05000245/LER-1995-008-02, Forwards Supplemental LER 95-008-02 Which Documents Event That Occurred at Plant on 950411,per 10CFR50.73(a)(2)(ii). Commitment Made within Ltr,Submitted

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Forwards Supplemental LER 95-008-02 Which Documents Event That Occurred at Plant on 950411,per 10CFR50.73(a)(2)(ii). Commitment Made within Ltr,Submitted
Person / Time
ML20132G552
Site:	Millstone
Issue date:	12/19/1996
From:	Hinnenkamp P NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20132G556	List: 05000245/LER-1995-008, :on 950411,potential Inoperability Was Determined Re Feedwater Coolant Injection Sys Upon Failure of S2 DC Power.Caused by Error That Occurred During Original Plant Design.Physical Plant Mods Have Been Completed 05000245/LER-1995-008-02, Forwards Supplemental LER 95-008-02 Which Documents Event That Occurred at Plant on 950411,per 10CFR50.73(a)(2)(ii). Commitment Made within Ltr,Submitted
References
B15998, NUDOCS 9612260294
Download: ML20132G552 (1)
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LER-1995-008, Forwards Supplemental LER 95-008-02 Which Documents Event That Occurred at Plant on 950411,per 10CFR50.73(a)(2)(ii). Commitment Made within Ltr,Submitted

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ii)
2451995008R02 - NRC Website
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text

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g$g Northeast Mai ne otrm. none rerry na.. w.terrora, cr Utilities System P.o.iu 128 Waterrord. Fr 06385-0128 l

(203) 447-1791 i

December 19,1996 Docket No. 50-245 B15998 Re: 10CFR50.73(a)(2)(ii) l U.S. Nuclear Regulatory Comuission Document Control Desk Washington, DC 20555 l

l This letter forwards supplemental Licensee Event Report (LER) 95-008-02, documenting an

[

event that occurred at Millstone Nuclear Power Station, Unit No. I on April 11,1995. This LER is submitted pursuant to 10CFR50.73(a)(2)(ii).

This supplemental LER updates the information contained in the Corrective Action section. Also, additional information is included regarding the reactor feed pump runout protection system.

Lastly, there are some editorial and administrative changes.

j The following is Northeast Nuclear Energy Company's (NNECO's) commitment made within l

this letter. All other statements made within this letter are for information only.

B15998-1 NNECO will complete the integrated testing prior to startup for operating Cycle 16.

j Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY j

YY

~

P. D. Hinnenkamp Director, Unit Operation Attachment: LER 95-008-02 cc: Dr. W. D. Travers, Director, Special Projects H. J. Miller, Region I Administrator 3gQ,,

l S. Dembek, NRC Project Manager, Millstone Unit No.1 T. A. Eastick, Senior Resident Inspector, Millstone Unit No.1 9612260294 961219 Y

PDR ADOCK 05000245 osu22., ary. i.os G

Licensee Event Report

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10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | 23 | 24 | 25 |

		Reporting criterion
05000336/LER-1995-001, :on 950118,crane Operated Over Spent Fuel Pool While Enclosure Bldg Ventilation Sys Inoperable.Caused by Inadequate or Insufficient Procedures.Ts 3.9.7,3.9.14 & 3.19.15 Will Be Reviewed for Clarifications	on 950118,crane Operated Over Spent Fuel Pool While Enclosure Bldg Ventilation Sys Inoperable.Caused by Inadequate or Insufficient Procedures.Ts 3.9.7,3.9.14 & 3.19.15 Will Be Reviewed for Clarifications	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)
05000423/LER-1995-001, :on 950202,SWS Pipe Expansion Joint Discovered to Be Improperly Bolted.Caused by Loss of Work Control.Joint Properly Bolted	on 950202,SWS Pipe Expansion Joint Discovered to Be Improperly Bolted.Caused by Loss of Work Control.Joint Properly Bolted	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000336/LER-1995-002, :on 950125,confirmed Assumption for Original Design Basis Re Containment Sump Isolation Valves non- Conservative.Caused by Inadequate Engineering Evaluation. Hole Drilled Through Disc Ctr Line	on 950125,confirmed Assumption for Original Design Basis Re Containment Sump Isolation Valves non- Conservative.Caused by Inadequate Engineering Evaluation. Hole Drilled Through Disc Ctr Line	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000336/LER-1995-002-01, :on 950125,confirmed That Assumptions Made for Original Design Basis Analysis for Containment Sump Isolation Valve non-conservative.Caused by Inadequate Evaluation.Second Review Completed	on 950125,confirmed That Assumptions Made for Original Design Basis Analysis for Containment Sump Isolation Valve non-conservative.Caused by Inadequate Evaluation.Second Review Completed	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000423/LER-1995-002-02, :on 950209,radioactive Source Was Found Outside Protected Area in Uncontrolled Location.Caused by Radiological Inventory Control Oversight.Surveyed Potentially Involved Areas	on 950209,radioactive Source Was Found Outside Protected Area in Uncontrolled Location.Caused by Radiological Inventory Control Oversight.Surveyed Potentially Involved Areas	10 CFR 50.73(a)(2)
05000336/LER-1995-003-02, :on 960205,failed to Enter TS LCO 3.0.3 After Discovering Svc Water Strainers Inoperable.Caused by Failure to Recognize Ice Plug Formation in Strainer Backwash Line. Implement Comprehensive Operability Process	on 960205,failed to Enter TS LCO 3.0.3 After Discovering Svc Water Strainers Inoperable.Caused by Failure to Recognize Ice Plug Formation in Strainer Backwash Line. Implement Comprehensive Operability Process	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 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000336/LER-1995-003, :on 950130,intake Structure Ventilation Sys Deficiencies Noted.Caused by Allowing non-Category 1 Exhaust Fans to Provide Cooling for Category 1 SW Pump Motors.No Immediate Corrective Action Taken	on 950130,intake Structure Ventilation Sys Deficiencies Noted.Caused by Allowing non-Category 1 Exhaust Fans to Provide Cooling for Category 1 SW Pump Motors.No Immediate Corrective Action Taken	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000423/LER-1995-003-01, :on 950304,separate Components in Independent Trains of ECCS Declared Inoperable Due to Loose Terminal Block in Exhaust Fan Circuitry.Tightened Terminal Block & Secured Retaining Cover	on 950304,separate Components in Independent Trains of ECCS Declared Inoperable Due to Loose Terminal Block in Exhaust Fan Circuitry.Tightened Terminal Block & Secured Retaining Cover	10 CFR 50.73(a)(2)(1)
05000336/LER-1995-004, :on 950131,TS Surveillance for Liquid Waste Radiation Monitor Was Missed Due to Personnel Error. Performed Surveillances to Satisfactory Completion on Following Day	on 950131,TS Surveillance for Liquid Waste Radiation Monitor Was Missed Due to Personnel Error. Performed Surveillances to Satisfactory Completion on Following Day	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)
05000423/LER-1995-004, :on 950322,historical Breaches Affected CR Pressurization & Secondary Containment Vacuum Due to Misinterpretation of Ts.Work Controls Minimized Possibility of Pressure Boundary Breaches	on 950322,historical Breaches Affected CR Pressurization & Secondary Containment Vacuum Due to Misinterpretation of Ts.Work Controls Minimized Possibility of Pressure Boundary Breaches	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1)
05000423/LER-1995-005-01, Forwards Suppl LER 95-005-01,updating Cause of Event & Including Addl Actions to Prevent Recurrence	Forwards Suppl LER 95-005-01,updating Cause of Event & Including Addl Actions to Prevent Recurrence	10 CFR 50.73(a)(2)
05000336/LER-1995-005, :on 950211,inadvertent Actuation of ESF Equipment Occurred.Caused by Wiring Error During Const of Cabinets Combined W/Plant Mod.Verified All Cabinets & Actuation Relay Wiring for Correct Polarity	on 950211,inadvertent Actuation of ESF Equipment Occurred.Caused by Wiring Error During Const of Cabinets Combined W/Plant Mod.Verified All Cabinets & Actuation Relay Wiring for Correct Polarity	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)
05000423/LER-1995-005-02, :on 950413,discovered That Primary Containment Potentially Breached for Almost 2 H on 950405.Caused by Personnel Error & Program & Procedure Weaknesses.Personnel Counselled & Tags Put on Drain Valves	on 950413,discovered That Primary Containment Potentially Breached for Almost 2 H on 950405.Caused by Personnel Error & Program & Procedure Weaknesses.Personnel Counselled & Tags Put on Drain Valves	10 CFR 50.73(a)(2)
05000423/LER-1995-005, :on 950413,discovered That Primary Containment Potentially Breached for Almost Two H on 950405 Due to Personnel Error & Program Weakness.Operators Involved Counseled on Importance of Task Review	on 950413,discovered That Primary Containment Potentially Breached for Almost Two H on 950405 Due to Personnel Error & Program Weakness.Operators Involved Counseled on Importance of Task Review
05000336/LER-1995-006, :on 950213,determined That Unit 1 Swing Bus Relay Power Supply Wiring Not Separated from Unit 2 Swing Bus Power Supply Wiring.Caused by Installation Error. Wiring Encl in Flexible Conduit	on 950213,determined That Unit 1 Swing Bus Relay Power Supply Wiring Not Separated from Unit 2 Swing Bus Power Supply Wiring.Caused by Installation Error. Wiring Encl in Flexible Conduit	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)
05000423/LER-1995-006-01, :on 950413,MSSV Simmer Tested Below TS Setpoint Tolerance.Cause Unknown.No Generic Problem W/Safety Valves or pre-existing Condition Identified.Valve Reset & Verified	on 950413,MSSV Simmer Tested Below TS Setpoint Tolerance.Cause Unknown.No Generic Problem W/Safety Valves or pre-existing Condition Identified.Valve Reset & Verified
05000336/LER-1995-007, :on 950219,fire Watch Found Sleeping in Auxiliary Bldg.Caused by Personnel Error.New Fire Watch Assigned to Affected Areas & Tours of Continuous Posts by Fire Watch Supervisors Increased	on 950219,fire Watch Found Sleeping in Auxiliary Bldg.Caused by Personnel Error.New Fire Watch Assigned to Affected Areas & Tours of Continuous Posts by Fire Watch Supervisors Increased	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1)
05000423/LER-1995-007-02, :on 950416,partial CDA Signal Generated When Limit Switch Contacts Grounded While Performing Mods.Caused by Personnel Error & Programmatic Weaknesses.Reviews W/ Affected Dept Personnel Performed	on 950416,partial CDA Signal Generated When Limit Switch Contacts Grounded While Performing Mods.Caused by Personnel Error & Programmatic Weaknesses.Reviews W/ Affected Dept Personnel Performed	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)
05000245/LER-1995-008, :on 950411,potential Inoperability Was Determined Re Feedwater Coolant Injection Sys Upon Failure of S2 DC Power.Caused by Error That Occurred During Original Plant Design.Physical Plant Mods Have Been Completed	on 950411,potential Inoperability Was Determined Re Feedwater Coolant Injection Sys Upon Failure of S2 DC Power.Caused by Error That Occurred During Original Plant Design.Physical Plant Mods Have Been Completed	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)
05000245/LER-1995-008-02, Forwards Supplemental LER 95-008-02 Which Documents Event That Occurred at Plant on 950411,per 10CFR50.73(a)(2)(ii). Commitment Made within Ltr,Submitted	Forwards Supplemental LER 95-008-02 Which Documents Event That Occurred at Plant on 950411,per 10CFR50.73(a)(2)(ii). Commitment Made within Ltr,Submitted	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000336/LER-1995-008, :on 950221,determined That Vital DC Switchgear Rooms Vital Chillers Could Fail During Periods of Low SW Temp.Caused by Inadequate Design.Isolated Flow Control Valves & Using Bypass Valves to Control Flow	on 950221,determined That Vital DC Switchgear Rooms Vital Chillers Could Fail During Periods of Low SW Temp.Caused by Inadequate Design.Isolated Flow Control Valves & Using Bypass Valves to Control Flow	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000423/LER-1995-008-02, :on 950423,an Individual w/non-active SRO License Assumed Position of Refueling SRO W/O Activating License Per Requirements of 10CFR55.53(f).Cause Due to Lack of Sros.Active SRO Dispatched for Oversight	on 950423,an Individual w/non-active SRO License Assumed Position of Refueling SRO W/O Activating License Per Requirements of 10CFR55.53(f).Cause Due to Lack of Sros.Active SRO Dispatched for Oversight	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)(1)
05000423/LER-1995-009-01, :on 950426,containment Leakage Exceeded TS Limits Due to Valve Leakage.Inspected Valve Seats for Containment Purge Supply & Exhaust Line Valves	on 950426,containment Leakage Exceeded TS Limits Due to Valve Leakage.Inspected Valve Seats for Containment Purge Supply & Exhaust Line Valves	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)
05000423/LER-1995-009, :on 950426, as Found Leak Rate for Containment Isolation Valves Exceeded TS Bypass Leakage Limit.Caused by Deterioration of Resilient Valve Seats.Seats Continue to Be Replaced	on 950426, as Found Leak Rate for Containment Isolation Valves Exceeded TS Bypass Leakage Limit.Caused by Deterioration of Resilient Valve Seats.Seats Continue to Be Replaced	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)(ii)(A), Seriously Degraded 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000336/LER-1995-009, :on 950304,determined That RBCCW Sys Outside of Design Basis.Caused by Failure to Update FSAR Prior to Initial Startup.Ist Has Been Written to Obtain & Adjust Flow Rates,As Needed,To Various RBCCW Loads	on 950304,determined That RBCCW Sys Outside of Design Basis.Caused by Failure to Update FSAR Prior to Initial Startup.Ist Has Been Written to Obtain & Adjust Flow Rates,As Needed,To Various RBCCW Loads	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000423/LER-1995-010-01, :on 950430,power Signal Was Lost During Refueling Outage Due to Procedural Weakness.Revised Procedure for Denergizing Emergency 4160 Volt Bus to Require Tagging Sequencer Bypass Switch	on 950430,power Signal Was Lost During Refueling Outage Due to Procedural Weakness.Revised Procedure for Denergizing Emergency 4160 Volt Bus to Require Tagging Sequencer Bypass Switch	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)
05000336/LER-1995-010, :on 950303,determined That Each Circuit Contained an Auxiliary Contact Off Smoke Detector Circuit Which de-energizes Fan During Fire.Caused by Inadequate Design.Design Change Being Processed	on 950303,determined That Each Circuit Contained an Auxiliary Contact Off Smoke Detector Circuit Which de-energizes Fan During Fire.Caused by Inadequate Design.Design Change Being Processed	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000423/LER-1995-011-01, :on 950515,mussel Shells Found in Recirculation Spray Sys Heat Exchanger.Caused by High Density of Mussel Plantigrades in Spring 1994.Hypochlorite Metering Pumps Installed	on 950515,mussel Shells Found in Recirculation Spray Sys Heat Exchanger.Caused by High Density of Mussel Plantigrades in Spring 1994.Hypochlorite Metering Pumps Installed	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(1)
05000336/LER-1995-011, :on 950316,determined That EHC Pressure Switches Not Isolated from RPS Circuitry Due to Inadequate Design Control.Design Engineering Reviewing Listed Potential Options for Corrective Actions	on 950316,determined That EHC Pressure Switches Not Isolated from RPS Circuitry Due to Inadequate Design Control.Design Engineering Reviewing Listed Potential Options for Corrective Actions	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000336/LER-1995-012, :on 950313,determined That RPS RCS Low Flow Trip Setting May Not Satisfy Assumptions in Sa.Caused by Excessive Component (Transmitter) Drift & Inadequate Design Review.Rcs Flow Transmitter Recalibrated	on 950313,determined That RPS RCS Low Flow Trip Setting May Not Satisfy Assumptions in Sa.Caused by Excessive Component (Transmitter) Drift & Inadequate Design Review.Rcs Flow Transmitter Recalibrated	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)
05000423/LER-1995-012-01, :on 950602,CR Received Containment Smoke Alarm. Caused by Flashing of Small Quantity of RCP Lube Oil. Performed Exam of Remaining Areas of Maint	on 950602,CR Received Containment Smoke Alarm. Caused by Flashing of Small Quantity of RCP Lube Oil. Performed Exam of Remaining Areas of Maint	10 CFR 50.73(a)(2)(x)
05000423/LER-1995-013-01, :on 950628,determined That an IST Surveillance Had Lapsed on C Charging Sys Pump & Discharge Check Valve. Caused by Inadequate Procedures.Surveillances Performed & Procedures Revised	on 950628,determined That an IST Surveillance Had Lapsed on C Charging Sys Pump & Discharge Check Valve. Caused by Inadequate Procedures.Surveillances Performed & Procedures Revised	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)
05000336/LER-1995-013, :on 950314,SPEC 200 Cabinet Electrical Separation Was Not Maintained Due to Installation Error During Original Installation of ATWS Circuit.Enclosed Wiring in Flexible Conduit	on 950314,SPEC 200 Cabinet Electrical Separation Was Not Maintained Due to Installation Error During Original Installation of ATWS Circuit.Enclosed Wiring in Flexible Conduit	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000423/LER-1995-014-01, :on 950713,TDAFWP Did Not Start within One Minute as Required by TS While Performing Surveillance Test on Tdafwp Due to Governor Valve Position.Revised Procedures	on 950713,TDAFWP Did Not Start within One Minute as Required by TS While Performing Surveillance Test on Tdafwp Due to Governor Valve Position.Revised Procedures	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)
05000336/LER-1995-014, :on 950404,continuous Fire Watch Was Found Sleeping in West 480 Volt Switchgear Room Due to Personnel Error.Posted Another Individual as Fire Watch	on 950404,continuous Fire Watch Was Found Sleeping in West 480 Volt Switchgear Room Due to Personnel Error.Posted Another Individual as Fire Watch	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B)
05000336/LER-1995-015, :on 950418,crane Operation Over Spent Fuel Pool W/Emergency Ventilation Inoperable Occurred Due to Disassembly of Main Exhaust Fan.Installed Bypass Jumper to Blank Off Opening in Ductwork	on 950418,crane Operation Over Spent Fuel Pool W/Emergency Ventilation Inoperable Occurred Due to Disassembly of Main Exhaust Fan.Installed Bypass Jumper to Blank Off Opening in Ductwork	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000423/LER-1995-015-01, :on 950718,missed ASME Insps Due to Programatic Oversight.Components Inspected by ASME XI VT-2 Certified Personnel	on 950718,missed ASME Insps Due to Programatic Oversight.Components Inspected by ASME XI VT-2 Certified Personnel	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)(1)
05000423/LER-1995-016-02, :on 950911,A Train Quench Spray Pump Discharge Valve Exceeded TS Surveillence Periodicity Limit.Caused by Programmatic Error.Surveillance Tracking Procedure Revised	on 950911,A Train Quench Spray Pump Discharge Valve Exceeded TS Surveillence Periodicity Limit.Caused by Programmatic Error.Surveillance Tracking Procedure Revised
05000336/LER-1995-016, :on 950428,operator W/Inactive SRO License Assumed Position of Fuel Handling SRO for Movement of Upper Guide Structure Into Rv.Caused by Failure to Recognize Inactive Status.Briefing Conducted	on 950428,operator W/Inactive SRO License Assumed Position of Fuel Handling SRO for Movement of Upper Guide Structure Into Rv.Caused by Failure to Recognize Inactive Status.Briefing Conducted	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)
05000423/LER-1995-017-02, :on 951012,TS Surveillance Was Missed Due to Programmatic Weakness & Personnel Error.Counseled Individuals Involved	on 951012,TS Surveillance Was Missed Due to Programmatic Weakness & Personnel Error.Counseled Individuals Involved	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000336/LER-1995-017, :on 950503,contract Individual Assigned as Continous Fire Watch Found Sleeping in West 480 Volt Switch Gear Room.Caused by Personnel Error.Individual Replaced & Chairs Removed from Location	on 950503,contract Individual Assigned as Continous Fire Watch Found Sleeping in West 480 Volt Switch Gear Room.Caused by Personnel Error.Individual Replaced & Chairs Removed from Location	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)
05000336/LER-1995-018, :on 950510,determined That Plant Entered Mode 6 from Defueled Condition W/O Satisfying TS 3.8.1.2.Caused by Design Error by Contact Reader Mfg.Mods Made to ESFAS Components	on 950510,determined That Plant Entered Mode 6 from Defueled Condition W/O Satisfying TS 3.8.1.2.Caused by Design Error by Contact Reader Mfg.Mods Made to ESFAS Components	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)
05000423/LER-1995-018-02, :on 951121,FSAR Limit for New Fuel Movement Over New Fuel Storage Racks Was Exceeded.Caused by Inadequate Procedures.Procedures Revised	on 951121,FSAR Limit for New Fuel Movement Over New Fuel Storage Racks Was Exceeded.Caused by Inadequate Procedures.Procedures Revised
05000423/LER-1995-019-01, :on 951201,reactor Coolant Sys Pressure Boundary Leak Occurred Due to Instrument Line & Drain Line Socket Weld Failure.All 16 RCS Loop Flow Instrument Line Socket & Weld Bosses Have Been Cut & Removed	on 951201,reactor Coolant Sys Pressure Boundary Leak Occurred Due to Instrument Line & Drain Line Socket Weld Failure.All 16 RCS Loop Flow Instrument Line Socket & Weld Bosses Have Been Cut & Removed	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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii)
05000336/LER-1995-019-01, Forwards LER 95-019-01.Util Commitments Listed,Including Reviews of Operation Procedures to Be Completed by 961115	Forwards LER 95-019-01.Util Commitments Listed,Including Reviews of Operation Procedures to Be Completed by 961115	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000423/LER-1995-019-02, :on 951201,leaks Found in 3/4 Inch Socket Welds on C RCS Loop Flow Instrumentation Line & RCP Seal Injection Drain Line.Caused by Vibration Induced Fatigue at Stress Riser in Weld.Welds & Weld Bosses Removed	on 951201,leaks Found in 3/4 Inch Socket Welds on C RCS Loop Flow Instrumentation Line & RCP Seal Injection Drain Line.Caused by Vibration Induced Fatigue at Stress Riser in Weld.Welds & Weld Bosses Removed	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)
05000336/LER-1995-019-02, Forwards LER 95-019-02,documenting Event That Occurred at Millstone Nuclear Power Station Unit 2 on 950514.Util Commitments Made within Ltr,Listed	Forwards LER 95-019-02,documenting Event That Occurred at Millstone Nuclear Power Station Unit 2 on 950514.Util Commitments Made within Ltr,Listed	10 CFR 50.73(a)(2)(i)
05000336/LER-1995-020, :on 950516,automatic Actuation of ESF Occurred During Maint Due to Inadequate Design of ESFAS Circuitry for Maint.Fans F25A & F32A Secured & Possible Changes to ESFAS Sys Will Be Investigated	on 950516,automatic Actuation of ESF Occurred During Maint Due to Inadequate Design of ESFAS Circuitry for Maint.Fans F25A & F32A Secured & Possible Changes to ESFAS Sys Will Be Investigated	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000423/LER-1995-020, :on 951202,RCS Pressure Boundary Leak from Valve Bonnet Stem leak-off Pipe Occurred.Caused by Crack Near Toe of Fillet Weld Between Pipe & Valve Body.Removed Pipe & Valve Bonnet Weld	on 951202,RCS Pressure Boundary Leak from Valve Bonnet Stem leak-off Pipe Occurred.Caused by Crack Near Toe of Fillet Weld Between Pipe & Valve Body.Removed Pipe & Valve Bonnet Weld	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 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000336/LER-1995-020-01, :on 950516,automatic Actuation of Engineered Safety Feature Occurred During Maint.Caused by Procedure Deficiency.Revised Operations Procedure OP-2384 to Add Appropriate Caution for de-energization of Cabinets	on 950516,automatic Actuation of Engineered Safety Feature Occurred During Maint.Caused by Procedure Deficiency.Revised Operations Procedure OP-2384 to Add Appropriate Caution for de-energization of Cabinets	10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)
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