Proposed Rev to Tech Spec Table 3.3.2-2,allowing Main Steam Tunnel Leak Detection Differential Temp Setpoint to Be Raised to 36 F W/Max of 42 FML20091H361 |
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LaSalle |
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05/25/1984 |
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COMMONWEALTH EDISON CO. |
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Shared Package |
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ML20091H355 |
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NUDOCS 8406050140 |
Download: ML20091H361 (6) |
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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. 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[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
- - - _ _ - - _ . _ _ . _ - . _ _ _ _ . . - . _ - - _ . _ .
m COMMONWEALTH EDISON COMPANY LASALLE COUNTY-STATION UNITS 1 and 2 ,
TECHNICAL SPECIFICATION CHANGE REQUEST ATTACHMENT 1 i:
! BACKGROUND
-Reference _(a)' specifies the required setpoints for the Main '
-SteamLTunnel Differential Temperature (MSL delta T) Group 1 Isolation.
..These setpoints are-based on a 25 gpm leak in the main steam tunnel.
Reference (d) specifies that this setpoint will be based on a 1% to 10%
b rated. steam leak.- Prior to operation, calculations were performed by
-Sargent and.Lundy-(S&L) to determine initial setpoints. These setpoints were based on design information rather than actual plant as-built conditions. During the initial startup test program all-_the isolations
-setpoints of this: type were monitored to determine if setpoint. changes were required. At the completion of this testing, certain setpoints were
- 1+ ~found to-be non-con ~servative and were administratively controlled. These setpoints were corrected (Reference (b)). At that time it was noticed
. .that MSL. delta T setpoints were. conservative and could be raised; however, L Lbecause of changing plant ventilation conditions affecting the main steam tunnel due to_ Unit 2 startup, and design changes to improve temperature
-sensor location, no Technical Specification changes were requested:at j that time.
Discussion
- The Sargent and Lundy calculation LI-01 was used as the theoretical basis for the Technical' Specification setpoint of 240F differential temperature which would detect a 25 gpm steam leak in the main steam tunnel. . The 'value for the normal (no leakage) temperature n rise 1was tcr be verified by actual operating experience collected by Reference (e).
The accumulated data was forwarded to Sargent and Lundy.for
,cnalysis. .The results of that analysis state that the trip setpoint for the. dif ferential temperature should be 360F- with an allowable of 420F rather than the existing setpoint of 240F and allowable of 300F, ,
The theoretical calculation assumed a normal (no leakage) ,
temperature rise between inlet air sensors and outlet air sensors of
- .- -60F. With Unit 1 operating at full power, the normal (no leakage)
~ differential temperature is as high as 220F. To ensure that no leakage exists,. visual. inspections of the steam tunnel have been performed.
PP a r d a .m ~ .
i The difference between the original theoretical calculations and the actual observed values can be attributed to various factors-including: (1) lower actual total air flow and different air flow distribution than used_in the original calculations (2) lower inlet air temperatures to-the steam tunnel'than used in the original calculation and (3) higher,-more realistic, heat transfer rates through the insulation than those used in the theoretical calculations.
Summary At this time the actual differential temperature is very close to the Trip Setpoint of 240F as specified in Table 3.3.2-2. This does not allow sufficient margin for minor plant ventilation changes, or differing weather conditions or' instrument drift which may cause the no leakage actual MSL delta T to exceed the Trip Setpoint causing unnecessary and undesirable isolations. At this time single channel (half isolatio..) trips have occurred.. ~The main steam line space
' differential temperature setpoints should be set far enough above the actual no leakage conditions which are present in the steam tunnel at rated power to avoid spurious isolations and unnecessary challenges to plant systems, yet low enough to provide early_ indications of a steam line break. This Technical Specification change request should be approved as soon as possible to prevent a full isolation from occurring with no leak present.
The cumulative effect of these differences between theoretical and actual values justifies the request that-the main steam tunnel leak detection differential temperature setpoint should be raised to 360F with an allowable of 420F. This change also applies to FSAR Table 7.3-2. The FSAR will_be updated as part of the next annual update.
1 8696N
4 / A 4
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t 4
i-ATTACHMENT 2 I
j- Proposed Change to Appendix A Technical Specifications to l- _
~
Operating-Licensing NPF-ll and NPF-18 4-ti l
Revised'Pages; NPF-ll page 3/4 3-15 NPF-18-page 3/4 3 ;
6 4
e a
4 l'
L -8696N 1-I L
i l
l I
t-l i-
= . I TA8LE 3.3.2-2 ..
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS
, - ALLOWABLE
? TRIP SETPOINT VALUE E, TRIP FUNCTION A. AUTOMATIC INITIATION .
c
- 1. PRIMARY CONTAINMENT ISOLATION
'{ Reactor Vessel Water Level e a.
> 12.5 inches * ,
> 11.0 inches *
- 1) Low, Level 3 > -57 inches
- Low Low, level 2 > -50 inches
- 2) 1 1.69 psig 1 1.89 psig
- b. Drywell Pressure - High
- c. Main Steam Line 1 3.0 x full power background 5 3.6 x full background
- 1) Radiation - liigh ,
> 854 psig > 834 psig
- 2) Pressure - Low I 5 116 psid
- 3) Flow - High 5 111 psid
- d. Main Steam Line Tunnel $ 146*F**
Tsuperature - High 5 140*F** p*p w e. Main Steam Line Tunnel ; ggy ,
5 l
3: A Temperature - High ' f> M*F**
7 inches Hg vacuum
> 5.5 inches Hg vacuum u, f. Condenser' Vacuum - Low i
- 2. SECONDARY CONTAINMENT ISOLATION
- a. Reactor Building Vent Exhaust $ 15 mr/hr**
Plenum Radiation - High 5 10'ar/hr** i 1.89 psig
- b. Drywell Pressure - High i 5 1.69 psig
- c. Reactor Vessel Water ! > -57 inches
- Level - Low Low, Level 2 > -50 inches *
- d. Fuel Pool Vent Exhaust 1 15 mr/hr**
Radiation - High 5 10 mr/hr**
1 l
- 3. REACTOR WATER CLEANUP SYSTEM!' ISOLATION $ 87.5 gpm
- a. AFlow - High 1 70 gpm l b. Heat Exchanger Area Temperature < 191*F**
- Hi.gh, < 185'F**
~
~
- c. Heat Exchanger Area Ventilation < 101*F**
AT - High
< 95***
3160*F** 5166*Fa*
- d. " Pump Area Temperature :H10h $ 76*F**
- e. Pump Area Ventilation AT - High 1 70*F** NA NA
. f. SLCS Initiation g .- g., Reactor Vessel Water Level - > -5" inches *
> -57 inches
> I TABLE-3.3.2-2 -
b ISOLATION ACTUATION INSTRUMENTATION SETPOINTS m
jE ALLOWABLE E TRIP FUNCTION TRIP SETPOINT VALUE
' A. AUTOMATIC INITIATION k
a
- 1. PRIMARY CONTAINMENT ISOLATION
- a. Reactor Vessel Water Levell m .
, 1) Low, Level 3 > 12.5 inches *
> 11.0 inct.es*
{ 2) Low Low, Level 2 [-50 inches * [-57 inches *
- b. Drywell Pressure - High , i 1.69 psig i 1.89 psig l
- c. Main Steam Line j Radiation - High 3 3.6 x full background
~
j 1) $ 3.0 x full power background j ?'s Pressure - Loy ; > 854 psig
> 834 psig i
- 3) Flow - High . i 1 111 psid 5 116 psid I
i d. Main Steam Line Tunnel i Temperature - High 5 140*F 5 146*F .
j w e. Main Steam Line Tunnel g6 yp__
) A Temperature - High 1.24*F $ JU"F l w f. Condenser Vacuum - Low > 7 inches Hg vacuum > 5.5 inches Hg vacuum
- 2. SECONDARY CONTAINMENT ISOLATION 1 a. Reactor Building Vent Exhaust j Plenum Radiation - High 5 10 ar/h 5 15 mr/h
- b. Drywell Pressure - High 5 1.69 psig i 1.89 psig
- c. Reactor Vessel Water
- Level - Low Low, Level 2. > -50 inches *
> -57 inches *
- d. Fuel Pool Vent Exhaust Radiation - High 1 5 10 mr/h 1 15 mr/h '
i
- 3. REACTOR WATER CLEANUP SYSTEM ISOLATION
- a. AFlow - High ,,,
1 70 gpm 5 87.5 gpm
- b. Heat Exchanger Area Temperature
! - High < 181*F
-< 187'F i
- c. Heat Exchanger Area Ventilation Af - High < 85* *
< 91*F
- d. Pump Area Temperature - High i 116*F 7 122*F -
, e. Pump Area Ventilation AT - High 513*F 519*F
) f. SLCS Initiation . N.A. N.A.
j g. Reactor Vessel Water Level -
Low Low, Level 2 > -50 inches * > -57 inches *
! o - - - - _ _ _ -
\' '.
ATTACHMENT 3 SIGNIFICANT 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 10CFR50.92, 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 an accident previously evaluated because the differential temperature leak detection instrument setpoints which are revised will still provide isolation cabability at or below their design point as specified in the FSAR. These instruments are not part of the plant accident analysis as described in the FSAR and are only one of severa? methods for automatic isolation of the main steam. lines on loss of line integrity (such as MSL high flow, MSL area high ambient temperature, MSL low pressure).
- 2) _ Create the possibility of a new or different kind of accident from any previously evaluated because no equipment is removed or accident analysis changed. The original basis for the setpoint as specified in the FSAR is still maintained.
- 3) Involve a significant reduction in the margin of safety because the original basis for this instrumentation setpoint is not reduced or revised. The revised setpoints are based on actual plant data versus design data.
Based on the preceeding discussion, it is concluded that the proposed system change clearly falls within all acceptable criteria with respect to the system or-component, in that the consequences of previously evaluated accidents will not be increased and the margin of safety will not be decreased. 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.
8696N