ML17157B682

Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 8, Electric Power

ML17157B682
Person / Time
Site:	Duane Arnold
Issue date:	05/22/2017
From:	NextEra Energy Duane Arnold
To:	Office of Nuclear Reactor Regulation
Shared Package
ML17157B650	List: ML17157B649 ML17157B674 ML17157B675 ML17157B677 ML17157B678 ML17157B679 ML17157B680 ML17157B681 ML17157B682 ML17157B683 ML17157B684 ML17157B685 ML17157B686 ML17157B687 ML17157B688 ML17157B689 ML17157B690 ML17157B691 ML17157B692 NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 4, Reactor NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 8, Electric Power NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Table of Contents NG-17-0111, Redacted - Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics
References
NG-17-0111
Download: ML17157B682 (40)

Text

UFSAR/DAEC-1 Chapter 8: ELECTRIC POWER 8- Revision 23 - 5/15 i TABLE OF CONTENTS Section Title Page

8.1 INTRODUCTION

................................................................................................. 8.1-1

8.2 OFFSITE

POWER SYSTEM ................................................................................ 8.2-1

8.

2.1 DESCRIPTION

........................................................................................................ 8.2-1 8.2.1.1 POWER GENERATION OBJECTIVE ...................................................................... 8.2-1 8.2.1.2 POWER GENERATION D ESIGN B ASES ................................................................ 8.2-1 8.2.1.3 SYSTEM DESCRIPTION ....................................................................................... 8.2-1 8.2.1.3.1 DAEC SWITCHYARD ...................................................................................... 8.2-1 8.2.1.3.2 SWITCHYARD PROTECTIVE B REAKERS AND R ELAYING .................................. 8.2-2 8.2.1.3.3 DAEC T RANSMISSION L INES ......................................................................... 8.2-2 8.2.2 A NALYSIS ............................................................................................................. 8.2-3 8.2.2.1 GENERAL ........................................................................................................... 8.2-3 8.2.2.2 O FFSITE POWER G RID V OLTAGE A NALYSIS ...................................................... 8.2-3 8.2.2.2.1 I NTRODUCTION ............................................................................................... 8.2-3 8.2.2.2.2 G RID S TABILITY AND RELIABILITY ANALYSIS ................................................ 8.2-4 REFERENCES FOR SECTION 8.2 ............................................................................. 8.2-6

8.3 ONSITE

POWER SYSTEMS ................................................................................ 8.3-1 8.3.1 AC POWER SYSTEMS............................................................................................ 8.3-1 8.3.1.1 A UXILIARY AC POWER S YSTEM ....................................................................... 8.3-1 8.3.1.1.1 S AFETY OBJECTIVE ........................................................................................ 8.3-1 8.3.1.1.2 S AFETY D ESIGN B ASES .................................................................................. 8.3-1 8.3.1.1.3 POWER GENERATION OBJECTIVE ................................................................... 8.3-2 8.3.1.1.4 POWER GENERATION D ESIGN B ASES ............................................................. 8.3-2 8.3.1.

1.5 DESCRIPTION

.................................................................................................. 8.3-2 8.3.1.1.6 A NALYSIS ....................................................................................................... 8.3-5 8.3.1.2 STANDBY AC POWER S YSTEM ........................................................................ 8.3-11 8.3.1.2.1 S AFETY OBJECTIVE ...................................................................................... 8.3-11 8.3.1.2.2 S AFETY D ESIGN B ASES ................................................................................ 8.3-11 8.3.1.2.3 D ESCRIPTION OF S TANDBY AC POWER SYSTEMS ......................................... 8.3-11 8.3.1.3 A NALYSIS ........................................................................................................ 8.3-13 8.3.1.4 I NSPECTION AND T ESTING ............................................................................... 8.3-15 8.3.2 DC POWER SYSTEMS.......................................................................................... 8.3-16 8.3.

2.1 DESCRIPTION

................................................................................................... 8.3-16 8.3.2.1.1 S AFETY OBJECTIVE ...................................................................................... 8.3-16 8.3.2.1.2 S AFETY D ESIGN B ASES ................................................................................ 8.3-16 8.3.2.1.3 D ESCRIPTION OF DC POWER SYSTEMS ......................................................... 8.3-16 8.3.2.1.3.1 250-V S YSTEM .......................................................................................... 8.3-16 8.3.2.1.3.2 125-V S YSTEM .......................................................................................... 8.3-16 UFSAR/DAEC-1 Chapter 8: ELECTRIC POWER TABLE OF CONTENTS (Continued)

Section Title Page 8- Revision 23 - 5/15 ii 8.3.2.1.3.3 24-V S YSTEM ............................................................................................ 8.3-17 8.3.2.2 A NALYSIS ........................................................................................................ 8.3-17 8.3.2.2.1 GENERAL ...................................................................................................... 8.3-17 8.3.2.2.2 L OSS OF 250-V BATTERY ............................................................................. 8.3-18 8.3.2.2.3 L OSS OF 125-V BATTERY ............................................................................. 8.3-18 8.3.2.2.4 L OSS OF 24-V BATTERY ............................................................................... 8.3-18 8.3.2.3 I NSPECTION AND T ESTING ............................................................................... 8.3-18 8.3.3 F IRE PROTECTION FOR CABLE SYSTEMS ............................................................ 8.3-18 REFERENCES FOR SECTION 8.3 ..........................................................................

8.3-20 UFSAR/DAEC-1 Chapter 8: ELECTRIC POWER 8- Revision 23 - 5/15 iii LIST OF TABLES

Tables Title Page 8.3-1 SINGLE DIESL-GENERATOR LOADING SEQUENCE AND RESPONSE -

LOSS-OF-COOLANT ACCIDENT PLUS LOSS OF OFFSITE POWER ...... T8.3-1

UFSAR/DAEC-1 Chapter 8: ELECTRIC POWER 8- Revision 23 - 5/15 iv LIST OF FIGURES Figures Title

8.2-1 DAEC Switchyard Schematic

8.3-1 Sheet 1 Single Line Diagram Station Connections

8.3-1 Sheet 2 Single Line Diagram Station Connections

8.3-2 Sheet 1 Uninterruptible AC, RPS AC and Instrument AC Distribution

8.3-2 Sheet 2 Uninterruptible AC, RPS AC and Instrument AC Distribution

8.3-3 deleted

8.3-4 deleted

8.3-5 deleted

8.3-6 Single Line Meter and Relay Diagram 125 VDC

8.3-7 Single Line Meter and Relay Diagram 250 VDC System

UFSAR/DAEC-1 8.1-1 Revision 12 - 10/95 Chapter 8 ELECTRIC POWER

8.1 INTRODUCTION

The preferred electrical power system of the Duane Arnold Energy Center (DAEC) are designed to provide redundant, di verse, and dependable power sources that are physically independent so that any failu re affecting one source of supply will not propagate to alternative sources. The preferred power system provides adequate power for startup, operation, shutdown, and other plant requirements that are important to safety.

In the event of a total loss of power from the preferred source, auxiliary power will be supplied from diesel generators (standby AC power system) on the site. These power sources are physically and electrically independent from any normally connected power system. Each power source, up to the point of its connection to the auxiliary power bus, is capable of complete and rapid electrical isolation from any other source. Loads important to plant safety are divided and connected to separate and redundant switchgear sections and means are provided for rapid detection and isolation of system faults. Electrically and physically independent battery systems serve as reliable sources of control power and perform other required tasks when AC power is not available.

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UFSAR/DAEC - 1 T8.3-1 Revision 21 - 5/11 Table 8.3-1 (Page 1 of 2)

SINGLE DIESEL-GENERATOR LOADING SEQUENCE AND RESPONSE -

LOSS-OF-COOLANT ACCIDENT PLUS LOSS OF OFFSITE POWER a Elapsed Time from Initiation of

Event Load Increment (kW)e Total Load (kW)d Voltage

(% of rated) Recovery Time to 90%

Rated Voltage (sec) Frequency

(% of rated) Recovery Time to 98% Rated Frequency(sec)

Description 0 SEC LOCA ACCIDENT 3 SEC LOW REACTOR WATER LEVEL OR HIGH DRYWELL

PRESSURE SIGNAL, EDG

START SIGNAL 13 SEC 100 100 EDG CLOSES TO BUS, SIGNAL REACTOR RECIRC AND CONTAINMENT

ISOLATION, LPCI AND

CORE SPRAY INJECT

VALVES OPEN 13.0 MCC LOADS 135.0 MCC LOADS SYSTEM LOSSES AND

CHILLER AUX LOADS.

345.1 MCC LOADS &

114.0 MCC LOADS 104.0 711.1 73 1.2 96.7 3.07 RIVER WATER SUPPLY PUMP START b 18 SEC 612 1323.1 80 1.3 97.2 3.91 CORE SPRAY PUMP START 21 SEC CORE SPRAY INJECT VALVE OPEN UFSAR/DAEC - 1 T8.3-2 Revision 21 - 5/11 Table 8.3-1 (Page 2 of 2)

SINGLE DIESEL-GENERATOR LOADING SEQUENCE AND RESPONSE - LOSS-OF-COOLANT ACCIDENT PLUS LOSS OF OFFSITE POWER a 23 SEC 496 1819.1 80 1.3 97.2 3.91 FIRST RHR (LPCI) PUMP START 28 SEC 496 2315.1 83 1.1 97.1 2.45 SECOND RHR (LPCI) PUMP START 31 SEC LPCI VALVES OPEN 43 SEC REACTOR RECIRC VALVES CLOSE, COMPLETION OF

LPCI SEQUENCE After 10 min c 66 2381.1 -- -- -- -- CONTROL BUILDING CHILLER START f -162 2219.1 -- -- -- -- MCC LOAD REDUCTION -496 1723.1 -- -- -- -- TRIP RHR PUMP 470 2193.1 -- -- -- -- RHR SERVICE WATER PUMP START 470 2663.1 RHR SERVIE WATER PUMP START NOTE: a See Section 15.3.1 for actual safety analysis assumptions.

b If the RWS pump selected for auto start was running prior to the LOOP, the selected RWS pump will trip and will restart 120 sec onds after the diesel generator output breaker closes.

c Additional loads may be a pplied at operator's discretion.

d Present loads are less than original design loads listed fo r all total loads. Thus the frequency and voltage responses sho uld be equal to or better than the original design responses listed.

e Original Design Loads f Original CB Chiller Start was shown at 73 seconds, which is incorrect. Corrected to After 10 minutes.