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Category:Technical Specification
MONTHYEARRA-23-0121, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area2023-10-0505 October 2023 License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area ML23145A1602023-05-25025 May 2023 Submittal of Updated Final Safety Analysis Report (Revision No. 30), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 28), Technical Specifications Bases Revisions, Quality RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-22-0153, License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core.2022-09-21021 September 2022 License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core. RA-21-0183, Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer)2022-04-28028 April 2022 Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer) RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-22-0017, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-01-0606 January 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-21-0057, Independent Spent Fuel Storage Installation, Submittal of Updated Final Safety Analysis Report (Revision No. 29), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 27), Technical .2021-05-27027 May 2021 Independent Spent Fuel Storage Installation, Submittal of Updated Final Safety Analysis Report (Revision No. 29), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 27), Technical . RA-19-0183, License Amendment Request to Add New Feedwater Bypass Valves to Technical Specification 3.7.32019-07-29029 July 2019 License Amendment Request to Add New Feedwater Bypass Valves to Technical Specification 3.7.3 RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019 License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description RNP-RA/18-0044, Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transform2018-07-11011 July 2018 Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers RA-18-0001, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications ML18130A8072018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-17-0005, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2017-11-0707 November 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing RA-17-0022, Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses2017-10-19019 October 2017 Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017 Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. RNP-RA/17-0041, Transmittal of Technical Specifications Bases Revisions2017-05-23023 May 2017 Transmittal of Technical Specifications Bases Revisions RNP-RA/17-0034, Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)2017-05-0202 May 2017 Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) RA-16-0019, Duke Energy Progress - Application 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 Proces2016-09-27027 September 2016 Duke Energy Progress - Application 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 RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016 Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process ML16116A0332016-04-24024 April 2016 Application for Technical Specification Change to Adopt Technical Specifications Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2 RA-16-0005, Supplement to Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 52016-02-0101 February 2016 Supplement to Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5 RNP-RA/15-0083, Submits Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits2015-11-0202 November 2015 Submits Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits RNP-RA/15-0086, Transmittal of Technical Specifications Bases Revisions2015-10-0808 October 2015 Transmittal of Technical Specifications Bases Revisions RNP-RA/15-0077, Submittal of Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report, 14-Day Report for the Inoperability of Pressurizer Power Operated Relief Valves Position Indication2015-09-0101 September 2015 Submittal of Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report, 14-Day Report for the Inoperability of Pressurizer Power Operated Relief Valves Position Indication ML14188B0152014-06-20020 June 2014 Request for Technical Specifications (TS) Change Regarding Correction to TS 5.5.9.b.2, Steam Generator (SG) Program Accident-Induced Leakage Performance Criterion RNP-RA/14-0042, Transmittal of Technical Specifications Bases Revisions2014-04-29029 April 2014 Transmittal of Technical Specifications Bases Revisions RNP-RA/13-0077, License Amendment Request for Technical Specification(Ts) Change to Use NRC-Approved TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications2013-09-30030 September 2013 License Amendment Request for Technical Specification(Ts) Change to Use NRC-Approved TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications RNP-RA/13-0038, Replacement of Technical Specification Pages to Correct Typographical Errors in Request for TS Changes Regarding TS 3.1.4 Rod Group Alignment Limits and TS 3.1.7 Rod Position Indication2013-04-24024 April 2013 Replacement of Technical Specification Pages to Correct Typographical Errors in Request for TS Changes Regarding TS 3.1.4 Rod Group Alignment Limits and TS 3.1.7 Rod Position Indication RNP-RA/12-0066, Transmittal of Technical Specifications Bases Revisions2012-09-17017 September 2012 Transmittal of Technical Specifications Bases Revisions RNP-RA/12-0033, Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2012-08-0606 August 2012 Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process RNP-RA/11-0095, Request for Technical Specifications Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process2012-02-10010 February 2012 Request for Technical Specifications Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process RNP-RA/11-0002, Transmittal of Technical Specifications Bases Revisions2011-01-12012 January 2011 Transmittal of Technical Specifications Bases Revisions RNP-RA/10-0001, Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation2010-03-0505 March 2010 Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation ML0828301372008-10-0606 October 2008 License Amendment Request to Eliminate Work Hour Controls to Support Compliance with Revised 10 CFR 26 RNP-RA/08-0006, Request for Technical Specifications Changes Related to Control Room Habitability - Supplement2008-04-0101 April 2008 Request for Technical Specifications Changes Related to Control Room Habitability - Supplement RNP-RA/08-0016, Supplement to the Request for Administrative Changes to the Technical Specifications2008-02-0404 February 2008 Supplement to the Request for Administrative Changes to the Technical Specifications RNP-RA/07-0126, Request for Technical Specifications Change to Section 3.6.8 Isolation Valve Seal Water System2007-11-29029 November 2007 Request for Technical Specifications Change to Section 3.6.8 Isolation Valve Seal Water System RNP-RA/07-0073, Request for Administrative Changes to the Operating License and Technical Specifications2007-11-19019 November 2007 Request for Administrative Changes to the Operating License and Technical Specifications RNP-RA/07-0124, Request for Technical Specifications Change to Section 3.1.7 Rod Position Indication2007-11-15015 November 2007 Request for Technical Specifications Change to Section 3.1.7 Rod Position Indication RNP-RA/07-0108, Transmittal of Technical Specifications Bases Revisions2007-10-30030 October 2007 Transmittal of Technical Specifications Bases Revisions RNP-RA/07-0056, Request for Technical Specifications Changes Related to Control Room Habitability2007-07-17017 July 2007 Request for Technical Specifications Changes Related to Control Room Habitability RNP-RA/06-0095, Request for Technical Specifications Change to Section 3.3.3, Post Accident Monitoring2007-02-0202 February 2007 Request for Technical Specifications Change to Section 3.3.3, Post Accident Monitoring ML0702404832007-01-19019 January 2007 H. B. Robinson, Unit 2 - Resubmission of Request for Technical Specifications Change Regarding Steam Generator Alternate Repair Criteria ML0634104702006-11-29029 November 2006 Technical Specification Pages Re Core Operating Limit Report References, ML0628900812006-10-12012 October 2006 Submittal of H. B. Robinson, Unit 2 - Request for Technical Specifications Change Regarding Steam Generator Alternate Repair Criteria RNP-RA/06-0033, Transmittal of Technical Specifications Bases Revisions2006-04-0606 April 2006 Transmittal of Technical Specifications Bases Revisions RNP-RA/05-0107, Request for Technical Specifications Change to Section 3.8.1 for the Diesel Generator Automatic Trips Bypass2005-11-30030 November 2005 Request for Technical Specifications Change to Section 3.8.1 for the Diesel Generator Automatic Trips Bypass 2023-05-25
[Table view] Category:Amendment
MONTHYEARRA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0153, License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core.2022-09-21021 September 2022 License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core. RA-21-0183, Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer)2022-04-28028 April 2022 Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer) RA-19-0183, License Amendment Request to Add New Feedwater Bypass Valves to Technical Specification 3.7.32019-07-29029 July 2019 License Amendment Request to Add New Feedwater Bypass Valves to Technical Specification 3.7.3 RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019 License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description RNP-RA/18-0044, Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transform2018-07-11011 July 2018 Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers RA-18-0001, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications ML18130A8072018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-17-0005, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2017-11-0707 November 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing RA-17-0022, Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses2017-10-19019 October 2017 Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses RNP-RA/17-0034, Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)2017-05-0202 May 2017 Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) RNP-RA/15-0083, Submits Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits2015-11-0202 November 2015 Submits Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits RNP-RA/13-0077, License Amendment Request for Technical Specification(Ts) Change to Use NRC-Approved TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications2013-09-30030 September 2013 License Amendment Request for Technical Specification(Ts) Change to Use NRC-Approved TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications RNP-RA/12-0033, Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2012-08-0606 August 2012 Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process ML0828301372008-10-0606 October 2008 License Amendment Request to Eliminate Work Hour Controls to Support Compliance with Revised 10 CFR 26 RNP-RA/08-0006, Request for Technical Specifications Changes Related to Control Room Habitability - Supplement2008-04-0101 April 2008 Request for Technical Specifications Changes Related to Control Room Habitability - Supplement RNP-RA/08-0016, Supplement to the Request for Administrative Changes to the Technical Specifications2008-02-0404 February 2008 Supplement to the Request for Administrative Changes to the Technical Specifications RNP-RA/07-0126, Request for Technical Specifications Change to Section 3.6.8 Isolation Valve Seal Water System2007-11-29029 November 2007 Request for Technical Specifications Change to Section 3.6.8 Isolation Valve Seal Water System RNP-RA/07-0073, Request for Administrative Changes to the Operating License and Technical Specifications2007-11-19019 November 2007 Request for Administrative Changes to the Operating License and Technical Specifications RNP-RA/07-0124, Request for Technical Specifications Change to Section 3.1.7 Rod Position Indication2007-11-15015 November 2007 Request for Technical Specifications Change to Section 3.1.7 Rod Position Indication RNP-RA/07-0056, Request for Technical Specifications Changes Related to Control Room Habitability2007-07-17017 July 2007 Request for Technical Specifications Changes Related to Control Room Habitability RNP-RA/06-0095, Request for Technical Specifications Change to Section 3.3.3, Post Accident Monitoring2007-02-0202 February 2007 Request for Technical Specifications Change to Section 3.3.3, Post Accident Monitoring ML0634104702006-11-29029 November 2006 Technical Specification Pages Re Core Operating Limit Report References, ML0628900812006-10-12012 October 2006 Submittal of H. B. Robinson, Unit 2 - Request for Technical Specifications Change Regarding Steam Generator Alternate Repair Criteria RNP-RA/05-0107, Request for Technical Specifications Change to Section 3.8.1 for the Diesel Generator Automatic Trips Bypass2005-11-30030 November 2005 Request for Technical Specifications Change to Section 3.8.1 for the Diesel Generator Automatic Trips Bypass ML0522003672005-08-0202 August 2005 Technical Specification Pages Re Bases Control Program (Tac No. MC3636) ML0511102212005-04-19019 April 2005 Enclosure, Amendment No. 204 on TS Revisions to Eliminate Monthly Operating and Annual Occupational Radiation Exposure Report Requirements (Tac No. MC5129) RNP-RA/05-0005, Request for Technical Specifications Change to Section 3.8.4, DC Sources - Operating2005-02-14014 February 2005 Request for Technical Specifications Change to Section 3.8.4, DC Sources - Operating ML0405707022004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.3-20 Through 3.3-28 for Amendment 176 ML0405706622004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 1.3-1 Through 1.3-13 for Amendment 176 ML0405706652004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 1.1-1 Through 1.2-3 for Amendment 176 ML0405706702004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 1.4-1 Through 1.4-4 for Amendment 176 ML0405706752004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Operating License Effective Pages Through Technical Specifications Effictive Pages ML0405706832004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Table of Contents for Amendment 176 ML0405706872004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 2.0-1 Through 2.0-2 for Amendment 176 ML0405706912004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.0.1 Through 3.0.5 for Amendment 176 ML0405706942004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.1-1 Through 3.1-21 for Amendment 176 ML0405706962004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.2-1 Through 3.2-14 for Amendment 176 ML0405706992004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.3-1 Through 3.3-19 for Amendment 176 ML0407804992004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.6-1 Through 3.6-21 for Amendment 176 ML0407805072004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 5.0-1 Through 5.0-34 for Amendment 176 ML0407805052004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 4.0-1 for Amendment 176 Through 4.0-3 for Amendment 198 ML0407805042004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.9-1 Through 3.0-12 for Amendment 176 ML0407805022004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.8-1 for Amendment 176 Through 3.8-36 for Amendment 190 ML0407805002004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.7-1 Through 3.7-33 for Amendment 176 ML0405707052004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Techncial Specification Pages 3.3-29 Through 3.3-32 for Amendment 176 ML0407804962004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.5-1 Through 3.5-11 for Amendment 176 ML0407804942004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.4-1 Through 3.4-28 for Amendment 176 ML0407804912004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.4-29 Through 3.4-51 for Amendment 176 2023-02-16
[Table view] |
Text
RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 3.4 REACTORCOOLANTSYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:
- a. Pressurizer pressure > 2205 psig;
- b. RCS average temperature < 579.4"F; and C. RCS total flow rate > 97.3 x lo6 lbm/hr.
APPLICABILITY: MODE 1.
__-______--___--___--------- NOTE----------------------------
Pressurizer pressure limit does not apply during:
- a. THERMAL POWERramp > 5% RTP per minute: or
- b. THERMAL POWERstep > 10% RTP.
ACTIONS CONDITION REQUIRED ACTION COMPLETIONTIME I
A. One or more RCS DNB A.1 Restore RCS DNB 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> parameters not within parameter(s) to limits. within limit.
B. Required Action and B.l Be in MODE2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.
HBRSEP Unit No. 2 3.4-l Amendment No. 176
RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is = 2205 psig. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.4.1.2 Verify RCS average temperature is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
< 579.4OF.
SR 3.4.1.3 Verify RCS total flow rate is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
> 97.3 x lo6 lbm/hr.
SR 3.4.1.4 -------------------NOTE--------------------
Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after > 90% RTP.
Verify by precision heat balance that RCS 18 months total flow rate is > 97.3 x lo6 lbm/hr.
HBRSEP Unit No. 2 3.4-2 Amendment No. 176
RCS Minimum Temperature for Criticality 3.4.2 3.4 REACTORCOOLANTSYSTEM (RCS) 3.4.2 RCS Minimum Temperature for Criticality LCO 3.4.2 Each RCS loop average temperature (T,,,) shall be > 53O F.
APPLICABILITY: MODE 1, MODE2 with keff > 1.0.
ACTIONS CONDITION REQUIRED ACTION COMPLETIONTIME A. Tavg in one or more RCS A.1 Be in MODE2 with Keff 30 minutes loops not within < 1.0.
limit.
HBRSEP Unit No. 2 3.4-3 Amendment No. 176
RCS Minimum Temperature for Criticality SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS Tavg in each loop > 53O F. w- wwI NOTE------
Only required if low T alarm not reset and any RCS loop T
< 543"F 30 minutes thereafter HBRSEP Unit No. 2 3.4-4 Amendment No. 176
RCS P/T Limits 3.4.3 3.4 REACTORCOOLANTSYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cooldown rates shall be maintained within the limits specified in Figures 3.4.3-l and 3.4.3-2.
APPLICABILITY: At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETIONTIME A. ---------NOTE--------- A.1 Restore parameter(s) 30 minutes Required Action A.2 to within limits.
shall be completed whenever this AND Condition is entered.
-_-_________I-________ A.2 Determine RCS is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
- acceptable for Requirements of LCO continued operation.
not met in MODE 1, 2, 3, or 4.
B. Required Action and B.l Be in MODE3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A AND not met.
B.2 Be in MODE5 with RCS 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> pressure < 400 psig.
(continued)
HBRSEP Unit No. 2 3.4-5 Amendment No. 176
RCS P/T Limits 3.4.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETIONTIME C. ---------NOTE--------- c.1 Initiate action to Immediately Required Action C.2 restore parameter(s) shall be completed to within limits.
whenever this Condition is entered. AND c.2 Determine RCS is Prior to Requirements of LCO acceptable for entering MODE4 not met any time in continued operation.
other than MODE 1, 2, 3, or 4.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 -------------------NOTE--------------------
Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.
__-________-I_____-_I___________________---
Verify RCS pressure, RCS temperature, and 30 minutes RCS heatup and cooldown rates are within the limits specified in Figures 3.4.3-l and 3.4.3-2.
HBRSEP Unit No. 2 3.4-6 Amendment No. 176
RCS P/T Limits 3.4.3 INDlCA-IED TEMPERATURE CF)
Figure 3.4.3-l Reactor Coolant System Heatup Limits Applicable Up to 23.96 EFPY HBRSEP Unit No. 2 3.4-7 Amendment No. 196
RCS P/T Limits 3.4.3 so 100 1!xI2002!50soo3!50400450!mo INDICATED TEMPEFWURE CF)
Figure 3.4.3-2 Reactor Coolant System Cooldown Limitations Applicable Up to 23.96 EFPY HBRSEP Unit No. 2 3.4-8 Amendment No. 196
.---. _~ -_.- ---- -
RCS Loops-MODES 1 and 2 3.4.4 3.4 REACTORCOOLANTSYSTEM (RCS) 3.4.4 RCS Loops-MODES 1 and 2 LCO 3.4.4 Three RCS loops shall be OPERABLE and in operation.
APPLICABILITY: MODES1 and 2.
ACTIONS CONDITION REQUIRED ACTION COMPLETIONTIME A. Requirements of LCO A.1 Be in MODE3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> HBRSEP Unit No. 2 3.4-9 Amendment No. 176
RCS Loops-M;D;.;
3.4 REACTORCOOLANT SYSTEM(RCS) 3.4.5 RCS Loops-MODE 3 LCO 3.4.5 Two RCS loops shall be OPERABLE and two RCS loops shall be in operation.
OR Two RCS loops shall be OPERABLE and one RCS loop shall be in operation provided one of the following requirements is met:
- a. The Rod Control System is not capable of rod withdrawal:
or
- b. The reactor trip breakers are open; or C. The lift disconnect switches for all control rods not fully withdrawn are open; or
- d. SHUTDOWN MARGIN(SDM) is within the MODE3 limits for one RCS loop in operation as specified in the COLR.
___________ _____ _____ _______NOTE ______ __ _______ ___________- -
All reactor coolant pumps may be de-energized for 5 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in any 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided:
- a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDMof LCO 3.1.1;
- b. Core outlet temperature is maintained at least 10°F below saturation temperature; and
- 1. Rod Control System is not capable of rod withdrawal, QR
- 2. Reactor Trip Breakers are open.
- 3. Lift disconnect switches for all control rods not fully withdrawn are open, QR
- 4. SDM is within MODE3 limits for no RCS loops in operation as specified in the COLR.
HBRSEPUnit No. 2 3.4-10 AmendmentNo. 376.190
RCS Loops-M;D; ;
APPLICABILITY: MODE3.
CONDITION REQUIRED ACTION COMPLETION TIME A. One required RCS loop 1.1 Restore required RCS 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. loop to OPERABLE status.
B. Required Action and 3.1 Be in MODE4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not met.
C. Requirements of the C.l Satisfy the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> LCO not met for conditions of the reasons other than LCO.
Condition A or D.
D. Required Action C.l D.l De-energize all Immediately and associated CRDMs.
Completion Time not Met.
OR Suspend operations Immediately that would cause introduction into the Two required RCS loops RCS. coolant with inoperable. boron concentration less than required to meet SDMof LCO 3.1.1.
No RCS loop in operation.
D.3 Initiate action to Immediately restore one RCS loop to OPERABLE status and operation.
HBRSEPUnit No. 2 3.4-11 AmendmentNo. W6.190
RCS Loops-MODE 3 3.4.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE I FREQUENCY SR 3.4.5.1 Verify required RCS loops are in operation. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.4.5.2 Verify steam generator secondary side water 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> levels are 2 16% for required RCS loops.
SR 3.4.5.3 -----.-----------NOTE--------------------
Only required to be met if LCO 3.4.5.a is required to be met.
Verify the Rod Control System is not 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> capable of rod withdrawal.
SR 3.4.5.4 -------.---------NOTE--------------------
Only required to be met if LCO 3.4.5.b is required to be met.
Verify the reactor trip breakers are open. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.4.5.5 -----------------NOTE--------------------
Only required to be met if LCO 3.4.5.~ is required to be met.
Verify the lift disconnect switches for all 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> control rods not fully withdrawn are open.
(continued)
HBRSEP Unit No. 2 3.4-12 Amendment No. 176
RCS Loops-MODE 3 3.4.5 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.5.6 -----------------NOTE--------------------
Only required to be met if LCO 3.4.5.d is 1 required to be met.
______-_____-1--_-_1---------------------
I Verify SDM is within required limits 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> specified in the COLR.
SR 3.4.5.7 Verify correct breaker alignment and 7 days indicated power are available to the required pump that is not in operation.
HBRSEP Unit No. 2 3.4-13 Amendment No. 176
RCS Loops-M;DE4 ;
3.4 REACTOR COOLANTSYSTEM(RCS) 3.4.6 RCS Loops-MODE 4 LCO 3.4.6 Two loops or trains consisting of any combination of RCS loops and residual heat removal (RHR) trains shall be OPERABLE,and one loop or train shall be in operation.
______----_______-- _-____- _- NOTES _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
- 1. All reactor coolant pumps (RCPs) and RHRpumps may be de-energized for 5 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in any 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided:
- a. No operations are permitted that would cause introduction into the RCS. coolant with boron
- EnEr;tion less than required to meet the SDMof
- b. Core outlet temperature is maintained at least 10°F below saturation temperature; and C. Rod Control System is not capable of rod withdrawal.
- 2. No RCP shall be started unless there is a steam bubble in the pressurizer or the secondary side water temperature of each steam generator (SG) is < 50°F above each of the RCS cold leg temperatures.
APPLICABILITY: MODE4.
CONDITION A. One required loop or A.1 Initiate action to Immediately train inoperable. restore a second loop 100~
or train to OPERABLE' OPERABLE ANIl status.
C);;l;;;ired RCS loop (continued)
HBRSEPUnit No. 2 3.4-14 AmendmentNo. W6.190
RCS Loops-M;D; ;1 ACTIONS (continwd~
CONDITION REQUIRED ACTION COMPLETION TIME B. One required loop B.l Be in MODE5. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or train inoperable.
Cl;;l;;;ired RHRtrain C. Two required loops or c.1 Suspend operations Immediately trains inoperable. that would cause introduction into the 118 RCS, coolant with boron concentration Required loop or train less than required to not in operation. tnn;t3SyMIof Al!lR c.2 Initiate action to Immediately restore one loop or train to OPERABLE status and operation.
SR 3.4.6.1 Verify one RHRtrain or RCS loop is in operation.
SR 3.4.6.2 Verify SG secondary side water levels are 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2 16% for required RCS loops.
SR 3.4.6.3 Verify correct breaker alignment and 7 days indicated power are available to the required pump that is not in operation.
HBRSEPUnit No. 2 3.4-15 AmendmentNo. W6,190
RCS Loops-MODE 5, Loops F;lpy 3.4 REACTORCOOLANT SYSTEM(RCS) 3.4.7 RCS Loops-MODE 5, Loops Filled LCO 3.4.7 One residual heat removal (RHR) train shall be OPERABLE and in operation, and either:
- a. One additional RHRtrain shall be OPERABLE;or
- b. One OPERABLE steam generator (SG) with a secondary side water level of 2 16%.
___________________________ -NOTES- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
- 1. The RHRpump of the train in operation may be de-energized for < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in any 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided:
- a. No operations are permitted that would cause introduction into the RCS. coolant with boron concentration less than required to meet the SDMof LCO 3.1.1; and
- b. Core outlet temperature is maintained at least 10°F below saturation temperature.
- 2. One required RHRtrain may be inoperable and de-energized for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided that the other RHRtrain is OPERABLE.
- 3. No reactor coolant pump shall be started unless there is a steam bubble in the pressurizer or the secondary side water temperature of each SG is < 50°F above each of the RCS cold leg temperatures.
- 4. All RHRtrains may be removed from operation during planned heatup to MODE4 when at least one RCS loop is in operation.
APPLICABILITY: MODE5 with RCS loops filled.
HBRSEPUnit No. 2 3.4-16 AmendmentNo. V6.190
RCS Loops-MODE 5. Loops Filled 3.4.7 S
CONDITION REQUIRED ACTION COMPLETION TIME A. One RHRtrain A.1 Initiate action to Immediately inoperable. restore a second RHR train to OPERABLE status.
Required SG secondary side water level not within limits. A.2 Initiate action to Immediately restore required SG secondary side water level to within limits.
B. Required RHRtrains B.l Suspend operations Immediately inoperable. that would cause introduction into the QR RCS. coolant with boron concentration No RHRtrain in less than required to operation. ;n;t3S;MIof N!lD B.2 Initiate action to Immediately restore one RHRtrain to OPERABLE status and operation.
SR 3.4.7.1 Verify one RHRtrain is in operation.
SR 3.4.7.2 Verify SG secondary side water level is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2 16% in required SG.
(continued)
HBRSEPUnit No. 2 3.4-17 AmendmentNo. W6.190
RCS Loops-MODE 5, Loops Filled 3.4.7 n
SURVEILLANCE REQUIREMENTS (continued>
SURVEILLANCE FREQUENCY I
SR 3.4.7.3 Verify correct breaker alignment and 7 days indicated power are available to the required RHR pump that is not in operation.
HBRSEP Unit No. 2 3.4-18 Amendment No. 176
RCS Loops-MODE 5, Loops Not F;lpi 3.4 REACTOR COOLANT SYSTEM(RCS) 3.4.8 RCS Loops-MODE 5. Loops Not Filled LCO 3.4.8 Two residual heat removal (RHR) trains shall be OPERABLE and one RHRtrain shall be in operation.
______-_____________________ NOTES---------------------------
- 1. All RHR pumps may be de-energized for 5 15 minutes when switching from one train to another or to perform testing of the RHRloop supply valves provided:
- a. The core outlet temperature is maintained > 10°F below saturation temperature,
- b. No operations are permitted that would cause introduction into the RCS. coolant with boron concentration less than required to meet the SDMof LCO 3.1.1; and C. No draining operations to further reduce the RCS water volume are permitted.
- 2. One RHRtrain may be inoperable for 5 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided that the other RHRtrain is OPERABLE.
APPLICABILITY: MODE5 with RCS loops not filled.
A. One RHRtrain Initiate action to inoperable. restore RHRtrain to OPERABLE status.
(continued)
HBRSEPUnit No. 2 3.4-19 AmendmentNo. W6.190
RCS Loops-MODE 5. Loops Not F;lp; CONDITION REQUIRED ACTION COMPLETION TIME B. Required RHRtrains B.l Suspend operations Immediately inoperable. that would cause introduction into the OR RCS. coolant with boron concentration No RHRtrain in less than reauired to operation. meet SDMof '
LCO 3.1.1.
8.2 Initiate action to Immediately restore one RHRtrain to OPERABLE status and operation.
SURVEILLANCE SR 3.4.8.1 Verify one RHRtrain is in operation. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.4.8.2 Verify correct breaker alignment and 7 days indicated power are available to the required RHRpump that is not in operation.
HBRSEPUnit No. 2 3.4-20 AmendmentNo. 3%.190
Pressurizer 3.4.9 3.4 REACTORCOOLANTSYSTEM (RCS) 3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLEwith:
- a. Pressurizer water level < 63.3% in MODE 1:
- b. Pressurizer water level < 92% in MODES2 and 3: and C. Pressurizer heaters OPERABLEwith a capacity of > 125 kW and capable of being powered from an emergency power supply APPLICABILITY: MODES1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETIONTIME
- A. Pressurizer water A.1 Be in MODE3 with 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> level not within reactor trip breakers limit. open.
A.2 Be in MODE4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B. Capacity of required B.l Restore required 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> pressurizer heaters pressurizer heaters
< 125 kW. to OPERABLE status.
C. Required pressurizer c.1 Restore capability to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
heaters not capable of power the required being powered from an pressurizer heaters emergency power from an emergency supply power supply.
(continued)
HBRSEP Unit No. 2 3.4-21 Amendment No. 176
Pressurizer 3.4.9 CONDITION REQUIRED ACTION COMPLETIONTIME D. Required Action and D.l Be in MODE3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition B or AND C not met.
D.2 Be in MODE4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY I
SR 3.4.9.1 Verify pressurizer water level is within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> limits.
SR 3.4.9.2 Verify capacity of required pressurizer 18 months heaters is > 125 kW.
SR 3.4.9.3 Verify required pressurizer heaters are 18 months capable of being powered from an emergency power supply.
HBRSEP Unit No. 2 3.4-22 Amendment No. 176
Pressurizer Safety Valves 3.4.10 3.4 REACTORCOOLANTSYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.10 Three pressurizer safety valves shall be OPERABLEwith lift settings > 2410 psig and < 2560 psig.
APPLICABILITY: MODES1, 2, and 3.
---_____________-___-------- NOTE----------------------------
The lift settings are not required to be within the LCO limits during MODE3 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions.
This exception is allowed for 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> following entry into MODE3 provided a preliminary cold setting was made prior to heatup.
ACTIONS CONDITION REQUIRED ACTION COMPLETIONTIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable. OPERABLE status.
B. Required Action and B.l Be in MODE3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND OR B.2 Be in MODE4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Two or more pressurizer safety valves inoperable.
HBRSEP Unit No. 2 3.4-23 Amendment No. 176
Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is In accordance OPERABLE in accordance with the Inservice with the Testing Program. Following testing, lift Inservice settings shall be within f 1%. Testing Program HBRSEP Unit No. 2 3.4-24 Amendment No. 176
Pressurizer PORVs 3.4.11 3.4 REACTORCOOLANTSYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)
LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.
APPLICABILITY: MODES1, 2, and 3.
ACTIONS
__1--_____1____-_-_----- NoTESwmw- www- ms wmwwwwm- wmm_ m_ _ _ _ _ _ _ _ _ _ __ _
1Separate Condition entry is allowed for each PORV.
- 2. LCO 3.0.4 is not applicable.
CONDITION REQUIRED ACTION COMPLETIONTIME A. One or more PORVs A.1 Close and maintain 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
- inoperable and capable power to associated of being manually block valve.
cycled.
B. One PORV inoperable B.l Close associated 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and not capable of block valve.
being manually cycled.
AND B.2 Remove power from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated block valve.
AND B.3 Restore PORV to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.
(continued)
HBRSEP Unit No. 2 3.4-25 Amendment No. 176
Pressurizer PORVs 3.4.11 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETIONTIME C. One block valve c.1 Place associated PORV 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. in manual control.
AND c.2 Restore block valve 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to OPERABLE status.
D. Required Action and D.l Be in MODE3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A, AND B, or C not met.
D.2 Be in MODE4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> E. Two PORVs inoperable E.l Close associated 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and not capable of block valves.
being manually cycled.
AND E.2 Remove power from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated block valves.
E.3 Be in MODE3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND E.4 Be in MODE4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> F. Two block valves F.l Place associated 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. PORVs in manual control.
AND (continued)
HBRSEP Unit No. 2 3.4-26 Amendment No. 176
Pressurizer PORVs 3.4.11
- h ACTIONS CONDITION REQUIRED ACTION COMPLETIONTIME F. (continued) F.2 Restore one block 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> valve to OPERABLE status.
AND F.3 Restore remaining 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> block valve to OPERABLE status.
G. Required Action and G.l Be in MODE3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition F AND not met.
6.2 Be in MODE4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 -------------------NOTE--------------------
Not required to be met with block valve closed in accordance with the Required Action of Condition B or E.
_-__II______________-----------------------
Perform a complete cycle of each block 92 days valve.
(continued)
HBRSEP Unit No. 2 3.4-27 Amendment No. 176
Pressurizer PORVs 3.4.11 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.11.2 -------------------NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entry into MODE3.
Perform a complete cycle of each PORV. 18 months SR 3.4.11.3 Perform a complete cycle of each solenoid 18 months air control valve and check valve on the nitrogen accumulators in PORV control systems.
SR 3.4.11.4 Verify accumulators are capable of 18 months operating PORVs through a complete cycle.
HBRSEP Unit No. 2 3.4-28 Amendment No. 176