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MONTHYEARML0511700122005-04-22022 April 2005 Tech Spec Pages for Amendments 172 & 158 Re the Deletion of Technical Specification Requirements to Maintain Hydrogen Recombiners and Hydrogen/Oxygen Monitors and Related Surveillance Requirements Project stage: Other ML0509605412005-04-22022 April 2005 Issuance of Amendments 172 & 158 Re the Deletion of Technical Specification Requirements to Maintain Hydrogen Recombiners and Hydrogen/Oxygen Monitors and Related Surveillance Requirements Project stage: Approval 2005-04-22
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Category:Technical Specifications
MONTHYEARML24018A0682024-02-0909 February 2024 Issuance of Amendment Nos. 262 and 247 Revised Design Bases of Lower Downcomer Braces RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs ML22332A4502022-11-10010 November 2022 Attachment 2 - Markup of Technical Specification Pages 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 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 ML21158A2282021-07-13013 July 2021 Issuance of Amendments to Renewed Facility Operating Licenses a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink ML21265A5362021-06-30030 June 2021 Attachment 2: LaSalle County Station Units 1 & 2 - Proposed Technical Specifications Markups ML21082A4222021-05-27027 May 2021 Issuance of Amendment Nos. 249 and 235 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems 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 RS-20-136, Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018)2020-10-29029 October 2020 Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018) RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems 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 RS-17-127, Submittal of Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-12-13013 December 2017 Submittal of Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. ML17257A3042017-10-30030 October 2017 Non-Proprietary - Issuance of Amendments Request to Revise Suppression Pool Swell Design Analysis and the Facility Licensing Basis ML16259A0592016-10-19019 October 2016 License Appendix a and B RS-16-035, County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings2016-02-0303 February 2016 County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings ML15324A4392015-12-17017 December 2015 Issuance of Amendments (CAC Nos. MF5471-MF5476) RS-15-279, Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls.2015-11-19019 November 2015 Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls. ML15202A5782015-11-19019 November 2015 Issuance of Amendment to Revise the Ultimate Heat Sink Temperature Limits ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML14323A5222015-04-0808 April 2015 Issuance of Amendments Regarding the Emergency Plan Definition of Annual Training ML14353A0832015-01-29029 January 2015 Issuance of Amendments Revising Peak Calculated Primary Containment Internal Pressure ML14220A5172014-11-25025 November 2014 Issuance of Amendment Revising Pressure and Temperature Limits ML14085A5322014-07-21021 July 2014 Issuance of Amendments Adoption of TSTF-522 Ventilation System Surveillance Requirements RS-13-092, License Amendment Request to Revise Peak Calculated Primary Containment Internal Pressure2013-09-0505 September 2013 License Amendment Request to Revise Peak Calculated Primary Containment Internal Pressure RS-13-137, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process2013-09-0303 September 2013 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process RS-11-149, Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limit2011-10-12012 October 2011 Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limit RS-11-036, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.2011-04-0404 April 2011 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation. RS-11-014, Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks2011-01-28028 January 2011 Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks ML1018303612010-09-16016 September 2010 License Amendment, Measurement Uncertainty Recapture Power Uprate RS-10-080, License Amendment Request Regarding Reactor Coolant System Pressure and Temperature Limit Curves2010-04-19019 April 2010 License Amendment Request Regarding Reactor Coolant System Pressure and Temperature Limit Curves RS-10-015, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.2010-02-22022 February 2010 Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System. RS-10-001, LaSalle, Units 1 and 2, Attachment 2 - Markup of Proposed Operating License and Technical Specifications Pages2010-01-27027 January 2010 LaSalle, Units 1 and 2, Attachment 2 - Markup of Proposed Operating License and Technical Specifications Pages ML1003213062010-01-27027 January 2010 Attachment 2 - Markup of Proposed Operating License and Technical Specifications Pages ML0927202312009-10-0202 October 2009 Correction Letter for License Amendment Nos. 195 and 182, Revise Local Power Range Monitor Calibration Frequency ML0924504042009-09-0303 September 2009 Correction Letter for License Amendment Nos. 193 and 180 Obsolete License Conditions and Revise Technical Specifications RS-09-110, Additional Information Supporting Request for License Amendment to Delete Obsolete License Conditions and Revise Technical Specifications2009-08-11011 August 2009 Additional Information Supporting Request for License Amendment to Delete Obsolete License Conditions and Revise Technical Specifications RS-09-020, Request for a License Amendment to Technical Specification 3.5.1, Emergency Core Cooling Systems (ECCS) Operating.2009-03-26026 March 2009 Request for a License Amendment to Technical Specification 3.5.1, Emergency Core Cooling Systems (ECCS) Operating. ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses ML0821301362008-07-25025 July 2008 Braidwood/Byron/Clinton/Dresden/Lasalle/Oyster Creek/Peach Bottom/Quad Cities/Three Mile Island - Tech Spec Pages for Amds to Change TS Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators RS-08-091, Request for a License Amendment to Revise Local Power Range Monitor Calibration Frequency2008-07-25025 July 2008 Request for a License Amendment to Revise Local Power Range Monitor Calibration Frequency RA-08-024, Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours.2008-04-21021 April 2008 Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours. ML0807303512008-03-10010 March 2008 Tech. Spec. Pages, Issuance of Amendments Revise TS 3.7.5 RS-08-012, Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications2008-02-28028 February 2008 Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications ML0733310942007-11-19019 November 2007 Tech Specs for Amendments to Provide Consistency with Quality Assurance Topical Report ML0731003892007-10-31031 October 2007 Technical Specifications, Changes Resulting from the Incorporation of TSTF-448, Control Room Habitability. ML0728907472007-10-12012 October 2007 Technical Specifications, Revise Technical Specifications, Section 5.5.7, Inservice Testing Program. 2024-02-09
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Text
PAM Instrumentation 3.3.3.1 SURVEILLANCE REQUIREMENTS
NOTES -----------------------------------
- 1. These SRs apply to each Function in Table 3.3.3.1-1. I
- 2. When a-channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the other required channel in the associated Function is OPERABLE.
SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK. 31 days SR 3.3.3.1.2 (Deleted) I SR 3.3.3.1.3 Perform CHANNEL CALIBRATION. 24 months I Amendment No. 172 /158 LaSalle 1 and 2 3.3.3.1-3
PAM Instrumentation 3.3.3.1 Table 3.3.3.1-1 (page I of 1)
Post Accident Monitoring Instrumentation CONDITIONS REFERENCED REQUIRED FROM REQUIRED FUNCTION CHANNELS ACTION D.1
- 1. Reactor Steam Dome Pressure 2 E
- 2. Reactor Vessel Water Level
- a. Fuel Zone 2 E
- b. Wide Range 2 E
- 3. Suppression Pool Water Level 2 E
- 4. Drywell Pressure
- a. Narrow Range 2 E
- b. Wide Range 2 E
- 5. Primary Containment Gross Gacma Radiation 2 F
- 6. Penetration Flow Path PCIV Position 2 per penetration I flow path'alb,
- 7. (Deleted)
I
- 8. (Deleted)
I
- 9. Suppression Pool Water Temperature 2 E (a) Not required for Isolation valves whose associated penetration flow path Is Isolated by at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.
(b) Only one position indication chainnel is required for penetration flow paths with only one installed control room indication channel.
LaSalle 1 and 2 3.3.3. 1-4 Amendment No.172/158
3.6.3.1 3.6 CONTAINMENT SYSTEMS 3.6.3.1 (Deleted) I LaSalle I and 2 3.6.3.1-1 Amendment No. 172/158
AC Sources-Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE:
- a. Two qualified circuits between the offsite transmission network and the onsite Class IE AC Electric Power Distribution System;
- b. Three diesel generators MOGs); and
- c. The opposite unit's Division 2 DG capable of supporting the associated equipment required to be OPERABLE by LCO 3.6.4.3, "Standby Gas Treatment (SGT) System,"
LCO 3.7.4, "Control Room Area Filtration (CRAF) System,"
and LCO 3.7.5, "Control Room Area Ventilation Air Conditioning (AC) System."
APPLICABILITY: MODES 1, 2, and 3.
NOTES-------------------
- 1. Division 3 AC electrical power sources are not required to be OPERABLE when High Pressure Core Spray (HPCS)
System is inoperable.
- 2. The opposite unit's Division 2 DG in LCO 3.8.1.c is not required to be OPERABLE when the associated required equipment is inoperable.
LaSalle I and 2 3.8.1-1 Amendment Ho. / 172/158
Distribution Systems-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The following electrical power distribution subsystems shall be OPERABLE:
- a. Division 1 and Division 2 AC and 125 V DC distribution subsystems;
- b. Division 3 AC and 125 V DC distribution subsystems;
- c. Division 1 250 V DC distribution subsystem; and
- d. The portions of the opposite unit's Division 2 AC and 125 V DC electrical power distribution subsystems capable of supporting the equipment required to be OPERABLE by LCO 3.6.4.3, "Standby Gas Treatment (SGT) I System," LCO 3.7.4, "Control Room Area Filtration (CRAF)
System," LCO 3.7.5, 'Control Room Area Ventilation Air Conditioning (AC) System," and LCO 3.8.1, "AC Sources-Operating."
APPLICABILITY: MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or both Division 1 A.1 Restore Division 1 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 2 AC electrical and 2 AC electrical power distribution power distribution AND subsystems inoperable. subsystems to OPERABLE status. 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from discovery of failure to meet LCO 3.8.7.a (continued)
LaSalle I and 2 3.8.7-1 Amendment No. /172/158
Programs and Manuals 5.5 5.5 Programs and Manuals.
5.5.1 Offsite Dose Calculation Manual (ODCM) (continued)
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e.,
month and year) the change was implemented.
5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include the Low Pressure Core Spray, High Pressure Core Spray, Residual Heat Removal/Low Pressure Coolant Injection, Reactor Core Isolation Cooling, containment monitoring, Standby Gas Treatment, hydrogen recombiner and process sampling (until such time as a modification eliminates the hydrogen recombiner.and PASS penetrations as potential leakage paths). The program shall include the following:
- a. Preventive maintenance and periodic visual inspection requirements; and
- b. Integrated leak test requirements for each system at 24 month intervals.
The provisions of SR 3.0.2 are applicable to the 24 month Frequency for performing integrated system leak test activities.
5.5.3 Deleted.
(continued)
LaSalle 1 and 2 5.5-2 Amendment No0. /172/158