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| {{#Wiki_filter:-4-(1) Maximum Power Level Carolina Power & Light Company is authorized to operate the facility at reactor core power levels not in excess of 2900 megawatts thermal (100 percent rated core power) in accordance with the conditions specified herein.(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. , are hereby incorporated into this license.Carolina Power & Light Company shall operate the facility in accordance with te Technical Specifications and the Environmental Protection Plan.(3) Antitrust Conditions Carolina Power & Light Company shall comply with the antitrust conditions delineated in Appendix C to this license.(4) Initial Startup Test Program (Section 14)1 Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b)within one month of such change.(5) Steam Generator Tube Rupture (Section 15.6.3)Prior to startup following the first refueling outage, Carolina Power & Light Company shall submit for NRC review and receive approval of a steam generator tube rupture analysis, including the assumed operator actions, which demonstrates that the consequences if the design basis steam generator tube rupture event for the Shearon Harris Nuclear Power Plant are less than the acceptance criteria specified in the Standard Review Plan, NUREG-0800, at §15.6.3 Subparts 11(1) and (2) for calculated doses from radiological releases. | | {{#Wiki_filter: (1) Maximum Power Level Carolina Power & Light Company is authorized to operate the facility at reactor core power levels not in excess of 2900 megawatts thermal (100 percent rated core power) in accordance with the conditions specified herein. |
| In preparing their analysis Carolina Power & Light Company will not assume that operators will complete corrective actions within the first thirty minutes after a steam generator tube rupture.1 The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed. | | (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. , are hereby incorporated into this license. |
| Amendment No. 126 TABLE 2.2-1 (continued) | | Carolina Power & Light Company shall operate the facility in accordance with te Technical Specifications and the Environmental Protection Plan. |
| REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS TOTAL ALLOWANCE FUNCTIONAL UNIT (TA)SENSOR ERROR z (S)TRIP SETPOINT ALLOWABLE VALUE 89.5% of loop indicated flow 12. Reactor Coolant Flow-Low 13. Steam Generator Water Level Low-Low 14. Steam Generator Water Level -Low Coincident With Steam/Feedwater Flow Mismatch 15. Undervoltage | | (3) Antitrust Conditions Carolina Power & Light Company shall comply with the antitrust conditions delineated in Appendix C to this license. |
| -Reactor Coolant Pumps 16. Underfrequency
| | (4) Initial Startup Test Program (Section 14)1 Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change. |
| -Reactor Coolant Pumps 17. Turbine Trip a. LOw Fluid Oil Pressure b. Turbine Throttle Valve Closure 18. Safety Injection Input from ESF RTP = RATED THERMAL POWER 4.58 25.0 8.9 20.0 14.0 5.0 1.98 0.6 17.45 2.0 5.95 2.0> 90.5% of loop full indicated flow> 25.0% of narrow range instrument span> 25.0% of narrow range instrument span full 3.01 Note 6 40% of full flow at RTP**steam> 23.5% of narrow range instrument span> 24.05% of narrow range instrument span<43.1% of full steam flow at RTP**4920 volts 57.3 Hz 1.3 0.0 3.0 0.0 5148 volts 57.5 Hz N.A.N.A.N.A.N.A. N.A.N.A. N.A.N.A. N.A.1000 psig> 1% open 950 psig 1% open N.A.N.A.SHEARON HARRIS -UNIT 1 2-5 Amendment No.126 TABLE 3.3-4 (Continued)
| | (5) Steam Generator Tube Rupture (Section 15.6.3) |
| ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TOTAL ALLOWANCE (TA)SENSOR ERROR z (S)8.15 2.0 5.. Turbine Trip and Feedwater Isolation (Continued) | | Prior to startup following the first refueling outage, Carolina Power & Light Company shall submit for NRC review and receive approval of a steam generator tube rupture analysis, including the assumed operator actions, which demonstrates that the consequences if the design basis steam generator tube rupture event for the Shearon Harris Nuclear Power Plant are less than the acceptance criteria specified in the Standard Review Plan, NUREG-0800, at §15.6.3 Subparts 11(1) and (2) for calculated doses from radiological releases. In preparing their analysis Carolina Power & Light Company will not assume that operators will complete corrective actions within the first thirty minutes after a steam generator tube rupture. |
| : b. Steam Generator Water Level--High-High (P-14)22.0 TRIP SETPOINT78.0% of narrow range instrument span.ALLOWABLE VALUE 79.5% of narrow range instrument span.C. Safety Injection See Item 1. above for Allowable Values..Safety Injection Trip Setpoints and 6. Auxiliary Feedwater a. Manual Initiation | | 1The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed. |
| : b. Automatic Actuation Logic and Actuation Relays c. Steam Generator Water Level--Low-Low
| | Amendment No. 126 |
| : d. Safety InjectionStart Motor-Driven Pumps e. Loss-of-Offsite Power Start Motor-Driven Pumps and Turbine-Driven Pump f. Trip of All Main Feedwater Pumps Start Motor-Driven Pumps N.A.N.A.25.0 N.A. N.A. .N.A.N.A.N.A.N.A. N.A.17.45 2.0 N.A. 25.0% of narrow range instrument span. 23.5% of narrow range instrument span.See Item 1. above for Allowable Values.See Item 9. below for Allowable Values.all Safety Injection Trip Setpoints and all Loss-of-Offsite Trip Setpoint and N.A.N.A. N.A.N.A.N.A.SHEARON HARRIS -UNIT 1 3/4 3-32 Amendment No. 126}}
| | |
| | TABLE 2.2-1 (continued) |
| | REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS TOTAL SENSOR ALLOWANCE ERROR FUNCTIONAL UNIT (TA) z (S) TRIP SETPOINT ALLOWABLE VALUE |
| | : 12. Reactor Coolant Flow-Low 4.58 1.98 0.6 > 90.5% of loop full 89.5% of loop full indicated flow indicated flow |
| | : 13. Steam Generator Water 25.0 17.45 2.0 > 25.0% of narrow > 23.5% of narrow Level Low-Low range instrument span range instrument span |
| | : 14. Steam Generator Water 8.9 5.95 2.0 > 25.0% of narrow > 24.05% of narrow Level - Low range instrument span range instrument span Coincident With Steam/Feedwater Flow 20.0 3.01 Note 6 *40% of full steam <43.1% of full steam Mismatch flow at RTP** flow at RTP** |
| | : 15. Undervoltage - Reactor 14.0 1.3 0.0 5148 volts 4920 volts Coolant Pumps |
| | : 16. Underfrequency - Reactor 5.0 3.0 0.0 57.5 Hz 57.3 Hz Coolant Pumps |
| | : 17. Turbine Trip |
| | : a. LOw Fluid Oil Pressure N.A. N.A. N.A. 1000 psig 950 psig |
| | : b. Turbine Throttle Valve N.A. N.A. N.A. > 1% open 1% open Closure |
| | : 18. Safety Injection Input N.A. N.A. N.A. N.A. N.A. |
| | from ESF RTP = RATED THERMAL POWER SHEARON HARRIS - UNIT 1 2-5 Amendment No.126 |
| | |
| | TABLE 3.3-4 (Continued) |
| | ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS SENSOR TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE (TA) z (S) TRIP SETPOINT ALLOWABLE VALUE 5.. Turbine Trip and Feedwater Isolation (Continued) |
| | : b. Steam Generator Water 22.0 8.15 2.0 *78.0% of |
| | * 79.5% of narrow Level--High-High (P-14) narrow range range instrument instrument span. |
| | span. |
| | C. Safety Injection See Item 1. above for .Safety Injection Trip Setpoints and Allowable Values. |
| | : 6. Auxiliary Feedwater |
| | : a. Manual Initiation N.A. N.A. N.A. . N.A. N.A. |
| | : b. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A. |
| | and Actuation Relays |
| | : c. Steam Generator Water 25.0 17.45 2.0 Ž 25.0% of Ž 23.5% of narrow Level--Low-Low narrow range range instrument instrument span. |
| | span. |
| | : d. Safety InjectionStart See Item 1. above for all Safety Injection Trip Setpoints and Motor-Driven Pumps Allowable Values. |
| | : e. Loss-of-Offsite Power See Item 9. below for all Loss-of-Offsite Trip Setpoint and Start Motor-Driven Pumps and Allowable Values. |
| | Turbine-Driven Pump |
| | : f. Trip of All Main Feedwater N.A. N.A. N.A. N.A. N.A. |
| | Pumps Start Motor-Driven Pumps SHEARON HARRIS - UNIT 1 3/4 3-32 Amendment No. 126}} |
Letter Sequence Approval |
|---|
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|
MONTHYEARML0703206562007-02-0606 February 2007
Request for Additional Information Shearon Harris Nuclear Power Plant Unit 1 - Revision for Steam Generator Water Level Trip Setpoints
Project stage: RAI
ML0707501162007-02-23023 February 2007
RAI for Steam Generator Water Level Setpoint Review
Project stage: RAI
ML0724707482007-08-31031 August 2007
Technical Specification, Issuance of Amendment to Revise Steam Generator Water Level Trip Setpoint Values
Project stage: Approval
ML0719801592007-08-31031 August 2007
License Amendment, Issuance of Amendment to Revise Steam Generator Water Level Trip Setpoint Values
Project stage: Approval
2007-02-06
[Table View] |
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|---|
Category:Technical Specifications
MONTHYEARML23234A1702023-10-0303 October 2023
Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications
ML23195A0782023-08-29029 August 2023
Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1
ML22126A0082022-08-0909 August 2022
Issuance of Amendment No. 194 Revise Technical Specifications Related to Reactor Protection System Instrumentation P7
ML21316A2482022-01-19019 January 2022
Issuance of Amendment No. 188, Regarding Revision of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML21035A1322021-03-16016 March 2021
Issuance of Amendment No. 182 Regarding Technical Specifications Related to Accident Monitoring Instrumentation, and Refueling Operations Instrumentation
RA-20-0321, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Comple2020-11-11011 November 2020
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completi
ML20183A4082020-07-0909 July 2020
Correction to Amendment No. 177 Regarding Elimination of Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications
ML19225C0692019-09-19019 September 2019
Issuance of Amendment No. 175 Modify Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints
RA-18-0201, Corrected Technical Specification Page Regarding License Amendment Request to Self Perform Core Reload Design and Safety Analyses2018-10-15015 October 2018
Corrected Technical Specification Page Regarding License Amendment Request to Self Perform Core Reload Design and Safety Analyses
ML17324B1292017-12-0606 December 2017
Correction to License Amendment No. 127 Regarding Changes to the Inservice Inspection and Testing Requirements and Establishment of a TS Bases Control Program (CAC No. MD5802) - Corrected TS Pages
ML17324B0482017-12-0606 December 2017
Correction to License Amendment No. 127 Regarding Changes to the Inservice Inspection and Testing Requirements and Establishment of a Technical Specifications Bases Control Program
RA-17-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2017-07-18018 July 2017
Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules
ML17074A6722017-05-25025 May 2017
Issuance of Amendment Relocation of Explosion Gas Monitoring Program Technical Specifications
ML17066A3742017-04-26026 April 2017
Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049)
ML16155A1242016-07-25025 July 2016
Issuance of Amendment on Main Steam Safety Valve Lift Setting Tolerance, Nominal Reactor Trip Setpoint on Pressurizer Water Level, and Pressurizer Water Level Span in Technical Specifications
RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.2015-11-19019 November 2015
Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.
RA-15-0031, Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.2015-08-19019 August 2015
Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.
HNP-15-040, Transmittal of Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2015-08-18018 August 2015
Transmittal of Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
ML15163A0562015-06-30030 June 2015
Issuance of Amendment to Revised Technical Specifications Table 3.3-4, Engineered Safety Features Actuation System Instrumentation
ML15075A2122014-11-30030 November 2014
Attachment 8 - DPC-NE-2005 Appendix H Robinson Plant Specific Data
ML15075A2132014-11-30030 November 2014
Attachment 9 - DPC-NE-2005 Appendix I Harris Plant Specific Data
RA-15-000, Attachment 8 - DPC-NE-2005 Appendix H Robinson Plant Specific Data2014-11-30030 November 2014
Attachment 8 - DPC-NE-2005 Appendix H Robinson Plant Specific Data
ML12339A0672012-12-18018 December 2012
Issuance of License Amendments Regarding Cyber Security
HNP-12-116, License Amendment Request to Revise Technical Specification Table 3.3-4 Re Degraded Voltage Time Delay Values2012-11-29029 November 2012
License Amendment Request to Revise Technical Specification Table 3.3-4 Re Degraded Voltage Time Delay Values
HNP-12-098, Application for Technical Specification Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process2012-10-22022 October 2012
Application for Technical Specification Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process
HNP-12-040, Application for Revision to Technical Specification 5.3.1 and Core Operating Limits Report References for M5 Cladding Revised Technical Specification Pages2012-03-20020 March 2012
Application for Revision to Technical Specification 5.3.1 and Core Operating Limits Report References for M5 Cladding Revised Technical Specification Pages
ML12080A2172012-03-20020 March 2012
Application for Revision to Technical Specification 5.3.1 and Core Operating Limits Report References for M5 Cladding Revised Technical Specification Pages
HNP-11-067, License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis2011-08-22022 August 2011
License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis
HNP-11-053, Transmittal of Technical Specifications Bases Revisions2011-05-0505 May 2011
Transmittal of Technical Specifications Bases Revisions
ML1023707682010-08-16016 August 2010
Response to Second Request for Additional Information Regarding Amendment to Remove Credit for Boraflex in Boiling Water Reactor Spent Fuel Pool Storage Racks
ML0926402472009-10-14014 October 2009
Issuance of Amendment Regarding Lowering the Minimum Allowed Level of the Ultimate Heat Sink Main Reservoir
ML0923203862009-08-25025 August 2009
Correction to Operating License and Technical Specification Page Issued with Amendment No. 131 Issued on July 2, 2009
ML0923102232009-08-25025 August 2009
Correction to Operating License and Technical Specification Page Issued with Amendment No. 131 Issued on July 2, 2009
ML0923102862009-08-20020 August 2009
Letter & Technical Specifications - Corrections to Technical Specification Pages Issued with Amendment No. 128 Issued on January 29, 2009
HNP-08-075, Request for License Amendment Technical Specifications 5.6.1.3.a and 5.6.1.3.b - Incorporation of Updated Criticality Analyses to Reflect Removal of Credit for Boraflex in BWR Spent Fuel Pool Storage Racks2008-09-29029 September 2008
Request for License Amendment Technical Specifications 5.6.1.3.a and 5.6.1.3.b - Incorporation of Updated Criticality Analyses to Reflect Removal of Credit for Boraflex in BWR Spent Fuel Pool Storage Racks
ML0814301512008-06-12012 June 2008
Technical Specifications, Changes to the Inservice Inspection and Testing Requirements and Establishment of a Technical Specifications Bases Control Program
HNP-08-049, Request for License Amendment Technical Specification 3.7.5a2008-04-30030 April 2008
Request for License Amendment Technical Specification 3.7.5a
ML0726003592007-09-19019 September 2007
Technical Specification Page Correction Issued with Amendment No. 125 Issued on July 23, 2007
HNP-07-127, Correction to Technical Specification Page in Amendment 1252007-09-13013 September 2007
Correction to Technical Specification Page in Amendment 125
ML0724707482007-08-31031 August 2007
Technical Specification, Issuance of Amendment to Revise Steam Generator Water Level Trip Setpoint Values
HNP-07-005, Request for License Amendment to Relocate and Revise Technical Specifications Surveillance Requirement 4.0.52007-06-15015 June 2007
Request for License Amendment to Relocate and Revise Technical Specifications Surveillance Requirement 4.0.5
ML0622003982006-08-0202 August 2006
Request for License Amendment to Revise Values Associated with the Steam Generator Water Level Trip Setpoints
ML0622004022006-08-0202 August 2006
Request for License Amendment HNP Calculation HNP-I/INST-1010
HNP-06-060, License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-05-23023 May 2006
License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
ML0606803122006-03-0808 March 2006
Tech Spec Pages for Amendment 120 Regarding Temperature Limit for Dissolved Oxygen in Reactor Coolant System
HNP-05-143, Supplement to Request for License Amendment to Credit Soluble Boron for Fuel Storage Pools2005-12-22022 December 2005
Supplement to Request for License Amendment to Credit Soluble Boron for Fuel Storage Pools
HNP-05-002, Supplemental Information to the Proposed License Amendment Request to Technical Specification (TS) 6.8.4.k and TS Surveillance Requirement (SR) 4.6.1.6.12005-12-0909 December 2005
Supplemental Information to the Proposed License Amendment Request to Technical Specification (TS) 6.8.4.k and TS Surveillance Requirement (SR) 4.6.1.6.1
ML0525105022005-09-0101 September 2005
Request for License Amendment to Credit Soluble Boron for Fuel Storage Pools
ML0517401142005-06-21021 June 2005
TS for Shearon Harris, Units 1, Enclosure, Amd MC4794, Extend the Inspection Interval for Reactor Coolant Pump Flywheels
HNP-05-062, Request for License Amendment Technical Specifications (TS) 3/4.4.7 Temperature Limit for Reactor Coolant System Dissolved Oxygen2005-06-20020 June 2005
Request for License Amendment Technical Specifications (TS) 3/4.4.7 Temperature Limit for Reactor Coolant System Dissolved Oxygen
2023-08-29
[Table view] |
Text
(1) Maximum Power Level Carolina Power & Light Company is authorized to operate the facility at reactor core power levels not in excess of 2900 megawatts thermal (100 percent rated core power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. , are hereby incorporated into this license.
Carolina Power & Light Company shall operate the facility in accordance with te Technical Specifications and the Environmental Protection Plan.
(3) Antitrust Conditions Carolina Power & Light Company shall comply with the antitrust conditions delineated in Appendix C to this license.
(4) Initial Startup Test Program (Section 14)1 Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
(5) Steam Generator Tube Rupture (Section 15.6.3)
Prior to startup following the first refueling outage, Carolina Power & Light Company shall submit for NRC review and receive approval of a steam generator tube rupture analysis, including the assumed operator actions, which demonstrates that the consequences if the design basis steam generator tube rupture event for the Shearon Harris Nuclear Power Plant are less than the acceptance criteria specified in the Standard Review Plan, NUREG-0800, at §15.6.3 Subparts 11(1) and (2) for calculated doses from radiological releases. In preparing their analysis Carolina Power & Light Company will not assume that operators will complete corrective actions within the first thirty minutes after a steam generator tube rupture.
1The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Amendment No. 126
TABLE 2.2-1 (continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS TOTAL SENSOR ALLOWANCE ERROR FUNCTIONAL UNIT (TA) z (S) TRIP SETPOINT ALLOWABLE VALUE
- 12. Reactor Coolant Flow-Low 4.58 1.98 0.6 > 90.5% of loop full 89.5% of loop full indicated flow indicated flow
- 13. Steam Generator Water 25.0 17.45 2.0 > 25.0% of narrow > 23.5% of narrow Level Low-Low range instrument span range instrument span
- 14. Steam Generator Water 8.9 5.95 2.0 > 25.0% of narrow > 24.05% of narrow Level - Low range instrument span range instrument span Coincident With Steam/Feedwater Flow 20.0 3.01 Note 6 *40% of full steam <43.1% of full steam Mismatch flow at RTP** flow at RTP**
- 15. Undervoltage - Reactor 14.0 1.3 0.0 5148 volts 4920 volts Coolant Pumps
- 16. Underfrequency - Reactor 5.0 3.0 0.0 57.5 Hz 57.3 Hz Coolant Pumps
- 17. Turbine Trip
- a. LOw Fluid Oil Pressure N.A. N.A. N.A. 1000 psig 950 psig
- b. Turbine Throttle Valve N.A. N.A. N.A. > 1% open 1% open Closure
- 18. Safety Injection Input N.A. N.A. N.A. N.A. N.A.
from ESF RTP = RATED THERMAL POWER SHEARON HARRIS - UNIT 1 2-5 Amendment No.126
TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS SENSOR TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE (TA) z (S) TRIP SETPOINT ALLOWABLE VALUE 5.. Turbine Trip and Feedwater Isolation (Continued)
- b. Steam Generator Water 22.0 8.15 2.0 *78.0% of
- 79.5% of narrow Level--High-High (P-14) narrow range range instrument instrument span.
span.
C. Safety Injection See Item 1. above for .Safety Injection Trip Setpoints and Allowable Values.
- 6. Auxiliary Feedwater
- a. Manual Initiation N.A. N.A. N.A. . N.A. N.A.
- b. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A.
and Actuation Relays
- c. Steam Generator Water 25.0 17.45 2.0 Ž 25.0% of Ž 23.5% of narrow Level--Low-Low narrow range range instrument instrument span.
span.
- d. Safety InjectionStart See Item 1. above for all Safety Injection Trip Setpoints and Motor-Driven Pumps Allowable Values.
- e. Loss-of-Offsite Power See Item 9. below for all Loss-of-Offsite Trip Setpoint and Start Motor-Driven Pumps and Allowable Values.
Turbine-Driven Pump
- f. Trip of All Main Feedwater N.A. N.A. N.A. N.A. N.A.
Pumps Start Motor-Driven Pumps SHEARON HARRIS - UNIT 1 3/4 3-32 Amendment No. 126
