ML18220B103
| ML18220B103 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/24/2018 |
| From: | Manny Comar NRC/NRO/DLSE/LB1 |
| To: | Whitley B Southern Nuclear Operating Co |
| Comar M/415-3863 | |
| Shared Package | |
| ML18220B095 | List: |
| References | |
| EPID L-2018-LLA-0115 LAR 18-014 | |
| Download: ML18220B103 (3) | |
Text
ATTACHMENT TO LICENSE AMENDMENT NO. 139 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-255 C-255
(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. 139, 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. 139
C-255 Amendment No. 139 Table 2.3.10-4 Inspections, Tests, Analyses, and Acceptance Criteria No.
ITAAC No.
Design Commitment Inspections, Tests, Analyses Acceptance Criteria 440 2.3.10.05b Not used per Amendment No. 85 441 2.3.10.06a Not used per Amendment No. 85 442 2.3.10.06b Not used per Amendment No. 85 443 2.3.10.07a.i Not used per Amendment No. 112 444 2.3.10.07a.ii 7.a) The WLS provides the nonsafety-related function of detecting leaks within containment to the containment sump.
i) Inspection will be performed for retrievability of the displays of containment sump level channels WLS-034, WLS-035, and WLS-036 in the MCR.
i) Nonsafety-related displays of WLS containment sump level channels WLS-034, WLS-035, and WLS-036 can be retrieved in the MCR.
ii) Testing will be performed by adding water to the sump and observing display of sump level.
ii) A report exists and concludes that sump level channels WLS-034, WLS-035, and WLS-036 can detect a change of 1.34 +/- 0.5 inches.
7.b) The WLS provides the nonsafety-related function of controlling releases of radioactive materials in liquid effluents.
Tests will be performed to confirm that a simulated high radiation signal from the discharge radiation monitor, WLS-RE-229, causes the discharge isolation valve WLS-PL-V223 to close.
A simulated high radiation signal causes the discharge control isolation valve WLS-PL-V223 to close.
- 8. Controls exist in the MCR to cause the remotely operated valve identified in Table 2.3.10-3 to perform its active function.
Stroke testing will be performed on the remotely operated valve listed in Table 2.3.10-3 using controls in the MCR.
Controls in the MCR operate to cause the remotely operated valve to perform its active function.
- 9. The check valves identified in Table 2.3.10-1 perform an active safety-related function to change position as indicated in the table.
Exercise testing of the check valves with active safety functions identified in Table 2.3.10-1 will be performed under pre-operational test pressure, temperature and flow conditions.
Each check valve changes position as indicated on Table 2.3.10-1.
- 10. Displays of the parameters identified in Table 2.3.10-3 can be retrieved in the MCR.
Inspection will be performed for retrievability of the displays identified in Table 2.3.10-3 in the MCR.
Displays identified in Table 2.3.10-3 can be retrieved in the MCR.
445 2.3.10.07b Not used per Amendment No. 112 446 2.3.10.08 Not used per Amendment No. 112 447 2.3.10.09 Not used per Amendment No. 112