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0. Biennial Written Prep > EOP Week 5 & 6 > Flashcards

EOP Week 5 & 6 Flashcards

Deck Covers: E-3, ES-3.1, ES-3.2, ES-3.3, ECA-3.1, ECA-3.2, ECA-3.3, CRE

1
Q

While in E-3 (Steam Generator Tube Rupture), what is the purpose of the Major Action Category “TERMINATE SI”

A
  • Stops the primary to secondary leakage
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2
Q

From E-3 (Steam Generator Tube Rupture), what transition is made if RWST level is less than 30%

A
  • Per FOP go to ES-1.3 (Transfer to Cold Leg Recirculation)
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3
Q

From E-3 (Steam Generator Tube Rupture), what transition is made if a SINGLE Steam Generator PRESSURE is lowering in an uncontrolled manner OR is completely depressurized and WAS NOT previously isolated

A
  • Per FOP go to E-2 (Faulted Steam Generator)
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4
Q

From E-3 (Steam Generator Tube Rupture), what transition is made if any intact SG level rises in an uncontrolled manner OR has abnormal radiation

A
  • Per FOP stabilize the plant and go to E-3 (Steam Generator Tube Rupture) step 1
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5
Q

From E-3 (Steam Generator Tube Rupture), what transition is made following SI termination IF EITHER subcooling is less than 40 deg F OR Pzr Level CAN NOT be maintained greater than 16% {28% Adverse}

A
  • Per FOP go to ECA-3.1 (SGTR with Loss of Reactor Coolant - Subcooled Recovery
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6
Q

In E-3 (Steam Generator Tube Rupture), when balancing SG and RCS level/pressure what is the preferred method of pressure control if L/D is AVAILABLE with NO RCPs

A
  • Aux Spray
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7
Q

What is Iodine Partitioning

A
  • With adequate SG levels (greater than 13%) Iodine concentrates in the SG while steaming minimizing the release.
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8
Q

How is SG overfill prevented in E-3 (Steam Generator Tube Rupture)

A
  • Isolating the ruptured SG
  • Cooldown and Depressurizing RCS
  • Terminating SI
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9
Q

What are the consequences of SG Overfill during E-3 (Steam Generator Tube Rupture)

A
  • Rupture of MS line from weight and water hammer
  • Damage to SG PORVs
  • Damage to SG Safeties
  • Damage to TDAFP
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10
Q

While in E-3 (Steam Generator Tube Rupture), why is the SG PORV setpoint raised to 1040 psig on the RUPTURED SG

A
  • Minimize release

- Maintains ruptured SG pressure greater than pressure in intact SG

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11
Q

In addition to Iodine Partitioning, why are SG levels maintained greater than 13% in the ruptured SG

A
  • Keeps tubes covered which prevents steam from condensing on tubes and lowering SG pressure which would re-initiate/cause a rise in primary to secondary leakage
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12
Q

In E-3 (Ruptured Steam Generator) with NO RCPs running, why is the CL temperature indication for the loop containing the ruptured SG disregarded for CSFST monitoring

A
  • With NO RCPs there is no flow in this loop
  • ECCS is injecting in this loops and moving BACKWARDS through the SG past the CL RTD
  • The vessel IS NOT subjected to this FALSE LOW CL temperature
  • ONLY APPLICABLE WHILE IN E-3
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13
Q

When is a SG Tube Leak considered a SG Tube Rupture

A
  • When the leak rate exceeds the capacity of one CCP with max flow AND L/D isolated
  • Reactor trip AND SI required
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14
Q

What is the Tech Spec limit for Primary to Secondary Leakage

A
  • 150 GPD (0.1 gpm)
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15
Q

What is the EPRI recommended limit for continued operation with Primary to Secondary Leakage

A
  • 75 GPD

- SG’s not evaluated for leak before break

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16
Q

Per the SG tube leak AOP, what is the leakage threshold for initiating a Reactor Trip

A
  • 50 gpm
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17
Q

Per the SG tube leak AOP, what is the leakage threshold for initiating a Reactor Trip AND SI

A
  • 100 gpm
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18
Q

What is does the UFSAR assume regarding a SGTR

A
  • Operator actions are taken to isolate the ruptured SG efficiently
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19
Q

What is the preferred method (Procedure) used to cooldown and depressurize the RCS following a SGTR

A
  • ES-3.1 (Cooldown Using Backfill)
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20
Q

What are the ADVANTAGES of ES-3.1 (Post SGTR Cooldown using Backfill)

A
  • Minimizes radiological releases

- Allows processing of water

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21
Q

What are the DISADVANTAGES of ES-3.1 (Post SGTR Cooldown using Backfill)

A
  • Secondary chemistry effecst on RCS components
  • Potential Boron dilution (could cause SR count to rise during cooldown)
  • Slower than steaming
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22
Q

How is the ruptured SG LEVEL controlled during cooldown using ES-3.1 (Post SGTR Cooldown using backfill)

A
  • RCS Pressure

- AFW

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23
Q

How is the SG metal temperature cooled when using ES-3.1 (Post SGTR Cooldown using Backfill)

A
  • Allow SG level to lower to 20% (27%)
  • SLOWLY refill to 62%
  • SLOW to prevent rapid pressure drop that would reinitiate or raise leakage
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24
Q

What would happen if SG LEVEL was allowed to lower below 20% (27%) while in ES-3.1 (Post SGTR Cooldown using backfill)

A
  • Tubes would become uncovered
  • Causes depressurization of ruptured SG
  • Reinitiates the leak
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25
Q

Why is Shutdown Margin verified during ES-3.1 (Post SGTR Cooldown using backfill)

A
  • Dilution occurring from backfill

- No boration occurring since SI has been terminated

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26
Q

Why are RCP No. 1 seal dP and No. 1 Seal Leak off flow monitored during ES-3.1 (Post SGTR Cooldown using backfill)

A
  • RCPs may need be stopped if these parameters get too low
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27
Q

What are the ADVANTAGES of ES-3.2 (Post SGTR Cooldown using Blowdown)

A
  • Minimizes radiological releases
  • No boron dilution
  • No secondary chemistry effects
28
Q

What are the DISADVANTAGES of ES-3.2 (Post SGTR Cooldown using Blowdown)

A
  • Storage and processing capabilities of BD system are limited
  • Will spread contamination to secondary side
  • Small drain lines mean this is slow (especially with no RCPs)
29
Q

What are the ADVANTAGES of ES-3.3 (Post SGTR Cooldown using Steam Dump)

A
  • FASTEST of the 3 methods
30
Q

What are the DISADVANTAGES of ES-3.3 (Post SGTR Cooldown using Steam Dump)

A
  • Radiological consequences must be considered especially if condenser is not available
  • Potential water hammer effects
  • Should NOT be used if SG overfill has occurred
31
Q

What are the important entry conditions for ECA-3.1 (SGTR With Loss of Reactor Coolant - Subcooled Recovery)

A
  • Ruptured SG CANNOT be isolated from ANY intact SG
  • Faulted AND Ruptured SG
  • Minimum dP (250#) between ruptured and intact SGs CANNOT be maintained
  • SGTR w/ LOCA
  • CANNOT BE ENTERED DIRECTLY FROM E-2 SERIES
32
Q

Starting with E-0, what is the procedure flow path for a Ruptured AND Faulted SG

A
  • E-0 -> E-2 -> E-3 -> ECA-3.1
33
Q

While in ECA-3.1 (SGTR with Loss of Reactor Coolant - Subcooled Recovery) what transition is made if RWST level is LESS THAN 56% without a corresponding rise in sump levels OR SG narrow range level is GREATER THAN 91%

A
  • Transition to ECA-3.2 (SGTR With Loss of Reactor Coolant - Saturated Recovery)
34
Q

While in ECA-3.2 (SGTR With Loss of Reactor Coolant - Saturated Recovery) when will you STOP securing ECCS pumps

A
  • Once you no longer meet the subcooling requirements to do so
  • Remove as many pumps as possible until saturation occurs
  • Continued cooldown will restore subcooling
35
Q

While in ECA-3.3 (SGTR without Pressurizer Pressure Control) when is transition to E-3 (Steam Generator Tube Rupture Made)

A
  • If normal spray is restored
  • If PORVs are restored
  • If Aux Spray is restored
  • If there is an uncontrolled Level Rise in intact SG
36
Q

Why does the SI Termination criteria in ECA-3.3 (SGTR without Pressurizer Pressure Control) NOT check Pressurizer Level or RCS Pressure

A
  • Because you are not able to depressurize the RCS
37
Q

While in ECA-3.3 (SGTR without Pressurizer Pressure Control) if Pressurizer Level IS on scale, what will be the effect of SI termination

A
  • Pressure will lower

- RCS & SG pressure will equalize stopping leakage

38
Q

During a Control Room Evacuation, where can N-23 SR be read

A
  • RCS Shutdown Indication Panel
  • LSI-4
  • 587’ Center Hallway
39
Q

Why is the Hot Shutdown Panel NOT used for NFPA 805

A
  • Inadequate train separation of cabling
40
Q

Which CVCS Crosstie Valve provides flow from the opposite unit

A
  • CS-536
41
Q

Which CVCS Crosstie Valve provides flow to seal injection

A
  • CS-535
42
Q

Which CVCS Crosstie Valve provides flow to the BIT

A
  • CS-534
43
Q

What is the AFW crosstie Valve and where is it located

A
  • FW-129

- EMDAFP Rooms

44
Q

What is the only remote indication of Reactor Power

A
  • N-23 from LSI-4
45
Q

What powers N-23

A
  • Opposite unit CRID 3
46
Q

What two systems are crosstied during Emergency Remote Shutdown

A
  • CVCS through the BIT

- MDAFPs

47
Q

Why must delays be communicated when establishing crosstie to the BIT

A
  • Inventory Control
48
Q

Who performs the cross tie of the MDAFPs

A
  • Turbine Tour AEO (1st Action)
49
Q

Why is the WMDAFP the preferred pump to crosstie

A
  • Because it feeds the affected unit SG 2 & 3
50
Q

Which units cross tie valve is used to cross tie the MDAFPs

A
  • The affected units FW-129
51
Q

During emergency remote shutdown, what must be done PRIOR to evacuation

A
  • Plan Announcement

- Trip the Reactor

52
Q

During emergency remote shutdown, why are Pressurizer PORV block valves closed

A
  • Inventory Control

- Safety Valves control pressure

53
Q

During emergency remote shutdown, why are Pressurizer Heaters de-energized

A
  • In case level is lost and they don’t trip automatically
54
Q

What assumptions are made for Control Room Evacuation

A
  • No failure to CR panels would prevent safe operation from outside Control Room
  • All auto features are fully functional
  • No accident condition at the time of the CR evacuation
55
Q

When are the Reactor and Turbine tripped during a Control Room Evacuation

A
  • BEFORE evacuation occurs
56
Q

During a Control Room Evacuation WHEN must the Control Room be evacuated to the SM’s office

A
  • 4 mins
57
Q

During a Control Room Evacuation WHEN must Prz PORV Block Valves be de-energized

A
  • 8 mins from announcement
58
Q

During a Control Room Evacuation WHEN must power be removed from RCP 4 kV breakers

A
  • 8 mins from unsuccessful RCP trip from CR
59
Q

During a Control Room Evacuation WHEN must actions be taken to ensure MSIVs remain closed

A
  • 15 mins from announcement
60
Q

During a Control Room Evacuation WHEN must remote control be established at LSI 3 & 4

A
  • 15 mins from announcement
61
Q

During a Control Room Evacuation WHEN must actions be taken to ensure Pressurizer Heaters remain tripped

A
  • 17 mins from announcement
62
Q

During a Control Room Evacuation WHEN must CVCS cross tie through the BIT be established

A
  • 40 mins from announcement
63
Q

During a Control Room Evacuation WHEN must AFW cross tie to SGs 2 & 3 be established

A
  • 40 mins from announcement
64
Q

In E-3 (Ruptured Steam Generator) with NO RCPs running, is the INTEGRITY status DISREGARDED

A
  • NO, only the ruptured CL input to the INTEGRITY status tree
65
Q

While in ECA-3.3 (SGTR without Pressurizer Pressure Control) how is RCS pressure controlled after ECCS termination

A
  • By controlling Charging and Letdown flow

- (Procedure doesn’t know if you have letdown available or not)

66
Q

While in ECA-3.3 (SGTR without Pressurizer Pressure Control), the first step has you check if the ruptured SG level is LESS THAN 67%. What is the basis for this step

A
  • If the ruptured SG level is greater than 67% overfill is a concern and ECCS should be terminated promptly if termination criteria are met

0. Biennial Written Prep (12 decks)

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