ML20070J625

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs,Relocating Seismic Monitoring Instrumentation Lco,Srs & Associated Tables & TS Bases to Updated FSAR
ML20070J625
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 07/20/1994
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20070J623 List:
References
NUDOCS 9407250227
Download: ML20070J625 (5)
v • d • e


Text

, .

ATTACHMENT 1 UMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS.

50-352 50-353 LICENSE NOS.

NPF-39 NPF45 REVISED TECHNICAL SPECIFICATIONS PAGES SUPPORTING TECHNICAL SPECIFICATIONS CHANGE REQUEST NO. 93-16-0 THE FOLLOWING PAGES ARE CONTAINED WITHIN LGS Unit 1 LGS Unit 2 TS Paaes TS Paaes xix xix B 3/4 3-5 83/43-5 9407250227 940720.2 DR ADOCK 0500

INDEX

' BASES PAGE SECTION fNSTRUMENTATION (Continued)

(Deleted).............................................. B 3/4 3-5 (Deleted).............................................. B 3/4 3-5 Remote Shutdown System In<trumentation and Controls.... B 3/4 3-5 Accident lionitoring Instrumentation. . . . . . . . . . . . . . . . . . . . B 3/4 3-5 Source Range Monitors.................................. B 3/4 3-5 Traversing In-Core Probe System........................ B 3/4 3-6 Chlorine and Toxic Gas Detection Systems. . . . . . . . . . . . . . . B 3/4 3-6 Fire Detection Instrumentation......................... B 3/4 3-6 Loose-Part Detection System............................ B 3/4 3-7 (Deleted).............................................. B 3/4 3-7 Offgas Monitoring Instrumentation...................... B 3/4 3-7 TURBINE OVERSPEED PROTECTION SYSTEM.................... B 3/4 3-7 3/4.3.8 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION........................................ B 3/4 3-7 Bases Figure B 3/4.3-1 Reactor Vessel Water Level..................... B 3/4 3-8 3/4.4 REACTOR COOLANT SYSTEM RECIRCULATION SYSTEM................................... B 3/4 4-1 3/4.4.1 3/4.4.2 SAFETY / RELIEF VALVES................................... B 3/4 4-2 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems............,................. B 3/4 4-3 Operational Leakage.................................... B 3/4 4-3 CHEMISTRY.............................................. B 3/4 4-3 3/4.4.4 LIMERICK - UNIT 1 xix

t INSTRUMENTATION ,

BASES 3/4.3.7 MONITORING INSTRUMENTATION 3/4.3.7.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring instrumentation ensures that; (1) the radiation levels are continually measured in the areas served by the individual channels, and (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeced; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with 10 CFR Part 50, Appendix A, General Design Criteria 19, 41, 60, 61, 63, and 64.

The specified surveillance interval for the Main Control Room Normal Fresh Air Supply Radiation Monitor has been determined in accordance with GENE-770-06-1, " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,".as approved by the NRC and documented in the SER (letter to R.D. Binz, IV, from C.E. Rossi dated July 21,1992).

1 3/4.3.7.2 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE UFSAR.

3/4.3.7.3 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE ODCM.

3/4.3.7.4 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION AND CONTROLS The OPERABILITY of the remote shutdown system instrumentation and controls ensures that sufficient capability is available to permit shutdown and maintenance of l HOT SHUTDOWN of the unit from locations outside of the control room. This capability ,

is required in the event control room habitability is lost and is consistent with l General Design Criterion 19 of 10 CFR Part 50, Appendix A. {

3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident,"

December 1975 and NUREG-0737, " Clarification of TMI Action Plan Requirements,"

November 1980.

3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown.

At these power levels, reactivity additions shall not be made without this flux level information available to the operator. When the intermediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted.

LIMERICK - UNIT 1 B 3/4 3-5

INDEX  ;

1 J

' BASES l

SECTION -

PAGE i 1

i INSTRUMENTATION (Continued)

(Deleted)..................................................... B3/43-5 (Deleted)..................................................... B 3/4 3-5 l Remote Shutdown Systeni Instrumentation and Controls. . . . . . . . . . . B 3/4 3-5 Accident Monitoring Instrumentation........................... B 3/4 3-5 Source Range Monitors......................................... B 3/4 3-5 Traversing In-Core Probe System............................... B 3/4 3-6 Chlorine and Toxic Gas Detection Systems. . . . . . . . . . . . . . . . . . . . . . B 3/4 3-6 Fire Detection Instrumentation................................ B 3/4 3-6 Loose-Part Detection System.................................. B 3/4 3-7 (Deleted)..................................................... B 3/4 3-7 1

Offgas Monitoring Instrumentation............................. B 3/4 3-7 l 1

3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM........................... B 3/4 3-7 1 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION............................................... B 3/4 3-7 Bases Figure B 3/4.3-1 Reactor Vessel Water ,

Level........................... B 3/4 3-8 l 3/4.4 REACTOR COOLANT SYSTEM  !

3/4.4.1 RECIRCULATION SYSTEM.......................................... B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES.......................................... B 3/4 4 l 3/4.4.3 REACTOR COOLANT SYSTEM LEAXAGE Leakage Detection Systems..................................... B 3/4 4-3 1

Op e r a t i o n al L e a k ag e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-3 l 3/4.4.4 CHEMISTRY..................................................... B 3/4 4-3a LIMERICK - UNIT 2 xix

i

)

I STRUMENTATION i BASES 3/4.3.7 MONITORING INSTRUMENTATION 3/4.3.7.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring instrumentation ensures that; (1 the radiation levels are continually measured in the areas served by the ind)ividual channels, and (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is

' available on selected plant parameters to monitor and assess these variable following an accident. This capability is consistent with 10 CFR Part 50, Appendix A, General Design Criteria 19, 41, 60, 61, 63, and 64.

The specified surveillance interval for the Main Control Room Normal Fresh Air Supply Radiation Monitor has been determined in accordance with GENE-770-06-1,

" Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specification," as a) proved by the NRC and documented in the SER (letter to R. D. Binz, IV, from C. E. Rossi dated July 21,1992).

3/4.3.7.2 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE UFSAR.

3/4.3.7.3 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE ODCM.

3/4.3.7.4 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION AND CONTROLS The OPERABILITY of the remote shutdown system instrumentation and controls ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR Part 50, Appendix A. The Unit 1 RHR transfer switches are included only due to their potential impact on the RHRSW system, which is common to both units.

3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that I sufficient information is available on selected plant parameters to monitor and I assess important variables following an accident. This capability is consistent I with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light l Water Cooled Nuclear Power Plants to Assess Plant Conditions During and .

Following an Accident," December 1975 and NUREG-0737, " Clarification of TMI Action Plan Requirements," November 1980.

j 3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the (

status of the neutron level in the core at very low power levels during startup i and shutdown. At these power levels, reactivity additions shall not be made without this flux level information available to the operator. When the intermediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted LIMERICK - UNIT 2 B 3/4 3-5 l

Retrieved from "https://kanterella.com/w/index.php?title=ML20070J625&oldid=2711699"