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Category:Letter type:NL
MONTHYEARNL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 NL-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0745, Refueling Outage 1R24 Steam Generator Tube Inspection Report2023-09-22022 September 2023 Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2) NL-23-0666, License Amendment Request: Remove Combined License Appendix C (LAR 23-008)2023-08-28028 August 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-008) NL-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-08-11011 August 2023 Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0672, Licensee Guarantees of Payment of Deferred Premiums2023-08-10010 August 2023 Licensee Guarantees of Payment of Deferred Premiums NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0611, Core Operating Limits Report, Cycle 11 Version 12023-07-19019 July 2023 Core Operating Limits Report, Cycle 11 Version 1 NL-23-0584, Preservice Inspection Program Owner'S Activity Report2023-07-10010 July 2023 Preservice Inspection Program Owner'S Activity Report NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement 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-23-0541, Inservice Inspection Program Owners Activity Report for Outage 1R242023-06-28028 June 2023 Inservice Inspection Program Owners Activity Report for Outage 1R24 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0339, Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1)2023-06-13013 June 2023 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1) NL-23-0455, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2023-06-12012 June 2023 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report NL-23-0467, Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1)2023-06-0909 June 2023 Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1) NL-23-0346, License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007)2023-05-25025 May 2023 License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007) NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0385, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1)2023-05-17017 May 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1) NL-23-0398, Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-05-16016 May 2023 Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0360, Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-05-0505 May 2023 Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-23-0326, Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-1082023-05-0101 May 2023 Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-108 NL-23-0217, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-022023-05-0101 May 2023 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-02 NL-23-0330, Core Operating Limits Report, Cycle 25, Version 12023-04-26026 April 2023 Core Operating Limits Report, Cycle 25, Version 1 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0135, License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005)2023-04-17017 April 2023 License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005) NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0152, License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-04-11011 April 2023 License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0136, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-04-0505 April 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0132, License Amendment Request: Remove Combined License Appendix C (LAR 23-001)2023-04-0404 April 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-001) NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0193, Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003)2023-03-24024 March 2023 Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) NL-23-0196, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-03-24024 March 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-22-0977, License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing2023-02-0909 February 2023 License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing NL-23-0010, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-02-0606 February 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0076, Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004)2023-01-31031 January 2023 Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004) NL-23-0013, Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements2023-01-30030 January 2023 Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements NL-23-0068, Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report2023-01-27027 January 2023 Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report NL-23-0012, Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-01-20020 January 2023 Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel 2024-01-29
[Table view] Category:Technical Specifications
MONTHYEARML23317A2072023-12-22022 December 2023 Issuance of Amendments 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-1448 ML23243B0572023-12-19019 December 2023 VEGP Unit 4 Amendment Attachment ML23243A9802023-12-19019 December 2023 VEGP Unit 3 Amendment Attachment ML23268A0572023-11-0707 November 2023 Issuance of Amendments 194 & 191 Request for License Amendment Relocation of Technical Specification 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) ML23093A0282023-08-0101 August 2023 Issuance of Amendments Nos. 220 and 203, Regarding Use of Accident Tolerant Fuel Lead Test Assemblies ML23159A0992023-07-31031 July 2023 Attachment - Vogtle Electric Generating Plant, Unit 3 Amendment No. 192 (LAR 23-001) ML23158A2092023-07-19019 July 2023 LAR-23-005 U/4 Amd 189 Timing of TS Effectiveness Prior to Initial Criticality Amendment Attachment 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 ML23115A1492023-06-15015 June 2023 Issuance of Amendments No. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology NL-23-0385, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1)2023-05-17017 May 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1) ML23072A2752023-05-0101 May 2023 Attachment to Enclosure 1 - VEGP U3 Amendment 191 LAR-22-005 ML23037A0902023-02-0808 February 2023 Amend Attachment - Vogtle 3 Amend No. 190, Tech Spec Exceptions for In-Containment Refueling Water Storage Tank Operability Prior to Initial Criticality (Exigent Circumstances) ML23037A9212023-02-0606 February 2023 SNC Presentation - Draft Vogtle TSTF-339 LAR - Pre-Submittal Meeting - February 13 2023 ML23013A2192023-01-13013 January 2023 Amendment No. 189 - Amendment Attachment ND-22-0219, Technical Specifications Setpoint Report2022-08-11011 August 2022 Technical Specifications Setpoint Report ML22116A0842022-07-0505 July 2022 Issuance of Amendment Nos. 215 and 198, Regarding Revision to Technical Specification 3.7.2, Main Steam Isolation Valves (Msivs) 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 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 ML20247J4632020-10-14014 October 2020 Attachment - Vogtle Electric Generating Plant Unit 4 Amendment 183 (LAR-20-004) ML20247J4602020-10-14014 October 2020 Attachment - Vogtle Electric Generating Plant Unit 3 Amendment 185 (LAR-20-004) ND-20-0668, Request for License Amendment for Vacuum Relief Valve Technical Specification Changes (LAR-20-005)2020-06-19019 June 2020 Request for License Amendment for Vacuum Relief Valve Technical Specification Changes (LAR-20-005) ML20013G7122020-02-0303 February 2020 Amendment 173 (LAR-19-016) ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19298A1042019-10-25025 October 2019 Attachment - VEGP U4 Amendment XX5 (LAR-19-001) NL-19-1183, Response to Request for Additional Information Regarding End State Revision from Hot Shutdown to Cold Shutdown2019-10-17017 October 2019 Response to Request for Additional Information Regarding End State Revision from Hot Shutdown to Cold Shutdown ND-19-1129, Supplement to the Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification ...2019-10-0707 October 2019 Supplement to the Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification ... ML19238A3482019-09-27027 September 2019 Attachment - Vogtle Electric Generating Plant Unit 3 (LAR-19-004) ML19238A3492019-09-27027 September 2019 Attachment - Vogtle Electric Generating Plant Unit 4 (LAR-19-004) ML19063C6402019-04-11011 April 2019 Attachment - Vogtle Electric Generating Plant Unit 3 Amendment 158 (LAR-18-027) ML19063C6412019-04-11011 April 2019 Attachment - VEGP U4 Amendment 156 (LAR-18-027) ML19038A4572019-02-25025 February 2019 Attachment - Vogtle Electric Generating Plant, Units 4 (LAR 18-025) ML19038A4552019-02-25025 February 2019 Attachment - Vogtle Electric Generating Plant, Units 3 (LAR 18-025) ML19035A7602019-02-22022 February 2019 Attachment for Amendment 153 - LAR-18-024 ML19035A7582019-02-22022 February 2019 Attachment for Amendment 154 - LAR-18-024 ML18351A1942019-01-15015 January 2019 Attachment - Vogtle Electric Generating Plant Unit 4 LAR 18-017 ML18351A1922019-01-15015 January 2019 Attachment - Vogtle Electric Generating Plant Unit 3 LAR 18-017 ML18341A0832018-12-18018 December 2018 Attachment - Vogtle Electric Generating Plant - Unit 3 Amendment 149(LAR-18-022) ML18341A0852018-12-18018 December 2018 Attachment - Vogtle Electric Generating Plant, Unit 4 Amendment 148 (LAR-18-022) ML18296A4182018-11-13013 November 2018 Attachment - Vogtle Electric Generating Plant Unit 4 ML18296A4172018-11-13013 November 2018 Attachment - Vogtle Electric Generating Plant Unit 3 ML18263A0392018-10-29029 October 2018 Issuance of Amendments to Extend the Containment Type a Leak Rate Test Frequency to 15 Years and Type C Leak Rate Test Frequency to 75 Months (CAC Nos. MG0240 and MG0241; EPID L-2017-LLA-0295) ML18180A0622018-08-10010 August 2018 Issuance of Amendment Nos. 196 and 179 Regarding Application of the Seismic Probabilistic Risk Assessment Into the Previously Approved 10 CFR.50.69. Categorization Process ML18173A3062018-07-26026 July 2018 Attachment - Vogtle Electric Generating Plant, Unit 4 Amendment 134 (LAR-18-003) ML18173A3042018-07-26026 July 2018 Attachment - Vogtle Electric Generating Plant, Unit 3 Amendment 135 (LAR-18-003) ML18082B3772018-07-19019 July 2018 Attachment - Vogtle Electric Generating Plant Unit 3 Amendment 134(LAR-18-005) ML18082B3792018-07-19019 July 2018 Attachment - Vogtle Electric Generating Plant Unit 4 Amendment 133(LAR-18-005) ML18156A1482018-07-10010 July 2018 Attachment - Vogtle Electric Generating Plant Unit 4 (LAR 17-044) 2023-08-01
[Table view] |
Text
L M. Stinson (Mikel Southern Nuclear Vice President Operating Company, Inc.
Fleet Operations Support 40 Inverness Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Tel 205.992.5181
~
Fax 205.992.0341 SOUTHERN COMPANY January 30, 2008 Energy to Serve YtJur WorIJ'M Docket Nos.: 50-424 NL-08-0106 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant Supplemental Information Supporting Review of the Measurement Uncertainty Recapture Power Uprate Amendment Request Ladies and Gentlemen:
On August 28,2007, Southern Nuclear Operating Company (SNC) submitted a request to change the licensed maximum power level for Vogtle Electric Generating Plant (VEGP) Units 1 and 2 (letter NL-07-1020). SNC proposed to increase the licensed maximum power level by 1.7% by performing a measurement uncertainty recapture power uprate (MURPU). On December 21, 2007, SNC submitted responses (letter NL-07-2346) to requests for additional information (RAI) from the NRC dated November 20,2007, and November 29, 2007.
Subsequent to responding to the RAls, SNC was requested to provide the NRC with the Technical Requirements that will be incorporated into the VEGP Unit 1 and Unit 2 Technical Requirements Manual (TRM), stipulating actions to be taken when the Leading Edge Flow Meter (LEFM) based calorimetric is not functional.
The Technical Requirements are included in the enclosure.
The TRM is incorporated by reference in Section 16.3.9 of the VEGP Unit 1 and Unit 2 Updated Final Safety Analysis Report (UFSAR). As discussed in UFSAR Section 16.3.9, changes to the TRM are controlled by SNC in accordance with the processes in 10 CFR 50.59.
(Affirmation and signature are provided on the following page.)
U. S. Nuclear Regulatory Commission NL-08-0106 Page 2 L. M. Stinson states he is a Vice President of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Soutliern Nuclear Operating Company and to the best of his knowledge and belief, the facts set forth in this letter are true.
This letter contains no NRC commitments. If you have any questions, please advise.
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY L. M. Stinson Vice President Fleet Operations Support Sworn to and subscribed before me this30 ti day of Jan Udn; ,2008.
Ma.vJ4 "Notary Public My commission expires: .J: I'} s; .)010 LMS/DRG/daj
Enclosure:
Technical Requirement 13.3.7 Ultrasonic Mode Calorimetric cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. T. E. Tynan, Vice President - Vogtle Mr. D. H. Jones, Vice President - Engineering RType: CVC7000 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Acting Regional Administrator Mr. S. P. Lingam, NRR Project Manager - Vogtle Mr. G. J. McCoy, Senior Resident Inspector - Vogtle State of Georgia Mr. N. Holcomb, Commissioner - Department of Natural Resources
Vogtle Electric Generating Plant Enclosure Technical Requirement 13.3.7 Ultrasonic Mode Calorimetric
Ultrasonic Mode Calorimetric TR 13.3.7 13.3 Instrumentation TR 13.3.7 Ultrasonic Mode Calorimetric TR 13.3.7 The Ultrasonic Mode Calorimetric shall be FUNCTIONAL with:
- a. The Caldon LEFM CheckPlus system FUNCTIONAL, and
- b. The Integrated Plant Computer (IPC) calorimetric (UQ1118)
FUNCTIONAL.
APPLICABILITY: MODE 1 with THERMAL POWER> 3565 MWt.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LEFM CheckPlus system A.1 Switch UQ1118 calorimetric Immediately not FUNCTIONAL. display from the Ultrasonic Mode (Ccal) to the Normalized Venturi Mode (Neal).
AND A.2 Restore the LEFM 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> CheckPlus system to FUNCTIONAL status.
B. Required Actions and B.1 Switch UQ1118 calorimetric Immediately associated Completion display from the Normalized Times of Condition A not Venturi Mode (Neal) to the met. non-normalized Venturi Mode (Veal).
AND B.2 Reduce reactor core power Immediately to ~ 3565 MWt.
(continued)
Vogtle Units 1 and 2 13.3 - 19 Rev.
Technical Requirement
Ultrasonic Mode Calorimetric TR 13.3.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. IPC Calorimetric C.1 Verify reactor core power 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (UQ1118) not ~ 3625.6 MWt by ensuring FUNCTIONAL for reasons the higher of average Power other than Condition A. Range NIS or Delta-T indications ~ 100 %RTP.
AND C.2 Restore the IPC Calorimetric Prior to performing (UQ1118) to FUNCTIONAL the next required status. power range channel calorimetric heat balance comparison per SR 3.3.1.2 D. Required Actions and D.1 Reduce reactor core power Immediately associated Completion to ~ 3565 MWt ensuring the Times of Condition C not higher of average Power met. Range NIS or Delta-T indications ~ 98.3% RTP.
Vogtle Units 1 and 2 13.3 - 20 Rev.
Technical Requirement
Ultrasonic Mode Calorimetric TR 13.3.7 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.3.7.1 Verify that the most recent performance of SR 3.3.1.2 is Prior to exceeding based on an Ultrasonic Mode Calorimetric (Ccal). 3565 MWt.
TRS 13.3.7.2 Locally verify LEFM CheckPlus system FUNCTIONAL. With LEFM CheckPlus system FUNCTIONAL, once within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with the Main Control Board (MCB) LEFM trouble annunciator illuminated or not FUNCTIONAL.
Every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter.
TRS 13.3.7.3 Perform LEFM CheckPlus electronics and system Once per 18 months maintenance in accordance with plant procedures.
TRS 13.3.7.4 Perform calibration of instrumentation and IPC Once per 18 months computer points to support calorimetric (UQ1118) in accordance with plant procedures.
Vogtle Units 1 and 2 13.3 - 21 Rev.
Technical Requirement
Ultrasonic Mode Calorimetric B TR 13.3.7 B TR 13.3.7 Ultrasonic Mode Calorimetric BASES The reactor core power levels discussed in this Technical Requirement (TR) are based on the reactor core power level assumed in the reactor safety analysis and the magnitude of the calorimetric power determination uncertainty which is a function of the calorimetric method.
Operation at indicated core power levels above 3565 MWt requires a calorimetric power uncertainty determination of less than 2.0%. This is only possible if the Ultrasonic Mode calorimetric (Ccal) is functional. The Ccal is unique in that it receives feedwater mass flow, feedwater temperature, and feedwater pressure inputs directly from the Caldon LEFM CheckPlus system. The LEFM system measures and transmits this data with lower uncertainty than the functionally equivalent instrumentation from the feedwater Venturi Mode calorimetric.
The reduced uncertainty that is characteristic of the Ultrasonic Mode calorimetric requires a FUNCTIONAL LEFM System to provide the feedwater parameters listed above as well as a FUNCTIONAL IPC Calorimetric (UQ1118) for performing the thermal power calculations. The Normalized Venturi calorimetric (Ncal) will support operation above 3565 MWt and the required Power Range NIS channel adjustments for power level monitoring for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> while the LEFM system is not FUNCTIONAL. Upon the expiration of the 48-hour allowed outage time, reactor core power is reduced to ~ 3565 MWt. Use of a non-normalized venturi-based calorimetric does not support operation above 3565 MWt.
Vogtle Units 1 and 2 B 13.3 - 1 Rev. 0 Technical Requirement Bases
Ultrasonic Mode Calorimetric B TR 13.3.7 BASES (continued)
FUNCTIONALITY REQUIREMENTS LEFM CheckPlus System For this TR, "FUNCTIONAL" is defined as the ability of the system to calculate and communicate feed water mass flow, feedwater temperature and pressure at the required uncertainty level to be used as input for the IPC Ultrasonic Mode calorimetric calculation (Ccal).
The LEFM electronics package and the IPC/LEFM data link application perform extensive self monitoring and diagnostics to ensure proper operation. Conditions which impact the LEFM status, LEFM/IPC communication status, or electronics cabinet internal temperature will trigger a MCB annunciator. An available IPC screen may be reviewed to determine what condition has caused the annunciator to alarm. More detailed diagnostic information is available locally at the LEFM electronics cabinet display screen.
MCB Annunciator Discussion LEFM System Status Condition LEFM/IPC Data The data from the LEFM cabinet is not NOT FUNCTIONAL communication communicating properly to the IPC. The IPC link has failed Ultrasonic Mode for calorimetric determination is impacted. Alarm condition.
LEFM meter in The LEFM system has experienced a failure NOT FUNCTIONAL non-normal affecting the uncertainty requirements for the status Ultrasonic Mode Calorimetric. Specific cause of the status is available locally at the LEFM (Alert or Failure electronics display.
status)
LEFM Electronics The temperature of the LEFM electronics cabinet FUNCTIONAL cabinet internal is above the high temperature setpoint. The temperature is LEFM system can continue to meet the above the high uncertainty requirements for the Ultrasonic Mode setpoint. Calorimetric. MCB annunciator will be triggered when High Temperature limit has been exceeded to allow monitoring and corrective action prior to exceeding the Hi-Hi limit.
Failure to restore the LEFM CheckPlus system to FUNCTIONAL status will result in reducing the reactor core power to ~ 3565 MWt.
Vogtle Units 1 and 2 B 13.3 - 2 Rev. a Technical Requirement Bases
Ultrasonic Mode Calorimetric B TR 13.3.7 BASES (continued)
(PC Calorimetric (UQ1118)
For this TR, "FUNCTIONAL" condition of the IPC Calorimetric (UQ1118) is defined as the ability of the IPC to perform the following calculations for the UQ1118 thermal power indication:
- 1. IPC Ultrasonic Mode calorimetric calculation (Ccal) (See Note Below)
- 2. IPC Normalized Venturi Mode calorimetric (Neal) calculation if in Action A.1
- 3. IPC non-normalized Venturi Mode calorimetric (V-cal) calculation if in Action B.1 When the IPC Calorimetric (UQ1118) is not FUNCTIONAL, reactor core power limitations for this TR are based on the higher of the average Power Range NIS or Delta-T indications.
Operation at 100% power may continue until the next Tech Spec required power range channel calorimetric heat balance comparison per SR 3.3.1.2, which could be up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from entry into Condition C. Failure to restore the IPC Calorimetric (UQ1118) to FUNCTIONAL status will result in reducing the core power to ~3565 MWt (~98.3% RTP based on the higher of the average Power Range NIS or Delta-T indications). For the purpose of power level monitoring, adjustments of the Power Range NIS indication based on the use of a manual non-normalized venturi-based calorimetric does not support operation above 3565MWt.
Note: A condition causing the LEFM CheckPlus system to be not FUNCTIONAL (Condition A) does not require entry into Condition C.
Vogtle Units 1 and 2 B 13.3 - 3 Rev. 0 Technical Requirement Bases