05000361/LER-1997-001-01, Forwards Ltr Provided LER 97-001-01 for Occurences Involving Surveillance Testing & Implementation of New Standard TSs Re San Onofre Nuclear Generating Station,Units 2 & 3

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Forwards Ltr Provided LER 97-001-01 for Occurences Involving Surveillance Testing & Implementation of New Standard TSs Re San Onofre Nuclear Generating Station,Units 2 & 3
Person / Time
ML20147E453
Site:	San Onofre
Issue date:	03/03/1997
From:	Krieger R SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20147E459	List: 05000361/LER-1997-001-01, Forwards Ltr Provided LER 97-001-01 for Occurences Involving Surveillance Testing & Implementation of New Standard TSs Re San Onofre Nuclear Generating Station,Units 2 & 3
References
RTR-NUREG-1022 NUDOCS 9703110128
Download: ML20147E453 (1)
v • d • e

LER-1997-001, Forwards Ltr Provided LER 97-001-01 for Occurences Involving Surveillance Testing & Implementation of New Standard TSs Re San Onofre Nuclear Generating Station,Units 2 & 3

Event date:
Report date:
3611997001R01 - NRC Website
v • d • e

text

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bhfqj EDISON Z TA L.

,50VIHERN CALIF ORNIA R. W. Krieger An EDISONJN1EIL% ail 0NAL Cumpans i

March 3, 1997 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.

20555

Subject:

Docket Nos. 50-361 and 50-362 30-Day Report Licensee Event Report No.97-001, Revision 1 San Onofre Nuclear Generating Station, Units 2 and 3

Reference:

Letter, R. W. Krieger (Edison) to USNRC Document Control Oesk, dated February 4, 1997 The referenced letter provided Licensee Event Report (LER) No.97-001 for occurrences involving surveillance testing and implementation of new standard Technical Specifications.

Edison is submitting the enclosed supplemental LER to report two additional occurrences.

Because these occurrences involve similar systems, causes, and corrective actions applicable to Units 2 and 3, a l

single report for Unit 2 is being submitted in accordance with NUREG-1022.

Neither the health nar the safety of plant personnel or the public was affected by this occurrence or condition.

If you require any additional information, please so advise.

Sincerely,

)

?/

,/

WM O

Enclosure:

LER No. 97-001-01 cc:

J. E. Dyer, Acting Regional Administrator, Region IV K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV J. A. Sloan, NRC Senior Resident Inspector, Units 2 and 3 M. B. Fields, NRC Project Manager, San Onofre Units 2 and 3 Institute of Nuclear Power Operations (INP0) 9703110128 970303 1

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San Cienwme, CA 92674 0128 714-368-6255

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Licensee Event Report

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		Reporting criterion
05000361/LER-1997-001-01, Forwards Ltr Provided LER 97-001-01 for Occurences Involving Surveillance Testing & Implementation of New Standard TSs Re San Onofre Nuclear Generating Station,Units 2 & 3	Forwards Ltr Provided LER 97-001-01 for Occurences Involving Surveillance Testing & Implementation of New Standard TSs Re San Onofre Nuclear Generating Station,Units 2 & 3
05000206/LER-1997-001-02, Forwards LER 97-001-02 Re Missed Testing/Insp of Security Sys.Util Has Noted That Counselling of Individual Was Inadvertently Not Completed & LER Is Being Revised, Accordingly	Forwards LER 97-001-02 Re Missed Testing/Insp of Security Sys.Util Has Noted That Counselling of Individual Was Inadvertently Not Completed & LER Is Being Revised, Accordingly
05000206/LER-1997-001, :on 970107,missed Security Test/Insp Occurred. Caused by Cognitive Personnel Error.Individual Involved Counseled & Security Testing/Insp Tracking Process Enhanced	on 970107,missed Security Test/Insp Occurred. Caused by Cognitive Personnel Error.Individual Involved Counseled & Security Testing/Insp Tracking Process Enhanced	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)
05000362/LER-1997-001-02, :on 970412,four Out of Five RCS Nozzles Leaked During Plant Operation & Fifth Suspected of Leaking.Caused by Crack Through Nozzle in Heat Affected Zone of Partial Penetration Weld.Completed Required Welding	on 970412,four Out of Five RCS Nozzles Leaked During Plant Operation & Fifth Suspected of Leaking.Caused by Crack Through Nozzle in Heat Affected Zone of Partial Penetration Weld.Completed Required Welding	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1)
05000206/LER-1997-002-02, :on 971027,discovered That Single Copy of Security Contingency Plan Was Missing.Cause Indeterminate. Revised LER Will Be Submitted by 971219 to Provide Results of Investigation	on 971027,discovered That Single Copy of Security Contingency Plan Was Missing.Cause Indeterminate. Revised LER Will Be Submitted by 971219 to Provide Results of Investigation	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(iii)
05000361/LER-1997-002, :on 970128,increase in Pressurizer Level Occurred Due to Valve Alignment Error.Npeo Was Temporarily Removed from Duties & Counseled by Mgt	on 970128,increase in Pressurizer Level Occurred Due to Valve Alignment Error.Npeo Was Temporarily Removed from Duties & Counseled by Mgt	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-1997-002-01, :on 970703,RCS Leakage Occurred in Instrument Thermowell Nozzles.Caused by Primary Water Stress Corrosion Cracking of Alloy 600 Type Matls.Replaced Outer Half of Nozzles W/Inconel 690 Matl	on 970703,RCS Leakage Occurred in Instrument Thermowell Nozzles.Caused by Primary Water Stress Corrosion Cracking of Alloy 600 Type Matls.Replaced Outer Half of Nozzles W/Inconel 690 Matl	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)(1)
05000362/LER-1997-002, Forwards LER 97-002-00 Re Occurrence Involving RCS Pressure Boundary Leakage,Per 10CFR50.73(d)	Forwards LER 97-002-00 Re Occurrence Involving RCS Pressure Boundary Leakage,Per 10CFR50.73(d)
05000206/LER-1997-002, Forwards LER 97-002-00 Re Loss of Single Copy of Security Contingency Plan.Revised LER Will Be Submitted by 971219 After Investigation Into Cause & Development of Corrective Actions	Forwards LER 97-002-00 Re Loss of Single Copy of Security Contingency Plan.Revised LER Will Be Submitted by 971219 After Investigation Into Cause & Development of Corrective Actions
05000206/LER-1997-003-01, :on 970520,SCE Discovered Security Computer Sys Was Out of Svc.Caused by Unit 1 Permanently Shutdown,Unit 2 at 100% Full Power & Unit 3 Shutdown.Computer Sys Was Restored	on 970520,SCE Discovered Security Computer Sys Was Out of Svc.Caused by Unit 1 Permanently Shutdown,Unit 2 at 100% Full Power & Unit 3 Shutdown.Computer Sys Was Restored
05000362/LER-1997-003-01, Forwards LER 97-003-01 Re Out of Tolerance Condition Identified During Testing of Pressurizer Safety Valve Setpoints.Ler Contains No New Commitments	Forwards LER 97-003-01 Re Out of Tolerance Condition Identified During Testing of Pressurizer Safety Valve Setpoints.Ler Contains No New Commitments
05000362/LER-1997-003-02, :on 971218,determined That Pressurizer Safety Valve Setpoints Were Out of Tolerance.Caused by Setpoint Drift.Valves Will Be Disassembled,Inspected,Reassembled & Reset by Proper Personnel	on 971218,determined That Pressurizer Safety Valve Setpoints Were Out of Tolerance.Caused by Setpoint Drift.Valves Will Be Disassembled,Inspected,Reassembled & Reset by Proper Personnel	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) 10 CFR 50.73(a)(2)(1)
05000361/LER-1997-003, :on 970225,out of Tolerance Condition Identified During Testing of Pressurizer Safety Valve Setpoints.Caused by Setpoints Drift.Setpoints Bounded by Analysis	on 970225,out of Tolerance Condition Identified During Testing of Pressurizer Safety Valve Setpoints.Caused by Setpoints Drift.Setpoints Bounded by Analysis	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 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) 10 CFR 50.73(a)(2)(1)
05000206/LER-1997-003, Forwards LER 97-003,providing 30-day follow-up Rept Required by 10CFR73.71(d) for Security Computer Sys Being Inoperable for Few Minutes	Forwards LER 97-003,providing 30-day follow-up Rept Required by 10CFR73.71(d) for Security Computer Sys Being Inoperable for Few Minutes
05000361/LER-1997-004, :on 970303,discovered Steam Leakage from Reactor Coolant Sys Pressurizer Thermowell.Caused by Primary Water Stress Corrosion Cracking of Alloy 600 Type Materials. Removed & Replaced Nozzle W/Inconel 690	on 970303,discovered Steam Leakage from Reactor Coolant Sys Pressurizer Thermowell.Caused by Primary Water Stress Corrosion Cracking of Alloy 600 Type Materials. Removed & Replaced Nozzle W/Inconel 690
05000362/LER-1997-004, Forwards LER 97-004-00 for Occurrence Involving Typo in Ts. Health & Safety of Public or Plant Personnel Was Not Affected	Forwards LER 97-004-00 for Occurrence Involving Typo in Ts. Health & Safety of Public or Plant Personnel Was Not Affected
05000362/LER-1997-004-01, :on 971205,typo in TS Was Found.Caused by Personnel Error.Tendon Surveillance Procedure Correctly Referenced Tendon 88-154 & Not 38-154	on 971205,typo in TS Was Found.Caused by Personnel Error.Tendon Surveillance Procedure Correctly Referenced Tendon 88-154 & Not 38-154	10 CFR 50.73(a)(2)(1)
05000361/LER-1997-005, :on 970319,determined That RCS Leakage Was Through Body of Valve Packing Leakoff Plug Caused by Defect. Defective Plug Confirmed to Be Free of Similar Defects, Removed Head & Ground Smooth	on 970319,determined That RCS Leakage Was Through Body of Valve Packing Leakoff Plug Caused by Defect. Defective Plug Confirmed to Be Free of Similar Defects, Removed Head & Ground Smooth
05000361/LER-1997-006, :on 970319,NRC Noted Some Utils Had Not Been Fully Complying W/Requirements of TS Re Surveillance Testing of Electronic Circuits,Per GL 96-01.Specific Cause of Omission Not Known.Procedures Revised	on 970319,NRC Noted Some Utils Had Not Been Fully Complying W/Requirements of TS Re Surveillance Testing of Electronic Circuits,Per GL 96-01.Specific Cause of Omission Not Known.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)(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)(viii)(B)
05000361/LER-1997-007-01, Forwards LER 97-007-01,reporting Occurrence Involving Incomplete Surveillance Testing of Radiation Monitors. Neither Health Nor Safety of Plant Personnel or Public Affected by Occurrence	Forwards LER 97-007-01,reporting Occurrence Involving Incomplete Surveillance Testing of Radiation Monitors. Neither Health Nor Safety of Plant Personnel or Public Affected by Occurrence
05000361/LER-1997-007, :on 970403,incomplete Surveillance Testing of Radiation Monitors Occurred.Caused by Cognitive Personnel Error.Procedures Corrected	on 970403,incomplete Surveillance Testing of Radiation Monitors Occurred.Caused by Cognitive Personnel Error.Procedures Corrected	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1)
05000361/LER-1997-008, :on 970304,TS Surveillance of Pressurizer Cooldown Rate Was Missed Because Operator Did Not Recognize That real-time Evaluation Plant Data Was Required.Cooldown Transient Terminated	on 970304,TS Surveillance of Pressurizer Cooldown Rate Was Missed Because Operator Did Not Recognize That real-time Evaluation Plant Data Was Required.Cooldown Transient Terminated	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)
05000361/LER-1997-009, :on 970509,class IE 125 Vdc Battery Surveillance Testing Was Completed on 3 Replaced Batteries, Indicating Apparent Drop in Capacity of Two.Caused by No Requirement to Test.Revised TS Bases	on 970509,class IE 125 Vdc Battery Surveillance Testing Was Completed on 3 Replaced Batteries, Indicating Apparent Drop in Capacity of Two.Caused by No Requirement to Test.Revised TS Bases	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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000361/LER-1997-010-01, Forwards LER 97-010-01 for Check Valve in Charging Subsystem Which Failed to Open Completely.Single Rept for Unit 2 Is Being Submitted as Condition Involved Same System,Cause & Corrective Actions Applicable to Units 2 & 3	Forwards LER 97-010-01 for Check Valve in Charging Subsystem Which Failed to Open Completely.Single Rept for Unit 2 Is Being Submitted as Condition Involved Same System,Cause & Corrective Actions Applicable to Units 2 & 3
05000361/LER-1997-011-01, Forwards LER 97-011-01,reporting Occurrence Involving Use of Wrong Boron Sample for Determination of Reactor Shutdown Margin,Per NUREG-1022	Forwards LER 97-011-01,reporting Occurrence Involving Use of Wrong Boron Sample for Determination of Reactor Shutdown Margin,Per NUREG-1022
05000361/LER-1997-012, :on 970814,discovered Design Inadequacy in Backup N Supply to CCW Surge Tanks.Caused by Cognitive Personnel Error.Plant Personnel Immediately Took Compensatory Action to Restore Sys Operability	on 970814,discovered Design Inadequacy in Backup N Supply to CCW Surge Tanks.Caused by Cognitive Personnel Error.Plant Personnel Immediately Took Compensatory Action to Restore Sys Operability	10 CFR 50.73(c)(2)(1)
05000361/LER-1997-013, :on 971010,charcoal Filter Surveillance Testing Was Not Current.Caused by Cognitive Personnel Error.No Irradiated Fuel Has Been Moved in Either Fuel Bldg Since 970522.Filters Will Be Replaced Before Fuel Is Next Moved	on 971010,charcoal Filter Surveillance Testing Was Not Current.Caused by Cognitive Personnel Error.No Irradiated Fuel Has Been Moved in Either Fuel Bldg Since 970522.Filters Will Be Replaced Before Fuel Is Next Moved	10 CFR 50.73(a)(2)(1)
05000361/LER-1997-014, :on 971020,licensed Operators Did Not Have Corrective Lenses for Use W/Full Face Respirators.Cause Due to Util Not Establishing Administrative Controls for Special Lens Inserts.Improved Associated Procedures	on 971020,licensed Operators Did Not Have Corrective Lenses for Use W/Full Face Respirators.Cause Due to Util Not Establishing Administrative Controls for Special Lens Inserts.Improved Associated Procedures	10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(2)(viii)(3)
05000361/LER-1997-015, :on 971117,inadequate Surveillance Testing of Charging Pump Relay Contacts Noted.Caused by Inadequate Surveillance Test Procedure.Subject K108 Subgroup Relay Contacts Tested Satisfactorily & Procedures Revised	on 971117,inadequate Surveillance Testing of Charging Pump Relay Contacts Noted.Caused by Inadequate Surveillance Test Procedure.Subject K108 Subgroup Relay Contacts Tested Satisfactorily & Procedures Revised	10 CFR 50.73(a)(2)(1)
05000361/LER-1997-016, :on 971202,SONGS Personnel Recognized That Fire Damper SARW504165001FD Was Not in Licensee Controlled Specification Surveillance Procedure.Caused by Cognitive Personnel Error.Occurrence Reviewed W/Appropriate Personnel	on 971202,SONGS Personnel Recognized That Fire Damper SARW504165001FD Was Not in Licensee Controlled Specification Surveillance Procedure.Caused by Cognitive Personnel Error.Occurrence Reviewed W/Appropriate Personnel	10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000361/LER-1997-017, :on 971216,STAs Were Questioned Re Respirator Qualifications & Requirements Re Corrective Lense Wearers. Cause Not Determined.Util Has Requalified & Certified All STAs for Respirator Use	on 971216,STAs Were Questioned Re Respirator Qualifications & Requirements Re Corrective Lense Wearers. Cause Not Determined.Util Has Requalified & Certified All STAs for Respirator Use	10 CFR 50.73(a)(2)(1)

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