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0. Biennial Written Prep > EOP Week 1 > Flashcards

EOP Week 1 Flashcards

Deck Covers: Intro to EOP, Mass and Energy Balance, Rules of Use, E-0, ES-0.0, ES-0.1, ES-0.2, ES-0.3, SUP-010, SUP-011

1
Q

With what frequency is it expected that events will occur that require entering EOP series procedures

A
  • 10^-8 events per reactor year
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2
Q

When is foldout page guidance applicable

A
  • Any time that procedure is in effect
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3
Q

What conditions requiring using adverse containment criteria

A
  • Containment pressure greater than 5 psig
  • Radiation dose rates greater than 10^5 (100,000) R/hr
  • During an ELAP when Pzr or SG doghouse temperatures are greater than 196.8 deg F
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4
Q

When can you quit using adverse containment values

A
  • When containment pressure lowers to less than 5 psig
  • If dose rates lower below 10^5 (100,000) R/hr and total accumulated dose is less than 10^6 (1,000,000) Rem
  • During an ELAP when Pzr or SG doghouse temperatures lower to less than 196.8 deg F
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5
Q

For EOP steps with multiple substeps, in which order can the substeps be performed

A
  • If the substeps are preceeded by a letter/number then they must be performed in order.
  • If the substeps are bulleted then they may be performed in any order
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6
Q

If a contingency action cannot be performed what is the crew supposed to do

A
  • Proceed to the next step/sub-step
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7
Q

What is the order of priority for Critical Safety Functions

A
  • (S) Subcriticality
  • (C) Core Cooling
  • (H) Heat Sink
  • (P) Integrity
  • (Z) Containment
  • (I) Inventory
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8
Q

When is continuous monitoring of a Critical Safety Function required

A
  • When a Red (Extreme Challenge) or Orange (Severe Challenge) path is present
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9
Q

At what periodicity are Yellow (Not Satisfied) and Green (Satisfied) Critical Safety Functions required to be monitored

A
  • Every 10-20 minutes
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10
Q

Given an ORANGE Subcriticality path and a RED Heat Sink path, which FRP would be entered first and why?

A
  • FRH series then FRS if the ORANGE path is still present

- RED before ORANGE, Highest to Lowest Priority

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11
Q

What are the fission product barriers

A
  • Fuel Cladding
  • RCS Pressure Boundary
  • Containment
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12
Q

As RCS pressure lowers, what happens to break flow

A
  • Break flow lowers
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13
Q

How does a lowering Tave affect break flow from density effect

A
  • Density rises, more mass flows out the break
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14
Q

How does a lowering Tave affect break flow from the Choke Flow effect

A
  • Break flow flashes to steam further from the break, which lowers back pressure at the break, causing break flow to rise
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15
Q

What are the methods of heat removal available on the Primary (RCS) side

A
  • ECCS flow

- Break Flow

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16
Q

What are the methods of heat removal available on the Secondary (SG) side

A
  • AFW

- Steam Generators

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17
Q

What are the effects of “Uncovering the Break”

A
  • Rapid Depressurization
  • Energy Removal (latent heat of evaporization)
  • Break flow is reduced
  • ECCS flow is raised
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18
Q

Where is the worst location to have a SBLOCA and why

A
  • Cold Leg

- It requires more mass to be lost before the break is uncovered because the cross under loop seal must be cleared

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19
Q

What indications are consistent with a Faulted Steam Generator (E-2)

A
  • Tave Lowering
  • Rx Power Rising
  • SF>FF
  • Turbine Load Lowering
  • Pzr Pressure Lowering
  • Pzr Level Lowering
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20
Q

What indications are consistent with a Ruptured Steam Generator (E-3)

A
  • Secondary Rad monitors (SJAE/Gland Steam)
  • SG Level rising
  • Pzr Pressure Lowering
  • Pzr Level Lowering
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21
Q

What indications are consistent with a LOCA (E-1)

A
  • Containment Radiation Monitors
  • Pzr Pressure Lowering
  • Pzr Level Lowering
  • Containment Pressure Rising
  • Containment Sump Levels
  • Containmetn Dew Point Rising
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22
Q

What are the SI termination criteria

A
  • Subcooling greater than 40 deg F
  • SG NR lvl greater than 13% OR AFW flow greater than 240K pph
  • RCS Pressure stable or rising
  • Pzr Level greater than 16% (20%) OR {28% (24%) ADVERSE}
23
Q

What are the EOP RCP trip Fold Out Page criteria

A
  • Phase B

- RCS pressure less than 1300 # AND 1 CCP or SI pp running

24
Q

What are the AFW switchover Fold Out Page criteria

A
  • CST level less than 15%
25
Q

What are the SI actuation Fold Out Page criteria

A
  • RCS subcoolin less than 40 deg F

- Pzr level cannot be maintained greater than 7%

26
Q

What are the Major Action Categories of E-0

A
  • Verify
  • Diagnose
  • Actions
27
Q

What are the modes of applicability for E-0

A
  • Rx Trip (Modes 1 & 2)

- SI (Modes 1-3)

28
Q

When is FR-S.1 Entered from E-0

A
  • If Rx Trip is unsuccessful (i.e., no RNOs are successful)
29
Q

When is FR-H.1 Entered from E-0

A
  • If secondary heat sink cannot be verified (i.e., less than 240k PPH AND less than 13% NR SG lvl)
30
Q

What are the order of diagnostic transitions from E-0 and what is the basis

A
  • E-1 LOCA (If PORV stuck open)
  • E-2 Faulted SG (can mask other transients)
  • E-3 Ruptured SG (dose to the public)
  • E-1 LOCA (Automatic actions in place to mitigate)
31
Q

What are the immediate actions of E-0

A
  • Verify Rx Tripped
  • Verify Turbine Tripped
  • Verify AC Emergency bus power
  • Check SI status
32
Q

Why is AFW flow lowered to less than 450K PPH in E-0

A
  • To limit over cooling of the RCS
33
Q

Why is AFW flow maintained greater than 240K PPH in E-0

A
  • To ensure enough FW flow for decay heat removal (Heat Sink)
34
Q

What are the entry conditions to ES-0.0

A
  • Based on operator judgement with ALL of the following met:
  • SI is I/S or required
  • E-0 has been exited
  • E Series EOP is in progress
35
Q

What are the Major Action categories of ES-0.1 (Reactor Trip Response)

A
  • Ensure Primary stabilizes at No Load
  • Ensure Secondary stabilizes at No Load
  • Ensure power is available
  • Establish/Maintain forced circulation
  • Maintain stable RCS
36
Q

In ES-0.1 what must be done for each control rod not fully inserted

A
  • Borate 160 ppm (150 ppm) for each rod not fully inserted
37
Q

What E series procedures can be entered from ES-0.1 (Reactor Trip Response)

A
  • E-0 if SI occurs or is required

- ES-0.2 if natural circulation cool down is required

38
Q

In ES-0.2 (Natural Circ Cooldown) when are accumulators isolated and why

A
  • Accumulators isolated when RCS pressure is less than 1000# for LTOP
39
Q

In ES-0.2 (Natural Circ Cooldown) when are SI pumps removed and why

A
  • SI pumps removed when temperature is less than 350 deg F for LTOP
40
Q

What E series procedures can be entered from ES-0.2 (Natural Circ Cooldown)

A
  • ES-0.3 for a Natural Circ cool down with a void in the head if CST inventory is low
  • (E-0 and E-1 from fold out page)
41
Q

In ES-0.2 (Natural Circ Cooldown) why is there a procedure loop to ensure that Cold Shutdown SDM is met before cooling down

A
  • Because there are stagnant areas of the RCS and the potential for uneven boron cocentrations
42
Q

What is the primary source of cooling during the onset of a Natural Circ cool down

A
  • CRDM fans remove the majority of the heat from the head at the start of a Natural Circ cool down
43
Q

What are the subcooling requirements for an ES-0.2 (Natural Circ Cooldown) Natural Circ cool down with AND without CRDM fans running that ensure head voiding does not occur

A
  • 90 deg F if CRDM fans running

- 220 deg F if NO CRDM fans running

44
Q

What are the entry conditions for ES-0.3 (Natural Circ Cooldown w/ Void)

A
  • Can ONLY be entered from ES-0.2 once cold shutdown SDM has been achieved (first 13 steps of ES-0.2)
45
Q

What is the first thing that ES-0.3 (Natural Circ Cooldown w/ Void) attempts to accomplish

A
  • Restart an RCP (Do NOT start if subcooling has been lost)
46
Q

While in ES-0.2(Natural Circ Cooldown) for a Natural Circ Cooldown, what must Pressurizer Level be BEFORE starting an RCP IF RVLIS indicates less than full and WHY

A
  • Pzr Level greater than 84%

- To prevent a loss of subcooling due to lowering Pressurizer Level due to voids collapsing

47
Q

What are the two reasons listed in SUP-010 (RCP Restart) that you would not want to attempt an RCP restart

A
  • If there is a SBLOCA (subcooling lost)

- Loss of ALL seal cooling (Seal Inj AND CCW)

48
Q

During non-LOCA conditions why should an RCP restart be attempted

A
  • Better heat removal
  • Improved Temperature and Pressure control
  • Improved Pressurizer Level Control (Spray)
49
Q

What three factors influence Pressurizer Spray Flow

A
  • Vessel and RCS Piping delta P
  • Velocity head at spray flow scoop
  • Pressurizer Level
  • NOT RCS PRESSURE (felt at top and bottom of pressurizer cancels each other out)
50
Q

What are the indications that Natural Circ has been established

A
  • RCS subcooling based on CETC is greater than 40 deg F
  • Stable or Lowering SG Pressure, HL temperatures, CETCS
  • RCS CL temps at saturation for SG pressure
51
Q

Which Critical Safety Functions are associated with protecting the Fuel Matrix and Fuel Cladding

A
  • Subcriticality
  • Core Cooling
  • Heat Sink
  • Inventory
52
Q

Which Critical Safety Functions are associated with protecting the RCS Pressure Boundary

A
  • Heat Sink
  • Integrity
  • Inventory
53
Q

Which Critical Safety Functions are associated with protecting Containment

A
  • Containment
54
Q

How can you tell if non-condensables bubble is present in the upper head region

A
  • In EOPs if RCS pressure is less than 150# then assume N2 from accumulators is present in upper head

0. Biennial Written Prep (12 decks)

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