ML18152B274

LAR-16-030R1, Ventilation System Changes Amendment 128 - Attachment

ML18152B274
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: ML18152B268 ML18152B269 ML18152B270 ML18152B271 ML18152B272 ML18152B273 ML18152B274 ML18152B277
References
EPID L-2017-LLA-0096
Download: ML18152B274 (5)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 128 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-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 hours1 days <br />0.143 weeks <br />0.0329 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. 128, 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. 128

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 Inspection of the as-built system The as-built VAS conforms VAS is as described in the Design will be performed. with the functional Description of this Section 2.7.5. arrangement described in the Design Description of this Section 2.7.5.

C-393 Amendment No. 128

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 i) Testing will be performed to i) The time average pressure area at a slightly negative pressure confirm that the VAS maintains differential in the served areas relative to the atmosphere or adjacent each building at a slightly of the annex, fuel handling clean plant areas. negative pressure when and radiologically controlled operating all VAS supply AHUs auxiliary buildings as and all VAS exhaust fans. measured by each of the instruments identified in Table 2.7.5-1 is negative.

ii) Testing will be performed to ii) A report exists and confirm the ventilation flow rate concludes that the calculated through the auxiliary building exhaust flow rate based on the fuel handling and rail car measured flow rates is greater bay/solid radwaste system areas than or equal to 10,710 cfm.

when operating all VAS supply AHUs and all VAS exhaust fans.

iii) Testing will be performed to iii) A report exists and confirm the auxiliary building concludes that the calculated radiologically controlled area exhaust flow rate based on the ventilation flow rate when measured flow rates is greater operating all VAS supply AHUs than or equal to 22,500 cfm.

and all VAS exhaust fans.

3. Displays of the parameters identified Inspection will be performed for The displays identified in in Table 2.7.5-1 can be retrieved in the retrievability of the parameters Table 2.7.5-1 can be retrieved MCR. in the MCR. in the MCR.

720 2.7.05.02.ii Not used per Amendment No. 112 721 2.7.05.02.iii Not used per Amendment No. 112 722 2.7.05.03 Not used per Amendment No. 112 C-394 Amendment No. 128

Table 2.7.7-3 Component Name Tag No. Component Location Reactor Containment Recirculation Fan Coil Unit VCS-MS-01A Containment Assembly A Reactor Containment Recirculation Fan Coil Unit VCS-MS-01B Containment Assembly B Reactor Containment Recirculation Fan Coil Unit VCS-MS-01C Containment Assembly C Reactor Containment Recirculation Fan Coil Unit VCS-MS-01D Containment Assembly D 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.

4. The OSC has voice communication equipment for communication with the MCR and TSC.

5. The TSC and OSC are in different locations.

6. The CSA provides a habitable workspace environment.

C-400 Amendment No. 128