ML20234B746

From kanterella
Jump to navigation Jump to search
Revised Pages to Semiannual Effluent & Release Rept for First Half 1987, Correcting Errors in Radioiodine Samples
ML20234B746
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 06/30/1987
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20234B737 List:
References
NUDOCS 8801050660
Download: ML20234B746 (7)
v • d • e


Text

{{#Wiki_filter:T TAltE iC EFFLUENT AND WASTE DI!POIAL SErilANNUAL REPORT ',1987) 6AIE005 EffLUENTI-GROUNL-LEVEL RELEASEI CONTINU0]S H0DE BATCH MODE I l NUCLIDEI RELEAIED UNIT GUARTER 1 i QUARTER 2 l QUARTER t 00ARTER 2 I I i

1. FI!SION GA!ES KR 85 l CI i(8.00E-06I(8.00E-061 1.20E+00l 1.42E-Gi _

KR 85ft i CI I(5.00E-08I(5.00E-08l 1.97E-031 7.16E-02 KR 87 i CI l(8.00E-081(8.00E-08l(8.00E-08I(8.00E-08 KR 88 l CI I(1.00E-07I(1.00E-07l 1.43E-03 1 3.90E-02 XE133 1 CI I (8.00E-08 ! 2.53E+021 5.61E-021 3.46E+02 XE 135 i CI l 4.97E-04 1 2.77E+01 1 3.23E-02 l 1.35E+01 XE 135M l CI J(5.00E-07I i.97E-64I(5.00E-07I(5.00E-07 XE 138 I CI 1(3.00E-07i(3.00E-07l(3.00E-07l(3.00E-07 XE 133t!  ! CI l (2.00E-f? ! (2.00E-07 I 7.64E-04 l 1.25E+00 XE 131M i CI l (3.90E-07 l (3.00E-07 I 6. lie-02 1 1.75E+00 AR 41 l CI i (3.00E-07 I (3.00E-07 ! 4.69E-04 1 3.07E-01 TOTAL FOR PERIOD I CI l 4.97E-04 1 2.00E+02 l 1.36E+001 3.63E+K{

2. 10 DINES O

I 8l 24 lodines 2nd Quarter for I-131 and 

                 ._[_______I I
                                           '0$b".I2
                                           ._ _..         I    ) (1 I 132         i Cl I (1.00E-10 1 (1.00E-10 1 (1.00E-08 1 3.86E-10           I-133 are revised.

I 133 _ l CI i(1.00E-10l 2.41E-07 , (1.00E< B l 7.57E-07 TOTAL FOR PERIOD l CI ,1 0.00E+00 l 9.07E-05 1 0.00E+00 1 3.00E-06 3.FARTICULATEI SR 89 l CI I(1.00E-liI(1.00E-11l(1.00E-08I(1.00E-08 IR 90 l CI l(t.00E-il!(1.0f>E-tll(1.00E-08l(1.00E-08 CS134 I CI I(1.00E-11I(1.00E-il1(1.00E-08I(1.00E-08 C5 137 i CI l(1.00E-11l(1.00E-il1(1.00E-08I(1.00E-08 BA 140 I CI I(1.00E-il!(1.00E-111(1.00E-08I(1.00E-08 LA 140 l CI ! (1.00E-11 l (1.00E-ii I (1.00E-08 1 (1.00E-08 NOTE: ALL LESS THAN VALUES ( O ARE IN UCI/fL. 8801050660 871229 PDR ADOCK 05000289 R PDR C_____________-___________-___-.__--___---________

1AP.LE1A  ! EFFLUENT AND WAITE DISP 05AL SEMIANNUAL REPORT (l?81) GAIEOUI EFFLUENTS-IUnnATION OF ALL RELEASES i UNIT QUARTER 1 QUARTER 2 ESTTOTAL i ERROR. I-A. FIIIION A G ACTIVATION GAIES l

1. TOTAL RELEAIE I CI i 1.36E+00 1 6.43E+02l 2.50E+01
2. A L RELEA!E RATE I l

FORPERIOD UCI/I I 1.74E-01 8.18E+0i

3. PERCENT OF TECH. I SPECIFICATION LIMIT.  %  ! *
  • B. 10 DINES -{
i. TOTAL [0 DINE I  !

1131 CI l(1.00E-08 9.27E-05 1 2.50E+01 B.1. Total Iodine for 2nd Quarter

2. AE RELEASE RATE; I is revised. ]

FOR PERIOD UCI/I 1 N/A 1.iBE-05 B.2. Avg. Release Rate is revised.

3. PERCENT OF TECH. I I l SPECIFICATION LinITl % l W/A 1
  • C. PARTICULATE 1.PART.WITHHALF- 1 I I LIVES ) 8 DAVI CI I (1.00E-04 I (1.00E-04 1 2.50E+0i
2. A L RELEAIE RATE I l F0RPERIOD UCI/5 , N/A I N/A
3. PERCENT OF TECH. I l SPECIFICATION LIMITI % N/A I N/A
4. GR0!S ALPHA i l l HAD10 ACTIVITY l CI 1(1.00E-111(1.00E-11 1

D. TRITIUM 1.TOTALRELEASE l CI i 6.02E-01 1 3.74E-01 1 2.59E+01

2. A L RELEATE RATE:

FORPERIOD  : UCDI l 7.74E-02 4.75E-02

3. PERCENT OF TECH. I SPECIFICATION LInIT  % l *
  • NOTE: ALL LESS THAN VALUES (() ARE IN UCI/HL.
    *% TECH.IPEC. LIMITS: LIITED DN DOIE

SUMMARY

TAI (LE. l E-------_____--_------_-----__---_----. - _ - - - - - - - - - -- - -- _-- ---------a

EXECUTIVE

SUMMARY

Three Mile Island Nuclear Station Unit 1 Effluent and Offsite Dose Report for the Period of January 1,1987 to June 30, 1987 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, 1987. Radiological releases from the plant are calculated from sample analyses of gaseous releases from the plant and liquid sample analyses for discharges to the Susquehanna River. These monitors provide a means for accurate detennination 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 plant- The use of real-time meteorological information permits the determ.aation 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 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 Comission. Liquid discharges made during the reporting period January 1 to June 30, 1987 consisted of 55 Curies of tritium, 0.00057 Curies of noble gases (predominately. Xe-133), and 0.017 Curies of other beta and gamma emitters, predominately Co-58. The quantities of effluents are similar to average semiannual releases from previous Unit 1 operations.

During the reporting period January 1 to June 30, 1987, the maximum  ; hypothetical calculated whole body dose to an individual due to liquid l effluents from Three Mile Island Unit 1 was 0.095 mrem, the maximum hypothetical calculated dose to any organ of an individual was 0.14 mrem to l the liver. Airborne discharges made during this same time period consisted of 0.98 Curies of tritium, 640 Curies of noble gases, and 0.000093 Curies of iodines and no Curies of particulate. These releases are less than average semiannual releases from previous Unit 1 operations. The maximum hypothetical calculated dose to any individual from noble gases was 0.0065 mrem to the skin and 0.0023 mrem to the whole body. Airborne j iodines and particulate are calculated to produce 0.0024 mrem to the Thyroid ' of the maximum hypothetical individual. The total maximum hypothetical whole body dose of 0.097 mrem, received by any individual from effluents from the TMI-1 for the reporting period is 510 times l 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 semiannually in the TMI-l area. In addition, average equivalent dose to the lung from natural radon for the same period is about 90 mrem per quarter. The calculated total whole body population dose from all plant releases is 0.75 man-rem. This is 140,000 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 by the Nuclear Regulatory Commission in Appendix I of 10 CFR 50.

INTERPRETATION OF DOSE

SUMMARY

TABLE The Dose Summary Table presents the maximum hypothetical doses to an individual and the general population resulting from the release of gaseous and liquid effluents from TMI-1 during the second quarter reporting period of 1987. A. Liquid (Individual) The first two lines present the maximum hypothetical dose to an i ndividual . Presented are the whole body and critical organ doses. Calculations are performed on the four age groups and eight organs recommended in Regulatory Guide 1.109. The pathways considered for TMI are drinking water, consumption of fish, irrigated cow milk, irrigated goat milk, irrigated beef, 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 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 l 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. i For the second quarter of 1987 the calculated maximum whole body dose I received by anyone would have been 5.1E-2 mrem to an adult. Simil arly, i the maximum organ dose would have been 7.4E-2 mrem to the liver of a j teenager. j B. Gaseous (Individual) There are seven major pathways considered in the dose calculations for gaseous effluents. These are: (1) plume, (2) inhalation, consumption of i (3) cow milk, (4) goat milk, (5) vegetables, (6) meat, and (7) standing ' on contaminated ground.  ! l 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 Sumary 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 second quarter of 1987. The calculated - maximum whole body dose received by anyone from noble gases would have been 2.3E-3 mrem. Similarly, the maximum dose to the skin would have been 6.4E-3 mrem. 

                                                                                )j 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. 1 1 The second quarter 1987 f odines and particulate would have resulted in a maximum dose of 2.4E-3 mrem to the thyroid of an infant 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 sumed over-all pathways and the affected populations. Liquid person-rem is based upon the population i 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 j 3 around TMI. Population doses are summed over all distances and sectors l to give an aggregate dose.  ! Based upon the calculations performed for the second quarter, liquid effluents resulted in a whole body population dose of 0.56 person-rem. The maximum critical organ population dose to the liver 'was 0.59  ; person-rem. Gaseous effluents resulted in a whole body population dose of 9.6E-2 person-rem. Maximum critical organ population dose to the skin ' was 0.32 person-rem. ) l l 1 1 I e

A i111I I1I1l1II lll s s t0t y i 5il m iRi e mr 50 0 0 - - 5 LFL t . - - . C r 15 5 0 - - 7 a 1 0 u 1 Q-Ii! lI111 I111lllI l1i l 6 0 62 6 a 4 5 7 44 1 u 77 0 0 00 0 n e n 1 0 0 0 00 0 l A b . atlIl11 I111ll1I i1l f ci e oim s) M l i y M O dDe om O  % pL l r R p r 2 R e F A e 45 1 4 - - 3 F t n - t 1 1 - - 0 7 aon 6 17 r 31 - - 1 8 mio 6992 8 a 0 0 0 its 5503 T9 u T 9 t ar I 1 Q I 1 sl e 0000 N N , Eup U , ili lI11i IIlllliI Ili U 0 p( 0 o t R3 R 3 P O ) O r F e d Fe n o p n rr W W e Su nia 11 N N WW E Su E J R EJ oDw W W S i o rr S e O t t oo O D a ( tt D s c pp 2 o L D ot ee 3 3 00 0 N e y E 1 D A U E S L s) i m cc ee 1 4 1 4 55 88 0 7 O I l bn d o .d L Tr D I D( RR 2 2 22 T aa B B B I e I hV - A h cg A Nt V gE L ir l rl T U r I uR Ill lIilI Ill1li11 Iii Ug l O aean a Do P u p t vti u Q N r Oor p oiok I h t p t t n P h A _ TLT d a M t n M eu l n - - ll o U go ue - - ll f U M Ar d e - - AA n M c I7 G AT I I e X8 X 7 S A9 - A 8 M1 ili lI!11 IlIllllI ill M9 1 F , - F , dd uu O1 O t iioo 1 n uuee qqss Yl d Y e Ri e 33 3 Rl Ai r u iiaa LLGG Ar t ) 3 2 l HpA aem 14 - - - - - M Mp f P U mse ior 57 00 E 6 E 4 EE 34 E 4 U A f E )) 01 

                                                                                                                          )

S tDm S 8911 s ( 00 5 1 26 2 (((( E - llI i!111 I1lil1iI 1il 

                                                         )

e y d a 

                                                                   )

d y l b d r ad an o emero ca B s smB d i g oao- i l r l r DmDal o pO ae m t an r p tv rareti y A oi i gib ok h TL A( A(TS T - IliiIill Illl1llI lIi s e s s ss t a a ea &a G G GG l t dd - eu n ii e e ee nc e uu i dti_ l l ll u qq b b bb l ii o o oo or f LL N N NN I a f P E )) ) ) )) ) 12 3 4 56 7 (( ( ( - (( ( ll1lilllIll11llIlli 

                          '}}
Retrieved from "https://kanterella.com/w/index.php?title=ML20234B746&oldid=3194963"