ML20033E315

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Forwards TMI-1 Effluent & Offsite Dose Rept for Jul-Dec 1989. No Unplanned Releases Occurred During Reporting Period.No Changes to Process Control Program & ODCM
ML20033E315
Person / Time
Site: Crane Constellation icon.png
Issue date: 03/01/1990
From: Hukill H
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20033E316 List:
References
C311-90-2013, NUDOCS 9003120270
Download: ML20033E315 (2)
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{{#Wiki_filter:- .; y ,+ Nuolear ?:su m :~z ~ Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct D'at Number: March 1,1990 C311-90-2013 US Nuclear Regulatory Commission Attnt-Document Control Desk ' Washington, DC 20555 t

Dear Sir:

7hree Mile Nuclear Station Unit 1 (TMI-1) Operating License No. DPR-50 Docket No. 50-289 Second Half - 1989 Semi Annual Effluent and Release Report Enclosed is the THI-1 Semi Ann,ual Effluent and Release Report for the period ' July 1, 1989 through December 31, 1989. This report includes an Executive Summary of the Effluent Release Report, the Disposal and Effluent Release Data, and an assessment of the radiation doses due to liquid and gaseous effluents released from the Unit during the reporting period. .TMI Techriical-Specification Sections 6.9.4.2.1 and 6.9.4.2.2 require reporting "of affluent data and solid waste shipment data in accordance with Reg. Guide 1.21 for the semi-annual' report period. These tables'are attached including summaries of solid waste shipments and liquid and gaseous effluents for..the reporting period. TMI-Technical Specification Section 6.9.4.2.3 requires a summary of unplanned releases from the site to unrestricted areas. During this report period, there , ere no unplanned releases. w TMI Technical Specification'Section 6.9.4.2.4 also requires that changes to the Process Control Program (PCP) and Offsite Dose Calculation Manual (ODCM) be e . reported.. There were no changes to either of these. programs. This section also requires "a listing of new locations for dose calculations and/or monitoring identified by the land use census pursuant to Specification 3.23.2." There were no new locations during this semi-annual period.- 9003120270 $ PDR ADOCK 05 Ov289 'R PDC GPU Nuclear Corporation is a subsidiary of the Ger eral Public Utilities Corporation 'le. W

t C3'11-90*2013 March 1, 1990 t TMI Technical Specification Section 6.9.4.2.5 requires reporting of i instrumentation not returned to OPERABLE status within 30 days per Section 3.21.1.b and 3.21.2.b. All instrumentation under this Tech. Spec. section was returned to OPERABLE service within 30 days. TMI Technical Specification Section 6.9.4.3.1 requires an annual summary of hourly meteorological data collected over the previous year. This data is i contained in the attached Joint Frcquency Tables. In accordance with Technical Specification Section 5.9.4.3.2, this report includes an annual summation table and a semi-annual table showing the assessment of the radiation doses due to liquid and gaseous affluents released from the Unit during 1989. Technical Specification Section 6.9.4.3.3 also requires in part that annually this same report shall include "an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the site boundary (Figures 5-3 and 5-4) during the report period." Since the public does not have unrestricted access to TMI-1, no assessment of this dose is applicable. TMI Technical Specification Section 6.9.4.3.4 requires an annual assessment of radiation dose to the most likely exposed real individual from reactor releases and other nearby uranium fuel cycle sources (TMI Unit 2) to show compliance with 40 CFR 190 " Environmental Radiation Protection Standards for Nuclear Power Operations." The annual dose to the maximum exposed individual from effluents for comparison to 40 CFR 190, would be no greater than 0.53 mrem to the thyroid. This sums doses from Unit I and Unit 2 and includes the maximum dose regardless of age group for different pathways. It is further estimated based on the maximum average fenceline dose rate for the year of 25.5 mrem above background per standard month, a person residing at the fenceline for the duration specified in RG 1.109 for shoreline exposura, would receive no more than 2.3 mrem direct dose, for a maximum potential total dose of 2.8 mram for both units. Sincerely, f .q-i .D.Hbill Vice President & Director, THI-1 HDH/DVH/spb 2013 cc T. Martin R. Hernan F. Young Enclosures +

l '1 5 EXECUTIVE

SUMMARY

Three Mile Island Nuclear Station Unit 1 Ef fluent and Offsite Dose Report i for the Period of July 1,1989 to December 31, 1989 { t This report sumarizes the radioactive liquid and gaseous releases (effluents) from Three Mile Island Unit 1 and the calculated maximum hypothetical radiation exposure to the public resulting from these releases. This report covers the period of operation from July 1 to December 31, 1989. Radiological' releases from the plant are monitored by installed plant monitors sempling the plant stacksfor gaseous releases and liquid monitors for i discharges to the Susquehanna stver. These monitors and sample analyses provide a means for accurate detemination 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 radioactise 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 i to liquid releases. Actual or "real-time" meteorological data from an onsite tower is used to detemine the doses resulting from gaseous releases from the l plant. The use of real-time meteorological infomation pemits the l. detemination of both the direction in which the release traveled and the dispersion of radioactive material in the environment. i 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 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 i. l' of water and fish withdrawn from the Susquehanna River downstream of the plant is also calculated. Dose calculations for liquid and gaseous effluents are perfomed using a mathematical model which is based on the methods defined by the U. S. Nuclear j. Regulatory Corission. The maximum hypothetical doses are conservative overestimates of the actual offsite doses which 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 l and consumption. 1 I

1.iquid discharges made during the reporting period July 1 to December t 31, 1989 consisted of 216 curies of tritium, 0.24 curies of noble gases (predominantly Xe-133), and 0.012 curies of other beta and gamma emitters, predominantly I Co-58. The quantities of effluents are similar to average semi-annual releases from previous Unit 1 operations. During the reporting period July 1 to December 31, 1989, the maximum hypothetical calculated whole body dose to an individual due to liquio effluents from Three Mile Island Unit I was 0.021 mrem. The maximum hypothetical calculated dose to any organ of an individual wss 0.028 mrem to the liver. Airborne discharges made during this same time period consisted of 3.0 curies of tritium,1676 curies of noble gases, and 0.016 curies of fodines and particulates. These releases are similar to semi-annual ecleases from .t previous Unit 1 operation, since the 1985 restart. The maximum hypothetical calculated dose to any individual from noble gases was 0.054 mrem to the skin and 0.025 mrom to the whole body. Airborne iodine and particulates are calculated to produce 0.29 mrem to the thyroid of the maximum hypothetical individual. The total maximum hypothetical whole body dose of 0.047 mrem, received by any individual from effluents from TMI-1 for the reporting period is 1000 times lower than the doses the average individual in the area of TMI-1 receives from natural background during the same time period. about 50 mrem whole body semi-annually in the TMI-1 area. Natural background avera In addition, average equivalent dose to the total body from natural radon for the same period is about 100 mrem. The calculated total whole body population dose from all plant releases is 3.3 person-rem. This is 33,000 times lower than the dose attributed to natural background radiation for the reporting period. The doses which could be received by the maximum hypothetical individual are each less than 4% of the annual limits established by the Nuclear Regulatory Comission in Appendix I of 10 CFR 50. 1

l EFFLUENT & WASTE DISPOAL SEMIANNUAL REPORT ~ SUPPLEMENTAL INFORMATION FACILITY: TMI UNIT 1 LICENSE: DPR 50-289 i 1. . REGULATORY LIMITS - - - REFER TO TMI UNIT 1 TECENICAL SPECIFICATIONS A. FISSION AND ACTIVATION GASES B. 20 DINES 8 C. PARTICULATES, EALF-LIVES > S DAYS D. LIQUID EFFLUENTS: 2. MAXIMUM PBRMISSIBLE CONCENTRATIONS - - - 10 CFR 20, APPENDIE B TABLE II PROVIDE TEE MPCS USED IN DETERMINING ALLOWABLE RELEASE q i RATES OR CONCENTRATIONS. A. FISSION AND ACTIVATION GASES: B. 20 DINES: C. PARTICULATES, EALF-LIVES > S DAYSt D. LIQUID EFFLUENTS L 3. AVERAGE ENERGY PROVIDE TEE AVERAGE ENERGY-(E-BAR) 0F TER RADIONUCLIDE MIETURE IN RELEASES OF FISSION AND ACTIVATION GASES, IF APPLICABLE E-BAR BET &m R.19E-01;E-BAR GAMMAz 2.343-01;E-BAR BETA AND GAMMA = 4.53E-01 -4. MEASUREMENTG AND APPROEIMATIONS OF TOTAL RADICACTIVITY-PROVIDE TRE.METRODS USED TO MEASURE OR APPROEIMATE TEE TOTAL RADICACTIVITY IN. EFFLUENTS:AND TEE METHODC USED TO DETERMINE RADIONUCLIDE COMPOSITION: I' A. FISSION AND ACTIVATION GASES EpGe SPECTROMETRY, LIQUID SCINTILLATION l B. 10 DINES Epce SPECTROMETRY C. PARTICULATES-EpGe SPECTROMETRY, GAS FLOW PROPORTIONAL, 5 i BETA SPECTROMETRY D. LIQUID EFFLUENTS EpGe SPECTROMETRY, LIQUID SCINTILLATION S. BATCE RELEASES PROVIDE TEE FOLLOWING INFORMATION RELATING TO BATCE RELEASES OF ' RADI0 ACTIVITY MATERIALS IN LIQUID AMD GASEOUS EFFLUENTS. A. LIQUID QUARTER 3 l QUARTER 4

1. NUMBER OF BATCE RELEASES 50 61 i

l

2. TOTAL TIME PERIOD FOR BATCE RELEASEst (MIN.)

16902. 20395. L

3. MARIMUM TIME PERIOD FOR A BATCE RELEASE (MIN.)

705. 915.

4. AVERAGE TIME PERIOD FOR BATCH RELEASEst (MIN.)

338. 334.

8. MINIMUM TIME PERIOD FOR A BATCE RELEASES (MIN.)

95. 218. F

6. AVERAGE STREAM FLOW DURING PERIODS OF RELEASE l

OF EFFLUENT INTO A FLOWING STREAM (CFM) 1.26E+06 1.31E+06 B.' GASEOUS-

1. NUMBER OF:BATCE RELEASESt 24 24
2. TOTAL TIME PERIOD FOR BATCE RELEASES:

(MIN.) 17154. 34077. L _3.L MAXIMUM TIME PERIOD FOR A BATCH RELEASE:' (MIN. ) 980. 10100. l '4. AVERAGE TIME PERIOD FOR' BATCH RELEASEst (MIN.) 715. 1420. S. MINIMUM TIME PERIOD FOR A BATCE RELEASE: (MIN.) 1. 1. ~ 6. ABNORMAL RELEASES I A. LIQUID

1. NUMBER OF RELEASES: 2. TOTAL ACTIVITY RELEASED (CURIES)

N/A N/A l B. GASEOUS l-

1. WUMBER OF RELEASES: 2.-TOTAL ACTIVITY RELEASED: (CURIES)

N/A N/A b -+%- y i-w- su %ew- -wg--eww-uw-+t-Ntev= T- 'te v e'

  • A's
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~. -. _ -. - -. -. _ f TABLE LA 1 ' EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1989) { GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES i UNIT QUARTER 3 QUARTER 4 EST TOTAL l ERROR A. FISSION AND ACTIVATION GASES t

1. TOTAL RELEASE l

CI 3.11E+02 1.35E+03 ............................l............l............l. 2. 5 0 E + 0l

2. AVG. RELEASE RATE FOR PERIOD UCI

......................../S 3.92E+01 1.70E+02

3. PERCENT OF TECE.

SPECIFICATION LIMIT E. 10 DINES

1. TOTAL IODINE L

I131 CI. 2.83E-03 2.50E-0 2.50E+01 ................................................3

2. AVG. RELEASE RATE FOR PERIOD.

UCI/S 3.54E-04 3.15E-0 ................................................4 L 3s PERCENT OF TECE. SPECIFICATION LIMIT i i C. PARTICULATES 1 I

1. PART. WITE RALF-LIVES > S DAYS CI

<1.003-04 2.18E-06 .................................................... 2.50E+01 i

2. AVG. RELEASE RATE 70R PERIOD UCI/S NA 2.743-07 i

3.c#ERCENT OF TECE. GP2CIFICATION LIMIT NA l .<t................................................

4. GROSS ALPEA BADI0 ACTIVITY CI

<1.00E <1.003-11 D. TRITIUM

1. TOTAL RELEASE l

CI 1.05E+00 2.00E+00 ............................l............l............l. 2. 5 0 E + 0

2. AVG. RELEASE RATE FOR PERIOD UCI/S 1.325-01 2.51E-0

..................................................1-..

3. PERCENT OF TECE.

SPECIFICATION LIMIT NOTE: ALL LESS TRAN VALUES (<) ARE IN uci/cc.

  • % TECE. SPEC. LIMITS LISTED ON DOSE

SUMMARY

TABLE. 1 1 'h z l:

TABLE 1C ' EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT (1989) GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINUOUS NODE ......................._................................. BATCH NODE NUCLIDES RELEASED UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 t

1. FISSION GAbd8 KR 85 l

CI 2.16E-02 8.01E-03 ...........................l............l............l.. 4. 0 0 E - 0 9.90E+00 KR SSN l CI 9.08E-01 7.083-0 .._........................l...........l.........1 l <5.00E-08 l 4.87E-0. KR-87 l CI 6.07E-01 4.44E-0 ...........................l............l.........1 l <4.00E-08 l 5.04E-06 KR 88 l CI 1.12E+00 1.11E+0 ...........................l...........l.........0 l <1.00E-07 l 3.06E-01 IE 133 l CI 9.07E+01 1.72E+02 ...........................l............l............l.. 2. 0 8 E + 1.13E+03 IE 135 l CI 5.43E+00 5.37E+00 ....... _...................l............l............l.. 3. 4 8 E - 0 1.48E+01 13 135N l CI 8.23E-01 1.093+00 ...........................l............l............l.. 5. 0 0 E - 0 7.73E-06 i 13 138 l CI 2.73E-01 4.41E-0 l ...........................l............l.........1 l <3.00E-07 l 4.39E-06 IE 133N l CI 3.92E-01 4.065- ...........................l............l........01 l 1.37E+00 l 9.71E+00 l IE 131M l CI <3.00E-07 <3.00E-07 ...........................l............l............l. 8. 3 4 E - 0 1 4.65E+00 kR 41 l CI <3.00E-07 <3.00E-07 ...........................l............l............l.. 3. 0 0 E - 7.69E-01 TOTAL FOR PERIOD l CI l 1.00E+02 1.82E+02 ......................................l............l. 2.11E+02 l 1.17E+03 l 2. IODINES I 131 l CI l 2.83E-03 2.48E-03 <1 .......................................l............l... 00E-08 l 2.17E-05 I 132 l CI <1.00E-10 <1.00E-10 <1 ...........................l.... _ _.......l............l... 0 0 E - 0 1.25E-06 l l_ I 133 l CI 5.09E-03 4.46E-03 ...........................l............l............l..1. 0 0 E - 0 8 1.46E-05 I 135 l CI 5.73E-04 <1.00E-10 ...........................l............l............l..1. 0 0 E - 1 0 TOTAL FOR PERIOD l CI 8.49E-03 6.943-03 ...........................l............l............l. 0. 0 0 E + 0 0 l 3.75E-05

3. PARTICULATES BR 89 l

CI <1.00E-11 <1.00E-11 ...........................l............l............l..1. 0 0 E - 0 8 SR 90 l CI <1.00E-11 <1.00E-11 ...........................l...........l...........l..1.00E-08 l <1.00E-08 CS 134 l CI <1.00E-11 <1.00E-11 ............ ___.........l............l..... _.....l..1.00E-08 l 1.01E-06 C8 137 l CI <1.00E-11 <1.00E-11 ...........................l............l............l..1. 0 0 E - 0 1.17E-06 NOTE: ALL LESS TRAN VALUES (<) ARE IN uCi/cc.

3 g l TABLE RA 'EPPLUENT AND WASTE DISPOSAL SENIANNUAL REPORT (1989) LIQUID EFFLUENT 8-SUBOl& TION OF ALL RELunEs UNIT QUARTER 3 QUARTER 4 EST TOTAL ERROR, % A. . FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (31.

TRIT.,GASE8, ALPRA) CI 2.44E-03 1.00E-02 2.50E ...........................................................+.01

2. AVG. DILUTED CONC. DURING PRD.

UCI/NL 2.233-10 8.453-10

3. PERCENT OF APPLICABLE LIMIT E.

TRITIUM

1. TOTAL RELEASE l

CI l 1.17E+02 9.84Ec01 ........................................l............l. 2.50E+01

2. AVG. DILUTED CONC. DURING.PRD.

UCI/NL 1.073-05 8.313-06

3. PERCENT OF APPLICABLE LIMIT C.

DISSOLVED AND ENTRAINED GASES

1. TOTAL RELRASE l

CI 1.873-02 1.983-01 ............................l............l............l. 2. 5 0 E + 0 1

2. AVG. DILUTED CONC. DURING PRD.

UCI/NL 1.71E-09 1.675-08 3. PERCENT OF APPLICABLE LIMIT D.'. GROS 8 ALPBA RADIOACTIVITY

1. TOTAL.RELRASE l

CI <1.00E-07 <1.005-07 ............................l............l............l. 2. 5 0 E + 0 1 E. VOL. OF WASTE RELEASED (No DIL.). LITER 8 1.07E+07 1.12E+07 9 00E+01 F. VOL. OF DILUTION UATER DURING PERIOD LITERS 1.09E+10 1.18E+10 ......................................................1.00E+01 NOTE: ALL LE8S TRAN VALUE8 (<) ARE IN uCi/cc.

  • % TECH. 8PEC. LIMIT 88 LISTED ON DO8E SUNNARY TABLE.

l j 4 l

1 i TABLE 2B ,CFFLUENT AND CASTE DISPOSAL SEMIAMNUAL REPORT (1989) LIQUID EFFLUENTS CONTI ....................................NUOUS MODE BATCH NODE i NUCLIDES RELEASED l UNIT QUARTER 3 ...........................l............l. Q. U ART E R 4 l QUARTER 3 QUARTER 4 ......................l........... SR 89 l CI <5.00E-08 <5. ...........................l............l.... 0 0 E - 0 8 l <5.00E-08 l 5.10E-05 SR 90 l CI <5.00E-04 <5. ...........................l............l... 00E-08 l <5.00E-08 l <5.00E-08 CS 134 l CI <5.00E-07 <5 ...........................l............l... 0 0 5 - 0 7 l 1.83E-04 l 2.25E-04 [ CS 137 l CI 9.20E-07 <5 ...........................l............l... 0 0 E - 0 7 l 3.38E-04 l 5.99E-04 ....................l.......l............l... 0 3 E - 0 4 l 1.38E-05 l 1.02E-03 I 131 CI <1 00E-06 2 ....................l.......l............l... 0 0 E - 0 7 l 1.57E-03 l 7.65E-03 CO 58 CI <5.00E-07 <5 ....................l.......l............l... 0 0 E - 0 7 l 2.36E-05 l 2.10E-05 CO 60 CI <$.00E-07 <5 EN 65 CI <5.00E-07 <5 ....................l.......l............l... 0 0 3 - 0 7 l <5.00E-07 l <5. NN 54 l CI <5.00E-07 <5 ...........................l............l... 0 0 E - 0 7 l <5.00E-07 l <5.00 ...................l.......l.. m.........l.. 5. 0 0 3 - 0 7 CR 51 CI <5.00E-07 l <5.00E-07 <5.00E-07 .....................l........... SR 95 CI <5.00E-07 ....................l.......l............l.. 5. 0 0 E - 0 7..........i..< l <5.00E-07 NB 95 l CI <5.00E-07 <5 ...........................l............l... 0 0 3 - 0 7 l <5.00E-07 <5.00E-07 ....................l........... NO 99 CI <5.00E-07 <5 ....................l.......l............l... 0 0 E - 0 7 l <5.00E-07 l 1.23E-04 FE 55 l CI <1.00E-06 ...........................l............l..1. 0 0 E - 0 6 l 2.63E-04 l <1.00E-06 AG 110M l CI <5.00E-07 <5.00E- ...........................l............l........07 l 4.50E-05 l 4.30E-05 I 133 l CI <5.00E-07 <5 ...........................l............l.... 0 0 5 - 0 7 l <5.00E-07 l 5.22E-05 CS 136 l CI <5.00E-07 <5 ...........................l............l... 005-07 l <5.00E-07 l 8.01E=06 SB 125 l CI <5.00E-07 <5 ...........................l............l... 00E-07 l 7.33E-06 l <5.00E-07 TOTAL FOR PERIOD CI 9.20E-07 ....................l.......l............l. 2. 0 3 E - 0 4 l 2.442-03 9.80E-03 ......................l........... KR 85M l CI <1.00E-04 <1.00 ...........................l............l......E-04 l <1.00E-04 l 1.25E-05 ....................l.......l............l..1.00E-04 IE 131M CI <1.00E-04 l <1.00E-04 1.86E-04 .....................l........... IE 133M l CI <1.00E-04 <1.0 ...........................l............l.....0E-04 l 1.29E-04 l 1.65E-03 ....................l.......l............l..1. 0 0 E - 0 4 IE 133 CI 7.02E-04 l 1.75E-92 1.95E-01 .....................l........... XE 135 CI <1.00E-04 ....................l.......l............l..1. 0 0 E - 0 4 l 3.10E-04 l 1.14E-03 NOTE: ALL LESS TRAN VALUES (<) AJ2 IN uCi/cc.

TMI-1 TABLE 3A ETTLtTNT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED TUEL SHIPMENTS A. Solid waste shipped off-site for burial or disposal (not irradiated fuel) l'. Type of waste wit f,yp @j6p]M

a. spent resins, Z11ter sluoges n'

40g47 m3 e avatiorator bot toms. etc. Ci 6.Eco 01 5%

b. Dry compressible waste, contaminated a3 tu7.35 m3 eeufement. etc.

$g e4 .phs? c!

c. Irractateo components, control i

rods, etc. m Ci n/a n/a

d. Other (describe) as C1 "I"

"/"

2. Estimate of major nuclide cotsposit1Sn (bv type of Vaste) a.

Cobb 34.06 % H3 26.19 ? Cs] 37 1$,4 ( g Cc134 8.86 % b. Cs13I $0. 05 g NioS coSe Id.6w t Cobo 11.19 g Cal 34 10.4 9 g ~ 5,39 g C I T t __ d. t l

3. Solid Wasta Disposition Number of Shipments Mode of Transportation Destination SEE ATTACHED B.

Irradiated Fuel Shipments (Disposition) Sumber of Shipments Mode of Transportation Destination N/A -B-nn

y L.' L I-TMI-1 EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT 06/01/89 Through 12/31/89 i Table A.3.a No. of Shirments Mode of Transportation Destination 4 Tractor-Flatbed Hanford-Richland, WA 1 Tractor-Closed Van Hanford-Richland, WA i Table A.3.b No. Of i Shipments Mode of Transportation Destination

  • 3 Tractor-Flatbed Scientific Ecology Group-Oak Ridge TN-3 Tractor-Flatbed Hanford-Richland, WA 1

Tractor-Closed Van Hanford-Richland, WA WASTE SHIPPED AS FOLLOWSt TABLE'A.I.a: Seven (7) - 170 Ft.* Steel Liners /Dewatered Resin One (1) - 183.2 Ft.8 Steel Liner /Dewatered Resin Two (2) - 178 Ft.8. Steel Liners / Solidified with Cement TABLE A.I.br Seven (7) - 44 Ft.8. Steel Boxes

  • Three (3) - 1040 Ft.* Cargo Containers / DAW for Volume Reduction Two (2) --73.4 Ft.* Steel Boxes one (1) - 98 Ft." Steel Box
  • 0ne (1) - 92 Ft.* Steel Box / DAW for volume reduction.

Two (2) - 7.5 Ft.* Steel Drums One (1) - 11.3 Ft." Steel Drum

  • Material Sent to Waste Processor for Volume Reduction

INTERPRETATION OF DOSE SUIMARY TABLE 4 The Dose Sumary Table presents the maximum hypothetical doses to an i individual and the general population resulting from the release of gaseous and liquid effluents from TMI-1 during the second half reporting period of 1989 A. Liquid (Individual) The first two lines present the maximum hypothetical dose to an indi vidual. Presented are the whole body and critical organ doses. Calculations are performed on the four age groups and eight organs 1 recomended in Regulatory Guide 1.109. The pathways considered for TMI are drinking water, irrigated cow milk, irrigated goat milk, irrigated beef, consumption of fish, and standing on the shoreline influenced by i l TMI effluents. The latter two pathways are considered to be the primary recreational activities associated with the Susquehanna River in the The irrigation pathways apply to the sewage sludge, vicinity of TMI. The " receptor" would be that individual who consumes water from the i Susquehanna River and fish residing in the plant discharge, while j occupying an area of shoreline influenced by the plant discharge and consuming the milk and beef fed irrigated vegetation. t After calculating the doses to all age groups for all eight organs resulting from the three pathways described above, the Dose Sumary Table presents the maximum whole body dose and affected age group along with the organ and associated age grcup that mceived the largest dose. L J For the second half of 1989 the calculated maximum whole body dose received by anyone would have been 0.021 mrem to an' adult. t. Similarly, l the maximum organ dose would have been 0.028 mrem to the liver of a teen, r B. Gaseous (Individual) L 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, Lines 3 and 4 present the maximum plume exposure at or beyond the site f boundary. 1 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 occurmd at or beyond the site boundary. The Dose Sumary Table presents the distance in meters to the location in the L affected sector (compass point) where the theoretical maximum plume L exposure occurred. It should be noted that real-time meteorology was I used in all dose calculations for gaseous effluents. Lines 5 and 6 present the dose which could actually be received by an individual from the noble gas effluents for the second half of 1989. The calculated u L maximum whole body dose received by anyone from noble gases would have been 0.025 mrem. Similarly, the maximum dose to the skin would have been m 0.054 mrem. l l

l The iodines and particulates section described in line 7 represents the maximum exposed organ due to iodine and particulates. This does not include any whole body plume exposure which would be separated out by lines 5 and 6. The doses presented in this section a 1 maximum exposed organ for the appropriate age group. gain reflect the The second half 1989 iodines and particutates would have resulted in a maximum dose of 0.29 mrem to the thyroid of an infant residing 560 meters i from the site in the W sector. have received a greater dose. No other organ of any age group would 1 C. Liquid and Gaseous (Population) j Lines 8 - 11 present the person-rem doses resulting from the liquid and i gaseous effluents. These doses are summed over all pathways and the af fected 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 sunned over all distances and sectors ~; to give an aggregate dose. Based upon the calculations performed for the second half of 1989 li effluents resulted in a whole body population dose of 3.1 person-r,em. quid The maximum critical organ population dose to the thyroid was 3.4 person-rem. Gaseous effluents resulted in a whole body population dose of 0.24 person-rem. Maxinmm critical organ population dose to the thyroid was 1.9 person-rem. v k w--- - +ww=

TABLE 1 IMIT 1 ~ Second Half 1989 Dose P.eport St# MARY OF MAXIMUM INDIVIDUAL DOSES FOR IMIT 1 FROM July 1,1989 through December 31,1999 I I I Estimated i I Location I % of I Technical i I l Applicable i Dose i Age l Dist Dir i Applicable 1 Specification ( l Ef fluent i Organ I (area) l Group l (a) (toward) l Limit I limits (ares) 1 I I I I I I Quarterly I Annual I Quarterly I Annual l i I I I I i l i i I l(1) Liquid i Total Body i 'O.021 l Adult i Receptor 1 1 1.4 1 0.71 1 1.5 1 3.0 l l(2) Liquid i Liver 1 0.028 i Teen i Receptor 1 1 0.56 1 0.28 l 5.0 1 10.0 I I I I I I I i i i I I I I I i i I I I i l(3) Noble Gas l Air Dose 1 0.34 l l 160 WNW l 6.8 1 3.4 1 5.0 1 10.0 I I i (gamma-arad) I l l l 1 I I I i l(4) Noble Gas l Air Dose 1 0.36 l l 160 WNW l 3.6 l 1.8 l 10.0 1 20.0 I I I (beta-arad) l I I I I i l i 1(5) Noble Gas l Total Body 1 0.025 l All l 560 W l 1 --- 1 1 1(6) Noble Gas i Skin 1 0.054 l All l 560 W I _1 l I l ) i 1 i i i I I l i i i i I i i I I I i I I l(7) Iodine & I Thyroid 1 0.29 l Infant 1 560 W l 3.9 l 1.9 1

7. 5 l

15.0 l l Particulatesl i I I I I I I I SupmARY OF MAXIMUM POPULATION DOSES FOR UNIT 1 FROM July 1, 1989 through December 31, 1989 Estimated Applicable Population Dose Effluent Organ (person-rem) (8) Liquid Total Body 3.1 (9) Liquid Thyroid 3.4 (10) Gaseous Total Body 0.24 (11) Gaseous Thyroid 1.9

TABLE 2 UNIT 1 Anaual 1989 Dose Report SupeiARY OF MAXIMUM INDIVIDUAL DOSES FOR UNIT 1 FROM January 1,1989 through De: ember 31, 1989 l l 1 Estimated l l Location l 7, o f I Technical l l l Applicable l Dose l Age l Dist Dir i Applicable l Specification l I Effluent l Organ 1 (mrem) l Group l (m) (toward) l Limit i Limit.s (ares) l l l 1 1 1 1 Quarterly I Annual I Quarterly I Annual l I i l I I I I I-1 l l(1) Liquid l Total Body l

0. 0 31 l

Adult l Receptor 1 1 l 1.0 1.5 1 3.0 l l(2) Liquid i Liver 1 0.041 l Teen l Receptor 1 1 1 0.4 I 5.0 l 10.0 l l l l I i I I I I I I I I I I I 'I l l l(3) Noble Gas l Air Dose 1 0.42 l l 160 WNW l I ^ l 5.0 1 10.0 1 1 l (gansna-mrad) l l 1 l l I I I l(4) Noble Gas l Air Dose 1 0.44 l l 160 WNW I 1 2.2 1 10.0 1 20.0 l l l (beta-arad) l l l 1 I l l 1(5) Noble Gas 1 Total Body l 0.032 l All l 560 W l I l 1 l l(6) Noble Gas i Skin 1 0.072 l All l 750 ENE i 1 l I l 1 1 1 1 I I I I I I l 1 1 I I I I I I I l(7) Iodine & I Thyroid 1 0.45 l Infant 1 560 W l 1 3.0 1 7.5 1 15.0 l l Particulatesi l l l l I I I I SUP#iARY OF MAXIMUM POPULATION DOSES FOR UNIT 1 FROM January 1,1989 through December 31, 1989 Estimated Applicable Population Dose Effluent Organ (person-rem) (8) Liquid Total Body 4.0 (9) Liquid Thyroid 4.4 (!0) Gaseous Total Body 0.32 (11) Gaseous Thyroid 2.9 Annual summations will not equal the sum of each periodic report due to receptor location changes and interpolation results.

9% 8 j .E JOINT FREQUENCY TABLES NOURS AT 8ACN WIND. SPEED AND DIRECTION-PER100 0F RECORD = 89010101 09123124 PER100 0F RECORD e 89010101 09123124 SIAllLITY CLASS: A DT/02 STAtlLITY CLASSt C DT/02-ELEVATlute SPEEDISP1004 OIRECT10N01100A LAPSE 071 ....................................................... 50A ELEVAfl0N: SPEED:SpiOOA O! RECT .................................. 10N:011004 LAPSE 0T150A WIND SPEED (NPN)l WINO WIND SPEED (MPN) WIND DIRECTION 13 47 8 12 13 16 19 24 >24 TOTAL DIRECTION 13 47 8 12 13 18 19 24 >24 TOTAL N 3 41 21 0 2 0 67 N 4 2 0 9 0 0 15 i NNE 4 B' O 0 0 0 12 NNE O 3 1 0 0 'O 4 L NE 4 4 3 0 0' 0 11 NE 1 5 1 0 0 0 7 + ENE O 1 0 0 0 0 1 ENE 1 2 2 0 0 0 5 E 4 6 4 0 0 0 14 E 1 3 2 0 0 0 6 E SE O 7 11 0 0 0' 18 ESE O 2 6 ~ 0 0 0 8 SE 2 8 7 0 0 0 17 SE D 1 3' 0 0 0 4 $$7 1 1 0 0 'O 'O 2 $$E O 2 0 0-0 0 2 S 1 0 2 0 0 0 3 8 2 0 4 0 0 0 6 SSW 4 15 17 3 0 0 39 SSW 0-12 10 4 0 0 26 SW 5 32 15 5 0 0 57 SW 3 5 4 3 0 0 15 WSW 6 14 3 0 0' 0 23 WSW 2 2 3 0 0 0 7 i W 12 20 16 1 0 0 49 W 3 2 1 -4 0 0 -10 WNW 20 24 24 3 0 0 71 WNW 3 2 7 11 1 0 24 - l ' NW 23 72 61 20 2 0 178 NW 4 8 10 13 1 2 38 I NNW 24 3 46 15 7 1 168 NNW 5 2 '2 11 ( ..................................................1 25 ' TOTAL 113 328 230 47 11 1 730 TOTAL 29 53 56 55 6 .........j ...........l ............................................................................................................... 3 202 ~ PER1005 0F CALM (NOURS): 1 PERIOOS OF CALM (NOURS): 1 VARIABLE DIRECTION 233 VARIABLE DIRECTION 41 NOURS OF MIS $1NC DATA: 166 NOURS OF MIS $1NG DATA: 166 PERIOD OF RECORD =, 89010101 89123124 PERIOD OF RECORD e 89010101 89123124 ' STAtlLITY CLAS$2 0-0T/02 STABILITY CLASS: 8 01/01 ELEVATION: SPEED:SP100A DIRECTION:01100A LAPSE:01150A ELEVATION: SPEED:SP100A DIRECT!0N01100A LAPSE:0T150A WIND SPEE0(MPH) WIND SPEE0(MPH) WIND WIND DIRECTION 13 47,8 12 13 18 19 24 >24 TOTAL DIRECTION 13 47 8 12 13 18 19 24 >24 TOTAL 1 i N: 33, 71 27 8 0 0 139 N 0 10 2 -4 4 0 20 NNE 32 51 5 1 0 0 ' 89 NNE O 3 0 0 0 0 3 ' NE 27 95 7 0 0 0 129 NE 2 2 0 0 0 0 4 ENE 42 ' 86 16 0 0. 0 144 ENE 2 7 1 0 0 0 10 t 18 97 71 4 0 0 200 E 0-8 4 0 0 0 12 a ESE' 20 64 88 1 0 0 1 73 ESE 2 8 8 0 0 0 18 SE 25 - 60 26 5 0 0 116 SE 2 2 3 1 0 0 8' l SSE - 18 35 17 2 0 1 73 ' SSE 2 0 3 1 0 0 6 l 'S 12 69 42 3 0 0 126 S 1 5 5 0 0 0 11 SSW - 11 63 63 9 1 0 147 SSW 2 to 12 5 1 0 30 SW '31 56 28 9 2 0 126 SW 5 13 7 4 0 0 29 WSW 18 29 ' 18 5 0 0 70 WSW 5 I l-0 0 0 13 W-28 - 35 70 61 9 .0 203 W 5 8 4 7 0' 1 25 WNW 25 37 62 94 22 7 247 WNW 2 10 15 9 -2 0 38 - 1 NW 28 54 98 95 47 7 329 NW 2 13 13 20 4 0 52 j NNW. 37 61 50 36 12 0 1% NNW 5 16 10 12 7 0 50 3 ............................................................ l TOTAL '415 963 688 333 93 15 2507 TOTAL 37 118 92 63 18 1 329. ' PERICSS OF CALM (NOURS): 1 PERIDOS OF CALM (NOURS): 1 i VARIA8LE DIRECT!0N 626 VARIABLE DIRECTION 73 NOURS OF MIS $1NG DATA: 166 HOURS OF MISSING DATA: 166 l I s -{ -1 4 $l

~e: ,.. '.-+ 7-JOINT FREQUENCY TABLES b PERIOD OF RECORD e 89010101 89123124 PERite OF RECORD e 890*0101 8P123124 STASILITT CLASS: E DT/DZ STASILITT CLASS: G DT/DZ ELEVAfl0N: SPEED SP100A DIRECTIONID1100A LAPSE:DT150A ELEVATION: SPEED SPiOOA DIRECT 10N01100A LAPS ...................................................E DT1504 WIND SPEED (MPN) ...... 2 WIND WIND SPEED (MPN) WIND DIRECTION 13 47 6 12 13 18 19 24 >24 TOTAL DIRECTION 13 47 8 12 13 18 19 24 >24 TOTAL j N 60 114 21 3 0 0 198 N 25 ' 13 0 0 0 0 38 i NNE 47 95 12 1 0 0 155 NNE 8 3 0 0-0 0' 11 NE 65 82 9 0 0 0 156 NE 13 2 0 0 0 0 15 - ENE 61 94 ' 14 8 0 0 177 ENE 25 7 0 .0 0 0 32 E 59 99 36 11 0 0 205 E 20 3 0 0 0 0 23 - ESt 42 51 46 1 0 0 140 ESE 25 9 0 0-0 0 34 SE 53 34 9 2 0 0 98 SE 25 2 0 0 0 0 27

  • SSE 34 37 13 6

0 0 90 SSE 24 3 0 0 0 0 27 5 40 78 34 3 0 0 155 s 27 4 0 0 0 0-31 SSW. 48 136-68 14 2 0 268 SSW 22 19 0 0 0 0 41 SW ' 62 127 48 3 1 0 241 SW 25 13 0 0 0 0 38 WSW ' 74 114 23 3 0 0 214 WSW 19 18 1 0 0 0 38 W 68 - 130-81 15 6 0 300 W 27 18 2 1 0 0 48 WW 66 89 118 40 5 2 320 WW 20 14 1 0 0 0 35 WW 62 66 91 69 8 1 297 WW 27 10 4 0 0 0 41 NNW 78 90 41 16 4 0 229 NNW 18 15 2 0 0 0 35

  • TOTAL 919 1436 664 195 26 3 3243 TOTAL 350 153 10 1

0 0 514 PERIODS OF CALM (NOURS): 1 PERICES OF CALM (NOURS): 1 VARIAtl,E DIRECTION 1157s VAR!ASLE DIRECTION - 297 NOUR$ OF MIS $1NG DATA 166 NOURS OF MISSING DATA: 166 f PERIOD OF RECORD e 89010101 89123124 PERIOD of RECORD e 89010101 89123124 STASILITY CLASS: F DT/DZ STA81LITY CLASS:- ALL 07/02 ELEVAfl0N: SPEED SP100A DIRECTION:D1100A LAPSE DT150A ELEVATION: SPEED SP100A DIRECTION 01100A LAPSE DT150e WIND SPEED (MPN) Wlho SPEED (MPN)' . WIND WIND DIRECTION 1*3 4*7 8 12 13 18 19 24 >24 TOTAL DIRECTION 13 4*7 8 12 13 18 19 24 >24 TOTAL-N 25 45 3 0 0 0 73 N-150 296 74 24 6 0 550 ~ NNE 25 to 0 0 0 0 35 NNE 116 173 18 2 0 0 309-NE 22 8 -0 0 0 0 30 NE 134 198 20 0 0 0 352 - ENE 30 18 0 0 0 0 48 ENE 161 215 33 8 0 0 '417 E 47 26 1 0 0 0 74 E 159 242 118 15 0 0 534 .ESE 44 15 3 0 0 0 62 ESE 133 156> 162 2 0 0 453 SE 28 7 1 0 0 0 36 SE 135 114. 49 - 8 0 0 306 SSE 31 2 0 0 0 0 33 $$E 110 80 33 9 0 1 233. S 31 7 1 0 0 0 39 114 163 88 6-0 0 371 SSW 36 .41 0 1 1 0 79 $$W 123 296 170 36 5= 0 630', SW 41 36 2 2 0 0 81 SW 172 282 104 26 3 0.587 WSW 52 31 2 0 0 0 85 WSW 1 76 211 55 8 0 0 450 W 53 42 4 1 0 0 100 W 196 255 178 90 15 1 735-WW 50 28 4 0 0 0 82 WW 186 204 231 157 30 9 817-NW 52 30 11 0 0 1 94 NW 198 253 288 217 62 11 1029 NNW 56 47 15 0 0 0 118 NNW 223 306 166 90 34 2. 821 ......................................................................................................................( TOTAL' 623 393 47 4 1 1 1069 TOTAL 2486 3444 1787 698 155 24 8594-PERIODS OF CALM (NOURS): 1 PERIOOS OF CALM (HOURS): 1 VARIABLE DIRECTION 592 VARIABLE DIRECT!0N 3019 HOURS OF MISSING DATA: 166 NOURS OF MISSING DATA: 166 +}}

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