ML17334A876
| ML17334A876 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/23/1985 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17321A579 | List: |
| References | |
| AEP:NRC:0856H, AEP:NRC:856H, NUDOCS 8504260197 | |
| Download: ML17334A876 (27) | |
Text
ATTACHMENT TO AEP:NRC:0856H PROPOSED CHANGES TO THE DONALD C.COOK NUCLEAR PLANT UNIT NOS.1 AND 2 TECHNICAL SPECIFICATIONS 8504260197 850423 PDR ADOCY 05000315 PDR TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO.OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION 6.MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Water Level-Low-Low b.4 kv Bus Loss of Voltage 3/Stm.Gen.2/Bus 2/Stm.Gen.any Stm.Gen.2/Bus 2/Stm.Gen.2/Bus 1I 2I 3 1/2I 3 14 14 c.Safety Injection 1I 2I 3 18 d.Loss of Main Feedwater Pumps 2 1, 2 18 7.TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Water Level-Low-Low 3/Stm.Gen.2/Stm.Gen.any 2 Stm.Gen.2/Stm.Gen.li 2I 3 14 b.Reactor Coolant Pump Bus Undervoltage 4-1/Bus 1I 21 3 19 8.LOSS OF POWER a.4 kv Bus Loss of Voltage 3/Bus 2/Bus 2/Bus 1, 2, 3, 4 14 b.4 kv Bus Degraded Voltage 3/Bus 2/Bus 2/Bus 1, 2, 3, 4 14 PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2't least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with: a.Two feedwater pumps, each capable of being powered from separate emergency busses, and b.One feedwater pump capable of being powered from an OPERABLE steam supply system.APPLICABILITY MODES 1 g 2 g and 3~ACTION: 'a~With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.b.c~With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.SURVEILLANCE RE UIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE: a~At least once per 31 days by: Verifying that each motor driven pump develops an 0 equivalent discharge pressure of>1375 psig at 60 F on recirculation flow.2.Verifying that the steam turbine driven pump develops an 0 equivalent discharge pressure of>1285 psig at 60 F and at a flow of>700 gpm when the secondary steam supply pressure is greater than 310 psig.The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.D.C.COOK-UNIT 1 3/4 7-5 Amendment No.
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) 3.Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position.4.Verifying that when above 10%RATED THERMAL POWER each automatic valve in the flow path is in the fully open position and that each auxiliary feedwater pump is in automatic control (capable of automatic actuation).
b.At least once per 18 months during shutdown by: 1.Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.2.Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.D.C.COOK-UNIT 1 3/4 7-6 Amendment No.
PLANT SYSTEMS BASES U=maximum number of inoperable safety valves per operating steam line=1, 2 or 3.(109)=Power Range Neutron Flux-High Trip Setpoint for 4 loop operation.
(76)=Maximum percent of RATED THERMAL POWER permissible by P-8 Setpoint for 3 loop operation.
X=Total relieving capacity of all safety valves per steam line=4,288,450 lbs/hour.Y=Maximum relieving capacity of any one safety valve=857,690 lbs/hour.3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the 0 Reactor Coolant System can be cooled down to less than 350 F from normal operating conditions in the event of a total loss of off-site power.Each electric driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 450 gpm at a pressure of 1065 psig to the entrance of the steam generators.
The steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 900 gpm at a pressure of 1065 psig to the entrance of the steam generators.
This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350 F when the Residual Heat Removal System may be placed into operation.
The acceptance discharge pressures for the auxiliary feedwater pumps are based on a fluid temperature of 60 F.Water density corrections are 0 permitted to allow comparison of test results which vary depending on ambient conditions.
In addition to its safety design function, the AFW system is used to maintain steam generator level during startup (including low power operation).
During this time, the system design allows for automatic initiation of the auxiliary feedwater pumps and their related automatic valves in the flow path.D.C.COOK-UNIT 1 B 3/4 7-2 Amendment No.
J PLANT SYSTEMS BASES 3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> with steam discharge to the atmosphere concurrent with total loss of off-site power.3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of.10 CFR Part 100 limits in the event of a steam line rupture.This dose also includes the effects of a coincident 1.0 gpm primary to secondary tube leak in the steam generator of the affected steam line.These values are consistent with the assumptions used in the accident analyses.3/4.7.1.5 STEAM GENERATOR STOP VALVES The OPERABILITY of the steam generator stop valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture.This restriction is required to 1)minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2)limit the pressure rise within containment in the event the steam line rupture occurs within containment.
The OPERABILITY of the steam generator stop valves within the closure times of the surveillance requirements are'onsistent with the assumptions used in the accident analyses.D.C.COOK-UNIT 1 B 3/4 7-3 Amendment No.
TABLE 3.3<<3 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO.OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION 6.MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Water Level-Low-Low b.4 kv Bus Loss of Voltage 3/Stm.Gen.2/Bus 2/Stm.Gen.any Stm.Gen.2/Bus 2/Stm.Gen.2/Bus 1I 2I 3 1/2/3*14~14 c.Safety Injection 1/2/3 18 d.Loss of Main Feedwater Pumps 1/2 18 7.TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Water Level-Low-Low 3/Stm.Gen.2/Stm.Gen.any 2 Stm.Gen.2/Stm.Gen.1/21 3 14 b.Reactor Coolant Pump Bus Undervoltage 4-1/Bus 1/2I 3 19 8.LOSS OF POWER a.4 kv Bus Loss of Voltage 3/Bus 2/Bus 2/Bus 1, 2, 3, 4 14 b.4 kv Bus Degraded Voltage 3/Bus 2/Bus.2/Bus 1, 2, 3, 4 14
PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent, steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with: a.Two feedwater pumps, each capable of being powered from separate emergency busses, and b.One feedwater pump capable of being powered from an OPERABLE steam supply system.APPLICABILITY:
MODES 1, 2, and 3.ACTION: a 0 With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.b.c~With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.SURVEILLANCE RE UIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE: a 0 At least once per 31 days by: Verifying that each motor driven pump develops an 0 equivalent discharge pressure of,>1375 psig at 60 F on recirculation flow.2.Verifying that the steam turbine driven pump develops an equivalent discharge pressure of>1285 psig at 60 F and 0 at a flow of>700 gpm when the secondary steam supply pressure is greater than 310 psig.The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.D.C.COOK-UNIT 2 3/4 7-5 Amendment No.
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3.Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position.4.Verifying that when above 10%RATED THERMAL POWER each automatic valve in the flow path is in the fully open position and that each auxiliary feedwater pump is in automatic control (capable of automatic actuation).
b.At least once per 18 months during shutdown by: 1.Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of the appropriate engineered safety features actuation.test signal required by Specification 3/4.3.2.2.Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.D.C.COOK-UNIT 2 3/4 7-6 Amendment No.
PLANT SYSTEMS BASES U=maximum number of inoperable safety valves per operating steam line 109=Power Range Neutron Flux-High Trip Setpoint for 4 loop operation 76=Maximum percent of RATED THERMAL POWER permissible by P-8 Setpoint for 3 loop operation.
X=Total relieving capacity of all safety valves per steam line in lbs./hours
=4,288,450 Y=Maximum relieving capacity of any one safety valve in lbs/hour=857,690.3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooled down to less than 350 F from normal 0 operating'conditions in the event of a total loss of off-site power.Each electric driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 450 gpm at a pressure of 1065 psig to the entrance of the steam generators.
The steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 900 gpm at a pressure of 1065 psig to the entrance of the steam generators.
This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350 F when the Residual Heat Removal System may be placed into operation.
0 The acceptance'discharge pressures for the auxiliary feedwater pumps are based on a fluid temperature of 60 F.Water density corrections are 0 permitted to allow comparison of test results which vary depending on ambient.conditions.
In addition to its safety design function, the AFW system is used to maintain steam generator level during startup (including low power operation).
During this time, the system design allows for automatic initiation of the auxiliary feedwater pumps and their related automatic valves in the flow path.D.C.COOK-UNIT 2 B 3/4 7-2 Amendment No.
PLANT SYSTEMS BASES 3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> with steam discharge to the atmosphere concurrent with total loss of off-site power.The contained water volume limit includes an allowance for water not usable because of tank discharge line location, or other physical characteristics.
3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of.10 CFR Part 100 limits in the event of a steam line rupture.This dose also includes the effects of a coincident 1.0 gpm primary to secondary tube leak in the steam generator of the affected steam line.These values are consistent with the assumptions used in the accident analyses.3/4.7.1.5 STEAM GENERATOR STOP VALVES The OPERABILITY of the steam generator stop valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture.This restriction is required to 1)minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2)limit the pressure rise within containment in the event the steam line rupture occurs within containment.
The OPERABILITY of the steam generator stop valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses.D.C.COOK-UNIT 2 B 3/4 7-3 Amendment No.
I TABLE 3.3-3 (Continued) r ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO.OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION 6.MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Water Level--Low-Low b.4 kv Bus Loss of Voltage 3/Stm.Gen.2/Bus 2/Stm.Gen.any Stm.Gen.2/Bus 2/Stm.Gen.2/Bus 1I 2I 3 1, 2, 3 14 14 c.Safety Injection 1I 2I 3 18 d.Loss of Main Feedwater Pumps li 2 18 7.TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Water Level-Low-Low b.Reactor Coolant Pump Bus Undervoltage 3/Stm.Gen.4-1/Bus 2/Stm.Gen.-any 2 Stm.Gen.2/Stm.Gen.1, 2, 3 1I 2I 3 14*~8.LOSS OF POWFR a.4 kv Bus Loss of Voltage 3/Bus 2/Bus 2/Bus 1, 2, 3, 4 14 b.4 kv Bus Degraded Voltage 3/Bus 2/Bus 2/Bus 1, 2, 3, 4 14 PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with: a.Two feedwater pumps, each capable of being powered from separate emergency busses, and b.One feedwater pump capable of being powered from an OPERABLE steam supply system.APPLICABILITY:
MODES 1, 2, and 3.ACTION: a~With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.b.c~With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.SURVEILLANCE RE UIREMENTS 4.7.1~2 Each auxiliary feedwater pump shall be demonstrated OPERABLE: a~At least once per 31 days by: Verifying that each motor driven pump develops an 0 equivalent discharge pressure of>1375 psig at 60 F on recirculation flow.2.Verifying that the steam turbine driven pump develops an 0 equivalent discharge pressure of>1285 psig at 60 F and at a flow of>700 gpm when the secondary steam supply pressure is greater than 310 psig.The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.D.C.COOK-UNIT 1 3/4 7-5 Amendment No.
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) 3.Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position.4~Verifying that when above 10%RATED THERMAL POWER each automatic valve in the flow path is in the fully open position and that each auxiliary feedwater pump is in automatic control (capable of automatic actuation)
.b.At least once per 18 months during shutdown by: 1.Verifying that each automatic valve in the flow path actuates to its correct, position upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.2.Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.D.C.COOK-UNIT 1 3/4 7-6 Amendment No.
PLANT SYSTEMS BASES U=maximum number of inoperable safety valves per operating steam line=1, 2 or 3.(109)=Power Range Neutron Flux-High Trip Setpoint for 4 loop operation.
(76)=Maximum percent of RATED THERMAL POWER permissible by P>>8 Setpoint for 3 loop operation..
X=Total relieving capacity of all safety valves per steam line=4,288,450 lbs/hour.Y=Maximum relieving capacity of any one safety valve=857,690 lbs/hour.3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the 0 Reactor Coolant System can be cooled down to less than 350 F from normal operating conditions in the event of a total loss of off-site power.Each electric driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 450 gpm at a pressure of 1065 psig to the entrance of the steam generators.
The steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 900 gpm at a pressure of 1065 psig to the entrance of the steam generators.
This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350 F when the Residual Heat Removal System may be placed into operation.
0 The acceptance discharge pressures for the auxiliary feedwater pumps are based on a fluid temperature of 60 F.Water density corrections are 0 permitted to allow comparison of test results which vary depending on ambient conditions.
In addition to its safety design function, the AFW system is used to maintain steam generator level during startup (including low power operation).
During this time, the system design allows for automatic initiation of the auxiliary feedwater pumps and their related automatic valves in the flow path.D.C.COOK-UNIT 1 B 3/4 7-2 Amendment No.
PLANT SYSTEMS BASES 3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> with steam discharge to the atmosphere concurrent with total loss of off-site power.3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of 10 CPR Part 100 limits in the event of a steam line rupture.This dose also includes the effects of a coincident 1.0 gpm primary to secondary tube leak in the steam generator of the affected steam line.These values are consistent with the assumptions used in the accident analyses.3/4.7.1.5 STEAM GENERATOR STOP VALVES The OPERABILITY of the steam generator stop valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture.This restriction is required to 1)minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and.2)limit the pressure rise within containment in the event the steam line rupture occurs within containment.
The OPERABlLITY of the steam generator stop valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses.D.C.COOK-UNIT 1 B 3/4 7-3 Amendment No.
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION
~~3/Stm.Gen.b.4 kv Bus Loss of Voltage 2/Bus 8 TOTAL NO.FUNCTIONAL UNIT OF CHANNFLS I 6.MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Water Level-Low-Low CHANNELS TO TRIP 2/Stm.Gen.any Stm.Gen.2/Bus MINIMUM CHANNELS OPERABLE 2/Stm.Gen.2/Bus APPLICABLE MODES 1i 2I 3 1, 2, 3 ACTION 14*~14 c.Safety Injection li 2i 3 18 d.Loss of Main Feedwater Pumps 2 1I 2 18 7.TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Water Level-Low-Low 3/Stm.Gen.2/S tm.Gen.any 2 Stm.Gen.2/Stm.Gen.1I 2I 3 b.Reactor Coolant Pump Bus Undervoltage 4-1/Bus 1, 2, 3 19 8.LOSS OF POWER 0 fh 8 0 0 a.4 kv Bus Loss of Voltage b.4 kv Bus Degraded Voltage 3/Bus 3/Bus 2/Bus 2/Bus 2/Bus 2/Bus 1, 2, 3, 4 1, 2, 3, 4 14 14 PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with: a.Two feedwater pumps, each capable of being powered from separate emergency busses, and b.One feedwater pump capable of being powered from an OPERABLE steam supply system.APPLICABILITY:
MODES 1, 2, and 3.ACTION: a 0 With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.b.c~With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY wi.'thin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.SURVEILLANCE RE UIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE: a~At least once per 31 days by: 1.Verifying that each motor driven pump develops an 0 equivalent discharge pressure of>1375 psig at 60 F on recirculation flow.2.Verifying that the steam turbine driven pump develops an 0 equivalent discharge pressure of>1285 psig at 60 F and at a flow of>700 gpm when the secondary steam supply pressure is greater than 310 psig.The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.D.C.COOK-UNIT 2 3/4 7-5 Amendment No.
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) 3.Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position.4.Verifying that when above 10%RATED THERMAL POWER each automatic valve in the flow path is in the fully open position and that each auxiliary feedwater pump is in automatic control (capable of automatic actuation).
b.At least once per 18 months during shutdown by: 1.Verifying that each automatic valve in the flow path'actuates to its correct position upon receipt of the appropriate engineered safety features actuation.test signal required by Specification 3/4.3.2.2.Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.D.C.COOK-UNIT 2 3/4 7-6 Amendment No.
V PLANT SYSTEMS BASES U=maximum number of inoperable safety valves per operating steam line 109=Power Range Neutron Flux-High Trip Setpoint for 4 loop operation 76=Maximum percent of RATED THERMAL POWER permissible by P-8 Setpoint for 3 loop'operation.
X=Total relieving capacity of all safety valves per steam line in lbs./hours
=4,288,450 Y=Maximum relieving capacity of any one safety valve in lbs/hour=857,690.3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the 0 Reactor Coolant System can be cooled down to less than 350 F from normal operating conditions in the event of a total loss of off-site power.Each electric driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 450 gpm at a pressure of 1065 psig to the entrance of the steam generators.
The steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 900 gpm at a pressure of 1065 psig to the entrance of the steam generators.
This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350 F when the Residual Heat Removal System may be placed into operation.
0 The acceptance discharge pressures for the auxiliary feedwater pumps are based on a fluid temperature of 60 F.Water density, corrections are 0 permitted to allow comparison of test results which vary depending on-ambient conditions.
In addition to its safety design function, the AFW system is used to maintain steam generator level during startup (including low power operation).
During this time, the system design allows for automatic initiation of the auxiliary feedwater pumps and their related automatic valves in the flow path.C D.C.COOK-UNIT 2 B 3/4 7-2 Amendment No.
PLANT SYSTEMS BASES 3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> with steam discharge to the atmosphere concurrent with total loss of off-site power.The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of,10 CFR Part 100 limits in the event of a steam line rupture.This dose also includes the effects of a coincident, 1.0 gpm primary to secondary tube leak in the steam generator of the affected steam line.These values are consistent with the assumptions used in the accident analyses.3/4.7.1.5 STEAM GENERATOR STOP VALVES The OPERABILITY of the steam generator stop valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture.This restriction is required to 1)minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2)limit the pressure rise within containment in the event the steam line rupture occurs within containment.
The OPERABILITY of the steam generator stop valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses.D.C.COOK-UNIT 2 B 3/4 7-3 Amendment No.