ML20205T637

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Proposed Tech Spec Changes to Sections 3.15 & 4.1 Re Inadequate Core Cooling Instrumentation
ML20205T637
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 06/06/1986
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20205T628 List:
References
NUDOCS 8606160122
Download: ML20205T637 (5)
v • d • e


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 .

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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 />.

a f

j i

l l

Basis i

The operability of the event monitoring instrumentation ensures that sufficient i

information is available on selected plant parameters to monitor and assess 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."

l l 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.

s F

l _ . . ... . _ _ _ _ _ _ _ _ _ _ . _

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 *)

i j 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 **)

j

! 7. a. Containment Water Level (wide range) 2 1

{ 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
  1. $o j $

3 L

  • - 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

<5m 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  :

Radiation Instruments gl E! ,m, m i

c. Post-Accident Monitoring M R NA NA Includes all those in Table <j $ ,

TS.3.15-3 mm Reactor Vessel Level Instrumentation *d M NA See FSAR Appendix I,Section I.14.6 S *

36. Steam Exclusion Actuation W Y System 20 7'
37. Overpressure Mitigation NA R R NA Instrument Channels for PORV Control System Including Overpressure Mitigation System
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