ML18011A893

Attachment to License Amendment No. 107 for the Main Control Room Emergency Habitability System Changes to Satisfy Post Actuation Performance Requirements (LAR 17-001) for Vogtle Electric Generating Plant Unit 4

ML18011A893
Person / Time
Site:	Vogtle
Issue date:	02/01/2018
From:	Chandu Patel NRC/NRO/DNRL/LB4
To:	Whitley B Southern Nuclear Operating Co
PATEL C/415-3025
Shared Package
ML18011A885	List: ML18011A886 ML18011A888 ML18011A889 ML18011A890 ML18011A891 ML18011A892 ML18011A893 ML18011A894
References
CAC RP9639, EPID L-2017-LLA-0145, LAR 17-001
Download: ML18011A893 (15)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 107 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 A to Facility Combined License Nos. NPF-91 and NPF-92 REMOVE INSERT 3.3.13-1 3.3.13-1 3.3.16-1 3.3.16-1 3.7.6-1 3.7.6-1 3.7.6-2 3.7.6-2 3.7.6-3 3.7.6-3 3.7.6-4 3.7.6-4

--- 3.7.6-5 Appendix C to Facility Combined License No. NPF-92 REMOVE INSERT C-168 C-168 C-169 C-169 C-172 C-172 C-175 C-175 C-178 C-178 C-294 C-294

(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 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. 107, 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. 107

Technical Specifications ESFAS Control Room Air Supply Radiation Instrumentation 3.3.13 3.3 INSTRUMENTATION 3.3.13 Engineered Safety Feature Actuation System (ESFAS) Control Room Air Supply Radiation Instrumentation LCO 3.3.13 Two channels of ESFAS Control Room Air Supply Radiation - High 2 instrumentation shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel inoperable A.1 Verify alternate radiation 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in MODE 1, 2, 3, or 4. monitors are OPERABLE.

AND A.2 Verify main control room 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> isolation, air supply initiation, and electrical load de-energization manual controls are OPERABLE.

B. One channel inoperable B.1 Restore channel to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during movement of OPERABLE status.

irradiated fuel assemblies.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.

C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR Two channels inoperable in MODE 1, 2, 3, or 4.

VEGP Units 3 and 4 3.3.13 - 1 Amendment No. 108 (Unit 3)

Amendment No. 107 (Unit 4)

Technical Specifications ESFAS Actuation Logic

- Shutdown 3.3.16 3.3 INSTRUMENTATION 3.3.16 Engineered Safety Feature Actuation System (ESFAS) Actuation Logic -

Shutdown LCO 3.3.16 Four divisions with one subsystem for each of the following Functions shall be OPERABLE:

a. ESF Coincidence Logic; and

b. ESF Actuation.

---

- NOTE -

Only the divisions necessary to support Main Control Room Isolation, Air Supply Initiation, and Electrical Load De-energization are required to be OPERABLE during movement of irradiated fuel assemblies when not in MODE 1, 2, 3, 4, 5, or 6.

---

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS

- NOTE -

Separate condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required division 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> within one required to OPERABLE status.

division inoperable.

VEGP Units 3 and 4 3.3.16 - 1 Amendment No. 108 (Unit 3)

Amendment No. 107 (Unit 4)

Technical Specifications VES 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Main Control Room Emergency Habitability System (VES)

LCO 3.7.6 The VES shall be OPERABLE.

---

- NOTE -

The main control room envelope (MCRE) boundary may be opened intermittently under administrative control.

---

APPLICABILITY: MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One valve or damper A.1 Restore valve or damper to 7 days inoperable. OPERABLE status.

B. One PMS Division B.1 Restore PMS division in 7 days inoperable in one or both MCR load shed more MCR load shed panels to OPERABLE panel(s). status.

C. Thermal mass of one or C.1 Restore required heat sink 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> more required heat air temperatures to within sink(s) not within limit(s).

limit(s).

AND C.2 Restore thermal mass of 5 days required heat sink(s) to within limit(s).

VEGP Units 3 and 4 3.7.6 - 1 Amendment No. 108 (Unit 3)

Amendment No. 107 (Unit 4)

Technical Specifications VES 3.7.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. VES inoperable due to D.1 Initiate action to implement Immediately inoperable MCRE mitigating actions.

boundary in MODE 1, 2, 3, or 4. AND D.2 Verify mitigating actions 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ensure MCRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.

AND D.3 Restore MCRE boundary 90 days to OPERABLE status.

E. One bank of VES air E.1 Verify that the OPERABLE 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> tanks inoperable. tanks contain

> 245,680 scf of AND compressed air.

Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND E.2 Verify VBS MCRE ancillary 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> fans and supporting equipment are available.

AND E.3 Restore VES to 7 days OPERABLE status.

VEGP Units 3 and 4 3.7.6 - 2 Amendment No. 108 (Unit 3)

Amendment No. 107 (Unit 4)

Technical Specifications VES 3.7.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action F.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and associated Completion Time of AND Condition A, B, C, D, or E not met in F.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> MODE 1, 2, 3, or 4.

OR VES inoperable for reasons other than Condition A, B, C, D, or E in MODE 1, 2, 3, or 4.

G. Required Action G.1 Suspend movement of Immediately and associated irradiated fuel assemblies.

Completion Time of Condition A, B, C, or E not met during movement of irradiated fuel.

OR VES inoperable for reasons other than Condition A, B, C, or E during movement of irradiated fuel.

OR VES inoperable due to inoperable MCRE boundary during movement of irradiated fuel.

VEGP Units 3 and 4 3.7.6 - 3 Amendment No. 108 (Unit 3)

Amendment No. 107 (Unit 4)

Technical Specifications VES 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify the compressed air storage tanks contain 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

> 327,574 scf of compressed air.

SR 3.7.6.2 Verify thermal mass for the following heat sink 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> locations is within limit:

a. MCRE;

b. Each required individual room adjacent to and below MCRE;

c. Each required room-pair adjacent to and below MCRE; and

d. Room above MCRE.

SR 3.7.6.3 Operate VES for 15 minutes. 31 days SR 3.7.6.4 Verify each VES air header manual isolation valve is 31 days in an open position.

SR 3.7.6.5 Verify the air quality of the air storage tanks meets the 92 days requirements of Appendix C, Table C-1 of ASHRAE Standard 62 with a pressure dew point of 40°F at 3400 psig.

SR 3.7.6.6 Verify all MCRE isolation valves are OPERABLE and 24 months will close upon receipt of an actual or simulated actuation signal.

SR 3.7.6.7 Verify each VES pressure relief isolation valve within In accordance with the MCRE pressure boundary is OPERABLE. the Inservice Testing Program SR 3.7.6.8 Verify each VES pressure relief damper is 24 months OPERABLE.

VEGP Units 3 and 4 3.7.6 - 4 Amendment No. 108 (Unit 3)

Amendment No. 107 (Unit 4)

Technical Specifications VES 3.7.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.6.9 Verify the self-contained pressure regulating valve in In accordance with each VES air delivery flow path is OPERABLE. the Inservice Testing Program SR 3.7.6.10 Perform required MCRE unfiltered air inleakage In accordance with testing in accordance with the Main Control Room the Main Control Envelope Habitability Program. Room Envelope Habitability Program SR 3.7.6.11 Perform required VES Passive Filtration system filter In accordance with testing in accordance with the Ventilation Filter Testing the VFTP Program (VFTP).

SR 3.7.6.12 Verify the MCR load shed function actuates upon 24 months receipt of an actual or simulated actuation signal.

SR 3.7.6.13 Verify each VES main air delivery isolation valve 24 months actuates to the correct position upon receipt of an actual or simulated actuation signal.

VEGP Units 3 and 4 3.7.6 - 5 Amendment No. 108 (Unit 3)

Amendment No. 107 (Unit 4)

b) The VES maintains the MCR pressure boundary at a positive pressure with respect to the surrounding areas. There is a discharge of air through the MCR vestibule.

c) The heat loads within the MCR, the I&C equipment rooms, and the Class 1E dc equipment rooms are within design basis assumptions to limit the heatup of the rooms identified in Table 2.2.5-4.

d) The system provides a passive recirculation flow of MCR air to maintain main control room dose rates below an acceptable level during VES operation.

8. Safety-related displays identified in Table 2.2.5-1 can be retrieved in the MCR.

9. a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.2.5-1 to perform their active functions.

b) The valves identified in Table 2.2.5-1 as having protection and safety monitoring system (PMS) control perform their active safety function after receiving a signal from the PMS.

c) The MCR Load Shed Panels identified in Table 2.2.5-1 perform their active safety function after receiving a signal from the PMS.

10. After loss of motive power, the remotely operated valves identified in Table 2.2.5-1 assume the indicated loss of motive power position.

11. Displays of the parameters identified in Table 2.2.5-3 can be retrieved in the MCR.

12. The background noise level in the MCR does not exceed 65 dB(A) at the operator workstations when the VES is operating.

C-168 Amendment No. 107

Table 2.2.5-1 ASME Class 1E/ Loss of Code Remotely Qual. for Safety- Motive Section Seismic Operated Harsh Related Control Active Power Equipment Name Tag No. III Cat. I Valve Envir. Display PMS Function Position MCR Load Shed Panel 1 VES-EP-01 No Yes - Yes/No Yes Yes De-energize -

MCR Loads MCR Load Shed Panel 2 VES-EP-02 No Yes - Yes/No Yes Yes De-energize -

MCR Loads Emergency Air Storage VES-MT-01 No Yes - -/- - - - -

Tank 01 Emergency Air Storage VES-MT-02 No Yes - -/- - - - -

Tank 02 Emergency Air Storage VES-MT-03 No Yes - -/- - - - -

Tank 03 Emergency Air Storage VES-MT-04 No Yes - -/- - - - -

Tank 04 Emergency Air Storage VES-MT-05 No Yes - -/- - - - -

Tank 05 Emergency Air Storage VES-MT-06 No Yes - -/- - - - -

Tank 06 Emergency Air Storage VES-MT-07 No Yes - -/- - - - -

Tank 07 Emergency Air Storage VES-MT-08 No Yes - -/- - - - -

Tank 08 Emergency Air Storage VES-MT-09 No Yes - -/- - - - -

Tank 09 Emergency Air Storage VES-MT-10 No Yes - -/- - - - -

Tank 10 Note: Dash (-) indicates not applicable.

C-169 Amendment No. 107

Table 2.2.5-1 (cont.)

ASME Class 1E/ Loss of Code Remotely Qual. for Safety- Motive Section Seismic Operated Harsh Related Control Active Power Equipment Name Tag No. III Cat. I Valve Envir. Display PMS Function Position Eductor Bypass Isolation VES-PL-V046 Yes Yes No -/- No - Transfer -

Valve Open Pressure Regulating VES-PL-V002A Yes Yes No -/- No - Throttle -

Valve A Flow Pressure Regulating VES-PL-V002B Yes Yes No -/- No - Throttle -

Valve B Flow MCR Air Delivery VES-PL-V005A Yes Yes Yes Yes/No No Yes Transfer Open Isolation Valve A Open MCR Air Delivery VES-PL-V005B Yes Yes Yes Yes/No No Yes Transfer Open Isolation Valve B Open Temporary Instrument VES-PL-V018 Yes Yes No -/- No No Transfer -

Isolation Valve A Open Temporary Instrument VES-PL-V019 Yes Yes No -/- No No Transfer -

Isolation Valve B Open MCR Pressure Relief VES-PL-V022A Yes Yes Yes Yes/No No Yes Transfer Open Isolation Valve A Open MCR Pressure Relief VES-PL-V022B Yes Yes Yes Yes/No No Yes Transfer Open Isolation Valve B Open C-172 Amendment No. 107

Table 2.2.5-2 ASME Code Functional Capability Line Name Line Number Section III Required MCR Relief Line VES-PL-022A Yes Yes MCR Relief Line VES-PL-022B Yes Yes Table 2.2.5-3 Equipment Tag No. Display Air Storage Tank Pressure VES-001A Yes Air Storage Tank Pressure VES-001B Yes Table 2.2.5-4 Heat Load 0 to 24 Hours Heat Load 24 to 72 Hours Room Name Room Numbers (Btu/s) (Btu/s)

MCR Envelope 12401 23.5 (hour 0 to 0.5) 3.95 14.5 (hour 0.5 to 3.5) 4.75 (hour 3.5 through 24)

I&C Rooms 12301, 12305 8.8 0 I&C Rooms 12302, 12304 13.0 4.2 dc Equipment Rooms 12201, 12205 3.7 (hour 0 through 1) 0 2.4 (hour 2 through 24) dc Equipment Rooms 12203, 12207 5.8 (hour 0 through 1) 2.0 4.5 (hour 2 through 24)

Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 252 2.2.05.01 1. The functional arrangement of the Inspection of the as-built system The as-built VES conforms VES is as described in the Design will be performed. with the functional Description of this Section 2.2.5. arrangement described in the Design Description of this Section 2.2.5.

C-175 Amendment No. 107

Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 270 2.2.05.07c 7.c) The heat loads within the MCR, An analysis will be performed to A report exists and concludes the I&C equipment rooms, and the determine that the heat loads that: the heat loads within Class 1E dc equipment rooms are from as-built equipment within rooms identified in Table within design basis assumptions to limit the rooms identified in 2.2.5-4 are less than or equal the heatup of the rooms identified in Table 2.2.5-4 are less than or to the specified values or that Table 2.2.5-4. equal to the design basis an analysis report exists that assumptions. concludes:

- The temperature and humidity in the MCR remain within limits for reliable human performance for the 72-hour period.

- The maximum temperature for the 72-hour period for the I&C rooms is less than or equal to 120°F.

- The maximum temperature for the 72-hour period for the Class 1E dc equipment rooms is less than or equal to 120°F.

271 2.2.05.07d 7.d) The system provides a passive Testing will be performed to The air flow rate at the outlet recirculation flow of MCR air to confirm that the required amount of the MCR passive filtration maintain main control room dose rates of air flow circulates through the system is at least 600 cfm below an acceptable level during VES MCR passive filtration system. greater than the flow operation. measured by VES-003A/B.

272 2.2.05.08 8. Safety-related displays identified in Inspection will be performed for Safety-related displays Table 2.2.5-1 can be retrieved in the retrievability of the safety- identified in Table 2.2.5-1 can MCR. related displays in the MCR. be retrieved in the MCR.

273 2.2.05.09a 9.a) Controls exist in the MCR to cause Stroke testing will be performed Controls in the MCR operate remotely operated valves identified in on remotely operated valves to cause remotely operated Table 2.2.5-1 to perform their active identified in Table 2.2.5-1 using valves identified in Table functions. the controls in the MCR. 2.2.5-1 to perform their active safety functions.

274 2.2.05.09b 9.b) The valves identified in Testing will be performed on The remotely operated valves Table 2.2.5-1 as having PMS control remotely operated valves listed identified in Table 2.2.5-1 as perform their active safety function in Table 2.2.5-1 using real or having PMS control perform after receiving a signal from the PMS. simulated signals into the PMS. the active safety function identified in the table after receiving a signal from the PMS.

877 2.2.05.09c 9.c) The MCR Load Shed Panels Testing will be performed on the The MCR Load Shed Panels identified in Table 2.2.5-1 perform their MCR Load Shed Panels listed in identified in Table 2.2.5-1 active safety function after receiving a Table 2.2.5-1 using real or perform their active safety signal from the PMS. simulated signals into the PMS. function identified in the table after receiving a signal from the PMS.

C-178 Amendment No. 107

Table 2.5.2-3 PMS Automatically Actuated Engineered Safety Features Safeguards Actuation Containment Isolation Automatic Depressurization System (ADS) Actuation Main Feedwater Isolation Reactor Coolant Pump Trip CMT Injection Turbine Trip (Isolated signal to nonsafety equipment)

Steam Line Isolation Steam Generator Relief Isolation Steam Generator Blowdown Isolation Passive Containment Cooling Actuation Startup Feedwater Isolation Passive Residual Heat Removal (PRHR) Heat Exchanger Alignment Block of Boron Dilution Chemical and Volume Control System (CVS) Makeup Line Isolation Steam Dump Block (Isolated signal to nonsafety equipment)

Main Control Room Isolation, Air Supply Initiation, and Electrical Load De-energization Auxiliary Spray and Letdown Purification Line Isolation Containment Air Filtration System Isolation Normal Residual Heat Removal Isolation Refueling Cavity and Spent Fuel Pool Cooling System (SFS) Isolation In-Containment Refueling Water Storage Tank (IRWST) Injection IRWST Containment Recirculation CVS Letdown Isolation Pressurizer Heater Block (Isolated signal to nonsafety equipment)

Containment Vacuum Relief Table 2.5.2-4 PMS Manually Actuated Functions Reactor Trip Safeguards Actuation Containment Isolation Depressurization System Stages 1, 2, and 3 Actuation Depressurization System Stage 4 Actuation Feedwater Isolation Core Makeup Tank Injection Actuation Steam Line Isolation Passive Containment Cooling Actuation Passive Residual Heat Removal Heat Exchanger Alignment IRWST Injection Containment Recirculation Actuation Main Control Room Isolation, Air Supply Initiation, and Electrical Load De-energization Steam Generator Relief Isolation Chemical and Volume Control System Isolation Normal Residual Heat Removal System Isolation Containment Vacuum Relief C-294 Amendment No. 107