ML20070V686
| ML20070V686 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 02/09/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070V683 | List: |
| References | |
| NUDOCS 8302170519 | |
| Download: ML20070V686 (2) | |
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i, NUCLEAR REGULATORY COMMISSION 5
- a WASHINGTON, D. C. 20066 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 81 TO LICENSE NO. DPR-49 IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER 1.0 Introduction By letter dated December 6,1982 Iowa Electric Light and Power Company (the licensee) forwarded a proposed Technical Specification change that would permit defueling and refueling while the torus is drained or has a reduced water volume.
The justification for the change is schedular, i.e. the duration of the Duane Arnold Energy Center (DAEC) Cycle 7 refueling outage, scheduled to commence in early February 1983, is controlled by containment modifica-tions that require the torus to be drained. The ability to defuel or refuel while the torus is drained or with a reduced water volume will save approximately 3 weeks of the critical path refueling outage duration.
2.0 Evalua tion During defueling or refueling operations, the licensee proposed to provide at least one core spray loop with the condensate storage tank as the water source.
In addition, the licensee would provide controls to ensure that the upper pool level and the condensate storage tank water volume would have adequate water available during all fuel movement operations and also, stated that the proposed chaage is consistent with the Standard Technical Specifications for General Electric Roilina Water Reactors HUREG-0123 Rev. 3, Sections 3.5.2 and 3.5.3.
In our review of the proposed specifications, we evaldated the systems required, water level demands for shielding and heat: dissipation, and design basis accident recovery requirements during refueling operations and found the proposed Technical Specifications to be conststent with
' Standard Technical Specifications for General Electric B.oilinn Water Reactors.
The BWR Standard Technical Specifications served as the basis in assessing the acceptability of the proposed change. The model Technical Specifica-tions, Sections 3.5.2 and 3.5.3 pertaining to refueling operations is recognized by the staff as an acceptable implementation of the limiting conditions of operation for the emergency core cooling systems. There-fore, we find the proposed Technical Specification acceptable.
8302170519 830209 PDR ADOCK 05000331 P
3.0 Environmental Considerations We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental *1mpact. Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 351.5(d)(4), that an environmental impact statement, or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of this amendment.
4.0 Conclusion We have concluded, based on the considera'tions discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated, does not create the possibility of an accident of a type different from any evaluated previously, and does not involve a significant reduction in a margin of safety, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in canpliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated:
February 9,1983 Pincipal Contributor:
F. L. Apice11a r
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