05000373/LER-1995-001, Cancels LER 95-001-00 for Facility.Licensee Determined That LaSalle County Station Not in Condition Prohibited by TS 3.4.3.2

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Cancels LER 95-001-00 for Facility.Licensee Determined That LaSalle County Station Not in Condition Prohibited by TS 3.4.3.2
Person / Time
ML20096H030
Site:	LaSalle
Issue date:	01/23/1996
From:	Ray D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9601260231
Download: ML20096H030 (1)
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LER-1995-001, Cancels LER 95-001-00 for Facility.Licensee Determined That LaSalle County Station Not in Condition Prohibited by TS 3.4.3.2

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
3731995001R00 - NRC Website
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text

Commonwealth lilimn Company lahalle Gencrating Atation

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2601 North 21st Road Marseillen, 11.61341 9-(7 Tel H15357476 l January 23,1996 United States Nuclear Regulatory Conunission Attention: Document Control Desk Washington, D.C. 20555 The cwaHation ofLicensee Event Report #95-001-00, Docket #050-373 is being

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submitted to your office in accordance with 10 CFR 50.73 (a) (2) (i) (B).

Upon further review of this licensee event report, it has been determined that LaSalle County Station was not in a condition prohibited by Technical Specification 3.4.3.2.

Technical Specification 3.4.3.2.d. states, "With one or more higMow pressure interface valve leakage pressure monitors inoperable, restore the inoperable monitor (s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm setpoint at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by local indication". Since local verification was accomplished on a shiftly (8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) basis by the Unit 1 Equipment Attendant, LaSalle was in full compliance with Tech Spec 3.4.3.2.

Our lack of thoroughness during the initial review of this event caused us to inappropriately classify this event as reportable under 10 CFR 50.73. LaSalle Station has implemented a more rigorous initial screening and technical review process.

Sin l

D. J.

y Station Manager LaSalle County Station Enclosure cc:

H. J. Miller, NRC Region III Administrator H. J. Simons, Acting NRC Senior Resident Inspector IDNS Resident Inspector F. Niziolek, IDNS Senior Reactor Analyst INPO-Records Center D. L. Farrar, Nuclear Regulatory Services Manager PRnno~

}\\ D 960t260231 960123 PDR ADOCK 05000373 j

g PDR A I!nicom Company

Licensee Event Report

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		Reporting criterion
05000373/LER-1995-001-01, :on 950106,RHR Instrument Root Valve Was Found Closed.No Specific Cause Could Be Determined.Functional Test Satisfactorily Completed & Switch Restored to Proper Unisolated Condition	on 950106,RHR Instrument Root Valve Was Found Closed.No Specific Cause Could Be Determined.Functional Test Satisfactorily Completed & Switch Restored to Proper Unisolated Condition	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)
05000374/LER-1995-001-06, :on 950112,unit 2 in Operational Condition 1 at 100% Power,Eccs & Reactor Core Isolation Cooling Low Level Initiation Occurred Resulting in Rcic.Caused by Incorrect Test Vent Valve Being Opened	on 950112,unit 2 in Operational Condition 1 at 100% Power,Eccs & Reactor Core Isolation Cooling Low Level Initiation Occurred Resulting in Rcic.Caused by Incorrect Test Vent Valve Being Opened	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)
05000373/LER-1995-001, Cancels LER 95-001-00 for Facility.Licensee Determined That LaSalle County Station Not in Condition Prohibited by TS 3.4.3.2	Cancels LER 95-001-00 for Facility.Licensee Determined That LaSalle County Station Not in Condition Prohibited by TS 3.4.3.2	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000373/LER-1995-002-05, :on 950208,Unit 1 Reactor Shutdown Commenced Due to Inability to Isolate Inboard Steam Supply to Rcic. PCIS Valve 1E51-F063 Declared Inoperable & Outboard Isolation Valve 1E51-F007 Closed & Deactivated	on 950208,Unit 1 Reactor Shutdown Commenced Due to Inability to Isolate Inboard Steam Supply to Rcic. PCIS Valve 1E51-F063 Declared Inoperable & Outboard Isolation Valve 1E51-F007 Closed & Deactivated	10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000374/LER-1995-002-04, :on 950203,TS Hourly Firewatch Was Missed Due to Personnel Error.Individual Involved Has Been Counseled Re Actions	on 950203,TS Hourly Firewatch Was Missed Due to Personnel Error.Individual Involved Has Been Counseled Re Actions	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 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000373/LER-1995-003-01, :on 950127,potential Traversing in-core Probe Containment Isolation Design Concern Noted.Interim Administrative Controls Put in Place to Ensure That Containment Isolation Function Not Compromised	on 950127,potential Traversing in-core Probe Containment Isolation Design Concern Noted.Interim Administrative Controls Put in Place to Ensure That Containment Isolation Function Not Compromised	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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000374/LER-1995-003-04, :on 950221,an Unexpected CRD Scram Discharge Vol High Level Scram Signal Received.Caused by High Water Level Due to Mgt Deficiency.Reactor Scram Signal Reset & High Level Scram Bypassed	on 950221,an Unexpected CRD Scram Discharge Vol High Level Scram Signal Received.Caused by High Water Level Due to Mgt Deficiency.Reactor Scram Signal Reset & High Level Scram Bypassed	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) 10 CFR 50.73(a)(2)(viii)(8)
05000373/LER-1995-004, :on 950131,senior Licensed Operator Was Not Present in MCR Due to Personnel Error.Memo Was Sent to All Active SRO Licensed Personnel Informing of Event at Station & Reminding of Need for Operator to Be in MCR	on 950131,senior Licensed Operator Was Not Present in MCR Due to Personnel Error.Memo Was Sent to All Active SRO Licensed Personnel Informing of Event at Station & Reminding of Need for Operator to Be in MCR	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 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1)
05000374/LER-1995-004-02, :on 950228,determined That on Three Separate Occasions Between 950220-24 That Hourly Fire Watches Not Performed.Caused by Mgt Deficiency.Immediate Investigation Conducted	on 950228,determined That on Three Separate Occasions Between 950220-24 That Hourly Fire Watches Not Performed.Caused by Mgt Deficiency.Immediate Investigation Conducted	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) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000374/LER-1995-005-01, :on 950218,outboard MSIV Failed to Close When Switch Placed in Closed Position.Caused by Sticking of Solenoid Pilot Valve.Valves Replaced	on 950218,outboard MSIV Failed to Close When Switch Placed in Closed Position.Caused by Sticking of Solenoid Pilot Valve.Valves Replaced	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) 10 CFR 50.73(a)(2)(viii)(8)
05000373/LER-1995-005-06, :on 950208,discovered That Samples of Diesel Fuel Required by TS 4.8.1.1.2.c.2 Not Taken Due to Failure to Properly Implement Changes to TS 4.8.1.1.2.c.2 Sampling Requirements.Sampling Procedures Revised.W/O Ltr	on 950208,discovered That Samples of Diesel Fuel Required by TS 4.8.1.1.2.c.2 Not Taken Due to Failure to Properly Implement Changes to TS 4.8.1.1.2.c.2 Sampling Requirements.Sampling Procedures Revised.W/O Ltr	10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000373/LER-1995-006-01, :on 950210,recirculation Flow Units Rod Block Function Was Inoperable Due to Procedure to Test Flow Unit Inadequate.Procedure Revised	on 950210,recirculation Flow Units Rod Block Function Was Inoperable Due to Procedure to Test Flow Unit Inadequate.Procedure Revised	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)
05000374/LER-1995-006-02, :on 950302,primary Containment Maximum Allowable Leakage Exceeded Due to LLRT Failure.Generated Action Requests to Repair 2RE024 & 2RE025	on 950302,primary Containment Maximum Allowable Leakage Exceeded Due to LLRT Failure.Generated Action Requests to Repair 2RE024 & 2RE025	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)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000374/LER-1995-006, :on 950302,primary Containment Maximum Allowable Leakage Was Exceeded Due to LLRT Failure.Repaired Valves	on 950302,primary Containment Maximum Allowable Leakage Was Exceeded Due to LLRT Failure.Repaired Valves	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) 10 CFR 50.73(a)(2)(1)
05000374/LER-1995-007-02, :on 950411,division 2 ESF Actuation Occurred Due to Instrument Ref Line Pressure Spike.Closed Injection Valve 2E12-F042C & Secured 2A DG	on 950411,division 2 ESF Actuation Occurred Due to Instrument Ref Line Pressure Spike.Closed Injection Valve 2E12-F042C & Secured 2A DG	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000373/LER-1995-007, :on 950216,noted That Quarterly TS Surveillances for Fourth Quarter 1994 Had Not Been Performed.Caused by Personnel Error.Surveillances Performed	on 950216,noted That Quarterly TS Surveillances for Fourth Quarter 1994 Had Not Been Performed.Caused by Personnel Error.Surveillances Performed	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)(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 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000373/LER-1995-008-01, :on 950301,determined That TS SR to Take CR Temp Not Met Due to Deficient Procedure.Required Readings Immediately Taken & Verified & Operations Dept Sp LOS-AA-S2 Revised	on 950301,determined That TS SR to Take CR Temp Not Met Due to Deficient Procedure.Required Readings Immediately Taken & Verified & Operations Dept Sp LOS-AA-S2 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)(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)
05000374/LER-1995-008-02, :on 950415,reactor Scrammed from High Scram Discharge Vol Water Due to Mgt Deficiency.Operating Personnel Responded to Alarm/Annunciator Conditions & Performed Required Immediate Action	on 950415,reactor Scrammed from High Scram Discharge Vol Water Due to Mgt Deficiency.Operating Personnel Responded to Alarm/Annunciator Conditions & Performed Required Immediate Action	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000373/LER-1995-009, :on 950315,flood Protection Features Not as Described in UFSAR Due to Const Deficiencies.Stationed Operators in Unit 1 Division I & Division III CSCS-ECWS Pump Rooms as Flood Watches	on 950315,flood Protection Features Not as Described in UFSAR Due to Const Deficiencies.Stationed Operators in Unit 1 Division I & Division III CSCS-ECWS Pump Rooms as Flood Watches	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 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000374/LER-1995-009-02, :on 950503,HPCS DG & HPCS Pump Initiation Occurred Due to Procedural Deficiency.Hpcs Pump Was Secured After Verification That Actual Rv Water Level Was Not Low	on 950503,HPCS DG & HPCS Pump Initiation Occurred Due to Procedural Deficiency.Hpcs Pump Was Secured After Verification That Actual Rv Water Level Was Not Low	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) 10 CFR 50.73(a)(2)(viii)(B)
05000374/LER-1995-010-04, :on 951007,Unit Two Fire Door 615 Was Left Open Due to Personnel Error.Reviewed Fire Impairment Log & Was Determined No Active Fire Impairment for Fire Door 615	on 951007,Unit Two Fire Door 615 Was Left Open Due to Personnel Error.Reviewed Fire Impairment Log & Was Determined No Active Fire Impairment for Fire Door 615	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)
05000373/LER-1995-010-01, :on 950415,auto Start of Standby Gas Treatment, Units 1 & 2 Division 2 Reactor Bldg Ventilation Isolation & Other Isolation Signals Received Due to Wrong Fuse Being Pulled Due to Personnel Error.Replaced Fuse	on 950415,auto Start of Standby Gas Treatment, Units 1 & 2 Division 2 Reactor Bldg Ventilation Isolation & Other Isolation Signals Received Due to Wrong Fuse Being Pulled Due to Personnel Error.Replaced Fuse	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)
05000374/LER-1995-011-06, :on 951127,inadvertent Esfa & RCIC Occurred Due to Personnel Error.Replaced Failed Differential Pressure Switch	on 951127,inadvertent Esfa & RCIC Occurred Due to Personnel Error.Replaced Failed Differential Pressure Switch	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)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000373/LER-1995-011-02, :on 950621,noted That Firewatch/Compensatory Measure Logs Showed That TS Hourly Fire Watches Frequently Performed at Intervals Exceeding 1 H.Caused by Lack of Mgt Oversight.Security Post Orders Revised	on 950621,noted That Firewatch/Compensatory Measure Logs Showed That TS Hourly Fire Watches Frequently Performed at Intervals Exceeding 1 H.Caused by Lack of Mgt Oversight.Security Post Orders Revised	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) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000373/LER-1995-012-02, :on 950710,fire Protection Valve Was Missed Due to Mgt Deficiency.Verified 1FP141 & 2FP141 to Be in Proper Open Positions	on 950710,fire Protection Valve Was Missed Due to Mgt Deficiency.Verified 1FP141 & 2FP141 to Be in Proper Open Positions	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 50.72(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) 10 CFR 50.73(a)(2)(1)
05000373/LER-1995-013-01, :on 950726,discovered That DG 1B Low Lube Oil Pressure Shutdown Switch (PS-1E22-N515) Not Calibr Per Procedure LIP-DG-505 Due to Personnel Error.Dg 1B Low Lube Oil Pressure Shutdown Switch Calibr	on 950726,discovered That DG 1B Low Lube Oil Pressure Shutdown Switch (PS-1E22-N515) Not Calibr Per Procedure LIP-DG-505 Due to Personnel Error.Dg 1B Low Lube Oil Pressure Shutdown Switch Calibr	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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1)
05000373/LER-1995-014-02, :on 950816,reactor Scram Occurred Due to 1D RPS Trip Causing Group 1 Isolation.Upgrade Model of EPM Assembly Logic Cards Installed on Both Unit 1 RPS Motor Generator Sets & Upper Main Steam Tunnel Switches Calib	on 950816,reactor Scram Occurred Due to 1D RPS Trip Causing Group 1 Isolation.Upgrade Model of EPM Assembly Logic Cards Installed on Both Unit 1 RPS Motor Generator Sets & Upper Main Steam Tunnel Switches Calib	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)
05000373/LER-1995-015-01, :on 950824,TS Fire Protection Valve Surveillance Was Missed.Caused by Insufficient Review of TSs During Mod Process.Revised Fire Protection Design Checklist	on 950824,TS Fire Protection Valve Surveillance Was Missed.Caused by Insufficient Review of TSs During Mod Process.Revised Fire Protection Design Checklist	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000373/LER-1995-015-02, :on 950824,TS Fire Protection Valve Surveillance Was Missed Due to Insufficient Review of TS Fire Surveillance During Mod Process.Implemented Fire Watch in Unit 1 Csr	on 950824,TS Fire Protection Valve Surveillance Was Missed Due to Insufficient Review of TS Fire Surveillance During Mod Process.Implemented Fire Watch in Unit 1 Csr	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)
05000373/LER-1995-016-03, :on 950924,initiated Manual Reactor Scram Due to Emergency Governor Lockout Valve Sticking.Oil Samples Taken of Supply Oil (Turbine Lube Oil Sys) for 1A & 1B Turbine Driven Reactor Feed Pump for Analysis	on 950924,initiated Manual Reactor Scram Due to Emergency Governor Lockout Valve Sticking.Oil Samples Taken of Supply Oil (Turbine Lube Oil Sys) for 1A & 1B Turbine Driven Reactor Feed Pump for Analysis	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(2)(3)
05000373/LER-1995-017-03, :on 951010,determined That PCIS Contacts for RB Ventilation & FPC Exhaust Ventilation High RM Trip Sys Not Being Tested Per TS 4.3.2.2 Due to Procedural Deficiencies. Changes Will Be Made to Sps for Logic Testing	on 951010,determined That PCIS Contacts for RB Ventilation & FPC Exhaust Ventilation High RM Trip Sys Not Being Tested Per TS 4.3.2.2 Due to Procedural Deficiencies. Changes Will Be Made to Sps for Logic Testing	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)
05000373/LER-1995-018-03, :on 951128,1B RPS M/G Set Tripped Resulting in Half Scram Due to Relay failure.1B RPS M/G Set 1C71-S001B-1K Relay Replaced & Normally Energized Model CR120A Relay in M/G Sets 1A,2A & 2B Will Be Replaced	on 951128,1B RPS M/G Set Tripped Resulting in Half Scram Due to Relay failure.1B RPS M/G Set 1C71-S001B-1K Relay Replaced & Normally Energized Model CR120A Relay in M/G Sets 1A,2A & 2B Will Be 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)(x) 10 CFR 50.73(a)(2)(iii) 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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