ML20033B686
| ML20033B686 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/27/1981 |
| From: | Chandu Patel Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033B668 | List: |
| References | |
| NUDOCS 8112010640 | |
| Download: ML20033B686 (3) | |
Text
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i;iWED STATUS Or WERfCA NUCl. EAR REGULATORY COM:11SS10N BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Mat.ter of
)
Docket Nos. 50-254 C0:EONWEALTH EDISON COMPANY 50-265 (Spent fuel Pool Modifications)
(Quad Cities Station, Units 1 and 2) )
TESTIMONY OF CHANDU P, PATEL ON CONTENTION 3.a I, Chandu P. Patel, do state as follows:
I am employed by the United States Nuclear Regulatory Commission, as a nuclear engineer in the Division of Systems Integration, Effluent Treatment Systems Branch.
This testimony addresses Contention 3.a concerning the matter of increasing the capacity of the ventilation system, which is stated as follows:
3.
"Intervenors contend that the increased amounts of irradiated fuel in the proposed spent fuel pools will increase radiological releases from the pools and occupational exposures in the pools area.
In light of this, the present radiation monitoring system is inade-quate to provide a reasonable assurance of public health and safety.
Specifically, reanalysis of the present system should be required, and should consider:
a.
increasing the capacity of the ventilation system,"
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It should be noted that the spent fuel storage capcity will be increased by changing the design of spent fuel storage racks from present design to a high density rack design. Thus, the licensee will be able to store more spent fuel assemblies in the same pool. Additional capacity will accommo-date the spent fuel which has been out of the reactor for a longer period of time, e.g., four to five years.
With respect to releases of gaseous materials to the atmosphere, the only radioactive gas of significance which could be attributable to storing additional fuel assemblies for longer periods of time would be the noble gas radionuclide Krypton-85. Other short lived radionuclides are not present
- in the aged fuel.
Due to the reduced specific activity, low radiological heating and the physical characteristics of spent fuel, there will not be a significant release of fission products, including Krypton-85, from the stored fuel after it has decayed for one year in the spent fuel pool. Thus, the amount of Krypton-85 released from the aged fuel at the spent fuel pool temperature will be neg-ligibly small.
Based on above analysis, I conclude that there is no need to increase the capacity of the ventilation system due to the increased storage of spent fuel assembli.es.
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3-The above statements and opinions are true and correct to the best of my personal knqwledge and belief.
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n.l+t f-f h Chandu P. Patel, Nuclear Engineer Effluent Treatment Systems Branch Division of Systems Integration, NRR l
Subscribed and sworn to before me thisd'M-day of November,1981.
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4 Notary Public y My Commission expires:' d'cg /, / 9 93_
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