05000362/LER-1995-001, Forwards LER 95-001 for Discovery of Minor RCS Pressure Boundary Weepage Which Occurred During Cycle 7 Operation. Neither Public Health Nor Safety of Plant Personnel or Public Affected by Occurrence

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Forwards LER 95-001 for Discovery of Minor RCS Pressure Boundary Weepage Which Occurred During Cycle 7 Operation. Neither Public Health Nor Safety of Plant Personnel or Public Affected by Occurrence
Person / Time
ML20091L632
Site:	San Onofre
Issue date:	08/23/1995
From:	Krieger R SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20091L637	List: 05000362/LER-1995-001, Forwards LER 95-001 for Discovery of Minor RCS Pressure Boundary Weepage Which Occurred During Cycle 7 Operation. Neither Public Health Nor Safety of Plant Personnel or Public Affected by Occurrence 05000362/LER-1995-001-01, :on 950722,discovered That RCS Pressure Boundary Weepage Occurred During Cycle 7 Operation Due to PWSCC of Alloy 600 Type Matls.Accessible Exterior of Two RCS Hot Leg Nozzles Will Be Replaced W/Alloy 690 Nozzles
References
NUDOCS 9508290261
Download: ML20091L632 (1)
v • d • e

LER-1995-001, Forwards LER 95-001 for Discovery of Minor RCS Pressure Boundary Weepage Which Occurred During Cycle 7 Operation. Neither Public Health Nor Safety of Plant Personnel or Public Affected by Occurrence

Event date:
Report date:
3621995001R00 - NRC Website
v • d • e

text

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/~ 2 Southem Callkwnla Edison Company P. O. SOM 128 I

SAN CLEMENTE, CALWORNIA 92674 0128 R. W. MRIEGE R T E L E,MO.*E

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August 23, 1995

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U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

Docket No. 50-362 30 Day Report t

Licensee Event Report No.95-001 San Onofre Nuclear Generating Station, Unit 3 This submittal provides a written Licensee Event Report (LER) for the discovery of minor reactor coolant system pressure boundary weepage which had occurred iluring cycle 7 operation.

Neither the

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public health nor the safet'7 of plant personnel or the public was i

affected by this occurrence.

Sincerely, l

[h]l/

>$W "

Enclosure:

LER No.95-001 3

cc:

L. J. Callan, Regional Administrator, NRC Region IV J. E. Dyer, Director, Division of Reactor Projects, NRC l

Region IV K. E.

Perkins, Jr.,

Director, Walnut Creek Field Office, NRC i

Region IV J. A. Sloan, NRC Senior Resident Inspector, San Onofre Units f

2& 3 M. B.

Fields, NRC Project Manager, San Onofre. Units 2 and 3 Institute of Nuclear-Power Operations (INPO) l P

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+, v s 9508290261 950923 I

PDR ADOCK 05000362

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Licensee Event Report

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		Reporting criterion
05000361/LER-1995-001, :on 950116,two Firewatch Contractors Were Involved in Physical Altercation.Caused by Firewatch Union Accounting/Financial Matter.No Firewatch Postings Were Missed	on 950116,two Firewatch Contractors Were Involved in Physical Altercation.Caused by Firewatch Union Accounting/Financial Matter.No Firewatch Postings Were Missed	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000362/LER-1995-001-01, :on 950722,discovered That RCS Pressure Boundary Weepage Occurred During Cycle 7 Operation Due to PWSCC of Alloy 600 Type Matls.Accessible Exterior of Two RCS Hot Leg Nozzles Will Be Replaced W/Alloy 690 Nozzles	on 950722,discovered That RCS Pressure Boundary Weepage Occurred During Cycle 7 Operation Due to PWSCC of Alloy 600 Type Matls.Accessible Exterior of Two RCS Hot Leg Nozzles Will Be Replaced W/Alloy 690 Nozzles	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) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000362/LER-1995-001, Forwards LER 95-001 for Discovery of Minor RCS Pressure Boundary Weepage Which Occurred During Cycle 7 Operation. Neither Public Health Nor Safety of Plant Personnel or Public Affected by Occurrence	Forwards LER 95-001 for Discovery of Minor RCS Pressure Boundary Weepage Which Occurred During Cycle 7 Operation. Neither Public Health Nor Safety of Plant Personnel or Public Affected by Occurrence
05000362/LER-1995-002-01, :on 950826,noticed Open Vent Valve on AFW Line for SG E089 While SG E089 Adv Open to Drain SG During Refueling.Caused by Incomplete Communication.Adv Closed & Core Alterations Halted	on 950826,noticed Open Vent Valve on AFW Line for SG E089 While SG E089 Adv Open to Drain SG During Refueling.Caused by Incomplete Communication.Adv Closed & Core Alterations Halted	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 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000361/LER-1995-002, :on 950211,soft Seated Mfivs,Intended for Maintenance & Insp,Found Inoperable.Caused by Personnel Error.Individuals Responsible Received Counsel & Procedures Revised	on 950211,soft Seated Mfivs,Intended for Maintenance & Insp,Found Inoperable.Caused by Personnel Error.Individuals Responsible Received Counsel & Procedures 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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000362/LER-1995-003-01, :on 950827,electrical Test Technicians Failed to Install Jumpers for EDG Output Breaker During Tests on Protective Relay on Supply Breaker to Train B Class 1E Bus. Technicians Involved Appropriately Disciplined	on 950827,electrical Test Technicians Failed to Install Jumpers for EDG Output Breaker During Tests on Protective Relay on Supply Breaker to Train B Class 1E Bus. Technicians Involved Appropriately Disciplined	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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000361/LER-1995-003, :on 950225,discovered Cracking in Rotor Discs. Caused by Stress Corrosion Cracking.Cracks Removed by Excavation	on 950225,discovered Cracking in Rotor Discs. Caused by Stress Corrosion Cracking.Cracks Removed by Excavation	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)(viii)(A) 10 CFR 50.73(a)(2)(1)
05000361/LER-1995-004, :on 941114,valve Release Weight Stuck & Did Not Drop Upon Electronic Actuation & Valve Did Not Open as Required.Replaced Incorrectly Mfg Weight Switch on 950126 & Ensured Correct Positioning	on 941114,valve Release Weight Stuck & Did Not Drop Upon Electronic Actuation & Valve Did Not Open as Required.Replaced Incorrectly Mfg Weight Switch on 950126 & Ensured Correct Positioning	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)
05000361/LER-1995-005, :on 950406,loss of Pressurizer Level Occurred Due to Valve Alignment Error.Terminated Event at 0207 When Licensee Reclosed mini-flow Isolation Valves	on 950406,loss of Pressurizer Level Occurred Due to Valve Alignment Error.Terminated Event at 0207 When Licensee Reclosed mini-flow Isolation Valves	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)
05000361/LER-1995-006, :on 950406,RCS Dissolved Oxygen Found Out of Specification.Caused by Failure to Follow Procedure.Returned Oxygen Level to Below TS Steady State Limit by Addition of Hydrazine	on 950406,RCS Dissolved Oxygen Found Out of Specification.Caused by Failure to Follow Procedure.Returned Oxygen Level to Below TS Steady State Limit by Addition of Hydrazine	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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000361/LER-1995-007, :on 950331,incorrect Rod Shadowing Factors in Core Protection Calculators Occurred.Caused by Incorrect Values Provided by ABB Ce.Revised Reload Power Ascension Procedure to Include Addl Data Verification Steps	on 950331,incorrect Rod Shadowing Factors in Core Protection Calculators Occurred.Caused by Incorrect Values Provided by ABB Ce.Revised Reload Power Ascension Procedure to Include Addl Data Verification Steps	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)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000361/LER-1995-008, :on 950412,TS 3.0.3 Entry Occurred Due to Inoperable Containment Emergency Cooling Fans.Removed Fan Immediately Upon Discovery	on 950412,TS 3.0.3 Entry Occurred Due to Inoperable Containment Emergency Cooling Fans.Removed Fan Immediately Upon Discovery	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) 10 CFR 50.73(a)(2)(1)
05000361/LER-1995-009, :on 950511,EDG Initial Step Load Should Have Been 20% Higher than 1,720 Kw.Caused by Bechtel Who Did Not Recognize That Lovs May Cause Larger EDG Initial Step Load than Lovs W/Sias.Revised Appropriate Load Circuitry	on 950511,EDG Initial Step Load Should Have Been 20% Higher than 1,720 Kw.Caused by Bechtel Who Did Not Recognize That Lovs May Cause Larger EDG Initial Step Load than Lovs W/Sias.Revised Appropriate Load Circuitry	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)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000361/LER-1995-010, :on 950530,pressurizer Safety Valve Setpoints Found to Be Out of Tolerance Due to Setpoint Drift.Util Assessing Expansion of Current TS Tolerances to Reduce Future TS Violations Caused by Setpoint Drift	on 950530,pressurizer Safety Valve Setpoints Found to Be Out of Tolerance Due to Setpoint Drift.Util Assessing Expansion of Current TS Tolerances to Reduce Future TS Violations Caused by Setpoint Drift	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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000361/LER-1995-011, :on 950605,fire Dampers Failed Due to Long Term Matl Degradation.Completed Repair & Replacement of All 54 Impaired Dampers & Svc Any Fire Damper Not Tested	on 950605,fire Dampers Failed Due to Long Term Matl Degradation.Completed Repair & Replacement of All 54 Impaired Dampers & Svc Any Fire Damper Not Tested	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)(viii) 10 CFR 50.73(a)(2)
05000361/LER-1995-012, :on 950707,Unit 2 Containment Air Lock Door Seal Test Did Not Meet Literal TS Requirements Due to Typo in Ts.Revised Containment Air Lock Seal Test Procedure to Ensure Compliance W/Literal Wording of TS for Both Units	on 950707,Unit 2 Containment Air Lock Door Seal Test Did Not Meet Literal TS Requirements Due to Typo in Ts.Revised Containment Air Lock Seal Test Procedure to Ensure Compliance W/Literal Wording of TS for Both Units	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)(1) 10 CFR 50.73(a)(2)(viii)(8)
05000361/LER-1995-013, :on 950718,recognized That Sf Handling Machine (Sfhm) Operated Over SFP on 950207 W/O Train a Post Accident Cleanup Unit (Pacu) in Operation Contrary to Ts.Required Monthly 10-h Operation for Pacu E-371 Performed	on 950718,recognized That Sf Handling Machine (Sfhm) Operated Over SFP on 950207 W/O Train a Post Accident Cleanup Unit (Pacu) in Operation Contrary to Ts.Required Monthly 10-h Operation for Pacu E-371 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)(iv), System Actuation 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)
05000361/LER-1995-014, :on 950813,TS Surveillance Was Missed Due to Lack of Alarm.Returned Control of Breaker to Automatic on 950813	on 950813,TS Surveillance Was Missed Due to Lack of Alarm.Returned Control of Breaker to Automatic on 950813	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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000361/LER-1995-015, :on 950822,determined RCS Lds Inoperable for About 31 H Due to Containment Atmosphere Particulate RMs Filter Paper Supply Roll Being Inadvertently Installed Upside Down.Paper for Monitors Corrected	on 950822,determined RCS Lds Inoperable for About 31 H Due to Containment Atmosphere Particulate RMs Filter Paper Supply Roll Being Inadvertently Installed Upside Down.Paper for Monitors Corrected	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)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000361/LER-1995-016, :on 951127,omission in High Energy Line Break Analysis Occurred.Caused by Original UFSAR Section 3.6A Hypothesized High Energy Line Break Analysis Completed by Plant.Interim Compensatory Review Initiated	on 951127,omission in High Energy Line Break Analysis Occurred.Caused by Original UFSAR Section 3.6A Hypothesized High Energy Line Break Analysis Completed by Plant.Interim Compensatory Review Initiated	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)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000361/LER-1995-017, :on 951207,toxic Gas Isolation Sys Monitor Setpoint & Propane Trip Setpoint Was Less than 193 Ppm. Because Personnel Did Not Establish Appropriate Butane Setpoint to Envelope Propane TS Limit	on 951207,toxic Gas Isolation Sys Monitor Setpoint & Propane Trip Setpoint Was Less than 193 Ppm. Because Personnel Did Not Establish Appropriate Butane Setpoint to Envelope Propane TS Limit	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)(A) 10 CFR 50.73(a)(2)(1)

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