05000339/LER-1998-001, Forwards LER 98-001-00,reviewed by Station Nuclear Safety Operating Committee & Will Be Forwarded to Mgt Safety Review Committee for Review

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Forwards LER 98-001-00,reviewed by Station Nuclear Safety Operating Committee & Will Be Forwarded to Mgt Safety Review Committee for Review
Person / Time
ML20217M911
Site:	North Anna
Issue date:	04/30/1998
From:	Matthews W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20217M916	List: 05000339/LER-1998-001, Forwards LER 98-001-00,reviewed by Station Nuclear Safety Operating Committee & Will Be Forwarded to Mgt Safety Review Committee for Review 05000339/LER-1998-001-02, :on 980405,manual Reactor Trip Was Declared Inoperable Due to Control Bank B Group Step Counter.Caused by Malfunction of Mechanical Drive.Ts Action Statement 3.1.3.3 Initiated
References
98-221, NUDOCS 9805050164
Download: ML20217M911 (1)
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LER-1998-001, Forwards LER 98-001-00,reviewed by Station Nuclear Safety Operating Committee & Will Be Forwarded to Mgt Safety Review Committee for Review

Event date:
Report date:
3391998001R00 - NRC Website
v • d • e

text

r o.,

i 10 CFR 50.73 Virginia Electric and Power Company North Anna Power Station P. O. Box 402 Mineral, Virginia 23117 April 30,1998 U. S. Nuclear Regulatory Commission Serial No.98-221 1

Document Control Desk NAPS: GSS Washington, D.C. 20555 Docket Nos. 50-339 License Nos. NPF-7

Dear Sirs:

I i

Pursuant to North Anna Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to North Anna Unit 2.

f Report No. 50-339/98-001-00 This Report has been reviewed by the Station Nuclear Safety Operating Committee and will be forwarded to the Management Safety Review Committee for its review.

Very truly yours, 2Y l

W. R. Matthews Site Vice President Commitments contained in this document: None Enclosure; cc:

U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303

\\\\

M. J. Morgan NRC Senior Resident inspector y'

North Anna Power Station l

9905050164 900430 PDR ADOCK 05000339 S

)

Licensee Event Report

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10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | 23 | 24 | 25 |

		Reporting criterion
05000339/LER-1998-001-02, :on 980405,manual Reactor Trip Was Declared Inoperable Due to Control Bank B Group Step Counter.Caused by Malfunction of Mechanical Drive.Ts Action Statement 3.1.3.3 Initiated	on 980405,manual Reactor Trip Was Declared Inoperable Due to Control Bank B Group Step Counter.Caused by Malfunction of Mechanical Drive.Ts Action Statement 3.1.3.3 Initiated	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000339/LER-1998-001, Forwards LER 98-001-00,reviewed by Station Nuclear Safety Operating Committee & Will Be Forwarded to Mgt Safety Review Committee for Review	Forwards LER 98-001-00,reviewed by Station Nuclear Safety Operating Committee & Will Be Forwarded to Mgt Safety Review Committee for Review
05000338/LER-1998-001, :on 980108,determined That Potential to Miss Interlock Logic Surveillance Testing During Previous mid- Cycle Shutdowns Existed.Caused by Inadequate Test Design Supplied by Vendor.Info from Last Startup Reviewed	on 980108,determined That Potential to Miss Interlock Logic Surveillance Testing During Previous mid- Cycle Shutdowns Existed.Caused by Inadequate Test Design Supplied by Vendor.Info from Last Startup Reviewed	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000338/LER-1998-002-01, :on 980312,missed Surveillance on Charging Pump Undervoltage Relay Occurred.Caused by Inadequate Revisions to Periodic Test Procedures.Review of Potentially Applicable Periodic Test Was Performed	on 980312,missed Surveillance on Charging Pump Undervoltage Relay Occurred.Caused by Inadequate Revisions to Periodic Test Procedures.Review of Potentially Applicable Periodic Test Was 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)(i)(B), Prohibited by Technical Specifications 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)
05000339/LER-1998-002-02, :on 980411,average of as Found Setpoints for Three Pressurizer Safety Valves Exceeded Setpoint Tolerance Allowed by TS 3.4.3.1.Caused by Setpoint Drift.Pressurizer Safety Valves Disassembled,Inspected & Repaired	on 980411,average of as Found Setpoints for Three Pressurizer Safety Valves Exceeded Setpoint Tolerance Allowed by TS 3.4.3.1.Caused by Setpoint Drift.Pressurizer Safety Valves Disassembled,Inspected & Repaired	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)(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) 10 CFR 50.73(a)(2)(1)
05000339/LER-1998-002, Forwards LER 98-002-00,applicable to North Anna Unit 2.Rept Has Been Reviewed by Station Nuclear Safety Operating Committee & Will Be Forwarded to Mgt Safety Review Committee for Review	Forwards LER 98-002-00,applicable to North Anna Unit 2.Rept Has Been Reviewed by Station Nuclear Safety Operating Committee & Will Be Forwarded to Mgt Safety Review Committee for Review
05000338/LER-1998-003-02, :on 980804,noted That Ten Svc Water Pipe Supports Had Been Inspected During First ISI Interval.Caused by Personnel Error.Completed Changes to Insp Isometric Drawings & Changes to ISI Program	on 980804,noted That Ten Svc Water Pipe Supports Had Been Inspected During First ISI Interval.Caused by Personnel Error.Completed Changes to Insp Isometric Drawings & Changes to ISI Program	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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000339/LER-1998-003-01, :on 980424,multiple Failures Occurred During Functional Testing of RCS Large Bore Snubbers.Cause Unknown. Large Bore Snubbers Replaced.With	on 980424,multiple Failures Occurred During Functional Testing of RCS Large Bore Snubbers.Cause Unknown. Large Bore Snubbers Replaced.With	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)(iii) 10 CFR 50.73(a)(2)(viii)
05000338/LER-1998-003, :on 980804,service Water Supports Surveillance Was Missed.Caused by Personnel Error.Component Supports Were Examined & Found to Be Acceptable.With	on 980804,service Water Supports Surveillance Was Missed.Caused by Personnel Error.Component Supports Were Examined & Found to Be Acceptable.With	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)(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)
05000339/LER-1998-004, Forwards LER 98-004-00,IAW 10CFR50.73.Commitments Made by Util,Listed	Forwards LER 98-004-00,IAW 10CFR50.73.Commitments Made by Util,Listed
05000339/LER-1998-004-02, :on 980917,reactor Trip Was Noted.Caused by Lightning Strike.Operations Emergency Procedure 2-E-0, RT or SI Was Entered	on 980917,reactor Trip Was Noted.Caused by Lightning Strike.Operations Emergency Procedure 2-E-0, RT or SI Was Entered	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)
05000338/LER-1998-004-01, :on 980902,motor Operated Valve Surveillance Was Missed.Caused by Personnel Error.Station Entered 24 H Action of TS 4.0.3 & Station Deviation Rept Was Initiated to Document Condition.With	on 980902,motor Operated Valve Surveillance Was Missed.Caused by Personnel Error.Station Entered 24 H Action of TS 4.0.3 & Station Deviation Rept Was Initiated to Document Condition.With	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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000338/LER-1998-005-01, :on 980921,safety Valve Setpoints Were Noted Out of Tolerance.Caused by Setpoint Variance.Valves Were Disassembled,Inspected,Repaired as necessary,re-assembled & Tested Satisfactory.With	on 980921,safety Valve Setpoints Were Noted Out of Tolerance.Caused by Setpoint Variance.Valves Were Disassembled,Inspected,Repaired as necessary,re-assembled & Tested Satisfactory.With	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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000338/LER-1998-006-01, :on 980922,ESFA Occurred.Caused by Human Error. Safety Injection Signal Was Reset & Equipment Was Restored to Normal	on 980922,ESFA Occurred.Caused by Human Error. Safety Injection Signal Was Reset & Equipment Was Restored to Normal	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)
05000338/LER-1998-006, Forwards LER 98-006-00,per 10CFR50.73.Commitment Re Completion of Root Cause Evaluation,Listed	Forwards LER 98-006-00,per 10CFR50.73.Commitment Re Completion of Root Cause Evaluation,Listed
05000338/LER-1998-007-01, :on 981015,3B Casing Cooling Pump Failed to Develop Discharge Pressure & Recirculation.Caused by Air Binding.Subject Pump Was Vented of Air,Started & Tested Satisfactorily.With	on 981015,3B Casing Cooling Pump Failed to Develop Discharge Pressure & Recirculation.Caused by Air Binding.Subject Pump Was Vented of Air,Started & Tested Satisfactorily.With	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)

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