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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
. _. . - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Attachment.B Proposed changes to Appendix A, Technical Specifications of Facility Operating Licenses NPF 18 and NPF 11.
Revised Pages UnlLL(NEFA.1) UnlL2JNPF 18) 3/4 1 4 3/4 1-4 3/4 1 5 3/4 1 5 i
l
)
i EN1.0745/10 9104300360 910424 PDR ADOCK 05000373 P POR
~
l l
REACTIVITY CONTROL SYSTEM k LIMITING CONDITION FOR OPERATION (Continued)
ACTION (Continueo)
- 2. 'If the~ inoperable control rod (s) is inserted: -
a) Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> disarm the associated directional control l valves
- 1) Electrically, or
- 2) Hydraulically by closing the drive water aM exhaust water isolation valves.
b) Otherwise, be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
6fE 3. The provisions of Specification 3.0.4 are not applicable.
l
_ c. With more than 8 control rods inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
L -
p SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE by:
- a. At least once per 31 days verifying each valve to be open**, and l
- b. At least once per 92 days cycling each valve through at least one complete cycle of full travel.
4.1.3.1.2 When above the low power setpoint of the RWM and RSCS, all withdrawn control rods not required to have their directional control valves disarmed electrically or hydraulically shall be demonstrated OPERABLE by moving each control rod at least one notch:
- a. At least once per 7 days, anti
- b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when any control rod is immovable as a result of excessive friction or mechanical interference.
4.1.3.1.3 All control rods shall be demonstrated OPERABLE by performance of l Surveillance Requirements 4.1.3.2, 4.1.3.4, 4.1.3.5, 4.1.3.6 and 4.1.3.7.
, *May be rearmed intermittently, under administrative control, to permit testing l associated with restoring the control rod to OPERABLE status.
- These valves may be closed intermittently for testing under administrative l control.
LA SALLE - UNIT 1 3/4 1-4 Amendment No. 18
- - _ . . - . . _ ._. .... ~._ -. - .. - - -. -. ..___ .- -.
l s ,
REACTIVITY CONTROL SMTJ SURVEILLANCE REQUIREMENTS (Continued) 4.1. 5.1. 4 The. scram discharge volume shall be determined OPERABLE by '
demonstrating:
- a. The scram discharge volume drain and vent valves OPERABLE, when .
control rods are scram tested from a normal control rod configura- 2 tion of less than or equal to 50% ROD DENSITY _ at least once per ,
18 months
- by verifying that the drain and vent valves:
l
.1. Close within 30 seconds after receipt of a signal for control rods to scram, and ,
- 2. Open after the scram signal is reset. ;
[b. Proper float response by performance of a CHANNEL FUNCTIONAL TEST of the scram discharge volume-scram and control rod block level instewntation af ter each scram from a pressurized condition.
7 4
4 1
"The provisions of-Specification 4.0.4 are-not applicable for entry into
' OPERATIONAL CONDITION 2 provided the surveillance is performed within
-12 hours-after achieving less than or equal to 50% ROD DENSITY. -
LA St',LE - UNIT 1 3/4 1-5 Amendment No. 18
~,
T INSERT A I'
d.- With one scram discharge volume vent valve and/or one scram dischar e volume drain valve inoperable and open, restore the Inoperable valve ( to - -.
OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN 'Ithin the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.--
~
- e. With any scram discharge volume vent valve (s) and/or any scram discharge !
otherwise inoperable, restore the inoperable valve (s) to -i OPERABLEdrain volume status valve w (s)ithin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOl next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, i la
.r
?
r ZNLD747/23
... , .____._. __ . _ _ _ _ . _ _ . ._._..m . ... _ _ _ . . __ _ . .
'. . 6;,[.?
~
,y(f(
REACTIVITY CONTROL SYSTEM.
LIMITING CONDITION FOR OPERATION (Continued)
ACTION (Continued)
- 2. 'If thelinoperable control rod (s) is inserted:
a) Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> disarm the associated directional control-valves
1)- Electrically,' or
- 2) -Hydraulically by clusing._the drive water and exhaust-water isolation valves.
4 b) Otherwise, be= in at least HOT SHUTDOWN within the next
. -12 hours.
7k( 3.. - The provisions of Specification 3.0.4 are not apolicable'.-
.i c.
With more than 8 control rods inoperable, be-in at least HOT SHUTDOWN
=within-12 hours.
2 '
1 SURVEILLANCE REQUIREMENTS
.+
4.1.3.1.1- The scram discharge volume' drain and vent valves shall be~ demonstrated OPERA 8LE.by:
s
's. At:least once-per 31 days verifying each valve _to be.open**, and'
- b. _ 1 At_least once per 92 days cycling each valve through at:1 east one:
complete' cycle of full-travel.. .-
4:
4.1.3.1.2 When above the-low power setpoint of5the RWM and RSCS, all withdrawn o
control rods not required.to 'have their directionalt control valves disarmed -
~ electrically or hydraulically shalltbe demonstrated OPERA 8LE by: moving _each-W : control rod at least one notch:-
- .. . a.. At'least once per_7Ldays, and; b . -- 1At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when any contro} rod.is immovable as a'
'@ result of excessive friction or mechanical- interference, _
a 4 14.1.3.1.3 All control rods shall be demonstrated 0PERABLE by-performance of-L. Surveillance Requirements 4.1. 3. 2, . 4.1. 3. 4,- 4.1. 3. 5, 4'.1. 3. 6, ' and 4.1. 3. 7.
b a
-+
o "May be rearmed intermittently, under administrative control, to permit testing
+ associated with restoring the; control' rod to OPERA 8LE status.
' **These valves may be closed intermittently for testing under administrative 4
control.
LA SALLE-- UNIT 2- 3/4 1-4
- z.-. __ . _ . _ . . . _
~
REACTIVITY CONTROL SYSTEM
( SURVEILLANCE REQUIREMENTS (Continued) 4.1.3.1.4 The scram discharge volume shall be determined OPERABLE by demonstrating: !
- a. The scram discharge volume drair. and vent valves OPERABLE,.when . j control rods are scram tested from a normal control rod configura-tion of less than or equal to 50% ROO DENSITY at least once per 18 months
- by verifying that the drain and vent valves:
- 1. Close within 30 seconds after receipt of a signal for control rods to scram, and 1
- 2. Open after the scram signal is reset. l
[b. Proper float and level sensor response by performance of a CHANNEL i l
FUNCTIONAL TEST of the scram discharge volume scram and control rod block level instrumentation at least once per 31 days. )
t!
- The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 2 provided ths. surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> af ter achieving less than or aqual to 50% ROD DENSITY.
LA SALLE - UNIT 2 3/4 1-5
9 9
{
INSERT A
- d. With one scram discharge volume vent valve and/or one scram dischar e volume drain valve inoperable and open, restore the inoperable valve ( to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN lthin the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- e. With any scram discharge volume vent valve (s) and/or any scram discharge vo!ume drain valve (s) otherwise inoperable, restore the inoperable valve (s) to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 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 />.
y a
ZNLD747/23
- AttachmenLC 1
Evaluation _otSignificant Hazards _ 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 establishment of an allowed outage time (AOT) for the scram discharge volume (SDV) vent and drain valve will not significantly increase the probability of an accident previously evaluated. The proposed AOT introduces a minor increase in the risk of a loss of coolant via the SDV vent and/or drain valve pathway. However, this event can only occur if the redundant valve should f all to close after a reactor scram. The probability of such an event is reduced by the use of redundant valves in the pathway. Therefore, the proposed AOT does not involve a significant increase in the probability of an accident as previously evaluated for LaSalle Station.
The consequences of an accident previously evaluated are not significantly increased by creating the AOT for the SDV vent and drain valve. As previously mentioned, the proposed AOT for the SDV system increases the risk of a loss of coolant via the SDV vent and/or drain valve pathway. However, the volume of coolant lost via this pathway is relatively small. Also, this event can only occur following a reactor scram. The primary concern associated with a SDV vent and/or drain valve failure to close following a reactor scram is secondary containment contamination. Therefore, the consequences of an accident previously evaluated is not significantly increased.
lf any of the SDV vent or drain valves fall closed the SDV will fill as a result of normal control rod drive leakage. The increasing level will cause successively an alarm, a control rod block and finally a reactor scram if action is not taken to reopen the valves and drain the SDV. The reactor scram will occur while there is still enough volume remaining in the SDV to ensure a full reactor scram.
Therefore the ability to shut the reactor down under this f ailure mode is not impaired.
Deletion of Specification 4.1.3.1.4.b which contains the channel functional test requirements for SDV level detector instruments does not increase the probability or consequences of a previously evaluated accident. The requirements are either obsolete or redundant to other technical specification requirements.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated because:
The establishment of an AOT does not involve any changes to the facility or the operation of the facility as described in the UFSAR.
Surveillance requirements for the SDV level instrumentation are covered under the RPS and control rod block instrumentation Technical Specification requirements.
ZitLD#45(5
Attachment.C r
EvaluatiottoLSigolficant Hazards _Considoration (Cont.)
- 3) Involve a significant reduction in the margin of safety because:
Establishment of an AOT where none currently exists may result in a small increase in risk, however it is expected that this increase will be offset by the reduction of risk to plant safety resulting from a reduced number of unnecessary plant shutdowns.
The surveillance requirements for the SDV level Instruments are adequately addressed in the RPS and control rod block Instrumentation specifications.
Therefore deletion of specification 4.1.3.1.4.b will not reduce the margin of safety.
Guidance has been provided in " Final Procedures and Standards on No Significant Hazards Considerations," Final Rule,51 FR 7744, for the application of standards to license change requests for determination of the existence of significant hazards considerations. This document 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 conditions for operations. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10 CFR 50.92(e), the proposed change does not constitute a significant hazards consideration.
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. . AttachmentD EnykonmentalAssessmenLStatement.ApplicabilityBevie.w 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 51.21. It has been determined that the prowsed change meets the criteria for a categorical exclusion as provided for under 10 CFR 51.22(c)(10). This determination is based on the f act that this change is being proposed as an amendment to a license issued pursuant te 10 CFR 50. This proposed change involves no significant hazards consideration or a significant change in the types or significant increase in the amounts of any effluents that may be released offsite. In addition, this amendment request does not involve a significant increase in individual or cumulative occupational radiation exposure.
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