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Extra resources for System 80+ Standard [nucl. powerplnt] Design - Vol 18

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IH Level Control I OH iH i IH Rupture I IH Signal System Advisor Bypass System Bypass Valve Generator Governor Direct Current H Valve Amendment xxvi August H 31, 1990 ...... 1 PURPOSE One of the requirements of 10 CFR Part 52 (1) is that an application for design certification must contain a design specific Probabilistic Risk Assessment (PRA). This Appendix documents the results of the probabilistic risk assessment for the System 80+ Standard Design. The System 80+ Standard Design PRA has three primary purposes.

The transient analyses in Chapter 15 of CESSAR-F (7) provided the basic information on plant responses to accidents and transients. This information was supplemented with discussions with safety analysts and licensed operators and with information contained in the report, "Depr_@urization and Decay Heat Removal - Response to NRC System Questions? 80 plants' 9_UJl0@n d its associated ' -. Operator actions were eval_$d and established Guideline _ " and discussions at the Arizona Nuclear Power and operability definite/ks Technical Specifications_ needed, from the Palo Maintenance information, industry practices.

Operator actions were eval_$d and established Guideline _ " and discussions at the Arizona Nuclear Power and operability definite/ks Technical Specifications_ needed, from the Palo Maintenance information, industry practices. supplements pertinent to during plant transients based on C-E's Emergency Procedure with licensed operators at C-E and Project. Surveillance requirements were derived from C-E's Standard and, Verde where where more specific detai_l_S_J; Technical Specifications" . needed, was based on common • ..

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