TS Bases Quiz Flashcards

1
Q

What reasons are the core Safety Limits established?

A

Protect integrity of fuel cladding barrier.

Prevent release to the public.

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2
Q

What is safety limit pressure & why?

A

1325#, ensure integrity of system is not endangered.
1375# is 110% of design pressure, minus head of water for recirc pump suction piping.

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3
Q

What constitutes operable control rods?

A

scram time, rod position indication, & coupling integrity

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4
Q

When is a control rod considered stuck?

A

Will not insert using all available insertion methods by either CRD or Scram Pressure.

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5
Q

What is the stuck control rod separation criteria?

A

Stuck control rod may not occupy a location adjacent to a “slow” control rod.

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6
Q

What is separation criteria for rods out of pattern regarding BPWS?

A

Inserted rods not in compliance must be separated by at least two operable control rods in all directions.

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7
Q

What is the basis of shutting down when 9 or more control rods are inoperable?

A

Could have more than 9 inoperable, but that many inoperable control rods is indicative of a bigger problem, thus 9 was chosen.

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8
Q

What/which thermal limit does the scram function of the CRD protect?

A

All three (MCPR, LHGR, APLHGR)

Also protects against overpressure in conjuction with SRVs.

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9
Q

What are “slow” control rods & what requirements exist regarding their locations in the core?

At what point is a “slow” control rod considered inopreable?

A

Rods whose scram times do not conform to TS scram time requirements.

Can not be adjacent to any other slow control rods or stuck control rods.

If scram time is > 7 seconds, rod is inoperable.

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10
Q

How is scram accumulator operability determined?

A

Based on maintaining adequate accumulator pressure.

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11
Q

What does the BPWS (Rod Pattern Controller) protect from?

Why is this applicable only below 19% RTP?

A

Protects from postulated control rod drop accident resulting in peak fuel energy deposition > 280 cal/gram, thus reactor pressure is guaranteed to stay below ASME limits, and offsite dose will be within required limits.

Above 19% RTP, no credible control rod configuration results in any control rod worth that could exceed the energy deposition limits in a CRDA.

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12
Q

What does compliance with each thermal limit LCO guarantee?

A

APLHGR - Ensure peak clad temp during postulated DBA LOCA does not exceed limit.

MCPR - Ensures no fuel damage results during anticipated operational occurrences and that 99.9% of the fuel rods avoid transition boiling.

LHGR - Ensures fuel design limits are not exceeded anywhere in the core during normal ops, AOOs, and PCT during postulated DBA LOCA does not exceed limits - specifically the 1% plastic strain.

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13
Q

What protection does the scram function provide?

A

Preserve integrity of fuel cladding
Preserve integrity of the RCS boundary
Minimize energy that must be absorbed following a LOCA.

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14
Q

What does the IRM Neutron High Flux scram protect from?

A

Local control rod withdrawal error, maintains energy deposition < 170 cal/gm.

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15
Q

What does the APRM Neutron Flux High scram protect from?

What about its setdown mode?

A

Assumed to terminate the MSIV closure event and in conjunction with the SRVs limits peak pressure below ASME limits.

Setdown is not credited for anything, but is assumed to both act as a backup to the IRM High Flux scram and prevent fuel damage during a reactivity increase event below 23.8% RTP.

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16
Q

What does the APRM Flow Biased simulated thermal power high scram protect from?

A

Slow thermal power increases (such as loss of FW heating) and protects fuel cladding integrity ensuring MCPR SL is not exceeded.

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17
Q

What does Vessel Steam Dome Pressure High Scram protect from?

A

Not credited for anything, but backs up APRM Neutron Flux High and protects from overpressure condition of vessel.

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18
Q

What does the Rx Lvl 3 Scram ensure?

A

The scram is inserted in the DBA LOCA to reduce energy required to be absorbed along with the actions of the ECCS systems ensures PCT remains below limits.

Ensures that in a loss of all normal feedwater flow, initiation of low pressure ECCS systems will not be required.

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19
Q

What does the L8 scram ensure?

When is it required to be operable?

A

Protects violation of MCPR SL due to gross reactivity add from high water level.

Greater than or equal to 23.8% RTP.

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20
Q

What does the MSIV closure scram protect from?

A

Scram is not credited to any analyzed incident, but, along with the actions of ECCS, ensures that fuel PCT remains below limits.

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21
Q

What is the basis of the high drywell pressure scram?

A

Minimize possibility of fuel damage & reduce amount of energy added to coolant & drywell in the DBA LOCA.

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22
Q

What is the basis of the TSV Closure?

A

Credited for the Turbine trip event, scram, along with EOC RPT, ensures MCPR SL not violated.

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23
Q

What is the basis of the TCV Fast Closure scram?

A

Credited for the Generator Load Reject event, scram, along with the EOC RPT, ensures MCPR SL is not violated.

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24
Q

Unit is at 50% RTP during a startup.

All channels for TSV closure scram & TCV fast closure scram are inoperable. LCO 3.3.1.1 Condition E is entered requiring power reduction to < 38% RTP within 4 hours.

When should power reduction begin?

A

Required no later than 15 minutes after entering Condition E.

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25
Q

What requirements exist regarding APRM indicated power vs heat balance calculated power?

A

APRMs must agree within 2% less conservative. If the APRM is 2% more conservative (indicating higher than calculated heat balance), the adjustment is not required but still performed.

26
Q

What does the rod withdrawal limiter protect?

A

Prevent violation of MCPR SL & 1% plastic strain fuel design limit resulting from a single rod withdrawal error.

27
Q

What provisions allow for the RPC to remain operable when a control rod becomes inoperable and must be bypassed/inserted?

A

S.R. 3.3.2.1.9 - Verify bypassing & movement of control rods required to be bypassed in RACS is in conformance with applicable analysis by a second licensed operator or other qualified member of the technical staff.

28
Q

What assumption is the Mode Switch credited for?

A

Mode Switch inserts a rod block, preserving assumptions of the safety analysis and ensuring reactor remains subcritical.

29
Q

When is the RWL considered inoperable?

What MUST be done in this situation?

A

Main turbine bypass valve(s) is/are not fully closed & Thermal Power > LPSP.

Withdrawal shall be prevented and verified by a second licensed operator or other technically qualified member of the unit staff.

30
Q

What is the basis of the EOC-RPT?

A

Trips recirc pumps to reduce peak reactor pressure & power resulting from a turbine trip or generator load reject transient, provide additional margin to MCPR safety limit.

31
Q

Which breakers are required to be operable for EOC-RPT operability?

A

3 Breakers

32
Q

What does the ATWS-RPT protect?

A

Preserves integrity of fuel cladding following event in which scram does not, but should occur.

33
Q

Design basis of ECCS is based on one single principal, what is it?

A

Limit post LOCA peak cladding temperature to less than federal limits (2200F).

34
Q

Inoperable time delay relays of RHR A or B can render their counterpart LP ECCS pumps inoperable (LPCS or RHR C) as well. Why is this?

A

With TDR inoperable, two pumps starting simultaneously on the same source could result in a failure of both pumps or compromise their function within the assumed response time.

35
Q

Is RCIC an Engineer Safety Feature System?

A

No.

36
Q

What is the basis of the recirc loop flow matching requirement?

A

Ensures that during a LOCA caused by a recirc loop pipe break, the assumptions of the LOCA analysis are satisfied.

37
Q

With flows mismatched greater than TS requirements, which loop is declared inoperable?

A

The loop with the lower flow is considered inoperable.

38
Q

What is the basis of the Jet Pump structural integrity requirement?

A

Maintains the 2/3s floodable volume, an assumption in design analysis.

39
Q

What is the acceptance criteria for ECCS

A
  1. Max fuel cladding temp less than or equal to 2200F
  2. Max cladding oxidation is less than or equal to 0.17x total cladding thickness before oxidation.
  3. Max hydrogen generation from zirc water reaction is less than or equal to 1% of the hypothetical amount that would be generated if all of the metal in the cladding surrounding the fuel, except around the plenum volume, were to oxidize.
  4. Core is maintained in a coolable geometry.
  5. Adequate long term cooling capability maintained.
40
Q

What does RCIC operability guarentee?

A

Adequate core cooling such that actuation of any of the ECCS subsystems is not required in the event of RPV isolation accompanied by a loss of feedwater flow.

41
Q

What requirements exist for entry/exit of the Containment through an inoperable door?

What activities are permitted with entry through an inoperable door? Any exceptions?

A

Administrative controls to include a dedicated individual that ensures door closure except during entry/exit, and also assures door is relocked after entry/exit.

Tech Spec surveillances & required actions, activities supporting TS or TS required equipment, responding to fire alarms, or personnel safety.

Allowed to do other stuff if entry was to satisfy tech spec related stuff.

42
Q

How does SRIA affect PCIV operability?

A

Outboard MSIVs require B train of SRIA with pressure > 45 psig to meet their operability requirements.

43
Q

What does containment spray provide?

A

Mitigate drywell bypass leakage paths
Maintain primary containment pressure below design limits
Scrub containment atmosphere for dose reduction

44
Q

Testing is in progress with RCIC running. How often is suppression pool temperature supposed to be checked?

How is this documented?

A

Every five minutes.

SVI-D23-T1213.

45
Q

What are the 5 constraints accounted for by the suppression pool level tech spec requirement?

A
  1. Maintain 2 ft minimum post-loca horizontal vent coverage
  2. Maintain adequate ECCS pump NPSH
  3. Adequate depth for vortex prevention
  4. Adequate depth for minimum recirculation volume
  5. Minimize hydrodynamic loads on submerged structures during SRV & horizontal vent steam discharges
46
Q

How many igniters are allowed to be inoperable per division?

A

5

47
Q

Both Hydrogen igniters are inoperable, what alternate means must be verified within 1 hour of entering condition?

A

At least one recombiner AND one CGM subsystem.

48
Q

Both CGM subsystems are inoperable. What must be verified within one hour of entering this condition?

A

Alternate hydrogen control capabilities: one recombiner or one division of ignitors.

49
Q

At what pressure is the secondary containment inoperable?

A

Less than or equal to 0.66” H2O

50
Q

What is the Drywell DP Tech Spec requirement and what is the basis of this range?

A

-0.5 psid to 2.0 psid, based on ensuring water does not get forced over the weir wall, vent clearing does not occur during normal ops, & pool loads/drywell pressure are within design values.

51
Q

What is the design temperature of the Drywell & at what temperature will a DBA stay below this threshold?

A

330F

145F (EOP-2 Entry Condition)

52
Q

Sluice gate maintenance on Div 1 requires the sluice gate to be removed from operability.

What actions must be done to ensure that failure of the remaining sluice gate does not affect the capabilities of the ESW systems?

A

Either:

Enter the condition for the LCO of the applicable ESW division and take the necessary actions or;

Align ESW loops to the swale and deactivate one of the sluice gates in the open position. This method must ensure that SW discharge to the discharge tunnel will not raise temperatures of the ESW forebay & inlet exceeding design limits.

53
Q

What is the concern for the requirements of maintaining the control room envelope integrity?

What are the design metrics associated with habitability ensured by the CRER system?

A

In leakage that, during a DBA, could have radiological implications for the control room beyond design limits.

Maintain habitable environment in the CRE for 30 days of continuous occupancy after a DBA without exceeding 5 Rem TEDE.

54
Q

What does operability of the Control Room HVAC system ensure?

A

30 days of continuous occupancy in a habitable environment & ensures the operability of components in the control room.

55
Q

With spent fuel in a pool, how high must the water level be above the top of that fuel?

What is the basis of this requirement?

A

23 Ft

Scrub iodine in a fuel handling accident.

56
Q

What is an “offsite circuit” regarding LCO 3.8.1?

A

Startup transformer thru IB transformer, thru the feeder breakers of each division.

57
Q

How fast must DGs come up to rated speed & voltage and tie to their respective busses in order to be considered operable?

A

Within 10 (Div 1/2) or 13 (Div 3) seconds of receipt of a bus undervoltage.

58
Q

How many air start subsystems are required for operability of each DG?

A

Div 1 & 2 only need one air start subsystem to be operable.

Div 3 needs both.

59
Q

What are the 6-day fuel and lube oil supply levels for all diesels?

A

Div 1 & 2:
Fuel -> 65,100 Gallons
Lube -> 350 Gallons

Div 3:
Fuel -> 32,000 Gallons
Lube -> 236 Gallons

60
Q

What are the DG Starting air pressure limits & what is their basis?

A

210 PSIG required for five successive DG start attempts.

165 PSIG is required for one start, and must be declared inoperable below this.

61
Q

What are the components of the divisional DC subsystems that are considered for operability?

A

Div 1:
Unit 1 or 2 battery, Unit 1 or Reserve charger

Div 2:
Unit 1 or 2 battery, Unit 1 or Reserve charger

Div 3:
Div 1 or 2 battery, Unit 1 or reserve charger.