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MONTHYEARML0600504962006-01-11011 January 2006
License Amendment, Eliminate Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports
Project stage: Other
ML0601305642006-01-11011 January 2006
Technical Specifications Pages Re Elimination of Monthly Operating Repots and Annual Occupational Radiation Exposure Reports
Project stage: Other
2006-01-11
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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 ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY ....................................... 6-1 6.2 ORGANIZATION ......................................... 6-1 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS ................ 6-1 6.2.2 UNIT STAFF ...................................... 6-1 Figure 6.2.1-1 (Deleted)............................ 6-3 Figure 6.2.2-1 (Deleted)............................ 6-4 Table 6.2.2-1 Minimum Shift Crew Composition Single Unit Facility .................. 6-5 6.2.3 SHIFT TECHNICAL ADVISOR ......................... 6-6 6.3 UNIT STAFF QUALIFICATIONS ............... 6-6 6.4 TRAINING ........................ 6-6 6.5 REVIEW AND AUDIT (THIS SECTION DELETED) . ....... 6-6 6.6 REPORTABLE EVENT ACTION ................ 6-14 6.7 SAFETY LIMIT VIOLATION ................ 6-14 6.8 PROCEDURES AND PROGRAMS ................ 6-15 6.9 REPORTING REQUIREMENTS ................ 6-17 6.9.1 ROUTINE REPORTS .................................... 6-17 STARTUP REPORT ..................................... 6-17 ANNUAL REPORTS ..................................... 6-17 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT. 6-18 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ......... 6-19 CORE OPERATING LIMITS REPORT ....................... 6-20 6.9.2 SPECIAL REPORTS .................................... 6-21 HOPE CREEK xxciv Amendment No. 161
ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the USNRC Administrator, Region 1, unless otherwise noted.
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.
6.9.1.2 The startup report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the startup report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed.
ANNUAL REPORTS*
6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.
6.9.1.5 Reports required on an annual basis shall include:
- a. Deleted
- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
HOPE CREEK 6-17 Amendment No. 161
ADMINISTRATIVE CONTROLS
- b. Documentation of all challenges to main steamline safety/relief valves.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 The Annual Radiological Environmental Operating report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
HOPE CREEK 6-18 Amendment No. 161
ADMINISTRATIVE CONTROLS 6.9.1.8 Deleted l CORE OPERATING LIMITS REPORT 6.9.1.9 Core operating limits shall be established and documented in the PSEG Nuclear LLC generated CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following Technical Specifications:
3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 3/4.2.3 MINIMUM CRITICAL POWER RATIO 3/4.2.4 LINEAR HEAT GENERATION RATE 3/4.3.11 OSCILLATION POWER RANGE MONITOR (OPRM)
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by NRC as applicable in the following documents:
- 1. NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel (GESTAR-II)m
- 2. CENPD-397-P-A, "Improved Flow Measurement Accuracy Using Crossflow Ultrasonic Flow Measurement Technology"
- 3. NEDO-32465-A, Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, August 1996 The CORE OPERATING LIMITS REPORT will contain the complete identification for each of the TS referenced topical reports used to prepare the CORE OPERATING LIMITS REPORT (i.e., report number title, revision, date, and any supplements).
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
HOPE CREEK 6-20 Amendment No. 161
