ML20062H237

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Revised Semiannual Radioactive Effluent Release Rept for 3rd & 4th Quarters of 1988
ML20062H237
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 12/31/1988
From:
CLEVELAND ELECTRIC ILLUMINATING CO.
To:
Shared Package
ML20062H213 List:
References
NUDOCS 9012040183
Download: ML20062H237 (10)
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Attachment 5 1 1

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I Semi-Annual Radioactive Ef fluent 'Aelease Report i ror the Year 1988 Quarters 3 and 4 (Revision) r 5

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f';DR ADOCK 05000440 Poc

RADIOLOGICAL IMPACT ON MAN Sampling and analysis of liquid and gaseous effluents were performed in accordance with the frequencies, types of analysis, and Lower Limit of Detection (LLD) outlined in the PNPP Unit 1 Technical Specifications.

Radioactive material was detected in some of the liquid and gaseous effluent samples analyzed. Dose calculations, using measured effluent flow and meteorological data, resulted in dose to individuals at levels well below 10CTR20 and 10CTR50, Appendix I limits. Direct radiation resulting from plant operation, as measured by environmental thermoluminescent dosimeters located around the plant, did not c;ntribute any measurable dose to members of the public for tr.e reporting period and, as there are no other nearby fuel cycle sources, 40CTR190 limits were not exceeded.

Summaries of maximum individual and population doses resulting from liquid and gaseous radioactive effluent releases are given, in Regelatory Guide 1.21 format, in Attachment 1.

Technical Specification 6.9.1.7 requires assessment of radiation doses from radioactive liquid and gaseous effluent to members of the public while onsite. These onsite doses are '

assessed relative to offsite dose values, and are adjusted for appropriate dilution, dispersion, and occupancy factors.

s 'ONSITE DOSE FOR LIQUID ETTLUENTS The onsite liquid ef fluent pathway of concern f or members of l the public is shore exposure while fishing along the Lake Eriu coast. Occupaney is assumed to be 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year and the dilution factor for the point of exposure is 10.

Ratioing this exposure pathway to doses calculated for of f site locations yields the following onsite dose values.

Total Body Crean Year 1988 7.o E-03 arem a 1.7 E-03 meta (skin) l Quarters 3 & 4 5.6 E-03 arem 1.4 E-03 mrem (skin) l Quarter 3 2.8 E-04 mrea 3.1 E-05 meem (skin) l Quarter 4 5.3 E-03 aren 1.4 E-03 mrem (skin) f This value reflects corrected doses for Quarters 1 and 2 1988; 6.8 E-04 meem f or Quarter 1 and 1.0 E-03 mrem f or Quarter 2.

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1 ONSITE DOSE FOR GASEOUS ErrLUENTS Several cases are considered for onsite gaseous effluent exposure to members of the public including traversing a public road within the site boundary, shoreline fishing, non-plant related training, car pooling, and job interviews.

The onsite activity with the highest dose potential, relative to gaseous effluents, i s shoreline fishi..;. Occupancy is again assumed to be 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year. Accounting for this and the difference between annual average disgersion values for the onsite point of concern, 6.6 E-05 s/m , (a unity occupancy factor is assumed for this calculation), the following maximum onsite dose values are generated.

Total Body Oroan Year 1988 1.7 E-01 mrem 6.7 E-01 mrem (thyroid)

Quarters 3 & 4 5.9 E-02 arem 1.8 E-01 mrem (thyroid) .

Quarter 3 3.6 E-02 stem 9.9 E-02 mrem (thyroid)

Quarter 4 2.3 E-02 mren 7.9 E-02 mrem (thyroid)

AVERAGE INDIVIDUAL TOTAL BODY DOSES '

Average total body dose to individual members of the public is determined for the population that lives within fifty miles of the plant for gaseous effluents (2.42 E+06 persons) and the population that receives drinking water from intakes within fifty miles for liquid effluents (2.37 E+06 persons).

These doses are calculated using the total population dose figures found in Attachment 1.

Gases Liquids Year 1988 1.1 E-04 mrem 1.5 E-04 mrem Quarters 3 & 4 1.4 E-05 mrem 1.1 E-04 mrem Quarter 3 7.4 E-06 mrem 3.6 E-06 aren Quarter 4 6.6 E-06 mrem 1.1 E-04 mrem Gaseous and Air Dose calculations at the site boundary were performed for two cases. Attachment 1 provides the calculated maximum site boundary dose values for all sectors including those sectors which are totally over water in which no member of the public resides (These are the W, WNW, NW, NNW, N AND NNE SECTORS). Attachment 2 provides the calculated maximum site boundary dose values for the land based sectors in which members of the public reside, l

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LIQUID ErrLUENTS ,

For the third quarter of 1988 there were 12 batch and 80 continuous releases. Batch release total waste volume for the third quarter was 1.3 E6 liters; total continuous l release waste volume was 4.8 E9 liters; total plant discharge during periods of relear' was 2.4 E10 liters.

For the fourth quarter of 1988 there were 54 batch and 52 continuous releases. Batch release total waste volume for the fourth quarter was 6.0 E6 liters; total continuous l release waste volume was 4.2 E9 liters; total plant discharge during periods of release was 2.5 E10 liters.

Summaries of the radionuclide total curie activities, average diluted concentrations, and percentage of MPC (in Regulatory Guide 1.21 format) are included in Attachment 4.

If a radionuclide was not detected, zero activity was used for that isotope in dose calculations. A zero activity indicates that the radionuclide was not present at a level greater than the Lower Level of Detection (LLD) of the instrumentation used. In all cases, these LLDs were less-than the levels required by Technical Specifications. The following are typical LLDs.

l Radionuclide LLD (uCi/ml)

Mn-54 2.4 E-08 Fe-59 5.8 E-08 Co-58 1.9 E-08 Co-60 3.4 E-08 zn-65 4.6 E-08 Mo-99 2.1 E-07 I-131 2.3 E-08 l

Cs-134 2.3 E-00 l 73-137 2.6 E-08 Ce-141 3.2 E-08 o Ce-144 1.3 E-07 St-89 3.0 E St-90 3.7 E-08 Fe-55 5.7 E-09 H-3 4.6 E-06 Gross Alpha 6.0 E-08 1

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4 Attachment 1 (Page 1 of 4)

Radiological Impact on Man (Dese Summaries) 1988: Quarters 3 & 4

SUMMARY

OF MAXIMUM INDI'JIDUAL DOSES h!!MS AIR II?i1:!!!!!!!!

88 7 1 1-881:3124 APPLICABLE ESTIMATED AGE LOCATION 1 0F' LIMIT EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MREM) (M) (TOWARD) LIMIT (nREM)

LIQUID TOTAL BODY 1.42E-03 TEEN RE0EFTOR 1 4.7E-02 3 0Et00 LIQUID . GI-TRACT 3.98E-03 ADULT RECEPTOR 1 4.0FA)2 1.0E+01 NOBLE GAS AIR DOSE 8.45E-01 294 H 8 5Ef00 1.0Ef01 .

(GAMMA-MRAD)

NOPLE GAS ~ AIR DOSE 5.41E-01 294. N 2 8E400 2.0E401 (BETA-MRAD)

NOBLE GAS T. BODY 5 45E-01 ALL 2?4. N 1 1Et01 5.0E+00

. N0BLE GAS SKIN 1.00E+00 ALL 294. N 4 7E+00 1 5Et01 10 DINE 1. THYROID 1.43E+00 INFANT 080. Nilu 1 1Et01 1.5Et01 PARTICULMES

SUMMARY

OF POPULATION DOSES L100!D 88 7 1 1-88123124 GAtt0US -88 7 1 1-88123124 EFFLUENT APPLICABLE ESTIMATED-ORGAN POPULATI0il DOSE (PERSON-REM)

LIQUID TOTAL BODY 2 6E-01 LIOUID . THYROID Z.0E-01 GASEOUS TOTAL BODY 3.4E-02 GASEQUS THYROID 3.tE-01

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Attachment 1 (Continued - Page 2 of 4) l Radiological Impact on Man (Dose Summaries) I 1988: Quarter 3 l

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SUMMARY

OF MAXIMUM INDIVIDUAL DOSES  !

LIGUID 88 7 1 1-89 93024 GASEOUS 88 7 1 1-88 93024

, AIR 88 7 1 1-88 93024 APPLICABLE ESTIMATED AGE LOCATION " 0F LIMIT EFFLUENT ORGAN DOSE GROUP DIST DIR APSLICABLE (MREM) (M) (TOWARD) LIMIT (MREM)

LIQUID TOTAL BODY 4.55E-05 TEEN RECEPT 0R 1 1.5E.03 3.0Et00 f- ' LIQUID 01-TRACT 1.42E-04 ADULT RECEPTOR ; 1.4E.03 1.CE+01 NOBLE GAS AIR DOSE 5.20E-01 294. N 5.2E+00 1.0E+01 (GAMMA-MRAD)

NOBLE GAS AIR DOSE 3.68E-01 283. WNU 1.8E+00 2.0E+01 (BETA-nRAD)

NOBLE GAS T. BODY 3 33E-01 ALL 294. N 6.7E400 5.0Ef00 L NOBLE OAS SKIN 5.98E-01 ALL 274. N 4.0Ef00 1.5E+01 i

10 DINE 1 THYR 0!D 9.04E-01 INFANT 280. NNU 4 2E+00 1.5Ef01 1 PARTICULATES

SUMMARY

Ohh0PU,LATIONDOSES L LIQUID 88 7 1 1-98 93024 GASEOUS 88 7 1 1-88 93024 EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE (PERSON-REM) l LIQUID TOTAL BODY I.65-03 8

LIQUID THYROID 3.7E-03 GASEOUS TOTAL BODY 't.8E-02 4 GASEOUS THYROID 2.6E-01 J'

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Attachment 1 (Continued - Page 3 of 4)

Radiological Impact on Man (Dose Summaries) 1988: Quarter 4

SUMMARY

OF MAXIMUM INDIVIDUAL DOSE 3 LIQUID 8810 1 1-88123124 GASEQUS 8810 1 1-88123124

... .................................1 AIR 8810 1-88123124 APPLICABLE ESTIMATED AGE LOCATION  % OF LIMII EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MREM) (M) (TOWARD) LIMIT (hREMi LIQUID TOTAL BODY 1.37E-03 TEEN RECEPTOR 1 4.6E-02 3,ongo LIQUID GI-TRACT 3.84E-03 RECEPIOR 1 3.8E.02

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ADULT

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HOBLE gab AIR DOSE 3.25E-01 294. H 2.3E100 1 0E+01 (OAMMA-nFAD:

NOBLE GAS AIR DOSE 2.23E-01 294. H 1 2E+00 2.0E+01 (BETA-MRAD)

NOBLE GAS T. BODY 2.12E-01 ALL 294. H 4.2E400 5 0E+00 NOBLE GAS SKIH 4.06E-01 AL. 294. N 2.7E+00 1.5E+01 10 DINE 1 THYROID 7.31E-01 INFANT 294. N 4.9Et00 1.5E+01 PARTICULATES

SUMMARY

OF POPULATION DOSES LIQUID 8810 1 1-88123124 GASEOUS A810 1 1-88123128 EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE (PERSON-REM)

LIOUID TOTAL BODY 3 5E. 1 LIQUID THYROID 1.9 1 GASEOUS TOTAL BODY 1.4E-02 OASE0d" THYROID 1.3E-01 1

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Attachment 1 (Continued - Page 4 of 4) i Radiological Impact on Man (Doss Summaries) l Year 1983 l i

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SUMMARY

OF MAXIMUM INDIVIDUAL DOGES l 1

LIQUID 88 1 1 1-88122124  !

GASEOUS 88 1 1 1-88123124 AIR 88 1 1 1-88123124 APPLICABLE ESTIMATED AGE LOCATION  % OF LIMIT EFFLUENT ORGAN DOSE GROUP OIST DIR APPLICABLE (MREM) (M) (TOUARD) L1 HIT (MREM)

LIQUID ' TOTAL BODY 1.82E-03 TEEN RECEPTOR 1 6.1E.02 3.0E+00 LIQUID 01-TRACT 5.23E-03 ADULT RECEPT 0R 1 5.2E.02 1.)E+01 NOBLE GAS AIR DOSE 2.55E+00 294. H 2.!E+01 1.0Et01 (GAMMA-MRAD)

NOBLE GAS AIR 003E 2.95E+00 294. H 1.5E+01 2 0Et01 (BETA-MRAD)

NOBLE GAS T. BODY 1 55E400 ALL 294. N 3.1E+01 5 0E+00 NOBLE GAS SKIN 3 30E+00 ALL 294. H 2.2E+01 1 5E+01 IODINE 1 THYR 0!D 4.19E+00 INFANT 294. N 4 1E+01 1.5E+01  !

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SUMMARY

OF POPULATION DOSES LIQUID 88 1 1 1-88123124

  • OASEOUS 35 1 1 1 98123124 EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE (PERSON-REM)

...................................................................... i l LIQUID TOTAL BODY 3.

LIQUID THYROID 5.6E-01 7E-01 OASE00S TOTAL BODY 2 7E-01 OASEOUS _ THYROID 1 6Et00 L

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Attachment 4 (Page 1 of 2)

. Liquid Rffluents QUARTER 3 : START DATE 88070101 END DATE 88093024 ..

QUARTER 4 : START DATE 88100101 END DATE 88123124 LIOV! EFTLUENTI UNITE : QUARTER : QUAE!!R :

3 4  :
4. FIS$10N AND ACTIVATION PRODUCTS

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1 1. TOTAL RELEA$E (EXCL.: C1  : 1.03E.02 . 2.025 01  :

TRIT., 6A$Ese ALPNA):  :  :  :

I 2. AVERAG O!Lult :UC1/ML : 4.27E-10 7.94E.09  :

CONC. Uk!NG P RIOD :  :  :  :

3. PERCENT OF  : 1
c.0ct+0c : 0.00Et00

' ..... APPL ........I C A >L.L...LI.MI.T

8. TR!T!UM l l 1. TOTAL RELEAEE  : C1  ; 7.31E-01 : 2.86E+00 l

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5~27$Vk5hiDi[Uki"D"~~~EUC)~/5[.~[ 3I64E268 : ~5$55EI67

..... CONC. DURING.PE.RI.O.D.

.g.... 7...... 7 3.gg .gg. .. 3.gg.gg

...................11......................................

APPLICABLE LIM  :  :  :  :

9 C. D!W50LVED AND ENTRAINED Gastl .

l 1. TOTAL RELEASE  : C1 1 6.91E.04  : 3.73E.03  :

2. AVERAGE DILUTED :UC!/ML : 2.87E.11 1.46E.10 :
CONC. $URING PfRIOD :  :  :
:  : 1 A PL . .. CABLE

. . LIMI.T _ . - ....... ..................

D. BROSS ALPHA RAD 10ACT!VITY

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, i~1. T0T A[. 5ki.iiii".~......I~i}~~~53!5E26T....'2!76526k.i E. VOLUME waste RELEASED l LITER $  ; 4.84E+0? 4.20E+09 :

(PRIOR TO D  : 3,  !  !

.. _ ..........ILUTI.ON) .... ...... - ............................

F. VOLUME DILUTION WATER l LITERS 2.41E+10 :

Uttb

.... DUR PERI.U.D

_ ..I.NG . ... ... -

2.54E+10 ::

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Litruid Efflug, L10VID EFFLUENTS QUAFTER 3 : START tlATE E8070101 EMD DATE 88093024 OUARTER 4 : START DATE E8100:01 END DATE 88123124 DATE OF REPORT: FEli. 25,1989 1 PREPARED BY:

CONTINUOU5 MODE kATCH MODE

NUCL1 DES
UNITS : OUARTER : QUARTER : QUARTER : GUARTER :
RELEASED :  : 3 1 4 3  : 4  :

H3  : C1  : 0.00E+00 1 0 00E+00  : 7.31E.01 : 2.86E+00  :

CR51  : C1  : 0.00Ef00 : 0.00E400  : 3.47E.03 : 1.46E-01  :

MN54  : CI  : 0 00E400 0 00E+00 : 1.30E-03 : 1.61E.02  :
FESS  : C1  : 0 00Ef00 : 0.00E+00 2.23E.03 : 2.44E.03 .

FE59  : 6 10E.04 : 4.86E-03  :

. ..___ . . . .. .. .C. I .. ..:. . 0. 0 0.E.+.0 0. . . . 0. 0 0.E.+.0 0. . .: . . ..

C058  : CI  : 0 00E+00 1 0.00E400 : 5.50E-04
5.28E.03  :
C060  : CI  : 0.00Ef00 : 0.00E400 : 1.43E.03__ 2.11E.02  :
SR89  : C1  : 0.00E+00 : 0 00E+00 : 7.45E-05 : 1.31E 03  :
SR90  : CI  : 0.00E+00 3 0 00E+00  : 0.00E+00 : 6.18E.05  : i TC99M  : Cl  : 0.00E400 0.00E400 1 0.00E+00 3.91E.05  :

AG110M  : C1  : 0.00E400 : 0,00E400 ; 6.31E.04 : 2.17E-03  :

1131  : C1  : 0.00Ef00 0.00E+00 0.00E+00  : 7.48E.04  :

I133  : C1  : 0 00E+00 0 00E+00 : 0.00E+00 : 1.11E.04  :
CS137  : CI  : 0.00E+00 0.00E+00 : 0.00E+00 7.91E-05  :

il546~~~i"Ci"'i'~hIhhdidd'i"d hhk+~55'i"6~00E+00 5.51E.04 'i

AS76  : C1  : 0 00E+00 1 0 00E+00 . 2.69E-04  :

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. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . " . . . _0.00E+00

! D f C1' : 0.00E+00 f 0.00E+00 f 7.40E-01 3.06E+00 f

(ABOVE)  :  :  :  :  :  :

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l  : XE133'  : C1  : 0.00E+00 : 0.00E+00 : 6.20E.04  : 2.34E-03  :

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XE135  : C!  : 0.00Et00 : 0.00E+00 : 7.09E-05  : 1.39E-03  :

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