05000254/LER-1996-025, Forwards LER 96-025-00 Re Operability Calculations Performed on ECCS Suction Strainers W/Incorrect Head Loss Values

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Forwards LER 96-025-00 Re Operability Calculations Performed on ECCS Suction Strainers W/Incorrect Head Loss Values
Person / Time
ML20134A170
Site:	Quad Cities
Issue date:	01/22/1997
From:	Pearce L COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20134A173	List: 05000254/LER-1996-025, Forwards LER 96-025-00 Re Operability Calculations Performed on ECCS Suction Strainers W/Incorrect Head Loss Values 05000254/LER-1996-025-01, :on 961220,discovered Original Value for Strainers Head Loss Incorrect.Cause Could Not Be Determined. Training Provided for Operators to Recognize Pump Cavitation During Design Basis Accidents
References
LWP-97-006, LWP-97-6, NUDOCS 9701280196
Download: ML20134A170 (1)
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LER-1996-025, Forwards LER 96-025-00 Re Operability Calculations Performed on ECCS Suction Strainers W/Incorrect Head Loss Values

Event date:
Report date:
2541996025R00 - NRC Website
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text

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Commonwealth Idmn Compan)

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Quad Cines (eentrating Station 12*lo 2@4h M enue North [ordou 11. 612 4 2 9* 10 Irl MNM e-22 a l LWP-97-006 January 22, 1997 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk Reference: Quad Cities Nuclear Power Station Docket Number 50-254, DPR-29, Unit one Docket Number 50-265, DPR 30, Unit Two Enclosed is Licensee Event Report (LER)96-025, Revision 00, for Quad Cities Nuclear Power Station.

This report is submitted as a vcluntary report only.

The following commitment is being made by this letter:

The site Plant Operations Review Committee will determine how much, if any, to lower the administrative limits for torus water temperature, to improve NPSH margin in the actual plant response to design bases event (s). Correlation between initial torus water temperature and NPSH margin will be determined prior to 033197.

If there are any questions or comments concerning this letter, please refer them to Mr. Charles Peterson, Regulatory Affairs Manager at 309-654-2241, ext. 3602.

Respectfully, COMMONWEALTH EDISON QU TIES LEAR POWER STATION Y

. W. Pearce i

Station Manager LWP/CP/plm 280019 Enclosure l

l cc:

A. B. Beach, Regional Administrator, Region III gM il R. M. Pulsifer, Project Manager, NRR C. G. Miller, Senior Resident Inspector, Quad Cities R. J. Singer, MidAmerican Energy Company D. C. Tubbs, MidAmerican Energy Company 2800 T*> 0

" ' "** '*""*"8' F. A. Spangenberg, Regulatory Affairs Manager, Dresden INPO Records Center 9701280196 970122 PDR ADOCK 05000254 S

Licensee Event Report

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		Reporting criterion
05000254/LER-1996-001-07, :on 960303,B CR HVAC Sys Inoperable Due to Malfunctioning Relay Which Prevented Isolation of Air Handling Unit Fan.Ems Replaced Relay & Forwarded Damaged Relay to Engineering for Evaluation	on 960303,B CR HVAC Sys Inoperable Due to Malfunctioning Relay Which Prevented Isolation of Air Handling Unit Fan.Ems Replaced Relay & Forwarded Damaged Relay to Engineering for Evaluation	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation
05000265/LER-1996-001, Forwards LER 96-001-00.Listed Commitments Made,Including Event Will Be Included as Part of Continuing Training for Both Licensed Operators & Engineering Dept	Forwards LER 96-001-00.Listed Commitments Made,Including Event Will Be Included as Part of Continuing Training for Both Licensed Operators & Engineering Dept	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000265/LER-1996-001-10, :on 960417,HPCIS Was Declared Inoperable Due to Procedural Deficiency Which Allowed Isolation of Turbine Exhaust Vacuum.Licensed Operators Have Been Trained on Procedure Changes	on 960417,HPCIS Was Declared Inoperable Due to Procedural Deficiency Which Allowed Isolation of Turbine Exhaust Vacuum.Licensed Operators Have Been Trained on Procedure Changes	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000265/LER-1996-002, Forwards LER 96-002-00.Licensee Revised Qcop 2300-1 to Ensure That Piping Downstream of Sys Isolation Valve Is Filled & Vented After Maint	Forwards LER 96-002-00.Licensee Revised Qcop 2300-1 to Ensure That Piping Downstream of Sys Isolation Valve Is Filled & Vented After Maint	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000265/LER-1996-002-10, :on 961009,HPCI Sys Declared Inoperable.Caused by Improper Filling & Venting After Aug 1996 Maint.Air Purged from Sys & line-up Procedure Revised to Ensure Filling & Venting of Piping	on 961009,HPCI Sys Declared Inoperable.Caused by Improper Filling & Venting After Aug 1996 Maint.Air Purged from Sys & line-up Procedure Revised to Ensure Filling & Venting of Piping
05000254/LER-1996-002-04, :on 960220,CR HVAC Sys Inoperable.Caused by Design Oversight Involving Toxic Gas Anlayzer.On 960223 Procedure Change to Qcop 5750-09, CR Ventilation Sys, Made to Allow for Operation of Booster Fans	on 960220,CR HVAC Sys Inoperable.Caused by Design Oversight Involving Toxic Gas Anlayzer.On 960223 Procedure Change to Qcop 5750-09, CR Ventilation Sys, Made to Allow for Operation of Booster Fans	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)
05000265/LER-1996-003-01, :on 961112,Unit 2 LPCI Was Declared Inoperable. Caused by Failure of 2D RHR Pump Discharge Check Valve.Lpci Kf Pressure Was re-established within One Hour	on 961112,Unit 2 LPCI Was Declared Inoperable. Caused by Failure of 2D RHR Pump Discharge Check Valve.Lpci Kf Pressure Was re-established within One Hour
05000265/LER-1996-003-13, :on 961112,Unit 2 LPCI Was Declared Inoperable to 2D RHR Pump Discharge Check Valve Failure.Lpci Kf Was re-established within 1 Hour & Operability Determination Was Completed for PIF 96-3196	on 961112,Unit 2 LPCI Was Declared Inoperable to 2D RHR Pump Discharge Check Valve Failure.Lpci Kf Was re-established within 1 Hour & Operability Determination Was Completed for PIF 96-3196
05000265/LER-1996-003, Forwards LER 96-003-00 Submitted IAW Requirements of 10CFR50.73(a)(2)(v)(D).Commitments Made by Ltr,Submitted	Forwards LER 96-003-00 Submitted IAW Requirements of 10CFR50.73(a)(2)(v)(D).Commitments Made by Ltr,Submitted	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000254/LER-1996-003-02, :on 960222,unanticipated Start Occurred on Unit 1 Edg.Caused by Inadequate Guidance within Procedure Qcmms 6600-03.Procedure Qcmms 6600-03 Will Be Revised to Clarify Switch Settings	on 960222,unanticipated Start Occurred on Unit 1 Edg.Caused by Inadequate Guidance within Procedure Qcmms 6600-03.Procedure Qcmms 6600-03 Will Be Revised to Clarify Switch Settings	10 CFR 50.73(a)(2)
05000254/LER-1996-003, Forwards LER 96-003-00 Re Unit 1 Start of Egd Due to Inadequate Procedure	Forwards LER 96-003-00 Re Unit 1 Start of Egd Due to Inadequate Procedure	10 CFR 50.73(a)(2)(iv), System Actuation
05000254/LER-1996-004-01, :on 960130,HPCI Sys Declared Inoperable Due to Gland Exhauster Breaker Trip.Hpci Gland Exhauster Breaker Replaced & Tested for Proper Operation & AOP Time Delay Bypass Switches in Starting Circuit Replaced	on 960130,HPCI Sys Declared Inoperable Due to Gland Exhauster Breaker Trip.Hpci Gland Exhauster Breaker Replaced & Tested for Proper Operation & AOP Time Delay Bypass Switches in Starting Circuit Replaced	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)
05000254/LER-1996-005-07, :on 960203,B CR HVAC Sys Declared Inoperable Due to Outside Air Temp.Submitted TS Change Requesting That Heater Power Be Measured Instead of Differential Temp Across Heater to Determine Operability	on 960203,B CR HVAC Sys Declared Inoperable Due to Outside Air Temp.Submitted TS Change Requesting That Heater Power Be Measured Instead of Differential Temp Across Heater to Determine Operability
05000254/LER-1996-006, :on 960210,TS 3.0.A Incorrectly Invoked Due to Procedural & Operator Knowledge Deficiencies.Policy Statement Developed & Presented to Licensed Operator Re Expectations for Use & Entry Into TS 3.0.A	on 960210,TS 3.0.A Incorrectly Invoked Due to Procedural & Operator Knowledge Deficiencies.Policy Statement Developed & Presented to Licensed Operator Re Expectations for Use & Entry Into TS 3.0.A	10 CFR 50.73(a)(2)(i)
05000254/LER-1996-007-02, :on 960510,secondary Containment Damaged.Caused by Tornado.Initiated Shutdown,Ac Power Restored to Prompt Notification Sys & Station Blackout Bldg Cables Spliced Per Er 9603099	on 960510,secondary Containment Damaged.Caused by Tornado.Initiated Shutdown,Ac Power Restored to Prompt Notification Sys & Station Blackout Bldg Cables Spliced Per Er 9603099	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(e)(2)(vii)
05000254/LER-1996-008-02, :on 960607,TS Required Pressure Not Met During Local Leak Rate Testing.Caused by Procedural Deficiency. Procedure Changes Submitted & Check Valves Retested Using Appropriate Vent Paths	on 960607,TS Required Pressure Not Met During Local Leak Rate Testing.Caused by Procedural Deficiency. Procedure Changes Submitted & Check Valves Retested Using Appropriate Vent Paths	10 CFR 50.73(a)(2)(viii)(B)
05000254/LER-1996-008, Forwards LER 96-008,Rev 00 & Makes Following Commitment: Procedure Qcts 0600-34 Will Be Revised to Ensure Appropriate Vent Path Exists When Leak Rate Testing 2251(2)-81A/B Panels	Forwards LER 96-008,Rev 00 & Makes Following Commitment: Procedure Qcts 0600-34 Will Be Revised to Ensure Appropriate Vent Path Exists When Leak Rate Testing 2251(2)-81A/B Panels	10 CFR 50.73(a)(2)(1)
05000254/LER-1996-009-01, :on 960523,noted Discrepancy in Cable Length Modeled in Existing Degraded Voltage Calculations.Caused by Design Analysis Deficiency.Performed Design Changes to Correct Voltage Problems	on 960523,noted Discrepancy in Cable Length Modeled in Existing Degraded Voltage Calculations.Caused by Design Analysis Deficiency.Performed Design Changes to Correct Voltage Problems	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B)
05000254/LER-1996-010-02, :on 960611,discovered Installed Gallery Steel Configuration Lacked Required Cross Bracing.Caused by Deficiency in Original Design Configuration Control Process. Installed Gallery Cross Bracing	on 960611,discovered Installed Gallery Steel Configuration Lacked Required Cross Bracing.Caused by Deficiency in Original Design Configuration Control Process. Installed Gallery Cross Bracing	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A)
05000254/LER-1996-011, Forwards LER 96-011-00.Circuit Mods & Procedure Changes Will Be Implemented Prior to Startup & Review of Sample of Assumptions from Safe Shutdown Repts & Calculations Investigated	Forwards LER 96-011-00.Circuit Mods & Procedure Changes Will Be Implemented Prior to Startup & Review of Sample of Assumptions from Safe Shutdown Repts & Calculations Investigated	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000254/LER-1996-011-02, :on 960708,determined Postulated Fire Could Have Caused Disabling Damage to Selected Motor Operated Valves.Caused by Inadequate Design Analysis Review.Movs Analyzed for Susceptibility to Single Failure	on 960708,determined Postulated Fire Could Have Caused Disabling Damage to Selected Motor Operated Valves.Caused by Inadequate Design Analysis Review.Movs Analyzed for Susceptibility to Single Failure
05000254/LER-1996-012-02, :on 960620,diesel Fuel Oil Transfer Piping Noted in Unanalysed Condition Due to an Incomplete Safety Classification Upgrade.Minor Mod Has Been Completed Which Removes Autofill Capability for Fire Pump Day Tanks	on 960620,diesel Fuel Oil Transfer Piping Noted in Unanalysed Condition Due to an Incomplete Safety Classification Upgrade.Minor Mod Has Been Completed Which Removes Autofill Capability for Fire Pump Day Tanks
05000254/LER-1996-012, Forwards LER 96-012-00,for Quad Cities Nuclear Power Station.Review Plan Will Be Prepared to Identify Open Items within Component Classification Program & Ensure Resolution of Items.Plan Will Be Completed by 970301	Forwards LER 96-012-00,for Quad Cities Nuclear Power Station.Review Plan Will Be Prepared to Identify Open Items within Component Classification Program & Ensure Resolution of Items.Plan Will Be Completed by 970301	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000254/LER-1996-013-01, :on 960808,zebra Mussels Were Discovered on Fire Pump Suction Strainers.Caused by Inadequate Insp Frequency of Fire Pump Suction Strainers.Divers Removed & Cleaned Zebra Mussels from Fire Pump Suction Strainers	on 960808,zebra Mussels Were Discovered on Fire Pump Suction Strainers.Caused by Inadequate Insp Frequency of Fire Pump Suction Strainers.Divers Removed & Cleaned Zebra Mussels from Fire Pump Suction Strainers	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B)
05000254/LER-1996-013, Forwards LER 96-013,Rev 0 IAW Requirements of 10CFR50.73(a)(2)(i)(B).Commitments Made by Ltr,Listed	Forwards LER 96-013,Rev 0 IAW Requirements of 10CFR50.73(a)(2)(i)(B).Commitments Made by Ltr,Listed	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000254/LER-1996-014, Forwards LER 96-014-00.All Personnel Will Be Briefed in Event by 961215,reinforcing Expectations to Initiate Procedure Changes When Needed	Forwards LER 96-014-00.All Personnel Will Be Briefed in Event by 961215,reinforcing Expectations to Initiate Procedure Changes When Needed	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000254/LER-1996-014-03, :on 960927,electrical Distribution Weekly Surveillance Did Not Document Voltage Verification Due to an Inadequate Procedure.Qcos 0005-06 Has Been Revised to Ensure Verification of Proper Voltages	on 960927,electrical Distribution Weekly Surveillance Did Not Document Voltage Verification Due to an Inadequate Procedure.Qcos 0005-06 Has Been Revised to Ensure Verification of Proper Voltages	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000254/LER-1996-015-01, :on 960816,HPCI Sys Jet Impingement Support Baseplate/Concrete Expansion Anchors Were Improperly Installed,Due to Ineffective Work Practices & QA Program. Review Will Be Completed	on 960816,HPCI Sys Jet Impingement Support Baseplate/Concrete Expansion Anchors Were Improperly Installed,Due to Ineffective Work Practices & QA Program. Review Will Be Completed	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii)
05000254/LER-1996-015, Forwards LER 96-015-00.Commits to Completion Review of All Pipe Whip & Vibration Restraint Configuations by 961231	Forwards LER 96-015-00.Commits to Completion Review of All Pipe Whip & Vibration Restraint Configuations by 961231	10 CFR 50.73(a)(2)(1)
05000254/LER-1996-016-01, :on 960823,secondary Containment Would Not Have Satisfied All UFSAR Requirements,Due to Siding Explosion Bolts Which Were Damaged by Either High Winds or Ineffective Work Pratices.Damaged Bolts Replaced	on 960823,secondary Containment Would Not Have Satisfied All UFSAR Requirements,Due to Siding Explosion Bolts Which Were Damaged by Either High Winds or Ineffective Work Pratices.Damaged Bolts Replaced	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000254/LER-1996-017, Forwards LER 96-017-00,for Quad Cities Nuclear Power Station.Review Plan Will Be Prepared to Identify Open Items	Forwards LER 96-017-00,for Quad Cities Nuclear Power Station.Review Plan Will Be Prepared to Identify Open Items	10 CFR 50.73(a)(2)(iv), System Actuation
05000254/LER-1996-017-01, :on 960825,manual Scram Taken During Reactor Startup When Reactor Water Level Increased Following Unplanned Opening of All Main Turbine Bypass Valves Occurred,Due to Inadequate Procedures.Procedures Revised	on 960825,manual Scram Taken During Reactor Startup When Reactor Water Level Increased Following Unplanned Opening of All Main Turbine Bypass Valves Occurred,Due to Inadequate Procedures.Procedures Revised	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)
05000254/LER-1996-018, Forwards Supplemental Info Re LER 96-018-00,correcting Editorial Error	Forwards Supplemental Info Re LER 96-018-00,correcting Editorial Error
05000254/LER-1996-018-01, :on 960903,TS Surveillance Requirements Were Misinterpreted Due to Conservative Misunderstanding of Requirement.Memo Was Written to Explain Which Min TS Surveillances Must Be Performed Re Mode Switch	on 960903,TS Surveillance Requirements Were Misinterpreted Due to Conservative Misunderstanding of Requirement.Memo Was Written to Explain Which Min TS Surveillances Must Be Performed Re Mode Switch	10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A)
05000254/LER-1996-019, Forwards LER 96-019 IAW Requirements of 10CFR50.73(a)(2)(ii)(B) & Discusses Listed Commitments	Forwards LER 96-019 IAW Requirements of 10CFR50.73(a)(2)(ii)(B) & Discusses Listed Commitments	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000254/LER-1996-019-01, :on 960904,main Steam Line Radiation Monitor Functional Test Was Not Performed within Frequency Established for TS When in Refueling Mode Due to Incomplete Documentation of TS Interpretation.Qcap 2300-11 Was Changed	on 960904,main Steam Line Radiation Monitor Functional Test Was Not Performed within Frequency Established for TS When in Refueling Mode Due to Incomplete Documentation of TS Interpretation.Qcap 2300-11 Was Changed	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000254/LER-1996-020, Forwards LER 96-020-00.Commitments Included in LER & Submitted	Forwards LER 96-020-00.Commitments Included in LER & Submitted	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000254/LER-1996-020-01, :on 960907,CR Emergency Filtration Sys Declared Inoperable.Caused by Operator Knowledge Weakness.Operators Declared CR Emergency Filtration Sys Inoperable & Entered 14-day LCO	on 960907,CR Emergency Filtration Sys Declared Inoperable.Caused by Operator Knowledge Weakness.Operators Declared CR Emergency Filtration Sys Inoperable & Entered 14-day LCO	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000254/LER-1996-021-01, :on 961011,B CR HVAC Sys Was Declared Inoperable Due to Crankcase Heater Power Supply Design Deficiency.Design Change Notice 9600380 Issued,Which Replaced Crankcase Heater W/Safety Related Heater	on 961011,B CR HVAC Sys Was Declared Inoperable Due to Crankcase Heater Power Supply Design Deficiency.Design Change Notice 9600380 Issued,Which Replaced Crankcase Heater W/Safety Related Heater
05000254/LER-1996-021, Forwards LER 96-021-00,for Quad Cities Nuclear Power Station.No Commitments Being Made	Forwards LER 96-021-00,for Quad Cities Nuclear Power Station.No Commitments Being Made	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000254/LER-1996-022-01, Extends Commitment Date for Completing Rev to Plant CR Dose Analysis of Record,Per LER 96-022-01	Extends Commitment Date for Completing Rev to Plant CR Dose Analysis of Record,Per LER 96-022-01
05000254/LER-1996-023-01, :on 961124,CR Emergency Filtration Sys Failed to Maintain Required Airflow Due to Cognitive Personnel Error.Instrument Loop for Gauge Fi 1/2-5795-307 Calibr	on 961124,CR Emergency Filtration Sys Failed to Maintain Required Airflow Due to Cognitive Personnel Error.Instrument Loop for Gauge Fi 1/2-5795-307 Calibr
05000254/LER-1996-023, Provides Commitments Re LER 96-023.Predefined Model Work Request Which Initiates Perodic Maint Procedure Initiated	Provides Commitments Re LER 96-023.Predefined Model Work Request Which Initiates Perodic Maint Procedure Initiated	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000254/LER-1996-025, Forwards LER 96-025-00 Re Operability Calculations Performed on ECCS Suction Strainers W/Incorrect Head Loss Values	Forwards LER 96-025-00 Re Operability Calculations Performed on ECCS Suction Strainers W/Incorrect Head Loss Values
05000254/LER-1996-025-01, :on 961220,discovered Original Value for Strainers Head Loss Incorrect.Cause Could Not Be Determined. Training Provided for Operators to Recognize Pump Cavitation During Design Basis Accidents	on 961220,discovered Original Value for Strainers Head Loss Incorrect.Cause Could Not Be Determined. Training Provided for Operators to Recognize Pump Cavitation During Design Basis Accidents	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)

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