ML16343A197

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7 to Updated Final Safety Analysis Report, Chapter 14, Table 14.1-7 - Sgtp Program Input Assumptions for Reactor Coolant System Pressure Drop
ML16343A197
Person / Time
Site: Cook  
Issue date: 10/24/2016
From:
Indiana Michigan Power Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML16336A263 List: ... further results
References
AEP-NRC-2016-42
Download: ML16343A197 (1)


Text

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16.1 Table:

14.1-7 Page:

1 of 1 DONALD C. COOK NUCLEAR PLANT UNIT 1 SGTP PROGRAM INPUT ASSUMPTIONS FOR REACTOR COOLANT SYSTEM PRESSURE DROP(1)

Initial Conditions Input Assumptions 0% SGTP Pressure Drop, psi 30% SGTP Pressure Drop, psi Reactor Vessel, including nozzles (psi) 47.21 44.26 Loop Piping (psi) 5.14 4.55 Steam Generator (psi) 43.23 53.58 Total (psi) 95.58(1) 102.39(1)