AMPP-Nuclear 시험 - AMPP실제시험문제와 답 - 1400문항

Question No : 1

PWR load follow ±10% power, T 310°C, holidays in polyurea (15 kV spark). RWP 2025-845 (14 mR/hr), LOTO on CRDM (600 V). Per 10 CFR 50.59 2025, which screening?

A.Holiday density ρ = N/A = 20 / 5 m² = 4/m² <5 limit, CDM electrical breakdown.
B.Decon kinetics k=0.1 hr^{-1}, t_1/2=6.93 hr for 90% reduction.
C.LOTO audit with voltage test <2 V at terminals.
D.Dose with angle Ω= π sterad, D= Γ t / r² * Ω/4π.

정답:
Explanation:
ρ <5/m² screens changes per 50.59. LOTO <2 V verifies. Angular D for fields; kinetics post.

Question No : 2

A nuclear facility's quality assurance audit reveals that the vinyl ester lining for a spent fuel pool (Coating Service Level II) was qualified using samples prepared with inconsistent substrate roughness, violating the ANSI/ASTM framework's reproducibility requirements.
Which elements of the umbrella standard ASTM D5144 and its sub-standards must be applied to rectify this for ongoing compliance?

A.Re-preparation of test panels per referenced ASTM D5139 with 100% coverage at 20 mils DFT and curing at 77°F/50% RH for 7 days
B.Radiation tolerance verification per ASTM D4082 at 2 x 10^7 rads with no more than 10% adhesion loss post-exposure
C.Chemical resistance spot tests per ASTM D3912 in demineralized water at ambient temperature for 30 days, checking for discoloration only
D.Integration of decontamination factor calculations from ASTM D5144 Section 6, targeting <1.0 mg/sq ft removable contamination

정답:
Explanation:
Under the ANSI/ASTM framework, ASTM D5144 ensures reproducible qualification for nuclear coatings, mandating consistent sample preparation to reflect field conditions; for vinyl ester linings in Level II pools, this invokes ASTM D5139 for panel specs including 20 mils dry film thickness (DFT) at 100% coverage, cured under controlled 77°F and 50% relative humidity for 7 days to mimic pool immersion. Radiation testing per ASTM D4082 is required for Level II areas outside containment, using a reduced dose of 2 x 10^7 rads with adhesion retention >90% to confirm no brittle failure. Decontamination efficacy per ASTM D5144 Section 6 must achieve <1.0 mg/sq ft removable activity via swip tests post-exposure, critical for radiological control. Chemical spot tests per ASTM D3912 are valid but must include quantitative metrics like weight loss (<2%) beyond visual checks for full validation in water-based environments.

Question No : 3

When performing ASTM D4256 decontamination tests, which factor most affects the coating’s apparent removal efficiency?

A.Type and application of decontaminant
B.Coating thickness uniformity
C.Gamma radiation dose history
D.Steam exposure duration

정답:
Explanation:
The nature of the decontamination chemical or process significantly influences contaminant removal effectiveness, directly impacting removal efficiency results in ASTM D4256.

Question No : 4

An inspector conducting a touch-up using brush and roller on a CSL I coating notices that the solvent content of the coating is higher than spray-applied material.
What is the best recommendation?

A.Use coating batch matched for solvent content and apply cross-hatch roller technique
B.Proceed with touch-up for expedience
C.Dilute spray coating to match touch-up batch solvent content
D.Avoid touch-up; entirely spray coat the affected area again

정답:
Explanation:
Variations in solvent content affect drying, texture, and adhesion. Matching solvent content and applying touch-up in cross-hatch roller strokes ensures smoother texture and maintains CSL I quality.

Question No : 5

In a nuclear fuel handling area, post-flooding test coatings exhibit varied blistering on a two-coat epoxy system.
According to ASTM D714 guidelines for nuclear service, which blister profiles require escalation to engineering for potential removal and reapplication to maintain radiological control zone integrity?

A.Dense No. 10 blisters uniformly across the surface
B.Medium No. 6 blisters in small clusters near floor drains
C.Few No. 4 blisters with patchy distribution
D.Dense No. 2 blisters covering overhead beams

정답:
Explanation:
While dense No. 10 (smallest size) may represent superficial pinholing tolerable in non-critical zones, medium No. 6 in clusters or dense No. 2 (largest size) signify severe delamination driven by hydrostatic pressure or contaminant ingress, critical in flood-prone nuclear areas where blister rupture could release alpha -emitting particulates. ASTM D714 emphasizes that frequency and size combinations exceeding medium for sizes >No. 6 or any dense for >No. 8 demand intervention to prevent ECCS strainer blockage, aligning with RG 1.54 endorsements for blister-free performance in DBA scenarios.

Question No : 6

In a nuclear power plant undergoing a post-LOCA containment sump debris assessment, an inspector identifies a Level II certified personnel under ASTM D4537 who has accumulated 1,440 hours of supervised nuclear coatings inspection over 12 months but failed to document 40 hours of annual visual acuity renewal training.
During a qualification audit, which of the following actions must the employer's certification authority initiate to restore compliance with ASTM D4537 procedures for this inspector to continue inspecting safety-related epoxy linings?

A.Administer a supplemental 40-hour training module on nuclear-specific inspection ethics and retest on NQA-1 alignment
B.Conduct a proficiency demonstration on a mock containment surface using ISO 8503 visual standards, followed by recertification exam
C.Immediately suspend the inspector's Level II status and require 80 hours of retraining per Table 1 of ASTM D4537 before reinstatement
D.Perform an equivalence evaluation under Section 7.3 of ASTM D4537, allowing substitution with 20 hours of hands-on wet film thickness gauging if prior performance records show no discrepancies

정답:
Explanation:
ASTM D4537 requires ongoing qualification maintenance for nuclear coatings inspectors, including annual visual acuity testing (typically 4-8 hours but scaled to 40 hours in complex scenarios involving detailed documentation). For Level II personnel, failure to document this triggers a multi-step restoration: supplemental ethics and NQA -1 training to reaffirm uniform interpretation of ANSI/ASME requirements, plus a practical proficiency demonstration on mock surfaces to verify conformance to specified nuclear facility standards like ISO 8503 for cleanliness. Suspension is not immediate unless safety compromise is evident; instead, equivalence under Section 7.3 allows limited substitution only if overall experience (1,440 hours minimum) and performance history support it, but full retraining to 80 hours applies only for lapsed general training, not isolated visual renewal. This ensures inspectors avoid compromising safety-related systems during critical post-LOCA assessments.

Question No : 7

Which Lockout/Tagout (LOTO) procedure step is NOT typically required before beginning coating inspection on energized electrical equipment in nuclear plants?

A.Verify energy isolation by testing the de-energized status with a voltmeter
B.Remove lockout devices prior to completing inspection for quick access
C.Notify affected personnel before lockout application
D.Apply locks and tags to all energy isolating devices

정답:
Explanation:
Removing lockout devices before inspection completion is strictly prohibited since it exposes personnel to energized equipment risks. All other steps are standard LOTO requirements ensuring safety during inspection.

Question No : 8

During review of coatings used in CSL I areas, an inspector notes the manufacturer certified compliance with ASTM D5144 but no actual test data for chemical resistance was submitted.
What is the proper course of action?

A.Reject the coating until full documented evidence of chemical resistance is provided
B.Accept based on manufacturer’s certification alone
C.Conduct onsite chemical resistance tests instead of reviewing documents
D.Consider it acceptable if direct bond adhesion data is present

정답:
Explanation:
Certification without substantiating test data is insufficient. Complete documented proof of all ASTM D5144 criteria including chemical resistance is mandatory for qualified coatings.

Question No : 9

CSL III dry wall, delam from vib. Low rad.

A.Adhesion D7234 900 psi, vib sim 10 Hz.
B.VT-3 borescope, area calc ellipse πab >2%.
C.DFT magnetic 0.1 mil, 8-mil.
D.QA code DEL-04, sketch freehand.

정답:
Explanation:
Dry delam adhesion vib-sim 900 psi. VT-3 ellipse >2%. DFT/sketch secondary.

Question No : 10

During application of a CSL I coating by spray, a qualified applicator notices reduced coating film thickness readings of about 15% below specification.
What is the best course of corrective action?

A.Continue spraying and accept minor deviations due to nuclear coating tolerance
B.Immediately stop and remove the coat for reapplication
C.Reduce coating thickness specification to match applied film thickness
D.Apply additional coating passes to achieve total film thickness specified

정답:
Explanation:
Achieving specified dry film thickness is critical for CSL I coatings due to safety requirements. Applying additional passes to meet minimum thickness is standard corrective practice unless the deficiency compromises coating integrity severely.

Question No : 11

During PWR shutdown cooldown to 93°C for mid-loop operations (boron 1500 ppm, pH 4.8), the inspector integrates coatings assessment on ECCS piping into outage critical path method (CPM) schedule per Primavera P6 v2025, with LOTO sequence: de-energize breakers CB-1A/1B at 480 VAC, tag per color-code red for danger (NFPA 70E Table 130.5(C)). Active RWP 2025-078 limits stay time to
2 hrs at 20 mR/hr.
Which verbatim procedural integrations and dosimetry parameters ensure Appendix B Criterion X (inspection) compliance without exceeding TEDE 100 mrem?

A.Sequence inspection post-LOTO verification Step 4.2.1: visual zero-energy state check with voltmeter Fluke 87V (<50 VAC threshold), then apply CPM float calculation FS = LF - EF = Day 15 - Day 12 = 3 days slack for blister rating per ISO 4628.
B.Calculate stay time t = D_limit / R = 100 mrem / 20 mR/hr = 5 hrs max, but cap at RWP 2 hrs with shielding factor SF = e^{-μx} = e^{-0.5 cm ⁻ ¹ * 5 cm Pb} = 0.367, reducing effective dose to 7.34 mrem/hr.
C.Verify access controls per 10 CFR 73.55(b)(9), scanning badge RFID with duress code 2025-SEC, and confirm training module completion on CDM terminology (e.g., chalking as surface degradation from ionizing flux >10^6 R).
D.Initiate hot work permit for adhesion test pull-off per ASTM D4541 at 2000 psi min, with flash arrestor on oxy-acetylene (flow 20 scfh), but defer to cold work per ALARA review showing dose savings 50 mrem.

정답:
Explanation:
PWR mid-loop shutdowns require LOTO sequencing per NFPA 70E, with zero-energy verification (<50 VAC) before CPM integration (FS slack avoids path compression), ensuring blister assessments fit outage windows per Appendix B Criterion X. Stay time t = D_limit / R, adjusted by SF = e^{-μx} for Pb shielding, enforces RWP limits to <100 mrem TEDE in 20 mR/hr fields from Co-60. Access per 10 CFR 73.55 uses RFID with training on CDM terms like chalking (radiation-induced chain scission >10^6 R); hot work deferral prioritizes ALARA, as D4541 is mechanical, not thermal.

Question No : 12

Phenolic containment linings for nuclear plants are exposed to multiple stresses.
Which combination below is the most stringent for coating inspection?

A.Only gamma radiation resistance testing per ASTM D4082
B.UV exposure, abrasion testing, and adhesion testing
C.Thermal cycling and decontamination chemical exposure only
D.High-temperature steam, gamma radiation, followed by decontamination testing

정답:
Explanation:
Nuclear containment linings must resist the combined effects of high -temperature steam, intense gamma radiation, and efficient decontamination, presenting a complex and stringent inspection challenge.

Question No : 13

Scenario: CSL II coating for RCA radwaste liner walls, exposed to 10^6 rads and 10% oxalic acid decons. Prep Sa 2.0/2 mil. Qual includes microbial res for wet areas.

A.Chem per D3912 in oxalic/160°F/192 hrs, no delam
B.Rad per D4082 to 2 x 10^6 rads, adhesion >1500 psi D4541
C.ASTM G21 fungal resistance rating 0, no growth
D.UV exposure per ASTM G154 200 hrs for window proximity

정답:
Explanation:
Liner walls in radwaste RCA need acid tolerance per D3912 and radiation-adhesion per D4082-D4541 for decontamination integrity. Fungal for submerged, but CSL II minimal; UV irrelevant internally.

Question No : 14

During contamination removal testing on phenolic coating, the inspector uses a wipe technique before and after decontamination.
What is the minimum efficiency required to pass ASTM D4256?

A.75%
B.80%
C.88%
D.90%

정답:
Explanation:
The ASTM D4256 test specifies a required minimum of 90% contaminant removal efficiency to ensure the coating is suitable for decontamination in nuclear environments.

Question No : 15

In a scenario-based audit, a vendor submits epoxy data for CSL I use showing failure in radiation test at 5 x 10^6 rads with 12% elongation loss. Per ASTM D4082 and D5144, which corrective formulation changes and retest parameters must be implemented?

A.Add 15% aromatic hydrocarbon resin to improve flexibility, retest at 10^6 rads/hour rate
B.Increase cure time to 168 hours at 77°F before irradiation, measure post-exposure per ASTM D638 ultimate strength >80% retention
C.Incorporate 5% UV stabilizer, but omit as irrelevant for gamma-only exposure
D.Dose fractionation: 2 x 10^6 rads increments with 24-hour intervals at 50% RH

정답:
Explanation:
To mitigate embrittlement in CSL I epoxies, D5144 via D4082 recommends extended cure for full cross-linking, with strength retention per D638. Fractionated dosing simulates operational buildup, preventing thermal spikes. Aromatic resins aid flexibility but require full re-qualification; UV stabilizers are for light, not gamma radiation.

AMPP AMPP-Nuclear 시험