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| number = ML060530214
| number = ML060530214
| issue date = 02/17/2006
| issue date = 02/17/2006
| title = Limerick, Units 1 and 2, Technical Specification Pages Pressure Isolation Valve Table
| title = Technical Specification Pages Pressure Isolation Valve Table
| author name =  
| author name =  
| author affiliation = NRC/NRR/ADRO/DORL
| author affiliation = NRC/NRR/ADRO/DORL
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=Text=
=Text=
{{#Wiki_filter:[ NDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE REACTOR COOLANT SYSTEM (Continued)
{{#Wiki_filter:[ NDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION                                                                               PAGE REACTOR COOLANT SYSTEM (Continued)
Figure 3.4.1.1-1 Deleted .........  
Figure 3.4.1.1-1   Deleted .........         ..................... 3/4 4-3 Jet Pumps .................................................                 3/4 4-4 Recirculation Pumps .       ........................................ 3/4 4-5 Idle Recirculation Loop Startup ........           ..................... 3/4 4-6 3/4.4.2   SAFETY/RELIEF VALVES .     ........................................ 3/4 4-7 3/4.4.3   REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems ...........         ........................ 3/4 4-8 Operational Leakage .     ........................................ 3/4 4-9 Table 3.4.3.2-1     Deleted .........       ..................... 3/4 4-11   I 3/4.4.4   (Deleted) The information from pages 3/4 4-12 through 3/4 4-14 has been intentionally omitted.
.....................
Refer to note on page 3/4 4-12 .........           ..................... 3/4 4-12 3/4.4.5   SPECIFIC ACTIVITY .     .......................................... 3/4 4-15 Table 4.4.5-1   Primary Coolant Specific Activity Sample and Analysis Program ..... ........ 3/4 4-17 3/4.4.6     PRESSURE/TEMPERATURE LIMITS Reactor Coolant System ......         ................................ 3/4 4-18 Figure 3.4.6.1-1   Minimum Reactor Pressure Vessel Metal Temperature Vs. Reactor Vessel Pressure ......           ................ 3/4 4-20 Table 4.4.6.1.3-1   Deleted ........       ..................... 3/4 4-21 Reactor Steam Dome .     .......................................... 3/4 4-22 3/4.4.7   MAIN STEAM LINE ISOLATION VALVES ........             .................... 3/4 4-23 3/4.4.8   STRUCTURAL INTEGRITY .     ........................................ 3/4 4-24 LIMERICK - UNIT 1                           xi         Amendment No. .1-6.,     .1-4, 1-7,, 182
3/4 4-3 Jet Pumps .................................................
 
3/4 4-4 Recirculation Pumps .........................................
REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FQR OPERATIO_
3/4 4-5 Idle Recirculation Loop Startup ........ .....................
3.4.3.2     Reactor coolant system leakage shall be limited to:
3/4 4-6 3/4.4.2 SAFETY/RELIEF VALVES .........................................
: a. No PRESSURE BOUNDARY LEAKAGE.
3/4 4-7 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems ...........  
: b. 5 gpm UNIDENTIFIED LEAKAGE.
........................
: c. 30 gpm total leakage.
3/4 4-8 Operational Leakage .........................................
: d. 25 gpm total leakage averaged over any 24-hour period.
3/4 4-9 Table 3.4.3.2-1 Deleted .........  
: e. 1 gpm leakage at a reactor coolant system pressure of 950 +/-10 psig from any reactor coolant system pressure isolation valve.**                                 I
.....................
: f. 2 gpm increase in UNIDENTIFIED LEAKAGE over a 24-hour period.
3/4 4-11 3/4.4.4 (Deleted)
APPLICABILITY:   OPERATIONAL CONDITIONS 1, 2, and 3.
The information from pages 3/4 4-12 through 3/4 4-14 has been intentionally omitted.Refer to note on page 3/4 4-12 .........  
ACTION:
.....................
: a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours.
3/4 4-12 3/4.4.5 SPECIFIC ACTIVITY ...........................................
: b. With any reactor coolant system leakage greater than the limits in b, c and/or d above, reduce the leakage rate to within the limits within 4 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
3/4 4-15 Table 4.4.5-1 Primary Coolant Specific Activity Sample and Analysis Program ..... ........ 3/4 4-17 3/4.4.6 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System ...... ................................
: c. With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours by use of at least one other closed manual, deactivated automatic, or check* valves, or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
3/4 4-18 Figure 3.4.6.1-1 Minimum Reactor Pressure Vessel Metal Temperature Vs. Reactor Vessel Pressure ...... ................
: d. With one or more of the high/low pressure interface valve leakage pressure monitors inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm setpoint at least once per 12 hours; restore the inoperable monitor(s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
3/4 4-20 Table 4.4.6.1.3-1 Deleted ........ .....................
: e. With any reactor coolant system leakage greater than the limit in f above, identify the source of leakage within 4 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
3/4 4-21 Reactor Steam Dome ...........................................
* Which have been verified not to exceed the allowable leakage limit at the last refueling outage or after the last time the valve was disturbed, whichever is more recent.
3/4 4-22 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES ........ ....................
**   Pressure isolation valve leakage is not included in any other allowable operational leakage specified in Section 3.4.3.2.
3/4 4-23 3/4.4.8 STRUCTURAL INTEGRITY  
LIMERICK - UNIT 1                           3/14 4-9         Amendment No. 2.8, 49, 4-72, 182
.........................................
 
3/4 4-24 I LIMERICK -UNIT 1 xi Amendment No. .1-6., .1-4, 1-7,, 182 REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FQR OPERATIO_3.4.3.2 Reactor coolant system leakage shall be limited to: a. No PRESSURE BOUNDARY LEAKAGE.b. 5 gpm UNIDENTIFIED LEAKAGE.c. 30 gpm total leakage.d. 25 gpm total leakage averaged over any 24-hour period.e. 1 gpm leakage at a reactor coolant system pressure of 950 +/-10 psig from any reactor coolant system pressure isolation valve.** I f. 2 gpm increase in UNIDENTIFIED LEAKAGE over a 24-hour period.APPLICABILITY:
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS                                             _
OPERATIONAL CONDITIONS 1, 2, and 3.ACTION: a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours.b. With any reactor coolant system leakage greater than the limits in b, c and/or d above, reduce the leakage rate to within the limits within 4 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.c. With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours by use of at least one other closed manual, deactivated automatic, or check* valves, or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.d. With one or more of the high/low pressure interface valve leakage pressure monitors inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm setpoint at least once per 12 hours; restore the inoperable monitor(s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.e. With any reactor coolant system leakage greater than the limit in f above, identify the source of leakage within 4 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.* Which have been verified not to exceed the allowable leakage limit at the last refueling outage or after the last time the valve was disturbed, whichever is more recent.** Pressure isolation valve leakage is not included in any other allowable operational leakage specified in Section 3.4.3.2.LIMERICK -UNIT 1 3/14 4-9 Amendment No. 2.8, 49, 4-72, 182 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS
4.4.3.2.1   The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:
_4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by: a. Monitoring the primary containment atmospheric gaseous radioactivity at least once per 12 hours (not a means of quantifying leakage), b. Monitoring the drywell floor drain sump and drywell equipment drain tank flow rate at least once per eight (8) hours, c. Monitoring the drywell unit coolers condensate flow rate at least once per 12 hours, d. Monitoring the primary containment pressure at least once per 12 hours (not a means of quantifying leakage), e. Monitoring the reactor vessel head flange leak detection system at least once per 24 hours, and f. Monitoring the primary containment temperature at least once per 24 hours (not a means of quantifying leakage).4.4.3.2.2 Each reactor coolant system pressure isolation valve shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit: a. At least once per 24 months, end b. Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.4.4.3.2.3 The high/low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints set less than the specified allowable values by performance of a: a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and b. CHANNEL CALIBRATION at least once per 24 months.LIMERICK -UNIT 1 3/4 4-10 Amendment No. 33, 49, Zi, 182 TABLE 3.4.3.2-1 (Deleted)THE INFORMATION FROM THIS TECHNICAL SPECIFICATION SECTION HAS BEEN RELOCATED TO THE TECHNICAL REQUIREMENTS MANUAL (TRM)LIMERICK -UNIT 1 3/4 4-11 Amendment No. 44, 182 REACTOR COOLANT SYSTEM BASES _ __3/4.4.3.2 OPERATIONAL LEAKAGE (Continued)
: a. Monitoring the primary containment atmospheric gaseous radioactivity at least once per 12 hours (not a means of quantifying leakage),
The function of Reactor Coolant System Pressure Isolation Valves (PIVs) is to separate the high pressure Reactor Coolant System from an attached low pressure system.The ACTION requirements for pressure isolation valves are used in conjunction with the system specifications for which PIVs are listed in the Technical Requirements Manual and with primary containment isolation valve requirements to ensure that plant operation is appropriately limited.The Surveillance Requirements for the RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA. Leakage from the RCS pressure isolation valves is not included in any other allowable operational leakage specified in Section 3.4.3.2.3/4.4.4 (Deleted)
: b. Monitoring the drywell floor drain sump and drywell equipment drain tank flow rate at least once per eight (8) hours,
INFORMATION FROM THIS SECTION RELOCATED TO THE TRM LIMERICK -UNIT I B 3/'4 4-3e Amendment No. 44Q, 1-7-, 1474, 182 I NDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE REACTOR COOLANT SYSTEM (Continued)
: c. Monitoring the drywell unit coolers condensate flow rate at least once per 12 hours,
Figure 3.4.1.1-1 Deleted ..............................
: d. Monitoring the primary containment pressure at least once per 12 hours (not a means of quantifying leakage),
3/4 4-3 Jet Pumps .................................................
: e. Monitoring the reactor vessel head flange leak detection system at least once per 24 hours, and
3/4 4-4 Recirculation Pumps .........................................
: f. Monitoring the primary containment temperature at least once per 24 hours (not a means of quantifying leakage).
3/4 4-5 Idle Recirculation Loop Startup .............................
4.4.3.2.2     Each reactor coolant system pressure isolation valve shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit:
3/4 4-6 3/4.4.2 SAFETY/RELIEF VALVES ........................................
: a. At least once per 24 months, end
3/4 4-7 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems ...................................
: b. Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.
3/4 4-8 Operational Leakage .........................................
The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.
3/4 4-9 Table 3.4.3.2-1 Deleted ...............................
4.4.3.2.3     The high/low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints set less than the specified allowable values by performance of a:
3/4 4-11 3/4.4.4 (Deleted)
: a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and
The information from pages 3/4 4-12 through 3/4 4-14 has been intentionally omitted.Refer to note on page 3/4 4-12 ...........................
: b. CHANNEL CALIBRATION   at least once per 24 months.
3/4 4-12 3/4.4.5 SPECIFIC ACTIVITY ...........................
LIMERICK - UNIT 1                         3/4 4-10           Amendment No. 33, 49, Zi, 182
3/4 4-15 Table 4.4.5-1 Primary Coolant Specific Activity Sample and Analysis Program ..... 3/4 4-17 3/4.4.6 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System ..... 3/4 4-18 Figure 3.4.6.1-1 Minimum Reactor Pressure Vessel Metal Temperature Vs. Reactor Vessel Pressure ..... 3/4 4-20 Table 4.4.6.1.3-1 Deleted ..... 3/4 4-21 Reactor Steam Dome ..............
 
3/4 4-22 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES .............................
TABLE 3.4.3.2-1 (Deleted)
3/4 4-23 3/4.4.8 STRUCTURAL INTEGRITY  
THE INFORMATION FROM THIS TECHNICAL SPECIFICATION SECTION HAS BEEN RELOCATED TO THE TECHNICAL REQUIREMENTS MANUAL (TRM)
.............................
LIMERICK - UNIT 1                       3/4 4-11                 Amendment No. 44, 182
3/4 4-24 I LIMERICK -UNIT 2 xi Amendment No. 1.3O, 136, 439, 144 REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to: a. No PRESSURE BOUNDARY LEAKAGE.b. 5 gpm UNIDENTIFIED LEAKAGE.c. 30 gpm total leakage.d. 25 gpm total leakage averaged over any 24-hour period.e. 1 gpm leakage at a reactor coolant system pressure of 950 +/-10 psig from any reactor coolant system pressure isolation valve.**f. 2 gpm increase in UNIDENTIFIED LEAKAGE over a 24-hour period.APPLICABILITY:
 
OPERATIONAL CONDITIONS 1, 2, and 3.ACTION: a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours.b. With any reactor coolant system leakage greater than the limits in b, c and/or d above, reduce the leakage rate to within the limits within 4 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.c. With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours by use of at least one other closed manual, deactivated automatic, or check* valves, or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.d. With one or more of the high/low pressure interface valve leakage pressure monitors inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm setpoint at least once per 12 hours; restore the inoperable monitor(s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.e. With any reactor coolant system leakage greater than the limit in f above, identify the source of leakage within 4 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.* Which have been verified not to exceed the allowable leakage limit at the last refueling outage or after the last time the valve was disturbed, whichever is more recent.** Pressure isolation valve leakage is not included in any other allowable operational leakage specified in Section 3.4.3.2.LIMERICK -UNIT 2 3/4 4-9 Amendment No. .4-, 434, 144 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS
REACTOR COOLANT SYSTEM BASES                                                                     _     __
_4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by: a. Monitoring the primary containment atmospheric gaseous radioactivity at least once per 12 hours (not a means of quantifying leakage), b. Monitoring the drywell floor drain sump and drywell equipment drain tank flow rate at least once per eight (8) hours, c. Monitoring the drywell unit coolers condensate flow rate at least once per 12 hours, d. Monitoring the primary containment pressure at least once per 12 hours (not a means of quantifying leakage), e. Monitoring the reactor vessel head flange leak detection system at least once per 24 hours, and f. Monitoring the primary containment temperature at least once per 24 hours (not a means of quantifying leakage).4.4.3.2.2 Each reactor coolant system pressure isolation valve shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit: a. At least once per 24 months, and b. Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.4.4.3.2.3 The high/low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints set less than the specified allowable values by performance of a: a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and b. CHANNEL CALIBRATION at least once per 24 months.LIMERICK -UNIT 2 3/4 4-10 Amendment No. 44, 34,144 TABLE 3.4.3.2-1 (Deleted)THE INFORMATION FROM THIS TECHNICAL SPECIFICATION SECTION HAS BEEN RELOCATED TO THE TECHNICL REQUIREMENTS MANUAL (TRM).LIMERICK -UNIT 2 3/4 4-11 Amendment No. 144 REACTOR COOLANT SYSTEM BASES _3/4.4.3.2 OPERATIONAL LEAKAGE (Continued)
3/4.4.3.2   OPERATIONAL LEAKAGE (Continued)
The function of Reactor Coolant System Pressure Isolation Valves (PIVs) is to separate the high pressure Reactor Coolant System from an attached low pressure system.The ACTION requirements for pressure isolation valves are used in conjunction with the system specifications for which PIVs are listed in The Technical Requirements Manual and with primary containment isolation valve requirements to ensure that plant operation is appropriately limited.The Surveillance Requirements for the RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA. Leakage from the RCS pressure isolation valves is not included in any other allowable operational leakage specified in Section 3.4.3.2.3/4.4.4 (Deleted)
The function of Reactor Coolant System Pressure Isolation Valves (PIVs) is to separate the high pressure Reactor Coolant System from an attached low pressure system.
INFORMATION FROM THIS SECTION RELOCATED TO THE TRM LIMERICK -UNIT 2 B 3/4 4-3e Amendment No. 44X, 1.34, 436, 144}}
The ACTION requirements for pressure isolation valves are used in conjunction with the system specifications for which PIVs are listed in the Technical Requirements Manual and with primary containment isolation valve requirements to ensure that plant operation is appropriately limited.
The Surveillance Requirements for the RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA. Leakage from the RCS pressure isolation valves is not included in any other allowable operational leakage specified in Section 3.4.3.2.
3/4.4.4   (Deleted) INFORMATION FROM THIS SECTION RELOCATED TO THE TRM LIMERICK - UNIT I                       B 3/'4 4-3e     Amendment No. 44Q, 1-7-,   1474, 182
 
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION                                                                           PAGE REACTOR COOLANT SYSTEM (Continued)
Figure 3.4.1.1-1       Deleted .............................. 3/4 4-3 Jet Pumps .................................................           3/4 4-4 Recirculation Pumps ......................................... 3/4 4-5 Idle Recirculation Loop Startup ............................. 3/4 4-6 3/4.4.2   SAFETY/RELIEF VALVES ........................................ 3/4 4-7 3/4.4.3   REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems ................................... 3/4 4-8 Operational Leakage ......................................... 3/4 4-9 Table 3.4.3.2-1       Deleted ............................... 3/4 4-11   I 3/4.4.4     (Deleted) The information from pages 3/4 4-12 through 3/4 4-14 has been intentionally omitted.
Refer to note on page 3/4 4-12 ...........................           3/4 4-12 3/4.4.5   SPECIFIC ACTIVITY ...........................                         3/4 4-15 Table 4.4.5-1   Primary Coolant Specific Activity Sample and Analysis Program .....             3/4 4-17 3/4.4.6     PRESSURE/TEMPERATURE LIMITS Reactor Coolant System .....                                         3/4 4-18 Figure 3.4.6.1-1     Minimum Reactor Pressure Vessel Metal Temperature Vs. Reactor Vessel Pressure .....                     3/4 4-20 Table 4.4.6.1.3-1       Deleted .....                         3/4 4-21 Reactor Steam Dome ..............                                     3/4 4-22 3/4.4.7   MAIN STEAM LINE ISOLATION VALVES ............................. 3/4 4-23 3/4.4.8   STRUCTURAL INTEGRITY .............................                     3/4 4-24 LIMERICK - UNIT 2                                   xi   Amendment No. 1.3O, 136, 439, 144
 
REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2   Reactor coolant system leakage shall be limited to:
: a. No PRESSURE BOUNDARY LEAKAGE.
: b. 5 gpm UNIDENTIFIED LEAKAGE.
: c. 30 gpm total leakage.
: d. 25 gpm total leakage averaged over any 24-hour period.
: e. 1 gpm leakage at a reactor coolant system pressure of 950 +/-10 psig from any reactor coolant system pressure isolation valve.**
: f. 2 gpm increase in UNIDENTIFIED LEAKAGE over a 24-hour period.
APPLICABILITY:     OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
: a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours.
: b. With any reactor coolant system leakage greater than the limits in b, c and/or d above, reduce the leakage rate to within the limits within 4 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
: c. With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours by use of at least one other closed manual, deactivated automatic, or check* valves, or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
: d. With one or more of the high/low pressure interface valve leakage pressure monitors inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm setpoint at least once per 12 hours; restore the inoperable monitor(s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
: e. With any reactor coolant system leakage greater than the limit in f above, identify the source of leakage within 4 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
* Which have been verified not to exceed the allowable leakage limit at the last refueling outage or after the last time the valve was disturbed, whichever is more recent.
**   Pressure isolation valve leakage is not included in any other allowable operational leakage specified in Section 3.4.3.2.
LIMERICK - UNIT 2                           3/4 4-9               Amendment No. .4-,434, 144
 
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS   _
4.4.3.2.1   The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:
: a. Monitoring the primary containment atmospheric gaseous radioactivity at least once per 12 hours (not a means of quantifying leakage),
: b. Monitoring the drywell floor drain sump and drywell equipment drain tank flow rate at least once per eight (8) hours,
: c. Monitoring the drywell unit coolers condensate flow rate at least once per 12 hours,
: d. Monitoring the primary containment pressure at least once per 12 hours (not a means of quantifying leakage),
: e. Monitoring the reactor vessel head flange leak detection system at least once per 24 hours, and
: f. Monitoring the primary containment temperature at least once per 24 hours (not a means of quantifying leakage).
4.4.3.2.2     Each reactor coolant system pressure isolation valve shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit:
: a. At least once per 24 months, and
: b. Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.
The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.
4.4.3.2.3     The high/low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints set less than the specified allowable values by performance of a:
: a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and
: b. CHANNEL CALIBRATION at least once per 24 months.
LIMERICK - UNIT 2                         3/4 4-10               Amendment No. 44, 34,144
 
TABLE 3.4.3.2-1   (Deleted)
THE INFORMATION FROM THIS TECHNICAL SPECIFICATION SECTION HAS BEEN RELOCATED TO THE TECHNICL REQUIREMENTS MANUAL (TRM).
LIMERICK - UNIT 2                         3/4 4-11                     Amendment No. 144
 
REACTOR COOLANT SYSTEM BASES _
3/4.4.3.2 OPERATIONAL LEAKAGE (Continued)
The function of Reactor Coolant System Pressure Isolation Valves (PIVs) is to separate the high pressure Reactor Coolant System from an attached low pressure system.
The ACTION requirements for pressure isolation valves are used in conjunction with the system specifications for which PIVs are listed in The Technical Requirements Manual and with primary containment isolation valve requirements to ensure that plant operation is appropriately limited.
The Surveillance Requirements for the RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA. Leakage from the RCS pressure isolation valves is not included in any other allowable operational leakage specified in Section 3.4.3.2.
3/4.4.4   (Deleted) INFORMATION FROM THIS SECTION RELOCATED TO THE TRM LIMERICK - UNIT 2                       B 3/4 4-3e     Amendment No. 44X, 1.34, 436, 144}}

Latest revision as of 23:09, 23 November 2019

Technical Specification Pages Pressure Isolation Valve Table
ML060530214
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 02/17/2006
From:
Plant Licensing Branch III-2
To:
References
TAC MC9306, TAC MC9307
Download: ML060530214 (12)
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Text

[ NDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE REACTOR COOLANT SYSTEM (Continued)

Figure 3.4.1.1-1 Deleted ......... ..................... 3/4 4-3 Jet Pumps ................................................. 3/4 4-4 Recirculation Pumps . ........................................ 3/4 4-5 Idle Recirculation Loop Startup ........ ..................... 3/4 4-6 3/4.4.2 SAFETY/RELIEF VALVES . ........................................ 3/4 4-7 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems ........... ........................ 3/4 4-8 Operational Leakage . ........................................ 3/4 4-9 Table 3.4.3.2-1 Deleted ......... ..................... 3/4 4-11 I 3/4.4.4 (Deleted) The information from pages 3/4 4-12 through 3/4 4-14 has been intentionally omitted.

Refer to note on page 3/4 4-12 ......... ..................... 3/4 4-12 3/4.4.5 SPECIFIC ACTIVITY . .......................................... 3/4 4-15 Table 4.4.5-1 Primary Coolant Specific Activity Sample and Analysis Program ..... ........ 3/4 4-17 3/4.4.6 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System ...... ................................ 3/4 4-18 Figure 3.4.6.1-1 Minimum Reactor Pressure Vessel Metal Temperature Vs. Reactor Vessel Pressure ...... ................ 3/4 4-20 Table 4.4.6.1.3-1 Deleted ........ ..................... 3/4 4-21 Reactor Steam Dome . .......................................... 3/4 4-22 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES ........ .................... 3/4 4-23 3/4.4.8 STRUCTURAL INTEGRITY . ........................................ 3/4 4-24 LIMERICK - UNIT 1 xi Amendment No. .1-6., .1-4, 1-7,, 182

REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FQR OPERATIO_

3.4.3.2 Reactor coolant system leakage shall be limited to:

a. No PRESSURE BOUNDARY LEAKAGE.
b. 5 gpm UNIDENTIFIED LEAKAGE.
c. 30 gpm total leakage.
d. 25 gpm total leakage averaged over any 24-hour period.
e. 1 gpm leakage at a reactor coolant system pressure of 950 +/-10 psig from any reactor coolant system pressure isolation valve.** I
f. 2 gpm increase in UNIDENTIFIED LEAKAGE over a 24-hour period.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b. With any reactor coolant system leakage greater than the limits in b, c and/or d above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c. With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one other closed manual, deactivated automatic, or check* valves, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d. With one or more of the high/low pressure interface valve leakage pressure monitors inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm setpoint at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; restore the inoperable monitor(s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
e. With any reactor coolant system leakage greater than the limit in f above, identify the source of leakage within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
  • Which have been verified not to exceed the allowable leakage limit at the last refueling outage or after the last time the valve was disturbed, whichever is more recent.
    • Pressure isolation valve leakage is not included in any other allowable operational leakage specified in Section 3.4.3.2.

LIMERICK - UNIT 1 3/14 4-9 Amendment No. 2.8, 49, 4-72, 182

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS _

4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:

a. Monitoring the primary containment atmospheric gaseous radioactivity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (not a means of quantifying leakage),
b. Monitoring the drywell floor drain sump and drywell equipment drain tank flow rate at least once per eight (8) hours,
c. Monitoring the drywell unit coolers condensate flow rate at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,
d. Monitoring the primary containment pressure at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (not a means of quantifying leakage),
e. Monitoring the reactor vessel head flange leak detection system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and
f. Monitoring the primary containment temperature at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (not a means of quantifying leakage).

4.4.3.2.2 Each reactor coolant system pressure isolation valve shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit:

a. At least once per 24 months, end
b. Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.

The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.

4.4.3.2.3 The high/low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints set less than the specified allowable values by performance of a:

a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and
b. CHANNEL CALIBRATION at least once per 24 months.

LIMERICK - UNIT 1 3/4 4-10 Amendment No. 33, 49, Zi, 182

TABLE 3.4.3.2-1 (Deleted)

THE INFORMATION FROM THIS TECHNICAL SPECIFICATION SECTION HAS BEEN RELOCATED TO THE TECHNICAL REQUIREMENTS MANUAL (TRM)

LIMERICK - UNIT 1 3/4 4-11 Amendment No. 44, 182

REACTOR COOLANT SYSTEM BASES _ __

3/4.4.3.2 OPERATIONAL LEAKAGE (Continued)

The function of Reactor Coolant System Pressure Isolation Valves (PIVs) is to separate the high pressure Reactor Coolant System from an attached low pressure system.

The ACTION requirements for pressure isolation valves are used in conjunction with the system specifications for which PIVs are listed in the Technical Requirements Manual and with primary containment isolation valve requirements to ensure that plant operation is appropriately limited.

The Surveillance Requirements for the RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA. Leakage from the RCS pressure isolation valves is not included in any other allowable operational leakage specified in Section 3.4.3.2.

3/4.4.4 (Deleted) INFORMATION FROM THIS SECTION RELOCATED TO THE TRM LIMERICK - UNIT I B 3/'4 4-3e Amendment No. 44Q, 1-7-, 1474, 182

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE REACTOR COOLANT SYSTEM (Continued)

Figure 3.4.1.1-1 Deleted .............................. 3/4 4-3 Jet Pumps ................................................. 3/4 4-4 Recirculation Pumps ......................................... 3/4 4-5 Idle Recirculation Loop Startup ............................. 3/4 4-6 3/4.4.2 SAFETY/RELIEF VALVES ........................................ 3/4 4-7 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems ................................... 3/4 4-8 Operational Leakage ......................................... 3/4 4-9 Table 3.4.3.2-1 Deleted ............................... 3/4 4-11 I 3/4.4.4 (Deleted) The information from pages 3/4 4-12 through 3/4 4-14 has been intentionally omitted.

Refer to note on page 3/4 4-12 ........................... 3/4 4-12 3/4.4.5 SPECIFIC ACTIVITY ........................... 3/4 4-15 Table 4.4.5-1 Primary Coolant Specific Activity Sample and Analysis Program ..... 3/4 4-17 3/4.4.6 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System ..... 3/4 4-18 Figure 3.4.6.1-1 Minimum Reactor Pressure Vessel Metal Temperature Vs. Reactor Vessel Pressure ..... 3/4 4-20 Table 4.4.6.1.3-1 Deleted ..... 3/4 4-21 Reactor Steam Dome .............. 3/4 4-22 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES ............................. 3/4 4-23 3/4.4.8 STRUCTURAL INTEGRITY ............................. 3/4 4-24 LIMERICK - UNIT 2 xi Amendment No. 1.3O, 136, 439, 144

REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

a. No PRESSURE BOUNDARY LEAKAGE.
b. 5 gpm UNIDENTIFIED LEAKAGE.
c. 30 gpm total leakage.
d. 25 gpm total leakage averaged over any 24-hour period.
e. 1 gpm leakage at a reactor coolant system pressure of 950 +/-10 psig from any reactor coolant system pressure isolation valve.**
f. 2 gpm increase in UNIDENTIFIED LEAKAGE over a 24-hour period.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b. With any reactor coolant system leakage greater than the limits in b, c and/or d above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c. With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one other closed manual, deactivated automatic, or check* valves, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d. With one or more of the high/low pressure interface valve leakage pressure monitors inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm setpoint at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; restore the inoperable monitor(s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
e. With any reactor coolant system leakage greater than the limit in f above, identify the source of leakage within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
  • Which have been verified not to exceed the allowable leakage limit at the last refueling outage or after the last time the valve was disturbed, whichever is more recent.
    • Pressure isolation valve leakage is not included in any other allowable operational leakage specified in Section 3.4.3.2.

LIMERICK - UNIT 2 3/4 4-9 Amendment No. .4-,434, 144

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS _

4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:

a. Monitoring the primary containment atmospheric gaseous radioactivity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (not a means of quantifying leakage),
b. Monitoring the drywell floor drain sump and drywell equipment drain tank flow rate at least once per eight (8) hours,
c. Monitoring the drywell unit coolers condensate flow rate at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,
d. Monitoring the primary containment pressure at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (not a means of quantifying leakage),
e. Monitoring the reactor vessel head flange leak detection system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and
f. Monitoring the primary containment temperature at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (not a means of quantifying leakage).

4.4.3.2.2 Each reactor coolant system pressure isolation valve shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit:

a. At least once per 24 months, and
b. Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.

The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.

4.4.3.2.3 The high/low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints set less than the specified allowable values by performance of a:

a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and
b. CHANNEL CALIBRATION at least once per 24 months.

LIMERICK - UNIT 2 3/4 4-10 Amendment No. 44, 34,144

TABLE 3.4.3.2-1 (Deleted)

THE INFORMATION FROM THIS TECHNICAL SPECIFICATION SECTION HAS BEEN RELOCATED TO THE TECHNICL REQUIREMENTS MANUAL (TRM).

LIMERICK - UNIT 2 3/4 4-11 Amendment No. 144

REACTOR COOLANT SYSTEM BASES _

3/4.4.3.2 OPERATIONAL LEAKAGE (Continued)

The function of Reactor Coolant System Pressure Isolation Valves (PIVs) is to separate the high pressure Reactor Coolant System from an attached low pressure system.

The ACTION requirements for pressure isolation valves are used in conjunction with the system specifications for which PIVs are listed in The Technical Requirements Manual and with primary containment isolation valve requirements to ensure that plant operation is appropriately limited.

The Surveillance Requirements for the RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA. Leakage from the RCS pressure isolation valves is not included in any other allowable operational leakage specified in Section 3.4.3.2.

3/4.4.4 (Deleted) INFORMATION FROM THIS SECTION RELOCATED TO THE TRM LIMERICK - UNIT 2 B 3/4 4-3e Amendment No. 44X, 1.34, 436, 144

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