ML16340A109

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7 to Updated Final Safety Analysis Report, Chapter 4, Table 4.3-1, Summary of Estimated Primary Plus Secondary Stress Intensity for Components of the Reactor Vessel (Unit 1)
ML16340A109
Person / Time
Site: Cook  American Electric Power icon.png
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: ML16340A109 (1)


Text

IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:

21 Table:

4.3-1 Page:

1 of 1

SUMMARY

OF ESTIMATED PRIMARY PLUS SECONDARY STRESS INTENSITY FOR COMPONENTS OF THE REACTOR VESSEL (UNIT 1)1 Stress Intensity (psi)

Item Original Rerated Allowable Stress (psi)

(at Operating Temperature)

Control Rod Housing 55,300 66,050 69,900 Head Flange 50,400 54,380 80,100 Vessel Flange 45,350 65,850 80,100 Primary Nozzles Inlet 48,400 49,860 80,000 Primary Nozzles Outlet 54,060 59,580 80,000 Stud Bolts 95,870 83,320 104,400 Core Support Pad 40,800 69,700 69,900 Bottom Head to Shell 34,100 34,530 80,000 Bottom Instrumentation 53,400 51,490 69,900 Vessel Wall Transition 37,900 33,570 80,000 1 The vessel stress intensities for Unit 2 are available in the Unit 2 Stress Report.