05000354/LER-1996-025, Forwards LER 96-025-00.Commitments Listed Including Work Order Initiated to Install Recording Instrumentation to Determine Actual Line Dynamics During Next RCIC warm-up

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Forwards LER 96-025-00.Commitments Listed Including Work Order Initiated to Install Recording Instrumentation to Determine Actual Line Dynamics During Next RCIC warm-up
Person / Time
ML20135F397
Site:	Hope Creek
Issue date:	12/06/1996
From:	Bezilla M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20135F400	List: 05000354/LER-1996-025, Forwards LER 96-025-00.Commitments Listed Including Work Order Initiated to Install Recording Instrumentation to Determine Actual Line Dynamics During Next RCIC warm-up 05000354/LER-1996-025-01, :on 961107,during warm-up of RCIC Sys Automatic Isolation Signal Received from High Steam Flow Signal.Caused by Spurious Steam Line Pressure &/Or Steam Line Flow Signals.Rcic Isolation Signal Reset & Work Order Initiated
References
LR-N96408, NUDOCS 9612130028
Download: ML20135F397 (2)
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LER-1996-025, Forwards LER 96-025-00.Commitments Listed Including Work Order Initiated to Install Recording Instrumentation to Determine Actual Line Dynamics During Next RCIC warm-up

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv), System Actuation
3541996025R00 - NRC Website
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text

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"*O psgG Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 l

Nuclear Business Unit DEC 061996 I

LR-N96408' 1

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 I

i

Dear Sir:

HOPE CREEK GENERATING STATION DOCKET NO. 50-354 I

UNIT NO. 1 LICENSEE EVENT REPORT NO. 96-025-00 i

This Licensee Event Report entitled, " Engineered Safety Feature Actuation - Reactor Core Isolation Cooling System Isolation," is i

being submitted pursuant to the requirements of l

10CFR50.73 (a) (2) (iv).

i Sincerely, g?ll p '

Mark Bezilla General Manager -

Hope Creek Operations l

l t

Attachment i

JPP SORC Mtg.96-111 l

C Distribution LER File

\\N 6y 4

120085 9612130028 961206 PDR ADOCK 05000354, S

PDR Thepwerisinyourfunds.

95-2168 HEV 694

.. _, _ -.... _ _ _ _ _. _. _ _ _.... _ _... _. _ _ _.. _ _.. ~. _.. _. _. _ _. _.. - _.. _. _ _ _ _ _ _

e.

DEC 061996 Attachment A i

The following items represent commitments that Public Service Electric.& Gas (PSE&G)- made to the Nitclear Regulatory Commission (NRC) relative to this LER (354/96-025-00).

The commitments are

.as-follows:

l A work order (961126200) has been initiated to install l

recording instrumentation to determine actual line dynamics 1

during the next RCIC warm-up.

This work is scheduled to be completed during the next forced / planned cold shutdown of l

the plant.

A plan will be developed to perform a RCIC system walkdown to evaluate the adequacy of the flow venturi installation.

This plan will be completed by February 28, 1997.

This t

walkdown will be completed no later than the next refueling i

outage.

i l

L i

1 i

1 s

f i

3 l

i i

=

Licensee Event Report

70 | 71 | 72 | 73 | 74 | 75 | 76 | 77 | 78 | 79 | 80 | 81 | 82 | 83 | 84 | 85 | 86 | 87 | 88 | 89 |

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
05000354/LER-1996-001-03, :on 960113,safety & Turbine Acs HXs Fouled W/Grass Due to Failed Service Water Strainer.Caused by Detritus Overloading.Strainer Replaced & Maint & Design Mods Enhanced	on 960113,safety & Turbine Acs HXs Fouled W/Grass Due to Failed Service Water Strainer.Caused by Detritus Overloading.Strainer Replaced & Maint & Design Mods Enhanced	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)
05000354/LER-1996-001, :on 960113,safety & Turbine Acs Heat Exchangers Fouled W/Detritus Occurred Due to Failed Svc Water Strainer. Strainers Replaced & Enhanced Maint & Design Mod	on 960113,safety & Turbine Acs Heat Exchangers Fouled W/Detritus Occurred Due to Failed Svc Water Strainer. Strainers Replaced & Enhanced Maint & Design Mod	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(e)(2)(x) 10 CFR 50.73(s)(2)(iv)
05000354/LER-1996-002-01, :on 960119,TS Violation Occurred Re Failure to Complete Flood Protection Actions within Required Timeframe. Caused by Malfuntioned three-way Pneumatic Supply Valve. Repaired Watertight Door	on 960119,TS Violation Occurred Re Failure to Complete Flood Protection Actions within Required Timeframe. Caused by Malfuntioned three-way Pneumatic Supply Valve. Repaired Watertight Door	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 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(1)
05000354/LER-1996-003, :on 960214,failure to Perform Rcics Surveillances Condition Prohibited by Ts.Caused by Inadequate Review & Testing of Procedures.Surveillance Procedure Revised & Testing of Subject Valves	on 960214,failure to Perform Rcics Surveillances Condition Prohibited by Ts.Caused by Inadequate Review & Testing of Procedures.Surveillance Procedure Revised & Testing of Subject 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)(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)(1)
05000354/LER-1996-004, :on 960229,discovered Required IST Surveillances for D Safety Auxiliaries Cooling Sys Pump & B Station Svc Water Pump Not Performed.Caused by Less than Adequate Oversight.Instruction Provided	on 960229,discovered Required IST Surveillances for D Safety Auxiliaries Cooling Sys Pump & B Station Svc Water Pump Not Performed.Caused by Less than Adequate Oversight.Instruction Provided	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)
05000354/LER-1996-005, :on 960130,inadequate Surveillance Testing for RHR Suppression Pool & Spray Modes Occurred.Caused by Lack of Rigorous Application of Engineering Priciples.Ts Surveillance Requirements Revised	on 960130,inadequate Surveillance Testing for RHR Suppression Pool & Spray Modes Occurred.Caused by Lack of Rigorous Application of Engineering Priciples.Ts Surveillance Requirements Revised	10 CFR 50.73(a)(2)(i)
05000354/LER-1996-006, :on 920120,side Backdraft Isolation Dampers Installed Backwards.Caused by Construction Error.Restored Backdraft Isolation Dampers to Design Configuration	on 920120,side Backdraft Isolation Dampers Installed Backwards.Caused by Construction Error.Restored Backdraft Isolation Dampers to Design Configuration	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(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)
05000354/LER-1996-008, :on 920510,plant Operated W/Control Rod Withdrawal Speeds Outside of Design Basis.Caused by mis-adjustment of Control Rod Drive Sys Flow Control Needle Valves.Rods Properly Set within UFSAR Limits	on 920510,plant Operated W/Control Rod Withdrawal Speeds Outside of Design Basis.Caused by mis-adjustment of Control Rod Drive Sys Flow Control Needle Valves.Rods Properly Set within UFSAR Limits	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000354/LER-1996-009, :on 960317,determined That Plant Operating in Unanalyzed Condition Due to Inappropriate Sws/Safety Auxiliary Cooling Sys Throttle Valve Settings.Repositioned Valves & Revised Appropriate Procedures	on 960317,determined That Plant Operating in Unanalyzed Condition Due to Inappropriate Sws/Safety Auxiliary Cooling Sys Throttle Valve Settings.Repositioned Valves & Revised Appropriate Procedures	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000354/LER-1996-010, :on 960319,automatic Isolation Signal Received from High Steam Flow Signal.Caused by Deficient RCIC warm-up Procedure.Isolation Signal re-set,warm-up Completed & RCIC Sys Returned to svc.Warm-up Procedure Revised	on 960319,automatic Isolation Signal Received from High Steam Flow Signal.Caused by Deficient RCIC warm-up Procedure.Isolation Signal re-set,warm-up Completed & RCIC Sys Returned to svc.Warm-up Procedure 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)(B), Prohibited by Technical Specifications 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)
05000354/LER-1996-011, :on 960320,HPCIS Failed Surveillance & ADS Declared Inoperable Resulting in Entry Into TS 3.0.3.Caused by Personnel Error.Procedures Revised & Personnel Trained	on 960320,HPCIS Failed Surveillance & ADS Declared Inoperable Resulting in Entry Into TS 3.0.3.Caused by Personnel Error.Procedures Revised & Personnel Trained	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)
05000354/LER-1996-012, :on 960320,missed Offgas Sample Resulting in Condition Prohibited by Ts.Caused by Defective Needle Luer Lock Adapter.Needle Luer Lock Adapter on Backup Sample Apparatus Replaced	on 960320,missed Offgas Sample Resulting in Condition Prohibited by Ts.Caused by Defective Needle Luer Lock Adapter.Needle Luer Lock Adapter on Backup Sample Apparatus 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)(i)(B), Prohibited by Technical Specifications 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)
05000354/LER-1996-013, :on 960406,ESFA Occurred Due to Isolation of MSL Drain Inboard Isolation Valve.Replaced & Tested Circuit Board	on 960406,ESFA Occurred Due to Isolation of MSL Drain Inboard Isolation Valve.Replaced & Tested Circuit Board	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 10 CFR 50.73(a)(2)(viii)
05000354/LER-1996-014, :on 960416,nonconservative Safety Limit Min Critical Power Ratio Calculation Methodology Error Discovered.Caused by Inadequate Design Assumptions.Interim Controls Placed on MCPR	on 960416,nonconservative Safety Limit Min Critical Power Ratio Calculation Methodology Error Discovered.Caused by Inadequate Design Assumptions.Interim Controls Placed on MCPR	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000354/LER-1996-015, :on 960410,potential to Operate in Unanalyzed Condition Occurred.Caused by Original Design Calculation Deficiency.Appropriate Maximum UHS Temp Will Be re-evaluated	on 960410,potential to Operate in Unanalyzed Condition Occurred.Caused by Original Design Calculation Deficiency.Appropriate Maximum UHS Temp Will Be re-evaluated	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000354/LER-1996-016, :on 960427,unplanned High Pressure Coolant Injection Sys Inoperability Due to Blown Fuse & Trip Unit Card Failure.Caused by Shorted Capacitor.Trip Unit Card & Fuse Were Replaced	on 960427,unplanned High Pressure Coolant Injection Sys Inoperability Due to Blown Fuse & Trip Unit Card Failure.Caused by Shorted Capacitor.Trip Unit Card & Fuse Were 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)(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)
05000354/LER-1996-017, :on 960505,failed to Perform Electrical Distribution Sys line-up.Caused by Personnel Error.Personnel Issues Addressed & Repaired Temp Control Valves for a and D Emergency Diesel Generator	on 960505,failed to Perform Electrical Distribution Sys line-up.Caused by Personnel Error.Personnel Issues Addressed & Repaired Temp Control Valves for a and D Emergency Diesel Generator	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 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000354/LER-1996-018, :on 960522,failed to Test Control Room Emergency Filtration Sys.Caused by Inadequate Review & Approval of Surveillance Activities.Revised Surveillance Procedures	on 960522,failed to Test Control Room Emergency Filtration Sys.Caused by Inadequate Review & Approval of Surveillance Activities.Revised Surveillance Procedures	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 10 CFR 50.73(a)(2)
05000354/LER-1996-019, :on 960614,LPCI Has Not Been Appropriately Tested as Specified in TS SR 4.5.1.c.1.Caused by Ineffective Reviews of Procedures That Implement TS Requirements. Procedures Implementing TS Sr,Will Be Reviewed	on 960614,LPCI Has Not Been Appropriately Tested as Specified in TS SR 4.5.1.c.1.Caused by Ineffective Reviews of Procedures That Implement TS Requirements. Procedures Implementing TS Sr,Will Be 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000354/LER-1996-020, :on 960719,south Plant Vent Radioactive Gaseous Effluent Monitor Declared Inoperable.Caused by Failure to Perform Actions for Inoperable Instrumentation.Frequency of Grab Samples Flow Estimations Increased	on 960719,south Plant Vent Radioactive Gaseous Effluent Monitor Declared Inoperable.Caused by Failure to Perform Actions for Inoperable Instrumentation.Frequency of Grab Samples Flow Estimations Increased	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000354/LER-1996-021-01, :on 961020,operation in Condition Prohibited by TS Due to Failure to Adequately Perform Standby Liquid Control Sys Surveillances.Temporary Log Was Established to Record Actual Tank Temperature	on 961020,operation in Condition Prohibited by TS Due to Failure to Adequately Perform Standby Liquid Control Sys Surveillances.Temporary Log Was Established to Record Actual Tank Temperature	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000354/LER-1996-022-02, Forwards LER 96-022-02,documenting Event That Occurred at Hope Creek Generating Station,Unit 1.Util Commitments Made within Ltr,Listed	Forwards LER 96-022-02,documenting Event That Occurred at Hope Creek Generating Station,Unit 1.Util Commitments Made within Ltr,Listed	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000354/LER-1996-022, :on 960816,identified Condition That Could Have Prevented Removal of RHR safety-auxiliaries Cooling Sys for Deficiencies.Caused by Procedure Changes Made W/O Adequate Review.Established Administrative Controls	on 960816,identified Condition That Could Have Prevented Removal of RHR safety-auxiliaries Cooling Sys for Deficiencies.Caused by Procedure Changes Made W/O Adequate Review.Established Administrative Controls	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 10 CFR 50.73(a)(2)(viii)
05000354/LER-1996-023, :on 960821,RCIC Sys Isolation Occurred Due to Failed Steam Leak Detection Monitor.Failure Drawer Was Replaced & RCIC Sys Was Returned	on 960821,RCIC Sys Isolation Occurred Due to Failed Steam Leak Detection Monitor.Failure Drawer Was Replaced & RCIC Sys Was Returned	10 CFR 50.73(a)(2)(iv), System Actuation
05000354/LER-1996-024-01, :on 961029,two Redundant Vacuum Breakers on a Station Svc Water Sys Loop Were Tested & Found Inoperable Due to Accumulation of Deposits on Internal Moving Parts. Both Vacuum Breakers on a Station,Repaired	on 961029,two Redundant Vacuum Breakers on a Station Svc Water Sys Loop Were Tested & Found Inoperable Due to Accumulation of Deposits on Internal Moving Parts. Both Vacuum Breakers on a Station,Repaired	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 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)
05000354/LER-1996-025-01, :on 961107,during warm-up of RCIC Sys Automatic Isolation Signal Received from High Steam Flow Signal.Caused by Spurious Steam Line Pressure &/Or Steam Line Flow Signals.Rcic Isolation Signal Reset & Work Order Initiated	on 961107,during warm-up of RCIC Sys Automatic Isolation Signal Received from High Steam Flow Signal.Caused by Spurious Steam Line Pressure &/Or Steam Line Flow Signals.Rcic Isolation Signal Reset & Work Order Initiated	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000354/LER-1996-025, Forwards LER 96-025-00.Commitments Listed Including Work Order Initiated to Install Recording Instrumentation to Determine Actual Line Dynamics During Next RCIC warm-up	Forwards LER 96-025-00.Commitments Listed Including Work Order Initiated to Install Recording Instrumentation to Determine Actual Line Dynamics During Next RCIC warm-up	10 CFR 50.73(a)(2)(iv), System Actuation
05000354/LER-1996-026-01, :on 961108,ESF Actuation/Single Rod Scram Occurred Due to Stuck Scram Solenoid Pilot.Sspv Replaced & CR 42-07 Returned to Svc	on 961108,ESF Actuation/Single Rod Scram Occurred Due to Stuck Scram Solenoid Pilot.Sspv Replaced & CR 42-07 Returned to Svc	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 50.73(a)(2)
05000354/LER-1996-027-01, :on 961202,ESF Actuation & Unplanned Automatic Start of Safety Auxiliaries Cooling Sys Pump a Occurred Due to Personnel Error.Nco Involved in Event Counseled	on 961202,ESF Actuation & Unplanned Automatic Start of Safety Auxiliaries Cooling Sys Pump a Occurred Due to Personnel Error.Nco Involved in Event Counseled	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)
05000354/LER-1996-028-01, :on 961220,potential Loss of Containment Integrity Occurred Due to Water Hammer in Drywell Cooler Piping.Administrative Controls Were Implemented to Prevent Defeating of Drywell Cooler Isolation Interlocks	on 961220,potential Loss of Containment Integrity Occurred Due to Water Hammer in Drywell Cooler Piping.Administrative Controls Were Implemented to Prevent Defeating of Drywell Cooler Isolation Interlocks	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)
05000354/LER-1996-028, Forwards LER 96-028-00,submitted Pursuant to Requirements of 10CFR50.73(a)(2)(v).Commitments Listed	Forwards LER 96-028-00,submitted Pursuant to Requirements of 10CFR50.73(a)(2)(v).Commitments Listed	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000354/LER-1996-029-01, :on 961228,unplanned Reactor Core Isolation Cooling Sys Inoperability Occurred Due to Stuck Governor Valve.Valve Stem Was Replaced & RCIC Sys Was Returned to Service on 961230	on 961228,unplanned Reactor Core Isolation Cooling Sys Inoperability Occurred Due to Stuck Governor Valve.Valve Stem Was Replaced & RCIC Sys Was Returned to Service on 961230	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000354/LER-1996-030-01, :on 961230,uplanned HPCI Sys Inoperability Occurred Due to Stuck Open Extended Containment Boundary Valve.Repaired Check Valve & HPCI Sys Restored	on 961230,uplanned HPCI Sys Inoperability Occurred Due to Stuck Open Extended Containment Boundary Valve.Repaired Check Valve & HPCI Sys Restored	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)
05000354/LER-1996-030, Submits List of Commitments Re Unplanned HPCI Sys Inoperability Due to Stuck Open Extended Containment Boundary Valve in LER 96-030-00	Submits List of Commitments Re Unplanned HPCI Sys Inoperability Due to Stuck Open Extended Containment Boundary Valve in LER 96-030-00	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000354/LER-1996-033, :on 951114,two Events Occurred Due to Identification of TS Surveillance Test Inadequacy.Caused by Ineffective Procedures.Tssip Review Will Be Completed	on 951114,two Events Occurred Due to Identification of TS Surveillance Test Inadequacy.Caused by Ineffective Procedures.Tssip Review Will Be Completed	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 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)

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