Proposed Tech Specs Providing Enhancements for ATWS-RPT Instrumentation & Logic SysML20081F571 |
Person / Time |
---|
Site: |
LaSalle |
---|
Issue date: |
06/04/1991 |
---|
From: |
COMMONWEALTH EDISON CO. |
---|
To: |
|
---|
Shared Package |
---|
ML20081F567 |
List: |
---|
References |
---|
NUDOCS 9106100510 |
Download: ML20081F571 (12) |
|
|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20210R3581999-08-13013 August 1999 Proposed Tech Specs Allowing Performance of CRDM & Ni Instrumentation Replacement to Not Be Considered Core Alterations During Operational Condition 5,Refueling,while Fuel Is in Reactor Vessel ML20210Q4101999-08-0606 August 1999 Proposed Tech Specs Section 3/4.6.4, Vacuum Relief, Removing Specific Operability Requirements Related to Position Indication for Suppression chamber-drywell Vacuum Breakers & Revising Action Statements & Srs,Per NUREG-1433 ML20209G3581999-07-14014 July 1999 Proposed Tech Specs Pages Re Amend to Licenses NPF-11 & NPF-18,revising TS Allowing LCS Units 1 & 2 to Operate at Uprated Power Level of 3489 Mwt ML20209D3931999-07-0707 July 1999 Proposed Tech Specs,Changing Proposed Degraded Voltage Low Limit Setpoint & Adding High Limit Setpoint & Allowable Value ML20209D3231999-07-0707 July 1999 Proposed Tech Specs,Revising MCPR Safety Limits & Adding Approved Siemens Power Corp Methodology List of TRs for COLR ML20206T1401999-05-19019 May 1999 Proposed Tech Specs Section 3/4.4.4, Chemistry, Relocating to UFSAR ML20195E0101998-11-0909 November 1998 Proposed Tech Specs Re Application for Amends to Licenses NPF-11 & NPF-18,adding Automatic Primary Containment Isolation on Ambient & Differential Temperature to High for RWCU Sys Pump,Pump Valve,Holdup Pipe & Filter/Demineralizer ML20195E0541998-11-0909 November 1998 Proposed Tech Specs Pages Re Application for Amends to Licenses NPF-11 & NPF-18,to Modify Degraded Voltage Second Level Undervoltage Relay Setpoint & Allowable Value to TS 3/4.3.3 & TS Table 3.3.3-2 ML20154M4641998-10-16016 October 1998 Proposed Tech Specs,Lowering Power Level Below Which TCV & TSV Closure Scram Signals & EOC-RPT Signal Are Not in Effect ML20217M6671998-05-0101 May 1998 Proposed Tech Specs Adding Ventilation Filter Testing Program ML20216E3221998-04-0707 April 1998 Proposed Tech Specs Pages Re Addition of Ventilation Filter Testing Program ML20217J2981998-03-24024 March 1998 Proposed Tech Specs Deleting Unit 1 License Condition 2.C.(30)(a) in Entirety ML20202C8971998-02-0202 February 1998 Proposed Tech Specs Re Changes to Relocate Fire Protection Requirements ML20203G5051997-12-12012 December 1997 Proposed Tech Specs,Modifying Bypass Logic for Msli Valve Isolation Acuation Instrumentation on Condenser Low Vacuum ML20199K5481997-11-24024 November 1997 Proposed Ts,Adding Automatic Primary Containment Isolation on Ambient & Differential Temp High for Rwcs Pump,Pump Valve,Holdup Pipe & F/D Valve Rooms & Eliminating RHR Sys Steam Condensing Mode Isolation Actuation Instrumentation ML20211P9331997-10-15015 October 1997 Proposed Tech Specs Eliminating Unnecessary Detail from Accident Monitoring Instrumentation Surveillance Requirements ML20217C3771997-09-26026 September 1997 Proposed Tech Specs Adding Ventilation Filter Testing Program ML20216H7711997-09-0404 September 1997 Corrected TS Bases Sections B 3/4.2.1 & B 3/4.2.3 Re Thermal Limits ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20141J5671997-08-12012 August 1997 Proposed Tech Specs Surveillance Requirement 4.7.1.3.c Re Ultimate Heat Sink by Deletion of Sediment Deposition Insp in Lake Screen House ML20151K9551997-08-0101 August 1997 Proposed Tech Specs Changing Title of Site Quality Verification Director to Manager of Quality & Safety Assessment ML20148U2591997-07-0101 July 1997 Proposed Tech Specs to Change Definition of Channel Calibration & Correcting Miscellaneous Errors in TS & Bases. TS Affected Are TS Definition 1.4,TS Tables 3/4.3.2-1 & 3/4.3.6-1 & Bases for TS 3/4.3.1 ML20148Q4301997-07-0101 July 1997 Proposed Tech Specs Reflecting Improvements Made to Control Room Ventilation Air Intake Radiation Monitoring Sys Logic to Reduce Spurious Actuation of Emergency Filtration Mode of Operation & Unnecessary Challenges to ESF ML20148N0201997-06-19019 June 1997 Proposed Tech Specs,Relocating Fire Protection Requirements ML20141L0371997-05-27027 May 1997 Proposed Tech Specs,Incorporating Restructured Station Organization,Change to Submittal Frequency of Radiological Effluent Release Rept & Other Administrative Changes ML20137W5131997-04-14014 April 1997 Proposed Tech Specs Re Feedwater/Main Turbine Trip Sys Actuation Instrumentation Design Change ML20134A1931997-01-20020 January 1997 Proposed Tech Specs 3/4.1.3.5 Re Control Rod Scram accumulators,3/4.4.4.3.2 Re Reactor Coolant Sys Operational leakage,3/4.5.1 Re ECCS - operating,3/4.5.3 Re ECCS, Suppression Chamber & 3/4.6.2.1 Re Suppression Chamber ML20135E6841996-12-0202 December 1996 Proposed Tech Specs,Requesting Amend to Section 3.4.2 to Revise SRV Configuration to Include Only 13 of Current 18 SRVs ML20129J4491996-10-31031 October 1996 Proposed Tech Specs Re Elimination of Seismic Monitoring Instrumentation Requirements ML20129B7981996-10-14014 October 1996 Proposed Tech Specs 2.1.2 Re Thermal Power,High Pressure & High flow,5.3 Re Reactor core,4.0 Re Design features,3/4.1.3 Re Control Rods & 3/4.2.4 Re Linear Heat Generation Rate ML20116A9601996-07-15015 July 1996 Proposed Tech Specs Re Revision of App A,Ts for Licenses NPF-11 & NPF-18,relocating Fire Protection Requirements of Listed TS Sections ML20113C8641996-06-21021 June 1996 Proposed Tech Specs,Including Extension of 18 Month Surveillance Interval & One Time Change to TS to Extend AOT for Each Subsystem of CR & Auxiliary Electric Equipment Room Emergency Filtration Sys ML20107F0641996-04-16016 April 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements ML20107A8641996-04-0808 April 1996 Proposed Tech Specs for Siemens Power Corp Fuel Transition ML20096G3411996-01-18018 January 1996 Proposed Tech Specs,Changing Setpoints for Automatic Primary Containment Isolation on MSL Tunnel Differential Temp High & Deleting Automatic Isolation Function on MSL Tunnel Temp High ML20095K6971995-12-21021 December 1995 Proposed Tech Specs,Deleting TS LCO 3.4.2 Action Statement B ML20093D4421995-10-0202 October 1995 Proposed TS Section 3.4.2,changing SRV Safety Valve Function Lift Setting Tolerance ML20091P8971995-08-28028 August 1995 Proposed Tech Specs,Eliminating MSIV Leakage Control Sys & Increasing MSIV Leakage Limits for Unit 2 ML20084U3071995-06-0808 June 1995 Proposed Tech Specs Re Revised SRs & Administrative Requirements Associated W/Edgs ML20084C2491995-05-23023 May 1995 Proposed Tech Specs,Clarifying Described Equipment out-of- Svc Options ML20083P6401995-05-19019 May 1995 Proposed Tech Specs,Revising TS Requirement That Verifies Each Fire Protection Valve in Correct Position at Least Once Per 31 Days ML20082J9341995-04-11011 April 1995 Proposed Tech Specs Re Extension of Specific Surveillance Intervals ML20087H7871995-03-31031 March 1995 Proposed Tech Specs Section 3.4.2,revising SRV Safety Function Lift Setting Tolerances ML20078H1531995-01-30030 January 1995 Proposed Tech Specs,Proposing One Time Extension of Functional Test for Main Steam Line Isolation Valve - Closure Scram Functional Unit in RPS ML20077S3041995-01-13013 January 1995 Proposed Tech Specs Revising Pressure Alarm Setpoint Allowable Values for ECCS & RCIC Sys Keep Filled Pressure Instrumentation Channels ML20078R7081994-12-14014 December 1994 Proposed Tech Specs,Minimizing Unnecessary Testing & Excessively Restrictive AOT for Certain Actuation Instrumentation in Reactor Protection,Isolation,Emergency Core Cooling,Recirculation Pump Trip & RCIC Sys ML20078B9571994-10-24024 October 1994 Proposed Tech Specs Associated W/Exemption Requests from App J for LaSalle Unit 2 to Return to Cilrt Type a Test Schedule of Three Times in 10 Yrs & for LaSalle Units 1 & 2 to Decouple Cilrt Type a Test Schedule from ISI Schedule ML20069J7801994-06-0909 June 1994 Proposed Tech Specs for Partial Implementation of GE ARTS Program ML20065A2231994-03-22022 March 1994 Proposed Tech Specs Re Deletion of Primary Containemnt Structural Integrity ML20063F3441994-01-28028 January 1994 Proposed Tech Specs 3.3.1 & 3.3.4,extending Surveillance Test Interval from Monthly to Quarterly to Verify Proper Position of MSIV Limit Switches for RPS Instrumentation Operability 1999-08-06
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212F9221999-09-23023 September 1999 Rev 2.3 to Chapters 10,11,12 & App F of LaSalle Annex Odcm ML20211L2871999-09-0202 September 1999 Revs to ODCM, for LaSalle Annex Including Rev 2.2 for Chapters 10,11,12 & App F ML20210R3581999-08-13013 August 1999 Proposed Tech Specs Allowing Performance of CRDM & Ni Instrumentation Replacement to Not Be Considered Core Alterations During Operational Condition 5,Refueling,while Fuel Is in Reactor Vessel ML20210Q4101999-08-0606 August 1999 Proposed Tech Specs Section 3/4.6.4, Vacuum Relief, Removing Specific Operability Requirements Related to Position Indication for Suppression chamber-drywell Vacuum Breakers & Revising Action Statements & Srs,Per NUREG-1433 ML20209G3581999-07-14014 July 1999 Proposed Tech Specs Pages Re Amend to Licenses NPF-11 & NPF-18,revising TS Allowing LCS Units 1 & 2 to Operate at Uprated Power Level of 3489 Mwt ML20209D3231999-07-0707 July 1999 Proposed Tech Specs,Revising MCPR Safety Limits & Adding Approved Siemens Power Corp Methodology List of TRs for COLR ML20209D3931999-07-0707 July 1999 Proposed Tech Specs,Changing Proposed Degraded Voltage Low Limit Setpoint & Adding High Limit Setpoint & Allowable Value ML20206T1401999-05-19019 May 1999 Proposed Tech Specs Section 3/4.4.4, Chemistry, Relocating to UFSAR ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20207A9491999-02-23023 February 1999 Rev 4 to LaSalle County Station Restart Plan for Unit 2 ML20195E0101998-11-0909 November 1998 Proposed Tech Specs Re Application for Amends to Licenses NPF-11 & NPF-18,adding Automatic Primary Containment Isolation on Ambient & Differential Temperature to High for RWCU Sys Pump,Pump Valve,Holdup Pipe & Filter/Demineralizer ML20195E0541998-11-0909 November 1998 Proposed Tech Specs Pages Re Application for Amends to Licenses NPF-11 & NPF-18,to Modify Degraded Voltage Second Level Undervoltage Relay Setpoint & Allowable Value to TS 3/4.3.3 & TS Table 3.3.3-2 ML20154M4641998-10-16016 October 1998 Proposed Tech Specs,Lowering Power Level Below Which TCV & TSV Closure Scram Signals & EOC-RPT Signal Are Not in Effect ML20151Y5991998-09-14014 September 1998 Rev 3 to LaSalle County Station Restart Plan, for Unit 2 Only ML20236U5511998-07-24024 July 1998 NRC Manual Chapter 0350 Restart Action Plan,For LaSalle County Station ML20217M6671998-05-0101 May 1998 Proposed Tech Specs Adding Ventilation Filter Testing Program ML20217N9541998-04-30030 April 1998 Rev 1.9 to Chapter 10,rev 2 to Chapter 11 & Rev 1.9 to Chapter 12 of LaSalle Odcm ML20217P2511998-04-28028 April 1998 Rev 2 to LaSalle County Station Unit 1/Unit 2 Restart Plan ML20216E3221998-04-0707 April 1998 Proposed Tech Specs Pages Re Addition of Ventilation Filter Testing Program ML20217J2981998-03-24024 March 1998 Proposed Tech Specs Deleting Unit 1 License Condition 2.C.(30)(a) in Entirety ML20202C8971998-02-0202 February 1998 Proposed Tech Specs Re Changes to Relocate Fire Protection Requirements ML20203G5051997-12-12012 December 1997 Proposed Tech Specs,Modifying Bypass Logic for Msli Valve Isolation Acuation Instrumentation on Condenser Low Vacuum ML20199K5481997-11-24024 November 1997 Proposed Ts,Adding Automatic Primary Containment Isolation on Ambient & Differential Temp High for Rwcs Pump,Pump Valve,Holdup Pipe & F/D Valve Rooms & Eliminating RHR Sys Steam Condensing Mode Isolation Actuation Instrumentation ML20211P9331997-10-15015 October 1997 Proposed Tech Specs Eliminating Unnecessary Detail from Accident Monitoring Instrumentation Surveillance Requirements ML20217C3771997-09-26026 September 1997 Proposed Tech Specs Adding Ventilation Filter Testing Program ML20216H7711997-09-0404 September 1997 Corrected TS Bases Sections B 3/4.2.1 & B 3/4.2.3 Re Thermal Limits ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20217Q7981997-08-26026 August 1997 Rev 1a to LaSalle County Station Unit 1/Unit 2 Restart Plan ML20141J5671997-08-12012 August 1997 Proposed Tech Specs Surveillance Requirement 4.7.1.3.c Re Ultimate Heat Sink by Deletion of Sediment Deposition Insp in Lake Screen House ML20151K9551997-08-0101 August 1997 Proposed Tech Specs Changing Title of Site Quality Verification Director to Manager of Quality & Safety Assessment ML20148U2591997-07-0101 July 1997 Proposed Tech Specs to Change Definition of Channel Calibration & Correcting Miscellaneous Errors in TS & Bases. TS Affected Are TS Definition 1.4,TS Tables 3/4.3.2-1 & 3/4.3.6-1 & Bases for TS 3/4.3.1 ML20148Q4301997-07-0101 July 1997 Proposed Tech Specs Reflecting Improvements Made to Control Room Ventilation Air Intake Radiation Monitoring Sys Logic to Reduce Spurious Actuation of Emergency Filtration Mode of Operation & Unnecessary Challenges to ESF ML20148N0201997-06-19019 June 1997 Proposed Tech Specs,Relocating Fire Protection Requirements ML20141L0371997-05-27027 May 1997 Proposed Tech Specs,Incorporating Restructured Station Organization,Change to Submittal Frequency of Radiological Effluent Release Rept & Other Administrative Changes ML20148D9561997-05-16016 May 1997 LSCS Unit 1/Unit 2 Restart Plan ML20137W5131997-04-14014 April 1997 Proposed Tech Specs Re Feedwater/Main Turbine Trip Sys Actuation Instrumentation Design Change ML20140C9231997-03-31031 March 1997 Rev 1.9 to Chapter 11, Radiological Environ Monitoring Program & LaSalle Annex Index ML20216H8691997-03-31031 March 1997 Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F ML20134A1931997-01-20020 January 1997 Proposed Tech Specs 3/4.1.3.5 Re Control Rod Scram accumulators,3/4.4.4.3.2 Re Reactor Coolant Sys Operational leakage,3/4.5.1 Re ECCS - operating,3/4.5.3 Re ECCS, Suppression Chamber & 3/4.6.2.1 Re Suppression Chamber ML20135E6841996-12-0202 December 1996 Proposed Tech Specs,Requesting Amend to Section 3.4.2 to Revise SRV Configuration to Include Only 13 of Current 18 SRVs ML20134L0221996-11-30030 November 1996 Rev 1.8 to ODCM, Annex,Chapters 10,11 & 12 ML20129J4491996-10-31031 October 1996 Proposed Tech Specs Re Elimination of Seismic Monitoring Instrumentation Requirements ML20129B7981996-10-14014 October 1996 Proposed Tech Specs 2.1.2 Re Thermal Power,High Pressure & High flow,5.3 Re Reactor core,4.0 Re Design features,3/4.1.3 Re Control Rods & 3/4.2.4 Re Linear Heat Generation Rate ML20116A9601996-07-15015 July 1996 Proposed Tech Specs Re Revision of App A,Ts for Licenses NPF-11 & NPF-18,relocating Fire Protection Requirements of Listed TS Sections ML20115D8781996-07-0808 July 1996 Cycle 8 Startup Test Rept ML20113C8641996-06-21021 June 1996 Proposed Tech Specs,Including Extension of 18 Month Surveillance Interval & One Time Change to TS to Extend AOT for Each Subsystem of CR & Auxiliary Electric Equipment Room Emergency Filtration Sys ML20107F0641996-04-16016 April 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements ML20107A8641996-04-0808 April 1996 Proposed Tech Specs for Siemens Power Corp Fuel Transition ML20097C9051996-02-0202 February 1996 Rev 1 to ISI Plan for Comm Ed LaSalle County Station Units 1 & 2 Second Ten-Yr Interval Insp Program ML20096G3411996-01-18018 January 1996 Proposed Tech Specs,Changing Setpoints for Automatic Primary Containment Isolation on MSL Tunnel Differential Temp High & Deleting Automatic Isolation Function on MSL Tunnel Temp High 1999-09-23
[Table view] |
Text
.
AUACliMENLB PROPOSED CHANGES TO APPENDIX A, TECilNICAL SPECIFICATIONS OF FACILITY OPERATING LICENSES NPF-11 AND NPF-18 REVISED _PAGES UNILONElNPL-ID UNILTHQJNPL-J 81 3/4 3-35 3/4 3-35 3/4 3-36 3/4 3-36 3/4 3-38 3/4 3-38 ,
Insert Page Insert Page I i
?
9106100510 910604 FDR A00a 05000373 P FDR
!!Lt:841?::
, INSTRUMENTATION 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING 20NOITION FOR OPERATION 3.3.4.1 The anticipated transient without scram recirculation pump trip (AT'45-RPT) system instrumentation channels shown in Table 3.3.4.1-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.4.1-2.
APPLICABILITY: OPERATIONAL CONDIlION 1.
ACTION:
- a. With an Ah'S recirculation pump trip system instrumentation channel
- trip setpoint less conservative then the value shown in the Allowable Values column of Table 3.3.4.1-2, oeclare the chanael inoperable until the channel is restored to OPERABLE status with i'.s trip setpoint adjusted consistent with the Trip Setpoint value.
!v b. With the number of OPERABLE channels one less than required by the
+
- Minimum OPERABLE Channels requirement for.one trip function in one
%.. ' trip system, restore the inoperable :hannel to OPERABLE status within 14 days or be in at least STARTUP within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. J SURVEILLANCE REOUIREMENTS 4.3.4.1.1 Each ATWS recirculation- pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown-in Table 4.3.4.1-1.
4.3.4.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated autom, tic operation of all channels shall be performed at least once per 18 months.
"The specified 18-month interval may be walvad for Cycle 1 provided the surveillance is performed during Refuel 1. ) l LA SALLE - UNIT 1 3/4 3-35 Amendment No.24
INSERT A
- b. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, placa the inoperable channel (s) in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />,
- c. With the number of OPERABLE channels two or more less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system and:
- 1. If the operable channels consist of one reactor vessel water level channel and one reactor vessel pressure channel, place both inoperable channels in the tripped condition within I hour, or, if this action will initiate a pump trip, declare the trip system inoperable.
- 2. If the inoperable channels include two reactor vessel water level channels or two reactor vessel pressure channels, declare the trip system inoperable,
- d. With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
- e. With both trip systems inoperable, restore at least one trip system to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, llLL-9 41/ 21
- ' G TABLE 3.3.4.1-1 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION MINIMUMOPERABLECHgNjELS c TRIP FUNCTION PER TRIP SYSTEM
- 1. Reactor Vessel Water Level - 1 Low Low, Level 2 S U
- 2. Reactor Vessel Pressure-High 1 (a)0ne chnnel in one trip system may be pi eced in an i,' operable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance provided that all other channels are OPEWABLE.
l M w
W
~
I s
l TABLE 4.3.4.1-1 I
9 ~
l w ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION SURVEILLANCE REQ (i!REMENTS P
G CHANNEL CHANNEL FUNCTIONAL CHANNEL i
, TRIP FUNCTION- CHECK TEST CALIBRATION
$ l. Reactor Vessel Water level - S M- R Low' Low, Level 2 /
]
- 2. Reactor Vessel Pressure - High' NA M Q [
S ea M l l .
l L
I I
L
( ( (
1
INSTRUMENTATION 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION, LIMITING CONDITICN FOR OPERATION 3.3.4.1 The anticipated transient without scram recirculation pump trip
.(ATVS-RPT) system instrumentation channels shown in Table 3.3.4.1-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3."L4.1-2.
APPLICABILITY: OPERATIONAL CONDITION 1.
ACTION:
- a. With an ATWS recirculation pump trip system instrumentation chaniel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.4.1-2, declare the channel inop: able until the channel is restored to OPERABLE status with its trip f setpoint adjusted consistent with the Trip Setpoint value.
2, 8 b. With the number of OPERABLE channels one less than required by the _ _ _l b Minimum OPERABLE Channels requirement for one trip function in one d
p[ trip system, restore the inoperable channel to OPERABLE status within 14 days or be in at least STARTUP within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, y SURVEILLANCE REQUIREMENTS 4.3.4.1.1 Each ATWS recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.4.1-1.
4.3.4.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
LA SALLE - UNIT 2 3/4 3-35
INSERT A
- b. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, place the inoperable channel (s) in the tripped condition within I hour,
- c. With the number of OPERABLE channels two or more less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip
! system and:
- 1. If the operable channels consist of one reactor vessel water level channel and one reactor vessel pressure channel, place both
- inoperable channels in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or, if this action will initiate a pump trip, declare tne trip system inoperable.
- 2. If the inoparable channels include two reactor vessel water level
! channels or two reactor vessel nressure channels, declare the trip system inoperable.
l d. With one trip system inoperable, restore the inoperable trip system to l OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- e. With both trip systems inoperable, restore at least one trip system to OPERABLE status within I hour or be in at least STARTUP within the next
! 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
i 1
l l-l N!.h ti ti: 3 L
.O l TABLE 3.3.4.1-1 . .
r-l ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION
, en l
l l
E MINIMUMOPERABLECHpNjELS 1
TRIP F8tNCTION FER TRIP SYSTEM l ..
i l c z 1. ReactoH Vessel Water Level - 1
-4 Low Low, level 2 :
~ 22 '
- 2. Reactor Vessel Pressure-High 1 4
1 i
! w l
D l
'1
. i f '
4 i
(a)One channel in one trip system may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required i surveillance provided that all other channels are OPERABLE.
I f
f
n.%
TABLE 4.3.4.1-1 9
m ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E CHANNEL CHANNEL FUNCTIONAL CHANNEL 7 TRIP FUNCT'M CHECK TEST CALIBRATION E 1. Reactor Vessel Water Level - 5 M R
~
-4 Low Low, Level 2 !
m
- 2. Reactor Vessel Pressure - High. NA H Q S
s
AlIACHMENI_C SIGNIFICANT llAZARDS CONSIDERATION Commonwealth Edison has evaluated the proposed Technical Specification Amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a significant hazards consideration established in 10 CFR 50.92, operation of LaSalle County Station Units 1 and 2 in accordance with the proposed amendment will not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated because:
The action requirements for Technical Specifications 3.3.4.1 provides a higher degree of protection and operational flexibility by addressing all possible combinations of inoperable channels and trip systems, The allowed outage times in the proposed amendment become progressively more restrictive depending on the nature of any failures. The proposed allowed outage. time for an inoperable trip channel is reduced from 14 days to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, The reduced outage times will not significantly increase the probability of an accident previously evaluated.
The proposed amendment to Table 3.3.4.1-1 increases the required number of instrumentation channels from 1 to 2 for each trip system. This enhanced design reflects modifications being made to the anticipated transient without scram-recirculation pump trip (ATHS-RPT) in response to 10 CFR Part 50.62 requirements.
This change clarifies the channel operability requirements for the ATHS-RPT instrumentation and ensures consistent application of the requirements. This amendment will not affect the performance of the ATWS-RPT system. Therefore, the consequences of an accident previously evaluated are not significantly increased by enhancing the ATHS-RPT logic.
The proposed amendment to Table 4,3.4.1-1 adds a shiftly
" channel check" requirement for the ATHS-RPT high reactor vessel pressure instrumentation. The addition of this requirement provides additional assurance of the ATWS-RPT instrumentation operability. The probability of an undetected instrument failure is lessened by the implementation of a shiftly " channel check". The current Technical Specifications do not require this surveillance.
l l
NLD641/24
m___ _ _ _ _ _ - _ _ _ _ _ . ._ _ _ .
AllACMELU_ClContinutd1 l
.ihis amendment also removes a footnote that allowed waiver of the 18 month surveillance interval for certain surveillance requirements during Unit 1 Cycle 1. This footnote is no longer j applicable and the change has no impact on-safety. !
?. ) - Create the possibility of a new or_different kind of accident from any accident previously evaluated because: )
l:
The proposed amendments are intended to clarify and enhance the- ,
existing Technical Specification requirements. The proposal reflects. improvements being made to the ATHS-RPT instrumentation and does not constitute a change to the operation of the '
' facility as described in the UFSAR. The reduction of allowed outage times from 14 oays to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for the-ATHS-RPT trip channels does not involve any changes to the facility or the operation of the facility as described in the UFSAR. The proposed amendment would not create the possibility of a new or different kind of accident from any accident previously o evaluated.
1:
Involve a significant reduction in the margin of safety because:
3) l The proposed amendments clarify and enhance _the existing i requirements for ATHS-RPT instrumentation. The changes will l help to reduce the potential for misinterpretation of the i requirements and institute additional surveillance requirements l for the new instrumentation. Therefore, it is CECO's expectation that the proposed amendments will increase the margin of safety.
- . Guidance has been provided in " Final Procedures and Standards on No t Significant Hazards Considerations," Final Rule, 51 FR 7744, for.the application of standards to license change requests for determination of the-existence oflsignificant hazards considerations. This document (51 FR 7744)-
provides examples of amendments which are and are not considered likely.to involve =significant hazards considerations. This proposed amendment does not involve a significant relaxation-of the criteria used to establish safety limits, a significant relaxation of the bases for the limiting' safety _ system- -
L settings or a significant relaxation of the bases for the limitir.g conditions for operations. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10CFR50.92(e), the proposed change-does not constitute a significant hazards consideration, l
l NLbe41/25 L _
ATTACHMENT _D ENVIRONMENTAL ASSESSMENT STATEMENT APPLICABILITY REVIEH Commonwealth Edison has evaluated the proposed amendment against the criteria for the identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.20. It has been determined that the proposed changes meet the criteria for a categorical exclusion as provided under 10 CFR 51.22(c)(9). This conclusion has been determined because the proposed changes do not pose a significant hazards 1 consideration or do not involve a significant increase in the amounts, and no !
significant changes in the types, of any effluents that may be released :
offsite. In addition, the proposed changes provide greater controls not included in the present Technical Specifications. This request does not involve a significant increase in individual or cumulative occupational radiation exposure. Therefore, the Environmental Assessment Statement is not applicable for these changes.
l f
I tilD U 41.'2 6 l
l