ML20199D815
| ML20199D815 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/12/1999 |
| From: | Bill Dean NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199D819 | List: |
| References | |
| NUDOCS 9901200219 | |
| Download: ML20199D815 (17) | |
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30666 4 001 k
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t PECO ENERGY COMPANY l
l DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE t
Amendment No.133 License No. NPF-39 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by PECO Energy Company (the licensee) dated October 15,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set j
forth in 10 CFR ChapterI; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can l
be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amenda ent will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9901200219 990112 PDR ADOCK 05000352 P
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-39 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.133, are hereby incorporated into this license. PECO Energy Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION i
William M. Dean, Director Project Directorate 12 Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: January 12, 1999 i
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e ATTACHMENTTO LICENSE AMENDMENT NO.133 FACILITY OPERATING LICENSE 'NO. NPF-39 DOCKET NO. 50-352 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove jnged xyl xvi xxii xxil 1-10 1-10 3/4147 3/4148 B 3/410-1 B 3/410-1 B 3/4142 l
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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION PEiE REFUELING OPERATIONS (Continued) l 3/4.9.10 CONTROL ROD REMOVAL Si ngl e Control Rod Remova1............................
3/4 9-13 Mul tipl e Control Rod Remova1..........................
3/4 9-15 l
l 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION l
l High Water Leve1......................................
3/4 9-17 l
Low Water Leve1.......................................
3/4 9-18 l
3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY.........................
3/4 10-1 3/4.10.2 R0D WORTH MINIMIZER...................................
3/4 10-2 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS........................
3/4 10-3 3/4.10.4 RECIRCULATION L00PS...................................
3/4 10-4 j
3/4.10.5 OXYGEN CONCENTRATION..................................
3/4 10-5 l
3/4.10.6 TRAINING STARTUPS.....................................
3/4 10-6 3/4.10.7 RESERVED - CURRENTLY NOT USED.........................
3/4 10-7 3/4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING................
3/4 10-8 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS The information from pages 3/4 11-1 i
through 3/4 11-6 has been intentionally omitted. Refer to note on page 3/4 11-1..............
3/4 11-1 l
Liquid Holdup Tanks...................................
3/4 11-7 i
l 3/4.11.2 GASEOUS EFFLUENTS The information from pages 3/4 11-8 through 3/4 11-14 has been intentionally 4
omitted.
Refer to note on page 3/4 11-8..............
3/4 11-8 LIMERICK - UNIT 1 xvi Amendment No. 77, 33, #S, 133
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BASES SECTION E8E REFUELING OPERATIONS (Continued) 3/4.9.6 REFUELING PLATF0RM...............................
B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P00L...........
B 3/4 9-2 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAGE P00L........
B 3/4 9-2 3/4.9.10 CONTROL ROD REM 0 VAL..............................
B 3/4 9-2 i
3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION....
B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY....................
B 3/410-1 l
3/4.10.2 ROD WORTH MINIMIZER..............................
B 3/410-1 3/4,10.3 SHUTDOWN MARGIN DEM0NETRATIONS...................
B 3/410-1 3/4.10.4 RECIRCULATION L00PS..............................
B 3/410-1 3/4.10.5
- OXYGEN CONCENTRATION.............................
B 3/410-1 3/4.10.6 TRAINING STARTUPS................................
B 3/410-1 3/4.10.7 RESERVED - CURRENTLY NOT USED....................
B 3/410-1 j
3/4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING...........
B 3/410-2 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 L1 QUID EFFLUENTS The information on page B 3/4 11-1 has been intentionally omitted.
Refer to note on this page.
B 3/411-1 i
(Deleted)........................................
B 3/411-2 Liquid Holdup Tanks..............................
B 3/411-2 3/4.11.2 GASEOUS EFFLUENTS (Deleted)........................................
B 3/411-2 The information on page B 3/4 11-3 has been intentionally omitted.
Refer to note on this page.
B 3/411-3 f
( Del e t ed )........................................
B 3/411-4 LIMERICK - UNIT 1 xxii Amendment No. U/, /M,133 w
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l DEFINITIONS TABLE 1.2 OPERATIONAL CONDITIONS MODE SWITCH AVERAGE REACTOR CONDITION POSITION COOLANT TEMPERATURE
- 1. POWER OPERATION Run Any temperature
- 2. STARTUP Startup/ Hot Standby Any temperature
- 3. HOT SHUTDOWN Shutdown # ***
> 200*F
- 4. COLD SHUTDOWN Shutdown # ## ***
s 200*F ****
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- 5. REFUELING
- Shutdown or Refuel ** #
NA
- The reactor mode switch may be placed in the Run or Startu)/ Hot Standby position to test the switch interlock functions provided t1at the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.
- The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Specification 3.9.10.1.
- Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
- See Spec U Test Exceptions 3.10.1 and 3.10.3.
- The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled provided that the one-rod-out interlock is OPERABLE.
cc8*See Special Test Exception 3.10.8.
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LIMERICK - UNIT 1 1-10 Amendment No. SS, 133 mw--
SPECIAL TEST EXCEPTIONS 3/4.10.7 RESERVED-CURRENTLY NOT USED l
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l LIMERICK - UNIT 1 3/4 10-7 Amendment No. 133
SPECIAL TEST EXCEPTIONS 3/4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING LIMITING CONDITIONS FOR OPERATION 3.10.8 When conducting inservice leak or hydrostatic testing, the average reactor coolant temperature specified in Table 1.2 for OPERATIONAL CONDITION 4 may be increased to 212'F, and operation considered not to be in OPERATIONAL CONDITION 3, to allow performance of an inservice leak or hydrostatic test provided the following OPERATIONAL CONDITION 3 Specifications are met:
- a. 3.3.2 ISOLATION ACTUATION INSTRUMENTATION, Functions 7.a, 7.c.1, 7.c.2 and 7.d of Table 3.3.2-1;
- b. 3.6.5.1.1 REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY;
- c. 3.6.5.1.2 REFUELING AREA SECONDARY CONTAINMENT INTEGRITY;
- d. 3.6.5.2.1 REACTOR ENCLOSURE SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES;
- e. 3.6.5.2.2 REFUELING AREA SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES; and
- f. 3.6.5.3 STAND 8Y GAS TREATMENT SYSTEM.
i APPLICABILITY: OPERATIONAL CONDITION 4, with average reactor coolant temperature greater than 200*F and less than or equal to 212*F.
ACTION-With the requirements of the above Specifications not satisfied:
- 1. Immediately enter the applicable (OPERATIONAL CONDITION 3) action for the affected Specification; or
- 2. Immediately suspend activities that could increase the average reactor coolant temperature or pressure and reduce the average reactor coolant temperature to 200 F or less w thin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE RE0VIREMENTS 4.10.8 Verify applicable OPERATIONAL CONDITION 3 surveillances for the Specifications listed in 3.10.8 are met.
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i LIMERICK - UNIT 1 3/4 10-8 Amendment No. 133 l
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l 3/4.10 SPECIAL TEST EXCEPTIONS BASES l
3.4.10.1 PRIMARY CONTAINMENT INTEGRITY j
The requirement for PRIMARY CONTAINMENT INTEGRITY is not ap)licable durir.g the period when open vessel tests are being performed during tle low power PHYSICS TESTS.
l 3/4.10.2 ROD WORTH MINIMIZER In order.to perform the tests required in the technical specifications it is necessary to bypass the sequence restraints on control rod movement. The additional surveillance requirements ensure that the specifications on heat l
generation rates and shutdown margin requirements are not exceeded during the l
period when these tests are being )erformed and that individual rod worths do not exceed the values assumed in t1e safety analysis.
3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS l
l PerMmance of shutdown margin demonstrations with the vessel head removed requires additional restrictions in order to ensure that criticality does not occur. These additional restrictions are specified in this LCO.
3/4.10.4 RECIRCULATION LOOPS This special test exception permits reactor criticality under no flow j
conditions and is required to perform certain startup and PHYSICS TESTS while l
at low THERMAL POWER levels.
l 3/4.10.5 OXYGEN CONCENTRATION l
Relief from the oxygen concentration specifications is necessary in order to provide access to the primary containment during the initial startup and testing phase of operation. Without this access the startup and test program could be restricted and delayed.
3/4.10.6 TRAINING STARTUPS This special test exception permits training startups to be performed with the reactor venel depressurized at low THERMAL POWER and temperature while I
controlling RCS temperature with one RHR subsystem aligned in the shutdown cooling mode in order to minimize contaminated water riischarge to the l
radioactive waste disposal rystem.
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3/4.10.7 RESERVED - CURRENTLY NOT USED l
l LIMERICK - UNIT 1 B 3/4 10-1 Amendment No. Y7, W,133
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L 3/4.10 SPECIAL TEST EXCEPTIONS BASES 3/4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING This special test exception permits certain reactor coolant pressure tests to be performed in OPERATIONAL CONDITION 4 when the metallurgical characteristics of the reactor pressure vessel (RPV) or plant temperature control capabilities during these tests require the pressure testing at temperatures greater than 200'F and less than or equal to 212*F (normally corresponding to OPERATIONAL CONDITION 3). The additionally imposed OPERATIONAL CONDITION 3 requirements for SECONDARY CONTAINMENT INTEGRITY provide conservatism in response to an operational event.
Inservice hydrostatic testing and inservice leak pressure tests required by Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code are performed prior to the reactor going critical after a refueling outage. The l
minimum temperatures (at the required pressures) allowed for these tests are determined from the RPV pressure and temperature (P/T) limits required by LC0 3.4.6, Reactor Coolant System Pressure / Temperature Limits. These limits are conservatively based on the fracture toughness of the reactor vessel, taking into account l
anticipated versel neutron fluence. With increased reactor fluence over time, the minimum allowable vessel temperature increases at a given pressure. Periodic updates to the RCS P/T limit curves are performed as necessary, based upon the results of analysis of irradiated surveillance specimens removed from the vessel.
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LIMERICK - UNIT 1 B 3/4 10-2
.Anendment No.133 l
NUCLEAR REGULATORY COMMISSION wAaHINGTON, D.C. enasam PECO ENERGY COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT 10 FACILITY OPERATING LICENSE
^
Amendment No. 95 License No. NPF-85 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by PECO Energy Company (the licensee) dated October 15,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR ChapterI; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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!, 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated i
in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows:
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Technical Specifications l
The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 95, are hereby incorporated in the license. PECO Energy Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
l 3.
This license amendment is effective as of its date ofissuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
^ O( -f ] V William M. Dean, Director l
Project Directorate 1-2 Division of Reactor Projects -l/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: January 12, 1999 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 45 i
FACILITY OPERATING LICENSE NO. NPF-85 l
DOCKET NO. 50-353 l
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Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment numbsr and contain verticallines indicating the area of change.
Remove Insert xyl xvi xxii xxii i
1-10 1-10 3/4149 i
B 3/410-2 l
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION EAGE REFUELING OPERATIONS (Continued) l 3/4.9.10 CONTROL R0D REMOVAL l
Single Control Rod Remova1............................
3/4 9-13 Mul tipl e Control Rod Remova1..........................
3/4 9-15 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level......................................
3/4 9-17 Low Water Level.......................................
3/4 9-18 3/4.10 SPECIAL TEST EXCEPTIONS i
3/4.10.1 PRIMARY CONTAINMENT INTEGRITY.........................
3/4 10-1 l
3/4.10.2 R0D WORTH MINIMIZER...................................
3/4 10-2 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS........................
3/4 10-3 3/4.10.4 RECIRCULATION L00PS...................................
3/4 10-4 3/4.10.5 OXYGEN CONCENTRATION..................................
3/4 10-5 l
3/4.10.6 TRAINING STARTUPS.....................................
3/4 10-6 l
3/4.10.7 SPECIAL INSTRUMENTATION - INITIAL CORE LOADING........
3/4 10-7 i
l, 3/4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING.................
3/4 10-9 l
3/4.11 RADI0 ACTIVE EFFLUENTS l
t 3/4.11.1 LIQUID EFFLUENTS The information from pages 3/4 11-1 through 3/4 11-6 has been intentionally omitted.
Refer to note on page 3/4 11-1..............
3/4 11-1 Liquid Holdup Tanks...................................
3/4 11-7 l
3/4.11.2 GASEOUS EFFLUENTS The information from pages 3/4 11-8 through 3/4 11-14 has been intentionally omitted.
Refer to note on page 3/4 11-8..............
3/4 11-8 i
i LIMERICK - UNIT 2 xvi Anendment No. YY, 95 l
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INDEX BASES SECTION 13G1 REFUELING OPERATIONS (Continued) 3/4.9.6 REFUELING PLATF0RM...............................
B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P00L...........
B 3/4 9-2 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL AND WATER LEVEL - SPENT FUEL STORAGE P00L........
B 3/4 9-2 2
3/4.9.10 CONTROL R0D REM 0 VAL..............................
B 3/4 9-2 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION....
B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY....................
B 3/4 10-1 3/4.10.2 R0D WORTH MINIMIZER..............................
B 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS...................
B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS..............................
B 3/4 10-1 3/4.10.5 0XYGEN CONCENTRATION.............................
B 3/4 10-1 3/4.10.6 TRAINING STARTUPS................................
B 3/4 10-1 3/4.10.7 SPECIAL INSTRUMENTATION - INITIAL CORE LOADING....
B 3/4 10-1 3/4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING...........
B 3/4 10-2 l
3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS The information on page B 3/4 11-1 has been intentionally omitted.
Refer to note on this page..............................................
B 3/4 11-1
( Del e t ed )........................................
B 3/4 11-2 Liquid Holdup Tanks..............................
B 3/4 11-2 3/4.11.2 GASEOUS EFFLUENTS (Deleted)........................................
B 3/4 11-2 The information on page B 3/4 11-3 has been intentionally omitted.
Refer to note on this page.............................................
B 3/4 11-3 (Deleted)........................................
B 3/4 11-4 LIMERICK - UNIT 2 xxii Amendment No. 95
_ _ _ _. q DEFINITIONS TABLE 1.2 OPERATIONAL CONDITIONS MODE SWITCH AVERAGE REACTOR CONDITION POSITION COOLANT TEMPERATURE
- 1. POWER OPERATION Run Any temperature
- 2. STARTUP Startup/ Hot Standby Any temperature
- 3. HOT SHUTDOWN Shutdown # ***
> 200*F
- 4. COLD SHUTDOWN Shutdown # ## ***
s 200*F ****
l
- 5. REFUELING
- Shutdown or Refuel ** #
NA
- The reactor mode s' witch may be placed in the ~Run or Startu)/ Hot Standby position to test the switch interlock functions provided t1at the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.
- The reactor mode switch may be placed in the Refuel position while a single
- control rod drive is being removed from the reactor pressure vessel per Specification 3.9.10.1.
- Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
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- See Special Test Exceptions 3.10.1 and 3.10.3.
- The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled provided that the one-rod-out interlock is OPERABLE.
- See Special Test Exception 3.10.8.
l LIMERICK - UNIT 2 1-10 Amendment No. 50, 95
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SPECIAL TEST EXCEPTIONS 3/4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING LIMITING CONDITION FOR OPERATION 3.10.8 When conducting inservice leak or hydrostatic testing, the average reactor coolant temperature specified in Table 1.2 for OPERATIONAL CONDITION 4 may be increased to 212*F, and operation considered not to be in OPERATIONAL CONDITION 3, to allow performance of an inservice leak or hydrostatic test provided the following OPERATIONAL CONDITION 3 Specifications are met:
- a. 3.3.2 ISOLATION ACTUATION INSTRUMENTATION, Functions 7.a. 7.c.1, 7.c.2 and 7.d of Table 3.3.2-1; b.-3.6.5.1.1 REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY;
- c. 3.6.5.1.2 REFUELING AREA SECONDARY CONTAINMENT INTEGRITY;
- d. 3.6.5.2.1 REACTOR ENCLOSURE SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES;
- e. 3.6.5.2.2 REFUELING AREA SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES; and
- f. 3.6.5.3 STANDBY GAS TREATMENT SYSTEM.
APPLICABILITY: OPERATIONAL CONDITION 4, with average reactor coolant temperature greater than 200*F and less than or equal to 212*F.
l ACTION:
With the requirements of the above Specifications not satisfied:
- 1. Immediately enter the applicable (OPERATIONAL CONDITION 3) action for the affected Specification; or
- 2. Immediately suspend activities that could increase the average reactor coolant temperature or pressure and reduce the average reactor coolant temperature to 200 F or less w' thin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REOUIREMENTS 4.10.8 Verify applicable OPERATIONAL CONDITION 3 surveillances for the Specifications listed in 3.10.8 are met.
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?/4 10-9 Amendment No. 95 l
3/4.10 SPECIAL TEST EXCEPTIONS BASES 3/4.10.8 INSERVICE LEAK AND HYOROSTATIC TESTING This special test exception permits certain reactor coolant pressure tests to be performed in OPERATIONAL CONDITION 4 when the metallurgical characteristics of the reactor pressure vessel (RPV) or plant temperature control capabilities during these tests require the pressure testing at temperatures greater than 200*F and less than or equal to 212*F (normally corresponding to OPERATIONAL CONDITION 3). The additionally imposed OPERATIONAL CONDITION 3 requirements for SECONDARY CONTAINMENT INTEGRITY provide conservatism in response to an operational event.
l Inservice hydrostatic testing and inservice leak pressure tests required by Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code are performed prior to the reactor going critical after a refueling outage. The minimum temperatures (at the required pressures) allowed for these tests are i
determined from the RPV pressure and temperature (P/T) limits required by LC0 3.4.6, Reactor Coolant System Pressure / Temperature Limits. These limits are conservatively based on the fracture toughness of the reactor vessel, taking into account l
anticipated vessel neutron fluence. With increased reactor fluence over time, the l
minimum allowable vessel temperature increases at a given pressure. Periodic updates to the RCS P/T limit curves are performed as necessary, based upon the results of l
analysis of irradiated surveillance specimens removed from the vessel.
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LIMERICK - UNIT 2 B 3/4 10-2 Amendment No. 95 l
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