ML19317F217
| ML19317F217 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/05/1975 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Muller D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001080929 | |
| Download: ML19317F217 (4) | |
Text
-.
~.-
\\
tu a
, /,-
DEC 0 51975 Docket No. 50-287 D. R. Muller, Assistant Director for Environmental Projects, RL SPENT FUEL POOL HDDIFICATION FOR OCONEE (TAR-3047)
We have considere?. the effect on radioactive materials in affluanta as a result of the proposed enlargement of the spent fuel storage capacity for the Oconee Nucisar Station and our comments are enclosed. Based on our evaluation, we find that the proposed modificatien will have a negligible affect on radioactive matarials released fron the site and is therefore, acceptable.
Odx,r.ai dg.~1 by:
Robert L. Tedtaeo Robert L. Tedesec, Assisunt Director for Contninment Safet7 Divd.sion of Technien1 Review
Enclosure:
As stated ces R. Boyd (w/o encl)
W. Mcdonald (w/o encl)
S. Hanauer R. Heineman
- 7. Schrooder J.' Collins K. Coller G. Zach R. Purple D. Eisenhut J. Glynn E. Jacobs D. Scaletti G. Dicker W. Barke l
M. Bell l
J. 'we Distribution:
l
[DocketFile50-287 l
'NRR Reading File CS Reading File 8001080 y ETSB Reading File i
caric s >
TR:ETSB
- 3TSB..
.IR:C ee*1w bl su.maas s >
o., 1 n
_RLT sco _
12/.h/.7.5.:
12/A/75
_12/I]l5
._.12/$ D1_
oa7s.
Ferna AEC 314 (Rev. 9 53) ABCM 0240 TT u. e. oovsnmusnv eninvine orrecas so74.eae. nee
rCc D
DEC 0 51975 m,
SPENT FUEL STORAGE POOL MODIFICATION FOR OCONEE NUCLEAR STATION, UNIT 3 DOCKET NO. 50-287 We have considered the effect on radioactive effluents of che proposed enlargement of the spent fuel storage pool at the Oconee Nuclear Station, Unit 3.
The Oconee Nuclear Station, Units 1, 2 and 3, is provided with two spent fuel storage pools. Units 1 and 2 share a common spent fuel storage pool while a separate spent fuel storage pool is provided for Unit 3.
There will be no modification for the spent fuel storage pool of Units 1 and 2, while. Unit 3 fuel storage capacity will be increased from 216 fuel assemblies to 474 fuel assemblies, an increase of 1197., by installing new racks with closer spacing of spent fuel assemblies.
There will be no change in the physical size of the fuel pool or of the spent fuel pool cleanup system. The proposed modification will permit storage of discharged fuel for an additional two years, under normal operating conditions, without the need to ship spent fuel offsite.
The Oconee 1
Nuclear Station is provided widt the capability of transferring and inter-changing the spent fuel assemblies between the two pools.
In our evaluation we have considered only the effect on the releases of radioactive material that may result from the additional two years storage time of the extra 258 fuel assemblies in the (nent fuel pool. We have considered that releases of radioactive mat,erials occur only from fuel that already contain cladding defects at the tima of discharge from the reactor and that no new cladding defects will occur while fuel is being stored in the pool.
m.
"w e
?
.g
-s.
The Oconee Unit 3 spent fuel storage pool was designed with the capability to store spent fuel discharged from the core for one year and to unload the entire core, if necessary. We have considered the potential effect on the release of radioactive materials of enlarging the spent fuel storage capacity from one year to three years.
If the applicant is to retain the capability to unload an entire core from either Unit 1, 2 or 3 to either pool, the spent fuel assemblies must be shipped offsite prior to 1977 refueling without the pool enlargement and prior to 1979 refueling with enlargement. Thus, there will be at least a storage, period of one year in the pool with or without enlargement.
The only significant radioactive noble gas isotope remaining in spent fuel stored for one year will be krypton-85, since short-lived noble gases would have decayed to negligible amounts.
Considering 0.25% of the fuel to have cladding defects, we have calculated the inventory of krypton-85 in fuel rods with cladding defects in an average fuel assembly that achieved the design equilibrium burnup of 33,000 mwd /MTU to be 3.4 C1/ assembly.
Since 1
the storage capacity of the pool is proposed to be enlarged by 258 fuel assemblies, the inventory of krypton-85 in all of the fuel with cladding defects in these assemblies is calculated to be 867 C1.
On this basis, we estimate the amount of krypton-85 that could potentially be released from these 258 fuel assemblies during the three year storage period to be 289 Ci/yr, which is a small fraction of the total of 19,400 Ci of all noble gases released from Units 1 and 2 during 1974.
e
S m
.m
~3-j
=
Iodine-131 releases from the plant will not be increased by the addition ot fuel storage capacity since the additional fuel stored in the pool will have decayed for a year or more and the iodine-131 inventory in the fuel will have decayed to negligib1'e levels.
Nonvolatile fission products and corrosion products that enter the water in the fuel storage pool will be removed by the fuel pool cleanup system.
The cleanup system consists of two filters and a mixed-bed demineralizer, each rated at 180 gpm, which are in continuous service. The fuel storage pool contains approximately 500,000 gal of water, so that the cleanup system is capable of processing the pool contents in approximately 2 days.
The principal effect of the increased spent fuel storage capacity due to leakage of nonvolatile radioactive materials into the pool water will be an increase in the quantity of radioactive materials accumulated on the fuel pool filter and demineralizer, which are disposed of as solid waste.
In our evaluation we considered the quantity of long-lived radioactive materials removed by the cleanup system increased in proportion to the increased st irage capacity, therefore, the quantity and curie content of the solid wastes from the fuel pool cleanup system would increase by approximately 119%. However, these additional spent resin and filter cartridge wastes will be a small fraction of the total quantity of solid wastes shipped from the site (less than 1% by volume), so that.the overall impact on solid waste shipments will be negligible.
Based on our evaluation, we find that the proposed modification will have a negligible effect on radioactive materials released from the site.
h