ML051110061
| ML051110061 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 04/18/2005 |
| From: | NRC/NRR/DLPM |
| To: | |
| References | |
| TAC MC1415, TAC MC1416 | |
| Download: ML051110061 (13) | |
Text
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE REACTOR COOLANT SYSTEM (Continued)
Figure 3.4.1.1-1 Thermal Power versus Core Flow.
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 Reactor Coolant System Pressure Isolation Valves......
............... 3/4 4-11 3/4.4.4 (Deleted) The information from pages 3/4 4-12.....
.......... 3/4 4-12 through 3/4 4-14 has been intentionally omitted Refer to note on page 3/4 4-12 3/4.4.5 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, +6i, 174
DE F ITI (aThS
~
CORE ALTERATION 1.7 CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel.
The following exceptions are not considered to be CORE ALTERATIONS:
a)
Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special moveable detectors (including undervessel replacement); and b)
Control rod movement, provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMITS REPORT 1.7a The CORE OPERATING LIMITS REPORT (COLR) is the unit-specific document that provides the core operating limits for the current operating reload cycle.
These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specifications 6.9.1.9 thru 6.9.1.12.
Plant operation within these limits is addressed in individual specifications.
CRITICAL POWER RATIO 1.8 The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in the assembly which is calculated by application of the (GEXL) correlation to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
DOSE EQUIVALENT I-131 1.9 DOSE EQUIVALENT 1-131 shall be that concentration of I-131, microcuries per gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites."
DOWNSCALE TRIP SETPOINT (DTSP) 1.9a The downscale trip setpoint associated with the Rod Block Monitor (RBM) rod block trip setting.
1.10 (Deleted)
EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME 1.11 The EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ECCS actuation set-point at the channel sensor until the ECCS equipment is capable of performing its safety function, i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.
Times shall include diesel generator starting and sequence loading delays where applicable. The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.
LIMERICK - UNIT I 1-2 Amendment No. 34, &6, 84,174
.34.4,4 (DELETED)
THE INFORMATION FROM THIS TECHNICAL SPECIFICATIONS SECTION HAS BEEN RELOCATED TO THE TECHNICAL REQUIREMENTS MANUAL (TRM).
TECHNICAL SPECIFICATIONS PAGES 3/4 4-13 AND 3/4 4-14 HAVE BEEN INTENTIONALLY OMITTED.
LIMERICK - UNIT I 3/4 4 -12 Amendment No. +/-69,174
REACTOR COOLANT SYSTEM 3/4.4.5 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.5 The specific activity of the primary coolant shall be limited to:
- a.
Less than or equal to 0.2 microcurie per gram DOSE EQUIVALENT 1-131.
- b.
(Deleted)
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3, and 4.
ACTION:
- a.
In OPERATIONAL CONDITION 1, 2, or 3 with the specific activity of the primary coolant;
- 1.
Greater than 0.2 microcurie per gram DOSE EQUIVALENT I-131 but less than or equal to 4 microcuries per gram, DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or greater than 4.0 microcuries per gram DOSE EQUIVALENT I-131, be in at least HOT SHUTDOWN with the main steam line isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The provisions of Specification 3.0.4.c are applicable.
- 2.
(Deleted)
- b.
In OPERATIONAL CONDITION 1, 2, 3, or 4, with the specific activity of the primary coolant greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131, perform the sampling and analysis requirements of Item 4.a of Table 4.4.5-1 until the specific activity of the primary coolant is restored to within its limit.
- c.
In OPERATIONAL CONDITION 1 or 2, with:
- 1.
THERMAL POWER changed by more than 15% of RATED THERMAL POWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or
- 2.
The off-gas level, at the SJAE, increased by more than 10,000 microcuries per second in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during steady-state operation at release rates less than 75,000 microcuries per second, or
- 3.
The off-gas level, at the SJAE, increased by more than 15% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during steady-state operation at release rates greater than 75,000 microcuries per second, perform the sampling and analysis requirements of Item 4.b of Table 4.4.5-1 until the specific activity of the primary coolant is restored to within its limit.
LIMERICK - UNIT 1 3/4 4 -15 Amendment No.,
169-, 174
TABLE 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM TYPE OF MEASUREMENT AND ANALYSIS SAMPLE AND ANALYSIS FREQUENCY OPERATIONAL CONDITIONS IN WHICH SAMPLE AND ANALYSIS IS REQUIRED
- 1.
(Deleted)
- 2.
Isotopic Analysis for DOSE EQUIVALENT I-131 Concentration At least once per 7 days 1
- 3.
(Deleted)
- 4.
Isotopic Analysis for Iodine a) At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, whenever the specific activity exceeds a limit, as required by ACTION b.
1**, 2**, 3**, 4**
b) At least one sample, between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following the change in THERMAL POWER or off-gas level, as required by ACTION c.
1, 2
- 5.
Isotopic Analysis of an Off-gas Sample Including Quantitative Measurements for at least Xe-133, Xe-135, and Kr-88 At least once per 31 days 1
- Until the specific activity of the primary coolant system is restored to within its limits.
LIMERICK - UNIT I 3/4 4 -17 Amendment No. 34,174
REACTOR COOLANT SYSTEM BASES 3/4.4.3.2 OPERATIONAL LEAKAGE (Continued)
The ACTION requirements for pressure isolation valves (PIVs) are used in conjunction with the system specifications for which PIVs are listed in Table 3.4.3.2-1 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 1 B 3/4 4-3e Amendment No. 440, 4-72, 174
.)
REACTOR COOLANT SYSTEM BASES 3/4.4.4 (Deleted) INFORMATION FROM THIS SECTION RELOCATED TO THE TRM 3/4.4.5 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines of 10 CFR Part 100.
The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations.
These values are conservative in that specific site parameters, such as SITE BOUNDARY location and meteorological conditions, were not considered in this evaluation.
The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than 0.2 microcurie per gram DOSE EQUIVALENT 1-131, but less than or equal to 4 microcuries per gram DOSE EQUIVALENT I-131, accommodates possible iodine spiking phenomenon which may occur following changes in the THERMAL POWER.
Operation with specific activity levels exceeding 0.2 microcurie per gram DOSE EQUIVALENT I-131 but less than or equal to 4 microcuries per gram DOSE EQUIVALENT I-131 must be restricted since these activity levels increase the 2-hour thyroid dose at the SITE BOUNDARY following a postulated steam line rupture.
Closing the main steam line isolation valves prevents the release of activity to the environs should a steam line rupture occur outside containment.
The surveillance requirements provide adequate assurance that excessive specific activity levels in the reactor coolant will be detected in sufficient time to take corrective action.
3/4.4.6 PRESSURE/TEMPERATURE LIMITS All components in the reactor coolant system are designed to withstand the effects of cyclic loads due to system temperature and pressure changes.
These cyclic loads are introduced by normal load transients, reactor trips, and startup and shutdown operations. The various categories of load cycles used for design purposes are provided in Section 3.9 of the FSAR.
During startup and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.
LIMERICK - UNIT I B 3/4 4-4 Amendment No. 2-0, 40, 49,174
INDEX ULMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE REACTOR COOLANT SYSTEM (Continued)
Figure 3.4.1.1-1 Thermal Power versus Core Flow....... 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 Reactor Coolant System Pressure Isolation Valves......
................ 3/4 4-11 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 3/4.4.5 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. +35, 136
DEFINITIONS CORE ALTERATION 1.7 CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel.
The following exceptions are not considered to be CORE ALTERATIONS:
a)
Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special moveable detectors (including undervessel replacement); and b)
Control rod movement, provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMITS REPORT 1.7a The CORE OPERATING LIMITS REPORT (COLR) is the unit-specific document that provides the core operating limits for the current operating reload cycle.
These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specifications 6.9.1.9 thru 6.9.12.
Plant operation within these limits is addressed in individual specifications.
CRITICAL POWER RATIO 1.8 The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in the assembly which is calculated by application of the (GEXL) correlation to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
DOSE EQUIVALENT I-131 1.9 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131, microcuries per gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, I-133, I-134, and 1-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites."
DOWNSCALE TRIP SETPOINT (DTSP) 1.9a The downscale trip setpoint associated with the Rod Block Monitor (RBM) rod block trip setting.
1.10 (Deleted)
EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME 1.11 The EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ECCS actuation set-point at the channel sensor until the ECCS equipment is capable of performing its safety function, i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.
Times shall include diesel generator starting and sequence loading delays where applicable. The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.
LIMERICK - UNIT 2 1-2 Amendment No. 4, 48, 4X,136
REACTOR COOLANT SYSTEM 3/4.4.4 (Deleted)
THE INFORMATION FROM THIS TECHNICAL SPECIFICATIONS SECTION HAS BEEN RELOCATED TO THE TECHNICAL REQUIREMENTS MANUAL (TRM).
TECHNICAL SPECIFICATIONS PAGES 3/4 4-13 AND 3/4 4-14 HAVE BEEN INTENTIONALLY OMITTED.
LIMERICK - UNIT 2 3/4 4 -12 Amendment No.132, 136
REACTOR COOLANT SYSTEM 3/4.4.5 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.5 The specific activity of the primary coolant shall be limited to:
- a.
Less than or equal to 0.2 microcurie per gram DOSE EQUIVALENT I-131.
- b.
(Deleted)
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3, and 4.
ACTION:
- a.
In OPERATIONAL CONDITION 1, 2, or 3 with the specific activity of the primary coolant;
- 1.
Greater than 0.2 microcurie per gram DOSE EQUIVALENT I-131 but less than or equal to 4 microcuries per gram, DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or greater than 4.0 microcuries per gram DOSE EQUIVALENT I-131, be in at least HOT SHUTDOWN with the main steam line isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The provisions of Specification 3.0.4.c are applicable.
- 2.
(Deleted)
- b.
In OPERATIONAL CONDITION 1, 2, 3, or 4, with the specific activity of the primary coolant greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131, perform the sampling and analysis requirements of Item 4.a of Table 4.4.5-1 until the specific activity of the primary coolant is restored to within its limit.
- c.
In OPERATIONAL CONDITION 1 or 2, with:
- 1.
THERMAL POWER changed by more than 15% of RATED THERMAL POWER in 1 hour*, or
- 2.
The off-gas level, at the SJAE, increased by more than 10,000 microcuries per second in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during steady-state operation at release rates less than 75,000 microcuries per second, or
- 3.
The off-gas level, at the SJAE, increased by more than 15% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during steady-state operation at release rates greater than 75,000 microcuries per second, perform the sampling and analysis requirements of Item 4.b of Table 4.4.5-1 until the specific activity of the primary coolant is restored to within its limit.
- Not applicable during the startup test program.
LIMERICK - UNIT 2 3/4 4 -15 Amendment No. 442,136
TABLE 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM TYPE OF MEASUREMENT AND ANALYSIS SAMPLE AND ANALYSIS FREQUENCY OPERATIONAL CONDITIONS IN WHICH SAMPLE AND ANALYSIS IS REQUIRED
- 1.
(Deleted)
- 2.
Isotopic Analysis for DOSE EQUIVALENT 1-131 Concentration At least once per 7 days 1
- 3.
(Deleted)
- 4.
Isotopic Analysis for Iodine a) At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> whenever the specific activity exceeds a limit, as required by ACTION b.
1**, 2**, 3**, 4**
b) At least one sample, between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following the change in THERMAL POWER or off-gas level, as required by ACTION c.
1, 2
- 5.
Isotopic Analysis of an Off-gas Sample Including Quantitative Measurements for at least Xe-133, Xe-135, and Kr-88 At least once per 31 days 1
- Until the specific activity of the primary coolant system is restored to within its limits.
LIMERICK - UNIT 2 3/4 4 -17 Amendment No. 136
REACTOR COOLANT SYSTEM 3/4.4.3.2 OPERATIONAL LEAKAGE (Continued)
The ACTION requirements for pressure isolation valves (PIVs) are used in conjunction with the system specifications for which PIVs are listed in Table 3.4.3.2-1 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. 1OP, 134, 136