ML20237C568

Proposed Tech Specs,Authorizing Use of Fuel Assembly & Control Blade Lead Test Assemblies Subj to Prior Written NRC Approval

ML20237C568
Person / Time
Site:	Cooper
Issue date:	12/14/1987
From:	NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20237C388	List: ML20237C385 ML20237C568
References
NUDOCS 8712210390
Download: ML20237C568 (1)

Text

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5.0 MAJOR DESIGN FEATURES 5.1 Site Features The Cooper Nuclear Station site is located in Nemaha County, Nebraska, on the west bank of the Missouri River, at river mile 532.5. This part of the river is referred to by the Corps of Engineers as the Lower Brownvill a Bend.

Site coordinates are approximately 40' 21' north latitude and 95' 38' west longitude. The site consists of 1351 acres of land owned by Nebraska Public Power District. About 205 acres of this property is located in Atchison County, Missouri, opposite the Nebraska portion of the station site. The land area upon which the station is constructed is crossed by the Missouri River on the east and is bounded by privately owned property on the north, south, and west. At the west site boundary, a county road and Burlington Northern Railroad spur pass the site.

The reactor (center line) is located approximately 3600 feet from the nearest property boundary. No part of the present property shall be sold or leased by the applicant which would reduce the minimum distance from the reactor to the nearest site boundary to less than 3600 feet without prior NRC approval.

The protected area is formed by a seven foot chain link fence which surrounds the site buildings.

5.2 Reactor A. The core shall consist of n6e more than 548 fuel assemblies in any combination of 7x7 (49 fuel rods) and 8x8 (63 fuel rods) and 8x8R/P8x8R/BP8x8R (62 fuel rods). -

B. The core shall contain 137 cruciform-shaped control rods. The control material shall be boron carbide powder (3 C)3 compacted to approximately 70% theoretical density, except for the Hybrid I control rods which contain approximately 15% hafnium.

C. Subject to prior written approval from the NRC, Lead Test Assembly (LTA) control blades and fuel assemblies of different design than described above may be installed in the reactor in conjunction with vendor test programs.

5.3 Reactor Vessel The reactor vessel shall be as described in Section IV-20 of the SAR. The applicable design shall be as described in this section of the SAR.

5.4 Containment A. The principal design parameters for the primary containment shall be as ,

given in Table V-2-1 of the SAR. The applicable design shall be as des- l cribed in Section XII-2,3 of the SAR.

B. The secondary containment shall be as described in Section V-3.0 of the SAR.

C. Penetrations to the primary containment and piping passing through such 8712210390 871214' PDR ADOCK 05000298 '

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