ML20082M291

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TMI-1 Effluent & Offsite Dose Rept for Jan-June 1991
ML20082M291
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 06/30/1991
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20082M290 List:
References
NUDOCS 9109050121
Download: ML20082M291 (13)
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Text

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EXECVIIVE St@g Three Mile Island Nuclear Station Unit 1 Erfluent and Off Site Icse Report for the Period of January 1,1991 through June 30, 1991 ,

t This report sumarizes the radioactive liquid and gaseous releases f (effluents) frcxn Three Mile Island Unit 1 and the calculated maximum i hypothetical radiation exposure to the public resulting frm these  !

releases. This report covers the period of operation frm January 1  ;

through June 30, 1991. '

Radiclogical releases frm the plant are nonitored by installed plant )

radiation nenitors which survey the plant stack for gaseot.a releases  :

and liquid discharges to the Susquehanna River for liquid releases.

These monitors and associated sample analyses provide a means to accurately determine the type and quantities of radioactive materials being released to the environment. '

i calculations of the m vi= = hypothetical dose to an individual and the i total pcp11ation around Three Mile Island due to radioactive releases frm the plant are made utilizing environmental conditions existing at the time of the release. Susquehanna River flow data are used to calculate the rninn- hypothetical doses to an individual and the population downstream of TMI due to liquid releases. Actual or ',

"real-time" meteorological data fmn an onsite tower is used to determine the doses resulting frw gaseous releases frcan the plant.

The use of real-time meteorological information permits the determination of both the direction in which the releare traveled and i the dispersion of radioactive material in the environment.

t Utilizing gaseous effluent data and real-time meteorology, the maximum

( hypothetical dose to any individual and to the total population within  ;

l 50 miles of the plant is calculated. Similarly, Susquehanna River flow and liquid effluent data are used to calculate a evi== hypothetical dose to an individual and a population dose fr m liquid effluents for any shoreline exposure down to the Chesapeake Bay. Exposure to the public frm consumption of water and fish withdrawn frm the Susquehanna River downstream of the plant is also calculated.

Dose calculatinns for liquid and gaseous effluents are performed using a mathanatical model which is based on the methods defined by the U.S.

Nuclear Regulatory Ccx: mission. ,

The maximum hypothetical doses are conservative overestimates of the actual off site doses which are likely to occur. For example, the dose ,

does not take into consideration the renoval of radioactive material frm the river water by precipitation of insoluble salts, absorption onto river sediment, biological removal, or removal during processing  ;

by water ccx:tpanies prior to distribution av. consumption.

9109050121 910529 DR ADOCK 0500

l l

l Liquid discharges mado during the reporting period January 1 through June 30, 1991 consisted of 226 curies of tritium, 0.0011 curies of noble 'Tases , pre &xninately Xe-133, and 0.003 curies of other bets and gama emitters, pre &xninately cs-134 and Cs-137. The quantities of effluents are similar to average s miannual releases fmn Unit 1 operations.

During the reporting period January 1 throtgh June 30, 1991, the mvien hypothetical calculated whole body dose to an individual due to liquid effluents frm Three Mile Island Unit 1 was about 0.028 millirm. The maximum hypothetical calculated dose to any organ of an individual was 0.039 millirm to the liver.

Airborne discharges mado during this same time period consisted of 31.2 curies of tritium, 29.26 curies of noble gases, and 0.0012 curies of iodines and particulates. These quutities of effluents are also similar to smiannual releases fmu previous Unit 1 operation, since 1985 restart.

The mv4 = = hypothetical calculated dose to any individual fmn noble gases was 0.033 mrom to the skin and 0.017 mran to the whole body.

Airborne iodine and particulates are calculated to produce 0.01 mran to the thyroid of the nav4== hypothetical individual.

The total ev4== hypothetical whole body dose of 0.048 mrm, received by any individual frm effluents fmu the Three Mile Island Nuclear Station Unit 1 during the reporting period is 3100 times lower than the dose the average individual in the Three Mile Island area receives fmn natural bado;round, including natural radon, during the same time period. Natural background averages about 50 millirm whole body semiannually in the Three Mile Island area. In addition, the average equivalent saniannual dose to the total body fmu natural radon is atout 100 milliian.

The calculated whole body population dose frcan all plant releases is 1.65 pe m n-Iun. This is 200,000 times lower than the dose attrib 2ted to natural background radiation for the reporting period. The doses which could have been received by the maximum hypothetical individual are each 3.0 percent or less of the annual limits established by the Nuclear Regulatory Ocmission in Appendix I of 10 CFR 50.

EFFLUENT & WASTE DISPOSAL SEMI ANNUAL REPORT

) SUPPLEMENTAL INFORMATION l FACILITY : TMI UNIT I LICENSE: DPR 50-289 I

1. REGULATORY LIMITS - - - REFER TO TMI UNIT 1 TECl!NICAL SPECIFICATIONG FOR:

A. FISSION AND ACTIVATION GASES:

D. IODINES:

C. PARTICUIATES IIALF-LIVES > 8 DAYS:

D. LIQUID EFFLUbNTS:

2, . MAXIMUM PERMISSIBLE CONCENTRATIONS ---

10 CPR 20, APPENDIX B TABLE II PROVIDE THE MPCS USED IN DETERMINING ALLOWABLE RELEASE RATES OR CONCENTRATIONS.

A. FISSION AND ACTIVATION GASES:

B. ICDINES:

C. PARTICULATES HALF-LIVES > 8 DAYS:

D. LIQUID EFFLUbHTS:

3. AVERAGE ENERGY PROVIDE THE AVERAGE ENERGY (E-BAR) OF Tile RADIONUCLIDE MIXTURE IN RELEASES OF FISSION AND ACTIVATION GASES, IF APPLICABLE E-BAR BETA = 2.64E-01 E-BAR GAMMA = 4.62E-01 E-BAR BETA AND GAMMA = 7.26E-01
4. MEASUREMENTS AND APPROX 1MATIONS OF TOTAL RADIOACTIVITY PROVIDE Tile METilODS USED TO MEASURE OR APPROXIMATE Tile TOTAL RADIOACTIVITY IN EFFLUENTS AND Tile METilODS USED TO DETERMINE RADIONUCLIDE COMPOSITION:

A. FISSION AND ACTIVATION GASES: IIPGE SPECTROMETRY, LIQUID B. IODINES:

SCINTILLATION C. PARTICULATES IIPGE SPECTROMETRY IIPGE SPECTROMETRY GAS PLOW PROPORTIONAL BET 1 SPECTROMETRY D. LIQUID EFFLUENTS: ilPGE SPECTROl4ETRY, LIQUID SCINTILLATION S. BATCH RELEASES PROVIDE Tile FOLLOWING INFORMATION RELATING TO BATCII RELEASES OF RADIOACTIVITY MATERIALS IN LIQUID AND GASEOUS EFFLUENTS.

A. LIQUID (ALL TIMES IN MINETES) QUARTER 1 QUARTER 2

1. NUMBER OF BATCil RELEASES: 25 33
2. TOTAL TIME PERIOD FOR BATCl! RELEASES: 9954. 11355.
3. MAXIMUM TIME PERIOD FOR A BATCli RELEASE: 1085, 1146.
4. AVERAGE TIME PERIOD FOR BATCH RELEASES: 398. 344, 5 MINIMUM TIME PERTOD FOR A BATCH RELEASE: 140.
6. AVE. STREAM FLOW DURING PERIODS OF RELEASE 45.

OF EFFLUENT INTO A FLOWING STREAM: (CFM) 3.41E+06 1.64EiO6 D. GASEOUS (ALL TIMES IN MINUTES)

1. NUMBER OF BATCH RELEASES: 21 13 2.

3.

TOTAL TIME PERIOD FOR BATCH RELEASES: 13976 8099.

4.

MAXIMUM TIME PERIOD FOR A BATCil RELEASE: 860. 870.

5.

AVERAGE TIME PERIOD FOR BATCH RELEASES: 666. 623.

MINIMUM TIME PERIOD FOR A BATCII REL. EASE: 1. 1.

6. ABNORMAL RELEASES A. LIQUID
1. NUMBER OF RELEASES: 2. TOTAL ACTIVITY RELEASED: (CURIES) N/A N/A B. GASEOUS
1. NUMBER OF RELEASES: 2. TOTAL ACTIVITY RELEASED: (CURIES) N/A N/A

)

TABLE 1A EFFLUENT AND WASTE GASEOUS DISPOSAL SEMIANNUAL EFFLUENTS-SUMMATION OF ALLREPORT RELEAoESfl991) i UNIT QUARTER 1 QUARTER 2 EST. TOTAL ERROR, %

A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE Ci 9.36E+00 1.99E+01 2.50E+01
2. AVG. RELEASE RATE FOR PERIOD uCi/sec 1.20E+00 2.53E+00
3. PERCENT OF TECH.

SPECIFICATION LIMIT  % *

1. TOTAL IODINE I-131 Ci 3.99E-05 7.41E-05 2.50E+01
2. AVG. RELEASE RATE FOR PERIOD uCi/sec 5.13E-06 9.42E-06
3. PERCENT OF TECH.

SPECIFICATION LIMIT  % *

  • C. PARTICULATES
1. PART. WITH HALF-LIVES > 8 DAYS Ci <1.00E-04 <1.00E-04 2.50E+01
2. AVG. RELEASE RATE FOR PERIOD uCi/sec NA NA
3. PERCENT OF TECH.

SPECIFICATION LIMIT  % NA NA

4. GROSS ALPHA RADIOACTIVITY Ci :1.COE-11 <1.00E-11 D. TRITIUM
1. TOTAL RELEASE Ci 1.57E+01 1.55E+01 2.50E+01
2. AVG. RELEASE RATE FOR PERIOD uCi/coc 2.02E+00 1.97E+00
3. PERCENT OF TECH.

SPECIFICATION LIMIT  % *

  • NOTE: ALL LESS THAN VALUES (<) ARE IN uCi/ml.
  • % TECH. SPEC. LIMITS: LISTED ON DOSE

SUMMARY

TABLE.

o TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT (1991)

GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINUOUS MODE BATCH MODE o

NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 h

1. FISSION GASES AR 41 Ci 2.21E-01 1.77E-01 6.13E-06 6.00E-04 KR 85 Ci <8.00E-06 <8.00E-06 1.82E-01 4.29E-01 KR 85M Ci 9.18E-02 2.56E-01 2.44E-06 1.68E-03 KR 87 Ci 1.34E-01 3.69E-01 3.31E-06 1.18E-03 KR 88 Ci 2.05E-01 5.7(E-01 5.38E-06 3.00E-03 XE 131M Ci <3.00E-07 <3.00E-07 4.55E-02 6.33E-02 XE 133 C1 1.95E+00 6.13E+00 4.08E+00 5.85E+00 XE 133M Ci 3.65E-03 1.05E-01 3.37E-02 4.43E-02 XE 135 Ci 1.43E+00 2.97E+00 4.60E-03 3.28E-02 XE 135M Ci 7.98E-01 2.14E+00 1.70E-05 1.03E-03 XE 138 Ci 1.85E-01 7.20E-01 6.19E-06 <3.00E-07 TOTAL FOR PERIOD Ci 5.01E+00 1.34E+01 4.35E+00 6.42E+00
2. IODINES I 131 Ci 3.97E-05 7.41E-05 1.18E-07 <l.00E-08 I 133 Ci 4.07E-04 7.09E-04 6.64E-07 <1.00E-08 I 135 Ci <1.00E-10 <1.00E-10 <1.00E-10 <l.00E-10 TOTAL FOR PERIOD Ci 4.47E-04 7.83E-04 7.81E-07 0.00E+00
3. PARTICULATES CS 134 Ci <1.00E-ll <l.00E-11 <1.00E-08 <1.00E-08 CS 137 Ci <1.00E-11 <1.00E-11 <l.00E-08 <1.00E-08 NOTE: ALL LESS THAN VALUES (<) ARE IN uCi/ml.

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TABLE 2A j

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES (1991)

UNIT QUARTER 1 QUARTER 2 EST. TOTAL ERROR, %

A. FISSION AND ACTIVATION PRODUCTS-

1. TOTAL RELEASE (EX.

H-3, GASES, ALPHA) Ci 6.17E-04 1.83E-03 2.50E+01

2. AVG.. DILUTED CONC. DURING PERIOD uCi/ml 6.17E-08 1.79E-07
3. PERCENT OF APPLICABLE LIMIT  % *
1. TOTAL RELEASE' C1 1.03E+02 1.23E+02- 2.50E+01
2. AVG. DILUTED CONC. DURING PERIOD uCi/ml 1.03E-02 1.16E-02
3. PERCENT OF APPLICABLE LIMIT  % *
  • C. DISSOLVED AND ENTRAINED GASES
1. TOTAL RELEASE C1 1.90E-04 9.44E-04 2.50E+01
2. AVG. DILUTED CONC. DURING PERIOD uCi/ml 1.90E-08 8.91E-08
3. PERCENT OF APPLICABLE LIMIT ,  % * * '

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE Ci <1.00E-07 <1.00E-07 2.50E+01 E. VOL. OF WASTE RELEASED (NO DIL.) LITERS 9.03E+06 7.60E+06 1.00E+01 F..VOL. OF DILUTION WATER.IN PERIOD LITERS 1.00E+07 1.06E+07 1.00E+01 NOTE:

ALL LESS THAN VALUES (<) ARE IN uCi/ml.

O % TECH. SPEC. LIMITS: LISTED ON DOSE

SUMMARY

TABLE.

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TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1991)

LIQUID EFFLUENTG CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 CR 51 Ci <5.00E-07 <5.00E-07 <5.00E-07 <5.00E-07 MN 54 Ci <5.00E-07 <5.00E-07 <5.00E-07 8.13L-07 FE 55 Ci <1.00E-06 <1.00E-06 <1.00E-06 1.83E-04 CO 58 Ci <5.00E-07 <5.00E-07 8.32E-05 4.14E-04 FE 59 Ci <5.00E-07 <5.00E-07 <5.00E-07 <5.00E-07 _

CO 60 Ci <5.00E-07 <5.00E-07 5.04E-06 1.01E-04 ZN 65 Ci <5.00E-07 <5.00E-07 <5.00E-07 <5.00E-07 1 SR 89 Ci <5.00E-08 <5.00E-08 <5.00E-08 <5.00E-08 SR 90 Ci <5.00E-08 <5.00E-08 <5.00E-08 <5.00E-08 NB 95 Ci <5.00E-07 <5.00E-07 <5.00E-07 <5.00E-07 ZR 95 Ci <5.00E-07 <5.00E-07 <5.00E-07 <5.00E-07 MO 99 Ci <5.00E-07 <5.00E-07 <5.00E-07 <5.00E-07 TC 99M Ci <5.00E-07 <5.00E-07 <5.00E-07 <5.00E-07 ,

AG 110M Ci <5.00E-07 <5.00E-07 1.03E-05 4.13E-05 1 131 Ci <1. 00E-06 <1.00E-06 <1.00E-06 <1.00E-06 CS 134 Ci <5.00E-07 <5.00E-07 1.85E-04 3.47E-04 CS 137 Ci <5.00E-07 2.80E-05 3.34E-04 7.7PE-04 BA 140 Ci <5.00E-07 <5.00E-07 <5.00E-07 <5.00E-07 LA 140 Ci <5.03E-07 <5.00E-07 <5.00E-07 <5.00E-07 CE 141 Ci <5.00E-07 <5.00E-07 <5.00E-07 <5.00E-07 TOTAL FOR PERIOD Ci 0.00E+00 2.80L-05 6.17E-04 1.87E-03 KR 87 Ci <1.00E-04 <1.00E-04 <1.00E-04 1.49E-06 XE 133 Ci <1.00E-04 <1.00E-04 1.90E-04 9.37E-04 XE 135 Ci <1.00E-04 <1.00E-04 <1.00E-04 6.20E-06 NOTE: ALL LESS THAN VALUES (<) ARE IN uCi/ml.

TMI-l January 1, 1991 to June 30, 1991 TABLE 3A I

ETTLLT'iT AND WAS1E DISPOSAL SD11 ANNUAL REPORT SOLID WASTE AND IRRADI ATED FUEL SilIPMENTS A. Solid waste shipped of f-site for burial or disposal (not irradiated f uel) l'. Type of waste h

4. Spent resins, filter sluages, UNIT 3

h , TOTAL evaporator bottoms. cre.

m 87,3 m 3 (A, Ci 11.70 Cl

b. Dry co=pressible waste, con t and na t ed m 3 b/.Hb m3 enuinnent, etc. ,g-
c. Irraalateo :omponents, control r1 .01Hfi C i 3

m rod s . e t c . Ci N/A nfA aD

d. Other (deveribc) C1 N/A M/A
2. Estimate of major nuclide composition (bv type of waste) a, H3 14,? ;

Cohn 74,y .

C513/ ~~[,99

]

Ls134 34,qp.

b. N i fi3 ?O.1
  • r058 y() , y ..

Csl3/ 17,g g le5b ~

14,9 :

Crbl 9,87

c. ,

2

'4 d.

3. Solid Waste Disposition Number of Shipments Mode of Transoortation Destinatten St L Al I Attil.D B. Irradinted Fuel Shipments (Disposition) umber of Shirtentr, Mode o f Transnortat ion Destination N/A  !

I

.g.

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TABLE 3A ATTACilMENT 1 TM1-1 I FFLUENT & WASTE D]SPOSAL SEMI-ANNUAL Ri p0RT

.1anuary 1, 1991 t broup.h . lune ~10 . 1991 A.1.a - Mat erial Shipped as l'ollows:

Seven (7) Steel Liners at 178 Ft.' Each - Solidif ied wit h Cemeat Two (2) Steel Liners at 183.2 Ft.' Each

  • Four (4) Steel 1.iners at 196 ft ' Each
  • Three (3) Steel Iiners at 170 Ft .' Each A.1.h
  • Two (2) 8' x 8' x 20' Cargo Containers at 1,040 ft.' Each
  • Two (2) Steel Boxes at 92 Ft." Each
  • 0ne (4) Steel Box at 44 Ft.'

Two (2) Steel Boxes at 44 Ft ' Each Table A.3.a No. of Shipments Mode of Transportation Destinatinn Five (5) Shipments Tractor - Cask (NuPac 14/190m) U. S. Ecology - llanf ord Two (2) Shipments Tractor - Flatbed U. S. Ecology - Hanford

  • Three (3) Shipments 1ractor - Flatbed Scient ific Ecology Group Oak Ridge. TN Table A.3.h No. of Shipments Mode of Transportation Destination 4, *Two (2) Shipments Tractor-Flatbed Scientific Ecology Group Oak Ridge, TN One (1) Shipment Tractor-Flatbed U S. Ecology, Hanford
  • Mat erial Sent to a Waste Processor for Volume Reduction

INltRPRllA110N Of DOSE

SUMMARY

1ABII; 1he Dose Summary lable presents the maximum hypothetical doses to an individual and the general population resulting from the release of gaseous and liquid effluents from IMl-1 during the first half reporting period of 1991.

A. Ii_ quid (Individual)

The first two lines present the maximum hypothetical dose to an individual. presented are the whole body and critical organ doses.

Calculi.t ions are perf ormed on t he four age groups and eight organs recommended in Regulatory Guide 1.109. The pathways considered for 1MI are the comsumption of drinking water and fish and standing on the shoreline influenced by 1M1 ef fluents. The latter two pathways are considered to be the primary recreational activities associated with the Susquehanna River in the vicinity of IMI. 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 f rom the three pathways described above, the Dose Summary lable presents the maximum whole body dose and af fected age group along with the organ and associated age group that received the largest dose.

For the first half of 1991 the calculated maximum whole body dose received by anyone would have been 2.82L-2 mrem to an adult. Similarly, the maximum organ dose would have been 3.88E-2 mrem to the liver of a teen.

B. Gaseous (Individuall fhere 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 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 doses that would have occurred at or beyond the site boundary. The Dose Summary Table presents the distance in meters to the location in the af fected sector (compass point) where the theoretical maximum plume exposures occurred. It should be noted that real-time meteorology was used in all dose calculations f or gaseous ef fluents, l.ines 5 and 6 present the doses which could actually be received by an individual f rom the noble gas ef fluents for the first hali of 1991. The calculated maximum whole body dose received by anyone from noble gases would have been 1.73E-2 mrem. Similarly, the maximum dose to the skin would have been 3.341-2 mrem.

. j

.1he iodines and particulates- section described in line 7 represents the -

l maximum exposed organ due to iodine and particulates. _ . The dose -  ;

presented in this section again reflects the maximum exposed organ for  :

the appropriate age group. I The first half 1991 iodines and particulates would have resulted in a maximum dose of 1.03E-2 mrem to the thyroid of an infant residing 560 meters from the site in the W sector. No other organ of any age group would have received a greater dose.

C. Liquid and Gaseous (Population) [

t 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 TMl 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 1 miles around TMI. Population doses are summed over all distances and  ;

sectors to give an aggregate dose. ,

Based upon the calculations performed for the first half of 1991, liquid  ;

ef fluents resulted in a whole body population dose of 1.54E0 person-rem. ,

The maximum critical organ population dose to the liver was 1.55E0  !

f person-rem. Gaseous effluents resulted in a whole body population dose

.of 1.11E-_1 person-rem. And the maximum critical organ population dose j

.to the thyroid was 1.53E-1 person-rem.

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=m*-t* N T- F v __r-- -- .__.__--- - -_____

=. +

Jj

. TABLE 1 .'.

i UNIT 1  ;

First Half 1991' Dose Report i 1 >

SUMMARY

OF MAXIMUM: INDIVIDUAL DOSES FOR UNIT 1 FROM January 1, 1991 through June 30, 1991

  • i l j Estimated l Location- l  % of Technical l l Applicable l --Dose Age l Dist .Dir l Applicable - Specification {

' Effluent Organ I (mrem)- I Group l. (m) (toward) j Limit Limits (mrem) {

l l l l l Quarterly l Annual l Quarterly l Annual 'j.

. 1 I I I I I l

! ((1) Liquid Total Body l 2.82E-2 Adult Receptor 1 l 1.8BE0 l 9.40E-1 l- ,1. 5 i 3.0 i l(2) Liquid ,l Liver i 3.88E-2 l Teen l Receptor 1 "

7.76E-1 l'3.88E-1 l 15 . 0 l 10.0 l l l i i '

l-

j{3) Noble Gas Air Dose 2.39E-1 l 160 WNW 4.78EO 2.39EO "

5.0 10.0 l-l l (gamma-mrad) l l l' (

i l(4) Noble Gas l Air Dose 1.78E-1 l 160 WNW l.78EO l 8.90E-1 l 10. C ' , 20.0 l-(beta-mrad)

I 1 L l l l l l l(5) Noble Gas Total Body 1.73E-2 l All 560 W ---

l --- l l

.)

l(6) Noble Gas l Skin 3.34E-2 l All 560 W  !

l --- l l- ---

'l' l l I i

((7) Iodine & Thyroid

  • 1.03E-2 Infant l 560 W 1.37E-1 6.87E-2 ] 7.5 -1 15.0 (

l Particulates l l l I 1 l l l

SUMMARY

OF MAXIMUM POPULATION DOSES FOR UNIT 1 FROM January 1, 1991 through June 30, 1991 Estimated Applicable Population Dose Effluent Organ (person-rem)

(8) Liquid Total Body 1.54E0 (9) Liquid Liver 1.55EO (10) Gaseous Total Body 1.11E-1 (11) Gaseous Thyroid 1.53E-1

_- _ . _ . . i

C311-91-2091 AITACilMENT 1 The following is a brief summary of the individual changes to the Process Control Program.

1. Etclion 1.0 Distuis_Lqn A note was added to limit performance of the Process Control Program to Unstable Waste forms Only.
2. Etc11gn. 1 0 Referentti A new Item 2.10 was added to reference Revision 1 to the Waste form Technical Position, dated January 24, 1991.

A new Item 2.11 was added to reference Generic Letter 91-02, Reporting Mishaps involving LLW forms Prepared for Disposal, dated December 28, 1990.

3. Section 4.0 Reportinr' Requiremepig A new Section 4.3 was added to define the criteria for off normal or improper solidification of stable waste forms and required NRC notifications.
4. Section 6J Test Solidification of 4 t o 10 Wt% Boric Acid _(ConcJntzatfd Waligl lention 7.0 Test Solidification of >10 tolQlt% Boric _Ac1 (foncentn led Wa_s.tgl Section 8.0 Telt_S.glid_ification of_ Waste Oil (12-40% 0111 Etcti9n 9.0 TesLlolidifica.11on ofjhnd Precoat lection 10.0 Test jolidification of Bead Resin Section 11.0 Alternate Test Solidification Programs lhe first note in each of these sections has been expanded to remind personnel that test solidification of these wastes will only apply for the production of Unstable Waste forms.

A copy of OP 1104-281 is attached 1

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