ML20209A104
Text
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 CALLAWAY PLANT 3.4-i
CHAPTER TABLE OF CONTENTS (Continued)
Section Page 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 CALLAWAY PLANT 3.4-ii
CHAPTER TABLE OF CONTENTS (Continued)
Section Page ACTIONS ..................................................................................................... 3.4-44 SURVEILLANCE REQUIREMENTS ............................................................ 3.4-46 CALLAWAY PLANT 3.4-iii
LIST OF FIGURES Number Title 3.4.2-iv Rev. OL-14 12/04
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;
- 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 COMPLETION CONDITION REQUIRED ACTION TIME A. One or more RCS DNB A.1 Restore RCS DNB 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> parameters not within limits. parameter(s) to within limit.
B. Required Action and 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 /> associated Completion Time not met.
CALLAWAY PLANT 3.4-1 Amendment No. 183
RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is greater than or equal to In accordance the limit specified in the COLR. with the Surveillance Frequency Control Program SR 3.4.1.2 Verify RCS average temperature is less than or equal In accordance to the limit specified in the COLR. 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 Once after each rate is 382,630 gpm. refueling prior to THERMAL POWER exceeding 75%
RTP AND In accordance with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-2 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 551F.
APPLICABILITY: MODE 1, MODE 2 with keff 1.0.
ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. Tavg in one or more A.1 Be in MODE 2 with keff 30 minutes operating RCS loops not < 1.0.
within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS Tavg in each operating loop 551F. In accordance with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-3 Amendment No. 202
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 COMPLETION CONDITION REQUIRED ACTION TIME A. ------------- NOTE ------------- A.1 Restore parameter(s) to 30 minutes Required Action A.2 shall within limits.
be completed whenever this Condition is entered. AND Requirements of LCO not A.2 Determine RCS is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> met in MODE 1, 2, 3, or 4. acceptable for continued operation.
B. Required Action and B.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 /> associated Completion Time of Condition A not AND met.
B.2 Be in MODE 5 with RCS 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> pressure < 500 psig.
(continued)
CALLAWAY PLANT 3.4-4 Amendment No. 133
RCS P/T Limits 3.4.3 ACTIONS (continued)
COMPLETION CONDITION REQUIRED ACTION TIME C. ------------- NOTE ------------- C.1 Initiate action to restore Immediately Required Action C.2 shall parameter(s) to within be completed whenever limits.
this Condition is entered.
AND Requirements of LCO not C.2 Determine RCS is Prior to entering met any time in other than acceptable for continued MODE 4 MODE 1, 2, 3, or 4. operation.
SURVEILLANCE REQUIREMENTS 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 In accordance heatup and cooldown rates are within the limits with the specified in the PTLR. Surveillance Frequency Control Program CALLAWAY PLANT 3.4-5 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 COMPLETION CONDITION REQUIRED ACTION TIME A. Requirements of LCO not 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 /> met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation. In accordance with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-6 Amendment No. 202
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 10F below saturation temperature.
APPLICABILITY: MODE 3.
ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. One required RCS loop A.1 Restore required RCS 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. loop to OPERABLE status.
B. Required Action and 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 /> associated Completion Time of Condition A not met.
(continued)
CALLAWAY PLANT 3.4-7 Amendment No. 149
RCS Loops - MODE 3 3.4.5 ACTIONS (continued)
COMPLETION CONDITION REQUIRED ACTION TIME C. One required RCS loop not C.1 Restore required RCS 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in operation with Rod loop to operation.
Control System capable of rod withdrawal. OR C.2 Place the Rod Control 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> System in a condition incapable of rod withdrawal.
D. Required RCS loops D.1 Place the Rod Control Immediately inoperable. System in a condition incapable of rod OR withdrawal.
No RCS loop in operation. AND D.2 Suspend operations that Immediately would cause introduction into the RCS, coolant with boron concentration less than required to meet SDM of LCO 3.1.1.
AND D.3 Initiate action to restore Immediately one RCS loop to OPERABLE status and operation.
CALLAWAY PLANT 3.4-8 Amendment No. 149
RCS Loops - MODE 3 3.4.5 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 In accordance water levels are 7% for required RCS loops. with the Surveillance Frequency Control Program SR 3.4.5.3 Verify correct breaker alignment and indicated power In accordance are available to the required pump that is not in with the operation. Surveillance Frequency Control Program CALLAWAY PLANT 3.4-9 Amendment No. 202
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 10F below saturation temperature.
- 2. No RCP shall be started with any RCS cold leg temperature 275F unless the secondary side water temperature of each steam generator (SG) is 50F above each of the RCS cold leg temperatures.
APPLICABILITY: MODE 4.
ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. One required loop A.1 Initiate action to restore a Immediately inoperable. second loop to OPERABLE status.
AND 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)
CALLAWAY PLANT 3.4-10 Amendment No. 149
RCS Loops - MODE 4 3.4.6 ACTIONS (continued)
COMPLETION CONDITION REQUIRED ACTION TIME B. Required loops inoperable. B.1 Suspend operations that Immediately would cause introduction OR into the RCS, coolant with boron concentration less No RCS or RHR loop in than required to meet operation. SDM of LCO 3.1.1.
AND B.2 Initiate action to restore Immediately one loop to OPERABLE status and operation.
SURVEILLANCE REQUIREMENTS 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 In accordance are 7% for required RCS loops. with the Surveillance Frequency Control Program (continued)
CALLAWAY PLANT 3.4-11 Amendment No. 213
RCS Loops - MODE 4 3.4.6 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.6.3 Verify correct breaker alignment and indicated power In accordance are available to the required pump that is not in with the operation. 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 In accordance accumulation are sufficiently filled with water. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-12 Amendment No. 213
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:
- 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 10F 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 275F unless the secondary side water temperature of each SG is 50F 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.
CALLAWAY PLANT 3.4-13 Amendment No. 213 l
RCS Loops - MODE 5, Loops Filled 3.4.7 ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. One RHR loop inoperable. A.1 Initiate action to restore Immediately a second RHR loop to AND OPERABLE status.
Required SGs secondary OR side water levels not within limits. A.2 Initiate action to restore Immediately required SG secondary side water levels to within limits.
B. Required RHR loops B.1 Suspend operations that Immediately inoperable. would cause introduction into the RCS, coolant OR with boron concentration less than required to No RHR loop in operation. meet SDM of LCO 3.1.1.
AND B.2 Initiate action to restore Immediately one RHR loop to OPERABLE status and operation.
CALLAWAY PLANT 3.4-14 Amendment No. 213 l
RCS Loops - MODE 5, Loops Filled 3.4.7 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 In accordance 86% in required SGs. with the Surveillance Frequency Control Program SR 3.4.7.3 Verify correct breaker alignment and indicated power In accordance are available to the required RHR pump that is not in with the operation. Surveillance Frequency Control Program SR 3.4.7.4 Verify required RHR loop locations susceptible to gas In accordance accumulation are sufficiently filled with water. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-15 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 10F 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 COMPLETION CONDITION REQUIRED ACTION TIME A. One RHR loop inoperable. A.1 Initiate action to restore Immediately RHR loop to OPERABLE status.
(continued)
CALLAWAY PLANT 3.4-16 Amendment No. 213 l
RCS Loops - MODE 5, Loops Not Filled 3.4.8 ACTIONS (continued)
COMPLETION CONDITION REQUIRED ACTION TIME B. Required RHR loops B.1 Suspend operations that Immediately inoperable. would cause introduction into the RCS, coolant OR with boron concentration less than required to No RHR loop in operation. meet SDM of LCO 3.1.1.
AND B.2 Initiate action to restore Immediately one RHR loop to OPERABLE status and operation.
SURVEILLANCE REQUIREMENTS 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 In accordance are available to the required RHR pump that is not in with the operation. Surveillance Frequency Control Program SR 3.4.8.3 Verify RHR loop locations susceptible to gas In accordance accumulation are sufficiently filled with water. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-17 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 COMPLETION CONDITION REQUIRED ACTION TIME A. Pressurizer water level not 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 /> within limit.
AND A.2 Fully insert all rods. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND A.3 Place Rod Control 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> System in a condition incapable of rod withdrawal.
AND 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 B.1 Restore required group 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> backup pressurizer heaters of backup pressurizer inoperable. heaters to OPERABLE status.
(continued)
CALLAWAY PLANT 3.4-18 Amendment No. 213 l
Pressurizer 3.4.9 ACTIONS (continued)
COMPLETION CONDITION REQUIRED ACTION TIME C. Required Action and C.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 /> associated Completion Time of Condition B not AND met.
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 REQUIREMENTS 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 In accordance pressurizer heaters is 150 kW. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-19 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 > 275F.
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 COMPLETION CONDITION REQUIRED ACTION TIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable. OPERABLE status.
B. Required Action and B.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 /> associated Completion Time not met. AND OR B.2 Be in MODE 4 with any 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> RCS cold leg Two or more pressurizer temperature 275F.
safety valves inoperable.
CALLAWAY PLANT 3.4-20 Amendment No. 213 l
Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is OPERABLE in In accordance with accordance with the Inservice Testing Program. the Inservice Following testing, lift settings shall be within 1% of Testing Program 2460 psig.
CALLAWAY PLANT 3.4-21 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.
COMPLETION CONDITION REQUIRED ACTION TIME A. One or more PORVs A.1 Close and maintain 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable solely due to power to associated excessive seat leakage. block valve.
B. One PORV inoperable for B.1 Close associated block 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> reasons other than valve.
excessive seat leakage.
AND B.2 Remove power from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated block valve.
AND B.3 Restore PORV to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.
(continued)
CALLAWAY PLANT 3.4-22 Amendment No. 213 l
Pressurizer PORVs 3.4.11 ACTIONS (continued)
COMPLETION CONDITION REQUIRED ACTION TIME 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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in manual control.
AND C.2 Restore block valve to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.
D. Required Action and D.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 /> associated Completion Time of Condition A, B, or C AND not met.
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 E.1 Close associated block 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> reasons other than valves.
excessive seat leakage.
AND E.2 Remove power from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated block valves.
AND E.3 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND 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)
CALLAWAY PLANT 3.4-23 Amendment No. 213 l
Pressurizer PORVs 3.4.11 ACTIONS (continued)
COMPLETION CONDITION REQUIRED ACTION TIME F. More than one block valve -------------------- NOTE -------------------
inoperable. 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 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to OPERABLE status.
G. Required Action and G.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 /> associated Completion Time of Condition F not AND met.
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 /> CALLAWAY PLANT 3.4-24 Amendment No. 213 l
Pressurizer PORVs 3.4.11 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 3.4-25 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
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 275F, MODE 5, MODE 6 when the reactor vessel head is on.
CALLAWAY PLANT 3.4-26 Amendment No. 213 l
COMS 3.4.12 ACTIONS
NOTE -----------------------------------------------------------
LCO 3.0.4.b is not applicable when entering MODE 4.
COMPLETION CONDITION REQUIRED ACTION TIME A. One or more safety A.1 Initiate action to verify a Immediately injection pumps capable of maximum of zero safety injecting into the RCS. injection pumps are capable of injecting into the RCS.
B. Two ECCS centrifugal B.1 Initiate action to verify a Immediately charging pumps capable of maximum of one ECCS injecting into the RCS. centrifugal charging pump and the normal charging pump capable of injecting into the RCS.
C. An accumulator not isolated C.1 Isolate affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> when the accumulator accumulator.
pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.
(continued)
CALLAWAY PLANT 3.4-27 Amendment No. 213 l
COMS 3.4.12 ACTIONS (continued)
COMPLETION CONDITION REQUIRED ACTION TIME D. Required Action and D.1 Increase all RCS cold 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion leg temperatures to Time of Condition C not > 275F.
met.
OR D.2 Depressurize affected 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> accumulator to less than the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.
E. One required RCS relief E.1 Restore required RCS 7 days valve inoperable in relief valve to MODE 4. OPERABLE status.
F. One required RCS relief F.1 Restore required RCS 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> valve inoperable in relief valve to MODE 5 or 6. OPERABLE status.
G. Two required RCS relief G.1 Depressurize RCS and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> valves inoperable. establish RCS vent of 2.0 square inches.
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.
CALLAWAY PLANT 3.4-28 Amendment No. 213 l
COMS 3.4.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify a maximum of zero safety injection pumps are In accordance capable of injecting into the RCS. with the Surveillance Frequency Control Program SR 3.4.12.2 Verify a maximum of one ECCS centrifugal charging In accordance pump and the normal charging pump capable of with the injecting into the RCS. Surveillance Frequency Control Program SR 3.4.12.3 Verify each accumulator is isolated when In accordance accumulator pressure is greater than or equal to the with the maximum RCS pressure for the existing RCS cold Surveillance leg temperature allowed by the P/T limit curves Frequency provided in the PTLR. Control Program SR 3.4.12.4 Verify RHR suction isolation valves are open for each In accordance required RHR suction relief valve. 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)
CALLAWAY PLANT 3.4-29 Amendment No. 213 l
COMS 3.4.12 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.12.6 Verify PORV block valve is open for each required In accordance PORV. with the Surveillance Frequency Control Program SR 3.4.12.7 Not used.
SR 3.4.12.8 --------------------------------- 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 275F.
Perform a COT on each required PORV, excluding In accordance actuation. with the Surveillance Frequency Control Program SR 3.4.12.9 Perform CHANNEL CALIBRATION for each required In accordance PORV actuation channel. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-30 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 COMPLETION CONDITION REQUIRED ACTION TIME A. RCS operational A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> LEAKAGE not within limits within limits.
for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.
B. Required Action and B.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 /> associated Completion Time of Condition A not AND met.
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 /> OR Pressure boundary LEAKAGE exists.
OR Primary to secondary LEAKAGE not within limit.
CALLAWAY PLANT 3.4-31 Amendment No. 213 l
RCS Operational LEAKAGE 3.4.13 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 In accordance performance of RCS water inventory balance. 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 In accordance gallons per day through any one SG. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-32 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.
COMPLETION CONDITION REQUIRED ACTION TIME A. One or more flow paths with A.1 ----------- NOTE ------------
leakage from one or more Each valve used to satisfy RCS PIVs not within limit. 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 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> portion of the affected system from the low pressure portion by use of one deactivated remote manual or check valve.
AND A.2 Restore RCS PIV to within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limits.
(continued)
CALLAWAY PLANT 3.4-33 Amendment No. 213 l
RCS PIV Leakage 3.4.14 ACTIONS (continued)
COMPLETION CONDITION REQUIRED ACTION TIME B. Required Action and B.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 /> associated Completion Time for Condition A not AND met.
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 C.1 Isolate the affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> interlock function penetration by use of one inoperable. deactivated remote manual valve.
CALLAWAY PLANT 3.4-34 Amendment No. 213 l
RCS PIV Leakage 3.4.14 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 In accordance with 0.5 gpm per nominal inch of valve size up to a the Inservice maximum of 5 gpm at an RCS pressure 2215 psig Testing Program, and 2255 psig.
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)
CALLAWAY PLANT 3.4-35 Amendment No. 213 l
RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 In accordance the valves from being opened with a simulated or with the actual RCS pressure signal 425 psig except when Surveillance the valves are open to satisfy LCO 3.4.12. Frequency Control Program CALLAWAY PLANT 3.4-36 Amendment 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 COMPLETION CONDITION REQUIRED ACTION TIME A. Required containment sump A.1 ----------- NOTE ------------
level and flow monitoring Not required until system inoperable. 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 /> AND A.2 Restore required 30 days containment sump level and flow monitoring system to OPERABLE status.
(continued)
CALLAWAY PLANT 3.4-37 Amendment No. 213 l
RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued)
COMPLETION CONDITION REQUIRED ACTION TIME B. Required containment B.1.1 Analyze samples of the Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> atmosphere particulate containment atmosphere.
radioactivity monitor inoperable. OR 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. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND B.2.1 Restore required 30 days containment atmosphere particulate radioactivity monitor to OPERABLE status.
OR B.2.2 Verify containment air 30 days cooler condensate monitoring system is OPERABLE.
(continued)
CALLAWAY PLANT 3.4-38 Amendment No. 213 l
RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued)
COMPLETION CONDITION REQUIRED ACTION TIME C. Required containment C.1 Perform SR 3.4.15.1. Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> cooler condensate monitoring system OR inoperable.
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 D.1 Restore required 30 days atmosphere particulate containment atmosphere radioactivity monitor particulate radioactivity inoperable. monitor to OPERABLE status.
AND OR Required containment cooler condensate D.2 Restore required 30 days monitoring system containment cooler inoperable. condensate monitoring system to OPERABLE status.
E. Required Action and E.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 /> associated Completion Time not met. AND 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 F.1 Enter LCO 3.0.3. Immediately methods inoperable.
CALLAWAY PLANT 3.4-39 Amendment No. 213 l
RCS Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the required In accordance containment atmosphere particulate radioactivity with the monitor. Surveillance Frequency Control Program SR 3.4.15.2 Perform COT of the required containment In accordance atmosphere particulate radioactivity monitor. with the Surveillance Frequency Control Program SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required In accordance containment sump level and flow monitoring system. with the Surveillance Frequency Control Program SR 3.4.15.4 Perform CHANNEL CALIBRATION of the required In accordance containment atmosphere particulate radioactivity with the monitor. Surveillance Frequency Control Program SR 3.4.15.5 Perform CHANNEL CALIBRATION of the required In accordance containment cooler condensate monitoring system. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-40 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 COMPLETION CONDITION REQUIRED ACTION TIME A. DOSE EQUIVALENT -------------------- NOTE -------------------
I-131 not within limit. LCO 3.0.4.c is applicable.
A.1 Verify DOSE Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> EQUIVALENT I-131 60 Ci/gm.
AND A.2 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT I-131 to within limit.
B. DOSE EQUIVALENT -------------------- NOTE -------------------
XE-133 not within limit. LCO 3.0.4.c is applicable.
B.1 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT XE-133 to within limit.
(continued)
CALLAWAY PLANT 3.4-41 Amendment No. 213 l
RCS Specific Activity 3.4.16 ACTIONS (continued)
COMPLETION CONDITION REQUIRED ACTION TIME C. Required Action and C.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 /> associated Completion Time of Condition A or B AND not met.
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 /> OR DOSE EQUIVALENT I-131
> 60 Ci/gm.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 --------------------------------- NOTE ----------------------------
Only required to be performed in MODE 1.
Verify reactor coolant DOSE EQUIVALENT XE-133 In accordance specific activity 225 Ci/gm. with the Surveillance Frequency Control Program (continued)
CALLAWAY PLANT 3.4-42 Amendment No. 213 l
RCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.16.2 --------------------------------- NOTE ----------------------------
Only required to be performed in MODE 1.
Verify reactor coolant DOSE EQUIVALENT I-131 In accordance specific activity 1.0 Ci/gm. 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 CALLAWAY PLANT 3.4-43 Amendment No. 213 l
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 -----------------------------------------------------------
Separate Condition entry is allowed for each SG tube.
COMPLETION CONDITION REQUIRED ACTION TIME A. One or more SG tubes A.1 Verify tube integrity of 7 days satisfying the tube plugging the affected tube(s) is criteria and not plugged in maintained until the next accordance with the Steam refueling outage or Generator Program. inspection.
AND A.2 Plug the affected tube(s) Prior to entering in accordance with the MODE 4 following Steam Generator the next refueling Program. outage or SG tube inspection (continued)
CALLAWAY PLANT 3.4-44 Amendment No. 215
SG Tube Integrity 3.4.17 ACTIONS (continued)
COMPLETION CONDITION REQUIRED ACTION TIME B. Required Action and B.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 /> associated Completion Time of Condition A not AND met.
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 /> OR SG tube integrity not maintained.
CALLAWAY PLANT 3.4-45 Amendment No. 213 l
SG Tube Integrity 3.4.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify SG tube integrity in accordance with the Steam In accordance with Generator Program. the Steam Generator Program SR 3.4.17.2 Verify that each inspected SG tube that satisfies the Prior to entering tube plugging criteria is plugged in accordance with MODE 4 following the Steam Generator Program. a SG tube inspection CALLAWAY PLANT 3.4-46 Amendment No. 215