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| * Public Service Electric and Gas Com*pany P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station April 27, 1992 | | * Public Service Electric and Gas Com*pany P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station April 27, 1992 |
| : u. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 | | : u. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
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| ==Dear Sir:== | | ==Dear Sir:== |
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| : n. QI Q | | : n. QI Q |
| ."I i.,;_ 20.406(o)(1lliJ 20.4051o)(1Jliil -- 60.36(c) (1) 50.36lcll21 - | | ."I i.,;_ 20.406(o)(1lliJ 20.4051o)(1Jliil -- 60.36(c) (1) 50.36lcll21 - |
| ......_
| | . 60.73(o)(2J(v) 60.73(o)(2J(vilJ 73.71 (cl OTHER (Specify in Abstr1cr 11111111ltlllllllll~ |
| . 60.73(o)(2J(v) 60.73(o)(2J(vilJ | |
| .....__
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| ......_
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| 73.71 (cl OTHER (Specify in Abstr1cr 11111111ltlllllllll~ | |
| 20.4061*111 )(ill) 20.405(0)(1 )liv) 20.4051*111 JM | | 20.4061*111 )(ill) 20.405(0)(1 )liv) 20.4051*111 JM |
| --* 50.73loJl21(1) li0.7311112llii) 60.73loll2l (iiiJ | | --* 50.73loJl21(1) li0.7311112llii) 60.73loll2l (iiiJ 60.73(o)(2)(viiiJIAJ 60.73(o)l2JlvliiJIBI 60,73JoJ(2llxJ below and in Texr, NRC Form 366AJ LICENSEE CONTACT FOR THIS LER 1121 NAME - TELEPHONE NUMBER AREA CODE M. J. Pollack - LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
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| 60.73(o)(2)(viiiJIAJ 60.73(o)l2JlvliiJIBI 60,73JoJ(2llxJ below and in Texr, NRC Form 366AJ LICENSEE CONTACT FOR THIS LER 1121 NAME - TELEPHONE NUMBER AREA CODE M. J. Pollack - LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) | |
| MANUFAC-REPORTABLEi:::::::::::::::::::::: ::::::::::}\:::::::: MANUFAC* . REPORT AB LE[~:.::::*::::::*:*,*:::::::::::::::::::::*=-,,:,:::*::::*::::::;:::1 CAUSE SYSTEM COMPONENT TO NP RDS I*:*:*:*:*.*.*.*.*.:*:*:*:*:*:*:*::.: :*:-:-: CAUSE SYSTEM COMPONENT TO NP RDS t.:_:..:.:::,.:;:.:::::::,::',:.:::::::::::::::::::;,:,:,:,:::::::::;:i TURER TURER* | | MANUFAC-REPORTABLEi:::::::::::::::::::::: ::::::::::}\:::::::: MANUFAC* . REPORT AB LE[~:.::::*::::::*:*,*:::::::::::::::::::::*=-,,:,:::*::::*::::::;:::1 CAUSE SYSTEM COMPONENT TO NP RDS I*:*:*:*:*.*.*.*.*.:*:*:*:*:*:*:*::.: :*:-:-: CAUSE SYSTEM COMPONENT TO NP RDS t.:_:..:.:::,.:;:.:::::::,::',:.:::::::::::::::::::;,:,:,:,:::::::::;:i TURER TURER* |
| ::*::::::::::::::::::::::r:::::=:::::::::::::::: ,... *:-:* | | ::*::::::::::::::::::::::r:::::=:::::::::::::::: ,... *:-:* |
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| ----*~-- *-*~---- LICENSEE EVENT REPORT (LER) TEXT CONTINUATION . | | ----*~-- *-*~---- LICENSEE EVENT REPORT (LER) TEXT CONTINUATION . |
| Salem G~nerating Station DOCKET NUMBER LER NUMBER PAGE u__n_i~*_t_2_ _~_**_ _ _ _ _ _ _ _ _ _ _50_Q_Q_31=.!,_ _ _ . ___~-~-=-_Q_Q_6-_Q~Q ____ 3- -of | | Salem G~nerating Station DOCKET NUMBER LER NUMBER PAGE u__n_i~*_t_2_ _~_**_ _ _ _ _ _ _ _ _ _ _50_Q_Q_31=.!,_ _ _ . ___~-~-=-_Q_Q_6-_Q~Q ____ 3- -of DESCRIPTION OF OCCURRENCE: (cont'd) |
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| DESCRIPTION OF OCCURRENCE: (cont'd) | |
| On April. 1, 19.92, at 1643 hours, a CP/P-VR System isolation signal was again actua-"ted off the 2R11A RMS channel. Again this occurred concurrently with a 2Rl1A RMS channel filter tear alarm. Technical Specification Table 3.3-6 and 3.4.7.1 Action Statements w~re entered. | | On April. 1, 19.92, at 1643 hours, a CP/P-VR System isolation signal was again actua-"ted off the 2R11A RMS channel. Again this occurred concurrently with a 2Rl1A RMS channel filter tear alarm. Technical Specification Table 3.3-6 and 3.4.7.1 Action Statements w~re entered. |
| The Nuclear Regulatory Commission was notified of these three (3) ESF actuations in accordance with Code of Federal Regulations 10CFR 50.72(b) (2) (ii) on March 29, 1992 ai liOS hou~s, on March ~1, 1992 at 1841 hours and on April 1, 1992 at 1813.hours. | | The Nuclear Regulatory Commission was notified of these three (3) ESF actuations in accordance with Code of Federal Regulations 10CFR 50.72(b) (2) (ii) on March 29, 1992 ai liOS hou~s, on March ~1, 1992 at 1841 hours and on April 1, 1992 at 1813.hours. |
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| . During the recent Unit 2 refueling* outage. ( 2R6) , several RMS channels | | . During the recent Unit 2 refueling* outage. ( 2R6) , several RMS channels |
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| r- | | r-LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station ,DOCKET NUMBER LER NUMBER PAGE u~=n=i~t-=2'------------------=5000311~_ --~-~-~O_Q_6-Q_Q_:__ _____ 4 o_L5_ _ |
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| | APPARENT CAUSE OF OCCURRENCE: (cont'd) were upgrad~d via replacement ot their electronics with state of the art equipment (reference design change package 2EC~3086). Included in this design change was the tying together of downscale alarms (e.g.*, |
| * LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station ,DOCKET NUMBER LER NUMBER PAGE u~=n=i~t-=2'------------------=5000311~_ --~-~-~O_Q_6-Q_Q_:__ _____ 4 o_L5_ _
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| APPARENT CAUSE OF OCCURRENCE: (cont'd) | |
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| were upgrad~d via replacement ot their electronics with state of the art equipment (reference design change package 2EC~3086). Included in this design change was the tying together of downscale alarms (e.g.*, | |
| "low flow alarm" on the 2R41C and "paper tear alarm" on the 2R11A) with the CP/P-VR System isolation signal circuitry. Subsequent engineering assessment has shown that actuation of CP/P-VR System isolation on these downscale failures is not necessary; therefore, those failure alarms_ which were tied to the CP/P-VR System isolation circuit as a result of DCP 2EC~3086 have been returned to original design (i.e., alarm only). | | "low flow alarm" on the 2R41C and "paper tear alarm" on the 2R11A) with the CP/P-VR System isolation signal circuitry. Subsequent engineering assessment has shown that actuation of CP/P-VR System isolation on these downscale failures is not necessary; therefore, those failure alarms_ which were tied to the CP/P-VR System isolation circuit as a result of DCP 2EC~3086 have been returned to original design (i.e., alarm only). |
| Investigation of the 2R11A events revealed that. the filter paper take.,..up motor did not maintain adequate tension on the ,filter paper to ensure it would not loosen and subsequently jam/bind. The filter_ | | Investigation of the 2R11A events revealed that. the filter paper take.,..up motor did not maintain adequate tension on the ,filter paper to ensure it would not loosen and subsequently jam/bind. The filter_ |
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| The 2R41C channel moriitors Plant Vent ef flµent releases for ' ! | | The 2R41C channel moriitors Plant Vent ef flµent releases for ' ! |
| * Salem Generating Station | | * Salem Generating Station |
| -* .*DOCKET NUMBER | | -* .*DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION LER NUMBER PAGE Unit 2 5000311 92-006 - - - - * -of ANALYSIS OF OCCURRENCE: (cont'd) radioactive noble gasses~ The 2R41C CP/P-VR Syste~ isolation function, is-redundant to the 2R12A channel. In addition to CP/P-VR' System isolation function, the 2R41C channel .isolates the 2WG-41 valve (Waste Gas Decay Tank Vent Control Valve). |
| * LICENSEE EVENT REPORT (LER) TEXT CONTINUATION LER NUMBER PAGE Unit 2 5000311 92-006 - - - - * -of
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| ANALYSIS OF OCCURRENCE: (cont'd) radioactive noble gasses~ The 2R41C CP/P-VR Syste~ isolation function, is-redundant to the 2R12A channel. In addition to CP/P-VR' System isolation function, the 2R41C channel .isolates the 2WG-41 valve (Waste Gas Decay Tank Vent Control Valve). | |
| The CP/P-VR System.isolation signals were not the result of a release | | The CP/P-VR System.isolation signals were not the result of a release |
| *of plant vent high activity.- During thes_e events, the CP/P-VR System valves were closed and did not change position. Therefore, these. | | *of plant vent high activity.- During thes_e events, the CP/P-VR System valves were closed and did not change position. Therefore, these. |
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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. 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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. 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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. 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[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
[Table view] |
Text
PS~G *
- Public Service Electric and Gas Com*pany P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station April 27, 1992
- u. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
.I SALEM GENERATING STATION LICENSE NO .. DPR-75 DOCKET NO.* 50-311 UNIT NO. 2 LICENSEE EVENT REPORT 92-006~00 This Licensee Event Report is being submitted pu~~uan~ to the re.quirements of* the Code of .Federal Regulations 10CFR 50.73(a) (2) (iv). This report is required to. ~e issued within thirty (30) days of event discovery.
C. A. Vondra General Manager -
Salem Operations MJP:pc
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9205050189 920427 PDR ADOCK 05000311 9s-21s1tt~1 i2-ss s . PDR -
NRC FORM 366 (0-89) I U.S. NUCLEAR REGULATORY COMMISSION .. APPROVED OMB NO*: 3150:0104 EXPIRES: 4/30/92 0
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1 LIC~NSEE EVENT REPORT (LER) . COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS.
AND REPORTS MANAGEMENT BRANCH (P*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 (11 DOCKET NUMBER 121 I P 131 Salem Generating Station TITLE (41 *
~-Unit 2 Io I 5 I o I o I o I 31 11 l 1 loF 0 I 5 3 ESF Actuation -Signals For Containment Ventilation Isolatdicim Due To Design 0
EVENT DATE 151 LER NUM BER (6) REPORT DATE (7) OTHER*FACILITIES INVOLVED (Bl MONTH DAY YEAR YEAR tt~ SE~~~~~lfL [ : ) ~~~~~~ MONTH DAY YEAR FA.Cl LITY NAMES DOCKET NUMBERISJ 01s1010101 I 1.
oI 3 2 9I 9 2 91 2 - oI o I 6 - o I o a 14 211 91 2 OPERATING THIS REPORT IS SUBMITTED PURSUANT TD THE R~QUIREMENTS OF 10 *cFR §: (Ch*ck ons or mors of th* foilowing) (11)
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--* 50.73loJl21(1) li0.7311112llii) 60.73loll2l (iiiJ 60.73(o)(2)(viiiJIAJ 60.73(o)l2JlvliiJIBI 60,73JoJ(2llxJ below and in Texr, NRC Form 366AJ LICENSEE CONTACT FOR THIS LER 1121 NAME - TELEPHONE NUMBER AREA CODE M. J. Pollack - LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
MANUFAC-REPORTABLEi:::::::::::::::::::::: ::::::::::}\:::::::: MANUFAC* . REPORT AB LE[~:.::::*::::::*:*,*:::::::::::::::::::::*=-,,:,:::*::::*::::::;:::1 CAUSE SYSTEM COMPONENT TO NP RDS I*:*:*:*:*.*.*.*.*.:*:*:*:*:*:*:*::.: :*:-:-: CAUSE SYSTEM COMPONENT TO NP RDS t.:_:..:.:::,.:;:.:::::::,::',:.:::::::::::::::::::;,:,:,:,:::::::::;:i TURER TURER*
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SUPPLEMENTAL REPORT EXPECTED* (141 MONTH DAY YEAR EXPECTED n YES (If yes. complete EXPECTED SUBM/S~ION OA TEI fxl ABSTRACT .flimir ro 1400 spaces. i.~ .. approximately fifteen single-space typewritten lines} (1'61 NO
.SUBMISSION DATE 1151 I I I This LER addresses 3 Engineered Safety Feature (ESF) signals initiated by the Radiation Monitoring System (RMS). The signals were for Containment Purge/Pressure-Vacuum Relief (CP/P-VR) System isolation.
The isolation valves were closed at the time of the signals and did not change position. On.3/29/92 and 4/01/92, the 2RllA Containment Particulate RMS Monitor channel initiated CP/P-VR System isolation signals. Each of these signal actuations was the result of a "paper tear alarm". On 3/31/92, the 2R41C Plant Vent Noble Gas Monitor charinel alarmed on "low flow". The ~oot cause of these 3 events is design. During the recent Unit 2 refueling outage (2R6), RMS channels were upgraded including the tying together of downscale alarms with the CP/P-VR System isolation signal circuitry. Subsequently, it has been shown that actuation of CP/P-VR System isolation on these downscale failures is not necessary; therefore, those failure alarms which were tied to the CP/P-VR System isolation circuit have been returned to original design (i.e., alarm only). The 2RllA paper tear qlarm actuated due to failure of the paper take-up motor to maintain adequate tension. The motor was replaced. The 2R41C channel low flow alarm actuated d~e to a momentary decrease of flow as a result of concurrent work. The Auxiliary Building Ventilation System supply and exhaust fans were being swapped. Also, Che~istry had disconnected the Plant Vent composite iodine and particulate sample pump downstream connection which pulls its sample from the 2R41 sample line.
NRC Form 366 16-89)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station* DOCKET NUMBER LER NUMBER PAGE Unit 2
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5000311 _ _ _9 2--_Q_Q_G-_Q_Q________~___ gJ___~---*_
PLANT AND SYSTEM IDENTIFICATION:
Westing~ouse - Pressurized Water Reactor
.Ener~y Industry tdent{fication System (EIIS) codes are identified in the text as {xx}
IDENTIFICATION OF OCCURRENCE:
3 Engineered Safety Feature actuation signals for Containment Ventilation Isolatibn Ev~nt Dates: 3/29/92, 3/31/92 and 4/01/92 Report Date~ 4/27/92 This report was initiated by Incident Report Nos.92-215, 92-218 and 92-220.
CONDITIONS PRIOR TO OCCURRE_N~$:_
March *2*9, 1992: Mode 5 (Cold Shutdown) (Gth Refueling/Maintenance Outage in Progress)
- March 31, 1992: Mode 5 April 01, 1992: Mode *4 (Hot Shutdown)
DESCRIPTION OF OCCURRENCE:
This LER addresses three (3) Engineered Safety Feaiure fES~) signals initiated by the Radiation Monitoring System (RMS) {ILi. The signals were for Containment Purge/Pressure-Vacuum Relief (CP/P-VR) System
{BF) isolation., The isolation valves were closed at the time of the signals .and did n9t change position.
On March 29, 1992r at 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br />, the 2R11A Containment Particul~te RMS Monitor channel initiated a CP/P-VR System isolation signal.
Alarms included annunciator panel 2RP4 "Vent Isolation" and console alarm "Phase A and Cont Vent Isolation Operate". Also, the 2R11A green normal light was off. The 2R11A RMS channel was declared inoperable. Inve~tigation revealed that the ESF signal actuation was the result of a "paper tear alarm". The 2R11A RMS channel filter paper had loosened. After the filter paper was tightened onto its*
take-up reel the alarm cleared. Upon direction from System Engin~ering, a daily.inspection ~~s initi~ted to ensure filter pap~r tension was maintained. The channel was returned to service*on March 31, 19~2 following successful completion of a channel check.
On March 31, 1992, at 1745 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.639725e-4 months <br />, a CP/P-V*R System isolation signal actuated from the RMS Plant Vent Noble.Gas Monitor, 2R41C. The 2R41C RMS ch~nnel was declared inoperable due to the signal actuation.
Since the 2R12A RMS channel was also inoperable at the. time, Technical Specification 3.3.3.9 Action 34 was entered. At the time of this signal actuation the Au'xiliary Building Ventilation System (ABV) {VF}
I supply and exhaust fans were being swapped.
*~-- *-*~---- LICENSEE EVENT REPORT (LER) TEXT CONTINUATION .
Salem G~nerating Station DOCKET NUMBER LER NUMBER PAGE u__n_i~*_t_2_ _~_**_ _ _ _ _ _ _ _ _ _ _50_Q_Q_31=.!,_ _ _ . ___~-~-=-_Q_Q_6-_Q~Q ____ 3- -of DESCRIPTION OF OCCURRENCE: (cont'd)
On April. 1, 19.92, at 1643 hours0.019 days <br />0.456 hours <br />0.00272 weeks <br />6.251615e-4 months <br />, a CP/P-VR System isolation signal was again actua-"ted off the 2R11A RMS channel. Again this occurred concurrently with a 2Rl1A RMS channel filter tear alarm. Technical Specification Table 3.3-6 and 3.4.7.1 Action Statements w~re entered.
The Nuclear Regulatory Commission was notified of these three (3) ESF actuations in accordance with Code of Federal Regulations 10CFR 50.72(b) (2) (ii) on March 29, 1992 ai liOS hou~s, on March ~1, 1992 at 1841 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.005005e-4 months <br /> and on April 1, 1992 at 1813.hours.
Technical Specification Tab~e 3.3-6 Action 24 states:
"With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.7.1".
Technical Specification 3.4.7.1 states:
"The following Reactor Coolant Syste~ lea~age detection systems .
shall be. OPERABLE:
- a. The containment atmosphere particulate radioactivity.*
monitoring system, '
- b. The containment sump level moni~oring system, and
- c. Either the containment fan cooler condensate flow ra.te or the containment atmosphere gaseous radioactivity monitoring system."
Technical Specification 3.4.7.1 Action Statement states:
"With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required gaseous and/or particulate radioactivity monitoring system is inoperable; otherwise, be in at least HOT S~ANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the .following 30_hours.".
Techni~al Specification 3.3.3.9 Action 34.states:
With the number of channels QPERABLE less.than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway."-
The root cause of the three (3) ESF actuation signal ~vents is attributed to design .
. During the recent Unit 2 refueling* outage. ( 2R6) , several RMS channels
r-LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station ,DOCKET NUMBER LER NUMBER PAGE u~=n=i~t-=2'------------------=5000311~_ --~-~-~O_Q_6-Q_Q_:__ _____ 4 o_L5_ _
APPARENT CAUSE OF OCCURRENCE: (cont'd) were upgrad~d via replacement ot their electronics with state of the art equipment (reference design change package 2EC~3086). Included in this design change was the tying together of downscale alarms (e.g.*,
"low flow alarm" on the 2R41C and "paper tear alarm" on the 2R11A) with the CP/P-VR System isolation signal circuitry. Subsequent engineering assessment has shown that actuation of CP/P-VR System isolation on these downscale failures is not necessary; therefore, those failure alarms_ which were tied to the CP/P-VR System isolation circuit as a result of DCP 2EC~3086 have been returned to original design (i.e., alarm only).
Investigation of the 2R11A events revealed that. the filter paper take.,..up motor did not maintain adequate tension on the ,filter paper to ensure it would not loosen and subsequently jam/bind. The filter_
paper take-up motor was replaced. Also, the 2R11A sample box was cleaned and all moving parts lubricated.
Investigation of the 2R41C event revealed that system flow had decreased to the alarm setpoint as a iesult of concurrent wprk. As stated previously, the ABV System fans were being swapped. Also, Chemistry had disconnected the downstream connection to the_ Plant Vent composite iodine and particulate sample pump (in support of 2R45 RMS Channel functional testing), which pulls its sample from the 2R41-sample line and returns it back to the 2R41 sample line. The combination 6f ihese two (2) evolutions resulted in the 2R41 sample flow decreasing to the ~10~ flow alarm" setpoint.
Testing showed that Plant_ Vent flow fluctuates when the ABV System supply and exhaust fans are swapped; however, by itself, swapping of the fans did not cause a drop in flow to the *2R41 alarm setpoint.
With the Composite Sample Pump line disconnected, some ABV System configuration changes would momentarily cause a sufficient decrease in the 2R41 sample pump flow rate to the alarm setpoint.
ANALYSIS OF OCCURRENCE :
- CP/P-VR System Isolation mitigates the release of rad~oactive material to the environment after a design basis accident. Several RMS cheynnels, including the 2R11A and 2R41C channels, aie designed to initiate a CP/P-VR System isolation signal on high activity.
The 2R11A RMS channel monitors the radioactive particulate _content of
- the Containment atmosphere. The channel i~ used in Modes 1 through 4 to identify Reactor Coolant System (ABI leakage in conjunction with the containment sump level monitor_ing system, the containment fan cooler co~densate flow rate monitors, and the, containment radioactive noble gas (2R12A) RMS.
- In Mode 6, the 2R11A chann~l provides indi~ation of a fuel handling accident and early isolation of the Containment in the event of an accident.
The 2R41C channel moriitors Plant Vent ef flµent releases for ' !
-* .*DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION LER NUMBER PAGE Unit 2 5000311 92-006 - - - - * -of ANALYSIS OF OCCURRENCE: (cont'd) radioactive noble gasses~ The 2R41C CP/P-VR Syste~ isolation function, is-redundant to the 2R12A channel. In addition to CP/P-VR' System isolation function, the 2R41C channel .isolates the 2WG-41 valve (Waste Gas Decay Tank Vent Control Valve).
The CP/P-VR System.isolation signals were not the result of a release
- of plant vent high activity.- During thes_e events, the CP/P-VR System valves were closed and did not change position. Therefore, these.
events did not affect the health or safety of the public. However, due t6 the automatic a6tu~tion of an ESF sys~em, these events are i:-eportable in accordance with Code of Federal Regulations 10CFR SO. 73 (a) (2) (iv).
CORRECTIVE ACTION:
The CP/P-VRS System isolation signals which were added to downscale failure alarm~ via DCP 2EC-3086 have been removed. The downscale failure alarms reioain active;' although, independent of the CP/P-VR
~ystem isolation signal circuitry.
The 2RllA RMS channel filter paper motor was replaced. Upon successful completion of a channel check, the channel was returned to service and the associated Technical Specifications wer~ exited on April 4, 1992, at 0505 hours0.00584 days <br />0.14 hours <br />8.349868e-4 weeks <br />1.921525e-4 months <br />.
General Manager -
Salem Operations MJP:pc SORC Mtg.92-051