ML20209A951

Submits Corrections to Semiannual Effluent & Release Repts Submitted W/Listed ltrs.Marked-up Rept Pages Encl

ML20209A951
Person / Time
Site:	Crane
Issue date:	01/27/1987
From:	Hukill H GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
5211-87-2012, NUDOCS 8702030484
Download: ML20209A951 (17)

Text

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.o GPU Nuclear Corporation g

gf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

January 27, 1987 5211-87-2012 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

Dear Sir:

Three Mile Island Nuclear Station Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Semi Annual Effluent and Release Report Revisions Ref. 1.

GPUN Letter 5211-84-2048, dated March 28, 1984 2.

GPUN Letter 5211-84-2219, dated August 31, 1984 3.

GPUN Letter 5211-85-2038, dated March 1,1985 4.

GPUN Letter 5211-85-2140, dated August 29, 1985 5.

GPUN Letter 5211-86-2036, dated February 28, 1986 6.

GPUN Letter 5211-86-2148, dated August 29, 1986 The above referenced GPUN letters transmitted Semi Annual Effluent and Release Reports. GPUN has recently determined that several problems existed with these reports. This letter will serve to correct those problems.

A.

Technical Specification 6.9.5.2 requires in part that "This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to individuals due to their activities inside the site boundary (Figures 5-3 and 5-4) during the report period." This wording which identifies individuals was submitted and approved based on Rev. O of NUREG 0472. Subsequently, Rev. 2 of NUREG 0472 clarified individuals to mean members of the public. This is consistent with NUREG 0133 Section 2.2 definition of unrestricted area.

GPUN, as an oversight, has not been addressing this requirement.

It is the determination of GPUN that the term individuals is interpreted to o,

sgg mean members of the public. TMI-l has no areas inside the site boundary ruo a.

that are open to members of the public.

Based on the above, the 58 following should be added to each of the above six (6) references.

So "TMI-1 Tech. Spec. Section 6.9.5.2 requires an assessment of the E

radiation doses from radioactive liquid and gaseous effluents to gg individuals due to their activities inside the site boundary.

n<

Individuals is construed to mean members of the public.

Since the public does not have unrestricted access to TMI-1, no assessment of dose is og applicable. "

ma.tC GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation 4

5211-87-2012 January 27, 1987 B.

The Semi Annual Report submitted in Reference 5 contained Table 6 titled

" Maximum Off Site Doses and Dose Commitments to Members of the Public."

However, the following paragraph should also have been included in the cover letter.

In accordance with HRC letter of March 30, 1983, to all Licensees regarding reporting of Off-Site Radiation Doses, we have included Table 6, " Maximum Off-Site Doses and Dose Commitments to Members of the Public." Compliance with the dose design objectives in 40 CFR 190 are demonstrated by compliance with 10 CFR 50, Appendix I Off-Site Radiation Doses, and also by the fact that there are no other fuel cycle facilities within 8 kilometers of THI-1.

C.

The Semi Annual Report submitted in Reference 6 contained some minor errors which have recently been identified.

The following portions have been revised and should be replaced in the referenced report. The corrected items have been circled and correspond to the below listed reason for change.

In addition, the Executive Summary has been rewritten to note these corrections.

1.

SUPPLEMENTAL INFORMATION:

a.

Average Energy - difference due to rounding for E beta and gamma, b.

5.A.2 Total time period for the second quarter was 11041 min.

versus 11042 min.

c.

5.A.3 Maximun time period for a batch release (liquid) is 338 min, for the 1st Quarter and 390 min. for the second

quarter, d.

Under Gaseous Releases - B.2. - Additional time had been added to batch releases from Reactor Building in-leakage calculations, therefore the total time is less.

B.3. - Maximum time period for a gaseous batch release was 1.7?E4 versus 1.73E4 min.

B.4 -

Average time changed due to total minutes being changed.

e.

Under Gaseous Releases - 6.B.2 difference due to rounding.

l 2.

TABLE lA - GASEOUS EFFLUENT

SUMMARY

TABLE i

a.

B.2, D.1, D.2 difference due to rounding.

l 3.

TABLE 1C - GAS EFFLUENT DATA a.

Under - 1. Fission Gases and 2. Iodines 1.

First Quarter Continuous

-Xe-133, I-131, difference due to rounding

5211-87-2012 January 27, 1987

-Xe-135 curies are higher by 1.37 curies in the continuous column due to previously including continuous release G8603532 in the batch release column for the first quarter.

2.

First Quarter Batch

-I-131 and Iodine total for first quarter batch -

differences due to rounding.

-Xe-135 curies are lower by 1.37 curies in the batch column due to excluding continuous release G8603532 in the batch column for the first quarter.

3.

Second Quarter Batch

-Kr-85n, Xe-135, Xe-131m - dif ferences due to rounding.

4 TABLE 2A - LIQUID EFFLUENT

SUMMARY

TABLE a.

Under A. Fission and Activation Products A.1 and A.2 for the second quarter are lower by 1.06E-4 curies due to change in Sr-90 curies on Table 28 (5.d.1 and 5.d.3).

b.

Under F. Volume of Dilution Water j

First Quarter Volume = 1.20E10 liters versus 8.22E10 liters.

c.

Under B. Tritium B.1 - difference due to rounding l

d.

Under A, B, and C l

A.2, B.2, C.2 for the first quarter are changed due to volume of dilution water change as noted above, e.

Under B and C for the Second Quarter B.2 and C.2 - difference due to rounding 5.

TABLE 2B - LIQUID EFFLUENT DATA a.

First Quarter Continuous 1.

Xe-133 curies are lower due to a calculation error in l

continuous release L8603510.

5211-87-2012 January 27, 1987 b.

First Quarter Batch 1.

Xe-135 has a positive 1.33E-4 curies rather than less than LLD due to calculational error, c.

Second Quarter Continuous 1.

I-131 LLD is less than lE-6 versus less than SE-7.

d.

Second Quarter Batch 1.

Sr-90 curies are 1.06E-4 curies lower due to an error of including Sr-90 in April continuous releases L8604514, L8604515, L8604516, L8604517.

Sr-90 was not found in any continuous releases.

2.

Ba-140 and La-140 are listed separately rather than individually.

3.

Total for period difference due to Sr-90 error above.

4.

Xe-135 difference due to rounding.

6.

EXECUTIVE

SUMMARY

/ Semi-Annual Off-Site Dose Calculations a.

Revised and attached.

7.

TABLE 2 a.

Values for Liquid - Total body revised due to above noted revisions.

b.

Values for Liquid - Item 2 are now for Liver in place of Bone -

applicable organ with highest dose changed.

Sincerely, H. D. Hukill Vice President & Director, TMI-l HDH/DVH/spb:0755A cc:

T. Murley, NRC

= -

OFLe is.4ICJhn.,4.c G m.s au ai SL'PPLEMENTAL ENFORPA710N FACILITY:

IMIUNET1 LZCENIE:

DfR99-289

1. REGULATORY LIMITI - - - REFER TO TMI UNIT 1 TECHNICAL IPECIFICATIONI MB ACTIVATION GAIEI:

{.{

TEgI-LIVEI ) 8 DAYI:

2. MAXIlpl PERMI!!!BLE CONCENTRATIONI - - - 19 CFR 29. APPENDIX B TABLE II g D g i g p g DETERMINING ALLOWABLE RELEAIE

{. ggMD ACTIVATION GAIES:

C. PARTICULATEI HALF-LI'EI ) 8 DAYI:

D. LIQUID EFRUINTI:

3. AVERAGE EERGY M12M FReM FFBIHf ATTMrfeRAEF AertICABLE E-BAR BETA = 0.257 E-BAR GAMMA = 9.285 E-BAR BETA MD GMMA =@ 1

/ct

4. MEAIUREMENT! MD APPROXIMATIONI 0F TOTAL RADI0 ACTIVITY 0EfE$bfhl0 fEC hfhf UE I H0 I i: fii E " ' " " Sa " 5GjE!E!F""ct="

hPG IPECTROMETRY GAI R0W PROPORTIONAL, C. PARTICULATEI PETASPdCTROMETRY D. LIQUID ETRUENTI:

HPGE IPECTROMETRY. LIQUID ICINTILLATION

5. BATCH RELEASEI b OkThi QUh INL GA A. LIQUID QUARTER 1 ' QUARTER 2

/b lhALTE O

A CH RELEASEI.

(MIN.)

i T

YhAG f b f $ $A fN.*f

5. MINI M TIME PERIOD FOR A BATCH RELEAIE: (MIN.)

67. !

119.

6. AVERAGE ITREAM R0W DURING PERIODI 0F RELEAIE 0F EFFLUENT INTO A R0 WING ITREM:

(CFM) 3.57E+96

' 2.08E+06 B. GAIEDUI l

b ifENCD ffCHRELEASEI:

(MIN.)

)

O

3. MAXI M TIME PERIOD FOR A BATCH RELEAIE: (MIN.)

52

!C + 77#. J 4 ld

4. AVERAGE TIME PERIOD FOR BATCH RELEASES: (MIN.)

2192 ? 4

5. MINIMUM TIME PERIOD FOR A BATCH RELEAIE: (MIN.)

6. ABNORMAL RELEAIEI NUMBER OF RELEAIES: ! 2. TOTAL ACTIVITY R.iLEAIED: (CURIEI)

N/A N/A B.GAIE0VI i9.99 4

{ e-2.'

AC IV Y D: (CURIEI)

b!E0h5Efffubff-kN i

e i

e i

! UNIT! QUARTER 1;! QUARTER 2!EITTOTAL!

.' ERROR. I !

A. FIIIIW AND ACTIVATION GAIEI

!1.TOTALRELEASE

! CI ! 1.7tE+03'__5.96E+02' 2.59E+91!

!2. AVG.RELEAIERATE!

! FOR PERIC)

!UCI/I' 2.20E+62 ! 7.58E+01 !

i.__

...__.i

!3.PERCENTOFTECH.!

! IPECIFICATION LI.'t!T! I i

B. 10DINEI i

it.TOTALIODINE I131

! CI ' 4.27E-96 ' 2.62E-05 8 2.50E+61!

b D

!UCI/I '

!3.PERCENTOFTECH.!

i i

! IPECIFICATION LIMIT! I C. FARTICULATEI i__.

it.PART.li!THHALF-!

i

! LIVEI ) 8 DAYI. _ _. '. _. -CI ' (1.06E-04 ' 4.38E-06 ' 2.59E+61 !

i

!2. AVG. RELEAIE PATE!

! FOR PERIOD

!UCI/I' N/A

. '..5.57E-67!

-i i..

!3.PERCENTOFTECH.!

! IPECIFICATION LIMIT! I '

N/A i

bk TY CI (1.00E-!! I(i.e9E-11 i

i D. TRITIUM i

.i

!1.TOTALRELEASE

' CI '.._8.27E+99 !/1.14E-61 ) 2.50E+01 ! e d ct i

__..___..W._-

!2. AVG. RELEA!E RATE!

Q j

,! FOR PERIOD

!UCI/I ' 1.06E+09 ' i.45E-9' i

!3.PERCENTOFIECH.!

i i

! IPECIFICATION LIMIT! I.'

i t

NOTE: ALL LEII THAN VALUES (() ARE IN UCI/ML.

l il TECH. IPEC. LIMITI: LIITED ON DOIE

SUMMARY

TABLE.

t

h.h5 LN.5-YL Eb CONTINU0VIMODE BATCHMODE i

i. -

i i

e a

i e

i

! NUCLIDE! RELEASED i (MIT i QUARTER 1 i QUARTER 2 i GUARTER 1 ! QUARTER 2 i 1.FI!!!ONGAIEI i ___ ________

'..(.8.96E-06'_..t.68E-62'..(.8.96E-06'(8.96E-06!

KR 85 _ _ _ _ _.. '. CI i

i.__..

N..I.

• 4 S.O2 I *.06E-62 ' 4.72E-61'[78E-62 3 ct,3 E.__.!5"._

__.__...' l.00E-63 8 1.64E-64 ' (8.96E-08 ' (8.66E-68 !

KR 87

! CI i.

KR 88 CI ! 2.69E-62' 4.67E-63 ! 2.54E-61 * (1.90E-67 !

..__.____.___.__..__'...___..k38E+62)1.9tE+02' 3 4. !

1.30E+63 ' 3.82E+02 !

XE133...__.' CI '

_i i.____

! UI '.

_I*03E+61 ! 6 41E+ )6 [-.55E-Q "

34.I

!..____b5 XE135M

! CI ' l.41E-62 ' 9.85E-63 ' (5.66E-67 ' (5.96E-67 !

3d 3C5 XE138

' CI. ' (3.96E _67 ! (3.96E _67 ' (.3.90E-67 ' (3.66E-67 !

i.__....___..___.

CI.__' 2.t6E _62 !1. tie-93 '.._9.43E+66 ' 1.68E+66 !

XE133M i_....____.__.__. '

i

!..____*.$_1.33..' UI.' (3.96E-67 ',(3.96E-67 ! 1.37E+g!(2.46E+6e 3 a. 3 i

AR 41

! CI ! (3.96E-67 ' (3.90E-67 '. 4.76E-61 ' (3.96E-67 !

i,.

3.87E+021 3.fk+U 3 09E+02 ' 1.34E 63 '

ibiUbRPERIOD'CI 2.10 DINES i.____.

.- -- ^

^-

' CI !(2.85E-66)(1.09E-12'(142E-06J2.62E-05l 3 a.,

l I 131 CI ' (1.69E-19 ' (1.69E-19 ! (1.96E-08 ' 5.57E-06!

3 (A 2 I 132 i

'._CI.. ' 9.42E-67 ! (1.09E-19 ! 3.66E-67 '_ 2.76E-06 '

I 133 I

^

e

'TOALFORPERIOD',,,CI'3.86E-06',0.00E+00'd.78E-96).3.45E-65]!

4 3 a_. R_

{

3. PARTICULATEI i

i l

IR 89

' CI ' (1.00E-11 ' (1.96E-it '..(.1.66E-68 ' (1.00E-68 !

i I

i ___._

IR 96

.__'.____.-' (1.90E-11 ' 4.38E-06'(1.96E-06'(1.96E-68!

CI l

CI134

' CI.' (1.96E-it * (1.96E-11 '.(.1.66E-68 ' (1.96E-68 !

l CI137.__.. ' CI ' (1.66E-!! ! (1.00E-il ' (1.96E-68 ' (1.00E-68 !

l BA 146

' CI ' (1.69E-11 8 (1.96E-it '_.(.1.90E-68 ' (.1.96E-68 !

1

_._.. i

. ' (1.00E-il ' (1.96E-11 ' (1.96E-68 ' (1.90E-68 !

i LA146

' CI i

t NOTE: ALL LEI! THAN VALUEI ( O ARE IN UCI/ML.

t I

TABLE 2A bI 0A

._____i l

IT TOTAL i

! UNIT ! QUARTER 1 ',! QUARTER 2 ! {MM. I !

i i

A. FIIIION AND ACTIVATION PRODUCTI e

i____

!!.TOTALRELEASE(EX.'

i f,4

! TRIT.,GAIEI, ALPHA)! CI ! 1.50E-03 ' 7.26E-04 2.50E+01 !

s__.

i M

00

'D RD.

1/ML!

!3.FERCENTOF 4d

! APPLICABLE LIMIT' I.__'__.

i.____..

.i B. TRITIUM

~

.__.i

' CI !(6.79E+09! 5.41E+0! ' 2.50E+01,' d 4C

!!.TOTALRELEAT n

!2. AVG. DILUTEI 4 df

! CONC. DURING fRD. !UCI/ML!

5.iiE-06',

i

!3. FERCENT OF

! AFPLICABLE LIMIT ! %

i

-i C. DIIIOLVED AND ENTRAINED GA!EI i______

i

!1.TOTALRELEAIE

! CI ' l.09E-02' 5.09E-03! 2.50E+01!

!2. AVG. DILUTED 4e_

! CONC. DURING PR). !UCI/ML! 9.01E-10 4.81E-10 '

i

!3.PERCENTOF

!APPLICABLELIMIT D. GROIS ALFHA RADI0 ACTIVITY 2.50E+01!

!!$~TbTALRELEAIE

' CI ' (1.00E-07 ' (1.60E-07 '

-i i

i-

!E. YOL. Of liAITE !

!RELEA!ED (N0 DIL.) !LITERI! l.43E+07 ' 1.22E+07 ' 1.00E+01 !e i

i

!F. VCL. OF DILLTION!

!niATER DURING PEF.IOD !LITERI! i.20E+10 1.06E+10 ' 1.00E+01 !

h b 2

i i

NOTE: ALL LESI THAN VALUEI (() ARE IN UCI/ML.

• I TECH. IPEC. iIMITI: LISTED ON DOIE IUMMARY TABLE.

EFFLUENTANDWASTE9HP0fAL!ENTANNUALREPORT(1986)

LfMD EFFLUENTS CONTINU0VIMOK BATCHMODE i

i e

i i

e i

i

!NUCLIMJRELEASED!UNITiQUARTERIiQUARTER2iQUARTER1iQUARTER2i e

i i

i e

a i

i

~

.i

__ ' __........'.__.....__' _.__.. -68 '. ( 5. 9E48 !

! CI (5.96E68 (5.96E-68 (5.9E IR 89 l_... "..

' CL.i.L'2**_i.!!2:* ' (?:"~*.i @... ___i

%I

=

..........-....' (5.9E-67 ' (5.96E-67 ' (5.9E-07 '...l.56E-66 !

i CI134

' CI CJ137..___'_..

' 7.67E-64 ! 4.28E-64 !..........'....8.57E-65 !

1.31E-64 CI i_._

!. I '!1

.__.$_ !..b.}:!.#Eg,[.--MM,,,4;,q,,y,l,,}.36E,,j,l -

5c

'(5.90E_67'(5.90E_67'_.1.62E-95'._.3.14E-65i C0 58

! CI i

i ____....-

i.__... ___..___....'...-CI ! (5.00E-67 ' (5.9E-67 ! 1.84E-65'__(5.96E-67!

i C0 66 FE 59

' CI__'.(5.9E-67'(5.99E-67!(5.96E-67'..(.5.96E-67!

i ZN 65

. '. __.' (5.00E-67 ' (5.9E _67 ? (5.00E-67 '..(.5.90E-67 !.

CI

'. _ _ _ _.... _ _ _ ' _...(5.96E-67!(5.96E-67!(5.9E-67!

MN 54 CI (5.96E47

'__ ___.(5.00E-67 ! (5.00E-67 ' (5.96E-67 ' (5.9E47 !

CI CR 51

.____e i_.

ZR 95

! CI ' (5.96E47 ! (5.00E-67 ' (5.9E47 ' (5.9E-67 !

NI 95.__....'____...'.(5.96E-67!(5.90E-67'(5.90E-67!(5.90E-67!

CI

._____i i.

.___'_.___(5.00E-67!(5.00E-67'._(_5.90E-07!(5.96E-67i MO 99

? CI

..____..'____. ' (5.00E-67 '__(5.00E _67 '.(5.96E-67 ! (5.9E47 !

CI TC 99M i

{!

BA 149

' CI ' (5.99E-07 ? (5.99E-67 ' (5.9E-67 ! Q-0)5 Id 2

i..

~

!~~5!![ ' CI1!! *d7 ' E558i (5.m47 628E45 p -

M CE 141

.' (5.00E-67 ' (5.99E-67 ' (5.96E-67 ' (5.9 E -67 !

i_.____..____.__.. ' CI i

.__'_.. __..(1.90E-06'(1.00E-66'.2.8E-65'.(1.00E-66i FE 55

' CI i,...

.____.==

=

6d,3 6]lE44 ' [2.99E-64 !

lTOTALFORPERIOD! CI!j81E-64' 4.28E-94 '

i..

..'.__.' (1.9E44 ' (1.09E-64 '..(.1.96E44 ' 9.62E-06 !

CI KR 85M

...____i i

CI!648E_-64)(1.90E-64'[-t.04E-62'4.9

.6ct i

XE 133 i._.

CI ' (l.99E-64 ' (1.99E-64 !

33E-64)(13E-64; 6b XE 135 1

=

D g* 4

~

EXECUTIVE

SUMMARY

Three Mile Island Nuclear Station Unit 1 Effluent and Offsite Dose Report for the Period of January 1,1986 to June 30, 1986 This report summarizes the radioactive liquid and gaseous releases (effluents) from Three Mile Island Unit I 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, 1986.

Radiological releases from the plant are measured by installed plant monitors sampling the plant stack for gaseous releases and liquid monitors for discharges to the Susquehanna River. These monitors provide a means for accurate determination of the type and quantities of radioactive materials being released to the environment.

Calculations of the maximum hypothetical dose to an individual and the total population around Three Mile Island due to radioactive releases from the plant are made utilizing environmental conditions that existed at the time of the relcase.

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 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 j

hypothetical dose to any individual and to the total population within 50 l

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.

The maximum hypothetical doses are conservative overestimates of the actual offsite doses which are likely to occur. For example, the dose does not take I

D

- - - - ~, - -,, -., - - -, - -... -. ~

.,,,_.n

= -

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.

Liquid discharges made during the reporting period January 1 to June 30, 1985 consisted of 120 Curies of tritium, 0.016 Curies of noble gases (predominately Xe-133), and 0.0022 Curies of other beta and gamma emitters, predominately Cs-137. The quantities of effluents are similar to average semiannual releases from previous Unit 1 operations.

During the reporting period January 1 to June 30, 1986, the maximum hypothetical calculated whole body dose to an individual due to liquid effluents from Three Mile Island Unit 1 was 0.018 mrem. The maximum hypothetical calculated dose to any organ of an individual was 0.027 mrem to the thyroid.

Airborne discharges made during this same time period consisted of 8.4 Curies of tritium, 2300 Curies of noble gases, and 0.00004 Curies of iodines and 0.0000044 Curies of particulates.

These releases are less than average semi-annual releases from previous Unit 1 operation.

The maximum hypothetical calculated dose to any individual from noble gases was 0.026 mrem to the skin and 0.0091 mrem to the whole body. Airborne particulates are calculated to produce 0.0017 mrem to the bone of the maximum hypothetical individual.

The total maximum hypothetical whole body dose of 0.027 mrem, received by any individual from effluents from the TMI-1 for the reporting period is 1850 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 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 0.95 man-rem. This is 230,000 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 1% of the annual limits established by the Nuclear Regulatory Commission in Appendix ! of 10 CFR 50.

l

INTERPRETATION OF DOSE StNMARY 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 THI-1 during the first quarter reporting period of 1986.

A.

Liquid (Individual)

The first two lines present the maximum hypothetical dose to an i ndivi dual.

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, and standing on the shoreline influenced by TMI effluents. The latter two pathways are considered to be the primary recreational activities associated with the Susquehanna River in the vicinity of TMI.

The " receptor" would be that individual who consumes water from the Susquehanna River and fish residing in the plant discharge, while occupying an area of shoreline influenced by the plant discharge.

After calculating the doses to all age groups for all eight organs resulting form 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 croup that received the largest dose.

For the first quarter of 1986 the calculated maximum whole body dose received by anyone would have been 1.1E-2 mrem to an adult.

Similarly, the maximum organ dose would have been 1.7E-2 mrem to the liver of a teenager.

B.

Gaseous (Individual)

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 boundary.

The notation of " air dose" is interpreted to mean that these doses are not to an individual, but are considered to be the maximum dose that would have occurred at or beyond the site boundary. The Dose Summary Table presents the distance in meters to the location in the affected sector (compass point) where the thecretical 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 quarter of 1986. The calculated maximum whole body dose received by anyona from noble gases would have been 7.1E-3 mrem.

Similarly, the maximum dose to the skin would have been 2.0E-2 mrem.

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 again reflect the maximum exposed organ for the appropriate age group.

The first quarter 1986 iodines and particulates would have resulted in a maximum dose of 1.7E-4 mrem to the thyroid of a teenager residing 2400 meters from the site in the SSE sector.

No other organ of any age group would have received a greater dose.

C.

Liquid and Gaseous (Population)

Lines 8 - 11 present the person-rem doses resulting from the liquid and gaseous effluents. These doses are summed over all pathways and the affected populations.

Liquid person-rem is based upon the population encompassed within the region from the TMI outfall extending down to the Chesapeake Bay.

The person-rem for gaseous ef fluents are based upon the 1980 population and consider the population out to a distance of 50 miles around TMI. Population doses are summed over all distances and sectors to give an aggregate dose.

Based upon the calculations performed for the first quarter, liquid effluents resulted in a whole body population dose of 0.29 person-rem.

The maximum critical organ population dose to the thyroid was 0.32 person-rem.

Gaseous effluents resulted in a whole body population dose of 0.24 person-rem. Maximum critical organ population dose to the skin was 0.79 person-rem.

,,-,------.---,----a, y---y-_

n-

INTERPRETATION OF DOSE StM1ARY TABLE The Dose Summary Table presents the maximum hypothetical doses to an individual and the general population resulting from the release of gaseous i

and liquid effluents from TMI-1 during the second quarter reporting period of

1986, i

A.

Liquid (Individual)

The first two lines present the maximum hypothetical dose to an l

i ndivi dual. 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, 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 i

River in the vicinity of TMI.

The " receptor" would be that individual who consumes water from the Susquehanna River and fish residing in the plant discharge, while occupying an area of shoreline influenced by the plant discharge.

I Af ter calculating the dnses to all age groups for all eight organs resulting form 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 group that received the largest dose.

For the second quarter of 1986 the calculated maximum whole body dose received by anyone would have been 6.5E-3 mrem to an adult.

Similarly, the maximum organ dose would have been 9.8E-3 mrem to the liver of a teenager.

B.

Gaseous (Individual)

There are seven major pathways considered in the dose calculations for gaseous effluents. These are:

(1) plume, (2) inhalation, consumption of l

(3) cow milk, (4) goat milk, (5) vegetables, (6) meat, and (7) standing on contaminated ground.

Lines 3 and 4 present the maximum plume exposure at or beyond the site boundary. The notation of " air dose" is interpreted to mean that these doses are not to an individual, but are considered to be the maximum dose that would have occurred at or beyond the site boundary.

The Dose Summary Table presents the distance in meters to the location in the affected sector (compass point) where the theoretical maximum plume exposure occurred.

It should be noted that real-time meteorology was l

used in all dose calculations for gaseous effluents.

Lines S and 6 present the dose which could actually be received by an individual from the noble gas effluents for the second quarter of 1986. The calculated j

maximum whole body dose received by anyone from noble gases would have been 2.0E-3 mrem. Similarly, the maximum dose to the skin would have l

been 5.7E-3 mrem.

l l

l l

{

l The iodines and particulates section described in If ne 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 again reflect the maximum exposed organ for the appropriate age group.

The second quarter 1986 fodines and particulates would have resulted in a l

maximum dose of 1.7E-3 mrem to the bone of a child residing 2400 meters from the site in the NNE sector.

No other organ of any age group would have received a greater dose.

C.

Liquid and Gaseous (Population) i Lines 8 - 11 present the person-rem doses resulting from the liquid and gaseous effluents.

These doses are summed over all pathways and the affected populations. Liquid person-rem is based upon the population encompassed within the region from the TMI outfall extending down to the i

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 sumed over all distances and sectors l

to give an aggregate dose.

1 Based upon the calculations performed for the second quarter, liquid effluents resulted in a whole body population dose of 0.34 person-rem.

The maximum critical organ population dose to the liver was 0.34 person-rem.

Gaseous effluents resulted in a whole body population dose of 6.8E-2 person-rem. Maximum critical organ population dose to the skin was 0.22 person-rem.

i 4

TABLE 1 l

UNIT 1 First Quarter Dose Report O CHAN6E.S I

SUMARY OF MAXIMUM INDIVIDUAL DOSES FOR UNIT 1 FROM January 1,1986 through March 31,1986 l

l l

l Estimated l

I Location I

% of I

Limits (nres) l l

l l Applicable l Dose l

Age l

Dist Dir l

Applicable l 10 CFR 50 Appendix I l l Effluent i

Organ I

(ares) l Group I

(m)

(toward) l Limit l

Limits (area) l l

l l

1-1 l Quarterly I Annual I Quarterly l Annual l

l 1

I i

l l

l 1

l l

1 l(1) Liquid l Total Body l

1.1E-2 l

Adul t l

Receptor 1 1

0.74 l 0.37 l

1.5 1

3.0 l

l(2) Liquid l Liver l

1.7E-2 l

Teen i Receptor 1 1

0.34 1 0.17 1.

5.0 l

10.0 l

i l

1 l

1 l

1 I

l I

l l

1 1

I I

I I

I I

l 1

l 2413 NNE l

0.24 l 0.12 1

5.0 l

10.0 l

l(3) Noble Gas l Air Dose l

1.2E-2 1

l l (gamma-arad) l l

l l

l l

l l

l 2413 NNE l

0.32 1

0.16 l

10.0 1

20.0 l

l(4) Noble Gas l Air Dose 1

3.3E-2 l

l l (beta-arad l

l l

l l

l l

l l

_ 5.0 l

l(5) Noble Gas l Total Body l

7.lE-3 l

All 1

3000 NNE l

l 0.14 1

l 3000 NNE l

l 0.13 l

l 15.0 l

l l(6) Noble Gas l Skin l

2.0E-2 l

l l

1 l

l 1

I l

l l

l I

I I

I I

I I

I l

s l(7) Iodine &

I Thyroid l

1.7E-4 1

Teen l 2400 SSE l

2.4E-3 l 1.2E-3 l

7.5 l

15.0 l

l Particulatesl l

l l

l l

l l

l

SUMMARY

OF MAXIMUM POPULATION DOSES FOR UNIT 1 FROM January 1,1986 through March 31,1986 Estimated i

Applicable Population Dose Ef fluent Organ (person-rem)

(8) Liquid Total Body 0.29 (9) Liquid Thyroid 0.32 (10) Gaseous Total Body 0.24 (11) Gaseous Skin 0.79 i

~

TABLE 2 UNIT 1 Second Quarter Dose Report SupMARY OF MAXIMUM INDIVIDUAL DOSES FOR UNIT 1 FROM April 1,1986 through June 30,1986 j

i l

l Estimated i

I Location I

% of I

Limits (mres) l i

l l Applicable l

Dose l

Age l

Dist Dir l

Applicable l 10 CFR 50 Appendix I l

}

l Effluent l

Organ I

(area) l Group l

(m)

(toward) l Limit l

Limits (area) l l

I i

gi i

I Quarterly l Annual l Quarterly l Annual l

(1) Liquid Total Body l

Adult Receptor 1 l

h]

1.5 3.0 l

l(2) Liquid (Liver ] g lI ( 9.8E-3 bl l

Receptor 1 l

0.20 lCo.09D lI 5.0 l

10.0 l

I I

7bl i

I 7b l

l 1

1 I

I I

I I

I I

I I

{

1(3) Noble Gas l Air Dose 1

4.7E-3 l

l 2413 NNE l

9.4E-2 l

4.7E-2 l 5.0 l

10.0 l

l l (gamma-mrad) l l

l l

l l

l l

i l(4) Noble Gas l Air Dose l

1.3E-2 l

l 2413 NNE l

0.12 l

6.3E-2 1 10.0 l

20.0 l

l l (beta-mrad l

l l

l l

l l

l 1

l(5) Noble Gas l Total Body 1

2.0E-3 l

All l

3000 NNE l

l 4.lE-2 l l

5.0 l

I l(6) Noble Gas l Skin l

5.7E-3 l

All l

3000 NNE l

l 3.8E-2 l l

15.0 l

l l

1 l

l l

l l

I I

l i

I I

I I

I I

I l

l(7) Iodine &

l Bone i

1.7E-3 l

Child 1

2400 NNE l

2.4E-2 l 1.2E-2 l

7.5 l

15.0 l

4 l

Particulates!

l l

l l

l l

l l

SUPMARY OF MAXIMUM POPULATION DOSES FOR UNIT 1 FROM l

April 1,1986 through June 30,1986 i

I Estimated Applicable Population Dose Effluent Organ (person-ren)

I (8) Liquid Total Body 7L (9) Liquid M

ib

'7 b (10) Gaseous Total Body

-2 (11) Gaseous Skin 0.22 i