AP1000 European 21. Construction Verification Process Design Control Document

Similar documents
AP1000 European 21. Construction Verification Process Design Control Document

AP1000 European 16. Technical Specifications Design Control Document

A. the temperature of the steam at the turbine exhaust increases. B. additional moisture is removed from the steam entering the turbine.

Overall nuclear power plant thermal efficiency will decrease if... A. the temperature of the steam at the turbine exhaust increases.

NUCLEAR TRAINING CENTRE COURSE 134 FOR ONTARIO HYDRO USE ONLY

AP1000 European 7. Instrumentation and Controls Design Control Document

AP1000 European 15. Accident Analysis Design Control Document

AP1000 European 9. Auxiliary Systems Design Control Document

Combined Cycle Power

TOPIC: KNOWLEDGE: K1.01 [2.5/2.5]

NSSS Design (Ex: PWR) Reactor Coolant System (RCS)

C. heating turbine exhaust steam above its saturation temperature. D. cooling turbine exhaust steam below its saturation temperature.

Technology Options for Existing Coal Units

DISTRIBUTION LIST. Preliminary Safety Report Chapter 11 Steam and Power Conversion System UK HPR1000 GDA. GNS Executive.

STEAM TURBINE-GENERATOR & AUXILLIARY SYSTEMS Presentation by: RANA NASIR ALI General Manager, Power Plants Projects, at PITCO November 02, 2017

Steam Cycle Chemistry in Air-Cooled Condensers. NV Energy ACC User s Group * November 12-13, 2009 Andrew Howell * Xcel Energy

CANDU Safety #6 - Heat Removal Dr. V.G. Snell Director Safety & Licensing

APR1400 Feedwater System Hydraulic Analysis using AFT Fathom TM

CHAPTER 51 MACHINIST'S MATE (MM) NAVPERS F CH-70

Shutdown and Cooldown of SEE-THRU Nuclear Power Plant for Student Performance. MP-SEE-THRU-02 Rev. 004

PMAX Cycle Isolation Module Greg Alder

NPP Simulators Workshop for Education - Passive PWR NPP & Simulator Overview

PI Heat and Thermodynamics - Course PI 25 CRITERION TEST. of each of the following a. it

AP1000 European 6. Engineered Safety Features Design Control Document

UK ABWR Generic Design Assessment Generic PCSR Chapter 17 : Steam and Power Conversion Systems

PSA ANALYSIS FOCUSED ON MOCHOVCE NPP SAFETY MEASURES EVALUATION FROM OPERATIONAL SAFETY POINT OF VIEW

AP1000 European 1. Introduction and General Description of the Plant Design Control Document

CANDU Fundamentals. Table of Contents

Modeling Techniques for Increased Accuracy

AP1000 European 15. Accident Analyses Design Control Document

3. Design of Structures, Components, AP1000 European

Fatigue Monitoring for Demonstrating

Lesson 10: Overall Unit Control Module 1: Boiler Pressure Control

PSA Michael Powell, Roy Linthicum, Richard Haessler, Jeffrey Taylor

DETERMINING CYCLE LEAKAGE MEGAWATT EFFECTS USING PMAX & PEPSE

Boiler Energy Efficiency & Overview of Economizers

Newman Station Units 1, 2, and 4 Condition Assessment Report. El Paso Electric, Inc. El Paso, TX

Work Exercises and Case Studies to Write Safety Evaluation Report

Prohibition of Boiler Feed Water Pump Failure in Power Plant

Equipment Design. Detailed Plant Conceptual Design. Version 9.0

Joint ICTP-IAEA Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety. Trieste,12-23 October 2015

Cycle Isolation Prioritization and Organization

Application for Permission to Extend the Operating Period and Application for Approval of Construction Plans of Unit 3 at Mihama Nuclear Power Station

WESTENGHOUSE AP600 ADVANCED NUCLEAR PLANT DESIGN

Chapter Two. The Rankine cycle. Prepared by Dr. Shatha Ammourah

Equipment Design. Detailed Plant Conceptual Design. Version 7.0

Westinghouse Small Modular Reactor Development Overview

SMR/1848-T21b. Course on Natural Circulation Phenomena and Modelling in Water-Cooled Nuclear Reactors June 2007

Power Optimization Center Leveraging plant process data for advanced analytical diagnostics. June 16, 2016

A Brief Overview of the APR1400 Commissioning. KHNP Sep. 13, 2017 Sang Won Lee

Status report Economic Simplified Boiling Water Reactor (ESBWR)

Pressurized Water Reactor Systems

5. Steam Turbine Performance

AP1000 European 17. Quality Assurance Design Control Document

INVESTIGATION OF CRITICAL SAFETY FUNCTION INTEGRITY IN CASE OF STEAM LINE BREAK ACCIDENT FOR VVER 1000/V320

Lecture 7 Heat Removal &

Power Engineering Course Acceptance Criteria AB-533

AP1000 The PWR Revisited

Nuclear Service Valves

ABSTRACT DESING AND IMPLEMENTATION OF FORCED COOLING TOWERS FOR LOVIISA NPP SAFETY- AND RESIDUAL HEAT REMOVAL (RHR) COOLING CIRCUITS

The cause of RCIC shutdown in Unit 3

The Westinghouse AP1000 Advanced Nuclear Plant Plant description

Metropolitan Community College COURSE OUTLINE FORM LEC: 4.5 LAB:

CANDU Safety #14 - Loss of Heat Sink Dr. V.G. Snell Director Safety & Licensing

CCI. Aftermarket. Services

Design of Traditional and Advanced CANDU Plants. Artur J. Faya Systems Engineering Division November 2003

Consider a simple ideal Rankine cycle with fixed turbine inlet conditions. What is the effect of lowering the condenser pressure on

MARAMA Webinar August 7, Angelos Kokkinos Chief Technology Officer Babcock Power, Inc.

Module 05 WWER/ VVER (Russian designed Pressurized Water Reactors)

AP1000 European 11. Radioactive Waste Management Design Control Document

B/B-UFSAR FEEDWATER SYSTEM TO SECTION OF THE STANDARD REVIEW PLANS AND BRANCH TECHNICAL POSITION ASB 10-1

BESTPRACTICES STEAM PROGRAM STEAM TOOLS SPECIALIST QUALIFICATION TRAINING PREREQUISITE STUDY GUIDE (1/12/2004)

ENERGY RECOVERY IMPROVEMENT USING ORGANIC RANKINE CYCLE AT COVANTA S HAVERHILL FACILITY

Main Steam & T/G Systems, Safety

NOTICE CONCERNING COPYRIGHT RESTRICTIONS

TCN 02, Dated: WITH REFERENCE TO ABOVE FOLLOWING CHANGES MAY PLEASE BE NOTED AND COMPLIED WHILE SUBMITTING THE OFFER FOR THE SUBJECT JOB:

Secondary Systems: Steam System

CHAPTER 7: OVERALL UNIT CONTROL MODULE 3: UNIT STARTUP

Power Uprate Studies for Nuclear Power Plants Using PEPSE - Lessons Learned Update 2

4th Class Power Engineering (PEN) Curriculum Mapping

SIMPACK - MODEL DEVELOPMENT PACKAGE FOR POWER PLANTS

Welcome to. Kendal Power Station

DYNAMICS OF BASELOAD LIQUEFIED NATURAL GAS PLANTS ADVANCED MODELLING AND CONTROL STRATEGIES

Heat exchanger equipment of TPPs & NPPs

Combined Cycle Power Plants. Combined Cycle Power Plant Overview (Single- and Multi-Shaft) Training Module. ALSTOM (Switzerland) Ltd )*+,

Steam Cooling Systems and Hybrid Cooling. Andrew G. Howell Xcel Energy

Feedwater Heaters (FWH)

Severe Accident Progression Without Operator Action

An Introduction to Central Heating Plant Planning

AP1000 European 9. Auxiliary Systems Design Control Document

BEST PRACTICES IN THERMAL POWER PLANT. Confederation of Indian Industry CII Godrej Green Business Centre, Hyderabad, India

Air Cooled Condenser Users Group: Corrosion Product Transport Monitoring

IAEA Training in level 1 PSA and PSA applications. Other PSA s. Low power and shutdown PSA

Maintenance Optimization: A Critical Aspect of the Equipment Reliability Program

Steve Connor. Technical Services Consultant

THERMAL POWER PLANT SIMULATOR TPP 200 LABORATORY EXERCISE TUTORIAL N4: INTRODUCTION TO THE HEAT PRODUCTION SYSTEM

The Locomotive. A Copper-Plated Thief: The Problem of Copper Deposits in Turbines

Front Range Power Plant: Air Cooled Condenser Tom Cook, PE Colorado Springs Utilities, Operating Engineering Group Air Cooled Condenser User Group:

Chapter Two { TC "Chapter Two " \l 1 } Detailed System Description

Thermodynamics: Homework A Set 6 Jennifer West (2004)

Transcription:

2.4 Steam and Power Conversion Systems 2.4.1 Main and Startup Feedwater System See Section 2.2.4 for information on the main feedwater system. Design Description The startup feedwater system supplies feedwater to the steam generators during plant startup, hot standby and shutdown conditions, and during transients in the event of main feedwater system unavailability. 1. The functional arrangement of the startup feedwater system is as described in the Design Description of this Section 2.4.1. 2. The FWS provides the following nonsafety-related functions: The FWS provides startup feedwater flow from the condensate storage tank (CST) to the steam generator system (SGS) for heat removal from the RCS. 3. Controls exist in the main control room (MCR) to cause the components identified in Table 2.4.1-1 to perform the listed function. 4. Displays of the parameters identified in Table 2.4.1-1 can be retrieved in the MCR. Inspections, Tests, Analyses, and Acceptance Criteria Table 2.4.1-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the FWS. EPS-GW-GL-700 21-301 Revision 1

Table 2.4.1-1 Equipment Name Tag No. Display Control Function Startup Feedwater Pump A (Motor) FWS-MP-03A Yes (Run Status) Startup Feedwater Pump B (Motor) FWS-MP-03B Yes (Run Status) Startup Feedwater Pump A Isolation Valve FWS-PL-V013A Yes (Valve Position) Startup Feedwater Pump B Isolation Valve FWS-PL-V013B Yes (Valve Position) Start Start Open Open EPS-GW-GL-700 21-302 Revision 1

Table 2.4.1-2 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 1. The functional arrangement of the startup feedwater system is as described in the Design Description of this Section 2.4.1. 2. The FWS provides startup feedwater flow from the CST to the SGS for heat removal from the RCS. 3. Controls exist in the MCR to cause the components identified in Table 2.4.1-1 to perform the listed function. 4. Displays of the parameters identified in Table 2.4.1-1 can be retrieved in the MCR. Inspection of the as-built system will be performed. Testing will be performed to confirm that each of the startup feedwater pumps can provide water from the CST to both steam generators. Testing will be performed on the components in Table 2.4.1-1 using controls in the MCR. Inspection will be performed for retrievability of parameters in the MCR. The as-built startup feedwater system conforms with the functional arrangement as described in the Design Description of this Section 2.4.1. Each FWS startup feedwater pump provides a flow rate greater than or equal to 260 gpm (59.05 m 3 /hr) to each steam generator system at a steam generator secondary side pressure of at least 1106 psia (7.626 MPa abs). Controls in the MCR operate to cause the components listed in Table 2.4.1-1 to perform the listed functions. The displays identified in Table 2.4.1-1 can be retrieved in the MCR. Table 2.4.1-3 Component Name Tag No. Component Location Startup Feedwater Pump A FWS-MP-03A Turbine Building Startup Feedwater Pump B FWS-MP-03B Turbine Building EPS-GW-GL-700 21-303 Revision 1

Figure 2.4.1-1 Main and Startup Feedwater System EPS-GW-GL-700 21-304 Revision 1

2.4.2 Main Turbine System Design Description The main turbine system (MTS) is designed for electric power production consistent with the capability of the reactor and the reactor coolant system. The component locations of the MTS are as shown in Table 2.4.2-2. 1. The functional arrangement of the MTS is as described in the Design Description of this Section 2.4.2. 2. a) Controls exist in the MCR to trip the main turbine-generator. b) The main turbine-generator trips after receiving a signal from the PMS. c) The main turbine-generator trips after receiving a signal from the DAS. 3. The overspeed trips for the AP1000 turbine are set for 110% and 111% (±1% each). Each trip is initiated electrically in separate systems. The trip signals from the two turbine electrical overspeed protection trip systems within the PLS are isolated from, and independent of, each other. Inspections, Tests, Analyses, and Acceptance Criteria Table 2.4.2-1 specifies the inspections, tests, analyses, and associated acceptance criteria for the MTS. Table 2.4.2-1 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Test, Analyses Acceptance Criteria 1. The functional arrangement of the MTS is as described in the Design Description of this Section 2.4.2. 2.a) Controls exist in the MCR to trip the main turbine-generator. 2.b) The main turbine-generator trips after receiving a signal from the PMS. 2.c) The main turbine-generator trips after receiving a signal from the DAS. Inspection of the as-built system will be performed. Testing will be performed on the main turbine-generator using controls in the MCR. Testing will be performed using real or simulated signals into the PMS. Testing will be performed using real or simulated signals into the DAS. The as-built MTS conforms with the functional arrangement as described in the Design Description of this Section 2.4.2. Controls in the MCR operate to trip the main turbine-generator. The main turbine-generator trips after receiving a signal from the PMS. The main turbine-generator trips after receiving a signal from the DAS. EPS-GW-GL-700 21-305 Revision 1

Table 2.4.2-1 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Test, Analyses Acceptance Criteria 3. The trip signals from the two turbine electrical overspeed protection trip systems within the PLS are isolated from, and independent of, each other. i) The system design will be reviewed. ii) Testing of the as-built system will be performed using simulated signals from the turbine speed sensors. iii) Inspection will be performed for the existence of a report verifying that the two turbine electrical overspeed protection systems have diverse hardware and software/firmware. i) The system design review shows that the trip signals of the two electrical overspeed protection trip systems are isolated from, and independent of, each other. ii) The main turbine-generator trips after overspeed signals are received from the speed sensors of the 110% emergency electrical overspeed trip system, and the main turbinegenerator trips after overspeed signals are received from the speed sensors of the 111% backup electrical overspeed trip system. iii) A report exists and concludes that the two electrical overspeed protection systems within the PLS have diverse hardware and software/firmware. EPS-GW-GL-700 21-306 Revision 1

Table 2.4.2-2 Component Name Tag No. Component Location HP Turbine MTS-MG-01 Turbine Building LP Turbine A MTS-MG-02A Turbine Building LP Turbine B MTS-MG-02B Turbine Building LP Turbine C MTS-MG-02C Turbine Building Gland Steam Condenser GSS-ME-01 Turbine Building Gland Condenser Vapor Exhauster 1A GSS-MA-01A Turbine Building Gland Condenser Vapor Exhauster 1B GSS-MA-01B Turbine Building Electrical Overspeed Trip Device -- Turbine Building Emergency Electrical Overspeed Trip Device -- Turbine Building EPS-GW-GL-700 21-307 Revision 1

2.4.3 Main Steam System No entry. Covered in Section 2.2.4, Steam Generator System. EPS-GW-GL-700 21-308 Revision 1

2.4.4 Steam Generator Blowdown System No entry. Containment isolation function covered in Section 2.2.1, Containment System and 2.2.4, Steam Generator System. No entry. Steam generator isolation function covered in Section 2.2.4, Steam Generator System. EPS-GW-GL-700 21-309 Revision 1

2.4.5 Condenser Air Removal System No entry. Covered in Section 3.5, Radiation Monitoring. (Note: Monitor is TDS-RE001.) EPS-GW-GL-700 21-310 Revision 1

2.4.6 Condensate System Design Description The condensate system (CDS) provides feedwater at the required temperature, pressure, and flow rate to the deaerator. Condensate is pumped from the main condenser hotwell by the condensate pumps and passes through the low-pressure feedwater heaters to the deaerator. The circulating water system (CWS) removes heat from the condenser and is site specific starting from the interface at the locations where the CWS piping enters and exits the turbine building. The CDS operates during plant startup and power operations (full and part loads). The component locations of the CDS are as shown in Table 2.4.6-3. 1. The functional arrangement of the CDS is as described in the Design Description of this Section 2.4.6. 2. Displays of the parameters identified in Table 2.4.6-1 can be retrieved in the main control room (MCR). Inspections, Tests, Analyses, and Acceptance Criteria Table 2.4.6-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the CDS. Table 2.4.6-1 Equipment Name Tag No. Display Condenser Backpressure CDS-056A Yes Condenser Backpressure CDS-056B Yes Condenser Backpressure CDS-056C Yes Table 2.4.6-2 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 1. The functional arrangement of the CDS is as described in the Design Description of this Section 2.4.6. 2. Displays of the parameters identified in Table 2.4.6-1 can be retrieved in the MCR. Inspection of the as-built system will be performed. Inspection will be performed for retrievability of the parameters in the MCR. The as-built CDS conforms with the functional arrangement as described in the Design Description of Section 2.4.6. The displays identified in Table 2.4.6-1 can be retrieved in the MCR. EPS-GW-GL-700 21-311 Revision 1

Table 2.4.6-3 Component Name Low Pressure Feedwater Heaters Deaerator Feedwater Heater and Storage Tank Main Condenser Shell A Main Condenser Shell B Main Condenser Shell C Condensate Pump A Condensate Pump B Condensate Pump C Component Location Turbine Building Turbine Building Turbine Building Turbine Building Turbine Building Turbine Building Turbine Building Turbine Building EPS-GW-GL-700 21-312 Revision 1

2.4.7 Circulating Water System No entry for this system. EPS-GW-GL-700 21-313 Revision 1

2.4.8 Auxiliary Steam Supply System No entry for this system. EPS-GW-GL-700 21-314 Revision 1

2.4.9 Condenser Tube Cleaning System No entry for this system. EPS-GW-GL-700 21-315 Revision 1

2.4.10 Turbine Island Chemical Feed System No entry for this system. EPS-GW-GL-700 21-316 Revision 1

2.4.11 Condensate Polishing System No entry for this system. EPS-GW-GL-700 21-317 Revision 1

2.4.12 Gland Seal System No entry. Covered in Section 2.4.2, Main Turbine System. EPS-GW-GL-700 21-318 Revision 1

2.4.13 Generator Hydrogen and CO 2 System No entry for this system. EPS-GW-GL-700 21-319 Revision 1

2.4.14 Heater Drain System No entry for this system. EPS-GW-GL-700 21-320 Revision 1

2.4.15 Hydrogen Seal Oil System No entry for this system. EPS-GW-GL-700 21-321 Revision 1

2.4.16 Main Turbine and Generator Lube Oil System No entry for this system. EPS-GW-GL-700 21-322 Revision 1