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| | number = ML060590026 | | | number = ML060590026 |
| | issue date = 02/27/2006 | | | issue date = 02/27/2006 |
| | title = Farley, Units 1 and 2, Technical Specifications, Eliminate Power Range Neutron High-Flux Negative Rate Reactor Trip Function. Enclosure 1 | | | title = Technical Specifications, Eliminate Power Range Neutron High-Flux Negative Rate Reactor Trip Function. Enclosure 1 |
| | author name = Martin R E | | | author name = Martin R E |
| | author affiliation = NRC/NRR/ADRO/DORL | | | author affiliation = NRC/NRR/ADRO/DORL |
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MONTHYEARML0605900262006-02-27027 February 2006 Technical Specifications, Eliminate Power Range Neutron High-Flux Negative Rate Reactor Trip Function. Enclosure 1 Project stage: Other ML0531903812006-02-27027 February 2006 License Amendments, Eliminate Power Range Neutron High-Flux Negative Rate Reactor Trip Function Project stage: Other 2006-02-27
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Category:Technical Specifications
MONTHYEARML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-22-0223, License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value2022-06-30030 June 2022 License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value ML22069A0042022-04-27027 April 2022 Issuance of Amendments Revision to TSs to Adopt TSTF-269-A, Rev. 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves NL-22-0091, Correction of Technical Specification Typographical Omission2022-02-24024 February 2022 Correction of Technical Specification Typographical Omission ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21316A0552022-01-0505 January 2022 1 & 2, and Vogtle Electric Generating Plant, 1 & 2 - Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0163 ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls NL-21-0385, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2021-09-29029 September 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML20303A1192020-12-11011 December 2020 Issuance of Amendment Nos. 232 and 229 Regarding Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19071A1382019-07-16016 July 2019 Issuance of Amendments 223 and 220 Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations TSTF-51 and TSTF-471 ML18151A1742018-06-27027 June 2018 Issuance of Amendment Nos. 219 and 216, Adopt Technical Specification Task Force Traveler TSTF-412, Revision 3, Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable ML17333A0792017-12-0606 December 2017 Reissue of Corrected Technical Specification Page 3.6.6-3 NL-17-1974, Supplemental Submittal of Corrected Technical Specification Pages for the AST, TSTF-448 and TSTF-312 Amendment Package2017-11-21021 November 2017 Supplemental Submittal of Corrected Technical Specification Pages for the AST, TSTF-448 and TSTF-312 Amendment Package NL-17-1067, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request2017-06-0808 June 2017 Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request ML17034A1932017-02-16016 February 2017 Issuance of Amendments to Adopt TSTF-427 Allowance for Non Technical Specification Barrier Degradation on Supported System Operability ML16232A0002016-10-17017 October 2016 Issuance of Amendments Related to NFPA-805 Supplement ML16272A1892016-10-0303 October 2016 Correction to Amendment Nos. 203 (Unit 1) and 199 (Unit 2) ML15289A2272016-06-10010 June 2016 Issuance of Amendments Related to TSTF-432-A, Revision 1 ML16083A2652016-05-17017 May 2016 Issuance of Amendments to Revise Technical Specification 3.4.14 NL-16-0034, License Amendment Request and 10 CFR 50.12 Exemption Request, Optimized Zirlo Fuel Rod Cladding2016-03-16016 March 2016 License Amendment Request and 10 CFR 50.12 Exemption Request, Optimized Zirlo Fuel Rod Cladding NL-15-1956, Adoption of TSTF-65-A, Rev. 1, Use of Generic Titles for Utility Positions2016-03-14014 March 2016 Adoption of TSTF-65-A, Rev. 1, Use of Generic Titles for Utility Positions NL-15-2062, Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-52, Revision 22015-11-25025 November 2015 Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-52, Revision 2 NL-15-0722, Technical Specification 3.3.5 Loss of Power Diesel Generator Start Instrumentation License Amendment Request2015-11-20020 November 2015 Technical Specification 3.3.5 Loss of Power Diesel Generator Start Instrumentation License Amendment Request ML15180A3342015-08-0303 August 2015 Issuance of Amendments ML15083A0982015-06-0202 June 2015 Issuance of Amendments (TAC Nos. MF4828, MF4829, MF4889, and MF4890) ML14308A0482015-03-10010 March 2015 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) NL-15-0188, Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.52015-02-13013 February 2015 Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.5 NL-14-0115, Units 1 & 2 & Vogtle Electric Generating Plant - Units 1 and 2 - License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.52014-09-17017 September 2014 Units 1 & 2 & Vogtle Electric Generating Plant - Units 1 and 2 - License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.5 ML14155A3022014-08-15015 August 2014 Issuance of Amendment Regarding Minimum Condensate Storage Tank Level Technical Specifications ML14069A3442014-05-13013 May 2014 Issuance of Amendments to Incorporate the Schedule for Degraded Grid Voltage Modification NL-12-0867, License Amendment Request to Technical Specification 3.7.6, Condensate Storage Tank2012-08-20020 August 2012 License Amendment Request to Technical Specification 3.7.6, Condensate Storage Tank NL-12-0868, Request to Revise Technical Specifications Associated with the Low Temperature Overpressure Protection System and the Pressure and Temperature Limits Report2012-08-15015 August 2012 Request to Revise Technical Specifications Associated with the Low Temperature Overpressure Protection System and the Pressure and Temperature Limits Report NL-12-1226, License Amendment Request to Allow Nexus Nuclear Data Methodology in the Preparation of the Core Operating Limits Report2012-08-14014 August 2012 License Amendment Request to Allow Nexus Nuclear Data Methodology in the Preparation of the Core Operating Limits Report NL-12-1552, Emergency Technical Specification Revision Request for 3.8.1 AC Sources - Operating2012-07-23023 July 2012 Emergency Technical Specification Revision Request for 3.8.1 AC Sources - Operating NL-12-0403, Exigent Technical Specification Revision Request for TS 3.5.4 Refueling Water Storage Tank (RWST)2012-02-28028 February 2012 Exigent Technical Specification Revision Request for TS 3.5.4 Refueling Water Storage Tank (RWST) NL-11-0299, Application to Amend Surveillance Requirement 3.4.11.1 and 3.4.11.42012-01-18018 January 2012 Application to Amend Surveillance Requirement 3.4.11.1 and 3.4.11.4 NL-10-0272, License Amendment Request for Adoption of TSTF-425-A, Revision 3, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Using the Consolidated..2010-10-29029 October 2010 License Amendment Request for Adoption of TSTF-425-A, Revision 3, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Using the Consolidated.. NL-09-1676, Request to Revise Technical Specification 3.7.8, Service Water System (Sws).2009-10-21021 October 2009 Request to Revise Technical Specification 3.7.8, Service Water System (Sws). NL-09-1622, Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, Service Water System (Sws).2009-10-0808 October 2009 Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, Service Water System (Sws). NL-09-1861, License Amendment Request to Technical Specification 3.3.2 ESFAS Instrumentation and 5.6.8 Post Accident Monitoring Report2009-09-15015 September 2009 License Amendment Request to Technical Specification 3.3.2 ESFAS Instrumentation and 5.6.8 Post Accident Monitoring Report ML0917706642009-09-0404 September 2009 Southern Nuclear Operating Company Plants, License Amendments, Regarding Elimination of Working Hour Restrictions from Technical Specifications ML0827300082008-09-29029 September 2008 Tech Spec Pages for Amendment Nos. 178 and 171 Revised TS for Limiting Condition for Operation 3.9.3, Containment Penetrations. NL-08-0832, Southern Nuclear Operating Company, Inc., Revision to License Amendment Request to Technical Specification 5.2, Organization, and License Amendment Request to TS 5.3. Unit Staff Qualifications.2008-06-12012 June 2008 Southern Nuclear Operating Company, Inc., Revision to License Amendment Request to Technical Specification 5.2, Organization, and License Amendment Request to TS 5.3. Unit Staff Qualifications. ML0818202472008-05-23023 May 2008 Updated Final Safety Analysis Report, Revision 21, Technical Specifications Bases NL-06-2801, Technical Specification Amendment Request, Containment Leakage Rate Testing Program2007-11-0505 November 2007 Technical Specification Amendment Request, Containment Leakage Rate Testing Program NL-07-1079, Edwin I. Hatch Nuclear Plant, Vogtle Electric Generating Plant, License Amendment Request to Technical Specification 5.2, Organization2007-07-17017 July 2007 Edwin I. Hatch Nuclear Plant, Vogtle Electric Generating Plant, License Amendment Request to Technical Specification 5.2, Organization ML0719804822007-07-16016 July 2007 Tech Spec Pages for Amendments 175 and 168 Regarding Technical Specification Changes to Reflect Change in Organizational Structure 2023-08-24
[Table view] |
Text
RTS Instrumentation
3.3.1 Table
3.3.1-1 (page 1 of 8)Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT 1. Manual Reactor 1,2 2 B SR 3.3.1.12 NA NA Trip 3 (a), 4 (a), 5 (a) 2 C SR 3.3.1.12 NA NA 2. Power Range Neutron Flux a. High 1,2 4 D SR 3.3.1.1 S 109.4% RTP s 109%SR 3.3.1.2 RTP SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.14 b. Low 1 (b), 2 4 E SR 3.3.1.1 S 25.495, RTP S 25% RTP SR 3.3.1.8 SR 3.3.1.10 SR 3.3.1.14 3. Power Range 1,2 4 D SR 3.3.1.7 S 5.4% RTP S 5% RTP Neutron Flux High SR 3.3.1.10 with time with time Positive Rate constant constant a2sec 22sec 4. Intermediate 1 (b), 2 (c) 2 FG SR 3.3.1.1 S 40% RTP S 35% RTP Range Neutron SR 3.3.1.8 Flux SR 3.3.1.10 2 (d) 2 H SR 3.3.1.1 s 40% RTP s 35% RTP SR 3.3.1.8 SR 3.3.1.10 (a) With Reactor Trip Breakers (RTSs) closed and Rod Control System capable of rod withdrawal.(b) Below the P-10 (Power Range Neutron Flux) interlocks.(c) Above the P-6 (Intermediate Range Neutron Flux) interlocks.(d) Below the P46 (intermediate Range Neutron Flux) Interlocks.
Farley Units 1 and 2 3.3.1-14 Amendment No. 171 (Unit 1)Amendment No. 164 (Unit 2)
RTS Instrumentation B 3.3.1 BASES APPLICABLE
- b. Power Range Neutron Flux-Low SAFETY ANALYSES, LCO, and The LCO requirement for the Power Range Neutron Flux -APPLICABILITY Low trip Function ensures that protection is provided against (continued) a positive reactivity excursion from low power or subcritical conditions.
The LCO requires all four of the Power Range Neutron Flux -Low channels to be OPERABLE.
The channels are combined in a 2-out-of-4 trip Logic.In MODE 1, below the Power Range Neutron FlUx (P-10 setpoint), and in MODE 2, the Power Range Neutron Flux -Low trip must be OPERABLE.
This Function may be manually blocked by the operator when two out of four power range channels are greater than approximately 10% RTP (P-1 0 setpoint).
This Function is automatically unblocked when three out of four power range channels are below the P-1 0 setpoint.
Above the P-10 setpoint, positive reactivity additions are mitigated by the Power Range Neutron Flux --High trip Function.In MODE 3, 4, 5, or 6, the Power Range Neutron Flux -Low trip Function does not have to be OPERABLE because the reactor is shut down. Other RTS trip Functions and administrative controls provide protection against positive reactivity additions or power excursions in MODE 3, 4, 5, or 6.3. Power Ranae Neutron Flux -High Positive Rate The Power Range Neutron Flux -High Positive Rate trip uses the same NIS detectors as discussed for Function 2 above.The Power Range Neutron Flux -High Positive Rate trip Function ensures that protection is provided against rapid increases in neutron flux that are characteristic of an RCCA drive rod housing rupture and the accompanying ejection of the RCCA. In certain cases, this Function compliments the Power Range Neutron (continued)
Farley Units I and 2 B 3.3.11-110 Revision RTS Instrumentation B 3.3.1 BASES APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY
- 3. Power Range Neutron Flux-High Positive Rate (continued)
Flux- High and Low Setpoint trip Functions to ensure that the criteria are met for a rod ejection event.I The LCO requires all four of the Power Range Neutron Flux -High Positive Rate channels to be OPERABLE.
The channels are combined in a 2-out-of-4 trip Logic.In MODE 1 or 2, when there is a potential to add a large amount of positive reactivity from a rod ejection accident (REA), the Power Range Neutron Flux-High Positive Rate trip must be OPERABLE.In MODE 3, 4, 5, or 6, the Power Range Neutron Flux -High Positive Rate trip Function does not have to be OPERABLE because other RTS trip Functions and administrative controls will provide protection against positive reactivity additions.
Also, since only the shutdown banks may be withdrawn in MODE 3, 4, or 5, the remaining complement of control bank worth ensures a sufficient degree of SDM in the event of an REA. In MODE 6, no rods are withdrawn and the SDM is increased during refueling operations.
The reactor vessel head is also removed or the closures bolts are detensioned preventing any pressure buildup.(continued)
Farley Units 1 and 2 B 3.3.1-11 Revision RTS Instrumentation B 3.3.1 BASES APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY
- 4. Intermediate Range Neutron Flux.The Internediate Range Neutron Flux trip Function ensures that protection is provided against an uncontrolled RCCA bank rod withdrawal accident from a subcritical condition during startup. This trip Function provides diverse protection to the Power Range Neutron Flux--Low Setpoint trip Function.
The NIS intermediate range detectors are located external to the reactor vessel and measure neutrons leaking from the core. The NIS intermediate range channels also provide a control interlock signal to prevent automatic and manual rod withdrawal prior to initiating a reactor trip.Limiting further rod withdrawal may terminate the transient and eliminate the need to trip the reactor. No credit is taken in the safety analyses for this trip function.The LCO requires two channels of Intermediate Range Neutron Flux to be OPERABLE.
Two OPERABLE channels are sufficient to ensure no single random failure will disable this trip Function.
The trip function is accomplished by a 1-out-of-2 trip Logic.Because this trip Function is important only during startup, there is generally no need to disable channels for on-line testing while the Function is required to be OPERABLE.
Therefore, a third channel is unnecessary.
In MODE 1 below the P-1 0 setpoint, and in MODE 2, vwhen there is a potential for an uncontrolled RCCA bank rod withdrawal accident during reactor startup, the Intermediate Range Neutron Flux trip must be OPERABLE.
Above the P-1 0 setpoint, the Power Range Neutron Flux-High Setpoint trip and the Power Range Neutron Flux -High Positive Rate trip provide core protection for a rod (continued)
Farley Units I and 2 B 3.3.1-12 Revision RTS Instrumentation B 3.3.1 BASES ACTIONS C.1 and C.2 (continued) within the allowed 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Completion Time, the unit must be placed in a MODE in which the requirement does not apply. To achieve this status, the RTBs must be opened within the next hour. The additional hour provides sufficient time to accomplish the action in an orderly manner. With the RTBs open, these Functions are no longer required.The Completion Time is reasonable considering that in this Condition, the remaining OPERABLE train is adequate to perform the safety function, and giver the low probability of an event occurring during this interval.D.1.1. D.1.2, D.2.1. D.2.2, and D.3 Condition D applies to the Power Range Neutron Flux -High and Power Range Neutron Flux -High Positive Rate Functions.
The Nl44 power range detector provides input to the CRD System therefore, the NIS has a two-out-of-four trip logic. A known inoperable channel must be placed in the tripped condition.
This results in a partial trip condition requiring only one-out-of-three logic for actuation.
The 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> allowed to place the inoperable channel in the tripped condition is justified in WCAP-1 0271 -P-A (Ref. 7).In addition to placing the inoperable channel in the tripped condition, THERMAL POWER must be reduced to < 75% RTP within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.Reducing the power level prevents operation of the core with radial power distributions beyond the design limits. With one of the NIS power range detectors inoperable, 1/4 of the radial power distribution monitoring capabilily is lost.As an alternative to the above actions, the inoperable channel can be placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and the QPTR monitored once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as per SR 3.2.4.2, QPTR verification.
Calculating QPTR every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> compensates for the lost monitoring capability due to the inoperable NIS power range channel and allows continued unit operation at power levels > 75% RTP. The 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Completion Time and the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency are consistent with LCO :3.2.4,"QUADRANT POWER TILT RATIO (QPTR)." (continued)
Farley Units 1 and 2 B 3.3.1-38 Revision