ML21209A141

From kanterella
Revision as of 19:07, 18 January 2022 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
1 to Updated Final Safety Analysis Report, Chapter 8, Electric Power
ML21209A141
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 04/30/2021
From:
Dominion Energy South Carolina
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21209A581 List: ... further results
References
21-167
Download: ML21209A141 (251)


Text

TABLE OF CONTENTS Section Title Page 8.0 ELECTRIC POWER 8.1-1

8.1 INTRODUCTION

8.1-1 8.

1.1 REFERENCES

8.1-2 8.2 OFFSITE POWER SYSTEM 8.2-1 8.

2.1 DESCRIPTION

8.2-1 8.2.1.1 Unit Auxiliary, Emergency Auxiliary, and Safeguard Transformers 8.2-3 8.2.1.2 Transmission System 8.2-4 8.2.2 ANALYSIS 8.2-8 8.2.2.1 Introduction 8.2-8 8.2.2.2 Stability Study Results 8.2-8 8.

2.3 REFERENCES

8.2-11 8.3 ONSITE POWER SYSTEMS 8.3-1 8.3.1 A-C POWER SYSTEMS 8.3-1 8.3.1.1 Description 8.3-1 8.3.1.2 Analysis 8.3-19 8.3.1.3 Conformance with Appropriate Quality Assurance Standards 8.3-20 8.3.1.4 Independence of Redundant Systems 8.3-21 8.3.1.5 Physical Identification of Safety-Related Equipment 8.3-25 8.3.1.6 Electrical Penetration Areas 8.3-26 8.3.2 D-C POWER SYSTEMS 8.3-27 8.3.2.1 Description 8.3-27 8.3.2.2 Analysis 8.3-36 8.3.2.3 Physical Identification of Safety-Related Equipment 8.3-37 8.3.3 FIRE PROTECTION FOR CABLE SYSTEMS 8.3-38 8.3.3.1 Cable Derating, Cable Tray Fill, and Cable Construction 8.3-38 8.3.3.2 Fire Detection and Protection Devices 8.3-42 8.3.3.3 Fire Barriers and Separation Between Redundant Cable Trays 8.3-42 8.3.3.4 Fire Stops 8.3-43 8.3.4 SAFETY-RELATED CABLE 8.3-43 8.

3.5 REFERENCES

8.3-43 8.4 STATION BLACKOUT 8.4-1 8.4.1 STATION BLACKOUT DURATION 8.4-1 8.4.2 COPING METHOD 8.4-2 8.4.2.1 Class 1E Battery Capacity 8.4-2 RN 8.4.2.2 Condensate Inventory For Decay Heat Removal 8.4-2 99-181 8.4.2.3 Compressed Air 8.4-2 8.4.2.4 Effects of Loss of Ventilation 8.4-2 8.4.2.5 Containment Isolation 8.4-3 8.4.2.6 Reactor Coolant Inventory 8.4-3 8.

4.3 REFERENCES

8.4-3 8-i Reset April 2021

TABLE OF CONTENTS (Continued)

Section Title Page APPENDIX 8A ADDITIONAL CABLE AND TRAY DESIGN CONSIDERATIONS 8A-1 APPENDIX 8B CABLE RACEWAY FIRE DESIGN 8B-1 APPENDIX 8C

SUMMARY

OF ANALYSIS OF SEPARATION BETWEEN TRAY FOR 8C-1 NON-CLASS 1E CIRCUITS AND TRAY FOR CLASS 1E CIRCUITS APPENDIX 8D ANALYSIS OF THE ACCEPTABLE VOLTAGE RANGE TO BE APPLIED 8D-1 TO THE ESF SYSTEM APPENDIX 8E ANALYSIS OF THE VOLTAGE DROPS ON THE ESF SYSTEM WHEN 8E-1 STARTING A 6900 OR 460 VOLT MOTOR WITH THE DIESEL GENERATOR AS THE SOURCE APPENDIX 8F STARTING SEQUENCE OF ESF EQUIPMENT FOLLOWING AN 8F-1 ACCIDENT COINCIDENT WITH A DEGRADED VOLTAGE CONDITION APPENDIX 8G ELECTRICAL CONTAINMENT PENETRATION CONDUCTOR 8G-1 OVERCURRENT PROTECTION DEVICES 8-ii Reset April 2021

LIST OF TABLES Table Title Page No.

8.1-1 Transmission System Ties to Other Utilities 8.1-3 8.1-2 Implementation of IEEE Standards 8.1-4 8.1-3 List of Applicable Criteria 8.1-6 8.2-1 Distances of Lines to First Major Substation 8.2-12 8.2-2 Allowable Variation in Offsite System Voltage 8.2-13 8.3-1 Major Electrical Equipment 8.3-45 8.3-2 Symmetrical Interrupting Capacity for 480 Volt Unit Substation 8.3-46 Cubicles 8.3-3 Connected Automatic and Manual Loading and Unloading of the 8.3-47 Diesel Generator 8.3-3a Diesel Generator Protective Devices 8.3-79 8.3-3b Engineered Safety Features Bus Indicators 8.3-80 8.3-4 Identification of Safety-Related Cable Trays and Cables 8.3-81 8.3-5 Sequence of Operation Following a Loss or Degraded Voltage 8.3-82 Condition 8D-1 Intentionally Deleted per RN 99-087. (Calculated Minimum Voltage 8D-4 RN Levels on Motors and Buses provided in referenced Calculation 99-087 DC-820-001, Table 7.3.3) 8D-2 Calculated Motor Voltages for Maximum Offsite Voltage 8D-5 8D-3 (Deleted per RN 99-007) 8D-6 RN 99-007 8E-1 Calculated Voltage Level of ESF System Buses and Motor Terminals 8E-4 with a Diesel Generator as a Source and Starting the 6900 Volt Charging/Safety Injection Pump Motor 8E-2 Calculated Voltage Level of ESF System Buses and Motor Terminals 8E-5 with a Diesel Generator as a Source and Starting the 460 Volt Service Water Booster Pump Motor 8F-1 Degraded Grid Voltage Coincident with LOCA 8F-2 8F-2 Degraded Grid Voltage Coincident with MSLB 8F-4 8-iii Reset April 2021

LIST OF FIGURES Figure Title 8.1-1 Transmission System Map 8.2-1 Site Transmission Map 8.2-2 230 kV Substation Layout 8.2-2a Electrical - General Arrangement 230 kV Substation Arrangement 8.2-2b Electrical - 230 kV Substation Arrangement Plan - Bus Sections 2 and 3 8.2-2c Electrical - 230 kV Substation Arrangement Plan - Bus Sections 1 and 3 8.2-2d Electrical - Overhead Line Arrangement - 230 kV and 115 kV Outdoor Transformer Area 8.2-3 Electrical - One Line and Relay Diagram - Balance of Plant Power System 8.2-4 Electrical - One Line and Relay Diagram - Engineered Safety Features Power System 8.2-5 Deleted 8.2-6 Deleted 8.2-7 Deleted 8.3-0 Outdoor Cable Bus Layout and Sections Emergency Auxiliary Transformer Area 8.3-0a Outdoor Cable Bus Layout and Sections Unit Auxiliary Transformer Area 8.3-0b Outdoor Cable Bus Layout and Sections Safeguard Transformer Area 8.3-0b.1 Outdoor Cable Bus Layout and Sections Safeguard Transformer Area 8.3-0c Indoor Cable Bus Layout and Sections Plan View, Elevation 436'-0", Col. A to Col. D 8.3-0d Indoor Cable Bus Layout and Sections Plan View, Elevation 436'-0", Col. d-f.1 and 8-11.1 8.3-0e Indoor Cable Bus Layout and Sections Plan View, Elevation 412'-0", Col. 4 Through 8 and Col. A to B 8.3-0f Indoor Cable Bus Layout and Sections Plan View, Elevation 412'-0", Col. 8 to 11.1 and Col. A to C 8.3-0g Indoor Cable Bus Layout and Sections Plan View, Elevation 412'-0", Col. 8 to 11.1 and Col. C-f-1 8.3-0h Diesel Generator Starting Control Logic Diagram 8.3-0i Diesel Generator Shutdown Control Logic Diagram 8.3-0j Diesel Generator Breaker Logic Diagram 8.3-0k 7.2 kV Bus 1DA Normal Incoming Breaker Logic Diagram 8.3-0l 7.2 kV Bus 1DA Emergency Incoming Breaker Logic Diagram 8.3-0m Main Control Board Annunciator Station 8.3-0n Diesel Generator Local Annunciator Stations 8.3-0o Electrical - 7.2 kV Bus 1DA-1DB Undervoltage Relaying Logic Diagram 8-iv Reset April 2021

LIST OF FIGURES (Continued)

Figure Title 8.3-1 Electrical One Line and Relay Diagram - Vital A-C System 8.3-2 Electrical One Line and Relay Diagram - Engineered Safety Features Vital A-C System 8.3-2a Electrical - Duct Runs for Diesel Generator Circuits - Main Plant Area - West End 8.3-2aa Electric One Line and Relay Diagram - Vital D-C System 8.3-2ab One Line and Relay Diagram Engineered Safety Features Vital DC System 8.3-2b Electrical - Duct Runs for Diesel Generator Circuits - Main Plant Area - East End 8.3-2c Electrical - Duct Runs for Diesel Generator Circuits - Outdoor Area - East End 8.3-2d Electrical - Duct Runs for Diesel Generator Circuits to Service Water Intake Structure 8.3-2e Miscellaneous Outdoor Structures - Yard Duct Run - Turbine Building to Service Water Intake Structure 8.3-2f Miscellaneous Outdoor Structures - Yard Duct Run -Electrical - Manhole MH-2 8.3-2g Electrical Duct Banks - Control Complex, Intermediate Building and Turbine Building 8.3-3 Containment Penetration Separation 8.3-4 Electrical One Line and Relay Diagram - Balance of Plant Vital AC-DC System 8.3-4a Balance of Plant - Vital AC and DC System 8.3-4b Balance of Plant - Vital AC and DC System 8.3-5 230 kV Substation D-C Station Service Diagram 8.3-5a 230 kV Substation Unit 1 Relay House DC One Line Diagram and Panel Schedules RN 12-001 8.3-6 125 Volt D-C Main Distribution Panel 8.3-7 125 Volt D-C Main Distribution Panel 8.3-8 Electrical Reactor, Turbine and Generator Trip Diagram 8B-1 Electrical - Fire Barrier Details 8B-2 Electrical - Fire Barrier Details 8B-3 Electrical - Fire Barrier Details 8B-4 Electrical - Fire Barrier Details 8B-5 Electrical - Fire Barrier Details 8B-6 Electrical - Fire Barrier Details 8B-7 Electrical - Fire Barrier Details 8B-8 Electrical - Fire Barrier Details 8B-9 Electrical - Fire Barrier Details 8B-10 Electrical - Fire Barrier Details 8-v Reset April 2021

LIST OF FIGURES (Continued)

Figure Title 8B-11 Electrical - Fire Barrier Details 8B-12 Electrical - Fire Barrier Details 8C-1 Case 041-C 8C-2 Case 102-A 8C-3 Case 073-A 8G-1 Containment Penetration Conductor Overcurrent Protection Devices 8G-2 Containment Penetration Conductor Overcurrent Protection Devices 8G-3 Containment Penetration Conductor Overcurrent Protection Devices 8G-4 Containment Penetration Conductor Overcurrent Protection Devices 8G-5 Containment Penetration Conductor Overcurrent Protection Devices 8G-6 Containment Penetration Conductor Overcurrent Protection Devices 8G-7 Containment Penetration Conductor Overcurrent Protection Devices 8G-8 Containment Penetration Conductor Overcurrent Protection Devices 8G-9 Containment Penetration Conductor Overcurrent Protection Devices 8G-10 Containment Penetration Conductor Overcurrent Protection Devices 8-vi Reset April 2021

LIST OF EFFECTIVE PAGES (LEP)

The following list delineates pages to Chapter 8 of the Virgil C. Summer Nuclear Station Final Safety Analysis Report which are current through October 2020. The latest changes to pages and figures are indicated below by Revision Number (RN) in the Amendment column along with the Revision Number and date for each page and figure included in the Final Safety Analysis Report.

Page/Fig.No. Amend. No. Date Page/Fig.No. Amend. No. Date Page 8-i Reset April 2021 Page 8.2-7 RN12-026 April 2015 RN12-028 April 2015 8-ii Reset April 2021 RN14-019 April 2015 8-iii Reset April 2021 8-iv Reset April 2021 8.2-8 RN12-039 April 2015 8-v Reset April 2021 RN14-019 April 2015 8-vi Reset April 2021 RN16-028 April 2018 8-vii Reset April 2021 8.2-9 RN10-030 November 2011 RN16-028 April 2018 8-viii Reset April 2021 8.2-10 RN10-030 November 2011 8-ix Reset April 2021 RN16-028 April 2018 8-x Reset April 2021 8.2-11 RN10-030 November 2011 8-xi Reset April 2021 RN16-028 April 2018 Page 8.1-1 RN07-001 April 2007 8.2-12 RN12-017 April 2015 8.1-2 99-01 June 1999 RN12-026 April 2015 RN12-028 April 2015 8.1-3 RN12-026 April 2015 RN12-039 April 2015 RN12-028 April 2015 RN14-019 April 2015 RN16-010 March 2019 RN16-010 March 2019 8.1-4 RN99-002 February 2000 8.2-13 RN13-008 September 2014 8.1-5 RN99-002 February 2000 Fig. 8.2-1 RN12-029 September 2014 8.1-6 RN99-002 February 2000 RN16-010 March 2019 8.1-7 RN99-002 February 2000 8.2-2 RN11-036 April 2015 RN12-017 April 2015 8.1-8 00-01 December 2000 RN12-026 April 2015 8.1-9 00-01 December 2000 RN12-028 April 2015 RN12-039 April 2015 Fig. 8.1-1 98-01 April 1998 RN13-003 April 2015 Page 8.2-1 RN06-042 April 2007 RN13-026 April 2015 RN14-011 April 2015 8.2-2 RN13-015 September 2014 RN14-013 April 2015 RN12-001 February 2015 RN14-019 April 2015 RN14-013 April 2015 RN15-015 May 2016 RN14-019 April 2015 RN16-005 May 2016 8.2-3 RN06-042 April 2007 RN14-031 October 2016 RN13-012 April 2018 8.2-4 RN12-026 April 2015 RN16-010 March 2019 RN12-028 April 2015 RN19-019 October 2019 RN12-039 April 2015 RN14-019 April 2015 8.2-2a RN13-015 September 2014 RN16-010 March 2019 RN11-036 April 2015 8.2-5 RN13-015 September 2014 RN12-017 April 2015 RN12-026 April 2015 8.2-6 RN12-026 April 2015 RN12-028 April 2015 RN12-039 April 2015 RN12-039 April 2015 RN13-003 April 2015 RN13-026 April 2015 8-vii Reset April 2021

LIST OF EFFECTIVE PAGES (LEP)

Page/Fig.No. Amend. No. Date Page/Fig.No. Amend. No. Date RN14-011 April 2015 8.3-8 UCR-2021-005 April 2021 RN14-013 April 2015 00-01 December 2000 RN14-019 April 2015 8.3-9 UCR-2021-005 April 2021 RN15-015 May 2016 RN98-061 January 2000 RN14-031 October 2016 RN13-012 April 2018 8.3-10 UCR-2021-005 April 2021 RN16-010 March 2019 00-01 December 2000 8.3-11 UCR-2021-005 April 2021 Fig. 8.2-2b RN11-036 April 2015 RN01-113 December 2001 RN12-017 April 2015 8.3-12 00-01 December 2000 RN12-026 April 2015 RN12-028 April 2015 8.3-13 00-01 December 2000 RN12-039 April 2015 RN13-003 April 2015 8.3-14 RN01-113 December 2001 RN13-026 April 2015 8.3-15 00-01 December 2000 RN14-011 April 2015 RN14-013 April 2015 8.3-16 00-01 December 2000 RN14-019 April 2015 8.3-17 00-01 December 2000 RN13-012 April 2018 RN16-010 March 2019 8.3-18 00-01 December 2000 8.2-2c RN12-016 April 2015 8.3-19 00-01 December 2000 RN12-026 April 2015 8.3-20 00-01 December 2000 RN12-028 April 2015 UCR-2020-022 October 2020 RN13-003 April 2015 RN13-026 April 2015 8.3-21 00-01 December 2000 RN14-011 April 2015 8.3-22 RN03-018 June 2003 RN14-019 April 2015 RN14-031 October 2016 8.3-23 00-01 December 2000 RN13-012 April 2018 UCR-2020-025 October 2020 RN16-010 March 2019 8.3-24 00-01 December 2000 8.2-2d RN09-014 April 2010 8.3-25 00-01 December 2000 8.2-3 RN13-002 April 2013 Page 8.3-26 RN96-041 September 1996 RN17-010 April 2018 RN19-019 October 2019 8.3-27 RN12-001 February 2015 RN14-013 April 2015 8.2-4 RN12-007 October 2014 8.3-28 RN12-001 February 2015 RN17-013 September 2017 8.3-29 00-01 December 2000 Page 8.3-1 00-01 December 2000 RN18-004 February 2019 8.3-2 00-01 December 2000 8.3-30 00-01 December 2000 8.3-3 RN07-001 April 2007 8.3-31 00-01 December 2000 RN18-019 May 2018 8.3-32 00-01 December 2000 8.3-4 00-01 December 2000 8.3-33 00-01 December 2000 8.3-5 RN98-065 January 2000 8.3-34 00-01 December 2000 RN99-007 November 1999 RN99-087 February 2000 8.3-35 00-01 December 2000 RN18-004 February 2019 8.3-6 00-01 December 2000 8.3-36 00-01 December 2000 8.3-7 00-01 December 2000 8.3-37 00-01 December 2000 8-viii Reset April 2021

LIST OF EFFECTIVE PAGES (LEP)

Page/Fig.No. Amend. No. Date Page/Fig.No. Amend. No. Date 8.3-38 00-01 December 2000 RN17-033 May 2018 RN17-015 October 2017 8.3-64 02-01 May 2002 8.3-39 00-01 December 2000 8.3-65 RN12-006 June 2015 8.3-40 00-01 December 2000 RN17-033 May 2018 8.3-41 00-01 December 2000 8.3-66 RN15-025 January 2016 8.3-42 00-01 December 2000 8.3-67 02-01 May 2002 RN17-033 May 2018 8.3-43 00-01 December 2000 8.3-68 02-01 May 2002 8.3-44 00-01 December 2000 RN17-033 May 2018 RN18-019 May 2018 8.3-69 02-01 May 2002 8.3-45 RN10-018 November 2011 8.3-70 02-01 May 2002 8.3-46 02-01 May 2002 RN17-033 May 2018 8.3-47 02-01 May 2002 8.3-71 02-01 May 2002 8.3-48 RN12-006 June 2015 RN17-033 May 2018 RN17-033 May 2018 8.3-72 RN12-006 June 2015 RN17-022 December 2018 RN17-033 May 2018 8.3-49 RN12-006 June 2015 8.3-73 02-01 May 2002 RN17-033 May 2018 RN17-033 May 2018 RN17-022 December 2018 8.3-74 RN15-025 January 2016 8.3-50 RN15-025 January 2016 8.3-75 02-01 May 2002 8.3-51 RN10-014 November 2011 RN17-033 May 2018 8.3-76 02-01 May 2002 RN17-033 May 2018 8.3-52 RN10-014 November 2011 RN17-033 May 2018 8.3-77 02-01 May 2002 RN17-022 December 2018 RN17-033 May 2018 8.3-53 02-01 May 2002 8.3-78 02-01 May 2002 8.3-54 02-01 May 2002 8.3-79 RN98-027 R1 March 1999 8.3-55 02-01 May 2002 8.3-80 RN99-002 February 2000 RN 19-014 July 2019 8.3-56 RN12-006 June 2015 RN17-033 May 2018 8.3-81 02-01 May 2002 RN17-022 December 2018 8.3-82 02-01 May 2002 8.3-57 02-01 May 2002 Fig. 8.3-0 02-01 May 2002 RN17-033 May 2018 RN17-015 October 2017 RN17-022 December 2018 8.3-0a 02-01 May 2002 8.3-58 RN15-025 January 2016 8.3-0b 00-01 December 2000 8.3-59 RN10-014 November 2011 8.3-0b.1 02-01 May 2002 8.3-60 RN10-014 November 2011 RN17-033 May 2018 8.3-0c RN12-007 October 2014 8.3-61 RN10-014 November 2011 8.3-0d RN12-007 October 2014 RN17-033 May 2018 RN17-015 October 2017 RN17-022 December 2018 8.3-0e 02-01 May 2002 Page 8.3-62 02-01 May 2002 RN17-015 October 2017 8.3-63 02-01 May 2002 8.3-0f 02-01 May 2002 8-ix Reset April 2021

LIST OF EFFECTIVE PAGES (LEP)

Page/Fig.No. Amend. No. Date Page/Fig.No. Amend. No. Date RN17-015 October 2017 RN14-031 October 2016 RN13-012 April 2018 8.3-0g 02-01 May 2002 RN17-015 October 2017 8.3-5a RN12-001 February 2015 RN11-036 April 2015 8.3-0h 02-01 May 2002 RN12-016 April 2015 8.3-0i 02-01 May 2002 RN12-026 April 2015 RN12-028 April 2015 8.3-0j 02-01 May 2002 RN13-026 April 2015 8.3-0k RN12-007 October 2014 RN14-011 April 2015 RN14-019 April 2015 8.3-0l RN12-007 October 2014 RN14-031 October 2016 8.3-0m 00-01 December 2000 RN13-012 April 2018 Fig. 8.3-0n 98-01 April 1998 8.3-6 02-01 May 2002 8.3-0o 02-01 May 2002 8.3-7 98-01 April 1998 8.3-1 RN10-014 November 2011 8.3-8 RN13-030 January 2014 RN17-022 December 2018 Page 8.4-1 00-01 December 2000 8.3-2 02-01 May 2002 8.4-2 00-01 December 2000 8.3-2a RN06-039 February 2014 8.4-3 00-01 December 2000 RN07-026 April 2008 Page 8A-1 00-01 December 2000 8.3-2aa 02-01 May 2002 RN14-039 May 2016 8A-2 00-01 December 2000 RN14-041 February 2019 Page 8A-3 02-01 May 2002 8.3-2ab 02-01 May 2002 8A-4 02-01 May 2002 RN14-039 May 2016 RN14-041 February 2019 8B-1 00-01 December 2000 UCR-2020-025 October 2020 8.3-2b RN07-026 April 2008 8B-2 00-01 December 2000 8.3-2c RN07-026 April 2008 8B-3 00-01 December 2000 8.3-2d RN06-039 February 2014 8B-4 00-01 December 2000 8.3-2e RN07-026 April 2008 Fig. 8B-1 0 August 1984 8.3-2f RN07-026 April 2008 Fig. 8B-2 0 August 1984 8.3-2g 02-01 May 2002 8B-3 0 August 1984 8.3-3 0 August 1984 8B-4 0 August 1984 8.3-4 RN15-016 August 2015 RN14-041 February 2019 8B-5 0 August 1984 8.3-4a RN11-015 November 2011 8B-6 0 August 1984 RN 14-010 June 2019 8B-7 0 August 1984 8.3-4b RN06-011 August 2007 8B-8 0 August 1984 RN18-004 February 2019 8B-9 0 August 1984 8.3-5 RN11-036 April 2015 RN12-016 April 2015 8B-10 0 August 1984 RN12-026 April 2015 8B-11 0 August 1984 RN12-039 April 2015 RN13-026 April 2015 8B-12 0 August 1984 RN14-011 April 2015 RN14-019 April 2015 Page 8C-1 00-01 December 2000 8-x Reset April 2021

LIST OF EFFECTIVE PAGES (LEP)

Page/Fig.No. Amend. No. Date Page/Fig.No. Amend. No. Date 8C-2 02-01 May 2002 8C-38 97-01 August 1997 8C-3 00-01 December 2000 8C-39 97-01 August 1997 8C-4 00-01 December 2000 Fig. 8C-1 0 August 1984 8C-5 00-01 December 2000 8C-2 0 August 1984 8C-6 02-01 May 2002 8C-3 0 August 1984 8C-7 00-01 December 2000 Page 8D-1 RN12-007 October 2014 8C-8 97-01 August 1997 8D-2 RN12-007 October 2014 8C-9 97-01 August 1997 8D-3 RN12-007 October 2014 8C-10 97-01 August 1997 8D-4 00-01 December 2000 8C-11 97-01 August 1997 Page 8E-1 RN12-007 October 2014 8C-12 97-01 August 1997 8E-2 RN12-007 October 2014 8C-13 97-01 August 1997 8E-3 RN12-007 October 2014 8C-14 97-01 August 1997 8E-4 99-01 June 1999 8C-15 97-01 August 1997 8E-5 02-01 May 2002 8C-16 97-01 August 1997 Page 8F-1 98-01 April 1998 8C-17 97-01 August 1997 8F-2 00-01 December 2000 8C-18 97-01 August 1997 8F-3 00-01 December 2000 Page 8C-19 97-01 August 1997 Page 8F-4 00-01 December 2000 8C-20 97-01 August 1997 8F-5 00-01 December 2000 8C-21 97-01 August 1997 Page 8G-1 97-01 August 1997 8C-22 97-01 August 1997 Fig. 8G-1 00-01 December 2000 8C-23 97-01 August 1997 8G-2 00-01 December 2000 RN16-003 February 2018 8C-24 97-01 August 1997 8G-3 02-01 May 2002 8C-25 97-01 August 1997 RN16-011 September 2017 8C-26 97-01 August 1997 8G-4 02-01 May 2002 8C-27 97-01 August 1997 Fig. 8G-5 02-01 May 2002 8C-28 97-01 August 1997 8G-6 RN07-006 February 2013 8C-29 97-01 August 1997 8G-7 RN07-006 February 2013 8C-30 97-01 August 1997 8G-8 RN07-006 February 2013 8C-31 97-01 August 1997 8G-9 00-01 December 2000 8C-32 97-01 August 1997 8G-10 00-01 December 2000 8C-33 97-01 August 1997 8C-34 97-01 August 1997 8C-35 97-01 August 1997 8C-36 97-01 August 1997 8C-37 97-01 August 1997 8-xi Reset April 2021

8.0 ELECTRIC POWER

8.1 INTRODUCTION

The Licensees transmission system, along with points of interconnection with neighboring utilities, is shown in Figure 8.1-1. The Licensee is a member utility of the Virginia-Carolinas (VACAR) Subregion Reliability Agreement which is a part of the Southeastern Reliability Council. As a member of such a group, the Licensee can supply power to, or consume power from other members, as its system allows or demands. Transmission system ties to other utilities are as listed in Table 8.1-1. The specific interface between the transmission grid and the Virgil C. Summer Nuclear Station is discussed in Section 8.2.

The Virgil C. Summer Nuclear Station 230 kV switchyard has a single bus, single RN 02-013 breaker arrangement, with three main bus sections. The center section is designated bus section 3, the east section designated bus section 1 and the west section designated bus section 2. A tap from bus section 2 provides a subsection of this bus RN 02-013 with two bay positions for the Fairfield No. 1 and No. 2 lines.

The Parr 115 kV engineered safety features (ESF) line terminates in a bay in bus section 3, crosses over bus section 3 with rigid bus construction, and continues to the Virgil C. Summer Nuclear Station.

There is an Alternate AC (AAC) source of power installed that is fed from an underground 13.8kV cable to the Parr Hydro Power Station (Separate from Parr Generating Complex). This line feeds a 13.2/7.2kV weather event hardened RN transformer located in the VCS Substation that is connected on the low side to a 07-001 non-safeguards bus in the turbine building. This source of power was designed to the requirements of NUMARC 87-00 App B and can power one entire safeguards train of equipment.

The onsite power network consists of three non-Class 1E distribution networks and two independent, redundant Class 1E distribution networks. The voltage levels of each network are 7200 volts, 480 volts and 120 volt a-c and 125 volt d-c.

The main source of power for the non-Class 1E networks is the unit auxiliary transformer which is connected to the output of the main generator between the generator circuit breaker and the low voltage bushings of the main power transformer (see Figure 8.2-3).

The emergency auxiliary transformers provide an emergency source of power for the non-Class 1E distribution network.

The normal source of power for the two independent Class 1E distribution networks are the ESF transformers and a winding of the emergency auxiliary transformers. These two sources of power also serve as an alternate source of power to each other (see Figures 8.2-3 and 8.2-4).

8.1-1 Reformatted March 2019

Two diesel generators are provided, one for each of the Class 1E buses to serve as an emergency source of power. The safety-related loads their safety functions and power requirements, supplied by the two emergency diesel generators are listed in Table 8.3-3. The ESF battery buses, inverter buses and associated loads are shown by Figures 8.3-1 and 8.3-2.

The Class 1E power network provides an adequate and reliable source of electric power for safe reactor shutdown following any design basis event, including loss of offsite power and for all normal modes of station operation.

The Virgil C. Summer Nuclear Station electrical systems are designed to comply with the scope of IEEE-308 [1] as specified in Section 1 of IEEE-308. Onsite power systems are designed to satisfy the applicable criteria of Reference [1], as well as the criteria of Regulatory Guides 1.6 and 1.9 (see Appendix 3A).

Implementation of IEEE Standards and the extent to which any alternative approaches are used is itemized in Table 8.1-2. Applicable criteria, including: General Design Criteria, Appendix A to 10 CFR 50; Regulatory Guides; and Branch Technical Positions are listed in Table 8.1-3 with references to appropriate sections of this FSAR.

Implementation of Regulatory Guides is discussed in Appendix 3A.

8.

1.1 REFERENCES

1. Institute of Electrical and Electronics Engineers, "Criteria for Class 1E Electric Systems for Nuclear Power Generating Stations," IEEE-308-1971.

8.1-2 Reformatted March 2019

TABLE 8.1-1 TRANSMISSION SYSTEM TIES TO OTHER UTILITIES South Carolina Electric South Carolina and Gas Company Public Service Authority Voltages(kV)

RN VCS1 Blythewood 230 12-026 12-028 VCS1 Winnsboro 230 16-010 Williams Charity 230 Lyles Sandy Run 115 RN 16-010 Lyles Columbia 115 St. George St. George 115 Faber Place Carnes 115 RN 16-010 Faber Place North Charleston 115 Pepper Hill Mateeba 230 Southeastern Power Administration CLM Tap Clark Hill 115 RN Duke Energy - Carolinas12-026 16-010 VCS1 Newport 230 VCS2 Bush River 230 RN 16-010 Saluda Hydro #2 Bush River (W) 115 Saluda Hydro #1 Bush River (B) 115 RN Duke Energy - Progress12-026 16-010 Wateree Sumter 230 St. George Sumter 230 Eastover Sumter 115 RN Georgia Power Company 16-010 Calhoun Falls Hart 115 (N.O.)

Okatie McIntosh 115 RN Savannah River Services12-026 Savannah River Plant Vogtle 230 8.1-3 Reformatted March 2019

TABLE 8.1-2 IMPLEMENTATION OF IEEE STANDARDS

1. IEEE-279-1971, "Criteria for Protection Systems for Nuclear Power Generating Stations," (ANSI N42.7, 1972).

Refer to Sections 7.1, 7.2, 7.3 and 7.6.

2. IEEE-308-1971, "Criteria for Class 1E Electric Systems for Nuclear Power Generating Stations."

Onsite and offsite electrical power systems are designed to satisfy the applicable criteria of IEEE-308-1971.

Refer to Sections 7.1.2.1.3, 7.6.1.2, 8.1, and 8.2.2.1. RN 99-002

3. IEEE-317-1972, "Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations."

Electrical penetrations are designed and fabricated in accordance with the requirements of IEEE-317-1972.

Refer to Sections 3.11.2.2.2 and 7.1.2.9 and the discussion of Regulatory Guide 1.63 in Appendix 3A.

IEEE-323-1971, "General Guide for Qualifying Class 1E Electrical Equipment for Nuclear Power Generating Stations."

RN Environmental Qualification (EQ) of Class 1E electrical equipment is addressed in 99-002 Section 3.11, which identifies the commitment to NUREG-0588, Cat. II (IEEE-323-1971) for the original plant design. NUREG-0588, Cat. I (IEEE-323-1974), 10CFR50.49, and NRC RG 1.89 requirements have also been used as the bases for environmental qualification, as described in FSAR Section 3.11 and Appendix 3A, under NRC RG 1.89.

4. IEEE-336-1971, "Installation, Inspection and Testing of Nuclear Power Generating Station Protection Systems," (ANSI N45.2.4., 1972).

Refer to Section 8.3.1.3 and Chapters 14.0 and 17.0.

5. IEEE-338-1971, "IEEE Standard Criteria for the Periodic Testing of Nuclear Power Generating Station Class 1E Power and Protection Systems."

Refer to Section 7.1.2.11 and Chapter 14.0.

8.1-4 Reformatted March 2019

TABLE 8.1-2 (Cont.)

6. IEEE-344-1975, "IEEE Recommended Practices for Seismic Qualification of Class RN 99-002 1E Equipment for Nuclear Power Generating Stations."

Class 1E electric equipment is tested and data is recorded to ensure that equipment satisfies design performance requirements during and following a safe shutdown earthquake (SSE). The qualification program meets the requirements of RN IEEE-344-1975 as discussed in Section 3.10.99-002

7. IEEE-379-1972, "Guide for the Application of the Single Failure Criteria to Nuclear Power Generating Station Protection Systems," (ANSI N41.2).

Refer to Section 7.1.2.7 and the discussion of Regulatory Guide 1.53 in Appendix 3A.

8. IEEE-384-1974, "Criteria for Separation of Class 1E Equipment and Circuits,"

(ANSI N41.14).

Refer to Sections 7.1.2.2.1, 8.3.1.4 and 8.3.1.5 and the discussion of Regulatory Guide 1.75 in Appendix 3A.

9. IEEE-387-1972, "Criteria for Diesel Generator Units Applied As Standby Power Supplies for Nuclear Power Stations."

IEEE-387-1972 is used as the basis for design criteria for the diesel generators and accessories. Included among the referenced standards in IEEE-387-1972, Section 4.1, are IEEE-308-1971 and IEEE-323-1971. Diesel generators are designed to satisfy these standards.

10. IEEE-450-1987, "Recommended Practice for Maintenance, Testing and 99-01 Replacement of Large Stationary Type Power Plant and Substation Lead Storage Batteries."

Refer to Section 8.3.2.2.2.

8.1-5 Reformatted March 2019

TABLE 8.1-3 LIST OF APPLICABLE CRITERIA Criteria Title Reference FSAR Section(s)

1. General Design Criteria (GDC),

Appendix A to 10 CFR 50 GDC-1 Quality Standards and Records 3.1.2 GDC-2 Design Bases for Protection Against 3.1.2, 3.10, 3.11 Natural Phenomena GDC-3 Fire Protection 3.1.2, 7.1.2.2.3, 8.3.3.2 GDC-4 Environmental and Missile Design Bases 3.1.2 GDC-5 Sharing of Structures, Systems and 3.1.2 Components GDC-13 Instrumentation and Control 3.1.2, 7.3.1, 7.3.2 GDC-17 Electric Power Systems 3.1.2, 8.2.1, 8.2.2.2, 8.3.1.2.1, RN 8.3.2.2.1 99-002 GDC-18 Inspection and Testing of Electric Power 3.1.2, 8.2.1, 8.3.1.2.1, 8.3.2.2.1 Systems GDC-21 Protection System Reliability and Testability 3.1.2, 7.2.2.2, 7.3.1, 7.3.2 GDC-22 Protection System Independence 3.1.2, 7.2 GDC-33 Reactor Coolant Makeup 3.1.2, 8.3 GDC-34 Residual Heat Removal 3.1.2, 8.3 8.1-6 Reformatted March 2019

TABLE 8.1-3 (Continued)

LIST OF APPLICABLE CRITERIA Criteria Title Reference FSAR Section(s)

GDC-35 Emergency Core Cooling 3.1.2, 8.3 GDC-41 Containment Atmosphere Cleanup 3.1.2, 8.3 GDC-44 Cooling Water 3.1.2, 8.3

2. Regulatory Guides (RG)

RG 1.6 Independence Between Redundant App. 3A, 8.1, 8.3.1.2.1, 8.3.2.2.1 Standby (Onsite) Power Sources and Between Their Distribution Systems RG 1.9 Selection of Diesel Generator Set Capacity App. 3A, 8.1, 8.3.1.1.2.4, 8.3.1.2.1 for Standby Power Supplies RG 1.22 Periodic Testing of Protective System App. 3A, 7.1.2.5, 7.3.2 Actuation Functions RG-1.29 Seismic Design Classification App. 3A RN 99-002 RG 1.30 Quality Assurance Requirements for the App. 3A, Chapter 17.0 Installation, Inspection and Testing of Instrumentation and Electric Equipment RG 1.32 Use of IEEE Std. 308-1971, "Criteria for App. 3A, 8.2.1, 8.3.1.2.1, 8.3.2.2.1 Class 1E Electric Systems for Nuclear Power Generating Stations" 8.1-7 Reformatted March 2019

TABLE 8.1-3 (Continued)

LIST OF APPLICABLE CRITERIA Criteria Title Reference FSAR Section(s)

RG 1.41 Preoperational testing of redundant onsite App. 3A, 8.3.1.1.2.6, Chapter 14.0 Electric Power Systems to verify proper load group assignments.

RG 1.47 Bypassed and Inoperable Status Indication App. 3A, 7.1.2.6 for Nuclear Power Plant Safety Systems RG 1.53 Application of the Single Failure Criterion to App. 3A, 7.1.2.7 Nuclear Power Plant Protection Systems RG 1.63 Electric Penetration Assemblies in App. 3A, 7.1.2.8, 8.3.1.1.4 Containment Structures for Water-Cooled Nuclear Power Plants RG 1.68 Preoperational and Initial Startup Test App. 3A, Chapter 14.0 Programs for Water-Cooled Power Reactors RG 1.70 Standard Format and Content of Safety App. 3A Analysis Reports for Nuclear Power Plants RG 1.75 Physical Independence of Electric Systems App. 3A, 7.1.2.2.1, 8.3.1.4.3 RG 1.81 Shared Emergency and Shutdown Electric App. 3A Systems for multi-unit Nuclear Power Plants RG 1.89 Qualification of Class IE Equipment for App. 3A, 3.11, 8.3.1.2.2.1 Nuclear Power Plants RG 1.93 Availability of Electric Power Sources App. 3A 8.1-8 Reformatted March 2019

TABLE 8.1-3 (Continued)

LIST OF APPLICABLE CRITERIA Criteria Title Reference FSAR Section(s)

3. Branch Technical Positions (ETCSB)

ETCSB1 Backfitting of the Protection and Emergency Chapters 7.0 and 8.0 Power Systems of Nuclear Reactors ETCSB2 Diesel-Generator Reliability Qualification 8.3.1.1.6 Testing ETCSB6 Capacity Test Requirements of Station 8.3.2.2.2 Batteries-Technical Specifications ETCSB8 Use of Diesel-Generator Sets for Peaking 8.3.1.1.2.4 ETCSB10 Electrical and Mechanical Equipment 3.10, 8.3.2.2.1 Seismic Qualification Program ETCSB11 Stability of Offsite Power Systems` 8.2.2.2 ETCSB17 Diesel Generator Protective Trip Circuit 8.3.1.1.2.8, Table 8.3-3a Bypasses ETCSB21 Guidance for Applicable of Regulatory App. 3A (discussion of RG 1.47),

Guide 1.47 7.1.2.6 ETCSB27 Design Criteria for Thermal Overload App. 3A (discussion of RG 1.106),

Protection for Motors of Motor-Operated 8.3.1.1.4 Valves 8.1-9 Reformatted March 2019

N 0 R T H

-. c A R TL I N A

-.y 0 It IC.--.-

-r CM!ST!R Lil! 1Utl11

'OlT IACISOI

-esceae-t

.\. .."'* -

--___ --u.

r


1.111 ......

r

. .. . . ---9'S --

- - - - -.s.m

'= ---........ -...--...

~.._. ....

--~11\S

,...... __..._ um: ... Lam - -


uc-~

9J'C _ _ . . _

  • . . . . . . . . . . Mii - * - - . . . . . . ..aa 8
  • ,..........,:;-:;::::::,===-...;-==-=;;:...lL=-==l=='=!~!=----1 1.C.WDI y/

SOUTH CAROLINA ELECTRIC & GAS CO.

VIRGIL C. SUMMER NUCLEAR STATION Transmission System Map Fi ure 8.1-1 CAllAll llKAWl118 - 110 HOT REVISE MAIUILL Y PLAN "SAFETY" IHTO EVERY JOO ~

Arne11df!Jt nI

  • 11Tt11n1n1n11111111II11

8.2 OFFSITE POWER SYSTEM 8.

2.1 DESCRIPTION

The SCE&G transmission system supplies offsite a-c power for operating the engineered safety features (ESF) buses as well as for startup and shutdown of the station. Two (2) separate sources of offsite power are provided for the Class 1E electric system, which is in compliance with General Design Criterion 17 and Regulatory Guide 1.32 (see Appendix 3A). One (1) source is the SCE&G transmission grid terminating at the Virgil C. Summer Nuclear Station 230 kV switchyard bus, which feeds the plant RN 02-013 through a step down transformer. The second source is from the existing Parr Generating Complex over a 115 kV transmission line (see Figure 8.2-1). This source is connected to the plant through onsite step down transformers and a separate regulating transformer. These 2 sources have sufficient separation and isolation so that loss of the Virgil C. Summer Nuclear Station with the Fairfield Hydro Units offline will not degrade either of the sources below their acceptable voltage limit. Thus, loss of the station output, in conjunction with an accident, will not result in a degraded voltage condition on either source. Likewise, loss of a line or generation on the 115 kV network will not cause a degraded condition on the Emergency Auxiliary Transformer which is fed power from the 230 kV bus. Also, no single event such as an insulator or bushing failure, transformer failure, transmission line tower failure, line breakage, or similar event can cause simultaneous disruption of both sources. The offsite power system is not designed to withstand tornadoes, exceptionally severe hurricanes or ice storms.

However, the circuit breakers for isolation of the 2 separate onsite power systems from the offsite power system are located within 2 separate, missile protected rooms.

Therefore, any failure of the offsite power system, including the bus duct system between the offsite power system and the ESF buses, is isolated from the ESF buses before the emergency diesel generators are started (see Figure 8.2-2).

The allowable system voltage fluctuations for each of the 2 preferred offsite sources are defined in Table 8.2-2. As noted in the table, the allowable voltage range is dependent on generating unit availability, the number of buses connected to the source, and on the RN 97-025 configuration of the transformers for the 115 kV line. The SCE&G dispatchers are provided with instructions to make every effort to maintain the system voltage fluctuations within these allowable ranges. The instructions require maintenance of the voltage limits during shutdown, as well as during operation, of Virgil C. Summer Nuclear Station. The transmission system voltage drop due to loss of the Virgil C. Summer RN 99-002 Nuclear Station is included within the allowable voltage ranges during plant operation with the unit online. The transmission system voltage drop is not included within the RN allowable voltage ranges during plant operation with the unit offline because the unit is06-042 not generating. A direct communications link is provided between the SCE&G Dispatch Office in Columbia, SC, and all SCE&G generating plants. Through this communications link, the plant operators receive the instructions from the dispatch office for setting generator kilowatt, kilovar output, voltage level, and for controlling the VAR output on the Fairfield units when they are used for pumping.

8.2-1 Reformatted April 2021

The plant operators are provided with indicators for the engineered safety features (ESF) bus network as discussed in Section 8.3.1.2.1. Also, voltmeters, ammeters, kilowatt meters, kilovar meters, and frequency meters are provided for the main generator bus. If generator output differs from that specified by the dispatch office, the operator notifies the dispatch office and receives a new set of operating levels for the generator.

Control and indication are provided locally at the substation relay house and/or the RN Unit 1 relay house and remotely in the system dispatchers office for each of the 12-001 incoming 230 kV transmission line circuit breakers and the 230 kV bus tie circuit RN 02-013 breakers. Circuit breaker control consists of tripping and closing capability. Indication includes circuit breaker status (open or closed) and the amount and direction of the power being transmitted over each transmission line. Control power for the substation RN relay house is supplied from a 125 VDC battery, with a backup feed from the plant 12-001 non-1E. Control power for the Unit 1 relay house is supplied from two (2) 125 volt d-c 14-013 batteries, each sized to serve as back-up to the other.

The 230 kV buses are protected by bus differential relays. Each 230 kV line and the 115 kV line is protected by primary and backup relaying. Each 230 kV line terminal has RN relays that provide breaker failure protection that trips the appropriate bus lockout relay 01-043 02-013 when the breaker fails to trip. Each line relays also provide a multi-shot, static reclosing 14-019 function that is active in some breakers.13-012 The 230 kV circuit breakers associated with the plant main transformer and emergency RN auxiliary transformers, as well as the circuit switches associated with the ESF 02-013 transformers, are controlled from, and provide indication in, the control room. Also, the 230 kV circuit breakers can be tripped at the circuit breaker control panels mounted on the circuit breaker structures.

Manually operated disconnect switches are provided for the 230 kV circuit breakers to isolate each from the bus and associated lines. These manual disconnects permit testing and maintenance of each circuit breaker on an individual basis while allowing the 230 kV substation to remain energized, which satisfies General Design Criterion 18.

Testing and maintenance are performed periodically in accordance with a SCE&G program.

As shown by Figure 8.2-2, the 115 kV line terminates in a rigid bus construction for the crossover of the 230 kV middle bus section. The 115 kV bus has no connection to the 230 kV bus. Therefore, any problems associated with the 230 kV bus do not affect the 115 kV bus. The rigid bus construction offers high reliability by eliminating the RN possibility of line dropping at this crossover point.13-015 8.2-2 Reformatted April 2021

The preferred power source transformers, which are the emergency auxiliary transformers and the combination of the safeguard transformers and the voltage regulator are located out of doors and are physically separated from each other.

Lightning arrestors are used where applicable for lightning protection. The transformers are protected by automatic water spray systems to extinguish oil fires quickly, thus preventing spreading. The transformer area is provided with a gravel filled sump pit to contain transformer oil should a rupture occur.

Power from both the emergency auxiliary transformer and from the combination of the 2 safeguard transformers and the voltage regulator is brought into the plant by independent 7200 volt buses. These buses are physically separated and independently supported throughout their length to the 2 separated, missile protected rooms which contain the separate Class 1E electric system 7200 volt buses, thus maintaining redundancy.

8.2.1.1 Unit Auxiliary, Emergency Auxiliary, and Safeguards Transformers Normal station service power for non-Class 1E equipment, which includes that required during normal operation, startup, shutdown, and following shutdown, is provided from the unit auxiliary transformer. The primary side of the unit auxiliary transformer is connected to the generator isolated phase bus duct at a point between the generator circuit breaker and the low voltage connections to the main step up transformer as shown by Figure 8.2-3.

The unit auxiliary transformer is rated 22 kV - 7200 volts. The three 7200 volt secondaries are used to feed 3 independent 7200 volt non-Class 1E auxiliary buses.

The 2 ESF system 7200 volt buses are fed independently from other sources.

Two (2) emergency auxiliary transformers are provided. The primary sides of these 2 transformers are connected in parallel to the 230 kV substation bus. The 2 secondary windings on each bank are rated 7200 volts. Three (3) of the 4 windings are used as an emergency power source for the three 7200 volt non-Class 1E auxiliary system buses.

The fourth winding is a preferred offsite power source for either or both of the ESF system power trains (see Figures 8.2-3 and 8.2-4). Normally this winding is used to supply the 7200 volt ESF bus 1DB.

The primary windings of the 2 safeguard transformers, XTF-4 and 5, are connected in parallel to the 115 kV line. These 2 transformers, in combination with the regulating transformer, XTF-6, are the second preferred offsite power source for either or both of the ESF system power trains. Normally, safeguard transformer 4 is used in combination with the voltage regulator to supply 7200 volt ESF system bus 1DA. If the voltage regulator is out of service, the 2 safeguard transformers can be used in parallel to supply either or both of the 7200 volt ESF system buses; or 1 of the 2 transformers can RN be used to supply either or both of the buses (see Figure 8.2-4).06-042 8.2-3 Reformatted April 2021

Connected to the same intermediate bus (1DX) as transformers XTF-4, 5 and 6 is the VC Summer Alternate AC Source (AAC). The AAC source is fed from an underground 13.8kV cable to the Parr Hydro Power Station main generator bus via Parr BKR 13123.

This line feeds a 13.2/7.2 kV transformer located in the VCS Substation that feeds into the 1DX bus. All cabling and lightning protection equipment associated with this feed is weather protected. The installed cable is oversized for the potential load attached to it RN such that the 105ºC normal rating of the cable cannot be reached with the maximum 07-001 loading of a single ESF bus (750 mcm AL cable with most limiting rating of 490 amps will be loaded to a running maximum of 245 amps, 5.9MW load equivalent or 50% cable rating). Direct monitoring of underground cable temperature is not required as long as total ESF bus loading does not exceed 5.9MW (5MW calculated load with 15%

conservatism). The loading of the AAC source onto either one of two ESF buses is to be done manually (sequencer Out-of-Service).

Each of the 2 principle 7200 volt ESF buses is provided with a manually initiated transfer scheme to shift the bus power supply between the 2 preferred offsite power sources.

8.2.1.2 Transmission System The network interconnections between the Virgil C. Summer Nuclear Station and the RN SCE&G transmission system consist of eight 230 kV transmission lines which approach 12-039 the site from 3 directions. The 230 kV transmission lines interconnect the Virgil C.14-019 Summer Nuclear Station with the major sources of generation on the SCE&G system through major transmission grid substations as shown by Figures 8.1-1 and 8.2-1. The lines are designed to meet or exceed NESC (ANSI-C2) 1973 edition, medium loading, grade B construction requirements.

RN Two of these eight transmission lines extend directly from the Virgil C. Summer Nuclear 01-043 02-013 Station 230 kV bus section 2 to the SCE&G Fairfield Pumped Storage Facility.16-010 In addition, two 230 kV transmission lines interconnect the Virgil C. Summer Nuclear RN 12-026 Station with the South Carolina Public Service Authority (SCPSA) system.12-028 16-010 RN One (1) 115 kV transmission line extends from the Virgil C. Summer Nuclear Station to 02-013 the SCE&G Parr Generating Complex. The Parr 115kV substation and associated Transmission Grid connections serve as one of the preferred power sources for the ESF buses at the Virgil C. Summer Nuclear Station. Within the Parr 115kV substation are four gas-fired combustion turbines that with the substation form the Parr Generating RN 07-001 Complex. The Parr Hydro station is connected to the Parr 115kV substation via a 115/13.2kV tap changing transformer, but is not considered part of the Parr Generating Complex even with its close proximity.

8.2-4 Reformatted April 2021

The 115 kV transmission line has no direct ties to the Parr Generating Complex 230 kV switchyard. This switchyard does have a tie from the Virgil C. Summer Nuclear Station 230 kV switchyard bus. The Parr Generating Complex 115 kV switchyard bus receives RN power from the Parr Generating Complex and from a 115 kV tie line to the Denny 02-013 Terrace substation. With this arrangement, an outage at the Virgil C. Summer Nuclear Station 230 kV switchyard does not have a direct effect on the 115 kV ESF transmission line.

Figures 8.2-2 and 8.2-2a through 8.2-2d indicate the physical relationship between transmission lines entering the switchyard, between the switchyard and the plant and within the switchyard. All 230 kV transmission tie lines to other major interconnection points converge on the switchyard. All transmission line structures have a minimum of RN 60 feet center to center as they approach the switchyard.02-013 Each transmission line has adequate capacity for the supply of the preferred power source emergency auxiliary transformer. The 230 kV transmission lines, 230 kV circuit RN breakers and 230 kV buses in the switchyard are designed to withstand and interrupt 02-013 the maximum fault level at the bus.

Details of the construction of each transmission line are as follows:

1. Parr-Summer Safeguard 115 kV Line This line is about 2.6 miles long. Wood, H-frame construction and steel monopole structures are used. The line extends from the Parr 115 kV substation to the vicinity of the Parr 230 kV substation and then to Virgil C. Summer Nuclear Station. RN An approximately 600 foot segment of this line is routed from above ground to an 02-013 13-015 underground duct bank and then returns to above ground routing. This underground segment eliminates the crossing of the 115 kV line over 230kV transmission lines near the Parr Substation.

There is a switchable tie to the Parr-Winnsboro No. 1 line. It also crosses over the RN Norfolk-Southern Railroad at Parr and over a railroad spur at Virgil C. Summer 02-013 Nuclear Station. The last 2 line structures at Virgil C. Summer Nuclear Station are steel monopole structures which raise this line above a VCS1-VCS2 tie. There are RN no structure or circuit conflicts since a failure of the towers would not result in loss13-015 of both sources of offsite power, as the VCS1-VCS2 tie breaker would trip leaving the other 230 kV lines intact.

8.2-5 Reformatted April 2021

2. Summer-Edenwood Line, 230 kV This line is about 33.02 miles long. At Virgil C. Summer Nuclear Station it is on 3 double circuit, 230 kV steel towers. The end of this line ties to the Edenwood RN 230 kV line about 1.2 miles from Parr. The line crosses over the Parr-Denny 02-013 Terrace 230 kV line and the double circuit Parr-Denny Terrace 115 kV line. The line is of wood H-frame construction on a right-of-way with no other lines. The line continues past McMeekin Station on to Edenwood Substation.

RN

3. Deleted 12-039
4. Summer-Pineland Line, 230 kV This line is on 3 double circuit, steel towers with the Summer-Denny Terrace line. RN 02-013 These lines then are on wood H-frame structures designed for double circuits. The structures are in the center of a 240 foot wide right-of-way which extends for about 17.24 miles. In this area, the line parallels the SCPSA Summer-Blythewood 230 RN 02-013 kV H-frame. There are structure conflicts in this area. For the next 1.62 miles, this RN line is on single circuit wood H-frame on a common right-of-way with the 09-024 Summer-Denny Terrace line. There are no structural conflicts in this area. For the RN 02-013 next 5.0 miles, this line is on single circuit, wood H-frame on its own right-of-way.

For about the final 0.54 mile, this line is on double circuit, improved appearance, RN steel poles at Pineland substation. This line crosses over several transmission 97-025 lines but none cross over it. Total length is about 24.4 miles.

5. Summer-Denny Terrace Line, 230 kV RN 02-013 This line is attached to the same structures as the Summer-Pineland line at the Virgil C. Summer Nuclear Station and for the first 17.24 miles. From this point the Summer-Denny Terrace line is attached to single circuit H-frame structures and RN 02-013 shares a common 240 foot right-of-way with the Summer-Pineland line for 1.62 miles. It is then on its own right-of-way for 5.91 miles. The Summer-Denny Terrace line then parallels the Denny Terrace-Rader double circuit 115 kV lines (crossing over them twice) to Denny Terrace, a distance of about 1.48 miles. Total length is 26.25 miles.

RN

6. Deleted 12-026 12-039 8.2-6 Reformatted April 2021

RN

7. South Carolina Public Service Authority, VCS1-Blythewood Line, 230 kV 14-019 This line is installed on multi-pole single circuit (MPSC) structures with 1272 ACSR single conductor and is operated and owned by SCPSA. This line is located on variable width right-of-way (R/W) that extends for 20 miles from the VCS1 to SCPSAs Blythewood substation. This line is on common R/W with SCPSAs VCS1-Winnsboro 230 kV line and SCE&Gs VCS1-Killian, Denny Terrace and RN 02-013 Pineland 230 kV lines for 1.0 mile to a point referred to as Winnsboro Junction.14-019 From Winnsboro Junction, the line extends 2.8 miles to SCPSA Pomaria-Winnsboro 69 kV line. From the Pomaria-Winnsboro 69 kV line, the line extends 13.4 miles on common R/W with SCE&Gs VCS1-Denny Terrace and Pineland 230 kV lines. From this point, the line veers off and extends 2.9 miles to SCPSAs Blythewood substation.
8. VCS2 Bus 2 Tie Line, 230 kV RN 02-013 This line connects V. C. Summer Unit 1, Bus 2 to V. C. Summer Unit 2 switchyard.12-026 It parallels the Duke-Newport line for approximately 0.63 mile. Total length is 0.87 mile.
9. South Carolina Public Service Authority, Summer-Winnsboro Line, 230 kV This line is operated and owned by the SCPSA. It parallels the Summer- RN Blythewood line for a distance of 3.7 miles on the east side and abutting the 12-028 existing right-of-way. From that point the line heads in a northeasterly direction and double circuits with the existing SCPSA Pomaria-Winnsboro 69 kV line. Total length is about 14 miles.
10. VCS1-Killian Line, 230 kV This line is installed on single pole single circuit (SPSC) and single pole double circuit (SPDC) steel monopole structures with bundled 1272 ACSR conductor. The line is located on variable width right-of-way (R/W) that extends for 35 miles from the VCS1 Switchyard to the Killian 230/115 kV Transmission substation. A SPSC section of this line is on common R/W with SCPSAs VCS1-Winnsboro and Blythewood 230 kV lines and SCE&Gs VCS1-Denny Terrace and Pineland 230 kV RN lines for 1 mile to a point referred to as Winnsboro Junction. From Winnsboro 14-019 Junction, the line extends 13 miles to Winnsboro and is constructed SPDC with the second circuit being the Parr-Winnsboro 115 kV Line #1. This line section is on common R/W with the Parr-Winnsboro 115 kV Line #2. From Winnsboro, the line extends 15 miles to a point referred to as Blythewood PMSS and is constructed SPDC with the second circuit being the Blythewood-Winnsboro 115 kV line. From Blythewood PMSS, the line extends 6 miles to the Killian 230/115 kV Transmission substation and is constructed SPDC with the second circuit being the Blythewood-Killian 115 kV line.

8.2-7 Reformatted April 2021

11. VCS1, Bus 1-VCS2 Tie, 230 kV This line is installed on single pole single circuit (SPSC) steel monopole structures with bundled 1272 ACSR conductor. This is one of three 230 kV bus ties each RN approximately 1 mile in length that runs between the VCS1 and VCS2 14-019 Switchyards.

Distances of all lines from the Virgil C. Summer Nuclear Station terminal to the first major substation are listed in Table 8.2-1.

8.2.2 ANALYSIS 8.2.2.1 Introduction UCR-The basis for design of DESC transmission facilities is such that a defined system will 2021-005 maintain stability with the loss of any system generator, including Virgil C. Summer RN Nuclear Station, or the most critical transmission line, or the loss of the largest system 16-028 load. The system will also remain stable for the most severe fault condition on any transmission line or substation bus. As such, the loss of any single system generator, including Virgil C. Summer Nuclear Station, does not degrade the alternate system to where it cannot furnish shutdown power to Virgil C. Summer Nuclear Station on an uninterrupted basis. The Virgil C. Summer Nuclear Station buses and the location of the emergency auxiliary transformers and ESF transformers supplying shutdown power are such that no single permanent fault condition can prevent at least 1 of the auxiliary transformers from being available to furnish shutdown power. Table 8.2-1 lists the RN distances of lines from the Virgil C. Summer Nuclear Station switchyard to each first 02-013 major substation.

8.2.2.2 Stability Study Description The System Stability study was performed using power system simulator software. The dynamic simulation cases and dynamics data were updated versions of cases and data which were issued by the NERC and which were modified to meet the specific requirements of this study. The dynamic simulation cases and data were validated using the simulator software case initialization and model testing features. This was followed by a 30 second steady state simulation in order to demonstrate that the cases RN 02-013 and data represented non-disturbed conditions prior to simulating system contingencies.06-042 The results of the steady state simulations are not included in this report but are 10-030 available for review.16-028 Special attention was given to the analysis of disturbances in the vicinity of the V. C. UCR-2021-Summer Nuclear Station during various system conditions. The simulations that were 005 performed were selected as a result of discussions between V. C. Summer Design Engineering and DESC Transmission Planning.

8.2-8 Reformatted April 2021

The simulations which were performed for each contingency began with a 1 second steady state period which was followed by a sequence of contingency events and a subsequent new steady state period for a total of 30 seconds for each contingency simulation.

Both peak and light system load conditions were studied. System faults during peak load conditions are generally more challenging for offsite power voltage adequacy.

System faults during light load conditions are generally more challenging for generator angular stability.

The base year chosen for summer peak and light load conditions is the year of the UCR-2021-Study and is typically 3-4 years in the future. Since the previous study was 005 completed, a number of changes have been made or have been planned for the DESC generating and transmission systems. All actual and planned system improvements are incorporated in the simulation models used for the current study.

The base year chosen for summer peak and light load conditions is the year of the Study and is typically 3-4 years in the future. The study includes any actual system changes since the last study and any changes planned for 3-4 years beyond the base year.

The VCS FSAR required scenarios assume three MVAR levels (170, 330, and 484 MVAR). The peak load cases assume the VCS exciter provides 330 MVAR and 484 MVAR. The light load cases assume the VCS exciter provides 170 MVAR and 330 RN MVAR. 170 MVAR was modeled for a specific ESF bus alignment.02-013 06-042 10-030

.Use of the 484 MVAR and 330 MVAR levels for the VCS FSAR required scenarios is16-028 considered conservative for several reasons. The VCS generator exciter has a maximum momentary rating of 484 MVAR and a typical maximum continuous rating of 330 MVAR. Therefore. these values represent the maximum MVAR load the station can support for any loading scenario. These values can also represent a substantial portion of the total typical MVAR load seen on the DESC transmission system.

Therefore, these values are consistent with the VCS generator exciter providing a significant portion of the voltage support for the entire DESC system. Therefore, these loadings conditions are considered extremely conservative and unlikely to occur.

V. C. Summer Balance of Plant (BOP) station loads were updated. In addition, because it is possible for Engineered Safeguard Features (ESF) bus loads to all be served from one bus, these loads were simulated as being located fully at each ESF bus (i.e., two ESF trains of equipment connected to each of the GDC 17 credited offsite sources).

For this study, the V. C. Summer generator governor model was disengaged from the simulation. A review of neighboring utilities' practices in modeling nuclear generators for transient stability simulations confirms that this is the accepted practice for representing block loaded nuclear generator governors.

8.2-9 Reformatted April 2021

The transfer of the Balance of Plant loads to the Emergency Auxiliary Transformers following a generator breaker operation has been incorporated into the study. UCR-The study models various contingencies and transmission operating scenarios. These 2021-005 scenarios resulted in a combined effect to lessen the available transmission voltage and angular stability support of V.C. Summer for the conditions studied. The practice of maintaining reactive power reserves in three separate areas of the Dominion Energy South Carolina system ensures that reactive power sources are available to provide voltage support to V.C. Summer.

The V. C. Summer 7.2 kV Engineered Safeguard Features (ESF) buses are supplied from the 230 kV and the 115 kV Offsite Power Supply buses. Protection from unacceptable voltage conditions is provided by Loss of Voltage and Degraded Voltage Relays that monitor the voltages of the 7.2 kV buses. The Loss of Voltage Relay scheme is modeled to operate after a 13.5 cycle (0.225 seconds) time delay at 82.00 %

of the nominal 7.2 kV bus voltage unless the voltage recovers to 82.75% during the time delay period of 0.225 seconds. The Degraded Voltage Relay scheme is set to operate after a 174.0 cycle (2.9 seconds) time delay at 91.75% of the nominal 7.2 kV bus voltage unless the voltage recovers to 92.328% during the 2.90 seconds time delay period. Because of the number of variables involving load tap changer settings and step change times, and ESF bus loads, no attempt has been made to report the voltages at the 7.2 kV ESF buses. Descriptions of loss of voltage and degraded voltage timer and relay operations assume that the per unit value of the 7.2 kV bus voltages are the same as those at the 230 kV and 115 kV Offsite Power Supply buses. The voltage RN results of the simulations are reported to V. C. Summer Design Engineering for use in 16-028 calculations to determine acceptability of the voltage responses.

DESC load under frequency and generator over frequency/under frequency responses UCR-2021-as a result of the studied conditions were also identified. The VCS generator frequency 005 responses were monitored and evaluated in order to assess whether the VCS generator reactor coolant pump under frequency or over frequency relays would trip for frequency excursions.

CONCLUSIONS Each of the contingencies which were simulated for this study were evaluated for generator rotor angle, generator frequency deviation, tie line flows, system under frequency load shedding, under/over frequency tripping operations, and system voltage responses. In addition, the effects of each contingency on the 230 kV and 115 kV V. C.

Summer Offsite Power Supply buses were examined as well as the resulting steady state power flows on the transmission lines which are connected to the V. C. Summer transmission substation.

8.2-10 Reformatted April 2021

The generator rotor angle responses demonstrated that no conditions existed in which a generator would become unstable. None of the transmission lines connected to the V. UCR-2021-C. Summer substation DESC system to neighboring systems remained in service 005 throughout all conditions studied. No conditions were found that would result in the islanding of the DESC system or neighboring systems.

Generator and system frequency responses were all within the normal operating ranges and there was no indication of system under frequency load shedding or generator under I over frequency tripping, Reactor Protection System under frequency operation, or Reactor Coolant Pump under frequency tripping.

The results of this study demonstrate that the DESC generating and transmission RN system is stable for the conditions that were studied. The contingencies were selected 02-013 so as to test the capability and capacity of the 115 kV and 230 kV Offsite Power Supply 06-042 buses at the V. C. Summer Station Unit 1 to supply the loads assigned in normal,10-030 16-028 abnormal, accident, or plant shutdown conditions. No contingency conditions were found to result in the simultaneous loss of both GDC 17 credited Offsite Power Supply buses.

Also, no conditions were found to result in under frequency load shedding operations or generator under/over frequency tripping. In addition, no System Operating Limits (SOL's) or Interconnection Reliability Operating Limits (IROL's) were identified. Finally, there were no indications of voltage instability or stability limits. None of the contingencies that were simulated in this study indicated generator rotor angle instability would develop for generators in neighboring systems.

8.

2.3 REFERENCES

1. Institute of Electrical and Electronics Engineers, "Criteria for Class 1E Electric Systems for Nuclear Power Generating Stations," IEEE-308-1971.

8.2-11 Reformatted April 2021

TABLE 8.2-1 DISTANCES OF LINES TO FIRST MAJOR SUBSTATION Distance from Virgil C.

First Major Summer Nuclear Station Substation Terminal (miles)

RN 12-039 16-010 Denny Terrace 26.25 RN 02-013 Pineland No. 1 24.4 Fairfield No. 1 1.24 Fairfield No. 2 1.24 RN 12-026 14-019 Blythewood 20.0 VCS2 Bus 2 Tie 0.87 RN 12-026 VCS2 Bus 3 Tie 0.91 12-017 RN Winnsboro 14.0 12-028 RN Killian 38.6 14-019 16-010 VCS2 Bus 1 Tie 1.0 Newport 55.62 8.2-12 Reformatted April 2021

TABLE 8.2-2 ALLOWABLE VARIATION IN OFFSITE SYSTEM VOLTAGE Allowable Range of Offsite Voltage Transformer(s) Connected Buses (Kilo Volts) RN Unit Online Unit Online Unit Offline 10-030 115 kV Source 330 Mvar 484 Mvar XTF4 with XTF6 1DA (1) or 1DB(5) 105.5 to 131.3 106.4 to 131.3 102.3 to 131.3 XTF4 with XTF6 1DA and 1DB (3) 112.8 to 131.3 113.7 to 131.3 109.5 to 131.3 XTF4 and XTF5 1DA (2) or 1DB(2, 5) 113.4 to 119.8 113.4 to 119.8 109.3 to 119.8 XTF4 and XTF5 1DA and 1DB (2,3) 114.8 to 119.8 115.7 to 119.8 111.6 to 119.8 XTF4 or XTF5 1DA (2) or 1DB(5) 114.7 to 119.8 115.6 to 119.8 111.5 to 119.8 XTF4 or XTF5 1DA and 1DB (2,3) 119.5 to 119.8 (4) 119.5 to 119.8 (4) 117.5 to 119.8 RN 99-185 06-042 230kV Source 10-030 13-008 XTF31 1DB (1) or 1DA(5) 225.7 to 239.6 228.4 to 239.6 218.3 to 239.6 XTF31 1DA and 1DB (3) 233.0 to 239.6 235.8 to 239.6 225.7 to 239.6 XTF31 1DB and 1C or 226.4 to 239.6 229.1 to 239.6 219.0 to 239.6 1DA and 1C(5)

XTF31 1DA, 1DB, and 1C (3) 233.7 to 239.6 236.5 to 239.6 226.4 to 239.6 NOTES:

1. Normal operating alignment
2. Used only if regulator is out of service
3. Maintenance only, LCO in effect, if in Modes 1-4 RN 06-042 RN
4. Limit Mvar generation output to 170 Mvar 10-030 RN
5. Alternate operating alignment 13-008 8.2-13 Reformatted April 2021

FSAR FIGURE REFERENCE FIGURE 8.2-1 DRAWING E-747-035

FSAR FIGURE REFERENCE FIGURE 8.2-2 DRAWING E-229-054

FSAR FIGURE REFERENCE FIGURE 8.2-2a DRAWING E-229-001

FSAR FIGURE REFERENCE FIGURE 8.2-2b DRAWING E-229-002

FSAR FIGURE REFERENCE FIGURE 8.2-2c DRAWING E-229-003

FSAR FIGURE REFERENCE FIGURE 8.2-2d DRAWING E-229-006

FSAR FIGURE REFERENCE FIGURE 8.2-3 DRAWING E-206-011

FSAR FIGURE REFERENCE FIGURE 8.2-4 DRAWING E-206-012

8.3 ONSITE POWER SYSTEMS 8.3.1 A-C POWER SYSTEMS 8.3.1.1 Description The a-c power systems consist of the various auxiliary and engineered safety features electrical systems designed to provide reliable electrical power during all modes of station operation and under shutdown conditions. The a-c power systems are shown by Figures 8.2-3 and 8.2-4. The major electrical equipment is described in Table 8.3-1.

Engineered safety features (ESF) auxiliaries are arranged so that loss of a single bus, for any reason, still leaves sufficient auxiliaries to safely perform required functions. In general, auxiliaries related to functions other than engineered safety features are connected to 3 auxiliary buses. A generator circuit breaker is provided to permit isolation of the generator from the system, which eliminates the necessity for a transfer from the emergency auxiliary transformer to the normal auxiliary transformer on plant startups. Engineered safety features loads are divided between 2 additional essential system buses in observance of the single failure criteria.

Controls are provided in the control room for selected 7200 volt and 480 volt switchgear units. These units are selected to provide the operator with control of the distribution network and remote control of selected loads.

8.3.1.1.1 Plant Distribution Network

1. 7200 Volt Network The 7200 volt network is arranged in 5 medium voltage primary bus sections.

There are 2 additional medium voltage bus sections located in the Service Water Pumphouse. Each of these 2 buses is fed as a stub bus from the related ESF primary bus. Each bus consists of a separate, metal clad type, dead front construction, rated 7.2 kV nominal (8.25 kV max) volt, 500 MVA switchgear assembly. Each circuit breaker cubicle is isolated from the adjacent cubicle by metal barriers. Interrupting ratings for the switchgear breakers are 66 kA momentary, and 41 kA symmetrical at 6.6 kV, or 37.8 kA symmetrical at 7.2 kV (based on the symmetrical rating of 33 kA at 8.25 kV). These interrupting ratings are greater than any of the fault current levels on the various buses. Control power for tripping and closing the switchgear is obtained from the station batteries.

8.3-1 Reformatted October 2020

The 7200 volt buses 1A, 1B, and 1C supply power to non-safety-related auxiliaries.

Each of these 3 buses supplies power to a reactor coolant pump. The normal power source for these buses is the main generator through the unit auxiliary transformer or back feed from the 230 kV bus through the main power transformer and unit auxiliary transformer. Upon tripping of the normal feeder breaker to these bus sections, the balance of plant (non-Class 1E) electrical system is automatically transferred to the emergency auxiliary transformers which are the emergency power sources. This automatic transfer is initiated when the normal feeder is tripped by main and unit transformer lockout relaying, generator differential protection relaying, generator and main transformer backup and field failure relaying, overall backup lockout relaying, and the condition of both the main transformer breaker and the generator breaker open. There is no automatic transfer when a bus over-current condition exists. Provisions are also available for manual transfer, as required.

In addition to the protective relays discussed above, there are 3 undervoltage sensing relays (1 for each phase) and 1 underfrequency sensing relay connected for each reactor coolant pump. These devices provide the reactor coolant pump undervoltage trip signal described in Section 7.2.1.1.2, Item 4.b, and the reactor coolant pump underfrequency trip signal described in Section 7.2.1.1.2, Item 4.c.

These relays, together with the potential transformers from which they receive a voltage signal, are located in the reactor protection undervoltage and underfrequency relay panel. This panel is housed in the Seismic Category 1 Intermediate Building. Power feeds to the reactor coolant pumps are routed through this panel. Therefore, the voltage signal is sensed on the pump side of the supply circuit breaker.

To satisfy the single failure criteria, the panel is constructed in 3 sections, 1 section for each of the 3 reactor coolant pump power circuits. Each section is physically isolated from adjacent sections by a double, metal side sheet barrier. Any terminal blocks or fuse blocks mounted on a barrier side sheet are mounted on a polyester glass material. Polyester glass material is also placed under any wiring on a barrier side sheet. Thus, complete isolation of power cables, potential transformers and relays for each pump is maintained within the panel. The panel has been qualified to satisfy the requirements of IEEE-323[11] and IEEE-344[12].

Electrical separation of circuits associated with the reactor protection inputs is in accordance with the criteria outlined in Section 8.3.1.4.

8.3-2 Reformatted October 2020

The 7200 volt buses 1DA and 1DB supply power to the ESF equipment. These ESF buses provide an adequate and reliable source of electrical power for safe reactor shutdown under conditions resulting from any design basis event and/or during loss of offsite power, as well as for all modes of normal station operation.

The normal and preferred power source for bus 1DA is the emergency auxiliary transformer XTF-4 in conjunction with the voltage regulator XTF-6. In the event that the voltage regulator is out of service, either or both of the 2 emergency auxiliary transformers, XTF-4 and XTF-5, can be used to supply bus 1DA. When the voltage regulator is out of service, parallel operation of the 2 transformers is preferred since it provides more flexibility and a greater range of allowable offsite voltage for the 115 kV system. The normal and preferred power source for bus 1DB is also the backup power supply for 1DA. In addition to the normal power sources, each 7200 volt ESF bus has an onsite emergency power source. The RN AAC source ties into the same plant bus (1DX) as the ESF transformers.07-001 The physical layout of the cable bus system for connecting the 2 power transformers (emergency auxiliary and safeguard transformers) and the voltage regulator or the AAC source to the 7.2 kV ESF buses is shown by Figures 8.3-0 RN 07-001 through 8.3-0g. Figure 8.3-0b.1 shows the modifications to the bus shown in RN Figure 8.3-0b for the addition of the voltage regulator and its by-pass switches.98-112 RN Each onsite power source is capable of carrying the total ESF load required for 18-019 safe shutdown. The onsite standby power system consists of 2 fully equipped diesel generators which provide 7200 volt power to buses 1DA and 1DB, RN respectively, within 10.25 seconds after detection of a loss of the associated 98-091 preferred power sources by loss of voltage relays and 13 seconds after detection of a degraded voltage condition. Buses 1DA and 1DB are provided with a manually initiated transfer to the alternate offsite power source.

Transfer switches are used to select power from 7.2 kV Channel A or Channel B sources for the C pump motors in the Service Water, Component Cooling and Safety Injection Systems. The switches are manually operated locally and are equipped with Kirk key interlock to prevent simultaneous closure of circuit breakers from both sources.

Speed switches are used to control the 2 speed, single winding motors used for the 3 component cooling water pumps.

8.3-3 Reformatted October 2020

2. 480 Volt Network The 480 volt network distributes and controls power for all 480 volt and 120 volt a-c RN station demands. This network consists of 22 unit substations and 28 motor 99-005 control centers. The unit substation switchgear is of metal clad, dead front construction, with 125 volt d-c operated air circuit breakers. Transformers for the 480 volt unit substations are air cooled and are directly connected to the switchgear. Except in special cases, motors rated above 50 hp to 350 hp are controlled directly by circuit breakers in the 480 volt switchgear. Motor control centers are used for control of motors 50 hp and smaller.

The maximum symmetrical interrupting capacity of the 480 volt motor control centers is 22,000 amperes. This interrupting capacity is greater than any of the fault levels on the motor control center buses. Current limiting reactors are provided in series with selected non-Class 1E motor control centers where the maximum symmetrical fault current that could otherwise occur at the motor control center would have exceeded 22,000 Amperes.

The maximum symmetrical interrupting capacity of the 480 volt unit substations is dependent upon the frame size of individual unit substation cubicles. In each case the interrupting capacity of a cubicle exceeds the maximum symmetrical fault current. Frame size rating and capacity is listed in Table 8.3-2.

a. Balance of Plant 480 Volt Network The balance of plant 480 volt network consists of 18 unit substations and 18 motor control centers. Fifteen (15) of the unit substations are 4 wire, consisting of transformers and metal clad switchgear; 3 are 3 wire, consisting of transformers and power distribution panels. The 3 wire 480 volt unit substations provide power to the pressurizer heaters. Two (2) of these unit substations are connected to redundant safety-related (Class 1E) buses.

These are loaded manually from the 7.2 Kv diesel generator buses 1DA and 1DB and furnish power to the 2 groups of heaters designated as backup groups. The third unit substation is connected to a balance-of-plant bus (1C) which powers the control group of heaters which are the normally energized heaters. Main feeder breakers for the 2 backup groups have been qualified in accordance with safety-grade equipment. Safety class heater cables and trays are protected by jet spray shields in the event of a PRT diaphragm rupture. Procedures for energizing the pressurizer heaters are addressed in Emergency Operating Procedures and System Operating Procedures as appropriate. These procedures describe (1) precautions to be observed if pressurizer heaters are to be used to prevent overloading diesel generators, (2) suggested loads to trim, (3) the time required to accomplish the connection. This time shall be consistent with the timely initiation and maintenance of natural circulation conditions. This meets the requirements of 8.3-4 Reformatted October 2020

NUREG-0578, Section 2.1.1, Position 3.1. All motor control centers are fed by 4 wire unit substations. The unit substations receive power from 7200 volt balance of plant buses 1A, 1B, and 1C through 7200 - 480/277 volt transformers. Each motor control center has a separate feed from the 480 volt unit substations. Selected motor control centers are provided with automatic transfer to an alternate power source.

b. Engineered Safety Features 480 Volt Network The ESF 480 volt network consists of 6 unit substations and 9 motor control centers. The 480 volt ESF buses are fed through transformers with 7200 volt primaries and 480/277 volt secondaries which feed motor control centers, motors, and miscellaneous loads. These buses are independent from each other and there is neither automatic nor manual transfer capability. ESF 7200 - 480/277 volt transformers and switchgear are redundant and are located in separate areas of Seismic Category 1 structures to maintain isolation. ESF motor control centers are powered from the 480 volt ESF buses and have neither manual nor automatic transfer capability. The motor control centers are redundant and are located in separate areas of Seismic Category 1 structures or are separated by fire walls to maintain isolation.

Under loss of offsite power conditions, power may be supplied to selected non-Class 1E 480 volt buses by the diesel generators. Equipment which is not safety-related but is considered essential for protection of the turbine or desired for convenience is manually activated by the operators.

The voltage fluctuates on the preferred sources within the limits defined in Table 8.2-2, as described in Section 8.2.1. Appendix 8D discusses the analytical method used for determining the optimum tap settings for the step down transformers in the plant distribution network. Also, included in the appendix is a tabulation of, or a referenced RN calculation for, the calculated voltages at the 7.2 kV and 480 volt distribution levels in 99-087 the plant during light and accident load conditions with power being supplied from the offsite sources. The voltage fluctuation will be less than those given in Appendix 8E RN 99-007 during diesel generator operation as the diesels output is held to approximately + 0.5%

of the voltage regulators setting, and the regulator is set within the range of + 2%, - 5%

of 7.2 kV. The light and accident condition loads were determined to be the worst case loads. The results indicate that with the design tap settings the motors terminal voltages will remain within the design limits of +/- 10% of their rated voltages for the anticipated range of transmission system voltages.

If a degraded voltage occurs, with the established relay setting, the lowest voltage which could exist at a motor terminal is 90.0% of rated voltage (460 volts) and at a RN 98-061 motor control center bus is 87.71% of rated voltage (480 Volts).

8.3-5 Reformatted October 2020

When the plant is at the startup stage and the design tap settings have been applied to the step down transformers, the voltages on the buses will be verified to ensure that they are not out of the range for proper equipment operation. Prior to fuel loading when the loads on the distribution system reflects the values to be expected during plant operation, the voltages and loads of the ESF system buses will be measured and the data used to verify the calculation of voltage levels. Appendix 8D discusses the calculation procedures and method of this verification of the calculation. Results were provided in a March 1, 1982 letter to the NRC. As part of the results, a tolerance study will be made and presented to show that the variations between the measured and calculated values are within the expected ranges.

The voltages on the buses are monitored during plant operation and recorded as part of RN 99-146 operator logs to verify the proper range for equipment operation.

No load break, 480 volt a-c transfer switches are used to transfer power from 480 volt channel A or channel B sources for the motors for HVAC water chiller C and chilled water pump C. These switches are equipped with a walking beam interlock to prevent simultaneous closure of circuit breakers from both sources.

8.3.1.1.2 Onsite Standby Power Supplies The onsite standby a-c power supplies for Virgil C. Summer Nuclear Station are 2, 12 cylinder, V configuration diesel engine driven generator sets. The generators operate at 514 rpm and provide 3 phase, 60 Hz, 7200 volt power. Each diesel generator has the following ratings:

1. Continuous, 4250 kW.
2. Short time, 4676 kW.
3. Overload (2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />), 4548 kW.
4. Seven (7) days, 4676 kW.
5. Thirty (30) minutes, 5100 kW.

The diesel generators are located in a building designed to satisfy Seismic Category 1 requirements and to protect the diesel generators against tornadoes, hurricanes and missiles. Within this building, the diesel generators, including associated starting equipment and other auxiliaries, are completely isolated from one another by a wall designed to withstand a safe shutdown earthquake (SSE).

8.3-6 Reformatted October 2020

Each diesel generator is provided with a separate, missile protected combustion air intake as shown by Figure 1.2-13 and a separate air discharge and engine exhaust.

The diesel generators, together with associated fuel storage tanks, auxiliaries and related piping are designed to remain functional during an SSE and remain in a condition suitable for the performance of their function in shutting down and maintaining the plant in a safe condition.

Essential subsystems for each of the diesel generators and the physical arrangement of these subsystems are discussed in Sections 9.5.4 through 9.5.8.

8.3.1.1.2.1 Deleted by Amendment 98-01, April 1998 8.3.1.1.2.2 Deleted by Amendment 98-01, April 1998 RN 97-025 8.3.1.1.2.3 Deleted by Amendment 98-01, April 1998 8.3.1.1.2.4 Diesel Generator Operation Each 7200 volt ESF bus is continually energized from either the 230 kV or the 115 kV preferred power source transformer or from the onsite emergency diesel generators, as shown by Figures 8.2-2 and 8.2-3. The transfer from preferred power source to emergency diesel generator is accomplished automatically, when required, by the opening of the preferred power source air circuit breakers and closing of the emergency diesel generator air circuit breaker. The emergency buses and power supplies for all essential components are normally connected to the preferred offsite power sources.

The emergency diesel generators are automatically started upon receipt of an undervoltage signal from the associated bus from either the loss of voltage relays or degraded voltage relays, or upon receipt of a safety injection signal. They are also started upon receipt of a manually initiated signal from the control room. Loss of voltage on an ESF bus opens the normal or alternate supply circuit breaker (whichever is closed) and, when emergency diesel generator voltage and frequency are established, closes the emergency power source circuit breaker. In the case of a safety injection signal and/or ESF bus undervoltage, the ESF loading sequencer (see Section 7.3.1 for a detailed discussion) trips selected bus loads including all non-Class 1E loads. The bus is then reloaded in the sequence shown in Table 8.3-3, Parts A1 and B1. Items indicated by 0 second loading sequence in Table 8.3-3 are not tripped and, therefore, are immediately loaded when the emergency power source circuit breaker is closed. All other required loads are loaded in sequence by the ESF loading sequencer.

8.3-7 Reformatted October 2020

The 7.2 Kv ESF buses are each provided with 3 loss of voltage relays set at approximately 81% of the nominal bus voltage level and 3 degraded voltage relays set at approximately 91.34% of the nominal bus voltage level. Operation of a set of loss of voltage or degraded voltage relays will initiate a diesel generator start, a permissive for EFW turbine pump start, an ESF load sequence operation and a permissive for diesel generator circuit breaker close. These operations occur in a timed sequence as outlined in Table 8.3-5. The logic of the controls are illustrated in Figure 8.3-0o.

As illustrated in Table 8.3-5 the 7.2 Kv bus circuit breakers are tripped 4 seconds after the diesel generator is started on a degraded voltage condition as compared to 2 seconds for a loss of voltage condition. The delay in tripping for a degraded voltage condition allows the bus to be energized during the time the diesel generator is coming up to speed. Therefore, with the degraded voltage condition, the maximum dead bus time is 6 seconds as compared to a 10.25 seconds dead bus time allowed for a loss of voltage condition.

Appendix 8F provides a discussion of the time sequence of equipment operation with a degraded voltage condition coincident with an accident condition. When the diesel generators are started and loaded as a result of an undervoltage condition, the ESF loading sequencer logic prevents further undervoltage tripping of the safety related loads. When the buses are returned to the offsite power sources, the undervoltage tripping feature is automatically reinstated.

The emergency diesel generators and normal station service are synchronized only during periodic testing. Synchronizing capability is provided to reconnect the emergency diesel generators to the offsite power network when voltage is restored subsequent to the loss of offsite power. Synchronization is performed manually, when required. ESF equipment is duplicated on separate 7200 volt and 480 volt (as appropriate) buses as listed in Table 8.3-3, Parts A1 and B1. All equipment does not start simultaneously but is programmed to start automatically in sequenced steps. The first group, indicated by 0 load sequence seconds in Table 8.3-3, Parts A1 and B1, is connected to the ESF buses when the buses are energized. During recovery from step load increase, or from disconnection of the complete load, emergency diesel generator speed change will not exceed 75% of the difference between nominal speed and the overspeed trip setpoint or 115% of nominal speed, whichever is lower. Voltage is restored to within 10% and frequency to within 2% of the nominal values in less than 40% of each load sequence time interval. This complies with Regulatory Guide 1.9 (see Appendix 3A). Subsequent groups are each connected in sequence after short time delays.

8.3-8 Reformatted October 2020

The load profile after an accident, without offsite power, is generally outlined by Table 8.3-3, Parts A1 and B1. At no time following an accident will the load exceed the short time rating (110% of the continuous rating) of the diesel generators nor is it expected that the load will fall below 30% of the diesel generator rating.

In the event of an accident with offsite power available, the diesel generators will start and run at no load. Should a subsequent loss of offsite power occur, the diesel generators would be loaded automatically. If offsite power is not subsequently lost, the diesel generators would continue to run at no load until manually stopped by the operator.

The injection phase of a loss of coolant accident should not exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and the short term phase of a main steam line break accident is estimated to be 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Therefore, it is expected that both diesel generators can be stopped within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after an accident if offsite power is available. If the diesel generators are operated at no load or less than 20% load for a period of time longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, operating procedures will require paralleling of each machine with the bus and loading the generator to at least 50% of rated load. Only 1 diesel generator will be paralleled with a bus at a time.

Criteria discussed are conservative with respect to the manufacturers recommendations (see Colt Industries, Fairbanks Morse Engine Division, "Operating and Maintenance Manual, South Carolina Electric and Gas Co., Virgil C. Summer Nuclear Station - Unit 1, Standby Diesel Generator Set," Colt-13-206152, Chapter 1, RN 97-085 Tab 1, page 5-1) which, in part, are as follows:

"In the event it is necessary to operate the engine for extended periods of time RN (over 24 hrs.) at from no load up to 20% of the engine rating, the engine should run 98-061 at above 50% load for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in each 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period in order to minimize RN the accumulation of products of combustion and lubricating products in the exhaust 97-085 systems. Above 20% load rating, the engine may run continuously as required with the recommendation that the engine parameters be monitored closely and RN 98-061 logged at least daily so as to be able to discover any problems early. (Changes in exhaust temperatures are of particular interest.)"

8.3.1.1.2.5 Diesel Generator Permissives After the emergency diesel generator has received a starting signal, the following conditions must be satisfied before the generator is automatically connected to the ESF bus:

1. The diesel generator must be at approximately 90% of rated voltage and approximately 98% of rated frequency, based upon 2 out of 3 relaying schemes in each case.

8.3-9 Reformatted October 2020

2. The ESF bus normal and alternate power supply circuit breakers must be open.
3. There must be no electrical faults in the 7200 volt bus.

RN Figures 8.3-0h through 8.3-0j present diesel generator logic diagrams. Logic diagrams97-085 for the bus 1DA normal and alternate power supply circuit breakers are shown by Figures 8.3-0K and 8.3-0l. The bus 1DB normal and alternate supply circuit breakers use similar control schemes.

8.3.1.1.2.6 Diesel Generator Testing The diesel generators are tested as follows at the manufacturers plant prior to shipment to the plant site:

1. The diesel generators are initially started and run in accordance with the manufacturers standard procedure which includes the following:
a. Operation at reduced RPM for approximately 50 minutes.
b. Operation at rated RPM and variable load for approximately 6-1/2 hours.
2. The engine overspeed setting is tested and operation at 115% overspeed is demonstrated.
3. Diesel generator starting system capacity is demonstrated.
4. Diesel generator speed governing system is tested for steady state and transient performance, including load rejection tests at 25, 50, 75, and 100% of rated load.
5. The diesel generators are started and automatically loaded with a combination of resistive and inductive loads to simulate design loading conditions for the Virgil C.

Summer Nuclear Station. This test is performed 10 times on each diesel generator.

6. The ability of the diesel generators to start and accept load without service water flow and without 480 volt auxiliary power is demonstrated.
7. The starting margin of each diesel generator is demonstrated by simultaneously starting and accelerating a 1750 horsepower motor and a 500 horsepower motor with the generator carrying a resistive load of approximately 50% of rated capacity.
8. Operation of the diesel generator in parallel with a utility system is demonstrated.

8.3-10 Reformatted October 2020

9. The diesel generators are operated at variable load for a total of 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />, including 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> at 100% of rated load followed by 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 110% of rated load.

Certified evidence is supplied by the manufacturer of the diesel generators that a total of 300 start and load tests, with a maximum of 3 failures, have been performed on a diesel generator of the design supplied for Virgil C. Summer Nuclear Station.

Each start and load test consisted of starting the diesel generator and applying load RN within 10 seconds after the start signal, increasing load to at least 50% of the 01-113 continuous rating within 30 seconds and operating under load for a minimum of 5 minutes.

Some of these tests are initiated from design cold ambient conditions (keep warm temperatures) and some from hot equilibrium temperature conditions.

Tests and inspections are performed to ensure that all components are properly mounted, connections are correct, circuits are continuous and components are operational. Tests are performed to ensure that emergency loads do not exceed diesel generator rating and that each diesel generator is suitable for starting and operating required loads.

Proper operation of the onsite standby power supply is tested periodically. An availability test is performed periodically when the plant is in operation. Only 1 diesel generator is tested at a given time. The test consists of a manually initiated start of the diesel generator, followed by manual synchronization with and connection to the station ESF buses and assumption of load by the diesel generators. Normal station operation is not affected by this test. The operational test, automatic starting, load shedding and loading of the diesel generators, initiated by a simulated loss of voltage on the ESF buses are performed normally during reactor shutdown for refueling. Preoperational testing according to Regulatory Guide 1.41 is discussed in Chapter 14 and Appendix 3A.

RN 8.3.1.1.2.7 Deleted by Amendment 98-01, April 1998 97-085 8.3.1.1.2.8 Instrumentation and Control Systems Control power required for operation of each diesel generator is supplied from the 125 volt d-c distribution system. Control power for the diesel generator breaker to the ESF bus is supplied from the 125 volt d-c distribution system associated with the corresponding ESF bus. Controls are provided locally and in the control room for manual start and stop of each diesel generator. An automatic control system is provided for automatic startup and adjustment of speed and voltage to a ready-to-load condition.

8.3-11 Reformatted October 2020

A start diesel signal overrides all other operating modes and immediately returns the controls for the diesel generator to the emergency mode except under the following conditions:

1. Engine tripped due to overspeed.
2. Engine tripped due to low lube oil pressure.
3. Generator tripped due to generator differential relay operation.
4. When maintenance is in progress.

A matrix arrangement is provided for tripping the diesel generator for low lube oil pressure. This matrix consists of 4 pressure relays set at 70, 65, 60, and 60 psi. To cause a diesel generator trip due to low lube oil pressure, 2 of the low pressure switches must be activated and at least 1 of the 2 activated switches must be 1 of the 2 with 60 psi setpoints.

The other protective functions for the diesel generator are able to cause a diesel generator trip only during testing. Under emergency conditions, these protective functions actuate alarms only and do not trip the diesel generator.

Table 8.3-3a is a list of the protective devices provided for the diesel generators. This list also includes the function of these devices under emergency start and test start conditions.

Also, the engine manual stop pushbutton cannot override an ESF signal.

Instrumentation is provided locally and in the control room to monitor diesel generator frequency, voltage, loading and circuit breaker position.

Alarms are provided locally for all critical variables and trip functions as shown in Figure 8.3-0n. The local annunciator provides "first out" indication to aid in determining the cause of any trips or malfunctions. Alarms and status indication are also provided in the control room as shown in Figure 8.3-0m to indicate diesel generator status and permit remote operation of the diesel generators.

Most of the instrumentation is designed and installed to permit inplace calibration.

Logic diagrams for the diesel generator starting and shutdown controls are presented by Figures 8.3-0h and 8.3-0i.

8.3-12 Reformatted October 2020

8.3.1.1.2.9 Diesel Generator Environment Combustion air for the diesel generators is taken directly from the outside through an intake which is completely independent of the ventilation air intake. The bottom of the ventilation air intake is located 29 feet above grade, as shown in the Figures 1.2-13 and 1.2-14. This high elevation will minimize the amount of dust taken in by the ventilation system. In addition, all cabinets containing control relays and associated devices have gasketed doors and openings. Therefore, the ventilation system will introduce a minimum of dust into the building and the controls are protected from whatever dust does enter the building.

There are several elements which interact to assure the cleanliness of the Diesel Generator Room and the supportive electronic and electrical components contained therein. They are as follows:

1. All electrical and electric component cabinets are weather sealed with rubber gaskets and have filtering media provided where air is circulated through the cabinets.

RN 98-133

2. The Diesel Generator Building is to be designated as a Cleanliness Zone IV, which requires periodic inspections, specifically for cleanliness.
3. The mandatory surveillances for assuring the diesels ability to start are supported RN 99-142 by a periodic preventive maintenance task which requires inspection of the electrical and electronic components to determine operability and condition.

Cleanliness is one of the areas that is inspected during the performance of the preventive maintenance task.

8.3.1.1.3 120 Volt A-C Vital Bus System Six (6) 120 volt a-c vital buses are provided. Each of 4 buses is supplied by 1 of 4 single phase static inverters. The normal feed to Panel APN5907 is from APN5901.

The normal feed to Panel APN5908 is from APN 5903.

One (1) Channel A and 1 Channel D inverters are connected to ESF battery 1A, and 1 Channel B and 1 Channel E inverters are connected to ESF battery 1B.

The 120 volt a-c vital buses constitute a reliable electrical system which provides a stable power supply to vital equipment and guarantees proper action when power is required while eliminating spurious shutdowns. Controls for the backup groups of heaters, the pressurizer level transmitters and for the pressurizer relief block valve operators receive their power from this vital a-c bus source through the emergency power buses. The control power for the block valves is supplied from an emergency power bus different from that which supplies the associated PORV. Safety grade circuit breakers and fuses are used for circuit protection.

8.3-13 Reformatted October 2020

The normal source of power for the 120 volt a-c vital bus inverters is through the inverter static rectifier. These inverter rectifiers are fed from 480 volt buses 1DA2 and 1DB2. The station batteries and battery chargers constitute the standby power source.

The battery chargers are fed from 480 volt buses 1DA2 and 1DB2. In the event of loss of 480 volt power, the power source for the vital bus inverters is the station batteries.

These batteries are floating, on standby service. The change in power source, from normal to standby, occurs without exceeding the stated inverter output voltage and frequency regulation. The station batteries are sized to carry this additional inverter RN load without being charged for no less than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The battery chargers are sized to 98-100 recharge from a design minimum charge to full charge in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while carrying the largest combined demand from the various steady-state loads.

An alternate power supply for the 120 volt a-c vital buses is provided through 480-120 volt transformers from 480 volt buses 1DA2 and 1DB2 for use when the inverters are out of service.

8.3.1.1.4 Equipment Criteria

1. Motor Size The criterion for motor size is that the motor develops sufficient horsepower to drive the mechanical load under maximum expected flow and pressure. Motors are sized to permit the driven equipment to develop its specified capacity without exceeding the temperature rise rating of the motor when operated at the duty cycle of the driven equipment. Motors are furnished with service factors ranging from 1.0 to 1.15. The service factor is a ratio of the safe load to the nameplate load and identifies the margin available for motor operation under overload conditions.

RN When a motor is furnished with a service factor greater than 1.0, it is the design 99-002 intent to size the motor to handle the normal operating requirements of the driven equipment without taking credit for the service factor. Motor size is determined based on the driven equipment load characteristics.

2. Engineered Safety Features Motor Starting Torque Motors are designed for across the line starting. ESF motors rated 6900 volts are capable of accelerating the driven equipment to rated speed at 70% of the motor nameplate voltage. ESF motors rated 460 volts are capable of accelerating the driven equipment to rated speed at 80% of rated voltage. The motors are RN designed to operate at +/- 10% of rated voltage, +/- 5% of rated frequency or a 01-113 combined variation in voltage and frequency of +/- 10% of absolute values, provided that frequency variation does not exceed +/- 5% of rated frequency.

8.3-14 Reformatted October 2020

Calculations based on the diesel generator factory test data indicate that the motor terminal voltage during starting will not go below 90% of the rated voltage for 6,900 RN volt motors or below 82% for 460 volt motors. The motor terminal voltage for the 99-080 6900 volt motors was calculated using the diesel generator voltage regulation for starting of a 1750 Hp motor. The motor terminal voltage for the 460 volt motors was calculated using the diesel generator voltage regulation for starting a 500 Hp motor and considering the voltage drop through the 7200/480 volt transformers.

The actual largest system motors are 900 Hp and 350 Hp for the 7200 volt and 480 volt systems respectively (Refer to Appendix 8E). These voltage levels are well RN 99-080 above those allowed by Regulatory Guide 1.9. The adequacy of bus voltage regulation during motor starting is confirmed during the preoperational testing program.

3. Motor Insulation Motor insulation is a minimum of Class B outside the Reactor Building and Class F inside the Reactor Building. The insulation temperature rating is greater than the sum of the motor temperature rise and the ambient temperature at the motor location.

Service life is extended when necessary by 1, or a combination, of the following methods:

a. Derating - use of a larger motor than required by the motor sizing criteria previously discussed.
b. Insulation type - use of motor insulation with a higher temperature limit than specified for the operating conditions (e.g., specifying Class F insulation to Class B temperature limitations).
c. Service factor - motors with 1.15 service factor are operated under normal conditions without encroaching upon the service factor.
4. Engineered Safety Features Motor Temperature Protection ESF motors rated 6900 volts and 600 hp and larger are provided with 6 stator RN winding embedded, resistance type, 10 ohm, copper at 25°C, resistance 99-079 temperature detectors (RTDs). Smaller horsepower motors are not equipped with stator RTDs due to the problems involved in embedding them in the stator. The exceptions are the 400 hp reactor building spray pump motors which do have stator RTDs.

8.3-15 Reformatted October 2020

Motors rated 6900 volts and selected 460 volt motors are provided with bearing thermocouples. Outputs from each of the 2 motor temperature measuring devices are routed to the plant computer which actuates an alarm and provides a printed output if the stator RTD or bearing thermocouple measured value exceeds a predetermined setpoint.

5. Interrupting Capacity Switchgear, unit substations, motor control centers and distribution panels are sized for interrupting capacity greater than the maximum short circuit availability at their location. The calculations to document this application take into account the fault contributions of all rotating machines and source transformers. Source impedances are selected to ensure adequate starting voltage for all motors and to limit short circuit currents at unit substation buses and motor control center buses.
6. Network Protection Each major motor or other major item of electrical equipment is protected by overcurrent relays that disconnect the equipment if the load current becomes excessive. Prior to plant operation protective relays are set and calibrated.

Availability and proper operation of standby equipment are periodically tested during normal operation.

The protection philosophy for the 7200 volt and 480 volt systems is based upon the following considerations:

a. A faulted piece of equipment is cleared by isolating the smallest possible portion of the system.
b. A faulted piece of equipment is cleared in the minimum possible time to reduce damage to that equipment and limit the stress on the remainder of the system.
c. Protective devices are selected and set for fault sensing and overload RN sensing as required for applicable system/component protection.99-002 8.3-16 Reformatted October 2020
d. Motor control centers that serve loads located inside the Reactor Building typically have starters, (with thermal overloads) magnetic molded case circuit breakers, and a current limiting circuit breaker in series. The current limiting circuit breakers have thermal and magnetic elements incorporated in their protection circuit. Loads that do not require a starter, that use a contactor without overload protection, or have overloads bypassed under accident conditions, or are mentioned in Section 8.3.1.4.1; have an additional thermal element provided in the molded case circuit breaker. This arrangement provides primary and backup protection in compliance with Regulatory Guide 1.63 (see Appendix 3A).
e. Overload elements provided for safety-related valve operators are bypassed under accident conditions by the safety injection signal contact that initiates the valve operation. This is in compliance with Regulatory Guide 1.106 (see Appendix 3A).
7. Grounding Requirements Design criteria for grounding of safety-related systems are as follows:
a. All equipment hardware, exposed surfaces and potential induced voltage hazards are adequately grounded to assure that no danger to plant personnel exists.
b. A low impedance ground return path is provided to facilitate the operation of ground fault detection or protective devices in the event of ground fault or insulation failure on any electrical load or circuit.

The following are the methods for grounding electrical equipment:

a. A ground wire is connected to the equipment frame and the ground grid. The ground wire is run through the equipment conduit or lashed to the power cable for the equipment where no conduit is provided. The wire is either connected directly to the ground grid or to other equipment, such as a cable tray which is connected to the grounding grid.
b. Where conduit is used as the grounding path, the conduit is connected to the equipment and the grounding grid. The connection to the grounding grid is either a direct connection or is connected to other equipment such as a cable tray which is connected to the grounding grid.

8.3-17 Reformatted October 2020

The cable tray system is solidly grounded. Ground connections are made to the station grounding grid or building steel work, which is connected to the station grounding grid.

The station grounding grid is designed to maintain the station area at an effective ground potential during a worst case ground fault in any installed electrical equipment, including transmission facilities and unit main generators, as well as lightning effects. An effective ground is considered to be the maintenance of voltage potentials below a "safe touch" level for plant personnel.

8. Maintenance Program A maintenance program, in accordance with the recommendations of the manufacturers, is followed. This program includes periodic visual inspection and lubrication for each motor. A record is maintained for each motor indicating the date when each action is performed.
9. Starter Voltages Starter coils for motor control centers are designed to pull in at 85% of rated voltage and to hold in at 65% of rated voltage. The coils are energized through a 480/120 volt instrument transformer.
10. Heat tracing is provided for Nuclear Safety Related and Non-Nuclear Safety Related equipment, piping, and/or tubing for the purpose of process temperature maintenance and freeze protection of liquids and for prevention of condensation in instrument air lines.

The heat tracing equipment protecting Safety Related systems (i.e., reactor makeup RN 99-070 water storage tank and piping, refueling water storage tank and piping, and sodium hydroxide) includes redundant centralized control panels, temperature measuring equipment, wiring and conduit, and heat tracing cables, except for the refueling water storage tank and reactor makeup water storage tank. These tanks are monitored by redundant temperature instrumentation and are provided with 1 set of heat tracing each. Based upon the thermal capacity and insulated design of these tanks, the redundant instrumentation provides adequate operator control to prevent freezing. The centralized control panels provide power distribution, control and alarm functions from signals received from temperature measuring equipment attached to the piping systems. The primary and redundant heat trace circuits are each designed with the capability to provide the necessary freeze protection, or RN 99-070 maintain the necessary process temperature. In the event of a failure to the primary heat trace circuit, the redundant heat trace circuit provides the necessary heat trace function. The heat tracing cables are of the parallel self-limiting type. The centralized control panels are powered from Class 1E Channel A and Channel B motor control centers. Alarms are transmitted to the control room from a local annunciator panel.

8.3-18 Reformatted October 2020

8.3.1.2 Analysis 8.3.1.2.1 Compliance Analysis The basic design criteria are that the Class 1E electric power systems satisfy the single failure criterion and Regulatory Guide 1.32 (see Appendix 3A). The safety-related loads are assigned to 2 independent, separate 7200 volt ESF buses. Either of these buses is capable of supplying required ESF or shutdown loads. Each of these buses is continuously energized from the preferred source ESF transformer(s), 1 set of windings in emergency auxiliary transformer (XTF-31), or from 1 of the diesel generators. Each 7200 volt ESF bus serves as a power source for the safety-related loads on the 480 volt buses and for equipment which is not safety-related but is considered essential for protection of the turbine or desired for convenience. This design, including the ties to the non-ESF buses, satisfies the independence and redundancy requirements of Regulatory Guide 1.6 (see Appendix 3A) and General Design Criterion 17.

The main control board is provided with indicators to monitor the ESF bus operating levels. A voltmeter, ammeter, wattmeter, varmeter and kilowatt hour meter are provided on each of the incoming, preferred power sources. The onsite power source has a voltmeter, frequency meter, wattmeter and ammeter provided on the main control board to indicate the ESF bus operating levels. Figures 8.2-3 and 8.2-4 indicate the metering provided on the plant electrical system. Table 8.3-3b is a listing of the indicator types associated with the ESF electrical network.

The ESF buses have sufficient redundancy to allow testing of each safety-related item as a system, or in some cases as individual components to comply with General Design Criteria 17 and 18.

Two (2) diesel generators provide onsite power to the 7200 volt ESF buses. Each diesel generator is assigned exclusively to 1 bus and each is automatically started upon a loss of bus voltage, degradation of bus voltage or receipt of a safety injection actuation signal. Under conditions outlined in Section 7.3.1, normal loads, with the exception of the group indicated by 0 seconds in Table 8.3-3 Parts A1 and B1, are RN 97-085 disconnected and the ESF loads are automatically loaded in sequence on each diesel generator in accordance with the sequence presented in Table 8.3-3.

If a loss of preferred power is not concurrent with a postulated accident, certain ESF equipment is not required. Under these conditions, other plant auxiliary equipment may be manually operated. Safety injection loads are sequenced on by the load sequencer in this case, but loads are not disconnected prior to the sequencing. Instrumentation is provided to indicate emergency diesel generator loading.

8.3-19 Reformatted October 2020

The onsite standby power supply complies with Regulatory Guide 1.9, including load limits, (see Appendix 3A). The diesel generators have a continuous rating of 4250 kw, a RN short time rating of 4676 kw for up to 7 days, and a 30 minute rating of 5100 kw. The 98-024 limiting accident load is calculated to be 4390 kw and the maximum load under loss of offsite power conditions is calculated to be 4920 kw. These short time and continuous rating loads are verified by test during each periodically. (The largest bus connected UCR 2020-022 load is calculated to be approximately 5450 kVA.)

8.3.1.2.2 Hostile Environments 8.3.1.2.2.1 Equipment Identification The most severe environmental conditions expected to be imposed upon the equipment which would operate inside and outside the Reactor Building during normal operation and subsequent to a LOCA or main steam line break are presented in Section 3.11.

Regulatory Guide 1.89 is discussed in Appendix 3A.

8.3.1.2.2.2 Loss of Ventilation To ensure that loss of the air conditioning and/or ventilation systems does not adversely affect the operability of safety-related control and electrical equipment located throughout the plant, the environmental systems for these areas satisfy the single failure criterion. Section 9.4 presents a detailed discussion of ventilation systems. Section 3.11.4 discusses loss of ventilation.

8.3.1.2.2.3 Qualification Tests See Section 3.11 for a discussion of the hostile environment for which electrical equipment is procured and the maximum DBA environmental conditions to which it may be subjected.

8.3.1.3 Conformance with Appropriate Quality Assurance Standards The quality assurance procedures used during equipment design, fabrication, shipment, field storage, field installation and system and component checkout and the records pertaining to each of these during the construction and preoperational test phases are described in Chapter 17.

The Quality Assurance Program, as discussed in Chapter 17, is in conformance with IEEE-336[1].

8.3-20 Reformatted October 2020

8.3.1.4 Independence of Redundant Systems 8.3.1.4.1 Criteria for Independence of Redundant Electric Systems The electrical power supply, control and instrument cables for mutually redundant equipment are physically separated to preserve the redundancy and to ensure that no single, credible event will prevent operation of the associated function because of electrical conductor damage. Critical circuits and functions include power, control and instrumentation associated with reactor protection, ESF and reactor shutdown. Credible events include, but are not limited to, the effects of short circuits, pipe ruptures, fires, earthquakes, and missiles. The minimum electrical separation required for protection against design basis accidents is included in the basic plant design.

The separation of electrical circuits has been reviewed to the criteria of IEEE 384[14] as RN modified by Regulatory Guide 1.75 (see Appendix 3A). The plant design complies with 99-037 these criteria as described below:

1. Redundant Class 1E circuits are run in separate and independent raceways. In general plant areas, not subject to hazards, such as missiles, open ventilated cable trays for redundant circuits are separated by a minimum of 3 feet horizontally or 5 feet vertically. In cable spreading rooms open ventilated cable trays are separated by a minimum of 1 foot horizontally or 3 feet vertically. Totally enclosed raceways for redundant circuits are separated by a minimum of 1 inch. Where these separation criteria cannot be satisfied, suitable barriers are placed between the raceways. The design of these barriers is described in Appendix 8B.
2. In areas where redundant circuits are exposed to hazards, such as missiles, the minimum spacing between mutually redundant wireways is 20 feet. Where this spacing cannot be achieved, a suitable missile proof barrier is used to ensure that no common hazard could render more than 1 mutually redundant circuit inoperative. Barriers have been provided to protect trays for Class 1E circuits from the effects of jet impingement and piping is restrained to prevent pipe whip as described in Section 3.6.
3. Where non-Class 1E circuits are connected to Class 1E equipment or are routed in the same raceways with Class 1E circuits, they are designated as associated circuits. Circuits designated as associated are routed with the designated separation channel throughout their length. Where non-Class 1E circuits are connected to Class 1E equipment, an isolation device is provided to protect the Class 1E equipment. These isolation devices are further discussed in Appendix 3A under the discussion of Regulatory Guide 1.75.

8.3-21 Reformatted October 2020

4. Non-Class 1E circuits are routed in raceways independent from the raceways for Class 1E circuits. Where the separation between the raceways for non-Class 1E circuits and raceways for Class 1E circuits do not satisfy the criteria for raceways carrying redundant Class 1E circuits, as described in Item 1, above, a case by case analysis has been performed to ensure that adequate separation exists. This analysis reviewed 2 types of violations, single and multiple. Single violations are those in which a non-1E tray violates the minimum separation required at one point along its path. These cases are summarized in Appendix 8C. A multiple violation is defined as a non-Class 1E tray which violates the minimum separation required at 1 point, and then, within the same fire area, the same non-Class 1E tray violates another Class 1E tray which is of a redundant channel to the initial 1E tray. For identified multiple violations in control (4000 series) trays, tray covers have been provided between the non-Class 1E tray and one of the Class 1E trays. The remaining violation is then analyzed as a single violation (Appendix 8C). For power trays (1000, 2000 and 3000 series) which cannot be covered, periodic testing of certain cable protective devices is performed in accordance with a controlled breaker surveillance program. This testing ensures that adequate overcurrent protection exists for the cables in the non-Class 1E trays so that they cannot be a hazard to the Class 1E trays whose separation distance has been violated. The results of the analysis for identified multiple violations are RN summarized in the Fire Barriers Raceway Database.03-018 All 5000 series instrument trays are deemed as acceptable barriers for multiple violations without the use of top hats, Kaowool, or any other fire related enhancements. Because of this, multiple violations in which 1 or more of the trays involved were 5000 series were classified as single or no violations as appropriate.
5. The Class 1E circuits routed to the service water intake structure are installed in underground concrete duct banks. These duct banks are seismic Category 1 structures and, as such, are designed to protect the cables from postulated natural phenomena, including SSE. The layout of the duct banks and associated manholes is illustrated by Figures 8.3-2a through 8.3-2g.
6. Separation of safety-related circuits is maintained in the electrical penetrations of the Reactor Building. Circuits for nuclear and protection instrumentation are not mixed with other type circuits in the same penetration. The redundant circuits for the 4 nuclear and protection instrumentation channels enter containment through penetrations located around the periphery with a minimum horizontal separation of 20 feet, centerline to centerline, between any 2 channels (see Figure 8.3-3).

Physical separation between penetrations containing redundant circuits, other than the 4 nuclear instrument channels, is maintained in accordance with Section 8.3.1.4.3, Item 2.

8.3-22 Reformatted October 2020

The 4 penetrations containing the nuclear and protection instrumentation are provided with metal barriers. The metal barriers are used to separate the nuclear and protection instrumentation.

These barriers are grounded and are arranged to provide an effective electromagnetic shield over the full length of the penetration assembly.

Structural criteria require that penetrations be spaced on minimum horizontal and vertical centerlines as shown by Figure 8.3-3. This provides a 3 foot minimum separation between any electrical penetration and any other type of penetration.

The design objective is to maintain maximum separation between safety related electrical penetrations and any large piping penetrations to minimize mechanical damage from the postulated rupture of steam or water lines. The design objective is also to maintain maximum separation between any safety-related penetrations and large power penetrations, such as those for reactor coolant pump or pressurizer heater power cables. Separation of safety-related electrical penetrations from main steam lines is maintained by a concrete floor or a minimum horizontal distance of 40 feet. One (1) exception is the penetrations for the power feeds to the Channel A Reactor Building cooling unit fans. The main steam lines and cooling unit fan power feeds both penetrate the Reactor Building above the operating floor. A 20 foot minimum separation is maintained between these penetrations. Separation from any other steam, high pressure water or large power electrical penetration is maintained by a concrete floor or by an 8 foot minimum horizontal centerline separation.

7. Cable trays, conduits and cables are marked for ready identification of the channel and to guard against violation of separation. Specific color coding is discussed in Section 8.3.1.5.
8. SP-834, Electrical Construction Guideline for Electrical Circuit Physical UCR Separation, and Electrical Maintenance Procedure EMP-405.012, "Guide for 2020-025 Electrical Physical Separation," identity the minimum separation guidelines for internal wiring and components within control boards, panels, relay racks, etc. A minimum separation distance of 6 inches between redundant components and/or RN 99-002 wiring and between Class 1E and non-Class 1E components and/or wiring within the enclosures is required. Where 6 inches of air separation is not available, a suitable fire barrier is installed or an analysis is performed to demonstrate that the separation distance is adequate. Design exceptions to the separation guidelines UCR are addressed in Attachment 1 to SP-834. 2020-025 8.3-23 Reformatted October 2020

8.3.1.4.2 Compliance with Criteria for Independence of Redundant Electric Systems A discussion of the administrative responsibility and control provided to ensure compliance with the criteria, set forth in Section 8.3.1.4.1, during design and installation is presented in Chapter 17.

8.3.1.4.3 Criteria for Design and Installation of Electrical Cable The recommendations of IEEE Proposed Guide P-422,[3] IEEE STD 384,[14] and RN 99-037 Regulatory Guide 1.75 (see Appendix A) are used, except as modified by Items 1 through 6, below, as the general design criteria for the design of the power, control and instrument cable and cable tray systems related to all Class 1E electrical systems.

1. Power cable capacities are determined using derating factors listed in IPCEA P-46-426,[4] supplemented by IPCEA-NEMA P54-440.[5] Cable derating and cable tray fill are discussed in Section 8.3.3.1.
2. Cable routing in the Reactor Building, penetration areas, cable spreading room, control room, etc., is arranged following the recommendations in IEEE Proposed Guide P-422.[3] Channel separation and cable tray physical separation requirements are maintained in these areas in accordance with Section 8.3.1.4.1, item 6. Cables which must enter areas surrounded by shield walls are routed to minimize the cable length within the shields area.
3. Fire and/or smoke detection equipment is installed in areas of heavy cable concentration, as recommended by IEEE Proposed Guide P-422.[3] Fire stops are provided at cable tray penetrations through floors and fire barrier walls.
4. An exception is taken to IEEE Proposed Guide P-422[3] recommendations for 30%

cable tray fill. Experience has indicated that a design objective of 50% physical fill, including all anticipated future cables, is satisfactory. This fill calculation is based upon the summation of the cable diameter squared divided by the cross-sectional area in the tray. The tables referred to in Item 1, above, are used as the basis for ampacity rating. The allowable depth is determined from the physical fill calculations outlined above and in Section 8.3.3.1.

5. The design objective for the minimum physical vertical spacing between the power, control and instrument cable trays of the same redundant channel is 12 inches, measured from the top of the lower tray to the bottom of the upper tray and a 9 inch clearance between the top of a tray and beams, piping, etc., to facilitate installation of cables in the tray. However, in areas where physical limitations govern, the physical separation may be less than the 12 inches and 9 inches, respectively.

8.3-24 Reformatted October 2020

6. The same basic design considerations are incorporated for tray and conduit supports as for the structures to which they are attached. Therefore, the same supports can be used for redundant raceways or for a redundant and non-safety raceway.

8.3.1.5 Physical Identification of Safety-Related Equipment Identification of cable and raceways is readily apparent in the design and installation stages and is such that any safety-related cable can be readily identified. Raceways and cables (particularly for redundant systems) are adequately identified to prevent violation of separation criteria. Channel identification for safety-related and associated circuits is based upon the 4 reactor protection process control channel colors: red, orange, blue, and yellow. In addition, green is used for C train and tan is used for RN 99-139 non-safety-related circuits. Cable trays and cables for these circuits, as well as for R1 power, control and instrumentation circuits for ESF Channels A and B are identified relative to the 6 colors as indicated in Table 8.3-4.

Cable identification is as follows:

1. Color coding Cables are marked at 5 foot intervals. The circumference of the cable is marked such that the marking is visible no matter how the cable is turned.
2. Tagging Tags are placed at each end of the cable. These tags are marked to indicate the circuit and channel. Any nonengineered safety feature cables in a safety-related tray are marked to distinguish them from the safety-related cables.
3. Conduits Conduits are marked with identification markers. Color coding is done with colored tape at 15 foot intervals. Tags for embedded conduit are attached to the concrete above the conduit.
4. Cable Trays Cable trays for safety-related cables are identified with tags. The color coded tags are located on the trays so they are visible from easily accessible vantage points, such as walkways, etc.

8.3-25 Reformatted October 2020

5. Equipment Identification Each piece of equipment has an identification (ID) tag attached which identifies the equipment. Channel designation for safety related and associated equipment is identified by a strip of color coded tape.

Tags mounted on equipment inside the Reactor Building are of stainless steel and have the required information engraved. Where there is not room to mount the tag to the equipment, it will be attached by wire. In these cases, the color coded tape will be attached to the back of the tag. Stainless steel ID tags are also used outside the Reactor Building. Tags for associated equipment have 2 colors.

8.3.1.6 Electrical Penetration Areas Electrical penetration areas are located as follows:

1. Fuel Handling Building penetration area (penetration access area - North).

RN Number of penetrations is 7.99-011

2. Intermediate Building penetration area (penetration access area - East). Number of penetrations is 5.
3. Intermediate and Auxiliary Building penetration area (penetration access RN area - West). Number of penetrations is 33.99-011 No special designations have been assigned areas where penetrations enter the Reactor Building.

Redundant circuits are spatially separated by 40 feet or a concrete floor, except for nuclear instrumentation penetrations, which are spatially separated by 20 feet.

Provisions for fire detection and protection in the penetration access areas consist of the following:

1. An early warning fire detection system comprised of smoke detectors. RN 96-041
2. A fire hose/standpipe system.
3. Manual fire extinguishers.

Protection to ensure that missiles inside the Reactor Building will not jeopardize plant safety are discussed in Section 3.5.1.

8.3-26 Reformatted October 2020

All containment penetration seal assemblies are protected against major incidents, such as missiles and rupture of high energy piping. Additionally safety related penetrations are protected on both sides of the nozzle. Therefore, based upon good design practice, a separation of 3 feet from other penetrations, the failure of which could inflict only minor or insignificant damage to an electrical penetration, was provided.

8.3.2 D-C POWER SYSTEMS 8.3.2.1 Description Separate Class 1E and non-Class 1E d-c power systems are provided. Two (2) Class 1E 125 volt d-c systems provide sources of reliable, uninterruptible d-c power for control and instrumentation for normal operation and orderly shutdown of ESF equipment. A separate non-Class 1E 125 volt d-c system is provided to supply non-ESF d-c loads, including large power non-ESF loads. This system is also a manually switched backup d-c source for the Substation Relay House d-c system. The 125 volt d-c battery systems, located in the Substation Relay House and in the Unit 1 Relay House, are RN 14-013 provided for 230 kV substation protection and control. These systems are shown in Figures 8.3-1, 8.3-2, 8.3-4, 8.3-5 and 8.3-5a.

The Class 1E d-c system for control and instrumentation consists of 2 full capacity, 125 volt d-c, lead calcium, 60 cell batteries, 2 125 volt d-c battery buses and 3 static battery chargers. Two (2) of the 3 battery chargers are supplied from separate, redundant motor control centers. One (1) of these 3 chargers serves as a standby charger and is provided for use during maintenance of, and to backup, either of the normal power supply chargers. The standby battery charger, 1A-1B, is provided with a set of 2 transfer switches which consist of mechanically interlocked circuit breakers on the a-c input and d-c output. These circuit breakers, as shown by Figures 8.3-6 and 8.3-7, are interlocked to allow only the 2 breakers associated with Channel A or the 2 breakers associated with Channel B to close at the same time. The battery chargers remain connected to the respective a-c source buses upon loss of offsite power. Each battery charger is protected by the molded case circuit breakers in the input and output circuits. The d-c circuit has a voltage adjustment of 100 to 145 volts d-c. During an equalizing charge, d-c voltage may be set at 140 volts. All Class 1E d-c loads can operate at 140 volts d-c without damage. An overvoltage alarm is provided to annunciate in the control room upon detection of voltages greater than 140 volts d-c.

The non-Class 1E 230 kV Substation d-c systems provided for the 230 kV substation control and relaying consists of the following:

RN

1. For the Substation Relay House, the d-c system consists of a 125 volt battery with 14-013 a main battery bus, two battery changers and two separate distribution panels for 230 kV circuit breaker tripping. Backup for non-1E loads is also provided by this system.

8.3-27 Reformatted October 2020

2. For the Unit 1 Relay House, the d-c system consists of two independent d-c systems. Each system is comprised of a 125 volt battery with two distribution panels, a battery charger and common bus-tie fuse-disconnect switch. One d-c RN system supplies the 230 kV substation system primary protection and control. The 14-013 second d-c system supplies backup protection and control. Other 230 kV substation systems and relay house d-c loads and can be supplied from either d-c system.

The second non-Class 1E d-c system provided for the 230 kV substation control and RN relaying in the substation relay house consists of a 125 volt battery with a battery bus,12-001 2 static battery chargers and 2 separate distribution panels for power circuit breaker 98-065 tripping. Backup for large power non-ESF loads is also provided by the system.

The non-Class 1E d-c system in the Unit 1 relay house consists of two 125 volt d-c RN batteries, each with its battery charger, feeding 2 separate distribution panels for power 12-001 circuit breaker tripping.

The non-Class 1E battery has adequate storage capacity to power the following loads for a period of 1 hour:

1. Main generator emergency seal oil pump.
2. Circuit breaker closing and tripping (non-ESF buses).
3. Miscellaneous non-ESF loads.
4. Non-ESF instrumentation inverter and computer inverter.
5. D-C turbine bearing oil pump.
6. Feedwater pump d-c oil pump (3 pumps).
7. Reactor and Diesel Generator Building emergency panels.

A 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period is considered to be the minimum time for use in sizing the batteries.

Complete loss of offsite and onsite a-c power for such a period of time is considered highly unlikely. Loss of both diesel generators during an assumed prolonged loss of offsite power is not postulated nor is complete loss of all battery chargers postulated.

Battery chargers are considered to be available to sustain the bulk of the battery loads well within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period of time.

The non-Class 1E battery supplying power to the d-c turbine bearing oil pumps is of sufficient capacity to power the pumps during turbine coastdown to avoid turbine bearing damage.

8.3-28 Reformatted October 2020

Battery capacity in addition to that which is absolutely essential is provided.

8.3.2.1.1 Uninterruptible Non-Class 1E System The uninterruptible non-Class 1E 125 volt d-c system is an ungrounded system. The system is operated ungrounded with the battery floating on the system. Dual input inverter No. 5 (450 volt a-c normal input, 125 volt d-c backup input) provides uninterruptible 120 volt a-c power for the AMSAC system, secondary plant digital control systems, the station computer and other non-Class 1E loads. No Class 1E loads are supplied from this system. The secondary plant digital control system can also be RN 18-004 powered by the ISFSI Electrical Building uninterruptible power supply.

The dual input inverter No. 5 provides continuous power to non-Class 1E 120 volt vital secondary digital control system and computer loads. Transfer from one input to the other is accomplished without interruption to the load. The inverter is protected by circuit breakers on the 480 volt a-c input side and the 125 volt d-c input side. Abnormal 00-01 conditions in the dual input inverter cause alarms to occur in the control room.

The output of inverter No. 5 is connected to a distribution panel through an automatic static transfer switch. An alternate backup 480-120 volt transformer non-Class 1E power source is provided through the automatic static transfer switch. The feed to the transformer is from a 480 volt motor control center as indicated by Figures 8.3-4 and 8.3-4b.

All metering and monitoring is performed by a digital control system that includes a microprocessor. The operation of the microprocessor has no impact on the ability of inverter No. 5 to perform its function.

Inverter No. 6 is also powered from the non-Class 1E 125 volt d-c bus. A static switch is provided on the output of this inverter to switch the feed to the inverter distribution panel from the inverter output to a 120 volt ac supply upon detection of loss of inverter output.

8.3.2.1.2 Uninterruptible Class 1E Systems Each uninterruptible Class 1E system contains a separate 125 volt d-c and 120 volt ac system.

The 125 volt d-c system is a 2 wire, ungrounded system centered around a full capacity 125 volt, lead calcium battery, 125 volt d-c main distribution panel and solid state battery chargers. Figures 8.3-2aa and 8.3-2ab show connection of the battery, battery charger and main distribution panel of each redundant Class 1E power system.

No ties are provided between the redundant Class 1E 125 volt d-c systems. All non-Class 1E loads connected to the Class 1E d-c system are identified by Figure 8.3-1 (see Note 4, Figure 8.3-1). Connection of non-Class 1E loads to the Class 1E d-c system is discussed in the statement concerning Regulatory Guide 1.75 in Appendix 3A.

8.3-29 Reformatted October 2020

Eight (8) separate 125 volt d-c distribution panels including the 2 main distribution panels are provided. Each panel provides d-c instrumentation and control power as necessary for proper functioning of the plant.

The battery, battery charger and main distribution panel of each system are located in protected areas of the Intermediate Building, separate from the location of redundant channel equipment. The protected areas are separated by a fire resistant barrier. The inverters and other distribution panels are also located in protected areas.

Each ESF battery has a rated capacity of 2175 ampere hours (with an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> discharge cycle to 1.75 volts per cell). This capacity is sufficient to power essential loads and normally connected non-essential loads for a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> duty cycle following loss of all a-c power. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> duty cycle is based on coping requirements for Station Blackout[15]

defined by NUMARC 87-00[17] and endorsed by NRC Regulatory Guide 1.155[16]. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> duty cycle with loss of all a-c power envelopes the previous 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duty cycle based on a LOCA in conjunction with the loss of all a-c. The 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duty cycle represents standard industry practice for sizing batteries for generating stations and does not reflect V. C. Summer design basis requirements for demonstrating d-c system operability. Essential loads include the following:

1. Instrumentation inverters - with ESF and non-ESF loads.
2. Engineered safety features control.
3. Diesel generator control and field flashing.
4. Circuit breaker closing and tripping (ESF buses).
5. Controls and alarms, including Auxiliary Relay Racks, Isolator Cabinets, Main Control Boards, HVAC Boards and Control Room Annunciators.
6. Control Room emergency lighting.

During normal operation, the 125 volt d-c load is supplied from the battery chargers with the batteries floating on the system. Upon loss of station a-c power, the entire d-c load is supplied from the batteries until the a-c power to the chargers is restored by the emergency diesel generator or the preferred power source. The function of the battery is to provide sufficient stored energy to operate necessary d-c loads for as long as each load is required during the loss of a-c power. The time duration for the loss of a-c power is the time required for the diesel generator to start and accept load. For the V. C.

Summer Station, the diesel generator breaker will close and energize the battery charger within 10.25 seconds after a loss of a-c power. Failure of a battery charger or failure of a diesel generator to start would be a single failure for which there is a redundant train of electrical systems that will be used to achieve safe shutdown and mitigate design basis events. A failure of a battery charger would not prevent either 8.3-30 Reformatted October 2020

start of the diesel generator or closure of the necessary breakers to re-establish a-c power to the auxiliary a-c system. In the event of a charger failure, a backup charger has been provided and can be connected well within the batterys 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> duty cycle.

Thus, the minimum 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> battery capacity provides considerable margin for the battery to perform its intended function.

Separate evaluations were performed to demonstrate sufficient battery capacity and to demonstrate system operability based on sufficient voltage at d-c equipment/device terminals.

The evaluation to demonstrate sufficient Class 1E battery capacity was based on ampere loads associated with Class 1E and non-Class 1E equipment as shown on Figures 8.3-1, 8.3-2, 8.3-2aa, and 8.3-2ab.

RN 98-065 The evaluation to demonstrate d-c equipment/device operability was based on ensuring that the available operating voltage (or current) for required equipment was equal to or greater than the minimum operating voltage recommended by the applicable vendor or by actual tests to demonstrate component operability with margin. Available operating voltages (or currents in the case of D.G. field flashing) were evaluated to ensure operability of Class 1E devices based on the required time of operation and the applicable system losses resulting from voltage drop. Operability of non-Class 1E loads which are supplied from the 1A and 1B batteries was not evaluated.

System operating voltages were determined based on the battery as the sole source during the first 10.25 seconds following LOOP with only 59 cells or 58 cells connected.

System operating voltages after 10.25 seconds were determined based on the battery at float voltage following restoration of a-c power to the battery charger.

The evaluation conservatively determined voltage drop based on the d-c load currents established by the battery capacity evaluation, as modified to include design margins, and the equivalent circuit resistance, as modified to compensate for worst case conductor temperatures.

Although there is no accident analysis that requires d-c system operability with the battery as the sole source after 10.25 seconds, the design objective was to ensure the ESF 125 v d-c system is capable of supporting/operating normal and required emergency d-c loads in the event of a DBA, or required SBO loads in the event of a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> station blackout. Required SBO loads are normal (non-accident) loads necessary to ensure the reactor core is cooled and containment integrity is maintained in the event all a-c power is lost for a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> period.

8.3-31 Reformatted October 2020

8.3.2.1.3 Capacity The ampere demand of each ESF battery was calculated for the loads listed in the preceding Items 1 through 6, as well as for other connected d-c loads, to establish the worst case 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> duty cycle. This calculation resulted in the following 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> load profile.

1. Battery 1A - 376.9 amperes for the first minute, 200.3 amperes for the next 238 minutes, and 246.3 amperes for the last minute. RN 99-138
2. Battery 1B - 392.4 amperes for the first minute, 215.8 amperes for the next 238 minutes, and 261.8 amperes for the last minute.

The capacity of each ESF battery was then checked to ensure that the batteries are capable of supplying required d-c loads for the duty cycle. In addition the battery capacity includes design margin, accounts for battery degradation with age, and considers the reduction of battery capacity due to temperature variations. The capacity evaluation was based on a final (end of discharge) battery terminal voltage of 108 V d-c (or greater), which provides sufficient margin to ensure device operability with a reduction of up to 2 cells (58 cells connected) on either battery.

The calculated ampere demand includes normally connected devices with no distinction as to whether devices are required to operate or are desirable loads. The inclusion of the latter precludes the need for any load shedding and no operator action is required to maintain power to essential safety related loads during the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> duty cycle. However, any load shedding performed during the battery duty cycle adds to the existing capacity margin and results in a higher battery voltage at the end of the duty cycle. RN 98-065 The d-c system is designed so that the loads with common a-c and d-c power supplies, such as inverters, are powered by the batteries during blackout, but are automatically returned to the a-c system upon ac bus voltage restoration. As a result, the battery chargers are required to have a minimum capacity of 150 amperes to provide the necessary 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> recharge. This is well within the systems 300 ampere battery charger rating.

8.3.2.1.4 Ventilation The battery rooms and battery charger rooms are located in the Intermediate Building and are provided (as a group) with a once through ventilation system consisting of two (2) 100% capacity supply fans and two (2) 100% capacity exhaust fans as shown in Figure 9.4-16. The ventilation system is designed for continuous operation. Therefore, the chance of producing an explosive atmosphere due to evolution of hydrogen during the process of battery charging is minimized. The system is provided with high and low temperature alarm inputs to the HVAC control board annunciator system. The battery room ventilation system is discussed further in Section 9.4.6.

8.3-32 Reformatted October 2020

8.3.2.1.5 Equipment 8.3.2.1.5.1 Batteries and Battery Racks All batteries are of the central station, lead calcium type and are designed for continuous float duty. Each cell is of the sealed type, assembled in a shock absorbing clear plastic container, with covers bonded in place to form a leakproof seal. The batteries are mounted on protected, corrosion resistant, steel racks for security and to facilitate maintenance. The Class 1E batteries and racks are designed to remain functional during a safe shutdown earthquake and remain in a satisfactory condition to perform their function in shutting down the reactor and maintaining the station in a safe condition.

8.3.2.1.5.2 Battery Chargers Each solid state battery charger has an output for float and equalize modes with an input of 480 volt 3-phase, a-c power. Each charger is equipped with a d-c voltmeter, d-c ammeter, a-c failure relay, a ground detection annunciator alarm, low battery voltage alarm relay and fan failure alarm. A battery charger malfunction activates an alarm in the control room. Each battery charger is designed to prevent the 480 volt a-c system from becoming a load on the battery as a result of loss of 480 volt a-c input.

Tests have verified that battery charger stability is not load dependent.

There is no annunciator to alarm when the battery charger goes into a current limiting condition.

In addition to the charger output ammeter, a 0 center scale ammeter is connected to a shunt in the leads between the battery and the battery bus to indicate current flow to and from the battery. These 2 ammeters show the status of battery charging or discharging currents and d-c system loads at all times. Main breakers, as shown on Figures 8.3-1, 8.3-2, and 8.3-4 are equipped with auxiliary switches to operate indicator lights in the control room for an off normal position. Thus, the operator is provided with system status information. Following a loss of normal station power, the battery chargers are energized from the diesel generators.

Additional monitoring is provided by a special, narrow band, d-c voltage relay to monitor Class 1E battery voltage. The relay initiates an alarm in the control room if battery voltage falls slightly below normal float voltage.

Voltage monitoring in this manner provides a backup alarm if a charger fails since a fully charged battery suffers a rapid drop in voltage if its floating charge fails. Such a rapid voltage drop causes the voltage monitoring relay to initiate the associated alarm.

Battery ground detection annunciation is provided on the main control board for both Class 1E and non-Class 1E Plant d-c systems.

8.3-33 Reformatted October 2020

The ratings for each battery charger continuous output are as follows:

1. Charger 1A - 300 amperes
2. Charger 1B - 300 amperes
3. Charger 1A-B - 300 amperes
4. Charger 1X - 400 amperes
5. Charger 1X-2X - 400 amperes Each battery charger has capacity adequate to restore its associated battery to full charge while providing power to the largest combination of the various steady-state loads. The charging capacity is based upon restoring the battery to full charge from the design minimum charge within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after discharge regardless of the status of the station.

8.3.2.1.5.3 Main D-C Distribution Panels Each battery distribution switchboard consists of a metal clad structure with 125 volt d-c, RN 2 wire, ungrounded main bus. Two (2) pole, manually operated, air circuit breakers98-065 protect each feed.

8.3.2.1.5.4 Class 1E Dual Input Inverters The dual input inverter in each system provides continuous power to the 120 volt vital a-c buses. The output of the inverter is a regulated supply. Transfer from 1 input to the other is accomplished without interruption of the output. Each inverter is protected by circuit breakers on the 480 volt a-c input side, 120 volt vital a-c output side and 125 volt d-c input side. Each dual input inverter is provided with an a-c and a d-c ammeter.

Abnormal conditions in the dual input inverter, including loss of a-c input, loss of d-c input, and loss of a-c output voltage cause alarms to occur in the control room.

The output of each inverter is connected to a distribution cabinet through an automatic static transfer switch and a normally closed circuit breaker. An alternate backup 480-120 volt transformer Class 1E power source is provided through the automatic static transfer switch. The feed to the transformers is from a 480 volt motor control center as indicated by Figures 8.3-1 and 8.3-2. The distribution cabinets have RN appropriately sized branch circuit breakers to feed reactor protection and other vital 98-072 instrument channels. Most reactor protective schemes have 3 or 4 channels.

Redundant instrument channels are fed from redundant vital buses.

8.3-34 Reformatted October 2020

Because of the preferred failure mode defined for the reactor protective instrumentation, failure of an instrument channel power source results in a reactor trip signal from the affected channel. Multiple power supplies are provided to prevent a single power supply failure from initiating a false reactor trip.

The vital bus rectifiers and inverters are assembled from high quality components, conservatively designed for long life and continuous operation.

By avoiding the use of electromechanical devices, routine maintenance downtime is greatly reduced. There are no vacuum tubes or moving parts in the completely static vital bus supply systems.

The ratings of each inverter are as follows:

1. Inverter No. 1 - 10 kVA.
2. Inverter No. 2 - 10 kVA.
3. Inverter No. 3 - 10 kVA.
4. Inverter No. 4 - 10 kVA.

8.3.2.1.5.5 Non-Class 1E Inverters There are 2 non-Class 1E (balance of plant) inverters. Inverter No. 5 is a dual input inverter. The dual input inverter No. 5 provides continuous power to non-Class 1E 120 volt vital digital control systems and computer loads. Transfer from one input to the other is accomplished without interruption to the load. The output of inverter No. 5 is 00-01 connected to a distribution panel through an automatic static transfer switch. An alternate backup 120 volt non-Class 1E power source is provided through the automatic static transfer switch. The AMSAC system, secondary plant digital control systems and the station computer constitutes the primary loads on this inverter. The secondary plant RN 18-004 digital control system can also be powered by the ISFSI Electrical Building uninterruptible power supply.

Inverter No. 6 is a single input inverter supplied from the 125 volt d-c non-ESF system.

Output from this inverter is paralleled with a supply from a 480-120 volt transformer which is connected, through a static transfer switch to the inverter main distribution panel. The transformer source serves as an alternate supply to the inverter main distribution panel. Upon loss of inverter output, automatic transfer of the inverter main distribution panel to the alternate supply is initiated. The primary load on inverter No. 6 is non-ESF instrumentation.

An alternate power source circuit breaker is provided in the distribution cabinet to permit manual transfer from the inverter or transformer power source to a backup power source as indicated by Figure 8.3-4.

8.3-35 Reformatted October 2020

Inverter ratings are as follows:

1. Inverter No. 5 - 10.0 kVA. 00-01
2. Inverter No. 6 - 10.0 kVA.

8.3.2.1.5.6 480-120 Transformer and Static Transfer Switch An alternate source of power to each of the 120 volt vital a-c buses is provided by a 480-120 volt Class 1E, single phase transformer. The 480-120 volt transformer in each system is designed to supply the total 120 volt vital a-c bus load when the dual input inverter is out of service.

A static transfer switch is provided for inverter No. 6 to switch the 120 volt vital a-c bus loads from the single input inverter to the 480-120 volt transformer. The static transfer switch is a solid state device. Its operation is unaffected by load and power factor variations. Transfer of the 120 volt vital a-c bus loads from the single input inverter to the 480-120 volt transformer causes an alarm to occur in the control room. Transfer back to the inverter is performed manually at the discretion of the operator.

8.3.2.1.5.7 Nominal 120 Volt Vital A-C Bus System The nominal 120 volt a-c vital bus system consists of 6 panels and 4 inverters which provide power to 4 independent channels of ESF instrumentations. Channels A and B consist of 2 panels and 1 inverter each while Channels C and D consist of 1 panel and 1 inverter each. Figures 8.3-1, 8.3-2, 8.3-2aa, and 8.3-2ab depict the system.

The vital bus system is a very reliable electrical system. It provides a stable supply to vital equipment and guarantees proper action when power is required, while eliminating spurious shutdowns.

The normal power source for each vital bus inverter is through the inverter static rectifier from a 480 volt ESF bus. Should the normal power source fail completely or be subject to transient voltage or frequency variations, the vital bus inverter power source becomes the battery charger or battery which is floating on standby service. This transition from static rectifier to battery power supply takes place without disturbing vital bus voltage or frequency. The station batteries are sized to carry this additional inverter load without chargers for no less than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The chargers are sized to bring a fully discharged battery up to equalize charge voltage with the inverter load connected in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

8.3-36 Reformatted October 2020

8.3.2.2 Analysis 8.3.2.2.1 Compliance The Class 1E uninterruptible systems satisfy the criteria of Regulatory Guides 1.6 and 1.32 (see Appendix 3A), and General Design Criteria 17 and 18. The uninterruptible systems are designed so no action, automatic or manual, needs to be taken to make d-c or vital a-c power available to the equipment required immediately following LOCA or after a loss of a-c power. No operator action is required to maintain d-c or vital a-c power availability, based on single failure criteria, for safe shutdown or accident mitigation following a loss of a-c power.

Class 1E system components are identified and seismically qualified as described in Section 3.10. The battery was connected to a resistive load of approximately 20 amperes during seismic testing.

Class 1E equipment and the hostile environment to which it is subjected are discussed in Section 3.11.

Each uninterruptible system includes power sources and a distribution system arranged to provide power to associated system loads. No ties exist between Class 1E systems.

Figures 8.3-1, 8.3-2, 8.3-2aa, and 8.3-2ab illustrate the independence of the Class 1E uninterruptible systems. Equipment, cables and other components are designed, identified and located in accordance with the criteria given herein. Sections 8.3.1.4 and 8.3.1.5 discuss general design criteria applicable to the uninterruptible systems as well as to the a-c systems.

8.3.2.2.2 Maintenance and Testing The uninterruptible systems are subjected to periodic maintenance tests to determine the condition of each individual component. Batteries are checked for electrolyte level, specific gravity, cell voltage and visual signs of deterioration. A battery performance discharge test is performed according to IEEE-450[7]. Battery chargers, and inverters are checked by visual inspection weekly and performance tests are conducted periodically.

Maintenance and testing procedures for batteries are in accordance with IEEE-450[7].

Testing and inspection are performed according to the following:

1. General inspections and recording of data are performed in accordance with IEEE-450[7].
2. Quarterly tests, inspections, and recording of data are performed in accordance with IEEE-450[7].
3. Yearly inspections are performed in accordance with IEEE-450[7].

8.3-37 Reformatted October 2020

4. Battery service tests are performed in accordance with IEEE-450[7]. The time interval between tests is based on a nominal 18 month refueling outage schedule.

RN Service tests are not performed during outages that require performance of a 98-140 capacity (performance discharge) test. (See Regulatory Guide 1.32 discussion in Appendix 3A.)

5. Battery capacity tests are performed in accordance with IEEE-450[7] and IEEE-308[8].

8.3.2.3 Physical Identification of Safety-Related Equipment The physical identification of safety-related equipment is discussed in Section 8.3.1.5.

8.3.3 FIRE PROTECTION FOR CABLE SYSTEMS RN The 15,000 volt rated power cable, the 8,000 volt rated power cable, 600 volt rated 17-015 power cable for 480 volt and 120 volt a-c systems and 125 volt d-c systems, 600 volt rated control cable for 120 volt a-c and 125 volt d-c controls and 300 volt instrument cable are constructed with an overall fire retardant outer jacket.

Cable for external circuits is type tested in accordance with Section 2.5 (Flame Tests) of IEEE-383[9] and the cables are certified to be of fire retardant construction.

8.3.3.1 Cable Derating, Cable Tray Fill, and Cable Construction Cables are derated to compensate for ambient temperatures and for the presence of adjacent power cables. Power cables are sized and derated on the basis of IPCEA P-46-426[4], supplemented by IPCEA-NEMA P54-440[5].

Motor feeders, power panel feeds and small lighting and receptacle panel transformer feeds are sized for 125% of full load current. Large power transformer feeders are sized for 140% of full load current at maximum rating. Motor control center feeders are sized for 140% of the calculated normal diversified load current. Feeders to resistive loads are sized on the basis of 110% of rated current at rated voltage.

In selecting IPCEA ampacity tables, a load factor of 100% is assumed.

Ampacities of 7200 volt power cables are in accordance with IPCEA P-46-426[4] in air ratings, derated by factors of 0.70 in 40°C areas and 0.63 in 50°C areas.

Ampacities of 480 volt cables or large d-c cables in single layer power trays are in accordance with IPCEA P-46-426[4] in air ratings and are derated by factors of 0.70 in 40°C areas and 0.63 in 50°C areas.

Ampacities of 480 volt cables or d-c cables in a random lay power tray are in accordance with IPCEA-NEMA P-54-440[5]. Derating factors for 3 inch depth are used.

8.3-38 Reformatted October 2020

Ampacities of small 480 volt cables or small 125 volt d-c cables (#10 AWG and smaller),

when run in control trays, are in accordance with IPCEA P-46-426[4] in air ratings derated by a factor of 0.50.

Ampacities for 7.2 kV and 480 V 3 conductor cables in conduit wrapped in Kaowool at 40°C ambient temperature are calculated to ensure a maximum copper surface temperature of 90°C. Basis for these calculations are data obtained from IPCEA P-46-426. The application ampacities of the cables are determined by applying a 1.25 derating factor to the design ampacities. The cable sizes are then selected so that the RN cable application ampacity is equal to or greater than the design current value 99-002 determined from the cable sizing criteria.

No ampacity derating factors are applied to control and instrument cables.

Ampacities are determined on the basis of 90°C tables at 40°C ambient in all interior areas except containment. Containment or ESF motors in areas requiring forced ventilation of the motor are determined on the basis of 50°C ambient.

Pressurizer heater cables are sized by special ratings due to the operating environment.

The Reactor Building cooling unit fan motor power cables and the post accident hydrogen recombiner unit power cables[10] require special consideration since these motors must operate in the post accident containment environment. These cables are sized to carry the required current during the post accident temperature and pressure transient without exceeding the recommended emergency operating temperature rating for the cable and to continue to operate for a minimum of 6 months after the accident.

A preventive maintenance program to test the insulation values of circuits and equipment is followed.

Ladder type tray systems are used for power and control trays. Instrument trays are solid bottom trays with top cover plates.

The 5 basic tray systems are as follows:

1. The 7200 volt power trays.
2. The 480 volt and below, single layer power trays.
3. The 480 volt and below, random lay power trays.
4. Control trays.
5. Instrument trays.

8.3-39 Reformatted October 2020

In vertical stacking the 7200 volt power trays are on top, 480 volt power trays next lower, control trays next lower, and instrument trays on the bottom.

8.3.3.1.1 7200 Volt Power Trays No other type cable is mixed in the same tray with 7200 volt power cable. These trays are 4 inches deep (inside dimension). There is 1 layer of cable with no spacing between cables.

8.3.3.1.2 480 Volt and Below, Single Layer Power Trays The 480 volt and below, single layer power tray system is exclusively for 480 volt, 3-conductor power cables or d-c power cables. This tray system is 4 inches deep (inside dimensions) and contains only large (MCM sizes) and 4/0 cables. There is 1 layer of cables with no spacing between cables.

8.3.3.1.3 480 Volt and Below, Random Lay Power Trays The 480 volt and below, random lay power cable tray is for 480 volt power cables 4/0 and smaller. The tray is 6 inches deep (inside dimensions).

Percent fill =

(d +d + . . . . +d ) x 100 2

1 2

2 2

n Tray Depth x Tray Width where: d1, d2, . . . . dn = Diameters of all cables in the tray presently planned plus all known future cables.

Small 480 volt power cables (#10 AWG and smaller) may be run either in the random lay power cable tray or the control tray. Circumstances may dictate running an MCM size power cable in a random lay power tray. The cable is then derated with the derating factor appropriate to the random lay trays.

8.3.3.1.4 Control Trays The control trays contain control cables, small 480 volt power cables (#10 AWG and smaller, except for selected motor operated valves which use larger sized cables) and small d-c power cables (#10 AWG and smaller). All of these cables carry either intermittent current or continuous current of 5 Amps or less. Single phase, 120 volt a-c circuits (#10 AWG and smaller) carrying 5 amps or less may also be run in the control trays. The amount of heat generated from cables which carry intermittent current is RN 99-014 negligible based on the large majority of time the load is not operating.

The control trays are 6 inches deep (inside dimensions). The design limit for control tray fill is based on verifying that the weight of new and existing cable is within the tray and tray support weight capability.

8.3-40 Reformatted October 2020

8.3.3.1.5 Instrument Trays Instrument trays contain low level analog signals cables. These trays are 6 inches deep (inside dimensions). The design limit for instrument tray fill is based on verifying that RN 99-014 the weight of new and existing cable is within the tray and tray support weight capability.

In addition to all low level analog signal cables, the instrument trays are used for digital contact (breaker contact) cables where the source of power is the reactor protection or computer packages, otherwise all digital circuits are in the control trays.

8.3.3.1.6 Cable Tray Fill Criteria The 50% cable tray fill criteria is the design objective that applies only to random lay RN 99-014 power trays. Random lay power trays contain 480 volt power cables smaller than MCM sizes. Power cables, No. 10 and smaller, may be run either in random lay power tray or in control tray.

RN The 30% fill criteria recommendation in IEEE Propose Guide P-422[3] is based upon the 99-014 summation of cross sectional areas of cables. The 50% fill noted in Section 8.3.1.4.3 is based upon the summation of the cable diameter squared areas. Fill of 50% on this RN basis is equivalent to 39% fill on the IEEE Propose Guide P-422[3] basis (i.e., 3.1416/4.0 99-014 times 50%). Through experience, it has been found that approximately 40% fill on the basis of cross sectional area or 50% fill on the basis of diameter squared area is satisfactory with respect to physical tray loading and uses the tray more efficiently.

Power cables are rated on the basis of this 3 inch physical depth, using the derating factors of IPCEA-NEMA P-54-440[5].

These derating factors are in agreement with the 50% or 3 inch depth physical loading.

Control and instrument cables require no derating.

Where random lay power tray fill exceeds 50%, worst case conditions have been analyzed to assure the capability of the tray hangers to support the additional weight and, that sufficient margin exists in the cable sizing to account for the heating effects (Reference IEEE Transaction Paper 70TP557PWR "Ampacities for Cables in Randomly Filled Trays", also, see FSAR Section 8A.1.2). For each random lay power tray, a calculation was performed to address the additional heat loading from the new power cable and its effect on the ampacity (heat loading) of other power cables in that tray.

RN The existing and new power cables were derated if the total heat loading of the cables99-014 in the tray was not within the allowable heat loading based on the percent fill. In addition, this calculation determined the weight of the new and existing cables to ensure that their combined weight was less than the maximum weight that the tray support can carry. For trays filled to the maximum weight allowed by the tray supports, the maximum allowable cable sidewall pressures will not be exceeded (Reference FSAR Section 8A.1.3). In the event overfill occurs at tray intersections, protection will be provided to preclude cable damage.

8.3-41 Reformatted October 2020

The cable tray fill criteria for control and instrument trays is controlled by the cable management system computer program. This program contains an alarm limit for the maximum weight allowed for each tray size used. Therefore, manual calculations to RN monitor cable weight are not required since this calculation is done by the cable 99-014 management system and an alarm is provided if the tray or tray support weight capability is exceeded. Heat loading is not a concern for control and instrumentation cables due to their small currents and/or intermittent operation.

For expanded cable and tray design considerations, see Appendix 8A.

8.3.3.1.7 Cable Construction Feeder and motor cables in 7200 volt service are insulated cables rated at a minimum of 8000 volts. Single conductor cables or each conductor of multi-conductor cables in 7200 volt service are shielded.

Power cables for 480 volt service are insulated cable rated at a minimum of 600 volts.

Single conductor cables and multi-conductor cables are provided with an overall flame retardant jacket.

Control cables are of single or multi-conductor construction with a 600 volt (minimum) insulation, total coverage electrostatic shield and overall flame retardant jacket.

Low voltage instrument cables are insulated cables rated at 300 volts, minimum. Where required, these cables are provided with a total coverage electrostatic shield and with an overall flame retardant jacket.

8.3.3.2 Fire Detection and Protection Devices Fire detection and protection systems, either automatically or manually initiated, are provided in those areas required to preserve the integrity of circuits for redundant safety-related systems. A fixed, low pressure carbon dioxide fire extinguishing system is installed in the relay room and computer room at elevation 436 of the Control Building. A preaction sprinkler system is installed in the following areas of the Control Building:

1. Cable spreading room - elevation 425.
2. Cable spreading room - elevation 448.
3. Cable chase areas.

Smoke detection systems are installed in the switchgear rooms and penetration access areas. Section 9.5.1 provides greater detail concerning fire detection and protection.

The fire hazard to cables is reduced by cable construction as described in Section RN 98-112 8.3.3.1.7.

8.3-42 Reformatted October 2020

8.3.3.3 Fire Barriers and Separation Between Redundant Cable Trays Criteria used for the separation between different Class 1E system trays and between Class 1E and non-Class 1E trays are given in Section 8.3.1.4. Where the required separation cannot be maintained, fire barriers are installed in accordance with IEEE P-422[3], Section 8.3.2. The fire barriers are qualified in accordance with criteria given in Section 9.5.1.

In cases of multiple separation violations between non-safety related trays and redundant safety related trays in the same fire area, tray covers or circuit breaker surveillance has been provided as a resolution. Refer to FSAR Section 8.3.1.4.1, item 4 for details.

8.3.3.4 Fire Stops Openings in walls, floors, and ceilings, which are provided for the routing of raceways, are protected by fire stops. Fire stops are designed with a fire rating equivalent to that required for the wall, floor or ceiling with which it is associated. The materials used in fabricating fire stops are rated in accordance with ASTM E 119. In addition to preventing the spread of fire, fire stops are designed to be reasonably leaktight, thereby limiting the propagation of smoke and gases from one area to another.

8.3.4 SAFETY RELATED CABLE No natural polyethylene materials are used in safety related inter-connecting circuits between equipment in the Virgil C. Summer Nuclear Station. Cables which have cross linked polyethylene are used for various plant applications.

8.

3.5 REFERENCES

1. Institute of Electrical and Electronic Engineers, "Installation Inspection, and Testing Requirements for Instrumentation and Electric Equipment during the Construction of Nuclear Power Generating Stations," IEEE-336-1971.

RN 99-037

2. Deleted (RN 99-037)
3. Institute of Electrical and Electronics Engineers, "Design and Installation of Cable Systems in Power Generation Stations," IEEE Proposed Guide P-422, prepared by RN 99-037 the Working Group on Wire and Cable Systems Station Design Subcommittee, Power Generation Committee.
4. Insulated Power Cable Engineers Association, "Power Cable Ampacities," IPCEA P-46-426-1962.
5. Insulated Power Cable Engineers Association - National Electrical Manufacturers Association, "Ampacities of Cables in Open-Top Cable Trays," IPCEA-NEMA P-54-440.

8.3-43 Reformatted October 2020

6. Institute of Electrical and Electronics Engineers, "Guide for Class 1E Control Switch Boards for Nuclear Power Generating Stations," IEEE-420-1973.
7. Institute of Electrical and Electronics Engineers, "Recommended Practice for Maintenance, Testing, and Replacement of Large Stationary Type Power Plant RN 96-070 and Substation Lead Storage Batteries," IEEE-450-1987.
8. Institute of Electrical and Electronics Engineers, "Criteria for Class 1E Electric Systems for Nuclear Power Generating Systems," IEEE-308-1971.
9. Institute of Electrical and Electronics Engineers, "Standard for Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations," IEEE-383-1974.
10. "Electric Hydrogen Recombiner for PWR Containments," WCAP-7709-L, Supplement 7, (Proprietary) and WCAP-7820, Supplement 7 (non-Proprietary),

August, 1977.

11. Institute of Electrical and Electronics Engineers, "Qualifying Class 1E Electric Equipment for Nuclear Power Generating Stations, General Guide,"

IEEE-323-1971.

12. Institute of Electrical and Electronics Engineers, "Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations,"

RN

13. Fire Protection (FP) DBD 98-101 18-019
14. Institute of Electrical and Electronics Engineers, "Criteria for Separation of Class 1E Equipment and Circuits," IEEE-384, 1974.
15. 10 CFR Part 50, Section 50.63, "Loss of all Alternating Current Power."
16. U. S. Nuclear Regulatory Commission Regulatory Guide 1.155, "Station Blackout."
17. NUMARC 87-00, Nuclear Management and Resources Council, Inc., "Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactor."
18. Calculation No. DC08500-022, "Determination of Maximum Sidewall Pressure RN 99-014 Imposed on Cable in Cable Tray as a Result of Cable Weight."

8.3-44 Reformatted October 2020

TABLE 8.3-1 MAJOR ELECTRICAL EQUIPMENT Equipment Tag Numbers Description and ratings RN Unit Generator XGN1-EG 1,137,680 kVA, 0.905 pf,05-038 22 kV, 1800 rpm, 3, 60 Hz Standby Diesel Generator XEG0001A, B-E (Engine) 4250 kW. 7.2 kV, 0.8 pf, 3, XEG0001A, B-G (Generator) 60 Hz RN Main Transformer XTF1-EG 1100/1232 MVA, 55C/65C,99-006 FOA, 242-22 kV, 3, 60 Hz 09-014 Unit Auxiliary Transformer XTF2-ES 48/64 MVA, 55C, 22-7.2/7.2/7.2 kV Emergency Auxiliary XTF31-ES 24/32/40/44.8 MVA, Transformer XTF32-ES 55/55/55/65 with nominal 8.0% impedance from HV to LV, based upon 24 MVA base, 230-7.2/7.2 kV Engineered Safety XTF4-ES 10/12.5/14 MVA, 115/7.2 kV Transformer XTF5-ES 7.2 kV Line Voltage XTF6-ES 1500 kVA, 55° C rise, Class Regulator OA, 7.2 kV +/- 10% in RN 32 - 5/8% steps, 1200 Amps,99-006 1.12% based on 15 MVA, 3, 60 Hz Generator Circuit Breaker XCB0010-EG 1, 60 Hz, 22 kV (nominal) 36 kV (max), interrupting RN rating of 210 kA (Sym 10-018 System Source) and 150 kA (Sym Gen Source).

8.3-45 Reformatted October 2020

TABLE 8.3-2 SYMMETRICAL INTERRUPTING CAPACITY FOR 480 VOLT UNIT SUBSTATION CUBICLES Symmetrical Interrupting Capacity Frame Size (amps) Instantaneous Trip (amps) Delayed Trip (amps) 600 30,000 22,000 1600 50,000 50,000 2000 65,000 55,000 3000 65,000 65,000 8.3-46 Reformatted October 2020

FSAR TABLE 8.3-3 PART A1 Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data Load Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<------------------------> Sequencer <-------------------------------> <--------------------> <-------------------------------> <--------------------> <-------------------------------> <-------------------->

Tag Number Hp/kVA kW Volts (Sec.) (9) Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Notes XMC1B1X XTG00001 TURBINE TURNING GEAR 60.0 52.2 460 N/A NO 0.0 0.0 54.8 63.0 NO 0.0 0.0 54.8 63.0 NO 54.8 63.0 54.8 63.0 1,25 Total Load On Motor Control Center: XMC1B1X 0.0 0.0 54.8 63.0 0.0 0.0 54.8 63.0 54.8 63.0 54.8 63.0 XMC1DA2X APN08004A LIGHTING PANEL #4, ESSENTIAL PANEL, TRAIN A 10.0 8.5 480 0 N/A 3.4 4.0 3.4 4.0 N/A 3.4 4.0 3.4 4.0 N/A 3.4 4.0 3.4 4.0 APN08012A LIGHTING PANEL #13, ESSENTIAL PANEL, TRAIN A 30.0 25.5 480 0 N/A 22.9 27.0 22.9 27.0 N/A 22.9 27.0 22.9 27.0 N/A 1.7 2.0 22.9 27.0 APN08034 LIGHTING PANEL #34, ESSENTIAL PANEL 65.0 55.3 480 0 N/A 15.3 18.0 15.3 18.0 N/A 15.3 18.0 15.3 18.0 N/A 15.3 18.0 15.3 18.0 APN08035A LIGHTING PANEL #35, ESSENTIAL PANEL (TRAIN A POWER FEED) 10.0 8.5 480 0 N/A 4.3 5.0 4.3 5.0 N/A 4.3 5.0 4.3 5.0 N/A 4.3 5.0 4.3 5.0 APN08053A ESSENTIAL OUTDOOR LTG. PNL A 49.0 41.6 480 0 N/A 41.6 49.0 41.6 49.0 N/A 41.6 49.0 41.6 49.0 N/A 41.6 49.0 41.6 49.0 XBC1A DC 1A BATTERY CHARGER 43.3 32.5 480 0 N/A 7.6 10.1 7.6 10.1 N/A 7.6 10.1 7.6 10.1 N/A 7.6 10.1 7.6 10.1 XFN00026 CONTROLLED ACCESS COOLING SUPPLY FAN MOTOR 15.0 12.8 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 22 XFN00028A CONTROLLED ACCESS EXHAUST FAN A 50.0 42.5 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 22 XFN00030A CONT RM EMERGENCY FILTERING SYS FAN A 40.0 33.1 460 0 YES 33.1 40.0 33.1 40.0 YES 33.1 40.0 33.1 40.0 YES 33.1 40.0 0.0 0.0 XFN00032A CONTROL ROOM COOLING UNIT A FAN 25.0 20.8 460 0 YES 14.9 18.0 14.9 18.0 YES 14.9 18.0 14.9 18.0 YES 14.9 18.0 14.9 18.0 XFN00036A RELAY ROOM SUPPLY FAN A 15.0 12.4 460 0 YES 9.1 11.0 9.1 11.0 YES 9.1 11.0 9.1 11.0 YES 9.1 11.0 9.1 11.0 XFN00038A BATT&CHG RM AIR HANDLING UNIT A SUP FAN 10.0 8.2 460 0 YES 5.7 7.0 5.7 7.0 YES 5.7 7.0 5.7 7.0 YES 5.7 7.0 5.7 7.0 XFN00039A BATTERY ROOM EXHAUST FAN A 5.0 4.3 460 0 YES 0.5 0.6 0.5 0.6 YES 0.5 0.6 0.5 0.6 YES 0.5 0.6 0.5 0.6 XFN00041A COMPUTER ROOM SUPPLY FAN A (UNIT 1) 5.0 4.3 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 22 XFN00050 ESF SWGR ROOM 1DA AH UNIT SUPPLY FAN 25.0 20.8 460 0 YES 7.5 9.0 7.5 9.0 YES 7.5 9.0 7.5 9.0 YES 7.5 9.0 7.5 9.0 XFN00055 CONTROL ACCESS LAB HOOD SUPPLY FAN 5.0 4.3 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 22 XFN00081A SW BSTR PUMP AREA AH UNIT A SUPPLY FAN 3.0 2.3 460 0 YES 2.3 3.0 2.3 3.0 YES 2.3 3.0 2.3 3.0 YES 2.3 3.0 0.0 0.0 5 XFN00083A EMER FW PUMP AREA AH UNIT A SUPPLY FAN 5.0 3.6 460 0 YES 2.2 3.0 0.0 0.0 YES 2.2 3.0 0.0 0.0 YES 2.2 3.0 0.0 0.0 23 8.3-47 Reformatted December 2018

FSAR TABLE 8.3-3 PART A1 Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data Load Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<------------------------> Sequencer <-------------------------------> <--------------------> <-------------------------------> <--------------------> <-------------------------------> <-------------------->

Tag Number Hp/kVA kW Volts (Sec.) (9) Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Notes XMC1DA2X (Continued)

XFN00087A CONTROLLED ACCESS LAB HOOD EXHAUST FAN A 5.0 4.3 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 22 XFN00106A SPEED SWITCH ROOMS AH UNIT A SUPPLY FAN 10.0 8.2 460 0 YES 5.7 7.0 5.7 7.0 YES 5.7 7.0 5.7 7.0 YES 5.7 7.0 5.7 7.0 XHX00001A CNTRL PWR HVAC SYSTEM MECHANICAL WATER CHILLER A 3.0 2.4 480 0 N/A 2.4 3.4 2.4 3.4 N/A 2.4 3.4 2.4 3.4 N/A 2.4 3.4 2.4 3.4 RN 17-022 XHX00001C CNTRL PWR HVAC SYSTEM MECH. WATER CHILLER C CHANNEL A 15.0 12.8 480 0 N/A 6.4 7.5 6.4 7.5 N/A 6.4 7.5 6.4 7.5 N/A 6.4 7.5 6.4 7.5 XTF09005A RECEPTACLE TRANSFORMER #5 10.0 8.5 480 0 N/A 4.3 5.0 4.3 5.0 N/A 4.3 5.0 4.3 5.0 N/A 4.3 5.0 4.3 5.0 XTF1FA XFMR FOR 120V AC NSSS INSTR. MAIN DISTR. PNL 1FA 25.0 21.3 480 0 N/A 7.1 8.3 7.1 8.3 N/A 7.1 8.3 7.1 8.3 N/A 7.1 8.3 7.1 8.3 RN Total Load On Motor Control Center: XMC1DA2X 201.2 241.6 199.0 238.7 201.2 241.6 199.0 238.7 201.2 241.6 163.6 195.7 17-022 XMC1DA2Y IRM00003 RADIATION MONITORING MAIN PLANT VENT EXHAUST PUMP 1 1.0 0.8 460 0 YES 0.8 1.0 0.8 1.0 YES 0.8 1.0 0.8 1.0 YES 0.8 1.0 0.8 1.0 4 IRM00004 RADIATION MONITORING REACTOR BUILDING PURGE EXHAUST PUMP 1.0 0.8 460 0 YES 0.8 1.0 0.8 1.0 YES 0.8 1.0 0.8 1.0 YES 0.8 1.0 0.8 1.0 4 XBC1A-1B TRAIN A DC 1A-1B BACKUP BATTERY CHRG 43.3 32.5 480 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 21 XBC1X BATTERY CHARGER 1X 86.7 65.0 480 0 N/A 39.0 52.0 39.0 52.0 N/A 39.0 50.2 39.0 52.0 N/A 39.0 52.0 39.0 52.0 19 RN 17-033 XFN00046A CHARGING/SI PUMP RM 1 COOLING UNIT FAN 3.0 2.3 460 0 YES 2.3 3.0 2.3 3.0 YES 2.3 3.0 0.0 0.0 YES 2.3 3.0 0.0 0.0 XFN00049A RHR/SPRAY PUMP ROOM 1 COOLING UNIT FAN 3.0 2.3 460 0 YES 2.3 3.0 2.3 3.0 YES 2.3 3.0 2.3 3.0 YES 2.3 3.0 2.3 3.0 XFN00132 AUX BLDG MCC-SWGR ROOM COOLING UNIT FAN 3.0 2.3 460 0 YES 1.5 2.0 1.5 2.0 YES 1.5 2.0 1.5 2.0 YES 1.5 2.0 1.5 2.0 XIT05901 INSTRUMENT SUPPLY INVERTERS 10.0 8.5 480 0 N/A 8.7 10.2 8.7 10.2 N/A 8.7 10.2 8.7 10.2 N/A 8.7 10.2 8.7 10.2 RN 17-022 XIT05902 INSTRUMENT SUPPLY INVERTERS 10.0 8.5 480 0 N/A 5.4 6.3 5.4 6.3 N/A 5.4 6.3 5.4 6.3 N/A 5.4 6.3 5.4 6.3 RN 17-022 XMC1DA2Y HTR SPACE HTRS FOR XMC1DA2Y 3.4 3.4 480 N/A N/A 3.4 3.4 3.4 3.4 N/A 3.4 3.4 3.4 3.4 N/A 3.4 3.4 3.4 3.4 XPN00040 TRAIN A PUMP AUXILIARIES TRANSFER PNL-XPP0043C 5.0 4.3 480 0 YES 0.8 1.0 0.8 1.0 YES 0.8 1.0 0.8 1.0 YES 0.8 1.0 0.8 1.0 17 XPN02023 REFLING WTR STRGE TNK & PIPNG HEAT TRACNG CNTRALZED CONT PAN RN 12-006 30.0 30.0 480 0 YES 22.7 22.7 22.7 22.7 YES 22.7 22.7 22.7 22.7 YES 22.7 22.7 22.7 22.7 17-033 XPN02007 REAC MU WTR STRGE TANK&PIPING HEAT TRACING CENTRLZD CONTROL 20.0 20.0 480 0 YES 17.0 17.0 17.0 17.0 YES 17.0 17.0 17.0 17.0 YES 17.0 17.0 17.0 17.0 8.3-48 Reformatted December 2018

FSAR TABLE 8.3-3 PART A1 Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data Load Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<------------------------> Sequencer <-------------------------------> <--------------------> <-------------------------------> <--------------------> <-------------------------------> <-------------------->

Tag Number Hp/kVA kW Volts (Sec.) (9) Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Notes XMC1DA2Y (Continued)

XPN02021 SODIUM HYDROXIDE SPRAY SYSTEM HEAT TRACING CENTRLZD CONRL P RN 3.0 3.0 480 0 YES 0.0 0.0 0.0 0.0 YES 0.0 0.0 0.0 0.0 YES 0.0 0.0 0.0 0.0 12-006 XPN07215A 480V PWR POST ACCIDENT ANALYZER SYSTEM 1.5 1.3 480 0 N/A 0.0 0.0 1.3 1.5 N/A 0.0 0.0 0.0 0.0 N/A 0.0 0.0 0.0 0.0 1 XPP00013A BORIC ACID PUMPS 15.5 13.2 460 0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 XPP00043A PP AUX OIL CHARGING/SI PUMP A AUXILIARY OIL PUMP ALOP1 2.0 1.7 460 0 YES 1.2 1.4 1.2 1.4 YES 1.2 1.4 1.2 1.4 YES 1.2 1.4 0.0 0.0 XTF04006 SECURITY SYSTEM TRANSFER SWITCH (FEEDS XTF05014)

RN 37.5 31.9 480 0 N/A 27.1 31.8 27.1 31.8 N/A 27.1 31.8 27.1 31.8 N/A 27.1 31.8 27.1 31.8 17 17-033 XTF05032 480/240/120V XFMR FOR METEOROLOGICAL TOWER 6.0 5.1 480 0 N/A 4.6 5.4 4.6 5.4 N/A 4.6 5.4 4.6 5.4 N/A 4.6 5.4 4.6 5.4 XTF08023A XFMR FOR LIGHTING PANEL 23, ESSENTIAL PANEL, TRAIN A 15.0 12.8 480 0 N/A 7.6 9.0 7.6 9.0 N/A 7.6 9.0 7.6 9.0 N/A 7.6 9.0 7.6 9.0 RN Total Load On Motor Control Center: XMC1DA2Y 145.4 170.4 146.7 171.9 145.4 170.4 143.1 167.4 145.4 170.4 141.9 166.0 17-033 17-022 XMC1DA2Z APN08037A LIGHTING PANEL #37, ESSENTIAL PANEL 45.0 38.3 480 0 N/A 2.5 3.0 2.5 3.0 N/A 2.5 3.0 2.5 3.0 N/A 2.5 3.0 2.5 3.0 XAC00008A AIR STARTING PACKAGE - DIESEL GEN.

15.0 12.8 460 0 YES 13.2 15.5 0.0 0.0 YES 13.2 15.5 0.0 0.0 YES 13.2 15.5 0.0 0.0 24 XAC00008B AIR STARTING PACKAGE - DIESEL GEN.

15.0 12.8 460 0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 XFN00075A DG AREA A VENTILATION AIR SUPPLY FAN A 30.0 24.7 460 0 YES 20.6 25.0 20.6 25.0 YES 20.6 25.0 20.6 25.0 YES 20.6 25.0 20.6 25.0 XFN00075B DG AREA A VENTILATION AIR SUPPLY FAN B 30.0 24.7 460 0 YES 20.6 25.0 20.6 25.0 YES 20.6 25.0 20.6 25.0 YES 20.6 25.0 20.6 25.0 XMC1DA2Z HTR SPACE HTRS FOR XMC1DA2Z 0.7 0.7 480 N/A N/A 0.7 0.7 0.7 0.7 N/A 0.7 0.7 0.7 0.7 N/A 0.7 0.7 0.7 0.7 XPN00047 NO. 1A DIESEL POWER PANEL 56.0 47.6 480 0 N/A 47.6 56.0 47.6 56.0 N/A 47.6 56.0 47.6 56.0 N/A 47.6 56.0 47.6 56.0 XPP00004A DG FUEL OIL TRANSFER PUMP 4A 1.0 0.7 460 0 YES 0.4 0.6 0.4 0.6 YES 0.4 0.6 0.4 0.6 YES 0.4 0.6 0.4 0.6 XPP00141A DG FUEL OIL TRANSFER PUMP 141A 1.0 0.7 460 0 YES 0.4 0.6 0.4 0.6 YES 0.4 0.6 0.4 0.6 YES 0.4 0.6 0.4 0.6 XPP00146A DIESEL GENERATOR BLDG SUMP PUMP 2.0 1.7 460 0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 22 Total Load On Motor Control Center: XMC1DA2Z 106.1 126.4 93.0 110.9 106.1 126.4 93.0 110.9 106.1 126.4 93.0 110.9 8.3-49 Reformatted December 2018

FSAR TABLE 8.3-3 PART A1 Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data Load Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<------------------------> Sequencer <-------------------------------> <--------------------> <-------------------------------> <--------------------> <-------------------------------> <-------------------->

Tag Number Hp/kVA kW Volts (Sec.) (9) Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Notes XMC1EA1X APN04006 SW BLDG POWER PANEL 1 60.0 60.0 480 0 N/A 17.0 17.0 17.0 17.0 N/A 17.0 17.0 17.0 17.0 N/A 17.0 17.0 17.0 17.0 APN08031A LIGHTING PANEL 31, ESSENTIAL PANEL, TRAIN A POWER FEED 10.0 8.5 480 0 N/A 6.0 7.0 6.0 7.0 N/A 6.0 7.0 6.0 7.0 N/A 6.0 7.0 6.0 7.0 XFN00080A SERVICE WATER BUILDING SUPPLY FAN A 50.0 41.9 460 0 YES 48.6 58.0 48.6 58.0 YES 48.6 58.0 48.6 58.0 YES 48.6 58.0 48.6 58.0 XPP00147A SERVICE WATER PUMP HOUSE SUMP PUMP 1.0 0.8 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 22 XRS00002A SW TRAVELING SCREEN A RN 1.0 0.8 460 0 NO 0.8 1.0 0.8 1.0 NO 0.8 1.0 0.8 1.0 NO 0.8 1.0 0.8 1.0 22 15-025 XTF09016 RECEPTACLE PANEL 16 10.0 8.5 480 0 N/A 4.3 5.0 4.3 5.0 N/A 4.3 5.0 4.3 5.0 N/A 4.3 5.0 4.3 5.0 Total Load On Motor Control Center: XMC1EA1X 76.7 88.0 76.7 88.0 76.7 88.0 76.7 88.0 76.7 88.0 76.7 88.0 XMC1EC1X XRS00002C SW TRAVELING SCREEN C RN 1.0 0.8 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 16,22 15-025 Total Load On Motor Control Center: XMC1EC1X 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 XSW1DA MPP00001A COMPONENT COOLING PUMP A MOTOR 600.0 548.4 6900 15 YES 502.7 550.0 502.7 550.0 YES 502.7 550.0 502.7 550.0 YES 502.7 550.0 502.7 550.0 2,11,30 MPP00001C COMPONENT COOLING PUMP C MOTOR 600.0 548.4 6900 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 16 XPP00021A EMERGENCY FEEDWATER PUMP A 600.0 495.0 6900 20 YES 453.8 550.0 0.0 0.0 YES 453.8 550.0 0.0 0.0 YES 453.8 550.0 0.0 0.0 11 XPP00038A REACTOR BUILDING SPRAY PUMP A 400.0 352.0 6900 N/A YES 352.0 400.0 369.6 420.0 YES 352.0 400.0 352.0 400.0 YES 0.0 0.0 0.0 0.0 3 XPP00043A CHARGING/SI PUMP A 900.0 829.8 6900 0 YES 811.4 880.0 811.4 880.0 YES 811.4 880.0 0.0 0.0 YES 682.3 740.0 0.0 0.0 14 XPP00043C CHARGING/SI PUMP C 900.0 829.8 6900 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 16 XTF04101 PRESSURIZER HEATERS BACKUP GROUP 1 750.0 750.0 480 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 537.0 537.0 0.0 0.0 1 Total Load On Switchgear: XSW1DA 2119.8 2380.0 1683.7 1850.0 2119.8 2380.0 854.7 950.0 2175.8 2377.0 502.7 550.0 8.3-50 Reformatted December 2018

FSAR TABLE 8.3-3 PART A1 Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data Load Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<------------------------> Sequencer <-------------------------------> <--------------------> <-------------------------------> <--------------------> <-------------------------------> <-------------------->

Tag Number Hp/kVA kW Volts (Sec.) (9) Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Notes XSW1DA1 APN01DA1 SWITCHGEAR XSW1DA1 DISTRIBUTION PANEL 10.0 8.5 480 0 N/A 7.6 9.0 7.6 9.0 N/A 7.6 9.0 7.6 9.0 N/A 7.6 9.0 7.6 9.0 RN XFN00019A AUXILIARY BUILDING CHARCOAL EXHAUST FAN A 10-014 125.0 106.3 460 N/A NO 0.0 0.0 106.3 125.0 NO 0.0 0.0 106.3 125.0 NO 106.3 125.0 106.3 125.0 1,26 XFN00019C AUXILIARY BUILDING CHARCOAL EXHAUST FAN C 125.0 106.3 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 XFN00064A MFN00096A REACTOR BUILDING COOLING UNIT FAN (MFN0096A) 275.0 244.5 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 XFN00064A MFN00097A REACTOR BUILDING COOLING UNIT FAN (MFN0097A) 75.0 58.4 460 25 YES 70.1 90.0 70.1 90.0 YES 70.1 90.0 70.1 90.0 YES 70.1 90.0 70.1 90.0 6,14,27 XFN00065A MFN00096C REACTOR BUILDING COOLING UNIT FAN (MFN0096C) 275.0 244.5 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 XFN00065A MFN00097C REACTOR BUILDING COOLING UNIT FAN (MFN0097C) 75.0 58.4 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 14,27 XHX00001A HVAC SYSTEM MECHANICAL WATER CHILLER A 321.0 288.9 460 30 YES 288.9 321.0 288.9 321.0 YES 288.9 321.0 288.9 321.0 YES 288.9 321.0 288.9 321.0 13 XHX00001C TRAIN A HVAC SYSTEM MECHANICAL WATER CHILLER C - LOAD FOR TRAIN A 321.0 288.9 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 16 XPP00031A RESIDUAL HEAT REMOVAL PUMP A 300.0 274.2 460 0 YES 260.5 285.0 274.2 300.0 YES 260.5 285.0 260.5 285.0 YES 260.5 285.0 274.2 300.0 XPP00040A REACTOR MAKE-UP WATER PUMP A 60.0 51.0 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 XPP00045A SERVICE WATER BOOSTER PUMP A 350.0 322.0 460 35 YES 230.0 250.0 230.0 250.0 YES 230.0 250.0 230.0 250.0 YES 230.0 250.0 0.0 0.0 7,14 RN Total Load On Switchgear: XSW1DA1 857.2 955.0 977.1 1095.0 857.2 955.0 963.4 1080.0 963.4 1080.0 747.1 845.0 10-014 XSW1DA2 APN01DA2 SWITCHGEAR XSW1DA2 DISTRIBUTION PANEL 10.0 8.5 480 0 N/A 7.6 9.0 7.6 9.0 N/A 7.6 9.0 7.6 9.0 N/A 7.6 9.0 7.6 9.0 XFN00023A FUEL BUILDING EXHAUST FAN 23A 60.0 49.9 460 25 YES 46.5 56.0 46.5 56.0 YES 46.5 56.0 46.5 56.0 YES 46.5 56.0 46.5 56.0 XHR00004A HYDROGEN RECOMBINER A 75.0 75.0 480 N/A NO 0.0 0.0 75.0 75.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 1,28 XIT05936 TRAIN A INCOMING TRAIN A POWER 125.0 125.0 480 0 N/A 60.4 60.4 60.4 60.4 N/A 60.4 60.4 60.4 60.4 N/A 60.4 60.4 60.4 60.4 15 RN 17-033 XPP00032A SPENT FUEL PIT COOLING PUMP A 75.0 63.0 460 N/A NO 0.0 0.0 50.4 60.0 NO 0.0 0.0 50.4 60.0 NO 50.4 60.0 50.4 60.0 1,29 XPP00048A CHILLED WATER PUMP A 60.0 55.8 460 10 YES 44.6 48.0 44.6 48.0 YES 44.6 48.0 44.6 48.0 YES 44.6 48.0 44.6 48.0 13 XPP00048C TRAIN A CHILLED WATER PUMP C - LOAD FOR TRAIN A 50.0 46.0 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 16 XSW1DA2 BUS 1.8 0.0 480 N/A 0.0 1.8 0.0 1.8 0.0 1.8 0.0 1.8 0.0 1.8 0.0 1.8 RN 17-033 Total Load On Switchgear: XSW1DA2 159.3 175.3 284.7 310.3 159.3 175.3 209.7 235.3 209.7 235.3 209.7 235.3 8.3-51 Reformatted December 2018

FSAR TABLE 8.3-3 PART A1 Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data Load Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<------------------------> Sequencer <-------------------------------> <--------------------> <-------------------------------> <--------------------> <-------------------------------> <-------------------->

Tag Number Hp/kVA kW Volts (Sec.) (9) Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Notes XSW1EA MPP00039A SERVICE WATER PUMP A MOTOR 700.0 645.4 6900 10 YES 599.3 650.0 599.3 650.0 YES 599.3 650.0 599.3 650.0 YES 599.3 650.0 599.3 650.0 12 MPP00039C TRAIN A SERVICE WATER PUMP C MOTOR - LOAD FOR TRAIN A 700.0 645.4 6900 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 16 Total Load On Switchgear: XSW1EA 599.3 650.0 599.3 650.0 599.3 650.0 599.3 650.0 599.3 650.0 599.3 650.0 XSW1EA1 APN01EA1 SWITCHGEAR XSW1EA1 DISTRIBUTION PANEL 10.0 8.5 480 0 N/A 7.6 9.0 7.6 9.0 N/A 7.6 9.0 7.6 9.0 N/A 7.6 9.0 7.6 9.0 Total Load On Switchgear: XSW1EA1 7.6 9.0 7.6 9.0 7.6 9.0 7.6 9.0 7.6 9.0 7.6 9.0 RN Subtotal Load On The Diesel Generator: 4257.1 4794.0 4080.7 4555.1 4257.1 4794.0 3177.1 3580.6 4502.6 5014.0 2558.9 2886.2 17-022 Cable Losses: 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 RN Transformer Losses: 31.0 31.0 31.0 31.0 31.0 31.0 31.0 31.0 31.0 31.0 31.0 31.0 10-014 Generator Exciter Load: 26.0 31.0 26.0 31.0 26.0 31.0 26.0 31.0 26.0 31.0 26.0 31.0 17-022 17-033 Total Generator Load With Optional Loads: 4324.1 4866.0 4147.7 4627.1 4324.1 4866.0 3244.1 3652.6 4569.6 5086.0 2625.9 2958.2 10 Optional Loads: 0.0 0.0 287.8 324.5 0.0 0.0 211.5 248.0 748.5 785.0 211.5 248.0 RN Total Generator Load Without Optional Loads: 4324.1 4866.0 3859.9 4302.6 4324.1 4866.0 3032.6 3404.6 3821.1 4301.0 2414.4 2710.2 17-022 Total Records Printed: 93 8.3-52 Reformatted December 2018

FSAR TABLE 8.3-3 PART A1 Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A Notes:

1 This is an optional load which can be started manually. It may be added if the DG loading conditions permit, and this load was not considered for fuel oil storage requirements since it is not a required load.

2 The pump is normally in low speed but is assumed to be auto-started in high speed. The speed change switch is manually operated. The pump will be operated in high speed for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for the first 7 days following a DBE. If both DGs are running, only one train's pump will be in high speed during the plant shutdown.

3 The pump starts on receipt of a spray initiation signal.

4 The motor is not required for the accident scenarios but the motor will be running as it is not locked out by the load sequencer.

5 The motor is running in the Hot Standby scenario as the SWBP is automatically started by the load sequencer.

6 The motor is not required for the LOOP - Hot standby / Cold shutdown scenarios but is auto started by the load sequencer and expected to remain on for air circulation related purposes.

7 The motor is not required for the LOOP - Hot standby scenario but is auto started by the load sequencer.

8 The equipment is required to be operable for six months following an accident.

9 Time 0 indicates the emergency diesel generator has started and reached no load speed and voltage, at which the circuit breaker connecting to the 7200 volt bus has closed.

10 Total includes the RHR pump and all manual loads whose application will be limited so that neither the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating (4676 kW) is exceeded for more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> nor the continuous rating of 4250 kW is exceeded.

11 The required safety function is for emergency core cooling.

12 The required safety function is for emergency core cooling and containment cooling.

13 The required safety function is for equipment area cooling.

14 The required safety function is for containment cooling.

15 This inverter is assumed to be running on this diesel generator. It is fed via a manual switchgear breaker.

16 The "C" train equipment is assumed to be not running as the normal train equipment is running.

17 This equipment is assumed to be supplied from this diesel generator.

18 Generator efficiency is assumed to be taken into account by the diesel manufacturer as the load limit is based on generator output kW (including the exciter) as monitored at the MCB.

19 The dc powered oil pumps associated with the turning gear are included in the battery charger loads.

20 For the Auto-Start columns, YES means the load is able to automatically start based on its control circuitry, NO means it does not, and N/A means the load is continuous and not subject to starting and stopping.

21 The normal battery charger is assumed in service.

22 The load is locked out on receipt of an SI signal.

23 The fan runs only when the EFWP is running.

24 The compressor runs only to recharge the air start system. It is assumed to be running in the first hour only.

25 XTG00001 will be running less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> total during the 7 days following a DBE.

26 The fan is expected to be manually started within the first 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> and is therefore shown as a load for the LOOP/Hot Standby mode.

27 Only 1 out of 2 RBCU fans is required to run post accident as selected.

28 The H2 recombiner will be operated as needed to support post accident response.

29 The pump will be operated as needed to maintain spent fuel pool temperatures within acceptable limits.

30 The component cooling water pump slow speed ratings are 250hp, .8094 PF, .9114 Efficiency, and 250kVA.

8.3-53 Reformatted December 2018

FSAR TABLE 8.3-3 PART A2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XMC1B1X XTG00001 TURBINE TURNING GEAR 60.0 57.0 0.870 N/A NO 0.0 0.0 0.0 63.0 52.0 59.8 0.0 0.0 0.0 63.0 52.0 59.8 63.0 52.0 59.8 63.0 52.0 59.8 1,25 460 49.6 0.903 Total Load On Motor Control Center: XMC1B1X 0.0 0.0 52.0 59.8 0.0 0.0 52.0 59.8 52.0 59.8 52.0 59.8 XMC1DA2X APN08004A LIGHTING PANEL #4, ESSENTIAL PANEL, TRAIN A 10.0 10.0 0.850 0 N/A 4.0 3.4 4.0 4.0 3.4 4.0 4.0 3.4 4.0 4.0 3.4 4.0 4.0 3.4 4.0 4.0 3.4 4.0 480 8.5 APN08012A LIGHTING PANEL #13, ESSENTIAL PANEL, TRAIN A 30.0 30.0 0.850 0 N/A 27.0 22.9 27.0 27.0 22.9 27.0 27.0 22.9 27.0 27.0 22.9 27.0 2.0 1.7 2.0 27.0 22.9 27.0 480 25.5 APN08034 LIGHTING PANEL #34, ESSENTIAL PANEL 65.0 65.0 0.850 0 N/A 18.0 15.3 18.0 18.0 15.3 18.0 18.0 15.3 18.0 18.0 15.3 18.0 18.0 15.3 18.0 18.0 15.3 18.0 480 55.3 APN08035A LIGHTING PANEL #35, ESSENTIAL PANEL (TRAIN A POWER FEED) 10.0 10.0 0.850 0 N/A 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 480 8.5 APN08053A ESSENTIAL OUTDOOR LTG. PNL A 49.0 49.0 0.850 0 N/A 49.0 41.6 49.0 49.0 41.6 49.0 49.0 41.6 49.0 49.0 41.6 49.0 49.0 41.6 49.0 49.0 41.6 49.0 480 41.6 XBC1A DC 1A BATTERY CHARGER 43.3 43.3 0.750 0 N/A 10.1 7.6 10.1 10.1 7.6 10.1 10.1 7.6 10.1 10.1 7.6 10.1 10.1 7.6 10.1 10.1 7.6 10.1 480 32.5 XFN00026 CONTROLLED ACCESS COOLING SUPPLY FAN MOTOR 15.0 15.2 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 22 460 12.9 0.865 XFN00028A CONTROLLED ACCESS EXHAUST FAN A 50.0 48.5 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 22 460 41.3 0.904 XFN00030A CONT RM EMERGENCY FILTERING SYS FAN A 40.0 39.3 0.828 0 YES 40.0 32.5 39.3 40.0 32.5 39.3 40.0 32.5 39.3 40.0 32.5 39.3 40.0 32.5 39.3 0.0 0.0 0.0 460 32.5 0.918 XFN00032A CONTROL ROOM COOLING UNIT A FAN 25.0 25.5 0.830 0 YES 18.0 15.3 18.4 18.0 15.3 18.4 18.0 15.3 18.4 18.0 15.3 18.4 18.0 15.3 18.4 18.0 15.3 18.4 460 21.2 0.880 XFN00036A RELAY ROOM SUPPLY FAN A 15.0 15.6 0.830 0 YES 11.0 9.5 11.4 11.0 9.5 11.4 11.0 9.5 11.4 11.0 9.5 11.4 11.0 9.5 11.4 11.0 9.5 11.4 460 12.9 0.865 XFN00038A BATT&CHG RM AIR HANDLING UNIT A SUP FAN 10.0 10.7 0.820 0 YES 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 460 8.8 0.850 8.3-54 Reformatted December 2018

FSAR TABLE 8.3-3 PART A2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XMC1DA2X (Continued)

XFN00039A BATTERY ROOM EXHAUST FAN A 5.0 5.5 0.850 0 YES 0.6 0.6 0.7 0.6 0.6 0.7 0.6 0.6 0.7 0.6 0.6 0.7 0.6 0.6 0.7 0.6 0.6 0.7 460 4.7 0.800 XFN00041A COMPUTER ROOM SUPPLY FAN A (UNIT 1) 5.0 5.3 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 22 460 4.5 0.831 XFN00050 ESF SWGR ROOM 1DA AH UNIT SUPPLY FAN 25.0 25.5 0.830 0 YES 9.0 7.6 9.2 9.0 7.6 9.2 9.0 7.6 9.2 9.0 7.6 9.2 9.0 7.6 9.2 9.0 7.6 9.2 460 21.2 0.880 XFN00055 CONTROL ACCESS LAB HOOD SUPPLY FAN 5.0 5.3 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 22 460 4.5 0.831 XFN00081A SW BSTR PUMP AREA AH UNIT A SUPPLY FAN 3.0 3.7 0.760 0 YES 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 0.0 0.0 0.0 5 460 2.8 0.799 XFN00083A EMER FW PUMP AREA AH UNIT A SUPPLY FAN 5.0 6.2 0.720 0 YES 3.0 2.7 3.7 0.0 0.0 0.0 3.0 2.7 3.7 0.0 0.0 0.0 3.0 2.7 3.7 0.0 0.0 0.0 23 460 4.5 0.831 XFN00087A CONTROLLED ACCESS LAB HOOD EXHAUST FAN A 5.0 5.3 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 22 460 4.5 0.831 XFN00106A SPEED SWITCH ROOMS AH UNIT A SUPPLY FAN 10.0 10.7 0.820 0 YES 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 460 8.8 0.850 XHX00001A CNTRL PWR HVAC SYSTEM MECHANICAL WATER CHILLER A 15.0 15.0 0.850 0 N/A 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 480 12.8 XHX00001C CNTRL PWR HVAC SYSTEM MECH. WATER CHILLER C CHANNEL A 15.0 15.0 0.850 0 N/A 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 480 12.8 XTF09005A RECEPTACLE TRANSFORMER #5 10.0 10.0 0.850 0 N/A 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 480 8.5 XTF1FA XFMR FOR 120V AC NSSS INSTR. MAIN DISTR. PNL 1FA 25.0 25.0 0.850 0 N/A 8.3 7.1 8.3 8.3 7.1 8.3 8.3 7.1 8.3 8.3 7.1 8.3 8.3 7.1 8.3 8.3 7.1 8.3 480 21.3 Total Load On Motor Control Center: XMC1DA2X 202.4 242.8 199.8 239.1 202.4 242.8 199.8 239.1 181.2 217.8 164.5 196.1 8.3-55 Reformatted December 2018

FSAR TABLE 8.3-3 PART A2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XMC1DA2Y IRM00003 RADIATION MONITORING MAIN PLANT VENT EXHAUST PUMP 1 1.0 1.3 0.750 0 YES 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 4 460 1.0 0.765 IRM00004 RADIATION MONITORING REACTOR BUILDING PURGE EXHAUST PUMP 1.0 1.3 0.750 0 YES 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 4 460 1.0 0.765 XBC1A-1B TRAIN A DC 1A-1B BACKUP BATTERY CHRG 43.3 43.3 0.750 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 21 480 32.5 XBC1X BATTERY CHARGER 1X 86.7 86.7 0.750 0 N/A 52.0 39.0 52.0 52.0 39.0 52.0 52.0 39.0 52.0 52.0 39.0 52.0 52.0 39.0 52.0 52.0 39.0 52.0 19 RN 480 65.0 17-033 XFN00046A CHARGING/SI PUMP RM 1 COOLING UNIT FAN 3.0 3.7 0.760 0 YES 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 0.0 0.0 0.0 3.0 2.8 3.7 0.0 0.0 0.0 460 2.8 0.799 XFN00049A RHR/SPRAY PUMP ROOM 1 COOLING UNIT FAN 3.0 3.7 0.760 0 YES 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 460 2.8 0.799 XFN00132 AUX BLDG MCC-SWGR ROOM COOLING UNIT FAN 3.0 3.7 0.760 0 YES 2.0 1.9 2.5 2.0 1.9 2.5 2.0 1.9 2.5 2.0 1.9 2.5 2.0 1.9 2.5 2.0 1.9 2.5 460 2.8 0.799 XIT05901 INSTRUMENT SUPPLY INVERTERS 10.0 10.0 0.850 0 N/A 10.2 8.7 10.2 10.2 8.7 10.2 10.2 8.7 10.2 10.2 8.7 10.2 10.2 8.7 10.2 10.2 8.7 10.2 RN 480 8.5 0.755 17-022 XIT05902 INSTRUMENT SUPPLY INVERTERS 10.0 10.0 0.850 0 N/A 6.3 5.4 6.3 6.3 5.4 6.3 6.3 5.4 6.3 6.3 5.4 6.3 6.3 5.4 6.3 6.3 5.4 6.3 480 8.5 0.714 XMC1DA2Y HTR SPACE HTRS FOR XMC1DA2Y 3.4 3.4 1.000 N/A N/A 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.4 480 3.4 XPN00040 TRAIN A PUMP AUXILIARIES TRANSFER PNL-XPP0043C 5.0 5.0 0.850 0 YES 1.0 0.8 1.0 1.0 0.8 1.0 1.0 0.8 1.0 1.0 0.8 1.0 1.0 0.8 1.0 1.0 0.8 1.0 17 480 4.3 XPN02023 REFLING WTR STRGE TNK & PIPNG HEAT TRACNG CNTRALZED CONT PAN RN 30.0 30.0 1.000 0 YES 22.7 22.7 22.7 22.7 22.7 22.7 22.7 22.7 22.7 22.7 22.7 22.7 22.7 22.7 22.7 22.7 22.7 22.7 12-006 480 30.0 17-033 XPN02007 REAC MU WTR STRGE TANK&PIPING HEAT TRACING CENTRLZD CONTROL 20.0 20.0 1.000 0 YES 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 480 20.0 XPN02021 SODIUM HYDROXIDE SPRAY SYSTEM HEAT TRACING CENTRLZD CONRL P RN 3.0 3.0 1.000 0 YES 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 12-006 480 3.0 XPN07215A 480V PWR POST ACCIDENT ANALYZER SYSTEM 1.5 1.5 0.850 0 N/A 0.0 0.0 0.0 1.5 1.3 1.5 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1 480 1.3 8.3-56 Reformatted December 2018

FSAR TABLE 8.3-3 PART A2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XMC1DA2Y (Continued)

XPP00013A BORIC ACID PUMPS 15.5 15.7 0.850 0 NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 460 13.4 0.865 XPP00043A PP AUX OIL CHARGING/SI PUMP A AUXILIARY OIL PUMP ALOP1 2.0 2.2 0.850 0 YES 1.4 1.3 1.5 1.4 1.3 1.5 1.4 1.3 1.5 1.4 1.3 1.5 1.4 1.3 1.5 0.0 0.0 0.0 460 1.8 0.808 XTF04006 SECURITY SYSTEM TRANSFER SWITCH (FEEDS XTF05014) 37.5 37.5 0.850 0 N/A 31.8 27.1 31.8 31.8 27.1 31.8 31.8 27.1 31.8 31.8 27.1 31.8 31.8 27.1 31.8 31.8 27.1 31.8 17 RN 480 31.9 17-033 XTF05032 480/240/120V XFMR FOR METEOROLOGICAL TOWER 6.0 6.0 0.850 0 N/A 5.4 4.6 5.4 5.4 4.6 5.4 5.4 4.6 5.4 5.4 4.6 5.4 5.4 4.6 5.4 5.4 4.6 5.4 480 5.1 XTF08023A XFMR FOR LIGHTING PANEL 23, ESSENTIAL PANEL, TRAIN A 15.0 15.0 0.850 0 N/A 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 RN 480 12.8 17-033 Total Load On Motor Control Center: XMC1DA2Y 147.3 173.0 148.6 174.5 147.3 173.0 144.5 169.3 147.3 173.0 143.2 167.8 17-022 XMC1DA2Z APN08037A LIGHTING PANEL #37, ESSENTIAL PANEL 45.0 45.0 0.850 0 N/A 3.0 2.5 3.0 3.0 2.5 3.0 3.0 2.5 3.0 3.0 2.5 3.0 3.0 2.5 3.0 3.0 2.5 3.0 480 38.3 XAC00008A AIR STARTING PACKAGE - DIESEL GEN.

15.0 15.2 0.850 0 YES 15.5 13.4 15.7 0.0 0.0 0.0 15.5 13.4 15.7 0.0 0.0 0.0 15.5 13.4 15.7 0.0 0.0 0.0 24 460 12.9 0.865 XAC00008B AIR STARTING PACKAGE - DIESEL GEN.

15.0 15.2 0.850 0 NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 460 12.9 0.865 XFN00075A DG AREA A VENTILATION AIR SUPPLY FAN A 30.0 30.4 0.824 0 YES 25.0 20.9 25.3 25.0 20.9 25.3 25.0 20.9 25.3 25.0 20.9 25.3 25.0 20.9 25.3 25.0 20.9 25.3 460 25.0 0.894 XFN00075B DG AREA A VENTILATION AIR SUPPLY FAN B 30.0 30.4 0.824 0 YES 25.0 20.9 25.3 25.0 20.9 25.3 25.0 20.9 25.3 25.0 20.9 25.3 25.0 20.9 25.3 25.0 20.9 25.3 460 25.0 0.894 XMC1DA2Z HTR SPACE HTRS FOR XMC1DA2Z 0.7 0.7 1.000 N/A N/A 0.7 0.7 0.7 0.7 0.7 0.7 0.7 0.7 0.7 0.7 0.7 0.7 0.7 0.7 0.7 0.7 0.7 0.7 480 0.7 XPN00047 NO. 1A DIESEL POWER PANEL 56.0 56.0 0.850 0 N/A 56.0 47.6 56.0 56.0 47.6 56.0 56.0 47.6 56.0 56.0 47.6 56.0 56.0 47.6 56.0 56.0 47.6 56.0 480 47.6 XPP00004A DG FUEL OIL TRANSFER PUMP 4A 1.0 1.4 0.720 0 YES 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 460 1.0 0.765 XPP00141A DG FUEL OIL TRANSFER PUMP 141A 1.0 1.4 0.720 0 YES 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 460 1.0 0.765 8.3-57 Reformatted December 2018

FSAR TABLE 8.3-3 PART A2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XMC1DA2Z (Continued)

XPP00146A DIESEL GENERATOR BLDG SUMP PUMP 2.0 2.2 0.850 0 NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 22 460 1.8 0.808 Total Load On Motor Control Center: XMC1DA2Z 107.1 127.7 93.8 112.0 107.1 127.7 93.8 112.0 107.1 127.7 93.8 112.0 XMC1EA1X APN04006 SW BLDG POWER PANEL 1 60.0 60.0 1.000 0 N/A 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 480 60.0 APN08031A LIGHTING PANEL 31, ESSENTIAL PANEL, TRAIN A POWER FEED 10.0 10.0 0.850 0 N/A 7.0 6.0 7.0 7.0 6.0 7.0 7.0 6.0 7.0 7.0 6.0 7.0 7.0 6.0 7.0 7.0 6.0 7.0 480 8.5 XFN00080A SERVICE WATER BUILDING SUPPLY FAN A 50.0 48.6 0.838 0 YES 58.0 47.2 56.4 58.0 47.2 56.4 58.0 47.2 56.4 58.0 47.2 56.4 58.0 47.2 56.4 58.0 47.2 56.4 460 40.7 0.916 XPP00147A SERVICE WATER PUMP HOUSE SUMP PUMP 1.0 1.1 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 22 460 1.0 0.765 XRS00002A SW TRAVELING SCREEN A RN 1.0 1.1 0.850 0 NO 1.0 1.0 1.1 1.0 1.0 1.1 1.0 1.0 1.1 1.0 1.0 1.1 1.0 1.0 1.1 1.0 1.0 1.1 22 15-025 460 1.0 0.765 XTF09016 RECEPTACLE PANEL 16 10.0 10.0 0.850 0 N/A 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 480 8.5 Total Load On Motor Control Center: XMC1EA1X 75.4 86.5 75.4 86.5 75.4 86.5 75.4 86.5 75.4 86.5 75.4 86.5 XMC1EC1X XRS00002C SW TRAVELING SCREEN C RN 1.0 1.1 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 16,22 15-025 460 1.0 0.765 Total Load On Motor Control Center: XMC1EC1X 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 8.3-58 Reformatted December 2018

FSAR TABLE 8.3-3 PART A2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XSW1DA MPP00001A COMPONENT COOLING PUMP A MOTOR 600.0 535.6 0.914 15 YES 550.0 448.8 491.0 550.0 448.8 491.0 550.0 448.8 491.0 550.0 448.8 491.0 550.0 448.8 491.0 550.0 448.8 491.0 2,11,30 6900 489.6 0.914 MPP00001C COMPONENT COOLING PUMP C MOTOR 600.0 535.6 0.914 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 16 6900 489.6 0.914 XPP00021A EMERGENCY FEEDWATER PUMP A 600.0 587.8 0.825 20 YES 550.0 444.5 538.8 0.0 0.0 0.0 550.0 444.5 538.8 0.0 0.0 0.0 550.0 444.5 538.8 0.0 0.0 0.0 11 6900 484.9 0.923 XPP00038A REACTOR BUILDING SPRAY PUMP A 400.0 367.0 0.880 N/A YES 400.0 322.9 367.0 420.0 339.1 385.3 400.0 322.9 367.0 400.0 322.9 367.0 0.0 0.0 0.0 0.0 0.0 0.0 3 6900 322.9 0.924 XPP00043A CHARGING/SI PUMP A 900.0 778.0 0.922 0 YES 880.0 701.4 760.7 880.0 701.4 760.7 880.0 701.4 760.7 0.0 0.0 0.0 740.0 589.8 639.7 0.0 0.0 0.0 14 6900 717.3 0.936 XPP00043C CHARGING/SI PUMP C 900.0 778.0 0.922 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 16 6900 717.3 0.936 XTF04101 PRESSURIZER HEATERS BACKUP GROUP 1 750.0 750.0 1.000 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 537.0 537.0 537.0 0.0 0.0 0.0 1 480 750.0 Total Load On Switchgear: XSW1DA 1917.6 2157.5 1489.2 1637.0 1917.6 2157.5 771.7 858.0 2020.1 2206.5 448.8 491.0 XSW1DA1 APN01DA1 SWITCHGEAR XSW1DA1 DISTRIBUTION PANEL 10.0 10.0 0.850 0 N/A 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 RN 480 8.5 10-014 XFN00019A AUXILIARY BUILDING CHARCOAL EXHAUST A 125.0 119.5 0.850 N/A NO 0.0 0.0 0.0 125.0 101.6 119.5 0.0 0.0 0.0 125.0 101.6 119.5 125.0 101.6 119.5 125.0 101.6 119.5 1,26 460 101.6 0.918 XFN00019C AUXILIARY BUILDING CHARCOAL EXHAUST FAN C 125.0 119.5 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 460 101.6 0.918 XFN00064A MFN00096A REACTOR BUILDING COOLING UNIT FAN (MFN0096A) 275.0 246.5 0.889 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 460 219.2 0.936 XFN00064A MFN00097A REACTOR BUILDING COOLING UNIT FAN (MFN0097A) 75.0 77.4 0.779 25 YES 90.0 72.3 92.9 90.0 72.3 92.9 90.0 72.3 92.9 90.0 72.3 92.9 90.0 72.3 92.9 90.0 72.3 92.9 6,14,27 460 60.3 0.928 XFN00065A MFN00096C REACTOR BUILDING COOLING UNIT FAN (MFN0096C) 275.0 246.5 0.889 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 460 219.2 0.936 8.3-59 Reformatted December 2018

FSAR TABLE 8.3-3 PART A2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XSW1DA1 (Continued)

XFN00065A MFN00097C REACTOR BUILDING COOLING UNIT FAN (MFN0097C) 75.0 77.4 0.779 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 14,27 460 60.3 0.928 XHX00001A HVAC SYSTEM MECHANICAL WATER CHILLER A 321.0 286.1 0.900 30 YES 321.0 257.5 286.1 321.0 257.5 286.1 321.0 257.5 286.1 321.0 257.5 286.1 321.0 257.5 286.1 321.0 257.5 286.1 13 460 257.5 0.930 XHX00001C TRAIN A HVAC SYSTEM MECHANICAL WATER CHILLER C - LOAD FOR TRAIN A 321.0 286.1 0.900 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 16 460 257.5 0.930 XPP00031A RESIDUAL HEAT REMOVAL PUMP A 300.0 262.2 0.914 0 YES 285.0 227.6 249.1 300.0 239.6 262.2 285.0 227.6 249.1 285.0 227.6 249.1 285.0 227.6 249.1 300.0 239.6 262.2 460 239.6 0.934 XPP00040A REACTOR MAKE-UP WATER PUMP A 60.0 58.3 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 460 49.6 0.903 XPP00045A SERVICE WATER BOOSTER PUMP A 350.0 303.5 0.920 35 YES 250.0 199.5 216.8 250.0 199.5 216.8 250.0 199.5 216.8 250.0 199.5 216.8 250.0 199.5 216.8 0.0 0.0 0.0 7,14 460 279.3 0.935 RN Total Load On Switchgear: XSW1DA1 764.6 853.9 878.1 986.5 764.6 853.9 866.2 973.4 866.2 973.4 678.7 769.7 10-014 XSW1DA2 APN01DA2 SWITCHGEAR XSW1DA2 DISTRIBUTION PANEL 10.0 10.0 0.850 0 N/A 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 480 8.5 XFN00023A FUEL BUILDING EXHAUST FAN 23A 60.0 59.0 0.831 25 YES 56.0 45.8 55.1 56.0 45.8 55.1 56.0 45.8 55.1 56.0 45.8 55.1 56.0 45.8 55.1 56.0 45.8 55.1 460 49.0 0.913 XHR00004A HYDROGEN RECOMBINER A 75.0 75.0 1.000 N/A NO 0.0 0.0 0.0 75.0 75.0 75.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1,28 480 75.0 XIT05936 TRAIN A INCOMING TRAIN A POWER 125.0 125.0 1.000 0 N/A 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 15 RN 17-033 480 125.0 XPP00032A SPENT FUEL PIT COOLING PUMP A 75.0 73.4 0.840 N/A NO 0.0 0.0 0.0 60.0 49.3 58.7 0.0 0.0 0.0 60.0 49.3 58.7 60.0 49.3 58.7 60.0 49.3 58.7 1,29 460 61.6 0.908 XPP00048A CHILLED WATER PUMP A 60.0 53.4 0.930 10 YES 48.0 39.7 42.7 48.0 39.7 42.7 48.0 39.7 42.7 48.0 39.7 42.7 48.0 39.7 42.7 48.0 39.7 42.7 13 460 49.6 0.902 XPP00048C TRAIN A CHILLED WATER PUMP C - LOAD FOR TRAIN A 50.0 44.4 0.920 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 16 460 40.9 0.913 XSW1DA2 BUS 1.8 1.8 0.000 N/A 1.8 0.0 1.8 1.8 0.0 1.8 1.8 0.0 1.8 1.8 0.0 1.8 1.8 0.0 1.8 1.8 0.0 1.8 RN 480 0.0 17-033 Total Load On Switchgear: XSW1DA2 153.5 169.0 277.8 302.7 153.5 169.0 202.8 227.7 202.8 227.7 202.8 227.7 8.3-60 Reformatted December 2018

FSAR TABLE 8.3-3 PART A2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XSW1EA MPP00039A SERVICE WATER PUMP A MOTOR 700.0 622.0 0.922 10 YES 650.0 532.5 577.6 650.0 532.5 577.6 650.0 532.5 577.6 650.0 532.5 577.6 650.0 532.5 577.6 650.0 532.5 577.6 12 6900 573.5 0.911 MPP00039C TRAIN A SERVICE WATER PUMP C MOTOR - LOAD FOR TRAIN A 700.0 622.0 0.922 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 16 6900 573.5 0.911 Total Load On Switchgear: XSW1EA 532.5 577.6 532.5 577.6 532.5 577.6 532.5 577.6 532.5 577.6 532.5 577.6 XSW1EA1 APN01EA1 SWITCHGEAR XSW1EA1 DISTRIBUTION PANEL 10.0 10.0 0.850 0 N/A 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 480 8.5 Total Load On Switchgear: XSW1EA1 7.6 9.0 7.6 9.0 7.6 9.0 7.6 9.0 7.6 9.0 7.6 9.0 RN Subtotal Load On The Diesel Generator: 3971.1 4485.4 3793.6 4245.6 3971.1 4485.4 3001.1 3391.1 4256.2 4749.5 2442.1 2762.7 17-022 Cable Losses: 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 Transformer Losses: 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 RN Generator Exciter Load: 24.0 28.0 24.0 28.0 24.0 28.0 24.0 28.0 24.0 28.0 24.0 28.0 10-014 17-033 Total Generator Load With Optional Loads: 4035.1 4553.4 3857.6 4313.6 4035.1 4553.4 3065.1 3458.6 4320.2 4817.5 2506.1 2830.7 10 17-022 Optional Loads: 0.0 0.0 279.2 314.6 0.0 0.0 202.9 238.0 739.9 775.0 202.9 238.0 Total Generator Load Without Optional Loads: 4035.1 4553.4 3578.4 3999.0 4035.1 4553.4 2862.2 3221.6 3580.3 4042.5 2302.2 2592.7 17-022 Total Records Printed: 93 8.3-61 Reformatted December 2018

FSAR TABLE 8.3-3 PART A2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel A Notes:

1 This is an optional load which can be started manually. It may be added if the DG loading conditions permit, and this load was not considered for fuel oil storage requirements since it is not a required load.

2 The pump is normally in low speed but is assumed to be auto-started in high speed. The speed change switch is manually operated. The pump will be operated in high speed for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for the first 7 days following a DBE.

If both DGs are running, only one train's pump will be in high speed during the plant shutdown.

3 The pump starts on receipt of a spray initiation signal.

4 The motor is not required for the accident scenarios but the motor will be running as it is not locked out by the load sequencer.

5 The motor is running in the Hot Standby scenario as the SWBP is automatically started by the load sequencer.

6 The motor is not required for the LOOP - Hot standby / Cold shutdown scenarios but is auto started by the load sequencer and expected to remain on for air circulation related purposes.

7 The motor is not required for the LOOP - Hot standby scenario but is auto started by the load sequencer.

8 The equipment is required to be operable for six months following an accident.

9 Time 0 indicates the emergency diesel generator has started and reached no load speed and voltage, at which the circuit breaker connecting to the 7200 volt bus has closed.

10 Total includes the RHR pump and all manual loads whose application will be limited so that neither the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating (4676 kW) is exceeded for more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> nor the continuous rating of 4250 kW is exceeded.

11 The required safety function is for emergency core cooling.

12 The required safety function is for emergency core cooling and containment cooling.

13 The required safety function is for equipment area cooling.

14 The required safety function is for containment cooling.

15 This inverter is assumed to be running on this diesel generator. It is fed via a manual switchgear breaker.

16 The "C" train equipment is assumed to be not running as the normal train equipment is running.

17 This equipment is assumed to be supplied from this diesel generator.

18 Generator efficiency is assumed to be taken into account by the diesel manufacturer as the load limit is based on generator output kW (including the exciter) as monitored at the MCB.

19 The dc powered oil pumps associated with the turning gear are included in the battery charger loads.

20 For the Auto-Start columns, YES means the load is able to automatically start based on its control circuitry, NO means it does not, and N/A means the load is continuous and not subject to starting and stopping.

21 The normal battery charger is assumed in service.

22 The load is locked out on receipt of an SI signal.

23 The fan runs only when the EFWP is running.

24 The compressor runs only to recharge the air start system. It is assumed to be running in the first hour only.

25 XTG00001 will be running less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> total during the 7 days following a DBE.

26 The fan is expected to be manually started within the first 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> and is therefore shown as a load for the LOOP/Hot Standby mode.

27 Only 1 out of 2 RBCU fans is required to run post accident as selected.

28 The H2 recombiner will be operated as needed to support post accident response.

29 The pump will be operated as needed to maintain spent fuel pool temperatures within acceptable limits.

30 The component cooling water pump slow speed ratings are 250hp, .8094 PF, .9114 Efficiency, and 250kVA.

31 The "BHP/kVA" field lists the demand load that has been calculated for the specified event.

32 The "kW" field equals BHP/kVA x 0.746 kW/HP / EFF for motors. For non-motor loads this field equals BHP / kVA x PF.

33 The "kVA" field equals BHP / kVA x 0.746 kW/HP / (EFF x PF) for motors. For non-motor loads this field equals BHP / kVA.

8.3-62 Reformatted December 2018

FSAR TABLE 8.3-3 PART B1 Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data Load Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<------------------------> Sequencer <-------------------------------> <--------------------> <-------------------------------> <--------------------> <-------------------------------> <-------------------->

Tag Number Hp/kVA kW Volts (Sec.) (9) Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Notes XMC1B1X XTG00001 TURBINE TURNING GEAR 60.0 52.2 460 N/A NO 0.0 0.0 54.8 63.0 NO 0.0 0.0 54.8 63.0 NO 54.8 63.0 54.8 63.0 1,25 Total Load On Motor Control Center: XMC1B1X 0.0 0.0 54.8 63.0 0.0 0.0 54.8 63.0 54.8 63.0 54.8 63.0 XMC1DB2X APN08005B LIGHTING PANEL 5, ESSENTIAL PANEL, TRAIN B 10.0 8.5 480 0 N/A 3.4 4.0 3.4 4.0 N/A 3.4 4.0 3.4 4.0 N/A 3.4 4.0 3.4 4.0 APN08036B LIGHTING PANEL 36, ESSENTIAL PANEL, TRAIN B POWER FEED 10.0 8.5 480 0 N/A 4.3 5.0 4.3 5.0 N/A 4.3 5.0 4.3 5.0 N/A 4.3 5.0 4.3 5.0 APN08054B OUTDOOR ESSENTIAL LIGHTING PANEL B 46.0 39.1 480 0 N/A 39.1 46.0 39.1 46.0 N/A 39.1 46.0 39.1 46.0 N/A 39.1 46.0 39.1 46.0 IRM00001 RADIATION MONITORING CONTROL ROOM SUPPLY AIR PUMP 1.0 0.8 460 0 YES 0.0 0.0 0.0 0.0 YES 0.0 0.0 0.0 0.0 YES 0.0 0.0 0.0 0.0 XBC1B DC 1B BATTERY CHARGER 43.3 32.5 480 0 N/A 7.1 9.4 7.1 9.4 N/A 7.1 9.4 7.1 9.4 N/A 7.1 9.4 7.1 9.4 XBC1X-2X BATTERY CHARGER 86.7 65.0 480 0 N/A 39.0 52.0 39.0 52.0 N/A 39.0 52.0 39.0 52.0 N/A 39.0 52.0 39.0 52.0 19 RN 17-033 XFN00038B BATT&CHG RM AIR HANDLING UNIT B SUP FAN 10.0 8.2 460 0 YES 5.7 7.0 5.7 7.0 YES 5.7 7.0 5.7 7.0 YES 5.7 7.0 5.7 7.0 XFN00039B BATTERY ROOM EXHAUST FAN B 5.0 4.3 460 0 YES 0.5 0.6 0.5 0.6 YES 0.5 0.6 0.5 0.6 YES 0.5 0.6 0.5 0.6 XFN00076 ESF SWGR ROOM 1DB AH UNIT SUPPLY FAN 15.0 12.4 460 0 YES 5.8 7.0 5.8 7.0 YES 5.8 7.0 5.8 7.0 YES 5.8 7.0 5.8 7.0 XFN00081B SW BSTR PUMP AREA AH UNIT B SUPPLY FAN 3.0 2.3 460 0 YES 2.3 3.0 2.3 3.0 YES 2.3 3.0 2.3 3.0 YES 2.3 3.0 0.0 0.0 5 XFN00083B EMER FW PUMP AREA AH UNIT B SUPPLY FAN 5.0 3.6 460 0 YES 2.2 3.0 0.0 0.0 YES 2.2 3.0 0.0 0.0 YES 2.2 3.0 0.0 0.0 23 XFN00106B SPEED SWITCH ROOMS AH UNIT B SUPPLY FAN 10.0 8.2 460 0 YES 5.7 7.0 5.7 7.0 YES 5.7 7.0 5.7 7.0 YES 5.7 7.0 5.7 7.0 XHX00001B CNTRL PWR HVAC SYSTEM MECHANICAL WATER CHILLER B 15.0 12.8 480 0 N/A 6.4 7.5 6.4 7.5 N/A 6.4 7.5 6.4 7.5 N/A 6.4 7.5 6.4 7.5 XHX00001C CTRL PWR B XHX1C CTRL PWR HVAC SYS MECH. WATER CHILLER C CHANNEL B 15.0 12.8 480 0 N/A 6.4 7.5 6.4 7.5 N/A 6.4 7.5 6.4 7.5 N/A 6.4 7.5 6.4 7.5 XPN07215B 480V PWR POST ACCIDENT ANALYZER SYSTEM 1.7 1.4 480 0 N/A 0.0 0.0 1.4 1.6 N/A 0.0 0.0 0.0 0.0 N/A 0.0 0.0 0.0 0.0 1 XTF1FB XFMR FOR 120V AC NSSS INSTR. MAIN DISTR. PNL 1FB 25.0 21.3 480 0 N/A 7.1 8.3 7.1 8.3 N/A 7.1 8.3 7.1 8.3 N/A 7.1 8.3 7.1 8.3 Total Load On Motor Control Center: XMC1DB2X 134.9 167.4 134.1 166.0 134.9 167.4 132.7 164.4 134.9 167.4 130.5 161.4 RN 17-033 8.3-63 Reformatted May 2018

FSAR TABLE 8.3-3 PART B1 Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data Load Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<------------------------> Sequencer <-------------------------------> <--------------------> <-------------------------------> <--------------------> <-------------------------------> <-------------------->

Tag Number Hp/kVA kW Volts (Sec.) (9) Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Notes XMC1DB2Y APN08013B LIGHTING PANEL 13, ESSENTIAL PANEL, TRAIN B 30.0 25.5 480 0 N/A 23.8 28.0 23.8 28.0 N/A 23.8 28.0 23.8 28.0 N/A 23.8 28.0 23.8 28.0 IRM00002 RADIATION MONITORING REACTOR BUILDING SAMPLE LINE PUMP 1 1.0 0.8 460 0 YES 0.8 1.0 0.8 1.0 YES 0.8 1.0 0.8 1.0 YES 0.8 1.0 0.8 1.0 4 IRM00006 RADIATION MONITORING FUEL HANDLING BLDG. EXHAUST PUMP 1.0 0.8 460 0 YES 0.8 1.0 0.8 1.0 YES 0.8 1.0 0.8 1.0 YES 0.8 1.0 0.8 1.0 4 IRM00011 RADIATION MONITOR AUX. BLDG. VENTS 1.0 0.8 460 0 YES 0.8 1.0 0.8 1.0 YES 0.8 1.0 0.8 1.0 YES 0.8 1.0 0.8 1.0 4 XBC1A-1B TRAIN B DC 1A-1B BACKUP BATTERY CHRG 43.3 32.5 480 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 21 XFN00028B CONTROLLED ACCESS EXHAUST FAN B 50.0 42.5 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 22 XFN00030B CONT RM EMERGENCY FILTERING SYS FAN B 40.0 33.1 460 0 YES 33.1 40.0 33.1 40.0 YES 33.1 40.0 33.1 40.0 YES 33.1 40.0 0.0 0.0 XFN00032B CONTROL ROOM COOLING UNIT B FAN 25.0 20.8 460 0 YES 14.9 18.0 14.9 18.0 YES 14.9 18.0 14.9 18.0 YES 14.9 18.0 14.9 18.0 XFN00036B RELAY ROOM SUPPLY FAN B 15.0 12.4 460 0 YES 9.1 11.0 9.1 11.0 YES 9.1 11.0 9.1 11.0 YES 9.1 11.0 9.1 11.0 XFN00041B COMPUTER ROOM SUPPLY FAN B (UNIT 1) 5.0 4.3 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 22 XFN00046B CHARGING/SI PUMP RM 3 COOLING UNIT FAN 3.0 2.3 460 0 YES 2.3 3.0 2.3 3.0 YES 2.3 3.0 0.0 0.0 YES 2.3 3.0 0.0 0.0 XFN00049B RHR/SPRAY PUMP ROOM 2 COOLING UNIT FAN 3.0 2.3 460 0 YES 2.3 3.0 2.3 3.0 YES 2.3 3.0 2.3 3.0 YES 2.3 3.0 2.3 3.0 XFN00087B CONTROLLED ACCESS LAB HOOD EXHAUST FAN B 5.0 4.3 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 22 XFN00133 AUX BLDG MCC-SWGR ROOM COOLING UNIT FAN 5.0 3.6 460 0 YES 2.4 3.4 2.4 3.4 YES 2.4 3.4 2.4 3.4 YES 2.4 3.4 2.4 3.4 XIT05903 INSTRUMENT SUPPLY INVERTERS 10.0 8.5 480 0 N/A 6.5 7.6 6.5 7.6 N/A 6.5 7.6 6.5 7.6 N/A 6.5 7.6 6.5 7.6 XIT05904 INSTRUMENT SUPPLY INVERTERS 10.0 8.5 480 0 N/A 4.6 5.4 4.6 5.4 N/A 4.6 5.4 4.6 5.4 N/A 4.6 5.4 4.6 5.4 XPN00040 TRAIN B PUMP AUXILIARIES TRANSFER PNL-XPP0043C 1.0 0.8 480 0 N/A 0.8 1.0 0.8 1.0 N/A 0.8 1.0 0.8 1.0 N/A 0.8 1.0 0.8 1.0 17 8.3-64 Reformatted May 2018

FSAR TABLE 8.3-3 PART B1 Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data Load Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<------------------------> Sequencer <-------------------------------> <--------------------> <-------------------------------> <--------------------> <-------------------------------> <-------------------->

Tag Number Hp/kVA kW Volts (Sec.) (9) Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Notes XMC1DB2Y (Continued(

XPN02022 REFLING WTR STRGE TANK & PIPING HEAT TRACING CENTRLZD CONT P RN 12-006 15.0 15.0 480 0 YES 11.0 11.0 11.0 11.0 YES 11.0 11.0 11.0 11.0 YES 11.0 11.0 11.0 11.0 17-033 XPN02008 REAC MU WTR STRGE TANK&PIPING HEAT TRACING CENTRLZD CONTRL P 6.0 6.0 460 0 YES 0.0 0.0 0.0 0.0 YES 0.0 0.0 0.0 0.0 YES 0.0 0.0 0.0 0.0 XPN02020 SODIUM HYDROXIDE SPRAY SYSTEM HEAT TRACING CENTRLZD CONT PN RN 12-006 3.0 3.0 460 0 YES 0.0 0.0 0.0 0.0 YES 0.0 0.0 0.0 0.0 YES 0.0 0.0 0.0 0.0 XPP00013B BORIC ACID PUMPS 15.5 13.2 460 0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 XPP00043B PP AUX OIL CHARGING/SI PUMP B AUXILIARY OIL PUMP ALOP2 2.0 1.7 460 0 YES 1.2 1.4 1.2 1.4 YES 1.2 1.4 1.2 1.4 YES 1.2 1.4 0.0 0.0 XTF05014 SECURITY SYSTEM VIA XET04006 37.5 31.9 480 0 N/A 27.1 31.8 27.1 31.8 N/A 27.1 31.8 27.1 31.8 N/A 27.1 31.8 27.1 31.8 17 RN 17-033 XTF05930 BACKUP MET. TOWER DISTR. PANEL 0.0 0.0 480 0 N/A 12.8 15.0 12.8 15.0 N/A 12.8 15.0 12.8 15.0 N/A 12.8 15.0 12.8 15.0 XTF08024B XFMR FOR LIGHTING PANEL 24, ESSENTIAL PANEL, TRAIN B 15.0 12.8 480 0 N/A 6.4 7.5 6.4 7.5 N/A 6.4 7.5 6.4 7.5 N/A 6.4 7.5 6.4 7.5 XTF09006B RECEPTACLE TRANSFORMER #6 10.0 8.5 480 0 N/A 8.5 10.0 8.5 10.0 N/A 8.5 10.0 8.5 10.0 N/A 8.5 10.0 8.5 10.0 RN 17-033 Total Load On Motor Control Center: XMC1DB2Y 169.2 200.2 169.2 200.2 169.2 200.2 166.9 197.2 169.2 200.2 132.6 155.8 XMC1DB2Z APN08038B LIGHTING PANEL 38, ESENTIAL PANEL 45.0 38.3 480 0 N/A 2.5 3.0 2.5 3.0 N/A 2.5 3.0 2.5 3.0 N/A 2.5 3.0 2.5 3.0 XAC00008C AIR STARTING PACKAGE - DIESEL GEN.

15.0 12.8 460 0 YES 13.2 15.5 0.0 0.0 YES 13.2 15.5 0.0 0.0 YES 13.2 15.5 0.0 0.0 24 XAC00008D AIR STARTING PACKAGE - DIESEL GEN.

15.0 12.8 460 0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 XFN00045A DG AREA B VENTILATION AIR SUPPLY FAN A 30.0 24.7 460 0 YES 20.6 25.0 20.6 25.0 YES 20.6 25.0 20.6 25.0 YES 20.6 25.0 20.6 25.0 XFN00045B DG AREA B VENTILATION AIR SUPPY FAN B 30.0 24.7 460 0 YES 20.6 25.0 20.6 25.0 YES 20.6 25.0 20.6 25.0 YES 20.6 25.0 20.6 25.0 XMC1DB2Z HTR SPACE HTRS FOR XMC1DB2Z 0.5 0.5 480 N/A N/A 0.5 0.5 0.5 0.5 N/A 0.5 0.5 0.5 0.5 N/A 0.5 0.5 0.5 0.5 XPN00048 1B DIESEL POWER PANEL 56.0 47.6 480 0 N/A 47.6 56.0 47.6 56.0 N/A 47.6 56.0 47.6 56.0 N/A 47.6 56.0 47.6 56.0 XPP00004B DG FUEL OIL TRANSFER PUMP 4B 1.0 0.7 460 0 YES 0.4 0.6 0.4 0.6 YES 0.4 0.6 0.4 0.6 YES 0.4 0.6 0.4 0.6 XPP00141B DG FUEL OIL TRANSFER PUMP 141B 1.0 0.7 460 0 YES 0.4 0.6 0.4 0.6 YES 0.4 0.6 0.4 0.6 YES 0.4 0.6 0.4 0.6 XPP00146B DIESEL GENERATOR BLDG SUMP PUMP 2.0 1.7 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 22 Total Load On Motor Control Center: XMC1DB2Z 105.9 126.3 92.8 110.8 105.9 126.3 92.8 110.8 105.9 126.3 92.8 110.8 8.3-65 Reformatted May 2018

FSAR TABLE 8.3-3 PART B1 Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data Load Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<------------------------> Sequencer <-------------------------------> <--------------------> <-------------------------------> <--------------------> <-------------------------------> <-------------------->

Tag Number Hp/kVA kW Volts (Sec.) (9) Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Notes XMC1EB1X APN04007 SW BLDG POWER PANEL #2 60.0 51.0 480 0 N/A 21.3 25.0 21.3 25.0 N/A 21.3 25.0 21.3 25.0 N/A 21.3 25.0 21.3 25.0 APN08032B LIGHTING PANEL 32, ESSENTIAL PANEL, TRAIN B POWER FEED 10.0 8.5 480 0 N/A 5.1 6.0 5.1 6.0 N/A 5.1 6.0 5.1 6.0 N/A 5.1 6.0 5.1 6.0 XFN00080B SERVICE WATER BUILDING SUPPLY FAN B 50.0 41.9 460 0 YES 48.6 58.0 48.6 58.0 YES 48.6 58.0 48.6 58.0 YES 48.6 58.0 48.6 58.0 XPP00147B SERVICE WATER PUMPHOUSE SUMP PUMP 1.0 0.8 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 22 XRS00002B SW TRAVELING SCREEN B RN 1.0 0.8 460 0 NO 0.8 1.0 0.8 1.0 NO 0.8 1.0 0.8 1.0 NO 0.8 1.0 0.8 1.0 22 15-025 Total Load On Motor Control Center: XMC1EB1X 75.8 90.0 75.8 90.0 75.8 90.0 75.8 90.0 75.8 90.0 75.8 90.0 XMC1EC1X XRS00002C SW TRAVELING SCREEN C 1.0 0.8 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 16,22 RN 15-025 Total Load On Motor Control Center: XMC1EC1X 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 XSW1DB MPP00001B COMPONENT COOLING PUMP B MOTOR 600.0 548.4 6900 15 YES 502.7 550.0 502.7 550.0 YES 502.7 550.0 502.7 550.0 YES 502.7 550.0 502.7 550.0 2,11,30 MPP00001C TRAIN B COMPONENT CLG PP C FED VIA XES2001C & XET02001C 600.0 519.6 6900 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 16 XPP00021B EMERGENCY FEEDWATER PUMP B 600.0 495.0 6900 20 YES 453.8 550.0 0.0 0.0 YES 453.8 550.0 0.0 0.0 YES 453.8 550.0 0.0 0.0 11 XPP00038B REACTOR BUILDING SPRAY PUMP B 400.0 352.0 6900 N/A YES 352.0 400.0 369.6 420.0 YES 352.0 400.0 352.0 400.0 NO 0.0 0.0 0.0 0.0 3 XPP00043B CHARGING/SI PUMP B 900.0 829.8 6900 0 YES 792.9 860.0 792.9 860.0 YES 792.9 860.0 0.0 0.0 YES 663.8 720.0 0.0 0.0 14 XPP00043C TRAIN B CHARGING/SI PUMP C FED VIA XET2002C 900.0 829.8 6900 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 16 XTF04102 PRESSURIZER HEATERS BACKUP GROUP 2 750.0 750.0 480 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 485.1 485.1 0.0 0.0 1 Total Load On Switchgear: XSW1DB 2101.4 2360.0 1665.2 1830.0 2101.4 2360.0 854.7 950.0 2105.4 2305.1 502.7 550.0 8.3-66 Reformatted May 2018

FSAR TABLE 8.3-3 PART B1 Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data Load Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<------------------------> Sequencer <-------------------------------> <--------------------> <-------------------------------> <--------------------> <-------------------------------> <-------------------->

Tag Number Hp/kVA kW Volts (Sec.) (9) Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Notes XSW1DB1 APN01DB1 SWITCHGEAR XSW1DB1 DISTRIBUTION PANEL 10.0 8.5 480 0 N/A 7.6 9.0 7.6 9.0 N/A 7.6 9.0 7.6 9.0 N/A 7.6 9.0 7.6 9.0 XAC00012 SUPPLEMENTAL INSTRUMENT AIR COMPRESSOR 150.0 129.0 460 N/A NO 0.0 0.0 129.0 150.0 NO 0.0 0.0 129.0 150.0 NO 129.0 150.0 129.0 150.0 1 XFN00019B CHARCOAL EXHAUST FAN B 125.0 106.3 460 N/A NO 0.0 0.0 106.3 125.0 NO 0.0 0.0 106.3 125.0 NO 106.3 125.0 106.3 125.0 1,26 XFN00019D AUXILIARY BUILDING CHARCOAL EXHAUST FAN D 125.0 106.3 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 XFN00064B MFN00096B REACTOR BUILDING COOLING UNIT FAN (MFN0096B) 275.0 244.5 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 XFN00064B MFN00097B REACTOR BUILDING COOLING UNIT FAN (MFN0097B) 75.0 58.4 460 25 YES 70.1 90.0 70.1 90.0 YES 70.1 90.0 70.1 90.0 YES 70.1 90.0 70.1 90.0 6,14,27 XFN00065B MFN00096D REACTOR BUILDING COOLING UNIT FAN (MFN0096D) 275.0 244.5 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 XFN00065B MFN00097D REACTOR BUILDING COOLING UNIT FAN (MFN0097D) 75.0 58.4 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 14,27 XHX00001B HVAC SYSTEM MECHANICAL WATER CHILLER B 321.0 288.9 460 30 YES 288.9 321.0 288.9 321.0 YES 288.9 321.0 288.9 321.0 YES 288.9 321.0 288.9 321.0 13 XHX00001C TRAIN B HVAC SYSTEM MECHANICAL WATER CHILLER C - LOAD FOR TRAIN B 321.0 288.9 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 16 XPP00031B RESIDUAL HEAT REMOVAL PUMP B 300.0 274.2 460 0 YES 260.5 285.0 274.2 300.0 YES 260.5 285.0 260.5 285.0 YES 260.5 285.0 274.2 300.0 XPP00040B REACTOR MAKE-UP WATER PUMP B 60.0 51.0 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 XPP00045B SERVICE WATER BOOSTER PUMP B 350.0 322.0 460 35 YES 230.0 250.0 230.0 250.0 YES 230.0 250.0 230.0 250.0 YES 230.0 250.0 0.0 0.0 7,14 Total Load On Switchgear: XSW1DB1 857.2 955.0 1106.1 1245.0 857.2 955.0 1092.4 1230.0 1092.4 1230.0 876.1 995.0 XSW1DB2 APN01DB2 SWITCHGEAR XSW1DB2 DISTR. PNL.

10.0 8.5 480 0 N/A 7.6 9.0 7.6 9.0 N/A 7.6 9.0 7.6 9.0 N/A 7.6 9.0 7.6 9.0 XFN00023B FUEL BUILDING EXHAUST FAN 23B 60.0 49.9 460 25 YES 46.5 56.0 46.5 56.0 YES 46.5 56.0 46.5 56.0 YES 46.5 56.0 46.5 56.0 XHR00004B HYDROGEN RECOMBINER B 75.0 75.0 480 N/A NO 0.0 0.0 75.0 75.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 1,28 XIT05936 TRAIN B INCOMING TRAIN B POWER 125.0 125.0 480 0 N/A 60.4 60.4 60.4 60.4 N/A 60.4 60.4 60.4 60.4 N/A 60.4 60.4 60.4 60.4 15 RN XPP00032B SPENT FUEL PIT COOLING PUMP B 17-033 75.0 63.0 460 N/A NO 0.0 0.0 50.4 60.0 NO 0.0 0.0 50.4 60.0 NO 50.4 60.0 50.4 60.0 1,29 XPP00048B HVAC SYSTEM CHILL WATER PUMP B 60.0 55.8 460 10 YES 44.6 48.0 44.6 48.0 YES 44.6 48.0 44.6 48.0 YES 44.6 48.0 44.6 48.0 13 XPP00048C TRAIN B CHILLED WATER PUMP C - LOAD FOR TRAIN B 50.0 46.0 460 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 16 XSW1DB2 BUS 13.3 0.0 480 N/A 0.0 13.3 0.0 13.3 0.0 13.3 0.0 13.3 0.0 13.3 0.0 13.3 RN 17-033 Total Load On Switchgear: XSW1DB2 159.3 186.7 284.7 321.7 159.3 186.7 209.7 246.7 209.7 246.7 209.7 246.7 8.3-67 Reformatted May 2018

FSAR TABLE 8.3-3 PART B1 Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data Load Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<------------------------> Sequencer <-------------------------------> <--------------------> <-------------------------------> <--------------------> <-------------------------------> <-------------------->

Tag Number Hp/kVA kW Volts (Sec.) (9) Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Auto-Start Load kW Load kVA Load kW Load kVA Notes XSW1EB MPP00039B SERVICE WATER PUMP B MOTOR 700.0 645.4 6900 10 YES 599.3 650.0 599.3 650.0 YES 599.3 650.0 599.3 650.0 YES 599.3 650.0 599.3 650.0 12 MPP00039C TRAIN B SERVICE WATER PUMP C MOTOR - LOAD FOR TRAIN B 700.0 645.4 6900 N/A NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 NO 0.0 0.0 0.0 0.0 16 Total Load On Switchgear: XSW1EB 599.3 650.0 599.3 650.0 599.3 650.0 599.3 650.0 599.3 650.0 599.3 650.0 XSW1EB1 APN01EB1 SWITCHGEAR XSW1EB1 DISTRIBUTION PANEL 10.0 8.5 480 0 N/A 7.6 9.0 7.6 9.0 N/A 7.6 9.0 7.6 9.0 N/A 7.6 9.0 7.6 9.0 Total Load On Switchgear: XSW1EB1 7.6 9.0 7.6 9.0 7.6 9.0 7.6 9.0 7.6 9.0 7.6 9.0 Subtotal Load On The Diesel Generator: 4241.4 4797.9 4193.9 4709.1 4241.4 4797.9 3308.8 3754.5 4563.9 5116.0 2690.5 3060.1 RN 17-033 Cable Losses: 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 Transformer Losses: 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 Generator Exciter Load: 29.0 34.0 29.0 34.0 29.0 34.0 29.0 34.0 29.0 34.0 29.0 34.0 RN Total Generator Load With Optional Loads: 4313.4 4874.9 4265.9 4786.1 4313.4 4874.9 3380.8 3831.5 4635.9 5193.0 2762.5 3137.1 10 17-033 Optional Loads: 0.0 0.0 416.9 474.7 0.0 0.0 340.5 398.0 825.6 883.1 340.5 398.0 Total Generator Load Without Optional Loads: 4313.4 4874.9 3849.0 4311.4 4313.4 4874.9 3040.3 3433.4 3810.3 4309.9 2422.1 2739.1 RN 17-033 Total Records Printed: 91 8.3-68 Reformatted May 2018

FSAR TABLE 8.3-3 PART B1 Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B Notes:

1 This is an optional load which can be started manually. It may be added if the DG loading conditions permit, and this load was not considered for fuel oil storage requirements since it is not a required load.

2 The pump is normally in low speed but is assumed to be auto-started in high speed. The speed change switch is manually operated. The pump will be operated in high speed for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for the first 7 days following a DBE.

If both DGs are running, only one train's pump will be in high speed during the plant shutdown.

3 The pump starts on receipt of a spray initiation signal.

4 The motor is not required for the accident scenarios but the motor will be running as it is not locked out by the load sequencer.

5 The motor is running in the Hot Standby scenario as the SWBP is automatically started by the load sequencer.

6 The motor is not required for the LOOP - Hot standby / Cold shutdown scenarios but is auto started by the load sequencer and expected to remain on for air circulation related purposes.

7 The motor is not required for the LOOP - Hot standby scenario but is auto started by the load sequencer.

8 The equipment is required to be operable for six months following an accident.

9 Time 0 indicates the emergency diesel generator has started and reached no load speed and voltage, at which the circuit breaker connecting to the 7200 volt bus has closed.

10 Total includes the RHR pump and all manual loads whose application will be limited so that neither the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating (4676 kW) is exceeded for more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> nor the continuous rating of 4250 kW is exceeded.

11 The required safety function is for emergency core cooling.

12 The required safety function is for emergency core cooling and containment cooling.

13 The required safety function is for equipment area cooling.

14 The required safety function is for containment cooling.

15 This inverter is assumed to be running on this diesel generator. It is fed via a manual switchgear breaker.

16 The "C" train equipment is assumed to be not running as the normal train equipment is running.

17 This equipment is assumed to be supplied from this diesel generator.

18 Generator efficiency is assumed to be taken into account by the diesel manufacturer as the load limit is based on generator output kW (including the exciter) as monitored at the MCB.

19 The dc powered oil pumps associated with the turning gear are included in the battery charger loads.

20 For the Auto-Start columns, YES means the load is able to automatically start based on its control circuitry, NO means it does not, and N/A means the load is continuous and not subject to starting and stopping.

21 The normal battery charger is assumed in service.

22 The load is locked out on receipt of an SI signal.

23 The fan runs only when the EFWP is running.

24 The compressor runs only to recharge the air start system. It is assumed to be running in the first hour only.

25 XTG00001 will be running less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> total during the 7 days following a DBE.

26 The fan is expected to be manually started within the first 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> and is therefore shown as a load for the LOOP/Hot Standby mode.

27 Only 1 out of 2 RBCU fans is required to run post accident as selected.

28 The H2 recombiner will be operated as needed to support post accident response.

29 The pump will be operated as needed to maintain spent fuel pool temperatures within acceptable limits.

30 The component cooling water pump slow speed ratings are 250hp, .8094 PF, .9114 Efficiency, and 250kVA.

8.3-69 Reformatted May 2018

FSAR TABLE 8.3-3 PART B2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XMC1B1X XTG00001 TURBINE TURNING GEAR 60.0 57.0 0.870 N/A NO 0.0 0.0 0.0 63.0 52.0 59.8 0.0 0.0 0.0 63.0 52.0 59.8 63.0 52.0 59.8 63.0 52.0 59.8 1,25 460 49.6 0.903 Total Load On Motor Control Center: XMC1B1X 0.0 0.0 52.0 59.8 0.0 0.0 52.0 59.8 52.0 59.8 52.0 59.8 XMC1DB2X APN08005B LIGHTING PANEL 5, ESSENTIAL PANEL, TRAIN B 10.0 10.0 0.850 0 N/A 4.0 3.4 4.0 4.0 3.4 4.0 4.0 3.4 4.0 4.0 3.4 4.0 4.0 3.4 4.0 4.0 3.4 4.0 480 8.5 APN08036B LIGHTING PANEL 36, ESSENTIAL PANEL, TRAIN B POWER FEED 10.0 10.0 0.850 0 N/A 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 5.0 4.3 5.0 480 8.5 APN08054B OUTDOOR ESSENTIAL LIGHTING PANEL B 46.0 46.0 0.850 0 N/A 46.0 39.1 46.0 46.0 39.1 46.0 46.0 39.1 46.0 46.0 39.1 46.0 46.0 39.1 46.0 46.0 39.1 46.0 480 39.1 IRM00001 RADIATION MONITORING CONTROL ROOM SUPPLY AIR PUMP 1.0 1.0 0.750 0 YES 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 460 0.8 XBC1B DC 1B BATTERY CHARGER 43.3 43.3 0.750 0 N/A 9.4 7.1 9.4 9.4 7.1 9.4 9.4 7.1 9.4 9.4 7.1 9.4 9.4 7.1 9.4 9.4 7.1 9.4 480 32.5 XBC1X-2X BATTERY CHARGER 86.7 86.7 0.750 0 N/A 52.0 39.0 52.0 52.0 39.0 52.0 52.0 39.0 52.0 52.0 39.0 52.0 52.0 39.0 52.0 52.0 39.0 52.0 19 RN 17-033 480 65.0 XFN00038B BATT&CHG RM AIR HANDLING UNIT B SUP FAN 10.0 10.7 0.820 0 YES 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 460 8.8 0.850 XFN00039B BATTERY ROOM EXHAUST FAN B 5.0 5.5 0.850 0 YES 0.6 0.6 0.7 0.6 0.6 0.7 0.6 0.6 0.7 0.6 0.6 0.7 0.6 0.6 0.7 0.6 0.6 0.7 460 4.7 0.800 XFN00076 ESF SWGR ROOM 1DB AH UNIT SUPPLY FAN 15.0 15.6 0.830 0 YES 7.0 6.0 7.3 7.0 6.0 7.3 7.0 6.0 7.3 7.0 6.0 7.3 7.0 6.0 7.3 7.0 6.0 7.3 460 12.9 0.865 XFN00081B SW BSTR PUMP AREA AH UNIT B SUPPLY FAN 3.0 3.7 0.760 0 YES 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 0.0 0.0 0.0 5 460 2.8 0.799 XFN00083B EMER FW PUMP AREA AH UNIT B SUPPLY FAN 5.0 6.2 0.720 0 YES 3.0 2.7 3.7 0.0 0.0 0.0 3.0 2.7 3.7 0.0 0.0 0.0 3.0 2.7 3.7 0.0 0.0 0.0 23 460 4.5 0.831 XFN00106B SPEED SWITCH ROOMS AH UNIT B SUPPLY FAN 10.0 10.7 0.820 0 YES 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 7.0 6.1 7.5 460 8.8 0.850 8.3-70 Reformatted May 2018

FSAR TABLE 8.3-3 PART B2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XMC1DB2X (Continued)

XHX00001B CNTRL PWR HVAC SYSTEM MECHANICAL WATER CHILLER B 15.0 15.0 0.850 0 N/A 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 480 12.8 XHX00001C CTRL PWR B XHX1C CTRL PWR HVAC SYS MECH. WATER CHILLER C CHANNEL B 15.0 15.0 0.850 0 N/A 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 480 12.8 XPN07215B 480V PWR POST ACCIDENT ANALYZER SYSTEM 1.7 1.7 0.850 0 N/A 0.0 0.0 0.0 1.6 1.4 1.6 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1 480 1.4 XTF1FB XFMR FOR 120V AC NSSS INSTR. MAIN DISTR. PNL 1FB 25.0 25.0 0.850 0 N/A 8.3 7.1 8.3 8.3 7.1 8.3 8.3 7.1 8.3 8.3 7.1 8.3 8.3 7.1 8.3 8.3 7.1 8.3 480 21.3 Total Load On Motor Control Center: XMC1DB2X 137.0 170.1 135.7 168.0 137.0 170.1 134.3 166.4 137.0 170.1 131.5 162.7 RN 17-033 XMC1DB2Y APN08013B LIGHTING PANEL 13, ESSENTIAL PANEL, TRAIN B 30.0 30.0 0.850 0 N/A 28.0 23.8 28.0 28.0 23.8 28.0 28.0 23.8 28.0 28.0 23.8 28.0 28.0 23.8 28.0 28.0 23.8 28.0 480 25.5 IRM00002 RADIATION MONITORING REACTOR BUILDING SAMPLE LINE PUMP 1 1.0 1.3 0.750 0 YES 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 4 460 1.0 0.765 IRM00006 RADIATION MONITORING FUEL HANDLING BLDG. EXHAUST PUMP 1.0 1.3 0.750 0 YES 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 1.0 1.0 1.3 4 460 1.0 0.765 IRM00011 RADIATION MONITOR AUX. BLDG. VENTS 1.0 1.1 0.850 0 YES 1.0 1.0 1.1 1.0 1.0 1.1 1.0 1.0 1.1 1.0 1.0 1.1 1.0 1.0 1.1 1.0 1.0 1.1 4 460 1.0 0.765 XBC1A-1B TRAIN B DC 1A-1B BACKUP BATTERY CHRG 43.3 43.3 0.750 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 21 480 32.5 XFN00028B CONTROLLED ACCESS EXHAUST FAN B 50.0 48.5 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 22 460 41.3 0.904 XFN00030B CONT RM EMERGENCY FILTERING SYS FAN B 40.0 39.3 0.828 0 YES 40.0 32.5 39.3 40.0 32.5 39.3 40.0 32.5 39.3 40.0 32.5 39.3 40.0 32.5 39.3 0.0 0.0 0.0 460 32.5 0.918 XFN00032B CONTROL ROOM COOLING UNIT B FAN 25.0 25.5 0.830 0 YES 18.0 15.3 18.4 18.0 15.3 18.4 18.0 15.3 18.4 18.0 15.3 18.4 18.0 15.3 18.4 18.0 15.3 18.4 460 21.2 0.880 XFN00036B RELAY ROOM SUPPLY FAN B 15.0 15.6 0.830 0 YES 11.0 9.5 11.4 11.0 9.5 11.4 11.0 9.5 11.4 11.0 9.5 11.4 11.0 9.5 11.4 11.0 9.5 11.4 460 12.9 0.865 8.3-71 Reformatted May 2018

FSAR TABLE 8.3-3 PART B2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XMC1DB2Y (Continued)

XFN00041B COMPUTER ROOM SUPPLY FAN B (UNIT 1) 5.0 5.3 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 22 460 4.5 0.831 XFN00046B CHARGING/SI PUMP RM 3 COOLING UNIT FAN 3.0 3.7 0.760 0 YES 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 0.0 0.0 0.0 3.0 2.8 3.7 0.0 0.0 0.0 460 2.8 0.799 XFN00049B RHR/SPRAY PUMP ROOM 2 COOLING UNIT FAN 3.0 3.7 0.760 0 YES 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 3.0 2.8 3.7 460 2.8 0.799 XFN00087B CONTROLLED ACCESS LAB HOOD EXHAUST FAN B 5.0 5.3 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 22 460 4.5 0.831 XFN00133 AUX BLDG MCC-SWGR ROOM COOLING UNIT FAN 5.0 6.2 0.720 0 YES 3.4 3.1 4.2 3.4 3.1 4.2 3.4 3.1 4.2 3.4 3.1 4.2 3.4 3.1 4.2 3.4 3.1 4.2 460 4.5 0.831 XIT05903 INSTRUMENT SUPPLY INVERTERS 10.0 10.0 0.850 0 N/A 7.6 6.5 7.6 7.6 6.5 7.6 7.6 6.5 7.6 7.6 6.5 7.6 7.6 6.5 7.6 7.6 6.5 7.6 480 8.5 XIT05904 INSTRUMENT SUPPLY INVERTERS 10.0 10.0 0.850 0 N/A 5.4 4.6 5.4 5.4 4.6 5.4 5.4 4.6 5.4 5.4 4.6 5.4 5.4 4.6 5.4 5.4 4.6 5.4 480 8.5 XPN00040 TRAIN B PUMP AUXILIARIES TRANSFER PNL-XPP0043C 1.0 1.0 0.850 0 N/A 1.0 0.8 1.0 1.0 0.8 1.0 1.0 0.8 1.0 1.0 0.8 1.0 1.0 0.8 1.0 1.0 0.8 1.0 17 480 0.8 XPN02022 REFLING WTR STRGE TANK & PIPING HEAT TRACING CENTRLZD CONT P RN 15.0 15.0 1.000 0 YES 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 12-006 480 6.0 17-033 XPN02008 REAC MU WTR STRGE TANK&PIPING HEAT TRACING CENTRLZD CONTRL P 6.0 6.0 1.000 0 YES 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 460 6.0 XPN02020 SODIUM HYDROXIDE SPRAY SYSTEM HEAT TRACING CENTRLZD CONT PN RN 3.0 3.0 1.000 0 YES 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 12-006 460 3.0 XPP00013B BORIC ACID PUMPS 15.5 15.7 0.850 0 NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 460 13.4 0.865 XPP00043B PP AUX OIL CHARGING/SI PUMP B AUXILIARY OIL PUMP ALOP2 2.0 2.2 0.850 0 YES 1.4 1.3 1.5 1.4 1.3 1.5 1.4 1.3 1.5 1.4 1.3 1.5 1.4 1.3 1.5 0.0 0.0 0.0 460 1.8 0.808 XTF05014 SECURITY SYSTEM VIA XET04006 RN 37.5 37.5 0.850 0 N/A 31.8 27.1 31.8 31.8 27.1 31.8 31.8 27.1 31.8 31.8 27.1 31.8 31.8 27.1 31.8 31.8 27.1 31.8 17 17-033 480 31.9 8.3-72 Reformatted May 2018

FSAR TABLE 8.3-3 PART B2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XMC1DB2Y (Continued)

XTF05930 BACKUP MET. TOWER DISTR. PANEL 0.0 0.0 0.850 0 N/A 15.0 12.8 15.0 15.0 12.8 15.0 15.0 12.8 15.0 15.0 12.8 15.0 15.0 12.8 15.0 15.0 12.8 15.0 480 0.0 XTF08024B XFMR FOR LIGHTING PANEL 24, ESSENTIAL PANEL, TRAIN B 15.0 15.0 0.850 0 N/A 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 7.5 6.4 7.5 480 12.8 XTF09006B RECEPTACLE TRANSFORMER #6 10.0 10.0 0.850 0 N/A 10.0 8.5 10.0 10.0 8.5 10.0 10.0 8.5 10.0 10.0 8.5 10.0 10.0 8.5 10.0 10.0 8.5 10.0 RN 480 8.5 17-033 Total Load On Motor Control Center: XMC1DB2Y 171.6 203.4 171.6 203.4 171.6 203.4 168.8 199.7 171.6 203.4 135.0 158.9 XMC1DB2Z APN08038B LIGHTING PANEL 38, ESENTIAL PANEL 45.0 45.0 0.850 0 N/A 3.0 2.5 3.0 3.0 2.5 3.0 3.0 2.5 3.0 3.0 2.5 3.0 3.0 2.5 3.0 3.0 2.5 3.0 480 38.3 XAC00008C AIR STARTING PACKAGE - DIESEL GEN.

15.0 15.2 0.850 0 YES 15.5 13.4 15.7 0.0 0.0 0.0 15.5 13.4 15.7 0.0 0.0 0.0 15.5 13.4 15.7 0.0 0.0 0.0 24 460 12.9 0.865 XAC00008D AIR STARTING PACKAGE - DIESEL GEN.

15.0 15.2 0.850 0 NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 460 12.9 0.865 XFN00045A DG AREA B VENTILATION AIR SUPPLY FAN A 30.0 34.0 0.824 0 YES 25.0 23.3 28.3 25.0 23.3 28.3 25.0 23.3 28.3 25.0 23.3 28.3 25.0 23.3 28.3 25.0 23.3 28.3 460 28.0 0.800 XFN00045B DG AREA B VENTILATION AIR SUPPY FAN B 30.0 34.0 0.824 0 YES 25.0 23.3 28.3 25.0 23.3 28.3 25.0 23.3 28.3 25.0 23.3 28.3 25.0 23.3 28.3 25.0 23.3 28.3 460 28.0 0.800 XMC1DB2Z HTR SPACE HTRS FOR XMC1DB2Z 0.5 0.5 1.000 N/A N/A 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 480 0.5 XPN00048 1B DIESEL POWER PANEL 56.0 56.0 0.850 0 N/A 56.0 47.6 56.0 56.0 47.6 56.0 56.0 47.6 56.0 56.0 47.6 56.0 56.0 47.6 56.0 56.0 47.6 56.0 480 47.6 XPP00004B DG FUEL OIL TRANSFER PUMP 4B 1.0 1.4 0.720 0 YES 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 460 1.0 0.765 XPP00141B DG FUEL OIL TRANSFER PUMP 141B 1.0 1.4 0.720 0 YES 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 0.6 0.6 0.8 460 1.0 0.765 XPP00146B DIESEL GENERATOR BLDG SUMP PUMP 2.0 2.2 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 22 460 1.8 0.808 Total Load On Motor Control Center: XMC1DB2Z 111.9 133.5 98.5 117.8 111.9 133.5 98.5 117.8 111.9 133.5 98.5 117.8 8.3-73 Reformatted May 2018

FSAR TABLE 8.3-3 PART B2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XMC1EB1X APN04007 SW BLDG POWER PANEL #2 60.0 60.0 0.850 0 N/A 25.0 21.3 25.0 25.0 21.3 25.0 25.0 21.3 25.0 25.0 21.3 25.0 25.0 21.3 25.0 25.0 21.3 25.0 480 51.0 APN08032B LIGHTING PANEL 32, ESSENTIAL PANEL, TRAIN B POWER FEED 10.0 10.0 0.850 0 N/A 6.0 5.1 6.0 6.0 5.1 6.0 6.0 5.1 6.0 6.0 5.1 6.0 6.0 5.1 6.0 6.0 5.1 6.0 480 8.5 XFN00080B SERVICE WATER BUILDING SUPPLY FAN B 50.0 48.6 0.838 0 YES 58.0 47.2 56.4 58.0 47.2 56.4 58.0 47.2 56.4 58.0 47.2 56.4 58.0 47.2 56.4 58.0 47.2 56.4 460 40.7 0.916 XPP00147B SERVICE WATER PUMPHOUSE SUMP PUMP 1.0 1.1 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 22 460 1.0 0.765 XRS00002B SW TRAVELING SCREEN B RN 1.0 1.1 0.850 0 NO 1.0 1.0 1.1 1.0 1.0 1.1 1.0 1.0 1.1 1.0 1.0 1.1 1.0 1.0 1.1 1.0 1.0 1.1 22 15-025 460 1.0 0.765 Total Load On Motor Control Center: XMC1EB1X 74.6 88.5 74.6 88.5 74.6 88.5 74.6 88.5 74.6 88.5 74.6 88.5 XMC1EC1X XRS00002C SW TRAVELING SCREEN C 1.0 1.1 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 16,22 RN 460 1.0 0.765 15-025 Total Load On Motor Control Center: XMC1EC1X 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 XSW1DB MPP00001B COMPONENT COOLING PUMP B MOTOR 600.0 535.6 0.914 15 YES 550.0 448.8 491.0 550.0 448.8 491.0 550.0 448.8 491.0 550.0 448.8 491.0 550.0 448.8 491.0 550.0 448.8 491.0 2,11,30 6900 489.6 0.914 MPP00001C TRAIN B COMPONENT CLG PP C FED VIA XES2001C & XET02001C 600.0 600.0 0.866 N/A No 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 16 6900 519.6 XPP00021B EMERGENCY FEEDWATER PUMP B 600.0 587.8 0.825 20 YES 550.0 444.5 538.8 0.0 0.0 0.0 550.0 444.5 538.8 0.0 0.0 0.0 550.0 444.5 538.8 0.0 0.0 0.0 11 6900 484.9 0.923 XPP00038B REACTOR BUILDING SPRAY PUMP B 400.0 367.0 0.880 N/A YES 400.0 322.9 367.0 420.0 339.1 385.3 400.0 322.9 367.0 400.0 322.9 367.0 0.0 0.0 0.0 0.0 0.0 0.0 3 6900 322.9 0.924 XPP00043B CHARGING/SI PUMP B 900.0 778.0 0.922 0 YES 860.0 685.4 743.4 860.0 685.4 743.4 860.0 685.4 743.4 0.0 0.0 0.0 720.0 573.8 622.4 0.0 0.0 0.0 14 6900 717.3 0.936 8.3-74 Reformatted May 2018

FSAR TABLE 8.3-3 PART B2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XSW1DB (Continued)

XPP00043C Train B Charging/SI Pump C Fed via XET2002C 900.0 778.0 0.922 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 16 6900 717.3 0.936 XTF04102 PRESSURIZER HEATERS BACKUP GROUP 2 750.0 750.0 1.000 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 485.1 485.1 485.1 0.0 0.0 0.0 1 480 750.0 Total Load On Switchgear: XSW1DB 1901.7 2140.2 1473.3 1619.8 1901.7 2140.2 771.7 858.0 1952.3 2137.3 448.8 491.0 XSW1DB1 APN01DB1 SWITCHGEAR XSW1DB1 DISTRIBUTION PANEL 10.0 10.0 0.850 0 N/A 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 480 8.5 XAC00012 SUPPLEMENTAL INSTRUMENT AIR COMPRESSOR 150.0 141.0 0.860 N/A NO 0.0 0.0 0.0 150.0 121.2 141.0 0.0 0.0 0.0 150.0 121.2 141.0 150.0 121.2 141.0 150.0 121.2 141.0 1 460 121.2 0.923 XFN00019B CHARCOAL EXHAUST FAN B 125.0 119.5 0.850 N/A NO 0.0 0.0 0.0 125.0 101.6 119.5 0.0 0.0 0.0 125.0 101.6 119.5 125.0 101.6 119.5 125.0 101.6 119.5 1,26 460 101.6 0.918 XFN00019D AUXILIARY BUILDING CHARCOAL EXHAUST FAN D 125.0 119.5 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 460 101.6 0.918 XFN00064B MFN00096B REACTOR BUILDING COOLING UNIT FAN (MFN0096B) 275.0 246.5 0.889 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 460 219.2 0.936 XFN00064B MFN00097B REACTOR BUILDING COOLING UNIT FAN (MFN0097B) 75.0 77.4 0.779 25 YES 90.0 72.3 92.9 90.0 72.3 92.9 90.0 72.3 92.9 90.0 72.3 92.9 90.0 72.3 92.9 90.0 72.3 92.9 6,14,27 460 60.3 0.928 XFN00065B MFN00096D REACTOR BUILDING COOLING UNIT FAN (MFN0096D) 275.0 246.5 0.889 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 460 219.2 0.936 XFN00065B MFN00097D REACTOR BUILDING COOLING UNIT FAN (MFN0097D) 75.0 77.4 0.779 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 14,27 460 60.3 0.928 XHX00001B HVAC SYSTEM MECHANICAL WATER CHILLER B 321.0 286.1 0.900 30 YES 321.0 257.5 286.1 321.0 257.5 286.1 321.0 257.5 286.1 321.0 257.5 286.1 321.0 257.5 286.1 321.0 257.5 286.1 13 460 257.5 0.930 XHX00001C TRAIN B HVAC SYSTEM MECHANICAL WATER CHILLER C - LOAD FOR TRAIN B 321.0 286.1 0.900 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 16 460 257.5 0.930 XPP00031B RESIDUAL HEAT REMOVAL PUMP B 300.0 262.2 0.914 0 YES 285.0 227.6 249.1 300.0 239.6 262.2 285.0 227.6 249.1 285.0 227.6 249.1 285.0 227.6 249.1 300.0 239.6 262.2 460 239.6 0.934 8.3-75 Reformatted May 2018

FSAR TABLE 8.3-3 PART B2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XSW1DB1 (Continued)

XPP00040B REACTOR MAKE-UP WATER PUMP B 60.0 58.3 0.850 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 460 49.6 0.903 XPP00045B SERVICE WATER BOOSTER PUMP B 350.0 303.5 0.920 35 YES 250.0 199.5 216.8 250.0 199.5 216.8 250.0 199.5 216.8 250.0 199.5 216.8 250.0 199.5 216.8 0.0 0.0 0.0 7,14 460 279.3 0.935 Total Load On Switchgear: XSW1DB1 764.6 853.9 999.4 1127.5 764.6 853.9 987.4 1114.4 987.4 1114.4 800.0 910.6 XSW1DB2 APN01DB2 SWITCHGEAR XSW1DB2 DISTR. PNL.

10.0 10.0 0.850 0 N/A 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 480 8.5 XFN00023B FUEL BUILDING EXHAUST FAN 23B 60.0 59.0 0.831 25 YES 56.0 45.8 55.1 56.0 45.8 55.1 56.0 45.8 55.1 56.0 45.8 55.1 56.0 45.8 55.1 56.0 45.8 55.1 460 49.0 0.913 XHR00004B HYDROGEN RECOMBINER B 75.0 75.0 1.000 N/A NO 0.0 0.0 0.0 75.0 75.0 75.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1,28 480 75.0 XIT05936 TRAIN B INCOMING TRAIN B POWER RN 125.0 125.0 1.000 0 N/A 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 60.4 15 17-033 480 125.0 XPP00032B SPENT FUEL PIT COOLING PUMP B 75.0 73.4 0.840 N/A NO 0.0 0.0 0.0 60.0 49.3 58.7 0.0 0.0 0.0 60.0 49.3 58.7 60.0 49.3 58.7 60.0 49.3 58.7 1,29 460 61.6 0.908 XPP00048B HVAC SYSTEM CHILL WATER PUMP B 60.0 53.4 0.930 10 YES 48.0 39.7 42.7 48.0 39.7 42.7 48.0 39.7 42.7 48.0 39.7 42.7 48.0 39.7 42.7 48.0 39.7 42.7 13 460 49.6 0.902 XPP00048C TRAIN B CHILLED WATER PUMP C - LOAD FOR TRAIN B 50.0 44.4 0.920 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 16 460 40.9 0.913 XSW1DB2 BUS 13.3 13.3 0.000 N/A 13.3 0.0 13.3 13.3 0.0 13.3 13.3 0.0 13.3 13.3 0.0 13.3 13.3 0.0 13.3 13.3 0.0 13.3 RN 480 0.0 17-033 Total Load On Switchgear: XSW1DB2 153.5 180.5 277.8 314.1 153.5 180.5 202.8 239.2 202.8 239.2 202.8 239.2 XSW1EB MPP00039B SERVICE WATER PUMP B MOTOR 700.0 622.0 0.922 10 YES 650.0 532.5 577.6 650.0 532.5 577.6 650.0 532.5 577.6 650.0 532.5 577.6 650.0 532.5 577.6 650.0 532.5 577.6 12 6900 573.5 0.911 MPP00039C TRAIN B SERVICE WATER PUMP C MOTOR - LOAD FOR TRAIN B 700.0 622.0 0.922 N/A NO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 16 6900 573.5 0.911 Total Load On Switchgear: XSW1EB 532.5 577.6 532.5 577.6 532.5 577.6 532.5 577.6 532.5 577.6 532.5 577.6 8.3-76 Reformatted May 2018

FSAR TABLE 8.3-3 PART B2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B LARGE BREAK LOCA WITH A LOOP STEAM LINE BREAK WITH A LOOP LOSS OF OFFSITE POWER Rated Load Data (9) Injection Phase - 1/2 to 1 Hour Indefinite Recirc. (8) Short Term Phase - 2 Hours Long Term. (8) Hot Standby - 30 Hours Cold Shutdown (8)

<-----------------------------------> Load (20) <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------> <-------------------------------------> <------------------------------------>

Hp/kVA kVA PF Seq Auto (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33) (31) (32) (33)

Tag Number Volts kW Eff (Sec.) Start Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Bhp/kVA kW kVA Notes XSW1EB1 APN01EB1 SWITCHGEAR XSW1EB1 DISTRIBUTION PANEL 10.0 10.0 0.850 0 N/A 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 9.0 7.6 9.0 480 8.5 Total Load On Switchgear: XSW1EB1 7.6 9.0 7.6 9.0 7.6 9.0 7.6 9.0 7.6 9.0 7.6 9.0 Subtotal Load On The Diesel Generator: 3890.5 4414.4 3834.5 4316.1 3890.5 4414.4 3057.8 3478.9 4245.0 4767.6 2498.8 2850.4 RN 17-033 Cable Losses: 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 Transformer Losses: 31.0 31.0 31.0 31.0 31.0 31.0 31.0 31.0 31.0 31.0 31.0 31.0 RN 17-033 Generator Exciter Load: 25.0 30.0 25.0 30.0 25.0 30.0 25.0 30.0 25.0 30.0 25.0 30.0 RN Total Generator Load With Optional Loads: 3956.5 4485.4 3900.5 4387.1 3956.5 4485.4 3123.8 3549.9 4311.0 4838.6 2564.8 2921.4 10 17-033 Optional Loads: 0.0 0.0 400.6 455.6 0.0 0.0 324.2 379.0 809.3 864.1 324.2 379.0 Total Generator Load Without Optional Loads: 3956.4 4485.4 3499.9 3931.4 3956.4 4485.4 2799.6 3170.9 3501.7 3974.5 2240.6 2542.4 RN 17-033 Total Records Printed: 91 8.3-77 Reformatted May 2018

FSAR TABLE 8.3-3 PART B2 BASIS FOR DIESEL GENERATOR FUEL OIL CONSUMPTION Connected Automatic and Manual Loading and Unloading of the Diesel Generator Channel B Notes:

1 This is an optional load which can be started manually. It may be added if the DG loading conditions permit, and this load was not considered for fuel oil storage requirements since it is not a required load.

2 The pump is normally in low speed but is assumed to be auto-started in high speed. The speed change switch is manually operated. The pump will be operated in high speed for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for the first 7 days following a DBE.

If both DGs are running, only one train's pump will be in high speed during the plant shutdown.

3 The pump starts on receipt of a spray initiation signal.

4 The motor is not required for the accident scenarios but the motor will be running as it is not locked out by the load sequencer.

5 The motor is running in the Hot Standby scenario as the SWBP is automatically started by the load sequencer.

6 The motor is not required for the LOOP - Hot standby / Cold shutdown scenarios but is auto started by the load sequencer and expected to remain on for air circulation related purposes.

7 The motor is not required for the LOOP - Hot standby scenario but is auto started by the load sequencer.

8 The equipment is required to be operable for six months following an accident.

9 Time 0 indicates the emergency diesel generator has started and reached no load speed and voltage, at which the circuit breaker connecting to the 7200 volt bus has closed.

10 Total includes the RHR pump and all manual loads whose application will be limited so that neither the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating (4676 kW) is exceeded for more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> nor the continuous rating of 4250 kW is exceeded.

11 The required safety function is for emergency core cooling.

12 The required safety function is for emergency core cooling and containment cooling.

13 The required safety function is for equipment area cooling.

14 The required safety function is for containment cooling.

15 This inverter is assumed to be running on this diesel generator. It is fed via a manual switchgear breaker.

16 The "C" train equipment is assumed to be not running as the normal train equipment is running.

17 This equipment is assumed to be supplied from this diesel generator.

18 Generator efficiency is assumed to be taken into account by the diesel manufacturer as the load limit is based on generator output kW (including the exciter) as monitored at the MCB.

19 The dc powered oil pumps associated with the turning gear are included in the battery charger loads.

20 For the Auto-Start columns, YES means the load is able to automatically start based on its control circuitry, NO means it does not, and N/A means the load is continuous and not subject to starting and stopping.

21 The normal battery charger is assumed in service.

22 The load is locked out on receipt of an SI signal.

23 The fan runs only when the EFWP is running.

24 The compressor runs only to recharge the air start system. It is assumed to be running in the first hour only.

25 XTG00001 will be running less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> total during the 7 days following a DBE.

26 The fan is expected to be manually started within the first 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> and is therefore shown as a load for the LOOP/Hot Standby mode.

27 Only 1 out of 2 RBCU fans is required to run post accident as selected.

28 The H2 recombiner will be operated as needed to support post accident response.

29 The pump will be operated as needed to maintain spent fuel pool temperatures within acceptable limits.

30 The component cooling water pump slow speed ratings are 250hp, .8094 PF, .9114 Efficiency, and 250kVA.

31 The "BHP/kVA" field lists the demand load that has been calculated for the specified event.

32 The "kW" field equals BHP/kVA x 0.746 kW/HP / EFF for motors. For non-motor loads this field equals BHP / kVA x PF.

33 The "kVA" field equals BHP / kVA x 0.746 kW/HP / (EFF x PF) for motors. For non-motor loads this field equals BHP / kVA.

8.3-78 Reformatted May 2018

TABLE 8.3-3a DIESEL GENERATOR PROTECTIVE DEVICES Protective Relay Function if Diesel Start is Initiated By:

ESF OR Test Device Undervoltage Start Switch 67 DG Motoring - reverse power flow Alarm Trip (2) RN 98-027 51 DG Ground Overcurrent Alarm (2) R1 Trip 51VDG Time overcurrent - voltage controlled Alarm Trip (2) 46 DG Negative phase sequence Alarm Trip (2) 64 FDG Field ground relay Alarm Alarm 87 DG Generator differential Trip (3)

Trip (3)

RN 40 DG Field failure relay Alarm Trip (2)98-027 R1 Lube oil pressure low (4 switches) Trip (1) (3)

Trip (3)

Engine overspeed Trip (3)

Trip (3)

Crankcase pressure high Alarm Trip (3)

Lube Oil temperature high Alarm Trip (3)

Jacket coolant temperature high Alarm Trip (3) 59 Overvoltage Alarm Alarm Fuel Oil Pressure Low Alarm Alarm RN Start failure Alarm Alarm 98-027 Barring Device Engaged Prevent Start Prevent start R1 Note:

1. Trip occurs on actuation of 2 of 4 switches if at least 1 of the 2 actuated switches has setpoint of 60 psi. Setpoints are at 70, 65, 60, and 60 psi.
2. Trips Diesel Generator Breaker only.
3. Trips Diesel Generator Breaker and Diesel Generator Engine.

8.3-79 Reformatted July 2019

TABLE 8.3-3b ENGINEERED SAFETY FEATURES BUS INDICATORS Indicator Type Function Location GE Type AB-40, Frequency Meter Diesel generator A, frequency Main Control Board (MCB) panel XCP6117 GE Type AB-40, A-C Wattmeter Diesel generator A, watts MCB panel XCP6117 GE Type AB-40, A-C Voltmeter Diesel generator A, volts MCB panel XCP6117 GE Type AB-40, A-C Wattmeter ESF transformer, watts MCB panel XCP6117 GE Type AB-40, A-C Voltmeter ESF bus 1DA, volts MCB panel XCP6117 GE Type AB-40, A-C Varmeter ESF transformer, vars MCB panel XCP6117 GE Type 180, A-C Ammeter Diesel generator A, amperes MCB panel XCP6117 GE Type 180, A-C Ammeter ESF transformer, amperes MCB panel XCP6117 GE Type 180, A-C Ammeter 7.2 kV bus 1DA feeder, amperes MCB panel XCP6117 GE Type AB-40, Frequency Meter Diesel generator B, frequency MCB panel XCP6117 GE Type AB-40, A-C Wattmeter Diesel generator B, watts MCB panel XCP6117 GE Type AB-40, A-C Voltmeter Diesel generator B, volts MCB panel XCP6117 GE Type AB-40, A-C Voltmeter 7.2 kV bus 1DB, volts MCB panel XCP6117 GE Type 180, A-C Ammeter Diesel generator B, amperes MCB panel XCP6117 GE Type 180, A-C Ammeter 7.2 kV bus 1DB feeder, amperes MCB panel XCP6117 RN GE Type AB-40, A-C Ammeter 7.2 kV bus tie 1DX2DX, amperes MCB panel XCP6117 99-002 Electro Industries DTVA120, A-C Voltmeter 115 kV incoming, volts MCB panel XCP6117 RN 19-014 8.3-80 Reformatted July 2019

TABLE 8.3-4 IDENTIFICATION OF SAFETY-RELATED CABLE TRAYS AND CABLES Engineered Safety Reactor Protection Process Control Features Actuation &

Color Channel Channel Equipment Channel Red I 1 A, J Orange II 2 D, L Blue III 3 B, K Yellow IV 4 E, M Green - - C Tan, plus Associated - X, plus channel Channel Color 99-01 Tan or no color Non-Safety-Related - X 8.3-81 Reformatted July 2019

TABLE 8.3-5 SEQUENCE OF OPERATION FOLLOWING A LOSS OR DEGRADED VOLTAGE CONDITION Items of Operation Loss of Voltage Degraded Voltage (Time in Seconds) (Time in Seconds)

Loss or Degraded Voltage Condition 0 0 Diesel Generator Start 0.25 3 Permissive to EFW Pump Start 0.25 3 Initiate ESFLS Operation 2.25 7 7.2Kv Bus Circuit Breaker Trip 2.25 7 Permissive to Close Diesel Generator 5.25 10 Circuit Breaker Diesel Generator Ready to Load 10.25 13 (Initiate Block Loading) 8.3-82 Reformatted July 2019

FSAR FIGURE REFERENCE FIGURE 8.3-0 DRAWING 1MS-33-007

FSAR FIGURE REFERENCE FIGURE 8.3-0a DRAWING 1MS-33-008

FSAR FIGURE REFERENCE FIGURE 8.3-0b DRAWING 1MS-33-009

FSAR FIGURE REFERENCE FIGURE 8.3-0b.1 DRAWING 1MS-33-191

FSAR FIGURE REFERENCE FIGURE 8.3-0c DRAWING 1MS-33-028

FSAR FIGURE REFERENCE FIGURE 8.3-0d DRAWING 1MS-33-029

FSAR FIGURE REFERENCE FIGURE 8.3-0e DRAWING 1MS-33-030

FSAR FIGURE REFERENCE FIGURE 8.3-0f DRAWING 1MS-33-033

FSAR FIGURE REFERENCE FIGURE 8.3-0g DRAWING 1MS-33-034

FSAR FIGURE REFERENCE FIGURE 8.3-0h DRAWING C-203-005

FSAR FIGURE REFERENCE FIGURE 8.3-0i DRAWING C-203-006

FSAR FIGURE REFERENCE FIGURE 8.3-0j DRAWING C-203-007

FSAR FIGURE REFERENCE FIGURE 8.3-0k DRAWING C-203-008

FSAR FIGURE REFERENCE FIGURE 8.3-0l DRAWING C-203-009

1 2 3 4 5 6 DG FUEL NOTE 1 - INCLUDES:

DG LOW DG DG FUEL OIL STORAGE OIL DAY TANK DG ENGINE Al STARTING AIR LOW PRESSURE; Bl DIFFERENTIAL LOCKOUT ENERGIZED:

LUBE OIL OVERSPEED NOTE 5 TANK LOW/LOW LOW/LOW LEVEL FAILED START Cl LOW LUBE OIL PRESSURE; OJ BARRING DEVICE ENGAGED; El DIESEL PRESSURE TRIP LEVEL GENERA TOR AUXILIARIES NOT IN AUTO POSITION; Fl MANUAL VALVES NOT ALIGNED PROPERLY; Gl SELECTOR SWITCH 43 IN MAINTENANCE: HJ LOSS OF DC POWER; Il ENGINE TROUBLE SHUTDOWN; Jl START FAILURE RELAY; DG NOT DG FUEL DG ENGINE Kl EXCITER NOT RESET.

DG AUX DG FUEL 2 READY FOR OIL STORAGE RUNNING NOT IN AUTO OIL DAY TANK NOTE 5 TROUBLE AUTO START TANK HI/LOW NOTE 2 INCLUDES:

POSITION LOW LEVEL (NOTE 2l (NOTE 1l LEVEL Al LOW COOLANT PRESSURE: Bl FUEL OIL PUMP RUNNING; CJ WATER IN AIR TANKS; OJ HIGH AFTER COOLING TEMPERATURE; El CRANKCASE PRESSURE HIGH; Fl ROCKER ARM LUBE OIL LEVEL HIGH: Gl ROCKER ARM LUBE OIL OG DG MANUAL DG ENGINE PRESSURE LOW: HJ LUBE OIL LEVEL LOW;IlCOOLANT SYSTEM LEVEL LOW; STARTING DG FUEL DG LOSS 3 VLVS NOT TEMPERATURE JJFUEL OIL DAY TANK LEVEL HIGH;KJAIR INTAKE DIFFERENTIAL PRESSURE OIL LOW OF DC NOTE 5 AIR LOW ALIGNED HIGH.

PRESSURE POWER TROUBLE PRESSURE PROPERLY (NOTE 3l NOTE 3 INCLUDES:

DG AJLUBE OIL TEMPERATURE LOW; Bl COOLING SYSTEM TEMPERATURE LOW; DG DIFF GENERATOR Cl LUBE OIL TEMPERATURE HIGH; OJ COOLING SYSTEM TEMPERATURE HIGH 4 SPARE LOCKOUT NOTE 5 NOTE 5 TROUBLE NOTE 5 ENERGIZED (NOTE 4l NOTE 4 INCLUDES:

AJOVERVOLTAGE; BJOVERCURRENT 51VDG; Cl REVERSE POWER 67DG; DJGEN.STATOR HIGH TEMPERATURE: EJNEG.PHASE SEQUENCE 46DG; DG ENGINE DG SELECT Fl FIELD GROUND 64DG; Gl FIELD FAILURE 400G; HJ SYSTEM GROUND 5 TROUBLE SWITCH IN NOTE 5 SPARE NOTE 5 51DG.

SHUTDOWN MAINTENANCE NOTE 5 - ALARMS ASSOCIATED WITH OTHER SYSTEMS DG BARRING DG DEVICE ANNUNCIATOR 6 NOTE 5 NOTE 5 NOTE 5 NOTE 5 ENGAGED GROUND/POWER FAILURE SOUTH CMOLINA ELECTRIC 8t GAS CO.

(SHOWN TYPICAL FOR BOTH ANNUNCIATOR STATIONS XCP0636 & XCP0637.l VIRGIL C. SUMMER NUCLEAR STATION MAIN CONTROL BOARD ANNUNCIATOR STATION B-804-636 SH.1 8t 637 SH.1 REV.9 Flgin 8.3-0m AMENDMENT 00-01 DECEMBER

  • ----~

2000

1 2 3 4 5 5 7 8 ROCKER ARM I

LOW ROCKER LOW START- START LUBE PUMP DIFFERENTIAL LOW LUBE LOW COOLANT LOW FUEL 1 OIL PRESSURE PRESSURE OIL PRESSURE ARM LUBE OIL AIR PRESSURE FAILURE OVERRUN OR CONT ACTOR )

GENERATOR LOCKOUT PRESSURE  ; \

I FAILURE

\. . -

HIGH LUBE OIL HIGH COOLANT DC FUEL OIL HIGH ROCKER WATER IN OVERSPEED OVERCURRENT SYSTEM ARM LUBE OIL AIR TANKS 2 TEMPERATURE TEMPERATURE PUMP RUNNING LEVEL TRIP 51 VDG GROUND 51 DG HIGH FUEL HIGH HIGH ENGINE REVERSE NEGATIVE PHASE LOW LUBE OIL LOW COOLANT TEMPERATURE OIL LEVEL CRANKCASE AFTERCOOLER TROUBLE POWER 67 DG SEQUENCE 46 DG 3 TEMPERATURE PRESSURE SHUTDOWN c==1 TEMPERATURE HIGH AIR LOW LUBE LOW COOLANT LOW FUEL EMERGENCY GENERATOR FIELD INT AKE FILTER OVERVOLTAGE OIL LEVEL LEVEL OIL LEVEL SHUTDOWN STATOR HIGH GROUND 4 DIFF. PRESSURE TEMPERATURE 64 DG c==1 SELECTOR VALVE LOCAL AUX. SWITCH FIELD LOSS OF BARRING LOW-LOW FUEL SWITCH IN IMPROPER CONTROL NOT IN AUTO FAILURE DEVICE OIL LEVEL 5 DC POWER POSITION 40 DG c==1 ENGAGED MAINTENANCE

<SHOWN TYPICAL FOR BOTH ANNUNCIATOR STATIONS XCX5201 & XCX5202.l SOUTH CAROLINA ELECTRIC & GAS CO.

VIRGIL C. SUMMER NUCLEAR STATION DIESEL GENERATOR LOCAL ANNUNCIATOR STATIONS DWG. NO. 1MS-32-120 REV. 0 Figure 8.3-0n

. sm I n I n I II I II I 111**11

FSAR FIGURE REFERENCE FIGURE 8.3-0o DRAWING C-203-010

FSAR FIGURE REFERENCE FIGURE 8.3-1 DRAWING E-206-062

FSAR FIGURE REFERENCE FIGURE 8.3-2 DRAWING E-206-062

FSAR FIGURE REFERENCE FIGURE 8.3-2a, Sheet 1 DRAWING E-216-011

FSAR FIGURE REFERENCE FIGURE 8.3-2aa DRAWING E-206-062

FSAR FIGURE REFERENCE FIGURE 8.3-2ab DRAWING E-206-062

FSAR FIGURE REFERENCE FIGURE 8.3-2b DRAWING E-216-012

FSAR FIGURE REFERENCE FIGURE 8.3-2c DRAWING E-216-013

FSAR FIGURE REFERENCE FIGURE 8.3-2d DRAWING E-216-014

FSAR FIGURE REFERENCE FIGURE 8.3-2e DRAWING E-434-006

FSAR FIGURE REFERENCE FIGURE 8.3-2f DRAWING E-434-007

FSAR FIGURE REFERENCE FIGURE 8.3-2g DRAWING E-441-001

FUEL.

N qua d. 4-1--4 HOL.~. BLDG,.

NIS*

17 -----!~--


!~-- ~uod.1 REACTOR.

BLDc:,.

o BLDG.

Quad .. ~ - - - 0 \ - - -

Quad.~~------~

NlS-'*

NlS'* 't\,JQd. '2.

II.---I----

-~ NIS 1*

CO ....

.JT~OL.

JT~OL.

BL.D~.

BL.D~.

t-JTERMEDIA,TE I t-JTERMEDIA,TE

__----1.._. . . . . .

__----1.._..........

BLDG,. >>t5 m *"

UCLe.AR

~-N UCLEAR IJ1JSTR ..

IJlJSTR TURBI~e:

TURBI~e:

SYS,EM (/<.lIS)

SYS\'EM ("'JIs) t:>LD~. C H"'t-.hIELS I}

CH",tJtJELS l} 1I.m II. m 4-::Dl 4.:Dl EACt-l SYMP.:lOL.

SYMP.:IOL-REPRESENTS REPR.ESENTS A PA\R of: '2" ,'2."

PE~ETR.AT'O~St FOR PE~ETR.AT'O~St NeuTRON NEUTRON DETeCTo~ elRc'S ...

DETeCTo~ eIRc'S...

SEPARATION CRITERIA (DISTANCES ARE CENTER LINE ABOVE MEZZANINE ELEVATION 436'-0". TO CENTER LINE)

A 4'-0" HORIZONTAL AND VERTICAL SPACING MAY BE USED BETWEEN ANY 2 ADJACENT PENETRATIONS A4'-0" IF THE COMBINED RADI I OF THE PENETRATIONS DO NOT EXCEED 18".

A MINIMUM OF 18" CANNOT BE USED THEN THE SPACINGS MUST GO TO AT LEAST 8'-0".

IF AMINIMUM BELOW MEZZANINE ELEVATION 436'-0".

VERTICAL SPACINGS - SAME AS ABOVE.

HORIZONTAL SPACINGS ~- SAME AS ABOVE - EXCEPT THAT THE COMBINED RADII OF THE PENETRATIONS 10",

MUST NOT EXCEED 10".

A MINIMUM OF 10" CANNOT BE USED THEN THE SPACINGS MUST GO TO 8'-0".

IF AMINIMUM AMENDMENT 0 AUGUST 1984 SOUTH CAROLINA ELECTRIC & GAS CO.

VIRGIL C. SUMMER NUCLEAR STATION Containment Penetration Separation Figure 8.3-3

FSAR FIGURE REFERENCE FIGURE 8.3-4, Sheet 1 DRAWING E-206-061

FSAR FIGURE REFERENCE FIGURE 8.3-4a, Sheet 2 DRAWING E-206-061

FSAR FIGURE REFERENCE FIGURE 8.3-4b, Sheet 3 DRAWING E-206-061

FSAR FIGURE REFERENCE FIGURE 8.3-5 DRAWING E-229-025

FSAR FIGURE REFERENCE FIGURE 8.3-5a DRAWING E-229-152

FSAR FIGURE REFERENCE FIGURE 8.3-6 DRAWING 1MS-37-043

FSAR FIGURE REFERENCE FIGURE 8.3-7 DRAWING 1MS-37-041

FSAR FIGURE REFERENCE FIGURE 8.3-8 DRAWING E-203-201

8.4 STATION BLACKOUT V. C. Summer Nuclear Station Unit No. 1 conforms to 10CFR50.63 entitled "Loss of All Alternating Current Power" (Station Blackout). V. C. Summer's program meets the guidance provided by Regulatory Guide (RG) 1.155, Station Blackout; Nuclear Management and Resources Council, Inc (NUMARC) 87-00, Guidelines and Technical Bases for NUMARC Initiatives addressing Station Blackout at Light Water Reactors; and NUMARC 87-00 Supplemental Questions/Answers and Major Assumptions dated December 27, 1989. Virgil C. Summer Technical Report TR08200-003 entitled "Compliance to NRC Rule 10CFR50.63" (Station Blackout), documents VCSNS compliance. Additional details are provided in the NRC issued Safety Evaluations References 1 and 2.

8.4.1 STATION BLACKOUT DURATION NUMARC 87-00 was used to determine an SBO duration of four hours.

The following plant factors were identified in determining the proposed Station Blackout duration:

1. AC Power Design Characteristic Group is P1 based on: 00-01
a. Independence of offsite power classification of Group "1 1/2"
b. Severe weather (SW) classification of Group "1"
c. An extreme severe weather (ESW) classification of Group "3"
2. The emergency AC power configuration group is C based on:
a. There are two EDGs credited as AC power supplies
b. One emergency AC power supply is necessary to operate safe shutdown equipment following a loss of offsite power.
3. The target EDG reliability is 0.95.
a. A target EDG reliability of 0.95 was based on the Virgil C. Summer Station having an average EDG greater than 0.95 over the last 100 demands.
b. EDG failure statistics for the last 20 and 50 demands, in accordance with the requirements of RG 1.155 was provided, which confirms that the target selection is appropriate.

8.4-1 New Section Per Amendment 00-01

8.4.2 COPING METHOD The V. C. Summer Nuclear Station coping method is in accordance with the "AC-Independent Approach" delineated in NUMARC 87-00 for the required coping duration of four hours and recovery therefrom. In this approach for VCSNS, DC power is required to be available for the coping duration to operate equipment necessary to achieve safe shutdown conditions until offsite or emergency AC power is restored. The following plant systems and components are required to have the availability, adequacy, and capability to achieve and maintain a safe shutdown and to recover from an SBO for a four-hour coping duration.

8.4.2.1 Class 1E Battery Capacity The V. C. Summer Nuclear Station has sufficient battery capacity and size to support decay heat removal during a Station Blackout for the required four-hour coping duration in accordance with NUMARC 87-00 without load stripping, as discussed in Section 8.3.2.1.2. The battery analysis is documented/maintained in SCE&G Calculation DC08320-005.

8.4.2.2 Condensate Inventory For Decay Heat Removal 00-01 The V. C. Summer plant has adequate condensate inventory for decay heat removal during a Station Blackout for a required duration of four hours. The necessary condensate inventory is assessed by a bounding analysis based on the NUMARC 87-00 Equation. The minimum permissible condensate storage tank level per technical specification requirements provides 172,700 gallons, which exceeds the required quantity for coping with a four-hour Station Blackout per SCE&G Technical Report TR08200-003.

8.4.2.3 Compressed Air The V. C. Summer air operated valves required for decay heat removal have been evaluated and accepted for manual operation under Station Blackout conditions for the four-hour duration.

8.4.2.4 Effects of Loss of Ventilation The effects of loss of ventilation within areas of the plant containing equipment necessary to achieve and maintain safe shutdown during a Station Blackout is evaluated per NUMARC 87-00. The dominant areas of concern (DACs) and analysis are documented in SCE&G Technical Report TR08200-003.

8.4-2 New Section Per Amendment 00-01

8.4.2.5 Containment Isolation Containment isolation valves that must be operated under SBO conditions must have the ability to be positioned, with indication, independent of the preferred and Class 1E AC power supplies and that no modifications or procedure changes are necessary to ensure containment integrity can be obtained if it is needed under SBO conditions.

Containment isolation valve design and operation at VCSNS meet the intent of the guidance described in RG 1.155.

8.4.2.6 Reactor Coolant Inventory The ability to maintain adequate reactor coolant system (RCS) inventory to ensure that the core is cooled has been assessed for four hours. The generic analysis listed in NUMARC 87-00 was used in this assessment. The expected rates of RCS inventory loss under SBO conditions do not result in core uncovery.

00-01 8.

4.3 REFERENCES

1. USNRC Letter to SCE&G dated January 30, 1992,

Subject:

Safety Evaluation Regarding Station Blackout Analysis, Virgil C. Summer Nuclear Station, Unit No. 1 (TAC No. M68610).

2. USNRC Letter to SCE&G dated June 1, 1992,

Subject:

Supplemental Safety Evaluation Regarding Station Blackout, Virgil C. Summer Nuclear Station, Unit No.

1 (TAC No. M68610).

3. U. S. Nuclear Commission Regulatory Guide 1.155, "Station Blackout".
4. NUMARC 87-00, Nuclear Management and Resources Council, "Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors".

8.4-3 New Section Per Amendment 00-01

APPENDIX 8A ADDITIONAL CABLE AND TRAY DESIGN CONSIDERATIONS 8A.1 METHODS EMPLOYED Sections 8A.1.1 through 8A.1.3 describe methods employed to show sufficient conservatism in the cable and tray design to assure that adequate cable tray hanger strength exists, that cables are sufficiently sized, and that the weight of upper cables in trays does not damage bottom layer cables.

8A.1.1 WEIGHT ON HANGER Cables are routed in tray in two different configurations (e.g., single lay and random lay). The weight of the cables, tray, tray covers, fire barrier materials on the tray, and any conduits and pipes hung from the tray supports were used to establish the tray support cap ability. The allowable cable weight limit is based on the capability of the cable tray (e.g., 35 lbs/ft2 of tray bottom area for single lay 4" deep trays and 45 lbs/ft2 of tray bottom area for random lay 6" deep trays).

For single lay cable tray, percent fill and cable heating were not the deciding factors for limiting tray fill. Engineering determined that the maximum number of cables that a single lay tray can accommodate is based on the cable diameters versus the width of the tray.

The initial design criteria for random lay tray was based on a maximum of 50% fill.

00-01 Engineering performed calculations to ensure that cable heating and cable weight were acceptable whenever the tray fill was less than 50%. Because the tray fill was conservatively calculated based on the square of the cable diameter in lieu of the cross sectional area of the cable, the actual tray fill is less than the calculated tray fill. The cable management system computer program was used to monitor tray fill. The 50%

limit originally established was found to be inadequate as cables were added over the life of the plant. Therefore, calculations were performed whenever a random lay cable tray fill exceeded 50%. Subsequently the criteria for random lay power cable trays was changed to weight per tray support with an alarm point of either 50% fill for trays presently less than 50% filled or the last calculated allowable % fill for trays whose fill exceeded 50%. In addition, the criteria and alarm point for instrument and control tray were changed to weight only per tray support only, since heat loading was not a concern.

8A-1 Reformatted Per Amendment 00-01

Whenever a power cable is added to a random lay power tray and the associated tray fill exceeds the previously accepted percent tray fill limit, a calculation is performed.

The calculation addresses additional loading from the new power cables to ensure that the combined weight of the new and existing cables is less than the allowable design weight capability of the tray support. Heat loading is also evaluated to ensure that the existing ampacity derating factors are still applicable.

Engineering determined that cable heating was not a concern for the small currents and intermittent operating conditions associated with control and instrument cables and 00-01 therefore only total cable weight needed to be considered. The design limit for control and instrumentation cable tray fill is based on verifying that the weight of the new and existing cable does not exceed the tray and tray support weight capability. The cable tray fill criteria for control and instrument trays is controlled by the cable management system computer program. This program contains an alarm limit for the maximum weight allowed for each tray size used. Therefore, manual calculations to monitor cable weight are not required because this calculation is performed by the cable management system and an alarm is provided if the tray or tray support weight capability is exceeded.

8A.1.2 CABLE HEATING Single layer kV and 480 volt cable trays need not be considered with respect to possible cable overheating since, inherently, the fill is limited to the single layer of cable with appropriate derating factors applied. Rated ampacities are in accordance with ICEA P-46-426 [1]; the free air ratings for the applicable ambient temperatures were derated 00-01 for the presence of adjacent power cables. In addition, a load factor of 100 percent was 00-01 assumed and feeders are sized for 110, 125, or 140 percent of rated current, depending upon type of service (resistive loads; motors, power panels and small transformers; and large power transformers, respectively).

No ampacity derating factors are applied to control and instrument cables due to the type of service and low current levels.

For random lay power trays (Reference [2], Table 12), a 3 inch depth was used to determine cable ampacity. Therefore, derating due to tray fill need only be considered for trays with fill greater than 50 percent design objective, since the 50 percent design fill is equivalent to a 3 inch depth. The 100 percent load factor feeder sizing considerations previously noted were also applied, along with appropriate derating where required for higher ambient temperatures.

In selected cases fill above 50% was authorized to larger values after specific evaluation of heat dissipation and weight loading. Heat dissipation was evaluated using the methods described in Reference [3].

8A-2 Reformatted Per Amendment 00-01

From Figure 4 of Reference [3] the following linear approximation can be made for the 02-01 allowable heat generation versus tray fill:

6 .5 Qd = (1) d1.47 Where:

Q d = Allowable heat generation per unit area of cable cross-section to limit conductor temperature to 90°C d = Depth of tray fill in inches Since heat generation in a given cable at a fixed temperature is proportional to the square of the current, the following relationships can be established:

Q d = KI2d (2)

Where:

Id = Ampacity of cable for tray fill depth d K = Constant Combining into equation (1) and developing a ratio: 00-01 Q d' KI2d' (d)1.47

Qd KI2d (d' )1.47 Using the relationship, the curve of Figure 4 in Reference [3] was extended to cover larger fills of six inch deep tray. Because Reference [3] was developed for three inch deep tray, the tray fill permitted is one-half the value shown in Figure 4. As long as the tray fill meets this criterion, the cable ampacities of Reference [2] are still permissible.

There is an additional margin of conservatism in the heat dissipation calculation. Tray fill is calculated using diameter squared to represent cable cross-sectional area instead of actual cable area. This represents a margin of 27.3 percent above actual tray fill. In addition, non-continuous current carrying cables are not included in heat density calculations but are included in tray fill and weight calculations, which ensures conservatism.

No ampacity derating of cables has been necessary because of heat dissipation.

8A-3 Reformatted Per Amendment 00-01

8A.1.3 CABLE SIDE WALL PRESSURE In accordance with manufactures published information the maximum allowable side wall pressure of typical cables used is considerably higher than the pressure that cables 00-01 on the bottom of a tray will experience from cables above, even for fills in excess of 50 percent. The minimum allowable side wall pressure is 50 lb/ft, while the maximum 00-01 loading per cable in a tray filled to the tray support limit, or 100% physical fill, will be less than 7 lb/ft [18] *.

8A.2 CONCLUSIONS Tray fill is monitored by computer. Any tray that exceeds the design fill is reported on a separate printout. This printout is used in routing design, and cables are routed through other, less full trays. Late in construction other trays may exceed the maximum values justified in Sections 8A.1.1 through 8A.1.3. When this occurs, the situation will be evaluated and action will be taken to relieve such a condition. Alternatives are to calculate the actual tray load and verify that the load does not exceed the design capacity, enlarge the existing tray, strengthen the existing hangers, or in the case of random lay power trays where the concern is ampacity, each individual circuit application can be evaluated and the total ampacity calculated.

8A.3 REFERENCES

1. Insulated Cable Engineers Association, "Power Cable Ampacities," ICEA P-46-426-1962.
2. Insulated Cable Engineers Association, "Ampacities of Cables in Open-Top Cable Trays," ICEA P-54-440.
3. Stolpe, J. "Ampacities for Cables in Randomly Filled Trays," Institute of Electrical 00-01 and Electronics Engineers Transaction Paper 70TP557PWR.
  • Refers to Section 8.3, Reference [18], Calculation No. DC08500-022, "Determination of Maximum Sidewall Pressure Imposed on Cable in Cable Tray as a Result of Cable Weight." 02-01 See Amendment 00-01, Revision Notice 99-14.

8A-4 Reformatted Per Amendment 00-01

RN NOTE Appendix 8B 98-173 Appendix 8B is being retained for historical purposes only.

APPENDIX 8B CABLE RACEWAY FIRE BARRIERS DESIGN 8B.1 PURPOSE This report describes the criteria, assumptions and design used by Gilbert Associates, Inc. (GAI) to locate and construct cable raceway fire barriers on the Virgil C. Summer Nuclear Station for the South Carolina Electric and Gas Company.

8B.2 CRITERIA Fire barriers were designed to comply with IEEE Standard 384-1977 Criteria for Independence of Class 1E Equipment and Circuits.

Fire barriers are required to prevent propagation of a fire between two, or more, raceways of redundant divisions or non-class 1E to Class 1E cable trays which do not maintain minimum physical separation. This minimum physical separation is specified in IEEE-384, and in SP-834 - Electrical Construction Guideline for Electrical Circuit UCR 2020-025 Physical Separation. In summary, the minimum separation distances are based on open ventilated cable trays and are as follows:

1. Cable spreading area - one foot horizontally and three feet vertically.
2. General plant area - three feet horizontally and five feet vertically.

Where the above separation is not provided the following specified criteria extracted from IEEE-384 are used:

1. The use of physical barriers or enclosed raceways, which qualify as barriers, shall be separated by a minimum distance of one inch.
2. Vertical barriers, separating redundant horizontal tray running parallel requiring horizontal separation will have a minimum of one foot (or to ceiling) extension above the top of the tray at the highest elevation in a stack.
3. Horizontal barriers, separating redundant horizontal trays crossing requiring vertical separation will have a minimum of three feet extension beyond each side of the widest tray (one foot in the cable spreading area).
4. Horizontal barriers, separating redundant horizontal trays running parallel requiring RN 98-061 vertical separation will have a minimum of six inches extension beyond each side of the widest tray.

8B-1 Reformatted Per October 2020

These barriers are intended to prevent redundant raceway-to raceway fires which are self-initiated only.

Based on the above, the following was extrapolated:

1. Solid tray covers and bottoms, referred to in this report as fire shields, may be added to open ladder tray to quality it as an enclosed raceway. Trays containing power cables (480 volt and higher) may require barriers in lieu of fire shields since fire shields may inhibit ventilation.
2. Channel tray (4 inch open top, solid bottom) will be considered an enclosed, open top tray and may require covers only.
3. Instrument trays, in this plant are installed with solid covers and bottoms and constitute an enclosed raceway.
4. Conduit alone constitutes an enclosed raceway.
5. Conduit installed beneath or alongside of an open tray of a redundant division does not require a barrier.
6. Conduit installed less than five feet ( three feet in a cable spreading area) above a tray of a redundant division requires a barrier.
7. Conduits may be wrapped with a flexible fireproof material which will suffice as a barrier. This may be used where space permits installation.

8B.3 MATERIALS AND INSTALLATION 8B.3.1 FIRE SHIELDS Tray covers and bottoms will be made of 18 gauge steel. They will be attached to the tray by one of several methods described in detail by the tray vendor for other applications in the plant. Basically, the covers are strapped or clamped to the tray.

Covers will be peaked to 1 inch, except for covers for fittings which will be flat; bottoms will be flat.

8B.3.2 BARRIERS Board barriers will be made from Babcock and Wilcox M-Board in one inch thickness.

Installation techniques are under development.

8B-2 Reformatted Per October 2020

8B.3.3 CONDUIT WRAPPING Conduit wrapping will be done with Johns-Manville Cerablanket, or Babcock and Wilcox Kaowool blanket materials. These are high-temperature fiber blankets in a thickness of one inch and, typically, a width of 24 inches. The blanket will be wrapped around the conduit and fastened with fire resistant tape or by other similar method.

8B.4 ACTUAL CASES Detailed in Figures 8B-1 through 8B-12 are representatives cases found in the Virgil C.

Summer Nuclear Station where physical separation of redundant channels could not be maintained. The type of fire barrier designed for each case and the installation methods are described below. Options are provided for each case and an option may be selected, for individual cases, based on economics, available space and complexity (e.g., it may be more advantageous to use one board barrier rather than many covers and bottoms where several trays are involved).

1. Detail 1 - Redundant Horizontal Trays Crossing, Requiring Vertical separation
a. Option A - shows the use of fire shields on each tray.
b. Option B - shows the use of a horizontal board barrier.
2. Detail 2 - Redundant Horizontal Trays Running Parallel Requiring Vertical Separation
a. Option A - shows the use of fire shields on each tray.
b. Option B - shows the use of a horizontal board barrier
3. Detail 3 - Redundant Horizontal Trays Running Parallel Requiring Horizontal Separation
a. Option A - shows the use of fire shields on each tray.
b. Option B - shows the use of a vertical board barrier.
4. Detail 4 - Horizontal Tray Crossing Redundant Vertical Tray Requiring Horizontal Separation
a. Option A - shows the use of a fire shield on each tray.
b. Option B - shows the use of a vertical board barrier.

8B-3 Reformatted Per October 2020

5. Detail 5 - Horizontal Conduit Crossing Over Redundant Horizontal Tray Requiring Vertical Separation
a. Option A - shows the use of a fire shield on each tray.
b. Option B - shows the wrapping of conduit.
c. Option C - shows the use of a horizontal board barrier
6. Detail 6 - Horizontal Conduit Above Redundant Horizontal Tray Running Parallel Requiring Vertical Separation.
a. Option A - shows the use of a fire shield on each tray.
b. Option B - shows wrapping of the conduit
c. Option C - shows the use of a horizontal board barrier.
7. Detail 7 - Vertical Conduit Crossing Redundant Horizontal Tray Requiring Horizontal Separation
a. Option A - shows the use of a fire shield on each tray.
b. Option B - shows wrapping of the conduit.
c. Option C - shows the use of a vertical board barrier.
8. Detail 8 - Horizontal Conduit Crossing redundant Vertical Tray Requiring Horizontal Separation
a. Option A - shows the use of a fire shield on each tray
b. Option B - shows wrapping of the conduit.
c. Option C shows the use of a vertical board barrier.

8B-4 Reformatted Per October 2020

SOUTH CAROLINA ELECTRIC& GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION UNIT #1 DETAILS TAKEN FROM GAi DRAWING ELECTRICAL FIRE BARRIER DETAILS E-201-240 FI£. c


REDUNDANT CLASS 1E CABLE TRAY CLASS 1E CABLE TRAY---...

BOARD BARRIER

'---------"----< 31 -0" MINIMUM (TYPICAL) GENERAL PLANT AREA 11 -0" MINIMUM (TYPICAL) CABLE SPREADING AREA OPT ION "B" BOARD BARRIER 3*-0" MINIMUM (TYPICAL) GENERAL PLANT AREA 11 -0" MINIMUM (TYPICAL) CABLE SPREADING AREA REDUNDANT CLASS lE CABLE TRAY-----~

CLASS 1E CABLE TRAY FIRE SHIELD COHSISTIHG OF #18 GA PEAKED COVER AHO FLAT BOTTOM--~

FIRE SHIELDS DETAIL 11 111 REDUNDANT HORIZONTAL TRAYS CROSSING REQUIRING VERTICAL SEPARATION AMENDMENT 0 AUGUST 1984 Figure 88-1

SOUTH CAROLINA ELECTRIC& GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION UNIT #1 DETAILS TAKEN FROM GAi DRAWING ELECTRICAL FIRE BARRIER DETAILS E-201-240 F I )( IE ,8 A £ ,.e I .e /) 7 A I l s CLASS lE CABLE TRAY 6"

MINIMUM MINIMUM OPTION "B" BOARD BARRIER CLASS 1E CABLE TRAY FIRE SHIELD CONSISTING OF #18 GA PEAKED COVER AND FLAT BOTTOM (TYPICAL)

OPTION "A" FIRE SHIELDS DETAIL 11 211 REDUNDANT HORIZONTAL TRAYS RUNNING PARALLEL REQUIRING VERTICAL SEPARATION AMENDMENT 0 AUGUST 1984 Figure 88-2

SOUTH CAROL I NA ELECTRIC & GAS COMP ANY VIRGIL C. SUMMER NUCLEAR STATION UNIT #1 DETAILS TAKEN FROM GAi DRAWING ELECTRICAL FIRE BARRIER DETAILS E-201-240 1'-0" MINIMUM 1 i-----BOARO BARRI ER TRAY--~~'---

REDUNDANT CLASS IE CABLE

~ _

CLASS lE CABLE TRAY OPTION "B" BOARD BARRIER FIRE SHIELDS CONSISTING OF #18 GA PEAKED COVER ANO FLAT BOTTOM (TYPICAL)

REDUNDANT CLASS lE CLASS IE CABLE TRAY - - - . . c . _ CABLE TRAY OPTION 11 A11 FIRE SHIELDS DETAIL 11 311 REDUNDANT HORIZONTAL TRAYS RUNNING PARALLEL REQUIRING HORIZONTAL SEPARATION AMENDMENT 0 AUGUST 1984 Figure 8B-3

SOUTH CAROLI NA EL EC TR IC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION UNIT #1 DETAILS TAKEN FROM GAi DRAWING ELECTRICAL FIRE BARRIER DETAILS E-201-240 31 -0" MINIMUM GENERAL PLANT AREA

,..------.......--11 1 -0" MINIMUM CABLE SPREADING AREA 51 -0" MI NIMUM CLASS lE GENERAL PLANT AREA CABLE TRAY 31 -0" MINIMUM CABLE SPREADING AREA REDUNDANT CLASS lE CABLE TRAY----

OPTION "B" BOARD BARRIER 1 1 -0" Ml NIMUM CLASS 1E 51 -0" MiNIMUM PLUS TRAY CABLE TRAY DEPTH GENERAL PLANT AREA 31 -0" MINIMUM PLUS TRAY FIRE SHIELD CONSISTING DEPTH CABLE SPREADING AREA OF #lB GA PEAKED COVER AND FLAT BOTTOM -----J 3'-0" MINIMUM GENERAL PLANT AREA 1'-0" MINIMUM CABLE SPREADING AREA

---REDUNDANT CLASS 1E FIRE SHIELD CONSISTING CABLE TRAY OF #lB GA FLAT COVER AND FLAT BOTTOM---' OPTION "A" FIRE SHIELDS DETAIL 11 411 HORIZONTAL TRAY CROSSING REDUNDANT VERTICAL TRAY REQUIRING HORIZONTAL SEPARATION AMENDMENT 0 AUGUST 1984 Figure 88-4

SOUTH CAROL I NA ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION UNIT #1 DETAILS TAKEN FROM GAi DRAWING ELECTRICAL FIRE BARRIER DETAILS E-201-240 CLASS lE (OR ASSOCIATED) CONDUIT HIGH TEMPERATURE FIBER BLANKET REDUNDANT CLASS lE

~

3'-0" MINIMUM GENERAL PLANT AREA 11 -0" MINIMUM CABLE SPREADING AREA OPTION "8" CONDUIT WRAPPING 31 -0" MINIMUM GENERAL PLANT AREA 11 -0" MINIMUM CABLE SPREADING AREA CLASS 1E (GR ASSOCIATED)

CONDUIT  ???

FIRE SHIELD CONSISTING REDUNDANT CLASS lE OF #10 GA PEAKED COVER CABLE TRAY-----' AND FLAT BOTTOM OPTION "A" FIRE SHIELD DETAIL 11 511 HORIZONTAL CONDUIT CROSSING OVER REDUNDANT HORIZONTAL TRAY REQUIRING VERTICAL SEPARATION AMENDMENT 0 AUGUST 1984 Figure 88-5

SOUTH CAROL I NA ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION UN IT #.1 DETAILS TAKEN FROM GAi DRAWING ELECTRICAL FIRE BARRIER DETAILS E-201-240 REDUNDANT CLASS lE CABLE TRAY ----....

CLASS lE (OR ASSOCIATED)

CONDUIT

.....__BOARD BARRI ER

"----------'------<3'-0" MINIMUM (TYPICAL) GENERAL PLANT AREA 11 -0" MINIMUM (TYPICAL) CABLE SPREADING AREA OPTION "C" BOARD BARR IER DETAIL 11 511 HORIZONTAL CONDUIT CROSSING OVER REDUNDANT HORIZONTAL TRAY REQUIRING VERTICAL SEPARATION AMENDMENT 0 AUGUST 1984 Figure SB-6

SOUTH CAROL I NA ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION UNIT #1 DETAILS TAKEN FROM GAi DRAWING ELECTRICAL FIRE BARRIER DETAILS E-201-240 CLASS lE (OR ASSOCIATED) CONDUIT HIGH TEMPERATURE FI BER BLANKET

}

~REDUNDANT*

CABLE TRAY CLASS 1E OPT ION "B" CONDUIT WRAPPING

~CLASS IE (OR ASSOCIATED) CONDUIT OPTION "A" FIRE SHIELD DETAIL 11 6 11 HORIZONTAL CONDUIT ABOVE REDUNDANT HORIZONTAL TRAY RUNNING PARALLEL REQUIRING VERTICAL SEPARATION AMENDMENT 0 AUGUST 1984 Figure 8B-7

SOUTH CAROL I NA ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION UNIT #1 DETAILS TAKEN FROM GAi DRAWING ELECTRICAL FIRE BARRIER DETAILS E-201-240 I El(. DTA I LS a l C L A S S IE (OR ASSOCIATED) CONDUIT MINIMUM~ s s ~BOARD w w I" ' BARRIER 1 1 1 MINIMUM MINIMUM REDUNDANT CLASS lE CABLE TRAY OPTION "C" BOARD BARRIER DETAIL 11 611 HORIZONTAL CONDUIT ABOVE REDUNDANT HORIZONTAL TRAY RUNNING PARALLEL REQUIRING VERTICAL SEPARATION.

AMENDMENT 0 AUGUST 1984 Figure 88-8

SOUTH CAROL I NA ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION UN IT #1 DETAILS TAKEN FROM GAi DRAWING ELECTRICAL FIRE BARRIER DETAILS E-201-240 CLASS IE (OR ASSOCIATED) CONDUIT HIGH TEMPERATURE 51 -D" MINIMUM FIBER BLANKET GENERAL PLANT AREA 31 -0" MINIMUM CABLE SPREADING AREA REDUNDANT CLASS 1E CABLE TRAY 6" MINIMUMr...._

OPTION 8 11 11 CONDUIT WRAPPING 31 -0" MINIMUM GENERAL PLANT AREA 1'-0" MINIMUM CABLE SPREADING AREA II II II REDUNDANT CLASS lE L~~o:::t--CLASS IE (OR ASSOCIATED) CONDUIT CABLE TRAY --~ FIRE SHIELD CONSISTING OF #IS GA PEAKED COVER ANO FLAT BOTTOM OPTION "A" FIRE SHIELD DETAIL 11 711 VERTICAL CONDUIT CROSSING REDUNDANT HORIZONTAL TRAY REQUIRING HORIZONTAL SEPARATION AMENDMENT 0 AUGUST 1984 Figure 88-9

SOUTH CAROL I NA ELECTRIC & GAS COMPANY VIRGIL C. SUMNER NUCLEAR STATION UNIT #1 DETAILS TAKEN FROM GAi DRAWING ELECTRICAL FIRE BARRIER DETAILS E-201-240

,------...-<3'-0" Ml NIMUM GENERAL PLANT AREA 11 -0" Ml NlMUM CABLE SPREAD I NG AREA 51 -0" MINIMUM --BOARD BARRIER GENERAL PLANT AREA 31 -0 11 MINIMUM REDUNDANT CLASS IE CABLE SPREAOING AREA CABLE TRAY OPTION "C" BOARD BARR IER DETAIL 11 711 VERTICAL CONDUIT CROSSING REDUNDANT HORIZONTAL TRAY REQUIRING HORIZONTAL SEPARATION AMENDMENT 0 AUGUST 1984 Figure 8B-10

SOUTH CAROLINA ELECTRIC & GAS COMPANY' VIRGIL C. SUMMER NUCLEAR STATION UNIT #1 DETAILS TAKEN FROM GAi DRAWING ELECTRICAL FIRE BARRIER DETAILS E-201-240

.----------......--<3'-0" MINIMUM GENERAL PLANT AREA 11 -0" MINIMUM CABLE SPREADING AREA CLASS lE (OR ASSOCIATED)

CONDUIT REDUNDANT CLASS lE HIGH TEMPERATURE CABLE TRAY FI BER BLANKET OPTION!'B" CONDUIT WRAPPING

- - - REDUNDANT CLASS 1E CABLE TRAY 1'-0"-r--

MINIMUij__

CLASS lE (OR ASSOCIATED)

CONDUIT-~---'

- - - FIRE SHIELD CONSISTING OF #lB GA FLAT COYER AHO FLAT BOTTOM 5*-0" MINIMUM GENERAL PLANT AREA 31 -0" MINIMUM CABLE SPREADING AREA OPTION "A" FIRE SHIELD DETAIL 11 811 HORIZONTAL. CONDUIT CROSSING REDUNDANT VERTICAL TRAY REQUIRING HORIZONTAL SEPARATION AMENDMENT 0 AUGUST 1984 Figure 88-11,

SOUTH CAROL I NA ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION UN IT #1 DETAILS TAKEN FROM GAi DRAWING ELECTRICAL FIRE BARRIER DETAILS E-201-240 D~ TAI t..S


.....-----< 31 -0" MINIMUM GENERAL PLANT AREA 11 -0" MINIMUM CABLE SPREADING AREA CLASS lE (OR ASSOCIATED)

CONDUIT 51 -0" MINIMUM GENERAL PLANT AREA 31 -0" MINIMUM CABLE SPREADING AREA REDUNDANT CLASS 1E CABLE TRAY OPTION "C" BOARD BARRIER DETAIL 11 811 HORIZONTAL CONDUIT CROSSING REDUNDANT VERTICAL TRAY REQUIRING HORIZONTAL SEPARATION AMENDMENT 0 AUGUST 1984 Figure 88-12

APPENDIX 8C

SUMMARY

OF ANALYSIS OF SEPARATION BETWEEN TRAY FOR NON-CLASS 1E CIRCUITS AND TRAY FOR CLASS 1E CIRCUITS 8C.1 OBJECTIVE Perform an analysis in accordance with IEEE 384-1974, Section 5.1.1.2, to ensure acceptable separation between trays for non-class 1E circuits and trays for Class 1E circuits.

8C.2 CRITERIA Separation shall be sufficient that no single electrically initiated fire can result in the loss 00-01 of a safety system function.

8C.3 BASIS The Fire Protection Research Program tests performed at Sandia Laboratories for the U.S. Nuclear Regulatory Commission (NRC) were used as a source of data on the characteristics of cable fires. The following conclusions drawn from the reports were used in the analysis of individual situations:

1. It is difficult to initiate a fire from an electrical fault or overload in trays with cables which satisfy the flame retardant criteria of IEEE 384-1974.
2. If a fire can be started and propagated, it spreads through a stack of trays with an angle of spread of approximately 35 degrees from vertical.
3. In horizontal trays, the fire does not propagate horizontally within a given tray.
4. Fire does not propagate downward from one tray to the tray below.

The results of the IEEE 383 flammability tests for cable actually used at Virgil C.

Summer Nuclear Station were also used to determine that the flammability of the cable used at Virgil C. Summer Nuclear Station is less than that used for the full scale tests at 00-01 Sandia Laboratories.

8C-1 Reformatted Per Amendment 00-01

8C.4 METHOD The tray drawings for plant areas containing trays for Class 1E circuits are reviewed and each case where a tray for non-Class 1E circuits approaches a tray for Class 1E circuits is noted and given an identification number. Each case is then clarified with sections and details as necessary to determine separation distances and to categorize the situation. The cases are then individually reviewed using the basis given above to determine the adequacy of the separation. If the criteria stated above are not satisfied by the existing design, suitable barriers are added to the raceway system design so that the final design satisfies the criteria.

1. Tray for non-Class 1E circuits parallel to tray for Class 1E circuits. Subcategories include: above, below, beside, and between. 02-01
2. Tray for non-Class 1E circuits crossing tray for Class 1E circuits. Subcategories include: above, below, and between.
3. Tray for non-Class 1E circuits bridging between routes of trays for redundant Class 1E circuits. Subcategories include: above, below, and between.
4. Trays for non-Class 1E circuits diagonally parallel trays for Class 1E circuits.

Subcategories include: above and below.

5. Trays for non-Class 1E circuits vertical. Subcategories include: parallel to or crossing tray for class 1E circuits.

8C.5 ANALYSIS A listing of cases analyzed is provided by Section 8C.6. In addition, detailed analyses for three typical cases are presented in Sections 8C.5.1 through 8C.5.3.

8C.5.1 CASE NO. 041-C 8C.5.1.1 Description

1. Location Control Building, Elevation 425-0
2. Figure Figure 8C-1 8C-2 Reformatted Per Amendment 00-01
3. Type of Area Cable spreading room
4. General Description A tray for non-Class 1E (channel X) control circuits passes over a vertical stack of trays for Class 1E, channel A circuits and further north passes over a vertical stack of trays for Class 1E, channel B circuits.
5. Category Bridging - above
6. Types of Trays All trays shown in Figure 8C-1 are open ventilated ladder type, except tray 5144 (A) which is the totally metal enclosed type.
7. Number of Circuits Tray 4290 (x) - 316 control circuits Tray 4351 (x) - 103 control circuits Tray 4650 (x) - 38 control circuits Tray 4314 (A) - 337 control circuits Tray 4284 (A) - 182 control circuits Tray 5144 (A) - 124 instrument circuits Tray 4326 (B) - 435 control circuits Tray 4325 (B) - 209 control circuits
8. Significant Circuits Both the channel A and B trays contain a number of circuits for the component cooling water, emergency feedwater, safety injection, and service water systems; as well as circuits for other safety systems.

8C-3 Reformatted Per Amendment 00-01

8C.5.1.2 Analysis All circuits are for control or instrumentation and have very low internal energy levels.

Therefore, energy is not available to initiate a fire.

Any fire which might start in the trays for non-class 1E circuits will not propagate to either of the stacks of trays for the Class 1E circuits since tests have demonstrated that cable fires do not propagate downward. In addition, the tests have shown that a cable fire will not propagate horizontally over the 5 foot-8 inch distance between the stacks of trays for the Class 1E circuits.

A fire which might start in the trays for the Class 1E circuits could propagate to trays for the non-Class 1E circuits but, as stated above, tests have shown that the fire would not 00-01 propagate horizontally to the trays for the redundant Class 1E circuits nor would the fire propagate downward to the other stack.

Although the preceding analysis documents that a fire barrier is not required, a barrier was installed in the Channel B control trays in compliance with the licensing 00-01 commitment to provide barriers for multiple separation violations as describe in paragraph 8.3.1.4.1, Item 4.

8C.5.2 CASE NO. 102-A 8C.5.2.1 Description

1. Location Reactor Building Elevation, 436'-0"
2. Figure Figure 8C-2
3. Type of Area General plant area
4. General Description Trays for Class 1E circuits, channels A and D, run parallel to trays for non-Class 1E (channel X) circuits throughout this elevation of the Reactor Building. No trays of other channels are present.

8C-4 Reformatted Per Amendment 00-01

5. Category Parallel - beside
6. Types of Trays The trays, as shown by Figure 8C-2, consist of both open ventilated ladder trays and totally metal enclosed trays.
7. Number of Circuits Tray 3098 (X) - 13 480 volt random layed power circuits Tray 4168 (X) - 33 control circuits Tray 5063 (X) - 22 instrument circuits Tray 4174 (A) - 62 control circuits Tray 5069 (A) - 3 instrument circuits Tray 5077 (D) - 3 instrument circuits
8. Significant Circuits Tray 4174 contains a number of circuits from the chemical and volume control system, reactor coolant system, and safety injection system; as well as from other systems.

8C.5.2.2 Analysis The Class 1E, channel D circuits are in a totally metal enclosed raceway at the bottom of the stack. Therefore they are adequately separated from other trays.

The lower of the two trays for Class 1E channel A circuits is totally metal enclosed and therefore, is adequately separated. Any fires which might start in the upper of the two trays for Class 1E channel A circuits would not propagate to the tray for the channel D 00-01 circuits nor to the trays for non-Class 1E circuits.

The bottom tray for non-Class 1E circuits is totally metal enclosed and therefore, is adequately separated from other trays.

8C-5 Reformatted Per Amendment 00-01

The middle tray for non-Class 1E circuits contains control circuits which do not have adequate energy to initiate a fire. Should a fire occur, it could propagate to the top tray for the Class 1E, channel A circuits and to the top tray for non-Class 1E circuits.

However, this is acceptable because only one channel of Class 1E circuits would be affected and, therefore, system safety functions would be maintained.

The top tray for non-Class 1E circuits contains power circuits which potentially could initiate a fire. However, the tests have shown that such a fire is very unlikely and should such a fire occur, it would not propagate to any other trays in this configuration.

Although the preceding analysis documents that a fire barrier is not required, a barrier was installed in the Channel D control trays in compliance with the licensing 00-01 commitment to provide barriers for multiple separation violations as describe in paragraph 8.3.1.4.1, Item 4.

8C.5.3 CASE NO. 073-A 8C.5.3.1 Description

1. Location Auxiliary Building Elevation, 388'-0" 02-01
2. Figure Figure 8C-3 3 Type of Area General plant area
4. General Description Trays for Class 1E circuits, channels A and B, run parallel to trays for non-Class 1E circuits, channel X. This situation exists for a distance of 20 feet. 02-01
5. Category Parallel - above and beside
6. Types of Trays Both trays for Class 1E circuits contain control circuits. Trays for non-Class 1E circuits include instrument, control, and random layed power circuits.

8C-6 Reformatted Per Amendment 00-01

7. Number of Circuits Tray 4062 (A) - 28 control circuits Tray 4064 (B) - 27 control circuits Tray 5022 (X) - 38 instrument circuits Tray 4059 (X) - 106 control circuits Tray 3033 (X) - 49 random layed power circuits
8. Significant Circuits Both trays 4062 and 4064 contain circuits for the chemical and volume control system and the leak detection system, as well other systems.

8C.5.3.2 Analysis Tray 4064 for Class 1E, channel B circuits is separated by considerably more than 5 feet vertically and 3 feet horizontally from all other trays and, therefore, is adequately separated.

Tray 4062 for Class 1E, channel A circuits is 14 inches away from tray 5022 for non-Class 1E, channel X circuits. However, tray 5022 is totally metal enclosed and, therefore, is not a hazard to tray 4062. Tray 4062 is more than 5 feet horizontally and 3 feet vertically from all other trays and therefore, is adequately separated.

8C.6 CASES ANALYZED The following pages list the cases analyzed.

8C-7 Reformatted Per Amendment 00-01

I Il I I I I I I I I I I I I I I I I I I I I I I I I I I I l tLECTR IC a GAS COMPANY -

ID 1auu 1H t;Anv._ INA  :;r-~1~*

D*.awtMG MO. aM . .u. * ... v t 1i t H IJ *

!'~ _'-!:_ 01tl1t1t61!ss-200-91\t lo*u-t NOit~:

VIRGIL C. SUdER llllClEAR SUflOH

?.#2_ __

UNIT II 8 = BRIDGING I rttn J llCITI U( Un J llCllS tf CHU TUY ....... *u*111; !;Olli l-114-UI.

i: _ -I

... ~*r

  • Ctl.8£9'T ASSOCIATI*.. IMC.

C = CROSSING 1. JOI IUlllllH If CllCUIT CM&Hfl IUIHllllH. SU nu Tiil( l.J-4.

ElECTRICAl ~HGtNf';_'!'.!~!'o~=~UL1AM11

= DIAGONAL 0 J * - JIU£ HIRIOS *Ut lttlUD!I II lllCllll JUT snn* IUIU.

TRAY SEPARATION ANALYSIS tC*L* I ..... ~*, r~~/ ,.., 1 / .~'.*oft....-

P Y

= PAllAlUt

= YlRJICAL

  • Ot*81CHU $P[CUl Mt!U - sn fHHI s*-1 CONfROl BUllOING ABOVE 1125' -0"
  • 0 044411-121 r-.-,.o.wc:

v ..

C. I,.., I l"""f"'*

- ou.T. - or,.* -

I f" I LH I

L I . ,J -,,

""n HUMBER fNOTE l l ORAllNG COOROINAllS CATEGORY Sl1UA110N (NOTl 2) VUTICAL HORIZONTAL SH lEGlNO (t(lt£RS RtPRESlNJ CHANMH Of CIRCUllS IN CAIU TRATS) OIS1ANC£

.rt;;,i,rto OISIANCE !NOTE 3)

RfMIR!IS 041-* . E -11 I' * *t0n I ~*-1* - ns*

z 041-11 G-11 , l ABD'fE A :z*-1* - Y(S*

fl.fl-£ f-6 I' t 8 BHOll l 12" - NO tj) (G:i 0 041-D H-1 c 0 ABOVE l 12" NO *z*

c D ABOVE A 2'-1" - ns*

ac:

zt:

C> C> C>

-a. .._ 041--E E-5 p B ABOVE E 12* - KO E lOTAll Y tNCl 05£0 CX>

()

>- ac:

U;:::>

~

0 c

B BHOI ( I '-1" 12* NO ns*

B IOIALLT ENCLOSED 14-

.,. z:

  • I 8 BltOI E I '-II" -

CX>

z- ~

Do

<..>IQ ~ 041-f 0-3 p 8 &HOW X 12" - NO ~

041-G H-8 ,. 0 NUJ 10 l - 6" NO (I' p o uon l 12* - NO '<21 c

~-- ~-

041 H H 12 8 BELOW l 12 * - HO I)

C> 041 ~ I E-8 p ( BtlOW x 12* NO (j) 041-K C-3 p B ABOvt l 12" - HO ,2,' l3J (£0. 0 041-t £-3 p I ABOYE E 1*-z* - NO l tOTAllT ENCLOSED 041-M H-6 I'. y 0 NEU TO l - &" KO (1_* 0 lOTAltY ENCLOSED 041-N E-10 c I BUOW l 4'-2" - NO CD 041-P £-9 c I ABOVl 8 2*-1* - ns*

)> )>

c s:::

G) m CZ 0

-; s:::

Cf)

...... m c.o z

~ -;

c.o

--.J I

0

I I I I I I I I I I I I I I I I I I I I _LJ__J_l_LJ_l_l_l_J

  • i\Oillil ( IPOI IHI fl [(!RIC A GAS COHPAHY ---; ~ <**o D*AWI ... IMI.

~0~ :~~-!. c);p11J61!ss-200 9lll jo1J1 2 I IM. NO. f ***

,p_

lEGlHD llOlts* - il~~l~_£_!~11!1 HiJClllR S!lllOH UNIT If B =BRIDGING I Jtall J llClll UI LISI J llClll 81 Cllll 1111 1111111 IUllll 111111 I lll 111 **Loo ~~1~ GILHU AHOCIATIS, IHC.

C = CROSSING - - - - .f ~~~ __ _ _ _ fHOHU~~*.!~~o~~~~ULUMU El!ClRICAl

l. IDI OlllllllOI Ir CtatVll COU!l llllUlllOWI Ill 1111 11111 I I I -~-----~-~ - - * - - - -

0 =DIAGONAL l * - IMISI UUIUS IUI llClUDU II ea"IUI JUI 111111 111111 IPA! -~~~~~~ll{)_H AHAL!SIS

~HI ~::.it, ,,.., f'.c, .,, I I ?i'! ("

~H81 ~f0 -~:~*lf.t;,.ii . . - - 01..r. - oi"1 -

P =PARAll H V = YlRllCAL

' QtlOIClllS SPIClll MOHS Sii !Hiii SI I - - - - - -COH lROL BUILOlllG


~-

ABOVE 1125' -0" lll H l A.Pf' DA rl' "-f'!°fWti'lal

c. *~u I - I - l'llE"l'l'i;.tfU- r-ArP I I *

~ASl ORUING CAHGORY SllUAflON (NOH 2) VERTICAL HORIZONTAL HUWBER t(*tuWEi REMARKS It HOH I l CO ORD INA IE S SH LEGEND (lElURS REPRESEHI CHANNEL or CIRCUITS IN CABLE lRAYSJ DISIAHC£ 0 I STANCE <HOIE ll 041-0 G-9 p l ABOVE I 12" - NO @

c l ABOVE A 2 '-1" - NO Q* l IOJAllY £NCLOS(O cC t!I c I ABOVE A 12* - NO IV I IOI All Y ENCLOSED z

UJ

-041-R- 011 p v BNEHIOX

- 8' NO {J). (!)

- p ,:i_

00-S 0-1 £ mo* x 2 1 -1* - NO UI 041-l C-5 p A NE IT 10 K - 6" HO (l'

g UJ 0:

ii§ 0

-a. u.

..... 0: 041-U £-4 p A ABOVE X 8" - HO <1' iG. ffi u ::>

~I UI ~

ti J;. J z~

0 t!I UJ Cl UJ 041-V C-S p B ABOVE X 12* - NO ((J)) D Uo m

0:

041-1 G-5 c B HEll 10 A - 21 -8" YES*

' I 04H C~4 0 8 BHOI A I *-1 * . I NO l1J i

0

(:. ( ..

~

I I I I I -I l E GE H0 I I I HO I! S I I I I I I I I I I I I I I I I I I I I

  • SOUTlt CAROLINA ELECTRIC & GAS COMPANY e""',~:;"""

_Djl _-<y_

DAAWINQ MO.

011 j*11161!ss-200 94 I 0112 I I H HO ...

Ic VIRGIL C. SUMMER NUCLEAR STATION UHll II

  • we 1" 'CllHRT ASSOCIATES IMC IQ l.0111:

I flm J ftl&llS II! LISI 3 01511$ Of till! JUI Dill!MI MUllU; SUl!S !-Ill-Ill 8 = BR IOGIHG C = CROSSING I. FOi OlflMlllOM Of CUCUll CHIUH O!SICMlllONS. !IE fSll lllll l.J-1.

ELECTRICAL 5'!.-'!..'l_ ~ ~ fMCIH(flllS AHO CON~Ul TAHU.

ICAt.f

- - - - ftfAOIHO, l'A

! TRAY SEPARATION ANALYSIS I)?/' ;:+>Lt;;..- O~J I 0 =DIAGONAL J - IH!S! llUl!IS l!R! IMtlUO!O IM ORl,CINll JRll SISHM O!SICM o/.ir/71 CONTROL BUILDING

  • 0 04H6HJ10 r -fi4Q1Ncfft-. ,,JioVii: - Oi",.f - -oA.,£ -

l Q IHOICIHS SP!Clll NOl!S

.a ..

P = PARAll!l  !(( SHH! SN I

-._'!ti_;JCH_,~u~*w;;'1*.T~t!!~l ~~11wrr:~

Y = YlRllCll ABOVE 1136' O" c - - 10 ti 0 #.

CASE *ORlllNG CA IE GORY SITUATION (HOT£ 1) YER! !CAL llORIZONTAl B*nn It" NUMBER REOUIREO REMAR~S (HOH I) COOROIHAHS SH LE GEHO (tfTTERS REPRESENT CHANNEL OF CIRCUITS IN CABLE TRAYS) DISTANCE DISTANCE (HOH Jl OH*A C *14 p B ABOVE X 10"

- NO CD X IOTALLY ENClOS£0

(.

.-...-~

v <V. ©

"'z c..

---~

041 *B 0 *I I p 8 Hf XI TO I - 6" HO w

c5 041-C p A NE 11 ID X - 6" HO ©.QJ (_

041-0 ____

.____ £ -4 p A ABOVE X 8" HO l_f. (_

"'~~ 042- E c5 p A ABOVE x 8" HO ct c

.~ f ..... -

v 6 ..

co u

042-f H-6 p 0 NEXT TO X - HO ()) k:..

~

CJ I I t;; -

I

"'z f---

c - (])

01 I-' I z UJ 041- G 0-4 A ABOVE I I '*-8" NO k:_

oo UJ Uo ' I

--~--- ----------

0

I I I I 11 I I I I I I I I I I I I IJ I I I I I I I I I SOUTll CAROllNA ELECTRIC& GAS COMPANY l"' ttO. orv IC 010** 010 l+O. tH, LE GI HD HO TES*

<o- !! - .!_ o*lj*11161!ss-200 9111 !0113 1 VIRGIL C SUUER NUCLEAR SIAllOH UHll #I IQ LOA **a'", '"' 'GllllRT UIOCIUU, IHC.

U; C;

URIOGIHG CROSSING I flRSI J OICllS lRI LISI l Dims Of Clfl( fall DilJINC IUllll. 111111 1-111-111 ELECTRICAL i?_t~E'- __ -J- _ ~ fMGIHfflllAHOCOHIUll'ANU

' I 10! 0(11111101 Of tllCUll CHllN!l D£SICNl11CI!. Sii 1111 Tiil[ I J-1 fl(A01140, fl'A.

o*m-Mt ............. d?.;l- "'*' -r::J~i TRAY SEPARATION ANALYSIS Id'<' j(~. _1r.~

rrtJ , IBt~,~;;~~~t~!!!tQt1 0 ; OIAGOHAL J * - !Hflf llUlllS llR[ INCLUD£0 II OAIGllll Till !!!HI O(llCN ~-~~ '(Al* (J-IJ / ~.JI/>>-

0 0

P; PARAtl ll I INDl(llfl SP([lll MDI£! Ill Iliff f SH I COllTROL BU I LO I UG

  • OATl -

Y; YlRllCAL ABOVE 11118' O" H u L

, CASE OR Al ING CATEGORY SITUATION (HOH 7) VERTICAL HOR I IOHTAl oMnlER HUMBER RE OU IRED REMAR~S

(NOT[ I) COOROINms SH UGEHO (lEITERS REPRESEHI CHAHHEL Of CIRCUITS IN CABLE TRAYS) DISIAHCE OISUHCE (HOIE 3)

OU

- *A 1

0 .I] c A ABOVE B 8" - YES'

<:J 00-B f-4 c A HOT 10 0

  • 6" NO G>' (J) --

L z

UJ

-- - - - - * - c c

-043-C

- - f - ! II p A ABOVE x I '-3" - HO <V c * - (_

<D

~--*

[ .8 p A ABOVE X I '-*J" HO 043-0 043-[ [ 14 p B ABOVE X 12" - HO  !(D X IOTALLY EHCLOSEO

"' (.:

UJ a:

~:g Cl p BNfXTTOX - 1 '-0" NO (I) (2) (_

-o. -

.... 0::

U::> Cl p 8 HEX! TO A - 4 '-0" HO 4) c.

iii! IL ... © -

UJ VI p A NEXT TO l - I' 6" NO ~,. If I- <:J VI Z w z- -'

c CIC UJ uo a: 043-f G4 p A ABOVE 0 4' *5" - tlo 0 TOI All Y £HCLOSEO

<D 043 *G G5 c A ABOVE X 12" - NO (1 ".:.

P. 0 A ABOVE 0 4 '-5" J *. o** HO :i '-i (_

c A BELOW X 9" - NO (j' J) (.

.......... 00-H H5 c A ABOVE 0 4 '-5" NO .© c.

Cl 043-J C- 5 p A BELOW X II" - NO <l . Qi c.

p A HE ll TO X - 6" NO  !) ' (2) (_

043-K 0-11 p. y BHEXTTOX - 6" HO Q). CV ~


-----~.

l: . :.<'>

_Jjr-Jc h~ l __L Jflo~E i--Ll I I I I I I I I I I.LU LJ __LJ JLJ i

  • <r;1r1-l.i""Ti1iTrilT1n1( & GA', COHPhfll

-:__f=!.-

  • 'r;  :, "--...---P*"t"'"o *o. .!'*"°cI I"'c"
      • t-'01111
  • I -.

01111111fi1:ss-?OO 'Jiii YIPf.tl [ \\UIR Wl'!flR lll!IOM UHi! fl 8 = BRIDGING ---- --

I I IRS! J DIGlll UI LISI J DIGllS Of Ciel[ IRI! OllllMG IUl!ll. !flll! f -*""'".-~!i GILBERT ASSOCIATES IHC.

':' _w_,c:' - *. .

IQ LO*

' " Ill  ! l [I. Iµ Ir Al

'"" -- -r=- , . '.- .,

'HG<Hff., AHO (OHIUll.*HH C = CROSSING 7 !DI OHINlllON or CIRCUIT CHUN!l Q[SICNlllOMS. Sii FSIR lllll I H - -- --- - ---- - - -- l'lfl<Olt.iG, ....

.. J . IHl!I 81RRIUS llll INCLUOIO IN DllGllll !ill srnu DESIGN lRAI-. SfPARAllOH AtlAUSIS 0 = OIAGOHAl -- -*- -?'1,*~

- I 04H61*-070 -,HGt;fe,r.. P,.fi.Ofil-* (if,.y - or, -

  • ------------~~--

COtllflOL BIJllOltlG

  • 0 P = PARAllfl

' ( :* IHOILlllS SPU:lll HOllS Sf I SKF! I SH I --------* . -- 0 V = VERllCH ABOVE ~GJ' -0" ~~~-~r~!f~~JW1~*

flLH ~ "f,.f,1 8 '-t ~1~r*'~

CASE *DRAWING CAHGORY SITUATION (HOH 2) YER! IC Al HORI ZOHTAl oonrOttt HUMBER REQUIRED REMARKS

,(NOIE ll COOHOINHlS SH lEGEHO (l£11ERS REPRESENI CHANNEL Of CIRCUITS IN CABLE TRAY SJ OISIANCE DISIAHCE (NOTE 3) 044-*A u4 c A ABOYI 0 12" HO (i). (7) 0 IO!AllY ENClOSCO c.

p A BElQI 0 7 '-3" NO @.(i c a:

lll z ----*---

044 -B I 4 p A BElOI 0 2 '-3" HO '3).(i) c.

UJ

p. y A NEXT TO 0 - 12 .. HO (_},. (2) c..

...!!!:..L. G-5 c A ABOVE x 1 '-6 ..

HO l(J) L p A BllOW X 12" NO 'I) ~* A IOI All Y ENCLOSEO r_

li f~~ ... 044 0 (. I0 c 8 HEX! IO X (I YIRllCAlo 6" HO CD -

u ~ fi: p B ABOVE x 12" - NO rn '-

> p (!)

a: 0- "' 8 BH 01 X 1 '-1" HO ~..

co t; zW lll ...

(") z .....

I oo w f-'

Uo

- "" ' I N I I

w 0

_j_ j~filHl- 1 .I 1 1lo~rl *1 I I I I I I I I I I LLJ I I I I I I "'I SOIJTll r.hROl IHA fl EC TR IC & GAS COMPAHY ~

'!'! ~~*- r11i(1;;11i!fs;--;o~ ();;;!

' O*U<HG M-0 -1 IH "° J C

  • tV VIRGii C SUOER HUClEAR STAllOH UHi! NI

~7r.J-I GILBERT ASIOCIA TEI. IHC.

B = BRIOGING I flRSI J DICllS IR( LISI l D"11S Of CIBl! !Ill OAlllNC Mll~Bll. SllllS I 114 Ill 10 to*

C "CROSSING 1 fDR O!flNlllOM 01 CIACUll CHUM!l D!SIGNlllONS. SH flll lllll 8 l-4 -

EllClHICAI ~!......-.- -- .J (f.fC.l!HflHJ.~OCOHSULTUOS l'lfAOO.i<,. "A

~~_:r,>_'/*---., ,:::.: , '<JI J/:*J/7y

THAY SEPARAllOH ANALYSIS 0 = OIAGOHAl J IHl!f BURl!IS l!Al IMCLUDlO IM ORIGIMll IRll Slll!W O!SICM - -*--------------------------
  • 0 OH461 -070 iMGiffrfi' APPfio~ ...t - o;,., -Di°"li -

P = PARAllfl I.

- INlll 11111 \PHI II NO 11 \ Ill IHI 11 .IN *------- COii TROL BIJ IL 0 1llG ---~

fyt~~~f*q[f~1iJ;J"B'~!Q!f ~J~q~r-~

Y = YlRllCAl AOOV( 110?' O" L~5t ORAllllG CAHGORI SITUATIOH (HOH 1) YER! ICAl HOR I ION!Al BlRRllR HUMBER REOUIREO RI MARKS l<HOll I> COORO I HAif S SH llGEH O (lElHRS RlPRESEHf CllAHHH Of CIRCUllS IH CABLE TRAYS) 0 !STANCE 0 IS I AHCE (HOH 3) 045-A f 8 c A BEL OW l 5 '-0" - HD CD c

"' 045-e c. 14 c 8 BflOI l

- NO CD (_

Cl --

z: -----*----*-

w l '-*"


* -----~------------- --~----

~--- ---- *--- -----------


~--------

Ill

~~

... f ...

'~

u gfil

~

... Cl tnz w

.._Ill k-z: - ..J w

8g 1

...w...

0

--- -~---- ----. -*-------* - --- --- ----------- **------


~--*-~---~~ -------

(**.* (: '.'*

. J

c

---1-----*----+------+-----------------------r---- -*----- -----1,.,,---------*------

a: 041 f. I P C A BEL 01 I 17" NO ~

~~-*-**------~-----+*----------------------- *----~--------- '--

uJ 041 *c _____O_**-----l-----Jf-B_B_l_l_OJ_1_________________-J_ _11_*_*-t-------t--N"-'Oc____li'==<---------------------------------------- (_


~*-- -- --------*------------ ------------

"'UJ l5 :g ~

- ... u.

... a:


~*-- - - - - - - - - - - - - - - - - ----------------

g~ ~1----*-------t----1------------- ---------~------<------+-------------------------*-------

... l!I "'

-Ct------1------'t------f----------------,-------------1-----t------~-----lf------------------- -----------

~u ca:

c ~ ~t-------f------1-------t---------------

CJ UJ ---------1------t--------t---'r-------f*---------------------*~------

a> t------1------t------t-------------------------1----

1----.---------t-----~---------------*--------+----+-----1----+-------------------------------

,....,...r~---.,_

w __-+---------t------1-----------------------+----+--------t-----+-------------------

!;;;1------>--------lf-----1------------------*--------1-----r-----1f-----t-----------------------*-

o

.._~.__,----+------~--------f----------------------+-------t-----+--------t-----------------------------

1-----l--------Jf-----1------------*------------t-----~-*---t-----+-------------------------------

  • ------------------ - - - - - - - - - - - * -----ti-----t------------------*---**----- - - - - - - - - - - - -

!------ ------------------------ --- *---------------~

- - - ---- -~----- ~*-*----------


~------t-----*-- +-----+------ - ----------- ...

  • -------- - ---- ~----I-*----------- --------*----!------- -~--- 1------t----------------- ---*- -**- *----------------~

U LI I l [Tl II [ [ ( [] I I I L((J J 11 *

[I I I I _LL so11111 CAROllHA ELECTnlC&GAS COMPAHY'~~~~;l=~;: 0-;,;;,-,-,~~Js!~~*;~ 0 -~~~-1~~ii~,f~"-

- L t t iiti- --- ifilid- - ---- - - - - -- VIRGIL C SUMMER NUCLEAR SIAllON UHi! NI '-j w~=..,..,..,..,*=*~

I llR!l J OICllS m LISI l DICllS or CIBI! IRIT ORlllNC NUNBfR; SIRl[S 1-114-111 0

B = BRIOGIHI; ELECTRICAL 0

'V' 0

,'"- !"1~--'tGILBERT 1-;,- --

4.:.

fJ (

USOCIATH;ltlC.

llGIH(f IU A!lO (01Hlll l.t.Hll C - CROSSll'G fOR OlflNlllON Of CIR'Ult CK'NNll OISIGNlllONS. ;([ fS'R llBl[. )-4 -----*---* .. - - . . *** 0 ** 0 * *

'!~!.;;~~'!1**o<i~- 'i!~ ,_ :'~f.7-

- ' ' * * ' lRAY SEPARATIOll ANALYSIS i'fm---

0 OIA!iONAl 1

  • IHISI BIRR II RS llR! INClUOIO u ORIGINH IRIT SllllN O[SICN -- ----co1liii'Ol'Biill0i11'G _______ -- - ~-"o!H~l~_lii

~:::\ ~~~ ......~'.,.o=...,,. .u,__.-*'_11_'_sP_'_ll_'_l_N_u_"_'_....s'_'_sH_1_1_' _s,_*----------,,....,.=,...,... . . ---.--~* ----A00v**-; 13~-------- ~~i~f'"I ~HfKJ~fT~_~,. f'-q1~~ 0 LAH OllAiitiG-* r.AJIGORY SllUATIOtl (HOH 2) VERTICAL llORllOH!Al fE~Wi'Jto RCMAR~S HUMBER

! NO 11 1 l f.!JORll INA l_f_S -+S_l_f_l_l_G_IH_Dt--!_l_ll_T_r_RS_R_lr_R_E_Sl_H_T_C_ll_AH_H_E_l_O_f_t_IR_c_u_11_s_u1_CA_B_l_E_1_R_AY_S_)t-0_1_sl_A_u_cr_T_1_i1_s_1A_N__

cl ..._(:...N.;:.O.;.;H;.._;.3'"-)4---------------- -------*--

O~B A c J * -p-v* - A HIX! IO l ------ J' O" NO CV -----*------ c

---!,----+------------------ -------------

a:

z: ------- *- *------ ------------------*--------- ----- -----<-------f-------------------------*- -------~-----

-t-----1---------------------------- -----

UJ


<>----** ------*--------------~-

z "'

~ a: t-----+--------+----1------------ -----------*>-----+-----+------+-----------------*-.---------

0 C> 0

- a:

t-a.. u.1------+-------~-----+-----------------------+-----;------+-----t-----------------------------~

00 gi( filt----t-------1-----~---------------------**--t------1-----+-----t-----------------------------*-1.~

CJ I

a: "'

t-"' *t-----+-----*-o------------------~--------- . . -----t-------+-----1------------------------------__. ~

f--1 "' z: UJ

~ - ;:!,___--------- ----+-----------------------~----! - - - - - + I - + - - - - - - - - - - - - --------------1 ug - - - - - - - - _______ ,__ _, ____ -*----*-----.----------------------- - - - - - -

lJ1 a:

- - - , _ _ _ . - - - - - - - - l f - - - - - - - - - - - - - - - - - - - - - - - + - - - - - - - - - - - --------------------------------------*-

w

>- 1-----1--------

0

~ ~

C") [.J

~---*>---*-------------------------- -------

c::: z **----+-----J------------------------*----------

(/) t:;I H

~

f--1

'° H z ----

~------


-*----+------------------------

'° '°I ----- _________________________,.___

-._J

-._J

--- -----*-- --lf------t--------*----- ----------------- -----------

0 f--1

( .. (**'.'i

F .. **:.*.:'::

1:

"~': ...

~

I; *:**

lil_l_l_LLLLLrI.LLI I I 11 I I I I I I I I I I I I I I I SOUTll CAROL lflA ELECTRIC & GAS COMPANY .. "'!""""

~)!.*~ ~'.'..s_

""'"'"o *o

();,1;,;;fiJss -?oo

-~+**v

')l;;- 011 1i 1 11 c l' --

L*tc HO HOI S

  • VIRGIL C SUMMER NUCLEAR STA!IOH UHi! #I *---'--t-~,!-,,,..,.,.../-..-----J----'--'

e = BRIOGIHG FIRS! l OIGlfl II! ll!I J DIGllS OF CUL! !UY ORlllNG NUMB!R. srrns 1-lll Ill ELECTRICAL IO lO*

~-~_;:_I~ -

~**!*. *~!:J GILURT ASSOCIATES IHC fNGIHf[RlAHO(OHWlf .... HlS C =CROSSING fOR OfllNlllON Of tlRtUll tKINMll OISIGNlflOMS. S£I fSIR lift(( 8 JI -----'==.:..:c..:...=c=-------1 ***o**o.**

- ;:'O:'l'l-~-l-0~{),:.~,.-,:,~*. 11.~~-.-,.,.; y_1,.'.-, p~ i.,'.1, _

0 = OIAGOHAl p = PARAllll 1 ' fH[![ URRlfRS rm INClUOIO IN ORIGINll lRll SYSllN OISICM I Q1wo1w11 SPltlll MOHS Sil SHI[! SH I lRAY SEPARATION ANALYSIS COIHROL BUILOltlG -,iE~.J!.f ___ T~ ;i 'f~~ 0 ' 0 1--'llT~V~=;..;V~E~R~ll~C~A~l,.,.;-;,,--,,-;:~""""""'-r----------------------.-,-,,.--L-,------,ArB~OTV~(;..,.,'l~l~IB,*__;o~*-*---------~~=*v~l~4*;~*:_!t!J_~_:Lj_"_'l!.:"t~~,~V~AOil_f!!rS~f~f~

H~~~~R DRAWIHG CAIEGORY SllUAllOH rnoJ£ 2> vm1w 110R1ZON!Al N~J,'No Al MARKS 1HOH ll COORIJIHAl[S Sll lEGlHO (lE!IERS REPRES£HT CllAHHll Of CIRCUITS IH CADLE TRAYS) OISlAHI:! OISTAHCl {NOIE 3J c

P"~'--'-<-t----~--;1--~--'--t---~~----~-------------t-----t------jf-"~.::;_"'---f-..,.---~----~-----------------*~

049 A __ _!1 __1_3_____ B HEX! 10 K *----- _ _l..'._:..4..__ HO (1


- - - - - * - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - + - - - - + - = - - - - - - - - - - - - - - - - - * - - - - - -

~ ~ _ _1_!_3__._______ e H(XI 10 K _,_.'_6_"_, __H_o__ ,,_\..'.;o'I_*______________ c UJ O-+-+-.... - - - - ------------ *-----* - - - * - - - - - - - * * - - - - - - - - - ----1-----J------------*----- -----~----- ---**---

-- ~------ * - - - - - - - - - - - - - - - - - - - - - - - - - - - ' - - - - - - ! - - - - - -....- - - - + - - - - - - - - - - - - - - -- **--~-------------*--* - - - -

  • -*- -- - - - - - - - - - - - - - f - - - - - - - - - - - - - - - - - - - - - - - - - - - *------- ----- - - - - - - - - --*--------------*-----------

,_____ - - - - - - - - - - t - - - - - - - - - - - - - - - - - - - - - - - - - + - - - -

  • 1 - - - - - - I - - - - - + - - - - - - - - - - - - - * - - - * - - - - - - - - - - - -

z~ "' a:t----i-------t-----~----------------------;c-----t------l------t----------------*--------*-*--*--

o o o

g; lLl-----l-------1----+------------*----------+------1-----l*----1-----------------------------

u~~= ::> ot----1-------1-----1------------------------l----- ------+-----t------------------------------J

~

~ <:I.! *t-----t------*t-----1-------------'-------------l-----+-------+-.,-----I---------------------------

~

0 Cl w

<->o""

1-----+------*----+------------------------~------

l - - - - - t - - - - - - - t - - - - + - - - - - - - - - - - - - * - - - - - - - - - - + - - - - + - - - - - - - - - t - - - - - - - - - - - - - - - --------

t-t-~...-1-----i~-----+-----+---------------------l-----l-----l----l------------------*----*~

~

Cl

!-----+-------------------------------

  • ----+------------ ------ - - - - - - - - - - - - - - - - - - - - - - - - - + - - - -------f----*1---------------------**--- -*----------

+------+-----------------------:1--------- -----1------;f---------------


~-----*---11-----,------------------------1----- - - - - '-----+--------------- --------------

I 1Lahl--LLJ11MJ- I I I I I I I I I I I I I I I I I I I .I sourn CAROllHA ELECTRIC& GAS COMPANY !~ H*U

'.:~! *_~'.__ t>i1-r11~5;r55 O>AW<NO NO.

200 9111

~~

u;->1-1 c IH HO -r *fll l __

VIRGIL C. SUMMER HUCLEAR S!AllOH UHi! NI B = BRIOGIHr. I flRSI J DIGllS m llSl J DIGllS Df CUll IRll DRUING MUNIER; SUl!S 1-114-111 ,_:.!'; ~*~~"--1 CILIERT AISOCIA TES, IHC.

10 lD*_,

  • . 1 IOR Dlf IMll ION Df CIRCUll CHIMM!l DlSIGMlllOMS. m rm fllll e H ELECTRICAL SI:'.'..~- __ rnc1Hfllli'-HocoH1utTAHfS

.,,""&VLT~

C = CROSSING "r.a.Ot'40, ""'

__ TRAY SEPARATION ANALYSIS_

0 = 01 IGOHAL IHIS£ 8UilllS *£RI INClU0£0 IN ORIGINll IRll lllHN OfSICN

'°'~----~f~f.('J-<i'.

I*~r~ **

l

- irl*.;;,.(oii :t - Qf,.y - :y.-,/;y

'0 - - - - Bil OH~6 O:/O

-~-~H..~F1-g

-oArl.

0

- - - - -CONTROL I LO I NG

  • p = PARll Lll INOlflllS SPHlll HOil! S1£ SHH I SH I -- -------- 0 V = VlRllCll ABOVE IPIB'-0" r,;- - ,_,,,,. c5 I
  • I*
  • I ; '.f',

~A~t ORAllNG CA IE GORY . SITUATION (llO IE 2) .V£Rl IC Al HOR I ZOHTll BAHHltH NUMBER REOU IRED REMARKS 1NOH II COORO IHA ff S SE£ lEGlNO (lE!HRS REPRES£Hl CHAHHEl Of CIRClllTS IH CABLE TRAYS) DISTAHd OISIAHC£ (HOH 3) 051 *A l-12 p

- -p- -

l HEX I JO x --

12"


- - HO --- 0 c

(.\; (i c

~---- -----~----


~

A NEXT 10 B 4' O"

-~--*-- ---*----~-

HO I

..:}i - - - - - - - _ _P_ _ 8 HE XI 10 l I' O" HO (i) -* --*-- *-------*---- --------

c.

UJ

- **-- ------- - - - - -- *------------*----~------

' ! f~~ .._ -- *-----

... a:

U::::> Cl ii!"- "'

UJ

~

... tD U>z UJ I z- -'

c o UJ Uc:>

a:

UJ Cl

\ . '*:***

-~--.*

/ *'

(

IIIIIIIIIIIIIIIII I I I I

!011 SOUTH CAROLINA ELECTRIC & GAS COMPANY *-.: ~ ';J.'""

I lu c!1l~-U-~JJ _I OAAWIMO MO. I IH. iiO: OIV

~{)!-A~ otq111161!ss-?.oo 9111 116-

-r-VIRGIL C. SUMMER HUCLUR SJAllOH 'UNIJ II 8 = BRIDGING  : I fllll l llCllS U! USI J llCllS Of CAIL! IUI DRllllC NUllU; S!Al!S f-m-m _10 lo* r '" --~ CILIUT ASSOCIATES, lllC.

C = CROSSING 7. IOI CHlllllOI or tlltUll tHAllH llSICllllONS. Sil IUI llllf l.l-*.

ELECTRICAL !t!P.._ - - fHGIH(~~~~~o~~~~ULIANU

¥t-I * .

0 =DIAGONAL J * - mu llUIUS In! llClUDU II IRICllll Ull SISlll emu TRAY SEPARATION ANALYSIS 1c*lt A~ '1i;** o/.i~t

. . . o*'*

,) ~ "

0 CNJ I P = PAR All H l INOIClllS SP!Cllt NOllS SH SHiii SN I AUX I LI ARY BUILDING

  • o llH\1 ~lO Ift~ll"~f~ or*t - -OAT[ -

ABOVE 374' -0" lniITTrFl-~

~ - - 'l11C' 'Yii10 0 (.- ~F1~-~F7

!!!Y ...

.. J V " VERllCAL CA St DRAWING CAI£ GORY SIJUAflOH (NO!E 2) VERJICAL HOR I ZONfAl B~Kff lfR NUNS ER REMARKS l[G(N 0 (l(IHRS REPRESEHf CHANNEL or CIRCUllS IN CABLE TRAYS) DI STANCE DISIANCE (HOfE REQUIRE,~

IHOIE ll COOROINAl!S S£( 3 011-A

~

p A ABOVE X J *-s *

- - HO 6

..: 011 8

~------

r s p 8 BELOW X 1' .fl. NO (i' Q; _(j}

UI z ~~--- ---- ----------------

011-t (-9

--- p 8 HEX! 10 X 6" NO (I) (<D)

~--* ------


f------- -

r -11 HO 071-D p 0 HUI 10 X - 6" (l) (~)

c li :g a:

011-[ G-12 B ABOVE X 4 '-5" - HO (2)

-11.

CJ u.. --

~f e i.

t; z~

UI ....~

..J

' I Bg UJ *-'--

a:

......w CJ t

L '*rnhl~JJ I I I I I I I I I I I I l I I l l l I l sou Tll CAROLINA ELECTRIC& GAS COMPANY ,.~u~f"""

I It E Jll~_L O*U.WINO HO. IH. MO Ill!~

~§ '.'.'~- o~f4il6ifss-?OO 9 I013 1jc B.' '"""" . '""'""' . . .

VIRGIL C. SUMMER NUCLEAR STATION UHi T #I B = BRIOGIHG FIRS! l Ol&llS IRI LISI 3 Ol&llS Of ClBll IRll DRlllNG NUMB!R; SElllS l-11Hll so Lo* ~ ~***~"""'j GILaERT ASSOCIATES IHC.

"' w"'

I HE CTR I CAL C = CROSSING l FOR OEFINlllDN Of CIRCUIT CHIMN[l O!Sl&NlllONS. SE! FSIR IUll 8.l-4. - - - - - -- -* - - - JIU AOIMG. ""-*

TRAY SEPARATION ANALYSIS c

0 = OIAGOHAI l IH!SI URRllRS *IRI IMClUDID IM DRl&IOl !Rll STSH* Ofll&N i(ilf--'-- --- 14'1{>- *14; / ~;.; ?"1

.:~r~1--i~rf~Ft:rfut;;1~~1~

-~-

\ AUXILIARY BUI LO ING P = PARAllEl 4 IHOICll!S SPIClll HOil! S[f SH{f I SH I V = VERTICAL ABOVE 388' -0" c - a- lt*IJ, i3 "

1 J)

CASE HUMBER ORAWING CA TC GORY SITUATION (HOH 1)

SEE LE GENO (LET HRS RlPRESENI CHAHHH Of CIRCUITS IH CABLE TRAYS)

VERTICAL DISTANCE HORIZOH!Al R'to"u'\

OISTAHCE (NOTE 3) i1i REMARKS t HOH I) COORO ltlA ll S

~-

Oil* A H- 9 p A HEX! 10 x -

11"

___ ....J ____ HO (}' '21 ---~----

c Pi


~------- - -

"':z:

UJ

- - - - - - ----- ----------~--~--- -- --*--*-- *--

_. ____ --- -- -- ---- ----*- -----------------------~-

UJ

z:.,, a:

I oo u. C>

- IL

.... a:

I

~ .,,

U::> Cl UJ

~IL If-

z: w z-oo

...J w

Uo a:

...- ' I i

UJ Cl q

~

0 ~ ----

U) ~*

H -----

I-' ~ ----- -----

'°'° '° H

'-I

'-I I

0 I-'

(:.:.<: ,._

t<*

/* .. '

I. *; .. '

I I I I I I sourn CARllrlllA £LE CTR IC & GAS COMPANY .* *.... "° .....

10"°

6M. MO.

I I I I I I I I I I l I I I I I I I I I I I I ,---~ ~

~~ ~~-!. 011j111151!ss-200 9111l0711 1 ltGtffll NllHS:

  • VIRGIL C. SUMllEA NUCLEAR SUJION UNlf 11 B = BRIDGING I 11111 ! llCllS II[ LISI J tlCllS If CHU IUI IUll*G *UHU; suns l-11f-lll ~ ** ,.~~ CILllUT AUOCl.1.TU, IHC.

El"'

IQ...

ELECTRICAL {'::!.f: __ fHClt.f((lllS J.~0 CONlUL UNYI C "'CROSSING  : 7. IOI Dlfl*1110* Of cmu11 CMl ..ll IUICllllOO. m JSll !Alli 11.!-4. llllf aou110, ""*

J * - tH[lf UUlllS wrn l*ClUDll II DllCIMll 1111 STSlll HSIU TRAY SEPARATION ANALYSIS ~.-_/../. .'*O, '#"u/7, 0 = 0 I AGOHAL ICHI P = PARllLH I 0 IMDIClllS SP!tlll MOil! Sil SH £11 SM I AUXILIARY BUILDING

.:;;!~F!;f~~~~f ::r:~*:1*~

Y = VERllCAl AOOVE 397' -0" C Vil * - ~ U;v 0 fJ~ _

CASE DRAWING CAI£ GORY SIJUAJIDH (HOH 2) VERTICAL HOR I ZOHJAl B~HH ICR NUMBER RE OU IRED RUARKS c HOil I l COORO IHA IE S SH lEGEH 0 (LEllCRS REPRESENT CltAHNEl Of CIRCUITS IN CABLE fRAYS) DISJANCE OISUHCE tNOIE J>

014-A 0-9 p ANElflDI - 1 1 -2. NO* © -

co: CD 014-B I* 17 0 8 UOY( l

    • -2* 12' HO (<0) t:I
z: ~----

~-

~:fl

..."' oc:

0

-a. u..

... oc:

U:::> c ------- ~

~a.

co 88 ...

... t:I

"' z '

(")

N I z-

~ I 0 -

m " *-- *--

~

0 I

I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 15UUlll CAROLINA ELECTRICS GAS COHPANY OJU1WINO MO.

e;~J~M" 0*1l*11161lss-200 I IH. WO, 9111 jo751 ID NOl[S:. - j;'I --~

LE CE NO VIRGIL C. SUMMER NUCLEAR SUflON UNIT II I fllll 3 llCllS U( LISI J 111111 If um IHI UlllU IUllU; sum (-1"-111 10 LD" 8 = BRIDGING ELECTRICAL <'IVP IP~-l~~, GILIEltT USOCIUU, IHC.

f HCINHJU AHO COHSUl U.Mfl

"(AOIMO, ,A.

C = CROSSING  !. ro* 11r1i1m* er ClltWll UUIH IUICMAllOU, SU rsu lllU 1.3-*. - - - - ~

TRAY SEP AR AT ION ANALYSIS l * - IHI!( umus Ill! UClUDll II HISIUL IHI SUl(I oms~.

ICALI 0 = DIAGONAL I~'-:.~-. /c,.1"/ ~,I ~,;,,

AUXILIARY BUILDING 0 UH&**11l0 r*-i"ttOiM*i*ai"'rii~"":' - OlrT- OA;J' -

P = PARALLEL '011om11s SP[tlll NOllS $(( SHHI SN* 1 l:V WAD* Ui V = VERTICAL ABOVE 1112' -0" -1

c. l'f-ll I ~-,rn,~:.,,:ioyt~!tS"t=r "f~

~AU ORUIHG CAHGORY SITUATION (NOif 2) VERJICAl HORI ZONTA HUMBER L :lluWEi REMARKS 11 HOil I l COORDINAHS SH lCGCHO !LHHRS REPRlSEHT CHAHHlL Of CIRCUllS IH CABLE JRAYS) OISIAHCE DISUHCE fHOlf l) 016-A f-9 r ANClllOk - 2 '-4. HO Q) 0 A BHOI X 9* I '-IO' HO (!)

a::

UI z

w 016-8 0 6 p A HEii 10 I


- 2*.9* NO CD CfD) 0 076-C 1-9 p A HCl I TO I - 3. -9" HO 'I) p A BHOI l 12" - HO (I)

.,, 016-0 G-9 p A HEif TO X - 2'-4" NO (I) l I

!~ ~

-CL ...

""' ID p A BELOI X 12* - HO (i) oo I iCL ~

L> ::J

-  !+

016-( J.-4 r B*HEH TO I I '-6" HO (f) t; tll w

~I I I

z~ _.

88 II>

I.LI a: 076-f G-5 p B BELOI l 9* - HO I-oC C>

I i

I

I* (. .. '. ~ .*. *. *.

1.'.*

I I 'JJJ

~L..ll G Ho_L I l -JH-0jhIJ.. II I II I II I I I II I rII r rI

_l._.l_,_J.__J_____JL-JL.....;L-L-L-L--L-L-L_L.-,_.._.._..._..__..__-'--'-.L--1 SOUlll CAROlfNA El£CTR I c & GAS COMPANY 1~u*;~' '""" o;;-r,lt1161iss-200

_oc:J ~~

o*u*** *o 9111 tH "°11 ...

077 E.

VIRGIL C SUMMER NUCLEAR STATION UNIT 11 I '-

8 = BRIDGING " I FIRS! J DICllS IR[ LISI l Dl&IJS Of tl8l£ !All DRlllNG NUUU; SERl!S f-l!C-111 C = CROSSING I fOR DfflNlllON Of CIRCUll CHINMH OESIGNlllONS. SH HIR !Ill£ l.H.

0 =DIAGONAL l ' - lHllf BIRRHRS l!RI INtlUO!D IN ORIGINll !UY S!SHM O[SIGM.

P = PARAltEt '0 IHOICllfl IPIClll HOl(S SH SH((I IH I Y = VERTICAL CASE OHWING CAHGORY SITUATION (HOH 2) VERTICAL llORIZOH!Al BARRIER NUMB CR REOU I REO REMARKS IHO!( ll COOROINAlfS Sf[ LEG£HO (l£!1ERS REPRESENT ClllNHll Of CIRCUITS IN CABLE TRAYS) DISTANCE OISTAHC£ (HO!E 3) 011-A H*9 - 6" HO ()) c


*--~----~-------------------->-----*------+-----+--=---------------*---------*-

.....,l-ll-1---*- - * - - - - - - - - - - - - - - - - - - - - - - - - - - - - * - - - - --- ------*-----+~----------------- ------------

__!l_I! ~- --2__!___ -----+--..;;,;,..,-----------------+..--'12:_"_+--------if---H-'0:___-1--""1~)-------------*-------------- C.....

Ul Oll-f B* 6 IX

~~ u. 0

-~

I- IX 011-f R5 OJ U::> Cl

>~

(') IX .

c

... r----r------t----t---------------------t------+--1'_*_9_"--li--11'---N0_--1~*~1*-'-----------------~~-*-~-ll.

I I- UI V>z Ul N z- ..J 011-G f-5 N

...- fl) X GOES TltROiiGll I RE STOP IN WAI l c:IQ a: 5" i HO ' (

f UQ 011-H 11-5 011-l 11-2 I 1" I *.. 2" YES*

Ul c

CJ 017-K G*2 2 '-6" g; ~

0 c::: z tI:I '

(/)

1-3 t:I trj f-'

\0 1-3 z

\0

'-..J \0

'-..J I

0 f-'

I I I I I I I I I I I I I I I I I I I I I I I I I I I I

  • I SOUTH CAf!ULIHA H.£CTRIC& GAS COMPANY

'"'o;y;;* DINA91N0 NO, I ht. NO.

I 01e D i't../f: _ ,- 1

_'§ _}_ 011 j111161!ss-200 9111 1J rrn No NOTES:. VIRGIL c. mm HUCLUR STATION UHIT II

1. mu l mm 111 LISI l urns er mu mr mmc *u*m: mm 1-m-111 IQ LOtt B = BRIDGING ~ GILIUT AUOCIATll, INC.

ELECTRICAL fHGIHf(IH AHO COHSUlUHft C " CROSS ING  !. ro* llfl*lllDM er CllCVll tMlUll t!SIGMlllDMS, Ill flll 1111.[ l.l-4. - - - - IUAO!ti!O, PA.

D " DIAGONAL l * - IHISI UUIUS 1£11 IMCLVIU ,. OllCIUL Ulf sum llS ICI.

lRAY SEPARATION ~NALYSIS IC.Cl i~Jc /<,  !"-<'. .:y ,_u l I  ;;/,£'!,

" I Q llDltlllS SPltlll MOHS - Sil SHl!I SN I c:rt.u 1-~, *~l ~it:1Wl~fs.f!J"'l1 AUXILIARY BUILDING 0 04U61-1!10 -************"" - - oiH - -o.. r -

P = PARAllH

  • Y = VERTICAL ABOVE 1136' -0" I *.

cm DRAWING CATEGORY SllUAllON (NOi! 2) VERT ICAl HOR I ZOHIAl ltif~i'Ji\ REMARKS HUMB£R INO!( I 1 COORO IHA IE S SH UGEHO(UTTERS REPRESENT CHAHHEl Of CIRCUllS IN CAEL( TRAYS) DISUHCE OISIAHCE (NOi£ 3) 018-A H-9 p A BELOI l I '-2 * - HO (i)

..: 018-8 J 5 p A ABOVE l * *-2* NO (.)

...z lO 079-C H-6 c A ABOVE 8 5'-2" - NO (i';

cp 8 ABOVE l 3 '-0' - NO 151 (~) D 078-0 J-6 c A ABOVE I s*-2* - HO !4';

&ti cp A BELOI I 3 '-0" - HO IJ (~) 0 UI

!~ C>

-a.

~* iQ. ffl t~ 078-E G-6 C.P A ABOVE 8 8 '-2. NO  ! 4)

&ti I+

t; UI c z~ ~ 078-f J-6 p A ABOVE I 8 '-2. - HO 4')

eg ~

Ii Cl>

Oll-6 H-6 p A ABOVE 8 8 '-2. -

NO

  • ~ '

078-H f-3 p A BHOI I 12* - NO u*;

078-J G-5 p A BHOI l 12. - ND i I)

UI I-c 0 018-K G-1 c A BELOI l 6" - HO **1:

p A BHOI I 8'-3" - NO iJ

(*....

.. *.:::. (

\::.

I I I I I I I I I I I I I I I I I I I LLUJ_LJJJJJ

  • 1.1'111l11 I 11i~1I !Qi 11 r f.I RI c & GAS COHPAHY ';~ ;r 0
            • "°*

_ rJ -"'~3- 011j111161lss-200.9111 jo79 .1

      • "°* .!!!.'!.

ID 0

l l u l H!J NOTES:*

-r _

llRG!l c sv111* NUU!lA SllllOH UHi! II I. fllSI J llCllS au Ult J llCllS" Clllf Tiii OlllllC IUllll.111111 I-Ill Ill **c ,., * ., 1 CILIUT ASSOCtUU, IHC.

10 to*

8 = SRl~GIHG '

C =CROSSING

1. fOI DHlllllU Of CllCUll t"lU!l llSICUllOIS, lll flll !IHI I l-1 Ell cl R, C~l  !:'!'!.;:>_ __ ~ **°'**~~*.~~ ~~:IUl D = DIAGONll J. * - IMISI IURlllS Ill( IMtlUDlt ll OllClllL nn STSlll llSICl

_ _ _l_RA¥ SEPARATION ANALYSIS ~'.A* ,1_,u* 0 ,.,, r)~y AUKILIARY BUILDING ~!H -1110 -<*O.**!i'*?,----c.r.r- ;;,r-P = PARAllH I *,..)llOl(lllS lr!CIAL IOllS - Ill 1"111 SM I w~ I - r__!~r~r~*:pr,1~!!1~r~

0 V = VERllCAL ABO\!£ 1136' -0 __:. **** - .P *7/.1,, D f CASE ORAllHG CAHCORY SllUAllOH <HOH 2) VERT lCAl HOAIZOHTAL BARRllK HUIBER RE OU IRED REMARKS

.!NOTE I l CDOROINAHS SH UGEHD (lEIHRS REPRESEHI CHAHHEL Of CIRCUllS IH CABLE TRAYS) 0 ISUHC[ DlSUHCE IHOIE l) 019-A G-12 c B HEXT TO X (8 VERllCALJ - J'-9" HO ,.,-.. '1)

..c ,..,

UI 019-8 ( -12 c 8 NEXI TO J (8 VERllCAl J - J '-9" HO .I'. \.4)

z:

UJ 019-C D-9 p A BHOI l

  • l '*l 0" - HO rt) p AHllJIOl - 6" NO (Jl 019-0 8-9 p A BE LOI J l '-2" - NO (I)

.,,w

- CD a:

!~ u. C> 019-E G-9 p A BHOI X 11" HO

-o..

I

... a:

ffi p A HEU 10 X .. 8" HO (J) <w) D i~ Cit

!~ ti UI !.j-c z! 019-1 r-6 c A ABOVE l ' lo* - i NO  !~)

ca w t.> C>

019* G 0-6 p A NEii 10 X - 2'-0" NO 'J) 019-H 0-6 c A ABOVE l 2'-1" - NO (5) (6) DI w

019-J C-6 D A ABOVE l 5" 6" HO m (ti>) 0 I' c

a

~*~

c:: it-::t Cf)

'z '

H~

rx:l

,z  !

I-'

'° 'H l..O I

i

'--! l..O I

0 I

I-'

I I.

I

I I I I I I LEGEND I II HOHS:

  • I IIl I I I I I I I I I I I I I I l l SOUTH CAROLINA ELECTRIC& GAS COMPANY VIRGIL C. SUMIER NUCLEAR STAllOH UHIT 11

~D~~ ~~~ Oilfi1lj:;,;~*:2~~ .9111 ;;~~; I i D B = BRIDGING I. rust l llCllS UC USI l llCllS tr tllll IUI UlllWG MUll!I; 1!1111 f-!11-111 ~a to* r~f~ CILUlll AHOCIUU, IMC.

ELECTRICAL ~ !:;-/_/~ _ _ _ _ __ _ ff.IG!Hf~~S.!~o~:~~Ul TAHU C =CROSSING  ?. fOI DlflMlllOM Of CUCUll t"&Ufl emmttm, I(( rsu IOU l.H.

l .** IM!SI auuus lfll UCl~tl* tr ORl61Ul un 111111 lfSIU. TRAY SEPARATION ANALYSIS -I/? /* _.. (/. ""' ~ I Y,/'1;"7,.

0 =DIAGONAL *. ICHI P = PARALLEL 4 0 IMDICll!S SPltlll MDII! Sil !Kilt SM* I. AUXILIARY BUILDING

  • 0 14146Hl10 t -*********~**=-~ oiH - -.r,r -

V WAn . . ~~1 _!!!!; Aft11t1nu.,.5f .. H L l't.ul -

  • t~l'Y11Ji,t 0 rr: I I
  • ~L V = YlRTICAL ABOVE 1.163' -011 t I UH DRAWING CATEGORY SITUAJIOH (HOH 7) vm 1cAt HORIZONTAL lto"tl'11ifcffo REMARKS HUMBER

<HO!( 11 COORDIHAHS SH lEGEHD (UlflRS RlPRESEHl CHANNEL Of CIRCUITS IN CAIU i~AYS) OISIANCE DISIAHCC (HO!£ 3) 080-*l 1-12 p B BE LOI I 12* - HO (i')

p 8 ABOYE l ** - NO m a:

l.O p B HEX! ID l - J '-J" HO (i\ffi z

UJ 080-B r -12 p 8 ABOVE I - HO (ti) p 8 BELOI I 12 * - NO fl J UJ 080-C E-10 p B ABOVE I B BElOI l r

12*

NO HD

(~

ru 0:

li~ C> 0 2*-1* 4'-8" NO (I). (i')

  • ~ .m.,,

-o.. u..

B HUI TO l

...0

... a:

U::>

ii! 0.. 080-0 0-6 p B ABOVE l - HO (5:. -

t; l.O z~ ~ p 8 BELOI l 12* NO fl' (IO)

I Bg UJ a: f I 080-E K-8 p D HEU JO l - a* I HO {Jl (G>) 0 UJ Cl 1.?.,'.::

t. ...

\,.*

' .. ( . *.. ..

.. *. (

11 l E G1µ I I I I I I I I I I I I I I I I I I I I I I I I ISOUlH CAROLINA ELECTRIC II GAS COMPANY *-**;~ '"'""

Co "-<1 -::-r::: D** .. WO NO.

-~ -~ 01q111161!ss-200-9111 l 001 1lP IH. ""* I AfV (N NOHs:

  • 8 = BRIDGING C = CROSS ING '

I. 11111 3 oum uc u11 J 11c11S If cuu un num 1u1m; suns 1-111-111 VIRGIL C. SUHEA NUCLEAR STAllOH ELECTRICAL UHIT 11

?.!:!_~- _

  • 10 Lo_*

-J _

L!!!~J 1".~"'-j CILHRT AUOCIUES, IHC.

(HCIMf(ltiA.He>COHSULTANll

.c -**.* -.*,* .

l. IOI 1111111101 Gf ClltUlf tMlUll DISIGUllOIS, lfl flll llll! 1.3-4.

/.:c "lAOUfO. f'A, D =DIAGONAL J' *- IMlll llUlll! IUI lltlUDll II GllCIUl Ill! S!Sll* DUIGI.

lRAY SEPARAllOH ANALYSIS ~-r.1-~ /f "-

  • 1 ,., ) I '.!./..';IJ' t/:Jf P = PARAllfl
  • Q1101u11s SPICIU KOiis. m SHiii 11-1 AUXILIARY BUILDING **cuu~-~M~~W,J!J~**""- H -

V = VERllCAL ABOVE 1163' O" M.Afl!_I~

l"Ld .

Ql  !.!:! A!

it"' '(tJ 0 r,:

!'f\:l"fW~Ql~tlfl!:~

CASE DRAWING CATEGORY SllUAllOH (llOH 2) YER! ICAL HOR I ZOHIAL Ul!l!JER HUIBIR REQUIRED REMARKS I HOH II COORDINATES SH lEGEHD(LEJIERS REPRESEHI CHAHHEl Of CIRCUllS IH CABtl TRAYS) DI STANCE OISIAHCE ( HOIE 3) 061-A H-1 J p 0 HEH TO X "

.. J" HO (i).(2) 0 lOflLL Y E~l'.i OSEO _ ----*-*

p 11. (3

. ---- '-------- 0 ABOVE A

--- - HO a:

~--- ----

p A NU 1 10 X -

3* 110

- (t)' G11L (G,) -*---*- --- -- - * * * - - - - - - - --

0 IU

_I!~-'-~!._ _ _G~--

p p

B. ABOVE X BNIXllOI 8"

- HO HO I5 I)

,.__ ~-** p 8 BHOI X I '-I" - HO I m

VI 081-C f -14 p B ABOVE X I" - NO.

LU a:: - -~

(i) i!i~

- 0.

I- a:

0 p B BHOI I 12.

- " HO Cl ..

~£ ... -

LU I) t; VI 081-0 0-12 p B BHOI l 12" NO UI LU z:!: -' p B ABOVE X II' - I HO (5 BS -

LU a: p I), (1}_0 IOTALLY EHCLOSEO 0 BHOI l 12" HO


~

p 12. HO (!)

081-E E-12 B BHOI X -

P~ B ABOVE X - HO (5) 12" - NO I) 11' 0 lOIAllY EHCLOS!O p 0 BElOI l LU I- 081-f B-12 £ B BElDI l ]" - NO (! I <D *-

c Cl B ABOVE X IO" - HO (51 (f . (2) 0 IOIAll Y ENCtOSlO 0 BELOI l 12' - NO 081-G 8-12 p 8 BHOf X 12* - HO (I) p 8 ABOVE X IO" - NO (S) 081-H B-10 p 0 BHOI l 12. - HO Q) .

I' 0 HEii 10 X - 6" HO (l) (<D) -* D 081-1 8--8 p 0 H!Xl 10 X - 6" HO ffi (G>) .o

[_J_JrJ-d-"t_ Li I I I I I I I I I I I I I I I I I I l I I I _L SOlllH CAROl.INA ELECTRIC & GAS COMPANY'~":~;;!'" --,-.--!!* .. *MC HO. JM"° RIV IC, NII IE S * - .?~ :.'!.~ 01q111161!ss-200 9111 loa1 2 VIRGIL C. SUMMER NUCLEAR STAii ON UNIT #I f'IQ LOR

= BRIOGING I. fliSI J 016111 IR[ LISI 3 DIGllS or Cl8lE IRll DRlllMG NUM8£R; S!il£S !-rn-m GILBERT AUOCIATES, IHC.

lMG ' " " " '

1 *'

8 _I:!!_-~_ - -- -* - - fMGOH[( .. AHOCOHIULUHTI ELECTRICAL c =CROSSING 1 fOR OHINlllON Of CIRCUll CHIMN!l O£SIGNlllONS, SH fSIR 118l£ ! .3-4 RtAOIHG, ,.,._

0 = OIAGOllAl l fH!Sf BIRRHRS l!lf INClUDfD IN ORIGIHIL IRIY SYSl!W 0£SIGN __ TRAY SEPARATION AN~LYSl_S_____ *<<<< -=-_::i:~,1, Y,/.-/1' 0

'-i"Miiw~~r~l:"'"' - - 0' " -

.7;,'Jo ~y -'!!1!'11.t:J!E P = PARALL! l I Q1NOl[llfS SPlClll HOllS - SH SH[! l SN I AUXILIARY Ill! I LOI NG

  • 04HSHl10 v = VERllCAL -- ABOVE ~63' 0" 'i'W~r~1-~1~ MAO_

CASE ORAllNG CHE CORY VERTICAL llOR I ZOHIAL 1E~J ~E"o 1

R[ MAR~S HUMBFR SITUATION (HOH 2)

DISTAHCE DISTANCE (NOIE 3) 1

<NOH ll

  • COOROINAIES S£( UGlNO (UTTERS REPRESENT CHANllEL Of CI RCU 11 S IH CABLE TRAYS) 081-K

-~---*--

G-9 p v A NEXT TO X -

--- __]~--- - - NO

-© ---------------*---- c

z:

w 081

  • l G-10

"' - - - - - ----------- ~--p-

____ c__ -

A NCXT JO x A BELOW x I '-5" J '-2" NO NO CD (i'*


*- -*-------------- ~-


t v A ABOVE x c


~-

i(5)


~----

081-N 0 B 4 '-0" - NO J

,51

.,, -081-H

- - -----------G-11

- c 8 ABOVE x IO"

- --- NO t

'1),(2) D TOTALLY EtlCL OSED


*~---

0 8 ABOVE 0 1'--1" 3" NO w *-*-- -- (

~:g

-o.. ....""

0


*-------- 0 0 ABOVE A

- - - II"--- 1 '--0" HO BOTH TRAYS IOTALLY INCL OS ED I- IX U:::> 0 ------------------

"'w...

w

~o..

t; Cl ----------------

+

%~

Oo w

_J uo 0::

w 0

-- --- . -------~-----

(:* : :: . \  : . ; ....

I i

( . ....

C..

I I I I Il E GEHO I I I I -1 I I I I I I I I I I I I I I I I I I I

  • SOUTH CAROLTlll ELECTRIC& GAS CCJ!.ll'AHY ~u

~ --::i-----.- OOAW*MOMO.

_ Olljll1161lSS-200 9111 J101 I 0 I IN. MO. I J

    • v NOTES:*

VIRGIL C. SUHER HUCLUA STATION UHIT #I B = BRIDGING I flUI l DIGl!S U( USI 3 llUIS Of Cllll Ill! IUll*~ *uHIR; Slllts l-111-111 ** LOO fr!-~*.l** '"'--~ Gil HR T ASSOCIATES IHC.

1

ELECTRICAL ~i-.J? (

fHGIMff"S .&NO CONIUl T ANTI C = CROSSING l fOl DlflMlllOI Of ClltUll CHlUll O!SICUllOU. Sil Ull !Ill( l.l-1. ---- - - - - - fl(AOINO,PA.

D = OIAGOHAl  !. *

  • IHISI llllllll Ill! tlCLUO!I II CRIGIUl Ul! SUl!I llSIU -- TRAY SEPARATION A~AlYSIS ICAL< [ *;:: - /. "' /' ~

0 REACTOR*BUILOIHG ~441\r~ .~~**lf!tm¥.h ~ .J~. .- P = PARAllH Y = VERll CAL I IMOltllf! !P!Clll MDIII - 11£ !Hiii SH-I ABOVE llf 2' -0" e1TTJ;i-

... Di i;w

-=-QT ,. , m t# *~

"'V .. rFl~Fr~n 11t* ..

GAS( DRU IHG CATI GORY* SITUATION (HOH l) YER II CAL HOA I ZOHIAL IARRttff HUM8£R REQUIRED REMARKS I HOIE ll COORD IHA IE S SH UGEH 0 (UTTERS AEPRfSEHf CHAHHCL Of CIRCUITS '" cmE JRAYS) 0 ISTAHC( OISTAllCE (HOH 3)

I -

I Q)

I 01-A 0-1 p 8 ABOVE E 12* HO -------

I p E Hut TO I e* Ha I _( 2) <a>> I D

- a* 't _(2'

.~-

a: p 8 NEXT TO l HO l 12* ... H1 (2 p -

B ABOVE I

--- p I '--1 * - H3 JI I 01-B

- . K-9 B ABOYE f c 8 BHOI X I '-J* - HO I . 21 p E HEX T TO I - &" HD I (2)

~~ C>

IX p

p 8 llEXT 10 X 1 '-I.

6" NO fl, 2)

'21 I B ABOVE I HC I

u.

- D-

... a:

c.> ::I Cl col

~D-

......_, I 01-C K-10 p B ABOVE E 6" - HO J -

~

... tD

<JI II)

z -
z E HUT 10 I 6" 1 HO I .ffi I'

88 a:

N*

co I II m

t p

B ABOVE l 8 ABOY[ I 6"

I '-1" -

- 110 NO (zi 2

p 8 HUI lO I - e* HO (I; I 01-0 K-17 c 8 ABOVE I &* - HO ii 3 I~


D p 8 ABOVE E I '-1" - NO J ~ ()

c £ BHOI l a* - HO I 31 (D 0 C> p E HUT TO I - s* HD ". l2J ~ D p B ABOVE l I '-1" - HO (z'J p B NUT TO l - 6" !lO (f}

. I I 01-E 11-14 p B A~OVE E I'- l" - HO

,, _l2J (3 -CG>) -- {)

,p EllElllOI 8 ABOVE I I '-1" -

HO HO (2

((p) 0 p B HEX I JO I - 6" HO ,(I * (2}

I LLl 11 LE GE°lfO

  • SUUTH CAROL !HA ELECTRIC & GAS COMPANY ..y

...!""-n ID I I I I I

, - * * ;~ <HWO I IH Wl.

I I I I I I I I I I I I I I I I I I O*AWIMO HO HOHS:* '!>~ ~"!.-! 011j1J1J61!ss-20~-9111 j1oi 2 C.

8 = BRIDGING I fml J DIUIS HI llSI J llCllS OF Cllll 1111 DIAlllC IUlllA: SUl!I .1-714-UI.

VIRGIL SUMMER NUCLEAR SIATIOH. UHll 11 ELECTRICAL '

.** L**-

'f../P _ _ _ CILllERT ASSOCIUU. IHC.

fNe1Nf(IUANOCOHIUlfANJl C = CROSSING 1 IOI DlllWlllOI Of CllCUll CMIOll BISICWlllOMI, SH FSU lllll 1.3-C. JltAOIMQ, P'A.

TRAY SEPARATION ANALYSIS D = DIAGONAL l * - IH!Sf UlllUS IU! llClUD!t II ORIGllll 1111 SlSlll HSIU. f .:.... /r'" f-4 .I~; ,./~J'Z-ICAU Ufl) /

  • . REACTOR BUILOIHG  ;;~iW~t:$-r\l"-d:~tl**foo""- of~i. - D t[

P = PARAllfl 4 IMOltlllS SPltUI MOllS. Ill SHiii Sl*I Y Cl H ~ AIJP' OAf( 1\VIITT~ 1*m *A** 1"'Al Y = YERllCAl ABOVE 1112' -0" L l'f .. I l~l'lfol r:: I I I CAH HUl8£R DRU ING CAI£ GORY SllUAJIOH (HOIE 2) VERTICAL HORI ZOHU L ;tO'u'Wto RUAR~S 11110 IE ll COORD IHA IE S SH lf GEHD(lEIHRS R£PRES£HT CHANNEL Of CIRCUllS IN CABLE TRAYS) DISIAHC[ DISTANCE (HOH 3)

,__I 01-f f -15 p ( BHOI l 12* - HO :T~ (Co) D p E NEii TO l - I '-J" NO J\ ({o) 0

<< p B HEH TO E - I '-6" HO (3)

  • ' '* -2:*

l.l>

z --------------*-

p - 12" NO I

UJ 8 NEXT TO X

- -- c B BHOI X I '-10' - HO ' 1) ({p) D 101-G C-15 p p

8 BHOf X 8 HEH TO £ 10" g*

HO NO

.1.)

iJ1 (t0) ol

~1

((0)

UJ a:

p E HEU TD X 1 '-6" NO If li~ µ.

-a..

0 p E BELOI X 2'-5" - NO  : i) ((Ji)

.... a:

U::> Ii}

CJ:) jjjl IL ~

?N I- l.l>

U)z Z- ~

Bg UJ a:

'° -

m

' i i

UJ I-0 I

I

( '*

(,

( .. * .::*

,*, ( *,*.

(,.;~:*>.

I I Il f 6 ! H~_L_J_lllo11 J. 1 I I I I I I I I I I I I I I I I I r TI sourn CAIWl1Rl nrcrn1c & GAS coMPANY 'e"~f""" 0 "°*

_ tJ ~~ 011j*1116iTss-zoo 9111 1102 1

'"* "° '!!'!

ID

-C YIRGtl C. SUlMER NUCLEAR SUJIOH. UNIT II 10 ' ** ~ , *

.'"'~-~ GILIUT ASSOCIATES, IMC.

B = BRIDGING I. flm J 11;111 m Ull 3 llClll tr Clll( 1111 HlllMG NUHER: IUIU r-m-111.

C = CROSSING I. IOI l!fl*lllOI or CIRCllll CMIHH 1mm11ou, m fSU !Ill( 1.3-f.

ELECTRICAL /:f..f.?___ rH01Hr~~*.~~:.~~:~umu11 D = 0 IA GOH Al - IMISI 11111111 *m llCLUOll ,. 811CIUl un IUlll tlSICW. --* TRAY SEPARAHON ANALYSIS ~:,, /,~ ~~ 7 ~

euu -a10 *-;Mo.~ I*-* ,.,. ... - - 01..r -0A1r -

1CA.i ,:;,, 71 J

0 REAClOR BUILOlttG " 0 mrr..m~f~~f c 1'1'11 I - - ~ t.~-Wr~~~r~Fr.'f P = PARAtLH I IMDICI II S SPIC Ill IOI! S - SI! SKiii iW-1' '---

Y = VERllCAl ABOVE 1136' *O" y,," D '( .'

ORA II HG CAHGORY YERllCAl HOR IZOHTAL BARR llH HUMBER SITUAllOH (NOH 2) REOUIREO REMARKS tNOH II COOROIHAHS SH l£GENO (UTTERS REPRESEHl CHAHHHOF CIRCUllS IN CABLE TRAYS) 0 ISfAHCl DISTANCE (HOH J)

._!.0?-A r -1 p A HUT TO X - 12

  • HO G) p A ABOVE 0 12' - HO J) D p - 10) (Co)

..,z""

0 HEX T TO l I '-J' HO CJI

-- 6' *------------

~**-

C-14 p 102-8 ANEITTOX HO I

--- ---* p A ABOVE 0 I '-2" - HO JI

- ------ D p DNEXTTOX - -- 6" HO J ((I))

c - ***--*---***

D

"' r.m *~

UJ I 02-C r'-15 0 ABOVE l I '-2' HO J

"'....0 c I *-s* - D


~-----------

li~

-a.

0 BElOI X -- HO c -

I-"' A ABOVE 0 2 1-6'. HO l U::>

fil

> Q.

"'ti%~ "'~oC p A HUT 10 l - 2'-9" HO .!.. -

' I I.II oc ~

uc

- '02-0 H-15 p A BHOI l e* - i HD 11.m m p A ABOVE 0 ** - HD '1 ' 0 TO!All Y ENCLOSED p A NUT TOD - 6" HO 11 102-l K-10 p A HEX T TO X - -2. HO I p A ABOVE D 12* - NO 3 UJ I-oC p D NEXT to X - I '-5" NO (l CJ I

I I. !.~TI I I I I I I I I I I I I I I I I I I I I I I I SOllTll CAROLINA ELECTRIC& GAS COMPANY ***;~:** *u DOUIHO HO.

'~v.v ~./- ~~146-tiSS-200 IH. MO.

9111 1131 I O!V jt

-r _

LEG£ H NOTES.* VIRGIL C. SUMMER NUCLEAR STATION UNIT #I 8 = BRIOGING I flASI 3 01611! IRE UST 3 DICllS Of Clell !All DAlllM& NUN!lR; SERIES E-!H-Ul ~~.!*!!.** ~1 GILBERT ASSOCIATH IHC.

IQ LD*

C = CROSS ING 1 FOR D!rlMlllOM or CIRCUIT CHlMNIL OfSIGNlllONS, S(( rsu lllll 1.3-t.

ELECTRICAL I?}:}_t_ ___ ~ ftWIHf~~,-~~~G~~:~ul 1"""

TRAY SEPARATION ANALYSIS 0 = OIAGOtlAI )

  • IHISI UIRl!RS llRE IMCLUOCO IM ORIGIMll !Rll SISHM DESIGN. --* ~'--~,.._ *~--*f 0 .. '1/ ~/,,/,,.

" I ti TE RMfO I A1E BUILDING 0 P = PARAllfl t Q1NOIClllS SP£Clll MOHS. SH SHH! SN I *:  !!~~;:~-1 -l~*fl/11

~~~~-i~~~i~f[~µ-~~~ ,,, .1,,

V = VERT ICAl ABOVE *412* O" ~-;-

GAS!

HUMBER ORAWlllG CA IE GORY SllUATIOH (NOTE 2)

SH lEGENO <LETTERS REPRESENT CHANNEL Of CIRCUITS IN CABLE TRAYS)

VERT ICAl OISTANC£ llOR I ZOHTAl

t;;,itto 0 I STANCE (1101£ 3)

REMARKS

<HOH I) coono1t1AHS 131-A 0- 16 p 8 ABOVE X 17" ..

NO (])

p BNEXITOX __Ii" NO CD (11

..; p 12" - ij) (i) l!I z

8 BELOW X NO


~-- --

w ..

.Jl)-L E-15 p 6 ABDV£ E I '-2" - NO E TOT All Y ENCLOSEO p B H£Xl TOE - 1 '-3" NO [ TOTALLY ENCLOSED

--~-- - *---

-I - -

JI -C u 14 p B ABOVE E I '-2" .. NO l TOTALLY ENCLOSED I

I *

!~

"' 0 Ul

-a.. u..

I-"" Cl I JI -0 C-1 J p

~

p 6HEXTTOE

mfEr~ I B HEX! TO X l'-1" I '-3" 6"

HO D8 HO r E TOTALLY ENCLOSED

~ m *- c U::>

~\

UJ

~

0 B ABOVE X 12" 6" HO ~

_, w I- l!I v>z UJ B BELOW X 12" 6" NO

~\

z- w 0 co

-a>

U c IX p B NEXT TO E

- I '-3 NO E TOTALLY fNClOSEO 131-E C *I I '

u B OELOW E 11" I '-3" NO F TOTAllY ENCLOSED 131-f f *12 p B ABOVE E I '-2" - HO l TOIALL Y ENCLOSED p 8 NEXT 10 E - I '-2" HO f TOIALLY EHCLOSEO UJ I-Cl 131-G f -10 p B ABOVE E 3 '-3" - HO E IOTALL Y ENCLOSED C B ABOVE E 12" - HO I TOIALlY £HCLOSEO

-131-H

- -* 1 0 p B ABOYI x 2 '-5" - HO X TO!AlLY INCLOSED p 8 NEXT TO X - 6" HO {IJ, X TOTALLY ENCLOSED 131 -J f 13 c 8 BELOW X J" - NO *--------*-----

--- - - - - c B ABOVE X " - HO --- -*--------------

( **<<*

  • >** (

I I I I J I I I I I I I I I I I I I I I I I I I I I I I I 1~uurn CAROLINA ELECTRIC&GAS COMPANY R~~ ~~,;'." ....... MO.

_<jl _"!-! 01J 1111161Jss-200 9111 jtJ1 2ID LEGEND NOTES:* VIRGIL C. SUMMER NUCLEAR STATION UNIT 11 ...!* LD* . . . . . . . . . . I ClllEltT ASSOCIATES, IMC.

8 = BRIOGIHG rim J llClll Ill Ull l llClll If tllll IHI UAllH IUllU: snm (-211-111

' 1.I. ru ELECTRICAL ":{~/P_ ____ ~ _ ~ fHCINf(H A.H:O CONJUL1AMU C " CROSSING em111101 Of tlltUll tHlO!l DISICUllOU. SU rsu TUI( 1.3-f. flllAOINO, PA..

TRAY SEPARATION ANALYSIS D "DIAGONAL P = PUAllEl

3. * - IHlll llUllll Ill! llClUl!t II OllCllll JUI llSlll tlllCI.

I 0 IMUICllfl srttlll MOlll - Ill SHH! Sl-1 INIERMEOIATE BUILOIHG l<Al*

0 l~/.- * .Jcr.;~:r~J' '!'fir/.>,

    • OU41U-02t)I -iN01Nit*AilP

~1 IQ~l~!if:J*"'~WAOf;t~*H

- - Oi"rT - "°bATf -

C fiPul-

  • l/M V = YERllCAL ABOVE 1112' - O" *A11 D ~ I I I CASE ORA II HG CAHGORY SITUAllOH (NOTE 2) VERT IC Al HORI ZONU l BARRltK HUMBER REQUIRED REMARKS l HOil 11 COORDltlAJ(S SH LEGEN0 (UITERS REPR£SEHf CHANNEL Of CIRCUITS IN CABLE TRAYS) DIST AHCE DISTANCE I HOil 3) 131-K G-11 c B ABOVE l s* - HO 5) a:

t!I z

w I Jl-l e---

G-1 D

p A ABOVE l A NH! lO l A ABOY( l 10" 10*

~ -** ...

- HO HO HO

\S)

I© (S) (0) 0 e* --

c0 2 '-3" . HS*

I Jl-11 I-JO A BHOI C - --

.,, IJl-H l-1 cv A BELOI I (I VERllCll) &" - NO' j) w a:

i!'l~ u.

-a..

... a:

C> p A HE IT TO I - 6" NO (i) 00: ia.. fi1 U::>

.,, ~

ZI

..: ' I

... t!I V>z ~ I z-ag I

N' I ll

~

w

~

C>

I I ILEGE.I HDI I l I I I I 1 r rr 1 I I I I I I I I I I 11 *r *I '

SOllTH CAROLINA ELECTRIC& GAS COMPANY .e-;;;J'f""" O*AWIHO HO.

_ ..f>. !°1.d. 01q111J61!ss-200.9111 1132 1 e, 0

IH NO.

j

  • IV HOJES*
  • VIRGIL C. SUMMER NUCLEAR STATION UHIT #I 9 = BRIOGIHG I FIRS! 3 DIGITS UE USI J DIGITS or CIBl! TRI! ORlllNG NUMB!R; S£Rl£S E-214-111 kl"" '".!~*~i GILBERT AUOCIUU IMC fhj p_ ~ ~~

IQ LO*

ELECTRICAL 1

C = CROSSING fHGIHfffU AHO COH1Ul t AHTS *

' FOR DEflMlllON or CIRCUIT CHIWWH OESIGNITIOMS, Sf! rsu Ill(( 1.3-L - fl.IAOIHG, P4.

TRAY SEPARATION ANALYSIS D = OIAGOHAl l. * - IHISI llUllU lfRI INClUOIO IN ORIGINAL !RU SYSTIM OISIGM I _.b.'. fr /'~L-'f: .,.,, , ~~r /77 IC All P =PARAllfl 1 0 INOIClllS SP!Clll NOllS - Sii SHFEI SM-I INTERMEDIATE BUILOING

  • 0 OHlSl--Om~***"c"'

lllltt~J;!!. l:_ ,.,.,. Q..lll,~yt~An(

- cfrf - -.;;-,r -

CH nnL !_~~

V = Y£RTI CAL ABOVE 412'

  • O" /; 'G' ..,,,,/10 B I I 1~*.. >91 t:ASE DRAllHG CATEGORY SI TUATIOH (NOTE 2) YERllCAL HOR t ZOHTAL /taRJt'RtERO HUMBER REMARKS I< HOH I l CODRDIHA![S SH lEGEHD <LETTERS REPRESENT CHANNEL Of CIRCUITS IN CABLE TRAYS) DISTANCE DISTANCE (NOTE 3l I 32-A J-11 c A BELOW X 4* - HO 0 (

c A ABOVE l IO" - NO '~) c.

Cl z

UJ 132-8 f -II p 8 ABOVE X I '-IO" - NO (1). l TOTAll Y ENCLOSED I'.

p B NEXT TO X - 6" HO 1(1),(2) l Cl) uJ 0:

i li~ .....

0

-a..

cor

._ 0:

U:::> Cl ii"- UJ

(")

z - _,

._ <.O oC I "'z UJ w oo w UJ Uo 0:

I a>  !

I UJ 0

I c.

( I-I,

/"c-;-,' .

[_Lll~G Iirk J -.,I -'No11[ !' I I I I I I I I I I I I I I I I I I I . I "'L SOllTll CAROLINA ETECTR IC & GAS COMPANY r 1~"

_011 ~'If-'-

o*rnNO NO, o~T~1~6Js-s. ?oo .. **-rcv 9111 j 1:Ll I [-

-- fHClllf~~s-~~~G~~:~uL VIRGIL C SUMMER NUCLEAR STAllOH UHIT II B = BRIOGING so'""

I ..!c~~-'"-"-:J GILBERT ASSOCIATES IHC

.fJff'_ -

flRSl 3 DIGllS IRI LISI 3 D"llS Of Cllll IRll DRUIMC NUUIR, S!RlfS 1-114-111 C =CROSSING 1 IOR D!f INll IOM Of CIACUll CHINNH DlSIGMll IONS. Sil f!U lllll 8 H ELECTRICAL ~-.- ~1~ TA Hf\.

TRAY SEPARATION ANALYSIS 0 =DIAGONAL ] - rnrsr umos 1m INCLUO!O IN O!IGINll !Ill SlSfU OISICM. - -- -* IC>lf [; I . ~-C~ r.'17' 01'/l7

  • IHTERMEOIAJE.BUILOING
  • 0 04H6Hl10 -.fHG1Wti,.-A;;,.111ou1 - Of,.T - *0.-,1 -

P =*PARALLEL Q1NOICl If I SPIClll MOHS - S(f IH!fl SN I V = Y!RllCAl ABOVE 1136' O" ~!fEl-*9]'.§:~fi~31~**r.~F'p?;pj~

ICl' 111 I* 8 -+ 1f)

CASE ORAWINI: CAHGORY .SllUAllON (HOH 2) VERT IC Al HOR I ZOHTAL BARR1ttt HUM Bf R REOUIREO Rf MARKS (HOH I) COORO INA 1l S SH llGlH O (l£TTERS REPR£SEN1 CllANllH OF CIRCUITS IN CABLE TRAYS) OISIANCE 0 IS UNCl (HOH J) 133-A f - - H-10 cv A NEil JO x <A VERTICAL! - -- ----- 2 '-6" NO CD ----

(_

c A DHOW X IO" HO 1(1)

(_

.r. ------

CJ z - - - - ------ -- -- ----*---- -----------

w I JJ-B H 13 C. y A HEX! TO X I A YE~llCAl) I '-2" NO I IOTALlY ENCLOSED I JJ-r. [ 14 c A ABOVE x 1" NO (5) c._

"' a:

w --

15~ 0

-a.. u.

... a:

U::> Cl

>a.. w

... CJ "'

a:

tnz w _, -----

z-oo w

-"' a:

~

Uc w

Cl

~ ----- ---

s::s:~

CJ - - -----------------

c:::

C/l - - - ---------- --~---- -- ----- *- -------------*-----------

>-3 ----- --*- --*---***- ----------------

t;rj ------ -----

r-' z ---- - * - - - * - --*--- ----------------

'° 1--3

'-) '°

\0'

'-)

0 I f r-'

_L~-h~Hl- I !-_LHJrrlc-lJ I I I I I I l I I I LW_LLLLL1 L

  • '.lltifiTTIJHii IH.i flfCIRIC&GAS COMPANY Jpgl~L o*--.--,

OfllA*ltiO JllO.

11 i 11116 t:ss. ;>oo 9111 1135 I

,,...{',

fM, JIG.

8 = BRIDGING VIRGIL C SUllER NUCLEAR SIAllOH UHll II IQ""' '-~ji""-:1 GllllUTIiAlSOCIUU, flRSI J 01611! Ill llSI J OIGllS Of CABll till DUllM& MUIB!l; 11111! f-114-111

--=t:i I IHC.

ELECIRICAL i?WJ~_ - - - - - - f HGtHHAl'AOIJUO. AHD CONWI. UHTS C = CROSS ltlG 1 FOR Dlfl~l110N Of ClaCUll CHINNll Df!IGMlllONS. Sfl ISll llllf l.l*4. ~A.

IRAY SEP ARA Tl OH AHAL YS IS 0 = OIAGOHAI l * !Hiil !IRRl!IS llRI UCLUDID IN ORIGIWIL IRll llSlll DISIGM K*L<  ;.~ /q,/~ o+:J.I J/!q~,

P = 'PARAll fl 4 0 IMOICll!S IP!Clll NOffl Sii SHI 11 IN* I INHRHEOIA IE BUllOING

  • 0 0U46 .--020 . ,-...01Wr:i.t*..,,.f111iQYii - OCrf 0.oi -

!rf~~1f>!l-'1~~J**y1M*Otpfm~

Y = YERllCAl ABOVE 1163' *0" 'r_l! ' <:le /I~ .,_ I CASE ORAWIHG CA 1£ GORY SllUAllOH (HOH 2) YERI !CAL HORI ZOHIAL BARRl[H HUM8£R REQUIRED Rf MARKS

<NOil II COOROIHAHS SH lfG!HO (LlllERS REPRESEHI CHAHNH Of GIRCUllS IH CABLE IRAYS) 0 ISIANC( DI STANCE (NOTE J) 135 *A l u p A 8£LOW l 12" - HO © c

.-* c A 8£LOI l 12" NO I) ~

ex

z:

w 135. e G 14 p A ABOVE l 12.


.. HO -

(

1)

-~-----*

p A BHOI X I '*3" - HO

- I' Vl I

UJ ex li

-IL l:1 c>

u..

~ ....~ .....,,:z: w....

.... 0::

U::>

!il Vl Ill z: - -'

c> c> w u

- a:

Cl 03

....0.... - - - - - -

UI

.. _ --~~--------

r--- *---*

I,',

1* ..

I It E GLJLLJ;Ar~l_Ul_LI I I I I I [I I I I I I I I I I

  • SOUlll CAflOl INA HFCTRIC& GAS COMPANY ~" O*AW*HG HO IH HO:f *lY

~ 01lfil%Jss 200 q111 J1111 1 c:_-

-r _.

VIRGll C SUMMER HUClEAR SUTIOH UHIT #I CllaERT ASSOCIUU IMC 8 = BRIOGIHG  : I f IRS! l DIGllS Ill llll l Ol&llS Of Cl!l[ Ull ORlllNG NU*BO; SEWS 1-114--lll 10 to*

/{l:/.P_ _ __

~~~ [llJ!~-1 1 ELECTRICAL fNGINE(Rl.lt.NOC0HSULT AHI$,

C =CROSSING I FOR OfflMlllOM Of CllCUll CHIMMH O!SICMlllOMS. SH ISIR ll!ll l.l-4. - ftfAO*HG, ""

0 = OIAGOHAl J !HIS! llUl!RS 1111 INtlUO!O IM ORICIMll JUI SHH* D!SIGM. ___ ___!RAY ~E_!'.!_~T IOH ~~Al Y~~--- ~~1~ O~J/ *01/?7 tHc*,.;,1,.-.. ?.:"o-;-; . -. - or.. 1 - -or,r -

PENEIRAllON ACCESS AREA

-

  • 0 04446 --070 P = PARM! Cl V = VERllCAl 4 QIMOltlllS SP!tlll MOHS - Sf! IHI ff IN* I ABOVE 412' O"
  • 1w~,~~

t, '.Ji . 1~r!!n~:J!tE1**

- t:'"' '111 0

~fl~t1~~~0- *,

CAS! DRAWING CA IE GORY S_ITUAT ION !HOH 2) YERllCAl HORllOHTAl lJARRltR HUN BER REQUIRED REMARKS t NOH ll COORO IHAIE S SEE LEGlH O (lETIERS REPRESENT CHAHHfl Of CIRCUllS IH CABLE TRAYS) OISTAHCE OISTAHCE (HOIE l)

I* I -A


*G-11 0 8 AHOY! l I ' 9" l '-6" HO ©. l IOTAll Y EHClOS£0


L Cl z: --*-* -*---*- ----- ---------

UJ f-.------ - - ---

V>

UJ

... V> a:

Oo 0u..

-CL

.... a:

~I' U::> UJ

~CL VI 0

--- 14--

w. I ,_Cl

.°' z: ..... I V> UJ Z-oo a:

UJ uo '

---~-*---

0

-- ~------- ------- ---- ----- ------------ -------------

- - - - -- ~-*---- ---- -*----*- - - - - - - - - - - -

~----

_Llr~rjJ-lJ_Jiia 11 [ !*1 I I I I I I I I I I I I I I I I I I I I SUU Ill CARUl.i HA ELECTRIC& GAS COMPANY l'>:*;~ CH*U O***oWO N<),

!!{} '_'."j_ Qi~;~l6Tss-200

'~UV c:

T'-*Jt"'i 9111 1161 I YI RG IL c SUMMER NUCLEAR SIAllOH UHi! #I 8 =

C=

BRIDGING CROSS ING

' l I 11111 3 llCIJS ur LISI J !ICllS er Clll! 1111 DllllWG IUl!IR; S!lll! f-lll-111 rot DHlllllOI Of CllCUll CHl.. H OISIUl!IOU, m rm um

  • J-l, HE CTR I CAL KW

~*LP G!LIUT ASSOCIATES. IHC, fHG!Hff*S AHO COHiULUHH Jlf AOIMO, ,. ...

TRAY SEPARATION ANALYSIS ~- ':-~/,...~-A~l!i:: O'f'tl s;/1r/;o1 0 = OIAGONAt ) * - IM!!I Utll!IS l!I[ llClUDll IN OllGINll Ull llSllM HSIU 1~44461-IJJO /. iHG"1Nli ..-.~ .. " *~ - *or..1 *- -oi"Yf -

P= PARAlLH 0 FUEL llAUDL I HG BUILDIUG Y= YERllCAl l llOl(llfS Sf!Clll IOl!S SH SHH l S" I ABOVE 412. -0" AtlD 1136' -0" ~et~r1-~\1~~nw!f£fill~

US[ DRAWING CATEGORY SllUAllOH (HOH 2) VERllCAL HOR I ZOHIAl DANrl ltH NUMBER REOU I REO RI MARKS

I HOH II COORO INA l! S SEE l EGE NO ( l El HRS RE PRE SEHi CllANHEl Of Cl RCU II S IN CABLE TRAYS) OISJAHCE DIS!AHCE (HOH ])

161 A H I~ p A BELOI X 12" - HO (I)

--*---~-

t

.x ---- - - - --------- ~-

lD z

uJ


**---~-

uJ IX

!~

-A-0 t- IX

.,,.... r-------- --

L) 0 iii"- UJ t- CJ cnz __, . ~

co "'

z - UJ I Uc a: I t-0 g; ~ ---- r-------- ------ --- ----------

0 trj c: z - - * - * ----- ----- ---------------

[fl t::I 1-3 ::;;:: --*--- ------- -----------

z trj f-' - .,~~---

- -----~ *-- ---- -~- -*- ---------*-----------------

l.O 1-3 ----- ---- - - --

l.O

--~-------~----------

'-.I l.O

'-.I - -

I ------ ------------ *- - ---* ---------*-------------

0 f-'

r*..

(-:'**::

I IL[G+JJ.:J IHOHr I: *I I I I I I I I I I I LLtLLLLIJJJI

.. r.As COHPANY j -y I c.

,.-~<l.'*,'li>d 111u1i1c& , **v~ C HKO OJUWIHQ N<), SH. HO. -T lll(V

~DjJ ~+:J_ 041'1116 i!sS-200-9111 1162 I VI RGI l C SUOER NUCLEAR STAllOH UNIT #I t __

B= BRIOGING I FIRST J DIGllS IR[ UST J DIGITS Df Clll! Till DRllm NUW!U, S!RI!! 1-114 Ill *o Lo* , '"" '":'~ CILIERT ASSOCIATES, IHC.

ELECTRICAL f?!:!_P _ _ fHCIHf(lt\ AHO COHSULTANU C= CROSS ING l FOR DHIWlllOW Of CllCUll CHUNCl O!SIGNl!IONS. SH FSll llllf l.J-4. ,.lADIHO, PA

. TRAY SfPARATlON ANALYSIS f J~ /r. /q_£1. 1/J.r/,7 D= DI AG OH Al ) - !HIS! etU!IRS l!RI INClU0£0 IN ORIGINIL !RIY SISllW DISICN. *cAlf 01' l /

P= PARAllH 4 0 INOICU!S !P!Clll NOH! - !£1 !Hfll SN I FUEL HANDLING BUILDING

  • 0 OH'6rf1~1~**********"°"1,;

~'" .. ,.01 " __ *p:t-9*~11~r!.Yr~~£!!F~

-oiH' -

V= VER! I CAL ABOVE 463' -0" (' ,flf.11 I* . L G- "/11 II B ... '""

CASE DRAWING CA H GORY SITUATION (NOH 2) VERTICAL HOR I ZOHIAL U~ttrt IER HUMBER REQUIRED REMARKS

<NOif I\ COOROIUAHS SE£ LEG£H O ( lE llERS REPRESENT CHANNEL Of CIRCUITS IN CABLE TRAYS) DISTANCE DISTANCE (NOTE J) 162-A G-15 p B ABOVC X 9"

- - NO © ('.

p 8 BELOW X 12" - NO (I) ('_

c:C Cl z --*----

(I)

-*~-

w G- 13 p B HEX! TO I - 12" 110

,________ ___ -- p B BELOI X 12" - NO (i). (2) (.

  • .,,w --

, II a:

~:g C>

-o.. u..

,_ a:

co/ iil"- .,,

<->::> C>

w

-c

'  ! i..-

'(i _.

,_ Cl w

w "'"'

z - w co -

C> C>

Uc a:

a>

w

-c Cl t

I

_j

i SOlllll CAROLINA ClfCTRIC & GAS COMPANY I

VIRGll C SUMNER HUClEAR SIAllON UNI! fll---L-4-.....t-~~..--.,.._,,....,_ _._____,,.,_..~-i

i ELECTR I CA.""l_ _ _ __

l TRAY SEPARATION ANALYSIS

  • -* ---*---------*--------~
  • i** SPECIAL NOTES
  • .1

.'l

,\

.~'

  • i . NOTES fOR SN- I

. '~

0::

FIRE Will HOI PROPAGAI( 00111 OR HORIZOHIAl z

UJ COHIROl OR IHSIRUMEHI !RAY HAVE YERY LOI INIERHAl IHfRGY UVHS IHUHORE, ENERGY IS NOi AVlllABlE TO IHlllATE A FIRE

!RAYS ARE lO!AllY fHClOSEO ADIOUAH SPACIAl SEPARAllOHS llAIH!AIHED OHlY OHE CltANHfl or ClASS IE CIRCUITS HFECIEO IHfREFORC. SVSH* SUHY fUHCllOHS

. en w 0::

IUINUIHEO I j§~

- 0.

0 u.. 6. This analysis concluded a barrier was not required. However, a barrier

  • ~

I- 0::

... enfil-c U::>

~

was subsequently installed in compliance with the licensing connnitrnent I- <JI to provide barriers for multiple separation violations as described

"'z z-w ag

..J w in paragraph 8.3.1.4.1, Item 4

  • D<

w 1-

-c C)

(;:>':"...

(.*.*.*

.. (\:.**". ,*_*.:: *.**:

0 4~51-)(

~ 4351*X~c6>AG~ *X 4Z90*X~

430'*:3" 4~2G*8 4325*8 4?.'2.6*B 43'25-8

---,rrn-----------,..,.,,--F_LOO_IC 425'-0" 4650*')( SECTION A-A 4'290-')( ----1-----e ~4'290-X I _ _ _ _ _ _ _4_30'-3" 4314-A SECTION B*B I!

c.c

....c:: PLAN Cl> Case 041- C Q:)

....0

M

('-'1

~

0 t'-1

~

11 I I 'i I I r---- 3098-X

{6. 1z.*

I I I I fil J  ;--4114-A LLl _ _ 45G'-a" m

LLl 4174-A !5069-A ---~

41,8-X --t::!...J 454~8" 5009-A

~ ~ 4Sa'-1" 3098-X 5077*0 4168-X ~5017-0 50G3*X 50Ga-x SECTION A-A PLAN Case 102-A Figure SC-2

~_,

!. tO

~.;.

~

Co Ul'

>(.

~

Cl\

Ill

~ ~

Ul ~

~

)(

,n <(

<{

~ 2 0

~~* j::

u 0..,

in Ill

<I)

~

-*0 r-

<(

I m

0 QJ a

11'1 x

1~

~~

'in

\9 2

z

<(

---...., ...J Cl.

Figure 8C-3

APPENDIX 8D ANALYSIS OF THE ACCEPTABLE VOLTAGE RANGE TO BE APPLIED TO THE ESF SYSTEM 8D.1 CRITERIA This calculation was based on two criteria:

- The voltage at each piece of safety related equipment must be within the safe operating range for that piece of equipment.

- The voltage of the offsite sources must be sufficient to operate the required loads in the event of an accident without actuating the degraded voltage relays.

NOTE 8D.2 RN 99-093 This section is being retained for historical purposes only.

8D.2 METHOD In preparation for the development of the calculations, a "Feeder/Load Data Base" was developed and verified. This data base contains information on the characteristics of the safety related loads and their feeder circuits, including the demand load for various plant operating conditions. The characteristics for the system equipment and materials, such as transformers and cables, were taken from the "as-built" data for the specific equipment and materials.

The system calculations were performed using electrical analysis software. The first RN 12-007 calculation established a base case model of the electrical power distribution system.

This model includes the existing transformer tap settings which include a 2.5% boost for the 480 volt unit substation transformers 1DA1, 1DA2, 1DB1, and 1DB2. For unit substations, 1EA1 and 1EB1 and for the emergency auxiliary and safeguards transformers, the taps are set at the nominal position. Throughout the calculation process, the transformer tap settings were reviewed to determine if revised settings could improve the overall performance of the system. (Reference Calculation DC-820-001.)

The next calculation modified the base case system model to evaluate the system under the worst case loading conditions. This condition results from the large break LOCA accident during the injection phase. The source voltage in this model was manually reduced and the system was repeatedly analyzed in an iterative process until the worst case motor terminal voltage was reduced to 90% of its rated voltage. The motors in V. C. Summer Station were specified and designed for steady state operation with a terminal voltage in the range of +/- 10% of their rated voltage. The voltage at the motor control center (MCC) buses was also checked and found to exceed 420 volts.

8D-1 Reformatted October 2014

This ensures that there is sufficient voltage for the pick-up of the MCC contactors. The resulting system model established that a voltage equal to or greater than 90.2% on 7.2 kV buses 1DA and 1DB is sufficient to ensure adequate voltage at the terminals of the safety related motors. Since the purpose of this part of the evaluation is to determine the minimum 7.2 kV bus voltage to provide adequate terminal voltage for all Class 1E loads, the number of buses connected to the offsite source and the voltage of the offsite source are not significant. The results of this model are summarized in Table RN 7.3.3 of Calculation DC-820-001.99-087 With the minimum 7.2 kV bus voltage established, the next effort determined the minimum setpoint for the degraded voltage relays. Since these relays have a tolerance on both their calibration and operation, a detailed evaluation of the total tolerance band was performed. This determined a total tolerance band of +/- 0.328%. Since the relay must operate before the 7.2 kV buses reach the minimum acceptable voltage, the setpoint value must exceed the minimum value by an amount at least equal to the tolerance. To provide both a margin and consistency with the previous settings, the setpoint was established at 91.34% of rated voltage. (Reference Calculation DC-820-001.)

Based on the degraded voltage relay setting, the tolerance on the relay calibration and operation, and the response of the SCE&G transmission system to a trip of the V. C.

Summer Nuclear Station, the next part of the effort determined the minimum acceptable offsite source voltages during normal plant operation.

Studies of the transmission system under extreme loading and system configuration conditions have determined that 230 kV system voltage will dip to 95.5% of the pre-trip voltage in the event of a unit trip. After less than 3 seconds, the system voltage will RN recover to 97.1% of the pre-trip voltage. Similarly, the 115kV system voltage will dip to 06-042 95.6% of the pre-trip voltage in the event of a unit trip and will recover in less than 3 seconds to 97.3% of the pre-trip voltage.

Electrical analysis software was used to model the effects of motor starting conditions RN due to an accident loading sequence on the 230 kV and 115 kV offsite sources. Based 12-007 on the tolerance band of the relays and the motor inrush conditions, the 7.2 kV bus voltage must be at least 93.9% of rated voltage prior to motor starting to avoid relay actuation (including a 1% margin which was determined to be unnecessary subsequent to the completion of the calculation). The minimum pre-accident voltage is also dependent on the number of plant buses connected to each offsite source. In a further evaluation, the capabilities of the various combinations of safeguard transformers and the voltage regulating transformer were determined and combined with the worst case voltage dip resulting from a unit trip. The results of these evaluations are summarized in Table 8.2-2. (Reference Calculation DC-820-001.)

8D-2 Reformatted October 2014

The final part of the analysis determined the maximum allowable offsite system voltages. Additional system models were developed with electrical analysis software for RN 12-007 plant operation in modes 5 or 6, cold shutdown or refueling. One model evaluated the system using the emergency auxiliary transformer, XTF-31, as the source and the second model used the safeguard transformers, XTF-4 and 5, as the source. The loading consisted of the minimum set of equipment that would be expected to be operational during plant shutdown and only one of the two trains of ESF equipment was supplied from each offsite source. The models were repeatedly analyzed with increased source voltages until the worst case motor terminal voltage reach 110% of motor rated voltage. The results of these models are summarized in Table 8D-2, and the maximum voltage limits are included in Table 8.2-2.

8D.3 CONCLUSION As described above, the 7.2 kV bus voltage must be at least 90.2% of rated voltage to ensure the voltage at motor terminals exceeds the rated minimum motor voltage for steady state operation. This voltage is also sufficient to ensure MCC contactor pick-up.

(Reference Calculation DC-876-007.)

The setpoint for the degraded voltage relays must be at least 90.528% of rated voltage to ensure that the relays actuate when the 7.2 kV bus voltage reaches the minimum defined above. The actual relay setpoint is 91.34% of rated voltage.

The offsite system voltages must exceed the minimum values listed in Table 8.2-2 (Reference Calculation DC-820-001) in order to ensure that the degraded voltage relays RN 99-093 will reset after the first loading step and will not (inadvertently) drop-out on subsequent steps in the event of an accident. These minimum voltages are dependent on the number of buses connected to each offsite source, the arrangement of transformers, and on whether the voltage regulator is in service.

The voltage of the offsite sources must not exceed 104.2% of rated in order to avoid excessive voltage on motor terminals. The 115 kV line voltage can be higher than this if the voltage regulator is in service.

No improvement in overall system performance can be obtained with alternative transformer tap settings.

8D-3 Reformatted October 2014

TABLE 8D-2 CALCULATED MOTOR VOLTAGES FOR MAXIMUM OFFSITE VOLTAGE Two (2) cases, BLLXTF45 (115 kV source) and BLLXTF31 (230 kV source), were created to determine the maximum offsite system voltage allowable without producing excessive voltages at the motor terminals. Since "A" train was chosen as the worst case bus (heaviest load), "B" train was chosen as the bus to study under light load conditions (Mode 6). The criterion for evaluating worst case conditions was a running motor reaching 110% of rated terminal voltage (NEMA standard maximum).

The source used for the evaluation of the 230 kV system was an emergency auxiliary transformer, XTF-31. The source used for the evaluation of the 115 kV system was 2 ESF transformers, XTF-4 and 5, in parallel.

The offsite voltage was decreased by small increments of voltage from 1.0 per unit until the worst case motor was found.

MAXIMUM OFFSITE VOLTAGE DAPPER MAXIMUM 115kV SOURCE 230 kV SOURCE BUS # OPERATING "B" ALLOWABLE CASE BLLXTF45 CASE BLLXTF31 TRAIN MOTORS VOLTAGE 120 kV (1.042 pu) 240 kV (1.042 pu) 55 XPP1B 7590 7477 7476 72 XPP39B 7590 7472 7471 502 XHX1B 506 506

  • 506
  • 504 XPP31B 506 504 504 509 MFN97B 506 501 501 601 XPP48B 506 497 497 602 XFN23B 506 495 495 604 XPP32B 506 496 496 5004 ALOP2 506 497 497 5007 XFN36B 506 496 496 5504 XFN46B 506 496 496 5507 XFN133 506 498 498 5509 XFN32B 506 497 497 6002 XPP4B 506 498 498 6003 XPP141B 506 498 498 6004 XFN45B 506 497 497 6006 XPN48 506 497 497 6007 XFN45A 506 497 497 7006 XFN80B 506 494 494 9003 XFN38B 506 498 498 9005 XFN39B 506 499 499 9013 XFN83B 506 498 498
  • Worst Case Motor 8D-4 Reformatted October 2014

APPENDIX 8E ANALYSIS OF THE VOLTAGE DROPS ON THE ESF SYSTEM WHEN STARTING A 6900 OR 460 VOLT MOTOR WITH THE DIESEL GENERATOR AS THE SOURCE 8E.1 CRITERIA The criteria was to determine (1) the voltage at the terminals of the largest safety related 6900 and 460 volt motors when they are started and (2) the voltage at the other Safety Related buses during the same period. The power source was considered to be the diesel generator with the safety injection signal loads operating on the buses.

8E.2 BACKGROUND The 6900 volt charging/safety injection (CH/SI) pump motors and the 460 volt service water booster pump (SWBP) motors are the largest safety related motors for their respected voltages. Therefore, their characteristics were used in the calculations.

RN Electrical analysis software was used to simulate the restart of the largest motors and to 12-007 determine the effect on system voltages. The diesel generator can be modeled as an infinite source with zero impedance when modeling the system under steady state conditions since the generator voltage regulator will hold the terminal voltage to within +/-

1/2% of the setting. However, for transient conditions, the diesel generator model needs to include an internal impedance since the voltage regulator can not respond immediately to changes in loading. The source impedance for the transient model was based on the short circuit impedance of the generator as described below in section 8E.3. To obtain the internal source voltage, the source voltage of the model was manually adjusted to produce a machine terminal voltage of 0.945 per unit (under steady state conditions) with the generator load equal to the maximum system load, minus the load of the motor to be restarted. A terminal voltage of 0.945 per unit was used because the lower administrative limit for setting the voltage regulator is 95% and the regulator has a tolerance of +/- 1/2%. To find the voltage levels during the initial RN 98-061 inrush for motor starting, the source voltage was held constant and the starting load of the motor was added to the system. The system voltages were then calculated.

As described in Section 8D.2, the safety injection signal load is the largest load to be applied to the ESF system buses at any one time. Thus, this load was used as the running load on the buses.

8E-1 Reformatted October 2014

8E.3 METHOD An analytical software model (from calculation DC-836-008, case DSTEP8S) of the RN 12-007 diesel generator steady state full load condition was used as a base case for developing the large motor restart model (Reference calculation DC-8360-012). This DSTEP8S RN 98-042 case model determines the voltage at the A train buses when the Safety Injection loads are operating and when the Diesel Generator is supplying the load.

To evaluate the restart of large motors on the diesel generator, the steady state analytical software model was modified to incorporate a source impedance and to RN create two new cases. The first analytical software model, case DS825R, simulates the 12-007 restart of the 6900 Volt Charging/SI pump (XPP43, 900 HP) and the second, case 00-01 DS8101R, simulates the restart of the 480 volt service water booster pump (XPP45, 350 HP).

The source impedance was taken as equal to the short circuit impedance of the RN 98-061 generator. This short circuit impedance was based on the generator test data which includes the following information:

Generator rating: 5845 KVA Generator X/R ratio: 16 Short circuit reactance: 0.13 per unit RN The steady state analytical software model was copied and modified by adding the 12-007 source impedance and turning pumps XPP43A and XPP45A off-line in order to simulate the pumps tripping. The source voltage for the model was manually adjusted until the generator terminal voltage was equal to 0.945 per unit. This is the lowest value allowed by the combination of the regulator setting limit of 95% and the +/- 1/2% tolerance of the regulator. The resulting source voltage was then held constant and the starting load for each of the two motors was added into each of the two respective models. The following are the load values used:

MODEL BUS TAG KW KVAR RN 12-007 25 XPP43A 485 2992 101 XPP45A 231 1074 RN The resulting bus voltage from the two new model cases DS825R and DS8101R were 12-007 then evaluated to determine the following: 00-01

a. Acceptance of the motor starting voltage by comparing the model case voltage RN 12-007 with the motors minimum required starting voltage.
b. Verification that the motor control center (MCC) contactors do not drop out during large motor restart.

8E-2 Reformatted October 2014

The 6900 volt safety related motors were designed to start at 70% of rated voltage and, therefore, have a minimum starting voltage of 4830 volts. The 460 volt safety related motors were designed to start at 80% of rated voltage and, therefore, have a minimum starting voltage of 368 volts.

The contactors in the SQUARE D motor control centers have a dropout of 65% of nominal voltage. A value of 5% was added to account for voltage drop within the control circuit.

Since the 480/120 Volt power transformers are wound to produce 120 volts on the secondary when fully loaded, a value of 70% of 480 volts (336V) on the MCC busses was used in the evaluation.

8E.4 CONCLUSION Considering the diesel generator as the power source, the calculated voltage at the terminals of the 6900 volt CH/SI pump motor and 460 volt SWBP motor is above the minimum design starting voltage as mentioned in Section 8.3.1.1.4.2 and listed below: 00-01 VOLTAGE RN 01-113 MODEL BUS TAG MIN START CALCULATED MARGIN 12-007 25 XPP43A 4830 6323 31%

101 XPP45A 368 415 13%

Since other safety related motors are smaller than the CH/SI pump motor and the SWBP motor for their respective voltage levels, the motor terminal voltage during the starting of all safety related motors will be above the design starting voltage for these motors.

The following table lists the voltages at each MCC bus for each of the two restart conditions.

The table shows that all voltages are substantially above the 336 volt criteria and, therefore, verifies that the energized contactors will not drop out during large motor restart.

RN MODEL BUS TAG START XPP43A START XPP45A 12-007 1000 XMC1DA1X-P 410 431 1500 XMC1DA2X-S 409 430 2000 XMC1DA2Y-P 408 429 2500 XMC1DA2Y-S 409 430 3000 XMC1DA2Z 407 428 RN 01-113 4000 XMC1EA1X 418 438 8000 XMC1EC1X* 418 438

  • Loads on this MCC are not energized. Therefore, the voltages are the same as for bus 4000.

Tables 8E-1 and 2 list the calculated voltages of the ESF system buses and the motor terminals.

8E-3 Reformatted October 2014

TABLE 8E-1 CALCULATED VOLTAGE LEVEL OF ESF SYSTEM BUSES AND MOTOR TERMINALS WITH A DIESEL GENERATOR AS A SOURCE AND STARTING THE 6900 VOLT CHARGING/SAFETY INJECTION PUMP MOTOR Condition:

Initial voltage: 6804 (94.5% of 7200 volts at diesel generator terminals prior to starting motor)

Initial Load: 3505 KW Power Source: Diesel Generator Motor: Charging/Safety Injection Pump Mtr. (6900 Volt)

Resulting Voltages:

Percent of ESF System Points Voltages Nominal Bus Voltage Diesel Generator 6339 88.04 7200 Volt Bus 1DA 6328 87.88 6900 Volt CH/SI Pump 6323 91.63 of motor nominal rating 480 Volt Bus 1DA1 418 87.08 480 Volt Bus 1DA2 410 85.41 480 Volt MCC 1DA2Z 407 84.79 7200 Volt Bus 1EA 6322 87.8 480 Volt MCC 1EA1X 418 87.08 8E-4 Reformatted October 2014

TABLE 8E-2 CALCULATED VOLTAGE LEVEL OF ESF SYSTEM BUSES AND MOTOR TERMINALS WITH A DIESEL GENERATOR AS A SOURCE AND STARTING THE 460 VOLT SERVICE WATER BOOSTER PUMP MOTOR Condition:

Initial voltage: 6804 (94.5% of 7200 volts at diesel generator terminals prior to starting motor)

Initial Load: 4087 kW Power Source: Diesel Generator Motor: Service Water Booster Pump Motor (460 Volt)

Resulting Voltages:

Percent of ESF System Points Voltages Nominal Bus Voltage Diesel Generator 6627 92.04 7200 Volt Bus 1DA 6618 91.92 460 Volt SWBP Pump 415 90.21 RN 01-113 of motor nominal rating 480 Volt Bus 1DA1 423 88.12 480 Volt Bus 1DA2 431 89.79 480 Volt MCC 1DA2Z 428 89.16 7200 Volt Bus 1EA 6612 91.83 480 Volt MCC 1EA1X 438 91.25 8E-5 Reformatted October 2014

APPENDIX 8F STARTING SEQUENCE OF ESF EQUIPMENT FOLLOWING AN ACCIDENT COINCIDENT WITH A DEGRADED VOLTAGE CONDITION 8F.1 INTRODUCTION The following study identifies the timed sequence of starting the ESF system equipment for an accident coincident with degraded voltage on the offsite power system. The accidents considered are (1) Loss of Coolant Accident (LOCA) and (2) Main Steam Line Break (MSLB). The study compares the equipment starting times during accident conditions, with a degraded voltage to the starting times assumed in the accident analyses with total loss of voltage. See Tables 8F-1 and 2.

8F.2 DISCUSSION During these two accident scenarios, the diesel generator will start when safety injection is initiated at time zero. A maximum of 10 seconds is then required for the generator to reach the speed and voltage necessary to connect to the ESF buses.

The degraded voltage relays are set to actuate at 91.34% of nominal voltage. If the voltage drops below 80% of nominal, the undervoltage relays will actuate. A time delay of 3 seconds is provided before the degraded voltage relays signal a start to the diesel to allow for voltage dips caused by a large motor starting. However, it should be noted that for these accidents the diesel was started at time zero by safety injection; therefore the signal to start the diesel generated by the degraded voltage relay is duplicative. If the degraded voltage condition persists for 4 more seconds (now a total of 7 seconds),

the 7.2 kV ESF buses are cleared. An additional time delay of 3 seconds is then provided to allow residual motor voltage to decay.

8F.3 CONCLUSION Under the accidents discussed here, a maximum of 10 seconds is required before the diesel generator can be connected to the ESF buses. However, if there is no accident and a degraded voltage condition exists, a maximum of 13 seconds would be required before the diesel is connected.

8F-1 AMENDMENT 98-01 APRIL 1998

TABLE 8F-1 DEGRADED GRID VOLTAGE COINCIDENT WITH LOCA TIME (SECONDS) DESCRIPTION OF EVENT 0 Degraded voltage condition on 7.2 kV ESF Buses Loss of Coolant Accident (SI Signal - Start Diesel Generator signal).

3 Degraded voltage detection signal.

7 Clear 7.2 kV ESF bus (Trip incoming and feeder breakers).

10 Close Diesel Generator breaker.

Start load block #1 (Start SI/Charging Pump, Start opening valves).

12 SI/Charging Pump at full speed Note 1 (~2 sec starting time). 98-01 15 Start RHR Pump.

19 RHR Pump at full speed Note 1 (~4 sec starting time). 98-01 20 Start SW Pump.

Start Chilled Water Pump.

00-01 24.5 SW Pump at full speed Note 2 (~4.5 sec starting time). 98-01 25 Start Component Cooling Pump.

Component Cooling Pump at full speed

(~4 sec starting time).

27 Safety Injection related valves at their final position Note 1 (27 sec. includes EDG start time, valve stroke time, and 00-01 signal processing time).

30 Start Emergency Feedwater Pump.

35 Start Reactor Building Cooling Units.

Start Fuel Handling Building Exhaust Fan.

8F-2 Reformatted Per Amendment 00-01

TABLE 8F-1 (Continued)

DEGRADED GRID VOLTAGE COINCIDENT WITH LOCA TIME (SECONDS) DESCRIPTION OF EVENT 40 Start SW Booster Pump.

42 Emergency Feedwater Pump at Full Speed.

(~12 sec starting time).

43 Reactor Building Cooling Units at full speed and air flow Note 4 has reached operating values 98-01 (8 sec delay from time of starting the fans to the time of having reached operating values of air flow per FSAR, Section 6.2.2.2.2.2).

45 Start HVAC Chiller.

SW Booster Pump at full speed (5 sec starting time per FSAR, Section 6.2.2.2.2.2).

NOTES:

1.) See FSAR Table 15.4-1. 98-01 2.) Critical case is the requirement to provide cooling water to the Diesel Generator within 1 minute from the time of starting.

3.) See FSAR, Section 15.4.2.2.2.1.

98-01 4.) See FSAR, Section 6.2.1.3.4.3.

8F-3 Reformatted Per Amendment 00-01

TABLE 8F-2 DEGRADED GRID VOLTAGE COINCIDENT WITH MSLB TIME (SECONDS) DESCRIPTION OF EVENT 0 Degraded voltage condition on 7.2 kV ESF Bus on Main Steam Line Break Accident (SI Signal - Start Diesel Generator signal).

3 Degraded voltage detection signal.

7 Clear 7.2 kV ESF bus (Trip incoming and feeder breakers).

10 Close Diesel Generator breaker.

Start load block #1 (Start SI/Charging Pump, Start opening valves).

12 SI/Charging Pump at full speed Note 1 (~2 sec starting time). 98-01 15 Start RHR Pump.

19 RHR Pump at full speed Note 1 (~4 sec starting time). 98-01 20 Start SW Pump.

Start Chilled Water Pump.

00-01 24.5 SW Pump at full speed Note 2 (~4.5 sec starting time). 98-01 25 Start Component Cooling Pump.

27 Safety Injection related valves at their final position Note 1 (27 sec. includes EDG start time, valve stroke time, and 00-01 signal processing time).

29 Component Cooling Pump at full speed

(~4 sec starting time).

30 Start Emergency Feedwater Pump.

35 Start Reactor Building Cooling Units.

Start Fuel Handling Building Exhaust Fan.

8F-4 Reformatted Per Amendment 00-01

TABLE 8F-2 (Continued)

DEGRADED GRID VOLTAGE COINCIDENT WITH MSLB 00-01 TIME (SECONDS) DESCRIPTION OF EVENT 40 Start SW Booster Pump.

42 Emergency Feedwater Pump at Full Speed.

(60) Note 3 (~12 sec starting time). 00-01 43 Reactor Building Cooling Units at full speed and air flow Note 4 has reached operating values 98-01 (8 sec delay from time of starting the fans to the time of having reached operating values of air flow per FSAR, Section 6.2.2.2.2.2).

45 Start HVAC Chiller.

SW Booster Pump at full speed (5 sec starting time per FSAR, Section 6.2.2.2.2.2).

NOTES:

1.) See FSAR Section 15.4.2.1.2.1. 98-01 2.) Critical case is the requirement to provide cooling water to the Diesel Generator within 1 minute from the time of starting.

3.) See FSAR, Section 15.4.2.2.2.1.

98-01 4.) See FSAR, Section 6.2.1.3.4.3.

8F-5 Reformatted Per Amendment 00-01

APPENDIX 8G ELECTRICAL CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTION DEVICES The following drawings identify overcurrent protection devices required to protect containment penetration assembly conductors in accordance with the requirements of Regulatory Guide 1.63. Regulatory Guide 1.63 is discussed in further detail in Appendix 3A.

8G-1 AMENDMENT 97-01 AUGUST 1997

FSAR FIGURE REFERENCE FIGURE 8G-1, Sheet 1 DRAWING E-224-532

FSAR FIGURE REFERENCE FIGURE 8G-2, Sheet 2 DRAWING E-224-532

FSAR FIGURE REFERENCE FIGURE 8G-3, Sheet 3 DRAWING E-224-532

FSAR FIGURE REFERENCE FIGURE 8G-4, Sheet 4 DRAWING E-224-532

FSAR FIGURE REFERENCE FIGURE 8G-5, Sheet 5 DRAWING E-224-532

FSAR FIGURE REFERENCE FIGURE 8G-6, Sheet 6 DRAWING E-224-532

FSAR FIGURE REFERENCE FIGURE 8G-7, Sheet 7 DRAWING E-224-532

FSAR FIGURE REFERENCE FIGURE 8G-8, Sheet 8 DRAWING E-224-532

FSAR FIGURE REFERENCE FIGURE 8G-9, Sheet 9 DRAWING E-224-532

FSAR FIGURE REFERENCE FIGURE 8G-10, Sheet 10 DRAWING E-224-532