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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 (66 cards)

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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
Why is Shutdown Margin verified during ES-3.1 (Post SGTR Cooldown using backfill)
- Dilution occurring from backfill | - No boration occurring since SI has been terminated
26
Why are RCP No. 1 seal dP and No. 1 Seal Leak off flow monitored during ES-3.1 (Post SGTR Cooldown using backfill)
- RCPs may need be stopped if these parameters get too low
27
What are the ADVANTAGES of ES-3.2 (Post SGTR Cooldown using Blowdown)
- Minimizes radiological releases - No boron dilution - No secondary chemistry effects
28
What are the DISADVANTAGES of ES-3.2 (Post SGTR Cooldown using Blowdown)
- 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
What are the ADVANTAGES of ES-3.3 (Post SGTR Cooldown using Steam Dump)
- FASTEST of the 3 methods
30
What are the DISADVANTAGES of ES-3.3 (Post SGTR Cooldown using Steam Dump)
- 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
What are the important entry conditions for ECA-3.1 (SGTR With Loss of Reactor Coolant - Subcooled Recovery)
- 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
Starting with E-0, what is the procedure flow path for a Ruptured AND Faulted SG
- E-0 -> E-2 -> E-3 -> ECA-3.1
33
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%
- Transition to ECA-3.2 (SGTR With Loss of Reactor Coolant - Saturated Recovery)
34
While in ECA-3.2 (SGTR With Loss of Reactor Coolant - Saturated Recovery) when will you STOP securing ECCS pumps
- 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
While in ECA-3.3 (SGTR without Pressurizer Pressure Control) when is transition to E-3 (Steam Generator Tube Rupture Made)
- 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
Why does the SI Termination criteria in ECA-3.3 (SGTR without Pressurizer Pressure Control) NOT check Pressurizer Level or RCS Pressure
- Because you are not able to depressurize the RCS
37
While in ECA-3.3 (SGTR without Pressurizer Pressure Control) if Pressurizer Level IS on scale, what will be the effect of SI termination
- Pressure will lower | - RCS & SG pressure will equalize stopping leakage
38
During a Control Room Evacuation, where can N-23 SR be read
- RCS Shutdown Indication Panel - LSI-4 - 587' Center Hallway
39
Why is the Hot Shutdown Panel NOT used for NFPA 805
- Inadequate train separation of cabling
40
Which CVCS Crosstie Valve provides flow from the opposite unit
- CS-536
41
Which CVCS Crosstie Valve provides flow to seal injection
- CS-535
42
Which CVCS Crosstie Valve provides flow to the BIT
- CS-534
43
What is the AFW crosstie Valve and where is it located
- FW-129 | - EMDAFP Rooms
44
What is the only remote indication of Reactor Power
- N-23 from LSI-4
45
What powers N-23
- Opposite unit CRID 3
46
What two systems are crosstied during Emergency Remote Shutdown
- CVCS through the BIT | - MDAFPs
47
Why must delays be communicated when establishing crosstie to the BIT
- Inventory Control
48
Who performs the cross tie of the MDAFPs
- Turbine Tour AEO (1st Action)
49
Why is the WMDAFP the preferred pump to crosstie
- Because it feeds the affected unit SG 2 & 3
50
Which units cross tie valve is used to cross tie the MDAFPs
- The affected units FW-129
51
During emergency remote shutdown, what must be done PRIOR to evacuation
- Plan Announcement | - Trip the Reactor
52
During emergency remote shutdown, why are Pressurizer PORV block valves closed
- Inventory Control | - Safety Valves control pressure
53
During emergency remote shutdown, why are Pressurizer Heaters de-energized
- In case level is lost and they don't trip automatically
54
What assumptions are made for Control Room Evacuation
- 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
When are the Reactor and Turbine tripped during a Control Room Evacuation
- BEFORE evacuation occurs
56
During a Control Room Evacuation WHEN must the Control Room be evacuated to the SM's office
- 4 mins
57
During a Control Room Evacuation WHEN must Prz PORV Block Valves be de-energized
- 8 mins from announcement
58
During a Control Room Evacuation WHEN must power be removed from RCP 4 kV breakers
- 8 mins from unsuccessful RCP trip from CR
59
During a Control Room Evacuation WHEN must actions be taken to ensure MSIVs remain closed
- 15 mins from announcement
60
During a Control Room Evacuation WHEN must remote control be established at LSI 3 & 4
- 15 mins from announcement
61
During a Control Room Evacuation WHEN must actions be taken to ensure Pressurizer Heaters remain tripped
- 17 mins from announcement
62
During a Control Room Evacuation WHEN must CVCS cross tie through the BIT be established
- 40 mins from announcement
63
During a Control Room Evacuation WHEN must AFW cross tie to SGs 2 & 3 be established
- 40 mins from announcement
64
In E-3 (Ruptured Steam Generator) with NO RCPs running, is the INTEGRITY status DISREGARDED
- NO, only the ruptured CL input to the INTEGRITY status tree
65
While in ECA-3.3 (SGTR without Pressurizer Pressure Control) how is RCS pressure controlled after ECCS termination
- By controlling Charging and Letdown flow | - (Procedure doesn't know if you have letdown available or not)
66
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
- 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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