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| issue date = 02/01/2018
| issue date = 02/01/2018
| title = Attachment to License Amendment No. 108 for the Main Control Room Emergency Habitability System Changes to Satisfy Post Actuation Performance Requirements (LAR 17-001) for Vogtle Electric Generating Plant Unit 3
| title = Attachment to License Amendment No. 108 for the Main Control Room Emergency Habitability System Changes to Satisfy Post Actuation Performance Requirements (LAR 17-001) for Vogtle Electric Generating Plant Unit 3
| author name = Patel C P
| author name = Patel C
| author affiliation = NRC/NRO/DNRL/LB4
| author affiliation = NRC/NRO/DNRL/LB4
| addressee name = Whitley B H
| addressee name = Whitley B
| addressee affiliation = Southern Nuclear Operating Co, Inc
| addressee affiliation = Southern Nuclear Operating Co, Inc
| docket = 05200025
| docket = 05200025
Line 15: Line 15:
| page count = 15
| page count = 15
| project = CAC:RP9629, EPID:L-2017-LLA-0145
| project = CAC:RP9629, EPID:L-2017-LLA-0145
| stage = Other
| stage = Acceptance Review
}}
}}


=Text=
=Text=
{{#Wiki_filter:ATTACHMENT TO LICENSE AMENDMENT NO. 108 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 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-91 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,  for Changes and  SNC shall report the change to the Director of NRO, or the  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 hours. 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. 108, 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. 108 
{{#Wiki_filter:ATTACHMENT TO LICENSE AMENDMENT NO. 108 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 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-91 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


C-168 Amendment No. 108  b) c)  d)          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.
(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).
C-169 Amendment No. 108             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 -                                                                                                     Note: Dash (-) indicates not applicable.
(b)  SNC shall report any violation of a requirement in Section 2.D.(3),
C-172 Amendment No. 108                                                               Temporary Instrument Isolation Valve A VES-PL-V018 Yes Yes No -/- No No Transfer Open - Temporary Instrument Isolation Valve B VES-PL-V019 Yes Yes No -/- No No Transfer Open -
Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within [[estimated NRC review hours::24 hours]]. 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.
C-175 Amendment No. 108                                  23.5 (hour 0 to 0.5) 14.5 (hour 0.5 to 3.5) 4.75 (hour 3.5 through 24) 3.95                   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 C-178 Amendment No. 108 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            271 2.2.05.07d    272 2.2.05.08    273 2.2.05.09a    274 2.2.05.09b      877 2.2.05.09c 9.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. Testing will be performed on the MCR Load Shed Panels listed in Table 2.2.5-1 using real or simulated signals into the PMS. The MCR Load Shed Panels identified in Table 2.2.5-1 perform their active safety function identified in the table after receiving a signal from the PMS.
(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. 108, are hereby incorporated into this license.
C-294 Amendment No. 108                                                  
(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. 108
 
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    [[estimated NRC review hours::72 hours]] in MODE 1, 2, 3, or 4.              monitors are OPERABLE.
AND A.2      Verify main control room      [[estimated NRC review hours::72 hours]] isolation, air supply initiation, and electrical load de-energization manual controls are OPERABLE.
B. One channel inoperable    B.1      Restore channel to            [[estimated NRC review hours::72 hours]] during movement of                  OPERABLE status.
irradiated fuel assemblies.
C. Required Action and      C.1      Be in MODE 3.                  [[estimated NRC review hours::6 hours]] associated Completion Time of Condition A not  AND met.
C.2      Be in MODE 5.                  [[estimated NRC review hours::36 hours]] 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              [[estimated NRC review hours::72 hours]] 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            [[estimated NRC review hours::24 hours]] 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    [[estimated NRC review hours::24 hours]] 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      [[estimated NRC review hours::2 hours]] tanks inoperable.              tanks contain
                                    > 245,680 scf of              AND compressed air.
Once per [[estimated NRC review hours::12 hours]] thereafter AND E.2    Verify VBS MCRE ancillary    [[estimated NRC review hours::24 hours]] 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.                [[estimated NRC review hours::6 hours]] and associated Completion Time of      AND Condition A, B, C, D, or E not met in        F.2    Be in MODE 5.                [[estimated NRC review hours::36 hours]] 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          [[estimated NRC review hours::24 hours]]
                  > 327,574 scf of compressed air.
SR 3.7.6.2      Verify thermal mass for the following heat sink          [[estimated NRC review hours::24 hours]] 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. 108
 
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. 108
 
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. 108
 
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. 108
 
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. 108
 
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. 108}}

Latest revision as of 03:29, 8 March 2020

Attachment to License Amendment No. 108 for the Main Control Room Emergency Habitability System Changes to Satisfy Post Actuation Performance Requirements (LAR 17-001) for Vogtle Electric Generating Plant Unit 3
ML18011A892
Person / Time
Site: Vogtle Southern Nuclear icon.png
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:
References
CAC RP9629, EPID L-2017-LLA-0145, LAR 17-001
Download: ML18011A892 (15)


Text

ATTACHMENT TO LICENSE AMENDMENT NO. 108 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 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-91 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 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. 108, 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. 108

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 hours3 days <br />0.429 weeks <br />0.0986 months <br /> in MODE 1, 2, 3, or 4. monitors are OPERABLE.

AND A.2 Verify main control room 72 hours3 days <br />0.429 weeks <br />0.0986 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 hours3 days <br />0.429 weeks <br />0.0986 months <br /> during movement of OPERABLE status.

irradiated fuel assemblies.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> associated Completion Time of Condition A not AND met.

C.2 Be in MODE 5. 36 hours1.5 days <br />0.214 weeks <br />0.0493 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 hours3 days <br />0.429 weeks <br />0.0986 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 hours1 days <br />0.143 weeks <br />0.0329 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 hours1 days <br />0.143 weeks <br />0.0329 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 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> tanks inoperable. tanks contain

> 245,680 scf of AND compressed air.

Once per 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> thereafter AND E.2 Verify VBS MCRE ancillary 24 hours1 days <br />0.143 weeks <br />0.0329 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 hours0.25 days <br />0.0357 weeks <br />0.00822 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 hours1.5 days <br />0.214 weeks <br />0.0493 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 hours1 days <br />0.143 weeks <br />0.0329 months <br />

> 327,574 scf of compressed air.

SR 3.7.6.2 Verify thermal mass for the following heat sink 24 hours1 days <br />0.143 weeks <br />0.0329 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. 108

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. 108

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. 108

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. 108

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. 108

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. 108