ML16343A982: Difference between revisions

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| number = ML16343A982
| number = ML16343A982
| issue date = 10/24/2016
| issue date = 10/24/2016
| title = Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 14, Table 14.1.10B-3, Time Sequence of Events (Full V-5 Core), Page 1 of 1
| title = 7 to Updated Final Safety Analysis Report, Chapter 14, Table 14.1.10B-3, Time Sequence of Events (Full V-5 Core), Page 1 of 1
| author name =  
| author name =  
| author affiliation = Indiana Michigan Power Co
| author affiliation = Indiana Michigan Power Co
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=Text=
=Text=
{{#Wiki_filter:I I N N D D I I A A N N A A  A A N N D D  M M I I C C H H I I G G A A N N  P P O O W W E E R R D D.. C C.. C C O O O O K K  N N U U C C L L E E A A R R  P P L L A A N N T T U U P P D D A A T T E E D D  F F I I N N A A L L  S S A A F F E E T T Y Y  A A N N A A L L Y Y S S I I S S R R E E P P O O R R T TRevision:17Table:14.1.10B-3 Page:1 of 1UNIT 2TIME SEQUENCE OF EVENTS(FULL V-5 CORE)AccidentEventTime (sec)Feedwater System Malfunctions:Excessive feedwater flow at fullpower to all four steam generators (Manual Rod Control)All four main feedwater control valves fail fully
{{#Wiki_filter:IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:
 
17 Table:14.1.10B-3 Page:
open 0.0Hi-hi steam generator water level signalgenerated 31.5Turbine trip occurs due to hi-hi steam generatorwater level 34.0Minimum DNBR occurs34.5Reactor trip occurs due to turbine trip36.0Feedwater isolation achieved 42.5}}
1 of 1 UNIT 2 TIME SEQUENCE OF EVENTS (FULL V-5 CORE)
Accident Event Time (sec)
Feedwater System Malfunctions:
Excessive feedwater flow at full power to all four steam generators (Manual Rod Control)
All four main feedwater control valves fail fully open 0.0 Hi-hi steam generator water level signal generated 31.5 Turbine trip occurs due to hi-hi steam generator water level 34.0 Minimum DNBR occurs 34.5 Reactor trip occurs due to turbine trip 36.0 Feedwater isolation achieved 42.5}}

Latest revision as of 16:22, 9 January 2025

7 to Updated Final Safety Analysis Report, Chapter 14, Table 14.1.10B-3, Time Sequence of Events (Full V-5 Core), Page 1 of 1
ML16343A982
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: ML16343A982 (1)
v • d • e


Text

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

17 Table:14.1.10B-3 Page:

1 of 1 UNIT 2 TIME SEQUENCE OF EVENTS (FULL V-5 CORE)

Accident Event Time (sec)

Feedwater System Malfunctions:

Excessive feedwater flow at full power to all four steam generators (Manual Rod Control)

All four main feedwater control valves fail fully open 0.0 Hi-hi steam generator water level signal generated 31.5 Turbine trip occurs due to hi-hi steam generator water level 34.0 Minimum DNBR occurs 34.5 Reactor trip occurs due to turbine trip 36.0 Feedwater isolation achieved 42.5

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