ML18018A911

Attachment 1 - VEGP U4 Amendment No. 106 (LAR-17-010)

ML18018A911
Person / Time
Site:	Vogtle
Issue date:	02/01/2018
From:	Office of New Reactors
To:	Southern Nuclear Operating Co
References
EPID No. L 2017-LLA-0143, LAR-17-010
Download: ML18018A911 (15)

Text

ATTACHMENT 1 TO LICENSE AMENDMENT NO. 106 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 9 9 Appendix C to Facility Combined License No. NPF-92 REMOVE INSERT C-43 C-43 C-204 C-204 C-205 C-205 C-206 C-206 C-208 C-208 C-209 C-209 C-251 C-251 C-252 C-252 C-253 C-253 C-256 C-256 C-420 C-420 Attachment 1 to Appendix C to Facility Combined License No. NPF-92 REMOVE INSERT C-489 C-489

(7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in FSAR 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. 106, 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. 106

(m) Initial Test Program (ITP)

1. Component Test Program implemented before the first component test;

2. Preoperational Test Program implemented before the first preoperational test; and

3. Startup Test Program implemented before initial fuel load; (n) Special Nuclear Material Control and Accounting Program implemented before initial receipt of special nuclear material; and (o) Special Nuclear Material Physical Protection Program implemented before initial receipt of special nuclear material on site.

(11) Operational Program Implementation Schedule No later than 12 months after issuance of the COL, SNC shall submit to the Director of NRO, or the Directors designee, a schedule for implementation of the operational programs listed in FSAR Table 13.4-201, including the associated estimated date for initial loading of fuel. The schedule shall be updated every 6 months until 12 months before scheduled fuel loading, and every month thereafter until all the operational programs listed in FSAR Table 13.4-201 have been fully implemented.

(12) Site- and Unit-specific Conditions (a) SNC shall either remove and replace, or shall improve, the soils directly above the blue bluff marl for soils under or adjacent to Seismic Category I structures, to eliminate any liquefaction potential.

(b) Before commencing installation of individual piping segments and connected components in their final locations, SNC shall complete the as-designed pipe rupture hazards analysis for compartments (rooms) containing those segments in accordance with the criteria outlined in the AP1000 DCD, Rev. 19, Sections 3.6.1.3.2 (as revised by Amendment No. 51 and Amendment No. 106) and 3.6.2.5, and shall inform the Director of NRO, or the Directors designee, in writing, upon the completion of this analysis and the availability of the as-designed pipe rupture hazards analysis reports.

(c) Before commencing installation of individual piping segments, identified in AP1000 DCD, Rev. 19, Section 3.9.8.7, and connected components in their final locations in the facility, SNC shall complete the analysis of the as-designed individual piping segments and shall inform the Director of NRO, or the Directors 9 Amendment No. 106

List of Acronyms and Abbreviations (cont.)

QA Quality Assurance RAP Reliability Assurance Program RAT Reserve Auxiliary Transformer RC Reinforced Concrete RCA Radiologically Controlled Area RCCA Rod Cluster Control Assembly RCDT Reactor Coolant Drain Tank RCP Reactor Coolant Pump RCS Reactor Coolant System RFI Radio Frequency Interference RM Refueling Machine RMS Radiation Monitoring System RNS Normal Residual Heat Removal System RPV Reactor Pressure Vessel RSR Remote Shutdown Room RSW Remote Shutdown Workstation RTD Resistance Temperature Detector RXS Reactor System RV Reactor Vessel SC Steel and Concrete scf Standard Cubic Feet scfm Standard Cubic Feet per Minute SDS Sanitary Drainage System SFHT Spent Fuel Handling Tool SFP Spent Fuel Pool SFS Spent Fuel Pool Cooling System SG Steam Generator SGS Steam Generator System SJS Seismic Monitoring System SMS Special Monitoring System SRS Savannah River Site SSCs Structures, Systems, and Components SSE Safe Shutdown Earthquake SWC Surge Withstand Capability SWS Service Water System TEDE Total Effective Dose Equivalent TSC Technical Support Center UAT Unit Auxiliary Transformer UPS Uninterruptible Power Supply V Volt VAS Radiologically Controlled Area Ventilation System VBS Nuclear Island Nonradioactive Ventilation System VCS Containment Recirculation Cooling System C-43 Amendment No. 106

2.3.4 Fire Protection System Design Description The fire protection system (FPS) detects and suppresses fires in the plant. The FPS consists of water distribution systems, automatic and manual suppression systems, a fire detection and alarm system, and portable fire extinguishers. The FPS provides fire protection for the nuclear island, the annex building, the turbine building, the radwaste building and the diesel generator building.

The FPS is as shown in Figure 2.3.4-1 and the component locations of the FPS are as shown in Table 2.3.4-3.

1. The functional arrangement of the FPS is as described in the Design Description of this Section 2.3.4.

2. The FPS piping shown on Figure 2.3.4-2 remains functional following a safe shutdown earthquake.

3. The FPS provides the safety-related function of preserving containment integrity by isolation of the FPS line penetrating the containment.

4. The FPS provides for manual fire fighting capability in plant areas containing safety-related equipment.

5. Displays of the parameters identified in Table 2.3.4-1 can be retrieved in the main control room (MCR).

6. The FPS provides nonsafety-related containment spray for severe accident management.

7. The FPS provides two fire water storage tanks, each capable of holding at least 100 percent of the water supply necessary for FPS use.

8. Two FPS fire pumps provide at least 2000 gpm each at a total head of at least 350 ft.

9. The fuel tank for the diesel-driven fire pump is capable of holding at least 385 gallons.

10. Individual fire detectors provide fire detection capability and can be used to initiate fire alarms in areas containing safety-related equipment.

11. The FPS seismic standpipe subsystem can be supplied from the FPS fire main by opening the normally closed cross-connect valve to the FPS plant fire main.

Table 2.3.4-1 Equipment Name Tag No. Display Control Function Motor-driven Fire Pump FPS-MP-01A Yes (Run Status) Start Diesel-driven Fire Pump FPS-MP-01B Yes (Run Status) Start Jockey Pump FPS-MP-02 Yes (Run Status) Start C-204 Amendment No. 106

Table 2.3.4-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 326 2.3.04.01 1. The functional arrangement of the Inspection of the as-built system The as-built FPS conforms FPS is as described in the Design will be performed. with the functional Description of this Section 2.3.4. arrangement described in the Design Description of this Section 2.3.4.

327 2.3.04.02.i 2. The FPS piping shown on Figure i) Inspection will be performed i) The piping shown on 2.3.4-2 remains functional following a to verify that the piping shown Figure 2.3.4-2 is located on safe shutdown earthquake. on Figure 2.3.4-2 is located on the Nuclear Island.

the Nuclear Island.

328 2.3.04.02.ii 2. The FPS piping shown on Figure ii) A reconciliation analysis ii) The as-built piping stress 2.3.4-2 remains functional following a using the as-designed and as- report exists and concludes safe shutdown earthquake. built piping information will be that the piping remains performed, or an analysis of the functional following a safe as-built piping will be shutdown earthquake.

performed.

329 2.3.04.03 Not used per Amendment No. 84 330 2.3.04.04.i 4. The FPS provides for manual fire i) Inspection of the passive i) The volume of the PCS fighting capability in plant areas containment cooling system tank above the standpipe containing safety-related equipment. (PCS) storage tank will be feeding the FPS and below the performed. overflow is at least 18,000 gal.

331 2.3.04.04.ii 4. The FPS provides for manual fire ii) Testing will be performed by ii) Water is simultaneously fighting capability in plant areas measuring the water flow rate as discharged from each of the containing safety-related equipment. it is simultaneously discharged two highest fire-hose stations from the two highest fire-hose in plant areas containing stations and when the water for safety-related equipment at the fire is supplied from the PCS not less than 75 gpm.

storage tank.

332 2.3.04.05 5. Displays of the parameters identified Inspection will be performed for The displays identified in in Table 2.3.4-1 can be retrieved in the retrievability of the parameters Table 2.3.4-1 can be retrieved MCR. in the MCR. in the MCR.

333 2.3.04.06 6. The FPS provides nonsafety-related Inspection of the containment The FPS has spray headers containment spray for severe accident spray headers will be performed. and nozzles as follows:

management. At least 44 nozzles at plant elevation of at least 260 feet, and 24 nozzles at plant elevation of at least 275 feet.

334 2.3.04.07 7. The FPS provides two fire water Inspection of each fire water The volume of water storage tanks, each capable of holding storage tank will be performed. dedicated to FPS use provided at least 100 percent of the water supply in each fire water storage tank necessary for FPS use. is at least 396,000 gallons.

C-205 Amendment No. 106

Table 2.3.4-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 335 2.3.04.08 8. Two FPS fire pumps provide at least Testing and/or analysis of each The tests and/or analysis 2000 gpm each at a total head of at least fire pump will be performed. concludes that each fire pump 350 ft. provides a flow rate of at least 2000 gpm at a total head of at least 350 ft.

336 2.3.04.09 9. The fuel tank for the diesel-driven Inspection of the diesel-driven The volume of the diesel fire pump is capable of holding at least fire pump fuel tank will be driven fire pump fuel tank is 385 gallons. performed. at least 385 gallons.

337 2.3.04.10 10. Individual fire detectors provide Testing will be performed on the The tested individual fire fire detection capability and can be used as-built individual fire detectors detectors respond to simulated to initiate fire alarms in areas containing in the fire areas identified in fire conditions.

safety-related equipment. subsection 3.3, Table 3.3-3.

(Individual fire detectors will be tested using simulated fire conditions.)

338 2.3.04.11 11. The FPS seismic standpipe Inspection for the existence of a Valve FPS-PL-V101 exists subsystem can be supplied from the cross-connect valve from the and can connect the FPS FPS fire main by opening the normally FPS seismic standpipe seismic standpipe subsystem closed cross-connect valve to the FPS subsystem to FPS plant fire main to the FPS plant fire main.

plant fire main. will be performed.

Table 2.3.4-3 Component Name Tag No. Location Motor-driven Fire Pump FPS-MP-01A Yard Diesel-driven Fire Pump FPS-MP-01B Yard Jockey Pump FPS-MP-02 Yard Primary Fire Water Tank FPS-MT-01A Yard Secondary Fire Water Tank FPS-MT-01B Yard Fire Pump Diesel Fuel Day Tank FPS-MT-02 Yard C-206 Amendment No. 106

Figure 2.3.4-1 (Sheet 1 of 2)

Fire Protection System C-208 Amendment No. 106

FROM PAsSIVE  :

CONTAINMENT COOLING :

SYSTEM STORAGE TANK :

PCS-MT -01  :

..... -- ----~- ---- - - '

I I

I TO HOSE I STATION I CTYPICAU I

I TYPICAL

'\17 X (PCS-PL-V005)

L.).

C-209 FROM FPS FIREMAIN FPS-PL-V101 TO TO CONTAINMENT CONTAINMENT SPRAY RING STANDPIPES HEADER I

Figure 2.3.4-1 (Sheet 2 of 2)

I FPS-PL-V700 I

TO OTHER STANDPIPES IN I I

SAFE SHUTDO~N AREAS I Amendment No. 106 L- - - - - - - - - - - - - - - l ' - - - - i "

..... _rL l.l...-

J --"-..

I

~*---.----l'--------'

T Fire Protection System FPS-PL-V050 FPS-Pl-V052 ORC I IRC I

AUXILIARY BUILDING I I TO CONTAINMENT I SPRAYS IN FIRE ZONE 1100-AF -1 i 3008

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.

10. Displays of the parameters identified in Table 2.3.10-3 can be retrieved in the MCR.

11. a) The Class 1E components identified in Table 2.3.10-1 are powered from their respective Class 1E division.

b) Separation is provided between WLS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.

12. Safety-related displays identified in Table 2.3.10-1 can be retrieved in the main control room (MCR).

C-251 Amendment No. 106

Table 2.3.10-1 Class 1E/

Remotely Qual. for Safety-ASME Code Seismic Operated Harsh Related Active Equipment Name Tag No.Section III Cat. I Valve Envir. Display Function WLS Containment Sump Level Sensor WLS-034 No Yes No No/No No -

WLS Containment Sump Level Sensor WLS-035 No Yes No No/No No -

WLS Containment Sump Level Sensor WLS-036 No Yes No No/No No -

WLS Drain from Passive Core Cooling WLS-PL-V071B Yes Yes No -/- No Transfer System (PXS) Compartment A (Room Closed 11206) Check Valve WLS Drain from PXS Compartment A WLS-PL-V072B Yes Yes No -/- No Transfer (Room 11206) Check Valve Closed WLS Drain from PXS Compartment B WLS-PL-V071C Yes Yes No -/- No Transfer (Room 11207) Check Valve Closed WLS Drain from PXS Compartment B WLS-PL-V072C Yes Yes No -/- No Transfer (Room 11207) Check Valve Closed WLS Drain from Chemical and Volume WLS-PL-V071A Yes Yes No -/- No Transfer Control System (CVS) Compartment Closed (Room 11209) Check Valve WLS Drain from CVS Compartment WLS-PL-V072A Yes Yes No -/- No Transfer (Room 11209) Check Valve Closed WLS Auxiliary Building Radiologically WLS-400A No Yes No Yes/No Yes -

Controlled Area (RCA) Floodup Level Sensor WLS Auxiliary Building RCA Floodup WLS-400B No Yes No Yes/No Yes -

Level Sensor Note: Dash (-) indicates not applicable.

C-252 Amendment No. 106

Table 2.3.10-2 Line Name Line No. ASME Section III Functional Capability Required WLS Drain from PXS WLS-PL-L062 Yes Yes Compartment A WLS Drain from PXS WLS-PL-L063 Yes Yes Compartment B WLS Drain from CVS WLS-PL-L061 Yes Yes Compartment Table 2.3.10-3 Equipment Name Tag No. Display Active Function WLS Effluent Discharge Isolation WLS-PL-V223 - Close Valve Reactor Coolant Drain Tank Level WLS-JE-LT002 Yes -

Letdown Flow from CVS to WLS WLS-JE-FT020 Yes -

WLS Auxiliary Building RCA WLS-400A Yes -

Floodup Level Sensor WLS Auxiliary Building RCA WLS-400B Yes -

Floodup Level Sensor Table 2.3.10-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 430 2.3.10.01 1. The functional arrangement of the Inspection of the as-built system The as-built WLS conforms WLS is as described in the Design will be performed. with the functional Description of this Section 2.3.10. arrangement as described in the Design Description of this Section 2.3.10.

431 2.3.10.02a 2.a) The components identified in Inspection will be conducted of The ASME Code Section III Table 2.3.10-1 as ASME Code Section the as-built components and design report exists for the as III are designed and constructed in piping as documented in the built components and piping accordance with ASME Code ASME design reports. identified in Tables 2.3.10-1 Section III requirements. and 2.3.10-2 as ASME Code 2.b) The piping identified in Table Section III.

2.3.10-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.

C-253 Amendment No. 106

Table 2.3.10-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 448 2.3.10.10 10. Displays of the parameters Inspection will be performed for Displays identified in identified in Table 2.3.10-3 can be retrievability of the displays Table 2.3.10-3 can be retrieved in the MCR. identified in Table 2.3.10-3 in retrieved in the MCR.

the MCR.

878 2.3.10.11a 11. a) The Class 1E components Testing will be performed on the A simulated test signal exists identified in Table 2.3.10-1 are powered WLS by providing a simulated at the Class 1E components from their respective Class 1E division. test signal in each Class 1E identified in Table 2.3.10-1 division. when the assigned Class 1E division is provided the test signal.

879 2.3.10.12 12. Safety-related displays identified in Inspection will be performed for Safety-related displays Table 2.3.10-1 can be retrieved in the retrievability of the safety- identified in Table 2.3.10-1 main control room (MCR). related displays in the MCR. can be retrieved in the MCR.

Table 2.3.10-5 Component Name Tag No. Component Location WLS Reactor Coolant Drain Tank WLS-MT-01 Containment WLS Containment Sump WLS-MT-02 Containment WLS Degasifier Column WLS-MV-01 Auxiliary Building WLS Effluent Holdup Tanks WLS-MT-05A Auxiliary Building WLS-MT-05B WLS Waste Holdup Tanks WLS-MT-06A Auxiliary Building WLS-MT-06B WLS Waste Pre-Filter WLS-MV-06 Auxiliary Building WLS Ion Exchangers WLS-MV-03 Auxiliary Building WLS-MV-04A WLS-MV-04B WLS-MV-04C WLS Waste After-Filter WLS-MV-07 Auxiliary Building WLS Monitor Tanks WLS-MT-07A Auxiliary Building WLS-MT-07B WLS-MT-07C WLS-MT-07D Radwaste Building WLS-MT-07E WLS-MT-07F C-256 Amendment No. 106

Table 3.3-2 Nuclear Island Building Room Boundaries Required to Have Flood Barrier Floors and Walls Between Room Number to Room Number Boundary/ Room with Postulated Maximum Flood Level (inches) Flooding Source Adjacent Room Floor/36 12306 12211 Floor/3 12303 12203/12207 Floor/3 12313 12203/12207 Floor/1 12300 12201/12202/12207 12203/12204/12205 Floor/3 12312 12212 Wall/36 12306 12305 Floor/1 12401 12301/12302/12303 12312/12313 Wall/1 12401 12411/12412 Floor/36 12404 12304 Floor/4 12405 12305 Floor/36 12406 12306 Wall/36 12404 12421 Wall/30 12452 12421 Floor/3 12501 12401/12411/12412 Floor/3 12555 12421/12423/12422 Wall/168 12156 12111/12112 Wall/76.5 12158 12111 Wall/132 12258 12211/12212 C-420 Amendment No. 106

Security-Related Information, Withhold Under 10 CFR 2.390 SRI Figure 3.3-11B Turbine Building General Arrangement Plan at Elevation 100-0 C-489 Amendment No. 106