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For a small, well-characterized set of degraded tubes, qualified tube plugging is usually the safer immediate action. It isolates the affected tubes without the heavy lifting, welding, radiological work and restart risks of replacing an entire steam generator. Replacement is usually the safer lifecycle strategy when degradation is widespread, recurring, difficult to detect or predict, or when plugging is approaching the plant’s approved thermal, flow, leakage or accident-analysis limits.

There is no universal plugging percentage or one-size-fits-all answer. The licensee must use plant-specific inspection data, safety analyses, technical specifications and regulatory approvals to show that either action preserves the steam generator’s pressure boundary and the reactor’s operating and accident margins.

Why the choice matters

A pressurized-water reactor steam generator transfers heat between two closed loops. High-pressure primary water flows through thousands of tubes; a lower-pressure secondary system receives the heat and produces steam. The tubes therefore have two jobs at once: they are the heat-transfer surface and the pressure boundary separating potentially radioactive primary coolant from the nonradioactive secondary system.

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A tube failure can release primary coolant into the secondary side. For that reason, nuclear regulations require continuous attention to tube condition, limits on leakage and shutdown or corrective action when leakage exceeds the plant’s approved limits. The United States has steam generators in 65 pressurized-water reactors, with two to four generators per reactor unit, according to a 2013 Nuclear Regulatory Commission (NRC) description.

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The maintenance decision balances two different kinds of risk:

  • Tube-plugging risk: leaving fewer active tubes to carry heat and primary flow, while relying on inspection and plug integrity to control degradation.
  • Replacement risk: performing a major radioactive-component removal and installation project with heavy lifts, welding, quality-control and commissioning hazards.

The safer option is the one that leaves the greatest demonstrated margin for the specific unit, not necessarily the option that appears newest or least invasive.

When qualified tube plugging is safer

Localized damage with reliable inspection results

Plugging is a targeted removal-from-service action. If nondestructive examination identifies a tube that is too thin, cracked or otherwise outside the plant’s acceptance criteria, a qualified plug can isolate it from service. The remaining tube population continues to perform the heat-transfer function.

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This approach is strongest when the degradation mechanism is localized, the inspection method can reliably detect and size it, and engineers can establish a credible crack-growth or wear-growth expectation until the next inspection. The plant must also demonstrate that the plug design, installation procedure and verification tests are qualified for the location and loading involved.

Circumferential cracks that cannot be sized reliably

NRC Generic Letter 95-03 specifically addresses circumferential cracking. When an indication cannot be reliably sized and its growth rate cannot be predicted with confidence, the NRC states that the affected tube is removed from service by plugging or sleeving when detected. This is a defense-in-depth response to uncertainty: isolate the pressure boundary rather than rely on an optimistic estimate of remaining wall.

The generic letter records a case in which inadequate eddy-current procedures allowed severe degradation to remain undiscovered. Enhanced examinations and destructive testing measured maximum crack depths of 45%, 37% and 57% of tube-wall thickness in the examined tubes. Those figures are historical NRC findings from 1995, not a universal failure threshold, but they illustrate why inspection procedure qualification and data review are central to a plugging decision.

When the remaining margins are demonstrated

Plugging is acceptable only if the plant’s analyses show that the reduced number of active tubes still satisfies all applicable limits. The review normally covers:

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  • Heat-transfer capability at normal and limiting operating conditions.
  • Primary-side flow resistance and distribution.
  • Reactor power or steam-production capability.
  • Leakage limits and the consequences of a postulated tube rupture.
  • Structural and accident-analysis margins for the next operating interval.
  • Inspection intervals, examination sensitivity and expected degradation growth.

If those margins remain comfortably positive and the affected tubes can be isolated with a qualified method, plugging avoids the additional hazards of a replacement outage.

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When steam-generator replacement is safer

Widespread or recurring degradation

Replacement becomes the stronger option when many tubes are affected, the same mechanism keeps returning after repeated plugging, or damage is distributed through locations that are difficult to inspect. Plugging treats individual tubes; it does not remove a systemic cause such as a design, material or operating condition that continues to damage the population.

The European Commission’s Joint Research Centre (JRC) describes replacement projects involving stress-corrosion cracking, fretting, wear, pitting, denting and material problems. If a mechanism is likely to challenge a large fraction of the population during the expected service period, replacing the generators can provide more durable margin than accumulating plugs.

Plugging is approaching a plant-specific limit

Each plugged tube removes some heat-transfer surface and some primary flow area. The resulting effect depends on generator design, tube arrangement, operating power, flow distribution and accident analyses. There is no universal regulatory percentage at which replacement is mandatory.

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In a JRC model of the Spanish three-loop Westinghouse Ascó-2 plant, plugging about 12% of the tubes was around the limit for optimal reactor operation. That is a plant-specific modeled result, not a limit that can be applied to another reactor. A different unit may reach a thermal, flow, power or accident-analysis constraint at a lower or higher percentage.

Inspection cannot establish a defensible safety case

If the inspection method cannot reliably detect, size or trend the relevant degradation, the uncertainty itself becomes a safety issue. Continued operation would require assumptions about undetected damage and growth that may not be supportable. A replacement with a design and material selected to address the mechanism can reduce that uncertainty, provided the new design is fully verified.

What replacement fixes—and what it adds

Potential lifecycle benefits

Modern replacement generators have used more corrosion-resistant tube alloys than some early designs, according to NRC material. A properly selected design can reduce susceptibility to the mechanism that drove the original degradation and restore lost heat-transfer and structural margin.

Replacement also resets the population of active tubes. Instead of carrying an increasing inventory of plugs and an inspection program focused on a damaged legacy component, the plant begins operation with a new tube bundle subject to its own baseline examinations and surveillance plan.

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Heavy-lift and radiological hazards

The NRC describes replacement as work performed during a refueling shutdown, with hundreds of specialized workers removing old generators and installing new ones. The old components become low-level radioactive waste. The project therefore introduces hazards that do not arise from a single-tube plug:

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  • Fit-up, cutting and welding on safety-significant systems.
  • Contamination control and worker dose management.
  • Foreign-material exclusion during open-system work.
  • Quality-assurance hold points, documentation and independent inspections.
  • Nondestructive examination of welds and installed components.
  • System flushing, pressure testing, functional testing and restart verification.

These hazards can be managed, but they are real contributors to outage and commissioning risk. Installing new tubes does not automatically make the project safer than isolating a few degraded tubes.

Design and commissioning must be validated

The San Onofre experience cited in NRC materials demonstrates why replacement design, inspection and operating validation require scrutiny. A new generator can introduce flow-induced vibration, wear or other behavior if the design, fabrication or operating envelope is not adequately verified. Licensing review where applicable, baseline inspection, startup testing and early operating surveillance are part of the safety case.

Side-by-side safety comparison

Decision factor Qualified tube plugging Steam-generator replacement
Immediate barrier protection Isolates identified degraded tubes before leakage or rupture, provided the plug is qualified and correctly installed. Removes the old tube bundle, but protection depends on successful installation, testing and commissioning of the new generators.
Best fit Small, localized and well-characterized degradation with adequate remaining margins. Widespread, recurring or poorly characterized degradation, or plugging near a plant-specific limit.
Effect on heat-transfer area Decreases as tubes are removed from service; the effect must be analyzed for the specific unit. Restores the active tube population, subject to the new design’s verified performance.
Primary-flow effect Plugged tubes remove some flow area; hydraulic and flow-distribution margins must be checked. New geometry can change flow behavior and must be validated by design analysis and testing.
Outage execution risk Normally a focused inspection and repair activity, with no major component lift. Major refueling-outage project involving heavy lifts, radioactive-component handling, welding and restart testing.
Recurrence risk Remains if the underlying degradation mechanism continues to affect other tubes. Can reduce recurrence when the replacement design and materials address the mechanism; it does not eliminate the need for inspection.
Regulatory basis Inspection results, qualified repair method, leakage control, technical specifications and a safety assessment for continued operation. Approved design, fabrication and installation controls, licensing review where required, examinations and commissioning evidence.

How a plant decides between the options

  1. Identify the degradation mechanism. Determine whether the indications represent wear, corrosion, cracking, denting, pitting, fretting or another mechanism. The mechanism determines detectability, growth behavior and whether plugging addresses the cause or only the symptom.
  2. Confirm inspection reliability. Review eddy-current procedures, probe selection, calibration, analyst qualification, data-quality screening and independent review. Generic Letter 95-03 shows the consequence of inadequate procedures: severe damage can remain undiscovered.
  3. Characterize the affected population. Map indications by tube location, depth, length, orientation and operating history. Establish whether the damage is isolated or distributed and whether similar tubes may have been missed.
  4. Set the immediate disposition. Plug or sleeve tubes that exceed the plant’s acceptance criteria or cannot be reliably characterized. Circumferential cracks are removed from service on detection under the NRC guidance cited above.
  5. Recalculate remaining margins. Quantify the effect of inactive tubes on heat transfer, primary flow, power, leakage and accident response. Do not substitute a generic percentage for a unit-specific analysis.
  6. Project future degradation. Compare the expected growth and discovery rate with the next inspection interval and the plant’s planned remaining service. Include uncertainty, not only the best-estimate growth curve.
  7. Compare lifecycle outcomes. Estimate whether continued plugging preserves safe operation for the expected period or merely postpones an inevitable replacement. Include outage duration, worker dose, heavy-lift risk, waste handling, quality assurance and restart testing.
  8. Obtain the required approvals. Confirm compliance with technical specifications, surveillance requirements, approved repair criteria and any licensing or regulator notification obligations before returning the unit to power.

What happens during a plugging campaign

Inspection and data disposition

During a refueling outage, technicians perform the approved nondestructive examinations and classify indications against the plant’s tube integrity criteria. Analysts must distinguish reportable flaws from noise and assess whether the inspection can size the relevant damage mechanism. Any data-quality limitation must be treated as uncertainty, not as evidence that the tube is sound.

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Plug selection and installation

The plug must be qualified for the tube material, dimensions, pressure, temperature, chemistry and expected loads. Installation records identify the tube, plug type, procedure, technician and verification results. The plant then confirms that the repair does not create an unacceptable leakage path or interfere with future examination.

Post-repair evaluation

Engineers update the active-tube count and rerun the analyses affected by the changed tube population. If the resulting margins support continued operation, the licensee documents the technical basis and sets the next inspection scope and interval. A plug is not a waiver from future surveillance of the remaining tubes.

What happens during a replacement outage

Planning and licensing

Replacement starts years before the outage with design selection, procurement, fabrication surveillance, transport planning and work-package development. The plant must resolve interfaces with supports, piping, instrumentation, insulation, secondary-side equipment and containment structures. Licensing review is required where the design or analyses change the licensing basis.

Removal and installation

Workers isolate systems, control contamination, disconnect the old generators and execute the heavy lift under approved rigging and foreign-material controls. The new generators are positioned, connected and welded or otherwise joined according to qualified procedures. Radiographic, ultrasonic or other nondestructive examinations verify critical welds and interfaces.

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Testing and restart

Before startup, the plant performs pressure, leak, functional and system tests required by its procedures and technical specifications. Startup data are checked against design expectations, including flow, vibration and heat-transfer behavior where applicable. Any unexpected result must be resolved before the unit returns to normal operation.

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Does tube plugging reduce reactor power?

It can, but not automatically. Removing tubes reduces heat-transfer surface and primary flow area. Whether that requires a power reduction depends on the unit-specific thermal-hydraulic and safety analyses, the number and location of plugged tubes, operating conditions and the limits in the approved technical specifications.

The JRC’s Ascó-2 model reported no significant impact on modeled operator actions for a steam-generator tube rupture or a small-break loss-of-coolant accident with 12% plugging. That result supports moderate, qualified plugging in that particular model; it does not establish that another reactor can operate at the same percentage or power.

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How many plugged tubes is too many?

There is no universal answer. The practical limit is the point at which the plant can no longer demonstrate acceptable heat transfer, flow, power, leakage or accident performance for the intended operating period, or when the technical specifications require another action.

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A useful way to think about the limit is not just the percentage plugged, but the margin remaining after considering:

  • Where the inactive tubes are located and how they affect flow distribution.
  • The generator’s design heat-transfer capability and operating duty.
  • Expected future plugging before the next inspection and through planned service life.
  • Leakage and tube-rupture consequences under licensing-basis events.
  • Uncertainty in inspection sensitivity and degradation growth.

The approximately 12% Ascó-2 result is an example of a modeled operating boundary, not a regulatory threshold for all plants.

What the NRC expects before continued operation

The NRC’s decision logic is defense in depth: prevent uncontrolled degradation, detect it early and mitigate the consequences of a failed tube. A licensee seeking continued operation with degraded tubes must support the decision with evidence covering:

  • Inspection scope, sensitivity and data-analysis procedures.
  • Personnel qualification and independent review of examination results.
  • Crack-growth or wear-growth expectations and their uncertainty.
  • Tube leakage measurements and applicable technical-specification limits.
  • Structural and accident-analysis margins for the proposed operating interval.
  • A documented safety assessment and a justified next-inspection plan.

For circumferential cracks, the NRC language is explicit: tubes with those cracks are removed from service by plugging or sleeving when detected. Continued operation cannot be based solely on a general statement that the crack appears stable.

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Common decision errors

Choosing replacement simply because it is new

A new component may have better materials, but the replacement project creates its own lifting, welding, contamination and commissioning hazards. Safety depends on verified design performance, not age alone.

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Using a generic plugging percentage

Applying a percentage from another reactor or a published model can misstate the available margin. The Ascó-2 value is explicitly plant-specific. Each unit needs its own thermal, hydraulic, structural and accident analyses.

Treating a clean inspection as proof of no degradation

Inspection sensitivity, probe coverage, analyst qualification and data quality determine what a clean result means. If the procedure cannot reliably detect the relevant mechanism, uncertainty remains.

Ignoring recurrence

Repeated plugging can be safe for a defined interval, but it may be a poor lifecycle strategy when the same mechanism is damaging new tubes. The trend in indications matters as much as the current count.

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Forgetting restart risk

Replacement schedules often focus on the heavy lift and underestimate the time required for examination, flushing, testing, documentation and resolution of unexpected findings. Those activities are part of the safety case, not administrative overhead.

Practical decision checklist

  • Is the degradation mechanism identified and understood?
  • Can the approved inspection method detect and size it with demonstrated reliability?
  • Have all affected and potentially affected locations been examined?
  • Are degraded, ambiguous or circumferentially cracked tubes isolated as required?
  • Do updated analyses show adequate heat-transfer, flow, leakage and accident margins?
  • Is the projected plugging trend compatible with the remaining service period?
  • Would plugging address the immediate condition without leaving a systemic mechanism untreated?
  • Has a replacement project’s lifting, radiological, welding, quality-assurance and restart risk been included?
  • Are technical-specification, licensing and regulator-notification requirements satisfied?
  • Is the next inspection interval short enough for the uncertainty and expected growth?

Bottom line

Plugging is generally safer now when only a small, well-characterized group of tubes is degraded and the plant can demonstrate ample remaining margin. Replacement is generally safer over the plant’s service life when degradation is widespread, recurring, poorly characterized or pushing the unit toward its plant-specific plugging limits. The defensible choice comes from qualified inspection, conservative tube-integrity criteria, unit-specific safety analysis and approved operating limits—not from a universal tube count or the assumption that a new generator is automatically safer.

Frequently Asked Questions

Can a plant plug tubes and later replace the generators?

Yes. Plugging can provide an interim barrier-protection measure while the licensee plans a replacement, provided the reduced tube population remains within approved operating and accident-analysis limits during the interim period.

Are plugged tubes inspected again?

The plugged tubes are removed from service, while the remaining active population continues under the plant’s approved surveillance and inspection program. The scope and interval depend on the degradation mechanism, inspection reliability and technical basis.

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Does a replacement eliminate future tube inspections?

No. New generators require baseline examinations and continuing surveillance because material, fabrication and operating conditions can still produce degradation.

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