LER-1997-002, Forwards LER 97-002-00.Commitment Made:Evaluation Will Be Performed to Review Preventive Maint Frequency for MSSV & Psv Disassembly,Insp & Retesting |
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10 CFR 50.73 Virginia Electric and Power Company t
North Anna Power Station P. O. Box 402 Mineral, Virginia 23117 June 12,1997 U. S. Nuclear Regulatory Commission NAPS:MPW Document Control Desk Docket Nos. 50-338
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Washington, D.C. 20555 License Nos. NPF-4
Dear Sirs:
Pursuant to North Anna Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to i
North Anna Unit 1.
4 Report No. 50-338/97-002-00 4
This Report has been reviewed by the Station Nuclear Safety Operating Committee and will be forwarded to the Management Safety Review Committee i
for its review.
i Very truly yours, D
v W R. Matthews Station Manager
Enclosure:
Commitments contained in this report:
- 1. An evaluation will be performed to review the preventive maintenance frequency for MSSV and PSV disassembly, inspection and retesting.
cc:
U. S. Nuclear Regulatory Commission Region 11
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Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303 Mr. M. J. Morgan NRC Senior Resident inspector North Anna Power Station
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PDR
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| 05000338/LER-1997-001-03, :on 970312,auxiliary Svc Water Pump Bolts Exceeded Design Basis Allowable Due to Personnel Error. Asw Pumps Were Declared Inoperable |
- on 970312,auxiliary Svc Water Pump Bolts Exceeded Design Basis Allowable Due to Personnel Error. Asw Pumps Were Declared Inoperable
| 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)(viii) | | 05000339/LER-1997-001-02, :on 970314,reactor Vessel Level Dynamic Range Indication on a Train Declared Inoperable.Caused by Procedural Error.Revised Calibr Procedures,Normalized a & B Trains & Returned Train to Service |
- on 970314,reactor Vessel Level Dynamic Range Indication on a Train Declared Inoperable.Caused by Procedural Error.Revised Calibr Procedures,Normalized a & B Trains & Returned Train to Service
| 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)(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)(viii)
10 CFR 50.73(a)(2) | | 05000338/LER-1997-002, Forwards LER 97-002-00.Commitment Made:Evaluation Will Be Performed to Review Preventive Maint Frequency for MSSV & Psv Disassembly,Insp & Retesting | Forwards LER 97-002-00.Commitment Made:Evaluation Will Be Performed to Review Preventive Maint Frequency for MSSV & Psv Disassembly,Insp & Retesting | | | 05000338/LER-1997-002-02, :on 970515,set Pressure for One MSSV Was Found Outside Setpoint Tolerance Due to Setpoint Variance.Mssv That Failed Was Disassembled,Inspected,Repaired,Reassembled & Tested Satisfactorily |
- on 970515,set Pressure for One MSSV Was Found Outside Setpoint Tolerance Due to Setpoint Variance.Mssv That Failed Was Disassembled,Inspected,Repaired,Reassembled & Tested Satisfactorily
| 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)(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)(viii)
10 CFR 50.73(a)(2) | | 05000338/LER-1997-003-01, :on 970516,positive Reactivity Addition During Refueling Was Determined.Caused by Personnel Error.Control Room Crews Were Coached on Positive Reactivity Effect of Filling Cavity from R ST When RCS Is Greater |
- on 970516,positive Reactivity Addition During Refueling Was Determined.Caused by Personnel Error.Control Room Crews Were Coached on Positive Reactivity Effect of Filling Cavity from R ST When RCS Is Greater
| 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)(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) | | 05000338/LER-1997-004-01, :on 970524,found Hi-Hi Alarm Setpoint for 1-RM-RMS-160 Out of Tolerance Due to Personnel Error. Instrumentation & Control Supervisor Coached Dept Personnel on Importance of Self Check |
- on 970524,found Hi-Hi Alarm Setpoint for 1-RM-RMS-160 Out of Tolerance Due to Personnel Error. Instrumentation & Control Supervisor Coached Dept Personnel on Importance of Self Check
| 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)(B), Prohibited by Technical Specifications
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)(viii)
10 CFR 50.73(a)(2) | | 05000338/LER-1997-005-01, :on 970519,determined That eddy-current Testing Results Did Not Match Signatures Reported During Preservice Baseline Testing,Due to Personnel Error.Verified Current Signatures on Duplicate eddy-current Testing |
- on 970519,determined That eddy-current Testing Results Did Not Match Signatures Reported During Preservice Baseline Testing,Due to Personnel Error.Verified Current Signatures on Duplicate eddy-current Testing
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
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) | | 05000338/LER-1997-006-01, :on 970731,TS 3.0.3 Was Entered When Two Individual RPIs in Same Group Were Inoperable.Caused by Inoperable Control Rod Indicators.Review of Plant Parameters to Determine Failure Was Limited to Irpi |
- on 970731,TS 3.0.3 Was Entered When Two Individual RPIs in Same Group Were Inoperable.Caused by Inoperable Control Rod Indicators.Review of Plant Parameters to Determine Failure Was Limited to Irpi
| 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)(x)
10 CFR 50.73(a)(2) | | 05000338/LER-1997-007, :on 970818,NIS High Flux Trip Setpoint Errors Occurred.Caused by Inherent Inaccuracies Associated with Calorimetric Heat Balance at Low Power Levels.High Power Trip Setpoints Were Reduced |
- on 970818,NIS High Flux Trip Setpoint Errors Occurred.Caused by Inherent Inaccuracies Associated with Calorimetric Heat Balance at Low Power Levels.High Power Trip Setpoints Were Reduced
| 10 CFR 50.73(a)(2) | | 05000338/LER-1997-008, :on 971027,both EDGs Inoperable During Testing. Caused by TS Surveillance Requirement to Demonstrate Operability of Remaining EDG When One Inoperable.Required TS Actions Cleared Following 1J EDG Testing |
- on 971027,both EDGs Inoperable During Testing. Caused by TS Surveillance Requirement to Demonstrate Operability of Remaining EDG When One Inoperable.Required TS Actions Cleared Following 1J EDG Testing
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(viii)
10 CFR 50.73(a)(2) | | 05000338/LER-1997-009-01, :on 971118,incomplete Surveillance on Solid State Protection Circuits Was Noted.Caused by Inadequate Design by Vendor.Controlling Tps Were Revised to Include Instructions to Test Affected Logic Circuits |
- on 971118,incomplete Surveillance on Solid State Protection Circuits Was Noted.Caused by Inadequate Design by Vendor.Controlling Tps Were Revised to Include Instructions to Test Affected Logic Circuits
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(1) |
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