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 3.3.3-2ML20195E054 |
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Site: |
LaSalle ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
11/09/1998 |
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From: |
COMMONWEALTH EDISON CO. |
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To: |
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Shared Package |
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ML20195E053 |
List: |
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References |
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NUDOCS 9811180223 |
Download: ML20195E054 (8) |
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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
_ . _ _ . _ _ . _ _ . _ _ . . - . __. . _ _ . _ . _ . _ . _. __ .
f -
g TABLE 3.3.3-2(Continued) -
EfERGENCY CORE COOLING SYSTEM ACTUATION INSTIMENTATIOM SETP0lNTS ,
ALLOWABLE TRIP FINICTION TRIP SETP0 INT VALUE i
n p, ~o;2 ' ~
q C. DIVISION 3 TRIP SYSTEM .
q-p
- 1. HPCS SYSTEM n s
[ .
Reacter Vessel Water Level - Low Low, Level 2
- a. >- 50 inches * >- 57 inches 3 C.n
- b. Drywell Pressure - Hi @ i 1.69 e (b
- c. Reacter Vessel Water .evel - High, Level 8 7 1.89 P s 9* 5
- d. Deleted
?55.5 lies * . 156inc o
,,y
- e. Deleted 3T !
- f. Pische Pressure - High > 120 psig > 110 psig O 5
- g. System ow Rate - Low i 1000 pm F 900 p m E. l
- h. Manual Intiation M M $_%{
., [. D. : LOSS OF POWER E 1. 4.16 kV Ese Bus Undervoltage
~
( ,
i (LossofVo1 age #
- a. 4.16 kV Suses l
- -l
- 1) Divisions 1 and 2 2625 i 131 volts with 2625 1 262 volts with !
i 10 seconds time delay 1 11 seconds time delay 2496 i 125 volts with 2496 i 250 volts with
> 4 seconds time delay > 3 seconds time delay ,
- 2) Division 3
' 2870 i 143 volts with 2870
- 287 volts with i 10 seconds time delay i 11 seconds time delay F
- See Bases Figure 5 3/4 3-1.
3 IThese are inverse time delay voltage relays or instantaneous voltage relays with a time delay. The voltages shown are the maximum that will not result in a trip. Lower voltage conditions will result in i 2 decreased trip times. i
. l
~
jn"E8ERUssjb
t TABLE 3.3.3-2(Continued) g EERGEKY CORE COOLIE SYSTEN ACTMTION INSTRISENTATION SETFOINTS - -
E ~
i TRIP FUNCTION ALLOWBLE TRIP SETPOINT VALUE h 2. -4.16 kV Ese (DegradedVo ag)
Bus Undervoltage
- a. 4.16 kV Buses >
P b
- 1) Divistens 1, 2 and 3 14 i X) volts with l 14 i S veits with .
10 1 1 seconds time 10 i I seconds time delay with LOCA stenal delay wfth LOCA signal er er 5 i 0.5 minutes time 5 1 0.5 minutes time de without LOCA del without LOCA si g 1 si 1
.. y 2 n .
r N
>* i
, .-~. .
TABLE 3.3.3-2 (Continued) -
g EE RGENCY CORE C00LIIr 3Y5TUrXETUATIGN INSTRtN NTATION SETPOINTS ALLOWA8LE E TRIP FUNCTION TRIP SETPOINT -
VALUE 4 o 2 ~
5 O C. DIVISION 3 TRIP SYSTEM .
- 1. HPCS SYSTEM E
U a. Re ator Vessel Water Level - Low Low, Level 2 >- 50 inches * >- 57 inches
n N b.
c.
Drywell Pressure - Hif Reactor Vessel Water .evel - High, Level 8 i 1.69 psig
'-Y 55.5 inches
i 56 inches S
A $
- d. Deleted i
- e. Deleted Pump Discharge Pressure - High > 120 psig > 110 psig 3E'2 b
~h f.
- g. HPCS System Flow Rate - Low 5_ I
> 1000 gym > 900 gym j 3 n)
Manual Intiation
- h. R.A. R.A.
}
D. LOSS OF POWER R 1. 4.16 kV Emergency Bus Undervoltage .
.. * (Loss of Voltage)#
Y -
- a. 4.16 kV Buses l
- 1) Divisions 1 and 2 2625 i 131 volts with 2625 1 262 volts with 1 10 second time delay 1 11 second tint delay 2496 i 125 volts with 2496 i 250 volts with
> 4 second time delay > 3 second time delay
- 2) Division 3 2870 i 143 volts with 2870 1 287 volts with 1 10 second time delay 1 11 second time delay F TABLE NOTATIONS
=
- See Bases Figure B 3/4 3-1.
- These are inverse time delay voltage relays or instantaneous voltage relays with a time delay. The voltages
,F shown are the maximum that will not result in a trip. Lower voltage conditions will result in decreased trip times.
M N.A. Not Applicable
- I
.- -s.
t -
..)
s .e TABLE 3.3.3-2 (Continued) ,-
E EDERGENCY CORE COOLING SYSTEM ACTUATION INSTIRNENTATION SETPOINTS - !
M!
g- ALLOWR8LE
. i m
TRIP FINICTION TRIP SETPOINT VALUE 6
8 g D. LOSS OF POWER'(Continued) -
Q 2. 4.16 kV Ese Bus Undervoltage
~
l (negraded Vo tage) >3g70 - ,23g/
- a. 4.16 kV Buses p F l ,
- 1) Divisions 1, 2 and 3 14
~
4 1 3 volts with -
i 10
- 1 seconds time 10 i 1 seconds time delay -
delay with LOCA signal with LOCA signal !
or or !
5
- 0.5 minutes time delay delay without LOCA without LOCA signal ;
signal k* s Y
f I
2 Y
.M E
t
. . - . _ . . ~ _ - .. . - - _m. _ m._...__._ _ . _ _ _ .- _ _ ._ ..__ _ _ _ _ _ _ _
t ATTACHMENT C
' SIGNIFICANT HAZARDS CONSIDERATION
~
Commonwealth Edison (Comed) ha evaluated this proposed amendment and determined that it
' involves no signi6 cant hazards consideration. . According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazards consideration if operation of facility in accordance with the proposed amendment will not:
Involve a significant increase in the probability or consequences of an accident previously ,
evaluated; I
Create the possibility of a new or different kind of accident from any previously analyzed; or Involve a significant reduction in a margin of safety.
Comed proposes to amend Appendix A, Technical Specifications, of Facility Operating Licenses
' NPF-11 and NPF-18, LaSalle County Station Units 1 and 2. %e proposed amendment requests a -
change to the Technical Specifications to modify the degraded voltage second level undervoltage relay ,
setpoint and allowable values. The affected Technical Specification is Technical Specification 3/4.3.3, ECCS System Actuation Instrumentation, and Technical Specification Table 3.3.3-2, ECCS System L Actuation Instrumentation Setpoints. The proposed changes are supported by calculations that address known instrument errors and plant accident bus loading conditions.
The determination that the criteria set forth in 10 CFR 50.92 are met for this amendment request is
- indicated below
- -
- 2
- Does the change involve a significant increase in the probability or consequences of an accident
- previously evaluated?
l %e setpoint change does not change the logic or function of the degraded voltage protection L circuits as described in UFSAR Section 8.2.3. Hey also do not reduce the reliability of these l ' circuits. %e increase in the degraded voltage protection circuit setpoint is conservative L compared to the existing setpoint. There is no change as a result of this amendment to the underlying accident and transient analyses that support operations of.LaSalle County Station.
Inadvertent or spurious operation of the degraded voltage protection function will initiate L
loading of the safe shutdown loads on the diesel generators and is not assumed to initiate an accident. %e proposed degraded voltage setpoints are low enough to prevent spurious actuations given the expected offsite grid voltages. After implementation of this amendment, no operator actions are required for equipment operations in response to degraded voltage conditions.
P his change does not affect the initiators or precursors of any accident previously evaluated.
, his change will not increase the likelihood that a transient initiating event will occur because
, transients are initiated by equipment malfunction and/or catastrophic system failure.
1.
t C-1 L
ATTACHMENT C SIGNIFICANT HAZARDS CONSIDERATION The consequences of accidents previously evaluated are not increased. He proposed change does not affect the required level of availability of systems required to mitigate the accidents considered in the analyses. The proposed changes will ensure that the Class 1E equipment will be capable of starting and operating during a design basis accident with degraded offsite grid voltage. %e increase in the level of confidence is the result of the more rigorous methodology used to determine limiting Class 1E bus voltages at the minimum expected l offsite AC voltage. %ese calculations demonstrate that the degraded voltage relays will not I actuate follomng a block start of the electrical loads that are automatically actuated by or as a consequence of the LOCA signal if the switchyard voltage remains above 352 kV.
If the grid voltage drops below 352 kV, then the analytical limit of 3814 volts for proper i operation of class 1E loads connected to each 4.16 kV Class 1E bus is assured by transfer to I the respective onsite power sources (Emergency Diesel Generators (EDGs)) by the degraded i voltrge logic.
Herefore this proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated because:
Setpoint methodology established the bases to ensure that, with known errors, the relays will ,
detect degraded voltage conditions and transfer safety loads to the EDGs at a voltage level l adequate to ensure proper safety equipment performance and to prevent equipment damage. j The 2 3870 volt setpoint and the 2 3814 volt allowable value includes adequate tolerance to );
calibrate the relay trip units while ensuring that the Class 1E bus voltage will remain above the analytical limits.
These setpoint changes will ensure that adequate voltages will be available for the continuous operation of safety-related equipment required to function during a LOCA. These proposed changes will also ensure that adequate voltages will be available for starting any Class 1E equipment.
l l
C-2 l
1 l
. l l
ATTACHMENT C SIGNIFICANT HAZARDS CONSIDERATION The proposed degraded voltage serpoint change does not change the design of the degraded voltage protection system or its function to protect against degraded offsite power. Actuation of the degraded voltage protection system will initiate a sequence of events that will start the EDG for the associated Class 1E bus, strip loads from the Class 1E bus, open all feed breakers to the Class 1E bus, close the Emergency feed breaker (thus energizing the Class 1E bus from the respective EDG), and initiate starting of the Safe Shutdown equipment supplied by the Clus 1E bus.
Since the scope of this change does not affect the operation of the auxiliary power system or any actions necessary to mitigate the consequences of accidents or achieve safe shutdown, the change does not involve a new or different accident scenario.
Therefore, these proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3) Involve a significant reduction in the margin of safety because:
The proposed amendment will allow the degraded voltage serpoint to be conservatively established based on new engineering calculations which consider the lowest expected offsite grid voltage and operation of required Class 1E equipment under design basis accident loading conditions.
1
%e proposed degraded voltage serpoints will ensure that adequate Class 1E bus voltage will be available to support starting and operation of required Class 1E loads. The proposed setpoint includes instrument error to ensure that the lowest possible voltage will not be lower than the degraded voltage analytical limits. Additionally, the proposed serpoints are low enough to prevent spurious actuations due to expected Ductuations in the grid voltage. The new setpoints are also set with margin to the minimum Class 1E bus voltage, which is based on a minimum grid voltage of 352 kV, which is less than the expected grid voltage of 354 kV. The proposed changes will provide an increase in the level of protection that currently I exists and will ensure the margin of safety is adequately maintained.
l Therefore, these changes do not involve a significant reduction in the margin of safety.
Therefore, based upon the above evaluation, Comed has concluded that these changes involve no significant hazards consideration.
l l
C-3
l ATTACHMENT D ENVIRONMENTAL ASSESSMENT STATEMENT APPLICABILITY REVIEW Comed has evaluated this proposed operating license amendment request against the criteria for identification oflicensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.21. Comed has determined that the proposed license amendment request meets the criteria for a categorical exclusion set forth in 10 CFR 51.22(c)(9) and as such, has determined that no irreversible consequences exist in accordance with 10 CFR 50.92(b). This determination is based on the fact that this change is being proposed as an amendment to a license issued pursuant to 10 CFR 50 that changes a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or that change an inspection or a surveillance requirement, and the amendment meets the following specific criteria:
- 6) the amendment involves no significant hazards consideration.
As demonstrated in Attachment C, this proposed amendment does nat involve any significant hazards consideration.
(u) there is no significant change in the types or significant increase in the amouitts of any effluent that may be released offsite.
As documented in Attachment A, there will be no change in the types or significant increase in the amounts of any effluents released offsite.
i Qii) there is no significant increase in individual or cumulative occupational radiation exposure.
'Ihe proposed changes will not result in changes in the operation or configuration of the facility. There will be no change in the level of controls or methodology used for processing of radioactive effluents or handling of solid radioactive waste, nor will the proposal result in any change in the norma" radiation levels within the plant. Therefore, there will be no increase in individual or cumulative occupational radiation exposure resulting from this change.
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l D-1