Text

Semiannual Effluent Rept for Jul-Dec 1984
	ML20099F928
Person / Time
Site:	Diablo Canyon
Issue date:	12/31/1984
From:	Shiffer J; PACIFIC GAS & ELECTRIC CO.
To:	Martin J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
	CON-#285-937 DCL-85-090, DCL-85-90, OL, NUDOCS 8503140407
	Download: ML20099F928 (37)
	v • d • e

. . _ - - .- . _ _ _ - - _ _ _ _ _ - _ - _ _ - _ _ - _ _ _

! DIABLO CANYON NUCLEAR POWER PLANT SEMIANNUAL EFFLUENT REPORT JULY 1 - DECEMBER 31,1984 p Ge>E

\

0 275 PDR TEI

DIABLO CANYON NUCLEAR POWER PLAN sEMIAfMJAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1984 TABLE OF CO EENTS 1

PAGE INTRODUCTION......................................................... 2 j PART ONE - GASE0US AND LIQUID EFFLUENTS ............................. 3 t

S u ppl emen ta l I n fo rma t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Table 1 - Gaseous Effluents - Sunnation of All Releases. . . . . . . .... 9

Table 2 - Gaseous Effluents - Ground-Level Releases. . . . . . . . . . . . . . . 10 Table 3 - Gaseous Effluents - Lower Limits of Detection........... 12 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 - SOLID RADWASTE SHIPMENTS.................................. 20 PART THREE - RADIATION DOSE DUE TO GASE0US AND LIQUID EFFLUENTS...... 23 Table 7 - Radiation Dose Due to the Release of Radioactive Liquid Effluents................ 25 Table 8 - Radiation Dose due to the Release of Radioactive Gaseous Effluents............... 26 Table 9 - Percent of Technical Specification Limits for Radioactive Liquid Effluents....................... 30 Table 10 - Percent of Technical Specification' Limits for Radioactive Gaseous Effluents...................... 31 PART FOUR - METEOROLOGICAL DATA...................................... 32 i

DC0414 'VI i

DIABLO CANYON NUCLEAR POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1984 INTRODUCTION This Semiannual Radioactive Effluent Release Report summarizes the gaseous and liquid effluent releases made from Diablo Canyon Power Plant's Unit 1 for the third and fourth quarters of 1984.

This report also includes a summary of solid radwaste shipments, the annual sumary of the Meteorological data for the site during 1984, and an assessment of radiation dose due to the release of liquid and gaseous effluents during 1984. This report contains the information required by Technical Specifications 6.9.1.8 and 6.9.1.9 and is generally presented in the format of Regulatory Guide 1.21, Appendix B.

The Unit I reactor was critical for short periods in July and Ieugust and then shut down until the power ascension testing program started in November. Unit I had progressed to the 50%

power plateau by the end of December.

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.

DC0414 2

PART ONE GASEOUsANDLIQUIDEFFLUENT5 I

l DC0414 VI I

SUPPLEENTAL INFORMATION I Regulatory Limits A. Gaseous Effluents

1. Noble Gas Dose Rate Limit 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.)

2. Particulate and Iodine Dose Rate Limit 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.)

3. Noble Gas Dose Limit The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site, is limited to the following.

CALENDAR QUARTER CALENDAR YEAR Gamma radiation 5 millirad 10 millirad Beta radiation 10 millirad 20 millirad (Tech. Spec. 3.11.2.2)

4. Particulate and Iodine Dose Limit The dose tc an individual from radioiodines and radioactive materials in particulate form and radionuclides (other than noble gases) with half lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site, is limited to less than or equal to 7.5 millirem to any organ in any calendar quarter and less than or equal to 15 millirem to any organ during a calendar year. (Tech. Spec. 3.11.2.3)

DC0414 VI ,

B. Liquid Effluents

1. Concentration The concentration of radioactive material released from the site is limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration is limited to 2 x 10 4 microcuries/ml total activity. (Tech. Spec. 3.11.1.1)

2. Dose 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 CALENDAR YEAR Total Body 1.5 millirem 3 millirem 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.

B. Liquid Effluents The concentrations listed in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases 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-the point of discharge is limited to 2 x 10 4 microcuries per milliliter total activity for liquid effluents.

III Measurements and Approximations of Total Radioactivity A. Gaseous Effluents

1. Fission and Activation Gases The gaseous radioactivity released from the plant vent is measured by a pair of off line monitors each using DC0414 VI 1

l 1

l Geiger-Mueller detector readings from these monitors. These I monitor readings are correlated to isotopic concentration based l on isotopic analysis of a grab sample using a germanium detector. '

A grab sample is obtained and analyzed at least weekly. The i 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 are below the lower limit of detection, the individual batch release data is used to characterize 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 Radioiodines 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 the period of cartridge sample collection.

Other potential pathways for releasing radioiodines are 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 using an internal proportional counter. All of the plant vent particulate filters collected during a quarter are used for the composite analysis for strontium 89 and 90 which is counted on an internal proportional counter after chemical separation.

l DC0414 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 i Each tank of liquid 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 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 proportional counter following chemical separation. The steam generator blowdown tank quarterly composite is analyzed for iron-55 using a thin sodium iodide detector and for strontium-89 and 90 using an internal proportional counter 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 entre.ined gases using a germanium detector. The results of this analysis are assumed to remain constant over the period of one month.

i DC0414 VI !

l ._

IV Batch Releases A. Liquid

1. Numbe r of batch rel eases . . . . . . . . . . . . . . . . . . . . . . . . . . 200

2. Total time period for batch releases. . . . . . . . . . . . . . 875.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

3. Maximum time period for a batch release. . . . . . . . . . . . 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

4. Average time period for a batch release. . . . . . . . . . . . 4.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

5. Minimum time period for a batch release............ 0.38 hours4.398148e-4 days 0.0106 hours 6.283069e-5 weeks 1.4459e-5 months

6. Average saltwater flow during batch releases....... 7.60 E5 GPM B. Gaseous

1. Numbe r of batch releases . . . . . . . . . . . . . . . . . . . . . . . . . . . 34

2. Total time period for batch releases. . . . . . . . . . . . . . 135.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

3. Maximum time period for a batch release. . . . . . . . . . . . 24.0 hours0 days 0 hours 0 weeks 0 months

4. Average time period for a batch release. . . . . . . . . . . . 3.99 hours0.00115 days 0.0275 hours 1.636905e-4 weeks 3.76695e-5 months

5. Minimum time period for a batch release............ 0.017 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months V Abnormal Releases There were no abnormal releases during this reporting period.

DC0414 VI ,

1 l

l l

DIABLO CANYON NUCLEAR POWER PLANT sEMIAf6UALRADI0ACTIVEEFFLUENTRELEA5EREPORT1984 TABLE 1 GASE005 EFFLUENTS - 50Ff% TION OF ALL ELEAsEs Unit 3rd 4th Est. Total Quarter Quarter Error,%

A. Fission & activation gases

1. Total release Ci LLD 5.86 E-2 5.0 El

2. Averege release rate for period pCi/sec LLD 7.37 E-3

3. Percent of technical specification limit % 0.0 5.05 E-5 B. Iodines

1. Total iodine-131 Ci LLD LLD 2.3 El

2. Average release rate for period pCi/sec LLD LLD

3. Percent of technical specification limit % 0.0 0.0 C. Particulates

1. Particulates with half-lives > 8 days Ci LLD 1.20 E-5 2.3 El

2. Average release rate for period pCi/sec LLD 1.51 E-6

3. Percent of technical specification limit % 0.0 8.97 E-4

4. Gross alpha radioactivity Ci LLD LLD D. Tritium

1. Total release C1 7.35 E-5 1.30 E-2 1.2 El

2. Average release rate for period pCi/sec 9.24 E-6 1.64 E-3

3. Percent of technical specification limit % 1.65 E-8 2.93 E-6 1

)

DC0414 VI ._ __ _ - _ _ _ _ . . - -

DIABID CANYON NUCLEAR POER PIANT SEMIANNUAL RADIOACTIVE EFFIUENT RELENSE REPORT 1984 TABLE 2 GASEOUS EFFIDENTS - GROUND-IJNEL RELEASES 3RD QUAIEER 4'IH QUARTER CONTINUOUS BNICH CCNTINUCUS BNICH Nuclides Released Unit KDE MJDE MODE MODE

1. Fission gases krypton-85 Ci IID UD LID IID krypton-85m Ci UD UD LID LID krypton-87 Ci LID LID LID LID krypton-88 Ci LID LLD UD LID xenon-133 Ci UD LID UD UD xenon-133n ci LLD LID LID LID xen a "5 Ci LID LID LID IID xenon-135m Ci LID LID LID LID xenon-138 Ci LID IID LID UD argon-41 Ci LID IID LID 5.86 E-2

'IUTAL EDR PERIOD Ci 0 0 0 5.86 E-2

2. Iodines iodine-131 Ci HD UD iodine-133 Ci UD UD iodine-135- Ci LID LID

'IUIE EDR PERIOD Ci 0 0 DC0414 VI DIABLO CANYON NUCLEAR POWER PLANT sEMIAlWUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1984 TABLE 2 (CONTINUED) l GASEOUS EFFLUENTS - GROUf0-LEVEL RELEA5Es l 1

l CONTINUOU5 MODE l

i Nuclides Released Unit 3rd Quarter 4th Quarter i

3. Particulates 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 ,

manganese-54 Ci LLD LLD !

molybdenum-991 Ci LLD LLD strontium-89 Ci LLD 7.86 E-6 strontium-901 Ci LLD 4.13 E-6 i

zinc-65 Ci LLD LLD TOTAL FOR PERIOD Ci 0 1.20 E-5 NOTES:

1 Includes Daughters DCD414 VI I

2 DIABLO CANYON NUCLEAR POWER PLANT I

SEMIAfNUAL RADI0 ACTIVE EFFLLENT RELEASE REPORT 1984 TABLE 3

, GASEOUS EFFLUENTS - LOER LIMITS OF DETECTION

+

l i

l Nuclide Unit Continuous Mode Batch Mode i i

Containment Gas Decay. l

1. Fission gases Purge Tank l

krypton-85 pCi/ml 2.29E-6 2.37E-6 3.37E-6!

krypton-85m pCi/ml 5.81E-9 8.08E-9 7.64E-6 krypton-87 pCi/ml 1.26E-8 3.20E-7 1.21E-5 l

krypton-88 pCi/ml 1.68E-8 4.59E-8 2.00E-5 xenon-133 pCi/ml 1.60E-8 2.21E-8 1.44E-5 xenon-133m pCi/ml 2.83E-8 4.54E-8 4.92E-5 xenon-135 I pCi/ml 4.09E-9 5.66E-9 3.28E-6 l

j xenon-135m pCi/ml 4.45E-8 7.99E-7 1.76E-5 xenon-138 pCi/ml 1.08E-7 2.79E-6 3.61E-5 argon-41 pCi/ml 1.62E-8 3.18E-8 1.54E-5

2. Tritium l hydrogen-3 pCi/ml 3.52E-10 4.12E-10

{ 3. Iodines i

iodine-131 pCi/ml 5.06E-13 iodine-133 pCi/ml 6.74E-13

iodine-135 pCi/ml 5.37E-12 e

I i

DC0414 VI i

l DIABLO CANYON NUCLEAR POWER PLANT

$EMIAlWUALRADIOACTIVEEFFLUEMIRELEAsEREPORT1984 TABLE 3 (CONTINUED)

GASE005 EFFLUENTS-LOWERLIMITs0FDETECTION Nuclide Unit Continuous Mode

4. Particulates cerium-141 pCi/ml 4.43 E-13 cerium-144 pCi/ml 4.32 E-13 cesium-134 pC1/ml 5.60 E-13 cesium-137 pCi/ml 4.66 E-13 cobalt-58 pCi/ml 4.29 E-13 cobalt-60 pCi/ml 7.56 E-13 iron-59 pC1/ml 9.46 E-13 manganese-54 pCi/ml 4.27 E-13 molybdenum-991 pCi/ml 3.39 E-12 strontium-89 pCi/ml 2.98 E-15 strontium-901 pCi/ml 1.57 E-15 zinc-65 pCi/ml 1.24 E-12 i

t gross alpha pCi/ml 7.23E-15 Notes:

I Includes daughters DC0414- VI DIABLO CANYON NUCLEAR POWER PLAN sEMIAlWUALRADI0ACTIVEEFFLUENTRELEAsEREPORT1984 TABLE 4 4

LIQUIDEFFLUEMS-stMMTIONOFALLRELEASEs 3rd 4th Est Total Unit Quarter Quarter Error, %

A. Fission and activation products

1. Total release (not including

-tritium, gases, alpha) Ci 3.51 E-3 7.61 E-3 2.1 El

2. Average diluted concentration during period pCi/mi 9.49 E-11 6.68-11

3. Percent of applicable limit % 1.25 E-4 5.06 E-4 B. Tritium

1. Total release Ci 1.59 E-1 8.43 E-1 7.0 E0

2. Average diluted concentration during period pCi/ml 4.29 E-9 7.40 E-9

3. Percent of applicable limit % 1.43 E-4 2.47 E-4 C. Dissolved and entrained gases

1. Total release Ci LLD 4.78 E-6 2.1 El

2. Average diluted concentration during period pCi/ml LLD 4.19 E-14

3. Percent of applicable limit % 0 2.10 E-8 D. Gross alpha radioactivity

1. Total release Ci LLD LLD 6.0 El DC0414 VI .

DIABLO CANYON NUCLEAR POWER PLANT SEMIA N AL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1984

TABLE 4 (CONTINUED)

LIQUID EFFLUENTS - SultlATION OF ALL RELEASES 3rd 4th Est Total Unit Quarter Quarter Error, %

E. Volume of waste released (prior to dilution) liters 3.04 E6 3.90 E6 5.0 E0 F. Volume of circulating saltwater used during release liters 3.70 E10 1.14 E11 6.6 EO l

i I

b e

i DC0414 VI _

DIABLO CANYON NUCLEAR POWER PLANT sEMIAM40AL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1984 TABLE 5 LIQUIDEFFLUENTs 3RD QUARTER 4TH QUARTER CONTINU0US BATCH CONTINU0US BATCH Nuclides Released Unit MODE MODE MODE MODE antimony-124 Ci LLD 2.33 E-5 LLD LLD cerium-141 Ci LLD LLD LLD LLD 4

cerium-144 Ci LLD LLD LLD LLD cesium-134 Ci LLD LLD LLD LLD cesium-137 Ci LLD LLD LLD 1.01 E-7 chromium-51 Ci LLD 1.47 E-4 LLD 2.53 E-4 i

cobalt-58 Ci LLD 2.65 E-3 LLD 8.80 E-4 cobalt-60 Ci LLD 4.76 E-4 LLD 2.69 E-4 iron-55 Ci LLD LLD LLD LLD iron-59 Ci LLD 2.43 E-5 LLD 1.26 E-5

! manganese-54 Ci LLD 1.32 E-4 LLD 9.24 E-5 1

molybdenum-99 Ci LLD LLD LLD 9.27 E-4 l phosphorous-32 Ci LLD LLD LLD 4.34 E-3 sodium-24 Ci LLD LLD LLD 3.42 E-4 strontium-89 Ci LLD LLD LLD LLD strontium-90 1 Ci LLD LLD LLD LLD tungsten-187 Ci LLD LLD LLD 3.25 E-4 1

zirconium-95 Ci LLD 5.43 E-5 LLD 4.12 E-5 zinc-65 Ci LLD LLD LLD 6.17 E-6 TOTAL FOR PERIOD Ci 0 3.51 E-3 0 7.49 E-3 NOTES:

1 Includes daughters

-DC0414 VI .. -. .. - . . - . .-

DIABLO CANYON NUCLEAR POWER PLANT sEMIAMUALRADI0ACTIVEEFFLUENTRELEASEREPORT1984 TABLE 5 (CONTINUBD)

LIQUIDEFFLUENTs 3RD QUARTER 4TH QUARTER CONTINUOUS BATCH CONTINUOUS BATCH Nuclides Released Unit MODE MODE M0DE MODE iodine-131 Ci LLD LLD LLD 3.15 E-5 iodine-133 Ci LLD LLD LLD 8.64 E-5 i

xenon-133 Ci LLD LLD LLD LLD xenon-135 Ci LLD LLD LLD 4.78 E-6 DC0414 VI i

'DIABLO CANYON NUCLEAR POWER PLANT 5EMIAfhUALRADI0ACTIVEEFFLUENTRELEAsEREPORT1984

TABLE 6 LIQUIDEFFLUENTS-LOWERLIMITs0FDETECTION Nuclide Unit Continuous Mode Batch Mode antimony-124 pCi/ml N/A2 3.80 E-8 cerium-141 pCi/ml ,

2.31 E-8 3.46 E-8 cerium-144 pCi/ml 9.84 E-8 1.45 E-7 cesium-134 pCi/ml 1.82 E-8 2.82 E-8 cesium-137 pCi/ml 1.26 E-8 2.46 E-8

) chromium-51 pCi/ml 9.71 E-8 1.88 E-7 cobalt-58 pCi/ml 1.80 E-8 2.81 E-8 i cobalt-60 pCi/ml 7.14 E-8 3.31 E-8 fron-55 pCi/ml 6.00 E-7 2.60 E-7 fron-59 pCi/ml 3.34 E-8 4.69 E-8 manganese-54 pCi/ml 1.50 E-8 2.64 E-8 molybdenum-991 pC1/ml 1.11 E-7 1.70 E-7 phosphorous-32 pCi/ml 1.84 E-7 4.16 E-7

sodium-24 pCi/ml 3.15 E-8 4.56 E-8

! strontium-89 pCi/ml 2.82 E-8 7.13 E-9 strontium-901 pC1/ml 8.69 E-9 1,63 E-8 tungsten-187 .pC1/ml 6.14 E-8 1.94 E-7 zirconium-951 pCi/ml 2.77 E 3.86 E-8 zinc-65 pCi/ml 3.60 E 5.20 E-8 gross alpha pCi/ml 8.03 E-8 7.36 E-8 NCTES:

I Ir.cludes Daughters 2

This is a nuclide not. routinely checked for LLD DC0414 VI _ _ _ . _

DIABLO CANYON NUCLEAR POWER PLANT 5EMIAMUAL RADI0AC'IVE EFFLUENT RELEASE REPORT 1984 TABLE 6 (CONTINUED)

LIQUID EFFLUENTS - LOWER LIMITS OF DETECTION Nuclide Unit Continuous Mode Batch Mode iodine-131 pCi/ml 1.17 E-8 2.76 E-8 iodine-133 pCi/ml 1.94 E-8 6.44 E-8 xenon-133 pCi/ml 6,?8 E-8 5.55'E-8 xenon-135 pCi/ml 1.45 E-8 1.63 E-8 i

i

'1 l

l

- DC0414 VI - _ _

I

I l

l PART TWO SOLIDRADWAsTESHIPfENTs DC0414 VI DIABLO CANYON NUCLEAR POWER PLANT sEMIAffiUAL RADI0 ACTIVE EFFLUENT RELEA5E REPORT 1984 SOLID WASTE AND IRRADIATED FUEL sHIPENT A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

Est. Total

1. Type of Waste Unit 6-Month Period Error, %

a. Spent Resins m3 0.00E+0 N/A Ci 0.00E+0

b. Dry Compressible m3 0.00E+0 N/A Waste, Contaminated Ci 0.00E+0

Equip. Etc.

1 Irradiated m3

c. 0.00E+0 N/A Components, Control Ci 0.00E+0 Rods, Etc.

d. Absorbed liquids, m3 0.00E+0 N/A Sand, Building C1 0.00E+0 Rubble, Biological Waste

2. Estimate of Major Nuclide Composition (by type of waste) a.

NOT APPLICABLE % 0.00+0 b.

NOT APPLICABLE % 0.00+0 c.

NOT APPLICABLE % 0.00E+0 d.

NOT APPLICABLE % 0.00E+0

! DC0414 VI ,

DIABLO CANYON NUCLEAR POWER PLANT 5EMIAMUALRADI0ACTIVEEFFLUENTRELEASEREPORT1984 50LIDWAsTEANDIRRADIATEDFUELsHIPMENT A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

(Continued)

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 i

i l

't DC0414 VI _-. -. - - -

1 PART THREE RADIATION D0sE DUE TO GASE0US AND LIQUID EFFLUENTS DC0414 VI RADIATION DOSES I. Radiation doses due to radioactive liquid effluents

! The radiation dose contributions due to releases of radioactive liquid effluents to the total body and each individual organ for the maximum

, exposed adult have been calculated in accordance with the methodology in the Offsite Dose Calculation Procedure. These dose contributions are listed in Table 7.

! II. Radiation doses due to radioactive gaseous effluents The ra'diation dose contributions due to radioactive gaseous effluents at the site boundary for the land sectors have been calculated in accordance i with the calculated methodology in the Offsite Dose Calculation Procedure.

I The meteorology concurrent with the time of discharge were used in these calculations. In addition to the site boundary doses, the dose to an

] individual at the nearest residence within the low population zone for each i

of the land sectors and a five mile infant milk dose in each of the land sectors is included. These dose contributions are listed in Table 8 for the third and fourth quarters and the annual total. There were no measurable releases of radioactivity in gaseous effluents during the second j quarter.

i

! III. Radiation dose to individuals within the site boundary due to the release of liquid and gaseous effluents.

a. Liquid effluents i The radiation dose to individuals within the site boundary.due to the l release of radioactive liquid effluents is negligible. This is because the discharge piping for liquid radwaste is mostly buried in ,

i concrete walls, is located in remote or inaccessible areas or is

underground. In addition, the quantity of radioactivity released was very low during 1984.

f l b. Gaseous Effluents l The maximum radiation dose to individuals within the . site boundary due l_

to the release of radioactive gaseous effluents is evaluated to be 2E-3 mrem during 1984. This dose is to an individual at the plant i overlook located 250 meters from the Unit 1 plant vent in the l northeast sector. It was assumed that an individual was present at

{ the overlook at the time the containment discharges occurred with i winds in this direction.

l I IV. 40 CFR 190 Considerations The releases of radioactivity in liquid and gaseous effluents during 1984 i resulted in doses that are small percentages of the technical specification-c limits as shown in Tables 9 and 10. This coupled with the fact that there i are no other uranium fuel cycle sources within eight kilometers of the Diablo Canyon Nuclear Power Plant shows conformance with 40 CFR 190.

DC0414 VI _ . _ . . .

DIABLO CANYON NUCLEAR POWER PLANT SEMIAff4JAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1984 TABLE 7 RADIATION DOSE DUE TO THE RELEASE OF RADI0 ACTIVE LIQUID EFFLUENTS 4

DOSE millirem Annual ORGAN 2nd Quarter! 3rd Quarter 4th Quarter Total Total Body 1.41 E-6 1.38 E-5 2.58 E-3 2.60 E-3 Bone 0 3.66 E-6 6.68 E-2 6.68 E-2 4

Liver 1.02 E-6 1.50 E-5 4.16 E-3 4.18 E-3 I

Thyroid 1.42 E-14 8.45 E-8 4.69 E-6 4.77 E-6 Kidney 1,38 E-7 6.02 E-7 2.58 E-6 3.32 E-6

Lung 1.42 E-14 2.50 E-6 8.37 E-7 3.34 E-6 f

G. I. LLI 1.32 E-5 1.26 E-4 7.52 E-3 7.66 E-3 NOTES:

I Date of Unit 1 initial criticality was April 29, 1984 DC0414 VI l

- . - . - . . _ . - - - -.- - . -- .. - - . _ _ _ . - - - . - . . . - . . _ - -. = . . -- . . - . - -

DIABLO CANYON N'JCLEAR POWER PLANT l SEMIAff0AL RADI0 ACTIVE EFFLUENT RELEA5E EPORT 1984 TABLE 8 RADIATION DOSE DUE TO THE RELEASE OF RADI0 ACTIVE GASEOUS EFFLUENTS-

THIRD QUARTER 1984 S: ctori (Land only).

NW NNW N NNE NE ENE E- ESE SE Site Boundary (distance) meters 800 800 800 800 970 1175 1660 1750 1800 Noble Gas Gamma air dose mrad - 0 0 0 0 0 0 0 0 0 Beta air close mrad 0 0 0 0 0 0 0 0 0 l

I.P.T2 Adult 3 mrem 0 0 0 0- 0 0 0 1.40 E-7 0 R2sidence - direction, distance-miles 326;3.7 333;1.5 008;4.4 018;3.3 037;5.1 062;4.4 096;4.5 2 mi4 N/A

N:ble Gas Gamma air dose mrad 0 0 0 0 0 0 0 0 N/A '

. Bata air dose mrad 0 0 0 0. 0 0 0 0 '

I.P,T2

. Child 5 mrem 0 0 0 0 0 0 0 .2.07E-75 !

i x

Five Mile Dairy ant mrem N/A 0 0 0 0 0 0 4.00 E-8 N/A DC0414 VI 76-

DI ABLO CANYON NUCLEAR POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1984 TABLE 8 (Continued)

RADIATION DOSE DUE TO THE RELEASE OF RADI0 ACTIVE GASE0US EFFLUENTS FOURTH QUARTER 1984 Sector 1 (Land only) NW NNW N NNE NE ENE E ESE SE Sita Boundary (distance) meters 800 800 800 800 970 1175 1660 1750 1800 Nobla Gas Gamma air dose mrad 1.48 E-4 5.25 E-5 0 0 1.02 E-3 0 0 1.13 E-5 0 B:ta air close mrad 5.20 E-5 1.85 E-5 0 0 3.58 E-4 0 0 3.96 E-6 0 I'

t3 mrem 9.86 E-5 2.60 E-5 1.25 E-5 1.29 E-5 6.13 E-5 9.84 E-6 8.20. E-6 2.39 E-5 5.08 E-5 R:sidence - direction, distance-miles 326;3.7 33371.5 00814.4 01873.3 03715.1 06274.4 096i4.5 2 mi N/A Noble Gas Gamma air dose mrad 6.04 E-6 2.06 E-5 0 0 2.69 E-5 0 0 2.22 E-6 Bata air dose mrad 2.12 E-6 7.23 E-6 0 0 9.49 E-6 0 0 7.82 E-7 I,P,T2 Adult 3 mrem 4.20 E-6 5.89 E-6 8.13 E-7 1.12 E-6 1.88 E-6 1.21 E-6 1.25 E-6 2.98 E-455 Fiva Mile Dairy ant mrem N/A 2.07 E-6 7.59 E-7 6.75 E-7 5.09 E-6 9.41 E-7 1.20 E-6 5.58 E-6 N/A DC0414 VI 77-

1 ,1 j

DI ABLO CANYON NUCLEAR POWER PLANT i

SEMIANNUAL RADI0 ACTIVE EFFLUENT "CLEASE REPORT 1984 TABLE 8 (Continued)

RADIATION DOSE DUE TO THE RELEASE OF RADI0 ACTIVE GASE0US EFFLUENTS ~

1984 ANNUAL

SUMMARY

Sectorl (Land only) NW NNW N NNE NE ENE 'E ESE SE Siti Boundary (distance) meters 800 8 00 800 800 970 1175 1660 1750 1800 Noble Gas Gamma air dose mrad 1.48 E-4 5.25 E-5 0 0 1.02 E-3 0 0 1.13 E-5 0 Beta air close mrad 5.20 E-5 1.85 E-5 0 0 3.58 E-4 0 0 3.96 E-6 0 I,P,T2 Adul t3 mrem 9.86 E-5 2.60 E-5 1.25 E-5 1.29 E-5 6.13 E-5 9.84 E-6 8.20 E-6 2.39 E-5 5.08 E-5 Residence - direction, distance-miles 32613.7 333;1.5 00814.4 01873.3 037;5.1 06214.4 09614.5 2 mi N/A Noble Gas Gamma air dose mrad -6.04 E-6 2.06 E-5 0 0 2.69 L-5 0 0 2.22 E-6 Beta air dose mrad 2.12 E-6 7.23 E-6 0 0 9.49 E-6 0 0 7.82 E-7 I,P,T 2 Adult 3 mrem 4.20 E-6 5.89 E-6 8.13 E-7 1.12 E-6 1.88 E-6 1.21 E-6 1.25 E-6 2.98 E-45 Five Mile Dairy I,P,T2 Infant mrem N/A 2.07 E-6 7.59 E-7 6.75 E-7 5.09 E-6 9.41 E-7 1.20 E-6 5.62 E-6 N/A DC0414 VI ?R-

. DIABLO CANYON NUCLEAR POWER PLANT SEMIAthUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 19814 TABLE 8 (CONTINUED) t NOTES:

1. The ocean sectors SSE, S, SSW, SW, WSW, W, and WNW, are not included.

2.- Radiciodines, Radioactive Material in Particulate Form and Radionuclides Other Than Noble Gases With Half-lives Greater Than Eight Days.

3. The _ inhalation, ground plane and animal-meat pathways are included in this dose calculation. The adult age group had the highest doses of the four age groups.

4. This location is a vegetable farm located throughout the ESE sector starting at 2 miles.

5. The inhalation, ground plane, animal-meat and vegetable pathways are included for this location. An occupancy factor of 0.5 was used for the inhalation and ground plane pathways. The child age group had the highest calculated dose for this location.

D'0414 C VI _

DIABLO CANYON NUCLEAR POWER PLANT sEMIAt#JALRADIOACTIVEEFFLUENTRELEASEREPORT1984 TABLE 9 l

PERCENT OF TECHNICAL SPECIFICATION LIMITS FOR RADI0 ACTIVE LIQUID EFFLUENTS t

PERCENT Annual ORGAN 2nd Quarterl 3rd Quarter 4th Quarter Total Total Body 9.40 E-5 9.20 E-4 1.72 E-1 8.67 E-2 Bone 0 7.32 E-5 1.34 E-0 6.68 E-l' Liver 2.04 E-5 3.00 E-4 8.32 E-2 4.18 E-5 I Thyroid 2.84 E-13 1.69 E-6 9.38 E-5 4.77 E-5 Kidney 2.76 E-6 1.20 E-5 5.16 E-5 3.32 E-5 Lung 2.84 E-13 5.00 E-5 1.67 E-5 3.34 E-5 G. I. LLI 2.64 E-4 2.52 E-3 1.50 E-1 7.66 E-2 NOTES:

1 Date of Unit 1 initial criticality was April 29, 1984 l

DC0414 VI l

O DI ABLO CANYON NUCLEAR POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1984 TABLE 10 PERCENT OF TECHNICAL SPECIFICATION LIMITS FOR RADI0 ACTIVE GASE0US EFFLUENTS 3rd Quarter 4th Quarter Annual Total Sector %lof Sector % of Sector % of T.S. Limit T.S. Limit T.S. Limit Site Boundary i

Noble Gas

. gamna air dose 0 NE 2.04 E-4 NE 1.02 E-4 beta air dose 0 NE 3.58 E-5 NE 1.79 E-5 I,P,T adult ESE 1.87 E-8 NW 1.32 E-5 NW 6.57 E-6 4

i Residence Noble Gas

} gamma air dose 0 NE 5.38 E-6 NE- 2.69 E-6 beta air dose 0 NE 9.49 E-7 NE 4.74 E-7 4

I,P,T child ESE 2.76 E-8 ESE 3.97 E ESE 1.99 E-5 Five Mile Dairy infant ESE 5.33 E-9 ESE 7.44 E-7 ESE 3.75 E-7 1

l DC0414 VI ,

3,-.,-, -

-r - - - , , --

y .-y- - - - - , - - .. , - - - , , v , - -- --- - - ,

l l

PART 4 ETEOR0 LOGICAL DATA DC0414 VI f-1 PETEOR0 LOGICAL DATA l

The hour-by-hour listing of wind speed, wind direction, atmospheric stability and precipitation is being submitted on magnetic tape in accordance with Technical Specification 6.9.1.9.

\

l DC0414 VI -

_ _ _ _ _ _ _ _ _ _ _ - _ l

\

l PACIFIC GAS AND E LE C T RIC C O M PANY bbMb f 77 BEALE STREET . SAN FRANCISCO, CAllFORNIA 94106 * (415)781-4211 . TWX 910 372-6587

"". isk"I""

= =,o="""="

March 1,1985 PGandE Letter No.: DCL-85-090 Mr. John B. Martin, Regional Administrator U. S. Nuclear Pegulatory Commission, Pegion V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368 Re: Docket No. 50-275, OL-DPR-80 Diablo Canyon Unit 1 Semiannual Effluent Release Peport

Dear Mr. Martin:

Enclosed is a copy of the Diablo Canyon Unit 1 Semiannual Radioactive Effluent Release Report for the second half of 1984 (Enclosure 1). The report describes the quantities of radioactive gaseous and liquid effluents released from the plant over the period of July 1,1984 to December 31, 1984 and the solid radioactive waste shipments during the same period. Also enclosed is a magnetic tape of the annual summary of hourly site meteorological data (Enclosure 2).

The report is required by Section 6.9.1.8 of the Diablo Canyon Technical l Specifications, and by 10 CFR 50.36a(a)(2).

Kindly acknowledge receipt of this material on the enclosed copy of this letter and return it in the enclosed addressed envelope.

I Sincerely, N *A Enclosures cc w/o enc. 2: California Department of Health Services Radiological ' Health Section R. W. Carr, Director San Luis Obispo Air Pollution Control District Director, Office of Inspection and Enforcement i

Attn: Document Control Desk Central Cost Regional Water Quality Control Board Service List

') R -/7

PGandE Letter No.: DCL-85-090 ENCLOSlfRE 1 0166S/0027K

DCL-85-090, Semiannual Effluent Rept for Jul-Dec 1984

Text

SUMMARY

Dear Mr. Martin:

Navigation menu

DCL-85-090, Semiannual Effluent Rept for Jul-Dec 1984

Text

SUMMARY

Dear Mr. Martin:

Navigation menu

Search