05000461/LER-1996-016-01, Forwards LER 96-016-01:re Residual Water Covering Portion of Disc/Seat Area During Testing Due to Design Not Allowing Complete Draining Results in Invalid Local Leak Rate Testing of Feedwater Containment Isolation

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Forwards LER 96-016-01:re Residual Water Covering Portion of Disc/Seat Area During Testing Due to Design Not Allowing Complete Draining Results in Invalid Local Leak Rate Testing of Feedwater Containment Isolation
Person / Time
ML20137J857
Site:	Clinton
Issue date:	03/27/1997
From:	Connell W ILLINOIS POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20137J861	List: 05000461/LER-1996-016, :on 950402,residual Water Observed Covering Portion of Disc/Seat Area.Caused by Plant Design Not Allowing Complete Draining of FW Lines.Drain Valves Installed on Bottom of Isvs & Rev of Test Procedures 05000461/LER-1996-016-01, Forwards LER 96-016-01:re Residual Water Covering Portion of Disc/Seat Area During Testing Due to Design Not Allowing Complete Draining Results in Invalid Local Leak Rate Testing of Feedwater Containment Isolation
References
U-602717, WC-154-97, NUDOCS 9704040161
Download: ML20137J857 (1)
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LER-1996-016, Forwards LER 96-016-01:re Residual Water Covering Portion of Disc/Seat Area During Testing Due to Design Not Allowing Complete Draining Results in Invalid Local Leak Rate Testing of Feedwater Containment Isolation

Event date:
Report date:
4611996016R01 - NRC Website
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text

lilinois Power Company V

4 Clinton Power Station P.o. Box 678 Clinton.IL 61727 Tel 217 935-5623 Fax 217 935-4632 Wilfred Connell kMN h

Vice President P6WER U 602717 2C.220 WC-154-97 March 27, 1997 Docket No. 50-461 10CFR50.73 Document Control Desk Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Clinton Power Station - Unit 1 Licensee Event Report No. 96-016-01 Dear Madam or Sir; Enclosed is Licensee Event Rerart No. 96-016-01: Residual Water Coverinn Portion of Disc / Seat Area Durina Testina Due to Desian Not Allowinn Comolete

' Draining Results in Invalid Loca[ Leak Rate Testing ot'Feedwater Containment Isolation Valves The enclosed report has been revised to identify the cause of the event and corrective action, discuss the safety consequences and implications of the event, provide a discussion of similar events, and provide other clarifying information. This report is being submitted in accordance with the requirements of 10CFR50.73.

Sincerely yours, ilfred Connell Vice President RSF/krk 0 W l7 Enclosure cc:

NRC Clinton Licensing Project Manager NRC Resident Office, V-690 Regional Administrator, Region III, USNRC y

Illinois Department of Nuclear Safety J

INPO Records Center P

9704040161 970327 PDR ADOCK 05000461 lglgg gg s

Licensee Event Report

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		Reporting criterion
05000461/LER-1996-001, :on 960110,isolation of Mechanical Vacuum Pumps on Main Steam Line High Radiation Signal Occurred.Caused by Lack of Clarity of Meaning of Note in Table 3.3.2-1. Procedure Revised	on 960110,isolation of Mechanical Vacuum Pumps on Main Steam Line High Radiation Signal Occurred.Caused by Lack of Clarity of Meaning of Note in Table 3.3.2-1. Procedure 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) 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)
05000461/LER-1996-002, :on 960131,discovered HPCS Sys High Reactor Vessel Water Level seal-in & Ready to Reset Lamps.Caused by Spurious High Reactor Vessel Water Level Signal of Indeterminate origin.HPCS-1 Card Replaced	on 960131,discovered HPCS Sys High Reactor Vessel Water Level seal-in & Ready to Reset Lamps.Caused by Spurious High Reactor Vessel Water Level Signal of Indeterminate origin.HPCS-1 Card 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)(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)
05000461/LER-1996-003, :on 951118,failure of Procedure to Recognize MSL Radiation Monitor Detector Housing Tube as Secondary Cl Path Resulted in Operable Secondary Containment During Corrective Maint.Revised Procedure	on 951118,failure of Procedure to Recognize MSL Radiation Monitor Detector Housing Tube as Secondary Cl Path Resulted in Operable Secondary Containment During Corrective Maint.Revised Procedure	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)(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)
05000461/LER-1996-004, :on 960409,inadequate Job Preparation for Preventive Maint Task on Switchyard Breaker Caused MSIV Closure & Reactor Scram.Plant Procedures Revised	on 960409,inadequate Job Preparation for Preventive Maint Task on Switchyard Breaker Caused MSIV Closure & Reactor Scram.Plant Procedures 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)(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 50.73(a)(2)(viii) 10 CFR 50.73(e)(2)(ii)
05000461/LER-1996-005, :on 960411,failure to Follow Procedures During Completion of one-rod-out Interlock Test Results in Reactor Mode Switch Not Locked in Refuel During Control Rod Exercising as Required by TS	on 960411,failure to Follow Procedures During Completion of one-rod-out Interlock Test Results in Reactor Mode Switch Not Locked in Refuel During Control Rod Exercising as Required by TS	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(1)
05000461/LER-1996-006, :on 960529,degraded Control Room HVAC Train Declared Inoperable.Caused by Personnel Error.Briefed Personnel Re Event & Developed Standing Order	on 960529,degraded Control Room HVAC Train Declared Inoperable.Caused by Personnel Error.Briefed Personnel Re Event & Developed Standing Order	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)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000461/LER-1996-007, :on 960529,discovered Inoperable Leak Detection Instruments.Caused by Personnel Error.Personnel Briefed Re Event & Labelled Both Reactor Water Cleanup Sys HX Rooms Ceiling Plugs	on 960529,discovered Inoperable Leak Detection Instruments.Caused by Personnel Error.Personnel Briefed Re Event & Labelled Both Reactor Water Cleanup Sys HX Rooms Ceiling Plugs	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) 10 CFR 50.73(a)(2)(1)
05000461/LER-1996-009, :on 960808,inadequate Procedure Leads to Failure to Properly Implement TS Surveillance.Caused Appears to Be Misinterpretation of Ts.Cps Procedure 9065.02 Performed at Frequency Required by TS	on 960808,inadequate Procedure Leads to Failure to Properly Implement TS Surveillance.Caused Appears to Be Misinterpretation of Ts.Cps Procedure 9065.02 Performed at Frequency Required by TS	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) 10 CFR 50.73(a)(2)(1)
05000461/LER-1996-010-01, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Even	Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events
05000461/LER-1996-011, :on 961002,EDG Surveillance Test Procedures Written to Satisfy TS (SR) 3.8.1.7, 3.8.1.12 & 3.8.1.19 Were Inadequate.Caused by Lack of Guidance in Surveillance Procedure.Procedures Revised	on 961002,EDG Surveillance Test Procedures Written to Satisfy TS (SR) 3.8.1.7, 3.8.1.12 & 3.8.1.19 Were Inadequate.Caused by Lack of Guidance in Surveillance Procedure.Procedures 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)(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) 10 CFR 50.73(a)(2)(1)
05000461/LER-1996-012, :on 910316,failed to Demonstrate Operability of Offsite Power Sources within One Hr During Surveillance While Div 3 EDG Governor Speed Droop Control Set to 50% Due to Inadequate Procedures.Revised Procedures	on 910316,failed to Demonstrate Operability of Offsite Power Sources within One Hr During Surveillance While Div 3 EDG Governor Speed Droop Control Set to 50% Due to Inadequate Procedures.Revised Procedures	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) 10 CFR 50.73(a)(2)(1)
05000461/LER-1996-013-01, Forwards LER 96-013-01 Re Inadequate Actuator Design & Failure to Recognize Limitations of Resilient Seat Design Result in Local Leak Rate Test Feedwater Containment Isolation Valves	Forwards LER 96-013-01 Re Inadequate Actuator Design & Failure to Recognize Limitations of Resilient Seat Design Result in Local Leak Rate Test Feedwater Containment Isolation Valves
05000461/LER-1996-013, :on 961015,inadequate Actuator Design Occurred. Caused by Svc Conditions Experienced & Inherently Stringent Leakage Criteria.Procedure Revised	on 961015,inadequate Actuator Design Occurred. Caused by Svc Conditions Experienced & Inherently Stringent Leakage Criteria.Procedure 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)(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
05000461/LER-1996-014-01, Forwards LER 96-014-01,containing Cause for Event & Corrective Actions to Prevent Recurrence Re Inadequately Tested Auxiliary Bldg Roof Plug.Commitments,Listed	Forwards LER 96-014-01,containing Cause for Event & Corrective Actions to Prevent Recurrence Re Inadequately Tested Auxiliary Bldg Roof Plug.Commitments,Listed
05000461/LER-1996-015-02, Forwards LER 96-015-02 Re Lack of Attention to Detail During Procedure Performance.Ler Has Been Revised to Remove Contributing Cause of Event & Corrective Action Associated W/Contributing Cause	Forwards LER 96-015-02 Re Lack of Attention to Detail During Procedure Performance.Ler Has Been Revised to Remove Contributing Cause of Event & Corrective Action Associated W/Contributing Cause
05000461/LER-1996-016-01, Forwards LER 96-016-01:re Residual Water Covering Portion of Disc/Seat Area During Testing Due to Design Not Allowing Complete Draining Results in Invalid Local Leak Rate Testing of Feedwater Containment Isolation	Forwards LER 96-016-01:re Residual Water Covering Portion of Disc/Seat Area During Testing Due to Design Not Allowing Complete Draining Results in Invalid Local Leak Rate Testing of Feedwater Containment Isolation
05000461/LER-1996-016, :on 950402,residual Water Observed Covering Portion of Disc/Seat Area.Caused by Plant Design Not Allowing Complete Draining of FW Lines.Drain Valves Installed on Bottom of Isvs & Rev of Test Procedures	on 950402,residual Water Observed Covering Portion of Disc/Seat Area.Caused by Plant Design Not Allowing Complete Draining of FW Lines.Drain Valves Installed on Bottom of Isvs & Rev of Test Procedures	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(c)(2)(v)
05000461/LER-1996-017, :on 961102,div 3 DG Failed to Energize Emergency Bus within Required Time Limit.Caused by Personnel Misinterpretation of Setpoint Data.Added Note to Drawing to Clearly Show Setpoint	on 961102,div 3 DG Failed to Energize Emergency Bus within Required Time Limit.Caused by Personnel Misinterpretation of Setpoint Data.Added Note to Drawing to Clearly Show Setpoint	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 50.72(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)
05000461/LER-1996-018, :on 961014,incorrect Torque Value for Control Rod Drive Hydraulic Control Units Was Specified by Supplier. Caused by Lack of Attention to Detail.All Hold Down Bolts on CRD HCUs Were Replaced	on 961014,incorrect Torque Value for Control Rod Drive Hydraulic Control Units Was Specified by Supplier. Caused by Lack of Attention to Detail.All Hold Down Bolts on CRD HCUs Were Replaced	10 CFR 50.73(a)(2)(v), Loss of Safety Function 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 21.21(b)(3)
05000461/LER-1996-019, :on 961120,inadequate Surveillance Procedures Were Noted Due to Misinterpretation of TS Bases Results in Source Range Monitor Reactor Period Display Not Verified. Procedures CPS 9031.13 Will Be Revised	on 961120,inadequate Surveillance Procedures Were Noted Due to Misinterpretation of TS Bases Results in Source Range Monitor Reactor Period Display Not Verified. Procedures CPS 9031.13 Will Be 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)(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) 10 CFR 50.73(a)(2)(1)
05000461/LER-1996-020, :on 961223,failure of CR Drive Hydraulic Control Unit Air Line Occurred Due to Overtightening Fitting During Maintenance to Correct Air Leak.Broken Air Line Was Replaced in Accordance with Mwr D61669	on 961223,failure of CR Drive Hydraulic Control Unit Air Line Occurred Due to Overtightening Fitting During Maintenance to Correct Air Leak.Broken Air Line Was Replaced in Accordance with Mwr D61669	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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