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PWR Operator Manual · Open the simulator

08 — Accident Study: Three Mile Island Unit 2 (1979)

Document: PWR-X01
Title: Three Mile Island Unit 2 — the four hours in the control room
Revision: 24
Category: Accident case study (sourced narrative + walkthrough)


1.0 The plant and the night

What this chapter is. The TMI-2 accident as it can be lived on this plant: what the crew saw, what they believed, what they did — and what happens when the same actions are taken on this board. Every historical clock and every operator-reasoning claim below is quoted from the primary listed in §7.0. Every plant number is a measurement taken on this plant through the full stack (service → control layer → engine) on 2026-09-08; where the model departs from the history, the departure is stated in the same row rather than smoothed over.

How to run it. Open Main Menu → Walkthroughs and press Start on the Three Mile Island row, under Incidents. The walkthrough starts at full power and injects the failures behind the scenes, on the step that needs them; you operate the board. It is on the preview channel while the two playthrough reviews are open. Free play alternative: start Hot Full Power and inject Loss of Main Feedwater, **Auxiliary Feedwater Failure, PORV Stuck Open and PORV Indicator Stuck Closed** together (07 PWR-E01, PWR-E12, PWR-E07, PWR-E08).

The first minute arrives as five beats, not one. Steps 2-6 are the cascade, one event to a step and each on its own clock: the condensate polisher goes off line (told, not simulated, §6.0), the condensate and main feed pumps trip, the turbine trips after them, the auxiliary feed pumps start into shut valves, and the relief valve lifts and does not reseat. **On two of those beats the walkthrough stops the clock** — the feed-pump trip and the relief valve — because the events are seconds wide and are not the player's to control: the primary pressure spike peaks about six seconds in and is over by thirty-five. The sim resumes when you press Continue; Rewind step and Stop release it too. Steps 2, 3 and 6 ask for no action at all — read the board, then press Continue.

**One thing is armed earlier than it is narrated, and it is a plant fact rather than an authoring choice.** The stuck relief valve is armed with the feed-pump trip on step 3, three steps before the beat that tells you about it. The stick does nothing to a shut valve: it latches on the first lift, the valve lifts about five seconds in and reseats near twenty-five, and measured full-stack the accident happens if the failure is armed at or before 21 seconds and does not happen at all at 22 — the plant settles at 1989 psi (13.71 MPa) with pressurizer level 41.5 % and the valve shut. A narrated chain cannot spend that budget, so the arming rides with the initiating event and only the lamp failure — which is timing-insensitive — lands on the relief-valve step.

1.1 Two different plants

TMI-2This plant
TypeBabcock & Wilcox, two once-through steam generatorsWestinghouse-style, one U-tube steam generator (lumped single loop)
Rating2772 MWt (GEND-061 §4.3)300 MWt, ≈ 100 MWe
Relief-valve setpoint2255 psig (15.55 MPa) (Appendix II.1 E6)Press SP + 100 psi (0.69 MPa) — 2335 psi (16.10 MPa) at the normal 2235 psi (15.41 MPa) program, and it follows the setpoint down a cooldown (03 §6.1)
Relief capacityone power-operated relief valve at 2772 MWt3.6× TMI-2's per MWt — the anchor plant's two valves at 179,000 lb/hr each and 1520 MWt, power-scaled
Vessel level instrumentnonenone — the same gap, and it is the whole reason the pressurizer is read as an inventory gauge
Reactor trip on turbine tripnot fitted — "Some other vendors-GE and Westinghouse-voluntarily provided for these 'anticipatory trips' in their designs" (Vol. II Pt 2)armed above P-9, 50 % power (09 §2.0)

Why the walkthrough defeats this plant's anticipatory trip (ruled 2026-09-08). At TMI-2 the turbine tripped and the reactor kept running for eight seconds; primary pressure climbed into the relief valve, which is the event the whole accident hangs from. The report is explicit about what the missing feature cost and what a fitted one would have done:

*"The anticipatory trip prevents, in most instances, the opening of the PORV… The influence of the lack of such a feature is to decrease the time available to the operating crew to cope with the event."* — Vol. II Pt 2

That is exactly this plant's behaviour: a turbine trip above P-9 scrams the reactor at once, the pressure turns before it reaches the valve, and there is no stuck valve to find. The walkthrough therefore injects Anticipatory Trip Failure on its first step and says so to the player in one sentence. It is a declared departure from this plant's own sourced behaviour, taken so the accident can happen at all — and the departure is itself the first lesson: one relay decides whether this night is a routine trip or an accident.

The consequence of the bigger relief valve. Per megawatt this plant loses inventory through a stuck-open valve faster than TMI-2 did. Read the shape of the ride below — the plateau, the level that rises while mass falls, the margin that pegs — and not the minutes as real-plant figures.


2.0 The first minutes — 04:00:36 to 04:02:39

NOTE — how to read the clocks. The source quotes a wall clock for the first two events only (04:00:36 and 04:00:37) and gives elapsed time after initiation for everything after. **Every other wall clock in this chapter is derived** by adding the elapsed time to 04:00:37 — arithmetic on the source, not a quote from it.

ClockElapsedTMI-2 (sourced)This plant (measured)
04:00:36−1 sCondensate pump CO-P1A trips — postulated closure of the condensate polisher valves "because of water in the control air system" (E1)No polisher model — the initiator is narrated, not injected (§6.0). Walkthrough step 2, which asks for no action
04:00:370 s"Feedwater pumps FW-P1A and FW-P1B tripped" (E2)Loss of Main Feedwater injected, and the relief-valve stick armed with it; FEED FLOW to 0. Walkthrough step 3 — the sim pauses here
04:00:370 sTurbine trip follows, "Normal following trip of feedwater pumps" (E3)Nothing injected — the turbine trips out of the feed loss on its own, within about a second. TURBINE TRIP lit. Walkthrough step 4
04:00:370 sAuxiliary feed pumps start into valves already shut — "Block valves EF-V12A and EF-V12B were closed" (E4)Auxiliary Feedwater Failure injected, hidden — the pumps run and deliver nothing. Walkthrough step 5
04:00:403 s"RCS pressure reaches the setpoint of the pilot-operated relief valve (PORV) RC-R2. PORV opens. (Setpoint = 2255 psig)" — 2255 psig (15.55 MPa) (E6)The relief valve lifts at 5 s, 2346 psi (16.175 MPa). Its setpoint here is Press SP + 100 psi (0.69 MPa) = 2335 psi (16.10 MPa) at the normal program (03 §6.1)
04:00:458 s"Reactor trips on high pressure. (Setpoint = 2355 psig)" — 2355 psig (16.24 MPa); the reactimeter peak is 2346 psig (16.175 MPa), the strip chart 2435 psig (16.79 MPa) (E7)The reactor trips at 43 s on over-temperature ΔT — the declared divergence of §1.1. (The historical peak and this plant's lift pressure share their digits by coincidence: different plants, different datum.)
04:00:5013 sThe valve is told to shut at 2205 psig (15.20 MPa) and does not: "Valve did not close." The lamp is a solenoid indication — "Light 'off' indicates solenoid deenergized. There is no actual position indicator." (E12)PORV Stuck Open was armed on the feed trip and latches on the lift at 5 s; PORV Indicator Stuck Closed lands on walkthrough step 6, which carries E6 and E12 together at E6's clock — the sim pauses here too. Until it lands the lamp reads honestly, which is what the crew had for their first thirteen seconds
04:00:5215 sPressurizer level peaks at 255 in; "RCS parameters are normal." (E17)—
04:01:0730 sRelief-line high-temperature alarm at 239.2 °F (115.1 °C), dismissed: "Alarms were not considered abnormal, because the PORV had previously opened." (E20)Tailpipe temperature rises above hot-leg temperature and stays there — the unalarmed indication that tells the truth (03 §6.1, ~302 °F (150 °C) class while relief passes)
04:01:551 min 18 sBoth steam generators dry out: "Indicates dryout. No feedwater was being admitted." (E28)At 1 min: 1705 psi (11.756 MPa), pressurizer level 67 %, RCS mass 98.5 %
04:02:392 min 2 sSafety injection actuates on its own — "Actuation on low RCS pressure (setpoint 1600 psig.)", 1600 psig (11.03 MPa) (E31)Safety injection actuates at 65.5 s on low pressurizer pressure, 1715 psi (11.824 MPa) (09 §2.0)

The lesson of these two minutes. Nothing on either board was lying about itself. The lamp reported the signal it was wired to report; the tailpipe alarm reported a hot pipe; the pressurizer reported its own level. What was missing at TMI-2 is missing here too — a direct reading of how much water is in the vessel.


3.0 The deception — 04:03:50 to 04:06:28

3.1 What the crew knew

The standing condition, in the report's own words:

"No instruments are provided for reading the level of water in the reactor vessel." — Vol. II Pt 2 §II.A, Figure II-6 caption

*"Their training on this particular equipment has taught the operators that the only credible check on the amount of coolant in the system is the indicator showing water level in the pressurizer… If the pressurizer level remains high, the operators are not trained to anticipate that coolant water may be leaking out of the primary system."* — Vol. I

*"the operator training at Met Ed, at B&W, even back in the navy, tells these men that the condition to avoid at all costs is 'going solid'"* — Vol. I

3.2 What they did

ClockElapsedTMI-2 (sourced)This plant (measured)
04:03:503 min 13 s"ESF emergency injection bypassed by operator." (E33) — taken before any valve was touchedThere is no engineered-safeguards bypass switch on this board (03 §17.4). The nearest action is the trip block on the safety-injection trip, gated by permissive P-11, 1973 psi (13.6 MPa) (09 §2.0)
04:05:074 min 30 s"Operator throttles makeup valves (MU-V16) to reduce injection flow." Purpose: "(a) to reduce rate of rise of pressurizer level (b) to prevent pump damage as RCS pressure drops." (E35)Injection is On / Off here, with no throttle valve (§6.0). Securing it is refused for 60 s after actuation and until the reactor is tripped (P-4); the stop is first accepted at 2.09 min and was accepted on the ride at 4.50 min — the crew's clock works on this plant
04:05:154 min 38 sOne of three makeup pumps stopped, two valves shut, two throttled (E36)No partial equivalent — one control, one decision
04:05:294 min 52 sLetdown raised to its high limit as part of the same action: "they stopped makeup pump MU-PlC and increased letdown flow to its high limit" (§II.A); flow alarms above 160 gpm six seconds later (E37, E38)Letdown Orifices A + B — the maximum lineup on this plant, a net drain against charging (03 §7.3)
04:05:375 min 0 sPressurizer level peaks at 377 in (E39)Level is already pegged at 100 % here, and the plant reads 1045 psi (7.205 MPa) with 97.2 % of its mass still aboard at 4.5 min
04:06:285 min 51 s"Pressurizer level goes offscale high (greater than 400 inches)." (E43)—

3.3 The coupling, on this plant's numbers

They throttled on a level that was still rising, not on a pegged gauge. The sourced order is throttle at 4 min 30 s → level peaks at 5 min → off scale at 5 min 51 s. The reaction was to the rate.

On this plant the same divergence is emergent physics, not a script: at 4.5 minutes the pressurizer reads 100 % on 97.2 % of the plant's water, while pressure has fallen from 2235 psi (15.41 MPa) to 1045 psi (7.205 MPa). Steam forming in the hot leg pushes liquid up the surge line; the gauge measures the surge, not the inventory. Rising level with falling pressure is the signature — one of those two indications is about water and the other is about heat, and only their disagreement carries the diagnosis.

WARNING: Do not throttle or secure injection on rising pressurizer level alone. Read the subcooling margin and the pressure trend with it.


4.0 Boiling and the pumps — 04:06 to 05:41

ClockElapsedTMI-2 (sourced)This plant (measured)
04:06:275 min 50 s"RCS pressure reaches minimum (~1350 psig), then begins to increase. Temperature reaches saturation." — 1350 psig (9.31 MPa); "Reaching saturation temperature means that steam voids can form in system" (E42)Board subcooling margin 0.0 at 5 min; the hot leg first reads above saturation at 2.7 min
04:08:378 min"operator finds emergency feedwater block valves EF-V12A and EF-V12B shut and opens them" (E49), on three cues — "low OTSG level, low steam pressure, high emergency feedwater discharge pressure". The report's verdict: "the 8-minute delay in restoring emergency flow did not directly affect the outcome of the accident-though it did serve to divert the attention of the operators" (Vol. I)Opening the aux feed block takes flow 0.000 → 1.000 within 30 s; plant at 1049 psi (7.233 MPa), RCS mass 90.8 %
04:10:3710 minFirst reactor coolant pump high-vibration alarm — "Indication of voids in system. Apparently not recognized." (E56)RCP CAVITATION stands from 2.58 min — a step, not a ramp, crossing its threshold 20 s after the margin reaches zero. Indication only: no damage model, no automatic pump trip
04:30:3730 minRCS at or near saturation and staying there967 psi (6.667 MPa), RCS mass 53.8 %
04:5757 min—The subcooling margin pegs on its floor, −50.4 °F (−28 °C), and stays there to about 150 min. That is this board's "the instrument has run out of scale"
05:13:371 h 13 minLoop B pumps secured: "Operator stops reactor coolant pump RC-P2B because of increasing vibration and decreasing flow and amperage" (E99)The cue has stood for 71 minutes by now. Securing pumps is a real handswitch here
05:20:371 h 20 min"The operators now have adequate information to deduce that the PORV is open — (a) No reduction in outlet temperature, and (b) PORV outlet 70°F hotter than code safety outlets." (E103)The same comparison is on this board: tailpipe temperature against hot-leg temperature
05:41:371 h 41 minLoop A pumps secured — "The pump has been operating without adequate suction head." (E111). Then: "As soon as all the pumps were stopped, circulation of coolant decreased drastically, because natural circulation was blocked by steam." (§II.A)Forced flow stops. The primary holds about 1020 psi (7.033 MPa) through this window, on the auxiliary-feed level hold; the accumulators are 100 % full at 60 min and have bled only to 86 % at 120 min — on this plant they never dump
06:11:372 h 11 minLoop A hot leg off the top of its scale — "TAVE will not be correctly shown." (E119)The hot leg never pegs here. Its detector spans 32 – 752 °F (0 – 400 °C) and the whole ride's peak reading is 632.0 °F (333.3 °C) at 232 min. The pegged instrument on this board is the subcooling margin, above

The pumps are the hard lesson. Vibration, falling flow and falling amperage all said the same thing — the pumps were passing a froth and had no suction head. Securing them was the correct equipment decision and it removed the last forced circulation from a core that could not set up natural circulation, because the loops were full of steam.


5.0 The block valve and the recovery — 06:18 onward

ClockElapsedTMI-2 (sourced)This plant (measured)
06:18:372 h 18 min"Operator closes PORV block valve RC-V2." / "RCS pressure begins to increase." (E122, E124). The relieving shift supervisor read the discharge temperatures: "Mehler dismisses the pressurizer level reading and moves to a fresh conclusion: The PORV is leaking." (Vol. I)PORV Block Valve → Isolate (two-press CONFIRM). Discharge goes to zero and pressure turns up, whatever the relief valve is doing — the block valve is upstream of it (03 §6.2)
06:28:372 h 28 minLoop B hot leg off scale: "There is now clear evidence of superheating in the hot legs." (E126)—
06:45:372 h 45 min"Radiation alarms are now indicative of extensive fuel damage." (E136)Not modelled on this path — see §6.0
07:12:373 h 12 minBlock valve reopened "in an attempt to control RCS pressure" (E163)—
07:20:373 h 20 minInjection restored by hand: "ESF manually initiated. Makeup pump MU-P1C starts." Post-accident: "Rapid quenching probably caused major fuel damage." (E167)Injection restarts on one control
~07:27 – 07:30~3 h 27 – 3 h 30 minNot sustained: safety injection reset, the makeup pump stopped, the block valve shut again — the reason is rationing, not diagnosis: "There was thus an inclination to use ES as little as possible (high pressure injection water is taken from the BWST)." (§II.A)This plant has no injection water inventory to ration — a declared simplification, and it removes the pressure the crew was under
07:413 h 41 minBlock valve reopened again (§II.A)—
07:563 h 56 minSafety injection actuates again, injection at maximum (§II.A)At 260 min the plant reads 1505 psi (10.377 MPa), RCS mass 78.0 %, and it is alive
09:435 h 43 minThe RCS is repressurized and held between 2000 and 2200 psig "by operation of the PORV block valve" for the next hour and a half (§II.A)The same control, used the same way
13:50:379 h 50 minHydrogen burn in containment, heard as an "Audible 'thump'", 28 psig (0.193 MPa) peak, read at the time as "electrical noise" (E273)Not modelled — §6.0
19:50:3715 h 50 min"Start reactor coolant pump RC-P1A." Post-accident: "Adequate core cooling now has been established." (E347)A real handswitch

The recovery is one valve. Everything upstream of 06:18 is diagnosis; the action itself was available from the first minute. This is the step to take away from the chapter: an open relief path is stopped by the block valve whether or not the relief valve can be commanded shut, and whether or not its lamp agrees.

5.1 Correct recovery on this board

#ActionWhy
1Read subcooling margin and pressure trend togetherThe leak signature. Rising level does not contradict it
2Command PORV CloseIt can fail; the attempt costs nothing
3PORV Block Valve → IsolateStops the loss, stuck valve or not
4Leave injection runningInventory. Securing it is a decision, not a tidy-up
5Restore the heat sink — aux feed block valves open, feed to the steam generatorDecay heat
6With the path isolated, recover pressure deliberatelyHeaters were shed on the injection signal; reload them first (03 §17.4)

CAUTION: The spring safety valves are a separate path. The block valve isolates the relief line only (03 §6.3).


6.0 What the model does not show

Each gap below carries the measurement or the file that declares it, so the departure is checkable rather than asserted.

GapThe declaration
Cladding heat-up while the core is uncoveredMeasured: the cladding reads 555 °F (290.6 °C) at 94 % uncovered. The core is a homogeneous node that credits residual steam flow with cooling every rod, so an uncovered core here does not get hot. This is the model defect the whole damage chain below hangs from
Oxidation and hydrogen generation on this pathThe reaction is built and sourced — Baker-Just, mandated by 10 CFR 50 Appendix K. It self-gates on temperature: at 572 °F (300 °C) the law integrates to 0.07 mg/cm² in a year. With the cladding never heating, this path generates no hydrogen at all
The 13:50 hydrogen burnNot modelled. ctmt_h2_burned is a registered static 0, and containment has no recombiners — their capacity is in no document in the corpus, so none was invented. Containment spray, the fan coolers and the steam-line isolation that goes with them are built and auto-actuate on sourced containment-pressure setpoints — see 09 §3.0 — so a large break no longer only heats and pressurises; whether this specific TMI-2 path ever reaches the 30 psig actuation is not remeasured here
Fuel damage on the TMI pathThe damage latch is a cladding temperature of 2200 °F (1204.4 °C) — 10 CFR 50.46 criterion 1, "the calculated maximum fuel element cladding temperature shall not exceed 2200F". It is a clad limit, not a fuel one, and the fuel runs far hotter than the clad in normal operation. 1200 °F (648.9 °C) is a third quantity — GEND-061's onset of significant hydrogen generation. On this ride none of the three is reached
A quench tank / pressurizer relief tankThere is none (12 §13.0). Relief and safety discharge go directly to the containment atmosphere, where a real plant fills a relief tank and bursts its rupture disc first
The condensate polisherNo polisher model — the board's polisher status is behavioural, not a resin condition, so the historical initiator is narrated rather than injected. Modelling it was costed against giving it a failure-registry row and a board command, and declined on player complexity rather than on fidelity. The walkthrough's step 2 is that narration
A partial injection throttleInjection is one On / Off control merging the high- and low-head pumps (03 §11.0). TMI-2's crew shut two makeup valves, throttled two more and stopped one of three pumps. Here the same decision is all or nothing, which makes it a starker choice than the crew faced
Offsite release and doseNo source term, no release model, no radiation monitors. The simulation ends at fuel damage (12 §13.0)

Where the numbers come from, and how far they carry. Every plant figure in §2.0–§5.0 was taken on one continuous full-stack ride from Hot Full Power on 2026-09-08. To 15 minutes that ride and the engine-direct rides agree within 3 %; at 30 minutes within 3.4 %. **Past 50 minutes the figures are the shipped plant's alone** — the auxiliary-feed level-hold channel throttles feed there, which holds the primary near 1020 psi (7.033 MPa) instead of letting it fall, and it is the reason the accumulators never dump. Numbers past 30 minutes were taken on a scripted ride whose holds are not a player's route; treat them as the shape of the ride, not as step targets.


7.0 Sources

Primary — the chronology and the operator reasoning.

DocumentWhat it carries
NUREG/CR-1250, Vol. II, Part 2 — Three Mile Island: A Report to the Commissioners and to the Public, NRC Special Inquiry Group (Rogovin), January 1980§II.A Sequence of Physical Events and Appendix II.1 Sequence of Events — the numbered event table (E<n> above) with the information available to the operators and the post-accident calculations in adjacent columns
NUREG/CR-1250, Vol. I — Narrative of the AccidentWhat the operators believed and why; quoted above for the training, the "going solid" rule and the block-valve closure
GEND-061 — TMI-2 hydrogen burn reportCore inventory, the burn, the 2772 MWt rating, the oxidation onset; its "almost 30 lb/in² gage" burn pressure corroborates Appendix II.1's 28 psig (0.193 MPa)
IE Bulletin 79-06A — Review of Operational Errors and System Misalignments Identified During the Three Mile Island IncidentThe regulator's immediate instructions to licensees
IE Bulletins 79-05C / 79-06C — Nuclear Incident at Three Mile Island — SupplementThe follow-on supplement

Why Appendix II.1 and not NUREG-0600 or NSAC-1. The appendix states in its own introduction that it is the reconciliation of those two plus the utility's own sequence: *"An attempt has been made to reconcile discrepancies found in other published sequences."* It also flags the disagreements it could not reconcile and names which reference it believes.

NOT in this project's source corpus, stated plainly: the Kemeny Commission report and NUREG-0600 were both sought and neither was obtained — NUREG-0600's full text 404s at its public identifier and it is not in the NRC's web document store; the Kemeny report is not carried by the archive the others came from. Nothing in this chapter rests on either.

A trap for anyone re-extracting the appendix. pdftotext -layout **mis-assigns Appendix II.1's Event column by one row**, printing "Reactor trips on high pressure" against the 3-second event instead of the 8-second one — exactly the distinction §2.0 turns on. Both documents are laid out in columns, so grepping a text rendering for a quote returns zero even when the quote is right; read down the column by its x-offset.

7.1 Related documents in this set

DocumentFor
07_ABNORMAL_EMERGENCY.mdPWR-E01 loss of main feedwater, PWR-E07 stuck-open relief valve, PWR-E08 relief indicator stuck closed, PWR-E11 degraded injection, PWR-E12 aux feed failure
06_ALARM_RESPONSE.mdPWR-A07 PORV OPEN, PWR-A10 LO SUBCOOL, PWR-A11 SUBCOOL LOST, PWR-A12 PZR LVL HI, PWR-A27 RCP CAVITATION
03_CONTROLS_AND_INDICATIONS.md§6.0 relief and block valve, §7.3 letdown orifices, §11.0 injection, §17.4 the reset permissive
09_SETPOINTS_LIMITS.mdThe trips, permissives and actuation setpoints quoted above
12_SIM_PHYSICS.mdWhat this simulation computes and what it leaves out

These manuals are licensed CC BY 4.0 — see Legal. Training documents for an educational simulator, not licensing-basis documents for a real plant.