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Nuclear Coatings Inspection Specialty Practice Test

AMPP-Nuclear exam Format | Course Contents | Course Outline | exam Syllabus | exam Objectives

Exam Code: AMPP NCIS
Exam Name: Nuclear Coatings Inspection Specialty (NCIS)
Number of Questions: 75 multiple-choice questions
Time Allotted: 2 hours.
Passing Marks: Pass/Fail (no numerical score provided; candidates receive a post-exam chart of strengths and weaknesses by domain).

Topic 1: Nuclear Power Plant (NPP) Operations- Work Procedures- and Industry Terminology
- NPP Operational Cycles: Reactor startup- normal power operation- shutdown- and refueling outages; role of coatings in maintaining structural integrity during thermal cycling and steam exposure.
- Work Procedures: Lockout/tagout (LOTO) procedures- confined space entry- hot work permits- and radiological work permits (RWPs); integration of coatings inspection into outage schedules.
- Safety and Administrative Controls: Personnel training- access controls- dosimetry monitoring- and decontamination processes; emphasis on verbatim compliance with procedures in safety-related areas.
- Industry Terminology Overview: Basic terms related to coatings in nuclear contexts- including exposure conditions like ionizing radiation- chemical sprays- and abrasion.

- Pressurized Water Reactor (PWR): A nuclear reactor type where water is kept under pressure to prevent boiling- used in ~60% of U.S. NPPs; coatings must withstand high-temperature steam.
- Boiling Water Reactor (BWR): A reactor where water boils in the core to produce steam; coatings face direct steam and suppression pool immersion.
- Radiation-Controlled Area (RCA): Designated zones in NPPs with potential radiation exposure; all work requires dosimetry and contamination surveys.
- Radiological Work Permit (RWP): Authorization document specifying dose limits- protective equipment- and decontamination requirements for work in RCAs.
- Lockout/Tagout (LOTO): Safety procedure to isolate energy sources before maintenance; critical for coatings work near electrical or steam systems.
- Decontamination Factor (DF): Measure of coating removability of radioactive contaminants; higher DF indicates easier cleanup.
- Qualified/Unqualified Coatings Inventory (QUCI): Plant-wide database tracking all coatings as qualified (meeting DBA criteria) or unqualified (non-safety-related).

Topic 2: Recognition of Industry Regulatory Organizations Worldwide
- U.S.-Focused Regulators: NRC's oversight of licensing- inspections- and enforcement; integration with ASTM/ANSI standards for coatings.
- International Organizations: IAEA's global safety standards; OECD/NEA's technical cooperation; regional groups like ENSREG for EU harmonization.
- National Regulators: Examples from major nuclear-operating countries- including their coatings-specific guidelines.
- Standards Bodies: Role of ASTM and ANSI in developing nuclear-specific coating qualification tests.

- U.S. Nuclear Regulatory Commission (NRC): U.S. federal agency regulating commercial nuclear power; enforces 10 CFR 50 Appendix B for QA in coatings.
- International Atomic Energy Agency (IAEA): UN-affiliated body promoting peaceful nuclear use; issues Safety Standards Series (SSR-2/1) for coatings in containment.
- Nuclear Energy Agency (NEA): OECD agency for advanced nuclear countries; develops guidelines via Committee on Nuclear Regulatory Activities (CNRA).
- European Nuclear Safety Regulators Group (ENSREG): EU forum for harmonizing nuclear safety; reviews coatings in stress tests post-Fukushima.
- ANSI N5.12: American National Standard for protective coatings in water-cooled NPPs; replaced by ASTM equivalents for qualification.Regulatory Guide 1.54 (RG 1.54)NRC guide on QA for protective coatings; requires DBA qualification for CSL I areas.

Topic 3: Performing Inspections in Various Areas of an NPP
- Inspection Areas: Containment (CSL I)- RCA outside containment (CSL II)- and non-RCA (CSL III); wet vs. dry areas.
- Methods and Tools: Visual examination (VT-1/VT-3 per ASME Section XI)- holiday detection- adhesion pull-off tests- and dry film thickness (DFT) measurements.
- Documentation and Reporting: Use of inspection checklists- defect classification (e.g.- blisters- cracks)- and integration with plant QA programs.
- Challenges: Working under RWPs- in high-radiation fields- or during outages; post-DBA debris assessment.

- Visual Testing (VT-1/VT-3): ASME-qualified surface examination; VT-1 for general surfaces- VT-3 for accessibility in nuclear inspections.
- Holiday Detection: Non-destructive test using low/high-voltage to detect pinholes or voids in coatings.
- Dry Film Thickness (DFT): Measured coating layer depth post-cure; must meet spec (e.g.- 5-10 mils for epoxies).
- Adhesion Pull-Off Test (ASTM D4541): Measures bond strength between coating and substrate; minimum 200 psi for nuclear apps.
- Blistering (ASTM D714): Coating defect rated by size/frequency; critical in DBA-exposed areas.
- Degraded Coating: Failure mode (e.g.- chalking- cracking) requiring condition assessment per ASTM D5163.

Topic 4: Purpose- Criteria- and Types of Qualified NPP Coatings
- Purpose: Protect against corrosion- radiation- chemicals; ensure no debris in emergency core cooling systems (ECCS).
- Qualification Criteria: Testing per ASTM D5144 for radiation (ASTM D4082)- chemicals (ASTM D3912)- and fire (ASTM E84).
- Types: Safety-related (qualified) vs. non-safety (acceptable); shop-applied vs. field-applied.
- Evaluation: Physical properties (abrasion per ASTM D4060)- fire resistance- and post-exposure integrity.

- Qualified Coating: Meets DBA- radiation- and chemical tests per ASTM D5144; used in CSL I areas.
- Acceptable Coating: Non-safety-related; no formal DBA qualification but evaluated for RCA use.
- Epoxy Coating: Common nuclear type; provides chemical resistance and adhesion to steel/concrete.
- Phenolic Lining: High-temperature resistant for containment liners; withstands steam at 300°F+.
- Gamma Radiation Resistance: Ability to endure 10^7-10^8 rads without embrittlement (ASTM D4082).
- Decontamination (ASTM D4256): Test for removable contamination; coatings must achieve >90% efficiency.

Topic 5: Developing and Managing a Safety-Related Coatings Program
- Program Development: Align with RG 1.54; include training- procurement- and auditing.
- Management: Q UCI tracking- non-conformance handling (ASTM D7491)- and condition assessments (ASTM D5163).
- Maintenance: Periodic inspections- repair strategies- and vendor qualification.
- QA Integration: Audits- records retention- and compliance with NQA-1.

- Safety-Related Coating: Applied to structures/systems/components (SSCs) vital to accident mitigation.
- Non-Conforming Coating: Degraded- unqualified- or unknown; managed via disposition (remove/repair) per ASTM D7491.
- Condition Assessment Program: Scheduled monitoring of CSL I coatings; uses visual and adhesion tests (ASTM D5163).
- NQA-1: ASME QA standard for nuclear facilities; covers coatings procurement and application.
- EPRI Report 1019157: Guideline for nuclear coatings selection- application- and maintenance.

Topic 6: Classifying Surface Preparation and Coating Application for Different Coating Service Level (CSL) Areas
- CSL Classification: I (DBA-qualified)- II (radiation-resistant)- III (general industrial).
- Surface Preparation: Abrasive blasting (SSPC-SP 10)- power tool cleaning (SSPC-SP 3); profile measurement (ASTM D4417).
- Application Techniques: Brush/roller for touch-up- spray for full coats; environmental controls (dew point- temp).
- Differences by CSL: Stricter QA for CSL I (e.g.- qualified applicators per ASTM D4228).

- Coating Service Level I (CSL I): Safety-related in containment; requires DBA qualification and strict prep (Sa 2.5 blast).
- Coating Service Level II (CSL II): RCA outside containment; no DBA test but radiation/chemical resistance needed.
- Coating Service Level III (CSL III): Non-RCA; general coatings like service water linings; minimal qualification.
- Surface Profile: Anchor pattern roughness (e.g.- 2-3 mils) for adhesion; measured via replica tape (ASTM D4417).
- SSPC-SP 10: Near-white blast cleaning; standard for CSL I steel prep.
- Qualified Applicator: Certified per ASTM D4228; demonstrates proficiency on test panels.

Topic 7: Matching Coating System Type and DBA Qualification Requirements
- System Types: Multi-coat systems for steel/concrete; immersion vs. atmospheric service.
- DBA Requirements: Simulate loss-of-coolant accident (LOCA) per ASTM D3911; no debris >0.125 in. post-test.
- Matching Process: Evaluate substrate (ferritic steel- stainless)- environment (pH 2-12 sprays)- and performance data.
- Requalification: When to retest (e.g.- formulation changes) per ASTM D8104.

- Design Basis Accident (DBA): Worst-case event (e.g.- LOCA); coatings must survive without debris impacting ECCS.
- Loss-of-Coolant Accident (LOCA): Pipe break releasing steam/chemicals; DBA test simulates 340°F/150 psig for 100 days.
- Debris Limit: Post-DBA- <1% weight loss and no chunks >0.125 in. diameter (ASTM D3911).
- Coating System: Multi-layer (primer- intermediate- topcoat); e.g.- inorganic zinc + epoxy for containment.
- Simulated DBA Test: Environmental chamber exposure to steam- radiation- and borated water sprays.

Topic 8: Determining and Applying Required Qualifications to Meet Industry and Plant-Specific ANSI and ASTM Standards
- ANSI/ASTM Framework: Use D5144 as umbrella; sub-standards for tests (D4082 radiation- D3912 chemicals).
- Qualification Process: demo prep (ASTM D5139)- testing- and data applicability (ASTM D8104).
- Plant-Specific Application: Customize for licensing basis; inspector certification (ASTM D4537).
- Compliance Verification: Audits- records- and peer reviews for CIP Level 3 Nuclear Specialty.

- ASTM D5144: Guide for protective coating standards in NPPs; covers qualification for CSL I/II/III.
- ANSI N101.2: Legacy standard for containment coatings; superseded by ASTM but referenced in licenses.
- Coating Qualification Test Document: Plant-specific plan outlining tests (radiation- DBA- fire) per RG 1.54.
- Inspector Certification (ASTM D4537): Procedures for qualifying personnel; requires training- exams- and experience for nuclear work.
- 10 CFR 50.49: NRC rule for environmental qualification of safety-related equipment- including coatings.
- Fire Resistance (ASTM E84): Class A rating required for CSL I; measures flame spread/smoke development.

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Question: 1437
Safety-related coatings must remain effective after a design basis fire event. Which test or criterion best
evaluates this according to EPRI guidelines?
A. ASTM D5163 adhesion test after thermal aging at rated temperatures
B. Visual inspection for discoloration only
C. Smoke toxicity and flammability testing under ASTM E162 and ASTM E662
D. Chemical resistance to inorganic acids
Answer: C
Explanation: Fire safety evaluation includes smoke toxicity and flammability per ASTM E162 and E662
to ensure coatings do not contribute to fire hazards, essential under design basis fire conditions. Adhesion
and aging tests are important but secondary to fire safety.
Question: 1438
High-complexity: Nuclear shield wall steel to SSPC-SP 10, D4417 2.5 mils; D4228 demo with 10%
overspray. Formula for efficiency = (applied volume / total sprayed) x100 >90%. Mitigations?
A. Adjust gun distance to 12 inches, re-measure efficiency
B. Peak density 220 peaks/inch� min
C. Bake panels at 200�F for 1 hour post-apply
D. Oil extraction per D7393 on abrasive <50 mg/kg
Answer: A, D
Explanation: Distance adjustment boosts transfer efficiency per D4228. Oil limit per D7393 prevents
defects in shields.
Question: 1439
At a BWR Mark I containment during a 2024 steam dryer replacement outage, the inspector assesses a
degraded vinyl ester coating on the torus suppression pool baffle after exposure to two-phase flow at
120�C and 0.3 MPa, revealing intercoat delamination per ASTM D5179 tape test rated 1. Holiday testing
shows 15 defects/m�. Using the delamination propagation model d = s � t � (1 - ?) / E, where s=stress
20 MPa, t=thickness 15 mils, ?=Poisson 0.35, E=modulus 3 GPa, compute d=0.08 mm. Identify all
mandatory repair sequences and quality control metrics per ANSI/ANS-56.8 for hydrodynamic loading
resistance.
A. Remove delaminated areas via needle gun to Sa 2.5 per ISO 8501-1, then spot-repair with 100%
solids epoxy at 10 mils DFT, curing via IR lamp at 150�C for 2 hours.
B. Verify repair adhesion with X-cut test per ASTM D3359 Method A, requiring 5B rating, and perform
pull-off to 800 psi minimum per ASTM D4541 on 5-grid pattern.
C. Simulate hydrodynamic impulse with water jet at 200 psi, 30� angle, 1 m distance, ensuring no
disbondment >2% area per mock-up test per NUREG-0800 Branch 5.2.1.
D. Calculate coating stress under LOCA using finite element analysis (FEA) with ANSYS, inputting
Young's E=3 GPa, yield strength 50 MPa, and validate model against strain gauge data at 0.5% strain.
Answer: A, B, C
Explanation: BWR torus baffles endure cyclic two-phase flow inducing shear stresses that propagate
delamination in vinyl ester coatings, risking debris in ECCS sumps during accidents. The model predicts
0.08 mm crack growth, nearing critical 0.1 mm threshold, mandating removal to Sa 2.5 for clean
substrate, followed by epoxy spot-repair for chemical resistance in wet environment, with IR curing
accelerating to outage timeline. Adhesion verification via X-cut (5B no lift-off) and pull-off (800 psi for
hydrodynamic durability) ensures repair integrity per ASTM standards. Hydrodynamic simulation with
jet testing replicates LOCA bubble collapse forces, limiting disbondment to prevent failure modes in
NUREG-reviewed designs. FEA is design-phase tool, not repair QC; strain validation supports but isn't
sequential step.
Question: 1440
When transferring qualification data between plants, which ASTM approach ensures applicability
regarding substrate composition differences?
A. Assuming all carbon steels behave identically without consideration
B. Evaluation according to ASTM D8104 focusing on substrate metallurgical similarity
C. Matching only the nominal steel thickness value
D. Ignoring substrate differences if coating system is certified elsewhere
Answer: B
Explanation: ASTM D8104 emphasizes assessment of metallurgical and surface compatibility to verify
applicability of qualification data, as substrate chemistry can significantly impact coating performance.
Question: 1441
A coating removal process provides a DF of 5 on a radioactive surface. The plant requires minimum DF
of 10 for reusable coatings. What is the status of this coating?
A. Coating qualifies as safe for reuse with slight remediation
B. Coating is unqualified due to insufficient removal of contamination
C. Coating can be used for non-safety applications only
D. Coating requires additional radiological monitoring but remains qualified
Answer: B
Explanation: The coating does not meet minimum DF criteria (which is 10) set by the plant for safe
reuse; therefore, it is categorized as unqualified for reuse in safety-related applications.
Question: 1442
During application of a CSL I epoxy coating on a containment sump strainer, the applicator must
maintain environmental controls per ASTM D4228. In a scenario with ambient conditions of 85�F and
75% RH, which controls and measurements must be implemented to ensure defect-free application?
A. Dew point measurement every 4 hours, maintaining surface temp =5�F above dew point
B. Substrate temperature control at 80-100�F, Tested with infrared thermometer per ASTM E1862
C. Relative humidity reduction to <60% using dehumidifiers with 500 cfm capacity
D. Airflow monitoring at 50-100 fpm in spray booth, per ANSI Z9.3 ventilation standards
Answer: A, B, D
Explanation: ASTM D4228 mandates environmental controls for CSL I coatings to prevent moisture
entrapment. Dew point =5�F above surface temp avoids condensation, critical for adhesion in sumps
exposed to LOCA sprays. Substrate temp of 80-100�F ensures proper cure kinetics, avoiding amine
blush. Airflow at 50-100 fpm removes overspray, maintaining DFT uniformity within �10% of 10 mils,
ensuring strainer integrity.
Question: 1443
Scenario: A PWR enters a 45-day refueling outage (RFO) after 18 months at 95% capacity factor, with
reactor coolant system (RCS) drained to mid-loop for inspections. Coatings on the refueling canal exhibit
chalking (ASTM D4214 rating 3) due to prior borated water exposure at pH 4.5. Procedure follows NRC
Bulletin 89-01 and AMPP SP0892 for nuclear-specific inspections. As the inspector, which complex
evaluations and procedural steps must you perform to restore operability before reenabling fuel handling?
A. Quantify chalking extent via ASTM D659-14 surface tension measurement, requiring >30 dynes/cm
for rewettability, and apply de minimis criteria per RG 1.82 allowing up to 5% affected area if no loose
particles >0.125 inch diameter.
B. Execute a full Qualified/Unqualified Coatings Inventory (QUCI) per EPRI TR-101248, categorizing
the system as Safety-Related Coating System (SRCS) and verifying post-repair qualification under
LOCA simulation at 315�C/150 psig for 30 days.
C. Perform holiday detection per NACE SP0188 using 30 kV DC pulse on 20 mil DFT, documenting
holidays as Coating Degradation Mechanism (CDM) Type 3 (pinholes), and calculate repair epoxy
volume: V = A * t * (1 - p), where A=100 m�, t=15 mil, p=0.9 porosity.
D. Initiate radiation survey per 10 CFR 20.1501 with smear tests <5000 dpm/100 cm� beta-gamma,
followed by surface prep to SSPC-SP 10 near-white metal and recoating with Carboline Carcothane 134
HG polyurethane per manufacturer PDS.
Answer: A, B, D
Explanation: In PWR RFOs, chalking in refueling canals from borated water (pH 4.5, ~2500 ppm B)
degrades epoxy integrity, risking particulate release during fuel movement that could clog fuel transfer
tubes per NRC Bulletin 89-01. ASTM D659 surface tension measurement assesses cleanability, with de
minimis thresholds per RG 1.82 permitting minor defects if particles are controlled to prevent ECCS
interference. Q UCI per EPRI ensures SRCS compliance, mandating LOCA qualification to confirm no
>1% weight loss or cracking post-exposure, critical for post-outage licensing. Holiday detection per
NACE SP0188 identifies voids in 20 mil systems, classifying as CDM to prioritize repairs, though
volume calculation aids material planning but isn't a direct procedural step. Radiation surveys per 10
CFR 20 confirm fixability (<5000 dpm limits), enabling SSPC-SP 10 prep (achieving <3% staining) and
application of nuclear-qualified polyurethanes like Carcothane 134 HG (per PDS: 4-6 mil DFT, pot life 4
hrs at 70�F), ensuring 99% solids for minimal VOC during confined space work.
Question: 1444
In a nuclear HVAC duct coating (atmospheric, galvanized steel), a single-coat acrylic is proposed.
Previous qual on ferritic. DBA test shows 0.18 in. debris in airflow. Calculate duct velocity increase if 10
ducts, 5000 cfm each, debris blocks 5% area. Select requalification.
A. Change to two-coat epoxy/urethane, primer 3 mils, topcoat 4 mils for adhesion to zinc
B. Requalify per ASTM D8104 with galvanized substrate, 1000 h ASTM D2247 humidity; no corrosion
>5%
C. Simulate DBA airflow: 50 ft/s, 300�F, 50 Mrad; debris <0.05 in.
D. Update matching to exclude concrete; galvanized system isolated
Answer: A, B
Explanation: Multi-coat required for galvanized adhesion. Humidity test verifies zinc compatibility. DBA
airflow prevents loose debris in ventilation.
Question: 1445
A coating system in a nuclear plant exhibits delamination after several thermal cycles involving rapid
cooling. Which modification would Excellerate its resistance to such conditions?
A. Incorporation of elastomeric components to enhance flexibility
B. Increasing the coating�s hardness by adding mineral fillers
C. Reducing overall coating thickness to minimize stress accumulation
D. Applying a thin primer layer with high permeability
Answer: A
Explanation: Elastomeric components Excellerate the coating�s flexibility, allowing it to absorb thermal
stresses during rapid cooling cycles and prevent delamination. Increasing hardness or reducing thickness
alone may not address the flexibility needed, and a high-permeability primer could exacerbate
environmental ingress.
Question: 1446
Scenario: HTGR phenolic at 330�F, 10^7 rads, then mixed nuclide decon D4256, 93% for Cs/Co. Use
MCNP code for dose simulation, F4 tally for flux. Which inspections?
A. Flux f <10^{14} n/cm�s equivalent for gamma
B. Nuclide-specific DF >20 via gamma spec
C. Post-decon adhesion pull-off 2,000 psi D4541
D. MCNP variance reduction <5% for accuracy
Answer: B, C, D
Explanation: DF >20 per gamma spec verifies 93% for mixed per D4256. Pull-off 2,000 psi ensures
lining post-decon/irradiation. MCNP <5% variance validates simulation tying to D4082.
Question: 1447
In a nuclear coating system failure investigation post-DBA test, which factor would most likely
contribute to excessive coating debris formation?
A. Use of topcoat with polyurethane content
B. Excessive coating thickness over 500 microns
C. Use of inorganic zinc primer instead of organic zinc
D. Improper curing leading to weak cohesion between layers
Answer: D
Explanation: Improper curing compromises the bond strength inside and between coating layers, causing
them to break apart under thermal and chemical stress, producing debris. Thickness, material choice, and
polyurethane content are secondary if curing is deficient.
Question: 1448
In a nuclear facility, a CSL III alkyd coating on auxiliary building piping requires touch-up after
mechanical damage. Per SSPC-SP 3 (power tool cleaning), which preparation steps and acceptance
criteria must be met for brush-applied repairs?
A. Surface cleaning to St 3, removing all loose rust with 80-grit flap disc at 10,000 rpm
B. Feathering edges to 1:3 taper ratio, Tested by caliper measurement per ASTM D4138
C. Post-cleaning solvent wipe with MEK, ensuring <5 �g/cm� residue per ASTM D4262
D. Profile verification at 1-1.5 mils using ASTM D4417 Method B (stylus instrument)
Answer: A, B
Explanation: SSPC-SP 3 for CSL III touch-ups requires St 3 cleanliness, achieved with abrasive discs to
remove rust, ensuring adhesion >150 psi for non-critical piping. Feathering at 1:3 blends repair edges,
preventing stress risers that could lead to peeling under thermal cycling (50-150�F). These steps align
with ASTM D4138 for seamless integration, maintaining corrosion protection without stringent CSL I
controls.
Question: 1449
A coating system qualified under ASTM D5144 exhibits a loss in adhesion after chemical exposure per
ASTM D3912. What remedial action should be documented before field application?
A. Requalification with revised chemical resistance testing and possible reformulation
B. Acceptance based on radiation resistance alone per ASTM D4082
C. Extending cure times without retesting
D. Substituting chemical testing with accelerated UV exposure tests
Answer: A
Explanation: Loss of adhesion after chemical resistance testing indicates insufficient performance; the
system must be requalified possibly with reformulation before plant application to meet nuclear safety
standards.
Question: 1450
A coatings inspector in a BWR standby liquid control (SLC) system RCA encounters sodium
pentaborate residue on degraded vinyl coatings, with B-12 (short-lived neutron capture) transients. RWP
specifies neutron monitoring. Which neutron survey settings and decon formulas must be applied for
residue removal?
A. Neutron rem-ball (e.g., Thermo 75-10), moderated with 10B polyethylene, energy response 0.025 eV-
15 MeV, count rate <1 cpm background, alarm >0.1 mrem/hr.
B. Decon: 10% boric acid rinse (5% B-10, pH 7), followed by NaOH scrub (2N, 140�F), efficiency E = 1
- (Post / Pre), target >95% via gamma spec for B-12 daughters.
C. Dose equiv calc: H*(10) = f_thermal � 2.7 (rem-sec/cm� per n/cm�/s) � Q=10, for 1E4 n/cm�/s flux,
ensuring <50 mrem for 30 min.
D. Post-decon air: Sniffer probe for thermal neutrons (He-3 tube, 0.5 eV cutoff), scan at 6 inch/s, log
variances >2s for RWP closeout.
Answer: A, B, C
Explanation: SLC residues induce B-12 (0.95 MeV gamma, 20 ms half-life) via capture on B-10 (n,a),
per ANL physics models, requiring rem-balls for quality factor 10 fast neutrons. Boric rinse leverages
isotope exchange, NaOH for alkali solubles, E formula per IAEA decon guides. Flux-to-dose uses ICRP
74 conversion for tissue kerma; sniffer verifies but is secondary to primary neutron.
Question: 1451
A nuclear coatings inspector is verifying applicator qualification for CSL I coating application. Which
documentation best confirms a qualified applicator?
A. Manufacturer�s recommendation letter for the applicator
B. Certificate of performance per ASTM D4228 showing successful skill demonstration
C. Completion of a common industrial paint application course
D. Supervisory approval on jobsite without certification
Answer: B
Explanation: ASTM D4228 certification is the recognized standard for verifying applicators qualified to
apply nuclear CSL I coatings, ensuring skill in thickness control, coverage, and appearance critical to
nuclear safety.
Question: 1452
EPRI Report 1019157 Section 4.5 maintenance for submerged safety-related coatings in condenser pits
specifies biofouling controls. In a zebra mussel infestation scenario, which treatments and verifications?
A. Chlorination at 5 ppm free Cl2 for 24 hours, followed by dechlor flush to <0.1 ppm
B. Ultrasonic cleaning at 20 kHz, 120 dB, removing >95% biomass per ASTM G121 weight loss
C. Post-treatment inspection via borescope, no fouling thickness >0.1 inch per 10 ft�
D. Biocide compatibility soak, <2% adhesion loss per ASTM D543 after 30 days
Answer: A, C, D
Explanation: EPRI addresses fouling eroding pit coatings. Chlorination targets mussels without
delamination. Borescope confirms cleanliness for flow. Soak verifies biocide inertness, maintaining
barrier.
Question: 1453
During a coating inspection, an inspector discovers inconsistent documentation in QA records. According
to NQA-1 requirements, how must this be addressed?
A. File the records as-is with a notation of discrepancy
B. Initiate a record review and corrective action to ensure completeness and accuracy
C. Discard the records and redo the inspection
D. Ignore if physical inspections were satisfactory
Answer: B
Explanation: NQA-1 mandates thorough record management, requiring corrective measures when
discrepancies arise to maintain QA integrity.
Question: 1454
Under RG 1.54, a 2026 NRC inspection at a U.S. BWR assesses epoxy coatings on containment sumps
for DBA debris resistance at 0.5 m/s flow. Which qualification steps address incomplete debris data?
A. Debris testing per ASTM D7109 at 0.5 m/s, with ablation <4%
B. Post-debris adhesion testing per ASTM D4541, requiring pull-off strength >1000 psi
C. CFD modeling with drag coefficient C_d = 0.5, predicting particle settling <0.05 g/cm�
D. Documentation per 10 CFR 50.49, with test logs at �3% flow accuracy
Answer: A, B, D
Explanation: RG 1.54 requires debris resistance for sump coatings. ASTM D7109 verifies ablation. Post-
debris adhesion per D4541 ensures integrity. Documentation per 50.49 logs conditions. CFD modeling is
analytical.
Question: 1455
Which method is preferred for measuring surface profile in nuclear coatings inspection and why?
A. Visual comparison to standard profile charts for quick evaluation
B. ASTM D4417 Method B (Replica Tape) for non-destructive accurate profile measurement
C. ASTM D4417 Method A (Micrometer) for rough surfaces
D. Thickness gauge readings for profile assessment
Answer: B
Explanation: Replica tape (Method B) allows precise, non-destructive measurement of surface profile
critical for verifying nuclear coating substrate preparation, making it highly preferred over subjective
visual methods or less accurate mechanical gauges.
Question: 1456
During a DBA qualification trial for a PWR containment liner coating, steam at 340�F induces blistering
visible under 10x magnification. Using ASTM D714 standards adapted for nuclear post-accident
functionality, which blister size-frequency pairs necessitate requalification of the entire system batch?
A. Medium No. 2 blisters on horizontal surfaces
B. Few No. 10 blisters uniformly
C. Dense No. 8 blisters in patches
D. Medium No. 4 blisters clustered
Answer: A, D
Explanation: In nuclear DBA testing, ASTM D714's medium No. 2 (large blisters, moderate frequency)
or medium No. 4 (moderate size, clustered) denote failure modes like vapor barrier loss, risking coating
detachment and ECCS impairment. These exceed allowable thresholds for CSL I, where even moderate
large-blister incidences can lead to >1 g/100 cm� debris yield, violating EPRI TR-109937 criteria. Few
No. 10 or dense small No. 8 are often deemed passable if leachables remain <10^-4 g/cm� per ASTM
D3862.
Question: 1457
ANSI N5.12 addressed protective coatings for which specific NPP system prior to the ASTM
replacement?
A. Water-cooled nuclear power plant systems including primary and secondary circuit components
B. Dry storage facilities exclusively
C. Non-nuclear HVAC systems
D. Electrical conduit protection only
Answer: A
Explanation: ANSI N5.12 targeted protective coatings within water-cooled NPP systems, providing
specifications for corrosion prevention before more comprehensive ASTM standards superseded it.
Question: 1458
A nuclear coatings inspector measuring surface profile following SSPC-SP 10 uses ASTM D4417
Method B (replica tape). The measurement reads 3.2 mils. The specification requires 2.5�3.0 mils. What
should the inspector recommend?
A. Accept as within tolerances considering measurement error
B. Apply coating with reduced dry film thickness to compensate
C. Reject surface preparation and request re-blasting to reduce profile
D. Approve if other surface cleanliness criteria are met
Answer: C
Explanation: Excessively high surface profile can lead to poor coating adhesion and rough surfaces that
compromise performance. Specifications are strict for nuclear applications. Measurement above upper
limits must be corrected by re-blasting to maintain coating integrity.
Question: 1459
During a BWR torus immersion coating inspection, a multi-layer system (epoxy primer 6 mils, glass-
flake vinyl ester 15 mils, novolac topcoat 12 mils) undergoes simulated DBA LOCA testing at 330�F,
120 psig, pH 5.5 borated spray, 80 Mrad TID. Post-test, 0.9% weight loss is recorded, but 0.13 in. debris
clogs mock ECCS strainers. Which parameters must be adjusted to meet debris limits?
A. Adjust spray chamber to cycle pH 4-6 over 60 days, verifying no blisters >#4 per ASTM D714
B. Incorporate 8% polymeric microspheres in topcoat to limit debris size to <0.10 in.
C. Recalibrate coating system DFT: primer 5 mils, vinyl ester 18 mils, novolac 15 mils; total >38 mils
D. Perform pull-off adhesion test per ASTM D4541; require >2500 psi post-DBA exposure
Answer: B, C, D
Explanation: Debris size 0.13 in. exceeds ASTM D3911�s 0.125 in. limit, risking ECCS strainer
blockage; microspheres reduce fragment size by enhancing film cohesion. Increased DFT strengthens the
multi-layer system, reducing weight loss and delamination under prolonged immersion. Post-DBA
adhesion >2500 psi ensures coating integrity in torus environments under thermal and radiation stress.
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