Letter Sequence Approval |
---|
|
|
MONTHYEARML0318102952003-06-30030 June 2003 Environmental Assessment and Finding of No Significant Impact Technical Specifications Table 3.3-1, Reactor Trip System Instrumentation Project stage: Other ML0323701192003-10-0101 October 2003 Issuance of License Amendments Table 3.31, Reactor Trip System Instrumentation Project stage: Approval ML0327511302003-10-0101 October 2003 Technical Specification Pages for Salem Nuclear Generating Station, Units 1 and 2, Issuance of License Amendments Table 3.31, Reactor Trip System Instrumentation Project stage: Approval ML0330100252003-10-28028 October 2003 Correction to Amendment No. 259, Table 3.3-1, Reactor Trip System Instrumentation Project stage: Other 2003-10-28
[Table View] |
Similar Documents at Salem |
---|
Category:Technical Specifications
MONTHYEARML24145A1772024-07-15015 July 2024 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location LR-N22-0006, License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days2022-06-29029 June 2022 License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days ML21295A2292021-11-15015 November 2021 Issuance of Amendment Nos. 340 and 321 Revise Technical Specifications to Adopt TSTF 569, Revision of Response Time Testing Definitions ML20034E6172020-02-27027 February 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 222, 333, and 314 Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer ML19275D6942019-11-18018 November 2019 Issuance of Amendment Nos. 330 and 311 Revise Technical Specifications to Adopt TSFT-547, Clarification of Rod Position Requirements LR-N18-0129, License Amendment Request to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements.2019-02-0404 February 2019 License Amendment Request to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements. ML16096A4192016-04-28028 April 2016 Issuance of Amendments Replacement of Source Range and Intermediate Range Neutron Monitoring Systems ML16054A0682016-03-28028 March 2016 Issuance of Amendments Regarding Revision to Reactor Trip System Instrumentation Technical Specifications ML16035A0872016-03-0707 March 2016 Issuance of Amendments New Technical Specifications to Isolate Unborated Water Sources in Mode 6 LR-N16-0044, Emergency License Amendment Request to Modify Technical Specification Requirements for One Inoperable Subcooling Margin Monitor Channel2016-02-11011 February 2016 Emergency License Amendment Request to Modify Technical Specification Requirements for One Inoperable Subcooling Margin Monitor Channel LR-N15-0224, Response to Request for Additional Information License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors During Mode 6 (Refueling)2015-11-25025 November 2015 Response to Request for Additional Information License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors During Mode 6 (Refueling) LR-N15-0182, License Amendment Request to Correct a Non-Conservative Technical Specification Applicability Statement and Inconsistent Action Statements2015-10-12012 October 2015 License Amendment Request to Correct a Non-Conservative Technical Specification Applicability Statement and Inconsistent Action Statements ML15245A6362015-09-0404 September 2015 Issuance of Emergency Amendment Regarding Removal of Pressurizer Power Operated Relief Valve Position Indication Instrumentation from Technical Specifications ML15153A2302015-07-30030 July 2015 Issuance of Amendments Adopting Technical Specification Task Force (TSTF)-510, Rev, 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection(Tac Nos. MF4574 & MF457 ML15141A2712015-06-17017 June 2015 and Salem Nuclear Generating Station, Unit Nos.1 and 2, Issuance of Amendments Update of Appendix B to the Renewed Facility Operating Licenses ML15063A2932015-03-30030 March 2015 Issuance of Amendments Revision to Power Distribution Limits for Axial Flux Difference and Heat Flux Hot Channel Factor LR-N14-0074, License Amendment Request to Revise Power Distribution Limits for Axial Flux Difference and Heat Flux Hot Channel Factor2014-03-24024 March 2014 License Amendment Request to Revise Power Distribution Limits for Axial Flux Difference and Heat Flux Hot Channel Factor LR-N12-0183, License Amendment Request: Revision to Technical Specification (TS) 3.7.6.1 (Unit 1) and 3.7.6 (Unit 2) Control Room Emergency Air Conditioning System2012-07-17017 July 2012 License Amendment Request: Revision to Technical Specification (TS) 3.7.6.1 (Unit 1) and 3.7.6 (Unit 2) Control Room Emergency Air Conditioning System LR-N11-0208, Revised License Condition- Salem-Hope Creek Cyber Security Plan Supplement Submittal2011-07-0606 July 2011 Revised License Condition- Salem-Hope Creek Cyber Security Plan Supplement Submittal ML11175A2072011-06-30030 June 2011 Appendices a, B and C ML11136A0642011-06-30030 June 2011 Issuance of Renewed Facility Operating License Nos. DPR-70 and DPR-75 for Salem Nuclear Generating Station, Units 1 and 2 LR-N10-0363, License Amendment Request: Changes to Snubber Surveillance Requirements2010-10-0404 October 2010 License Amendment Request: Changes to Snubber Surveillance Requirements ML1020805012010-08-20020 August 2010 License Amendment, Issuance of Amendments Surveillance Requirements for Inservice Inspection and Inservice Testing LR-N10-0098, License Amendment Request - One Time On-Line Safety-Related Battery Replacement2010-03-29029 March 2010 License Amendment Request - One Time On-Line Safety-Related Battery Replacement ML1005704522010-03-29029 March 2010 Issuance of Amendment Steam Generator Inspection Scope and Repair Requirements ML0936308182010-01-12012 January 2010 License Amendment, Revise the Definition of Fully Withdrawn for the Rod Cluster Control Assemblies ML0929605842009-10-0808 October 2009 License Amendment Request, Revision to Technical Specification 6.8.4.i, Steam Generator Program, for One-Time (Interim) Alternate Repair Criteria (H*) LR-N09-0001, License Amendment Request to Eliminate Unnecessary Reporting Requirements in the Operating License and the Administrative Controls Section of the Technical Specifications2009-01-0505 January 2009 License Amendment Request to Eliminate Unnecessary Reporting Requirements in the Operating License and the Administrative Controls Section of the Technical Specifications ML0823409962008-09-24024 September 2008 Technical Specifications, Issuance of Amendment No. 273 Refueling Operations - Decay Time ML0823409752008-09-24024 September 2008 Technical Specifications, Issuance of Amendment No. 289 Refueling Operations - Decay Time ML0806700642008-03-13013 March 2008 Tech Spec Pages for Amendment 288, Surveillance Requirements for Containment Building Penetrations ML0806700822008-03-13013 March 2008 Tech Spec Pages for Amendment 272, Surveillance Requirements for Containment Building Penetrations LR-N08-0054, License Amendment Request (LAR) S08-03, Request for Change to Technical Specifications Refueling Operations - Containment Building Penetrations2008-03-0505 March 2008 License Amendment Request (LAR) S08-03, Request for Change to Technical Specifications Refueling Operations - Containment Building Penetrations ML0803204342008-03-0505 March 2008 Tech Spec Pages for Amendment 271 Re Refueling Operations - Decay Time ML0802204242008-02-27027 February 2008 Technical Specifications, Amendment. 270, License DPR-75, Steam Generator Feedwater Pump Trip, Feedwater Isolation Valve Response Time Testing and Containment Cooling System ML0802204142008-02-27027 February 2008 Technical Specifications to Amendment 287, License DPR-70, Steam Generator Feedwater Pump Trip, Feedwater Isolation Valve Response Time Testing and Containment Cooling System ML0734705152008-01-24024 January 2008 Amd 286/License DPR-75, Technical Specifications, Established More Effective & Appropriate Action, Surveillance & Administrative Requirements Re Ensuring the Habitability of the Control Room Envelop ML0734704082008-01-24024 January 2008 Amd 286/License DPR-70, Technical Specifications, Established More Effective & Appropriate Action, Surveillance & Administrative Requirements Re Ensuring the Habitability of the Control Room Envelop ML0717101192007-06-19019 June 2007 Technical Specifications for Amendment No. 266, Issuance of Amendments Relocation of Response Time Testing Limits (TAC Nos. MD2804 & MD2805) ML0717101212007-06-19019 June 2007 Technical Specifications for Amendment No. 283, Issuance of Amendments Relocation of Response Time Testing Limits (TAC Nos. MD2804 & MD2805) ML0715901892007-06-0606 June 2007 Units, 1 and 2, Tech Spec Pages for Amendment 282 Relocation of Technical Specification Requirements for the Movable Incore Detectors and Radioactive Gaseous Effluent Oxygen Monitoring Instrumentation ML0712202912007-05-10010 May 2007 Correction to Technical Specification Pages for Amendment Nos. 276 and 258 LR-N07-0103, Units 1 & 2, Correction to Technical Specification Pages/Amendment 276 and 2582007-05-0404 May 2007 Units 1 & 2, Correction to Technical Specification Pages/Amendment 276 and 258 ML0710906192007-04-19019 April 2007 Tech Spec Pages for Amendment 263 Accident Monitoring Instrumentation and Source Check Definition ML0710906332007-04-19019 April 2007 Tech Spec Pages for Amendment 280 Accident Monitoring Instrumentation and Source Check Definition ML0711503562007-04-19019 April 2007 Technical Specifications Elimination of Requirements for Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process ML0711503582007-04-19019 April 2007 Technical Specifications Elimination of Requirements for Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process LR-N07-0058, Application to Revise Technical Specifications (LCR S07-02) Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-04-15015 April 2007 Application to Revise Technical Specifications (LCR S07-02) Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0709203782007-03-29029 March 2007 Technical Specifications, Steam Generator Tube Integrity 2024-07-15
[Table view] |
Text
TABLE 3.3-1 (Continued)
ACTION 10 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT STANDBY in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.1.1.1, provided the other channel is OPERABLE.
ACTION 11 - With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 12 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.
ACTION 13 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status withiin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the reactor trip breakers within the next hour.
ACTION 14 - With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.
REACTOR TRIP SYSTEM INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-6 With 2 of 2 Intermediate Range P-6 prevents or defeats Neutron Flux Channels < 6x10-1 the manual block of source amps. range reactor trip.
P-7 With 2 of 4 Power Range Neutron P-7 prevents or defeats Flux Channels 2 11% of RATED the automatic block of THERMAL POWER or 1 of 2 Turbine reactor trip on: Low flow steam line inlet pressure channels in more than one primary
- a pressure equivalent to 11% of coolant loop, reactor RATED THERMAL POWER. coolant pump undervoltage and under-frequency, pressurizer low pressure, pressurizer high level, and the opening of more than one reactor coolant pump breaker.
SALEM - UNIT 1 3/4 3-7 Amendment No. 259
TABLE 3.3-1 (Continued)
ACTION 10 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT STANDBY in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.1.1.1 provided the other channel is OPERABLE.
ACTION 11 - With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 12 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.
ACTION 13 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the reactor trip breakers within the next hour.
ACTION 14 - With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.
REACTOR TRIP SYSTEM INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-6 With 2 of 2 Intermediate Range P-6 prevents or defeats Neutron Flux Channels < 6x10- 1 the manual block of source amps. range reactor trip.
P-7 With 2 of 4 Power Range Neutron P-7 prevents or defeats Flux Channels 2 11% of RATED the automatic block of THERMAL POWER or 1 of 2 Turbine reactor trip on: Low flow steam line inlet pressure channels in more than one primary
> a pressure equivalent to 11% of coolant loop, reactor RATED THERMAL POWER. coolant pump undervoltage and under-frequency, pressurizer low pressure, pressurizer high level, and the opening of more than one reactor coolant pump breaker.
SALEM - UNIT 2 3 /4 3-7 Amendment No. 240