PNO-I-85-062, on 850829,at 100% Power,Reactor Tripped & Safety Injection Occurred.Caused by Broken Pipe Fitting on Instrument Air Compressor Tank in Turbine Bldg.Pressurizer Pressure Restored to Normal
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| ML20134L574 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/29/1985 |
| From: | Asars A, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| References | |
| PNO-I-85-062, PNO-I-85-62, NUDOCS 8509030334 | |
| Download: ML20134L574 (1) | |
Similar Documents at Beaver Valley | |
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Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-I-99-048, on 991022,operators Initiated Plant Shutdown from 100% Reactor Power,Due to Continued RCS Leakage Through B Pressurizer Code Safety Valve to Primary Relief Tank. Operators Are Reducing Reactor Power at 12% Per H1999-10-22022 October 1999
[Table view]PNO-I-99-048:on 991022,operators Initiated Plant Shutdown from 100% Reactor Power,Due to Continued RCS Leakage Through B Pressurizer Code Safety Valve to Primary Relief Tank. Operators Are Reducing Reactor Power at 12% Per H PNO-I-99-036, on 990718,update to Beaver Valley,Unit 2 Forced Outage Made.Licensee Replaced Suspected Voltage Regulator Control Relays & Satisfactorily Retested EDG 2-2.Resident Inspectors Continue to Monitor Licensee Corrective Action1999-07-26026 July 1999 PNO-I-99-036:on 990718,update to Beaver Valley,Unit 2 Forced Outage Made.Licensee Replaced Suspected Voltage Regulator Control Relays & Satisfactorily Retested EDG 2-2.Resident Inspectors Continue to Monitor Licensee Corrective Action PNO-I-99-033, on 990716,apparent Electrical Fault Occurred During EDG Full Load Test,Which Opened Supply Breaker Between Emergency & Normal 4 Kilovolt Busses.Station Personnel Intend to Resolve & Correct Electrical Fault1999-07-19019 July 1999 PNO-I-99-033:on 990716,apparent Electrical Fault Occurred During EDG Full Load Test,Which Opened Supply Breaker Between Emergency & Normal 4 Kilovolt Busses.Station Personnel Intend to Resolve & Correct Electrical Fault PNO-I-98-002, on 980130,operators Declared Both Trains of Component Cooling Reactor & Reactor Plant River Water Sys Inoperable Due to Failure to Meet TS Surveillance Testing Requirements.Entered TS 3.0.3 & 4.0.31998-02-0202 February 1998 PNO-I-98-002:on 980130,operators Declared Both Trains of Component Cooling Reactor & Reactor Plant River Water Sys Inoperable Due to Failure to Meet TS Surveillance Testing Requirements.Entered TS 3.0.3 & 4.0.3 PNO-I-97-077, on 971216,Duquesne Light Co Initiated Unit 2 Reactor Shutdown in Accordance W/Ts 3.0.3.Licensee Plans to Address Unit 2 Design Deficiency for CR Emergency Air Cleanup & Pressurization,During Shutdown1997-12-17017 December 1997 PNO-I-97-077:on 971216,Duquesne Light Co Initiated Unit 2 Reactor Shutdown in Accordance W/Ts 3.0.3.Licensee Plans to Address Unit 2 Design Deficiency for CR Emergency Air Cleanup & Pressurization,During Shutdown PNO-I-97-040, on 970627,Unit 1 RPS Trip Functions Did Not Meet Design Requirements & Were Inoperable.Licensee Intends to Install Design Change to Resolve IEEE-279 Postulated Failure Concerns.Operators Began TS Required Shutdown1997-06-30030 June 1997 PNO-I-97-040:on 970627,Unit 1 RPS Trip Functions Did Not Meet Design Requirements & Were Inoperable.Licensee Intends to Install Design Change to Resolve IEEE-279 Postulated Failure Concerns.Operators Began TS Required Shutdown PNO-I-97-020, on 970407,Allegheny Power Sys Inc & Dqe Inc, Parent Co of Duquesne Light Co,Announced Billion Dollar Agreement to Merge Companies.Merger Unanimously Approved by Both Companies Boards of Directors1997-04-0707 April 1997 PNO-I-97-020:on 970407,Allegheny Power Sys Inc & Dqe Inc, Parent Co of Duquesne Light Co,Announced Billion Dollar Agreement to Merge Companies.Merger Unanimously Approved by Both Companies Boards of Directors PNO-I-97-017, on 970319,Units 1 & 2 Experienced Dual Unit Reactor Trip from Full Power Due to Electrical Fault Protection Signal from 345 Kv Bus in Onsite Switchyard. Signal Tripped Both Main Generators1997-03-20020 March 1997 PNO-I-97-017:on 970319,Units 1 & 2 Experienced Dual Unit Reactor Trip from Full Power Due to Electrical Fault Protection Signal from 345 Kv Bus in Onsite Switchyard. Signal Tripped Both Main Generators PNO-I-97-001, on 970106,unit 2 Experienced Reactor Trip from 98% Power Due to Turbine Trip.All Control Rods Inserted Completely.Auxiliary Feedwater Sys Started on Low SG Water Level Signal as Expected.Plant Remains Stable in Mode 31997-01-0808 January 1997 PNO-I-97-001:on 970106,unit 2 Experienced Reactor Trip from 98% Power Due to Turbine Trip.All Control Rods Inserted Completely.Auxiliary Feedwater Sys Started on Low SG Water Level Signal as Expected.Plant Remains Stable in Mode 3 PNO-I-93-061A, on 931119,determined That Util Adequately Met Commitments in CAL 1-93-20,dtd 931109.Determination Based on Completed Actions & Tests Which Demonstrated Reasonable Assurance That Both EDG Sequencers Operable & Reliable1993-11-22022 November 1993 PNO-I-93-061A:on 931119,determined That Util Adequately Met Commitments in CAL 1-93-20,dtd 931109.Determination Based on Completed Actions & Tests Which Demonstrated Reasonable Assurance That Both EDG Sequencers Operable & Reliable PNO-I-93-061, on 931104 & 1106,EDG Number 1 & 2,failed auto-load Test When Loads Did Not Sequence on Emergency Bus During Simulated Loss of Offsite Power W/Safety Injection Signal.Ait Sent to Review Circumstances1993-11-0909 November 1993 PNO-I-93-061:on 931104 & 1106,EDG Number 1 & 2,failed auto-load Test When Loads Did Not Sequence on Emergency Bus During Simulated Loss of Offsite Power W/Safety Injection Signal.Ait Sent to Review Circumstances PNO-V-90-038, A:on 900927,main Generator Trip Resulted in Unplanned Plant Shutdown.Transient Caused 140 MW Excursion on Grid,Tripped Off Nearby Substation & Shook Turbine Bldg Deck.Ge Contacted for Recommendations1990-09-27027 September 1990 PNO-V-90-038-A:on 900927,main Generator Trip Resulted in Unplanned Plant Shutdown.Transient Caused 140 MW Excursion on Grid,Tripped Off Nearby Substation & Shook Turbine Bldg Deck.Ge Contacted for Recommendations PNO-I-90-070, on 900830,licensee Declared Alert Following Apparent Release of CO2 Gas Into Several Spaces.Isolation Valve Apparently Leaked.Licensee Immediately Dispatched Onsite Fire Brigade in self-contained Breathing Apparatus1990-08-30030 August 1990 PNO-I-90-070:on 900830,licensee Declared Alert Following Apparent Release of CO2 Gas Into Several Spaces.Isolation Valve Apparently Leaked.Licensee Immediately Dispatched Onsite Fire Brigade in self-contained Breathing Apparatus PNO-I-89-046, on 890621,unusual Event Declared Due to Plant Shutdown,Necessitated by Excessive RCS Leakage Into C Steam Generator,During Which Auxiliary Feedwater Auto Start & Auto Isolation Experienced.Generator Levels Reestablished1989-06-22022 June 1989 PNO-I-89-046:on 890621,unusual Event Declared Due to Plant Shutdown,Necessitated by Excessive RCS Leakage Into C Steam Generator,During Which Auxiliary Feedwater Auto Start & Auto Isolation Experienced.Generator Levels Reestablished PNO-I-89-043, on 890607,unit Declared Unusual Event Due to Excessive RCS Leakage & Initiated Tech Spec Required Shutdown.Leak Stopped.Facility Stabilized at About 20% Power & Monitoring Plant Parameters to Confirm That Leak Stopped1989-06-0707 June 1989 PNO-I-89-043:on 890607,unit Declared Unusual Event Due to Excessive RCS Leakage & Initiated Tech Spec Required Shutdown.Leak Stopped.Facility Stabilized at About 20% Power & Monitoring Plant Parameters to Confirm That Leak Stopped PNO-I-88-086, on 880822,Unit 2 Experienced one-out-of-three Actuation of Chlorine Detection Sys.Unit 1 Actuated on two-out-of-three Coincidence.Bottled Air Pressurization Sys Began to Discharge Into Control Room.Addl Tests Performed1988-08-23023 August 1988 PNO-I-88-086:on 880822,Unit 2 Experienced one-out-of-three Actuation of Chlorine Detection Sys.Unit 1 Actuated on two-out-of-three Coincidence.Bottled Air Pressurization Sys Began to Discharge Into Control Room.Addl Tests Performed PNO-I-87-107, on 871117,turbine Reactor Tripped Due to Spuriously Generated Turbine Thrust Bearing Trip.Caused by Technician Inadvertently Tripping Power Switch on Turbine Rotor Position Drawer.Offsite Transformer Inspected1987-11-18018 November 1987 PNO-I-87-107:on 871117,turbine Reactor Tripped Due to Spuriously Generated Turbine Thrust Bearing Trip.Caused by Technician Inadvertently Tripping Power Switch on Turbine Rotor Position Drawer.Offsite Transformer Inspected PNO-I-87-073, on 870803,reactor Trip Breakers Shut to Commence Approach to Initial Criticality.Criticality Achieved on 870804.Insp Team on Site Providing Continuous Coverage Throughout Low Power Physics Testing1987-08-0404 August 1987 PNO-I-87-073:on 870803,reactor Trip Breakers Shut to Commence Approach to Initial Criticality.Criticality Achieved on 870804.Insp Team on Site Providing Continuous Coverage Throughout Low Power Physics Testing PNO-I-87-016, on 870310-11 Commissioner KM Carr Will Visit Plant.Agenda Consists of Briefing & Tour1987-03-0909 March 1987 PNO-I-87-016:on 870310-11 Commissioner KM Carr Will Visit Plant.Agenda Consists of Briefing & Tour ML20210E9641987-02-0606 February 1987 PNS-I-87-001:on 870206,site Telephone Operator Received Anonymous Call Stating That Three Bombs Placed in Facility. Bomb Threat Procedure & Security Survey Initiated ML20212B1811986-12-22022 December 1986 PNS-I-86-024:on 861218,discovered Power Available Indicator for One of Six safety-related Auxiliary Feedwater Valves Dark.Caused by Security Guard Tampering W/Breaker Device.Guard Suspended Pending Completion of Investigation ML20211E2951986-10-17017 October 1986 PNS-I-86-019:on 861016,contractor Providing Security Svcs for Plant Changed from Burns Intl Security Svcs to Security Bureau,Inc.Licensee Advised NRC of Proposed Change During 861014 Meeting PNO-I-86-079, on 860926,facility Switchboard Operator Received Bomb Threat by Telephone.Reactor Bldg Evacuated. Licensee Will Resume Work in Reactor Bldg,If No Bomb Found1986-09-26026 September 1986 PNO-I-86-079:on 860926,facility Switchboard Operator Received Bomb Threat by Telephone.Reactor Bldg Evacuated. Licensee Will Resume Work in Reactor Bldg,If No Bomb Found PNO-I-86-071, on 860911,bomb Threats Received by Telephone. Nonessential Personnel Released & Bldg Searched1986-09-11011 September 1986 PNO-I-86-071:on 860911,bomb Threats Received by Telephone. Nonessential Personnel Released & Bldg Searched PNO-I-86-070, on 860905,telephone Bomb Threat Received for Unit 2.Fuel Bldgs of Both Units Evacuated & Searched.No Bomb Found.Info Assessment Team & Commonwealth of PA Notified1986-09-0505 September 1986 PNO-I-86-070:on 860905,telephone Bomb Threat Received for Unit 2.Fuel Bldgs of Both Units Evacuated & Searched.No Bomb Found.Info Assessment Team & Commonwealth of PA Notified PNO-I-85-083, on 851031,unmonitored Release of 1,600 Gallons Radioactive Water from Unit 1 Boric Acid Holding Tank Occurred.Caused by Personnel Error.Leak Isolated & Sewers Monitored.Unit 2 Worker Contaminated on Shoe1985-10-31031 October 1985 PNO-I-85-083:on 851031,unmonitored Release of 1,600 Gallons Radioactive Water from Unit 1 Boric Acid Holding Tank Occurred.Caused by Personnel Error.Leak Isolated & Sewers Monitored.Unit 2 Worker Contaminated on Shoe PNO-I-85-062, on 850829,at 100% Power,Reactor Tripped & Safety Injection Occurred.Caused by Broken Pipe Fitting on Instrument Air Compressor Tank in Turbine Bldg.Pressurizer Pressure Restored to Normal1985-08-29029 August 1985 PNO-I-85-062:on 850829,at 100% Power,Reactor Tripped & Safety Injection Occurred.Caused by Broken Pipe Fitting on Instrument Air Compressor Tank in Turbine Bldg.Pressurizer Pressure Restored to Normal PNO-I-85-051A, on 850717,diesel Generator 1 Failed Monthly Surveillance Test.Initially Attributed to Possible Tampering W/Load Limit Setting Knob.Investigation Concluded That Knob May Have Been Inadvertently Moved During Cleaning1985-07-25025 July 1985 PNO-I-85-051A:on 850717,diesel Generator 1 Failed Monthly Surveillance Test.Initially Attributed to Possible Tampering W/Load Limit Setting Knob.Investigation Concluded That Knob May Have Been Inadvertently Moved During Cleaning PNO-I-85-051, on 850717,diesel Generator 1 Failed Monthly Surveillance Test Due to Woodward Governor Load Limit Setting Being Set at 3,instead of Normal Setting of 10. Caused by Possible Tampering W/Generator Setting1985-07-18018 July 1985 PNO-I-85-051:on 850717,diesel Generator 1 Failed Monthly Surveillance Test Due to Woodward Governor Load Limit Setting Being Set at 3,instead of Normal Setting of 10. Caused by Possible Tampering W/Generator Setting ML20148D7611979-10-0909 October 1979 PNS-I-79-001A:on 791008,licensee & Ibew Union Committee Reached Tentative Agreement on New Contract.Licensee Believes New Contract Will Be Ratified Thereby Avoiding Strike ML20249A6311978-08-0707 August 1978 PNS-78-038:on 780804,phone Call Was Received at Plant Welding Shop.Unidentified Person Stated That Bomb Was in Power House & Hung Up.Site Was Not Evacuated.Cursory Search Was Conducted ML20207G6391977-11-17017 November 1977 PNO-77-202:on 771116,facilty Shutdown from 100 Percent Power to Investigate Noises Which Developed in Main Generator. Exams Performed on 771116 Revealed That Hot Hydrogen Gas Return Duct Inside Generator Had Loosened ML20151X4901977-08-24024 August 1977 PNO-77-148:on 770823,licensee Discovered That Small Amounts of Radioactive,Borated Water Had Been Leaking from Unit 1 Auxiliary Bldg Via Concrete Trench to Unit 2 Construction Area for Undetermined Time ML20126D1901977-08-12012 August 1977 PNO-77-143:Pacific Pump Co Supplied Facilities W/Production Lot of 40 Pumps Mfg Using Shafts Made of Inferior Matl. Cause Unstated.All Utils W/Pumps Were Notified.Nrc Headquarters Notified on 770812 ML20151X7571977-07-26026 July 1977 PNO-77-134:on 770725,primary Water Storage Tank Overflowed During Filling Operation & Dumped 9000 Gallons of Slightly Radioactive Water Onto Ground.Unplanned Release Caused by Valving Error During Tank Filling Operation ML20151U9241977-06-0909 June 1977 PNO-77-100:on 770608,makeup Water from Primary Water Storage Tank Contaminated Plant Water Treatment Sys Which Provides Inplant Domestic Water.Licensee Posted All Domestic Water Outlets (Drinking Fountains & Lavoratories) ML20151U6421977-04-21021 April 1977 PNO-77-064:on 770420,plant Shutdown Due to Inadvertent MSIV Closure,Caused Safety Injection Signal & Plant Trip.Nrc Inspector or Site Reviewing Licensee Findings.Press Release Not Planned ML20236L0351977-01-0606 January 1977 PNO-77-004:on 770105,plant Automatically Scrammed,Steam Flow Feed Flow Mismatch,From 54 Percent Power When Feedwater Line Vibration Experienced.Licensee Determining Extent of Damage Which Occurred ML20236F3221976-12-27027 December 1976 PNO-76-225:on 761227,plant Was Shutdown When Feedline Vibration Was Experienced.Power Level at Time of Disturbance Was Approx 75%.Licensee Determining Extent of Damage as Result of Event.Commonwealth of Pennsylvania Informed ML20236F2651976-11-0808 November 1976 PNO-76-186:on 761105,rumbling Was Heard in Operating Areas & Guard House.Drain Line 3/4 Inch on AFW Line to B SG Had Failed.Licensee Plans to Have Westinghouse & Stone & Webster Analyze Event to Determine Cause ML20236F5121976-07-16016 July 1976 PNS-76-032:on 760716,Shippingport Police Received Phone Call Advising That Two Bombs Were in Conventional Power Plant; One Bomb in Stack & One in Power House.Midland Police Dept Advised of Call & in Turn Advised Licensee ML20249B5101976-06-18018 June 1976 PNO-76-105:on 760617,7,000 Gallons of Water Leaked to Containment from 3/8 Inch Flexible Pressure Hose in RCS Pressure Transmitter Line.Appears That Operators Failed to Respond to Sump Pump Alarms & Addl Pump Operation ML20249B3261976-05-11011 May 1976 PNO-76-084:on 760510,initial Criticality Achieved.Region 1 Inspector Witnessed Evolution & Repts That Actual Boron Concentration in Close Agreement W/Predicted Values.Media Interest Expected Because of Close Attention to Plant 1999-07-26 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARPNO-I-99-048, on 991022,operators Initiated Plant Shutdown from 100% Reactor Power,Due to Continued RCS Leakage Through B Pressurizer Code Safety Valve to Primary Relief Tank. Operators Are Reducing Reactor Power at 12% Per H1999-10-22022 October 1999
[Table view]PNO-I-99-048:on 991022,operators Initiated Plant Shutdown from 100% Reactor Power,Due to Continued RCS Leakage Through B Pressurizer Code Safety Valve to Primary Relief Tank. Operators Are Reducing Reactor Power at 12% Per H ML20217N1491999-10-21021 October 1999 Notice of Violation from Insp on 990720-29.Violation Noted: as of July 1999,licensee Did Not Take Adequate Measures to Assure That Condition Adverse to Quality Involving Macro Biological Fouling of Service Water System Corrected IR 05000334/19990061999-10-0707 October 1999 Insp Repts 50-334/99-06 & 50-412/99-06 on 990809-13 & 990823-27.Violations Noted.Major Areas Inspected:Licensee Corrective Action Program Implementation IR 05000334/19990051999-09-30030 September 1999 Insp Repts 50-334/99-05 & 50-412/99-05 on 990725-0904.Two Violations Noted & Being Treated as Nvcs.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support ML20211Q5791999-09-0707 September 1999 Insp Rept 50-412/99-07 on 990720-29.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000334/19990041999-08-24024 August 1999 Insp Repts 50-334/99-04 & 50-412/99-04 on 990613-0724. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support PNO-I-99-036, on 990718,update to Beaver Valley,Unit 2 Forced Outage Made.Licensee Replaced Suspected Voltage Regulator Control Relays & Satisfactorily Retested EDG 2-2.Resident Inspectors Continue to Monitor Licensee Corrective Action1999-07-26026 July 1999 PNO-I-99-036:on 990718,update to Beaver Valley,Unit 2 Forced Outage Made.Licensee Replaced Suspected Voltage Regulator Control Relays & Satisfactorily Retested EDG 2-2.Resident Inspectors Continue to Monitor Licensee Corrective Action PNO-I-99-033, on 990716,apparent Electrical Fault Occurred During EDG Full Load Test,Which Opened Supply Breaker Between Emergency & Normal 4 Kilovolt Busses.Station Personnel Intend to Resolve & Correct Electrical Fault1999-07-19019 July 1999 PNO-I-99-033:on 990716,apparent Electrical Fault Occurred During EDG Full Load Test,Which Opened Supply Breaker Between Emergency & Normal 4 Kilovolt Busses.Station Personnel Intend to Resolve & Correct Electrical Fault IR 05000334/19990031999-07-0707 July 1999 Insp Repts 50-334/99-03 & 50-412/99-03 on 990502-0612.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support.Results of Y2K Readiness Assessment Also Included IR 05000334/19990021999-05-21021 May 1999 Insp Repts 50-334/99-02 & 50-412/99-02 on 990321-0501.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000334/19990011999-04-22022 April 1999 Insp Rept 50-334/99-01 & 50-412/99-01 on 990207-0320. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support.Also Results of Insp by Regional Security & Inservice Insp Specialists IR 05000412/19993011999-04-20020 April 1999 NRC Operator Licensing Exam Rept 50-412/99-301(including Completed & Graded Tests) for Tests Administered on 990322- 25.All Applicants Passed All Portions of Exams IR 05000334/19980111999-02-25025 February 1999 Insp Repts 50-334/98-11 & 50-412/98-11 on 981227-990206. Violations Noted.Major Areas Inspected:Operations,Maint & Plant Support ML20207E0761999-02-25025 February 1999 Notice of Violation from Insp on 981227-990206.Violation Noted:Licensee Failed to Promptly Identify & Correct Condition Adverse to Quality in That Investigation of Improperly Calibr Channnels Was Incompleted ML20206U3141999-02-0505 February 1999 Notice of Violation from Insp on 981116-1217.Violation Noted:On or Before 981217,design Control Measures Were Not Established to Ensure That Design Basis Closing Voltage Requirements of Circuit Breakers Were Met & Verified IR 05000334/19980091999-02-0505 February 1999 Insp Repts 50-334/98-09 & 50-412/98-09 on 981115-1217. Violations Noted.Major Areas Inspected:Engineering IR 05000334/19980101999-01-13013 January 1999 Insp Repts 50-334/98-10 & 50-412/98-10 on 981115-1226.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support.Matl Condition of Fire Protection Equipment Installed in Plant Was Excellent IR 05000334/19980061998-12-0404 December 1998 Corrected Pages 17 & 18 to Insp Repts 50-334/98-06 & 50-412/98-06,correcting Errors on Subj Pages ML20196H2951998-12-0202 December 1998 Insp Repts 50-334/98-08 & 50-412/98-08 on 981026-30.No Violations Noted.Major Areas Inspected:Operations & Maint ML20196H3231998-12-0202 December 1998 Insp Repts 50-334/98-06 & 50-412/98-06 on 981004-1114.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support IR 05000334/19980071998-11-0505 November 1998 Insp Repts 50-334/98-07 & 50-412/98-07 on 981006-07.No Violations Noted.Major Areas Inspected:Performance of Emergency Response Organization IR 05000334/19980051998-10-23023 October 1998 Insp Repts 50-334/98-05 & 50-412/98-05 on 980816-1003. Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20151Z3231998-09-15015 September 1998 Insp Repts 50-334/98-04 & 50-412/98-04 on 980628-0815. Violation Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20151Z3181998-09-15015 September 1998 Notice of Violation from Insp on 980628-0815.Violation Noted:On 980808,inspectors Observed Maint Supervisor Manipulate Outboard Pump Packing Supply Valve & Perform Maint by Adjusting Outboard Packing Gland Nuts IR 05000334/19983011998-08-21021 August 1998 Exam Repts 50-334/98-301OL & 50-412/98-301OL Conducted During Wks of 980803-07 & 17-21.Exam Results:Four Unit 2 SRO Candidates Passed All Portions of Initial Exam.Good Performance Noted During Exam in Area of Crew Communication ML20236X8661998-08-0505 August 1998 Notice of Violation from Insp on 980426-0627.Violation Noted:From 1988 to Sept 1997,licensee Routinely Vented Units 1 & 2 HHSI Piping Prior to Surveillance Testing W/O Proper Controls to Evaluate Amount of Gas.No Response Required IR 05000334/19980031998-08-0505 August 1998 Insp Repts 50-334/98-03 & 50-412/98-03 on 980426-0627. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support ML20236X8631998-08-0505 August 1998 Notice of Violation from Insp on 980426-0627.Violation Noted:During Period of 980428-0608,licensee Failed to Implement Procedures as Evidenced by Listed Examples IR 05000334/19983001998-06-0303 June 1998 Exam Rept 50-334/98-300OL Conducted on 980420-24 & 0518.Exam Results:Three SRO Instant Candidates Passed All Portions of Initial License Exam ML20217F5881998-04-22022 April 1998 Notice of Violations from Insp on 980208-0321.Violations Noted:Conditions Adverse to Quality Were Not Promptly Corrected from Nov 1993 to March 1998,util Failed to Correct Known Unit 1 & 2 TS Deficiency in Timely Manner ML20217F5951998-04-22022 April 1998 Insp Repts 50-334/98-01 & 50-412/98-01 on 980208-0321. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20217B9771998-03-17017 March 1998 Notice of Violation from Insp on 971228-980207.Violations Noted:Repair Activities for 2-1 Station Battery Were Not Properly pre-planned & Implemented ML20217B9851998-03-17017 March 1998 Insp Repts 50-334/97-11 & 50-412/97-11 on 971228-980207. Violations Noted.Major Areas Inspected:License Operations, Engineering,Maint & Plant Support.Security Program Was Also Inspected ML20216E8071998-03-0909 March 1998 Notice of Violation from Insp on 980105-0212.Violations Noted:On 971218 Dl Implemented Change to Temporary Operating Procedure to Allow Operators to Control Cooldown & Heatup Rate of Reactor Coolant by Mean Other than by Regulating ML20216E8191998-03-0909 March 1998 Insp Repts 50-334/98-80 & 50-412/98-80 on 980105-0212. Violations Noted.Major Areas Inspected:Evaluation of Implementation of 10CFR50.59 SE Program Relating to Changes, Tests or Experiments at Plant ML20202A9691998-02-0404 February 1998 Insp Repts 50-334/97-09 & 50-412/97-09 on 971116-1227. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support.Rept Also Includes Results of Announced Insp in Areas of Emergency Preparedness IR 07100116/20120271998-02-0404 February 1998 Notice of Violation from Insp on 971116-1227.Violation Noted:Licensee Had Not Tested 20 of 27 Direct Lines at Alternate EOF in Coraopolis,Pa PNO-I-98-002, on 980130,operators Declared Both Trains of Component Cooling Reactor & Reactor Plant River Water Sys Inoperable Due to Failure to Meet TS Surveillance Testing Requirements.Entered TS 3.0.3 & 4.0.31998-02-0202 February 1998 PNO-I-98-002:on 980130,operators Declared Both Trains of Component Cooling Reactor & Reactor Plant River Water Sys Inoperable Due to Failure to Meet TS Surveillance Testing Requirements.Entered TS 3.0.3 & 4.0.3 IR 05000334/19970101998-01-0909 January 1998 NRC Operator Licensing Exam Rept 50-334/97-10OL (Including Completed & Graded Tests) for Tests Administered on 971215- 18 ML20198K4761998-01-0606 January 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Between 1988 & 970912, Condition Adverse to Quality Existed at Unit 1 & 2,when Excessive Gas Accumulated in HHSI Pumps Suction Lines ML20199A1711997-12-31031 December 1997 EN-97-119:on 980106,notice of Proposed Imposition of Civil Penalty in Amount of $55,000 Issued to Licensee.Action Based on Violation Involving Failure to Take Adequate Action to Correct Significant Condition Adverse to Quality PNO-I-97-077, on 971216,Duquesne Light Co Initiated Unit 2 Reactor Shutdown in Accordance W/Ts 3.0.3.Licensee Plans to Address Unit 2 Design Deficiency for CR Emergency Air Cleanup & Pressurization,During Shutdown1997-12-17017 December 1997 PNO-I-97-077:on 971216,Duquesne Light Co Initiated Unit 2 Reactor Shutdown in Accordance W/Ts 3.0.3.Licensee Plans to Address Unit 2 Design Deficiency for CR Emergency Air Cleanup & Pressurization,During Shutdown ML20203D7421997-11-26026 November 1997 Insp Repts 50-334/97-08 & 50-412/97-08 on 971005-1115. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 07100005/20110151997-11-26026 November 1997 Notice of Violation from Insp on 971005-1115.Violations Noted:Workers,Found in Radiology Controlled Areas,Not Aware of Radiological Conditions in Work or Travel Areas IR 05000334/19970071997-11-0707 November 1997 Insp Repts 50-334/97-07 & 50-412/97-07 on 970831-1004. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20198S6351997-11-0707 November 1997 Notice of Violation from Insp on 970830-1004.Violation Noted:Licensee Changed QA Program Resulting in Reduction in Commitments in QA Program Description Previously Accepted by NRC W/O Prior NRC Approval IR 05000334/19970061997-09-18018 September 1997 Insp Repts 50-334/97-06 & 50-412/97-06 on 970720-0830.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support & Licensed Operator Requalification Training Program ML20217P7731997-08-18018 August 1997 Notice of Violation from Insp on 970608-0719.Violation Noted:Previous Corrective Actions Inadequate in That on 970701,unplanned Engineered Safety Feature Actuation, Occurred During Troubleshooting Activities on Unit 1 IR 05000334/19970051997-08-18018 August 1997 Insp Repts 50-334/97-05 & 50-412/97-05 on 970608-0719. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20141G9971997-07-0303 July 1997 Notice of Violation from Insp on 970209-0426.Violation Noted:During EDG Surveillance Tests,Load Test Values Used Were Inadequate to Ensure That EDGs Achieved 2750 Kw Due to Inaccuracies in Kilowatt Meter Instrument Loop 1999-09-07 |
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DCS No: 50334850829 Date: August 29, 1985 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PNO-I-85-62 This preliminary notification constitutes EAPLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without verification or evaluation, and is basically all that is known by the Region I staff on this date.
Facility: Licensee Emergency Classification:
Duquesne Light Company X Notification of Unusual Event Beaver Valley Unit 1 Alert Shippingport, PA 15077 Site Area Emergency D/N 50-334 _ General Emergency Not Applicable
Subject:
REACTOR TRIP AND SAFETY INJECTION DUE TO LOSS OF INSTRUMENT AIR PRESSURE At 1:00 p.m. on 8/29 the licensee declared an Unusual Event after a safety injection (SI) and reactor trip from 100's power at 12:49 p.m. Loss of instrument air pressure was caused by a broken pipe fitting on the instrument air compressor tank in the tur-bine building. On loss of air, the main steam isolation valves (MSIV) closed. How-ever, initial closure of loop "B" MSIV resulted in a reduced loop' "C" steam line pressure which resulted in the SI initiation. SI injection lasted approximately 10 minutes. The minimum loop temperature obtained was 510 F, and primary system pressure decreased to 2010 psig. Pressurizer pressure was subsequently returned to normal (2235 psig), and plant conditions stabilized. The Unusual Event was terminated at 1:15 p.m.
All safety systems functioned as designed. This SI constituted the 19th occurrence based on the current analysis which is valid for 50 injections.
The State of Pennsylvania has been notified and the utility has issued a press release. _
NRC Region I received notification of this occurrence by telephone call at 1:09 p.m.
on August 29, 1985. The Senior Resident Inspector was on site at the time of the event and provided immediate follow up.
CONTACT: A. Asars L. Tripp 488-1356 488-1227 DISTRIBUTION:
H. St. ~~
MNL'll Phillips E/W Willste Mail: ADM:DMB Chairman Palladino EDO NRR IE NMSS DOT:Trans only Comm. Zech PA OIA RES Comm. Bernthal ELD AE00 Comm. Roberts Comm. Asselstine l ACRS Air Rights INP0----
! SECY SP NSAC----
l CA POR Regional Offices TMI Resident Section RI Resident Office Licensee:
(Reactor Licensees)
Region I Form 83 8509030334 050029 (Rev. July,1984) PDR
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