ML13317B649

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Forwards Environ Radiological Monitoring Program Summary Repts
ML13317B649
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 08/06/1991
From: Rosenblum R
Southern California Edison Co
To:
NRC/IRM
Shared Package
ML13317B650 List:
References
NUDOCS 9108120227
Download: ML13317B649 (20)
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Text

Enclosure 1 RESPONSE TO NRC REQUEST FOR RADIOLOGICAL ENVIRONMENTAL INFORMATION Following are responses to an NRC request for additional radiological environmental information. The NRC request is first stated and SCE's response follows.

NRC REQUEST The following information should be provided. If the information requested is already presented in the [Final Environmental Statement] FES or in the February 5, 1986 letter from M. 0. Medford to Mr. G. E. Lear, then those documents can be referenced and the location of the information cited.

General Comments

1.

Provide a description of the changes to the liquid, gaseous, and solid radwaste systems from the systems described in the 1973 FES. A comparison should be presented of the system as it was intended to' operate in the analysis by the staff in 1973 FES, the 1976 Appendix I submittal, and the present mode of operation. The comparison may be in the form of schematics or verbiage or both.

2.

Provide a listing, by year, of the number of occurrences in which San Onofre Unit 1 has exceeded the instantaneous release rates contained in their technical specifications for liquid and gaseous effluents. The occurrences should be further subdivided as liquid, airborne noble gas, or airborne radioiodine and particulates as appropriate. Some of the sources for this information would be LERS, 10 CFR 20.405 reports, 50.72 reports, and reports required by the technical specifications.

SCE RESPONSE TO "

GENERAL COMMENT

S," PART 1 Information updating the 1973 FES was provided in our letter from M. 0.

Medford to G. E. Lear dated February 5, 1986. The changes to the Unit 1 radwaste systems described in that letter are restated in the following table with minor editorial corrections. There have been no significant changes to the liquid, gaseous, or solid radwaste systems since the February 5, 1986 letter was submitted.

RADWASTE SYSTEM CHANGES 1973 FES Change as Described in Section Page February 5, 1986 SCE Letter 3.5.1 3-20 As discussed in the Semiannual Effluent Reports, treated liquid wastes are handled with both "batch" and "continuous" modes of release.(1.2) 3.5.1 3-21 As illustrated in current SONGS Unit 1 piping and Instrumentation Drawings(3) (P&IDs), several changes have been made to the liquid waste-discharge system described by Figure 3.11 of the 1973 FES.

  • Gaseous effluents from the flash tank and gas stripper are routed to the waste gas surge tank of the gaseous radwaste system and from there through the waste gas compressors to the waste gas decay tanks. There is no "waste gas storage tank."
  • The contents of the auxiliary building sump, the reactor sump and the sphere sump are directed to the decontamination drain tank, and not directly through the radwaste process filter into the monitor tanks.
  • The contents of the decontamination drain tank are directed through the radwaste process filter to the monitor tanks, and not directly into the radiochemistry lab drain tank.

3.5.1 3-21 The letdown flowrate may be set at either 45 or 90 gal/min (4.

The letdown flow is processed through the lithium demineralizer for removal of excess lithium only when and as directed by the Chemistry Group.

3.5.1 3-21 As illustrated on the SONGS Unit 1 P&IDs 3, the shim bleed stream flowpath from the letdown flow stream to the coolant radioactive waste processing system (flash tank) is normally closed.

RADWASTE SYSTEM CHANGES 1973 FES Change as Described

_ 1 in Section Page February 5, 1986 SCE Letter 3.5.2 3-26 As illustrated on current SONGS Unit 1 P&IDs"3, changes have been made to the radioactive gaseous waste system described by Figure 3.12 of the 1973 FES:

  • Each unit of the reactor containment air cleanup system also contains a demister and prefilter in addition to the charcoal absorber and high-efficiency filter.
  • Each of the exhaust paths from the reactor containment and the auxiliary building consists of flow through a building-unique prefilter discharging to a common discharge header. From the header a fan forces the exhaust through a high efficiency filter and to the plant vent stack.
  • Discharges from the air ejectors and the mechanical vacuum pumps are exhausted directly to the plant vent stack without passing through either a high efficiency filter or a fan.
  • Radioactive waste gas is no longer processed through the cryogenic waste gas treatment system which has been abandoned in place.

3.5.2 3-29 The alternative treatment of the gaseous waste that utilized the cryogenic absorption system is no longer used. The system was abandoned following unfavorable operating experience.

3.5.2 3-30 As illustrated in the SONGS Unit 1 P&IDs (),

all vent paths to the plant vent stack do not flow through high efficiency filters.

3.5.2 3-30 As illustrated in the SONGS Unit 1 P&IDs 3, each unit of the reactor containment air cleanup systems also contains a demister and prefilter in addition to the charcoal absorber and high-efficiency filter.

3.5.3 3-33 Spent ion exchange resins are placed within high integrity containers (HICs) and dewatered. The HIC is shipped to a licensed burial site. Spent filters are either placed within HIC's or encapsulated in cement. Very low level filters are placed in drums with an approved absorbent.

3.5.3 3-33 Clothing worn in the plant is no longer decontaminated offsite. Unit 1 laundry is processed onsite at a central decontamination facility along with the contaminated laundry from Units 2 and 3.

RADWASTE SYSTEM CHANGES 1973 FES Change as Described in Section jPage February 5, 1986 SCE Letter 3.5.3 3-34 The total volume and radioactivity of the solid waste shipped offsite for disposal are reported to the NRC in the Semiannual Effluent Reports 1,2,5 REFERENCES

1.

Southern California Edison Company, "San Onofre Nuclear Generating Station Units 1, 2 and 3 Semiannual Effluent Report," January June 1985.

2.

Southern California Edison Company, "San Onofre Nuclear Generating Station Unit 1 Semiannual Effluent Reports," January - June 1981 through July - December 1984.

3.

Southern California Edison Company, "San Onofre Nuclear Generating Station Unit 1, Piping & Instrumentation Diagrams," Series 5178000.

4.

Southern California Edison Company, "San Onofre Nuclear Generating Station Unit 1 Station Manual, System Descriptions," October 1965.

5.

Southern California Edison Company, "San Onofre Nuclear Generating Station Unit 1 Semiannual Operating Reports," January - June 1973 through July - December 1980.

SCE RESPONSE TO "

GENERAL COMMENT

S", PART 2 There have been no occurrences in which San Onofre Unit 1 exceeded the Technical Specification limits for liquid or gaseous effluents.

NRC REQUEST Solid Radwaste Provide the volume and curie content of the waste shipped offsite via the following headings:

a) resins, filters, evaporator bottoms; b) dry activated waste (DAW);

c) irradiated components; d) others; and e) waste shipped to compactors such as SEG [Scientific Ecology Group]

and the type of waste shipped.

SCE RESPONSE TO "SOLID RADWASTE" The requested information has been extracted from the San Onofre Unit 1 Semiannual Effluent Reports and tabulated below. Although not requested, Shipments of spent fuel off site, as indicated by our shipping records, have also been included. Waste shipped to compactors is included in the Dry Activated Waste totals when the compactor ships the waste for burial.

Therefore, no heading for item e) above has been provided.

SOLID RADWASTE SHIPMENTS

Resins, Filters, Dry Evaporator Activated Irradiated Bottoms Waste Components Spent Fuel Other JUN - DEC.

None None None None None 1967 JAN - JUN.

None 3.96 m3, None None None 1968 1.425 Ci (Note

5)

JUL - DEC.

3 Filters, 6.87 m3, Incore None 1 container 1968 Note 1 0.038 Ci self powered of detectors, contaminated 6.0 Ci lumber, Note JAN - JUN.

None 6.46 m3, None None None 1969 0.130 Ci JUL - DEC.

None 13.5 M3, None None None 1969 3.923 Ci JAN - JUN.

2.12 M3 9.79 M3, None None None 1970

resin, 0.0594 Ci 2.0 Ci JUL - DEC.

None 28.7 M3, None None 0.623 m3 Of 1970 8.41 Ci contaminated wood, Note 1 JAN - JUN.

None 14.8 M3,

None None None 1971 0.978 Ci JUL - DEC.

None 8.03 M3, None None None 1971 0.210 Ci JAN - JUN.

5.66 M3 78.1 M3, None 14 None 1972

resin, 3.48 Ci, assemblies 72.0 Ci Note 2 SOLID RADWASTE SHIPMENTS
Resins, Filters, Dry Evaporator Activated Irradiated Bottoms Waste Components Spent Fuel Other JUL - DEC.

None 52.8 m',

None 41 None 1972 4.19 Ci, assemblies Note 2

JAN - JUN.

None 69.4 m',

None None None 1973 172 Ci, JUL - DEC.

None 43.3 m3, None 9

None 1973 209 Ci assemblies JAN - JUN.

None 57.2 m',

None 3

None 1974 230 Ci assemblies JUL - DEC.

None 10.9 m, None 7

None 1974 0.38 Ci assemblies JAN - JUN.

None 79.6 m',

None 11 None 1975 26 Ci assemblies JUL - DEC.

None None None 10 None 1975 assemblies JAN - JUN.

None 50.1 M3, None 53 None 1976 18.6 Ci assemblies JUL - DEC.

None 94.3 M3, None 2

None 1976 679 Ci assemblies JAN - JUN.

None 249 m3, None 27 None 1977 18.1 Ci assemblies JUL - DEC.

None 120 m3,

None 58 None 1977 42.1 Ci assemblies JAN - JUN.

None 51.8 m3, None 19 None 1978 1.61 Ci assemblies JUL - DEC.

None 131 in, None None None 1978 7.17 Ci JAN - JUN.

None 83.5 m3, None None None 1979 92.4 Ci JUL - DEC.

None None None None None 1979 Note 3 Note 3 Note 3 Note 3 SOLID RADWASTE SHIPMENTS

Resins, Filters, Dry Evaporator Activated Irradiated Bottoms Waste Components Spent Fuel Other JAN - JUN.

2 resin 3.96 M3,

None 13 None 1980 shipments, 51.0 Ci assemblies volume and activity not reported JUL - DEC.

8 resin 708 M3, None 3

None 1980 shipments, 332 Ci assemblies volume and activity not reported JAN - JUN.

12 resin 1353 M3,

None None None 1981 shipments, 620 Ci volume and activity not reported JUL - DEC.

16 M3,

249 M3, None None None 1981 resin and 2.7 Ci

filters, 13.5 Ci JAN - JUN.

3.95 M3, 206 M3, None None 36.7 M3, 1982 filter 7.03 Ci 0.0138 Ci

media, 23.5 Ci JUL - DEC.

2.27 M3, 283 M3, None None 395 M3, 1982

resin, 5.14 Ci 0.0531 Ci 39.5 Ci JAN - JUN.

19.8 M3, 107 M3, None None 67.3 M3, 1983

resin, 5.73 Ci 3.13 Ci 217 Ci JUL - DEC.

None 69.9 M3, None None 68.6 M3, 1983 0.622 Ci 0.134 Ci JAN - JUN.

None 47.2 m',

None None None 1984 0.129 Ci JUL - DEC.

None 147 M3, None None 97.3 M3, 1984 15.0 Ci 0.239 Ci SOLID RADWASTE SHIPMENTS

Resins, Filters, Dry Evaporator Activated Irradiated Bottoms Waste Components Spent Fuel Other JAN - JUN.

None 115 m3, None None 19.1 n3 1985 2.89 Ci 0.67 Ci Note 4

JUL - DEC.

None 21.3 m',

None None 24.9 M3, 1985 2.16 Ci 0.325 Ci Note 4 Note 4 JAN - JUN.

None 38.7 m3, None None 1.7 M3, 1986 3.52 Ci 0.24.Ci JUL - DEC.

4.02 M3, 202 M3, None None 4.24 M3, 1986 370 Ci 8.04 Ci 0.19 Ci Note 4 JAN - JUN.

None 3.18 M3, None None 2.90 M3, 1987 10.5 Ci 1.64 Ci Note 4

JUL - DEC.

4.02 M3, 26.8 M3,

None None 1987 25.7 Ci 12.0 Ci Note 4 JAN - JUN.

None 15.3 M3,

None None 1.70 M3,

1988 0.846 Ci 1.25 Ci Note 4

JUL - DEC.

None 13.6 M3, None None 0.212 M3, 1988 1.85 Ci 0.117 Ci Note 4

JAN - JUN.

16.1 M3,

43.7 M3, None None 2.69 M3, 1989 673 Ci 2.33 Ci 5.20 Ci JUL - DEC.

23.3 M3,

29.1 M3, None None 3.79 M3, 1989 1,020 Ci 0.09 Ci 18.6 Ci JAN - JUN.

None 7.45 M3, None None None 1990 0.197 Ci JUL - DEC.

None 50.6 M3, None None 0.0566 M3,

1990 4.20 Ci 8.34 Ci

_Note 4

Note 1:

The activity for these items was included in the dry activated waste activity for that period.

SOLID RADWASTE SHIPMENTS Note 2:

The total volume for 1972 was corrected subsequent to the 1972 Jan-Jun.

Semiannual Effluent Report. The correction has been applied equally to both 6 month periods.

Note 3:

The data reported in the Jul-Dec. 1979 Semiannual Effluent Report section titled "Solid Waste" was erroneous. Table III of the report and our review of records indicate no solid radwaste was shipped during the Jul-Dec. 1979 period.

Note 4:

This data does not include shipments reported as common to Units 1, 2 and 3.

Note 5:

This is a conservative estimate based on the most active drum (7.5 X 10-2 Ci) times the total number of drums shipped (19).

NRC REQUEST Liquid Effluent and Doses

1.

Provide for all years in which calculations were performed, the doses reported in the Semi-annual Effluent Release Reports and/or the Radiation Environmental Monitoring Program Reports.

2.

Provide for the years 1967-1971 and 1988-1990, the total curies of effluents discharged. The data should be provided in terms of fission and activation products and tritium. Information should also be provided, for the years in which doses were calculated, on the radionuclides which contribute the major portion of the maximum organ and total body doses. [Minor editorial changes have been made to this request for clarity.]

SCE RESPONSE TO "LIQUID EFFLUENTS AND DOSES," PART 1

1.

Calculations for doses at the site boundary due to liquid effluent releases were performed starting in 1985. The data from 1985 through 1990 is provided below. This data was extracted from the Semiannual Effluent Reports. Data contained in the Radiological Environmental Operating Reports (REORs) represents the total dose detected at various offsite locations. It is not possible to determine the source of the dose (i.e., liquid effluent, airborne effluent, or other).

Therefore REOR data was not used in the table below.

LIQUID DOSES MREN 1ST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER 1985 Whole Body 2.36 X 10-'

1.84 X 10-'

6.36 X 10-2 8.83 X 10 Limiting Organ 1.25 X 100 3.72 X 10-'

1.04 X 10-1 1.21 X 100 1986 Whole Body 5.88 X 10-1 8.36 X 10-2 2.58 X 10-2 8.91 X 10-3 Limiting Organ 1.74 X 100 2.68 X 10-1.27 X 10-'

2.47 X 10-2 1987 Whole Body 7.45 X 10-3 6.54 X 10-2 1.42 X 10-2 2.27 X 10-2 Limiting Organ 1.44 X 102 1.69 X 10-6.44 X 10-2 2.55 X 10 1988 Whole Body 2.83 X 10-1 3.78 X 10-2 3.20 X 10-2 2.01 X 10 Limiting Organ 4.77 X 10-1 5.10 X 10-2 4.30 X 10-2 2.89 X 10 1989 Whole Body 2.55 X 10-2 2.35 X 10-2 1.49 X 10- 2 5.23 X 10-2 Limiting Organ 3.48 X 10- 2 2.62 X 10-2 1.74 X 10-2 6.78 X 102 1990 Whole Body 2.67 X 10-3 2.82 X 10-1.47 X 10-6.74 X 10-2 Limiting Organ 3.34 X 10-3 4.39 X 10-2 1.98 X 10-1 9.13 X 10-2 SCE RESPONSE TO "LIQUID EFFLUENTS AND DOSES," PART 2 Tabulated below are the curies of liquid effluent discharged in 1967 through 1971, and 1988 through 1990 as reported in the Semiannual Effluent Reports.

LIQUID EFFLUENTS Fission and Tritium Major Radionuclide Activation Ci Contributor to:

Product Ci Organ Whole Body Ci Ci JUN-DEC 67 3.17 X 10-NA NA NA Note 1

JAN-JUN 68 1.40 X 101 NA NA NA Note 1

JUL-DEC 68 1.50 X 100 NA NA NA Note 1

JAN-JUN 69 2.04 X 100 1.77 X 10+'

NA NA Note 2 JUL-DEC 69 5.96 X 100 1.76 X 10+3 NA NA Note 2 JAN-JUN 70 1.81 X 100 2.74 X 10+3 NA NA Note 2 JUL-DEC 70 2.00 X 100 2.04 X 10+3 NA NA Note 2

JAN-JUN 71 6.67 X 10-'

2.58 X 10' NA NA Note 2

JUL-DEC 71 7.96 X 100 1.99 X 10+

NA NA Note 3

1988 1ST QUARTER 3.67 X 10-4.73 X 10+'

9.54 X 10-7.97 X 10-2 1311 134cs 2ND QUARTER 1.16 X 10' 1.44 X 10+2 3.35 X 10-2 3.35 X 10-2 134cS 134cS 3RD QUARTER 6.91 X 10-2 1.61 X 10+2 2.64 X 10-2 2.64 X 10-2 134cs 13cs 4TH QUARTER 1.59 X 10-7.56 X 10+2 7.62 X 10-2 1.88 X 10 1311 134S LIQUID EFFLUENTS Fission and Tritium Major Radionuclide Activation Ci Contributor to:

Product Ci Organ Whole Body Ci Ci 1989 1ST QUARTER 1.43 X 10-1 6.05 X 10+1 3.21 X 10-2 3.21 X 10 134cs 34cs 2ND QUARTER 1.22 X 10-2.17 X 10+1 5.89 X 10-2 3.96 X 10 137Cs 134cs 3RD QUARTER 1.11 X 10-2.15 X 10+2 4.80 X 10-2 3.03 X 10 1

3 7 Cs 1 3 4 cs 4TH QUARTER 2.90 X 10-6.65 X.10+2 1.50 X 10-'

1.01 X 101 1

3 7 Cs 1

3 4 Cs 1990 1ST QUARTER 9.53 X 10-3 3.30 X 10+2 5.71 X 10-3 5.71 X 10-3 137cs 137 Cs 2ND QUARTER 1.98 X 10-8.49 X 10+2 2.70 X 10-2 6.06 X 10 1311 1

3 4 cs 3RD QUARTER 1.57 X 10-1 2.12 X 10+2 6.71 X 10-2 4.69 X 10-2 1

3 7 Cs

'34Cs 4TH QUARTER 3.59 X 10-2 3.26 X 10+1 1.74 X 10-2 1.11 X 10-2 L

3 7 Cs 1

3 4 cs NA -

Data not available Note 1:

Reported as total activity released. Breakdown by radionuclide is not available.

Note 2:

Reported as total beta - gamma activity released.

Note 3:

Sum of beta-gamma plus xenon isotopes.

NRC REQUEST Airborne Effluents and Doses

1.

Provide for all years in which calculations were performed, the doses reported in the Semi-annual Effluent Release Reports and/or the Radiation Environmental Monitoring Program Reports.

2.

Provide for the years 1967-1971 and 1988-1990, the total curies of effluents discharged. Data should be provided in terms of noble gases, "'I, and tritium. Information should also be provided, for the years in which doses were calculated, on the radionuclides which contribute the major portion of the maximum organ, gamma and beta air, skin and total body doses.

[Minor editorial changes have been made to this request for clarity.]

SCE RESPONSE TO "AIRBORNE EFFLUENTS AND DOSES," PART 1

1.

Calculations for doses at the site boundary due to airborne effluent releases were performed starting in 1985. The data from 1985 through 1990 is provided below. This data was extracted from the Semiannual Effluent Reports. The data contained in the Radiological Environmental Operating Reports (REORs) represents the total dose detected at various offsite locations. It is not possible to determine the source of the dose (i.e., liquid effluent, airborne effluent, or other).

Therefore, REOR data was not used in the table below.

AIRBORNE DOSES 1ST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER 1985 Tritium, lodines and Particulates - mrem 4.36 X 10-3.78 X 10-1.05 X 10-5.05 X 10 Noble gases gamma - mrad 3.32 X 10-1.73 X 10-'

1.11 X 10-1 6.56 X 10-2 beta - mrad 6.54 X 10-'

4.67 X 10-3.04 X 10-1 1.81 X 10 Direct radiation -

2.37 X 10-'

2.26 X 10-'

1.91 X 10-1 1.48 X 10-'

mrem 1986 Tritium, lodines and Particulates - mrem 2.09 X 10-4 1.08 X 10-'

1.15 X 10-6.31 X 10-s Noble gases gamma - mrad 3.59 X 10-4 0.00 3.21 X 10' 1.69 X 10-2 beta - mrad 1.08 X 10-3 0.00 7.36 X 10- 2 4.69 X 10-2 Direct radiation -

2.11 X 10-1.63 X 10-2.75 X 10-5.47 X 10 mrem 1987 Tritium, lodines and Particulates - mrem 1.18 X 10-1.07 X 10-1.29 X 10-1.78 X 10 Noble gases gamma - mrad 1.46 X 102 3.38 X 10-2 3.08 X 10~

3.48 X 10-2 beta - mrad 4.35 X 10-2 8.79 X 10-'

8.37 X 10-2 9.45'X 10-2 Direct radiation -

2.60 X 10-1 4.64 X 10-'

1.12 X 100 2.47 X 100 mrem AIRBORNE DOSES II 1ST 1 2ND 1

3RD 1

4TH

, QUARTER QUARTER J

QUARTER J

QUARTER

___1988 Tritium, lodines and Particulates - mrem 8.27 X 8.09 X 1.89 X 4.78 X Noble gases gamma - mrad 8.51 X 10' 0.00 4.99 X 10' 2.87 X 10 beta - mrad 2.48 X 101 0.00 1.25 X 101 7.78 X 101 Direct radiation -

1.23 X 100 1.05 X 100 4.00 X 100 5.30 X 0 mrem

_____________1989 Tritium, lodines and Particulates - mrem 6.28 X 9.95 X 8.43 X 3.27X Noble gases gamma - mrad 1.78 X 2.70 X 102 4.76 X 1.24 X 10' beta - mrad 1.68 X 10' 3.57 X 1.26 X 10' 3.39 X 10 Direct radiation -

2.94 X 100 2.65 X 100 1.09 X 10-1.02 X 10 mrem 1990 Tritium, lodines and Particulates - mrem 5.59 X 10-3.33 X 10-4.44 X 10-6.86 X 10 Noble gases gamma - mrad 3.33 X 1.06 X i0-1.03 X 10-0.00 beta - mrad 9.51 X 1T-2.90 X 10-3.07 X 10-0.00 Direct radiation -

1.53 X i0' 98 X 1T-1.62 X i0-1.12 X 10+1 nirem SCE RESPONSE TO "AIRBORNE EFFLUENTS AND DOSES", PART 2

2.

Tabulated below are the curies of airborne effluent discharged in 1967 through 1971, and 1988 through 1990 as reported in the Semiannual Effluent Reports.

Noble gas releases are dominated by a single isotope. That isotope is therefore the major contributor to the beta/gamma dose. Since beta provides the skin dose and gamma provides the total body dose, the isotope that is the major contributor to beta/gamma is also the major contributor to the skin and total body doses. Therefore headings for skin and total body have not been included.

AIRBORNE EFFLUENTS Noble lodine-131 Tritium Major Radionuclide Gases Ci Ci Contributor to:

Ci Organ Gamma-Beta Ci Air J

Ci JUN-4.02 X 100 NA NA NA NA DEC 67 Note 1 JAN-2.63 X 100 NA NA NA NA JUN 68 Note 1 JUL-2.02 X 100 NA NA NA NA DEC 68 Note 1 JAN-5.64 X 10+'

NA 3.21 X 10-NA NA JUN 69 Note 1 JUL-2.00 X 10+2 NA 2.15 X 100 NA NA DEC 69 Note 2 JAN-8.48 X 10+2 NA 6.21 X 100 NA NA JUN 70 Note 2 JUL-7.58 X 10+

NA 4.56 X 100 NA NA DEC 70 Note 2 JAN-1.36 X 10+3 NA 8.63 x 100 NA NA JUN 71 Note 2 1

JUL-4.64 X 10+

NA 4.50 X 10 NA NA DEC 71 X

10i 1988 1ST 9.60 X 10+

9.76 X 10- 4 3.62 X 100 9.76 X 10-'

9.36 X 10+2 QTR 1311 33Xe 2ND

< LLD 7.24 X 10-7 1.16 X 10+1 7.24 X 10-7 None QTR 1311 Shutdown AIRBORNE EFFLUENTS Noble lodine-131 Tritium Major Radionuclide Gases Ci Ci Contributor to:

Ci Organ Gamma-Beta Ci Air Ci 3RD 2.38 X 10+'

7.44 X 10-1.53 X 100 7.44 X 10-s 2.14 X 10+2 QTR

1.

1 133Xe 4TH 1.79 X 10+3 9.27 X 10-3 3.78 X 100 9.27 X 10- 3 1.70 X 10+

QTR 1311 133 Xe 1989 1ST 1.35 X 10-2 6.64 X 10-1.00 X 100 6.64 X 10' 1.32 X 10-2 QTR 131I 85Kr 2ND 4.55 X 10+1 4.11 X 10-s 5.11 X 10-1 4.11 X 10-s 3.49 X 10+1 QTR I311_133 Xe 3RD 2.73 X 10+2 1.81 X 10-4 1.32 X 10-1.81 X 10- 4 2.58 X 10+2 QTR 1311 133Xe 4TH 7.89 X 10+

1.20 X 10-3 3.21 X 10+

1.20 X 10-3 5.26 X 10+2 QTR 1311 133Xe 1990 1ST 3.05 X 10' 4.56 X 10-'

5.43 X 100 4.56 X 10-2.96 X 10' QTR 1311 1

3 3 Xe 2ND 7.06 X 10+2 7.36 X 10-5.77 X 10k' 7.36 X 10' 6.68 X 10+2 QTR 3

1313 Xe 3RD 7.93 X 10+'

6.02 X 10-3 2.12 X 10+1 6.02 X 10-3 7.80 X 10+2 QTR 1311 133Xe 4TH

< LLD 1.02 X 10-s 6.93 X 100 1.02 X 10-s None QTR 131I Shutdown NA -

Data not available LLD -

Lower limit of detection Note 1:

Reported as total activity released.

Breakdown by radionuclide is not available.

Note 2:

Reported as total beta - gamma activity released.

NRC REQUEST Radiological Environmental Monitoring Program Reports The results of the individual samples obtained to meet the requirements of Table 3.18.1 of the San Onofre Unit 1 Technical Specifications should be provided for the years in which only San Onofre Unit 1 was operating and for the years 1985, 1987, 1988, and 1990 when San Onofre Units 2 and 3 were also operating. The information should be summarized as in the example given in Attachment 1 to this Enclosure.

[Attachment 1 has not been included in our restatement.]

SCE RESPONSE TO "RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORTS" to this letter contains data for the specified years. To provide a manageable database, we have limited the data to the most significant nuclides analyzed. Enclosure 2 contains data for the nuclides which have reporting levels specified in Technical Specification Table 3.18.2, and for strontium, gross alpha and gross beta. Data for other nuclides is included only if the analysis found levels above the lower limit of detection (LLD).

COMB-ENC.JW1

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