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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 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. 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(2) Technical Specifications and Environmental Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.266 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Special Low Power Test Program PSE&G shall complete the training portion of the Special Low Power Test Program in accordance with PSE&G's letter dated September 5, 1980 and in accordance with the Commission's Safety Evaluation Report "Special Low Power Test Program",
dated August 22, 1980 (See Amendment No. 2 to DPR-75 for the Salem Nuclear Generating Station, Unit No. 2) prior to operating the facility at a power level above five percent.
Within 31 days following completion of the power ascension testing program outlined in Chapter 13 of the Final Safety Analysis Report, PSE&G shall perform a boron mixing and cooldown test using decay heat and Natural Circulation. PSE&G shall submit the test procedure to the NRC for review and approval prior to performance of the test. The results of this test shall be submitted to the NRC prior to starting up following the first refueling outage.
(4) Initial Test Program PSE&G shall conduct the post-fuel-loading initial test program (set forth in Chapter 13 of the Final Safety Analysis Report, as amended) without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:
(a) Eliminatioxn of any test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential; (b) Modification of test objectives, methods or acceptance criteria for any test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential; (c) Performance of any test at a power level different by more than five percent of rated power from there described; and Amendment No. 266
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 for 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.2 3/4 3-1 Amendment No. 266
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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 conservative 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 for the MODES and at 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 "Total No. 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 2 3/4 3-14 Amendment No.266
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