Text

Semiannual Radioactive Effluent Release Rept for Jul-Dec 1990
	ML20029B101
Person / Time
Site:	Crane
Issue date:	12/31/1990
From:	Long R; GENERAL PUBLIC UTILITIES CORP.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	C-91-1221, C000-91-1221, C312-91-2010, NUDOCS 9103050423
	Download: ML20029B101 (21)
	v • d • e

m 4

4 GPU Nuclear Corporation

' ice.9 Nuclear

=,9:enao Middletown, Pennsylvania 17057 0111 717 944 782!

TELEX 84 2386 WrPor's Direct Onni Number:

(717) 948-8832 February 28, 1991 CS12-91-2010 C000-91-1221 US Nuclear Regulatory Commi.ssion Washington, DC 20555 Attn:i: Document Control Desk Three Mile Island Nuclear Station, Unit 2 (TMi-E)

Operating License No. DPR-73 Docket No. 50-320 Quarterly. Dose Assessinent Repcrt Fourth Quarter 1990 Semi-Annual Radioactive Effluent Release Report

Dear Sir:

The attached submittal includes:

1) the quarterly report of radiological releases and estimated doses for the Fourth Quarter 1990 in accordance with the THI-2 Technical Specifications Appendix B Section 5.6.1.c; and 2) the THI 2 semi-annual radioactive effluent release report for the Third and Fourth Quarters 1990, in accordance with the requirements of 10CFR50.36a(a)(2).

The maximum hypothetical doses received by an individual from THI-2 effluents for the latest reporting period is 0.0006 mrem whole body dose fram liquid relea",es

-and 0.0002 mrem teen whole body dose from gaseous releases. Each of these dosos is less than 0.03% of the Technical Specificatica limits and 32,000 ti.nes lower -

than the dose the average individual in the TMI area receives from natural background radiation during the same time period.

The reported maximum hypothetical doses are conservative overestimates of the actual offsite doses which are likely to occur.

pc GPU Nuclear Corporation is a subsidiary of the Gentiral Public UtiliNes Corporation 9103050423 901231

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{DR ADOCK 05000320 PDR

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_ pocuM M torn.vl Desk iebistr; ??, in '.

C.G2-2fil9 C000-H-411 Ryo 2' i

l Dose summaries and effluent releases for the previaus quarters of the 1990 calendar year were submit *.ed via GPU Nuclear letters 4410-90-L-0042 dated May 30, 1990, 4410--90-L-0063 dated August 13,1990, 4410-90-L-0069 dated August 28, 1990, 4410-90+d083 dated November 29,1990, and C312-91-2007, dated January 28, 1991.

Sincerely, I<

Oirecter., Corp. Services /b !%

EDS/dib Attacliments cc:

T. T. Martin - Regional Administrator, Region 1 M

I. Masnik - Project Manager, PNDP Directorate L. H. Thonus - Proje'.t Manager, TM1 F. 3.-Young - Senior Resident inspector, TMI y

l

t,lS1 Of A11ACIMIN[S 1MI-2 Quarterly Dose _ Assessment Report _ Fourth Quarter 1990 - Executive Summary - Effluent Summary Attachreent 3 - Dose Report - Interpretation of Dose Summary Table

_ I-2 Semi-An_nual Radioactive Effluent Release Reg. art TM Third and fourth Quarters 1990

, Effluent and Waste Disposal Semi-Annual Report 3

T:9-2 QUA".T R Y DOSE A$5ESSMENT REPORT ATTACH"U!T 1 FOURTH TIARTIP.1990 C 31 ? 91 -2010 gqrgygjpgnt Page 1 of 2 Three Mile Island Nuctur Station Unit 2 Ef.Pluent and off Site Dose Report for the Period of October 1,1990 through Whal 31, 1990 This report surenarires the radioactive liquid and gaseous releases (effluents) fmu Three Mile IslanS Unit 2 and the calculated maxinun hypothetical radiation a p sure to the p1blic resulting fmn these releases.

This report covers the period of operation fmn Octraber 1, 1990 thtungh W2 31,1990.

Radiological releases fmn the plant are acnitored by insta11ed plant radiation non.itors which survey the plant stack for gaseous releases and liquid discharges to the Susquehanna River. 'Ihase monitors and associated sanple analyses provide a means to accurately determine the type and quantities of radioactive anterials being released to the environmanL.-

Calculations of the mw4== bypothetical dose to an individual and the total pcpulation around Three Mile Island due to radioactive reins.ses fmn the plant are made utilizing environmental conditions existing at the time of the release.

Busquehanna River f1w data are used to calculats the marimm hypothetical doses to an individual and the population downstream of 'IMI due to liquid releases.

Actual or "real-time" meteorological data from an onsite twar is used to datamim the doses resulting fmn gaseous releases frorn the plant.

The use of real-time meteorological infonnation permits the det*m4 = tion of both the direction in which the release traveled and the dispersion of radioactive material in the envi. w t.

Utilizing gaseous ofnuant data and real-time meteorology, the mtdmun hypothetical &ase to any inilvidual and to the total population within 50 miles of the plant is calculated. Similarly, Busquehanna River now and liqul4 afnuent data are used to calculate a==i== hypothetical dose to an individual and a population dose fmn liquid affluents for any shoreline exposure down to the Chesapeake Bay. Exposure to the public fran consmption of water and fish withdrawn fmn the Susquehanna River downstream of the plant is also calculated.

Dose calculations for liquid and gaseous efnuents are performed using a mathematical mod 61 which is based on the methods defirC by the U.S.

Nuclear Regulatory nnnni.ssion.

The maximum hypothetical doses are conservative overnstimates of the actual off site doses which are likely to occur. Ibr exanple, the dose does not take into consideration the renoval of radioactive material fmn the river water by precipitation of insoluble salts, absorption onto river W imant, biological renoval, or renoval during processing by watar ompanies prior to distribution and consmption.

THI-2 OUARTERLY DO$E AS$[55f'[NT REPORT ATTACHMENT 1

_ _ _r. _U.R T H Ot t A_R T E.R 19 40

... - ~

C312-91-2010 n

P 2M2 Liquid discharyes made during the riportirq period October 1 through NmNr 31, 1990 consisted of 0.0007 curies of tritiun, 0.00003 curies of cosiun-137, and 0.00004 curies of strontiun-90.

The quantities of effluents are consistant with results cf previous quarters.

The quantities of each radionuclide released are actually up to 1 million times analler than the normal existing environmental quantities that flowod past the plant during the same time period.

31 During the reporting period October 1 through Docmber J&*of 1990, the marinan hypothetical calculated whole body dose to an individual due to liquid effluer.ts frcrn Three Mile Island Unit 2 was 0.0006 millirm.

The m W = =n hypothetical calculated dose to any organ of an individual was 0.0013 millirm to the bone.

Airborne discharges made durirg this same time period consisted of 2.0 curies of tritlun.

This quantity is consistent with the results frun previous reporting periods. The maxinza hypothetical calculated organ dose to any individual due to gaseous offluents was about 0.00015 millirem to the total tody of a toen.

The maxinrn hypothetical calculated viole body dose to any individual due to gaseous effluunts was 0.00015 mram.

The total mW==n hypothetical whois body dose of 0.0007 mrcan received by any individual frun offluents trcc the Threo Mile Island Nuclear Station Unit 2 for the reportily period is 32,000 times lower than the i

dose the average individual in the Three Mile Island area receives frcru natural background during the same time period. Natural background averages about 25 millirm whole body per quarter in the Three MDe Island area.

In addition, average equivalent dose to the total bocy frcrn natural radon is about 50 millirm par quarter.

l The dosas which could be recei wi by the maxinun hypothetical individual are each less than 0.03 parcent of the annual guidelines i

est_blished by the Nuclear Regulatory comnissic.n.

1

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TfS 2 QUARTERLY DOSE ASSCS$ttENT REPORT ATTACHMENT 2 FOU RTH O_U_M_T E R 199_0.

C312 91-2010 pogc ) og 4 Ef7LUENT $U9%RT 11sRLE MILT 15 LAND Uk!1 & LIQ'J1D AND (R$tal's ErrLUEris (8'J>pARY Of ALL RELIABLS)

TTPE EFTLUrJrT 4 W QUARTER 1960 M AL

1. LIGRJ10 ETTLUtttSt M't^6 tR K NEH0th 14CEMBER 478 QUAR 1TP A. F1&S10N AND A"TIVAT10N 110DVC"f5

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1. TUTAt RELLARE (C1) 2.228 06

8. 4 *k Cl 4.418 D6 1.498 06

2. CT*CtrrRATICm (uC1/ec) 6.40t 12 2.138 12 1.14t il 6.27t 12

3. TRIT!VM

1. TVTAL PILEASE (C1) 6.25t-06 1.778 06 6.628 04 6.708 04

2. CONCErrhAT10N ( W1/tt) 1.$21-12 4.48t 1)

$,718 10 S.61%.11 C. D1880LVED AND ENTFAINED CASE 8 18 TVIAL RELLAEE (C1)

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1. TvrAL RELEAsf (Cil (LLD

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t. VOLUME OF WA8tt RELEA8ED lR10R to DILLTION (LITERS) 2.10t*04 1.32teD4 1.34t*06 1.68t805 F. VOLUME or 01LUT10N WATER 4.121*09 3.95t*09 3.97t*09 1.19E*10 (ritM to RIVER 1p Lit %R8 FloM RPDES REPORT)

O. NUMbEM OT SATCc. RELEAPt3 9

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itil-2 QUARTERLY DO$E ASSESS"ENT REPOT!T ATTACHMENT 2 FOURTH QUt.RTER 1990 C312 91-2010

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Tt'I.2 QUAPTERLY DOSE ASSESSMENT REPORT ATTACHMENT 2 FOURTH QUARTER 1990 C312-91 2010 Page 3 of 4 trrwrn sumur

'ntRtt MILE 15 LAND 1917 2 LIQ'JID AND GASEOU$ EFTit41fte (SUMMA *v oF Att RtttAsts)

Tris Err!*Tx7 d u guam m 1990 4..................................

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1. TOTAL RELIAat (C1) 6.618-01 6.311 01 7.39t-01 2.035*00

2. REL'.A8E MTE (uC1/see).

2.478-01 2.441-01 2 76t-01 2.561 3. SECOND$ IN FERIOD REPORIED 2.682606 2.59t*06 2.66t+06 7.9tt+06 F. Ir.HBO Cr BANil RELEAsts 0

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1 TMl.2 QUARTERLY DOSE ASSESStiENT REPORT ATTAC!! MENT 2 FOURTil OVARTER 1990 C312 91-2010 Page 4 of 4 WIT 3 *.MLFOU8 PAD 3CarKL!DE RiatAsta SY 180mrt (Cl)

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TABIE 1-I tJIIIT 2 Tourth Cuarter t% e Report i

SID88RT OF MAMIMUp9 INDIVIDUAL DOSES FOR tatt 2 790m i

October 1. 1990 through Decentier 31. 1990 s

!' Estimated 8

i i

I' Location 1 of Applicable Dose Age Ols Dir Applicalde 1

Effluent ormen

! (e)t Lie 8ts (aram)

}

(arem)

Grom (toward) !

tielt

! 10 CTR SO ^__ _ _^;n i I g

l l

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(1) Ll wid Totet to#

6.3E-4 Adult neceptor 1

!2.1E-2 3.0 Y

g g

g(2) Li pid g one g

g g Receptor 1 t

1.3E-3 Adult g

1.3E-2'g g

10.0 N

t.

c g

a a

s I

a i(4)Wbt i ie G.s, Tot.t sody l 0

15.0 0

s.O g(6)sobteG.s,Stin g

g 0

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I 3sM (7) Iodine &

Totet Bo#

1 5E-4 feen 2150 asuE 1.or-3 15.0 M>

Particu"etes.

23y I

SupeuART or mAataus POPULATim DOSES FOR tatY 2 Frat

%w r, i

M l$ $

October 1. 1990 through Dac h 30. 1990 i

C Estlested

Q ApplicaH e Poputation Dose l
Effluent Oreen p rem)
{ $
Il 3'
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(8)' Liquid fotel Body 2.6E-3 (V) Llwid Bone 1.0E-2
--4 j
(10) Gescous Totet sody 3.6E-3 i
(11) Caseous Liver, Thyroid, 3.6E-3 j
twg, GI in t f
7OM l
Or WH-s a w ~4 ONNe m
>=* C Z w2 O I M mN=OM ww r
OM j
3
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TMI-2 OUART[RLY DOSE ASSESSMENT PErnni ATTACIMENT 4
_....F.O.U.R.T H. Oy A.R.T..[.h.1.990_ _..
C312-91-2010 INTERPRETATION OF DOSE
SUMMARY
ThSIl The Dose Summary Table presents the maximum hypothetical doses to an individual and the general population resulting from the release of gaseous and liquid ef fluents f rom THI-2 during the fourth quarter reporting period of 1990.
A.
Licuid (Indiviggh The first two lines present the meximum hypothetical dose to an individual.
Presented are the whole body and critical organ dosec.
Calculations are performed on the four age groups and eight organs recouended in Regulatory Guide 1.109.
The pathways considered for TMI-2 are drinking water, consumption of fish, and standing on the shoreline influenced by TMI effluents.
The latter two pathways are consicered to be the primary recreational activities associated with the Susquehanna River in the vicinity of TMI.
The " receptor" would be chat 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, for the fourth quarter of 1990 the calculated maximum whole body dose roccived by anyone would have been 6.3E-4 mrem to an adult.
Similarly, the maximum organ dose would have been 1.3E-3 mrom to the bone of an adult.
B.
OQ.Deoun (Individual.).
There are seven major pathways considered in the dose calculations for gaseous offluents.
These aros (1) plume, (2) inhalation, consumption of (3) cow milk, (4) goat milk, (5) vsgetables, (6) meat, and (7) standing on contaminated ground.
Lines 3 and 4 present the maximum plume exposure at or beyond the sito 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 Doso Summary Table presents the distanco in meters to the location in the affected sector (compass point) where the theoretical maximum plume exposure occurred.
It should be noted that real-timo noteorology was used in all dose t
calculations for gaseous effluents.
Direct noble gas plume dose to the maximum individual is shown on lines 5 and 6.
Since there were no noble gases released in the fourth quarter, the doses are zero.
THI-2 QUARTERLY DOSE ASSESSMENT REPORT ATTACHMENT 4 i
_...._ _F OU_.R.T_H OV ART.E R._199_0 C312-01-2010 P
2M2 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 plume exposure which is 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 fourth quarter 1990 lodines and particulates would have resulted in a maximum dose of 1.5E-4 mrem to the total body of a teen residing 2150 meters from the site in the NNE sector.
No other organ of any age group would have received a greater dose.
C.
Lirruid and Gaseous (Pooulation)
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.
The person-rem values from liquid effluents are based upon the population encompassed within the region from the TMI outfall extending down to the Chesapeake Bay.
The person-rem values from gaseous effluents are based upon the 1980 population and consider the population out to a distance of 50 miles arounc TMI..
population doses are summed over all distances and
-sectors to give an aggregate dose.
Based upon the calculations performed for the fourth quarter, liquid effluents resulted :n a whole body population dose of 2.6E-3 person-rem.
The maximum critical organ population dose to the bone was 1.0E-2 person rem.
Gaseous effluents resulted in a whole body population dose of 3.6E-3 person-rem. Maximum organ population dose was 3.6E-3 person-rem to the liver, lung, thyroid and GI tract.
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ATTACHMENT 5 C 312-91-2010 THi-?
Page 1 of 9 EFFIDENT AIO 10#1T DISPOSAL BD(I ANNLIAL RERET July 1,1990 to Deosaber 31, 1990 SUPPIDENTAL D50000LTICR4 FACILITY: 'DG Unit 2 (All Release Points)
LICERIEEt DPR-73-320 1.
Regulatory Limitst Fission and activation gasest a.
b.
Iodinast c.
Part.culates d.
Ligtt,d Efflue,ntsthalf-lives > 8 dayst Emrironmental Tech spec.,
Article 2.3 2.
Mari== Permissible concentrations:
Prwide the MPC's used in detamining allowabic release rates or concentrations.
Fission and activation gases a.
b.
Iodinesi 10CFR, Part 20, Appendix B c.
Part,culatas half-lives 8 dayst d.
Liqu:.d afflue,nts:
3.
Average Energy Prwide the average (E) of the radionuclide mixture in releases of fission and activation games, f
licable - WA 4.
Maamtrements and Approximations of Total Radioactivity Prwide the methods used to measure or b hamte the total radi affluents and the methods used to detam% radionuclide ocupositstivity in
a. Fission and activation gasest
.? 8:ectranstry, Liquid Scintillation
b. Iodinest 8aectranetry, i
c. Particulatmot
.h spectrunetry, Gas Flow Proportional,
d. Liquid Effluents:
HpGe(
try, Liquid Scintillation 5.
Batch Releasest Prwide th9 following information relating batch relesses of radioactive materials an liquid and gaseous affluents.
A. Liqui.d 1990 1990 3rd Ouarter Ath Ouarter
1. Number of ba releasest 51 22
2. Total tint od for batch releaseet A
3. Marian tmo per.od for a batch release:
A
4. Av etme par.od for batch releases:
A A
5. Mir t me 'per.od for a ba releaset
6. Average stream flow durina ods of rulease of effluent into f1 streamt WA N/A B. Gaseoust 3rd Ouarter Ath _Ouarter
1. Ninhar of batch rela < qast 0
2. Total timo period for batch releases:
0
3. Naw4mm tmo per:Ad for a batch releaset A
4. Avera me :er:.od for a batch releasest A
5. Min 4=ge ttme ;per: od for a batch releaset
=
'- k"" ifq"u d" " '
1. Ranbar of r91easest None None
2. 'Ibtal activity released:
WA N/A B.
Gaseous:
1.
Number of r91easest None None 2.
Total activity released!
WA N/A N/A = not applicable i
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p ATTACH!!ENT 5 C312-91-2010
- TABLE 1A Page 2 of 9 TMI EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT n
U GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES
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1990-1990
- EST. TOTAL l
UNITS 3RD OUARTER 4TH QUARTER ERROR %
(
' A. RS'ilON AND ACTIVATION GASES h
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+/- 60%
[
1. TOTAL RELEASE Ci
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' 2. AVERAGE RELEASE RATE FOR PERIOD uCi/sec N/A N/A
{
3. PERCENT OF TECH SPEC UMIT
'N/A N/A TECH SPEC UMIT =
7.2 E+3 uCifsec
[
j.
FOR KR-85 j.
B. IODINES
1. TOTAL IODINE-131 Ci
' <LLD
<LLD
+/- 60%
f f
l
2. AVERAGE RELEASE RATE FOR PERIOD uCi/sec N/A.
N/A l'
3. PERCENT OF TECH SPEC UMIT N/A N/A TECH SPEC UMIT =
2.4 E-2 uCi/sec r
C. PARTICULATES l
l-I
1. PARTICULATES WITH HALF-UVES
{
>8 DAYS Ci 3.52E-06
<LLD
+/- 60%
i
2. AVERAGE RELEASE RATE FOR PERIOD.
uCi/sec 4.43E-07 N/A f
3. PERCENT OF TECH SPEC UMIT 0.00 %
N/A TECH SPEC UMIT =
4. GROSS ALPHA RADIOACTIVITY Ci
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<LLD 2.4 E-2 uCi/sec I
?
t
' O.. TRITIUM j
I
{
1. TOTAL RELEASE Ci 2.89E+00 2.03E+00
+/- 60%
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2. AVERAGE RELEASE RATE FOR PERIOD uCi/sec 3.63E-01
- 2.56E-01 l
l
3. PERCENT OF TECH SPEC UMIT 0.01 %
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TECH SPEC UMIT =
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7 8
M A
4 7
N 1
G 8
8 8
8 3
5 5
8 1
3 5
U L
4 0
M M 3 3
A 3
3 3
3 S
3 3
3 SD N
N N N N 1
1 1
1 E
1 1
1 C
U U 1
1 L
1 Y 6 EE O
N N T-I 3
D S I
O O O O E E E-T T T I
N M M M O O A
S T
T T
T N N N N R
N N L
I I
I I
I I
M D D D P
R R S I
U B I
A U U L E S
P P P P O O O O D
N N N A
O O I
S R R T B
CL Y Y Y Y N N N N O
IF UE.
R R R R E E E E I
T T
E E A A N O O O O NR 1
K K K K X X X X 2
3 S S C C B C A C I
I I
l.
lj;
l
i
l ll
j!i ii
i' i !

;!!fj jjl
,i>
TABLE 2A
[$ $ M
~
Tm-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Page 4 of 9 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 1990 1990 EST. TOTAL UNITS 3RD QUARTER 4TH QUARTER ERROR %
A. FISSION AND ACTIVATION PRODUCTS
1. TOTAL RELEASES (NOT INCLUDING Ci 3.35E-05 7.49E-05
+/- 60%
TRITIUM, GASES, ALPHA)
BASED ON 2E-5
2. AVERAGE DILUTED CONCENTRATION uCiimt 3.28E-12 6.27E-12 DUR!NG PERIOD
3. PERCENT OF APPLICABLE LIMIT 0%
0%
B. TRITIUM
1. TOTAL RELEASE Ci 1.80E-04 6.70E-04
+/- 60%
2. AVERAGE DILUTED CONCENTRATION UCi/mi 1.76E-11 5.61E-11 uCi/mi(H-3)
DURING PERIOD
3. PERCENT OF APPLICABLE LIMIT 0%
0%
i C. DISSOLVED AND ENTRAINED GASES l
1. TOTAL RELEASE Ci
<tLD
<LLD
+/- 60%
2. AVERAGE DILUTED CO '
RATION uCi/mi
<LLD
<LLD DURING PERIOD
3. PERCENT OF APPLICABLE LIMIT
<tLD
<LLD I
D. GROSS ALPHA ACTIVITY
1. TOTAL RELEASE Ci
<LLD
<tLD 4 - 25 %
E. VOLUME OF WASTE RELEASED fiters 1.70E+05 1.68E+05
+/- 25%
(PRIOR TO DILUTION)
F. VOLUME OF DILUTION WATER USED liters 1.02E+10 1.19E+10
+/- 10%
i ATTACH"EMT 5-l' C312-91-2010 i
4 Page 5 o f 9.
TABLE 28 l
Tm-z EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l
l LIQUID EFFLUENTS I
t 4
i i
CONTINUOUS MODE BATCH MODE NUCLIDES 1990 1990' 1990; 1990 RELEASED UNIT.
3RD QUARTER 4TH OUARTER 3RD QUARTER 4TH QUARTER t
STHONTIUM-89 Ci
<LLD
<LLD STRONTIUM-90 Ci 8.69E-06 4.11E-05 f
1-CESIUM-134 Ci
<tLD
<tLD CESIUM-137 Ci 2_49E-05 3.38E-05 IODINE-131 Ci
<LLD
<tLD COBALT-58 Ci
<tLD
<LLD COBALT-60 Ci
<tLD
<tLD
[
IRON-59 Ci
<tLD
<LLD j
ZINC-65 Ci
<LLD
<LLD
[
j MANAGANESE-54 Ci
<tLD
<LLD l
l CHROMIUM-51 Ci
<LLD
<LLD l
ZIRCONIUM-NIOBlUM-95 Ci
<LLD
<tLD I
I I
MOLYBDENUM-99 Ci
<tLD
<tLD TECHNETIUM-99M Ci
<LLD
<LLD
~
BARIUM-LANTHANUM-140 Ci
<LLD
<LLD CERIUM-141 '
Ci
<LLD
<LLD
[
{
OTHER (SPECIFY)
Ci l
j TOTAL FOR PERIOD Ci 3.35E-05 7.49E-05
[
l XENON-133 Ci
<RD
<tLD
[
XENON-135 Ci
<LLD
<tLD i
4 i
{
f i
?
i 5
ATTACHMENT 5 1Hl.2 C312 91 2010 July 1 - December 31, 1990 Page 6 of 9 TABLE 3A ETTLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT i
SOLID WASTE AND IRRADIATED TVEL SHIPMENTS A.
Solid vaste shipped of f-site for bttrial or disposal (not irradiated f uel) i l'.
Type of vaste UNIT f,"*"jh E[JgpTpTAL
4. 5 pent resins.111ter sluoges.
E' 2
3 evseerster bet tees, etc.
Ci 76 CT 5%
b. Dry compressible vaste, contaminated a3 323.8 m4 ecuitment. etc.
Si c<
1 ra e q
c. Irractateo components. control 4
n r od s. e t c.
gjg ci aa
d. Other (describe) i et N/A
2. Estimate of major nuclide eennesttien (dv evre of vaste) n.
Sr90 Ss,g %
Cs137
" 0, r, PMI47 P 17 t Ni63
.472%
b.
Sr90 60,1 3
rt117
,l.2 Dmia?
7.56 %
Po?41 a on Sbl25 1.56 %
c.
t t
t d.
Y t
t
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination ten Attached B.
Irrac.ted Fuel Shiptents (Disposition)
Number of Shiptents Mode of Transportation Destination None i
]
l,
l
~
ATTACHt1ENT 5 C 312-91-2010 Page 7 of 9 THI-2 EFFEUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT July 1. 1990 - December 31, 1990 Table A.3.a No, of Shipments Mode of Transportation Destination 4
Tractor-Cask (CNS 8-120B)
Chem-Nuclear - Barnwell. SC i
1 Tractor-Cask (CNS 8-120B)
U. S. Ecology - Beatty. NY Table A.3.b No. of Shipments Mode of Transportation De.tination
6 Tractor-Flatbed Scientific EcoloEy Group. Oak Ridge. TN
-1 Tractor-Flatbed U. S. Ecology - Richland. WA WASTE SHIPPED AS FOLLOWS:
TABLE A.3.at Five (5) Steel Liners at 76,4 f t. ' Each TABLE A.3.br
0ne Hundred Eighteen (118) - Steel Boxes 0 92 ft.* Each
Seventeen (17) Wooden Boxes 0 24 Ft.' Each One (1) - Steel Liner 0 170 Ft.8
Material Sent Off-Site to a Waste Processor for Volume Reduction d
,,_p,o,-, - -.,,- - -_i, y-u-
,-.--m,--
n e-
---mg-m,-.
--~+y y
p-
m m2,,_
T5 TMl-2 SEMI-ANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT lTTACgMEp010 THIRD AND FOURTH QUARTERS 1990 p
g
,9 i
TYP1 CAL L10U10 tFFLUtWT LLD (Lower Limit of Detection) VALUt$
ASSUMPi!ONS:
Semple volume = 1 liter = 1000 cc Sample countin9 time 1000 set
=
Sample counted with a 25% Ge(Li) for Gamra Emitters 110 TOPE pti/cc Lt0 HDTil Gross Alpha a
4E-9 Counted with proportional counter Gross Beta 7E-8 Counted with proportional counter Tritium H 4E-6 Countee with liquid scintillation counter Krypton-85 Kr-85 1 E-4 Xenon-131m Re-131m 2E-5 Xenon-133 Xe-133 1E-6 Renon-135 Ke-135 3E-7
-Chromium-51 Cr-151 3E-6 Man 9anese-54 Mn-54 4E-7 Cobalt-5B Co-58 4E-7 tron-59 Fe-59 9E-7 Cobalt-60 Co-60 6E-7 Zinc-65 In-65 1E-6 lirconium-95 2r 7E-7 Wiobium-95 Mb-95 4E-7 Molybdenum-99 Mo-99 3E-7 Technetium-99m it-99m.
SE-1 511ver-110m Ag-110m -
6E-7 Antioony-125
$b-125 9E-7 Ce sium-134 Cs-134 SE-7 Cesium-136 Cs-136 4E-7 Cesium-137 Cs-137 SE-7 8arium 140 Ba-140 1E-6 Lenthanum-140 La-140 1E Cerium 141 Ce-141
$E-7
. "erium-144 Ce-144 3E-6
' todine-131 1-131 3E-1 lodine-133 1-133 4t-7
hosphorus-32 p-32 1E-4 These LLD values for liquid tron-55 Fe-55 5E-8 sample analyses of gross alpha, itrontium-89
$r-89 5E-8 P-32. Fe-55. Sr-89, and Sr-90 itrontium-90
' 5r-90 SE-8 are the same as Unit 1 which are-iross Alpha 1 E-7 of f site vendor LLD values.
m z-
. ~.....
TM1-2 SEMI-ANNUAL RADIDACTIVE EFFLUEllT RELEASE REPORT QCylfy THIRD AND FOURTH QUARTER $ 1990 p,g, 9 of 9 TYPICAL GAst005 EFFLUtWT Ll0 (Lower timit of Detection) VALUt5 A55 UMP 110NS:
sample volume (Marinelli) 1640cc Sample volume (Particulate & Charcoal Filters) 5.7L8cc Sampling Rate 2 cfm or 5.66E4cc/ min t
Sampling Time 1 week or 1E4 min Sample volume (tritium bubbled thru water) 7.56E5cc sampling Rate 75cc/ min Sampling Time 1E4 min sample Counting Time: a
& H-3 =20 min; A =10 min; t =1000sec Sample Counters:
y emitters 25% 6t(Li) e or #
Proportional Counter H-3 Licuid Scintillation Counter 150 Tort f,i/rJ,1,LQ tLQ.U,1 Gross Alpha o
1 E-15 Particulate Filter Paper Gross Beta B
1E-14 Tritium H-3 1E-10 Air bubbled thru water by a fritted disc or Fisher Milligan gas washer Krypton-85 Kr-85 5E-6 Marinelli Krypton-85m Kr-85m 2E-8 Krypton-87 Kr-87 6E-8 Krypton-88 Kr-88
$[-8 Xenon-133 Xe-133 4E-8 Xenon-133m Xe-133m 1E-7 Xenon-135 Xe-135 2E-8 Xeron-135m
. X e -13 5m 3E-7 Xenon-138 Xe-138 3E-7 lodine-131 1-131 2E-g locine-133 1-133 3E-8 lodine-135 1-135 2E-7 todine-131 1-131 3E-14 Charcoal Filter lodine-133 1-133 4 E-14 lodina-135 1-135 3E-13 Manganese-54 Mn 54 3E-14 Particulate filter Paper Iron-59 Fe-59 8E-14 Cobalt-58 Co-58 3E-14 Cobalt-60 Co-60 5E-14 lint-65 Zn-65 DE-14 Strontium-89
$r-89 2 E-14 Strontium-90 3r-90 2 E-14 Molybdenum-19 Mo 99 2E-14 Ruthenium-103 Ru-103 2E-14 Silver-110m Ag-110m 3E-14
. Ce sium-134 Cs-134 4E-14 Ce sium-137 CS-131 3E-14 l
Cerium-141 Ce-141 3E-14 Cerium-144 Ce-144 9 E-14
- _..,.. -. _ - -

ML20029B101

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