Proposed Tech Specs,Revising Wording of Jet Pump Operability Surveillance to Required Balanced Drive Flow Rather than Equal Flow Control Valve PositionML20238B689 |
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LaSalle |
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Issue date: |
08/24/1987 |
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From: |
COMMONWEALTH EDISON CO. |
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Shared Package |
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ML20238B678 |
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3485K, NUDOCS 8709010350 |
Download: ML20238B689 (10) |
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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
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ATTACHMENT B a
PROPOSED CHANGES TO
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THE TECHNICAL SPECIFICATIONS FOR ,
OPERATING LICENSES NPF-11 AND NPF-18 l
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REVISED PAGES:
1 1
l NPF-ll NPF-18 3/4 4-2 3/4 4-3 l B 3/4 4-1 B 3/4 4-1 .I 1
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l 3485K j900350e70824 '
P DOCK 05000373 PDR 1
y i
i REACTOR COOLANT SYSTEM i JET PUMPS . f LIMITING CONDITION FOR OPERATION
$(
3.4.1.2 All jet pumps shall be OPERABLE. $i APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2. !
ACTION:
s With one or more jet pumps inoperable, be in at least HOT SHUT 00WN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.1.2.1 Each of the above required jet pumps shall be demonstrated OPERABLE ;
prior to the THERMAL POWER exceeding 25% of RATED THERMAL POWER and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by measuring and recording each of the below specified l parameters and verifying that no two of the following conditions occur when both recirculation loops are operating at the :=: fi:n ::ntr:1 :h: p::ithn.
ws% botsnced Flov).
- a. The indicated recirculation loop flow differs by more than 10% from the established flow control valve position-loop flow characteristics for two recirculation loop operation. ,
- b. The indicated total core flow differs by more than 10% from the established total core flow value derived from either the:
- 1. Established THERMAL POWER-core flow relationship, or Mjferential
- 2. Established core plate i .:t:nt h i pressure-core flow relation-ship for two recirculation loop operation.
- c. The indicated diffuser-to-lower plenum differential pressure of any I individual jet pump differs from established two recirculation loop operation patterns by more than 10%.
4.4.1.2.2 During single recirculation loop operation, each of-the above required jet pumps shall be demonstrated OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that no two of the following conditions occur:
4he
- a. The indica recirculation loop flow in the operating loop differs by more a 10% from the established single recirculation flow control va ve position-loop flow characteristics.
- b. The indicated total core flow differs by more than 10% from the established total core flow value from single recirculation loop ow measurements 8'ejerived from e,#,er +4e:
ggg
- c. The indicated diffuser-to-lower plenum differential pressure of any individual jet pump differs from established single recirculation loop operational patterns by more than 10%.
LA SALLE - UNIT 1 3/4 4-2 Amendment No.
I 3/4.4 REACTOR COOLANT SYSTEM BASES j l
3/4.4.1 RECIRCULATION SYSTEM j Operation with one reactor core coolant recirculation loop inoperable has 3, been evaluated and been found to be acceptable provided the unit is operated j!
in accordance with the single recirculation loop operation Technical Specifi- )l cations herein. # '
An inoperable jet pump is not, in itself, a sufficient reason to declare a recirculation loop inoperable, but it does present a hazard in case of a design-basis-accident by increasing the blowdown area and reducing the capability of reflooding the core; thus, the requirement for shutdown of the l facility with a jet pump inoperable. Jet pump failure can be detected by l monitoring jet pump performance on a prescribed scheduled for significant degradation I N N O . Recirculation loop flow mismatch limits are in compliance with the ECCS LOCA analysis design criterion. The limits will ensure an adequate core flow coastdown from either recirculation loop following a LOCA. Where the recircu- ]
lation loop flow mismatch limits can not be maintained during the recirculation i loop operation, continued operation is permitted in the single recirculation loop operation mode.
In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop temperatures shall be within 50 F of each other prior to startup of an idle loop. The loop temperature must also be within -
50 F of the reactor pressure vessel coolant temperature to prevent thermal shock to the recirculation pump and recirculation nozzles. Since the coolant in the bottom of the vessel is at a lower temperature than the water in the upper regions of the core, undue stress on the vessel would result if the temperature difference was greater than 145 F.
The possibility of thermal hydraulic instability in a BWR has been inves-tigated since the startup of early BWRs. Based on tests and analytical models, it has been identified that the high power-low flow corner of the power-to-flow map is the region of least stability margin. This region maybe encountered during startups, shutdowns, sequence exchanges, and as a result of a recircula-tion pump (s) trip event.
To ensure stability, single loop operation is limited in a designated restricted region (Figure 3.4.1.1-1) of the power-to-flow map. Single loop 4 operation with a designated surveillance region (Figure 3.4.1.1-1) of the i power-to-flow map requires monitoring of APRM and LPRM noise levels.
3/4.4.2 SAFETY / RELIEF VALVES The safety valve function.of the safety relief valves operate to prevent
~
the reactor coolant system from being pressurized above the Safety Limit of 1325 psig in accordance with the ASME Code. A total of 18 OPERABLE safety /
relief valves is required to limit reactor pressure to within ASME III allowable values for the worst case upset transient.
Demonstration of the safety-relief valve lift settings will occur only.
during shutdown and will be performed in accordance with the provisions of Specification 4.0.5.
LA SALLE-UNIT 1 B 3/4 4-1 Amendment No 40 '
INSERT A q
- 1. Established THERMAL POWER-core flow relationship, or
- 2. Established core plate differential pressure-core flow relationship for two recirculation loop operation.
l INSERT B l
During dual loop operation, the jet pump operability surveillance should be performed with balanced drive flow (drive flow mismatch less than 5%) to ensure an accurate indication of jet pump performance.
1 I
l 3500K
REACTOR COOLANT SYSTEM JET PUMPS I LIMITIMG CONDITION FOR OPERATION 3.4.1.2 All jet pumps shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
, With one or more jet pumps inoperable, be in at least HOT SHUTOOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, ,
i SURVEILLANCE REQUIREMENTS 4.4.1.2.1 Each of the above required jet pumps shall be demonstrated OPERABLE prior to THERMAL POWER exceeding 25% of RATED THERMAL POWER and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by measuring and recording each of the below specified parameters and verifying that no two of the following conditions occur when both recircula- l tion loops are operating :t th: ::= f ht :: .tr:;' :h: p::it;;r.. l wi% hlured flow. l
- a. The indicated recirculation loop flow differs by more than 10% from the established flow control valve position-loop flow characteristics for two recirculation loop operation.
- b. The indicated total core flow differs by more than 10% from the ,
established total core flow value derived from either the:
]
- 1. Established THERMAL POWER-core flow relationship, or
- 2. Established core plate differential pressure-core flow relationship for two recirculation loop operation.
- c. The indicated diffuser-to-lower plenum differential pressure of afiy individual jet pump differs from established two recirculation loop
, operation patterns by more than 10%.
4.4.1.2.2 During single recirculation loop operation, each of the above required jet pumps shall be demonstrated OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that no two of the following conditions occur:
fhM
- a. The indica recirculation loop flow in the operating loop differs by more a 10% from the established single recirculation flow II control va ve position-loop flow characteristics.
- b. The indicated total core flow differs by *more than 10% from the established total core flow value from single recirculation loop
.TNSERT c.A +i1ow measurementsfdenWd'fmm eiker Noe:
The indicated diffuser-to-lower plenum differential pressure of l any individual jet pump differs from established single recirculation loop by more than 10%.
LA SALLE - UNIT 2 3/4 4-3 dment No.
< 3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 RECIRCULATION SYSTEM
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Operation with one reactor recirculation loop inoperable has been evaluated and been found to be acceptable provided the unit is operated in accordance with i ;
the single recirculation loop operation-Technical Specifications herein.
An inoperable jet pump is not, in itself, a sufficient reason to declare a recirculation loop inoperable, but it does present a hazard in case of a design-basis-accident by increasing the blowdown area and reducing the capability of reflooding the core; thus, the requirement for shutdown of the facility with a jet pump inoperable. Jet pump failure can be detected by monitoring jet pump performance on a prescribed scheduled for significant degradation
.TNSERT 6 lecirculationloopflowmismatchlimitsareincompliancewiththeECCS LOCA analysis design criterion. The limits will ensure an adequate core flow coastdown from either recirculation loop following a LOCA. Where the retir-culation loop flow mismatch limits can not be maintained during the recir-culation loop operation, continued operation is permitted in the single recirculation loop operation mode.
In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop temperatures shall be within 50 F of each other j prior to startup of an idle loop. The loop temperature must also be within ,
50 F of the reactor pressure vessel coolant temperature to prevent thermal shock to the recirculation pump and recirculation nozzles. Since the coolant .
in the bottom of the vessel is at a lower temperature than the water in the ;
upper regions of the. core, undue stress on the vessel would result if the
~
temperature difference was greater than 145 F.
The possibility of thermal hydraulic instability in a BWR has been investi- l gated since the startup of early BWRs. Based on tests and analytical models, -
it has been identified that the high power-low flow corner of the power-to-flow l map is the region of least stability margin. This region may be encountered ;
during startups, shutdowns, sequence exchanges, and as a result of a retircula-tion pump (s) trip event.
To ensure stability, single loop operation is limited in a designated j restricted region (Figure 3.4.1.1-1) of the power-to-flow map. Single loop t operation with a designated surveillance region (Figure 3.4.1.1-1) of the !
power-to-flow map requires monitoring of APRM and LPRM noise levels. !
3/4.4.2 SAFETY / RELIEF VALVES The safety valve function of the safety / relief valves operate to prevent the reactor coolant system from being pressurized above the Safety Limit of 1325 psig in accordance with the ASME Code. A total.of 18 OPERABLE safety /
relief valves is required to limit reactor pressure to within ASME III allowable values for the worst case upset transient.
j Demonstration of the safety / relief valve lift settings will occur only during shutdown and will be performed in accordance with the provisions of Specification 4.0.5.
LA SALLE - UNIT 2 B 3/4 4-1 Amendment No. [3
INSERT A
- 1. Established THERMAL POWER-core flow relationship, or
- 2. Established core plate differential pressure-core flow relationship for two recirculation loop operation.
INSERT B j During dual loop operation, the jet pump operability surveillance should be performed with balanced drive flow (drive flow mismatch less than 5%) to ensure an accurate indication of jet pump performance.
1 1
i 1
3500K
l 1
ATTACHMENT C TECHNICAL SPECIFICATION CHANGE REQUEST LASALLE COUNTY STATION UNITS 1,and 2 NO 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 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:
l This proposed change of the Technical Specifications is an ,
administrative change to clarify the conditions necessary to perform the !
jet pump operability surveillance and correct typographical errors.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated because:
This proposed change of the Technical Specifications is an administrative change to clarify the conditions necessary to perform the jet pump operability surveillance and correct typographical errors.
- 3) Involve a significant reduction in the margin of safety because:
This proposed change of the Technical Specifications is an administrative change to clarify the conditions necessary to perform the jet pump operability surveillance and correct typographical errors.
Guidance has been provided in 51 FR 7744 (reference (c)), for the application of standards to license change requests for determination of the existence of significant hazards considerations. This document provides i
examples of amendments which are not likely considered to involve significant hazards considerations. This proposed amendment most clearly resembles example e(i) of those examples deemed not likely to involve a significant i
hazards consideration. It is purely an administrative change meant to clarify the requirements.
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1 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 settings or a significant relaxation of the bases for limiting conditions for operations. Therefore, based on the guidance provided in 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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l ATTACHMENT D TECHNICAL SPECIFICATION CHANGE REQUEST ;
LASALLE COUNTY STATION UNITS 1 AND 2 GENERAL ELECTRIC REPORT EA5-59-0687 NSSS PERFORMANCE EFFECTS DUE TO USE OF BLACK FOX RECIRCULATION PUMP IMPELLER AT LASALLE UNIT 1 i
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