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Category:Technical Specifications
MONTHYEARML23192A8212023-08-14014 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
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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
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License Amendment Request to Revise Power Distribution Limits for Axial Flux Difference and Heat Flux Hot Channel Factor
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Revised License Condition- Salem-Hope Creek Cyber Security Plan Supplement Submittal
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Appendices a, B and C
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License Amendment Request - One Time On-Line Safety-Related Battery Replacement
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License Amendment, Revise the Definition of Fully Withdrawn for the Rod Cluster Control Assemblies
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License Amendment Request to Eliminate Unnecessary Reporting Requirements in the Operating License and the Administrative Controls Section of the Technical Specifications
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Technical Specifications, Issuance of Amendment No. 273 Refueling Operations - Decay Time
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Technical Specifications, Issuance of Amendment No. 289 Refueling Operations - Decay Time
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Tech Spec Pages for Amendment 288, Surveillance Requirements for Containment Building Penetrations
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Tech Spec Pages for Amendment 272, Surveillance Requirements for Containment Building Penetrations
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License Amendment Request (LAR) S08-03, Request for Change to Technical Specifications Refueling Operations - Containment Building Penetrations
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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
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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)
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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
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Technical Specifications Elimination of Requirements for Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process
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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
ML0708704672007-03-27027 March 2007
Technical Specifications, Issuance of Amendment Steam Generator Alternate Repair Criteria
2023-08-14
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(1) Maximum Power Level PSEG Nuclear LLC is authorized to operate the facility at a steady state reactor core power level not in excess of 3459 megawatts (one hundred percent of rated core power).
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 283, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Deleted Per Amendment 22, 11-20-79 (4) Less than Four Loop Operation PSEG Nuclear LLC shall not operate the reactor at power levels above P-7 (as defined in Table 3.3-1 of Specification 3.3.1.1 of Appendix A to this license) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation have been submitted by the licensees and approval for less than four loop operation at power levels above P-7 has been granted by the Commission by Amendment of this license.
(5) PSEG Nuclear LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report, and as approved in the NRC Safety Evaluation Report dated November 20, 1979, and in its supplements, subject to the following provision:
PSEG Nuclear LLC may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
Amendment No. 283
3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1.1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE.
APPLICABILITY: As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each reactor trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown .in Table 4.3-1.
4.3.1.1.2 The logic for the interlocks shall be demonstrated OPERABLE prior to each reactor startup unless performed during the preceding 92 days. The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.
4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be verified to be within its limit at least once per 18 months. Neutron detectors are exempt from response time testing. Each verification shall include at least one logic train such that both logic trains are verified at least once per 36 months and one channel per function such that all channels are verified at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the "Total No. of Channels" column of Table 3.3-1.
SALEM - UNIT 1 3/4 3-1 Amendment No.283
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INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.
APPLICABILITY: As shown in Table 3.3-3.
ACTION:
- a. With an ESFAS instrumentation channel trip setpoint less conserva-tive than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.
- b. With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.
SURVEILLANCE REQUIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-2.
4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test. The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.
4.3.2.1.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be verified to be within the limit at least once per 18 months. Each verification shall include at least one logic train such that both logic trains are verified at least once per 36 months and one channel per function such that all channels are verified at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the "TotalNo. of Channels" Column of Table 3.3-3. The provisions of Specification 4.0.4 are not applicable to MSIV closure time testing. The provisions of Specification 4.0.4 are not applicable to the turbine driven auxiliary feedwater pump provided the surveillance is performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the secondary steam generator pressure is greater than 680 psig.
SALEM - UNIT 1 3/4 3-14 Amendment No. 283
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