05000280/LER-1997-008, Forwards LER 97-008-00 Re Invalid Actuation Esfs,Due to Personnel Errors.Lessons Learned from Event Will Be Presented to Safety Preparers/Reviewers

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Forwards LER 97-008-00 Re Invalid Actuation Esfs,Due to Personnel Errors.Lessons Learned from Event Will Be Presented to Safety Preparers/Reviewers
Person / Time
ML18153A177
Site:	Surry
Issue date:	11/07/1997
From:	Christian D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153A178	List: 05000280/LER-1997-008, Forwards LER 97-008-00 Re Invalid Actuation Esfs,Due to Personnel Errors.Lessons Learned from Event Will Be Presented to Safety Preparers/Reviewers 05000280/LER-1997-008-01, :on 971011,invalid Actuation of ESF Occurred. Caused by Personnel Errors.Main CR Bottled Air Sys Isolated & Containment Hydrogen Analyzer Heat Tracing Actuation Signal Reset
References
97-629, NUDOCS 9711120273
Download: ML18153A177 (2)
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LER-1997-008, Forwards LER 97-008-00 Re Invalid Actuation Esfs,Due to Personnel Errors.Lessons Learned from Event Will Be Presented to Safety Preparers/Reviewers

Event date:
Report date:
2801997008R00 - NRC Website
v • d • e

text

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

Dear Sirs:

e 10CFR50.73 VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station 5570 Hog Island Road Surry, Virginia 23883 November 7,1997 Serial No.:

97 -629 SPS:BCB Docket Nos.: 50~280, 50-281 License Nos.: DPR-32, DPR-37 Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to Surry Power Station Units 1 and 2.

Report No. 50-280, 50-281 /97-008-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be forwarded to the Management Safety Review Committee for its review.

Enclosure:

Commitments contained in this letter:

Very truly yours,

/

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f/~~c~r:

D. A Christian Station Manager

1.

The lessons learned from this event will be presented to Safety Evaluation preparers/reviewers.

2.

This event will also be discussed in Technical Staff Continuing training.

9711120273 971107 PDR ADOCK 05000280 S

PDR 11111111111111111 IIHli 1111111/il 111 lili

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e cc:

U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station e

Licensee Event Report

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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
05000281/LER-1997-001-01, :on 970218,manual Reactor Trip & ESF Actuation Occurred Due to Loss of EHC Control Power.Caused by Momentary Short.Relay Card Was Replaced	on 970218,manual Reactor Trip & ESF Actuation Occurred Due to Loss of EHC Control Power.Caused by Momentary Short.Relay Card Was Replaced	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 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)
05000280/LER-1997-001, :on 970123,shutdown Occurred Due to Drain Line Weld Leak.Inspected & Tested Turbine Trip Actuation Circuitry	on 970123,shutdown Occurred Due to Drain Line Weld Leak.Inspected & Tested Turbine Trip Actuation Circuitry	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)
05000281/LER-1997-002-01, :on 970713,main Steam High Range Radiation Monitor Was Declared Inoperable.Caused by Equipment Failure. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6	on 970713,main Steam High Range Radiation Monitor Was Declared Inoperable.Caused by Equipment Failure. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6	10 CFR 50.73(a)(2)
05000281/LER-1997-002, :on 961213,automatic Reactor Trip Occurred During Planned Shutdown.Caused by Steam Flow/Feedwater Flow Mismatch.Rps Functioned as Designed & Plant Placed in Hot Shutdown	on 961213,automatic Reactor Trip Occurred During Planned Shutdown.Caused by Steam Flow/Feedwater Flow Mismatch.Rps Functioned as Designed & Plant Placed in Hot Shutdown	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)
05000280/LER-1997-002, :on 970116,one Train of Auxiliary Ventilation Sys Was Inoperable Outside of Ts.Caused by Personnel Error. Submitted Deviation Rept Re Reverse Rotation of Fan & Work Request to Adjust Linkage	on 970116,one Train of Auxiliary Ventilation Sys Was Inoperable Outside of Ts.Caused by Personnel Error. Submitted Deviation Rept Re Reverse Rotation of Fan & Work Request to Adjust Linkage	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)(x) 10 CFR 50.73(a)(2)(i)(8)
05000280/LER-1997-002-01, :on 970116,one Train of Auxiliary Ventilation Sys Declared Inoperable.Caused by Personnel Error.Properly Adjusted Damper 1-VS-MOD-58B & Exited Seven Day LCO on 970116	on 970116,one Train of Auxiliary Ventilation Sys Declared Inoperable.Caused by Personnel Error.Properly Adjusted Damper 1-VS-MOD-58B & Exited Seven Day LCO on 970116	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)
05000281/LER-1997-002-03, :on 970713,CR annunciator,2-RMA-A-7 for Main Steam Line Effluent High Range Radiation Monitors Alarmed. Caused by Intermittent Component Failure.Preplanned Alternate Method of Monitoring Initiated	on 970713,CR annunciator,2-RMA-A-7 for Main Steam Line Effluent High Range Radiation Monitors Alarmed. Caused by Intermittent Component Failure.Preplanned Alternate Method of Monitoring Initiated
05000281/LER-1997-003-02, :on 971014,Unit 2 MSSVs Revealed That Lift Setting for Two MSSVs Were Outside as Found Setpoint Tolerance.Caused by Minor Setpoint Drift.Repaired,Revised & Adjusted Safety Valves	on 971014,Unit 2 MSSVs Revealed That Lift Setting for Two MSSVs Were Outside as Found Setpoint Tolerance.Caused by Minor Setpoint Drift.Repaired,Revised & Adjusted Safety Valves	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000280/LER-1997-003, :on 970219,loss of Pressurizer Heaters Resulted in Manual U1 Trip & U2 ESF Actuation.Caused by Loss of Group C Pressurizer Proportional Heaters.Reactor Trip Breakers Were Verified Open	on 970219,loss of Pressurizer Heaters Resulted in Manual U1 Trip & U2 ESF Actuation.Caused by Loss of Group C Pressurizer Proportional Heaters.Reactor Trip Breakers Were Verified Open	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(1)
05000281/LER-1997-004-02, :on 971202,invalid Mstv Indication Results in Manual Reactor Trip W/Esf Actuation Were Noted.Caused by Displaced Open Limit Switch Arms.Open Limit Switch for Mstv a Was Relocated Closer to Valve Position Bar	on 971202,invalid Mstv Indication Results in Manual Reactor Trip W/Esf Actuation Were Noted.Caused by Displaced Open Limit Switch Arms.Open Limit Switch for Mstv a Was Relocated Closer to Valve Position Bar	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(viii)
05000280/LER-1997-004, :on 970317,main Steam Safety Valve Was Outside as Found Setpoint Tolerance.Specific Cause Unknown,However, Minor Setpoint Drift Can Be Expected.No Immediate Corrective Actions Performed	on 970317,main Steam Safety Valve Was Outside as Found Setpoint Tolerance.Specific Cause Unknown,However, Minor Setpoint Drift Can Be Expected.No Immediate Corrective Actions 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 50.73(a)(2)(viii)
05000280/LER-1997-005, :on 970502,Unit 1 Power Range Nuclear Instrumentation Was Inoperable Due to Personnel Error.Sro & STA That Were Involved in Event Were Counseled	on 970502,Unit 1 Power Range Nuclear Instrumentation Was Inoperable Due to Personnel Error.Sro & STA That Were Involved in Event Were Counseled	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)
05000280/LER-1997-006, :on 970320,loss of Refueling Integrity Due to Inadequate Containment Closure Process & Verification.Fuel Movement Stopped IAW Action Statement Requirements of TS 3.10.B	on 970320,loss of Refueling Integrity Due to Inadequate Containment Closure Process & Verification.Fuel Movement Stopped IAW Action Statement Requirements of TS 3.10.B	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)(viii) 10 CFR 50.73(a)(2)
05000280/LER-1997-007, Forwards LER 97-007-00,per 10CFR50.73.Commitments Contained in Ltr,Listed	Forwards LER 97-007-00,per 10CFR50.73.Commitments Contained in Ltr,Listed
05000280/LER-1997-007-01, :on 970930,determined That Plant Was Outside App R Design Basis Due to Vital Bus Isolation Issue.Caused by Personnel Error.Installed Circuit Protective Device During Oct 1997 Refueling Outage	on 970930,determined That Plant Was Outside App R Design Basis Due to Vital Bus Isolation Issue.Caused by Personnel Error.Installed Circuit Protective Device During Oct 1997 Refueling Outage	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)
05000280/LER-1997-008, Forwards LER 97-008-00 Re Invalid Actuation Esfs,Due to Personnel Errors.Lessons Learned from Event Will Be Presented to Safety Preparers/Reviewers	Forwards LER 97-008-00 Re Invalid Actuation Esfs,Due to Personnel Errors.Lessons Learned from Event Will Be Presented to Safety Preparers/Reviewers
05000280/LER-1997-008-01, :on 971011,invalid Actuation of ESF Occurred. Caused by Personnel Errors.Main CR Bottled Air Sys Isolated & Containment Hydrogen Analyzer Heat Tracing Actuation Signal Reset	on 971011,invalid Actuation of ESF Occurred. Caused by Personnel Errors.Main CR Bottled Air Sys Isolated & Containment Hydrogen Analyzer Heat Tracing Actuation Signal Reset	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) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii)
05000280/LER-1997-009, :on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Caused by Inadequate Maint of Intake Canal Level Probes.Subject Probes Were Cleaned, Tested Satisfactorily & Returned to Operable Status	on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Caused by Inadequate Maint of Intake Canal Level Probes.Subject Probes Were Cleaned, Tested Satisfactorily & Returned to Operable Status	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
05000280/LER-1997-009-01, Forwards LER 97-009-01,per 10CFR50.73.Commitments Made by Util,Listed	Forwards LER 97-009-01,per 10CFR50.73.Commitments Made by Util,Listed
05000280/LER-1997-010, :on 971028,discovered Missed Fire Protection Surveillance Pt.Caused by Personnel Error.Satisfactorily Completed PT Procedure 0-OPT-FP-009 & Diesel Driven Fire Pump 1-FP-P-2 Declared Operable	on 971028,discovered Missed Fire Protection Surveillance Pt.Caused by Personnel Error.Satisfactorily Completed PT Procedure 0-OPT-FP-009 & Diesel Driven Fire Pump 1-FP-P-2 Declared Operable	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000280/LER-1997-011, :on 971030,determined That Periodic Test Procedures for Testing Reactor Trip Bypass Breakers Did Not Test Manual Undervoltage Trip.Caused by mis-interpretation of Term in-service. Procedures Revised	on 971030,determined That Periodic Test Procedures for Testing Reactor Trip Bypass Breakers Did Not Test Manual Undervoltage Trip.Caused by mis-interpretation of Term in-service. Procedures Revised	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000280/LER-1997-012, :on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Two Breakers in Security Distribution Panel.Reset Affected Breakers Which Restored Power to Security Systems & Affected Doors	on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Two Breakers in Security Distribution Panel.Reset Affected Breakers Which Restored Power to Security Systems & Affected Doors	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000280/LER-1997-012-01, Forwards LER 97-012-01,per 10CFR50.73.Commitments Made by Util,Listed	Forwards LER 97-012-01,per 10CFR50.73.Commitments Made by Util,Listed

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