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MONTHYEARML0610105602006-04-0707 April 2006 Issuance of Amendment Deletion of Requirement for Standby Liquid Control System During Refueling - Technical Specification Reactivity Control Systems Project stage: Approval ML0607304692006-04-0707 April 2006 Issuance of Amendment Deletion of Requirement for Standby Liquid Control System During Refueling Project stage: Approval 2006-04-07
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Category:Technical Specifications
MONTHYEARML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning 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 ML21050A0022021-03-12012 March 2021 Issuance of Amendment No. 227 Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-582, RPV WIC Enhancements ML21047A3132021-03-10010 March 2021 Issuance of Amendment No. 226 Revise Emergency Core Cooling System Technical Specification for High Pressure Coolant Injection System Inoperability (Non-Proprietary) ML20281A6132020-11-0909 November 2020 Issuance of Amendment No. 225 Revise Technical Specification Actions for Suppression Pool Cooling ML20231A6322020-09-29029 September 2020 Issuance of Amendment No. 224 Regarding Adoption of 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components of Nuclear Power Reactors 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 ML19186A2052019-08-0606 August 2019 Issuance of Amendment No. 217 Remote Shutdown System ML19065A1562019-03-27027 March 2019 Issuance of Amendment No. 215 Inverter Allowed Outage Time Extension ML17317A6052017-12-13013 December 2017 Issuance of Amendment, License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-535 ML17047A0202017-03-21021 March 2017 Issuance of Amendment to Delete Technical Specification Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves ML17053A1782017-03-15015 March 2017 Issuance of Amendment to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling ML16270A0382016-10-13013 October 2016 Issuance of Amendment No. 200 Safety Limit Minimum Critical Power Ratio Change ML15286A0912015-11-30030 November 2015 Issuance of Amendment Adoption of Technical Specifications Task Force Traveler-522 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 ML14108A3992014-12-18018 December 2014 Issuance of Amendment Request to Relocate Flood Protection Technical Specification to the Technical Requirements Manual LR-N14-0189, License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process2014-11-25025 November 2014 License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process ML14108A3122014-07-29029 July 2014 Issuance of Amendment Request to Relocate Safety Relief Valve Position Instrumentation to Technical Requirements Manual LR-N13-0155, License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual2013-09-0505 September 2013 License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual LR-N13-0143, License Amendment Request to Relocate Safety/Relief Valve Position Instrumentation to the Technical Requirements Manual2013-07-30030 July 2013 License Amendment Request to Relocate Safety/Relief Valve Position Instrumentation to the Technical Requirements Manual LR-N12-0067, License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items2012-03-0101 March 2012 License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items LR-N12-0028, Supplement to Application for Tech Spec Change TSTF-477 Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Tech Specs Using Consolidated Line Item Improvement Process2012-01-26026 January 2012 Supplement to Application for Tech Spec Change TSTF-477 Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Tech Specs Using Consolidated Line Item Improvement Process ML0527202982011-07-20020 July 2011 Current Facility Operating License NPF-57, Tech Specs, Revised 12/18/2017 ML11116A1482011-07-20020 July 2011 Issuance of Renewed Facility Operating License No. NPF-57 for Hope Creek Generating Station 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 ML1109801512011-04-19019 April 2011 Correction to Amendment No. 187 Regarding Relocation of Specific Surveillance Frequencies to a Licensee-Controlled Program Based on Technical Specification Task Force (TSTF) Change TSTF-425 LR-N11-0098, Format and Editorial Corrections to Technical Specification Pages Issued with Amendment 1872011-04-0404 April 2011 Format and Editorial Corrections to Technical Specification Pages Issued with Amendment 187 LR-N11-0068, Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process2011-02-28028 February 2011 Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process LR-N10-0310, Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times.2010-08-19019 August 2010 Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times. ML1015907132010-07-21021 July 2010 Issuance of Amendment Control Rod Notch Testing Frequency LR-N10-0097, License Amendment Request: Emergency Diesel Generators a and B Allowed Outage Time Extension2010-03-29029 March 2010 License Amendment Request: Emergency Diesel Generators a and B Allowed Outage Time Extension LR-N10-0015, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2010-03-19019 March 2010 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML0932700232009-12-0808 December 2009 Issuance of Amendment Mode Change Limitations ML0934302422009-12-0101 December 2009 License Amendment Request to Adopt TSTF-460, Revision 0, Control Rod Scram Times. ML0916006832009-07-15015 July 2009 Issuance of Amendment Technical Specification Requirements Related to Snubbers 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 LR-N08-0150, Relief Request for Third Interval Inservice Inspection Program for Examinations and Tests of Snubbers and Associated License Amendment Request2008-07-30030 July 2008 Relief Request for Third Interval Inservice Inspection Program for Examinations and Tests of Snubbers and Associated License Amendment Request LR-N08-0071, License Amendment Request - Hydrogen Water Chemistry Low Power Restriction2008-04-25025 April 2008 License Amendment Request - Hydrogen Water Chemistry Low Power Restriction ML0734500402008-01-24024 January 2008 Tech Spec Pages for Amendment 173 Control Room Habitability LR-N08-0003, Supplement to License Amendment Request for Extended Power Uprate2008-01-16016 January 2008 Supplement to License Amendment Request for Extended Power Uprate ML0728500372007-10-16016 October 2007 Technical Specifications, Issuance of Amendment Removal of Turbine First Stage Pressure Values from Technical Specifications ML0724003042007-08-27027 August 2007 Tech Spec Pages for Amendment 171 Relocate Component Lists for Primary Containment Isolation Valves from Technical Specifications LR-N07-0215, Supplement to License Amendment Request for Extended Power Uprate2007-08-27027 August 2007 Supplement to License Amendment Request for Extended Power Uprate ML0724805722007-06-15015 June 2007 Gnf S-0000-0068-2643, Gnf Additional Information Regarding the Requested Changes to the Technical Specification Slmcpr. Hope Creek (KT1) Cycle 15 LR-N07-0061, Application to Revise Technical Specifications (LCR H07-01) Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-04-17017 April 2007 Application to Revise Technical Specifications (LCR H07-01) Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0630704822006-10-31031 October 2006 Tech Spec Pages for Amendment 170 Regarding Clarification of Requirements During Handling of Irradiated Fuel Core Alterations, and Operations with the Potential for Draining the Reactor Vessel ML0624101882006-08-28028 August 2006 Technical Specifications - Fuel Storage and Handling ML0621403972006-08-0101 August 2006 Technical Specifications, Issuance of Amendment Ultimate Heat Sink, MC8054 LR-N06-0259, Supplement to Request for License Amendment Ultimate Heat Sink2006-07-18018 July 2006 Supplement to Request for License Amendment Ultimate Heat Sink ML0610105472006-04-10010 April 2006 Technical Specifications Pages Re Relocation of the Component Identification from the Overcurrent Protective Device Lists in TS 3/4.8.4.1, Primary Containment Penetration Conductor Overcurrent Protective Devices, and TS 3/4.8.4.5 2024-01-16
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REACTIVITY CONTROL SYSTEMS 3/4.1 5 STANDBY LIOUID CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.1.5 The standby liquid control system consists of two redundant subsystems and shall be OPERABLE.APPLICABILITY:
OPERATIONAL CONDITIONS 1 and 2 ACTION: a. In OPERATIONAL CONDITION 1 or 2: 1. With one system subsystem inoperable, restore'the subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.2. With both system subsystems inoperable, restore at least one subsystem to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.SURVEILLANCE REQUIREMENTS I 4.1.5 The a.standby liquid control system shall be demonstrated OPERABLE: At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that: 1. The temperature of the sodium pentaborate solution in the storage tank is greater than or equal to 70 0 F.2. The available volume of sodium pentaborate solution is within the limits of Figure 3.1.5-1.3. The heat tracing circuit is OPERABLE by determining the temperature of the pump suction piping to be greater than or equal to 70 0 F.HOPE CREEK 3 /4 1-19 Amendment No. 166 TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION TRIP FUNCTION 3. MAIN STEAM LINE ISOLATION a. Reactor Vessel Water Level -Low Low Low, Level 1 b. Main Steam Line Radiation
-High, High c. Main Steam Line Pressure -Low d. Main Steam Line Flow -High e. Condenser Vacuum -Low f. Main Steam Line Tunnel Temperature
-High g. Manual Initiation VALVE ACTUA-TION GROUPS OPERATED BY SIGNAL Cd)1 2 (b)1 1 1 1 1, 2, 17 MINIMUM OPERABLE CHANNELS PER TRIP SYSTEM(a)2 2 2 2/line 2 2/line.2 APPLICABLE OPERATIONAL CONDITION 1, 2, 3 1, 2, 3##1 1, 2, 3 1, 2**, 3**1, 2, 3 1, 2, 3 ACTION 21 28 22 20 21 21 25 4. REACTOR WATER CLEANUP SYSTEM ISOLATION a. RWCU A Flow -High b. RWCU A Flow -High, Timer c. RWCU Area Temperature
-High d. RWCU Area Ventilation A Temperature-High
- e. SLCS Initiation
- f. Reactor Vessel Water Level -Low Low, Level 2 g. Manual Initiation HOPE CREEK 7 7 7 7 7 C(f)7 7 1/Valve Ce)1/Valve (e)6/Valve (e)C e)6/Valve 1/Valve (e)2/Valve (e)1/Valve (e)1, 2, 3 1, 2, 3 1, 2, 3 1, 2, 3 1, 2 1, 2, 3 1, 2, 3 23 23 23 23 23 23 25 I 3 /4 3 -12 Amendment No. 166 TABLE 3.3.2-1 (Continued)
NOTES* When handling recently irradiated fuel in the secondary containment and during operations with a potential for draining the reactor vessel.** When any turbine stop valve is greater than 90% open and/or when the key-locked bypass switch is in the Norm position.The hydrogen water chemistry (HWC) system shall not be placed in service until reactor power reaches 20% of RATED THERMAL POWER.After reaching 20% of RATED THERMAL POWER, and prior to operating the HWC system, the normal full power background radiation level and associated trip setpoints may be increased to levels previously measured during full power operation with hydrogen injection.
Prior to decreasing below 20% of RATED THERMAL POWER and after the HWC system has been shutoff, the background level and associated setpoint shall be returned to the normal full power values. If a power reduction event occurs so that the reactor power is below 20% of RATED THERMAL POWER without the required setpoint change, control rod motion shall be suspended (except for scram or other emergency actions) until the necessary setpoint adjustment is made.(a) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Eor required surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.(b) Also trips and isolates the mechanical vacuum pumps.(c) Also starts the Filtration, Recirculation and Ventilation System (FRVS).(d) Refer to Table 3.3.2-1 table notation for the listing of which valves in an actuation group are closed by a particular isolation signal.Refer to Tables 3.6.3-1 and 3.6.5.2-1 for the listings of all valves within an actuation group.(e) Sensors arranged per valve group, not per trip system.(f) Closes only RWCU system isolation valve(s) HV-FO01 and HV-F004.(g) Requires system steam supply pressure-low coincident with drywell pressure-high to close turbine exhaust vacuum breaker valves.(h) Manual isolation closes HV-F008 only, and only following manual or automatic initiation of the RCIC system.(i) Manual isolation closes HV-F003 and HV-F042 only, and only following manual or automatic initiation of the HPCI system.Cj) Trip functions common to RPS instrumentation.
HOPE CREEK 3/4 3-16a Amendment No. 166 TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL FUNCTIONAL CHECK TEST TRIP FUNCTION MAIN STEAM LINE ISOLATION (Continued)
- e. Condenser Vacuum -Low f. Main Steam Line Tunnel Temperature
-High g. Manual Initiation S NA NA Q Q Q (a)CHANNEL CALIBRATION R R NA OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE REQUIRED 1, 2**, 3**1, 2, 3 1, 2, 3 4. REACTOR WATER CLEANUP SYSTEM ISOLATION a. RWCU A Flow -High b. RWCU A Flow -High, Timer c. RWCU Area Temperature
-High d. RWCU Area Ventilation A Temperature
-High e. SLCS Initiation
- f. Reactor Vessel Water Level -Low Low, Level 2 g. Manual Initiation S NA NA NA NA S NA Q Q Q Q Q(b)Q Q (a)R R R R NA R NA 1, 2, 3 1, 2, 3 1, 2, 3 1, 2, 3 1, 2 I 1, 2, 3 1, 2, 3 5. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a. RCIC Steam Line A Pressure (Flow) -High b. RCIC Steam Line A Pressure (Flow) -High, Timer c. RCIC Steam Supply Pressure -Low d. RCIC Turbine Exhaust Diaphragm Pressure -High NA NA NA NA Q R Q R 1, 2, 3 1, 2, 3 1, 2, 3 1, 2, 3 Q R Q R HOPE CREEK 3 /4 3-29 Amendment No. 166 TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION (Continued)
- h. HPCI Torus Compartment Temperature
-High NA Q R 1, 2, 3 i. Drywell Pressure -High NA Q R 1, 2, 3 j. Manual Initiation NA R NA 1, 2, 3 7. RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION a. Reactor Vessel Water Level -Low, Level 3
- S Q R 1, 2, 3 b. Reactor Vessel (RHR Cut-in Permissive)
Pressure -High NA Q R 1, 2, 3 C. Manual Initiation NA Q(a) NA 1, 2, 3* When handling recently irradiated fuel in the secondary containment and during operations with a potential for draining the reactor vessel.** When any turbine stop valve is greater than 90% open and/or when the key-locked bypass switch is in the Norm position.(a) Manual initiation switches shall be tested at least once per 18 months. All other circuitry associated with manual initiation shall receive a CHANNEL FUNCTIONAL TEST at least once per 92 days as part of circuitry required to be tested for automatic system isolation.(b) Each train or logic channel shall be tested at least every other 92 days.HOP ,CREEK_.3 /4 3-31 Amendment No. 166 INSTRUMENTATION BASES 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY (continued)
OPERABLE to ensure that no single instrument failure can preclude the isolation function.The valve groups actuated by this Function are listed in Table 3.3.2-1.4.c, 4.d. RWCU Area Temperature and Area Ventilation Differential Temperature
-High RWCU area temperatures and area ventilation differential temperatures are provided to detect a leak from the RWCU System. The isolation occurs even when very small leaks have occurred and is diverse to the high differential flow instrumentation for the hot portions of the RWCU System.If the small leak continues without isolation, offsite dose limits may be reached. Credit for these instruments is not taken in any transient or accident analysis in the UFSAR, since bounding analyses are performed for large breaks such as recirculation or MSL breaks.Area temperature and area ventilation differential temperature signals are initiated from temperature elements that are located in the room that is being monitored.
Twelve ambient temperature sensor/monitors provide input to the RWCU Area Temperature
-High Function.
Twelve channels are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function.Twelve differential temperature sensor/monitors provide input to the RWCU Area Ventilation Differential Temperature
-High Function.
Twelve channels are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function.The valve groups actuated by this Function are listed in Table 3.3.2--l.4.e. SLC System Initiation The isolation of the RWCU System is required when the SLC System has been initiated to prevent dilution and removal of the boron solution by the!RWCU System. SLC System initiation signals are initiated from the two SLC pump start signals."wo channels (one from each pump) of the SLC System Initiation Function are available and are required to be OPERABLE only in OPERATIONAL CONDITIONS 1 and 2 (when the SLC system is required to be OPERABLE), since these OPERATIONAL CONDITIONS are consistent with the Applicability for the SLC System (TS 3.1.5).4.f. Reactor Vessel Water Level -Low Low, Level 2 Low RPV water level indicates that the capability to cool the fuel may be threatened.
Should RPV water level decrease too far, fuel damage could result. Therefore, isolation of some interfaces with the reactor vessel occurs to isolate the potential sources of a break. The isolation of the RWCU System on Level 2 supports actions to ensure that the fuel peak cladding temperature remains below the limits of 10 CFR 50.46. The Reactor Vessel Water Level -Low Low, Level 2 Function associated with RWCU isolation is nDt Hope Creek B 3/4 3-2k Amendment No. 166