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RO31 ILT > Intro to Tech Specs > Flashcards

Intro to Tech Specs Flashcards

1
Q

What is the name of Tech Spec Chapter 1

A

Use and Application

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2
Q

What is the name of Tech Spec Chapter 2

A

Safety Limits

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3
Q

What is the name of Tech Spec Chapter 3

A

Limiting Conditions

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4
Q

What is the name of Tech Spec Chapter 4

A

Design Features

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5
Q

What is the name of Tech Spec Chapter 5

A

Admin Controls

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6
Q

What is the lowest functional capability or performance level of equipment required for safe operation of the facility?

A

Limiting Condition for Operation (LCO)

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7
Q

What is the TS 2.1.1.1 limit for DNBR with WRB-1 DNB?

A

≥ 1.17

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8
Q

What is the TS 2.1.1.1 limit for WRB-3 correlation with a DNBR where WRB-1 correlation is not applicable?

A

≥ 1.30

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9
Q

What is the TS 2.1.1.2 limit for peak fuel centerline temp?

A

< 5080°F and decreasing by 58°F/10,000 MWD/MTU

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10
Q

What does TS 2.1.2 state?

A

RCS pressure shall be maintained ≤ 2735# in Modes 1-5

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11
Q

What mode(s) is TS 2.1.2 required to be maintained?

A

Modes 1-5

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12
Q

What is TS 2.1.1?

A

Safety Limits

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13
Q

If TS Safety Limit 2.2.1 is violated, what needs to be done?

A

Required to be in Mode 3 w/in 1 hr

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14
Q

If TS Safety Limit 2.1.2 is violated in mode 2, what needs to be done?

A

Restore RCS pressure to ≤ 2735# (compliance) and be in mode 3 w/in 1 hr

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15
Q

If TS Safety Limit 2.1.2 is violated in mode 3 or 4, what needs to be done?

A

Restore RCS pressure to ≤ 2735# (compliance) within 5 minutes

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16
Q

What mode are you in if you have a Keff at .98 with RCS temp at 375°F?

A

Mode 3 - Hot Standby

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17
Q

What mode are you in if you have a Keff at .98 with RCS temp of 202°F?

A

Mode 4 - Hot Shutdown

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18
Q

What mode are you in if you have a Keff at .98 with RCS temp of 185°F?

A

Mode 5 - Cold Shutdown

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19
Q

What mode are you in if you have a Keff at .99 with rated thermal power at 5%?

A

Mode 2 - Startup

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20
Q

What mode are you in if you have a Keff at .99 with rated thermal power at 7%?

A

Mode 1 - Power Operation

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21
Q

If you just fully tensioned the last Reactor Head Bolt with RCS temp of 185°F, what mode are you in?

A

Mode 5 - Cold Shutdown

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22
Q

If you have all but one head bolt fully tensioned, what mode are you in?

A

Mode 6 - Refueling

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23
Q

If you just fully tensioned the last Reactor Head Bolt with RCS temp of 207°F, what mode are you in?

A

Mode 4 - Hot Shutdown

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24
Q

Surveillance Requirements 3.0.1 - 3.0.4 are general rules applicable to?

A

Chapter 3 Technical Specification SRs

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25
Q

What are the assumptions of Final Safety Analysis Report (FSAR)?

A
  • One train of ECCS is assumed to fail
  • One instrument failure would neither cause or prevent ECCS actuation
  • One accumulator is lost through a break
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26
Q

Surveillance Requirement 3.0.1 states?

A

Surveillance requirements must be met

27
Q

Surveillance Requirement 3.0.2 states?

A

Grace period of 25% (Drop dead due date)

28
Q

Surveillance Requirement 3.0.3 states?

A

Missed surveillance, meet within 24 hrs or normal surveillance frequency, whichever is greater

29
Q

Surveillance Requirement 3.0.4 states?

A

LCO surveillances must be met before a mode change

30
Q

What does LCO 3.0.3 state?

A
  1. When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or
  2. if directed by the associated ACTIONS, the unit shall be placed in a MODE or
  3. other specified condition in which the LCO is not applicable.

Action shall be initiated within 1 hour to place the unit, as applicable, in:

a. MODE 3 within 7 hours;
b. MODE 4 within 13 hours; and
c. MODE 5 within 37 hours.

31
Q

What are the 8 major ESFAS functional units?

A
  1. SI
  2. CTS
  3. Containment Isolation
  4. Steam Line Isolation
  5. Turbine Trip and FW Iso
  6. AFW
  7. Cnt Air Recirc/CEQ System
  8. ESFAS Interlocks
32
Q

What is the purpose of the Reactor Core Safety Limits?

A

Prevent overheating of the fuel and cladding, which would result in release of fission products to the RCS if not prevented

33
Q

What is the purpose of the RCS pressure Safety Limits

A

Prevents over pressurization of the RCS and maintains integrity which then prevents the release of radionuclides contained in the RCS from reaching the cnt atmo

34
Q

What are the Reactor Trips?

A
  1. Overpower ΔT
  2. Overtemp ΔT
  3. Pzr Pressure high
  4. Pzr Pressure low
  5. Pressurizer Level High
  6. RCP Bus Undervoltage
  7. RCP bus underfreq
  8. Turbine Trip
    - Auto Stop Oil #
    - Turbine Stop Valve Closure
  9. SG Level Low Low
  10. SG Level Low with ST Flow/Feed Flow Mismatch
  11. SI
  12. RCS Loop Flow low
  13. RCP Bkr position
  14. Pwr Range Neutron Flux High - set point
  15. Pwr Range Neutron Flux Low - set point
  16. Pwr Range High positive rate
  17. Intermediate Range Neutron Flux high
  18. Source Range Neutron Flux high
  19. Manual
35
Q

Can you extend a Surveillance Requirement if its the initial surveillance after the initial event?

A

No, you can only extend 25% for subsequent surveillances after the initial surveillance has been complete

36
Q

What is the instantaneous amount of reactivity by
which the reactor is subcritical or would be subcritical from its present condition assuming a single rod of highest reactivity worth is assumed to be fully withdrawn

A

Shutdown Margin (SDM)

37
Q

Define Operable/Operability

A

When a system and all of its aux equipment are capable of performing its specified safety function(s) and related support function(s)

38
Q

The amount of time allowed for completion of a Required Action is the definition of?

A

Completion Time

Required Actions must be completed prior to the expiration of the specified Completion Time

39
Q

Pursue without delay and in a controlled manner is the definition of?

A

Immediately

40
Q

Define mode

A

A MODE shall correspond to any one inclusive combination of:

  • Core Reactivity Condition (Keff)
  • Rated Thermal Power (%)
  • Average Reactor Coolant Temperature (°F)
  • Reactor vessel head closure bolt tensioning
41
Q

Define Core Alteration

A

Core Alteration shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of Core Alteration shall not preclude completion of movement of a component to a safe position.

42
Q

Equipment is assumed to be Operable if its what are met?

Ref SR 3.0.1

A

If its SRs are met

43
Q

Equipment is inoperable if?

Ref SR 3.0.1

A

Equipment is Inoperable if

  • It is known to be inoperable, even if the SRs are current
  • An SR is known not to be met, even if the SR is between its required performance interval
44
Q

Surveillance Requirements do not have to be performed if?

A

when the associated LCO is not applicable, unless specifically stated, or on inoperable equipment or variables that are outside limits

45
Q

Do Surveillance Requirements have to be performed following maintenance prior to returning equipment to Operable status?

A

Yes, unless otherwise stated

46
Q

Is SR 3.0.2 used to routinely extend the performance intervals?

A

No, it is not intended to be used to routinely extend the performance interval. It allows for unforeseen problems that may prevent performance of the SR during the normal interval. 25% extended time if needed

47
Q

Which Surveillance Requirement allows for an operational relief if a surveillance is missed?

A

SR 3.0.3

24 hours or the specified Frequency

48
Q

If the 24 hr delay period is surpassed within SR 3.0.3, what must you do?

A

A risk evaluation must be performed

49
Q

Define “Met” with respect to Surveillance Requirements

A

Implies all acceptance criteria are known or understood to be satisfied

50
Q

Define “Performed” with respect to Surveillance Requirements

A

A Surveillance Requirement must be run to demonstrate that all Acceptance Criteria are “met

51
Q

What are the ESFAS Functional Areas?

A
  1. Safety Injection (SI)
  2. Containment Spray
  3. Containment Isolation
  4. Steam Line Isolation
  5. Turbine Trip and Feedwater Isolation
  6. Auxiliary Feedwater
  7. Containment Air Recirculation/Hydrogen Skimmer (CEQ) System
  8. ESFAS Interlocks
52
Q

Why is there a shorter time constraint (5 minutes) while in Modes 3,4, and 5 with the TS Safety Limit Violation 2.2.2.2?

A

Brittle Fracture is more likely

53
Q

Define Loss of Safety Function

A

A LOSF exists when, assuming no concurrent single failure, and assuming no concurrent loss of offsite power or loss of onsite EDG(s), a safety function assumed in the accident analysis cannot be performed. A LOSF may exist when a support system is inoperable and a required system redundant to the support or supported systems is also inoperable

54
Q

What does LCO 3.0.5 state?

A

Allows testing under admin control

55
Q

What does LCO 3.0.6 state?

A

Do not need to cascade unless there is a loss of safety function

56
Q

What does LCO 3.0.7 state?

A

Physics Tests

57
Q

What does LCO 3.0.8 state?

A

AFW - do not declare system inop based solely on the required barriers be inoperable

58
Q

What does LCO 3.0.1 state?

A

LCO must be met during mode of applicability

59
Q

What does LCO 3.0.2 state?

A

Failure to meet the LCO, the actions of the condition must be met

60
Q

What are the 5 rules of LCO 3.0.2?

A

Rule 1
- actions of a tech spec are not required until the discovery of a failure to meet the LCO

Rule 2
- plant operation may continue if an LCO is not met as long as the req. of the actions are met

Rule 3
- if a condition has been entered but the req of the LCO are met before expiration of the completion time, completion of req action is not required unless otherwise stated

Rule 4
- “unless otherwise stated” refers to instances that require completion of required actions even if the affected equip is declared operable

Rule 5
- all of the actions requirements are applicable every time a TS condition is entered

61
Q

What are the assumptions of the Final Safety Analysis Review (FSAR)

A

Assumed that:

  • 1 Train of ECCS fails
  • 1 instrument failure WILL NOT cause or prevent an ECCS actuation
  • 1 Accumulator lost due to a break
62
Q

What is the TS Safety Limit Bases?

A

Bases on not violating following fuel criteria

 - 95% probability with 95% confidence level that the hottest fuel rod in the core does not experience DNB
 - 95% probability with 95% confidence level that the hottest fuel pellet in the core will not experience centerline fuel melting
63
Q

Programs from which T.S. chapter must have written procedures established, implemented, and maintained?

A

T.S. Chapter 5, Admin Ctrls

RO31 ILT (56 decks)

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