ML20214V612

Quarterly Dose Assessment Rept of Liquid & Gaseous Effluents & Max Individual Doses for Third Quarter 1986

ML20214V612
Person / Time
Site:	Crane
Issue date:	11/26/1986
From:	Standerfer F GENERAL PUBLIC UTILITIES CORP.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
4410-86-L-0199, 4410-86-L-199, NUDOCS 8612090757
Download: ML20214V612 (10)

Text

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GPU Nuclear Corporation Nuclear a=,orrs:reo Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

(717) 948-8461 4410-86-L-0199 Document ID 0080P November 26, 1986 Office of Inspection and Enforcement Attn: Dr. T. E. Murley Regional Administrator US Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406

Dear Dr. Murley:

Three Mile Island Nuclear Station, Unit 2 (TMI-2)

Operating License No. DPR-73 Docket No. 50-320 Quarterly Dose Assessment Report - Third Quarter 1986 Per Section 5.6.1.C of Appendix B to the Recovery Technical Specification, the quarterly report of radiological releases and estimated doses is submitted. is an executive summary of TMI-2 effluents and doses reported in Attachments 2 and 3. presents a summary of releases including estimates of total activity and the time rate of release of each nuclide. is a dose summary table which provides a summary of the maximum hypothetical and/or real doses to individuals and the general population resulting from TMI-2 activities. Doses were extracted from calculational models and represent the bounding dose for all cases. The reporting period includes July 1, 1986 through September 30, 1986.

Sincerely,

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f, k F. R. Stander er Vice President / Director, TMI-2

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FRS/CJD/eml

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Attachments PDR ADOCK 0500 0

R cc: Director - TMI-2 Cleanup Project Directorate, Dr. W. D. Travers GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

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Atte.chment 1

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Page 1 of 2 EXECUTIVE SUIMARY i

Three Mile Island Nuclear Station Unit 2 Effluent and Offsite Dose Report for the Period of July 1,1986 to September 30, 1986 j

3 This report summarizes the radioactive liquid and gaseous releases (effluents) from Three Mile Island Unit 2 and the calculated maximum

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hypothetical radiation exposure to the public resulting from these releases.

This report covers the period of operation from July 1 to September 30, 1986.

Radiological releases from the plant are measured by installed plant monitors sampling the plant stack for fiaseous releases and liquid monitors for discharges to the Susquehanna River. "hese monitors provide a means for accurate detemination of the type and quantities of radioactive materials being i

released to the environment.

I Calculations 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 that existed at the time of the i

release. Susquehanna River flow data are used to calculate the maximum hypothetical doses to an individual and the population downstream of TMI due to liquid releases. Actual 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 infomation permits the detemination of both the direction in which the release traveled and the dispersion of I

radioactive material in the environment.

1 i

i 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 plant is calculated.

Similarly, Susquehanna River flow and liquid effluent data are used to calculate a maximum hypothetical dose to an individual and a population dose from liquid effluents for any shoreline exposure down to the Chesapeake Bay.

Exposure to tne pubite from consumption of water and fish withdrawn from the Susquehanna River downstream of the plant is also calculated.

Dose calculations for liquid and gaseous effluents are performed using a 4

mathematical model which is based on the methods defined by the U.S. Nuclear l

Regulatory Commission.

c The maximum hypothetical doses are conservative overestimates of the actual l

offsite doses which are likely to occur. For example, the dose does not take J

into consideration the removal of radioactive material from the river water by precipitation of insoluble salts, absorption unto river sediment, biological i

removal, or removal during processing by water companies prior to distribution and consumption.

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i Page 2 of 2 Liquid discharges made during the reporting period July 1 to September 30, 1986 consisted of 0.0005 curies of tritium, 0.00003 curies of strontium-90 and unidentified beta activity and 0.00001 curies of cesium-137. Unidentified beta activity is treated as strontium-90 for the purpose of dose calculations. These release rates and quantities are consistent with results of previous quarters.

The quantities of each radionuclide released are actually up to 1 million times smaller than the normally existing environmental quantities that flowed past the plant during the same time period.

During the reporting period July 1 to September 30 of 1986, the maximum hypothetical calculated whole body dose to an individual due to liquid effluents from Three Mile Island Unit 2 was about 0.0003 millires. The maximum hypothetical calculated dose to any organ of an individual was 0.0009 millires to the bone.

Airborne discharges made during this same time period consisted of 11 curies of tritium, 0.000002 curies of cesium-137, 0.000002 curies of gross alpha activity, and 0.0001 curies of strontium 90 and unidentified beta activity.

Unidentified beta activity is, as with liquid effluents, conservatively assumed to be entirely strontium-90. These release rates and quantities are also consistent with the results from previous reporting periods.

Since there were no noble gas releases for this reporting period, there was no dose to any individual from noble gas. Airborne particulates are calculated to produce about 0.02 millirem to the bone of the maximum hypothetical individual.

The maximum hypothetical whole body dose received by any individual from effluents from the Three Mile Island Nuclear Station Unit 2 for the latest reporting period is 4,000 times lower than the dose the average individual in the Three Mile Island area receives from natural background 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 from natural radon is about 90 millirem per quarter.

The doses which could be received by the maximum hypothetical individual are at most about 0.1 percent of the guides established by the Nuclear Regulatory Covenission.

m

Attachment *2 Page 1 of 4

-s EFFLUENT SWWORY THREE MILE ISLAND UNIT 2 LIQUID AND GASEOUS EFFLUENTS (Summary of All Releases)

TYPE EFFLUENT JULY AUGUST SEPTEMBER 3rd QUARTER 1986 1.

Liquid Effluent:

A. Fission and activation products s.

(not including H-3, gases & alpha) 1.

Total Release (C1) (Note 2) 5.86E-6 2.96E-5 9.05E-6 4.45E-5 2.

Concentration (wC1/cc)(Note 2) 1.56E-12 7.05E-12 2.65E-12 4.07E-12

3. Tritium 1.

Total release (C1) 1.83E-4 1.86E-4 9.06E-5 4.60E-4 2.

Concentration (wC1/cc) 4.98E-11 4.93E-11 2.65E-11 4.11E-11 C. Dissolved and entrained gases 1.

Total release (C1)

<tLS

<LLS

<tLS

<LLS 2.

Concentration (wC1/cc)

N/A N/A N/A N/A S. Gross alpha radioactivity 1.

Total release (C1) Note 3

<LLD 4LLD

<tLU 4LLU I

E. Volume of weste released prior to dilution (liters) (Note 1) 5.31E4 5.61E4 2.75E4 1.37E5 F. Volume of dilution water (flow to river in liters from NPDES Report) 3.75E9 3.77E9 3.42E9 1.09E10 G. Number of batch releases:

Sumps 17 14 9

40 l

The concentration of radioactive meterial other than dissolved or entrained noble gases in liquid l

effluent released to the unrestricted area shall not exceed the values specified in 10CFR 20, Appendix 8. Table II.

- Present liquid effluent release limits are 105 of the concentration values specified in 10CFR 20, Appendix 8. Table II.

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- Liquid effluent releases are also limited to 10CFR 50, Appendix I, not to exceed a dose of 3 mrom total body and 10 mrem to any organ per year.

Note 1)

Includes only those releases which were found to contain radioisotopic concentration >LLO.

Note 2)

Concentration based on Industrial Maste discherged to the river.

Note 3)

These activities are to be verified <LLD by composite sampling.

7 Page 2 of 4 4

1986 EFFLUENT SUfWlARY THREE MILE ISLANO UNIT 2 LIQUID AND GASEOUS EFFLUENTS (Continued)

(Susunary of All Releases)

TYPE EFFLUENT JULY AUGUST SEPTENBER 3rd QUARTER 1986 Unit 2 Unit 2 Unit 2 Unit 2 II. Gaseous Effluent Note (1)

Note (1)

Note (1)

Note (1)

A.

Fission & activation gases 1.

Total release (Ci)

<tLD

<LLD

<tLD

<LLD 2.

Releass rate (yCi/sec)

N/A N/A N/A N/A B.

Iodine-131 released (C1):

<tLD

<LLD

<LLD

<LLD C.

Particulates with half-lives

>8 days:

1.

Total releases (not (Note 4) includingc<)(C1) 4.27E-6 1.30E-4 3.55E-6 1.38E-4 2.

Release rate (pCi/sec) 1.59E-6 4.85E-5 1.37E-6 1.74E-5 3.

Gross alpha radio-activity (Ci) 3.89E-8 2.44E-6 8.48E-9 2.49E-6 D.

Tritium 1.

Total release (C1) 3.90E0 3.01E0 4.17E0 1.11El 2.

Release rate (yC1/sec) 1.46E0 1.12E0 1.61 E0 1.40E0 E.

Seconds in period reported 2.6784E6 2.6784E6 2.5920E6 7.9488E6 F.

Number of batch releases 0

0 0

0 The concentration of radioactive material in gaseous ef fluents released to the unrestricted area shall not exceed the values specified in 10CFR 20. Appendix B. Table II.

10CFR 50 dose to individual for: a) 10 mrad /yr, gamma radiation; b) 20 mrad /yr, beta radiation; and c) 15 mrem /yr to any organ.

As of 01/01/81 there was less than 1E-15Ci of I-131 left that is of Unit-2 origin.

Not2 4) Onsite analyses indicated that Sr-90 was <tLD at <7.0E-12pCi/cc for the period of 8/10/86 to 8/11/86. However, offsite analyses for the same period indicated Sr-90 present at 6.20E-13pci/cc which is equivalent to 2.91pCi Sr-90 present in 34.4pti gross beta. Also, onsite analyses indicated that Sr-90 was <tLD at <2.6E-11pti/cc for the period of 8/11/86 to 8/17/86, while offsite analyses indicated Sr-90 present at 2.33E-12pCi/cc equivalent to 66.9pti Sr-90 present in 89.0pci gross beta. These increases are considered to be artifacts of low sample flowrates used to achieve combined particulate, iodine, and noble gas grab samples.

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4 1986 UNIT 2 L10ul0 RADIONUCLIDE RELEASES BY ISOTOPE (C1)

RADIDNUCLIDE JULY AUGUST SEPTEMBER 3rd QUARTER 1986 Fission and activation products (not including alpha, H-3 & gases)

<tLD

<LLD

<LLD

<LLD

. Ag-110m

<tLD

<LLD

<LLD

<LLD Ce-144

<tLD

<LLD

<tLD

<LLD Co-58

<LLD

<tLD

<tLD

<LLD Co-60

<LLD

<LLD

<LLD

<LLD Cs-134

<tLD

<LLD

<LLD

<LLD Cs-137 1.58E-7 1.07E-5 1.43E-6 1.23E-5 f

I-131

<LLD

<tLD

<LLD

<LLD Sr-90*

5.70E-6 1.89E-5 7.62E-6 3.22E-5 TOTAL 5.86E-6 2.96E-5 9.05E-6 4.45E-5 H-3 1.83E-4 1.86E-4 9.06E-5 4.60E-4 l

• The values reported include Sr-90 activity and any activity not specifically identified. Thus, the reported Sr-90 value represents a conservative estimate (i.e. overestimate) and contains activity from cther beta-gasuna emitters which were not positively identified during conduct of analytical procedures.

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Page 4 of 4 1986 UNIT 2 GASEOUS RADIONUCLIDE RELEASES 8Y ISOTOPE (C1)

RADIONUCLIDE JULY AUGUST SEPTEMBER 3rd QUARTER 1986 Fission and activation cases Unit 2 Unit 2 Unit 2 Total Kr-85

<tLD

<tLD

<LLD

<lLD T;tal Particulates (half lives >8 days)

Unidentified beta / gamma 4.27E-6 5.82E-5 (Note 4) 3.55E-6 6.60E-5 Cs-137

<LLD 1.78E-6

<LLD 1.78E-6 Cs-134

<tLD

<LLD

<LLD

<LLD Gross alpha 3.89E-8 2.44E -6 8.48E-9 2.49E-6 Sr-90

<tLD 6.98E-5

<LLD 6.98E-5 TOTAL (including alpha) 4.31E-6 1.32E-4 3.56E-6 1.40E-4 TOTAL (minus alpha) 4.27E-6 1.30E-4 3.55E-6 1.38E-4 Tritium (3 )

3.90E0 3.01E0 4.17E0 1.11El H

~ Attachment 3 Page 1 of 3 UNIT 2 Third Quarter Dose Report SUMARY OF MAXIMUM INDIVIDUAL DOSES FOR UNIT 2 FROM July 1,1986 through September 30, 1986 1

I I

I Estimated i

I Location 1

5 of I

Limits (aren) l l Applicable l Dose i

Age l Dist Dir l

Applicable l 10 CFR 50 Appendix I l l Effluent i

Organ I

(aren) l Group I

(m)

(toward)

Limit i

Limits (aren) l I

I I

I I

Quarterly I Annual I Quarterly l Annual l

I I

I I

I I

I I

I I

l 3.0 l

l 1.1E-2 1 l(1) Liquid 1 Total Bo@

l 3.4E-4 i

Adult l Receptor 1 l

l 10.0 l

l 8.9E-3 l l(2) Liquid i Bone 1

8.9E-4 1

Adult 1 Receptor 1 l

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

l 10.0 l

l 0

l I

l 1(3) Noble Gas ! Air Dose 1

0 1

I I (gamma-arad) l I

i i

l l

l l

l 20.0 I

l 0

l 1

1 l(4) Noble Gas i Air Dose 1

0 l

i 1 (wumrad l

I I

I I

I I

I 1

5.0 l

1 0

l l

1 I(5) Noble Gas l Total Body 1

0 1

l 15.0 l

l 0

l 1

1 1(6) Noble Gas i Skin 1

0 1

I I

I I

I I

I I

l l

l 1

1 I

I I

I I

l l

l 15.0 l

1 0.11 l

1(7) Iodine &

I Bone l

1.6E-2 l

Child l

500 W

l l

Particulatesl l

l l

l l

l l

l SUMARY OF MAXIMUM POPULATION DOSES FOR UNIT 2 FROM July 1,1986 through September 30, 1986 Estimated Applicable Population Dose Effluent Organ (person-ren)

(8) Liquid Total Bo%

0.01 2 (9) Liquid Bone 0.047 (10) Gaseous Total Body 0.15 (11) Gaseous Bone 0.23

Page 2 of 3 INTERPRETATION OF D0SE SLM4ARY TABLE

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The Dose jummary Table presents the maximum hypothetical doses to an individual and the general population resulting from the release of gaseous and liquid i

effluents from TMI-2 during the third quarter reporting period of 1986.

A.

Liquid (Individual) i The first two lines of the table present the maXd mum hypothetical dose to an individual. Presented are th whole bo@ and cr1tical organ doses, i

Calculations are performed on the four ape groups and eight organs recomended in Regulatory Guide 1.109.

hc pathways considered for TMI are l

drinking water, consumption of 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 i

the vicinity of TMI. The " receptor" would be that individual who consumes l

water from the Susquehanna River and fish residing in the plant discharge, j

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

After calculating the doses to all age groups for all eight organs resulting from the three pathways described above, the Dose Summary Table presents the

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maximum whole body dose and affected age group along with the organ and

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associated age group that received the largest dose, l

For the third quarter of 1986 the calculated maximum whole bo# dose t

l received by anyone would have been 3.4E-4 mrem to an adult. Similarly, the maximum organ dose would have been 8.9E-4 mrem to the bone of an adult.

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8.

Gaseous (Individual) i There are seven major pathways considered in the dose calculations for gaseous effluents.

These are:

(1) plume, (2) inhalation, consumption of (3) cow milk, (4) goat milk, (5) vegetables, (6) meat, and (7) standing on contaminated ground.

i Lines 3 and 4 present the maximum plume exposure at or beyond the site I

boundary. The notation of " air dose" is interpreted to mean that these 1

I doses are not to an individual, but are considered to be the maximum dose l

that would have occurred at or beyond the site boundary. The Dose Sumary Table presents the distance in meters to the location in the affected sector (compass point) where the theoretical maximum plume exposure occurred.

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j should be noted that real-time meteorology was used in all dose calculations i

for gaseous effluents.

For the third quarter 1986, no direct nobie gas plume dose occurred since no noble gases were released from Unit 2 during the period.

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i

lion described in line 7 krese ds the The Indines and Particulates r maximum exposed organ due to iodine and particulates. This does not include any wnole bo@ plume exposure which would be separated out by lines 5 and 6.

The doses presented in this section again reflect the maximum exposed organ for the appropriate age group.

The th'ird guarter 1986 iodines and particulates would have resulted in a maximum dose of 1.6E-2 mrom to the bone of a child residing 500 meters from the site in the W sector.

No other organ of any age group would have received a greater dose.

C.

Liquid and Gaseous (Population)

Lines 8 - 11 present the person-rem doses resulting from the liquid and gaseous effluents. These doses are summed over all pathways and the affected populations. Liquid person-rem is based upon the population encompassed within the region from the TMI outfall extending down to the Chesapeake Bay. The person-rem for gaseous effluents are based upon the 1980 population and consider the population out to a distance of 50 miles i

around TMI.

Population doses are sumed over all distances and sectors to give an aggregate dose.

Based upon the calculations performed for the third quarter, liquid effluents resulted in a whole bo# population dose of 1.2E-2 person-rem.

The maximum critical organ population dose to the bone was 4.7E-2 person rem. Gaseous effluents resulted in a whole bo# population dose of 0.15 person-rem. Maximum critical organ population dose to the bone was 0.23 person-rem.

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