ML20033B707
| ML20033B707 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/27/1981 |
| From: | Bevan R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033B668 | List: |
| References | |
| NUDOCS 8112010657 | |
| Download: ML20033B707 (3) | |
Text
(
I, Roby Bevan, being duly sworn, state that I hm an employee of the U.S. Nuclear Regulatory Comission (NRC). My present position is Operating Reactors Project Manager, Operating Red tors Branch #2, Division of Licensing within the Office of Nuclear Reactor Regulation.
The purpose of my affidavit is to respond to a contention having to do with the adequacy of the spent fuel pool cooling systems and the adequacy of the spent fuel pool cleanup systems. An exact statement of the contention and my response to that contention follows.
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8112010657 811127 PDR ADOCK 05000254 PDR
Contention 5 Intervenors contend that in the light of the increase in decay heat which will result from the proposed increase in the spent fuel pools' storage capacity, the current capacity of the radioactive waste treatment and cooling system for the spent fuel pools will be inadequate for the proposed modification, therby failing to provide the requisite assurance of public health and safety.
Response to Contention 5 In response to the part of the contantion concerning the adequacy of the pools' cooling system, reference is made to the response given for contention 1.
As stated there, the presently installed pool cooling capability is more than sufficient to handle the heat load with the pool filled to the limit of the proposed capacity. At present, the pool heat load is held by using only one of two cooling loops for each of the two units.
Should the reracking proposal be implemented and the new storage spaces be gradually filled up over the years, the average age of the spent fuel in the pool will increase, so that the aversge decay rate and heat load per asen bly stored will decrease. Should the pools be filled to capacity in this manner mi some time in the future, the heat load on the pool will OdVO been increased by only 50% or less over what is is now. This is well within the present cooli.g capability of the system.
In response to the part of the contention concerning the adequacy of the radioactive " waste treatment system --- for the spent fuel pools,"
some clarification is in order. Strictly speaking, there is no such system; we believe, however, that the contention is meant to refer to the spent fuel pool cleanup system. This is the system that provides for the
removal of radioactive materials, corrosion products and other impurities from the pool.
The staff has completed its review of that portion of the Licensees' applicatio'n having to do with the spent fuel pool cleanup system.
This evaluation has been officially transmitted from the Division of Engineering to the Division of Licensing for inclusion in the forthcoming Safety Evaluation Report on the Quad Cities Station augmented spent fuel storage application. The material in this evaluation addresses the concerns expressed by the Intervenors and a copy is attached hereto in response to the stated concerns.
The attached report might be changed somewhat by editing before inclusion in the forthcoming Safet;/ Evaluation Report.
It is not anticipated, however, that any substantive or conclusory changes will be made unless unexpected new information that differs significantly from that on which the evaluation was based comes to light.
The above statements and opinions are true and correct to the best of ray knowledge and belief.
f Roby B. Bevan, Jr.
Subscribed and sworn to before me this G ih day of November, 1981.
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Notary,Public J My Connission expires:
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