ML16336A405

Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 2, Table 2.9-1, Conditions/Effects Considered

ML16336A405
Person / Time
Site:	Cook
Issue date:	10/24/2016
From:	Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML16336A263	List: AEP-NRC-2016-42, Fire Protection Program Change Summary ML16336A225 ML16336A228 ML16336A238 ML16336A291 ML16336A292 ML16336A294 ML16336A295 ML16336A297 ML16336A298 ML16336A299 ML16336A300 ML16336A301 ML16336A302 ML16336A303 ML16336A304 ML16336A305 ML16336A306 ML16336A308 ML16336A309 ML16336A310 ML16336A311 ML16336A312 ML16336A313 ML16336A314 ML16336A315 ML16336A316 ML16336A317 ML16336A318 ML16336A319 ML16336A320 ML16336A322 ML16336A323 ML16336A324 ML16336A325 ML16336A327 ML16336A328 ML16336A329 ML16336A330 ML16336A332 ML16336A333 ML16336A334 ML16336A336 ML16336A337 ML16336A338 ML16336A339 ML16336A340 ML16336A341 ML16336A342 ML16336A345 ... further results
References
AEP-NRC-2016-42
Download: ML16336A405 (1)

Text

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:21Table:2.9-1 Page:1 of 1CONDITIONS/EFFECTS CONSIDEREDCONDITIONS 1EFFECTS CONSIDERED1NORMALDeadweight, Thermal, Pressure(Pressure is considered for vessel and pipe stress only)2UPSETSame as 1, OBE3EMERGENCYSame as 1, DBE(Thermal is considered for supports loads only)4FAULTEDSame as 1, Postulated Pipe Rupture(Thermal is considered for supports loads only)5FAULTED (Including DBE) 2Same as 3, Postulated Pipe RuptureNOTESThe Operating Load Combination categories are defined as follows:1NORMAL ConditionAny condition in the course of system startup, operation in the design powerrange and system shutdown, in the absence of Upset, Emergency or FaultedConditions.2UPSET ConditionAny deviations from Normal Conditions anticipated to occur often enough thatdesign should include a capability to withstand the conditions without operational impairment. The Upset Condition includes those transients caused by a fault in a system component requiring its isolation from the system, transients due to a loss of load or power and any system upset not resulting in aforced outage. The Upset Conditions include - the effect of the specifiedearthquake for which the system must remain operational or must regain its operational status.3EMERGENCY ConditionAny deviations from normal conditions which require shutdown for correctionof the conditions or repair of damage in the system. The conditions have a low probability of occurrence but are included to provide assurance that no grossloss or structural integrity will result as a concomitant effect of any damagedeveloped in the system. The total number of postulated occurrences for such events shall not exceed twenty-five (25). Among the Emergency Conditions may be a specified earthquake for which safe shutdown is required.4FAULTED ConditionThose combinations of conditions associated with extremely low probabilitypostulated events whose consequences are such that the integrity and operability of the nuclear energy system may be impaired to the extent whereconsiderations of public health and safety are involved. Such considerationsrequire compliance with safety criteria as may be specified by jurisdictional authorities.

1 Definition of Terms based on the Summer 1968 Addenda to the ASME Boiler and Pressure Vessel Code,Section III.2 The Westinghouse Nuclear Steam Supply System Equipment (piping and equipment) was designed for the faulted(including Design Basis Earthquake) condition by using the methodology presented in WCAP 5890 Rev. 1, whichincludes combining LOCA (Reactor Coolant Pipe Break) and Design Basis Earthquake (DBE) via Square RootSum of Squares (SRSS).