ML20246M782

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Effluent & Waste Disposal Semiannual Rept for Jan-June 1989
ML20246M782
Person / Time
Site: Crane Constellation icon.png
Issue date: 06/30/1989
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20246M712 List:
References
NUDOCS 8909070249
Download: ML20246M782 (14)
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Text

{{#Wiki_filter:-_ EXECUTIVE

SUMMARY

Three Mile Island Nuclear Station Ur.it 1 Effluent and Offsite Dose Report for the Period of January 1,1989 to June 30, 1989 This report summarizes 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 January 1 to June 30, 1989. Radiological releases from the plant are monitored by installed plant monitors sampling the plant stack for gaseous releases and liquid monitors for discharges to the Susquehanna River. These monitors and sample analyses 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 pcpulation around Three Mile Island due to radioactive releases from the plant are made utilizing environmental Londitions 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 relecses. Actual or "real-time" meteorological data from an onsite tower is used to. determine the doses resulting from gaseous releases from the plant. 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 in 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 Exposure to the public from consumption of water and fish withdrawn from the Susquehenna River downstream of the plant is also calculated.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 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 and consumption. L s90907o249 890630 FDR ADOCK 05000289 R PDC L-__--_-_____

l l Liquid discharges _made during the reporting period January 1 to June 30, 1989 consisted of 158 curies of tritium, 0.012 curies of noble gases (predominantly Xe-133), and 0.0036 curies of other beta and gamma emitters, predominantly Co-58. The quantities of effluents are similar to average semi-annual releases from previous Unit 1 operations. During the reporting period January 1 to June 30, 1989, the maximum hypothetical calculated whole body dose to an individual due to liquid effluents from Three Mile Island Unit 1 was 0.0099 mrem. The maximum hypothetical calculated dose to any organ of an individual was 0.013 mrom to the liver. Airborne discharges made during this same time period consisted of 1.7 curies of tritium, 438 curies of noble gases, and 0.0077 curies of iodines and particulate. These releases are similar to semi-annual releases from previous Unit 1 operation, since the 1985 restart. The maximum hypothetical calculated dose to any individual from noble gases was 0.041 mrem to the skin and 0.016 mrem to the whole body. Airborne iodine and particulate are calculated to produce 0.16 mrem to the thyroid of the maximum hypothetical individual. Tne total maximum hypothetical whole body dose of 0.026 mrem, received by any individual from effluents from TMI-1 for the reporting period is 1900 times lower than the doses the average individual in the area of TMI-1 receives from natural background during the same time period. Natural background averages about 50 mrem whole body semi-annually in the TMI-1 area. 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 1.0 person-rem. This is 110,000 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 2% of the annual limits established hy the Nuclear Regulatory Commission in Appendix I of 10 CFR 50.

a EFFLUENT & 1&ITE HFCIAL SEhlANNUAL REPORT IUPPLEENTAL INFORMATION FACILITY: ThI WIT 1 LICENIE: DPR50-289

1. REGULATORY LIMI15 - - - REFIR TO in! Wii i TECHNICAL IPEClflCATION!

. { g g 40 ACTIVATION GAIEI: {. g g I g tF-LIVEI ) B MY!: g 2.hAXIMUMPERMIIIIDLECONCEKl{ATIDNI---10CFR20,APPENIlXBIABLE!! g Dgi g g tl ETERMINING ALLOWABLE RELEAIE g g g AD ACTIVATIDN GAIEI! C. PAR 11CULATEI liALF-l.IVEI ) 6 MYI: D.LIQUIDEfflu!N15:

3. AVERAGE E E GY bkE ffl#Eif.1 WilflW TC11511RdBr AretiCAntt E4AR PETA = 2.16E41 E44R LANNA = 2.5tE41 E4AR BETA AG CAMA = 4.67E-91
4. HEAIURE E TI A G APPROXIhATIONI 0F TOTAL R O10 ACTIVITY kkkUfhi hkE k

1 JCf h C N b k1'kfb HI O 1: WfM a* "*" 5"* RE MRME "'" """, HPLE IliCIP0 METRY [CTR0HElRY GAIFLOWPROPORTIONAL C. PARTICULATE BE1ATP D.LIQUIDEFTLUENTI: HPGE SPECTROMETRY, LIQUID SCINTILLAllDN l S. M TCH RELEAIES bbkifbik blP5RRMWH10a!RUEliF

  • 7 A. LIQUID QUARTER 1 'DUAETER2 2*T TIMEhb0 hkCHRELEAIEI:

itb6. ! BN7. (HIN.)

3. MAXIMUM 11ME PEkl0D FOR A MICH RELEAIE: (hlN.)

075. ! 455.

4. AVERAGE TIME PERIOD FOR MICH RELEAIEI: -(MIN.)

395. ! 278.

5. MIKIWh TIME (ER10D FOR A MTCH RELE AIE: (KIN.)
95. !

39.

6. M.M2 IIREAM FLOW DukING PER101;I 0F RELEAIE 0F EffLUEFT IN10 A FLOWING IIREAM:

(CIK) 1.67E+06 ! 4.22E46 L. GAIEDUI b IfMEh0 khCHRELEAIEI: (MIN.) 6 9. 51.

3. hAXIMUM TIME PERIDD fitR A BAICH ii!IAIE: (hlN.)

610. ! 778.

4. AVERAGE TIME PEic10D FOR MTCH iiLEA!ES: (KIN.)

415. ! 451.

5. hlHIMuti TIE PERIOD FOR A MTCH RELEAIE: (elf.)

1. t.

6. ABNORMAL RELEAIEI hRERffRELEAIEI:

4-4- 2.101AL ACTIV11Y fiLEAIED: (CURIEI) N/A N/A 'f.NfEROFRELEATEI: 4-4- 2.101AL ACTIV11Y RELEA!ED: (CUFIEI) N/A N/A l

A..r 9 a t--

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_[ Q ? h7 Y./j.; i n i ,1-n , s. w: - n. - TABLElA 4 v> i4'

  1. M$hh3ML$[I

? .1 ~ j.y g k s g,' .!L N ..! UNIT.!.QUARTERi! QUARTER 2!EITTOTAL! ~ !.- 2! - ! ERROR, I' ! mgs n W' A..FIIIIDNANDACTIVATIONGAIE!- -i i- !iiTOTALRELEA!E ! CI !, L 47E+02i! 2.90E+42 ! 2.56E+01'_'_! o

.!2. AVG.RELEA!ERATE!-

i i

iFORPERIOD;

!UCI/T ! l.89E+91: ! 3.69E+91 :!" i

i.JPECIFICATIONLIMIT!'%

i3iPERCENTOFTECH.'!n. !; H u y l k h

B. JIODINEI.

>e i !i. TOTAL 10 DINE' l _.!n CI. ! 1.64E43 l ! 1.84E-93 ! 2.59E+0! ! 1131 i .!2. AVG.RELEASERATE! y ,'! FOR PERIOD: .!UCI/I ! 1.34E44 '! 2.33E44 ! i. y p_ _ _ _ 83.PERCENTOFTECH.! I ! SPECIFICATION LIMII! Z ! _ _:e. s t____ C. PARTICULATE!. a. s it !.PART.'WITHHALF-!! CI ! (i.ME-64 ! (1.ME44 ! 2.50E401 ! LIVES ) 8 DAYI e a !2.~ AVG.RELEA!ERATE! !FORPERIOD .!UCI/I! NA. - NA. ! i ____ Li31PEKEENTOFTECH.!.. ! L! IPECIFI*ATION LIhlT! % *- NA NA ! 3_, ____. _ W !bh b ' CI (i.PE-11 l ti.ME _if ! D. M!IW' ~- i p' - !b 70TAL 8tEl%IE'. 8 01 ! 1.%E43 ! i.?tEfM $ 2.50M i ~' '7. M. RELEAfE RAlCf- . i FOR FERIDD 1 30CI/I ! 2.64E44 ! 2.iBE-91 ! j .!1.PERCENTOFTECH.!- s ! IPECIFICATIDN LIMIT! I _'..._____..__ NOTE:. ALL LEIf THAN VALUE! H) ARE IN UCI/NL, AND ARE APPROPRIATELY NOT CONSIDERfD AS POSITIVF. ACTIVITY. -*ITECH.IPEC. LIMIT!:'LIITEDONll0!ESUNNARYTABLE.

h. 3 p

u I diz_'_ __ _m _m .m __m.. 2

g ~ ,.y / ~.# t A i 4 m m O . TABLE 1CL .l, T. ; ;, m ,s, q;7 ] EFFLUE g s g g }(19E 4 l 1 w .CONTINUGUI M0E - BATCHMODE' _i a: y,.i.. i is i QUET R 1 i QUETR 2 i QUETER 1 i QUARTER 2 i j !i NUCl.IDEIRELEA!ED i~ UNIT i .i t 4 i _ _____i sp

i.FIIIIDWGASE!

1 1 l: KR 85: ! CI ! (8.90E46 8 (8.9E46.! (8.90E46.! 6.49E41 ! l, i: i L i..c ' KR 85M~ l' CIL ! 9.89E-92 ! 3.39E41 ! 2. tie-92 ! 2.56E-92 !. ^ i-KR '87 ! CI ! ' 7.7?E-92 ! 2.BiE41 !.1.8BE-95 ' (8.99E46 i .i C,. .i . KR 88 ' ! : CI 1!~.1.49E41 !. 5.41E41 !. 3.68E-95 ! 1.22E42 i'. .g ! - XE133 ? CI ! 3.33E+H ! 4.25E+91 !' i.38E+92 ! 2.37E42 1.

1

'XE135 ! CI ! 7.75E41 ! 5.2iE+M ! 1.37E+99 ! 8.67E41 i: i' 3

XE135N-

! J CI ! 8.59E42 ! 3.28E41 ! 15.90E-97 ! (5.99E-971 il j XE 138 !L CI' _! (3.9E47 ! 4.76E-92 ! (3.90E47 t '(3.99E-97 ? i i 1.66E+99! l .i b I. ._XE 133M CI ! 4.19E-93 !.1.35E41 ! T 4.94E41_! !? ' XE13tM ! CI !-(3.99E47 !-(3.99E47 ! 2.28E+H ! 1.18E+99 ! l i-Ii AR 41 ! ' CI ! 2.16E-93 ! (3.NE-97 ! (3.99E-97 ! ~ 4.94E42 ! .i 3 j d i ! TOTAL FOR PERIOD ! CI ! 4.52E+49 ! 4.93E+01 ! 1.42E+92 ! 2.41E+02 1 e. q f 1 T i2.10DINET = i i . I 131 ! CI :!' 1.94E-93 ! ! 7.77E46 ! 5.93E47 ! 1.84E-93 i _ _. _I 132 - ! - CI !-(1.99L-10 ! (i.NE-te ! U.HE-# ! (1.90E48 ! ) ~ 4. Il'

I G3

? CI' !. 6.63E44 ! 1.17E-03 !' 3.5E46 ! (1.90E-98 i 'i g, 3._._'__..L) C1 ! !.99E43 ! - 1.93E-93 M1.NE-i91 (i.ME-19 j 1 W t. I 135 ~j l4a 6 ez s-u.._ _ n 1 yv i TOTAL FORERIDD ! CI ! ~ 2.79E43 3 4.94E-23 ! 1.14E45 ! 5.9K4? ! ' 3. FARTI(UTE! ~ l n-s_. ..~._.. H i IR 09 ! CI ! (l.Mi-11 ! (1.99E-11 ! (1.99E46 ! (1.99E-98 ! c 4- '} . SR 99 ' _ _! CI ! (1.9E-11'! (1.9E-il i (1.90E48 ! (1.99E-98 ! l e. _i CI134 '! CI ! (1.90E-11 ! (i.HE_11 ! it.99E_98 ! (i.ME48 ! i ___i L C5137 CI ! (1. M E-11 ! (1. ME-11 ! (1.99E-98 ! (1.99E-98 !. - % 149 !-' CI ! U.99E-il ! (1.90E-11 ! U.90E48 ! (i.HE48 !. D' LA149 ! CI ! (1.99E-11 ! (1.90E-11 ! (1.00E48 ! <t.90E48 ! ) ' !.= IETE: - ALL LESI THAM VALUEI (O ARE IN UCI/ML. AND ARE APPROPRIATELY NOT CONSIDERED AS l' j o un_. _. _r._ _ _1.

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,4 yQ"l% ' '~ _,._ ? g *:f: '

u M.y.:

s TARE 2Al wsp-. - .k.] .EFFLUE g g y g g g g g 989) w' k. 1 I', .a_ I i I !:UNIif!90ARTER1.i 3 QUARTER 2 i EIT TOTAL i ! ERROR, 1 ! r ~ ! , j :. A.f FIIIION AND ACTIVATION PRODUCT!J Ti !i.TOTALRELEASE(EX.! !~ I' 4

  • TRIT. GAIES, RPHA)!: CI ' ! ' 2.88E43 ! :7.53E-04 ! ~'.2.59E41' !

,i i !3. AVG.B!llitEDL 2 i '3 CONC. DURING PRD. !UCI/ML!. 2.16E-16 !- 7.13E-11 !. i U

!3.PERCENTOF ~

!L - ! APPLICAKE LIMIT-. !: % .____i a; a a 'It.. TRlilllM

e. N

.!1. TOTAL RELEAIE

!: CI ! 8.98E+61 ! 17.67E+01 ! 2.50E+0i i s

i

!2.' AVG.DILUTD~. !.

' CONC. DURING PRDi J !UCI/NL! L 6.66E46 !' 7.2?E-66 ! : I i. 1!3.PERCENTOF ~ 8 L8 ! APPLICARE LIMIT = ! I'. a a s

C. DITIDLVED AND ENTRAINED GAIES ;

i. a <!f. TOTAL RELEATE' ! CI ! 5.47E-63 ! 6.58E-63 1 2.59E+61! L !2. AVG. DILUTD !.. f!. ~

! CONC. DUR3G PRD. J!UCDN.! 4.10E _19 '_ 6.23E-16 i.
e-L!3.flv@TT i

'! M PLICA 3.1 LICIT ! L ': - 1. !_a

y. y [p ;i._.

.__3 g Nb- ). C@ff RPHA MlhACTIVIli:

7. ?
  1. 2

. !L TEAL RELEASE ,_! C1 ! G.00E 67 ! (l.ME-97 ! 2.56E61 ! .q__- A i-i lE. VOL. OF WAITF ! 1 8 e V ". ! RELEASED (NO D!L.1 !LITEU ! -8.18E+66 ! 9.3 0 96 ! 1.00E+61 ! g i-4, i. !F. VOL. OF DILUTION! .!WATERDURINGPERIOD!LITERI! 1.33E+i9! 1.66E+16 ! 1.00E+0! ! =3. NOTE: ' ALL LEIS THAN VALUES (O ARE IN UCI/HL. AND ARE APPROPRIATELY NOT CONSIDERED AS POSITIVE ACTIVITY. L ' *ITECH.IPEC.LIMITI: LISTED ON DOIE IUMMARf TA K E. 1. i, ' s 9 t _u 1

L ~ TABLE 2B 4 - EFFLUENT AND llAITEgIggNUAL REP 0RT (1989) CONTINUGUSHDDE BAICHN0DE e i e e i i s'. i - iNUCLIPE!RELEAIED! UNIT!00ARTER1! QUARTER 2iEUARTERi! QUARTER 2! i e. .i .i i IR.89 ! CI ! (5.ME-08 ! (5.ME _00 ! (5.00E-08 ! (5.ME-08 i i._ IR 90 ! CI !. (5.ME-08 ! (5.00E-08.! (5.ME-08 ! (5.00E-08 ! 4. i CI 134 ' CI ! (5.00E-07 -! (5.ME47 ! 7.11E-05 ! 1.23E-64 ! i i 3 Cl 137 _. ' _-.1.59E-05 ! (5.ME-07 ! ' t.62E44 ! 2.14E-04i .! CI -! i _. s I 131 ! CI ! (1.00E-06 ! (l. ME _06'! 1.60E-04 ! (i.ME-06 !- l i_ i C0 58 ~! CI- ! (5.00E-07 ! (5.00E _07 !'_2.20E-03 ! 3.45E-04 ! 4._._.. s CD 60 ! CI ! (5. ME-07 ! (5. M E-07 ! 5. % E-05 ! 7.73E-06 i _i FE 59 ! CI ! (5.00E47 ! (5.00E-07 ! (5.00E-07 '_(5.00E-07 ! .. j ZN 65 ! CI ! (5.ME-07 ! (5.00E _07 ! (5.00E47 ! (5.00E-07 ! -{ i______ MN 54 _ -07 ! (5. M E-07 ! (5.00E-07 ! (5.00E-07 ! !~ CI ! (5.00E i .__ i CR 51 ! CI ! (5.00E47 ! (5.ME-07 ! (5.ME _07 ! (5.0E47 ! 'l i i ___IR 95 ! CI ! (5.ME-07 ! (5.ME47. ! (5.00E-07 ! (5.ME-07 ! i - NB 95 ! CI ! (5.00E-07 ! (5.ME-07 ! (5.00E-07 ! (5.ME47 ! MD 99 ! CI ! (5.00E-07 ! (5.00E-07 ' (5.00E47 ! (5.ME-07 i j i TC 99M ! CI ! (5.00E-07 ! (5.ME-07 ! (5.00E-07 ! (5.00E47 ! ___.i BA140 ' CI ! (5.ME47.! (5.00E-07 ! (5.ME-07 ! (5.ME47 ! y LA 140 ! CI ! (5.00E47 ! (5.ME _07 ! (5.00E-07 ! (5.ME47 ! i. i CE141 ! Cl ! (5.00E-07 '__(5.00E47 ! (5.00E47 ! (5.00E47 ! ~ . _. i FE 55 ! Ci ! it.ME46 ! (i.HE46 ! 1.3BE-A4 ! 6.29E-16 ! i.__.._____ i i AG liOM ! Ci ! (5.10E47 ! EME-67 ! 094645 ! (5.MH7 ! a --.___s i TOTAL FOR PERIOD ! CI ! 1.59E-05 ! 0.ME+M ! 2.81E-031 7.53E44 ! I XE133h ! CI ! (1.00E44 i (1,ME-04 ! (1.00E44 ! 2.42E45 ! 3__._.- !'..__XE 133 ! CI ! (1.00E44 ! (1.ME44 ! 5.44E43 ? 6.5tE-03! i. i ~ ! XE135 ! CI ! (1.00E-04 ! (1.NE44 '._2.69E-05 ! 4.33E-05! l 3._ - IOTE: ALL LEIS THAN VALUES (() ARE IN UCI/dt. AND ARE APPROPRIATELY NOT CONSIDERED AS POSITIVE ACLVITY. i ... - - -. -L.-._..

1 4 TMI-1: 1/1/89 6/30/89 i t TABI.E 3A EFFLLT.NT AND WASTE DISPOSAL SEMIANNUAL REPORT ( SOLID WASTE AND IRRADIATED FUEL SHIPMENTS I A. Solid waste shipped off-site for burial or disposal (not irradiated fuel)

1. Type of waste 6

UNIT gh TOTAL 3e

a. 5 pent resins, filter sluoges, m'

45 87 evaporator bottoms, etc. Ci hp.89 5%

b. Dry co=pressible waste, contaminated 8

m 129.45 eeufement, etc. c4 7h17 5%

c. Irradiatec components, control 3

m rod s. e tc. Ci N/A N/A ma

d. Other (describe)

Ci v/r w/n

2. Estimate of major nuclide composition (bv type of waste) a.

Co50 ~ 71, (,h % "-41 b.307 Fr' 97 5.33t Ni63 3 52% b. CoS3 39.04g Os137 10.495 Ni63 10.07% MA1 0.4]t Fess 5 99% l c. t .L. e i ,,_= _ ~ ._a ~ }

3. Solid Wsate Disposition; l

__c.__ Nu :ber of Shi,pnents j Maide cf Transportation 4 Destination he Attached B. Irradiated Fuel Shipments (Disposition) Number of Shipments Mode of Transportation Destination N/A J i - s-t

4 TMI-1 EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT 01/01/89 Through 06/30/89 Table A.3.a '

No. of Shipments Mode of Transportation Destination 4 Tractor-Flatbed Hanford-Richland,.WA 1 Tractor-Cask (Nupac-14/190M) Hanford-Richland,-WA 1 Tractor-Cask (Nupac 14/190M) Barnwell. SC Table A.S.b No. Of Shipments Mode of Transportation Destination

  • 5 Tractor-Flatbed Scientific Ecology Group-Oak Ridge, TN
  • 1 Tractor-Closed Van Scientific Ecology Group-Oak Ridge, TN WASTE SHIPPED AS FOLLOWS:

TABLE A.I.a: Four (4) - 170 Ft.* Steel Liners /Dewatered Resin Five {5) - 178 Ft." Steel Liners / Solidified with Cement One (1) - 49.9 Ft.' EA-50 High Integrity Containers / Mechanical Filters TABLE A.1.b:

  • Fourteen (14)'- 92 Ft." Steel Boxes / DAW for Volume Reduction
  • Eighteen (18) - 7.5 Ft.* Steel Drumo/ DAW for Volume Reduction

'

  • Thirteen (13) - 7.5 Ft.* Steel. Drums /Dil for Incineration - V/R
  • Three (3) - R' x 8' x 20' Cargo Containers / DAW 'for Volume heductien
  • Material Sent to Waste P'.ocessor for Volume Reduction

'I

y l s L ;. l INTERPRETATION OF DOSE SUMMARi T.MLE-The Dose Summary Table' presents the mcximum hypothetical doses to an individual and the general population resulting from the release of gaseous and liquid effluents from TNI-1 during the first half reporting period of 1989. A. Liquid (Individual) L The' first two lines present the maximum hypothetical dose to an L 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 e'er, irrigated. cow milk, irrigated goat milk, irrigated-beef, 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 irrigation pathways apply to the sewage sludge. L The'" receptor" would be that individual.who consumes water from the l-Susquehanna River and fish residing in the plant discharge, while occupying an area of shoreline. influenced by the plant. discharge and consuming the milk and beef fed irrigated ' vegetation. 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 first half of 1989 the calculated maximum whole body dose received by anyone would have been 9.9E-3 mrem to an adult. Similarly, the maximum organ dose would have been 0.013 mrem to the liver cf an adult. B. Gasecas (Incividual) There are seven major pathways coasidered in the dose calculations for gareous effhents. These are: (1) 91ume, (2)' inhalation, ensumption of (3) cow milk, (4) goat milk, (5) '.'egetables, (6) meat, and (7) standing on contaminated ground. thes 3 and 4 present the maximan plur,e exposure at or beyond the site i 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 cr 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. Lines 5 and 6 present the dose which could actually be received by an individual from the noble gas effluents for the first half of 1989. The calculated maximum whole body dose received by anyone from noble gases would have been 0.016 mrem. Similarly, the maximum dose to the skin would have been 0.041 mrem.

.g ( .The ' iodines and particulate section described.in line 7 represents the maximum' exposed organ due _ to iodine and particulate. 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-again reflect the maximum exposed organ for the appropriate age group. The first half 1989 iodines and particulate would have resulted in a maximum dose of 0.16 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) 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 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 summed over all distances and sectors to give an aggregate dose. ll Based upon the calculations performed for the first half of 1989, liquid-l effluents resulted in a whole body population dose of 0.95 person-rem. The naximum critical orgen population dose to the thyroid was 0.98 person-rem. Gaseous effluents resulted in a whole body population dose of 0.081 person-rem. Maximum critical organ population dose to the thyroid was 1.0 person-rem. l. D i o i_____________________

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ist Half 1989 Semi Annual Effluent Report

SUMMARY

OF CHANGES TMI-1 WASTE SOLIDIFICATION FROCESS CONTROL PROGRAM The TMI-1 Wr te Solidification Process Control Program (OP 1104-281 Rev. 10) was revised in the first half of 1989. The change was prompted by Quality Assurance Department Internal Review which recognized a few items in need of clarification to ultimately provide a better control of the process. The changes are as follows: 1. Section 3.0 Limits and Precautions a. Former Step 3.10 (Deleted) This step provided the ability to draw known waste volumes from two (2) separate waste tanks and composite in order to do one verification test. This method was allowable under governing Westinghouse RS procedures. In practice this was never done at TMI-1. The ability to perform it was removed in order to consolidate the procedure and potentially improve overall control of the process. 2. Section 4.0 Test solidification of 4 to 10 wt% Boric Acid (concentrated Waste) d. 2nd Note Before Step 4.1.2 (Deleted) This acte was a reminder of Chemistry personnel to maintain the boric acid sample taken for the verification test heated if not within a pH band in which boric acid stays in solution. At TMI-1 the waste tanks to be solidified are neutralized within the pH band required for verification testing. This note was confusing and r.ot necessary for proper performance of the procedure. b. Step 4.2.4 This step provides the acceptable pH range required for the boric acid sample prior to the verification test. Additional guidance was added in order to lower pH into the acceptable band if it were too high. c. Step 4.2.8 This step was modified to provide guidance to personnel performing the verification test to determine an exact amount of oil present on the test sample. The change was initiated to ensure proper performance and control of the process. i 1

1st Half 1989 Semi Annual Effluent Report l

SUMMARY

OF CHANGES TMI-1 WASTE SOLIDIFICATION PROCESS CONTROL PROGRAM 3. Section 5.0 Test Solidification of >10 to 20 wt% Boric Acid (Concentrated ll Waste) a. 2nd Note Before Step 5.1.2 (Deleted) This change is the same as for. Item 2a above. b. Step 5.2.4 This change is the same as Item 2b above. c. Step 5.2.8 This change is the same as Item 2c above. 4. Test Solidification of Used Precoat a. Step 7.2.6 N? This c'ipnge is the same as Item 2c abovn. 5. Test. Solidification of Bed Resin i a. Step 8.2.10 This change is the same as Item 2c above. These changes are within the bounds of the Westinghouse RS Procedures and the topical report submitted to the NRC for approval to comoly with the stability requirements of 10 CFR 61.

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