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Technical Specifications > 3.9 REFUELING OPERATIONS > Flashcards

3.9 REFUELING OPERATIONS Flashcards

1
Q

What is the LCO and APPLICABILITY of Technical Specification 3.9.1, Refueling Equipment Interlocks?

A

LCO: The refueling equipment interlocks shall be OPERABLE.

APPLICABILITY: During in-vessel fuel movement with equipment associated with the interlocks.

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2
Q

What are the one hour, or less, actions associated with Technical Specification 3.9.1, Refueling Equipment Interlocks?

A

Condition A: One or more required refueling equipment interlocks inoperable - Suspend in-vessel movement with equipment associated with the inoperable interlock(s) - Immediately
OR
Insert a control rod withdrawal block - Immediately
AND
Verify all control rods are fully inserted - Immediately

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3
Q

What is the LCO and APPLICABILITY of Technical Specification 3.9.2, Refuel Position One-Rod-Out Interlock?

A

LCO: The refuel position one-rod-out interlock shall be OPERABLE.

APPLICABILITY: MODE 5 with the reactor modes switch in the refuel position and any control rod withdrawn.

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4
Q

What are the one hour, or less, actions associated with Technical Specification 3.9.2, Refuel Position One-Rod-Out Interlock?

A

Condition A: Refuel position one-rod-out interlock inoperable - Suspend control rod withdrawal - Immediately
AND
Initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies - Immediately

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5
Q

What is the LCO and APPLICABILITY of Technical Specification 3.9.3, Control Rod Position?

A

LCO: All control rods shall be fully inserted.

APPLICABILITY: When loading fuel assemblies into the core.

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6
Q

What are the one hour, or less, actions associated with Technical Specification 3.9.3, Control Rod Position?

A

Condition A: One or more control rods not fully inserted - Suspend loading fuel assemblies into the core - Immediately

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7
Q

What is the LCO and APPLICABILITY of Technical Specification 3.9.4, Control Rod Position Indication?

A

LCO: One control rod “full-in” position indication channel for each control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

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8
Q

What are the one hour, or less, actions associated with Technical Specification 3.9.4, Control Rod Position Indication?

A

NOTE
Separate Condition entry is allowed for each required channel
******
One or more required control rod position indication channels inoperable - Suspend in-vessel fuel movement - Immediately
AND
Suspend control rod withdrawal - Immediately
AND
Initiate actions to fully insert all insertable control rods in core cells containing one or more fuel assemblies - Immediately
OR
Initiate action to fully insert the control rod associated with the inoperable position indicator - Immediately
AND
Initiate action to disarm the control rod drive associated with the fully inserted control rod - Immediately

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9
Q

What is the LCO and APPLICABILITY of Technical Specification 3.9.5, Control Rod OPERABILITY-Refueling?

A

LCO: Each withdrawn control rod shall be OPERABLE.

APPLICABILITY: MODE 5

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10
Q

What are the one hour, or less, actions associated with Technical Specification 3.9.5, Control Rod OPERABILITY-Refueling?

A

Condition A: One or more withdrawn control rods inoperable - Initiate action to fully insert inoperable withdrawn control rods - Immediately

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11
Q

What is the LCO and APPLICABILITY of Technical Specification 3.9.6, Reactor Pressure Vessel (RPV) Water Level-Irradiated Fuel?

A

LCO: RPV water level shall be greater than 22 ft 9 inches above the top of the RPV flange.

APPLICABILITY: During movement of irradiated fuel assemblies within the RPV.

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12
Q

What are the one hour, or less, actions associated with Technical Specification 3.9.6, Reactor Pressure Vessel (RPV) Water Level-Irradiated Fuel?

A

Condition A: RPV water level not within limit - Suspend movement of irradiated fuel assemblies within the RPV - Immediately

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13
Q

What is the LCO and APPLICABILITY of Technical Specification 3.9.7, Reactor Pressure Vessel (RPV) Water Level-New Fuel or Control Rods?

A

LCO: RPV water level shall be greater than or equal to 23 ft above the top of irradiated fuel assemblies seated within the RPV.

APPLICABILITY: During movement of new fuel assemblies or handling of control rods within the RPV when irradiated fuel assemblies are seated within the RPV.

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14
Q

What are the one hour, or less, actions associated with Technical Specification 3.9.7, Reactor Pressure Vessel (RPV) Water Level-New Fuel or Control Rods?

A

Condition A: RPV water level not within limit - Suspend movement of new fuel assemblies and handling of control rods within the RPV - Suspend movement of new fuel assemblies and handling of control rods within the RPV - Immediately

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15
Q

What is the LCO and APPLICABILITY of Technical Specification 3.9.8, Residual Heat Removal (RHR)-HIgh Water Level?

A

LCO: One RHR shutdown cooling subsystem shall be OPERABLE and in operation.
NOTE
The required RHR shutdown cooling subsystem may be removed from operation for up to 2 hours per 8 hour period.
******

APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and with the water level greater than or equal to 22 ft 9 inches above the top of the RPV flange, and heat losses to the ambient are not sufficient to maintain average reactor coolant temperature less than or equal to 200F.

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16
Q

What are the one hour, or less, actions associated with Technical Specification 3.9.8, Residual Heat Removal (RHR)-HIgh Water Level?

A

Condition A: Required RHR shutdown cooling subsystem inoperable - Verify an alternate method of decay heat removal is available - 1 hour

Condition C: No RHR shutdown cooling subsystem in operation - Verify reactor coolant circulation by an alternate method - 1 hour from discovery of no reactor coolant circulation
AND
Monitor reactor coolant temperature - Once per hour

17
Q

What is the LCO and APPLICABILITY of Technical Specification 3.9.9, Residual Heat Removal (RHR)-Low Water Level?

A

LCO: Two RHR shutdown cooling subsystems shall be OPERABLE, and one RHR shutdown cooling subsystem shall be in operation.
NOTE
The required operating shutdown cooling subsystem may be removed from operation for up to 2 hours per 8 hour period
******

APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and with the water level greater than or equal to 22 ft 9 inches above the top of the RPV flange, and heat losses to the ambient are not sufficient to maintain average reactor coolant temperature less than or equal to 140F.

18
Q

What are the one hour, or less, actions associated with Technical Specification 3.9.9, Residual Heat Removal (RHR)-Low Water Level?

A

Condition A: One or two RHR shutdown cooling subsystems inoperable - Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem - 1 hour

Condition C: No RHR shutdown cooling subsystem in operation - Verify reactor coolant circulation by an alternate method - 1 hour from discovery of no reactor coolant circulation
AND
Monitor reactor coolant temperature - Once per hour

Technical Specifications (15 decks)

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