ML16257A149
| ML16257A149 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/25/2016 |
| From: | Entergy Operations |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16256A115 | List:
|
| References | |
| W3F1-2016-0053 | |
| Download: ML16257A149 (10) | |
Text
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 Cycle specific information has been replaced by the 3716 MWt Extended Power Uprate generated analysis and documented in appropriate FSAR Chapter 15 Sections.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-3 15D-ii Revision 7 (10/94)
APPENDIX 15D SUPPLEMENTAL CYCLE SPECIFIC EVENT ANALYSES TABLE OF CONTENTS Section Title Page
15D.1 LOSS OF CONDENSER VACUUM (CYCLE 2)
(DELETED) 15D-1 15D.
1.1 INTRODUCTION
(DELETED) 15D-1 15D.1.2 RESULTS (DELETED) 15D-1 15D.2 FEEDWATER SYSTEM PIPE BREAK (CYCLE 2) 15D-2 15D.
2.1 INTRODUCTION
WSES-FSAR-UNIT-3 15D-iii Revision 7 (10/94)
APPENDIX 15D SUPPLEMENTAL CYCLE SPECIFIC EVENT ANALYSES LIST OF TABLES Table Title
15D.1-1 Assumptions for the Loss of (DELETED)
Condenser Vacuum Analysis (Cycle 2)
15D.1-2 Sequence of Events for the Loss (DELETED) of Condenser Vacuum (Cycle 2)
15D.2-1 Assumptions for the Feedwater System Pipe Break (Cycle 2) 15D.2-2 Sequence of Events for the Feedwater System Pipe Break (Cycle 2)
WSES-FSAR-UNIT-3 15D-iv Revision 7 (10/94)
SUPPLEMENTAL CYCLE SPECIFIC EVENT ANALYSES LIST OF FIGURES Figure Title
15D.1-1 Loss of Condenser Vacuum - Core Power vs Time (DELETED)
15D.1-2 Loss of Condenser Vacuum - Core Heat Flux vs Time (DELETED)
15D.1-3 Loss of Condenser Vacuum - Reactor Coolant System Temperatures vs Time (DELETED)
15D.1-4 Loss of Condenser Vacuum - Reactor Coolant System Pressure vs Time (DELETED)
15D.1-5 Loss of Condenser Vacuum - Pressurizer (DELETED)
Pressure vs Time
15D.1-6 Loss of Condenser Vacuum - Pressurizer Water Volume vs Time (DELETED)
15D.1-7 Loss of Condenser Vacuum - Steam Generator Pressure vs Time (DELETED)
15D.2-1 Feedwater System Pipe Break - Core Power vs Time 15D.2-2 Feedwater System Pipe Break - Core Heat Flux vs Time 15D.2-3 Feedwater System Pipe Break - Reactor Coolant System Temperatures vs Time 15D.2-4 Feedwater System Pipe Break - Primary System Pressures vs Time 15D.2-5 Feedwater System Pipe Break - Pressurizer Water Volume vs Time 15D.2-6 Feedwater System Pipe Break - Steam Generator Pressure vs Time 15D.2-7 Feedwater System Pipe Break - Steam Generator Liquid Mass vs Time
WSES-FSAR-UNIT-3 15D-1 Revision 7 (10/94)
15D.1 LOSS OF CONDENSER VACUM (CYCLE 2)
SECTION 15D.1 DELETED
WSES-FSAR-UNIT-3 15D-2 15D.2 FEEDWATER SYSTEM PIPE BREAK (CYCLE 2) 15D.
2.1 INTRODUCTION
The feedwater line break (FWLB) was reanalyzed for Cycle 2 to verify that the peak RCS pressure was lower (less limiting) than the peak RCS pressure for Cycle 1. Important assumptions used in this analysis are given in Table 15D.2-1.
15D.2.2 RESULTS The maximum RCS pressure calculated for this event with Cycle 2 data is 2810 psia. This is less than the pressure 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-3 Table 15D.1-1 has been deleted.
Revision 7 (10/94)
WSES-FSAR-UNIT-3 Table 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)