ML20212F596
| ML20212F596 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 12/31/1986 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20212F485 | List: |
| References | |
| NUDOCS 8703050119 | |
| Download: ML20212F596 (25) | |
Text
ATTACHMENT 5 4410-87-L-0031
,. Page 1 of 13 t
EFFLUENT AND WASTE DISPOSAL SE:E ANNUAL REPORT July 1, 1986 to December 31, 1986 SUPPLEMENTAL INFORMATION FACILITY T!!I- Unit 2 (including EPICOR II) LICENSEE DPR-73-320
- 1. ~ Regulatory Limits
- a. Fission and activation gases:
- c. ates, half-lives > 8 days: Env mental Tech Specs,
- d. Liquid effluents: *
- 2. Maximum Permissible Concentrations Provide the MPCs used in determining allowable release rates or concentrations.
a, Fission and activation gases:
- c. Part ates, half-lives >8 days: 10 CFR, Part 20, Appendix B
- d. Liquid effluents:
- 3. Average. Energy Provide the average energy (E) of the radionuclide mixture in releases of fission -
and activation gases, if applicable 0.253 Mev (Kr-85)
- 4. Measurements and Approximations 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: Ge(Li) Spectronotry, Liquid Scintillation
- b. Iodines: Ge(Li) Spectrometry
- c. Particulates: Ge(Li) Spectrometry, Gas Flow Proportional
- d. Liquid effluents: Ge(L1) Spectromerty, Liquid Scintillation
- 5. Batch Releases '
Provide the following information relating to batch releases of radioactive materials. .
in liquid and gaseous effluents. . 1986 1986 3rd Quarter 4th Quarter
- 1. Number of batch releases: 40 35
- 2. Total time period for batch release: N/A N/A
- 3. Na v4 == time period for a batch release: N/A
- 4. N/A Average time period for batch releases: N/A N/A
- 5. Minimum time period for a batch release:
- 6. N/A N/A Average stream flow during periods of release of effluent into flowing stream: N/A N/A
- See Note (1) and
- on Page 6 of this report N/A = Not Applicable 19 W O O
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ATTACHMENT 5 4410-87-L-0031 .
Page 2 of 13
- 5. Batch Releases (cont.) _1986 1986 3rd Quarter 4th Quarter B. Gaseous
- 1. Number of batch releases: 0 2
- 2. Total time period for batch releases: N/A
- 3. Maximum time period for a batch release: 843 Minutes N/A 483 Minut&s
- 4. Average time period for batch release: N/A
- 5. Minimum time period for a batch release: 422 Minutes N/A 360 Minutes
- 6. Abnormal Releases
- A. Liquid
- 1. Number of releases:
- 2. None None Total activity released:
N/A N/A B. Gaseous
- 1. Number of releases:
- 2. Total activity released: e 1 NofA N , 2.77E-2*
- Attributed to Unit-1 from a release on 10/29/86. See the Unit-1 Semi-Annual report for this time period.
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ATTACHMENT 5 4410-87-L-0031 ,
Page 3 of 13 TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES UNIT 3rd 4th EST. TOTAL II QgER QU I 86
- A. Fission & activation gases
+
h Total release Ci <LLD 2.80E-1 - 60%
- 2. Average releace rate for period UCi/sec. N/A 3.52E-2 Tech Spec Limits
- 3. Percent of Tech Spec limit %
N/A 4.89E-4 7.20Et3 pCi/sec for B. Iodines . Kr-85
_1. Total Iodine-131 Ci < LLD < LLD . I 60% {
- 2. Average release rate for period uCi/sec. N/A N/A Tech Spec Limit =
- 3. Percent of Tech Spec limit 2.40E-2 pC1/sec.
% N/A N/A C. Particulates
- 1. Particulates with half-lives
> 8 my, C1- 1.38E-4 1.50E-5 I 60%
- 2. Average release rate for period iCi/sec. 1.74E-5 1.88E-6 Tech Spec Limit =
- 3. Percent of Tech Spec limit % 7.25E-2 7.83E-3
- ~ "'*
- 4. Cross alpha radioactivity C1 2.49E-6 4.32E-7 D. Tritium
- 1. Total release ci 1.11El 1.73E1 60% -
- 2. Averate release rate for period 11Ci/sec. 1.40E0 2.18E0 Tech Spec T.imit =
- 3. Percent of Tech Spec limit 4.80E+3 yCi/sec for
% 2.92E-2 4.54E-2 H-3 to
+e
ATTACHMENT 5 4410-87-L-0031 Page 4 of 13 TABLE IB EFFIlJENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-GROUND LEVEL RELEASE Continuous Mode Batch Mode Nuclides 1986 1986 1956 Released UNIT 3rd 1950 4th 3rd 4th II QUARTER QUARTER QUARTER QUARTER
- 1. Fission gases krypton-85 Ci < LLD <LLD <LLD 2.80E-1 krypton-85m Ci <LLD < LLD <LLD < LLD krypton-87
. Ci < LLD <LLD < LLD < LLD krypton-88 Ci < LLD < LLD < LLD < LLD xenon-133 Ci < LLD <LLD <LLD < LLD xenon-135 Ci < LLD < LLD < LLD < LLD l xenon-135m Ci < LLD
! < LLD ILLD < LLD xenon-138 Ci 4LLD < LLD :LLD < LLD Others (specify) Ci < LLD < LLD
Ci Ci 1 -
Ci Ci
~
___ Unidentified Ci < LLD < LLD < LLD < LLD Total for period Ci N/A < LLD N/A 2.80E-1 -
- 2. Iodines -.
iodine-131 Ci < LLD < LLD
' N/A N/A iodine-133 Ci < LLD < LLD N/A N/A iodine-135 Ci < LLD < LLD N/A N/A Total for period N/A Ci N/A N/A N/A i
.3j. .. . '.gi-u,_
ATTACHMEN[5 4410-87-L-0031 '
Page 5 of 13 TABLE IB (cont.)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides UNIT lhD $ $ @D Released II kUARTER QUARTER QUARTER QUARTER 3 Particulates strontiune-89 Ci <LLD
<LLD N/A N/A Ci 6.98E-5 <" "#^
N/A strontiusr-90
< LLD < LLD N/A n/a bariune-lanthanunr-140 Ci Others (specify) < LLD < LLD N/A N/A Unidentified
- 6.60E-5 1.50E-5 N/A N/A
- On-site analyses indicated that Sr-90 was <tLD at <7.0E-12uCi/cc for the period of 08/10/86 to 08/11/86. However, off-site analyses for the same period indicated Sr-90 present at 6.20E-13uCi/cc which is equivalent to 2.91uCi Sr-90.present in
- 34.4uci gross beta. Also, on-site analyses indicated that Sr-90 was <LLD at
<2.6E-11uci/cc for the period of 08/11/86 to 08/17/86, while off-site analyses indicated Sr-90 present at 2.33E-12uCi/cc equivalent to 66.9uCi Sr-90 present in 89.0uCi gross beta. These increases are considered to be artifacts of low sample flowrates used to achieve combined particulate, iodine, and noble gas grab samples.
,> -- - - , , - . . . . - . , . , - , , , , , - - , - - - - - , . . , - - . . - , , _ , . _ , . ,..-.--,-.-,--._,,,.,._..w- _n --,,-n,,,_n
ATTACHMENT 5
,, . 4410-87-L-0031 ,_
Page 6 of 13 TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Tech Spec Limit = 10CFR20, Appendix B Table II, Column 2 UNIT EST. T(yIAL II Q TER QU b R ERROR %
A. Fission and activation products u a .a$cha$ Ci 4.45E-5
- 2. Average diluted concentratl 7.34E-5 i,60%
durine eeriod
- mci /mi 4.07E-12 5.65E-12 Based on 2E-5
- 3. Percent of applicable limit pCi/ml (Cs 137)
% 2.04E-5 2.83E-5 B. Tritium
- 1. Total release Ci 4.60E-4
- 2. Average dilutec concentration 2.51E-4 60%
durine period uti/ml 4.11E-11 1.93E-11 Based on 3E-3
- 3. Percent of applicable limit %
1.37E-6 6.43E-7 C. Dissolved and entrained gases
- 1. Total release Ci <LLD
- 2. Average dilutea concentration <LLD i 60%
durine period UCi/ml N/A N/A
- 3. Percent of applicable limit %
1 N/A N/A D. Cross alpha radioactivity
- 1. Total release Ci Note 1 Note 1 I 60%
l .
E. Volume of waste releasea (prior to dilution) liters 1.37E 5 1.10E 5 I 25%
.F. Volume of dilution water used durine seriod liters 1.09E 10 1.30E 10 I 10 i Includes only concentration those releases mentioned in Note (1) which were found to contain radioisoto
>LLD.
Note (1)
There were no liquid releases from the radwaste system during the second half of 1986 since this system is flanged off from the discharge lines.
areradionuclides of appropriatelyhave beeninoccasionally included Item A2. found in the industrial waste stream andHowever Note (2) Refer to Table 5 for Typical LLD values.
Note (3) the values reported include Sr-90 activity and any activity not specifically identified Thus, the reported Sr-90 value represents a conservative estimate (i.e. overestimate) and contains activity from other beta-gamma emitters which were not positively l
i identified during conduct of analytigal procedures,
- s. _ _ . ._ .. ___ _ . _ _ . . - - _
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ATTACHMENT 5 '
4410-87-1.-0031 ..
Page 7 of 13 ~
e TABLE 2B '
EFTLUENT AND ilASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS 4
l'
_o Continuous Mode 3atch Mode Nuclides 1950 - 1986 1959 UNIT Avoo 3rd 4th 3rd 4th Released II QUARIER QUARTER QUARTER, QUARTER strontium-89 see oee - -
Ci Nnen m Note (2) < LT D < LLD /
strontium-90Note(3) Pg.6 Ci 3.22E-5 4.40E-5 '
cesium-134 Ci ' '
' O*'IE~#
cesium-137 Ci iod ine-131 ~ 1.01E-5 2.90E-b c4 <LO
- t. <LLD cobalt-58 '.h. '
/
cobalt-60 Ci ELLD <tLD ! i fron-59 Ci
~
<LLD <LLD zine-65 Ci
<LLD <LLD 6 manaranese-54 Ci <LL i <LLD 2 chromium-51 Ci ~
<LLD <LLD zirconium-niobium-95 Ci
< LLD <LLD molybdenum-99 i Ci ~
) technetium-992 '
<LLD Ci 1 (LLD ' <LLD barium-lanthanum-140 Ci # <LlD cerium-141 Ci
< LLD <LLD <
_ Other (specifv) Ci < LLD g.LD Ci CJ_ f .
Ci
""~
Ci .
, I ,
Ci s,
N
_ xenon-135
_Ci
.m I
' l
-_ _ . = _ _ _ _ - _ - . _ _ . , _ . . - . - - _ _
r ATTACHMENT 5 4410-87-L-0031 Unit 2 -Eipcor Liners-July Thru December 1986
[ TABLE 3A p s EFFLL*ENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid waste shipped off-site for burial or disposal (not irradiated fuel)
- 1. Type of vaste UNIT f,$[ hRRbR
- a. Spent resins, filter sluages, m' evaporator bottoms, etc. 39.3 m# 5%
Ci 30.465 Ci
- b. Dry compressible waste, contaminated m 3 N/A N/A equipment, etc. c4
- c. Irradiatec components, control m 3 rods, etc.
Ci N/A N/A 6
D3
- d. Other (describe) Ci N/A N/A
- 2. Esti=ste of major nuclide composition (bv type of waste)
- a. Sbl,g5 35.44 %
- .Pm147 MO 24.33t a, 17.56t Te125m 8.874 %
b.
y
?
- c. y i
r
~
~
d.
y
.< g
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 7 Shipments Tractor-Cask (HN-100 series 3) Hanford-Richland.WA.
o 2 Shipments 1 Shipment Tractor-Cask (NuPac 14/190M) Hanford-Richland.WA.
Tractor-Flatbed Hanford-Richland.WA
/
B. ' Irradiated Fuel Shipments (Disposition)
Number of Shipments Mode of Transportation Destination N/A
, Orpf.'cor resin shipped as follows:8 steel liners (161 ft )
i~
2 steel liners (50 ft3) c4 NOTE:
6 of the 10 Epicor Liners used Sr90 exemption at Hanford to be classified Class A
' ATTACHMENT 5
,4410-87-L-0031 0
Unit 2 LSA july thru december 1986
(
'TABL$ 3A {
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPCF.T l SOLID WASTE AND IRRADIATED FUEL SHIP.M TS l
4 A. Solid waste shipped off-site for burial or disposal (not irradiated fuel)
- l. Type of waste 6 UNIT o[yh {SyUR g a. Spent resins, filter sludges, '
m' evaporator bottoms, etc. ,
Ci N/A , N/A
- b. Dry compressible waste, contaminated: n 3 121.27m' 5%
2.224 Ci.
, equipment, etc. c4
- c. Irraciatec components. control m3 rod s , e tc. Ci N/A N/A m3
- d. Other (describe) C1 N/A N/A !
i 2., Estimate of major nuclide comDosition (bv type of waste)
- a. %
T
- b. Sr90 41.31 7 Cst 17 36.09*
Pm147 6.624g Rul06 3.429%
Pu241 2.7757,
- c. g i T
~
- d. g
~
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination O 4 Shipments Tractor-Closed Ven Hanford-Richland,WA 3 Shipments Tractor-Flatbed Hanford-Richland,WA B. Irradiated Fuel Shipments (Disposition)
Number of Shipments Mode of Transportation Destination 3
- LSA shipped as follows:375 Drums (7.5 fg each) 15 Boxes (98 ft each)
_. _ - , - - - - -_ -.r,- ,_.- y
)
ATTACHMENT 5 4410-87-L-0031 l Page 10 of 13 i Unit 2 H.i.C. s July thru December 1986 i l
TABLE 3A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS I i
A. Solid waste shipped off-site for burial or disposal (not irradiated fuel)
- 1. Type of waste 0
- a. Spent resins, filter sludges, UNIT m'
0e [ $6R evaporator bottoms, etc. Ci N/A, N/A
- b. Dry compressible waste, contaminated m 3 5.66m' equipment, etc. 5%
c4 13.082C1.
- c. Irradiatec components, control m 3 rods, etc. N/A N/A Ci m3
- d. Other (describe) Ci N/A N/A
- 2. Estimate of major nuclide composition (by type of waste)
- a. N/A %
T t
- b. Csl37 47.177 Sr90 36.16i Tc99 10.92%
Pml47 1.997%
Cs134 1.13 %
c.
g
\%
d.
g l
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation 0 Destination 1 Shipment Tractor-Cask (NuPac14/190M) Hanford-Richland,WA.
3 Shipments Tractor-Cask (HN-100 series 3) Hanford-Richland,WA.
i B. Irradiated Fuel Shipments (Disposition)
Number of Shipments Mode of Transportation Destination OShipped as follows:4 H.I.C.s (50 ft each)
NOTE:2 Class B 2 Class C
-- - ~ -.-
' ATTACHMENT 5
-
- 4410-87-L-0031 Page 11 of 13 Unit 2 Fuel Debris Shipments TABLE 3A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid waste shipped off-site for burial or disposal (not irradiated fuel)
- 1. Type of waste 0 UNIT oe! $6R
- a. Spent resins , filter sludges
- m' evaporator bottems. etc. Ci
- b. Dry co=pressible waste, contaminated m3 equipment, etc. c4
- c. Irraciated components, control m 3 rods, etc. Ci mJ
- d. Other (describe) Ci
- 2. Estimate of major nuclide comoosition (by type of waste)
- a. % )
T b.
y y
l 1
- c. g i l d.
7
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination B. Irradiated Fuel Shipments (Disposition)
Number of Shipments Mode of Transportation Destination 5 Shipments 125B Rail Cask INEL-Scoville, Idaho
s -
ATTACHMENT 5 4410-87-L-0031 Page 12 of 13 TYPICAL L10UID EFFLUENT LLD (Lower' Limit of Detection) VALUES ASSUMPTIONS: Sample volume = 1 liter = 1000 cc Sample counting time = 1000 see Sample counted with a 25% Ge(Li) for Gamma Emitters ISOTOPE- Ci/cc LLD NOTES Gross Alpha a 4E-9 Counted with proportional counter Gross Beta # 7E-8 Counted with proportional counter
-Tritium H-3 4E-6 Counted with liquid scintillation counter Krypton-85 Kr-85 1E-4 Xenon-131m Xe-131m 2E-5 Xenon-133 Xe-133 1E-6 Xenon-135 Xe-135 3E-7 Chromium-51 Cr-151 3E-6 Manganese-54 Mn-54 4E-7 Cobalt-58 Co-58 4 E-7 Iron-59 Fe-59 9 E-7 Cobalt-60 Co-60 6E-7 Zinc-65 Zn-65 1E-6 Zirconium-95 Zr-95 7E-7 Niobium-95 Nb-95 4E-7 Molybdenum-99 Mo-99 3E-7 Technetium-99m Tc-99m 3E-7
, Silver-110m Ag-110m 6E-7 l
Antimony-125 Sb-125 9E-7
- Cesium-134 Cs-134 SE-7 Cesium-136 Cs-136 4E-7 l Cesium-137 Cs-137 SE-7 Barium-140 Ba-140 1E-6 Lanthanum-140 La-140 7E-7 Cerium-141 Ce-141 SE-7 Cerium-144 Ce-144 3E-6
-Iodine-131 1-131 3E-7 t
Iodine-133 1-133 4E-7 l Phosphorus-32 p-32 1E-6 These LLD values for liquid Iron-55 Fe-55 SE-8 sample analyses of gross alpha, Strontium-89 Sr-89 SE-8 P-32, Fe-55, Sr-89, and Sr-90 Strontium-90 Sr-90 SE-8 are the same as Unit 1 which are Gross Alpha a 1E-7 offsite vendor LLD values.
. .. 4!
o .
_-l;f;;;-... ; CD%#
ATTACHMENT 5 4410-87-L-0031 Page 13 of 13 TYPICAL GASEOUS EFFLUENT LLO (lower limit of Detection) VALUES ASSUMPTIONS: Sample volume (Marinelli)' ~1640cc Sample volume (Particulate & Charcoal Filters) 5.7E8cc Sampling Rate- 2 cfm or 5.66E4cc/ min 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; $ =10 min; 7 =1000sec Sample Counters: y emitters 25% Ge(Li) a or S Proportional Counter H-3 Liquid Scintillation Counter ISOTOPE Ci/cc LLD NOTES Gross Alpha a 1 E-15 Particulate" Filter Paper Gross Beta # 1 E-14 Tritium H-3 1 E-10 Air bubbled thru water by a fritted disc or Fisher Milligan gas washer Krypton-85 Kr-85 SE-6 Marinelli Krypton-85m Kr-85m 2E-8 "
Krypton-87 Kr-87 6E-8 "
Krypton-88 Kr-88 SE-8 "
Xenon-133 Xe-133 4E-8 "
Xenon-133m Xe-133m 1E-7 "
Xenon-135 Xe-135 2E-8 "
L Xenon-135m Xe-135m 3E-7 "
Xenon-138 Xe-138 3E-7 "
Iodine-131 1-131 2E-8 "
Iodine-133 I-133 3E-8 "
Iodine-135 I-135 2E-7 "
Iodine-131 1-1 31 3E-14 Charcoal Filter Iodine-133 I-133 4E-14 "
lodine-135 I-135 3E-13 "
Manganese-54 Mn-54 3E-14 Iron-59 Particulate filter Paper Fe-59 BE-14 "
Cobalt-58 Co-58 3E-14 "
Zinc-65 Zn 9E-14 "
Strontium-89 Sr-89 2E-14 "
Ruthenium-103 Ru-103 2E-14 "
Silver-110m Ag-110m 3E-14 "
Cesium-134 Cs-134 4E-14 " '
Cerium-141 Ce-141 3E-14 "
Cerium-144 Ce-144 9E-14 *
..r .
QQ@L.s . . ' %';-
____ . - _ _ _ - _ -