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| }] REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISl NUMBER NUMBER 01s1010101 I I 1 12 il3 912 -ol ii? -olo 0!1 19 913 9 2 2 01s1010101 I I OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE R"-OUIREMENTS OF 10 CFR §: (Ch*ck on* or mor* of th* following/ | | }] REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISl NUMBER NUMBER 01s1010101 I I 1 12 il3 912 -ol ii? -olo 0!1 19 913 9 2 2 01s1010101 I I OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE R"-OUIREMENTS OF 10 CFR §: (Ch*ck on* or mor* of th* following/ |
| 1111 MODE 191 1 Z0.402(bl 20.405lcl 50,73111121livl 73.71lbl -----POWER 20.4061*111 llil 50.311lcll1l 50.73111121M 73.71 lcl LEVEL ------1101 0 9 9 20.4051*11111lil 50.311lcll21 50.731111211viil x OTHER (Specify in Abstr1ct ---bolow *nd in Tt1xt. NRC Form .. ,. 20.4081*111 llilll 50.731*11211il . .. 50.7311112llviiillAI J66AI ........ --. ,., .... 20.40611111 llivl 50.7311112lliil 50.7311112llviiillBI Voluntary | | 1111 MODE 191 1 Z0.402(bl 20.405lcl 50,73111121livl 73.71lbl -----POWER 20.4061*111 llil 50.311lcll1l 50.73111121M 73.71 lcl LEVEL ------1101 0 9 9 20.4051*11111lil 50.311lcll21 50.731111211viil x OTHER (Specify in Abstr1ct ---bolow *nd in Tt1xt. NRC Form .. ,. 20.4081*111 llilll 50.731*11211il . .. 50.7311112llviiillAI J66AI ........ --. ,., .... 20.40611111 llivl 50.7311112lliil 50.7311112llviiillBI Voluntary |
| .... , ... .... --, ... ,., 20.40811111 JM 50.731*11211iiil 50.731*112llxl LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER AREA CODE M. J. Pollack -LER Coordinator 61019 31319 I-12 I 01212 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC-REPORTABLE | | .... , ... .... --, ... ,., 20.40811111 JM 50.731*11211iiil 50.731*112llxl LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER AREA CODE M. J. Pollack -LER Coordinator 61019 31319 I-12 I 01212 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC-REPORTABLE |
| :-:*:*:-:*:-:.:*:*:*:*:*:*:*:*:*:*:.:*:*:-:*:-:*:*:*. | | :-:*:*:-:*:-:.:*:*:*:*:*:*:*:*:*:*:.:*:*:-:*:-:*:*:*. |
| MANUFAC* REPORTABLE | | MANUFAC* REPORTABLE |
| : :*:.:,,,:.::::*'Ji'.:':''.:,::::::::::*:::::::::::!: | | : :*:.:,,,:.::::*'Ji'.:':''.:,::::::::::*:::::::::::!: |
| CAUSE SYSTEM COMPONENT | | CAUSE SYSTEM COMPONENT |
| :-:-:-:-:-:*:.:*:*:*:*:*:*:*:.:*:*:*:-:*:*:*:*:*:*:* | | :-:-:-:-:-:*:.:*:*:*:*:*:*:*:.:*:*:*:-:*:*:*:*:*:*:* |
| CAUSE SYSTEM COMPONENT TUR ER TO NPRDS ::::;::::::::::::::::'::::::::::::;:;:::::::::::;:;: | | CAUSE SYSTEM COMPONENT TUR ER TO NPRDS ::::;::::::::::::::::'::::::::::::;:;:::::::::::;:;: |
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| .......... , ........... | | .......... , ........... |
| ;.;o;.;o;o;.;.;o:.;*:*:*:*:*:*:*:.:.:*:<*:<*:*:-:* | | ;.;o;.;o;o;.;.;o:.;*:*:*:*:*:*:*:.:.:*:<*:<*:*:-:* |
| *:*:*:*:*:*:*:*:*:*:<*:*:.: | | *:*:*:*:*:*:*:*:*:*:<*:*:.: |
| :::::?:::::::::::: | | :::::?:::::::::::: |
| I I I I I I I :*:*:*:*:*:*:*:*:*:*:*:*:*:*:-:*:.:*:*:-:*:*:*:*:*:* | | 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 MONTH D y YEAR EXPECTED SUBMISSION n YES (If yos. comp/ato EXPECTED SUBMISSION DATE/ DATE 1151 NO I I I ABSTRACT (Limit to 1400 S/JllCtJS, i.e .. 1Jpproxim*tt1ly fiftst1n 1inglt1*spact1 typewritten lines) (16) On 12/13/92, at 2122 hours, control Room personnel observed that Overhead Annunciators (OHAs) were not alarming upon receipt of alarm signals. The OHAs were returned to service at 2123 hours that day. They had stopped annunciating at 1946 hours. The Auxiliary Alarm System and other Control Room alarms and indicators continued to function. | | SUPPLEMENTAL REPORT EXPECTED 1141 MONTH D y YEAR EXPECTED SUBMISSION n YES (If yos. comp/ato EXPECTED SUBMISSION DATE/ DATE 1151 NO I I I ABSTRACT (Limit to 1400 S/JllCtJS, i.e .. 1Jpproxim*tt1ly fiftst1n 1inglt1*spact1 typewritten lines) (16) On 12/13/92, at 2122 hours, control Room personnel observed that Overhead Annunciators (OHAs) were not alarming upon receipt of alarm signals. The OHAs were returned to service at 2123 hours that day. They had stopped annunciating at 1946 hours. The Auxiliary Alarm System and other Control Room alarms and indicators continued to function. |
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| -the alarm is reset OHA A-45 annunciates | | -the alarm is reset OHA A-45 annunciates |
| -the alarm is not cleared in support of further investigation LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 DOCKET NUMBER 5000311 LER NUMBER 92-017-00 PAGE 3 of 6 SEQUENCE OF EVENTS: Time (Hours) -1soo 1946 1955 2008 2122 2123 Event Operations personnel access the Beta Remote Control Workstation to obtain information on OHA A-45 Beta System CRT display clock stops updating AAS prints "Chilled Water Expansion Tank Level Low"; the associated OHA for "AUX ALM SYS PRINTER" does not alarm Operations responds to the AAS printout by directing an Equipment Operator to fill the tank; the absence of the OHA actuation is not recognized by Operations Radiation Monitor channels 2R13A and 2R13B causes the "Radiation Alarm Process" alarm to actuate on the 2RP1 Control R90m panel; OHA A-6, "RMS TRBL", does not alarm Operations personnel respond to the 2RP1 alarm The "Chilled Water Expansion Tank Level Low" alarm returns to normal. This prints out on the AAS typewriter. | | -the alarm is not cleared in support of further investigation LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 DOCKET NUMBER 5000311 LER NUMBER 92-017-00 PAGE 3 of 6 SEQUENCE OF EVENTS: Time (Hours) -1soo 1946 1955 2008 2122 2123 Event Operations personnel access the Beta Remote Control Workstation to obtain information on OHA A-45 Beta System CRT display clock stops updating AAS prints "Chilled Water Expansion Tank Level Low"; the associated OHA for "AUX ALM SYS PRINTER" does not alarm Operations responds to the AAS printout by directing an Equipment Operator to fill the tank; the absence of the OHA actuation is not recognized by Operations Radiation Monitor channels 2R13A and 2R13B causes the "Radiation Alarm Process" alarm to actuate on the 2RP1 Control R90m panel; OHA A-6, "RMS TRBL", does not alarm Operations personnel respond to the 2RP1 alarm The "Chilled Water Expansion Tank Level Low" alarm returns to normal. This prints out on the AAS typewriter. |
| NCO's recognize that the OHA A-41 does not annunciate and that the clock on the OHA CRT is indicating 1946 hours and not updating Operations personnel reset Sequential Event Recorders (SERs) "A" and "B"; four (4) OHA alarms annunciate | | NCO's recognize that the OHA A-41 does not annunciate and that the clock on the OHA CRT is indicating 1946 hours and not updating Operations personnel reset Sequential Event Recorders (SERs) "A" and "B"; four (4) OHA alarms annunciate |
| : 1. Annunciator Logic; 2. RMS Trouble; 3. 104 Panel Trouble; and 4. AAS Printer. APPARENT CAUSE OF OCCURRENCE: | | : 1. Annunciator Logic; 2. RMS Trouble; 3. 104 Panel Trouble; and 4. AAS Printer. APPARENT CAUSE OF OCCURRENCE: |
| The root cause of this event is "Design, Manufacturing, Construction/ | | The root cause of this event is "Design, Manufacturing, Construction/ |
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| Contrary to the procedure, Operators did not ensure the "Black Box" switch was in the "SER A" position. | | Contrary to the procedure, Operators did not ensure the "Black Box" switch was in the "SER A" position. |
| The operator then loaded the PC installed "PROCOM" software program and inadvertently pressed the "Cntrl L" keys twice, instead of the "Alt L" keys, resulting in the controller being in a:* "wait for information from the keyboard" mode. Causal factors associated with the root cause of this event include: 1. OHA System lockup was not readily detectable. | | The operator then loaded the PC installed "PROCOM" software program and inadvertently pressed the "Cntrl L" keys twice, instead of the "Alt L" keys, resulting in the controller being in a:* "wait for information from the keyboard" mode. Causal factors associated with the root cause of this event include: 1. OHA System lockup was not readily detectable. |
| The OHA System did not provide a direct means to inform Operations personnel that the SER had been reconfigured such that it was no longer processing inputs through to the alarm windows. 2. The design specification for the Beta OHA System did not adequately specify software security. | | The OHA System did not provide a direct means to inform Operations personnel that the SER had been reconfigured such that it was no longer processing inputs through to the alarm windows. 2. The design specification for the Beta OHA System did not adequately specify software security. |
| : 3. Procedure S2.0P-SO.ANN-OOOl(Q) was inadequate. | | : 3. Procedure S2.0P-SO.ANN-OOOl(Q) was inadequate. |
| It implied that the Beta OHA System could not be affected without use of a password. | | It implied that the Beta OHA System could not be affected without use of a password. |
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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Text
e Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station U. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 LICENSEE EVENT REPORT 92-017-00 January 29, 19931 This Licensee Event Report is a voluntary report made pursuant to the Code of Federal Regulations 10CFR 50.73. MJP:pc Distribution 9302110009 PDR ADOCK s 050038 930129 05000311 PDR The Energy People Sincerely yours, c. A. Vondra General Manager -Salem Operations NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 16-891 ,_:; EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LERI INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD 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 (3150-01041, OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. FACILITY NAME 111 l°OCKET NUMBER 121 PAGE 131 Salem Generatinq Station -Unit 2 o 1 s Io Io Io I 3111 1 loF o 16 TITLE 141 Unrecognized loss of Overhead Annunciator System alarm indication EVENT DATE 151 LER NUMBER 161 REPORT DATE 171 OTHER FACILITIES INVOLVED (Bl MONTH DAY YEAR YEAR }{:' SEQUENTIAL
}] REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISl NUMBER NUMBER 01s1010101 I I 1 12 il3 912 -ol ii? -olo 0!1 19 913 9 2 2 01s1010101 I I OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE R"-OUIREMENTS OF 10 CFR §: (Ch*ck on* or mor* of th* following/
1111 MODE 191 1 Z0.402(bl 20.405lcl 50,73111121livl 73.71lbl -----POWER 20.4061*111 llil 50.311lcll1l 50.73111121M 73.71 lcl LEVEL ------1101 0 9 9 20.4051*11111lil 50.311lcll21 50.731111211viil x OTHER (Specify in Abstr1ct ---bolow *nd in Tt1xt. NRC Form .. ,. 20.4081*111 llilll 50.731*11211il . .. 50.7311112llviiillAI J66AI ........ --. ,., .... 20.40611111 llivl 50.7311112lliil 50.7311112llviiillBI Voluntary
.... , ... .... --, ... ,., 20.40811111 JM 50.731*11211iiil 50.731*112llxl LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER AREA CODE M. J. Pollack -LER Coordinator 61019 31319 I-12 I 01212 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC-REPORTABLE
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SUPPLEMENTAL REPORT EXPECTED 1141 MONTH D y YEAR EXPECTED SUBMISSION n YES (If yos. comp/ato EXPECTED SUBMISSION DATE/ DATE 1151 NO I I I ABSTRACT (Limit to 1400 S/JllCtJS, i.e .. 1Jpproxim*tt1ly fiftst1n 1inglt1*spact1 typewritten lines) (16) On 12/13/92, at 2122 hours0.0246 days <br />0.589 hours <br />0.00351 weeks <br />8.07421e-4 months <br />, control Room personnel observed that Overhead Annunciators (OHAs) were not alarming upon receipt of alarm signals. The OHAs were returned to service at 2123 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.078015e-4 months <br /> that day. They had stopped annunciating at 1946 hours0.0225 days <br />0.541 hours <br />0.00322 weeks <br />7.40453e-4 months <br />. The Auxiliary Alarm System and other Control Room alarms and indicators continued to function.
The root cause of this event is "Design, Manufacturing, Construction/Installation".
The OHA system did not provide indication to the control room operator that the system had been reconfigured to a non operational mode preventing OHA alarm actuation.
This manifested when Operations personnel did not follow procedures in assessing the cause of the spare OHA annunciations.
The main controller will stop sending events to any connected display devices when a specific combination of commands are entered into the computer.
Operations personnel involved in this event have been disciplined.
This event will be reviewed with applicable personnel.
This event will be reviewed by the Nuclear Training Center. A third party assessment of the Beta OHA System design modification is being performed.
A design modification is being prepared to install an independent alarm circuitry system to monitor OHA operation.
Procedure S2.0P-SO.ANN-0001 was revised. OHA System preventive maintenance and corrective maintenance procedures will be developed.
Abnormal Operating Procedures, for OHA system partial or total loss, have been issued. NRC Form 366 16-891 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 DOCKET NUMBER 5000311 PLANT AND SYSTEM IDENTIFICATION:
Westinghouse
-Pressurized Water Reactor LER NUMBER 92-017-00 PAGE 2 of 6 Energy Industry Identification System (EIIS) codes are identified in the text as {xx} IDENTIFICATION OF OCCURRENCE:
Unrecognized loss of Overhead Annunciator System alarm indication Event Date: 12/13/92 Report Date: 1/29/93 This report was initiated by Incident Report No.92-822. CONDITIONS PRIOR TO OCCURRENCE:
Mode 1 Reactor Power 99% -Unit Load 1170 MWe DESCRIPTION OF OCCURRENCE:
On December 13, 1992, at 2122 hours0.0246 days <br />0.589 hours <br />0.00351 weeks <br />8.07421e-4 months <br />, Control Room personnel observed that Overhead Annunciators (OHAs) {IB} were not alarming upon receipt of alarm signals. As identified in the Sequence of Events section, the OHAs were returned to service at 2123 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.078015e-4 months <br /> that day. Investigation identified that the OHAs had stopped annunciating at 1946 hours0.0225 days <br />0.541 hours <br />0.00322 weeks <br />7.40453e-4 months <br /> (that day). The Auxiliary Alarm System (AAS) and other Control Room alarms and indicators continued to function.
The Nuclear Regulatory Commission (NRC) was notified of the OHA system loss per Code of Federal Regulations lOCFR 50.72(b) (1) (v). The OHA system electronics, for both Salem Units, were modified during the recently completed refueling outages (i.e., lRlO design modification completed on June 12, 1992 and 2R6 design modification completed on March 26, 1992). This new system is microprocessor based. It is manufactured by Beta Products Division of Hathaway Industries.
SEQUENCE OF EVENTS: Date Time (Hours) 12/12/92 -1500 12/13/92 1200 Event OHA A-45, a spare alarm, annunciates
-the alarm is reset OHA A-45 annunciates
-the alarm is not cleared in support of further investigation LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 DOCKET NUMBER 5000311 LER NUMBER 92-017-00 PAGE 3 of 6 SEQUENCE OF EVENTS: Time (Hours) -1soo 1946 1955 2008 2122 2123 Event Operations personnel access the Beta Remote Control Workstation to obtain information on OHA A-45 Beta System CRT display clock stops updating AAS prints "Chilled Water Expansion Tank Level Low"; the associated OHA for "AUX ALM SYS PRINTER" does not alarm Operations responds to the AAS printout by directing an Equipment Operator to fill the tank; the absence of the OHA actuation is not recognized by Operations Radiation Monitor channels 2R13A and 2R13B causes the "Radiation Alarm Process" alarm to actuate on the 2RP1 Control R90m panel; OHA A-6, "RMS TRBL", does not alarm Operations personnel respond to the 2RP1 alarm The "Chilled Water Expansion Tank Level Low" alarm returns to normal. This prints out on the AAS typewriter.
NCO's recognize that the OHA A-41 does not annunciate and that the clock on the OHA CRT is indicating 1946 hours0.0225 days <br />0.541 hours <br />0.00322 weeks <br />7.40453e-4 months <br /> and not updating Operations personnel reset Sequential Event Recorders (SERs) "A" and "B"; four (4) OHA alarms annunciate
- 1. Annunciator Logic; 2. RMS Trouble; 3. 104 Panel Trouble; and 4. AAS Printer. APPARENT CAUSE OF OCCURRENCE:
The root cause of this event is "Design, Manufacturing, Construction/
Installation" (per NUREG 1022, "Licensee Event Report Program").
The OHA System did not contain adequate protection to prevent inadvertent access to software control functions which would place the system in an indefinite "lockup" condition.
Investigation identified that the
. , LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 APPARENT CAUSE OF OCCURRENCE:
DOCKET NUMBER 5000311 (cont'd) LER NUMBER 92-017-00 PAGE 4 of 6 main controller will stop sending events to any display devices that are connected when a specific combination of commands are entered into the computer.
This occurs when the RCW is in the "PROCOM PLUS" program and the "Black Box" switch is in RCW-A (rather than SER-A) and the "Cntrl L" command is entered twice. A causal factor of personnel error was also a contributor to the event. The software design inadequacy was manifested when Operations personnel did not follow procedure S2.0P-SO.ANN-0001(Q), "Overhead Annunciators Operation", in assessing the cause of the spare OHA A-45 annunciations.
Contrary to the procedure, Operators did not ensure the "Black Box" switch was in the "SER A" position.
The operator then loaded the PC installed "PROCOM" software program and inadvertently pressed the "Cntrl L" keys twice, instead of the "Alt L" keys, resulting in the controller being in a:* "wait for information from the keyboard" mode. Causal factors associated with the root cause of this event include: 1. OHA System lockup was not readily detectable.
The OHA System did not provide a direct means to inform Operations personnel that the SER had been reconfigured such that it was no longer processing inputs through to the alarm windows. 2. The design specification for the Beta OHA System did not adequately specify software security.
- 3. Procedure S2.0P-SO.ANN-OOOl(Q) was inadequate.
It implied that the Beta OHA System could not be affected without use of a password.
ANALYSIS OF OCCURRENCE:
The control room OHA System consists of a Betalog 4100 (a high performance sequential events recording system) a Betalog 1500 (a microprocessor based serial input distributed annunciator system, and a RCW Computer with printer. The OHA consists of ten (10) overhead boxes with forty-eight (48) windows per box and a redundant Control Room CRT. The OHA system electronics, for both Salem Units, were modified during the recently completed refueling outages (i.e., lRlO design modification completed on June 12, 1992 and 2R6 design modification completed on March 26, 1992). This new system is microprocessor based. It is manufactured by Beta Products Division of Hathaway Industries.
In addition to the principal design modification, the alarm window displays were rearranged, relabeled and system reflash capability modified.
Also a CRT with keypad controls and new A ' LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 DOCKET NUMBER 5000311 ANALYSIS OF OCCURRENCE: (cont'd) LER NUMBER 92-017-00 pushbutton/switches was installed on the control console. PAGE 5 of 6 The Updated Final Safety Analysis Report (UFSAR) states that the OHA System is not safety related. System alarms are not part of the plant protection scheme and failures cannot affect protective system operation.
Those component failures which would result in OHA System annunciation, during OHA system inoperability, were addressed by . Control Room personnel as appropriate.
Therefore, failure of the OHA System did not affect the health or safety of the public. Review of operator response to this event identified that a procedure for partial or total loss of the OHA System did not exist at the time of this event. Abnormal Operating Procedures, Sl/S2.0P-AB.ANN-0001, which address this, have been issued. CORRECTIVE ACTION: Operations personnel involved in this event have been disciplined as appropriate.
This event will be reviewed with applicable Operations, Engineering and Technical Department personnel.
This event will be reviewed by the Nuclear Training Center for inclusion in applicable training programs.
The engineering department is performing a third party assessment of the Beta OHA System design modification.
Appropriate corrective actions will be taken based on the assessment findings.
The assessment includes the role of the Nuclear Computer Group's responsibilities for the review of design modifications and design specifications that involve digital systems. Other proposed digital system design change packages are being reassessed for adequacy of software design. A design modification is being prepared to install an independent alarm circuitry system to monitor OHA operation.
The design will provide OHA failure alarms in the Control Room. Procedure S2.0P-SO.ANN-0001 (and the comparable Unit 1 procedure) was revised. It was revised to include resetting and testing the OHA System with an operability determination description.
OHA System preventive maintenance and corrective maintenance will be developed.
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 CORRECTIVE ACTION: (cont'd) DOCKET NUMBER 5000311 LER NUMBER 92-017-00 PAGE 6 of 6 Abnormal Operating Procedures, Sl/S2.0P-AB.ANN-0001, have been issued which address operator response to OHA System partial or total loss. MJP:pc SORC Mtg.93-009 General Manager -Salem Operations