ML20235U317
| ML20235U317 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 12/31/1988 |
| From: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 4410-89-L-0026, 4410-89-L-26, NUDOCS 8903090142 | |
| Download: ML20235U317 (24) | |
Text
.
ATTACHMENT 1 .
Tf1I-2 QUARTERLY DOSE ASSESSMENT REPORT
. FOURTH QUARTER 1988 4410-89-L-0026 EXECUTIVE SUfEARY Three Mile Island Nuclear Station Unit 2 Effluent and Offsite Dose Report for the Period of October 1,1988 to December 31, 1988 This report summarizes the radioactive liquid and gaseous releases (effluents) from Three Mile Island Unit 2 and the calculated maximum hypothetical radiation exposure to the public resulting from these releases.
This report covers the period of operation from October 1 to December 31, 1988.
Radiological releases from the plant are measured by installed plant monitors sampling the plant stack for gaseous releases and liquid monitors for discharges to the Susquehanna River. These monitors provide a means for accurate determination of the type and quantities of radioactive materials being released to the environment.
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 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 plaat.
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 it the environment.
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 Exposure to the public from consumption of water and fish withdrawn from the Susquehanna River downstream of the plant is also calculated.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 mathematical model which is based on the methods defined by the U.S. Nuclear Regulatory Commission.
The maximum hypothetical doses are conservative overestimates of the actual offsite doses eiich are likely to occur. For example, the dose does not take into consideration the removal of radioactive material from the river water by precipitation of insoluble salts, absorption onto river sediment, biological removal, or removal during processing by water companies prior to distribution and consumption.
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ATTACHMENT 1 TMI-2 QUARTERLY DOSE ASSESSMENT REPORT 4410-89-L-0026 FOURTH QUARTER 1988 Page 2 of 2 L'iquid discharges made during the reporting period October 1 to December 31, 1988 consisted of 0.0001 curies of tritium, 0.00007 curies of strontium-90 and unidentified beta activity, and 0.00006 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 radionuclides released are actually up to 1 million times smaller than the normally existing environmental quantities that flowed past the Klant during the same time period. .
During the reporting period October 1 to December 31 of 1988, the maximum hypothetical calculated whole body dose to an individual due to liquid effluents from Three Mile Island Unit 2 was about 0.00099 millirem. The maximun hypothetical calculated dose to any organ of an individual was 0.002 millirem to the bone.
Airborne discharges made during this same time period consisted of 4 curies of tritiurt, 0.00001 curies of cesium-137, 0.08 curies of krypton-85, 0.00000004 curies of strontium-90, and 0.00003 curies of unidentified beta activity. l Unidentified beta activity is, as with liquid effluents, conservatively assumed J to be entirely strontium-90 . These release rates and quantities are also consistent with the results from previous reporting periods. The maximum hypothetical dose to an individual due to gasecus effluents was about 0.0023 millirem to the bone of a child.
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 12,000 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 and average equivalent dose from natural radon is about 50 millirem per quarter for a total of about 300 mrem per year.
The doses which could be received by the maximum hypothetical individual are at most 0.1 percent of the guides established by the Nuclear Regulatory Commission.
1
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Mr ATTACHMENT 2 TMf.2 QUARTERLY DOSE ASSESSMENT REPOP.T 4410 89.L 0026 FOURTH QUARTER 1988 Page 1, of 4 m:
-4 EFFLUENT SUMARY -
+
THREE MILE ISLAND UNIT 2 LIGUID AND 6ASEOUS EFFLUENTS LSUMARY OF ALL RELEASESI TYPE EFFLUENT 4TH DUARTER 1988 E
TOTAL-l 1. LIQUID EFFLUENTS: DCTOBER NOVEMBER DECEMBER 4TH QUARTER t A. FISSION AND ACTIVATION FRODUCTS ========= ========= ========= :::========. !
(NOT INCLUDINS H-3,' 6ASES & ALPHA)
'1. TOIAL RELEASE (Cil 6.81E-85 6.;8E-85 1.1;E-85 1.34E-84 g 2. CONCENTRAi!CN luti/cc) 1.89E-11 !.61E-11 2.35E-12 9.43E-12 I. TRIT!UM
- . TOTAL RELEASE (Cil 2.68E-05 B.25E-86 8.82E 1.22E-84
- 2. CONCENTRATION (uC1/tt) 4.71E-12 2.llE-12 1.53E-Il B.59E-12 C. DISSOLVED AND ENTRAINED SASES
- 2. CONCENTRATION uCi/cc) N/A N/A N/A N/A
- 3. GR055 ALPHA ACTlVITY
- 1. TO*AL nELEASE (Cil 8.88E+88 8.88E+08 8.8BE488 8.88E+88 E. VOLUME OF WASTE RELEASED FR10R.T0 DILUTION (LliERS) 3.99E+84 2.92E+84 2.69E+84 9.28E+84 F. VOLUME OF DILUTION WATER 5.53E+89 3.91E+89 4.82E+89 1.43E+18 (FLOW TO RIVER IN LITERS FROM NPOES REPCRT)
S. NUMfER OF PATEN RELEASES 15 12 IB 37 6
+
ATTACHi1ENT 2 Tt11.'2 QUARTERLY; DOSE' ASSESSMENT REPORT .4410-89-L-0026 FOURTH QUARTER 1988 Page 2.of 4
-IFFLUENT
SUMMARY
THREE MILE ISLAND UNii 2 LIQUID AND 6ASEOUS EFFLUENTS (EUMMARY OF ALL RELEASES)
TYFE EFFLUENT 4TH QUARTER 1965 TOTAL OCTOBER NOVEMBER DECEMBER 4TH BUARTER
- === ::::::===== ::========= :::========
!!. BASE 00S EFFLUENTS:
A. FIS$10N AND ACTIVAT]CN 6ASES
- 2. RELEASE RATE (utilsec) 2.88E-82 N/A N/A 9.45E-83
- 8 DAYS
- 1. TOTAL RELEASES (NOT 5.66E-86 1.88E-16 3.85E-85 3.88E-85 INCLUDING ALPHA) (Ci!
- 2. RELEASE RATE (uCi/ set) 2.11E-86 6.94E-87 1.14E-85 4.78E-86.
- 1. TOTAL RELEASE (Ci) 1.8BE+18 !.lBE+88 !.38E+80 3.56E+88
- 2. RELEASE RATE (utilset) ~ 4.82E-81 4.54E-81 4.87E-81 4.4BE-Il E. SECONDS IN FER.'0D REFORTED 2.6784E+16 2.592BE+86 2.6784E+86 7.9488E+86 F. NUMBER OF BATCH EELEASES 8 8 8 8 l
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ATTACHMENT 2 TMI-2 QUARTERLY DOSE ASSESSMENT REPORT 4410-89-L-0026 FOURTH QUARTER 1988 Page 3 of 4 1988 UNIT 2 LIQUID RADICNUCLIDE RELEASES BY ISOTOPE (Cil FADIMUCLICE OCTOBER NOVEMBER DECEMBE't 4THQUARTER1988
=- = - -
FISS!DN AND ACTIVATION FR0 DUCTS
'NDT INCLUDING ALPHA. H-3 1 SASES 'LLD (LLD (LLD (LLD AB-!!2M (LLD (LLD (LLD (LLD CE-144 (LLD (LLD (LLD (LLD CC-52 (LLD (LLD (LLD (LLD CD-68 (LLD <;LLD (LLD - <LLD CS-1;4 f.BBE+00 B.taE+00 B.BOE+00 0.22E+0B CS-137 2.27E-05 2.95E-05 5.5?E-06 6.37E-25 1-1;;
(LLD (LLD (LLD (LLD SR-90 4 3.15E-85 3.35E-85 5.BIE-06 7.08E-05 10TAL 6.81E-85 6.38E-05 1.13E-65 1.34E-84 1
H-3 2.6BE-85 B.25E-86 8.82E-B5 1.22E-04
. TFE VAL'ES 'Ef 0FTE~ IhCL:.'E s IMa ACTIV iV JD AN( ACTIVITY SS, 5FECIFICALLY IDENTIFIED. TH:JS. THE TEFDRTEL EMD VALUE FEFRE!!NTS A 'M5ERVAi!VE EETIMAir :1.E. OVERESTIMATE) AND CONTAINS ACTIVITY
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ATTACHMENT 2-TMI.2'QUARTERt.Y DOSE ASSESSMENT REPORT 4410 89-0026 FOURTH QUARTER 1988 Page 4 of 4
- JNIT 2 6ASE005 RADIONUCLIDES RELEASES BY ISOTOPE (Cil RADIONUCLlDE- OCfDBER NOVEMBER DECEMBER 4TH QUARTER 1988
$33333333333333333333333333333333333333333333333333333333333333333333333333333333333&s333333333333333333333333333333333333 x
" v FISSION AND ACTIVATION 6ASEE KR-85 7.51E-82 (LLD <LLD
. 7.51E-82 TOTAL PARTICULATE (HALF-LIVES >B DAYS)
UNIDENTIFIED BETA /6AMMA 5.66E-86 1.66E-86 2.18E-05 2.84E-85
. CS-137 (LLD 1.36E-87 9.45E-06 9.5BE-96 CS-134 (LLO (LLD (LLD' (LLD SR/Y-90 (LLD (LLD 4.3BE-fB 4.3BE-IB BROSS ALPHA 3.45E-99 (LLD (LLD 3.45E-89 TOTAL llNCLUDIN6 ALPHA) 5.67E-86 1.BOE-86 3.85E-85 3.88E-95 TOTAL (MINUS ALPHA) 5.66E-86 1.88E-86 3.85E-B5 3.00E-85 TRIT!UM (H-3) 1.IBE+88 1.!BE400 1.30E+88 3.56E+86 l
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THI-2 QUARTERLY DOSE ASSESSMENT REPORT ATTACHMENT 4-FOURTH QUARTER 1988 4410 L-0026 Page 1 of 2
! INTERPRETATION OF DOSE
SUMMARY
TABLE' The Dose Sumary Table presents the maximum hypothetical doses to an individual and the general population resulting from the release of gaseous and liquid effluents from THI-2 during the fourth quarter reporting period of 1988.
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 recommended in Regulatory Guide 1.109. The pathways considered for TMI-2 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, 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 maximum whole body dose and affected age group along with the organ and associated age group that received the largest dose.
For tne fourth quarter of 1988 the calculated maximum whole body dose received by anyone would have been 9.9E-4 mrem to an adult. Similarly, the maximum organ dose would have been 2.0E-3 mrem to the bone of an adult.
- 8. Gaseous (Individual)
There ere seven majer 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.
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 1988, the noble gas individual doses are from krypton-85 releases as a result of plasma arc cutting in the reactor vessel. The calculated maximum wnole body dose to an individual would have been 2.8E-7 mrem. The calculated maximum dose to the skin would have been 3.3E-5 mrem.
a
Tfil-2 QUARTERLY DOSE ASSESSMENT. REPORT ATTACHMENT 4 FOURTH QUARTER 1988 4410-89-L-0026 Page 2 of 2 The Iodines and Particulate section described in line 7 represents the
' maximum exposed organ due to iodine and particulate. This does not include any plume exposure which is separated out by lines 5 and 6. The doses presented ir. this section !;ain reflect the maximum exposed organ for the appropriate age group.
The fourth quarter 1988 iodine:; and particulate would have resulted in a-maximum dose of 2.3E-3 mrem to the bone of a child residing 700 meters from the site in the E 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 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 0.028 person-rem.
The maximum critical ergan population dose to the bone was 0.11 person rem. Gaseous effluents resulted in a whole body population dose of 0.013 person-rem. Maximum organ population dcse to the bone, thyroid, lung, kidney, liver and GI was 0.011 person rem.
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' ATTACHf1ENT 5 TMI-2 SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 4410-89-t-0026 THIRD AND FOURTH QUARTERS 1988 Page 1 of 11 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT l July 1, 1988 to December 31, 1988 l
SUPPLEMENTAL INFORMATION 1
FACILITY TMI Unit-2 (Including Epicor-II) LICENSEE DPR-73-320 )
- 1. Regulatory Limits
- s. Fission and activation gases. i
- c. cu ates, half-lives > 8 days: " " Tech Specs,
- d. Liquid effluents: g *f3
- 2. Maximum Permissible Concentrations Provide the MPCs used in determining allowable release rates or concentrations.
a, Fission and activation gases:
- c. r cu ates, half-lives 8 days: 10 CFR, Part 20, Appendix B
- d. Liquid effluents:
- 3. Average Energy Provide the average energy (E) of the radionuclides mixture in releases of fission and activation gases, if applicable 0.253 Mev (Kr-85)
- 4. Measurements and Approximations of Total Radioactivity Provide the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclides composition.
- a. Fission and activation gases:
- b. Iodines: Ge (Li) Spectrometry, Liquid Scintillation
- c. Ge (Li) Spectrometry Particulate: Ge (Li) Spectrometry, Gas Flow Proportional
- d. Liquid effluents:
. Ge (Li) Spectrometry, Liquid Scintillation
- 5. Batch Releases Provide the following information relating to batch releases of radioactive materials in liquid and gaseous effluents.
A. 1988 1988 Liquid 3rd Quarter 4th Quar.ter
- 1. Number of batch releases:
- 2. 90 37 Total time period for batch release:
- 3. N/A N/A Maximum time period for a batch release:
- 4. N/A N/A
- 5. Average time period for batch releases: N/A N/A Minimum time period for a batch release:
- 6. N/A N/A Average stream flow during periods of release of effluent into flowing stream: N/A N/A N/A = not applicable
_ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ -w
- ATTACHMENT 5 TMI-2 SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 4410-89-L-0026 THIRD AND FOURTH QUARTERS 1988 Page 2 o'f 11 ,
- 5. Batch Releases (cont.)
B. Gaseous 1988 1988 3rd Quarter 4th Quarter
- 1. Number of batch releases: 0 0
- 2. Total time period for batch releases: N/A N/A
- 3. Maximum time period for a batch release: N/A N/A
- 4. Average time period for batch release: N/A N/A
- 5. Minimum time period for a batch release:
N/A N/A
- 6. Abnormal Releases A. Liquid
- 1. Number of releases:
- 2. None None Total activity released: N/A N/A B. Caseous
- 1. Number of releases: None None
- 2. Total activity released:
N/A N/A
- ATTACHENT 5 -
THI52 $EMI-ANNUAL RADI0ACTIlfE EFFLUENT RELEASE REPORT .
0- -0026 TH1RD' AND FOURTH QUARTERS 1988
ABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANN'JAL REPORT SASEDUS EFFLUENTS-SUMMATICN OF ALL RELEASES 1988 1988 EST. TOTAL UNITS 3RD GUARTER 4TH GUARTER ERROR 1-12322211233 EEEEEEESEES: 333322232 33 - EEEEEE323
' A. FISS10N AND ACTIVATION 6ASEE 1.~ TOTAL RELEASE Ci 3.65E-61 7.51E-82 +/- 681
- 2. AVERABE RELEASE F. ATE FOR PER100 uCi/sec 4.59E-82 '9.45E-83
- 3. PERCENT OF TECH SPEC LIMIT 1 6.3BE-84 1.31E-84 TECH SPEC LIMIT =
7.2 E+3 utilsec FOR tR-85
- B. 10 DINES
- 2. AVERAGE RELEASE RATE FOR PERIOD uC;/sec N/A N/A
- 3. PERCENT OF TECH SPEC LIMIT I N/A- N/A TECH SPEC LIMIT =.
2.4 E-2 utilsec C.FARVICULATES
- 1. PARTICULATE N11H ifALF-LIVES
')BDAYS Ci 1.57E-85 3.EBE-85 +/-.681
- 2. AVERASE RELEASE RATE FOR PERIOD uti/sec 1.97E-86 4.7BE-86
- 3. FERCENT OF TECH SPEC Linli I B.21E-83 1.99E-82 TECH SPEC LIMIT z
- 4. 6ROSS ALPHA RADIOACTIVITY C1 1.44E-OB 3.45E-29 2.4 E-2 utilsec D. TRIV!UM .
- 1. TOTAL RELEASE. Ci 3.3BE408 3.56E+B8 +/- 681
- 2. AVERASE RELEASE FATE FOR PERIOD utilsec 4.26E-El 4.4BC-21
- 3. FERCENT OF TECH SPEC LIMli I B.87E-23 ' 9.32E-83 TECH SPEC LIMIT a
- 4.B E+3 uCi/ set FOR H-3
[ _ _ _ . _ _ ___ - -_-_- - _-_ - - -
ATTACHME?lT 5 j
- TMI-2 SEMI-ANNUAL RADI0ACTlVE EFFLUENT RELEASE REPOR1 4410-89-L-0026 THIRD AND FOURTH QUARTERS 1988 Page 4 of 11 k
'ABLE IB d i
EFFLUENT AND WASTE DISF05AL SEMIANNUAL REPORT GASECUS EFFLUENTS-6RDUND LE'v'EL RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES 19BB 1988 19E8 1928 RELEASED UNIT 3RD GUARTER 4TH QUARTER 3RD QUARTER 23211 Z3333 4TH QUARTER 33 2 1:32 E3213233333 32 32333:3: 332==2223E23 22:333:223:2
- 1. FISSIDW BASES KRYPTON-85 Ci 3.65E-al 7.51E-82 <LLD (LLD rRYPTON-85M C1 (LLD (LLD (LLD (LLD KRYPTON-87 Ci (LLD (LLD <LLD (LLD rRYPTON-BB C1 (LLD l
(LLD (LLD (LLD IENON-133 Ci (LLD (LLD (LLD (LLD IENON-!!5 Ci (LLC (LLD (LLD (LLD IEN3N-135M C1 (LLD (LLD (LLD (LLD
-IEN0N-136 C1 (LLD (LLD (LLD (LLD OTHERS (SFECIFY) C1 (LLD (LLD (LLD (LLD C1 C1 C1 Ci UNIDENTIFIED Ci (LLD (LLD (LLD 4.LLD TOTAL FOR PERluD Ci 3.65E-81 7.51E-02 N/A N/A
!0 DINE-135 Ci (LLD (LLD (LLD (LLD TOTAL FOR PERIOD Ci N/A h/A N/A N/A
- 3. ARTICULATES ST60NT!UM-89 Ci (LLD (LLD N/A N/A STRONTIUM-98 Ci 1.9 E-EE 4.3BE-2B N/A N/A CESluft-134 Ci (LLD (LLD N/A N/A CESIUM-137 Ci 2.7hE-tB 9.5BE-26 N/A N/A BARIUM-LANTHANUM-148 Cf (LLD (LLD N/A N/A OTHERS (SFECIFY)
UN!!ENTIFIED Ci 1.56E-t5 2.54E-25 N/A N/A
-__ - - _ _ _ _ - - _ - - - - - _ _ _ - - ~
L ATTACHMENT 5 l TM1-2 SENI-ANNUAL RADI0ACT!VE EFFLUENT RELEASE REPORT 4410-89-t-0026 THIRD AND FOURTH QUARTERS 1988 Page 5 of 11 TABLE 2A EFFLUENT A 9 WASTE DISPOSAL SEMIANNUAL REPORT L:0UID EFFLUENTS-SUMMATION OF ALL RELEASES 1968 1988 EST. iGTAL UNITS 3RD DUARTEE 4TH QUARTER ERRDR %
23E233333 EEEEEEEEEEE EEEEEEEEEEE EEEEEEEEEE A. FISSION AND ACTIVATION FRODUCTE
- 1. TOTAL RELEASES (NOT INCLUDING Ci 2.10E-84 1.34E-84 +/- 60%
TRITIUM.6ASES. ALPHA)
- 2. AVERABE DILUTED CONCENTRATION uti/s] 1.39E-11 9.4;E-12 DURINS FER10D
- 1. PEECENT 0F AFFLICABLE LIMIT 1 6.97E-25 4.72E-25 B. TRIT!U't
- 1. TOTAL RELEASE Ci 1.1BE-83 1.22E-f4 +/- 6BI BASED ON 3E-3
- 2. AVERAGE DILUTED CDNCENTEATION uC1/ml 7.29E-11 DURINS FERIOD 8.59E-12 uti/al (H-3)
- 3. FERCENT OF AFFLICABLE LIMIT 1 2.43E-86 2.B6E-97 C. DISSDLVED AND ENTRAINED BASES
- 1. TOTAL RELEASE Cl N/A N/A +/- 68%
- 2. AVEEASE DILUTED CONCENTRAT!0h uCi/al N/A N/A DURING FERIDD
- 3. PERCENT OF AFFLICABLE LIMIT I N/A N/A D. BROSS ALFHA ACTIYlTY
+/- 251 E. UDLUME OF WASTE EELEASED liters 2.blE+05 9.80E+24 +/- 251 (FRIOR TO DILUTION)
F. VOLUME OF DILUT10N WATER USED liters 1.51E+18 1.43E419 +/- 12%
__ _- _ - - - -. _-_.- _ _ _ - - - _ - - - - - . - ~ _ - -
- _ ~ -- - _-
r >
7 .
c .
-ATTACHMENT 5' THI-2 SEMI-AN'NUAL RA'DI0 ACTIVE EFFLUENT RELEASE REPORT 4'- '
~ THIRD'AND FOURTH' QUARTERS 1988 4410-89-L-0026 -
Page- 6 of 11 l-
?ABLE P EFFLUENT AND NASTE DISPDSAL SEMIANNUAL PIPORT
-LIQUID EFFLUENTS CONTINUOUS MDDE BATCH MODE -
NUCLIDES 1982 !
198B 1988 19BB RELEASED- UNIT 7EDQUARTER 4TH QUARTER 3RD QUARTER : 4TH GUARTER
.83323E13333885 33F223332 53333321*** E28223232 5 EzzEstEstzz 3E23 233:33 STRDNTIUM-89 Cl (LLD (LLD 4
STRONT!UM-98 Ci $
1.17E-94 7.BBE-85
' CESIUM-134 C1 -
NO CONTINUGUS MODE RELEASES (LLD (LLD -
IN THE 3RD OR 4TH QUARTERS
~CES!UM-137 Ci 9.3BE-B5 6.37E-85 T 10 DINE-131 - Ci (LLD (LLD CDEALT-58 Ci (LLD .LLD e >
COBALT-62 Ci (LLD (LLD IRON-591 Ci (LLD (LLD 21NC-65 C1 (LLD (LLD MANAGANEEE-54 Ci (LLD (LLD '
~IIRCONIUM-N!DEIUM-95 Ci I (LLD (LLD MDLYBDENUM-99 Ci (LLD (LLD TECHNEilUM-99M >
'lBARIUM-LANTHANUM-148' C1 (LLI (LLD CERIUMl !41 Ci
<LLD
. (LLD ,
DTHER(SPECIFY) Ci UNIDENTIFIED Ci (LLD (LLD TOTALFORPER10t* Ci 2.!BE-88 1.34E-t4 s
IENGN-l!3 Ci
' U.D
<LLD
'IENON-!!! C1-(LLE<, (LLD 8 _ _ _ - _ - _ _ - _ _ _ _ _ _ _ _
. .TMI-2 SEMI-ANNUAL RADI0ACTfVE EFFLUENT RELEASE REPORT ATTACHMENT 5 THIRD AND FOURTH QUARTERS 1988 4410-89-L-0029
,- Page 7 of 11 TABLE 3A EFFLLTNT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIP.E TS TMI-2 July 1, 1988 through December 31, 1988 A. Solid vaste shipped off-site for burial or disposal (not irradiated fuel) i
- 1. Type of vaste UNIT 6m jh T,0TAL 3e E{
- a. Spent resins,111ter sludges, m' 85.95m3 evaporator bottoms, etc. h003,3Ci 5%
Ci
- b. Dry compressible waste, contaminated a3 469.3m3 eculement, etc. 5%
c4 138 C1.
- c. Irradiatec components, control m' rod s . e t c. N/A N/A Ci
- d. Other (describe) i U/A N/A
- 2. Est', mate of major nuclide composition (bv type of waste)
- a. cs137 46.9 %
Sr90 41.2 y Pml47 , o.b2 g Cs134 .626 %
- b. Sr90 c2.0 ,
Os197 14.0 h Pm147
.643 %
Pu?h2 .349 %
Cs13h .2c7 %
C-
. *?
I
, e d.
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination n) Fee Attnrhed Sheet For This Information b) See Attached Sheet For This Informati'on u
B. Irradiated Fuel Shipments (Disposition)
Number of Shipments Mode of Transportation Destination 12 Shipments Rail Cask (NuPac 125b) INEL-Scoville, !dano I
J3[f TMI-2 SENI-ANNUAL RADI0 ACTIVE' EFFLUENT RELEASE REPORT THIRD AND FOURTH QUARTERS 1988-jffAC, 1E 9- J -O 26 '
Page 8'of 11 TMI-2 EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT'-
07/01/88 Through 12/31/88 f
WASTE SHIPPED AS FOLLOWS:
TABLE 1.a:
Eleven (11) - 246 Gallon Poly High Integrity Containers 8 36.5 Ft.* Each
- Five-(5) - SDS Vessels (14.01 Ft." Each) Overpacked in LSA Boxes Five (5) - CNSI 8-120 Liners 6 125.2 Ft.* Each Ten (10) - RADLOK 200 High Integrity Containers # 73.4 Ft." Each-Five (5) - Steel Liners 9 170 Ft.* ~ Each Four (4) - EA-50 High Integrity Containers S 49.9 Ft.* Each Four (4) - Medium Poly High Integrity Containers 9 38.3 Ft.* Each TABLE 1.b:
One Hundred Three (103) - Steel Drums 6 7.5 Ft.* Each Two (2) Steel Boxes 6 98 Ft.8 Each one (1) Medium Poly High Integrity container S 38.3 Ft.* Each Five (5) EA-50 High Integrity Container 9 49.9 Ft.* Each One (1) EA-190 High Integrity Container 9 175 Ft.*
- 0ne Hundred Sixty-One (161) - Steel Boxes S 92 Ft.* Each
- 0ne (1) Steel Box 8 63 Ft."
- 0ne (1) Steel Box 6 44 Ft."
- Material Sent to Waste Processor for Volume Reduction
- f. ATTACHMENT S l
- THI-2 SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 4410-89-L-0026 THIRD AND FOURTH QUARTERS 1988' Page 9 of 11 TMI-2 EFFLUENT fr. WASTE DISPOSAL SEMI-ANNUAL REPORT 07/01/88 Through 12/31/88 Table A.3.a No. of Shipments Mode of Transportation Destination 16 Tractor-Cask (CNSI 8-120B) 'Barnwell, SC-10 Tractor-Cask (HN-200) Barnwell, SC 4 Tractor-Cask (HN-200) Hanford-Richland. WA 4 Tractor-Cask (NuPac 14/190M) Hanford-Richland, WA 1 Tractor-Cask (CNSI 21-300) Barnwell, SC 1 Tractor-closed Van Hanford-Richland, WA 1 Tractor-Closed Van Barnwell, SC Table A.3,b No. of Shipments Mode of Transportation Destination 3 Tractor-Cask (HN-200) Hanford-Richland. WA 2 Tractor-Cask (HN-200). Barnwell, SC 1 Tractor-Cask (NuPac 14/190M) Hanford-Richland, WA 1 Tractor-Cask (CNSI 21-300) Barnwell, SC 2 Tractor-Closed Van Hanford-Richland, WA 1 Tractor-Closed Van Barnwell, SC
- 7 Tractor-Flatbed Scientific Ecology Group Oak Ridge, TN
- Material Sent to Waste Processor for Volume Reduction
ATTACHMENT 5 TMI-2 SEMT-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 4410-89-L-0026 THfRD AND FOURTH QUARTERS 1988 Page 10 of 11 l
TYPICAL GASEOUS EFFLUENT LLD (lower Limit of Detection) VALUES ASSUMPTIONS: Sample volume (Marinelli) 1640cc )
Sample volume (Particulate & Charcoal Filters) 5.7E8cc Sampling Rate Sampling Time 2 cfm or 5.66E4cc/ min k 1 week or 1E4 min j Sample volume (tritium bubbled thru water) 7.56E5cc Sampling Rate l Sampling Time 75cc/ min 1 1E4 min Sample Counting Time: a & H-3 =20 min; $ =10 min; 7 =1000sec Sample Counters: y emitters 25% Ge(Li) a or S Proportional Counter H-3 Liquid Scintillation Counter ISOTOPE Ci/cc LLD NOTES Gross Alpha a 1 E-15 Gross Beta #
Particulate Filter Paper 1 E-14 "
Tritium H-3 1E-10 Air bubbled thru water by a fritted disc or Fisher Milligan
, gas washer Krypton-85 Kr-85 SE-6 Krypton-85m Kr-85m Marinelli 2E-8 "
Krypton-87 Kr-87 6E-8 "
Krypton-88 Kr-88 SE-8 "
Xenon-133 Xe-133 4E-8 "
Xenon-133m Xe-133m 1E-7 "
Xenon-135 Xe-135 2E-8 "
Xenon-135m Xe-135m 3E-7 "
Xenon-138 Xe-138 3E-7
- Iodine-131 1-131 2E-8 "
Iodine-133 I-133 3E-8 "
Iodine-135 I-135 2E-7 " ;
l Iodine-131 1-;31 3E-14 Iodine-133 1-133 4E-14 Charcoal "
Filter Iodine-135 I-135 3E-13 " '
Manganese-54 Mn-54 3E-14
-Iron-59 Fe-59 8E-14 Particulate filter Paper "
Cobalt-59 Co-58 3E-14 "
Zinc-65 Zn-65 9E-14 "
Strontium-89 Sr-89 2E-14 "
l Molybdenum-99 Mo-99 2E-14 " ,
Ruthenium-103 Ru-103 2E-14 "
Silver-110m Ag-110m 3E-14 "
i Cesium-134 Cs-134 4E-14 "
Cerium-141 Ce-141 3E-14 "
Cerium-144 Ce-144 9E-14 "
[ ._ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - _ - - - - - - - - - - -
7________________
y ..
~ * " ' ' ," TMI-2 SCMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
- ATTACHMENT 5
. THIRD AND FOURTH QUARTERS 1988 4410-89-L-0026 Page 11 of 11 l
4
~
TYPICAL L10UID EFFLUEWT LLD flower Limit of Detection) VALUES ASSUMPTIONS: Sample volume = 1 liter = 1000 cc sample counting time = 1000 see Sample counted with a 25% Ge(L1) for Gamma Emitters ISOTOPE uti/cc LLD ggt [1 Gross Alpha a 4E-9 Gross Beta Counted with proportional counter
- 7E-8 Counted with proportional counter Tritium H-3 4E-6 Counted with liquid scintillation counter Krypton-85 Kr-85 1 E-4 Xenon-131m Xe-131m 2E-5 Xenon-133 Xe-133 1E-6 Xenon-135 Xe-135 3E-7 Chromium-51 Cr-151 3E-6 Manganese-54 Mn-54 4E-7 Cobalt-58 Co-58 4E-7 Iron-59 Fe-59 9E-7 Cobalt-60 Co-60 6E-7 Zinc-65 2n-65 1E-6 21rconium-95 Zr-95 7E-7 Niobium-95 Nb-95 4E-7
' Molybdenum-99 Mo-99 3E-7 Technetium-99m Tc-99m 3E-7 rSilver-110m Ag-110m 6E-7 Antimony-125 Sb-125 9E-7 Cesium-134 ' Cs-134 SE-7 1
-Cesium-136 Cs-136 4E-7 Cesium-137 Cs-137 SE-7 Ba rium-140 Ba-140 1E-6 Lantha nun =.-140 La-140 7E-7' Ce rium-141 Cc-141 SE-7 l Cerium-144 Ce-144 3E-6 Iodine-131 1-131 3E-7 lodine-133 1-133 4E-7 Phosphorus-32 P-32 1E-6 Iron-35 Fe-55 These LLD values for liquid 5E-8 sample analyses of gross alpha, Strontium *89 Sr-89 SE-8 Strontium-90 P-32, Fe-55, Sr-89, and Sr-90 Sr-90 SE-8 i Gross Alpha 1E-1 are the same as Unit 1 which are of f site vendor LLD values.
l
-ATTACHliENT 6
~Tt11-2 RESIDENCE CENSUS FOR 1988 4410-89-L-0026 Page 1 of I
?
TMI-2 Residence Census for 1988 i
i.
Sector. Existing MIDAS (m) New Distance (m)
N 1,000 1,830 ME 1,130 1,160 NE 900 850 ENE 750 750 E 700 700 ESE 750 1,230 SE 1,150 1 ,71 0 SSE 1,200 1,260-S 3,630 3,660.
SSW 1,300 ~ 1,N Sy 900 870 ySy 1,150 780 y 600 560 gg 700 580 g 750 650 Ng 850 1,070 The methodology used was aerial photos confirmed by ground surveys.
l
l GPU Nuclear Corporation Jd Nuclear ::,omg==
Middiatown, Pent sylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number: 1 (717) 948-8461
!- Marcn 1, 1989 4410-89-L-0026/OO80P j US Nuclear Regulatory Commission l
ATTN: Document Control Desk Washington, DC 20555
Dear Sirs:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 Quarterly Dose Assessment Report - Fourth Quarter .1988 Semi-Annual Radioactive Effluent Release Report Per 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 su : nary of TMI-2 effluents and doses reported in Attachments 2 and 3. Attachment 2 presents a summary of releases including estimates of total activity and the time rate of release of each nuclide.
Attachment 3 is a Dose Summary Table which provides a summary of the maximum hypothetical doses to individuals and the general population resulting from TMI-2 activities for the Fourth Quarter 1988 and the entire year c71988.
Attachment 4 is an interpretation of the Dose Summary Table for the Fourth Quarter 1988. Doses were developed from calculational models and represent the bounding dose for all cases.
Attachment 5, in accordance with the requirements of 10 CFR 50.36(a)(2), is the Radioactive Erfluent Release Report for TMI-2 for the Third and Fourth Quarters of 1988. Table 18, " Effluent and Waste Disposal Semi-Annual Report, Gaseous Effluent-Elevated Releases," is not included as release paths at TMI-2 do not meet the Regulatory Guide 1.109 definition of an elevated release and are considered ground level releases. 4 Dose summaries and effluent releases for the previous cuarters of the 1988 l calendar year were submitted via GPU Nuclear letters 4410-88-L-0089, dated l l
May 27, 1988; 4410-88-L-0142, dated August 29, 1988; 4410-88-L-0184, dated November 29, 1988; and 4410-89-L-0022 (update), dated February 22, 1989.
l GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
i .
.t .
... Document Control Desk March 1 , 1989 4410-89-L-0026 i
Attachment 6 is a table listing the resulta of the first annual residence survey in accordance with Appendix B of the TMI-2 Recovery Technical Specifications,-Section 3.2.2.
Sincerely,
- 3. h.
M. B. Roche Director, TMI-2 EDS/ emf Attachments cc: D. M. Johnson - Acting Senior Resident Inspector, TMI W. T. Russell - Regional Administrator, Region I J. F. Stolz - Director, Plant Directorate I-4 l L. H. Thonus - Project Manager, TMI Site 4
_ .__ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ -