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Pirtle NRC PREP Group Study > EOP > Flashcards

EOP Flashcards

1
Q

What is adverse containment?

A

5 psig

10E5 R/hr

During ELAP Unit PRZ and SG temps verified below 196.8*F

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2
Q

If rad levels exceed 10E5 R/hr and eventually come back down, do you still have to use adverse containment values?

A

YES, until evaluated for integral dose

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3
Q

What is the order of priority of the Critical Safety Functions?

A

Subcriticality

Core Cooling

Heat Sink

Integrity

Containment

Inventory

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4
Q

Which CSFs require continuous monitoring?

A

Red or Orange

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5
Q

What are the fission product barriers?

A

Fuel Cladding

RCS

Containment

E-Plan

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6
Q

What are the methods of heat removal for a SBLOCA?

A

ECCS Flow / Breaker Flow

AFW / SGs

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7
Q

Why is a CL Break considered the worst scenario for a SBLOCA?

A

More mass is lost prior to ECCS flow equaling break flow. The cross under loop seal must be clear before steam can be vented from the break

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8
Q

What are indications of a faulted SG?

A

Tave lowers

Rx Power Rises

Possible turbine load lowering

SF > FF

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9
Q

What are indications of SGTR?

A

SJAE / GSLO Rad monitors high

SG Level rising uncontrollably

PRZ Pressure and Level Lowering

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10
Q

What are indications of a LOCA?

A

Containment Rad Monitor & Dew Point rising

PRZ Level and Pressure lowering

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11
Q

What is the SI Termination Criteria found in ES-1.1

A

Subcooling > 40*F

Heat Sink by SG level >13% OR > 240K ppm

RCS Pressure stable / rising

PRZ Level 16% (20%)

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12
Q

What does meeting your SI termination subcooling criteria tell you?

A

Adequate core cooling and secondary heat sink

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13
Q

What does meeting your heat sink SI termination criteria tell you?

A

Ensure subcooling will be maintained following termination

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14
Q

What does meeting your RCS Pressure SI Termination criteria tell you?

A

Ensures subcooling will be stable / rising and SI flow is effective in raising RCS Inventory

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15
Q

What does meeting your PRZ Level SI Termination Criteria tell you?

A

Sufficient RCS Inventory

Only valid if RC is subcooled

Ensures ability to maintain pressure following termination

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16
Q

Why do RCPs need to be tripped on a phase B?

A

Loss of CCW flow to RCP LO Coolers

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17
Q

Where do you transition from in E-0 if a Rx Trip is not successful?

A

FR-S.1

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18
Q

What is the order of diagnostic transitions in E-0 and why ?

A

E-2, easy to find/fix and can mask other issues

E-3, stops offsite dose. Lots of TCAs

E-1, auto actions can handle it

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19
Q

In E-0, why do we lower AW to < 450K pph?

A

Limits overcooling the RCS

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20
Q

In E-0, why is the minimum AFW 240K pph until the minimum SG water level is maintained?

A

ENsures enough FW flow for decay heat removal. Also, min # for Heat Sink CSF Status Tree

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21
Q

What are the entry conditions for ES-0.0, Rediagnosis?

A

ALL of the following:

SI is I/S or Required

E-0 has been exited

E-Series procedure in progress

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22
Q

What must be done after a reactor trip for each control rod not fully inserted?

A

Borate 160 (150) ppm for each rod

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23
Q

If in ES-0.1, Reactor Trip Response, what do you do if you get an SI?

A

Return to Step 1 of E-0

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24
Q

Why would you transition from ES-0.2, Natural Circ Cooldown to ES-0.3, NC Cooldown w Steam Void?

A

If CST Inventory is low

After LOOP when a high rate of planned Cooldown and depressurization is required due to reduced CST inventory

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25
Q

What removes most of the heat from the head on NC?

A

CRDMs

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26
Q

In ES-0.3, Natural Circ Cooldown with Steam odd, when should you not try to start an RCP?

A

If cooling had been previously lost

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27
Q

In ES-0.3, NC Cooldown w steam void, why is it required to raise PRZ Level to 84% prior to starting a RCP?

A

Ensures PRZ level doesn’t lower causing a loss of subcooling when the RCP is started due to void collapsing / lowering PRZ level

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28
Q

What are the benefits of restarting RCPs?

A

Enhances core heat removal

Improves RCS Pressure and Temp Control

Improves PRZ Level Control

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29
Q

Which RCP is the most effective?

A

3 bc it has the most dP

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30
Q

What are the 3 factors affecting spray flow?

A

Vessel and RCS piping DP

Coolant Velocity head at spray flow scoop located at spray flow penetration in CL

PRZ Level

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31
Q

What are the indications of NC?

A

Subcooling ? 40*F

Stable or Lowering:

  • SG Pressures
  • CETCs
  • RCS HL Temps

RCS CL Temps at saturation temp for SG Pressure

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32
Q

What should be done if NC cannot be verified?

A

Raise steam dump flow

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33
Q

For a SBLOCA, why is 1300# trip criteria?

A

Ensures RCPs are stopped before the break is uncovered so no additional mass is lost

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34
Q

Why is CCW to RHR adjusted to 5,000 gpm during CL Recirc?

A

Prevents pump Runout if 1 pump fails

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35
Q

When is RHR Spray placed in service?

A

50 mins (allows decay heat removal) - 70 mins (containment peak pressure)

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36
Q

What are the 10CFR100 Limits at the site boundary?

A

25 REM Whole Body, 300 REM Thyroid for 2 hours

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37
Q

While in ES-1.1, SI termination, what if you are unable to maintain 40*F subcooling and PRZ LeveL?

A

Go to E-1 bc there must be another issues. If you just add another CCP back on, you’d meet the SI Termination Criteria again

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38
Q

For a Faulted SG, when will you have a SI?

A

Upstream of the MSIVs for a steam break or downstream of check valve for a feed break.

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39
Q

In E-2, faulted SG Isolation, why will AFW have to be periodically reduced to maintain SG Levels after RCS Temp is stabilized?

A

Lowering Decay Heat Levels

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40
Q

In E02, Faulted SG Isolation, why do we control AFW Flow?

A

Prevent SG Dryout

Minimize RCS Cooldown

Prevent SG Overfill

Control RCS Temp after Cooldown is stopped

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41
Q

During E-3, SGTR, why do we want to terminate SI?

A

Helps control primary to secondary leakage

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42
Q

What could be a potential problem if the SG is overfilled during a SGTR?

A

Rupture of MS Line from weight of the water

Damage to PORVs, Safeties and TDAFP

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43
Q

During a SGTR, what is the affected SG PORV set point changed to and why?

A

1040 psig to minimize the release

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44
Q

Why do we ensure the ruptured SG level reaches 13% before isolated AFW to it?

A

To ensure SG Tubes are covered, which will prevent depressurization

45
Q

What does the UFSAR assume for a SGTR?

A

Operator actions are taken to isolate ruptured SG efficiently

46
Q

What are the advantages and disadvantages of ES-3.1, Cooldown using backfill?

A

+ Minimizes radiological releases and allows processing of RCS

  • Potential boring dilution, secondary chemistry effects on RCS, Slow
47
Q

What are the advantages and disadvantages of using ES-3.2, Cooldown using blowdown?

A

+ Minimizes radiological releases, NO boron dilutions or chemistry effects

  • storage / processing capabilities, spreads contamination, SLOW
48
Q

What are the advantages / disadvantages of using ES-3.3, cooldown using steam dump method?

A

+ FAST

  • Contamination / radiation, potential water hammer on secondary components.
49
Q

When would you transition back to E-2 from ECA-2.1, Uncontrolled depressurization of all SGs?

A

If any SG pressure boundary is restored, except while performing SI Term steps 10-20

50
Q

During ECA-2.1, what is AFW lowered to and why?

A

25K per SG to prevent boiling dry and minimize thermal shock effects if FF is later raised

51
Q

What is the minimum DP that should be maintained between the ruptured and intact SGs?

A

250#

52
Q

When would you enter ECA-3.1, SGTR w loss of RC, subcooled recovery?

A

Cannot isolate ruptured SG from any intact SGs

Faulted and Ruptured SG

Min DP cannot be maintained

SGTR w LOCA

53
Q

When would you transition from ECA-3.1 to ECA-3.2, SGTR w Loss of RC, saturated Recover?

A

RWST level is low with NO corresponding rise in Containment water level

54
Q

What are the immediate actions for FR-S.1?

A
  1. Trip Rx
  2. Insert Rods > 48 spm
  3. Manually actuate AMSAC
  4. Trip Turbine
    • ATWS Runback
    • MSICs close
55
Q

What is the purpose for tripping the turbine in FR-S.1?

A

Prevents excessive cooldown and conserves SG Water

56
Q

Why do you NOT trip RCPs if power is >5%?

A

Provides core cooling and keeps fuel integrity in tact

57
Q

Is an ATWS worse at BOL or EOL?

A

BOL due to less temperature feedback

58
Q

Why is RCS pressure checked less than PRZ PORV setpoint in FR-S.1?

A

ensures ability to emergency borate

59
Q

What is the minimum AFW flow during ATWS?

A

450K LBLOCA until 13% NR Level

60
Q

How could an unneeded SI complicate an ATWS?

A

FWI and MFPs will trip which will mean SGs could dryout

61
Q

What are the possible ways to lose subcriticality during an ATWS?

A

Dilution

Cooldown

Rods do not fully insert

62
Q

Is it necessary to have adequate SDM to exit from FR-S.2?

A

No, however a boration is expected to be continued after the transition to ensure adequate SDM

63
Q

What containment pressures put you into a red and orange path for Containment CSF?

A

Red - 12 psig

Orange - 2.8 psig

64
Q

While in ECA-1.2, LOCA Outside of containment, what is the indication that your leak has been isolated?

A

RCS Pressure Rising

65
Q

Why does ECA-1.1, Loss of emergency coolant recirc, direct depressurizing the SGs to 670 psig?

A

To prepare for a controlled accumulator injection to keep the core covered

66
Q

What are the assumptions concerning the LBLOCA analysis?

A

Some zirc-water reaction is expected

ECCS flow to the faulted loop and the accumulator injection for that loop spills to containment

RHR pumps must not be aligned for spray prior to 50 mins after the onset to ensure decay heat levels are within the heat removal capability of 1 CCP and 1 SI pump

Core safety could be challenged if RHR and CTS flow is interrupted for more than 5 mins while transferring over to CL Recirc

67
Q

What is the EOP basis for tripping the turbine in FR-S.1 when there is a loss of MFPs but no reactor trip?

A

Maintain/Extend SG Inventory

68
Q

When should you not restart RCPs for ES-1.2, Post LOCA Cooldown and Depressurization?

A

When all seal cooling has been lost long enough that maximum RCP seal parameters have been exceeded. Instead, cool the RCS to reduce temp of the water flowing thru the pump seals

This removes the potential thermal shock damage to the seals

69
Q

While in ES-1.2, Post LOCA Cooldown and Depressurization, you’re doing ECCS flow reduction. You’re ready to stop the first CCP. RCS Subcooling exactly meets subcooling table requirements. After you stop the pump, what do you expect?

A

Subcooling will lower to the minimum required value then recover with the cooldown

70
Q

In ECA-1.1, Loss of Emergency Coolant, what is the basis for cooling the RCS at a maximum cooldown rate (after a LOCA outside containment that has not been isolated)

A

The cooldown rate will minimize offsite releases due to the event by reducing the need for supporting systems and equipment

71
Q

If we have inadequate core cooling, what could happen?

A

Core uncovers

Fuel damage could occur

72
Q

What are the red path entries into FR-C.1?

A

5 highest CETs all > 1200*F

RVLIS NR < 46% with all 5 highest CETs > 757F with no RCPs running and SC < 40F

73
Q

What’s the most effective strategy of FR-C.1?

A

Establish ECCS Flow

74
Q

What are the 4 Major Action Categories of FR-C.1?

A

Establish ECCS Flow

Rapidly Depressurize SGs to Depressurize RCS

Start RCPs

Open all RCS Vent Paths to containment

75
Q

What is the purpose of rapidly Depressurize go SGs in FR-C.1?

A

Allows accumulator and RHR pump injection

76
Q

In FR-C.1, when would you not start a RCP?

A

If SG depressurization was ineffective due to loss of heat sink bc creep failure of the SG tubes

77
Q

In FR-C.1, would you start RCPs without support conditions?

A

YES! Start 1 RCP at a time until CETCs are < 1200*F

78
Q

What do CET temps of 757*F indicate?

A

Superheated core exit

79
Q

Why is a 1” SBLOCA the worst scenario for FR-C.1?

A

Loop seal never clears, so steam mass loss rate out the break isn’t reduced.

80
Q

What is indicative of superheated conditions?

A

High CETCs

81
Q

What is indicative of core uncovery?

A

Low RVLIS

82
Q

What is significant about 46% RVLIS level?

A

COre covered…. 3.5 ft from bottom of core

83
Q

Why are RCPs stopped in FR-C.1 after SGs are Depressurize to 160 psi?

A

Loss of #1 seal requirements

84
Q

Why are RCPs so important in FR-C.1?

A

They provide forced 2 phase flow to prevent inadequate core cooling

85
Q

In FR-C.2, if all RCPs are running, what must be done?

A

Stop #3 for later use

86
Q

What are the Major Action Categories for FR-H.1?

A

Attempt to restore FF to SGs

Initiate RCS Bleed and Feed

Restore and verify Heat Sink

Terminate RCS Bleed and feed

87
Q

When would the secondary heat sink not be required?

A

LBLOCA

RCS Temp <350*F bc RHR can be used

88
Q

What must be done during FR-H.1 if NO CCPs are available?

A

Stop all RCPs and initiate feed and bleed immediately to Depressurize to SI pressure

89
Q

How can you tell if secondary heat sink has been restored?

A

Lowering RCS Temps and rising SG Level

90
Q

What are the feeding guidelines after bleed and feed initiation per FR-H.1 FOP if CETCs are rising?

A
  1. Feed any SGs that are NOT dry at max Rate
  2. If ALL SGs are dry, feed 1 SG at max rate. When CETCs lower, check for fault or rupture. IF it is, then establish FF to INTACT SG at < 50E3 ppm
91
Q

What are the feeding criteria after bleed and feed initiation in FR-H.1 if CETCs are stable or lowering?

A

Feed any SGs that are not dry as necessary to restore NR level

If all SGs are try, then feed 1 SG at a time less than 50E3 ppm.

92
Q

What is considered a dry SG?

A

WR < 17%

93
Q

If SI termination criteria is not satisfied in FR-P.1, what should be done?

A

Start RCP to mix ECCS flow w RC to minimize thermal stresses not he vessel and then soak for 1 hr

94
Q

What is looked at for SI Termination criteria in FR-P.1?

A

Less Restricitive

SC > 90*F and RVLIS Level

95
Q

What is the operator error assumption made in FR-P.1 to make a PTS concern possible?

A

SI termination is delayed 30 mins

96
Q

In FR-P.1, how long do you soak and when does the clock start?

A

1 hr when temps is stable

97
Q

What is the cooldown limit in FR-P.1 after the soak?

A

50*F/hr

98
Q

How can you exit FR-P.1 without any actions?

A

RCS Pressure < 300# and RHR Flow > 400 gpm

LBLOCA

99
Q

Is a cooldown or heatup more limiting for RCS Integrity and why?

A

Cooldown bc of tensile stress on the inner wall

100
Q

What’s the worst case PTS accident and why?

A

3” SBLOCA when both RCS forced flow and NC are lost and cold RWST water streams to vessel belt line welds.

101
Q

What is the cooldown rate in FR-P.1?

A

100*F per hour

102
Q

WHat should have happened before implementing FR-P.2, yellow path?

A

SI should have been terminated

103
Q

When would you not perform FR-I.1?

A

SI is in service and needed

104
Q

In FR-H.1, what must be done if less than 2 PORV flow paths are open or CETCs are rising?

A

Use additional vent paths…. NSOs

105
Q

What is the preferred order of the secondary head sink sources?

A

AFW own unit
AFW cross tie
MFP
Condensate

106
Q

What’s key to determine if you have Nat Circ?

A

Large Delta T

107
Q

What are the benefits of feed and bleed?

A

Minimize core uncovery and prevent inadequate core cooling

108
Q

When is an ATWS worse?

A

BOL due to less feedback from a smaller MTC

Pirtle NRC PREP Group Study (10 decks)

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