05000336/LER-1996-043, Fowards LER 96-043-00,documenting Event That Occurred at Millstone Nuclear Power Station,Unit 2 on 961231.Util Commitments Made within Ltr,Listed

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Fowards LER 96-043-00,documenting Event That Occurred at Millstone Nuclear Power Station,Unit 2 on 961231.Util Commitments Made within Ltr,Listed
Person / Time
ML20134D795
Site:	Millstone
Issue date:	01/30/1997
From:	Price J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20134D798	List: 05000336/LER-1996-043, Fowards LER 96-043-00,documenting Event That Occurred at Millstone Nuclear Power Station,Unit 2 on 961231.Util Commitments Made within Ltr,Listed 05000336/LER-1996-043-02, :on 961231,flow Indicators to East & West DC Switchgear Rcs Were Approx 29% Lower than Indicator Flow. Caused by Inadequate Flow Instrument Design Documentation. Elements Orifice Dimensions Verified
References
B16177, NUDOCS 9702050375
Download: ML20134D795 (2)
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LER-1996-043, Fowards LER 96-043-00,documenting Event That Occurred at Millstone Nuclear Power Station,Unit 2 on 961231.Util Commitments Made within Ltr,Listed

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)
3361996043R00 - NRC Website
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text

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'hg Millstone Offices

Hope Ferry Rd., Waterford, CT j

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- Utilities System P.o.n, 128 Waterford, CT 06385-0128 i

(203) 447-1791 i

January 30,1997

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Docket No. 50-336 l

B16177

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i Re: 10 CFR 50.73(a)(2)(i) 4 e

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U.S. Nuclear Regulatory Commission Document Control Desk j

Washington, DC 20555 4

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This letter forwards Licensee Event Report (LER) 96-043-00, documenting an event that occurred at Millstone Nuclear Power Station, Unit No. 2 on December 31,1996.

This LER is being submitted pursuant to 10 CFR 50.73(a)(2)(i).

l The following are NNECO's commitments made within this letter. All other statements made within this letter are for information only.

q i

B16177-01:

Design calibration calculations for QA/ Safety Related orifice plates will be verified and a sample of these calculations will be checked to ensure they are consistent with calibration documentation. This will be completed before entry into Mode 4.

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Very truly yours, i

NORTHEAST NUCLEAR ENERGY CCMPANY

$am bb ss oc, t e le/~,

gb J. A. Pripe ~

Director - Millstone Unit No. 2 cc: see page 2 3EN 9702050375 970130 f

PDR ADOCK 05000336.

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063422-9 REV.1-95

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U. S. Nucirr Rtgulatory Commission B16177/Page 2 Attachment: LER 96-043-00 cc:

W. D. Travers, Director of Special Projects H. J. Miller, Region l Administrator

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D. P. Beaulieu, Senior Resident inspector (Acting), Millstone Unit No. 2 D. G. Mcdonald, Jr., NRC Project Manager, Millstone Unit No. 2

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Licensee Event Report

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		Reporting criterion
05000336/LER-1996-001, :on 960625,discovered Reactor Coolant Sys Heatup Rate Exceeded Tech Spec.Caused by Design & Procedural Weaknesses Re Plant Heatup Controls.Revised Plant Operating Procedures & Heatup/Cooldown Computer Program	on 960625,discovered Reactor Coolant Sys Heatup Rate Exceeded Tech Spec.Caused by Design & Procedural Weaknesses Re Plant Heatup Controls.Revised Plant Operating Procedures & Heatup/Cooldown Computer Program	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)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000423/LER-1996-001-02, :on 960120,supplementary Leak Collection & Release Sys Declared Inoperable Due to Equipment Failure of Door Latch.Door Repaired & Plant Returned to 100% Power	on 960120,supplementary Leak Collection & Release Sys Declared Inoperable Due to Equipment Failure of Door Latch.Door Repaired & Plant Returned to 100% Power	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000336/LER-1996-002, :on 960108,determined That Ice Plug in Common Line Resulted in Inability to Backwash Svc Water Strainers. Caused by Mod to Backwash Line Piping.Ice Plug Removed, Restoring Ability to Backwash	on 960108,determined That Ice Plug in Common Line Resulted in Inability to Backwash Svc Water Strainers. Caused by Mod to Backwash Line Piping.Ice Plug Removed, Restoring Ability to Backwash	10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
05000423/LER-1996-002-02, :on 960310,inadequate Surveillance for Determining Shutdown Margin When Unisolating Rcl Identified. Caused by Inadequate Procedure.Procedures Revised	on 960310,inadequate Surveillance for Determining Shutdown Margin When Unisolating Rcl Identified. Caused by Inadequate Procedure.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)(iv), System Actuation 10 CFR 50.73(a)(2)(x)
05000423/LER-1996-002, :on 960310,inadequate Surveillance for Determining Shutdown Margin When Unisolating Rcl Occurred Due to Procedure Inadequacy.Changes Will Be Made to Technical Requirements Manual	on 960310,inadequate Surveillance for Determining Shutdown Margin When Unisolating Rcl Occurred Due to Procedure Inadequacy.Changes Will Be Made to Technical Requirements Manual	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)(B), Prohibited by Technical Specifications 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
05000245/LER-1996-003, :on 960111,discovered Existing Anchorage of EDG Day Tank Not Seismically Adequate.Caused by Original Design Deficiency.Anchorage of EDG Tank Will Be Graded to Meet Design Basis of Seismic Load Requirements	on 960111,discovered Existing Anchorage of EDG Day Tank Not Seismically Adequate.Caused by Original Design Deficiency.Anchorage of EDG Tank Will Be Graded to Meet Design Basis of Seismic Load Requirements	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)(iv), System Actuation 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(e)(2)(i) 10 CFR 50.73(e)(2)(viii)
05000336/LER-1996-003-01, :on 960205,failed to Recognize Requirement to Enter TS LCO 3.0.3 Following Discovery of Ice Blockage. Caused by Inadequate Problem Identification Methods.Design Basis Summary Documents Have Been Prepared Re TS Safety Sys	on 960205,failed to Recognize Requirement to Enter TS LCO 3.0.3 Following Discovery of Ice Blockage. Caused by Inadequate Problem Identification Methods.Design Basis Summary Documents Have Been Prepared Re TS Safety Sys	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)(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) 10 CFR 50.73(a)(2)
05000245/LER-1996-003-02, Forwards LER 96-003-02 Which Documents an Event That Occurred at Mnps,Unit 1 on 960111,per 10CFR50.73(a)(2)(i) & 10CFR50.73(a)(2)(ii).Commitments Made in Ltr,Submitted	Forwards LER 96-003-02 Which Documents an Event That Occurred at Mnps,Unit 1 on 960111,per 10CFR50.73(a)(2)(i) & 10CFR50.73(a)(2)(ii).Commitments Made in Ltr,Submitted	10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000423/LER-1996-003-01, :on 960312,temporary I-Beams Located Overhead of Recirculation Spray Sys HXs Discovered.Caused by Inadequate Work Control.Work Control Procedures Revised	on 960312,temporary I-Beams Located Overhead of Recirculation Spray Sys HXs Discovered.Caused by Inadequate Work Control.Work Control 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)(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)(viii)
05000423/LER-1996-004-01, :on 960319,determined That Auxiliary Feedwater Isolation Valves Were in Noncompliance W/Ts.Caused by Misinterpretation of Ts.Revised Operating Procedure to Preclude cross-connected Sys Alignment	on 960319,determined That Auxiliary Feedwater Isolation Valves Were in Noncompliance W/Ts.Caused by Misinterpretation of Ts.Revised Operating Procedure to Preclude cross-connected Sys Alignment	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)
05000336/LER-1996-004, :on 960131,svc Water Strainer Backwash Sys Susceptibility to Freezing Following Loss of Intake Structure non-vital Heating Occurred.Caused by Inadequate Original Design.Design Change Implemented	on 960131,svc Water Strainer Backwash Sys Susceptibility to Freezing Following Loss of Intake Structure non-vital Heating Occurred.Caused by Inadequate Original Design.Design Change Implemented	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000423/LER-1996-004-02, :on 960316,auxiliary Feedwater Isolation Valves Noncompliance W/Ts Occurred.Caused by Misinterpretation of Ts.Event Reviewed W/Station Personnel to Caution Others on TS Surveillance Requirements	on 960316,auxiliary Feedwater Isolation Valves Noncompliance W/Ts Occurred.Caused by Misinterpretation of Ts.Event Reviewed W/Station Personnel to Caution Others on TS Surveillance Requirements	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)(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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000336/LER-1996-005-01, :on 960212,discovered PEO Improperly Utilized to Replace Automatic Backwash Function of Svc Water Strainer Backwash Sys.Caused by Failure to Enter TS Action Statement. Revise Procedures for IST SWS Pump Operability	on 960212,discovered PEO Improperly Utilized to Replace Automatic Backwash Function of Svc Water Strainer Backwash Sys.Caused by Failure to Enter TS Action Statement. Revise Procedures for IST SWS Pump Operability	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)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000423/LER-1996-005-02, :on 960321,service Water Booster Pump Auto Start Discovered Disable.Caused by Inadequate Review.C/A: Bypass Jumper Removed & Mod Initiated	on 960321,service Water Booster Pump Auto Start Discovered Disable.Caused by Inadequate Review.C/A: Bypass Jumper Removed & Mod Initiated	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)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(s)(2)
05000423/LER-1996-005-03, :on 960321,design Noncompliance Noted for High Temp Automatic Start Feature of SWS Booster Pumps.Caused by Weakness in Design Control Process.Operating Procedures Revised	on 960321,design Noncompliance Noted for High Temp Automatic Start Feature of SWS Booster Pumps.Caused by Weakness in Design Control Process.Operating Procedures Revised	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)(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 50.73(a)(2)
05000336/LER-1996-006-01, :on 960207,service Water Pump Motor Flood Protection Not Provided.Caused by Inadequate Administrative Controls.Administrative Controls Established	on 960207,service Water Pump Motor Flood Protection Not Provided.Caused by Inadequate Administrative Controls.Administrative Controls Established	10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(i)(B), Prohibited by Technical Specifications 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)
05000423/LER-1996-006-02, :on 960330,plant Shutdown Required by TS for AFW Containment Isolation Valves Declared Inoperable.Caused by Opened Valves Outside Containment.Unit Was Shutdown in Orderly Manner	on 960330,plant Shutdown Required by TS for AFW Containment Isolation Valves Declared Inoperable.Caused by Opened Valves Outside Containment.Unit Was Shutdown in Orderly Manner	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)(A), Completion of TS Shutdown
05000423/LER-1996-007, :on 960403,containment Recirculation Spray, Quench Spray & Safety Injection Sys Were Outside Design Basis Due to Design Errors.Design Reviews of Rss,Qss,Si & Other Sys Will Be Performed	on 960403,containment Recirculation Spray, Quench Spray & Safety Injection Sys Were Outside Design Basis Due to Design Errors.Design Reviews of Rss,Qss,Si & Other Sys Will Be Performed	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii)
05000336/LER-1996-007, :on 960220,discovered RCS C/D Rate Exceeded TS Limit.Caused by Use of Wrong Temp Sensor.Plant Operating Procedures,Heatup/C/D Monitoring Computer Program & Operator Training Involving These Events Revised	on 960220,discovered RCS C/D Rate Exceeded TS Limit.Caused by Use of Wrong Temp Sensor.Plant Operating Procedures,Heatup/C/D Monitoring Computer Program & Operator Training Involving These Events Revised
05000423/LER-1996-007-01, :on 960403,CRS & Qs Sys Found Outside Design Basis Due to Design Errors.Restored Sys to Appropriate Design Basis Requirements Prior to Declaring Sys Inoperable	on 960403,CRS & Qs Sys Found Outside Design Basis Due to Design Errors.Restored Sys to Appropriate Design Basis Requirements Prior to Declaring Sys Inoperable	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
05000423/LER-1996-007-02, Forwards LER 96-007-02 Which Supplements Rept Submitted on 960502,per 10CFR50.73(a)(2)(ii)(B),10CFR50.73(a)(2)(v)(B&D), 10CFR50.73(a)(2)(vii)(B&D).Commitments in Response to Event, Encl	Forwards LER 96-007-02 Which Supplements Rept Submitted on 960502,per 10CFR50.73(a)(2)(ii)(B),10CFR50.73(a)(2)(v)(B&D), 10CFR50.73(a)(2)(vii)(B&D).Commitments in Response to Event, Encl	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)
05000336/LER-1996-008, :on 960222,concluded That Condition of Wire Mesh Screen Encl Over Two Containment Recirculation Suction Pipes Outside Design Basis.Caused by Const/Installation Error.Screen Encl Being Replaced	on 960222,concluded That Condition of Wire Mesh Screen Encl Over Two Containment Recirculation Suction Pipes Outside Design Basis.Caused by Const/Installation Error.Screen Encl Being Replaced
05000423/LER-1996-008-01, :on 960412,reactor Protection Sys Lead/Lag Time Constants Found non-conservative.Caused by Failure of Vendor to Identify Conservative Calibr Requirements.Tss Changed to Correctly Identify Direction of Conservatism	on 960412,reactor Protection Sys Lead/Lag Time Constants Found non-conservative.Caused by Failure of Vendor to Identify Conservative Calibr Requirements.Tss Changed to Correctly Identify Direction of Conservatism	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000423/LER-1996-009, :on 960423,inoperable Shutdown Margin Monitors from Low Count Rate Occurred Due to Inadequate Design Control.Reduced SMM Setpoint	on 960423,inoperable Shutdown Margin Monitors from Low Count Rate Occurred Due to Inadequate Design Control.Reduced SMM Setpoint	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)(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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000245/LER-1996-009-01, :on 960109,isolation Condenser Makeup Water Temperature Below Design Basis Limit,Determined.Caused by Inadequate Design Specification.Preliminary Assessment of non-ductile Failure of Isolation Condenser Sys Performed	on 960109,isolation Condenser Makeup Water Temperature Below Design Basis Limit,Determined.Caused by Inadequate Design Specification.Preliminary Assessment of non-ductile Failure of Isolation Condenser Sys Performed	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)
05000336/LER-1996-009-01, :on 960216,post LOCA Contianment Pressure Prevented Timely Extraction of PASS Air Sample & H Sample. Caused by Inadequate Assessment of Revised Post LOCA Response Analysis.Implemented Design Change	on 960216,post LOCA Contianment Pressure Prevented Timely Extraction of PASS Air Sample & H Sample. Caused by Inadequate Assessment of Revised Post LOCA Response Analysis.Implemented Design Change	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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000423/LER-1996-009-02, Submits Table of Commitments Re LER 96-009-02 Per 10CFR50.73(a)(2)(ii)	Submits Table of Commitments Re LER 96-009-02 Per 10CFR50.73(a)(2)(ii)	10 CFR 50.73(a)(2)(i)
05000336/LER-1996-010, :on 960222,identified That Containment Hydrogen Monitor Flow Could Not Be Established W/Containment at Atmospheric Pressure Due to Improper Setting of Sys Pressure Regulators.Sys Calib Procedure Will Be Revised	on 960222,identified That Containment Hydrogen Monitor Flow Could Not Be Established W/Containment at Atmospheric Pressure Due to Improper Setting of Sys Pressure Regulators.Sys Calib Procedure Will Be Revised
05000423/LER-1996-010-02, :on 960425,determined That Potential Failure Mode of Rod Control Sys Acopian Power Supplies Could Create Unanalyzed Condition.Caused by Inadequate Design Review. Reset Feature Will Be Deleted	on 960425,determined That Potential Failure Mode of Rod Control Sys Acopian Power Supplies Could Create Unanalyzed Condition.Caused by Inadequate Design Review. Reset Feature Will Be Deleted	10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
05000336/LER-1996-011-01, :on 960222,required Time to Enter Mode 5 Exceeded.Caused by Effective Action Not Being Initiated to Revise SDC & Cooldown Rate Monitoring Procedures.Operating & Surveillance Procedures Will Be Revised	on 960222,required Time to Enter Mode 5 Exceeded.Caused by Effective Action Not Being Initiated to Revise SDC & Cooldown Rate Monitoring Procedures.Operating & Surveillance Procedures Will Be Revised
05000423/LER-1996-011-02, :on 960512,determined That Both Trains of CR Envelope Pressurization Sys Inoperable Due to Imbalance in air-conditioning Sys.Cr air-conditioning Sys Rebalanced.W/	on 960512,determined That Both Trains of CR Envelope Pressurization Sys Inoperable Due to Imbalance in air-conditioning Sys.Cr air-conditioning Sys Rebalanced.W/	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)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000423/LER-1996-012, :on 960515,containment Leakage in Excess of TS Limits Noted,Due to Valve Leakage.Containment Spray Line Penetration 100 Flushed to Remove Any Boron Deposits.W/	on 960515,containment Leakage in Excess of TS Limits Noted,Due to Valve Leakage.Containment Spray Line Penetration 100 Flushed to Remove Any Boron Deposits.W/	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(i)
05000336/LER-1996-012-01, :on 960228,SIS Drain Stop Valves Failed to Meet Functional Requirements of Ts.Caused by Personnel Error & Inadequate Retest Requirements.C/A:Valve 2-SI-618 Modified & Safety Related Solenoid Valves Inspected	on 960228,SIS Drain Stop Valves Failed to Meet Functional Requirements of Ts.Caused by Personnel Error & Inadequate Retest Requirements.C/A:Valve 2-SI-618 Modified & Safety Related Solenoid Valves Inspected	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)
05000423/LER-1996-012-02, :on 960515,containment Leakage Exceeded Tech Spec Limit.Caused by Boric Acid Residue.Performed Flush of Line to Remove Boron Deposits	on 960515,containment Leakage Exceeded Tech Spec Limit.Caused by Boric Acid Residue.Performed Flush of Line to Remove Boron Deposits	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
05000423/LER-1996-013, :on 960612,design Deficiency in Rhrs.Caused by Inconsideration That Failure Mode of RHS Flow Control Valves Could Create High RHS Heat Exchanger CCP Discharge Temps. Actuators for Heat Exchanger Valves,Modified	on 960612,design Deficiency in Rhrs.Caused by Inconsideration That Failure Mode of RHS Flow Control Valves Could Create High RHS Heat Exchanger CCP Discharge Temps. Actuators for Heat Exchanger Valves,Modified	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000336/LER-1996-013-01, :on 960314,assessed Wide Range Logarithmic Neutron Flux Monitors Nuclear Instrumentation Channels A,B,C & D as Inoperable Due to Potential Susceptability to Common Mode Failure.Replaced Failed Power Supply	on 960314,assessed Wide Range Logarithmic Neutron Flux Monitors Nuclear Instrumentation Channels A,B,C & D as Inoperable Due to Potential Susceptability to Common Mode Failure.Replaced Failed Power Supply	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)
05000423/LER-1996-013-02, :on 960515,determined Design Deficiency in Residual Heat Removal System (Rhs).Caused by Original Plant Design.Corrective Actions Will Be Described in Supplement	on 960515,determined Design Deficiency in Residual Heat Removal System (Rhs).Caused by Original Plant Design.Corrective Actions Will Be Described in Supplement	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
05000336/LER-1996-014-01, :on 960311,weekly TS Surveillances Missed. Caused by Personnel Error W/Respect to Scheduling.C/A: Implemented Requirements of Surveillance Procedure Sp 2614A-3	on 960311,weekly TS Surveillances Missed. Caused by Personnel Error W/Respect to Scheduling.C/A: Implemented Requirements of Surveillance Procedure Sp 2614A-3	10 CFR 50.73(a)(2)(i)
05000423/LER-1996-014-02, :on 960516,surveillances for Emergency Diesel Generator Performed During Operation,Versus Shutdown.Caused by Misinterpretation of Shutdown Stipulation.Surveillances Performed During Shutdown	on 960516,surveillances for Emergency Diesel Generator Performed During Operation,Versus Shutdown.Caused by Misinterpretation of Shutdown Stipulation.Surveillances Performed During Shutdown	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)(iii) 10 CFR 50.73(a)(2)(viii)
05000423/LER-1996-015-05, Forwards LER 96-015-05,documenting Event That Occurred at Plant,Unit 3 on 960610,per 10CFR50.73(a)(2)(ii)(B). Commitments Made within Ltr Submitted	Forwards LER 96-015-05,documenting Event That Occurred at Plant,Unit 3 on 960610,per 10CFR50.73(a)(2)(ii)(B). Commitments Made within Ltr Submitted	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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)
05000423/LER-1996-015-04, Forwards LER 96-015-04,documenting Condition Determined at Unit 3 on 960610.Util Commitments in Response to Event Contained within Attachment 1 to Ltr	Forwards LER 96-015-04,documenting Condition Determined at Unit 3 on 960610.Util Commitments in Response to Event Contained within Attachment 1 to Ltr	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)(i)(B), Prohibited by Technical Specifications
05000336/LER-1996-015-01, :on 960312,failed to Perform Action Requirement for TS LCO 3.3.1.1.Caused by Failure to Recognize Applicability of TS During Abnormal Equipment Configuration. Revised Procedures	on 960312,failed to Perform Action Requirement for TS LCO 3.3.1.1.Caused by Failure to Recognize Applicability of TS During Abnormal Equipment Configuration. Revised Procedures	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000423/LER-1996-015-02, Forwards LER 96-015-02 Re Inadequate Electrical Separation Between Redundant Protection Trains Associated W/Reactor Trip Switches & Reactor Trip Breaker Indicating Lights	Forwards LER 96-015-02 Re Inadequate Electrical Separation Between Redundant Protection Trains Associated W/Reactor Trip Switches & Reactor Trip Breaker Indicating Lights	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)(vii), Common Cause Inoperability
05000423/LER-1996-016-02, :on 960619,switchgear Cabinet in Noncompliance W/Seismic Design Basis & Subsequently Inadvertent Esfa Signal Occurred.Personnel Did Not Latch Known Seismic Latches as Required.Engaged Latches	on 960619,switchgear Cabinet in Noncompliance W/Seismic Design Basis & Subsequently Inadvertent Esfa Signal Occurred.Personnel Did Not Latch Known Seismic Latches as Required.Engaged Latches
05000336/LER-1996-016-01, :on 960312,common Power Supply Cable to 4 Condenser Pit Level Switches Found Improperly Connected. Caused by Inadequate Work Control.Cable Properly Connected & Trip Circuits Tested	on 960312,common Power Supply Cable to 4 Condenser Pit Level Switches Found Improperly Connected. Caused by Inadequate Work Control.Cable Properly Connected & Trip Circuits Tested	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) 10 CFR 50.73(a)(2)
05000336/LER-1996-017, :on 960320,discovered That Hydrogen Monitoring Sys Does Not Meet Single Failure Criterion by Reg Guide 1.97.Caused by Failure to Adequately Consider Sys Design Basis Requirements.Design Change Modified	on 960320,discovered That Hydrogen Monitoring Sys Does Not Meet Single Failure Criterion by Reg Guide 1.97.Caused by Failure to Adequately Consider Sys Design Basis Requirements.Design Change Modified	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)(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)
05000423/LER-1996-017-02, :on 960621,determined Design Deficiency Existed in Tornado Protection Ventilation Dampers,Could Have Affected EDGs Following Tornado.Caused by Inadequate Original Plant Const Design.Procedure Revised	on 960621,determined Design Deficiency Existed in Tornado Protection Ventilation Dampers,Could Have Affected EDGs Following Tornado.Caused by Inadequate Original Plant Const Design.Procedure Revised	10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
05000336/LER-1996-018-01, Forwards LER 96-018-01,documenting Condition That Was Discovered at Unit 2 on 960319.LER Suppl Provides Update on Analyses & Investigation of Condition.Attachment 1 Is Clarification of Original Commitment Associated W/Ler	Forwards LER 96-018-01,documenting Condition That Was Discovered at Unit 2 on 960319.LER Suppl Provides Update on Analyses & Investigation of Condition.Attachment 1 Is Clarification of Original Commitment Associated W/Ler	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000336/LER-1996-018, :on 960316,gaps Discovered in Encls Door Seals for Motor Control Ctrs B51 & B61.Caused by Weakness in Existing Program to Inspect & Verify Integrity of Environ Protective Barriers.Doors for MCC B51 & MCC B61 Replaced	on 960316,gaps Discovered in Encls Door Seals for Motor Control Ctrs B51 & B61.Caused by Weakness in Existing Program to Inspect & Verify Integrity of Environ Protective Barriers.Doors for MCC B51 & MCC B61 Replaced	10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii)
05000423/LER-1996-019-02, :on 960627,RCS PORV Block Valves Were Determined to Be Unable to Perform Intended Safety Functions.Caused by Structural Design Deficiency.C/A Will Be Provided in Supplement to Rept	on 960627,RCS PORV Block Valves Were Determined to Be Unable to Perform Intended Safety Functions.Caused by Structural Design Deficiency.C/A Will Be Provided in Supplement to Rept	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)(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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)
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