05000272/LER-1997-011, Forwards LER 97-011-00,re Failure to Test Isolation of SG Blowdown & Sampling Sys on Automatic Start of Afp,Per 10CFR50.73(a)(2)(ii)(A)

From kanterella

(Redirected from ML18106A217)

Jump to navigation Jump to search

Forwards LER 97-011-00,re Failure to Test Isolation of SG Blowdown & Sampling Sys on Automatic Start of Afp,Per 10CFR50.73(a)(2)(ii)(A)
Person / Time
ML18106A217
Site:	Salem
Issue date:	12/19/1997
From:	Bakken A Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18106A218	List: 05000272/LER-1997-011, Forwards LER 97-011-00,re Failure to Test Isolation of SG Blowdown & Sampling Sys on Automatic Start of Afp,Per 10CFR50.73(a)(2)(ii)(A) 05000272/LER-1997-011-02, :on 971119,failure to Test Isolation of Sgb & SS on Automatic Start of Afps Was Noted.Caused by Inadequate Incorporation of DBA Mitigation Features Into Plant Tp.Pse&G Committed to Complete GL 96-01 Evaluations by 971231
References
LR-N970799, NUDOCS 9801050376
Download: ML18106A217 (1)
v • d • e

LER-1997-011, Forwards LER 97-011-00,re Failure to Test Isolation of SG Blowdown & Sampling Sys on Automatic Start of Afp,Per 10CFR50.73(a)(2)(ii)(A)

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
2721997011R00 - NRC Website
v • d • e

text

.l e

OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LER 272/97-011-00 DEC 1 9 1997 LR-N970799 SALEM GENERA TING STATION - UNIT 1 FACILITY OPERA TING LICENSE NO. DPR-70 DOCKET NO. 50-272 Gentlemen:

This Licensee Event Report entitled "Failure to Test Isolation of Steam Generator Slowdown and Sampling System on the Automatic Start of the Auxiliary Feedwater Pumps" is being submitted pursuant to the requirements of the Code of Federal Regulations 1 OCFR50.73(a)(2)(ii)(A).

C Distribution LER File 3.7 The power is in mur hands.

Sincerely, A. C. Bakken Ill General Manager -

Salem Operations I lfl/ll f I/II f llll jllllf llllf llll[lll lfl/

!/

/

I

. /

95-2168 REV. 6/94 I

Licensee Event Report

70 | 71 | 72 | 73 | 74 | 75 | 76 | 77 | 78 | 79 | 80 | 81 | 82 | 83 | 84 | 85 | 86 | 87 | 88 | 89 |

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
05000272/LER-1997-001, :on 970215,failure to Perform TS Surveillance of Component Cooling Water Sys Check Valves Occurred.Caused by Inadequate Communication Between EOP Group & IST Reviewers.Procedure Revised.With	on 970215,failure to Perform TS Surveillance of Component Cooling Water Sys Check Valves Occurred.Caused by Inadequate Communication Between EOP Group & IST Reviewers.Procedure Revised.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)(i) 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)(1)
05000311/LER-1997-001-01, :on 970115,inadequate Surveillance for PORV Accumulator Discharge Check Valves Was Noted.Caused by Reviewers Not Identifying That Test Method Did Not Meet Requirements of ASME Code.Revised Procedure	on 970115,inadequate Surveillance for PORV Accumulator Discharge Check Valves Was Noted.Caused by Reviewers Not Identifying That Test Method Did Not Meet Requirements of ASME Code.Revised Procedure	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
05000272/LER-1997-001-02, :on 970117,discovered Inadequate IST Surveillance of B Injection Inlet Valves.Caused by Inadequate Communication Between EOP & Ist.Reviewed Salem EOPs for Similar Problems	on 970117,discovered Inadequate IST Surveillance of B Injection Inlet Valves.Caused by Inadequate Communication Between EOP & Ist.Reviewed Salem EOPs for Similar Problems	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000272/LER-1997-002-01, :on 970210,chilled Water Sys Single Failure Vulnerabilities Identified.Caused by Design Deficiency. License Change Request S97-05 Submitted	on 970210,chilled Water Sys Single Failure Vulnerabilities Identified.Caused by Design Deficiency. License Change Request S97-05 Submitted	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000311/LER-1997-002-02, :on 970213,discovered non-seismically Qualified Pressure Switches in Auxiliary Bldg Ventilation.Caused by Pressure Switches Being Replaced w/non-qualified Pressure switches.Re-installed Qualified Switches	on 970213,discovered non-seismically Qualified Pressure Switches in Auxiliary Bldg Ventilation.Caused by Pressure Switches Being Replaced w/non-qualified Pressure switches.Re-installed Qualified Switches	10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
05000272/LER-1997-003-01, :on 970131,new Alignment Assumes Single Failure of 125 Volt Dc Channel Resulted in Two SWS Pumps in Runout Condition Which Caused Insufficient SWS Flow Rates.Modified SW223 Valves for Five Unit 2 Cfcus	on 970131,new Alignment Assumes Single Failure of 125 Volt Dc Channel Resulted in Two SWS Pumps in Runout Condition Which Caused Insufficient SWS Flow Rates.Modified SW223 Valves for Five Unit 2 Cfcus
05000311/LER-1997-003-02, :on 970319,excessive Debris in Unit Two Containment Was Caused by Poor Enforcement & Lack of Mgt Expectations Over Life of Plant,Coupled W/Poor Worker Practices.Debris Removed	on 970319,excessive Debris in Unit Two Containment Was Caused by Poor Enforcement & Lack of Mgt Expectations Over Life of Plant,Coupled W/Poor Worker Practices.Debris Removed	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000311/LER-1997-003-03, :on 970909,loss of Fire Protection Water to Auxiliary Bldgs & Containments Was Noted.Caused by Human Error Due to Inattention to Detail.Loss Prevention Tours Have Been Revised	on 970909,loss of Fire Protection Water to Auxiliary Bldgs & Containments Was Noted.Caused by Human Error Due to Inattention to Detail.Loss Prevention Tours Have Been Revised
05000311/LER-1997-004-02, :on 970408,failed to Comply W/Ts Action Statement,Dg Start & Inadequate Surveillance Testing Due to Inadequate Tracking of Inoperable Equipment by Shift Personnel.Procedures Were Revised	on 970408,failed to Comply W/Ts Action Statement,Dg Start & Inadequate Surveillance Testing Due to Inadequate Tracking of Inoperable Equipment by Shift Personnel.Procedures Were Revised	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000311/LER-1997-004, :on 970408,failure to Comply with TS Action Statement,Dg Start & Inadequate Surveillance Testing,Was Noted.Caused by Inadequate Tracking of Inoperable Equipment. Discussed Event & Lessons Learned.With	on 970408,failure to Comply with TS Action Statement,Dg Start & Inadequate Surveillance Testing,Was Noted.Caused by Inadequate Tracking of Inoperable Equipment. Discussed Event & Lessons Learned.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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000272/LER-1997-004-01, :on 970221,inadequate Surveillance Testing of Molded Case Circuit Breakers Were Identified.Caused by Instantaneous Function Not Accurately Specified in Procedure.Tssip Has Been Initiated	on 970221,inadequate Surveillance Testing of Molded Case Circuit Breakers Were Identified.Caused by Instantaneous Function Not Accurately Specified in Procedure.Tssip Has Been Initiated	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x)
05000272/LER-1997-005-02, :on 970625,radioactive Liquid Effluent Samples Were Not Analyzed within Required Surveillance Interval. Caused by Incorrect Interpretation of TS Sr.Training Will Be Provided to Chemistry Supervisors	on 970625,radioactive Liquid Effluent Samples Were Not Analyzed within Required Surveillance Interval. Caused by Incorrect Interpretation of TS Sr.Training Will Be Provided to Chemistry Supervisors	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)
05000311/LER-1997-005-01, :on 970430,discovered Violation in Pressurizer Overpressure Protection Sys Ts.Caused by Inadequate Procedural Guidance.Revised Procedures for 115 Volt Vital Instrument Bus & 125 Vdc Bus Operations	on 970430,discovered Violation in Pressurizer Overpressure Protection Sys Ts.Caused by Inadequate Procedural Guidance.Revised Procedures for 115 Volt Vital Instrument Bus & 125 Vdc Bus Operations	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii)
05000272/LER-1997-006, :on 970312,determined Relays That Are Part of Logic for Opening PORVs Were Not Tested.Caused by Lack of Adequate Control for Maint of TS Surveillance Procedures. Initiated New Procedures & Revised Procedures	on 970312,determined Relays That Are Part of Logic for Opening PORVs Were Not Tested.Caused by Lack of Adequate Control for Maint of TS Surveillance Procedures. Initiated New Procedures & Revised Procedures	10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)
05000311/LER-1997-006-02, :on 970404,seismic Adequacy of Svc Water Header Was Invalidated Due to Unclear Work Instructions.Piping Has Been Reinstalled Correctly	on 970404,seismic Adequacy of Svc Water Header Was Invalidated Due to Unclear Work Instructions.Piping Has Been Reinstalled Correctly	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 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)
05000272/LER-1997-007-02, :on 970630,failure to Perform Independent Verification for Radioactive Release Lineup as Required by TS 3.3.3.8,noted.Caused by Personnel Error.Cr Supervisor Was Held Accountable for Actions	on 970630,failure to Perform Independent Verification for Radioactive Release Lineup as Required by TS 3.3.3.8,noted.Caused by Personnel Error.Cr Supervisor Was Held Accountable for Actions	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000311/LER-1997-007-01, :on 970623,TS 4.0.5 ISI Requirement to Perform Radiography of Check Valves 2CC195 & 2CC210 Every 92 Days Determined to Have Been Missed.Caused by Personnel Error. Check Valves Subsequently Tested	on 970623,TS 4.0.5 ISI Requirement to Perform Radiography of Check Valves 2CC195 & 2CC210 Every 92 Days Determined to Have Been Missed.Caused by Personnel Error. Check Valves Subsequently Tested	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000272/LER-1997-008, :on 970321,inadequate Surveillance Testing of PORV Accumulators & Check Valves Was Attributed to Lack of Adequate Controls for Development & Maintenance of TS Surveillance Procedures.New Procedure Made	on 970321,inadequate Surveillance Testing of PORV Accumulators & Check Valves Was Attributed to Lack of Adequate Controls for Development & Maintenance of TS Surveillance Procedures.New Procedure Made	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iii)
05000311/LER-1997-008-02, :on 970715,failure to Enter Action Statement for Having Both Radiation Monitors in Same Control Room Air Intake Duct Was Inoperable.Caused by Misjudgement by CR Supervisor.Personnel Was Held Accountable	on 970715,failure to Enter Action Statement for Having Both Radiation Monitors in Same Control Room Air Intake Duct Was Inoperable.Caused by Misjudgement by CR Supervisor.Personnel Was Held Accountable
05000311/LER-1997-009-02, :on 970711,failure to Stroke Pump Discharge Valves for Potential Pressure Locking Concern Was Noted. Caused by Personnel Error.Revised Procedures to Address Addl Instances of CS Pump Operation	on 970711,failure to Stroke Pump Discharge Valves for Potential Pressure Locking Concern Was Noted. Caused by Personnel Error.Revised Procedures to Address Addl Instances of CS Pump Operation	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(viii)
05000272/LER-1997-009, :on 970418,determined That Past Operation of ECCS Was Outside of Plant Design Basis.Caused by Failure to Address All Accident Scenarios Affecting Assumptions Made. Issued New NPSH Calculation Re RHR Pumps	on 970418,determined That Past Operation of ECCS Was Outside of Plant Design Basis.Caused by Failure to Address All Accident Scenarios Affecting Assumptions Made. Issued New NPSH Calculation Re RHR Pumps	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)(i)
05000311/LER-1997-010, :on 970819,CR Operators Initiated Plant Shutdown to Comply W/Requirements of Ts.Caused by Design, Mfg Const/Installation Deficiencies.Calibr Procedure Revised	on 970819,CR Operators Initiated Plant Shutdown to Comply W/Requirements of Ts.Caused by Design, Mfg Const/Installation Deficiencies.Calibr Procedure Revised	10 CFR 50.73(a)(2)(viii)
05000272/LER-1997-010-01, :on 970819,position Indication Sys Were Shutdown as Required by Ts.Caused by Deficiencies in Design, Mfg Const/Installation.Successfully Recalibrated Rod Position Indication Sys	on 970819,position Indication Sys Were Shutdown as Required by Ts.Caused by Deficiencies in Design, Mfg Const/Installation.Successfully Recalibrated Rod Position Indication Sys
05000272/LER-1997-011-02, :on 971119,failure to Test Isolation of Sgb & SS on Automatic Start of Afps Was Noted.Caused by Inadequate Incorporation of DBA Mitigation Features Into Plant Tp.Pse&G Committed to Complete GL 96-01 Evaluations by 971231	on 971119,failure to Test Isolation of Sgb & SS on Automatic Start of Afps Was Noted.Caused by Inadequate Incorporation of DBA Mitigation Features Into Plant Tp.Pse&G Committed to Complete GL 96-01 Evaluations by 971231	10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
05000272/LER-1997-011, Forwards LER 97-011-00,re Failure to Test Isolation of SG Blowdown & Sampling Sys on Automatic Start of Afp,Per 10CFR50.73(a)(2)(ii)(A)	Forwards LER 97-011-00,re Failure to Test Isolation of SG Blowdown & Sampling Sys on Automatic Start of Afp,Per 10CFR50.73(a)(2)(ii)(A)	10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
05000311/LER-1997-011-01, :on 970902,improper Scheduling of Staggered Surveillance Testing Was Noted.Caused by Personnel Error. Personnel Involved Have Been Held Accountable IAW Disciplinary Policies & Addl Training Provided	on 970902,improper Scheduling of Staggered Surveillance Testing Was Noted.Caused by Personnel Error. Personnel Involved Have Been Held Accountable IAW Disciplinary Policies & Addl Training Provided	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000272/LER-1997-012-01, :on 970709,identified Failure to Perform Surveillance Channel Checks of Loop Average Temp Channels. Caused by Misinterpretation of Info in Operating Logs. Revised Control Room Operating Logs	on 970709,identified Failure to Perform Surveillance Channel Checks of Loop Average Temp Channels. Caused by Misinterpretation of Info in Operating Logs. Revised Control Room Operating Logs	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000311/LER-1997-012-03, :on 970907,declared Reactor Coolant Loop 24 Overtemperature Differential Temp Inoperable Due to Differential Temp Being Lower than Acceptable.Returned Loop 23 Pressure Instrumentation to Service	on 970907,declared Reactor Coolant Loop 24 Overtemperature Differential Temp Inoperable Due to Differential Temp Being Lower than Acceptable.Returned Loop 23 Pressure Instrumentation to Service	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000311/LER-1997-013-01, :on 970902,unplanned Entry Into TS 3.0.3 Was Noted Due to Two Inoperable Pressurizer Level Channels. Caused by Error in RCS P&ID Drawing.Pressurizer Channel I Was Restored within Six Minutes of Event	on 970902,unplanned Entry Into TS 3.0.3 Was Noted Due to Two Inoperable Pressurizer Level Channels. Caused by Error in RCS P&ID Drawing.Pressurizer Channel I Was Restored within Six Minutes of Event
05000272/LER-1997-013-02, :on 970702,determined That EDG Should Have Been Declared Inoperable W/Test Instrumentation Connected.Caused by Personnel Error.Performed Satisfactory follow-up Test, Removed Equipment & Signed Off Procedure	on 970702,determined That EDG Should Have Been Declared Inoperable W/Test Instrumentation Connected.Caused by Personnel Error.Performed Satisfactory follow-up Test, Removed Equipment & Signed Off Procedure	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000311/LER-1997-014-01, :on 971002,Unit 2 Manually Tripped.Caused by Failure of Analog Input Circuit Board in Westrac Data Acquistion Sys.Westrac Data Acquisition Sys Removed from Digital Fws	on 971002,Unit 2 Manually Tripped.Caused by Failure of Analog Input Circuit Board in Westrac Data Acquistion Sys.Westrac Data Acquisition Sys Removed from Digital Fws
05000311/LER-1997-016-01, :on 970909,loss of Fire Protection Water to Auxiliary Bldgs & Containment Was Noted.Caused by Human Error Due to Inattention to Detail.Loss Prevention Tours Have Been Revised to Include Once Per Shift Verification	on 970909,loss of Fire Protection Water to Auxiliary Bldgs & Containment Was Noted.Caused by Human Error Due to Inattention to Detail.Loss Prevention Tours Have Been Revised to Include Once Per Shift Verification
05000272/LER-1997-016, ;on 970909,loss of FP Water to Salem,Units 1 & 2 Auxiliary Buildings & Containment Was Noted.Caused by Inadequate Control of 1RP5.Valves Were Opened & Locally Verified by Loss Prevention Personnel	;on 970909,loss of FP Water to Salem,Units 1 & 2 Auxiliary Buildings & Containment Was Noted.Caused by Inadequate Control of 1RP5.Valves Were Opened & Locally Verified by Loss Prevention Personnel
05000311/LER-1997-016-02, :on 971125,inadequate TS Testing Main Steam Isolation Valve Hydraulic Unit Override Contacts Were Noted. Caused by Lack of Adequate Controls.Operability of MSIV Hydraulic Unit Will Be Verified	on 971125,inadequate TS Testing Main Steam Isolation Valve Hydraulic Unit Override Contacts Were Noted. Caused by Lack of Adequate Controls.Operability of MSIV Hydraulic Unit Will Be Verified	10 CFR 50.73(a)(2)(i)
05000311/LER-1997-016, Forwards LER 97-016-00 Re Loss of Fire Protection Water to Auxiliary Bldgs & Containments.Ler Was Originally Submitted on 971015 as LER 97-003-00.Encl Is Being Resubmitted W/Next Sequential LER Number	Forwards LER 97-016-00 Re Loss of Fire Protection Water to Auxiliary Bldgs & Containments.Ler Was Originally Submitted on 971015 as LER 97-003-00.Encl Is Being Resubmitted W/Next Sequential LER Number
05000311/LER-1997-017-01, :on 971212,discovered That non-essential Heat Loads for Chilled Water Sys Were Not Isolated IAW TS Action Statement 3.7.10.a.1.Caused by Personnel Error.Personnel Involved Held Accountable & Revised Procedures	on 971212,discovered That non-essential Heat Loads for Chilled Water Sys Were Not Isolated IAW TS Action Statement 3.7.10.a.1.Caused by Personnel Error.Personnel Involved Held Accountable & Revised Procedures	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000311/LER-1997-018-01, :on 971125,inadequate TS Testing of MSIV Hydraulic Unit Override Contacts,Was Identified.Caused by Lack of Adequate Controls.Procedure S1(2).OP-ST.MS-0003(Q) Revised to Include Testing of MSIV Hydraulic Unit Override	on 971125,inadequate TS Testing of MSIV Hydraulic Unit Override Contacts,Was Identified.Caused by Lack of Adequate Controls.Procedure S1(2).OP-ST.MS-0003(Q) Revised to Include Testing of MSIV Hydraulic Unit Override	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000311/LER-1997-018, Forwards LER 97-018-00, Inadequate TS Testing - Main Steam Isolation Valve Hydraulic Unit Override Contacts. LER Was Originally Submitted on 971224 as LER 97-016.Number Was Already Assigned to Special Rept	Forwards LER 97-018-00, Inadequate TS Testing - Main Steam Isolation Valve Hydraulic Unit Override Contacts. LER Was Originally Submitted on 971224 as LER 97-016.Number Was Already Assigned to Special Rept

Retrieved from "https://kanterella.com/w/index.php?title=05000272/LER-1997-011,_Forwards_LER_97-011-00,re_Failure_to_Test_Isolation_of_SG_Blowdown_%26_Sampling_Sys_on_Automatic_Start_of_Afp,Per_10CFR50.73(a)(2)(ii)(A)&oldid=5000270"