ML19345H369
| ML19345H369 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/15/1981 |
| From: | Hovey G METROPOLITAN EDISON CO. |
| To: | Barrett L Office of Nuclear Reactor Regulation |
| References | |
| LL2-81-0136, LL2-81-136, NUDOCS 8105200215 | |
| Download: ML19345H369 (4) | |
Text
+
[#
.r#
[l 1
g
- }
xQ
.-/ <
Metropoliun Edison Company b, =! 't1 I ;*{ l
- y I
~ji Post Office Box 483 T' rg )
e M.ccmom, Pennsylvania 17C57 j
U-
- C. v4 %
, - - 1 na s /. A' u.s. rw.ua uatwont W"I'f'8 Direct Diat N ece.
Nm CP4
/,s
-8T 0 36 5
/
M.
=
W.
Y.=
N
- 1"
m --
D TMI Progran 0f fice 2
Attn:
Mr. L. H. Barrett, Deputy Director i n,.
U WE U. S. Nuclear Regulatory Commission c/o Three Mile Island Nuclear Station
.h Middletown, Pennsylvania 17057 c;;:,
w w
Dear Sir:
Three Mile Island Nuclear Statien, Unit 2 (TMI-2)
Operating License No. D?R-73 Docket No. 50-320 Submerged Demineralizer System During discussions with ac=bers of your staf f we have been requested to provide the folbwing additional infor=stien in support of the SDS Safety Review:
"The licensee will update alcborne source cerm description to include !ewatering operations and the use of processed water in the SFP.
Provide analysis of the radiological fuel consequences of placing processed water in the spent pool to NRC. This submittal should include (and, perhaps, be based on) data from previous storage of processed water in the pool."
This sub=ittal responds to that request.
Asn=ptions used for development of source ter=s associated with filling the spent fuel pool with triciated water and, hence, release rates are defined below.
H-3 1.0 pCi/::j Cs-134 1.0 x 10 1.6x10i Cs-137 Sr-39 8.0 x 10
- Sr-90 2.7 x 10-It is to be noted that the H-3 concentration in the water currently used to fill the pool is approximately 0.2 uCi/ml. Therefore, the release n.ce calculst.ed is actually higher (by about a factor of 500) than the o/
/g}
actual release rates we have seen in the past. Two primary factors contribute to this conservatism. They are:
1.
The evaporation rate factor is conservative.
l 2.
The H-3 concentration is lower than assuced.
!810520 N/S
'cr:= ur E:sc-cc ca^. s 3 /e-: e co e Ge n u : u tes s s e-
Mr. L. H. Barrett LL2-81-0136 We may, however, elect to fill the spent fuel pool with triciated water with a concentration of up to 1 pCi/ml.
Table 1 provides the results of our analysis for filling the spent fuel pool with critiated water.
During the process of dewatering spent SDS liners, the airborne source term will be increased as a result of the devatering operations. This increase in airborne radioactivity may be due to two primary factors.
They are:
1.
Airborne source term as a result of possible radionuclide '
concentration in the water.
2.
Zeolite fines carryover during dewatering.
Table 2 provides the results of our analysis for the airborne source term durivi dewatering Operations.
Should you wish to discuss this matter further, please. contact Mr. L. J.
Lehman, J r. o f my s taf f.
Sincerely, a
G. K. Hovey Vice-President and Director, TMI-2 GKH:LJL:djb Attachment Dr. B. J. Snyder, Program Director - TMI Program Of fice cc; f.
p Table 1 Source Term of Gaseous Effluents Filling of Spent Fuel Fool with Processed Water Concentration Entering Concentration F.H. Bldg. Ventilation (a) in P; ant Effluent (b)
Release Rate Radionuclide tCi/mi uCi/mi-tCi/see
-6
-7 H-3 2.5 x 10 3.5 x 10 16.5
-1
-18
-10 Sr-89 2.0 x 10 2.8 x 10 1.3 x 10
-17
-20
-A Jr-90 6.7 x 10 9.4 x 10 4.5 x 10
-15
-18
-10 Cs-134 2.5 x 10 3.5 x 10 1.7 x 10
~1'
-18
-10 Cs-137 4.0 x 10 5.6 x 10 2.6 x 10 (a) This uis the catculated radionuclide concentration in the air entering the fuel 6
handling building ventilation. An entrainment factor of 10 and ventilation flow rate of 14000 CFM on 347' elevation with a resulting evaporation rate was assumed.
This is the calculated radionuclide concentration in ene off-gas (100,650 ft.3 (b)
/ min.) from TM1-II as it enters the atmosphere. An additional DF of 100 is is assumed for critiu=.
assumed for particlates however no further treatment l
l l
L i.
i
- _ _., _ _. _ -, _., ~. _. _, _,, _, _ _.
~._
.. - ~..,. -
f l
,s*. Source Term for Dewatering Liners Including Zeolite Fines Carryover Dewatering Concentration in SDS Dewatering Effluent Concentration in Air (a)
Plant Effluent (b)
Release Rate Radionuclide U Ci/ce_
UCi/cc u C1/sec.
~9 H-3 5.1 x 10 3.3 x 10 0.2
~
-12
-6
-8 Sr-89 8.0 x 10 5.2 x 10 2.4 x 10
-10
~13
~
Sr-90 2.7 x 10 1.7 x 10 a.3 x 10 6
-8 Cs-134 1.0 x 10~
6.5 x 10 3.1 x 10
~11
-15
-8 Cs-137 1.6 x 10 1.0 x 10 4,9 x 70 Zeolite Fines Carryover Concentration in SDS Dewatering Effluent Concentration in Air (a)
Plant Effluent (b)
Release Rate Radionuclide uCi/cc UCi/cc uCi/sec.
-13
~1
-10 Cs-137 2.1 x 10 1.3 x 10 6.3 x 10
-10
-14 Cs-134 3.4 x 10 2.2 x 10~
1.0 x 10
~1'
-18
~11 Sr-90 3.3 x 10 2.1 x 10 9.9 x 10
-16
-0
-12 Sr-89 6.9 x 10 4.5 x 10 2.1 x 10 This is the calculated radionuclide concentration in the off-gas (650 f t.3 (a)
/ min.) following treat =ent f rom the SDS prior to entering the existing effluegt treatment system in TM1-II.
DF of 100 and an entrainment facter 7
No effluent treat =ent is of 10 have begn assumed for particulates.
assumed is for H.
This is the calculated radionuclide concentratien in the off-gas (100,650 f t.3 (b) of 100 is
/ min.) from TM1-11 as it enters'the atmosphere.
AnadditionalD{H.
is assumed for assu=ed for particulates and no further treatment n