05000260/LER-1997-001, Forwards LER 97-001-00,providing Details Concerning Reactor Scram from 100 Percent Power Resulting from Personnel Error During Surveillance Testing

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Forwards LER 97-001-00,providing Details Concerning Reactor Scram from 100 Percent Power Resulting from Personnel Error During Surveillance Testing
Person / Time
ML20140A527
Site:	Browns Ferry
Issue date:	05/23/1997
From:	Crane C TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20140A534	List: 05000260/LER-1997-001, Forwards LER 97-001-00,providing Details Concerning Reactor Scram from 100 Percent Power Resulting from Personnel Error During Surveillance Testing 05000260/LER-1997-001-05, :on 970424,reactor Scram Occurred During Surveillance Testing.Caused by Personnel Error.Affected Sys Were Restored to pre-event Conditions,Administered Personnel Corrective Actions & Briefed Maintenance
References
NUDOCS 9706040257
Download: ML20140A527 (2)
v • d • e

LER-1997-001, Forwards LER 97-001-00,providing Details Concerning Reactor Scram from 100 Percent Power Resulting from Personnel Error During Surveillance Testing

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv), System Actuation
2601997001R00 - NRC Website
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text

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Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 i

Christopher M. (Chris) Crane Vice President, Browns Ferry Nuclear Plant May 23, 1997 i

U.S. Nuclear Regulatory Commission 10 CFR 50.73 ATTN:

Document Control Desk Washington, D.C.

20555

Dear Sir:

BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 2, DOCKET NO. 50- 260

- FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT 50-260/97001 The enclosed report provides details concerning a reactor scram from 100 percent power.

This event resulted from a personnel error during surveillance testing.

This report is i

submitted in accordance with 10 CFR 50.73 (a) (2) (iv) as a condition that resulted in an automatic actuation of an engineered safety feature, including the reactor protection system.

Sincerely, M

C. M Crane cc:

See page 2 1

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1 U.S. Nuclear Regulatory Commission Page 2 May 23, 1997 1

1 Enclosure cc Enclosure):

Mr. Mark S. Lesser, Branch Chief U.S. Nuclear Regulatory Commission Region II

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61 Forsyth Street, S. W.

Suite 23T85 f

Atlanta, Georgia 30303 l

NRC Resident Inspector l

Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Mr. J.

F. Williams, Project Manager U.S. Nuclear Regulatory Commission i

One White Flint, North i

l 11555 Rockville Pike Rockville, Maryland 20852 l

Licensee Event Report

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		Reporting criterion
05000260/LER-1997-001-05, :on 970424,reactor Scram Occurred During Surveillance Testing.Caused by Personnel Error.Affected Sys Were Restored to pre-event Conditions,Administered Personnel Corrective Actions & Briefed Maintenance	on 970424,reactor Scram Occurred During Surveillance Testing.Caused by Personnel Error.Affected Sys Were Restored to pre-event Conditions,Administered Personnel Corrective Actions & Briefed Maintenance	10 CFR 50.73(a)(2)
05000260/LER-1997-001, Forwards LER 97-001-00,providing Details Concerning Reactor Scram from 100 Percent Power Resulting from Personnel Error During Surveillance Testing	Forwards LER 97-001-00,providing Details Concerning Reactor Scram from 100 Percent Power Resulting from Personnel Error During Surveillance Testing	10 CFR 50.73(a)(2)(iv), System Actuation
05000259/LER-1997-001-03, :on 970203,potential Overpressurization Containment Penetration Pipe Occurred Due to Thermal Expansion of Entrapped Water Was Identified.Plant Procedures Will Be Revised	on 970203,potential Overpressurization Containment Penetration Pipe Occurred Due to Thermal Expansion of Entrapped Water Was Identified.Plant Procedures Will Be Revised	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)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)
05000296/LER-1997-001-04, :on 970305,loss of Offsite Power on Unit 3 During Refueling Outage Resulted from Shorted Component. Replaced Relays Involved in Event W/Less Sensitive Relays	on 970305,loss of Offsite Power on Unit 3 During Refueling Outage Resulted from Shorted Component. Replaced Relays Involved in Event W/Less Sensitive Relays	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)(viii) 10 CFR 50.73(a)(2)
05000296/LER-1997-001, Forwards LER 97-001-00 Re Loss of Offsite Power to Unit During Scheduled Refueling Outage Which Resulted in Auto Start of EDGs A,C & D	Forwards LER 97-001-00 Re Loss of Offsite Power to Unit During Scheduled Refueling Outage Which Resulted in Auto Start of EDGs A,C & D	10 CFR 50.73(a)(2)(iv), System Actuation
05000296/LER-1997-002-03, :on 970410,HPCI Declared Inoperable.Caused by Personnel Error.Operations Personnel Stopped Instrument Mechanics Testing & Returned HPCI to Standby Readiness	on 970410,HPCI Declared Inoperable.Caused by Personnel Error.Operations Personnel Stopped Instrument Mechanics Testing & Returned HPCI to Standby Readiness	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) 10 CFR 50.73(a)(2)
05000259/LER-1997-002-02, :on 970314,inadequate CREVS Surveillance Instruction Was Identified During GL 96-01 Review.Caused by Deficient Procedure.Rev to O-SI-4.2.G-2 Was Made & SI Section Was Successfully Completed	on 970314,inadequate CREVS Surveillance Instruction Was Identified During GL 96-01 Review.Caused by Deficient Procedure.Rev to O-SI-4.2.G-2 Was Made & SI Section Was Successfully Completed	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1)
05000260/LER-1997-002-04, :on 970626,discovered That Four Surveillance Instructions (Sis) Did Not Fully Test All Relay Logic Combinations.Caused by Personnel Error.Verified Relay Contacts Operable & Revised Applicable SIs	on 970626,discovered That Four Surveillance Instructions (Sis) Did Not Fully Test All Relay Logic Combinations.Caused by Personnel Error.Verified Relay Contacts Operable & Revised Applicable SIs	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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000260/LER-1997-003, Forwards LER 97-003-00 Re Failure of HPCI Surveillance Instruction	Forwards LER 97-003-00 Re Failure of HPCI Surveillance Instruction	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000259/LER-1997-003-01, Forwards LER 97-003-01,providing Assessment of Safety Consequences Which Was Inadvertently Omitted from Initial Rept	Forwards LER 97-003-01,providing Assessment of Safety Consequences Which Was Inadvertently Omitted from Initial Rept	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000296/LER-1997-003-01, :on 970314,Unit 3 Main Steam SRVs Pilot Cartridges Failed Setpoint Tolerance Bench Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Drifting.Main Steam SRV Pilot Replaced	on 970314,Unit 3 Main Steam SRVs Pilot Cartridges Failed Setpoint Tolerance Bench Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Drifting.Main Steam SRV Pilot Replaced	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) 10 CFR 50.73(a)(2)(i)(8)
05000260/LER-1997-003-03, :on 970711,determined That HPCI Turbine Speed Lower than Indicated.Caused by Improper Evaluation of Valve Leak.Work Orders to Troubleshoot HPCI Initiated	on 970711,determined That HPCI Turbine Speed Lower than Indicated.Caused by Improper Evaluation of Valve Leak.Work Orders to Troubleshoot HPCI 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)
05000259/LER-1997-003-04, :on 970812,potential for Containment Pressure to Exceed Design During Purging or Inerting If LOCA Occurred Due to Unanalyzed Suppression Pool Bypass Path Was Noted. Caused by Design Error.Revised Sys Operating Instructions	on 970812,potential for Containment Pressure to Exceed Design During Purging or Inerting If LOCA Occurred Due to Unanalyzed Suppression Pool Bypass Path Was Noted. Caused by Design Error.Revised Sys Operating Instructions	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000260/LER-1997-004-03, :on 970909,TS Surveillances Were Not Performed During Refueling Outage Timeframe.Caused by Personnel Error. Incorporated Missed Snubber & Vacuum Breaker Surveillances Into Refueling Outage Schedule	on 970909,TS Surveillances Were Not Performed During Refueling Outage Timeframe.Caused by Personnel Error. Incorporated Missed Snubber & Vacuum Breaker Surveillances Into Refueling Outage Schedule	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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000260/LER-1997-004, Forwards LER 97-004-00,providing Details Re Failure to Perform Required Surveillances During Refueling Outage Time Frames as Required by TS	Forwards LER 97-004-00,providing Details Re Failure to Perform Required Surveillances During Refueling Outage Time Frames as Required by TS	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000296/LER-1997-004-02, :on 970414,unplanned Manual Start of EDG During Scheduled Redundant Start Test Occurred.Caused by Personnel Error.Edg 3D Shutdown & Returned to pre-event Configuration	on 970414,unplanned Manual Start of EDG During Scheduled Redundant Start Test Occurred.Caused by Personnel Error.Edg 3D Shutdown & Returned to pre-event Configuration	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(o)(2)(vii)
05000259/LER-1997-004, Forwards LER 97-004-00 Re Discovery of non-conservative TS Lco.Will Submit TS Change Request to NRC to Remove non- Conservatism	Forwards LER 97-004-00 Re Discovery of non-conservative TS Lco.Will Submit TS Change Request to NRC to Remove non- Conservatism	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000259/LER-1997-004-04, :on 971010,discovered That RHR Swp LCO Is non- Conservative.Caused by Error in Preparation & Approval of Original TS 3.5.C.Will Submit TS Change to NRC to Remove non-conservatism from TS 3.5.C	on 971010,discovered That RHR Swp LCO Is non- Conservative.Caused by Error in Preparation & Approval of Original TS 3.5.C.Will Submit TS Change to NRC to Remove non-conservatism from TS 3.5.C	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)
05000260/LER-1997-005, Forwards LER 97-005-00,providing Details Concerning auto- Start of Engineered Safety Features.Event Resulted from Inadequate Procedure in That Procedure for Developing Post Mod Tests Did Not Require Task Risk Review	Forwards LER 97-005-00,providing Details Concerning auto- Start of Engineered Safety Features.Event Resulted from Inadequate Procedure in That Procedure for Developing Post Mod Tests Did Not Require Task Risk Review	10 CFR 50.73(a)(2)(iv), System Actuation
05000260/LER-1997-005-03, :on 971012,ESF Components Were Actuated.Caused by Inadequate Procedure.Cs Pumps Were Secured & Injection Valves Were Closed & Refueling Floor Activities Were Stopped	on 971012,ESF Components Were Actuated.Caused by Inadequate Procedure.Cs Pumps Were Secured & Injection Valves Were Closed & Refueling Floor Activities Were Stopped	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)
05000296/LER-1997-005, Forwards LER 97-005-00,providing Details Concerning Failure to Enter LCO When Unit 3 Primary Containment Isolation Flow Control Valve Was Declared Inoperable Due to Sticking Solenoid Valve.Rsos Developed Mindset Re Failure Mech	Forwards LER 97-005-00,providing Details Concerning Failure to Enter LCO When Unit 3 Primary Containment Isolation Flow Control Valve Was Declared Inoperable Due to Sticking Solenoid Valve.Rsos Developed Mindset Re Failure Mechanism	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000296/LER-1997-005-02, :on 970824,LCO Was Not Entered When Valve Was Malfunctioning.Caused by Lack of Questioning Attitude by Operations Crew.Involved SROs Were Counseled & Problem Evaluation Rept Will Be Discussed	on 970824,LCO Was Not Entered When Valve Was Malfunctioning.Caused by Lack of Questioning Attitude by Operations Crew.Involved SROs Were Counseled & Problem Evaluation Rept Will Be Discussed	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)(vi) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000260/LER-1997-006-02, :on 971019,declared Unit 2 Hpcis Inoperable. Caused by High Condensate Level in HPCI Turbine Inlet Steam Line Drain Pot.Work Request Initiated	on 971019,declared Unit 2 Hpcis Inoperable. Caused by High Condensate Level in HPCI Turbine Inlet Steam Line Drain Pot.Work Request 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 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000260/LER-1997-006, Forwards LER 97-006-00 Re Inoperable Unit 2 Hpcis Discovered During Power Ascension from Unit 2 Cycle 9 Refueling Outage. Rept Submitted in Accordance w/10CFR50.73(a)(2)(v)	Forwards LER 97-006-00 Re Inoperable Unit 2 Hpcis Discovered During Power Ascension from Unit 2 Cycle 9 Refueling Outage. Rept Submitted in Accordance w/10CFR50.73(a)(2)(v)	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000260/LER-1997-007-02, :on 971028,Unit 2 Automatically Scrammed.Caused by Momentary Pressure Drop in electro-hydraulic Control Sys at Turbine Control Valves.Scram Contactor Replaced	on 971028,Unit 2 Automatically Scrammed.Caused by Momentary Pressure Drop in electro-hydraulic Control Sys at Turbine Control Valves.Scram Contactor Replaced	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)
05000260/LER-1997-007, Forwards LER 97-007-00 Re Reactor Scram from 70 Percent Power.Event Resulted from Pressure Perturbation in electro- Hydraulic Control Sys at Turbine Control Valves	Forwards LER 97-007-00 Re Reactor Scram from 70 Percent Power.Event Resulted from Pressure Perturbation in electro- Hydraulic Control Sys at Turbine Control Valves	10 CFR 50.73(a)(2)(iv), System Actuation
05000260/LER-1997-008, Forwards LER 97-008-00,which Provides Details Re Main Steam Safety/Relief Valves That Exceeded TS Setpoint Limit During Surveillance Tests	Forwards LER 97-008-00,which Provides Details Re Main Steam Safety/Relief Valves That Exceeded TS Setpoint Limit During Surveillance Tests
05000260/LER-1997-008-02, :on 971104,main Steam Safety/Relief Valves Exceeded TS Setpoint Limit.Caused by Pilot Valve Disc/Seat Bonding.Replaced All 13 Unit 2 Main Steam SRV Pilot Cartridges	on 971104,main Steam Safety/Relief Valves Exceeded TS Setpoint Limit.Caused by Pilot Valve Disc/Seat Bonding.Replaced All 13 Unit 2 Main Steam SRV Pilot Cartridges	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)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)

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