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Category:Technical Specification
MONTHYEARML23334A1822023-11-30030 November 2023 Biennial Report for the Defueled Safety Analysis Report Update, Technical Specification Bases Changes, 10 CFR 50.59 Evaluation Summary, and Regulatory Commitment Change Summary – November 2021 Through October 2023 ML19044A5742019-02-0808 February 2019 Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications ML18260A0852018-09-13013 September 2018 Technical Specifications Proposed Change - Permanently Defueled Technical Specifications ML17086A1622017-04-0909 April 2017 Correction to Technical Specification Page 5.0-11 ML14349A4952014-12-10010 December 2014 Proposed Change to Technical Specifications Concerning the Safety Limit Minimum Critical Power Ratio ML14003A0462013-12-12012 December 2013 FSAR Update Revision 29, Technical Specifications Bases Changes, 10 CFR 50.59(d) Report, and Regulatory Commitment Changes ML13323A5182013-11-14014 November 2013 Technical Specifications Proposed Change No. 306 Eliminate Certain ESF Requirements During Movement of Irradiated Fuel ML11326A1532011-11-0909 November 2011 FSAR Update Revision 28, Technical Specifications Bases Changes, 10 CFR 50.59(d) Report, and Commitment Changes ML1106103972011-02-18018 February 2011 Marked-up and Re-typed Technical Specification and Bases Pages for the Proposed License Amendment Related to Setpoint and Setpoint Tolerance Increases for Safety Relief Valves (SRV) and Spring Safety Valves (Ssv). ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions ML0734600622007-11-29029 November 2007 Request for License Amendment - Control Room Envelope Habitability (TSTF-7448, Revision 3) ML0701105012007-01-0404 January 2007 Technical Specification Revisions for Control Rod Operability Scram Insertion Times and Control Rod Accumulator Requirements ML0700404412006-12-27027 December 2006 License Amendment Request for Adoption of TSTF-484 Revision 0, Use TS 3.10.1 for Scram Time Testing Activities ML0530404502005-10-18018 October 2005 Technical Specifications Amendment Request for Single Control Withdrawal Allowances, TS 3/4.14 Special Operations. ML0517204062005-06-0202 June 2005 Technical Specifications Amendment Request to Revise Reactor Coolant System Leakage Detection System Instrumentation Requirements and Actions ML0515204682005-05-24024 May 2005 Request for Amendment to Technical Specification to Remove Main Steam Isolation Valve Twice Per Week Testing Surveillance Requirement ML0508205272005-03-22022 March 2005 Technical Specification Pages Re Reporting Requirements ML0426400262004-09-0202 September 2004 License Amendment Request, Technical Specification Changes for Single Recirculation Loop Operation ML0421602262004-07-22022 July 2004 Deletion of Requirement from LCO 3/4.10.D, Multiple Control Rod Removal ML0411302792004-04-14014 April 2004 Request for Amendment to the Technical Specifications Reactor Vessel Hydrostatic and Leak Testing Requirements ML0400606222003-12-24024 December 2003 Application for Technical Specification (TS) Improvement to Delete the TS Requirements for the Hydrogen Analyzers Using the Consolidated Line Item Improvement Process ML0309905332003-03-27027 March 2003 Response to NRC Request for Additional Information Related to Technical Specification Changes to Post-Accident Monitoring Instrumentation Requirement ML0235200712002-12-10010 December 2002 Request for Amendment to the Technical Specifications (Ts), Jet Pump Operability Surveillance Requirements and Correction to Reference Cited in TS 4.11.C.1 ML0234402372002-12-0404 December 2002 Proposed Change to Applicability of Pilgrim'S Pressure-Temperature Curves as Described in Technical Specification Figures 3.6.1, 3.6.2, & 3.6.3, Revision 1 ML0233002762002-08-19019 August 2002 Request for Amendment to the Technical Specifications Changes to Post-Accident Monitoring Instrumentation Requirements ML0224000362002-08-19019 August 2002 Request for Amendment to the Technical Specifications Changes to Post-Accident Monitoring Instrumentation Requirements ML0219905242002-07-0505 July 2002 License Amendment Request, Appendix K Measurement Uncertainty Recovery - Power Uprate Request ML0207804112002-03-15015 March 2002 Enclosure -TS Pages and NRC Form 374 ML17037B7791974-02-0707 February 1974 Letter Regarding Petition for Derating of Certain Boiling Water Reactors and Enclosed Before the Atomic Safety and Licensing Appeal Board in the Matter of Vermont Yankee Nuclear Power Corporation - Vermont Yankee Nuclear ... 2023-11-30
[Table view] Category:Amendment
MONTHYEARML17086A1622017-04-0909 April 2017 Correction to Technical Specification Page 5.0-11 ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions ML0734600622007-11-29029 November 2007 Request for License Amendment - Control Room Envelope Habitability (TSTF-7448, Revision 3) ML0701105012007-01-0404 January 2007 Technical Specification Revisions for Control Rod Operability Scram Insertion Times and Control Rod Accumulator Requirements ML0700404412006-12-27027 December 2006 License Amendment Request for Adoption of TSTF-484 Revision 0, Use TS 3.10.1 for Scram Time Testing Activities ML0530404502005-10-18018 October 2005 Technical Specifications Amendment Request for Single Control Withdrawal Allowances, TS 3/4.14 Special Operations. ML0517204062005-06-0202 June 2005 Technical Specifications Amendment Request to Revise Reactor Coolant System Leakage Detection System Instrumentation Requirements and Actions ML0508205272005-03-22022 March 2005 Technical Specification Pages Re Reporting Requirements ML0426400262004-09-0202 September 2004 License Amendment Request, Technical Specification Changes for Single Recirculation Loop Operation ML0421602262004-07-22022 July 2004 Deletion of Requirement from LCO 3/4.10.D, Multiple Control Rod Removal ML0411302792004-04-14014 April 2004 Request for Amendment to the Technical Specifications Reactor Vessel Hydrostatic and Leak Testing Requirements ML0400606222003-12-24024 December 2003 Application for Technical Specification (TS) Improvement to Delete the TS Requirements for the Hydrogen Analyzers Using the Consolidated Line Item Improvement Process ML0235200712002-12-10010 December 2002 Request for Amendment to the Technical Specifications (Ts), Jet Pump Operability Surveillance Requirements and Correction to Reference Cited in TS 4.11.C.1 ML0234402372002-12-0404 December 2002 Proposed Change to Applicability of Pilgrim'S Pressure-Temperature Curves as Described in Technical Specification Figures 3.6.1, 3.6.2, & 3.6.3, Revision 1 ML0233002762002-08-19019 August 2002 Request for Amendment to the Technical Specifications Changes to Post-Accident Monitoring Instrumentation Requirements ML0224000362002-08-19019 August 2002 Request for Amendment to the Technical Specifications Changes to Post-Accident Monitoring Instrumentation Requirements ML0219905242002-07-0505 July 2002 License Amendment Request, Appendix K Measurement Uncertainty Recovery - Power Uprate Request ML0207804112002-03-15015 March 2002 Enclosure -TS Pages and NRC Form 374 ML17037B7791974-02-0707 February 1974 Letter Regarding Petition for Derating of Certain Boiling Water Reactors and Enclosed Before the Atomic Safety and Licensing Appeal Board in the Matter of Vermont Yankee Nuclear Power Corporation - Vermont Yankee Nuclear ... 2017-04-09
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Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.
5.6.1 Not Used 5.6.2 Annual Radiolocical Environmental Onerating Renort The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses 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 the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.
The Annual Radiological Environmental Operating Report shall include a summary of the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.
(Continued)
PNPS 5.0-1 1 Amendment No. 487, 212
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 Radioactive Effluent Release Renort The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a by May 15th of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and process control procedures and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.
5.6.4 Not Used 5.6.5 Core Operating Limits Report (COLR)
- a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
- 1. Table 3.1.1 - APRM High Flux trip level setting
- 2. Table 3.2.C -APRM Upscale trip level setting
- 3. 3.11 .A - Average Planar Linear Heat Generation Rate (APLHGR)
- 4. 3.11.B - Linear Heat Generation Rate (LHGR)
- 5. 3.11.C -Minimum Critical Power Ratio (MCPR)
- 6. 3.11 .D - Power/Flow Relationship During Power Operation
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. NEDE-2401 1-P-A, "General Electric Standard Application for Reactor Fuel," (through the latest NRC approved amendment at the time the reload analyses are performed as specified in the COLR).
(Continued)
PNPS 5.0-1 2 Amendment No. 487, 4-94-, 212