LER-1998-001, Forwards LER 98-001-00,concerning Engineered Safety Feature Actuations That Occurred When 2B Reactor Protection Sys Bus Transferred to de-energized Source |
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10 CFR 50.73(a)(2)(iv), System Actuation |
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| 2601998001R00 - NRC Website |
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CATEGORY 1~
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9804140082 DOC.DATE: 98/04/07 NOTARIZED: NO DOCKET FACZL:50-260 Browns'Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 AUTH.'NAME'UTHORAFFILIATION CRANE,C.M.
Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT: Forwards LER 98-001-00,concerning engineered safety feature actuations that occurred when 2B reactor protection sys bus was transferred to de-engergized source.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR j
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TITLE: 50.73/50.9 Licensee Event Report '(LER), Incident Rpt, etc.
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RECIPIENT ID CODE/NAME PD2-3-PD INTERNAL: ACRS AEOD/S PD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HZCB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB EXTERNAL: L ST LOBBY WARD NOAC POORE,W.
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1 RECIPIENT ID CODE/NAME DEAGAZZO,A AEOD/SPD/RAB~
~ENgJER~
R~DE/EELB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB
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NOTE TO ALL NRIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED:
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Tennessee Valley Authority, Post Oflice Box 2000; Decatur, Alabama 35609-2000 Christopher M. (Chris) Crane Vice President, Browns Feny Nuclear Rant April 7, 1998 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D. C.
20555 10 CFR 50.73
Dear Sir.:
BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 2 DOCKET, No. 50-260 FACILITY OPERATING LICENSE DPR-52 LICENSEE EVENT'EPORT (LER) '50-260/1998001 The enclosed report provides details concerning engineered safety feature actuations that occurred when the 2B reactor protection system bus was transferred to a de-energized source because of inattention-to-detail in the preparation of a clearance.
This report is submitted in accordance with 10 CFR 50.73(a) (2) (iv) as an event or condition that resulted in an automatic actuation of an engineered safety feature.
Sincerely,
. M. Cran cc:
See page 2
9804140082 980407 PDR ADOCK 05000260
U.S.. Nuclear Regulatory Commission Page 2
April 7, 1998 Enclosure cc Enclosure):
Mr. A.
W.
De Agazio, Project Manager U.S. Nuclear. Regulatory Commission One White Flint, North 11555 Rockville Pi:ke Rockville, Maryland 20852 Mr. Mark S. Lesser, Branch Chief U. S. Nuclear Regulatory Commission Region II 61 Forsyth Street, S.
W.
Suite 23T85
- Atlanta, Georgia 30303 NRC Resident Inspector.
Browns Fer'ry Nuclear Plant 10833 Shaw Road
- Athens, Alabama 35611
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| 05000259/LER-1998-001-01, Forwards LER 98-001-01 Re Failure to Meet Requirements of ANSI N510-1975 During Performance of SGTS Surveillance Testing.Both SGT & Units 2 & 3 Containment Purge HEPA Filters Meet Leakage Requirements of TS | Forwards LER 98-001-01 Re Failure to Meet Requirements of ANSI N510-1975 During Performance of SGTS Surveillance Testing.Both SGT & Units 2 & 3 Containment Purge HEPA Filters Meet Leakage Requirements of TS | 10 CFR 50.73(a)(2) | | 05000259/LER-1998-001-03, :on 980414,standby Gas Treatment Sys HEPA Filter Testing Was Not in Compliance W/Ansi Std Requirements.Caused by Lack of Understanding of DOP Testing. Filter Testing Training Will Be Provided |
- on 980414,standby Gas Treatment Sys HEPA Filter Testing Was Not in Compliance W/Ansi Std Requirements.Caused by Lack of Understanding of DOP Testing. Filter Testing Training Will Be Provided
| 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)
10 CFR 50.73(a)(2)(1)
10 CFR 50.73(a)(20) | | 05000259/LER-1998-001, Forwards LER 98-001-00 Re Failure to Meet Requirements of ANSI Stds N510-1975, Testing of Nuclear Air Cleaning Sys, During Performance of Standby Gas Treatment Sys Surveillance Testing | Forwards LER 98-001-00 Re Failure to Meet Requirements of ANSI Stds N510-1975, Testing of Nuclear Air Cleaning Sys, During Performance of Standby Gas Treatment Sys Surveillance Testing | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000296/LER-1998-001, :on 980121,determined That Temp Sensors for Certain HELB May Not Detect All Possible Break Locations. Caused by Differences in Computer Codes Rather than Actual Response.Computer Code Correctly Utilized |
- on 980121,determined That Temp Sensors for Certain HELB May Not Detect All Possible Break Locations. Caused by Differences in Computer Codes Rather than Actual Response.Computer Code Correctly Utilized
| 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)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000260/LER-1998-001-02, :on 980308,ESF Actuations Occurred When 2B RPS Bus Was Transferred to de-energized Source.Caused by Failure of Preparing Clearance to Exercise Proper Attention. 2B RPS Bus Restored to Transformer Source |
- on 980308,ESF Actuations Occurred When 2B RPS Bus Was Transferred to de-energized Source.Caused by Failure of Preparing Clearance to Exercise Proper Attention. 2B RPS Bus Restored to Transformer Source
| 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-1998-001, Forwards LER 98-001-00,concerning Engineered Safety Feature Actuations That Occurred When 2B Reactor Protection Sys Bus Transferred to de-energized Source | Forwards LER 98-001-00,concerning Engineered Safety Feature Actuations That Occurred When 2B Reactor Protection Sys Bus Transferred to de-energized Source | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000259/LER-1998-002-01, :on 980521,determined That Flow Switch Calibr Test Did Not Ensure Calibr of Both Instrument Channels as Required by Tss.Caused by Technical Inaccuracies in Surveillance Instruction.Surveillance Instructions Revised |
- on 980521,determined That Flow Switch Calibr Test Did Not Ensure Calibr of Both Instrument Channels as Required by Tss.Caused by Technical Inaccuracies in Surveillance Instruction.Surveillance Instructions Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000260/LER-1998-002, Forwards LER 98-002-00 Re Condition in Which Control Rods Moved Without Required Channels of Rod Block Monitor Being Operable.Util Reporting Event Pursuant to 10CFR50.73(a)(2)(i)(B),as Any Operation | Forwards LER 98-002-00 Re Condition in Which Control Rods Moved Without Required Channels of Rod Block Monitor Being Operable.Util Reporting Event Pursuant to 10CFR50.73(a)(2)(i)(B),as Any Operation | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000296/LER-1998-002, :on 980310,ESF Actuation Occurred Due to Failure of Alternate Feeder Breaker Position Switch.Will Continue Testing & Visual Insps on Addl Breaker Position Switches & Will Revise Applicable Maint Instructions |
- on 980310,ESF Actuation Occurred Due to Failure of Alternate Feeder Breaker Position Switch.Will Continue Testing & Visual Insps on Addl Breaker Position Switches & Will Revise Applicable Maint Instructions
| 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-1998-002-04, :on 980816,personnel Observed Both Channels of Rod Block Monitor Sys Bypassed for Cr.Caused by Failure of Gene to Properly Document & Specify Adjustments.Will Implement Necessary Procedure Controls |
- on 980816,personnel Observed Both Channels of Rod Block Monitor Sys Bypassed for Cr.Caused by Failure of Gene to Properly Document & Specify Adjustments.Will Implement Necessary Procedure Controls
| 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 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(viii)
10 CFR 50.73(a)(2) | | 05000259/LER-1998-002, Forwards LER 98-002-00 Re Inadequate Surveillance Instruction for Calibr of Standby Gas Treatment Sys Relative Humidity Control Heater Flow Switches.Calibr Performed to Determine Operability of Flow Switches | Forwards LER 98-002-00 Re Inadequate Surveillance Instruction for Calibr of Standby Gas Treatment Sys Relative Humidity Control Heater Flow Switches.Calibr Performed to Determine Operability of Flow Switches | | | 05000260/LER-1998-003-03, :on 981001,Unit 2 Received Full Automatic Scram from 100% Reactor Power.Caused by Failure of Normally Open Isolation Valve Which Blocked Flow of Stator Cooling Water Through Associated Heat Exchangers.Replaced Failed Valve |
- on 981001,Unit 2 Received Full Automatic Scram from 100% Reactor Power.Caused by Failure of Normally Open Isolation Valve Which Blocked Flow of Stator Cooling Water Through Associated Heat Exchangers.Replaced Failed Valve
| 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(s)(2)
10 CFR 50.73(s)(2)(iii) | | 05000260/LER-1998-003, Forwards LER 98-003-00 Re Automatic Reactor Scram on Unit 2 from 100% Power.Event Was Result of Valve Failure Which Caused Generator Stator Cooling Water to Exceed High Temp Setpoint for Tt Which Resulted in Automatic Reactor S | Forwards LER 98-003-00 Re Automatic Reactor Scram on Unit 2 from 100% Power.Event Was Result of Valve Failure Which Caused Generator Stator Cooling Water to Exceed High Temp Setpoint for Tt Which Resulted in Automatic Reactor Scram | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000296/LER-1998-003, :on 980407,reactor Manually Scrammed to Prevent thermal-hydraulic Instability After Recirculation Pump Runback.Caused by Human Error.Strengthened Controls Associated W/Walkdowns in NEDP-11 |
- on 980407,reactor Manually Scrammed to Prevent thermal-hydraulic Instability After Recirculation Pump Runback.Caused by Human Error.Strengthened Controls Associated W/Walkdowns in NEDP-11
| 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-1998-003, Forwards LER 98-003-00 Re Condition Which Resulted in Required Volume of Nitrogen Stored Onsite for CAD Not Being Sufficient to Meet Design Basis as Stated in TS Bases | Forwards LER 98-003-00 Re Condition Which Resulted in Required Volume of Nitrogen Stored Onsite for CAD Not Being Sufficient to Meet Design Basis as Stated in TS Bases | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000296/LER-1998-004-01, :on 981007,primary Containment Allowable Leak Rate Was Exceeded.Caused by Failure of Check Valve to Fully Seat Following Shutdown of Rbbccw Sys for Llrt.Valve Was Retested During Next Refueling Outage.With |
- on 981007,primary Containment Allowable Leak Rate Was Exceeded.Caused by Failure of Check Valve to Fully Seat Following Shutdown of Rbbccw Sys for Llrt.Valve Was Retested During Next Refueling Outage.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)(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) | | 05000260/LER-1998-004-03, :on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With |
- on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)
10 CFR 50.73(s)(2) | | 05000296/LER-1998-005, :on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.With |
- on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.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) | | 05000296/LER-1998-006, :on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With |
- on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With
| 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) | | 05000296/LER-1998-007, :on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor |
- on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor
| 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) |
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