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| * MONTH DAY YEAR YEAR J:t SE~~~~~~AL t? ~~~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI Salem Unit 1 o 15 I o I o I o I 2 I 71 2 oI5 21'1 9 3 9I 3 - oIo I s - q1 o 1s 2 6 I 91 3 I OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE R!,.QUIREMENTS OF 10 CFR §: (Ch*ck on* or more of the following) (111 MODE IBI 3 | | * MONTH DAY YEAR YEAR J:t SE~~~~~~AL t? ~~~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI Salem Unit 1 o 15 I o I o I o I 2 I 71 2 oI5 21'1 9 3 9I 3 - oIo I s - q1 o 1s 2 6 I 91 3 I OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE R!,.QUIREMENTS OF 10 CFR §: (Ch*ck on* or more of the following) (111 MODE IBI 3 |
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| '20.402lbl 20.405lcl 50.73(*112llivl 73.71lbl | | '20.402lbl 20.405lcl 50.73(*112llivl 73.71lbl POWER |
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| | * LEVEL 1101 0 I 010 - 20.405(*111 llil 20 ...05{*111 lllil 50.3Slcll11 50.38lcll21 * -,_ |
| POWER | | x - 50.73l*ll2llvl 50.731*11211viil 73.i11cl OTHER IS1H1cify in Abstr*ct btJ!ow and in Text, NRC F.orm 20.4051*111 llilil 50,731*112llil 50,73l*ll21lviiil IAI 366AI 20 *..051*111 llivl |
| * LEVEL 1101 0 I 010 - 20.405(*111 llil 20 ...05{*111 lllil | |
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| 50.3Slcll11 50.38lcll21 * -,_ | |
| x - 50.73l*ll2llvl 50.731*11211viil | |
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| 73.i11cl OTHER IS1H1cify in Abstr*ct | |
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| btJ!ow and in Text, NRC F.orm 20.4051*111 llilil 50,731*112llil 50,73l*ll21lviiil IAI 366AI 20 *..051*111 llivl | |
| - 50.73(*112lliil 50.731*112llviiillBI 20.4051*111 IM | | - 50.73(*112lliil 50.731*112llviiillBI 20.4051*111 IM |
| - 50.731*112lliiil 50.731*112llxl LICENSEE CONTACT FOR THIS LEA 1121 NAME TELEPHONE NUMBER AREA CODE M. J. Pastva, Jr. - LER Coordinator* 6 10 I 9 3 13 I 9 1- 15 I 1 16 15 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC* MANUFAC* | | - 50.731*112lliiil 50.731*112llxl LICENSEE CONTACT FOR THIS LEA 1121 NAME TELEPHONE NUMBER AREA CODE M. J. Pastva, Jr. - LER Coordinator* 6 10 I 9 3 13 I 9 1- 15 I 1 16 15 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC* MANUFAC* |
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| IDENTIFICATION OF OCCURRENCES: | | IDENTIFICATION OF OCCURRENCES: |
| Rod Control System Design Basis Concern (both Salem Units) | | Rod Control System Design Basis Concern (both Salem Units) |
| Event Date.: 5/27/93 Discovery Date: 6/4/93 Supplement Report Date: 8/26/93 The original report was initiated by Incident Report No. 93-263. This event is reportable in accordance with lOCFR50.73(a) (2) (v) (A). | | Event Date.: 5/27/93 Discovery Date: 6/4/93 Supplement Report Date: 8/26/93 The original report was initiated by Incident Report No. 93-263. This event is reportable in accordance with 10CFR50.73(a) (2) (v) (A). |
| CONDITIONS PRIOR TO OCCURRENCE: | | CONDITIONS PRIOR TO OCCURRENCE: |
| 5/27/93: Unit 1 - Mode. 1 - Reactor Power 100% - Unit Load 1145 MWe 5/27/93: Unit 2 - Mode 3 Reactor Power 0% - Unit Load -o- MWe; Unit 2 Reactor startup activities in progress following completion of. | | 5/27/93: Unit 1 - Mode. 1 - Reactor Power 100% - Unit Load 1145 MWe 5/27/93: Unit 2 - Mode 3 Reactor Power 0% - Unit Load -o- MWe; Unit 2 Reactor startup activities in progress following completion of. |
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| On June 4, 1993, at approximately 1700 hours, it was determined that a design basis concern exists where a single RCS failure could result in the withdrawal of a single RCCA. This resulted in an Unreviewed Safety Question in accordance with 10CFR50.59. At 1705 hours, a Unit 2 Reactor shutdown commenced and at 1734 hours the Reactor Trip Breakers were opened. The Unit was stabilized in MODE 3. | | On June 4, 1993, at approximately 1700 hours, it was determined that a design basis concern exists where a single RCS failure could result in the withdrawal of a single RCCA. This resulted in an Unreviewed Safety Question in accordance with 10CFR50.59. At 1705 hours, a Unit 2 Reactor shutdown commenced and at 1734 hours the Reactor Trip Breakers were opened. The Unit was stabilized in MODE 3. |
| A Unit 1 Justification for Continued Operation (jco) with the.RCS in manual control was provided to the NRC for review (reference letter evaluation S-C-RCS-EEE~0819 dated June 8, 1993). Following a reactor trip on June 8, 1993, Unit 1 was subsequently maintained in MODE 3 (Hot Standby) pending resolution of the design basis concern. On June 20, 1993, following restart authorization, Unit 1 was subsequently synchronized to the grid. The Unit 1 Reactor trip is rep~rted in LER 272/93~011-00. | | A Unit 1 Justification for Continued Operation (jco) with the.RCS in manual control was provided to the NRC for review (reference letter evaluation S-C-RCS-EEE~0819 dated June 8, 1993). Following a reactor trip on June 8, 1993, Unit 1 was subsequently maintained in MODE 3 (Hot Standby) pending resolution of the design basis concern. On June 20, 1993, following restart authorization, Unit 1 was subsequently synchronized to the grid. The Unit 1 Reactor trip is rep~rted in LER 272/93~011-00. |
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| SUPPLEMENTAL LICENSEE EVENT REPORT (LER) TEXT CONTINUATION . | | SUPPLEMENTAL LICENSEE EVENT REPORT (LER) TEXT CONTINUATION . |
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| Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-008-01 5 of 6 APPARENT CAUSE OF OCCURRENCE: | | Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-008-01 5 of 6 APPARENT CAUSE OF OCCURRENCE: |
| The apparent root cause of the postulated RCS single.failure design_ | | The apparent root cause of the postulated RCS single.failure design_ |
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| SUPPLEMENTAL LICENSEE EVENT REPORT {LER) TEXT CONTINUATION | | SUPPLEMENTAL LICENSEE EVENT REPORT {LER) TEXT CONTINUATION |
| *t Salem Generating Station Unit 2 . | | *t Salem Generating Station Unit 2 . |
| DOCKET NUMBER 5000311 LER NUMBER 93-008-01 PAGE 6 of 6 | | DOCKET NUMBER 5000311 LER NUMBER 93-008-01 PAGE 6 of 6 l |
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| | SAFETY SIGNIFICANCE: (cont'd) resulted in an Unreviewed Safety Question, in accordance with 10CFR50.59. However, by taking .credit for the available generic thermal margins, the .Departure from Nucleate Boiling Ratio (DNBR) limit is still met. on June 17, 1993, Public Service *Electric and Gas Company (PSE&G), requested an Emergency Amendment to the Operating License, for both Salem Units, to address the potential RCS single failure analysis. |
| l SAFETY SIGNIFICANCE: (cont'd) resulted in an Unreviewed Safety Question, in accordance with 10CFR50.59. However, by taking .credit for the available generic thermal margins, the .Departure from Nucleate Boiling Ratio (DNBR) limit is still met. on June 17, 1993, Public Service *Electric and Gas Company (PSE&G), requested an Emergency Amendment to the Operating License, for both Salem Units, to address the potential RCS single failure analysis.
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| CORRECTIVE ACTION: | | CORRECTIVE ACTION: |
| _On June 17, 1993, Public Service Electric and Gas Company (PSE&G); | | _On June 17, 1993, Public Service Electric and Gas Company (PSE&G); |
LER 93-008-01:on 930527,control Rod 1SA3 Withdrew to Approx 15 Steps from Fully Inserted in Response to Manual Insertion Command Due to Failure of Integrated Circuit Chips.Emergency License Amend Requested on 930617ML18100A581 |
Person / Time |
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Site: |
Salem ![PSEG icon.png](/w/images/c/cc/PSEG_icon.png) |
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Issue date: |
08/26/1993 |
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From: |
Pastva M Public Service Enterprise Group |
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To: |
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Shared Package |
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ML18100A580 |
List: |
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References |
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LER-93-008, LER-93-8, NUDOCS 9309030268 |
Download: ML18100A581 (6) |
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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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{{#Wiki_filter:NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION 16-891 APPROVED OMB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS
- INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LERI COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP-530). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104). OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME (1) DOCKET NUMBER (21 I PAGE 131 Salem Generating Station - Unit 2 TITLE 141 I o 15 I o Io I o 13 I 11 l 1 !oF .01 6 Rod Control System Design Basis Concern (both Salem Units).
EVENT DATE (5) LEA NUMBER (61 REPORT DATE (71 OTHER FACILITIES INVOLVED IBI
- MONTH DAY YEAR YEAR J:t SE~~~~~~AL t? ~~~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI Salem Unit 1 o 15 I o I o I o I 2 I 71 2 oI5 21'1 9 3 9I 3 - oIo I s - q1 o 1s 2 6 I 91 3 I OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE R!,.QUIREMENTS OF 10 CFR §: (Ch*ck on* or more of the following) (111 MODE IBI 3
I
'20.402lbl 20.405lcl 50.73(*112llivl 73.71lbl POWER
- LEVEL 1101 0 I 010 - 20.405(*111 llil 20 ...05{*111 lllil 50.3Slcll11 50.38lcll21 * -,_
x - 50.73l*ll2llvl 50.731*11211viil 73.i11cl OTHER IS1H1cify in Abstr*ct btJ!ow and in Text, NRC F.orm 20.4051*111 llilil 50,731*112llil 50,73l*ll21lviiil IAI 366AI 20 *..051*111 llivl
- 50.73(*112lliil 50.731*112llviiillBI 20.4051*111 IM
- 50.731*112lliiil 50.731*112llxl LICENSEE CONTACT FOR THIS LEA 1121 NAME TELEPHONE NUMBER AREA CODE M. J. Pastva, Jr. - LER Coordinator* 6 10 I 9 3 13 I 9 1- 15 I 1 16 15 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC* MANUFAC*
CAUSE SYSTEM COMPONENT TUR ER TUR ER x A1A E1C I B1D w I 112 I 0 y ::::::::::::::=:.. ::::,:::::::::::::.. : ~: : :..::::: . I I I I I. I I x A IA E IC I Bl D W 1* 112 I 0 y I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED
~NO SUBMISSION DATE 1151
---, YES (If yes. complot* EXPECTED SUBMISSION DATE)
I I I ABSTRACT (Limit to 1400 spaces, i.tJ., approximtJttJ/y fiftetm single-spac~ typewritten lines) 116)
During Unit 2 Reactor startup activities, following the unit's 7th refuel outage, it was determined on 6/4/93 that a postulated single failure concern existed where failure of one Rod Control System slave cycler decoder card, in conjunction with a rod motion command signal, may cause an unplanned Rod Control Cluster Assembly (RCCA) withdrawal.. At 1734 hours, all control rods were inserted, the Reactor trip breakers were opened, and the Unit *was stabilized in MODE 3. On 5/27/93, at 1844 hours, rod 1SA3 had withdrawn approximately 15 step~ from fully inserted following a manual insertion command. Rod control power was then deenergized to fully insert the rod. The RCS single failure concern is attributed to RCS design. 1SA3 withdrew as the result of inappropriate current orders to the RCCA. Integrated circuit chips on two slave cycler decoder cards had failed due to the relay* driver circuit card connector Pin No. 4 not making electrical contact with the surge suppression diode. Pin No. 4 was repaired.and the slave cycler cards were replaced to restore operability of rod 1SA3. An additional corrective action was installation of suppression diodes on the rod step counters of the RCS circuitry, of each unit, to mitigate consequences of an open or bad connection on the relay driver circuit card connector pin No. 4. All Unit 2 RCS logic cards.were replaced and satisfactorily tested and all RCS Power Cabinet cards were pulled, visually inspected, and retested satisfactorily. On 6/29/93 Unit 2 was taken critical.
9309030268 -930.826 1*.i PDR ADDCK
NRC Form 366 16-891 S PDR ' ~
*I SUPPLEMENTAL LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE Unit 2 50003*11 93-008-01 2 of 6 PLANT AND SYSTEM IDENTIFICATION:
Westinghouse - Pressurized Water Reactor.
Energy Industry Identification System (EIIS) codes and component function identifiers are identified in the text as-{xx/xx}
IDENTIFICATION OF OCCURRENCES:
Rod Control System Design Basis Concern (both Salem Units)
Event Date.: 5/27/93 Discovery Date: 6/4/93 Supplement Report Date: 8/26/93 The original report was initiated by Incident Report No. 93-263. This event is reportable in accordance with 10CFR50.73(a) (2) (v) (A).
CONDITIONS PRIOR TO OCCURRENCE:
5/27/93: Unit 1 - Mode. 1 - Reactor Power 100% - Unit Load 1145 MWe 5/27/93: Unit 2 - Mode 3 Reactor Power 0% - Unit Load -o- MWe; Unit 2 Reactor startup activities in progress following completion of.
the unit's seventh refueling outage.
DESCRIPTION OF OCCURRENCE:
on May 27, 1993, at 1844 hours, _control rod 1SA3 withdrew to .
approximately 15 steps from fully inserted in response to a manual insertion command (rod full out is 228 steps). Rod control power was deenergized to fully insert the rod. on June 4, 1993 at approximately 1700 hours, investigation determined that a single failure in the Rod Control System (RCS) could possibly result in a single rod withdrawal.
event (applicable to both Salem Units). All control rods on Unit 2 were inserted at 1734 hours, the Reactor trip breakers were opened, and the Unit was stabilized in MODE 3. A Justification for Continued Operation (JCO) of Unit 1, with the RCS in manual control, was provided to the NRC on June 8, 1993 (reference evaluation S-C-RCS-EEE-0819).
The Nuclear Regulatory commission (NRC) was notified of this event in accordance with the requirements of Code of Federal Regulations 10CFR50.72(b) (1) (ii) (B). The identified failure is conservatively postulated to be a single failure. The Updated Final Safety Analysis Report (UFSAR) states that only multiple failures would cause the withdrawal of a single Rod Cluster Control Assembly (RCCA). This condition in which a single RCCA withdrew results in an Unreviewed
SUPPLEMENTAL LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-008-01 3 of 6 DESCRIPTION OF OCCURRENCE: (cont'd)
Safety Question, per 10CFR50.59. Public Ser~ice Electric and Gas
{PSE&G) submitted an Emergency License Amendment to the operating License (for both Salem Units) to address the postulated RCS single failure.
ANALYSIS OF OCCURRENCE:
The RCS {AA} is used to withdraw control rods for reactor startup and to cqntrol reactor power during power operation. It consists of one Logic c,abinet, five Power Cabinets, and one Direct current "(DC) Hold Cabinet:
The Logic Cabinet translates manually initiated or automatic commands into signals required by the Power Cabinets to step the banks of Shutdown and Control rod assemblies. This cabinet contains power supply assemblies and processes logic commands required for rod movements. -
The Power Cabinets provide DC power.pulses to drive the Control Rod Drive Mechanisms {CRDMs) by converting three-phase alternating current {AC) power to DC power and applying it to the CROM magnetic coils.
The DC Hold Cabinet is used to supply power to the stationary
.gripper coi_ls of one group when required by Power Cabinet maintenance.
Westinghouse was contracted for full RCS refurbishment service during
- the Unit 2 seventh refueling/maintenance outage to avoid aging-related RCS circuit card failures. Wes'tinghouse supervised removal and testing of RCS logic cabinet and power cabinet printed c~rcuit cards, and their return to service. Numerous card problems were repaired, including suspect solder joints, arced and pitted terminals, and bad resistors.
On May 25, 1993,* the PSE&G Controls Group satisfactorily -completed Individual Rod Position Indication {!RPI) calibrations and Control Rod Drop testing. At 2300 hours (same day), following.completion of prerequisite testing, initial reactor startup commenced. After encountering various RCS card failures, all control rods were inserted. _The cards were replaced or repaired, car¢l edge connectors adjusted, and rod testing was completed satisfactorily. It was during these repairs to the RCS that Pin No. 4 of the relay driver was repaired.
bn May 27, 1993 at 1837 hours, reactor startup commenced. At 1844 hours, when- Shutdown Bank A was withdrawn to 20 steps, the Individual Rod Position Indicators (IRPis) did not indicate rod movement. A rod insertion signal was applied to the bank. As the
SUPPLEMENTAL LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem* Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 . 5000311 93-008-01 4 of 6 l ANALYSIS OF OCCURRENCE: (cont'd) group step counter indication decreased from*20 too steps, the IRPI for rod 1SA3 indicated a rod withdrawal to 15 steps. The position of 1SA3 was verified and rod control power fuses w*ere removed to reinsert (drop) the rod. Troubleshooting revealed the withdrawal of 1SA3 RCCA was caused by failure of integrated circuit chips on two. RCS slave 1*
cycler decoder cards. This failure resulted in inappropriate current orders being supplied to and simultaneously energizing the RCCA lift, movable, and stationary coils of all eight rods in Shutdown Bank A.
The sequence of these current orders was such that the most probable result wo~ld be outward rod motion for all rods in the bank. However, only 1SA3 withdrew. The*two logic cards (slave cycler decod~rs) were replaced with new, tested_ cards.
On May 28, 1993, a* functional check of.the Logic Cabinet was.
satisfactorily completed. In addition, a recorder was connected to monitor the RCS 15 VDC power supplies. Station management obtained Westinghouse assurance that the May*21th withdrawal of 1SA3 had not damaged the rod- control rod drive mechanism. Post-maintenance and operability testing confirmed that the RCS was ready for reactor start-up, which commenced ,at 1512 hours. At 1812 hours, Cont.rol Bank c, Group*l rods dropped and.the Reactor was tripped manually. The reactor t~ip of May 28, 1993 is reported in LER 311/93~001~00.
Ori June 2, 1993, at 2053 hours, following satisfactory RCS post~maintenance testing and Operations surveillance testing, a reactor startup commenced. At 2338 hours (same day) a Pulse to*Analog (P/A) converter read zero for control Rod Banks B and D.
Troubleshooting revealed a faulty supervisory data logging card with a failed integrated circuit chip and at 0347 hours (next day) all
'control rods were fully inserted. These problems were resolved ahd on Jurie 3, 1993 at 0620 hours, Reactor start-up commenced- and at 1359 hours criticality was achieved.
On June 4, 1993, at approximately 1700 hours, it was determined that a design basis concern exists where a single RCS failure could result in the withdrawal of a single RCCA. This resulted in an Unreviewed Safety Question in accordance with 10CFR50.59. At 1705 hours, a Unit 2 Reactor shutdown commenced and at 1734 hours the Reactor Trip Breakers were opened. The Unit was stabilized in MODE 3.
A Unit 1 Justification for Continued Operation (jco) with the.RCS in manual control was provided to the NRC for review (reference letter evaluation S-C-RCS-EEE~0819 dated June 8, 1993). Following a reactor trip on June 8, 1993, Unit 1 was subsequently maintained in MODE 3 (Hot Standby) pending resolution of the design basis concern. On June 20, 1993, following restart authorization, Unit 1 was subsequently synchronized to the grid. The Unit 1 Reactor trip is rep~rted in LER 272/93~011-00.
I i
SUPPLEMENTAL LICENSEE EVENT REPORT (LER) TEXT CONTINUATION .
Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-008-01 5 of 6 APPARENT CAUSE OF OCCURRENCE:
The apparent root cause of the postulated RCS single.failure design_
basis concern is "Design, Manufacturing, Construction/Installation" inadequacy, as per NUREG-1022. Subsequent testing and evaluation has demonstrated that failure of one slave cycler decoder card of an RCCA in conjunction with a rod motion command signal may cause an unplanned RCCA withdrawal. * *
- 1SA3 withdrew due to failure of integrated circuit chips*on _the 22AC and 22BD slave cycler decoder cards {AA/ECBD}. This resulted in
- inappropriate current orders being supplied to the RCCA operating.
coils causing the rod lift, movable, and stationary coils to energize at the same time. Although the current orders produced did not
- replicate those requi'red for a. normal rod withdrawal, the form of t_he resulting current orders was such that the most probable result would.
be outward rod motion. However, only 1SA3 withdrew. The reason why on1y*1sA3 withdrew has been attributed to manufacturing tolerances.
The Westinghouse owners Group is continuing to pursue resolution of this issue;;
Failure of the integrated circuit (IC) chips resulted from the relay driver circuit card not making electrical contact with the surge suppression diode in the circuit. This allowed the back electromagnetic field from the RCS step counters to apply voltage transients to the components of the Logic Cabinet's circuit cards which caused failure of the cards' IC chips. The poor electrical connection was caused by a spread pin (no. 4) on the logic card.
connector. The diodes suppress counter-electromotive force (CEMF) from the collapsing field coil of the group step demand indicators PRIOR OCCURRENCES:
This is the first occurrence of a single control rod withdrawal at either Salem Unit.
SAFETY SIGNIFICANCE:
This event did not affect the health and safety of the public. The.
current Licensing basis, as described in UFSAR sections 4.3 and 15.3.5, assumes that only multiple failures would cause the withdrawal of a single Rod Cluster Control Assembly (RCCA). PSE&G now considers this event as an American Nuclear Standards Institute (ANSI) Condition II "FAULTS OF MODERATE FREQUENCY" event rather than a Condition III "INFREQUENT FAULTS" event. The Amendment/JCO issued June 17, 1993, discusses this in detail.
For the current fuel cycles on each unit, analysis indicates two adjacent rods withdrawn from Control Rod Bank D (one from each group) is more limiting than one rod withdrawn from Control Bank D, which is addressed by UFSAR section 15.3.5. This increase in probability
9*
SUPPLEMENTAL LICENSEE EVENT REPORT {LER) TEXT CONTINUATION
- t Salem Generating Station Unit 2 .
DOCKET NUMBER 5000311 LER NUMBER 93-008-01 PAGE 6 of 6 l
SAFETY SIGNIFICANCE: (cont'd) resulted in an Unreviewed Safety Question, in accordance with 10CFR50.59. However, by taking .credit for the available generic thermal margins, the .Departure from Nucleate Boiling Ratio (DNBR) limit is still met. on June 17, 1993, Public Service *Electric and Gas Company (PSE&G), requested an Emergency Amendment to the Operating License, for both Salem Units, to address the potential RCS single failure analysis.
CORRECTIVE ACTION:
_On June 17, 1993, Public Service Electric and Gas Company (PSE&G);
requested an Emergency License Amendment to the Operating License/Justification.for Continued Operation, for both Salem Units, to address the postulated RCS single failure (reference NLR-N93098).
'The RCS Logic Cabinet slave cycler stationary decoder card,*
Westinghouse Part No. 3359C62G02, and the slave cycler ll,lovable card, Westinghouse Part No. 3359C62G03, were replaced to restore operability*
of rod 1SA3.
Additional suppression diodes were installed on the group step demand indicators (the source of the CEMF) of the RCS circuitry of each Unit. This action eliminates the consequences of an open or bad
. connection on the relay driver circuit card connector pin no. 4.
All RCS logic cards on Unit 2 were replaced and satisfactorily tested. In addition, all RCS Power Cabinet cards were pulled, visually inspected, and satisfactorily retested.
Additional immediate corrective actions to this event, as committed to on June 18, 1993 in a meeting at NRC Region I, have been implemented.
PSE&G Nuclear Fuels will incorporate this new Condition II event into the fuel .reload safety analysis for each unit.
The UFSAR will be reviewed and revised as appropriate in reference to this event.
Recommendations resulting from the Westinghouse owners Group evaluation of this event wiil be evaluated.
U.
General Manager -
Salem Operations MJPJ:pc SORC Mtg. 93-081}}