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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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Text
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE Table 3.3.7.4-1 Remote Shutdown Monitoring Instrumentation .... .......... 3/4 3-75 Table 3.3.7.4-2 Remote Shutdown Systems Controls ........................ 3/4 3-77 Table 4.3.7.4-1 Remote Shutdown Monitoring Instrumentation Surveillance Requirements ............................... 3/4 3-82 Accident Monitoring Instrumentation ..... ................ 3/4 3-84 Table 3.3.7.5-1 Accident Monitoring Instrumentation ..................... 3/4 3-85 Table 4.3.7.5-1 Accident Monitoring Instrumentation Surveillance Requirements ............................... 3/4 3-87 Source Range Monitors ........ ........................... 3/4 3-88 I
3/4.3.8 DELETED ............................ ............... 3/4 3-103 3/4.3.9 FEEDWATER/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION .......... ............... 3/4 3-105 Table 3.3.9-1 Feedwater/Main Turbine Trip System Actuation Instrumentation .......... 3/4 3-106 .
HOPE CREEK ix Amendment No. 164
INDEX BASES SECTION PAGE INSTRUMENTATION (Continued)
Remote Shutdown Monitoring Instrumentation and Controls ............................................ B 3/4 3-5 Accident Monitoring Instrumentation ...................... B 3/4 3-5 Source Range Monitors .................................... B 3/4 3-5 3/4.3.8 DELETED .................................................. B 3/4 3-7 3/4.3.9 FEEDWATER/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION .......................................... B 3/4 3-7 Figure B3/4 3-1 Reactor Vessel Water Level .............. B 3/4 3-8 3/4.3.10 MECHANICAL VACUUM PUMP TRIP INSTRUMENTATION ........... B 3/4 3-9 3/4.3.11 OSCILLATION POWER RANGE MONITOR ........................... B 3/4 3-13 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM ..................................... B 3/4 4-1 3/4.4.2 SAFETY/RELIEF VALVES . B 3/4 4-2 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems . B 3/4 4-3 Operational Leakage . B 3/4 4-3 3/4.4.4 CHEMISTRY ...................... B 3/4 4-3 3/4.4.5 SPECIFIC ACTIVITY ...................... B 3/4 4-4 3/4.4.6 PRESSURE/TEMPERATURE LIMITS .............................. B 3/4 4-5 Table B3/4.4.6-1 Reactor Vessel Toughness ............... B 3/4 4-7 Figure B3/4.4.6-lFast Neutron Fluence (E>lMev) at (1/4)T as a Function of Service life ............... B 3/4 4-8 Table B3/4.4.6-2 Numeric Values for Pressure/Temperature Limits ............ B 3/4 4-9 HOPE CREEK xiii Amendment No. 164
TABLE 4.3.1.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH FUNCTIONAL UNIT CHECK TEST CALIBRATION SURVEILLANCE REQUIRED
- 8. Scram Discharge Volume Water Level - High
- a. Float Switch NA Q R 1, 2, 5 (i)
- b. Level Transmitter/Trip Unit S Q(k) R 1, 2, 5(i)
- 9. Turbine Stop Valve - Closure NA Q R 1
- 10. Turbine Control Valve Fast Closure Valve Trip System Oil Pressure - Low NA Q R 1
- 11. Reactor Mode Switch Shutdown Position NA R NA 1, 2, 3, 4, 5
- 12. Manual Scram NA W NA 1, 2, 3, 4, 5 (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(b) The IRM and SRM channels shall be determined to overlap for at least 1/2 decades during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for at least 1/2 decades during each controlled shutdown, if not performed within the previous 7 days.
(c) DELETED (d) This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated~by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER 2 25% of RATED THERMAL POWER. Adjust the APRM channel if the absolute difference is greater than 2% of RATED THERMAL POWER.
(e) This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow signal.
(f) The LPRMs shall be calibrated at least once per 1000 effective full power hours (EFPH).
(g) Verify measured core flow (total core flow) to be greater than or equal to established core flow at the existing recirculation loop flow (APRM % flow).
(h) This calibration shall consist of verifying the 6 +/- 0.6 second simulated thermal power time constant.
(i) This item intentionally blank (j) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
(k) Verify the tripset point of the trip unit at least once per 92 days.
(1) Not required to be performed when entering OPERATIONAL CONDITION 2 from OPERATIONAL CONDITION 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering OPERATIONAL CONDITION 2.
HOPE CREEK 3 /4 3 -8 Amendment No. 164
INSTRUMENTATION 3.3.7.7 DELETED HOPE CREEK 3 /4 3 -89 Amendment No.164
INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.7.2 DELETED 3/4.3.7.3 DELETED 3/4.3.7.4 REMOTE SHUTDOWN MONITORING INSTRUMENTATION AND CONTROLS The OPERABILITY of the remote shutdown monitoring instrumentation and controls ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident,n December 1980 and NUREG-0737, "Clarification of TMI Action Plan Requirements," November 1980.
3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown. At these power levels, reactivity additions shall not be made without this flux level information available to the operator. For a discussion of SPIRAL RELOAD and SPIRAL UNLOAD and the associated flux monitoring requirements, see Technical Specification Bases Section 3/4.9.2.
When the intermediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted.
3/4.3.7.7 DELETED HOPE CREEK B 3/4 3-5 Amendment No. 164
