ML20212F521

From kanterella
Revision as of 07:54, 21 January 2021 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Quarterly Dose Assessment Rept for Fourth Quarter 1986
ML20212F521
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 12/31/1986
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20212F485 List:
References
NUDOCS 8703050107
Download: ML20212F521 (7)


Text

.

ATTACHMENT 2 :

" 4410-87-L-0031 '-

1986 EFFLUENT N Y Page 1 of 4 -

THREE MILE ISLAND UNIT 2 LIQUID ANO GASEOUS EFFLUENTS (Continued) , ;

- (Summary of All Releases)

I OCTOBER NOVENBER DECENBER 4th QUARTER 1986 TYPE EFFLUENT Unit 2 Unit 2 Unit 2 Unit 2 ,

Notes (146) Note (1) Note (1) Note (1) "

II. Gaseous Effluent A. Fission & activation gases 2.80E-1

<LLO 2.80E-1 <LLD

1. Total release (C1) 1.08E-1 N/A 3.52E-2 N/A 2.. Release rate (yC1/sec)

<LLD <LLD <LLO <LLS ,

8. Iodine-131 released (C1): Note (5) Notes (4&S)

C. Particulates with half-lives Note (4) Note (4) ,

>8 days:

1. Total releases (not 7.08E-6 3.19E-6 4.71E-6 1.50E-5

' including alpha)(C1) 1.88E-6 Release rate (yci/sec) 2.64E-6 1.23E-6 1.76E-6 2.

3. Gross alpha radio- 4.32E-7 activity (C1) 1.02E-7 1.51E-7 1.79E-7
0. Tritium 5.60E0 5.78E0 1.73E1 .

' 1. Total release (C1) 5.92E0 '

2.21E0 2.16E0 2.16E0 2.18E0

2. Release rate (yC1/sec) .

,o 7.9488E6 Seconds in period reported 2.6784E6 2.5920E6 2.6784E6 E.

0 2 0 2

. F. Number of batch releases

- The concentration of radioactive material in gaseous offluents released to the unrestricted area shall not exceed the values specified in 10CFR 20, Appendix 8. Table II.a) 10 mrad /yr, gaassa radiation; b) 20 mrad /yr, beta radiation; an 10CFR 50 dose to individual for:

any organ.

- As of 01/01/81 there was less than 1E-15C1 of I-131 left that is of Unit-2 origin. '

4 - Gaseous effluents reported are monitored at the following release points: Unit 2 Station Vent, EPICOR II Vent, ,

l Respirator Laundry & Maintenance Building, and the B&W Trailer Vent Stack.

10/26/86 to 11/02/86 was destroyed upon removal from the Nste 4) The Station vent particulate sample for the period sample holder. However, a review of the recorded hourly readings for the period while this sample was in place indicates that accumulated data was i 2 sigma of the monthly average value. The highest data from the previous month was used to estimate releases from 10/26/86 to 11/02/86. This represents a deviation from the normal sample regimen. (Ref. Tech. Specs. 2-12 table 2.3-2, Notes (5&6)).

i 8703050107 870227 l

PDR ADUCK 05000320 '

R PDR

ATTACHMENT 2' .

L4410-87-L-0031' '.

1986 EFFLUENT

SUMMARY

Pags 2 of 4-THREE MILE ISLAND UNIT 2 LIQUID AND GASEOUS EFFLUENTS ..

-(Summary of All Releases) ~

TYPE EFFLUENT OCTOBER NOVEMBER DECENBER 4th QUARTER 1986 I. Liquid Effluent:

A. Fission and activation products

! 3 (not including H-3, gases & alpha)

1. Total Release (Ci) (Note 2) 3.90E-6 6.46E-5 4.94E-6 7.34E-5
2. Concentration (pCi/cc)(Note 2) 1.29 E-12 1.33E-11 9.69E-13 5. 65 E-12 f

f B. Tritium j 1. Total release (C1) 1.75E 5.55E-5 2.09E-5 2.51E-4 l 2. Concentration (pCi/cc) 5.78E-11 1.14 E-11 4.10E-12 1.93E-11 i

C. Dissolved and entrained gases

1. Total release (C1) <LLD <LLD <LLD <LLD
2. Concentration (pCi/cc) N/A N/A N/A N/A i D. Gross alpha radioactivity j 1. Total release (C1) (Note 3) <LLD <LLD <LLD <LLD 4

E. Volume of waste released prior to dilution (liters) (Note 1) 3.09E4 5.92E4 1.96E4 1.10E5 F. Volume of dilution water (flow to river in liters from NPDES Report) 3.03E9 4.86E9 5.10E9 1.30E10 G. Number of batch releases:

Sumps .10 19 6 35

] - The concentration of radioactive material other than dissolved or entrained noble gases in liquid

-l ef fluent released to the unrestricted area shall not exceed the values specified in 10CFR 20,

{ Appendix B. Table II.

- Present liquid ef fluent release limits are 10% of the concentration values specified in 10CFR 20, 4

s Appendix B, Table II.

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

! Nate 1) Includes only those releases which were found to contain radioisotopic conce7tration >LLD.

Nate 2) Concentration based on Industrial Waste discharged to the river.

} Nate 3) These activities are to be verified <LLD by composite sampling.

j i

ATTACHMENT 2 4410-87-L-0031' -

'9' ' '

1986 UNIT 2 LIQUID RADIONUCLIDE RELEASES BY ISOTOPE (C1)'

RADIONUCLIDE OCTOBER NOVENBER DECEN8ER 4th QUARTER-1986 4

N Fission and activation products (not including alpha, H-3 & gases)

Ag-110m <LLD <LLD <LLD <LLD j t Ce-144 <LLD <LLD <LLD <LLD i Co-58 <LLD <LLD <LLD <LLD' i Co-60 <LLD <LLD <LLD <LLD

! Cs-134 <LLD 4.21E-7 <LLD 4.21E-7 4

Cs-137 <LLD 2.65E-5 2. 51 E-6 2.90E-5 I-131 <LLD <LLD <LLD <LLD Sr-90* 3.90E-6 3.77E-5 2.43E-6 4.40E-5 i

l i TOTAL 3.90E-6 6.46E-5 4.94E-6 7.34E-5 ,

H-3 1.75E-4 5.55E-5 2.09E-5 2.51E-4 1

j *The values reported include Sr-90 activity and any activity not specifically identified. Thus, the l

reported Sr-90 value represents a conservative estimate (i.e. overestimate) and contains activity from i other beta-gamma emitters which were not positively identified during conduct of analytical procedures.

Nate (5) The EPICOR II vent monitor was out of service from 12/10 to 12/21,1986. Sutstitute j airborne samples f rom within EPICOR II were used to generate release data. Particulate .

l concentrations were conservatively reduced by.10-3 to account for HEPA filter removal of particulates. Tech. Specs. 2-12, table 2.3-2 Notes (5&6) .

i Nate (6) On 10/29/86, a total of 2.77E-2 Curies of Xe-133 was detected at the Unit-2 station vent noble gas channel detector, and has been identified with Unit-1 operations

ATTACHMENT 2 ,

4410-87-L-0031 Page 4 of 4 1986 UNIT 2 GASEOUS RADIONUCLIDE RELEASES BY ISOTOPE (C1)

RADIONUCLIDE OCTOBER NOVEM8ER DECEM8ER. 4th QUARTER 1986 Fission and activation cases Unit 2 Unit 2 Unit 2 Total Kr-85 <LLD 2.80E-1 <LLD 2.80E-1 l

1 T@tal Particulates (half lives >8 days)

Unidentified beta /ganna 7.08E-6 3.18E-6 4.71E-6 1.50E-5 Cs-137 <LLD 1.16E-8 1.08E-9 1.27E-8 Cs-134 <LLD <LLD <LLD <LLD Gross alpha 1.02E-7 1. 51 E-7 1.79E-7 4.32E-7 Sr-90 <LLD <LLD <LLD <LLD TOTAL (including alpha) 7.18E-6 3.34E-6 4.89E-6 1.54E-5 TOTAL (minus alpha) 7.08E-6 3.19E-6 4.71E-6 1.50E-5 5.92E0 5.60E0 5.78E0 1.73E1 Tritium (3H)

ATTACHMENT 3 '

'4410-87-L-0031 -

UNIT 2 .

Fourth Quarter Dose Report

  • SUMARY OF MAXIMUM INDIVIDUAL DOSES FOR UNIT 2 FROM October 1,1986 through December 31, 1986 l l l Estimated I  ! Location I  % of I Limits (area) l l l Applicable l Dose i Age l Dist. Dir l Applicable 1 10 CFR 50 Appendix I l l Effluent i Organ I (arem) l Group l (m) (toward) l Limit l Limits (area) l 1

1 I I I I I Quarterly I Annual I Quarterly I Annual l l 1 l l l 1 l l l l l(1) Liquid l Total Body l 4.78E-4 l Adult l Receptor 1 l ---

l 1.6E-2 l ---

l 3.0 l l(2) Liquid l Bone l 1.07E-3 l Adul t i Receptor 1 l ---

l 1.1E-2 l ---

l 10.0 l i l l l l 1 I I I I

I I I I I I I I I l(3) Noble Gas l Air Dose l 6.8E-7 l ---

l 2413 W l ---

i 6.7E-6 l ---

l 10.0 l l l (gamma-mrad) l l l l l l l l i

l(4) Noble Gas l Air Dose 1 7.6E-5 1 ---

l 2413 W l ---

l 3.8E-4 l ---

l 20.0 l l l l (beta-mrad l l l l l l l l

! l(5) Noble Gas l Total Body l 4.2E-7 l All l 2500 W l- ---

l 8.3E-6 l ---

l 5.0 I j l(6) Noble Gas l Skin l 5.0E-5 l All l 2500 W l ---

l 3.3E-4 l ---

l 15.0 l l l I l l l 1 I I i l I i I I I I i l l(7) Iodine & l Bone 1 2.98E-3 i Child i 630 ESE l --- .

l 0.02 l ---

l 15.0 l l Particulatesl l l l l l l l l SUMARY OF MAXIMUM POPULATION DOSES FOR UNIT 2 FROM October 1,1986 through December 31, 1986 Estimated Applicable Population Dose Effluent Organ (person-rem)

(8) Liquid Total Body 0.0047 (9) Liquid Bone 0.01 9 (10) Gaseous Total Body 0.088 (11) Gaseous GI, Liver, Kidney, 0.082 Thyroid, Lung

ATTACHMENT 4 4410-87-L-0031 Page 1 of 2 INTERPRETATION OF DOSE SUtWARY 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 effluents from TMI-2 during the fourth quarter reporting period of 1986.

A. Liquid (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 recomended in Regulatory Guide 1.109. The pathways considered for TMI are 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 the vicinity of TMI. The " receptor" would be that individual who consumes water from the Susquehanna River and fish residing in the plant disch6rge, 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, ths Dose Sumary Table presents the maximum whole body dose and affected age group along with the organ and associated age group that received the largest dose.

For the fourth quarter of 1986 the calculated maximum whole body dose received by anyone would have been 4.8E-4 mrem to an adult. Similarly, the maximum organ dose would have been 1.1E-3 mrem to the bone of an adult.

B. Gaseous (Individual)

There are seven major pathways considered in the dose calculations for gaseous effluents. These are: (1) plume, (2) inhalation, censumption of (3) cow milk, (4) goat milk, (5) vegetables, (6) meat, and (7) standing on contaminated ground.

Lines 3 and 4 present the maximum plume exposure at or beyond the site boundary. The notation of " air dose" is interpreted to mean that these doses are not to an individual, but are considered to be the maximum dose that would have occurred at or beyond the site boundary. The Dose Summary Table presents the distance in meters to the location in the affected sector

! (compass point) where the theoretical maximum plume exposure occurred. It should be noted that real-time meteorology was used in all dose calculations for gaseous effluents.

Direct noble gas plume dose to the maximum individual is shown on lines 5 and 6. For the fourth quarter of 1986 the calculated maximum whole body dose received by anyone would have been 4.2E-7 mrem. Similarly, the maximum skin dose would have been 5.0E-5 mrem.

ATTACHMENT 4 4410-87-L-0031

- ** Page 2 of 2 The Iodines and Particulates section described in line 7 represents the maximum exposed organ due to iodine and particulates. This does not include any plume exposure which is 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 fourth quarter 1986 todines and particulates would have resulted in a maximum dose of 3.0E-3 mrem to the bone of a child residing 630 meters from the site in the ESE 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 sumed 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 around TMI. Population doses are summed over all distances and sectors to give an aggregate dose.

Based upon the calculations performed for the fourth quarter, liquid effluents resulted in a whole body population dose of 4.7E-3 person-rem.

The maximum critical organ population dose to the bone was 1.9E-2 person rem. Gaseous effluents resulted in a whole body population dose of 8.8E-2 person-rem. Maximum organ population dose to the GI, liver, thyroid, kidney, and lung was 8.2E-2 person-rem.

l l

l l

l l

l l

l

. _