05000272/LER-1996-010, Forwards LER 96-010-00 Re Inadequate Pressurizer Relief Tank Supports.Attachment a Represents Commitment Made to NRC

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Forwards LER 96-010-00 Re Inadequate Pressurizer Relief Tank Supports.Attachment a Represents Commitment Made to NRC
Person / Time
ML18102A262
Site:	Salem
Issue date:	07/16/1996
From:	Garchow D Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18102A263	List: 05000272/LER-1996-010, Forwards LER 96-010-00 Re Inadequate Pressurizer Relief Tank Supports.Attachment a Represents Commitment Made to NRC 05000272/LER-1996-010-01, :on 960619,identified Pressurizer Relief Tank Hydrodynamic Loads Had Not Previously Been Considered in Support Design.Caused by Failure to Consider Hydrodynamic Loads Caused by Water Discharge.Supports Revised
References
LR-N96200, NUDOCS 9607230284
Download: ML18102A262 (2)
v • d • e

LER-1996-010, Forwards LER 96-010-00 Re Inadequate Pressurizer Relief Tank Supports.Attachment a Represents Commitment Made to NRC

Event date:
Report date:
2721996010R00 - NRC Website
v • d • e

text

e OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit JUL 161996 LR-N96200 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

LER 272/96-010-00 SALEM GENERATING STATION -

UNIT* 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 This Licensee Event Report entitled "Inadequate Pressurizer Relief Tank Supports" is being submitted pursu?-nt to the requirements of the Code of Federal Regulations 10CFR50. 73 (a) (2) (ii).

Attachment SORC Mtg.96-095 JMO/tcp C

Distribution LER File 3.7 9607230284 960716 PDR ADOCK 05000272 S

PDR The po.ver is in )'Dur hands..

Sincerely, c;!:;;~/

General Manager -

Salem Operations 95-2168 REV. 6/94

Document Control Desk LR-N96200 Attachment A The following item represents the commitment that Public Service Electric & Gas (PSE&G) made to the Nuclear Regulatory Commission (NRC) relative to this LER (272/96-010-00).

The commitment is as follows:

Revise each unit's PRT support design to withstand hydrodynamic loads and complete any required modifications for each unit prior to that unit's entry into mode 3.

Licensee Event Report

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90 | 91 | 92 | 93 | 94 | 95 | 96 | 97 | 98 | 99 | 00 | 01 | 02 | 03 | 04 | 05 | 06 | 07 | 08 | 09 |

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

		Reporting criterion
05000272/LER-1996-001, :on 960103,discovered Insufficent Thermal Overload Relay Heater Margin.Caused by Inadequate Design of TOLs in 1970s.Issued Calculation ES-18.007 for Sizing of Thermal Overload Heaters for SR Rotating Loads	on 960103,discovered Insufficent Thermal Overload Relay Heater Margin.Caused by Inadequate Design of TOLs in 1970s.Issued Calculation ES-18.007 for Sizing of Thermal Overload Heaters for SR Rotating Loads
05000311/LER-1996-001-01, :on 960109,TS Violation Occurred Re Failure to Perform Chemistry Sampling within Required Timeframe.Caused by Personnel Error.Personnel Counseled & Chemistry Dept Shift Turnover Process Improved	on 960109,TS Violation Occurred Re Failure to Perform Chemistry Sampling within Required Timeframe.Caused by Personnel Error.Personnel Counseled & Chemistry Dept Shift Turnover Process Improved	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000311/LER-1996-002-02, :on 960701,waste Gas Decay Tank Oxygen Concentration Exceeded TSs Limit.Caused by Poor Wording & Interpretation of Tss.Oxygen Concentration Levels Restored. Request to Resolve TS 3.11.2.5 Submitted to NRC on 960815	on 960701,waste Gas Decay Tank Oxygen Concentration Exceeded TSs Limit.Caused by Poor Wording & Interpretation of Tss.Oxygen Concentration Levels Restored. Request to Resolve TS 3.11.2.5 Submitted to NRC on 960815	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000272/LER-1996-002, :on 960110,evaluation Determined That Motor Operated Gate Valves Susceptible to Pressure Locking & Thermal Binding.Caused by Inability to Meet GL 95-07 Criteria.Test Procedure Changed	on 960110,evaluation Determined That Motor Operated Gate Valves Susceptible to Pressure Locking & Thermal Binding.Caused by Inability to Meet GL 95-07 Criteria.Test Procedure Changed	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) 10 CFR 50.73(e)(2)(v)
05000311/LER-1996-003-02, :on 960515,failed to Perform Surveillance for Fuel Handling Bldg (Fhb) Ventilation Sys Auto Start.Caused by Lack of Adequate Controls for Surveillance Procedures. Added auto-start Capability	on 960515,failed to Perform Surveillance for Fuel Handling Bldg (Fhb) Ventilation Sys Auto Start.Caused by Lack of Adequate Controls for Surveillance Procedures. Added auto-start Capability	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation
05000272/LER-1996-003-01, :on 960220,TS Radiation Monitor Sampling in non-compliance.Caused by Failure of Plant Chemistry to Fully Understand TS Sample & Analysis Requirements.Established Process for Controlling Analyses	on 960220,TS Radiation Monitor Sampling in non-compliance.Caused by Failure of Plant Chemistry to Fully Understand TS Sample & Analysis Requirements.Established Process for Controlling Analyses	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)(viii)
05000311/LER-1996-004-02, :on 960515,failed to Perform Compensatory Radiological Survey.Caused by Personnel Error.Performed Survey,Revised Radiation Protection Schedule,Purchased Alarm Clocks & Counseled Personnel Re Event	on 960515,failed to Perform Compensatory Radiological Survey.Caused by Personnel Error.Performed Survey,Revised Radiation Protection Schedule,Purchased Alarm Clocks & Counseled Personnel Re Event	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)(iii) 10 CFR 50.73(a)(2)(viii)
05000272/LER-1996-004-01, :on 960307,surveillance Was Missed for Salem Generating Station.Caused by Lack of Adequate Control for Development & Maintenance of TS Surveillance Procedures. License Change Will Be Submitted	on 960307,surveillance Was Missed for Salem Generating Station.Caused by Lack of Adequate Control for Development & Maintenance of TS Surveillance Procedures. License Change Will Be Submitted
05000272/LER-1996-004, :on 960307,containment Isolation Valve Missed TS Surveillance.Caused by Lack of Adequate Controls & Inadequate Design Review.Ts Surveillance Improvement Project Has Been Initiated for Plant,Units 1 & 2	on 960307,containment Isolation Valve Missed TS Surveillance.Caused by Lack of Adequate Controls & Inadequate Design Review.Ts Surveillance Improvement Project Has Been Initiated for Plant,Units 1 & 2	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)
05000272/LER-1996-005-05, Forwards LER 96-005-05 Re Surveillance for turbine-driven AF Pump.Commitments Encl as Attachment a	Forwards LER 96-005-05 Re Surveillance for turbine-driven AF Pump.Commitments Encl as Attachment a
05000272/LER-1996-005-01, :on 960325,channel Checks for Average Temp Not Performed as Required by Ts.Caused by Inadequate Controls for Development & Maint of TS Surveillance Procedures.Tssip Initiated	on 960325,channel Checks for Average Temp Not Performed as Required by Ts.Caused by Inadequate Controls for Development & Maint of TS Surveillance Procedures.Tssip Initiated	10 CFR 50.73(a)(2)(iv), System Actuation
05000272/LER-1996-005, :on 971224,inadequate TS Testing of Containment Airlock Door Gasket Leakage Was Noted.Caused by Lack of Adequate Controls & Understanding of Development. Appropriate Procedures Reviewed	on 971224,inadequate TS Testing of Containment Airlock Door Gasket Leakage Was Noted.Caused by Lack of Adequate Controls & Understanding of Development. Appropriate Procedures Reviewed	10 CFR 50.73(a)(2)(1)
05000311/LER-1996-005-02, :on 960627,surveillance of Fuel Handling Bldg Ventilation Sys Charcoal Adsorber Test Was Missed.Caused by Inattention to Detail.Individual Involved Received Appropriate Level of Positive Discipline	on 960627,surveillance of Fuel Handling Bldg Ventilation Sys Charcoal Adsorber Test Was Missed.Caused by Inattention to Detail.Individual Involved Received Appropriate Level of Positive Discipline
05000272/LER-1996-005-15, Forwards LER 96-005-15, Inadequate TS Testing - Feedwater Sys Isolation Functional Test/Component Cooling Water Heat Exchanger Service Water Flow Control Valves	Forwards LER 96-005-15, Inadequate TS Testing - Feedwater Sys Isolation Functional Test/Component Cooling Water Heat Exchanger Service Water Flow Control Valves
05000272/LER-1996-005-03, :on 960325,TS Surveillance Requirement Implementation Deficiencies Identified.Caused by Lack of Adequate Controls & Understanding of Development Weakness. Procedures Revised	on 960325,TS Surveillance Requirement Implementation Deficiencies Identified.Caused by Lack of Adequate Controls & Understanding of Development Weakness. Procedures Revised	10 CFR 50.73(a)(2)(i)
05000311/LER-1996-006-02, :on 960717,sample Flow to non-radioactive Liquid Radwaste Monitor Was Not Adequate to Meet Plant Ts.Cause of Event Is Under Investigation.Design of 2R37 Sample Line Has Been Revised	on 960717,sample Flow to non-radioactive Liquid Radwaste Monitor Was Not Adequate to Meet Plant Ts.Cause of Event Is Under Investigation.Design of 2R37 Sample Line Has Been Revised	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000272/LER-1996-006-01, :on 960421,missed Independent Verification of Release Lineup on Waste Gas Decay Tanks (Wgdt) Due to Personnel.Wgdt Releases Suspended Pending Rev of Procedures. Procedures Revised	on 960421,missed Independent Verification of Release Lineup on Waste Gas Decay Tanks (Wgdt) Due to Personnel.Wgdt Releases Suspended Pending Rev of Procedures. 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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000311/LER-1996-006-01, :on 960717,determined That non-radioactive Liquid Basin Radwaste Monitor Inoperable During Low Head Conditions.Caused by Inadequate Design Change Package.Design Change 1EC3663-01 Has Been Installed.With	on 960717,determined That non-radioactive Liquid Basin Radwaste Monitor Inoperable During Low Head Conditions.Caused by Inadequate Design Change Package.Design Change 1EC3663-01 Has Been Installed.With	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)
05000272/LER-1996-007-01, :on 960524,determined P-12 Setpoint Above Tech Spec Table 3.3-3 Value.Caused by Incorrect Conversion from Standard Tech Spec for Westinghouse Pressurized Water Reactors. Revised Procedures	on 960524,determined P-12 Setpoint Above Tech Spec Table 3.3-3 Value.Caused by Incorrect Conversion from Standard Tech Spec for Westinghouse Pressurized Water Reactors. Revised Procedures
05000311/LER-1996-007, :on 980130,missed Surveillance of Containment Penetration Overcurrent Protection Devices Occurred.Caused by Failure to Tag 35 Amp Breaker.Surveillance Testing for Breakers 1ELC-1 & 1ELC-3 Will Be Completed	on 980130,missed Surveillance of Containment Penetration Overcurrent Protection Devices Occurred.Caused by Failure to Tag 35 Amp Breaker.Surveillance Testing for Breakers 1ELC-1 & 1ELC-3 Will Be Completed	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)
05000311/LER-1996-007-02, :on 960716,containment Penetration Conductor Overcurrent Circuit Breakers Had Not Been Demonstrated Operable Per Ts.Caused by Failure to Assure That Info Was Incorporated Into Sr.Procedures Reviewed	on 960716,containment Penetration Conductor Overcurrent Circuit Breakers Had Not Been Demonstrated Operable Per Ts.Caused by Failure to Assure That Info Was Incorporated Into Sr.Procedures Reviewed	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)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(e)(2)(viii)
05000272/LER-1996-008-01, :on 960613,failed to Meet Tech Spec Requirement While in Mode 5 for Natural Circulation.Caused by Insufficient Technical Input for Development of Controls. Revised Operating Logs for Mode 5	on 960613,failed to Meet Tech Spec Requirement While in Mode 5 for Natural Circulation.Caused by Insufficient Technical Input for Development of Controls. Revised Operating Logs for Mode 5	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000272/LER-1996-008-02, :on 960613,failure to Meet TS Requirements While in Mode 5 for Natural Circulation Was Noted.Caused by Insufficient Technical Input for Development of Controls. Revised Plant Operating Logs for Mode 5	on 960613,failure to Meet TS Requirements While in Mode 5 for Natural Circulation Was Noted.Caused by Insufficient Technical Input for Development of Controls. Revised Plant Operating Logs for Mode 5
05000311/LER-1996-008-02, :on 960729,battery Chargers Were Declared Inoperable Due to Mfg Discrepancies.Unit 2 Battery Chargers Will Be Reworked to Design Specifications by 960915	on 960729,battery Chargers Were Declared Inoperable Due to Mfg Discrepancies.Unit 2 Battery Chargers Will Be Reworked to Design Specifications by 960915	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) 10 CFR 50.73(a)(2)
05000272/LER-1996-009-01, :on 960530,concluded Potential Common Mode Failure for 4 Kv Magne-Blast Breakers.Caused by Misalignment of Breaker Mechanism & Internals.Assessed Breaker Mechanism Misalignment for Each Breaker	on 960530,concluded Potential Common Mode Failure for 4 Kv Magne-Blast Breakers.Caused by Misalignment of Breaker Mechanism & Internals.Assessed Breaker Mechanism Misalignment for Each Breaker
05000311/LER-1996-009-02, :on 960808,determined Current Shift Schedules Deviates from License Condition 2.C(24)(a).Caused by Inadequate Review of License Requirements.Will Continue to Operate on 12-hour Schedule	on 960808,determined Current Shift Schedules Deviates from License Condition 2.C(24)(a).Caused by Inadequate Review of License Requirements.Will Continue to Operate on 12-hour Schedule	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000272/LER-1996-010-01, :on 960619,identified Pressurizer Relief Tank Hydrodynamic Loads Had Not Previously Been Considered in Support Design.Caused by Failure to Consider Hydrodynamic Loads Caused by Water Discharge.Supports Revised	on 960619,identified Pressurizer Relief Tank Hydrodynamic Loads Had Not Previously Been Considered in Support Design.Caused by Failure to Consider Hydrodynamic Loads Caused by Water Discharge.Supports Revised	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000272/LER-1996-010, Forwards LER 96-010-00 Re Inadequate Pressurizer Relief Tank Supports.Attachment a Represents Commitment Made to NRC	Forwards LER 96-010-00 Re Inadequate Pressurizer Relief Tank Supports.Attachment a Represents Commitment Made to NRC
05000311/LER-1996-010-02, :on 960819,TS 4.0.5 Surveillance for Two Pressurizer Welds Was Missed Due to Insufficient Verification & Validation of Entry of Data Into Database. Exam of Pressurizer Spray Nozzle Was Completed	on 960819,TS 4.0.5 Surveillance for Two Pressurizer Welds Was Missed Due to Insufficient Verification & Validation of Entry of Data Into Database. Exam of Pressurizer Spray Nozzle Was Completed
05000311/LER-1996-011, Forwards LER 96-011-00 Regarding Missed Surveillance for Sampling Boron Concentration of Refueling Canal as Required by Ts.Commitments Encl as Attachment a	Forwards LER 96-011-00 Regarding Missed Surveillance for Sampling Boron Concentration of Refueling Canal as Required by Ts.Commitments Encl as Attachment a
05000311/LER-1996-011-01, :on 951206,missed Surveillance for Sampling Baron Concentration of Refueling Canal as Required by TS Occurred.Caused by Inadequate Implementation of Tech Specs Requirements.Procedure Revised	on 951206,missed Surveillance for Sampling Baron Concentration of Refueling Canal as Required by TS Occurred.Caused by Inadequate Implementation of Tech Specs Requirements.Procedure Revised	10 CFR 50.73(a)(2)(i)
05000272/LER-1996-011-02, :on 960620,pressurizer Safety Relief Valves Were Found Outside of TS Tolerance.Caused by Minor Testing Instrument Error.Valves Were Refurbished & Successfully Retested to within TS Tolerance	on 960620,pressurizer Safety Relief Valves Were Found Outside of TS Tolerance.Caused by Minor Testing Instrument Error.Valves Were Refurbished & Successfully Retested to within TS Tolerance	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)
05000311/LER-1996-012-02, :on 961005,two Potential Transformer Fuses Opened While Performing an Electrical Test of 21 Svc Water Pump.Cause Unknown.Work Practices for Specialized Electrical Testing Will Be Reviewed for Adequacy	on 961005,two Potential Transformer Fuses Opened While Performing an Electrical Test of 21 Svc Water Pump.Cause Unknown.Work Practices for Specialized Electrical Testing Will Be Reviewed for Adequacy	10 CFR 50.73(a)(2)(iv), System Actuation
05000272/LER-1996-012-01, :on 960723,potential Loss of Residual Capability Identified.Caused by Inadequate Valve Design.Rhr Flow Control Valves Replaced	on 960723,potential Loss of Residual Capability Identified.Caused by Inadequate Valve Design.Rhr Flow Control Valves Replaced	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000272/LER-1996-013-01, :on 960711,scaling Error of Over Temperature Delta Temp Resulted in Inoperable Protection Channels.Cause Under Investigation.Scaling Calculations Revised	on 960711,scaling Error of Over Temperature Delta Temp Resulted in Inoperable Protection Channels.Cause Under Investigation.Scaling Calculations Revised	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000272/LER-1996-013, :on 960711,concluded That Current Gain & Bias Settings Had Rendered Overtemperature Delta Temp Protection Channels Inoperable.Caused by Scaling Error.Licensee Will Revise Scaling Calculations.With	on 960711,concluded That Current Gain & Bias Settings Had Rendered Overtemperature Delta Temp Protection Channels Inoperable.Caused by Scaling Error.Licensee Will Revise Scaling Calculations.With	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000311/LER-1996-013-02, :on 961010,surveillance for Performing Tritium Grab Samples When Refueling Canal Is Flooded Was Missed. Caused by Inadequate Implementation of TS Requirements. Corrective Actions Include Procedure Revs	on 961010,surveillance for Performing Tritium Grab Samples When Refueling Canal Is Flooded Was Missed. Caused by Inadequate Implementation of TS Requirements. Corrective Actions Include Procedure Revs	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000272/LER-1996-014-02, :on 960717,potential Hydrogen Embrittlement on 4kV Breaker Parts Identified.Caused by Cracked Roll Pin,Due to Lack of Knowledge of Plating Induced Hydrogen Embrittlement.Cause Evaluation Being Conducted	on 960717,potential Hydrogen Embrittlement on 4kV Breaker Parts Identified.Caused by Cracked Roll Pin,Due to Lack of Knowledge of Plating Induced Hydrogen Embrittlement.Cause Evaluation Being Conducted	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000311/LER-1996-014-03, :on 961201,EDG Automatic Start Resulted in ESF Actuation.Caused by Defective anti-pump Relay in 23 Csd Vital Infeed Breaker.Defective anti-pump Relay Identified	on 961201,EDG Automatic Start Resulted in ESF Actuation.Caused by Defective anti-pump Relay in 23 Csd Vital Infeed Breaker.Defective anti-pump Relay Identified	10 CFR 50.73(a)(2)(iv), System Actuation
05000272/LER-1996-014, Corrected LER 96-014-00:on 960717,potential Hydrogen Embrittlement on 4kV Breaker Parts Identified.Root Cause Investigation Being Conducted.All NLI Refurbished Breakers Removed Except 2B4D from Vital Loads	Corrected LER 96-014-00:on 960717,potential Hydrogen Embrittlement on 4kV Breaker Parts Identified.Root Cause Investigation Being Conducted.All NLI Refurbished Breakers Removed Except 2B4D from Vital Loads	10 CFR 50.73(a)(2)(viii)
05000272/LER-1996-015-01, :on 960722,inadequate Cfcu Heat Removal Capability Identified.Caused by Failure to Effectively Chlorinate Service Water.Cfcu Monitoring Program Developed & Procedures & Training Revised	on 960722,inadequate Cfcu Heat Removal Capability Identified.Caused by Failure to Effectively Chlorinate Service Water.Cfcu Monitoring Program Developed & Procedures & Training Revised	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)
05000311/LER-1996-015-02, :on 961219,breach of Containment Closure During Core Reload Occurred.Caused by Inadequate Inplementation of Outage Scheduling & Risk Management Requirements.Containment Closure Was Reestablished Using Alternate Isolation Poi	on 961219,breach of Containment Closure During Core Reload Occurred.Caused by Inadequate Inplementation of Outage Scheduling & Risk Management Requirements.Containment Closure Was Reestablished Using Alternate Isolation Points	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000311/LER-1996-015, Forwards LER 96-015-00,documenting Event That Occurred at Salem Generating Station,Unit 2 on 961219.Commitments Made within Ltr,Listed	Forwards LER 96-015-00,documenting Event That Occurred at Salem Generating Station,Unit 2 on 961219.Commitments Made within Ltr,Listed	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000311/LER-1996-016-02, :on 961220,missed Surveillance for Determining Response Time of High Containment Gaseous Radioactivity ESF Actuation Occurred.Caused by Inadequate Implementation of TS Requirements.Procedures Will Be Revised	on 961220,missed Surveillance for Determining Response Time of High Containment Gaseous Radioactivity ESF Actuation Occurred.Caused by Inadequate Implementation of TS Requirements.Procedures Will Be Revised	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000272/LER-1996-016-01, :on 960719,missed Surveillance for RHR Pump Dynamic Head Prior to Entering Mode 4.Caused by Inadequate Procedural Control for Verification of Change Requirements	on 960719,missed Surveillance for RHR Pump Dynamic Head Prior to Entering Mode 4.Caused by Inadequate Procedural Control for Verification of Change Requirements	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)
05000272/LER-1996-017-01, :on 960725,surveillance Was Missed for Plant Vent.Caused by Personnel Error.Lco Compensatory Action Was Immediately Completed Upon Discovery of Missed TS Requirement	on 960725,surveillance Was Missed for Plant Vent.Caused by Personnel Error.Lco Compensatory Action Was Immediately Completed Upon Discovery of Missed TS Requirement	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)
05000272/LER-1996-018-01, :on 960719,potential Performance Impact on ECCS Identified Involving non-safety Related Refueling Water Storage Tank Piping.Caused by Design Discrepancy.Design Reviewed & Revised	on 960719,potential Performance Impact on ECCS Identified Involving non-safety Related Refueling Water Storage Tank Piping.Caused by Design Discrepancy.Design Reviewed & Revised
05000272/LER-1996-019-01, :on 960729,misclassification of Blow Down Sample Valves Noted.Caused by Flawed Engineering Evaluation. Review of Other Salem Piping Penetrations Performed	on 960729,misclassification of Blow Down Sample Valves Noted.Caused by Flawed Engineering Evaluation. Review of Other Salem Piping Penetrations Performed	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)(ii)(A), Seriously Degraded 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)
05000311/LER-1996-020, Provides Notification of Change in Commitment Implementation Schedule Re Potential for Thermal Overpressurization of Containment Fan Coil Unit Piping Per LER 96-020	Provides Notification of Change in Commitment Implementation Schedule Re Potential for Thermal Overpressurization of Containment Fan Coil Unit Piping Per LER 96-020
05000272/LER-1996-020-01, :on 960820,containment Fan Coil Units Were Outside Plant Design Basis.Caused by Failure of Plant Design Change to Update Plant Design Basis.Mod to Provide Overpressure Protection Will Be Implemented	on 960820,containment Fan Coil Units Were Outside Plant Design Basis.Caused by Failure of Plant Design Change to Update Plant Design Basis.Mod to Provide Overpressure Protection Will Be Implemented	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
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