ML20138Q764

Effluent Monitoring Rept,Third Quarter 1985

ML20138Q764
Person / Time
Site:	Crane
Issue date:	09/30/1985
From:	Standerfer F GENERAL PUBLIC UTILITIES CORP.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
0364A, 364A, 4410-85-L-0238, 4410-85-L-238, NUDOCS 8512270479
Download: ML20138Q764 (9)

Text

..-

ATTACHMENT 1 (4410-85-L-0238)

EXECUTIVE SU(44ARY Three Mile Island Nuclear - Unit 2 Effluent Monitoring Report Third Quarter, 1985 The purpose of this report is to summarize the radioactive liquid and gaseous releases and doses to the public resulting from THI-2 operations for the third quarter of 1985.

Effluent and real time meteorological data and Susquenanna River flow data were used to calculate the maximum postulated dose to any individual and the total population within 50 miles of the plant. Doses for liquid and gaseous discharges were calculated utilizing the guidelines and methodology set forth in USNRC Regulatory Guide 1.109. During the third quarter of 1985, the maximum hypothetical whole body dose received from TMI-2 was 3.3E-4 mrem and was attributable to the liquid effluents. The maximum hypothetical dose to any organ as a result of these effluents was 1.05E-3 mrem from the gaseous effluents. The dose which could have been received from liquid and gaseous discharges are each less than 0.1% of the applicable federal regulatory limits found in Appendix 1 of 10 CFR 50. The doses are insignificant when compared to approximately 20 mrems received by each individual from natural background

. radiation during the quarter. No detectable environmental or health effects are expected from the releases.

During the TMI-2 accident in 1979, large volunes of nighly radioactive water were generated. The water was processed through demineralizer systems to remove tne contamination. It is Deing stored on site in large tanks and nas not been discharged. Currently the only liquid releases from THI-2 are tnose from such areas as waste storage sumps, the air intake tunnel sump, and turbine building sumps.

For liquid discharges during the third quarter of 1985, tritium was the most abundant radionuclide released (4.51E-4 curies). This was followed by unidentified beta (conservatively estimated to be due to strontium-90, 3.1E-5 curies) and cesium-137 (1.5E-5 curies).

For gaseous discharges, the most abundant radionuclide was tritium (2.91 curies). A total of 2.74E-5 curies of total particulates were released.

These particulates included 3.5E-6 Ci for unidentified beta / gamma; 2.36E-5 Ci of Cs-137 and 2E-7 Ci of gross alpha. No noble gases (e.g., krypton-85) were released.

8512270479 850930 PDR ADOCK 05000320 (

R PDR 2

l

\

ATTACHMENT 2' EFFLUENT SUNNARY (6410-85-L-0238) -

THREE NILE ISLAND UNIT 2 LIQUID ANO GASEOUS EFFLUENTS Page 1 of 4 ..

(Sunnary of All Releases) '

TYPE EFFLUENT JULY AUGUST SEPTEMBER 3rd QUARTER 1985 I. Liquid Effluent:

A. Fission and activation products .

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

1. Total Release (Ci) (Note 2) 5.97E-6 2.91E-5 1.11E-5 4.62E-5

2. Concentration (yCi/cc) 1.17E-12 6.21E-12 2.32E-12 3.26E-12

8. Tritium

1. Total release (C1) 9.17E-5 9.39E-5 2.65E-4 4.51E-4

2. Concentration (yC1/cc) 2.22E-11 2.24E-11 6.43E-11 3.64E-11 C. Dissolved and entrained gases

1. Total release (C1) <LLD <LLD <LLD <LLD

2. Concentration (yC1/cc) N/A N/A N/A N/A

! D. Gross alpha radioactivity i 1. Total release (C1) Note 3 Note 3 Note 3 Note 3 j E. Volume of waste released 1 prior to dilution (liters) (Note 1) 3.67E4 3.41E4 4.26E4 1.13E5 i

j F. Volume of dilution water

, (flow to river in liters from NPDES Report) 4.13E9 4.19E9 4.12E9 1.24E10

6. Number of batch releases:

Sumps and sewage 19 21 21 61

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

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

]

- Present liquid effluent release limits are 10% of the concentration values specified in 10CFR 20, l

Appendix B. Table II.

l

- 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.

I Note 1) Includes only those releases which were found to contain radioisotopic concentration >LLD.

j Note 2) Includes Industrial Waste and Sanitary Waste.

Note 3) These activities are to be verified by composite sampling.

l

RTTACHMENT 2 (4410-85-L-0238) 1985 EFFLUENT

SUMMARY

Page 2 of 4 THREE MILE ISLAND UNIT 2 LIQUID AND GASEOUS EFFLUENTS (Continued) '. .

(Summary of All Releases)

TYPE EFFLUENT JULY AUGUST SEPTEMBER 3rd QUARTER 1985 -

Unit 2 Unit 2 Unit 2 II. Gaseous Effluent A. Fission & activation gases

1. Total release (C1) <LLD <LLD <LLD <LLD

2. Release rate (pC1/sec) N/A N/A N/A N/A

8. Iodine-131 released (C1): As of 01/01/81 there was less than 1E-15 curies of I-131 left in Unit 2 therefore, no release of I-131 can be detected.

C. Particulates with half-lives

>8 days:

1. Total releases (not including a)(C1) 1.57E-5 1.09E-5 5.75E-7 2.72E-5

2. Release rate (pC1/sec) 5.85E-6 4.06E-6 2.22E-7 3.42E-6

3. Gross alpha radio-activity (C1) 3.07E-9 2.34E-7 1.96E-9 2.39E-7 D. Tritium

1. Total release (C1) 7.18E-1 6.06E-1 1.59E0 2.91E0

2. Release rate (pC1/sec) 2.68E-1 2.26E-1 6.13E-1 3.66E-1 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 effluents released to the unrestricted area shall not exceed t 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 1 any organ.

h *

• e- - -

ATTACHMENT 2 (4410-85-L-0238) 1985 UNIT 2 LIQUID RADIONUCLIDE RELEASES BY ISOTOPE (C1) ','

RADIDNUCLIDE JULY AUGUST SEPTEMBER 3rd QUARTER 1985 -

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

Ag-110m <LLD <lLD <LLD <LLD Ce-144 <LLD <LLD <LLD <LLD Co-58 <LLD <LLD <LLD <LLD Co-60 <LLD <tLD <LLD <LLD Cs-134 <LLD <LLD <tLD <LLD Cs-137 1.54E-6 1.09E-5 2.46E-6 1.49E-5 I-131 <LLD <LLD <LLD <LLD Sr-90 1

Unidentified Beta 4.43E-6 1.82E-5 8.60E-6 3.12E-5 a

l TOTAL 5.97E-6 2.91E-5 1.11E-5 4.62E-5 j H-3 9.17E-5 9.38E-5 2.65E-4 4.51E-4 Tc-99m - Medical Administration ** 5.45E-6 N/A N/A N/A f

! *These activities are to be verified by composite sampling.

• • Released via sanitary sewage which received this isotope excreted by a person who had undergone

medical treatment at a physician's office.

i i

.- {

, ATTACHMENT 2 (

(4410-85-L-0238) 1985 UNIT 2 GASEOUS RADIONUCLIDE RELEASES BY ISOTOPE (Ci) Page 4 of 4 '.-

RADIONUCLIDE JULY AUGUST SEPTEMBER 3rd QUARTER .-1985 Fission and activation cases Unit 2 Unit 2 Unit 2 Total ,

K r-85 <LLD <tLD <LLD. <LLD Total

~

Particulates (half lives >8 days)

Unidentifiede, y 2.07E-6 8.85E-7 5.75E-7 3.53E-6 Cs-137 1.36E-5 1.0E-5 <LLD 2.35E-5 Cs-134 <LLD <LLD <LLD <LLD Gross alpha 3.07E-9 2.34E-7 1.96E-9 2.39E-7 TOTAL (including alpha 1.57E-5 1.11E-5 5.77E-7 2.74E-5 TOTAL (minus alpha) 1.57E-5 1.09E-5 5.75E-7 2.72E-5 Tritium (3H) 7.18E-1 6.06E-1 1.59E0 2.91E0 A _ __- _ __ _ _ _ _

ATTACHMEfT 3 (4410-85-L-0238) )

Page 1 of 2 1 INTERPRETATION OF DOSE

SUMMARY

TABLE The Dose Summary Table (Table 1) 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 third quarter reporting period of 1985.

A. Liquid (Individual)

The first two lines of Table 1 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 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 discharge, disc ha rge.

while occupying an area of shoreline influenced by the plant 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 maximum whole body dose and affected age. group along with the organ and associated age group that received the largest dose.

For the third quarter of 1985 the calculated maximum whole body dose received by anyone would have been 3.3E-4 mrem to an adult. Simila rly, the maximum organ dose would have been 8.2E-4 mrem to the bone of an adult.

(Note: The unidentified beta inventory is treated as Sr-90)

B. Caseous (Individual)

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

Lines 3 ord 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.

With respect to the gaseous release for the third quarter of 1985, the plume exposure at or near the site boundary would have been 0 mrad and 0 mrad, gamma and beta dose respectively.

W h.

- ATTACHfiENT 3 (4410-85-L-0238)

Page 2 of 2 Lines 5 and 6 present the largest calculated dose to a receptor (individual) in the maximally affected sector (s). The location of the receptor is described by both distance (meters) and direction from the site.

Plume exposures to an individual, regardless of age, from gaseous effluents during the second quarter were 0 mrem and 0 mrem, whole body and skin, -

respectively.

The Iodines and Particulates section described in line 7 represents the maximum exposed organ due to iodine and particulates. This does not include the whole body plume exposure which was separated out by line 5. The doses presented in this section again reflect the maximum exposed organ for the appropriate age group.

The third quarter exposure due to the iodines and particulates would have resulted in a maximum dose of 1.05E-3 mrem to the bone of a child residing 750 meters f rom the site in the SE 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 af f ected 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 projections of the FSAR 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 third quarter, liquid ef fluents resulted in a whole body population dose of 2.4E-3 person-rem with a maximum critical organ population dose to the bone of 9.4E-3 person-rem.

Caseous ef fluents resulted in a whole body population dose of 3.1E-2 person-rem with a maximum critical organ population dose to the liver of 2.9E-2 person-rem.

l

. ATTACHMENT 4 (4410-85-L-0238)

UNIT 2 Third Quarter Dose Report  ; -

SUMARY OF MAXIMUM INDIVIDUAL DOSES FOR UNIT FROM July 1, 1985 through September 30. 1985 Estimated Location  % of Applicable Dose Age Dist Dir Applicable 10CFR50 App. I '

Effluent Organ - (mrem) Croup (m) (toward) Limit Limits (mrem)

, Quarterly Annual Quarterly Annual (1) iquid Total Body 3.3E-4 Adult Receptor 1 (21.iquid 2.2E-2 1.lE-2 1.5 3.0 Bone 8.2E-4 Adult Receptor 1 1.6E-2 5.0 8.2E-3 10.0 (3hoble Cas Air Dose 0 -

(gamma-mrad)

_ 5.0 10.0 (4hoble Cas Air Dose 0 -

(beta-mrad)

- - 10,0 20.0 (SEoble Cas Total Body 0 -

5.0 (6Foble Cas Skin 0 -

15.0 (7)I dine & Bone Pcrticulates 1.05E-3 Child 750 SE 1.4E-2 7.0E-3 7.5 15.0

SUMMARY

OF MAXIMUM POPULATION DOSES FOR UNIT 2 FROM July 1. 1985 through September 30. 1985 Estimated Applicable Population Dose Effluent Organ (person-rem)

(8) Liquid Total Body 2.4E-3 (9) Liquid Bone 9.4E-3 *

(10) Caseous Total Body 3.lE-2 (l1) Caseous Liver 2.9E-2

1

,N ,o -

GPU Nuclear Corporation Nuclear  ;;;,omem,r8o Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

(717) 948-840 4410-85-L-0238 Document ID 0364A Novemoer 27, 1985 Office of Inspection and Enforcement Attn: Dr. T. E. Murley Regional Administrator US Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, PA 19406

Dear Dr. Murley:

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

Operating License No. OPH-73 Docket No. 50-320 Quarterly Dose Assessment Heport - Third Quarter 1985 Per the requirements of Section 5.6.1.C of Appendix B to the Recovery Technical Specifications, the quarterly report of radiological releases and estimated doses is submitted.

Attachment 1 is an executive summary of TM1-2 effluents and doses reported in Attachments 2 through 4. At*actynent 2 presents a summary of releases listing estimates of total activity and the time rate of release of each nuclide. Attachment 3 is the interpretation of Attachment 4, the Dose Summary Taule, which provides a summary of the maximum hypothetical and/or real doses to individuals and the general population resultjng from TMi-2 activities. Doses were extracted from calculational models and represent the bounding doses for all cases. The reporting period includes July 1, 1985 througn September 30, 1985.

Sincerely, F. H. Standerfer Vice President / Director, TM1-2 FHS/CJD/cm1 Attachments cc: Director - TML-2 Cleanup Project U1 rectorate, Ur. W. U. Travers OPU Nuclear Corporation is a subsidiary of the General Public Utilitios Corporation

['b))