE+O curies, and tritium was 8.57E-1 curies.

The radiation doses from gaseous releases were: (a) gamma air dose: O.OOE+O mrad at the site boundary, (b) beta air dose: O.OOE+O mrad at the site boundary, organ dose: 5.90E-4 mrem at the nearest receptor.

Liquid releases totaled 5.43E-1 curies of which particulates and iodines were 1.88E-3 curies, tritium was 5.41E-1 curies, and noble gases were O.OOE+O curies.

The radiation doses from liquid releases were: (a) total body: 9.74E-3 mrem, (b) limiting organ: 2.55E-2 mrem.

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

O.N.G.S.

2 and 3 So

TABLE OF CONTENTS SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION A

B C

D E

F G

H I

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

73

-iii-INTRODUCTION

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

- LIQUID EFFLUENTS

- PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT AD RADWASTE SHIPMENTS

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

ESTIMATION OF ERROR.....

10 CFR 50 APPENDIX I REQUIREMENTS...........

- CHANGES TO OFFSITE DOSE CALCULATION MANUAL

- CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS

- MISCELLANEOUS........

S..........

31 S..........

32 S......

42 DENDUM...........

51 S.........

52 S..

55 S..........

57 58 62 69 70

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

January - December SECTION A.

INTRODUCTION This Annual Radioactive Effluent Release Report summarizes the gaseous and liquid radioactive effluent releases and radwaste shipments made from the San Onofre Nuclear Generating Station, Units 2 and 3.

This report is prepared in the general format of USNRC Regulatory Guide 1.21 and includes:

1.

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

2.

Percent of Applicable Limits

3.

Estimated Total Percent Error

4.

Lower Limit of Detection Concentrations

5.

Batch Release Summaries

6.

Previous Radioactive Effluent Release Report Addendum

7.

Radwaste Shipments

8.

10 CFR 50 Appendix I Requirements

9.

Changes to Offsite Dose Calculation Manual.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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 and monitor calibration releases are considered to be "batch" releases.

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

Table 1D, "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 1E, "Gaseous Effluents-Radiation Doses at the Site Boundary,"

provides a quarterly summary of doses at the site boundary for this report period.

Table iF, "Gaseous Effluents-Batch Release Summary,"

provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Units 2 and 3.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

2 and 3 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit OuaterOuarter Eirror

%~

C. Fission and activation gases

1. Total release Ci 9.79E+1 4.52E+1 3.OOE+1

2.

Average release rate for period uCi/sec 1.26E+1 5.74E+O

3.

Percent of applicable limit

% MPC 2.55E-2 1.55E-2

4.

Percent Effluent Concentration Limit

% ECL 3.57E-2 3.41E-2 D. lodines

1. Total iodine-131 Ci 1.26E-2 1.87E-3 1.90E+1

2.

Average release rate for period gCi/sec 1.62E-3 2.38E-4

3.

Percent of applicable limit

% MPC 7.78E-3 1.14E-3

4.

Percent Effluent Concentration Limit

% ECL 3.89E-3 5.71E-4 E. Particulates

1. Particulates with half-lives >8 days Ci 4.95E-4 1.06E-3 1.60E+1

2.

Average release rate for period gCi/sec 6.37E-5 1.35E-4

3.

Percent of applicable limit

% MPC 1.69E-5 2.83E-5

4.

Percent Effluent Concentration Limit

% ECL 5.06E-5 7.67E-5

5.

Gross alpha activity Ci 1.19E-6 4.79E-7 5.OOE+1 F.

Tritium

1. Total release Ci 1.07E+1 1.40E+1 2.50E+1

2.

Average release rate for period yCi/sec 1.38E+O 1.78E+O

3.

Percent of applicable limit

% MPC 3.30E-3 4.27E-3

4.

Percent Effluent Concentration Limit

% ECL 6.60E-3 8.55E-3 First Estimated Second Total Unit

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Fourth Quarter Estimated Total

Error, A. Fission and activation gases

1. Total release Ci 2.66E+1 2.79E+1 3.OOE+1

2.

Average release rate for period MCi/sec 3.35E+O 3.51E+O

3.

Percent of applicable limit

% MPC 9.34E-3 9.29E-3

4.

Percent Effluent Concentration Limit

% ECL 2.12E-2 2.OOE-2 B. Iodines )

1. Total iodine-131 Ci 1.14E-4 7.35E-5 1.90E+1

2.

Average release rate for period gCi/sec 1.43E-5 9.25E-6

3.

Percent of applicable limit

% MPC 6.88E-5 4.44E-5

4.

Percent Effluent Concentration Limit

% ECL 3.44E-5 2.22E-5 C. Particulates ()

1. Particulates with half-lives >8 days Ci

<LLD

<LLD 1.60E+1

2.

Average release rate for period

)uCi/sec O.OOE+O O.OOE+O

3.

Percent of applicable limit

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

4.

Percent Effluent Concentration Limit

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

5.

Gross alpha activity Ci 5.13E-7 7.73E-6 5.OOE+1 D. Tritium

1.

Total release Ci 5.41E+O 9.65E+O 2.50E+1

2.

Average release rate for period gCi/sec 6.81E-1 1.21E+O

3.

Percent of applicable limit

% MPC 1.63E-3 2.91E-3

4.

Percent Effluent Concentration Limit

% ECL 3.27E-3 5.83E-3 I (1)

Unit 2 Condenser Air Ejector particulate and iodine samples from 8/2/99 @ 1530 to 8/3/99 @ 0015 and 10/13/99

@ 1200 to 10/14/99 @ 0635 were not collected.

There was no measurable activity in the previous or subsequent samples.

These incidents are documented in ARs 990800097 and 991000666.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

2 and 3 TABLE IC GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE LLD Lower Limit of Detection; see Table 1D. First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

1.

Fission and activation gases argon-41 Ci 3.86E+O 4.79E+O 3.04E+O 2.81E+O krypton-85 Ci

<LLD

<LLD krypton-85m Ci

<LLD

<LLD krypton-87 Ci 6.62E-3

<LLD

<LLD krypton-88 Ci

<LLD

<LLD xenon-133 Ci 9.33E+1 3.91E+1 2.33E+1 2.51E+1 xenon-133m Ci

<LLD

<LLD xenon-135 Ci 3.36E-1 2.59E-3

<LLD

<LLD xenon-135m Ci

<LLD

<LLD xenon-138 Ci

<LLD

<LLD Total for period Ci 9.75E+1 4.39E+1 2.63E+1 2.79E+1

2.

Iodines iodine-131 Ci 1.26E-2 1.87E-3 1.14E-4 7.35E-5 iodine-132 Ci 4.29E-3 6.88E-4

<LLD

<LLD iodine-133 Ci 6.96E-4 1.54E-4 2.60E-4 7.84E-5 iodine-135 Ci 2.07E-6

<LLD

<LLD Total for period Ci 1.76E-2 2.71E-3 3.74E-4 1.52E-4

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

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

3.

Particulates barium-140 Ci

<LLD

<LLD bromine-82 Ci 7.28E-5 6.17E-5 7.43E-5 5.34E-5 cerium-141 Ci

<LLD

<LLD cerium-144 Ci

<LLD

<LLD cesium-134 Ci 2.70E-7

<LLD

<LLD cesium-137 Ci 1.54E-6

<LLD

<LLD chromium-51 Ci 6.80E-5 3.03E-4

<LLD

<LLD cobalt-58 Ci 4.01E-4 6.60E-4

<LLD

<LLD cobalt-60 Ci 2.02E-5 2.44E-5

<LLD

<LLD iron-59 Ci 2.39E-7 6.84E-6

<LLD

<LLD lanthanum-140 Ci

<LLD

<LLD manganese-54 Ci 3.51E-7 1.11E-5

<LLD

<LLD molybdenum-99 Ci

<LLD

<LLD niobium-95 Ci 2.58E-6 3.44E-5

<LLD

<LLD strontium-89 Ci

<LLD

<LLD strontium-90 Ci

<LLD

<LLD yttrium-92 Ci 8.48E-6

<LLD

<LLD 2.02E-5 zinc-65 Ci

<LLD

<LLD zirconium-95 Ci 7.66E-7 2.28E-5

<LLD

<LLD zirconium-97 Ci 3.04E-8

<LLD

<LLD LLD Lower Limit of Detection; see Table ID.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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 4.18E-1 1.26E+O 3.03E-1

<LLD krypton-85m Ci

<LLD

<LLD krypton-87 Ci

<LLD

<LLD krypton-88 Ci

<LLD

<LLD xenon-133 Ci 3.31E-3 1.13E-2

<LLD

<LLD xenon-133m Ci

<LLD

<LLD xenon-135 Ci

<LLD

<LLD xenon-135m Ci

<LLD

<LLD xenon-138 Ci

<LLD

<LLD Total for period Ci 4.22E-1 1.27E+O 3.03E-1

<LLD LLD Lower Limit of Detection; see Table ID.

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

1. Fission and activation gases krypton-85 2.50E-5 krypton-85m 6.OOE-8 krypton-87 3.10E-7 krypton-88 2.10E-7 xenon-133m 4.80E-7 xenon-135 6.30E-8 xenon-135m 2.40E-6 xenon-138 4.10E-6

2.

Iodines iodine-132 3.80E-13 iodine-135 1.50E-12

3. Particulates barium-140 3.OOE-11 cerium-141 3.90E-12 cerium-144 1.70E-11 cesium-134 1.OOE-11 cesium-137 8.60E-12 chromium-51 3.50E-11 cobalt-58 9.10E-12 cobalt-60 1.50E-11 iron-59 2.20E-11 lanthanum-140 2.OOE-11 manganese-54 9.30E-12 molybdenum-99 2.10E-12 niobium-95 8.60E-12 strontium-89 1.OOE-13 strontium-90 1.OOE-14 yttrium-92 1.30E-10 zinc-65 2.50E-11 zirconium-95 1.50E-11 zirconium-97 9.50E-12 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

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

1.

Fission and activation gases krypton-85 1.30E-3 krypton-85m 2.80E-6 krypton-87 1.30E-5 krypton-88 1.OOE-5 xenon-133 8.30E-6 xenon-133m 2.50E-5 xenon-135 3.20E-6 xenon-135m 4.10E-5 xenon-138 6.10E-5

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

2 and 3 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A.

Noble Gas

1.

Gamma Air Dose mrad 1.06E-2 8.88E-3 5.55E-3 5.32E-3

2.

Percent Applicable Limit k

1.06E-1 8.88E-2 5.55E-2 5.32E-2

3.

Beta Air Dose mrad 1.71E-2 9.01E-3 5.33E-3 5.41E-3

4.

Percent Applicable Limit 8.55E-2 4.51E-2 2.66E-2 2.71E-2 B. Tritium, Iodine, Particulates (at the nearest receptor)

1.

Organ Dose mrem 8.79E-3 2.OOE-3 2.65E-4 3.39E-4

2.

Percent Applicable Limit

?

5.86E-2 1.33E-2 1.77E-3 2.26E-3 NOTE:

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

2 and 3 TABLE IF GASEOUS EFFLUENTS-BATCH RELEASE

SUMMARY

12 month period

1. Number of batch releases:

5 releases

2. Total time period for batch releases:

1965 minutes

3.

Maximum time period for a batch release:

422 minutes

4.

Average time period for a batch release:

393 minutes

5.

Minimum time period for a batch release:

358 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S. 2 and 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)

(2)

(3)

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

(1)

(2)

(3) the the the gross alpha radioactivity volume of waste released (prior to dilution) volume of dilution water The methodology used to Section F of this report.

in Table 2A is presented calculate the percent of applicable limit is presented in The methodology used to calculate the estimated total error in Section G of this report.

Table 2B, "Liquid Effluents," provides the systematic quantity of radioactivity released in each category.

radionuclide released is listed for each quarterly "batch" modes of release.

listing by radionuclide for the The total radioactivity of each period by both "continuous" and Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B.

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

Table 2E, "Liquid Effluents-Batch Release Summary,"

provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Units 2 and 3.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

2 and 3 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES IEstimated First Second Total Unit Quarter Quarter

Error, A. Fission and activation products

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

Ci 1.26E-1 6.21E-2 1.90E+1

2.

Average diluted concentration during period uzCi/ml 2.29E-10 9.95E-11

3.

Percent of applicable limit

% MPC 2.77E-4 1.62E-4

4.

Percent Effluent Concentration Limit

% ECL 1.14E-3 5.14E-4 B. Tritium

1. Total release

2.

Average diluted concentration during period

3.

Percent of applicable limit

4.

Percent Effluent Concentration Limit Ci btCi/ml

%MPC

>,ECL C. Dissolved and entrained gases

1. Total release Ci 4.68E-1 9.49E-4 1.90E+1

2.

Average diluted concentration du-r'i7ng period gCi/ml 8.51E-10 1.52E-12

3.

Percent of applicable limit

% MPC 4.26E-4 7.60E-7

4.

Percent Effluent Concentration Limit

% ECL 4.26E-4 7.60E-7 D. Gross alpha radioactivity

1. Total release Ci

<LLD 4.24E-6 5.OOE+1 E.

Volume of waste released (batch &

continuous, prior to dilution) liters 6.35E+7 7.19E+7 5.OOE+O F.

Volume of dilution water used during period liters 5.50E+II 6.24E+11 5.00E+O 2.87E+2 5.22E-7 1.74E-2 5.22E-2 2.74E+1 4.39E-8 1.46E-3 4.39E-3 1.90E+1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

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

A. Fission and activation products (1)

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

Ci 9.20E-3 1.49E-2 1.90E+1

2.

Average diluted concentration during period 4Ci/ml 1.21E-11 1.95E-11

3.

Percent of applicable limit

% MPC 2.17E-5 3.84E-5

4.

Percent Effluent Concentration Limit

% ECL 1.78E-4 2.89E-4 B. Tritium

1. Total release Ci 4.25E+1 4.84E+1 1.90E+1

2.

Average diluted concentration during period

[Ci/ml 5.57E-8 6.33E-8

3.

Percent of applicable limit

% MPC 1.86E-3 2.11E-3

4.

Percent Effluent Concentration Limit % ECL 5.57E-3 6.33E-3_

C. Dissolved and entrained gases

1. Total release Ci

<LLD

<LLD 1.90E+1

2.

Average diluted concentration during period ACi/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)

1.

Total release Ci

<LLD

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

continuous, prior to dilution) liters 1.03E+8 8.40E+7 5.OOE+O F.

Volume of dilution water used during period liters 7.63E+11 7.65E+11 5.OOE+O (1)

A Unit 3 Full Flow Condensate Polishing Demineralizer Holdup Tank clean sump release permit sample was not included in the August monthly composite for Fe-55, Sr-89 and Sr-90. This incident is documented in AR 990900593.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

2 and 3 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE J

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 8.03E-5

<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 8.03E-5

<LLD

2.

Dissolved and entrained gases xenon-133 Ci

<LLD

<LLD xenon-135 Ci

<LLD

<LLD Total for period Ci

<LLD

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

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

1. Fission and activation products antimony-122 Ci

<LLD 3.96E-5

<LLD

<LLD antimony-124 Ci 3.43E-3 5.10E-3

<LLD

<LLD antimony-125 Ci 6.08E-2 5.02E-2 6.25E-4 5.89E-4 barium-140 Ci

<LLD

<LLD cerium-141 Ci

<LLD

<LLD cerium-144 Ci

<LLD

<LLD cesium-134 Ci 4.10E-4 9.43E-5 1.89E-4 5.52E-5 cesium-137 Ci 3.64E-4 4.09E-4 2.35E-4 1.11E-4 cesium-138 Ci

<LLD 5.39E-4

<LLD

<LLD chromium-51 Ci 1.21E-2 2.92E-3 8.69E-4

<LLD cobalt-57 Ci

<LLD

<LLD 7.07E-6

<LLD cobalt-58 Ci 2.18E-2 2.07E-3 2.42E-3 1.17E-3 cobalt-60 Ci 3.25E-3 2.30E-4 1.84E-3 4.09E-3 iodine-131 Ci 4.87E-5

<LLD

<LLD iron-55 I')

Ci 1.32E-2

<LLD 9.06E-4 4.49E-3 iron-59 Ci 1.30E-3 1.63E-5

<LLD

<LLD lanthanum-140 Ci

<LLD

<LLD manganese-54 Ci 8.90E-4 6.88E-5 3.72E-4 3.66E-4 molybdenum-99 Ci

<LLD

<LLD niobium-95 Ci 4.58E-3 1.78E-4 7.16E-4 4.89E-4 niobium-97 Ci 6.56E-5

<LLD 1.58E-5

<LLD silver-110m Ci 4.42E-4 2.02E-5 5.48E-4 2.91E-3 strontium-89 (

Ci

<LLD

<LLD strontium-90 (1)

Ci

<LLD

<LLD strontium-92 Ci

<LLD

<LLD 2.56E-5 9.29E-5 technetirum-99m Ci

<LLD

<LLD tin-113 Ci 4.38E-4

<LLD 5.10E-5 1.27E-4 zinc-65 Ci

<LLD

<LLD zirconium-95 Ci 2.74E-3 9.79E-5 3.79E-4 2.50E-4 zirconium-97 Ci

<LLD

<LLD 1.74E-4 Total for period Ci 1.26E-1 6.20E-2 9.20E-3 1.49E-2 LLD Lower Limit of Detection; see Table 2C.

(1)

A Unit 3 Full Flow Condensate Polishing Demineralizer Holdup included in the August monthly composite for Fe-55, Sr-89 990900593.

Tank clean sump release permit sample was not and Sr-90. This incident is documented in AR ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

2 and 3 TABLE 2B (Continued)

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

2.

Dissolved and entrained gases krypton-85 Ci 6.30E-2

<LLD

<LLD xenon-131m Ci 3.31E-2

<LLD

<LLD xenon-133 Ci 3.72E-1 9.49E-4

<LLD

<LLD xenon-135 Ci

<LLD

<LLD Total for period Ci 4.68E-1 9.49E-4

<LLD

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

1. Fission and activation products barium-140 3.30E-7 cerium-141 5.20E-8 cerium-144 2.30E-7 cesium-134 9.90E-8 cesium-137 8.60E-8 chromium-51 4.20E-7 cobalt-58 8.70E-8 cobalt-60 1.30E-7 iodine-131 6.OOE-8 iron-55 I.OOE-6 iron-59 2.OOE-7 lanthanum-140 2.40E-7 manganese-54 8.80E-8 molybdenum-99 3.50E-8 niobium-95 8.50E-8 strontium-89 5.OOE-8 strontium-90 1.OOE-8 technetium-99m 3.50E-8 zinc-65 2.20E-7 zirconium-95 1.50E-7

2.

Dissolved and entrained gases xenon-133 3.10E-7 xenon-135 1.20E-7

3.

gross alpha I.OOE-7

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

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

1. Fission and activation products antimony-122 1.20E-7 antimony-124 3.10E-7 barium-140 3.30E-7 cerium-141

.5.20E-8 cerum-144 2.30E-7 cesium-138 7.90E-5 chromium-51 4.20E-7 cobalt-57 2.90E-8 iodine-131 6.OOE-8 iron-55 1.OOE-6 iron-59 2.OOE-7 lanthanum-140 2.40E-7 molybdenum-99 3.50E-8 niobium-97 2.00E-7 strontium-89 5.00E-8 strontium-90 I.OOE-8 strontium-92 7.80E-5 technetium-99m 3.50E-8 tin-113 7.50E-8 zinc-65 2.20E-7 zirconium-97 2.20E-7

2.

Dissolved and entrained gases krypton-85 4.20E-5 xenon-131m 3.90E-6 xenon-133 3.10E-7 xenon-135 1.20E-7

3.

gross alpha 1.OOE-7

LIQUI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

2 and 3 TABLE 2D D EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOU First Second Third Fourth Unit Quarter Quarter Quarter Quarter A.

1.

Total body dose mrem 2.01E-3 1.22E-4 2.09E-4 4.29E-4

2.

Percent Applicable Limit 6.70E-2 4.07E-3 6.97E-3 1.43E-2 B.

1.

Limiting organ dose mrem 1.27E-2 1.23E-3 2.66E-3 1.11E-2

2.

Percent Applicable Limit 1.27E-1 1.23E-2 2.66E-2 1.11E-I

3.

Limiting organ for period GI-LLI GI-LLI GI-LLI GI-LLI WNDARY

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

2 and 3 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE

SUMMARY

12 month period

1.

Number of batch releases:

85 releases

2. Total time period for batch releases:

15,118 minutes

3.

Maximum time period for a batch release:

756 minutes

4. Average time period for a batch release:

178 minutes

5.

Minimum time period for a batch release:

93 minutes

6. Average saltwater flow during batch releases:

740,000 gpm SECTION D.

PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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)

Total curie content estimated.

Material packaged in High Integrity Containers and shipped in Type B Cask (C of C 9208).

Material packaged in strong, tight containers of various sizes.

No shipment made. Estimated 12 month total error

1. Type of waste Unit period

(%)

a.

Spent resins, filter sludges, m3 1.71E+1 evaporator bottoms(*)

Ci 1.76E+2 3.OOE+1

b.

Dry active waste (DAW),

m3 3.64E+1 compactable and non-compactable(#)

E Ci 1.44E+0 3.00E+1

c.

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

d.

Other m3 N/A Ci N/A N/A Note:

(*)

(#)

N/A

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

2.

Estimate of major nuclide composition (by type of waste)

a.

americium-241 7.28E-8 antimony-125 1.46E-5 carbon-14 1.20E-1 cerium-144

__2.93E-6 cesium-134 1.06E+I1 cesium-137

__1.60E+1 cobalt-57 2.76E-7 cobalt-58 1.01E+1 cobalt-60 6.07E+O curium-242 1.16E-5 curium-243/244 2.59E-8 iodine-129

__4.04E-6 iron-55

__1.27E+1 manganese-54

__3.OOE+O nickel-59

__2.51E-1 nickel-63 4.12E+1 niobium-94 2.43E-2 plutonium-238 2.15E-8 plutonium-239/240 4.07E-8 plutonium-241 5.82E-3 strontium-90

2.70E-2 technetium-99 2.76E-5 tritium 8.71E-3 uranium-234 1.43E-7 uranium-238

__7.63E-8 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

2 and 3

2.

Estimate of major nuclide composition (by type of waste)

(Cont'd)

b.

americium-241 1_I._10E-3 antimony-124

__1.20E-1 antimony-125

__1.87E-1 carbon-14

__1.29E+O cerium-141 1.95E-2 cerium-144 6.52E-2 cesium-134 3.04E+O cesium-137 3.08E+1 chromi um-51 4.08E+O cobal t-57 3.84E-2 cobalt-58

___1.07E+1 cobalt-60

__6.68E+O curium-242

__9.29E-4 curium-243/244

__2.37E-3 iodine-129

__9.17E-3 iron-55

__2.98E+1 iron-59

__3.77E-1 manganese-54 2.82E-1 nickel-63 1.11E+1 niobium-94 1.84E-3 niobiurn-95 6.77E-1 plutonium-238 1.03 E-3 pl utonium-239/240 8.02E-4 pl utonium-241 1.26E-1 silver-110m

4.63E-3 stronti um-89 8.52E-3 strontium-90 2_

1.08E-2 techneti um-99 7.21E-4 tin-113

__1.14E-1 tritium

__4.18E-2 zi rconi um-95

__3.92E-1

c.

not applicable

__O.OOE+O

d.

not applicable

__O.OOE+O A.

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

3.

Solid Waste Disposition See COMMON section of this report B.

IRRADIATED FUEL SHIPMENTS (Disposition)

See COMMON section of this report ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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.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

MPC.ff where:

Fj n

MPCi

% ECL (Rel Rate)

(XIO)

(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, pmCi/sec.

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

31.

i-i MPC 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, CT.

total number of radionuclides identified Maximum Permissible Concentration (MPC) of the it' radionuclide from 10 CFR 20 (20.1-20.602),

Appendix B, Table II, Column 1.

(Rel Rate) (X/O) (100)

ECLeff where:

Rel Rate X/Q 0

ECLeff where:

Fj n

EC Li 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, uCi/sec.

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

31.

n F.

Mi ECL i fractional abundance of the it' radionuclide obtained by dividing the activity (curies) for each radionuclide, C1,

by the sum of all the isotopic activity, CT.

total number of radionuclides identified Effluent Concentration Limit (ECL) of the i'h radionuclide from 10 CFR 20 (20.1001-20.2402),

Appendix B, Table 2, Column 1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

2 and 3 Liquid Effluents - Applicable Limits The percent of Applicable Limits, using the following equations:

0

% Applicable Limit where:

Dil Conc 0

MPCeff where:

Fj n

tabulated in Sections A.3, B.3, and C.3 of Table 2A, were calculated (Dil 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, gCi/ml.

1 i-1 MPC i fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT.

total number of radionuclides identified Maximum Permissible Concentration (MPC) radionuclide from 10 CFR 20 (20.1-20.602),

Table II, Column 2.

of the i "

Appendix B, (Dil Conc)

(100)

ECLeff where:

Dil Conc 0

ECLeff where:

Fj n

ECL1 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, ACi/ml.

n Fi i-i ECL i fractional abundance of the ii" radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT.

total number of radionuclides identified Effluent Concentration Limit (ECL) of the i th radionuclide from 10 CFR 20 (20.1001-20.2402),

Appendix B, Table 2, Column 2. MPCi

%ECL

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

ESTIMATION OF ERROR Estimations of the error in reported values of gaseous and liquid effluents releases have been made.

Sources of error for gaseous effluents - batch releases are:

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

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

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

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

Total Error a

+

Error+ ascte

+

2.t a

where:

o(

=

Error associated with each component.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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, this data is also presented in Table 2D.

Categories 3, 4, and 5 were calculated utilizing RRRGS (Radioactive Release Report Generating System) 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 individuals who may, at times, be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary.

For members of the public who traverse the site boundary via highway 1-5, the residency time shall be considered negligible and hence the dose "0".

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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 2.01E-3 1.22E-4 2.09E-4 4.29E-4 2.77E-3

6)

7)

8)

9)

10)

Organ 1.27E-2 1.23E-3 2.66E-3 1.11E-2 2.77E-2 AIRBORNE EFFLUENTS

11)

12)

13)

14)

15)

Tritium, lodines, and Particulates 1.71E-2 4.55E-3 1.12E-3 4.84E-3 2.76E-2 NOBLE GASES **

16)

17)

18)

19)

20)

Gamma 4.15E-3 1.99E-3 2.42E-3 1.90E-3 1.OOE-2

21)

22)

23)

24)

25)

Beta 8.25E-3 1.86E-3 2.10E-3 2.53E-3 1.47E-2

26)

27)

28)

29)

30)

DIRECT RADIATION 9.69E-2 8.93E-2 7.24E-2 8.79E-2 3.41E-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 data was calculated using the methodology of the ODCM.

2.

This data was calculated using the methodology of the ODCM.

3.

This data was calculated using the methodology of the ODCM.

4.

This data was calculated using the methodology of the ODCM.

5.

This data was calculated using the methodology of the ODCM.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

2 and 3

6.

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

7.

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

8.

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

9.

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

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

11. The maximum organ dose was to a child's thyroid and was located in the NNW sector.

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

12. The maximum organ dose was to a child's thyroid and was located in the NNW sector.

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

13. The maximum organ dose was to a child's thyroid and was located in the NNW sector.

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

14. The maximum organ dose was to a child's thyroid and was located in the NNW sector.

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

15. The maximum organ dose was to a child's thyroid and was located in the NNW sector.

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

16.

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

19.

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

20.

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

21.

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

2 and 3

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

26.

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

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

28.

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

29.

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

30.

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

TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 6.70E-2 4.07E-3 6.97E-3 1.43E-2 4.62E-2 Organ 1.27E-1 1.23E-2 2.66E-2 1.11E-1 1.38E-1 AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 1.14E-1 3.04E-2 7.46E-3 3.23E-2 9.21E-2 NOBLE GASES Gamma 4.15E-2 1.99E-2 2.42E-2 1.90E-2 5.OOE-2 Beta 4.13E-2 9.31E-3 1.05E-2 1.26E-2 3.69E-2 NOTE:

Direct Radiation is not specifically addressed in the Applicable Limits.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 25, 1999, revision 32 to the Units 2/3 Offsite Dose Calculation Manual (ODCM) was adopted and published.

Incorporated into this revision were:

1.

changes due to the 1998 Land Use Census,

2.

updated monitor calibration constants to reflect periodic maintenance activity, and

3. moved dose calculations to Section 3.

The Units 2/3 ODCM contains requirements for an Inter-laboratory Comparison Program.

Standard RETS uses wording that requires the program to be approved by the NRC.

In the past, the approved program was the Environmental Protection Agency (EPA) cross check program.

The EPA no longer provides a cross-check program, as stated in a letter from Wayne N. Marchant, EPA to Charles L. Miller, NRC dated 5/18/95, discussing calibration standards and performance evaluation studies.

However, Regulatory Guide 4.15 provides the guidance for this program.

As such, Specification 5.3.1 was changed to reflect Regulatory Guide 4.15.

In accordance with the results of AR-980102040, Section 5.4 of the Units 2/3 ODCM was changed to remove the reference to Regulatory Guide 4.18 and add Radiological Assessment Branch Technical Position, Revision 1, November 1979.

Section 2.9.1.2 provided a number of TLD's of 47 around the site.

This section has been moved to 3.4.1 and was changed from '47' to 'at a minimum of 30' locations around the site.

In a previous revision some equation factors were combined for simplicity.

The factors were once again separated to provide a background for understanding the equations.

Elsewhere in the document, over the years, changes have left blank pages, mixed fonts, and other administrative errors.

Additionally, equations located throughout the ODCM have been renumbered to provide a consecutive numerical sequence and to number identical equations with the same number throughout the ODCM.

Finally, this revision changes the title of 'Blowdown Polishing Sump' to the correct nomenclature of

'Blowdown Polishing System Neutralization Sump' throughout. This revision corrected those.

None of the changes were substantive in nature nor did they 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.

As such, per NRC Generic Letter 89-01, no safety reviews were required or performed.

The following is a complete list of the changes:

OLD Page NEW Page CHANGE TOC Renumbered pages as necessary based on changes in the body of the ODCM.

TOCi Format only TOCii Moved Total Dose from Section 2 to Section 3 TOCv Format only ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

2 and 3 OLD Page NEW Page 1-2 1-4 1-10 1-13 1-14 1-15 1-15 1-16 1-17 1-21 1-22 2-2 2-4 2-6 2-9 2-13 2-14 2-18 2-19 2-20 2-21 2-22 2-23 2-27 2-32 2-35 2-37 2-44 2-45 2-46 2-47 2-49 2-57 2-69 2-70 to 2-72 3-5 5-4 5-6 1-13 1-14 1-14 1-15 1-16 1-20 1-21 3-2 2-33 2-35 2-42 2-43 2-44 2-45 2-47 2-55 2-67 3-3 to 3-5 CHANGE Changed the following equation numbers: 1-4a to 1-5, 1-5 to 1-6, 1-9 to 1-3, 1-10 to 1-4, 1-11 to 1-7, 1-12 to 1-8, 1-13 to 1-9, 1-14 to 1-10, 1-15 to 1-11, 1-16 to 1-12, 1-17 to 1-13, 1-18 to 1-14, 1-19 to 1-15, 2-3 to 2-4, 2-4 to 2-5, 2-4a to 2-6, 2-5 to 2-3, 2-6 to 2-8, 2-6a to 2-10, 2-7 to 2-9, 2-7a to 2-11, 2-8 to 2-7, 2-9 to 2-12, 2-10 to 2-13, 2-11 to 2-18, 2-12 to 2-19, 2-13 to 2-20, 2-14 to 2-21, 2-15 to 2-22, 2-16 to 2-23, 2-17 to 2-24, 2-18 to 2-25, 2-19 to 2-26 Changed 'Blowdown Processing Sump' to 'Blowdown Processing System Neutralization Sump' Note ***, Corrected valve numbers Reordered factors to the order presented in the equation Removed previously blank page Changed 'Blowdown Processing Sump' to 'Blowdown Processing System Neutralization Sump' Changed 'Blowdown Processing Sump' to 'Blowdown Processing System Neutralization Sump' Reordered factors to the order presented in the equation Changed 'Blowdown Processing Sump' to 'Blowdown Processing System Neutralization Sump' Changed 'Blowdown Processing Sump' to 'Blowdown Processing System Neutralization Sump' Added "is" to sentence Updated calibration constants Removed previously deleted line, changed note j to h Removed previously deleted notes h and i, renumbered note j as h Removed previously deleted line Moved Total Dose Specification from Section 2 to Section 3 Format only Split equation factor 472 into its separate factors Format only Format only Format only Format only Split equation factor 472 into its separate factors Format only Removed previously blank page Removed previously blank page Changed CLF factors due to LUC Sector P, Cotton Point Estates, ingestion factor changed Sector Q, S. C. Resident, ingestion factor changed Sector Q, San Clemente Ranch, occupancy factor changed Sector Q, San Clemente Ranch Admin Office, occupancy factor changed Sector Q, Outage Workers, occupancy factor changed Sector R, San Clemente Ranch, occupancy factor changed, format Renamed 'Sewage Facility' to 'Sewage Treatment Facility' Sector G, Hwy Patrol Weigh Station, occupancy factor changed Moved Total Dose Calculations to from Section 3 Changed number of TLD's to reflect current arrangements Added note g stating no drinking water pathway at SONGS.

Added note g stating no drinking water pathway at SONGS.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S. 2 and 3 OLD Page NEW Page 5-7 5-8 5-12 5-13 5-15 5-16 5-17 5-17 5-18 5-19 5-23 to 5-27 6-14 CHANGE Format only Format only Changed 'is approved by the Commission' to 'complies with Regulatory Guide 4.15' Changed reference to Reg Guide 4.8 to Radiological Assessment Branch Technical Position.

Removed reference to previously deleted TLD locations, removed previously deleted line Removed reference to previously deleted TLD locations Added new TLD locations 75, 76, 77, and 78, changed TLD location for 55 and 56 in title only, removed reference to previously deleted TLD locations Removed reference to previously deleted TLD locations

Format, removed previously deleted line, changed 'NEW CONTROL' to 'CONTROL' Added SONGS Garden to Local Crops Updated maps Changed Total Dose (2.5) to Total Dose (3.3)

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S.

2 and 3 On May 3, 1999, revision 33 to the Units 2/3 Offsite Dose Calculation Manual (ODCM) was adopted and published.

Incorporated into this revision were:

1. clarified 'transient sampling' requirements,

2.

changes to Action Statements 31 and 36 for flow estimate requirements on inoperable radiation instruments,

3.

added Action 41 for the SYF,

4.

added a definition of 25% extension on Surveillance Requirements

5.

removed dose parameter tables from section 2 per memo "ODCM Dose Parameter Evaluation" dated 11/13/99 from EM Goldin to D Dick,

6.

clarified Operability testing requirements for liquid waste treatment systems 1.3.1.2 and 1.3.1.3, and

7.

changes'Blowdown Polishing Sump' to 'Blowdown Polishing System Neutralization Sump' in Section 4.

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

Safety Evaluations were provided for the first four items.

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

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

The level of radioactive effluent control required by

IOCFR20, 40CFR190, 10CFR50.36a, and Appendix I to 10CFR50 was maintained.

The following is a complete list of the changes:

OLD Page NEW Page CHANGE TOC Renumbered pages as necessary based on changes in the body of the ODCM.

1-6 Clarified Operability testing requirements for liquid waste treatment systems 1.3.1.2 and 1.3.1.3 2-4 Clarified requirements for transient and routine sampling of noble gases, particulates, and iodines in notes b and d 2-10 Removed previously deleted page 2-15 2-14 Single spaced the lines 2-16 2-15 Single spaced the lines 2-17 2-15 Single spaced the lines and moved to the previous page 2-25 2-23 Single spaced the lines 2-27 2-25 Single spaced the lines 2-28 2-26 Single spaced the lines 2-29 2-27 Single spaced the lines ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S. 2 and 3 OLD Page NEW Page 2-34 2-37 2-39 2-40 2-41 2-44 2-48 2-50 2-54 2-55 2-60 2-63 2-64 2-65 2-67 2-69 2-70 2-71 2-72 2-73 2-74 2-75 2-76 2-77 2-78 3-1 3-3 3-5 4-1 4-2 4-4 4-5 4-6 4-8 4-9 4-11 4-11 4-15 5-18 5-22 6-4 2-32 2-35 2-37 2-38 2-39 2-42 2-46 2-48 2-52 2-53 2-58 2-61 2-62 2-63 2-65 2-67 2-68 2-69 2-70 2-71 2-72 2-73 2-74 2-75 2-76 CHANGE The following dose parameter location tables were removed fro the ODCM since other, more dose-conservative locations exist in those sectors:

Surf Beach/Life Guard from Sector P Rec.

Building Staff from Sector Q State Park Office Trailer from Sector Q Surf Beach/Guard Shack from Sector Q 51 Area Beach/Campground from Sector Q S. C. Ranch Adm. Offices from Sector Q SC Ranch Packing from Sector R Deer Consumer/Hunter from Sector A Camp San Onofre Fr. Stn from Sector C Sewage Treatment Facility from Sector C Sheep (Meat) from Sector E Border Patrol Checkpt. from Sector E Sheep (Meat)/Shepherd from Sector F Deer Consumer/Hunter from Sector F Hwy Patrol Weigh Station from Sector G Format the following changes due to table deletion 2-32 through 2-48, 2-51 through 2-54, 2-57 through 2-65 Format Format Format Format Format Format Format Format Format Format Single Single Single nuclide abbreviations nuclide abbreviations nuclide abbreviations nuclide abbreviations nuclide abbreviations nuclide abbreviations nuclide abbreviations nuclide abbreviations nuclide abbreviations nuclide abbreviations spaced the lines spaced the lines spaced the lines, changed cadmium covered TLD to thalium doped TLD Changed 4.1.1.2 per Safety Evaluation Added 'Processing System' to 1.b and 2.b Changed Action 31 per Safety Evaluation Added 'Processing System' to 1.b and 2.b Added reference symbol to 'automatic pathway isolation' in note 1, in order to clarify when the requirement is applicable Added P&I to Associated Sample Flow Measuring Device for clarification per the Safety Evaluation Changed Action 36 to Action 41, Added P&I to Associated Sample Flow Measuring Device for clarification Changed Action 36 per Safety Evaluation Added Action 41 per Safety Evaluation Added reference symbol to 'automatic pathway isolation' in note 1, in order to clarify when the requirement is applicable Corrected distance to City of San Clemente per Environmental Protection request Corrected Sector limit for Sector N per Environmental Protection request Added definition for Surveillance Requirement Frequency Extension, renumbered equation as required, format Formated Table 6-1 to match TSIP 6-5

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S. 2 and 3 On November 9, 1999, revision 34 to the Units 2/3 Offsite Dose Calculation Manual (ODCM) was adopted and published.

This change incorporated final turnover items related to DCP 6926 (replacement of various radiation monitors), along with some other minor administrative improvements.

Incorporated into this revision were:

1.

Revised Liquid Setpoint equation to adjust for low (<100 KeV) energy gamma

emitters,

2.

2/3 RE-7808 setpoint methodology changes related to DCP 6926,

3.

Modifying Tables 4-1 and 4-2 to include process flow devices for radiation monitor operability,

4.

Data Acquisition System introduction related to DCP 6926,

5.

Revised the Source Check definition,

6. Surveillance Requirement 4.1.1.2 wording change,

7.

Valve number change for discharges from Steam Generator Blowdown paths, and

8.

Updated Liquid and Gaseous Effluent Radiation Monitor Calibration Constants.

Safety Evaluations were provided for items 1, through 5.

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

Item 8 reflects routine calibration of the radiation monitors as is required by Section 4; no safety evaluation is required.

Discussions are provided below for items 6 and 7.

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

Surveillance Requirement 4.1.1.2 requirement of dilution flow "At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .... " This wording could lead to confusion as to when the flow must be checked.

The 'or' is being replaced with 'and' so as to clarify that the flow check is required under both conditions rather than either.

Action Request 990700033 identified that valve number HV-3773 could not be locked closed as required by ODCM Action 29c.

Investigation revealed that HV-3773 is an air operated valve with no physical means of locking.

Valve number $2(3)1319MU577 has been substituted in this Action.

It is a butterfly valve with a built-in locking device.

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

The level of radioactive effluent control required by

10CFR20, 40CFR190, 10CFR50.36a, and Appendix I to 10CFR5O will be maintained.

The following is a complete list of the changes:

PaQe CHANGE TOC Renumbered pages as necessary based on changes in the body of the ODCM.

Throughout Changed ZiCyi to FC' i Section 1 1-9 Added 'Blowdown Processing System' to 'Neutralization Sump' 1-10 Added Factor Cxe to equation 1-3 Changed definition of ZiCyi 1-12 Changed definition of

,iCyi ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S. 2 and 3 Page CHANGE 1-13 Changed definition of ZiCyi 1-14 Changed definition of ZiCyi Added Factor Cxe to equation 1-3 1-16 Changed definition of Z1iCy 1-18 Changed definition of EiCy1 1-19 Changed definition of ZCyi 1-21 Updated Liquid Rad Monitor calibration constants Removed calibration constants for monitors that are being converted to MGP 1-25 Changed procedure reference from S0123-III-5.11.23 to S0123-III-5.23 2-12 Left page intentionally blank due to consolidating equations Changed 7808 setpoint calculation to remove cpm values since the monitor is being converted to MGP.

2-13 Added 2/3RT-7808 to title Changed correction factor '2' to a variable value 'S' 2-16 Added note for applicability of 2(3)RT-7865 2-17 Added 2(3)RT-7828 only to main purge flow rate 2-18 Added 2(3)RT-7828 only to main purge flow rate 2-19 Changed 7808 setpoint calculation to remove cpm values Added 2/3RT-7808 to title Changed correction factor '2' to a variable value 'S' 2-20 Consolidated pages 2-21 Left page intentionally blank due to consolidating equations 2-22 Removed 2/3-7808C Calibration Constants since the monitor is being converted to MGP.

Removed previously blank pages:

2-32, 2-35, 2-37, 2-38, 2-39, 2-42, 2-46, 2-48, 2-52, 2-53, 2-58, 2-61, 2-62, 2-63, and 2-65 4-1 In Surveillance Requirement 4.1.1.2, Changed word 'or' to 'and' in order to clarify when the action is required 4-2 Added "Process" to 2.0 title Added TPS to process flow rate measurement devices Added DAS to Table 4-1 4-3 Changed valve numbers to identify a new valve to be locked closed per Action 29c.

4-4 Revised Action 31 Added Action 32 4-5 Added "Effluent" to i.e.

Added "Process" to 2.0 title Added TPS to process flow rate measurement devices Added DAS to Table 4-2 4-6 Added Note 4 about the DAS 4-8 Added equipment ID to 3e.

Added DAS to Table 4-3 4-9 Renamed SYF monitors to correct nomenclature 4-10 Deleted note (2),

removed previously deleted note (4) 4-11 Corrected typo in Action 41 Added Action 42 4-13 Added DAS to Table 4-4 4-14 Removed reference to Note (8) 4-16 Revised Note (8) 4-17 Format only 6-3 Changed definition of Source Check ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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, 1999 to December 31, 1999.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

MISCELLANEOUS Improper Setpoint for Unit 3 Containment Purge On 5/23/99, a Unit 3 Containment Purge was conducted using a non-conservative setpoint. The analysis instrumentation did not identify an isotope resulting in a non-conservative setpoint. The error was discovered and the purge was stopped.

A new release permit was generated with the proper setpoint and the purge was restarted. A review of the release data showed at no time did the monitor reading exceed the correct setpoint value. The resultant dose and curies released are included in the 1999 data. The station procedure was revised to require a second review of analyses and training was conducted to help identify analysis errors.

This incident is documented in AR 990501863.

Missed Sample flow Verification on Auxiliary Sampling Equipment On 9/6/99, a required sample flow check on the Unit 3 Condenser Air Ejector Auxiliary Sample Equipment was missed. The check was made upon discovery. The time between flow checks was 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and 10 minutes, exceeding both the procedure and ODCM time limit. This incident is documented in AR 990900295.

Missed Channel Functional Test on Unit 2 Turbine Plant Sump (TPS)

Process Flow Instrumentation On 11/24/99, it was determined that unit 2 TPS radmonitor was inoperable due to a missed surveillance on the process flow instrument loop. A new revision of the ODCM had been issued 11/9/99 which required testing on the process flow loop. The instrument was placed in service on 11/16/99. On 12/2/99, the surveillance was performed on the instrument and the radiation monitor was returned to service.

Since it was not recognized that the monitor was inoperable, nine days of compensatory sampling were not performed.

None of the weekly composites for this time period showed any detectable gamma activity. The procedure is being changed to verify that the affected departments complete their required program changes prior to issuance of the revised ODCM.

This incident is documented in AR 991101352.

Non-isokinetic Particulate and Iodine (P&I)

Sampling on Condenser Air Ejector Monitors On 1/21/00, it was determined the Unit 2 and Unit 3 Condenser Air Ejector (CAE) radiation monitors' sample flow was outside the isokinetic flow range. The process flow was immediately adjusted to allow sampling within the allowable range. The new nozzles installed during the 1999 cycle 10 outages maintained isokinetic sampling at a process flow of 11.3 cfm to 18.7 cfm. The allowable range was tested and recalculated to allow a process flow rate of 7 cfm to 22.5 cfm. From 2/21/99 to 1/21/00, Unit 2 CAE monitor sample flow was outside the allowable range 30% of the time while Unit 3, from 5/6/99, was outside 80% of the time. For the entire year, no P&I sample showed any detectable activity. The noble gas monitor was in service for the entire time period. This incident is documented in AR 000101252.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S. 2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 1999 - December 31, 1999 S.O.N.G.S.

2 Monitor Inoperability Period Inoperability Cause Explanation 2RT-7817 08/23/99 - 10/21/99 Radmonitor upgrade Design change upgrade modification BPS/FFCPD design change to install a new instrument and Discharge Monitor connect to Data Acquisition System.

2RT-7821 08/25/99 - 11/16/99 Radmonitor upgrade Design change upgrade modification Turbine Plant Sump design change to install a new instrument and Monitor connect to Data Acquisition System.

2RT-7865 01/06/99 - 02/17/99 Radmonitor upgrade Upgrade modification to connect to Containment Purge.

design change new radiation monitoring Data (Plant Vent Stack)

Acquistion System.

Monitor 2RT-7870 08/08/83 - 02/18/99 Non-isokinetic UFSAR Design Basis Document review Condenser Air sample flow during identified non-isokinetic sample Ejector Monitor normal air ejector flow during normal air ejector operation operation. New sample probe nozzle installed during 1999 outage. Noble gas radiation monitor functions were operable during this period.

LER-2-1998-015 05/02/99 - 08/04/99 Process flow rate Substitute process flow installed monitoring device during troubleshoot and trending of new design flow instrumentation.

Noble gas radiation monitor functions were operable during this period.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

S.O.N.G.S. 2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 1999 - December 31, 1999 S.O.N.G.S. 3 Monitor Inoperability Period Inoperability Cause Explanation 3RT-7817 04/26/99 - 07/14/99 Radmonitor upgrade Design change upgrade modification BPS/FFCPD design change to install a new instrument and Discharge Monitor connect to Data Acquisition System.

3RT-7821 04/26/99 -

09/21/99 Radmonitor upgrade Design change upgrade modification Turbine Plant Sump design change to install a new instrument and Monitor connect to Data Acquisition System.

3RT-7828 04/01/84 - 01/13/99 Non-isokinetic Non-isokinetic sample flow during Containment Purge.

sample flow during containment venting. Procedures and Monitor containment venting monitor software modified to (mini-purge with restrict venting within isokinetic fans off) flow limits. Noble gas radiation monitor functions were operable during this period. LER-2-1998-015 3RT-7865 03/28/99 - 05/17/99 Radmonitor upgrade Upgrade modification to connect to Plant Vent Stack design change new radiation monitoring Data (Containment Acquistion System.

Purge) Monitor 3RT-7870 04/01/84 - 05/06/99 Non-isokinetic UFSAR Design Basis Document review Condenser Air sample flow during identified non-isokinetic sample Ejector normal air ejector flow during normal air ejector operation operation. New sample probe nozzle installed during 1999 outage. Noble gas radiation monitor functions were operable during this period.

ILER-2-1998-015 S.O.N.G.S.

2/3 Monitor Inoperability Period Inoperability Cause Explanation 2/3RT-7808 08/23/99 - 12/30/99 Radmonitor upgrade Design change upgrade modification Plant Vent Stack design change to install a new instrument and Monitor connect to Data Acquisition System.

2/3RT-7813 04/13/99 - 05/20/99 Surveillance and Extensive decontamination of Liquid Radwaste decon effort detector and shielding components Monitor in effort to reduce background in addition to testing for installation of new radmonitor.

08/23/99 -

12/23/99 Radmonitor upgrade Design change upgrade modification design change to install a new instrument and connect to Data Acquisition System.

Liquid Radwaste 08/23/99 -

12/23/99 Radmonitor upgrade Design change upgrade modification System Flow Meter design change to install a new instrument and I_

I connect to Data Acquistion System.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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

S.O.N.G.S. 2 and 3 CONCLUSIONS Gaseous releases totaled 2.38E+2 curies of which noble gases were 1.98E+2 curies, iodines were 2.08E-2 curies, particulates were 1.85E-3 curies, and tritium was 3.98E+1 curies.

The radiation doses from gaseous releases were: (a) gamma air dose: 1.OOE-2 mrad at the site boundary, (b) beta air dose: 1.47E-2 mrad at the site boundary, (c) organ dose: 2.76E-2 mrem at the nearest receptor.

Liquid releases totaled 4.06E+2 curies of which particulates and iodines were 2.12E-1 curies, tritium was 4.06E+2 curies, and noble gases were 4.69E-1 curies.

The radiation doses from liquid releases were: (a) total body: 2.77E-3 mrem, (b) limiting organ: 2.77E-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 (1999)

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

b.

Dry active waste (DAW),

m 3 N/A compatible and non-compatible Ci N/A N/A

c.

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

d.

Other (filters)

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

2.

Estimate of major nuclide composition (by type of waste)

a.

not applicable

__N/A

b.

not applicable

__N/A

c.

not applicable

__N/A

d.

not applicable

__N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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 1

Kindrick Trucking Company Barnwell, SC Truck/Trailer 1

Kindrick Trucking Company Envirocare, UT Truck/Trailer 5

Kindrick Trucking Company Envirocare, UT 5__#

_Truck/Trailer 1 #

Kindrick Trucking Company Barnwell, SC I_ _

_Truck/Trailer All waste packaged at SONGS is staged at one location. There are no independent shipments of dry active waste made for Unit 1 or Units 2/3. All shipments consisted of waste from all three units, with Unit 1 contributing a very small percentage.

SONGS maintains contracts with vendors (GTS/ATG) that provide volume reduction services.

These shipments were made from their processing facility.

The six shipments made from these facilities included waste from other generators.

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

B. IRRADIATED FUEL SHIPMENTS (Disposition)

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

DEWATERING Number of Containers Solidification Agent 5

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 Licensee Controlled Specifications, Section 5.0.103.2.2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

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 3.88E-1

b.

Percent ODCM Specification Limit 1.55E+O

2.

Limiting Organ

a.

Organ Dose (GI-LLI) mrem 7.97E-2

b.

Percent ODCM Specification Limit k

3.19E-1

3.

Thyroid

a.

Thyroid Dose mrem 1.16E-2

b.

Percent ODCM Specification Limit 1.54E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

COMMON COMMON CONCLUSIONS Gaseous releases from S.O.N.G.S. 1, 2 and 3 totaled 2.39E+2 curies of which noble gases were 1.98E+2 curies, iodines were 2.08E-2 curies, particulates were 1.85E-3 curies, and tritium was 4.07E+1 curies.

Liquid releases form S.O.N.G.S.

1, 2 and 3 totaled 4.07E+2 curies of which particulates and iodines were 2.14E-1 curies, tritium was 4.07E+2 curies, and noble gases were 4.69E-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 2 radwaste shipments to Barnwell, SC and 6 shipments to Envirocare, UT.

Total volume was 6.11E+1 cubic meters containing 4.66E+2 curies of radioactivity.

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

Meteorological dispersion was good 30% of the time, fair 44% of the time and poor 26% 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 on the environment.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

COMMON APPENDIX A GASEOUS EFFLUENTS - APPLICABLE LIMITS A. Table 1A lists the total curies released and the release rate.

The percent of applicable limit compares the released concentrations to the concentration limits of 10 CFR 20, Appendix B, Table II, Column 1.

B. Table 1E lists the air doses as calculated using the historical X/Q.

dose due to noble gases released in gaseous effluents from S.O.N.G.S.

reactor) to areas at and beyond the site boundary shall be limited to following values:

The air (per the

1. During any calendar quarter:

2.

During any calendar year:

g 5 mrad for gamma radiation and g 10 mrad for beta radiation.

10 mrad for gamma radiation and g 20 mrad for beta radiation.

C. The dose to a Member of the Public from iodines, tritium, and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released form 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:

S7.5 mrem to any organ.

S15 mrem to any organ.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

COMMON APPENDIX A (Continued)

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

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

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

B. Table 2D lists doses due to liquid releases.

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

1.

During any calendar quarter:

1.5 mrem to the total body and 5

mrem to any organ.

2.

During any calendar year:

3 mrem to the total body and 10 mrem to any organ.

METEOROLOGY

METEOROLOGY The meteorology of the San Onofre Nuclear Generating Station for each of the four quarters, 1999 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.

This data is available, as well as the hourly data for the Annual Report, but has not been included in this report because of the bulk of data records.

Table 4A lists the joint frequency distribution for each quarter, 1999.

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 (1999)

METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 98123124-99033123 WIND SPEED (M/S)

AT 10 METER LEVEL

.22

.50 0

0 0

0 EXTREMELY UNSTABLE

.51

.75 0

0 0

0

.I76 1.0 0

0 0

0 1.1 1.5 0

1 0

0 0

1 0

0 0

0 1.6 2.0 0

0 0

0 1

0 0

0 1

1 1

2 0

0 0

0 PASQUILL A (DT/DZ <

2.1-

3.

3.0 5,

0 0

1 1

0 1

2 8

1 6

2 5

5 5

2 1

0 0

1.9

.1

.0 0

0 0

0 1

1

.7 14

.3 0

0 13 0

0

°C/100 5.1 7.0 0

0 0

3 15 13 11 20 53 25 2

0 METERS) 7.1 10.0 0

0 0

2 10 3

3 16 22 32 2

0 10.1 13.0 0

0 0

0 1

0 4

1 0

2 3

3 0

0 13.1 18.0 0

0 0

1 0

0 0

0 1

3 0

0

>18 TOTAL 0

0 0

1 0

0 2

1 2

8 49 41 44 86 134 78 4

0 TOTALS 0

0 0

3 6

31 159 142 90 14 5

0 450 NUMBER OF VALID HOURS 450 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 2160 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ

-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

1 0

0 0

1 NNE 1

0 0

1 0

0 0

0 2

NE 0

0 0

1 1

0 2

ENE 0

0 0

E 0

0 0

ESE 0

0 0

SE 0

0 0

1 1

0 0

0 2

SSE 0

0 0

1 1

0 0

0 2

S 0

0 0

0 2

3 3

0 0

0 8

SSW 0

0 0

0 1

0 0

1 0

0 2

SW 0

0 0

1 5

1 1

0 0

0 8

WSW 0

0 0

1 0

0 0

1 0

0 2

W 0

0 0

1 2

1 0

0 0

0 4

WNW 0

0 0

3 1

0 0

0 8

NW 0

0 0

0 1

0 0

1 0

0 2

NNW 0

0 0

TOTALS 1

0 0

0 2

7 11 10 7

4 1

0 43 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 43 0

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD WIND DIR N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 0

2160 EXTREMELY UNSTABLE

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 98123124-99033123 WIND SPEED (M/S)

AT 10 METER LEVEL

.51

.75 0

0 0

0 0 0 SLIGHTLY

.76 1.0 0

0 0

0 PASQUILL C UNSTABLE (-1.7 < DT/DZ

-1.5 °C/100 METERS) 1 1

.1-1.6-2.1-3.1-5.1

.5 2.0 3.0 5.0 7.0 0

0 0

1 0

0 0

0 1

0 0

1 0

0 0

0 1

0 0

1 0

0 0

1 0

3 0

0 1

0 0

1 0

0 1

0 2

0 1

1 1

0 0 0 1

3 1

1 2

3 1

0 1

0 0

0 1

TOTALS 1

0 0

2 2

6 15 12 10 2

1 0

51 NUMBER OF VALID HOURS 51 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 2160 PASQUILL D NEUTRAL (-1.5 < DT/DZ < -0.5 °C/100 METERS)

WIND

.22-

.51-

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

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 4

1 0

0 1

1 1

7.1 10.0 1

0 1

0 0

2 0

1 1

0 0

1 2

10.1 13.0 0

0 0

1 0

0 0

1 0

0 0

13.1 18.0 0

0 0

0 1

0 0

>18 TOTAL 0

0 0

2 2

1 1

0 0

2 7

7 5

5 4

4 5

5 u

0 0

1 0

0 0

0 1

u 0

2 0

0 0

1 0

1 1

0 0

3 1

1 1

1 0

1 1

0 0

1 0

3 1

0 2

0 3

0 0

3 2

2 3

6 5

1 2

1 5

18 33 4

5 1

1 2

3 4

10 4

1 7

2 1

4 1

6 1

4 1

5 64 16 7

10 2

1 0

2 25 24

.7 9

1 i0

.8 2

1 9

8 2

5 3

0 3

2 26 18 10 7

7 6

7 11 18 8

133 1

1 2

2 2

12 20 10 3

4 1

1 5

7 13 5

89 0

0 0

0 8

2 1

0 1

1 0

0 5

1 19 19 1549 0

0 1

0 0

2 8

2 0

1 0

0 0

0 1

0 15 0

0 0

0 1

1 0

0 1

0 0

0 3 19 23 12 4

8 25 94 69 42 38 29 22 38 38 58 30 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 549 0

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD WIND DIR N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW

.22

.50 0

1 0

0 0

0 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTALS 0

0 0

0 1

0 2160

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 98123124-99033123 WIND SPEED (M/S)

AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ *, -1.5 0C/100 METERS)

.22

.50 0

0 0

0

.51

.75 0

0 0

0

.7b 1.0 1

1 0

0 0

0 1.1 1.5 1

4 3

0 1

0 0

1 0

1 1.6 2.0 0

3 8

1 0

5 2

2 0

1 1 1 0

1 1

0 2.1 3.0 2

26 14 1

4 5

3 3

1 2

2 3

0 0

0 2

3.1 5.0 6

40 5

2 2

4 5

4 1

0 0

2 2

5 8

4 5.1 7.0 7

20 3

0 2

1 5

3 0

0 0

1 0

1 2

2 7.1 10.0 2

5 6

1 2

1 3

0 0

0 3

1 10.1 13.0 1

1 1

0 1

0 0

0 0 0

1 0

13.1 18.0 0

0 3

0 0

4 1

0

>18 TOTAL 0

0 0

0 20 100 43 5

12 16 19 12 2

3 3

7 2

12 16 10 TOTALS 0

0 2

11 26 68 90 47 24 6

8 0

282 NUMBER OF VALID HOURS 282 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 2160 PASQUILL F MODERATELY STABLE (1.5 e 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 1

1 1

1 4

6 4

1 0

0 0

19 NNE 0

0 0

2 8

20 72 32 12 0

0 0

146 NE 0

2 0

5 9

26 16 5

3 2

1 0

69 ENE 0

0 0

1 2

9 4

0 0

0 16 E

0 0

1 6

2 2

0 0

11 ESE 0

0 0

0 3

3 1

0 0

0 7

SE 0

0 0

0 1

4 2

0 1

0 0

0 8

SSE 0

0 0

1 0

0 4

1 0

0 0

0 6

S 0

0 0

1 0

0 0

0 1

SSW 0

0 0

1 0

0 0

0 1

SW 0

0 0

0 1

1 0

0 0

0 2

WSW 0

0 0

1 2

1 0

0 0

0 4

W 0

0 0

1 0

0 0

0 1

WNW 0

0 0

1 3

4 1

0 0

0 9

NW 0

0 0

1 3

1 0

0 0

0 5

NNW 0

0 0

TOTALS 0

3 1

11 28 79 113 49 18 2

1 0

305 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 305 0

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD WIND DIR N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 0

2160

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 98123124-99033123 WIND SPEED (M/S)

AT 10 METER LEVEL EXTREMELY STABLE 6-1.1-1.6 0

1.5 2.0 0

0 1

5 0

2 4

0 2

4 0

0 2

0 0

1 0

0 1

0 0

1 0

1 1

0 0

0 1

0 0

0 PASQUILL G (DT/DZ > 4 2.1-

3.

3.0

5.

2 16 15 9

1 1

2 1

0 1

0 2

1 0

.0 'C/100 METERS)

.1

.0 5

69 12 6

1 1

0 1 1

0 0 0

2 6

0 2

5.1 7.0 1

120 20 0

1 0

0 0

0 1

1 4

1 0

A 7

TOTALS 5

1 1

7 20 52 136 148 92 18 0

0 480 NUMBER OF VALID HOURS 480 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 2160 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

2 5

5 12 25 14 8

1 0

0 73 NNE 5

0 1

10 16 68 192 177 99 18 0

0 586 NE 0

2 0

10 24 56 65 31 19 5

6 0

218 ENE 0

0 0

3 7

20 13 1

3 0

0 0

47 E

0 0

0 2

4 14 5

8 4

1 0

0 38 ESE 0

0 0

1 12 13 8

3 13 0

2 0

52 SE 0

1 0

2 6

13 34 32 25 10 8

0 131 SSE 0

0 1

2 4

16 34 29 15 3

3 0

107 S

0 0

0 3

4 10 39 32 16 5

0 1

110 SSW 0

1 1

2 8

19 27 21 8

2 1

1 91 SW 0

0 1

2 8

13 40 19 6

1 1

0 91 WSW 2

0 0

3 8

14 53 27 17 5

0 0

129 W

0 0

1 1

3 12 76 62 27 3

1 1

187 WNW 0

0 0

2 2

14 43 46 42 3

7 0

159 NW 1

0 1

3 5

6 23 25 20 7

2 0

93 NNW 0

0 1

1 1

7 15 14 8

1 0

0 48 TOTALS 8

5 9

52 117 307 692 541 330 65 31 3

2160 7.1 10.0 3

81 7

0 0

10.1 13.0 0

17 1

0 0

13.1 18.0 0

0 0

>18 TOTAL 0

0 0

n 12 312 91 21 5

3 4

3 1

1 0

4 4

9 3

7 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2160 0

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD.7 1.

WIND DIR N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW

.22

.50 0

3 0

0 0

2 0

0 0

0

.51

.75 0

0 0

0 0 0 1

0 0

0 0 0 0

2160

.0

°C/100 METERS)

.7 1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99033124-99063023 WIND SPEED (M/S)

AT 10 METER LEVEL EXTREMELY UNSTABLE

.22

.50 0

0 0

.51

.75 0

0 0

.76 1.0 0

0 0

1.1 1.5 0

0 0

1.6 2.0 0

0 0

PASQUILL A (DT/DZ <

2.1-3 3.0 5

0 0

0 1 1

3 4

2 3

1 0

0 15 1:

-1.9

.I

.0 0

0 0

0 1

0 4

12 22 37 26 9

1 0

12

°C/100 5.1 7.0 0

0 0

0 1

3 18 17 55 78 100 11 0

0 283 METERS) 7.1 10.0 0

0 0

3 26 26 22 28 64 16 0

0 185 10.1 13.0 0

0 0

3 15 1

1 5

1 4

1 0

31 13.1 18.0 0

0 0

1 0

0 0

7 1

0 9

>18 TOTAL 0

0 0

0 0 0

0 0

0 2

10 64 60 104 150 194 48 3

0 635 NUMBER OF VALID HOURS 635 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 2

TOTAL HOURS FOR THE PERIOD 2184 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ * -1.7 °C/100 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

ENE 0

0 0

E 0

0 0

ESE 0

0 0

SE 0

0 0

SSE 0

0 0

3 1

1 0

0 5

S 0

0 0

1 3

4 3

2 1

0 14 SSW 0

0 0

0 4

6 8

2 0

0 20 SW 0

0 0

0 1

1 10 6

8 0

0 0

26 WSW 0

0 0

0 7

2 1

1 0

0 11 W

0 0

5 0

0 0

1 0

6 WNW 0

0 0

1 3

3 0

0 0

0 7

NW 0

0 0

0 1

0 0

0 1

NNW 0

0 0

TOTALS 0

0 0

0 1

3 32 24 22 6

2 0

90 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 90 2

NUMBER OF CALMS TOTAL HOURS FOR WIND DIR N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTALS THE PERIOD 0

2184

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99033124-99063023 WIND SPEED (M/S)

AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ * -1.5 °C/I00 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

SE 0

0 0

0 1

0 0

0 2

SSE 0

0 0

0 1

0 0

0 3

0 0

0 4

S 0

0 0

0 1

1 2

5 2

3 2

0 16 SSW 0

0 0

0 3

8 8

0 0

0 19 SW 0

0 0

0 5

9 4

1 0

0 19 WSW 0

0 0

2 4

1 4

1 0

0 12 W

0 0

0 1

2 1

0 0

4 WNW 0

0 0

1 3

1 1

0 0

0 6

NW 0

0 0

2 0

1 0

0 3

NNW 0

0 0

TOTALS 0

0 0

0 2

5 21 27 23 6

2 0

86 NUMBER OF VALID HOURS 86 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 2

TOTAL HOURS FOR THE PERIOD 2184 PASQUILL D NEUTRAL (-1.5 < DT/DZ * -0.5 °C/100 METERS)

WIND

.22-

.51-

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

>18 TOTAL DIR

.50

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

0 0

0 1

1 9

14 1

0 0

26 NNE 0

0 0

0 1

7 27 5

0 0

40 NE 0

0 0

1 1

4 18 6

1 0

0 0

31 ENE 0

0 0

0 1

6 7

4 1

0 0

0 19 E

0 0

0 4

6 15 1

0 0

0 26 ESE 0

0 0

0 1

6 13 6

4 1

1 0

32 SE 0

0 0

2 1

7 25 45 35 10 5

0 130 SSE 0

0 0

12 54 35 54 32 17 0

204 S

0 0

1 5

33 31 38 22 5

3 138 SSW 0

0 0

0 3

11 32 15 15 5

1 1

83 SW 0

0 0

1 3

13 19 12 6

2 0

0 56 WSW 0

0 0

0 4

9 15 4

2 1

1 0

36 W

0 0

0 3

3 8

19 5

1 5

1 0

45 WNW 0

0 0

0 2

10 21 6

4 3

2 2

50 NW 0

0 0

0 3

11 12 13 5

4 0

0 48 NNW 0

0 0

0 2

6 9

4 1

0 0

0 22 TOTALS 0

0 0

8 27 128 324 207 168 85 33 6

986 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 986 2

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0 2184

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99033124-99063023 WIND SPEED (M/S)

AT 10 METER LEVEL P

SLIGHTLY STABLE (-0.5

.76-1.1-1.6 1.0 1.5 2.0 0

0 1

0 2

0 0

1 3

0 0

1 0

2 0

0 0

1 0

0 1

1 0

0 0

1 0

0 0

1 1

0 0

1 0

0 0

0 ASQUILL E

< DT/DZ ! -1.5 °C/100 METERS) 2.1 3.0 5

9 4

1 3

5 1

2 3

2 0

0 0

3 3.1 5.0 4

20 5

1 3

6 5

6 3

1 0

0 0

4 1

0 5.1 7.0 0

6 0

0 2

1 5

0 0

2 1

0 7.1 10.0 0

0 0

0 1

0 3

0 0

1 1U.I 13.0 0

0 0

0 13.1 18.0 0

0 0

0

.0 0

0 0

2 0

0 4

TOTALS 1

0 0

7 11 38 59 17 5

0 2

0 140 NUMBER OF VALID HOURS 140 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 2

TOTAL HOURS FOR THE PERIOD 2184 PASQUILL F MODERATELY STABLE (1.5

DT/DZ * -0.5 °C/100 METERS)

WIND

.22-

.51-

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

>18 TOTAL DIR

.50

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

0 0

0 2

1 0

0 0

3 NNE 0

0 0

1 3

13 23 10 3

1 0

0 54 NE 0

0 0

0 4

7 7

1 0

0 0

0 19 ENE 0

0 0

0 2

4 0

0 0

0 6

E 0

0 0

0 2

0 1

0 0

0 3

ESE 0

0 0

3 0

0 0

0 3

SE 0

0 0

0 1

0 0

1 0

0 0

0 2

SSE 0

0 0

0 4

0 0

0 4

S 0

0 0

SSW 0

0 0

SW 0

0 0

1 1

0 0

0 2

WSW 0

0 0

1 1

0 0

0 2

W 0

0 0

1 0

0 0

0 1

WNW 0

0 0

4 0

0 0

0 4

NW 0

0 0

NNW 0

0 0

1 1

0 0

0 2

TOTALS 0

0 0

2 13 31 38 17 3

1 0

0 105

>18 TOTAL 0

0 0

10 37 13 3

12 13 15 10 6

4 0

0 2

7 4

VALID HOURS INVALID HOURS 105 2

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD WIND DIR N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW

.22

.50 0

0 0

0 1

0 0

0

.51

.75 0

0 0

0 0 0 NUMBER OF NUMBER OF 0

2184 I

r

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99033124-99063023 WIND SPEED (M/S)

AT 10 METER LEVEL EXTREMELY STABLE 6-1.1-1.6 0

1.5 2.0 0

0 0

1 0

0 3

0 0

1 0

0 1

0 0

1 0

0 0

0 PASQUILL G (DT/DZ > 4 2.1-3 3.0 5

0 5

6 0

0 0

1 0

0 1

2 0

0 0

.0 *C/100 METERS)

.1

.0 1

28 14 2

0 0

1 0

2 0 5.1 7.0 0

36 3

0 0

4 0

7.1 10.0 0

17 0

0 0

0 1

0 0

0 0 0

1 0,00 1

TOTALS 0

0 0

2 6

16 49 44 18 5

0 0

140 NUMBER OF VALID HOURS 140 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 2

TOTAL HOURS FOR THE PERIOD 2184 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 NNE NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTALS U

0 0

0 1

0 0

0 1 U

0 0

0 0 0

0 0

0 0 1

3 2

0 2

2 1

0 2

0 4

0 0

0 19 z

5 11 4

2 3

4 2

2 4

5 4

4 3

3 2

60 16 34 21 11 7

14 9

15 11 17 18 15 14 13 11 10 236 20 98 45 10 11 19 32 64 45 52 56 65 52 42 14 10 635 1

57 10 4

17 7

52 41 58 46 82 85 107 31 16 5

619 0

20 1

1 2

4 39 61 69 57 40 35 65 21 7

2 424 0

6 0

0 0

1 10 36 42 8

4 8

6 7

6 0

134 0

0 0

1 5

17 8

2 0

1 2

9 3

0 48 0

0 0

0 3

1 0

0 0

2 0

0 6 40 223 90 30 42 49 153 238 239 187 207 213 254 128 60 29 2182 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2182 2

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD.7 1.

WIND DIR N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW

.22

.50 0

0 0

0

>18 TOTAL

.51

.75 0

0 0

0 0 0 10.1 13.0 0

5 0

0 0

13.1 18.0 0

0 0

0 1

92 26 2

1 1

2 1

1 1

0 2

2 6

1 0

2184

.0 °C/100 METERS)

.7 1.(

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99063024-99093023 WIND SPEED (M/S)

AT 10 METER LEVEL EXTREMELY UNSTABLE

.22

.50 0

0 0

0

.51

.75 0

0 0

0

.76 1.0 0

0 0

0

[.1 1.5 0

0 0

0 1

2 0

0 0

0 1.6 2.0 0

0 0

0 2

1 7

6 4

0 0

0 PASQUILL A (DT/DZ <

2.1-3 3.0 5

0 0

0 1

7 4

5 20 13 10 0

0

-1.9

.1

.0 0

0 0

1 9

9 16 38 13 1

0 0

.C/io 5.1 7.0 0

1 0

0 0

1 9

15 28 50 102 59 3

0 METERS) 7.1 10.0 0

0 0

0 1

3 11 22 11 15 47 62 7 0 0

0 0

TOTALS 0

0 0

3 20 60 147 268 179 12 1

0 690 NUMBER OF VALID HOURS 690 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 2208 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 NNE 0

0 0

NE 0

0 0

ENE 0

0 0

E 0

0 0

ESE 0

0 0

SE 0

0 0

SSE 0

0 0

2 0

0 0

0 2

S 0

0 0

2 2

0 1

2 0

0 7

SSW 1

0 0

0 1

2 2

9 2

0 0

0 17 SW 0

0 0

3 8

7 4

0 0

0 22 WSW 0

0 0

1 5

1 0

0 0

0 7

W 0

0 0

1 0

2 7

0 0

0 10 WNW 0

0 0

1 3

1 1

0 0

0 6

NW 0

0 0

1 1

3 1

0 0

0 6

NNW 0

0 0

TOTALS 1

0 0

1 1

12 28 23 9

2 0

0 77 10.1 13.0 0

0 0

1 4

3 0

0 1

3 0

0 13.1 18.0 0

0 0

0 1

0 0

>18 TOTAL 0

0 0

0 1

0 0

1 7

43 54 68 131 210 165 10 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 77 0

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD WIND DIR N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 0

2208 EXTREMELY UNSTABLE

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99063024-99093023 WIND SPEED (M/S)

AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ * -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 NNE 0

0 0

0 1

0 0

0 2

NE 0

0 0

ENE 0

0 0

E 0

0 0

ESE 0

0 0

SE 0

0 0

1 0

0 0

0

.0 0

1 SSE 0

0 0

6 0

0 0

0 6

S 0

0 0

2 4

2 0

1 0

0 9

SSW 0

0 0

0 2

10 5

1 0

0 18 SW 0

0 0

0 3

3 4

5 3

0 0

0 18 WSW 0

0 0

2 3

0 0

0 5

W 0

0 0

2 7

3 0

0 0

0 12 WNW 0

0 0

1 3

2 0

0 0

0 6

NW 0

0 0

0 2

5 6

0 0

0 13 NNW 0

0 0

TOTALS 0

0 0

0 4

11 26 33 14 2

0 0

90 NUMBER OF VALID HOURS 90 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 2208 PASQUILL D NEUTRAL (-1.5 < DT/DZ * -0.5 °C/100 METERS)

WIND

.22-

.51-

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

>18 TOTAL DIR

.50

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

0 0

0 2

5 15 10 5

0 0

1 0

38 NNE 0

0 1

2 7

20 33 4

0 0

67 NE 0

0 0

2 4

8 14 0

0 0

28 ENE 0

0 0

0 1

7 2

0 0

0 10 E

0 0

2 3

7 0

0 0

12 ESE 0

0 0

2 1

6 5

2 4

1 0

0 21 SE 0

0 0

2 2

13 28 18 14 0

1 0

78 SSE 0

0 1

1 10 24 52 38 24 5

0 0

155 S

0 1

2 3

7 19 34 28 21 1

0 0

116 SSW 0

0 0

5 5

10 20 18 14 0

0 0

72 SW 0

1 0

4 5

18 15 6

0 1

0 0

50 WSW 0

0 1

3 6

13 9

2 1

0 0

0 35 W

0 0

2 1

6 17 23 8

3 0

0 0

60 WNW 0

1 2

2 7

14 32 6

4 0

0 0

68 NW 0

0 0

1 4

7 21 21 11 1

0 0

66 NNW 0

1 0

4 5

13 18 5

0 0

46 TOTALS 0

4 9

34 77 207 323 161 96 9

2 0

922 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 922 0

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0 2208

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99063024-99093023 WIND SPEED (M/S)

AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ - -1.5 °C/100 METERS)

.7b 1.0 1

3 1

1 0

0 0

0 1

2 0

0 0

0 1

0 1.1 1.5 0

4 1

1 2

0 0

2 0

3 0

0 6

1 2

2 1.6 2.0 7

8 4

1 2

2 2

2 4

2 3

0 1

2 0

1 2.1 3.0 8

26 5

0 6

0 2

3 2

2 0

6 3

2 1 4

3.1 5.0 10 27 3

1 1

0 3

9 2

2 2

2 5

4 3

1 5.1 7.0 1

1 0

0 0

0 6

0 0

1 1

0 0 1

2 1

7.

10.

.1-10.1-13.1

.0 13.0 18.0 0

0 0

0 1

0 0

1 0

0 0

1 0

0 0

0

>18 TOTAL 0

0 0

0 27 69 14 4

11 2

14 16 9

12 6

10 16 11 9

9 TOTALS 0

2 10 24 41 70 75 14 3

0 0

0 239 NUMBER OF VALID HOURS 239 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 2208 PASQUILL F MODERATELY STABLE (1.5 ! DT/DZ * -0.5 °C/100 METERS)

WIND

.22-

.51-

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

>18 TOTAL DIR

.50

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

0 0

0 2

2 1

4 1

1 0

0 0

11 NNE 0

1 1

0 2

15 35 7

2 0

0 0

63 NE 0

0 0

3 3

12 5

0 0

0 23 ENE 0

0 0

2 0

0 0

0 2

E 0

0 0

0 1

1 0

0 0

0 2

ESE 0

0 0

0 1

0 0

0 1

SE 0

0 0

1 0

0 1

0 0

0 3

SSE 0

0 0

1 0

0 0

0 3

S 0

0 0

SSW 0

0 0

SW 0

0 0

WSW 0

0 0

1 0

0 0

0 1

W 0

0 0

WNW 0

1 0

0 0

0 2

0 0

0 3

NW 0

0 0

NNW 0

0 0

0 1

1 1

0 0

0 3

TOTALS 0

2 1

8 8

33 46 10 7

0 0

0 115 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 115 0

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 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

1 1

0 0

2208

7.

10.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99063024-99093023 WIND SPEED (M/S)

AT 10 METER LEVEL EXTREMELY STABLE 6-1.1-1.6 0

1.5 2.0 0

0 2

0 0

0 2

1 0

0 1

0 0

1 0

0 0

1 0

0 0

0 1

0 0

0 1

0 PASQUILL (DT/DZ >

2.1 3.0 0

2 1

0 0

1 0

0 0

1 G

4.0 'C/100 METERS) 3.1 5.0 2

18 1

1 0

0 0

TOTALS 0

0 0

4 6

5 22 32 5

1 0

0 75 NUMBER OF VALID HOURS 75 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 0

TOTAL HOURS FOR THE PERIOD 2208 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S)

AT 10 METER LEVEL WIND

.22-

.51-

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

>18 TOTAL DIR

.50

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

0 0

1 4

16 24 26 7

1 0

80 NNE 0

1 5

6 18 63 114 45 5

0 0

0 257 NE 0

0 1

6 11 26 23 0

0 0

67 ENE 0

0 1

3 3

9 4

0 0

0 20 E

0 0

0 2

6 10 8

0 0

0 26 ESE 0

0 0

2 4

7 6

2 4

1 0

0 26 SE 0

0 0

3 4

17 31 24 17 0

1 0

97 SSE 0

0 1

4 12 29 62 48 27 6

0 0

189 S

0 1

3 3

13 32 51 39 33 8

1 0

184 SSW 1

0 2

8 10 18 35 53 43 4

0 0

174 SW 0

1 0

5 18 29 45 47 18 1

0 0

164 WSW 0

1 1

7 12 42 57 53 17 0

0 0

190 W

0 1

2 8

11 37 85 113 51 1

0 0

309 WNW 0

2 2

3 9

28 73 69 70 4

0 0

260 NW 0

0 1

3 4

9 27 34 26 1

0 0

105 NNW 0

1 0

7 6

18 20 7

1 0

0 0

60 TOTALS 1

8 20 74 157 398 667 541 313 26 3

0 2208 5.1 7.0 0

32 0

0 0

7.1 10.0 0

3 0

0 0

0 1

10.1 13.0 0

0 0

1 0

13.1 18.0 0

0 0

>18 TOTAL 0

0 0

4 55 2

4 1

2 0

0 0

1 0

1 1

NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2208 0

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD.7 1

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

2208

.7 i.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99093024-99123123 WIND SPEED (M/S)

AT 10 METER LEVEL EXTREMELY UNSTABLE

.76 1.0 0

0 0

0 1.1 1.5 0

0 0

0 1.6 2.0 0

0 0

0 1

0 0

0 1

0 0

0 PASQUILL A (DT/DZ 2.1 3.0 0

0 0

0 1 1 15 6

4 1

0 0

< -1.9 3.1 5.0 0

0 0

0 16 12 8

20 40 28 2

0

'C/100 METERS) 5.1-7.1 7.0 10.0 0

0 0

0 2

2 9

7 2

0 7

1 14 2

52 8

35 26 2

3 0

0 10.1 13.0 0

0 3

0 0

2 1

0 13.1 18.0 0

0 0

1 0

0

>18 TOTAL 0

0 0

0 3

0 1

0 0

4 33 15 31 42 105 93 8

0 TOTALS 0

0 0

0 2

28 126 123 49 6

1 0

335 NUMBER OF VALID HOURS 335 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 11 TOTAL HOURS FOR THE PERIOD 2208 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ - -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

NE 0

0 0

0 1

0 0

0 1

ENE 0

0 0

E 0

0 0

ESE 0

0 0

SE 0

0 0

0 1

0 0

1 0

0 0

0 2

SSE 0

0 0

1 0

0 0

0 1

S 0

0 0

0 1

0 0

0 1

SSW 0

0 0

1 0

0 0

0 3

SW 0

0 0

0 1

1 0

0 0

0 2

WSW 0

0 0

0 1

0 0

0 1

W 0

0 0

1 2

1 0

0 0

0 4

WNW 0

0 0

0 3

8 0

0 0

0 11 NW 0

0 0

2 1

0 0

0 3

NNW 0

0 0

TOTALS 0

0 0

1 1

2 8

15 2

0 0

0 29 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 29 11 NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 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

2208 EXTREMELY UNSTABLE

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99093024-99123123 WIND SPEED (M/S)

AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ * -1.5 °C/1O0 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

0 1

0 0

0 1

0 2

NE 0

0 0

1 0

0 1

ENE 0

0 0

E 0

0 0

ESE 0

0 0

SE 0

0 0

SSE 0

0 0

0 4

0 0

0 4

S 0

0 0

4 4

0 0

0 8

SSW 0

0 0

0 3

2 0

0 0

0 5

SW 0

0 0

1 1

0 0

0 2

WSW 0

0 0

0 5

0 0

0 5

W 0

0 0

1 0

0 0

0 2

WNW 0

0 0

0 2

1 0

0 0

0 3

NW 0

0 0

0 3

1 2

0 0

0 6

NNW 0

0 0

TOTALS 0

0 0

6 19 6

7 1

1 0

40 NUMBER OF VALID HOURS 40 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 11 TOTAL HOURS FOR THE PERIOD 2208 PASQUILL D NEUTRAL (-1.5 < DT/DZ - -0.5 °C/100 METERS)

WIND

.22-

.51-

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

>18 TOTAL DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 NN NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTALS u

0 0

U 0

0 0

0 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS u

u I

0 0

2 0

0 0

0 1

0 0

1 2

1 0

1 1

0 0

4 0

2 1

0 2

1 0

0 1

0 2

5 0

1 2

0 0

3 1

11 22 337 11 5

4 2

0 0

2 1

3 1

6 3

7 6

10 1

3 1

6 1

4 6

13 2

2 0

1 6

13 8

7 6

2

.6

.0

.0 7

5 1

62 109 79 40 3

6 4

0 0

1 3

12 6

3 2

2 0

15 17 0

2 3

0 0

1 3

5 6

3 0

1 0

3 12 1

0 1

0 0

1 1

0 2

0 0

0 5

0 11 11 0

0 0

1 0

0 0

0 1

0 2

NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0 0

0 0

0 0 0 16 27 12 3

0 6

14 38 30 20 18 14 27 38 54 20 337 0

2208

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99093024-99123123 WIND SPEED (M/S)

AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ *- -1.5 *C/100 METERS)

.22

.50 0

0 0

0 0 1

0 0

.51

.75 0

1 0

0 0

0 1

0 0

0

.76 1.0 0

0 0

0 1

0 0

0 1.1 1.5 3

1 2

2 0

1 1

2 0

0 0

2 0

0 1

1 1.6 2.0 3

14 4

3 2

2 2

4 4

1 0

3 0

1 3

1 2.1 3.0 10 22 10 5

1 6

8 1

8 6

3 3

7 3

5 2

3.1 5.0 12 42 10 5

3 6

13 12 7

1 2

2 13 8

5 10

5.

1 7.0 4

10 1

1 7

2 9

9 0

0 2

0 1

15 9

5 7.1 10.0 1

2 4

3 0

1 6

3 1

0 1

0 0

1 2

1 10.1 13.0 0

2 0

0 0

1 1 0

0 0

0 1 13.1 18.0 0

0 8

0 0

1 0

0 0

0

>18 TOTAL 0

0 0

0 33 94 39 19 14 18 39 33 21 8

9 10 21 29 25 21 TOTALS 1

2 1

16 47 100 151 75 26 5

9 0

433 NUMBER OF VALID HOURS 433 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 11 TOTAL HOURS FOR THE PERIOD 2208 PASQUILL F MODERATELY STABLE (1.5 - DT/DZ

-0.5 'C/100 METERS)

WIND

.22-

.51-

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

>18 TOTAL DIR

.50

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

0 0

1 4

3 4

12 5

1 0

0 0

30 NNE 0

0 0

3 12 37 80 29 7

0 0

0 168 NE 0

0 0

5 9

20 23 7

4 1

0 0

69 ENE 0

0 1

1 6

7 3

0 1

0 0

0 19 E

0 0

0 4

6 5

4 1

0 0

20 ESE 0

0 1

3 2

4 6

0 0

0 16 SE 0

0 0

7 3

2 2

0 0

0 14 SSE 0

0 0

1 0

4 4

4 1

0 0

0 14 S

0 0

0 3

1 7

2 0

0 0

13 SSW 0

0 0

4 2

0 0

0 6

SW 0

0 0

1 0

0 0

0 2

WSW 0

0 0

1 1

1 3

1 1

0 0

0 8

W 0

0 0

0 1

5 5

2 0

0 0

0 13 WNW 0

0 0

1 1

1 9

6 1

1 0

0 20 NW 0

0 1

0 3

1 5

3 3

0 0

0 16 NNW 0

0 0

1 1

2 3

2 2

0 0

0 11 TOTALS 0

0 4

28 46 110 164 62 23 2

0 0

439 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 439 11 NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD WIND DIR N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 0

2208

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1999)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99093024-99123123 WIND SPEED (M/S)

AT 10 METER LEVEL EXTREMELY STABLE 6-1.1-1.6 0

1.5 2.0 0

0 1

0 2

1 0

0 6

1 2

0 0

5 2

0 2

4 0

3 1

1 0

6 0

1 1

0 2

1 0

1 1

0 0

2 0

0 0

0 1

0 PASQUILL G (DT/DZ > 4 2.1-3 3.0 5

2 7

16 5

3 3

2 1

2 4

2 0

4 4

0 3

.0 'C/100 METERS)

.1

.0 12 79 35 7

2 5

3 6

0 0

3 8

6 3

5.1 7.0 1

157 18 2

1 1

3 4

0 0

0 3

5 2

7.1" 10.0 5

70 13 0

0 1

0 0

0 2

1 1

10.1 13.0 1

13 1

0 0

0 1

0 13.1 18.0 0

0 0

0

>18 TOTAL 0

0 0

0 22 329 89 17 13 19 12 18 4

7 4

2 7

17 13 11 TOTALS 4

0 2

19 26 58 169 197 93 16 0

0 584 NUMBER OF VALID HOURS 584 NUMBER OF CALMS 0

NUMBER OF INVALID HOURS 11 TOTAL HOURS FOR THE PERIOD 2208 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 1

0 0

2 1

1 0

2 0

0 0

0 1

0 8

7 6

9 6

4 5

5 3

4 5

0 3

2 3

75 8

29 19 9

11 8

4 11 7

6 2

7 3

7 8

5 144 21 70 48 17 9

15 18 9

28 19 29 16 32 12 12 11 366 42 215 70 17 9

18 25 35 38 25 18 33 79 68 31 23 746 14 202 30 3

9 4

18 32 15 8

12 17 57 83 39 14 557 8

81 25 4

0 3

11 15 14 3

2 4

8 33 24 5

240 2

15 7

0 0

1 1

1 3

0 0

3 7

1 41 0

1 8

0 0

2 0

0 0

1 1

0 13 0

0 0

0 0 103 620 214 58 48 59 81 112 110 64 68 82 179 211 125 63 2197 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2197 11 NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD.7 1.

WIND DIR N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW

.22

.50 0

0 0

3 0

0 0

1

.51

.75 0

0 0

0 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTALS U

0 0

3 0

0 0

1 0

1 5

0 1

0 0

1 0

0 0

2 0

2208

.0 °C/100 METERS)

.7 1.

13

ML003709674

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