DCL-86-144, Radioactive Effluent Release Data for 1984
ML20198J134 | |
Person / Time | |
---|---|
Site: | Diablo Canyon |
Issue date: | 12/31/1984 |
From: | PACIFIC GAS & ELECTRIC CO. |
To: | |
Shared Package | |
ML20198J120 | List: |
References | |
DCL-86-144, NUDOCS 8605300691 | |
Download: ML20198J134 (11) | |
Text
__ .. _.
. l PGandE Letter No.: DCL-86-144 ENCLOSURE Diablo Canyon Unit 1 Radioactive Effluent Release Data for 1984 4
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Copied from April 22, 1986 letter from R. A. Hartfield, Office of Resource Management, U.S. Nuclear Regulatory Commission, to J. O. Schuyler, Vice President, Nuclear Power Generation, Pacific Gas and Electric Company.
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COOLINC VATER SOURCEPACIFIC OCEAN AI; BORNE EFFLUENTS CUCLIDES PELEASED ACTIVITY (CI)
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LIQUID EFFLUENTS I
CUCLIDES RELEASED ACTIVITY (CI) /
KA-24 3.42E-sev P-32 4.34E-n3* .r CR-51 4.FRE-84' MN-54 ^ " ' - A Y W ~ OY s co-se -- u 3t=e3 3. qB__F - 03 FE-59 3. 9E-85/ -
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[ _MO-99 L270 S' 9.52 6-04 l 58-124 2.33E-85<
l I-131 3.15E-#5' 8.64E-D5' I-133 XE-135 4.78E-86#
CS-137 1. !'I E-p? #
V-187 3.25E-04 /
TOTAL AIRBORNE TRITIUM RELEASE I . '1 E-st '
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VOLUME OF L IOUID_WASIE.JLELEASED itfLI.OR TO DIL_UTJ00 LITERS _ G J"E.1"C la 7 3 f~ + 0 7 VOLUME OF DIL UTION _ WEER U. SED DU'!ING PER IOD LLTERS -tv & th+++ 2.0 0 E + 11 s
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EFFLCECT A7.D WASTE DISPOSAL SrMIANNUAL REPORT FOR 198s SUPPLEMENTAL IN; ORMATION DETECTOR PRIOR TO RELEASE. THE PRE-RELEASE ANALYSIS INCLUDES DISSO".VED AND ECTRAINED GASES. VOLUME PROPORTIONAL MONTHLY AND QUARTERLY COMPOSITES ARE PREPARED FROM ALIQUOTS OF EACH TANK RELEASED. THE MONTHLY COMPOSITE IS ANALYZr D FOR TRITIUM USING A v/
LIQUID SCINTILLATION SPECTROMETER. GROSS ALPHA RADIOACTIVITY USING AN INTERNAL PROPORTIONAL COUNTER AND PHOSPHOROUS-32 USING AN INTERNALS" f rapa<U,w / (s u w / e r-FOLLOWING CHEMICAL SEPARATION. THE QUARTERLY COMPOSITE IS ANALYZED FOR IROM-5S USING A THIN SODIUM IODIDE DETECTOR AND FOR STRONTIUM-89 AND 98 USIDG AN INTERNAL FROPORTIONAL DETECTOR FOLLOWING CHEMICAL SEPARATIONS.
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 VOLLME PROPORTIONED FOR WEEKLY. THE OILY WATER SEPARATOR -
VEEKLY COMPOSITE MONTHLY IS ANALYZED AND QUARTERLY FOR GROSSCOMPOSITES.AND GAMMA PRINCIPAL GAMMA EMITTERS USING A CECMANIUM DETECTOR. THE STEAM GENERATOR BLOWDOWN TANK WEEKLY COMPOSITE IS ANALVZED F OR PRINCIPAL GAMMA EMITTERS AND IODINE 131. THE STEAM GENERATOR BLOWDOVM TANK MONTHLY COMPOSITE IS ANALYZED FOR TRITIUM USING A LIQUID SCINTILLATION SPECTROMETER. 7 FOP GROSS ALPHA USING AN INTERNAL PROPORTIONAL COUNTER AND FOR PHOSPHOROUS-32 USING V A3 IOTERNAL PROPORTIONAL COUNTER FOLLOWING CHEMICAL SEPARATION. THE STEAM GENERATOR BLOWDOWN TANK OVARTERLY COMPOSITE IS ANALYZED FO,R IRON-55 USING A THIN SODIUM IODIDE DETECTOR AND FOR STRONTIUM-89 AND 98 USING AN INTERNAL PROPORTIONAL COUNTER FOLLOWING CHEMICAL SEPARATIONS. THE RESULTS FOR EACH OF THE COMPOSITES IS AVERAGED OVEQ THE PFRIOD OF THE COMPOSITE. IN ADDITION. ONE GRAB SAMPLE OF THE STEAM GENERATOR BLOWDOVN T/.N E IS ANALY2ED MONTHLV FOR DISSOLVED AND ENTRAINED GASES USING A GERMANIUM DETECTOR. THE RESULTS OF THIS ANALYSIS ARE ASSUMED TO REMAIN CON 9 TANT OVER THE PERIOD OF ONE MONTH.
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EFFLUENT AID VASTE DISPOSAL SEMIANNUAL REPORT FOR 1984 SUPPLEMENTAL INFORMAf t0N AVERAGE ENERGYtMEV/DISINTFCRATION)
SECOND SIX MONTHS .
BETA CAMMA ,
SECOND Six s Fict$ G YF l BATCH RELEASES N** '
f; A. LIQUID
/ 7 I I. MUMBER OF BATCH RELEASES- 288 . __
l 2. TOTAL TIME PERICD FOR BATCH RELEASEStMINi- ___5. 25 E - _ 4 _ " .. -*7. C 6 EA___ '
- 3. MAXIMUM TIME PERIOD FOR A BATCH RELEASEIMIN)- _ _ 7.2BE 2 "#
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! 4. AVERAGE TIME PERIOD FOR BATCH RELEASEStMIN3- _ _ 2.64[ 2 _ _ _ _ _ _._ _25T
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l S. MINIMUM TIME PERIOD FOR A BATCH RELEASE (MINI- 2.29F I - 7 . y _o__E _1__ t I 6. AVERAGE STREAM FLOV DURING PERIODS OF RELEASE :
l OF EFFLUENT INTO A FLOVING STREAMtLTS/ MINI- ---
2.BBE 6 < IO E ( - - - - _
- 8. CASEOUS
- 1. NUMBER OF BATCH RELEASES- 34 - 17
- 2. TOTAL TIME PERIOD FOR BATCH RELEASES (MIN)- __ _8.15F 3* 7,73 63 ~ ~~
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- 3. MAXIMUM TIME PERIOD FOR A BATCH RELEASEIMIN)- ___ I . 4 4 f E 3 ~7~~~~
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- 4. AVERAGE TIME PERIOD FOR BATCH RELEASES (MIN)- ~~~ ~ '~6.22_E_g _ ~~- ~
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- 5. MINIMUM TIME PERIOD FOR A BATCH RELEASEtMIN)- ___ I.82I s/ __ 3, cc go __
ABNORMAL RELEASES A.' LIQUID
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- 1. NUMBER OF RELEASES _ -- H _ " - .
- 2. TOTAL ACTIVITY RELEASED (CURIES 1 <
_ 8.88E a/ _ O,00 f . O B. CASEOUS
- 1. MUMBER OF RELEASES 0 '
O j 2. TOTAL ACTIVITY RELEASES (CURIES) 8.8FE 8 V 0,co_ F 0 _
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UNIT QUARTER _.0UARTER EST TOTAL ht/4#7.E('
.3 4 foPOP * (
l A. FISSION AND ACTIVATION CASES
- 1. TOTAL RELFASE CI N/D' 5 . R G E _2 /. 5 . FF E ._ _1 *'. _ _ _ _ _ N/B
- 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC N/Dv 7.37E__31 _ __
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[ 3. PE RCENT Or TECHNICAL SPECIFICATION LIMIT x 8.FFE' # 5.05L 5 ' _._ __ _ _g, pcip B. IODINES
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- 2. 3FE . 1 " _ _ _ _ __ M / F
- 2. AVEPACE RELEASE RATE FOR PERIOD UCI/SFC N/D 6
- 3. PERCENT OF TECHNICAL SPECIFICATION LIMIT x A.FFE ._ N / D - Fs
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- 1. PARTICULATES VITH HALF-LIVES >S DAYS CI _N/D' 1.2fE__.5f_2.3PE__1_e Pf/9
- 2. AVEPAGE RELEASE RATE FOR PERIOD UCI/Src N/D" .
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- 3. PIPCENT OF TECHNICAL SPECIFICATION LIMIT x (,8FE" 8 9.97E- 4" O, v0 60
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- D. TRITIUM
[ 1. TOTAL RELEASE CI 7. 35E ._ S t .1.3PE 2 < .I . 2PE_. 1/ _ _ _ _ __ N_/ C D 2. AVERACE RELEASE RATE FOR PERIOD UCI/SEC 1.24E- 6#_1,G4E .3 ._._ _ . . . . _ . _ . _ _ . Nf p_
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- 3. PFRCENT OF TECHNICAL SPECIFICATION LIMIT X 1.65E _Rf..Z.93E- 6_Y_ _______ _ _ . g eafo t
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g _
A. FISSION AND ACTIVATION PRODUCTS I. TOTAL RELEASE INOT INCLUDING TP,ITIUM, GASFS. ALPHA) CI 3.51E- 3< 7.61E- 3' 2.lFF 1- f.RFE-V ~' ~- --
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 1,01 g - r
- 3. PERCENT Or APPLICABLE LIMIT % 9.49E-ll'.6.68E-II' 1.2SE- 4 '5.F6E- 4' ,_ _-][jy]
B. TRITIUM
- 1. TOTAL RELEASE CI 1.59E- 1 .8.43E 7.FFF F< ~ - ~ -( 1f 6 2 ----- -
- 2. AVERAGE DILUTED CONCENTRATION DUPING PERIOD UCI/ML 4.29E- 9s.7.4FE- 9 ' f, y p g 9
- 3. PERCENT OF APPLICABLE LIMIT % I.43E- 4 /2.47E- 4< g y C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CI N/D < 4.Z.8E _67.2.lFE. Is 14 /'0-
- 2. AVERAGE DILUTED CONCENTRATION "
DURING PERIOD UCI/ML N/D 4 i l9F-14 / Ij ##
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- 3. PERCENT OF APPLICARLE LIMIT % 8.FFE -
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D. GROSS ALPHA RADIOACTIVITY I. TOTAL RELEASE CI N/D ' N/D__v 6.FFE_ .1_ '_ _ _ p /0 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTIOM) LITEeM 3.84E Gr_3,9FE_ 6T_S.ppE.. F' _ _ _ ilt 0 yJ_7 F. VOLUME OF DILUTION VATER USED DURING PERIOD LITE 9S 3.7FE 18- I.14E liv G.6pr F ' _ . _ __ _ __ _ _ M0_E / 0 i
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,. TYPE OF WASTE 3 A.SPECT RESINS. FILTER SLUDGES. EVAPORATOR .' ' _M3 S.88E N < ' ,
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- 8. DRY COMPRESSIRLE WASTE. CONTAMINATED .M3 8.98E 8 _
EOUIPMENT. ETC'. CI 5.ssE 8 -
C.IZADI ATED COMPONENTS. CONTROL /* M3 5.88E 9 / ~ ' - - ~ - ~ '
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CUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 9 v N/A v N/A -
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