ML20205T637
| ML20205T637 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/06/1986 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20205T628 | List: |
| References | |
| NUDOCS 8606160122 | |
| Download: ML20205T637 (5) | |
Text
1 TS-iii REV TABLE OF CONTENTS TS SECTION TITLE PAGE 3.5 Instrumentation System TS.3.5-1 3.6 Containment System TS.3.6-1 A. Containment System Integrity TS.3.6-1 B. Containment Internal Pressure TS.3.6-3 C. Containment and Shield Building Air Temperature TS.3.6-3 D. Containment Shell Temperature TS.3.6-3 E. Emergency Air Treatment Systems TS.3.6-3A F. Electric Hydrogen Recombiners TS.3.6-3A 3.7 Auxiliary Electrical Systems TS.3.7-1 3.8 Refueling and Fuel Handling TS.3.8-1 D. Spent Fuel Pool Special Ventilation System TS.3.8-3 3.9 Radioactive Effluents TS.3.9-1 A. Liquid Effluents TS.3.9-1 B. Gaseous Effluents TS.3.9-3 C. Solid Radioactive Waste TS.3.9-6 D. Dose from All Uranium Fuel Cycle Sources TS.3.9-7 E. Radioactive Liquid Effluent Monitoring TS.3.9-7 Instrumentation F. Radioactive Gaseous Effluent Monitoring TS.3.9-8 Instrumentation 3.10 Control Rod and Power Distribution Limits TS.3.10-1 A. Shutdown Reactivity TS.3.10-1 B. Power Distribution Limits TS.3.10~1 C. Quadrant Power Tilt Limits TS.3.10-4 D. Rod Insertion Limits TS.3.10-5 E. Rod Misalignment Limitations TS.3.10-6 F. Inoperable Rod Position Indicator Channels TS.3.10-6 G. Inoperable Rod Limitations TS.3.10-6 H. Rod Drop Time TS.3.10-7 I. Monitor Inoperability Requirements TS.3.10-7 J. DNB Parameters TS.3.10-8 3.11 Core Surveillance Instrumentation TS.3.11-1 3.12 Snubbers TS.3.12-1 3.13 Control Room Air Treatment System TS.3.13-1 3.14 Fire Detection and Protection Systems TS.3.14-1 A. Fire Detection Instrumentation TS.3.14-1 B. Fire Suppression Water System TS.3.14-1 C. Spray and Sprinkler Systems TS.3.14-2 D. Carbon Dioxide System TS.3.14-3 E. Fire Hose Stations TS.3.14-3 F. Yard Hydrant Hose Houses TS.3.14-4 G. Penetration Fire Barriers TS.3.14-4 3.15 Event Monitoring Instrumentation TS.3.15-1 A. Process Monitors TS.3.15-1 i
B. Radiation Monitors TS.3.15-1 l
C. Reactor Vessel Level Instrumentation TS.3.15-2 l
i DR AD C jf P
l TS.3.15-2 REV C.
Specification - Reactor Vessel Level Instrumentation
- 1. The reactor vessel level instrumentation channels specified in Table TS.3.15-3 shall be operable e
- 2. With the number of Operable reactor vessel level instrumentation channels less than the Required Total Number af Channels shown on Table TS.3.15-3, either restore the inoperable channels to Operable status within fourteen days, or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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- 3. With the number of Operable reactor vessel level instrumentation channels less than the Minimum Channels Operable requirements of Table TS.3.15-3, either restore the minimum number of channels to Operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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Basis i
The operability of the event monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess i
these variables during and following an accident. This capability is consistent with the recommendations of NUREG-0578, "TMI-2 Lessons Learned Task Force Status Peport and Short Term Recommendations."
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Core exit thermocouple readings necessary to meet the requirements of Specifica-tion 3.15.A are availabic from the Plant Process Computer, the Control Room Core l
Exit Thermocouple Display or if no other readout is available, from test equip-ment readings from the Core Exit Thermocouple Junction Boxes.
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TABLE TS.3.15-1 h
EVENT MONITORING INSTRUMENTATION - PROCESS & CONTAINMENT Required Total No.
Minimum Channels Instrument of Channels Operable I
b I
- 1. Pressurizer Water Level 2
1
- 2. Au.iliary Feedwater Flow to Steam Generators 2/ steam gen 1/ steam gen
]
(Oi.e Channel Flow and One Channel Wide Range Leve: for Each Steam Generator)
]
- 3. Reactor Coolant System Subcooling Margin 2
1 1
- 4. Pressurizer Power Operated Relief Block Valve Position 2/ valve 1/ valve (One Common Channel Temperature, One Channel Limit Switch per Valve, and One Channel Acoustic Sensor per Valve *)
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- 5. Pressurizer Power Operated Relief Block Valve Position 2/ valve 1/ valve j
(One Common Channel Temperature, One Channel Limit Switch per Valve, and One Channel Acoustic Sensor per Valve *)
- 6. Pressurizer Safety Valve Position 2/ valve 1/ valve (One Channel Temperature per Valve and Common j
Acoustic Sensor **)
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- 7. a. Containment Water Level (wide range) 2 1
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- b. Containment Water Level (narrow range) 2 1
- 8. Containment Hydrogen Monitor (2 sensors per Channel) 2 1
- 9. Containment Pressure (wide range) 2 1
gg
- 10. Core Exit Thermocouples 4/ core quadrant 2/ core quadrant o
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- A common acoustic sensor provides backup position indication for each pressurizer power operated l
relief valve and its associated block valve.
- The acoustic sensor channel is common to both valves. When operable, the acoustic sensor may be l
considered as an operable channel for each valve.
TABLE TS.3.15-3 EVENT MONITORING INSTRUMENTATION - REACTOR VESSEL LEVEL Required Total No.
Minimum Channels Instrument of Channels Operable 1.
Reactor Vessel Level Instrumentation
- 2 1
l EE U
<5 m
- w E
w
- Includes the full range and dynamic head range
TABLE TS.4.1-1 (Page 4 of 5)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND-TEST OF INSTRUMENT CHANNELS Channel Functional Response Description Check Calibrate Test Test Remarks j
26.
Reactor Trip Bypass NA NA M(l)
R(2)
- 1) Manually trip the undervoltage trip Breaker attachment remotely (i.e. from the protection system racks).
- 2) Automatically trip the undervoltage trip attachment 27.
Turbine Overspeed NA R
M NA Protection Trip Channel 28.
Deleted 29.
Deleted 30.
Deleted 31.
Seismic Monitors R
R NA NA 32.
Coolant Flow - RTD S
R M
NA Bypass Flowmeter 33.
CRDM Cooling Shroud S
NA R
NA FSAR page 3.2-56 34.
Reactor Gap Exhaust Air S
NA R
NA Temperature 35a. Post-Accident Monitoring M
R NA NA Includes all those in Table TS.3.15-1 Instruments (except for containment hydrogen monitors which are separately specified in this table) f 1
- b. Post-Accident Monitoring D
R M
NA Includes all those in Table TS.3.15-2 gl Radiation Instruments E!,m, m i
- c. Post-Accident Monitoring M
R NA NA Includes all those in Table
<j $,
mm Reactor Vessel Level TS.3.15-3
- d Instrumentation S
36.
Steam Exclusion Actuation W
Y M
NA See FSAR Appendix I,Section I.14.6 20 7' System 37.
Overpressure Mitigation NA R
R NA Instrument Channels for PORV Control Including Overpressure Mitigation System System