About Nuclear Trainer
Nuclear Trainer is a 3D training model of a generic commercial nuclear power plant, with linked drawings, guided lessons and practice tools. It is built for new designers, technicians, engineers and anyone learning how a plant is arranged, what each system does and how its switchyard is worked on.
This release covers the whole plant site, the containment and shield building, the turbine building and the 500 kV and 230 kV switchyard, with the plant one-line, the auxiliary power one-line, a containment section, a passive safety systems diagram and a steam cycle diagram. The inside of the auxiliary building and the other support buildings follow in later releases.
Content last reviewed: November 8, 2026 · Site version v4.1
Disclaimer
Training only. Nuclear Trainer is an educational model. It is not for design or licensing, operation or maintenance, radiological work planning or emergency response, and nothing on it is PE-sealed. At a real plant, the plant's own procedures, its NRC license and its qualified staff govern.
It is not a substitute for the applicable regulations and codes (NRC, OSHA, EPA, NESC, NFPA, ASME), the owner's or employer's standards and procedures, manufacturer instructions, or the judgment of a licensed engineer or a qualified person. Dimensions, ratings and calculations are representative.
Drawings, DXF downloads and CAD symbols are generated from the training model. They show typical arrangements at representative sizes and are not for design or construction.
No engineering services. The content, drawings and exports were not prepared, checked or sealed by a licensed Professional Engineer, and using the site does not create an engineer-client relationship. Everything is provided as is, without warranty of any kind.
The certificate records participation in a self-paced, unproctored program. It is not operator, technician or radiation-worker qualification, and it does not make anyone a qualified person under OSHA or the NRC's rules; the employer and the plant's licensed training program decide that.
A generic plant
The plant is a generic advanced passive pressurized water reactor of about 1,100 MWe class: two coolant loops, a steel containment vessel inside a concrete shield building with a cooling water tank on its roof, and safety systems that work on stored energy, gravity and natural circulation for an extended period with no AC power. It is not any real plant or design, and no reactor product, vendor, licensor, owner or operator is named anywhere on the site. The internal arrangement is simplified.
Radiological content stays at the level of the free NRC and DOE training material. Any dose rates shown are illustrative model values. Plant security, physical and cyber, is deliberately left out: it is not modeled or described.
How to read the numbers
Values fall into four kinds. Where it matters, the text says which kind a number is.
| Kind | Meaning | Example |
|---|---|---|
| Regulation or code requirement | Set by law or an adopted code, quoted from the primary text. | The 5 rem annual limit (10 CFR 20.1201); OSHA minimum approach distances |
| Standard method | From a consensus standard or guide, named with its edition. | IEEE 80 touch and step limits; IEEE 998 rolling sphere |
| Typical practice or catalog value | Common US practice or a real catalog dimension; varies by maker and company. | 12 in × 4 in steel ladder tray, rungs on 9 in centers; 1 in rigid conduit, 1.315 in OD |
| Model value | A representative number chosen for the 3D model, labeled "model value". Many are rounded from public NRC documents for this general type of plant; none is a design value for any real plant. | Vessel and building sizes, elevations, pump and tank ratings, fault levels |
A number that could not be sourced is labeled "Model value" or listed as "Needs source". Paywalled standards are named only: no values are taken from them. The calculators show their equations and every input on screen.
References
Editions shown are the ones the content was checked against. Regulations, codes and standards change: confirm the edition your project, plant or employer uses. A row that says "checked" with a date was confirmed on that date with the eCFR, the publisher or a reseller listing; "edition not verified" rows were not.
NRC regulations and guidance
| Reference | Edition | Used for |
|---|---|---|
| 10 CFR 50 Appendix A, General Design Criteria | eCFR, checked Oct 22, 2026 | GDC 2 (natural phenomena), 4 (environmental and dynamic effects, including turbine missiles), 10 (reactor design), 14 (reactor coolant pressure boundary), 15 (reactor coolant system design), 16 (containment design), 17 (electric power systems), 26 (reactivity control systems), 29 (protection against anticipated operational occurrences), 34 (residual heat removal), 35 (emergency core cooling), 38 (containment heat removal) and 50 (containment design basis), named on the equipment cards; no values taken |
| 10 CFR 50.46, ECCS acceptance criteria | eCFR, checked Oct 22, 2026 | Named on the passive core cooling cards |
| 10 CFR 50 Appendix J, containment leak-rate testing | eCFR, checked Oct 22, 2026 | Named on the containment vessel, hatch and airlock cards |
| 10 CFR 50.49, environmental qualification | eCFR, checked Oct 22, 2026 | Named on the transmitter cards |
| 10 CFR 50.55a, codes and standards | eCFR, checked Oct 22, 2026; incorporates ASME BPVC Section III and Section XI through the 2021 Edition, the ASME OM Code through 2022 and IEEE 603-1991 | Why the vessel, piping and valve cards name the ASME codes; no values taken |
| 10 CFR 50.48, fire protection | eCFR, checked Oct 22, 2026; 50.48(c) incorporates NFPA 805, 2001 Edition | Named; fire protection content comes in a later release |
| 10 CFR 50.63, loss of all alternating current power | eCFR, checked Oct 22, 2026 | Background to the passive systems that need no AC power (named) |
| 10 CFR Part 20, standards for protection against radiation | eCFR, checked Oct 30, 2026 | Quoted in the Safety guide: 20.1003 (radiation area, high and very high radiation area, airborne radioactivity area), 20.1101(b) (ALARA), the occupational dose-limit table from 20.1201(a)(1)(i) and (ii) and (a)(2)(i) and (ii), 20.1207 (minors), 20.1208(a) (declared pregnant woman), 20.1301(a) and (e) and 20.1302 (members of the public and effluents), 20.1502(a)(1) (monitoring above 10 percent of the limits), 20.1601 and 20.1602 (named), 20.1902 (posting wording) |
| 10 CFR 50.47, emergency plans | eCFR, checked Oct 30, 2026 | Quoted in the Safety guide: the sixteen planning standards in (b), (b)(4), and the emergency planning zones in (c)(2) (about 10 miles for the plume exposure pathway, about 50 miles for the ingestion pathway) |
| 10 CFR 50 Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities | eCFR, checked Oct 30, 2026 | The four emergency classes (IV.C.1), the 15-minute assess-classify-declare time (IV.C.2) and the 15-minute notification of State and local agencies (IV.D.3), quoted |
| NUREG-0654/FEMA-REP-1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants | Rev. 2, December 2019 (ML19347D139) | Emergency plan criteria, cited in the Safety guide |
| NRC web pages "Emergency Classification" and "Emergency Planning Zones" | reviewed by NRC Sep 8 and Aug 25, 2026; read Oct 30, 2026 | Class and zone descriptions, quoted in part |
| 10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants | eCFR, checked Oct 30, 2026 | Scope wording quoted on the info card of every safety-related part; the QA level column of the bill of materials |
| 10 CFR 50.65 (maintenance rule) and 10 CFR Part 100 (reactor site criteria) | eCFR titles checked Oct 30, 2026 | Named in the Safety guide sources |
| 10 CFR Part 51, environmental protection regulations; 10 CFR 50.34a and Appendix I to Part 50 | eCFR, checked Oct 30, 2026 (51.20(b), 50.34a); Appendix I named only | Environmental review and effluent design objectives (as low as is reasonably achievable) in the permits chapter |
| Regulatory Guide 1.204, Guidelines for Lightning Protection for Production and Utilization Facilities | Rev. 1, February 2024 (ML23241A957; 89 FR 8329), checked Oct 30, 2026; endorses IEEE 665-1995, 666-2007, 1050-2004 and C62.23-2017 | Basis for the lightning protection on the shield building and the turbine building (named) |
| NRC HRTD technology manuals: sections 4.0 (passive core cooling) and 5.2 (passive containment cooling) of the manual for this plant type, and 10.1 (reactor protection) of a generic PWR manual | read Oct 30, 2026 | Valve normal and fail positions on the P&IDs, actuation signals and the four-channel, two-out-of-four, de-energize-to-trip arrangement on the protection logic sheet, and the pH adjustment baskets |
| 10 CFR 19.12, instruction to workers | eCFR, checked Oct 22, 2026 | The 100 mrem (1 mSv) threshold for radiation safety instruction, quoted in the Safety guide |
| 10 CFR Parts 52 and 53, licensing | Part 53 final rule published March 30, 2026, effective April 29, 2026 (checked Oct 22, 2026) | Named only |
| 10 CFR Part 73 (including 73.54) and Part 26 | named only | Physical security, cyber security and fitness for duty. They are deliberately not modeled or described on this site |
| NRC–OSHA Memorandum of Understanding | 2013 (NRC July 19, OSHA September 6); replaced the 1988 memorandum (checked Oct 22, 2026) | Which agency covers which hazard at a nuclear plant |
| Regulatory Guide 1.29, Seismic Design Classification | Rev. 6, July 2021 (checked Oct 22, 2026) | Seismic Category I, and the rule for nearby structures whose failure could affect Category I items (the plant description calls these seismic Category II: the turbine building first bay and the annex next to the nuclear island) |
| Regulatory Guide 1.75, Criteria for Independence of Electrical Safety Systems | Rev. 3, February 2005, endorsing IEEE 384-1992 (checked Oct 22, 2026; IEEE 384-2018 is current) | Division separation of the modeled cable trays (named) |
| Regulatory Guide 1.151, Instrument Sensing Lines | Rev. 2, February 2020, endorsing ANSI/ISA-67.02.01-2014 (checked Oct 22, 2026; ISA-67.02.01-2021 is current and was not used) | Sensing line routing and slope for the remote-mounted transmitters (named; the 1 in per ft slope is typical practice from transmitter makers' instructions) |
| Regulatory Guide 1.189, Fire Protection for Nuclear Power Plants | Rev. 5, October 2023 (checked Oct 22, 2026) | Named; fire protection comes in a later release |
| Regulatory Guide 1.121, Bases for Plugging Degraded PWR Steam Generator Tubes | edition not verified | Named on the steam generator card |
| NUREG-0612, Control of Heavy Loads at Nuclear Power Plants | edition not verified | Named on the polar crane card |
| Regulatory Guide 1.115, Protection Against Turbine Missiles | edition not verified | Named on the turbine cards: why the shaft points at the nuclear island |
| Regulatory Guide 1.143, Radioactive Waste Management Systems | edition not verified | Named on the radwaste building card |
| Regulatory Guide 1.23, Meteorological Monitoring Programs for Nuclear Power Plants | Rev. 1, March 2007 (checked Oct 23, 2026) | Meteorological tower: wind instruments at about 10 m and 60 m, temperature difference between the levels |
| Regulatory Guide 1.26, Quality Group Classifications | Rev. 6, December 2021 | Named on the main steam and feedwater piping inside containment |
| 10 CFR 55.46, simulation facilities | eCFR (named) | Operator training simulator, named on the training center card |
| NUREG-0800, Standard Review Plan | Sections 6.3 Rev. 3 (2007), 8.2 Rev. 5 and 8.3.1, 8.3.2 Rev. 4 (2010) (checked Oct 22, 2026); Chapter 10 sections (10.2, 10.2.3, 10.3, 10.4.1, 10.4.2, 10.4.4, 10.4.5, 10.4.7) named, revisions not verified | Review guidance behind the passive core cooling, electrical and steam and power conversion systems (named) |
OSHA and EPA
| Reference | Edition | Used for |
|---|---|---|
| OSHA 29 CFR 1910.147, control of hazardous energy | eCFR, checked Oct 30, 2026 | Quoted in the lockout/tagout chapter: (a)(1)(i) and the utility exclusion in (a)(1)(ii)(C) |
| OSHA 29 CFR 1910.269 and App. B | eCFR, checked Oct 30, 2026 ((d)(1) and its Note); Oct 15, 2026 (tables) | Lockout of equipment that is not an integral part of power generation goes under 1910.147 (Note to (d)(1)); switchyard minimum approach distances (Tables R-6 and R-7, in the regulation text), altitude factors (Table R-5), switching and grounding order, arc-flash estimate and arc-rated clothing (1910.269(l)(8)) |
| OSHA 29 CFR 1910.333(c)(3) | eCFR, checked Oct 2026 | Unqualified-person distance: 10 ft up to 50 kV, plus 4 in per 10 kV above |
| OSHA 29 CFR 1910.302(a)(2)(v) | eCFR, checked Oct 22, 2026 | Utility generation installations are outside the Subpart S design rules |
| OSHA 29 CFR 1910.146, permit-required confined spaces | eCFR (named) | Tanks, the IRWST and the containment annulus in the Safety guide |
| OSHA 29 CFR 1910 Subpart D, walking-working surfaces | eCFR, checked Oct 22, 2026 | Platforms, stairs (1910.25), fall protection (1910.28) and guardrails: top rail 42 in, plus or minus 3 in (1910.29(b)(1)) |
| OSHA 29 CFR 1910.95, 1910.179 and 1910.269(d) | eCFR (named) | Noise, overhead cranes and lockout of machines in the turbine building safety cards |
| OSHA 29 CFR 1926.1408, Table A (cranes near power lines) | eCFR, checked Oct 15, 2026 | Crane and boom clearances in the Safety guide |
| OSHA 29 CFR 1910.151(c) | eCFR, checked Oct 2026 | Eyewash near battery electrolyte |
| EPA 40 CFR 112 (SPCC) and 40 CFR 761 (PCBs) | eCFR, checked Oct 2026 | Transformer oil containment and the PCB note on the transformer card |
Codes
| Reference | Edition | Used for |
|---|---|---|
| National Electrical Safety Code (NESC), IEEE C2 | 2023 | Switchyard clearances, fence and sign rules |
| NFPA 70, National Electrical Code | 2020 articles cited; 2026 is current | Scope: utility generating stations are not covered (90.2), so its rules are cited as typical practice: rigid conduit support, 344.30 (2020 text, quoted in a trade article); bends between pull points, 344.26; liquidtight flexible metal conduit, Article 350 |
| NFPA 804, Fire Protection for Advanced Light Water Reactor Electric Generating Plants; NFPA 20, 22, 30 and 37 | editions not verified | Named on the turbine island, transformer, tank, fire pump and diesel cards (NFPA 850 does not cover nuclear plants) |
| NFPA 70E, Electrical Safety in the Workplace | 2024 values used | Shock approach boundaries in the arc-flash calculator (Table 130.4(E)(a)) |
| NFPA 780, Installation of Lightning Protection Systems | edition not verified | Named on the lightning protection card |
| NFPA 497 and NFPA 70 Article 500, hazardous (classified) locations | editions not verified | Named in the note on the generator hydrogen and seal oil area; no extents are given |
| NFPA 805, Performance-Based Fire Protection for LWR Plants | 2001 Edition, as incorporated by 10 CFR 50.48(c) | Named only |
Standards
| Standard | Edition | Used for |
|---|---|---|
| ASME Boiler and Pressure Vessel Code, Section III, Division 1 (Subsections NB and NE) | 2025 is current; 10 CFR 50.55a incorporates through 2021 (checked Oct 22, 2026) | Named on the reactor vessel, piping and containment vessel cards; no values taken |
| ASME OM Code, Operation and Maintenance of Nuclear Power Plants | 2022 (checked Oct 22, 2026) | Inservice testing of the squib and powered valves (named) |
| ASME B36.10M and B36.19M, pipe dimensions | 2018 editions (checked Oct 22, 2026) | Named. Pipe outside diameters and walls are taken from free published pipe charts that list these sizes |
| NEMA VE 1, Metal Cable Tray Systems; NEMA VE 2, Cable Tray Installation Guidelines | VE 1-2017 (checked Oct 22, 2026); VE 2 edition not verified | Named. Ladder tray rail heights, rung spacing, section lengths and fitting radii and tangents are from free manufacturer catalogs (catalog dimensions; no brand named); supports within 2 ft of each fitting and no more than 12 ft apart |
| UL 514A conduit bodies, UL 360 liquidtight flexible metal conduit, ASTM E814 penetration firestop systems, IEEE 383 nuclear cable qualification, ANSI C80.1 rigid steel conduit | editions not verified | Named on the raceway cards; conduit, coupling, LB and flexible conduit dimensions are catalog values |
| ANSI C80.1, Rigid Steel Conduit | edition not verified | Named. Conduit outside diameters and factory elbow radii are from free manufacturer catalogs |
| ASTM A123/A123M, hot-dip galvanizing; ASTM A269, stainless tubing | editions not verified | Tray finish and instrument tubing material (named) |
| IEEE 384, Independence of Class 1E Equipment and Circuits | 2018 is current; RG 1.75 endorses 1992 (checked Oct 22, 2026) | Named |
| IEEE 603, Criteria for Safety Systems | 2018 is current; 10 CFR 50.55a references 1991 (checked Oct 22, 2026) | Named |
| ASME NQA-1, Quality Assurance Requirements for Nuclear Facility Applications | named only | Quality assurance, in the Safety guide sources |
| IEEE 308 (Class 1E power systems), IEEE 323 (qualifying Class 1E equipment) and IEEE 344 (seismic qualification) | 308-2020 (RG 1.32 Rev. 4 endorses it); 323 and 344 now IEC/IEEE 60780-323-2016 and 60980-344-2020 | Named |
| IEEE 665, 666, 1050 and C62.23 (generating station grounding, lightning and surge protection) | 665-1995, 666-2007, 1050-2004, C62.23-2017, as endorsed by RG 1.204 Rev. 1 | Named on the lightning protection card |
| IEEE 1100 and NFPA 70 Article 392 (cable tray grounding and barriers) | editions not verified | Named; tray ground conductors and the voltage barrier are typical practice, sizes are model values |
| IEEE 317, Electrical Penetration Assemblies | edition not verified | Named on the penetration card |
| IEEE 485 and 450, Station Batteries | 485-2020; 450-2020 (checked Oct 22, 2026) | Battery basics on the auxiliary power one-line |
| IEEE 80, Safety in AC Substation Grounding | 2013 with Cor 1-2015; Inactive-Reserved since 2024, revision P80 under way (checked Oct 22, 2026) | Tolerable touch and step voltage, surface-layer factor, grid equations |
| IEEE 998, Direct Lightning Stroke Shielding | 2012 equations used; 998-2026 is current, approved June 4, 2026 (checked Oct 22, 2026) | Rolling sphere radius S = 8·k·I0.65, per 998-2012 |
| IEEE 1427, Electrical Clearances in Air-Insulated Substations | 2020 | Basis for 500 kV clearances; the 500 kV row in the Measure tool is a model value |
| IEEE 605, Bus Design in Air-Insulated Substations | 2008 content; 605-2023 is current | Rigid bus, expansion fittings |
| IEEE 1584, Arc-Flash Hazard Calculations | 2002 equations used; 2018 is current | Arc-flash calculator (teaching model) |
| ANSI C37.32, High-Voltage Switches, Bus Supports and Accessories | 1996 values as reproduced in RUS 1724E-300 Table 4-7 | Clearances and live-part heights in the Measure tool |
| IEEE C37.2, Device Function Numbers | 2022 | Device numbers in the glossary and drawings |
| IEEE C57.13, Instrument Transformers; IEEE C62.11 and C62.22, Surge Arresters | C57.13-2016; C62.11-2020; C62.22 edition not verified | CT and VT ratings; arrester MCOV selection |
| ISA-5.1, Instrumentation Symbols and Identification | 2024 is current (checked Oct 22, 2026) | Named; the P&IDs, the passive safety and steam cycle diagrams use common P&ID valve and instrument symbols |
| ASME B16.9 (butt-welding fittings) and MSS SP-97 (branch outlet fittings) | editions not verified | Named; tee and branch outlet proportions in the model are model values |
| ASME B31.1 Power Piping; ASME PTC 6 Steam Turbines; ASME MFC-3M; ASME B30.2; ASME Section III Subsections NE and NF; AISC N690; ANS-57.1; NFPA 55 | editions not verified | Named on the turbine building piping, turbine, flow element, crane, component support, refueling machine, fuel transfer tube and gas storage cards |
| Heat Exchange Institute standards for steam surface condensers and closed feedwater heaters | editions not verified | Named on the condenser and feedwater heater cards |
| ACI 351.3R (foundations for dynamic equipment), ACI 334.2R (cooling tower shells), AISC 360, AWWA C301/C303 and D100, IEEE 421.1, Hydraulic Institute standards | editions not verified | Named on the turbine deck, cooling tower, building frame, circulating water pipe, tank, excitation and pump cards |
| IEEE 315 / ANSI Y32.2 and NECA 100, drawing symbols | 1975 (reaffirmed 1993); NECA 100-2013 | CAD symbol forms in the legend and DXF downloads (drawn in their style) |
Government guides and training material
- USDA RUS Bulletin 1724E-300, Design Guide for Rural Substations (2001): clearances (Table 4-7), suspension insulator quantities (Table 4-6), bus-arrangement relative cost (Table 4-1).
- U.S. DOE Fundamentals Handbooks, Nuclear Physics and Reactor Theory (DOE-HDBK-1019/1-93, /2-93), Thermodynamics, Heat Transfer and Fluid Flow (DOE-HDBK-1012-92) and Instrumentation and Control (DOE-HDBK-1013-92): background at a training level. The DOE site lists them with Archive status (checked Oct 22, 2026).
- NRC training and public licensing documents for advanced passive pressurized water reactors: equipment counts and ratings marked "public plant description", the arrangement, and the basis for the model values. No design, vendor, plant or utility is named on this site.
- EPA rules 40 CFR 112 (spill prevention), 40 CFR 122 (NPDES permits, usually issued by the state; EPA page "NPDES State Program Authority", updated Aug 17, 2026), 40 CFR 125 Subpart I (new facilities: 125.80(a), 125.84(b)(1), eCFR, checked Oct 30, 2026) and Subpart J (existing facilities, named), and 40 CFR 190.10(a) (eCFR, checked Oct 30, 2026): the tank, discharge and intake cards and the permits chapter.
- DOE-HDBK-1130-2022, Radiological Worker Training (November 2022): the level of the radiologically controlled area chapter.
- NRC Human Resources Training and Development (HRTD) technology manual sections on passive containment cooling and on condensate and feedwater for this plant type: the cooling tank drain valves, the air baffle supports, heater strings and drains, and one flow venturi in each feedwater line.
- USDA RUS Bulletin 1724E-200, Design Manual for High Voltage Transmission Lines, Table 4-1: the recommended 230 kV conductor clearance over roads, used to check the reserve line.
- OSHA 29 CFR 1910.25, 1910.28, 1910.29 (stairs, guardrails, stair rails, handrails and toeboards; checked on eCFR Oct 23, 2026) and 1910.103 (hydrogen): stairs, platforms and the gas storage pad.
Release history
v4.1, November 2026. Drawing legibility pass. Schedules, the line list and the instrument index wrap long entries inside their columns instead of cutting them; turbine P&ID line numbers sit beside their lines, clear of valves, text and other lines; the containment P&IDs, the containment section, the plant one-line, the raceway plans and the plan grids were relaid so no label overlaps another or runs off its sheet; sheet text has a dark outline so it stays readable where a line passes behind it. Corrected two drafting slips: the main condenser label on NPP-PID-03 (shells A, B and C) and the cooling water note on NPP-PID-02.
v4, October 2026. Answers an outside review: P&IDs for the reactor coolant system, passive core cooling, main steam, feedwater, condensate and circulating water with a line number on every pipe; a protection and actuation logic sheet; raceway plans, cable and raceway schedules with plant-wide cable numbers, a line list and an instrument index; a terminal box, feeder path and cable for every powered load in the containment and turbine building, with safety-related circuits by division (A to D); pipe tees and branch outlets; a voltage barrier in the 6.9 kV tray and ground conductors in the power trays; lightning protection on the shield and turbine buildings; pH adjustment baskets; the condensate polisher; motor ratings (model values); feeders for every large motor on the auxiliary one-line with transformer impedances and a short-circuit table; switchyard relay protection that matches the relay house; a 230 kV breaker for each reserve auxiliary transformer; revenue metering; fiber in the shield wires; main steam and feedwater through the auxiliary building in the site view; hydrogen igniters and recombiners are not modeled (no free source confirms them for this plant type); the Safety guide rewritten for a nuclear plant, with emergency planning, the full dose-limit table, the radiologically controlled area, lockout/tagout and permits; a faster 3D view; bill of materials in meters with safety class and QA columns; accessibility fixes; fixed drawing issue dates.
v3, October 2026. Accuracy review of every building, with the fixes it called for (steam generator channel head flow, vessel supports and primary shield wall, maintenance floor and stairs, guardrails, air baffle, main steam and feedwater inside containment, pressurizer spray, extraction steam and heater drains, condensate to all three condenser necks, feedwater venturis, pipe supports, turbine hatch and exciter, 500 kV clearances and take-offs, reserve transformer leads, shield wires, roads and parking); cable trays rebuilt with catalog fittings and conduit with couplings, LB bodies, drop-outs, hubs, flexible conduit and supports; meteorological tower, service water cooling tower, gas storage and water treatment building added.
v2, October 2026. The whole plant site (nuclear island, turbine building, annex, radwaste and diesel buildings, tanks, natural draft cooling tower, river intake, switchyard and transmission lines); the turbine building with the turbine-generator, moisture separator reheaters, condenser, feedwater train, crane, cable trays, conduit and instruments; X-ray now hides building walls and roofs; steam cycle diagram; library categories corrected.
v1, October 2026 (phase 1). Containment and shield building in cutaway with the reactor coolant system, passive core cooling, passive containment cooling, instruments, cable trays and conduit; 500 kV breaker-and-a-half and 230 kV reserve switchyard; plant and auxiliary one-lines; containment section; passive safety systems diagram; radiation chapter in the Safety guide.
Privacy and security
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Accessibility
The trainer is designed for a desktop or laptop with a mouse, at 100–200% browser zoom. Panels, lessons, the catalog and the drawings work from the keyboard, and the catalog and drawings are an alternative to clicking in 3D. In the switching simulator, device state is shown in words and symbols as well as by the utility red/green colors. Dialogs trap focus, close on Escape and return focus; camera flights are skipped when the browser asks for reduced motion. The 3D view itself is a picture; the catalog, building pages and drawings carry the same information as text. Screen-reader behavior has not been tested yet. If something does not work with your browser or assistive technology, please report it the same way as a content error.
Third-party software
The 3D view runs on the three.js library (r160, MIT License, © 2010-2023 three.js authors; license text). The type is IBM Plex Sans and IBM Plex Mono (SIL Open Font License 1.1; license text). Both are served from this site, with no third-party requests. Everything else on the site is © 2026 Locke Design Firm LLC.
Report an error
If you find a value that disagrees with a regulation, code, standard or manufacturer's data, tell us where it is, what it says, and your source. Every report is checked against the source, and confirmed errors are fixed.