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Category:Technical Specification
MONTHYEARML24278A3022024-10-0404 October 2024 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10 CFR 50.62 ATWS Rule to Support the Digital Modernization Project Installation - Rev Unit 2 Technical Spec ML24165A2642024-06-13013 June 2024 License Amendment Request for Proposed Changes to the Technical Specification Isolation Actuation Instrumentation Tables and New Turbine Enclosure Main Steam Line Tunnel Temperature TS 3/4.7.9 ML24106A1832024-04-15015 April 2024 Submittal of Changes to Technical Specifications Bases ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML23212B1052023-07-31031 July 2023 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the Digital Modernization Project Installation - Revise ML23103A3342023-04-13013 April 2023 Submittal of Changes to Technical Specifications Bases ML22105A0422022-04-13013 April 2022 Submittal of Changes to Technical Specifications Bases ML22055A6012022-02-24024 February 2022 License Amendment Request - Proposed Changes to Technical Specification 3.3.7.4, Remote Shutdown System Instrumentation and Controls ML21048A3242021-02-17017 February 2021 License Amendment Request for Application to Revise Technical Specifications to Adopt TSTF-205 -A Revision of Calibration, Channel Functional Test, and Related Definitions ML20273A2152020-09-29029 September 2020 License Amendment Request: Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability ML20111A1772020-04-13013 April 2020 Submittal of Changes to Technical Specifications Bases ML20078G3072020-03-18018 March 2020 License Amendment Request for Proposed Changes to Technical Specifications 3.10.8 Inservice Leak and Hydrostatic Testing JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls ML19106A1602019-04-12012 April 2019 Submittal of Changes to Technical Specifications Bases ML19036A9132019-02-28028 February 2019 Issuance of Amendment Nos. 234 and 197 Adopt TSTF-372, Revision 4, Addition of LCO 3.0.8, Inoperability of Snubbers ML18347B3662018-12-13013 December 2018 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b ML18235A1092018-08-23023 August 2018 Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers ML18108A1772018-04-13013 April 2018 Submittal of Changes to Technical Specifications Bases ML17109A0702017-04-13013 April 2017 Submittal of Changes to Technical Specifications Bases ML15323A2572015-11-19019 November 2015 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change ML15223B3232015-08-11011 August 2015 Submit License Amendment Request - Supplement Proposed Changes to the Technical Specifications to Address Secondary Containment Personnel Access Door Openings ML15119A5172015-04-14014 April 2015 Submittal of Changes to Technical Specifications Bases ML15043A6492015-02-12012 February 2015 Exigent License Amendment Request - Extension of Implementation Period for License Amendment No. 174, Leak Detection System Technical Specification Setpoint, Allowable Value and Design Basis Changes ML14112A4742014-04-10010 April 2014 Enclosure 2: Bases ML14112A4722014-04-10010 April 2014 Enclosure 1: Bases ML13119A5772013-04-10010 April 2013 Limerick Generating Station, Units 1 & 2, Submittal of Changes to Technical Specifications Bases ML12117A2242012-04-12012 April 2012 Limerick, Units 1 and 2, Submittal of Changes to Technical Specifications Bases 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 ML1116505632011-06-14014 June 2011 License Amendment Request to Include Alternate Method of Verifying Drywell Unidentified Leakage ML11126A2892011-04-15015 April 2011 Limerick Generating Station, Units 1 and 2, Regarding Submittal of Changes to Technical Specifications Bases ML1109700662011-04-0606 April 2011 License Amendment Request to Revise Operability Requirements and Actions for RCS Leakage Instrumentation ML1011706972010-04-22022 April 2010 Submittal of Changes to Technical Specifications Bases ML1011706982010-04-22022 April 2010 Submittal of Changes to Technical Specifications Bases ML1008503982010-03-25025 March 2010 Markup of Proposed Technical Requirements Manual & Technical Specifications Bases Pages ML0912800592009-04-17017 April 2009 Changes to Technical Specifications Bases, Including Changes Through 04/09/2009 ML0912800572009-04-17017 April 2009 Changes to Technical Specifications Bases, Including Changes Through 04/09/2009 ML0905703782009-02-25025 February 2009 License Amendment Request - Removal of Technical Specification 3/4.4.8 Concerning Structural Integrity Requirements ML0821207262008-08-27027 August 2008 Tech Spec Pages for Amendment 193 Increase in Emergency Diesel Generator Day Tank Minimum Fuel Volume RS-07-044, Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program2007-08-0808 August 2007 Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program ML0717802932007-06-27027 June 2007 License Amendment Request, Proposed Changes to Accident Monitoring Instrumentation Technical Specifications ML0713604212007-04-27027 April 2007 Changes to Technical Specifications Bases RS-07-020, Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-04-12012 April 2007 Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0606703282006-03-0606 March 2006 Tech Specification Pages for License Amendment 184 Removal of License Conditions Concerning Emergency Core Cooling System Pump Suction Strainers ML0605302142006-02-17017 February 2006 Technical Specification Pages Pressure Isolation Valve Table ML0532703942005-11-22022 November 2005 Technical Specification Pages Re Accident Monitoring Instrumentation Surveillance Requirements ML0533303552005-10-10010 October 2005 Supplement to the Request for License Amendment Related to Application of Alternative Source Term, Dated February 27, 2004 ML0527200192005-09-27027 September 2005 Issuance of Amendments Re Relocation of Operability and Surveillance Instrumentation, Technical Specifications 2024-06-13
[Table view] Category:Amendment
MONTHYEARML24278A3022024-10-0404 October 2024 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10 CFR 50.62 ATWS Rule to Support the Digital Modernization Project Installation - Rev Unit 2 Technical Spec ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML23212B1052023-07-31031 July 2023 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the Digital Modernization Project Installation - Revise ML22055A6012022-02-24024 February 2022 License Amendment Request - Proposed Changes to Technical Specification 3.3.7.4, Remote Shutdown System Instrumentation and Controls ML21048A3242021-02-17017 February 2021 License Amendment Request for Application to Revise Technical Specifications to Adopt TSTF-205 -A Revision of Calibration, Channel Functional Test, and Related Definitions JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability ML20078G3072020-03-18018 March 2020 License Amendment Request for Proposed Changes to Technical Specifications 3.10.8 Inservice Leak and Hydrostatic Testing RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls ML19036A9132019-02-28028 February 2019 Issuance of Amendment Nos. 234 and 197 Adopt TSTF-372, Revision 4, Addition of LCO 3.0.8, Inoperability of Snubbers ML18235A1092018-08-23023 August 2018 Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers ML15223B3232015-08-11011 August 2015 Submit License Amendment Request - Supplement Proposed Changes to the Technical Specifications to Address Secondary Containment Personnel Access Door Openings ML0905703782009-02-25025 February 2009 License Amendment Request - Removal of Technical Specification 3/4.4.8 Concerning Structural Integrity Requirements ML0821207262008-08-27027 August 2008 Tech Spec Pages for Amendment 193 Increase in Emergency Diesel Generator Day Tank Minimum Fuel Volume ML0717802932007-06-27027 June 2007 License Amendment Request, Proposed Changes to Accident Monitoring Instrumentation Technical Specifications ML0606703282006-03-0606 March 2006 Tech Specification Pages for License Amendment 184 Removal of License Conditions Concerning Emergency Core Cooling System Pump Suction Strainers ML0605302142006-02-17017 February 2006 Technical Specification Pages Pressure Isolation Valve Table ML0532703942005-11-22022 November 2005 Technical Specification Pages Re Accident Monitoring Instrumentation Surveillance Requirements ML0533303552005-10-10010 October 2005 Supplement to the Request for License Amendment Related to Application of Alternative Source Term, Dated February 27, 2004 ML0527200192005-09-27027 September 2005 Issuance of Amendments Re Relocation of Operability and Surveillance Instrumentation, Technical Specifications ML0510902392005-04-13013 April 2005 Tech Spec Pages for Amendment 173 and 135 Limiting Conditions for Operation and Surveillance Requirements ML0501805042005-01-18018 January 2005 Technical Specification Pages ML0434901662004-12-0303 December 2004 Supplement to the Request for License Amendment Related to Proposed Changes to Control Rod Requirements, Dated July 22, 2004 RS-04-125, Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program2004-11-29029 November 2004 Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program ML0415404572004-05-20020 May 2004 License Amendment Request, Activation of the Trip Outputs of the Oscillation Power Range Monitor Portion of the Power Range Neutron Monitoring System ML0411202312004-04-20020 April 2004 Technical Specification Pages for Limerick Generating Station, Units 1 and 2, License Amendment, Issuance of Amendment Generic Letter 88-01 Requirements ML0405603662004-02-13013 February 2004 Response to RAI Concerning Safety Limit Minimum Critical Power Ratio (SLMCPR) Change, License Amendment Request: AR A1443067 ML0326708342003-09-0808 September 2003 Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process ML0234505702002-11-27027 November 2002 Request for Technical Specifications Change to Eliminate Requirements for Post Accident Sampling System Using the Consolidated Line Item Improvement Process ML0208101822002-03-20020 March 2002 Technical Specification Pages, Limerick. Unit 1 & 2, Amendment Nos 158 & 120 (TAC Nos MB2271 & MB2272) ML0207204342002-03-12012 March 2002 Technical Specification Pages for Amendment 156, Limerick, Unit 1 2024-04-12
[Table view] |
Text
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 specified in Table 3.4.3.2-1.**
- f. 2 gpm increase in UNIDENTIFIED LEAKAGE over a 24-hour period.
APPLICABILLTY: 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 shown in Table 3.4.3.2-1 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 I 3/4 4-9 Amendment No. 2X8, 49, 172
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 CHEMISTRY The water chemistry limits of the reactor coolant system are established to prevent damage to the reactor materials in contact with the coolant. Chloride limits are specified to prevent stress corrosion cracking of the stainless steel. The effect of chloride is not as great when the oxygen concentration in the coolant is low, thus the 0.2 ppm limit on chlorides is permitted during POWER OPERATION. During shutdown and refueling operations, the temperature necessary for stress corrosion to occur is not present so a 0.5 ppm concentration of chlorides is not considered harmful during these periods.
LIMERICK - UNIT 1 B 3/4 4-3e Amendment No. 4-40, 172
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 specified in Table 3.4.3.2-1 .**
- 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 shown in Table 3.4.3.2-1 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. 14,134
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 CHEMISTRY The water chemistry limits of the reactor coolant system are established to prevent damage to the reactor materials in contact with the coolant. Chloride limits are specified to prevent stress corrosion cracking of the stainless steel.
The effect of chloride is not as great when the oxygen concentration in the coolant is low, thus the 0.2 ppm limit on chlorides is permitted during POWER OPERATION. During shutdown and refueling operations, the temperature necessary for stress corrosion to occur is not present so a 0.5 ppm concentration of chlorides is not considered harmful during these periods.
Conductivity measurements are required on a continuous basis since changes in this parameter are an indication of abnormal conditions. When the conductivity is within limits, the pH, chlorides and other impurities affecting conductivity must also be within their acceptable limits. With the conductivity meter inoperable, additional samples must be analyzed to ensure that the chlorides are not exceeding the limits.
The surveillance requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.
LIMERICK - UNIT 2 B 3/4 4-3e Amendment No. 1-03,134