ML20136C350
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| ML20136C350 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/31/1979 |
| From: | Midura H Public Service Enterprise Group |
| To: | |
| References | |
| NUDOCS 7909190438 | |
| Download: ML20136C350 (1) | |
Similar Documents at Salem | |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20099C1471992-07-23023 July 1992
[Table view]Special Rept 92-5:on 920713,radiation Monitoring Sys Channels 2R45B & 2R45C Declared Inoperable & Removed from Svc.Caused by Equipment Failure.Channel Repairs Will Be Tested Upon Completion of Mod ML20204H3761987-03-19019 March 1987 Special Rept 87-2:on 870310,fire Pump House Failed to Swap Alternate Power Source After Group Bus 1F Taken Out of Svc, Causing Loss of Ac Power to Auto Start Initiation Logic for Both Diesel Driven Fire Pumps.Caused by Equipment Failure ML20207T1111987-03-16016 March 1987 Special Rept 87-1:on 870303,increase in Containment Sump Leak Rate Noted.Caused by Pitting Corrosion on Welded Joint Between Elbow & Spoolpiece.New Spoolpiece Fabricated from Stainless Steel & Installed ML20210E3821987-02-0505 February 1987 Special Rept 86-11:on 861015,ion Exchange Resin Discovered in Reactor Cavity During Refueling.Caused by Resin Release from Prior Resin Slucing Operation or Backwashing During Valve Manipulations.Resin Cleanup Conducted ML20207P2521987-01-0909 January 1987 Special Rept 86-6:on 871210 & 16,fire Barriers Degraded Due to Impairment of Floor Hatch & Two Wall Penetrations Beyond 7 Days.Caused by Inoperable Hatch Remaining Open to Run Cable for Work.Weld Cable Removed & Hatch Returned to Svc ML20207D5591986-12-24024 December 1986 Special Rept 86-5:on 861120,two Fire Penetrations,One Fire Door & Two Fire Penetration Floor Hatches Remained Opened Beyond 7 Days Allowed by Tech Spec.Caused by Extended Cleanup Activities.One Hour Fire Watch Established ML20211Q1001986-12-11011 December 1986 Special Rept 86-4:on 861105,three Fire Doors Found Damaged. Caused by Heavy Traffic Experienced During Unit 2 Refueling Outage.Fire Watch Established on 861002.Repairs to Doors Completed on 861120 ML20214P1991986-11-26026 November 1986 Special Rept 86-4:on 861105,three Fire Doors Determined to Be Damaged.Cause,Other than High Traffic,Undetermined.Hinges on Doors 137-1 & 136-2 Welded & Panic Bar on Door 120-1 Repaired.Fire Watch Established for Duration of Outage ML20215N8711986-10-31031 October 1986 Special Rept 86-10:on 861007,diesel Generator 2A Valid Test Failed to Achieve Rated Speed in 10 S.Caused by Malfunctioning Switching Tachometer.Tachometer Replaced & Diesel Retested Successfully ML20215M5901986-10-23023 October 1986 Special Rept 86-7:on 860924,during RCS Fill & Vent Operations,Pressurizer Overpressure Protection Sys Actuation Occurred.Caused by Induced Pressure Transient.Review Being Conducted to Identify Ways to Avoid Future Actuations ML20214V2211986-09-23023 September 1986 Special Rept 86-9:on 860825,diesel Generator 2B Tripped on High Jacket Water Temp.Caused by Sticking of Diesel B Cooling Svc Water Throttle Valve.Valve Stroked & Generator Retested Successfully ML20214T1521986-09-19019 September 1986 Supplemental Special Rept 86-6:on 860814,certain Fire Barrier Penetrations Impaired.Caused by Addl SPDS Cable Pulling Activities Under Separate Fire Protection Impairment Permits.Suppl Will Be Provided ML20209H8101986-09-0909 September 1986 Special Rept 86-8:on 860825 & 27,following Reactor Trip/ Safety Injection,Containment Sump Pump Run Indicated Unidentified in-leakage.Caused by Galvanic Corrosion of Motor Cooler Outlet Line Welds.Welds Reworked ML20211A8921986-08-22022 August 1986 Special Rept 86-6:on 860724,fire Barrier Penetrations Impaired for More than 7 Days Due to Const Activities on Spds.Cable Pulling Completed & Penetrations Restored to Operable Status ML20212C8611986-07-18018 July 1986 Ro:On 860705,Kemps Ridley Sea Turtle Discovered Floating Near Trash Bars of Cooling Water Sys Intake.Caused by Summer Migration.Intake Monitored for Debris & Turtles.Sea Turtle Turned Over to Mammal Ctr ML20206S1491986-06-30030 June 1986 Special Rept 86-5:on 860524,fire Damper 2CAF207 Failed to Close Upon Receipt of Automatic Trip Signal.Caused by Trip Mechanism Binding & Not Being Properly Adjusted to Ensure Automatic Operation.Mechanism Replaced ML20199F5221986-06-18018 June 1986 Special Rept 86-3:on 860604,svc Water Leak Discovered Inside Containment on Containment Fan Coil Unit Motor Coolers 11 & 12.Caused by Leaks on Two Plug Pipes & Head Gasket, Respectively.Pipe Plugs & Head Gasket Replaced ML20203N5361986-04-29029 April 1986 Special Rept 86-4:on 860330,jacket Water Hose at Right Side Cylinders Ruptured & Diesel Generator Immediately Secured. Caused by Hose Failure.Hoses Being Replaced as Preventive Measure ML20203N3071986-04-25025 April 1986 Special Rept 86-2:on 860328,fire Doors Impaired for Duration of Refueling Outage.Caused by Deliberate Plan to Preclude Damage Due to Heavy Traffic During Refueling.Fire Watch Instituted ML20154S1831986-03-21021 March 1986 Special Report 86-1:on 860215,fire Barrier Penetration Door 121-1 Found Inoperable.Caused by Excessive Differential Pressure from Ventilation Sys.Door Will Be Replaced.Review of Problem Underway ML20154G8421986-02-28028 February 1986 Special Rept 86-3:on 860130,pressurizer Overpressure Protection Sys Actuated.Caused by Operator Error.Event Discussed W/Operators.Occurrence Reviewed by Nuclear Training Dept to Determine Need for Addl Training ML20141E1461986-02-14014 February 1986 Special Rept 86-2:on 860105,trouble Alarm Associated W/ Reactor Coolant Pump 22 Fire Detection Instrumentation Received in Control Room.Caused by High Resistance Across Contacts of Smoke Detector.Contacts Cleaned.Alarm Cleared ML20151V8331986-01-29029 January 1986 Special Rept 86-1:on 860102,generator Output Circuit Breaker Opened on Overcurrent Protection During Diesel Generator Surveillance Test.Caused by Lack of Adequate Procedural Guidance.Operating Procedure II-1.3.1 Revised ML20151R9871986-01-27027 January 1986 Informs That Util Erroneously Notified NRC of 851215 Apparent Violation of Tech Spec Requirements Which Resulted in Inoperability of Both ECCS Subsys During Mode 4 Operation.Justification for Nonreportability Provided ML20138R0411985-10-25025 October 1985 Ro:On 850930,discovered Dead Atlantic Loggerhead Sea Turtle Impinged on Circulating Water Sys Intake Trash Bars.Caused by Deep Carapace Slashes Indicative of Ship Propeller Cut. Turtle Removed for Autopsy & Disposal ML20138R1031985-09-0404 September 1985 Ro:On 850805,07 & 10,three Atlantic Loggerhead Sea Turtles Found Impinged on Trash Bars of Circulating Water Sys Intake.One Turtle Survived.Trash Bars Observed Once Per 8 H Shift & Cleaned at Least Once Per Day ML20199G0381985-08-0909 August 1985 Ro:On 850715,Atlantic Loggerhead Turtle Found Impinged on Trash Bars of Circulating Water Sys Intake.Turtle Freshly Dead When Found.Unsuccessful Attempt Made to Resuscitate Animal.Trash Bars Observed at Least Once Per 8 H Shift ML20132H2611985-07-0505 July 1985 Ro:On 850608,11 & 24,sea Turtles Found Impinged on Trash Bars of Circulating Water Sys Intake.Caused by Above Average Water Temp & Salinity.Trash Bars Will Be Observed at Least Once Per 8 H Shift ML20079M8521983-02-15015 February 1983 Ro:On 830210,tagging Error Discovered on Circuit Breakers for Accumulator Motor Operated Valves.Associated Tags Verified for Proper Placement.Addl Verification of Safety Significant Tagging Will Be Performed ML20071F0861980-09-25025 September 1980 Ro:On 800912,sample Analysis Taken from Hydrazine Addition Tank Indicated Sodium Chloride in Tank.Anonymous Telcon Indicated Salt May Have Been Added Prior to Labor Strike by Unknown Persons ML20136C3501979-08-31031 August 1979 RO 79-56/01P:in Response to NRC Question Re RHR Pump NPSH During post-LOCA Recirculation Mode Tests Indicated That RHR Pump Flow Exceeded Design Runout Flow.Problem Exists for Units 1 & 2 ML20136C0511979-08-24024 August 1979 RO 79-54/01P:on 790824,while Performing Wire Lock Insp of Pipe Snubbers,Three Snubbers on Main Feedwater Line 14 Were Found Frozen in Place 1992-07-23 Category:TEXT-SAFETY REPORT MONTHYEARML20217A9931999-09-30030 September 1999
[Table view]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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Public Se%e Electric end Gas Comexnv P.O. 0ns 66 Hencocks Bridt;pe, New Jmy 0803R Setem Nucteer Gmereting Station August 31, 1979 ,
9 Mr. Boyce H. Grier Director of USNRC Office of Inspection and Enforcement Region 1 4 n Park Avenue .
King of Prussia, Pennsylvania 19406-De,ar sir RCPORTILBrA OCCURRENCE 79-56/OlP SAIJDE WO. 1 UNIT I.BR
- This letter will serve to confirm one telephone report to the Realdent NRC Inspector on August 30, 1979, .edvising of a report-mbig occurrence in accordance with Technical specification 6.9.1.a.
In response to an NRC question on Salem Unit No. 2 regarding RHR purnp NPSH during pont-LOCA recirculation mode, tests were run wMeh indicated that the RHR pump flow excaaded the design runout ttow. Salem Unit No. I has an identical configuration end, therefore, a reportable condition exists. !
A detai. led report will be submitted in the tJme period specified by the Technical Specifications.
very truly yours, y c n_,
- u. J. Midura Manager - Salem Generating Stntion AWKrlda ___
cc Ganeral Manager - Electric Production Mc. nager - Quality Annurance
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