ML19003A484: Difference between revisions
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{{#Wiki_filter:}} | {{#Wiki_filter:ATTACHMENT TO LICENSE AMENDMENT NO. 152 TO FACILITY COMBINED LICENSE NO. NPF-91 DOCKET NO. 52-025 Replace the following pages of the Facility Combined License No. NPF-91 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-91 REMOVE INSERT 7 7 Appendix C to Facility Combined License No. NPF-91 REMOVE INSERT C-226 C-226 (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. 152, 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. 152 C-226 Amendment No. 152 Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 375 2.3.06.09b.ii iii) Inspection will be performed of the reactor coolant loop piping. iii) The RCS cold legs piping centerline is 17.5 inches +/- 2 inches above the hot legs piping centerline. iv) Inspection will be performed of the RNS pump suction piping. iv) The RNS pump suction piping from the hot leg to the pump suction piping low point does not form a local high point (defined as an upward slope with a vertical rise greater than 3 inches). v) Inspection will be performed of the RNS pump suction nozzle connection to the RCS hot leg. v) The RNS suction line connection to the RCS is constructed from 20-inch Schedule 140 pipe. 9.c) The RNS provides low pressure makeup flow from the cask loading pit to the RCS for scenarios following actuation of the ADS. Testing will be performed to confirm that the RNS can provide low pressure makeup flow from the cask loading pit to the RCS when the pump suction is aligned to the cask loading pit and the discharge is aligned to both PXS DVI lines with RCS at atmospheric pressure. When tested individually, each RNS pump provides at least 1100 gpm net flow to the RCS with the water level maintained within the range of > 10 ft and < 15 ft from the bottom of the cask loading pit. 9.d) The RNS provides heat removal from the in-containment refueling water storage tank (IRWST). Testing will be performed to confirm that the RNS can provide flow through the RNS heat exchangers when the pump suction is aligned to the IRWST and the discharge is aligned to the IRWST. Two operating RNS pumps provide at least 2000 gpm to the IRWST. 12.a) The motor-operated and check valves identified in Table 2.3.6-1 perform an active safety-related function to change position as indicated in the table. iii) Tests of the motor-operated valves will be performed under preoperational flow, differential pressure and temperature conditions. iii) Each motor-operated valve changes position as indicated in Table 2.3.6-1 under preoperational test conditions.}} | ||
Revision as of 03:45, 22 February 2019
| ML19003A484 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/28/2019 |
| From: | Office of New Reactors |
| To: | Southern Nuclear Operating Co |
| PATEL C/415-3025 | |
| Shared Package | |
| ML19003A479 | List: |
| References | |
| EPID L-2018-LLA--0205, LAR 18-016 | |
| Download: ML19003A484 (3) | |
Text
ATTACHMENT TO LICENSE AMENDMENT NO. 152 TO FACILITY COMBINED LICENSE NO. NPF-91 DOCKET NO.52-025 Replace the following pages of the Facility Combined License No. NPF-91 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-91 REMOVE INSERT 7 7 Appendix C to Facility Combined License No. NPF-91 REMOVE INSERT C-226 C-226 (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. 152, 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. 152 C-226 Amendment No. 152 Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 375 2.3.06.09b.ii iii) Inspection will be performed of the reactor coolant loop piping. iii) The RCS cold legs piping centerline is 17.5 inches +/- 2 inches above the hot legs piping centerline. iv) Inspection will be performed of the RNS pump suction piping. iv) The RNS pump suction piping from the hot leg to the pump suction piping low point does not form a local high point (defined as an upward slope with a vertical rise greater than 3 inches). v) Inspection will be performed of the RNS pump suction nozzle connection to the RCS hot leg. v) The RNS suction line connection to the RCS is constructed from 20-inch Schedule 140 pipe. 9.c) The RNS provides low pressure makeup flow from the cask loading pit to the RCS for scenarios following actuation of the ADS. Testing will be performed to confirm that the RNS can provide low pressure makeup flow from the cask loading pit to the RCS when the pump suction is aligned to the cask loading pit and the discharge is aligned to both PXS DVI lines with RCS at atmospheric pressure. When tested individually, each RNS pump provides at least 1100 gpm net flow to the RCS with the water level maintained within the range of > 10 ft and < 15 ft from the bottom of the cask loading pit. 9.d) The RNS provides heat removal from the in-containment refueling water storage tank (IRWST). Testing will be performed to confirm that the RNS can provide flow through the RNS heat exchangers when the pump suction is aligned to the IRWST and the discharge is aligned to the IRWST. Two operating RNS pumps provide at least 2000 gpm to the IRWST. 12.a) The motor-operated and check valves identified in Table 2.3.6-1 perform an active safety-related function to change position as indicated in the table. iii) Tests of the motor-operated valves will be performed under preoperational flow, differential pressure and temperature conditions. iii) Each motor-operated valve changes position as indicated in Table 2.3.6-1 under preoperational test conditions.