05000361/LER-1996-005-01, Forwards Revised LER 96-005-01 Which Discusses Occurrence Involving Environmental Qualification of Containment High Range Radiation Monitors

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Forwards Revised LER 96-005-01 Which Discusses Occurrence Involving Environmental Qualification of Containment High Range Radiation Monitors
Person / Time
ML20147D620
Site:	San Onofre
Issue date:	02/07/1997
From:	Krieger R SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20147D610	List: 05000361/LER-1996-005-01, Forwards Revised LER 96-005-01 Which Discusses Occurrence Involving Environmental Qualification of Containment High Range Radiation Monitors ML20147D635
References
NUDOCS 9702130099
Download: ML20147D620 (1)
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LER-1996-005, Forwards Revised LER 96-005-01 Which Discusses Occurrence Involving Environmental Qualification of Containment High Range Radiation Monitors

Event date:
Report date:
3611996005R01 - NRC Website
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text

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[M ~ SOUTHERN CAllioRNIA -

R. W. Krieger Vice President EDISO i j

Nuclear Generation

. An tDISON INTLRM110ML Company i

i l

February 7,1997 i

i U. S. Nuclear Regulatory Commission Document Control Desk Washington, D, C. 20555 l

l

Subject:

Docket Nos. 50-361 and 50-362 Revised 30 Day Report Licensee Event Report No. 96-005-01

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San Onofre Nuclear Generating Station, Units 2 and 3 i

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This submittal provides a revised Licensee Event Report (LER) for an occurrence involving the environmental qualifican on of containment high range radiation monitors. Because this

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occurrence involves simiiar systems, cause, and corrective actions applicable to Units 2 and 3, a

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single report is being submitted in accordance with NUREG-1022. Neither the health nor the j

safety of plant personnel or the public was affected by this occurrence.

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Sincerely,

/

Wf c

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Enclosure: LER No.96-005 L

l cc:

L. J. Callan, Regional Administrator, NRC Region IV f

T. P. Gwynn, Director of Reactor Safety, NRC Region IV l

K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV J. A. Sloan, NRC Senior Resident Inspector, San Onofre Units 2 & 3 l

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

I l

P.O.Ika 128 l

San Clemente. CA 92674 4

714 3 S 6255 fax 714 3S6183 j

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
05000362/LER-1996-001, :on 960304,voltage Signal Actuation Loss Due to Inadvertent Relay Trip.Enhanced Turbine Startup Sequence by Slowing (from 2.5 Seconds to 8 Seconds) Operation of Trip/ Throttle Valve	on 960304,voltage Signal Actuation Loss Due to Inadvertent Relay Trip.Enhanced Turbine Startup Sequence by Slowing (from 2.5 Seconds to 8 Seconds) Operation of Trip/ Throttle Valve	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)(B) 10 CFR 50.73(a)(2)(1)
05000361/LER-1996-001-02, :on 960205,waste Gas Sys H Monitor Was Declared Inoperable.Caused by Blown Fuse.Replaced Blown Fused & Performed Channel Calibr	on 960205,waste Gas Sys H Monitor Was Declared Inoperable.Caused by Blown Fuse.Replaced Blown Fused & Performed Channel Calibr
05000362/LER-1996-001-01, Forwards Supplemental LER 96-001-01,providing Addl Info on Safety Significance of Occurrence Involving Inadvertent ESFs Actuation	Forwards Supplemental LER 96-001-01,providing Addl Info on Safety Significance of Occurrence Involving Inadvertent ESFs Actuation
05000361/LER-1996-002, :on 960209,potential Decalibration of Logarithmic Power Level Instrumentation Discovered.Caused by Calibr Error.Reanalysis Underway Considering All Factors Effecting Calibr	on 960209,potential Decalibration of Logarithmic Power Level Instrumentation Discovered.Caused by Calibr Error.Reanalysis Underway Considering All Factors Effecting Calibr	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)
05000362/LER-1996-002-02, :on 960514,pressurizer Safety Valves Found to Be Above Tech Spec Setpoint.Caused by Setpoint Drift.Valves Disassembled,Inspected,Reassembled & Reset to Proper Setpoint	on 960514,pressurizer Safety Valves Found to Be Above Tech Spec Setpoint.Caused by Setpoint Drift.Valves Disassembled,Inspected,Reassembled & Reset to Proper Setpoint	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) 10 CFR 50.73(c)(2)(viii)(A)
05000361/LER-1996-003, :on 960212,identified Computer Data Error. Caused by Inattention to Detail.C/A:Colss Computer Restarted W/Correct Date	on 960212,identified Computer Data Error. Caused by Inattention to Detail.C/A:Colss Computer Restarted W/Correct Date	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)
05000362/LER-1996-003-02, :on 960803,delinquent I Sample Analysis Noted Following 15% Power Change in 1 H Period.Caused by Lack of Direct CR Indication to Confirm Compliance W/Ts Requirement. RCS Sample I Analysis Completed	on 960803,delinquent I Sample Analysis Noted Following 15% Power Change in 1 H Period.Caused by Lack of Direct CR Indication to Confirm Compliance W/Ts Requirement. RCS Sample I Analysis Completed	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) 10 CFR 50.73(a)(2)(1)
05000362/LER-1996-004-01, :on 960919,RCS Pressure Boundary Leakage Occurred.Caused by Thermowell Broken Off Inside RCS Pipe. Util Restored Broken Thermowell for Design Configuration	on 960919,RCS Pressure Boundary Leakage Occurred.Caused by Thermowell Broken Off Inside RCS Pipe. Util Restored Broken Thermowell for Design Configuration	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)(B) 10 CFR 50.73(a)(2)(1)
05000361/LER-1996-004, :on 960411,AF Sys Turbine Drive Pump Relatch Occurred.Caused by EFAS Signal Present.Appropriate Procedures Revised	on 960411,AF Sys Turbine Drive Pump Relatch Occurred.Caused by EFAS Signal Present.Appropriate 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)(viii)(A) 10 CFR 50.73(e)(2)
05000361/LER-1996-005-01, Forwards Revised LER 96-005-01 Which Discusses Occurrence Involving Environmental Qualification of Containment High Range Radiation Monitors	Forwards Revised LER 96-005-01 Which Discusses Occurrence Involving Environmental Qualification of Containment High Range Radiation Monitors
05000362/LER-1996-005-01, :on 960928,reactor Head Vent Valve Discovered Mispostioned.Caused by Incorrect Completion of RCS post-fill Valve Alignment Procedure.Util Confirmed Review of Records That Head Vent Valve Closed	on 960928,reactor Head Vent Valve Discovered Mispostioned.Caused by Incorrect Completion of RCS post-fill Valve Alignment Procedure.Util Confirmed Review of Records That Head Vent Valve Closed	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) 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-1996-006, :on 960826,NRC Inspector Observed Local Voltage Meter for Vital Bus Inverter Y003 Indicating 122.5 Volt Ac. Caused by Util Not Providing Quantitative Operability Info. Occurrence Will Be Reviewed	on 960826,NRC Inspector Observed Local Voltage Meter for Vital Bus Inverter Y003 Indicating 122.5 Volt Ac. Caused by Util Not Providing Quantitative Operability Info. Occurrence Will Be Reviewed	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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000362/LER-1996-006-01, :on 961025,CPIS Actuated W/Unit 3 in Mode 1 at Full Power.Caused by Radiation Increase Inside Due to Small Pressurizer Vapor Space Leak.Tsip Revising Cpis Actuation Setpoint Installed on 961101	on 961025,CPIS Actuated W/Unit 3 in Mode 1 at Full Power.Caused by Radiation Increase Inside Due to Small Pressurizer Vapor Space Leak.Tsip Revising Cpis Actuation Setpoint Installed on 961101	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)(1)
05000361/LER-1996-008, :on 960926,RCP Lube Oil Collection Sys Sightglass & Mounting Extended Slightly Beyond Lateral Limits of Oil Collection Sys Drain Pan,Resulting in Leaking Oil Outside Sys.Cause Under Investigation	on 960926,RCP Lube Oil Collection Sys Sightglass & Mounting Extended Slightly Beyond Lateral Limits of Oil Collection Sys Drain Pan,Resulting in Leaking Oil Outside Sys.Cause Under Investigation	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)(B) 10 CFR 50.73(a)(2)(1)
05000361/LER-1996-009, :on 961216,surveillance Testing of EDG non-critical Trip Bypasses Occurred.Caused by Inadequate Nov 1983 Test Procedure.Procedure Will Be Revised	on 961216,surveillance Testing of EDG non-critical Trip Bypasses Occurred.Caused by Inadequate Nov 1983 Test Procedure.Procedure Will Be Revised	10 CFR 50.73(a)(2)(i)
05000361/LER-1996-010, :on 961210,containment Escape Hatch Not Closed While Performing Core Alterations.Caused by Failure to Recognize That Opening Emergency Escape Hatch Doors Would Cause Pevs to Be Open.Event Reviewed W/Staff	on 961210,containment Escape Hatch Not Closed While Performing Core Alterations.Caused by Failure to Recognize That Opening Emergency Escape Hatch Doors Would Cause Pevs to Be Open.Event Reviewed W/Staff	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)(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-1996-011, :on 961216,air Operated Containment Isolation Valve Declared Inoperable.Caused by Two Separate Errors Could Have Caused Valve 2HVO513 to Have Insufficient Closing Force.Edison Will Reset & Retest Valve 2HV0513	on 961216,air Operated Containment Isolation Valve Declared Inoperable.Caused by Two Separate Errors Could Have Caused Valve 2HVO513 to Have Insufficient Closing Force.Edison Will Reset & Retest Valve 2HV0513	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-1996-012, :on 960229,discovered That CST Was Outside Design Basis.Cause Under Investigation.Compensatory Measures Were Put in Place to Administratively Increase Tanks Water Volume & to Procedularize Operator Actions	on 960229,discovered That CST Was Outside Design Basis.Cause Under Investigation.Compensatory Measures Were Put in Place to Administratively Increase Tanks Water Volume & to Procedularize Operator Actions	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)

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