ML19308B044
| ML19308B044 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/13/1967 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19308B034 | List: |
| References | |
| NUDOCS 7912120797 | |
| Download: ML19308B044 (3) | |
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sFFHCHAL USE ONL1 ii. 3 3 tyf7 LS, ATOMIC ENERGY _ COMMISSION DIVISION OF REACTOR LI_CENSINC FEPORT TO THE ADVISORY COMMITTEE ON REACTOR SAFECUARDS IN THE MATTER OF PRELIMINARY ASPECTS OF DUKE POWER COMPANY'S APPLICATION FOR A CONSTRUCTION PERMIT FOR ITS PROPOSED OCONEE NUCLEAR STATION UNITS 1 AND 2 l
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i; Note by the Director. Division of Reactor Licensine, The attached report has been prepared by the Division of Reactor Licensing for consideration by the Advisory Committee on Reactor Safeguards at its February 1967
- meeting, i
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-7912120 yyy OFFHCHAL USE ONLY
i JFFHCHAL USE ONLi The Duke Power Company has submitted an application dated December 2.1966, for a construction permit and operating license for its Oconee Nuclear Station Units 1 and 2 to be located on the shore of the future Lake Keowee in Oconee County, South Carolina.
The site will have an exclusion radius of 1 mile and 3 residences are located on the site. The nearest population center, Anderson, South Carolina (population 41,000), is about 21 miles southeast of the site.
Cooling water for the units will be provided from Lake Keowee. Earthen dams to form this lake are under construction. The foundation for the containment structure i
will be bedrock. The site grade will be about four.ieet below the level of the lake, I
but the land to the south and west slopes sharply away from the site.
The pressurized water reactor and steam system supplied by Babcock and Wilcox will be designed for an initial core thermal power level of 2452 Mw thermal (839 We) and an ultimate core thermal output of 2568 W thermal.
The reactor nuclear design parameters present no extreme departures it em recent designs proposed for the Turkey Point or Indian Point No. 2 reactors.
As in these reactors, a positive moderator temperature coefficient is predicted, but space is provided for the insertion of fixed poison shims to reduer. this coefficient if this is found necessary. A new statistical heat transfer analysis is used based on the BAW-168 correlation.
The control rod drive is a rack and pinion type which utilizes a nutating disk actuator to drive the pinion. The nutating drives are magnetically operated and hermetically sealed. The drives are being developed by the Diamond Power Specialty Corporation.
A unique ?eature of the steam system is the use of two once-through steam generators that will produce steam having approximately 35 deqrees of superheat.
The primary coolant enters the top of each steam generator through a single hot leg and returns to the reactor via two cold legs.
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JFFHCHAL USE ONLi r..
_2-Point and The proposed prestressed containments are similar to the Turkey No iodine removal equipment is provided in the containment Palisades containments.
l to the containment has pro-although a controlled leakage penetration room externa vision for iodine filtration, 1 and 2 in the A nutaber of engineered safety features are shared between Units In addition, it appears that the active components of many of th proposed design.
l operation. We understand engineered safety features will be in use during norma rt will be modified to h
that the low pressure injection systems as shown in t e repo
.l include core flooding tanks (accumulators).
hydro peaking Emergency power for the plant will be provided f rom two 80 We Steam-driven pumps are provided for decay heat plants located adjacent to the units.
blackout conditions removal, and shutdown cooling capability can be extended under tem.
by gravity flow f rom the lake through the condenser cooling water sys be no safety Based on a preliminary review of the application, there appear to problems which cannot be resolved.
y OFFECHAL USE ONLY