Tech Spec SRO Highly Likely Flashcards
TS 3.1.3 Control Rod OPERABILITY
LCO AND Applicability Only
LCO - Each Control Rod shall be OPERABLE
Applicability - Modes 1 and 2
TS 3.1.3 Control Rod OPERABILITY
Condition A
One withdrawn control rod stuck
Disarm - 2 hours AND CRD Exercise (N/A if < LPSP) - 24 hours AND SDM - 72 hours
TS 3.1.3 Control Rod OPERABILITY
Condition B
Two or more withdrawn control rods stuck - Actions
Disarm - 2 hours
AND
Mode 3 - 12 hours
TS 3.1.3 Control Rod OPERABILITY
Condition C
One or more control rods inop
(for reasons other than being stuck in the withdrawn position)
Fully Insert - 3 hours
AND
Disarm - 4 hours
TS 3.1.3 Control Rod OPERABILITY
Condition D
Two or more inop rods not in compliance with BPWS
N/A when > 10% RTP
Restore BPWS - 4 hours
OR
Restore CR to OPER - 4 hours
TS 3.1.3 Control Rod OPERABILITY
Condition E
Nine or more control rods inoperable
Mode 3 - 12 hours
TS 3.4.1 Recirculation Loops Operating
LCO AND Applicability Only
LCO - Two recirc loops w/ matched flows
OR
One recirc loop w/ the following limits
- APLHGR per COLR
- MCPR per COLR
- LHGR per COLR
- APRM STP - High adjusted for single loop
Applicability - Mode 1 and 2
TS 3.4.1 Recirculation Loops Operating
Condition A
Requirements of the LCO not met
Satisfy the LCO - 24 hours
TS 3.4.1 Recirculation Loops Operating
Condition B
No Loops in Operation
Mode 3 - 12 hours
TS 3.4.5 RCS Leakage Detection Instrumentation
LCO and Applicability
LCO - The following RCS leakage detection instrumentation shall be OPERABLE:
a. Drywell floor drain sump monitoring system; and b. One channel of primary containment atmospheric particulate or gaseous monitor system.
Applicability - Modes 1, 2, and 3
TS 3.4.5 RCS Leakage Detection Instrumentation
Condition A
Drywell floor drain sump monitoring system inop
Restore sump to Operable status - 30 days
TS 3.4.5 RCS Leakage Detection Instrumentation
Condition B
Primary containment atmospheric monitor system inop
Grab samples - Once per 12 hours
AND
Restore to Operable - 30 days
TS 3.4.5 RCS Leakage Detection Instrumentation
Condition D
All leakage detection systems inop
Enter LCO 3.0.3 Immediately
TS 3.5.1 ECCS - Operating
LCO and Applicability
LCO - Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six of seven safety/relief valves shall be OPERABLE.
Applicability - Mode 1,
Mode 2 and 3, except HPCI and ADS when Steam Dome ≤ 150 psig.
TS 3.5.1 ECCS - Operating
Condition A
One Low Pressure ECCS injection/spray subsystem INOP
OR
One LPCI pump in both LPCI subsystems INOP
Restore to Operable - 7 days
TS 3.5.1 ECCS - Operating
Condition C
HPCI System INOP
Verify RCIC Operable by administrative means - 1 hour
AND
Restore HPCI to Operable - 14 days
TS 3.5.1 ECCS - Operating Condition D HPCI INOP AND Cond A (One LP ECCS INOP OR one LPCI pump in each loop INOP)
Restore HPCI to Operable - 72 hours
OR
Restore LP ECCS to Operable - 72 hours
TS 3.5.1 ECCS - Operating
Condition F
Two or more ADS valves INOP
MODE 3 - 12 hours
AND
Reduce Steam Dome to ≤ 150 psig - 36 hours
TS 3.5.1 ECCS - Operating Condition G Two or more LP ECCS INOP OR HPCI and Two or more ADS valves INOP
LCO 3.0.3 - Immediately
TS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)
LCO and Applicability
LCO - Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE.
Applicability - Modes 1, 2, and 3
TS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)
Condition A
(Note: Applicable to penetrations w/ two PCIVs)
One or more penetration flow paths with one PCIV inoperable except due to leakage not within limit.
Isolate penetration flow path - 4 hours (8 hours MSL)
AND
Verify isolated - Once per 31 days (AND prior to entering MODE 2 or 3 from MODE 4 if de-inerted and if not performed within previous 92 days for isolation devices inside Primary Containment)
TS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)
Isolation is accomplished by one of the following:
- closed de-activated automatic valve
- closed manual valve
- blind flange
- check valve with flow through valve secured
TS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)
Notes:
What valves are not allowed to be unisolated intermittently under admin controls?
Note 1: Penetration flow paths except for 18 inch purge valve penetration flow paths may be unisolated intermittently under administrative controls.
TS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)
Notes:
Is LCO 3.0.6 (support/supported system; cascading) applicable to PCIVs? In other words, since the PCIV is INOP, do I also enter the spec for the INOP component supported by the PCIV?
Note 3: Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.
Example: 2E41-F003 fails and is manually isolated per 3.6.1.3 Cond A. I also enter LCO 3.5.1 Cond C for HPCI being INOP.
TS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)
Condition B
(Note: Applicable to penetrations w/ two PCIVs)
One or more penetration flow paths with two PCIVs inoperable except due to leakage not within limit.
Isolated penetration flow path - 1 hour
TS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)
Condition C
(Note: Applicable to penetrations w/ one PCIV)
One or more penetration flow paths with one PCIV inoperable except due to leakage not within limits.
Isolate penetration flow path - 4 hours (except for EFCV and Closed Systems)
AND
Isolate penetration flow path - 72 hours (EFCV and Closed Systems)
AND
Verify isolated - Once per 31 days
TS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)
Condition D
One or more penetration flow paths with leakage not within limit.
Restore Leakage - 4 hours
TS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)
Isolation devices verification requirement exceptions.
When am I allowed to verify the device by administrative means?
————NOTES———–
- Isolation devices in high radiation areas may be verified by use of administrative means.
- Isolation devices that are locked, sealed, or otherwise secured may be verified by administrative means.
TS 3.8.1 AC Sources - Operating
LCO and Applicability
LCO - The following AC electrical power sources SHALL be OPERABLE:
a. 2 qualified offsite circuits
b. 2 EDGs
c. 1 swing EDG
d. 1 Opposite unit EDG
e. 1 Opposite unit offsite circuit (supports SBGT, MCREC, and CR AC system)
f. 2 EDGs (any combo of Opposite Unit EDGs and Swing Diesel to support LPCI valves)
g. 1 Opposite unit offsite circuit (supports LPCI valves)
Applicability - 1, 2, and 3
TS 3.8.1 AC Sources - Operating
Condition A
One required offsite circuits inop
Perform breaker alignment (SR 3.8.1.1) - 1 hour and once per 8 hours
AND
Declare feature with no offsite circuit inop - 24 hours from discovery of no offsite concurrent with redundant features inop
AND
Restore offsite to Operable - 72 hours
TS 3.8.1 AC Sources - Operating
Condition B
Current Unit’s EDG or swing EDG Inop
Perform breaker alignment (SR 3.8.1.1) - 1 hour and once per 8 hours
AND
Declare feature supported by EDG inop - 4 hours from discovery concurrent with redundant features inop
AND
Perform Common Cause - 24 hours
OR
Run the other diesels - 24 hours
AND
Restore EDG to Operable - 72hours (14 days when inhibited or maintenance restrictions met)
TS 3.8.1 AC Sources - Operating
Condition C
Opposite Unit’s EDG inop
Perform breaker alignment (SR 3.8.1.1) - 1 hour and once per 8 hours
AND
Declare feature supported by EDG inop - 4 hours from discovery concurrent with redundant features inop
AND
Perform Common Cause - 24 hours
OR
Run the other diesels - 24 hours
AND
Restore EDG to Operable - 7 days (14 days when inhibited or maintenance restrictions met)
TS 3.8.1 AC Sources - Operating
Condition D
2 or more required offsite circuits inop
Declare feature with no offsite circuit inop - 12 hours from discovery of Cond D concurrent inoperability of redundant required feature(s)
AND
Restore all but one offsite to Operable - 24 hours
TS 3.8.1 AC Sources - Operating Condition E One offsite circuit inop AND One EDG Inop
Note: Enter 3.8.7 for 4160 with not power.
Restore offsite circuit to Operable - 12 hours
OR
Restore EDG to Operable - 12 hours
TS 3.8.1 AC Sources - Operating
If a 4160V bus becomes de-energized due to a combination of offsite circuit inop and EDG inop, is LCO 3.0.6 (support/supported; cascading) applicable? Do I have to enter 3.8.7 for the de-energized bus or only enter the applicable 3.8.1 spec?
3.8.1 Condition E Note:
Enter applicable Conditions and Required Actions of LCO 3.8.7, “Distribution Systems - Operating,” when Condition E is entered with no AC power source to one 4160 V ESF bus.
TS 3.8.1 AC Sources - Operating
Condition F
2 or more EDG’s INOP
(same unit’s EDG and swing)
Restore all but one EDG to Operable - 2 hours
TS 3.8.1 AC Sources - Operating
Condition G
No EDGs capable of suppling power to any of the current unit’s LPCI load center.
Restore one EDG to Operable - 2 hours
TS 3.8.1 AC Sources - Operating
Condition I
One or more offsite circuits and two or more EDGs inop
OR
Two or more offsite circuits and one EDG inop
LCO 3.0.3 - Immediately
TS 3.8.7 Distribution Systems - Operating
LCO and Applicability
LCO - The following AC and DC electrical power distribution subsystems shall be Operable:
a. Current Units AC and DC
1. 4160V E, F, & G
2. 600V C & D
3. Essential A & B
4. Instrument Bus A & B
5. 125/250DC Station Service Buses A & B
6. EDG DC Subsystem
7. Critical Instrument Bus A & B
b. Opposite Unit AC and DC to support SBGT, MCREC and CR AC systems.
Applicability - Modes 1, 2, and 3
TS 3.8.7 Distribution Systems - Operating
Condition A
One or more opposite unit’s AC or DC subsystems inop
Restore to Operable - 7 days
TS 3.8.7 Distribution Systems - Operating
Condition B
One or more current unit’s EDG DC subsystems inop
Restore to Operable - 12 hours
TS 3.8.7 Distribution Systems - Operating
Condition C
One or more AC distribution subsystems inop (eg listed bus inop)
Restore to Operable - 8 hours
TS 3.8.7 Distribution Systems - Operating
Condition D
One current unit’s station service DC distribution subsystem inop
Restore to Operable - 2 hours
TS 3.8.7 Distribution Systems - Operating
Condition F
Two or more electrical subsystems inoperable that result in a loss of function
LCO 3.0.3 - Immediately
TS 3.9.1 Refueling Equipment Interlocks
LCO and Applicability
LCO - The refueling equipment interlocks shall be OPERABLE.
Applicability - During in-vessel fuel movement with equipment associated with the interlocks.
TS 3.9.1 Refueling Equipment Interlocks
Condition A
One or more required interlocks inop
Suspend in-vessel fuel movement - Immediately
OR
Insert CR Block - Immediately
AND
Verify all control rods are fully inserted - Immediately
TS 3.9.2 Refuel Position One-Rod-Out Interlock
LCO and Applicability
LCO - The refuel position one-rod-out interlock shall be OPERABLE.
Applicability - MODE 5 with the reactor mode switch in the refuel position and any control rod withdrawn
TS 3.9.2 Refuel Position One-Rod-Out Interlock
Condition A
Interlock Inop
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
TS 3.9.3 Control Rod Position
LCO and Applicability
LCO - All control rods shall be fully inserted
Applicability - When loading fuel assemblies into the core
TS 3.9.3 Control Rod Position
Condition A
One or more control rods not fully inserted
Suspend loading fuel assemblies into the core - Immediately
TS 3.9.4 Control Rod Position Indication
LCO and Applicability
LCO - The control rod full-in position indication channel for each control rod shall be operable
Applicability - MODE 5
TS 3.9.4 Control Rod Position Indication
Condition A
One or more required CR position indication channels inop
Suspend in-vessel fuel movement - Immediately
AND
Suspend control rod withdrawal - Immediately
AND
Insert all insertable control rods with cells containing one or more fuel assemblies - Immediately
OR
Fully insert control rod with inop position - Immediately
AND
Initiate action to disarm control rod - Immediately
TS 3.9.4 Control Rod Position Indication
Condition A Question
One or more required CR position indication channels inop. Required Action Fully insert and disarm control rod.
Can the full in channel be bypassed to allow fuel movement to proceed?
Under these conditions (control rod fully inserted and disarmed), an inoperable full-in channel may be bypassed to allow refueling operations to proceed. An alternate method must be used to ensure the control rod is fully inserted (e.g., use the “00” notch position indication).
TS 3.9.4 Control Rod Position Indication
Condition A Question
One or more required CR position indication channels inop. Required Action Fully insert and disarm control rod.
What method(s) are allowed by this spec to disarm the control rod with the inop position indication?
Alternatively, actions must be immediately initiated to fully insert the control rod(s) associated with the inoperable full-in position indicator(s) and disarm (electrically or hydraulically) the drive(s) to ensure that the control rod is not withdrawn.
A control rod can be hydraulically disarmed by closing the drive water and exhaust water isolation valves.
A control rod can be electrically disarmed by disconnecting power from all four direction control valve solenoids.
TS 3.9.5 Control Rod OPERABILITY - Refueling
LCO and Applicability
LCO - Each withdrawn control rod shall be operable.
Applicability - MODE 5
Bases: The withdrawn control rod is considered OPERABLE if the scram accumulator pressure is ≥ 940 psig and the control rod is capable of being automatically inserted upon receipt of a scram signal.
TS 3.9.5 Control Rod OPERABILITY - Refueling
Condition A
One or more withdrawn control rods inop
Initiate action to fully insert inop withdrawn rods - Immediately
TS 3.9.5 Control Rod OPERABILITY - Refueling
LCO Bases
What is required for a withdrawn control rod to be Operable per this spec?
The withdrawn control rod is considered OPERABLE if:
1) the scram accumulator pressure is ≥ 940 psig and,
2) the control rod is capable of being automatically inserted upon receipt of a scram signal.
Inserted control rods have already completed their reactivity control function, and therefore, are not required to be Operable.
TS 3.9.6 Reactor Pressure Vessel (RPV) Water Level
LCO and Applicability
LCO - RPV water level shall be ≥ 23 ft above the top of the irradiated fuel assemblies seated within the RPV.
Applicability - During movement of irradiated fuel assemblies within the RPV, During movement of new fuel assemblies or handling of control rods within the RPV, when irradiated fuel assemblies are seated within the RPV.
TS 3.9.6 Reactor Pressure Vessel (RPV) Water Level
Condition A
RPV water level not within limit
Suspend movement of fuel assemblies and handling of control rods within the RPV - Immediately
TS 3.9.6 Reactor Pressure Vessel (RPV) Water Level
Bases Question
Why does the water level have to be ≥23ft above TAF in the RPV?
Sufficient water is necessary to retain iodine fission product activity in the water in the event of a fuel handling accident.
TS 3.9.6 Reactor Pressure Vessel (RPV) Water Level
Bases Question
IAW TS 3.9.6, what part of the fuel assembly is considered to be TAF?
The point from which the water level is measured is shown in Figure B 3.9.6-1 (Bases).
The point at which is indicated in the picture is the top of the upper tie plate. Not the bail handle.
TS 3.9.7 Residual Heat Removal (RHR) - High Water Level
LCO and Applicability
LCO - One RHR shutdown cooling subsystem shall be OPERABLE and in operation.
Applicability - MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level ≥ 22 ft 1/8 inches above the top of the RPV flange.
TS 3.9.7 Residual Heat Removal (RHR) - High Water Level
LCO and Applicability Question
Under what conditions can the RHR SDC subsystem be removed from service AND during the time the subsystem is removed from service, is it still considered Operable?
NOTE:
The required RHR shutdown cooling subsystem may be removed from operation for up to 2 hours per 8 hour period.
Additionally, each RHR shutdown cooling subsystem is considered OPERABLE if it can be manually aligned (remote or local) in the shutdown cooling mode for removal of decay heat.
TS 3.9.7 Residual Heat Removal (RHR) - High Water Level
Condition A
Required RHR shutdown cooling subsystem inoperable.
Verify an alternate method of decay heat removal is available. - 1 hour AND Once per 24 hours
TS 3.9.7 Residual Heat Removal (RHR) - High Water Level
Condition C
No RHR shutdown cooling subsystem in operation.
Verify reactor coolant circulation by an alternate method. - 1 hour from discovery of no circulation AND Once per 12 hours
AND
Monitor coolant temp - Once per hour
TS 3.9.7 Residual Heat Removal (RHR) - High Water Level
LCO Question
What is required for an RHR SDC subsystem to be considered operable IAW this spec?
An OPERABLE RHR shutdown cooling subsystem consists of one RHR pump and the associated heat exchanger, one RHRSW pump providing cooling to the heat exchanger with sufficient flow to maintain reactor coolant temperature in the desired range, valves, piping, instruments, and controls to ensure an OPERABLE flow path. RHR Crosstie valve is NOT required to be closed, therefore valve may be opened to allow RHR pumps in one loop to discharge through the opposite loop to make a complete subsystem.
i.e. 1 pump, 1 Hx, and 1 RHRSW pump
TS 3.9.8 Residual Heat Removal (RHR) - Low Water Level
LCO and Applicability
LCO - Two RHR shutdown cooling subsystems shall be OPERABLE, and one RHR shutdown cooling subsystem shall be in operation.
Applicability - MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level < 22 ft 1/8 inches above the top of the RPV flange.
TS 3.9.8 Residual Heat Removal (RHR) - Low Water Level
Condition A
One or two required RHR shutdown cooling subsystems inoperable.
Verify an alternate method of decay heat removal is available for each inoperable required RHR shutdown cooling subsystem. - 1 hour and Once per 24 hours
TS 3.9.8 Residual Heat Removal (RHR) - Low Water Level
Condition C
No RHR shutdown cooling subsystem in operation.
Verify coolant circulation by alt method - 1 hour from discovery of no circulation AND Once per 12 hours
AND
Monitor Temp - Once per hour
TS 3.9.8 Residual Heat Removal (RHR) - Low Water Level
LCO Question
What is required for an RHR SDC subsystem to be considered operable IAW this spec?
An OPERABLE RHR shutdown cooling subsystem consists of an RHR pump and the associated heat exchanger, an RHRSW pump providing cooling to the heat exchanger with sufficient flow to maintain reactor coolant temperature in the desired range, valves, piping, instruments, and controls to ensure an OPERABLE flow path. The two required RHR shutdown cooling subsystems have a common suction source and are allowed to have a common heat exchanger and common discharge piping.
2 subsystems meet by one of the following combinations:
1 pump in each loop, 2 Hx’s, and 1 RHRSW pumps per Hx.
or
2 pumps in one loop, one HX, and 2 RHRSW pumps for one Hx
