Core Construction Flashcards

1
Q

What does the core barrel do?

A
  • Provides the primary support of the core
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2
Q

What does the thermal shield do?

A
  • Protects vessel by supplying shielding from high gamma and neutron flux
  • Provides some preheat of reactor coolant
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3
Q

What does the Diffuser Plate do?

A
  • Provides uniform flow distribution to the lower core plate
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4
Q

What do the Core Baffles and Formers do?

A
  • Provide transition between rectangle fuel assemblies and circular core
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5
Q

What does the Upper Core Plate do?

A
  • Provides upper support for fuel assemblies

- Holes to accept control rod assemblies and upper support columns

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6
Q

What does the Vessel Support Ledge do?

A
  • Contains orientation pins for the fuel assemblies
  • Support reactor internals via core barrel
  • Cooled by CCW isolated on Phase A
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7
Q

What do the Reactor Vessel Internals do?

A
  • Support and orient fuel and control rod clusters
  • Absorb control rod dynamic loads and transmit these loads to the reactor flange
  • Direct reactor coolant thru core
  • Support in-core instrumentation
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8
Q

What does the Lower Core Plate do?

A
  • Provides support and orientation pins for fuel assemblies

- 4 holes direct flow thru each assembly

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9
Q

What does the Secondary Support Assembly do?

A
  • Limits core movement if core barrel falls

- With the maximum 1-1/4” downward displacement of the core the control rods would remain aligned in the fuel assemblies

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10
Q

What do the Upper Support Columns do?

A
  • Maintains spacing between upper support assembly and upper core plate
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11
Q

What do the Upper Control Rod Guide Tubes do?

A
  • Guides each control rod and drive shaft
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12
Q

What is a primary source of neutron radiation?

A
  • Californium 252
    • Spontaneous fission
    • Used for int. startup only
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13
Q

What is a secondary source of neutron radiation?

A
  • Antimony-Beryllium
    • 4 sources installed each made up of 4 rodlets
    • Activated by neutron flux during power operations
    • Gamma is used to activate the Beryllium
    • Beryllium is the neutron source ***
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14
Q

What is the vessel leak detection system made of?

A
  • Inner and Outer O-Ring
  • DTA-100 alarms at 140°F
  • DRV-100 fails open on loss of air and power
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15
Q

What are the core penetrations?

A
  • 58 for in-core NIs
  • 53 for CRDMs
  • 1 vent connection
  • 5 In-core Thermocouples
  • 1 RVLIS/Vent connection
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16
Q

What does the Core Support casting do?

A
  • Core support casting is the bottom of the core barrel.

- Prevents rotation and horizontal movement of barrel by fitting in keyways** on vessel wall.

17
Q

What is the Reactor Core flow path?

A
  1. Enters vessel through 4 inlet nozzles
  2. 1% leaks by upper core barrel to outlet nozzles
  3. 0.5% goes into upper head area for cooling
  4. 98.5% flows down between core barrel and vessel wall
  5. Flow between thermal shield and barrel for cooling
  6. Flow turns up through support casting, diffuser plate and lower core plate - proper flow distribution includes higher flow in center region of core
  7. 0.5% flows between barrel and baffles
  8. 2.5% flows up control rod guide thimbles
  9. Coolant mixes in upper internals region and exits via outlet nozzles
18
Q

What are the important flows to core?

A

Enter:

  • 1% leaks by upper core barrel to outlet nozzles
  • 0.5% goes into upper head area for cooling
  • 98.5% flows down between core barrel and vessel wall

Exit:

  • 0.5% flows between barrel and baffles
  • 2.5% flows up control rod guide thimbles
19
Q

What is the TS 2.1.1.1 limit for DNBR with WRB-1 DNB?

A
  • ≥ 1.17
20
Q

What is the TS 2.1.1.1 limit for WRB-3 correlation with a DNBR where WRB-1 correlation is not applicable?

A
  • ≥ 1.30
21
Q

What is the TS 2.1.1.2(RCS Core Safety Limits) limit for peak fuel centerline temp?

A
  • < 5080°F and decreasing by 58°F/10,000 MWD/MTU
22
Q

What does TS 2.1.2 (RCS Core Safety Limits) state?

A
  • RCS pressure shall be maintained ≤ 2735# in Modes 1-5
23
Q

What mode(s) is TS 2.1.2 (RCS Core Safety Limits)required to be maintained?

A
  • Modes 1-5
24
Q

If TS Safety Limit 2.2.1 is violated, what needs to be done?

A
  • Required to be in Mode 3 w/in 1 hr
25
Q

If TS Safety Limit 2.1.2 is violated in mode 2, what needs to be done?

A
  • Restore RCS pressure to ≤ 2735# (compliance) and be in mode 3 w/in 1 hr
26
Q

If TS Safety Limit 2.1.2 is violated in mode 4, what needs to be done?

A
  • Restore RCS pressure to ≤ 2735# (compliance) within 5 minutes
27
Q

What is the TS Safety Limit Bases?

A
  • Bases on not violating following fuel criteria
    • 95% probability with 95% confidence level that the hottest fuel rod in the core does not experience DNB
    • 95% probability with 95% confidence level that the hottest fuel pellet in the core will not experience centerline fuel melting
28
Q

What is the control rod Composition?

A
  • Silver - 80%
  • Indium - 15%
  • Cadmium - 5%
29
Q

What is the purpose of the NSO Orifice?

A
  • Limits downstream break flow to within the capacity of 1 CCP