ML063390060
| ML063390060 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/04/2006 |
| From: | NRC/NRR/ADRO/DORL/LPLIV |
| To: | |
| Kalynanam N, NRR/DORL/LP4, 415-1480 | |
| Shared Package | |
| ML062980429 | List: |
| References | |
| TAC MC9232, TAC MC9233 | |
| Download: ML063390060 (20) | |
Text
(3) SCE, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of San Onofre Nuclear Generating Station, Units 1 and 2 and by the decommissioning of San Onofre Nuclear Generating Station Unit 1.
C.. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level Southern California Edison Company (SCE) is authorized to operate the facility at reactor core power levels not in excess of full power (3438 megawatts thermal)
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 208, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Amendment No. £2- 208 I
TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.5 -Engineered Safety Features Actuation System (ESFAS)
Instrumentation . . . . . . . . . . . . . . . . 3.3-22 3.3.6 Engineered Safety Features Actuation System (ESFAS)
Logic and Manual Trip ...... ............. ... 3.3-27 3.3.7 Diesel Generator (DG) -Undervoltage Start ..... ... 3.3-32 3.3.8 Containment Purge Isolation Signal (CPIS) ..... ... 3.3-35 3.3.9 Control Room Isolation Signal (CRIS) ....... . . . 3.3-39 3.3.10 Not Used 3.3.11 Post Accident Monitoring Instrumentation (PAMI) 3.3-44 3.3.12 Remote Shutdown System ........... .............. 3.3-48 3.3.13 Source Range Monitoring Channels ... ......... ... 3.3-51 3.4 REACTOR COOLANT SYSTEM (RCS).... . . ............ ... 3.4-1 3.4.1 RCS DNB Pressure, Temperature, and Flow Limits ...................... 3.4-1 3.4.2 RCS Minimum Temperature for Criticality ....... 3.4-4 3.4.3 RCS Pressure and Temperature (P/T) Limits ..... ... 3.4-5 3.4.3.1 Pressurizer Heatup/Cooldown Limits ..... ......... 3.4-13 3.4.4 RCS Loops-MODES 1 and 2 ..... .............. .. 3.4-15 3.4.5 RCS Loops-MODE 3 ....... ................. .. 3.4-16 3.4.6 RCS Loops-MODE 4 ....... .................. .. 3.4-18 3.4.7 RCS Loops-MODE 5, Loops Filled .............. ... 3.4-21 3.4.8 RCS Loops-MODE 5, Loops Not Filled ........... ... 3.4-24 3.4.9 Pressurizer .................... 3.4-26 3.4.10 Pressurizer Safety Valves ........ ........... .. 3.4-28 3.4.11 Not Used 3.4.12.1 Low Temperature Overpressure Protection (LTOP)
System, RCS Temperature
System, RCS Temperature > PTLR Limit .... ...... 3.4-35 3.4.13 RCS Operational LEAKAGE ............ . . 3.4-37 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ........ 3.4-39 3.4.15 RCS Leakage Detection Instrumentation ......... ... 3.4-44 3.4.16 RCS Specific Activity .................. .... 3.4-47 3.4.17 RCS Steam Generator (SG) Tube Integrity .... ...... 3.4-51 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ..... ......... 3.5-1 3.5.1 Safety Injection Tanks (SITs) . . ......
. ........ 3.5-1 3.5.2 ECCS-Operating ....... ..... .................. 3.5-4 3.5.3 ECCS-Shutdown . .3..... . . . . .. . . 3.5-8 3.5.4 Refueling Water Storage Tank (RWST) .... ....... . 3.5-9 3.5.5 Trisodium Phosphate (TSP) ......... ............. 3.5-11 (continued)
SAN ONOFRE--Unit 2 iii Amendment No. 204 208
TABLE OF CONTENTS 3.6 CONTAINMENT SYSTEMS ............. 3.6-1 3.6.1 Containment . . . . . . . . . . . . . . . 3.6-1 3.6.2 Containment Air Locks .......... 3.6-3 3.6.3 Containment Isolation Valves .......... 3.6-8 3.6.4 Containment Pressure ..... ........... 3.6-16 3.6.5 Containment Air Temperature . ...... 3.6-17 3.6.6.1 Containment Spray and Cooling Systems . . 3.6-18 3.6.6.2 Containment Cooling System ........... 3.6-21 3.6.7 Not Used 3.6.8 Containment Dome Air Circulators ....... . . . . 3.6-25 3.7 PLANT SYSTEMS . . . . . . . . . . . . . . . . 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) ....... 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) . . . 3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs) 3.7-7 3.7.4 Atmospheric Dump Valves (ADVs) ......... 3.7-9 3.7.5 Auxiliary Feedwater (AFW) System ....... 3.7-11 3.7.6 Condensate Storage Tank (CST T-120 and T-121) 3.7-16 3.7.7 Component Cooling Water (CCW) System . . . 3.7-18 3.7.7.1 Component Cooling Water (CCW)
Safety Related Makeup System ..... . . . . 3.7-19a 3.7.8 Salt Water Cooling (SWC) System ..... . . . . 3.7-20 3.7.9 Not Used 3.7.10 Emergency Chilled Water (ECW) ..... . . . . 3.7-22 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) ..... ................ . . . . 3.7-24 3.7.12 Not Used 3.7.13 Not Used 3.7.14 Not Used 3.7.15 Not Used 3.7.16 Fuel Storage Pool Water Level ..... . . . . 3.7-29 3.7.17 Fuel Storage Pool Boron Concentration . . . . . 3.7-30 3.7.18 Spent Fuel Assembly Storage ....... . . . . 3.7-32 3.7.19 Secondary Specific Activity ....... . . . . 3.7-35 3.8 ELECTRICAL POWER SYSTEMS .... .......... . . 3.8-1 3.8.1 AC Sources-Operating ........... 3.8-1 3.8.2 AC Sources- Shutdown ..... ............. 3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air 3.8-20 3.8.4 DC Sources-Operating ........... 3.8-23 3.8.5 DC Sources-Shutdown . . . . ... ........ 3.8-27 3.8.6 Battery Cell Parameters .......... 3.8-30 3.8.7 Inverters -Operating .... ............. 3.8-34 3.8.8 Inverters - Shutdown ............ 3.8-36 3.8.9 Distribution Systems-Operating ...... 3.8-38 3.8.10 Distribution Systems-Shutdown .......... 3.8-40 (continued)
SAN ONOFRE--Unit 2 iv Amendment No. 4-59 208
TABLE OF CONTENTS B 3.3 INSTRUMENTATION (continued)
B 3.3.7 Diesel Generator Undervoltage Start ...... B .3.3-126 B 3.3.8 Containment Purge Isolation Signal (CPIS) . . . B 3.3-135 B 3.3.9 Control Room Isolation Signal (CRIS) ......... B 3.3-145 B 3.3.10 Not Used B 3.3.11 .Post Accident Monitoring Instrumentation (PAMI) B 3.3-159 B 3.3.12 Remote Shutdown System ..... ..... ........ B 3.3-176 B 3.3.13 Source Range Monitoring Channels ............ B 3.3-181 B 3.4 REACTOR COOLANT SYSTEM (RCS) .......... B 3.4-1 B 3.4.1 RCS DNB (Pressure, Temperature, and Flow) Limits B 3.4-1 B 3.4.2 RCS Minimum Temperature for Criticality . ... B 3.4-7 B 3.4.3 RCS Pressure and Temperature (P/T) Limits . . . B 3.4-9 B 3.4.4 RCS Loops-MODES I and 2 ...... ............ B 3.4-23 B 3.4.5 RCS Loops-MODE 3 ............... B 3.4-27 B 3.4.6 RCS Loops-MODE 4 ............... B 3.4-31 B 3.4.7 RCS Loops-MODE 5, Loops Filled ........ B 3.4-36 B 3.4.8 RCS Loops-MODE 5, Loops Not Filled .... . . B 3.4-42 B 3.4.9 Pressurizer . . .. . .. . . . . . . . . . . B 3.4-46 B 3.4.10 Pressurizer Safety Valves ........ B 3.4-51 B 3.4.11 Not Used B 3.4.12.1 Low Temperature Overpressure Protection (LTOP)
System, RCS Temperature
System, RCS Temperature > PTLR Limit . ... B 3.4-65 B 3.4.13 RCS Operational LEAKAGE ............ B 3.4-70 B 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage . . . B 3.4-76 B 3.4.15 RCS Leakage Detection Instrumentation ..... B 3.4-82 B 3.4.16 RCS Specific Activity ............. B 3.4-88 B 3.4.17 RCS Steam Generator (SG) Tube Integrity B 3.4-93 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) B 3.5-1 B 3.5.1 Safety Injection Tanks (SITs) . . . B 3.5-1 B 3.5.2 ECCS -Operating .......... B 3.5-11 B 3.5.3 ECCS -Shutdown .......... B 3.5-21 B 3.5.4 Refueling Water Storage Tank (RWST) B 3.5-24 B 3.5.5 Trisodium Phosphate (TSP) . . . . . B 3.5-30 B 3.6 CONTAINMENT SYSTEMS .......... B 3.6-1 B 3.6.1 Containment . . . . . . . . . . . . B 3.6-1 B 3.6.2 Containment Air Locks ....... B 3.6-5 B 3.6.3 Containment Isolation Valves . ... B 3.6-13 B 3.6.4 Containment Pressure .. ..... .. . B 3.6-27 B 3.6.5 Containment Air Temperature . ... B 3.6-30 B 3.6.6.1 Containment Spray and Cooling System B 3.6-33 B 3.6.6.2 Containment Cooling System ....... B 3.6-43 B 3.6.7 Hydrogen Recombiners ............ B 3.6-48 B 3.6.8 Containment Dome Air Circulators . . B 3.6-53 (conti nued)
SAN ONOFRE--Unit 2 ' vii Amendment No. 2G04 208
TABLE OF CONTENTS B 3.7 PLANT SYSTEMS ...... . . B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs) . ........ B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) ..... B 3.7-7 B 3.7.3 Main Feedwater Isolation Valves (MFIVs) . . . B 3.7-13 B 3.7.4 Atmospheric Dump Valves (ADVs) .... ........ B 3.7-17 B 3.7.5 Auxiliary Feedwater (AFW) System ....... B 3.7-23 B 3.7.6 Condensate Storage Tank (CST T-121 and T-120) B 3.7-35 B 3.7.7 Component Cooling Water (CCW) System ....... B 3.7-39 B 3.7.7.1 Component Cooling Water (CCW)
Safety Related Makeup System ....... B 3 .7-43c B 3.7.8 Salt Water Cooling System (SWC) B 3.7-44 B 3.7.10 Emergency Chilled Water (ECW) System ....... B 3.7-49 B 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) ........ ................. B 3.7-56 B 3.7.12 Not Used B 3.7.13 Not Used B 3.7.14 Not Used B 3.7.15 Not Used B 3.7.16 Fuel Storage Pool Water Level ........ B 3.7-68 B 3.7.17 Fuel Storage Pool Boron Concentration .... B 3.7-71 B 3.7.18 Spent Fuel Assembly Storage ......... B 3.7-74 B 3.7.19 Secondary Specific Activity ......... B 3.7-76 B 3.8 ELECTRICAL POWER SYSTEMS ..... ........... B 3.8-1 B 3.8.1 AC Sources-Operating .......... B 3.8-1 B 3.8.2 AC Sources- Shutdown ...... ........... B 3.8-30 B 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Ai r B 3.8-36 B 3.8.4 DC Sources-Operating .......... B 3.8-46 B 3.8.5 DC Sources- Shutdown ... ............. B 3.8-56 B 3.8.6 Battery Cell Parameters ......... B 3.8-60 B 3.8.7 Inverters- Operating ... ............. B 3.8-67 B 3.8.8 Inverters - Shutdown ........... B 3.8-71 B 3.8.9 Distribution Systems-Operating ..... B 3.8-75 B 3.8.10 Distribution Systems-Shutdown ......... B 3.8-84 B 3.9 REFUELING OPERATIONS ................ B 3.9-1 B 3.9.1 Boron Concentration ......... B 3.9-1 B 3.9.2 Nuclear Instrumentation ....... B 3.9-5 B 3.9.3 Containment Penetrations .......... B 3.9-9 B 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation -High Water Level . . . . . . . . . B 3.9-16 B 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation-Low Water Level . . . . . . . . . B 3.9-21 B 3.9.6 Refueling Water Level . . . . .. . . . . . . B 3.9-25 SAN ONOFRE--Unit 2 viii Amendment No. -Z04 208
THIS PAGE INTENTIONALLY LEFT BLANK SAN ONOFRE--UNIT 2 3.3-42 Amendment No. +/ 208
THIS PAGE INTENTIONALLY LEFT BLANK SAN ONOFRE--UNIT 2 3.3-43 Amendment No. +4-7 208
THIS PAGE INTENTIONALLY LEFT BLANK SAN ONOFRE--UNIT 2 3.7-27 Amendment No. 124 208
THIS PAGE INTENTIONALLY LEFT BLANK SAN ONOFRE--UNIT 2 3.7-28 Amendment No. 4-ý 208
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.12 Ventilation Filter Testing Program (VFTP)
This Program establishes the required testing of the Engineered Safety Feature filter ventilation system "Control Room Emergency Air Cleanup System." The frequency of testing shall be in accordance with Regulatory Guide 1.52, Revision 2. As a minimum the VFTP program shall include the following:
- a. Inplace testing of the high efficiency particulate air (HEPA) filters to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and
- b. Inplace testing of the charcoal adsorber to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and
- c. Laboratory testing of charcoal adsorber samples obtained in accordance with Regulatory Guide 1.52, Revision 2 and tested per the methodology of ASTM D3803-1989 at 30'C and 70%
relative humidity to show acceptable methyl iodide penetration; and
- d. Testing to demonstrate the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers, when tested at the appropriate system flowrate.
Note 1: Sample and injection points shall be qualified per ANSI N510-1975 unless manifolds have been qualified per ASME N510-1989.
HEPA testing will be conducted with DOP aerosol or suitable alternate.
(continued)
SAN ONOFRE--UNIT 2 5.0-17 Amendment No. £04 208
(3) SCE, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear materials as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of San Onofre Nuclear Generating Station, Units 1 and 3 and by the decommissioning of San Onofre Nuclear Generating Station Unit 1.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level Southern California Edison Company (SCE) is authorized to operate the facility at reactor core power levels not in excess of full power (3438 megawatts thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 200, are hereby incorporated in the license.
Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Amendment No. 4-99 200 1
TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.5 Engineered Safety Features Actuation System (ESFAS)
Instrumentation . . . . . . . . . . . . . . . . 3.3-22
.3.3.6 Engineered Safety Features Actuation System (ESFAS)
Logic and Manual Trip ...... ............. .. 3.3-27 3.3.7 Diesel Generator (DG) -Undervoltage Start ... ..... 3.3-32 3.3.8 Containment Purge Isolation Signal (CPIS) ..... ... 3.3-35 3.3.9 Control Room Isolation Signal (CRIS) .... ....... 3.3-39 3.3.10 Not Used 3.311 Post Accident Monitoring Instrumentation (PAM!) 3.3-44 3.3.12 Remote Shutdown System ...... ..... .............. 3.3-48 3.3.13 Source Range Monitoring Channels .............. .. 3.3-51 3.4 REACTOR COOLANT SYSTEM (RCS) ..... .............. .. 3.4-1 3.4.1 RCS DNB Pressure, Temperature, and Flow Limits ..................... 3.4-1 3.4.2 RCS Minimum Temperature for Criticality. ...... 3.4-4 3.4.3 RCS Pressure and Temperature (P/T) Limits ..... ... 3.4-5 3.4.3.1 Pressurizer Heatup/Cooldown Limits ..... ......... 3.4-13 3.4.4 RCS Loops-MODES 1 and 2 ..... .............. .. 3.4-15 3.4.5 RCS Loops-MODE 3 ........ ..... ......... .... 3.4-16 3.4.6 RCS Loops-MODE 4 ....... ................ ... 3.4-18 3.4.7 RCS Loops-MODE 5, Loops Filled................ .'3.4-21 3.4.8 RCS Loops-MODE 5, Loops Not Filled ... ........ .. 3.4-24 3.4.9 Pressurizer .* ****.......................... ... 3.4-26 3.4.10 Pressurizer Safety Valves ........ ... ....... .. 3.4-28 3.4.11 Not Used 3.4.12.1 Low Temperature Overpressure Protection (LTOP)
System, RCS Temperature
System, RCS Temperature > PTLR Limit ........ .. 3.4-35 3.4.13 RCS Operational LEAKAGE ..... .............. ... 3.4-37 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ........ 3.4-39 3.4.15 RCS Leakage Detection Instrumentation .... ....... 3.4-44 3.4.16 RCS Specific Activity ....... ... ............... 3.4-47 3.4.17 RCS Steam Generator (SG) Tube Integrity ......... 3.4-51 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ..... ......... 3.5-1 3.5.1 Safety Injection Tanks (SITs) ....... ........... 3.5-1 3.5.2 ECCS-Operating ......... .................. ... 3.5-4 3.5.3 ECCS -Shutdown . . .. . . . . .... . . . . . . 3.5-8 3.5.4 Refueling Water Storage Tank (RWST) ........ 3.5-9 3.5.5 Trisodium Phosphate (TSP) ..... ............. ... 3.5-11 (continued)
SAN ONOFRE--Unit 3 ii i Amendment No. +% 200
TABLE OF CONTENTS 3.6 CONTAINMENT SYSTEMS ............. . . . . 3.6-1 3.6.1 Containment . . . . . . . . . . . . . . . . . . . 3.6-1 3.6.2 Containment Air Locks .......... . . . . 3.6-3 3.6.3 Containment Isolation Valves .......... . . . . 3.6-8 3.6.4 Containment Pressure. ........... . . . . 3.6-16 3.6.5 Containment Air Temperature . ...... 3.6-17 3.6.6.1 Containment Spray and Cooling Systems . . . . . 3.6-18 3.6.6.2 Containment Cooling System ........ 3.6-21 3.6.7 Not Used 3.6.8 Containment Dome Air Circulators ....... . . . . 3.6-25 3.7 PLANT SYSTEMS . . . . . . . . . .. . . . . . . . 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) .... . . . . 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . 3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs) . . . . 3.7-7 3.7.4 Atmospheric Dump Valves (ADVs) ......... . . . . 3.7-9 3.7.5 Auxiliary Feedwater (AFW) System ....... . . . . 3.7-11 3.7.6 Condensate Storage Tank (CST T-120 and T-1;21) . . 3.7-16 3.7.7 Component Cooling Water (CCW) System . . . . . . . 3.7-18 3.7.7.1 Component Cooling Water (CCW)
Safety Related Makeup System ..... . . . . 3.7-19a 3.7.8 Salt Water Cooling (SWC) System ..... . . . . 3.7-20 3.7.9 Not Used 3.7.10 Emergency Chilled Water (ECW) ...... . . . . 3.7-22 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) ..... ................ . . . . 3.7-24 3.7.12 Not Used 3.7.13 Not Used 3.7.14 Not Used 3.7.15 Not Used 3.7.16 Fuel Storage Pool Water Level ...... . . . . 3.7-29 3.7.17 Fuel Storage Pool Boron Concentration . . . . . . 3.7-30 3.7.18 Spent Fuel Assembly Storage ....... . . . . 3.7-32 3.7.19 Secondary-Specific Activity ....... . . . . 3.7-35 3.8 ELECTRICAL POWER SYSTEMS ..... ........... 3.8-1 3.8.1 AC Sources-Operating . . ........ 3.8-1 3.8.2 AC Sources-Shutdown ..... ........... 3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Ai r 3.8-20 3.8.4 DC Sources-Operating .......... 3.8-23 3.8.5 DC Sources- Shutdown ... ............. 3.8-27 3.8.6 Battery Cell Parameters ......... 3.8-30 3.8.7 Inverters -Operating ..... ........... 3.8-34 3.8.8 Inverters -Shutdown ........... 3.8-36 3.8.9 Distribution Systems-Operating ..... 3.8-38 3.8.10 Distribution Systems-Shutdown ......... 3.8-40 (conti nued)
SAN ONOFRE--Unit 3 -iv Amendment No. 1-5G 200
TABLE OF CONTENTS B 3.3 INSTRUMENTATION (continued)
B 3.3.7 Diesel Generator Undervoltage Start ...... B 3.3-126 B 3.3.8 Containment Purge Isolation Signal (CPIS) . . . B 3.3-135 B 3.3.9 Control Room Isolation Signal (CRIS) ......... B 3.3-145 B 3.3.10 Not Used B 3.3.11 Post Accident Monitoring Instrumentation (PAMI) B 3.3-159 B 3.3.12 Remote Shutdown System ... ............... B 3.3-176 B 3.3.13 Source Range Monitoring Channels ............ B 3.3-181 B 3.4 REACTOR COOLANT SYSTEM (RCS) ...... ............ B 3.4-1 B 3.4.1 RCS DNB (Pressure, Temperature, and Flow) Limits B 3.4-1 B 3.4.2 RCS Minimum Temperature for Criticality .... B 3.4-7 B 3.4.3 RCS Pressure and Temperature (P/T) Limits . . . B 3.4-9 B 3.4.4 RCS Loops-MODES 1 and 2 ...... ............ B 3.4-23 B 3.4.5 RCS Loops-MODE 3 ............... B 3.4-27 B 3.4.6 RCS Loops-MODE 4 .............. . B 3.4-31 B 3.4.7 RCS Loops-MODE 5, Loops Filled ........ B 3.4-36 B 3.4.8 RCS Loops-MODE 5, Loops Not Filled ...... B 3.4-42 B 3.4.9 Pressurizer . . . . . . . . . . . . . . . . . . B 3.4-46 B 3.4.10 Pressurizer Safety Valves ........... B 3.4-51 B 3.4.11 Not Used B 3.4.12.1 Low Temperature Overpressure Protection (LTOP)
System, RCS Temperature
System, RCS Temperature > PTLR Limit . ... B 3.4-65 B 3.4.13 RCS Operational LEAKAGE ............ B 3.4-70 B 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage . . . B 3.4-76 B 3.4.15 RCS Leakage Detection Instrumentation ..... B 3.4-82 B 3.4.16 RCS Specific Activity ............. B 3.4-88 B 3.4.17 RCS Steam Generator (SG) Tube Integrity B 3.4-93 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ....... B 3.5-1 B 3.5.1 Safety Injection Tanks (SITs) ......... B 3.5-1 B 3.5.2 ECCS -Operating .... ............ B 3.'5-11 B 3.5.3 ECCS -Shutdown ...... ................. B 3.5-21 B 3.5.4 Refueling Water Storage Tank (RWST) ...... B 3.5-24 B 3.5.5 Trisodium Phosphate (TSP) ........... B 3.5-30 B 3.6 CONTAINMENT SYSTEMS .......... B 3.6-1 B 3.6.1 Containment . . . . . . . . . . . . B 3.6-1 B 3.6.2 - Containment Air Locks ....... B 3.6-5 B 3.6.3 Containment Isolation Valves . ... B 3.6-13 B 3.6.4 Containment Pressure ............ B 3.6-27 B 3.6.5 Containment Air Temperature . ... B 3.6-30 B 3.6.6.1 Containment Spray and Cooling System B 3.6-33 B 3.6.6.2 Containment Cooling System ....... B 3.6-43 B 3.6.7 Hydrogen Recombiners .... ........ B 3.6-48 B 3.6.8 Containment Dome Air Circulators . . B 3.6-53 (conti nued)
SAN ONOFRE--Unit 3 vi i Amendment No. +/-96 200
TABLE OF CONTENTS B 3.7 PLANT SYSTEMS . . . . . . . . . . . .. . . . B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs) ... ...... . B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) B 3.7-7 B 3.7.3 Main Feedwater Isolation Valves (MFIVs) B 3.7-13 B 3.7.4 Atmospheric Dump Valves (ADVs) .... ........ B 3.7-17 B 3.7.5 Auxiliary Feedwater (AFW) System ....... B 3.7-23 B 3.7.6 Condensate Storage Tank (CST T-121 and T-120) B 3.7-35 B 3.7.7 Component Cooling Water (CCW) System ....... B 3.7-39 B3. 7. 7. 1 Component Cooling Water (CCW)
Safety Related Makeup System ....... B 3.7-43c B 3.7.8 Salt Water Cooling (SWC) System B 3.7-44 B 3.7.10 Emergency Chilled Water (ECW) System ....... B 3.7-49 B 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) ........ ................. B 3.7-56 B 3.7.12 Not Used B 3.7.13 Not Used B 3.7.14 Not Used B 3.7.15 Not Used B 3.7.16 Fuel Storage Pool Water Level ........ B 3.7-68 B 3.7.17 Fuel Storage Pool Boron Concentration .... B 3.7-71 B 3.7.18 Spent Fuel Assembly Storage ......... B 3.7-74 B 3.7.19 Secondary Specific Activity ......... B 3.7-76 B 3.8 ELECTRICAL POWER SYSTEMS ......... B 3.8-1 B 3.8.1 AC Sources-Operating ..... B 3.8-1 B 3.8.2 AC Sources-Shutdown ......... B 3.8-30 B 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air B 3.8-36 B 3.8.4 DC Sources-Operating ..... B 3.8-46 B 3.8.5 DC Sources- Shutdown....... B 3.8-56 B 3.8.6 Battery Cell Parameters .... B 3.8-60 B 3.8.7 Inverters- Operating ....... . B 3.8-67 B 3.8.8 Inverters - Shutdown ...... B 3.8-71 B 3.8.9 Distribution Systems -Operating B 3.8-75 B 3.8.10 Distribution Systems-Shutdown B 3.8-84 B 3.9 REFUELING OPERATIONS ............. B 3.9-1 .
B 3.9.1 Boron Concentration ....... . . . . . . . . B 3.9-1 B 3.9.2 Nuclear Instrumentation ..... . . . . . . . . B 3.9-5 B 3.9.3 Containment Penetrations ....... . . . . . . . . B 3.9-9 B 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation- High Water Level-. ... . . .. . B 3.9-16 B 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation-Low Water Level . . . . . . . . . B 3.9-21 B 3.9.6 Refueling Water Level ....... . . . . . . . . B 3.9-25 SAN ONOFRE--Unit 3 viii Amendment No. 8 200
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Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.12 Ventilation Filter Testing Program (VFTP)
This Program establishes the required testing of the Engineered Safety Feature filter ventilation system "Control Room Emergency Air Cleanup System." The frequency of testing shall be in accordance with Regulatory Guide 1.52, Revision 2. As a minimum the VFTP program shall include the following:
- a. Inplace testing of the high efficiency particulate air (HEPA) filters to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and
- b. Inplace testing of the charcoal adsorber to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and
- c. Laboratory testing of charcoal adsorber samples obtained in accordance with Regulatory Guide 1.52, Revision 2 and tested per the methodology of ASTM D3803-1989 at 30 0 C and 70%
relative humidity to show acceptable methyl iodide penetration; and
- d. Testing to demonstrate the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers, when tested at the appropriate system flowrate.
Note 1: Sample and injection points shall be qualified per ANSI N510-1975 unless manifolds have been qualified per ASME N510-1989.
HEPA testing will be conducted with DOP aerosol or suitable alternate.
(continued)
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