ML20128B852

Unit Two Effluent & Off Site Dose Rept for Jul-Sept 1992

ML20128B852
Person / Time
Site:	Three Mile Island
Issue date:	09/30/1992
From:	Long R GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C-92-1952, C000-92-1952, C312-92-2085, NUDOCS 9212040110
Download: ML20128B852 (13)

Text

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4 GPU Nuclear Corporation

,9, Nuclear =eo =greo Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Olal Number:

(717) 948-8400 November 30,1992 C312-92-2085 C000-92-1952 US Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Desk Three hiile Island Nuclear Station, Unit 2 (Th11-2)

Operating Licensing No. DPR-73 Docket No. 50-320 Quarterly Dose Assessment Report Third Quarter 1992

Dear Sir:

The attached submittal includes the quarterly report of radiological releases and estimated doses t for the Third Quarter 1992 in accordance with the .h11-2 Technical Specifications Appendix B Section 5.6.1.c.

i l The maximum hypothetical doses received by an individual from Thil-2 effluents for the latest l reporting period is 0.0004 mrem whole body dose from liquid releases and 0.00005 mrem whole body dose from gaseous releases. These doses are each less than 0.01% of the Technical Specification limits and are 159,500 times lower than the dose the average individual in the Thil area receives from natural background radiation during the same time period. The reported maximum hypothetical doses are conservative overestiraates of the actual offsite doses which are likely to occur.

Dose summaries and effluent releases for the previous quarters of the 1992 calendar year v.ere reported via GPU Nuclear letters C312-92-2041 dated hiay 29,1992 and C312-92-2070 dated September 10, 1991, i Sincerely, g

h R. L. Long Director, Corporate Services /Th1I-2 JSS/dlb Attachments cc: T. T. h1artin - Regional Administrator, Region I hl. T. hiasnik - Project hlar.ager, PDNP Directorate L. H. Thonus - Project hianager, Thil Site F. i. Young - Senior Resident Inspector, TMI 9212040110 920930 QgQ DR ADOCK 0500 0 GPU Nuclear Corporation is a subsidiary of the General Public . Utilities Corporation I{

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J lST OF ATTACHMENTS i TMI-2 Ouarterly Dose Assessment Renort Third Ouarter 1992 Attachment 1 Executive Summary Attachment 2 Effluent Summary Attachment 3 Dose Report Attachment 4 Interpretation of Dose Summary Table 4

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ATTACHMENT T C312-92 2085 Page 1 of 2 EXECUTIVE

SUMMARY

Three Mile Island Nuclear Station Unit Two Effluent and Off Site Dose Report i for the Period of July 1, 1992 through September-30, 1992

. This report summarizes the radioactive liquid and gaseous releases (effluents) from Three Mile Island Unit Two and-the G1culated

. maximum hypothetical radiation exposure _to the public resulting l from these releases. This-report covers the period.of operation from July 1, 1992 through September 30, 1992.

l Radiological releases from the plant . are monitored by installed plant radiation monitors which survey the plant stack for gases ,s releases and liquid discharges to the Susquehanna River. These monitors and associated sample analyses provide a means to accurately determine the type and quantities of radioactive-

] materials being released to the environment.

Ualculations of the maximum hypothetical dose to an individual and the total' population around Three Mile Island due to radioactive releases from the plant are made utilizing . environmental conditions existing at the time of the release. Susquehanna River l flow data i are used to calculate the scrimum hypothetical doses to an individual and the population downstream of TMI due to liquid releases. Achual or "real-time" meteorological data from an onsite tower is used to determine the doses resulting from gaseous

releases from the plant. The use of real-time -meteorological

information permits the determination of both the direction in

which the release traveled 'and the - dispersion of radioactive material in the environment.

l Utilizing . gaseous effluent data and real-time meteorology, _the maximum hypothetical dose to any individual and to the total population within 50 miles of the plantiis calculated. Similarly, Susquehanna River flow' and liquid effluent data- are - used to-calculate ' a maximum hypothetical dose to an- individual and- a-4 population dose fram liquid effluents for any shoreline exposure i down to the Chesapeake -Bay. Exposure to the' public- from-  ;

consumption of water and fish withdrawn from the Susquehanna River i downatream of the plant ~is'also calculoted.

Dose calculations for liquid and gaseous effluents are performed i

using a mathematical-model which is based on the methods defined by i the U.S. - Nuclear Regulatory Commission.

The maximum-hypothetical doses are conservative overestimates of l the actual off site doses which are likely to occur. For example,  !

the dose does not take into consideration :the removal of j i radioactive material from the river water by precipitation of  !

j insoluble salts, absorption onto- river sediment, biological- '

j. removal, or removal during processing by water companies prior to

_ distribution ~and consumption. .

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ATTACHMENT 1 C312-92-2085 Page 2 of 2 Liquid discharges made during the reporting period Julj 1, 1992 through September 30, 1992 consisted of 0.00013 curies of tritium, 0.00004 curies of cesium-137, and 0.0000011 curies of cobalt-60.

The quantities of effluents are consistent with results of previous quarters. 'the quantities of each radionuclide released are actually up to 1 million times smaller than the normal existing environmental quantities that flowed past the plant during the same time period.

, During the reporting period July 1, 1992 through September 30, 1992, the maximum hypothetical calculated whole body dose to an individual due to liquid effluents from Three Mile Island Unit Two was 0.00042 millirem. The maximum hypothetical calculated dose to any organ of an individual was 0.0007 millirem to the liver.

Airborne discharges made during this same time period consisted of 0.078 curies of tritium and 0.0000000066 curies of cesium-137.

The maximum hypothetical calculated organ dose to any individual due to gaseous effluents was about 0.000054 millirem to the liver.

The maximum hypothetical calculated whole body dose to any individual due to gaseous effluents was 0.000054 mrem.

The total maximum hypothetical whole body dose of 0.00047 mrem received by any individual from effluents from the Three Mile Island Nuclear Stetion Unit 2 for the reporting period is 159,500 times lower than the done the average individual in the Three Mile Island area receives from natural background and radon (75 mrem) during the same time period. Natural background averages about 25 millirem whole body per quarter in the Three Mile Island area. In addition, average equivalent dose to the whole body from natural radon is about 50 millirem per quarter.

The doses which could be received by the maximum hypothetical individual are each less than 0.01 percent of the annual guidelines established by the Nuclear Regulatory Commission.

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ATTACHMENT 2  !

. , , C312-92-2085 Page 1 of 6 J

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) EFFLUENT

SUMMARY

TIIREE MILE ISLAND UNIT 2 LtQUID AND GASEOUS EFFLUENTS

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SUMMARY

OF ALL RELEASES)

TYPE EFFLUENT 3RD QUARTER 1992 y ................................................................................................................................

TOTAL

! LIQUID EFFLUENTSt JULY AUGUST SEPTEMBER 3RD QUARTFR A. FISSION AND ACTIVATION FRODUCTS *==== === = = ===== ** - *====u (NOT INCLUDING H-3, CASES, & ALPHA)

1. TOTAL RELEASE (C1) 3.92E.06 2.70E.06 3.40E.05 4.06E.05

2. CONCENTRA?!ON (uC1/cc) 8.682 13 6.15E.13 7.29E.12 2.99E.12

, B. TRITIUM 2

1. TOTAL RELEASE (C1) 2.77E.05 5.52E.05 4.45E.05 1<272 04

2. CONCENTRATION (uci/cc) 6.13E.12 1.26E.11 9.54E.12 9.39E.12 I C, DISSOLVED AND ENTRAINED CASES

1. TOTAL RELEASE (01) <LLD <LLD <LLD CLLD

2. CONCENTRATION uC1/cc) N/A N/A N/A N/A i

2 i D. GROSS ALPHA ACTIVITY

1. TOTAL RELEA3R (C1) <tLD CI.LD <LLD <LLD 1

i' E. VOLUME OF WASTE RELEASED t

PRIOR TO DILUTION (LITERS) 5.78E+04 4.313+04 1.77t+05 2.78E+05 1

i l F. VOLUME OF DILUTION WATER 4.52E+09 4.59E+09 4.67E+09 1.36E410 l (Flow To RIVER IN LITERS

( rROM NPDES REr0RT) i G. NUMBER OF BATCH RELEASES 17 15 19 51

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, ATTACHMENT 2

, . C312 92 2085 Page 2 of 6-1

, 1992 UNIT 2 L10UID . TAD 10WJCL10E RELEASES BY ISOTOPE (C1)

J l RADIONUCt DE JtfLY AUGUST SEPTEMBER 3RD QUJ TER 1992 j /IS$!ON AND ACTIVATION PRODUCTS

)I (NOT INCLUDING ALPHA, H.3 6 GASES <tLD <!10 <LLD <tLD AGol1034 < Lt.D <LLD <LLD <LtD I

CE.104 (LLD <t1D CLLD <LLL Co.58 <tLD <LLD <tLD <110

$ Co.60 <!1D <!1D 1.14E.06 1.14E.06 CS.134 (LLD <!10 <!10 <110 2

CS.137 3.92E.06 2.70E-06 3.29E 05 3.95E.05 t

1 131 <LLD <LLD <!10 <1.LD j SR.90 (110 <LLD <LLD <LLD TOTAL 3.922 06 2.70E.06 3.40E.05 4.06E.05 l

f H.3 2.77E.05 5.52E.05 4.45E.05 1.27E.04 -

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-ATTACHMENT 2 C312 92 2085 Page 3 of 6 a

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EFTLUENT

SUMMARY

73REE MILE ISLAND UNIT 2 LIQUID AND GASEOUS EFFLUENTS

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SUMMARY

OF ALL RELFJSES) 1 TYPE EFFLUENT 3RD QUARTER 1992 TOTAL JULY At1GIMT ScPTEMBER 3RD QUARTER j

fr. CASEOUS ErrLUEntSi A, FISSION AND ACTIVATION CASES

1. TOTAL RELEASE (C1) <1.t0 <LLD CLLD <LLD

2. RELEASE RATE (uct/sec) N/A N/A N/A N/A D. !ODINE 131 RELEASED (C1) <tLD <LLD CLLD CLLD 4

C. PARTICULATES WITH HALF. LIVES

$8 DAYS l

1. TOTAL RELEASES (NOT <LLD 6.66E.09 <Lt.D 6.662 09 INCLUDING A*JEA) (C1)

2. RELEASE RATE (uct/sec) N/A 2.49E.09 N/A 8.38E-10

3. CROSS ALPHA RADIO.

ACTIVITY (Cil <LLD <LLD <LLD <LLD D. TRITIUM

1. TOTAL EZLEASE (Cl) 3.04E.02 2.6$E.02 2.07E.02 7,76E.02

2. RELEASE RATE (uct/sec) 1.16E.02 9.90E.03 7.972 03 9.76E.03 i

l E. SECONDS IN PERIOD REPORTED 2,68t+06 2.68E+06 2.59E+06 7.95E+06 F. NUMBER OF BATCH RELEASES 0 0 0 0 a

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J ATTACHMENT 2 C312 92-2085 Page 4 of 6

UNIT 2 GASEOUS RADIONUCLICE RELEASES BY JSOTOPE (C1)

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i RADIONUCL!DE JULY AUGUST SEP" EMBER 3RD QUARTER 2992 TISSION AND ACTIVAT!ON CASES 1

l F.R.8$ <LLD CLLD <LLD <LLD TOTAL ar 1

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PARTICULATES (HALF.t!VES 78 DA1S) 1 i CS.137 <LLD 6.66E.09 (LLD 6.66E 09

+

C3 134 <LLD <LLD <LLD CLLD SR/Y.90 <tLD <LLD <tLD (LLD l C.14 <tLL <LLD <tLD <tLD 58-125 <LLD < t.LD <LLD <LLD Co.60

<tLD <LLD <LLD <LLD GROSS ALPHA <LLD <20 <LLD (LLO 1

t1 TOTAL (INCLUDING ALPHA) <LLD 6566E.09 <LLD 6.66E.09 TOTAL (MINUS ALPHA) (LLD 6,662 09 <LLD 6.66E.09 4

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<- TRITIUM (H.3) 3.04E.02 2.652 02 2.072 02 7.76E.02 a

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ATTACHMENT 2

- C 312- 92-2085 Page 5 of 6 TABLE 1 TYPICAL LIQUID EFFLUENT LLD (Lower Limit of Detection) VALUES ASSUMPTIONS: Sample volume = 1 liter = 1000 cc

, Sample counting time = 1000 sec Sample counted with a 25% Ge(LI) for Gamma Emitters ISOTOP6 pCi/cc LLO RQ]IS Gross Alpha a 4 E-9 Counted with proportional counter Gross Beta B 7 E-8 Counted with pror,ortional counter Tritium H-3 4 E-6 Counted with liquid scintillation counter Krypton-85 Kr-85 1 E-4 Xenon-131m Xe-131 m 2 E-5 Xenon-133 Xe-133 1 E-6 r

Xenon-135 Xe-135 3 E-7 Chromium-51 Cr-51 3 E-6 Manganese-54 Mn-54 4 E-7 Cobalt-58 Co-58 4 E-7 Iron-59 Fe-59 9 E-7 Cobalt-60 Co-60 6 E-7 Zinc-65 Zn-65 1 E-6 Zirconium-95 Zr-95 7 E-7 Niobium-95 Nb-95 4 E-7 Molybdenum-99 Mo-99 3 E-7 Technetium-99m Tc-99M 3 E-7 Silver-110m Ag-110m 6 E-7 l Antimony-125 Sb-125 9 E-7 l Cesium-134 Cs-134 5 E-7

! Cesium-136 Cs-136 4 E-7 l Cesium-137 Cs-137 5 E-7 l Barium-140 Ba-140 1 E-6 Lanthanum-140 La-140 7 E-7 i Cerium-141 Ce-141 5 E-7 Cerium-144 Ce-144 3~ 6 l

lodine-131 1-131 3 E-7 lodine-133 1-133 4 E-7 Phosphorus-32 P-32 1 E-6 These LLD values for liquid sample Iron-55 Fe-55 5 E-8 analyses of gross alpha, P-32, Fe-55, Strontium-89 St-89 5 E-8 Sr-89, and Sr-90 are the same as l

Strontium-90 Sr-90 5 E-8 Unit 1 which are offsite vendor LLD l Gross Alpha a 1 E-7 values.

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ATTACHMENT 2 C312-92-2085 Page 6 of 6 f TABLE 2 TYPICAL GASEOUS EFFLUENT LLD (Lower Limit ef Detection) VALUES s

ASStJMPTIONS: Sample volume (Mvinelli) 1640cc Sample volume (Particulate & Charcoal Filters) 5.7E8cc Sample Rate P cfm or 5.66E4cc/ min Sample Time 1 week or 1E4 min

Sample volume (tritium bubbled thru water) 7.56ESec Sample Rate 75cc/ min Sample Time 1E4 min Sample Counting Time: a & H-3-20 min; n=10 min; y=1000 sec Sample Counters: y emitters 25% Ge(LI) a or 8 Proportional Counter H-3 Liquid E-'ntillation Counter JFOTOPE UCi/cc LLD N[cTfg i Gross Alpha a 1 E-15 Particulate Filter Paper Gross Beta B 1 E-14 Tritium H-3 1 E-10_ Air bubbled thru water by a fritted disc or Fisner Milligen gas washer i Krypton-85 Kr-85 5 E-6 Marinelli Krypton-85m Kr-85m 2 E-8

. Krypton-87 Kr-87 6 E-8 l Krypton-88 Kr-88 5 E-8 j Xenon-133 Xe-133 4 E-8

Xenon-133m Xe-133m 1 E-7

! Xenon-135 Xe-135 2 E-8 l Xenon-135m - Xe-135m 3 E-7 Xenor.-138 Xe-138 3 E-7 i Iodine-131 1-131 2 E-8 l lodine-133 1-133 3 E-8 lodine-135 l-135 - 2 E -7 l

l lodine-131 1-131 3 E-14 Charcoal Filter -

i lodine-133 1-133 4 E-14 lodine-135 l-135 3 E-13 Manganese-54 Mn-54 3 E-14 Particulate filter paper i Iron-59 ft-59 8 E-14 l Cobait-58 Co-58 3 E-14

Cobalt-60 Co-60. - 5 E-14 Zinc-65 Zn-65 9 E-14 Strontium-89 Sr-89 2 E-14 Strontium-90 Sr-90 2 E-14 Molybdenum-99 -Mo-99 2 E-14 Ruthenium-103 - Ru-103 2 E-14 Silver-110m Ag-110m 3 E-14 Cesium-134 Cs-134 4 E-14 Cesium-137 Cs-137 3 E-14 Cerium-141 Ce-141 3 E-14 Cerium-144 Ce-144 9 E-14

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TABLE 1 UNIT 2 ,

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES FOR UNIT 2 FROM July 1. 1992 through September 30. 1992 Estimated Location  % of  ;

Applicable Dose Age Dist Dir Applicable Limits (nrem)

Effluent Organ (arem) Group (m) (toward) Limit 10 CFR 50 Appendix I Quarterly Annual Ouarterly Annual (1) Liquid Total Body 4.16E-4 Adult Receptor 1 ---

1.38E-2 ---

3.0 >'

(2) Liquid Liver 6.61E-4 Teen Receptor 1 ---

6.61E-3 --- 10.0 (3) Noble Gas Air Dose 0 --- --- --- ---

0 ---

10.0 (gamma-mrad)

(4) Noble Gas Air Dose 0 --- --- -- ---

0 --

20.0 (beta-arad)

(5) Noble Gas Total Body 0 --- --- --- --- 0 ---

5.0 (6) Noble Gas Skin 0 --- --- --- ---

0 ---

15.0 Lung, Liver, I (7) Iodine & Total Body, 5.36E-5 Child 580 WNW ---

3.57E-4 ---

15.0 Particulates Thyroid, Kidney, GI-LLI

SUMMARY

OF MAXIMUM POPULATION DOSES FOR UNIT 2 FROM July 1. 1992 through September 30. 1992 Estimated Applicable Population Dose Effluent Oroan foerson-rem)

(8) Liquid Total Body 2.81E-4 un >

(9) Liquid Liver 5.91E-4 y"d ,

(10) Gaseous Total Body 4.60E-4 <D N > '

(11) Gaseous Liver, Thyroid, 4.60E-4 . .b 9 Lung, GI-LLI, Kidney o7%

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. ATTACHMENT 4 C312-92-2085 Page 1 of 2-INTERPRETATION OF DOSE

SUMMARY

TABLE The Dose Summary Table presents the maximum hypothetical doses to an individual and the general population resulting from the release of gaseous and liquid ef fluents from TMI-2 during the third quarter reporting period of 1992, i

A. Licuid (Individual)

The first two lines present the maximum hypothetical dose to an individual. Presented are the whole body and critical organ doses. Calculations are performed on the four age groups and eight organs recommended in Regulatory Guide 1.109.

The pathways considered for TMI-2 are consumption of drinking water and fish and standing on the shoreline influenced by TMI

, effluents. The latter two pathways are considered to be the primary recreational activities associated with the Susquehanna River in the vicinity of TMI. The " receptor"

would be that individual who consunes water from the

Susquehanna River and fish residing in the plant discharge,

, while occupying an area of shoreline influenced by the plant discharge.

For the third quarter of 1992 the calculated maximum whole body dose received by anyone would have been 4.16E-4 mrem to an adult. Similarly, the-maximum organ dose would have been 6.61E-4 mrem to the liver of a teen.

B. Gaseous (Individual)

There are six major pathways considered in the dose

calculations for gaseous effluents. These are

(1) plume, (2) inhalation, consumption of (3) cow milk, (4) vegetables,-

(5) meat, and (6) standing on contaminated ground.

Lines 3 and 4 present the maximum gwnma and beta plume

. exposure, respectively, from noble' gases at or beyond the site boundary. Direct noble gas plume dose to the total body and

• l skin of an individual is shown on lines 5 and 6, respectively.

Because there were no noble gases releashd during the third

, quarter, the plume exposures (lines 3 and 4) and plume doses (lines 5 and 6) are zero.

The Iodines and Particulates section described in line 7

. represents the maximum- exposed organ due- to- iodine, particulates, and tritium. The dose presented in this section again reflects-the-maximum exposed organ for the appropriate age group.

The third quarter 1992 iodines and particulates would have resulted in a maximum organ dose of 5.36E-5 mrem to the liver-of a-child residing 580 maters from the site -in the WNW-sector. .The maximum. total body dose was 5.36E-5 mrem to'a child.

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l ATTACHt1ENT 4 C312-92-2085 i ,_ ' Page 2 of 2 4 .

'C. Licuid and Gaseous (Pooulation)

Lines 8 - 11 present the person-rem doses resulting from the; liquid and gaseous effluents. These doses are summed over all ,

i pathways and the affected populations. The person-rem doses-  !

from liquid ef fluents are based upon the population encompassed

! within the region from the TMI outfall extending down to the 4

Chesapeake Bay. The person-rem doses from gaseous effluents l are based upon the 1990 population and consider the population l out to a distance of 50 miles around TMI.- Population doses are summed over all distances and sectors to give an aggregate l dose.

Based upcn the calcu,1ations performed for the third quarter of 1992, liquid eff.'.aents resulted in a whole body population dose-

of 2.81E-4 person-rem. The maximum critical organ population dose was-5.91E-4 person-rem to-the . liver. Gaseous' effluents resulted in a whole body population d ~ s of 4.60E-4 person-rem.

The maximum organ population dose was 4.60E-4 person-rem to the ,

liver, lung, thyroid, kidney, and GI tract.

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