LER-1978-043, Forwards LER 78-043/03L-0 |
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| 2771978043R00 - NRC Website |
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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET PHILADELPHIA PA,19101 (215) 841-4o00 November 17, 1978 Mr. Boyce H.
Grier, Director Office of Inspection and Enforcement Region I United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Grier:
SUBJECT:
Licensee Event Report Narrative Description
Reference:
Docket Number 50-277 Report No:
LER 2-73-043/3L-0 Report Date:
November 17, 1978 Occurrence Date:
October 19, 1978 Facility:
Peach Botton Atomic Power Station R.D.
1, Delta, PA 17314 Technical Specification Reference:
Technical Specification 4.ll.D.1 states in part "All hydraulic snubbers..... shall be visually inspected.
The inspection shall include, but not necessarily be limited to, inspection of the hydraulic fluid reservoir, fluid connections, and linkage connections to the piping and anchor to verify snubber operability...
Technical Specification 4.11.D.4 states in part, "Once each refueling cycle, a representative sample of 10 hydraulic snubbers or approximately 10% of the hydraulic s r.u b b e r s, whichever is less, shall be functionally tested for operability including verification of proper piston movement, lock up and bleed.....
I 2236 092 b TI 7906040 3 3 o J
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'Mr.
Boyce H.
Grier Page 2 November 17, 1978 LER 78-043/3L-0 Description of the Event:
During a routine snubber inspection per Tech Spec 4.ll.D.1, snubber 23 HBS-38 on the HPCI turbine exhaust line was found with an empty reservoir.
Subsequent functional testing showed this snubber had a bleed velocity of.088 inches per minute.
The minimum acceptable bleed rate is.125 inches per minute.
During functional testing of ten snubbers per Tech Spec 4.ll.D.4, two snubbers failed to meet the minimum bleed rate criteria and two snubbers failed to meet the minimum 14" per uinute locking velocity criteria.
Because of this all safety related snubbers were ftnetionally tested.
Of 145 snubbers, 41 had average locking velocities and 12 had average bleed rates which failed to meet the minimum acceptance criteria.
Consequences of Event:
Safety significance is minimal since the majority of snubbers would have operated properly.
In addition, manufacturer's inf orma tion indicates that snubber locking velocities are somewhat temperature sensitive because of oil viscosity.- Since locking velocities increase with increasing temperature, most snubbers which failed to meet the minimum locking velocity operability criteria would have operated properly under normal higher ambient temperature conditions in their installed locations.
Cause of Event
Low bleed velocities were caused by plugging of the small bleed orifices in the snubber valve blocks.
Apparently seal material'which entered the snubber oil during p revious maintenance contributed to the plugging.
Low locking velocities were caused by lower than normal ambient temperatures in the test area which caused a downward shift in the as found locking velocity data due to temperature sensitivity.
Corrective Action
All safety related snubbers were tested, cleaned and repaired as necessary, and recalibrated.
Action to Prevent Recurrence:
The locking velocity setpoint of all snubbers was increased from 1511 inches per minute for main steam relief valve downcomer snubbers and 10 1 1 inches per minute for all other snubbers to 20 1 2 inches per minute in order to avoid exceeding the minimum locking velocity criteria in the future.
In addition, a representative sample of 10 snubbers will be retested
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2236 093
r Mr. Boyce H.
Grier Page 3 November 17, 1978 LER 78-043/3L-0 during the present operating cycle to verify that no additional bleed rate problems have developed.
Yours truly, G^
/
lM.
V
!Y Cooney Suyerintendent veneration Division-Nuclear Attachment ec:
Director, NRC - Office of Inspection and Enforcement Mr. Norman M.
Heller, NRC - Office of Management &
Program Analysis 2236 094
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| 05000271/LER-1978-009, Forwards LER 78-009/03L-0 | Forwards LER 78-009/03L-0 | | | 05000171/LER-1978-011-04, /04T-0 on 780223:approx 40 Gallons Light Diesel Fuel Oil Drained Into Discharge Canal.Caused by Valve Left Open After Use.Spillage Stopped Upon Discovery,Cleanup Initiated & Valve Locked to Control Use | /04T-0 on 780223:approx 40 Gallons Light Diesel Fuel Oil Drained Into Discharge Canal.Caused by Valve Left Open After Use.Spillage Stopped Upon Discovery,Cleanup Initiated & Valve Locked to Control Use | | | 05000171/LER-1978-011, Forwards LER 78-011/04T-0 | Forwards LER 78-011/04T-0 | | | 05000278/LER-1978-014-03, /03L-0:on 780626,at Power Operation,Shutoff Valve on Pressure Switch Found Closed.Caused by Closure During 780621 Testing.Valve Reopened & Valving for Safety Instrumentation Checked | /03L-0:on 780626,at Power Operation,Shutoff Valve on Pressure Switch Found Closed.Caused by Closure During 780621 Testing.Valve Reopened & Valving for Safety Instrumentation Checked | | | 05000278/LER-1978-016-03, /03L-0 on 780904:during Surveillance Test Unit 3 Dmain Steam Radiat Monitor Failed to Cause a Half Scram Due to Defective Transistor.Transitor Was Replaced & Monitor Returned to Svc in 6 Hours | /03L-0 on 780904:during Surveillance Test Unit 3 Dmain Steam Radiat Monitor Failed to Cause a Half Scram Due to Defective Transistor.Transitor Was Replaced & Monitor Returned to Svc in 6 Hours | | | 05000278/LER-1978-019-01, /01T-0:on 780929,quantity of Activity in Purge Stream of Offgas Sample Underestimated,Resulting in Three Peaks Exceeding Tech Specs.Purging of Offgas Directly Into Vent Sys During Offgas Process Halted | /01T-0:on 780929,quantity of Activity in Purge Stream of Offgas Sample Underestimated,Resulting in Three Peaks Exceeding Tech Specs.Purging of Offgas Directly Into Vent Sys During Offgas Process Halted | | | 05000278/LER-1978-019, Forwards LER 78-019/01T-0 | Forwards LER 78-019/01T-0 | | | 05000277/LER-1978-020-01, /01T-0 on 781019:unit 3 Containment Oxygen Concentration Had Increased to 0.1% Above 4 Percent Limit of Tech Spec 3.7.A.5.Caused by Open Air back-up Valves in Inoperable Instru Nitrogen Compressor | /01T-0 on 781019:unit 3 Containment Oxygen Concentration Had Increased to 0.1% Above 4 Percent Limit of Tech Spec 3.7.A.5.Caused by Open Air back-up Valves in Inoperable Instru Nitrogen Compressor | | | 05000277/LER-1978-020, Forwards LER 78-020/01T-0 | Forwards LER 78-020/01T-0 | | | 05000278/LER-1978-021-01, /01T-0 on 781106:while at Pwr Feedwater Control Sys Failure Resulted in Reactor Low Level Transient & Scram HPCI Initiated But Delivered Unstable Flow & Soon Tripped on Overspeed.Cause Was HPCI Governor Being Out of Calibr | /01T-0 on 781106:while at Pwr Feedwater Control Sys Failure Resulted in Reactor Low Level Transient & Scram HPCI Initiated But Delivered Unstable Flow & Soon Tripped on Overspeed.Cause Was HPCI Governor Being Out of Calibr | | | 05000278/LER-1978-021, Forwards LER 78-021/01T-0 | Forwards LER 78-021/01T-0 | | | 05000278/LER-1978-023-03, /03L-0 on 781127:D Reactor Bldg Area Exhaust Radiat Monitor Indicated Downscale & Was Determined to Be Inoperable.Caused by Defective Zener Diode in Amplifier of GE sensor-converter Unit,Model 194X927011 | /03L-0 on 781127:D Reactor Bldg Area Exhaust Radiat Monitor Indicated Downscale & Was Determined to Be Inoperable.Caused by Defective Zener Diode in Amplifier of GE sensor-converter Unit,Model 194X927011 | | | 05000278/LER-1978-024-03, /03L-0 on 781212:reactor Core Isolation Cooling Valve Mo-13-15 Failed to Close During Surveillance Test 6.11.Caused by Cocked Packing Follower Jamming Valve Stem | /03L-0 on 781212:reactor Core Isolation Cooling Valve Mo-13-15 Failed to Close During Surveillance Test 6.11.Caused by Cocked Packing Follower Jamming Valve Stem | | | 05000277/LER-1978-035-03, /03l-0 on 780830:E-3 Diesel Start Time to Reach Rated Voltage & Frequency Did Not Meet Surveillance Test Requirement,Probably Caused by Leaking Check Valve in the Hydraulic Sys Assoc W/The Air Booster Relay | /03l-0 on 780830:E-3 Diesel Start Time to Reach Rated Voltage & Frequency Did Not Meet Surveillance Test Requirement,Probably Caused by Leaking Check Valve in the Hydraulic Sys Assoc W/The Air Booster Relay | | | 05000277/LER-1978-036-03, /03L-0 on 780901:failure of Auxiliary Oil Pump to Start Due to a Ground in Motor.Motor,Baldor Type 1040D, 7 1/2 H.P.,25OV.D.C. Was Replaced & HPCI Sys Tested Satisfactorily W/In 36 Hours.Ads Timers Not W/In Tech Specs | /03L-0 on 780901:failure of Auxiliary Oil Pump to Start Due to a Ground in Motor.Motor,Baldor Type 1040D, 7 1/2 H.P.,25OV.D.C. Was Replaced & HPCI Sys Tested Satisfactorily W/In 36 Hours.Ads Timers Not W/In Tech Specs | | | 05000277/LER-1978-037-03, /03L-0 on 780901:while Testing ADS Subsys,Timers on Both Loops Were Found Outside the 115-125 Second Limit of Tech Specs Due to Setpoint Drift of Time Delay Relays. Timers Were Calibrated,Retested & Returned to Svc | /03L-0 on 780901:while Testing ADS Subsys,Timers on Both Loops Were Found Outside the 115-125 Second Limit of Tech Specs Due to Setpoint Drift of Time Delay Relays. Timers Were Calibrated,Retested & Returned to Svc | | | 05000277/LER-1978-038, Forwards LER 78-038/01T-0 | Forwards LER 78-038/01T-0 | | | 05000277/LER-1978-038-01, /01T-0 on 780908:one Point on Piping Outboard MO-12-15 Had Stress During DBE Above Code Allowable. Restraint to Be Added to Code | /01T-0 on 780908:one Point on Piping Outboard MO-12-15 Had Stress During DBE Above Code Allowable. Restraint to Be Added to Code | | | 05000277/LER-1978-039, Forwards LER 78-039/03L-0 | Forwards LER 78-039/03L-0 | | | 05000277/LER-1978-039-03, /03L-0 on 780904:backflow of Radioactive Liquid from Radwaste Demineralizers to Svc Air Sys Discovered on 780904 & 780921.Caused by Leaking Process Valves & Associated Check Vlaves Due to Dirt Deposits | /03L-0 on 780904:backflow of Radioactive Liquid from Radwaste Demineralizers to Svc Air Sys Discovered on 780904 & 780921.Caused by Leaking Process Valves & Associated Check Vlaves Due to Dirt Deposits | | | 05000277/LER-1978-041, Forwards LER 78-041/01T-0 | Forwards LER 78-041/01T-0 | | | 05000277/LER-1978-041-01, /01T-0 on 781010:2 4KV Emergency Bus Sequential Loading Relays Found Outside Tech Spec Limits.Caused by Error in Determining Setpoint & Calibr Span of Relays.Relays Recalib & Testing Procedures Revised | /01T-0 on 781010:2 4KV Emergency Bus Sequential Loading Relays Found Outside Tech Spec Limits.Caused by Error in Determining Setpoint & Calibr Span of Relays.Relays Recalib & Testing Procedures Revised | | | 05000277/LER-1978-042-03, /03L-0 on 781019:during start-up,inboard Main Steam Line Drain Isolation Valve MO-2-74 Would Not Close in Response to Hand Switch in Control Room,Due to Defective Limitorque SMB-000 Torque Switch on the Valve | /03L-0 on 781019:during start-up,inboard Main Steam Line Drain Isolation Valve MO-2-74 Would Not Close in Response to Hand Switch in Control Room,Due to Defective Limitorque SMB-000 Torque Switch on the Valve | | | 05000277/LER-1978-043-03, /03L-0 on 781019:snubber 23HBS-38 Found W/Unacceptable Bleed Rates & Locking Velocities.Caused by Clogged Bleed Orifices & Low Ambient Temp During Tests. Safety-related Snubbers Tested,Repaired & Recalib | /03L-0 on 781019:snubber 23HBS-38 Found W/Unacceptable Bleed Rates & Locking Velocities.Caused by Clogged Bleed Orifices & Low Ambient Temp During Tests. Safety-related Snubbers Tested,Repaired & Recalib | | | 05000277/LER-1978-043, Forwards LER 78-043/03L-0 | Forwards LER 78-043/03L-0 | | | 05000277/LER-1978-044-03, /03L-0 on 781021:during Startup,Excessive Oper of HPCI Gland Seal Condensate Pump Was Noted.Check Valve 2-23-131 Was Leaking Which Let Condensate Return to Gland Seal Condenser.Valves Were Blocked to Facilitate Repair | /03L-0 on 781021:during Startup,Excessive Oper of HPCI Gland Seal Condensate Pump Was Noted.Check Valve 2-23-131 Was Leaking Which Let Condensate Return to Gland Seal Condenser.Valves Were Blocked to Facilitate Repair | | | 05000277/LER-1978-046-03, /03L-0 on 781117:output Demand Signal from RCIC Flow Controller (Inst HCS213-115) Read Down Scale.Caused by Open Circuit in Controller Demand Current Loop | /03L-0 on 781117:output Demand Signal from RCIC Flow Controller (Inst HCS213-115) Read Down Scale.Caused by Open Circuit in Controller Demand Current Loop | | | 05000277/LER-1978-047-03, /03L-0 on 781102:during Third Refueling Outage, Failed to Remove Neutron Flux Samples from Reactor Vessel. Caused by Administrative Oversight.Eval of Sample Removal Prog Is in Progress | /03L-0 on 781102:during Third Refueling Outage, Failed to Remove Neutron Flux Samples from Reactor Vessel. Caused by Administrative Oversight.Eval of Sample Removal Prog Is in Progress | | | 05000277/LER-1978-048-03, /03L-0 on 781204:surveillance Test Revealed Failure of a Channel Main Steam Line High Flow Circuitry in Primary Containment Isolation Signal Logic Used to Provide Group 1 Isolation,Due to Failure of 5A-K30A Relay | /03L-0 on 781204:surveillance Test Revealed Failure of a Channel Main Steam Line High Flow Circuitry in Primary Containment Isolation Signal Logic Used to Provide Group 1 Isolation,Due to Failure of 5A-K30A Relay | | | 05000277/LER-1978-049-03, /03L-0 on 781218:surveillance Testing Revealed B Rod Block Monitor Set Points Had Shifted Upwards Approx 15%. Caused by Failure of Zener Diode in Flow Bias Circuitry Power Supply | /03L-0 on 781218:surveillance Testing Revealed B Rod Block Monitor Set Points Had Shifted Upwards Approx 15%. Caused by Failure of Zener Diode in Flow Bias Circuitry Power Supply | | | 05000277/LER-1978-050, Updated LER 78-050/03Z-1:on 781221,during Surveillance Test W/Units at Full Power,Time to Reach Rated Voltage & Frequency for E-2 & E-3 Diesels Was About 11 & 13 Seconds, Respectively.Caused by Wearing of Woodward Governors | Updated LER 78-050/03Z-1:on 781221,during Surveillance Test W/Units at Full Power,Time to Reach Rated Voltage & Frequency for E-2 & E-3 Diesels Was About 11 & 13 Seconds, Respectively.Caused by Wearing of Woodward Governors | | | 05000277/LER-1978-050-03, /03L-0 on 781221:during Routine Surveillance Test, Time to Reach Rated V & Hz for E2 Diesel Was 11 Seconds, & 13 Seconds for E3 Diesel.Probably Due to Faulty Woodward Governor | /03L-0 on 781221:during Routine Surveillance Test, Time to Reach Rated V & Hz for E2 Diesel Was 11 Seconds, & 13 Seconds for E3 Diesel.Probably Due to Faulty Woodward Governor | | | 05000277/LER-1978-051-03, /03L-0 on 781227:during Routine Surveillance Test, Setpoint of Pressure Switch Found to Be Approx 10% in Excess of Tech Spec Limit.Caused by Sheared Lockdown Screw on Setpoint Adjust.Pressure Switch Recalibr & Returned to Sv | /03L-0 on 781227:during Routine Surveillance Test, Setpoint of Pressure Switch Found to Be Approx 10% in Excess of Tech Spec Limit.Caused by Sheared Lockdown Screw on Setpoint Adjust.Pressure Switch Recalibr & Returned to Svc | |
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