05000352/LER-1996-022-01, Forwards LER 96-022-01 Re Event Which Occurred on 961102 Re Amount of Fuel Oil Contained in D14 EDG Fuel Oil Storage Tank.Challenging Method for Determining Tank Oil Level Resulted in Operator Obtaining an Incorrect Level Re

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Forwards LER 96-022-01 Re Event Which Occurred on 961102 Re Amount of Fuel Oil Contained in D14 EDG Fuel Oil Storage Tank.Challenging Method for Determining Tank Oil Level Resulted in Operator Obtaining an Incorrect Level Reading
Person / Time
ML20134D189
Site:	Limerick
Issue date:	01/30/1997
From:	Boyce R PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20134D192	List: 05000352/LER-1996-022, :on 961102,D14 EDG Was Declared Inoperable Due to Low Fuel Oil in Storage Tank.Caused by Challenging Method for Determining Tank Level.Increased Operator Awareness of Potential for Error Is Being Utilized 05000352/LER-1996-022-01, Forwards LER 96-022-01 Re Event Which Occurred on 961102 Re Amount of Fuel Oil Contained in D14 EDG Fuel Oil Storage Tank.Challenging Method for Determining Tank Oil Level Resulted in Operator Obtaining an Incorrect Level Re
References
NUDOCS 9702050018
Download: ML20134D189 (1)
v • d • e

LER-1996-022, Forwards LER 96-022-01 Re Event Which Occurred on 961102 Re Amount of Fuel Oil Contained in D14 EDG Fuel Oil Storage Tank.Challenging Method for Determining Tank Oil Level Resulted in Operator Obtaining an Incorrect Level Reading

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(1)
3521996022R01 - NRC Website
v • d • e

text

r

' f Robert W.Boyc3 Plant Manager Limerick Generatng Station

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l PECO NUCLEAR re m t" - "v Lanenck Generating Staen A Unit of PECO Energy Po Box 2300 Sanatoga. PA 19464-0920 610 718 2000 10CFR50.73 January 30, 1997 Docket No. 50-352 License No. NPF-39 I

U.S. Nuclear Regulatory Commission l

Attn:

Document Control Desk l

Washington, DC 20555 j

SUBJECT:

Licensee Event Report Limerick Generating Station - Unit 1 l

l-This LER reports a condition prohibited by the Technical Specifications in that the D14 Emergency Diesel Generator i

Fuel Oil Storage Tank did not contain the minimum amount of l

fuel oil. The cause of th!.s event was that a challenging method for determining the tank oil level resulted in an l

operator obtaining an incorrect tank level reading.

Reference:

Docket No. 50-352 Report Number:

1-96-022 Revision Number:

00 Event Date:

November 2,

1996 j

Discovery Date:

December 31, 1996

)

Report Date:

January 30, 1997 1

i l

Facility:

Limerick Generating Station l

P.O.

Box 2300, Sanatoga, PA 19464-I

(

2300 l

This LER is being submitted pursuant to the requirements of 10CFR50.73 (a) (2) (1) (B).

Very truly yours, 5

DBN:dbn cc:

H.

J.

Miller, Administrator Region I, USNRC j

N. S.

Perry, USNRC Senior Resident Inspector, LGS l

050007

/

9702050018 970130

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I PDR ADOCK 05000352!

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Licensee Event Report

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		Reporting criterion
05000352/LER-1996-001, :on 960111,automatic Isolation of RCIC Sys During Surveillance Testing Occurred Due to Less than Adequate Attention to Details.Counseled Technician & Held Team Meetings to Discuss Event	on 960111,automatic Isolation of RCIC Sys During Surveillance Testing Occurred Due to Less than Adequate Attention to Details.Counseled Technician & Held Team Meetings to Discuss Event	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000353/LER-1996-001-02, :on 960220,condition Prohibited by TS in That Two Independent SGTS Inoperable Due to Personnel Error. Counseled EO & Conducted Operator Standdown Meetings to Discuss Event	on 960220,condition Prohibited by TS in That Two Independent SGTS Inoperable Due to Personnel Error. Counseled EO & Conducted Operator Standdown Meetings to Discuss Event	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000352/LER-1996-002, :on 960118,unit Operated in Excess of 100% Rated Power Due to Core Thermal Power Calculation Methodology Error.Reactor Heat Balance Revised	on 960118,unit Operated in Excess of 100% Rated Power Due to Core Thermal Power Calculation Methodology Error.Reactor Heat Balance Revised	10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000353/LER-1996-002-02, :on 960315,ESFA Occurred Due to Loss of Power to Rps/Ups Power Distribution Panel.Caused by Inadvertent Actuation of Underfrequency Relay.Created Necessary Addl Physical Barriers Arounds Units 1 & 2	on 960315,ESFA Occurred Due to Loss of Power to Rps/Ups Power Distribution Panel.Caused by Inadvertent Actuation of Underfrequency Relay.Created Necessary Addl Physical Barriers Arounds Units 1 & 2	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000353/LER-1996-003-02, :on 960314,failed to Perform Accelerated Surveillance Testing of Unit 2 EDG Due to Inadequate Evaluation Program.Reviewed & Enhanced Program & Associated Implementing Documents for Failure Evaluations	on 960314,failed to Perform Accelerated Surveillance Testing of Unit 2 EDG Due to Inadequate Evaluation Program.Reviewed & Enhanced Program & Associated Implementing Documents for Failure Evaluations	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) 10 CFR 50.73(a)(2)(1)
05000352/LER-1996-003, :on 960204,ESFA Occurred Due to Loss of Power to Rps/Ups Power Distribution Panel Caused by Spurious Actuation of Underfrequency Relay.Replaced Relay	on 960204,ESFA Occurred Due to Loss of Power to Rps/Ups Power Distribution Panel Caused by Spurious Actuation of Underfrequency Relay.Replaced Relay	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000353/LER-1996-004-02, :on 960514,reactor Scram Resulted from Main Generator Lockout Due to Actuation of Voltz/Hertz Relay. Caused by Inadequate Design Change Package.Relay 359/381A Drawing Corrected & Relays Inspected	on 960514,reactor Scram Resulted from Main Generator Lockout Due to Actuation of Voltz/Hertz Relay. Caused by Inadequate Design Change Package.Relay 359/381A Drawing Corrected & Relays Inspected	10 CFR 50.73(a)(2)(iv), System Actuation 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)(1)
05000352/LER-1996-004, :on 960206,reactor Scram Signal Occurred While in Hot Shutdown Due to Operator Error During Depressurization.Provided Briefing Sheet to Operations Managers	on 960206,reactor Scram Signal Occurred While in Hot Shutdown Due to Operator Error During Depressurization.Provided Briefing Sheet to Operations Managers	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) 10 CFR 50.73(a)(2)(viii)(A)
05000353/LER-1996-005-02, :on 960527,automatic Actuation of ESF Occurred. Caused by Burnt Circuit Board Trace on Relay Board.Radiation Monitor Satisfactorily Tested & Returned	on 960527,automatic Actuation of ESF Occurred. Caused by Burnt Circuit Board Trace on Relay Board.Radiation Monitor Satisfactorily Tested & Returned	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)
05000352/LER-1996-005, :on 960207,daily RECW Sys Fluid Sample Not Obtained & Analyzed within 24 H as Required by TS 3.3.7.1. Caused by Personnel Error & Inadequate Chemistry Section Sampling Program.Program Revised	on 960207,daily RECW Sys Fluid Sample Not Obtained & Analyzed within 24 H as Required by TS 3.3.7.1. Caused by Personnel Error & Inadequate Chemistry Section Sampling Program.Program Revised	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000352/LER-1996-006-01, Forwards LER 96-006-01 Re Multiple Instances of Loss of Safety Function of Control Room Emergency Fresh Air Sys, Resulting in Operating Conditions Prohibited by Tech Specs	Forwards LER 96-006-01 Re Multiple Instances of Loss of Safety Function of Control Room Emergency Fresh Air Sys, Resulting in Operating Conditions Prohibited by Tech Specs	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(1)
05000352/LER-1996-006, :on 960207,control Room Emergency Fresh Air Sys Declared Inoperable.Caused by Flow Switch Coordination Deficiency.Flow Switches Adjusted,Station Guidance Revised & Site Staff Training Performed	on 960207,control Room Emergency Fresh Air Sys Declared Inoperable.Caused by Flow Switch Coordination Deficiency.Flow Switches Adjusted,Station Guidance Revised & Site Staff Training Performed	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)
05000353/LER-1996-006-02, :on 961202,inadvertent Start of D21 Edg,An ESF During Surveillance Testing Was Noted.Caused by Malfunction of Test Switch Box.Test Box Was Repaired & Tested & Generic Implications of Event Was Evaluated	on 961202,inadvertent Start of D21 Edg,An ESF During Surveillance Testing Was Noted.Caused by Malfunction of Test Switch Box.Test Box Was Repaired & Tested & Generic Implications of Event Was Evaluated	10 CFR 50.73(a)(2)(iv), System Actuation
05000352/LER-1996-007, :on 960220,trip of FPC Pumps Resulted in Loss of Core Circulaton & Decay Heat Removal.Caused by Insufficient Procedural Guidance.C/A:Assessment Performed	on 960220,trip of FPC Pumps Resulted in Loss of Core Circulaton & Decay Heat Removal.Caused by Insufficient Procedural Guidance.C/A:Assessment Performed	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)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 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)
05000353/LER-1996-007-02, :on 961206,manual Scram Occurred Due to Leak in Main Turbine EHC Sys.Caused by Failure of Pressure Switch Support Bracket & Tubing.Replaced Failed Bracket & Tubing & Performed Walkdown of Main Steam Sys	on 961206,manual Scram Occurred Due to Leak in Main Turbine EHC Sys.Caused by Failure of Pressure Switch Support Bracket & Tubing.Replaced Failed Bracket & Tubing & Performed Walkdown of Main Steam Sys	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)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A)
05000353/LER-1996-008-01, :on 961214,two Closed Primary Containment Isolation Valves Were Discovered W/Motor Operator Breaker Closed.Caused by Personnel Error.Procedure GP-2 Will Be Revised to Separate Specific Steps	on 961214,two Closed Primary Containment Isolation Valves Were Discovered W/Motor Operator Breaker Closed.Caused by Personnel Error.Procedure GP-2 Will Be Revised to Separate Specific Steps	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000353/LER-1996-008, Forwards LER 96-008-00 Which Documents Event That Occurred at Lgs,Unit 2 on 961214.Commitment Made within Ltr,Listed	Forwards LER 96-008-00 Which Documents Event That Occurred at Lgs,Unit 2 on 961214.Commitment Made within Ltr,Listed
05000352/LER-1996-008, :on 960303,HPCI,ESFA & Condition Which Could Have Prevented Intended Safety Function Occurred Due to Personnel Error.Issued Event Training Bulletin to All I&C Technicians by 960415	on 960303,HPCI,ESFA & Condition Which Could Have Prevented Intended Safety Function Occurred Due to Personnel Error.Issued Event Training Bulletin to All I&C Technicians by 960415	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000352/LER-1996-009-01, :on 960422,main Steam System Safety Relief Valve Setpoint Drift Occurred.Caused by Corrosion Induced Bonding Between Pilot Disc & Seat.Installed Special Modified Pilot Disc in Several SRVs	on 960422,main Steam System Safety Relief Valve Setpoint Drift Occurred.Caused by Corrosion Induced Bonding Between Pilot Disc & Seat.Installed Special Modified Pilot Disc in Several SRVs	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)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000353/LER-1996-009-03, :on 961224,unit Scram & Reactor Protection Sys Actuation Occurred Due to Failure of Bill Joint That Connects Recirculation Pump Motor Generator Set Scoop Tube to Tube Positioner.Failed Ball Joint Was Replaced	on 961224,unit Scram & Reactor Protection Sys Actuation Occurred Due to Failure of Bill Joint That Connects Recirculation Pump Motor Generator Set Scoop Tube to Tube Positioner.Failed Ball Joint Was Replaced	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000353/LER-1996-009, Forwards LER 96-009-00,documenting Event That Occurred at Limerick Generating Station,Unit 2 on 961224.LER Is Being Submitted Pursuant to Requirements of 10CFR50.73(a)(2)(iv)	Forwards LER 96-009-00,documenting Event That Occurred at Limerick Generating Station,Unit 2 on 961224.LER Is Being Submitted Pursuant to Requirements of 10CFR50.73(a)(2)(iv)	10 CFR 50.73(a)(2)(iv), System Actuation
05000352/LER-1996-009, :on 960314,five of Six as-found Setpoint Tests on Main Steam Sys SRVs Found Outside Required Pressure Ranges.Caused by Setpoint Drift Due to Corrosion Induced Bonding.Modified Pilot Disc Installed in SRVs	on 960314,five of Six as-found Setpoint Tests on Main Steam Sys SRVs Found Outside Required Pressure Ranges.Caused by Setpoint Drift Due to Corrosion Induced Bonding.Modified Pilot Disc Installed in SRVs	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000352/LER-1996-010, :on 960423,discovered Two Remote Shutdown Panel (RSP) Control Circuits Inoperable.Caused by Inadequate Procedures.Rsp Surveillance Test Procedures Revised by 960731 and RSP Cleaned by 960731	on 960423,discovered Two Remote Shutdown Panel (RSP) Control Circuits Inoperable.Caused by Inadequate Procedures.Rsp Surveillance Test Procedures Revised by 960731 and RSP Cleaned by 960731	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000352/LER-1996-011, :on 960425,manual Operation of CREFAS Sys Resulted from Initiation of Toxic Chemical Detection Sys. Caused by Insufficient Guidance in Planning Process.Work Packages for Cleaning & Sealing Reviewed	on 960425,manual Operation of CREFAS Sys Resulted from Initiation of Toxic Chemical Detection Sys. Caused by Insufficient Guidance in Planning Process.Work Packages for Cleaning & Sealing Reviewed	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000352/LER-1996-012, :on 921103,identified Improper Fuse Sizing. Caused by Personnel Error.Approved Design Change Re Proper Fuse Coordination & Reviewed Modifications Associated W/Fuse Ratings	on 921103,identified Improper Fuse Sizing. Caused by Personnel Error.Approved Design Change Re Proper Fuse Coordination & Reviewed Modifications Associated W/Fuse Ratings	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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000352/LER-1996-013, :on 960521,Unit 1 Reactor Scram Occurred.Caused by Inadequate Procedural Guidance & Undetermined Equipment Malfunction.Procedure Will Be Revised to Ensure Appropriate Barriers,In Place to Minimize Risk of Scram	on 960521,Unit 1 Reactor Scram Occurred.Caused by Inadequate Procedural Guidance & Undetermined Equipment Malfunction.Procedure Will Be Revised to Ensure Appropriate Barriers,In Place to Minimize Risk of Scram	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)(x) 10 CFR 50.73(a)(2)
05000352/LER-1996-014, :on 960702,discovered Improperly Controlled Safeguards Information.Cause Undeterminate.Corrective Actions Will Be Provided by 960930	on 960702,discovered Improperly Controlled Safeguards Information.Cause Undeterminate.Corrective Actions Will Be Provided by 960930	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000352/LER-1996-015, :on 960726,failure to Maintain Equipment Needed for Operator Actions to Assure Fire Safe SD Capability. Caused by Unclear Ownership & Accountability of Procedures. Interim Procedure Revs Implemented	on 960726,failure to Maintain Equipment Needed for Operator Actions to Assure Fire Safe SD Capability. Caused by Unclear Ownership & Accountability of Procedures. Interim Procedure Revs Implemented	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000352/LER-1996-016, :on 960725,core Thermal Power Exceeded Licensed Power Limit During Power Transient.Caused by Defective EHC Sys Component & Reactor Scram.Defective Primary Frequency/ Voltage Converter Replaced & Calibration Performed	on 960725,core Thermal Power Exceeded Licensed Power Limit During Power Transient.Caused by Defective EHC Sys Component & Reactor Scram.Defective Primary Frequency/ Voltage Converter Replaced & Calibration Performed	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000352/LER-1996-017, :on 960820,4 EDGs Inoperable Resulting from Separate Crankcase Pressurization Events.Caused by Plugging of Exhaust Stack Bird Screens by Rust Debris in Stream Gas Flow.Exhaust Stacks Scraped,Cleaned & Vacuumed	on 960820,4 EDGs Inoperable Resulting from Separate Crankcase Pressurization Events.Caused by Plugging of Exhaust Stack Bird Screens by Rust Debris in Stream Gas Flow.Exhaust Stacks Scraped,Cleaned & Vacuumed	10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000352/LER-1996-018-01, Forwards LER 96-018-01 Which Discusses Event That Occurred on 960925 Re Inoperability of HPCI Sys Due to Loss of HPCI Turbine Speed Signal Caused by Loose Speed Sensor Connector	Forwards LER 96-018-01 Which Discusses Event That Occurred on 960925 Re Inoperability of HPCI Sys Due to Loss of HPCI Turbine Speed Signal Caused by Loose Speed Sensor Connector	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000352/LER-1996-018, :on 960925,single Train HPCI Sys Was Declared Inoperable Due to Loose Signal Cable Connector.Connector Was Replaced on 970102 & Common HPCI Turbine Maint Procedures Have Been Revised	on 960925,single Train HPCI Sys Was Declared Inoperable Due to Loose Signal Cable Connector.Connector Was Replaced on 970102 & Common HPCI Turbine Maint Procedures Have Been 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)(iv), System Actuation 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)(1)
05000352/LER-1996-019, :on 961026,capability to Reject Electrical Load of RHR Pump Not Fully Verified.Caused by Inadequate Test Procedure.Tests Will Be Revised Prior to Next Performance & TS Change Request Is Being Pursued	on 961026,capability to Reject Electrical Load of RHR Pump Not Fully Verified.Caused by Inadequate Test Procedure.Tests Will Be Revised Prior to Next Performance & TS Change Request Is Being Pursued	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)(B), Prohibited by Technical Specifications
05000352/LER-1996-020, :on 961205,primary Containment Isolation Valves Inadvertently Closed Due to Personnel Error.Reopened Valves & Counseled Individual Involved on Work Techniques	on 961205,primary Containment Isolation Valves Inadvertently Closed Due to Personnel Error.Reopened Valves & Counseled Individual Involved on Work Techniques	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)
05000352/LER-1996-021-01, Forwards LER 96-021-01 Re Ability to Achieve Safe Shutdown in Event of Fire as Provided by Fire Protection Program	Forwards LER 96-021-01 Re Ability to Achieve Safe Shutdown in Event of Fire as Provided by Fire Protection Program
05000352/LER-1996-021, :on 841026,determined Fire Safe Shutdown Made in Fire Safe Shutdown Repair Would Not Function as Desired Due to Incorrect Assumption.Revised Fire Safe Shutdown Procedures	on 841026,determined Fire Safe Shutdown Made in Fire Safe Shutdown Repair Would Not Function as Desired Due to Incorrect Assumption.Revised Fire Safe Shutdown Procedures	10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B)
05000352/LER-1996-022-01, Forwards LER 96-022-01 Re Event Which Occurred on 961102 Re Amount of Fuel Oil Contained in D14 EDG Fuel Oil Storage Tank.Challenging Method for Determining Tank Oil Level Resulted in Operator Obtaining an Incorrect Level Re	Forwards LER 96-022-01 Re Event Which Occurred on 961102 Re Amount of Fuel Oil Contained in D14 EDG Fuel Oil Storage Tank.Challenging Method for Determining Tank Oil Level Resulted in Operator Obtaining an Incorrect Level Reading	10 CFR 50.73(a)(2)(1)
05000352/LER-1996-022, :on 961102,D14 EDG Was Declared Inoperable Due to Low Fuel Oil in Storage Tank.Caused by Challenging Method for Determining Tank Level.Increased Operator Awareness of Potential for Error Is Being Utilized	on 961102,D14 EDG Was Declared Inoperable Due to Low Fuel Oil in Storage Tank.Caused by Challenging Method for Determining Tank Level.Increased Operator Awareness of Potential for Error Is Being Utilized	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000352/LER-1996-023, :on 950403,FPS Surveillance Tests Not Performed.Caused by Personnel Error.Individuals Involved Disciplined & New Supervisor Assigned to Onsite Fire Protection Group	on 950403,FPS Surveillance Tests Not Performed.Caused by Personnel Error.Individuals Involved Disciplined & New Supervisor Assigned to Onsite Fire Protection Group	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1)

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