05000382/LER-1998-001, Forwards LER 98-001-00,providing Details of TS 3.0.3 Condition Experienced During Plant Malfunction When LCO Section 3.1.2.4 Was Not Met

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Forwards LER 98-001-00,providing Details of TS 3.0.3 Condition Experienced During Plant Malfunction When LCO Section 3.1.2.4 Was Not Met
Person / Time
ML20248L348
Site:	Waterford
Issue date:	03/16/1998
From:	Ewing E ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20248L350	List: 05000382/LER-1998-001, Forwards LER 98-001-00,providing Details of TS 3.0.3 Condition Experienced During Plant Malfunction When LCO Section 3.1.2.4 Was Not Met 05000382/LER-1998-001-01, :on 980214,TSs 3.0.3 Condition Occurred Due to Inoperable Charging Pumps.Replaced Failed SX-1 Relay
References
W3F1-98-0041, W3F1-98-41, NUDOCS 9803190392
Download: ML20248L348 (1)
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LER-1998-001, Forwards LER 98-001-00,providing Details of TS 3.0.3 Condition Experienced During Plant Malfunction When LCO Section 3.1.2.4 Was Not Met

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
3821998001R00 - NRC Website
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text

4 O

Ente perations. Inc.

Killona. LA 70066 Tel 504 739 6242 Early C. Ewing, Hi Drector Nuc ear Safety & Regulatory Affairs W3F1-98-0041 A4.05 PR March 16,1998 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38 Reporting of Licensee Event Report Gentlemen:

Attached is Licensee Event Report (LER) 98-001-00 for Waterford Steam Electric Station Unit 3. This report provides details of a Technical Specification 3.0.3 condition experienced during a plant malfunction when Limiting Condition for Operation (LCO) section 3.1.2.4 was not met. LCO section 3.1.2.4 specifies that at least two independent charging pumps shall be operable when the plant is operating in Modes 1 through 4. This LER is being submitted pursuant to 10CFR50.73(a)(2)(i)(B) and 10CFR50.36(c)(2).

Very truly yours, J

N E.C. Ewing Director' 7

Nuclear Safety & Regulatory Affairs a

ECE/RLW/ssf O

Attachment vA-

.v cc:

E.W. Merschoff (NRC Region IV), C.P. Patel (NRC-NRR),

l A.L. Garibaldi, J.T. Wheelock - INPO Records Center, J. Smith, N.S. Reynolds, NRC Resident inspectors Office, Administrator - LRPD kkk,kkk 9803190392 980316 PDR ADOCK 05000382 s

Licensee Event Report

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		Reporting criterion
05000382/LER-1998-001, Forwards LER 98-001-00,providing Details of TS 3.0.3 Condition Experienced During Plant Malfunction When LCO Section 3.1.2.4 Was Not Met	Forwards LER 98-001-00,providing Details of TS 3.0.3 Condition Experienced During Plant Malfunction When LCO Section 3.1.2.4 Was Not Met	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000382/LER-1998-001-01, :on 980214,TSs 3.0.3 Condition Occurred Due to Inoperable Charging Pumps.Replaced Failed SX-1 Relay	on 980214,TSs 3.0.3 Condition Occurred Due to Inoperable Charging Pumps.Replaced Failed SX-1 Relay	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)
05000382/LER-1998-002, :on 980215,brief Loss of Command Function in CR Occurred.Caused by Inappropriate Action (Human Error) on Part of Shift Superintendent.Ss Was Counseled IAW Corporate Discipline Policy	on 980215,brief Loss of Command Function in CR Occurred.Caused by Inappropriate Action (Human Error) on Part of Shift Superintendent.Ss Was Counseled IAW Corporate Discipline Policy	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)
05000382/LER-1998-003, :on 980302,inoperable Hydrogen Analyzers Were Noted Due to Undersized Thermal Overloads.Engineering Personnel Conducted all-hands Meetings to Discuss Management Expectations for Verifying Critical Design Inputs	on 980302,inoperable Hydrogen Analyzers Were Noted Due to Undersized Thermal Overloads.Engineering Personnel Conducted all-hands Meetings to Discuss Management Expectations for Verifying Critical Design Inputs	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)
05000382/LER-1998-004, :on 980304,TS 4.0.3 Condition - CPC Channel Functional Test,Was Concluded from Preliminary CEOG Rept. Caused by Human Error.Cpc Channels A,B & C Were Satisfactorily Tested	on 980304,TS 4.0.3 Condition - CPC Channel Functional Test,Was Concluded from Preliminary CEOG Rept. Caused by Human Error.Cpc Channels A,B & C Were Satisfactorily Tested	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000382/LER-1998-005, :on 980312,missed Thermal Overload TS Surveillance Were Noted.Caused by Inadequate Review of 1992 Rev to TS 3.8.4.2 IAW GL 91-08.Thermal Overloads for 8 MOVs Were Subsequently Tested & Determined to Be Operable	on 980312,missed Thermal Overload TS Surveillance Were Noted.Caused by Inadequate Review of 1992 Rev to TS 3.8.4.2 IAW GL 91-08.Thermal Overloads for 8 MOVs Were Subsequently Tested & Determined to Be Operable	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000382/LER-1998-006, :on 980306,increased Differential Pressure for Feedwater Isolation Valves Occurred.Caused by Failure to Consider All Pressure Source Affecting Mfivs.Admin Controls Have Been Enacted Requiring Entry Into TS 3.6.3	on 980306,increased Differential Pressure for Feedwater Isolation Valves Occurred.Caused by Failure to Consider All Pressure Source Affecting Mfivs.Admin Controls Have Been Enacted Requiring Entry Into TS 3.6.3	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)
05000382/LER-1998-007, :on 980317,discovered That No Allowance for Instrument Loop Uncertainity Included in Surveillance for Chilled Water Outlet Temp.Caused by Failure to Consider Instrument Loop Uncertainty.Revised Task	on 980317,discovered That No Allowance for Instrument Loop Uncertainity Included in Surveillance for Chilled Water Outlet Temp.Caused by Failure to Consider Instrument Loop Uncertainty.Revised Task	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)
05000382/LER-1998-008-01, Forwards LER 98-008-01,updating Info Re Potential for Concurrent Reduced Cooling Capacity in Both Trains of Ecw Sys.Revs Are Annotated W/Vertical Change Bars in right-hand Margin	Forwards LER 98-008-01,updating Info Re Potential for Concurrent Reduced Cooling Capacity in Both Trains of Ecw Sys.Revs Are Annotated W/Vertical Change Bars in right-hand Margin
05000382/LER-1998-008, :on 980414,potential Concurrent Degraded Ecw Sys Trains a & B Was Noted.Cause Was Indeterminate. Affected Circuits Have Been Corrected (within Design Parameters) to Address Condition	on 980414,potential Concurrent Degraded Ecw Sys Trains a & B Was Noted.Cause Was Indeterminate. Affected Circuits Have Been Corrected (within Design Parameters) to Address Condition	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)
05000382/LER-1998-009, :on 980415,inadvertent ESF Actuation Occurred. Caused by Inadequate Configuration Control.Restored Incorrectly Lifted Lead to Terminal Point & Made Maint Personnel Aware of Drawing Discrepancy	on 980415,inadvertent ESF Actuation Occurred. Caused by Inadequate Configuration Control.Restored Incorrectly Lifted Lead to Terminal Point & Made Maint Personnel Aware of Drawing Discrepancy	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)
05000382/LER-1998-010, :on 980514,potential Overpressurization of N Sys Was Noted.Caused by Inadequate Design.N Sys Lineup Changed to Allow for Addl Overpressure Protection Through Alternate Existing ASME Section Viii Relief Valve	on 980514,potential Overpressurization of N Sys Was Noted.Caused by Inadequate Design.N Sys Lineup Changed to Allow for Addl Overpressure Protection Through Alternate Existing ASME Section Viii Relief Valve	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000382/LER-1998-011, :on 980603,TS 3.0.3 Entry Was Noted.Caused by Component Cooling Water Makeup Check Valve Failing Ist. Operability of a Train of CCW Was Restored Immediately & Check Valve Internals Were Replaced	on 980603,TS 3.0.3 Entry Was Noted.Caused by Component Cooling Water Makeup Check Valve Failing Ist. Operability of a Train of CCW Was Restored Immediately & Check Valve Internals Were Replaced	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)
05000382/LER-1998-012, :on 980609,TS Channel Check for TS Surveillance 4.3.1.1 Was Missed.Caused by Human Error.Involved Employees Were Counseled & All Licensed Operators Were Apprised of Event	on 980609,TS Channel Check for TS Surveillance 4.3.1.1 Was Missed.Caused by Human Error.Involved Employees Were Counseled & All Licensed Operators Were Apprised of Event	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)
05000382/LER-1998-013, :on 980701,IST Valve Surveillances Were Missed. Caused by Inadequate Processing of Info Transferred Between Operations Procedure Group & Programs Engineering.Procedure Revised	on 980701,IST Valve Surveillances Were Missed. Caused by Inadequate Processing of Info Transferred Between Operations Procedure Group & Programs Engineering.Procedure Revised	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)(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)
05000382/LER-1998-014, :on 980716,manual Reactor Trip W/Subsequent EFAS Actuation Occurred.Caused by Short Circuit in FW Pump Turbine a Speed Control Relay.Plant Mgt Established Significant Event Response Team	on 980716,manual Reactor Trip W/Subsequent EFAS Actuation Occurred.Caused by Short Circuit in FW Pump Turbine a Speed Control Relay.Plant Mgt Established Significant Event Response Team	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)
05000382/LER-1998-015, :on 980724,discovered That T-ring Rubber Seat on CR Normal Outside Air Intake Downstream Isolation Valve Was Incorrectly Installed.Caused by Inadequate Info in Vendor Manual.Reworked Valves to Correct Configuration	on 980724,discovered That T-ring Rubber Seat on CR Normal Outside Air Intake Downstream Isolation Valve Was Incorrectly Installed.Caused by Inadequate Info in Vendor Manual.Reworked Valves to Correct Configuration	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000382/LER-1998-016, :on 980730,failed to Meet TS Requirements for for RT Bypasses.Cause Not Determined Because of Age of condition.1E-4% Bistables for All for Channels of Excore Log Power Channels Were Declared Inoperable 980730	on 980730,failed to Meet TS Requirements for for RT Bypasses.Cause Not Determined Because of Age of condition.1E-4% Bistables for All for Channels of Excore Log Power Channels Were Declared Inoperable 980730	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)
05000382/LER-1998-017, :on 980803,calculated Peak Clad Temp Exceeded 10CFR50.46 Criteria.Caused by Energy Redistributed Factor Error.Incorporated 0.2kw/ft Penalty for Plhgr Into Colss,Per Wa 01162252	on 980803,calculated Peak Clad Temp Exceeded 10CFR50.46 Criteria.Caused by Energy Redistributed Factor Error.Incorporated 0.2kw/ft Penalty for Plhgr Into Colss,Per Wa 01162252	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000382/LER-1998-018, :on 980901,TS 3.0.3 Was Entered,As Bldg Ventilation Valve Train a & B Inoperable Simultaneously. Caused by Electricians Performing Maint on Wrong Component. Panel Debriefing Held with Involved Personnel	on 980901,TS 3.0.3 Was Entered,As Bldg Ventilation Valve Train a & B Inoperable Simultaneously. Caused by Electricians Performing Maint on Wrong Component. Panel Debriefing Held with Involved Personnel	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)
05000382/LER-1998-019-01, Forwards LER 98-019-01,IAW 10CFR50.73(a)(2)(ii). LER 98-019-00,discussed.Refs to Feedwater Valves Have Been Deleted in Revised LER	Forwards LER 98-019-01,IAW 10CFR50.73(a)(2)(ii). LER 98-019-00,discussed.Refs to Feedwater Valves Have Been Deleted in Revised LER	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000382/LER-1998-019, :on 980920,failure of Containment Isolation Valves to Close During Testing Was Noted.Caused by Solenoid Failures.Solenoids Were Replaced & Valves Were Retested Successfully	on 980920,failure of Containment Isolation Valves to Close During Testing Was Noted.Caused by Solenoid Failures.Solenoids Were Replaced & Valves Were Retested Successfully	10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000382/LER-1998-020, :on 981204,determined That Certain Core Power Distribution SRs Had Been Incorrectly Scheduled.Caused by TS Change Implementation Error.Will Perform Final Review of TS SRs with 4.0.4 Exemption.With	on 981204,determined That Certain Core Power Distribution SRs Had Been Incorrectly Scheduled.Caused by TS Change Implementation Error.Will Perform Final Review of TS SRs with 4.0.4 Exemption.With	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)
05000382/LER-1998-021, :on 981210,boron Concentration Below TS Limit in SIT 2B,occurred.Caused by Lack of Complete Understanding of Cumulative Effects of Sys Design.B Concentration in SIT 2B Was Returned to within TS Required Concentrations	on 981210,boron Concentration Below TS Limit in SIT 2B,occurred.Caused by Lack of Complete Understanding of Cumulative Effects of Sys Design.B Concentration in SIT 2B Was Returned to within TS Required Concentrations	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)

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