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Westinghouse-style PWR Operations Knowledge Base

Westinghouse-style PWR operating knowledge — emergency operating procedures (complete set of E, ES, ECA, FR families) plus the plant reference, conduct of operations, human factors, and scenario layers — authored in Procedure Markdown (procmd) v0.6 and consumed both by human readers and by samsinn agents via the procedure_lookup tool.

⚠️ LLM-reconstructed content — not licensed plant procedures. See Scope and disclaimers before reading further.

The procedures here are interlinked: branches in one EOP refer directly to steps in another via [[wikilinks]]. Start at E-0 for any post-trip / post-SI scenario; the diagnostic flow there transitions to the appropriate event-specific procedure. The Critical Safety Function status trees (FR-x family) run continuously alongside the main EOP from event entry through recovery.

Coverage legend: ✅ developed · 🟡 partial · ⬜ stub. Classification is content-based (scripts/build-manifest.ts classifyByContent): counts steps with substantive body content and appendix tags with source: citations rather than raw step count. After Phase C all 39 procedures classify as ✅ developed. See PLAN.md for the roadmap (Phase D plant reference is next).

E-series — Initial Diagnostic and Mitigation

ID Title Coverage
E-0 Reactor Trip or Safety Injection ✅
E-1 Loss of Reactor or Secondary Coolant ✅
E-2 Faulted Steam Generator Isolation ✅
E-3 Steam Generator Tube Rupture ✅

ECA-series — Extreme Conditions

ID Title Coverage
ECA-0.0 Loss of All AC Power ✅
ECA-1.1 Loss of Emergency Coolant Recirculation ✅
ECA-1.2 LOCA Outside Containment ✅
ECA-2.1 Uncontrolled Depressurization of All Steam Generators ✅
ECA-3.1 SGTR with Loss of Reactor Coolant — Subcooled Recovery ✅
ECA-3.2 SGTR with Loss of Reactor Coolant — Saturated Recovery ✅
ECA-3.3 SGTR Without Pressurizer Pressure Control ✅

ES-series — Post-Trip Recovery

ID Title Coverage
ES-0.0 Rediagnosis ✅
ES-0.1 Reactor Trip Response ✅
ES-0.2 Natural Circulation Cooldown ✅
ES-1.1 SI Termination ✅
ES-1.2 Post-LOCA Cooldown and Depressurization ✅
ES-1.3 Transfer to Cold Leg Recirculation ✅
ES-1.4 Transfer to Hot Leg Recirculation ✅
ES-3.1 Post-SGTR Cooldown Using Backfill ✅
ES-3.2 Post-SGTR Cooldown Using Blowdown ✅
ES-3.3 Post-SGTR Cooldown Using Steam Dump ✅

FR-series — Critical Safety Function Status Trees

These run as Concurrent: ... [independent] from event entry; they monitor their respective Critical Safety Function and override the active EOP if the CSF degrades to RED or ORANGE.

FR-S — Subcriticality

ID Title Coverage
FR-S.1 Response to Nuclear Power Generation / ATWS ✅
FR-S.2 Response to Loss of Core Shutdown ✅

FR-C — Core Cooling

ID Title Coverage
FR-C.1 Response to Inadequate Core Cooling ✅
FR-C.2 Response to Degraded Core Cooling ✅
FR-C.3 Response to Saturated Core Cooling Conditions ✅

FR-H — Heat Sink

ID Title Coverage
FR-H.1 Response to Loss of Secondary Heat Sink ✅
FR-H.2 Response to Steam Generator Overpressure ✅
FR-H.3 Response to Steam Generator High Level ✅
FR-H.4 Response to Loss of Normal Steam Release Capabilities ✅
FR-H.5 Response to Steam Generator Low Level ✅

FR-P — RCS Integrity (Pressurized Thermal Shock)

ID Title Coverage
FR-P.1 Response to Imminent Pressurized Thermal Shock Condition ✅
FR-P.2 Response to Anticipated Pressurized Thermal Shock Condition ✅

FR-Z — Containment

ID Title Coverage
FR-Z.1 Response to High Containment Pressure ✅
FR-Z.2 Response to Containment Flooding ✅
FR-Z.3 Response to High Containment Radiation ✅

FR-I — RCS Inventory

ID Title Coverage
FR-I.1 Response to High Pressurizer Level ✅
FR-I.2 Response to Low Pressurizer Level ✅
FR-I.3 Response to Voids in Reactor Vessel ✅

Profiles