ML20045F129
| ML20045F129 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/19/2020 |
| From: | Donald Habib NRC/NRR/VPOB |
| To: | |
| Don Habib EX. 1035 | |
| References | |
| EPID L-2019-LLA-0194, LAR 19-017 | |
| Download: ML20045F129 (3) | |
Text
ATTACHMENT TO LICENSE AMENDMENT NO. 176 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 C to Facility Combined License No. NPF-92 REMOVE INSERT C-131 C-131
(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, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors 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. 176, 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)
- 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. 176
C-131 Amendment No. 176 Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No.
ITAAC No.
Design Commitment Inspections, Tests, Analyses Acceptance Criteria 174 2.2.03.08a Not used per Amendment No. 84 175 2.2.03.08b.01 8.b) The PXS provides core decay heat removal during design basis events.
- 1. A heat removal performance test and analysis of the PRHR HX will be performed to determine the heat transfer from the HX. For the test, the reactor coolant hot leg temperature will be initially at 350°F with the reactor coolant pumps running.
The IRWST water level for the test will be above the top of the HX. The test will continue until the hot leg temperature is 250°F.
- 1. A report exists and concludes that the PRHR HX heat transfer rate with the design basis number of PRHR HX tubes plugged is:
8.46 x 107 Btu/hr with 250°F HL Temp and an initial IRWST temperature of 80°F.
The heat transfer rate measured in the test should be adjusted to account for differences in the HL and IRWST temperatures and the number of tubes plugged.
176 2.2.03.08b.02 8.b) The PXS provides core decay heat removal during design basis events.
- 2. The elevation of the centerline of the HXs upper channel head is greater than the HL centerline by at least 26.3 ft.
177 2.2.03.08c.i.01 8.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.
i) A low-pressure injection test and analysis for each CMT, each accumulator, each IRWST injection line, and each containment recirculation line will be conducted. Each test is initiated by opening isolation valve(s) in the line being tested.
Test fixtures may be used to simulate squib valves.
- 1. CMTs:
Each CMT will be initially filled with water. All valves in these lines will be open during the test.
i) The injection line flow resistance from each source is as follows:
- 1. CMTs:
The calculated flow resistance between each CMT and the reactor vessel is 1.81 x 10-5 ft/gpm2 and 2.25 x 10-5 ft/gpm2.