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| | Salem Generating Station March 18, 1991 U. S. Nuclear Regulatory Commission Document Control Desk |
| * Salem Generating Station March 18, 1991 U. S. Nuclear Regulatory Commission Document Control Desk
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| * Washington, DC 20555 | | * Washington, DC 20555 |
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| Salem Generating Station - Uµit l - o 15 Io Io Io I 21 712 1 loF O 15 TITLE (41 ESF Actuation*siqnalsFor Cont. Vent. Isolation Due 'l'o Inad. Admin. Controls EVENT DATE UIJ LER NUMBER (81 REPORT DATE (71 OTHER FACILITIES INVOLVED (Ill MONTH QAY YEAR YEAR ?l SE~~~~~~AL At ~~X.~?.: MONTH DAY YEAR FACILITY NAMES | | Salem Generating Station - Uµit l - o 15 Io Io Io I 21 712 1 loF O 15 TITLE (41 ESF Actuation*siqnalsFor Cont. Vent. Isolation Due 'l'o Inad. Admin. Controls EVENT DATE UIJ LER NUMBER (81 REPORT DATE (71 OTHER FACILITIES INVOLVED (Ill MONTH QAY YEAR YEAR ?l SE~~~~~~AL At ~~X.~?.: MONTH DAY YEAR FACILITY NAMES |
| * DOCKET NUMBER(SI 0151010101 I *I 01s1010101 I I | | * DOCKET NUMBER(SI 0151010101 I *I 01s1010101 I I |
| * THIS REPORT II SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Choclt OM or mon of lhl fol/owing} (111 | | * THIS REPORT II SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Choclt OM or mon of lhl fol/owing} (111 OPERATING MOOE (I) |
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| I 5 Z0.402(bl 20.-lcl | | I 5 Z0.402(bl 20.-lcl |
| ...1 I0.73(1)(2lllvl 73.71(b) | | ...1 I0.73(1)(2lllvl 73.71(b) zo.-i.1111rn ll0.3111cl111 ll0.73!1ll21M 73.711*1 |
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| zo.-i.1111rn ll0.3111cl111 ll0.73!1ll21M 73.711*1 | |
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| . l'OWER | | . l'OWER |
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| LEVEL 1101 0 I 0 IO ZO.-(IJ(IJ(UI ll0.311(cJl21 I0.73(1ll2Jl*RI OTHER (5-lfy In Ab1tnct btlow '*nd In T11tt. NRC Fann zo.-1111110111 ll0.73(aJl2lllJ ll0.73!1ll2Jlwllll1Al 366A} | | LEVEL 1101 0 I 0 IO ZO.-(IJ(IJ(UI ll0.311(cJl21 I0.73(1ll2Jl*RI OTHER (5-lfy In Ab1tnct btlow '*nd In T11tt. NRC Fann zo.-1111110111 ll0.73(aJl2lllJ ll0.73!1ll2Jlwllll1Al 366A} |
| NAME zo.-!IJl1lU*I Z0.40lllaJ11lM - ll0.73(aJl2Jllll ll0.73(1112111111 . | | NAME zo.-!IJl1lU*I Z0.40lllaJ11lM - ll0.73(aJl2Jllll ll0.73(1112111111 . |
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| NRC f<>rm 311-5 19.fP.il | | NRC f<>rm 311-5 19.fP.il |
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| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Genera_ting Station DOCKET NUMBER LER NUMBER PAGE Unit 1 - 5000272 91-006-00 2 of 5 PLANT AND SYSTEM IDENTIFICATION: |
| LICENSEE EVENT REPORT (LER) TEXT CONTINUATION | |
| * Salem Genera_ting Station DOCKET NUMBER LER NUMBER PAGE Unit 1 - 5000272 91-006-00 2 of 5 PLANT AND SYSTEM IDENTIFICATION:
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| Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xxl IDENTIFICATION OF OCCURRENCE: | | Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xxl IDENTIFICATION OF OCCURRENCE: |
| Engineered Safety Feature actuation signals for Containment Purge/Pressure-Vacuum Relief System isolation from the lRllA Radiation Monitoring System channel Event Dates: 2/16/91, 2/20/91 and 2/27/91 Report Date: 3/18/91 This report was initiated by Incident Report Nos. 91-103, 91-124, and 91-149. | | Engineered Safety Feature actuation signals for Containment Purge/Pressure-Vacuum Relief System isolation from the lRllA Radiation Monitoring System channel Event Dates: 2/16/91, 2/20/91 and 2/27/91 Report Date: 3/18/91 This report was initiated by Incident Report Nos. 91-103, 91-124, and 91-149. |
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| On February 20, 1991 at 0203 hours, with the Unit in Mode 5, the 1~_:;_:_]:_ (.~1ar1i.lc~ '-<i.~c.l..tax...:: t..i.~o.~LJ., .i::i=sultirL9 iJ..l c.. CP/P-""lH. S:;{bLt.lii isolatior.L | | On February 20, 1991 at 0203 hours, with the Unit in Mode 5, the 1~_:;_:_]:_ (.~1ar1i.lc~ '-<i.~c.l..tax...:: t..i.~o.~LJ., .i::i=sultirL9 iJ..l c.. CP/P-""lH. S:;{bLt.lii isolatior.L |
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| LICENSEE EVENT REPORT (LER) TEXT CONTINUAT!ON Salem Generating Station DOCKET NUMBER ~ER HUMBER PAGE Unit 1. 5000272 *91-006-00 3 of 5 DESCRIPTION OF OCCURRENCE: (cont'd) signal actuation. The alarm was believed to b~ a result of the _lower alarm setpoint setting (tefere~ce LER 272/91-010-00): therefore, troubleshooting was*not performed. However, subsequent review did not substantiate this conclusion. | | LICENSEE EVENT REPORT (LER) TEXT CONTINUAT!ON Salem Generating Station DOCKET NUMBER ~ER HUMBER PAGE Unit 1. 5000272 *91-006-00 3 of 5 DESCRIPTION OF OCCURRENCE: (cont'd) signal actuation. The alarm was believed to b~ a result of the _lower alarm setpoint setting (tefere~ce LER 272/91-010-00): therefore, troubleshooting was*not performed. However, subsequent review did not substantiate this conclusion. |
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| On February 27, 1991 at 1735 hours, with the Unit in Mode 6, a Containment Purge/Pressure-Vacuum Relief System (CP/P-VRS) isolation signal was initiated by the lRllA RMS channel. At the time of the event, Containment Purge was in progress. The isolation valves closed as designed upon receipt of the signal. | | On February 27, 1991 at 1735 hours, with the Unit in Mode 6, a Containment Purge/Pressure-Vacuum Relief System (CP/P-VRS) isolation signal was initiated by the lRllA RMS channel. At the time of the event, Containment Purge was in progress. The isolation valves closed as designed upon receipt of the signal. |
| At the time of the February 27, 1991 event, an operator was resetting a lRllA chaimel warning alarm. The alarm signal actuated as the warning.alarm was reset. SubsGquently, a work order was initiated and cor~ective maintenance was performed. | | At the time of the February 27, 1991 event, an operator was resetting a lRllA chaimel warning alarm. The alarm signal actuated as the warning.alarm was reset. SubsGquently, a work order was initiated and cor~ective maintenance was performed. |
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| LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Statiori DOCKET NUMBER* * -LER NUMBER . PAGE Unit 1 . 5000272 91-006-00 4 of 5 APPARENT CAUSE OF OCCURRENCE: (cont'd) | | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Statiori DOCKET NUMBER* * -LER NUMBER . PAGE Unit 1 . 5000272 91-006-00 4 of 5 APPARENT CAUSE OF OCCURRENCE: (cont'd) |
| LER 311/90-044-00 initiated a commitment to investigate possible interim measures which can be taken to minimize the possibility of | | LER 311/90-044-00 initiated a commitment to investigate possible interim measures which can be taken to minimize the possibility of |
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| As previously committed to by LER 311/90-044-00, interim actions to limit. the number of RMS channel failures are being evaluated. These actions include review of maintenance techniques and procedures. | | As previously committed to by LER 311/90-044-00, interim actions to limit. the number of RMS channel failures are being evaluated. These actions include review of maintenance techniques and procedures. |
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| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 . . 50*00212 91-006,-00 5 of 5 CORRECTIVE ACTION: . (cont'd). |
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| * LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 . . 50*00212 91-006,-00 5 of 5 CORRECTIVE ACTION: . (cont'd).
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| As indicated in.prior LERs, engineering ;has investigated the. concerns w.ith the Salem U-1 and *u-~ RMS channels. Design modifications | | As indicated in.prior LERs, engineering ;has investigated the. concerns w.ith the Salem U-1 and *u-~ RMS channels. Design modifications |
| .include a proposal for _RMS channel equivalent replacement. | | .include a proposal for _RMS channel equivalent replacement. |
Similar Documents at Salem |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0081998-12-24024 December 1998 LER 97-001-01: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 981224 Ltr ML18106B0021998-12-17017 December 1998 LER 98-015-01:on 980924,improper Installation of Test Equipment to RPS Occurred.Caused by Inadequate 10CFR50.59 Applicability Reviews During Past Revs.Revised Procedures. with 981217 Ltr ML18106A9551998-11-0303 November 1998 LER 96-013-01:on 960711,concluded That Current Gain & Bias Settings Had Rendered Overtemperature Delta Temp Protection Channels Inoperable.Caused by Scaling Error.Licensee Will Revise Scaling Calculations.With 981105 Ltr ML18106A9451998-10-30030 October 1998 LER 97-004-01: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 981022 Ltr ML18106A9491998-10-22022 October 1998 LER 98-015-00:on 980924,identified Improper Installation of Test Equipment to Rps.Cause Indeterminate.Procedures for Installation of Test Equipment for Collection of State Point Data Were Placed on Administrative Hold.With 981022 Ltr ML18106A9301998-10-21021 October 1998 LER 98-014-00:on 980725,noted Improper Calibr of Liquid Radwaste Effluent Line Radiation Monitor.Caused by Inattention to Detail by Maint Personnel.Channel Calibr Was Successfully Performed on 1R18 on 980821.With 981019 Ltr ML18106A9071998-10-0101 October 1998 LER 98-014-00:on 980918,discovered That Fire Barrier Matl for HVAC Ducts Does Not Meet Required Level of Fire Resistance.Cause Indeterminate.Established Appropriate Compensatory Actions for Fire Barriers.With 981001 Ltr ML18106A8951998-09-28028 September 1998 LER 98-012-01:on 980725,noted That Afs Was Operated with Less than Required Number of Operable AFW Pumps.Caused by Improper Procedure Implementation.Runout Protection Pressure Device for 22 AFW Pumps Was Returned to Svc.With 980928 Ltr ML18106A8821998-09-21021 September 1998 LER 98-013-00:on 980820,noted Surveillance of Containment Penetration Overcurrent Protection Devices Missed.Caused by Human Error.Satisfactorily Tested Apprpriate Breakers & Disciplined Involved Personnel.With 980921 Ltr ML18106A8791998-09-16016 September 1998 LER 96-006-01:on 960717,determined That non-radioactive Liquid Basin Radwaste Monitor Inoperable During Low Head Conditions.Caused by Inadequate Design Change Package.Design Change 1EC3663-01 Has Been Installed.With 980916 Ltr ML18106A8801998-09-0808 September 1998 LER 98-013-00:on 980806,operation with TS Required Equipment OOS Was Noted.Caused by Human Error.Reviewed Processes & Practices Re Safety Sys Status Control,Procedure Rev & Extra Training.With 980908 Ltr ML18106A8531998-08-27027 August 1998 LER 98-007-00:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Cause of Event Has Not Yet Been Determined.Assembled Root Cause Team & Replaced Affected tubing.W/980827 Ltr ML18106A8521998-08-27027 August 1998 LER 98-011-00:on 980803,ESFA During a 4KV Automatic Transfer Test Was Noted.Caused by Premature Release of Control Console Pushbutton Due to Inadequate Procedural Step.Revised procedure.W/980827 Ltr ML18106A8421998-08-24024 August 1998 LER 98-012-00:on 980725,discovered That Plant Had Operated in Modes 1 & 2 w/twenty-two AFW Pumps Inoperable.Caused by Failure to Restore Pump Runout Protection Pressure Device to Svc.Returned Subject Device to svc.W/980824 Ltr ML18106A8431998-08-24024 August 1998 LER 98-009-00:on 980810,failure to Post Continuous Firewatch as Required by Fire Protection Plan Noted.Caused by Failure to Recognize Concurrent Conditions.Continuous Firewatch Was Posted Immediately & Repaired Smoke detectors.W/980824 Ltr ML18106A8141998-08-13013 August 1998 LER 98-010-00:on 980714,determined That Leakage from Boron Injection Tank Exceeded Max Allowable ECCS Leakage from Sources Outside Containment.Caused by Leaking 2SJ404 Manual Sample valve.2SJ404 Valve repaired.W/980813 Ltr ML18106A8201998-08-13013 August 1998 LER 98-012-00:on 980715,potential to Exceed Rating of Piping Due to Isolation of Overpressure Protection Line Was Noted. Caused by Inadequate Procedural Guidance.Appropriate Operations Dept Procedures Have Been revised.W/980813 Ltr ML18106A6931998-06-29029 June 1998 LER 98-003-00:on 980122,inappropriate Plugging of Tubes R9C60 & R10C60 in Salem Unit 2 Sg,Was Performed.Caused by Failure of Qualification,Verification & Validation Process. Tubes Reviewed to Verify No Others Inappropriately Plugged ML18106A6471998-06-0404 June 1998 LER 98-011-00:on 980505,improper Isolation of Single Cell Battery Charger from 125 Vdc Battery Was Noted.Caused by Inadequate 10CFR50.59 Applicability Review.Placed Procedure SC.MD-CM.ZZ-0024(Q) on Administrative hold.W/980604 Ltr ML18106A6421998-06-0101 June 1998 LER 98-010-00:on 931019,reactor Pressure Vessel Insp Plugs Were Out of Configuration,Was Noted.Caused by Personnel Error.Proper Configuration Was Restored Shortly After Discovery Prior to Entering Mode 2.W/980601 Ltr ML18106A6431998-05-29029 May 1998 LER 98-006-01:on 980227,determined Incorrect Scaling Error of First Stage Pressure Transmitter Existed.Caused by Human Error.Revised Setpoint Calculation SC-MS002-01 & Revised Associated Instrument Calibr Database info.W/980529 Ltr ML18106A6141998-05-18018 May 1998 LER 98-008-00:on 970814,failure to Test 21 & 22 AF 40 Valves in Closed Direction as Required by TS 4.0.5 Was Noted.Caused by Inadequate Design Mod Process.Motor Driven 21/22 AF 40 Valves Were Tested IAW Revised procedure.W/980518 Ltr ML18106A5901998-05-0101 May 1998 LER 98-009-00:on 980405,epoxy Missing from Terminals of H Analyzer Was Noted.Caused by Inadequate Development of Procedure.H Analyzers Were Repaired & Review of Other Safety Related Equipment in Containment Was performed.W/980501 Ltr ML18106A5611998-04-20020 April 1998 LER 98-008-00:on 980323,inadequate Testing of Salem Unit 1 Containment Air Locks Resulted in Entering TS 3.0.3.Caused by less-than-adequate Work Practices During Replacement of Equalizing Valve.Salem Unit 2 Airlocks Were Inspected ML18106A6061998-04-0101 April 1998 Corrected LER 98-004-00:on 980302,failure to Comply W/Tss 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Have Been Taken to Correctly Document Safety Factors.Corrects Prior Similar Occurrences ML18106A4451998-04-0101 April 1998 LER 98-004-00:on 980302,failure to Perform TS 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Were Taken to Correctly Document Safety factors.W/980401 Ltr ML18106A4351998-03-30030 March 1998 LER 98-006-00:on 980227,incorrect Scaling of First Stage Turbine Impulse Pressure Transmitters Noted.Cause Indeterminate.Implemented Procedure Changes & re-scaled Affected Turbine Impulse Pressure transmitters.W/980330 Ltr ML18106A3961998-03-20020 March 1998 LER 98-005-00:on 980219,inoperability of Twelve EDG Fuel Oil Transfer Pump (FOTP) Noted.Caused by Installation of Incorrect Control Switch.Installed Correct off-auto-manual Switch & Verified Operability of Twelve FOTP.W/980320 Ltr ML18106A5781998-03-20020 March 1998 Corrected LER 98-005-00:on 980219,inoperability of 12 Fuel Oil Transfer Pump (Fotp),Noted.Caused by Installation of Incorrect Control Switch.Field Insp Performed to Verify Configuration of Switches for 11,21 & 22 FOTPs ML18106A4021998-03-20020 March 1998 LER 98-007-00:on 980218,failure to Establish Containment Integrity (Closure) Prior to Fuel Movement Was Noted.Caused by Failure to Identify & Include Condensate Pot Vent in Appropriate Valve Lineup.Valves identified.W/980320 Ltr ML18106A4031998-03-20020 March 1998 LER 98-006-00:on 980221,ESF Actuation of 11 & 12 Auxiliary Feedwater Pumps Occurred.Caused by Human Error.Operators Promptly Established Feedwater to All SG & Restored Proper Water levels.W/980320 Ltr 1999-08-26
[Table view] Category:RO)
MONTHYEARML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0081998-12-24024 December 1998 LER 97-001-01: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 981224 Ltr ML18106B0021998-12-17017 December 1998 LER 98-015-01:on 980924,improper Installation of Test Equipment to RPS Occurred.Caused by Inadequate 10CFR50.59 Applicability Reviews During Past Revs.Revised Procedures. with 981217 Ltr ML18106A9551998-11-0303 November 1998 LER 96-013-01:on 960711,concluded That Current Gain & Bias Settings Had Rendered Overtemperature Delta Temp Protection Channels Inoperable.Caused by Scaling Error.Licensee Will Revise Scaling Calculations.With 981105 Ltr ML18106A9451998-10-30030 October 1998 LER 97-004-01: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 981022 Ltr ML18106A9491998-10-22022 October 1998 LER 98-015-00:on 980924,identified Improper Installation of Test Equipment to Rps.Cause Indeterminate.Procedures for Installation of Test Equipment for Collection of State Point Data Were Placed on Administrative Hold.With 981022 Ltr ML18106A9301998-10-21021 October 1998 LER 98-014-00:on 980725,noted Improper Calibr of Liquid Radwaste Effluent Line Radiation Monitor.Caused by Inattention to Detail by Maint Personnel.Channel Calibr Was Successfully Performed on 1R18 on 980821.With 981019 Ltr ML18106A9071998-10-0101 October 1998 LER 98-014-00:on 980918,discovered That Fire Barrier Matl for HVAC Ducts Does Not Meet Required Level of Fire Resistance.Cause Indeterminate.Established Appropriate Compensatory Actions for Fire Barriers.With 981001 Ltr ML18106A8951998-09-28028 September 1998 LER 98-012-01:on 980725,noted That Afs Was Operated with Less than Required Number of Operable AFW Pumps.Caused by Improper Procedure Implementation.Runout Protection Pressure Device for 22 AFW Pumps Was Returned to Svc.With 980928 Ltr ML18106A8821998-09-21021 September 1998 LER 98-013-00:on 980820,noted Surveillance of Containment Penetration Overcurrent Protection Devices Missed.Caused by Human Error.Satisfactorily Tested Apprpriate Breakers & Disciplined Involved Personnel.With 980921 Ltr ML18106A8791998-09-16016 September 1998 LER 96-006-01:on 960717,determined That non-radioactive Liquid Basin Radwaste Monitor Inoperable During Low Head Conditions.Caused by Inadequate Design Change Package.Design Change 1EC3663-01 Has Been Installed.With 980916 Ltr ML18106A8801998-09-0808 September 1998 LER 98-013-00:on 980806,operation with TS Required Equipment OOS Was Noted.Caused by Human Error.Reviewed Processes & Practices Re Safety Sys Status Control,Procedure Rev & Extra Training.With 980908 Ltr ML18106A8531998-08-27027 August 1998 LER 98-007-00:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Cause of Event Has Not Yet Been Determined.Assembled Root Cause Team & Replaced Affected tubing.W/980827 Ltr ML18106A8521998-08-27027 August 1998 LER 98-011-00:on 980803,ESFA During a 4KV Automatic Transfer Test Was Noted.Caused by Premature Release of Control Console Pushbutton Due to Inadequate Procedural Step.Revised procedure.W/980827 Ltr ML18106A8421998-08-24024 August 1998 LER 98-012-00:on 980725,discovered That Plant Had Operated in Modes 1 & 2 w/twenty-two AFW Pumps Inoperable.Caused by Failure to Restore Pump Runout Protection Pressure Device to Svc.Returned Subject Device to svc.W/980824 Ltr ML18106A8431998-08-24024 August 1998 LER 98-009-00:on 980810,failure to Post Continuous Firewatch as Required by Fire Protection Plan Noted.Caused by Failure to Recognize Concurrent Conditions.Continuous Firewatch Was Posted Immediately & Repaired Smoke detectors.W/980824 Ltr ML18106A8141998-08-13013 August 1998 LER 98-010-00:on 980714,determined That Leakage from Boron Injection Tank Exceeded Max Allowable ECCS Leakage from Sources Outside Containment.Caused by Leaking 2SJ404 Manual Sample valve.2SJ404 Valve repaired.W/980813 Ltr ML18106A8201998-08-13013 August 1998 LER 98-012-00:on 980715,potential to Exceed Rating of Piping Due to Isolation of Overpressure Protection Line Was Noted. Caused by Inadequate Procedural Guidance.Appropriate Operations Dept Procedures Have Been revised.W/980813 Ltr ML18106A6931998-06-29029 June 1998 LER 98-003-00:on 980122,inappropriate Plugging of Tubes R9C60 & R10C60 in Salem Unit 2 Sg,Was Performed.Caused by Failure of Qualification,Verification & Validation Process. Tubes Reviewed to Verify No Others Inappropriately Plugged ML18106A6471998-06-0404 June 1998 LER 98-011-00:on 980505,improper Isolation of Single Cell Battery Charger from 125 Vdc Battery Was Noted.Caused by Inadequate 10CFR50.59 Applicability Review.Placed Procedure SC.MD-CM.ZZ-0024(Q) on Administrative hold.W/980604 Ltr ML18106A6421998-06-0101 June 1998 LER 98-010-00:on 931019,reactor Pressure Vessel Insp Plugs Were Out of Configuration,Was Noted.Caused by Personnel Error.Proper Configuration Was Restored Shortly After Discovery Prior to Entering Mode 2.W/980601 Ltr ML18106A6431998-05-29029 May 1998 LER 98-006-01:on 980227,determined Incorrect Scaling Error of First Stage Pressure Transmitter Existed.Caused by Human Error.Revised Setpoint Calculation SC-MS002-01 & Revised Associated Instrument Calibr Database info.W/980529 Ltr ML18106A6141998-05-18018 May 1998 LER 98-008-00:on 970814,failure to Test 21 & 22 AF 40 Valves in Closed Direction as Required by TS 4.0.5 Was Noted.Caused by Inadequate Design Mod Process.Motor Driven 21/22 AF 40 Valves Were Tested IAW Revised procedure.W/980518 Ltr ML18106A5901998-05-0101 May 1998 LER 98-009-00:on 980405,epoxy Missing from Terminals of H Analyzer Was Noted.Caused by Inadequate Development of Procedure.H Analyzers Were Repaired & Review of Other Safety Related Equipment in Containment Was performed.W/980501 Ltr ML18106A5611998-04-20020 April 1998 LER 98-008-00:on 980323,inadequate Testing of Salem Unit 1 Containment Air Locks Resulted in Entering TS 3.0.3.Caused by less-than-adequate Work Practices During Replacement of Equalizing Valve.Salem Unit 2 Airlocks Were Inspected ML18106A6061998-04-0101 April 1998 Corrected LER 98-004-00:on 980302,failure to Comply W/Tss 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Have Been Taken to Correctly Document Safety Factors.Corrects Prior Similar Occurrences ML18106A4451998-04-0101 April 1998 LER 98-004-00:on 980302,failure to Perform TS 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Were Taken to Correctly Document Safety factors.W/980401 Ltr ML18106A4351998-03-30030 March 1998 LER 98-006-00:on 980227,incorrect Scaling of First Stage Turbine Impulse Pressure Transmitters Noted.Cause Indeterminate.Implemented Procedure Changes & re-scaled Affected Turbine Impulse Pressure transmitters.W/980330 Ltr ML18106A3961998-03-20020 March 1998 LER 98-005-00:on 980219,inoperability of Twelve EDG Fuel Oil Transfer Pump (FOTP) Noted.Caused by Installation of Incorrect Control Switch.Installed Correct off-auto-manual Switch & Verified Operability of Twelve FOTP.W/980320 Ltr ML18106A5781998-03-20020 March 1998 Corrected LER 98-005-00:on 980219,inoperability of 12 Fuel Oil Transfer Pump (Fotp),Noted.Caused by Installation of Incorrect Control Switch.Field Insp Performed to Verify Configuration of Switches for 11,21 & 22 FOTPs ML18106A4021998-03-20020 March 1998 LER 98-007-00:on 980218,failure to Establish Containment Integrity (Closure) Prior to Fuel Movement Was Noted.Caused by Failure to Identify & Include Condensate Pot Vent in Appropriate Valve Lineup.Valves identified.W/980320 Ltr ML18106A4031998-03-20020 March 1998 LER 98-006-00:on 980221,ESF Actuation of 11 & 12 Auxiliary Feedwater Pumps Occurred.Caused by Human Error.Operators Promptly Established Feedwater to All SG & Restored Proper Water levels.W/980320 Ltr 1999-08-26
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18107A5581999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr ML18107A5571999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr ML18107A5301999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 ML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF). ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr ML18107A4821999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF). ML18107A4351999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A3681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr ML18107A3721999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML18107A2991999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr ML18107A2971999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. ML18107A1821999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr ML18107A1831999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B1021999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr ML18106B1011999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0561999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr ML18106B0571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr ML20205P1671999-01-31031 January 1999 a POST-PLUME Phase, Federal Participation Exercise ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0251998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr 1999-09-30
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Salem Generating Station March 18, 1991 U. S. Nuclear Regulatory Commission Document Control Desk
Dear Sir:
SALEM GEllERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 91-006-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73(a} (2) (iv}. This report is required to be issued within thirty (30) days of event discovery.
I I
. I Sincerely yours,
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- s. LaBruna General Manager -
Salem Operations MJP:pc Distribution r::* F'[.lf~
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NRC Form 3118 (9-831
- LICENSEE EVENT REPORT (LER)
- -- U.S. NUCLEAR REGULATORY cOMMISllON APPROVED OMll NO. 3150~104
. EXPIRES: 8/31 is&
FACIL!TY NAME'.(11--------------------------------.,-DOC~K~ET~NU~M~B~E~R~(2-:-1----r-1""'"PA<l£13)""'
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- DOCKET NUMBER(SI 0151010101 I *I 01s1010101 I I
- THIS REPORT II SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Choclt OM or mon of lhl fol/owing} (111 OPERATING MOOE (I)
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LICENSEE CONTACT FOR THIS LER 1121 ll0.73(all2Jl*lllllll ll0.73(aJl2Jlxl TELEPHONE NUMBER AREA CODE M. J. Pollack - LER Coordinator
- 61019 313191- 12 I 01212 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRlllED IN THiii REPORT (131 .
CAUSE SYSTEM COMPONENT MANUFAC* MANUFAC*
TUR ER SYSTEM COMPONENT TUR ER I I I I I I *-1 . I I I I I I I I I I I I I I I I I.I I I I SUPPLEMENTAL REPORT EXPECTED 1141 YfAR rn MONTH DAV EXPECTED n YES (If yn, comploto EXPECTED SUBMISSION OATEI NO SUBMISSION DATE (151 I I I ASSTRACT (Limlr to r400 ipacn. l.1.. *ppro11im1trty fifrHn 1ingl1*1pac1 rypowritr.n linnJ (18)
Three Containment Purge/Pressure-Vacuum Relief (CP/P-VR) System isolation events occurred on 2/16/91, 2/20/91 and 2/27/91. They were initiated by the lRllA Radiation Monitoring System (RMS) Containment Particulate Radiation Monitor channel. The CP/P~VR System isolation is an Engineered Safety System (ESF). On 2/16/91 and 2/20/91, the isolation valves were closed at the time of the signal actuation; they did not change position as a result of the isolation signal. On 2/27/91, Containment Purge was in progress at the time of the* signal actuation; the isolation valves closed as designed. The Unit was in Mode 5 on 2/16/91 _and 2/20/91; it was in Mode 6 during the 2/27 /91 event. Tech. Spe~. 3.9.9 Action Statement was entered after the 2/27/91 event. The lRllA channel is not required to be operable in Mode 5. The cause of the 3 CP/P-VR System isolation signal events is attributed to equipment failure. The lRllA channel circuit board contacts and the reset switch contacts were found oxidized. The root cause of tjlis event is attributed to inadequate administrative controls. Analysis of recurring failures of this RMS chan_nel and.
other RMS channels failed to adequately define appropriate preventive maintenance. The lRllA channel reset switch contacts and .the circuit board connections were cleaned. Upon successful completion of a channel check, the lRllA channel was returned to service. The Tech.
Spec. 3.9.9 Action Statement was exited on 2/28/91. As indicated in prior LERs, engineering has investigated the concerns with the Salem U-1 and U-2 RMS c:i..1.a.1n-.1.els. Dt::bign modifications include a proposal i.oi:
RMS channel equivalent replacement~
NRC f<>rm 311-5 19.fP.il
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Genera_ting Station DOCKET NUMBER LER NUMBER PAGE Unit 1 - 5000272 91-006-00 2 of 5 PLANT AND SYSTEM IDENTIFICATION:
Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xxl IDENTIFICATION OF OCCURRENCE:
Engineered Safety Feature actuation signals for Containment Purge/Pressure-Vacuum Relief System isolation from the lRllA Radiation Monitoring System channel Event Dates: 2/16/91, 2/20/91 and 2/27/91 Report Date: 3/18/91 This report was initiated by Incident Report Nos.91-103, 91-124, and 91-149.
CONDITIONS PRIOR TO OCCURRENCE:
2/16/91: Mode 5 (Cold Shutdown): gt* Refueling Outage DESCRIPTION OF OCCURRENCE:
This LER addresses three (3) Containment Purge/Pressure-Vacuum Relief (CP/P-VR) System {BFI isolation events occurring on February 16, 1991, February 20, 1991 and February 27, 1991. All three (3) actuation signals were initiated by the lRllA Radiation Monitoring System (RMS) {ILi Containment Particulate Radiation Monitor channel.
On February 16, 1991 at 0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />, with the Unit in Mode 5, a Containment Purge/Pressure-Vacuum Relief (CP/P-VR) System isolation signal actuated as a result of a high channel spike on the lRllA channel. On February is, 1991 at 1653 hours0.0191 days <br />0.459 hours <br />0.00273 weeks <br />6.289665e-4 months <br />, the channel's sample pump and sample filter paper drive motor had been deenergized in support of outage related activities. The lRllA RMS channel is not required to be operable in Mode 5. The isolation valves were closed at the time of the signal actuation; they did not change position as a result of the isolation signal.
Initial review of the strip chart indication, for the February 16, 1991 event, indicated that the actuation may have been the result of high activity; therefore, troubleshooting was not performed.
However, subsequent review did not subs~antiate this conclusion.
On February 19, 1991 the 1R11A and 1R12A channel setpoints (alarm and warning) were changed to 2X background as per Technical Specifications in support of the upcoming Unit mode change to Mode 6 (accomplished on February 20, 1991 at 1840 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.0012e-4 months <br />). The lRllA alarm setpoint was set at 5600 cpm.
On February 20, 1991 at 0203 hours0.00235 days <br />0.0564 hours <br />3.356481e-4 weeks <br />7.72415e-5 months <br />, with the Unit in Mode 5, the 1~_:;_:_]:_ (.~1ar1i.lc~ '-<i.~c.l..tax...:: t..i.~o.~LJ., .i::i=sultirL9 iJ..l c.. CP/P-""lH. S:;{bLt.lii isolatior.L
LICENSEE EVENT REPORT (LER) TEXT CONTINUAT!ON Salem Generating Station DOCKET NUMBER ~ER HUMBER PAGE Unit 1. 5000272 *91-006-00 3 of 5 DESCRIPTION OF OCCURRENCE: (cont'd) signal actuation. The alarm was believed to b~ a result of the _lower alarm setpoint setting (tefere~ce LER 272/91-010-00): therefore, troubleshooting was*not performed. However, subsequent review did not substantiate this conclusion.
On February 27, 1991 at 1735 hours0.0201 days <br />0.482 hours <br />0.00287 weeks <br />6.601675e-4 months <br />, with the Unit in Mode 6, a Containment Purge/Pressure-Vacuum Relief System (CP/P-VRS) isolation signal was initiated by the lRllA RMS channel. At the time of the event, Containment Purge was in progress. The isolation valves closed as designed upon receipt of the signal.
At the time of the February 27, 1991 event, an operator was resetting a lRllA chaimel warning alarm. The alarm signal actuated as the warning.alarm was reset. SubsGquently, a work order was initiated and cor~ective maintenance was performed.
Technical Specification 3.3.3.1 Action *22 was entered. It states:
"With the number of channels OPERABLE less than required by* the Minimum Channels OPERABLE requirement, comply with .the Action*
requirements of Specification 3.9.9."
- Technical Specification*3.9.9 Action Statement states:
I "With the Containment* Purge and Pressure-Vacuum Relief isolation system inoperable, close each of the Purge and Pressure-Vacuum Relief penetrations providing direct access from the containment atmosphere to the outside atmosphere. The provision of Specification 3. 0 ~ 3 are not applicable.*"
The CP/P-VR System isolation is considered an Engineered Safety System {ESF). Therefore, on February 16, 1991 at 0150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />, February 20, 1991 at 0235 hours0.00272 days <br />0.0653 hours <br />3.885582e-4 weeks <br />8.94175e-5 months <br />, and February 27, 1991 at 2010 h6urs, the Nuclear Regulatory Commission was notified of the automatic actuation signals for CP/P-VR System isolation in accordance with Code of Federal Regulations lOCF,R 50.72{b) (2) (ii).
APPARENT CAUSE OF OCCURRENCE:
The cause of the three (3) CP/P-VR System isolation signal events is attributed to equipment failure. The 1R11A channel circuit board contacts ~nd the reset switch contacts were found to be oxidized.
The root cause of this event is attributed to inadequate administrative controls. Analysis of recurring failures of this RMS channel and other RMS channels failed to adequately define appro~riate preventive maintenance. Specifically, LER 272/90-001-00 required a review of the preventive maintenance program associated with the lRllA channel. The review concluded that additional preventive maintenance was not warranted due to the potential of damaging the circuit connections by the act of installing/removing circuit cards. Also, the channel components have been scheduled to
. be ~~pl~~--: ~- i~~i=;~~~ by LE~ ~72/90-034~C1.
'I
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Statiori DOCKET NUMBER* * -LER NUMBER . PAGE Unit 1 . 5000272 91-006-00 4 of 5 APPARENT CAUSE OF OCCURRENCE: (cont'd)
LER 311/90-044-00 initiated a commitment to investigate possible interim measures which can be taken to minimize the possibility of
- channel failures (resulting in ESF actuations}. These measures are still in review. This investigation will also be used to identify and implement appropriate preventive maintenance requirements.
ANALYSIS OF OCCURRENCE:
The 1R11A, Containment Particulate Monitor, (a NaI scintillation type detector, model LFE MDSB} monitors the air particulate gamma radioactivity in the Containment atmosphere.
- it is used in the identification of RCS leakage in conjunction with the containment pocket sump level monitoring syste_m,. the containment fan cooler condensate flow rate monitors, and the containment atmosphere gaseous radioactivity (1R12A) RMS channel.
- An alarm signal will cause the automatic isolation of the CP/P-VRS. In Mode
~. it is used to corroborate 1R12A radiation monitor indications of a fuel handling accident to provide early isolation of the Containment in the event of an accident.
- Air samples are pulled di_rectly from the Containment atmosphere through.a filter paper which.continuously inoves past the lR!°lA scintillation detector. After the air sample passes through the filter paper, it passes through a charcoal cart~idge (moni~ored.by the 1R12B monitor) and is then mixed into a fixed .shielded volume where it. is viewed by the 1R12A noble gas monitor. The* air sample is then returned to the Containment.
Several area radiation* monitors, in addition to the 1R12A moni.tor, .
are us.ed *to corroborate* the 1R11A channel's indications. The corroborating area radiation monitors do not have isolation capabilities. They only have alarm capability. l During the 1R11A channel spikes, Containment particulate airborne activity did not increase (as indicated by the corroborating RMS channels}. These CP/P-VR System isolation signals. are the result of an equipment failure. Therefore, these events did not affect the health or safety of the public. However, due to the automatic actuation signal of an ESF system, it is reportable in accordance
.with Code of Federal Regulations 10CFR 50.73(a}(2) (iv).
CORRECTIVE ACTION:
The 1R11A channel reset switch* contacts and the circuit board connections were cleaned. Upon successful completion of a channel check, the lRllA channel was *returned to service. The Technical
~pecific~tion 3.9.9 Action Statement was exited on February 28, 1991 at 0310 hours0.00359 days <br />0.0861 hours <br />5.125661e-4 weeks <br />1.17955e-4 months <br />.
As previously committed to by LER 311/90-044-00, interim actions to limit. the number of RMS channel failures are being evaluated. These actions include review of maintenance techniques and procedures.
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 . . 50*00212 91-006,-00 5 of 5 CORRECTIVE ACTION: . (cont'd).
As indicated in.prior LERs, engineering ;has investigated the. concerns w.ith the Salem U-1 and *u-~ RMS channels. Design modifications
.include a proposal for _RMS channel equivalent replacement.
G~neral Manager -
Salem Operations MJP:pc SORC Mtg.91-029
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