ML19063C641: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:}} | {{#Wiki_filter:ATTACHMENT TO LICENSE AMENDMENT NO. 156 TO FACILITY COMBINED LICENSE NO. NPF-92 DOCKET NO. 52-026 Replace the following pages of the Facility Combined License No. NPF-92 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Facility Combined License No. NPF-92 REMOVE INSERT 7 7 Appendix A to Facility Combined License Nos. NPF-91 and NPF-92 REMOVE INSERT 3.4.12-2 3.4.12-2 3.7.1-2 3.7.1-2 Appendix C to Facility Combined License No. NPF-92 REMOVE INSERT C-40 C-40 C-101 C-101 C-240 C-240 C-249a C-249a C-259 C-259 C-292 C-292 C-326 C-326 C-334 C-334 C-340 C-340 C-356 C-356 C-371 C-371 C-421 C-421 (7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, for Changes and SNC shall report the change to the Director of NRO, or the designee, in accordance with 10 CFR 50.59(d). (b) SNC shall report any violation of a requirement in Section 2.D.(3), Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73. (8) Incorporation The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively of this license, as revised through Amendment No. 156, are hereby incorporated into this license. (9) Technical Specifications The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g). (10) Operational Program Implementation SNC shall implement the programs or portions of programs identified below, on or before the date SNC achieves the following milestones: (a) Environmental Qualification Program implemented before initial fuel load; (b) Reactor Vessel Material Surveillance Program implemented before initial criticality; (c) Preservice Testing Program implemented before initial fuel load; (d) Containment Leakage Rate Testing Program implemented before initial fuel load; (e) Fire Protection Program 1. The fire protection measures in accordance with Regulatory Guide (RG) 1.189 for designated storage building areas (including adjacent fire areas that could affect the storage area) implemented before initial receipt 7 Amendment No. 156 | ||
C-40 Amendment No. 156 1.4 List of Acronyms and Abbreviations The acronyms presented in this section are provided for information. ac Alternating Current AC Acceptance Criteria ADS Automatic Depressurization System AHU Air Handling Units ANS Alert and Notification System ASME American Society of Mechanical Engineers atm Atmoshpere BTU British Thermal Unit CAS Compressed and Instrument Air System CAV Cumulative Absolute Velocity cc Cubic Centimeter CCS Component Cooling Water System CDE Committed Dose Equivalent CDS Condensate System cfm Cubic Feet per Minute CFR Code of Federal Regulations Ci Curie CIM Component Interface Module CMT Core Makeup Tank CNS Containment System COL Combined License CRDM Control Rod Drive Mechanism CSA Control Support Area CST Condensate Storage Tank CVS Chemical and Volume Control System CWS Circulating Water System DAS Diverse Actuation System DBT Design Basis Threat dc Direct Current DCD Design Control Document DDS Data Display and Processing System DOS Standby Diesel Fuel Oil System D-RAP Design Reliability Assurance Program DTS Demineralized Water Treatment System DVI Direct Vessel Injection DWS Demineralized Water Transfer and Storage System EAL Emergency Action Level ECS Main ac Power System EDS Non-Class 1E dc and Uninterruptible Power Supply System EFS Communication System EGS Grounding and Lightning Protection System | |||
C-240 Amendment No. 156 Figure 2.3.7-1 Spent Fuel Pool Cooling System C-249a Amendment No. 156 Table 2.3.9-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 427 2.3.09.04a 428 2.3.09.04b 429 2.3.09.05 2.3.10 Liquid Radwaste System Design Description The liquid radwaste system (WLS) receives, stores, processes, samples and monitors the discharge of radioactive wastewater. | |||
C-259 Amendment No. 156 Table 2.3.11-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 450 2.3.11.02.i ii) Type tests, analyses, or a combination of type tests and analyses of seismically designed equipment will be performed. ii) A report exists and concludes that the seismically designed equipment can withstand appropriate seismic design basis loads without loss of its structural integrity function. iii) Inspection will be performed for the existence of a report verifying that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions. iii) A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions. 451 2.3.11.02.ii 452 2.3.11.02.iii 453 2.3.11.03a 454 2.3.11.03b 455 2.3.11.03c C-292 Amendment No. 156 b) c) d) a) b) c) a) b) c) d) 14. | |||
C-326 Amendment No. 156 Figure 2.6.1-1 (Sheet 1 of 4) Main ac Power System C-334 Amendment No. 156 2.6.3 Class 1E dc and Uninterruptible Power Supply System Design Description The Class 1E dc and uninterruptible power supply system (IDS) provides dc and uninterruptible ac electrical power for safety-related equipment during normal and off-normal conditions. The IDS is as shown in Figure 2.6.3-1 and the component locations of the IDS are as shown in Table 2.6.3-4. 1. 2. 3. 4. a) b) c) d) e) f) g) h) i) j) 5. a) b) c) | |||
C-340 Amendment No. 156 Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 599 2.6.03.02.iii 600 2.6.03.03 601 2.6.03.04a 602 2.6.03.04b 603 2.6.03.04c C-356 Amendment No. 156 Table 2.6.6-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 637 2.6.06.01.i 638 2.6.06.01.ii C-371 Amendment No. 156 Table 2.7.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 677 2.7.01.01 678 2.7.01.02a 2.b) The piping identified in Table 2.7.1-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements. | |||
C-421 Amendment No. 156 Note 1: Dash () indicates not applicable. Note 2: Cables from this division in this fire area are limited to interdivisional cables terminating in this fire area. Table 3.3-4 is not used.}} | |||
Revision as of 21:35, 7 May 2019
| ML19063C641 | |
| Person / Time | |
|---|---|
| Site: | Vogtle |
| Issue date: | 04/11/2019 |
| From: | Office of New Reactors |
| To: | Southern Nuclear Operating Co |
| References | |
| EPID L-2018-LLA-0311 | |
| Download: ML19063C641 (16) | |
Text
ATTACHMENT TO LICENSE AMENDMENT NO. 156 TO FACILITY COMBINED LICENSE NO. NPF-92 DOCKET NO.52-026 Replace the following pages of the Facility Combined License No. NPF-92 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Facility Combined License No. NPF-92 REMOVE INSERT 7 7 Appendix A to Facility Combined License Nos. NPF-91 and NPF-92 REMOVE INSERT 3.4.12-2 3.4.12-2 3.7.1-2 3.7.1-2 Appendix C to Facility Combined License No. NPF-92 REMOVE INSERT C-40 C-40 C-101 C-101 C-240 C-240 C-249a C-249a C-259 C-259 C-292 C-292 C-326 C-326 C-334 C-334 C-340 C-340 C-356 C-356 C-371 C-371 C-421 C-421 (7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, for Changes and SNC shall report the change to the Director of NRO, or the designee, in accordance with 10 CFR 50.59(d). (b) SNC shall report any violation of a requirement in Section 2.D.(3), Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73. (8) Incorporation The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively of this license, as revised through Amendment No. 156, are hereby incorporated into this license. (9) Technical Specifications The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g). (10) Operational Program Implementation SNC shall implement the programs or portions of programs identified below, on or before the date SNC achieves the following milestones: (a) Environmental Qualification Program implemented before initial fuel load; (b) Reactor Vessel Material Surveillance Program implemented before initial criticality; (c) Preservice Testing Program implemented before initial fuel load; (d) Containment Leakage Rate Testing Program implemented before initial fuel load; (e) Fire Protection Program 1. The fire protection measures in accordance with Regulatory Guide (RG) 1.189 for designated storage building areas (including adjacent fire areas that could affect the storage area) implemented before initial receipt 7 Amendment No. 156
C-40 Amendment No. 156 1.4 List of Acronyms and Abbreviations The acronyms presented in this section are provided for information. ac Alternating Current AC Acceptance Criteria ADS Automatic Depressurization System AHU Air Handling Units ANS Alert and Notification System ASME American Society of Mechanical Engineers atm Atmoshpere BTU British Thermal Unit CAS Compressed and Instrument Air System CAV Cumulative Absolute Velocity cc Cubic Centimeter CCS Component Cooling Water System CDE Committed Dose Equivalent CDS Condensate System cfm Cubic Feet per Minute CFR Code of Federal Regulations Ci Curie CIM Component Interface Module CMT Core Makeup Tank CNS Containment System COL Combined License CRDM Control Rod Drive Mechanism CSA Control Support Area CST Condensate Storage Tank CVS Chemical and Volume Control System CWS Circulating Water System DAS Diverse Actuation System DBT Design Basis Threat dc Direct Current DCD Design Control Document DDS Data Display and Processing System DOS Standby Diesel Fuel Oil System D-RAP Design Reliability Assurance Program DTS Demineralized Water Treatment System DVI Direct Vessel Injection DWS Demineralized Water Transfer and Storage System EAL Emergency Action Level ECS Main ac Power System EDS Non-Class 1E dc and Uninterruptible Power Supply System EFS Communication System EGS Grounding and Lightning Protection System
C-240 Amendment No. 156 Figure 2.3.7-1 Spent Fuel Pool Cooling System C-249a Amendment No. 156 Table 2.3.9-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 427 2.3.09.04a 428 2.3.09.04b 429 2.3.09.05 2.3.10 Liquid Radwaste System Design Description The liquid radwaste system (WLS) receives, stores, processes, samples and monitors the discharge of radioactive wastewater.
C-259 Amendment No. 156 Table 2.3.11-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 450 2.3.11.02.i ii) Type tests, analyses, or a combination of type tests and analyses of seismically designed equipment will be performed. ii) A report exists and concludes that the seismically designed equipment can withstand appropriate seismic design basis loads without loss of its structural integrity function. iii) Inspection will be performed for the existence of a report verifying that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions. iii) A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions. 451 2.3.11.02.ii 452 2.3.11.02.iii 453 2.3.11.03a 454 2.3.11.03b 455 2.3.11.03c C-292 Amendment No. 156 b) c) d) a) b) c) a) b) c) d) 14.
C-326 Amendment No. 156 Figure 2.6.1-1 (Sheet 1 of 4) Main ac Power System C-334 Amendment No. 156 2.6.3 Class 1E dc and Uninterruptible Power Supply System Design Description The Class 1E dc and uninterruptible power supply system (IDS) provides dc and uninterruptible ac electrical power for safety-related equipment during normal and off-normal conditions. The IDS is as shown in Figure 2.6.3-1 and the component locations of the IDS are as shown in Table 2.6.3-4. 1. 2. 3. 4. a) b) c) d) e) f) g) h) i) j) 5. a) b) c)
C-340 Amendment No. 156 Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 599 2.6.03.02.iii 600 2.6.03.03 601 2.6.03.04a 602 2.6.03.04b 603 2.6.03.04c C-356 Amendment No. 156 Table 2.6.6-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 637 2.6.06.01.i 638 2.6.06.01.ii C-371 Amendment No. 156 Table 2.7.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 677 2.7.01.01 678 2.7.01.02a 2.b) The piping identified in Table 2.7.1-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
C-421 Amendment No. 156 Note 1: Dash () indicates not applicable. Note 2: Cables from this division in this fire area are limited to interdivisional cables terminating in this fire area. Table 3.3-4 is not used.