ML16257A149

Revision 309 to Final Safety Analysis Report, Chapter 15, Accident Analyses, Appendix 15D

ML16257A149
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Site:	Waterford
Issue date:	08/25/2016
From:	Entergy Operations
To:	Office of Nuclear Reactor Regulation
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15D-i Revision 14 (12/05)

APPENDIX 15D SUPPLEMENTAL CYCLE SPECIFIC EVENT ANALYSES(DRN 05-543, R14)This appendix is deleted. Cycle specific information has been replaced by the 3716 MWt Extended Power Uprate generated analysis and documented in appropriate FSAR Chapter 15 Sections. (DRN 05-543, R14)

WSES-FSAR-UNIT-315D-iiRevision 7 (10/94)APPENDIX 15DSUPPLEMENTAL CYCLE SPECIFIC EVENT ANALYSESTABLE OF CONTENTSSectionTitle Page15D.1LOSS OF CONDENSER VACUUM (CYCLE 2)(DELETED)15D-115D.

1.1INTRODUCTION

(DELETED)15D-1 15D.1.2RESULTS(DELETED)15D-1 15D.2FEEDWATER SYSTEM PIPE BREAK (CYCLE 2)15D-215D.

2.1INTRODUCTION

15D-215D.2.2RESULTS15D-2 WSES-FSAR-UNIT-315D-iiiRevision 7 (10/94)APPENDIX 15DSUPPLEMENTAL CYCLE SPECIFIC EVENT ANALYSESLIST OF TABLESTableTitle15D.1-1Assumptions for the Loss of(DELETED)Condenser Vacuum Analysis (Cycle 2)15D.1-2Sequence of Events for the Loss(DELETED)of Condenser Vacuum (Cycle 2)15D.2-1Assumptions for the Feedwater SystemPipe Break (Cycle 2)15D.2-2Sequence of Events for the FeedwaterSystem Pipe Break (Cycle 2)

WSES-FSAR-UNIT-315D-ivRevision 7 (10/94)SUPPLEMENTAL CYCLE SPECIFIC EVENT ANALYSESLIST OF FIGURESFigureTitle15D.1-1Loss of Condenser Vacuum - Core Power vs Time(DELETED)15D.1-2Loss of Condenser Vacuum - Core Heat Flux vs Time(DELETED)15D.1-3Loss of Condenser Vacuum - Reactor Coolant System Temperatures vs Time(DELETED)15D.1-4Loss of Condenser Vacuum - Reactor Coolant System Pressure vs Time(DELETED)15D.1-5Loss of Condenser Vacuum - Pressurizer(DELETED)Pressure vs Time15D.1-6Loss of Condenser Vacuum - Pressurizer Water Volume vs Time(DELETED)15D.1-7Loss of Condenser Vacuum - Steam Generator Pressure vs Time(DELETED)15D.2-1Feedwater System Pipe Break - Core Power vs Time15D.2-2Feedwater System Pipe Break - Core Heat Flux vs Time 15D.2-3Feedwater System Pipe Break - Reactor Coolant System Temperatures vs Time 15D.2-4Feedwater System Pipe Break - Primary System Pressures vs Time 15D.2-5Feedwater System Pipe Break - Pressurizer Water Volume vs Time15D.2-6Feedwater System Pipe Break - Steam Generator Pressure vs Time15D.2-7Feedwater System Pipe Break - Steam Generator Liquid Mass vs Time WSES-FSAR-UNIT-315D-1Revision 7 (10/94)15D.1LOSS OF CONDENSER VACUM (CYCLE 2)SECTION 15D.1 DELETED WSES-FSAR-UNIT-3 15D-215D.2FEEDWATER SYSTEM PIPE BREAK (CYCLE 2)15D.

2.1INTRODUCTION

The feedwater line break (FWLB) was reanalyzed for Cycle 2 to verify that the peak RCS pressure waslower (less limiting) than the peak RCS pressure for Cycle 1. Important assumptions used in this analysis are given in Table 15D.2-1.15D.2.2RESULTSThe maximum RCS pressure calculated for this event with Cycle 2 data is 2810 psia. This is less than thepressure calculated for Cycle 1 (2832 psia) and demonstrates that the Cycle 1 FWLB analysis bounds Cycle 2. The sequence of events is given in Table 15D.2-2. The dynamic behavior of important parameters is shown in Figures 15D.2-1 through 15D.2-7. The long term response to a FWLB is not cycle dependent and is similar to that described in Subsection 15.2 WSES-FSAR-UNIT-3Table 15D.1-1 has been deleted.Revision 7 (10/94)

WSES-FSAR-UNIT-3Table 15D.1-2 has been deleted.Revision 7 (10/94)

WSES-FSAR-UNIT-3 TABLE 15D.2-1 Revision 14 (12/05) (DRN 05-543, R14)

TABLE INTENTIONALLY DELETED. (DRN 05-543, R14)

WSES-FSAR-UNIT-3 TABLE 15D.2-2 Revision 14 (12/05) (DRN 05-543, R14)

TABLE INTENTIONALLY DELETED. (DRN 05-543, R14)