ML20086K304
| ML20086K304 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/05/1991 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20086K307 | List: |
| References | |
| NUDOCS 9112130043 | |
| Download: ML20086K304 (1) | |
Text
.,.
... e (5) CECO, pursuant to the Pt and 10 CFR Parts 30, 40, and 70, to possess, but not seperate, such byproduct special nuclear materials as may be paduced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act ar.d to the rules, regulations and orders of the C nission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authcrized to operate the facility at steady state reactor core power levels not in excess of 2527 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 114, are hereby incorperated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Operation in the coastdown mode ir permitted to 40% power.
(4) The valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation.
D.
The facility has been granted _certain exemptions from the require-ments of Section III.G of Appendix R to 10 CFR Part 50, " Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979." This section relates to fire protection features for ensuring the systems and associated circuits used to achieve and maintain safe shutdown are free of fire damage. These exemptions were granted and sent to the licensee in letters dated February 2, 1983, September 28, 1987, July 6, 1989, and August 15, 1989.
In addition, the facility has been granted certain exemptions from Sections II and III of Appendix J to 10 CFR Part 50, " Primary Reactor t.antainment Leakage Testing for Water-Cooled Power Reactors." This section contains leakage test requirements, schedules and acceptance criteria for tests of the leak-tight integrity of the primary reactor containment and systems and components which penetrate the containment. These exemptions were granted and sent to the licensee in a letter dated June 25, 1982.
Corrected by letter of 12/05/91 9112130043 911205 PDR ADOCK 05000237 f
P PDR
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