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| {{#Wiki_filter:*(DRN 04-1244, Am. 99)5.7-1AMENDMENT NO. 99 | | {{#Wiki_filter:*(DRN 04-1244, Am. 99)5.7-1AMENDMENT NO. 99 |
| ,110(DRN 04-1244, Am. 99) | | , 110(DRN 04-1244, Am. 99) |
| (DRN 04-1244, Am. 99)5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS5.7-1 The components identified in Table 5.7-1 are designed and shall be maintained within thecyclic or transient limits of Table 5.7-1.TABLE 5.7-1COMPONENT CYCLIC OR TRANSIENT LIMITSCOMPONENTCYCLIC ORDESIGN CYCLETRANSIENT LIMITOR TRANSIENTReactor Coolant System500 system heatup cycles andHeatup cycle500 cooldown cycles at ratesTcold from < 70°F to > 541°F;< 100°F / hr.cooldown cycleTcold from > 541°F to < 70°F.(DRN 06-1000, Am. 110) 200pressurizer heatup andHeatup cycle - Pressurizercooldown cycles at ratestemperature from | | (DRN 04-1244, Am. 99)5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS5.7-1 The components identified in Table 5.7-1 are designed and shall be maintained within thecyclic or transient limits of Table 5.7-1.TABLE 5.7-1COMPONENT CYCLIC OR TRANSIENT LIMITSCOMPONENTCYCLIC ORDESIGN CYCLETRANSIENT LIMITOR TRANSIENTReactor Coolant System500 system heatup cycles andHeatup cycle500 cooldown cycles at ratesTcold from < 70°F to > 541°F;< 100°F / hr.cooldown cycleTcold from > 541°F to < 70°F.(DRN 06-1000, Am. 110) 200pressurizer heatup andHeatup cycle - Pressurizercooldown cycles at ratestemperature from |
| < 200°F / hr.< 70 | | < 200°F / hr.< 70 |
Latest revision as of 05:33, 9 July 2018
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Category:Manual
MONTHYEARML23110A1122023-04-20020 April 2023
Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G
ML23018A2202023-01-18018 January 2023
Quality Assurance Program Manual Reduction in Commitment
ML22104A0782022-04-14014 April 2022
Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G
W3F1-2021-0035, Technical Requirements Manual Update2021-05-18018 May 2021
Technical Requirements Manual Update
W3F1-2017-0080, Submittal of Technical Requirements Manual Update2017-12-0606 December 2017
Submittal of Technical Requirements Manual Update
ML17341A6652017-12-0606 December 2017
Technical Requirements Manual Update to the NRC
ML17109A4872017-04-10010 April 2017
Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G
W3F1-2016-0040, Technical Requirements Manual Update to the NRC2016-06-0202 June 2016
Technical Requirements Manual Update to the NRC
ML16132A5102015-10-15015 October 2015
3 to EN-RW-102, Radioactive Shipping Procedure.
ML16132A5072015-08-27027 August 2015
to EN-RW-105, Process Control Program.
ML16132A5082015-04-0808 April 2015
to EN-RW-106, Integrated Transportation Security Plan.
ML16132A5062015-04-0202 April 2015
2 to EN-RW-104, Scaling Factors.
W3F1-2016-0038, UNT-005-014, Rev. 306, Offsite Dose Calculation Manual.2015-03-12012 March 2015
UNT-005-014, Rev. 306, Offsite Dose Calculation Manual.
W3F1-2015-0023, Technical Requirements Manual/Trm Revision 128/Trm34122015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/Trm3412
ML15086A1812015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/SEC2.0
ML15086A1822015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/SEC5.0
ML15086A1832015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/SEC6.0
ML15086A1862015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/Trm340
ML15086A1872015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/Trm341
ML15086A1892015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/Trm344
ML15086A2112015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/Trm3411
ML15086A2102015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/Trmintro
ML15086A2092015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/Trmindex
ML15086A2082015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/Trmbases
ML15086A2062015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/Trm349
ML15086A1882015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/Trm343
ML15086A2032015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/Trm346
ML15086A2042015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/Trm347
ML15086A2052015-03-10010 March 2015
Technical Requirements Manual/Trm Revision 128/Trm348
ENOC-13-00029, Planned Modification of the Entergy Quality Assurance Program Manual (EA-11-096)2013-11-0404 November 2013
Planned Modification of the Entergy Quality Assurance Program Manual (EA-11-096)
CNRO-2013-00007, Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2013-04-26026 April 2013
Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G
W3F1-2011-0018, License Amendment Request to Relocate Technical Specifications to the Technical Requirements Manual2011-11-21021 November 2011
License Amendment Request to Relocate Technical Specifications to the Technical Requirements Manual
W3F1-2011-0033, UNT-005-014, Rev. 302, Offsite Dose Calculation Manual.2011-02-14014 February 2011
UNT-005-014, Rev. 302, Offsite Dose Calculation Manual.
ML0904103222008-04-15015 April 2008
Entergy'S Quality Assurance Program Manual, Revision 18; Effective: April 15, 2008
ENOC-07-00020, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes, Revision 162007-06-15015 June 2007
Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes, Revision 16
CNRO-2005-00024, Entergy Quality Assurance Program Manual, Revision 122005-04-0606 April 2005
Entergy Quality Assurance Program Manual, Revision 12
ML0612303022004-10-20020 October 2004
Corp. Administrative Procedure AP 31A-100, Revision 5, Solid Radwaste Process Control Program.
ML0612303002004-09-29029 September 2004
Corp. Administrative Procedure AP 07B-003, Revision 5, Offsite Dose Calculation Manual.
ML0512504582004-09-0909 September 2004
Attachment 11.1, UNT-005-514, Offsite Dose Calculation Manual, Revision 7, Change 1 & 2
ML0612800752004-08-12012 August 2004
Amendment 92, Move Pressurizer Heat-up and Cooldown Limits to TRM and Remove Shutdown Requirements
ML0612800742004-07-27027 July 2004
Amendment 91, New TRM 3.0/4.0 Section, Remove Shutdown Requirments Form TRM
ML0312600022003-04-24024 April 2003
Issuance of Entergy Quality Assurance Program Manual (Qapm), Revision 8
2023-04-20
[Table view] |
Text
, 110(DRN 04-1244, Am. 99)
(DRN 04-1244, Am. 99)5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS5.7-1 The components identified in Table 5.7-1 are designed and shall be maintained within thecyclic or transient limits of Table 5.7-1.TABLE 5.7-1COMPONENT CYCLIC OR TRANSIENT LIMITSCOMPONENTCYCLIC ORDESIGN CYCLETRANSIENT LIMITOR TRANSIENTReactor Coolant System500 system heatup cycles andHeatup cycle500 cooldown cycles at ratesTcold from < 70°F to > 541°F;< 100°F / hr.cooldown cycleTcold from > 541°F to < 70°F.(DRN 06-1000, Am. 110) 200pressurizer heatup andHeatup cycle - Pressurizercooldown cycles at ratestemperature from
< 200°F / hr.< 70
°F to > 653
°F;cooldown cycle
> 653°F to < 70°F(DRN 06-1000, Am. 110)10 hydrostatic testing cycles.RCS pressurized to 3125 psiawith RCS temperature > 60°Fabove the most limiting components' NDTT value.200 leak testing cycles.RCS pressurized to 2250 psiawith RCS temperature greater than minimum for hydrostatictesting, but less than 400
°F.200 seismic stress cycles.Subjection to a seismic eventequal to the operating basis earthquake (OBE).480 cycles (any combination) ofTrip from 100% of RATEDreactor trip, turbine trip, orTHERMAL POWER; Turbinecomplete loss of forced reactortrip (total load rejection from coolant flow.100% of RATED THERMALPOWER followed by resulting reactor trip; simultaneous loss of all reactor coolant pumps at 100% of RATED THERMAL POWER.5 complete loss of secondaryLoss of secondary pressure frompressure cycles.either steam generator while inMODE 1, 2, or 3.
(DRN 04-1244, Am. 99)
