ML18011A892
| ML18011A892 | |
| 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: |
| 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 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. 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)
- 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 VEGP Units 3 and 4 3.3.13 - 1 Amendment No. 108 (Unit 3)
Amendment No. 107 (Unit 4) 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 in MODE 1, 2, 3, or 4.
A.1 Verify alternate radiation monitors are OPERABLE.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND A.2 Verify main control room isolation, air supply initiation, and electrical load de-energization manual controls are OPERABLE.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B.
One channel inoperable during movement of irradiated fuel assemblies.
B.1 Restore channel to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C.
Required Action and associated Completion Time of Condition A not met.
OR Two channels inoperable in MODE 1, 2, 3, or 4.
C.1 AND C.2 Be in MODE 3.
Be in MODE 5.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours
Technical Specifications ESFAS Actuation Logic
- Shutdown 3.3.16 VEGP Units 3 and 4 3.3.16 - 1 Amendment No. 108 (Unit 3)
Amendment No. 107 (Unit 4) 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 within one required division inoperable.
A.1 Restore required division to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
Technical Specifications VES 3.7.6 VEGP Units 3 and 4 3.7.6 - 1 Amendment No. 108 (Unit 3)
Amendment No. 107 (Unit 4) 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 inoperable.
A.1 Restore valve or damper to OPERABLE status.
7 days B.
One PMS Division inoperable in one or more MCR load shed panel(s).
B.1 Restore PMS division in both MCR load shed panels to OPERABLE status.
7 days C.
Thermal mass of one or more required heat sink(s) not within limit(s).
C.1 Restore required heat sink air temperatures to within limit(s).
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND C.2 Restore thermal mass of required heat sink(s) to within limit(s).
5 days
Technical Specifications VES 3.7.6 VEGP Units 3 and 4 3.7.6 - 2 Amendment No. 108 (Unit 3)
Amendment No. 107 (Unit 4)
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.
VES inoperable due to inoperable MCRE boundary in MODE 1, 2, 3, or 4.
D.1 AND Initiate action to implement mitigating actions.
Immediately D.2 Verify mitigating actions ensure MCRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND D.3 Restore MCRE boundary to OPERABLE status.
90 days E.
One bank of VES air tanks inoperable.
E.1 Verify that the OPERABLE tanks contain
> 245,680 scf of compressed air.
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> AND 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 fans and supporting equipment are available.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND E.3 Restore VES to OPERABLE status.
7 days
Technical Specifications VES 3.7.6 VEGP Units 3 and 4 3.7.6 - 3 Amendment No. 108 (Unit 3)
Amendment No. 107 (Unit 4)
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME F.
Required Action and associated Completion Time of Condition A, B, C, D, or E not met in 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.
F.1 AND F.2 Be in MODE 3.
Be in MODE 5.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours G.
Required Action and associated Completion Time of Condition A, B, C, or E not met during movement of irradiated fuel.
G.1 Suspend movement of irradiated fuel assemblies.
Immediately 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.
Technical Specifications VES 3.7.6 VEGP Units 3 and 4 3.7.6 - 4 Amendment No. 108 (Unit 3)
Amendment No. 107 (Unit 4)
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify the compressed air storage tanks contain
> 327,574 scf of compressed air.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 3.7.6.2 Verify thermal mass for the following heat sink 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.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 in an open position.
31 days SR 3.7.6.5 Verify the air quality of the air storage tanks meets the requirements of Appendix C, Table C-1 of ASHRAE Standard 62 with a pressure dew point of 40°F at 3400 psig.
92 days SR 3.7.6.6 Verify all MCRE isolation valves are OPERABLE and will close upon receipt of an actual or simulated actuation signal.
24 months SR 3.7.6.7 Verify each VES pressure relief isolation valve within the MCRE pressure boundary is OPERABLE.
In accordance with the Inservice Testing Program SR 3.7.6.8 Verify each VES pressure relief damper is OPERABLE.
24 months
Technical Specifications VES 3.7.6 VEGP Units 3 and 4 3.7.6 - 5 Amendment No. 108 (Unit 3)
Amendment No. 107 (Unit 4)
SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.7.6.9 Verify the self-contained pressure regulating valve in each VES air delivery flow path is OPERABLE.
In accordance with the Inservice Testing Program SR 3.7.6.10 Perform required MCRE unfiltered air inleakage testing in accordance with the Main Control Room Envelope Habitability Program.
In accordance with the Main Control Room Envelope Habitability Program SR 3.7.6.11 Perform required VES Passive Filtration system filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with the VFTP SR 3.7.6.12 Verify the MCR load shed function actuates upon receipt of an actual or simulated actuation signal.
24 months SR 3.7.6.13 Verify each VES main air delivery isolation valve actuates to the correct position upon receipt of an actual or simulated actuation signal.
24 months
C-168 Amendment No. 108 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-169 Amendment No. 108 Table 2.2.5-1 Equipment Name Tag No.
ASME Code Section III Seismic Cat. I Remotely Operated Valve Class 1E/
Qual. for Harsh Envir.
Safety-Related Display Control PMS Active Function Loss of Motive Power 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 Tank 01 VES-MT-01 No Yes
-/-
Emergency Air Storage Tank 02 VES-MT-02 No Yes
-/-
Emergency Air Storage Tank 03 VES-MT-03 No Yes
-/-
Emergency Air Storage Tank 04 VES-MT-04 No Yes
-/-
Emergency Air Storage Tank 05 VES-MT-05 No Yes
-/-
Emergency Air Storage Tank 06 VES-MT-06 No Yes
-/-
Emergency Air Storage Tank 07 VES-MT-07 No Yes
-/-
Emergency Air Storage Tank 08 VES-MT-08 No Yes
-/-
Emergency Air Storage Tank 09 VES-MT-09 No Yes
-/-
Emergency Air Storage Tank 10 VES-MT-10 No Yes
-/-
Note: Dash (-) indicates not applicable.
C-172 Amendment No. 108 Table 2.2.5-1 (cont.)
Equipment Name Tag No.
ASME Code Section III Seismic Cat. I Remotely Operated Valve Class 1E/
Qual. for Harsh Envir.
Safety-Related Display Control PMS Active Function Loss of Motive Power Position Eductor Bypass Isolation Valve VES-PL-V046 Yes Yes No
-/-
No Transfer Open Pressure Regulating Valve A VES-PL-V002A Yes Yes No
-/-
No Throttle Flow Pressure Regulating Valve B VES-PL-V002B Yes Yes No
-/-
No Throttle Flow MCR Air Delivery Isolation Valve A VES-PL-V005A Yes Yes Yes Yes/No No Yes Transfer Open Open MCR Air Delivery Isolation Valve B VES-PL-V005B Yes Yes Yes Yes/No No Yes Transfer Open Open 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 MCR Pressure Relief Isolation Valve A VES-PL-V022A Yes Yes Yes Yes/No No Yes Transfer Open Open MCR Pressure Relief Isolation Valve B VES-PL-V022B Yes Yes Yes Yes/No No Yes Transfer Open Open
C-175 Amendment No. 108 Table 2.2.5-2 Line Name Line Number ASME Code Section III Functional Capability 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 Room Name Room Numbers Heat Load 0 to 24 Hours (Btu/s)
Heat Load 24 to 72 Hours (Btu/s)
MCR Envelope 12401 23.5 (hour 0 to 0.5) 14.5 (hour 0.5 to 3.5) 4.75 (hour 3.5 through 24) 3.95 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) 2.4 (hour 2 through 24) 0 dc Equipment Rooms 12203, 12207 5.8 (hour 0 through 1) 4.5 (hour 2 through 24) 2.0 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 VES is as described in the Design Description of this Section 2.2.5.
Inspection of the as-built system will be performed.
The as-built VES conforms with the functional arrangement described in the Design Description of this Section 2.2.5.
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 7.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.
An analysis will be performed to determine that the heat loads from as-built equipment within the rooms identified in Table 2.2.5-4 are less than or equal to the design basis assumptions.
A report exists and concludes that: the heat loads within rooms identified in Table 2.2.5-4 are less than or equal to the specified values or that an analysis report exists that 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 recirculation flow of MCR air to maintain main control room dose rates below an acceptable level during VES operation.
Testing will be performed to confirm that the required amount of air flow circulates through the MCR passive filtration system.
The air flow rate at the outlet of the MCR passive filtration system is at least 600 cfm greater than the flow measured by VES-003A/B.
272 2.2.05.08
- 8. Safety-related displays identified in Table 2.2.5-1 can be retrieved in the MCR.
Inspection will be performed for retrievability of the safety-related displays in the MCR.
Safety-related displays identified in Table 2.2.5-1 can be retrieved in the MCR.
273 2.2.05.09a 9.a) Controls exist in the MCR to cause remotely operated valves identified in Table 2.2.5-1 to perform their active functions.
Stroke testing will be performed on remotely operated valves identified in Table 2.2.5-1 using the controls in the MCR.
Controls in the MCR operate to cause remotely operated valves identified in Table 2.2.5-1 to perform their active safety functions.
274 2.2.05.09b 9.b) The valves identified in Table 2.2.5-1 as having PMS control perform their active safety function after receiving a signal from the PMS.
Testing will be performed on remotely operated valves listed in Table 2.2.5-1 using real or simulated signals into the PMS.
The remotely operated valves identified in Table 2.2.5-1 as having PMS control perform 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 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.
C-294 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