ML20137N218

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Semiannual Radioactive Effluent Release Rept,Jan-June 1985
ML20137N218
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 06/30/1985
From:
PACIFIC GAS & ELECTRIC CO.
To:
Shared Package
ML20137N209 List:
References
NUDOCS 8509190045
Download: ML20137N218 (24)
v • d • e


Text

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i DIABLO CANYON POWER PLANT i

i SEMIANNUAL RADIOACTIVE

EFFLUENT RELEASE REPORT l -

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l JANUARY 1 - JUNE 30,1985 l c

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SENIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 TABLE OF CONTENTS PAGE INTRODUCTION......................................................... 2 PART OAC - GASEOUS AND LIQUID EFFLUENTS ............................. 3 Supplemental Information.......................................... 4 Table 1 - Gaseous Effluents - Summation of All Releases........... 9 t

Table 2 - Gaseous Effluents - Ground-Level Releases............... 10 Table 3 - Gasoous Effluents - Lower Limits of Detection........... 12 1

Table 4 - Liquid Effluents - Summation of All Releases............ 14 Table 5 - Liquid Effluents - Nuclides Released.................... 16

) Table 6 - Liquid Effluents - Lower Limits of Detection............ 18 PART TWO - SOLIO RADWASTE SHIPMENTS.................................. 20 0475S/0035K i

DIABLO CANYON POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 INTRODUCTION This Semiannual Radioactive Effluent Release Report summarizes the gaseous and liquid effluent releases made from Diablo Canyon Power Plant's Unit I for the first and second quarters of 1985. This report also includes a summary of solid radwaste shipments. This report contains the information required by Unit 1 Technical Specifications 6.9.1.8 and 6.9.1.9 and is generally presented in the format of Regulatory Guide 1.21, Appendix 8.

The Unit I reactor was critical for short periods in January and February. As the power ascension testing program continued, Unit 1 achieved 100% power in Ma rch. It was shut down during April and commercial operation was achieved on May 7. The Unit 2 reactor had not achieved initial criticality during the report period. Therefore, in accordance with Unit 2 Technical Specification 6.9.1.6, no Unit 2 information is included in this report.

There were no shipments of solid radioactive waste made during this report period. There were no changes made to the Process Control Program during this report period.

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PART ONE 1

GASEOUS AND LIQUID EFFLUENTS 4

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! i SUPPLEMENTAL INFORMATION '

! I I Regulatory Limits

A. Gaseous Effluents
1. Noble Gas Dose Rate Limit I j

The dose rate in unrestricted areas due to radioactive noble gases released in gaseous effluents is limited to less than or equal to 500 millirem per year to the total body and less than or equal to 3000 millirem per year to the skin. (Tech. Spec.

3.11.2.1.a.) e i

2. Particulate and Iodine Bose Rate Limit ,

I' The dose rate in unrestricted areas due to radiciodines and radioactive materials in particulate form, and radionuclides (other than noble gases) with half lives greater than 8 days in '

gaseous effluents is limited to less than or equal to 1500 millirem per year to any organ. (Tech. Spec. 3.11.2.1.b.)

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3. Noble Gas Dose Limit '

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i The air dose due to noble gases released in gaseous effluents, i from each reactor unit, from the site, is limited to the j following.

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! CALENDAR QUARTER CALENDAR YEAR 4

Gamma radiation 5 millirad 10 millirad i

j Beta radiation 10 millirad 20 millirad j (Tech. Spec. 3.11.2.2) i J

j 4. Particulate and Iodine Oose Limit

'l l The dose to an individual from radiotodines and radioactive i materials in particulate form and' radionuclides (other than  !

j noble gases) with half lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site, is i  !

I limited to less than or equal to 7.5 millirem to any organ in '

I any calendar quarter and less than or equal to 15 millires to  !

any organ during a calendar year. (Tech. Spec. 3.11.2.3)

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8. Liquid Effluents '

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1. Concentration The concentration of radioactive material released from the site is limited to the concentrations specified in 10 CFR Part l
20. Appendix 8. Table II, Column 2 for radionuclides other than  ;

dissolved or entrained noble gases. For dissolved or entrained i i noble gases, the concentration is limited to 2 x 10-4 j microcuries/ml total activity. (Tech. Spec. 3.11.1.1)

2. Dose 4

i The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site, is limited to the following:

CALENDAR QUARTER CALENOAR YEAR

! Total Body 1.5 millirem 3 millirem '

1 Any Organ 5 millirem 10 millirem

! (Tech. Spec. 3.11.1.2)

II Maximum Permissible Concentrations A. Gaseous Effluents Maximum permissible concentrations are not used in the methodology for determining allowable release rates for gaseous effluents at Diablo Canyon Power Plant.

8. Liquid Effluents j

l The concentrations listed in 10 CFR 20, Appendix 8. Table II, Column -

i 2 for radionuclides other than dissolved or entrained noble gases t are used for determining the allowable release rate at the point of

' discharge from the site for liquid effluents. For dissolved or entrained noble gases, the allowable release rate concentration at i l

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the point of discharge is limited to 2 x 10-4 microcuries per '

i milliliter total' activity for liquid effluents.

III Measurements and Approximations of Total Radioactivity A. Gaseous Effluents j 1. Fission and Activation Gases i

i The gaseous radioactivity released from the plant vent is 4

measured by a pair of off line monitors each using i

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0475S/0035K  !

Geiger-Mueller detector readings from these monitors. The_e monitor readings are correlated to isotopic concentration based on isotopic analysis of a grab sample using a germanium detector. A grab sample is obtained and analyzed at least weekly. The isotopic mixture is assumed to remain constant between grab sample analyses. Containment purges, gas decay tank releases and air ejector discharge are all routed through the plant vent for release. The gaseous radioactivity released from the steam generator blowdown tank vent is measured by analyzing grab samples with a germanium detector. The isotopic concentrations are assumed to remain constant between grab samples.

When the plant vent measurements as indicated by the process monitors ~are below the lower limit of detection, the results of the grab samples are used to quantify releases. In addition, the individual batch release data is used to quantify the radioactivity discharged from the gas decay tanks and containment.

Other potential pathways for releasing gaseous radioactivity are periodically monitored by collecting grab samples and analyzing these samples with a germanium detector system.

2. Iodines Radiolodines released from the plant vent are monitored by continuous sample collection on silver zeolite cartridges. The cartridges are changed at least weekly and analyzed with a germanium detector. The radioiodine releases are averaged over 4

the period of cartridge sample collection.

Other potential pathways for releasing radiotodines are i

periodically monitored by collecting samples using charcoal cartridges and analyzing these cartridges with a germanium detector.

3. Particulates Radioactive materials in particulate form released from the plant vent are monitored by continuous sample collection on particulate filters. The filters are changed at least weekly and analyzed with a germanium detector. The particulate radioactivity is averaged over the period of particulate filter sample collection. Each filter is analyzed for alpha emitters l

using an internal proportional counter. All of the plant vent particulate filters collected during a quarter are used for the i

composite analysis for strontium 89 and 90 which is counted on an internal proportional counter after chemical separation.

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Other potential pathways for releasing radioactive particulates are periodically monitored by collecting samples using particulate filters and analyzing these filters with a germanium detector.

B. Liquid Effluents

1. Batch Releases Each tank of Itquid radwaste is analyzed for principal gamma emitters using a germanium detector prior to release. The pre-release analysis includes dissolved and entrained gases.

Volume proportional monthly and quarterly composites are prepared from aliquots of each tank released. The monthly composite is analyzed for tritium using a liquid scintillation spectrometer, gross alpha radioactivity using an internal proportional counter and phosphorous-32 using an internal proportional counter following chemical separation. The quarterly composite is analyzed for iron-55 using a thin sodium iodide detector and for strontium-89 and 90 using an internal proportional detector following chemical separations.

2. Continuous releases for the continuous liquid releases of steam generator blowdown tank and turbine building sump oily water separator, daily grab samples are collected and volume proportioned for weekly, monthly and quarterly composites. The oily water separator weekly composite is analyzed for gross gamma and principal gamma emitters using a germanium detector. The steam generator blowdown tank weekly composite is analyzed for principal gamma emitters and iodine 131. The steam generator blowdown tank monthly composite is analyzed for tritium using a liquid scintillation spectrometer, for gross alpha using an internal proportional counter and for phosphorous-32 using an internal i proportional counter following chemical separation. The steam generator blowdown tank quarterly composite is analyzed for iron-55 using a thin sodium todide detector and for strontium-89 and 90 using an internal proportional counter j~ following chemical separations. The results for each of the composites is averaged over the period of the composite. In addition, one grab sample of the steam generator blowdown tank is analyzed monthly for dissolved and entrained gases using a germanium detector. The results of this analysis are assumed to remain constant over the period of one month.

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IV 8atch Releases A. Liquid

1. Number of batch releases.......................... 286
2. Total time period for batch releases.............. 1056 hours0.0122 days <br />0.293 hours <br />0.00175 weeks <br />4.01808e-4 months <br />
3. Maximum time period for a batch release............ 11.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />
4. Average time period for a batch release............ 3.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />
5. Minimum time period for a batch release............ 0.42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />
6. Average saltwater flow during batch releases....... 7.21 ES GPM
8. Gaseous
1. Number of batch releases........................... 92
2. Total time period for batch releases........,..... 410.33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />
3. Maximum time period for a batch release.........,.. 23.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />
4. Average time period for a batch release............ 4.46 hours5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br />
5. Minimum time period for a batch release............ 0.08 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> V Abnormal Releases On March 23, 1985, a planned gaseous release occurred via the steam generator pressure relief valves. A total of 2.54 E-8 curies of Na-24 was released. This occurred in conjunction with the 100% load rejection test which closely followed the Na-24 tracer secondary system performance study.

On May 8, 1985, an unplanned release from a gas decay tank occurred when a pressure relief disc on a boric acid evaporator ruptured. The release occurred inside the auxiliary building and was monitored by the plant vent monitors. A total of 7.99 E-4 curies of Kr-88, 7.83 E-3 curies of Xe-133,

' 1.01 E-2 curies of Xe-135, and 3.29 E-3 curies of Ar-41 were released during this event.

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DIABLO CANYON POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 TABLE 1 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Units 1st 2nd Est. Total Quarter Quarter Error,%

A. Fission & activation gases

1. Total release Ci 3.95 E-1 6.21 E+1 5.0 El
2. Average release rate for period pct /sec 5.08 E-2 7.90 E+0
3. Percent of technical specification limit 2  % 0.90 E-4 2.66 E-2 B. Iodines
1. Total iodine-131 1.54 E-5 C1 MDAI 2.3 El
2. Average release rate for period pCi/ set MDA 1.96 E-6
3. Percent of-technical specification limit 2  % 0.0 1.75 E-2 C. Particulates
1. Particulates with half-lives > 8 days C1 MDA 5.15 E-10 2.3 El
2. Average release rate for period pCi/sec MDA 6.55 E-11
3. Percent of technical specification limit 2  % 0.0 5.15 E-8
4. Gross alpha radioactivity C1 MDA MDA D. Tritium
1. Total release C1 9.43 E-1 1.61 E-1 1.2 El
2. Average release rate for period pC1/sec 1.21 E-1 2.05 E-2
3. Percent of technical specification limit 2 X 3.30 E-4 5.63 E-5 I

MDA =orthe "a posteriori" minimum detectable activity (microcuries per uni; ness volume) 2 Technical Specification 3.11.2.1 Limit 0475S/0035K DIABLO CANYON POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 TABLE 2 GASEQUS EFFLUENTS - GROUND-LEVEL RELEASES IST QUARTER' 2ND QUARTER CONTINUOUS BATCH CONTINUOUS BATCH Nuclides Released Units MODE MODE MODE MODE

1. Fission gases krypton-85 Ci MDA MDA MDA MDA krypton-85m Ci MDA 1.76 E-4 MDA 1.37 E-2 krypton-87 C) MDA MDA MDA MDA krypton-88 Ci MDA MDA MDA MDA xenon-131m C1 MDA MDA MDA 2.70 E-2 xenon-133 C1 MDA 2.76 E-1 3.08 E+1 2.93 E+1 xenon-133m C1 MDA MDA MDA 3.41 E-1 xenon-135 Ci MDA 8.88 E-3 5.59 E-2 3.06 E-1 xenon-135m Ci MDA MDA MDA MDA xenon-138 Ci MDA MDA MDA MDA argon-41 C1 MDA 1.10 E-1 5.26 E-1 7.30 E-1 TOTAL FOR PERIOD C) 0 3.95 E-1 3.14 E+1 3.07 E+1 v
2. Iodines iodine-131 Ci MDA 1.54 E-5 iodine-133 Ci MDA MDA iodine-135 Ci MDA MDA TOTAL FOR PERIOD Ci 0.0 1.54 E-5 04755/0035K --. . _ .

DIABLO CANYON POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 TABLE 2 (Continued)

GASEOUS EFFLUENTS - GROUNO-LEVEL RELEASES CONTINUGUS MODE Nuclides Released Units ist Quarter 2nd Quarter

3. Particulates cerium-141 Ci MDA MDA cerium-144 C1 MDA MDA cesium-134 Ci MDA MDA cesium-131 C1 MDA MDA cobalt-58 C1 MDA MDA cobalt-60 C1 MDA MDA tron-59 C) MDA MDA manganese-54 Ci MDA MDA molybdenum-99I C1 MDA MDA strontium-89 C1 MDA 5.15 E-10 strontium-901 C) MDA MDA zinc-65 C1 MDA MDA TOTAL FOR PERIOD C1 0 5.15 E-10 I Includes daughters i

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DIABLO CANYON POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 TABLE 3 GASE0US EFFLUENTS - LOWER LIMITS OF DETECTION Nuclide Units Continuous Mode Batch Mode

1. Fission gases Containment Gas Decay Purge Tank krypton-85m pC1/mi 6.90E-9 6.90E-9 9.58E-6 krypton-87 pCi/ml 1.88E-8 1.88E-8 1.36E-5 krypton-88 pC1/ml 2.26E-8 2.26E-8 3.23E-5 xenon-131m pC1/ml 1.87E-7 1.87E-7 3.39E-4 xenon-133 pC1/ml 1.97E-8 1.97E-8 6.97E-5 xenon-133m pC1/ml 4.61E-8 4.61E-8 9.35E-5 xenon-135 pC1/ml 4.15E-9 4.15E-9 6.37E-5

, xenon-135m pC1/ml 4.13E-8 4.13E-8 2.67E-5 xenon-138 pC1/ml 1.09E-7 1.09E-7 3.30E-5 argon-41 pC1/ml 3.34E-8 3.34E-8 2.84E-5

2. Tritium hydrogen-3 pC1/ml 3.52E-10 4.12E-10
3. Iodines iodine-131 pC)/ml 2.83E-13 todine-133 pC1/ml 4.77E-13 iodine-135 pC1/ml 6.66E-12 i

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DIABLO CANYON POWER PLANT SENIANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT 1985 TABLE 3 (Continued)

GASEOUS EFFLUENTS - LOWER LIMITS OF' DETECTION Nuclide Units Continuous Mode

4. Particulates cerium-141 pCi/ml 2.82 E-13 cerium-144 pC1/ml 1.51 E-12 cesium-134 pC1/ml 3.45 E-13 1

cesium-137 pCi/ml 2.72 E-13 i

! cobalt-58 pC1/ml 3.03 E-13 I

cobalt-60 pC1/ml 4.91 E-13 tron-59 pC1/ml 7.29 E-13 manganese-54 pCi/ml 4.37 E-13 j molybdenum-99I pCi/ml 2.36 E-12 i '

strontium-89 pC1/ml 2.98 E-15 strontium-901 pC1/ml 1.57 E-15 zinc-65 pC1/ml 8.12 E-13 3

gross alpha pC1/mi 7.23E-15 I

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DIABLO CANYON NUCLEAR PDWER PLANT SEMIANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT 1985 TABLE 4 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES IST 2ND Est Total Units Quarter Quarter Error, %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 3.48 E-1 1.91 E0 2.1 El
2. Average diluted concentration during period pC1/ml 4.08 E-9 2.18 E-8
3. Percent of applicable limitl  % 6.30 E-3 6.42 E-2 B. Tritium
1. Total release C1 2.29 E+1 5.11 E+1 7.0 E0
2. Average diluted concentration during peried pC1/ml 2.68 E-7 5.83 E-7
3. Percent of applicable limitl X 8.93 E-3 1.94 E-2 C. Dissolved and entrained gases
1. Total release C1 1.11 E-4 2.87 E-3 2.1 El
2. Average diluted concentration during period pCi/mi 1.30 E-12 3.27 E-11
3. Percent of applicable limitl  % 6.50 E-7 1.64 E-5 D. Gross alpha radioactivity
1. Total release Ci MDA MDA 6.0 El l Technical Specification 3.11.1.1 Limit 0475S/0035K _

DIABLO CANYON POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 TABLE 4 (Continued)

LIQUID EFFLUENTS - SUMMATION Of ALL RELEASES ist 2nd Est Total Units Quarter Quarter Error, %

' fpf$ ko E$$u$1o$)' ' liters 6.72 E+6 6.31 E+6 5.0 E0 F. Volume of circulating saltwater used during release liters 8.54 E+10 8.77 E+10 6.6 EO 5

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DIABLO CANYON PDWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 TABLE 5 LIQUID EFFLUENTS IST QUARTER 2ND QUARTER CONTINU0US BATCH CONTINUOUS BATCH Nuclides Released Units MODE MDDE MODE MODE antimony-124 C1 MDA 1.50 E-5 MDA 2.85 E-4 bromine-82 Ci MDA 1.09 E-5 MDA MDA cerium-141 Ci MDA MDA MDA MDA cerium-144 Ci MDA MDA MDA MDA cesium-134 Ci MDA MDA MDA 4.02 E-5 cesium-136 Ci MDA MDA MDA 2.38 E-5 cesium-137 Ci MDA MDA MDA 6.19 E-4 chromium-51 Ci MDA 3.90 E-3 MDA 1.70 E-2 cobalt-57 Ci MDA 1.38 E-4 MDA 1.78 E-3 cobalt-58 Ci MDA 2.72 E-1 MDA 1.56 E+0 cobalt-60 Ci MDA 1.75 E-2 MDA 2.38 E-1 iron-55 Ci MDA MDA MDA 3.64 E-3 iron-59 Ci MDA 2.00 E-2 MDA 5.48 E-3 lanthanum-140 Ci MDA 1.38 E-4 MDA 2.36 E-2 manganese-54 C1 MDA 2.20 E-2 MDA 4.04 E-2 molybdenum-991 Ci MDA 1.26 E-3 MDA 2.77 E-3 phosphorous-32 Ci MDA 5.71 E-3 MDA 5.64 E-3 sodium-24 Ci MDA 4.23 E-3 MDA 2.45 E-3 I Includes daughters 04755/0035K .

DIABLO CANYON POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 TABLE 5 (CONTINUED)

LIQUID EFFLUENTS IST QUARTER 2ND QUARTER CONTINUOUS BATCH CONTINUOUS BATCH Nuclides Released Units MODE MODE MODE MODE strontium-89 Ci MDA MDA MDA 3.70 E-4 strontium-901 Ci MDA MDA MDA MDA tungsten-187 Ci MDA 6.09 E-4 MDA 1.18 E-4 zircenium-951 C1 MDA 1.11 E-5 MDA 5.86 E-4 zint-65 C1 MDA MDA MDA MDA iodine-131 C1 MDA 7.99 E-5 MDA 8.29 E-3 iodine-133 C1 MDA 3.89 E-4 MDA 2.30 E-3 iodine-135 Ci MDA 1.14 E-4 MDA 4.88 E-5 TOTAL FOR PERIOD C1 0 3.48 E-1 0 1.91 E+0 xenon-133 C1 MDA 4.10 E-5 MDA 2.78 E-3 xenon-135 Ci MDA 7.01 E-5 MDA 8.61 E-5 I Includes daughters 0475S/0035K . . - - , - -

DIABLO CANYON POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 TA8LE 6 LIQUID EFFLUENTS - LOWER LIMITS OF DETECTION Nuclide Units LLD antimony-124 pCi/ml 2.06 E-8 bromine-82 pCi/ml 3.80 E-8 cerium-141 pCi/ml 3.49 E-8 cerium-144 pCi/ml 1.88 E-7 cesium-134 pCi/ml 2.92 E-8 cesium-136 pC1/mi 5.06 E-8 cesium-137 pC1/mi 4.90 E-8 chromium-51 pCi/ml 2.50 E-7 cobalt-57 pCi/ml 2.17 E-8 ,

4 cobalt-58 pC1/ml 3.82 E-8 cobalt-60 pC1/mi 4.36 E-8 iron-55 pCi/ml 4.80 E-7 tron-59 pCi/ml 6.45 E-8 lanthanum-140 pC1/ml 5.68 E-8 manganese-54 pCi/mi 3.91 E-8 molybdenum-99I pCi/ml 2.79 E-7 phosphorous-32 pC1/ml 3.31 E-7 sodium-24 pCi/ml 4.72 E-8 strontium-89 pCi/ml 4.07 E-8 strontium-901 pCi/ml 4.00 E-8 I

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DIABLO CANYON POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 TABLE 6 (CONTINUED)

LIQUID EFFLUENTS - LOWER LIMITS OF DETECTION Nuclide Units LLD tungsten-187 pC1/ml 8.96 E-8 zirconium-951 pCi/ml 6.51 E-8 zinc-65 pCi/ml 7.22 E-8 gross alpha pCi/mi 9.00 E-8 iodine-131 pC1/ml 2.55 E-8 d

iodine-133 pC1/ml 2.12 E-8 iodine-135 pC1/mi 1.63 E-7 xenon-133 pC1/ml 2.08 E-7 xenon-135 pCi/ml 2.16 E-8 I Includes daughters

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PART TWO SOLID RADWASTE SHIPMENTS 0475S/0035K DIABLO CANYON POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A.

Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

1. Type of Waste Units Est. Total 6-Month Period Error, %
a. Spent Resins m3 0.00E+0 yfg C) 0.00E+0
b. Dry Compressible m3 0.00E+0 C1 0.00E+0 N/A Waste, Equip. Etc. contaminated
c. Irradiated m3 0.00E+0 Control N/A ngt C1 0.00E+0
d. Absorbed liquids, m3 0.00E+0 Sand Build ng Ci 0.00E+0 g/A Rubble Waste , Bio:ogical
2. Estimate of Major Nuclide Composition (by type of waste) a.

NOT APPLICABLE  % 0.0E+0 b.

NOT APPLICABLE  % 0.0E+0 c.

NOT APPLICABLE  % 0.00E+0 d.

NOT APPLICABLE  % 0.00E+0 l

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DIABLO CANYON POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. 1 W Shipped Offsite for Burial or Disposal (Not irradiated fuel)

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination NONE N/A N/A B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination NONE N/A N/A 0475S/0035K - __ _- _ _ - . -

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