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{{#ask: [[TS::TS-3.3.3]]
 |?Start date
 |?Site
 |?Title
 |?System
 |format=table
 |limit=50
 |offset=115
 |sort=
 |order=asc
 |mainlabel=
}}

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{
    "query_string": "[[TS::TS-3.3.3]]",
    "query_source": "SMWSQLStore",
    "query_time": "0.5643",
    "from_cache": false
}

	Start date	Site	Title	System
CPSES-200600635, License Amendment Request (LAR) 06-004 Revision to Technical Specification 5.0, Administrative Controls.	31 March 2006	Comanche Peak	License Amendment Request (LAR) 06-004 Revision to Technical Specification 5.0, Administrative Controls.	Steam Generator Reactor Coolant System Feedwater Service water Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Shutdown Cooling HVAC Residual Heat Removal Control Room Emergency Filtration System Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Rod Containment Spray
CPSES-200601056, Response to Request for Additional Information Related to License Amendment Request (LAR) 2004-010 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity	7 June 2006	Comanche Peak	Response to Request for Additional Information Related to License Amendment Request (LAR) 2004-010 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity	Steam Generator Reactor Coolant System Feedwater Service water Main Steam Isolation Valve Auxiliary Feedwater Residual Heat Removal Main Steam Safety Valve Emergency Core Cooling System Main Steam Line Main Condenser Containment Spray
DCL-02-079, Units, 1 and 2, License Amendment Request 02-04, Revision of Technical Specification 5.6.6 - Reactor Coolant System Pressure and Temperature Limits Report	31 July 2002	Diablo Canyon	Units, 1 and 2, License Amendment Request 02-04, Revision of Technical Specification 5.6.6 - Reactor Coolant System Pressure and Temperature Limits Report	Steam Generator Reactor Coolant System Feedwater Main Steam Isolation Valve Reactor Pressure Vessel Residual Heat Removal Main Steam Safety Valve Emergency Core Cooling System
DCL-03-049, 2002 Annual Radioactive Effluent Release Report	30 April 2003	Diablo Canyon	2002 Annual Radioactive Effluent Release Report	Steam Generator Main Condenser
DCL-03-069, License Amendment Request 03-09, Revision of TS 3.1.7, Rod Position Indication 3.2.1, Heat Flux Hot Channel Factor, 3.2.4, Quadrant Power Tilt Ratio, & 3.3.1, Reactor Trip System Instrumentation for Beacon Implementation	11 June 2003	Diablo Canyon	License Amendment Request 03-09, Revision of TS 3.1.7, Rod Position Indication 3.2.1, Heat Flux Hot Channel Factor, 3.2.4, Quadrant Power Tilt Ratio, & 3.3.1, Reactor Trip System Instrumentation for Beacon Implementation	Reactor Coolant System Reactor Protection System Control Rod
DCL-03-101, Response to NRC Request for Additional Information Regarding License Amendment Request 02-04, Revision of TS 5.6.6 - Reactor Coolant System Pressure & Temperature Limits Report	15 August 2003	Diablo Canyon	Response to NRC Request for Additional Information Regarding License Amendment Request 02-04, Revision of TS 5.6.6 - Reactor Coolant System Pressure & Temperature Limits Report	Reactor Coolant System
DCL-03-118, License Amendment Request 03-13 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process	26 September 2003	Diablo Canyon	License Amendment Request 03-13 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process	Steam Generator Reactor Coolant System Auxiliary Feedwater Residual Heat Removal Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Main Steam
DCL-03-173, License Amendment Request 03-19 for Revision to Technical Specifications 3.3.3, Post-Accident Monitoring (PAM) Instrumentation and 3.6.8, Hydrogen Recombiners	30 December 2003	Diablo Canyon	License Amendment Request 03-19 for Revision to Technical Specifications 3.3.3, Post-Accident Monitoring (PAM) Instrumentation and 3.6.8, Hydrogen Recombiners	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Main Steam Isolation Valve Auxiliary Feedwater Primary containment Residual Heat Removal Emergency Core Cooling System Decay Heat Removal Main Steam Line Containment Spray
DCL-04-046, CFR 50.59 Report of Changes. Tests, and Experiments for the Period January 1, 2002, Through December 31, 2003	23 April 2004	Diablo Canyon	CFR 50.59 Report of Changes. Tests, and Experiments for the Period January 1, 2002, Through December 31, 2003	Steam Generator Reactor Coolant System Reactor Protection System Emergency Response Data System Safety Parameter Display System Residual Heat Removal Emergency Core Cooling System Decay Heat Removal Control Rod
DCL-04-141, Response to 09/08/2004 Request for Additional Information Re License Amendment Request 03-18, Revision to Technical Specifications 5.5.9. 'Steam Generator (SG) Tube Surveillance Program.' & 5.6.10	28 December 2004	Diablo Canyon	Response to 09/08/2004 Request for Additional Information Re License Amendment Request 03-18, Revision to Technical Specifications 5.5.9. 'Steam Generator (SG) Tube Surveillance Program.' & 5.6.10	Steam Generator Reactor Coolant System Main Steam Isolation Valve Main Steam Line Main Steam
DCL-06-048, 2005 Annual Radioactive Effluent Release Report.	31 December 2005	Diablo Canyon	2005 Annual Radioactive Effluent Release Report.	Steam Generator
DCL-07-047, Annual Radioactive Effluent Release Report	27 April 2007	Diablo Canyon	Annual Radioactive Effluent Release Report	Steam Generator Main Condenser
DCL-08-034, Transmittal of 2007 Annual Radioactive Effluent Release Report	30 April 2008	Diablo Canyon	Transmittal of 2007 Annual Radioactive Effluent Release Report	Steam Generator Main Condenser
DCL-09-025, 2008 Annual Radioactive Effluent Release Report	24 April 2009	Diablo Canyon	2008 Annual Radioactive Effluent Release Report	Steam Generator HVAC Main Condenser
DCL-10-026, Technical Specification 5.6.8 PAM Instrumentation Report	23 March 2010	Diablo Canyon	Technical Specification 5.6.8 PAM Instrumentation Report	Reactor Coolant System
DCL-10-042, Annual Radioactive Effluent Release Report	28 April 2010	Diablo Canyon	Annual Radioactive Effluent Release Report	Steam Generator Reactor Protection System HVAC Emergency Core Cooling System Main Condenser
DCL-11-049, 2010 Annual Radioactive Effluent Release Report, in Accordance with 10 CFR 50.36a(a)(2) and Section 5.6.3	28 April 2011	Diablo Canyon	2010 Annual Radioactive Effluent Release Report, in Accordance with 10 CFR 50.36a(a)(2) and Section 5.6.3	Steam Generator Main Condenser
DCL-11-104, Attachment 1: List of Regulatory Commitments	26 October 2011	Diablo Canyon	Attachment 1: List of Regulatory Commitments	Reactor Coolant System
DCL-12-040, 2011 Annual Radioactive Effluent Release Report	30 April 2012	Diablo Canyon	2011 Annual Radioactive Effluent Release Report	Steam Generator Main Condenser Control Rod
DCL-13-042, Submittal of 2012 Annual Radioactive Effluent Release Report	30 April 2013	Diablo Canyon	Submittal of 2012 Annual Radioactive Effluent Release Report	Steam Generator Main Condenser Control Rod
DCL-13-043, Supplement to License Amendment Request 11-07. Process Protection System Replacement.	30 April 2013	Diablo Canyon	Supplement to License Amendment Request 11-07. Process Protection System Replacement.	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Main Turbine Residual Heat Removal Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Rod Main Steam Containment Spray
DCL-13-092, Technical Specification Bases, Revision 8	16 September 2013	Diablo Canyon	Technical Specification Bases, Revision 8	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Primary containment Main Turbine Shutdown Cooling HVAC Residual Heat Removal Fuel Pool Cooling and Cleanup Circulating Water System Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Main Condenser Control Rod Main Steam Containment Spray
DCL-14-036, Response to Request for Additional Information on License Amendment Request for Digital Process Protection System Replacement	30 April 2014	Diablo Canyon	Response to Request for Additional Information on License Amendment Request for Digital Process Protection System Replacement	Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Main Turbine Containment Spray
DCL-14-039, Annual Radioactive Effluent Release Report	30 April 2014	Diablo Canyon	Annual Radioactive Effluent Release Report	Steam Generator Main Condenser
DCL-15-053, 2014 Annual Radioactive Effluent Release Report	29 April 2015	Diablo Canyon	2014 Annual Radioactive Effluent Release Report	Steam Generator Main Steam Isolation Valve Main Condenser
DCL-15-059, Technical Specification Bases, Revision 9	5 May 2015	Diablo Canyon	Technical Specification Bases, Revision 9	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Primary containment Main Turbine Shutdown Cooling HVAC Residual Heat Removal Fuel Pool Cooling and Cleanup Circulating Water System Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Main Condenser Control Rod Main Steam Containment Spray
DCL-16-054, Annual Radioactive Effluent Release Report for 2015	27 April 2016	Diablo Canyon	Annual Radioactive Effluent Release Report for 2015	Steam Generator Main Condenser
DCL-16-126, Revision 10 to Technical Specification Bases	30 December 2016	Diablo Canyon	Revision 10 to Technical Specification Bases	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Primary containment Main Turbine Shutdown Cooling HVAC Residual Heat Removal Fuel Pool Cooling and Cleanup Circulating Water System Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Main Condenser Control Rod Main Steam Containment Spray
DCL-17-031, Transmittal of 2016 Annual Radioactive Effluent Release Report	26 April 2017	Diablo Canyon	Transmittal of 2016 Annual Radioactive Effluent Release Report	Steam Generator Main Condenser Control Rod
DCL-18-028, Submittal of 2017 Annual Radioactive Effluent Release Report	24 April 2018	Diablo Canyon	Submittal of 2017 Annual Radioactive Effluent Release Report	Steam Generator Main Condenser
DCL-18-070, Technical Specification Bases, Revision 11	11 September 2018	Diablo Canyon	Technical Specification Bases, Revision 11	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Primary containment Main Turbine Shutdown Cooling HVAC Residual Heat Removal Fuel Pool Cooling and Cleanup Circulating Water System Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Main Condenser Control Rod Main Steam Containment Spray
DCL-18-112, Technical Specification 5.6.8 PAM Instrumentation Report	20 December 2018	Diablo Canyon	Technical Specification 5.6.8 PAM Instrumentation Report
DCL-19-026, Annual Radioactive Effluent Release Report	23 April 2019	Diablo Canyon	Annual Radioactive Effluent Release Report	Steam Generator Main Condenser Control Rod
DCL-20-068, Response to NRC Request for Additional Information Regarding License Amendment Request 20-01, Exigent Request for Revision to Technical Specification 3.7.5, 'Auxiliary Feedwater System	16 August 2020	Diablo Canyon	Response to NRC Request for Additional Information Regarding License Amendment Request 20-01, Exigent Request for Revision to Technical Specification 3.7.5, 'Auxiliary Feedwater System	Steam Generator Reactor Coolant System Feedwater Emergency Diesel Generator Auxiliary Feedwater Residual Heat Removal Remote shutdown
DCL-20-076, Technical Specification Bases	10 September 2020	Diablo Canyon	Technical Specification Bases	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Primary containment Main Turbine Shutdown Cooling HVAC Residual Heat Removal Fuel Pool Cooling and Cleanup Circulating Water System Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Main Condenser Control Rod Main Steam Containment Spray
DCL-20-092, License Amendment Request 20-03, Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition	3 December 2020	Diablo Canyon	License Amendment Request 20-03, Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Primary containment Safety Parameter Display System Residual Heat Removal Fuel Pool Cooling and Cleanup Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Control Rod Main Steam Containment Spray
DCL-22-017, Submittal of 2021 Annual Radioactive Effluent Release Report	21 April 2022	Diablo Canyon	Submittal of 2021 Annual Radioactive Effluent Release Report	Steam Generator Main Condenser
DCL-23-025, 2022 Annual Radioactive Effluent Release Report	1 May 2023	Diablo Canyon	2022 Annual Radioactive Effluent Release Report	Steam Generator Main Condenser Control Rod
ENS 40842	25 June 2004 14:50:00	Seabrook	Plant Exceeded Lco Action Statement Limits
ENS 48590	13 December 2012 21:30:00	Nine Mile Point	Technical Specification Required Shutdown Due to Primary Containment System Declared Inoperable	Feedwater High Pressure Coolant Injection Primary containment Shutdown Cooling Reactor Pressure Vessel Emergency Core Cooling System
ENS 50396	24 August 2014 05:00:00	Point Beach	Technical Specification Required Shutdown Due to Post Accident Monitoring Instrumentation Out of Service
ENS 50492	24 September 2014 20:33:00	Prairie Island	Unit 1 Train B Rvlis and Iccm Inoperable Due to Data Errors
ENS 52218	2 September 2016 13:08:00	Wolf Creek	Technical Specification Required Shutdown	Reactor Coolant System
ET 08-0009, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program for Interim Alternate Repair Criteria	8 February 2008	Wolf Creek	Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program for Interim Alternate Repair Criteria	Steam Generator Reactor Coolant System Control Rod
ET 08-0038, Application to Revise Technical Specification 5.6.6., Reactor Coolant System (RCS) Pressure and Temperature Limits Report (Ptlr).	10 July 2008	Wolf Creek	Application to Revise Technical Specification 5.6.6., Reactor Coolant System (RCS) Pressure and Temperature Limits Report (Ptlr).	Steam Generator Reactor Coolant System Reactor Pressure Vessel
ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation.	14 August 2008	Wolf Creek	Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation.	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Auxiliary Feedwater Control Room Emergency Ventilation Remote shutdown Emergency Core Cooling System Containment Spray
ET 09-0016, Revision to Technical Specifications 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for a Permanent Alternate Repair Criterion	2 June 2009	Wolf Creek	Revision to Technical Specifications 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for a Permanent Alternate Repair Criterion	Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Control Room Emergency Ventilation Control Rod
ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)	27 April 2020	Wolf Creek	Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Main Turbine Shutdown Cooling Residual Heat Removal Control Room Emergency Ventilation Shield Building Remote shutdown Emergency Core Cooling System Decay Heat Removal Control Room Envelope Control Rod Containment Spray
HL-4561, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Allow Testing Planned at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt	7 June 1994	Hatch	Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Allow Testing Planned at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt	Feedwater Service water High Pressure Coolant Injection Emergency Diesel Generator Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Shutdown Cooling HVAC Reactor Pressure Vessel Core Spray Residual Heat Removal Reactor Water Cleanup Standby Gas Treatment System Circulating Water System Emergency Core Cooling System Decay Heat Removal Main Steam Line Safety Relief Valve Main Condenser Control Rod Main Steam Containment Spray Low Pressure Coolant Injection
IA-86-827, Final Response to FOIA Request for Documents.App a Documents Consisting of La Crosse & Big Rock Point Semiannual Effluent Repts & App B Documents Consisting of Encl Turkey Point & St Lucie SALP Repts Available in Pdr.W/O Stated Encls	16 December 1986	Saint Lucie Turkey Point La Crosse Big Rock Point 05000000	Final Response to FOIA Request for Documents.App a Documents Consisting of La Crosse & Big Rock Point Semiannual Effluent Repts & App B Documents Consisting of Encl Turkey Point & St Lucie SALP Repts Available in Pdr.W/O Stated Encls	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Main Transformer Main Turbine Shutdown Cooling Safety Parameter Display System Residual Heat Removal Decay Heat Removal Main Steam Line Control Rod Auxiliary Feed Water Main Steam Containment Spray

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