Letter Sequence Other |
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MONTHYEARML0306906192003-03-10010 March 2003
Draft Safety Evaluation for Proposed Revision to Technical Specifications Safety Limit Minimum Critical Power Ratio for Cycle 8 Operation
Project stage: Draft Approval
ML0307105172003-03-11011 March 2003
Tech Spec Pages for Amendment 127, Revision to Technical Specifications Safety Limit Minimum Critical Power Ratio for Cycle 8 Operation
Project stage: Other
ML0307100182003-03-11011 March 2003
License Amendment 127, Revision to Technical Specifications Safety Limit Minimum Critical Power Ratio for Cycle 8 Operation
Project stage: Approval
ML0308400022003-03-25025 March 2003
Withholding Proprietary Information Letter, Request for Withholding Information from Public Disclosure, Limerick Generating Station, Unit 2
Project stage: Withholding Request Acceptance
2003-03-11
[Table View] |
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Category:Technical Specifications
MONTHYEARML23321A2362023-12-14014 December 2023
Issuance of Amendment Nos. 262 and 224 Adoption of TSTF-477, Revision 3 and Associated Technical Specification Changes
ML23089A1242023-05-17017 May 2023
Issuance of Amd Nos. 261 & 223 Alternate Seismic Approach for Risk-Informed Categorization and Treatment of Structures, Systems a Components for NPR and Denial Proposed Alternative Defense in Depth and Pressure Boundary Component
ML22272A0372023-01-0303 January 2023
Issuance of Amendment Nos. 258 and 220 Regarding Technical Specifications 3/4.8.1, AC Sources-Operating and 3/4.5.1, ECCS-Operating
ML22090A0862022-04-29029 April 2022
Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position
RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022
Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V
ML21347A0382022-01-13013 January 2022
Issuance of Amendments to Revise Reactor Coolant Leakage Requirements
ML21181A0442021-09-28028 September 2021
Issuance of Amendment Nos. 253 and 215 Technical Specification Changes Related to Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021
Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
ML21032A2702021-02-22022 February 2021
Issuance of Amendment Nos. 252 and 214, Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements
ML21013A0052021-02-0404 February 2021
Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2
ML20239A7252020-11-30030 November 2020
Issuance of Amendment Nos. 249 and 211 Adopt TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities
ML20178A5142020-06-26026 June 2020
TS Change and Relief Requests Related to Safety Relief Valve Testing - Response to Request for Additional Information
ML20034F6372020-02-28028 February 2020
Issuance of Amendment Nos. 240 and 203 to Implement TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B
ML19207A0062019-10-0303 October 2019
Issuance of Amendment Nos. 237 and 200 Revise Technical Specifications to Allow Penetration Flow Path Isolation for Inoperable Isolation Actuation Instrumentation
ML19078A0182019-05-24024 May 2019
Issuance of Amendment Nos. 235, 198, 14, 325, and 328 to Revise the Emergency Response Organization Staffing Requirements
ML19029B2492019-02-12012 February 2019
Correction to Amendment No. 195 Revising Technical Specifications to Lower the Minimum Standby Liquid Control System Pump Flowrate
ML19030A1472019-01-30030 January 2019
Supplemental Information Needed for Acceptance of Requested Licensing Action to Adopt Risk-Informed Completion Times in Accordance with TSTF-505, Revision 2
RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018
Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement
ML18017A2012018-02-27027 February 2018
Issuance of Amendment Nos. 227 and 190 Revising Technical Specifications to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control (CAC Nos. MF9967 and MF9968; EPID L-2017-LLA-0260)
ML17200D0962017-07-19019 July 2017
Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Rev. 2.
ML17103A0812017-05-16016 May 2017
Issuance of Amendments to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-545
ML16335A0382016-12-29029 December 2016
Issuance of Amendments to Revise Technical Specification Snubber Requirements
ML16041A0212016-03-15015 March 2016
Issuance of Amendment Safety Limit Minimum Critical Power Ratio Change
ML15356A1402016-01-28028 January 2016
Issuance of Amendments Secondary Containment Access Openings
ML15218A5012015-09-15015 September 2015
Issuance of Amendment Nos. 219 and 181 Proposed Change to Add New Limiting Conditions for Operation 3.0.5 and 3.0.6
ML15141A0582015-07-28028 July 2015
Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251)
ML15083A4032015-05-11011 May 2015
Issuance of Amendments Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation
ML14344A6812015-01-0707 January 2015
Issuance of Amendments - Main Steam Line Flow-High Isolation Response Time
ML14324A8082014-12-29029 December 2014
Issuance of Amendments - Leak Detection System Setpoint and Allowable Value Changes
ML14308A1442014-11-0303 November 2014
License Amendment Request Proposed Change to Add New Limiting Conditions for Operations 3.0.5 and 3.0.6
ML0527800342014-10-20020 October 2014
Current Facility Operating License NPF-39, Technical Specifications, Revised 08/15/2018
ML14191B1802014-07-10010 July 2014
Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
ML13214A0922014-03-26026 March 2014
Issuance of Amendments Elimination of Certain Technical Specifications Reporting Requirements
ML13100A0202013-04-0909 April 2013
License Amendment Request to Eliminate Certain Technical Specifications Reporting Requirements
ML1131802382011-11-10010 November 2011
Response to Request for Additional Information Concerning the License, Amendment Request Associated with the Reactivity Anomalies Surveillance
ML1128700802011-10-12012 October 2011
License Amendment Request - Safety Limit Minimum Critical Power Ratio Change
ML1117100072011-06-14014 June 2011
License Amendment Request to Include an Alternate Method of Verifying Drywell Unidentified Leakage
ML1115401202011-06-0202 June 2011
License Amendment Request - Reactivity Anomalies Surveillance
ML1109700662011-04-0606 April 2011
License Amendment Request to Revise Operability Requirements and Actions for RCS Leakage Instrumentation
ML1035001802010-12-15015 December 2010
License Amendment Request - Safety Limit Minimum Critical Power Ratio Change
ML1030603792010-10-29029 October 2010
Response to Request for Additional Information, License Amendment Request, Proposed Technical Specification Allowed Outage Time Extensions to Support Residual Heat Removal Service Water Maintenance
ML1024304662010-08-31031 August 2010
License Amendment Request, Proposed Administrative Changes to Technical Specifications
ML1018104342010-06-30030 June 2010
License Amendment Request - Table 3.3.2-2, Item 4e, HPCI Equipment Room Delta Temperature High Isolation Trip Setpoint and Allowable Value Changes
ML1008503952010-03-25025 March 2010
Markup of Proposed Operating License, Technical Specifications & Updated Final Safety Analysis Report Pages
ML0912800592009-04-17017 April 2009
Changes to Technical Specifications Bases, Including Changes Through 04/09/2009
ML0824703052008-08-28028 August 2008
Technical Specifications, TSTF Change Traveler TSTF-479 & TSTF-497
ML0821207302008-08-27027 August 2008
Tech Spec Pages for Amendment 154 Increase in Emergency Diesel Generator Day Tank Minimum Fuel Volume
ML0817802542008-08-0505 August 2008
Technical Specifications, Limerick Unit 1, Amendment 192, License NPF-39
ML0817802872008-08-0505 August 2008
Technical Specifications, Limerick Unit 2, Amendment 153, License NPF-85
ML0816305582008-06-11011 June 2008
Supplement to License Amendment Request Related to Proposed Changes to Emergency Diesel Generator Fuel Oil Requirements
2023-05-17
[Table view] |
Text
2.1 SAFETY LIMITS BASES
2.0 INTRODUCTION
The fuel cladding, reactor pressure vessel and primary system piping are the principle barriers to the release of radioactive materials to the environs.
Safety Limits are established to protect the integrity of these barriers during normal plant operations and anticipated transients. The fuel cladding integrity Safety Limit is set such that no fuel damage is calculated to occur if the limit is not violated. Because fuel damage is not directly observable, a step-back approach is used to establish a Safety Limit such that the MCPR is not less than 1.07 for two recirculation loop operation and 1.09 for single recirculation loop operation. MCPR greater than 1.07 for two recirculation loop operation and 1.09 for single recirculation loop operation represents a conservative margin relative to the conditions required to maintain fuel cladding integrity. The fuel cladding is one of the physical barriers which separate the radioactive materials from the environs. The integrity of this cladding barrier is related to its relative freedom from perforations or cracking. Although some corrosion or use related cracking may occur during the life of the cladding, fission product migration from this source is incrementally cumulative and continuously measurable. Fuel cladding perforations, however, can result from thermal stresses which occur from reactor operation significantly above design conditions and the Limiting Safety System Settings. While fission product migration from cladding perforation is just as measurable as that from use related cracking, the thermally caused cladding perforations signal a threshold beyond which still greater thermal stresses may cause gross rather than incremental cladding deterioration.
Therefore, the fuel cladding Safety Limit is defined with a margin to the conditions which would produce onset of transition boiling, MCPR of 1.0. These conditions represent a significant departure from the condition intended by design for planned operation.
2.1.1 THERMAL POWER, Low Pressure or Low Flow The use of the (GEXL) correlation is not valid for all critical power calculations at pressures below 785 psig or core flows less than 10% of rated flow. Therefore, the fuel cladding integrity Safety Limit is established by other means. This is done by establishing a limiting condition on core THERMAL POWER with the following basis. Since the pressure drop in the bypass region is essentially all elevation head, the core pressure drop at low power and flows will always be greater than 4.5 psi. Analyses show that with a bundle flow of 28 x 103 lb/hr, bundle pressure drop is nearly independent of bundle power and has a value of 3.5 psi. Thus, the bundle flow with a 4.5 psi driving head will be greater than 28 x 10 lb/hr. Full scale ATLAS test data taken at pressures from 14.7 psia to 800 psia indicate that the fuel assembly critical power at this flow is approximately 3.35 MWt. With the design peaking factors, this corresponds to a THERMAL POWER of more than 50% of RATED THERMAL POWER. Thus, a THERMAL POWER limit of 25% of RATED THERMAL POWER for reactor pressure below 785 psig is conservative.
LIMERICK -UNIT 2 B 2-1 Amendment No. 44, 8-3, 8-7-, 9;, 4-14, 127
2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS THERMAL POWER, Low Pressure or Low Flow with the reactor 2.1.1 THERMAL POWER shall not exceed 25% of RATED THERMAL POWER 10% of rated vessel steam dome pressure less than 785 psig or core flow less than flow.
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
the reactor vessel With THERMAL POWER 'exceeding 25% of RATED THERMAL POWER and flow, steam dome pressure less than 785 psig or core flow less than 10% of rated of 2 hours and comply with the requirements be in at least HOT SHUTDOWN within Specification 6.7.1.
THERMAL POWER. High Pressure and High Flow than 1.07 for two 2.1.2 The MINIMUM CRITICAL POWER RATIO (MCPR) shall not be less 1.09 for single recirculation loop operation and shall not be less than dome pressure greater recirculation loop operation with the reactor vessel steam than 785 psig and core flow greater than 10% of rated flow.
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
or less than 1.09 With MCPR less than 1.07 for two recirculation loop operation steam dome pressure for single recirculation loop operation and the reactor vessel greater than 10% of rated flow, be in at least greater than 785 psig and core flow of Specification HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and comply with the requirements 6.7.1.
REACTOR COOLANT SYSTEM PRESSURE the reactor vessel 2.1.3 The reactor coolant system pressure, as measured in steam dome, shall not exceed 1325 psig.
APPLICABILITY: OPERATION CONDITIONS 1, 2, 3, and 4.
ACTION:
reactor vessel steam With the reactor coolant system pressure, as measured in the with reactor coolant system dome, above 1325 psig, be in at least HOT SHUTDOWN comply with the pressure less than or equal to 1325 psig within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and requirements of Specification 6.7.1.
2-1 Amendment No. 44, 8-3, 8-7, 9;, 44-4, 127 LIMERICK - UNIT 2
