ML21194A282
Text
CALLAWAY PLANT 3.4-i CHAPTER TABLE OF CONTENTS CHAPTER 3.4 REACTOR COOLANT SYSTEM Section Page 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits............................................................................. 3.4-1 ACTIONS........................................................................................................ 3.4-1 SURVEILLANCE REQUIREMENTS............................................................... 3.4-2 3.4.2 RCS Minimum Temperature for Criticality........................................................... 3.4-3 ACTIONS........................................................................................................ 3.4-3 SURVEILLANCE REQUIREMENTS............................................................... 3.4-3 3.4.3 RCS Pressure and Temperature (P/T) Limits..................................................... 3.4-4 ACTIONS........................................................................................................ 3.4-4 SURVEILLANCE REQUIREMENTS............................................................... 3.4-5 3.4.4 RCS Loops - MODES 1 and 2............................................................................ 3.4-6 ACTIONS........................................................................................................ 3.4-6 SURVEILLANCE REQUIREMENTS............................................................... 3.4-6 3.4.5 RCS Loops - MODE 3......................................................................................... 3.4-7 ACTIONS........................................................................................................ 3.4-7 SURVEILLANCE REQUIREMENTS............................................................... 3.4-9 3.4.6 RCS Loops - MODE 4....................................................................................... 3.4-10 ACTIONS...................................................................................................... 3.4-10 SURVEILLANCE REQUIREMENTS............................................................. 3.4-11 3.4.7 RCS Loops - MODE 5, Loops Filled................................................................. 3.4-13 ACTIONS...................................................................................................... 3.4-14 SURVEILLANCE REQUIREMENTS............................................................. 3.4-15 3.4.8 RCS Loops - MODE 5, Loops Not Filled........................................................... 3.4-16
CHAPTER TABLE OF CONTENTS (Continued)
Section Page CALLAWAY PLANT 3.4-ii ACTIONS...................................................................................................... 3.4-16 SURVEILLANCE REQUIREMENTS............................................................. 3.4-17 3.4.9 Pressurizer........................................................................................................ 3.4-18 ACTIONS...................................................................................................... 3.4-18 SURVEILLANCE REQUIREMENTS............................................................. 3.4-19 3.4.10 Pressurizer Safety Valves................................................................................. 3.4-20 ACTIONS...................................................................................................... 3.4-20 SURVEILLANCE REQUIREMENTS............................................................. 3.4-21 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)....................................... 3.4-22 ACTIONS...................................................................................................... 3.4-22 SURVEILLANCE REQUIREMENTS............................................................. 3.4-25 3.4.12 Cold Overpressure Mitigation System (COMS)................................................ 3.4-26 ACTIONS...................................................................................................... 3.4-27 SURVEILLANCE REQUIREMENTS............................................................. 3.4-29 3.4.13 RCS Operational LEAKAGE............................................................................. 3.4-31 ACTIONS...................................................................................................... 3.4-31 SURVEILLANCE REQUIREMENTS............................................................. 3.4-32 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage.................................................. 3.4-33 ACTIONS...................................................................................................... 3.4-33 SURVEILLANCE REQUIREMENTS............................................................. 3.4-35 3.4.15 RCS Leakage Detection Instrumentation.......................................................... 3.4-37 ACTIONS...................................................................................................... 3.4-37 SURVEILLANCE REQUIREMENTS............................................................. 3.4-40 3.4.16 RCS Specific Activity......................................................................................... 3.4-41 ACTIONS...................................................................................................... 3.4-41 SURVEILLANCE REQUIREMENTS............................................................. 3.4-42 3.4.17 Steam Generator (SG) Tube Integrity............................................................... 3.4-44
CHAPTER TABLE OF CONTENTS (Continued)
Section Page CALLAWAY PLANT 3.4-iii ACTIONS..................................................................................................... 3.4-44 SURVEILLANCE REQUIREMENTS............................................................ 3.4-46
3.4.2-iv Rev. OL-14 12/04 LIST OF FIGURES Number Title
CALLAWAY PLANT 3.4-1 Amendment No. 183 RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:
a.
Pressurizer pressure is greater than or equal to the limit specified in the COLR; b.
RCS average temperature is less than or equal to the limit specified in the COLR; and c.
RCS total flow rate 382,630 gpm.
APPLICABILITY:
MODE 1.
NOTE ---------------------------------------------
Pressurizer pressure limit does not apply during:
a.
THERMAL POWER ramp > 5% RTP per minute; or b.
THERMAL POWER step > 10% RTP.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more RCS DNB parameters not within limits.
A.1 Restore RCS DNB parameter(s) to within limit.
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> B.
Required Action and associated Completion Time not met.
B.1 Be in MODE 2.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 CALLAWAY PLANT 3.4-2 Amendment No. 202 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is greater than or equal to the limit specified in the COLR.
In accordance with the Surveillance Frequency Control Program SR 3.4.1.2 Verify RCS average temperature is less than or equal to the limit specified in the COLR.
In accordance with the Surveillance Frequency Control Program SR 3.4.1.3 Verify RCS total flow rate is 382,630 gpm.
In accordance with the Surveillance Frequency Control Program SR 3.4.1.4
NOTE ----------------------------
Calculated rather than verified by precision heat balance when performed prior to THERMAL POWER exceeding 75% RTP.
Verify by precision heat balance that RCS total flow rate is 382,630 gpm.
Once after each refueling prior to THERMAL POWER exceeding 75%
RTP AND In accordance with the Surveillance Frequency Control Program
CALLAWAY PLANT 3.4-3 Amendment No. 202 RCS Minimum Temperature for Criticality 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 RCS Minimum Temperature for Criticality LCO 3.4.2 Each operating RCS loop average temperature (Tavg) shall be 551°F.
APPLICABILITY:
MODE 1, MODE 2 with keff 1.0.
ACTIONS SURVEILLANCE REQUIREMENTS CONDITION REQUIRED ACTION COMPLETION TIME A.
Tavg in one or more operating RCS loops not within limit.
A.1 Be in MODE 2 with keff
< 1.0.
30 minutes SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS Tavg in each operating loop 551°F.
In accordance with the Surveillance Frequency Control Program
CALLAWAY PLANT 3.4-4 Amendment No. 133 RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cooldown rates shall be maintained within the limits specified in the PTLR.
APPLICABILITY:
At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
NOTE -------------
Required Action A.2 shall be completed whenever this Condition is entered.
A.1 Restore parameter(s) to within limits.
AND 30 minutes Requirements of LCO not met in MODE 1, 2, 3, or 4.
A.2 Determine RCS is acceptable for continued operation.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B.
Required Action and associated Completion Time of Condition A not met.
B.1 Be in MODE 3.
AND 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> B.2 Be in MODE 5 with RCS pressure < 500 psig.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)
RCS P/T Limits 3.4.3 ACTIONS (continued)
CALLAWAY PLANT 3.4-5 Amendment No. 202 SURVEILLANCE REQUIREMENTS C.
NOTE -------------
Required Action C.2 shall be completed whenever this Condition is entered.
C.1 Initiate action to restore parameter(s) to within limits.
AND Immediately Requirements of LCO not met any time in other than MODE 1, 2, 3, or 4.
C.2 Determine RCS is acceptable for continued operation.
Prior to entering MODE 4 SURVEILLANCE FREQUENCY SR 3.4.3.1
NOTE ----------------------------
Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.
Verify RCS pressure, RCS temperature, and RCS heatup and cooldown rates are within the limits specified in the PTLR.
In accordance with the Surveillance Frequency Control Program CONDITION REQUIRED ACTION COMPLETION TIME
CALLAWAY PLANT 3.4-6 Amendment No. 202 RCS Loops - MODES 1 and 2 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loops - MODES 1 and 2 LCO 3.4.4 Four RCS loops shall be OPERABLE and in operation.
APPLICABILITY:
MODES 1 and 2.
ACTIONS SURVEILLANCE REQUIREMENTS CONDITION REQUIRED ACTION COMPLETION TIME A.
Requirements of LCO not met.
A.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation.
In accordance with the Surveillance Frequency Control Program
CALLAWAY PLANT 3.4-7 Amendment No. 149 RCS Loops - MODE 3 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Loops - MODE 3 LCO 3.4.5 Two RCS loops shall be OPERABLE, and either:
a.
Two RCS loops shall be in operation when the Rod Control System is capable of rod withdrawal; or b.
One RCS loop shall be in operation when the Rod Control System is not capable of rod withdrawal.
NOTE----------------------------------------------
All reactor coolant pumps may be removed from operation for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided:
a.
No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and b.
Core outlet temperature is maintained at least 10°F below saturation temperature.
APPLICABILITY:
MODE 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One required RCS loop inoperable.
A.1 Restore required RCS loop to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B.
Required Action and associated Completion Time of Condition A not met.
B.1 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)
RCS Loops - MODE 3 3.4.5 ACTIONS (continued)
CALLAWAY PLANT 3.4-8 Amendment No. 149 C.
One required RCS loop not in operation with Rod Control System capable of rod withdrawal.
C.1 Restore required RCS loop to operation.
OR 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C.2 Place the Rod Control System in a condition incapable of rod withdrawal.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D.
Required RCS loops inoperable.
D.1 Place the Rod Control System in a condition incapable of rod withdrawal.
AND Immediately D.2 Suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet SDM of LCO 3.1.1.
AND Immediately D.3 Initiate action to restore one RCS loop to OPERABLE status and operation.
Immediately CONDITION REQUIRED ACTION COMPLETION TIME
RCS Loops - MODE 3 3.4.5 CALLAWAY PLANT 3.4-9 Amendment No. 202 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify required RCS loops are in operation.
In accordance with the Surveillance Frequency Control Program SR 3.4.5.2 Verify steam generator secondary side narrow range water levels are 7% for required RCS loops.
In accordance with the Surveillance Frequency Control Program SR 3.4.5.3 Verify correct breaker alignment and indicated power are available to the required pump that is not in operation.
In accordance with the Surveillance Frequency Control Program
CALLAWAY PLANT 3.4-10 Amendment No. 149 RCS Loops - MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops - MODE 4 LCO 3.4.6 Two loops consisting of any combination of RCS loops and residual heat removal (RHR) loops shall be OPERABLE, and one loop shall be in operation.
NOTES --------------------------------------------
1.
All reactor coolant pumps (RCPs) and RHR pumps may be removed from operation for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided:
a.
No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and b.
Core outlet temperature is maintained at least 10°F below saturation temperature.
2.
No RCP shall be started with any RCS cold leg temperature 275°F unless the secondary side water temperature of each steam generator (SG) is 50°F above each of the RCS cold leg temperatures.
APPLICABILITY:
MODE 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One required loop inoperable.
A.1 Initiate action to restore a second loop to OPERABLE status.
AND Immediately A.2
NOTE ------------
Only required if one RHR loop is OPERABLE.
Be in MODE 5.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued)
RCS Loops - MODE 4 3.4.6 ACTIONS (continued)
CALLAWAY PLANT 3.4-11 Amendment No. 213 SURVEILLANCE REQUIREMENTS B.
Required loops inoperable.
OR No RCS or RHR loop in operation.
B.1 Suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet SDM of LCO 3.1.1.
AND Immediately B.2 Initiate action to restore one loop to OPERABLE status and operation.
Immediately SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify one RHR or RCS loop is in operation.
In accordance with the Surveillance Frequency Control Program SR 3.4.6.2 Verify SG secondary side narrow range water levels are 7% for required RCS loops.
In accordance with the Surveillance Frequency Control Program (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
RCS Loops - MODE 4 3.4.6 SURVEILLANCE REQUIREMENTS (continued)
CALLAWAY PLANT 3.4-12 Amendment No. 213 SR 3.4.6.3 Verify correct breaker alignment and indicated power are available to the required pump that is not in operation.
In accordance with the Surveillance Frequency Control Program SR 3.4.6.4
NOTE ----------------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 4.
Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water.
In accordance with the Surveillance Frequency Control Program SURVEILLANCE FREQUENCY
CALLAWAY PLANT 3.4-13 Amendment No. 213 l RCS Loops - MODE 5, Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loops - MODE 5, Loops Filled LCO 3.4.7 One residual heat removal (RHR) loop shall be OPERABLE and in operation, and either:
a.
One additional RHR loop shall be OPERABLE; or b.
The secondary side wide range water level of at least two steam generators (SGs) shall be 86%.
NOTES -------------------------------------------
1.
The RHR pump of the loop in operation may be removed from operation for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided:
a.
No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and b.
Core outlet temperature is maintained at least 10°F below saturation temperature.
2.
One required RHR loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided that the other RHR loop is OPERABLE and in operation.
3.
No reactor coolant pump shall be started with any RCS cold leg temperature 275°F unless the secondary side water temperature of each SG is 50°F above each of the RCS cold leg temperatures.
4.
All RHR loops may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.
APPLICABILITY:
MODE 5 with RCS loops filled.
RCS Loops - MODE 5, Loops Filled 3.4.7 CALLAWAY PLANT 3.4-14 Amendment No. 213 l ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One RHR loop inoperable.
AND Required SGs secondary A.1 Initiate action to restore a second RHR loop to OPERABLE status.
OR Immediately side water levels not within limits.
A.2 Initiate action to restore required SG secondary side water levels to within limits.
Immediately B.
Required RHR loops inoperable.
B.1 Suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet SDM of LCO 3.1.1.
AND Immediately B.2 Initiate action to restore one RHR loop to OPERABLE status and operation.
Immediately
RCS Loops - MODE 5, Loops Filled 3.4.7 CALLAWAY PLANT 3.4-15 Amendment No. 213 l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify one RHR loop is in operation.
In accordance with the Surveillance Frequency Control Program SR 3.4.7.2 Verify SG secondary side wide range water level is 86% in required SGs.
In accordance with the Surveillance Frequency Control Program SR 3.4.7.3 Verify correct breaker alignment and indicated power are available to the required RHR pump that is not in operation.
In accordance with the Surveillance Frequency Control Program SR 3.4.7.4 Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water.
In accordance with the Surveillance Frequency Control Program
CALLAWAY PLANT 3.4-16 Amendment No. 213 l RCS Loops - MODE 5, Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops - MODE 5, Loops Not Filled LCO 3.4.8 Two residual heat removal (RHR) loops shall be OPERABLE and one RHR loop shall be in operation.
NOTES --------------------------------------------
1.
All RHR pumps may be removed from operation for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided:
a.
The core outlet temperature is maintained at least 10°F below saturation temperature.
b.
No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and c.
No draining operations to further reduce the RCS water volume are permitted.
2.
One RHR loop may be inoperable for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided that the other RHR loop is OPERABLE and in operation.
APPLICABILITY:
MODE 5 with RCS loops not filled.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One RHR loop inoperable.
A.1 Initiate action to restore RHR loop to OPERABLE status.
Immediately (continued)
RCS Loops - MODE 5, Loops Not Filled 3.4.8 ACTIONS (continued)
CALLAWAY PLANT 3.4-17 Amendment No. 213 l SURVEILLANCE REQUIREMENTS B.
Required RHR loops inoperable.
B.1 Suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet SDM of LCO 3.1.1.
AND Immediately B.2 Initiate action to restore one RHR loop to OPERABLE status and operation.
Immediately SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one RHR loop is in operation.
In accordance with the Surveillance Frequency Control Program SR 3.4.8.2 Verify correct breaker alignment and indicated power are available to the required RHR pump that is not in operation.
In accordance with the Surveillance Frequency Control Program SR 3.4.8.3 Verify RHR loop locations susceptible to gas accumulation are sufficiently filled with water.
In accordance with the Surveillance Frequency Control Program CONDITION REQUIRED ACTION COMPLETION TIME
CALLAWAY PLANT 3.4-18 Amendment No. 213 l Pressurizer 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with:
a.
Pressurizer water level 92%; and b.
Two groups of backup pressurizer heaters OPERABLE with the capacity of each group 150 kW.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Pressurizer water level not within limit.
A.1 Be in MODE 3.
AND 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> A.2 Fully insert all rods.
AND 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> A.3 Place Rod Control System in a condition incapable of rod withdrawal.
AND 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> A.4 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B.
One required group of backup pressurizer heaters inoperable.
B.1 Restore required group of backup pressurizer heaters to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (continued)
Pressurizer 3.4.9 ACTIONS (continued)
CALLAWAY PLANT 3.4-19 Amendment No. 213 l SURVEILLANCE REQUIREMENTS C.
Required Action and associated Completion Time of Condition B not met.
C.1 Be in MODE 3.
AND 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> C.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level is 92%.
In accordance with the Surveillance Frequency Control Program SR 3.4.9.2 Verify capacity of each required group of backup pressurizer heaters is 150 kW.
In accordance with the Surveillance Frequency Control Program CONDITION REQUIRED ACTION COMPLETION TIME
CALLAWAY PLANT 3.4-20 Amendment No. 213 l Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.10 Three pressurizer safety valves shall be OPERABLE with lift settings 2411 psig and 2509 psig.
APPLICABILITY:
MODES 1, 2, and 3, MODE 4 with all RCS cold leg temperatures > 275°F.
NOTES --------------------------------------------
The lift settings are not required to be within the LCO limits during MODES 3 and 4 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions. This exception is allowed for 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> following entry into MODE 3 provided a preliminary cold setting was made prior to heatup.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One pressurizer safety valve inoperable.
A.1 Restore valve to OPERABLE status.
15 minutes B.
Required Action and associated Completion Time not met.
B.1 Be in MODE 3.
AND 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR Two or more pressurizer safety valves inoperable.
B.2 Be in MODE 4 with any RCS cold leg temperature 275°F.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
Pressurizer Safety Valves 3.4.10 CALLAWAY PLANT 3.4-21 Amendment No. 222 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is OPERABLE in accordance with the INSERVICE TESTING PROGRAM. Following testing, lift settings shall be within +/- 1% of 2460 psig.
In accordance with the INSERVICE TESTING PROGRAM
CALLAWAY PLANT 3.4-22 Amendment No. 213 l Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)
LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS
NOTE -----------------------------------------------------------
Separate Condition entry is allowed for each PORV and each block valve.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more PORVs inoperable solely due to excessive seat leakage.
A.1 Close and maintain power to associated block valve.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B.
One PORV inoperable for reasons other than excessive seat leakage.
B.1 Close associated block valve.
AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B.2 Remove power from associated block valve.
AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B.3 Restore PORV to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (continued)
Pressurizer PORVs 3.4.11 ACTIONS (continued)
CALLAWAY PLANT 3.4-23 Amendment No. 213 l C.
One block valve inoperable. -------------------- NOTE -------------------
Required Actions do not apply when block valve is inoperable solely as a result of complying with Required Actions B.2 or E.2.
C.1 Place associated PORV in manual control.
AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C.2 Restore block valve to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> D.
Required Action and associated Completion Time of Condition A, B, or C not met.
D.1 Be in MODE 3.
AND 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> D.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> E.
Two PORVs inoperable for reasons other than excessive seat leakage.
E.1 Close associated block valves.
AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> E.2 Remove power from associated block valves.
AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> E.3 Be in MODE 3.
AND 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> E.4 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
Pressurizer PORVs 3.4.11 ACTIONS (continued)
CALLAWAY PLANT 3.4-24 Amendment No. 213 l F.
More than one block valve inoperable.
NOTE -------------------
Required Action F.1 does not apply when block valve is inoperable solely as a result of complying with Required Action B.2 or E.2.
F.1 Restore one block valve to OPERABLE status.
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> G.
Required Action and associated Completion Time of Condition F not met.
G.1 Be in MODE 3.
AND 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> G.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> CONDITION REQUIRED ACTION COMPLETION TIME
Pressurizer PORVs 3.4.11 CALLAWAY PLANT 3.4-25 Amendment No. 222 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1
NOTE ----------------------------
Not required to be performed with block valve closed in accordance with the Required Actions of this LCO.
Perform a complete cycle of each block valve.
In accordance with the Surveillance Frequency Control Program SR 3.4.11.2 Perform a complete cycle of each PORV.
In accordance with the INSERVICE TESTING PROGRAM
CALLAWAY PLANT 3.4-26 Amendment No. 213 l COMS 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Cold Overpressure Mitigation System (COMS)
LCO 3.4.12 COMS shall be OPERABLE with a maximum of zero safety injection pumps, one Emergency Core Cooling System (ECCS) centrifugal charging pump, and the normal charging pump capable of injecting into the RCS and the accumulators isolated and one of the following pressure relief capabilities:
a.
Two power operated relief valves (PORVs) with lift settings within the limits specified in the PTLR, or b.
Two residual heat removal (RHR) suction relief valves with setpoints 436.5 psig and 463.5 psig, or c.
One PORV with a lift setting within the limits specified in the PTLR and one RHR suction relief valve with a setpoint 436.5 psig and 463.5 psig, or d.
The RCS depressurized and an RCS vent of 2.0 square inches.
NOTES --------------------------------------------
1.
Two ECCS centrifugal charging pumps may be made capable of injecting for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for pump swap operations.
2.
One or more safety injection pumps may be made capable of injecting in MODES 5 and 6 when the RCS water level is below the top of the reactor vessel flange for the purpose of protecting the decay heat removal function.
3.
Accumulator may be unisolated when accumulator pressure is less than the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.
APPLICABILITY:
MODE 4 with any RCS cold leg temperature 275°F, MODE 5, MODE 6 when the reactor vessel head is on.
COMS 3.4.12 CALLAWAY PLANT 3.4-27 Amendment No. 213 l ACTIONS
NOTE -----------------------------------------------------------
LCO 3.0.4.b is not applicable when entering MODE 4.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more safety injection pumps capable of injecting into the RCS.
A.1 Initiate action to verify a maximum of zero safety injection pumps are capable of injecting into the RCS.
Immediately B.
Two ECCS centrifugal charging pumps capable of injecting into the RCS.
B.1 Initiate action to verify a maximum of one ECCS centrifugal charging pump and the normal charging pump capable of injecting into the RCS.
Immediately C.
An accumulator not isolated when the accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.
C.1 Isolate affected accumulator.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (continued)
COMS 3.4.12 ACTIONS (continued)
CALLAWAY PLANT 3.4-28 Amendment No. 213 l D.
Required Action and associated Completion Time of Condition C not met.
D.1 Increase all RCS cold leg temperatures to
> 275°F.
OR 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D.2 Depressurize affected accumulator to less than the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> E.
One required RCS relief valve inoperable in MODE 4.
E.1 Restore required RCS relief valve to OPERABLE status.
7 days F.
One required RCS relief valve inoperable in MODE 5 or 6.
F.1 Restore required RCS relief valve to OPERABLE status.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> G.
Two required RCS relief valves inoperable.
OR Required Action and associated Completion Time of Condition A, B, D, E, or F not met.
OR COMS inoperable for any reason other than Condition A, B, C, D, E, or F.
G.1 Depressurize RCS and establish RCS vent of 2.0 square inches.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> CONDITION REQUIRED ACTION COMPLETION TIME
COMS 3.4.12 CALLAWAY PLANT 3.4-29 Amendment No. 213 l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify a maximum of zero safety injection pumps are capable of injecting into the RCS.
In accordance with the Surveillance Frequency Control Program SR 3.4.12.2 Verify a maximum of one ECCS centrifugal charging pump and the normal charging pump capable of injecting into the RCS.
In accordance with the Surveillance Frequency Control Program SR 3.4.12.3 Verify each accumulator is isolated when accumulator pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.
In accordance with the Surveillance Frequency Control Program SR 3.4.12.4 Verify RHR suction isolation valves are open for each required RHR suction relief valve.
In accordance with the Surveillance Frequency Control Program SR 3.4.12.5 Verify required RCS vent 2.0 square inches open.
In accordance with the Surveillance Frequency Control Program (continued)
COMS 3.4.12 SURVEILLANCE REQUIREMENTS (continued)
CALLAWAY PLANT 3.4-30 Amendment No. 213 l SR 3.4.12.6 Verify PORV block valve is open for each required PORV.
In accordance with the Surveillance Frequency Control Program SR 3.4.12.7 Not used.
NOTE ----------------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after decreasing any RCS cold leg temperature to 275°F.
Perform a COT on each required PORV, excluding actuation.
In accordance with the Surveillance Frequency Control Program SR 3.4.12.9 Perform CHANNEL CALIBRATION for each required PORV actuation channel.
In accordance with the Surveillance Frequency Control Program SURVEILLANCE FREQUENCY
CALLAWAY PLANT 3.4-31 Amendment No. 213 l RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:
a.
No pressure boundary LEAKAGE; b.
1 gpm unidentified LEAKAGE; c.
10 gpm identified LEAKAGE; and d.
150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
RCS operational LEAKAGE not within limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.
A.1 Reduce LEAKAGE to within limits.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B.
Required Action and associated Completion Time of Condition A not met.
B.1 Be in MODE 3.
AND 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR B.2 Be in MODE 5 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Pressure boundary LEAKAGE exists.
OR Primary to secondary LEAKAGE not within limit.
RCS Operational LEAKAGE 3.4.13 CALLAWAY PLANT 3.4-32 Amendment No. 213 l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1
NOTES -------------------------------
- 1. Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.
- 2. Not applicable to primary to secondary LEAKAGE Verify RCS operational LEAKAGE is within limits by performance of RCS water inventory balance.
In accordance with the Surveillance Frequency Control Program SR 3.4.13.2
NOTE -------------------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.
Verify primary to secondary LEAKAGE is 150 gallons per day through any one SG.
In accordance with the Surveillance Frequency Control Program
CALLAWAY PLANT 3.4-33 Amendment No. 213 l RCS PIV Leakage 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.14 Leakage from each RCS PIV shall be within limit.
APPLICABILITY:
MODES 1, 2, and 3, MODE 4, except valves in the residual heat removal (RHR) flow path when in, or during the transition to or from, the RHR mode of operation.
ACTIONS
NOTE -----------------------------------------------------------
NOTES ---------------------------------------------------------
1.
Separate Condition entry is allowed for each flow path.
2.
Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable PIV.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more flow paths with leakage from one or more RCS PIVs not within limit.
A.1
NOTE ------------
Each valve used to satisfy Required Action A.1 must have been verified to meet SR 3.4.14.1 and be in the reactor coolant pressure boundary.
Isolate the high pressure portion of the affected system from the low pressure portion by use of one deactivated remote manual or check valve.
AND 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> A.2 Restore RCS PIV to within limits.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (continued)
RCS PIV Leakage 3.4.14 ACTIONS (continued)
CALLAWAY PLANT 3.4-34 Amendment No. 213 l B.
Required Action and associated Completion Time for Condition A not met.
B.1 Be in MODE 3.
AND 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> B.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.
RHR suction isolation valve interlock function inoperable.
C.1 Isolate the affected penetration by use of one deactivated remote manual valve.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> CONDITION REQUIRED ACTION COMPLETION TIME
RCS PIV Leakage 3.4.14 CALLAWAY PLANT 3.4-35 Amendment No. 222 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1
NOTES --------------------------
1.
Not required to be performed in MODES 3 and 4.
2.
Not required to be performed on the RCS PIVs located in the RHR flow path when in the shutdown cooling mode of operation.
3.
RCS PIVs actuated during the performance of this Surveillance are not required to be tested more than once if a repetitive testing loop cannot be avoided.
Verify leakage from each RCS PIV is equivalent to 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm at an RCS pressure 2215 psig and 2255 psig.
In accordance with the INSERVICE TESTING
- PROGRAM, AND In accordance with the Surveillance Frequency Control Program AND Prior to entering MODE 2 whenever the unit has been in MODE 5 for 7 days or more and if leakage testing has not been performed in the previous 9 months AND (continued)
RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS CALLAWAY PLANT 3.4-36 Amendment 213 l SR 3.4.14.1 (continued)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following check valve actuation due to flow through the valve SR 3.4.14.2 Verify RHR suction isolation valve interlock prevents the valves from being opened with a simulated or actual RCS pressure signal 425 psig except when the valves are open to satisfy LCO 3.4.12.
In accordance with the Surveillance Frequency Control Program SURVEILLANCE FREQUENCY
CALLAWAY PLANT 3.4-37 Amendment No. 213 l RCS Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:
a.
The containment sump level and flow monitoring system; b.
One containment atmosphere particulate radioactivity monitor; and c.
The containment cooler condensate monitoring system.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Required containment sump level and flow monitoring system inoperable.
A.1
NOTE ------------
Not required until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.
Perform SR 3.4.13.1.
AND Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> A.2 Restore required containment sump level and flow monitoring system to OPERABLE status.
30 days (continued)
RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued)
CALLAWAY PLANT 3.4-38 Amendment No. 213 l B.
Required containment atmosphere particulate radioactivity monitor inoperable.
B.1.1 Analyze samples of the containment atmosphere.
OR Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B.1.2
NOTE ------------
Not required until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.
Perform SR 3.4.13.1.
AND Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B.2.1 Restore required containment atmosphere particulate radioactivity monitor to OPERABLE status.
OR 30 days B.2.2 Verify containment air cooler condensate monitoring system is OPERABLE.
30 days (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued)
CALLAWAY PLANT 3.4-39 Amendment No. 213 l C.
Required containment cooler condensate monitoring system inoperable.
C.1 Perform SR 3.4.15.1.
OR Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> C.2
NOTE ------------
Not required until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.
Perform SR 3.4.13.1.
Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> D.
Required containment atmosphere particulate radioactivity monitor inoperable.
AND D.1 Restore required containment atmosphere particulate radioactivity monitor to OPERABLE status.
OR 30 days Required containment cooler condensate monitoring system inoperable.
D.2 Restore required containment cooler condensate monitoring system to OPERABLE status.
30 days E.
Required Action and associated Completion Time not met.
E.1 Be in MODE 3.
AND 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> E.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> F.
All required monitoring methods inoperable.
F.1 Enter LCO 3.0.3.
Immediately CONDITION REQUIRED ACTION COMPLETION TIME
RCS Leakage Detection Instrumentation 3.4.15 CALLAWAY PLANT 3.4-40 Amendment No. 213 l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the required containment atmosphere particulate radioactivity monitor.
In accordance with the Surveillance Frequency Control Program SR 3.4.15.2 Perform COT of the required containment atmosphere particulate radioactivity monitor.
In accordance with the Surveillance Frequency Control Program SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required containment sump level and flow monitoring system.
In accordance with the Surveillance Frequency Control Program SR 3.4.15.4 Perform CHANNEL CALIBRATION of the required containment atmosphere particulate radioactivity monitor.
In accordance with the Surveillance Frequency Control Program SR 3.4.15.5 Perform CHANNEL CALIBRATION of the required containment cooler condensate monitoring system.
In accordance with the Surveillance Frequency Control Program
CALLAWAY PLANT 3.4-41 Amendment No. 213 l RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 RCS DOSE EQUIVALENT I-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
DOSE EQUIVALENT I-131 not within limit.
NOTE -------------------
LCO 3.0.4.c is applicable.
A.1 Verify DOSE EQUIVALENT I-131 60 Ci/gm.
AND Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> A.2 Restore DOSE EQUIVALENT I-131 to within limit.
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> B.
DOSE EQUIVALENT XE-133 not within limit.
NOTE -------------------
LCO 3.0.4.c is applicable.
B.1 Restore DOSE EQUIVALENT XE-133 to within limit.
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> (continued)
RCS Specific Activity 3.4.16 ACTIONS (continued)
CALLAWAY PLANT 3.4-42 Amendment No. 213 l SURVEILLANCE REQUIREMENTS C.
Required Action and associated Completion Time of Condition A or B not met.
C.1 Be in MODE 3.
AND 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR DOSE EQUIVALENT I-131
> 60 Ci/gm.
C.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE FREQUENCY SR 3.4.16.1
NOTE ----------------------------
Only required to be performed in MODE 1.
Verify reactor coolant DOSE EQUIVALENT XE-133 specific activity 225 Ci/gm.
In accordance with the Surveillance Frequency Control Program (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
RCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS (continued)
CALLAWAY PLANT 3.4-43 Amendment No. 213 l SR 3.4.16.2
NOTE ----------------------------
Only required to be performed in MODE 1.
Verify reactor coolant DOSE EQUIVALENT I-131 specific activity 1.0 Ci/gm.
In accordance with the Surveillance Frequency Control Program AND Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period SURVEILLANCE FREQUENCY
CALLAWAY PLANT 3.4-44 Amendment No. 215 SG Tube Integrity 3.4.17 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 Steam Generator (SG) Tube Integrity LCO 3.4.17 SG tube integrity shall be maintained.
AND All SG tubes satisfying the tube plugging criteria shall be plugged in accordance with Steam Generator Program.
APPLICABILITY:
MODES 1 2, 3, and 4.
ACTIONS
NOTE -----------------------------------------------------------
NOTE -----------------------------------------------------------
Separate Condition entry is allowed for each SG tube.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more SG tubes satisfying the tube plugging criteria and not plugged in accordance with the Steam Generator Program.
A.1 Verify tube integrity of the affected tube(s) is maintained until the next refueling outage or inspection.
AND 7 days A.2 Plug the affected tube(s) in accordance with the Steam Generator Program.
Prior to entering MODE 4 following the next refueling outage or SG tube inspection (continued)
SG Tube Integrity 3.4.17 ACTIONS (continued)
CALLAWAY PLANT 3.4-45 Amendment No. 213 l B.
Required Action and associated Completion Time of Condition A not met.
B.1 Be in MODE 3.
AND 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR SG tube integrity not maintained.
B.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> CONDITION REQUIRED ACTION COMPLETION TIME
SG Tube Integrity 3.4.17 CALLAWAY PLANT 3.4-46 Amendment No. 215 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify SG tube integrity in accordance with the Steam Generator Program.
In accordance with the Steam Generator Program SR 3.4.17.2 Verify that each inspected SG tube that satisfies the tube plugging criteria is plugged in accordance with the Steam Generator Program.
Prior to entering MODE 4 following a SG tube inspection