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ASME South African Workshop AP1000 Overview

Ralph Hill Consulting Engineer Westinghouse Nuclear Services

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AP1000 Design Overview · Introduction · AP1000 Design Overview · Overview of Reactor Pressure Vessel (RPV) Design Specification

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AP1000 Design Overview

· · · · · Background / Design Certification / Licensing / Overall Features Reactor Core and Vessel Design (core, control rods) Reactor Coolant System (2 loops, seal-less RCPs)* Passive Safety Systems (one-time valve actuation)* Non-Safety Defense-in-Depth Systems (previously safety systems) · I&C Systems (2 digital I&C w/data highway, AMSAC replacement)* · Miscellaneous Plant Information · AP1000 Classification System Overview

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AP1000 Investment in Technology

Extensive Testing of Passive Safety Systems Simplified Passive Safety Systems Proven Advanced Design Features

US Licensing Approval

Modular Construction

REACTOR VESSEL

PRA and Severe Accident Mitigation Features

STEAM VENTS TYPICAL 4 PLACES

REACTOR VESSEL SUPPORT STEEL

CORE

SHIELD WALL

INSULATION

WATER INLET

Reduced Components and Commodities

Short Construction Schedule

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AP1000 - Key Design Features

Integrated Power Plant Design (NSSS and BOP designs) ­ 60 yr plant life Proven Power-Producing Components (reactor, fuel, etc.) Simplified RCS ­ 2 loops (SGs) with 4 seal-less reactor coolant pumps Simplified Passive Safety Systems Simplified Non-Safety, Defense-in-Depth (DID) Systems Microprocessor, Digital-Technology-Based I&C Advanced / Compact Control Room / Electronic Operator Interface Optimized Plant Arrangement - Construction, Operation, Maintenance, Safety, Cost Extensive Use of Modular Construction ­ Shorter Construction Schedule

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AP1000 Simplifications Drive Economics and Construction Schedule

50% Fewer Valves

35% Fewer Pumps

80% Less Pipe

45% Less Seismic Building Volume

85% Less Cable

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AP1000 is Smaller and Dramatically Simpler than Evolutionary Plants

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AP1000 Design Overview

For the Power Generation Function, AP1000 is a typical Westinghouse PWR with advances in materials and components - Fuel - Reactor Coolant Loop - Pumps - Plant Controls Reactor Safety Functions are achieved without using any safety-related AC power (accident mitigation without diesel generator operation) - Battery Powered Valve Actuation - Natural Circulation - Compressed gasses (nitrogen, air) Passive safety systems actuated by simple, reliable valve position changes. System performance was proven by extensive testing approved by the NRC - Condensation - Evaporation - Reactor Vessel - Steam Generators - Turbine

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AP1000 Design Overview

Typical PWR safety active systems and safety support systems exist as simplified non-safety systems located in non-safety building structures

- Diesels - Chilled Water - Component Cooling - Spent Fuel Cooling - Diesel Support Systems (Fuel Oil, HVAC) - Instrument Air - Hot Water (heating) - Essential Service Water - Residual Heat Removal - Startup Feedwater (replaces Auxiliary Feedwater)

There are no safety-related pumps in the plant and no safety-related ventilation systems. The non-safety active systems are credited in the PRA, but are not required for reactor safety and are not required to achieve NRC required CDF Severe accident scenarios are mitigated by In-Vessel Retention (IVR) of the melted fuel (the core is retained in a cooled reactor vessel)

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Proven AP1000 Major Components

Fuel, Internals, Reactor Vessel

­ ­ ­ ­ 14-foot XL core (Doel / Tihange / S. Texas) Gray rods / rapid power reduction system 3-loop RV w/ CE shroud / 18-month cycle No bottom-mounted instrumentation

Steam Generators (inconel 690 TT tubes)

­ Similar to large W/CE SGs in operation ­ System 80, ANO RSG ­ 1200 MWe / 2 SGs instead of 4 SGs Seal-less pumps, no shaft seals, intermittent CVS operation ­ Early commercial reactors (Shippingport, Yankee Rowe) / extensive experience Variable speed (start at ~20% speed) 2 RCPs per SG w/ no cross-over leg About 50% larger than operating plants

Reactor Coolant Pumps

­

­ ­ ­

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Pressurizer Simplified Main Loop

AP1000 Reactor Coolant Pump

Pump Casing Pump Diffuser Pump Impeller Thermal Barrier Flywheel Motor Rotor Motor Stator Radial Bearings Thrust Bearings

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Passive Safety Features

Passive Safety Equipment Design ­ Reliable, experienced based, nuclear grade equipment ­ Design to ASME, Seismic I, full fire / flood / wind protection ­ Availability controlled by Technical Specification with shutdown requirements ­ Technical Specification surveillance requirements reference Inservice Testing program ­ Reliability controlled by Inservice Inspection, Inservice Testing, and maintenance programs

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Passive Safety Features

Residual Heat Removal ­ Natural circulation heat exchanger connected to reactor coolant system Safety Injection ­ Natural circulation / gravity drain core makeup tanks (at reactor coolant system pressure) ­ Nitrogen pressurized accumulators (700 psig / ~50 Kg/cm)

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Passive Safety Features

Containment Isolation ­ Prevents or limits escape of fission products that may result from postulated accidents. Gravity drain refueling water storage tank (at containment pressure) ­ Automatic transition to gravity recirculation (at containment pressure) ­ Automatic depressurization valves (6 from pressurizer / 4 from hot legs)

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Passive Safety Features

Containment Cooling ­ Natural circulation of air / evaporation of water on outside surface of steel containment vessel Radiation Removal from Containment Atmosphere ­ Natural circulation / removal mechanisms Main Control Room Habitability ­ Compressed air pressurization of main control room envelope

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AP1000 BOP Design

· Single Turbine-Generator

· 1 - HP, 3 - LPs · 2 Moisture-Separator Reheaters

· 3 Condensers and 3 (50%) Condensate Pumps

· 4 LP Feedwater Heating Stages

· 1 De-aerator / Storage Tank

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W e s t in g h o u s e P r o p r ie t a r y C l a s s 2 C O p e ra to r C o n tro l and M o n ito rin g L e v e l

M a in C o n t ro l Room

T ra d itio n a l S ta n d u p P a n e ls

H y b id C o n t r o l D e s k s O p e ra to r W o r k s ta tio n s

S o ftw a r e D e v e lo p m e n t Log S erve r

D a t a D i s p la y a n d P ro c e s s in g S y s te m ( D D S )

C o m p u ta tio n / A la r m S e rv e rs

H is t o r ic a l and R e tr ie v a l

R e m o te S h u td o w n P a n e l

D is t r i b u t e d P l a n t N e t w o r k M o n it o r B u s

D a t a li n k In t e r f a c e RPI R IO T u r b in e Is la n d C o n tro l S y s te m

C o m m u n ic a t io n Level

T o M C R /R Ö P In d i c a t o r s

S a f e t y N e t In f o B u s

G atew a ys ( T y p i c a l) T o M C R /R Ö P In d i c a t o r s

L o g ic B u s

L o g ic B u s

In te rfa c e to P la n t I n f o r m a t io n S y s te m

P la n t M o n it o r in g S y s te m s

Rod C o n tro l S y s te m

In c o r e S y s te m ( e x is t i n g )

IV

T r a in A PAM S C o n tro l L o g ic S y s te m NSSS C o n tro l S y s te m T o N IS S y s te m I/ O C a b in e t P la n t C o m p o n e n ts N IS I/ O C a b in e t MCC an d S w it c h g e a r

D iv e rs e A c t u a t io n S y s te m (D A S )

In fo

In t e g r a t e d C o n tro l L o g ic C a b in e ts (IL C ) ESFAC In f o In t e g r a t e d C o n tro l L o g ic C a b in e ts (IL C ) T r a in B PAM S D iv e rs e A c t u a t io n S y s te m (D A S )

P ro c e s s in g Level

I II II I

In t e g r a t e d P r o t e c t io n C a b in e ts E S F A C

S p e c ia l M o n ito ri n g S y s te m s

P la n t C o m p o n en ts

P la n t C o m p o n e n ts

M o t o rG e n e r a to r Set

P ro c e s s In t e r f a c e Level

P la n t C o n tr o l S y s te m (P C S )

R e a c t o r T r ip B r e a k e r s

P r o te c tio n a n d S a f e ty M o n ito rin g S y s te m (P M S )

N o n - 1 E F u n c t io n s

1 E F u n c tio n s

N o n - 1 E F u n c t io n s

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AP1000 Compact Control Room

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Advanced Control Room

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AP1000 Provides Safety Protection

U. S. NRC Requirements Current Plants US Utility Requirements

AP1000 Results

1 x 10-4

5 x 10-5

1 x 10-5

4 x 10-7

Core Damage Frequency per Year

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AP1000 General Arrangement

Maintenance / Inspection ­ Improved Larger containment diameter ­ Increased laydown area inside containment ­ Access platforms provided for equipment maintenance / inspection Improved Access to Containment ­ Equipment hatch(s) access from auxiliary building ­ Equipment hatches and personnel airlocks at both grade and operating deck levels Improved Separation ­ Radioactive vs nonradioactive ­ Fire areas, especially inside containment ­ Safety vs nonsafety

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CVS Equipment Module

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AP1000 Classification Overview

Safety and seismic classification of plant structures, systems, and components (SSCs)

­ Safety-related functions are protected during design basis events

­ Maintain reactor coolant pressure boundary integrity ­ Establish and maintain safe shutdown of the reactor ­ Prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to 10 CFR 100 limits

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AP1000 Seismic Classification

Safety-Related SSCs (Seismic C-I)

­ Withstand appropriate seismic loads and other applicable loads without loss of function AND protected from adjacent non-seismic structures

Nonsafety-Related SSCs (Seismic C-II)

­ Preclude nonsafety-related SSC structural failure or interaction with C-I SSCs which could unacceptably degrade safety-related structure SSC, or cause incapacitating injury to main control room occupants

Nonsafety-Related SSCs (Non-Seismic)

­ Non-seismic SSCs are those that are not classified C-I or C-II

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AP1000 Safety Classification

Conforms to 10 CFR 50.55a for the development of a Quality Group classification and the use of codes and standards Developed considering requirements and guidelines of:

­ ­ ­ ­ ­ ANSI N18.2 (Reference 1) ­ Safety Classification ANS 51.1 (Reference 2) ­ Safety Classification Regulatory Guide 1.26 ­ Quality Groups Regulatory Guide 1.97 ­ Instrumentation Requirements 10 CFR 21, Reporting of Defects and Noncompliance

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AP1000 Safety Classification

Safety-Related Classes A/B/C

­ Equivalent to ANS Safety Class 1/2/3 for mechanical equipment ­ Equivalent to Class 1E for electrical equipment ­ Seismic Class C-1

Class A (ANS Class 1)

­ Reactor coolant system pressure boundary ­ Includes isolation valves and mechanical supports ­ Provides highest integrity and lowest leakage probability

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AP1000 Safety Related SSCs

Class B (ANS Class 2) ­ Limits leakage of radioactive material from containment following a design basis accident ­ Fission product barrier or primary containment radioactive material holdup or isolation Class C (ANS Class 3) ­ Other safety-related functions required to mitigate design basis accidents / events and NOT in Class A/B ­ Minor leakage will not prevent Class C structures, systems, and components from meeting the safetyrelated function

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AP1000 Safety Classification

Class D - Nonsafety-Related SSCs

­ SSC containing radioactivity ­ SSCs that act to prevent unnecessary actuation of passive safety systems ­ Some additional requirements on procurement, inspection, or monitoring beyond other nonsafety-related class requirements ­ 10CFR50 Appendix B / 10CFR21 do NOT apply

Other Nonsafety-Related SSCs

­ SSCs NOT covered in the above classes ­ Have no safety-related functions to perform ­ Do NOT contain sufficient radioactive material that a release could exceed applicable limits

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AP1000 RPV Design Requirements

ASME and ANS codes and standards Electric Power Research Institute

­ ALWR Utility Requirements Document

Welding Research Council bulletins ASTM Standards NRC requirements:

­ U.S. Code of Federal Regulations, ­ NRC Orders, NRC Regulatory Guides ­ NRC NUREG publications

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AP1000 RPV Design Specification - 1

Sections 3.0 and 4.0 ­ Functional Description ­ provide a functional description of the RPV ­ define all of the safety, design and seismic classifications Sections 5.0 and 6.0 - Design and Analysis ­ define the design and analysis boundaries for the RPV ­ establish the design requirements and parameters for completing the analysis and Design Report

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AP1000 RPV Design Specification - 2

Section 7.0 - Material

­ selection of ASME materials for pressure boundary, structural parts, and items of RPV ­ detailed requirements for Alloy 690 material with optimized resistance to PWSCC ­ special limits on beltline material residual elements to minimize radiation damage effects ­ other material requirements beyond Section III requirements and the requirements of the applicable ASME materials specification from Section II of the Code

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AP1000 RPV Design Specification - 3

Sections 8.2 - Fabrication ­ special fabrication processing requirements in more detail than provided by NB-4000 ­ additional controls are imposed on:

­ ­ ­ ­ welding processes selection of weld filler materials post-weld heat treatment requirements other special processes

­ thermal cutting and cleaning procedures

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AP1000 RPV Design Specification - 4

Section 8.3 ­ Examination

­ addresses examination requirements for RPV materials and welds

­ for compliance with Code requirements ­ other industry standards for examinations in addition to the Section III examinations

Section 8.4 ­ Testing

­ additional testing requirements include material testing beyond minimum Code requirements ­ such as fracture mechanics tests

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AP1000 RPV Design Specification - 5

Section 8.5 ­ Surveillance Program

­ defines type and quantity of materials to be provided with the RPV

­ machined into specimens ­ installed in surveillance capsule in RPV to monitor response of beltline materials to fluence over lifetime of plant

Section 8.6 ­ Archive Materials

­ materials retained as contingency, in event that additional testing or characterization of material is needed to resolve an issue during the course of plant operation

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AP1000 RPV Design Specification - 6

Pre-service and In-service Inspection

­ techniques, procedures and personnel qualification requirements used to perform PSI are required to be the same as those that will be used to perform the ISI during operation ­ current Section XI performance based requirements for RPV PSI/ISI use sophisticated automated systems with computerized data acquisition systems

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AP1000 RPV Design Specification - 7

Section 9.0 ­ Quality Assurance

­ Subpart 1 of NQA-1-94

­ (equivalent to NQA-1-89 edition and up to the 1992 Addenda)

­ number of other aspects of NQA-1-94 Subpart 2 (formerly NQA-2)

­ cleaning, cleanliness criteria ­ packaging, shipping, handling requirements

­ Fabricator oversight

Section 10.0 ­ Packaging and Shipping

­ addresses preparation for shipment of the RPV

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Summary and Conclusion

AP1000 Key Features ­ 2 Loop Reactor Coolant System ­ Seal-less pumps ­ Passive Safety Systems ­ Non-Safety Defense-in-Depth Systems ­ previously safety systems ­ Digital I&C Systems with data highway AP100 Meets requirements of: ­ ASME and ANS codes and standards ­ Regulatory requirements ­ Other industry requirements

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Questions

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Information

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