ML20034F806
| ML20034F806 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/31/1992 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20034F805 | List: |
| References | |
| NUDOCS 9303050034 | |
| Download: ML20034F806 (16) | |
Text
ATTACHMENT 1
/
C312-93-2014 Page 1 of 2 EXECUTIVE
SUMMARY
Three Mile Island Nuclear Station Unit Two i
Effluent and Off Site Dose Report for the Period of October 1, 1992 through December 31, 1992 This report strummarizes the radioactive liquid and gaseous releases (effluents) from Three Mile Island Unit Two and the calculated maximum hypothetical radiation exposure to the public resulting from these releases.
This report covers the period of operation from October 1, 1992 through December 31, 1992.
Radiological releases from the plant are monitored by installed i
plant radiation monitors vhich survey the plant stack for gaseous releases and liquid discharges to the Susquehanna River.
These monitors and associated sample analyses provide a means to accurately determine 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 i
releases from the plant are made utilizing environmental conditions existing at the time of the release.
Susquehanna River flow data are used to calculate the maximum hypothetical doses to an i
individual and the population downstream of TMI due to liquid releases. Actual or "real-time" meteorological data from an onsite I
tower is used to determine the doses resulting from gaseous releases from the plant.
The use of real-time meteorological 3
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 j
calculate a maximum hypothetical dose to an individual and a population dose from liquid effluents for any shoreline exposure 1
down to the Chesapeake Bay.
Exposure to the public from consumption of water and fish withdrawn from the Susquehanna River i
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 Comaission.
The maximum hypothetical doses are conservative overestimates of the actual off site doses which are likely to occur.
For example, I
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.
h O
O S
AThm _
m C 312-93-2014 Page P. of 2 Executive Summary (cont.)
Liquid discharges made during the reporting period October 1, 1992 through December 31, 1992 consisted of 0.0014 curies of tritium, 0.00002 curies of cesium-137, and 0.00001 curies of strontium-90.
The quantities of effluents are consistent with results of previous quarters.
The quantities of each radionuclide released are actually up to 1 million times smaller than the normal existing environmental quantities that flowed past the plant during the same time period.
During the reporting period October 1, 1992 through December 31, 1992, the maximum hypothetical calculated whole body dose to an individual due to liquid effluents from Three Mile Island Unit Two was 0.0003 millires.
The maximum hypothetical calculated dose to any organ of an individual was 0.0005 millires to the bone.
Airborne discharges made during this same time period consisted of 19.2 curies of tritium, 0.000004 curies of cesium-137, 0.00000009 curies of strontium-90, and 0.000006 curies of carbon-14.
The maximum hypothetical calculated organ dose to any individual due to gaseous effluents was about 0.0061 millirem to the liver.
The maximum hypothetical calculated whole body dose to any individual due to gaseous effluents was 0.0061 arem.
The total maximum hypothetical whole body dose of 0.0063 mrem received by any individual from effluents from the Three Mile Island Nuclear Station Unit 2 for the reporting period is approximately 12,000 times lower than the dose the average individual in the Three Mile Island area receives from natural background and radon (75 mrem) during the same time period.
Natural background averages about 25 millires whole body per quarter in the Three Mile Island area.
In addition, average equivalcut dose to the whole body from natural radon is about 50 millirem per quarter.
The doses which could be received by the maximum hypothetical individual are each less than 0.04 percent of the annual guidelines established by the Nuclear Regulatory Cosemission.
a l
~ ATTACHMENT'2 C312-93-2014
+
Dage 1 of 4 i
)
l EFFLUENT
SUMMARY
THREE MILE ISLAND UNIT 2 LIDUID AND GASEOUS EFFLUENTS
(
SUMMARY
OF ALL RELEASES) g!
l?
x TYPE EFFLUENT 4TH QUARTER 1992 1
ji TOTAL
- 1. LIQUID EFFLUENTS:
OCTDBER NOVEMBER DECEMBER 4TH DUARTER A. FISSION AND ACTIVAT!DN PRODUCTS
=
=
=
=
(NOT INCLUDING H-3, CASES, & ALPHA)
- 1. TOTAL RELEASE (Ci) 4.5 BE-06 4.45E-06 1.95E-05 2.85E 05 i
- 2. CONCENTRATION (uCi/ce) 1.27E-12
<LLD
<LLD
- <tLD i
i B. TRIT!uM
- 1. TOTAL RELEASE (Cl) 7.54E-05 4.54E-04 8.64E-04 1.39E-03 5
- 2. CONCENTRATlDN (UCi/cc) 2.09E 11
<LLD
<LLD
<LLD C. DISSOLVED AND EN1 RAINED GASES I
- 1. TOTAL RELEASE (Cl)
<LLD
<LLD
<LLD
<LLD 1
- 2. CONCENTRATION UCi/cc)
N/A N/A N/A N/A i
Il D. CROSS ALPHA ACTIVITY
- 1. TOTAL RELEASE (Cl)
<LLD
<tLD
<LLD
<LLD e
E. VOLUME OF WASTE RFLEASED PRIOR TO DILi'TIDN (LITERS) 2.94E+04 9.83E+03 1.27E+05
- 1. 66E +05 I
i F. VOLUME OF DILUTION WATER 3.61E+09 3.49E+09 3.84E+09 1.09E+10 (FLOW TO RIVER IN LITERS FROM NPDES REPORT)
C. NJMBER OF BATCH RELEASES 8
4 9
21 i
i y
t i
P
?
i h
t P
ATTACHMENT 2' i
C312-93-2014 Page 2 of 4 t
r o
1992 UNIT 2 LIQUID RADf DWUCLIDE RELEASES SY ISOTOPE (Cl)
RADIDNUCLIDE OCTOBER NOVEMBER DECEMBER 4TH QUARTER 1992
}
FISSION AND ACTIVATIDN PRODUCTS (NOT INCLUDING ALPHA, H-3 & GASES
<LLD
<LLD
<LLD
<LLD AG-110M
<LLD
<LLD
<LLD
<LLD t
?
CE-144
<LLD
<LLD
<LLD
<LLD Co-58
<LLD
<LLD
<LLD
<LLD
<LLD
<tLD CS-134
<LLD
<LLD
<tLD
<LLD CS.137 2.40E-06 3.72E-06 1.01E-05 1.62E-05 I-131
<LLD
<LLD
<LLD
<tLD SR-90 2.1BE-06 7.27E-07 9.40E-06 1.25E l TOTAL 4.5BE-06 4.45E-06 1.95E-05 2.ESE-05 H-3 7.54E-05 4.54E-D4 8.64E-04 1.39E 03 t
J i
)
e ATTACHMENT 2 C 312-93-2014 Page 3 of 4 j
EFFLUENT
SUMMARY
f THREE MILE ISIAND UNIT.1 1.IQUID AND GASEOUS EFFLUENTS f
(
SUMMARY
OF ALL RELEASES)
TYPE ZFFLUENT 4TE QUARTER 1992 l
TOTAL OCTOBER NOVEMBER DECEMBER 4TH QUARTER
.i II. CASEOUS EFFLUENTS:
j A.
FISSION AND ACTIVATION CASES
- 1. TOTAL RELEASE (C1)
(LLD CLLD CLLD CLLD
- 2. RELEASE RATE (uC1/sec)
N/A N/A N/A N/A i
4 B. IODINE 131 RELEASED (C1)
C. PARTICULATES WITE EALF-LIVES
>8 DAYS I
- 1. TOTAL RELEASES (NOT 2.99E-06 4.44E-08 6.84E-06 9.88E-06 s
INCLUDING ALPEA) (C1) f
- 2. RELEASE RATE (uC1/sec) 1.12E-06 1,71E-08 2.56E-06 1.24E-06
- 3. GROSS ALPHA RADIO-ACTIVITY (C1)
(LLD
<LtD
<LLD
<LLD l
D. TRITIUN
- 1. TOTAL RELEASE (C1) 2.87E-02 1.80E+00 1.74E+01 1.92E+01
.f 2
- 2. RELEASE RATE (uci/see) 1.07E-02 6.96E-01 6.48E+00 2.41E+00 E. SECONDS IN PERIOD REPORTED 2.6BE+06 2.59E+06 2.68E+06 7.95E+06 F. NUMBER OF BATCH RELLASES 0
0 0
0 1
.e.
e h
E E
t 6
r r
/
' ATTACHMENT 2' U
C 312-93-2014 h
Page 4 of.4 l
UNIT 2 GASEOUS RADIONUCLIDE RELEASES BY ISDTOPE (C1) 6 i
i RADIONUCLIDE OCTOBER NOVEMBER DECEMBER 4TE QUARTER 1992' f
i FISSION AND ACTIVATION GASES KR-85 (LLD CLLD
<110 (LLD TOTAL l
PARTICULATES (EALF-LIVES >8 DAYS) r
.g CS-137 2.95E-06 7.352-09 6.24E-07 3.58E-06 l
l CS-134
<LLD
<LLD
<LLD
<LLD SR/Y-90 4.15E-08 3.71E-08 6.87E-09 8.55E-08 l
<LLD
<LLD 6.21E-06 6.21E-06 SB 125
<tLD
<LLD
<LLD
<LLD CO-60
<LLD (LLD
<LLD (LLD GROSS ALTEA CLLD CLLD CLLD
<LLD
. l
.meme we-TOTAL (INCLUDING ALPEA) 2.99E-06 4.44E-08 6.84E-06 9.88E-06 TOTAL (XINUS ALPHA) 2.99E-06 4.44E-08 6.84E-06 9.88E-06 l
TRITIUM (H-3) 2.87E-02 1.80E+00 1.745+01 1.92E+01 I
p r
I 1
i i
I
L TABLE 1 UNIT 2
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES FOR UNIT 2 FROM October 1.
1992 through December 31 1992 Estimated Location
% of Applicable Dose Age Dist Dir Applicable Limits (mrem)
Effluent Organ (mrem)
Group (m) (toward)
Limit 10 CFR 50 Appendix I Ouarterly Annual Quarterly Annual (1) Liquid Total Body 2.81E-4 Adult Receptor 1 9.37E-3
.3. 0 (2) Liquid Bone 5.21E-4 Child Receptor 1 5.21E-3 10.0 0
10.0 (3) Noble Gas Air Dose 0
(gamma-mrad)
(4) Noble Gas Air Dose 0
0 20.0 (beta-mrad)
(5) Noble. Gas Total Sody 0
0 5.0 15.0 (6) Noble Gas Skin 0
0 (7) Iodine &
- Liver, 6.06E-3 Teen 650 NW 4.04E-2 15.0 Particulates Total Body
SUMMARY
OF MAXIMUM POPULATION DOSES FOR UNIT 2 FROM October 1.
1992 through December 31. 1992 Estimat',d Applicable Population Dose Effluent Orcan foerson-rem)
(8) Liquid Total Body 1.59E-3 (9)
Liquid Bone 6.25E-3 (10) Gaseous Total Body 1.72E-2 (11) Gaseoud Liver 1.73E-2 y]3 to - -i
-ez O
rT1 m n> 2 eaS 4= t,a l
ATTACHMENT 4
' C312-93-2014
. Page 1 of 2 INTERPRETATION OF DOSE
SUMMARY
TABLE t
The Dose Summary Table presents the maximum hycothetical doses to an individual and the general population resulting from the release of gaseous and liquid effluents from TMI-2 during the fourth quarter reporting period of 1992.
A.
Liauid (Individual)
The first two lines present the maximum hypothetical dose to an 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.
j, The pathways considered for TMI-2 are consumption of drinking water and fish and standing on the shoreline influenced by TMI i
effluents.
The latter two pathways are considered to be the primary recreational activities associated with the f;
Susquenanna River in the vicinity of TMI.
The " receptor" l'
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.
For the fourth quarter of 1992 the calculated maximum whole body dose received by anyone would have been 2.81E-4 mrem to-an adult.
Similarly, the maximum organ dose would have been 5.21E-4 mrem to the bone of a child.
i B.
Gaseous (Individual)
There are six major pathways considered in the dose calculations for gaseous effluents.
These are:
(1) plume, (2) inhalation, consumption of (3) cow milk, (4) vegetables, (5) meat, and (6) standing on contaminated ground.
+
Lines 3 and 4 present the maximum gamma and beta plume exposure, respectively, from noble gases at or beyond the site boundary.
Direct noble gas plume dose to the total body and t
t skin of an individual is shown on lines 5 and 6, respectively.
Because there were no noble gases released during the fourth quarter, the plume exposures (lines 3 and 4) and plume doses (lines 5 and 6) are zero.
t The Iodines and Particulates section described in line 7 represents the maximum exposed organ due to
-l again reflects the maximum exposed organ (s) for the appropriate age group.
The fourth quarter 1992 iodines and particulates would have resulted in a maximum organ dose of 6.06E-3 mrem to the liver l
of a teen residing 650 meters from the site in the NW sector.
The maximum total body dose also was 6.06E-3 mrem to a teen i
residing at the same location.
I
~
l ATTACHMENT 4 i
C 312-93-2014 Page 2 of 2 C.
Liauid and Gaseous (Population)
Lines 8 - 11 present the person-rem doses resulting from the liquid and gaseous effluents.
These doses are summed over all 3
pathways and the affected populations.
The person-rem doses from liquid ef fluents are based upon the population encompassed within the region from the TMI outfall extending down to the l
The person-rem doses from 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 i
dose.
j l
Based upon the calculations performed for the fourth quarter of 1992, liquid effluents resulted in a whole body population dose of 1,59E-3 person-rem.
The maximum critical organ
]
population dose was 6.25E-3 person-rem to the bone.
Gaseous effluents resulted in a whole body population dose of 1 72E-2 person-rem.
The maximum organ population dose was 1.'3E-2 person-rem to the liver.
j 1
i l
t
i
/
EFFLUENT AND WASTE DISIOSAL SEMI ANNUAL REPORT ATTACHMENT 5 July 1,1992 to December 31,1992 C312-93-2014 l
Page 1 Of 9 SUPPLEMENTAL INFORMATION FACILITY: TMI Unit 2 (All Release Points) LICENSEE: DPR-73-320 1.
Regulatory Limits:
a.
Fasion and activation gases:
b.
todines:
l c.
Particulates, half-lives > 8 days:
Environmental Tech Spec.,
3 d.
Liquid Effluents:
Anicle 2.3 2.
Maximum Permissible Concentrations:
Provide the MPC's used in determining a110wagle release rates or concentrations.
l a.
Fission and activation gases:
b.
Particulates, half-lives 8 days:
d.
Liquid effluents:
i 3.
Average Energy:
Provide the average energy (E) of the radionuclide mixture in releases of fission and activation gases, if applicable
- N/A 4.
Measurementa and Appmximations of Total Radioactivity:
Provide the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.
a.
Fission and activation gases:
HpGe(Li)
Spectrometry, Liquid Scintillation b.
MpGe(Li)
Spectrometry, c.
Particulates:
Hpr.e(Li)
Spectrometry, Gas Flow Proportional. Beta Spectrometry d.
Liquid Effluents:
HpGe(Li)
Spectrometry, Liquid Scintillation 5.
Batch Releases:
Pmvide the following information relating batch releases of radioactive materials in liquid and gaseous effluents.
A.
Liquid 1992 1992 3rd Ouarter 4th Ouarter
- 1. Number of batch releases:
47 21
- 2. Total time period for batch releases:
N/A N/A
- 3. Maximum time period for a batch release:
N/A N/A
- 4. Average time period for batch releases:
N/A N/A l
- 5. Minimum time period for a batch release:
N/A N/A
- 6. Average stream flow during periods of release of effluent into flowing stream:
N/A N/A i
B.
Gaseou -
3rd Ouarter 4th Ouar.cr
- 1. Numt>er of batch releases:
0 0
- 2. Total time period for batch releases:
N/A N/A
- 3. Maximum time period for a batch release:
N/A N/A
- 4. Average time period for batch releases:
N/A N/A
- 5. Minimum time period for a batch release:
N/A N/A 6.
Abnormal Releases:
A. Liquid:
- 1. Number of releases:
- 2. Total activity releases:
N/A N/A B. Gaseous:
- 1. Number of releases:
- 2. Total activity released:
N/A N/A N/A = not appkalde SAEFF. SEW
?
' ATTACHMENT 5:
C312-93-2014 Page 2 of 9 i
?
TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 1992 1992 IST. TOTAL UNITS 3RD QUARTER 4TH QUARTER ERROR 4
[
1 i
A. FISSION AND ACTIVATION GASES f
r
- 1. TOTAL RELEASE Ci (LLD CLLD'
+/- 60%
i
- 2. AVERAGE RELEASE RATE FOR PERIOD uC1/sec N/A N/A
- 3. PERCENT OF TECH SPEC LIMIT 4
N/A N/A TECH SPEC LIMIT.
7.2 E+3 uci/see FOR RR-85 B. IODINES
- 1. TOTAL IODINE-131 Ci (LLD CLLD
+/- 60%
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/seo N/A N/A
- 3. PERCENT OF TECH SPEC LIMIT t
N/A N/A TECH SPEC LIMIT.'
2.4 E-2 uCi/sec C. PARTICULATES l,
- 1. PARTI T. ATES WITH HALF-LIVES 28 DKs.
Ci 6.66E-09 9.885-06
+/- 60%
i f
2, AVERAGE RELEASE RATE FOR PERIOD uci/sec 8.38E-10 1.24E-06
- 3. PERCENT OF TECH SPEC LIMIT 4
0.00%
0.01%
TECB SPEC LIMIT =
- 4. GROSS ALPHA RADIOACTIVITY C1
- <LLD CLLD
-2.4 E-2 uC1/sec '
D, TRITIUM
- 1. TOTAL REI. EASE Ci 7.76E-02 1.92E+01
+/- 60%
- 2. AVERAGE RELEASE RATE FOR PERIOD uC1/sec 9.76E-03 2.41E+00
- 3. PERCENT OF TECH SPEC LIMIT 4
0.00%
0.05%
TECH SPEC LIMIT =
4.8 E+3 uC1/see FOR H-3 i
i 6
6 s
i I
f l
i e
I e
I h
t h
1.
ATTACHMENT 5 M
C312-93 2014
-l Page-3 of 9 l
-1
.I.)
TABLE 1B
'l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT'
?
GASEOUS EFFLUENTS-GROUND LEVEL RELEASES r
l r
CONTINUOUS MODE BATCH MODE t
FJCLIDES 1992 1992 1992 1992 i'f RELEASED UNIT 3RD QUARTF.R 4TH QUARTER 3RD QUARTER 478 QUARTER f
- 1. FISSION GASES I
?
KRYPTON-85 Ci
<11D
<ILD
<LLD
<LLD
)
4 s -
IRYPTON-65M Ci (110 (LLD
<LLD (LLD l}
f; KRYPTON-87 Ci
<11D CLLD (110 (LLD KRYPTON-88 C1 (I1D CILD
<LLD C11D
.f (
XENON-133 Ci (11D (LLD
<!1D
<tLD k
XENON-135 Ci
<11D
<LLD
<LLD C11D XENON-135M Ci
<11D
<LLD CLLD
. CL1.D l
XENON-138 Ci
<11D
<LLD CIID
<ILD
[
OTHERS (SPECIFY)
C1
<LLD
<LLD
<11D (11D l
Ci f
Ci Ci Ci f
UNIDENTIFIED Ci
<LLD (11D
<LLD
<LLD TOTAL FOR PERIOD Ci N/A N/A N/A N/A
- 2. IODINES 4
j IODINE-131 Ci
<LtD
<!1D N/A N/A IODINE-133 Ci (I1D
<LLD N/A N/A f
f IODINE.135 Ci (ILD
<I1D N/A N/A 6,
TOTAL TOR PERIOD Ci N/A N/A N/A N/A f
- 3. PARTICUI.ATES i'
STRONTIUM-89 C4 (11D
<11D
<!1D CLLD STRONTIUM-90 Ci
<LLD 8.55E-08
<11D CLLD CESIUM-134 C1 CLD
<11D
<!10
<LLD CESIUM-137 Ci 6.66E-09 3.5BE-06
<11D
<LLD l
BARIUM-IANTEANUM-140 Ci
<I1D CILD
<IlO
<I1D CARBON-14 Ci
<tLD 6.21E-C6
<!1D CLtD ANTIMONY-125 Ci
<tLD (ILD
<11D
<LtD COBALT-60 Ci
<11D
<!1D
<LLD CILD j
?
n
)
UNIDENTIFIED Ci (LLD (LLD N/A N/A
?
i 1
~
- L i
i ATTACFuiENT 5 i
t C312-93-2014
^
Page 4 of 9 j
I f
TABLE 2A A
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIDUID EFFLUENTS-SUMKATION OF ALL RELEASES l
l 1992 1992 EST. TOTAL UNITS 3RD QUARTER 4TH QUARTER ERROR %
=
ses=
e.
rmes=====
A. FIS$10N AND ACTIVATIDW PRODUCTS j
- 1. TOTAL RELEA$fS (NOT INCLUDING Ci 4.06E-05 2.85E-05
+/ 63%
TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATIDH UCi/mi 2.99E-12
<LLD 1
DURING PERIDD
- 3. PERCENT OF APPLICABLE LIMIT 0%
D%
B. TRITIUM l
- 1. TOTAL RELEASE Cl 1.27E-D4 1.39E-03
+/- 60%
BASED ON 3E 3
- 2. AVERAGE DILUTED CONCENTRATION uti/mi 9.39E-12
<LLD uti/ml (H 3) f DURING PERIOD
- 3. PERCENT OF APPLICABLE LIMIT D%
0%
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE Ci
<tLD
<LLD
+/ 60%
i
- 2. AVERAGE DILUTED CONCENTRATION uti/mi
<LLD
<L! O 1
DURING PERIOD
- 3. PERCENT OF APPLICABLE LIMIT
<LLD
< lid j
D. GROSS ALPHA ACTIVITY t
- 1. TOTAL RELEASE Ci
<LLD
<LLD
+/- 25%
E. VOLUME OF WASTE RELEASED liters 2.78E+05 1.66E+05
+/- 25%
(PRIOR TO DILUTION)
F. VOLUME OF DILUTION WATER USED liters 1.36E+10 1.09E+10
+/- 10%
1 I
j i
J l
s l
l 4
l
)
i a
ATTACHMENT S
~
C 312-93-2014 Page 5 of 9 TABLE 28 I
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT I
LIQUID EFFLUENTS CONTINUQUS MDDE BATCH MDDE NUCLIDES 1992 1992 1992 1992 -
RELEASED UNIT 3RD QUARTER 4TH CJARTER-3RD QUARTER 4TH QUARTER'
==
ss=======
=
=
<
========ssa STRONTIUM-89 Ci
<LLD
<tLD
=
+
STRDNTIUM-90 Ci
<LLD 1.23E-05 COBALT-60 Ci 1.14E-06
- <LLD l
CESIUM-137 Ci 3.95E-05 1.62E-05 I
IDDINE-131 Ci
<LLD
<LLD COBALT-58 Ci (LLD
<LLD l
1 CESIUM-134 Cl
<LLD
<LLD -
-i 1RDN-59 Ci
<LLD
<LLD ZINC-65 Ci
<LLD
<LLD MANAGANESE-54 Ci (LLD
<LLD CHRDMIUM-51 Ci
<LLD
<tLD 2!RCONIUM-NIOBIUM-95 Ci
<LLD
<LLD i
MOLYBDENUM-99 Ci
<LLD
<LLD TECHNETIUM-99M Ci
<LLD
<LLD BARIUM-LANTHANUM-140 Ci
<LLD
<LLD CERIUM-141 Ci
<LLD
<LLD OTHER (SPECIFY)
Cl i
UNIDENTIFIED Ci
<LLD
<LLD TOTAL FOR PERIOD Cl 4.06E-05 2.85E-05 t
I XENON 133 Ci
<LLD
<LLD XENON-135 C1 (LLD
<LLD
.i e
5
~
ATTACHMENT 5-C312-93-2014 Page 6 of 9 TM1-2 7/1/92 to 12/31/92 TA3LE 3A EFF1,UENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT i
501,1D WASTE AND IRRADIATED TETE SHIPMENTS A.
Solid waste shipped off-site for burial or disposal (not irradiated fuel)
- 1. Type of waste UNIT 6 month EST. TgTAL eeried ERROD
- a. 5 pent resins, filter slunges, m'
161.2 m3 5,.
evaperator bottoms. etc.
ci 1030.5 Ci
- b. Dry co=pressible waste, contaminated m
502.2 m3 5 '"
3 eeui:=ent, etc.
c4 9.93 Ci i
- c. Irractatec co=ponents, control i
m N/A N/A r od s. e t c.
ci it' 2.3 m3
- d. Other (describe)
- ci 1.97 Ci 5*
i
- 2. Estimate of major nuclide composition (bv tvpe of waste) a.
Cs137 53.8 l
Sr90 40.1 Ni63 1.58?
Pml47 1.35 :
b.
Sr00 87.1 ;
k r 177 7.67 i s
Pm147 1.48 :
i Pu241 1.39 I
Ni63
.736:
e.
N/A
=
i i
g d.
Csl37 82.1 :
i; H3 16.9 g Sr90
.331 :
Csl34
)
.279 -
4
- 3. Solid Waste Disposition
'*u=ber of Shipments Mode of Transportation Destination j
See Attached I
i 3.
Irradiated Fuel Shipments (Disposition)
Nu=ber of Ship =ents Mode of Transoortation Destination N/A 4
t
- d.
Solidified Decon Waste, Hydraulic Fluid and Scintillation Fluids.
6-
i ATTACHMENT 5 l
C312-93-2014
' TMI-2 Semi-Annual Report Page 7 of 9 7/1/92 to 12/31/92 i
A.3.a Number of Shipments Mode Destination Fifteen (15) Shipments Tractor-Cask (14/190m)
CNSI - Barnwell, SC Three (3) Shipments Tractor-Cask CNSI - Barnwell, SC (CNS 8-1208)
Two (2) Shipments Tractor-Cask (14/190m)
U.S. Ecology - Richland, WA Three (3) Shipments Tractor-Closed Van U.S. Ecology - Richland, WA t4 One (1) Shipment Tractor-Closed Van CNSI - Barnwell, SC f i
- 0ne (1) Shipment Tractor-Flatbed SEG - Oak Ridge, TN l
A.3.b i
Number of Shipments Mode Destination l
i~ i
- Ten (10) Shipments Tractor-Flatbed SEG - Oak Ridge, TN ll Two (2) Shipments Tractor-Cask (14/190m)
CNSI - Barnwell, SC l!
One (1) Shipment Tractor-Flatabed CNSI - Barnwell, SC l: l' A.3.d Number of Shipments Mode Destination Three (3) Shipments Tractor-Closed Van U.S. Ecology - Richland, WA
[
- 0ne (1) Shipment Tractor-Flatbed SEG - Oak Ridge, TN i
i f
I P
L
- Material Shipped to Waste Processor for Volume Reduction.
f
ATTACHMENT 5 C312-93-2014 Page 8 of 9 t
TABLE 1 TYPICAL LIOUID EFFLUENT LLD (Lower Limit of Detection) VALUES ASSUMPTIONS:
Sample volume = 1 liter = 1000 cc t
Sample counting time 1000 sec
=
Sample counted with a 25% Ge(Li) for Gamma Emitters ISOTOPE DCi/cc LLD NOTES Gross Alpha a
4 E-9 Counted with proportional counter Gross Beta B
7 E-8 Counted with proportional counter Tritium H-3 4 E-6 Counted with liquid scintillation counter Krypton-85 Kr-85 1 E-4 Xenon-131m Xe-131m 2 E-5 Xenon-133 Xe-133 1 E-6 Xenon-135 Xe-135 3 E-7 i
Chromium-51 Cr-51 3 E-6 Manganese-54 Mn-54 4 E-7 Cobalt-58 Co-58 4 E-7 Iron-59 Fe-59 9 E-7 Cobalt-60 Co-60 6 E-7 Zinc-65 Zn-65 1 E-6 i
Zirconium-95 Zr-95 7 E-7 Niobium-95 Nb-95 4 E-7 Molybdenum-99 Mo-99 3 E-7 Technetium-99m Tc-99M 3 E-7 Silver-110m Ag-110m 6 E-7
)
Antimony-125 Sb-125 9 E-7 Cesium-134 Cs-134 5 E-7 Cesium-136 Cs-136 4 E-7 Cesium-137 Cs-137 5 E-7 i
Barium-140 Ba-140 1 E-6 Lanthanum-140 La-140 7 E-7 Cerium-141 Ce-141 5 E-7 Cerium-144 Ce-144 3 E-6 Iodine-131 I-131 3 E-7 i
Iodine-133 I-133 4 E-7 Phosphorus-32 P-32 1 E-6 These LLD values for liquid sample Iron-55 Fe-55 5 E-8 analyses of gross alpha, P-32, Fe-55, Strontium-89 Sr-89 5 E-8 Sr-89, and Sr-90 are the same as Strontium-90 Sr-90 5 E-8 Unit I which are offsite vendor LLD Gross Alpha a
1 E-7 values.
'l
ATTACHMENT 5 C312-93-2014 Page 9 of 9 TABLE 2 TYPICAL GASEOUS EFFLUENT LLD (Lower Limit of Detection) VALUES ASSUMPTIONS:
Sample volume (Marinelli) 1640cc Sample volume (Particulate & Charcoal Filters) 5.7E8cc Sample Rate 2 cfm or 5.66E4cc/ min Sample Time 1 week or 1E4 min i
Sample volume-(tritium bubbled thru water) 7.56E5cc Sample Rate 75cc/ min i
Sample Time 1E4 min Sample Counting Time:
a& H-3=20 min; B=10 min;
=1000 sec Sample Counters:
emitters 25% Ge(Li) a or B Proportional Counter H-3 Liquid Scintillation Counter ISOTOPE uCi/cc LLD NOTES Gross Alpha a
1 E-15 Particulate Filter Paper Gross Beta B
1 E-14 l
Tritium H-3 1 E-10 Air bubbled thru water by a fritted disc or Fisher Milligan gas washer Krypton-85 Kr-85 5 E-6 Marinelli Krypton-85m Kr-85m 2 E-8 Krypton-87 Kr-87 6 E-8 Krypton-88 Kr-88 5 E-8 Xenon-133 Xe-133 4 E-8 Xenon-133m Xe-133m 1 E-7 i
Xenon-135 Xe-135 2 E-8 Xenon-135m Xe-135m 3 E-7 Xenon-138 Xe-138 3 E-7 Iodine-131 I-131 2 E-8 Iodine-133 I-133 3 E-8 l
Iodine-135 I-135 2 E-7 Iodine-131 I-131 3 E-14 Charcoal Filter Iodine-133 I-133 4 E-14 Iodine-135 I-135 3 E-13 Manganese-54 Mn-54 3 E-14 Particulate filter paper Iron-59 Fe-59 8 E-14 Cobalt-58 Co-58 3 E-14 Cobalt-60 Co-60 5 E-14 f
Zinc-65 Zn-65 9 E-14 Strontium-89 Sr-89 2 E-14 l
Strontium-90 Sr-90 2 E-14 Molybdenum-99 Mo-99 2 E-14 Ruthenium-103 Ru-103 2 E-14 Silver-110m Ag-110m 3 E-14 Cesium-134 Cs-134 4 E-14 Cesium-137 Cs-137 3 E-14 Cerium-141 Ce-141 3 E-14 Cerium-144 Ce-144 9 E-14
.