ML18152B272
| ML18152B272 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/28/2018 |
| From: | NRC/NRO/DNRL/LB4 |
| To: | Southern Nuclear Engineering |
| gleaves b/415-5848 | |
| Shared Package | |
| ML18152B267 | List: |
| References | |
| EPID L-2017-LLA-0096 | |
| Download: ML18152B272 (5) | |
Text
ATTACHMENT TO LICENSE AMENDMENT NO. 129 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-393 C-393 C-394 C-394 C-400 C-400
(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. 129, 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. 129
C-393 Amendment No. 129 2.7.5 Radiologically Controlled Area Ventilation System Design Description The radiologically controlled area ventilation system (VAS) serves the fuel handling area of the auxiliary building, and the radiologically controlled portions of the auxiliary and annex buildings, except for the health physics and hot machine shop areas, which are provided with a separate ventilation system (VHS). The VAS consists of two subsystems: the auxiliary/annex building ventilation subsystem and the fuel handling area ventilation subsystem. The subsystems provide ventilation to maintain occupied areas, and access and equipment areas within their design temperature range. They provide outside air for plant personnel and prevent the unmonitored release of airborne radioactivity to the atmosphere or adjacent plant areas. The VAS automatically isolates selected building areas by closing the supply and exhaust duct isolation dampers and starts the containment air filtration system (VFS) when high airborne radioactivity in the exhaust air duct or high ambient pressure differential is detected.
The component locations of the VAS are as shown in Table 2.7.5-3.
- 1. The functional arrangement of the VAS is as described in the Design Description of this Section 2.7.5.
- 2. The VAS maintains each building area at a slightly negative pressure relative to the atmosphere or adjacent clean plant areas.
- 3. Displays of the parameters identified in Table 2.7.5-1 can be retrieved in the main control room (MCR).
Table 2.7.5-1 Equipment Tag No.
Display Control Function Fuel Handling Area Pressure Differential Indicator VAS-030 Yes Annex Building Pressure Differential Indicator VAS-032 Yes Auxiliary Building Pressure Differential Indicator VAS-033 Yes Auxiliary Building Pressure Differential Indicator VAS-034 Yes Note: Dash (-) indicates not applicable.
Table 2.7.5-2 Inspections, Tests, Analyses, and Acceptance Criteria No.
ITAAC No.
Design Commitment Inspections, Tests, Analyses Acceptance Criteria 718 2.7.05.01
- 1. The functional arrangement of the VAS is as described in the Design Description of this Section 2.7.5.
Inspection of the as-built system will be performed.
The as-built VAS conforms with the functional arrangement described in the Design Description of this Section 2.7.5.
C-394 Amendment No. 129 Table 2.7.5-2 Inspections, Tests, Analyses, and Acceptance Criteria No.
ITAAC No.
Design Commitment Inspections, Tests, Analyses Acceptance Criteria 719 2.7.05.02.i
- 2. The VAS maintains each building area at a slightly negative pressure relative to the atmosphere or adjacent clean plant areas.
i) Testing will be performed to confirm that the VAS maintains each building at a slightly negative pressure when operating all VAS supply AHUs and all VAS exhaust fans.
i) The time average pressure differential in the served areas of the annex, fuel handling and radiologically controlled auxiliary buildings as measured by each of the instruments identified in Table 2.7.5-1 is negative.
ii) Testing will be performed to confirm the ventilation flow rate through the auxiliary building fuel handling and rail car bay/solid radwaste system areas when operating all VAS supply AHUs and all VAS exhaust fans.
ii) A report exists and concludes that the calculated exhaust flow rate based on the measured flow rates is greater than or equal to 10,710 cfm.
iii) Testing will be performed to confirm the auxiliary building radiologically controlled area ventilation flow rate when operating all VAS supply AHUs and all VAS exhaust fans.
iii) A report exists and concludes that the calculated exhaust flow rate based on the measured flow rates is greater than or equal to 22,500 cfm.
- 3. Displays of the parameters identified in Table 2.7.5-1 can be retrieved in the MCR.
Inspection will be performed for retrievability of the parameters in the MCR.
The displays identified in Table 2.7.5-1 can be retrieved in the MCR.
720 2.7.05.02.ii Not used per Amendment No. 113 721 2.7.05.02.iii Not used per Amendment No. 113 722 2.7.05.03 Not used per Amendment No. 113
C-400 Amendment No. 129 Table 2.7.7-3 Component Name Tag No.
Component Location Reactor Containment Recirculation Fan Coil Unit Assembly A VCS-MS-01A Containment Reactor Containment Recirculation Fan Coil Unit Assembly B VCS-MS-01B Containment Reactor Containment Recirculation Fan Coil Unit Assembly C VCS-MS-01C Containment Reactor Containment Recirculation Fan Coil Unit Assembly D VCS-MS-01D Containment 2.7.8 Radwaste Building HVAC System No ITAAC for this system.
2.7.9 Turbine Island Building Ventilation System No entry for this system.
2.7.10 Health Physics and Hot Machine Shop HVAC System No ITAAC for this system.
2.7.11 Hot Water Heating System No entry for this system.
3.0 Non-System Based Design Descriptions and ITAAC 3.1 Emergency Response Facilities Design Description The technical support center (TSC) is a facility from which management and technical support is provided to main control room (MCR) personnel during emergency conditions. The operations support center (OSC) provides an assembly area where operations support personnel report in an emergency. The control support area (CSA) is an area nearby the main control room from which support can be provided to the main control room.
- 1. The TSC has floor space of at least 75 ft2 per person for a minimum of 25 persons.
- 2. The TSC has voice communication equipment for communication with the MCR, emergency operations facility, OSC, and the U.S. Nuclear Regulatory Commission (NRC).
- 3. The plant parameters listed in Table 2.5.4-1, minimum inventory table, in subsection 2.5.4, Data Display and Processing System (DDS), with a "Yes" in the "Display" column, can be retrieved in the TSC.
- 6. The CSA provides a habitable workspace environment.